SVP-10-021, Annual Radiological Environmental Operating Report
| ML101380328 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/12/2010 |
| From: | Tulon T Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SVP-10-021 | |
| Download: ML101380328 (116) | |
Text
Exeltn.
Exelon Generation Company, LLC Cuad Cities Nuclear Power Station 22710 206th Avenue North Cordova, I L 61242-9740 www.exelOnCOTP.COM Nuclear SVP-10-021 May 12, 2010 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:
Annual Radiological Environmental Operating Report Pursuant to Technical Specifications Section 5.6.2, enclosed is the 2009 Radiological Environmental Operating Report for Quad Cities Nuclear Power Station. This report contains the results of the radiological environmental and meteorological monitoring programs. Also included is the 2009 Radiological Groundwater Protection Program (RGPP) Report, as Appendix E of the enclosure.
Should you have any questions concerning this letter, please contact Wally J. Beck at (309) 227-2800.
Respectfully, hy J. Tulon
'ice President Cities Nuclear Power Station
Enclosure:
Annual Radiological Environmental Operating Report cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - Quad Cities Nuclear Power Station Ric
Enclosure 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 2009 Prepared By Teledyne Brown Engineering Environmental Services Exek n.
Nuclear Quad Cities Nuclear Power Station Cordova, IL 61242 May 2010
Table' Of Contents I. S m a r n C o nc'l~usi'o n~s.-::.. :":-.....'.ý'.;..i. ;...
................. i :...
......... i... i..
- ............. 1 I. Summary and Con.......s I1. Introd uctio n.......................................................................................................
..... 3 A. O bjectives of the R E M P........................................
........................................ 3 B. Im plem entation of the:O bjectives.!?..................................................................... 3 Ill. P rogram D escription................................................................................................
.. 3
'A.sam ple Collection 3.....
B. Sample Analysis...............................
5 C. D ata Interpretation....................................................................................
.....6 D. Program Exceptions.......................................................................................
7 E. Program Changes.....
9 IV. Results and Discussion.
9 A, Aquatic Environm ent..':.........................
. 9
- 1. Surface Water.....................................
9
- 2. G round W ater..................................................................................
.. 10 3. F is h...................................................................................................
..1. 1.1 4. S ed im e nt..........................................................................................
11 B. Atmospheric Environment............... ;t!
11 1. A irb o rn e....................................................
............................................. 1 1 a.- A ir P articul~ tes..........................................
................................ 11
- b. A irborne Iodine......................................................................
.. 12 2. T e rrestria l.........................................................................................
.. 12
- a. Mik.........
........ ý.,?.
........... 12
- b. Food Products........................................................................
13 C. A m bient G am m a Radiation...........................................................................
13 D. Independent Spent Fuel Storage.......
I 13
- E. Land U se S urvey.,
13 F. Errata Data..............
14 G. Summary of Results - Inter-laboratory Comparison Program
........... 15
Appendices Appendix A Radiological Environmental Monitoring Report Summary Tables Table A-1 Appendix B Tables Table B-i:
Table B-2:
Radiological Environmental Monitoring Program Annual Summary for Quad Cities Nuclear Power' Station, 12009 Location Designation, Distance & Direction, and Sample Collection &
Analytical Methods Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2009 Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2009 Figqures Figure B-I:
Figure B-2:
Appendix C Tables Table C-1.1 Table C-1.2 Table C-1.3 Table C-11.1 Table C-I1.2 Quad Cities REMP Sampling Locatidns- `2 Mile Radius,`2009 Quad Cities REMP Sampling Locations - 9.3 Mile Radius, 2009 Data Tables and Figures - Primary Laboratory Concentrations of Gross Beta in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
Concentrations of Tritium in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
Concentrations of Gamma Emitters in Ground Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
Table Table Table Table Table Table Table Table Table Table Table Table C4lIl. 1 Concentrations of Gamma Emitters,in, Fish Samples Collected in the Vicinity of Quad Cities'Nucear Power Station, 2009.
C-IV.1 Concentrations of Gamma EUhitters in Sediment Samples Collected in the Vicinity of Quad Cities' Nuclear Power Station, 2009.
C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations Air Particulate Samples Collected in the Vicinity ofQuad Cities Nuclear.
Power Station, 2009.
C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
C-V1,1 Concentrations of I-131 in Air Iodine SamplessCollected in the Vicinity of Quad Cities Nuclear PowerStation, 2009.
C-VII.1 Concentrations of 1-131 -in Milk Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
C-VII.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Quad Citie's Nuclear Power Station, 2009.
C-VIII.1 Concentrations of Gamma Emitters in Food Products Samples.,
Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
C-IX,1 Quarterly TLD Results for Quad Cities Nuclear Power Station, 2009.
C-IX,2.
Mean Quarterly TLD Results. for the Inner Ring, Outer Ring, Other and Control Locations for Quad Cities Nuclear Power Station, 2009.
C-IX.3 Summary of the Ambient Dosimetry Program for Quad Cities Nuclear Power Station, 2009.
Figqures Figure C-1 Figure C-2 Figure C-3 Figure C-4 Figure C-5 Figure C-6 Surface Water - Gross Beta - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2009.
Surface Water - Tritium - Stations Q-33 and Q-34 (C) Collected in the Vicinity of QCNPS, 2000 - 2009.
Ground Water - Tritium - Station Q-35 and Q-36 Collected in the Vicinity of QCNPS, 2000 - 2009.
Air Particulates - Gross Beta - Stations Q-01 and Q-02 Collected in the Vicinity of QCNPS, 2000 - 2009.
Air Particulates - Gross Beta - Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2000 - 2009.
Air Particulates - Gross Beta - Station Q-07 (C) Collected in the Vicinity of QCNPS, 2000 - 2009.
Figure C-7 Figure C-8 Figure C-9 Appendix D Air Particulates - Gross Beta -. Stations Q-13 and Q-16 Collected in the Vicin'ity of QCNPS, 2005-2009.."
Air Particulates - Gross Beta - Stations Q-37 and Q-38 Collected in the Vicinity'of QCNPS, 2005 - 2009.
Air Particulates - Gross Beta - Stations Q-41 Collected in the Vicinity of QCNPS, 2009.','
Inter-Laboratory Comparison Program' Tables Table D-1 Table D-2 Table D-3 Table D-4 Table D-5 Analytics Environmental Radioactivity Cross Check, Program Teledyne Brown Engineering, 2009, ERA Envir6nmentall Radioactivity Cross Check Program Teledyne BrownhEngineering, 2009 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)
Teledyne Brown Engineering, 2009, ERA Statistical Summary Proficiency Testing Program Environmental, Inc., 2009 DOE's Mixed Analyte Performance Evaluation Program (MAPEP)
Environmental, Inc., 2009 Annual Radiological'Gro'undwaýter Protectibn Prograr a Report (ARGPPR)
Appendix E
Summarykand Conclusions In 20091the Qiuad Cities Generating Station released to the environment through the radioactive effluent liquid and gaseous pathways approximately.172 curies of noble gas, fission and activation products and approximately 121-curies of tritium.
The dose from. both liquid and gaseous effluents was conservatively calculated for the Maximum Exposed Member of the Public. The results of those calculations and their comparison to the allowable limits were as follows:
Gaseous and liquid radiation doses to members of the public at locations Applicable Estimated Age Location
% of Site Unit Effluents Organ Dose Group Distance Direction Applicable Limit (meters) -
"(toward)
Limit Noble Gas Gamma - Air Dose 8.40E-04 AI[
.1029.
ESE 20 mRad Noble Gas Beta - Air Dose.
4.32E-04 All
.1029
..... ESE 40 mRad 1.08E-03 Noble Gas Total Body (Gamma) 4.30E-03.
Child 1029 ESE 10:
mrem 4.30E-02 Iodine, Particulate &
Thyroid 2.94E-01 I nfant
'1029 NNE "980E-01 30 mrem Tritium Liquid Total Body*
6.11E-03 Adult RDT via South Diffuser 1.01E-01 6
mrem Liquid Liver 9.67E-03 Teen RDT via South Diffuser 4.84E-02 20 mrem Total Body - Direct 7.29E+00 All 800 N
2.92E+01 25 mrem 40CFR1 90*
Radiation
- Thyroid and Organ doses <1% of 40CFR190 Limits.
The doses as a result of the radiological effluents released from the Quad Cities Generating Station were a very small percentage of the allowable limits, with the exception of 40CFR190 direct radiation which was calculated to be 29.2% of the 25 mrem/yr limit.
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 2009 through 31 December 2009. During that time period, 1,436 analyses were performed on 1,534 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.
1 of 109
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. A small concentration of Cs-1 37 was found in three of four sediment samples., No other fission products or activation products were found in sediment.
Air particulate samples were analyzed for conicentrations of gross beta and gamma emitting nuclides. No fission or activation productswere 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.
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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. Ufnit No. 2 went Critical on.02'December'1973.. The siteý is located in northern Illinois,.approximately 182 mileswest 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 2009 through, 31 December 2009.
A.
Objective of the. REMP The objectives of the;REMP are to:
- 1.
Provide data on measurable levels of radiation and radioactive materials in the site environs.
- 2.
Evaluate the relationship between quantities of radioactive material released from the plant and resultant radiation doses to individuals from principal pathways of exposure.
B.-
Implementationrof the Objectives The implementation of the objectives is accomplished by:
- 1.
Identifying significant exposure. pathways..
- 2.
Establishing baseline, radiological data. of media within those pathways.
- 3.
Continuously monitoring those media before and during Station operation to assess Station radiological effects (if any) on man and the environment.
Ill.
Program Description A.
Sample Collection 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 2009. Sample locations and 3 of 109
descriptions can be found in Table B-1 and Figures B-i -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 andQ-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 two locations semiannually, Q-39 and Q-40 (Control).
Atmospheric Environment The atmospheric environment was evaluated by performing radiological analyses on samples of air particulate, airborne iodine, and milk. Airborne iodine and particulate samples were collected and analyzed at ten locations (Q-01, Q-02, Q-03, Q-04, Q-07, Q-13, Q-16, Q-37, Q-38, and Q-41). The control location was Q-07. Airborne iodine and particulate samples were obtained at each location, using a-vacuum pump with charcoal and glass fiber filters attached. The pumps were run continuously and sampled air at the rate of approximately one cubic foot per minute. The 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 4 of 109
dosimeters (TLD). Each location consisted of 2 TLD sets. The TLD locations were placed on and around the QCNPS site as follows:
An inner rinq 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, 0-208, Q-209, Q-210; 0Q-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 ofnine locations (Q-01, Q-02, Q-03, Q-04, Q-13, Q-16, Q-37, Q-38 and Q-41). The locations are at each of the air sample stations around the site.
The'balance of one location (0-07),is the control site.
The specific TLD locations were determined by the following criteria:
1.'
The presence of relatively dense population;
- 2.
Site meteorologibal 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 2009 and the type of analyses. The analytical procedures used by the laboratories are listed in 5 of 109
Table B-2.
In order to achieve the stated objectives, the current program includes the following analyses:.
- 1.
Concentrations of beta emitters in surface water~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. 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 irntended 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.
6 of 109
- 2.
'Net Activity Calculation and Reporting of Results Net activity for'asample 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
- grquped 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-1 34, Cs-1 37 and Ba-140 and La-.140 were reported.
Means and standard deviations 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 2009 the QCNPS REMP had a sample recovery rate in excess of 99%. Sample anomalies and missed samples are listed in the tables below:
Table D-1 LISTING OF SAMPLE ANOMALIES Sample Location Collection Reason Type Code Date A/I Q-41 01/02/09 Low reading of 42.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> due to startup of new locations as of 12/31/08.
A/I Q-41 04/03/09 Low reading of 138.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> due to tripped breaker. Collector reset breaker.
TLD Q-205-1 04/03/09 Results were outside 3 sigma administrative trend. Duplicate TLD 205-4 in the same sector read as expected.
7 of 109
Table D-1, LISTING OF SAMPLE ANOMALIES (continued)
Sample.
Location Collection
,Reason-Type Code Date A/I Q-41 05/08/09 Low reading of120.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to blown breaker during storm.
A/I Q-01 06/12/09 LoW reading of 61.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> due to power outage at air station; workers replaced GFI TLD Q-205-1 07/01/09 Results were outside 3 sigma administrative trend. Duplicate TLD 205-4 in the same sector read-as expected.
A/I Q-38 08/14/09 Low reading of 162.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> due to severe weather causing power outages in the area.
TLD Q-201-1 09/04/09 TLD was found on the ground; remounted.
TLD Q-204-2 10/01/09 Results were outside 3 sigma administrative trend. Duplicate TLD 204-1 in the same sector-e~ad as expected.
A/I Q-13 12/11/09 Low reading of 166.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> due to power outage from snow storm.
A/I Q-41 12/11/09 Low reading of 137.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> due to power outage from show storm.
A/I Q-41 12/24/09 Low reading of 109.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to power outage from ice storm.
A/I Q-13 12/24/09 Low reading of 132.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> due to power outage from ice storm.
A/I Q-41 01/01/10-Low reading of 64.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to blown surge protector. GFCI was replaced.
Table D-2 LISTING OF MISSED SAMPLES Sample-Location Collection Reason Type Code Date SW
.Q-33 01/02/09 - 02/20/09 No sample'; water frozen SW Q-34 01/02/09 - 02/06/09 No sample; water frozen 8 of 109
'"Table D-2 -` 'LISTING 0F MISSED SAMPLES (continued)
Sample
- Location, Collection Reason Type Code Date TLD Q-41-1 04/03/09 TLDs were missing for 2 nd quarter Q-41 exchange. Collector placed spare TLDS at both locations.
TLD Q-13-1
.04/03/09:
V
- .Vendor misplaced TLDs upon Q-13-2 receiving them. No data available for the,2nd quarter.
A/I Q-37 10/23/09 Low reading of 0.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> due to ground fault outlet malfunction; collector replaced. Insufficient run time for viable sample.
A/I Q-37 10/30/09 Low reading'of 0.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> due to pump malfunction; collector replaced pump. Insufficient run time for viable sample.
.Q33 12/!,1/09 - 01/01/10 No sample; water frozen Q-34 The overall sample recovery rate indicates that the appropriate procedures and equipment are in place to assure reliable program implementation..
E.
Program Changes TLD and A/I station Q-41 was added to the AREOR program on January 01,2009.
Sediment station Q-40 was added to the AREOR program on January 01, 20090.'
IV.
Results and Discussion A.
Aquatic Environment
- 1.
Surface Water Samples were taken weekly and composited monthly at two 9 of 109
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.
Gross Beta Samples from all locations were analyzed for concentrations of gross beta (Table C-1.1, Appendix C). Gross beta activity was detected in 19 of 22 samples. The values ranged from 3.2 to 9.4 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.
Tritium 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.
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:
Tritium Quarterly grab samples from the locations were analyzed for tritium activity (Table C-11.1, 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.
10 of 109
- 3.
Fish Fish samples comprised, of various commercially and recreationally winportant species were cillected~attw6 locations (Q-24 and Q-29) semiannually. Location Q-24 could be affected by Quad Cities' effluent releases". The following analysis was performed:
Gamma Spectromet The edible portion of fish samplesfrom both locations was
, anIalyzed for gamma emittihg nuclides (Table C-I11.1, Appendix C).
No nuclides were detebted and all reqluired LLDs were met.
- 4.
Sediment Aquatic sediment samples'were collected at two locations (Q-39 and Q-40) semiannually.' The'locati6n, *located downstream, could be affected by Quad Cities' effluent releases. The following analysis was performed:&
Gamma Spectrometry Sediment samples from *Q-39: and Q-40 were analyzed for gamma
.emitting nuclides (Table C-IV.1, Appendix C). Cesium-137 was
detected in three of fou-r samples. The values ranged from 64 to 496 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 ten locations on a weekly basis. The ten 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, Q-41) and the Control sampler between 10 and 30 km from the site (Q-07). The following analyses were performed:
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Gross Beta Weekly samples.were, analyzed for concentrations of beta emitters (Table C-V.1 and C-V.2, Appendix C).
DetectableQgross 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
- 1) ranged from 5 to39 E-3 pCi/m 3 with a mean of 20 E-3 pCi/m. The results from the far-field locations (Group II) ranged from 5 to 4.1 E-3 pCi/m3 with a mean of 20 E-3 pCi/m 3. The results from the Control location (Group Ill) ranged from 6 to 42 E-3 pCi/m 3 with a mean of 22 E-3 pCi/m 3. Comparison of the 2009 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 2009 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 ten locations (Q-01, Q-02, Q-03, Q-04, Q-07, Q-13, Q-16, Q-37, Q-38 and Q-41) and analyzed weekly for 1-131 (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-1 31 Milk samples from the location were analyzed for 12 of 109
.concentratiohs of'1-131 (Table CG-VII.1,Appendix C). No
"'--13 Was detected and the LLDwas met.
Gamma Spectrometry Each milk sample was analyzed for concentrations of gamma emitting nuclides (Table C-VII:2, Appendix C). No nudlides were detected:and all required LLDs were met.
- b.
Food Products.
Food product samples were collected at four locations plus a control location (9-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-one 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 of the TLD measurements were-below 30 mR/quarter, with a range of 17 to:30 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 2009 around QCNPS was 13 of 109
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.
Distance in Miles from QCNPS Sector-Residence Livestock Milk Farm Miles Miles Miles N
0.6 2.7 NNE.
3.8 6.0 NE I
1.3.
ENE 2.9 2.9 E
2.0 2.7 ESE 2.8 3.1 3.1 SE 2.5 3.2 SSE 1.1 3.6 6.6,11.5 S
0.8 1.6 SSW 3.2 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 During a self assessment (AT 981645) the following, errors Were noted in the 2008 Annual Radiological Environmental Operating Report:
- 1.
Sample anomaly from 8/8/08 was not included in the annual report.
During this particular sampling period, air particulate sampling station Q-02 read low in overall sampling hours. The recorded time was 87.2 and should have read approximately 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />. The GFCI was found to be faulty and replaced. The pump was restarted with no further-issues. (Reference IR 808162)
- 2.
Sample-anomaly from 10/3/08 was noted twice in the Program Exceptions table. This repeat anomaly was for TLDs Q-1 11-1 and nd Q-114-1, which were not exchanged 2. quarter of 2008 due to flood waters. The table should only reflect one entry for these samples on 10/3/08.
14 of 109
3:.
Sample anomaly listings from 5/2/08, 6/27/08, and 10/3/08 reflect non-specific location Codes listed in the'('Other') Program Exceptions table. Each of these location codes should have read
'Q-202-1.'
G..
Summary of Results - Inter-Laboratory Comparison Program The primary and secondary laboratories analyze d 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-ESevaluates 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 percentagelimit promulgated under the appropriate regulatory document 3.,
DOE Evaluation Criteria MAPEP's evaluation report provides an acceptance range with
..,.associated flag values.
The MAPEP* defines three levels of performance: Acceptable (flag = "A"), Acceptable with Warning (flag = "W"), and Not Acceptable (flag = "N"). Performance is considered acceptable when a mean result for the specified analyte is +/- 20% of the reference value. Performance is acceptable with warning when a mean result falls in the range from +/-20% to +/-30% of the reference value (i.e., 20% < bias < 30%). If the bias is greater than 30%, the results are deemed not acceptable.
