ML101410102

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Annual Radioactive Effluent Release Report
ML101410102
Person / Time
Site: Ginna Constellation icon.png
Issue date: 12/31/2009
From:
Constellation Energy Nuclear Group, EDF Development, Ginna
To:
Office of Nuclear Reactor Regulation
References
Download: ML101410102 (26)
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Text

2009 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244

V.

TABLE OF CONTENTS 1.0 Introduction 1 2.0 Supplemental Information I 2.1 Regulatory Limits 1 2.2 Effluent Concentration Limits 3 2.3 Release Rate Limits 3 2.4 Measurements and Approximations of Total Radioactivity 3 2.5 Batch Releases 4 2.6 Abnormal Releases 4 3.0 Summary of Gaseous Radioactive Effluents 5 4.0 Summary of Liquid Radioactive Effluents 5 5.0 Solid Waste 5 6.0 Lower Limit of Detection 6 7.0 Radiological Impact 6 8.0 Meteorological Data 7 9.0 Land Use Census Changes 7 10.0 Changes to the Offsite Dose Calculation Manual 7 11.0 Changes to the Process Control Program 7 12.0 Major Changes to Radwaste Treatment Systems 7 13.0 Inoperable Monitors 8 14.0 Changes to Previous Annual Effluent Reports 8 15.0 Groundwater Monitoring 8

LIST OF TABLES Table 1A Gaseous Effluents - Summation of all Releases ...................................... 9 Table 2A Liquid Effluents - Summation of all Releases .......................................... 11 Table 1B Gaseous Effluents - Continuous and Batch Releases ............................. 13 Table 2B Liquid Effluents - Continuous and Batch Releases ................................... 15 Table 3 Solid Waste and Irradiated Fuel Shipments ............................................. 17 Table 4A Radiation Dose to Nearest Individual Receptor from Gaseous Releases ... 18 Table 4B Radiation Dose to Nearest Individual Receptor from Liquid Releases ........ 22 Table 5 Groundwater Monitoring Well Results ............................................ 23

1.0 INTRODUCTION

This Annual Radioactive Effluent Release Report is for the R.E. Ginna Nuclear Power Plant and is submitted in accordance with the requirements of Technical Specification Section 5.6.3. The report covers the period from January 1, 2009 through December 31, 2009.

This report includes a summary of the quantities of radioactive gaseous and liquid effluents and solid waste released from the plant presented in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June, 1974.

All gaseous and liquid effluents discharged during this reporting period were in compliance with the limits of the R.E. Ginna Technical Specifications as defined in the Offsite Dose Calculation Manual (ODCM).

2.0 SUPPLEMENTAL INFORMATION 2.1 Regqulatory Limits The ODCM limits applicable to the release of radioactive material in liquid and gaseous effluents are:

2.1.1 Fission and Activation Gases The instantaneous dose rate, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to a release rate which would yield < 500 mrem/yr to the total body and < 3000 mrem/yr to the skin if allowed to continue for a full year.

The air dose, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to the following:

(I) During any calendar quarter to < 5 mrad for gamma radiation and to

< 10 mrad for beta radiation.

(ii) During any calendar year to < 10 mrad for gamma radiation and to

< 20 mrad for beta radiation.

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2.1.2 Radioiodine. Tritium and Particulates The instantaneous dose rate, as calculated in the ODCM, due to radioactive materials released in gaseous effluents from the site as radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days shall be limited to a release rate which would yield

< 1500 mrem/yr to any organ if allowed to continue for a full year.

The dose to an individual, as calculated in the ODCM, from radioiodine, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days released with gaseous effluents from the site shall be limited to the following:

(i) During any calendar quarter to < 7.5 mrem to any organ.

(ii) During any calendar year to < 15 mrem to any organ.

2.1.3 Liquid Effluents The release of radioactive liquid effluents shall be such that the concentration in the circulating water discharge does not exceed the limits specified in accordance with Appendix B, Table II, Column 2 and notes thereto of 10CFR20, as explained in Section 1 of the ODCM. For dissolved or entrained noble gases the total activity due to dissolved or entrained noble gases shall not exceed 2E-04 uCi/ml.

