Text

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)
	v • d • e

Exelon Generation Company, LLC www.exeloncorp.com Exelkn,.

Quad Cities Nuclear Power Station Nuclear 22710 206t' Avenue North Cordova, IL61242-9740 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 ................................................................................................ 1 II. Intro d uctio n ........................................................................................................................ 2 A . O bjectives of the R EM P ................................................................................... 2 B. Implementation of the Objectives ..................................................................... 2 III. P rog ram D escription ................................................................................................... .. 2 A . S am ple Co llection ........................................................................................... .. 2 B. Sample Analysis .......................................... 4 C . D ata Interpretatio n ................................................................................ 5 D . P rogram Exceptions ...................................................................................... . . 6 E . P rogram C hanges ........................................................................................... . . 8 IV. Results and Discussion .............. ............................ 8 A. Aquatic Environment .................. ;. .......................... 8

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

2. Ground Water ...................................... 9 3 . F is h ....................................................................................................... . . 9 4 . Se d im e nt ............................................................................................ . . 10 B. Atmospheric Environment . ................................... 10

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

a. Air Particulates ................................. 10 b . A irbo rne Iodine ............... ......................................................... . . 11 2 . T e rre stria l ........................................................................................... . . 11 a . M ilk ......................................................................................... . . 11

b. Food P roducts ........................................................................ . . 12 C. Ambient Gamma Radiation ............................................................................ 12 D. Interim Spent Fuel Storage .................................. 12 E . Land Use S urvey ........................................................................................... . . 12 F . E rra ta D a ta .............................................................. ............................................. 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 Radiological Environmental Monitoring Program for Quad Cities Nuclear Power Station, 2007 Appendix B Location Designation, Distance & Direction, and Sample Collection &

Analytical Methods Tables Table B-i: Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2007 Table B-2: Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2007 Figure.-

Figure B-i: Quad Cities REMP Sampling Locations - 2 Mile Radius, 2007 Figure B-2: Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2007 Appendix C Data Tables and Figures - Primary Laboratory Tables Table C-I.1 Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

Table C-1.2 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

Table C-1.3 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

Table C-I1.1 Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

Table C-11.2 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 Concentrations of Gamma Emitters in Fish Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

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

Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

Table C-VI.1 Concentrations of 1-131 in Air Iodine Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

Table C-VII.1 Concentrations of 1-131 in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

Table C-VII.2 Concentrations of Gamma Emitters in Milk Samp.les Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

Table C-VIII.1 Concentrations of Gamma Emitters in 'Food Products Samples' Collected in the Vicinity of Quad Cities Nuclear Power Station, 2007.

Table C-IX.1 Quarterly TLD Results for Quad Cities Nuclear Power Station, 2007.

Table C-IX.2 Mean Quarterly TLD Results-for the Inner Ring; Outer Ring, Other and Control Locations for Quad Cities Nuclear Power Station, 2007.

Table C-IX.3 Summary of the Ambient Dosimetry Program for Quad Cities Nuclear Power Station, 2007.

Figures Figure C-1 Surface Water - Gross Beta - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2007.

Figure C-2 Surface Water - Tritium - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2007.

Figure C-3 Ground Water - Tritium - Station Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2007.

Figure C-4 Air Particulates -)Gross Beta - Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2007.

Figure C-5 Air Particulates - Gross Beta - Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2007.

Figure C-6 Air Particulates - Gross Beta - Station Q-07 (C) Collected in the Vicinity of QCNPS, 2000 - 2007.

iii 4 of 108

Figure C-7 Air Particulates - Gross Beta' Stations Q-13 and Q-16 Collected in the Vicinity of QCNPS, 2007.

Figure C-8 AirParticulates - Gross Beta - Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2007.

Appendix D 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.

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 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 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.

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 S1of 108

Table D-1 LISTING OF SAMPLE ANOMALIES (continued)

Sample Location Collection :Reason Type Code Date A/I Q-37 07/20/07 Estimated time; low timer reading possibly due to adverse weather A/I Q-38 07/20/07 Estimated time; low timer reading possibly due to adverse weather A/I Q-38 09/14/07 Estimated time; low timer reading for no apparent reason A/I Q-37 09/14/07 Estimated time; low timer reading for no apparent reason:

A/I Q-38 12/07/07 Estimated time; low timer reading possibly due to adverse weather A/I Q-38 12/14/07 Estimated time; low timer reading possibly due to adverse weather TLD Q-213-1 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 Table D-2 LISTING OF MISSED SAMPLES Sample Local [ion Collection Sample Locat Reason Type Cod e Date SW Q-33 01/19/07 No sample; water frozen SW Q-34 01/19/07 No sample; water frozen SW Q-33 01/26/07 No sample; water frozen SW Q-33 02/02/07 No sample; water frozen SW Q-34 02/02/07 No sample; water frozen SW Q-33 02/16/07 No sample; water frozen SW Q-34 02/16/07 No sample; water frozen 12 of 108

Table.D-2 LISTING OF MISSED SAMPLES (continued)

Sample Location Collection Reason Type Code Date A/M Q-03 03/09/07 Collector found 4" of water inside sample station TLD Q-210-5 03/30/07 TLD not received from vendor; collector placed spare TLD Q-215-2 03/30/07 TLD found broken; collector placed spare SW Q-34 12/07/07 No sample; water frozen SW Q-33 12/14/07 No sample; water frozen SW Q-33 12/28/07 No sample; water frozen AP All 08/04/07 - 08/10/07 Shipment damaged. In repackaging, U*,-, iscarueu 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 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:

GrossBeta 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/mi3 with a mean of 21 E-3 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/mi3. 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.

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.

17 of 108

Distance in Miles from QCNPS Sector Residence Livestock Milk Farm Miles Miles Miles N 0.6 2.7 NNE 3.8 5.4 NE 1.3 ENE 2.9 2.9 E 2.3 2.7 ESE 2.8 3.1 3.1 SE 2.5 5.5 SSE 1.1. 3.6 6.6 S 0.8 1.6 CI MA/

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 8 but is actually 30 (page 88).

Page 37 of 227, 2Q06, Q-205-1 is recorded as 11 but is actually 37 (page 88).

Page 45 of 227, 3Q06, Q-108-1 is recorded as 30 but is actually 27 (page 87).

Page 54 of 227, 4Q06, Q-205-1 is recorded as 13 but is actually 33 (page 88).

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" 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% <

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.

20 of 108

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING

'REPORT

SUMMARY

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 GR-B 24 4 5.2 5.3 5.3 Q-34 CONTROL 0 (PCI/LITER) (10/12) (12/12) (12/12) CAMANCHE - UPSTREAM (2.5/7.8) (3.8/7.5) (3.8/7.5) 4.4 MILES NNE OF SITE H-3 8 200 <LLD <LLD 0 GAMMA 24 MN-54 15 <LLD <LLD 0 CO-58 15 <LLD. <LLD 0 FE-59 30 <LLD <LLD 0 CO-60 15 <LLD <LLD 0

MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) 00

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 ZN-65 30 <LLD <LLD 0 (PCI/LITER)

NB-95 15 <LLD <LLD 0 ZR-95 30 <LLD <LLD 1-131 15 <LLD <LLD CS- 134 15 <LLD <LLD CS-137 18 <LLD <LLD 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 BA-140 60 <LLD <LLD 0 (PCI/LITER)

LA-140 15 <LLD <LLD 0 GROUND WATER H-3 8 200 <LLD NA 0 (PCI/LITER)

GAMMA 8 MN-54 15 <LLD NA 0 CO-58 15 <I LD NA - 0

-FE-59 30 <LLD NA 0 CO-60 15 <LLD NA 0 oc MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M) 00 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 ZN-65 30 <LLD NA 0 (PCI/LITER)

NB-95 15 <LLD NA 0 ZR-95 30 <LLD

NA 0 1-131 15 <LLD NA 0 CS-134 15 <LLD NA 0 CS-137 18 <LLD NA BA- 140 60 <LLD NA t,1 0

MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) 00

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 LA- 140 15 <LLD NA 0 (PCI/LITER)

U'h FISH GAMMA 8 (PCI/KG WET) MN-54 130 <LLD <LLD 0 CO-58 130 <LLD <LLD 0 FE-59 260 <LLD <LLD 0 CO-60 130 <LLD, *LLD 0 ZN-65" 260 <LLD <LLD 0 NB-95 NA <LLD <LLD 0 0

MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) 00

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 ZR-95 NA <LLD <LLD 0 (PCI/KG WET)

CS-134 130 <LLD <LLD 0 CS-137 150 <LLD .- - <LLD

0 BA- 140 NA <LLD <LLD 0 LA-140 NA <LED - ELLD 0 SEDIMENT GAMMA 2 (PCI/KG DRY) MN-54 NA <LLD NA 0

MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

Co 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 CO-58 NA <LLD NA 0 (PCI/KG DRY)

FE-59 NA <LLD NA 0 CO-60 NA .<LLD NA 0 ZN-65 NA <LLD... NA, 0 NB-95 NA <LLD NA 0 ZR-95 NA <LLD NA 0 CS-134 150 <LLD NA 0 00 0

00 MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) 00

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 CS-137 180 70 NA 70 Q-39 INDICATOR 0 (PCI/KG DRY) (1/2) (1/2) CORDOVA - DOWNSTREAM MISSISSIPPI RIVER (70). (70) 0.8 MILES SSW OF SITE 00 BA- 140 NA <LLD NA 0 LA-140 NA <LLD NA 0 AIR PARTICULATE GR-B 459 .10 21 23 23 Q- 13 INDICATOR 0 (PCI/TOTAL) (407/408) (51/51) (51/51) PRINCETON (6/54) (9/49) (9/50) 4.7 MILES SW OF SITE GAMMA 36 MN-54 NA <LLD ;<LLD 0 CO-58 ,NA., .<LLD - <LLD 0 FE-59 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 CO-60 NA <LLD <LLD 0 (PCI/TOTAL)

ZN-65 NA <LLD <LLD 0 NB-95 NA <LLD -.-...... <LLD 0 ZR-95 NA., <LLD <LLD 0 CS-134 50 <LLD <LLD 0 CS-137 60 <LLD <LLD 0 BA-140 NA <LLD <LLD 0 00 0

MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M) 0*

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 LA- 140 NA <LLD <LLD 0 (PCI/TOTAL) 0 AIR IODINE GAMMA 468 (E-3 PCI/CUMETER) 1-131 70 <LLD <LLD MILK 1-131 19 <LLD NA 0 (PCI/LITER)

GAMMA 19 MN-54 NA <LLD NA CO-58 NA <LLD NA FE-59 NA <LLD . NA CO-60 NA <LLD NA 0

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 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 ZN-65 NA <LLD NA 0 (PCI/LITER)

NB-95 NA <LLD NA 0 ZR-95 NA- <LLD *NA 0 CS-134 .15. <LLD, NA 0 CS-137 18 <LLD NA 0 BA-140 60 <LLD NA 0 LA-140 15 <LLD NA 0 0

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 VEGETATION GAMMA 10 (PCI/KG WET) MN-54 NA <LLD <LLD 0 CO-58 NA <LLD <LLD 0 FE-59 NA <LLD <LLD' 0 CO-60 NA <LLD <LLD 0 ZN-65 NA <LLD , <LLD 0 NB-95 NA <LLD <LLD 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-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 ZR-95 NA <LLD -<LLD 0 (PCI/KG WET) 1-131 60 <LLD <LLD 0 CS- 134 60 <LLD - <LLD 0 CS-137 80 <LLD -. LLD 0 BA- 140 NA <LLD <LLD 0 LA-140 NA <LLD <LLD 0 DIRECT RADIATION TLD-QUARTERLY 324 NA 21.8 21.9 25.3 Q-211-2 INDICATOR 0 (MILLI-ROENTGEN/QTR.) (316/316) (8/8) (4/4)

