Text

Annual Radiological Environmental Operating Report for the Year 2010
	ML11157A035
Person / Time
Site:	Limerick
Issue date:	04/30/2011
From:	; Exelon Generation Co, Exelon Nuclear
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML11157A035 (116)
	v • d • e

Docket No:

50-352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2010 Prepared By Teledyne Brown Engineering Environmental Services Exel Wns.

Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2011

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

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

3 A. O bjectives of the REM P...................................................................................

3 B. Im plem entation of the O bjectives.....................................................................

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

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

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

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

6 D. Program Exceptions........................................................................................

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

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

9 A. Aquatic Environm ent........................................................................................

9

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

9

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

9

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

10

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

10 B. Atm ospheric Environm ent...............................................................................

11

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

11

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

11

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

12

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

12

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

12

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

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

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

13 E. Independent Spent Fuel Storage Installation..................................................

13 F. Land Use Survey.............................................................................................

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

14 V. References.......................................................................................................................

15

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Appendix B Tables Table B-I:

Table B-2:

Table B-3:

Radiological Environmental Monitoring Program Annual Summary for the Limerick Generating Station, 2010.

Location Designation, Distance & Direction, and Sample Collection &

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

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2010.

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2010.

Ficgures Figure B-1:

Figure B-2:

Figure B-3:

Appendix C Tables Table C-1.1 Table C-1.2 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2010.

Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2010.

Environmental Sampling Locations Greater Than 26,400 Feet from the Limerick Generating Station, 2010.

Data Tables and Figures - Primary Laboratory Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2010.

ii

Table C-I1.1 Table C-II.2 Table C-II.3 Table C-II1.1 Table C-IV.1 Table C-V.1 Table C-V.2 Table C-V.3 Table C-VI.1 Table C-VII.1 Table C-VII.2 Table C-VIII.1 Table C-IX.1 Table C-IX.2 Table C-IX.3 Figures Figure C-1 Figure C-2 Concentrations of Gross Beta in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Monthly and Yearly Mean Values of Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of Gamma Emitters in Broad Leaf Vegetation Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Quarterly TLD Results for Limerick Generating Station, 2010.

Mean Quarterly TLD Results for the Site Boundary, Middle and Control Locations for Limerick Generating Station, 2010.

Summary of the Ambient Dosimetry Program for Limerick Generating Station, 2010.

Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 - 2010.

Mean Annual Cs-137 Concentrations in Fish Samples Collected in the Vicinity of LGS, 1982 - 2010.

iii

Figure C-3 Figure C-4 Figure C-5 Figure C-6 Appendix D Tables Table D-1.1 Table D-1.2 Table D-1.3 Table D-11.1 Table D-11.2 Table D-Ill.1 Figures Figure D-1 Figure D-2 Concentrations of Cs-137 in Sediment Samples Collected in the Vicinity of LGS, 1982 - 2010.

Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 - 2010.

Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2010.

Mean Quarterly Ambient Gamma Radiation Levels (TLD) in the Vicinity of LGS, 1985-2010.

Data Tables and Figures - Comparison Laboratory Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2010.

Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2010.

Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Concentrations of 1-131 by Chemical Separation and Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2010.

Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between ENV and TBE, 2010.

Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2, 2010.

iv

Appendix E Tables Table E-1 Table E-2 Table E-3 Table E-4 Table E-5 Appendix F Inter-Laboratory Comparison Program Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2010.

ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2010.

DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Teledyne Brown Engineering, 2010.

ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2010.

DOE's Mixed Analyte Performance Evaluation Program (MAPEP)

Environmental, Inc., 2010.

Annual Radiological Groundwater Protection Program Report (ARGPPR) v

Intentionally Left Blank vi

I.

Summary and Conclusions In 2010, the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 73 curies of noble gas, fission and activation products and approximately 51curies 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 Applicable Limit Noble Gas Gamma - Air Dose 4.04E-03 All Nearest Residence 2.OOE-02 20 mRad Noble Gas Beta - Air Dose 2.40E-03 All Nearest Residence 6.00E-03 40 mRad Noble Gas Total Body (Gamma) 3.83E-03 All Nearest Residence 3.80E-02 10 mrem Noble Gas Skin (Beta) 6.39E-03 All Nearest Residence 2.10E-02 30 mrem

Iodine, Particulate &

Bone 1.60E-01 Child Cow Milk 5.33E-01 30 mrem Trtium Liquid Total Body 1.76E-02 Child Aqua PA 2.93E-01 6

mrem Liquid Liver 1.77E-02 Child Aqua PA 8.90E-02 20 mrem The calculated 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 2010 through 31 December 2010. During that time period, 1133 analyses were performed on 926 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.

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

Sediment samples collected below the discharge had Cesium-1 37 concentrations that were consistent to those from previous years. No other station produced fission or activation products were found in sediment. The calculated dose to a teenager's skin and whole body was 4.36E-04 mrem and 3.74E-04 mrem, respectively. This dose represents 2.18E-03% and 6.23E-03%, respectively of the 10 CFR Part 50, Appendix I dose limits.

1

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

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

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

Broad leaf vegetation samples were analyzed for gamma emitting nuclides.

Concentrations of naturally occurring Be-7 and K-40 were detected. Radium-226 was found in eight of 33 samples. Thorium-228 and Th-232 were detected in low concentration just above the MDC (minimum detectable concentration). No activation or fission products were detected.

Environmental gamma radiation measurements were performed quarterly using thermoluminescent dosimeters (TLD). Levels detected were consistent with those observed in previous years.

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

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

A radiological groundwater protection program (RGPP) was established in 2006 as part of an Exelon Nuclear fleetwide assessment of potential groundwater intrusion from the operation of the Station. Well water samples were analyzed for tritium, Sr-90 and gamma emitters. Additionally, a select group of wells had hard-to-detect nuclides and gross alpha and gross beta analyses performed.

Most tritium values were less than the lower limit of detection of 200 pCi/L.

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

2

II.

Introduction The Limerick Generating Station (LGS), consisting of two 3,458 MWt boiling water reactors owned and operated by Exelon Corporation, is located adjacent to the Schuylkill River in Montgomery County, Pennsylvania. Unit No. 1 went critical on 22 December 1984. Unit No. 2 went critical on 11 August 1989. The site is located in Piedmont countryside, transversed by numerous valleys containing small tributaries that feed into the Schuylkill River. On the eastern river bank elevation rises from approximately 110 to 300 feet mean sea level (MSL). On the western river bank elevation rises to approximately 50 feet MSL to the western site boundary.

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

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

This report covers those analyses performed by Teledyne Brown Engineering (TBE), Mirion Technologies (Dosimetry Services Division), and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2010 through 31 December 2010.

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

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

A.

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

1.

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

2.

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

3

B.

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

1.

Identifying significant exposure pathways.

2.

Establishing baseline radiological data of media within those pathways.

3.

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

II1.

Program Description A.

Sample Collection Samples for the LGS REMP were collected for Exelon Nuclear by Normandeau Associates, Inc. (NAI). This section describes the general collection methods used by NAI to obtain environmental samples for the LGS REMP in 2010. 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 (1381 and 24S1) and four drinking water locations (15F4, 15F7, 16C2, and 28F3). Control locations were 24S1, and 28F3. All samples were collected in new unused plastic bottles, which were rinsed at least twice with source water prior to collection. Fish samples comprising of the flesh of two groups, 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, 1682, 16C4 and 33A2 (control).

Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, and milk. Airborne iodine and particulate samples were collected and analyzed weekly at six locations (6C1, 10S3, 11S1, 13C1, 14S1, and 22G). The control location was 22G1. Airborne iodine and particulate samples were obtained at each location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly 4

and sent to the laboratory for analysis.

Milk samples were collected biweekly at five locations (1 0F4, 18E1, 19B1, 23F1, and 25C1) from April through November, and monthly from December through March. One additional location (36E1) was sampled quarterly. Locations 36E1 and 23F1 were controls. All samples were collected in new unused two gallon plastic bottles from the bulk tank at each location, preserved with sodium bisulfite, and shipped promptly to the laboratory.

Broad leaf vegetation was collected monthly at three locations (11S3, 13S3 and 31G1). The control location was 31G1. Ten 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 rinq consisting of 16 locations (36S2, 3S1, 5S1, 7S1, 10S3, 11S1, 13S2, 14S1, 18S2, 21S2, 23S2, 25S2, 26S3, 29S1, 31S1 and 34S2) near and within the site perimeter representing fence post doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from LGS releases.

An intermediate distance rinq consisting of 16 locations (36D1, 2E1, 4E1, 7E1, 1OE1, 10F3, 13E1, 16F1, 19D1, 20F1, 24D1, 25D1, 28D2, 29E1, 31D2, and 34E1) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.

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

The specific 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.

5

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

10CFR20.2002 Permit Storagqe Area 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.

Independent Spent Fuel Storage Installation (ISFSl)

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

B.

Sample Analysis This section describes the general analytical methodologies used by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the LGS REMP in 2010. The analytical procedures used by the laboratories are listed in Appendix B Table B-3.

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

1.

Concentrations of beta emitters in drinking water and air particulates.

2.

Concentrations of gamma emitters in surface and drinking water, air particulates, milk, fish, broad leaf vegetation and sediment.

3.

Concentrations of tritium in surface and drinking water.

4.

Concentrations of 1-131 in air 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 6

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.

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 broad leaf vegetation eleven nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, 1-131, Cs-134, Cs-137, Ra-226, Th-228, and Th-232 were reported.

For fish nine nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, 1-131, Cs-134, and Cs-137 were reported.

For sediment eight nuclides, Be-7, K-40, Mn-54, Co-58, Co-60, 1-131, Cs-134, and Cs-137 were reported.

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

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

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.

7

D.

Program Exceptions For 2010 the LGS REMP had a sample recovery rate in excess of 99%.

Exceptions are listed below:

1.

Air sample from location 14S1 for the week 3/22/10 - 3/29/10 was not available due to equipment malfunction (IR 01087252 01).

2.

TLD data from station 29E1 was not available for the 2nd quarter due to the station being vandalized (IR 01087252 04).

3.

Only two vegetation samples were available at station 11S3 and 13S3 for the month of June (IR 01087252 02).

4.

Only two vegetation samples were available at station 13S3 for the month of September (IR 01087252 05).

5.

Weekly grab samples were taken for the composite surface water sampler at location 13B1 during the following periods due to equipment malfunction or frozen sample line (IR 01087252 06):

01/05/10 - 01/12/10 06/28/10 - 07/05/10 07/20/10 - 07/27/10 09/28/10 - 10/05/10 12/07/10 - 12/27/10

6.

Grab samples were taken for the composite surface water sampler at location 24S1 during the following periods due to equipment malfunction (IR 01087252 06):

02/09/10 - 02/16/10 11/03/10 - 12/07/10

7.

Weekly grab samples were taken for the composite drinking water sampler at location 16C2 during the following period due to equipment malfunction (IR 01087252 06):

12/28/09 - 01/19/10

8.

A grab sample was taken for the composite drinking water sampler at location 28F3 during the week of 12/29/09 - 01/05/10 due to equipment malfunction (IR 01087252 06).

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.

8

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

E.

Program Changes

1.

Air sampling station 6C1 was added to the REMP program on December 13, 2010 due to the increased population of the nearby shopping center (IR 1074042).

IV.

Results and Discussion A.

Aquatic Environment

1.

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

Tritium Monthly samples from all locations were composited quarterly and analyzed for tritium activity (Table C-1.1, Appendix C). All results were less than the MDC.

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:

Gross Beta Samples from all locations were analyzed for concentrations of total gross beta (Tables C-I1.1, Appendix C). The values ranged from 2.5 to 6.7 pCi/L. Concentrations detected were consistent with those detected in previous years (Figure C-1, Appendix C).

9

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

Gamma Spectrometry 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 Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting nuclides (Table C-111.1, Appendix C).

Naturally occurring K-40 was found at all stations and ranged from 2,640 to 3,920 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 (16B2, 16C4 and 33A2) semiannually. Of these locations two, 16B2 and 16C4, located downstream, could be affected by Limerick's effluent releases. The following analysis was performed:

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

Beryllium-7 was found at locations 16B2 and 16C4 and ranged from 1,630 to 3,740 pCi/kg dry. Potassium-40 was found at all locations and ranged from 10,800 to 16,100 pCi/kg dry. The fission product Cs-137 was found at 16B2 and 16C4 locations and ranged from 164 to 166 pCi/kg dry. The Cs-137 activity found at 1682 and 10

16C4 is attributed to LGS radioactive effluent releases. The dose to a teenager's skin and whole body was conservatively calculated at 4.36E-04 mrem and 3.74E-04 mrem, respectively. This dose represents 2.18E-03% and 6.23E-03%, 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.

B.

Atmospheric Environment 1.

Airborne

a.

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

Group II represents the locations at an intermediate distance from the LGS site (6C1 and 13C1), and Group III represents the control location at a remote distance from LGS (22G1).

The following analyses were performed:

Gross Beta Weekly samples were analyzed for concentrations of beta emitters (Table C-V.1 and C-V.2, Appendix C).

Detectable gross beta activity was observed at all locations.

The results from the on-site locations (Group I) ranged from 6 E-3 to 35 E-3 pCi/m 3 with a mean of 16.5 E-3 pCi/m 3.

The results from the intermediate distance location (Group II) ranged from 6 E-3 to 31 E-3 pCi/m 3 with a mean of 16 E-3 pCi/m 3. The results from the Distant locations (Group Ill) ranged from 7 E-3 to 32 E-3 pCi/m 3 with a mean of 16 E-3 pCi/m 3. Comparison of the 2010 air particulate data with previous year's data indicate no effects from the operation of LGS (Figure C-4, Appendix C). In addition, a comparison of the weekly mean values for 2010 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 11

detected in all samples. These values ranged from 47 E-3 to 135 E-3 pCi/m 3. All other nuclides were less than the MDC.

b.

Airborne Iodine Continuous air samples were collected from six locations (6C1, 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.

2.

Terrestrial

a.

Milk Samples were collected from five locations (10F4, 18E1, 119B1, 23F1, and 25C1) biweekly April through November and monthly December through March. Samples from one additional location (36E1) were taken quarterly. The following analyses were performed:

Iodine-131 Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VII.1, Appendix C). All results 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 1,050 to 1,500 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 31 G1) 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).

12

Cosmogenic Be-7 was found in 17 of 33 samples and ranged from 124 to 2,150 pCi/kg wet. Naturally occurring K-40 was found in all samples and ranged from 3,420 to 9,930 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.

All TLD measurements were below 10 mR/standard month, with a range of 4.9 to 9.8 mR/standard month. A comparison of the Site Boundary and Intermediate Distance data to the Control Location data, indicate that the ambient gamma radiation levels from the Control Location 5H1 were consistently higher than all other locations except 13S2. Location 13S2 historically shows higher ambient gamma radiation, which is assumed due to the rock substrate. The area that this TLD is located in has been determined to emanate radon prodingy.

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

D.

10 CFR 20.2002 Permit Storage Area The results of the surface water aquatic monitoring program from Location 24S1 were used to determine if radioactivity from the permit storage area had made it to the Schuylkill River. The data obtained from the gamma analysis program did not detect any migration of radioactivity from the permit storage area.

E.

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

F.

Land Use Survey A Land Use Survey conducted in September 2010 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 13

the nearest resident, milk producing animal and garden of greater than 500 ft2 in each of the sixteen 22 1/2 degree sectors around the site. The gardens in the N, ENE, E, and SW sectors are closer than in 2009. 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 Feet Feet Feet 1 N 3,109 3,775 24,775 2 NNE 2,706 9,610 3 NE 3,469 17,769 4 ENE 3,231 14,206 5 E 2,864 6,950 6 ESE 3,434 1,822 7 SE 5,108 1,282 8 SSE 5,403 6,898 9S 4,347 6,103 22,115 10 SSW 5,063 5,320 10,390 11 SW 3,251 4,559 12 WSW 3,799 12,013 14,175 13 W 3,627 4,208 14,654 14 WNW 3,932 3,932 15 NW 3,619 8,169 16 NNW 5,051 7,107 G.

Summary of Results - Inter-laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices for 18 and 14 analytes, respectively (Appendix E). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's MAPEP, were evaluated against the following pre-set acceptance criteria:

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 14

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, 16 out of 18 analytes met the specified acceptance criteria. Two analytes did not meet the specified acceptance criteria for the following reason:

1. Teledyne Brown Engineering's ERA November 2010 Sr-89 in water result of 77.8 pCi/L was higher than the known value of 68.5 pCi/L, resulting in a found to known ratio of 1.14. NCR 10-09 was initiated to investigate this failure. Since the ratio of 1.14 fell within an acceptance range of 20%, Teledyne considers this an acceptable result.

