SVP-08-023, Annual Radiological Environmental Operating Report

Annual Radiological Environmental Operating Report

ML081420104
Person / Time
Site:	Quad Cities
Issue date:	05/09/2008
From:	Tulon T Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209, SVP-08-023
Download: ML081420104 (110)

Text

Exelkn,.Exelon Generation Company, LLC Quad Cities Nuclear Power Station 22710 206t' Avenue North Cordova, IL 61242-9740 www.exeloncorp.com Nuclear SVP-08-023 May 9, 2008 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Quad Cities Nuclear Power Station Annual Radiological Environmental Operating Report In accordance with Quad Cities Technical Specifications 5.6.2, enclosed is the 2007 Radiological Environmental Operating Report for Quad Cities Nuclear Power Station.This report contains the results of the radiological environmental and meteorological monitoring programs.

Also attached is the 2007 Radiological Groundwater Protection Program (RGPP) report, as Appendix E of the enclosure.

Should you have any questions concerning this letter, please contact W.J. Beck at (309) 227-2800.Respectfully, Tim y J.Tulon sit ice President Quad Cities Nuclear Power Station

Attachment:

Quad Cities Nuclear Power Station 2007 Annual Radiological Environmental Operating Report cc: Regional Administrator-NRC Region III NRC Senior Resident Inspector

-Quad Cities Nuclear Power Station ii§~?5 Attachment Quad Cities Nuclear Power Station 2007 Annual Radiological Environmental Operating Report Docket No: 50-254 50-265 QUAD CITIES NUCLEAR POWER STATION UNITS 1 and 2 Annual Radiological Environmental Operating Report 1 January Through 31 December 2007 Prepared By Teledyne Brown Engineering Environmental Services Nuclear Quad Cities Nuclear Power Station Cordova, IL 61242 May 2008 Table Of Contents I. S um m ary and C o nclusions

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1 II. In tro d u c tio n ........................................................................................................................

2 A .O bjectives of the R EM P ...................................................................................

2 B. Implementation of the Objectives

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2 III. P rog ram D escription

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..2 A .S am ple C o llection ...........................................................................................

..2 B. Sample Analysis ..........................................

4 C .D ata Interpretatio n ................................................................................

5 D .P rogram Exceptions

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..6 E .P rogram C hanges ...........................................................................................

..8 IV. Results and Discussion

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8 A. Aquatic Environment

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8 1. S urface W ater .....................

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8 2. Ground Water ......................................

9 3 .F is h .......................................................................................................

..9 4 .S e d im e nt ............................................................................................

..10 B. Atmospheric Environment

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10 1. A irborne ..............

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..10 a. Air Particulates

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10 b .A irbo rne Iodine ...............

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..11 2 .T e rre stria l ...........................................................................................

..1 1 a .M ilk .........................................................................................

..1 1 b. Food P roducts ........................................................................

..12 C. Ambient Gamma Radiation

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12 D. Interim Spent Fuel Storage ..................................

12 E .Land U se S urvey ...........................................................................................

..12 F .E rra ta D a ta ..............................................................

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1 3 G. Summary of Results -Inter-laboratory Comparison Program .......................

14 2 of 108 Appendices Appendix A Radiological Environmental Monitoring Report Summary aiabpes Table A-1 Appendix B Tables Table B-i: Table B-2: Radiological Environmental Monitoring Program for Quad Cities Nuclear Power Station, 2007 Location Designation, Distance & Direction, and Sample Collection

&Analytical Methods Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2007 Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2007 Figure.-Figure B-i: Figure B-2: Appendix C Tables Table C-I.1 Table C-1.2 Table C-1.3 Table C-I1.1 Table C-11.2 Quad Cities REMP Sampling Locations

-2 Mile Radius, 2007 Quad Cities REMP Sampling Locations

-9.3 Mile Radius, 2007 Data Tables and Figures -Primary Laboratory Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.ii 3 of 108 Table C-111.1 Table C-IV.1 Table C-V.1 Table C-V.2 Table C-V.3 Table C-VI.1 Table C-VII.1 Table C-VII.2 Table C-VIII.1 Table C-IX.1 Table C-IX.2 Table C-IX.3 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu meter) in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Concentrations of Gamma Emitters in Milk Samp.les Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Concentrations of Gamma Emitters in 'Food Products Samples'Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.Quarterly TLD Results for Quad Cities Nuclear Power Station, 2007.Mean Quarterly TLD Results-for the Inner Ring; Outer Ring, Other and Control Locations for Quad Cities Nuclear Power Station, 2007.Summary of the Ambient Dosimetry Program for Quad Cities Nuclear Power Station, 2007.Figures Figure C-1 Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 Surface Water -Gross Beta -Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 -2007.Surface Water -Tritium -Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 -2007.Ground Water -Tritium -Station Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 -2007.Air Particulates

-)Gross Beta -Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 -2007.Air Particulates

-Gross Beta -Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 -2007.Air Particulates

-Gross Beta -Station Q-07 (C) Collected in the Vicinity of QCNPS, 2000 -2007.iii 4 of 108 Figure C-7 Figure C-8 Appendix D Air Particulates

-Gross Beta' Stations Q-13 and Q-16 Collected in the Vicinity of QCNPS, 2007.AirParticulates

-Gross Beta -Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2007.Inter-Laboratory Comparison Program Tables, Table D-1 Analytics Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2007 Table D-2 ERA Environmental Radioactivity Cross Check Program Teledyne Brown Engineering, 2007 Table D-3 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)Teledyne Brown Engineering, 2007 Table D-4 ERA Statistical Summary Proficiency Testing Program"Environmental, Inc., 200.7 Table D-5 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)' Environmental, 'Inc., 2007 'Appendix E Annual Radiological Groundwater Protection Program Report (ARGPPR)iv 5 of 108

1. Summary and Conclusions This report on the Radiological Environmental Monitoring Program (REMP)conducted for the Quad Cities Nuclear Power Station (QCNPS) by Exelon covers the period 1 January 2007 through 31 December 2007. During that time period, 1,417analyses were performed on 1,322 samples. In assessing all the data gathered for this report and comparing these results with preoperational data, it was concluded that the operation of QCNPS had no adverse radiological impact on the environment.

Surface water samples were analyzed for concentrations of gross beta, tritium and gamma emitting nuclides.

Ground water samples were analyzed for concentrations of tritium and gamma emitting nuclides.

No fission or activation products were detected.

Gross beta activities detected were consistent with those detected in previous years and consistent with the control stations.Fish (commercially and recreationally important species) and sediment samples were analyzed for concentrations of gamma emitting nuclides.

No fission or activation products were detected in fish. No fission products or activation products were found in sediment.Air particulate sample's were analyzed for concentrations of gross beta and gamma emitting nuclides.,No fission or activation products were detected.High sensitivity 1-131 analyses were performed on air samples. No 1-131 was detected.Cow milk samples were analyzed for concentrations of 1-131 and gamma emitting nuclides.

No 1-131 was detected.

Concentrations of naturally occurring isotopes were consistent with those detected in previous years. No fission or activation products were detected.Food product samples were analyzed for concentrations of gamma emitting nuclides.

No fission or activation products were detected.Environmental gamma radiation measurements were performed quarterly using thermoluminescent dosimeters.

Levels detected Were consistent with those observed in previous years.-1 -6 of 108 II. Introduction The Quad Cities Nuclear Power Station (QCNPS), consisting of two 2957 MWth boiling water reactor.owned and operated by Exelon Corporation,, is located in Cordova, Illinois along the Mississippi River. Unit No. 1 went critical on 16 March 1972. Unit No. 2 went critical on 02 December 1973. The site is located in northern Illinois, approximately 182 miles west of Chicago, Illinois.This report covers those analyses performed by Teledyne Brown Engineering (TBE), Global Dosimetry, and Environmental Inc. (Midwest Labs) on samples collected during the period 1 January 2007 through 31 December 2007.A. Objective of the REMP The objectives of the REMP are to: 1. Provide data on. measurable levels of radiation and radioactive materials in the site environs.2. Evaluate the relationship between quantities of radioactive material release~d fromthe plant andlresuliant radiation doses, to individuals from principal pathways of exposure.B. Implementation of the Objectives The implementation of the objectives is accom'plished by: 1. Identifying significant exposure pathways.'

2. Establishing baseline radiological data of media within those pathways.3. Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.

Ill. Program Description A. Sample Collection Samples for the QCNPS REMP were collected for Exelon Nuclear by Environmental Inc. (Midwest Labs). This section describes the general sampling methods used by Environmental Inc. to obtain environmental samples for the QCNPS REMP in 2007. Sample locations and-2-7 of 108 descriptions can be found in Table B-1 and Figures B-1 and B-2, Appendix B..Aquatic Environment The aquatic environment was evaluated by performing radiological analyses on samples of surface water, ground water, fish, and sediment.Surface water samples were collected weekly from two locations, Q-33 and Q-34 (Control).

Ground water samples were collected quarterly from two locations, Q-35 and Q-36. All water samples were collected in new containers, which were rinsed with source water. prior to collection.

Fish samples comprising the edible portions of commercially and recreationally important species were collected semiannually at two locations, Q-24 and Q-29 (Control).

Sediment samples composed of recently deposited substrate were collected at one location semiannually, Q-39.Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on'samples of air particulate, airbor-ne"iodine, and milk. Airborne iodine and particulate samples were collected and analyzed at nine locations'(Q-01, Q-02, 0-03, Q-04, Q-07:,'0-13, Q-16, Q-37 and Q-38).The control location was Q-07. Airborne iodine and particulate samples were obtained at each location, using avacuum, 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 air particulate filters and air iodine samples were replaced weekly and sent to the laboratory for analysis.Milk samples were collected biweekly at one location (Q-26) from May through October, and monthly from November through April. All samples were collected in new plastic containers from the bulk tank, preserved with sodium bisulfite, and shipped promptly to the laboratory.

Food products were collected annually in July at five locations (Q-Quad 1 Control, Q-Quad 1, Q-Quad 2, Q-Quad 3, and Q-Quad 4). The control location was Q-Quad 1 -Control. Various types of broadleaf and root vegetables were collected and placed in new plastic bags, and sent to the laboratory for analysis.Ambient Gamma Radiation Direct radiation measurements were made using thermoluminescent 8 of 108 dosimeters (TLD). Each location consisted of 2 TLD sets., The TLD locations were placed on and around the QCNPS site as follows: An inner ring consisting of 15 locations (Q-101, Q-102, Q-103, Q-104, Q-105, Q-106, Q-107, Q-108, Q-109, Q-111, Q-112, Q-113,'Q-114, Q-115 and Q-116). These TLD are located in 15 of the 16 meteorological sectors in the general area of the site boundry (approximately 0.1 -3 miles from the site). There are no TLDs located in the SSW sector because this sector is located over water.An outer ring consisting of 16 locations (Q-201, Q-202, Q-203, Q-204, Q-205, Q-206, Q-207, Q-208, Q-209, Q-210, Q-211, Q-212, Q-213, Q-214, Q-215 and Q-216). These TLDs are located in each of the 16 meteorological sectors (approximately 3.7,- 5 miles from the site)An other Set consisting of eight locations (Q-01, Q-02, Q-03, Q-04, Q-13, Q-1 6, Q-37 and Q-38). The locations are at each of the air sample stations around the site.The balance of one location (Q-07) is the control site.'The specifib TLD loc5tions were determined by the following criteria: 1. The jpresen"ce of relatively..dense population;

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

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

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

The TLDs were exchanged quarterly and sent to Global Dosimetry for analysis.B. Sample Analysis This section describes the general analytical methodologies used by TBE and Environmental Inc. (Midwest Labs) to analyze the environmental samples for radioactivity for the QCNPS REMP in 2007 and the type of analyses.

The analytical procedures used by the laboratories are listed in-4-9 of 108 Table B-2.In order to achieve the stated objectives, the current; program includes the following analyses: 1. Concentrations of beta emitters in surfacerwater and air particulates.

2. Concentrations of gamma emitters in ground and surface water, air particulates, milk, fish, sediment and vegetation.

3. Concentrations of tritium in ground and surface water.4. Concentrations of 1-131 in air and milk.5. Ambient gamma radiation levels at various site environs.C. Data Interpretation The radiological and direct radiation data collected prior to Quad Cities Nuclear.Power Station becoming operational-were.

used as a baseline with which these operational data were-compared:

C. For the purpose of this report, Quad Cities Nuclear.Power Station was-considered operational at initial criticality.

In addition, data were compared to previous years'operational data for consistency and trending.;

Several factors were important in the interpretation of the data: 1.- Lower Limit of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as an a priori (a before the fact) estimate of a system (including instrumentation, procedure and sample type) and not as an a posteriori (after the fact) criteria for the presence of activity.

All analyses were designed to achieve the required QCNPS detection capabilities for environmental sample analysis.The minimum detectable concentration (MDC) is defined above with the exception that the measurement is an a posteriori (after the fact) estimate of the presence of activity.-5-10 of 108

2. Net Activity Calculation and Reporting of Results Net activity for a sample was calculated by subtracting background activity from the sample activity.

Since the REMP measures extremely small changes in radioactivity in the environment, background variations may result in sample activity being lower than the background activity effecting a negative number. An MDC was reported in all cases where positive activity was not detected.Gamma spectroscopy results for each type of sample were grouped as follows: For surface water, groundwater and vegetation 12 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, 1-131, Cs-134, Cs-137, Ba-140, and La-140 were reported.For fish, sediment, air particulate and milk 11 nuclides, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, Cs-134, Cs-137 and Ba-140 andLa-140 were reported.Means and, standard:

deviatiohs of the results were calculated.

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

D. 'Program Exceptions For 2007 the QCNPS REMP had a sample recovery rate in excess of.99%.. Sample anomalies and missed samples are listed in the tables below: S -Table D-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection Reason Type Code Date AAl Q-38 03/23/07 Estimated time; timer malfunction A/I Q-03 04/06/07 Reported 30 min power outage due to station work A/I Q-02 04/06/07 Reported 30 min power outage due to station work A/I Q-37 04/27/07 Estimated time; low timer reading for no apparent reason-6-S1 of 108 Table D-1 LISTING OF SAMPLE ANOMALIES (continued)

Sample Type A/I Location Code Q-37 Collection Date:Reason A/I A/I A/I A/I A/I Q-38 Q-38 Q-37 Q-38 07/20/07 Estimated time; low timer reading possibly due to adverse weather 07/20/07 Estimated time; low timer reading possibly due to adverse weather 09/14/07 Estimated time; low timer reading for no apparent reason 09/14/07 Estimated time; low timer reading for no apparent reason: 12/07/07 Estimated time; low timer reading possibly due to adverse weather 12/14/07 Estimated time; low timer reading possibly due to adverse weather 01/01/08 TLD. read, higherthan expected (35.0 mrem)during 4 th quarter; duplicate TLD in same sector read 22 mrem, which is expected 2 LISTING OF MISSED SAMPLES Q-38 Q-213-1 TLD Table D-Sample Local Sample Type SW SW SW SW SW SW SW Locat Cod Q-33 Q-34 Q-33 Q-33 Q-34 Q-33 Q-34[ion Collection e Date 01/19/07 01/19/07 01/26/07 02/02/07 02/02/07 02/16/07 02/16/07 Reason No sample; water frozen No sample; water frozen No sample; water frozen No sample; water frozen No sample; water frozen No sample; water frozen No sample; water frozen-7-12 of 108 Table.D-2 LISTING OF MISSED SAMPLES (continued)

Sample Location Collection Reason Type Code Date A/M TLD TLD SW SW SW Q-03 Q-210-5 Q-215-2 Q-34 Q-33 Q-33 All 03/09/07 03/30/07 03/30/07 12/07/07 12/14/07 12/28/07 Collector found 4" of water inside sample station TLD not received from vendor;collector placed spare TLD found broken; collector placed spare No sample; water frozen No sample; water frozen No sample; water frozen Shipment damaged. In repackaging, AP 08/04/07 -08/10/07iscarueu all the Avs.The overall sample recovery rate indicates that the appropriate procedures eind equipment arein place to assure reliable program implementation.

E. Program Changes Starting in 2007, the mean and two standard deviation values are* calculated using, the positive values only.IV. Results and Discussion A., Aquatic Environment

1. Surface Water Samples were taken weekly and composited monthly at two locations (Q-33 and Q-34). Of these locations only Q-33 located downstream, could be affected by Quad Cities' effluent releases.The following analyses were performed.

GrssfBeta Samples from all locations were analyzed for concentrations of-8-13 of 108 gross beta (Table C-1.1, Appendix C). Gross beta activity was detected in 22 of 24 samples. The values ranged from 2.5 to 7.8 pCi/L. Concentrations detected were consistent with those detected in previous years and the control location (Figure C-1, Appendix C). The required LLD was met.Quarterly composites of weekly collections were analyzed for tritium activity (Table C-1.2, Appendix C). No tritium activity was detected (Figure C-2, Appendix C). The 2000 pCi/L OCDM and contractually required 200 pCi/L LLDs were-met.Gamma Spectrometry Samples from both locations were analyzed for gamma emitting nuclides (Table C-1.3, Appendix C). No nuclides were detected and all required LLDs were met.2. Ground Water Quarterly grab samples were collected at two locations (Q-35 and Q-36). Both locations could be affected by Quad Cities' effluent releases.