The dose or dose commitment to an individual as calculated in the ODCM from radioactive materials in liquid effluents released to unrestricted areas shall be limited:

(i) During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, and (ii) During any calendar year to < 3 mrem to the total body and to < 10 mrem to any organ.

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2.2 Effluent Concentration Limit (ECL) 2.2.1 For gaseous effluents, effluent concentration limits are not directly used in release rate calculations since the applicable limits are stated in terms of dose rate at the unrestricted area boundary, in accordance with Technical Specification 5.5.4.g.

2.2.2 For liquid effluents, ten times the effluent concentration values specified in 10CFR20, Appendix B, Table II, column 2, are used to calculate release rates and permissible concentrations at the unrestricted area boundary as permitted by Technical Specification 5.5.4.b. A value of 2E-04 uCi/ml is used as the ECL for dissolved and entrained noble gases in liquid effluents.

2.3 Release Rate Limits Based on Average Nuclide Energy The release rate limits for fission and activation gases from the R.E. Ginna Nuclear Power Plant are not based on the average energy of the radionuclide mixture in gaseous effluents; therefore, this value is not applicable. However the 2009 average beta/gamma energy of the radionuclide mixture in fission and activation gases released from Ginna is available for review upon request.

2.4 Measurements and Approximations of Total Radioactivity Gamma spectroscopy was the primary analysis method used to determine the radionuclide composition and concentration of gaseous and liquid effluents.

Composite samples were analyzed for Sr-89, Sr-90, and Fe-55 by a contract lab-oratory. Tritium and alpha analysis were performed using liquid scintillation and gas flow proportional counting respectively.

The total radioactivity in effluent releases was determined from the measured concentration of each radionuclide present and the total volume of effluents released.

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2.5 Batch Releases 2.5.1 Liquid

1. Number of batch releases: 1.44 E+02
2. Total time period for batch releases: 3.00 E+04 min
3. Maximum time period for a batch release: 1.23 E+04 min
4. Average time period for batch releases: 2.09 E+02 min
5. Minimum time period for a batch release: 3.0 E+00 min
6. Average blowdown in liters per minute (LPM) during periods of effluent release into the discharge canal. 4.68 E+02 LPM 2.5.2 Gaseous
1. Number of batch releases: 3.7 E+01
2. Total time period for batch releases: 5.46 E+05 min
3. Maximum time period for a batch release: 4.46 E+04 min
4. Average time period for batch releases: 1.48 E+04 min
5. Minimum time period for a batch release: 4.90 E+01 min 2.6 Abnormal Releases There was one abnormal or unplanned release in 2009. On August 19, 2009 a local radiation emergency (CR 2009-005783) due to a mispositioned valve in the Auxiliary Building was declared at 1245. A slight increase on plant vent effluent radiation monitors was noted shortly thereafter (CR 2009-005815). Chemistry personnel obtained grab samples at the plant vent and calculated the release as 1.38E-01 Curies of noble gas and 4.73E-02 Curies of tritium. This activity was included in August 2009 Effluents summary.

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3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 1A and 1B. Plant Vent and Containment Vent releases are modeled as mixed mode and the Air Ejector is modeled as ground level release. In 2009, Ginna completed installation of new counting room gamma spectroscopy equipment and effluent calculation software. Verification and validation against past equipment and software was performed and the results were acceptable. The response of the new higher efficiency detectors has resulted in more accurate response to cross-check standards.

4.0

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in tables 2A and 2B.

5.0 SOLID WASTE The quantities of radioactive material released in shipments of solid waste transported from the site during the reporting period are summarized in Table 3.

Principal nuclides were determined by gamma spectroscopy and non-gamma emitters were calculated from scaling factors determined by an independent laboratory from representative samples of that waste type. The majority of Dry Active Waste is processed utilizing an off-site processor who reduces the volume and then sends the waste for burial.

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6.0 LOWER LIMIT OF DETECTION The required Lower Limit of Detection, (LLD), as defined in the ODCM, was met for all samples used in reporting effluent releases for 2009.