(17/35) (19/27) (23/29) 4.5 MILES SW w

00a MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) 00

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 Cordova (indicator) 3.1 miles SSW Q-34 Camanche, Upstream (control) 4.4 miles NNE B Ground/Well Water Q-35 McMillan Well (indicator) 1.5 miles S Q-36 Cordova Well (indicator) 3.3 miles SSW C, Milk - hi-weekly I monthly Q-26 Bill Stanley Dairy (indicator) 3.5 miles ESE U /ir M.*arflIl aiPS I air Ilaiflnp Q-01 Onsite 1 (indicator) 0.5 miles N Q-02 Onsite 2 (indicator) 0.4 miles ENE Q-03 Onsite 3 (indicator) 0.6 miles S Q-04 Nitrin (indicator) 1.7 miles NE Q-07 Clinton (corntrol) 8.8 miles NE Q-13 Princeton '(indicator) 4.7 miles SW Q-16 Low Mobr (indicator). 5.7 miles NNW Q-37 Meredosia. Road (indicator) 4.4 miles ENE Q-38 Fuller Road (indicator) 4.7 miles E F Fish Q-24 Pool #14 of Mississippi River, Downstream (indicator) 0.5 miles SW Q-29 Mississippi River, Upstream (control) 1.0 miles N F Sediment Q-39 Cordova, Downstream on Mississippi River (indicator) 0.8 miles SSW G Food Products Quadrant 1 Janet Price 6.0 miles NE Quadrant 2 Dale Nimmic 3.0 miles ESE Quadrant 3 Amy Johnston 1.8 miles S Quadrant 4 Mike Fawcett 4.5 miles NW Control Charles Leavens 9.5 miles NE H Fnvironmental Dosimetry - TLD Inner Ring Q-101-1 0.6 miles N Q-101-2 0.9 miles N Q-102-1 1.3 miles NNE Q-102-3 1.4 miles NNE Q-103-1 and -2 1.2 miles NE Q-104-1 1.1 miles ENE Q-104-2 0.9 miles ENE Q-105-1 and -2 0.8 miles E Q-106-2 and -3 0.7 miles ESE Q-107-2 0.7 miles SE Q-107-3 0.8 miles SE Q-108-1 1.0 miles SSE Q-108-2 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 0.9 miles S Q-109-2 1.2 miles S Q-1 11-1 2.6 miles SW Q-111-2 2.5 miles SW Q-112-1 2.5 miles WSW Q-112-2 2.2 miles WSW.

Q-113-1 and-2 2.5 miles W Q-1 14-1 2.1 miles WNW Q-114-2 2.5 miles WNW Q-115-1 2.6 miles NW Q-115-2 2.3 miles NW Q-116-1 2.3 miles NNW Q-116-3 2.4 miles NNW 0 ijtpr Ring Q-201-1 and -2 4.2 miles N Q-202-1 4.4 miles NNE Q-202-2 4.8 miles NNE Q-203-1 4.7 miles NE Q-203-2 5.0 miles NE Q-204-1 4.7 miles ENE,..

Q-204-2 4.5 miles ENE Q-205-1 4.7 miles E Q-205-4 4.8 miles E Q-206-1 and -2 4.8 miles ESE Q-207-1 and -4 4.7 miles SE Q-208-1 4.3 miles SSE Q-208-2 4.9 miles SSE Q-209-1 and -4 4.7 miles S Q-210-1 and -4

4.1 miles SSW Q-210-5 3.3 miles SSW Q-211-1 and -2 4.5 miles SW Q-212-1 5.4 miles-WSW Q-212-2 4.4 miles WSW Q-213-1 4.3 miles W Q-213-2 4.8 miles W Q-214-1 4.7 miles WNW Q-214-2 4.4 miles WNW Q-215-1 5.0 miles NW.

Q-215-2 4.2 miles NW Q-216-1 4.6 miles NNW Q-216-2 4.3 miles NNW Othe.

Q-01 Onsite 1 (indicator) 0.5 miles N Q-02 Onsite 2 (indicator) 0.4 miles ENE Q-03 Onsite 3 (indicator) 0.6 miles S Q-04 Nitrin (indicator) 1.7 miles NE Q-13 Princeton (indicator) 4.7 miles SW Q-16 Low Moor (indicator) 5.7 miles NNW Q-37 Meredosia Road (indicator) 4.4 miles ENE Q-38 Fuller Road (indicator) 4.7 miles E Control Q-07 8.9 miles NE 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 El vir 10-. 2 6 Kl 11I 1 - I -`

0211 a-l EUE.1W t1~

21 `ll0 I 011.-

1-I -2 cuiL~ orte A-ý WesUA

. CITIES Le-13-2-n--k ' ~STTOFGR il5 ~ , ~ -

-- -~~~3AIJ - I~ji~~ ~ - IS REP SapleLoc26o1 I - ~

33 auh S 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 Q-33 Q-34 PERIOD 12/29/06 - 01/05/07 2.5 +/- 1.4 4.3 + 1.7 02/23/07 - 02/23/07 4.3 +/- 1.8 4.6 + 1.9 03/02/07 - 03/30/07 5.2 +/- 1.8 5.2 +/- 1.8 04/06/07 04/27/07 < 2.6 5.0 + 2.0 05/04/07 05/31/07 7.8 +/- 2.1 7.2 + 2.0 06/08/07 06/29/07 6.4 +/- 1.8 6.7 + 1.8 07/06/07 07/27/07 5.2 +/- 1.8 3.8 + 1.5 08/03/07 08/31/07 5.4 +/- 1.8 7.5 + 2.0 09/07/07 09/28/07 4.5 +/- 1.8 4.8 + 1.8 10/05/07 10/25/07 4.9 +/- 1.9 6.1 +/- 2.0 11/02/07 11/30/07 < 2.8 4.7 +/- 2.1 12/14/07 12/28/07 6.3 +/- 1.9 4.1 + 1.7 MEAN* 5.5 +/- 2.2 5.4 + 2.5 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 Q-33 Q-34 PERIOD 01/05/07 03/30/07 1591, , <i 67, -.

04/06/07 06/29/07 178 < 178 07/06/07 09/28/07 192,

<172 10/05/07 12/28/07 171 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 - 01/05/07 0.4 <1 <1 <0 <1 <1 <1 <14 <0 <0 <13 <4 02/23/07 - 02/23/07 3 <3 <6 <2 <5 <3 <5 < 12 <2 <2 < 27 <8 03/02/07 - 03/30/07 2 <2 <5 <2 <4 <2 <4 <10 <2 <2 < 18 <6 04/06/07 - 04/27/07 3 <3 <8 <3 <7 <4 <6 <15 <3 <3 < 28 < 10 05/04/07 - 05/31/07 1 <2 <3 <1 <3 <2 <3 <8 <1 <1

14 <4 06/08/07 - 06/29/07 1 <1 <3 <1 <2 <1 <2 <11 <1 <1 < 16 <5 07/06/07 - 07/27/07 2 <2 <4 <1 <3 <2 <3 < 13 <1 <2

20 <6 08/03/07 - 08/31/07 1 <1 <3 <1 <2 <1 <2 <15 <1 <1 < 19 <6 09/07/07 - 09/28/07 3 <3 <7 <3 <6 <3 <5 < 15 <3 <3

26 <9 10/05/07 - 10/25/07 1 <1 <2 <1 <1 <1 <2 < 10 <1 <1 < 12 <5 11/02/07 - 11/30/07 2 <3 <6 <2 <6 <3 <5 < 11 <2 <2 < 22 <7 12/07/07 - 12/21/07 1 <1 <3 <1 <2 <1 <3 < 13 <1 <1 < 29 <8 MEAN Q-34 12/29/06 - 01/05/07 < 0.4 <1 <1 <0 <1 <1 <1 15 <0 <0 < 13 <4 02/23/07 - 02/23/07 <3 <3 <6 <3 <5 <3 <5 14 <2 <3

27 <8 03/02/07 - 03/30/07 <2 <3 <6 <2 <5 <3 <5 11 <2 <2

21 <7 04/06/07 - 04/27/07 <3 <3 <8 <3 <6 <3 <6 15 <3 <3 < 27 < 10 05/04/07 - 05/31/07 <2 <2 <4 <2 <3 <2 <3 10 <1 <2 < 17 <5 06/08/07 - 06/29/07 <1 <2 <4 <1 <3 <2 <3 15 <1 <1 <.21 <7 07/06/07 - 07/27/07 <2 <2 <4 <1 <3 <2 <3 13 <1 <2

20 <6 08/03/07 - 08/31/07 <1 <1 <3 <1 <2 <1 <2 15 <1 <1

18 <6 09/07/07 - 09/28/07 <2 <2 <7 <2 <5 <3 <5 15 <2 <3 < 24 <8 10/05/07 - 10/25/07 <2 <3 <7 <3 <5 <3 <5 14 <2 <2 < 43 < 14 11/02/07 - 11/30/07 <2 <2 <6 <3 <5 <3 <4 11 <2 <2 < 21 <8 12/14/07 - 12/28/07 <1 <2 <4 <2 <3 <2 <3 12 <1 <2 < 27 <9 MEAN 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

184

183 04/13/07 - 04/13/07 < 168 < 164 07/13/07 - 07/13/07 < 164 < 162 10/12/07 - 10/12/07 < 190 < 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 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-35 01/12/07 - 01/12/07 <4 <6 <12 <5 <11 <5 < 10 13 <5 <5 < 27 < 11 04/13/07 - 04/13/07 <5 <5 < 10 <5 < 10 <5 <8 13 <4 <5

31 <9 07/13/07 - 07/13/07 <4 <4 <9 <4 < 10 <5 <7 11 <4 <4 < 29 <8 10/12/07 - 10/12/07 <5 <5 < 10 <5 <7 <5 <9 13 <5 <5

32 <8 MEAN 0-36 01/12/07 - 01/12/07 <4 <4 <9 <4 <7 <4 <7 11 <4 <4

27 <8

<9 l< 8 cI 04/13/07 - 04/13/07 <6 <6 <15 < 12 < 15 15 <7 <4 < 38 <11 07/13/07 - 07/13/07 <4 <3 <8 <4 <7 <4 <6 10 <3 <4

23 <7 10/12/07 - 10/12/07 <5 <4 < 11 <5 <9 <5 <7 15 <4 <4 < 30 <8 MEAN 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 - - - - - - - - - - -

(-AI 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 - - - - - - -

C)

