Text

Submittal of 2009 Annual Radiological Environmental Operating Report
	ML101250333
Person / Time
Site:	Limerick
Issue date:	04/27/2010
From:	Mudrick C; Exelon Generation Co, Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML101250333 (116)
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{{#Wiki_filter:W Exekln. Limerick Generating Station www.exeloncorp.com NucleaT 3146 Sanatoga Road Pottstown, PA 19464 TS 6.9.1.7 April 27, 2010 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353

Subject:

2009 Annual Radiological Environmental Operating Report

Dear Sir:

In accordance with the requirements of Section 6.9.17 of Limerick Generating Station (LGS) Unit 1 and Unit 2 Tech. Specs., and Section 6.1 of the LGS Units 1 and 2 Offsite Dose Calculation Manual (ODCM), this letter submits the 2009 Annual Radiological Environmental Operating Report No. 25. This report provides the 2009 results for the Radiological Environmental Monitoring Program (REMP) as called for in the Offsite Dose Calculation Manual. In assessing the data collected for the REMP, we have concluded that the operation of LGS, Units 1 and 2 had no adverse impact on the environment. No plant-produced fission or activation products, with the exception of Cs-1 37, were found in any pathway modeled by the REMP. Cesium-1 37 levels detected in sediment were consistent with levels found in previous years and were attributable to LGS liquid releases. Results of the groundwater protection program are also included in this report. Positive tritium was found in 3 of 15 groundwater monitoring locations that ranged up to 1,750 pCi/L. There are no commitments contained in this letter. If you have any questions, please do not hesitate to contact us. Sincerely, Christopher H. Mudrick Vice President -LGS Exelon Generation Company, LLC

Attachment:

2009 Annual Radiological Environmental Operating Report No. 25 cc: S. Collins, Administrator, Region I, USNRC (w/Attachment) E. DiPaolo, USNRC Senior Resident Inspector, LGS (w/Attachment) P. Bamford -Senior Project Manager-NRR, USNRC (w/Attachment) T. Moslak, Inspector, Region I, USNRC (w/Attachment)

LIMERICK GENERATING STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT DISTRIBUTION LIST bcc: E. Callan - GML 5-1 (w/o Attachment) C. Mudrick -GML 5-1 (w/o Attachment) D. Merchant - GML 1-1 (w/o Attachment) J. Hunter III - SSB 2-4 (w/Attachment) C. Cooney-SSB 2-2(w/Attachment) L. Birkmire -SSB 2-2 (w/Attachment) C. Smith - SSB 2-2 (w/Attachment) S. Gamble - SSB 2-4 (w/o Attachment) A. Columbus-SMB 1-2 (w/Attachment) K. Jury - Cantara (w/o Attachment) J. Grimes - KSA 3N (w/o Attachment) C. Lewis - KSA 3N (w/o Attachment) D. Helker - KSA 3E (w/o Attachment) R. Janati-Commonwealth of PA (w/Attachment) M. Murphy-PA DEP BRP Inspector - SSB 2-4 (w/Attachment) S. Focht - ANI (w/Attachment) David Katz - Deputy Water Commissioner Environmental Policy and Planning City of Phila. Water Dept, ARAMark Tower 5 th Fir, 1101 Market St. Phila. PA 19107-2994 (w/Attachment) Aqua Pennsylvania 762 West Lancaster Avenue Bryn Mawr, PA 19010 (w/Attachment) Andrew Fabian -Phoenixville Water Works 140 Church St Phoenixville, PA 19460 (w/Attachment) Pennsylvania American Water 800 W. Hershey Park Dr. Hershey, PA 17033 (w/Attachment) James Hennessey - Pottstown Water Authority 100 E. High St Pottstown, PA 19464-9525 (w/Attachment)

Docket No: 50 - 352 50-353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report Report No. 25 1 January Through 31 December 2009 Prepared By Teledyne Brown Engineering Environmental Services Exek~n. Nuclear Limerick Generating Station Sanatoga, PA 19464 April 2010

Table Of Contents I. Summary and Conclusions.......................................... 1 I1. Introduction.................................................... 3 A. Objectives of the REMP............... 3 B. Im plementation of the Objectives............................... .................................... 4 Ill. Program Description...................................................................................................... 4 A. Sample Collection.......................................... 4 B. Sam ple Analysis............................................................................................. 6 C. Data Interpretation.......................................................................................... 6 D. Program Exceptions........................................................................................ 7 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..................... I..................................................................................

10

4. Sediment............................................................................................

10 B. Atmospheric Environment............................................................................. 11

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

11

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

11

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

12

2. Terrestrial................... I......................................................................

12

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

12

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

12 C. Am bient Gam ma Radiation.......................................................................... 13 D. 10 CFR 20.2002 Perm it Storage Area........................................................ 13 E. Land Use Survey......................................................................................... 13 F. Summary of Results - Inter-Laboratory Comparison Program.................... 14 V. References................................................................................................................... 16

Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 ,Radiological Environmental Monitoring Program Annual Summary for the Limerick Generating Station, 2009. Appendix B Location Designation, Distance & Direction, and Sample Collection & Analytical Methods Tables Table B-I::, Location Designation and Identification System for theLimerick Generating Station. Table B-2: Radiological Environmental MonitoringProgram - Sampling Locations, Distance and Direction, Limerick. Generating Station, 2009. Tab!e B-3:,, Radiological Environmental Monitoring Program.- Summary of Sample Collection and Analytical Methods,, Limerick Generating Station, 2009. Figures Figure B-1: Figure B-2: Figure B-3. Environmental Sampling Locations Within Onei Mile of the Limerick. Generating Station, 2009. Environmental Sampling Locations'Between One and Five Miles frorm the Limerick Generating Station, 2009. Environmental'Sampling Locations GireaterlThan Five Miles from the !Limerick Generating Station, 2009, Data Tables and Figures - Primary Laboratory Appendix C Tables Table C-1.1 Table C-1.2 Concentrations of, Tritium in Surface Water Samples. Collected in the Vicinity.of Limerick Generating Station, 2009. Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Limerick Generating Station, 2009. ii

Table C-11.1 Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2009. Table C-11.2 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2009. Table C-11.3 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Limerick Generating Station, 2009. Table C-I11.1 Concentrations of Gamma Emitters in Predator and Bottom Feeder (Fish) Samples Collected in the Vicinity of Limerick'Generating'Station, 2009. Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Limerick Generating Station, 2009. Table C-V.1 Concentrations of Gross Beta in Air Paiticulate Samples Collected in the Vicinity of Limerick Generating Station, 2009. Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter)i n Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2009. Table C-V.3 Concentratiors of Gamma. Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2009. Table C-Vl.1 Concentrations of 1-131 in Air Iodine Samples Cotllcted in the Vicinity of Limerick Generating Station, 2009. Table C-VII.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2009. Table C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating'Station,. 2009'. Table C-VIII.1 Concentrations of Gamma Emitters in Broad Leaf Vegetation Samples Collected in the Vipinity:of Limerick"Generating Station, 2009. Table C-IX.1 Quarterly.TLD Results for Limerick Generating Station, 2009. Table C-IX.2 Mean Quarterly TLD Results for the Site -Boundary, Middle and Control Locations for Limerick Generating Station, 2009. Table C-IX.3 Summary of the Ambient Dosimetry Program for Limerick Generating Station, 2009.' Figures Figure C-i Mean Monthly Total Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of LGS, 1982 - 2009. Figure C-2. Mean Annual Cs-137 Concentratibns in Fish Samples Collected in the Vicinity of LGS, 1982 - 2009. 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-II.2 Table D-Ill.1 Figures Figure D-1 Figure D-2 Concentrations of Cs-1 37 in Sediment Samples Collected in4he. Vicinity of LGS, 1982 - 2009. Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 1982 -.2009... Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of LGS, 2009. Mean Quarterly Ambient Gamma Radiation Levels (TLD) in the Vicinity of LGS, 1985 -2009. Data Tables and Figures - Comparison Laboratory Concentrations of Total Gross Beta in Drinking Water Samples Collected in the Vicinity Of Limerick Generating Station, 2009. Concentrations of Tritium in Drinking.,Water.Samples!Collect.3d in the Vicinity Of Limerick Generating Station, 2009. Concentrations of Gamma Emitters in Drinking Water. Samples Collected in the Vicinity of Limerick Generating Station, 2009. Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2009. Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Limerick Generating Station, 2009. Concentrations of 1-131 by Chemical Separation and Gamma Emitters in Milk Samples Collected in the Vicinity of Limerick Generating Station, 2009. Comparison of Monthly Total Gross Beta Concentrations in Drinking Water Samples Split Between ENV and TBE, 2009. Comparison of Weekly Gross Beta Concentrations in Air Particulate Samples Collected from LGS Collocated Locations 11S1 and 11S2, 2009. iv

AppendixE Inter-Laboratory Comparison Program Tables..,. Table E-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2009. Table E-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2009. Table E-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Teledyne Brown Engineering, 2009. Table E-4 ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2009. Table E-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP) Environmental, Inc., 2009. Appendix-F Annual Radiological Groundwater Protection Program Report (ARGPPR).. v

C Intentionally Left Blank vi

I. Summary and Conclusions In 2009, the Limerick Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately 28 curies of noble gas, fission and activation products and approximately 56 curies of tritium. The dose from both liquid and gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public. The results of those calculations and their comparison to the allowable limits were as follows: Gaseous and liquid radiation doses to members of the public at locations Effluent Applicable Estimated Age Location % of Limit Unit Organ Dose Group Distance Direction Applicable (meters) (toward) Limit Noble Gas Gamma - Air Dose 2.17E-03 All 1004 ESE 0.011 20 mRad Noble Gas Beta - Air Dose 1.27E-03 All 1004 ESE 0.003 40 mRad Noble Gas Total Body (Gamma) 2.06E-03 All 1004 ESE 0.021 10 mrem Noble Gas Skin (Beta) 3.42E-03 All 1004 ESE 0.011 30 mrem Iodine, Particulate & Tritium Lung 6.06E-04 Teen 1004 ESE 0.002 30 mrem Liquid Total Body 7.75E-01 Child Aqua PA 12.917 6 mrem Liquid Liver-7.75E-01 Child Aqua PA 3.875 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 2009 through 31 December 2009. During that time period, 1088 analyses were performed on 887 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 Plant 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 ýnd 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 'naturallyobccurring Be-7 and K740 were detected., No activation or fission products were detected.' Environmenta! gamma radiation measurements were performe.d quarterlyusing thermoluminescent dosimeters. Levels detected were consistent with those .observed in previous years. Review of the gamma spectroscopy results from the sunrface water samples located at'the Limerick intake (24S1) and downstr'eam of t-he 10CFR20.2002 permitted storage area showed"ho'eviderice of bffsite 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 (ISFS) indicatesno direct dosewas. 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. Additionaill, a select group of wells had hard-to-detect nuclides and gross alpha ard,gro'ss betaanalyses performed. Most tritium values were less than the lower limit of detection of 200 pCi/L. However, one well located near the Unit 1 Condensate Storage Tank had a tritium value as high as 1,750 pCi/L.. This activity was due.to a leak from the exterior walls of both Ul and U2 condenser bays. The condensation was .,observed dripping directly to open ground and asphalt. Water samples were collected and analyzed for gamma isotopic andtritium. No gamma emitting nuclides were identified; however, tritium was identified: at'a concentration of 3.90E-3 uCi/ml. Although no drinking water pathway exist, the dose from drinking the water from the well containing 1,750 pCi/L tritium was calculated at 0.18 mrem to a child (total body), which was 3.02% of the 10 CFR 50, Appendix I dose limit. All results for Sr-90 and gamma emitting nuclides were less than MDC. 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

'I ntroduction,., ,.-.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 bn-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, 1"979). The preoperatiorial 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 ana!yses performed by Teledyne Brown. Engineering (TBE), Global Dosimetry, and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 20Q09 through 31 December 2009. On 6 July 1996 a 1 OCFR20.2002 permit was issued to Limerick for storage of slightly contaminated soils, sedimentS and sludges obtained from'the holding pond, cooling tower and'spray pond s'siems. Theseh materials will'decay to .backgrlound while in storage. ;Final disposition will be determined at Station 'decommissioning. On 21 July 2008 -an ISFS1 pad was put into service..- The ISFSI. is dry cast storage, where spent nuclear-fuel is*,stored. A. Objective of the REMP The objecti'es of the REMP are to:`

1.

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

2.

Evaluadte the reiationship between quantities of radioactive material released from the plant andresultant radiation doses to individuals from principal pathways of exposure. 3

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

1.

Identifying significant exposure pathways.

2.

Establishing baseline radiological data of media within those pathways.

3.

Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment. Ill. Program Description A. Sample Collection Samplesfor the L.GS REMP were.collected for Exelon N'uclear by Normandeau Associates,- Inc. (NAI). This section descri.es,the general collection methods used by NAI to obtain environmental samples for the LGS REMP in 2009. Sample locations and desoriptions can be found in Tables B-1 and B-2, and Figuwes 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, drinkingfwater, fish, and sediment. Two-galton water samples were -oolecied nmonthly from continuous samplers !ocated at fhree'surface water locatioris (10F2, 13B11 and 24S1) and four drinking water-locations (!5F,4, 1-5,F-7, 16C2,. and 28F3). Control locations were 24S1, and 28F3. All samples were collected in new unused plastic bottles, which were rinsedat leasttwice 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 depositedtsubstrate were collected at three locations semiannually,. 1 6B2, 16C4,and 33A2 (control). Atmospheric Environment Sý-. -The atmosphericienvironriient was evaluated by performing radiological anialyses on samples of air particulate,'airborne iodine, and milk. Airborne iodine and particulate samples were collected and analyzed weekly at five locations.(10S3, 11 S1, 13C1, 14S1, and 22G1). The control location was 22G1. Airborne iodine and particulate samples were obtained at each .location, using a vacuum pump with charcoal and glass fiber filters attached. The pumps were. run continuously and sampled air at the rate of approximately one cubic foot per minute. The filters were replaced weekly and sent to the laboratory for analysis. 4

Milk samples were collected biweekly at five locations (1 0F4, 1 8E1, 199B1, 23F1, and 25C1) from April through November, and monthly from December through. March. Two additional locations (25E1 and 36E1) were sampled quarterly. Locations 36E1 and 23F1 were controls. All 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 dollected monthly at three locations (11 S3, 13S3 and 31G1). The control location was 31G1. Eight different kinds of vegetation samples were collected and placed in new unused plastic bags, and sent to the laboratory for analysis. Ambient Gamma Radiation Direct radiation measurements were made using Panasonic 814 calcium sulfate (COSO 4) thermoluminescent dosimeters (TLD). *The TLD locations rwere placed on and around the LGS site as iollows. '-A site boundary ring consisting of 16 locations (36S2, 3S1, 5S1, 7S1, 10S33 11S1, 13S2, 14S1, 1.8S29 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 ring consisting-of 16 locations (36D1, 2E1, 4E1, 7E1, 10EI, 1OF3, 13E1., 16F17; 19DI, 20F1, 24D1, 25D1, 28D2, 29E1, 31 D2, and 34E1) extending to approximately 5 miles from the site designed to measure possible exposuies to close-in population. The balance of eight locations (5H1, 6C1,, 9C1,.13C1, 15D1, 17B1, 20D1 and 31 Dl) representing control and special, interests areas such as population centrs, schools; etc. The specific TLD locations were determined by the following. criteria:

1.

The presenceof relatively dense pOpullation;

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 dwel!ing to the vents in the prevailing downwind direction. 5

Two TLDs - each comprised of three CaSe 4 thermoluminescent phosphors enclosed in plastic - were placed at each location in a PVC conduit located approximately three feet above ground level. The TLDs were exchanged quarterly and sent to Global Dosimetry for analysis. 1 OCFR20.2002 Permit Storaci6 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 (ISFSI) The results from :1ne TLD location 36S2 were used to determine the direct radiation exp6suee to the nearest, residence from the ISFSI pad. B. Sample Analvsis. This section describes the general analytical imethodologies used, by TBE and Midwest Labs to analyze the environmental samples for radioactivity for the-LGS REMP in 2009. The analytical procedures used by the laboratories are listed in Table B-3. In order to achieve the stated objectives, the current program includes the following analyses:

1.

Concentrations of beta emitters in drinking water, and air particu!ates.

2.

Concentrations of gamma emitte'rs inr surfafce and drinking water, air particulates, milk,, fish, broad leaf. vegetation and sediment. 3:. Concentrations of tritium 4 surfae'and drinking water.

4.

Concentrations of 1-131 in air and milk.

5.

Arbient gamma radiation levels at various site environs. C.,, Data Interpretation The radiological and direct radiation data coHected prior to LGS becoming operational was used as a baseline with which these operational data weretcompared. For the purpose of this report,-LGS'was considered operational at initial criticality. In addition, data were compared to previous years' operati6nal 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 T... 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 ActivitVCalculation 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 sampld were groupedas follows: ., For surface and drinking water twelve nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, J-131, Qs-134i Cs-137, Ba-140, and La-140 were reported. For fish nine nuclides, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, 1-131, Cs-1 34,, and Cs-1 37 were reported. For'sedin~ent' ahd broadl leaf'veg~ettation eight nuclides, Be-7, -,K-40, Mn-54., Co-58; Co-60,- 1-i31, Cs-1 34, -and Cs-1 37 were reported. For air particulate six nuclides,.Be-7, Mn-54, Co-58, Co-60, Cs-134, and Cs-i137 were reported. For milk five nuclides, K-40, Cs-1 34, Cs-1 37, Ba-i-40, and La-1 40 were -reported:.. Means. and standard deviations of. positive results were calculated. -The standard deviations represent the variability of measured -results for different samples rather than single analysis uncertainty. D. Program Exceptions -For 2009 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 3/3/09 - 3/9/09 7

was not available due to equipment malfunction' (IR 00893287).

2.

Air sample from location 11 S2 for the week'4/20/09 - 4/27/09 was not available due to equipment malfunction (IR 00915359).

3.

Air sample from location 1 0S3 for the week 5/18/09.-25/26,/09 was not available due to equipment malfunction (IR 00925392).

4.

Air samples from location 11 S1 for the week 7/6/09 - 7/13/09 and 07/20/09 - 07/27/09'were not available due to equipment malfunction (IR 00944071).

5.

Air sample results from location 11 S2 for ýthe week of 8/3/09 - 8/10/09 were not available due to the loss of sample during processing.

6.

Grab samples were taken for the composite surface watersampler at location 13B1 during the following periods due to equipment malfunction or frozen sample line:- 02/01/09 - 02/18/09 03/01/09-03/14/09 , 03/29/094-04/04/090, .05/17/09 - 05/23/09. 08/30/09 - 09/05/09 10/11/09 - 10/17/09

7.

,A grab sample was. taken for ihecomposite surface water sampler at location 24S1 during the week of 02/01/09 - 02/07/09 due to equipment malfunction.

8.

Grab samples were taken for the composite drinking water sampler at location 16C2 during the following periods due to equipment malfunction: 03/22/09 - 03/28/09 12/20/09 - 01/02/10

9.