15 of 109
For the primary laboratory, 17 out of 18 analytes met the specified acceptance criteria. One sample did not.meet the specified acceptance criteria for the following reason:
- 1.
Teledyne Brown Engineering's Analytics June 2009 Zn-65 in AP result of 137 pCi/L was higher than the known value of 101 pCi/L, resulting in a found to known ratio of 1.36. NCR 09-23 was initiated to investigate.this failure. The failure appears to be a result of a slightly high bias on Detector 7. A recount on Detector 17 resulted ina Zn,-65 result of 101 pCi/L. The detector has been tagged odt-of-service until a recalibration can be performed.
Detector 7. is not used for client samples.
For the secondary laboratory, Environmental,Inc., 11 out of 14 analytes met the specified acceptance criteria. Four samples did not meet the specified acceptance criteria for the following reasons:
- 1. Environmental Inc.'s ERA April 2009 Cs--137 in water result of 147.7 pCi/L exceeded the lower control limit of 151.0 pCi/L. All gamma emitters showed a. low bias. A large plastic burr found on the base ofthe Marinelli kept the beaker from sitting directly on the detector. Recounting in a different beaker gave an acceptable result of 155.33 +/- 14.55 pCi/LJ-
- 2. Environmental Inc.'s ERA April 2009 H-3 in water result of 22819 pCi/L exceeded the upper'contr'ol limit of 22300 pCi/L. A recount of the original vials aver'aged 23,009'pCi/L. Reanalysis results were acceptable at 19,170 pCi/L. No cause could be found for the failure.
- 3. Environmental Inc.'s MAPEP.January 2009 Sr-90 in AP result of 0.93 exceeded the upper control limit of 0.83., Reanalysis results were acceptable at 0.54 +/- 0.12. Bq/filter. No cause could be found for the failure.
- 4. Environmental Inc.'s MAPEP July 2009 Sr-90 in soil result of 310.5 Bq/kg exceeded the lower control limit of 319 Bq/kg. Reanalysis results were acceptable at 363.3 Bq/kg. Incomplete separation of strontium from calcium could'result in a higher recovery percentage and consequently lower reported activity.
The Inter-Laboratory Comparison Program provides evidence of "in control" counting systems and methods, and that the laboratories are producing accurate and reliable data.
16 of 109
APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
SUMMARY
17 of 109
TABLE A-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
FOR QUAD CITIES NUCLEAR POWER STATION, 2009 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER:
50-254 & 50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD:
ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)
MEAN (M)
MEAN (M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE-RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS SURFACE WATER (PCI/LITER)
6.0 (9/11)
(3.2/9.4) 2000
<LLD 15
<LLD.
5.2 (10/11)
(3.3/7.1) 6.0 (9/11)
(3.2/9.4)
Q-33 INDICATOR CORDOVA 3.1 MILES SSW OF SITE
<LLD
<LLD 22 CO-58 FE-59 CO-60 ZN-65 NB-95 15
<LLD
<LLD 30
<LLD
<LLD 0
0 0
0 0
15
<LLD 30
<LLD 15
<LLD
<LLD
<LLD
<LLD 00 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, 2009 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER:
50-254 & 50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD:
ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)
MEAN (M)
MEAN (M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS SURFACE WATER (PCI/LITER) t'J ZR-95 1-131 CS-134 CS-137 BA-140 LA-140 15
<LLD 15
<LLD 18
<LLD 60
<LLD 15
<LLD 2000
<LLD 30
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 0
0 0
0 0
0 GROUND WATER (PCI/LITER)
H-3 8
NA 0
0 GAMMA MN-54 8
15
<LLD NA 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, 2009 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER:
50-254 & 50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD:
ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS
, LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)
MEAN (M)
MEAN (M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS GROUND WATER (PCI/LITER)
<LLD NA ZN-65 NB-95 ZR-95 30
<LLD 15
<LLD 30
<LLD 15
<LLD 30
<LLD 15
<LLD 15
< LD NA NA NA NA NA NA NA 0
0 0.
1-131 0
0' 0
CS-134" 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, 2009 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER:
50-254 & 50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD:
ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)
MEAN (M)
MEAN (M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS GROUND WATER (PCI/LITER)
CS-137 BA-140 LA-140 GAMMA MN-54 FISH (PCI/KG WET) 8 18
<LLD 60
<LLD 15
<LLD 130
<LLD 130
<LLD 260.
<LLD 130
<LLD 260
<LLD NA NA NA 0
0 0
<LLD
<LLD 0
0
<LLD 0
ZN-65
<LLD 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, 2009 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER:
50-254 & 50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD:
ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)
MEAN (M)
MEAN (M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS FISH (PCI/KG WET)
NB-95 ZR-95 6>
CS-134 NA
<LLD NA
<LLD 130
<LLD 150
<LLD NA
<LLD NA
<LLD
- LLD
<LLD
<LLD 0
CS-137 BA-140 LA-140 GAMMA MN-54
<LLD
<LLD
<LLD 0
0 0
SEDIMENT (PCI/KG DRY) 4 t'J 0o 0
NA
<LLD NA
<LLD
<LLD
<LLD 0
0 CO-58 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, 2009 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER:
50-254 & 50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD:
ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)
MEAN (M)
MEAN (M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS SEDIMENT (PCI/KG DRY)
FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 NA.
<LLD NA-
<LLD NA
<LLD NA
<LLD NA
<LLD 150
<LLD 180 112 (1/2)
NA
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 0
0 0
0 0
0 0
0 280-(?/2)
(64/496) cLLD 280 (2/2)
(64/496)
Q-40 CONTROL NORTH OF ALBANY 8.9 MILES NE OF SITE 0
BA-140 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, 2009 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER:
50-254 & 50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD:
ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)
MEAN (M)
MEAN (M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS SEDIMENT (PCI/KG DRY)
LA-140 AIR PARTICULATE (E-3 PCI/CU.METER)
GR-B 518 40 GAMMA MN-54 NA
<LLD 10 20 (463/466)
(5/41)
NA
<LLD NA
.<LLD NA
<LLD CO-58 FE-59
<LLD 22 (51/52)
(6/42)
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 22 (52/52)
(9/41)
Q-13 INDICATOR PRINCETON 4.7 MILES SW OF SITE 0
0 0
NA
<LLD ZN-65 NA
<LLD NA
<LLD 0
0 0
NB-95 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, 2009 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER:
50-254 & 50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD:
ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)
MEAN (M)
MEAN (M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS AIR PARTICULATE (E-3 PCI/CU.METER)
ZR-95 NA
<LLD
<LLD CS-134 50
<LLD
<LLD 00 CS-137 60
<LLD
<LLD 0
0 0
0 0
BA-140 LA-140 GAMMA 1-131 NA
<LLD
<LLD
<LLD NA
<LLD AIR IODINE (E-3 PCI/CU.METER) 518 MILK (PCI/LITER) 1-131 20 20 70
<LLD; I
<LLD NA
<LLD
<LLD 0
NA 0
0 GAMMA MN-54 NA 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, 2009 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER:
50-254 & 50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD:
ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)
MEAN (M)
MEAN (M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS MILK (PCI/LITER)
CO-58 FE-59 CO-60 ZN-65 NB-95 ZR-95 CS-134 CS-137 NA
<LLD NA
<LLD NA
<LLD NA
<LLD NA
<LLD NA
<LLD 15
<LLD 18
<LLD NA NA NA NA NA NA NA NA 0
0 0
0 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, 2009 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER:
50-254 & 50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD:
ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)
MEAN (M)
MEAN (M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS MILK (PCI/LITER)
BA-140 LA-140 VEGETATION (PCI/KG WET)
GAMMA MN-54 10 CO-58 FE-59 CO-60 ZN-65 NB-95 60
<LLD 15
<LLD NA
<LLD NA
<LLD.
NA
<LLD NA
<LLD NA
<LLD NA
<LLD NA NA
<LLD
<LLD
<LLD
<LLD.
<LLD
<LLD 0
0 0
0 0
0 0
0
- i-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, 2009 NAME OF FACILITY: QUAD CITIES DOCKET NUMBER:
50-254 & 50-265 LOCATION OF FACILITY: CORDOVA, IL REPORTING PERIOD:
ANNUAL 2009 INDICATOR CONTROL LOCATION WITH HIGHEST ANNUAL MEAN (M)
LOCATIONS LOCATION MEDIUM OR TYPES OF NUMBER OF REQUIRED MEAN (M)
MEAN (M)
MEAN (M)
STATION #
NUMBER OF PATHWAY SAMPLED ANALYSIS ANALYSIS LOWER LIMIT (F)
(F)
(F)
NAME NONROUTINE (UNIT OF PERFORMED PERFORMED OF DETECTION RANGE RANGE RANGE DISTANCE AND DIRECTION REPORTED MEASUREMENT)
(LLD)
MEASUREMENTS VEGETATION (PCI/KG WET)
ZR-95 1-131 CS-134 NA
<LLD
,60
<LLD 60
<LLD 80
<LLD NA
<LLD NA
<LLD
<LLD
<LLD
<LLD 0
CS-137 BA-140
<LLD
<LLD
<LLD 0
0 0
0 0
0 LA-140 DIRECT RADIATION (MILLI-ROENTGEN/QTR.)
TLD-QUARTERLY 328 NA 22.1 (320'/320)
(17/30) 21.6 (8/8)
(14/25) 26.5 (4/4)
(25/29)
Q-205-1 INDICATOR 4.7 MILES E 00 0-MEAN AND RANGE BASED ON DETECTABLE MEASUREMENTS ONLY (M)
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)
APPENDIX B LOCATION DESIGNATION, DISTANCE & DIRECTION, AND SAMPLE COLLECTION & ANALYTICAL METHODS 29 of 109
TABLE B-i:
Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2009 Location Location Description Distance & Direction From Site A.
Surface Water Q-33 Q-34 Cordova (indicator)
Camanche, Upstream (control)
B.
Ground/Well Water 0-35 Q-36 McMillan Well (indicator)
Cordova Well (indicator) 3.1 miles SSW 4.4 miles NNE 1.5 miles S 3.3 miles SSW 3.5 miles ESE C.
Milk - bi-weeklv / monthly Q-26 Bill Stanley Dairy (indicator)
D.
Air Particulates / Air Iodine Q-01 Q-02 Q-03 Q-04 Q-07 Q-13 Q-16 Q-37 Q-38 Q-41 Onsite 1 (indicator) 0.5 miles N Onsite 2 (indicator) 0.4 miles ENE Onsite 3 (indicator) 0.6 miles S Nitrin (indicator) 1.7 miles NE Clinton (control) 8.8 miles NE Princeton (indicator) 4.7 miles SW Low Moor (indicator) 5.7 miles NNW Meredosia Road (indicator) 4.4 miles ENE Fuller Road (indicator) 4.7 milesE Camanche (indicator) 4.3 miles NNE Pool #14 of Mississippi River, Downstream (indicator) 0.5 miles SW Mississippi River, Upstream (control) 1.0 miles N E.
Fish Q-24 Q-29 F.
Sediment Q-39 Q-40 Cordova, Downstream on Mississippi River (indicator)
North of Albany, Upstream on Mississippi River(control)
G.
Food Products 0.8 miles SSW 8.9 miles NE 2.3 miles ENE 3.0 miles ESE 1.8 miles S 4.5 miles NW 9.5 miles NE Quadrant 1 Quadrant 2 Quadrant 3 Quadrant 4 Control Ken DeBaille Dale Nimmic Amy Johnston Mike Fawcett Charles Leavens H.
Environmental Dosimetry - TLD Inner Ring Q-101-1 Q-101-2 Q-102-1 Q-102-3 Q-103-1 and -2 Q-104-1 Q-104-2 Q-105-1 and -2 Q-106-2 and -3 Q-107-2 Q-107-3 Q-108-1 Q-108-2 0.6 miles N 0.9 miles N 1.3 miles NNE 1.4 miles NNE 1.2 miles NE 1.1 miles ENE 0.9 miles ENE 0.8 miles E 0.7 miles ESE 0.7 miles SE 0.8 miles SE 1.0 miles SSE 0.9 miles SSE B-1 30 of 109
TABLE B-i:'
Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2009 Location Location Description Distance & Direction From Site H.
Environmental Dosimetry - TLD (continued)
Inner Ring Q-109-1 Q-109-2 Q-111-1 Q-111-2 Q-112-1 Q-1 12-2 Q-113-1 and -2 Q-114-1 Q-114-2 Q-115-1 Q-115-2 Q-116-1 Q-116-3 Outer Ring Q-202-1 Q-202-2 Q-203-1 Q-203-2 Q-204-1 Q-204-2 Q-205-1 Q-205-4 Q-206-1 and -2 Q-207-1 and -4 Q-208-1 Q-208-2 Q-209-1 and -4 Q-210-1 and -4
- Q-210-5 Q-211-1 and -2 Q-212-1 Q-212-2 Q-213-1 Q-213-2 Q-214-1 Q-214-2 Q-215-1 Q-215-2 Q-216-1 Q-216-2 0.9 miles S 1.2 miles S 2.6 miles SW 2.5 miles SW 2.5 miles WSW 2.2 miles WSW 2.5 miles W 2.1 miles WNW 2.5 miles WNW 2.6 miles NW 2.3 miles NW 2.3 miles NNW 2.4 miles NNW 4.4 miles NNE 4.8 miles NNE 4.7 miles NE 5.0 miles NE 4.7 miles ENE 4.5 miles ENE 4.7 miles E 4.8 miles E 4.8 miles ESE 4.7 miles SE 4.3 miles SSE 4.9 miles SSE 4.7 miles S 4.1 miles SSW 3.3 miles SSW 4.5 miles SW 5.4 miles WSW 4.4 miles WSW 4.3 miles W 4.8 miles W 4.7 miles WNW 4.4 miles WNW 5.0 miles NW 4.2 miles NW 4.6 miles NNW 4.3 miles NNW 0.5 miles N 0.4 miles ENE 0.6 miles S 1.7 miles NE 4.7 miles SW 5.7 miles NNW 4.4 miles ENE 4.7 miles E 4.3 miles NNE Other Q-01 Q-02 Q-03 Q-04 Q-13 Q-16 Q-37 Q-38 Q-41 Onsite 1 (indicator)
Onsite 2 (indicator)
Onsite 3 (indicator)
Nitrin (indicator)
Princeton (indicator)
Low Moor (indicator)
Meredosia Road (indicator)
Fuller Road (indicator)
Camanche (indicator)
B-2 31 of 109
TABLE B-i:
Radiological Environmental Monitoring Program - Sampling Locations, Distance and Direction, Quad Cities Nuclear Power Station, 2009 Location Location Description Distance. & Direction.
From Site H.
Environmental Dosimetry - TLD (continued)
Control Q-07 Clinton (control) 8.8 miles NE
- Removed from ODCM in December 2006 and replaced by Q-210-5. Q-210-4 is for trending only.
B-3 32 of 109
TABLE B-2:
Radiological Environmental Monitoring Program - Summary of Sample Collection and Analytical Methods, Quad Cities Nuclear Power Station, 2009 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)-O1 Determination of gross alpha and/or
_gross 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 Glmma 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-2011 Tritium analysis in drinking water by liquid scintillation Env. Inc., T-02 Detemination of tritium in water (direct
_________method)
Fish GammaSpectroscopy.
Semi-annual, samples 4TBE-2007 Gamriia emitting radioisotope analysis collected via:
electroshocking or other Env. Inc., GS-01 Determination of gamma emitters by techniques gamma spJectroscopy Sediment Gamma Spectroscopy Semi-annual grab
., TBE, TBE-2007 Gamma emitting radioisotope analysis samples
. Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy Air Pafticulates Gross Beta "One-week composite of TBE, TBE-2008,Gross Alpha and/or gross beta activity in S
...coritinuous airsamPling various matrices through glass fiberfilter,-
n "
. A paper nv.
02 Determination of gross alpha and/or gross b6eta in air particulate filters Air Particulates Gamma Spectroscopy Quarterly comý6silteof TBE,,,TBE-2007 Gamma emitting radioisotope analysis a'ch station Env.,
Envlnc GS-01 Deterrm intionof 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 S"
canisters by gamma spectroscopy (batch method)
Milk 1 -131, ";
Bi-weekly grab sample TBETBE-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 Gamma Spectroscopy 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 analyis Env. Inc., GS-01 Determination of gamma emitters by gamma spectroscopy TLD Thermoluminescence Quarterly TLDs Global Dosimetry Dosimetry B-4 33 of 109
U North 101-121 i*
01 IS-U-l,t t
o7 i
00tie- -
i*
.5il a M io-i.
a ii S1 i-i,.1 S =
- itoi, 3-0 7k q0 I/-
1.5 QUAD CITIES S
STATION 0 I*,
RFIGURE 6-1 REMP Sample Locations 0*
0
.I-1-ýJ-gnm fl-j-ý K +/- -
.1.
£~0 Figure B-1 Quad Cities REMP Sample Locations - 2 Mile Radius, 2009
v,,
I.,....I...1-Sw 101-1.233N11E 012
___-1.2 E
02 E a 3
NS3 01-2.3 N
3 S
111 400 10
,-2.
10014 2 ONE 3N 101 1R.
N2 N -E 0130 00 102-1.2 NN 00 0 o r
-l.a NE 3
.00 30 01 i-*jJ'
<.200-1.2 ESE A 300EONOLOCICOE 10W00 NN R7-S S20-1.2 SNE 0
11 0
l 210-1.0 3SSW 3100001 213-1.2 wNNt A,0.1 m;+
2 NWN I
ASýTCT
......... 7300....000.
QUAD CITIES 031
..... 0 3
STAT I O N
- o.
r 22M33 203LREIN IS Figure B-2 Quad Cities REMP Sampling Locations 9 93 Mile Radius, 2009
APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY 36 of 109
TABLE C-I.1 CONCENTRATIONS OF GROSS BETA IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2'SIGMA COLLECTION PERIOD 01/03/09 - 01/31/09 02/13/09 - 02/27/09 03/06/09 - 03/27/09 04/03/09 - 04/23/09 05/01/09 - 05/29/09 06/05/09 - 06/26/09 07/03/09 - 07/31/09 08/07/09 - 08/28/09 09/04/09 - 09/25/09 10/02/09 - 10/30/09 11/06/09 - 11/27/09 12/04/09 - 12/04/09 Q-33 Q-34 I
(1) 5.7 +/- 2.0 6.5 +/- 1.9 8.0 +/-2.2 7.4 +/- 2.2
< 3.0 9.4 +/- 2.3 3.6 +/- 1.9 3.4 +/-2.0 3.2 +/- 1.8
< 3.0 6.5 +/- 2.2 (1) 6.8 +/- 2.1 5.9 +/- 1.9 6.5 +/- 2.1 7.1 +/- 2.2 3.3 +/- 2.1 5.5 4.1 3.8 3.7
+/- 2.1
+/- 2.0
+/- 2.0
+/- 1.9
< 3.0 5.6 +/-2A1 5.2 +/- 2.8 MEAN 6.0 +/- 4.4 TABLE C-I.2 CONCENTRATIONS OF TRITIUM IN SURFACE-WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/-2 SIGMA Q-33 Q-34 COLLECTION PERIOD 02/13/09 - 03/27/09 04/03/09 - 06/26/09 07/03/09 - 09/25/09 10/02/09 - 12/04/09 176 120 173 161 176 121 171 162 MEAN
- MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES C-I 37 of 109
TABLE C-1.3 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD Q-33 01/03/09 - 01/31/09 02/13/09 - 02/27/09 03/06/09 - 03/27/09 04/03/09 - 04/23/09 05/01/09 - 05/29/09 06/05/09 - 06/26/09 07/03/09 - 07/31/09 08/07/09 - 08/28/09 09/04/09 - 09/25/09 10/02/09 - 10/30/09 11/06/09 - 11/27/09 12/04/09 - 12/04/09 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 (1)
<1
<1
<1
<1
<1
<1
<1
<1
<3
<2
<1
<2
<2
<1
<1
<2
<2
<1
<2
<3
<2
<1
<4
<4
<2
<3
<3
<4
<3
<4
<6
<5
<3
<1
<2
<1
<1
<1
<1
<1
<1
<3
<2
<1
<3
<3
<1
<3
<2
<3
<2
<3
<5
<4
<2
<2
<2.