The following analyses were performed:

Tritiuim Quarterly grab samples from the locations were analyzed for tritium activity (Table C-I1.1, Appendix C). No tritium activity was detected (Figure C-3, Appendix C). The 2000 pCi/L OCDM and contractually required 200 pCi/L LLDs were met.Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-11.2, Appendix C). No nuclides were detected.3. Fish Fish samples comprised of various commercially and recreationally important species were collected at two locations (Q-24 and Q-29)semiannually.

Location Q-24 could be affected by Quad Cities'effluent releases.

The following analysis was performed: 14 of 108 Gamma Spectrometry The edible portion of fish samples from both locations was ,analyzed for gamma emitting nuclides (Table C-I11.1, Appendix C).No nuclides were detected and all required LLDs were met.4. Sediment Aquatic sediment samples were collected at one location (Q-39)semiannually.

The location, located downstream, could be affected by Quad Cities' effluent releases.

The following analysis was performed:

Gamma Spectrometry Sediment samples- from Q-39 were analyzed for gamma emitting nuclides (Table C-1V.1, AppendixC).

Cesium-137 was detected in one sample at a concentration of 70. pCi/kg dry. No other nuclides were detected and all required LLDs were met.B. Atmospheric Environment

1. Airborne -, a. Air Particulates Continuous air particulate samples were collected from nine locations on a weekly basis. The nine locations were separated into three groups: Near-field samplers within 4..km of the site (Q-01, Q-02, Q-03 and Q-04), far-field samplers between 4 and 10 km from the site (Q-13, Q-16, Q-37, Q-38) and the Control sampler between 10 and 30 km from the site (Q-07). The following analyses were performed:

G rossBeta Weekly samples were analyzed for concentrations of beta emitters (Table C-V.1 and C-V.2, Appendix C).Detectable gross beta activity was observed at all locations.

Comparison of results among the four groups aid in determining the effects, if any, resulting from the operation of QCNPS. The results from the near-field locations (Group I)ranged from <5 to 54 E-3 pCi/mi 3 with a mean of 21 E-3-10-15 of 108 pCi/m 3.The results from the far-field locations (Group I1)ranged from 9 to 54 E-3 pCi/m 3 with a mean of 22 E-3 pCi/m 3.The results from the Control location (Group Ill)ranged from 9 to 49 E-3 pCi/m 3 with a mean of 23 E-3 pCi/mi 3.Comparison of the 2007 air particulate data with previous years data. indicate no effects from the operation of QCNPS. In addition a comparison of the weekly mean values for 2007 indicate no notable differences among the three groups (Figures C-4 through C-6, Appendix C).Gamma Spectrometry Weekly samples were composited quarterly and analyzed for gamma emitting nuclides (Table C-V.3, Appendix C). No nuclides were detected and all required LLDs were met.b. Airborne Iodine Continuous air samples were collected from nine locations (0-01I, Q-02, Q-03, Q-04, Q-07, Q-13, Q-16, Q-37, and Q-38) and analyzed weekly for -.131, (Table C-VI.1, Appendix C). All results were less than the MDC and the required LLD was met.2. Terrestrial

.a. Milk Samples were collected from one location (Q-26) biweekly May through October and monthly November through April.The following analyses were performed:

Iodine-131 Milk samples from the location were analyzed for concentrations of 1-131 (Table C-VII.1, Appendix C). No I-131 was detected and the LLD was met.Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII.2, Appendix C). No nuclides were detected and all required LLDs were met.-11 -16 of 108

b. Food Products Food product samples were collected at four locations plus a control location (Q-Quad 1 -Control, Q-Quad 1, Q-Quad 2, Q-Quad 3, and Q-Quad 4) annually during growing season.Four locations, (Q-Quad 1, Q-Quad 2, Q-Quad 3 and Q-Quad 4) could be affected by Quad Cities' effluent releases.

The following analysis was performed:

Gamma Spectrometry Samples from all locations were analyzed for gamma emitting nuclides (Table C-VIII.1, Appendix C). No nuclides were detected and all required LLDs were met.C. Ambient Gamma Radiation Ambient gamma radiation levels were measured utilizing 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 30 mR/quarter, with a range of 17 to 35 mR/quarter.

A comparison of the Inner Ring, Outer Ring and Other data to the Control Location data, indicate that the ambient gamma radiation levels from all the locations were comparable.

D. Independent Spent Fuel Storage Installation QCNPS commenced use of an Independent Spent Fuel Storage Installation (ISFSI) in Dec 2005. There were no measurable changes in ambient gamma and radiation level as a result of ISFSI operations.

E. Land Use Survey A Land Use Survey conducted during August 2007 around QCNPS was performed by Environmental Inc. (Midwest Labs) for Exelon Nuclear to comply with the Quad Cities' Offsite Dose Calculation Manual. The purpose of the survey was to document the nearest resident and milk producing animals in each of the sixteen 22 1/2 degree sectors around the site. The results from the land use census have not identified any locations, which yield a calculated dose or dose commitment, via the same pathway, that is at least 20% greater than at a location from which samples are currently being obtained.

The results of this survey are summarized below.-12-17 of 108 Sector N NNE NE ENE E ESE SE SSE S CI MA/Distance in Miles from QCNPS Residence Livestock Miles Miles 0.6 2.7 3.8 5.4 1.3 2.9 2.9 2.3 2.7 2.8 3.1 2.5 5.5 1.1. 3.6 0.8 1.6 Milk Farm Miles 3.1 6.6 SW 2.9 3.3 -WSW 2.2 2.2 -W 2.6 4.3 4.6 WNW 2.7 3.8 -NW 2.6 4.7 NNW 2.1 2.2 F. Errata Data There were several "location with the highest annual mean" values (averages) that were not correct that appear to be a cut /paste error.These errors are described beloW. -.Errata data-from 2006 AREOR Page 28 of 227, 1Q06, Q-215-2 is recorded as 88).Page 37 of 227, 2Q06, Q-205-1 is recorded as 88).Page 45 of 227, 3Q06, Q-108-1 is recorded as 87).Page 54 of 227, 4Q06, Q-205-1 is recorded as 88).8 but is actually 30 (page 11 but is actually 37 (page 30 but is actually 27 (page 13 but is actually 33 (page Page 64 of 227, Annual, Q-205-1 is recorded as 30 but is actually 27 (page 88).Page 7 (12 of 227), Q-03 02/25/06 -The value for this sample on page 79 (week 8, Q-03) is significantly less than the other samples for this week. If"no air was going through (the sample media)" then this is likely a "missed"-13-18 of 108 sample..Page 133 of 227 -section 3.2 (Dose to Man section);

The asterisked note indicates that liquid effluent dose calculations are performed using RG 1.109 calculations.

The site dose calculation software uses both NUREG 0133 and RG 1.109.G. Summary of Results -Inter-Laboratory Comparison Program The primary and secondary laboratories analyzed Performance Evaluation (PE) samples of air particulate, air iodine, milk, soil, vegetation and water matrices (Appendix D). The PE samples, supplied by Analytics Inc., Environmental Resource Associates (ERA) and DOE's Mixed Analyte Performance Evaluation Program (MAPEP), were evaluated against the following pre-set acceptance criteria: 1. Analytics Evaluation Criteria Analytics' evaluation report provides a ratio of laboratory results and Analytics' known value. Since flag values are not assigned by Analytics, TBE-ES evaluates the reported ratios based on internal QC requirements, which are based on the. DOE MAPEP criteria.2. ERA Evaluation Criteria ERA's evaluation report provides, an acceptance range for control and warning limits with associated flag values. ERA's acceptance limits are established-per the USEPA,- NELAC, state specific PT program requirements or ERA's SOP for the Generation of Performance Acceptance Limits, as applicable.

The acceptance limits are .either determined by a regression equation specific to each analyte or a fixed percentage limit promulgated under the appropriate regulatory document.3. DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with associated flag values.The MAPEP defines three levels of performance:

Acceptable (flag"A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value.Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% <-14-19 of 108 bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.

For the primary laboratory, 17 out of 19 analytes met the specified acceptance criteria.

Two samples did not meet the specified acceptance criteria for the following reasons: 1. Teledyne Brown Engineering's Analytics March 2007 1-131 in charcoal result of 34.7 pCi was lower than the known value of 71.3, resulting in a found to known ratio of 0.49. A new technician counted the charcoal cartridge on the back rather than the face side due to a label covering the flow indicator arrow. Due to decay of the 1-131, recounting could not be performed.

Counting the 2 nd quarter Analytics charcoal cartridge on the face and the back resulted in approximately 220% more activity on the face of the cartridge.

This .indicates that we would have had acceptable results (ratio approximately 1.07) if the cartridge had been counted on the face side. The investigation was documented by Nonconformance Report NCR 07-02.2. Teledyne, Brown Engineering's ERA July-2007 Cs-134 result of 57.6 pCi/L exceeded the. lbwer acceptancb' limit:of 60'.2 pCi/L. The high activity of the sample resulted in thejlower acceptance limit of 8.66, although the ratio of found to known was 83.6%, which is considered acceptable by TBE. The investigation was documented by Nonconformance Report NCR 07-07.For the secondary laboratory, 18 out of 19 analytes met the specified acceptance criteria.

One sample did not meet the specified acceptance criteria for the following reasons: 1. 1. Environmental Inc.'s ERA March 2007 air particulate Cs-137 result of 345.3 pCi/L exceeded the upper control limit of 336 pCi/L.The reported result was calculated using composite filter geometry rather than the single filter geometry.

The recalculated result of 305.8 pCi/filter fell within the acceptance limits. This was entered into their June 2007 Program Deviation Report.The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.-15-20 of 108 APPENDIX A RADIOLOGICAL ENVIRONMENTAL

'REPORT

SUMMARY

MONITORING 21 of 108 TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH tllGlHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER (PCI/LITER)

GR-B 24 H-3 8 GAMMA MN-54 24 4 5.2 (10/12)(2.5/7.8)200 <LLD 15 <LLD 15 <LLD.30 <LLD 15 <LLD 5.3 (12/12)(3.8/7.5)5.3 (12/12)(3.8/7.5)<LLD 0 Q-34 CONTROL CAMANCHE -UPSTREAM 4.4 MILES NNE OF SITE 0<LLD CO-58 FE-59 CO-60<LLD 0 0 0<LLD<LLD 0 00 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER (PCI/LITER)

ZN-65 NB-95 ZR-95 1-131 CS- 134 CS-137 30 <LLD 15 <LLD 30 <LLD 15 <LLD 15 <LLD 18 <LLD<LLD<LLD<LLD<LLD<LLD<LLD 0 0 0 0-t MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)00 TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF 'PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SURFACE WATER (PCI/LITER)

BA-140 LA-140 60 <LLD 15 <LLD 200 <LLD<LLD<LLD 0 0 0 GROUND WATER (PCI/LITER)

H-3 8 8 NA GAMMA MN-54 CO-58 15 <LLD 15 <I LD 30 <LLD 15 <LLD NA NA -NA NA 0 0 0 0-FE-59 CO-60 00 oc MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBEROF 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 GROUND WATER (PCI/LITER)

ZN-65 NB-95 ZR-95 1-131 30 <LLD 15 <LLD 30 <LLD 15 <LLD 15 <LLD 18 <LLD 60 <LLD NA* NA NA NA NA NA NA 0 0 0 0 CS-134 CS-137 0 BA- 140 t,1 0 00 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITHII HIG14EST 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 GROUND WATER (PCI/LITER)

FISH (PCI/KG WET)LA- 140 GAMMA MN-54 15 <LLD NA 0 U'h 8 CO-58 FE-59 130 <LLD 130 <LLD 260 <LLD<LLD<LLD<LLD 0 0 0 130 CO-60<LLD,LLD 0 ZN-65" 260 <LLD<LLD 0 NB-95 NA <LLD<LLD 0 0 00 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITHI HIGHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBEROF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBEROF 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 FISH (PCI/KG WET)ZR-95 NA <LLD 130 <LLD<LLD<LLD 0 CS-134 CS-137 BA- 140 LA-140 GAMMA MN-54 0 150 <LLD .- -<LLD *NA <LLD<LLD 0 0 0 NA <LED -ELLD SEDIMENT (PCI/KG DRY)2 NA <LLD NA 0 Co MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT (PCI/KG DRY)CO-58 FE-59 NA <LLD NA <LLD NA .<LLD NA 0 0 NA CO-60 ZN-65 NB-95 ZR-95 CS-134 NA NA<LLD...NA, NA <LLD NA <LLD 150 <LLD NA NA NA 0 0 0 0 0 00 0 00 00 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBEROF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS SEDIMENT (PCI/KG DRY)00 CS-137 BA- 140 LA-140 180 70 (1/2)(70).NA <LLD NA <LLD.10 21 (407/408)(6/54)NA <LLD NA 70 (1/2)(70)Q-39 INDICATOR 0 CORDOVA -DOWNSTREAM MISSISSIPPI RIVER 0.8 MILES SSW OF SITE NA 0 NA AIR PARTICULATE (PCI/TOTAL)

GR-B 459 23 (51/51)(9/49);<LLD 23 (51/51)(9/50)Q- 13 INDICATOR PRINCETON 4.7 MILES SW OF SITE 0 0 0 0 GAMMA MN-54 36 CO-58 FE-59 ,NA., .<LLD -<LLD NA <LLD<LLD 0 0'0 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE (PCI/TOTAL)

CO-60 ZN-65 NB-95 ZR-95 CS-134 NA <LLD NA <LLD<LLD 0<LLD 0 0 NA <LLD -.-......

<LLD NA., <LLD 50 <LLD 60 <LLD NA <LLD<LLD<LLD<LLD<LLD 0 0 0 CS-137 BA-140 0 00 0MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F), (F) .NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS AIR PARTICULATE (PCI/TOTAL)

AIR IODINE (E-3 PCI/CUMETER)

LA- 140 GAMMA 1-131 NA <LLD<LLD 0 0 468 70 <LLD<LLD MILK (PCI/LITER) 1-131 GAMMA MN-54 CO-58 FE-59 19 19<LLD NA NA 0 NA <LLD NA <LLD NA NA <LLD.NA NA CO-60 NA <LLD 0 00 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION 4 NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS MILK (PCI/LITER)

ZN-65 NB-95 ZR-95 CS-134 CS-137 BA-140 LA-140 NA <LLD NA <LLD NA- <LLD.15. <LLD, NA NA*NA NA 0 0 18 <LLD NA 0 0 0 0 0 60 <LLD 15 <LLD NA NA 0MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)00 TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) MEAN(M) MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION (PCI/KG WET)GAMMA MN-54 10 CO-58 FE-59 NA <LLD NA <LLD NA <LLD NA <LLD NA <LLD NA <LLD<LLD<LLD<LLD'<LLD , <LLD<LLD 0 0 CO-60 0 0 0 0 ZN-65 NB-95 0 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE A-I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL

SUMMARY

FOR QUAD CITIES NUCLEAR POWER STATION, 2007 NAME OF FACILITY:

QUAD CITIES DOCKET NUMBER: 50-254 &50-265 LOCATION OF FACILITY:

CORDOVA, IL REPORTING PERIOD: ANNUAL 2007 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN(M)LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN(M) .:-4EAN(M)

MEAN(M) STATION # NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F) (F) (F) NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT) (LLD) MEASUREMENTS VEGETATION (PCI/KG WET)ZR-95 1-131 CS- 134 CS-137 BA- 140 LA-140 NA <LLD -<LLD 60 <LLD <LLD 60 <LLD -<LLD 80 <LLD -.LLD 0 0 0 0 0 0 0 NA <LLD NA <LLD NA 21.8 (316/316)(17/35)<LLD<LLD DIRECT RADIATION (MILLI-ROENTGEN/QTR.)

TLD-QUARTERLY 324 21.9 (8/8)(19/27)25.3 (4/4)(23/29)Q-211-2 INDICATOR 4.5 MILES SW w 00 00a MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

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

& ANALYTICAL METHODS 35 of 108 TABLE B-1: Radiological Environmental Monitoring Program -Sampling.

Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2007 Location Location Description Distance & Direction From Site A. Surfarce Water Q-33 Q-34 Cordova (indicator)

Camanche, Upstream (control)B Ground/Well Water Q-35 Q-36 McMillan Well (indicator)

Cordova Well (indicator)

C, Milk -hi-weekly I monthly Q-26 Bill Stanley Dairy (indicator)

U /ir aiPS I air Ilaiflnp Q-01 Q-02 Q-03 Q-04 Q-07 Q-13 Q-16 Q-37 Q-38 Onsite 1 (indicator)

Onsite 2 (indicator)

Onsite 3 (indicator)

Nitrin (indicator)

Clinton (corntrol)

Princeton

'(indicator)

Low Mobr (indicator).

Meredosia.

