ML101230140

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Byron, Units 1 and 2, 2009 Annual Radiological Effluent Release Report
ML101230140
Person / Time
Site: Byron  Constellation icon.png
Issue date: 04/30/2010
From:
Exelon Generation Co, Exelon Nuclear
To:
Office of Nuclear Reactor Regulation
References
BYRON 2010-0029
Download: ML101230140 (50)
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Text

BYRON NUCLEAR POWER STATION ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT (ARERR)2009 Page 1 of94 BYRON NUCLEAR POWER STATION UNIT 1/2 DOCKETNUMBERSTN-50-454/455 RADIOACTIVE EFFLUENT RELEASE REPORT January 2009-December 2009 Supplemental Information 1.Regulatory Limits a.Fission and activation gases: Tech Spec Whole Body=Skin=10CFR50 Gamma=Beta=500 mrem/year 3000 mrem/year 5 mrad/quarter; 10 mrad/year 10 mrad/quarter; 20 mrad/year b.Iodine: (summed with particulate, see below)c.Particulates with half-lives>

8 days: Tech Spec Organ=10CFR50 Organ=d.Liquid Effluents:

1 OCFR50 Whole Body=Organ=e.Total Effective Dose Equivalent:

10CFR20 TEDE=2.Maximum Permissible Concentration 1500 mrem/year 7.5 mrem/quarter; 15 mrem/year 1.5 mrem/quarter; 3 mrem year 5 mrem/quarter; 10 mrem/year 100 mrem/year a.Fission and Activation Gases: 1 OCFR20 Appendix B Table 2 b.Iodine: 1 OCFR20 Appendix B Table 2 c.Particulates:

1 OCFR20 Appendix B Table 2 d.Liquid Effluents:

10 X 10CFR20 Appendix B Table 2 3.Average Energy: This item is not applicable.

Release rates are calculated using an isotopic mix rather than average energy.4.Measurements and Approximations of Total Radioactivity a.Fission and activation gases: Prior to release, the isotopic content is determined.

Released activity is calculated using volume of release, which is determined by the change in tank or containmentpressure.Additional methods of calculation utilize historical data and assign an isotopic mix, which is representative of normal vent stack isotopics.

b.Particulate, tritium and iodine sampling media for the plant vent stacks are collected and isotopically analyzed weekly.c.Liquid effluents:

Isotopic analysis is performed on each batch release prior to its release.Total release activity is calculated using volume of release.Total tritium activity released is calculated Page 2 of 94 from the highest of a monthly circulating water blowdown composite activity or a sum of the input composite activities.

d.Analysis results that are less than the lower limit of detection<<LLD)are reported in units of uCi/cc or uCi/ml unless otherwise noted.All LLD values are listed in Attachment A.5.Batch Releases: a.Liquid: 1.Number of batch releases=76 2.Total time period for batch releases=10,837 minutes 3.Maximum time period for a batch release=441 minutes 4.Average time period for a batch release=143 minutes 5.Minimum time period for a batch release=45 minutes 6.Average stream flow during periods of release of effluent into a flowing stream=309 m 3/sec, based on information from the U.S.Geological Survey Byron Gauging Station.b.Gaseous: 1.Number of batch releases=314 2.Total time period for batch releases=31,765 minutes 3.Maximum time period for a batch release=3,333 minutes 4.Average time period for batch releases=101 minutes 5.Minimum time period for a batch release=10 minutes 6.Abnormal Releases: a.Liquid-None b.Gaseous-None 7.2009 Radiological Groundwater Protection Program (RGPP)Results Summary: In 2009, the number of Radiological Groundwater Protection Program (RGPP)monitoring wells sampled was reduced from 22 to 13 based on the evaluation and recommendation from an environmental consulting firm.The 9 wells removed from the sampling program in 2009 had not tested positive for tritium since the program began in 2006 and were determined to be low risk for contamination based on their locations commensurate with local hydrogeology.

The samples obtained from the 13 wells in 2009 were obtained in April and October and analyzed for tritium.Of these samples, two wells contained levels of tritium above the lower limit of detection (LLD)of 200 pCi/L.They were: AR-4 (1350 pCi/L in April, 1360 pCi/L in October)and AR-11 (1110 pCi/L in April, 1010 pCi/L in October).Both of these wells are near the Circulating Water Blowdown piping, where historical leakage through vacuum breakers was known to have occurred.Well AR-4 has shown an overall steady decrease in tritium concentration since first sampled in 2006.Well AR-11 has also shown an overall decrease in tritium since 2006, and a slight decrease from 2008.The dose consequence from tritium present in these sample wells is negligible.

8.2007 Errata During the week of 8/3/2009, the biennial Nuclear Regulatory Commission (NRC)inspection per NRC inspection manual 71122.02, Radioactive Material Processing and Transportation, identified that resin radioactive waste shipment RWS07-015 on 12/5/07 used incorrect samples and scaling factors to characterize the resin.During the extent of condition review, one other resin shipment, RWS07-016 on 12/12/07, was found to contain the same error as found in shipment RWS07-015.Aftercharacterizing the shipments using the proper scaling factors, the waste shipment classification (Class Page 3 of 94 "C")did not change, however, the new radionuclide makeup resulted in minor changes to the total curie content of the shipments.

Using the correct scaling factors, shipment RWS07-015 on 12/5/07 went from 211 to 288 curies.Shipment RWS-07-016 on 12/12/07 went from 338 to 203 curies.Below are the corrected shipment and quarterly curie totals: SOLID RADIOACTIVE WASTE FOR BURIAL 4 TH QUARTER 2007 DISPOSITION OF MATERIAL MODE OF VOLUME CURIES*DATE (DESCRIPTION, CLASS, TYPE TRANSPORT DESTINATION PER PER AND SOLIDIFYING AGENT)SHIPMENTSHIPMENT RADIOACTIVE MATERIAL, LOW SPECIFIC 10108/07 ACTIVITY (LSA-I), 7, UN2912, CLASS A, EXCLUSIVE-USE Oak Ridge, TN 9.23E+00 4.62E-03 GENERAL DESIGN PACKAGE, 20'METAL BOX, NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 11/28/07 ACTIVITY (LSA-II), 7, UN3321, CLASS B, TYPE EXCLUSIVE-USE Barnwell, SC 2.63E+00 4.19E+01 B(U)PACKAGE, CASK, NONE RADIOACTIVE MATERIAL, TYPE B(U)1215/07 PACKAGE, 7, UN2916, CLASS C, TYPE B(U)EXCLUSIVE-USE Barnwell, SC2.63E+002.88E+02 PACKAGE,CASK,NONE RADIOACTIVE MATERIAL, TYPE B(U)12112107 PACKAGE, 7, UN2916, CLASS C, TYPE B(U)EXCLUSIVE-USE Barnwell, SC 2.63E+00 2.03E+02 PACKAGE, CASK, NONE Quarterly Totals Number of 4 1.71 E+01 5.33E+02 Shipments:

  • Calculated using measured ratios CUBIC M CURIES Page 4 of94

SUMMARY

Calculations based on gaseous and liquid effluents, Rock River flow and average/concurrent meteorological data indicate that public dose due to radioactive material attributable to Byron Station during the reporting period did not exceed any limits listed in the Regulatory Limits section.The Total Effective Dose Equivalent (TEDE)due to licensed activities at Byron Station calculated for the maximum-exposed individual for the period is 3.09E-01 mrem.The annual limit on TEDE is 100 mrem.The assessment of radiation doses to the public is performed in accordance with the ODCM.The results of these analyses confirm that the station is operating in compliance with 10CFR50 Appendix I, 10CFR20 and 40CFR190.There were no additional operational controls implemented which affected the areas of radiological effluents in 2009.There were no measurements which exceeded the reporting levels, including any which would not have been attributable to station effluents.

The results of the current radiological environmental monitoring program are approximately the same as those found during the pre-operational studies conducted at Byron Station.Gaseous Effluents to the Atmosphere A total of 1.20E+01 curies of fission and activation gases were releasedwitha maximum average quarterly release rate of 1.33E+00 IJCi/sec.A total of 1.01 E-04 curies of 1-131 were released during the yearwitha maximum average quarterly release rate of 6.41 E-06 IJCi/sec.A total of 1.51 E-05 curies were released as airborne particulate matterwitha maximum average quarterly release rate of 1.12E-06 IJCi/sec.Alpha-emitting radionuclides were below detectable limits.A total of O.OOE+OO curies of other radioisotopes were releasedwitha maximum average quarterly release rate of O.OOE+OO IJCi/sec.A total of 1.05E+02 curies of tritium were releasedwitha maximum average quarterly release rate of 2.60E+00 IJCi/sec.Liquids Released to Rock River A total of 2.76E+10 liters of radioactive liquid wastes (prior to dilution)containing 2.1 OE-02 curies (excluding tritium, noble gases and alpha)were discharged from the station.These wastes were released at a maximum quarterly average concentration of 1.01 E-09 IJCi/ml.A total of 1.81 E+03 curies of tritium were released.Page 5 of 94 Gamma Dose Rates Offsite Gamma air and whole body dose rates were calculated based on measured release rates, isotopic composition of the noble gases, and average meteorological data for the period.Based on measured effluents and average meteorological data, the maximum totalbodydose to an individual would be 1.73E-02 mrem for the year, with an occupancy or shielding factor of 0.7 included.The maximum totalbodydose based on measured effluents and concurrent meteorological data would be 9.72E-06 mrem.The maximum gamma air dose was 1.64E-04 mrad based on measured effluents and average meteorological data, and 1.93E-05 mrad based on concurrent meteorological data.Beta Air and Skin Dose Rates The range of beta particles in air is relatively small (on the order of a few meters or less);consequently,plumes of gaseous effluents may be considered"semi-infinite" for purpose of calculating the dose from beta radiation incident on the skin.However, the actual dose to sensitive skin tissues is difficult to calculate due totheeffect of the beta particle energies, thickness of inert skin and clothing covering sensitive tissues.For purposes of this report the skin is taken to have a thickness of 7.0 mg/cm 2 and an occupancy factor of 1.0 is used.The skin dose based on concurrent meteorological data for the year was 2.52E-04 mrem.The maximum offsite beta air dose for the year, based on measured effluents and average meteorological data, was 6.36E-04 mrad.The beta air dose based on concurrent meteorological data was 4.52E-04 mrad.Radioactive Iodine The human thyroid exhibits a significant capacity to concentrate ingested or inhaled iodine.The minimal levels of radioiodine,1-131,released during routine operation of the station, may be made available to man resulting in a dose to the thyroid.The principal pathway of interest for this radionuclide is ingestion of radioiodine in milk.Calculations made for 2009 and previous years indicate that contributions to doses from inhalation of 1-131 and 1-133 and ingestion of 1-133 in milk are negligible.