2. Teledyne Brown Engineering's ERA November 2010 Zn-65 in water result of 11.0 pCi/L was lower than the known value of 102 pCi/L.

NCR 10-09 was initiated to investigate this failure. The Zn-65 result of 111 was incorrectly reported as 11.0.

For the secondary laboratory, Environmental, Inc., all analytes met the specified acceptance criteria.

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.

15

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.

16

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:

2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

MEAN(M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

M EASUREME NTS SURFACE WATER H-3 8

200

<LLD

<LLD 0

(PCI/LITER)

SURFACE WATER (PCI/LITER)

GAMMA MN-54 CO-58 FE-59 CO-60 24 ZN-65 NB-95 ZR-95 15

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD

<LLD 0

0 0

1-131 CS-134 A-1

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:

2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS DRINKING WATER GR-B 48 4

4.4 3.8 5.2 15F4 INDICATOR 0

(PCI/LITER)

(26/36)

(2.5/6.7)

(10/12)

(3.2/5.3)

(9/12)

(3.7/6.7)

PHILADELPHIA SUBURBAN WATER COMPANY 45514 FEET SE OF SITE H-3 16 48 DRINKING WATER (PCI/LITER)

GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 N B-95 ZR-95 200

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD 30

<LLD 15

<LLD

<LLD 0

0 0

1-131 0

0 CS-134 A-2

TABLEA-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:

2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREME NTS BOTTOM FEEDER GAMMA 4

(PCI/KG WET)

K-40 M N-54 CO-58 FE-59 CO-60 ZN-65 NA 3780 (2/2)

(3640/3920) 3270 (2/2)

(3260/3280) 3780 (2/2)

(3640/3920) 16C5 INDICATOR VINCENT POOL DOWNSTREAM OF DISCHARGE 130

<LLD 130

<LLD 260

<LLD 130

<LLD 260

<LLD NA

<LLD 130

<LLD 150

<LLD

<LLD 0

0 0

1-131 CS-134 CS-137 A-3

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:

2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS PREDATOR GAMMA 4

(PCI/KG WET)

K-40 MN-54 CO-58 FE-59 CO-60 ZN-65 1-131 CS-134 NA 3075 (2/2)

(2640/3510) 3210 (2/2)

(3110/3310) 3210 (2/2)

(3110/3310) 29C1 CONTROL POTTSTOWN VIC IN ITY UPSTREAM OF INTAKE 130

<LLD 130

<LLD 260

<LLD 130

<LLD 260

<LLD NA

<LLD 130

<LLD

<LLD 0

0 0

0 A-4

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:

2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS SEDIMENT GAMMA 6

(PCI/KG DRY)

BE-7 K-40 MN-54 CO-58 CO-60 NA 2685 (2/4)

(1630/3740)

NA 14225 (4/4)

(10800/16100)

NA

<LLD NA

<LLD 150

<LLD 180 165 (2/4)

(164/166)

<LLD 3740 (1/2) 13350 (2/2)

(13000/13700) 15700 (2/2)

(15300/16100) 16B2 INDICATOR LINFIELD BRIDGE 7128 FEET SSE OF SITE 16B2 INDICATOR LINFIELD BRIDGE 7128 FEET SSE OF SITE 0

0 0

<LLD

<LLD 0

0 1-131 CS-134 CS-137

<LLD

<LLD 0

0 0

166 (1/2) 16C4 INDICATOR VINCENT DAM 11510 FEET SSE OF SITE A-5

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:

2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS AIR PARTICULATE GR-B 267 10 16 16 17 10S3 INDICATOR 0

(E-3 PCI/CU.METER)

(207/214)

(52/53)

(6/35)

(7/32)

(51/53)

(8/34)

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

MILK (PCI/LITER)

GAMMA BE-7 MN-54 CO-58 CO-60 CS-134 CS-1 37 GAMMA 1-131 1-131 GAMMA K-40 CS-134 CS-137 BA-140 LA-140 21 NA 87 (17117)

(47/135)

NA

<LLD NA

<LLD 50

<LLD 60

<LLD 70

<LLD 88 (4/4)

(79/103)

<LLD

<LLD 135 (1/1)

KEEN ROAD 2640 FEET E OF SITE 6C1 INDICATOR 11305 FEET NE OF SITE 267 114 114 0

0 0

<LLD

<LLD NA 1283 1290 1310 (88/88)

(26/26)

(22/22)

(1050/1500)

(1140/1410)

(1140/1410) 23F1 CONTROL 26506 FEET SW OF SITE 15

<LLD 18

<LLD 60

<LLD 15

<LLD

<LLD A-6

TABLEA-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2010 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER:

50-352& 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD:

2010 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)

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

MEAN (M)

MEAN(M)

STATION #

NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)

(F)

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

(LLD)

MEASUREMENTS VEGETATION GAMMA 33 (PCI/KG WET)

BE-7 NA 298 1334 1334 31G1 CONTROL (9/21)

(8/12)

PROUT'S JOLLYVIEW FARM (124/564)

(85/2150)

(85/2150) 71808 FEET NW OF SITE K-40 MN-54 CO-58 CO-60 1-131 CS-134 CS-137 RA-226 TH-228 TH-232 NA 4799 (21/21)

(3420/8510)

NA

<LLD NA

<LLD 60

<LLD 80

<LLD NA 2707 (7/2 1)

(1380/4140)

NA 62 (4/21)

(20/99)

NA 45 (1/21)

NA 6.8 (155/155)

(4.9/9.8) 5330 (12/12)

(3490/9660)

<LLD

<LLD 0

0 0

5330 (12/12)

(3490/9660) 31G1 CONTROL PROUT'S JOLLYVIEW FARM 71808 FEET NW OF SITE 0

0 2080 (1/12) 48 (2/12)

(30/68) 35 (3/12)

(35/36) 8.4 (4/4)

(7.8/9.1) 2707 (7/10)

(1380/4140) 71 (1/11) 45 (1/10) 9.3 (4/4)

(8.8/9.8) 13S3 INDICATOR LGS 500 KV YARD 1267 FEET SE OF SITE 11S3 INDICATOR LGS INFORMATION CENTER 1848 FEET ESE OF SITE 13S3 INDICATOR LGS 500 KV YARD 1267 FEET SE OF SITE 13S2 INDICATOR LGS 500 KV YARD 2149 FEET SE OF SITE 0

0 DIRECT RADIATION TLD-QUARTERLY (M ILLI-ROENTGEN/STD.MO.)

159 A-7

Intentionally Left Blank A-8

APPENDIX B LOCATION DESIGNATION, DISTANCE &

DIRECTION, AND SAMPLE COLLECTION &

ANALYTICAL. METHODS

TABLE B-1:

XXYZ -

Location Designation and Identification System for the Limerick Generating Station General code for identification of locations, where:

xx Y

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 A

B C

D on-site location 0-5,280 feet off-site 5,280-10,560 feet off-site 10,560-15,840 feet off-site 15,840-21,120 feet off-site E

F:

G:

H:

21,120-26,400 feet off-site 26,400-52,800 feet off-site 52,800-105,600 feet off-site 105,600-528,000 feet off-site Z

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

B-1

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2010 Location Location Description Distance & Direction From Site A.

Surface Water 13B1 24S1 Vincent Dam Limerick Intake (control) 9,225 feet SE 1,058 feet SW B.

Drinking (Potable) Water 15F4 15F7 16C2 28F3 Philadelphia Suburban Water Company Phoenixville Water Works Citizens Home Water Company Pottstown Water Authority (control)

C.

Milk - bi-weekly / monthly 10F4 18E1 19B1 23F1 Control 25C1 D.

Milk - quarterly 36E1 Control E.

Air Particulates / Air Iodine 45,514 feet SE 33,400 feet SSE 14,034 feet SSE 30,811 feet WNW 34,848 feet ESE 22,229 feet S 10,317 feet SSW 26,505 feet SW 14,224 feet WSW 24,816 feet N 10S3 11S1 11S2 13C1 14S1 22G1 6C1 F.Fish 16C5 29C1 Keen Road LGS Information Center LGS Information Center (quality control)

King Road Longview Road Manor Substation (control)

Pottstown Landing Field Vincent Pool Pottstown Vicinity (control) 2,648 feet E 2,017 feet ESE 2,006 feet ESE 14,980 feet SE 3,319 feet SSE 93,619 feet SW 11,305 feet NE Downstream of Discharge Upstream of Intake G.

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

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

TABLE B-2:

Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Limerick Generating Station, 2010 Location Location Description Distance & Direction From Site H.

Environmental Dosimetrv - TLD Site Boundary 36S2 3S1 5S1 7S1 10S3 11S1 13S2 14S1 18S2 21S2 23S2 25S2 26S3 29S1 31S1 34S2 Evergreen & Sanatoga Road Sanatoga Road Possum Hollow Road LGS Training Center Keen Road LGS Information Center 500 KV Substation Longview Road Rail Line along Longview Road Near Intake Building Transmission Tower Sector Site Boundary Met. Tower #2 Sector Site Boundary Sector Site Boundary Met. Tower #1 Intermediate Distance 36D1 2E1 4E1 7E1 1OE1 10F3 13E1 16F1 119D1 20F1 24D1 25D1 28D2 29E1 31 D2 34E1 Siren Tower No. 147 Laughing Waters GSC Neiffer Road Pheasant Road Royersford Road Trappe Substation Vaughn Substation Pikeland Substation Snowden Substation Sheeder Substation Porters Mill Substation Hoffecker & Keim Streets W. Cedarville Road Prince Street Poplar Substation Varnell Road 3,183 feet N 2,301 feet NNE 2,350 feet NE 3,099 feet ENE 2,648 feet E 2,017 feet ESE 2,149 feet SE 3,319 feet SSE 1,390 feet S 977 feet SSW 2,793 feet SW 2,445 feet WSW 2,088 feet W 2,886 feet WNW 1,395 feet NW 3,071 feet NNW 18,527 feet N 25,112 feet NNE 25,221 feet NE 22,489 feet ENE 20,826 feet E 29,442 feet ESE 22,772 feet SE 26,608 feet SSE 18,439 feet S 27,648 feet SSW 20,972 feet SW 21,044 feet WSW 20,231 feet W 26,110 feet WNW 20,446 feet NW 24,243 feet NNW 130,742 feet NE 11,305 feet NE 11,377 feet E 14,980 feet SE 16,877 feet SE 8,462 feet S 16,157 feet SSW 15,853 feet WNW Control and Special Interest 5H1 6C1 9Cl 13C1 15D1 17B1 20D1 31D1 Birch Substation (control)

Pottstown Landing Field Reed Road King Road Spring City Substation Linfield Substation Ellis Woods Road Lincoln Substation B-3

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2010 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Surface Water Gamma Spectroscopy Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis a continuous water radiological analysis (Limerick Generating compositor.

Station)

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

Station)

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

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

Station)

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

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

Drinking Water Gamma Spectroscopy Monthly composite from RMC-ER5 Collection of water samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis a continuous water radiological analysis (Limerick Generating compositor.

Station)

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

Station)

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

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

TBE, 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 approved techniques gamma spectroscopy Sediment Gamma Spectroscopy Semi-annual grab RMC-ER7 Collection of sediment samples for 500 grams (dry)

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

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

TABLE B-3:

Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2010 Sample Analysis Sampling Method Collection Procedure Number Sample Size Analytical Procedure Number Medium Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2023 Compositing of samples 13 filters TBE, TBE-2007 Gamma emitting radioisotope analysis each station (approximately 3600 Env. Inc., AP-03 Procedure for compositing air cubic meters)

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

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

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

Env. Inc., 1-131-01 Determination of 1-131 in milk by anion other times exchange Milk Gamma Spectroscopy Bi-weekly grab sample RMC-ER1 0 Collection of milk samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis when cows are on radiological analysis (Limerick Generating pasture. Monthly all Station)

Env. Inc., GS-01 Determination of gamma emitters by other times gamma spectroscopy TLD Thermoluminescence Quarterly TLDs RMC-ER9 Collection of TLD samples for 2 dosimeters Mirion Technologies Dosimetry comprised of two radiological analysis (Limerick Generating Panasonic 814 Station)

(containing 3 each CaSO4 elements)

B-5

i

,SE Figure B-1 Environmental Sampling Locations Within 5,280 Feet of the Limerick Generating Station, 2010 B-6

Figure B-2 Environmental Sampling Locations Between 5,280 and 26,400 Feet from the Limerick Generating Station, 2010 B-7

Figure B-3 Environmental Sampling Locations Greater than 26,400 Feet from the Limerick Generating Station, 2010 B-8

APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY

TABLE C-I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 13B1 24S1 PERIOD 12/28/2009

- 03/30/2010

< 161

< 161 03/30/2010

- 06/28/2010

< 159

< 158 06/28/2010

- 09/28/2010

< 175

< 177 09/28/2010

- 12/27/2010

< 182

< 178 MEAN c-1

TABLE C-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 13B 1 12/28/2009 - 02/01 02/01/2010 - 03/02 03/02/2010 - 03/30 03/30/2010 - 04/27, 04/27/2010 - 06/01 06/01/2010 - 06/28 06/28/2010 - 08/03, 08/03/2010 - 08/30, 08/30/2010 - 09/28, 09/28/2010 - 11/02, 11/02/2010 - 11/29 11/29/2010 - 12/27, Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 12010

/2010

'2010

/2010

'2010 5

8 4

3 2

6 1

1 6

6 5

5

<5

<8

<5

<4

<2

<6

<2

<1

<6

<7

<4

<6

< 12

< 13

<8

<4

< 11

<4

<3

< 11

< 13

<5

<7

<5

<4

<2

<6

<1

<7

<6

<5

<7

< 11

< 24

<8

<7

<4

< 12

<3

<2

< 11

< 10

<9

< 12

<6

< 10

< 5

<4

<2

<7

<2

<1

<6

<7

<4

<6

< 10

< 14

<9

<7

<4

< 10

<3

<2

< 12

< 10

< 12

<7

< 10

< 14

< 15

< 13

<8

<9

<6

< 10

< 12

<6

< 15

<4

<3

<2

<6

<1

<6

<5

<9

<5

<4

<2

<7

<2

<1

<6

<5

<6

< 24

< 33

< 36

< 30

< 21

< 24

< 15

< 11

< 28

< 31

< 29

< 35

<8

< 10

<9

<8

<7

<9

<5

<4

<9

< 10

< 14 MEAN 24S1 12/28/2009 02/02/2010 03/02/2010 03/30/2010 04/27/2010 06/01/2010 06/28/2010 08/03/2010 08/30/2010 09/28/2010 11/02/2010 11/29/2010 02/02/2010 03/02/2010 03/30/2010 04/27/2010 06/01/2010 06/28/2010 08/03/2010 08/30/2010 09/28/2010 11/02/2010 11/29/2010 12/27/2010 4

7 4

3 1

6 1

1 7

6 4

4

<4

<8

<5

<3

<2

<5

<2

<1

<6

<4

<5

<4

<8

< 17

< 11

<7

<3

< 14

<4

<3

< 12

< 11

< 10

<5

<4

<9

<5

<4

<1

< 10

<1

<6

<7

<4

<3

<7

< 18

<9

<6

<3

< 11

<3

< 11

< 10

<9

<8

<4

< 10

<5

<4

<2

<6

<2

<8

<5

<4

<7

< 13

<9

<5

<3

< 11

<3

< 12

< 10

<9

<6

<5

< 10

< 15

< 14

< 10

<6

< 14

<7

< 12

< 11

< 10

<7 4

7 4

3 1

5 1

1 7

5 4

3 4

9 4

3 1

6 6

6 4

4

< 17

< 29

< 31

< 22

< 16

< 22

< 20

< 13

< 27

< 35

< 22

< 18

<5

< 10

< 15

<8

<5

<8

<6

<4

< 11

<8

<7

<6 MEAN C-2

TABLE C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/28/2009 02/02 02/02/2010 03/02 03/02/2010 03/30 03/30/2010 04/27 04/27/2010 06/01 06/01/2010 06/28 06/28/2010 08/03 08/03/2010 08/30 08/30/2010 -

09/28 09/28/2010 -

11/02 11/02/2010 -

11/29 11/29/2010 -

12/27 15F4 151F7 16C2 28F3

/2010

/2010 3.9 +/- 1.8 5.2 +/- 2.9

< 2.9

< 2.6 3.0 + 1.7 4.1 + 1.3

< 3.2

< 2.6 4.0 + 1.8

< 2.7 3.3 +/- 1.8 4.4 +/- 1.3

< 3.3

< 2.8 2.5 +/- 1.7 3.8 +/- 2.0

< 2.8 3.3 +/- 1.8

< 2.5 5.3 +/- 2.8

< 3.1 5.0 +/-

5.7 +/-

6.2 +/-

6.7 +/-

6.4 +/-

3.7 +/-

4.0 +/-

< 3.2 1.8 2.0 2.1 2.0 1.9 1.8 1.7 5.3 5.9 5.0 3.8 3.6

+/-

2.0 2.0 1.9 1.8 1.6 3.2 3.6 4.2 4.2 3.4 3.3 3.4 3.9

+/- 1.8

+/- 1.7

+/- 2.0

+/- 1.8

+/- 1.7

+/- 1.8

+/- 1.7 3.4 3.6 3.1

+/-

1.8 1.9 1.7 4.4 +/- 2.2

< 3.7 3.4 +/- 2.2 3.8 +/- 1.3 MEAN 5.2 +/- 2.3 4.3 +/- 1.8 3.4 +/- 1.1 TAB LE C-I1.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/28/2009 - 03/30/

03/30/2010 - 06/28/

06/28/2010 - 09/28/

09/28/2010 - 12/27/

15F4 1 5F7 16C2 28F3 2010 2010 2010 2010

< 158

< 159

177

< 176 161 159 178 180

< 161

< 159

< 182

< 182 163 162 178 185 MEAN THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-3

TABLE C-11.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- SIGMA STC COLLECTION PERIOD 15F4 12/28/2009 - 02/02/2010 02/02/2010 - 03/02/2010 03/02/2010 - 03/30/2010 03/30/2010 - 04/27/2010 04/27/2010 - 06/01/2010 06/01/2010 - 06/28/2010 06/28/2010 - 08/03/2010 08/03/2010 - 08/30/2010 08/30/2010 - 09/28/2010 09/28/2010 - 11/02/2010 11/02/2010 - 11/29/2010 11/29/2010 - 12/27/2010 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140

<7

<4

<3

<1

<6

<2

<1

<7

<4

<5

<7

<5

<4

<2

<4.

