ML110670415

St. Lucie, Units 1 and 2 - Annual Radioactive Effluent Release Report - January 1, 2010 Through December 31, 2010

ML110670415
Person / Time
Site:	Saint Lucie
Issue date:	02/28/2011
From:	Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation
References
L-2011-064
Download: ML110670415 (60)

Text

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 THROUGH DECEMBER 31, 2010 L-2011-064 COMBINED ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JANUARY 1, 2010 THROUGH DECEMBER 31, 2010 ( 57 PAGES)

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 THROUGH DECEMBER 31, 2010 TABLE OF CONTENTS 1.0 PROGRAM DESCRIPTION

2.0 SUPPLEMENTAL

INFORMATION

2.1 Abnormal

Releases or Abnormal Discharges 2.2 Non-Routine Planned Discharges

2.3 Radioactive

Waste Treatment System Changes 2.4 Annual Land Use Census Changes 2.5 Effluent Monitoring System Inoperability

2.6 Offsite

Dose Calculation Manual Changes 2.7 Process Control Program Changes 2.8 Corrections to Previous Reports 2.9 Other 2.10 Groundwater Protection Program 3.0 TABLES 3.1 Gaseous Effluents 3.2 Liquid Effluents 3.3 Solid Waste Storage and Shipments 3.4 Dose Assessments FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 THROUGH DECEMBER 31, 2010 1.0 PROGRAM DESCRIPTION Regulatory Limits The ODCM Radiological Effluent Control limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.Fission and Activation Gases (Noble Gases)The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin.The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

Iodine-131, Iodine-133, Tritium, Carbon-14 and Radioactive Material in Particulate Form The dose rate due to iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal to 1500 mrem/yr to any organ.The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, carbon-14 and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released, from each unit, to areas at and beyond the site boundary, shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and b. During any calendar year: Less than or equal to 15 mrems to any organ.

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 THROUGH DECEMBER 31, 2010 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-4 gCi/ml total activity.

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to unrestricted areas shall be limited: a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.Total Dose The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.Effluent Concentration Limits Gaseous Effluents For gaseous effluents, effluent concentration limits (ECL) values are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary.Liquid Effluents The values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 are used as the ECL for liquid radioactive effluents released to unrestricted areas. A value of 2.0E-04 giCi/ml is used as the ECL for dissolved and entrained noble gases in liquid effluents.

Measurements and Approximations of Total Radioactivity Measurements of total radioactivity in liquid and gaseous radioactive effluents were accomplished in accordance with the sampling and analysis requirements of Tables 4.11-I and 4.11-2, respectively, of the St. Lucie ODCM. Estimates of errors are in accordance with Methodology Section 4.4, of the ODCM.

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 THROUGH DECEMBER 31, 2010 Liquid Radioactive Effluents Each batch release was sampled and analyzed for gamma emitting radionuclides using gamma spectroscopy, prior to release. Composite samples were analyzed monthly and quarterly for tritium and gross alpha radioactivity in the onsite laboratory using liquid scintillation and air ion chamber counting techniques, respectively.

Composite samples were analyzed quarterly for Sr-89, Sr-90, Fe-55 and C-14 by a contract laboratory.

The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter.The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent released during periods of discharge.

Gaseous Radioactive Effluents Each gaseous batch, the release was sampled and analyzed for radioactivity prior to release. For releases from Gas Decay Tanks, noble gas grab samples were analyzed for gamma emitting radionuclides using gamma spectroscopy.

For releases from the Containment Buildings, samples were taken of noble gas and tritium grab samples, and analyzed for gamma emitting radionuclides prior to each release. The results of the analyses and the total volume of effluent released were used to determine the total amount of radioactivity released in the batch mode.For continuous effluent release pathways, noble gas and tritium grab samples were collected and analyzed weekly for gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques, respectively.

Continuous release pathways were continuously sampled using radioiodine adsorbers and particulate filters. The radioiodine adsorbers and particulate filters were analyzed weekly for gamma emitting radionuclides using gamma spectroscopy.

