Text

Annual Radiological Environmental Operating Report No. 23, for 2007
	ML081260681
Person / Time
Site:	Limerick
Issue date:	04/30/2008
From:	; Teledyne Brown Engineering Environmental Services
To:	; Exelon Nuclear, Office of Nuclear Reactor Regulation
References
	Download: ML081260681 (112)
	v • d • e

Docket No: 50-352 50-353 LIMERICK GENERATING STATION UNITS I and 2 Annual Radiological Environmental Operating Report Report No. 23 1 January Through 31 December 2007 Prepared By Teledyne Brown Engineering Environmental Services Exel n.

Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2008

Nuclear TS 6.9.1.7 April 30, 2008 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:

2007 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 2007 Annual Radiological Environmental Operating Report No. 23. This report provides the 2007 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-1 37, 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 the attributable to LGS liquid releases. Results of the groundwater protection program are also included in this report. No tritium activity in well water samples was greater than the lower limit of detection of 2000 pCi/L.

There are no commitments contained in this letter.

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

Sincerely, 641.- ,J Christopher H. Mudrick Vice President -LGS Exelon Generation Company, LLC

Attachment:

2007 Annual Radiological Environmental Operating Report No. 23 cc: S. Collins, Administrator, Region I, USNRC (w/Attachment)

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

P. Bamford -Senior Project Manager-NRR, USNRC (w/Attachment)

USNRC Document Control Desk, Washington, DC (w/Attachment)

T. Moslak, Inspector, Region I, USNRC (w/Attachment)

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

C. Mudrick -GML 5-1 (w/o Attachment)

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

R. Kreider - SSB 2-4 (w/Attachment)

T. Basso - SSB 2-2(w/Attachment)

S. Mitten -SSB 2-2 (w/Attachment)

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

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

J. Toro- SMB 1-2 (w/Attachment)

K. Jury - Cantara (w/o Attachment)

R. DeGregorio - 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)

D. Dyckman - 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 th FIr, 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)

Donald Hershey- Executive Director, American Water Works, 1309 Bridge Street, New Cumberland, PA 17070 (w/Attachment)

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

Table Of Contents I. Sum m ary and Conclusions ................................................................................................ 1 I1. Introduction ................................................................................................................ 3 A. Objectives of the REM P ................................................................................... 3 B. Im plem entation of the O bjectives ..................................................................... 3 Ill. Program Description ..................................................................................................... 4 A. Sam ple Collection ............................................................................................. 4 B. Sam ple Analysis ................................................................................................ 6 C. Data Interpretation ........................................................................................... 6 D. Program Exceptions ........................................................................................ 7 E. Program Changes ............................................................................................. 8 IV. Results and Discussion .......................................... 9 A. Aquatic Environm ent ........................................................................................ 9

1. Surface Water ........................................................................................ 9

2. Drinking Water ........................................................................................ 9

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

4. Sedim ent ............................................................................................. 10 B. Atm ospheric Environm ent ................................................................................... 11

1. Airborne ............................................................................................... 11

a. Air Particulates ......................................................................... 11

b. Airborne Iodine ................................. 11

2. Terrestrial ............................................................................................. 12

a. M ilk .......................................................................................... 12

b. Broad Leaf Vegetation .............................................................. 12 C. Am bient G am m a Radiation ............................................................................ 12 D. 10 CFR 20.2002 Perm it Storage Area ........................................................... 13 E. Land Use Survey ............................................................................................. 13 F. Summary of Results - Inter-Laboratory Comparison Program ....................... 14 V. References ...................................................................................................................... 15

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Radiological Environmental Monitoring Program Annual Summary for the Limerick Generating Station, 2007.

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

Analytical Methods Tables Table B-I: 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, 2007.

Table B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2007.

Figures Figure B-I: Environmental Sampling Locations Within One Mile of the Limerick Generating Station, 2007.

Figure B-2: Environmental Sampling Locations Between One and Five Miles from the Limerick Generating Station, 2007.

Figure B-3: Environmental Sampling Locations Greater Than Five Miles from the Limerick Generating Station, 2007.

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, 2007.

Table C-1.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2007.

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Table C-11.1 Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table C-11.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table C-11.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table C-I11.1 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station,. 2007.

Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table C-Vl.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table C-VII. 1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table C-VIII.1 Concentrations of Gamma Emitters in Broad Leaf Vegetation Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table C-IX.1 Quarterly TLD Results for Limerick Generating Station, 2007.

Table C-IX.2 Mean Quarterly TLD Results for the Site Boundary, Middle and Control Locations for Limerick Generating Station, 2007.

Table C-IX.3 Summary of the Ambient Dosimetry Program for Limerick Generating Station, 2007.

Figures Figure C-1 Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 - 2007.

Figure C-2 Mean Annual Cs-1 37 Concentrations in Fish Samples Collected in the Vicinity of LGS, 1982 - 2007.

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Figure C-3 Concentrations of Cs-1 37 in Sediment Samples Collected in the Vicinity of LGS, 1982 - 2007.

Figure C-4 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 - 2007.

Figure C-5 Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2007.

Figure C-6 Mean Quarterly Ambient Gamma Radiation Levels (TLD) in the Vicinity of LGS, 1985 - 2007.

Appendix D Data Tables and Figures - Comparison Laboratory Tables Table D-1.1 Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2007.

Table D-1.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2007.

Table D-1.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table D-11.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table D-11.2 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Table D-111.1 Concentrations of 1-131 by Chemical Separation and Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2007.

Figures Figure D-1 Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between ENV and TBE, 2007.

Figure D-2 Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2, 2007.

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Appendix E Inter-Laboratory Comparison Program Tables Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2007.

Table E-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2007.

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

Teledyne Brown Engineering, 2007.

Table E-4 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2007.

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

Environmental, Inc., 2007.

Appendix F Annual Radiological Groundwater Protection Program Report (ARGPPR) v

Intentionally Left Blank vi

I. Summary and Conclusions In 2007 the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 49 curies of noble gas, fission and activation products and approximately 54 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 locations Effluent Applicable Estimated Age Location % of Limit Unit Organ Dose Group Distance Direction Applicable (meters) (toward) Limit Noble Gas Gamma - Air Dose 5.25E-03 All 762 SE 2.63E-02 20 mRad Noble Gas Beta - Air Dose 3.10E-03 All 762 SE 7.75E-03 40 mRad Noble Gas Total Body (Gamma) 3.47E-03 All 762 SE 3.47E-02 10 mrem Noble Gas Skin (Beta) 6.40E-03 All 762 SE 2.13E-02 30 mrem Iodine, Particulate & Thyroid 1.03E-02 Infant 762 SE 3.40E-02 30 mrem Tdtium Liquid total Body 3.82E-03 Adult LGS Outfall 6.37E-02 6 mrem Liquid Liver 5.07E-03 Teen LGS Outfall 2.54E-02 20 mrem The doses as a result of 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 2007 through 31 December 2007. During that time period, 1,124 analyses were performed on 914 samples.

Surface and drinking water samples were analyzed for concentrations of tritium and gamma emitting nuclides. Drinking water samples were also analyzed for concentrations of total gross beta. No fission or activation products were detected. Gross beta activities detected were consistent with those detected in previous years. Tritium was found at downstream surface water location 13Blat a concentration of 272 pCi/L and drinking water location 15F7 at a concentration of 189 pCi/L. Assuming the highest concentration of 272 pCi/L was present all year, the dose via the drinking water pathway was calculated at 0.0282 mrem to a child (total body), which was 0.47% of the 10 CFR 50, Appendix I dose limit.

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

Sediment samples collected below the discharge had elevated Cesium-1 37 concentrations that were the result of LGS discharges. No other Plant produced fission or activation products were found in sediment. The calculated dose to a teenager's skin and whole body was 2.34E-4 mrem and 2.OOE-4 mrem, 1

respectively. This dose represents 2.09E-04% and 5.98E-06%, 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.

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. No activation or fission products were detected.

Environmental gamma radiation measurements were performed quarterly using thermoluminescent dosimeters. 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 indicated no offsite radionuclide transport was evident.

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. Well water samples were analyzed for tritium, Sr-90 and gamma emitters. Most tritium values were less than the lower limit of detection of 200 pCi/L. However, one well located near the radwaste /cooling tower blowdown line had a tritium value as high as 309 pCi/L.

This activity is consistent with environmental background levels. Although no drinking water pathway exist, the dose via the drinking water pathway was calculated at 0.032 mrem to a child (total body), which was 0.53% of the 10 CFR 50, Appendix I dose limit. All results for Sr-90 and gamma emitting nuclides were less than MDC.

In assessing all 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 3458 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), Global Dosimetry, and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2007 through 31 December 2007.

On 6 July 1996 a 10CFR20.2002 permit was issued to Limerick for storage of slightly contaminated soils, sediments and sludges obtained from the holding pond, cooling tower and spray pond systems. These materials will decay to background while in storage. Final disposition will be determined at Station decommissioning.

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

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

2. Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.

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

1. Identifying significant exposure pathways.

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2. Establishing baseline radiological data of media within those pathways.

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

Ill. Program Description A. Sample Collection Samples for the LGS REMP were collected for Exelon Nuclear by Normandeau Associates, Inc.. This section describes the general collection methods used by NAI to obtain environmental samples for the LGS REMP in 2007. Sample locations and descriptions can be found in Tables B-1 and B-2, and Figures B-1 through B-3, Appendix B. The collection procedures used by NAI are listed in Table B-3.

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

Two-gallon water samples were collected monthly from continuous samplers located at two surface water locations (13B1 and 24S1) and four drinking water locations (15F4, 15F7, 16C2, and 28F3). Control locations were 24S1, and 28F3. All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising the flesh of two groups, catfish/bullhead (bottom feeder) and sunfish (predator), 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 Fnvironment 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 five locations (10S3, 11S1, 13C1, 14S1, and 22G1). The control location was 22G1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis.

Milk samples were collected biweekly at five locations (10F4, 18E1, 19B1, 23F1, and 25C1) from April through November, and monthly from December through March. Two additional locations (25E1 and 36E1) were sampled quarterly. Locations 36E1 and 23F1 were controls. All 4

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 were collected monthly at three locations (11 S3, 13S3 and 31G1). The control location was 31G1. Five 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 (CaSO4) 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 be potentially greater than maximum annual off-site doses) from LGS release.

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

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

The specific 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.

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 Global for analysis.

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10CFR20-2002 Permit Storage Area The results of the surface water sampling program were used to determine if radioactive nuclide transport from the storage area into the Schuylkill River had occurred.

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 2007. The analytical procedures used by the laboratories are listed in 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 and milk.

5. Ambient gamma radiation levels at various site environs.

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

1. Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was 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 was 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 were designed to achieve the required LGS detection limits for environmental sample analysis.

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The minimum detectable concentration (MDC) was 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 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 and broad leaf vegetation eight nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, 1-131, Cs-1 34, and Cs-137 were reported.

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

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

Means and standard deviations of positive results were calculated.

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

D. Program Exceptions For 2007 the LGS REMP had a sample recovery rate in excess of 99%.

Exceptions are listed below:

1. Air particulate sample from location 22G1 for the week 05/29/07 -

06/04/07 was not available due to incorrect placement of the air particulate filter in the air sampler (IR708393).

2. Air iodine sample from location 10S3 for the week 09/24/07 -

10/01/07 was not shipped to the primary laboratory due to a sample collection error (IR698183).

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3. Grab samples were taken for the composite drinking water sampler at location 16C2 during the following periods due to equipment malfunction or insufficient sample collected: 05/15 - 5/21/07, 05/29 - 06/04/07, 09/11 - 09/17/07 and 12/04 - 12/10/07.

4. A grab sample was taken for the composite drinking water sampler at location 28F3 from 12/26/06 - 01/02/07 due to insufficient sample collection.

5. A grab sample was taken for the composite drinking water sampler at location 15F4 from 10/30 - 11/05/07 due to sample collection error.

6. Grab samples were taken for the composite surface water sampler at location 13B1 during the following periods due to equipment malfunction, line freezing or low water levels: 01/08 - 01/15/07, 09/11 - 09/17/07, and 10/15 - 10/30/07.

7. Grab samples were taken for the composite surface water sampler at location 24S1 during the following periods due to equipment malfunction or line freezing: 02/06 - 02/20/07.

8. The TLD holder for location 10S3 was destroyed due to a vehicle accident on 02/18/07. The TLDs were found exposed to the elements; however, they were read by the TLD vendor, Global Dosimetry (IR663786).

9. TLD data from locations 18S2, 25S2 and 29S1 was not complete for the first quarter 2007 due to vendor inability to read all dosimeters. Each TLD location has two TLDs comprising three dosimeters each. In each case one of the TLDs was not readable by the vendor. Global Dosimetry suspected that the TLDs were damaged by moisture. Average ambient radiation level for these locations was determined by averaging the three remaining good dosimeters (IR663752).

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.

E. Program Changes Starting in 2007, the mean and two standard deviation values are calculated using the positive values only.

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IV. Results and Discussion A. Aquatic Environment I1. Surface Water Samples were taken from a continuous sampler at two locations (13131 and 24S1) on a monthly schedule. Of these locations only 13B1 located downstream, could be affected by Limerick's effluent releases. The following analyses were performed.

Tritum Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-1.1, Appendix C). Tritium activity was detected in one sample at a concentration of 272 pCi/L.

Although not a drinking water pathway, the dose via the drinking water pathway would result in a calculated dose to a child (total body) of 0.028 mrem, which was 0.47% of the 10 CFR 50, Appendix I dose limit.

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-1.2, Appendix C). All nuclides were less than the MDC.

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:

Samples from all locations were analyzed for concentrations of total gross beta (Tables C-11.1, Appendix C). The values ranged from 2.2 to 8.6 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C).

Tritum Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-11.2, Appendix C). Tritium activity was detected in one sample at a concentration of 189 pCi/L.

The dose via the drinking water pathway was calculated at 0.020 mrem to a child (total body), which was 0.33% of the 10 CFR 50, Appendix I dose limit.

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Gamma Spectromety Samples from all locations were analyzed for gamma emitting nuclides (Table C-11.3, Appendix C). All nuclides were less than the MDC.

3. Fish Fish samples comprised of catfish/bullhead (bottom feeder) and sunfish (predator) 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 Spectrometr The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-I11.1, Appendix C).

Naturally occurring K-40 was found at all stations and ranged from 2,330 to 4,300 pCi/kg wet and was consistent with levels detected in previous years. No other gamma emitting nuclides were found.

Historical levels of Cs-1 37 are shown in Figure C-2, Appendix C.

4. Sediment Aquatic sediment samples were collected at three locations (116B2, 16C4 and 33A2) semiannually. Of these locations two 166B2 and 16C4 located downstream, could be affected by Limerick's effluent releases. The following analysis was performed:

Gamma Spectromety 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-1 37.

Beryllium-7 was found at locations 16B2 and 16C4 and ranged from 1540 to 6320 pCi/kg dry, respectively. Potassium-40 was found at 16B2, 16C4 and 33A2 and ranged from 11,000 to 12,500, 14,000 - 14,200 and 11,700 to 11,800 pCi/kg dry, respectively.

The fission product Cs-137 was found at location 16B2 at 89 pCi/kg dry. The Cs-137 activity found is attributed to LGS radioactive effluent releases. The dose to a teenager's skin and whole body was conservatively calculated at 2.34E-4 mrem and 2.OOE-4 mrem, respectively. These doses represent 2.09E-4% and 5.98E-4% of the Appendix I to 10 CFR Part 50 dose limits, respectively. The activity detected was consistent with those detected in the pre-operational years. (Figure C-4, Appendix C). No other Limerick fission or activation products were found.

10

B. Atmospheric Environment

1. Airborne

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

Group II represents the location at an intermediate distance from the LGS site (13C1), and Group III represents the control location at a remote distance from LGS (22G1). The following analyses were performed:

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.

Comparison of results among the three groups aid in determining the effects, if any, resulting from the operation of LGS. The results from the On-Site locations (Group I) ranged from 6 to 31 E-3 pCi/m 3 with a mean of 16 E-3 pCi/m 3 . The results from the Intermediate Distance location (Group II) ranged from <8 to 27 E-3 pCi/m 3 with a mean of 16 E-3 pCi/m . The results from the Distant locations (Group Ill) ranged from 7 to 25 E-3 pCi/m 3 with a mean of 17 E-3 pCi/m 3 . Comparison of the 2007 air particulate data with previous years data indicate no effects from the operation of LGS (Figure C-4, Appendix C). In addition a comparison of the weekly mean values for 2007 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 53 to 136 E-3 pCi/m 3 . All other nuclides were less than the MDC.

b. Airborne Iodine Continuous air samples were collected from five locations (10S3, 11S1, 14S1, 13C1, and 22G1) and analyzed weekly for 1-131 (Table C-VI.1, Appendix C). All results were less than the MDC.

11

2. Terrestrial

a. Milk Samples were collected from five locations (10F4, 18E1, 199B1, 23F1, and 25C1) biweekly April through November and monthly December through March. Samples from two additional locations (36E1 and 25E1) were taken quarterly.

The following analyses were performed:

Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VII.1, Appendix C). All results were less than the MDC.