The hypothetical thyroid dose to the maximum exposed individual living near the station via ingestion of milk was calculated.

The radionuclide considered was 1-131 and the source of milk was taken to be the nearest dairy farm with the cows pastured from May through October.The maximum thyroid dose was 7.1 OE-02 mrem during the year (infant).Liquid Effluent Pathways The three principal pathways through the aquatic environment for potential doses to man from liquid waste are ingestion of potable water, eating aquatic foods, and exposure while on the shoreline.

Not all of these pathways are significant or applicable at a given time or station but a reasonable approximation of the dose can be made by adjusting the dose formula for season of the year or type and degree of use of the aquatic environment.

NRC developed equations were used to calculate the doses to the whole body, lower GI tracts, thyroid, bone and skin;specific parameters for use in the equations are given in the Exelon Offsite Dose Calculation Manual.The maximum whole body dose for the year was 2.92E-01 mrem (adult)and no organ dose exceeded 3.60E-01 mrem (adult).Page 6 of 94 Site Meteorology A summary of the site meteorological measurements taken during each calendar quarter of the year is included in the Annual Radiological Environmental Operating Report (AREOR)or is retained on file to be provided upon request.The data are presented as cumulative joint frequency distributions of the wind direction for the 250'levelandwind speed class by atmospheric stability class determined from the temperature difference between the 250'and 30'levels.Data recovery for all measurements on the tower was 99.8%during 2009.Page 7 of 94 SOLID RADIOACTIVE WASTE FOR BURIAL 1 ST QUARTER 2009 DISPOSITION OF MATERIAL MODE OF DESTINATION VOLUME (m 3)CURIES*DATE (DESCRIPTION, CLASS, TYPE AND TRANSPORT PER PER SOLIDIFYING AGENT)SHIPMENT SHIPMENT RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCEPTED, CLASS A, EXCLUSIVE-USE 9.77E-02 2/12/09 GENERAL DESIGN PACKAGE (GOP), 20'METAL BOX Oak Ridge, TN 6.52E+01 (2), NONE RADIOACTIVE MATERIAL, EXCEPTED PACKAGE 3/9/09 LIMITED QUANTITY OF MATERIAL, 7, UN2910, EXCLUSIVE-USE FISSILE EXCEPTED, CLASS A, GENERAL DESIGN Oak Ridge, TN 2.13E+01 8.23E-03 PACKAGE (GOP), 20'METAL BOX (3), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY 3/24/09 (LSA-II), 7, UN3321 , FISSILE EXCEPTED, CLASS A, EXCLUSIVE-USE GENERAL DESIGN PACKAGE (GOP), 20'METAL Oak Ridge, TN 3.21E+01 1.16E-01 BOX, NONE RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY 3/31/09 (LSA-II), 7, UN3321, FISSILE EXCEPTED, CLASS A, EXCLUSIVE-USE GENERAL DESIGN PACKAGE (GOP), 20'METAL BOX Oak Ridge, TN 6.80E+01 8.99E-02 (2), NONE Quarterly Totals Number of 4 1.87E+02 3.12E-01 Shipments:

  • Calculated using measured ratios CUBIC M CURIES Page 8 of 94 SOLID RADIOACTIVE WASTE FOR BURIAL 2 ND QUARTER 2009 DISPOSITION OF MATERIAL MODE OF VOLUME CURIES*DATE (DESCRIPTION, CLASS, TYPE TRANSPORT DESTINATION (m 3)PER PER AND SOLIDIFYING AGENT)SHIPMENT SHIPMENT RADIOACTIVE MATERIAL, EXCEPTED PACKAGE LIMITED QUANTITY OF MATERIAL, 4/1/09 7, UN291O, FISSILE EXCEPTED, CLASS A, EXCLUSIVE-USE Clive, UT 4.76E+Ol 6.83E-Q3 GENERAL DESIGN PACKAGE (GOP), POL YETHEL YNE LINER, NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 4/8/09 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Clive, UT 4.53E+00 2.04E+Ol EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GOP), CASK, NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 4114/09 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Clive, UT 4.67E+00 1.03E+Ol EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GOP), CASK, NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 5/11/09 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 2.07E+Ol 7.77E-03 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GOP), 20'METAL BOX (3), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 5/13109 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 6.63E+Ol 3.96E-02 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GOP), 20'METAL BOX (2), NONE Quarterly Totals Number of 5 1.44E+02 3.08E+01 Shipments:
  • Calculated using measured ratios CUBICM CURIES Page 9 of 94 SOLID RADIOACTIVE WASTE FOR BURIAL 3 RD QUARTER 2009 DISPOSITION OF MATERIAL MODE OF VOLUME CURIES*DATE (DESCRIPTION, CLASS, TYPE DESTINATION (m 3)PER PER AND SOLIDIFYING AGENT)TRANSPORT SHIPMENT SHIPMENT RADIOACTIVE MATERIAL, LOW SPECIFIC 7/22109 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 6,80E+01 7,35E-02 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GOP), 20'METAL BOX (2), NONE RADIOACTIVE MATERIAL, EXCEPTED PACKAGE LIMITED QUANTITY OF MATERIAL, 8/28/09 7, UN2910, FISSILE EXCEPTED, CLASS A, EXCLUSIVE-USE Oak Ridge, TN 1,04E+01 4,87E-03 GENERAL DESIGN PACKAGE (GOP), 20'METAL BOX, NONE Quarterly Totals Number of 2 Shipments:

7.84E+01 7.84E-02*Calculated using measured ratios CUBIC M CURIES Page 10 of 94 SOLID RADIOACTIVE WASTE FOR BURIAL 4 TH QUARTER 2009 DISPOSITION OF MATERIAL MODE OF VOLUME(m 3)CURIES'DATE (DESCRIPTION, CLASS, TYPE TRANSPORT DESTINATION PER PER AND SOLIDIFYING AGENT)SHIPMENTSHIPMENT RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-/l), 7, UN3321, FISSILE 10/14/09 EXCEPTED, CLASS A, GENERAL DESIGN EXCLUSIVE-USE Clive, UT 4.53E+OO 3.07E+00 PACKAGE (GOP), HIGH INTEGRITY CONTAINER, NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 10/21/09 ACTIVITY (LSA-II), 7, UN3321, CLASS A, EXCLUSIVE-USE Clive, UT 4.81 E+OO 8.17E+00 GENERAL DESIGN PACKAGE (GOP), HIGH INTEGRITY CONTAINER, NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 11/6/09 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 6.73E+01 7.52E-02 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GOP), 20'METAL BOX (2), NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 12/2/09 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 2.53E+01 2.04E-01 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GDP), 20'METAL BOX, NONE RADIOACTIVE MATERIAL, LOW SPECIFIC 12/3109 ACTIVITY (LSA-II), 7, UN3321, FISSILE EXCLUSIVE-USE Oak Ridge, TN 6.80E+01 2.51E-01 EXCEPTED, CLASS A, GENERAL DESIGN PACKAGE (GOP), 20'METAL BOX (2), NONE Quarterly Totals Number of 5 1.70E+02 1.18E+01 Shipments:

  • Calculated using measured ratios CUBIC M CURIES Page 11 of 94 Resins, Filters, Evap Bottoms 2009 Volume (m3)1.85E+01 Class A Nuclide%Adund Curies uCi/ml H-3 56.089 2.35E+01 1.27E+00 C-14 0.351 1.47E-01 7.95E-03 CR-51 0.002 9.82E-04 5.31 E-05 MN-54 1.174 4.93E-01 2.66E-02 FE-55 7.168 3.01E+00 1.63E-01 FE-59 0.002 9.33E-04 5.04E-05 CO-57 0.450 1.89E-01 1.02E-02 CO-58 14.027 5.89E+00 3.18E-01 CO-60 10.437 4.38E+00 2.37E-01 NI-59 0.153 6.40E-02 3.46E-03 NI-63 7.351 3.08E+OO 1.66E-01 ZN-65 0.113 4.75E-02 2.57E-03 SR-89 0.000 1.20E-04 6.49E-06 SR-90 0.009 3.82E-03 2.06E-04 ZR-95 0.009 3.90E-03 2.11 E-04 NB-95 0.002 8.75E-04 4.73E-05 TC-99 0.012 4.94E-03 2.67E-04 RU-103 0.000 1.07E-06 5.78E-08 AG-110M 0.012 4.99E-03 2.70E-04 SN-113 0.004 1.84E-03 9.95E-05 SB-124 0.001 3.06E-04 1.65E-05 SB-125 1.567 6.57E-01 3.55E-02 TE-123M 0.002 9.40E-04 5.08E-05 TE-125M 0.005 2.19E-03 1.18E-04 1-129 0.000 4.35E-05 2.35E-06 CS-134 0.039 1.63E-02 8.81 E-04 CS-137 0.426 1.79E-01 9.68E-03 CE-144 0.562 2.36E-01 1.28E-02 PU-238 0.000 4.11E-05 2.22E-06 PU-239 0.000 1.98E-05 1.07E-06 PU-241 0.033 1.39E-02 7.51E-04 AM-241 0.000 1.02E-05 5.51E-07 CM-242 0.000 6.70E-06 3.62E-07 CM-243 0.000 1.03E-05 5.57E-07 SOLID RADIOACTIVE WASTE FOR BURIAL Estimated Solid Waste CompositIon 2009 Drv Active Waste 2009 Volume (m3)5.50E+02 Class A Nuclide%Adund Curies uCVml H-3 3.845 3.73E-02 6.78E-05 C-14 0.046 4.45E-04 8.09E-07 CR-51 3.751 3.64E-02 6.62E-05 MN-54 1.469 1.43E-02 2.60E-05 FE-55 23.929 2.32E-01 4.22E-04 FE-59 0.803 7.79E-03 1.42E-05 CO-57 0.142 1.38E-03 2.51E-06 CO-58 23.267 2.26E-01 4.11E-04 CO-60 17.682 1.72E-01 3.13E-04 NI-59 0.051 4.93E-04 8.96E-07 NI-63 13.884 1.35E-01 2.45E-04 ZN-65 0.034 3.31E-04 6.02E-07 SR-90 0.006 6.16E-05 1.12E-07 ZR-95 3.615 3.51 E-02 6.38E-05 NB-95 4.918 4.77E-02 8.67E-05 TC-99 0.875 8.48E-03 1.54E-05 SN-113 0.052 5.02E-04 9.13E-07 SB-125 0.520 5.04E-03 9.16E-06 TE-123M 0.029 2.81E-04 5.11 E-07 1-129 0.000 2.59E-06 4.71E-09 CS-137 0.159 1.54E-03 2.80E-06 CE-144 0.467 4.53E-03 8.24E-06 PU-238 0.038 3.73E-04 6.78E-07 PU-239 0.018 1.78E-04 3.24E-07 PU-241 0.359 3.48E-03 6.33E-06 AM-241 0.010 9.27E-05 1.69E-07 CM-242 0.020 1.91E-04 3.47E-07 CM-243 0.011 1.08E-04 1.96E-07 Page 12 of 94 Irradiated Components 2009-No Shipments Volume (m3)O.OOE+OO Class N/A%Abund Curies uCi/ml Other Waste (Oil)2009 Volume (m3)1.04E+01 Class A%Abund Curies uCi/ml H-3 99.970 4.87E-03 4.68E-04 C-14 0.000 1.10E-09 1.06E-10 FE-55 0.004 1.97E-07 1.89E-08 CO-60 0.0031.68E-071.62E-08 NI-59 0.000 2.28E-09 2.19E-10 NI-63 0.003 1.63E-07 1.57E-08 SR-90 0.000 2.42E-09 2.33E-10 TC-99 0.000 8.05E-09 7.74E-10 1-129 0.000 2.92E-12 2.81E-13 CS-137 0.002 1.14E-07 1.10E-08 CE-144 0.017 8.14E-07 7.83E-08 PU-238 0.000 4.24E-10 4.08E-11 PU-239 0.000 2.01E-1O 1.93E-11 PU-241 0.000 3.72E-09 3.58E-10 AM-241 0.000 1.08E-10 1.04E-11 CM-242 0.000 4.99E-11 4.80E-12 CM-243 0.000 1.69E-10 1.63E-11 Process Control Program (PCP)for Radioactive Wastes During the calendar year 2009, no changes were implemented to RW-AA-100, Process Control Program for Radioactive Wastes.Page 13 of 94 Error Analysis The following is an estimate of the errors associated with effluent monitoring and analysis.The estimate is calculated using the square root of the sum of the squares methodology.1.Gaseous Effluents Ome=3.33%RM=N/A ECe=5%Stdcse/Smplcse=5%

gme=N/A Total error=7.8%2.Liquid Effluents Ome=3.33%RM=N/A ECe=N/A Stdcse/Sm plcse=5%qme=2.22%Total error=6.4%3.Waste Resin Ome=10.0%RM=N/A ECe=5%Stdcse/Smplcse=5%

gme=1.0%Total error=12.3%4.DAW, Mechanical Filters, and Contaminated Metal Ome=10.0%RM=N/A ECe=N/A Stdcse/Smplcse=5%

qme=N/A Instrument calibration error=10%Total error=11.2%Definition of Terms Ome=the process quantity measurement error associated with the release point (e.g.flow, level measurements)

Page 14 of94 RM=error associated with the radiation monitor used in quantifying releases through the release point EGe=error associated with the collection efficiency of the sample media Stdcse=one-sigma counting error associated with the counting instrument of interest Smplcse=one-sigma counting error associated with a sample of a given geometry that is used for the release point of interest qme=sample quantity measurement error associated with the sample of interest Page 15 of Miscellaneous Information A.As required by Technical Specification 5.6.2, meteorological and environmental impact information is reported in the Station Annual Radiological Environmental Operating Report or is retained on file to be provided upon request.B.No limits were exceeded in liquid hold up tanks as stated in Technical Specification 5.5.12 or in waste gas decay tanks as stated in Technical Specification 5.5.12.C.There were no irradiated fuel shipments during this reporting period.D.There were no REMP sample results that exceeded any technical specification limits or analytical results investigation levels during this reporting period.REMP third quarter composite surface water sample from point BY-12, Rock River downstream of the plant liquid effluent discharge, had a tritium result of 725 pCi/L.Althoughthis result is well below the reportable limit of 30,000 pCi/L, tritium is not typically observed above the detection limit in this sample under normal operating conditions.

The positive tritium result was likely due to the increase in liquid releases performed prior to and during the refueling outage beginning in September 2009.REMP November milk control sample result from26-1 was 3.58 pCi/L for 1-131, above the LLD of 1.00 pCi/L and the reportable limit of 3.00 pCi/L.This result was determined to be a false positive due to nuclide interference as a result of sample preparation contamination, asthesample was recounted one week later and showed an increase in activity, which is not consistent with radioactive decay of 1-131.Milk samples from other plants in the same time period also had similar results.The issue has been properly documented via the vendor laboratory corrective action process.E.There were no elevated releases during this reporting period.All releases are considered vent or ground level releases.F.There were no plant effluent radiation release monitors that exceeded inoperability time limits as stated in TRM TLCO 3.11.a, TRM TLCO 3.11.b, or Technical Specification 5.5.12.G.There were no unplanned or abnormal releases from the site to unrestricted areas during this reporting period.H.Revision 6 of the ODCM was issued on May of 2009.The revision included literature and references that were added to include the planned commencement of Independent Spent Fuel Storage Installation (ISFSI), updates to REMP sample locations and TLD locations, and editorial changes.Although originally planned for 2009, the ISFSI campaign experienced delays, and no spent fuel was moved in 2009.None of the changes to the ODCM affected the ability to maintain the level of radioactive effluent control required by 10CFR20, 40CFR190, or 10CFR50, nor did the changes impact the accuracy or reliability of effluent dose or set point calculations.