,< 1
<2
<2
.< 2
< 1.
< 2
'<3
<1
<3
<3
<1
<3
<3
<3
<2
<3
<5
<4
<2
<7
< 14
< 12
< 11
<8
< 14
<9
< 14
< 13
< 10
< 10
<1
<1
<1
<1
<1
<1
<1
<1
<2
<2
<1
<2
<2
<1
<1
<1
<1
<1
<2
<3
<.2
<1
< 14
< 21
< 16
< 17
< 14
< 20
< 15
< 20
<26
< 19
- < 42
<4
<7
<5 S<4 S<4
<6
- <5
<7
<8
< 6
< 14 MEAN Q-34 01/03/09 02/13/09 03/06/09 04/03/09 05/01/09 06/05/09 07/03/09 08/07/09 09/04/09 10/02/09 11/06/09 12/04/09 MEAN
- 01/31/09
- 02/27/09
- 03/27/09
- 04/23/09
- 05/29/09
- 06/26/09
- 07/31/09
- 08/28/09
- 09/25/09
- 10/30/09
- 11/27/09
- 12/04/09 (1)
<1
<1
<1
<1
<1
<1
<1
<1
<2
<2
<1
<2
<2
<1
<1
<1
<2
<1
<2
<2
<2
<1
<3
<4
<2
<3
<3
<4
<3
<3
<5
<5
<3
<1
<1
<1
<1
<1
<1
<1
<1
<2
< 2
<1
<3
<3
<1
<2
<3
<<3
<2
<2
<4
<4
.<2
<2
<2
<1
<1
<2
<<2
<1
<2
<2
<2
< 1'
<3
<3
<2
<2
<3
<3
<2
<3
<4
<4
<2
<7
<14
- 15
<8
<8 15
<7
<11
<11
<11
<9
<1
<2
<1
<1
<1
<1
<1
<2
< 2
<2
<1I
<2
<2
<*1
<1
<'1
<1
<1
<2
< 2
<:1
<14
< 4
<20
<6
<17
<4
<12
< 4
<13
< 4
< 22
<6
<11
<4
< 17
< 5
<19
<5
<20
<6
< 39
< 13 00 0
0 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION
TABLE C-I1.1 CONCENTRATIONS OFTRITIUM IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD Q-35 Q-36 01/09/09 - 01/09/09 04/10/09 - 04/10/09 07/10/09 - 07/10/09 10/09/09
- 10/09/09
< 172
< 182
< 130
< 175
< 175
< 181
< 136
< 187 MEAN C-3' 39 of 109
TABLE C-11.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUND WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD Q-35 01/09/09 - 01/09/
04/10/09 - 04/10/
07/10/09 - 07/10/
10/09/09 - 10/09/
Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 09 09 09 09 MEAN
<2
<1
<1
<4
<2
<1
<1
<4
<2
<2
<2
<4
<2
<1
<1
<3
<5
<4
<3
<7
<4
<3
<2
<9
<2
<1
<1
<3
<2
<1
<1
<4
<4
<3
<3
<7
<3
<2
<2
<8
<2
<2
<2
<4
<2
<2
<1
<4
<4
<3
<3
<7
<3
<3
<2
<7
< 12
< 14
<7
< 12
<8
< 13
<5
< 11
<2
<1
<1
<4
<1
<1
<1
<4
<2
<1
<1
<4
<2
<1
<1
<4
< 21
< 19
< 12
< 28
< 15
< 17
<8
< 27
<6
<6
<4
<-5
<6
<3
<8 Q-36 01/09/09 04/10/09 07/10/09 10/09/09 MEAN 01/09/09 04/10/09 07/10/09 10/09/09 0*
0
TABLE C-II1.1 CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 Q-24 Channel Catfish Common Carp Bigmouth Buffalo Common Carp 05/14/09 05/14/09 10/14/09 10/14/09
< 58
< 73
< 35
< 57
< 87
< 79
< 36
< 80
< 160
< 229
< 113
< 184
< 62
< 49
< 42
< 57
< 97
< 118
< 94
< 142
< 75
< 81
< 55
< 81
< 110
< 190
< 93
< 134
< 55
< 50
< 42
< 51
< 52
< 67
< 35
< 56
< 3760
< 3980
< 725
< 1000
< 1170
< 1000
< 154
< 321 MEAN
(
Q-29 Common Carp Largemouth Bass Bigmouth Buffalo Common Carp 05/14/09 05/14/09 10/14/09 10/14/09
< 54
< 36
< 51
< 53
< 75
< 48
< 63
< 64
< 149
< 130
< 145
< 175
< 49
< 32
< 50
< 56
< 107
< 72
< 133
< 106
< 87
< 59
< 74
< 64
< 120
< 112
< 118
< ill
< 44
< 32
< 45
< 48
< 47
< 35
< 52
< 51
< 3320
< 2130
< 891
< 985
< 1120
< 652
< 266
< 378 MEAN C
TABLE C-IV.1 STC COLLECTION PERIOD Q-39 05/25/09 10/22/09 MEAN Q-40 05/25/09 10/22/09 MEAN CONCENTRATIONS OF GAMMA EMITTERS IN SEDIMENT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/KG DRY +/- 2 SIGMA Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-1 34
<52
<58
< 109
<45
< 108
< 56
< 107
<37
< 19
< 19
< 50
< 13
< 27
< 23
< 33
< 11 Cs-137 112 +/- 47
< 25 Ba-140
< 777
< 266 La-140
< 189
< 45 112
< 68
< 22
< 81
< 23
< 184
< 42
< 61
< 21
< 160
< 51
< 98
< 25
< 141
< 60 496 +/- 74
< 35
< 17 64+/- 46 280 +/- 611
< 947
< 272
< 348
< 69 0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES
TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD GROUP I l
01/03/09 - 01/09/09 01/09/09 - 01/16/09 01/16/09 - 01/23/09 01/23/09 - 01/30/09 01/30/09 - 02/06/09 02/06/09 - 02/13/09 02/13/09 - 02/20/09 02/20/09 - 02/27/09 02/27/09 - 03/06/09 03/06/09 - 03/12/09 03/12/09 - 03/20/09 03/20/09 - 03/27/09 03/27/09 - 04/03/09 04/04/09 - 04/10/09 04/10/09 - 04/17/09 04/17/09 - 04/23/09 04/23/09-05/01/09 05/02/09 - 05/09/09 05/09/09 - 05/15/09 05/15/09 - 05/22/09 05/22/09 - 05/29/09 05/29/09 06/05/09 06/05/09 - 06/12/09 06/12/09 - 06/19/09 06/19/09 - 06/26/09 06/26/09 - 07/03/09 07/03/09 - 07/10/09 07/10/09 07/17/09 07/17/09 - 07/24/09 07/24/09-07/31/09 07/31/09 7 08/07/09 08/07/09 7 08/14/09 08/14/09 - 08/21/09 08/21/09 - 08/28/09 08/28/09 - 09/04/09 09/04/09 - 09/11/09 09/11/09
- 09/18/09 09/18/09 09/25/09 09/25/09 10/02/09 10/02/09. - 10/09/09 10/09/09 10/15/09 10/16/09 - 10/23/09 10/23/09 - 10/30/09 10/30/09 - 11/06/09 11/06/09.
11/13/09 11/15/09 11/20/09 11/20/09 - 11/27/09 11/27/09 - 12/04/09 12/04/09 - 12/11/09 12/11/09-12/18/09 12/19/09 - 12/26/09 12/26/09 - 01/02/10 Q-01 32 +/- 6 22 +/- 5 35 +/- 5 35 +/- 5 16 +/- 4 33 +/- 5 20 +/- 4 26 +/- 5 24 +/- 5 22 +/- 4 28 +/- 4 19 +/- 4 14 +/- 4 11 +/-4 16+/- 4 17 3
10 +/-4 24 +5 10 +/- 4 18 +/- 4 12 +/- 4 13 +/- 4 26 +/- 5 17 +/- 4 17 +/- 4 13 +/- 4 19 +/- 5 16 +/- 4 13 +/- 4 16 +/- 4 19 +/- 5 19 +/- 4 21 +/- 4 14 +/- 4 16 +/- 4 28 +/- 5 28 +/- 5 33 +/- 4 20 +/- 4 10 +/- 4 7+/-4 20 +/-4 17+/- 4 22 +/-4 14+/- 4 12+/- 5 23 +/- 4 25 +/- 4 33 +/- 5 36 +/- 4 33 +/- 5 33 +/- 5 Q-U2 36 +/- 6 31 +/- 5 19 +/- 4 35 +/- 5 15 +/- 4 28 +/- 5 21 +/- 4 30 +/- 5 23 +/- 5 24 +/- 5 21 +/- 4 14 +/- 4 17 +/- 4 16 +/- 4 21 +/- 4 17 +/- 3 10 +/- 4 21 +/- 4 11 +/-4 21 +4 10 4
14 +4 8+/-5 21 +/-4 17+/- 4 12 4
17+/- 4 16+/- 4 19+/- 4 19+/- 4 14 +/-4 16+/- 4 24 +/-5 13+/- 4 19+/- 4 30 +/-5 27 +/-5 28 +/-4 19+/- 4 5+/-3 17+/- 4 14+/- 4 14+/- 4 18 4
19 +/- 5 12 +/- 5 26 +/- 4 20 +/- 4 24 +/- 5 34 +/- 4 16 +/- 4 28 +/- 5 Q-03 31 +/- 6 30 +/- 5 34 +/- 5 36 +/- 5 20 +/- 4 29 +/- 5 20 +/- 4 30 +/- 5 22 +/- 5 20 +/- 4 21 +/- 4 21 +/- 4 14 +/- 4 15 +/- 4 18 +/- 4 18 +/- 4 8+/-3 20+/- 4 12+/- 4 17+/- 4 14+/- 4 15+/- 4
<7 20 +/-4 18+/- 4 14+/- 4 22 +/-5 18+/- 4 14+/- 4 11 +/-4 18+/- 5 20 +/-4 20 +/-4 13+/- 4 16+/- 4 27 +5 25 +/- 5 30 +/- 4 17 +/- 4 8+/-4 15+/- 4 14 4
16+/- 4 27 +4 17+/- 5 13 5
26 +/- 4 19 +/- 4 26 +/- 5 31 +/- 4 13 +/- 4 27 +/- 5 3
3 3
3 1
3 2
3 2
2 2
2 1
2 2
2 1
22 2
1 3
2 1
2 2
2 2
3 Q-04,-
Q-13 Q-16 7 +/-6 35 +/-5 40 +/-6 1 +/-5,,. 28+/- 5 27 +/- 5 7 +/-5 36 +/-5 34 +/- 5 9 +/-5:.
36+/-5
- 38-+/-5 8+/-4 18+/-4 22+/-5 2 +/-5 26 +/-5 33 +/- 5 1 +/-5 23+/-4 17+/-4 3+/-5 38+/-6 31 +/-5 5 +/-5., '22
+/
23-+/-'5.
0 +/-4-'
23 +/- 5 23 +/- 5
'6+4.
26 +/-4 23 +/-4
'1 4
21 +/-4 22 +/-4 6 +/-4 18 +/-4 17+/-44 3 +/-.4 15 +/-4 18 +/-4 0 +/-4 19 +/-4 21 +/-4 5+/-3 20+/-4 15+/-4 7 +/-4 12 +/-4 11 +/-4 0 +/
20 +/-4 21+/-4 3+/-4 9+/-4 9+/-4 8 +/-4' 16 +/-4 17+/-4 4 +/-4 17 +/-4 14 +/-4 3 +/-5 18 +/-4 18 +/-4 1 +/-5 10+/-5 8+/-5 9 +/-4 19 +/-4 17 +/-4 1 +/-5 13+/-4 18+/-5 4 +/-4 12 +/-4 13 4
1 +/-5 17+/-44, 15+/-4 8 +/-4:
13 +/- 4 16+/- 4 7+/-4 17+/-4 22+/-5 6 +/-4 b9 +/-4 15 +/-4 6+/-4 1.7 +/-5.
14 +/- 4 5 +/- 5 21 +/- 4 19-+/- 4 2 +/-5
.21
+/-4 23+/-5 9+/-4 17+/-4 14+/-4 7 +/-4 16 +/-4 17 +/-4 6 +/-.6 34 +/- 6 29 +/-5 3 +/-5 33 +/- 5 37 +/-5 0 +/-4 33 +/-4
,29 +/-4 7
4 20 +/-4 17 +/-4 9+/-4 11 +/-4 9+/-4 5
4 16+/-5 13+/-5 5 +/-4 19 +/-4 13 +/-4 9 +/-4 18 +/-4 12 +/-4 9
4 17 +/-4 19 +/-4 8+/-5 26+/-5 26+/-5 6 +/-6 16 +/-4 18+/-4 8 +/-4 33 +/-5 26+/-4 7 +/-4 25 +/-4 24 +/-4 8 +/-5 24 +/- 5 19 +/- 5 7 +/-4 35 +/-4 34 +/-.4 2 +/-5 41 +/- 7 40 +/-7 0 +/-5 32 +/-5 31.+/-5 GROUP II Q-37 35 +/- 6
.26 +/- 5 3ý3 +/- 5 36+/-5 16 +/-4 33 +/-'5 23 +/- 5 29 +/- 5
'18 +/- 4 24 +/- 5 22 +/- 4 20 +/-'4 11 +/-3 16 +/-'4 22 +/- 4 1.5 +/- 3 tl +/-4 24 +/-5
- 8 +/-4 19 +/-4 14+/- 4 15+/- 4
< 7-16 +/-4 21 +/-5 11 +/-4
.19+/-4 18 +/-4 17 +/-4 16+/- 4 19 "+/-'5 20 +/-4 18 +/- 4 16 +/- 4 15 +/- 4 27 +/- 5 27 +/- 5 27 +/- 4 17+/- 4 8 +/-3 13+/- 4 (1)
(1) 20 +/-4 15+/- 4 13+/- 5
.27 +/-4 22.+/- 4 27 +/-'5 32 +/-4 24 +/- 5 31 +/- 5 Q-38 33 +/- 6 29 +/- 5 30 +/- 5
,35 +/- 5
'17 +/- 4 26 +/- 4 19 +/- 4 31 +/- 5
.22+/-5 19 +/- 4 23 +/- 4
.18 +/- 4
.15 +/- 4 16 +/- 4 17 +/- 4 17 +/- 3 8+/-3 23 +/-4 8+/-4
.19 +/-4 16+/- 4 14 +/-4 15+/-5 16 +/-4 19 +/-5 11 +/-4 19 +/-4 13+/- 4 10+/- 4
.17 +/-4 16 +/- 5 20 +/-5 17+4 15 +/-4 15+/- 4 26 +/-5 30 +/-5 33 +/-4 15+/- 4 5+/-3 13+/- 4 15+/- 4 12+/- 4 21 +/-4 15+/-4 9+/-5 29 +/- 4 21 +/-4 26 +/- 5 35 +/-4 28 +/- 5 20 +/- 5 Q-41 37 +/- 5 25 +/- 5 39 +/- 5 39 +/- 5 16 +/- 4 26 +/- 5 11
+/-4 32 +/-5 17+/- 4 20 +/-5 21 4
19+/- 4
-11
+/- 5 13+/- 4 16 +/-4 18+/- 4 7+/-3 26 +/- 6 13 +/- 4 6+/-3 13+/- 4 13 +/-4
<.7
,18
+/- 4 "13+/- 4 7+/-3 14 4
,.12
+/-4 8+/-4
.14
+/- 4 13 +/- 4 19 +/- 4 20 +/- 4 15 +/- 4 18 +/- 4
..:30 +/- 5 29 +/- 5 31 +/- 4 21 +/- 4 10 +/- 4 16 +/- 5 11+/- 4 14 +/-4 17 +/-4 28 +/-5 8+/-4 24 +/- 4 25 +/- 4 15 +/- 5 34 +/- 4 36 +/- 8 26 +/- 10 I GROUP III Q-07 38 +/- 5 33 +/- 5 34 +/- 5 42 +/- 6 14 +/- 4 29 +/- 5 17+/- 4 28 +/-5 21 +/-5 22 +/-5 27 +/-4 21 +/-4 16+/- 4 15+/- 4 23 +/-4 23+/- 5 7+/-3 22 +/-4 6+/-3 17+/- 4 16+/- 4 17+/- 4
<7 21 +/-4 16+/- 5 21 +/-4 18 +/- 4 18 +/- 4 17 +/- 4 16 +/- 4 16 +/- 4 20 +/- 4 19 +/- 4 15 +/- 4 17 +/- 4 35 +/- 6 32 +/- 5 30 +/- 4 22 +/- 4 10 +/- 4 13 +/- 5 17 +/- 4 15 +/- 4 18 +/- 4 25 +/- 5 18+/-4 30 +/- 4 26 +/- 4 23 +/- 5 32 +/- 4 37 +/- 6 29 +/-5 MEAN 21 +/- 15 20 +/- 14 20 +/- 13 22 +/- 16 22 +/- 16 21 +/- 16 20 +/- 14 19 +/- 15 19 +/- 18 22 +/- 16
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-7 43 of 109
TABLE C-V.2 MONTHLY AND YEARLY MEAN VALUES OF GROSS BETA CONCENTRATIONS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA GROUP I - NEAR-SITE LOCATIONS GROUP II - FAR-FIELD LOCATIONS GROUP III - CONTROL LOCATIONS COLLECTION PERIOD MIN MAX MEAN+/-:
2SD COLLECTION PERIOD MIN MAX MEAN+/-
2SD COLLECTION PERIOD MIN MAX MEAN+
2SD 01/03/09 01/30/09 02/27/09 04/04/09 04/25/09 05/29/09 07/03/09 07/31/09 08/28/09 10/02/09 10/23/09 11/27/09 1 U II)UIUu 02/27/09 04/04/09 04/25/09 05/29/09 07/03/09 07/31/09 08/28/09 10/02/09 10/23/09 11/27/09 01/02/10 15 14 11 7
8 11 9
16 5
12 13 au 33 28 21 24 26 22 25 36 20 29 36 3o 25 20 16
- 15~
16
ý17 18
- 25.