Results of the noble gas and tritium grab samples, radioiodine adsorber and particulate filter analyses from the current week and the average effluent flow rate for the previous week were used to determine the total amount of radioactivity released in the continuous mode. Monthly composites of particulate filters were analyzed for gross alpha activity, in the onsite laboratory using the air ion chamber counting technique.

Quarterly composites of particulate filters were analyzed for Sr-89 and Sr-90 by a contract laboratory.

Meteorological Monitoring Program In accordance with ODCM Administrative Control 3.11.2.6.b., a summary of hourly meteorological data, collected during 2010, is retained onsite. This data is available for review by the NRC upon request. During 2010, the goal of >90% joint data recovery was met.

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 THROUGH DECEMBER 31, 2010 Carbon-14 Dose Estimation The estimate of carbon- 14 (C- 14) released from the St. Lucie Nuclear Plant was derived from the EPRI document, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents", Report 1021106, issued December 2010.The site specific source term values used in the St. Lucie calculations were taken from Section 4-28 of the report, and employed the proxy generation rate values for a Combustion Engineering reactor. The actual 2010 operating data for the units was employed for the calculations to derive the total curies released for each unit.The total amount of C-14 released in 2010 for Unit I was 8.03 Ci, and the total amount of C-14 released in 2010 for Unit 2 was 10.12 Ci. The highest calculated dose is found to be"Bone Dose" to a "Child" through "Inhalation".

The total combined dose, including C-14, through this pathway is 3.49E-02 mrem/yr.Additionally, a "Child" consuming vegetables from the garden located at 4.25 miles in the SSW direction from the plant would have received a total combined "Bone Dose", including C-14, of 3.35E-02 mrem/yr.Using the same release values, the dose to a visitor on site (Adult Lifeguard) is found to be 8.04E-03 mrem/yr.All C-14 dose calculations are based on Regulatory Guide 1.109 values.This is a small fraction of the I mrem annual whole body dose received to the average US citizen from natural occurring Carbon-14, primarily generated through cosmogenesis in the terrestrial biosphere. (Reference National Council of Radiation Protection Report 45, Natural Background Radiation in the United States.)Note: Carbon-14 values are provided on this page and are not included in the Tables in Section 3.

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 THROUGH DECEMBER 31, 2010 2.0 SUPPLEMENTAL INFORMATION

2.1 Abnormal

Releases or Abnormal Discharges One abnormal discharge from the site occurred on April 6, 2010. While Operations was re-aligning the Waste Gas Treatment System to the Plant Vent, a relief valve for the IC Gas Decay Tank (GDT) lifted, resulting in a pressure loss of 39 pounds in a four hour period. Investigation revealed the most likely cause of the event to be leakage from V6701, the isolation valve for the gas analyzer from the IC GDT relief valve.Corrective actions included installation of a new bonnet and valve diaphragm.

The I C GDT passed post maintenance testing and was subsequently returned to service. No additional leaks have been identified since its return to service.Release estimates are as follows: Nuclide uCi/cc concentration uCi released Kr-85m 2.11E-07 2.6 Xe-131m 3.87E-06 46.9 Xe-133m 1.60E-05 194.0 Xe-133 6.32E-04 7661.0 Xe-135 1.01E-04 1224.0 C-14 8.01E-09 0.1 Maximum Infant Dose for NW Site Boundary L Total Body -mRemI Skin -mRem I Gamma Air -mRad I Beta Air -mRad 2.29E-07 5.32E-07 2.60E-07 5.78E-07 2.2 Non-Routine Planned Discharges No non-routine planned discharges were made during the report period.2.3 Radioactive Waste Treatment System Changes No changes were made to the waste treatment system during the report period.2.4 Annual Land Use Census Changes No changes were made to the land use census during the report period.

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 THROUGH DECEMBER 31, 2010 2.5 Effluent Monitoring System Inoperability The liquid radioactive waste discharge monitor and the Unit I gaseous waste discharge monitors were out of service for greater than 30 days in 2010. This was due to a plant change/modification (PC/M) to replace the Unit I containment airborne monitors, during the SL1-23 Refueling Outage. This PC/M required the electrical power to the radiation monitor cabinet in the Control Room be removed to provide a safe work environment for replacement of the monitors.