Only two broad leaf vegetation samples were collected at Station S1.S3 during the month of September. Collards were not available.

10.

Milk sample'stations 23F1 and 25C1 showed positive 1-131 activity on 1 1/03/09. The elevated activity can be attributed to a naturally occurring isotope that was not completely separated from the sample. The activity is considered to be a false positive data point (IR 01039780). Each program exception wasereviewed to understand the causes of the program exception. Sampling and maintenance errors were reviewed with 8

the personnel involved to.prevent recurrence. Occasional equipment breakdowns and power outages were unavoidable. The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation. E. Program Changes

1.

Milk farm Station 25E1 went out of business in 2009.

2.

Surface water Station 10F2 was shut down until further notice. This location is sampled onlywhen LGS draws water from the Delaware River for cooling purposes. 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 133B1 located downstream, could be affected by Limerick's effluent releases. The following analyses were performed. Tritium Monthly samples from all locations were composited quarterly and analy:zed 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 K.'.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-11.1, Appendix C). The values ranged 9

from 2.3 to 7.4,pCi/L. :Concentrations detected were consistent with those.detected in previous years (Figure C-1, Appendix C). Tritium Monthly samples from all locations were composited quarterly and analyzed for tritiumactivity (Table C-11.2, Appendix C). One of 16 samples had a value of 168 pCi/L, which is less than the required 200 pCi/L LLD requirement. All other results were less than the MDC. Gamma Spectrometry Samples from all locations were analyzed for aamma emitting nuclides (Table C-11.3, Appendix C). All nuclides were less than the MDC.

3.

Fish" Fish samples comprised of Catfis h/bu.lhead (bottom feeder) and sunfish (predator) were'collecied afttwo' locations (16C5 and 29C1) in the spring arid fall seasohn. Location 16C5 could be affected by Limerick'W effluent releases'. The:following analysis was performed: Gamma Spectrometry The edible portion of fish samples from both locations was analyzed for gamma emitting Inuclides (Table C-111.1, Appendix C). Naturally occurring K-40 was found at all stations and ranged from 2,220 to 4,350 pCi/kg wet #rd'was consitent with levels detected in prIevious years. No other gamma emitting nuclideswere found. Historical levels of Cs-137 are shown in.Figure C-2, Appendix C.

4.

Sediment Aquatic sediment samples were collecled at three locations (166B2, I'16C4 and 33A2) sermiahnually.:' O-fthese locations two, 166B2 and '16C4,, located downstream,;'could bO affected by Limerick's effluent releases.t he following analysis waps erformed: i"Gamma.Spectrometry Sediment'samples from all"three" locations were analyzed for gamma emitting nuclides (Table C-I V.1;ý Appendix C). Nuclides detected Were'naturally'6ccuti'ing Be-7, K-40 and the fission product Cs-1 37. Beryllium-7 was found at locations. 16B2 and 16C4 and ranged from 1,660 to 1,990 pCi/kg dry. Potassium-40 was found at all locations and ranged from 11,800 to 17,800 pCi/kg dry. The fission product Cs-1 37 was found at all locations and ranged from 83 to 10

166 pCi/kg dry. The Cs-137 activity found at1 6B2 and 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.. Airborn,,

a.

Air Particulates Continuous air particulate samples were collected from five locations on a weekly basis. The five locations were - separated into three groups: Group I represents locations within the LGS site boundary (I 0S3, 1 lS1, and 14S1), Group 1i represents the location'at an, intermediate distance from the,.LGS site (13C01), and Group Ill represents the control location at a remote distance from LGS (22G1). The following analyses were performed: Gross Beta Weekly samoles wereanalyzed for concentrations of beta emitters (Table C-V. i" dnd 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 .8 E-3jto 29 E-33 pCi/m 3 with a mean of 15.8 E-3 pCi/m 3. The results fom the Intermediate Distance location 1-. 1.. 1 I ! .M (Group' 1)' ranged from 8. E-3 to 34 E-3 pCi/i 3 with a mean pf 16.3 E_ ,p.ir.. The results from the Distant locations (Group I1l) ranged from 8 E-3 to 31 E-3 pCi/m 3 with a mean of 15.9 E-3 pCi/i 3. Comparison of the 2009 airparticulate data with previous year's data indicate no effects from the I,.. operation. of LGS,(Figure,.C-4, Appendix C). In addition, a comparison of the weekly mean values for 2009 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). 11

Naturally occurring Be-7 due to cosmic ray activity was detected in all samples. Thase values ranged from 55 E-3 to 125 E-3 pCi/m 3. All other nuclides were less than the MDC.

b.

Airborne Iodine Continuous air samples were collected from five locations (10S3, 11S1, 14S1,. 13CI0, 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, S amples were collected from five locatins-(10F4, 18E1, 19B11, 23F4', and'25C1) biweekly Aprilthro0ughNovember and monthly December through March. Samples from one additional location (36E1) were taken quarterly.- The following ana!yses were.performed: *.

Ilodine-i 31"- Milk samples from all locations were analyzed for concentrations of 1-131 (Table C-VIIl, Appendix C). All results were less,than-the MC. Gamrmna Spectrornrtry Each milk sarple. was analyzed for concentrations of gamma emitting nuclides (Table.C-VII.2, Appendix C). Naturally occurring K-40 activitywas found in all samples and ranged from 1,090 to 1.,620 pCi/L. All other nuclides were less than the MDC.

b.

Broad Leaf Vegetation", Three types of broad lea4 'vegetation samples were collected ýV ,from three locations(11S3, 13S3 and 31G1) monthly from June through September. The following analysis was performed: Gamma Spectrometry Each broad leaf vegetation sample was analyzed for concentrations of gamma emitting nuclides (Table C-VIII.1, Appendix C). Cosmogeric Be-7 was found in 15 of 20 samples and ranged from 157 to 3,000 pCi/kg wet. Naturally occurring K-40 was 12

found in all samples and ranged from 2,650 to 10,300 pCi/kg S".wet. All other nuclides we're less than the MDC. C. Ambient Gam'ma Radiation Ambient gamma radiation levels were measured utilizing Panasonic 814 (CaSO*4 ) thermoluminescent dosimeters. Forty TLD locations were established around the site., Results of TLD measurements are listed in Tables C-IX. 1 to C-IX.3, Appendix C. Most TLD measurements were below I10 mR/standard month, with a range of 4.8 to 11.5 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 to all other locations. other than ..13S2. Location 13S2 historically shows higher ambient gamma radiation, which is'assumed due to the rock substrate: The area that this TLD is " locate'd in has been' determined to emanate radon prodingy. The'historical ambient gamma radiation'data from Location 5H1 were plotted along With, similardata 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 radonf emanating from the ground. D. 10 CFR 20.2002 P ermit Storage Are. a The results of the surface water aquatic, monitoring program from Location 2.4S1 were used to determine if radioactivity from the permit storage area had mad'eit to' the Scluylkill-River.' ThKe 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' lpd. The dIata, aifter'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 August 2009 around Limerick .Generating Station (LGS) was performed byNormandeau Associates, Inc. for Exelon Nuclear to comply with Bases 3.3.2 of the Limerick's Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident, milk producing animal and garden of greater than 500 ft2 in each of the sixteen 22 1/2 degree sectors around the site. The gardens in the NE and'SSE sectors are further away than 2008. The 13

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 Mi Miles Miles 1 N 0.6 1.8 2 NNE 0.5 .1.8 3 NE 0.7 3.4 4 ENE ý0.7 2.7 5 E 0.6 2.4 6 ESE 0.5. -. 0.3 7SE 0.7 0.2 8SSE 1.0 1.3 9S 1.0 --1.2 10 SSW 0.8 1.0 11 Sw 1.0 1.0 12 WSW 0.6 0.8* 13 W.

0.

,0.8 - 14WNW. ,*,0.7 0.7 15NW 0.7 1.6 16 NNW' 0.7 71.3 G. Summary of Results-Inter-laborato0ryComparison'Program ilk Farm Miles 4.7 4.2 2.0 2.7 2.8 The primary andsecondary 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, suppliedby Analytics Inc., Environmental Resource Associates (ERA) and. DOE's MAPEP, we reevalu.ted against the following pre-set acceptance criteria: 1 Analytics Evaluation Criteria Analytics' evaluation report provides a.ratio of TBE's result and .Analytics"'known value. Since flag;values are not assigned by Analytics, TBE-ES evaluates.the reported-ratios based on internal QC requirements, which are, based;on the DOE MAPEP criteria.

2.

ERA Evaluation Criteria ERA's evaluation report provides 'an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established per the USEPA, NELAC, state specific PT program requirements or ERA's'SOP for the Generation of Performance Acceptance Limits, as applicable. The acceptance limits are either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document. 14

3.

DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values. The MAPEP defines three levels of performance: Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is _ 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/- 20% to +/- 30% of the reference value (i.e., 20% < bias <' 30%). If the bias is greater than 30%, the results are deemed not acceptable. For the primary laboratory, 17 out of 18 analytes met the specified acceptance criteria. One sample did not meet the specified acceptance criteria for the following reason: 1, Teledyne Brown Engineering's Analytics June 2009 Zn-65 in AP result of 137 pCi/L was higher than the known value of 101 pCi/L, resulting in a found to known ratio of 1.36. NCR 09-23 was initiated to investigate this failure. The failure appears to be a result of a slightly high bias on Detector 7. A recount on Detector 17 resultedin a Zn-65 'result of 1001 pCi/L. The"detector has been -tagged out-of-service until a recalibratior can be% performed. Detectcr 7 is not used for client samrples For the secondary laboratory, Environmental, Inc., 11 Out of 14 analytes met the specified acceptance criterlia. I Four samples did not meet the specified acc6ptance criieria'for the following' reiason:

1. Environmental Inc.'s ERA April 2009 Cs-137 in water result of 147.7 pCi!Lexceeded the lower control limit of 151.0 pCi/L. All gammaeniittersshowed a low bias., A large plastic burr found on the base of.the Marinelli kept the beaker from sitting directly on the detector. Recounting in adifferent~beaker gave an acceptable result of 155.33 +/- 14.55 pCi/L.

..2. Environmental Inc.'s ERA April 2009 H-3 in water result of 22,819 pCi/Lexceeded the upper control limit of 22,,300 pCi/L. A recount of the original vials averaged 23,009 pCi/L. Reanalysis results were acceptable at-_ 9,170 pCi/L. No cause could be found for the failure. 15

3. Environmental Inc.'s MAPEP January 2009 Sr-90 in AP result of 0.93 exceeded the upper control limit of 0.83. Reanalysis results were acceptable at 0.54 +/- 0.12 Bq/filter. No cause could be found for the failure.

4. Environmental Inc.'s MAPEP July 2009 Sr-90 in soil result of 31.0.5 Bq/kg exceeded the lower control limit of 319 Bq/kg. Reanalysis results were acceptable at 363.3 Bq/kg. Incomplete separation of strontium from calcium could result in a higher recovery percentage and consequently lower reported activity.

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 T5 Philadelphia Electric Company.

2.

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

3.

Pre-operational Radiological Environmental Monitoring Program Report, Limerick Generating Station Units 1 and 2, 1 January 1982 through 21 December 1984, Teledyne Isotopes and Radiation Management Corpoiratibn. ~ 16

It APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2009 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER H-3 8 200 <LLD <LLD 0 (PCI/LITER) GAMMA MN-54 24 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 15 <LLD 15 <LLD .30 <LLD 15 <LLD 30 <LLD 15 <LLD 30 <LLD 15 <LLD 15 <LLD 18 <LLD 60 <LLD 15 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 0 0 0 0 0 0 0 1-131 CS-1 34 CS-137 BA-140 LA-140 0 0 0 0

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

A-3

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK.GENERATING STATION, 2009 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS DRINKING WATER GR--B 48 4 4 3.6 4.2 15F7 INDICATOR 0 (PCI/LITER) I (34/36) (9/12) (12/12) PHOENIXVILLE WATER WORKS (2.3/7.4) H-3 16 48 GAMMA MN-54 CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95. 200 168 (1/12) 15 <LLD

15.

<LLD 30 <LLD 15 <LLD (3.0/4.2) <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 168 (1/4) (2.8/6.3) 6.33 MILES SSE OF SITE 15F7 INDICATOR PHOENIXVILLE WATER WORKS 6.33 MILES SSE OF SITE 0 0 0 0 0 0 0 0 30 <LLD 1-131 CS-134 CS-1 37 BA-140 LA-140 15 <LLD 30 <LLD 15 <LLD 15 <LLD 18 <LLD 60 <LLD 15 <LLD 0 0 .0 0 0 <LLD <LLD

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

A-4

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2009 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS BOTTOM FEEDER GAMMA 4 (PCI/KG WET) K-40 NA 3575 3915 3915 29C1 CONTROL 0 MN-54 CO-58 FE-59 CO-60 ZN-65 1-131 PREDATOR (PCI/KG WET) CS-134 CS-137 GAMMA K-40 MN-54 CO-58 4 (2/2) (3310/3840) 130 <LLD 130 <LLD 260 <LLD 130 <LLD 260 <LLD NA <LLD 130 <LLD 150 <LLD NA 3510 (2/2) (3230/3790) 130 <LLD 130 <LLD 260 <LLD- -130- <LLE 260 <LLD NA <LLD' 130 <LLD 150 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 0 0 0 0 0 (2/2) (3480/4350) <LLD (2/2) (3480/4350) 0 POI ITITTWN VICINIIY UPSTREAM OF INTAKE 2785 (2/2) (2220/3350) 3510 (2/2) (3230/3790) 16C5 INDICATOR VINCENT POOL DOWNSTREAM OF DISCHARGE 0 0 FE-59 CO-60 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD ZN-65 1-131 CS-134 Cs-i 37 0 0 0 6 0 0 0 - THE MEAN ANDJ 2 STANDARD DEVIATION'VALUES'ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) A-5

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2009 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA

REPORTING PERIOD: :

2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M) LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT GAMMA 6 (PCI/KG DRY) BE-7 NA 1840 <LLD 1870 16B2 INDICATOR 0 (3/4) (1660/1990) (1/2) LINFIELD BRIDGE 1.35 MILES SSE OF SITE 16B2 INDICATOR LINFIELD BRIDGE 1.35 MILES SSE OF SITE K-40 NA 16550 (4/41 (1 5500/17800) 13350 (2/2) (11800/14900) 17200 (2/2) (16600/17800) 0 MN-54 CO-58 CO-60 NA <LLD NA <LLD NA <LLD NA <LLD <LLD <LLD <LLD <LLD <LLD 108 (i12) q 0 0 0 0 0 1-131 CS-134 CS-137 150 180 <LLD' 128 (4/4) (83/166) 153 (2/2) (139/166) 16B2 INDICATOR LINFIELD BRIDGE 1.35 MILES SSE OF SITE 0

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES FRACTION OF DETECTABLE MEASUREMENTS AT S.PECIFIED LOCATIONS ISINDICATED INPARENTHESES(F)

A-6

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2009 Name of Facility: LIMERICK GENERATING STATION DOCKET NUMBER: 50-352 & 50-353 Location of Facility: MONTGOMERY COUNTY PA REPORTING PERIOD: 2009 INDICATOR CONTROL. LOCATION WITH HIGHEST-ANNUAL MEAN (M) LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M) MEAN (M) MEAN (M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME" NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE IAANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) "!MEASUREMENTS AIR PARTICULATE GR-B 256 10 16 16 16 13C1 INDICATOR 0 (E-3 PCI/CU.METER) (200/204) (51./52) (51/52) KING ROAD (8/34) (8/31) AIR PARTICULATE (E-3 PCI/CU.METER) GAMMA BE-7 MN-54 CO-58 CO-60 CS-1 34 CS-i 37 GAMMA 1-131,- 20 (8/34) 95 (3/4) (75/116) NA 85 (15/16) (55/125) NA <LLD 95 (3/4) (75/116) <LZLD NA 2.84 MILES SE OF SITE 22G1 CONTROL MANOR SUBSTATION 17.73 MILES SW OF SITE <LLD <LLD <LLD <LLD 0 0 0 0 0 0 NA <LLD 50 <LLD - 60 <LLD -- <LLD AIR IODINE. (E-3 PCI/CU.METER) 256 70 <LLD <LLD -

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

.FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) A-7

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR THE LIMERICK GENERATING STATION, 2009 Name of Facility: LIMERICK GENERATING STATION Location of Facility: MONTGOMERY COUNTY PA DOCKET NUMBER: 50-352 & 50-353 REPORTING PERIOD: 2009 LOCATION WITH HIGHEST ANNUAL MEAN (M) MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT) MILK (PCI/LITER) TYPES OF ANALYSIS PERFORMED NUMBER OF ANALYSIS PERFORMED REQUIRED LOWER LIMIT OF DETECTION (LLD) 1 INDICATOR LOCATIONS MEAN (M) (F) RANGE <LLD CONTROL LOCATION MEAN (M) (F) RANGE MEAN (M) (F) RANGE STATION # NAME DISTANCE AND DIRECTION NUMBER OF NONROUTINE REPORTED MEASUREMENTS 0 0 1-131 109 109 <LLD GAMMA K-40 CS-134 CS-137 BA-140 LA-140 GAMMA BE-7 NA 1252 (84/84), "(1090,'i 450) 15 <PLD 1258 (25/25) (1150/1620) <LLD 1271 (21/21) (1170/1450) 10F4 INDICATOR 6.60 MILES ESE OF SITE 0 18 <LLD <LLD 60 "<L!LD <LLD 15 0 0 0 0 <LLD VEGETATION (PCI/KG WET) 20 K-40 NA .311 0 57/ýli9) NA .4991 (NA 50<L300D NA < LLD-1283 (7/9) (308/3000) 4980 (9/9) (3430/5940) 1283 (7/9) (308/3000) 8457 (3/3) (5950/10300) 31G1 CONTROL 13S3 INDICATOR VINCENT DAM 0.24 MILES SE OF SITE MN-54 CO-58 CO-60 NA <LLD, NA <LLD 60 <LLD 60 <LLD <LLD <LLD <LLD <LLD <LLD 0 1-131 CS-134 CS-137 0 0 0 0 0 80 <LLD " ". <LLD DIRECT RADIATION TLD-OUARTERLY (MILLI-ROENTG EN/STD. MO.) 160 NA 7.1 (156/156) (4.8/11.5) -8.5 (4/4) (7.9/9.4) 10.8 (4/4) (9.9/11.5) 13S2 INDICATOR 500 KV SUBSTATION 0.41 MILES SE

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

A-8

APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS

TABLE B-i: XXYZ - Location Designation and Identification System for the Limerick Generating Station General code for identification of locations, where: xx Angular Sector of Sampling Location. The compass is divided into 36 sectors of 10 degrees each with center at Limerick's Units 1 and 2 off-gas vents. Sector 36 is centered due North, and others are numbered in a clockwise direction. Radial Zone of Sampling Location (in this report, the radial distance from the Limerick vent for all regional stations). Y S : on-site location A : 0-1 mile off-site B : 1-2 miles off-site C : 2-3 miles off-site D : 3-4 miles off-site E : 4-5 miles off-site F : 5-10 miles off-site G : 10-20 miles off-site H : 20-100 miles off-site Z Station's Numerical Designation within sector and zone, using 1, 2, 3... in each sector and zone. B-1