The following sample failed to meet the a posteriori MDA for high background activity in the samples.

"A" Monitor Tank Release 2009004 failed to meet MDA for Fe-59 at 5.53E-07 uCi/cc and Zn-65 at 6.82E-07 uCi/cc.

7.0 RADIOLOGICAL IMPACT An assessment of doses to the hypothetical maximally exposed individual member of the public from gaseous and liquid effluents was performed for locations representing the maximum calculated dose in occupied sectors. Meteorological sectors from WNW through ENE are entirely over Lake Ontario. In all cases, doses were well below Technical Specification limits as defined in the ODCM. Doses were assessed based upon historical meteorological conditions considering the noble gas exposure, inhalation, ground plane exposure, and ingestion pathways. The ingestion pathways considered were the fruit, vegetable, fish, drinking water, goat's milk, cow's milk and cow meat pathways. Results of this assessment are presented in Tables 4A and 4B.

7.1 Total Dose 40CFR190 limits the total dose to members of the public due to radiation and radioactivity from uranium fuel cycle sources to:

< 25 mrem total body or any organ and;

< 75 mrem thyroid for a calendar year.

Using the maximum exposure and uptake pathways, the maximum liquid pathways, and the maximum direct radiation measurements at the site boundary, yield the following dose summaries to the hypothetical maximally exposed individual member of the public:

11.7 mrem total body (11.7 mrem direct radiation plus 1.4E-2 mrem all other pathways).

1.03E-2 mrem GI-LLI (maximum organ dose).

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8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 2009 is not included with this report, but can be made available at the R. E. Ginna Nuclear Power Plant.

9.0 LAND USE CENSUS CHANGES There were no major changes in critical receptor location for dose calculations during the reporting period. Minor changes in critical receptor locations and distances came from utilizing updated mapping technologies (hand held global positioning system and Google Earth software). There were no significant changes in land use within 5 miles of the plant. Additional new homes are being built at a rate comparable to recent years.

10.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL The ODCM was revised to remove unnecessary dosimeter terminology (Thermoluminescent). This revision does not change the number of or location of REMP dosimeters. ODCM revision 24 is included with this submittal.

11.0 CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Process Control Program during the reporting period.

12.0 MAJOR CHANGES TO RADWASTE TREATMENT SYSTEMS There were no major changes to the Radwaste Treatment Systems during the reporting period.

13.0 INOPERABLE MONITORS

  • RM-14A was out of service from 3/23/09 through 3/30/09 for corrective maintenance.

" RM-15 was out of service from 3/25/09 through 4/20/09 for corrective maintenance.

" R-1 1 out of service due to paper tearing 6/24/09 through 7/2/09.

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14.0 CHANGES TO PREVIOUS ANNUAL EFFLUENT OPERATING REPORTS RPA-RW-PCP, "Process Control Program", was revised in 2007 under Procedure Change Request 2007-3427-001. These changes were to update titles, remove references that no longer existed, remove a configuration that is no longer utilized, and to remove the Green is Clean process that is no longer employed. The changes did not change the intent of the Procedure or the PCP.

This change was not included in the 2007 Annual Radioactive Release report as required under Section 6.2 of the ODCM.

RPA-RW-PCP, "Process Control Program", was revised in 2008 under Procedure Change Request 2008-2107-001. This change provided clarification of when Ce-144 may be used to determine transuranics. The change does not change the intent of the PCP. This change was not included in the 2008 Annual Radioactive Release report as required under Section 6.2 of the ODCM.

15.0 GROUNDWATER MONITORING In accordance with R. E. Ginna Nuclear Power Plant's Chemistry procedures, environmental groundwater monitoring wells are sampled quarterly. There is a total of 9 onsite groundwater monitoring wells:

" Three located adjacent to the All Volatiles Treatment (AVT) Building, screened at 3 depths to include groundwater from top of the water table down to bedrock.

" Three located east of the Screenhouse, screened at 3 depths to include groundwater from top of the water table down to bedrock.

" One to the west of the Screenhouse.

" One to the southeast of the Contaminated Storage Building (CSB).