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

Naturally occurring K-40 activity was found in all samples and ranged from 1,070 to 1,630 pCi/L. All other nuclides were less than the MDC.

b. Broad Leaf Vegetation Three 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:

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

Cosmogenic Be-7 was found in 27 of 32 samples and ranged from 111 to 2550 pCi/kg wet. Naturally occurring K-40 was found in all samples and ranged from 2020 to 7,160 pCi/kg wet. All other nuclides were less than the MDC.

C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO4) 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 5.5 to 12.8 mR/standard month. A comparison of the Site Boundary and Intermediate Distance data to the Control Location data, 12

indicate that the ambient gamma radiation levels from the Control Location 5H1 were consistently higher. 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.

E. Land Use Survey A Land Use Survey conducted in August 2007 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 ft2 in each of the sixteen 22 % degree sectors around the site. Two new gardens are included in the 2007 survey. The garden in the E sector is further away than 2006. The garden in the WNW sector is closer than 2006. 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 Milk Farm Miles Miles Miles 1N 0.6 1.8 4.7 2 NNE 0.5 1.8 3 NE 0.7 1.6 4 ENE 0.7 0.7 5E 0.6 1.3 6 ESE 0.5 0.3 7 SE 0.7 0.2 8 SSE 1.0 1.1 9S 1.0 1.2 4.2 10 SSW 0.8 1.0 2.0 11 SW 1.0 0.6 12 WSW 0.6 2.3 2.7 13 W 0.7 0.8 2.8 14 WNW 0.7 0.7 15 NW 0.7 1.6 16 NNW 0.7 1.3 13

F. 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 28 analytes (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:

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 (i.e., 20% <

bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.

For the primary laboratory, 17 out of 19 analytes met the specified acceptance criteria. Two samples did not meet the specified acceptance criteria for the following reasons:

1. Teledyne Brown Engineering's Analytics March 2007 1-131 in charcoal result of 34.7 pCi was lower than the known value of 71.3, resulting in a found to known ratio of 0.49. A new technician counted the charcoal cartridge on the back rather than the face side. Due to decay of the 1-131, recounting could not be performed.

Counting the 2nd quarter Analytics charcoal cartridge on the face 14

and the back resulted in approximately 220% more activity on the face of the cartridge. This indicates that we would have had acceptable results (ratio approximately 1.07) if the cartridge had been counted on the face side.

2. Teledyne Brown Engineering's ERA July 2007 Cs-1 34 result of 57.6 pCi/L exceeded the lower acceptance limit of 60.2 pCi/L. The high activity of the sample resulted in the lower acceptance limit of 8.66, although the ratio of found to known was 83.6%, which is considered acceptable by TBE.

For the secondary laboratory, 18 out of 19 analytes met the specified acceptance criteria. One sample did not meet the specified acceptance criteria for the following reasons:

1. Environmental Inc.'s ERA March 2007 air particulate Cs-1 37 result of 345.3 pCi/L exceeded the upper control limit of 336 pCi/L. The reported result was calculated using composite filter geometry rather than the single filter geometry. The recalculated result of 305.8 pCi/filter fell within the acceptance limits.

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

V. References

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

2. Branch Technical Position Paper, Regulatory Guide 4.8, Revision 1, November 1979.

3. 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.

15

Intentionally Left Blank 16

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2007 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES 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 .8 200 272 <LLD 272 13B1 INDICATOR 0 (PCI/LITER) (1/4) (1/4) VINCENT DAM (272) (272)

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 ZR-95 30 <LLD <LLD 1-131 15 <LLD <LLD 0 CS-134 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0

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, 2007 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES 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 GR-B 48 4 4.7 4.3 5.1 15F4 INDICATOR 0 (PCI/LITER) (31/36) (9/12) (11/12) PHILADELPHIA SUBURBAN WATER COMPANY (2.2/8.6) (2.3/7.0) (2.8/8.6) 8.62 MILES SE OF SITE H-3 16 200 189 <LLD 189 15F7 INDICATOR 0 (1/12) (1/4) PHOENIXVILLE WATER WORKS (189) (189) 6.33 MILES SSE OF SITE GAMMA 48 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD <LLD* 0 FE-59 30 <LLD <LLD 0 CO-60 15 <LLD <LLD 0 ZN-65 30 <LLD <LLD 0 NB-95 15 <LLD <LLD 0 ZR-95 30 <LLD <LLD 0 i-131 15 <LLD <LLD 0 CS-1 34 15 <LLD <LLD 0 CS-137 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 PARENTHESES (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2007 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS FI-BOTTOM FEEDER GAMMA 4 (PCI/KG WET) K-40 N/A 3045 2775 3045 16C5 INDICATOR 0 (2/2) (2/2) (2/2) VINCENT POOL (2820/3270) (2750/2800) (2820/3270) 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 N/A <LLD <LLD 0 CS-1 34 100 <LLD <LLD 0 CS-137 100 <LLD <LLD 0 FI-PREDATOR GAMMA 4 (PCI/KG WET) K-40 N/A 3120 3000 3120 16C5 INDICATOR 0 (2/2) (2/2) (2/2) VINCENT POOL (2920/3320) (2860/3140) (2920/3320) DOWNSTREAM OF DISCHARGE MN-54 130 <LLD <LLD 0 CO-68 130 <LLD <LLD 0 FE-59 260 <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, 2007 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION.

MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS CO-60 130 <LLD <LLD 0 ZN-65 260 <LLD <LLD 0 1-131 N/A <LLD <LLD CS-134 100 <LLD <LLD 0 CS-137 100 <LLD <LLD 0 SEDIMENT GAMMA 6 (PCI/KG DRY) BE-7 NA 3930 <LLD 6320 16C4 INDICATOR 0 (2/4) (1/2) VINCENT DAM (1540/6320) (6320/6320) 2.18 MILES SSE OF SITE K-40 NA 12925 11750 14100 16C4 INDICATOR 0 (4/4) (2/2) (2/2) VINCENT DAM (11000/14200) (11700/11800) (14000/14200) 2.18 MILES SSE OF SITE MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 1-131 NA <LLD <LLD 0 CS-134 150 <LLD <LLD 0 CS-137 180 89 <LLD 89 16B2 INDICATOR 0 (1/4) (1/2) LINFIELD BRIDGE (89) (89) 1.35 MILES SSE OF SITE

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

-A 1- -rrfk rrr-rA-

-~ r nRA O frfAk Ar 0 -rIOffl- 1 llT~l 10 IKIM-A-*rf 1IN nA0=kILMtC00 IM

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2007 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 &50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES 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 GR-B 259 10 16 17 17 22G1 CONTROL 0 (E-3 PCI/CU.METER) (207/208) (51/51) (51/51) MANOR SUBSTATION (6/31) (7/25) (7/25) 17.73 MILES SW OF SITE GAMMA 20 BE-7 NA 82.2 90.3 97.1 13C1 INDICATOR 0 (16/16) (4/4) (4/4) KING ROAD (53.4/136) (65.6/130) (65.6/136) 2.84 MILES SE OF SITE MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 CS-134 10 <LLD <LLD 0 CS-137 10 <LLD <LLD 0 AIR IODINE GAMMA 259 (E-3 PCI/CU.METER) 1-131 70 <LLD <LLD 0 MILK 1-131 (LOW LVL) 118 1 <LLD <LLD 0 (PCI/LITER)

GAMMA 118 K-40 NA 1288 1254 1322 19B1 INDICATOR 0 (92/92) (26/26) (22/22)

(1120/1520) (1070/1630) (1220/1520) 1.95 MILES SSW 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 PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2007 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY, PA REPORTING PERIOD: 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN MEAN MEAN STATION # NUMBER OF PATHWAY SAMPLED ANALYSES ANALYSES LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS CS-1 34 15 <LLD <LLD 0 CS-137 18 <LLD <LLD 0 BA-140 60 <LLD <LLD 0 LA-140 15 <LLD <LLD 0 BROADLEAF VEGETATION GAMMA 32 (PCI/KG WET) BE-7 NA 412.8 606.9 606.9 31G1 CONTROL 0 (16/20) (11/12) (11/12)

(111/1110) (171/2550) (171/2550) 13.6 MILES NW K-40 NA 4694 5274.2 5274.2 31G1 CONTROL 0 (20/20) (12/12) (12/12)

(2020/6780) (3100/7160) (3100/7160) 13.6 MILES NW MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 CO-60 NA <LLD <LLD 0 1-131 60 <LLD <LLD 0 CS-134 60 <LLD <LLD 0 CS-137 80 <LLD <LLD 0 DIRECT RADIATION TLD-QUARTERLY 160 NA 7.3 8.8 11.2 13S2 INDICATOR 0 (MREM/STD. MTH.) (156/156) (4/4) (4/4) 500 KV SUBSTATION (5.2/12) (8.4/9.5) (10.6/12) 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)

APPENDIX B LOCATION DESIGNATION, DISTANCE &

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.

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

S on-site location E : 4-5 miles off-site A 0-1 mile off-site F : 5-10 miles off-site B 1-2 miles off-site G : 10-20 miles off-site C 2-3 miles off-site H : 20-100 miles off-site D 3-4 miles off-site z Station's Numerical Designation within sector and zone, using 1, 2, 3... in each sector and zone.

B-I

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2007 Location Location Description Distance & Direction From Site A RirfacA Water 13B1 Vincent Dam (indicator) 1.75 miles SE 24S1 Limerick Intake (control) 0.20 miles SW B Drinking (Pntahle) Water 15F4 Philadelphia Suburban Water Company (indicator) 8.62 miles SE 15F7 Phoenixville Water Works (indicator) 6.33 miles SSE 16C2 Citizens Home Water Company (indicator) 2.66 miles SSE 28F3 Pottstown Water Authority (control) 5.84 miles WNW C Milk - hi-weekly / monthly 10F4 6.60 miles ESE 18E1 4.21 miles S 19B1 1.95 miles SSW 23F1 Control 5.02 miles SW 25C1 2.69 miles WSW n Milk - quarterly 25E1 4.27 miles WSW 36E1 Control 4.70 miles N F Air Partoiulatea / Air Indine 10S3 Keen Road 0.50 miles E 11SI LGS Information Center 0.38 miles ESE 11S2 LGS Information Center 0.38 miles ESE 13C1 King Road 2.84 miles SE 14S1 Longview Road 0.63 miles SSE 22G1 Manor Substation (control) 17.73 miles SW Eih F,

16C5 Vincent Pool (indicator) Downstream of Discharge 29C1 Pottstown Vicinity (control) Upstream of Intake

r. Rdiment 16B2 Linfield Bridge (indicator) 1.35 miles SSE 16C4 Vincent Dam (indicator) 2.18 miles SSE 33A2 Upstream of Intake (control) 0.84 miles NNW H- Broad LeAf Vegetatinn 11S3 LGS Information Center 0.35 miles ESE 13S3 LGS 500 KV Yard 0.24 miles SE 31G1 Prout's Jollyview Farm 13.6 miles NW B-2

TABLE B-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2007 Location Location Description Distance & Direction From Site H Fnveronmpntal Donoimtry - TID Silep Rund=~

36S2 Evergreen & Sanatoga Road 0.60 miles N 3S1 Sanatoga Road 0.44 miles NNE 5S1 Possum Hollow Road 0.45 miles NE 7S1 LGS Training Center 0.59 miles ENE 10S3 Keen Road 0.50 miles E 11S1 LGS Information Center 0.38 miles ESE 13S2 500 KV Substation 0.41 miles SE 14S1 Longview Road 0.63 miles SSE 18S2 Rail Line along Longview Road 0.26 miles S 21S2 Near Intake Building 0.19 miles SSW 23S2 Transmission Tower 0.53 miles SW 25S2 Sector Site Boundary 0.46 miles WSW 26S3 Met. Tower #2 0.40 miles W 29S1 Sector Site Boundary 0.55 miles WNW 31S1 Sector Site Boundary 0.26 miles NW 34S2 Met. Tower #1 0.58 miles NNW Intermediate fligtance 36D1 Siren Tower No. 147 3.51 miles N 2E1 Laughing Waters GSC 4.76 miles NNE 4E1 Neiffer Road 4.78 miles NE 7E1 Pheasant Road 4.26 miles ENE 10E1 Royersford Road 3.94 miles E 10F3 Trappe Substation 5.58 miles ESE 13E1 Vaughn Substation 4.31 miles SE 16F1 Pikeland Substation 5.04 miles SSE 19D1 Snowden Substation 3.49 miles S 20F1 Sheeder Substation 5.24 miles SSW 24D1 Porters Mill Substation 3.97 miles SW 25D1 Hoffecker & Keim Streets 3.99 miles WSW 28D2 W. Cedarville Road 3.83 miles W 29E1 Prince Street 4.95 miles WNW 31 D2 Poplar Substation 3.87 miles NW 34E1 Vamell Road 4.59 miles NNW rnntml a'nd RpAcrjl Interest 5H1 Birch Substation (control) 24.76 miles NE 6C1 Pottstown Landing Field 2.14 miles NE 9C1 Reed Road 2.15 miles E 13C1 King Road 2.84 miles SE 15D1 Spring City Substation 3.20 miles SE 17B1 Linfield Substation 1.60 miles S 20D1 Ellis Woods Road 3.06 miles SSW 311D1 Lincoln Substation 3.00 miles WNW B -3

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2007 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 qamma 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 Gamma Spectroscopy Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis tZ a continuous water radiological analysis (Limerick Generating compositor. Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Drinking Water Tritium Quarterly composite RMC-ER5 Collection of water samples for 500 ml TBE, TBE-2011 Tritium analysis in drinking water by liquid from a continuous water radiological analysis (Limerick Generating scintillation compositor. Station)

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

Fish Gamma Spectroscopy Semi-annual samples RMC-ER6 Collection of fish samples for 1000 grams (wet) TBE-2007 Gamma emitting radioisotope analysis collected via radiological analysis (Limerick Generating electroshocking or other Station) Env. Inc., GS-01 Determination of gamma emitters by techniques gamma spectroscopy Sediment Gamma Spectroscopy Semi-annual grab RMC-ER7 Collection of sediment samples for 500 grams (dry) TBE, TBE-2007 Gamma emitting radioisotope analysis samples radiological analysis (Limerick Generating Station) Env. Inc., GS-01 Determination of gamma emitters by gamma soectroscopv 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 earticulate filters

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

Milk 1-131 Bi-weekly grab sample RMC-ER10 Collection of milk samples for 2 gallon TBE, TBE-2012 Radioiodine in various matrices when cows are on radiological analysis (Limerick Generating pasture. Monthly all Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by anion other times exchanae Milk Gamma Spectroscopy Bi-weekly grab sample RMC-ER10 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis when cows are on radiological analysis (Limerick Generating pasture. Monthly all Station) Env. Inc., GS-01 Determination of gamma emitters by other times gamma spectroscopy TLD Thermoluminescence Quarterly TLDs RMC-ER9 Collection of TLD samples for 2 dosimeters Global Dosimetry Dosimetry comprised of two radiological analysis (Limerick Generating Panasonic 814 Station)

(containing 3 each I CaSO4 elements)

Figure B-1 Environmental Sampling Locations Within One Mile of the Limerick Generating Station, 2007 B-6

Figure B-2 Environmental Sampling Locations Between One and Five Miles from the Limerick Generating Station, 2007 B-7

Figure B-3 Environmental Sampling Locations Greater than Five Miles from the Limerick Generating Station, 2007

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, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 13B1 24S1 01/02/07 04/02/07 < 171 < 168 04/02/07 07/02/07 < 163 < 162 08/17/07 10/01/07 272 +/- 122 <177 10/30/07 12/31/07

178 < 180 MEAN 272 +/- 0 C-I

TABLE C-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC 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 13B1 01/02/07 - 01/30/07 < 4 <5 <9 <4 < 11 <5 <8 <5 <6 <5 < 18 <6 01/30/07 - 02/27/07 < 7 <6 <13 <7 < 12 <7 < 12 <8 <7 <7 <28 <8 02/27/07 - 04/02/07 < 8 <8 < 17 <8 < 11 < 10 < 12 < 14 <7 <8 <46 < 13 04/02/07 - 04/30/07 < 4 <4 <8 <5 <7 <4 <7 <7 <3 <4 < 19 <7 04/30/07 - 05/29/07 < 4 <4 <8 <5 <6 <4 <6 <7 <4 <4 < 17 <6 05/29/07 - 07/02/07 < 2 <2 <4 <2 <4 <2 <4 <8 <2 <2 < 16 <5 07/02/07 - 07/30/07 < 3 <4 <9 <4 <9 <4 <8 <10 <4 <5 <27 <8 07/30/07 - 08/28/07 < 1 < 2 <4 <1 <3 < 2 < 3 < 14 < 1 <2 < 20 <6 08/28/07 - 10/01/07 < 5 <4 < 10 <4 < 12 <5 <9 <7 <5 <6 < 17 <5 10/01/07 - 10/30/07 < 2 <2 <5 <2 < 5 <2 <4 <6 <2 <2 < 15 <5 10/30/07 - 12/04/07 < 7 < 6 < 13 <8 < 15 < 11 < 15 < 14 < 7 < 9 < 36 < 14 12/04/07 - 12/31/07 < 5 <4 < 12 <7 < 12 <5 < 11 < 11 < 5 < 5 <26 < 10 MEAN - - - - - - - - - - - -