TABLE 13-2: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, LimericklGenerating Station, 2009 Location Location Description. Distance & Direction From Site A. Surface Water 113B1 24S1 1 0F2 Vincent Dam (indicator) Limerick Intake (control) Perkiomen Pumping Station (control) 1.75 miles SE 0.20 miles SW 7.25 miles E B. Drinkina (Potable) Water 15F4 15F7 16C2 28F3 Philadelphia Suburban Water Company (indicator) Phoenixville Water Works (indicator) Citizens Home Water Company (indicator) Pottstown Water Authority (control) C. Milk - bi-weekly / monthly 1 0F4 18E1 19B1 23F1 Control 25C1 D. Milk - quarterly 25E1 36E1 Control E. Air Particulates / Air Iodine 8.62 miles SE 6.33 miles SSE 2.66 miles SSE, 5.84 miles WNW. 6.60 miles ESE 4.21 miles S 1.95 miles SSW, 5.02 miles SW 2.69 miles WSW 4.27 miles WSW 4.70 miles N 10S3 11S1 11S2 13C1 14S1 22G1 Keen Road LGS Information Center LGS Information Center King Road Longview Road Manor Substation (control) 0.50 miles E 0.38 miles ESE 0.38 miles ESE 2.84 miles SE;. 0.63 miles'SSE 17.73 miles SW F. Fish 16C5 29C1 G. Sedimen Vincent Pool (indicator) Pottstown Vicinity (control) nt Linfield Bridge (indicator)' Vincent Dam (indicator) Upstream of Intake (control) Downstream of Discharge Upstream of Intake 1.35 miles SSE 2.18 miles SSE 0.84 miles NNW' 16B2 16C4 33A2 H. Broad Leaf Veqetation 11S3 13S3 31G1 LGS Information Center LGS 500 KV Yard Prout's Jollyview Farm 0.35 miles ESE 0.24 miles SE 13.6 miles NW B-2

TABLE B-2: Radioiogical Environmental Monitoring Program - Sampling Locations,' Distance and Direction, Limerick Generating Station, 2009 Location Location Description Distance & Direction From Site H. Environmental Dosimetry - 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 0.60 miles N 0.44 miles NNE 0.45 miles NE 0.59 miles ENE 0.50 miles E 0.38 miles ESE 0.41 miles SE 0.63 miles SSE 0.26 miles S 0.19 miles SSW 0.53 miles SW 0.46 miles WSW 0.40 miles W 0.55 miles WNW 0.26 miles NW 0.58 miles NNW 3.51 miles N 4.76 miles NNE 4.78 miles NE 4.26 miles ENE 3.94 miles E 5.58 miles.ESE 4.31 miles SE 5.04 miles SSE 3.49 miles S 5.24 miles SSW 3.97 miles SW 3.99 miles WSW 3.83 miles W 4.95 miles WNW 3.87 miles NW '4.59 miles NNW 36D1 2E1 4E1 7E1 10E1 1 0F3 13E1 16F1 19D1 20F1 24D1 25D1 28D2 29E1 31 D2 34E1 Siren Tower No. 147 Laughing Waters GSC Neiffer Road Pheasant Road Royersford Road Trappe Substation Vaughn Substation Pikeland Substation Snowden Substation Sheeder Substation Porters Mill Substation Hoffecker & Keim Streets. W. Cedarville Road Prince Street Poplar Substation Varnell Road Control and Special Interest 5H1 6C1 9C1 13C1 15D1 1781 20D1 31D1 Birch Substation (control) Pottstown Landing Field Reed Road King Road Spring City Substation Linfield Substation Ellis Woods Road Lincoln Substation 24.76 miles NE 2.14 miles NE 2.15 miles E 2.84 miles SE 3.20 miles SE 1.60milesS,. 3.06 miles SSW 3.00 miles WNW B-3

TABLE B-3: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Limerick Generating Station, 2009 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 amma 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-2007 Gamma emitting radioisotope analysis collected via radiological analysis (Limerick Generating electroshocking or other Station).. Env. Inc., GS-01 Determination of gamma emitters by techniques.. gamma spectroscopy Sediment Gamma Spectroscopy Semi-annual.grab RMC-ER7 Collection of sediment samples for 500. grams (dry). TBE, TBE-2007 Gamma emitting radioisotope analysis samples radiological analysis (Limerick Generating Station) Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Particulates Gross Beta One-week composite of RMC-ER8 Collection of. air particulate and air 1 filter (approximately TBE, TBE-2008 Gross Alpha and/or gross beta activity in continuous air sampling iodine samples for radiological analysis 280 cubic meters various matrices through glass fiber filter (Limerick Generating Station) weekly) paper Env. Inc., AP-02 Determinationof 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, 2009 Sample Analysis Sampling Method Collection Procedure Number - Sample Size Analytical Procedure Number T 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-ER,8 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 matri-es when cows are on radiological analysis (LimerickGenerating pasture. Monthly all Station) Env. Inc., 1-131-01 Determination of 1-131 in milk by anion other times I t,

exchange Milk Gamma Spectroscopy Bi-weeklly grab sample RMC-ER10 Collection of mill samples for 2 gallon TBE, TBE-2007 Gamma emitting radioisotope analysis when cows are on.,

radiological analysis (Limerick Generating pasture: Monthly all Station) Env. Inc., GS-01 Determination of gamma emitters by other times gamma spectroscopy TLD Thermoluminescence Quarterly TLDs RMC-ER9 Collection of.TLD samples for 2 dosimeters Global Dosimetry Dosimetry comprised of.two radiological analysis (Limerick Generating Panasonic 814 Station) (containing 3 each CaSO4 elements) 1 B -5

Figure B-1 Environmental Sampling Locations Within One Mile of the Limerick Generating Station, 2009 B-6

Figure B-2 Environmental Sampling Locations Between One and Five Miles from the Limerick Generating Station, 2009 B-7

Figure B-3 Environmental Sampling Locations Greater than Five Miles from the Limerick Generating Station, 2009 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, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION 10F2 13B1 24S1 PERIOD 12/29/2008 - 03/31/2009 03/31/2009 - 06/30/2009 06/30/2009 09/29/2009 09/29/2009 - 12/28/2009 (1) < 159 < 123 < 182 < 167 < 162 < 129 < 185 < 168 MEAN (1) SEE PROGRAM CHANGES SECTIONS FOR EXPLANATION c-1

TABLE C-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA-Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 STC COLLECTION PERIOD Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 1 0F2 (1) 13B1 12/29/2008 02/03/2009 03/03/2009 03/31/2009 04/28/2009 06/02/2009 06/29/2009 08/04/2009 09/01/2009 09/29/2009 11/02/2009 12/01/2009 MEAN 24S1 12/29/2008 02/03/2009 03/03/2009 03/31/2009 04/28/2009 06/02/2009 06/30/2009 08/04/2009 09/01/2009 09/29/2009 11/02/2009 12/01/2009 02/03/2009 03/03/2009 03/31/2009 04/28/2009 06/02/2009 06/29/2009 08/04/2009 09/01/2009 09/29/2009 11/02/2009 12/01/2009 12/28/2009 2 6 3 1 7 4 2 2 6 4 4 3 <2 <7 <4 <1 <7 <4 <3 <2 <6 <4 <4 <3 <5 < 12 <8 <3 < 14 <9 <6 <6 < 11 <7 <9 <7 <2 <6 <4 <1 <6 <4 <3 <2 <5 <5 <4 <2 <4 <11 <7 S<2 <16 < 8 <6 S<4 <11 <8 <8 <3 < 2 < 6 <4 <'1 < 6 <5 <3 <3 <5 <4 < 25 <2. <4 < 12 <7 <2 < 11 <7 <5 <5 <8 <6 <8 <4 <7 < 15 < 15 < 12 < 12 < 14 < 15 < 14 <6 <5 < 13 < 10 <2 <4 <4 <1 <5 <4 <2 <2 <5 <4 <4 <2 <2 < 6 <4 <1 <5 <4 <3 <2 <6 <4 <.4 <2 < 15 < 37 < 30 < 18 <34 < 31 < 25 < 22 < 21 < 16 < 29 < 22 <5 < 12 <9 <5 < 12 <9 < 10 <8 <5 <5 < 10 <6 02/03/2009 03/03/2009 03/31/2009 04/28/2009 06/02/2009 06/30/2009 08/04/2009 09/01/2009 09/29/2009 11/02/2009 12/01/2009 12/28/2009 1 3 2 1 4 3 2 2 4 4 4 3 <1 <4 <3 <1 <4 <3 <3 <2 <5 <5 <4 <4 <3 <8 < 5 <2 <<9 <8. <7 <6 <9 <10 <11 <7 <1 <3 <3 <1 <4 <3 <2 <2 <6 <4 <5 <3 <3 <8 <6 <2 <8 <6 <5 <4 < 10 <9 <9 <6 < 2" <4 <4 < 4 < 4 <3-. <6 <4 <5 <4 <3 <7 < 5 <2 <7 <7 <5 <5 <9 <7. < 8 <7; <5 <1 <11 <4 <11 <2 <10 <1 < 10 <4 <11 <3 <15 <2 <15 <2 <6 <5 <5 <4 <15 <4 < 11 <3 <1 <4 < 3 <1 <5 <4 <,3 <2 <5 <4 <5 <2 < 11 < 25 < 26 <13 < 22 < 23 <-26 < 25 < 19 < 18 < 31 < 30 <3 <7 <7 <4 <6 <5 < 10 <7 <5 <6 < 13 <6 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-2

TABLE C-I1.1 CONCENTRATIONS OF GROSS BETA IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 15F4 15F7 16C2 28F3 12/29/2008 - 02/03/2009 02/03/2009 - 03/03/2009 03/03/2009 - 03/31/2009 03/31/2009 - 04/28/2009 04/28/2009 - 06/02/2009 06/02/2009 - 06/29/2009 06/30/2009 - 08/04/2009 08/04/2009 - 09/01/2009 09/01/2009 - 09/29/2009 09/29/2009 - 11/02/2009 11/02/2009 - 12/01/2009 12/01/2009 - 12/28/2009 3.8 +/- 4.8 +/- 4.9 +/- 2.3 +/- 3.9 +/- 3.7 +/- 4.6 +/- 3.5 +/- 4.0 +/- 2.8 +/- 2.8 +/- 2.6 +/- 1.7 1.6 1.7 1.5 1.7 1.8 1.8 1.7 1.8 1.7 1.7 1.8 4.2 +/- 1.7 4.8 +/- 1.6 5.3 +/- 1.8 4.0 +/- 1.6 3.0 +/- 1.6 6.3 +/- 2.1 5.2 +/- 1.9 2.9 +/- 1.7 3.5 +/- 1.8 4.9 +/- 1.8 2.8 +/- 1.7 2.9 +/- 1.7 4.2 +/- 2.3 3.4 +/- 1.6 4.5 +/- 1.5 3.2 +/- 1.6 5.2 +/- 1.8 2.8 +/- 1.6 7.4 +/- 2.2 4.9 +/- 1.9 3.4 +/- 1.8 < 2.7 3.6 +/- 1.8 3.2 +/- 1.7 <*25 4.0 3.6 3.9 3.1 3.4 < 2.5 4.0 3.0 4.2 3.5 < 2.4 < 2.5 +/- +/- +/- +/- +/- +/- +/- 1.7 1.5 1.6 1.6 1.7 1.8 1.7 1.9 1.8 MEAN 3.6 +/- 1.7 4.2 +/- 2.8 3.6 +/- 0.8 TABLE C-II.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN*THE VICINITy OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 151F4 15F7 16C2 28F3 12/29/2008 - 03/31/2009 03/31/2009 - 06/30/2009 06/30/2009 - 09/29/2009 09/29/2009 - 12/28/2009 < 163 < 131 < 185 < 167 168 +/- 105 < 162 < 133 < 177 < 170 < 137 < 185 < 165 < 156 <.134 < 189 < 167 MEAN 168

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, 2009 RESULTS IN UNITS OF PCI/LITER +/- SIGMA STC COLLECTION PERIOD 15F4 12/29/2008 - 02/03) 02/03/2009 - 03/03, 03/03/2009 - 03/31/ 03/31/2009 - 04/28/ 04/28/2009 - 06/02) 06/02/2009 - 06/29) 06/29/2009 - 08/04; 08/04/2009 - 09/01, 09/01/2009 - 09/29) 09/29/2009 11/02/ 11/02/2009 - 12/01 12/01/2009 - 12/28, Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 2009 /2009 2009 2009 '2009 '2009 '2009 /2009 '2009 '2009 /2009 (2009 <2 <4 <3 < 1 <6 <4 <1 <2 <4 <4 <3 <2 <5 <3 <1 <6 ._3 <1 <2 <4 <3 <4 <3 <4 <10 <6 < 2 <13 < 10 <3 <6 <7 <5 <7 <7 < 2 <4 <2 <1 <6 <4 <1 <2 <4 <3 <4 <2 <4 <8 < 5 <1 < 14 <8 <2 <4 <6 <6 <8 <6 <2 <5 <3 <1 <6 <5 <1 <3 <5 <3 <4 <3 <4 <8 <5 <2 <9 <7 <2 <4 <8 <5 <8 <6 <7 < 12 < 15 < 10 < 14 < 15 <6 < 14 <6 <4 < 12 < 11 <2 <4 <3 <1 <6 <4 <1 <2 <4 <3 <4 <3 <2 <4 <3 <1 <6 <4 <1 <2 <5 <3 <4 <3 < 15 < 28 < 26 < 12

32

< 27 < 10

26

< 19 < 14 < 26 < 21 <4 <9 <7 <3 <9 <7 <3 <8 <5 <4 <9 <7 MEAN 15F7 12/29/2008 02/03/2009 03/03/2009 03/31/2009 04/28/2009 06/02/2009 06/30/2009 08/04/2009 09/01/2009 09/29/2009 11/02/2009 12/01/2009 02/03/2009 03/03/2009 03/31/2009 04/28/2009 06/02/2009 06/30/2009 08/041/2009 09/01/2009 09/29/2009 11/02/2009 12/0.1/2009 12/28/2009 <2 <5 <2 <-1 <5 <4 <2 <2 <6 <3 <4 <3 <2 <5 <2 <1 <6 < 4 <2 <2 <5 <4 <4 <3 <4, <10

5

<3 <9 <10 <5 <5 < 10 <8 <9 <7 <2 <4 <2 <1 <4 <5 <1 <2 <6 <4 <.4 <3 <3 <8 7ýý4 <2 <8 <9 <4 <4 <12 <7 <9 <6 <2 <5 <2 <1 < 5 <2 <2 <6 <4 <5 < 4 <3, < 10 <4 <2 <8 <7 <4 <4 ~< 10 <7o <6 <6 <6 < 15 <13 < 10 < 11 < 15 < 12 <12 <8" <ý5 < 11 < 13 <2 <4 <2 < 1 <5 <4 <2 <2 <6 <3 <3 <3 <2 <5 <2 <1 < 4 <5 <2 <2 <7 < 3 <3 < 1ý3 < 35 < 22 <14 < 27 < 32 < 20 < 21 < 22 < 15 .< 28 < 27 <4 <9 <7 <3 <7 <8 <7 <6 <7 < 8 MEAN C-4

TABLE C-11.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 STC COLLECTION PERIOD 16C2 12/29/2008 - 02/03/2009 02/03/2009 03/03/2009 03/03/2009 - 03/31/2009 03/31/2009 - 04/28/2009 04/28/2009 - 06/02/2009 06/02/2009 - 06/29/2009 06/29/2009 - 08/04/2009 08/04/2009 - 09/01/2009 09/01/2009 - 09/29/2009 09/29/2009 - 11/02/2009 11/02/2009 - 12/01/2009 12/01/2009 -. 12/28/2009 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 <2 <5 <3 <1 <4 <4 <2 <3 <5 <3 <4 <3 <3 <6 <2 <1 <4 <5 <2 <3 <5 <3 <5 <4 <6 < 12 <7 <2 < 11 < 8'- < 4 <7 <8 < 6- < 11 <8 <2 <4 <2 <1 <5 <4 <2 <3 <5 <3 <5 <3 MEAN <5 <11 < 6 <2 < 10 <8 <3 <5 <9 <7 <9 <7 <S., <8 <5 <1 <.11 < 10 <3- < 4 < 11 <6 <9 < 5 <3 <5 <3 < 5 <5 <2 <3 <5 <3 <5 <4 <4 < 11 <65 <.2 <9 <8 <3 <5 <9 <6 < 10 <7 <7 15 < 14 < 10 <10 <15 < 10 <15 <6 <5 <15 < 13 <2 <5 <2 <5 <4 <1 <2 <4 <4 <4 <3 <2 < 5 <3 <1 <5 <4 <2 <3 <5 <4 <5 <4 < 16 < 36 < 24 < 14 < 20 < 30 < 17 < 26 < 20 < 16 < 32 < 27 <6 <i~ <'8 <5 <8 < 12 <5 <8 <5 <4 < 11 < 6 28F3 12/29/2008 - 02/03/2009 - 03/03/2009 - 03/31/2009 04/28/2009 - 06/02/2009 - 06/29/2009 - 08/04/2009 - 09/01/2009 - 09/29/2009 - 11/02/2009 - 1 2/01 /2009'"° 02/03/2009 03/03/2009 03/31/2009 04/28/2009 06/02/2009 06/29/2009 08/04/2009 09/01/2009 09/29/2009 11/02/2009 12/oi/2009 12/28/2009 <2 <4 <3 <1 < 4 <4 <1 <2 <5 <3 <4 <2 <4 <3 <1 <6 <4 <2 <2 <4 <3 <5

"'*3'

<4 < 12 <6 <2 < 12 <9 <3.: <5 <9 <7 <8 <7 <2 <5 <3 <1 <5 < 1' <2 <4 <4 <4 <4 <2 <5 <3 <1 <5 <5 <2 <3 <6 <3 <5 <3 <8 <6 <1 <9 <9 <3 <4 <9 <6 <7 <6 < 14 <12 <8 <10

15

<9 < 14 <6 <4 <15 < 13 <2 <4 <2 <1 <4 <4 <1 <2 <4 <3 <4 <3 <2 <4 <3 <1 <5 <4 <1 <2 <5 <3 <5 <3 < 13

4 30

< 23 <9 < 22 < 27 <15 < 22 < 18 <13 < 29 < 23 <5 < 11 <7 <3 <8 < 11 <4 <8 <7 <5 < 11 <7 <'3 <6 MEAN 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, 2009 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 1-131 Cs-134 Cs-1 37 16C5 PREDATOR 06/25/2009 10/21/2009 MEAN 16C5 BOTTOM FEEDER 06/25/2009 10/21/2009 MEAN 29C1 PREDATOR 05/20/2009 12/18/2009 MEAN 29C1 BOTTOM FEEDER 05/20/2009 12/18/2009 3230 +/- 797 < 50 3790 +/- 874 < 60 3510 792 3840 +/- 818 < 41 3310 +/- 705 < 49 3575 +/- 750 < 49 -< 55