" One located south of the Butler Building and upgradient from the reactor containment building, which serves as a control sample point.

Groundwater samples are analyzed for tritium to a detection limit of 500 pCi/L.

In 2009, no radioactivity was detected in groundwater samples.

Results of the groundwater monitoring well sampling are presented in Table 5.

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Table 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES January-June 2009 Unit Quarter Quarter Est. Total A. Fission & actiVation gases 1st 2nd Error, %

1. Total release Ci 7.19E-01 6.53E-01 1.50E+01
2. Average release rate for period uCi/sec 9.12E-02 8.28E-02
3. Percent of technical specification limit %_ . 1.45E-05 1.31E-05 B. lodines
1. Total iodine-131 Ci 3.04E-06 1.50E+01
2. Average release rate for period uCi/sec 3.85E-07
3. Percent of technical specification limit  % 8.37E-04 C. Particulates
1. Particulates with half-lives > 8days Ci
2. Average release rate for period uCi/sec
3. Percent of technical specification limit  %
4. Gross alpha radioactivity Ci D. Tritium
1. Total release Ci 1.20E+01 1.53E+01 9.20E+00
2. Average release rate for period uCi/sec [ .53E+00 1.94E+00
3. Percent of technical specification limit  % I 1.79E-04 2.27E-04 Note: Isotopes for which no value is given were not identified in applicable releases.

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Table 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES July - December 2009 Unit Quarter Quarter Est. Total A. Fission & activation gases 3rd 4th Error, %

1. Total release Ci 1.75E+00 4,08E-01 1,50E+01
2. Average release rate for period uCi/sec 2.22E-01 5.18E-02
3. Percent of technical specification limit  % 3.52E-05 8.22E-06 B. Iodines
1. Total iodine-131 ] Ci ] 5.95E-07 j 4.17E-07 I 1.50E+01
2. Average release rate for period uCi/sec 7.54E-08 5.29E-08
3. Percent of technical specification limit  % 1.64E-04 1.15E-04 C. Particulates
1. Particulates with half-lives > 8days Ci
2. Average release rate for period uCi/sec
3. Percent of technical specification limit  %
4. Gross alpha radioactivity Ci D. Tritium
1. Total release Ci 1.82E___

1.82E+01 i8E0 1.58E+01 9.20E+00 9.E0

2. Average release' rate for period uCi/sec 2.30E+00 2.01E+00
3. Percent of technical specification limit  % 2.69E-04 2.35E-04 Note: Isotopes for which no value is given were not identified in applicable releases.

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Table 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES January - June 2009 Unit Quarter Quarter Est.Total A. Fission and activation products 1st 2nd Error, %

1. Total release (not including tritium, Ci 8.88E-04 6.46E-05 9.90E+00 gases, alpha) Ci _8.8E-0 6.6 -5 99E0
2. Average diluted concentration uCi/mI 2.09E-12 1,35E-13 during period u_ i/m_ _.9-__3E1
3. Percent of applicable limit  % 2.09E-05 1.35E-06 B. Tritium
1. Total release Ci 4.27E+01 1.25E+02 9.20E+00
2. Average diluted concentration uCi/mI 1,O1E-07 2,61E-07 during period u l 1 .
3. Percent of applicable limit  % 1.01E-03 2.61E-03 C. Dissolved and entrained gases
1. Total release Ci 3.35E-05 9.90E+00
2. Average diluted concentration uCi/mI 7.03E-14 during period ui/ml 7.03E-14
3. Percent of applicable limit  % 3.52E-08 D. Gross alpha radioactivity
1. Total release Ci E. Vol. of waste released (prior to dilution) Liters 9.75E+07 9.97E+07 F. Vol. of dilution Water used during period Liters 4.24E+11 4.77E+11 Note: Isotopes forwhich no value is given were not identified in applicable releases.