The liquid radioactive waste discharge monitor and the Unit 1 gaseous waste discharge monitor were both returned to service after work was completed on the Unit I Containment Atmosphere Radiation Monitors.2.6 Offsite Dose Calculation Manual Changes One change was made to the St. Lucie ODCM during the report period. The change was to document an evaluation of potential tritium release from the east settling basin, located on site. The evaluation determined that liquid evaporation from the pond represents

<1.0% of the total activity released via all gaseous release points, and does not qualify as a significant release point.2.7 Process Control Program Changes There were no changes to the Process Control Program during the report period.2.8 Corrections to Previous Reports The 2009 Annual Radioactive Effluent Report designated an isotope in the liquid effluent release tables as "Other". This isotope was actually nickel 63 (Ni-63).The "Other" designation conservatively reported the amount of Ni-63 released from the site.2.9 Other Two releases were made from the South Settling Basin to the Intake Canal during the year to lower the water level due to approaching severe weather. The first release took place during June, 2010, and the second took place during August, 2010. Both releases were analyzed according to the ODCM and site procedural requirements and were found to have no alpha, gamma, tritium or hard to detect isotopes.

The volume for each release was estimated to be 4.32E06 gallons.2.10 Groundwater Protection Program FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 THROUGH DECEMBER 31, 2010 3.0 TABLES 3.1 Gaseous Effluents 3.2 Liquid Effluents 3.3 Solid Waste Storage and Shipments 3.4 Dose Assessments Dose to a Member of the Public from Activities Inside the Site Boundary Assessment of radiation dose from radioactive effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY assumes the VISITOR to be a lifeguard at the Walton Rocks Beach recreation area. The visitor is assumed to be onsite for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> per day for 312 days per year at a distance of 1.6 kilometers in the South East Sector. The VISITOR received exposure from each of the two reactors on the site. Actual Met Data was used to calculate Visitor Dose for Calendar Year 2010.VISITOR DOSE RESULTS FOR CALENDAR YEAR 2010 were: Noble Gas Dose mrad F Gamma Air Dose 3.80E-03 Beta Air Dose 2.24E-03 Gas, Particulate, Iodine, Carbon Dose mrem Bone 9.81E-03 Liver 1.77E-03 Thyroid 1.81E-03 Kidney 1.77E-03 Lung 2.24E-03 GI-LLI 1.80E-03 Total Body 7.17E-03 F MCOLL- i gt, w~ N~v c' Sftware Page I of 2 Sunday, February 13, 2011 7:54:59PM Florida Power & Ught St. Lucie Power Plant Table 5A and 5B -Regulatory Guide 1.21 (2010)Batch Release Summary Unit: Site A. Liquid Releases 1. Number of batch releases 2. Total time period for Batch releases 3. Maximum time period for a batch release 4. Average time period for a batch release 5. Minimum time period for a batch release 6. Average stream flow during periods of release of liquid Effluent into a flowing stream Units 1st Quarter 19 (Minutes):

9.65E+03 (Minutes):

6.93E+02 (Minutes):

5.08E+02 (Minutes):

3.77E+02 (LPM ) : 3.86E+06 2nd Quarter 26 2.38E+04 8.28E+03 9.14E+02 3.84E+02 1.64E+06 3rd Quarter 14 2.56E+04 1.76E+04 1,83E+03 3.75E+02 2.09E+06 4th Quarter Year Totals 20 79 9.21E+03 6.82E+04 7.14E+02 1.76E+04 4.61E+02 8.64E+02 2.20E+02 2.20E+02 3.88E+06 2.16E+06 User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 7:54:59PM Page 2 of 2 B. Gaseous Releases Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Totals 1. Number of batch releases 26 31 32 39 128 2. Total time period for batch releases (Minutes):

1.83E+03 3.77E+03 2.31E+03 6.10E+03 1.40E+04 3. Maximum time period for a batch release (Minutes):

3.30E+02 6.OOE+02 2.85E+02 5.60E+02 6.OOE+02 4. Average time period for a batch release (Minutes):

7.04E+01 1.22E+02 7.23E+01 1.56E+02 1.10E+02 5. Minimum time period for a batch release (Minutes):