12 19 27
+/-13
+/-8
+/-5
+10
+/-9
+6
+/-9
+13
+/-9
+11
+/-.12 v IIUOIUu 01/30/09 02/27/09 04/04/09 04/25/09 05/29/09
-07/03/09 07/31/09 08/28/09 10/02/09 10/23/09 11/27/09
- 02/27/09
- 04/04/09
- 04/25/09
- 05/29/09
- 07/03/09
-. 07/31/09
-' 08/28/09
- 10/02/09
- 10/23/09 11/27/09
- 01/02/10 LU3 11 11 7
6 7
8..
13 15 5
8 15
.+v 38 26 22 26 21
.22 23 37 19 33 41 34 +/- 9 24 +/- 15 20 +/- 8 16 7
15+
11 15 8
15 +/- 7 18 5
25 +/-.14 13 +/- 7 20 +/- 14 28 +/- 13 01/03109 -
01/30/09 -
-"02/27/09 -
04/04/09 -
04/25/09 -
05/29/09 -
07/03/09 -
07/31/09 -
08/28/09 -
10/02/09 -
10/23/09 -
11/27/09 -
01/30/09 02/27/09 04/04/09 04/25/09 05/29/09 07/03/09 07/31/09 08/28/09 10/02/09 10/23/09 11/27/09 01/02/10 33 14 16 7
6 16 16 15 17.
10 18 23 42 29 27 23 22 21 18 20 35 17 30 37 37 +/- 8 22 +/- 15 821
+/-8 17 +/- 151 15 +/- 13 19 +/-:5 17 +/-;2 17 +/- 5 27 +/- '15.
14 +/-+5 23 +/- *12 30 +/-'1;i, 22 +/--16 80 01/03/09 - 01/02/10 5
39 20 +/- 15 01/02/09 - 01/02/10 5
41 20 +/- 16 01/02/09 -
01/01/10 6
42 I
0
- THE MEAN AND 2 STANDARD DEVIATION VALUES ARE CALCULATED USING THE POSITIVE VALUES
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER+ 2 SIGMA STC COLLECTION PERIOD Q-01 01/03/09 - 04/04/09 04/04/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/02/10 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140 MEAN C)
Q-02 01/03/09 - 04/04/09 04/04/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/02/10 MEAN Q-03 01/03/09 - 04/04/09 04/04/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/02/10 MEAN Q-04 01/03/09 0- 4/04/09 04/04/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/02/10
<3
<4
<4
<5
<3
<3
<4
<3
<3
<4
<5
<4
<5
< 13
<6
<5
<5
<7
<8
<4
< 12
< 36
< 22
< 8*
< 14
< 38
< 20
< 10
< 16
< 37
< 27
< 12
<2
<4
<4
<.4'
<4
<2
<4
<3
<6
< 14
< 10
< 10
<9
<7
< 11
< 10
<5
< 16
<7
< 5'
<4
<8
<9
<3
<7
< 25
< 11
<-8
<9
< 17
< 15
<:7-"
<8
< 18
< 16
<8
< 7
< 33
<7
<4
<3
<5
<5
< 6'
<4
<3
<5
<3
<3
<3
<5
<4
<3
<4.
<3
<3
<2
<4
<3
<5
<4
<2
<4
< 3
<3
<3
<4
< 3*
< 2
<-4
<2
<2
< 134
< 15500
< 1110
< 71
< 165
< 8420
< 1290
< 46ý
- 192
< 13100
< 1420
< 55
< 59
< 5160
< 353
< 19
< 73
< 4200
< 528
<17.
< 56
< 5110
< 527
< 20
- <50
< 6600
< 353
< 19
<5
< 11
<9
<4
<4
<3
<4
<4
< 3
<.3
<2
< 2
<7
< 10
< 13
<5
<4
< 11
< 10
<4
<4
< 14
<6
<3
<3
<3
< 9
<5
< 13
<;45
<3
<5
<19
<3.
<4
-7
<6
< 10
<5
.<8
- <129
< 14300
< 926
< 62 MEAN PC 0/
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD "
Mn-54 Co-58 FeL59 Co-60 Zný65 Nb-95 Zrý95 Cs-134 Cs-1 37 Ba-140 La-140 0*
Q-07 01/09/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10 MEAN Q-13 01/09/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10 MEAN Q-16 01/09/09 - 04/03/09 04/03/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/01/10 MEAN Q-37 01/03/09 - 04/04/09 04/04/09 - 07/03/09 07/03/09 - 10/02/09 10/02/09 - 01/02/10
<3
<3
<5
<2
<6
<9
<9
<2
< 18
< 37
< 28
< 5'
<3
<3
<6
<2
<8
<11
<11
< 3
<5
<5
< 10
<3
< 10
< 13
< 16
<-3
<3
<3
<5
<2
<2
<3
<5
<2
<3
<4
<13
<2
<7
<5
<7
<3
<3
<137
<4
<3
<3
<4
<3
<3
<3
<3
<3
< 3
< 11
<6
<.5
<7
<6
<6
<3
<4 9
<5
< 56
< 13
< 10
< 15
< 39
< 22
<8
<3
<3
"< 3
<3
<2
<3
<5
<9
<7
<8
<11
<7
<9 c< 6
< 11
<7
<4
<5
<9
<7
<4
< 20
<9
<'9
<9
< 14
< 12
< 7
<3
<3
<-4
<4
<2
<4
<2
<2
<2
<:3
<3
<2
<3
<4
< 13300
< 683
< 73
< 244
< 9850
< 1030
< 33
< 195
< 9920
< 1280
< 38
< 74
< 3660
< 516
< 10
< 62
< 4730
< 320
<-23
< 30
< 2700
< 496
< 23
< 12
< 34
< 16 S<6
<7
<4
<8
<3
<3
<172
< 4
<3
< 13
<9
< 14
<5
< 28
<9
.<4,
<3
.< 3
<2
'< 13800
< 699
< 58
< 4990
< 316
< 18
<4
<6' -
<4
<5
<2
<3
<43 MEAN ON 0
0
TABLE C-V.3 CONCENTRATIONS OF GAMMA EMITTERS IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS.IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA STC COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-1'i40 5
Q-38 01/03/09 04/04/09 07/03/09-10/02/09 MEAN Q-41 01109109 04/03/09 07/03/09 10/02/09 MEAN
- 04/04/09
- 07/03/09
-. 10/02/09
- 01/02/10
<2
<2
<3
<3
<4
<7
<6
<.4
- < 10
< 36
,< 18,
< 12
<3
<2
<3
<4
< 5
<7
<9
< 7
<4
<5
<8
<5
<7
< 12
< 12
'<8
< 23
<.12
'<10
<3
<3
<3
<3
<3
<4
<4
<4
<2
<2
<3
<4
<2
<3
<43
,<4
< 156
< 9230,
< 1100,
<69
< 101
< 12200
< 996
< 68
< 38
< ;290
< 265
< 26
< 43
< 3530
< 367-
< 28
- 04/10/09
- 07/03/09
- 10/02/09
- 01/01/10
<3
<5
<4
<5
< 5
< 10
<*6
< 5
< 13
< 50
< 20
< 11
<4
<5
<3
< 5
'< 9
< 13 A 10
"< 9
<5-
< 12
<57-
< 5 0
TABLE C-VI-.1 CONCENTRATIONS OF 1-131 IN AIRIODINE SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF E-3 PCI/CU METER +/- 2 SIGMA COLLECTION PERIOD Q-01 01/02/09 - 01/09/09
< 33 01/09/09 - 01/16/09
< 29 01/16/09 - 01/23/09
< 63 01/23/09 - 01/30/09
< 35 01/30/09 - 02/06/09
< 56 02/06/09 - 02/13/09
< 9 02/13/09 - 02/20/09
< 35 02/20/09 - 02/27/09
< 10 02/27/09 - 03/06/09
< 16 03/06/09 - 03/12/09
< 26 03/12/09 - 03/20/09
< 23 03/20/09 - 03/27/09
< 15 03/27/09 - 04/03/09
< 22 04/03/09 - 04/10/09
< 40 04/10/09 - 04/17/09
< 19 04/17/09 - 04/23/09
< 16 04/23/09 - 05/01/09
< 26 05/02/09 - 05/15/09
< 34 05/15/09 - 05/22/09
< 31 05/22/09 - 05/29/09
< 27 05/29/09 - 06/05/09
< 20 06/05/09 - 06/12/09
< 57 06/12/09 - 06/19/09
< 50 06/19/09 - 06/26/09
< 64 06/26/09 - 07/03/09
< 24 07/03/09 - 07/10/09
< 34 07/10/09 - 07/17/09
< 37 07/17/09 - 07/24/09
< 31 07/24/09 - 07/31/09
< 22 07/31/09 - 08/07/09
< 29 08/07/09 - 08/14/09
< 22 08/14/09 - 08/21/09
< 20 08/21/09 - 08/28/09
< 44 08/28/09 - 09/04/09
< 22 09/04/09 - 09/11/09
< 37 09/11/09 - 09/18/09
< 42 09/18/09 - 09/25/09
< 55 09/25/09 - 10/02/09
< 11 10/02/09 - 10/09/09
< 24 10/09/09 - 10/15/09
< 28 10/15/09 - 10/22/09
< 32 10/22/09 - 10/30/09
< 62 10/30/09 - 11/06/09
< 66 11/08/09 - 11/20/09
< 26 11/20/09 - 11/27/09
< 44 11/27/09 - 12/04/09
< 23 12/04/09 - 12/11/09
< 50 12/11/09 - 12/18/09
< 60 12/18/09 - 12/24/09
< 62 12/26/09 - 01/02/10
< 24 GROUPI GROUP II Q-02
< 59
< 53
< 38
< 65
< 56
< 16
< 35
< 18
< 16
< 46
< 45
< 28
< 43
< 50
< 34
< 37
< 32
< 62
< 59
< 49
< 36
< 25
< 50
< 64
< 42
< 32
< 36
< 54
< 21
< 37
< 38
< 34
< 42
< 22
< 64
< 66
< 53
< 20
< 24
< 49
< 31
< 32
< 64
< 58
< 43
< 52
< 49
< 58
< 60
< 55 Q-03
< 59
< 53
< 63
< 65
< 28
< 16
< 35
< 18
< 16
< 46
< 45
< 28
< 43
< 50
< 34
< 37
< 32
< 62
< 43
< 49
< 36
< 47
< 50
< 35
< 42
< 32
< 36
< 56
< 21
< 38
< 39
< 35
< 44
< 22
< 66
< 68
< 55
< 21
< 13
< 51
< 18
< 60
< 66
< 60
< 44
< 53
< 50
< 60
< 62
< 57
< 61t
< 55
< 65
< 67
< 58
< 16
< 22
< 19
< 16
< 48
< 47
< 29
< 45
< 52
< 35
< 38
< 33
< 64
< 44-
< 51
< 37
< 48
< 51
< 66
< 43
< 18
< 37
< 55.
< 22
< 38
< 39
< 35
< 44.
< 22
< 66
< 65
< 55
< 21.
< 24
< 50
< 32
< 60
< 66
< 60
< 59
< 53
< 50
< 60
< 62
< 57 Q-13
< 40
< 48
< 33
< 50
< 35
< 35
< 19
<8
<9
-< 38
< 25
< 39
< 51
< 27
- 33
< 34
< 40
< 43
< 26
< 37
< 36
< 17
<34
< 31
< 40
< 21
< 62
< 60
< 26
< 25
< 41
< 45
< 19
< 34
< 57
< 22
< 55
- 29
< 34
< 30
< 36
< 53
< 25
< 35
< 28
< 51
< 60
< 23
< 34
< 51 Q-16 Q037
< 52
< 64
< 60
< 56
< 62
<64
< 65
< 65
< 66
< 65
< 63
< 59
< 37
< 35
< 16
< 16
< 17
< 17-
< 50
< '49
< 39
< 38
< 48
< 49
< 35
< 41
< 50
< 53
< 34
< 29
< 65
< 42
< 40
< 40
< 44
< 48
< 63.
< 63
< 51
<.51
< 47
< 45
< 17
< 17
< 36
< 36
< 56
<*56
< 18
<40 -
< 51
<.49
< 63
<,.59
< 62
<,61
< 26
<'26
< 25
< 24
< 41
< 42
< 19
<-45
< 44
<ý44
< 14
<133
< 56
<':56
< 50
<'51
< 33
< 52
< 29
<"30
< 34
<'34
< 54
<l41
< 36 (1)
< 53 (1).
< 45
< 32
< 35
<22
< 65
< 65
< 51
< 23
< 59
< 49
< 53
< 49
< 58
< 39
< 51
<57 IGROUP III Q-38 Q-41
< 64
< 53
< 56
< 60
< 64
< 62
< 65
< 66
< 65
< 66
- 59
< 62
< 35
< 36
< 16
< 16
< 17
< 17
< 49
< 50
< 38
'-<40
< 49
< 48
< 40
< 62
< 53
. < 50
< 36
, < 34
< 42
< 65
< 22
< 40
< 48 37
< 63
< 63
< 51
< 51
< 46
< 47
<'12
< 57
< 37
< 20
< 58
< 59
<*41
< 41
< 51
< 51
< 61
< 27
<-35
< 62
<26
.< 14
< 14
<25
< 19
<41
< 47
<46
< 45
< 44
< 34
< 33
< 58
"<24
< 53
'<50
< 53
< 55
<13
<29
< 15
< 34
<42
< 54
< 36
< 36
< 56
< 53
< 32
< 45
< 52
< 35
< 65
< 65
< 54
< 51
< 49
< 31
< 49
< 53
< 38
< 69
< 57
< 52 Q-07
< 49
< 57
< 62
< 66
< 56
< 17
< 37
< 18
< 11
< 47
< 47
< 28
< 55
< 47
< 33
< 57
< 33
< 57
< 44
< 50
< 37
< 49
< 21
< 68
< 43
< 33
< 21
< 54
< 15
< 38
< 37
< 35
< 24
< 12
< 65
< 65
< 35
< 20
< 24
< 65
< 33
< 57
< 52
< 40
< 44
< 52
< 34
< 36
< 39
< 51 MEAN (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-12 48 of 109
TABLE C-VII.1 CONCENTRATIONS OF 1-131 IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA COLLECTION PERIOD 01/03/09 02/06/09 03/06/09 04/04/09 05/02/09 05/15/09 05/29/09 06/12/09 06/26/09 07/10/09 07/24/09 08/07/09 08/21/09 09/04/09 09/18/09 10/02/09 10/16/09 10/30/09 11/13/09 12/04/09 INDICATOR FARM 0Q26
< 0.6
< 0.7
< 0.6
< 0.5
< 0.5
< 0.6
< 0.6
< 0.9
<0.6
< 0.7
< 0.7
< 0.5
< 0.8
< 0.9
< 0.7
< 0.5
- < 0.6
< 0.8
< 0.6
< 0.8 MEAN C-13 49 of 109
TABLE C-VII.2 CONCENTRATIONS OF GAMMA EMITTERS IN MILK SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD Q-26 01/03/09 02/06/09 03/06/09 04/04/09 05/02/09 05/15/09 05/29/09 06/12/09 06/26/09 07/10/09 07/24/09 08/07/09 08/21/09 09/04/09 09/18/09 10/02/09 10/16/09 10/30/09 11/13/09 12/04/09 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 Cs-134 Cs-137 Ba-140 La-140
<4
<5
<5
<6
<2
<2
<7
<3
<4
<4
<5
<7
<7
<5
<5
<4
<4
<5
<6
<4
<4
<5
<6
<7
<3
<2
<7
<4
<4
<5
<5
<7
<9
<5
<4
<4
<5
<5
<7
<5
< 11
< 10
< 13
< 14
<8
<7
< 18
< 10
< 11
< 10
< 12
< 16
< 20
< 14
< 11
< 10
<9
< 12
< 15
< 12
<4
<4
<5
<6
<2
<2
<8
<3
<5
<4
<5
<7
< 12
<6
<5
<4
<5
<5
<6
<4
<9
< 10
< 12
< 13
<5
<5
< 20
<7
<9
< 10
< 11
< 15
< 19
< 13
< 10
< 10
< 10
< 11
< 14
<9
<4
<6
<6
<6
<3
<2
<9
<4
<4
<5
<6
<7
<8
<5
<5
<4,
<5
<5
<7
<5
<7
<9
< 10
< 12
<5
<4
< 12
<6
<8
<9
< 10
< 11
< 14
< 11
<8
<7
<8
< 10
< 11
<9
<3
<5
<5
<5
<2
<2
<7
<3
<4
<4
<4
<6
<9
<5
<4
<4
<4
<4
<5
<4
<4
<5
<6
<6
<2
<2
<8
<3
<4
<5
<5
<6
<8
<6
<5
<4
<5
<5
<5
<5
< 36
< 37
< 58
< 49
< 54
< 31
< 45
< 38
< 36
< 41
< 36
< 36
< 53
<34
< 22
< 25
< 24
< 41
< 46
< 38
<11
< 14
<9
< 14
< 14
<<9
< 15
<13
< 11
< 12,
" 12
< 13
<11
< 12
< 6
<7
.< 10
<12
<15
<12 "
MEAN 0h 0
TABLE C-VIII.1 CONCENTRATIONS OF GAMMA EMITTERS IN FOOD PRODUCT SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/KG WET +/- 2 SIGMA STC COLLECTION PERIOD Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 -
La-140 Q-CONTROL Potatoes Rhubarb Leaves 07/08/09 07/08/09 MEAN
< 12
< 11
< 34
< 12
< 35
< 14
< 24
< 51
< 10
< 13
< 99
<29
< 11
< 13
< 29
< 12
< 28
< 13
< 25
< 54
< 12
< 13
< 124
<:24
< 12
< 14
< 31
< 11
<24
< 14
< 22
< 54
< 11
< 14 3
<26
< 14
< 15
< 34
< 11
< 25
< 14
< 24
< 55
< 11
< 13
< I11
< 29 Q-QUAD 1 Lettuce Potatoes 07/08/09 07/08/09 MEAN Q-QUAD 2 Potatoes Rhubarb Leaves 07/08/09 07/08/09
- 11
< 12
<32
< 12
<25
< 12
<25
<58
< 11
<13
< 92
< 28
< 8
< 9
< 26
< 10
< 19
< 11
< 19
< 39
< 8
< 9
< 78
<.23 MEAN Q-QUAD 3 Lettuce Sunchokes 07/08/09 07/08/09
< 13
< 15
< 32
<<14
<17 26
< 54
< 13
< 13.
< 118
< 31
<14.
< 14
<, 38
< 14,
< 36
< 17
.< 30
< 51 12
< 1. 17
< 1118
<'25 MEAN Q-QUAD 4 Potatoes 07/08/09 Rhubarb Leaves 07/08/09
< 17
< 16
< 40
< 15
< 35
< 18
< 30
< 56
< 13
< 17
< 117
< 29
< 15
< 15
< 44
< 18
< 35
< 15
< 28
< 58
< 13
< 15
< 132
< 39 0/
0 MEAN
TABLE C-IX.1 QUARTERLY TLD RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2009 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 21.5 +/-,3.8 23 21 19 23 Q-01-2 22.0 +/- 2.8 23 22 20 23 Q-02-1 22.5 +/- 4.2 25 22 20 23 Q-02-2 20.8 +/- 4.1 21 21 18 23 Q-03-1 19.5 +/- 3.5 21 18 18 21 Q-03-2 20.8 +/- 3.4 21 19 20 23 Q-04-1 22.8 +/- 6.2 23 21 20 2.7 Q-04-2 22.0 +/- 4.6 24 20 20 24 Q-07-1 21.3 +/- 4.1 23 20 19
'23, Q-07-2 22.0 +/- 4.9 23 20 20 25.