I.Attached are offsite dose calculation reports for January through December of 2009.Page 16 of 94 Attachment A, 2009 Radioactive Effluent Release Report 2009 Lower Limits of Detection (LLD's)Gaseous Liquid Nuclide LLD (uCi/cc)Nuclide LLD (uCVml)H3 6.26E-08 H3 2.05E-06 Ar41 4.55E-07 Na24 3.27E-08 Cr51 3.05E-12 Cr51 2.10E-07 Mn54 6.23E-13 Mn54 3.56E-08 Co58 7.55E-13 Fe55 9.30E-07 Fe59 1.58E-12 Co57 2.20E-08 Co60 1.14E-12 Co58 3.12E-08 Zn65 3.38E-13 Fe59 8.86E-08 Br82 6.22E-13 Co60 5.10E-08 Kr85m 1.50E-07 Zn65 8.53E-08 Kr87 4.30E-07 Sr85 3.81E-08 Kr88 4.87E-07 Sr89 3.65E-07 Sr89 3.09E-14 Sr-90 6.23E-09 Sr-90 1.97E-15 Sr92 4.01E-08 Mo99 2.44E-13 Nb95 6.78E-09 1131 5.00E-13 Zr95 6.90E-08 Xe131m 6.58E-06 Mo99 2.14E-08 1133 7.87E-13 Ag110m 3.25E-08 Xe133 4.11E-07 Sb122 4.73E-08 Xe133m 1.71E-06 Te123m 2.29E-08 Cs134 4.80E-13 Sb124 1.03E-07 1135 3.07E-12 Sb125 8.52E-08 Xe135 1.94E-07 Te125m 6.95E-06 Cs137 3.44E-13 Sb126 3.76E-08 Xe138 6.97E-07 1131 2.89E-08 Ba140 2.00E-12 1132 2.08E-08 La140 2.58E-13 Te132 2.48E-08 Ce141 5.36E-13 1133 3.80E-08 Ce144 1.93E-12 Xe133 5.90E-08 Gross Alpha 4.09E-13 Cs134 3.73E-08 Xe135 2.77E-08 Cs137 3.05E-08 Ba140 1.07E-07 La140 1.42E-08 Ce141 4.06E-08 Ce144 1.67E-07 Gross Alpha 8.31E-08 Page 17 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 2009 Unit 1 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products 1.Total Release Ci 2.Avg.Diluted Conc.uCi/ml Tritium 1.Total Release Ci 2.Avg.Diluted Conc.uCi/ml Dissolved and Entrained Gases 1.Total Release Ci 2.Avg.Diluted Conc.uCi/ml Gross Alpha Radioactivity 1.Total Release Ci Volume of liquid waste liters 3.3SE-03 1.01E-09 1.63E+02 4.92E-OS 3.S4E-03 1.07E-09 O.OOE+OO 3.32E+09 2.64E-03 7.41E-IO 2.12E+02 S.96E-OS 4.88E-06 1.37E-12 O.OOE+OO 3.S6E+09 2.32E-03 6.49E-10 4.14E+02 1.16E-04 1.64E-03 4.S8E-10 O.OOE+OO 3.S8E+09 2.77E-03 8.38E-10 1.18E+02 3.S6E-OS O.OOE+OO O.OOE+OO O.OOE+OO 3.30E+09 1.0SE-02 7.61E-IO 9.07E+02 6.59E-05 S.18E-03 3.76E-10 O.OOE+OO 1.38E+10 Volume of dil.water litersO.OOE+OOO.OOE+OO O.OOE+OOO.OOE+OOO.OOE+OO Page 18 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A-Release Tank LIQUID EFFLUENTS-SUMMATION BY RELEASE POINT 2009 Unit 1 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products 1.Total Release Ci 2.Avg.Diluted Cone.uCi/ml Tritium 1.Total Release Ci 2.Avg.Diluted Cone.uCi/ml Dissolved and Entrained Gases 1.Total Release Ci 2.Avg.Diluted Cone.uCi/ml Gross Alpha Radioactivity 1.Total Release ci Volume of liquid waste liters 3.35E-03 6.23E-06 1.56E+02 2.91E-01 3.54E-03 6.58E-06 O.OOE+OO 5.38E+05 2.64E-03 4.91E-06 1.98E+02 3.69E-01 4.88E-06 9.08E-09 O.OOE+OO 5.37E+05 2.32E-03 1.68E-06 3.70E+02 2.68E-01 1.64E-03 1.18E-06 O.OOE+OO 1.38E+06 2.77E-03 3.88E-06 1.08E+02 1.51E-01 O.OOE+OO O.OOE+OO O.OOE+OO 7.14E+05 1.05E-02 3.30E-06 8.33E+02 2.62E-01 5.18E-03 1.63E-06 O.OOE+OO 3.17E+06 Volume of dil.water litersO.OOE+OOO.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 19 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A-Circulating Water Blowdown LIQUID EFFLUENTS-SUMMATION BY RELEASE POINT 2009 Unit 1 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products 1.Total Release Ci 2.Avg.Diluted Conc.uCi/ml Tritium 1.Total Release Ci 2.Avg.Diluted Conc.uCi/ml Dissolved and Entrained Gases 1.Total Release Ci 2.Avg.Diluted Cone.uCi/ml Gross Alpha Radioactivity 1.Total Release Ci Volume of liquid waste liters O.OOE+OO O.OOE+OO 6.96E+00 2.09E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.32E+09 O.OOE+OO O.OOE+OO 1.41E+01 3.96E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.56E+09 O.OOE+OO O.OOE+OO 4.41E+01 1.23E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3.58E+09 O.OOE+OO O.OOE+OO 9.61E+00 2.91E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.30E+09 O.OOE+OO O.OOE+OO 7.47E+01 5.43E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.38E+10 Volume of dil.water litersO.OOE+OOO.OOE+OOO.OOE+OOO.OOE+OOO.OOE+OO Page 20 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2B LIQUID EFFLUENTS-CONTINUOUS MODE 2009 Unit 1 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR---------------------