3.50E+01 5.50E+01 5.90E+01 4.70E+01 3.50E+01 END OF BATCH RELEASE

SUMMARY

REPORT User: Al Locke Database:

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NEOEMSP iEffuc i l\'Iat~atSiot Page 1 of 1 Sunday, February 13, 2011 7:55:42PM Florida Power & Light St. Lucie Power Plant Table IA -Regulatory Guide ( 2010 )Gaseous Effluents

-Summation Of All Releases Unit: Site Type of Effluent A. Fission And Activation Gases 1. Total Release 2. Average Release rate for period 3. Percent of Applicable Limit B. Radioiodines

1. Total Iodine-131

2. Average Release rate for period 3. Percent of Applicable Limit Units Curies uCi/sec Curies I uCi/sec 0%1st Quarter 1.73E+01 2.19E+00 1.10E-05 1.40E-06 2nd Quarter 1.07E+01 1.36E+00 1.26E-05 1.60E-06 ,.3rd Quarter 1.16E+01 1.47E+00 1.84E-05 2.33E-06 4th Quarter O/o Est. Total Error 1.31E+01 1.66E+00 1.76E-05 2.23E-06 C. Particulates

1. Particulates ( Half-Lives

> 8 Days) Curies 1.99E 2. Average Release rate for period uCi/sec : 2.52E 3. Percent of Applicable Limit %*D. Tritium 1. Total Release Curies 5.39E 2. Average Release rate for period uCi/sec : 6.83E 3. Percent of Applicable Limit %*E. Gross Alpha 1. Total Release Curies 2.26E 2. Average Release rate for period uCi/sec 2.86E* Applicable limits are expressed in terms of dose.-05-06-02--03 1.32E-05 1.67E-06 1.99E-01 2.53E-02 1.34E-07 1.70E-08 6.56E-03 8.32E-04 3.53E-01 4.47E-02 , 1.15E-07 1.46E-08 3.40E-06 4.309E-07 1.15E+01 1.45E+00 2.OOE-07 2.54E-08"-06-07 User: Al Locke Database:

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NEOEMSP Eftluctit Ntmiagenoit Smart.Page 1 of 4 Sunday, February 13, 2011 7:56:39PM Florida Power & Light St. Lucie Power Plant Table 1C*Annual Radioactive Effluent Release Report (2010)Gaseous Effluents

-Ground Level Releases Reactor Unit: Site Continuous Mode Nuclides Released Fission Gases Ar-41 Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-138 Total For Period Unit Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Cunes 1st Quarter 7.47E-01 1.70E-01 1.03E+01 2.21E-01 O.OOE+O0 1.24E+00 O.OOE+00 6.97E-01 O.OOE+00 0.OOE+00 3.62E+00 1.70E+O1 2nd Quarter O.OOE+00 3.11E-02 O.OOE+O0 1.10E-01 1.43E+00 2.05E+00 2.94E-01 5.35E-02 O.OOE+00 1.75E-01 2.77E+00 6.92E+00 3rd Quarter 6.30E+00 1.41E-01 O.OOE+0O O.OOE+0O 7.OOE-03 2.13E+00 1.46E+00 0.OOE+00 0.OOE+00 2.95E-01 8.61E-01 1.12E+01 4th Quarter 1.01E+00 5.11E-02 O.OOE+00 5,84E-01 4.66E-01 6.65E+00 1.65E+00 O.OOE+00 1.72E+00 O.OOE+00 O.OOE+00 1.21E+01 lodines 1-131 Curies 1.10E-05 1.26E-05 1.84E-05 1.76E-05 1-133 Curies 1.49E-04 1.86E-04 2.43E-04 2.51E-04 Total For Period Curies 1.60E-04 1.99E-04 2.61E-04 2.69E-04-. -.....- ..- ..- ..- ..- ..- ....- ..- ..- ......- ..- ..- ..- ..- ..-- ..- ..- ..-.- -....- ..- ..- ..- ..- ..- -...- ..- ....- .......-. .-. .-. .-. .-. .-. .- -..-- -. ...- ..- ..- -.-. ...- ..- ..- ..- ..- ..-- ..- .User: Al Locke D~tabase:

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NEOEMSP Sunday, February 13, 2011 7:56:39PM Page 2 of 4 Particulates Cr-51 Curies O.OOE+O0 Co-57 Curies 1.28E-05 Co-58 Curies 9.43E-07 Co-60 Curies O.OOE+00 Cs-134 Curies 0.OOE+00 Cs-137 Curies 5.08E-07 Ce-141 Curies OOOE+00 Ce-144 Curies 5.66E-06 Total For Period Curies 1.99E-05 6.22E-07 1.90E-07 4.95E-06 O.OOE+/-00 0.OOE+00 7.30E-06 1.37E-07 0.OOE+00 1.32E-05 4.50E-06 1.60E-07 0.OOE+O0 1.78E-06 1.53E-08 8.07 E-07 O.OOE-400 9.10E-07 8.17E-06 0.OOE+00 0.OOE+00 O.OOE+O0 0.OOE+00 OOOE+a0 3.40E-06 O.ODE+00 0.OOE+00 3.40E-06 Tritium H-3 Curies 0.OOE+00 0.OOE+00 0.OOE+00 1.14E+01 Gross Alpha G-Alpha Total For Period Curies Curies 2.26E-06 2.26E-06 1.34E-07 1.34E-07 1.15E-07 1.15E-07 2.OOE-07 2.OOE-07 User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 7:56:39PM Page 3 of 4 Table 1C*Annual Radioactive Effluent Release Report (2010)Gaseous Effluents

-Ground Level Releases Reactor Unit: Site Batch Mode Nuclides Released Fission Gases Ar-41 Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-133rm Xe-133 Xe-135m Xe-135 Xe-138 Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 2.25E-01 1.58E-05 1.43E-02 1.37E-04 1.88E-04 6.82E-04 2.80E-04 7.58E-02 2.79E-04 1.27E-03 0.OOE+00 3.19E+00 2.56E-06 1.86E-02 O.OOE+00 1.29E-04 3.11E-04 1.94E-04 5.60E-01 5.72E-04 4.19E-03 5.65E-05 2.64E-01 0.OOE+00 2.01E-02 3.02E-04 0.OOE-.00 0.OOE+00 4.42E-D4 8.05E-02 4.38E-04 1.65E-03 O.00E+00 3.51E-01 5.94E-05 O.OOE+00 O.OOE+00 O.OOE+O0 2.70E-03 7.27E-03 5.64E-01 4.90E-04 4.49E-03 6.85E-04 Total For Period Curies 3.18E-01 3.77E+00 3.68E-01 9.31E-01 lodines-N o N uclides Fo und ------------------------------------

---

N/A ---------------

N /A --------N/A N/A Particulates Ag-lOim Curies O.OOE+O0 O.OOE+00 Total For Period Curies O.OOE+O0 O.OOE+O0 Tritium 6.55E-03 6.55E-03 0.OOE+00 O.OOE+DO Batch Mode Nuclides Released H-3 Unit 1st Quarter 2nd Quarter 3rd Quarter Curies 5.39E-02 1.99E-01 3.53E-01 4th Quarter 1.05E-01 Gross Alpha No Nuclides Found N/A N/A.................................................................................

N/A N/A User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 7:56:39PM Page 4 of 4* Zeroes in this table indicate that no radioactivity was present at detectable levels.END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database:

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............I- l Page I1of I Sunday, February 13, 2011 8:36:13PM Efluent iit nSoftare Florida Power & Light St. Lucie Power Plant Table 1A -Regulatory Guide ( 2010)Gaseous Effluents

-Summation Of All Releases Unit: PSL1 Type of Effluent Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter % Est. Total Error A. Fission And Activation Gases 1. Total Release Curies 2.53E+00 5.83E+00 5.97E+00 8.01E+00 2. Average Release rate for period uCi/sec 3.22E-01 7.39E-01 7.58E-01 1.02E+00 3. Percent of Applicable Limit %* * * *B. Radioiodlnes

1. Total Iodine-131 Curies 2.14E-07 6.38E-07 0.OOE+00 O.OOE+00 2. Average Release rate for period uCi/sec 2.71E-08 8.10E-08 O.OOE+O0 O.OOE+00 3. Percent of Applicable Limit %* * * *C. Particulates