24S1 01/02/07 - 01/30/07 < 6 <6 < 12 <6 < 14 <6 < 11 <6 <6 <7 <21 <7 01/30/07 - 02/27/07 < 7 <7 <16 <7 < 13 <8 < 10 < 10 <6 <9 <29 <10 02/27/07 - 04/02/07 < 6 <8 < 15 <9 < 17 < 10 < 14 <14 <8 <8 <38 < 12 04/02/07 - 04/30/07 < 5 <6 < 14 <6 < 10 <6 < 10 < 10 <5 <6 <27 <8 04/30/07 - 05/29/07 < 5 <4 < 11 <5 < 10 <5 <7 <8 <4 <5 <21 <8 05/29/07 - 07/02/07 < 1 <1 <3 <1 <3 <1 <2 <5 < 1 <1 <9 <3 07/02/07 - 07/30/07 < 5 <5 < 11 <6 < 12 <5 <9 < 11 <5 <5 <27 <9 07/30/07 - 08/28/07 < 2 <2 <4 <2 <3 <2 <3 < 14 <1 <2 <20 <7 08/28/07 - 10/01/07 < 5 < 5 < 11 <7 < 9 <6 < 9 < 7 < 5 < 5 <22 <8 10/01/07 - 10/30/07 < 2 <2 <5 <2 < 5 <3 <5 <8 <2 <2 < 17 <5 10/30/07 - 12/04/07 < 8 <8 < 18 <9 < 16 < 10 < 16 < 14 <8 <8 <43 <12 12/04/07 - 12/31/07 < 5 <6 < 11 <5 < 10 <5 <11 < 11 <6 <7 <34 <8 MEAN

TABLE C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION 15F4 15F7 16C2 28F3 PERIOD 01/02/07- 01/30/07 3.2 +/- 1.5 <2.1 < 2.2 < 2.2 01/30/07- 02/27/07 3.3 +/- 1.4 4.6 +/- 1.6 3.5 +/- 1.5 4.4 +/- 1.6 02/27/07 - 04/02/07 3.8 +/- 1.6 2.4 +/- 1.4 2.6 +/- 1.5 3.1 +/- 1.5 04/02/07 - 04/30/07 3.2 +/- 1.4 2.2 +/- 1.3 2.2 +/-11.3 3.6 +/- 1.4 04/30/07- 05/29/07 < 2.2 < 2.1 < 2.2 2.3 +/- 1.5 05/29/07- 07/02/07 3.7 +/- 1.7 2.8 +/- 1.7 4.1 +/- 1.8 < 2.4 07/02/07- 07/30/07 5.7 +/- 1.6 5.3 +/- 1.6 4.5 + 1.6 4.2 +/- 1.5 07/30/07 - 08/28/07 7.5 +/- 2.0 6.1 +/- 1.9 6.6 +/-12.0 5.0 +/- 1.8 08/28/07- 10/01/07 6.1 +/- 2.1 5.7 +/- 2.0 5.2 + 2.0 4.3 +/- 1.9 10/01/07- 10/30/07 8.2 +/- 2.0 8.3 +/- 2.1 3.8 +/- 1.8 5.0 +/- 1.8 10/30/07 - 12/04/07 8.6 +/- 1.8 6.4 +/- 1.6 5.9 +/- 1.6 7.0 +/- 1.6 12/04/07- 12/31/07 2.8 +/- 1.7 3.2 +/- 1.8 3.4 +/- 1.8 < 2.4 MEAN 5.1 +/-4.4 4.7 +/- 4.0 4.2 +/- 2.8 4.3 +/- 2.7 TABLE C-II.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION 15F4 15F7 16C2 28F3 PERIOD 01/02/07 - 04/02/07 < 167 < 167 < 171 < 171 04/02/07 - 07/02/07 < 159 < 164 < 160 < 160 07/02/07 - 10/01/07 < 174 189 +/- 115 < 171 < 177 10/30/07 - 12/31/07 < 178 < 174 < 177 < 177 MEAN 189 +/- 0

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-3

TABLE C-II.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- SIGMA STC 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 01/02/07 - 01/30/07 <6 <6

12 <5

13 <6 <9 <7 <7 <6 < 22 <8 01/30/07 - 02/27/07 <7 <6

16 <6

17 <9 <13 < 12 <7 <7

30 < 12 02/27/07 - 04/02/07 <5 <6

12 <5

12 <6 <9 <11 <6 <7

30 11 04102/07 - 04/30/07 <2 <2 <4 <2 <3 <2 <3 <4 <2 <2

10 <3 04/30/07 - 05/29/07 <3 <4 <7 <4 <7 <4 <5 <6 <3 <4

18 <5 05?29/07 - 07/02/07 <2 <3 <6 <2 <5 <3 <5 <9 <2 <2 <19 <7 07/02/07 - 07/30/07 <3 <3 <8 <3 <7 <5 <6

10 <3 <3 < 22 <7 07/30/07 - 08/28/07 <1 <1 <3 <1 <3 <2 <1

<3

14 <1

19 <5 08/28/07 - 10/01/07 <5 <4 <9 <4 <9 <5 < 10 <8 <5 <5 < 22 <6 10/01/07 - 10/30/07 <2 <2 <5 <2 <4 <2 <4 <7 <2 <2

14 <4 10/30/07 - 12/04/07 <4 <5 < 10 <3

10 <5 <8 <8 <4 <5 < 21 <7 12/04/07 - 12/31/07 <5 <6 <11 <5

12 <6 < 10 < 12 <4 <5 < 32 <8 MEAN 15F7 01/02/07 - 01/30/07 <6 <6 <11 <6 <16 <6 *10 <8 <8 <7

26 <7 01/30/07 - 02/27/07 <7 <7

15 <5 <15 <8 *13 <11 <6 <8 < 37 < 12 02/27/07 - 04/02/07 <5 <5

10 <6 <11 <5 <9 < 10 <5 <5 <24 <9 04/02/07 - 04/30/07 <1 <1 <4 <2 <3 <2 <3 <3 <1 <2 <8 <3 04/30/07 - 05/29/07 <4 <4 <9 <5 <8 <4 <8 <7 <4 <4 < 22 <8 05/29/07 - 07/02/07 <3 <3 <6 <3 <5 <3 <5 < 10 <2 <3 < 21 <7 07/02/07 - 07/30/07 <4 <4 < 10 <4 <9 <4 <8

12 <4 <5

30 11 07/30/07 - 08/28/07 <2 <2 <4 <1 <3 <2 <3

15 <1 <2

21 <7 08/28/07 - 10/01/07 <5 <6 <11 <6 <11 <6 <9 <8 <6 <6

26 <4 10/01/07 - 10/30/07 <2 <2 <5 <2 <5 <3 <5 <8 <2 <2 *17 <5 10/30/07 - 12/04/07 <5 <6 < 14 <6 <11 <6 < 10 <8 <5 <6

23 <9 12/04/07 - 12/31/07 <6 <7 <13 <6 <11 <7 < 11 < 12 <6 <7 < 35 <11 MEAN

TABLE C-II.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- SIGMA STC 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 01102/07 - 01/30107 <5 <6 < 14 <6 < 13 <6 < 10 <7 <7 <6 < 21 <8 01/30/07 - 02/27/07 <5 <5 < 11 <6 < 11 <6 < 10 <9 <6 <6 < 24 <8 02/27/07 - 04/02/07 <6 <6 < 10 <6 < 15 <6 <10 < 10 <5 <5 < 24 <11 04/02/07 - 04/30107 <6 <5 < 10 <7 < 13 <6 <12 < 11 <5 <6 < 26 <11 04/30/07 - 05/29/07 <4 <5 < 10 <4 < 10 <5 <9 <7 <4 <4 < 21 <7 05/29/07 - 07/02/07 <2 <2 <4 <2 <4 <2 <4 <7 <2 <2 < 16 <5 07/02/07 - 07/30/07 <5 <4 < 11 <5 < 10 <5 <9 < 12 <4 <4 < 26 <9 07/30/07 - 08/28/07 <1 <2 <4 <2 <3 <2 <3 < 14 <1 <2 <19 <7 08/28/07 - 10/01/07 <4 <3 <9 <5 <9 <4 <7 <6 <4 <4 <17 <5 10/01/07 10/30/07 <2 <2 <5 <2 <4 <2 <4 <6 <2 <2 < 13 <5 10/30/07 - 12/04/07 <6 <7 <12 <7 < 16 <7 < 12 < 12 <6 <6 < 32 <12 12/04/07 - 12/31/07 <6 <7 < 14 <5 < 15 <7 < 10 < 12 <6 <7 < 31 < 10 MEAN L 28F3 01/02107 - 01/30/07 <5 <5 <9 <5 < 11 <5 <8 <6 <5 <5 < 18 <6 01/30/07 - 02/27/07 <6 <5 < 14 <7 <8 <7 <9 <9 <5 <7 < 31 < 12 02/27/07 - 04/02/07 <5 <6 < 10 <6 < 14 <6 <9 <8 <5 <6 < 28 <8 04/02/07 - 04/30/07 <3 <3 < 10 <3 <8 <4 <6 <7 <4 <3 < 22 <7, 04/30/07 - 05/29/07 <4 <5 <9 <5 <8 <5 <9 <7 <4 <5 < 22 <5 05/29/07 07/02/07 <1 <2 <3 <1 <3 <2 <3 <6 <1 <1 <4

- < 12 07102/07 - 07/30/07 <5 <5 < 10 <4 <8 <5 <9 < 12 <5 <6 < 26 <11 07/30/07 - 08/28/07 <2 <2 <5 <2 <4 <2 <4 < 15 <2 <2 < 23 <8 08/28/07 - 10/01/07 <6 <6 < 13 <5 < 14 <7 <9 <8 <5 <5 < 21 <7 10/01/07 - 10/30/07 <1 <1 <3 <2 <3 <2 <3 < 14 <I <I < 18 <7 10/30/07 - 12/04/07 <5 <6 < 13 <6 < 12 <6 < 10 < 10 <5 <6 < 29 < 10 12/04/07 - 12/31/07 <6 <8 < 12 <6 < 13 <7 < 13 < 13 <5 <6 < 33 < 13 MEAN

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

SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 1-131 CS-134 CS-137 PERIOD 05/08/07 3090 t 985 < 88 < 94 < 187 < 95 < 219 < 251 < 88 < 96 10/29/07 2400 +/- 251 < 14 < 15 < 34 < 16 < 32 < 56 < 13 < 14 MEAN 2745 +/- 976 -

16C5 BOTTOM FEEDER 05/08/07 2330 +/- 884 < 51 < 60 < 122 < 29 < 72.8 < 195 < 50 < 55 10/29/07 2840 +/- 352 < 18 < 19 < 41 < 15 < 38 < 88 < 17 < 21 MEAN 2665 +/- 725 -

29Cl PREDATOR 05/09/07 3140 +/- 910 < 81 < 54 < 174 < 82 < 172 < 161 < 73 < 62 10/29/07 2390 +/- 462 < 27 < 31 < 77 < 29 < 65.4 < 110 < 25 < 27 MEAN 2765 +/- 1061 -

29C1 BOTTOM FEEDER 05/09/07 4300 +/- 1100 < 58 < 63 < 174 < 81 < 174 < 210 < 63 < 67 10/29/07 2900 +/- 537 < 37 <44 < 74 < 31 < 88.8 < 176 < 32 < 42 MEAN 3182.5 +/- 1616

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

TABLE C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/KG DRY +/-2 SIGMA STC COLLECTION BE-7 K-40 MN-54 CO-58 CO-60 1-131 CS-134 CS-137 PERIOD 16B2 06/13/07 < 1200 11000 +/- 1860 < 103 < 134 < 109 < 946 < 114 < 127 12/07/07 1540 +/- 676 12500 +/- 1340 < 72 < 87 < 72 < 666 < 67 89 +/- 60 MEAN 1540 +/- 0 11750 +/- 2121 - - - - - 89 +/- 0 16C4 06/13/07 6320 +/- 1310 14200 +/--2730 < 138 < 134 < 190 < 1380 < 130 < 150 12/07/07 < 599 14000 +/- 1430 < 67 < 75 < 62 < 547 < 56 < 72 MEAN 6320 +/- 0 14100 +/- 283 - - - - - -

33A2 06/13/07 < 1020 11700 +/- 2140 < 142 < 89 < 94 < 851 < 79 < 105 12/07/07 < 740 11800 +/- 1280 < 69 < 82 < 60 < 597 < 66 < 73 MEAN - 11750 +/- 141 - - - - - -

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

TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I GROUP II GROUP III PFRIOfl 13C1 22G1

....... RIOD

.. l£ 10S3 11S1 14S1 U U IIUzIUf U IIUOIIi 1is b 14 +/-,5 16 +/- 14:b 14 +/--6 01/08/07 01/15/07 15 4 16 +/- 5 19 +/- 15+/- 5 17 +/- 5 01/15/07 01/22/07 9+/-5 10 +/- 5 9+/- 12+/- 5 15 +/- 5 01/22/07 01/29/07 16 5 16 +/- 5 18 +/- 17+/- 5 17 +/- 5 01/29/07 02/05/07 17 5 16 +/- 5 17 +/- 20 +/-6 25 +/- 6 02/05/07 02/12/07 17+/- 5 13 +/- 5 17 +/- 17+/- 5 15 +/- 5 02/12/07 02/20/07 12 4 12 +/- 5 13 + 12 +/-5 18 +/- 5 02/20/07 02/26/07 9+/-5 12 +/- 6 9+/- <8 11+/- 6 02/26/07 03/05/07 10+/- 4 16 +/- 5 15 +/- 10+/- 5 9+4 03/05/07 03/12/07 18 + 5 18 +/- 5 22 +/- 24 +/-6 20 +/-5 03/12/07 03/19/07 21 +5 17 +/- 5 18 +/- 15+/- 5 18+/- 5 03/19/07 03/27/07 15 4 14 +/- 4 14 +/- 12+/- 4 18 +/-5 03/27/07 04/02/07 17 5 12 +/- 6 12 +/- 15+/- 6 11+/- 6 04/02/07 04/09/07 9+/-4 13 +/- 5 15 +/- 16+/- 5 16 +/-5 04/09/07 04/16/07 9+/-4 9+/-4 6+/- 13+/- 5 7+/-4 04/16/07 04/23/07 14 +/-4 11 +/-4 9+/- 11 +/-4 11 +/-4 04123/07 04/30/07 12 +/-4 12+/- 5 11 +/- 16 5 6 14 +/-5 04/30/07 05/07/07 9+/-4 12+/- 5 8+/- 10+/- 5 10+/- 5 05/07/07 05/15/07 10 +/-4 10+/- 4 10 +/- 10+/- 4 9+/-4 05/15/07 05/21/07 13 5 10 5 16 +/- 11 +/-6 12 +/-6 05/21/07 05/29/07 17 +/-4 16 5 22 +/- 15 +/- 5 17 +/-5 05/29/07 06/04/07 16 6 21 +/-6 16 +/- 16 +/- 6 (1) 06/04/07 06/11/07 11 +/-4 9+/-5 12 +/- 11 +/-5 11 +/-5 06/11/07 06/18/07 15 4 13+/- 5 11 +/- 14 +/-5 16 +/-5 06/18/07 06/25/07 11 +5 15+/- 5 13 +/- 14+/- 5 15 +/-5 06/25/07 07/02/07 18 5 18 5 20 +/- 21 +/-5 18 +/-5 07/02107 07/09/07 20 +/-5 17 5 22 +/- 17+/- 5 18 +5 07/09/07 07/16/07 23:+/- 5 24 +6 22 +/- 26 +/- 6 23 +/-5 07/16/07 07/23/07 15 5 13+/- 5 12 +/- 16 +/- 5 16 +/-5 07/23/07 07/31/07 14 +4 20 +/- 4 20 +/- 20 +/- 4 17 +/-4 07/31/07 08/06/07 19 6 21 +/- 6 22 +/- 19 +/- 6 25 +/-6 08/06/07 08/14/07 21 +/-4 21 +/- 5 19 +/- 26 +/- 5 25 +/-5 08/14/07 08/20/07 12 5 16 +/- 6 19 +/- 16 +/- 6 19 +/-6 08/20/07 08/27/07 7+/-4 10 +/- 5 11 +/- 9+/-5 9 +/-5 08/27/07 09/04/07 22 +/-4 23 +/- 5 22 +/- 27 +/-5 23 +/-5 09/04/07 09/11/07 16 5 17 +/- 5 15 +/- 17+/- 5 22 +/-6 09/11/07 09/17/07 12 5 11 +5 13 +/- 20 +/-6 11 +/-5 09/17/07 09/24/07 20 +/-5 18 5 20 +/- 26 +/-6 19 +/-5 09/24/07 10/01/07 22 +/-5 22 +/-5 21 +/- 26 +/-6 21 +/-5 10/01/07 10/08/07 13+/- 5 13+/- 5 15 +/- 11 +/-5 21 +/-6 10/08/07 10/15/07 17 5 15+/- 5 20 +/- 19+/- 6 18 +/-5 10/15/07 10/22/07 24 +/-5 25 +6 31 +/- 23 +/-6 24 +/-6 10/22/07 10/29/07 16 5 13+/- 5 9+/- 13+/- 5 18 +/-5 10/29/07 11/05/07 12 5 18 +/- 6 20 +/- 19+/- 6 17 +/-6 11/05/07 11/12/07 14 +/-5 13 +/- 5 16 +/- 15 +/-5 19 +5 11/12/07 11/19/07 21 +/-5 19 +/- 5 23 +/- 21 +/-6 23 +/-6 11/19/07 11/26/07 10 +/- 5 14 +/- 5 15 +/- 17+/- 5 22 +/-6 11/26/07 12/03/07 15 +/- 5 20 +/- 6 19 +/- 15+/- 5 14 +/-5 12/03/07 12/10/07 15 +/- 5 14 +/- 5 12 +/- 9+/-5 13 +/-5 12/10/07 12/17/07 20 +/-5 17 +/- 5 20 +/- 18 +/-5 20 +/-5 12/17/07 12/24/07 17+/- 5 18 +/- 5 27 +/- 18+/- 5 19 +/-6 12/24/07 12/31/07 23 +5 17 +/- 5 23 +/- 25 +/-6 24 +/-6 MEAN 15 +/- 8 15 +/- 8 16 +/- 10 17 +/- 10 17 +/- 10