126
144

< 46 < 58 < 84

109

< 213 < 518 < 47 < 52 < 55 < 62 < 51 < 44 < 113 <'119 < 42 < 55 < 92 < 96 < 241 < 323 < 42 < 44 < 47 < 40 2220 +/- 464 3350 +/- 370 2785 +/- 1598 <18 <18 < 17 < 20 < 67 < 39 < 24 < 20 < 44 < 42 < 789 < 27.5 <17 < 20 <-16 < 21 .**j

4350 +/- 919"

< 54 3480 +/- 401 < 21 3915 +/- 1230 < 63 < 21 < 186 < 44 < 48 <21

< 114

-"< 44 < 3620 < 31.8 < 43 < 22 < 46 < 24 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, 2009 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA STC COLLECTION PERIOD Be-7 K-40 Mn-54 Co-58 Co-60 1-131 Cs-1 34 Cs-1 37 I 16B2 06/10/2009 12/16/2009 < 895 1870 +/-721 17800 +/- 1730 16600+/- 1540 17200 +/- 1697 < 78 < 76 < 89 <87 < 59' < 71 < 278 < 745 < 77 < 70 139 +/- 83 166 +/- 54 153 +/- 38 MEAN 1870 16C4 06/10/2009 .12/-16/2009 1990 +/- 829 1660 +/- 967 - 1825 +/- 467 15500 16300 +/- 1480 +/- 1690 < 57 < 41 < 55 < 38 < 71 < 34 < 152 < 456 < 43 < 34 123 83 +/- +/- 56 65 MEAN 15900 +/- 1131 103 +/- 57 33A2 06/10/2009 12/16/2009 < 652 < 523 11800 14900 +/- 1520 +/- 1440 < 82 < 28 < 76 < 32 < 84 < 35 < 243 < 565 < 66 < 22 < 73 108 +/- 85 MEAN 13350 +/- 4384 108

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 SAMPLEr COLLECTED IN THE VICINITY OF LIMERICK GENERATINuG STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2SIGMA GROUP I I GROUP II IGROUP III COLLECTION PERIOD 1 2/9/2uut0 01/05/2009 01/12/2009 01/19/2009 01/26/2009 02/02/2009 02/09/2009 02/17/2009 02/23/2009 03/03/2009 03/09/2009 03/16/2009 03/23/2009 03/30/2009 04/06/2009 04/13/2009 04/20/2009 04/27/2009 05/04/2009 05/11/2009 05/18/2009 05/26/2009 06/01/2009 06/08/2009 06/16/2009 06/22/2009 06/29/2009 07/06/2009 07/13/2009 07/20/2009 07/27/2009 08/03/2009 08/10/2009 08/17/2009 08/24/2009 08/31/2009 09/07/2009 09/15/2009 09/21/2009 09/28/2009 10/05/2009 10/12/2009 10/19/2009 10/26/2009 11/02/2009 11/09/2009 11/16/2009 11/23/2009 11/30/2009 12/07/2009 12/14/2009 12/21/2009 - U]/Ub/2UUY - 01/12/2009 - 01/19/2009 - 01/26/2009 - 02/02/2009 - 02/09/2009 - 02/17/2009 - 02/23/2009 - 03/03/2009 - 03/09/2009 - 03/16/2009 - 03/23/2009 - 03/30/2009 - 04/06/2009 - 04/13/2009 - 04/20/2009 - 04/27/2009 - 05/04/2009 - 05/11/2009 - 05/18/2009 - 05/26/2009 - 06/01/2009 - 06/08/2009 - 06/16/2009 - 06/22/2009 - 06/29/2009 - 07/06/2009 - 07/13/2009 - 07/20/2009 - 07/27/2009 - 08/03/2009 - 08/10/2009 - 08/17/2009 - 08/24/2009 - 08/31/2009 - 09/07/2009 - 09/15/2009 - 09/21/2009 - 09/28/2009 - 10/05/2009 - 10/12/2009 - 10/19/2009 - 10/26/2009 - 11/02/2009 - 11/09/2009 - 11/16/2009 - 11/23/2009 - 11/30/2009 - 12/07/2009 - 12/14/2009 - 12/21/2009 12/28/2009 10S3 22 5 17` 5 18 5 23 +/--5 26 +/- 6 16` 5 9+/--4 12+/- 6 18+/- 5 14+/- 6 23 +/- 5 27 +/- 6 17+/- 9 14 4 17+/- 5 13+/- 5 10+/- 5 16-5 12 4 13 t 5 (1) 7 12 +/- 5 10 +/- 4 <8 12 12 9 19 19 14 14 21 13 11 14 22 13 16 17 9 10 21 15 16 21 19 15 15 21 22 15 +/-5 +/-5 +/-5 +/-5 +/-5 +/-5 -5 +/-6 +/-5 +/-5 +/-5 4 +/-6 +/-5 +/-5 +/-5 +/-5 +/-5 4 +/-5 -5 -5 +/-5 4 +/-5 +/-5 +/-5 11S1 21 +/-5 17 +/- 5 16 + 5 28 +/- 6 22 +/- 5 20 +/- 5 10 +/- 4 14.+/- 6 17 +/- 5 15 +/- 6 23 +/- 5 20 +/- 5 15 +/- 5 9+/-4 18 5 19 5 10 5 15 +/-5 12,+/- 4 11 +/-5 15+/- 5 12 5 10+/- 5 14 4 14+/-5 12 5(1). 21 +/-5 (1) 17+/- 6 18+/- 5 19+/-6 17 6 13 5 12-5 16+/-4 10 6 13 5 13+/-5 15+/-5 11 +/-+5 16 +/- 5 13+/- 4 20 6 14 +/-5 16+/- 5 15+/- 5 18+/- 5 29 +/-+5 17+/- 4 13 +/- 5 1 22 13 19 26 20 21 10 13 20 18 18 '11 10 15 15 14 16 12 10 10 8 11 11 <8. 12 12 1:8 14 18 16 21 13 20 18 16 15 11 15 12 16 25 9 19 20 19 17 17 24 20 13 4S1 -5 -5 +/-5 -6 -5 ,+/-5 ,.4 +/-6 -5,(1) -5 S5: ,- 5. +/-4 -5 +/-5 -5 +5 +/-4 -+5' +4 +/-5 +/-5 -4 -5 +5 +5.. -5 +/-5 +/-5 +/-+ 5. -6 -5 +/- 5 +/-. 5:= +4*, +/-6' +5 -5 +/-5 +/-+5, -+/-6 +/-4" -6 +/-+5 -5 -5 " 5 +/-5 -5 +/-+5. 13C1 19-+ 5 14 +/- 5 20 +/- 5 22 +/- 5 20 +/- 5 ' 22 +/- 5 8+/-4 16+/- 6 15+/- 5 22 +/- 6 22 +/-k, 5 21 +/- 5 12 +/- 5 12 +/- 4 17 +/- 5 18 +/- 5 14 +/- 5 20 +/-,5 8 +/-..4 10 +/- 5. 17 +/- 5 <'7 12 +/- 5 13 +/- 4 9 5 13+/- 5 13+/- 5 14 +/- 5 21 +/- 5 19 +/--6 11 +/-5 20 +/- 5 18 +/- 6

17 +/-+6

.14 5 +/-,ý6 15:++/-4 -'18 +/-"6 14 +/- 5 15 +/- 5 -15: +/- 5 13 5 25 +/- 6 20 +/-+6 18-5 17+/- 5 12+/- 5 34 +/-+5 19+/- 5 12+/-5 U 22G 1 27 +5 22 +/-+5 19+/- 5 22-+5 21 5 20 +/-+5 16 -5. 12 +/- 6 19 -+/- 5 23 +/- 6 19 +/- 5 17-+/-5 16 +/- 5 12 +/-+4 21 +/- 5 16+/- 5 13 +/- 5. 10+/- 1*5: 1,ill : 5 11- +/- 4 11 +/-5' 8+/-5 11 +/-4 7. 11 +/- 5 10+/- 5 10+/-5 17+/- 5 9+/-5

19. + 5 12, +/- 5 16'-

5 14-+/- 5 .13+/-5 18+/-5 .13 +/-+4 12-+6 14+ 5 10+/- 5 20 +/-5. 10+/- 5 24,-6 13;+/- 4 21: 6 19 +/-+5 2C-+5 13 +/- 5 12 1+/-4. 31 +/--5 22 +/- 5 16+/- 5 MEAN 16 +/- 9 16 - 9 16 +/- 9 16 +/- 10 16 +/- 10

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

TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 Lu RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - ON-SITE LOCATIONS GROUP II - INTERMEDIATE DISTANCE LOCATIONS GROUP III - CONTROL LOCATIONS U COLLECTION PERIOD 12/29/2008 - 02/02/2009 02/02/2009 -. 03/03/2009 03/03/2009 - 03/30/2009 03/30/2009 - 04/27/2009 04/27/2009 - 06/01/2009 06/01/2009 - 06/29/2009 06/29/2009 - 08/03/2009 07/28/2009 - 08/31/2009 08/31/2009 - 09/28/2009 09/28/2009 - 11/02/2009 11/02/2009 - 11/30/2009 11/30/2009 - 12/28/2009 MIN MAX MEAN+/- 2SD 13 28 20.6 +/- 8 12/29/2008 9 21 15 +/- 9 02/02/2009 11 27 18.3 +/- 9 03/03/2009 9 19 13.7 7 -03/30/2009 .8 16 12.3 +/- 5 04/27/2009 8 14 11.5 + 3 06/01/2009 9 21 14.8 +/- 8 06/29/2009 11 21,. 16.3 +/- 7 07/28/2009 10 22 14.8 +/- 6 -08/31/2009 9 25 14.4 +/- 8 09/28/2009 14 21 17.5 +/- 5 11/02/2009 13 29 18.7 +/- 10 11/30/2009 COLLECTION PERIOD 02/02/2009 03/03/2009 03/30/2009 04/27/2009 06/01/2009 06/29/2009 08/03/2009 08/31/2009 09/28/2009 11/02/2009 11/30/2009 12/28/2009 MIN MAX MEAN+/- 2SD' 14 22 -19.1 +/-,6. 8 22 15.4 +/- 12 12 22 19.2 +/- 10 12 18 15.3 3.6 8 .20 13.7,+/- 11 9 13 11.6+/- 3 11 21 15.6+/- 8 14 .20 17.5 +/-5. 14 20 16.7 +5 8 25 15.4 +/-12 12 20 16.6+/- 7 11 34 18.9 +/- 21 8 34 16 +/-10 12/29/2008 02/02/2009 03/03/2009 03/30/2009 04/27/2009 06/01/2009 06/29/2009 07/28/2009 08/31/2009 -09/28/2009 11/02/2009 COLLECTION PERIOD 02/02/2009 03/03/2009 03/30/2009 04/27/2009 06/01/2009 06/29/2009 08/03/2009 08/31/2009 09/28/2009 11/02/2009 11/30/2009 MIN MAX MEANi-C, .2SQD'-' 19 27 22.1 +/-6& 12 20- 16.9 +/- 8 1C-23 18.7 +/-6 12 21 15.6 +/- 8 -10 17 12 +/- 6 81 11 10.3 +/- 3. 9 19 13 +/- 9 < 12 16 13.7 +/- 4 12 18 14.1 +/- 5 10 24 15.4 +/- 12 13 21 18 +/- 7 12 31 20.1 +/- 16 11/30/2009 - 12/28/2009 12/29/2008 - 12/28/2009 12/29/2008 -. 12/28/2009 8' .29 .16+/-9 12/29/2008 - 12/28/2009 8 31 16 +/- 10

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

t4 7-TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED INTHE VICiNITY OF LIMERICK GENERATING,STATION',,-2009'" RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA-! -,-`". Cs,- 134 STC COLLECTION PERIOD Be-7 Mn-54 Co-58 Co-60 Cs-137 10S3 12/29/2008 03/30/2009 06/29/2009 03/30/2009 06/29/2009 09/28/2009 90 +/- 34 92 +/- 44 72 +/- 45 .<4 <5 <3 <4 <8 <7 <4 <2 <5 <2 <4 < 3" <is5 <4 <.5 <4 <4 <2 <4 09/28/2009 - 12/28/2009 MEAN 70 +/- 31 < 5 81 +/- 23 1lSi 12/29/2008 03/30/2009 06/29/2009 09/28/2009 03/30/2009 06/29/2009 09/28/2009 12/28/2009 70 108 96 71 +/- 38

69

+/- 47 +/- 37 <3 <6 <4 <3 <5 < 11 <7 <5 <4 <5 <5 <4 < 3 <,5 <4. <5 <3 <3 <3 <<4 MEAN 86 +/- 38 13C1 12/29/2008 03/30/2009 06/29/2009 09/28/2009 03/30/2009 06/29/2009 09/28/2009 1 2/28/2009 92 +/- 34 125 +/- 50 < 97 55 +/- 37 91 +/- 70 <3 <4 <5 <4 <5 <10 <.9 <7 < 3 <4 <3 <5 <3 <"5 <6 <6 <2 '<-4 <4 <4 MEAN 14S1 12/29/2008 03/30/2009 06/29/2009 09/28/2009 03/30/2009 06/29/2009 09/28/2009 12/28/2009 66 +/- 19 79 +/- 36 102 +/- 44 3 3 3 <3 <8 <6 <5 <3 <3 <3 < 4 <2 <4 <3 <4 93 +/- 36 < 5 MEAN 85 +/- 32 <2 <4 <3 <4 <3 <4 <2 <4 22G1 12/29/2008 - 03/30/2009 03/30/2009 - 06/29/2009 06/29/2009 - 09/28/2009 09/28/2009 - 12/28/2009 MEAN 75 +/- 40 116 +/- 96 94 +/- 38 < 67 95 t 41 <3 <6 <3 <4 <4 < 11 <6 <7 <3 <6 <-3 <4 <3 <7' <3. <5

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

TABLE CG-C07'ýCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER -,2 SIGMA U COLLECTION PERIOD" 12/29/;2oo8 u oii5/2 01/05/2009 - 01/12/2009 01/12/2009 - 01/19/20,0oý;,:. 01/19/2009 - 01/26/2009 01/26/2009 - 02/02/2009 02/02/2009 - 02/09/2009 02/09/2009 - 02/17/2009 02/17/2009 - 02/23/2009 02/23/2009 - 03/03/2009 03/03/2009 - 03/09/2009 03/09/2009 - 03/16/2009 03/16/2009 - 03/23/2009 03/23/2009 - 03/30/2009 03/30/2009 - 04/06/2009 04/06/2009 - 04/13/2009 04/13/2009 - 04/20/2009 04/20/2009 - 04/27/2009 04/27/2009 - 05/04/2009 05/04/2009 - 05/11/2009 05/11/2009 - 05/18/2009 05/18/2009 - 05/26/2009 05/26/2009 - 06/01/2009 06/01/2009 - 06/08/2009 06/08/2009 - 06/16/2009 06/16/2009 - 06/22/2009 06/22/2009 - 06/29/2009 06/29/2009 - 07/06/2009 07/06/2009 - 07/13/2009 07/13/2009 - 07/20/2009 07/20/2009 - 07/27/2009 07/27/2009 - 08/03/2009 08/03/2009 - 08/10/2009 08/10/2009 - 08/17/2009 08/17/2009 - 08/24/2009 08/24/2009 - 08/31/2009 08/31/2009 - 09/07/2009 09/07/2009 - 09/15/2009 09/15/2009 - 09/21/2009 09/21/2009 - 09/28/2009 09/28/2009 - 10/05/2009 10/05/2009 - 10/12/2009 10/12/2009 - 10/19/2009 10/19/2009 - 10/26/2009 10/26/2009 - 11/02/2009 11/02/2009 - 11/09/2009 11/09/2009 - 11/16/2009 11/16/2009 - 11/23/2009 11/23/2009 - 11/30/2009 11/30/2009 - 12/07/2009 12/07/2009 - 12/14/2009 12/14/2009 - 12/21/2009 12/21/2009 - 12/28/2009 U los

22
20
50

<13 < 57 < 25 < 48 <7 <18 < 30 <18 < 22 < 49 < 27 < 67 < 23 < 45 < 64 < 64 < 27 <16 < 64 < 54 < 65 < 57 < 44 < 37 < 36 < 20 <12 < 29 < 21 < 56 < 44 < 41 < 66 < 44 < 55 < 53 < 63 < 22 < 63 < 61 < 57 < 25 < 63 < 59 < 59

< 65

< 60 GRC 3 u1S < 39 < 36 < 27 < 23 < 57 < 47 < 48 <17 <18 < 44 < 41 < 27 < 27 < 63 < 67 < 41 < 45 < 64 < 64 (1) < 69 < 48 < 30 < 35 < 54 < 66 < 58 )UP I 14S1 < 54 < 40 < 37

50
23

< 57 < 47

21
17

< 39 <12 < 22 < 30 <9 < 57 < 44 <42 < 67 < 45 < 57 < 55 < 64 < 23 < 28 < 63 < 59 < 25 < 65 < 60 < 60 < 66 < 61 < 45 < 41 < 27 < 49 < 63 < 67 < 41 < 20 < 65 < 64 < 69 < 48 < 30 < 65 < 36 < 66 < 58 (1) < 25 < 38 (1) < 19 < 21 < 22 < 30 < 22 < 58 < 45 < 43 < 67 < 45 < 57 < 55 < 64 < 23 < 65 < 63 < 59 < 25 < 36 < 60 < 61 <-67 < 62 GROUP II 13C1 < 53 < 39

36

< 49 < 23

31

< 47 <48 <17 (1) < 17 < 44 < 41 < 27 < 49 < 62 < 28 < 41 < 45 < 64 < 63 < 68 < 47 < 29 < 63 <54

<29

< 25 < 46 21 37 < 21 < 22 < 23 < 22 < 25 <25 < 24 < 42 <19 < 32 < 24 < 65-

< 17

< 66 < 27 < 33 < 26 < 66 < 33 < 61 29 < 31 I GROUP III 22G 1 < 40 < 37

50
23

< 57 < 48 S<49 <17 <14 < 45 < 42 < 27 < 50 < 63 < 68 < 41, .< 46 < 66 < 32 < 70 < 48 < 30 < 66 .< 54 <64 < 56 < 45 < 37 < 36 < 20 < 21 <29 < 21