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Table 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES July - December 2009 Unit Quarter Quarter Est.Total A. Fission and activation products 3rd 4th Error, %

1. Total release (not including tritium, 1.0E -03 2.72E-03 gases, alpha) Ci 9.90E+00
2. Average diluted concentration uCi/ml 2.14E-12 4.88E-12 during period _
3. Percent of applicable limit _ 2.14E-05 4.88E-05 B. Tritium
1. Total release Ci 9.59E+01 7.04E+01 9.20E+00
2. Average diluted concentration uCi/mI 1,95E-07 1.26E-07 during period u/ _950 16-
3. Percent of applicable limit  % 1.95E-03 1.26E-03 C. Dissolved and entrained gases
1. Total release Ci 1.32E-04 9.90E+00
2. Average diluted' concentration uCi/mI 2,69E-13 during period ui/ml 2._9E-1_
3. Percent of applicable limit  % 1.35E-07 D. Gross alpha radioactivity
1. Total release Ci E. Vol. of waste released (prior ro dilution) Liters 9.11E+07 1.00E+08 F. Vol. of dilution water used during period Liters 4.90E+11 5.57E+11 Note: Isotopes for Which no value is given were not identified in applicable releases.

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Table 1 B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES January - June 2009 Continuous Mode Batch Mode Nuclides released Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd

1. Fission gases argon-41 Ci 7.62E-02 8.49E-02 krypton-85 Ci krypton-85m Ci 1.90E-04 3.93E-04 krypton-87 Ci krypton-88 Ci xenon-131m Ci xenon-133 Ci 6.18E-01 5.42E-01 xenon-133m Ci 5.70E-03 6.47E-03 xenon-135 Ci 1.93E-02 1.85E-02 xenon-135m Ci xenon-138 Ci others (specify) Ci Ci Total for period Ci 7.19E-01 6.52E-01
2. lodines iodine-131 Ci 3.04E-06 iodine-132, Ci iodine-133 Ci iodine-135 Ci Total for period Ci 3.04E-06 _
3. Particulates strontium-89 Ci strontium-90 Ci cesium-134 Ci cesium-137 Ci cobalt-58 Ci unidentified Ci Total for period Ci
4. Tritium

[Hydrogen-3 Ci 1.20E+01 1.52E+01 7.0SE-02 9.60E-021 Note: Isotopes for':which no value is given were not identified in applicable releases.

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Table 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - CONTINUOUS AND BATCH RELEASES July - December 2009 Continuous Mode Batch Mode Nuclides released; Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th

1. Fission gases argon-41 Ci 3.43E-01 5.67E-02 9.93E-02 6.97E-02 krypton-85 Ci krypton-85m Ci 7,23E-05 krypton-87 Ci krypton-88 Ci xenon-131m Ci 1.87E-03 xenon-133 Ci 7.30E-01 1.12E-01 4.76E-01 1.65E-01 xenon-133m Ci 3.68E-03 3.96E-03 xenon-135 Ci 2.57E-02 1.89E-03 6.42E-02 2.89E-03 xenon-135m Ci xenon-138 Ci others (specify) Ci Ci unidentified Ci Total for period Ci 1.10E+00 1.71E-01 6.46E-01 2.38E-01
2. lodines iodine-131 Ci 5.95E-07 4,17E-07 iodine-133 Ci iodine-135 Ci Total for period Ci 5.95E-07 4.17E-07
3. Particulates strontium-89 Ci strontium-90 Ci cesium-134 Ci cesium-137 Ci cobalt-58 Ci unidentified Ci Total for period Ci
4. Tritium jHydrogen-3 Ci I 1.81E+01 I 1,56E+01 I 4.18E-02I 2.18E-01 Note: Isotopes for which no value is given were not identified in applicable releases.