--0 00

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 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-39 05/25/07 < 46 < 50 < 112 < 49 < 112 < 68 < 98 < 40 70 +/- 48 < 362 < 102 10/05/07 < 74 < 70 < 233 < 56 < 235 < 118 < 162 < 60 < 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 FAR-FIELD CONTROL GROUP I GROUP 11 IGROUP III COLLECTION PERIOD Q-0 1 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-07 12/29/06 -01/05/07 25 +/- 5 20 +/- 4 18 +/- 4 24 +/- 5 22 +/- 4 21 +/- 4 23 +/- 4 22 +/- 4 24 +/-5 01/05/07 -01/12/07 22 +/- 4 19 +/- 4 20 +/- 4 27 +/- 5 24 +/- 5 26 +/- 5 25 +/- 5 25 +/- 4 20 +/-4 01/12/07 -01/19/07 20 +/- 4 18 +/- 4 18 +/- 4 24 +/- 5 20 +/- 4 23 +/- 5 22 +/- 4 16 +/- 4 20 +/-4 01/19/07 -01/26/07 38 +/- 5 34 +/- 5 29 +/- 5 44 +/- 6 38 +/- 5 38 +/- 5 36 +/- 5 35 +/- 5 42 +/-5 01/26/07 -02/02/07 21 +/- 5 24 +/- 5 22 +/- 4 24 +/- 5 23 +/- 5 26 +/- 5 22 +/- 5 22 +/- 4 23 +/-5 02/02/07 -02/09/07 24 +/- 5 24 +/- 5 25 +/- 5 29 +/- 5 30 +/- 5 24 +/- 5 25 +/- 5 24 +/- 4 24 +/-5 02/09/07 -02/16/07 20 +/- 5 17+/- 4 22 +/- 5 20 +/- 5 22 +/- 5 21 +/- 4 19 +/- 5 24 +/- 5 23 +/-5 02/15/07 -02/22/07 27 +/- 5 23 +/- 4 27 +/- 5 22 +/- 4 26 +/- 5 23 +/- 4 29 +/- 5 25 +/- 5 26 +/-5 02/22/07 -03/02/07 10 +/- 3 10 +/- 3 11 +/-3 8+/-3 13 +/- 4 13 +/- 4 11 +/-.3 12 +/- 3 9 +/-3 03/02/07 -03/08/07 13 +/- 4 16 +/- 4 14 +/-4 12 +/-4 16 +/- 5 16 +/- 5 20 +/-4 15 +/- 4 20 +/-5 03/08/07 -03/16/07 18 +/- 4 15 +/- 4 20 +/-4 21 +/-4 19 +/- 4 20 +/- 4 20 +/- 4 20 +/- 4 16 +/-4 03/16/07 -03/23/07 16 +/- 4 18 +/- 4 16 +/-4 15 +/-4 17 +/- 4 18 +/- 4 22 +/- 4 17 +/- 4 18 +/-4 03/23/07 -03/30/07 12 +/- 4 14 +/- 4 10 +/-4 13+/-4 13 +/- 4 15 +/-4 15 +/- 4 13 +/- 4 11 +/-4 03/30/07 -04/06/07 14 +/- 4 12 +/- 4 15 +/-4 12 +/-4 16 +/- 5 13 +/-4 16 +/- 4 11 +/-4 13 +/-4 04/06/07 -04/13/07 15 +/- 4 16 +/- 4 14 +/-4 17 +/-4 18 +/- 4 13 +/- 4 17 +/- 4 15 +/-4 12 +/-4 04/13/07 -04/20/07 19 +/- 4 19 +/- 4 16 +/- 4 19 +/-4 18 +/- 4 .. 18 +4 14 +/- 4 19 +/-4 20 +/-4 04/20/07 -04/27/07 17 +/- 4 14 +/- 4 13 +/- 4 11 +/-4 14 +/-4 13 +/-4 11 +/-4 13 +/-4 16 +/-4 04/27/07 -05/03/07 19 +/- 4 14 +/- 4 13 +/- 4 18+/-4 21 +/-5 22 5 16 +/-4 15 +/-4 18 +/-5 05/03/07 -05/11/07 18 +/- 4 20 +/- 4 17 +/- 4 24 +/-5 21 +/-4 19+/-4 22 +/-4 15+/-4 22 +/-4 05/11/07 -05/18/07 15 +/- 4 13 +/- 4 14 +/- 4 17 +/-4 16 +/-4 12 +/-4 13 +/-4 13 +/-4 13 +/-4 05/18/07 -05/25/07 27 +/- 5 19 +/- 4 22 t 4 27 +/-5 22 +/-4 21 +/-4 20 +/-4 22 +/- 4 23 +/-5 05/25/07 -05/31/07 17 +/- 4 16 +/- 4 17 +/- 4 15 +/- 4 16 +/- 5 '20 +/- 5 19 £ý4 17 +/- 4 22 +/-5

,05/31/07 -06/08/07 11 +/-3 12 +/- 3 12 +/- 3 14 +/- 4 15 +/- 4 *12 +/- 3 17 +/-*4 13 +/- 4 16 +/-4 06/08/07 -06/15/07 26 +/-5 17 +/-4 18 +/- 4 22 +/- 4 22 +/- 4 27 +/- 5 20 +/- 23 +/- 4 21 +/-4 06/15/07 -06/21/07 22 +/-5 17 +/-4 22 +/- 4 22 +/- 5 30 +/- 6

24 +/- 5 19 +/-£4 20 +/- 4 27 +/-5 06/21/07 06/29/07 16 +/-4 16 +/-4 12 +/- 4 15 +/- 4 23 +/- 4 14 +/- 4 120 +/-_4 17 +/- 4 17 +/-4 06/29/07 -07/06/07 16 +/-4 17 +/-4 16 +/- 4 19 +/- 4 20 +/- 5 20 +/- 5 19 +/- 4 18 +/- 4 19 +/-5 07/06/07 -07/13/07 17 +/-4 21 +/-5 20 +/- 5 21 +/- 5 23 +/- 5 19 +/- 5 .17+/-4 15 +/-4 17 +/-4 07/13/07 -07/20/07 13 +/- 4 12 +/-4 11 +/-4 10 +/- 4 13 +/- 4 13 +/- 4 13 +/-.4 10 +/-4 13 +/-4 07/20/07 -07/27/07 18 +/- 4 20 +/- 5 22 +/-5 22 +/- 5 27 +/- 5 22 +/- 5 24 +/- 5 24 +/- 5 25 +/-5 07/27/07 -08/04/07 24 +/- 4 26 +/- 4 21 +/-4 31 +/- 5 30 +/- 5 27 +/- 5 24 +/- 4 23 +/- 4 26 +/-5 (1) 08/10/07 -08/17/07 23 +/- 5 29 +/- 5 33 +/-5 25 +/- 5 28 +/- 5 *26 +/- 5 31 +/- 5 29 +/- 5 30 +/-5

.08/17/07 -08/24/07 16 +/- 4 11 +/-4 14 +/-4 18 +/- 4 17 +/- 4 11 +/-4 13 +/- 4 12 +/- 4 16 +/-4 08/24/07 -08/31/07 20 +/- 4 20 +/-4 <5 21 +/- 4 23 +/- 5 27 +/-5 24 +/- 5 23 +/- 5 22 +/-5 08/31/07 -09/07/07 24 +/- 4 25 +/-4 31 +/-5 30 +/- 5 29 +/- 5 *26 +/-5 26 +/- 4 33 +/- 5 28 +/-5 09/07/07 -09/14/07 15 +/- 4 15 +/-4 18 +/- 4 16 +/- 4 20 +/- 4 16 +/-4 16 +/- 4 17 +/- 4 17 +/-4 09/14/07 -09/21/07 30 +/- 5 26 +/-5 26 +/- 5 34 +/- 5 30 +/- 5 28 +/-5 27 +/-5 25 +/- 5 30 +/-5 09/21/07 -09/30/07 25 +/- 4 29 +/-4 27 +/- 4 31 +/- 4 21 +/- 4 20 +/-4 24 +/-4 25 +/- 4 28 +/-5

.09/30/07 -10/07/07 19 +/- 4 21 +/-4 21 +/- 5 20 +/- 5 22 +/-5 32 +/-5 21 +/- 4 26 +/- 5 29 +/-5

.10/07/07 -10/13/07 7+/-4 8+/-4 6+/-4 8+/-5 9+/-4 12 +/-4 11 +/-5 10 +/- 5 10 +/-4 10/13/07 -10/19/07 22 +/-5 25 +/-6 26 +/-6 25 +/-6 28 +/-5 28 +/- 5 32 +/-6 32 +/- 6 31 +/-5

.10/19/07 -10/25/07 19 +/-4 15 +/-4 18 +/-4 17 +/-4 21 +/-5 19 +/- 5 20 +/-4 16 +/- 4 22 +/-5 10/25/07 -11/02/07 21 +/-5 22 +/-5 23 +/-5 21 +/-5 23 +/-4 22 +/- 4 15 +/-4 21 +/- 5 22 +/-4 11/02/07 -11/09/07 20 +/-4 21 +/-4 24 +/-5 24 +/-5 22 +/-5 21 +/-4 20 +/-4 29 +/- 5 22 +/-4 11/09/07 -11/16/07 23 5 23 +/- 5 25 +/-6 30 +/-5 26 +/-5 29 +/- 5 27 +/-5 26 +/- 5 25 +/-4 11/16/07 -11/23/07 25 +/- 5 21 +/- 4 26 +/- 5 28 +/- 5 22 +/- 4 21 +/- 4 23 +/- 4 27 +/- 5 22 +/-4 11/23/07 -11/30/07 28 +/- 4 29 +/- 5 27 +/- 5 29 +/- 5 26 +/- 5 33 +/- 5 29 +/- 5 33 +/- 5 35 +/-5 11/30/07 -12/07/07 18 +/- 5 21 +/- 5 18 +/- 5 23 +/- 5 19 +/- 4 19 +/- 4 20 +/- 5 16 +/- 6 19 +/-4 12/07/07 -12/14/07 45 +/- 6 44 +/-6 54 +/- 6 49 +/- 6 50 +/- 6 54 +/- 6 49 +/- 6 54 +/- 6 49 +/-6 12/14/07 -12/21/07 44 +/- 6 35 +/-5 47 +/- 6 40 +/- 6 41 +/-6 52 +/- 6 45 +/- 6 52 +/- 6 45 +/-6 12/21/07 -12/28/07 30 +/- 5 25 +/-5 29 +/- 5 32 +/- 5 31 +/-6 35 +/- 6 28 +/- 5 32 +/- 5 36 +/-6 MEAN* 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 MIN MAX MEAN* COLLECTION MIN MAX MEAN+/- COLLECTION MIN MAX MEAN+/-

PERIOD 2SD PERIOD 2SD PERIOD 2SD I

12/29/06 -02/02/07 18 44 25 +/- 14 12/29/06 - 02/02/07 16 38 25 +/- 12 1 2/2e9/06 -02/02/07 20 42 26 +/- 19 02/02/07 -03/02/07 8 29 20 +/- 13 02/02/07 - 03/02/07 11 30 21 +/- 12 02/0 12/07 -03/02/07 9 26 20 +/- 16 03/02/07 -03/30/07 10 21 15 +/- 6 03/02/07 - 03/30/07 13 22 17 +/- 5 03/0 12/07 -03/30/07 11 20 16 +/- 8 03/30/07 -04/27/07 11 19 15 +/- 5 03/30/07 - 04/27/07 11 19 15 +/- 5 03/3 10/07 -04/27/07 12 20 15 +/- 7 04/27/07 -06/01/07 13 27 18 +/- 8 04/27/07 - 06/08/07 12 22 18 +/- 7 04/2 ~7/07 -06/08/07 13 23 19 +/- 7 06/0 1/07 -06/29/07 11 26 17 +/- 9 06/01/07 - 06/29/07 13 30 21 +/- 9 06/C18/07 -06/29/07 17 27 *22 +/- 10 06/29/07 -07/27/07 10 22 17 +/- 8 06/29/07 - 07/27/07 10 27 18 +/- 10 06/2 ~9/07 -07/27/07 13 25 19 +/- 10 07/27/07 -08/31/07 <5 33 22 +/- 12 07/27/07 - 08/31/07 11 31 23 +/- 13 07/2 7/07 -08/31/07 16 30 23 +/- 12 08/31/07 -09/30/07 15 34 25 +/- 12 08/31/07 - 10/05/07 16 33 24 +/- 10 08/3 11/07 -10/05/07 17 30 26 +/- 10 00 09/30/07 -11/03/07 6 26 18 +/- 12 09/30/07 - 11/09/07 9 32 20 +/- 13 10/C 15/07 -11/09/07 10 31 21 +/- 15 11/03/07 -12/01/07 20 30 25 +/- 6 11/03/07 - 12/07/07 19' 33 26 +/- 9 11/C 19/07 -12/07/07 19 35 25 +/- 14 12/01/07 -12/29/07 18 54 35 +/- 24 12/01/07 - 12/29/07 16 54 40 +/- 26 12/C 17/07 -12/28/07 36 49 43 +/- 13 12/29/06 - 12/29/07 < 5 54 21 +/- 11 12/29/06 - 12/29/07 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 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-01 12/29/06 - 03/30/07 <3 <4