<43,

< 42.- < 66 < 43 < 56 < 53 62 < 22 < 63 < 61-- < 58 <15

63

< 59

25
65

< 59 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-1.1

TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA CONTROLFARM I INDICATOR FARM 19B1 COLLECTION PERIOD 01/13/2009 02/10/2009 03/10/2009 04/07/2009 04/22/2009 05/05/2009 05/19/2009 06/02/2009 06/16/2009 06/30/2009 07/14/2009 07/28/2009 08/11/2009 08/25/2009 09/08/2009 09/22/2009 10/06/2009 10/20/2009 11/03/2009 11/17/2009 12/08/2009 23F1 36E1 1 0F4 18E1 25C1 25E1 < 0.5 < 0.5 < 0.5 < 0.8 < 0.5 < 0.3 < 0.6 < 0.4 < 0.6 < 0.6 < 0.4 < 0.6 < 0.7 < 0.6 < 0.6 < 0.6 < 0.4 < 0.4 < 0.9 < 0.6 < 0.7 <,0.7 < 0.6 < 0.2 < 0.4 < 0.6 < 0.6 < 0.7 < 0.9 0*(.6 < 0.5 < 0.8 < 0.5 < 0.9 < 0.6 < 0.6 < 0.7 < 0.9 < 0.7 < 0.7 < 0.8 < 0.4 < 0.3 ,< 0.6 < 0.7 < 0.8 < 0.7 < 0.7 < 0.7 < 0.8 < 0.6 < 0.5 < 0.6 < 0.5 < 0.7 < 0.7 < 0.5 < 0.7 < 0.8 < 0.7 < 0.6 < 0.6 < 0.4 < 0.3 < 0.6 < 0.6 < 0.7 < 0.6 < 0.7 < 0.7 < 1.0 < 0.7 < 0.5 < 0.8, < 0.6 < 0;7 < 0.7 < 0.5 < 0.6 < 0.8 < 0.7 < 0.5 < 0.6 < 0.4 < 0.3 < 0.7 < 0.6 < 0.8 < 0.6 < 0.7 < 0.7 < 1.0 < 0.8 < 0.5 < 0.8" < 0.6 < 0.7 < 0.7.-. < 0.6 < 0.8', < 0.8. < 0.7 < 0.6 < 0.6 < 0.4 < 0.41 < 1.0 < 0.5 < 0.8 (1) MEAN (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-12

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITnERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/-:.2 SIGMA STC, COLLECTION PERIOD 10F4 01/13/2009 02/10/2009 03/10/2009 04/07/2009 04/21/2009 05/05/2009 05/19/2009 06/02/2009 06/16/2009 06/30/2009 07/14/2009 07/28/2009 08/11/2009 08/25/2009 09/08/2009. 09/22/2009 10/06/2009 10/20/2009 11/03/2009 11/17/2009 12/08/2009 MEAN 18E1 01/13/2009 02/10/2009 03/10/2009 04/07/2009 04/22/2009 05/05/2009 05/19/2009 06/02/2009 06/16/2009 06/30/2009 07/14/2009 07/28/2009 08/11/2009 08/25/2009 09/08/2009 09/22/2009 10/06/2009 10/20/2009 11/03/2009 11/17/2009 12/08/2009 MEAN ,K-40 Cs-134 Cs-137 Ba-140 La-140 1220 1240 1220 1260 1200 1190 1390 1210 1200 1450 1220 1370 1180 1370 1210 1350 1220 1170 1370 1290 1370 +/- 41 +/- 122 +/- 84 +/- 42 +/- 37 +/- 48 +/- 50 +/- 100 +/- 167 +/- 58 +/- 142 +/- 124 +/- 108 +/- 163. +/- 137 +/- 99 +/- 115 +/- 116 +/- 118 +/- 76 +/- 124 <1 <5 <3 <1 <1 <2 <1 <4 <7 <2 <5 <2 <4 <9 <6 <4 <4 <5 <4 <3 <5 <2 <6 <3 <2 <1 <2 <1 <5 <7 <2 <7 <.3 <5 <9 <6 <5 <5 <6 <5 <4 <5 <16 <52 15 < 24 .< 22 < 50 <'22 < 44 <ý' 33 < 33 <.39 < 22 < 22 < 43 < 36 < 20 < 22 < 25 -,4*25 <16 < 38 <4 < 14 <4 <8 <6 <14 <5 <14 <7 <10 <14 <8 <6 <11 <10 <6 <5 <7 <7 <5 < 14 1271 +/- 171 1270 1160 1230 1170 1130 1140 1240 1170 1160 1260 1240 1130 1240 1270 1230 1170 1360 1170 1120 1310 1230 49 111 108 52 48 49 40 129 157 46 120 69 106 186 130 98 145 144 112 100 117 <2 <5 <5 <2 <2 <2 <1 <-3 <6 <2 <5 <2 <3 <6 <5 <4 <6 <6 <4 <3 <4 <2 <5 < 5 <2 <2 <2 <2 <4 <7 <2 <6 <3 <4 <8 <6 <4 <8 <6 <4 <4 <5 < 23 < 50 < 24 < 30 < 28 < 47 < 24 < 39 < 25 < 27 < 40 < 20 <17 < 33 < 32 < 20 < 35 < 29 < 27 <19 < 41 <6 <12 '< 7 <10 <8 <14 <7 <11 <8 <8 <12 <5 <5 <11 <10 <4 <9 <9 <8 <4 < 14 1210 +/- 129

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

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITrERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK.GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER + 2 SIGMA STC COLLECTION PERIOD K-40 Cs-134 Cs-137 Ba-140 La-140 1961 01/13/2009 02/10/2009 03/10/2009 04/07/2009 04/21/2009 05/05/2009 05/19/2009 06/02/2009 06/16/2009 06/30/2009 07/14/2009 07/28/2009 08/11/2009 08/25/2009 09/08/2009 09/22/2009 10/06/2009 10/20/2009 11/03/2009 11/17/2009 12/08/2009 MEAN 23F1 01/13/2009 02/10/2009 03/10/2009 04/07/2009 04/21/2009 05/05/2009 05/19/2009 06/02/2009 06/16/2009 06/30/2009 07/14/2009 07/28/2009 08/11/2009 08/25/2009 09/08/2009 09/22/2009 10/06/2009 10/20/2009 11/03/2009 11/17/2009 12/08/2009 MEAN 1330 1330 1270 1320 1110 1180 1260 1170 1130 1240 1230 1210 1280 1380 1220 1310 1320 1120 1320 1270 1340 +/- 50 +/- 101' +/- 100 +/- 50 +/- 47 +/- 46 +/- 50 +/- 112 +/- 176 +/- 38 +/- 140 +/- 99 +/- 141 +/- 154 +/- 138 +/- 99 +/- 112 +/- 116 +/- 134 +/- 69 +/- 80 <2 <4 <4 "<2 <2 <2 < 1 <2 <7 <1 <5 <3 <5 <6 <5 <4 < 4 -< 5

<5

<3 <5 <2 <4 <4 <2 <2 <2 <1 <3 <7 <1 <6 <4 <6 <7 <6 <4 <5 <5 ,<6 <3 <5 1254 +/- 157 <19 < 43 < 20 < 29 < 27 < 47 < 20 < 32 < 30 < 20 < 36 < 29 < 24 <33 < 33 <22 <24 <.26 < 33

<13

< 31 < 15 < 55 < 22 < 28 < 30 < 41 <15 < 39 < 22 < 30 < 44 < 23 <17 < 26 < 38 < 17 . 32 < 30 < 22. < 42 < 30 <6 < 13 <7 <9 < '9 <14 <6 <7 < 10 '<6 '<10 <6 .< 10 <10 < 6 <8 9.. <4 <11 ,i 1320 1230 1240 1280 1190 1260 1310 1190 1240 1240 1340 1250 1300-1370 1150 1150 1270 1270 1190 1620 1200 +/- 41 +/- 121 +/- 112 +/- 55 +/- 47 +/- 46 +/- 47 +/- 102 +/- 133 +/- 48 +/- 142 +/- 130 +/- 102 t 120 ,+/- 171 +/- 93 +/- 136 +/- 123 +/- 105 +/- 155 +/- 92 <1 .< 4 <4 <2 <2 <2 <1 <4 <5 <2 <6 <3 <3 <5 <7 <3 <5 <6 <4 <5 <4 <.2 <5 <4 <2 <2 <2 <1 <4 <5 <2 <7 <3 <4 <6 <8 < 4 <5 <6 <5 <6 <4 <4 <14 <8 <8 <9 < 12 .< 4 < 10 <7 <9 < 1.2 <7 < 6' < 12 <5 < 11 <8 <8 <11 <,9 I. 1267 +/- 200

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

TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 25C1 01/13/2009 02/10/2009 03/10/2009 04/07/2009 04/21/2009 05/05/2009 05/19/2009 06/02/2009 06/16/2009 06/30/2009 07/14/2009 07/28/2009 08/11/2009 08/25/2009 09/08/2009 09/22/2009 10/06/2009 10/20/2009 11/03/2009 11/17/2009 12/08/2009 MEAN 25E1 01/13/2009 04/07/2009 07/14/2009 10/06/2009 36E1 01/13/2009 04/07/2009 07/14/2009 10/06/2009 MEAN K-40 Cs-134 Cs-137 Ba-140 La-140 1370 +/- 52 1260 +/- 104 1450 +/- 91 1440 +/- 58 1230 +/- 48 1300 +/- 48 1320 +/- 53 1090 +/- 135 1310 +/-.126 1350 +/- 49 1290 +/- 138 1310 +/- 104 1300 +/- 123 1240+/- 108 1110 +/- 134 1200 +/- 123 1290 +/- 156 1270 +/- 134 1180 +/- 137 1180 +/- 112 1200 +/- 70 1271 +/- 186 <2 <4 <3 <2 <2 <2 .<2 <5. <5 <2 < 6 <4 <4 ,< 4 <5 <5 <4 <5 <6 <5 <3 <2 <5 <4 <2 <2 <2 <2 <5 <4 <2 <7 <5 <6 <5 <6 <6 <7 <6 <7 <5 <3 < 21 < 42 < 18 < 35 < 29 < 55 < 37 < 46 < 21

28

< 43 < 33 < 29 < 22 < 32 < 27

29

< 31 < 30 < 29 < 26 <6 < 11 <7 <9 <8 <15 < 11 < 10 <7 <8 < 13 < 10 <7 <6 <7 <8 <8 <9 < 12 <8 < 7 (1) 1270 +/- 138 1220 +/- 96 1150 +/- 127 1190 +/- 99 1208 +/- 101 <6 .< 4 <<5 <4 <7 <4 <5 <5 < 39 < 27 < 34 < 22 ,'< 12 "<9 < 11 <6

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM CHANGES SECTION FOR EXPLANATION C-15

TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN BROAD LEAFY VEGETATION SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 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 Cs7i137 11S3 07/20/2009 07/20/2009 07/20/2009 08/12/2009 08/12/2009 08/12/2009 09/24/2009 09/24/2009 MEAN 13S3 07/20/2009 08/12/2009 09/24/2009 Cabbage Collards. Kale Cabbage Collards Kale Cabbage Kale 157 +/- 70 211 +/-159 326 +/- 182 < 67 340 +/- 111 195 - 78

190 401 +/- 337 3980

.4110 5280 2650 2750 3690 3540 3530 +/- 189 +/- 311 +/- 446 +/- 141 +/- 197 +/- 202 +/- 469 +/- 732 <8 < 14 < 13 <6 <6 <6 < 21 < 42 <8 < 13 < 13 <8 <6 <6 < 19 < 45 <7 < 14 < 11 <7 <6 <7 < 22 < 42 < 27 < 52 < 50 < 46 < 38 < 42 < 32 < 58 <7 < 13 < 12 <6 <5 <5 < 20 < 40 <8 <1 14 < 13 <7 <5 <6 < 23 < 42 272 +/- 194 3691 +/- 1656 Swiss Chard Swiss Chard Swiss Chard 342 +/- 235 519 +/- 122 < 235 9120 10300 5950 +/- +/- +/- 514 293 581 < 12 <7 < 25 < 12 <8 < 24 MEAN 431 +/-+ 250 8457 +/- 4499 31G1 07/20/2009 07/20/2009 07/20/2009 08/12/2009 08/12/2009 08/12/2009 09/24/2009 09/24/2009 09/24/2009 Cabbage Pickle Leaves Zucchini Leaves Cabbage Eggplant Leaves Zucchini Leaves Bioccoli Leaves Cabbage Lettuce < 146 1790 +/- 193 1000 +/- 143 638 +/- 79 3000'+/- 122 1900 +/- 96 308 +/- 204 < 242 343 +/- 184 5330 3920 5940 5640 5870 4440 4620 3430 5630 +/- 382 +/- 315 +/- 310 +/- 176 +/- 200 +/- 159 +/- 565 +/- 494 +/- 646 < 14 < 16 < 12 < 15 < 13 < 12 < 6 <.7, <"8 9. <.6 -<7- < 22 < 21 < 24 < 30 < 34 < 31 < 16 <7 < 30 < 17 < 14 < 13 .< 6 <:8 <6 < 20 < 23 < 26 < 46 < 53 < 43 < 12 <6 < 24 <12 <6 < 26 < 50 < 50 < 45 < 47 < 60 < 48 < 32 < 36 < 37 < 12 < 11 < 11 <6 <7 <6 < 21 < 23 <26 < 14 <12 " 12 <6 ,< 9 <6 < 23 < 24 < 34 MEAN 1283 +/- 1986 4980 +/- 1822

THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-16

TABLE C-IX.1 QUARTERLY TLD RESULTS FOR LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH +/- 2 STANDARD DEVIATIONS STATION CODE 2E1 3S1 4E1 5H1 5S1 6C1 7E1 7S1 9Cl 10E1 1 0F3 10S3 11l1 13C1 13E1 13S2 14S1 15D1 16F1 17B1 18S2 19D1 20D1 20F1 21 S2 23S2 24D1 25D1 25S2 26S3 28D2 29E1 29S1 3101 31 D2 31S1 34E1 34S2 36D1 36S2 MEAN +/- 2 S.D. 7.2 + 1.9 7.4 + 0.9 5.4 + 1.3 8.5 +/- 1.5 8.1 + 1.6 7.0 +/- 0.8 7.7 2.0 7.4 + 1.1 7.1 +/- 1.4 7.2 +/- 1.6 7.1 +/-1.4 7.1 +/- 1.2 8.2 +/- 1.6 5.5 1.1 7.2 +/- 1.8 10.8 t 1.5 6.7 +/- 0.9 7.7 1.5 7.4 + 1.3 7.0 + 1.5 8.1 +/- 1.1 7.1 +/- 1.3. 6.8 1.4 7.1 +/- 0.9 6.9 + 1.3 6.7 + 1.0 6.6 +/- 2.0 5.9 + 0.9 6.7 +/- 1.6 6.5 +/- *1.0 6.8 +/- 2.0 6.8 +/- 1.9 6.4 +/- 1.4 8.1 + 1.3 7.3 t 1.2 7.3 +/- 1.4 7.0 .1.2 7.1 +/-1.2 6.7 +/- 1.2. 7.5 + 1.0 JAN - MAR APR - JUN JUL - SEP OCT-DEC 7.5 t 0.6 7.6 +/- 0.7 5.5 +/- 0.5 8.9 +/- 2.2 8.0 +/- 0.9 7.2 +/- 0.8 9.1 + 0.6 7.7 +/- 1.8 7.1 +/- 1.1 7.4 +/- 0.8 7.5 +/- 1.0 7.5 +/- 0.4 - 9.1 +/- 1.7 5.8 +/- 0.6 8.1 +/- 0.5 11.5 +/- 0.7 7.2 +/- 1.2 8.3 +/- 0.9 7.9 +/- 0.6 7.7 +/- 1.1 8.8 +/- 1.0 7.7 +/- 0.5 7.5 +/- 0.4 7.6 +/- 1.7 -7.3 +/- 1.0 6.9 +/- 0.4 6.6 +/- 0.8 6.5 +/- 0.4 7.6 +/--1.4 7.1 +/- 0.5 6.4 +/- 0.5 .7.6 +/- 1.0 7.2 +/- 0.9 8.8 +/- 0.7 7.9 +/- 2.0 8.0 + 1.5 -7.8 +/- 1.3 8.0 +/- 0.8 7.3 +/- 0.6 7.3 +/- 0.2 6.3 +/- 0.5 7.0 +/- 1.7 4.8 +/- 0.5 7.9 +/- 1.0 7.3 +/- 0.9 6.8 +/- 0.6 7.0 +/- 1.0 7.0 +/- 1.1 6.7 +/- 0.6 6.2 +/- 0.3 6.5 +/- 0.2 6.5 +/- 0.4 7.2 +/- 0.6 5.2 +/- 0.5 6.4 +/- 0.6 10.5 +/- 0.8 6.1 +/- 0.4 .7.1 +/- 0.6,. 7.0 +/- 1.2 6.5 +/- 0.7 7.4 +/- 1.0 6.6 +/- 0.4 6.1 +/- 0.6 6.8 +/- 1.1 6.5,+/- 0.7 6.4 +/- 0.3 5.9 +/- 0.7 5.6 +/- 1.1 6.2 3i0.4 6.3 +/- 0.4 6.7 +/- 0.4 5.9 +/- 0.5 6.0 +/- 0.3 7.4 +/- 0.8 6.9 +/- 0.7 6.6 +/- 0.4 6.7 +/- 0.5 6.8 +/- 0.4 5.9 +/- 0.4 6.9 +/- 0.7 8.4 +/- 1.5 7.9 +/- 1.4 6.3 +/- 0.5 9.4 +/- 0.8 9.2 +/- 0.7 7.5 +/- 1.2 7.9 +/- 0.4 8.1 +/- 10 8.1 +/- 0.2 8.2 t 0.6 7.9 t 0.7 7.7 +/- 1.0 8.4 +/- 1.3 6.2 +/- 0.5 7.8 +/- 0.8 11.3 +/- 1.2 6.8 +/- 1.3 8.3 +/- 0.3, 8.1 +/- 1.1 7.7 +/- 0.3 8.1 t 1.7 7.7 +/- 0.4 7.2 +/- 1.1 7.4 +/-1.2 7.6 +/- 0.5 7.3 t 0.8 8.0 +/- 1.3 6.0 +/- 0.7 7.1 +/- 0.6 6.7 +/- 0.7 8.3 +/-t2.7 7.5 +/- 0.7 6.8 +/- 0.6 8.4 t 0.7 7.8 +/- 0.8 7.9 +/- 0.3 7.2 +/- 1.0 7.1 +/- 0.6' 7.0 +/-'0.4 8.0 +/- 0.7 6.7 +/- 0.7 7.1 +/- 0.5 5.1 +/- 0.4 8.0 +/- 0.6 8.1 +/- 0.7 6.7 +/- 0.7 6.9 +/- 0.7 6.9 +/- 0.4 6.5 +/- 0.4 7.1 +/- 0.7 6.5 +/- 0.4 6.7 +/- 0.3 8.2 +/- 0.6 5.0 +/- 0.4 6.4 +/- 0.6 9.9 +/- 1.1 6.6 +/- 1.0 7.0 +/- 0.7 6.8 +/- 0.3 6.3 +/- 0.3 8.0 '+/- 1.7 6.6 0.4 6.3 +/- 0.5 6.6 +/- 0.4 6.3 +/- 0.8 6.2 +/- 0.4 5.9 +/- 0.5 5.6 +/-0.1 5.9 +/-0.3 6.0 0.7 6.0 +/- 0.7 6.0 +/- 0.6 5.8 +/- 0.7 7.7 +/- 0.3 6.7 +/- 0.7 6.9 +/- 0.5 6.4 +/- 0.5 6.6 +/- 0.5 6.5 +/- 0.5 7.9 +/- 1.2 C-17

TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE SITE BOUNDARY, MIDDLE AND CONTROL LOCATIONS FOR LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH +/-2 STANDARD DEVIATIONS OF THEýSTATION DATA COLLECTION PERIOD SITE BOUNDARY +/-+2 S.D. INTERMEDIATE CONTROL JAN-MAR APR-JUN JUL-SEP OCT-DEC 7.9 +/- 2.2 6.9 +/- 2.1 7.9 +/- 2.3 7.0 +/- 2.2 - 7.4 +/-1.7 6.4 +/-1.3 7.6 +/- 1.4 .. 6.4_+/- 1.2 8.9 +/- 0.0 7.9 +/- 0.0., 9.4 +/- 0.0' 8.0 +/- 0.0 TABLE C-IX.3

SUMMARY

OF THE AMBIENTDOSIMETRY PROGRAM FOR LIMERICK GENERATING STATION, .2.009 RESULTS IN UNITS OF MILLI-ROENTGEN/STD. MONTH LOCATION -SAMPLES., ANALYZED[_ý, -PERIOD

"MINiIMUM' PERIOD MAXIMUM.