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Table 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Liquid Effluents January-June 2009 Continiioijc~ Mode Ratc~h Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd chromium-51 Ci manganese-54 Ci iron-55 Ci 2.25E-04 iron-59 Ci cobalt-58 Ci 5.05E-04 4.16E-05 cobalt-60 Ci 1.59E-04 2.30E-05 zinc-65 Ci strontium-89 Ci strontium-90 Ci niobium-95 Ci molybdenum-99 Ci silver-lOrm Ci antimony-122 Ci antimony-124 Ci antimony-125 Ci iodine-131 Ci iodine-132 Ci iodine-135 Ci cesium-134 Ci cesium-136 Ci cesium-137 Ci 5.02E-08 barium/lanthanum-140 Ci cerium-141 Ci Te-132 Ci Zr-95 Ci Co-57 Ci Total for period (above) Ci 8.89E-04 g 6.47E-05 j unidentified Ci ITritium I Ci I 1.07E-01 I 5.29E-02 4.26E+01 1.25E+02 Ixenon-133 Ci I I 3.35E-05 xenon-135 Ci I I Note: Isotopes for which no value is given were not identified in applicable releases.

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Table 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Liquid Effluents July- December 2009 Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th chromium-51 Ci manganese-54 Ci iron-55 Ci iron-59 Ci cobalt-58 Ci 1.05E-03 2.72E-03 cobalt-60 Ci 2.43E-09 zinc-65 Ci strontium-89 Ci strontium-90 Ci niobium-95 Ci molybdenum-99 Ci silver-110m Ci antimony-122 Ci antimony-124 Ci antimony-125 Ci iodine-131 Ci iodine-132 Ci iodine-135 Ci cesium-134 Ci cesium-136 Ci cesium-137 Ci 4.02E-09 9.92E-07 barium/lanthanum-140 Ci cerium-141 Ci ,,

Te-132 Ci _

Zr-95 Ci Co-57 Ci Total for period (above) Ci 1.05E-03 2.72E-03 unidentified Ci ITritium Ci 2.44E-02 9,59E+o1 7.04E+01 xenon-133 Ci 1.32E-04 oxenon-135 Ci Note: Isotopes for 'Which no value is given were not identified in applicable releases, 16

Table 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1, 2009 - December 31, 2009 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL- (Not irradiated fuel)

1. Type of waste Unit 12 month period Est. total Error %
a. Spent resins, filter sludges, evaporator m3 12.91 7.0 E+00 bottoms, etc. Ci 90.42 1.4 E+01
b. Dry compressible waste, contaminated m3 262.4 7.0 E+00 equip, etc. Ci 1.64 1.4 E+01 clrradiated components, control rods, m3 None N/A etc. Ci N/A d.Other: m3 None N/A Ci N/A 2.Estimate of major nuclide composition (by type of waste)
a. b. d.