<2

<1

<6

<5

<4

<5

<9

< 11

<7

<4

< 11

<5

<3

<11

<8

< 12

<6

<5

<3

<4

<1

<6

<2

<1

< 10

<6

<4

<5

<8

< 11

<7

<3

<9

<4

<2

< 14

< 10

<9

< 10

<6

<4

<2

<5

<2

<1

<8

<7

<5

<6

<8

< 10

<8

<7

<3

< 10

<4

<2

< 12

<9

<8

< 11

<8

<7

< 15

< 14

< 11

<7

< 11

<7

< 12

< 11

<9

< 13

<5

<4

<3

<1

<6

<2

<1

<7

<5

<3

<6

<5

<4

<2

<7

<2

<1

<7

<5

<6

< 27

< 22

< 29

< 30

< 18

< 25

< 20

< 12

< 31

< 25

< 23

< 32

<8

<9

<8

<5

<6

<4

< 13

< 10

<8

< 11 MEAN 15F7 12/28/2009 - 02/02/2010 02/02/2010 - 03/02/2010 03/02/2010 - 03/30/2010 03/30/2010 - 04/27/2010 04/27/2010 - 06/01/2010 06/01/2010 - 06/28/2010 06/28/2010 - 08/03/2010 08/03/2010 - 08/30/2010 08/30/2010 - 09/28/2010 09/28/2010 - 11/02/2010 11/02/2010 - 11/29/2010 11/29/2010 - 12/27/2010

<8

<4

<3

<2

<6

<2

<1

<6

<4

<6

<4

< 10

<4

<3

<2

<6

<2

<7

<4

<7

<4

< 13

<8

<9

<7

<5

< 12

<5

<3

< 10

<8

< 12

< 10

<9

<4

<3

<2

<7

<2

<1

<8

<4

<7

<5

< 14

< 10

<6

<4

< 14

<4

<3

< 13

<8

< 12

<9

<5

<4

<2

<6

<2

<8

<4

<7

<5

< 15

<8

<7

<6

<4

< 10

<4

<3

< 13

<8

< 11

<8

< 12

<6

< 15

< 14

< 15

<8

< 12

<8

< 12

<8

< 14

< 10

<8

<4

<3

<2

<8

<2

<1

<6

<4

<5

<4

<8

<4

<3

<2

<6

<2

<1

<6

<4

<7

<5

< 31

< 17

< 32

< 28

< 23

< 24

< 21

< 13

< 25

< 23

<34

< 23

< 14

<5

< 10

<7

<6

<7

<5

<4

<6

< 13

<6 MEAN C-4

TABLE C-II.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- SIGMA STC COLLECTION PERIOD 16C2 12/28/2009 - 02/01/2010 (1) 02/01/2010 - 03/02/2010 03/02/2010 - 03/30/2010 03/30/2010 - 04/27/2010 04/27/2010 - 06/01/2010 06/01/2010 - 06/28/2010 06/28/2010 - 08/03/2010 08/03/2010 - 08/30/2010 08/30/2010 - 09/28/2010 09/28/2010 - 11/02/2010 11/02/2010 - 11/29/2010 11/29/2010 - 12/27/2010 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140

<6

<5

<3

<2

<5

<2

<6

<4

<6

<5

<4

<2

<4

<2

<7

<4

<5

< 14

< 13

< 10

<7

<5

< 10

<4

< 11

<7

< 11

<5

<4

<3

<2

<5

<2

<8

<4

<6

< 14

< 10

<7

<4

< 12

<3

<4

< 14

<9

< 10

< 12

<6

<5

<3

<2

<5

<2

<6

<5

<7

<6

< 10

<9

<6

<4

<9

<4

< 13

<8

< 10

<9

<7

< 15

< 14

<7

< 11

<9

< 12

< 10

< 14

< 12

<7

<5

<4

<3

<2

<5

<2

<7

<4

<5

<7

<5

<4

<2

<6

<2

<6

<4

<5

<5 22 22 33 26 23 18 20 17 32 25 29 29

<7

< 10

<7

<5

< 12

<8

<9

< 10 MEAN 28F3 12/28/2009 02/02/2010 03/02/2010 03/30/2010 04/27/2010 06/01/2010 06/28/2010 08/03/2010 08/30/2010 09/28/2010 11/02/2010 11/29/2010

- 02/02/2010 (1)

- 03/02/2010

- 03/30/2010

- 04/27/2010

- 06/01/2010

- 06/28/2010

- 08/03/2010

- 08/30/2010

- 09/28/2010

- 11/02/2010

- 11/29/2010

- 12/27/2010

<4

<6

<5

<3

<2

<5

<2

<5

<4

<6

<4

<2

<5

<2

<6

<5

<8

< 13

< 10

<7

<4

< 10

<5

<4

<8

< 10

< 11

<9

<4

<5

<4

<2

<6

<2

<6

<5

<4

<6

<8

< 13

< 10

<7

<3

< 12

<4

<3

< 10

<8

<9

<5

<6

<4

<2

< 6

<2

<5

<4

<6

<9

<8

<7

<3

<9

<4

<3

<8

< 10

<6

<7

< 14

< 13

<6

< 11

< 10

< 11

<4

<5

<3

<2

<5

<2

<6

<4

<5

<6

<5

<3

<2

<6

<2

<5

<4

<5

<5 16 26 32 24 21 23 18 18 27 23 25 28

<6

<7

< 13

<8

<6

<5

<8

< 10 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-5

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

SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/KG W ET +/- 2 SIGMA STC COLLECTION PERIOD 16C5 PREDATOR 05/20/2010 11/03/2010 MEAN 16C5 BOTTOM FEEDER 05/20/2010 11/03/2010 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Cs-134 C s-1 37 I

MEAN 2640

+/- 586 3510

+/- 783 3075

+/- 1230 3640 +/- 799 3920

+/- 857 3780

+/- 396 3310

+/- 677 3110

+/- 796 3210

+/- 283 3260

+/- 708 3280

+/- 937 3270

+/- 28.3

< 36

45

< 40

< 55

< 95

99

< 47

< 49

< 86

< 87

< 624

< 164

< 39

< 49

55

< 54

< 66

< 60

< 171

< 120

< 51

42

< 115

< 126

< 955

< 187

< 41

53

< 48

< 60

38

43 29C1 PREDATOR 05/14/2010 11/03/2010 MEAN 29C1 BOTTOM FEEDER 05/14/2010 11/03/2010

< 34

< 70

37

< 73

< 90

< 128

< 44

< 63

< 84

< 131

< 146

212

37

65

< 38

69

< 29

< 56

< 41

< 61

< 89

< 140

< 29

< 75

83

< 143

169

221

< 42

< 61

< 34

< 69 MEAN

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-6

TABLE C-IV.1 CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA STC COLLECTION PERIOD Be-7 K-40 M n-54 Co-58 Co-60 1-131 Cs-134 Cs-137 16B2 06/07/2010 12/03/2010 3740

< 925

+/- 947 MEAN 16C4 06/07/2010 12/03/2010

< 396 1630

+/- 1380 16100 +/- 1570 15300 +/- 1470 15700 +/- 1131 10800 +/- 1270 14700 +/- 1910 12750 +/- 5515 13700 +/- 1320 13000 +/- 1280 13350 +/- 990

< 76

< 64

< 63

< 70

< 71

< 79

< 388

< 642

< 63

< 67

< 37

< 103

< 32

< 120

< 22

< 116

< 160

925

< 28

82 166 +/- 75

< 134 164 +/- 86

< 81 MEAN 33A2 06/07/2010

< 871 12/03/2010

< 697

< 81

< 66

< 82

< 66

< 73

< 425

< 495

114

< 55

< 88

< 68 MEAN

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

TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTIO N PERIOD 12/28/2009

- 01/04/2010 01/04/2010

- 01/11/2010 01/11/2010

- 01/18/2010 01/18/2010

- 01/26/2010 01/26/2010

- 02/01/2010 02/01/2010

- 02/08/2010 02/08/2010

- 02/15/2010 02/15/2010

- 02/22/2010 02/22/2010

- 03/01/2010 03/01/2010

- 03/08/2010 03/08/2010

- 03/15/2010 03/15/2010

- 03/22/2010 03/22/2010

- 03/29/2010 03/29/2010

- 04/05/2010 04/05/2010

- 04/12/2010 04/12/2010

- 04/19/2010 04/19/2010

- 04/26/2010 04/26/2010

- 05/03/2010 05/03/2010

- 05/10/2010 05/10/2010

- 05/17/2010 05/17/2010

- 05/24/2010 05/24/2010

- 06/01/2010 06/01/2010

- 06/07/2010 06/07/2010

- 06/14/2010 06/14/2010

- 06/21/2010 06/21/2010

- 06/28/2010 06/28/2010

- 07/06/2010 07/06/2010

- 07/12/2010 07/12/2010

- 07/19/2010 07/19/2010

- 07/26/2010 07/26/2010

- 08/02/2010 08/02/2010

- 08/09/2010 08/09/2010

- 08/16/2010 08/16/2010

- 08/23/2010 08/23/2010

- 08/30/2010 08/30/2010

- 09/06/2010 09/06/2010 - 09/13/2010 09/13/2010 - 09/20/2010 09/20/2010 - 09/27/2010 09/27/2010 - 10/04/2010 10/04/2010 - 10/11/2010 10/11/2010 - 10/18/2010 10/18/2010 - 10/25/2010 10/25/2010 - 11/01/2010 11/01/2010 - 11/08/2010 11/08/2010 - 11/15/2010 11/15/2010 - 11/22/2010 11/22/2010 - 11/29/2010 11/29/2010 - 12/06/2010 12/06/2010 - 12/13/2010 12/13/2010 - 12/20/2010 12/20/2010 - 12/27/2010 12/27/2010 - 01/03/2011 10S3 14 +5 8+/-5 24 +/-5 15 +/-4 25 +6 14 +5 8+/-4 14 +4

<6 11 +/-4 15 5

16 5

12 5

8+/-4 21 +4

<7 GROUP I lisi 12_+5 8+/-5 26 _5 18+/- 4 17_ 6 17+/- 5 11 +/-4 12 +/- 4

<6 14S1 13_5 7+/-5 29_ 6 16+/- 4 22+/- 6 21 +/-+6 8+/-4 10+/- 4

<6

<7 13C1 6C1 I

GROUP II I GROUP III 13C5

_4

_5

+/-5

_5

+/-5

+/-4

_6

_5

+/-4

+/-5

+/-+6

_5

+/-6

_4

+/-6

+/-5

_5

+/-6

_4

_5

+/-6

_4

_6

+5

+4

_4

+4

+5

_5

+/-4

-4

+/-6

_4

_5 9

16 16 16 8

16 11 15 17 12 11 16 16 15 10 16 22 20 31 22 21 19 21 24 25 15 27 15 14 21 8

16 16 17 7

6 19 19 27 13 17 14 9

23 9

16 9

12 18 11 10 13 17 14 11 14 23 15 26 25 14 15 19 25 26 15 35 15 15 21 11 16 18 18 9

7 16 20 31 13 13 13 10 24 20 16

+/-5

_5 (1)

_5

_4

_5

+4

_5

+5

+/-5

_5

+/-6

_5

+4

_5

+/-6

_5

_4

_5

5

_5

+/-5

+/-6

_4

_5

+/-6

_4

+/-6

_5

+/-4

_4

_5

+/-6

_4

+4

+/-6

+4

_4

<7 26 24 16 16 10 14

<6 12 13 17 18 8

19 9

13 17 13 13 12 15 13 13 17 20 16 29 22 17 18 20 21 27 16 31 15 19 21 12 16 17 15 8

6 15 16 23 15 12 10 7

25

+/-

_+/-

_+

+/-t

_+

+5

+/-5

_5

+5

_+/-4

+/-5

+5

+/-5

_5

_+5

_+/-5

+4

_6

_5

+/-4

_5

+/-6

+/-4

+/-5

+/-4

_5

+/-5

_5

+/-6

+4

_5

+/-6

+/-4

_6

+5

_4

+4

_4

+/-5

_4

+/-6

_4

+/-4 5

5 6

5 4

4 22G1 12_+/-T 10 +/- 5 25 +/- 5 17 +/- 4 19 +/- 6 17 +/- 5 10 +/- 4 10 +/- 4 8+/-4 7+4 14+/- 5 19+/- 5 16 +/-5 7_4 18+/- 4 10+/- 5 13+/- 4 13+/- 5 9_5 10+/- 5 14_ 5 17+/- 4 15+/- 6 15+/- 5 17 +/- 4 22 +/- 6 14 +/- 5 29 +/- 6 22 +/- 4 17 +/- 5 18 +/- 4 22 +/- 6 25 +/- 5 27 +/- 5 12 +/- 5 32 +/- 6 12 +/- 4 17 +/- 5 21 +/- 6 8+/-4 20+/- 4 29+/- 6 20+/- 5 7+/-4

<6 13+/- 4 19 5

19+/- 5 15+/- 4 12+/- 4 10+/- 6 10+/- 4 21_ 4 13 10 21 (2)

+/-6

+4

+/-4 M EAN 17 +/- 13 16 +/- 11 16 +/- 13 16 +/- 11 15 +/- 11 16 +/- 12

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

TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS I N AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF UIVERICK GENERATING STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU IVETER +/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GRUP II - INTERMVEDIATE DISTANCE LOCATIONS GROUP III - CONTROL LOCATIONS COLLECTION PEROD 12/2&2009 - 02/01/2010 02/01)2010 - 02222010 03101f2010 - 04/05/2010 03/30)2010 - 05/03/2010 05/03/2010 - 06/01/2010 06/01)2010 - 06/28/2010 06/2&2010 - 08/02/2010 08/02/2010 - 08/30/2010 08/30/2010 - 10/04/2010 10/04/2010 - 11/01/2010 11/01/2010 - 11/29/2010 11/29/2010 - 01/03/2011 12/2&2009 - 01/03/2011 MIN NWX MEAN+

2SD 7

29 16.8 +/- 14 8

21 12.7 +/- 9 8

20 13.7 +/-8 9

21 14.1 +/- 8 10 17 13.3 +/- 5 10 23 16.4 +/- 8 14 31 21 +/- 10 15 30 22.3 +/- 10 8

35 18.9 +/- 15.9 7

18 14.6 +/- 8 6

31 172 +/- 16 9

27 15 +/- 11.1 COLLECTI ON PERIOD 12/28/2009 - 02/01/2010 02/01/2010 - 02/22,2010 03/01/2010 - 04/05/2010 04/05/2010 - 05/03/2010 05/03/2010 - 06/01/2010 06/01/2010 - 06/28&2010 06/28/2010 - 08/02/2010 08/02/2010 - 08/30/2010 08/30(2010 - 10/0412010 10/04/2010 - 11/01/2010 11/01/2010 - 11/29/2010 11/29/2010 - 01/03/2011 MN MAX MEAN+