Road (indicator)

Fuller Road (indicator) 3.1 miles SSW 4.4 miles NNE 1.5 miles S 3.3 miles SSW 3.5 miles ESE 0.5 miles N 0.4 miles ENE 0.6 miles S 1.7 miles NE 8.8 miles NE 4.7 miles SW 5.7 miles NNW 4.4 miles ENE 4.7 miles E 0.5 miles SW 1.0 miles N 0.8 miles SSW 6.0 miles NE 3.0 miles ESE 1.8 miles S 4.5 miles NW 9.5 miles NE F Fish Q-24 Q-29 Pool #14 of Mississippi River, Downstream (indicator)

Mississippi River, Upstream (control)Cordova, Downstream on Mississippi River (indicator)

F Sediment Q-39 G Food Products Quadrant 1 Quadrant 2 Quadrant 3 Quadrant 4 Control Janet Price Dale Nimmic Amy Johnston Mike Fawcett Charles Leavens H Fnvironmental Dosimetry

-TLD In ner Ring Q-101-1 Q-101-2 Q-102-1 Q-102-3 Q-103-1 and -2 Q-104-1 Q-104-2 Q-105-1 and -2 Q-106-2 and -3 Q-107-2 Q-107-3 Q-108-1 Q-108-2 0.6 miles N 0.9 miles N 1.3 miles NNE 1.4 miles NNE 1.2 miles NE 1.1 miles ENE 0.9 miles ENE 0.8 miles E 0.7 miles ESE 0.7 miles SE 0.8 miles SE 1.0 miles SSE 0.9 miles SSE B -1 36 of 108 TABLE B-1: Radiological Environmental Monitoring Program -Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2007 Location Location Description Distance & Direction From Site Q-109-1 Q-109-2 Q-1 11-1 Q-111-2 Q-112-1 Q-112-2 Q-113-1 and-2 Q-1 14-1 Q-114-2 Q-115-1 Q-115-2 Q-116-1 Q-116-3 0 ijt pr Ring Q-201-1 and -2 Q-202-1 Q-202-2 Q-203-1 Q-203-2 Q-204-1 Q-204-2 Q-205-1 Q-205-4 Q-206-1 and -2 Q-207-1 and -4 Q-208-1 Q-208-2 Q-209-1 and -4 Q-210-1 and -4 *Q-210-5 Q-211-1 and -2 Q-212-1 Q-212-2 Q-213-1 Q-213-2 Q-214-1 Q-214-2 Q-215-1 Q-215-2 Q-216-1 Q-216-2 0.9 miles S 1.2 miles S 2.6 miles SW 2.5 miles SW 2.5 miles WSW 2.2 miles WSW.2.5 miles W 2.1 miles WNW 2.5 miles WNW 2.6 miles NW 2.3 miles NW 2.3 miles NNW 2.4 miles NNW 4.2 miles N 4.4 miles NNE 4.8 miles NNE 4.7 miles NE 5.0 miles NE 4.7 miles ENE,..4.5 miles ENE 4.7 miles E 4.8 miles E 4.8 miles ESE 4.7 miles SE 4.3 miles SSE 4.9 miles SSE 4.7 miles S 4.1 miles SSW 3.3 miles SSW 4.5 miles SW 5.4 miles-WSW 4.4 miles WSW 4.3 miles W 4.8 miles W 4.7 miles WNW 4.4 miles WNW 5.0 miles NW.4.2 miles NW 4.6 miles NNW 4.3 miles NNW 0.5 miles N 0.4 miles ENE 0.6 miles S 1.7 miles NE 4.7 miles SW 5.7 miles NNW 4.4 miles ENE 4.7 miles E 8.9 miles NE Othe.Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Onsite 1 (indicator)

Onsite 2 (indicator)

Onsite 3 (indicator)

Nitrin (indicator)

Princeton (indicator)

Low Moor (indicator)

Meredosia Road (indicator)

Fuller Road (indicator)

Control Q-07 Removed from ODCM in December 2006 and replaced by 0-210-5. Q-210-4 is for trending only.B -2 37 of 108 TABLE B-2: Radiological Environmental Monitoring Program -Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2007 Sample Analysis Sampling Method Analytical Procedure Number Medium Surface Water Gamma Spectroscopy Monthly composite from TBE, TBE-2007 Gamma emitting radioisotope analysis weekly grab samples.Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Surface Water Gross Beta Monthly composite from TBE, TBE-2008 Gross Alpha and/or gross beta activity in weekly grab samples. various matrices Env. Inc., W(DS)-01 Determination of gross alpha and/or cross-beta in water (dissolved solids or total residue)Surface Water Tritium Quarterly composite TBE, TBE-2011 Tritium analysis in drinking water by liquid from weekly grab scintillation samples.Env. Inc., T-02 Determination of tritium in water (direct method)Ground Water Gamma Spectroscopy Quarterly grab samples. TBE, TBE-2007 Gamma emitting radioisotope analysis Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Ground Water Tritium Quarterly grab samples. TBE, TBE-201 1 Tritium analysis in drinking water by liquid scintillation Env. Inc., T-02 Determination of tritium in water (direct method)Fish Gamma Spectroscopy Semi-annual samples TBE-2007 Gamma emitting radioisotope analysis collected via electroshocking or other Env. Inc., GS-01 Determination of gamma emitters by techniques gamma spectroscopy Sediment Gamma Spectroscopy Semi-annual grab TBE, TBE-2007 Gamma emitting radioisotope analysis samples Env. Inc., GS-01 Determination of gamma emitters by gamma soectroscopV Air Particulates Gross Beta One-week composite of TBE, TBE-2008 Gross Alpha and/or gross beta activity in continuous air sampling various matrices through glass fiber filter paper Env. Inc., AP-02 Determination of gross alpha and/or gross beta in air particulate filters Air Particulates Gamma Spectroscopy Quarterly composite of TBE, TBE-2007 Gamma emitting radioisotope analysis each station Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Iodine Gamma Spectroscopy Weekly composite of TBE, TBE-2007 Gamma emitting radioisotope analysis continuous air sampling through charcoal filter Env. Inc., 1-131-02 Determination of 1-131 in charcoal I _canisters by gamma spectroscopy (batch method)38 of 108 B-3 TABLE B-2: Radiological Environmental Monitoring ,Program -Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear'Power Station, 2007 Sample Analysis Sampling Method. Analytical Procedure Number Medium Milk 1-131 Bi-weekly grab sample TBE, TBE-2012 Radioiodine in various matrices when cows are on pasture. Monthly all Env. Inc., 1-131-01 Determination of 1-131 in milk by anion other times exchange Milk GammaSpectroscopy Bi-weekly grab sample TBE, TBE-2007 Gamma emitting radioisotope analysis when cows are on pasture. Monthly all Env. Inc., GS-01 Determination of gamma emitters by other times gamma spectroscopy Food Products Gamma Spectroscopy Annual grab samples. TBE, TBE-2007 Gamma emitting radioisotope analysis Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy TLD Thermoluminescence Quarterly TLDs Global Dosimetry Dosimetry 39 of 108 B-4 o Figure B-I Quad Cities REMP Sample Locations

-2 Mile Radius, 2007 00 0 10-. 2 El vir 6 Kl 11I -` 1 -I 0211 a-l EUE.1W t1~21 0 `ll I 011.-1-I -2 cuiL~ orte A-ýWesUA CITIES .Le-13-2-n--k

' ~STTO il5 ~ , ~ FGR --- -~~~3AIJ -I~ji~~ ~ -IS REP SapleLoc26o1 I -~ auh S 33 o Figure B-2 Quad Cities REMP Sampling Locations

-9.3 Mile Radius, 2007 00

-APPENDIX.-C-DATA TABLES AND FIGURES-PRIMARY LABORATORY' 42 of 108 TABLE C-1.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD Q-33 Q-34 12/29/06 -01/05/07 02/23/07 -02/23/07 03/02/07 -03/30/07 04/06/07 05/04/07 06/08/07 07/06/07 08/03/07 09/07/07 10/05/07 11/02/07 12/14/07 04/27/07 05/31/07 06/29/07 07/27/07 08/31/07 09/28/07 10/25/07 11/30/07 12/28/07 2.5 +/- 1.4 4.3 +/- 1.8 5.2 +/- 1.8< 2.6 7.8 +/- 2.1 6.4 +/- 1.8 5.2 +/- 1.8 5.4 +/- 1.8 4.5 +/- 1.8 4.9 +/- 1.9< 2.8 6.3 +/- 1.9 5.5 +/- 2.2 4.3 + 1.7 4.6 + 1.9 5.2 +/- 1.8 5.0 + 2.0 7.2 + 2.0 6.7 + 1.8 3.8 + 1.5 7.5 + 2.0 4.8 + 1.8 6.1 +/- 2.0 4.7 +/- 2.1 4.1 + 1.7 5.4 + 2.5 MEAN*TABLE C-1.2 CONCENTRATIONS OF TRITIUM, I.N SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION PERIOD Q-33 Q-34 01/05/07 04/06/07 07/06/07 10/05/07 03/30/07 06/29/07 09/28/07 12/28/07 1591, 178 192, 171 , <i 67, -.< 178<172 MEAN* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES 43 of 108 c-I TABLE C-I.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-33 12/29/06 02/23/07 03/02/07 04/06/07 05/04/07 06/08/07 07/06/07 08/03/07 09/07/07 10/05/07 11/02/07 12/07/07 MEAN-01/05/07-02/23/07-03/30/07-04/27/07-05/31/07-06/29/07-07/27/07-08/31/07-09/28/07-10/25/07-11/30/07-12/21/07-01/05/07-02/23/07-03/30/07-04/27/07-05/31/07-06/29/07-07/27/07-08/31/07-09/28/07-10/25/07-11/30/07-12/28/07 0.4 3 2 3 1 1 2 1 3 1 2 1<1<3<2<3<2<1<2<1<3<1<3<1<1<3<3<3<2<2<2<1<2<3<2<2<1<6<5<8<3<3<4<3<7<2<6<3<1<6<6<8<4<4<4<3<7<7<6<4<0<2<2<3<1<1<1<1<3<1<2<1<0<3<2<3<2<1<1<1<2<3<3<2<1<5<4<7<3<2<3<2<6<1<6<2<1<5<5<6<3<3<3<2<5<5<5<3<1<3<2<4<2<1<2<1<3<1<3<1<1<3<3<3<2<2<2<1<3<3<3<2<1<5<4<6<3<2<3<2<5<2<5<3<1<5<5<6<3<3<3<2<5<5<4<3<14< 12<10<15<8<11< 13<15< 15< 10< 11< 13<0<2<2<3<1<1<1<1<3<1<2<1<0<2<2<3<1<1<2<1<3<1<2<1<0<3<2<3<2<1<2<1<3<2<2<2<13< 27< 18< 28* 14< 16* 20< 19* 26< 12< 22< 29< 13* 27* 21< 27< 17<.21* 20* 18< 24< 43< 21< 27<4<8<6< 10<4<5<6<6<9<5<7<8 Q-34 12/29/06 02/23/07 03/02/07 04/06/07 05/04/07 06/08/07 07/06/07 08/03/07 09/07/07 10/05/07 11/02/07 12/14/07 MEAN< 0.4<3<2<3<2<1<2<1<2<2<2<1 15 14 11 15 10 15 13 15 15 14 11 12<0<2<2<3<1<1<1<1<2<2<2<1<4<8<7< 10<5<7<6<6<8< 14<8<9 0 0O TABLE C-I1.1 CONCENTRATIONS OF TRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION Q-35 Q-36 PERIOD 01/12/07 -01/12/07 04/13/07 -04/13/07 07/13/07 -07/13/07 10/12/07 -10/12/07* 184< 168< 164< 190* 183< 164< 162< 188 MEAN 45 of 108 C-3 TABLE C-II.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION PERIOD Q-35 01/12/07 -01/12/07 04/13/07 -04/13/07 07/13/07 -07/13/07 10/12/07 -10/12/07 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 MEAN<4<5<4<5<4<6<4<5<6<5<4<5<4<6<3<4<12< 10<9< 10<9<15<8< 11<5<5<4<5<4<9<4<5<11< 10< 10<7<7< 12<7<9<5<5<5<5< 10<8<7<9<7< 15<6<7 13 13 11 13 11 15 10 15<5<4<4<5<5<5<4<5< 27* 31< 29* 32* 27< 38* 23< 30< 11<9<8<8 cI 0-36 01/12/07 04/13/07 07/13/07 10/12/07 MEAN-01/12/07-04/13/07-07/13/07-10/12/07<4 l< 8<4<5<4<7<3<4<4<4<4<4< 8<11<7<8 0 o TABLE C-II1.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PC/KG WET +/- 2 SIGMA STC COLLECTION Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-24 Channel Catfish 05/02/07 < 52 < 57 < 121 < 52 < 114 < 74 < 111 < 51 < 51 < 452 < 144 White Bass 05/02/07 < 58 < 53 < 95 < 63 < 100 < 66 < 96 < 55 < 57 < 491 < 142 Channel Catfish 10/02/07 < 37 < 44 < 126 < 46 < 111 < 55 < 94 < 44 < 53 < 470 < 121 Common Carp 10/02/07 < 55 < 61 < 145 < 48 < 133 < 53 < 100 < 43 < 50 < 519 < 165 MEAN -----------Q-29 Channel Catfish '05/02/07

< 43 < 49 < 110 < 46 < 93 < 54 < 90 < 46 < 45 < 395 < 125 Largemouth Bass 05/02/07 < 59 < 54 < 169 < 48 < 150 < 64 < 96 < 49 < 57 < 502 < 139 Channel Catfish 10/02/07 < 50 < 56 < 143 < 47 < 96 < 47 < 94 < 49 < 54 < 429 < 165 Common Carp 10/02/07 < 36 < 45 < 114 < 41 < 97 < 54 < 106 < 39 < 39 < 444 < 91 MEAN -------(-AI C)00--0 TABLE C-IV.1'CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PC/KG DRY +/- 2 SIGMA STC COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-39 05/25/07 < 46 < 50 10/05/07 < 74 < 70< 112 < 49 < 112 < 68 < 98 < 40< 233 < 56 < 235 < 118 < 162 < 60 70 +/- 48 < 362< 102< 117< 618 < 138 MEAN 70+/-0 -* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES: 00 00 0 00 TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA NEAR-FIELD GROUP I FAR-FIELD GROUP 11 CONTROL IGROUP III COLLECTION PERIOD 12/29/06 -01/05/07 01/05/07 -01/12/07 01/12/07 -01/19/07 01/19/07 -01/26/07 01/26/07 -02/02/07 02/02/07 -02/09/07 02/09/07 -02/16/07 02/15/07 -02/22/07 02/22/07 -03/02/07 03/02/07 -03/08/07 03/08/07 -03/16/07 03/16/07 -03/23/07 03/23/07 -03/30/07 03/30/07 -04/06/07 04/06/07 -04/13/07 04/13/07 -04/20/07 04/20/07 -04/27/07 04/27/07 -05/03/07 05/03/07 -05/11/07 05/11/07 -05/18/07 05/18/07 -05/25/07 05/25/07 -05/31/07 ,05/31/07