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-8

TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP II- INTERMEDIATE DISTANCE LOCATIONS GROUP III - CONTROL LOCATIONS COLLECTION MIN MAX MEAN + COLLECTION MIN MAX MEAN+ COLLECTION MIN MAX MEAN+/-

PERIOD 2SD PERIOD 2SD P[:RI~lr' PERIOD 2SD U01/02/U07 01129/07 I 14 +/-.6 01/02/07 - 01/29/07 12 17 15 +/- 4 0llO2/07 - 01/29/07 14 17 16+/- 3 01/29/07 02/26/07 9 17 14:+/- 6 01/29/07 - 02/26/07 <8 20 16 +/-8 01/29/07 - 02/26/07 11 25 17 +/- 12 02/26/07 04/02/07 10 22 16 6 02/26/07 - 04102/07 10 24 15 +/- 10 02/26/07 - 04/02/07 9 20 15 +/- 10 04/02/07 04/30/07 6 15 11-+/- 5 04/02/07 - 04/30/07 11 16 14 +/- 5 04/02/07 - 04/30/07 7 16 12+/- 7 04/30/07 05/29/07 8 22 13 8 04/30/07 - 05/29/07 10 15 11 +/- 5 04130/07 - 05/29/07 9 17 12 +/- 7 05/29/07 07/02/07 9 21 15 7 05/29/07 - 07/02/07 11 21 15 +/- 7 06/04/07 - 07/02/07 11 18 15 +/- 6 07/02/07 07/31/07 12 24 18 8 07/02/07 - 07/31/07 16 26 19 +/- 9 07/02/07 - 07/31/07 16 23 18 +/- 7 07/31/07 08/27/07 7 22 17 +/- 10 07/31/07 - 08/27/07 9 26 18 +/- 14 07/31/07 - 08/27/07 9 25 20+/- 15 08/27/07 10/01/07 11 23 18+/- 8 08/27/07 - 10/01/07 17 27 23 +/- 9 08/27/07 - 10/01/07 11 23 19 +/- 10 10/01/07 10/29/07 9 31 18 + 12 10/01/07 - 10/29/07 11 23 17 +/- 11 10/01/07 - 10/29/07 .18 24 20 +/- 6 10/29/07 12/03/07 10 23 17+/- 7 10/29/07 - 12/03/07 15 21 17+/- 5 10/29/07 - 12/03/07 14 23 19 +/- 8 12/03/07 12/31/07 12 27 19+/- 8 12/03/07 - 12/31/07 9 25 18 13 12/03/07 - 12/31/07 13 24 19 +/- 10 01/02/07 - 12/31/07 6 31 16 +/- 5 01/02/07 - 12/31/07 < 8 27 16 +/- 6 01/02/07 - 12/31/07 7 25 17 +/- 6

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

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION BE-7 MN-54 CO-58 CO-60 CS-134 CS-137 PERIOD 10U33 U'HU.IUf IU'+ <3 U IIU/-/U f <3 04/02/07 07/02/07 77 +/- 40 <6 <4 <3

<3 <3 07/02/07 10/01/07 82 +/- 28 <3 <3 <2

<3 10/01/07 121/31/07 60 +/- 27 <2 <4 <4 <3 MEAN 81 +/- 37

<3 11S1 01/02107 04/02/07 67 +/- 31 <3 <4 <4 <3

<3 04/02107 07/02107 81 +/- 36 <4 <5 <4 <3 07/02/07 10/01/07 88 +/- 31 <2 <3 <2 <4 <2 10/01/07 12131/07 72 +/- 24 <2 <3 <4 <3 <2 MEAN 77 +/- 19 13C1 01/02/07 04/02107 66 +/- 26 <3 <3 <3 <3 <2 04/02/07 07/02107 77 +/- 36 <3 <5 <4 <4 <3 07/02107 10/01/07 110 +/- 28 <3 <5 <3 <5 <3 10/01/07 12/31/07 136 +/- 26 <2 <3 <3 <2 <2 MEAN 97 +/- 64 14S1 01/02/07 04/02/07 67 +/- 33 <3 <5 <4 <4 <3 04/02107 07/02/07 105 +/- 57 <4 <7 <4 <4 <4 07/02/07 10/01/07 71 +/- 23 <3 <4 <3 <4 <3 10/01/07 .12/31/07 53 +/- 27 <3 <4 <4 <3 <3 MEAN 74 +/- 44 22G1 01/02107 04/02107 66 +/- 26 <2 <3 <3 <3 <2 04/02107 07/02/07 130 +/- 48 <4 <7 <3 <4 <3 07/02107 10/01/07 95 +/- 29 <3 <4, <3 <4 <3 10/01/07 12131/07 71 +/- 26 <2 <2 <2 <3 <2 MEAN 90 +/- 59

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-10

TABLE C-VI.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION GROUP I I GROUP II I GROUP III PERIOD 10S3 lisi 14S1 13C1 22G1 UI/U2IU( - Ol/uts/u/ <l1 < lb <11 <11 01/08/07 - 01/15/07 < 29 < 31 < 31

32

17 01/15/07 - 01/22/07 < 25 < 28 < 28 < 28

15 01/22/07 - 01/29/07 < 30 < 50

50

51

50 01/29/07 - 02/05/07 < 22 < 37 <38

38 < 38 02/05/07 - 02/12/07 < 42 < 45 < 46 < 26 < 46 02/12/07 - 02/20/07 < 23

25

26 < 26 <17 02/20/07 - 02/26/07 < 26 < 36 <36 < 37 < 36 02/26/07 - 03/05/07 < 24

26 <26 < 26

13 03/05/07 - 03/12/07 < 35 < 38 < 39 < 39

21 03/12/07 - 03/19/07

14

16

16

16

12 03/19/07 - 03/27/07 < 26

28 < 29 < 29

21 03/27/07 - 04/02/07 < 45

48 < 49 < 49

27 04/02/07 - 04/09/07 < 40 <44 <44 < 45 < 24 04/09/07 - 04/16/07 <34 < 36 < 37 < 37

20 04/16/07 - 04/23/07 < 45 < 49 < 50 < 40 < 50 04/23/07 - 04/30/07

21 < 42 < 42 < 43 < 42 04/30/07 - 05/07/07 < 57 < 62 < 63 < 63 < 50 05/07/07 - 05/15/07

25 < 27 < 28 < 28 < 28 05/15/07 - 05/21/07 < 27 < 29

30

30 *18 05/21/07 - 05/29/07 < 44 < 48 < 48 < 49

32 05/29/07 - 06/04107

15 <16

17 <17

10 06/04/07 - 06/11/07

18 <19

14

19

19 06/11/07 - 06/18/07

16 <18

18

18

10 06/18/07 - 06/25/07 < 53 < 57 <58

58 < 39 06/25/07 - 07/02/07 < 20

21 <22

22

16 07/02/07 - 07/09/07 < 26

29

29 < 29 < 19 07/09/07 - 07/16/07 < 20 < 40 < 41 < 41 < 41 07/16/07 - 07/23/07 < 40 < 43 <44 <44

26 07/23/07 - 07/31/07

51 < 56 <56 < 57 < 29 07/31/07 - 08/06/07 < 49 < 53 <54 < 55 < 30 08/06/07 - 08/14/07

16

31 < 31 < 32

32 08/14/07 - 08/20/07 < 63 <54

69 < 69 < 69 08/20/07 - 08/27/07 < 28 < 55 < 55 < 56

56 08/27/07 - 09/04/07 < 46 < 50 < 25

51 < 51 09/04/07 - 09/11/07 < 20 < 40 < 40 < 41 < 40 09/11/07 - 09/17/07 < 45 < 61 < 61 < 62 < 61 09/17/07 - 09/24/07 <15 < 27 < 27 < 28

27 09/24/07 - 10/01/07 (1) < 42 < 42 < 43 < 42 10/01/07 - 10/08/07 <15 < 39 < 40

70 < 39 10/08/07 - 10/15/07 < 24 < 61

62

63 < 62 10/15/07 - 10/22/07

16 < 31

31 < 31 < 31 10/22/07 - 10/29/07 < 25 < 50

50

51 <50 10/29/07 - 11/05/07

15 < 30

30 < 31 < 30 11/05/07 - 11/12/07 < 35

61

62 < 63 < 62 11/12/07- 11/19/07 < 54 < 59 < 59 < 60 < 36 11/19/07- 11/26/07 < 58

63 < 63 <64

27 11/26/07 - 12/03/07 < 26

28

28 < 28

16 12/03/07- 12/10/07

19

38 < 39 < 39 < 39 12/10/07 - 12/17/07 < 26 < 28

29 < 29 < 15 12/17/07 - 12/24/07 <44 < 48

20 < 49 < 50 12/24/07 - 12/31/07 <22 <44 < 45 < 45 < 45 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-11

TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF E-3 PCI/LITER +/- 2 SIGMA CONTROL FARMS I INDICATOR FARMS COLLECTION 23F1 36E1 10F4 18E1 19B1 25C1 25E1 PERIOD 01/16/07 < 0.8 < 0.4 < 0.7 < 0.7 < 0.4 < 0.8 < 0.4 02/13/07 < 0.6 < 0.7 < 0.6 < 0.6 < 0.6 03/13/07 < 0.7 < 0.8 < 0.8 < 0.7 < 0.8 04/03/07 < 0.8 < 0.6 < 0.7 < 0.7 < 0.6 < 0.5 < 0.8 04/17/07 < 0.5 < 0.9 < 0.6 < 0.6 < 0.6 05/01/07 < 0.6 < 0.6 < 0.6 < 0.6 < 0.6 05/15/07 < 0.6 < 0.8 < 0.8 < 0.6 < 0.7 05/30/07 < 0.8 < 0.7 < 0.6 < 0.9 < 0.8 06/12/07 < 0.7 < 0.5 < 0.5 < 0.6 < 0.9 06/26/07 < 0.7 < 0.6 < 0.6 < 0.6 < 0.7 07/10/07 < 0.8 < 0.8 < 0.9 < 0.8 < 0.8 < 0.8 < 0.9 07/24/07 < 0.7 < 0.7 < 0.8 < 1.0 < 0.6 08/07/07 < 0.5 < 0.4 < 0.5 < 0.6 < 0.4 08/21/07 < 0.6 < 0.7 < 0.8 < 0.5 < 0.8 09/04/07 < 0.7 < 0.8 < 0.9 < 0.8 < 0.7 09/18/07 < 0.7 < 0.4 < 0.4 < 0.5 < 0.5 10/02/07 < 0.6 < 0.5 < 0.6 < 0.5 < 0.5 < 0.4 < 0.5 10/16/07 < 0.8 < 0.6 < 0.6 < 0.7 < 0.8 10/30/07 < 0.5 < 0.7 < 0.7 < 0.6 < 0.6 11/13/07 < 0.7 < 0.7 < 0.8 < 0.7 < 0.7 11/27/07 < 0.6 < 0.6 < 0.7 < 0.7 < 0.6 12/11/07 < 0.6 < 0.6 < 0.6 < 0.6 < 0.7 MEAN (1) See Exceptions Section for Explanation C-12

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 CS-134 CS-137 BA-140 LA-140 PERIOD 10F4 01/16/07 - 01/16/07 1240 +/- 141 < 6 < 5 < 28 <7 02/13/07- 02/13/07 1210 +/- 109 < 4 <4 < 23 <7 03/13/07 - 03/13/07 1300 +/- 142 < 6 <6 < 28 < 10 04/03/07- 04/03/07 1220 +/- 130 < 6 < 6 < 21 < 7 04/17/07- 04117107 1250 +/- 102 < 4 <4 < 20 <6 05/01/07- 05/01/07 1290 +/- 158 < 8 < 7 < 33 < 11 05/15107 - 05/15/07 1310 +/- 73 < 3 < 3 < 13 < 5 05/29/07 - 05/29/07 1270 +/- 153 < 5 <7 < 51 < 13 06/12/07 - 06/12/07 1360 +/- 126 < 4 <4 < 28 <6 06/26/07- 06/26/07 1330 +/-95 < 3 <3 < 20 < 6 07/10/07 - 07/10/07 1170 +/- 109 < 5 <5 < 27 < 8 07/24/07 - 07/24/07 1330 +/- 82 < 3 <3 < 24 < 6 08/07/07'- 08/07/07 1260 +/- 186 < 6 < 9 < 36 < 10 08/21/07 - 08/21/07 1350 +/- 137 < 5 <5 < 37 < 12 09/04/07 - 09/04/07 1410 +/- 161 < 6 <6 < 49 < 12 09/18/07 - 09/18/07 1420 +/- 145 < 5 <7 < 39 < 13 10/02/07 - 10/02/07 1270 +/- 143 < 6 < 6 < 31 < 12 10/16/07 - 10/16/07 1360 +/- 163 < 6 <6 < 34 < 11 10/30/07 - 10/30/07 1310 +/- 175 < 6 <8 < 31 < 10 11/13/07 - 11/13/07 1320 +/- 62 < 2 <2 < 35 < 12 11/27/07 - 11/27/07 1300 +/- 144 < 5 < 5 < 34 < 13 12/11/07- 12/11/07 1280 +/- 47 < 2 <2 < 13 <4 MEAN 1298 +/- 123 - - - -

18E1 01/16/07 - 01/16/07 1170 +/- 198 < 8 < 9 < 31 < 7 02/13/07- 02/13/07 1270 +/- 151 < 5 < 7 < 32 < 9 03/13/07 - 03/13/07 1430 +/- 148 < 6 < 7 < 31 < 9 04/03107 - 04/03/07 1250 +/- 155 < 6 < 7 < 24 < 8 104/17/07 - 04/17/07 1230 +/- 91 < 3 < 4 < 19 < 4

.05/01/07 - 05/01/07 1160 +/- 197 < 7 < 8 < 45 < 10 05/15/07 - 05/15/07 1210 +/- 89 < 3 < 4 < 16 < 5 05/30/07 - 05/30/07 1240 +/- 126 < 5 < 6 < 31 < 10 06/12/07- 06/12/07 1150 +/- 164 < 6 < 7 < 28 < 6 06/26/07 - 06/26/07 1240 +/- 113 < 5 < 5 < 38 < 14 07/10/07 - 07/10/07 1240 +/- 142 < 3 < 4 < 22 < 7 07/24/07 - 07/24/07 1250 +/- 97 < 4 < 4 < 30 < 7 08/07/07 - 08/07/07 1310 +/- 167 < 7 < 8 < 42 < 11 08/21/07 - 08/21/07 1240 +/- 168 < 7 < 7 < 51 < 13 09/04/07- 09/04/07 1290 +/- 185 < 6 < 7 < 52 < 13 09/18/07 - 09/18/07 1310 +/- 124 < 5 < 5 < 35 < 10 10/02/07- 10/02/07 1300 +/- 126 < 5 < 5 < 24 < 6 10/16/07 - 10/16/07 1230 +/- 153 < 6 < 7 < 29 < 6 10/30/07 - 10/30/07 1120 +/- 183 < 8 < 8 < 33 < 14 11/13/07- 11/13/07 1140 +/- 71 < 3 < 3 < 44 < 12 11/27/07 - 11/27/07 1290 +/- 143 < 6 < 7 < 39 < 13 12/11/07 - 12/11/07 1150 +/- 60 < 2 < 3 < 19 < 5 MEAN 1237 +/- 144 - - - -