2SD 8

26 18.3 +/- 16.6 10 16 13.3 7

8 18 13.7 9

9 19 14.4 9

12 15 13.3 3

13 20 15.7 7

16 29 20.3 10 16 27 20.8 9

12 31 19.4 +/- 15 8

17 13.8 8

6 23 15 13 7

25 14 12 COLLECTION PERIOD 12/28/2009 - 02/01/2010 02/01/2010 - 03/01/2010 03/01/2010 - 04/05/2010 04/05/2010 - 05/03/2010 05/3/2010 - 06/01/2010 06/01/2010 - 06/28/2010 06/28/2010 - 08/02/2010 06/02/2010 - 08/30/2010 08/30/2010 - 10/04/2010 10/04/2010 - 11/01/2010 11/08/2010 - 11/29/2010 11/29/2010 - 01/03/2011 MN N/AX MVEAN+

2SD 10 25 16.6 +/- 12 8

17 11.2 +/- 8 7

19 12.4 +/- 11 10 18 13.1 +/- 7 9

17 12.5 +/- 8 15 22 17 +/- 7 14 29 19.9 +/- 11 12 27 21.5 +/- 13 8

32 17.8 +/- 19 7

29 19 +/- 18 13 19 17.1 +/- 7 10 21 13.6 +/- 9 7

32 16 +/- 12 Z--1 6

35 17 +/- 12 12/28/2009 - 01/032011 6

31 16 +/- 11 12/28/2009 - 01/03/2011

THE IVEAN A.ND 2 STANDARD DEMA11ON VALUES AFE CALCULATED USI N3 THE POSITIVE VALUES C-9

TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER + 2 SIGMA STC COLLECTION PERIOD Be-7 M n-54 Co-58 Co-60 Cs-1 34 Cs-137 10S3 12/28/2009 03/29/2010 06/28/2010 09/27/2010 M EAN 11S1 12/28/2009 03/29/2010 06/28/2010 09/27/2010 M EAN 13C1 12/28/2009 03/29/2010 06/28/2010 09/27/2010 M EAN 14S1 12/28/2009 03/30/2010 06/28/2010 09/27/2010 MEAN 22G 1 12/28/2009 03/29/2010 06/28/2010 09/27/2010 M EAN 03/29/2010 06/28/2010 09/27/2010 01/03/2011 126 69 106 52

+/-+

+/-

42 32 33 15

<4

<2

<3

<2 6

3 3

2

<3

<4

<2

<4

<3

<4

<3

<2 88 +/- 68 03/29/2010 06/28/2010 09/27/2010 01/03/2011 86 91 110 47

+/-

t-29 36 31 24

<3

<3 3

7 5

3

<3

<5

<3

<4

<3

<4

<3

<3 84 + 53 03/29/2010 06/28/2010 09/27/2010 01/03/2011 117 88 86 60

- 40

+/- 27

+/- 15

<3

<2 5

4 5

2 2

4 4

3

<2

<3

<4

<2

<4

<3

<2 88 +/- 46 03/29/2010 06/28/2010 09/27/2010 01/03/2011 91 88 75 60

+/- 36

+/- 35

+/- 38

+/- 19

<3

<2

<4

<2 3

2 2

2

<4

<3

<2

<3

<2 79 +/- 29 03/29/2010 06/28/2010 09/27/2010 01/03/2011 89 103 79 82

+/- 30

+/- 40

+/- 26

+/- 22

<4

<5

<3

<2

<4

<6

<3

<3 3

4 3

2

<3

<5

<2

<3

<4

<2

<3 88 +/- 21 6C1 12/13/2010 - 01/03/2011 (1) 135 +/- 75

< 16

< 18

< 12

< 13

< 12 M EAN

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE P ROGRAM CHANG ES SECTION FOR EXPLANATION c-10

TABLE C-Vl.1 CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 12/26/2009 - 01/04/2010 01/04/2010 - 01/11/2010 01/11/2010 - 01/18/2010 01/18/2010 - 01/26/2010 01/26/2010 - 02/01/2010 02/01/2010 - 02/08/2010 02/08/2010 - 02/15/2010 02/15/2010 - 02/22/2010 02/22/2010 - 03/01/2010 03/01/2010 - 03/08/2010 03/08/2010 - 03/15/2010 03/15/2010 - 03/22/2010 03/22/2010 - 03/29/2010 03/29/2010 - 04/05/2010 04/05/2010 - 04/12/2010 04/12/2010 - 04/19/2010 04/19/2010 - 04/26/2010 04/26/2010 - 05/03/2010 05/03/2010 - 05/10/2010 05/10/2010 - 05/17/2010 05/17/2010 - 05/24/2010 05/24/2010 - 06/01/2010 06/01/2010 - 06/07/2010 06/07/2010 - 06/14/2010 06/14/2010 - 06/21/2010 06/21/2010 - 06/28/2010 06/28/2010 - 07/06/2010 07/06/2010 - 07/12/2010 07/12/2010 - 07/19/2010 07/19/2010 - 07/26/2010 07/26/2010 - 08/02/2010 08/02/2010 - 08/09/2010 08/09/2010 - 08/16/2010 08/16/2010 - 08/23/2010 08/23/2010 - 08/30/2010 08/30/2010 - 09/06/2010 09/06/2010 - 09/13/2010 09/13/2010 - 09/20/2010 09/20/2010 - 09/27/2010 09/27/2010 - 10/04/2010 10/04/2010 - 10/11/2010 10/11/2010 - 10/18/2010 10/18/2010 - 10/25/2010 10/25/2010 - 11/01/2010 11/01/2010 - 11/08/2010 11/08/2010 - 11/15/2010 11/15/2010 - 11/22/2010 11/22/2010 - 11/29/2010 11/29/2010 - 12/06/2010 12/06/2010 - 12/13/2010 12/13/2010 - 12/20/2010 12/20/2010 - 12/27/2010 12/27/2010 - 01/03/2011 10S3

<*b

<66

<22

<29

<19

<26

<16

<21

<16

<15

<20

<52

<14

<31

<12

< 24

<22

< 35

<12

<14

<12

<40

<13

< 34

<9

<43

<12

< 37

<16

<13

<23

<14

<26

<22

< 34

< 37

<28

<14

< 37

<18

<16

< 40

<41

<50

<42

<16

< 55

<56

<36

< 54

<58

<44 GROUP I il~i

61

29

22

30

< 35

27

30

<21

30

< 37

23

14

31

22

24

30

36

30

< 26

22

<17

32

< 34

<18

< 43

< 28

< 37

< 22

28

< 30

<12

< 33

26

22

< 34

< 37

28

26

< 37

< 41

29

< 40

< 17

50

42

< 37

< 55

56

36

< 54

58

< 44 14S

< b1

< 68

22

30

< 35

<15

< 30

< 21

< 30

< 37

< 53

< 37

22

25

30

36

30

26

22

< 41

32

< 35

<18

< 24

29

< 37

22

29

31

23

< 33

27

12

19

< 37

29

< 26

< 38

< 41

< 30

< 40

< 41

< 50

< 42

< 38

< 24

< 57

< 36

< 58

<54

< 49 13C1

34

68

<12

<13

36

27

31

21

30

< 37

< 54 (1)

< 15

<18

22

< 25

30

< 36

30

< 27

< 23

< 41

32

<15

<18

< 42

28

36

22

28

< 30

22

< 33

14

22

< 33

< 37

<16

26

< 37

41

29

< 39

< 41

50

31

< 37

< 55

< 56

< 36

< 57

< 53

< 48 GROUPII IGROUP III 6C1 22G1

< 60

< 67

< 22

< 29

< 34

< 27

< 29

< 11

< 28

< 36

< 52

< 14

< 31

< 21

< 24

< 29

< 15

< 29

< 26

< 21

< 39

< 32

< 34

< 17

< 51

< 29

< 16

< 22

< 29

< 30

< 23

< 33

< 27

< 22

< 34

< 16

< 30

< 26

< 16

< 43

< 30

<17

< 41

< 28

< 43

< 38

< 56

< 24 (2)

< 16

< 56

< 58

< 36

< 54

< 44

< 49 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION (2) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-11

TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROL FARM INDICATOR FARM COLLECTION PERIOD 01/12/2010 02/09/2010 03/16/2010 04/06/2010 04/20/2010 05/04/2010 05/18/2010 06/01/2010 06/15/2010 06/30/2010 07/13/2010 07/27/2010 08/11/2010 08/24/2010 09/07/2010 09/22/2010 10/05/2010 10/19/2010 11/02/2010 11/16/2010 11/30/2010 12/14/2010 23F1 36E1 10F4 18E 1 1 9B1 25C1

< U.4

< 0.6

< 0.5

< 0.6

< 0.4

< 0.7

< 0.5

< 0.6

< 0.4

< 0.5

< 0.8

< 0.5

< 0.6

< 0.5

< 0.6

< 0.3

< 0.5

< 0.4

< 0.7

< 0.8

< U.4

< 0.7

< 0.4

< 0.5

< 0.8

< 0.9

< 0.7

< 0.6

< 0.8

< 0.6

< 0.8

< 0.7

< 0.6

< 0.7

< 0.6

< 0.7

< 0.6

< 0.7

< 0.4

< 0.7

< 0.5

< 0.8

< 0.4

< 0.5

< 0.6

< 0.9

< 0.5

< 0.8

< 0.7

< 0.8

< 0.6

< 0.7

< 0.6

< 0.7

< 0.8

< 0.7

< 0.4

< 0.7

< 0.5

< 0.7

< 0.4

< 0.5

< 0.6

< 0.9

< 0.5

< 0.6

< 0.8

< 0.4

< 0.7

< 0.8

< 0.7

< 0.6

< 0.8

< 0.6

< 0.8

< 0.7

< 0.4

< 0.7

< 0.3

< 0.8

< 0.6

< 0.4

< 0.7

< 0.6

< 0.8

< 0.6

< 0.8

< 0.9

< 0.7

< 0.6

< 0.8

< 0.7

< 0.5

< 0.6 MEAN C-12

TABLE C-V 11.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 10F4 01/12/2010 02/09/2010 03/16/2010 04/06/2010 04/20/2010 05/04/2010 05/18/2010 06/01/2010 06/15/2010 06/29/2010 07/13/2010 07/27/2010 08/10/2010 08/24/2010 09/07/2010 09/21/2010 10/05/2010 10/19/2010 11/02/2010 11/16/2010 11/30/2010 12/14/2010 MEAN 18E1 01/12/2010 02/09/2010 03/16/2010 04/06/2010 04/20/2010 05/04/2010 05/18/2010 06/01/2010 06/15/2010 06/30/2010 07/13/2010 07/27/2010 08/11/2010 08/24/2010 09/07/2010 09/22/2010 10/05/2010 10/19/2010 11/02/2010 11/16/2010 11/30/2010 12/14/2010 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 I

1220 1310 1370 1220 1280 1280 1290 1320 1390 1470 1370 1340 1260 1310 1190 1240 1300 1390 1280 1210 1270 1340 94 146 1 53 1 22 98 1 35 1 28 1 66 131 1 56 144 151 111 1 50 1 66 1 25 1 38 1 50 1 04 1 31 149 1 28

<4

<5

<7

<4

<5

<6

<5

<7

<3

<4

<7

<5

<6

<4

<6

<7

<5 27 30 24 57 40 43 37 50 42 35 22 29 22 39 34 32 21 29 19 29 38 27 7

8 8

11 11 14 13 8

14 7

7 9

6 8

13 8

7 9

6 9

10 8

1302 +/- 1 37 1350 1330 1290 1240 1240 1140 1310 1260 1290 1160 1230 1440 1230 1050 1160 1220 1060 1180 1210 1260 1200 1460

+/- 113

+/- 1 59

+/- 143

+/- 108

+/- 94

+/- 130

+/- 133

+ 114 S1 36

- 151

+ 166 S1 57

+ 160

+ 137

+/- 141

+118

+ 152

+ 142

- 107 S1 22 S1 35 S1 37

<4

<6

<10

<3

<5

<7

<10

<5

<3

<7

<5

<6

<7

<5

<5 36 35 24 45 41 44 34 34 43 37 26 42 25 35 42 33 29 31 24 26 32 28 10 8

7 12 12 14 11 9

8 9

6 12 7

10 11 8

6 9

6 8

9 9

1241

+/- 203 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-13

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 19B1 01/12/2010 02/09/2010 03/16/2010 04/06/2010 04/20/2010 05/04/2010 05/18/2010 06/01/2010 06/15/2010 06/29/2010 07/13/2010 07/27/2010 08/10/2010 08/24/2010 09/07/2010 09/21/2010 10/05/2010 10/19/2010 11/02/2010 11/16/2010 11/30/2010 12/14/2010 MEAN 23F1 01/12/2010 02/09/2010 03/16/2010 04/06/2010 04/20/2010 05/04/2010 05/18/2010 06/01/2010 06/15/2010 06/29/2010 07/13/2010 07/27/2010 08/10/2010 08/24/2010 09/07/2010 09/21/2010 10/05/2010 10/19/2010 11/02/2010 11/16/2010 11/30/2010 12/14/2010 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1220 1260 1310 1300 1360 1350 1190 1370 1190 1400 1380 1330 1390 1320 1160 1440 1240 1460 1380 1320 1050 1320 1 02 146 131 1 30 83 119 124 120 111 1 37 190 142 1 39 128 145 126 1 57 1 54 98 122 1 36 105 31 35 33 37 53 49 32 38 33 40 33 26 28 47 39 42 24 33 20 26 33 33

< 9

< 8

<10

15

<14

< 7

<12

<10

<13

< 8

< 7

<8

<14

< 11

<10

< 6

<10

<6

< 7

< 9

<10 1306 +/- 198 1330 1260 1360 1320 1400 1390 1320 1300 1340 1260 1410 1390 1390 1270 1230 1220 1360 1140 1360 1170 1270 1320 128 1 78 116 120 85 112 1 23 171 1 26 1 25 168 143 1 39 143 1 35 1 03 1 30 1 43 119 1 26 1 32 101 6

9 4

5 4

4 4

6 6

5 10 8

6 2

5 4

5 5

5 6

5 4

47 52 20 40 44 36 34 56 42 28 31 35 31 36 27 25 19 28 23 23 26 24 14 15 6

11 12 10 9

11 14 9

10 9

10 6

10 8

6 9

7 8

7 6

1310 +/- 150

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-14

TAB LE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 25Cl 01/12/2010 02/09/2010 03/16/2010 04/06/2010 04/20/2010 05/04/2010 05/1812010 06/01/2010 06/15/2010 06/29/2010 07/13/2010 07/27/2010 08/10/2010 08/24/2010 09/07/2010 09/21/2010 10/05/2010 10/19/2010 11/02/2010 11/16/2010 11/30/2010 12/1412010 MEAN 36E1 01/12/2010 04/06/2010 07/13/2010 1010512010 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1380 1260 1370 1350 1340 1230 1380 1340 1350 1360 1180 1210 1140 1120 1190 1240 1500 1270 1280 1290 1220 1230 118 119 129 118 88 101 123 142 158 131 137 1 55 182 110 126 116 151 1 39 112 131 135 110

<6

<4

< 10

<6

<4

<5

<6

<7

<3

<5

<6

<5

<4

<5

<4

<5

<3

<6

< 45

< 22

38

< 39

< 44

30

< 45

< 48

29

<21

< 29

41

< 34

< 29

< 32

< 25

31

< 21

< 28

< 30

< 21

< 33

24

< 15

23

< 10

<6

< 10

< 13

< 14

< 11

< 14

< 11

<8

<6

<7

< 11

<6

<9

<8

<6

<9

<8

<7

< 13

<9

<4

<6 1283 +/- 184 1150 1160 1200 1210

+/-

120 98 93 147 5

4 4

6 1180

+/- 59 THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-15

TABLE C-V 111.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAF VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-134 Cs-137 Ra-226 Th-228 Th-232 11S3 06/24/2010 06/24/2010 07/20/2010 07/20/2010 07/20/2010 08/17/2010 08/17/2010 08/17/2010 09/13/2010 09/13/2010 09/13/2010 Cabbage Collards Cabbage Collards Swiss Chard Cabbage Collards Swiss Chard Cabbage Collards Swiss Chard Collards Swiss Chard Cabbage Collards Swiss Chard Cabbage Collards Swiss Chard Collards Swiss Chard (1) < 169

< 191 267 +/- 207 168 +/- 133

< 272

< 169

< 168 425 +/- 125

< 112 124 +/- 101 138 +/- 121 5190 +/- 468 4760 +/- 448 3420 +/- 506 4550 +/- 446 5430 +/- 471 4430 +/- 369 3680 +/- 334 4040 +/- 293 4740 +/- 305 4840 +/- 299 3720 +/- 278