Q-13-1 22.3 +/- 3.1 22 (1) 21 24 Q-13-2 22.0 +/- 5.3 23 (1) 19 24 Q-16-1 20.8 +/- 3.0 22 19 20
- 22 Q-16-2 20.5 +/- 3.5 20 19 20 23 Q-37-1 22.5 +/- 5.3 26 21 20 23 Q-37-2 22.0,+/- 2.8 23 22 20 23 Q-38-1 23.0 +/- 2.3 24 22 22 24 Q-38-2 23.5 +/- 5.3 24 22 21 27' Q-41-1 20.3 +/- 4.6 (1) 19 19
.23.
Q-41-2 20.0 +/- 5.3 (1) 19 18 23 Q-101-1 21.5 +/- 5.0 21 19 2'1 25 Q-101-2 22.3 +/- 7.5 27 21 18 23 Q-102-1 22.3 +/- 4.4 25 21 20 23 Q-102-3 22.3 +/- 4.4 24 23 19 23 Q-103-1 20.8 +/- 6.2 21 19 18 25, Q-103-2 22.0 +/- 1.6 22 22 21 23 Q-104-1 20.8 +/- 4.1 22 19 19 23 Q-104-2 21.5 +/- 6.0 23 19 19 25 Q-105-1 21.0 +/- 2.8 22 19 21 22 Q-105-2 20.5.+/- 5.0 20 18 20 24 Q-106-2 21.0, + 2.3 22 20 20 22 Q-106-3 21.5 +/- 5.3 22 19 20 25 Q-107-2 22.0 +/- 5.2 23 21 19 25 Q-107-3 20.8 +/- 3.4 21 20 19 23 Q-108-1 21.3 +/- 5.3
-21 20 19 25 Q-108-2 20.8 +/- 7.0 22 19 17 25 Q-109-1 22.0 +/- 4.3 22 21 20 25.
Q-109-2 21.3 +/- 4.4 24 20 19 22 Q-111-1 23.8 +/- 3.4 24 23 26 22 Q-111-2 21.3 +/- 3.0 22 20 20 23 Q-112-1 21.5 +/- 2.6 23 21 20 22 Q-112-2 20.3 +/- 1.9 21 19 20 21 Q-113-1 20.5 +/- 2.6 21 20 19 22 Q-113-2 19.5 +/- 2.6 20 19 18 21 Q-114-1 20.0 +/- 5.4 19 19 18 24-Q-114-2 22.8 +/- 5.7 25 19 22 25 Q-115-1 20.8 +/- 4.4 22 18 20 23 Q-115-2 21.3 +/- 5.7 22 19 19 25 (1) SEE PROGRAM EXCEPTIONS SECTION FOR EXPLANATION C-16 52 of 109
TABLE C-IX.1 STATION CODE QUARTERLY TLD RESULTS FOR QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF MILLI-ROETGEN/QUARTER +/-2 STANDARD DEVIATIONS MEAN,,
+/- 2 S.D:
JAN-MAR, APR-JUN JUL - SEP OCT - DEC Q-116-1 Q-116-3.
Q-201 -1 QG201-2 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 23.0 21:.5 21.8 21.8 20.3 22.0 22.8 25.0 23.0 25.0 26.5 24.8 23.5 22.0 23.3 22.8 22.0 22.8 24.5 21.5 23.8 22.5 20.0 24.3 24.8 22.8 21.0 22.8 20.3 21.5 24.5 24.8 22.5 23.5 23.5
+/- 5.7
+/-,5.3
+/- 3.0
+/- '4.7
+/- 4.4
+/- 0.0
+/-.6.0
+/- 6.3
+/- 3.7
+/- 7.1
+/- 3.5
+/- 6.6
+/- 5.0
+/- 6.3
+4.1
+ 1.0
+ 5.7
+/-+4.4
+/- 4.8
+/- 3.8
+/- 4.4
+/-*2.6
+/- 3.7
+/- 1.9
+/- 1.0
+/- 1.9 i+4.3
+/-6:2
+/- 1.9
+/- 2.6
+/- 2.6
+/- 5.5
+/- 3.5
+/- 4.8
+/- 3.5 27
22 23 22 21 22 26 26 24 25 25 28 23' 23 23 23 22 24
.24 22 26 23 22 25 25 22 S
22 :
27'
'21 22 25 23 24 26 25 21 19 20 20 19 22 22 22 21 22 26 23 23 20 21 22 20 22 23 20 23 22 18 23 25 22 21 21 20 21
.23 26.
21 21 22 21 20 21 S20 18 22 19 23 22 23 29 21 21 19 23 23 20 20 23 20 21 21 19 24 25 23
- 18 20
.19 20 m
-24..-
22 21 22 22 23 25 23 S 25 23 22 24 29 25 30 26 27 27 26 26 23 26 25
- 28 24 25 24 21 25 24 24 23 23 21 23 26 28 24 25 25 C-17 53 of 109
TABLE C-IX.2 MEAN QUARTERLY TLD RESULTS FOR THE INNER RING, OUTER RING, OTHER AND CONTROL LOCATION FOR QUAD CITIES NUCLEAR POWER STATION, 2009
' I....
- j' RESULTS IN UNITS OF MILLIkROETGEN/QUARTER +/-2 STANDARD DEVIATIONS OF THE STATION DATA COLLECTION PERIOD INNER RING
+/-2 S.D.
OUTER RING OTHER CONTROL JAN-MAR APR-JUN JUL-SEP OCT-DEC 22.4 +/- 3.7 19.9 +/- 2.6 19.7 +/- 3.2 23.5 +/- 2.7 23.8 +/- 3.6 21.7 +/- 3.5 21.5 +/- 4.5 24.8 +/- 4.2 22.8 +/- 3.2
.20.4 +/- 2.8 19.7 +/- 2.1 23.5.+/- 2.9 23.0 +/- 0.0 20.0 +/- 0.0 19.5 +/-- 1.4 24.0 +/- 2.8 TABLE C-IX.3
SUMMARY
OF THE AMBIENT DOSIMETRY PROGRAM FOR QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF MILLI-ROENTGEN/QUARTER LOCATION INNER RING OUTER RING OTHER CONTROL SAMPLES PERIOD ANALYZED MINIMUM 120 17 132 18 68 18 8
19 PERIOD MAXIMUM 27 30 27 25 PERIOD MEAN
+/-+2 S.D.
21.4 +/- 4.4 22.9 +/- 4.8 21.6 +/- 4.2
.21.6 +/- 4.3 INNER RING STATIONS - Q-101-1, Q-101-2, Q-102-1, Q-102-3, Q-10311, Q-103-2, Q-104-1, C-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-11-3-1, 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, 0-211-2, 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, Q-38-1, Q-38-2, Q-41-1, Q-41-2 CONTROL STATIONS - Q-07-1, Q-07-2 C718 54 of 109
FIGURE C.-
SSurface Water;- Gross Beta'- Stations' Q-33 and Q-34 (C)
Collected,inlthe Viciinity of QCNPS, 2000- 2004 Q-33 Cordova 12.0 r No samples; water frozen.
10.0 -1 No samples; water frozen.
8.0+:
I 6.0+/-
4,0-2.0 0.0 i 01-01-00 I
I I
12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 Q-34 (C) Camanche 10.0 8.0 6.0 No samples; water frozen.
0J UJ 2.0- K no 4
I I
01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 C-19 55 of 109
FIGURE C-1, (cont.)
Surface Water - Gross Beta - Stations Q-33 and Q-34 (C)
Collected in the, Viciniity of QCNPS,,2005,- 2009 Q-33 Cordova 12.0 T 10.0 +
8.0 +
.-J 0.
6.0 +
4.0 +
2.0 an J I
I I
I 12-01-04 12-07-05 12-13-06 12-19-07 12-24-08 12-30-09 Q-34 (C) Camanche 12.0 -
10.0 -
8.0 -
-L 0.
6.0 +
4.0 -
2.0 +
n0.0 I
I I
I I
12-01-04 12-07-05 12-13-06 12-19-07 12-24-08 12-30-09 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-20 56 of 109
- ý FIGURE C-2 Surface Water - Tritium.- Stations Q-33 and Q-34 (C) 1 Coected in the Vicinity of QCNPS, 2000 - 2004 Q-33 Coyrdova 500 -
400 -
300
_J 200 4-100 0+
-100 4 I
01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04
,_Q.34 (9C),Camanche 500 -r 400-300+
.J cl 200-100 +
0
-100 1 I
01-01-00 12-31-00 12-31-01 l
12-31-02 12-31-03 12-30-04 C-21 57 of 109
FIGURE C-2 (cont.)
Surface Water-Tritium - Stations Q-33 and Q-34J(C)
Collected in the Vicinity of QCNPS, 2005 - 2009 Q-33 Cordova 500 400 300 L.
2 CL 200 1UU 0 1 03-01-05 02-17-06 02'05-07 01-24-08 01-11-09 12-30-09 Q-`34 (C)Camanche 500 T 400 +
300 +
,J 0.
200 100 -
0 i
i i
i ii 03-01-05 02-17-06 02-05-07 01-24-08 01-11-09 12-30-09 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-22 58 of 109
FIGURE C-3 S*G'round Water - Tritium -.Station's Q-35 and Q-36 Coilected in the Vicinityeof QCNPS,ý 2000 2004 Q-35 McMillan Well 500 400 300
-J 200 100
.X 0-
-100-
-200 I
I 01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 Q,-36Cqrdova Well 500 400 300 200 100-
-100
-200 I
I I
01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 C-23 59 of 109
FIGURE.C-3 (cont.)
Ground Water - Tritium - Stations Q-35 and Q-36 Collected in the Vicinity of QCNPS,:,2005w-2009 Q-35 McMillan Well 500 400 300 200 100
-J 0.
--- I -
V
ý 0
03-31-05 03-07-06 02-11-07 01-18-08 12-24-08
ý 11-30-09 Q-36 Cordova Well 500 T 400 +
300 +
-J C.)
0.
200 100
/-
o 4I-03-31-05 03-07-06 02-11-07 01-18-08 12-24-08 11-30-09 DUE TO VENDOR CHANGE, < VALUES ARE LLD VALUES JANUARY THROUGH JUNE 2005 AND MDC VALUES AFTER JULY 2005 C-24 60 of 109
FIGURE C-4 AirParticulates - Gross Beta-Stations Q-01 and Q-02 C"ollected 'in the Vicinity of QCNPS, 2000 - 2004 Q-01 Onsite No. 1 3
10.0 8.0 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 Q-02 Onsite No. 2 10.0 8.0 0.
CLl 9us 6.0 4C0 2.0 0.0
-t.
01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 C-25 61 of 109
FIGURE C-4 (cont.)
Air Particulates.- Gross Beta-Stations Q-01 and Q-02 Collected in the Vicinity 0f QCNPS, :2005,-72009 Q-01 Onsite No. 1 60.0 50.0 40.0 E
- 0. 30.0 Cl9 Lu o
20.0
.. W 10.0 10.0 01-07-05 01-07-06 01-07-07 01-07-08 01-06-09 01-06-10 Station Q-01 lost power 10-07 10-21-05.
Q-02 Onsite No.02 E
0.
CL 9
Lu 012 60.0 50.0 40.0 30.0 20.0 10.0 0.07-01-07-05 01-07-06 01-07-07 01-07-08 01-06-09 01-06-10 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-26 62 of 109
FIGURE C-5 Air'Particulates "'Gross Beta-Stations Q-03 and Q-04 Ciollecited in the Vicinity of QCNPS,-2000 - 2004 Q-03 Onsite No. 3 10.0 8-0 E
C N,
6.0 4.0 2.0 0.0 01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 Q-04 Nitrin 10.0 8.0 6.0 4 V 2.O 0.0 1 1
01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 C-27 63 of 109
FIGURE C-5 (cont.)
Air Particulates - Gross Beta-Stations Q-03 and Q-04 Collected in the Vicinity of QCNPS, 2005 - 2009 Q-03 Onsite No. 3 60.0 50.0 40.0 E
6 0L 30.0 M9 ED 20.0 10.0 0.0 01-07-05 01-07-06 01-07'07 01-07-08 01-06-09 '
01-06-10 Q,04 Nitrin 60.0 50.0 40.0
- 0. 30.0 9
CD 20.0 10.0 0.0 01-07-05 01-07-06 01-07-07 01-07-08 01-06-09 01-06-10 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-28 64 of 109
FIGURE C-6 Air Particulates - Gross. Beta-Stations Q-07 (C)
ý'Colledcted,inthe Vicinity of QCNPS, -2000 2009 Q-07 (C) Clinton 10.0 8.0 60.-
0 4,0 1h, 01-01-00 12-31-00 12-31-01 12-31-02 12-31-03 12-30-04 Q-07 (C) Clinton en CL w0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 01-07-05 01-07-06 01-07-07 01-07-08 01-06-09 01-06-10 DUE TO VENDOR CHANGE IN 2005, THE REPORTED UNITS CHANGED FROM E-02 PCI/M3 TO E-03 PCI/M3 C-29 65 of 109
, FIGURE C-7 Air Particulates - Gross Beta-, Stations Q-13 and Q-16 Collected in the. Vicinity, f QCNPS, 2005 -2009 Q-13 Princeton mE a.
=0 60.0 50.0 40.0 30.0 20.0 10.0 0.0 1
07-08-05 06-01-06 04-25-07 03-18-08 02-09-09 01-03-10 Q-16 Princeton 60.0 50.0 40.0 30.0 20.0 10.0 0.0 07-08-05 06-01-06 04-25-07 03-18-08 02-09-09 01-03-10 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 C-30 66 of 109
FIGURE C-8 Air Particulates - Gross Beta-Stations Q-37 and Q-38 Collected in the Vicinity of QCNPS, 2005 - 2009 Q-37 Meredosia Road 60.0 50.0 40.0
- 0. 30.0 9
o 20.0 10.0 0.0 i
07-08-05 06-01-06 04-25-07 03-18-08 02-09-09 01-03-10 STATION Q-37 YEILDED AN INSUFFICIENT RUN TIME FOR SAMPLE TO BE OBTAINED 10/23/09 - 10/30/09 Q-38 Fuller Road 60.0 50.0 M 40.0 0L 30.0 9
o 20.0 10.0 0.0 I
07-08-05 06-01-06 04-25-07 03-18-08 02-09-09 01-03-10 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 C-31 67 of 109
FIGURE C-9 Air Particulates - Gross Beta-Stations Q-41 Collected in the Vicinity of QCNPS, 2009,,:ý Q-41 Camanche 50.0 40.0 30.0 C-)
0.
9 20.0 10.
0 10.0 0.0 I
i I
I I
01-03-09 03-05-09' 05-05-09 07-05-09 09-04-09
'11-04-09 01-04-10 C-32 68 of 109
APPENDIX D INTER-LABORATORY COMPARISON PROGRAM 69 of 109
TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 1 OF 3)
Identification Reported Known Ratio (c)
Month/Year Number Matrix Nuclide Units Value (a)
Value (b)
TBE/Analytics Evaluation (d)
March 2009 E6533-396 E6534-396 E6536-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L 102 97.7 pCi/L 14.9 15.6 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi "pCi' pCi pCi pCi pCi 66.7 87.5 275 82.0 111 114 136 112 160 142 120 385 113 149 153 155 118 195 190 79.3 94.9 305 93.7 111 119 128 99.9 156 142 115 371 114 135 145 155 121 189 173 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co'-58 Mn-54 Fe-59 Zn-65 Co-60 June 2009 E6535-396 E6742-396 E6743-396 Charcoal 1-131 pCi Milk Sr-89 pCi/L Sr-90 pCri/L',
Milk 1-131 Ce-141 Cr-51 Cs-1 34 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L 82.8 107 19.0 98.1 260 389 144.0 185 86.9 133 126 173 298 79.4 112 16.7 102.0 284 400 166 192 91.9 137 122 175 312 1.04 0.96 0.84 0.92 0.90 0.88 1.00 0.96 1.06 1.12 1.03 1.00 1.04 1.04 0.99 1.10 1.06 1.00 0.98 1.03 1.10 1.04 0.96 1.14 0.96 0.92 0.97 0.87 0.96 0.95 0.97 1.03 0.99 0.96 1.14 1.13 1.06 1.22 1.16 1.05 1.19 1.36 1.12 0.96 A
A A
A A
A A
A A
A A
A A
E6745-396 AP Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Charcoal 1-131 pCi pCi pCi pCi pCi pCi pCi pCi pCi 186 262 101 135 61 83.1 84 137 202 163 231 95 111 53 79 70 101 180 A
A A
W A
A A.
N (1)
A E6744-396 pCi 92.2 95.8 A
D-1 70 of 109
TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE*BROWN ENGINEERING, 2009 (PAGE 2 OF 3)
Identification' Reported Known
'Ratio (c)
Month/Year-
'Number, Matrix'
- Nuclide, Units Value.(a)
Value (b)
TBE/Analytips
.Eyaluation (d)
September 2009 E'16897-396 Milk E6898-396 Milk E6900-396 AP Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-1 34 Cs-1 37 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 89.2 249 213 104.0 172 96.3 201 154 213 154 181 145 71.8 115 62 129 97 110 98.7 98.6 275 221 123 185 99.4 206 147 204 160 161 130 72 109 58 121 98 120 94.1 pCi/L 113-107 pCi/L 17.4 18.8 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 E6899-396 Charcoal 1-131 pCi 89.5 92.3 pCi/L 131 131 pCi/L 19.3 17.9 1.06 0.93 0.90 0.91 0.96 0.85 0.93 0.97 0.98 1.05 1.04 0.96 1.12 1.12 0.99 1.06 1.06 1.07 0.98 0.92 1.05 0.97 1.00 1.08 0.91 0.96 0.93 0.88 0.91 0.95 1.00 0.99 0.94 0.94 1.00 1.04 0.90 1.02 1.03 0.89 1.17 0.88 1.03 A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
December 2009 E6946-396 E6947-396 Milk Milk Sr-89 Sr-90 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi pCi pCi pCi pCi pCi pCi pCi pCi 79.2 193 512 222 163 200 178 176 326 240 103 290 116 93.4 111 81.0 106 155 135 87.3 202 548 253 179 211 178 178 345 256 103 280 129 91.5 108 90.8 90.8 176 131 E6949-396 AP Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 D-2 71 of 109
TABLE D-1 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 3 OF 3)
Identification Reported
-Known.,
Ratio (c)
Month/Year Number Matrix Nuclide Units.
Value (a)
Value (b)'
TBE/Analytics Evaluation (d)
December 2009 E6948-396 Charcoal 1-131 pCi.
93.3
.93.9 0.99.
A (1)
(a)
(b)
(c)
(d)
Detector 7 appears to have a slightly high bias. Detector 7 was removed from service until it can be recalibrated. NCR 09-23 Teledyne Brown Engineering reported result.
The Analytics known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
Ratio of Teledyne Brown Engineering to Analytics results.
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 72 of 109
TABLE D-2 ERA ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM TELEDYNE BROWN ENGINEERING, 2009 (PAGE 1 OF 1)
Idehtification Reported Known
.Month/Year
-Number.'.....