-06/08/07 06/08/07 -06/15/07 06/15/07 -06/21/07 06/21/07 06/29/07 06/29/07 -07/06/07 07/06/07 -07/13/07 07/13/07 -07/20/07 07/20/07 -07/27/07 07/27/07 -08/04/07 Q-0 1 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-07 25 +/- 5 22 +/- 4 20 +/- 4 38 +/- 5 21 +/- 5 24 +/- 5 20 +/- 5 27 +/- 5 10 +/- 3 13 +/- 4 18 +/- 4 16 +/- 4 12 +/- 4 14 +/- 4 15 +/- 4 19 +/- 4 17 +/- 4 19 +/- 4 18 +/- 4 15 +/- 4 27 +/- 5 17 +/- 4 11 +/-3 26 +/-5 22 +/-5 16 +/-4 16 +/-4 17 +/-4 13 +/- 4 18 +/- 4 24 +/- 4 23 +/- 5 16 +/- 4 20 +/- 4 24 +/- 4 15 +/- 4 30 +/- 5 25 +/- 4 19 +/- 4 7+/-4 22 +/-5 19 +/-4 21 +/-5 20 +/-4 23 5 25 +/- 5 28 +/- 4 18 +/- 5 45 +/- 6 44 +/- 6 30 +/- 5 20 +/- 4 19 +/- 4 18 +/- 4 34 +/- 5 24 +/- 5 24 +/- 5 17+/- 4 23 +/- 4 10 +/- 3 16 +/- 4 15 +/- 4 18 +/- 4 14 +/- 4 12 +/- 4 16 +/- 4 19 +/- 4 14 +/- 4 14 +/- 4 20 +/- 4 13 +/- 4 19 +/- 4 16 +/- 4 12 +/- 3 17 +/-4 17 +/-4 16 +/-4 17 +/-4 21 +/-5 12 +/-4 20 +/- 5 26 +/- 4 29 +/- 5 11 +/-4 20 +/-4 25 +/-4 15 +/-4 26 +/-5 29 +/-4 21 +/-4 8+/-4 25 +/-6 15 +/-4 22 +/-5 21 +/-4 23 +/- 5 21 +/- 4 29 +/- 5 21 +/- 5 44 +/-6 35 +/-5 25 +/-5 18 +/- 4 20 +/- 4 18 +/- 4 29 +/- 5 22 +/- 4 25 +/- 5 22 +/- 5 27 +/- 5 11 +/-3 14 +/-4 20 +/-4 16 +/-4 10 +/-4 15 +/-4 14 +/-4 16 +/- 4 13 +/- 4 13 +/- 4 17 +/- 4 14 +/- 4 22 t 4 17 +/- 4 12 +/- 3 18 +/- 4 22 +/- 4 12 +/- 4 16 +/- 4 20 +/- 5 11 +/-4 22 +/-5 21 +/-4 33 +/-5 14 +/-4<5 31 +/-5 18 +/- 4 26 +/- 5 27 +/- 4 21 +/- 5 6+/-4 26 +/-6 18 +/-4 23 +/-5 24 +/-5 25 +/-6 26 +/- 5 27 +/- 5 18 +/- 5 54 +/- 6 47 +/- 6 29 +/- 5 24 +/- 5 27 +/- 5 24 +/- 5 44 +/- 6 24 +/- 5 29 +/- 5 20 +/- 5 22 +/- 4 8+/-3 12 +/-4 21 +/-4 15 +/-4 13+/-4 12 +/-4 17 +/-4 19 +/-4 11 +/-4 18+/-4 24 +/-5 17 +/-4 27 +/-5 15 +/- 4 14 +/- 4 22 +/- 4 22 +/- 5 15 +/- 4 19 +/- 4 21 +/- 5 10 +/- 4 22 +/- 5 31 +/- 5 25 +/- 5 18 +/- 4 21 +/- 4 30 +/- 5 16 +/- 4 34 +/- 5 31 +/- 4 20 +/- 5 8+/-5 25 +/-6 17 +/-4 21 +/-5 24 +/-5 30 +/-5 28 +/- 5 29 +/- 5 23 +/- 5 49 +/- 6 40 +/- 6 32 +/- 5 22 +/- 4 24 +/- 5 20 +/- 4 38 +/- 5 23 +/- 5 30 +/- 5 22 +/- 5 26 +/- 5 13 +/- 4 16 +/- 5 19 +/- 4 17 +/- 4 13 +/- 4 16 +/- 5 18 +/- 4 18 +/- 4 14 +/-4 21 +/-5 21 +/-4 16 +/-4 22 +/-4 16 +/- 5 15 +/- 4 22 +/- 4 30 +/- 6 23 +/- 4 20 +/- 5 23 +/- 5 13 +/- 4 27 +/- 5 30 +/- 5 28 +/- 5 17 +/- 4 23 +/- 5 29 +/- 5 20 +/- 4 30 +/- 5 21 +/- 4 22 +/-5 9+/-4 28 +/-5 21 +/-5 23 +/-4 22 +/-5 26 +/-5 22 +/- 4 26 +/- 5 19 +/- 4 50 +/- 6 41 +/-6 31 +/-6 21 +/- 4 26 +/- 5 23 +/- 5 38 +/- 5 26 +/- 5 24 +/- 5 21 +/- 4 23 +/- 4 13 +/- 4 16 +/- 5 20 +/- 4 18 +/- 4 15 +/-4 13 +/-4 13 +/- 4..18 +4 13 +/-4 22 5 19+/-4 12 +/-4 21 +/-4'20 +/- 5*12 +/- 3 27 +/- 5* 24 +/- 5 14 +/- 4 20 +/- 5 19 +/- 5 13 +/- 4 22 +/- 5 27 +/- 5*26 +/- 5 11 +/-4 27 +/-5*26 +/-5 16 +/-4 28 +/-5 20 +/-4 32 +/-5 12 +/-4 28 +/- 5 19 +/- 5 22 +/- 4 21 +/- 4 29 +/- 5 21 +/- 4 33 +/- 5 19 +/- 4 54 +/- 6 52 +/- 6 35 +/- 6 23 +/- 4 25 +/- 5 22 +/- 4 36 +/- 5 22 +/- 5 25 +/- 5 19 +/- 5 29 +/- 5 11 +/-.3 20 +/- 4 20 +/- 4 22 +/- 4 15 +/- 4 16 +/- 4 17 +/- 4 14 +/- 4 11 +/-4 16 +/-4 22 +/-4 13 +/-4 20 +/-4 19 £ý4 17 +/-*4 20 +/-19 +/-£4 120 +/-_4 19 +/- 4.17 +/-4 13 +/-.4 24 +/- 5 24 +/- 4 31 +/- 5 13 +/- 4 24 +/- 5 26 +/- 4 16 +/- 4 27 +/-5 24 +/- 4 21 +/- 4 11 +/-5 32 +/-6 20 +/-4 15 +/-4 20 +/-4 27 +/-5 23 +/- 4 29 +/- 5 20 +/- 5 49 +/- 6 45 +/- 6 28 +/- 5 22 +/- 4 25 +/- 4 16 +/- 4 35 +/- 5 22 +/- 4 24 +/- 4 24 +/- 5 25 +/- 5 12 +/- 3 15 +/- 4 20 +/- 4 17 +/- 4 13 +/- 4 11 +/-4 15 +/-4 19 +/-4 13 +/-4 15 +/-4 15+/-4 13 +/-4 22 +/- 4 17 +/- 4 13 +/- 4 23 +/- 4 20 +/- 4 17 +/- 4 18 +/- 4 15 +/-4 10 +/-4 24 +/- 5 23 +/- 4 29 +/- 5 12 +/- 4 23 +/- 5 33 +/- 5 17 +/- 4 25 +/- 5 25 +/- 4 26 +/- 5 10 +/- 5 32 +/- 6 16 +/- 4 21 +/- 5 29 +/- 5 26 +/- 5 27 +/- 5 33 +/- 5 16 +/- 6 54 +/- 6 52 +/- 6 32 +/- 5 24 20 20 42 23 24 23 26 9 20 16 18 11 13 12 20 16 18 22 13 23 22 16 21 27 17 19 17 13 25 26 30 16 22 28 17 30 28 29 10 31 22 22 22 25 22 35 19 49 45 36+/-5+/-4+/-4+/-5+/-5+/-5+/-5+/-5+/-3+/-5+/-4+/-4+/-4+/-4+/-4+/-4+/-4+/-5+/-4+/-4+/-5+/-5+/-4+/-4+/-5+/-4+/-5+/-4+/-4+/-5+/-5+/-5+/-4+/-5+/-5+/-4+/-5+/-5+/-5+/-4+/-5+/-5+/-4+/-4+/-4+/-4+/-5+/-4+/-6+/-6+/-6 08/10/07.08/17/07 08/24/07 08/31/07 09/07/07 09/14/07 09/21/07.09/30/07.10/07/07 10/13/07.10/19/07 10/25/07 11/02/07 11/09/07 11/16/07 11/23/07 11/30/07 12/07/07 12/14/07 12/21/07 MEAN*(1)-08/17/07-08/24/07-08/31/07-09/07/07-09/14/07-09/21/07-09/30/07-10/07/07-10/13/07-10/19/07-10/25/07-11/02/07-11/09/07-11/16/07-11/23/07-11/30/07-12/07/07-12/14/07-12/21/07-12/28/07 20 +/- 16 20 +/- 14 21 +/- 17 22 +/- 17 23 +/- 15 22 +/- 18 22 +/- 15 22 +/- 18 23 +/- 17*THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C -7 C-7 49 of 108 TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS (PCIICU METER) IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 GROUP I -NEAR-FIELD LOCATIONS GROUP 11 -FAR-FIELD LOCATIONS GROUP III -CONTROL LOCATIONS COLLECTION PERIOD MIN MAX MEAN*2SD COLLECTION PERIOD MIN MAX MEAN+/-2SD 12/29/06 -02/02/07 02/02/07 -03/02/07 03/02/07 -03/30/07 03/30/07 -04/27/07 04/27/07 -06/01/07 06/0 1/07 -06/29/07 06/29/07 -07/27/07 07/27/07 -08/31/07 08/31/07 -09/30/07 09/30/07 -11/03/07 11/03/07 -12/01/07 12/01/07 -12/29/07 18 44 8 29 10 21 11 19 13 27 11 26 10 22< 5 33 15 34 6 26 20 30 18 54 25 +/- 14 20 +/- 13 15 +/- 6 15 +/- 5 18 +/- 8 17 +/- 9 17 +/- 8 22 +/- 12 25 +/- 12 18 +/- 12 25 +/- 6 35 +/- 24 21 +/- 11 12/29/06 -02/02/07 02/02/07 -03/02/07 03/02/07 -03/30/07 03/30/07 -04/27/07 04/27/07 -06/08/07 06/01/07 -06/29/07 06/29/07 -07/27/07 07/27/07 -08/31/07 08/31/07 -10/05/07 09/30/07 -11/09/07 11/03/07 -12/07/07 12/01/07 -12/29/07 12/29/06 -12/29/07 16 38 11 30 13 22 11 19 12 22 13 30 10 27 11 31 16 33 9 32 19' 33 16 54 25 +/- 12 21 +/- 12 17 +/- 5 15 +/- 5 18 +/- 7 21 +/- 9 18 +/- 10 23 +/- 13 24 +/- 10 20 +/- 13 26 +/- 9 40 +/- 26 1 2/2e 02/0 03/0 03/3 04/2 06/C 06/2 07/2 08/3 10/C 11/C 12/C COLLECTION MIN MAX MEAN+/-PERIOD 2SD 9/06 -02/02/07 20 42 26 +/- 19 12/07 -03/02/07 9 26 20 +/- 16 12/07 -03/30/07 11 20 16 +/- 8 10/07 -04/27/07 12 20 15 +/- 7~7/07 -06/08/07 13 23 19 +/- 7 18/07 -06/29/07 17 27 *22 +/- 10~9/07 -07/27/07 13 25 19 +/- 10 7/07 -08/31/07 16 30 23 +/- 12 11/07 -10/05/07 17 30 26 +/- 10 15/07 -11/09/07 10 31 21 +/- 15 19/07 -12/07/07 19 35 25 +/- 14 17/07 -12/28/07 36 49 43 +/- 13 I 00 12/29/06 -12/29/07 < 5 54 9 54 22 +/- 13 12/29/06 -12/28/07 9 49 23 +/-15* THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES 0'00 TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-01 12/29/06 03/30/07 06/29/07 09/30/07 MEAN Q-02 12/29/06 03/30/07 06/29/07 09/30/07 MEAN Q-03 12/29/06 03/30/07 06/29/07 09/30/07-03/30/07-06/29/07-09/30/07-12/29/07-03/30/07-06/29/07-09/30/07-12/29/07<3<3<4<2<4< 5<3< 3<4<' 6< 5<5* 10< 19< 13<9< 11< 15<11< 11 3 3 3 4 MEAN Q-04 12/29/06 03/30/07 06/29/07 09/30/07 MEAN Q-07 12/29/06 03/30/07 06/29/07 09/28/07 MEAN-03/30/07-06/29/07-09/30/07-12/29/07-03/30/07-06/29/07-09/30/07-12/29/07-03/30/07-06/29/07-09/30/07-12/28/07 3 4 3 4 5 2 4 2 5 6 4 3 6 6 5 3 4 5 3 3 15 17 10 13 14 17 12 7 12 16 8 7<5<3<2<3<4<3<2<4< 3.< 2<3< 2"<6< 3.*< 5<2<2<3<3<2< 7<8<8<6< 7< 10<9< 8<5<5<5<3< 7<11< 8<5< 3< 6<4<5< 6<5<3<9! 9.< 12<5<6< 10<7<6< 5<*11<. 5<7<6<7<7<5<7< 13<5<5<6<8<7<6<4 <7<7 <14<54 < 7<5 <8<3<4< 5<3<3< 4<4<4<3<4<4<4<4<3<5<2<2<4<3<2 4 2 4 2 4 3 3 3 4 3 2 3 81 472 100 63 82 553 71 79 73 635 62 95 38 226 25 29 19 244 11 38 28 173 25 25< 35< 179* 28* 28 5 2 3 2* 85< 358< 76< 39 3 3 3 3<5<6<3<3 3 3 2 2 68 557 56 63 27 207 19 24 0 0O TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/-2 SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 STC COLLECTION PERIOD Q-13 12/29/06 03/30/07 06/29/07 09/28/07 MEAN ('i 0 Q-16 12/29/06 03/30/07 06/29/07 09/28/07 MEAN Q-37 12/29/06 03/30/07 06/29/07 09/30/07 MEAN Q-38 12/29/06 03/30/07 06/29/07 09/30/07-03/30/07-06/29/07-09/30/07-12/28/07-03/30/07-06/29/07-09/30/07-12/28/07-03/30/07-06/29/07-09/30/07-12/29/07-03/30/07-06/29/07-09/30/07-12/29/07<3<4<3<3<3<4<3< 2<3<5<4<4<4<3<4<3<5<5<3<4<3<6<4 13 22 9 9 5 13 7 5 12 23 10 9 7 18 9<5<3<4<3<3<3<3<3<5<3<2<4<2< 3<3 12 9 9 6<4<7<4<4<4<5<4<3<7< 13< 7<5<6<9< 6< 3<3<5< 4<3<2<4<4<2 5 8 7 5<4<3<3<2<2<3<2<2<3<3< 3<4< 92< 591< 62< 77< 76< 575< 54< 47< 105<'693< 81< 74 33 225 34 23 18 171 18 24 3 5 3 3 10 9 12 6 5 7 10 4 6 4 4 8 11 7 6 4 11 7 4 4 4 3 2 4 4 36 259 27 36 2 4 3 3 3 6 4<2 < 56-< 3 < 521<.2 < 74< 23< 261< 33< 25< 4 < 11 < 2 <6 < 4 < 8 < 4 < 3 < 71 MEAN 04 00,,