C- 13

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 CS-134 CS-137 BA-140 LA-140 PERIOD 19B1 01/16/07 - 01/16/07 1250 +/- 184 < 6 < 8 < 32 < 11 02/13/07 - 02/13/07 1320 +/- 147 < 6 < 7 < 41 < 11 03/13/07 - 03/13/07 1260 + 156 < 7 < 7 < 31 < 10 04/03/07 - 04/03/07 1350 + 160 < 6 < 7 < 21 < 9 04/17/07- 04/17/07 1290 + 104 < 4 < 5 < 21 < 6 05/01/07 - 05/01/07 1300 +/- 140 < 5 < 6 < 28 < 9 05/15/07 - 05/15/07 1360 +/- 87 <3 <3 < 15 < 5 05/29/07- 05/29/07 1390 +/- 126 < 5 < 6 < 39 < 14 06/12/07 - 06/12/07 1400 + 151 < 6 < 6 < 30 < 7 06/26/07 - 06/26/07 1400 +/- 132 < 5 < 6 < 46 < 14 07/10/07 - 07/10/07 1230 +/- 142 < 6 < 7 <,39 < 10 07/24/07 - 07/24/07 1260 +/- 117 < 5 < 5 < 38 < 10 08/07/07- 08/07/07 1430 +/- 202 < 8 < 8 < 39 < 10 08/21/07 - 08/21/07 1250 +/- 125 < 5 < 6 < 38 < 12 09/04/07- 09/04/07 1320 +/- 90 < 4 < 4 < 28 < 8 09/18/07 - 09/18/07 1520 +/- 142 < 5 < 6 < 39 < 14 10/02107 - 10/02/07 1220 +/- 148 < 5 < 6 < 30 < 10 10/16/07 - 10/16/07 1390 +/- 156 < 7 < 8 < 37 < 11 10/30/07 - 10/30/07 1280 +/- 194 < 9 < 10 < 43 < 14 11/13/07 - 11/13/07 1340 +/- 65 < 2 < 3 < 38 < 12 11/27/07 - 11/27/07 1290 +/- 157 < 7 < 8 < 44 < 13 12/11/07- 12/11/07 1240 +/- 58 < 2 < 2 < 16 < 4 MEAN 1322 +/- 153 - - -

23F1 01/16/07 - 01/16/07 1170 +/- 129 <4 < 5 < 25 < 6 02/13/07 - 02/13/07 1110 +/- 140 < 5 < 6 < 35 < 11 03/13/07 - 03/13/07 1250 +/- 182 < 7 < 8 < 35 < 13 04/03/07- 04/03/07 1290 +/- 172 <5 < 8 < 26 < 7 04/17/07- 04/17/07 1220 +/- 79 < 3 < 3 < 16 < 4 05/01/07 - 05/01/07 1070 +/- 149 <6 < 7 < 33 < 11 05/15/07 - 05/15/07 1330 +/- 91 <3 < 4 < 16 < 5 05/30/07- 05/30/07 1220 +/- 125 <4 < 6 < 35 < 9 06/12/07 - 06/12/07 1330 +/- 158 <6 < 8 < 31 < 10 06/26/07 - 06/26/07 1340 +/- 102 <4 < 5 < 35 < 12 07/10/07 - 07/10/07 1230 +/- 177 <7 < 7 < 39 < 13 07/24/07 - 07/24/07 1410 +/- 89 <3 < 4 < 26 < 7 08/07/07 - 08/07/07 1240 +/- 218 <8 < 8 < 48 < 13 08/21/07 - 08/21/07 1630 +/- 173 <5 < 8 < 52 < 14 09/04/07 - 09/04/07 1300 +/- 147 < 6 < 7 < 43 < 15 09/18/07 - 09/18/07 1090 +/- 127 < 5 < 6 < 42 < 14 10/02/07 - 10/02/07 1400 +/- 151 < 5 < 7 < 29 < 8 10/16/07 - 10/16/07 1260 +/- 120 <4 < 5 < 22 < 8 10/30/07 - 10/30/07 1190 +/- 218 < 7 < 10 < 47 < 7 11/13/07 - 11/13/07 1280 +/- 79 <3 < 3 < 47 < 15 11/27/07 - 11/27/07 1290 +/- 142 <6 < 7 < 50 < 13 12/11/07 - 12/11/07 1240 +/- 61 <2 < 2 < 17 < 5 MEAN 1268 +/- 240 - - -

C- 14

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION K-40 CS-134 CS-137 BA-140 LA-140 PERIOD 25C1 01/16107 - 01/16/07 1230 +/- 155 < 6 <7 < 28 < 6 02/13/07 - 02/13/07 1370 +/- 161 <6 < 7 < 37 < 15 03/13/07 - 03/13/07 1250 +/- 127 <5 < 6 < 28 < 9 04/03107- 04/03/07 1270 +/- 143 <5 < 6 < 19 < 7 04/17/07- 04/17/07 1250 +/- 98 <4 <4 < 21 < 7 05/01/07 - 05/01/07 1230 +/- 159 <6 <7 < 33 < 11 05/15/07 - 05/15/07 1240 +/- 97 <3 <4 < 18 < 6 05/29/07 - 05/29/07 1210 +/- 99 <4 <4 < 28 <9 06/12/07 - 06/12/07 1280 +/- 176 <6 <8 < 29 < 10 06/26/07 - 06/26/07 1340 +/- 116 <4 <5 < 37 < 13 07/10/07 - 07/10/07 1440 +/- 147 <5 <6 < 31 < 7 07/24/07 - 07/24/07 1360 +/- 102 <4 <5 < 30 < 10 08/07/07 - 08/07/07 1320 +/- 159 < 6 <6 < 35 < 11 08/21/07 - 08/21/07 1370 +/- 110 <4 <5 < 37 < 12 09/04/07 - 09/04/07 1250 +/- 196 <7 <8 < 55 < 12 09/18/07 - 09/18/07 1300 +/- 155 <6 <7 < 41 < 13 10/02/07- 10/02/07 1280 +/- 113 < 5 <5 < 24 <8 10/16/07 - 10/16/07 1260 +/- 141 <6 < 6 < 28 < 10 10/30/07 - 10/30/07 1420 +/- 178 <6 < 8 < 35 < 12 11/13/07 - 11/13/07 1260 +/- 67 <3 < 3 < 43 < 13 11/27/07 - 11/27/07 1210 +/- 112 < 5 <6 < 39 < 11 12/11/07 - 12/11/07 1270 +/- 63 <3 < 3 < 22 < 7 MEAN 1291 +/- 131 - - - -

25E1 01/16/07 - 01/16/07 1320 +/- 139 <5 <6 < 29 < 10 04/03/07 - 04/03/07 1360 +/- 127 <5 <7 < 21 <6 07/10/07 - 07/10/07 1360 +/- 168 <6 <7 < 41 < 12 10/02/07 - 10/02/07 1150 +/- 120 <4 <5 < 24 <8 MEAN 1298 +/- 200 - - - -

36E1 01/16/07 - 01/16/07 1240 +/- 159 < 6 <7 < 35 < 10 04/03/07 - 04/03/07 1250 +/- 116 < 4 <5 < 20 <4 07/10/07 - 07/10/07 1100 +/- 136 < 5 <7 < 31 < 11 10/02/07- 10/02/07 1120 +/- 120 < 4 <5 < 23 < 6 MEAN 1178 +/- 157 - - - -

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C- 15

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES COLLECTED INTHE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION TYPE BE-7 K40 MN-54 CO-58 CO-60 1-131 CS-134 CS-137 PERIOD 11S3 Ub/21/U/ Cabbage 331U Z LOO C 13

< 1~

I'40 331IU zaaO < Ia < 13 < id < its < 14 <

110 Collards 111 +/- 62 5770 +/- 201 <8 <9 <9 <24 <7 <8 Zucchini Leaves 1060 +/- 210 4020 +/- 384 < 18 <19 < 19 < 48 < 16 < 19 07/17/07 Cabbage < 37 2020 +/- 82 <3 <4 <3 < 25 <3 <4 Collards 134 +/- 71 4820 +/- 184 <8 <9

10

56 <7 <9 Zucchini Leaves 334 +/- 204 4200 +/- 533 < 22 < 30 < 24 < 50 < 23 < 25 08/13/07 Cabbage 125 +/- 45 3510 +/- 124 <7 <8 <7 <54 <8 <8 Collards 243 +/- 66 6470 +/- 183 <7 <8 <7 < 53 <7 <8 09/10/07 Cabbage < 135 2450 +/- 274 < 14 < 17 < 13

32 < 13 < 14 MEAN 335 +/- 731 4063 +/- 2911 13S3 06/21/07 Cabbage 223 +/- 117 4360 +/- 313 <11

12 < 10 < 37 <1*1 <11 Collards < 181 5130 +/- 543 < 18 < 20 < 15 < 40

12 < 16 Zucchini Leaves 633 +/- 221 4340 +/- 443 < 14 < 15 < 16 < 54 < 12 < 12 07/17/07 Cabbage 256 +/- 71 4800 +/- 187 <8 <9 <8 <44 <7 <8 Collards 188 +/- 83 4740 +/- 150 <6 <6 <6 < 48 <6 <6 Zucchini Leaves 697 +/- 92 4880 +/- 194 <8 <9 <9 < 52 <7 <8 08/13/07 Cabbage 406 +/- 54 4400 +/- 120 <7 <8 <7 < 57 < 11 <7 Collards 273 +/- 55 6480 +/- 158 <5 <6 <5 < 42 <5 <5 Zucchini Leaves 1110 +/- 75 5790 +/- 160 <7 <8 <7

52 <6 <7 09/10/07 Cabbage 535 +/- 205 6780 +/- 486

23 < 21 < 21 < 42 < 19 < 21 Collards 277 +/- 154 5610 +/- 519 < 22 < 20 < 25 < 34

17 < 20 MEAN 460 +/- 580 5210 +/- 1699

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

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES COLLECTED INTHE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/-2 SIGMA STC COLLECTION TYPE BE-7 K-40 MN-54 CO-58 CO-60 1-131 CS-134 CS-137 PERIOD 31G1 06/21/07 Cabbage 225 1 198 4910 +/- 482 < 22 < 23 < 22 < 59 < 18 < 22 Lettuce 256 +/- 119 3100 +/- 345 < 16 < 13 < 15 < 40 ,11 < 15 Zucchini Leaves 662 +/- 154 5530 +/- 446 < 17 < 20 < 20 < 54 < 15 < 15 07/17/07 Acorn Squash 758 +/- 79 5760 +/- 165 <6 < 7 < 6 < 39 <5 <6 Cabbage < 69 4660 +/- 178 <7 < 8 < 7 < 48 <6 <7 Zucchini Leaves 331 +/-:78 5990 +/- 188 <8 < 9 < 8 < 56 <7 <8 08/13/07 Acorn Squash Leaves 2550 +/- 70 4440 +/- 108 <6 < 7 < 6 < 59 < 7 <7 Cabbage 371 +/- 53 7160 +/- 152 <8 < 8 < 8 < 59 <8 <7 Zucchini Leaves 934 +/- 62 5500 +/- 124 <6 < 8 <6 < 54 <7 <6 09/10/07 Cabbage 233 +/- 143 5690 +/- 395 < 16 < 17 < 18 < 41 < 16 < 17 C) Lettuce 171 +/- 112 5600 +/- 291 < 10 < 10 < 12 < 20 <9 < 10 Zucchini Leaves 185 +/- 91 4950 +/- 293 < 12 < 11 < 10 < 22 < 11 < 11 MEAN 607 +/- 1388 5274 +/- 1976 - - - - - -

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

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR LIMERICK GENERATING STATION, 2007 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.

36S2 7.5 +/- 0.3 7.7 +/- 0.7 7.4 +/- 0.4 7.6 +/- 0.5 7.4 +/- 0.4 36D1 6.8 +/- 0.3 6.7 +/- 0.5 6.6 +/- 1.3 6.7 +/- 0.6 7.0 +/- 0.7 2E1 7.4 +/- 1.1 6.9 +/- 0.3 7.0 +/- 0.2 7.9 +/- 0.7 7.9 +/- 1.0 3S1 7.3 +/- 0.3 7.1 +/- 0.6 7.4 +/- 0.8 7.4 +/- 0.6 7.1 +/- 0.7 4E1 6.0 +/- 0.8 5.7 +/- 0.6 5.7 +/- 0.3 5.9 +/- 0.6 6.5 +/- 0.5 5S1 8.2 +/- 1.0 7.8 +/- 0.9 8.2 +/- 0.8 8.9 +/- 0.8 8.0 +/- 0.2 5H1 8.8 +/- 1.0 8.6 +/- 0.5 8.4 +/- 0.9 8.5 +/- 0.3 9.5 +/- 0.6 6C1 7.4 +/- 1.0 7.0 +/- 0.5 7.0 +/- 0.4 7.8 +/- 0.4 7.9 +/- 0.7 7S1 7.6 +/- 0.3 7.5 +/- 0.7 7.6 +/- 1.2 7.8 +/- 0.6 7.6 +/- 0.5 7E1 7.7 +/- 0.2 7.7 +/- 0.4 7.8 +/- 0.5 7.6 +/- 0.8 7.7 +/- 1.0 9C1 7.5 +/- 0.5 7.4 +/- 1.1 7.1 +/- 0.8 7.6 +/- 0.6 7.7 +/- 0.7 10S3 7.5 +/- 0.3 7.5 +/- 0.8 7.5 +/- 5.0 7.7 +/- 0.6 7.4 +/- 1.0 10E1 7.6 +/- 0.6 7.4 +/- 1.0 7.3 +/- 0.3 7.9 +/- 0.8 7.8 +/- 0.5 10F3 7.7 +/- 0.8 7.3 +/- 0.6 7.3 +/- 0.6 8.0 +/- 1.0 8.0 +/- 0.3 1isi 8.5 +/- 0.6 8.4 +/- 0.4 8.2 +/- 0.4 8.9 +/- 0.6 8.4 +/- 0.3 13S2 11 +/- 1.2 12 +/- 0.4 11 +/- 0.4 11 +/- 0.6 11 +/- 0.8 13C1 5.6 +/- 0.9 5.6 +/- 0.3 5.4 +/- 0.2 5.2 +/- 0.3 6.2 +/- 0.8 13E1 7.5 +/- 0.7 7.4 +/- 0.5 7.1 +/- 0.6 7.5 +/- 0.5 8.0 +/- 0.8 14S1 6.9 +/- 0.7 7.2 +/- 0.3 6.4 +/- 0.3 7.1 +/- 0.7 6.7 +/- 0.4 15D1 7.7 +/- 1.1 6.9 +/- 0.4 7.7. +/- 0.3 7.8 +/- 0.4 8.2 +/- 0.8 16F1 7.9 +/- 0.9 7.9 +/- 0.6 7.2 +/- 0.5 8.1 +/- 0.7 8.2 +/- 0.2 17B1 7.3 +/- 1.3 6.7 +/- 0.5 6.9 +/- 0.4 8.2 +/- 2.8 7.4 +/- 0.7 18S2 7.9 +/- 0.3 8.0 +/- 0.3 7.8 +/- 1.1 8.1 +/- 0.9 7.8 +/- 0.6 19D1 7.1 +/- 0.4 7.2 +/- 0.5 6.8 +/- 0.5 7.3 +/- 0.3 7.2 +/- 0.6 20D1 6.8 +/- 0.3 6.9 +/- 0.4 6.6 +/- 0.3 6.8 +/- 0.2 6.7 +/- 0.8 20F1 7.2 +/- 0.6 6.9 +/- 0.8 7.0 +/- 0.3 7.4 +/- 0.7 7.5 +/- 0.4 21S2 6.6 +/- 0.8 6.3 +/- 0.2 7.1 +/- 0.4 6.6 +/- 0.5 6.3 +/- 0.5 23S2 6.8 +/- 0.5 6.7 +/- 0.7 6.8 +/- 0.4 7.2 +/- 1.7 6.6 +/- 0.5 24D1 6.5 +/- 0.5 6.3 +/- 0.4 6.2 +/- 0.4 6.7 +/- 0.8 6.7 +/- 0.7 25S2 6.5 +/- 0.0 6.5 +/- 0.2 6.5 +/- 0.3 6.5 +/- 0.6 6.5 +/- 0.5 25D1 6.3 +/- 0.3 6.1 +/- 0.9 6.3 +/- 0.2 6.4 +/- 0.6 6.5 +/- 0.5 26S3 6.5 +/- 0.6 6.2 +/- 0.6 6.4 +/- 0.2 6.9 +/- 0.8 6.5 +/- 0.3 28D2 7.0 +/- 0.5 7.1 +/- 0.5 6.7,, +/- 0.3 6.9 +/- 0.5 7.3 +/- 0.7 29S1 6.5 +/- 0.3 6.5 +/- 1.1 6.3 +/- 0.4 6.6 +/- 0.3 6.5 +/- 0.3 29E1 7.2 +/- 0.5 7.3 +/- 0.6 6.8 +/- 0.6 7.3 +/- 0.3 7.3 +/- 0.5 31S1 7.4 +/- 0.4 7.4 +/- 0.8 7.3 +/- 0.6 7.7 +/- 0.9 7.2 +/- 0.9 31D1 8.5 +/- 0.4 8.6 +/- 0.4 8.2 +/- 0.3 8.5 +/- 0.5 8.7 +/- 1.3 31D2 7.6 +/- 0.5 7.6 +/- 0.7 7.3 +/- 0.9 7.7 +/- 0.2 7.9 +/- 0.6 34S2 7.4 +/- 0.8 7.3 +/- 0.6 7.0 +/- 0.3 7.5 +/- 0.3 7.9 +/- 1.1 34E1 7.3 +/- 0.7 6.9 +/- 0.4 7.0 +/- 0.5 7.5 +/- 0.3 7.6 +/- 0.4 C- 18

TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDRY, MIDDLE AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION SITE BOUNDARY MIDDLE CONTROL PERIOD +/-2 S.D.