Fission and Activation Products**No Nuclide Activities

    • Tritium H-3 Ci 6.96E+00 1.41E+01 4.41E+01 9.61E+00 7.47E+01 Totals for Period...Ci Dissolved and Entrained Gases**No Nuclide Activities
    • Gross Alpha Radioactivity
    • No Nuclide Activities
    • 6.96E+00 1.41E+01 4.41E+01 9.61E+00 7.47E+01 Page 21 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2B LIQUID EFFLUENTS-BATCH MODE 2009 Unit 1 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and AG-llOM CO-57 CO-58 CO-60 CS-137 1-131 MN-54 NB-95 SB-124 SB-125 SR-85 TE-125M Activation Products Ci Ci Ci Ci Ci Ci ci Ci Ci Ci Ci ci O.OOE+OO 1.09E-05 2.48E-03 2.97E-04 O.OOE+OO O.OOE+OO 1.08E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.53E-05 5.36E-04 O.OOE+OO 1.70E-05 1.39E-03 4.38E-04 O.OOE+OO O.OOE+OO 1.07E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.62E-04 2.29E-05 8.07E-06 8.18E-04 6.48E-04 O.OOE+OO 1.34E-06 2.16E-05 O.OOE+OO 5.44E-06 1.34E-05 4.59E-06 4.48E-04 O.OOE+OO 2.66E-06 2.59E-03 1.14E-04 2.52E-06 O.OOE+OO 2.41E-06 1.36E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.29E-05 3.87E-05 7.28E-03 1.50E-03 2.52E-06 1.34E-06 4.55E-05 1.36E-06 5.44E-06 1.34E-05 1.99E-05 1.55E-03 Totals for Period...Ci Tritium H-3 Ci Totals for Period...Ci Dissolved and Entrained Gases KR-85 Ci XE-133 Ci Totals for Period...Ci Gross Alpha Radioactivity
    • No Nuclide Activities
    • 3.35E-03 2.42E-03 1.99E-03 2.71E-03 1.05E-021.56E+021.98E+02 3.70E+02 1.08E+02 8.33E+02 1.56E+02 1.98E+02 3.70E+02 1.08E+02 8.33E+02 3.50E-03 O.OOE+OO 1.05E-03 O.OOE+OO 4.55E-03 3.70E-05 4.88E-06 5.91E-04 O.OOE+OO 6.32E-04 3.54E-03 4.88E-06 1.64E-03 O.OOE+OO 5.18E-03 Page 22 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit 1 2009 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases 1.Total Release Ci 2.Avg.Release Rate uCi/sec 2.67E-01 3.39E-02 2.28E-01 2.89E-02 3.63E-01 4.61E-02 1.06E+01 1.33E+OO 1.14E+01 3.62E-01 Iodine-131 1.Total Release 2.Avg.Release Rate Ci uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.99E-06 8.86E-07 5.96E-06 7.56E-07 1.29E-05 4.10E-07 Particulates Half Life>=8 days 1.Total Release Ci O.OOE+OO 2.Avg.Release Rate uCi/sec O.OOE+OO 4.56E-06 5.78E-07 8.85E-06 1.12E-06 O.OOE+OO O.OOE+OO 1.34E-05 4.25E-07 Tritium 1.Total Release 2.Avg.Release Rate Gross Alpha 1.Total Release 2.Avg.Release Rate Ci uCi/sec Ci uCi/sec 2.60E+00 3.29E-01 O.OOE+OO O.OOE+OO 3.11E+01 3.95E+00 O.OOE+OO O.OOE+OO 1.16E+01 1.47E+OO O.OOE+OO O.OOE+OO 7.74E+00 9.82E-01 O.OOE+OO O.OOE+OO 5.31E+01 1.68E+OO O.OOE+OO O.OOE+OO Page 23 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE lC GASEOUS EFFLUENTS-GROUND RELEASES-CONTINUOUS MODE Unit 1 2009 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci 1.21E-Ol 1.27E-Ol 6.44E-02 5.81E-02 3.70E-Ol Totals for Period...Iodines 1-131 1-132 1-133 ci Ci ci Ci 1.21E-Ol O.OOE+OO O.OOE+OO O.OOE+OO 1.27E-Ol O.OOE+OO O.OOE+OO O.OOE+OO 6.44E-02 6.99E-06 3.40E-04 9.70E-05 5.81E-02 5.96E-06 O.OOE+OO O.OOE+OO 3.70E-Ol 1.29E-05 3.40E-04 9.70E-05 Totals for Period...Ci O.OOE+OO O.OOE+OO 4.44E-04 5.96E-06 4.50E-04 Particulates CR-51 TE-123M ZN-69M Half Life>=8 days ci O.OOE+OO Ci O.OOE+OO Ci O.OOE+OO 4.05E-06 5.07E-07 O.OOE+OO O.OOE+OO O.OOE+OO 8.85E-06 O.OOE+OO O.OOE+OO O.OOE+OO 4.05E-06 5.07E-07 8.85E-06 Totals for Period...Ci Tritium H-3 Ci Totals for Period...Ci Gross Alpha Gross Alpha Ci Totals for Period...Ci O.OOE+OO 4.56E-06 8.85E-06 O.OOE+OO 1.34E-05 2.60E+OO 3.11E+Ol 1.16E+Ol 7.74E+OO 5.31E+Ol 2.60E+OO 3.11E+Ol 1.16E+Ol 7.74E+OO 5.31E+Ol O.OOE+OO O.OOE+OOO.OOE+OOO.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 24 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE lC GASEOUS EFFLUENTS-GROUND RELEASES-BATCH MODE Unit 1 2009 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation AR-41 KR-85 KR-85M XE-131M XE-133 XE-133M XE-135 Gases Ci Ci Ci Ci Ci Ci Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.36E-04 1.46E-Ol 7.93E-06 3.78E-04 7.61E-03 O.OOE+OO O.OOE+OO 5.71E-05 9.38E-02 O.OOE+OO 9.34E-07 1.01E-02 O.OOE+OO 1.74E-04 2.46E-04 2.62E-Ol 2.59E-03 2.39E-02 1.57E-02 1.05E+Ol O.OOE+OO 7.43E-05 1.78E-02 3.03E-04 1.28E-03 3.34E-02 1.05E+Ol 1.74E-04 5.13E-04 5.19E-Ol 2.90E-03 2.56E-02 Totals for Period...Ci Iodines**No Nuclide Activities
    • Particulates Half Life>=8 days**No Nuclide Activities
    • Tritium**No Nuclide Activities
    • Gross Alpha**No Nuclide Activities
    • 1.47E-Ol1.02E-Ol 2.99E-Ol1.05E+Ol1.10E+Ol Page 25 of94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 2009 Unit 2 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products 1.Total Release Ci 2.Avg.Diluted Cone.uCi/ml Tritium 1.Total Release Ci 2.Avg.Diluted Cone.uCi/ml Dissolved and Entrained Gases 1.Total Release Ci 2.Avg.Diluted Cone.uCi/ml Gross Alpha Radioactivity 1.Total Release Ci Volume of liquid waste liters 3.35E-03 1.01E-09 1.63E+02 4.92E-05 3.54E-03 1.07E-09 O.OOE+OO 3.32E+09 2.64E-03 7.41E-10 2.12E+02 5.96E-05 4.88E-06 1.37E-12 O.OOE+OO 3.56E+09 2.32E-03 6.49E-10 4.14E+02 1.16E-04 1.64E-03 4.58E-10 O.OOE+OO 3.58E+09 2.77E-03 8.38E-10 1.18E+02 3.56E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3.30E+09 1.05E-02 7.61E-10 9.07E+02 6.59E-05 5.18E-03 3.76E-10 O.OOE+OO 1.38E+10 Volume of dil.water liters O.OOE+OOO.OOE+OOO.OOE+OO O.OOE+OO O.OOE+OO Page 26 of94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A-Release Tank LIQUID EFFLUENTS-SUMMATION BY RELEASE POINT 2009 Unit 2 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products 1.Total Release Ci 2.Avg.Diluted Cone.uCi/ml Tritium 1.Total Release Ci 2.Avg.Diluted Cone.uCi/ml Dissolved and Entrained Gases 1.Total Release Ci 2.Avg.Diluted Cone.uCi/ml Gross Alpha Radioactivity 1.Total Release Ci Volume of liquid waste liters 3.35E-03 6.23E-06 1.56E+02 2.91E-01 3.54E-03 6.58E-06 O.OOE+OO 5.38E+05 2.64E-03 4.91E-06 1.98E+02 3.69E-01 4.88E-06 9.08E-09 O.OOE+OO 5.37E+05 2.32E-03 1.68E-06 3.70E+02 2.68E-01 1.64E-03 1.18E-06 O.OOE+OO 1.38E+06 2.77E-03 3.88E-06 1.08E+02 1.51E-01 O.OOE+OO O.OOE+OO O.OOE+OO 7.14E+05 1.05E-02 3.30E-06 8.33E+02 2.62E-01 5.18E-03 1.63E-06 O.OOE+OO 3.17E+06 volume of dil.water liters O.OOE+OOO.OOE+OOO.OOE+OO O.OOE+OO O.OOE+OO Page 27 of94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A-Circulating Water Blowdown LIQUID EFFLUENTS-SUMMATION BY RELEASE POINT 2009 Unit 2 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products 1.Total Release Ci 2.Avg.Diluted Conc.uCi/ml Tritium 1.Total Release Ci 2.Avg.Diluted Conc.uCi/ml Dissolved and Entrained Gases 1.Total Release Ci 2.Avg.Diluted Conc.uCi/ml Gross Alpha Radioactivity 1.Total Release Ci Volume of liquid waste liters O.OOE+OO O.OOE+OO 6.96E+00 2.09E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.32E+09 O.OOE+OO O.OOE+OO 1.41E+01 3.96E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.56E+09 O.OOE+OO O.OOE+OO 4.41E+01 1.23E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3.58E+09 O.OOE+OO O.OOE+OO 9.61E+00 2.91E-06 O.OOE+OO O.OOE+OO O.OOE+OO 3.30E+09 O.OOE+OO O.OOE+OO 7.47E+01 5.43E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.38E+10 Volume of dil.water litersO.OOE+OOO.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 28 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2B LIQUID EFFLUENTS-CONTINUOUS MODE 2009 Unit 2 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR---------------------

Fission and Activation Products**No Nuclide Activities

    • Tritium H-3 ci 6.96E+00 1.41E+Ol 4.41E+Ol 9.61E+00 7.47E+Ol Totals for Period...Ci Dissolved and Entrained Gases**No Nuclide Activities
    • Gross Alpha Radioactivity
    • No Nuclide Activities
    • 6.96E+00 1.41E+Ol 4.41E+Ol 9.61E+00 7.47E+Ol Page 29 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2B LIQUID EFFLUENTS-BATCH MODE 2009 Unit 2 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and AG-llOM CO-57 CO-58 CO-60 CS-137 I-131 MN-54 NB-95 SB-124 SB-125 SR-85 TE-125M Activation Products Ci Ci Ci ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+OO 1.09E-05 2.48E-03 2.97E-04 O.OOE+OO O.OOE+OO 1.08E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.53E-05 5.36E-04 O.OOE+OO 1.70E-05 1.39E-03 4.38E-04 O.OOE+OO O.OOE+OO 1.07E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.62E-04 2.29E-05 8.07E-06 8.18E-04 6.48E-04 O.OOE+OO 1.34E-06 2.16E-05 O.OOE+OO 5.44E-06 1.34E-05 4.59E-06 4.48E-04 O.OOE+OO 2.66E-06 2.59E-03 1.14E-04 2.52E-06 O.OOE+OO 2.41E-06 1.36E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.29E-05 3.87E-05 7.28E-03 1.50E-03 2.52E-06 1.34E-06 4.55E-05 1.36E-06 5.44E-06 1.34E-05 1.99E-05 1.55E-03 Totals for Period...Ci Tritium H-3 Ci Totals for Period...Ci Dissolved and Entrained Gases KR-85 Ci XE-133 Ci Totals for Period...Ci Gross Alpha Radioactivity
    • No Nuclide Activities
    • 3.35E-03 2.42E-03 1.99E-03 2.71E-03 1.05E-02 1.56E+02 1.98E+02 3.70E+02 1.08E+02 8.33E+02 1.56E+02 1.98E+02 3.70E+02 1.08E+02 8.33E+02 3.50E-03 O.OOE+OO 1.05E-03 O.OOE+OO 4.55E-03 3.70E-05 4.88E-06 5.91E-04 O.OOE+OO 6.32E-04 3.54E-03 4.88E-06 1.64E-03 O.OOE+OO 5.18E-03 Page 30 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1A GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit 2 2009 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases 1.Total Release Ci 2.Avg.Release Rate uCi/sec 1.57E-01 1.99E-02 1.30E-01 1.65E-02 2.33E-02 2.96E-02 1.07E-02 1.36E-02 6.27E-01 1.99E-02 Iodine-131 1.Total Release 2.Avg.Release Rate Ci uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.80E-05 4.81E-06 5.05E-05 6.41E-06 8.85E-05 2.81E-06 Particulates Half Life>=8 days 1.Total Release Ci O.OOE+OO 2.Avg.Release Rate uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO 6.86E-07 8.71E-08 9.77E-07 1.24E-07 1.66E-06 5.27E-08 Tritium 1.Total Release 2.Avg.Release Rate Gross Alpha 1.Total Release 2.Avg.Release Rate Ci uCi/sec Ci uCi/sec 9.13E+00 1.16E+00 O.OOE+OO O.OOE+OO 5.94E+OO 7.53E-01 O.OOE+OO O.OOE+OO 2.05E+01 2.60E+00 O.OOE+OO O.OOE+OO 1.61E+01 2.04E+00 O.OOE+OO O.OOE+OO 5.16E+01 1.64E+00 O.OOE+OO O.OOE+OO Page 31 of 94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1C GASEOUS EFFLUENTS-GROUND RELEASES-CONTINUOUS MODE Unit 2 2009 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci 1.21E-01 1.27E-01 6.44E-02 5.81E-02 3.70E-01 Totals for Period...Iodines I-131 I-132 I-133 Ci Ci Ci Ci 1.21E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.27E-01 O.OOE+OO O.OOE+OO O.OOE+OO 6.44E-02 3.80E-05 9.26E-05 1.86E-04 5.81E-02 5.05E-05 O.OOE+OO O.OOE+OO 3.70E-01 8.85E-05 9.26E-05 1.86E-04 Totals for Period...CiO.OOE+OOO.OOE+OO 3.17E-04 5.05E-05 3.67E-04 Particulates Half Life>=CO-58 Ci CS-136 Ci 8 days O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.58E-07 3.28E-07 5.10E-07 4.67E-07 8.68E-07 7.95E-07 Totals for Period...Ci Tritium H-3 Ci Totals for Period...Ci Gross Alpha GR-A Ci Totals for Period...Ci O.OOE+OO O.OOE+OO 6.86E-07 9.77E-07 1.66E-06 9.13E+OO 5.94E+OO 2.05E+01 1.61E+01 5.16E+01 9.13E+OO 5.94E+OO 2.05E+01 1.61E+01 5.16E+01O.OOE+OOO.OOE+OOO.OOE+OO O.OOE+OO O.OOE+OOO.OOE+OOO.OOE+OOO.OOE+OOO.OOE+OOO.OOE+OO Page 32 of94 EFFLUENT AND WASTE DISPOSAL REPORT TABLE lC GASEOUS EFFLUENTS-GROUND RELEASES-BATCH MODE Unit 2 2009 REPORT FOR 2009 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation AR-41 KR-85M XE-131M XE-133M XE-133 XE-135 XE-138 Gases Ci Ci Ci Ci Ci Ci Ci 5.19E-03 O.OOE+OO 1.36E-04 7.93E-06 2.69E-02 2.56E-06 4.22E-03 2.35E-03 O.OOE+OO 5.71E-05 O.OOE+OO 1.25E-03 9.34E-07 O.OOE+OO 3.15E-03 1.74E-04 2.46E-04 2.59E-03 1.39E-Ol 2.39E-02 O.OOE+OO 1.82E-02 O.OOE+OO 1.02E-02 3.03E-04 1.88E-02 1.28E-03 O.OOE+OO 2.89E-02 1.74E-04 1.06E-02 2.90E-03 1.86E-Ol 2.52E-02 4.22E-03 Totals for Period...Ci Iodines**No Nuclide Activities
    • Particulates Half Life>=8 days**No Nuclide Activities
    • Tritium**No Nuclide Activities
    • Gross Alpha**No Nuclide Activities
    • 3.65E-023.67E-03 1.69E-Ol 4.88E-02 2.58E-02 Page 33 of 94 40CFR190 FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1 Liquid Receptor===PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)============