SITE BOUNDARY INTERMEDIATE CONTROL 645. 92 4 479 1 .11.5 9.1 9.4 PERIOD MEAN +/-2 S.D. 7.4 +/- 2.3' 6.9 +/- 1.8 8.5 +/- 1.6 SITE BOUNDARY STATIONS -i10S3, !11Sl, y1`3S2, 14S1, 18S2, 21S2, 23S2, 25S2, 26S3,, 29S1,31S1,34S2,36S2, 3S1..5S1,7S!, MIDDLE STATIONS - l;0El, iOF3, 13C1, 13E", 15Dl, 16F1, 17B1, 19D1,20D1,20F1, 24D1,25D1,28D2, 29E1,2E', 31D1, 31D2, 3'4EI1, 36D1-, 4E1-,6C1,7E1,9C1, CONTROL STATIONS -{5H1 1 C-18

FIGURE C-3 CONCENTRATIONS OF CS-137 IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2009 E 0,._ CL 1400 1200-1000-800-600-400-20 0 1 0- _3nn-

1

--16B2 16C4 ~LGS CRITICALITY UNIT NO.1: 1212284 16B2-U NIT NO.2:0811/89 I CONTROL33A2LITY A .2 : 08/1118 ,'~~~~~ O T O

32.

I I I I I II I I I I I a II I I a a a a a a a " a a l a a a a a i a a a a a a l r* r' "'a,-- a -. a a a a, a a a a i a 'a a a a a al a a a a a a a a a a a a a a a" a a a a a a ,a a al a

a a

a a l a a a a a a a a a a a a l a a a a a a a a a a a a a a a a a a a a a a a a a a a a a a --L*Jt,/ I I I I I I I I I I I l 82 83 85 86 88 89 91 92 94 95 97 98 00 01

03. 04 06 07 09 Year C -21

FIGURE C-4 MEAN MONTHLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LGS, 1982 - 2009 1'50 -uGroup I 120 -....................... i~ :rin og :b 1] 105 135 GroupII 120 r l ... i* i" r-up 960 T UNI NO. 2: 08118 4 5 ................ L.......

15 W

IF .1 0 60 UI NO 1: 12228 i 4----- 82 84 86 88 90 92 94 96 98 00 02 -04 06-- 08 10 YEAR C - 22

MEAN 50 401 FIGURE C-5 WEEKLY GROSS BETA CONCENTRATIONS IN SAMPLES COLLECTED IN THE VICINITY OF AIR PARTICULATE LGS, 2009 ý E-0 cf) w 30 20 10 0 3 16 9 12 15 18 21 24 27 30 WEEKNO.- 33 36 39 42 45 48 51 C -23

FIGURE C-6 MEAN QUARTERLY AMBIENT GAMMA RADIATION LEVELS (TLD) IN THE VICINITY OF LGS, 1985 - 2009 13-1SITE 12 -'.--INTERMEDIATE CONTROL 1--o--Control 5H1 10 9 9 - A 4 q:I~ 9: I0:,Iq w8 -T A-------------------- 1 5 4-85 86 87 88 89 90 91 92 93-94 -95 96 9798 99 00 01 02 03 04 05 06 07 08 09 10 YEAR NOTE: Control Station 5H1 became the only distant location beginning in 1995 C - 24

-APPENDIX D DATA TABLES COMPARISON AND FIGURES LABORATORY

The following section contains data and figures illustrating the analyses performed by the quality control laboratory, Environmental Incorporated (ENV). Duplicate samples were obtained from several locations and media and split between the primary laboratory, Teledyne Brown Engineering (TBE) and ENV. Comparison of the results for most media was within expected ranges. D-1

- '.L~ 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, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 12/29/08 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/29/09 08/04/09 09/01/09 09/29/09 11/02/09 12/01/09 16C2 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/29/09 08/04/09 09/01/09 09/29/09 11/02/09 12/01/09 12/28/09 2.3 3.82 0.91 1.82 ,2.65 1.93 2.95 1.59 2.22 2.24 1.67 1.01 +/- 1.0 +/- 1.0 +/- 0.5 +/- 0.6 +/- 1.1 +/- 0.8 +/- 1.1 . 0.6 +/- 0.8 +/- 0.6 +/- 0.6 +/- 0.6 MEAN 2.1 +/- 0.4 TABLE D-I.2 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 16C2 12/29/08 - 03/31/08 03/31/08 - 06/29/09 06/29/09 - 09/29/09 09/29/09 - 12/28/09 < 148 < 148 < 148 < 150 MEAN D-3

TABLE D-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 16C2 12/29/09 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/29/09 08/04/09 09/01/09 09/29/09 11/02/09 12/01/09 02/03/09 03/03/09 03/31/09 04/28/09 06/02/09 06/29/09 08/04/09 09/01/09 09/29/09 11/02/09 12/01/09 12/28/09 <3 <3 <3 <1 <6 <7 <2 <5 <4 <3 <5 <3 <3 <17 <3 <5 <4 <4 <3 <3 <2 <12 <3 <4 <3 <2 <3 <2 <3 <11 <3 <3 <5 <4 <3 <9 <3 <8 <2 <2 <6 <3 <5 <4 <3 <8 <3 <8 <4 <2 <7 <3 <4 <5 <4 <4 <5 <4 <11 <7 <4 <7 <4 <3 <19 <3 <3 <6 <4 <3 <14 <7 <4 <8 <4 <3 <16 <5 <3 <4 <3 <3 <12 < 2, <2 <2 <2 <4 <2 <3 <_1 <2 <1 " <3 <1 <3 <3 <3 <5 <3 <2 <2 <4 <4 <3 <2 <7 <9 <5 <5 <2 <3 <3 <4-" <2 <3 <7 <5 <.6 <4. <4 <8 <8 <6 <4 <4 <2 <5 <3 <4 -<2 <'6 <4 <3 <14 <3 <5 <3 <4 <3 < 2 < 19 < 14 < 16 MEAN D-4

TABLE D-II.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD 12/291Ut Ol/5b/uU 01/05/09 01/12/09 01/12/09 01/19/09 01/19/09 01/26/09 01/26/09 02/02/09 02/02/09 02/09/09 02/09/09 02/17/09 02/17/09 02/23/09 02/23/09 03/03/09 03/03/09 03/09/09 03/09/09 03/16/09 03/16/09 03/23/09 03/23/09 03/30/09 03/30/09 04/06/09 04/06/09 04/13/09 04/13/09 04/20/09 04/20/09 04/27/09 04/27/09 05/04/09 05/04/09 05/11/09 05/11/09 05/18/09 05/18/09 05/26/09 05/26/09 06/01/09 11S2 31+/- 4 21 +/- 4 23 +/- 4 33 +/- 4 33 +/- 4 23 +/- 4 18 +/- 3 15 +/- 4 27 +/- 4 28 +/-5 28 +/-4 29 +/-4 17+/- 4 12+/- 3 23 +/-4 29 +/-4 06/01/09 06/08/09 06/16/09 06/22/09 06/29/09 07/06/09 07/13/09 07/20/09 07/27/09 08/03/09 08/10/09 08/17/09 08/24/09 08/31/09 09/07/09 09/15/09 09/21/09 09/28/09 10/05/09 10/12/09 10/19/09 10/26/09 11/02/09 11/09/09 11/16/09 11/23/09 11/30/09 12/07/09 12/14/09 12/21/09 MEAN 06/08/09 06/16/09 06/22/09 06/29/09 07/06/09 07/13/09 07/20/09 07/27/09 08/03/09 08/10/09 08/17/09 08/24/09 08/31/09 09/07/09 09/15/09 09/21/09 09/28/09 10/05/09 10/12/09 10/19/09 10/26/09 11/02/09 11/09/09 11/16/09 11/23/09 11/30/09 12/07/09 12/14/09 12/21/09 12/28/09 20 14 21 23 17 15 .14 8 18 18 17 22 21 23 27 22 21 29 26 25 22 22 18 16 25 14 25 31 24 15 16 35 26 15 (1) +/-4 +/-3 +/-4 +/-4 +/-4 +/-4 +/-3 +/-4 +/-4 +/-4 +/-4 +/-4 +/-4 +/-4 ,(1) +/-4 +/-4 +/-4 +/-4 +/-4 +/-5 +/-4 +/-4 +/-4 +/-4 +/-4 +/-4 +/-4 +/-4 +/-4 +/-4 +/-4 +/-4 +/-4 +/-4 22 +/- 12 (1) See Program Exceptions for Explahation D-5

TABLE D-1I.2 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES 'COLLECYEII IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD 11S2 12/29/09 03/30/09 03/30/09 06/29/09 06/29/09 09/28/09 09/28/09 12/28/09 MEAN Be-7 Mn-54 Co-58 Co-60 Cs-134 Cs-137 84 +/- 14 < 0.5 91++/-.7 < 1.1 103 +/- 15 < 0.8 63 +/- 14 < 0.5 < 0.6 < 1.1 < 0.6 < 0.9 < 0.6 .- <0.8 < 0.6 < 0.9 < 0.7 < 0.9 < 0.8 < 0.6 < 0.5 <'0.6 < 0.5 85 +/- 34 D-6

TABLE D-III.1 CONCENTRATIONS OF 1-131 BY CHEMICAL SEPARATION AND GAMMA EMITTERS IN MILK SAMPLES COLLECTED-IN THE VICINITY OF LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 19B1 01/13/09 04/07/09 07/14/09 10/06/09 MEAN 10F4 01/13/09 04/07/09 07/14/09 10/06/09 MEAN 25C1 01/13/09 04/07/09 07/14/09 10/06/09 131 K-40 Cs-1 34 . Gs-137 Ba,1 40 La-140 < 0.22 < 0.15 < 0.15 < 0.4 1356 1359 1290 1333 +/- 126 +/- 118 +/- 110 +/- 120 <5 <4 <3 <4 <4 <4 <3 <4 19 16 11 13 <3 <3 <2 <3 1335 +/- 64 < 0.22 < 0.16 < 0.28 < 0.14 1382 1398 1454 1249 +/- 127 +/- 121 +/- 43 +/- 119 <4 <5 <1 <3 <3 <4 <1 <3 23 12 6 15 <3 <4 <2 <5 1371 +/- 173 < 0.21 < 0.14 < 0.28 < 0.25 1419 1505 1362 1459 +/- 130 +/- 105 +/- 119 +/- 112 <4 <4 <7 <4 <2 <3 <6 <4 < 23 < 16 < 20 < 19 <3 <4 <4 <3 MEAN 1436 +/- 121 D-7

FIGURE D-1 COMPARISON OF MONTHLY TOTAL GROSS BETACONCENTRATIONS IN DRINKING WATER SAMPLES SPLIT BETWEEN ENV AND TBE, 2009 10 9 -u--ENV 6 I A 6S 5------- lý------------------------------------------------- ,A* -\\ 4** .. l \\....... / 1,=...... ....... -.......................-,,......... I............................. ol

1.

O I8 J n-. FeAa-p.ay J n J . A g.. e c N v ~ MONTH D-8

FIGURE D-2 COMPARISON-OF WEEKLY GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED FROM LGS COLLOCATED LOCATIONS 11Si AND 11S2, 2009 50 11S2-ENV -11S1-TBE 40.......................................................... ,. ~~ ~ ~ ~ ~ ~ ~ ~...... &4 A A 30

o........

.,,*... *....:': *r-.......................... :................... 1 4 7 10 13 16 19 22 25 28 31 34 37 40 43 46 49 52 WEEK NO. D-9

I C. Intentionally Left Blank D-IO

APPENDIX E INTER-LABORATORY COMPARISON PROGRAM

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 1 OF 3) Identification Reported Known Ratio (c) Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d) March 2009 E6533-396 E6534-396 E6536-396 E6535-396 June 2009 E6742-396 E6743-396 E6745-396 Milk Milk AP 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 Ce-1 41 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 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 pCi pCi pCi pCi pCi pCi pCi pCi pCi 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 pCi pCi pCi pCi pCi pCi pCi pCi 102 14.9 66.7 87.5 275 82.0 111 114 136 112 160 142 120 385 113 149 153 155 118 195 190 82.8 107 19.0 98.1 260 389 144 185 86.9 133 126 173 298 186 262 101 135 61 83.1 84 137 202 92.2 97.7 15.6 79.3 94.9 305 93.7 111 119 128 99.9 156 142 115 371 114 135 145 155 121 189 173 79.4 112 16.7 102.0 284 400 166 192 91.9 137 122 175 312 163 231 95 111 53 79 70 101 180 95.8 1.04 0.96 0.84 0.92 0.90 0.88 1.00 0.96 1.06 1.12 1.03 1.00 1.04 1.04 0.99 1.10 1.06 1.00 0.98 1.03 1.10 1.04 0.96 1.14 0.96 0.92 0.97 0.87 0.96 0.95 0.97 1.03 0.99 0.96 1.14 1.13 1.06 1.22 1.16 1.05 1.19 1.36 1.12 0.96 A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A Milk Milk AP Sr-89 Sr-90 1-131 Ce-1 41 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 A A A W A A A N (1) A E6744-396 Charcoal 1-131 pCi A E-1

TABLE E-1 ANALYTICS ENVIRONMENTAL, RAD:OACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 2 OF 3) Identification Reported Known Ratio (q) Month/Year .. Number Matrix Nuclide Units, Value (a) Value (b) TBE/An aytic .Evaluation (d) September 2009 E6897-396 Milk Sr-89 Sr-90 E6898-396 Milk E6900-396 AP E6899-396 Charcoal 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 1-131 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 pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi/L pCi/L 89.2 249 213 104.0 172 96.3 201 154 213 154 181 145 71.8 115 62 129 97 110 98.7 89.5 113 17.4 107 18.8 98.6 275 221 123 185 99.4 206 147 204 160 161 130 72 109 58 121 98 120 94.1 92.3 131 17.9 1.06* 0.93 0.90 0.91 0.96 0.85 0.93 0.97 0.98 1.05 1.04 0.96 1.12 1.12 0.99 1.06 1.06 1.07 0.98 0.92 1.05 0.97 A A December 2009 E6946-396 Milk E6947-396 Milk Sr-89 Sr-90 131 19.3 1-131 Ce-1 41 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L. pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 79.2 87.3 193 202 512 548 222 253 163 179 200 211 178 178. 176 178 326 345 240 256 103 103 290 280 116 129 93.4 91.5 111 108 81.0 90.8 106 90.8 155 176 135 131 1.00 1.08 0.91 0.96 0.93 0.88 0.91 0.95 1.00 0.99 0.94 0.94 1.00 1.04 0.90 1.02 1.03 0.89 1.17 0.88 1.03 A A A A A A A A A A A A A A A A A A A A A E6949-396 AP" E-2

TABLE E-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 3 OF 3) Identification Reported Known Ratio (c) Month/Year Number

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

December 2009.E6948-396 Charcoal 1-131 pCi 93.3 93.9 *. 0.99 A. (1) Detector 7 appears to have a slightly high bias. Detector 7 was removed from service until it can be recalibrated. NCR 09-23 (a) Teledyne Brown Engineering reported result. (b) The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) Ratio of Teledyne Brown Engineering to Analytics results. (d) Analytics evaluation based on TBE internal QC limits: A= Acceptable. Reported result falls within ratio limits of 0.80-1.20. W-Acceptable with warning. Repoiled result falls within 0.70-0.80 or 1.20-1.30. N = Not Acceptable. Reported result falls outside the ratio limits of < 0. 70 and > 1.30. E-3

TABLE E-2 ERA ENVIRONMENTAL RADIOACTIVITY CRCSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 1 OF 1) Identification Reported Known Month/Year Number Media Nuclide Units Value (a) Value'bjiý " Control Lim its",",'Evaluation (c) April 2009 RAD 77 Water Sr-89. Sr-90 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Gr-A Gr-B 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 P5Ci/L pCi/L pCi/L fpCi/L pCi/L pCi/L pCi/L -.pGi/L pCi/L.- '57.4ý 30.6 55.2 65.8 157 86.4 85.5 47.7 45.2 25.2 19733 64.75 30.30 97.9 76.8 59.9 121 115 19:6, 28.5 22A1 16133 48.3 31.4 52.7 72.9 168 88.9 84.4 54.2 43.5 26.1 20300 62.2 30.7 92.9 79.4 54.6 117 99.5 23.2 26.0 22.2 16400 37.8 - 55.7 22.9 - 36.4 43.4 - 58.3 59.5 - 80.2 151 - 187 80.0- 100 76.0- 101 28.3 - 67.7 29.1 - 50.8 21.7-30.8 17800 - 22300 50.2 - 70.1 22.4 - 35.6 78.3-102 65.0 - 87.3 49.1 -62.9 105-131 89.6-119 11.6 - 31.1 16.2 - 33.9 18.4 -26.5 14300 - 18000 N (1) A A A A A A A A A A October 2009 RAD 79 Water Sr-89 Sr-90 Ba-i33 Cs-134 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131. H-3 A A A A A A A A A A A (1) Calculation did not allow for Y-90 ingrowth on the Sr-89 mount. NCR 09-14 (a) Teledyne Brown Engineering reported result. (b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit. E-4

TABLE: E-3 DCH'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) TELEDYNE BROWN ENGINEERING, 2009 (PAGE 1 OF 2) Identification Reported

Known, Acceptance Month/ear Number Media Nuclide Units Value (a)