TABLE C-VI-.i CONCENTRATIONS OF 1-131 IN AIR IODINE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA NEAR-FIELD GROUP I FAR-FIELD GROUP 11 CONTROL IGROUP III COLLECTION PERIOD Q-16 Q-01 0-02 Q-03 0-04 Q-13 Q-37 Q-38 Q-07 0 1 2/29/06 01/05/07 01/12/07 01/19/07 01/26/07 02/02/07 02/09/07 02/16/07 02/23/07 03/02/07 03/08/07 03/16/07 03/23/07 03/30/07 04/06/07 04/13/07 04/20/07 04/27/07 05/03/07 05/11/07 05/18/07 05/25/07 05/31/07 06/08/07 06/15/07 06/21/07 06/29/07 07/06/07 07/13/07 07/20/07 07/27/07 08/04/07 08/10/07 08/17/07 08/24/07 08/31/07 09/07/07 09/14/07 09/21/07 09/30/07 10/07/07 10/13/07 10/19/07 10/25/07 11/02/07 11/10/07 11/16/07 11/23/07 11/30/07 12/07/07 12/14/07 12/21/07-01/05/07-01/12/07-01/19/07-01/26/07-02/02/07-02/09/07-02/16/07-02/23/07-03/02/07-03/08/07-03/16/07-03/23/07-03/30/07-04/06/07-04/13/07-04/20/07-04/27/07-05/03/07-05/11/07-05/18/07-05/25/07-05/31/07-06/08/07-06/15/07-06/21/07-06/29/07-07/06/07-07/13/07-07/20/07-07/27/07-08/04/07-08/10/07-08/17/07-08/24/07-08/31/07-09/07/07-09/14/07-09/21/07-09/30/07-10/07/07-10/13/07-10/19/07-10/25/07-11/02/07-11/10/07-11/16/07-11/23/07-11/30/07-12/07/07-12/14/07-12/21/07-12/28/07* 63* 35* 14* 42* 29* 55* 61* 48* 26* 31* 32< 47* 51* 57* 70* 27< 8* 55* 39< 47* 49* 23* 19* 58* 32* 35* 42* 35* 19* 39* 24* 60* 69* 58* 37* 36* 51* 26* 60* 27* 51* 37* 45* 24* 34* 65* 36* 43* 26* 63* 21< 8* 61* 43* 21* 40< 37* 29* 59* 47* 25* 30* 31* 46<50* 55* 68* 27* 15* 53* 37* 46* 47* 22* 18 56* 31* 34* 40* 55< 11* 39* 48* 61* 69* 59* 68* 45* 51* 27* 60* 50* 64* 48* 45* 56* 43* 65< 48* 18* 44* 61* 21* 15* 61* 43* 21* 40* 37* 53* 59* 31* 25* 30* 31* 47* 50* 55* 68* 26* 15* 53* 37* 46* 47* 22* 18* 56.* 31* 34* 40* 55* 18* 21* 48* 60* 69* 58* 68* 47* 52* 27* 62* 52* 66* 48* 47* 58* 44* 67< 49* 44* 45* 40* 14* 15* 63* 44* 21* 42* 39* 55* 61* 48* 26* 31* 32* 47*<51* 57* 70* *27 I,< 16* 55* 39<'47 1 < 49* 23* 19* 58*<17* 35* 42* 57* 19* 40* 50* 62* 43* 61* 68* 47* 52* 27* 62* 52* 66* 48* 47* 58* 44* 67< 49* 44< 45* 62* 22* 15* 67* 45* 28* 28* 39* 45* 48* 46* 32* 39* 33* 43* 59* 47* 46*<14* 58* 30* 47* 63* 31* 19* 62* 42* 42* 29* 42-* 19* 38* 46* 55* 64* 59* 66* 58* 28* 27* 39* 68* 59* 53* 66* 46* 13* 58* 44* 36* 37* 61* 29* 31* 67* 45* 28* 29* 39* 45* 48* 46* 31* 39* 33* 43* 58* 47* 46< 27< 14< 58< 29< 47< 63< 30< 19< 62*< 42< 42< 29< 41*< 19< .38< 46< 54* 64* 59* 66* 57* 52* 22* 39* 68* 60* 53* 66* 48* 12* 60* 44* 37* 37< 61* 30* 30* 68* 46* 28* 28* 39* 44* 58* 51* 30* 29* 37* 42* 61* 35* 55<_ 54<14* 56*<18* 47< .60.24< 21* 58* 33* 48* 27* 41* 19* 36* 40* 59* 67* 46* 65* 57* 51* 27< 31* 55* 66* 59* 45* 48* 21* 70* 44* 30* 43* 63* 29* 24* 68* 46* 28* 16* 39* 44* 58* 51* 30* 29* 37* 42* 61* 35* 55* 54* 14* 56* 33* 47.< 60< 24< 11* 32* 33* 50* 14*< 42* 20* 37* 41* 61* 69* 48* 67* 59* 53* 28* 32* 57* 68* 61* 31* 49* 22* 31< 45* 31* 64* 67* 30* 24* 37j* 42* 21* 29* 38* 54* 27*<42* 16* 22* 15* 26* 29* 56* 32* 54* 16* 37* 29* 36* 34* 20* 19* 62* 40* 16* 29* 56* 19* 41* 55* 37* 66* 25* 69* 46* 52* 27* 32* 62* 59* 42* 66* 57* 46* 58* 48* 54* 39* 60* 22* 19 MEAN C-11 c-il 53 of 108 TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA INDICATOR FARM Q-26 COLLECTION PERIOD 01/05/07 02/02/07 03/02/07 04/07/07 05/04/07 05/18/07 06/01/07 06/15/07 06/29/07 07/13/07 07/27/07 08/10/07 08/24/07 09/07/07 09/21/07 10/07/07 10/19/07 11/03/07 12/07/07< 0.3< 0.3< 0.8<.0.9< 0.8< 0.9< 0.8< 0.6< 0.8< 0.7< 0.5< 0.9< 0.6< 0.9< 0.7< 0.6< 0.6<'0.8< 0.7 MEAN 54 of 108 C-12 TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA STC COLLECTION PERIOD Q-26 01/05/07 02/02/07 03/02/07 04/07/07 05/04/07 05/18/07 06/01/07 06/15/07 06/29/07 07/13/07 07/27/07 08/10/07 08/24/07 09/07/07 09/21/07 10/07/07 10/19/07 11/03/07 12/07/07 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140<6<6<9<5<5<4<4<5<5<5<4<4<6<5<2<6<2<2<5<6<7< 10<8<5<6<5<6<5<5<4<5<6<6<2<8<3<3<6< 16< 14< 21< 18< 13< 17<9< 13< 10< 12< 10< 12< 18< 15<5< 17<6<7< 14<6<5<9<8<5<6<5<5<5<5<5<4<7<6<2<6<2<2<6< 12< 13< 27< 17< 12< 12< 10< 13< 10< 13< 10<9< 13< 15<5< 18<6<6< 13<5<7<9<8<6<6<5<6<5<7<4<5<7<6<2<8<3<3<7<11<11< 15< 15< 10< 10<9<9<9<9<7<9< 13< 10<4< 14<5<6< 11<3<6<9<7<4<5<4<4<4<5<3<4<5<5<2<7<2<2<5<4<6<9<7<6<5<5<5<5<6<4<4<6<6<2<8<2<2<5< 35< 29* 48< 38< 30* 59< 41< 42< 41< 31< 23< 54< 42< 35< 19< 46< 20< 31.< 50< 11 "<9< 13<13<11< 13<11<14< 13-<8<7< 15< 12< 13<5<9<7<9< 15 MEAN tUh C)00 TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION Mn-54 PERIOD Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Q-CONTROL Potatoes Rhubarb Leaves Q-QUAD 1 Potatoes Rhubarb Leaves Q-QUAD 2 Kohlrabi Rhubarb Leaves Q-QUAD 3 Horseradish Rhubarb Leaves 07/09/07 < 25 < 29 < 56 < 18 < 51 < 30 < 34 < 52 < 21 < 29 < 112 < 35 07/09/07 < 11 < 12 < 27 < 10 < 25 < 12 < 22 < 20 < 10 < 11 .< 52 < 16 MEAN 07/09/07 < 26 < 28 < 63 < 21 < 52 < 26 < 41 < 46 < 21 < 28 .< 145 < 44 07/09/07 < 15 < 17 < 39 < 19 < 43 < 16 < 31 < 33 < 18 < 19 < 88 .< 16 MEAN 07/09/07 < 23 07/09/07 < 22< 24 < 75 < 28 < 63 < 24 < 37 < 43 < .24 < 30 <131 "< 34< 22 < 51 < 26 < 46 < 20 < 32 < 39 < 20 < 20 <89 < 22 MEAN 07/09/07 < 22 < 21 " 49 < 25 07/09/07 < 14 < 11 < 21 < 12< 49'. <23-<25.. < 10< 40 < 45- <21< 24 < 22 < 11< 22 < 121< 13 <65< 36< 9 MEAN Q-QUAD 4 Lettuce Potatoes 07/09/07 < 31 < 29 07/09/07 < 18 < 23< 77 < 27 < 78 < 32 < 54 < 55 < 31 < 31 <133 < 49< 53 < 22 , < 49 <27 < 45 < 36 < 20 < 23 < 107 < 40 MEAN 00 0~00 TABLE C-IX.1 QUARTERLY TLD RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF MILLI-ROETGEN/QUARTER

+/- 2 STANDARD DEVIATIONS STATION MEAN JAN -MAR APR -JUN JUL -SEP OCT -DEC CODE 2 S.D.Q-01-1 23.0 +/- 7.1 26 26 19 21 Q-01-2 20.5 +/- 5.3 24 19 18 21 Q-02-1 .21.8 +/- 6.4 24 19 19 25 Q-02-2 20.8 +/- 8.5 27 18 18 20 Q-03-1 19.0 +/- 4.3 22 18 17 19 Q-03-2 19.5 +/- 5.3 23 17 18 20 Q-04-1 20.8 +/- 4.7 24 19 19 21 Q-04-2 22.8 +/- 7.0 27 21 19 24 Q-07-1 22.8 +/- 6.0 27 22 20 22 Q-07-2 21.0 +/- 3.7 23 22 19 .20 Q-13-1 21.3 +/- 7.7 27 19 19 20 Q-13-2 21.8 +/- 3.4 24 22 20 21 Q-16-1 20.0 +/- 5.9 23 17 18 22 Q-16-2 21.0 +/- 4.9 23 20 18 23 Q-37-1 23.8 +/- 6.6 28 23 20 24 Q-37-2 21.3 +/- 3.0 23 20 20 22 Q-38-1 23.3 +/- 6.6 28 21 21 23 Q-38-2 23.3 +/- 6.4 26 21 '. 20 ;26 Q-101-1 20.5 +/- 3.5 23 20 19 20 Q-101-2 21.3 +/- 4.7 23 21 18 *23 Q-102-1 22.3 +/- 5.3 25 20 20 24 Q-102 20.8 +/- 4.1 23 21 18 21 Q-103-1 19.5 +/- 5.3 23 18 17 20 Q-103-2 20.3 +/- 7.2 25 18 17 21 Q-104-1 20.3 +/- 7.2 25 18 17 21 Q-104-2 19.8 +/- 4.7 23 18 18 20 Q-105-1 21.3 +/- 7.0 25 20 17 23 Q-105-2 19.3 +/- 6.6 24 17 17 19 Q-106-2 20.0 +/- 4.3 23 18 19 20 Q-106-3 20.0 +/- 5.2 23 21 17 .19 Q-107-2 21.0 +/- 5.4 25 20 19 20 Q-107-3 21.3 +/- 6.4 26 20 19 20 Q-108-1 20.0 +/- 4.3 23 19 18 20 Q-108-2 20.0 +/- 4.9 23 20 17 20 Q-109-1 21.5 +/- 6.0 25 19 19 23 Q-109-2 21.3 +/- 5.7 25 18 21 21 Q-111-1 23.3 +/- 1.9 24 22 23 24 Q-111-2 20.8 +/- 3.4 23 21 19 20 Q-112-1 22.3 +/- 6.8 27 22 19 21 Q-112-2. 20.3 +/- 4.1 23 18 20 20 Qm113-1 21.3 +/- 5.3 23 19 19 24 Q-113-2 19.3 +/- 5.3 22 17 17 21 Q-114-1 21.3 +/- 5.7 25 19 19 22 Q-114-2 22.3 +/- 4.7 24 22 19 24 Q-115-1 20.8 +/- 8.4 27 19 18 19 Q-115-2 20.5 +/- 5.8 23 18 18 23 Q-116-1 21.5 +/- 5.3 25 20 19 22 Q-116-3 21.3 +/- 5.7 25 19 19 22 57 of 108 C-15 TABLE C-IX;i STATION CODE.QUARTERLY TLD RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF MILLI-ROETGEN/QUARTER

+/-2 STANDARD DEVIATIONS MEAN+/- 2 S.D.JAN-MAR APR-JUN JUL SEP OCT-DEC 0-201-1 Q-201-2 Q-202-1 Q-202-2 Q-203-1 Q-203-2 Q-204-1 Q-204-2 Q-205-1 Q-205-4 Q-206-1 Q-206-2 Q-207-1 Q-207-4 Q-208-1 Q-208-2 Q-209-1 Q-209-4 Q-210-1 Q-210-4 *Q-210-5 Q-211-1 Q-211-2 Q-212-1 Q-212-2 Q-213-1 Q-213-2 Q-214-1 Q-214-2 Q-215-1 Q-215-2 Q-216-1 Q-216-2 22.8 +/- 5.5 23.5 +/- 2.6 20.8 +/- 3.4 20.0 +/- 8.2 22:5. +/- 6.0 23.3 +/- 4.1 23.0 +/- 7.1 24.5 +/- 7.7 23.5 +/- 6.6 23.5 +/- 7.4 21.8 +/- 4.4 22.8 +/- 5.5 22.0 +/- 3.7 23.0 +/- 4.0 22.0 +/- 4.0 23.5 +/- 7.4 21.8 + 4.7*22.3 +/- 3.4 21.8 +/- 8.5 20.3 +/- 6.8 25.0 +/- 4.6 25.3 +/- 5.3 23.5 +/- 3.5 22.3 +/- 7.5 24.8 +/- 14 21.5 +/- 8.1 22.8 +/- 7.7 25.3 +/- 6.6 22.0 +/- 4.3 23.3 +/- 6.6 23.0 +/- 6.7 25.3 +/- 6.6 26 25 23 26 27 26 28 30 28 28 24 26 24 26 25 28 25 24 24 28 25 27 29 25 27 24 27 28 30 25 28 28 29 21 23 20 18 21 21 21 21 23 21 23-20 20 22 21 23 20 22 22 19 19 23 24 24.21 21 19 21 23 21 21 21 25 20 22 21 17.21 23 20 24 20 20 19 21 23 22..21 19 20 20 20 19 17 23 23 21-..-, .18 19 18'19 23 20 21 22 21 24 24 19 19.21 23 23 23 23 25 21 24 21 22 21 24 22 S 22 ,,, 23 21 20 27 25 24 23 35 22 23 25 22 23 21 26* Removed from ODCM in December 2006 and replaced by Q-210-5. Q-210-4 is for trending only.C -16 58 of 108 TABLE C-IX.2 MEAN QUARTERLY TLD'RESULTS FOR THE INNER.RING, OUTER RING,.OTHER AND CONTROL LOCATION FOR QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF MILLI-ROETGEN/QUARTER

+/-2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION PERIOD INNER RING.+/- 2 S.D.OUTER RING OTHER CONTROL JAN-MAR APR-JUN JUL-SEP OCT-DEC 24.1 +/- 2.6 19.4 +/- 2.9 18.5 +/- 2.7 21.2 +/- 3.2 26.5 +/- 3.8 21.4 +/- 3.2 20.5 +/- 3.6 23.1 +/- 5.7 24:9 +/- 4.0 20.0 +/- 4.7 18.9 +/- 2.1 22.0 +/- 4.0:25.0 + 5.7 22.0 +/- 0.0 19.5 +/- 1.4 21.0 +/- 2.8 TABLE C-IX.3

SUMMARY

OF THE AMBIENT DOSIMETRY PROGRAM FOR QUAD CITIES NUCLEAR POWERSTATION, 2007 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER LOCATION OAINSAMPLES, PERIOD ANALYZED MINIMUM PERIOD MAXIMUM PERIOD MEAN+2 S.D.INNER RING OUTER RING OTHER CONTROL 120 -.132 64 8 17 17 17 19 27 35 28 27 20.8 +/- 5.1 22.8 + 6.1.21'.5 5.9 21.9 +/- 4.9 INNER RING STATIONS -Q-101-1, Q-101-2, Q-102-1, Q-102-3, Q-103-1, Q-103-2, Q-104-1, Q-104-2, Q-105-1, Q-105-2, Q-106-2, Q-106-3, Q-107-2, Q-107-3, Q-108-1, Q-108-2, Q-109-1, Q-109-2, Q-111-1, Q-111-2, Q-112-1, Q-112-2, Q-113-1, Q-113-2, Q-114-1, Q-114-2, Q-115-1, Q-115-2, Q-116-1, Q-116-3 OUTER RING STATIONS-Q-201-1, Q-201-2, Q-202-1, Q-202-2, Q-203-1, Q-203-2, Q-204-1, Q-204-2, Q-205-1, Q-205-4, Q-206-1, Q-206-2, Q-207-1, Q-207-4, Q-208-1, Q-208-2, Q-209-1, Q-209-4, Q-210-1, Q-210-4", Q-210-5, Q-211-1, Q-211-2, Q-212-1, Q-212-2, Q-213-1, Q-213-2, Q-214-1, Q-214-2, Q-215-1, Q-215-2, Q-216-1, Q-216-2 OTHER STATIONS -Q-01-1, Q-01-2, Q-02-1, Q-02-2, Q-03-1, Q-03-2, Q-04-1, Q-04-2, Q-13-1, Q-13-2, Q-16-1, Q-16-2, Q-37-1, Q-37-2, Q738-1, Q-38-2 CONTROL STATIONS -Q-07-1, Q-07-2* Removed from ODCM in December 2006 and replaced by Q-210-5. Q-210-4 is for trending only.C -17 59 of 108 FIGURE C-1 Surface Water -.Gross Beta -Stations Q-33 and Q-34 (C)Collected in the Vicinity of QCNPS, 2000 -2004 Q-33 Cordova 2.0 10,0 8.0 6.0 4.0 2M0 0.0 01-00 1 2-31-00 12-31-01 12-3!1-02 12-31-03 12-30-04 Q-34 (C)Camanche 10.0 T 8.0 -No samples;water frozen.6.0 +~4.0 2.0 -0.0 ,i 01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 60 of 108 C -18 FIGUREC-1 (cont.)Surface Water -Gross Beta -Stations Q-33 andQ-34 (C)Collected in the Vicinity of QCNPS, 2005 -2007 Q-33 Cordova 12.0 -10.0 +8.0 +-j G.C.6.0-4.0 +2.0-0.01-12-01-04 09-01-05 06-01-06 03-01-07 12-01-07 Q-34 Camanche 12.0 -10.0 -I 8.0+-j 5-C.6.0+4.0 -1 2.0 0.0 I I I I I I 12-01-04 06-01-05 12-01-05 06-01-06 12-01-06 06-01-07 12-01-07 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 61 of 108 C-19 FIGURE C-2 Surface Water -Tritium -Stations Q-33 and Q-34 (C)Collected in the Vicinity of QCNPS, 2000 -2004.Q-33 Cordova-J 500 400, 300 200 100 0 4--100 1-01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 Q-34 (C) Camanche CJ UL 500 400 300 200 0-100-01-01-00 12-31-00 12-31-01 1 1I I 12-31-02 12-31-03 12-30-04 62 of 108 C -20 FIGURE C-2 (cont.)Surface Water -Tritium -Stations Q-33 and Q-34 (C)iCollected-in the Vicinity of QCNPS, 2005 -2007 Q-33 Cordova 500-400-300-200 100-0.01 03-31-05 09-14-05 02-28-06 08-14-06 01-28-07 07-14-07 12-28-07 Q-34 (C) Camanche 500,-400 -300+,-200 100 -I 0 I I I I I 03-31-05 09-14-05 02-28-06 08-14-06 01-28-07 07-14-07 12-28-07 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 63 of 108 C-21 I FIGURE C-3 Ground Water --Tritium -Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 -2004 Q-35 McMillan Well-J U3 500 400 300 200-100-200 01-01-00 12-31-00\* /1.12-31-01 12-31-02 12-31-03 12-30-04 Q-36 Cordova Well-j 0~500 400 300 200 100 0-100-200 L 01-01-00/ \ z-.-N\ \\12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 64 of 108 C -22 FIGURE C-3 (cont.)Ground Water -Tritium,-

Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2005 -2007 Q-35 McMillan Well 500 400 300 200 100 ,-I--0 4-l 03-31-05 10-02-05 04-05-06 10-07-06 04-10-07 10-12-07 Q-36 Cordova Well 500 400 300 200-J 100 03-31-05 10-02-05 04-05-06 10-07-06 04-10-07 10-12-07 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 65 of 108 C -23 I- TFIGURE C-4 Air Particulates

-Gross Beta- Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 -2004 Q-01 Onsite No. 1 I 8.0 M E.6.0 4,t 2.0 0,0 0 12-31-00 12-31-01 12.31-02 12-31-03 12-30-04 Q-02 Onsite No. 2 C?U 10.0 8.0 4.0 2.0 \0.0 4-01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 66 of 108 C -24 FIGURE C-4 (cont.)Air Particulates