1. Particulates ( Half-Lives

> 8 Days) Curies 1.96E-06 4.58E-06 7.20E-06 0.OOE+00 2. Average Release rate for period uCi/sec 2.49E-07 5.81E-07 9.14E-07 O.OOOE+0O 3. Percent of Applicable Limit %* * * *D. Tritium 1. Total Release Curies O.OOE+00 0.OOE+00 0.OOE+00 1.14E+01 2. Average Release rate for period uCi/sec 0,00E+00 0.OOE+00 O.OOE+00 1.45E+00 3. Percent of Applicable Limit %* * * *E. Gross Alpha 1. Total Release Curies = 5.45E-08 8.84E-08 8.96E-08 1.11E-07 2. Average Release rate for period uCi/sec 6.92E-09 1.12E-08 1.14E-08 1.40E-08* Applicable limits are expressed in terms of dose.User: Al Locke Database:

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NEOEMSP TME~S Efilnuet M~rasnwrint Sc~ttarv Page 1 of 3 Sunday, February 13, 2011 8:38:03PM Florida Power & Light St. Lucie Power Plant Table 1C*Annual Radioactive Effluent Release Report (2010)Gaseous Effluents

-Ground Level Releases Reactor Unit: PSL1 Continuous Mode Nuclides Released Fission Gases Ar-41 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133m Xe-133 Xe-135 Xe-138 Total For Period.....................

e.......1odines Unit Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 1st Quarter 7.47E-01 1.42E-01 2.21E-01 O.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.42E+00 2.53E+00 2nd Quarter O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 2.05E+00 2.94E-01 5.35E-02 o.0oE+00 O.o0E+00 2.39E+00 3rd Quarter 4.22E+00 O.OOE+O0 O.OOE+O0 7.OOE-03 1.25E-05 1.46E+00 O.OOE+00 2.71E-01 O.OOE+00 5.96E+00 4th Quarter 1.01E+00 O.OOE+00 O.OOE+00 4.66E-01 4.99E+00 1.32E+00 0.00E+00 0.OOE+00 O.OOE+00 7.78E+00 1-131 Total For Period Particulates Cr-51 Co-58 Co-60 Cs-137 Ce-144 Curies 2.14E-07 6.38E-07 Curies 2.14E-07 6.38E-07---------------------.. --------------------------------- -- ----0.OOE+00 0.OOE+00 O.OOE+O0 O.OOE+00-----------------------------------

Curies O.OOE+O0 O.OOE+O0 4.50E-06 Curies 9.43E-07 2.44E-06 O.OOE+00 Curies O.OOE+00 O.OOE+00 1.78E-06 Curies 2.85E-07 2.14E-06 1.94E-08 Curies 7.31E-07 O.OOE+O0 9.10E-07 Curies 1.96E-06 4.58E-06 7.20E-06-. -........- ..- -...- ..- .. .- ..- .....- ..- ..-.- --. .-. .-. ... .. ....- ..- ..- ....- ..-.- -..- ..- ....-- -....- -...O.OOE+OO 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Total For Period...........................

Tritium H-3 Curies 0,OOE+00 0.OOE+00 O.OOE+00 1.14E+01 User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 8:38:03PM Page 2 of 3 Gross Alpha G-Alpha Total For Period Curies Curies 5.45E-08 8.84E-08 5.45E-08 8.84E-08 8.96E-08 8.96E-08 1.11E-07 1.11E-07 User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 8:38:03PM Page 3 of 3 Table 1C*Annual Radioactive Effluent Release Report (2010)Gaseous Effluents