Value (b) Range Evaluation (c) March 2009 09-MaW20 Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Bq/L Bq/L Bq/L BqIL BqIL Bq/L Bq/L Bq/L Bq/L Bq/L 09-GrW20 Water Gr-A' Gr-B 09-MaS20 Soil Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-55 09-RdF20 AP Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bqfsample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 18.8 0.06 17.0 16.1 332 13.8 6,88 13.2 0.53' 1.87 433 649 -0.1201-3.91 339 644 245 272 2.77 1.41 1.24. 1.33 2.42 0.71 1.30 0.635 >0.0 - 1.27 1.27 0.64-1.91 467 327 - 607 605 424 - 787 (1) 4.11 (2) 307 215-399 570 399-741 257 180-334 242 169-315 22.5 18.9 17.21 330.9 14.7 7.21 13.6 18.5-29.3 (1) 13.2-24.6 12.1 -22.4 232 - 430 10.3-19.1 5.05-9.37. 9.5-17.7 A A A A A A A A A A A A A A A A A A A A A A A A A A A 2.93 1.52 1.30 1.22 2.27 0.64 1.36 2.05 - 3.81 1.06-1.98 0.91 - 1.69 0.85 - 1.59 1.59 - 2.95 0.45 - 0.83 0.95-1.77 09-GrF20 AP Gr-A Bq/sample 0.19 0.35. >0.0 - 0.7 Gr-B Bq/sample 0.31 0.28 0.14 - 0.42 March 2009 09-RdV20 Vegetation Cs-1 34 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 September 2009 09-MaW21 Water Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 3.48 1.15 3.12 -0.01 2.98 64.1 1.09 1.73 26.5 37.2 32.2 14.0 705 -0.1015 13.9 26.2 1.27 9.70 3.40 2.38 - 4.42 0.93 0.65 - 1.21 2.36 1.65 - 3.07 (1) 2.30 1.61 - 2.99 (4) 1.26 0.88 - 1.64 1.35 0.95-1.76 32.2 22.5 - 41.9 41.2 28.8 - 53.6 36.6 25.6 - 47.6 15.40 10.8 -20.0 634.1 443.9 - 824.3 (1) 12.99 9.09-16.89 26.9 18.8 - 35.0 1.047 >0.0 - 2.09 7.53 3.77 - 11.30 A W N (3) A W A W A A A A A A A A A A 09-GrW21 Water Gr-A Gr-B E-5

TABLE E-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (Mti *EP) TELEDYNE BROWN ENGINEERING, 2009 (PAGE 2 OF 2) Identification Reported... Known Acceptance' Month/Year Number Media. Nuclide Units Value (a) Value (b) Range Evaluation (c) September 2009 09-MaS21 Soil Am-241 Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/kg Bq/kg Bq/kg Bq!kg Bq/kg Bq/kg Bq,/kg Bq/kg Bq/kg 74.7 0.6 706 606 350 876 425 505 1370 89.8 669 586. 327.000 796 375 455 1178 62.9-116.7 ... (1).. 468 - 870 410.- 762 229..- 425' 557'- 1035 263-488 319-592 825 - 1531, (1). 0.98 - 1.82 4.54 - 8.42 0.72 - 1.34 ,3.84 - 7.14 .0.59:R 1.0,9.0'9 2.75 -5.-11 A A. A A A A A A A A A A A A -A A 09-RdF21.., AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 Bq/sample Bq/sample. Bq/sample Bq/sainple Bq/sample Bq/sample Bq/sample -0.02 1.4 5.98 1.01

5.16 0.93 4.39 1.4 6.48 1.03 5.49,-

0.08 3.93 09-GrF21 AP Gr-A Bq/sample 0.36 Gr-B Bq/sample 1.40 09-RdV2-1 Vegetation Cs-134 Cs-137 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample -0.0027 2.36 .2.58 8.36 57.8 1.73 -0.59 0.66 >0.0 - 1.32 1.32 0.66-1.98 (1) 2.43 1.70-3.16 2.57 1.80 - 3.34, 7;9 5.5,-10*3 (4) 1.78 1.25-2.31 (1) A A A A A A A A (1) False positive test. (2) Sensitivity evaluation. (3) Homogeneity problem. MAPEP requires using entire sample but due to geometry limitations we can only use part of the sample. NCR 09-13 (4) Not evaluated by MAPEP. (a) Teledyne Brown Engineering reported result. (b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation. (c) DOE/MAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable. E-6

TABLE E-4 Lab Code M31WA (a) STATISTICAL

SUMMARY

PROFICIENCY TESTING ENVIRONMENTAL, INC., 2009 (Page 1 of 1) PROGRAMa Concentration piL Date Analysis Laboratory Resultb ERA Resultc Control Limits Acceptance STW-1181 STW-1 181 STW-1182 STW-1 182 STW-1 182 STW-1 182 d STW-1 182 STW-1 183 STW-1 183 STW-1 184 STW-1 1866 STW-1 193 STW-1 193 STW-1 194 STW-1 194 STW-1 194 STW-1194 STW-1 194 STW-1 195 STW-1 195 STW-1 196 STW-1198 04/06/09 r, 04/06/09. 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/0.6/09 04/06/09 04/06/09 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131, H-3 41.0 +/- 5.8 32.4 +/- 2.4 44.6 +/- 3.1 81.0 +/- 3.1 65.6 +/- 5.2 147.7 +/- 5.3 79.8 +/- 7.5 47.6 +/- 2.1 38.5 +/-1.3 24.4+/-. 2.5 22819.0 4 453.0 53.0 +/- 6.0 31.1 +/-2.2 82.5.4: 3.5 - 116.8 +/- 3.3 78.8 +/- 5.7 54.2 3.7 .102.5 +6.2 20.3 _2.0 23.7 +/- 1.4 22.4 +/-1.4 17228.0 +/- 694.0 48.3 31.4 52.7 88.9 72.9 168.0 84.4 54.2 43.5 26.1 20300.0 37.8 - 55.7 22.9 - 36.4 43.4 - 58.3 80.0 - 100.0 59.5 - 80.2 151.0 - 187.0 76.0 - 101.0 28.3 - 67.7 29.1 - 50.8 21.7 - 30.8 17800.0 - 22300.0 Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Fail 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-134' Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 62.2 30.7

92.9 117.0

.78.8 54.6 99.5 23.2 26.0 22.2 16400.0 50.2 - 70.1 22.4,- 35.6 78.3 - 102.0 105.0 - 131.0 65.0 - 87.3 49.1 -62.9 89.6-119.0 11.6 -31.1 16.2 - 33.9 18.4 - 26.5 14300.0 - 18000.0 Pass Pass Pass Pass Pass Pass Pass 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 Assc (ERA). Unless otherwise indicated, the laboratory result is given as the mean +/-t standard deviation for three determinations. c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. d All gamma -emitters showed a low bias. A large plastic burr found on the base of the Marinelli kept the beaker from sitting directly on the detector. Result of recount in a different beaker, Cs-137, 155.33 +/- 14.55 pCi/L. e Samples were recounted and also reanalyzed. A recount of the original vials averaged 23,009 pCi/L. Reanalysis results were acceptable, 19,170 pCi/L. E-7

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2009 (Page 1 of 2) Concentration.b Known Control Lab Code c Date 'Ana!ysis Laboratory result Activity Limits d .. :::'- -Acceptance STW-1 170 STW-1170 STW-1 170 STW-1 170 e STW-1 170 STW-1 170 STW-1 170 STW-1 170 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 Co-57 Co-60 Cs-1 34 Cs-137 H-3 Mn-54 Sr-90 Zn-65 19.6 +/- 0.4 16.6 +/- 0.3 20.4 +/- 0.5 0.1 +/-0.2 359.9 +/- 33.9 15.0 +/- 0.4 7.9 +/- 1.4 14.0 +/- 0.7 0.56 +/- 0.06 1.29 +/- 0.05 18.9 17.2 22.5 0.0 330.9 14.7 ,7.2 13.6 0.64 1.27 STW-1171 01/01/09 Gr. Alpha STW-1171 01/01/09 Gr. Beta 13.2-224.6 12.1 -22.4, 15.8 - 29.3 0.0 - 1.0 231.6 - 430.2 p10.3 -19.1 5.1 -9.4 9.5 -17.7 0.00 - 1.27 0.64.- 1.91 0.0 - 1.0, 327.0 - 607.0 424.0 - 787.0 360.4 - 669.4 215.0 - 399.0 180.0 - 334.0 169.0 - 315.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STSO-1 172 e STSO-1 172 STSO-1 172 STSO-1 172 STSO-1 172 STSO-1,172 STSO-1 172 STVE-1 173 STVE-1 173 e STVE-1 173 STVE-1 173 STVE-1 173 STVE-1 173 STAP-1 174 STAP-1174 STAP-1 174 STAP-1 174 STAP-1 174 STAP-1174 f STAP-1 174 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 Co-57 Cs-134 Cs-1 37 K-40 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Zn-65 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 0.0 +/- 0.0 458.6 +/- 7.4 652.3 +/- 3.5 636.4 +/- 9.5 346.4 +/- 3.1 180.6 +/- 12.1 268.3 +/- 4.0 ,0.0 467.0 605.0 570.0 307.0 257.0 242.0 Pass Pass Pass Pass Pass Pass Pass 12.75 - 0.11 0.06 - 0.09 3.49 +/- 0.22 1.01 - 0.11 2.52 +/- 0.14 1.52 +/- 0.18 1.25 +/- 0.05 1.17 +/- 0.06 2.67 +/- 0.14 1.53 +/- 0.08 2.34 +/- 0.09 0.93 +/- 0.14 1.44 +/- 0.14 0.22 +/- 0.03 0.36 +/- 0.04 37.2 +/- 1.5 15.1 +/- 0.9 30.3 +/- 2.1 41.9 +/- 1.8 680.3 +/- 33.6 0.01 +/- 0.26 12.9 +/- 1.7 28.5 +/- 2.4 2.36 0.00 3.40 0.93 2.30 1.35 1.30 1:22 2.93 1.52 2.27 0.64 1.36 0.35 0.28 36.60 15.40 32.20 41.20 634.10 0.00 12.99 26.90 1.65 - 3.07 0.00-1.00 2.38 - 4.42 0.65 - 1.21 1.61 -2.99 0.95-1.76 0.91 -1.69 0 1.59 2.05 - 3.81 1.06-1.98 1.59 -2.95 0.45 - 0.83 0.95 -1.77 Pass Pass Pass Pass Pass Pass Pass Pass. Pass Pass Pass Fail Pass STAP-1175 01/01/09, Gr.Alpha STAP-1175 01/01/09 Gr. Beta STW-1192 STW-1 192 STW-1192 STW-1 192 STW-1192 STW-1192 e STW-1 192 STW-1 192 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Co-57 Co-60 Cs-134 Cs-137 H-3 Mn-54 Sr-90 Zn-65 0.00 - 0.70 0.14 -0.42 25.6 - 47.6 10.8-20.0 22.5 -41.9 28.8 - 53.6 443.9 - 824.3 0.0-1.0 9.1 -16.9 18.8 - 35.0 .Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass E - 8

TABLE E-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP). ENVIRONMENTAL, INC., 2009" (Page 2 of 2) Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STW-1191 07/01/09 Gr. Alpha STW-1191 07/01/09 Gr. Beta 0.88 +/- 0.07 ,7.29 +/- 0.10 1.05 7.53 0-2.1 3.77 - 11.3 STSO-1 188 STSO-1 188 STSO-1 188 STSO-1,188 STSO-1 188 STSO-1 188 STSO-1 188 g STSO-1 188 STVE-1-190 STVE-1 190 STVE-1190 STVE-1 190 STVE-1 190 STVE-1 190 STAP-1189 STAP-1189 STAP-1 190 STAP-1 190 STAP-1190 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09' 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Sr-90 Zn-65 Co-57 CoL60 cs-134 Cs-137 Mn-54 Zn-6.5 674.60 356.40 0.20 767.50 433.00 931.60 3i0.50 1433.90 - 9.00

6.30

+/- 1.90 +/- 12.00- - 37.20 + 14.10 +/- 12.20

25.20 07/01/09 Gr. Alpha 07/01/09 Gr. Beta 8.90 +/- 0.60 2.50 +/- 0.36 0.01 +/-_0.11 2.42 +/- 0.16 8.35 +/- 0.70 0.01 +/- 0.26 0.33 +/- 0.04 1.57 +/- 0.07 6.78 +/- 0.27 1.06 +/- 0.18

'0.0'1 +/- 0.06 1.49 +/- 0.27 6.00 +/- 0.45 079 +/- 0.13, 4.55 +/- 0.66 586 327 0 669 375 796 455 '1178 8.00 2.57 0.00 2.43 7.90 0.00 0.66 1.32 6.48 ,1.03 0.00 1.40 5.49 0.84 3.93 410 -762 229 - 425 0 0-1.0 468 - 870

263 - 488 557 - 1035 319-592 825-1531 5.60 - 10.40 1.80 - 3.34 0 -0.10
1.70 -3.163

'5.50 - 10.30 0 -0.10 Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass-Pass Pass Pass Pass Pass 0-1.32 0.66 -1.98 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 4.54 '0.72 0.01 0.98 23.84 0.59 ,2.75 - 8.42' -1.34 - 0.05 -1.82 -7.14. -1.09. -5.11 Pass Pass Pass Pass Pass Pass Pass Pass Pass t a Results obtained by Environmental, Inc., Midwest Laboratory'asa participant in the Department of. Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idahb Falls, Idaho' b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation). c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation)., d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. e Included in the testing series as a "false positive". No reason was determined for the initial high results. The analysis was repeated; result of reanalysis; 0.54 +/-0 0. 12 Bq/filter. g Incomplete separation of strontium from calcium could result in a higher recovery percentage and consequently lower reported activity. The analysis tEas ?epeated; result of reanalysis 363.3 : 28.6 Bq/kg.

4 Intentionally Left Blank E - 10

APPENDIX F ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)

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ý.. V-4 1.,i "

I r-t* .1 jlý

Docket No: 50 - 352 50 - 353 LIMERICK GENERATING STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2009 Prepared By Teledyne Brown Engineering Environmental Services Exeion. Nuclear Limerick Generating Sanatoga, PA April 2010

Table Of Contents I. Sum mary and Conclusions.............................................................................................. 1 I1. Introduction..................................................................................................................... 3 A. Objectives of the RG PP................................................................................. 3 B. Im plementation of the Objectives................................................................... 3 C. Program Description.................................. 4 D. Characteristics of Tritium (H-3)...................................................................... 5 II1. 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 Discussion......................................................................................... 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.......................................................................................................... 13 G. Investigations............................................................................................... 13 H. Actions Taken............................................................................................... 13 V. References................................................................................................................... 14

Appendices Appendix A Location Designation Tables Table A-1 -ý_Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2009 Figures Figure 1 Routine *Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2009 Appendix B Data Tables,. Tables Table B-1.1 Concentrations of Tritium, Strontium-90, Gross Aloha and Gross Beta in Well Water Samples Collected as Part of the Radiological Groundwater Protection, Program,- Limerick Generating Station, 2009. Table B-1.2 Concentrations of Gamma Emitters in Well Water Samples Collected as Part of the Radiological: Groundwater Protection Program, Limerick GeneratingStation-,; 2009, Table B-1.3 Concentriations of Hard-To-Detects in-Well Water Samples C illected as Partof the"Radiological Groundwater Protection Program, Limerick SGeneirAting Station,!;2009.' Table B-I11 Concentrations of Tritiumn,"Strontiurn-90', G*rbss Alpha and Gross Beta in Surface Water Saniples'Collected asPartof the Radiological Groundwater Protection.Program,: LimerickGenerating Station, 2009. Table B-11.2 Concentriations'of Gamma Emitters 'in Surface Water amples -Collected as Part of the.Radiological Grpundwater Protection Program, Limerick Generating Station,,2009. ii

Summary and Conclusions This report on the Radiological Groundwater Protectibn Program (RGPP) conducted for the Limerick Generating Station (LGS) by Exelon Nuclear covers the period 01 January 2008 through 31 December 2008. During that time period, 264 analyses were performed on 44 samples from. 15 groundwater and 7 surface water locations collected from the environment, both on and off station property in 2009. There was one known release into the groundwater at the Limerick Generating Station that occurred from a leak from the exterior walls of both Ul and U2 condenser bays. The condensation was observed dripping directly to open-ground and asphalt,.One well (LM-MW-9) located near'the Unit 1 Condensate Storage Tank had a tritium value as high as 1750 pCi/L.. Tritium was not detected in any of the groundwater or surface water samples at concentrations greater than the United States Environmental Protection Agency (USEPA) drinking water standard (and the Nuclear Regulatory Commission Reporting Limit) of 20,000 pCi/L. Low levels of tritium were detected at three of the 15 groundwater monitoring locations. The tritium concentrations ranged from 189 to 1750 pCi/L. Strontium-90 was not detected in either the, groundwater or surface water samples. Gross Alpha and Gross Beta analyses in the dissolved land suspended fractions performed on groundwater surface water samples during the second sampling in 2009. Gross Alpha (dissolved) was detected in 9 of 15 groundwater and 1 of 7 surface water locations. The concentrations ran'ged from 2.1 to 9.1 pCi/L. Gross Alpha (suspended) was detected in 5 of 15 groundwater.locations. The concentrations ranged from 1.6 to 7.5 pCi/L. Gross Beta (dissolved) was detected in all 15 groundwater and 6 of 7 surface water locations. The concentrations ranged from26 to 17 pCi/L. Gross Beta (suspended) was detected in 3 of 15 locations. The concentrations ranged from 4.3 to 11 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 in four of five groundwater monitoring locations. The U-233/234 concentrations ranged from 0.9 to 2.3 pCi/L and the U-238 concentrations ranged from 0.5 to 1.8 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 0.1 8.1 mrem to a child (total body), which was 3.20% 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 Stationhad no adverse radliological impact on the environment offsite of. LGS.:.." 4 ' Ii 2

11. ý lntýoduction 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 criticalon 11 August 1989. The site is located in Piedmont countryside, transversed by numerousvalleys 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 2009. 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 as well as the public on an Exelon web site in station specific, reports. www.exeloncorp.com/ourcom panies/powercien/n uclear/Tritium.htm

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 Gene rating Station,tajffand consultinghydrogeologist assess analytical resultsý on an ongoing blasis to identify adverse trends. C. Program Description Samples for the pngoing glround water`rmoniitorinrg program were collected for Exelon Nuclear by Normanrdeau Associates, 'Inc. (NAI). This section describes the generat collection mebtho0ds used to obtain environmental samples for the, LGS RGPP in 2009. Sample locations can be found in Table A,l, 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 mrethods. Sample locations, sample collection frequen'cies and analytic i frequencies were controlled in accordance with approved Station po'0cedires. Contractor and/or station personnel were trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events. Analytical laboratories were subject to internal quality assurance programs, industry cross-check programs, as well as nuclear industry audits. Station personnel reviewed and evaluated all analytical data deliverables as data were received. 4

..'Both station,personnel and, an independent hydrogeologist reviewed analytical data results for adverse trends or changes to h'ydrogeologIc 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

hydrogeh.

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 .6learance rate characterized byan effective biological half-life of about 14 days'. Within:odne r 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. Tritiurfi is alsb 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 pr6duce 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 approoximately 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 radionuc!ides 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 toanalyze the environmental samples for radioactivity for the Limerick Generating Station RGPP in 2009. 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 Suspendediand Gross Beta, Dissolved and Suspended in groundwater and surface water.

3.

Concentrationsof gamma emitters in groundwater and surface water.

4.

Concentrations of strontium in. groundwater and surface water.

5.

Concentrations of Am-241" in g r wter.