-Gross Beta- Stations Q-01,and Q-02 Collected-in the-Vicinity of QCNPS, 2005.- 2007-: Q-01 Onsite No. I 60.0--50.0 40.0-3 30.0 o 20.0 10.0 *.0.0 01/07/05 06/11/05 11/13/05 04/17/06 09/,19/06 02/21/07 07/26/07 12/28/07 Station Q-01 lost power 10-07-05 21-05.Q-02 Onsite No. 2 60.0 C.)m.9 Lu CD 50.0 40.0 30.0 20.0 10.0 01/07/05 06/11/05 11/13/05 04/17/06 09/19/06 02/21/07 07/26/07 12/28/07 Station Q-02 lost power 08-19-05 26-05.DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C -25 67 of 108 I .FIGURE C-5.Air Particulates

-Gross Beta- Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 -2004 Q-03Onsite No. 3 10.0 8.0 J 6.0 4.0 C.)'4 ul 0 01-01-00 12-31.-00 12-31-01 12-31-02 12-31-03 12-30-04.Q-04 Nitrin to CJ 640 0.0 1- 0 01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 68 of 108 C -26 FIGURE C-5 (cont.)Air Particulates

-Gross Beta- Stations Q-03 and Q-04"Collected in the Vicinity of QCNPS, 2005 -2007 Q-03 Onsite No. 3 60.0-50.040 40.0 D 20-. A, AAAAW\0.ob i ., 01/07/05 06/11/05 11/13/05 04/17/06 09/19/06 02/21/07 07/26/07 12/28/07 Q-'04 Nitrin 60.0 50.0 E 40.0 CL 30.0 o 20.0 10.0 0.0 01/07/05 06/11/05 11/13/05 04/17/06 09/19/06 02/21/07 07/26/07 12/28/07 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C -27 69 of 108 FIGURE C-6 Air Particulates

-Gross Beta- Stations Q-07 (C)Collected in the Vicinity .of QCNPS, 2000 -2004 Q-07 (C) Clinton 10.0 9 0 6°0 4.0 0,0~ ___12-30-04 70 of 108 C -28 FIGURE C-6 (cont.)Air Particulates

-Gross Beta- Stations Q-07 (C)Collected in the Vicinity of QCNPS, 2005-- 2007 Q-07 (C) Clinton 60.0-*50.0 E40.0-Cal 30.0 LU.20.0 10.0-'0.0 I I I I I II 01/07/05 06/11/05 11/13/05 04/17/06 09/19/06 02/21/07 07/26/07 12/28/07 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C -29 71 of 108

.FIGURE C-7 Air. Particulates

-Gross Beta- Stations Q-13 and Q-16 Collected in the Vicinity of QCNPS, 2005 -2007 Q-13 Princeton 60.0 50.0 40.0" 30.0 w 0.20.0 10.0 0.0 08-05 01-05-06 07-05-06 01-02-07 07-02-07 12-30-07 Q-16 Princeton 60.0 50.0 40.0 30.0 20.0 10.0 0.0 4-07-08-05 01-05-06 07-05-06 01-02-07 07-02-07 12-30-07 AIR PARTICULATE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 72 of 108 C-30 FIGURE C-8 Air Particulates

-Gross Beta- Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 -2007 Q-37 Meredosia Road 60.0 50.0 40.0 mo 30.0 9 o 20.0 10.0 0.0 I I I I 07-08-03 01-05-06 07-05-06 01-02-07 07-02-07 12-30-07 S;." ': 6Q-38 Fuller Road 60.0 50.0 40.0" 30.0 u.J 20.0 10.0 0.0 07-08-05 01-05-06 07-05-06 01-02-07 07-02-07 12-30-07 AIR PARTICULATE GROSS BETA ANALYSES OF FAR FIELD LOCATIONS STARTED IN JULY 2005 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 73 of 108 C-31 APPENDIX D INTER-LABORATORY COMPARISON PROGRAM'74 of 108 TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 1 OF 3)Identification Reported Known Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)March 2007 E5255-396 Milk E5256-396 Milk E5258-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60, Cr-51 Cs-134 Cs-1 37 Co-58 Mn-54 Feý59 ZnL65 Co-60, 3/4pCi/L 125 pCi/L 10.8 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 107 269 244 98.1 227 92.5 182.0 108.0 985 143 252 204 74.9 190.0 79.7 156 i99. 1;', 122 34.7 137 10 85.2 297 245 112 234 98.8 182 106 1000 152 245 202 92.3 197.0 81.6 151-87T2 826 126 71.3 E5257-396 Charcoal 1-131 0.91 1.08 1.26 0.91 1.00 0.88 0.97 0.94 1.00 1.02 0.99 0.94 1.03 1.01 0.81 0.96 0.98 1.03 1.14 1.08 0.97 0.49 1.03 1.25 1.01 0.88 0.90 0.81 0.93 0.91 0.98 0.95 0.95 0.89 0.83 0.87 0.80 0.89 0.88 0.99 1.03 1.02 0.89 1.00 A A W A A A A A A A A A A A A A A A A A A N (1)A W June 2007 E5384-396 Milk E5385-396 Milk E5387-396 AP Sr-89 Sr-90 pCi/L 98.3 95.2 pCi/L 16.1 12.9 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 71.0 176 459 197 158 180 163 158 318 212 87.5 232 101 78.9 91.8 85.6 89.8 178 il1 70.1 200 512 242 169 198 166 167 334 238 105 268 127 88.5 104.0 87 87.3 175 125 A A A A A A A A A A A A A A A A A A A A E5386-396 Charcoal 1-131 pCi 79.3 79.1 D-1I 75 of 108 TABLE D-1 ANALYTICSENVIRONMENTAL RADIOACTIVITY CROSS.CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 , (PAGE 2 OF 3)Identification

--Reported Known, Ratio (c)Month/Year Number Matrix Nuclide Units. Value (a) Value (b), TBE/Analytics Evaluation (d)September 2007 E5492-396 Milk E5493-396 Milk E5495-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 99.0 pCi/L 13.9 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 81.9 200 271 131 131 114 171 117 212 143 128 181 85.9 83.2 69.4 112 79.6 159 92.0 94.9 13.1 85.2 211 289 147 131 114 168 111 202 148 136 186 94.7 83.9 73.3 108 71.1 130 95.2 E5494-396 Charcoal 1-131 pCi 70.8 69.5 1.04 1.06 0.96 0.95 0.94 0.89 1.00 1.00 1.02 1.05 1.05 0.97 0.94 0.97 0.91 0.99 0.95 1.04 1.12 1.22 0.97 1.02 0.93 1.02 1.00 0.97 0.97 0.85 1.00 0.91 1.00 1.01 0.99 0.94 0.95 1.04 0.93 1.01 0.98 1.07 1.21 1.11 0.97 December 2007 E5749-396 Milk E5750-396 Milk E5752-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 87.6 pCi/L 15.5 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 60.6 137 497 117 166 159 190 149 231 198 88.6 352 84.6 111 114 135 119 172 137 93.7 15.2 60.8 141 512 137 166 174 190 148 234 211 93.4 340 91.2 110.0 116.0 126 98.5 155 141 A A A A A A A A A A A A A A A A A A w A A D-2 76 of 108 TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE-BROWN ENGINEERING, 2007 (PAGE 3 OF 3)Identification Reported Known , Ratio (c)Month/Year Number Matrix Nuclide Units Value (a) Value (b) TBE/Analytics Evaluation (d)December 2007 E5751-396 Charcoal 1-131 pCi 65.8 74.1 0.89 A (1) New technician counted charcoal cartridge on the back rather than the face, resulting in low activity.

If the charcoal cartridge had been counted on the face, the ratio would have been approximately 1.07, which is acceptable.

NCR 07-02 (a) Teledyne Brown 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. Reported result falls within 0. 70-0.80 or 1.20-1.30.

N = Not Acceptable.

Reported result falls outside the ratio limits of < 0. 70 and > 1.30.D-3 77 of 108 TABLE D-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2007 (PAGE 1 OF 1)Identification

..Reported Known Month/Year Number Media Nuclide Units Value (a) Value (b) Control Limits Evaluation (c)July 2007 Rad 70 Water Sr-89 Sr-90 Ba-1 33 Cs-1 34 Cs-1 37 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 58.6 18.7 18.6 57.6 55.4 31.3 49.0.26.8 12 31.1 1700 58.2'19.0 19.4 68.9 61.3 33.5 54.6 27.1 11.5 26.5 1770"27.4 18.2 12.6 71.1 180 23.2 251 58.6 9.73 28.9 9700 49.5 -66.9 10.3-27.7 10.7-28.1 60.2 -77.6 52.6 -70.0 24.8 -42.2 45.2 -64.0 15.4-38.8 2.84 -20.2 21.3-31.7 1180-2360 A A A N (1)A A A A A A A October 2007 RAD 71 Water Sr-89 Sr-90 Ba-133 Cs-1 34 Cs-137 Co-60 1-',Zn-65 Gr-A Gr-B-131': ~H-3" pCi/L 27.07 pCi/L 17.40 pCi/L 12.57 pCi/L .63.33 pCi/L 168 pCi/L 21.93 pCi/L .245.33 pCi/L -:55.60 pCi/L 15.23 pCi/L .'27.43 pCi/L. 9263.3 19.3 -33.9 12.9- 21.6 8.64- 15.5 58.0 -78.2 162 -200 19.9 -28.3 226 -294 30.6 -72.9 4.26- 18.2 24.0 -33.8 8430- 10700 A A A A A A A A A A A (1) The Cs-134 TBE found/ERA known ratio is 83.6%, which TBE considers acceptable.

NCR 07-07 (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.D-4 78 of 108 TABLE D-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)TELEDYNE BROWNENGINEERING, 2007..(PAGE 1 OF 1)Identification

.Reported Known Acceptance Month/Year Number. Media Nuclide Units Value (a) Value (b) .Range Evaluation (c)February 2007 07-MaW17 Water 07-GrW17:

Water 07-MaS17.

Soil Cs-134 Cs-1 37 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Gr-A Gr-B Cs-134 Cs-137 Co-57 Co-60 Mn-54-K-40 Sr-90:Zn-65 Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L 74.5 162 140.27.9 346 125 8.90 117 83.5 163.0 143.7 26.9 283.0 123.8 8.87 114.8 58.5- 108.6 114-1 -211.9 100.6- 186.8 18.8- 35.0 198.1 -367.9 86.7- 160.9 6.21- 11.53 80.4 -149.2 Bq/L 0.502 0.327 >0.0 -0.654 Bq/L 0.975 0.851 0.426 -1.277 Bq/kg Bq/kg Bq/kg Bq/kg.Bq/kg Bq/kg.Bq/kg Bq/kg* Bq/sample,,.Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 322' 893.508.3.300.3.779.682 293.618.7 3.230-2.453 3.067 2.767 3.557 0.584 2.463 327.4 799.7 471.2 274.7 685.2 602 319.0 536.8 1.4960 2.5693 2.8876 2.9054 3.5185 0.6074 2.6828 229.2 -425.6 559.8 -1039.6 329.8 -612.6 192.3 -357.1 479.6 -890.8 421 -783 223.3 -414.7 375.8 -697.8 2.9372 -5.4548 1.7985 -3.3401 2.0213 -3.7539 2.0338 -3.7770 2.4630 -4.5741 0.4252 -0.7896 1.8780 -3.4876 A A A A W A A A A A A A A A A A A A W A A A A A A A A A A A A A A W 07-RdF17 ;AP .Cs-134;'.Cs-137 Co-57 Co-60 Mn-54 Sr-90 Zn-65 07-GrF17 AP Gr-A Gr-B 07-RdV17 Vegetation Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Bq/sample 0.353 0.601 >0.0 -1.202 Bq/sample 0.500 0.441 0.221 -0,662 February 2007 Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample Bq/sample 6.207 7.80 8.64 6.10 9.41 63.5 1.51 7.15 6.2101 6.9949 8.1878 5.8215 8.4492 4.3471 -8.0731 4.8964 -9.0934 5.7315 -10.6441 4.0751 -7.5680 5.9144- 10.9840 Not evaluated by MAPEP 1.5351 1.0746- 1.9956 5.6991 3.9894 -7.4088 (a) Teledyne Brown Engineering reported result.(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.(c) DOEIMAPEP evaluation:

A=acceptable, W=acceptable with warning, N=not acceptable.

D- 5 79 of 108 TABLE'D-4' ERA(a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2007 (Page 1 of 2).Concentration (pCi/L)Lab Code

• Date Analysis Laboratory ERA -Control Resultb Resultc Limits Acceptance STAP-1 116 STAP-1 116 STAP-l 117 STAP-1 117 STAP-1117 e STAP-1117 STAP-1 117 STAP-1 117 STSO-1 118 STSO-1 118 STSO- 1118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1118 1 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1118' STVE-1 119 STVE-1 119 STVE-11 19 STVE-1119 STVE-1 119'STVE-1 119 STVE-1 119 03/19/07 Gr. Alpha 03/19/07 Gr. Beta 34.64 +/- 2.56 93.41 +/- 3.20 25.8 79.5 12.4 -39 48.8-116 Pass Pass 03/19/07 03/19/07 03/19/07.03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07'03/19/07 03/19/07 03/19/67 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 Co-60 Cs-134 Cs-137 Mn-54 Sr-90.Zn-65 Ac-228 Bi-212 Co-60: Cs- 134 Cs-137 K-40 '" Mn-t54 Pb-212 Pb-21'4 Sr-90 Th-234 Zn-65 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Sr-90 Zn-65 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 1610.00 +/- 8.40 1340.40 +/- 48.84 345.30 +/- 8.20.<5.0.156.10 + 6:60 363.80 +/- 11.90 3097.77 +/- 94.96 2467.87,+/-:+/-

1.14.33 7847.40 +/- 86;60 7910.60:+

356:88 4635.00 +/-99.40 12201.60 +/-423.20< 34.0 2046.80 +/-'127.20 4142.80+/-'

110.40 6163.30 +/- 791.60 4329.40-+/-

569.10 0.00 +/- 0.00 2827.90 +/-.62.40 654.80 +/- 48.40 3307.30 +/- 58.80, 40814.20 +/- 618..80< 27.6 8999.70 +/-+580.90 474.30 +/- 45.70 541.40 +/- 9.00 1623.80 +/- 66.10 1839.10 +/- 17.90<8.1 949.40 +/- 16.70 2009.00 +/- 36.40 1300.0-1120.0 255.0 0.0 156.0 245.0 2790.0, 2500.0.7330.0 7560.0 '430010 11100.0, 0.0 173010"'3330.06" 7500.0 3590.d-, 0.0 2600.0.579.0 2920.0 37900.0 0.0.8890.0, 366.0 10,10.0 732.0 192.0-1620-1380-336 Pass Pass Fail* Pass Pass Pass 66.6 -246 208.0-412 1790.0 -3930 658.0 -3730 5340.0'- 9820 4850.0'- 9070 3290.0 -5580 8050.0 -15000 Pass Pass Pass Pass 1120.0 1980.0 2610.0 2190.0 0.0 1760.0 308.0 2150.0',27200.0'-.2430-4980-1.2400-4560-0-3720-822-4060-53600* ,. Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass"Pass Pass Pass Pass Pass Pass Pass , Pass Pass Pass 4900.0 -11800 267.0-500 STW-1 STW-1 STW-1 STW-1 STW-1 STW-1 120 120 120 120'120 120 536.0 1750.0 1850.0 0.0 ,989.0 1910.0 467.0 1290.0 1570.0-631-2020-2220 630.0 -1320 1600.0 -2410 26.7 -44.1 33.4 -50.8 STW-1 121 04/09/07 Sr-89 STW-1 121 04/09/07 Sr-90 30.7 +/- 4.3 39.3 +/- 1.8 35.4 42.1 Pass Pass D-6 80 of 108 TABLE D-4 ERA t a) STATISTICAL

SUMMARY

PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2007.(Page 2 of 2)Concentration (pCi/L)Lab Code

• Date Analysis Laboratory ERA Control t Resultb. Resultc Limits Acceptance STW-1122 STW-1122 STW-1 122 STW-1 122 STW-1122 STW-1123 STW-1 123 STW-1124 STW-1125 STW-1127*STW-1 127 STW-1 128 STW-1128 STW-1128 STW-1128* STW-1 128.STW-1129 STW-1129 STW- 1131 STW-1131 STW-1 132 STW-1 132 STW-1 132'STW-1 132 STW-1132 STW-1133 STW-1133 STW- 1134 STW-1135 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 07/09/07 07/09/07*07/09/07..07/09/07.

07/09/0T 07/09/0.7.