10 <5 < 7 <5 <6 <3 4 81 < 35 03/30/07 - 06/29/07 <3 < 5 < 19 <3 <8 <5 <8 <4 2 472 < 179 06/29/07 - 09/30/07 <4 <3 < 13 <2 <8 <5 <7 < 5 4 100

28 09/30/07 - 12/29/07 <2 < 3 <9 <3 <6 <3 <6 <3 2 63

28 MEAN Q-02 12/29/06 - 03/30/07 3 <4 < 11 <4 < 7 <4 <7 <3 4 82 38 03/30/07 - 06/29/07 3 <' 6 < 15 <3 < 10 <7 <14 < 4 3 553 226 06/29/07 - 09/30/07 3 < 5 <11 <2 <9 <54 < 7 <4 3 71 25

<5 <8 29 09/30/07 - 12/29/07 4 <5 < 11 <4 < 8 <4 3 79 MEAN Q-03 12/29/06 - 03/30/07 3 5 15 < 3. < 7 < 3 < 5 <3 4 73 19 03/30/07 - 06/29/07 4 6 17 < 2 <11 < 6 <*11 <4 3 635 244 06/29/07 - 09/30/07 3 4 10 <3 < 8 <4 <. 5 <4 2 62 11

< 2" <5 <7 <4 3 95 38 09/30/07 - 12/29/07 4 3 13 <5 MEAN 14 <6 <9 < 6 <6 <4 5

85 28 Q-04 12/29/06 - 03/30/07 5 6 03/30/07 - 06/29/07 2 6 17 < 3.* ! 9. <7 <3 2 < 358 173 06/29/07 - 09/30/07 4 5 12 < 5 < 12 <5 <7 <5 3 < 76 25 09/30/07 - 12/29/07 2 3 7 <2 <5 <3 <5 <2 2 < 39 25 MEAN Q-07 12/29/06 - 03/30/07 3 4 12 <2 <6 <5 <7 <2 3 68 27 03/30/07 - 06/29/07 3 5 16 <3 < 10 <6 < 13 <4 3 557 207 06/29/07 - 09/30/07 3 3 8 <3 <7 <3 <5 <3 2 56 19 09/28/07 - 12/28/07 3 3 7 <2 <6 <3 <5 <2 2 63 24 0

MEAN 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 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-13 12/29/06 - 03/30/07 <3 <3 13 <5 12 <4 <7 <3 <4 < 92 33 03/30/07 - 06/29/07 <4 <5 22 <3 9 <7 < 13 <5 <3 < 591 225 06/29/07 - 09/30/07 <3 <4 9 <4 9 <4 < 7 < 4 <3 < 62 34 09/28/07 - 12/28/07 <3 <4 9 <3 6 <4 <5 <3 <2 < 77 23 MEAN

('i Q-16 12/29/06 - 03/30/07 <3 <4 5 <3 5 <4 <6 <2 <2 < 76 18 0 03/30/07 - 06/29/07 <4 <3 13 <3 8 <5 <9 <4 <3 < 575 171 06/29/07 - 09/30/07 <3 <4 7 <3 7 <4 <6 <4 <2 < 54 18 09/28/07 - 12/28/07 < 2 <3 5 <3 5 <3 <3 <2 <2 < 47 24 MEAN Q-37 12/29/06 - 03/30/07 3 <5 12 <5 10 4 8 4 <3 < 105 36 03/30/07 - 06/29/07 5 <5 23 <3 9 6 11 4 <3 <'693 259 06/29/07 - 09/30/07 3 <3 10 <2 12 4 7 4 < 3 < 81 27 09/30/07 - 12/29/07 3 <4 9 <4 6 4 6 3 <4 < 74 36 MEAN Q-38 12/29/06 - 03/30/07 2 <3 7 <2 5 3 4 2 <2 < 56 < 23 03/30/07 - 06/29/07 4 <6 18 < 3 7 6 11 4 -< 3 < 521 < 261 06/29/07 - 09/30/07 3 <4 9 <3 10 4 7 4 <.2 < 74 < 33 09/30/07 - 12/29/07 3 < 4 < 11 < 2 <6 < 4 < 8 < 4 < 3 < 71 < 25 MEAN 00,,

04

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 FAR-FIELD CONTROL GROUP I GROUP 11 IGROUP III COLLECTION PERIOD Q-01 0-02 Q-03 0-04 Q-13 Q-16 Q-37 Q-38 Q-07 0

12/29/06 -01/05/07

63

61

61

63

67

67

68

68

37j 01/05/07 -01/12/07

35

43

43

44

45

45

46

46

42 01/12/07 -01/19/07

14

21

21

21

28

28

28

28

21 01/19/07 -01/26/07

42

40

40

42

28

29

28

16

29 01/26/07 -02/02/07

29 < 37

37

39

39

39

39

39

38 02/02/07 -02/09/07

55

29

53

55

45

45

44

44

54 02/09/07 -02/16/07

61

59

59

61

48

48

58

58

27 02/16/07 -02/23/07

48

47

31

48

46

46

51

51 *<42 02/23/07 -03/02/07

26

25

25

26

32

31

30

30

16 03/02/07 -03/08/07

31

30

30

31

39

39

29

29

22 03/08/07 -03/16/07

32

31

31

32

33

33

37

37

15 03/16/07 -03/23/07 < 47

46

47

47

43

43

42

42

26 03/23/07 -03/30/07

51 <50

50 *<51

59

58

61

61

29 03/30/07 -04/06/07

57

55

55

57

47

47

35

35

56 04/06/07 -04/13/07

70

68

68

70

46

46

55

55

32 04/13/07 -04/20/07

27

27

26 * *27 < 27 <_ 54

54

54 04/20/07 -04/27/07 <8

15

15 I,< 16 *<14 < 14 <14

14

16 04/27/07 -05/03/07

55

53

53

55

58 < 58

56

56

37 05/03/07 -05/11/07

39

37

37

39

30 < 29 *<18

33

29 05/11/07 -05/18/07 < 47

46

46 <'47

47 < 47

47

47

36 05/18/07 -05/25/07

49

47

47 1< 49

63 < 63 <.60 .< 60

34 05/25/07 -05/31/07

23

22

22

23

31 < 30 .24 < 24

20 05/31/07 -06/08/07

19

18

18

19

19 < 19 < 21 < 11

19 06/08/07 -06/15/07

58 56

56.

58

62 < 62

58

32

62 06/15/07 -06/21/07

32

31

31 *<17

42 *< 42

33

33

40 06/21/07 -06/29/07

35

34

34

35

42 < 42

48

50

16 06/29/07 -07/06/07

42

40

40

42

29 < 29

27

14

29 07/06/07 -07/13/07

35

55

55

57

42- < 41

41 *< 42

56 07/13/07 -07/20/07

19 < 11

18

19

19 *< 19

19

20

19 07/20/07 -07/27/07

39

39

21

40

38 < .38

36

37

41 07/27/07 -08/04/07

24

48

48

50

46 < 46

40

41

55 08/04/07 -08/10/07

60

61

60

62

55 < 54

59

61

37 08/10/07 -08/17/07

69

69

69

43

64

64

67

69

66 08/17/07 -08/24/07

58

59

58

61

59

59

46

48

25 08/24/07 -08/31/07

37

68

68

68

66

66

65

67

69 08/31/07 -09/07/07

36

45

47

47

58

57

57

59

46 09/07/07 -09/14/07

51

51

52

52

28

52

51

53

52 09/14/07 -09/21/07

26

27

27

27

27

22

27

28

27 09/21/07 -09/30/07

60

60

62

62

39

39 < 31

32

32 09/30/07 -10/07/07

27

50

52

52

68

68

55

57

62 10/07/07 -10/13/07

51

64

66

66

59

60

66

68

59 10/13/07 -10/19/07

37

48

48

48

53

53

59

61

42 10/19/07 -10/25/07

45

45

47

47

66

66

45

31

66 10/25/07 - 11/02/07

24

56

58

58

46

48

48

49

57 11/02/07 -11/10/07

34

43

44

44

13

12

21

22

46 11/10/07 -11/16/07

65

65

67

67

58

60

70

31

58 11/16/07 -11/23/07

36 < 48 < 49 < 49

44

44

44 < 45

48 11/23/07 -11/30/07

43

18

44

44

36

37

30

31

54 11/30/07 -12/07/07

26

44

45 < 45

37

37

43

64

39 12/07/07 -12/14/07

63

61

40

62

61 < 61

63

67

60 12/14/07 -12/21/07

21

21

14

22

29

30

29

30

22 12/21/07 -12/28/07 <8

15

15

15

31

30

24

24

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 COLLECTION Q-26 PERIOD 01/05/07 < 0.3 02/02/07 < 0.3 03/02/07 < 0.8 04/07/07 <.0.9 05/04/07 < 0.8 05/18/07 < 0.9 06/01/07 < 0.8 06/15/07 < 0.6 06/29/07 < 0.8 07/13/07 < 0.7 07/27/07 < 0.5 08/10/07 < 0.9 08/24/07 < 0.6 09/07/07 < 0.9 09/21/07 < 0.7 10/07/07 < 0.6 10/19/07 < 0.6 11/03/07 <'0.8 12/07/07 < 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 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-26 01/05/07 <6 <6 < 16 <6 < 12 <5 <11 <3 <4 < 35 < 11 "

02/02/07 <6 <7 < 14 <5 < 13 <7 <11 <6 <6 < 29 <9 03/02/07 <9 < 10 < 21 <9 < 27 <9 < 15 <9 <9

48 < 13 04/07/07 <5 <8 < 18 <8 < 17 <8 < 15 <7 <7 < 38 <13 05/04/07 <5 <5 < 13 <5 < 12 <6 < 10 <4 <6 < 30 <11 05/18/07 <4 <6 < 17 <6 < 12 <6 < 10 <5 <5