QUARTER 1===========

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB-----------------------------------------------------------------------ADULT 1.84E-03 3.86E-02 3.80E-02 4.49E-02 3.74E-02 5.29E-02 O.OOE+OO 3.86E-02 TEEN 2.00E-03 2.93E-02 2.87E-02 2.81E-02 2.81E-02 3.95E-02 O.OOE+OO 2.93E-02 CHILD 2.57E-03 3.24E-02 3.20E-02 3.13E-02 3.13E-02 3.57E-02 O.OOE+OO 3.26E-02 INFANT 6.27E-06 1.39E-02 1.39E-02 1.39E-021.39E-021.39E-02 O.OOE+OO 1.39E-02==:::::::::::::::=:==::::=:==::::::======:::========

SITE DOSE LIMIT ANALYSIS Quartr-Limit Age Group Organ Dose (mrem)QUARTER 1 Limit (mrem)========

Max%of Limit Qtr 1 Qtr 1-Admin.Any Organ-Admin.Total Body ADULT ADULT GILLI TBODY 5.29E-02 3.86E-02 3.75E+OO 1.13E+00 1.41E+00 3.43E+00 Qtr1-T.Spc.Any Organ ADULT GILLI Critical Pathway: Fresh Water Fish-Sport (FFSP)Major Contributors (0%or greater to total)Nuclide Percentage 5.29E-02 5.00E+OO 1.06E+00 H-3 MN-54 CO-58 CO-60 TE-125M 7.07E+Ol 3.65E-Ol 1.14E+Ol 3.64E+00 1.39E+Ol Qtr1-T.Spc.Total Body ADULT TBODY Critical Pathway: Fresh Water Fish-Sport (FFSP)Major Contributors (0%or greater to total)Nuclide Percentage 3.86E-02 1.50E+00 2.57E+OO H-3 MN-54 CO-58 CO-60 TE-125M 9.70E+Ol 3.12E-02 1.73E+OO 5.85E-Ol 6.38E-Ol Page 34 of 94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1 Liquid Receptor===PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)============

QUARTER 2===========

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB-------------------------------

ADULT 3.74E-03 3.62E-02 3.57E-02 4.11E-02 3.54E-02 4.59E-02 O.OOE+OO 3.61E-02 TEEN 3.67E-03 2.74E-022.69E-022.65E-02 2.66E-02 3.45E-02 O.OOE+OO 2.73E-02 CHILD 4.39E-03 3.04E-02 3.01E-022.95E-022.96E-02 3.26E-02 O.OOE+OO 3.04E-02 INFANT 4.64E-05 1.31E-021.31E-021.31E-02 1.31E-02 1.31E-02 O.OOE+OO 1.31E-02=============================

===SITE DOSE LIMIT ANALYSIS Quartr-Limit Age Group Organ Dose (mrem)QUARTER 2 Limit (mrem)Max%of Limit Qtr 2 Qtr 2-Admin.Any Organ-Admin.Total Body ADULT ADULT GILLI TBODY 4.59E-02 3.61E-02 3.75E+00 1.13E+00 1.22E+00 3.21E+00 Qtr2-T.Spc.Any Organ ADULT GILLI Critical Pathway: Fresh Water Fish-Sport (FFSP)Major Contributors (0%or greater to total)Nuclide Percentage 4.59E-02 5.00E+00 9.19E-Ol H-3 MN-54 FE-55 CO-58 CO-60 SR-89 SR-90 TE-125M 7.69E+Ol 3.12E-Ol 1.20E-Ol 5.48E+00 4.59E+00 5.37E-02 1.10E-Ol 1.25E+Ol Qtr2-T.Spc.Total Body ADULT TBODY Critical Pathway: Fresh Water Fish-Sport (FFSP)Major Contributors (0%or greater to total)Nuclide Percentage 3.61E-02 1.50E+00 2.41E+00 H-3 MN-54 FE-55 CO-58 CO-60 SR-89 SR-90 TE-125M 9.78E+Ol 2.47E-02 6.23E-02 7.71E-Ol 6.86E-Ol 1.22E-02 1.12E-Ol 5.33E-Ol Page 35 of94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1 Liquid Receptor===PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)============

QUARTER 3===========

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB-----------------------------------------------------------------------ADULT 2.35E-03 3.46E-02 3.43E-023.65E-023.41E-02 3.91E-02 O.OOE+OO 3.45E-02 TEEN2.25E-032.61E-022.58E-022.56E-02 2.56E-02 2.93E-02 O.OOE+OO 2.60E-02 CHILD 2.64E-03 2.89E-02 2.88E-02 2.85E-02 2.85E-02 2.99E-02 O.OOE+OO 2.90E-02 INFANT 3.37E-05 1.26E-02 1.26E-02 1.26E-02 1.26E-02 1.26E-02 O.OOE+OO 1.26E-02=============================

SITE DOSE LIMIT ANALYSIS Quartr-Limit Age Group Organ Dose (mrem)QUARTER 3 Limit (mrem)========

Max%of Limit Qtr 3 Qtr 3-Admin.Any Organ-Admin.Total Body ADULT ADULT GILLI TBODY 3.91E-02 3.75E+00 1.04E+00 3.45E-02 1.13E+00 3.07E+00 Qtr 3-T.Spc.Any Organ ADULT GILLI Critical Pathway: Fresh Water Fish-Sport (FFSP)Major Contributors (0%or greater to total)Nuclide Percentage 3.91E-02 5.00E+00 7.82E-01 H-3 MN-54 FE-55 CO-58 CO-60 SR-89 SR-90 AG-llOM TE-125M 1-131 8.73E+01 3.80E-01 1.08E-01 1.95E+00 4.12E+00 4.82E-02 9.88E-02 1.15E-02 6.03E+00 1.01E-04 Qtr 3-T.Spc.Total Body ADULT TBODY Critical Pathway: Fresh Water Fish-Sport (FFSP)Major Contributors (0%or greater to total)Nuclide Percentage 3.45E-02 1.50E+00 2.30E+00 H-3 MN-54 36 Nuclide TE-125M 1-131 40CFR190 URANIUM FUEL CYCLE DOSE REPORT Percentage 2.29E-01 2.49E-04 Page 37 of94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1 Liquid Receptor===PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)============