Co-58  % 10.8 Co-58  % 3.6 None  % None Ni-63  % 21.1 Fe-55  % 17.8  %

Ag-11im  % 0.4 Sb-125  % 1.3  %

Cs-137  % 0.1 Co-60  % 10.7  %

Co-60  % 4.9 Ni-63  % 58.2  %

Fe-55  % 21.3 Mn-54  % 2.2  %

Mn-54  % 0.3 Ni-59  % 0.8  %

Ce-144  % 0.4 Co-57  % 0.3  %

H-3  % 35.6 Cs-1 37  % 4.2  %

Sb-125  % 3.5  %  %

Nb-95 0.3  %/

Total 98.8% Total 99.1 Total 0

3. Solid Waste Disposition Number of Shipet Moeoqrnprtaition P~ Destinaition.

2 Sole Use Truck Energy Solutions 16 Sole Use Truck Studsvic B. IRRADIATED FUEL SHIPMENTS (Disposition)

NumerofShpmnts Mode of Transportation Destinatinon None 17

Gas Rel 1st Qt Table 4A Radiation Dose to Maximum Individual Receptor First Quarter 2009 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N 2.62E-06 2.58E-06 NNE 2.20E-06 2.17E-06 NE 2.53E-06 2.49E-06 ENE 3.22E-06 3.17E-06 E 5.86E-06 5.38E-05 3.36E-04 3.68E-04 5.06E-04 2.21 E-04 ESE 7.45E-06 7.35E-06 4.28E-04 4.65E-04 6.44E-04 2.81 E-04 SE 4.51 E-06 4.45E-06 2.58E-04 2.05E-04 3.89E-04 1.70E-04 SSE 1.86E-06 1.83E-06 1.06E-04 1.16E-04 1.60E-04 6.99E-04 S 3.25E-06 3.20E-06 1.86E-04 2.04E-04 2.81E-04 1.23E-04 SSW 3.25E-06 3.20E-06 1.85E-04 2.04E-04 2.81E-04 1.23E-04 SW 3.26E-06 3.20E-06 1.86E-04 2.04E-04 2.81 E-04 1.22E-04 WSW 3.46E-06 3.41E-06 1.98E-04 2.17E-04 2.99E-04 1.31E-04 W 2.20E-06 2.17E-06 1.26E-04 1.38E-04 1.90E-04 8.33E-05 WNW 1.86E-07 1.86E-07 NW 6.11 E-07 6.02E-07 NNW 1.91 E-06 1.88E-06 MAX. 7.45E-06 5.38E-05 4.28E-04 4.65E-04 6.44E-04 6.99E-04 18

Gas Rel 2nd Qt Table 4A Radiation Dose to Maximum Individual Receptor Second Quarter 2009 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N 2.76E-06 2.44E-06 NNE 2.31 E-06 2.04E-06 NE 2.67E-06 2.36E-06 ENE 3.39E-06 2.78E-06 E 6.17E-06 5.46E-06 6.06E-04 6.63E-04 9.12E-04 3.98E-04 ESE 7.85E-06 6.96E-06 7.71E-04 8.43E-04 1.16E-03 5.07E-04 SE 4.75E-06 4.21E-06 4.67E-04 5.1OE-04 7.02E-04 3.07E-04 SSE 1.95E-06 1.73E-06 1.92E-04 2.1OE-04 2.89E-04 1.26E-04 S 3.42E-06 3.03E-06 3.36E-04 3.68E-04 5.06E-04 2.21 E-04 SSW 3.41 E-06 3.02E-06 3.35E-04 3.68E-04 5.06E-04 2.21E-04 SW 3.42E-06 3.03E-06 3.36E-04 3.67E-04 5.06E-04 2.22E-04 WSW 3.65E-06 3.14E-06 3.58E-04 3.92E-04 5.39E-04 2.05E-04 W 2.30E-06 2.04E-06 2.27E-04 2.48E-04 3.42E-04 1.49E-04 WNW 2.32E-07 2.06E-07 NW 6.43E-07 5.70E-07 NNW 2.01E-06 1.78E-06 MAX. 7.85E-06 6.96E-06 7.71E-04 8.43E-04 1.16E-03 5.07E-04 19

Gas Rel 3rd Qt Table 4A Radiation Dose to Maximum Individual Receptor Third Quarter 2009 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N 2.87E-05 2.05E-05 NNE 2.41 E-05 1.72E-05 NE 2.77E-05 1.98E-05 ENE 3.53E-05 2.52E-05 E 6.41 E-05 4.58E-05 7.01 E-04 8.43E-04 1.16E-03 5.07E-04 ESE 8.15E-05 5.83E-05 9.90E-04 1.08E-03 1.49E-03 6.51E-04 SE 4.94E-05 3.53E-05 5.99E-04 6.55E-04 9.01 E-04 6.70E-04 SSE 2.03E-05 1.45E-05 2.46E-04 2.68E-04 3.70E-04 1.61E-04 S 3.56E-05 2.54E-05 4.30E-04 4.69E-04 6.48E-04 2.83E-04 SSW 3.56E-05 2.55E-05 4.29E-04 4.69E-04 6.47E-04 2.83E-04 SW 3.55E-05 2.54E-05 4.30E-04 4.70E-04 6.47E-04 2.82E-04 WSW 3.79E-05 2.71 E-05 4.60E-04 5.03E-04 6.92E-04 3.02E-04 W 2.41E-05 1.72E-05 2.92E-04 3.19E-04 4.39E-04 1.92E-04 WNW 2.03E-06 1.45E-06 NW 6.69E-06 4.78E-06 NNW 2.08E-05 1.49E-05 IMAX. 8.15E-05 5.83E-05 9.90E-04 1.08E-03 1.49E-03 6.70E-04 20

Gas Rel 4th Qt Table 4A Radiation Dose to Maximum Individual Receptor Fourth Quarter 2009 (Units In milliRem)