JAN-MAR 7.5 +/- 2.7 7.0 +/- 1.4 8.6 +/- 0.5 APR-JUN 7.4 +/- 2.1 6.9 +/- 1.3 8.4 +/- 0.9 JUL-SEP 7.7 +/- 2.3 7.3 +/- 1.6 8.5 +/- 0.3 OCT-DEC 7.4 +/- 2.3 7.5 +/- 1.3 9.5 +/- 0.6 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH LOCATION SAMPLES PERIOD PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +/-2 S.D.

-I SITE BOUNDARY 64 6.2 12 7.5 +/- 2.3 MIDDLE DISTANCE 92 5.2 8.7 7.2 +/- 1.4 CONTROL 4 8.4 9.5 8.8 +/- 1.0 THE PREOPERATIONAL MEAN WAS CALCULATED FROM MONTHLY TLD READINGS 01/15/82 TO 12/02/84.

SITE BOUNDARY STATIONS - 36S2, 3S1,5S1, 7S1, 10S3, 1lS1, 13S2, 14S1, 18S2, 21S2, 23S2, 25S2,26S3,29S1,31S1,34S2 MIDDLE DISTANCE STATIONS - 36D1, 2E1, 4E1,6C1,7E1,9C1 1OEl,10F3,13C1,13E1,15D1, 16F1, 17B1, 19D1, 20D1,20F1, 24D1, 25D1, 28D2, 29E1, 31D1, 31D2, 34E1 CONTROL STATIONS - 5H1 C- 19

FIGURE C-1 MEAN MONTHLY TOTAL GROSSBETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2007 11:. :: . . : :

a . . , . a

a *. a, 10 ---------------

9d -a-~- - ---- :

8 7~ : ; --------

0 7

IjI -~ -:- - - - :I '. , *~ 1 I4; 5I.:

4 3 ~, I :: : :-- f...:

2 - -I. -I.- .- - - - - - - .... - ..- ..- - ...-- - - -

_ __ _ _ _ a aS . Ia. I I, I --- CONTROL :-"--

---&---IN DICATOR 0 t _.._.

F- 1 .*_0 r 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 Note: 2005 analysis changed from Insoluble & Soluble to Total Gross Beta YE A R 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 -2007 70 60 65 60 a

_..]__

a a

.............__ *..... . .].. . . . .0...S..1.. . .! ! * - - *-'. .

a . a -

2 16C5

-~-

55 ... .. 55. ... . ... -- -- -- - --. ------- ~..~1 . :

45 .- -* * * . . . . . ... ... ....... :.......

40 " -------- -------- 29C ........

35 30

.*. . ., CR TI AL T

, . . ..,. N.a..

- UNIT.N. . ..........

1. ....................

2: 1. ..45 . ..

aI Note

0,/11/89*

a Seon hal of 2000

... ...... a when no..*

was activity =,t 0IU N IT N O. 2" 08111/89 Note: Second half of 2000 " -

-switched to reporting < MDC " a 30 - '"" I ' ' ' ', ' ', ' ' ' '. . . . . . . . when no activity was detected. ;, . 'a' ' ,

a.. . a a . a Using MDC values result in a

,L 25- --------------- ----

, --- --.-------------------- larger number. LLD 150 , - -

pCi/kg...

110----------------------------------------------------------------------

5 -- ----

5 ] ------- *- -.------

0 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 YEAR CONTROL = 29C1 Station 20S1 discontinued in 1995

FIGURE C-3 CONCENTRATIONS OF CS-137 IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2007 1400 - .I--...-..-..-

I

-.- 16B2 1200 - .......... -- 16C4 ..

. -i33AA2 1000 -

S SS SS S S S S S S S S S

800 - S S S S S S S S S S S S S S E S S

- ~ ~ ~ ~ ~ . . - . . - . . - ... - . - .-- - - - - . - -

0

) 600 -

400-200 k

0-

.9nn

VV

- I 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 LGS CRITICALITY Year UNIT NO. 1: 12/22/84 UNIT NO. 2: 08/111/89 CONTROL = 33A2

FIGURE C-4 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2007 150 135 ".-'--Group II 120 ,, -.-- Group III

,' .. iil Chernobyl , ....

105 ........ .......

E.90

,7 5: . ....... ..... ... ....... ................ . . . . . . . . . . . . . . . . . . . . . . . . . . .

" 60 ... " LGSUNITCRITICALITY NO. 1: 12122184 . . . ... . .

SUNIT NO. 2: 0811/89 45-isi 0

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 YEAR

FIGURE C-5 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 2007 50 -

-u-GROUP I

--*-GROUP 1 40 - -.- GROUP III E 30 -

C.)

20 wl 10 0 ........................i .. . .. .. . .. . . m

, i , m, m, m, m, m, i , m, w, m

, m, i , i - i - i - i - i i l 1 1 1 1 1 1 1 1 4 8 12 16 20 24 28 32 36 40 44 48 52 WEEK NO.

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

IN THE VICINITY OF LGS, 1985 - 2007 13 _ _ _ _ _ _ _ _ _ _ _

-:: w--=SITE 12 ..... ..... .. ...... INTE RM E DIAT E CONTROL 11 .................... ............. .... -- o-- C o n tro lI5 H l

.9 19:11 .

9 8 . 9; ....-.... ' . .... :

Q :,

.t.

60 11f 4 - I I & I I S I S I I I & I I I I II I 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 YEAR NOTE: Control Station 5H1 became the only distant location beginning in 1995

Intentionally Left Blank APPENDIX D DATA TABLES AND FIGURES COMPARISON LABORATORY

The following section contains data and figures illustrating the analyses performed by the quality control laboratory, Environmental Incorporated (ENV). Duplicate samples were obtained from several locations and media and split between the primary laboratory, Teledyne Brown Engineering (TBE) and ENV. Comparison of the results for most media were within expected ranges.

D-1

Intentionally Left Blank D-2

TABLE D-I.1 CONCENTRATIONS OF TOTAL GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 16C2 PERIOD 01/02/07 - 01/30/07 1.7 +/- 0.9 01/30/07 - 02/27/07 1.6 +/- 0.6 02/27/07 - 04/02/07 1.7 +/- 0.6 04/02/07 - 04/30/07 1.6 +/- 0.9 04/30/07 - 05/29/07 2.4 +/- 1.1 05/29/07 - 07/02/07 2.8 +/- 1.1 07/02/07 - 07/30/07 3.1 +/- 1.0 07/30/07 - 08/28/07 4.3 +/- 1.2 08/28/07 - 10/01/07 2.9 +/- 0.7 10/01/07 - 10/30/07 4.4 +/- 1.2 10/30/07 - 12/04/07 2.4 +/- 0.7 12/04/07 - 12/31/07 2.8 +/- 1.1 MEAN 0.9 +/- 0.5 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 16C2 PERIOD 01/02/07 04/02/07 < 155 04/02/07 07/02/07 < 152 07/02/07 10/01/07 < 189 10/01/07 12/31/07 <176 MEAN D-3

TABLE D-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED INTHE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER 12 SIGMA STC 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 01/02/07 01/30107 <2 <2 <5 <3 <6 <5 <2 <3 <3 <3 <13 <3 01/30/07 02/27/07 <4 <2 <8 <2 <3 <5 <3 <5 <4 <3 *15 <3 02/27/07 04/02/07 <2 <2 <5 <2 <5 <3 <3 <3 <2 <3 < 13 <3 04/02/07 04/30/07 <2 <3 <8 <4 <8 <4 <3 <6 <3 <3 <17 <2 04/30/07 05/29/07 <4 <3 <9 <4 <5 <9 <5 <7 <4 <3 < 20 <4 05/29/Oi 07/02/07 <5 <4 <7 <3 <7 <4 <5 <5 <4 <5 < 23 <7 07/02/07 07/30/07 <2 <3 <6 <3 <4 <4 <2 <9 <2 <2 < 17 <3 07/30/07 08/28/07 <3 <3 <9 <4 <8 <6 <4 <4 <4 <4 *13 <6 08/28/07 10/01/07 <5 <5 <12 <5 <4 <7 <4 <12 <5 <5

19 <6 10/01/07 10/30/07 <4 <3 <6 <4 <6 <5 <3 <8 <4 <3

20 <6 10/30/07 12/04/07 <2 <1 <5 <1 <6 <5 <2 <6 <3 <2 <10 <1 12/04/07 12/31/07 <2 <2 <2 <3 <4 <3 <3 <3 <3 <2

10 <1 MEAN

TABLE D-II.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION 11 S2 PERIOD 01/U21UT - Ul/UdlU( 12 + b 01/08/07 - 01/15/07 19 +/- 4 01/15/07 - 01/22/07 17 +/- 4 01/22/07 - 01/29/07 21 +/- 5 01/29/07 - 02/05/07 21 +/- 5 02/05/07 - 02/12/07 27 +/- 5 02/12/07 - 02/20/07 26 +/- 4 02/20/07 - 02/26/07 22 +/- 5 02/26/07 - 03/05/07 16 +/- 4 03/05/07 - 03/12/07 31 +/- 4 03/12/07 - 03/19/07 24 +/- 5 03/19/07 - 03/27/07 18 +/- 4 03/27/07 - 04/02/07 21 +/- 5 04/02/07 - 04/09/07 8 +/- 4 04/09/07 - 04/16/07 12 +/- 4 04/16/07 - 04/23/07 11 +/- 4 04/23/07 - 04/30/07 14 +/- 4 04/30/07 - 05/07/07 15 +/- 4 05/07/07 - 05/15/07 15 +/- 4 05/15/07 - 05/21/07 24 +/- 5 05/21/07 - 05/29/07 23 +/- 4 05/29/07 - 06/04/07 26 +/- 5 06/04/07 - 06/11/07 17 +/- 4 06/11/07 - 06/18/07 21 +/- 4 06/18/07 - 06/25/07 25 +/- 5 06/25/07 - 07/02/07 27 +/- 5 07/02/07 - 07/09/07 20 +/- 4 07/09/07 - 07/16/07 31 +/- 5 07/16/07 - 07/23/07 26 +/- 5 07/23/07 - 07/31/07 22 +/- 4 07/31/07 - 08/06/07 31 +/- 5 08/06/07 - 08/14/07 30 +/- 4 08/14/07 - 08/20/07 29 +/- 5 08/20/07 - 08/27/07 16 +/- 4 08/27/07 - 09/04/07 32 +/- 4 09/04/07 - 09/11/07 38 +/- 5 09/11/07 - 09/17/07 19 +/- 4 09/17/07 - 09/24/07 29 +/- 4 09/24/07 - 10/01/07 31 +/- 5 10/01/07 - 10/08/07 13 +/- 4 10/08/07 - 10/15/07 23 +/- 4 10/15/07 - 10/22/07 30 +/- 5 10/22/07 - 10/29/07 18 +/- 4 10/29/07 - 11/05/07 27 +/- 4 11/05/07 - 11/12/07 25 +/- 5 11/12/07 - 11/19/07 21 +/- 5 11119/07 - 11/26/07 23 +/- 5 11/26/07 - 12/03/07 27 +/- 5 12/03/07 - 12/10/07 17 +/- 5 12/10/07 - 12/17/07 23 +/- 4 12/17/07 - 12/24/07 29 +/- 5 12/24/07 - 12/31/07 33 +/- 5 D-5

TABLE D-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 PERIOD 11S2 01/02/07 - 04/02/07 81 +/- 12 < 0.4 < 0.6 < 0.7 < 0.7 < 0.5 04/02/07 - 07/02/07 82 +/- 17 < 0.9 < 0.9 < 1.1 < 0.6 < 0.7 07/02/07 - 10/01/07 96 +/- 19 < 0.5 < 0.5 < 0.7 < 0.6 < 0.9 10/01/07 - 12/31/07 65 +/- 16 < 0.7 < 0.8 < 0.4 < 0.3 < 0.5 MEAN 81 +/- 25 - - - -

D-6

TABLE D-1Il.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION AND GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION 1-131 K Cs-134 Cs-137 Ba-140 La-140 PERIOD 19B1 01/16/07 < 0.2 1401 +/- 116 <3 < 3.4 < 11 <2 04/03/07 < 0.2 1446 +/- 128 < 3.2 < 4.9 < 15 <3 07/10/07 < 0.4 1339 +/- 125 < 4.2 < 4.5 < 17 <2 10/02/07 < 0.4 1407 +/- 121 < 2.4 < 2.7 < 24 <3 MEAN - 1398 +/- 89 10F4 01/16/07 < 0.4 1487 +/- 119 < 3.7 <3 < 10 <2 04103/07 < 0.2 1399 +/- 116 <4.1 <5 < 14 <3 07/10/07 <*0.3 1202 +/- 111 <5 < 3.8 < 17 <3 10/02/07 < 0.2 1342 +/- 118 < 3.8 < 3.2 < 20 <5 MEAN - 1358 +/- 239 25C1 01/16/07 < 0.4 1294 +/- 116 < 4.1 < 2.7 < 11 <3 04/03/07 < 0.2 1424 +/- 119 < 5.2 < 3.1 < 16 <2 07/10/07 < 0.3 1367 +/- 118 < 3.5 < 3.4 < 10 <4 10/02/07 < 0.3 1327 +/- 119 < 2.4 < 2.7 < 24 <3 MEAN 1353 +/- 112 D-7

FIGURE D-1 COMPARISON OF MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES SPLIT BETWEEN ENV AND TBE, 2007 10

7. . . . . . ..

9 ........

ENV.....

.. .. . . . . . . . . . . . . . . . . . . . . . 1..........

I.. . . . . . .

86- . ......- - B I'l ...............

A 1%

5 ............... .................... .... ............ . . . . .. . . . . . . . . . .. o . . . . . o .. . . . .

e \%

4 . . . . . . . .. .0A./

00 U

'

5~...............

~~ .. . . . . . . . . . . . . . . . . . . . . . . "........ ....... ,".............* .....: . '"....

... . ..-. ...................... ......... .. ... ... ...... . ....... o...............

1 . ...................... 2 . : . . -.. .. . . .................. . . . . . ...... , .......... ........ . . . . . . .

0 0 I I I I I I Il I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec MONTH ENVIRONMENTAL INC. SOLUBLE AND INSOLUBLE FRACTIONS WERE COMBINED FOR TOTAL GROSS BETA COMPARISON.

FIGURE D-2 COMPARISON OF WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM LGS COLLOCATED LOCATIONS 11S1 AND 11S2, 2007 50

--- "11S2-ENV

-- 1IS1 -TBE 40 I.

E30 .. .. ... ....... "........................

C 2 0 . . . .. .. .

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

Intentionally Left Blank D- Jo

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 1 OF 3)

Identification Reported Known Ratio (c)

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

March 2007 E5255-396 Milk Sr-89 pCi/L 125 137 0.91 A Sr-90 pCi/L 10.8 10 1.08 A March 2007 E5256-396 Milk 1-131 pCi/L 107 85.2 1.26 W Ce-141 pCi/L 269 297 0.91 A Cr-51 pCi/L 244 245 1.00 A Cs-134 pCi/L 98.1 112 0.88 A Cs-137 pCi/L 227 234 0.97 A Co-58 pCi/L 92.5 98.8 0.94 A Mn-54 pCi/L 182.0 182 1.00 A Fe-59 pCi/L 108.0 106 1.02 A Zn-65 pCi/L 985 1000 0.99 A Co-60 pCi/L 143 152 0.94 A March 2007 E5258-396 AP Ce-141 pCi 252 245 1.03 A Cr-51 pCi 204 202 1.01 A Cs-134 pCi 74.9 92.3 0.81 A Cs-137 pCi 190.0 197.0 0.96 A Co-58 pCi 79.7 81.6 0.98 A Mn-54 pCi 156 151 1.03 A Fe-59 pCi 99.1 87.2 1.14 A Zn-65 pCi 894 826 1.08 A Co-60 pCi 122 126 0.97 A March 2007 E5257-396 Charcoal 1-131 pCi 34.7 71.3 0.49 N (1)

June 2007 E5384-396 Milk Sr-89 pCi/L 98.3 95.2 1.03 A Sr-90 pCi/L 16.1 12.9 1.25 W June 2007 E5385-396 Milk 1-131 pCi/L 71.0 70.1 1.01 A Ce-141 pCi/L 176 200 0.88 A Cr-51 pCi/L 459 512 0.90 A Cs-134 pCi/L 197 242 0.81 A Cs-137 pCi/L 158 169 0.93 A Co-58 pCi/L 180 198 0.91 A Mn-54 pCi/L 163 166 0.98 A Fe-59 pCi/L 158 167 0.95 A Zn-65 pCi/L 318 334 0.95 A Co-60 pCi/L 212 238 0.89 A E-1

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 2 OF 3)

Identification Reported Known Ratio (c)