59 < 13 06/01/07 <4 <5 <9 <5 < 10 <5 <9 <4 <5 < 41 <11 06/15/07 <5 <6 < 13 <5 < 13 <6 <9 <4 <5 < 42 <14 06/29/07 <5 <5 < 10 <5 < 10 <5 <9 <4 <5 < 41 < 13-07/13/07 <5 <5 < 12 <5 < 13 <7 <9 <5 <6 < 31 <8 07/27/07 <4 <4 < 10 <5 < 10 <4 <7 <3 <4 < 23 <7 08/10/07 <4 <5 < 12 <4 <9 <5 <9 <4 <4 < 54 < 15 08/24/07 <6 <6 < 18 <7 < 13 <7 < 13 <5 <6 < 42 < 12 09/07/07 <5 <6 < 15 <6 < 15 <6 < 10 <5 <6 < 35 < 13 09/21/07 <2 <2 <5 <2 <5 <2 <4 <2 <2 < 19 <5 10/07/07 <6 <8 < 17 <6 < 18 <8 < 14 <7 <8 < 46 <9 10/19/07 <2 <3 <6 <2 <6 <3 <5 <2 <2 < 20 <7 11/03/07 <2 <3 <7 <2 <6 <3 <6 <2 <2 < 31 <9 12/07/07 <5 <6 < 14 <6 < 13 <7 < 11 <5 <5 .< 50 < 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 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD Q-CONTROL Potatoes 07/09/07 < 25 < 29 < 56 < 18 < 51 < 30 < 34 < 52 < 21 < 29 < 112 < 35 Rhubarb Leaves 07/09/07 < 11 < 12 < 27 < 10 < 25 < 12 < 22 < 20 < 10 < 11 .< 52 < 16 MEAN Q-QUAD 1 Potatoes 07/09/07 < 26 < 28 < 63 < 21 < 52 < 26 < 41 < 46 < 21 < 28 .< 145 < 44 Rhubarb Leaves 07/09/07 < 15 < 17 < 39 < 19 < 43 < 16 < 31 < 33 < 18 < 19 < 88 .< 16 MEAN Q-QUAD 2 Kohlrabi 07/09/07 < 23 < 24 < 75 < 28 < 63 < 24 < 37 < 43 < .24 < 30 <131 "< 34 Rhubarb Leaves 07/09/07 < 22 < 22 < 51 < 26 < 46 < 20 < 32 < 39 < 20 < 20 <89 < 22 MEAN Q-QUAD 3 Horseradish 07/09/07 < 22 < 21 " 49 < 25 < 49'. <23 < 40 < 45- <21 < 22 < 121 < 36 Rhubarb Leaves 07/09/07 < 14 < 11 < 21 < 12 -<25.. < 10 < 24 < 22 < 11 < 13 <65 < 9 MEAN Q-QUAD 4 Lettuce 07/09/07 < 31 < 29 < 77 < 27 < 78 < 32 < 54 < 55 < 31 < 31 <133 < 49 Potatoes 07/09/07 < 18 < 23 < 53 < 22 , < 49 <27 < 45 < 36 < 20 < 23 < 107 < 40 MEAN 0~

00 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 .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.

0-201-1 22.8 +/- 5.5 26 21 20 24 Q-201-2 23.5 +/- 2.6 25 23 22 24 Q-202-1 20.8 +/- 3.4 23 20 21 19 Q-202-2 20.0 +/- 8.2 26 18 17 19 Q-203-1 22:5. +/- 6.0 27 21 .21 .21 Q-203-2 23.3 +/- 4.1 26 21 23 23 Q-204-1 23.0 +/- 7.1 28 21 20 23 Q-204-2 24.5 +/- 7.7 30 21 24 23 Q-205-1 23.5 +/- 6.6 28 23 20 23 Q-205-4 23.5 +/- 7.4 28 21 20 25 Q-206-1 21.8 +/- 4.4 24 23- 19 21 Q-206-2 22.8 +/- 5.5 26 20 21 24 Q-207-1 22.0 +/- 3.7 24 20 23 21 Q-207-4 23.0 +/- 4.0 26 22 22.. 22 Q-208-1 22.0 +/- 4.0 25 21 21 21 Q-208-2 23.5 +/- 7.4 28 23 19 24 Q-209-1 21.8 + 4.7 25 20 20 22 Q-209-4 24 22 20 S 22 ,,,

Q-210-1 *22.3 +/- 3.4 24 22 20 23 Q-210-4

21.8 +/- 8.5 28 19 19 21 Q-210-5 20.3 +/- 6.8 25 19 17 20 Q-211-1 25.0 +/- 4.6 27 23 23 27 Q-211-2 25.3 +/- 5.3 29 24 23 25 Q-212-1 23.5 +/- 3.5 25 24 21 24 Q-212-2 22.3 +/- 7.5 27 .21 -..- , .18 23 Q-213-1 24.8 +/- 14 24 21 19 35 Q-213-2 21.5 +/- 8.1 27 19 18 22 Q-214-1 22.8 +/- 7.7 28 21 '19 23 Q-214-2 25.3 +/- 6.6 30 23 23 25 Q-215-1 22.0 +/- 4.3 25 21 20 22 Q-215-2 23.3 +/- 6.6 28 21 21 23 Q-216-1 23.0 +/- 6.7 28 21 22 21 25 21 26 Q-216-2 25.3 +/- 6.6 29

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 INNER RING OUTER RING OTHER CONTROL PERIOD .+/- 2 S.D.

JAN-MAR 24.1 +/- 2.6 26.5 +/- 3.8 24:9 +/- 4.0 :25.0 + 5.7 APR-JUN 19.4 +/- 2.9 21.4 +/- 3.2 20.0 +/- 4.7 22.0 +/- 0.0 JUL-SEP 18.5 +/- 2.7 20.5 +/- 3.6 18.9 +/- 2.1 19.5 +/- 1.4 OCT-DEC 21.2 +/- 3.2 23.1 +/- 5.7 22.0 +/- 4.0 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 PERIOD PERIOD MEAN ANALYZED MINIMUM MAXIMUM +2 S.D.

INNER RING 120 -. 17 27 20.8 +/- 5.1 OUTER RING 132 17 35 22.8 + 6.1 OTHER 64 17 28 .21'.5 5.9 CONTROL 8 19 27 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 -

01-01-00 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. 6.0-C.

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- 6.0+

C.

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 500 400,

300

-J 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 500 400 300 CJ UL 200 0

-100- 11I I 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 01-01-00 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 500-400-300-0.

200 100-01 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 500 400 300

-J 200 U3

/

\

-100

-200 1.

01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 Q-36 Cordova Well 500 400 300

-j 200 0~

100

/ \ z-.-

0 N

\ \\

-100

-200 L 01-01-00 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

,-I 200 100 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

-J 200 100 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 6.0 E.

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 10.0 8.0 C?

U 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 40.0-330.0 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 10-21-05.

Q-02 Onsite No. 2 60.0 50.0 40.0 C.)

m. 30.0 9

Lu CD 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 08-26-05.

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 C.)

'4 ul 0 4.0 01-01-00 12-31.-00 12-31-01 12-31-02 12-31-03 12-30-04

.Q-04 Nitrin 640 to CJ 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 6°0 9

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-Cal30.0 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 -

07-08-05 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 Sr-89 pCi/L 125 137 0.91 A Sr-90 pCi/L 10.8 10 1.08 A E5256-396 Milk 1-131 pCi/L 107 85.2 1.26 W Ce-141 pCi/L 269 297 0.91 A Cr-51 pCi/L 244 245 1.00 A Cs-134 pCi/L 98.1 112 0.88 A Cs-137 pCi/L 227 234 0.97 A Co-58 pCi/L 92.5 98.8 0.94 A Mn-54 pCi/L 182.0 182 1.00 A Fe-59 pCi/L 108.0 106 1.02 A Zn-65 pCi/L 985 1000 0.99 A Co-60 pCi/L 143 152 0.94 A Ce.141* , 245 1.03 A E5258-396 AP 252 Cr-51 pCi 204 202 1.01 A Cs-134 pCi 74.9 92.3 0.81 A Cs-1 37 pCi 190.0 197.0 0.96 A Co-58 pCi 79.7 81.6 0.98 A Mn-54 pCi 156 151 1.03 A Feý59 pCi i99. 1;', -87T2 1.14 A ZnL65 826 1.08 A Co-60, 3/4 122 126 0.97 A pCi E5257-396 Charcoal 1-131 34.7 71.3 0.49 N (1)

June 2007 E5384-396 Milk Sr-89 pCi/L 98.3 95.2 1.03 A Sr-90 pCi/L 16.1 12.9 1.25 W E5385-396 Milk 1-131 pCi/L 71.0 70.1 1.01 A Ce-141 pCi/L 176 200 0.88 A Cr-51 pCi/L 459 512 0.90 A Cs-1 34 pCi/L 197 242 0.81 A Cs-1 37 pCi/L 158 169 0.93 A Co-58 pCi/L 180 198 0.91 A Mn-54 pCi/L 163 166 0.98 A Fe-59 pCi/L 158 167 0.95 A Zn-65 pCi/L 318 334 0.95 A Co-60 pCi/L 212 238 0.89 A E5387-396 AP Ce-141 pCi 87.5 105 0.83 A Cr-51 pCi 232 268 0.87 A Cs-1 34 pCi 101 127 0.80 A Cs-1 37 pCi 78.9 88.5 0.89 A Co-58 pCi 91.8 104.0 0.88 A Mn-54 pCi 85.6 87 0.99 A Fe-59 pCi 89.8 87.3 1.03 A Zn-65 pCi 178 175 1.02 A Co-60 pCi il1 125 0.89 A E5386-396 Charcoal 1-131 pCi 79.3 79.1 1.00 A 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 Sr-89 pCi/L 99.0 94.9 1.04 Sr-90 pCi/L 13.9 13.1 1.06 E5493-396 Milk 1-131 pCi/L 81.9 85.2 0.96 Ce-141 pCi/L 200 211 0.95 Cr-51 pCi/L 271 289 0.94 Cs-1 34 pCi/L 131 147 0.89 Cs-1 37 pCi/L 131 131 1.00 Co-58 pCi/L 114 114 1.00 Mn-54 pCi/L 171 168 1.02 Fe-59 pCi/L 117 111 1.05 Zn-65 pCi/L 212 202 1.05 Co-60 pCi/L 143 148 0.97 E5495-396 AP Ce-141 pCi 128 136 0.94 Cr-51 pCi 181 186 0.97 Cs-1 34 pCi 85.9 94.7 0.91 Cs-1 37 pCi 83.2 83.9 0.99 Co-58 pCi 69.4 73.3 0.95 Mn-54 pCi 112 108 1.04 Fe-59 pCi 79.6 71.1 1.12 Zn-65 pCi 159 130 1.22 Co-60 pCi 92.0 95.2 0.97 E5494-396 Charcoal 1-131 pCi 70.8 69.5 1.02 December 2007 E5749-396 Milk Sr-89 pCi/L 87.6 93.7 0.93 A Sr-90 pCi/L 15.5 15.2 1.02 A E5750-396 Milk 1-131 pCi/L 60.6 60.8 1.00 A Ce-141 pCi/L 137 141 0.97 A Cr-51 pCi/L 497 512 0.97 A Cs-1 34 pCi/L 117 137 0.85 A Cs-1 37 pCi/L 166 166 1.00 A Co-58 pCi/L 159 174 0.91 A Mn-54 pCi/L 190 190 1.00 A Fe-59 pCi/L 149 148 1.01 A Zn-65 pCi/L 231 234 0.99 A Co-60 pCi/L 198 211 0.94 A E5752-396 AP Ce-141 pCi 88.6 93.4 0.95 A Cr-51 pCi 352 340 1.04 A Cs-1 34 pCi 84.6 91.2 0.93 A Cs-1 37 pCi 111 110.0 1.01 A Co-58 pCi 114 116.0 0.98 A Mn-54 pCi 135 126 1.07 A Fe-59 pCi 119 98.5 1.21 w Zn-65 pCi 172 155 1.11 A Co-60 pCi 137 141 0.97 A 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 charcoalcartridgeon the back rather than the face, resulting in low activity. If the charcoalcartridge had been counted on the face, the ratio would have been approximately 1.07, which is acceptable. NCR 07-02 (a) Teledyne Brown Engineeringreported result.