QUARTER 4===========

Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB---------------------------------------

ADULT 2.94E-03 3.93E-023.63E-023.71E-023.66E-02 5.01E-02 O.OOE+OO 3.90E-02 TEEN 2.97E-03 3.03E-02 2.72E-02 2.81E-02 2.76E-02 3.67E-02 O.OOE+OO 2.93E-02 CHILD3.60E-033.31E-023.03E-023.11E-023.06E-02 3.36E-02 O.OOE+OO 3.19E-02 INFANT 2.13E-05 1.34E-02 1.34E-02 1.34E-02 1.34E-02 1.34E-02 O.OOE+OO 1.34E-02===SITE DOSE LIMIT ANALYSIS Quartr-Limit Age Group Organ Dose (mrem)QUARTER 4 Limit (mrem)Max%of Limit Qtr 4 Qtr 4-Admin.Any Organ-Admin.Total Body ADULT ADULT GILLI TBODY 5.01E-02 3.90E-02 3.75E+00 1.13E+00 1.34E+00 3.47E+00 Qtr4-T.Spc.Any Organ ADULT GILLI Critical Pathway: Fresh Water Fish-Sport (FFSP)Major Contributors (0%or greater to total)Nuclide Percentage 5.01E-02 5.00E+00 1.00E+00 H-3 MN-54 FE-55 CO-58 CO-60 SR-89 SR-90 NB-95 CS-137 7.23E+Ol 1.21E-Ol 5.42E-02 1.76E+Ol 2.07E+00 2.42E-02 4.96E-02 7.64E+00 9.51E-02 Qtr4-T.Spc.Total Body ADULT TBODY Critical Pathway: Fresh Water Fish-Sport (FFSP)Major Contributors (0%or greater to total)Nuclide Percentage 3.90E-02 1.50E+00 2.60E+00 H-3 MN-54 9.29E+Ol 9.67E-03 2.83E-02 of 94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1 Liquid Receptor===PERIOD DOSE BY ORGAN AND AGE GROUP (mrem)============

ANNUAL 2009=========Agegrp Bone Liver Thyroid Kidney Lung GI-LLI Skin TB-----------------------------------------------------------------------ADULT 4.70E-03 1.46E-01 1.44E-01 1.58E-01 1.43E-01 1.80E-01 O.OOE+OO 1.46E-01 TEEN 5.11E-03 1.11E-011.08E-011.07E-01 1.07E-01 1.34E-01 O.OOE+OO 1.10E-01 CHILD 6.54E-03 1.23E-011.21E-011.19E-011.19E-01 1.29E-01 O.OOE+OO 1.22E-01 INFANT 1.34E-05 5.27E-02 5.27E-02 5.27E-025.27E-025.27E-02 O.OOE+OO 5.27E-02=============================

SITE DOSE LIMIT ANALYSIS Annual-Limit Age Group Organ Dose (mrem)ANNUAL 2009 Limit (mrem)=======

Max%of Limit 2009 2009-Admin.Any Organ-Admin.Total Body ADULT ADULT GILLI TBODY 1.80E-01 1.46E-01 7.50E+00 2.25E+00 2.40E+00 6.49E+00 2009-T.Spc.Any Organ ADULT GILLI Critical Pathway: Fresh Water Fish-Sport (FFSP)Major Contributors (0%or greater to total)Nuclide Percentage 1.80E-01 1.00E+01 1.80E+00 H-3 MN-54 CO-58 CO-60 NB-95 AG-llOM TE-125M I-131 CS-137 7.93E+01 3.25E-01 7.03E+00 3.85E+00 1.09E+00 4.65E-03 8.42E+00 4.10E-05 1.35E-02 2009-T.Spc.Total Body ADULT TBODY Critical Pathway: Fresh Water Fish-Sport (FFSP)Major Contributors (0%or greater to total)Nuclide Percentage 1.46E-01 3.00E+00 4.87E+00 H-3 MN-54 CO-58 CO-60 NB-95 AG-llOM TE-125M 1-131 CS-137 9.76E+01 2.49E-02 9.58E-01 5.57E-01 1.18E-04 8.33E-06 3.48E-01 1.10E-04 5.63E-01 Page 39 of94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1==============================

I&P DOSE LIMIT ANALYSIS Quartr-Limit Age Group Organ Dose (mrem)QUARTER 1 Limit (mrem)========

Max%of Limit Qtr 1 Qtr 1-Admin.Any Organ-Admin.Total Body CHILD CHILD LIVER TBODY 9.68E-04 9.68E-04 5.63E+00 5.25E+00 1.72E-02 1.84E-02 Qtr 1-T.Spc.Any Organ CHILD LIVER 9.68E-04 7.50E+00 1.29E-02 Receptor: 5 Composite Crit.Receptor-IP Distance: 0.00 (meters)Compass Point: NA Critical Pathway: Vegetation (VEG)Major Contributors (0%or greater to total)Nuclide Percentage H-3 1.00E+02 Qtr 1-T.Spc.Total Body CHILD TBODY 9.68E-04 7.50E+00 1.29E-02 Receptor: 5 Composite Crit.Receptor-IP Distance: 0.00 (meters)Compass Point: NA Critical Pathway: Vegetation (VEG)Major Contributors (0%or greater to total)Nuclide Percentage H-3 1.00E+02 Page 40 of94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1===NG DOSE LIMIT ANALYSIS===============================

Dose Quartr-Limit (mrad)QUARTER 1 Limit (mrad)Max%of Limit Qtr 1 Qtr 1-Admin.Gamma-Admin.Beta 1.36E-05 6.75E-06 3.75E+00 7.50E+00 3.62E-04 9.00E-05 Qtr 1-T.Spc.Gamma Receptor: 4 Composite Crit.Receptor Distance: 0.00 (meters)Nuclide Percentage 1.36E-05-NG Compass Point: NA 5.00E+00 2.72E-04 AR-41 XE-138 XE-135 XE-133M XE-131M XE-133 2.06E+Ol 1.66E+Ol 3.12E-Ol 2.21E-03 1.80E-02 6.25E+Ol Qtr 1-T.Spc.Beta Receptor: 4 Composite Crit.Receptor Distance: 0.00 (meters)Nuclide Percentage 6.75E-06-NG Compass Point: NA 1.00E+Ol 6.75E-05 AR-41 XE-138 XE-135 XE-133M XE-131M XE-133 3.59E+00 4.24E+00 1.98E-Ol 4.96E-03 6.35E-02 9.19E+Ol Page 41 of 94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1==============================

===I&P DOSE LIMIT ANALYSIS Quartr-Limit Age Group Organ Dose (mrem)QUARTER 2 Limit (mrem)Max%of Limit Qtr 2 Qtr 2-Admin.Any Organ-Admin.Total Body CHILD CHILD GILLI TBODY 3.06E-03 3.06E-03 5.63E+00 5.25E+00 5.44E-02 5.83E-02 Qtr 2-T.Spc.Any Organ CHILD GILLI 3.06E-03 7.50E+00 4.08E-02 Receptor: 5 Composite Crit.Receptor-IP Distance: 0.00 (meters)Compass Point: NA Critical Pathway: Vegetation (VEG)Major Contributors (0%or greater to total)Nuclide Percentage H-3 CR-51 TE-123M 1.00E+02 2.76E-04 O.OOE+OO Qtr 2-T.Spc.Total Body CHILD TBODY 3.06E-03 7.50E+00 4.08E-02 Receptor: 5 Composite Crit.Receptor-IP Distance: 0.00 (meters)Compass Point: NA Critical Pathway: Vegetation (VEG)Major Contributors (0%or greater to total)Nuclide Percentage H-3 CR-51 TE-123M 1.00E+02 7.74E-05 O.OOE+OO Page 42 of94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1===NG DOSE LIMIT ANALYSIS Quartr-Limit===============================

Dose (mrad)QUARTER 2 Limit (mrad)Max%of Limit Qtr 2 Qtr 2-Admin.Gamma-Admin.Beta 1.25E-05 5.68E-06 3.75E+00 7.50E+00 3.34E-04 7.57E-05 Qtr2-T.Spc.Gamma Receptor: 4 Composite Crit.Receptor Distance: 0.00 (meters)Nuclide Percentage 1.25E-05-NG Compass Point: NA 5.00E+00 2.50E-04 AR-41 XE-135 XE-131M XE-133 4.30E+Ol 1.66E-03 8.26E-03 5.70E+Ol Qtr 2-T.Spc.Beta Receptor: 4 Composite Crit.Receptor Distance: 0.00 (meters)Nuclide Percentage 5.68E-06-NG Compass Point: NA 1.00E+Ol 5.68E-05 AR-41 XE-135 XE-131M XE-133 8.20E+00 1.15E-03 3.18E-02 9.18E+Ol Page 43 of94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1==============================

I&P DOSE LIMIT ANALYSIS Quartr-Limit Age Group Organ Dose (mrem)QUARTER 3 Limit (mrem)========