Media Nuclide Units.. Value (a)
Value (b), Control Limits Evaluation (c)
April 2009 RAD 77 Water Sr-89 Sr-90 Ba-1 33 Cs-i 34 Cs-1 37 Co-60 Zn-65 Gr-A Gr-B 1-131 H-3 Water Sr-89 Sr-90 Ba-1 33 Cs-134 Cs-137 Co-60 Zn-65 Gr-'A Gr-B 1-131 H pCi/L 57.4 pCi/L 30.6 pCi/L-55.2 pCi/L 65.8 pCi/L 157 pCi/L 86.4 pCi/L 85.5 pCiL'.
47.7 pCi/L 45.2 pCi/L 25.2 pCi/L 19733 pCi/L 64.75 pCi/L 30.30 pCi/L 97.9 pCi/L 76.8 pCi/L 59.9 pCi/L 121 pCi/L 115 pCi/L 19.6 pCi/L 28.5 pCi/L 22.1 pCi/L 16133 48.3 31.4 52.7 72.9 168 88.9 84.4 54.2 43.5 26.1 20300 62.2 30.7 92.9 79.4 54.6 117 99.5 23.2 26.0 22.2 16400 37.8 - 55.7 22.9 - 36.4 43.4 - 58.3 59.5 - 80.2 151 - 187 80.0 - 100 76.0- 101 28.3 - 67.7 29.1 -50.8 21.7 - 30.8 17800 - 22300 50.2 - 70.1 22.4 - 35.6 78.3-102 65.0 - 87.3 49.1 - 62.9 105-131 89.6-119 11.6-31.1 16.2 - 33.9 18.4 - 26.5 14300- 18000 N (1)
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A October 2009 RAD 79 (1) Calculation did not allow for Y-90 ingrowth on the'Sr-89 mount. NCR 09-14 (a) Teledyne Brown Engineering reported result.
(b) The ERA known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) ERA evaluation: A=acceptable. Reported result falls within the Warning Limits. NA=not acceptable. Reported result falls outside of the Control Limits. CE=check for Error. Reported result falls within the Control Limits and outside of the Warning Limit.
D-4 73 of 109
TABLE D-3 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP]
TELEDYNE BROWN ENGINEERING, 2009 (PAGE 1 OF 2)
Identification Reported Known...
Acceptance Month/Year Number Media Nuclide Units Value,(a)
Value (b)
Range Evaluation (c)
March 2009 09-MaW20 Water.
Cs-134 Cs-137 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Water Gr-A Gr-B 09-GrW20 09-MaS20 09-RdF20 Bq/L 18.8 22.5 Bq/L 0.0601 Bq/L 17.0 18.9 Bq/L 16.1 17.21 Bq/L 332 330.9 Bq/L 13.8 14.7 Bq/L 6.88 7.21 Bq/L 13.2 13.6 Bq/L 0.529 0.635 Bq/L 1.87 1.27 Bq/kg 433 467 Bq/kg 649 605 Bq/kg.
-0.120 Bq/kg 3.91 4.113 Bq/kg 339 307 Bq/kg.
644 570 Bq/kg 245 257 Bq/kg 272 242 18.5-29.3 (1) 13.2-24.6 12.05 - 22.37 231.6 - 430.2 10.26-19.06 5.05-9.37 9.5-17.7
>0.0 - 1.270 0.64-1.91 327 - 607 424 - 787 (1)
(2) 215 -399 399 - 741 180 - 334 169-315 Soil Cs-1 34 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
09-GrF20 March 2009 09-RdV20 September 2009 09-MaW21 09-GrW21 AP Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 Sr-90 Zn-65 AP Gr-A Gr-B Vegetation Cs-134 Cs-1 37 Co-57 Co-60 Mn-54 K-40 Sr-90 Zn-65 Water Cs-1 34 Cs-1 37 Co-57 Co-60 H-3 Mn-54 Sr-90 Zn-65 Water Gr-A Gr-B Bq/sample 2.77 2.93 2.05 - 3.81 Bq/samp!e 1.41 1.52 1.06-1.98 Bq/sample 1.24 1.30 0.91 -1.69 Bq/sample 1.33 1.22 0.85 - 1.59 Bq/sample 2.42 2.2709 1.5898 - 2.9522 Bq/sample 0.713 0.64 0.448 - 0.832 Bq/sample 1.30 1.36 0.95 - 1.77 Bq/sample 0.188 0.348
>0.0 - 0.696 Bq/sample 0.313 0.279 0.140 - 0.419 Bq/sample 3.48 3.40 2.38 - 4.42 Bq/sample 1.15 0.93 0.65-1.21 Bq/sample 3.12 2.36 1.65-3.07 Bq/sample
-0.0105 (1)
Bq/sample 2.98 2.3 1.61 - 2.99 Bq/sample 64.1 (4)
Bq/sample 1.09 1.260 0.882 - 1.638 Bq/sample 1.73 1.3540 0.948 - 1.760 Bq/L 26.5 32.2 22.5-41.9 Bq/L 37.2 41.2 28.8-53.6 Bq/L 32.2 36.6 25.6 - 47.6 Bq/L 14.0 15.40 10.8-20.0 Bq/L 705 634.1 443.9 - 824.3 Bq/L
-0.1015 (1)
Bq/L 13.9 12.99 9.09-16.89 Bq/L 26.2 26.9 18.8-35.0 Bq/L 1.27 1.047
>0.0 -,2.094 Bq/L 9.70 7.53 3.77 - 11.30 A
A A
W N (3)
A W
A W
A A
A A
A A
A A
A A
D-5 74 of 109
TABLE D-3
' DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP)
TELEDYNE BROWN ENGINEERING, 2009 (PAGE 2 OF 2)
Identification Reported Known Acceptance Month/Year Number Me dia Nuclide Units Value (a)
Value (b)
Range Evaluation (c)
September 2009 09-MaS21' Soil-Am-241 Cs-134 Cs-137 Co-57 Co-60 Mn-54 K-40 Sr Zn-65 Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg Bq/kg 09-RdF21 09-GrF21 09-RdV21 AP Cs-1 34 Bq/sample Cs-137 Bq/sample Co-57 Bq/sample Co-60 Bq/sample Mn-54 Bq/sample Sr-90 Bq/sample Zn-65 Bq/sample AP Gr-A Bq/sample Gr-B" Bq/sample Vegetation Cs-134 Bq/sample Cs-137 Bq/sample Co-60 Bq/sample Mn-54 Bq/sample K-40 Bq/sample Sr-90 Bq/sample Zn-65' Bq/sample S.74.7-.
0.554 706 606 350*
876 425 505 1370
-0.02 1.4 5.98 1.01 5.16 0.925 4.39 0.357 1.403
-0.0027 2.36 2.58, 8.36 57.8 1.73
-0.59
. 669 586 327.000 796
- -375 455
-1178 89:8-
- 62.9 - 116.7.
(1) 468-870' 410-762.
229-425 557-1035 263-488 319-592
- 85 1531.
S (1)
.0,98 -1.82 4.54-8.42 0.72-1.34 3.84-7.14 0.585 - 1.086 2.75-5.11 1.4 6.48.,
1.03 5.49 0.0835 3.93 A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A 0.659.,
>0.0- 1.318 1.320 0.66-1.98 (1).
2.43' 1.70-3.16 2.57 1.80 - 3.34 7.9 5.5-10.3 (4) 1.78 1.25-2.31 (1)
(1) False positive test.
(2) Sensativity evaluation.
(3) Homogeniety problem. MAPEP requires using entire sample but due to geometry limitations we can only use part of the sample. NCR 09-13 (4) Not evaluated by MAPEP.
(a) Teledyne Brown Engineering reported result.
(b) The MAPEP known value is equal to 100% of the parameter present in the standard as determined by gravimetric and/or volumetric measurements made during standard preparation.
(c) DOEIMAPEP evaluation: A=acceptable, W=acceptable with warning, N=not acceptable.
D-6 75 of 109
TABLE D-4 ERA (a) STATISTICAL
SUMMARY
PROFICIENCY TESTING PROGRAM ENVIRONMENTAL, INC., 2009 (Page 1 of 1)
Concentration (pCi/L)
Lab Code Date Analysis Laboratory...
ERA.
Resultb Resultc Control.,
Limits Acceptance STW-1181 STW-1 181 STW-1182 STW-1182 STW-1182 STW-1182 STW-1182 STW-1183 STW-1183 STW-1184 STW-1186 STW-1193 STW-1193 STW-1194 STW-1194 STW-1194 STW-1194 STW-1194 STW-1195 STW-1 195 STW-1196 STW-i 198 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 41.0 32.4 44.6 81.0 65.6 147.7 79.8 47.6 38.5 24.4 22819.0 53.0 31.1 82.5 116.8 78.8 54.2 102.5 20.3 23.7 22.4 17228.0
+/- 5.8
+/- 2.4
+/- 3.1
+/- 3.1
+/- 5.2
+/- 5.3
+/- 7.5
+/- 2.1
+/- 1.3
+/- 2.5
+/- 453.0
+/- 6.0
+/- 2.2
+/- 3.5
+/- 3.3
+/- 5.7
+/- 3.7,
+/- 6.2
+/- 2.0
+/- 1.4
+/- 1.4
+/- 694.0 48.3 31.4 52.7 88.9 72.9 168.0 84.4 54.2 43.5 26.1 20300.0 62.2 30.7 92.9' 117.0 78.8, 54.6 99.5 23.2 26.0 22.2 16400.0 37.8 - 55.7 22.9 - 36.4 43.4 - 58.3 80.0 - 100.0 59.5 - 80.2 151.0 - 187.0 76.0 -101.0 28.3 - 67.7 29.1 --50.8 21.7 - 30.8 17800.0 - 22300.0 50.2 - 70.1 22.4 - 35.6 78.3 -102.0 105.0 - 131.0 65.0- 87.3 49.1 -62.9 89.6 -119.0 11.6 -31.1 16.2 - 33.9 18.4 - 26.5 14300.0 - 18000.0 Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
d All gamma -emitters showed a low bias. A large plastic burr found on the base of the Marinelli kept the beaker from sitting directly on the detector. Result of recount in a different beaker, Cs-137, 155.33
+/- 14.55 pCi/L.
e Samples were recounted and also reanalyzed., A recount of the original vials averaged 23,009 pCi/L.
Reanalysis results were acceptable, 19,170 pCi/L.
D-7 76 of 109
TABLE D-5 DOE'S MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEPr ENVIRONMENTAL, INC., 2009 (Page 1 of 2)
.Concentration Known Control Lab Code c Date Analysis Laboraio r'result Activity Limits d Acceptance STW-1 170 STW-1 170' STW-1 170 STW-1 170 e STW-1170 STW-1170 STW-1170 STW-1170 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 Co-57 Co-60 Cs-1 34 Cs-137 H-3 Mn-54 Sr-90 Zn-65 STW-1171 01/01/09 Gr. Alpha STW-1171 01/01/09 Gr. Beta 19.60 +/- 0.40 16.60 +/- 0.30-20.40 +/- 0.50 0.10 +/- 0.20 359.90 +/- 33.90 15.00 +/- 0.40 7.87 +/- 1.39 14.00 +/- 0.70 0.56 +/- 0.06 1.29 +/- 0.05 0.00 +/- 0.00 458.60 +/- 7.40 652.30 +/- 3.50 636.40 +/- 9.50 346.40 +/- 3.10 180.60 +/- i2.10 268.30 +/- 4.00 18.90 17.21 22.50 0.00 330.90 14.66 7.21 13.60 13.20 -24.60' 12.05'-22.37 15.80 - 29.30 0.00-1.00 231.60 - 430.20 10.26 - 19.06 5.05 - 9.37 9.50 - 17.70 0.64 1.27 0.00 - 1.27 0.64-1.91 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STSO-1172 e STSO-1 172 STSO-1 172 STSO-1 172 STSO-1 172 STSO-1 172 STSO-1 172 STVE-1 173 STVE-1173 e STVE-1 173 STVE-1 173 STVE-1 173 STVE-1 173 STAP-1 174 STAP-1 174 STAP-1 174 STAP-1 174 STAP-1 174 STAP-1174 STAP-1 174 STAP-1175 STAP-1 175 STW-1192 STW-1192 STW-1 192 STW-1 192 STW-1192 STW-1192 STW-1192 STW-1192 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Co-57 Cs-134 Cs-137 K-40 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 0.00 467.00 605.00 570.00 307.00 257.00 242.00 0.00-1.00 327.00 - 607.00 424.00- 787.00-360.40 - 669.40 215.00 -399.00-180.00 -334.00' 169.00 - 315.00 2.75 40. 11 0.06 +/- 0.09 3.49 +/- 0.22 1.01 +/- 0.11 2.52 +/- 0.14 1.52 +/- 0.18 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Sr-90 Zn-65 Gr. Alpha Gr. Beta 1.25 +/-0.05 1.17 +/- 0.06 2.67 +/- 0.14 1.53 +/- 0.08 2.34 +/- 0.09 0.93 +/- 0.14 1.44 +/- 0.14 0.22 +/- 0.03 0.36 + 0.04 2.36 0.00 3.40 0.93 2.30 1.35 1.30 1.22 2.93 1.52 2.27 0.64 1.36 0.35 0.28 1.65 -3.07 0.00-1.00 2.38 - 4'.42 0.65-1.21 1.61 -2.99 0.95 -1.76 0.91 - 1.69 0.85-*1.59 2.05 -3.81 1.06-1.98 1.59 -2.95 0.45 -0.83 0.95-1.77 0.00 -0.70 0.14 -0.42 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
'Co-57 Co-60 Cs-1 34 Cs-1 37 H-3 Mn-54.
Sr-90 Zn-65 37.20 +/- 1.50 15.10 +/- 0.90 30.30 +/- 2.10 41.90 +/- 1.80 680.30 +/- 33.60 0.01 +/- 0.26 12.90 +/- 1.70 28.50 +/- 2.40 36.60 15.40 32.20 41.20 634.10 0.00 12.99 26.90 25.60 - 47:60 10.80 -20.00 22.50 -41.90 28.80 - 53.60 443.90 - 824.30 0.00-1.00 9.09 -16.89 18.80 -35.00 D-8 77 of 109
TABLE D-5 DOE'S MIXEDANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEPr ENVIRONMENTAL, INC., 2009 (Page 2 of 2)
Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STW-1191 07/01./09.
Gr. Alpha 0.88 +/- 0.07 STW-1191 07/01/09 Gr. Beta 7.29 +/- 0.10 1.05 7.53 0.00 - 2.09 3,77 -11.30 Pass Pass STSO-1 188 STSO-1 188 STSO-1 188 STSO-1 188 STSO-1 188 STSO-1 188 STSO-1 188 STSO-1 188 STVE-1 190 STVE-1 190 STVE-1 190 STVE-1 190 STVE-1 190 STVE-1 190 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 g 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09
.07/01/09 07/01/09 Co-57 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 674.60 +/- 9.00 356.40 +/- 6.30 0.20 +/- 1.90 767.50 +/- 12.00 433.00 +/- 37.20 931.60 +/- 14.10 310.50 +/- 12.20 1433.90 +/- 25.20 8.90 +/- 0.60 2.50 +/- 0.36 0.01 +/- 0.11.
2.42 +/- 0.16 8.35 +/- 0.70 0.01 +/- 0.26 586.001 327.00 0.00 669.00 375.00 796.00 455.00 1178.00 8.00 2.57 0.00 2.43 7.90 0.00 410.00 -762.00 229.00 - 425.00 0.00 -1.00 468.00 - 870.00 -
263.00 - 488.00 557.00 -1035.00 319.00 - 592.00 825.00 -1531.00 5.60-10.40 1.80 -3.34 0.00,70.10 1.70 -3.16 5.50 -10.30 0.00-0.10 Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1189 07/01/09 Gr. Alpha STAP-1189 07/01/09 Gr. Beta 0.33 +/- 0.04 1.57 +/- 0.07 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 STAP-1 190 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 6.78. +/- 0.27 1.06 +/- 0.18 0.01 +/- 0.06 1.49 +/- 0.27 6.00 +/- 0.45 0.79 +/- 0.13 4.55 +/- 0.66 0.66 1.32 6.48 1.03, 0.00 1.40 5.49 0.84 3.93 0.00-1.32 0.66-1.98 4.54 - 8.42 0.72,-1.34 0.01 - 0.05 0.98-1.82 3.84 -7.14 0159 -1.09 2.75.-5.11 Pass Pass Pass
-Pass Pass Pass 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 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, I determination) and control limits as defined by the MAPEP.
e Included in the testing series as a "false positive".
No reason was determined for the initial high results. The analysis was repeated; result of reanalysis; 0.54 +/- 0.12 Bq/filter.
9 Incomplete separation of strontium from calcium could result in a higher recovery percentage and consequently lower reported activity. The analysis was repeated; result of reanalysis 363.3 +/- 28.6 Bq/kg.
D-9 78 of 109
APPENDIX E ANNUAL RADIOLOGICAL GROUNDWATER PROTECTION PROGRAM REPORT (ARGPPR) 79 of 109
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 2009 Prepared Byt.
Teledyne Brown Engineering Environmental Services Exekn S.
Nuclear Quad Cities Nuclear Power Station Cordova, IL 61242 May 2010 80 of 109
Table Of Contents I. Summary and Conclusion....................................................
1 II. Introduction..................................................
4 A., O bjectives of the RG PP
................................................................. 4 B. Implementation of the Objectives...'..
4 C. P rogram D escription......................................................................................
5 Ill. P rog ra m D escriptio n............................
- .................................... 6 A. Sample Analysis.
6 B. Data Interpretation.........................
.............. 6 C. Background Analysis.........................
7
- 1. Background Concentrations of Tritium....... :................... I........................ 7 IV. R esults and D iscussion...........................................................................................
9 A. Groundwater Results..............................................................
9 B. S urface W ater Results..................................................................................
10 S.8, 109 81 of 109
Appendices Appendix A Tables Table A-i:
Location Designation Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2009 Figqures Figure A-I:
Figure A-2:
Appendix B Tables Table B-I.1 Table B-1.2 Table B-11.1 Table B-11.2 Table B-111.1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2009 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2009 Data Tables Concentrations of Tritium and Strontium in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
Concentrations of Gamma Emitters in Groundwater Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Quad Cities Nuclear Power Station, 2009.
Concentrations of Tritium in Groundwater Samples Collected and Anaylzed by Quad Cities Station Personnel, 2009.
82 of 109
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 0.1 Januar.2009 through 31 December 2009.
In 2006, Exelon undertook a Fleetwide Assessment of groundwater at and in the vicinity of its nuclear power generating facilities forthe presence of radionuclides. The data collected. from the Quad Cities Station as part of the Fleetwide Assessment was summarized in a report entitled
-,ý "Hydrogeologic.Investigation Report, Fleetwide Assessment, Quad Cities
.Generation,Station, Cordova,,Illinois", dated September 2006. This report was submitted to the Illinois Environmental Protection Agency (IEPA) in September 2006. The Quad Cities Hydrogeologic Investigation Report concluded that tritium had, not migrated :off Site at detectable concentrations.