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 (ILLD) 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'analyseswere 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. Statisticaily, 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'staridards,ý,sample volume or weight measurements, sampling uncertainty and other, factors. Exelon reports the uncertainty of a measurerhient 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 Thepurpose 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 asjfrom .anthropogenic (i.le., 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 lrocks by neutrons produced by the radioactive decay of naturally , I/ 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 significan't amounts of tritium to the atmosphere. The Canadianjlheavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environmentjý

b.

Precipitation Data Precipitation samples are routinely collected at stations 8

around the world for theanalysis of tritium and other

,radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes inPrecipitation (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 1,963. This peak, which approached 10,000 pCi/L for some stations, coincided with the atmospheric testing of thermbihudlear 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 pCiIL 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 1,960s 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 r eported '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" 2The 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 ditferent 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, C~o-58, Fe-59, Co-60, Zn65, Nb-95, Zr-95, 1-131,; Cs-134,. CS-i37, 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 1,750 pCi/L. Well MVW.-LRg-9had the highest yalue of 1,75Q pCi!L. Although no drinking water pathway is available from groundwater, th. theoretical dose via the drinking water pathway was calculated at Q.181 mrem to a child (total body), which represents,3.02% 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) GrossAlpha and Gross Beta analyses in the dissolved and suspended fractions were performed on groundwater surface water samples during the second sampling in 2009. Gross Alpha '(dissolved) was detected in 9 of 15 groundwater locations, The concentrations ranged from 2.1 "to 9.1 pCi/L. Gross Alpha (suspended) was detected in 5 of 15 groundwater locations. The~concentrations ranged from 1.6;to 7.5 pCi/L. Gross Beta (dissolved) was detected in all 15 groundwater locations: The concentrations.ranged from 2.6.to,17.pCi/L. Gross Beta (suspended) was detected, in 3 of 15 groundwater locations. ýThe concentrations ranged from 4.3 to, 1-1 pCi/L (Table B-I.1 ;,Appendix.B).. Gamma Emitters. Potassium-40 was detected on three of 15 groundwater locations with a range of 72 to 120 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-24.1, 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 in four of five groundwater monitoring locations. The U-233/234 concentrations ranged from 0.9 to 2.3 pCi/L and the U-238 concentrations ranged from 0.5 to 1.8 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 acc6rdance with the Siation's radiological groundwater protection program surface water sampes were collected from'streams that transverses the site, as well as, from other wate`rb6dies that could influence the tritium concentration at Limerick. Analytical results and anomalies aide discussed below. Tritium Samples from seven locations were analyzed for tritium activity Tritium activity was detected in station SW-LR-8 at a concentration of 198 pCi/Liter (Table B-11.1, Appendix B". Strontium -No Sr-90 activity was detecbed in any of surface water samples analyzed (Table B-II. 1, Appendix B)., Gross Alpha andcGross Beta (diss6lved and suspended) Gross Alpha and Gross Beta analyses in the d'ss6lved and suspended fractions were performed on surface water samples during the second ,sampling'in 2009... Gross Alpha (dissolved) was-detected in one of seven surface water locations. The concentration was 3.9 pCi/L. Gross Alpha and Gross Beta (suspended) was not detected in any surface water location. Gross Beta (dissolved) was detected in six of seven surface water locations. The concentrations ranged.from 2.6.to 17 pCi/L (Table B-11.1, Appendix B). 11

Gamma Emitters No gamma emitting nuclides were detected (Table B-11.2, Appendix B). C. Drinking Water Well Survey A drinking water well survey was conducted during the summer 2006 by CRA (CýRA 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, fireý,water well. The potable supply well isconstruqted as an0open,-rock borehole. Groundwater was measured at a depth 102 feet bgs during a well pump replacement in 2004 (personal communication with Station, 2006). Thepump was placed at a depth of approximately 294 feet bgs. The total well depth and the depth of the steel casing are unknowni -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 2004YThe 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-ýLaboratory Comparison Program results for TBE are presented in the Annual Radiological Environmental Operating Report. E. Leaks, Spills, and Releases On February 13, 2009 a leak from the exterior walls of both U1 and U2 condenser bays was discovered via operator rounds (IR880716). The condensation was observed dripping directly to open ground and asphalt. Water samples were collected and analyzed for gamma isotopic and tritium. No gamma emitting nuclides were identified; however, tritium was identified at a concentration of 3.90E-03 uCi/ml (3.90E+06 pCi/L). 12

Sampling of NPDES outfalls verified that no offsiterel ease.of tritium occurred. The release to ground occurred for up to six days until catch containments were installed. The total release of tritium to the ground was conservatively estimated at 1.23E-03 Curies. Groundwater sampling, as part of the radiological groundwNater protection program (RGPP), has identified tritium in one down gradient well, MW-LM-9, at a maximum 'concentration of 1750 pCi/L, which is below the environmen'fal lower limit of detection (LLD) of 2000pCi/L. The leaks along the condenser bay joints Were sealed with'caulk and periodic inspections for future leakihg has been a'dde'd to bperator rounds. All data related't 'thýs release was added to the Stations 10 CFR 50.75(g) decommissioning file. On April 3, 2009 the water from the catch containmnents was released to the station's holding pond. The holding pond releases through the normal 6iqiid effluent releaseapoint itoutfall.001. The~catch Containment water contained approximately'747 uCi of tritiu m. F. Trends No trends have, been identified., G. Investigations Conclusions from the Phase 1 report have been made available to state and federal regulators and to the public. Currently no investigations are on going. H. Actions Taken

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

2. Installation of Monitoring Wells No new wells have been installed in 2009

3. Actions to Recover/Reverse Flumes

-No actions were required to recover or reverse groundwater plumes. 13

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.

14

APPENDIX A LOCATION DESIGNATION

TABLE A-I: Radiological Groundwater Protection Program - Sampling Locations for the Limerick Generating Station, 2009 Location Type Distance MW-LR-1 Monitoring Well Onsite MW-LR-2 Monitoring Well Onsite MW-LR-3 Monitoring Well Onsite MW-LR-4 Monitoring Well Onsite MW-LR-5 Monitoring Well Onsite MW-LR-6 Monitoring Well Onsite MW-LR-7 Monitoring Well Onsite MW-LR-8 Monitoring Well Onsite MW-LR-9 Monitoring Well Onsite P11 Monitoring Well Onsite P14 Monitoring Well Onsite P16 Monitoring Well Onsite P17 Monitoring Well Onsite P3 Monitoring Well Onsite SP22 Monitoring Well Onsite SW-LR-2 Surface Water Offsite SW-LR-4 Surface Water Offsite SW-LR-6 Surface Water Offsite SW-LR-7 Surface Water Onsite SW-LR-8 Surface Water Onsite SW-LR-9 Surface Water Onsite SW-LR-9 Surface Water Onsite SW-LR-10 Surface Water Onsite A-1

// / 1 Mile Radius .. V NNW hTL-R--70 NE N \\ / 7 ~"' ,IVWLR.10 / /: 7,i /;4 'N 1 -22 / / W NW! / ".... / "R70 ENE N I/ W-L4O / 7 / -e\\ X I WSW - '? N / //,-' 7.. I "N"/ I '(/ N-*-" 0 500 1,000 1,500 2,000 '-S..- SE Feet' / k, Figure 1 Routine Well Water and Surface Water Sample Locations for the Radiological Groundwater Protection Program, Limerick Generating Station, 2009 A-2

APPENDIX B DATA TABLES

TABLE B-I.1 CONCENTRATIONS OF TRITIUM, STRONTIUM-90, GROSS ALPHA, AND GROSS BETA IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2009 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) MW-LH-1 MW-LR-1 Mean + 2 SD 04/28/2009 < 139 10/28/2009 < 181 04/30/2009 < 165 10/28/2009 < 185 < 0.6 4.2 +/- 2.5 < 1.5 3.2 +/- 2.1 < 2.4 4.2 3.2 MW-LR-2 MW-LR-2 < 0.7 6.6 +/- 2.5 2.8 +/- 1.1 8.2 +/-2.3 < 1.9 8.2 Mean + 2 SD 6.6 2.8 MW-LR-3 MW-LR-3 Mean + 2 SD 04/30/2009 < 168 10/28/2009 < 182 04/28/2009 < 166 10/29/2009 < 185 < 0.7 < 0.6 6.2 +/-2.8 < 0.8 6.6 3.5 +/- 1.5 7.5 - 1.9 4.1 +/-2.4 < 1.8 4.1 17 +/- 3.8 5.9 +/- 1.6 MW-LR-4 MW-LR-4 Mean + 2 SD 3.5 7.5 17 5.9 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 MW-LR-5 TBE TBE EIML TBE TBE EIML 04/30/2009 04/30/2009 04/30/2009 10/29/2009 10/29/2009 10/29/2009 189 191 375 < 184 < 178 < 152 +/- 110 +/- 110 +/- 97 < 0.9 < 0.8 < 0.6 Mean + 2 SD 6.2 +/- 2.8 2.4 +/- 1.0 7.6 +/-,3.0 1.6 +/- 0.9 6.9 +/- 2.0 2.0 +/- 1.1 2.4 +/- 1.2 .2.4 +/- 1.2 252 +/- 214 MW-LR-6 MW-LR-6 Mean + 2 SD MW-LR-7 MW-LR-7 04/30/2009 < 168 10/28/2009 < 183 04/30/2009 < 168 10/28/2009 < 182 04/28/2009 < 169 10/30/2009 < 182 9.0 +/- 2.4 < 1.9 8.1 +/-2.3 < 1.7 8.6 +/- 1.3 3.5 +/- 2.1 < 2.1 3.5 3.9 +/- 1.9 < 1.8 2.4 2.4' < 0.7 < 1.0 < 2.9 < 0.8 Mean + 2 SD 3.9 MW-LR-8 MW-LR-8 < 0.4 2.1 +/- 1.2 < 0.8 5.6 +/- 2.0 < 1.8 Mean + 2 SD 2.1 5.6 Samples are distilled for H-3 analysis B-1

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, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION DATE SITE MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 H-3 SR-90 GR-A (DIS) GR-A (SUS) GR-B (DIS) GR-B (SUS) U0224/2UU9 ORIGINAL 04/28/2009 RERUN 04/28/2009 ORIGINAL 04/28/2009 RERUN 04/28/2009 EIML 04/28/2009 06/11/2009 07/14/2009 08/18/2009 09/17/2009 10/30/2009 10/30/2009 EIML 10/30/2009 02/24/2009 04/28/2009 04/28/2009 EIML 04/28/2009 10/28/2009 10/28/2009 EIML 10/30/2009 434 658 821 794 830 803 1190 1750 .582 545 708 864 961 +/- 138 +/- 135 +/- 148 +/- 147 +/- 151 +/- 115 +/- 190 +/- 215 +/- 161 +/- 133 +/- 145 +/- 152 +/- 120 < 0.7 < 0.5 < 0.6 4.1 +/-+1.5 < 1.2 9.1 +/- 3.2 < 2.0 8.8 +/- 2.6 4.3 +/- 1.6 9.7 +/-2.4 11 +/-2.1 9.2 +/- 1.3 .7.4 +/- 8.8 Mean + 2 SD 842 +/- 668 P1l P1l P1l P1l P11 P1l P11 375 187 200 343

181
172

< 152 +/- 136 +/- 110 +/- 110 +/- 96 <.0.8 < 0.9 < 0.6 6.6 +/-7.1 4.0 +/- 2.3 < 0.8 17 +/- 3.0 < 1.7 17 Mean + 2 SD 276 +/- 1,93 4.0 P14 P14 P14 02/24/2009 04/28/2009 10/30/2009 180 165 181

< 1.0 Mean + 2 SD P16 P16 Mean + 2 SD P17 P17 04/28/2009

< 168 10/30/2009 < 181 04/28/2009 < 140 10/27/2009 < 182 04/28/2009 < 167 10/27/2009 < 180 < 0.6 Mean + 2 SD P3 P3 < 0.7 Mean + 2 SD SP22 04/28/2009 < 140 SP22 10/28/2009 < 181 Mean + 2 SD Samples are distilled for H-3 analysis < 0.7 B-2

TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN WELL WATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2009 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-5 MW-LR-6 MW-LR-7 MW-LR-8 MW-LR-9 MW-LR-9 MW-LR-9 MW-LR-9 P1l Pl1 P1l P14 P16 P17 P3 SP22 COLLECTION PERIOD 10/28/09 10/28/09 10/28/09 10/29/09 TBE 10/29/09 TBE 10/29/09 EIML 10/29/09 10/28/09 10/28/09 10/30/09 06/11/09 10/30/09 10/30/09 EIML 10/30/09 10/28/09 10/28/09 EIML 10/30/09 10/30/09 10/30/09 10/27/09 10/27/09 10/28/09 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140, < 43 < 60 < 47 < 46 < 38 <52 < 29 < 50 < 48 <43 < 36 < 59 < 31 < 35 < 56 < 50 < 34 < 25 < 20 < 44 < 50 < 46 < 45 < 71 < 99 < 36 < 65 < 60 105 - 27 < 71 < 58 < 92 < 62 < 69 < 111 120 +/- 41 < 51 < 110 104 +/- 35 72 +/- 39 <44 < 41 < 53 < 34 <5 <6 <5 <4 <4 <5 <3 <5 <7 <5 <4 <6 <5 <3 <6 <7 <4 <3 <2 <5 <5 <4 <4 <7 <6 <5 <4 <5 <3 <5 <6 <4 <3 <7 <3 <2 <6 <5 <3 <3 <2 <5 <5 <5 < 9 < 15 < 12 <9 <9 <11 <8 <9 < 13 < 12 <8 < 14 <4 <4 < 14 < 10 <4 <6 <5 < 10 < 12 < 10 <3 <8 <7 <4 <5 <5 <3 <5 <6 <5 <4 <7 <5 <3 <6 <7 <2 <3 <2 <5 <6 <4 <9 <15 <11 <11 <9 < 11 <7 <9 < 12 < 10 <7 < 16 <6 <7 < 13 < 12 <5 <7 <5 " <.10 < 11 <8 <6 <9 <6 <6 -<5 <6 <5 <6 <7 <6 <4 <8 <5 <4 <8 <.5 <.5 <3 <-2 <5 <7 <5 <7 < 10 < 10 <9 <8 < 10 <5 < 10 < 10 < 10 <7 < 13 <9 <8 <11 <8 < 4 <5 .< 4 <9 < 10 <8 <9 < 13 <11 <11 <9 <11 <6 < 9 < 10 <<7 <7 < 12 <6 <6 < 14 <11 .< 8 <.6 < 4 <11 < 12 <9 <4 <6 <6 <5 <4 <4 <4 <5 <5 <5 <4 <7 <4 <4 <5 <4

.-< 3

<3 < 2 <5 <5 <5 <5 <7 <6 <7 <4 <5 <4 <5 <5 <5 <4 <8 <5 <4 <6 <6 <4 <3 < 2 <6 <5 <5 < 23 < 35 < 29 < 29 < 23 < 26 < 19 < 25 < 30 < 28 < 22 < 33 < 17 < 20 < 35 < 27. < 22 < 15ý < 12 < 27 < 29 < 27 < P < 13 <9 ~< 7 <8 <9 .< 9 <6 < 14 <5 <5 <,10 <-8 <6 < 5 <4 <7 <8 -< 7 B-3

TABLE B-113 CONCENTRATIONS OF HARD TO DETECTS IN GROUNDWATER SAMPLES COLLECTED AS PART OF THE RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM, LIMERICK GENERATING STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD FE-55 NI-63 AM-241 CM-242 CM-243/244 PU-238 PU-239/240 U-233t234 U -235 'U-238 MW-LR-1 MW-LR-8 MW-LR-9 P1l P14 10/28/2009 10/30/2009 10/30/2009 10/28/2009 10/30/2009 < 199 < 87

163
124
108

< 2.9 <0.1 < 0.05 < 4.8 < 0.1 < 0.1 < 42 < 0.1 < 0.2 < 3.7 < 0.1 < 0.1 < 4.8 < 0.1 < 0.05 < 0.02 < 0.1

0.1

< 0.1 < 0.05

0.1
0.1

< 0.2 < 0.1 < 0.1 <0.1 <0.1 <0.2 < 0.02 <0.1 < 0.03 2.3 +/- 0.3 1.3 +/- 0.5 0.9 +/- 0.3 1.9 +/- 0.7 < 02 < 0.1

0.1
0.1
0.1

<ý 0.2 -,1.3

0.6

.0.5 1.8 +/- 0.2 +/- 0.3 +/- 0.2 +/- 0.7 B-4

TABLE B-II.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, 2009 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) SW-LR-2 SW-LR-2 Mean + 2 SD SW-LR-4 SW-LR-4 4/28/2009 < 140 10/27/2009 < 178 4/30/2009 < 169 10/27/2009 < 179 4/30/2009 < 167 10/27/2009 < 182 < 0.6 < 0.9 < 1.6 < 0.9 3.0 +/- 1.7 < 1.9 3.0 4.4 +/- 1.9 <.1.8 4.4 < 2.2 < 0.8 Mean + 2 SD SW-LR-6 SW-LR-6 < 0.8 < 0.9 < 1.7 71 < 2.4 <.. 8 Mean + 2 SD 2.4 SW-LR-7 SW-LR-7 4/28/2009 < 138 10/27/2009 < 169 < 1.0 3.9 +/- 2.3 < 0.8 6.8 +/- 2.1 < 1.7 Mean + 2 SD 3.9 6.8 SW-LR-8 SW-LR-8 5/1/2009 10/28/2009 < 159 198 +/- 119 < 0.8 < 1.6 < 0.9 2.6 +/- 1.5 < 1.8 Mean + 2 SD 198 2.6 SW-LR-9 SW-LR-9 5/1/2009 < 157 10/28/2009 < 166 Mean + 2 SD SW-LR-1 0 SW-LR-1 0 SW-LR-10 Mean + 2 SD < 0.6 < 0.7 < 2.9 < 1.7 2/24/2009 4/28/2009 10/27/2009 186 141 171 < 0.8., 1.5 0.9 <08 17 3.1 < 1.7 17 4.1 +/- 1.6 < 1.8 4.,, 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, 2009 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 PERIOD 10/27/2009 10/27/2009 10/27/2009 10/27/2009 10/28/2009 10/28/2009 10/27/2009 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 < 49 <44 < 52 <42 < 58 < 51 < 45 < 53 < 41

65

< 51 < 73 < 50 < 46 <5 <5 <6 <5 <6 <5 <4 <4 <6 <7 <5 <5 <5 <4 < 11 < 14 < 13 <8 < 13 < 12 <10 <5 <6 <6 <5 <5 <5 <5 11 11 15 11 11 10 9 <5 <6 <6 <6 <6 <6 <5 <8 <9 <8 <9 < 10 <9 < 10 13 12 12 12 13 12 11 <5 <5 <6 <5 <6 <5 <4 <6 <6 <6 <5 <6 <6 <5 < 27 < 29 < 34 < 32 < 32 < 29 < 28 <9 < 11 < 12 <9 < 11 <7 <9 B-6}}

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