Max%of Limit Qtr 3 Qtr 3-Admin.Any Organ-Admin.Total Body INFANT CHILD THYROID TBODY 1.52E-02 2.66E-03 5.63E+00 5.25E+00 2.70E-Ol 5.06E-02 Qtr 3-T.Spc.Any Organ INFANT THYROID 1.52E-02 7.50E+00 2.03E-01 Receptor: 5 Composite Crit.Receptor-IP Distance: 0.00 (meters)Compass Point: NA Critical Pathway: Grs/Goat/Milk (GMILK)Major Contributors (0%or greater to total)Nuclide Percentage H-3 CO-58 1-131 1-132 1-133 CS-136 1.35E+Ol 1.07E-04 8.17E+01 7.30E-03 4.78E+00 3.87E-05 Qtr3-T.Spc.Total Body CHILD TBODY 2.66E-03 7.50E+00 3.54E-02 Receptor: 5 Composite Crit.Receptor-IP Distance: 0.00 (meters)Compass Point: NA Critical Pathway: Vegetation (VEG)Major Contributors (0%or greater to total)Nuclide Percentage H-3 CO-58 1-131 1-132 1-133 CS-136 9.96E+01 1.08E-03 3.53E-01 2.85E-03 2.88E-02 1.11E-02 Date/Time:

02/08/2010 09:28 retdas Page 44 of 94 Page-11 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1===NG DOSE LIMIT ANALYSIS Quartr Limit===============================

Dose (mrad)QUARTER 3 Limit (mrad)Max%of Limit Qtr 3 Qtr 3-Admin.Gamma-Admin.Beta 2.35E-05 1.03E-05 3.75E+00 7.50E+OO 6.26E-04 1.38E-04 Qtr3-T.Spc.Gamma Receptor: 4 Composite Crit.Receptor Distance: 0.00 (meters)Nuclide Percentage 2.35E-05-NG Compass Point: NA 5.00E+00 4.69E-04 AR-41 KR-85M XE-135 XE-133M XE-131M XE-133 3.05E+Ol 1.06E-Ol 2.27E+Ol 4.19E-Ol 1.90E-02 4.62E+Ol Qtr3-T.Spc.Beta Receptor: 4 Composite Crit.Receptor Distance: 0.00 (meters)Nuclide Percentage 1.03E-05-NG Compass Point: NA 1.00E+Ol 1.03E-04 AR-41 KR-85M XE-135 XE-133M XE-131M XE-133 6.00E+00 9.42E-02 1.62E+Ol 1.06E+OO 7.52E-02 7.65E+Ol of 94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1==============================

I&P DOSE LIMIT ANALYSIS Quartr-Limit Age Group Organ Dose (mrem)QUARTER 4 Limit (mrem)========

Max%of Limit Qtr 4 Qtr 4-Admin.Any Organ-Admin.Total Body INFANT CHILD THYROID TBODY 1.71E-02 1.98E-03 5.63E+00 5.25E+00 3.05E-01 3.77E-02 Qtr 4-T.Spc.Any Organ INFANT THYROID 1.71E-02 7.50E+00 2.29E-01 Receptor: 5 Composite Crit.Receptor-IP Distance: 0.00 (meters)Compass Point: NA Critical Pathway: Grs/Goat/Milk (GMILK)Major Contributors (0%or greater to total)Nuclide Percentage H-3 CO-58 I-131 CS-13 6 8.93E+00 1.35E-04 9.llE+01 4.88E-05 Qtr 4-T.Spc.Total Body CHILD TBODY 1.98E-03 7.50E+00 2.64E-02 Receptor: 5 Composite Crit.Receptor-IP Distance: 0.00 (meters)Compass Point: NA Critical Pathway: Vegetation (VEG)Major Contributors (0%or greater to total)Nuclide Percentage H-3 CO-58 I-131 CS-136 9.94E+01 2.06E-03 5.95E-01 2.llE-02 Page 46 of94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1===NG DOSE LIMIT ANALYSIS Quartr-Limit===============================

Dose (mrad)QUARTER 4 Limit (mrad)===========

Max%of Limit Qtr 4 Qtr 4-Admin.Gamma-Admin.Beta 3.22E-05 2.95E-04 3.75E+00 7.50E+00 8.59E-04 3.93E-03 Qtr4-T.Spc.Gamma Receptor: 4 Composite Crit.Receptor Distance: 0.00 (meters)Nuclide Percentage 3.22E-05-NG Compass Point: NA 5.00E+00 6.44E-04 AR-41 KR-85 XE-135 XE-133M XE-131M XE-133 5.67E+Ol 3.24E+Ol 8.86E-Ol 3.57E-02 2.89E-Ol 9.71E+00 Qtr4-T.Spc.Beta Receptor: 4 Composite Crit.Receptor Distance: 0.00 (meters)Nuclide Percentage 2.95E-04-NG Compass Point: NA 1.00E+Ol 2.95E-03 AR-41 KR-85 XE-135 XE-133M XE-131M XE-133 5.37E-Ol 9.86E+Ol 3.05E-02 4.34E-03 5.51E-02 7.76E-Ol Page 47 of 94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1==============================

===I&P DOSE LIMIT ANALYSIS Annual-Limit Age Group Organ Dose (mrem)ANNUAL 2009 Limit (mrem)Max%of Limit 2009 2009-Admin.Any Organ-Admin.Total Body INFANT CHILD THYROID TBODY 3.55E-02 8.67E-03 1.13E+01 1.05E+01 3.15E-01 8.25E-02 2009-T.Spc.Any Organ INFANT THYROID 3.55E-02 1.50E+01 2.37E-01 Receptor: 5 Composite Crit.Receptor-IP Distance: 0.00 (meters)Compass Point: NA Critical Pathway: Grs/Goat/Milk (GMILK)Major Contributors (0%or greater to total)Nuclide Percentage H-3 CR-51 CO-58 1-131 1-132 1-133 CS-136 TE-123M 1.90E+01 6.50E-06 1.llE-04 7.90E+01 3.13E-03 2.05E+00 4.02E-05 O.OOE+OO 2009-T.Spc.Total Body CHILD TBODY 8.67E-03 1.50E+01 5.78E-02 Receptor: 5 Composite Crit.Receptor-IP Distance: 0.00 (meters)Compass Point: NA Critical Pathway: Vegetation (VEG)Major Contributors (0%or greater to total)Nuclide Percentage H-3 CR-51 CO-58 1-131 1-132 1-133 CS-136 TE-123M 9.97E+01 2.73E-05 7.99E-04 2.44E-01 8.75E-04 8.84E-03 8.23E-03 O.OOE+OO Page 48 of94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GASEOUS DOSE

SUMMARY

2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1===NG DOSE LIMIT ANALYSIS Annual-Limit===============================

Dose (mrad)ANNUAL 2009 Limit (mrad)=========Max%of Limit 2009 2009-Admin.Gamma-Admin.Beta 8.18E-05 3.18E-04 7.50E+00 1.50E+Ol 1.09E-03 2.12E-03 2009-T.Spc.Gamma Receptor: 4 Composite Crit.Receptor Distance: 0.00 (meters)Nuclide Percentage 8.18E-05-NG Compass Point: NA 1.00E+Ol 8.18E-04 AR-41 KR-85 XE-138 KR-85M XE-135 XE-133M XE-131M XE-133 4.11E+Ol 1.28E+Ol 2.76E+00 3.03E-02 6.92E+00 1.35E-Ol 1.23E-Ol 3.62E+Ol 2009-T.Spc.Beta Receptor: 4 Composite Crit.Receptor Distance: 0.00 (meters)Nuclide Percentage 3.18E-04-NG Compass Point: NA 2.00E+Ol 1.59E-03 AR-41 KR-85 XE-138 KR-85M XE-135 XE-133M XE-131M XE-133 9.16E-Ol 9.15E+Ol 9.00E-02 3.07E-03 5.61E-Ol 3.85E-02 5.55E-02 6.80E+00 Page 49 of94 40CFR190 URANIUM FUEL CYCLE DOSE REPORT 2009 Unit 1 Report for: 2009 Unit Range-From: 1 To: 1===MAXIMUM DOSE ANALYSIS================================

ANNUAL 2009=========Dose Type Age Group Organ Dose (mrem)Receptor-IP Compass Point: NA Any Organ Liquid Receptor: 0 Gaseous Receptor: 5 Distance: 0.00 ADULT Liquid Receptor Composite Crit.(meters)GILLI 1.85E-01 Liquid Dose: Critical Pathway: Major Contributors Nuclide H-3 MN-54 CO-58 CO-60 NB-95 AG-llOM TE-125M 1-131 CS-137 Gaseous Dose: Critical Pathway: Major Contributors Nuclide H-3 CR-51 CO-58 1-131 1-132 1-133 CS-136 TE-123M 1.80E-01%of Total: 9.71E+01 Fresh Water Fish-Sport (FFSP)(0%or greater to total)Percentage 7.93E+01 3.25E-01 7.03E+00 3.85E+00 1.09E+00 4.65E-03 8.42E+00 4.lOE-05 1.35E-02 5.25E-03%of Total: 2.84E+00 Vegetation (VEG)(0%or greater to total)Percentage 9.99E+01 2.44E-04 2.94E-03 6.87E-02 1.27E-03 1.29E-02 1.17E-03 O.OOE+OO===MAXIMUM DOSE ANALYSIS================================

ANNUAL 2009=========Dose Type Age Group Organ Dose (mrem)Receptor-IP Compass Point: NA Total Body Liquid Receptor: 0 Gaseous Receptor: 5 Distance: 0.00 ADULT Liquid Receptor Composite Crit.(meters)TBODY 1.51E-01 Page 50 of 94

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