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

U June 2007 E5387-396 AP Ce-141 pCi 87.5 105 0.83 A Cr-51 pCi 232 268 0.87 A Cs-134 pCi 101 127 0.80 A Cs-137 pCi 78.9 88.5 0.89 A Co-58 pCi 91.8 104.0 0.88 A Mn-54 pCi 85.6 87 0.99 A Fe-59 pCi 89.8 87.3 1.03 A Zn-65 pCi 178 175 1.02 A Co-60 pCi 111 125 0.89 A June 2007 E5386-396 Charcoal 1-131 pCi 79.3 79.1 1.00 A September 2007 E5492-396 Milk Sr-89 pCi/L 99.0 94.9 1.04 Sr-90 pCi/L 13.9 13.1 1.06 September 2007 E5493-396 Milk 1-131 pCi/L 81.9 85.2 0.96 Ce-141 pCi/L 200 211 0.95 Cr-51 pCi/L 271 289 0.94 Cs-134 pCi/L 131 147 0.89 Cs-1 37 pCi/L 131 131 1.00 Co-58 pCi/L 114 114 1.00 Mn-54 pCi/L 171 168 1.02 Fe-59 pCi/L 117 ill 1.05 Zn-65 pCi/L 212 202 1.05 Co-60 pCi/L 143 148 0.97 September 2007 E5495-396 AP Ce-141 pCi 128 136 0.94 Cr-51 pCi 181 186 0.97 Cs-134 pCi 85.9 94.7 0.91 Cs-137 pCi 83.2 83.9 0.99 Co-58 pCi 69.4 73.3 0.95 Mn-54 pCi 112 108 1.04 Fe-59 pCi 79.6 71.1 1.12 Zn-65 pCi 159 130 1.22 Co-60 pCi 92.0 95.2 0.97 September 2007 E5494-396 Charcoal 1-131 pCi 70.8 69.5 1.02 December 2007 E5749-396 Milk Sr-89 pCi/L 87.6 93.7 0.93 Sr-90 pCi/L 15.5 15.2 1.02 E-2

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 3 OF 3)

Identification Reported Known Ratio (c)

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

December2007 E5750-396 Milk 1-131 DCi/L 60.6 60.8 1.00 A Ce-141 pCi/L 137 141 0.97 A Cr-51 pCi/L 497 512 0.97 A Cs-134 pCi/L 117 137 0.85 A Cs-1 37 pCi/L 166 166 1.00 A Co-58 pCi/L 159 174 0.91 A Mn-54 pCi/L 190 190 1.00 A Fe-59 pCi/L 149 148 1.01 A Zn-65 pCi/L 231 234 0.99 A Co-60 pCi/L 198 211 0.94 A December 2007 E5752-396 AP Ce-141 pCi 88.6 93.4 0.95 A Cr-51 pCi 352 340 1.04 A Cs-134 pCi 84.6 91.2 0.93 A Cs-1 37 pCi 111 110.0 1.01 A Co-58 pCi 114 116.0 0.98 A Mn-54 pCi 135 126 1.07 A Fe-59 pCi 119 98.5 1.21 W Zn-65 pCi 172 155 1.11 A Co-60 pCi 137 141 0.97 A December 2007 E5751-396 Charcoal 1-131 pCi 65.8 74.1 0.89 A (1) New techniciancounted charcoalcartridgeon the back ratherthan the face, resulting in low activity. If the charcoal cartridge had been counted on the face, the ratio would have been approximately 1.07, which is acceptable. NCR 07-02 (a) Teledyne Brown Engineeringreportedresult.

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

(c) Ratio of Teledyne Brown Engineeringto Analytics results.

(d) Analytics evaluation based on TBE internalQC limits: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20.

W-Acceptable with warning. Reportedresult falls within 0.70-0.80 or 1.20-1.30. N =Not Acceptable. Reported result falls outside the ratio limits of < 0. 70 and > 1.30.

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TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 1 OF 1)

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

July 2007 Rad 70 Water Sr-89 pCi/L 58.6 58.2 49.5 - 66.9 A Sr-90 pCi/L 18.7 19.0 10.3 -27.7 A Ba-133 pCi/L 18.6 19.4 10.7-28.1 A Cs-134 pCi/L 57.6 68.9 60.2 - 77.6 N (1)

Cs-1 37 pCi/L 55.4 61.3 52.6 - 70.0 A Co-60 pCi/L 31.3 33.5 24.8 - 42.2 A Zn-65 pCi/L 49.0 54.6 45.2 - 64.0 A Gr-A pCi/L 26.8 27.1 15.4-38.8 A Gr-B pCi/L 12 11.5 2.84 - 20.2 A 1-131 pCi/L 31.1 26.5 21.3- 31.7 A H-3 pCi/L 1700 1770 1180 -2360 A October 2007 RAD 71 Water Sr-89 pCi/L 27.07 27.4 19.3 - 33.9 A Sr-90 pCi/L 17.40 18.2 12.9-21.6 A Ba-1 33 pCi/L 12.57 12.6 8.64- 15.5 A Cs-1 34 pCi/L 63.33 71.1 58.0 - 78.2 A Cs-1 37 pCi/L 168 180 162-200 A Co-60 pCi/L 21.93 23.2 19.9-28.3 A Zn-65 pCi/L 245.33 251 226 - 294 A Gr-A pCi/L 55.60 58.6 30.6 - 72.9 A Gr-B pCi/L 15.23 9.73 4.26 - 18.2 A 1-131 pCi/L 27.43 28.9 24.0 - 33.8 A H-3 pCi/L 9263.3 9700 8430- 10700 A (1) The Cs-134 TBE found/ERA known ratio is 83.6%, which TBE considers acceptable. NCR 07-07 (a) Teledyne Brown Engineeringreportedresult.

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

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

E-4

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

TELEDYNE BROWN ENGINEERING, 2007 (PAGE 1 OF 1)

I Identification Reported Known Acceptance.

Month/Year Number Media Nuclide Units Value (a) Value (b) Range Evaluation (c)

February 2007 07-MaW17 Water Cs-1 34 Bq/L 74.5 83.5 58.5- 108.6 A Cs-137 Bq/L 162 163.0 114-1 -211.9 A Co-57 Bq/L 140 143.7 100.6 - 186.8 A Co-60 Bq/L 27.9 26.9 18.8 - 35.0 A H-3 Bq/L 346 283.0 198.1 - 367.9 W Mn-54 Bq/L 125 123.8 86.7- 160.9 A Sr-90 Bq/L 8.90 8.87 6.21- 11.53 A Zn-65 Bq/L, 117 114.8 80.4 - 149.2 A 07-GrW17 Water Gr-A Bq/L 0.502 0.327 >0.0 - 0.654 A Gr-B Bq/L 0.975 0.851 0.426 - 1.277 A 07-MaS17 Soil Cs-1 34 Bq/kg 322 327.4 229.2 - 425.6 A Cs-1 37 Bq/kg 893 799.7 559.8 - 1039.6 A Co-57 Bq/kg 508.3 471.2 329.8 - 612.6 A Co-60 Bq/kg 300.3 274.7 192.3 - 357.1 A Mn-54 Bq/kg 779 685.2 479.6 - 890.8 A K-40 Bq/kg 682 602 421 - 783 A Sr-90 Bq/kg 293 319.0 223.3 - 414.7 A Zn-65 Bq/kg 618.7 536.8 375.8 - 697.8 A 07-RdF17 AP Cs-134 Bq/sample 3.230 1.4960 2.9372 - 5.4548 W Cs-137 Bq/sample 2.453 2.5693 1.7985 - 3.3401 A Co-57 Bq/sample 3.067 2.8876 2.0213 - 3.7539 A Co-60 Bq/sample 2.767 2.9054 2.0338 - 3.7770 A Mn-54 Bq/sample 3.557 3.5185 2.4630 - 4.5741 A Sr-90 Bq/sample 0.584 0.6074 0.4252 - 0.7896 A Zn-65 Bq/sample 2.463 2.6828 1.8780 - 3.4876 A 07-GrF17 AP Gr-A Bq/sample 0.353 0.601 >0.0 - 1.202 A Gr-B Bq/sample 0.500 0.441 0.221 - 0.662 A February 2007 07-RdV17 Vegetation Cs-134 Bq/sample 6.207 6.2101 4.3471 - 8.0731 A Cs- 137 Bq/sample 7.80 6.9949 4.8964 - 9.0934 A Co-57 Bq/sample 8.64 8.1878 5.7315 - 10.6441 A Co-60 Bq/sample 6.10 5.8215 4.0751 - 7.5680 A Mn-54 Bq/sample 9.41 8.4492 5.9144 - 10.9840 A K-40 Bq/sample 63.5 Not evaluated by MAPEP Sr-90 Bq/sample 1.51 1.5351 1.0746 - 1.9956 A Zn-65 Bq/sample 7.15 5.6991 3.9894 - 7.4088 W (a) Teledyne Brown Engineeringreportedresult.

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

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

E-5

TABLE E-4 ERA(a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2007 (Page 1 of 2)

Concentration (pCi/L)

Lab Codeb Date Analysis Laboratory ERA Control Resultc Resultd Limits Acceptance STAP-1116 03/19/07 Gr. Alpha 34.64 +/- 2.56 25.8 12.4 -39 Pass STAP-1116 03/19/07 Gr. Beta 93.41 +/- 3.20 79.5 48.8-116 Pass STAP-1117 03/19/07 Co-60 1610.00 +/- 8.40 1300.0 1010.0 - 1620 Pass STAP-1117 03/19/07 Cs-1 34 1340.40 +/- 48.84 1120.0 732.0 - 1380 Pass e

STAP-1117 03/19/07 Cs-1 37 345.30 +/- 8.20 255.0 192.0 -336 Fail STAP-1117 f 03/19/07 Mn-54 < 5.0 0.0 Pass STAP-1117 03/19/07 Sr-90 156.10 +/- 6.60 156.0, 66.6 - 246 Pass STAP-1117 03/19/07 Zn-65 363.80 +/- 11.90 245.0 208.0 -412 Pass STSO-1 118 03/19/07 Ac-228 3097.77 +/- 94.96 2790.0 1790.0 - 3930 Pass STSO-1 118 03/19/07 Bi-212 2467.87 +/- 114.33 2500.0 658.0 - 3730 Pass STSO-1 118 03/19/07 Co-60 7847.40 +/- 86.60 7330.0 5340.0 - 9820 Pass STSO-1 118 03/19/07 Cs-1 34 7910.60 +/- 356.88 7560.0 4850.0 - 9070 Pass STSO-1 118 03/19/07 Cs-1 37 4635.00 +/- 99.10 4300.0 3290.0 - 5580 Pass STSO-1 118 03/19/07 K-40 12201.60 +/- 423.20 11100.0 8050.0 - 15000 Pass STSO-1118 03/19/07 Mn-54 < 34.0 0.0 Pass STSO-1 118 03/19/07 Pb-212 2046.80 +/- 127.20 1730.0 1120.0 - 2430 Pass STSO-1 118 03/19/07 Pb-214 4142.80 +/- 110.40 3330.0 1980.0 - 4980 Pass STSO-1 118 03/19/07 Sr-90 6163.30 +/- 791.60 7500.0 2610.0 - 12400 Pass STSO-1 118 03/19/07 Th-234 4329.40 +/- 569.10 3590.0 2190.0 - 4560 Pass STSO-1 118 f 03/19/07 Zn-65 0.00 +/- 0.00 0.0 0.0 - 0 Pass STVE-1119 03/19/07 Co-60 2827.90 +/- 62.40 2600.0 1760.0 -3720 Pass STVE-1 119 03/19/07 Cs-1 34 654.80 +/- 48.40 579.0 308.0 -822 Pass STVE-1119 03/19/07 Cs-1 37 3307.30 +/- 58.80 2920.0 2150.0 -4060 Pass STVE-1119 03/19/07 K-40 40814.20 +/- 618.80 37900.0 27200.0 -53600 Pass STVE-1119 f 03/19/07 Mn-54 < 27.6 0.0 Pass STVE-1 119 03/19/07 Sr-90 8999.70 +/- 580.90 8890.0 4900.0 - 11800 Pass STVE-1 119 03/19/07 Zn-65 474.30 +/- 45.70 366.0 267.0 -500 Pass STW-1 120 03/19/07 Co-60 541.40 +/- 9.00 536.0 467.0 -631 Pass STW-1 120 03/19/07 Cs-1 34 1623.80 +/- 66.10 1750.0 1290.0 -2020 Pass STW-1 120 03/19/07 Cs-1 37 1839.10 +/- 17.90 1850.0 1570.0 -2220 Pass STW-1120 f 03/19/07 Mn-54 <8.1 0.0 Pass STW-1 120 03/19/07 Sr-90 949.40 +/- 16.70 989.0 630.0 -1320 Pass STW-1 120 03/19/07 Zn-65 2009.00 +/- 36.40 1910.0 1600.0 -2410 Pass STW-1121 04/09/07 Sr-89 30.7 +/- 4.3 35.4 26.7 -44.1 Pass STW-1 121 04/09/07 Sr-90 39.3 +/- 1.8 42.1 33.4 - 50.8 Pass E-6

TABLE E-4 ERA(a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2007 (Page 2 of 2)

Concentration (pCi/L)

Lab Codeb Date Analysis Laboratory ERA Control Resultc Resultd Limits Acceptance STW-1 122 04/09/07 Ba- 133 30.0 +/- 2.4 29.3 20.6 - 38.0 Pass STW-1 122 04/09/07 Co-60 118.5 +/- 3.9 119.0 109.0 - 129.0 Pass STW-1 122 04/09/07 Cs-1 34 52.6 +/- 2.3 54.3 45.6 - 63.0 Pass STW-1 122 04/09/07 Cs-137 49.5 +/- 3.8 50.3 41.6-59.0 Pass STW-1 122 04/09/07 Zn-65 91.7 +/- 6.3 88.6 73.3 - 104.0 Pass STW-1 123 04/09/07 Gr. Alpha 33.8 +/- 3.5 56.5 32.0 -81.0 Pass STW-1 123 04/09/07 Gr. Beta 24.2 +/- 2.3 25.3 16.6 -34.0 Pass STW-1 124 04/09/07 1-131 19.2 +/- 1.2 18.9 13.7 -24.1 Pass STW-1 125 04/09/07 H-3 7540.0 +/- 255.0 8060.0 6660.0 - 9450.0 Pass STW-1 127 07/09/07 Sr-89 51.7 +/- 5.0 58.2 49.5 - 66.9 Pass STW-1 127 07/09/07 Sr-90 21.4 +/-2.3 19.0 10.3 - 27.7 Pass STW-1 128 07/09/07 Ba- 133 19.4 +/-2.2 19.4 10.7 -28.1 Pass STW-1 128 07/09/07 Co-60 32.8 +/- 2.0 33.5 24.8 - 42.2 Pass STW-1 128 07/09/07 Cs-134 67.0 +/- 2.9 68.9 60.2 - 77.6 Pass STW-1 128 07/09/07 Cs-137 61.6 +/- 3.8 61.3 52.6 - 70.0 Pass STW-1 128 07/09/07 Zn-65 55.6 +/-7.5 54.6 45.2 - 64.0 Pass STW-1 129 07/09/07 Gr. Alpha 19.2 +/- 1.6 27.1 15.4 - 38.8 Pass STW-1 129 07/09/07 Gr. Beta 9.1 +/-0.9 11.5 2.8 -20.2 Pass STW-1 131 10/05/07 Sr-89 27.3 +/- 3.3 27.4 19.3 - 33.9 Pass STW-1 131 10/05/07 Sr-90 17.7 +/- 1.2 18.2 12.9 -21.6 Pass STW-1 132 10/05/07 Ba-133 12.2 +/- 3.3 12.6 8.6 - 15.5 Pass STW-1132 10/05/07 Co-60 23.8 +/- 1.4 23.2 19.9 -28.3 Pass STW-1132 10/05/07 Cs-1 34 70.5 +/- 4.2 71.1 58.0 - 78.2 Pass STW-1 132 10/05/07 Cs-137 178.2 +/- 3.3 180.0 162.0 - 200.0 Pass STW-1 132 10/05/07 Zn-65 263.9 +/- 6.9 251.0 226.0 - 294.0 Pass STW-1 133 10/05/07 Gr. Alpha 54.7 +/-2.1 58.6 30.6 - 72.9 Pass STW-1 133 10/05/07 Gr. Beta 11.9 +/-0.9 9.7 4.3 - 18.2 Pass STW-1134 10/05/07 1-131 33.0 +/- 1.5 28.9 24.0 - 33.8 Pass STW-1 135 10/05/07 H-3 9965.0 +/- 250.0 9700.0 8430.0 - 10700.0 Pass 8 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

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

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

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

e A high bias (- 20%) was observed in gamma results for air filters. A composite filter geometry was used in the calculations vs. a single filter.geometry. Result of recalculation. Cs-1 37, 305.8 +/- 6.0 pCi/filter.

f Included in the testing series as a "false positive". No activity expected.