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

(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 pCi/L 58.6 58.2' 49.5 - 66.9 A Sr-90 pCi/L 18.7 19.0 10.3-27.7 A Ba-1 33 pCi/L 18.6 19.4 10.7-28.1 A Cs-1 34 pCi/L 57.6 68.9 60.2 - 77.6 N (1)

Cs-1 37 pCi/L 55.4 61.3 52.6 - 70.0 A Co-60 pCi/L 31.3 33.5 24.8 - 42.2 A Zn-65 pCi/L 49.0 54.6 45.2 - 64.0 A Gr-A pCi/L .26.8 27.1 15.4-38.8 A Gr-B pCi/L 12 11.5 2.84 - 20.2 A 1-131 pCi/L 31.1 26.5 21.3-31.7 A H-3 pCi/L 1700 1770 1180-2360 A October 2007 RAD 71 Water Sr-89 pCi/L 27.07 "27.4 19.3 - 33.9 A Sr-90 pCi/L 17.40 18.2 12.9- 21.6 A Ba-133 pCi/L 12.57 12.6 8.64- 15.5 A Cs-1 34 pCi/L .63.33 71.1 58.0 - 78.2 A Cs-137 pCi/L 168 180 162 - 200 A Co-60 pCi/L 21.93 23.2 19.9 - 28.3 A 1-',Zn-65 pCi/L .245.33 251 226 - 294 A Gr-A pCi/L -:55.60 58.6 30.6 - 72.9 A Gr-B pCi/L 15.23 9.73 4.26- 18.2 A

-131 pCi/L . '27.43 28.9 24.0 - 33.8 A

': ~H-3" pCi/L. 9263.3 9700 8430- 10700 A (1) The Cs-134 TBE found/ERA known ratio is 83.6%, which TBE considers acceptable. NCR 07-07 (a) Teledyne Brown Engineering reported result.

(b) The ERA known value is equal to 100% of the parameterpresentin the standardas determinedby gravimetric and/or volumetric measurements made during standardpreparation.

(c) ERA evaluation:A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the 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 Cs-134 Bq/L 74.5 83.5 58.5- 108.6 A Cs-1 37 Bq/L 162 163.0 114-1 -211.9 A Co-57 Bq/L 140 143.7 100.6- 186.8 A Co-60 Bq/L .27.9 26.9 18.8- 35.0 A H-3 Bq/L 346 283.0 198.1 - 367.9 W Mn-54 Bq/L 125 123.8 86.7- 160.9 A Sr-90 Bq/L 8.90 8.87 6.21- 11.53 A Zn-65 Bq/L 117 114.8 80.4 - 149.2 A 07-GrW17: Water Gr-A Bq/L 0.502 0.327 >0.0 - 0.654 A Gr-B Bq/L 0.975 0.851 0.426 - 1.277 A 07-MaS17. Soil Cs-134 Bq/kg 322 327.4 229.2 - 425.6 A Cs-137 Bq/kg ' 893 799.7 559.8 - 1039.6 A Co-57 Bq/kg .508.3 471.2 329.8 - 612.6 A Co-60 Bq/kg. .300.3 274.7 192.3 - 357.1 A Mn-54 Bq/kg .779 685.2 479.6 - 890.8 A

-K-40 Bq/kg. .682 602 421 - 783 A Sr-90 Bq/kg 293 319.0 223.3 - 414.7 A

Zn-65 Bq/kg .618.7 536.8 375.8 - 697.8 A 07-RdF17 ;AP . Cs-134;

Bq/sample,, 3.230 1.4960 2.9372 - 5.4548 W

'.Cs-137 . Bq/sample -2.453 2.5693 1.7985 - 3.3401 A Co-57 Bq/sample 3.067 2.8876 2.0213 - 3.7539 A Co-60 Bq/sample 2.767 2.9054 2.0338 - 3.7770 A Mn-54 Bq/sample 3.557 3.5185 2.4630 - 4.5741 A Sr-90 Bq/sample 0.584 0.6074 0.4252 - 0.7896 A Zn-65 Bq/sample 2.463 2.6828 1.8780 - 3.4876 A 07-GrF17 AP Gr-A Bq/sample 0.353 0.601 >0.0 - 1.202 A Gr-B Bq/sample 0.500 0.441 0.221 - 0,662 A February 2007 07-RdV17 Vegetation Cs-134 Bq/sample 6.207 6.2101 4.3471 - 8.0731 A Cs-1 37 Bq/sample 7.80 6.9949 4.8964 - 9.0934 A Co-57 Bq/sample 8.64 8.1878 5.7315 - 10.6441 A Co-60 Bq/sample 6.10 5.8215 4.0751 - 7.5680 A Mn-54 Bq/sample 9.41 8.4492 5.9144- 10.9840 A K-40 Bq/sample 63.5 Not evaluated by MAPEP Sr-90 Bq/sample 1.51 1.5351 1.0746- 1.9956 A Zn-65 Bq/sample 7.15 5.6991 3.9894 - 7.4088 W (a) Teledyne Brown Engineeringreportedresult.

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

(c) DOEIMAPEP evaluation:A=acceptable, W=acceptablewith 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 03/19/07 Gr. Alpha 34.64 +/- 2.56 25.8 12.4 - 39 Pass STAP-1 116 03/19/07 Gr. Beta 93.41 +/- 3.20 79.5 48.8-116 Pass STAP-l 117 03/19/07 Co-60 1610.00 +/- 8.40 1300.0- 10,10.0 -1620 Pass STAP-1 117 03/19/07 Cs-134 1340.40 +/- 48.84 1120.0 732.0 -1380 Pass STAP-1117 e 03/19/07 Cs-137 345.30 +/- 8.20 255.0 192.0 -336 Fail STAP-1117 .03/19/07 Mn-54 .<5.0. 0.0

Pass STAP-1 117 03/19/07 Sr-90. 156.10 + 6:60 156.0 66.6 -246 Pass STAP-1 117 03/19/07 Zn-65 363.80 +/- 11.90 245.0 208.0-412 Pass STSO-1 118 03/19/07 Ac-228 3097.77 +/- 94.96 2790.0, 1790.0 - 3930 Pass STSO-1 118 03/19/07 Bi-212 2467.87,+/-:+/- 1.14.33 2500.0. 658.0 - 3730 Pass STSO- 1118 03/19/07 Co-60: 7847.40 +/- 86;60 7330.0 5340.0'- 9820 Pass STSO-1 118 03/19/07 Cs- 134 7910.60:+ 356:88 7560.0 ' 4850.0'- 9070 Pass STSO-1 118 '03/19/07 Cs-137 4635.00 +/-99.40 430010 3290.0 - 5580 * ,. Pass STSO-1 118 03/19/07 K-40 '" 12201.60 +/-423.20 11100.0, 8050.0 -15000 Pass STSO-1118 1 03/19/67 Mn-t54 < 34.0 0.0 Pass STSO-1 118 03/19/07 Pb-212 2046.80 +/-'127.20 173010"' 1120.0 '-.2430 Pass STSO-1 118 03/19/07 Pb-21'4 4142.80+/-' 110.40 3330.06" 1980.0 -4980 Pass STSO-1 118 03/19/07 Sr-90 6163.30 +/- 791.60 7500.0 2610.0 -1.2400 Pass STSO-1 118 03/19/07 Th-234 4329.40-+/- 569.10 3590.d-, 2190.0 - 4560 Pass STSO-1118' 03/19/07 Zn-65 0.00 +/- 0.00 0.0 0.0 -0 Pass STVE-1 119 03/19/07 Co-60 2827.90 +/-.62.40 2600.0. 1760.0 -3720 Pass STVE-1 119 03/19/07 Cs-1 34 654.80 +/- 48.40 579.0 308.0 -822 Pass STVE-11 19 03/19/07 Cs-1 37 3307.30 +/- 58.80, 2920.0 2150.0 -4060 Pass STVE-1119 03/19/07 K-40 40814.20 +/- 618..80 37900.0 ',27200.0 -53600 "Pass STVE-1 119' 03/19/07 Mn-54 < 27.6 0.0. Pass STVE-1 119 03/19/07 Sr-90 8999.70 +/-+580.90 8890.0, 4900.0 - 11800 Pass STVE-1 119 03/19/07 Zn-65 474.30 +/- 45.70 366.0 267.0-500 Pass STW-1 120 03/19/07 Co-60 541.40 +/- 9.00 536.0 467.0 -631 Pass STW-1 120 03/19/07 Cs-134 1623.80 +/- 66.10 1750.0 1290.0 -2020 Pass STW-1 120 03/19/07 Cs-137 1839.10 +/- 17.90 1850.0 1570.0 -2220 Pass STW-1 120' 03/19/07 Mn-54 <8.1 0.0 , Pass STW-1 120 03/19/07 Sr-90 949.40 +/- 16.70 ,989.0 630.0 -1320 Pass STW-1 120 03/19/07 Zn-65 2009.00 +/- 36.40 1910.0 1600.0 -2410 Pass STW-1 121 04/09/07 Sr-89 30.7 +/- 4.3 35.4 26.7 -44.1 Pass STW-1 121 04/09/07 Sr-90 39.3 +/- 1.8 42.1 33.4 -50.8 Pass D-6 80 of 108

TABLE D-4 ERAt 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 04/09/07 Ba-133 30.0 +/- 2.4 29.3 20.6 - 38.0 Pass STW-1122 04/09/07 Co-60 118.5 +/- 3.9. 119.0 109.0,-129.0 Pass STW-1 122 04/09/07 Cs-134 52.6 +/- 2.3 54.3 45.6 - 63.0 Pass STW-1 122 04/09/07 Cs- 137. 49.5 +/- 3.8 50.3 41.6 -59.0 Pass STW-1122 04/09/07 Zn-65 91.7 +/- 6.3 88.6 73.3 - 104.0 Pass STW-1123 04/09/07 Gr. Alpha 33.8 +/- 3.5 56.5 32.0 -81.0 Pass STW-1 123 04/09/07 Gr. Beta 24.2 +/- 2.3 25.3 16.6 -'34.0 Pass STW-1124 04/09/07 1-131 19.2 + 1:.2 18.9 13.7-24.1 Pass STW-1125 04/09/07 H-3 7540.0 +/- 255.0 8060.0 6660.0 - 9450.0 Pass STW-1127 07/09/07 Sr-89 51.7 +/- 5.0 58.2 49.5- 66.9 Pass

STW-1 127 07/09/07* Sr-90 '..21.4: +/- 23 19.0 10.3- 27.7 Pass STW-1 128 07/09/07. Ba-133.ý 19A4+/- 2.2 19:4 10.7 -28.1 Pass STW-1128 .07/09/07. Co-60 .* .32.8 +/- 2.0 33.5. 24.8 - 42.2 Pass STW-1128 07/09/0T Cs-134. 67.0*+/--2.9 . 68.9 6 0 .2 . -7 7 .6 - Pass STW-1128 07/09/0.7. Cs-137. :61-.6 +/- 3.8 61.3, 52.6 -,70.0

Pass

STW-1 128 07/09/07 Zn-65 55.6 +/- 7.5 54,.6., 45.2 -f64.0 Pass

. STW-1129 07/09/07 Gr. Alpha,, -19.2 +/- 1.6 27.1 15.54 -138.8 Pass STW-1129 07/09/07 Gr. Beta.. 9.1 +/- 0.9 11.5 2.8 -.20.2. Pass STW- 1131 10/05/07 Sr-89 27.3. +/- 3.3 27.4 .19.3.- 33.9 Pass STW-1131 10/05/07 Sr-90 17.7+/- 1f.2 18.2 12.9- 21.6' Pass STW-1 132 10/05/07 Ba-133' 12.2 +/- 3.3, 12.6 8.6 - 15.5 Pass STW-1 132 10/05/07 Co-60 23.8 +/- 1.4 23.2 19.9 - 28.3 Pass STW-1 132 10/05/07 Cs-134 ..- 70.5+/- 4.2 71.1 58.0 - 78.2 Pass