< 19

< 25

< 23

< 26

< 17

< 14

< 12

< 13

< 12 MEAN 224 +/- 251 4436 +/-

1297 13S3 06/24/2010 06/24/2010 07/20/2010 07/20/2010 07/20/2010 08/17/2010 08/17/2010 08/17/2010 09/13/2010 09/13/2010 (1) < 178

< 194 564 +/- 248

< 191 308 +/- 144 364 +/- 184

< 173 327 +/- 98 (1) < 125

< 91 6370 +/- 490 6100 +/- 532 3500 +/- 577 3830 +/- 508 5220 +/- 532 3490 +/- 327 4970 +/- 406 8510 +/- 281 4830 +/- 288 5160 +/- 233

< 22

< 24

< 31

< 20

< 23

< 16

< 15

< 12

< 9

< 20

< 22

< 25

< 22

< 26

< 16

< 17

< 14

< 12

< 13

< 18

< 22

< 29

< 24

< 17

< 16

< 17

< 13

14

< 10

< 22

< 23

< 25

< 15

<9

<8

< 10

<7

< 10

< 18

< 25

< 22

< 21

< 26

< 15

< 16

< 13

< 15

< 14

< 15

< 21

< 24

< 34

< 20

< 17

< 16

< 15

< 14

< 15

< 11

< 20

< 38

< 21

< 25

< 22

< 21

< 11

<9

< 12

<8

< 10

< 42

< 49

< 28

< 26

< 31

< 56

< 58

< 42

< 48

< 53

< 46

< 45

< 44

< 36

< 29

< 27

< 58

< 49

< 43

< 53

< 54

56

< 43

< 48

< 31

< 27

< 25

< 30

< 26

< 33

< 40

< 54

< 18

18

< 24

< 19

< 27

< 15

< 16

< 12

< 11

< 12

< 11

< 18

< 25

19

23

< 16

< 13

< 11

<9

< 19

23

< 23

< 18

<8

<7

<9

<6

<8

< 18

< 22

< 24

< 19

< 27

< 17

< 12

< 14

< 12

< 20

< 23

< 35

< 23

< 20

< 19

< 13

< 12

<8

< 24

< 27

< 20

< 25

< 28

< 22

<9

<8

< 10

<7

<9

<8

< 381

< 395

< 527

< 439

< 697

< 365

< 373

< 263

< 301

< 247

< 204

< 30

< 31

< 45

< 42

< 54 71

< 26

< 22

< 19

< 21

< 32

< 29

< 46

< 44

< 43 99

< 31 58

< 23 20

< 93

< 94

< 115

< 83

< 110

+/- 20

< 51

< 77

< 60

< 45

< 55

< 50

< 453 1390 +/- 424 4000 +/- 810 1380 +/- 478

< 556 3260 +/- 487 2010 +/- 433 2770 +/- 271 4140 +/- 342

< 200

< 80

< 93

< 134

< 108

< 94

+/- 28

< 85

< 59

+/- 18

< 50 45 +/- 32

+/- 11

< 33 MEAN 391

+/- 236 5198 +/- 3056 2707 +/- 2312 59 +/- 79 31G1 06/24/2010 06/24/2010 06/2412010 07/20/2010 07/20/2010 07/20/2010 08/17/2010 08/17/2010 08/17/2010 09/13/2010 09/13/2010 09/13/2010 Broccoli Leaves Cabbage Cauliflower Leaves Pickel Leaves Yellow Squash Leaves Zucchini Leaves Mellon Leaves Yellow Squash Leaves Zucchini Leaves Broccoli Leaves Brussel Sprout Leaves Cabbage 206 211 175 1140 2070 1210 2150 1930 1830 85

+/- 227

+/- 298

+/- 209

+/- 134

+/- 106

+/- 125

+/- 72 4320 +/- 455 5620 +/- 561 4760 +/- 471 3990 +/- 476 3940 +/- 507 3490 +/- 432 6250 +/- 263 5880 +/- 207 5330 +/- 240 5120 +/- 186 5600 +/- 201 9660 +/- 221

< 20

< 26

< 20

< 26

< 22

< 8

< 7

< 9

< 7

< 9

< 515

< 445

< 475

< 569

< 513

< 500

< 203

< 161

< 191

< 164

< 208 2080 +/- 224

< 42

< 34

< 38

< 50

< 47

30 68 +/- 16 30 +/- 12

< 16

< 12

< 17

< 15

< 95

< 110

< 101

< 108

104 35 +/- 20

< 37 36 +/- 21

< 28

< 35 36 +/- 16

< 91 263 +/- 74 MEA N 1335 +/- 1616 5330 +/-

3222 49 +/- 54 36 +/- 2

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

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH +/- 2 STANDARD DEVIATIONS STATION MEAN JAN - MAR APR - JUN JUL - SEP OCT - DEC CODE

+/- 2 S.D.

2E1 7.0 +/- 1.3 6.7 +/- 0.6 6.5 +/- 0.3 7.7 +/- 0.8 7.2 +/- 0.8 3S1 7.0 +/- 0.6 6.7 +/- 0.6 7.0 +/- 1.0 7.3 +/- 1.0 6.9 +/- 0.8 4E1 5.3 +/- 0.6 5.0 +/- 0.3 5.2 +/- 0.4 5.6 +/- 0.7 6.1 +/- 0.6 5H1 8.4 +/- 1.3 7.8 +/- 0.4 8.3 +/- 0.6 9.1 +/- 0.4 8.2 +/- 1.3 5S1 7.5 + 1.0 7.5 +/- 0.6 7.0 +/- 0.3 8.0 +/- 0.5 7.5 +/- 1.0 6C1 7.3 +/- 1.6 6.4 +/- 0.9 7.4 +/- 1.4 8.0 +/- 0.6 6.9 +/- 0.7 7E1 7.1 +/- 0.6 7.2 +/- 0.8 6.8 +/- 0.5 7.4 +/- 1.0 8.0 +/- 0.5 7S1 7.0 +/- 1.2 7.0 +/- 1.1 6.4 +/- 0.5 7.6 +/- 0.8 7.4 +/- 1.3 9C1 6.8 +/- 1.1 6.6 +/- 0.9 6.3 +/- 0.5 7.4 +/- 1.0 6.5 +/- 0.7 10E1 6.9 +/- 1.1 6.6 +/- 0.7 6.5 +/- 0.4 7.5 +/- 0.7 7.4 +/- 0.4 10F3 6.9 +/- 1.1 7.1 +/- 1.0 6.3 +/- 0.1 7.3 +/- 1.4 7.4 +/- 0.7 10S3 7.0 +/- 1.7 6.6 +/- 0.6 6.5 +/- 0.8 8.0 +/- 0.6 7.2 +/- 0.8 1iSi 7.9 +/- 1.7 7.6 +/- 0.5 7.2 +/- 0.7 8.8 t 1.2 8.1 +/- 1.1 13C1 5.3 + 0.8 5.2 +/- 0.5 4.9 +/- 0.2 5.7 +/- 0.5 5.5 +/- 0.5 13E1 7.0 +/- 1.3 6.6 +/- 0.4 6.7 +/- 0.5 7.8 +/- 0.7 7.1 +/- 1.0 13S2 9.3 +/- 1.0 9.2 + 1.2 8.8 +/- 1.3 9.8 +/- 1.4 9.5 +/- 1.0 14S1 6.2 +/- 1.0 6.1 +/- 0.6 5.7 +/- 0.7 6.7 +/- 1.1 6.8 +/- 0.8 15D1 6.9 +/- 1.4 6.7 + 0.5 6.3 +/- 0.6 7.7 +/- 0.8 7.4 +/- 0.8 16F1 7.0 +/- 0.8 6.8 +/- 0.5 6.7 +/- 0.5 7.4 +/- 0.6 7.5 +/- 0.7 1781 6.6 +/- 0.6 6.6 + 0.5 6.3 +/- 0.3 6.9 +/- 0.9 6.5 +/- 0.2 18S2 7.2 +/- 1.5 7.1 +/- 0.7 6.5 +/- 1.7 8.0 +/- 0.8 7.9 +/- 1.0 19D1 6.6 +/- 1.0 6.5 + 0.7 6.2 +/- 0.4 7.2 +/- 1.0 7.0 +/- 0.8 20D1 6.3 +/- 0.8 6.6 + 0.5 5.8 +/- 0.5 6.4 +/- 0.8 6.2 +/- 0.4 20F1 6.6 +/- 0.6 6.7 + 0.8 6.3 +/- 1.3 6.9 +/- 0.5 7.2 +/- 0.9 21S2 6.8 +/- 1.7 6.5 +/- 0.8 6.1 +/- 0.6 7.7 +/- 0.6 6.7 +/- 0.4 23S2 6.3 +/- 1.2 5.8 +/- 0.3 6.2 +/- 0.3 7.0 + 0.9 6.8 +/- 1.0 24D1 6.4 +/- 0.9 6.5 + 0.7 5.9 +/- 1.1 6.8 +/- 0.8 5.9 +/- 0.4 25D1 5.9 +/- 0.7 6.0 + 1.0 5.5 +/- 0.8 6.2 +/- 0.7 6.1 +/- 0.8 25S2 6.0 +/- 0.7 5.9 + 0.8 5.7 +/- 0.7 6.4 +/- 1.0 6.1 +/- 1.1 26S3 5.9 +/- 1.2 5.5 + 0.6 5.7 +/- 0.6 6.6 + 0.7 6.4 +/- 0.7 28D2 6.2 +/- 1.3 6.1 + 0.4 5.6 +/- 0.4 6.9 +/- 0.4 6.6 +/- 0.6 29E1 6.9 +/- 1.1 6.5 +/- 1.0 (1) 7.3 + 0.9 6.7 +/- 0.5 29S1 6.3 +/- 1.3 6.7 +/- 1.9 5.6 +/- 0.4 6.7 +/- 0.4 6.6 +/- 0.8 31D1 8.0 +/- 1.9 8.6 + 1.2 6.9 +/- 0.5 8.4 + 1.3 8.4 +/- 0.6 31D2 6.8 +/- 1.2 6.6 +/- 0.6 6.3 +/- 0.3 7.5 + 0.3 7.3 +/- 0.6 31S1 7.1 +/- 1.6 7.2 +/- 1.4 6.3 +/- 0.6 7.9 +/- 0.7 7.5 +/- 0.5 34E1 6.5 +/- 1.4 6.2 +/- 0.5 6.0 +/- 0.9 7.3 +/- 0.4 7.1 +/- 0.4 34S2 7.0 +/- 0.8 6.9 +/- 0.8 6.6 +/- 0.5 7.4 +/- 1.0 7.8 +/- 0.8 36D1 6.3 +/- 0.8 5.9 +/- 0.7 6.2 +/- 0.7 6.7 +/- 0.7 6.5 +/- 0.7 36S2 7.6 +/- 0.8 7.7 +/- 0.6 7.1 +/- 0.7 7.9 +/- 0.6 7.2 +/- 0.3 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-17

TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, MIDDLE AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH +/- 2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION PERIOD SITE BOUNDARY

+/-2 S.D.

INTERMEDIATE CONTROL JAN-MAR APR-JUN JUL-SEP OCT-DEC 6.9 +/- 1.8 6.5 +/- 1.6 7.6 +/- 1.8 7.3 +/- 1.6 6.5 +/- 1.4 6.2 +/- 1.1 7.1 +/- 1.4 6.9 +/- 1.4 7.8 +/- 0.0 8.3 +/- 0.0 9.1 +/- 0.0 8.2 +/- 0.0 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH LOCATION SAMPLES PERIOD PERIOD ANALYZED MINIMUM MAXIMUM SITE BOUNDARY INTERMEDIATE CONTROL 64 91 4

5.5 4.9 7.8 9.8 8.6 9.1 PERIOD MEAN

+/-2 S.D.

7.1 +/- 1.9 6.7+/- 1.5 8.4+/- 1.1 SITE BOUNDARY STATIONS-10S3, 11S1, 13S2, 14S1, 18S2,21S2,23S2,25S2,26S3, 29S1, 31S1, 34S2, 36S2, 3S1, 5S1,7S1 INTERMEDIATE STATIONS - 10E1, 10F3, 13C1, 13E1, 15D1, 16F1, 17B1, 19D1, 20D1, 20F1, 24D1, 25D1, 28D2, 29E1, 2E1, 31D1, 31D2, 34E1, 36D1, 4E1, 6C1, 7E1,9C1 CONTROL STATIONS - 5H1 C-18

FIGURE C-1 MEAN MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2010 12 10

H--

I------

4 i:

I I

CONTROL

-*--INDICATOR.

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 08 09 10 11 Note: 2005 analysis changed from Insoluble & Soluble to Total Gross Beta YEAR LGS CRITICALITY UNIT NO. 1: 12/22/84 UNIT NO. 2: 08/11/89 LGS CHANGED TO TOTAL GROSS BETA AT THE BEGINNING OF 2005. PREVIOUS DATA INCLUDED SUMMATION OF LESS THAN VALUES.

C-19

FIGURE C-2 MEAN ANNUAL CS-137 CONCENTRATIONS IN FISH SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2010 6 5

-,---16C5 20S1 5 5 Note: Second half of 2000 45

""""switched to reporting < MDC

.Using MDC values result in a larger number. LLD < 150 35 pCi/kg.

LGS CRITICALITY UNIT NO. 1: 12/22/84 UNIT NO. 2: 08/11/89 --------

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

FIGURE C-3 CONCENTRATIONS OF CS-137 IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2010 1400

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

16C4 LGS CRITICALITY

33A2 UNIT NO. 1: 12/22/84 1000 UNIT NO. 2: 08/11/89 CONTROL =33A2 a

800.

E 2- 00 00

-200 82 83 85 86 88 89 91 92 94 95 97 98 00 01 03 04 06 07 09 10 Year C -21

FIGURE C-4 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2010 150

-u-Group I 135

--- Group II

.-- Group III 1 2 0.............

Chernobyl 105--

E 9 0

- - o-o - - - --

o LGS CRITICALITY 60 T UNIT NO. 1: 12/22184 C'?

UNIT NO. 2: 08/11/89 LU

L 4 5 0

i i

i 1

1 1

1 0-82 84 86 88 90 92 94 96 98 00 02 04 06 08 10 YEAR C - 22

p FIGURE C-5 MEAN WEEKLY GROSS BETA CONCENTRATIONS IN SAMPLES COLLECTED IN THE VICINITY OF 50

---GROUP I

GROUP II 40... GROUP III....................................

10 30................----........................................

0 I

10.)

0 AIR PARTICULATE LGS, 2010 3

6 9

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

C - 23

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

IN THE VICINITY OF LGS, 1985 - 2010 13 SITE 12

.INTERMEDIATE CONTROL

-- o-Control 51 1 0

11 9

8......---

4 I

I I

85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 00 01 02 03 04 05 06 07 08 09 10 11 YEAR NOTE: Control Station 5H1 became the only distant location beginning in 1995 0-24

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 Environmental, Inc (ENV).

Comparison of the results for most media was within expected ranges.