All All Adult Teen Child Infant Gamma Air Beta Air THYRD THYRD THYRD THYRD N 3.32E-06 1.87E-06 NNE 2.91E-06 1.63E-06 NE 3.34E-06 1.88E-06 ENE 4.25E-06 2.39E-06 E 7.72E-06 4.34E-06 5.27E-04 5.76E-04 7.93E-04 3.46E-04 ESE 9.88E-06 5.53E-06 6.71E-04 7.34E-04 1.01 E-03 4.41E-04 SE 5.94E-06 3.34E-06 4.06E-04 4.44E-04 6.11E-04 2.67E-04 SSE 2.45E-06 1.38E-06 1.67E-04 1.82E-04 2.51E-04 1.10E-04 S 4.28E-06 2.41E-06 2.92E-04 3.19E-04 4.40E-04 1.92E-04 SSW 4.28E-06 2.41E-06 2.93E-04 3.19E-04 4.40E-04 1.92E-04 SW 4.29E-06 2.40E-06 2.92E-04 3.20E-04 4.40E-04 1.91 E-04 WSW 4.41E-06 2.48E-06 3.12E-04 3.41E-04 4.69E-04 2.05E-04 W 2.90E-06 1.63E-06 1.98E-04 9.43E-05 2.97E-04 1.30E-04 WNW 2.45E-07 1.38E-07 NW 8.09E-07 4.53E-07 NNW 2.51E-06 1.41 E-06 MAX. 9.88E-06 5.53E-06 6.71E-04 7.34E-04 1.01E-03 4.41E-04 21

Table 4B Radiation Dose To Maximum Individual Receptor From Liquid Release 2009 (Units in milliRem)

Adult Teen Child Infant First Quarter T. Body 3.60E-04 2.54E-04 4.85E-04 4.77E-04 GI-LLI 3.61E-04 2.55E-04 4.88E-04 4.80E-04 Thyroid 3.85E-04 2.53E-04 4.84E-04 4.76E-04 Second Quarter T. Body 9.65E-04 7.01 E-04 1.30E-03 1.28E-04 GI-LLI 9.65E-04 7.01 E-04 1.30E-03 1.28E-04 Thyroid 9.65E-04 7.02E-04 1.30E-03 1.28E-04 Third Quarter T. Body 5.22E-03 3.68E-03 7.04E-03 6.93E-03 GI-LLI 5.25E-03 3.70E-03 7.08E-03 6.97E-03 Thyroid 5.20E-03 3.66E-03 7.02E-03 6.91 E-03 Fourth Quarter T. Body 5.52E-04 3.89E-04 7.44E-04 7.32E-04 GI-LLI 5.56E-04 3.94E-04 7.51 E-04 7.37E-04

.Thyroid 5.52E-04 3.80E-04 7.43E-04 7.31 E-04 22

TABLE 5 Groundwater Monitoring Wells Location Sample Date Tritium AVT, S. 13' 03/17/09

  • S06/09/09
  • 09/10/09 12/18/09
  • S.... . ... . ..................

S06/09/09

  • AVT, N. 6' 03/17/09
  • 12/18/09 TScreen House East6 N. 24 03/17/09 i..... ... .. ...... . . . . . . . . . . . ..............

. . . . ....................... ...... 5"# 6 6....................... . ....... ...... .................. ..................... ... .................... ...........................

09/10/09 Screen House East, 204 .. 11 03/17/09 /10/09 ** .....

06/09/09 .. ......... ......... ........... .... -

09/10/09 11/10/09

  • Screen House East, So. 15.5" 03/17/09
  • 06/09/09
  • 09/10/09 _ -

........... -............. . ... ...... .. . . . . . . . ... 011/10/09 6 0.9 0 ....

Screen House West S 503/17/09

  • 110/10/09 06/09/09*
  • CScree HouseWest03/17/09 09/10/09
  • 11/10/09

_____________________________11/18/09 ______________

GSB, 24' 03/17/09*

06/09/09*

09/10/09 12/18/09 23

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