Following the Fleetwide Assessment, Exelon continued groundwater monitoring for radionuclides at the Site. As a result of this monitoring, Exelon detected higher than expected tritium levels, in the vicinity of the station's Service Building and. Tu~rbine Building., Quad Cities undertook supplemental investigative activities to determine and characterize the source of the tritium,These investigative activities included completion of an aquifer pumping test, installationof sentinel monitoring wells in the vicinity of the Service Building and Turbine Building, and several' additional rounds of hydraulic mohitoring arid groundwater sampling.The collected groundwater data was utilized to assist with an extensive underground piping inspection program tolocbate the source of the..tritium.
In May 2008, during the underground piping inspection program, Exelon located a small leak in the Unit 1 Residual Heat' Removal (RHR) suction line located near the Service Building/ Turbine Building area. The line was isolated and through further testing, Exelon determined it to be a source of the monitored tritium levels. In June 2008, the line was repaired, thereby eliminating this source of tritiated water.
In a letter dated June 5, 2008, Exelon informed the Illinois Environmental Protection Agency (IEPA) of its plan to prepare a Migration Control Plan (MCP) to minimize migration of the tritium plume offsite. The MCP was submitted to the IEPA July 17, 2008. The MCP listed Monitored Natural Attenuation as the preferred remediation option. 83 of 109
This report covers groundwater samples, collected from the' environment on station property in 2009. During that time period, RGPP samples were collected from 53 locations.
Sample locations include twenty-seven;'designated *monitoring Wells," two surface water monitoring points, nine production wells (three of which are used for site drinking water) and fifteen sentinel wells.'The twenty-seven designated monitoring well's are sampled' on a quarterly basis for tritium, annually for gamma, and biannual for Sr-90'.Samples from the twenty-seven designated monitoring wells were collected by a contractor (Envirohmental inc.) and analyzed by a contract iab (Teledyne Brown). Theremaining sample locations are collected quarterly (at a minimum) by' site' ersonnel andanalyzed'fr t'ritium by Teledyne Brown or onsite by station personnel.
Tritium concentrations ranged from less than:the LLD of 200 pCi/L at the site boundaries up to 771,000 pCi/L in a sentinel monitoring well. Tritium concentrations ranged from less than the LLD of 200 pCi/L to 611 pCi/L in surface water'monit6ring locations.-
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
'alculation Manual (ODCM) in any of the groundwater samples.. In, the case of tritium,.Exelonspecified that it's laboratories achieve. a lower limit of detection, 10 times lower than that required by federal. regulation.,.Most ofthe tritium that wasdetected in groundwater at the Station is on the south and west side of the Reactor / Turbine buildings.
Strontium-90 was not detected at concentrations greaterthan the Lower Limit of Detection (LLD) of 2.0 pCi/L as specifie~d in the Offsite Dose Calculation Manual (ODCM).
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.
. 84 of 109
Intentionally left blank 85 of 109
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.
A.
Objective of the RGPP The long-term objectives of the RGPP are as follows:
- 1. Identify suitable locations to monitor and evaluate potential impacts from station operations before significant radiological impact to the environment and potential drinking water sources.
- 2. Understand the local hydrogeologic regime in the vicinity of the station and maintain up-to-date knowledge of flow patterns on the surface and shallow subsurface.
- 3. Perform routine water sampling and radiological analysis of water from selected locations.
- 4. Report new leaks, spills, or other detections with potential radiological significance to stakeholders in a timely manner.
- 5. Regularly assess analytical results to identify adverse trends.
- 6. Take necessary corrective actions to protect groundwater resources.
B.
Implementation of the Objectives The objectives identified have been implemented at 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://www.exelonCorp.com/ourcompanies/powerqen/nuclear/Tritiu m.htm 86 of 109
- 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 leaks, 'spills, or other detections with potential radiological significance in a timely 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.
Sample Collection Sample locations can be found in Table A-1 and Figures A-1 & A-2, Appendix A.
Groundwater and'Surface Water Samplesof-water-are collected, managed, transported and analyzed In accordance with approved procedures following 7"reculatory methods. Both-groundwater and surface water are collected. Sample locations, sample collection frequencies and a. nalýtical frequencies-are controlled in'accordance with approved station procedures. Contractor and/or station personnel are trained in the collection, preservation management, analysis, and shipment of samples, as wellý'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. 87 of 109
Ill.
Program Description This section covers those analyses performed by Teledyne Brown Engineering (TBE) on samples collected in 2009.
A.
Sample Analysis This section describes the general analytical methodologies used by TBE
,and station personnel to analyzethe environmental samples for radioactivity for the Quad Cities Nuclear Power Station RGPP in 2009.
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 Cities N.uclear 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 Station was considered operational at initial criticality. Several factors were important in the interpretation of the data:
- 1.
Lower Limit-of Detection and Minimum Detectable Concentration The lower limit of detection (LLD) is specified by federal regulation as a minimum sensitivity value that must be achieved routinely by the analytical parameter.
- 2.
Laboratory Measurements Uncertainty The estimated uncertainty in measurement of tritium in environmental samples is frequently on the order of 50% of the measurement value.
Statistically, the exact value of a measurement is expressed as a range with a stated level of confidence. The convention is to report results with a 95% level of confidence. The uncertainty comes from calibration standards, sample volume or weight 88 of 109
measurements, sampling uncertainty and other factors. Exelon reports the uncertainty of a measurement created by statistical Sprocess (c"ounting 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 ieporting consistency with the Annual Radiological Environmental'Operating Report (AREOR).
Gamma spectroscopy results for each type of sample were grouped as follows:
For groundwaterand 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-1 37, 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:0peration of'the Station. The environmental media sampled and analyzed during the. pre-operational REMP were atmospheric radiation,, fall-out, domestic water, surface water, marine life, and vegetation. The results of the monitoring wer'e detailed in the reports entitled, Quad Cities Nuclear P'bwer Plant Environmental Monitoring Report, Commonwealth Edison-Company, covering the period from July 1 968 through September 1971.
The pre-operational REMP contained analytical results from samples collected from the surface water and groundwater.
1..,
Background Concentrations of Tritium 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 89 of 109
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 grotund, "lithogenic" tritium is produced by the bombardment of natural, lithium present in crystalline rocks by neutrons produced by the radioactive decay of naturally abundant uranium and thorium. Lithogenic production of tritium is usually negligible compared to other sources due to the limited abundance of lithium in rock. The lithogenic tritium is introduced directly to groundwater.
A major anthropogenic source of tritium and strontium-90 comes from the former atmospheric testing of thermonuclear weapons. Levels of tritium in precipitation increased significantly during the 1950s and early,1 960s, and later with additional testing, resulting in the release of significant amounts of tritium to the atmosphere. The Canadian heavy water nuclear power reactors, other commercial power reactors, nuclear research and weapons production continue to influence tritium concentrations in the environment.
- b.
Precipitation Data Precipitation samples are routinely collected at stations around the world for the analysis of tritium and other radionuclides. Two publicly available databases that provide tritium concentrations in precipitation are Global Network of Isotopes in, Precipitation (GNIP) and USEPA's RadNet database. GNIP providestritium 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 some stations, coincided with the atmospheric testing of thermonuclear weapons. Tritium concentrations in surface water showed a sharp decline up until 1975 followed by a, gradual decline since that time. Tritium concentrations in 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. 90 of 109
- 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 100 pCi/L.
ýThe radio-analytical laboratory is counfting tritium results to an Exelon specified LLD of 200ýpCi/L. Typically, the lowest positive measurement will be reported Within a range of 40 -
240 pCi/L or 140 +/- 100 pCi/L. Clearly, these sample results cannot be distinguished as different from. background at this concentration.
IV.
Results and Discussion A.
Groun'dwater-Results""
Groundwater Samples were collected from on-site wells in accordance with the station radiological groundwater protection program. Analytical results and anomalies are discussed below.
Tritium Samples from all locations were analyzed for tritium activity (Table B-1.1 & B-1ll.1 Appendix B). Tritium values ranged from the detection limit to 771,000 pCi/I. All samples obtained at the site boundaries were less then the detection limit of 200 pCi/L. The location most representative of potential offsite user of drinking water was <200 pCi/L.
Strontium Strontium-90 was not detected above the Lower Limit of Detection (LLD) of 2.0 pCi/L. (Table B-1.1 Appendix B) 91 of 109
Gamma Emitters Naturally occurring PotassiuMT40: was detected in six of 33 samples. The concentratJons ranged from 102 pCi/liter to 180 pCi/liter. No other gamma emitting nuclides were detected. (Table B-1.2, Appendix B)
B.
Surface Water Results Surface Water
- Tritium, Samples from two locations were analyzed for tritium activity (Table 3B-II.1 Appendix B). Tritium was detected above the detection limit of 200 pCi/i in six of 10:samples. The concentrations ranged from 264 to 61 1 pCi/L.
Strontium Strontium-90 was not analyzed in 2009. (Table B-I.1 Appendix B)
Gamma Emitters No gamma emitting nuclides were detected. (Table B-II.2, Appendix B) 92 of 109
APPENDIX A LOCATION DESIGNATION 93 of 109
TABLE A-1:
Radiological Groundwater Protection Program - Sampling Locations, Quad Cities Nuclear Power Station, 2009 Site Site Type MW-QC-1 MW-QC-2 MW-QC-1011 MW-QC-101S MW-QC-102D MW-QC-1 021 MW-QC-1 02S MW-QC-1031 MW-QC-104S MW-QC-1051 MW-QC-1061 MW-QC-106S MW-QC-1071 MW-QC-108D MW-QC-1081 MW-OC-108S MW-QC-1091 MW-QC-109S MW-QC-1i101 MW-QC-111 D1 MW-OC-i 11 D2 MW-QC-1 111 MW-QC-1 121 MW-QC-1 131 MW-QC-1 141 MW-QC-1 15S MW-QC-1 16S SURFACE WATER #1 SURFACE WATER #2 WELL #1 WELL #5 WELL #6 LITTLE FISH WELL #7 BIG FISH WELL WELL #8 FIRE TRAINING WELL WELL #9 DRY CASK WELL WELL #10 FISH HOUSE WELL WELL #11 SPRAY CANAL WELL STP SAND POINT WELL QC-GP-1 QC-GP-2 QC-GP-3 QC-GP-4 QC-GP-5 QC-GP-6 QC-GP-7 QC-GP-8 QC-GP-9 QC-GP-10 QC-GP-11 QC-GP-12 QC-GP-13 QC-GP-14 QC-GP-15 Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well
.,Monitorih'g Well Monitoring Well Monitoring Well Monitoring Well Monitoring Well Mohitoririg, Well
" M6nitoring Well Monitoring Well Surface Water Surface Water Production Well Production Well Production Well Production Well Production Well Production Well Production Well Production Well Production Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well Sentinel Well A-2 94 of 109
Wt
$t~I
- i. 4 rfr k I 1TI' M7-1143U2 -RDVt PUJELK; DISLOSUPE EXE104GEERATIONC ~AfNY1L
=3 4
Exal-n, FIGURE A-1 Sampling Locations Near the Site Boundary of the Quad Cities Nuclear Power Station, 2009
1-14
'4a-r~
r~j 32 a--
~
C)~
L
_L
-~
~
~'.
(F LE~~~47-f L1, t-.t' Jf1L 111
-ýo~
Wj t
~
figure I MON=TORING WELL LOCATIONS EXELON GENERATION COMPANY, LLC.
QUAD CITIES GENERATING STATION Co~rao
/ ilOas ON 0D 401 1%W;4 FIGURE A-2 Sentinel Monitoring Point Locations, Quad Cities Nuclear Power Station, 2009
L*'.,,*i..
APPENDIX B DATA TABLES 97 of 109
TABLE B-1.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-QC-1 MW-QC-1 MW-QC-1 MW-QC-1 MW-QC-2 MW-QC-2 MW-QC-2 MW-QC-2 MW-QC-1011 MW-QC-1011 MW-QC-101I MW-QC-101I MW-QC-101S MW-QC-101S MW-QC-101S MW-QC-1O1S MW-QC-102D MW-QC-102D MW-QC-102D MW-QC-102D MW-QC-1021 MW-QC-1 021 MW-QC-1021 MW-QC-1021 MW-QC-102S MW-QC-102S MW-QC-102S MW-QC-102S MW-QC-1031 MW-QC-1031 MW-QC-1031 MW-QC-1031 MW-QC-104S MW-QC-104S MW-QC-104S MW-QC-104S MW-QC-104S MW-QC-1051 MW-QC-1051 MW-QC-1051 MW-QC-1051 MW-QC-1061 MW-QC-1061 MW-QC-1061 MW-QC-1061 COLLECTION DATE 03/10/09 06/02/09 08/25/09 11/03/09 03/10/09 06/02/09 08/25/09 11/03/09 03/10/09 06/02/09 08/25/09 11/03/09 03/10/09 06/02/09 08/25/09 11/03/09 03/10/09 06/02/09 08/25/09 11/03/09 03/10/09 06/02/09 08/25/09 11/03/09 03/10/09 06/02/09 08/25/09 11/03/09 03/10/09 06/02/09 08/25/09 11/03/09 03/10/09 03/10/09 06/02/09 08/25/09 11/03/09 03/10/09 06/02/09 08/25/09 11/03/09 03/10/09 06/02/09 08/25/09 11/03/09 H-3 SR-90
- 191
- 183
- 174
- 182
- 185
- 180
- 180
- 180
- 185
- 148
< 168
< 163
< 177
< 145
< 167
< 164 6120 +/- 681 5340 +/- 572 5940 +/- 629 5450 +/- 591 4220 +/- 493 1330 +/- 182 849 +/- 168 270 +/- 115
< 191
< 147
< 167
< 165
< 193
< 150
< 167
< 157 ORIGINAL 43200 +/- 4380 RERUN 39900 +/- 4040
- 144
< 190 221 +/- 110 77500 +/- 7750 30600 +/- 3080 87100 +/- 8690 37200 +/- 3760
< 190
< 160
< 191
< 165 B-1 98 of 109
TABLE B.I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM IN GROUNDWATER SAMPLES C&OLLECTED IN THE VICI NITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LiTER +/-+2 SIGMA SITE MW-QC-106S MW-QC-106S MW-QC-106S MW-QC-106S MW-QC-1071 MW-QC-1 071 MW-QC-1071 MW-QC-1071 MW-QC-108D MW-QC-108D MW-QC-108D MW-QC-108D MW-QC-1081 MW-QC-1081 MW-QC-1081 MW-QC-1081 MW-QC-108S MW-QC-108S MW-QC-108S MW-QC-108S MW-QC-1091 MW-QC-1091 MW-QC-1091 MW-QC-1091 MW-QC-109S MW-QC-109S MW-QC-109S MW-QC-109S MW-QC-1 101 MW-QC-1101 MW-QC-1101 MW-QC-111D1 MW-QC-111D1 MW-QC-111D1 MW-QC-111D1 MW-QC-1 11 D2 MW-QC-1 11 D2 MW-QC-1 11 D2 MW-QC-1 11 D2 MW-QC-1111 MW-QC-1111 MW-QC-1 111 MW-QC-1111 COLLECTION DATE 03/10/09 06/02/09 08/25/09 11/03/09 03/09/09 06/01/09 08/26/09 11/03/09 03/11/09 06/03/09 08/26/09 11/04/09 03/11/09 06/03/09 08/26/09 11/04/09 03/11/09 06/03/09 08/26/09 11/04/09 03/10/09 06/02/09 08/25/09 11/03/09 03/10/09 06/02/09 08/25/09 11/03/09 06/03/09 08/26/09 11/04/09 03/11/09 06/03/09 08/26/09 11/04/09 03/11/09 06/03/09 08/26/09 11/04/09 03/10/09 06/03/09 08/26/09 11/04/09
...H-ý3.,
< 190
- 142
- 191
- 162
- 191
- 163
- 193
- 180 7060 +/- 775 6930 +/- 725 6180 +/- 668 6670 +/- 720
- 190 185 +/- 115
- 189 828 +/- 156
- 192 180 +/- 111
- 182
- 182 230 +/- 128 514 +/- 139 442 +/- 139 296 +/- 126
- 199
- 162
- 186
- 181
- 160
- 187
- 180
- 194
- 163
- 178
- 180
- 193
- 162
- 170
- 181
- 193
< 166
< 182
< 181 I SR-90 B-2 99 of 109
TABLE B-I.1 CONCENTRATIONS OF TRITIUM AND STRONTIUM-IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE MW-QC-1 121 MW-QC-1 121 MW-QC-1 121 MW-QC-1 121 MW-QC-1 131 MW-QC-1 131 MW-QC-1 131 MW-QC-1 131 MW-QC-1 141 MW-QC-1 141 MW-QC-1 141 MW-QC-1 141 MW-QC-1 15S MW-QC-1 15S MW-QC-1 15S MW-QC-1 15S MW-QC-1 16S MW-QC-1 16S MW-QC-1 16S MW-QC-1 16S QC-GP-9 QC-GP-9 QC-GP-13 QC-GP-13 QC-GP-14 QC-GP-14 COLLECTION DATE 03/09/09 06/01/09 08/25/09 11/02/09 03/11/09 06/03/09 08/26/09 11/04/09 03/11/09 06/03/09 08/26/09 11/04/09 03/09/09 06/01/09 08/26/09 11/03/09 03/09/09 06/01/09 08/25/09 11/03/09 09/18/09 12/01/09 09/18/09 12/01/09 09/18/09 12/01/09 H-3 SR-90 199 163 171 183 194 160 173 182 190 162 173 176 181 182 175 182 193 183 170 182
< 0.8-
<. 0.5,
< 06;
< 0:8
< 0.9
< 0.4 B-3 100 of 109
TABLE B-1.2 CONCENTRATIONS OF GAMMA EMITTERS IN GROUNDWATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION Be-7 PERIOD 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 MW-QC-1 MW-QC-2 MW-QC-1011 MW-QC-1O1S MW-QC-102D MW-QC-1021 MW-QC-102S MW-QC-1031 MW-QC-104S MW-QC-1051 MW-QC-1 061 MW-QC-1 06S MW-QC-1071 MW-QC-108S MW-QC-1081 MW-QC-108D MW-QC-1091 MW-QC-109S MW-QC-1101 MW-QC-1111 MW-QC-1 11 Dl MW-QC-1 11 D2 MW-QC-1 121 MW-QC-1131 MW-QC-1 141 MW-QC-1 15S MW-QC-1 16S QC-GP-9 QC-GP-9 QC-GP-13 QC-GP-13 QC-GP-14 QC-GP-14 08/25/09 08/25/09 08/25/09 08/25/09 08/25/09 08/25/09 08/25/09 08/25/09 08/25/09 08/25/09 08/25/09 08/25/09 08/26/09 08/26/09 08/26/09 08/26/09 08/25/09 08/25/09 08/26/09 08/26/09 08/26/09 08/26/09 08/25/09 08/26/09 08/26/09 08/26/09 08/25/09 09/18/09 12/01/09 09/18/09 12/01/09 09/18/09 12/01/09
< 40
< 39
< 4
< 4
< 9
< 38 180 +/- 54 <4
< 4
< 11
< 41
< 89
< 4
< 5
< 10
<47 105 +/-64 <6
<6
<15
<33
<34
<3
<4
<9
< 43
< 42
< 4
< 5
< 10
<50
<54
<5
<5
<12
< 48
< 41
< 5
< 5
< 11
< 33
< 27
< 4
< 4
< 7
< 38
< 25
< 4
< 5
< 7
< 42
< 87
< 4
< 5
< 10
< 51
< 43
< 5
< 5
< 16
< 59
< 112
< 6
<6
< 15
< 34
< 20
< 3
< 4
< 9
<35
<31
<3
<4
<9
< 45
< 85
< 4
< 5
< 12
< 35
< 29
< 4
< 4
< 9
<36 130 +/-46 <4
<4
<9
< 33
< 30
< 3
< 4
< 9
< 33
< 24
< 3
< 4
< 7
<42 145 +/-69 <4
<4
<11
< 33
< 27
< 3
< 4
< 7
< 30
< 29
< 3
< 3
< 8
<42
<61
<3
<4
<8
< 29
< 26
< 3
< 3
< 7
<45 132 +/-46 <4
< 5
< 10
< 33
< 31
< 3
< 3
< 8
< 39
< 47
< 4
< 4
< 10
< 25
< 28
< 3
< 3
< 6
< 38
< 40
< 5
< 5
< 10
< 26
< 58
< 2
< 3
< 5
< 43 102 + 60
< 4
< 5
< 11
< 23
< 29
< 2
< 2
< 6
<4
<9
<4
<7
<4
<9
<7
<9
<3
<7
<5
<10
<5
<11
<4
<10
<4
<7
<4
<6
<5
<10
<5
<8
<5
<11
<4
<7
<4
<8
<4
<11
<3
<6
<3
<7
<3
<7
<3
<6
<5
<8
<3
<7
<3
<7
<3
<7
<3
<7
<4
<8
<3
<6
<3
<8
<3
<6
<5
<10
<2
<4
<5
<8
<2
<5
<5
<8
<5
<7
<6
<9
<7
<9
<4
<7
<5
<7
<8
<9
<6
<8
<4
<7
<5
<6
<5
<10
<6
<10
<7
<9
<5
<9
<5
<7
<6
<10
<4
<7
<5
<7
<4
<6
<4
<6
<5
<8
<4
<6
<4
<6
<4
<7
<4
<6
<5
<8
<4
<6
<4
<8
<3
<5
<5
<9
<2
<4
<5
<9
<2
<5
<25
<4
<4
<40!