D-1

Intentionally Left Blank D-2

TABLE D-1.1 CONCENTRATIONS OF TOTAL GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 12/28/2009 02/01/2010 03/02/2010 03/30/2010 04/27/2010 06/01/2010 06/28/2010 08/03/2010 08/30/2010 09/28/2010 11/02/2010 11/29/2010 02/01/2010 03/02/2010 03/30/2010 04/27/2010 06/01/2010 06/28/2010 08/03/2010 08/30/2010 09/28/2010 11/02/2010 11/29/2010 12/27/2010 1.2 +/- 0.6 2.9 +/- 1.1

< 1.8

< 2.0 1.0 +/- 0.6 2.5 +/- 0.9 2.5 +/- 1.1 2.5 +/- 1.1 2.3 +/- 1.1 2.3 +/- 1.1 2.8 +/- 0.9 2.3 +/- 0.8 MEAN 2.2 +/- 1.2 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 12/28/2009 03/30/2010 06/28/2010 03/30/2010 06/28/2010 09/28/2010

< 138

< 168

< 154

< 144 09/28/2010 - 12/27/2010 MEAN D-3

TABLE D4.3 OONCNTRTIOSOFGAMVMABEiTFERS IN ORNNGV~ATBR SAANRE (X)LLB~ED IN11-E\\IOM1Ya UUCGEAlNS~C 2010 FIRLLS IN LNTS CF RJI/UTER+/- 2 SGvA SIC s-Ic QaLECT1QN RERCQD Ml-54 0>58 Fe-59 CD-6) 7n658 Z-9 W95-031 Cs-134 (33137 Ba-140 La-140 I

16C2 12MOxe OM/201O C928/2010 llC2/20io 11/29291o C2M2ia1i 03TJ2910 033Y2D1O 04/27/2910 6O1U/291O 062Y291 CBM20a10 c8'a2010 09W2910 11AC2'12o1 llrR2)1O 1227/2010

<3

<4

<2

<4

<3

<5

<3

<1

<3

<2

<3

<2

<4

<3

<6

<7

<5

<9

<6

<8

<7

<2

<7

<9

<5

<2

<3

<2

<3

<4

<2

<5

<4

<8

<5

<8

<4

<3

<7

<5

<6

<4

<3

<5

<7

<3

<7

<5

<4

<8

<6

<3

<4

<2

<4

<3

<4

<3

<4

<2

<3

<2

<5

<3

<4

<7

<6

<8

<4

<5

<4

<6

<3

<2

<5

<4

<3

<4

<3

<5

<3

<2

<3

<4

<3

<4

<3

<2

<17

<2

<12

<2

<11

<2

<11

<2

< 19

<4

< 14

<2

< 16

<3

<12

<1

< 14

<2

<19

<1

< 14

<3

<16

<1 LVAN D-4 S

" ql

TABLE 0-11.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA COLLECTION 11IS2 PERIOD 12/28/09

-01/04/10 17

+/- 4 01/04/10

-01/11/10 17

+/- 4 01/11/10

-01/18/10 37

+/- 5 01/18/10

-01/26/10 18 +/- 4 01/26/10

-02/01/10 22

+/- 4 02/01/10

-02/08/10 24

+/- 4 02/08/10

-02/15/10 17 +/- 4 02/15/10

-02/22/10 12

+/- 4 02/22/10

-03/01/10 7 +/- 3 03/01/10

-03/08/10 22

+/- 4 03/08/10

-03/15/10 20 +/- 4 03/15/10

-03/22/10 27

+/- 4 03/22/10

-03/29/10 22 +/- 4 03/29/10

-04/05/10 13 +/- 3 04/05/10

-04/12/10 27 +/- 4 04/12/10

-04/19/10 19

+/- 4 04/19/10

-04/26/10 20 +/- 4 04/26/10

-05/03/10 19 +/- 4 05/03/10

-05/10/10 17 +/- 4 05/10/10

-05/17/10 15 +/- 4 05/17/10

-05/24/10 19 +/- 4 05/24/10

-06/01/10 16

+/- 4 06/01/10

-06/07/10 22 +/- 4 06/07/10

-06/14/10 17 +/- 4 06/14/10

-06/21/10 21 +/- 4 06/21/10

-06/28/10 28 +/- 4 06/28/10

-07/06/10 19 +/- 3 07/06/10

-07/12/10 31 +/- 5 07/12/10

-07/19/10 25 +/- 4 07/19/10

-07/26/10 29 +/- 4 07/26/10

-08/02/10 20 +/- 4 08/02/10

-08/09/10 23 +/- 4 08/09/10

-08/16/10 31

+/- 4 08/16/10

-08/23/10 25 +/- 4 08/23/10

-08/30/10 20 +/- 4 08/30/10

-09/06/10 29 +/- 4 09/06/10

-09/13/10 26 +/- 4 09/13/10

-09/20/10 25 +/- 5 09/20/10

-09/27/10 22 +/- 4 09/27/10

-10/04/10 12

+/- 4 10/04/10

-10/11/10 16

+/- 4 10/11/10

-10/18/10 25 +/- 4 10/18/10

-10/25/10 23 +/- 4 10/25/10

-11/01/10 12

+/- 4 11/01/10

-11/08/10 12

+/- 3 11/08/10

-11/15/10 24 +/- 4 11/15/10

-11/22/10 35 +/- 4 11/22/10

-11/29/10 30 +/- 4 11/29/10

-12/06/10 13 +/- 4 12/06/10

-12/13/10 17 +/- 4 12/13/10

-12/20/10 25 +/- 4 12/20/10

-12/27/10 15 +/- 4 12/27/10

-01/03/11 33 +/- 4 M EAN 21

+/- 13 D-5

TABLE D-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION Be-7 Mn-54 Co-58 Co-E PERIOD 11S2 12/28/2009 03/29/2010 83 +/- 13

< 0.5

< 0.6

< 0.

03/29/2010 06/28/2010 98 +/- 16

< 0.8

< 1.0

< 0.

06/28/2010 09/27/2010 88 +/- 16

< 0.9

< 1.0

< 0.

09/27/2010 01/03/2010 63 +/- 13

< 0.8

< 0.9

< 0.

WVEAN 83 +/- 29 50 Cs-134 Cs-137 3

8 4

4

<0.7

<0.8

<0.9

<0.5

< 1.2

<0.5

< 0.6 D-6

TABLE D-Ill. 1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION AND GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 19B1 01/12/10 04/06/10 07/13/10 10/05/10 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140

< 0.3

0.2

< 0.3

< 0.3 MEAN 10F4 01/12/10 04/06/10 07/13/10 10/05/10

< 0.3

0.2

< 0.2

< 0.3 1431 +/- 109 1385 +/- 112 1497 +/- 118 1513 +/- 109 1457 +/- 119 1389 +/- 107 1350 +/- 100 1426 +/- 108 1393 +/- 101 1389 +/- 62 1317 +/- 109 1380 +/- 111 1417 +/- 109 1380 +/- 106 1374 +/- 83

<3

<4

<2

<4

< 26

<13

<16

< 29

<5

<3

<5

<2

<3

<4

<5

<3

<4

<16

<19

< 22

< 39

<8

<6

<4

<6 MEAN 25C1 01/12/10 04/06/10 07/13/10 10/05/10

0.2

0.2

< 0.3

<4

<3

<4

<3

<4

<3

< 16

< 18

<17

< 35

<2

<4

<3

<3 MEAN D-7

FIGURE D-1 COMPARISON OF MONTHLY TOTAL GROSS BETA CONCENTRATIONS IN DRINKING WATER SAMPLES SPLIT BETWEEN ENVAND TBE, 2010 10 9

8 7

1~a,

'U C-,

0.

6 5

4 3

2 1

0 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov De(

MONTH D-8 b

)

,t" I

FIGURE D-2 COMPARISON OF WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM LGS COLLOCATED LOCATIONS 11S1 AND 11S2, 2010 50 40 30 20 10 lO 1

4 7

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

D-9

Intentionally Left Blank D-IO

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2010 (PAGE 1 OF 2)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

March 2010 E6978-396 E6979-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 89.3 pCi/L 13.8 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 65.2 241 388 157 150 143 202 146 247 177 211 304 142 131 119 162 110 217 145 80.2 E6981-396 E6980-396 E7132-396 E7133-396 AP Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi June 2010 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 82.0 pCi/L 15.8 92.8 12.7 74.0 261 361 178 158 143 207 137 254 183 185 255 125 ill 101 146 97 179 129 85.6 93.4 16.7 96.9 110 339 126 150 101 169 119 206 197 91.6 282 105 125 84.0 140 98.6 171 163 79.9 92.8 14.7 0.96 1.09 0.88 0.92 1.07 0.88 0.95 1.00 0.98 1.07 0.97 0.97 1.14 1.19 1.14 1.18 1.18 1.11 1.14 1.21 1.12 0.94 0.88 0.95 0.86 0.97 0.96 0.90 0.96 0.91 0.98 1.02 0.96 0.96 0.97 1.04 0.96 1.06 1.04 1.07 1.06 0.98 1.04 0.96 0.92 0.86 A

A A

W A

A A

A pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 83.5 107 325 114 144 92.3 165 121 197 190 88.4 292 101 132 87.3 150 105 168 170 76.4 E7135-396 E7134-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi September 2010 E7229-396 Milk Sr-89 Sr-90 pCi/L 85.0 pCi/L 12.6 E-1

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2010 (PAGE 2 OF 2)

Identification Reported Known Ratio (c)

Month/Year Number Matrix Nuclide Units Value (a)

Value (b)

TBE/Analytics Evaluation (d)

September 2010 E7230-396 E7232-396 Milk 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 80.2 130 235 83.2 95.1 77.3 121 96.4 216 172 122 228 79.9 93.8 71.5 113 73.8 186 163 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 94.1 130 234 93.0 94.5 73.7 119 91.1 204 171 119 214 85.3 86.7 67.6 110 83.6 187 157 59.9 98.0 13.5 0.85 1.00 1.00 0.89 1.01 1.05 1.02 1.06 1.06 1.01 1.03 1.07 0.94 1.08 1.06 1.03 0.88 0.99 1.04 1.04 0.95 1.00 December 2010 E7231-396 E7375-396 E7376-396 pCi/L 62.3 pCi/L 92.7 pCi/L 13.5 A

A A

A W

A A

4 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 87.9 not provided 389 137 172 84.3 120 134 162 284 96.9 by Analytics 456 157 186 90.2 120 131 174 301 0.91 for this study 0.85 0.87 0.92 0.93 1.00 1.02 0.93 0.94 E7378-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi not provided by Analytics for this study 387 365 1.06 135 126 1.07 157 149 1.05 73.6 72.3 1.02 88.7 96 0.92 127 105 1.21 151 139 1.09 249 241 1.03 December 2010 E7377-396 Charcoal 1-131 (a) Teledyne Brown Engineering reported result.

79.6 84.2 0.95 A

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

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

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

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

E-2

TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2010 (PAGE 1 OF 1)

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

Value (b)

Control Limits Evaluation (c)

May 2010 RAD-81 Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 Co-60 Zn-65 G r-A G r-B 1-131 H-3 Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 Co-60 Zn-65 G r-A Gr-8 1-131 H-3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCilL 64.4 37.8 66.4 66.43 137.33 83.33 177 26.37 28.77 26.27 12967 60.4 41.3 65.9 71.6 146 84.5 186 32.9 37.5 26.4 12400 48.6 - 68.2 30.4 - 47.4 54.9 - 72.5 58.4 - 78.8 131 - 163 76.0 - 95.3 167 -219 16.9 - 42.6 24.7 - 45.0 21.9 -31.1 10800 -13600 A

A A

November2010 RAD-83 77.8 39.3 70.3 39.9 117 53.5 11.0 35.1 35.5 27.9 68.5 43.0 68.9 43.2 123 53.4 102 42.3 36.6 27.5 55.8 - 76.7 31.7 - 49.3 57.5 - 75.8 34.5 - 47.5 111 - 138 48.1 - 61.3 91.8-122 21.9 -53.7 24.0 - 44.2 22.9 - 32.3 Note 1 A

A A

Note 2 A

A A

A pCi/L 13233 12900 11200 - 14200 (1)

Sr-89 rBE to known ratio oft. 14 fell within acceptable range oft 20%. No action required. NCR 10-09 (2) Zn-65 result of I I 1 was incorrectly reported as 11.0. No acton required. NCR 10-09 (a)

Teledyne Brown Engineering reported result.

(b) The ERA known value is equal to 100% of the paramete r present in the standard as determined by gravimetric and/or volumetric m eas urements made during standard preparation.

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

E-3

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

TELEDYNE BROWN ENGINEERING, 2010 (PAGE 1 OF2)

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

Value (b)

Range Evaluation (c)

March 2010 10-MaW 22 Water Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Water Gr-A Gr-B Bq/L Bq/L Bq/L Bq/L Bq/L Bq(L Bq/L B q/L

-0.0942 58.5 27.2 0.0226 104 26.6 0.1029 42.0 (1) 60.6 42.4 - 78.8 28.3 19.8 - 36.8 (1) 90.8 63.6 - 118.0 26.9 18.8 - 35.0 (1) 40.7 28.5 - 52.9 A

A A

A 10-GrW22 10-MaS22 10-RdF22 Bq/L 0.5173 0.676 0.00 - 1.352 Bq/L 3.98 3.09 1.55 -4.64 Soil Cs-1 34 Cs-1 37 Co-57 Cow60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sa mple Bq/sample Bq/sample Bq/sample Bq/sample 665 800 508 648 893 597 221

-4.97 1.81 1.70 0.0056 2.65 3.70 0.0523

-0.0627 733 779 522 622 849 559 288 513-953 545 -1013 365 -679 435-809 594 -1104 391 -727 202 -374 (1) 10-GrF22 10-RdV22 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Water Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Water Gr-A Gr-B 2.13 1.49 -2.77 1.53 1.07-1.99 (1) 2.473 1.731 - 3.215 3.02 2.11 -3.93 (1)

(1) 0.0427 0.00-0.854 1.29 0.65 - 1.94 Bq/sample 0.1533 Bq/sample 1.240 A

A A

A W

A A

A W

A A

A Bq/sample Bq/sa mp le Bq/sa mple Bq/sample Bq/sa mp le Bq/sample Bq/sample 4.48 3.43

-0.0117 3.55 0.007

-0.0002 8.12 4.39 3.06 3.27 7.10 September 2010 10-MaW 23 B q/L Bq/L B q/L B q/L Bq/L B q/L Bq/L Bq/L 27.1 41.8 33.2 26.5 500 0.024 8.10 30.8 31.4 44.2 36.0 28.3 453.4 8.3 31.0 3.07 - 5.71 2.14 - 3.98 (1) 2.29 - 4.25 (1)

(1) 4.97 - 9.23 22.0 - 40.8 30.9 - 57.5 25.2 - 46.8 19.8 -36.8 317.4 -589.4 (1) 5.8 -10.8 21.7 -40.3 0.58 - 3.26 2.20 - 6.59 10-GrW23 Bq/L 2.36 Bq/L 6.37 1.92 4.39 E-4

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

TELEDYNE BROWN ENGINEERING, 2010 (PAGE 2 OF 2)

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

Value (b)

Range Evaluation (c)

September 2010 10-MaS23 10-RdF23 Soil Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 837 680 2.78 350 853 721 2.24 287 2.31

-0.025 3.64 2.81 3.19 1.01 0.0310 10-GrF23 10-RdV23 AP Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A G r-B Vegetation Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 940 670 343 820 699 265 2.98 4.08 2.92 3.18 1.01 0.50 658 - 1 222 469 - 871 (1) 240 - 446 574 - 1 066 489 - 909 (1) 186 -345 2.09 - 3.87 (1) 2.86 - 5.38 2.04 - 3.80 2.23-4.13 0.71 - 1.31 (1)

(1) 0.25 - 0.75 A

-A A

A A

A W

A A

Bq/sample 0.004 Bq/sample 0.473 A

A Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sa mp le 4.90 6.78 10.2 0.00 7.36 2.53 6.40 4.79 3.35 - 6.23 5.88 4.12 - 7.64 8.27 5.79 - 1 0.75 (1) 6.287 4.401 - 8.173 2.63 1.84 - 3.42 5.3900 3.77 - 7.01 A

A W

A A

(1) False positive test.

(a) Teledyne Brown Engineering reported result (b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.

(c) DOEIMAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.