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TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2007 (Page I of 1)

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activityb Limits d Acceptance STW-1110 01/01/07 Gr. Alpha 0.45 +/- 0.08 Concentration0.33 0.00 - 0.65 Pass STW-1110 01/01/07 Gr. Beta 0.90 +/- 0.14 0.85 0.43 -1.28 Pass STW-1111 01/01/07 Co-57 151.60 +/- 10.00 143.70 100.60 - 186.80 Pass STW-1111 01/01/07 Cs-134 79.20 +/- 8.00 83.50 58.50 - 108.60 Pass STW-1111 01/01/07 Cs-1 37 168.70 +/- 12.10 163.00 114.10 -211.90 Pass STW-1111 01/01/07 H-3 262.20 +/- 9.10 283.00 198.10 - 367.90 Pass STW-1111 01/01/07 Mn-54 130.60 +/- 11.50 123.80 86.70 - 160.90 Pass STW-1111 01/01/07 Sr-90 9.60 +/- 1.40 8.87 6.21 -11.53 Pass STW-1111 01/01/07 Zn-65 123.70 +/- 17.00 114.80 80.40 - 149.20 Pass STSO-1112 01/01/07 Co-57 501.20 +/- 2.90 471.20 329.80 -,612.60 Pass STSO-1112 01/01/07 Co-60 285.90 +/- 2.10 274.70 192.30 - 357.10 Pass STSO-1 112 01/01/07 Cs-1 34 325.90 +/- 7.40 327.40 229.20 - 425.60 Pass STSO-1 112 01/01/07 Cs-1 37 855.70 +/- 4.60 799.70 559.80 - 1039.60 Pass STSO-1 112 01/01/07 Mn-54 750.90 +/- 4.70 685.20 479.60 - 890.80 Pass STAP- 113 01/01/07 Gr. Alpha 0.27 +/- 0.04 0.60 0.00-1.20 Pass STAP-1 113 01/01/07 Gr. Beta 0.57 +/- 0.05 0.44 0.22 -0.66 Pass STAP-1 114 01/01/07 Co-57 3.51 +/- 0.07 2.89 2.02 -3.75 Pass STAP-1 114 01/01/07 Co-60 2.98 +/- 0.10 2.91 2.03 -3.78 Pass STAP-1 114 01/01/07 Cs-1 34 4.02 +/- 0.16 4.20 2.94-5.45 Pass STAP-1 114 01/01/07 Cs-137 2.75 +/- 0.12 2.57 1.80-3.34 Pass STAP-1 114 01/01/07 Mn-54 3.94 +/- 0.12 3.52 2.46 -4.57 Pass STAP-1 114 01/01/07 Sr-90 0.58 +/- 0.18 0.61 0.43 -0.79 Pass STAP-1 114 01/01/07 Zn-65 2.70 +/- 0.10 2.68 1.88 -3.49 Pass STVE-1115 01/01/07 Co-57 8.90 +/- 0.20 8.19 5.73 -10.64 Pass STVE-1 115 01/01/07 Co-60 6.50 +/- 0.20 5.82 4.08 -7.57 Pass STVE-1115 01/01/07 Cs-1 34 6.90 +/- 0.30 6.21 4.35-8.07 Pass STVE-1115 01/01/07 Cs-137 8.20 +/- 0.30 6.99 4.90-9.09 Pass STVE-1 115 01/01/07 Mn-54 10.10 +/- 0.30 8.46 5.91 -10.98 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte 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.

E-8

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 2007 Prepared By Teledyne Brown Engineering Environmental Services Exel nI Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2008

Table Of Contents

1. Summary and Conclusions .................................................................... 1 11.Introduction ....................................................... ..... 2 A. Objectives of the RGPP............................................................... 2 B. Implementation of the Objectives..................................................... 2 C. Program Description................................................................... 3 D. Characteristics of Tritium (H-3)....................................................... 4 Ill. Program Description ........................................................................... 4 A. Sample Analysis ....................................................................... 4 B. Data Interpretation ..................................................................... 5 C. Background Analysis .................................................................. 6

1. Background Concentrations of Tritium ....................................... 6 IV. 'Results and Discussion........................................................................ 8 A. Groundwater Results .................................................................. 8 B. Surface Water Results................................................................. 9 C. Drinking Water W ell Survey ..........................................9 D. Summary of Results - Inter-laboratory Comparison Program.................... 10 E. Leaks, Spills, and Releases ......................................................... 10 F. Trends.................................................................................. 11 G. Investigations ......................................................................... 11 H. Actions Taken......................................................................... 11 V. References .................................................................................... 11

Appendices Appendix A Location Designation Tables Table A-1 Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2007 Figures Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2007 Appendix B Data Tables Tables Table B-1.1 Concentrations of Tritium and Stronium-90 in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2007.

Table B-1.2 Concentrations of Gamma Emitters in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2007.

Table B-11.1 Concentrations of Tritium and Stronium-90 in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2007.

Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2007.

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 2007 through 31 December 2007.

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.

This report covers groundwater and surface water samples, collected from the environment, both on and off station property in 2007. During that time period, 90 analyses were performed on 36 samples from 21 locations.

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. There are no know active releases into the groundwater at Limerick Generating Station.

Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater or surface water samples. In the case of tritium, Exelon specified that it's laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation.

Strontium-90 was not detected at a concentration greater than the LLD of 2.0 picoCuries per liter (pCi/L) in any of the groundwater or surface water samples tested.

Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 4 of 15 groundwater monitoring locations. The tritium concentrations ranged from 201 to 309 pCi/L.

Although no drinking water pathway is available from groundwater, the dose via the drinking water pathway was calculated at 0.032 mrem to a child (total body),

which was 0.553% of the 10 CFR 50, Appendix I dose limit. All results for Sr-90 and gamma emitting nuclides were less than MDC.

1

II. Introduction The Limerick Generating Station (LGS), consisting of two 3458 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.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2007.

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

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

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

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

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

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

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

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

www-exeloncorn-comlouircomnanieslnoweraen/nuclearlTritium-htm 2

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

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

4. Limerick Generating Station has 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, lnc.(NAI). This section describes the general collection methods used to obtain environmental samples for the LGS RGPP in 2007. Sample locations can be found in Table A-i, Appendix A.

1. Sample Collection Groundwater and Surface Water Samples of water were collected, managed, transported and analyzed in accordance with approved procedures following EPA methods. Both groundwater and surface water were collected.

Sample locations, sample collection frequencies and analytical frequencies were controlled in accordance with approved station procedures. Contractor and/or station personnel were trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories were subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits.

Station personnel reviewed and evaluated all analytical data deliverables as data were received.

Analytical data results were reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to hydrogeologic conditions.

3

D. Characteristics of Tritium (H-3)

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

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

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

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

Ill. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Limerick Generating Station RGPP in 2007.

In order to achieve the stated objectives, the current program includes the following analyses:

4

1. Concentrations of gamma emitters in groundwater and surface water.

2. Concentrations of strontium in groundwater and surface water.

3. Concentrations of tritium in groundwater and surface water.

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

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

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

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

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

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

5

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

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

C. Background Analysis A pre-operational radiological environmental monitoring program (pre-operational REMP) was conducted to establish background radioactivity levels prior to operation of the Station. The environmental media sampled and analyzed during the pre-operational REMP were atmospheric

'radiation, fall-out, domestic water, surface water, aquatic life, and foodstuffs. The results of the monitoring were detailed in the report entitled, Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corporation.

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

Monthly surface water sampling began in 1982, and the samples were analyzed for tritium as well as other radioactive analytes. During the preoperational program tritium was detected at a maximum concentration of 420 pCi/L, indicating that these preoperational results were from nuclear weapons testing and are 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 6

bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.

A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early 1960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.

b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP) and USEPA's RadNet database. GNIP provides tritium precipitation concentration data for samples collected 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. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time.

Tritium concentrations in have typically been below 100 pCi/L since around 1980.ý Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above. Water from previous years was naturally captured in groundwater. As a result, some well water sources today are affected by the surface water from the 1960s that contained elevated tritium activity.

7

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

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

IV. Results and Discussion Gamma spectroscopy results for groundwater and surface water sample were reported for twelve nuclides (Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, I-131, Cs-134, Cs-137, Ba-140 and La-140).

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 fifteen locations were analyzed for tritium activity (Table B-1.1, Appendix B)., Tritium values ranged from non detectable to 309 pCi/L.

Well MW-LR-5 had the highest value of 309 pCi/L. Although no drinking water pathway is available from groundwater, the dose via the drinking water pathway was calculated at 0.032 mrem to a child (total body), which was 0.553% of the 10 CFR 50, Appendix I dose limit.

Strontium No Sr-90 activity was detected in any of the ground water samples analyzed (Table B-1.1, Appendix B).

8

Gamma Emitters Potassium-40 was detected in one of 15 samples at a concentration of 155 pCi/Liter. No other gamma emitting nuclides were detected (Table B-1.2, Appendix B).

B. Surface Water Results In accordance with the Station's radiological groundwater protection program surface water samples were collected from streams that transverses the site, as well as, from other water bodies that could influence the tritium concentration at Limerick. Analytical results and anomalies are discussed below.

Tritium Samples from six locations were analyzed for tritium activity No tritium activity was detected in any surface water samples analyzed (Table B-1.3, Appendix B).

Strntum No Sr-90 activity was detected in any of surface water samples analyzed (Table B-4.3, Appendix B).

Gamma Emitters No gamma emitting nuclides were detected in any of the surface water samples analyzed (Table B-1.4, Appendix B).

C. Drinking Water Well Survey A drinking water well survey was conducted during the summer 200) 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 bgs, and they yield between 8 and 100 gallons per minute (gpm). All wells are completed in the Brunswick Formation.

The Station has one potable supply well and one fire water well. The potable supply well is constructed as an open-rock borehole. Groundwater was measured at a depth 102 feet bgs during a well pump replacement in 2004 (personal communication with Station, 2006). The pump was placed at a depth of approximately 294 feet bgs. The total well depth and the 9

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.

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

E. Leaks, Spills, and Releases Tritium was discovered in the "C" aux boiler on 11/17/2007 (IR 700944).

Activity found was 4030 pCi/L. Subsequent sampling of the Refuel Water Storage Tank (RWST) and the telltale indicator for the guard pipe from the condensate return line of the steam heat to the circulating water pump house (gooseneck) showed positive tritium, as well. The gooseneck was discharging directly to the ground, which resulted in a notification to the PA DEP per the Exelon radiological groundwater protection program procedure. Total time that tritiated water was being discharged to the ground was three days. On 11/20/2007 the discharge from the gooseneck was redirected to a drain that goes through the oil interceptors, oily waste separators, hold pond and then to radwaste discharge line to outfall 001.

The release rate was determined by operations as 2.9 gallons/minute.

Total volume released to the ground was calculated as 47,423 liters for the three days of discharge. The highest activity observed during that time period was 4850 pCi/L. Based upon this information a total of 2.3E+08 pCi were discharged to the ground. There is no drinking water pathway that could become contaminated from this release. Monitoring well P-11 is the closes well to the release. The maximum dose via the drinking water pathway was calculated at 0.502 mrem to a child (total body), which was 8.369% of the 10 CFR 50, Appendix I dose limit.

10

F. Trends No trends have been identified.

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

H. 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 2007

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

V. References

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

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

11

Intentionally Left Blank 12

APPENDIX A LOCATION DESIGNATION

TABLE A-1: Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2007 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 Surface Water Onsite SW-LR-9 Surface Water Onsite A-I

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/

i 1 Mile Radius

$ ;Y,,.

3O N

NNE /

"\

"I WNW' ENE LR-GO&',.

w Ww Mq WSW",

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0 500 1,000 1,500 2, 000 SSW - SSE Feet S

Fiur Wae an apeLoain RutneWllWae Surac o heRdooia m I Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2007 A-2

APPENDIX B DATA TABLES

TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM-90 IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 MW-LR-1 05/02/07 < 162 MW-LR-1 10/30/07 < 178 < 1.8 MW-LR-2 05/01/07 < 164 MW-LR-2 10/31/07 < 189

0.8 MW-LR-3 05/02/07 < 166 MW-LR-3 10/31107 < 196 < 1.4 MW-LR-4 05/01/07 < 163 MW-LR-4 10/30/07 < 179 < 1.3 MW-LR-5 05/02/07 309 +/- 117 MW-LR-5 11/01/07 281 +/- 125 < 0.8 MW-LR-5F 11/01/07 201 +/- 126 < 0.7 MW-LR-5 SPLIT 11/01/07 222 +/- 101 < 0.6 MW-LR-6 05/02/07 < 166 MW-LR-6 10/31/07 < 194 < 1.8 MW-LR-7 05/02/07 < 163 MW-LR-7 10/30/07 < 191 < 1.3 MW-LR-8 05/03/07 281 +/- 114 MW-LR-8 10/30/07 < 188 < 1.0 MW-LR-8M 10/30/07 215 + 128 < 1.2 MW-LR-8 SPLIT 10/30/07 < 175 < 0.5 MW-LR-9 05/03/07 308 + 117 MW-LR-9 DUP 05/03/07 209 +/- 112 MW-LR-9 10/30/07 269 + 131 < 1.3 MW-LR-9M 10/30/07 250 + 127 < 1.5 MW-LR-9 SPLIT 10/30/07 < 175 < 0.4 P-11 05/01/07 < 163 P-1I 10/30/07 < 194 < 1.6 P-14 05/03/07 < 165 P-14 10/30/07 < 196 < 1.3 P-16 05/03/07 < 167 P-16 DUP 05/03/07 < 164 P-16 10/30/07 213 +/- 122 < 1.7 P-17 05/01/07 < 164 P-17 10/30/07 < 199 < 1.4 P-3 05/01/07 < 158 P-3 10/31/07 < 194 < 1.6 SP-22 05/01/07 < 159 SP-22 10/30/07 < 194 .0.8 SAMPLES ARE DISTILLED FOR H-3 ANALYSIS B-1

TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC 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 PERIOD MW-LR-1 10/30/07 < 44 < 92 <4 <4 <11 <4 <11 <5 <9 <17 <5 <5 <35 <10 MW-LR-2 10/31/07 < 44 < 45 <4 <5 <10 <5 <11 <6 <9 <14 <5 <4 < 36

12 MW-LR-3 10/31/07 < 43 < 98 <5 <6 <10 <4 <9 <6 <8 <13 <4 <5 < 29

14 MW-LR-4 10/30/07 < 36 < 78 <4 <4 <8 <4 <7 <4 <7 <12 <3 <4 <24

10 MW-LR-5 11/01/07 < 31 < 73 <3 <3 <8 <3 <7 <3 <7 <9 <3 <4 < 24 <8 MW-LR-5F 11/01/07 < 41 < 36 <5 <5 <11 <5 <11 <6 <10 <14 <5 <5

30 <12 MW-LR-5 SPLIT 11/01/07 < 27 < 65 <2 <2 <4 <3 <7 <3 <6 <7 <3 <3 < 11 <5 M R MW-LR-6 10/31/07 < 42 < 101 <5 <6 <12 <5 <11 <5 <10 <13 <5 <5 < 35 < 13 t-j MW-LR-7 10/30/07 < 44 < 92 <5 <4 <11 <5 <9 <6 <8 <14 <4 <5 < 33 <9 MW-LR-8 10/30/07 < 44 -e 95 <5 <5 <12 <5 <9 <6 <10 <15 <4 <5 < 39 < 12 MW-LR-8M 10/30/07 < 36 <4 <4 <9 <4

< 78 <7 <4 <7 <12 <3 <4

29 <8 MW-LR-8 SPLIT 10/30/07 < 28- < 69 <3 <2 <3 <2 <5 <2 <4 <6 <2 <2 < il <3 MW-LR-9 10/30/07 < 46 < 92 <5 <5 <10 <5 <13 <6 <10 <18 <5 <5 < 41 < 14 MW-LR-9M 10/30/07 < 31 < 36 <3 <4 <8 <4 <7 <4 <7 <11 <3 <4 <25 <9 MW-LR-9 SPLIT 10/30/07 < 28 < 76 <2 <3 <8 <1 <5 <4 <5 <8 <2 <3

13 <3 P-11 10/30/07 < 51 < 47 <5 <5 <11 <7 <11 <6 <10 <17 <4 <5 < 35 < 12 P-14 10/30/07 < 37 155 + 45 <4 <4 <8 <3 <8 <4 <7 <12 <4 <4 < 26 <.8 P-16 10/30/07 < 27 < 28 <3 <3 <7 <3 <7 <3 <6 <11 <3 <3 < 24 <7 P-17 10/30/07 < 30 < 31 <3 <3 <7 <4 <6 <4 <6 <11 <3 <3 < 23 <7 P-3 10/31/07 < 35 < 70 <4 <4 <9 <3 <7 <4 <7 <12 <4 <4 < 29 < 10 SP-22 10/30/07 < 25 ' 53 <3 <3 <6 <2 <5 <3 <5 <9 <3 <3 < 21 <7

TABLE B-II.1 CONCENTRATIONS OF TRITIUM AND STRONIUM-90 IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 SW-LR-2 4/30/07 < 164 SW-LR-2 10/29/07 < 197 < 0.7 SW-LR-4 10/29/07 < 195 SW-LR-6 10/29/07 < 194 SW-LR-7 4/30/07 < 166 SW-LR-7 10/30/07 < 181 < 1.5 SW-LR-8 10/31/07 < 192 SW-LR-9 10/31/07 < 191 SAMPLES ARE DISTILLED FOR H-3 ANALYSIS B-3

TABLE B-1I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2007 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC 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 PERIOD SW-LR-2 10/29/07 < 38 < 35 <4 <4 < 9 < 4 <7 <5 < 7 < 14 <4 <4 < 31. < 10 SW-LR-7 10/30/07 < 34 < 74 <4 < 4 < 8 < 4 <7 <4 < 7 < 13 <3 <4 < 28 <9 4

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