< 15
< 23
< 4
< 4
< 42
< 15
< 17
< 4
< 5
< 36
< 14
< 23
< 5
< 6
< 45
< 14
<15
<3
<4
<29
<10
< 20
< 4
< 5
< 36
< 11
<21
<5
<5
<42
< 15
< 20
< 4
< 5
< 38
< 14
< 14
< 3
< 3
<28
< 13
< 15
< 3
< 4
< 30
< 10
<17
<4
<5
<32
<13
<22
<4
<6
<45
<15
< 24
< 6
< 6
<49
< 10
<13
<3-
<3
<23
<9
<20
<3.
<4
<35
< 14
< 26
< 4
< 5
< 46
< 15
<20
< 3
<4
<40
< 13
< 23
<3
<4
< 37
< 12
< 22
< 3
< 4
< 34
< 10
<19
<3-
<3
<34
<9
< 24
<4,
<4
<40
< 15
< 19
< 3
< 3
< 30
< 11
< 21
< 3.
< 3
< 39
< 12
<26
<3,
<4
<40
< 11
< 19
<3
< 3
< 31
<9
<27
<4:
<4
<44
< 14
< 21
< 3
< 3
< 36
< 9
< 14
<4:
<4
<28
< 10
<14
<2.
<3
<27
<8
< 15
<4.
< 5
< 30
< 12
<14
<2.
<2
<21
<7
<15
<4
<5
<33
<7
<12
<2
<3
<24
<5 0
0 0
TABLE B-1I.1 CONCENTRATIONS OF TRITIUM IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA SITE Surface Water #1 Surface Water #1 Surface Water #1 Surface Water #1 Surface Water #1 Surface Water #2 Surface Water #2 Surface Water #2 Surface Water #2 Surface Water #2 COLLECTION DATE 03/09/09 06/01/09 08/25/09 08/25/09 11/03/09 03/09/09 06/01/09 08/25/09 08/25/09 11/03/09 H-3
- 188
< 179 611 483 264
< 190
< 182 480 455 313
+
+
-I
+/-1
- t
-I 161 160 124 152 155 127 B-5 102 of 109
TABLE B-1I.2 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES COLLECTED IN THE VICINITY OF QUAD CITIES NUCLEAR POWER STATION, 2009 RESULTS IN UNITS OF PCI/LITER +/- 2 SIGMA STC COLLECTION PERIOD 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 Surface Water #1 Surface Water #2 08/25/09 08/25/09
<38
<35
<4
<4
<11
<4
<9
<5
<8
<24
<4
<4
<44
<14
< 31
< 31
< 3
< 3
< 8
< 3
<6
<4
< 6
< 22
< 3
<3
< 36
< 10 0*
0
TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2009 RESULTS IN UNITS OF PCI/LITER COLLECTION DATE SITE ACTIVITY QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-GP-1 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-QP-2 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-3 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-4 01/05/09 01/28/09 03/06/09 03/30/09 04/14/09 05/03/09 05/26/09 06/22/09 07/13/09 08/12/09 09/01/09 10/05/09 11/02/09 12/01/09 01/05/09 01/28/09 02/12/09 03/06/09 03/30/09 04/14/09 05/03/09 05/26/09 06/22/09 07/13/09 08/12/09 09/01/09 10/05/09 11/02/09 12/01/09 01/05/09 01/28/09 02/12/09 03/06/09 03/30/09 04/14/09 05/03/09 05/26/09 06/22/09 08/12/09 09/01/09 10/05/10 11/02/10 12/01/09 01/05/09 01/28/09 02/12/09 03/06/09 03/30/09 04/14/09 05/03/09 05/26/09 3,390 2,640 8,350 6,560 7,090 7,690 6,650 12,000 14,500 10,400 31,100 11,700 34,000 2,880 46,500 28,500 38,200 23,300 9,420 22,500 43,000 15,700 2,000 2,000 2,000 12,200 2,000 2,560 2,000 2,920 2,980 2,150 2,850
<2000 3,200 2,120 2,880
<2000
<2000 2,710
<2000
<2000
<2000 211,000 198,000 187,000 175,000 123,000 89,900 96,500 63,800 AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER
-I B-7 104 of 109
TABLE B-Ill.,
CONCENTRATIONS &OFTRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2009 RESULTS IN UNITS OF PCI/LITER SITE QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-4 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-5 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-6 QC-GP-7 QC-GP-7 QC-GP-7 QC-GP-7 QC-GP-7 QC-GP-7 QC-GP-7 QC-GP-7 QC-GP-7 QC-GP-7 QC-GP-7 QC-GP-7 QC-GP-7 COLLECTION DATE 06/22/09 07/13/09 08/12/09 09/01/09 10/05/09 11/02/09 12/01/09 12/14/09.
01/05/09 01/28/09 02/12/09 03/06/09 03/30/09 04/14/09 05/03/09 05/26/09 06/22/09 07/13/09 08/12/09 09/01/09 10/05/09 11/02/09 12/01/09 01/05/09 01/28/09, 02/12/09 03/06/09 03/30/09 04/14/09 05/03/09 05/26/09 06/22/09.
07/13/09 08/12/09.
09/01/09 10/05/09 11/02/09 12/01/09.
01/05/09 01/28/09:
02/12/09 03/06/09 03/30/09 04/14/09 05/03/09 05/26/09 06/22/09 07/13/09 08/12/09.-
09/01/09 10/05/09
'ACTIVITY 106,000 113,000, 123,000
.139,000 124,000:
. 117,000.
92,700
-88,100 15,300 14,600 32,100
.73,700 10,900.,
43,600
- 16,100.
16,100
.12,200 5,940 6,370 5,950.
- 4,670 7,830
, 5,380
.4,400 10,600.
19,800 2,000
.6,570.
2,100 2,110, 5,350 2000.
2,000
.5,890
.3,540 2,000.
2,000.
2,000 38,100 23,000 21,400 22,700 22,100 21,300 19,700 20,200 13,400 11,200 6,960 6,590 5,700
-:AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER.
SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW.AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER-SHALLOW AQUIFER SHALLOW AQUIFER.
SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER-.
SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER.
SHALLOW AQUIFER.
SHALLOW AQUIFER, SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER B-8 105 of 109
TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION:PERSONNEL, 2009 RESULTS IN UNITS OF PCI/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-7 11/02//09
.-, 5,940,...
SHALLOW AQUIEER QC-GP-7 12/01/09 6,240 SHALLOW AQUIFER QC-GP-8 01/05/09
<2000 "
SHALLOW AQUIFER QC-GP-8 01/28/09
<2000 SHALLOW AQUIFER QC-GP-8 03/06/09
<2000 SHALLOW AQUIFER QC-GP-8 03/30/09
<2000 SHALLOW AQUIFER QC-GP-8 04/14/09
<200' SHALLOW AQUIFER" QC-GP-8 05/03/09
<2000 SHALLOW AQUIFER QC-GP-8 05/26/09
<2000 SHALLOW AQUIFER QC-GP-8 06/22/09
<2000 SHALLOW AQUIFER QC-GP-8 07/13/09
<2000 SHALLOW AQUIFER QC-GP-8 08/12/09
<2000 SHALLOW AQUIFER QC-GP-8 09/01/09
<2000 SHALLOW AQUIFER QC-GP-8 10/05/09
<2000 SHALLOW AQUIFER QC-GP-8 11/02/09
<2000 SHALLOW AQUIFER QC-GP-8 12/01/09
<2000 SHALLOW AQUIFER QC-GP-9 01/05/09 86,700 SHALLOW AQUIFER QC-GP-9 01/28/09 94,700 SHALLOW AQUIFER QC-GP-9 02/12/09 -
106,000 SHALLOW AQUIFER" QC-GP-9 03/06/09
<2000 SHALLOW AQUIFER QC-GP-9 03/30j09' 6,030 SHALLOW AQUIFER QC-GP-9 04/14/09 55,900 SHALLOW AQUIFER" QC-GP-9 05/03/09
<2000 SHALLOW AQUIFER QC-GP-9 05/26/09 57,600 SHALLOW AQUIFER QC-GP-9 06/22/09
<2000-SHALLOW AQUIFER*
QC-GP-9 07/13/09
'73,600 SHALLOW AQUIFER-QC-GP-9 08/12/09 172,000 SHALLOW AQUIFER QC-GP-9 09/01/09 126,000 SHALLOW AQUIFER' QC-GP-9 09/18/09 189,000' SHALLOW AQUIFER QC-GP-9 10/05/09' 313,000 SHALLOW AQUIFER QC-GP-9 10/19/09" 156,000 SHALLOW AQUIFER' QC-GP-9 11/02/09 69,800' SHALLOW AQUIFER QC-GP-9 11/16/09 i7,400 SHALLOW AQUIFER QC-GP-9 12/01/09
<2000 SHALLOW AQUIFER QC-GP-9 12/14/09
<2000 SHALLOW AQUIFER QC-GP-10 01/05/09
<2000 SHALLOW AQUIFER QC-GP-10 03/06/09
<2000 SHALLOW AQUIFER QC-GP-10 03/30/09
<2000 SHALLOW AQUIFER QC-GP-10 04/14/09 507 SHALLOW AQUIFER QC-GP-10 05/03/09
<2000 SHALLOW AQUIFER QC-GP-10 05/26/09
<2000 SHALLOW AQUIFER QC-GP-10 06/22/09
<2000 SHALLOW AQUIFER QC-GP-10 07/13/09
<2000 SHALLOW AQUIFER QC-GP-10 08/12/09
<2000 SHALLOW AQUIFER QC-GP-10 09/01/09 3,670 SHALLOW AQUIFER QC-GP-10 10/05/09
<2000 SHALLOW AQUIFER QC-GP-10 11/02/09
<2000 SHALLOW AQUIFER QC-GP-10 12/01/09
<2000 SHALLOW AQUIFER QC-GP-11 01/05/09 20,600 SHALLOW AQUIFER QC-GP-1 1 01/28/09 17,700 SHALLOW AQUIFER QC-GP-1 1 02/12/09 15,700 SHALLOW AQUIFER B-9 106 of 109
TABLE B-i11.1 CONCENTRATIONS OF'TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2009 RESULTS IN UNITS OF PCI/LITER COLLECTION SITE DATE ACTIVITY AQUIFER QC-GP-1 1 03/06/09 17,700 SHALLOW AQUIFER QC-GP-1 1 03/30/09 43,500.
SHALLOW AQUIFER QC-GP-1 1 04/14/09-70,200 SHALLOW AQUIFER QC-GP-1 1 05/03/09 79,200 SHALLOW AQUIFER QC-GP-1 1 05/26/09 98,400 SHALLOW AQUIFER QC-GP-11 06/22/09 31,600 SHALLOW AQUIFER QC-GP-11 07/13/09 26,500 SHALLOW AQUIFER.
QC-GP-11 08/12/09 25,700 SHALLOW AQUIFER QC-GP-11 09/01/09
.18,400 SHALLOW AQUIFER QC-GP-11 10/05/09 14,200 SHALLOW AQUIFER QC-GP-11 11/02/09 13,000 SHALLOW AQUIFER QC-GP-11 12/01/09 18,800 SHALLOW AQUIFER QC-GP-12 01/05/09
<2000 SHALLOW AQUIFER QC-GP-12 03/06/09.,
,;2000 SHIALLOW AQUIFER QC-GP-12 03/30/09
<2000 SHALLOW AQUIFER QC-GP-12 04/14/09
<200 SHALLOW AQUIFER QC-GP-12 05/03/09ý
<2000 SHALLOW AQUIFER QC-GP-12 05/26/09.,
<2000 SHALLOW AQUIFER QC-GP-12 06122/.09
<2000 SHALLOW AQUIFER QC-GP-12 07/13/09
<2000, SHALLOW AQUIFER QC-GP-12 08/12/09
<2000 SHALLOW AQUIFER QC-GP-12 09/01/09
<2000.
SHALLOW AQUIFER QC-GP-12 10/05/09
<2000 SHALLOW AQUIFER QC-GP-12 11/02/09
'<2'000 SHALLOW AQUIFER QC-GP-12 12/01/09
<2060 SHALLOW AQUIFER QC-GP-13 01/05/09 48,300 SHALLOW AQUIFER QC-GP-13 01/28/09 16,500 SHALLOW AQUIFER QC-GP-13 02/12/09 10,100 SHALLOW AQUIFER QC-GP-13 03/06/09 39,700 SHALLOW AQUIFER QC-GP-13 03/30/09 162,000 SHALLOW AQUIFER QC-GP-13 04/14/09 165,000 SHALLOW AQUIFER QC-GP-13 05/03/09 184,000 SHALLOW AQUIFER QC-GP-13 05/26/09 160,000 SHALLOW AQUIFER QC-GP-13 06/22/09 94,900 SHALLOW AQUIFER QC-GP-13 07/13/09 85,800 SHALLOW AQUIFER QC-GP-13 08/12/09 31,300 SHALLOW AQUIFER QC-GP-13 09/01/09 140,000 SHALLOW AQUIFER QC-GP-13 09/18/09 30,500 SHALLOW AQUIFER QC-GP-13 10/05/09 36,200 SHALLOW AQUIFER QC-GP-13 11/02/09 52,400 SHALLOW AQUIFER QC-GP-13 11/16/09 190,000 SHALLOW AQUIFER QC-GP-13 12/01/09 147,000 SHALLOW AQUIFER QC-GP-13 12/14/09 206,000 SHALLOW AQUIFER QC-GP-14 01/05/09 597,000 SHALLOW AQUIFER QC-GP-14 01/28/09 740,000 SHALLOW AQUIFER QC-GP-14 02/12/09 771,000 SHALLOW AQUIFER QC-GP-14 03/06/09 771,000 SHALLOW AQUIFER QC-GP-14 03/27/09 390,000 SHALLOW AQUIFER QC-GP-14 03/30/09 404,000 SHALLOW AQUIFER QC-GP-14 04/14/09 592,000 SHALLOW AQUIFER QC-GP-14 05/03/09 740,000 SHALLOW AQUIFER B-10 107 of 109
TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2009 RESULTS IN UNITS OF PCI/LITER SITE QC-GP-14 QC-GP-14 QC-GP-14 QC-GP-14 QC-GP-14 QC-GP-14 QC-GP-14 QC-GP-14 QC-GP-14 QC-GP-14 QC-GP-14 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 QC-GP-15 MW-QC-1051 MW-QC-1051 MW-QC-1 051 MW-QC-1 051 MW-QC-1051 MW-QC-1051 SURFACE WATER #1 SURFACE WATER #1 SURFACE WATER #2 SURFACE WATER #2 WELL #1 WELL #1 WELL #1 WELL #1 WELL #5 WELL #5 WELL #5 WELL #5 WELL #6 WELL #6 WELL #6 WELL #6 WELL #7 COLLECTION DATE 05/26/09 06/22/09 07/13/09 08/12/09 09/01/09 09/18/09 10/05/09' 11/02/09 11/16/09 12/01/09 12/14/09 01/05/09 01/28/09 02/12/09 03/06/09 03/36/09 04/14/09 05/03/09 05/26/09 06/22/09 07/13/09 08/12/09 09/01/0"9 10/05/09 11/02/09 12/01/09 03/31/09 04/14/09 05/04/09 09/02/09 10/07/09.
12/02/09 04/14/09 12/02/09 04/14/09 12/02/09 03/09/09 06/01/09 08/24/09 11/02/09 03/09/09 06/01/09 08/24/09 11/02/09 03/09/09 06/01/09 08/24/09 11/02/09 03/09/09 ACTIVITY 516,000 313,000 197,000 62,100 70,900-62,500 32,600 51,400 102,000 199,000 356,000 4,680 9,500 6,950 4,620-9,700 14,300 5,690
<2000' 6,690 14,300 5,930
<2000
<2000
<2000
<2000 62,300 27,100 39,000 99,200 92,500"
<2000
<200
<200
<200
<200'
<200
<200
<200
<2Q0
<200
<200
<200
<200
<200
<200
<200
<200
<200 AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER' SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER-SHALLOW AQUIFER SHALLOW AQUIFER SHALLOW AQUIFER
-I B-11 108 of 109
TABLE B-Ill.1 CONCENTRATIONS OF TRITIUM IN GROUNDWATER SAMPLES COLLECTED AND ANALYZED BY QUAD CITIES STATION PERSONNEL, 2009 RESULTS IN UNITS OF PCI/LITER SITE WELL #7 WELL #7 WELL #7 WELL #7 WELL #7 WELL #7 WELL #8 WELL #8 WELL #8 WELL #8 WELL #9 WELL #9 WELL #9 WELL #9 WELL #10 WELL #10 WELL #10 WELL #10 WELL #11 WELL #11 WELL #11 WELL #11 STP SAND POINT STP SAND POINT STP SAND POINT STP SAND POINT COLLECTION DATE 06/01/09 08/24/09 09/02/09 10/07/09 11/02/09 12/02/09 03/09/09 06/01/09 08/24/09 11/02/09 03/09/09 06/01/09 08/24/09 11/02/09 03/09/09 06/01/09 08/24/09 11/02/09 03/09/09 06/01/09 08/24/09 11/02/09 03/09/09 06/01/09 08/24/09 11/02/09 ACTIVITY
<200 246
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200
<200 AQUIFER B-I2 109 of 109