07/09/07 07/09/07 07/09/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07-10/05/07 ,10/05/07 10/05/07 10/05/07 10/05/07 Ba-133 Co-60 Cs-134 Cs- 137.Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 Sr-89 Sr-90 Ba-133.ýCo-60 .*Cs-134.Cs-137.Zn-65 Gr. Alpha,, Gr. Beta..Sr-89 Sr-90 Ba-133'Co-60 Cs-134 ..-Cs-137 Zn-65 Gr. Alpha'Gr. Beta 1-131 H-3 30.0 +/- 2.4 118.5 +/- 3.9.52.6 +/- 2.3 49.5 +/- 3.8 91.7 +/- 6.3 29.3 119.0 54.3 50.3 88.6 20.6 -38.0 109.0,-129.0 45.6 -63.0 41.6 -59.0 73.3 -104.0 32.0 -81.0 16.6 -'34.0 13.7-24.1 6660.0 -9450.0 Pass Pass Pass Pass Pass 33.8 24.2 19.2 7540.0+/- 3.5+/- 2.3+ 1:.2+/- 255.0 56.5 25.3 18.9 8060.0 Pass Pass Pass Pass 51.7 +/- 5.0'..21.4: +/- 23 19A4+/- 2.2.32.8 +/- 2.0 67.0*+/--2.9

.:61-.6 +/- 3.8 55.6 +/- 7.5-19.2 +/- 1.6 9.1 +/- 0.9 27.3. +/- 3.3 17.7+/- 1f.2 12.2 +/- 3.3, 23.8 +/- 1.4 70.5+/- 4.2 1782 +/- 3.3 263.9 +/-6.9 54.7,+/- 2.1 11.9 +/-.0.9.33.0 +/- 1.5 9965.0.+/- 250.0 58.2 19.0 19:4 33.5.68.9 61.3, 54,.6., 27.1 11.5 27.4 18.2 12.6 23.2 71.1 180.0 251.0 58.6 9.7 28.9 9700.0 49.5- 66.9 10.3- 27.7 10.7 -28.1 24.8 -42.2 6 0 .2 .-7 7 .6 -52.6 -,70.0 45.2 -f64.0 15.54 -138.8 2.8 -.20.2..19.3.- 33.9 12.9- 21.6'8.6 -15.5 19.9 -28.3 58.0 -78.2 162.0 -200.0 226.0 '- 294.0 30.6 -72.9 4.3 -18.2 *24.0 -33.8 8430.0 -1070C Pass Pass Pass Pass Pass* Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 1.0 Pass Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.A high bias (- 20%) was observed in gamma results for air filters. A composite filter geometry was used in the calculations vs. a single filter geometry.

Result of recalculation.

Cs-1 37, 305.8 + 6.0 pCi/filter.

Included in the testing series as a "false positive".

No activity expected.D-7 81 of 108 TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)a ENVIRONMENTAL, INC., 2007 (Page 1 of 1)Lab Codec STW-1110 STW-1 110 STW-1111 STW-1111 STW-1111 STW-1111 STW-1111 STW-1111 STW-1111 Date 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 Analysis Gr. Alpha Gr. Beta Co-57 Cs-134 Cs-1 37 H-3 Mn-54 Sr-90 Zn-65 Laboratory res 0.45 +/- 0.(0.90 +/- 0.1 151.60 +/- 10 79.20 +/- 8.(168.70 +/- 12 262.20 +/- 9.'130.60 +/- 11 9.60 +/- 1.4 123.70 +/- 17 Concentration b Known sult Activity 08 0.33 14 0.85.00 143.70 00 83.50.10 163.00 10 283.00.50 123.80 40 8.87.00 114.80 Control Limits d Acceptance 0.00 -0.65 0.43-1.28 100.60 58.50 114.10 198.10 86.70 6.21 80.40 329.80 192.30 229.20 ,559.80 479.60-186.80-108.60-211.90-367.90-160.90-11.53-149.20-612.60-357.10-425.60-.1039.60-890.80 STSO-1 112 STSO-1 112 STSO-1 112 STSO-1 112.STSO-11 12Z STAP-1 113 STAP-1 113 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STVE-1115 STVE-1115 STVE-1 115 STVE-1 115 STVE-1 115 01/01/07 01/01/07 01/01/07 01/01/07'01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 Co-57 Co-60 Cs-1 34...Cs-1 37 , Mn-54 Gr. Alpha Gr. Beta 501.20 +/- 2.90 285.90 +/- 2.10 325.90 +/- 7.40 855.70 +/-A.60.,7`50690C

'4370 0.27 +/- 0.04 0.57 +/- 0.05 471.20 274.70 327.40 799.70.-685-.2b0 0.60 0.44 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 0.00-1.20 0.22 -0.66 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-134 Cs-137 Mn-54 3.51 +/- 0.07 2.98 +/- 0.10 4.02 +/- 0.16 2.75 +/- 0.12 3.94 +/- 0.12 0.58 +/- 0.18 2.70 +/- 0.10 8.90 +/- 0.20 6.50 +/- 0.20 6.90 +/- 0.30 8.20 +/- 0.30 10.10 +/- 0.30 2.89 2.91 4.20 2.57 3.52 0.61 2.68 8.19 5.82 6.21 6.99 8.46 2.02 2.03 2.94 1.80 2.46 0.43 1.88 5.73 4.08 4.35 4.90 5.91-3.75-3.78-5.45-3.34-4.57-0.79-3.49-10.64-7.57-8.07-9.09-10.98 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.D- 8 82 of 108 APPENDIX E ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR)83 of 108 Docket No: 50-254 50-265 QUAD CITIES NUCLEAR POWER STATION UNITS 1 and 2 Annual Radiological Groundwater Protection Program Report 1 January Through 31 December 2007 Prepared By Teledyne Brown Engineering Environmental Services I S Nuclear Quad Cities Nuclear Power Station Cordova, IL 61242 May 2008 84 of 108 Table Of Contents I. "Sum m ary and C onciJ'sion,...............M.........I............

.........

........ 1 11. Introduction

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

4 A. Objectives of the RGPP...............................................................

4 B. Implementation of the Objectives.....................................................

4 C. Program Description

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

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

6 Ill. Program Description

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

6 A. Sample Analysis .......................................................................

6 B. Data Interpretation

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

7 C. Background Analysis.:

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

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

8 IV. Results and Discussion

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

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

10 85 of 108 Appendices Appendix A Location Designation Tables Table A-i: Radiological Groundwater Protection Program -Sampling Locations, Quad Cities Nuclear Power Station, 2007 Figures Figure A-i: Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2007 Appendix B Data Tables;Table B-1.1.Concentrations of Tritium in Groundwater Samples Collected in the Vici nity of Quad Cities Nuclear Power Station, 2007.Table B-1.2 Concentrations of Gamma Emitters.in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear PowerStation, 2007: Table B-11.1 Concentrations of Tritium'-in Surface'Water Samples Coliected in the Vicinity of Quad Cities Nuclear Power'Station, 2007.Table B-11.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.ii 86 of 108

1. Summary and Conclusions This report on the Radiological Groundwater Protection Program (RGPP)conducted for the Quad Cities Nuclear Power Station (QCNPS) by Exelon Nuclear covers the period 01 January 2007 through 31 December 2007.In 2006, Exelon instituted a comprehensive program to evaluate the impact of station operations on groundwater and surface water in the vicinity of QCNPS.This evaluation involved numerous station personnel and contractor support personnel.

This report covers groundwater samples, collected from the environment on station property in 2007. During that time period, 236 analyses were performed on 199 samples from 38 locations.

In assessing all the data gathered for this report,it was concluded that the operation of QCNPS had no adverse radiological impact on the environment offsite of QCNPS.Tritium was detect6d ini twVb'groundwater samples at concentrations of 21,900 pCi/L and 30, 400' CijL, exceeding the United Statesý Environmental Protection Agency (USEPA) drinking.water.

standard (and the-Nuclear Regulatory Commission Reporting-Limit)' of 20,000 pCi/L. Low levels of tritium were detected at concentrations greater than the LLD of 200 pCi/L in 14 of 38 groundwater monitoring The tritiurri concentrations ranged from 203 to 8,280 pCi/L. Low levels 6f trtium Were detected at*concentrations greater than the LLD of 200,pCi/L both surface water monitoring locations.

The concentrations ranged from 275"to 438 pCi/L.Gamma-emitting radionuclides associated with licensed plant operations were not detected at concentrations greater than their respective Lower Limits of Detection (LLDs) as specified in the Offsite Dose Calculation Manual (ODCM) in any of the groundwater samples. In the case of tritium, Exelon specified that it's laboratories achieve a lower limit of detection 10 times lower than that required by federal regulation.

Most of the tritium that was detected in groundwater at the Station is on the south and east side of the Reactor / Turbine buildings.

Strontium-90 was not evaluated in 2007.87 of 108 Intentionally left blank-'3-88 of 108 II. Introduction The Quad Cities Nuclear Power Station (QCNPS), consisting of two 2957 MWth boiling water reactor owned and operated by Exelon Corporation, is located in Cordova, Illinois along the Mississippi River. Unit No. 1 went critical on 16 March 1972. Unit No. 2 went critical on 02 December 1973. The site is located in northern Illinois, approximately 182 miles west of Chicago, Illinois.This report covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2007.A. Objective of the RGPP The long-term objectives of the RGPP are as follows: 1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.

3. Perform routine teir samrpling 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 Quad Cities Nuclear Power Station as discussed below: 1. Exelon and its consultant identified locations as described in the Phase 1 study. Phase 1 studies were conducted by Conestoga Rovers and Associates (CRA) and the results and conclusions were made available to state and federal regulators as well as the public on an Exelon web site in station specific reports.http l/www.exelonCorp.com/ourcompanies/powergen/nuclear/Tritiu mchJln-4-89 of 108

2. The Quad Cities Nuclear Power Station reports describe the local hydrogeologic regime. Periodically, the flow patterns on the surface- and shallow subsurface are updated based on ongoing measurements.

3. Quad Cities Nuclear Power Station will continue to perform routine sampling and radiological analysis of water from selected locations.

4. Quad Cities Nuclear Power Station has implemented procedures to identify and report new leaks, spills, or other detections with potential radiological significance in atimely manner.5. Quad Cities Nuclear Power-Station staff and consulting hydrogeologist assess analytical results.on an ongoing basis to identify adverse trends.'C. Program Description S 1,,. Sample Collection.-

%Sarmiple locations can be-found in:Table' A-iand Figures A-i, Appendix A.Groundwater and Surface Water-' .Samples of water are collected, managed, transported and analyzed in accordance with approved procedures following regulatory methods. Both groundwater and surface water are collected.

Sample locations,'sample:collection frequencies and analytical frequencies are controlle'd in accordance with approved station procedures.

Contractor and/or station personnel are trained in the collection, preservation management, and shipment of samples, as well as in documentation of sampling events.Analytical laboratories'are subject to internal quality assurance programs, inter-laboratory cross-check programs, as well as nuclear industry audits. Station personnel review and evaluate all analytical data deliverables after initial review by the contractor.

Analytical data results are reviewed by both station personnel and an independent hydrogeologist for adverse trends or changes to hydrogeologic conditions. 90 of 108 D. Characteristics of.Tritium (H-3)Tritium (chemical symboltH-3) is a radioactive isotope of hydrogen.

The most common form of tritium is tritium oxide, which is also called "tritiated water." The chemical properties of tritium are essentially those of ordinary hydrogen..

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

Tritium is also, produced during nuclear weapons explosions, as a by-product in reactors producing electricity, and in special production re'actors, where.;the isotopes lithium-7 and/or boron-10 are activated to produce tritium. Like normal water,- tritiated water is colorless and odorless.

Tritiated water behaves chemically and physically like non-tritiated water in the subsurface, an d.therefore tritiated water will travel at the same velocity as the average groundwater velocity.Tritium has a half-life of approximately 12.3 years. It decays spontaneously to helium-3 (3He). This radioactive decay releases a beta-particle, (low-energy, electron).

The radioactive decay of tritium is the source of the health risk from exposure to tritium. Tritium is one of the least dangerous, radionupc ides because it emits very weak beta radiation and leaves the body relatively quickly. Since tritium is almost always found as water, it goes directly into soft tissues and organs. The associated dose to these tissues is generally uniform and is dependent on the water content of the specific tissue.Ill. Program Description A. Sample Analysis This section describes the general analytical methodologies used by TBE to analyze the environmental samples for radioactivity for the Quad Cities Nuclear Power Station RGPP in 2007.-6-91 of 108 In order to achieve the stated objectives, the current program includes the following analyses: 1. Concentrations of gamma emitters in groundwater and surface water.2., Concentrations of strontium in groundwater and surface water.3. Concentrations of tritium in groundwater and surface water.B. Data Interpretation The radiological data collected prior to Quad CitiesNuclear Power Station becoming operational were used as a baseline with which these operational data were compared.

For the purpose of this report, Quad Cities Nuclear Power Stationrwas considered operational at initial criticality.

Several factors were important in the interpretation of the data: 1... Lower Limit of Detection and MinimumDetectable Concentration The lower limit of detection (LLD) is specified by federal regulation as a minimum sensitivity value that, rnust be achieved routinely by the~analytical parameter.

2. Laboratory.

MeasurementsUncertanty

." The-estimated uncertainty in rmeasurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence.

The convention is to report results with a 95% level of confidence.

The uncertainty comes from calibration standards, sample volume or weight measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of a measurement created by statistical process (counting-error) as well as all sources of error (Total Propagated Uncertainty or TPU). Each result has two values calculated.

Exelon reports the TPU by following the result with plus or minus +the estimated sample standard deviation, as TPU, that is obtained by propagating all sources of analytical uncertainty in measurements.'

Analytical uncertainties are reported at the 95% confidence level in this report for reporting consistency with the Annual Radiological 92 of 108 Environmental Operating Report (AREOR);Gamma spectroscopy results for each type of sample were grouped as follows: For groundwater and surface water 14 nuclides, Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb-95, Zr-95, 1-131, Cs-134, Cs-137, Ba-140 and La-140 were reported.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. Theenvironmental media sampled and analyzed during the pre-operational, REMP were atmospheric radiation, fall-out, .domestic water, surface water, marinelife, and vegetation.

The resultsof the. monitoring Were detailed.in the reports entitled, Quad Cities Nuclear Power Plant Environmental Monitoring R .eport; Commonwealth Edison.lCompany,.covering the period from July 1968 through September 1971.The pre-operational REMP contained analytical, results from samples collected from the surface water and groundwater..

1. Background.

Concentrations.

ofT.ritium

...I The-purpose of the following discussion is.to summarize background measurements of tritium in various media performed by others.a. .Tritium Production Tritium-is created in the environment from naturally occurring processes both cosmic and subterranean, as well as from anthropogenic (i.e., man-made) sources. In the upper-*atmosphere, "Cosmogenic" tritium is produced from the bombardment of stable nuclides and combines with oxygen to form tritiated water, which will then enter the hydrologic cycle. Below ground, "lithogenic" tritium is produced by the bombardment of natural lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater. 93 of 108 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 iadditional testing, resulting in the release of significant amounts of tritium to the atmosphere.

The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.

b. Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides.

Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in Precipitation (GNIP).-and USEPA's RadNet.,,database.

GN I P provides, tritium precipitation concentration data for samples collected world wide from 1960 to 2006.RadNet provides tritium precipitation concentration data for samples collected at stations through out the U.S. from 1960 up to and including 2006. Based on GNIP data for sample stations located in-the U.S. Midwest, tritium concentrations peaked around 1963. This peak, which approached 10,000 pCi/L for-somestations,:coincided with the atmospheric testing of thermonuclear.

weapons. Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a gradual decline since that time. Tritium concentrations in Midwest precipitation have typically been below 100 pCi/L since around 1980. Tritium concentrations in wells may still be above the 200 pCi/L detection limit from the external causes described above.c. Surface Water Data Tritium concentrations are routinely measured in large surface water bodies, including the Mississippi River. Illinois surface water data were typically less than 100 pCi/L.The USEPA RadNet surface water data typically has a reported 'Combined Standard Uncertainty' of 35 to 50 pCi/L.According to USEPA, this corresponds to a +/- 70 to 100 pCi/L 95% confidence bound on each given measurement.

Therefore, the typical background data provided may be subject to measurement uncertainty of approximately

+/- 70 to 94 of 108 100 pCi/L.The radio-analytical laboratory is counting tritium results to an Exelon specified LLD of 200 pCi/L. Typically, the lowest positive measurementwill be reported within a range of 40-240 pCi/L or 140 +/- 100 pCi/L. Clearly, these sample results-cannot be distinguished as different from background at this concentration.

IV. Results and Discussion A. Groundwater Results Groundwater; Samples4were collected, from on-site .wblls in accordance with the station"radiological grounidwater protection program. Analytical results and,,anomalies are'discussed below.Tritium~'Samples from all locationswere, analyzed for tritium activity (Table B-1.1 Appendix'B).

Tritiumvalues ranged from the detection limit to.30,400 pCi/I. All samplesobtained at the site boundaries were less then the detection limitof200 pCi/L. The location most representative of potential offsite user of drinking water was <200 pCi/L., Strontium-90 was not evaluated in 2007.Gamma Emitters Naturally occurring Potassium-40 was detected in three of 27 samples. The concentrations ranged from 155 pCi/liter to 226 pCi/liter.