E-5

TABLE E-4 ERA STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM8 ENVIRONMENTAL, INC., 2010 (Page l of 1)

Lab Code Date Analysis Laboratory Resultb Concentration (pCiL)

ERA Resultc Control Limits Acceptance STW -1205 STW -1205 STW -1206 STW -1206 STW -1206 STW -1206 STW -1206 04/05110 04/05/10 04/05/10 04/05/10 04/05/10 04105/10 04/05/10 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 STW-1207 04/05/10 Gr. Alpha STW -1207 04/05/10 Gr. Beta STW-1208 04/05/10 1-131 STW-1209 STW -1209 STW-1209 STW-1210 04/05/10 04/05/10 04/05/10 04/05/10 Ra-226 Ra-228 Uranium H-3 63.0 +/- 5.7 37.4 +/- 2.4 63.6 +/- 3.3 83.3 +/- 2.9 71.0 +/- 3.4 145.5 +/- 5.1 194.9 +/- 7.8 26.5 +/- 1.7 34.5 +/- 1.6 22.7 +/- 0.8 15.2 +/- 0.7 15.6 +/- 1.8 59.5 +/- 0.7 12955 +/- 332 65.3 +/- 5.7 39.9 +/- 2.3 67.2 +/- 4.3 53.2 +/- 3.3 47.3 +/- 5.1 118.0 +/- 5.9 107.0 +/- 8.7 30.7 +/- 2.9 32.7 +/- 0.8 28.6 +/- 1.1 11.8 +/- 0.6 12.0 +/- 1.8 34.8 +/- 0.4 13682 +/- 352 60.4 41.3 65.9 84.5 71.6 146.0 186.0 32.9 37.5 26.4 48.6 30.4 54.9 76.0 58.4 131.0 167.0

-68.2

-47.4

- 72.5

-95.3

-78.8

-163.0

-219.0 16.9 -42.6 24.7 -45.0 21.9 -31.1 STW-1224 10/04/10 Sr-89 STW -1224 10/04/10 Sr-90 14.6 15.1 62.3 12400.0 68.5 43.0 68.9 53.4 43.2 123.0 102.0 10.9 - 16.8 10.1 - 18.3 50.7 -69.1 10800 - 13600 55.8 - 76.7 31.7 -49.3 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1225 STW-1225 STW -1 225 STW -1225 STW -1 225 10/04/10 10/04/10 10/04/10 10/04/10 10/04/10 Ba-1 33 Co-60 Cs-1 34 Cs -137 Zn-65 57.5 48.1 34.5 111.0 91.8

- 75.8

-61.3

-47.5

- 138.0

-122.0 STW-1226 10/04/10 Gr. Alpha STW -1226 10/04/10 Gr. Beta STW-1227 10/04/10 1-131 42.3 36.6 27.5 21.9 -53.7 24.0 -44.2 22.9 -32.3 STW -1228 STW -1228 STW -1 228 STW -1 229 10/04/10 10/04/10 10/04/10 10/04/10 Ra-226 Ra-228 Uranium H-3 11.4 9.9 36.8 12900.0 8.5 -13.2 6.4 -12.3 29.8 -41.0 11200 - 14200 Pass Pass Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

E-6

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2010 (Page 1 of 3)

Concentration b Laboratory Known Control Lab Code c Date Analysis Result Activity Limits d Acceptance STVE-1199 STVE-1199 STVE-1199 STVE-1199 STVE-1199 STVE-1 199 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 0.01 +/- 0.03 3.39 +/-0.12 4.74 +/- 0.15 3.32 +/- 0.17 0.01 +/- 0.05 8.03 +/- 0.33 0.40 +/- 0.05 3.03 +/- 0.07 0.00 3.27 4.39 3.06 0.00 7.10 0.68 3.09 2.29 -4.25 3.07 -5.71 2.14 -3.98 4.97 -9.23 0.00 -1.35 1.55 -4.64 STW-1200 03/01/10 Gr. Alpha STW-1200 03/01/10 Gr. Beta STW -1201 STW -1201 STW -1201 STW -1201 STW -1201 STW -1201 STW -1201 STW -1201 STW-1201 STW-1201 STW -1201 STW -1201 STW-1201 STW-1201 STSO-1 202 STSO-1 202 STSO-1 202 STSO-1 202 STSO-1 202 STSO-1 202 STSO-1 202 STSO-1 202 STSO-1 202 STSO-1 202 STAP-1 203 STAP-1 203 STAP-1203 STAP-1203 STAP-1 203 STAP-1 203 STAP-1 203 STAP-1 203 03/01/10 03/01/10 03/01/10 03/01/1.0 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 Am-241 Co-57 Co-60 Cs-134 Cs-137 Fe-55 H-3 Mn-54 Ni-63 Sr-90 Tc-99 U-233/4 U-238 Zn-65 Co-57 Co-60 Cs-1 34 Cs -137 K-40 Mn-54 Sr-90 U-233/4 U-238 Zn-65 Am-241 Co-57 Co-60 Cs-1 34 Cs -137 Mn-54 Sr-90 Zn-65 1.05 +/- 0.08 28.90 +/- 0.40 0.06 +/- 0.05

-0.03 +/- 0.09 60.60 +/- 0.60 3.00 +/- 14.40 93.20 +/- 18.30 27.80 +/- 0.40 49.10 +/- 3.50

-0.10 +/- 0.60 0.50 +/- 0.50 1.21 +/- 0.05 1.20 +/- 0.05 42.70 +/- 0.80 520.00 +/- 10.80 599.10 +/-2.80 666.10 +/- 4.70 774.40 +/- 4.50 562.00 +/- 15.30 866.20 +/- 4.60 225.50 +/- 11.80 59.90 +/- 2.50 62.10 +/- 2.60

-1.23 +/- 1.96 0.10 +/- 0.01 0.01 +/- 0.02 2.63 +/- 0.19 2.21 +/- 0.34 1.66 +/- 0.22 3.42 +/- 0.26 0.02 +/- 0.06

-0.05 +/- 0.11 1.30 28.30 0.00 0.00 60.60 0.00 90.80 26.90 59.90 0.00 0.00 1.22 1.25 40.70 522.00 622.00 733.00 779.00 559.00 849.00 288.00 60.00 64.00 0.00 0.15 0.00 2.47 2.13 1.53 3.02 0.00 0.00 0.91 -1.69 19.80 -36.80 42.40 -78.80 63.60 -118.00 18.80 -35.00 41.90 -77.90 0.85 -1.59 0.88 -1.63 28.50 -52.90 365.00 -679.00 435.00 - 809.00 513.00 -953.00 545.00 - 1013.00 391.00 -727.00 594.00 - 1104.00 202.00 - 374.00 42.00 -78.00 45.00 - 83.00 0.10 -0.19 1.73 -3.22 1.49 -2.77 1.07 -1.99 2.11 -3.93 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass E-7

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2010 (Page 2 of 3)

Laboratory Lab Code c STAP-1 204 STAP-1 204 Concentration b Known Activity 043 1.29 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 Date 03/01/10 03/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 Analysis Gr. Alpha Gr. Beta Result 0.13 +/-0.03 1.46 +/- 0.07 Control Limits d 0.00 -0.85 0.65 -1.94 Acceptance Pass Pass Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Fe-55 H-3 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 STW-1212 08/01/10 Gr. Alpha STW-1212 08/01/10 Gr. Beta 0.02 +/- 0.02 36.40 +/- 4.80 28.30 +/- 1.00 29.30 +/- 2.10 44.60 +/- 1.80 48.50 +/- 20.10 503.60 +/- 12.80 38.50 +/- 2.50 0.10 +/- 0.30 49.30 +/- 3.10 1.49 +/- 0.15 1.20 +/- 0.10 9.20 +/- 1.30 28.10 +/- 0.90 2.04 +/- 0.14 2.05 +/- 0.14 32.80 +/- 3.00 1.54 +/- 0.09 4.13 +/- 0.15 9.60 +/- 0.54 0.05 +/- 0.08 4.83 +/- 0.26 6.45 +/- 0.66 7.12 +/- 0.66 6.05 +/- 0.74 0.10 +/- 1.60 370.00 +/- 6.00 1005.00 +/- 21.00 755.00 +/- 15.00 783.00 +/- 54.00 942.00 +/- 15.00 69.20 +/- 6.20 76.50 +/- 6.20 3.50 +/- 8.00 76.50 +/- 6.20 271.40 +/- 9.00 310.00 +/- 18.00 0.00 36.00 28.30 31.40 44.20 60.20 453.40 38.90 0.00 56.10 1.81 1.35 8.30 33.60 2.01 2.07 31.00 1.92 4.39 8.27 0.00 4.79 5.88 629 5.39 0.00 343.00 940.00 670.00 699.00 820.00 64.00 71.00 0.00 71.00 289.00 265.00 25.20 -46.80 19.80 -36.80 22.00 -40.80 30.90 -57.50 42.10 -78.30 317.40 - 589.40 27.20 - 50.60 39.30 -72.90 1.27 -2.35 0.95 -1.76 5.80 -10.80 23.50 -43.70 1.41 -2.61 1.45 -2.69 21.70 -40.30 0.58 -3.26 2.20 -6.59 5.79 -10.75 3.35 -6.23 4.12 -7.64 4.40 -8.17 3.77 -7.01 240.00 - 446.00 658.00 - 1222.00 469.00 -871.00 489.00 - 909.00 574.00 - 1066.00 45.00 - 83.00 50.00 -92.00 50.00 -92.00 202.00 -376.00 186.00 - 345.00 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STVE-1 213 STVE-1 213 STVE-1 213 STVE-1 213 STVE-1 213 STVE-1 213 STSO-1 214 STSO-1 214 STSO-1 214 STSO-1 214 STSO-1 214 STSO-1 214 STSO-1 214 STSO-1 214 STSO-1 214 STSO-1 214 STSO-1 214 STSO-1 214 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 E-8

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2010 (Page 3 of 3)

Concentration b Laboratory Known Control Lab Code c Date Analysis Result Activity Limits d Acceptance STAP-1 215 STAP-1 215 STAP-1 215 STAP-1 215 STAP-1 215 STAP-1 215 STAP-1 215 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Sr-90 Zn-65 4.47 +/- 021 3.15 +/- 0.30 3.03 +/- 0.17 0.01 +/- 0.05 3.69 +/- 0.39 1.00 +/- 0.12 0.03 +/- 0.15 0.01 +/- 0.01 0.54 +/- 0.05 4.08 2.92 2.98 0.00 3.18 1.01 0.00 0.00 0.50 2.86 -5.30 2.04 -3.80 2.09 -3.87 2.23 -4.13 0.71 -1.31 0.25 -0.75 Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1216 08/01/10 Gr. Alpha STAP-1216 08/01/10 Gr. Beta 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 0 Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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, I determination) and control limits as defined by the MAPEP.

E-9

Intentionally Left Blank E - 10

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 2010 Prepared By Teledyne Brown Engineering Environmental Services Exeln.

Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2011

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

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

3 A. O bjectives of the RG PP...................................................................................

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

3 C. Program Description.........................................................................................

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

5 I1l. Program Description.....................................................................................................

6 A. Sam ple Analysis................................................................................................

6 B. Data Interpretation...........................................................................................

6 C. Background Analysis.........................................................................................

7

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

8 IV. Results and Discussions...........................................................................................

10 A. Groundwater Results......................................................................................

10 B. Surface W ater Results....................................................................................

11 C. Drinking W ater W ell Survey............................................................................

12 D. Summary of Results - Inter-laboratory Comparison Program.......................

12 E. Leaks, Spills, and Releases............................................................................

12 F. Trends..............................................................................................................

12 G. Investigations..................................................................................................

13 H. Actions Taken..................................................................................................

13 V. References......................................................................................................................

13

Appendices Appendix A Tables Table A-1 Location Designation Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2010 Figures Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2010 Appendix B Tables Table B-1.1 Data Tables Table B-1.2 Table B-1.3 Table B-11.1 Table B-11.2 Concentrations of Tritium, Strontium-90, Gross Alpha and Gross Beta in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2010.

Concentrations of Gamma Emitters in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2010.

Concentrations of Hard-To-Detects in Well Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2010.

Concentrations of Tritium, Strontium-90, Gross Alpha and Gross Beta in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2010.

Concentrations of Gamma Emitters in Surface Water Samples Collected as Part of the Radiological Groundwater Protection Program, Limerick Generating Station, 2010.

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 2010 through 31 December 2010. During that time period, 481 analyses were performed on 76 samples from 15 groundwater and 7 surface water locations collected from the environment, both on and off station property in 2010.

There were no spills that could affect the ground water monitoring program in 2010.

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 two of the 15 groundwater monitoring locations. The tritium concentrations ranged from 238 to 1,320 pCi/L.

Strontium-90 was not detected in either the groundwater or surface water samples.

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions performed on groundwater surface water samples during the second sampling in 2010. Gross Alpha (dissolved) was detected at 5 of 15 groundwater locations.

The concentrations ranged from 2.9 to 6.2 pCi/L. Gross Alpha (suspended) was detected at 8 of 15 groundwater and 2 of 7 surface water locations. The concentrations ranged from 1.1 to 60.0 pCi/L. Gross Beta (dissolved) was detected at 14 of 15 groundwater and all 7 surface water locations. The concentrations ranged from 2.1 to 38.5 pCi/L. Gross Beta (suspended) was detected at 11 of 15 groundwater and 5 of 7 locations. The concentrations ranged from 1.7 to 124.0 pCi/L.

Gamma-emitting radionuclides associated with licensed plant operations were not detected in either groundwater or surface water samples.

Hard-To-Detect analyses were performed on a select group of groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-233/234, U-235 and U-238. The isotopes of U-233/234, and U-238 were detected at four of six groundwater monitoring locations. The U-233/234 concentrations ranged from 1.4 to 2.7 pCi/L and the U-238 concentrations ranged from 0.8 to 1.2 pCi/L. The levels detected are considered background.

All other hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs.

1

Although no drinking water pathway is available from groundwater, the dose via the drinking water pathway was calculated at 0.08 mrem to a child (total body),

which was 1.30% of the 10 CFR 50, Appendix I dose limit.

In assessing all the data gathered for this report, it was concluded that the operation of Limerick Generating Station had no adverse radiological impact on the environment offsite of LGS.

2

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.

This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2010.

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

A.

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

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

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

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

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

5. Regularly assess analytical results to identify adverse trends.

6. Take necessary corrective actions to protect groundwater resources.

B.

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

1.

Exelon and its consultant identified locations as described in the 2006 Phase 1 study. The Phase 1 study results and conclusions 3

were made available to state and federal regulators in station specific reports.

2.

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

3.

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

4.

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

5.

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

C.

Program Description Samples for the ongoing ground water monitoring program were collected for Exelon Nuclear by Normandeau Associates, Inc. (NAI). This section describes the general collection methods used to obtain environmental samples for the LGS RGPP in 2010. Sample locations can be found in Table A-i, Appendix A.

1.

Sample Collection Groundwater and Surface Water Samples of both groundwater and surface water were collected, managed, transported and analyzed in accordance with approved procedures following EPA methods. Sample locations, sample collection frequencies and analytical frequencies were controlled in accordance with approved station procedures. Contractor and/or station personnel were trained in the collection, preservation A

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.

4

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

D.

Characteristics of Tritium (H-3)

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

Tritiated water behaves the same as ordinary water in both the environment and the body. Tritium can be taken into the body by drinking water, breathing air, eating food, or absorption through skin. Once tritium enters the body, it disperses quickly and is uniformly distributed throughout 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.

5

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 2010.

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

1.

Concentrations of tritium in groundwater and surface water.

2.

Concentrations of Gross Alpha, Dissolved and Suspended and Gross Beta, Dissolved and Suspended in groundwater and surface water.

3.

Concentrations of gamma emitters in groundwater and surface water.

4.

Concentrations of strontium in groundwater and surface water.

5.

Concentrations of Am-241 in groundwater.

6.

Concentrations of Cm-242 and Cm-243/244 in groundwater.

7.

Concentrations of Pu-238 and PU-239/240 in groundwater.

8.

Concentrations of U-233/234, U-235 and U-238 in groundwater.

9.

Concentrations of Fe-55 in groundwater.

10.

Concentrations of Ni-63 in groundwater.

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 6

5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD is intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criterion for the presence of activity. All analyses were designed to achieve the required LGS detection capabilities for environmental sample analysis.

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

2.

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

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

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

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

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.

7

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

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

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

1.

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

a.

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

A major anthropogenic source of tritium and strontium-90 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 8

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

c.

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

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

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

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

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

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

9

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 1,320 pCi/L. Well MW-LR-9 had the highest value of 1,320 pCi/L. Although no drinking water pathway is available from groundwater, the theoretical dose via the drinking water pathway was calculated at 0.08 mrem to a child (total body), which represents 1.30% of the 10 CFR 50, Appendix I dose limit of 6 mrem.

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

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater surface water samples during the second sampling in 2010. Gross Alpha (dissolved) was detected in 5 of 15 groundwater locations. The concentrations ranged from 2.9 to 6.2 pCi/L. Gross Alpha (suspended) was detected in 8 of 15 groundwater locations. The concentrations ranged from 1.1 to 60.0 pCi/L. Gross Beta (dissolved) was detected in 14 of 15 groundwater locations. The concentrations ranged from 2.1 to 38.5 pCi/L. Gross Beta (suspended) was detected in 11 of 15 groundwater locations. The concentrations ranged from 1.7 to 124.0 pCi/L (Table B-1.1, Appendix B).

Gamma Emitters Potassium-40 was detected at four of 15 groundwater locations with a range of 77 to 136 pCi/L. No other gamma emitting nuclides were detected (Table B-1.2, Appendix B).

10

Hard-To-Detect Hard-To-Detect analyses were performed on a select group of groundwater locations to establish background levels. The analyses included Fe-55, Ni-63, Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240, U-233/234, U-235 and U-238. The isotopes of U-233/234 and U-238 were detected at four of six groundwater monitoring locations. The U-233/234 concentrations ranged from 1.4 to 2.7 pCi/L and the U-238 concentrations ranged from 0.8 to 1.2 pCi/L (Table B-1.3, Appendix B).

The concentrations detected are considered background.

All other hard-to-detect nuclides were not detected at concentrations greater than their respective MDCs.

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 nine locations were analyzed for tritium activity. Tritium activity was detected in station SW-LR-8 at a concentration of 196 pCi/Liter (Table B-11.1, Appendix B).

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

Gross Alpha and Gross Beta (dissolved and suspended)

Gross Alpha and Gross Beta analyses in the dissolved and suspended fractions were performed on surface water samples during the second sampling in 2010. Gross Alpha (dissolved) was not detected in any surface water locations. Gross Alpha (suspended) was detected at 2 of 7 surface water locations. The concentration ranged from 1.3 to 1.9 pCi/L.