'STW-1 132 10/05/07- Cs-137 1782 +/- 3.3 180.0 162.0 - 200.0 Pass STW-1132 10/05/07 Zn-65 263.9 +/-6.9 251.0 226.0 '- 294.0 Pass STW-1133 ,10/05/07 Gr. Alpha' 54.7,+/- 2.1 58.6 30.6 - 72.9 Pass STW-1133 10/05/07 Gr. Beta 11.9 +/-.0.9 9.7 4.3 - 18.2

Pass STW- 1134 10/05/07 1-131 .33.0 +/- 1.5 28.9 24.0 - 33.8 Pass STW-1135 10/05/07 H-3 9965.0.+/- 250.0 9700.0 8430.0 - 1070C1.0 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)

Concentration b Known Control Lab Codec Date Analysis Laboratory ressult Activity Limits d Acceptance STW-1110 01/01/07 Gr. Alpha 0.45 +/- 0.(08 0.33 0.00 - 0.65 Pass STW-1 110 01/01/07 Gr. Beta 0.90 +/- 0.114 0.85 0.43-1.28 Pass STW-1111 01/01/07 Co-57 151.60 +/- 10.00 143.70 100.60 -186.80 Pass STW-1111 01/01/07 Cs-134 79.20 +/- 8.( 00 83.50 58.50 -108.60 Pass STW-1111 01/01/07 Cs-1 37 168.70 +/- 12.10 163.00 114.10 -211.90 Pass STW-1111 01/01/07 H-3 262.20 +/- 9.' 10 283.00 198.10 -367.90 Pass STW-1111 01/01/07 Mn-54 130.60 +/- 11.50 123.80 86.70 -160.90 Pass STW-1111 01/01/07 Sr-90 9.60 +/- 1.440 8.87 6.21 -11.53 Pass STW-1111 01/01/07 Zn-65 123.70 +/- 17.00 114.80 80.40 -149.20 Pass STSO-1 112 01/01/07 Co-57 501.20 +/- 2.90 471.20 329.80 -612.60 Pass STSO-1 112 01/01/07 Co-60 285.90 +/- 2.10 274.70 192.30 -357.10 Pass STSO-1 112 01/01/07 Cs-1 34 325.90 +/- 7.40 327.40 229.20 -425.60 Pass STSO-1 112. 01/01/07 ...Cs-1 37 , 855.70 +/-A.60. 799.70. ,559.80 -.1039.60 Pass STSO-11 12Z '01/01/07 Mn-54

,7`50690C '4370 -685-.2b0 479.60 -890.80 Pass STAP-1 113 01/01/07 Gr. Alpha 0.27 +/- 0.04 0.60 0.00-1.20 Pass STAP-1 113 01/01/07 Gr. Beta 0.57 +/- 0.05 0.44 0.22 -0.66 Pass STAP-1 114 01/01/07 Co-57 3.51 +/- 0.07 2.89 2.02 -3.75 Pass STAP-1 114 01/01/07 Co-60 2.98 +/- 0.10 2.91 2.03 -3.78 Pass STAP-1 114 01/01/07 Cs-1 34 4.02 +/- 0.16 4.20 2.94 -5.45 Pass STAP-1 114 01/01/07 Cs-1 37 2.75 +/- 0.12 2.57 1.80 -3.34 Pass STAP-1 114 01/01/07 Mn-54 3.94 +/- 0.12 3.52 2.46 -4.57 Pass STAP-1 114 01/01/07 Sr-90 0.58 +/- 0.18 0.61 0.43 -0.79 Pass STAP-1 114 01/01/07 Zn-65 2.70 +/- 0.10 2.68 1.88 -3.49 Pass STVE-1115 01/01/07 Co-57 8.90 +/- 0.20 8.19 5.73 -10.64 Pass STVE-1115 01/01/07 Co-60 6.50 +/- 0.20 5.82 4.08 -7.57 Pass STVE-1 115 01/01/07 Cs-134 6.90 +/- 0.30 6.21 4.35 -8.07 Pass STVE-1 115 01/01/07 Cs-137 8.20 +/- 0.30 6.99 4.90 -9.09 Pass STVE-1 115 01/01/07 Mn-54 10.10 +/- 0.30 8.46 5.91 -10.98 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.

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. "Summary and ConciJ'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 l**atirons. 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 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 1,,.

S 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.

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 Report;

. 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 IP 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 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 Monitoring Well MW-2 Monitoring Well MW-QC-1011 Monitoring Well MW-QC-101S Monitoring Well MW-QC-102D Monitoring Well MW-QC-1021 Monitoring Well MW-QC-102S Monitoring Well MW-QC-1031 Monitoring Well MW-QC-104S Monitoring Well MW-QC-1051 Monitoring Well MW-QC-1061 Monitoring Well MW-QC-106S Monitoring Well MW-QC-1071 Monitoring Well MW-QC-108D Monitoring Well MW-QC-1081 Monitoring Well MW-QC-108S Monitoring Well MW-QC-1091 Monitoring Well MW-QC-109S Monitoring Well MW-QC-1101 Monitoring Well MW-QC-111D1 Monitoring Well MW-QC-1 11D2 Monitoring Well MW-QC-1111 Monitoring Well MW-QC-1 121 Monitoring Well MW-QC-1131 Monitoring Well MW-QC-1141 Monitoring Well MW-QC- 115S Monitoring Well MW-QC-1 16S Monitoring Well STP SAND POINT WELL Production Well WELL #1 Production Well WELL #5 Production Well WELL #6 LITTLE FISH Production Well WELL #7 BIG FISH WELL Production Well WELL #8 FIRE TRAINING WELL Production Well WELL #9 DRY CASK WELL Production Well WELL #10 FISH HOUSE WELL Production Well WELL #11 SPRAY CANAL WELL Production Well SURFACE WATER #1 SPRAY CANAL - ACCESS ROAD Surface Water SURFACE WATER #2 SPRAY CANAL - RIVER ROAD Surface Water A-1 98 of 108

K~KK~

42 ~ K K" ij K" K K K 52KV K K KK P K 5 V

52 2 V ~K~4S2 5 I~

KK

/ K, ( &, ,S U'::*: A

~K4K"

~KS 1.1

~

~2~K K K¶ KIS K~ *K'~$KK.K~K~NN,.~

1 ~<

U 1-.

V1 i*** * ...... .....

"N 4 3/4. --

~5f

.; It S K N 2- K "N' N K N' ~ S5~i. ~KKKAK> $~KPKKK~ K 3/4.- KKK

K" 2 K4K~KK-i-K552$LKKSE 3/4I'KZ9,*~~**K 4fl4,, 2K~ *-KK~ -. ____

NJ / "K!

K~KQ, 4 3/4."*Kt* j ____

ff1

~S K/K" 9 K*-VK. KKKKKIKK.

KKKK2-KK flK C KKK"IK EKX,<K (K AK..

KKKKKK5KKNAK#KIK KKKKKK 5*54. "I~KK~4 1K*?,~a4K*KKC*1KIKI2$

2KKJ~KKKIKK3KKKKKVK~KK 4 t'¶K4KSKKtKKKKK;K Kr.

9 1/4 7

5K V NJ ii

~K H ~""

~K K-K I -

FIGURE A-1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2007 a

00 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 SITE DATE H-3 MW-i 02/22/07 203 + 126 MW-i 05/16/07

162 MW-i 09/19/07

189 MW-i 10/17/07

196 MW-i 12/12/07

181 MW-2 02/22/07

192 MW-2 05/16/07

161 MW-2 09/19/07

189 MW-2 10/17/07

195 MW-2 12/12/07

181 MW-QC-1011 02/22/07

190 MW-QC-1011 05/16/07

155 MW-QC-1011 09/19/07 188 + 119 MW-QC-1011 10/16/07

187 i.? ' 'i<::1'69 : .

MW-QC-1011 12/12/07.

MW-QC-1OiS 02/22/07 MW-QC-10iS 05/16/07

158 MW-QC-iOlS 09/19/07

180 MW-QC-10lS 10/16/07

189 MW-QC-i01S 12/12/07

162 MW-QC-102D 02/22/07 3640 + 426 MW-QC-1 02D 05/16/07 .. i. '3970, +/-+44Q MW-QC-102D 06/05/07 3060 +/- 353 MW-QC-102D 06/19/07 2940 +/- 350 MW-QC-102D 09/19/07 3760 +/- 440 MW-QC-102D 10/16/07 3110 +/- 218 MW-QC-102D 12/12/07 3340 +/- 398 MW-QC-1021 02/22/07 5590 +/- 616 MW-QC-1021 05/16/07 17100 +/- 1740 MW-QC-1021 06/05/07 30400 +/- 3060 MW-QC-1021 06/19/07 21900 +/- 2230 MW-QC-1021 07/16/07 8280 +/- 873 MW-QC- 021 09/19/07 4090 +/- 472 MW-QC-1021 10/16/07 6120 +/- 363 MW-QC-1021 12/12/07 3900 +/- 455 MW-QC-102S 02/22/07 < 176 MW-QC-102S 05/16/07 2160 +/- 263 MW-QC-102S 06/05/07 724 +/- 132 MW-QC-1 02S 06/19/07 < 188 MW-QC-102S 09/19/07 < 184 MW-QC-102S 10/16/07

189 MW-QC-102S 12/12/07 < 174 MW-QC-1 031 02/23/07 < 189 MW-QC-1031 05/16/07 < 154 B -I 101 of 108

TABLE1B-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 SITE DATE H-3 MW-QC-1031 09/19/07 < 186 MW-QC-1 031 10/17/07 < 190 MW-QC-1031 12/12/07 < 171 MW-QC-1 04S 02/23/07 < 188 MW-QC-1 04S 05/16/07 < 150 MW-QC-104S 09/19/07 < 185 MW-QC-104S 10/16/07

188 MW-QC-104S 12/12/07 < 172 MW-QC-1051 02/23/07 < 189 MW-QC-1051 05/16/07 < 159 MW-QC-1051 09/19/07 < 188 MW-QC-1051 10/16/07 < 188' MW-QC-1051 12/12/07 < 181.

MW-QC-1061 02/23/07 < 193 MW-QC-1 061 05/16/07 < 154.