No other gamma emitting nuclides were detected. (Table B-1.2, Appendix B).Surface Water IrillUm Samples from two locations were analyzed for tritium activity (Table-10-95 of 108 B-II.1 Appendix B). Tritium values ranged from the detection limit to 438 pCi/l. The location most representative of potential offsite user of drinking water was <200 pCi/L.Strontium Strontium-90 was not evaluated in 2007.Gamma Emitters No gamma emitting nuclides were detected. (Table B-11.2, Appendix B).-11 -96 of 108 I APPENDIX A LOCATION DESIGNATION 97 of 108 TABLE A-1: Radiological Groundwater Protection Program -Sampling Locations, Quad Cities Nuclear Power Station, 2007 Site Site Type MW-1 MW-2 MW-QC-1011 MW-QC-101S MW-QC-102D MW-QC-1021 MW-QC-102S MW-QC-1031 MW-QC-104S MW-QC-1051 MW-QC-1061 MW-QC-106S MW-QC-1071 MW-QC-108D MW-QC-1081 MW-QC-108S MW-QC-1091 MW-QC-109S MW-QC-1101 MW-QC-111D1 MW-QC-1 11D2 MW-QC-1111 MW-QC-1 121 MW-QC-1131 MW-QC-1141 MW-QC- 115S MW-QC-1 16S STP SAND POINT WELL WELL #1 WELL #5 WELL #6 LITTLE FISH WELL #7 BIG FISH WELL WELL #8 FIRE TRAINING WELL WELL #9 DRY CASK WELL WELL #10 FISH HOUSE WELL WELL #11 SPRAY CANAL WELL SURFACE WATER #1 SPRAY CANAL -ACCESS ROAD SURFACE WATER #2 SPRAY CANAL -RIVER ROAD Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Production Well Production Well Production Well Production Well Production Well Production Well Production Well Production Well Production Well Surface Water Surface Water A-1 98 of 108 KK K~KK~42 ~ K K" K" K K K 52KV K ij/ K, ( ,S &, V 1...... .....K KK~2~K 1 ~<.; It 4~5f~S P K 5 V*52 2 V ~K~4S2 5 I~~K4K" 1.1 A ~KS ~K K¶ KIS K~ *K'~$KK.K~K~NN,.~

U 1-."N3/4. --S K N' ~ S5~i. ~KKKAK> $~KPKKK~ K 2 K4K~KK -i-K552$LKKSE KKK

• K" 3/4I'KZ9,*~~**K 4fl4,, 2K~ *-KK~ -.____43/4."*Kt* j ____K*-VK. KKKKKIKK.

flK EKX,<K (K AK..*KKKK2-KK C KKK"IK KKKKKK KKKKKK5KKNAK#KIK"I~KK~4 1K*?,~a4K*KKC*1KIKI2$

2KKJ~KKKIKK3KKKKKVK~KK 4 t'¶K4KSKKtKKKKK;K 1/4H ~""~K K-K N 2- K"N' N K/ "K!3/4.- Kfly."-K'.

4/NJ K~KQ, Kr.V 554.NJ ~K ff1 K/K" 9 9 7 ii I -5K FIGURE A-1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2007 00 a 00 APPENDIX B..DATA TABLES 100 of 108 TABLE B-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION DATE SITE MW-i MW-i MW-i MW-i MW-i MW-2 MW-2 MW-2 MW-2 MW-2 MW-QC-1011 MW-QC-1011 MW-QC-1011 MW-QC-1011 MW-QC-1011 MW-QC-1OiS MW-QC-10iS MW-QC-iOlS MW-QC-10lS MW-QC-i01S MW-QC-102D MW-QC-1 02D MW-QC-102D MW-QC-102D MW-QC-102D MW-QC-102D MW-QC-102D MW-QC-1021 MW-QC-1021 MW-QC-1021 MW-QC-1021 MW-QC-1021 MW-QC- 021 MW-QC-1021 MW-QC-1021 MW-QC-102S MW-QC-102S MW-QC-102S MW-QC-1 02S MW-QC-102S MW-QC-102S MW-QC-102S MW-QC-1 031 MW-QC-1031 H-3 02/22/07 05/16/07 09/19/07 10/17/07 12/12/07 02/22/07 05/16/07 09/19/07 10/17/07 12/12/07 02/22/07 05/16/07 09/19/07 10/16/07 12/12/07.02/22/07 05/16/07 09/19/07 10/16/07 12/12/07 02/22/07 05/16/07 06/05/07 06/19/07 09/19/07 10/16/07 12/12/07 02/22/07 05/16/07 06/05/07 06/19/07 07/16/07 09/19/07 10/16/07 12/12/07 02/22/07 05/16/07 06/05/07 06/19/07 09/19/07 10/16/07 12/12/07 02/23/07 05/16/07 203 + 126* 162* 189* 196* 181* 192* 161* 189* 195* 181* 190* 155 188 + 119* 187<:: .? i 'i ' 1'69 : .* 158* 180* 189* 162 3640 + 426.. i. '3970, +/-+44Q 3060 +/- 353 2940 +/- 350 3760 +/- 440 3110 +/- 218 3340 +/- 398 5590 +/- 616 17100 +/- 1740 30400 +/- 3060 21900 +/- 2230 8280 +/- 873 4090 +/- 472 6120 +/- 363 3900 +/- 455< 176 2160 +/- 263 724 +/- 132< 188< 184* 189< 174< 189< 154 B -I 101 of 108 TABLE1 B-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF.QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF. PCI/LITER

+/- 2 SIGMA COLLECTION DATE SITE H-3 MW-QC-1031 MW-QC-1 031 MW-QC-1031 MW-QC-1 04S MW-QC-1 04S MW-QC-104S MW-QC-104S MW-QC-104S MW-QC-1051 MW-QC-1051 MW-QC-1051 MW-QC-1051 MW-QC-1051 MW-QC-1061 MW-QC-1 061 MW-QC-1061 MW-QC-1061 MW-QC-1061 MW-QC-106S MW-QC-1 06S MW-QC-106S MW-QC-106S MW-QC-106S MW-QC-1071 MW-QC-1071 MW-QC-1071 MW-QC-1071 MW-QC-1071 MW-QC-108D MW-QC-108D MW-QC-108D MW-QC-108D MW-QC-108D MW-QC-108D MW-QC-108D MW-QC-1081 MW-QC-1081 MW-QC-1081 MW-QC-1081 MW-QC-1081 MW-QC-1081 MW-QC-1081 MW-QC-108S MW-QC-108S 09/19/07 10/17/07 12/12/07 02/23/07 05/16/07 09/19/07 10/16/07 12/12/07 02/23/07 05/16/07 09/19/07 10/16/07 12/12/07 02/23/07 05/16/07 09/19/07 10/17/07 12/12/07 02/23/07 05/16/07 09/19/07 10/17/07 12/12/07 02/21/07 05/15/07 09/18/07 10/15/07 12/10/07 02/22/07 05/15/07 06/05/07 06/19/07 09/18/07 10/16/07 12/11/07 02/22/07 05/15/07 06/05/07 06/19/07 09/18/07 10/16/07 12/11/07 02/21/07 05/15/07< 186< 190< 171< 188< 150< 185* 188< 172< 189< 159< 188< 188'< 181.< 193< 154.'194 +/- 122< 187:ý< 183,"230 +/- 127< 154.:< 192,i< 188%< 183.-< 191< 156'< 191< 187,< 182 3300 5180 6260 5810 5950 8050 6770 1290 1730 3080 3500 3680 4930 5330 363 787+/- 398+/- 563+/- 671+/- 632+/- 656+/- 870+/- 741+/- 199+/- 223+/- 355+/- 406+/- 433+/- 560+/- 597+/- 128+/- 137 B- 2 102 of 108 TABLE B-1.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES, COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007:RESULTS IN UNITS OF PCI/LITER

+/-2 SIGMA SITE MW-QC-108S MW-QC-108S MW-QC-108S MW-QC-108S MW-QC-108S MW-QC -1091 MW-QC-1091 MW-QC-1091 MW-QC-1091 MW-QC-1091 MW-QC-i09S MW-QC-1 09S MW-QC-109S MW-QC-109S MW-QC-109S MW-QC-1 101 MW-QC-1101 MW-QC-1101 MW-QC-1101 MW-QC-111 Dl MW-QC-111 Dl MW-QC-111 Dl MW-QC-111 Dl MW-QC-111 Dl MW-QC-111 D2 MW-QC-1 11 D2 MW-QC-1 11 D2 MW-QC-1 11 D2 MW-QC-111 D2 MW-QC-1111 MW-QC- 111i MW-QC- 111i MW-QC-111I MW-QC-1111 MW-QC-1 121 MW-QC-1 121 MW-QC-1 121 MW-QC-1 121 MW-QC-1 121 MW-QC-1 121 MW-QC-1 121 MW-QC-1131 MW-QC-1131 MW-QC-1 131 COLLECTION DATE 06/05/07 06/19/07 09/18/07 10/16/07 12/11/07 02/22/07 05/16/07 09/19/07 10/17/07 12/12/07 02/22/07 05/16/07 09/19/07 10/17/07 12/12/07 02/21/07 05/15/07 09/19/07 12/11/07 02/21/07 05/15/07 09/18/07 10/16/07 12/11/07 02/21/07 05/15/07 09/18/07 10/16/07 12/11/07 02/21/07 05/15/07 09/18/07 10/16/07 12/11/07 02/21/07 05/15/07 09/18/07 10/16/07 12/11/07 12/11/07 12/11/07 02/21/07 05/15/07 09/18/07 H-3 843 870 478< 190 424 1380 429 492++142 157 135+ 132+/- 214+ 118+ 139< 196*.396 +/- 129 187 159 191 192'182 189 157 1886 180 193.157-190 195.186 191 162 187 197-181 185 409 +/- 115<* '187* 196* 184* 184* 163* 185* 195 446 +/- 132 252 +/- 125 412 +/- 119<. 184< 160< 192 B- 3 103 of 108 TABLE B-I.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE MW-QC-1 131 MW-QC-1131 MW-QC-1 141 MW-QC-1 141 MW-QC-1 141 MW-QC-1141 MW-QC-1 141 MW-QC-1 15S MW-QC-1 15S MW-QC -115S MW-QC-i 15S MW-QC-1 15S MW-QC-1 16S MW-QC-1 16S MW-QC-1 16S MW-QC-1 16S MW-QC-1 16S MW-QC-1 16S STP-SANDPOINT WELL STP-SANDPOINT WELL STP-SANDPOINT WELL STP-SANDPOINT WELL WELL #1 WELL #1 WELL #1 WELL #1 WELL #1 WELL #1 WELL #1 WELL #1 WELL #1 WELL #1 WELL #1 WELL #10 FISH HOUSE WELL WELL #10 FISH HOUSE WELL WELL #10 FISH HOUSE WELL WELL #10 FISH HOUSE WELL WELL #11 SPRAY CANAL WELL WELL #11 SPRAY CANAL WELL WELL #11 SPRAY CANAL WELL WELL #5 WELL #5 WELL #5 WELL #5 COLLECTION DATE 10/16/07 12/11/07 02/21/07 05/15/07 09/18/07 10/16/07 12/11/07 02/22/07 05/15/07, 09/17/07 10/15/07 12/10/07 02/21/07 05/15/07 09/17/07 10/15/07 12/10/07 12/10/07 02/22/07 05/14/07 09/20/07 10/30/07 02/06/07 02/22/07 03/26/07 05/14/07 06/05/07 06/19/07 07/16/07 08/22/07 09/20/07 10/30/07 11/30/07 02/22/07 05/14/07 09/20/07 11/01/07 05/14/07 09/20/07 11/01/07 03/26/07 05/14/07 06/05/07 06/19/07 H-3< 195< 180< 189< 160< 190< 189* 182< 190* 160< 192< 198< 178< 189< 156 203 +/- :122< 195 222 +/- 118< 195< 191< 157 1< 92< 189 287'327 395 313 414 257< 164 373 307 225 231< 190< 159< 192< 190< 159< 192< 193< 190< 151< 153< 184+/-+/-+++/-+/-+/-++/-128 124 140 110 117 126 109 128 127 126 B- 4 104 of 108 TABLE B-I.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE QC-MW-1 QC-MW-2 QC-MW-QC-101 I QC-MW-QC-101S QC-MW-QC-102D QC-MW-QC-1021 QC-MW-QC-102S QC-MW-QC-1031 QC-MW-QC-104S QC-MW-QC-1051 QC-MW-QG-1061 QC-MW-QC-106S QC-MW-QC-1071 QC-MW-QC-108D QC-MW-QC-1081 QC-MW-QC-108S QC-MW-QC-1 091 QC-MW-QC-109S QC-MW-QC-1101 QC-MW-QC-111 Dl QC-MW-QC-111 D2 QC-MW-QC-1111 QC-MW-QC-1 121 QC-MW-QC-1 131 QC-MW-QC-1 141 QC-MW-QC-1 15S QC-MW-QC-1 16S COLLECTION PERIOD 09/19/07 09/19/07 09/19/07 09/19/07 09/19/07 09/19/07 09/19/07 09/19/07 09/19/07 09/19/07 09/19/07 09/19/07 09/18/07 09/18/07 09/18/07 09/18/07 09/19/07 09/19/07 09/19/07 09/18/07 09/18/07 09/18/07 09/18/07 09/18/07 09/18/07 09/17/07 09/17/07 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< 42< 30< 16< 20< 27< 38< 46* 42< 30< 34< 30< 39< 33< 39* 41< 42< 50< 47< 44< 54< 41< 47* 31< 50< 48< 33* 38< 41 226< 18< 21< 30< 40< 46< 85.36< 93* 65< 107< 33< 91* 50< 53< 107 155< 41* 122* 46< 39< 62< 120* 89 197< 116<5+56 <4<2< 2<3< 5<6<..4<j 3 S<4<3<4<4<4<5<5< '6+ 79 < 5'<5<6<5<5<4<6<5+/- 47 < 4<5<5<3<2<2<3<'5"< 5<5< 3<5<4<5<4<5<5<.5< : 6<5<6<5<4<5<3<6<5<4<4<9<8<4<4<7<9< 11<8<9.< 8< 7< 10<8* 10< 12<.11.'< "'11< 12< 12<9< 10*<. 7< 10-*10<8< 10.<4<4<2<2<4< 4-< 6.'< 4<5<'4<4<4<4<7<'4< 5'.'<5<6<5<5<4<6<7< 4"<6<9<8<4<4<6<11<"9<'9<':8< 7'<6< 10<9<8< 11<.10'"< 9" <'.'11"< 10< 11< 10< 10<9< 10< 10< 7'< 9<5<4<2<2<4<4<6<6<4.<5< 3<5<4<5<5< 6-'<5< .5<6<7<5<5<4< 7<6'< 4<5<9< 7< 3<4<6<9< 10<8<8< 7< 7-<9< 8<8<9<11< 12<9< 11< 12<9< 11<8< 12< 11< 8< 11<4<3<2<2<3<4<5<4<3<4<3<4<4<4<4<5<5< 5<5<5<4<5<4<5<4<3<4<4<2<2<3"<5'<5'< 4"< 4< 4<4<5<4'<4<5< 5<6<<5'< 6< 6<<5<6< 4< 6<5<4.22 17 9 11 15 25 27 24 19 21 18 22 22 25 27 27 33 27 30 30 25 27 23 31 26 20<8<5<3<4< 6'<8<9<9<6< 7< 6< 8<6< 9<9<7< 10< 11< 10<9<7<9<6< 11<9<6< 4 < 5 < 29 o< 11 L.,h C O4*

TABLE B-11.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE SURFACE WATER #1 SURFACE WATER #1 SURFACE WATER #1 SURFACE WATER #1 SURFACE WATER #2 SURFACE WATER #2 SURFACE WATER #2 SURFACE WATER #2 COLLECTION DATE 05/14/07 06/04/07 06/18/07 09/17/07 05/14/07 06/04/07 06/18/07 09/17/07 H-3 413 +/- 115 438 +/- 116< 191< 190 330 +/- 110 275 +/- 108< 187< 187 B- 6 106 of 108 TABLE B-Il.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 SITE PERIOD SURFACE WATER #1 09/17/07 SURFACE WATER #2 09/17/07< 45 < 100 < 5 < 6 < 10 < 6< 43 < 52 < 5 < 5 < 12 < 6<11 <6 <9 <11 <4< 11 < 4 < 10 < 11 < 5<5 <29 <9<5 < 29 <9 0 00 0-..00 TABLE B-1.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2007 RESULTS IN UNITS OF PCI/LITER

+/- 2 SIGMA SITE WELL #5 WELL #5 WELL #5 WELL #5 WELL #5 WELL #6 LITTLE FISH WELL WELL #6 LITTLE FISH WELL WELL #6 LITTLE FISH WELL WELL #6 LITTLE FISH WELL WELL #7 BIG FISH WELL WELL #7 BIG FISH WELL WELL #7 BIG FISH WELL WELL #7 BIG FISH WELL WELL #7 BIG FISH WELL WELL #7 BIG FISH WELL WELL #8 FIRE TRAINING WELL WELL #8 FIRE TRAINING WELL WELL #8 FIRE TRAINING WELL WELL #8 FIRE TRAINING WELL WELL #9 DRY CASK WELL WELL #9 DRY CASK WELL WELL #9 DRY CASK WELL WELL #9 DRY CASK WELL COLLECTION DATE 07/16/07 08/22/07 09/20/07 10/30/07 11/30/07 02/22/07 05/14/07 09/20/07 11/01/07 02/22/07 05/14/07 06/05/07 06/19/07 09/20/07 11/01/07 02/22/07 05/14/07 09/20/07 10/30/07 02/22/07 05/14/07 09/20/07 10/30/07 H-3< 165< 144< 187< 192< 191* 195< 152< 190< 193 205 341 421 236 221+ 126+ 110+ 119+ 129+ 126< 191< 189 169 +/- 105* 193* 196* 190< 156< 191* 188 B -8 108 of 108