Gross Beta (dissolved) was detected at all surface water locations. The concentrations ranged from 2.6 to 25.7 pCi/L. Gross Beta (suspended) was detected at 5 of 7 surface water location. The concentration ranged from 1.8 to 6.5 pCi/L (Table B-11.1, Appendix B).

11

Gamma Emitters No gamma emitting nuclides were detected (Table B-I1.2, Appendix B).

C.

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

The Station has one potable supply well and one fire water well. The potable supply well is constructed as an open-rock borehole. Groundwater was measured at a depth 102 feet bgs during a well pump replacement in 2004 (personal communication with Station, 2006). The pump was placed at a depth of approximately 294 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located approximately 175 feet east of the Reactor Building. The Station estimates that the well is pumped at approximately 2 gpm. The fire water well is constructed as an open-rock borehole. Groundwater was encountered at 121 feet bgs during a well pump replacement in 2004. The well pump was placed at a depth of approximately 399 feet bgs. The total well depth and the depth of the steel casing are unknown. The well is located approximately 500 feet east of the cooling towers. The well is used only in an emergency fire situation; therefore, water use is estimated to be zero.

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 There were no leaks, spills or releases to the ground that could impact the ground water.

F.

Trends Well MW-LR-9 tritium concentration levels continue to decrease from the levels observed from the 2009 leak.

12

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 2010

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.

13

Intentionally Left Blank

APPENDIX A LOCATION DESIGNATION

TABLE A-1:

Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2010 Location MW-LR-1 MW-LR-2 MW-LR-3 MW-LR-4 MW-LR-5 MW-LR-6 MW-LR-7 MW-LR-8 MW-LR-9 P11 P14 P16 P17 P3 SP22 Type Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Surface Water Distance Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite Onsite SW-LR-2 SW-LR-4 SW-LR-6 SW-LR-7 SW-LR-8 (Hold Pond)

SW-LR-9 (Spray Pond)

SW-LR-1 0 Offsite Offsite Offsite Onsite Onsite Onsite Onsite A-1

Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2010 A-2

APPENDIX B DATA TABLES

TABLE B-1.1 CONCENTRATIONS OF TRITIUM, STRONTIUM-90, GROSS ALPHA AND GROSS BETA IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-LR-1 MW-LR-1 MW-LR-1 MW-LR-2 MW-LR-2 MW-LR-2 MW-LR-3 MW-LR-3 MW-LR-3 MW-LR-3 MW-LR-4 MW-LR-4 MW-LR-4 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-6 MW-LR-6 MW-LR-6 MW-LR-7 MW-LR-7 MW-LR-7 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-8 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 Pll P11 P1l P1l P1l P14 P14 P14 P16 P16 P16 P17 P17 P17 COLLECTION DATE 05/04/2010 08/11/2010 10/19/2010 05/05/2010 08/13/2010 10/19/2010 05/05/2010 05/05/2010 08/13/2010 10/20/2010 05/04/2010 08/13/2010 10/20/2010 05/05/2010 08/13/2010 08/13/2010 10/19/2010 05/05/2010 08/13/2010 10/19/2010 05/05/2010 08/13/2010 10/19/2010 05/04/2010 08/10/2010 10/19/2010 10/19/2010 01/12/2010 05/04/2010 05/04/2010 08/10/2010 08/10/2010 10/19/2010 10/19/2010 05/04/2010 08/10/2010 08/10/2010 10/19/2010 10/19/2010 05/04/2010 08/11/2010 10/19/2010 05/05/2010 08/10/2010 10/19/2010 05/04/2010 08/11/2010 10/19/2010

172

180

179

< 173

178

176

< 174

175

177

< 171

< 175

176

< 178

177

< 173

< 181

< 180

177

176 24 24 23

< 178 132 96 79

< 179 30 45 54

< 173

< 178

< 170

< 168

< 171

< 173

< 170

< 173

< 172

< 170

< 169

< 168

< 176 H-3 SR-90 GR-A (DIS)

< 3.9

< 0.6 2.9 + 1.9

< 2.0

< 2.5

< 0.8

< 2.7

< 2.3

< 3.0

< 0.8

< 2.6

< 2.0

< 3.3

< 0.5

< 3.1

< 2.6 3.1 +/- 2.0

< 0.8

< 2.6

< 0.7

< 2.8 6.2 +/- 2.1

< 0.5

< 2.5

< 2.3

< 2.2

< 0.9

< 2.0

< 1.1 3 +/- 119

< 3.4 5 +/- 115

< 0.6

< 2.8 8 +/- 117

< 2.4

< 2.5 0 +/- 180 (1) 4 +/- 162 3.1 +/- 1.9 3 +/- 145

< 2.3

< 0.8

< 2.8 8 +/- 118

< 0.7

< 2.9 55 +/- 127 4.0 +/- 1.9 7 +/- 126

< 2.3

< 3.8

< 0.7

< 3.5

< 0.5

< 3.2

< 2.3

< 3.8

< 0.6

< 3.6

< 3.1

< 8.7 (2)

< 5.2

< 2.4

< 0.6

< 2.5

< 2.0 GR-A (SUS)

< 0.9

< 2.2

< 1.5 1.3 +/- 0.7 1.3 +/- 0.9

< 1.5 1.5 +/- 0.9

< 0.6 1.7 +/- 1.0

< 1.4

< 0.6

< 0.9

< 1.5 2.7 +/- 1.0

< 1.0

< 0.9

< 1.5 1.6 +/- 0.8 3.6 +/- 1.3

< 1.7

< 0.6

< 1.0

< 4.0

< 0.6

< 0.9

< 1.4

< 1.4 (1)

< 3.5 11 +/- 4.9

< 1.0

< 1.8

< 3.4 4.4 +/- 2.6 1.1 +/- 0.7

< 0.9

< 1.4

< 1.5 12 +/- 4.1 19 +6.4 12 + 5.5 60 +/- 10.4 (2) 35 +/- 8.0

< 0.5

< 0.9

< 1.4 GR-B (DIS) 14 +/- 3.8 39 +/- 1.9 8.0 +/- 2.9 3.6 +/- 1.9 3.9 +/- 2.2

< 3.1 5.1 +/- 2.3 6.0 +/- 2.5

< 3.2 5.8 +/- 2.7 7.1 +/- 2.9

< 3.9 5.4 +/- 3.0 5.6 +/- 2.1 12 +/- 2.8 9.2 +/- 2.5

< 3.7 2.1 +/- 1.1 4.5 +/- 2.5 3.7 +/- 2.2 3.6 +/- 1.7 2.7 +/- 1.7 14 +/- 2.4 5.3 +/- 2.8

< 3.8 3.7 +/- 1.2 5.2 +/- 1.3 GR-B (SUS) 3.8 +/- 1.4

< 3.2

< 1.8

< 1.6 2.2 +/- 1.2 2.4 +/- 1.3 11 +/- 1.7

< 1.6 3.3 +/- 1.3

< 1.8

< 1.6

< 1.7

< 1.8 4.1 +/- 1.3 3.3 +/- 1.3 2.0 +/-1.2

< 1.8 1.9 +/-1.1 4.9 +/-1.4

< 2.0

< 1.6

< 1.7

< 2.6 7.2 5.6 9.2 6.9 6.0 6.2 19

< 4.0 14 15 13 5.3

< 4.0 4.3 18 16

< 3.6

< 3.4

< 3.8 (1)

+/- 2.5

+/- 2.3

+/- 2.5

+/- 2.3

+/- 2.2

+/- 2.3

+/- 4.2

+/- 3.4

+/- 3.5

+/- 3.4

+/- 3.2

+/- 1.6

+/- 8.0 (2)

+/- 6.4 1.9 +/- 1.1 1.7 +/- 1.1

< 1.8

< 1.8 (1)

< 2.6 24 +/- 3.0

< 1.7 8.9 +/- 1.9 3.1 +/- 1.7 10 +/- 2.1 1.8 +/- 1.1 2.8 +/- 1.2

< 1.6

< 1.8

< 1.8 32 +/- 3.2 28 +/- 3.2 28 +/- 3.6 124 +/- 9.3 (2) 74 +/- 6.4

< 1.5

< 1.6

< 1.8 (1) Analyses not added until May 2010 (2) Gross Alpha and Gross Beta analyses could not be performed due to low sample volume Samples are distilled for H-3 analysis B-1

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM-90, GROSS ALPHA AND GROSS BETA IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION SITE DATE H-3 SR-90 GR-A (DIS)

GR-A (SUS)

GR-B (DIS)

GR-B (SUS)

P3 P3 P3 SP22 SP22 SP22 05/04/2010 08/11/2010 10/19/2010 05/04/2010 08/11/2010 10/19/2010

< 168

< 171

< 177

< 171

< 177

< 172

< 2.3

< 0.7

< 2.8

< 0.5

< 0.9 8.4 +/- 2.5

< 1.5

< 3.0

< 3.2

< 1.6

< 1.8 4.0 +/- 2.0

< 1.4

< 2.4

< 0.5 5.8 +/- 2.4

< 0.9

< 0.9 6.7 +/- 2.8

< 1.5 4.9 +/- 2.7 3.3 +/- 1.2 7.7 +/- 1.4

< 1.8

< 2.3

< 1.4 Samples are distilled for H-3 analysis A

B-2

Q TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC MW-LR-1 MW-LR-2 MW-LR-3 MW-LR-4 MW-LR-5 MW-LR-5 MW-LR-6 MW-LR-7 MW-LR-8 MW-LR-9 MW-LR-9 Pl1 P1l P14 P16 P17 P3 SP-22 COLLECTION Be-7 PERIOD 08/11/2010

< 46 08/13/2010

< 45 08/13/2010

< 47 08/13/2010

< 44 08/13/2010

< 52 08/13/2010

< 50 08/13/2010

< 65 08/13/2010

< 52 08/10/2010

< 34 08/10/2010

< 39 08/10/2010

< 41 08/10/2010

< 39 08/10/2010

< 43 08/11/2010

< 60 08/10/2010

< 52 08/11/2010

< 51 08/11/2010

< 43 08/11/2010

< 42 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-140 133 +/- 48 < 4

<47

<5

<50

<5

< 110

< 5 77 +/- 49 < 4

<46

<4

<65

<7

<94

<6

<54

<4

<82

<4

<41

<4

<77

<4

<32

<4 136 +/- 66 < 7

<41

<5 124 +/- 54 < 5

<79

<5

<37

<4

<5

<6

<5

<6

<4

<5

<7

<3

<4

<5

<4

< 10

< 12

< 10

< 11

< 15

< 12

<7

<9

<8

<9

< 13

< 12

< 11

< 10

<8

<5

<4

<5

<9

<4

<5

<7

<6

<4

<3

<7

<5

<6

<4

< 10

< 11

<8

< 13

< 12

<8

< 15

< 13

<7

<8

<9

< 10

<9

<5

<6

<5

<6

< 10

<7

<4

<5

<7

<6

<5

<7

<5

<8

<9

< 10

<8

<9

< 13

< 11

<6

<9

<8

<7

<8

<9

< 10

<8

<9

<8

< 13

< 12

< 11

< 13

< 15

< 14

<7

< 14

< 10

< 14

< 11

< 12

< 14

< 10

< 13

<5

<6

<7

<3

<4

<7

<6

<5

<7

<4

<5

<4

<6

<5

<6

<5

<4

< 31

< 34

< 29

< 30

< 29

< 33

< 36

< 21

< 30

< 23

< 30

< 29

< 32

< 33

< 28

< 29

<8

< 12

< 10

<9

< 10

< 12

<9

<7

<8

<9

<8

< 13

<9

<8

<7

<8 B-3

TABLE B-I.3 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC MW-LR-1 MW-LR-3 MW-LR-7 MW-LR-8 P-17 P-3 COLLECTION PERIOD 05/04/2010 05/05/2010 05/05/2010 05/04/2010 05/04/2010 05/04/2010 AM-241 CM-242 CM-243/244 PU-238 PU-239/240 U-233/234 U-235 U-238 FE-55 N 1-63

< 0.1

< 0.2

< 0.1

< 0.2

< 0.13

< 0.10

< 0.08

< 0.05

< 0.07

< 0.15

< 0.11

< 0.10

< 0.07

< 0.02

< 0.11

< 0.03

< 0.2

< 0.1

< 0.2

< 0.1

< 0.1 2.7 + 0.4

< 0.2 2.1 + 0.3 1.4 + 0.3 2.5 + 0.4 0.06 0.04 0.07 0.04 0.06 0.02

< 0.1 0.9 +/- 0.2

<0.1 0.8 +/- 0.2 0.9 +/- 0.2

.1.2

+/- 0.2

< 75

< 141

< 78

< 72

< 146

179

< 4.2

< 4.3

< 3.9

< 4.2

< 4.2 B-4 IJ p

I t,

t

TABLE B-1I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM-90, GROSS ALPHA AND GROSS BETA IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE SW-LR-2 SW-LR-2 SW-LR-2 SW-LR-4 SW-LR-4 SW-LR-4 SW-LR-6 SW-LR-6 SW-LR-6 SW-LR-7 SW-LR-7 SW-LR-7 SW-LR-8 SW-LR-8 SW-LR-8 SW-LR-9 SW-LR-9 SW-LR-9 SW-LR-10 SW-LR-10 SW-LR-10 SW-LR-10 COLLECTION DATE 05/03/2010 08/12/2010 10/18/2010 05/04/2010 08/12/2010 10/18/2010 05/03/2010 08/12/2010 10/18/2010 05/03/2010 08/12/2010 10/18/2010 05/05/2010 08/11/2010 10/20/2010 05/05/2010 08/11/2010 10/20/2010 05/04/2010 05/04/2010 08/12/2010 10/18/2010

< 172

< 180

< 171

< 170

< 174

< 171

< 176

< 179

< 171

< 172

< 170

< 171

< 171 19(

< 175

< 172

< 170

< 171

< 172

< 181

< 168 H-3 SR-90 GR-A (DIS)

< 1.2

< 0.5

< 2.7

< 1.3

< 1.1

< 0.8

< 2.1

< 1.3

< 1.4

< 0.6

< 2.8

< 1.4

< 1.6

< 0.6

< 2.8

< 1.5

< 2.3

< 0.5

< 2.5

+ 114

< 2.1

< 2.3

< 0.5

< 2.9

< 2.2

< 2.3

< 2.2

< 0.7

< 2.7

< 1.7 GR-A (SUS)

GR-B (DIS)

GR-B (SUS) 1.9 +/- 1.1

< 0.9

< 1.5

< 0.6

< 0.9

< 1.5 1.3 + 0.8

< 0.9

< 1.5

< 0.6

< 0.9

< 1.4

< 0.9

< 1.5

< 0.9

< 1.0

< 1.6

< 0.9

< 1.4 3.6 +/- 1.5

< 2.7

< 2.7 2.9 +/- 1.5

< 2.6

< 2.7 2.6 +/- 1.5

< 2.8

< 2.7 3.9 +/- 1.7 5.2 +/- 2.2

< 2.8 9.6 +/- 2.7 20 +/- 3.6 15 +/- 3.1 11 +/- 2.8 26 +/- 4.0 22 +/- 3.9 3.8 +/- 2.0 4.5 +/- 2.0

< 3.1

< 2.8 3.3 +/- 1.4 3.3 +/- 1.2

< 1.8

< 1.6 3.3 +/- 1.3

< 1.8 2.9 +/- 1.3 2.9 +/- 1.2

< 1.8 1.8 +/- 1.1

< 1.6

< 1.8

< 1.7

< 1.8

< 1.7

< 1.9

< 1.7

< 1.7 6.5 +/- 1.4

< 1.8 SAMPLES ARE DISTILLED FOR H-3 ANALYSIS B-5

TABLE B-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2010 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC SW-LR-2 SW-LR-4 SW-LR-6 SW-LR-7 SW-LR-8 SW-LR-9 SW-LR-10 COLLECTION Be-7 PERIOD 08/12/2010

< 40 08/12/2010

< 52 08/12/2010

< 27 08/12/2010

< 45 08/11/2010

< 38 08/11/2010

< 50 08/12/2010

< 46 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-137 Ba-140 La-140 171 199

< 44

< 108

< 89

< 95

< 88

+ 53 < 5

+ 59 < 5

<3

<5

<4

<5

<4

<5

<3

<6

<4

<5

< 12

<6

< 11

<9

< 10

<8

<5

<2

<4

<3

<5

<12

< 10

<7

< 10

<9

<6

<7

<3

<6

<5

<6

<9

< 10

<6

< 10

<8

<9

<9 10 13 10 14 10 11 13

<4

<6

<3

<5

<4

<5

<4

<5

<3

<5

<6

<5

< 29

< 36

< 19

< 30

< 24

< 26

< 31 12 7

6 9

8 7

8 B-6 a,

ML11157A035

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search