MW-QC-1061 09/19/07 '194 +/- 122 MW-QC-1061 10/17/07 < 187:ý MW-QC-1061 12/12/07 < 183, MW-QC-106S 02/23/07 "230 +/- 127 MW-QC-1 06S 05/16/07 < 154.:

MW-QC-106S 09/19/07 < 192,i MW-QC-106S 10/17/07 < 188%

MW-QC-106S 12/12/07 < 183.-

MW-QC-1071 02/21/07 < 191 MW-QC-1071 05/15/07 < 156' MW-QC-1071 09/18/07 < 191 MW-QC-1071 10/15/07 < 187, MW-QC-1071 12/10/07 < 182 MW-QC-108D 02/22/07 3300 +/- 398 MW-QC-108D 05/15/07 5180 +/- 563 MW-QC-108D 06/05/07 6260 +/- 671 MW-QC-108D 06/19/07 5810 +/- 632 MW-QC-108D 09/18/07 5950 +/- 656 MW-QC-108D 10/16/07 8050 +/- 870 MW-QC-108D 12/11/07 6770 +/- 741 MW-QC-1081 02/22/07 1290 +/- 199 MW-QC-1081 05/15/07 1730 +/- 223 MW-QC-1081 06/05/07 3080 +/- 355 MW-QC-1081 06/19/07 3500 +/- 406 MW-QC-1081 09/18/07 3680 +/- 433 MW-QC-1081 10/16/07 4930 +/- 560 MW-QC-1081 12/11/07 5330 +/- 597 MW-QC-108S 02/21/07 363 +/- 128 MW-QC-108S 05/15/07 787 +/- 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 COLLECTION SITE DATE H-3 MW-QC-108S 06/05/07 843 + 142 MW-QC-108S 06/19/07 870 + 157 MW-QC-108S 09/18/07 478 135 MW-QC-108S 10/16/07 < 190 MW-QC-108S 12/11/07 424 + 132 MW-QC -1091 02/22/07 1380 +/- 214 MW-QC-1091 05/16/07 429 + 118 MW-QC-1091 09/19/07 492 + 139 MW-QC-1091 10/17/07 < 196 MW-QC-1091 12/12/07 *.396+/- 129 MW-QC-i09S 02/22/07 187 MW-QC-1 09S 05/16/07 159 MW-QC-109S 09/19/07 191 MW-QC-109S 10/17/07 192' MW-QC-109S 12/12/07 182 MW-QC-1 101 02/21/07 189 MW-QC-1101 05/15/07 157 MW-QC-1101 09/19/07 1886 MW-QC-1101 12/11/07 180 MW-QC-111 Dl 02/21/07 193.

MW-QC-111 Dl 05/15/07 157-MW-QC-111 Dl 09/18/07 190 MW-QC-111 Dl 10/16/07 195.

MW-QC-111 Dl 12/11/07 186 MW-QC-111 D2 02/21/07 191 MW-QC-1 11 D2 05/15/07 162 MW-QC-1 11 D2 09/18/07 187 MW-QC-1 11 D2 10/16/07 197-MW-QC-111 D2 12/11/07 181 MW-QC-1111 02/21/07 185 MW-QC- 111i 05/15/07 409 +/- 115 MW-QC- 111i 09/18/07 <*'187 MW-QC-111I 10/16/07

196 MW-QC-1111 12/11/07

184 MW-QC-1 121 02/21/07

184 MW-QC-1 121 05/15/07

163 MW-QC-1 121 09/18/07

185 MW-QC-1 121 10/16/07

195 MW-QC-1 121 12/11/07 446 +/- 132 MW-QC-1 121 12/11/07 252 +/- 125 MW-QC-1 121 12/11/07 412 +/- 119 MW-QC-1131 02/21/07 <. 184 MW-QC-1131 05/15/07 < 160 MW-QC-1 131 09/18/07 < 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 COLLECTION SITE DATE H-3 MW-QC-1 131 10/16/07 < 195 MW-QC-1131 12/11/07 < 180 MW-QC-1 141 02/21/07 < 189 MW-QC-1 141 05/15/07 < 160 MW-QC-1 141 09/18/07 < 190 MW-QC-1141 10/16/07 < 189 MW-QC-1 141 12/11/07

182 MW-QC-1 15S 02/22/07 < 190 MW-QC-1 15S 05/15/07,

160 MW-QC -115S 09/17/07 < 192 MW-QC-i 15S 10/15/07 < 198 MW-QC-1 15S 12/10/07 < 178 MW-QC-1 16S 02/21/07 < 189 MW-QC-1 16S 05/15/07 < 156 MW-QC-1 16S 09/17/07 203 +/- :122 MW-QC-1 16S 10/15/07 < 195 MW-QC-1 16S 12/10/07 222 +/- 118 MW-QC-1 16S 12/10/07 < 195 STP-SANDPOINT WELL 02/22/07 < 191 STP-SANDPOINT WELL 05/14/07 < 157 STP-SANDPOINT WELL 09/20/07 1<

92 STP-SANDPOINT WELL 10/30/07 < 189 WELL #1 02/06/07 287 +/- 128 WELL #1 02/22/07 '327 124 WELL #1 03/26/07 395 +/- 140 WELL #1 05/14/07 313 + 110 WELL #1 06/05/07 414 + 117 WELL #1 06/19/07 257 +/- 126 WELL #1 07/16/07 < 164 WELL #1 08/22/07 373 +/- 109 WELL #1 09/20/07 307 +/- 128 WELL #1 10/30/07 225 + 127 WELL #1 11/30/07 231 +/- 126 WELL #10 FISH HOUSE WELL 02/22/07 < 190 WELL #10 FISH HOUSE WELL 05/14/07 < 159 WELL #10 FISH HOUSE WELL 09/20/07 < 192 WELL #10 FISH HOUSE WELL 11/01/07 < 190 WELL #11 SPRAY CANAL WELL 05/14/07 < 159 WELL #11 SPRAY CANAL WELL 09/20/07 < 192 WELL #11 SPRAY CANAL WELL 11/01/07 < 193 WELL #5 03/26/07 < 190 WELL #5 05/14/07 < 151 WELL #5 06/05/07 < 153 WELL #5 06/19/07 < 184 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 COLLECTION Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 PERIOD QC-MW-1 09/19/07 < 42 < 41 <5 <5 <9 <4 <9 <5 <9 <4 <4 .22 <8 QC-MW-2 09/19/07 < 30 226 +56 <4 <3 <8 <4 <8 <4 < 7 <3 <4 17 <5 QC-MW-QC-101 I 09/19/07 < 16 < 18 <2 <2 <4 <2 <4 <2 < 3 <2 <2 9 <3 QC-MW-QC-101S 09/19/07 < 20 < 21 < 2 <2 <4 <2 <4 <2 <4 <2 <2 11 <4 QC-MW-QC-102D 09/19/07 < 27 < 30 <3 <3 <7 <4 <6 <4 <6 <3 <3 15 < 6 QC-MW-QC-1021 09/19/07 < 38 < 40 < 5 <'5 <9 < 4- <11 <4 <9 <4 "<5 25 '<8 QC-MW-QC-102S 09/19/07 < 46 < 46 <6 "< 5 < 11 < 6.' <"9 <6 < 10 <5 '<5 27 <9

42 < 85 <..4 <5 <8 < 4 <'9 <6 <8 <4 4 24 <9 QC-MW-QC-1031 09/19/07 '<

QC-MW-QC-104S 09/19/07 < 30 .36 <j 3 < 3 <9 <5 <':8 <4 <8 <3 "< 4 19 <6 QC-MW-QC-1051 09/19/07 < 34 < 93 S<4 <5 .< 8 < 7' .<5 < 7 <4 < 4 21 < 7 QC-MW-QG-1061 09/19/07 < 30

65 <3 <4 < 7

<'4 <6 < 3 < 7- <3 <4 18 < 6 QC-MW-QC-106S 09/19/07 < 39 < 107 <4 <5 < 10 <4 < 10 <5 <9 <4 <5 22 < 8 QC-MW-QC-1071 09/18/07 < 33 < 33 <4 <4 <8 <4 <9 <4 < 8 <4 <4 22 <6 QC-MW-QC-108D 09/18/07 < 39 < 91 <4 <5

10 <4 <8 <5 <8 <4 '<4 25 < 9 09/18/07

41

50 <5 <5 < 12 <7 < 11 <5 <9 <4 <5 27 <9 QC-MW-QC-1081 <.5 QC-MW-QC-108S 09/18/07 < 42 < 53 <5 <'4 <.10' < 6- <11 <5 < 5 27 <7

< 50 < 107 < '6

< :6 <.11.' '<5 < 12 <5 <6 33 < 10 QC-MW-QC-1 091 09/19/07 "< 9

< "'11 " <'.'11" < .5 QC-MW-QC-109S 09/19/07 < 47 155 + 79 < 5' <5 < 5'.' <9 < 5 <<5 27 < 11 QC-MW-QC-1101 09/19/07 < 44 < 41 <5 <6 < 12 <5 < 10 <6 < 11 <5 '< 6 30 < 10 QC-MW-QC-111 Dl 09/18/07 < 54

122 <6 <5 < 12 <6 < 11 <7 < 12 <5 < 6 30 <9 QC-MW-QC-111 D2 09/18/07 < 41

46 <5 <4 <9 <5 < 10 <5 <9 <4 <<5 25 <7 QC-MW-QC- 1111 09/18/07 < 47 < 39 <5 <5 < 10 <5 < 10 <5 < 11 <5 <6 27 <9

< 62 <4 <3 *<.7 <4 <9 <4 <8 <4 < 4 23 <6 QC-MW-QC-1 121 09/18/07

31 QC-MW-QC-1 131 09/18/07 < 50 < 120 <6 <6 < 10- <6 < 10 < 7 < 12 <5 < 6 31 < 11 QC-MW-QC-1 141 09/18/07 < 48

89 <5 <5 *10 <7 < 10 <6 < 11 <4 <5 26 <9 QC-MW-QC-1 15S 09/17/07 < 33 197 +/- 47 < 4 <4 <8 < 4" < 7 '< 4 < 8 <3 <4 20 <6

<4 < 10. <6 '< 9 <5 < 11 < 4 < 5 < 29 o< 11 QC-MW-QC-1 16S 09/17/07

38 < 116 <5 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 COLLECTION SITE DATE H-3 SURFACE WATER #1 05/14/07 413 +/- 115 SURFACE WATER #1 06/04/07 438 +/- 116 SURFACE WATER #1 06/18/07 < 191 SURFACE WATER #1 09/17/07 < 190 SURFACE WATER #2 05/14/07 330 +/- 110 SURFACE WATER #2 06/04/07 275 +/- 108 SURFACE WATER #2 06/18/07 < 187 SURFACE WATER #2 09/17/07 < 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 < 45 < 100 < 5 < 6 < 10 < 6 <11 <6 <9 <11 <4 <5 <29 <9 SURFACE WATER #2 09/17/07 < 43 < 52 < 5 < 5 < 12 < 6 < 11 < 4 < 10 < 11 < 5 <5 < 29 <9 0

0-..

00 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 COLLECTION SITE DATE H-3 WELL #5 07/16/07 < 165 WELL #5 08/22/07 < 144 WELL #5 09/20/07 < 187 WELL #5 10/30/07 < 192 WELL #5 11/30/07 < 191 WELL #6 LITTLE FISH WELL 02/22/07

195 WELL #6 LITTLE FISH WELL 05/14/07 < 152 WELL #6 LITTLE FISH WELL 09/20/07 < 190 WELL #6 LITTLE FISH WELL 11/01/07 < 193 WELL #7 BIG FISH WELL 02/22/07 205 + 126 WELL #7 BIG FISH WELL 05/14/07 341 + 110 WELL #7 BIG FISH WELL 06/05/07 421 + 119 WELL #7 BIG FISH WELL 06/19/07 236 + 129 WELL #7 BIG FISH WELL 09/20/07 221 + 126 WELL #7 BIG FISH WELL 11/01/07 < 191 WELL #8 FIRE TRAINING WELL 02/22/07 < 189 WELL #8 FIRE TRAINING WELL 05/14/07 169 +/- 105 WELL #8 FIRE TRAINING WELL 09/20/07

193 WELL #8 FIRE TRAINING WELL 10/30/07

196 WELL #9 DRY CASK WELL 02/22/07

190 WELL #9 DRY CASK WELL 05/14/07 < 156 WELL #9 DRY CASK WELL 09/20/07 < 191 WELL #9 DRY CASK WELL 10/30/07

188 B -8 108 of 108

SVP-08-023, Annual Radiological Environmental Operating Report

Contents

Text

Subject:

Attachment:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

SVP-08-023, Annual Radiological Environmental Operating Report

Text

Subject:

Attachment:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search