-Ground Level Releases Reactor Unit: PSL1 Batch Mode Nuclides Released Fission Gases Ar-41 Kr-85m Xe-131m Xe-133rm Xe-133 Xe-135 Xe-138 Total For Period Unit Curies Curies Curies Curies Curies Curies Curies Curies 1st Quarter O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+O0 2nd Quarter 2.96E+00 2.56E-06 4.69E-05 1.94E-04 4.76E-01 1.22E-03 5.65E-05 3.44E+00 3rd Quarter 1.83E-04 O.OOE+00 O.OOE+00 O.0OE+00 1.52E-02 1.11E-05 0.OOE+00 1.54E-02 4th Quarter 1.17E-01 0.OOE+00 6.30E-04 5.63E-04 1.05E-01 O.OOE+00 6.85E-04 2.24E-01 Iodines No Nuclides Found N/A N/A N/A N/A Particulates No Nuclides Found Tritium N/A N/A N/A N/A Batch Mode Nuclides Released Unit H-3 Curies Gross Alpha No Nuclides Found------------------------------------------------

1st Quarter O.OOE+00 2nd Quarter 0.OOE+00 3rd Quarter 4th Quarter O.OOE+O0 4.70E-02---..-- -------------- --------------- ----------.NIA N/A NIA N/A------------------..-------------------------------------.

.* Zeroes in this table indicate that no radioactivity was present at detectable levels.I END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT I User: Al Locke Database:

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,i.EMS...Page 1 of 1 Sunday, February 13, 2011 8:00:43PM Florida Power & Light St. Lucie Power Plant Table 1A -Regulatory Guide (2010 )Gaseous Effluents

-Summation Of All Releases Unit: P51-2 Type of Effluent A. Fission And Activation Gases 1. Total Release 2. Average Release rate for period 3. Percent of Applicable Limit B. Radioiodines

1. Total Iodine-131

2. Average Release rate for period 3. Percent of Applicable Limit C. Particulates

1. Particulates ( Half-Lives

> 8 Days)2. Average Release rate for period 3. Percent of Applicable Limit D. Tritium 1. Total Release 2. Average Release rate for period 3. Percent of Applicable Limit E. Gross Alpha 1. Total Release 2. Average Release rate for period Units 1st Quarter Curies uCVsec Curies uCsec Curies uCi/sec Curies uCi/sec Curies uCi/sec 1.47E+01 1.87E+00 1.08E-05 1.37E-06 1.79E-05 2.27E-06 5.39E-02 6.83E-03 2.20E-06 2.79E-07 2nd Quarter 4.86E+00 6.16E-01 3rd Quarter 5.58E+00 7.08E-01 4th Quarter 0/0 Est. Total Error 5.05E+00 6.40E-01*k 1.20E-05 1.52E-06 8.62E-06 1 .09E-06 1.99E-01 2.53E-02 4.59E-08 5.82E-09 1.84E-05 2.33E&06 6.55E-03 8.31E-04 3.53E-01 4.47E-02 2.57E-08 3.26E-09 1.76E-05 2.23E-06 3.40E-06 4.309E-07 5.75E-02 7.29E-03 8.96E-08 1.14E-08* Applicable limits are expressed in terms of dose.User: Al Locke Database:

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NEOEMSP EMS B-flUCLA hlanwgemeut S4tware Page 1 of 4 Sunday, February 13, 2011 8:01:09PM Florida Power & Light St. Lucie Power Plant Table 1C*Annual Radioactive Effluent Release Report (2010)Gaseous Effluents

-Ground Level Releases Reactor Unit: PSL2 Continuous Mode Nuclides Released Fission Gases Ar-41 Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-138 Unit Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 1st Quarter 0.OOE+00 2.82E-02 1.03E+01 0.OOE+00 0.OOE+00 1.24E+00 0.OOE+00 6.97E-01 0.OOE+00 0.OOE+00 2.20E+00 1.44E+01 1.08E-05 1.49E-04 1.60E-04 2nd Quarter O.OOE+00 3.11E-02 O.OOE+00 1.IOE-01 1.43E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 1.75E-01 2.77E+00 4.53E+00 1.20E-05 1.86E-04 1.98E-04 3rd Quarter 2.08E+00 1.41E-01 O.OOE+00 O.OOE+OO 0.OOE+00 2.13E+00 0.OOE+00 0-00E+00 0.OOE+00 2.35E-02 8.61E-01 5.23E+00 1.84E-05 2.43E-04 2.61E-04 4th Quarter O.OOE+00 5.11E-02 0.OOE+00 5.84E-01 0.OOE+00 1 .66E+00 3.33E-01 0.OOE+0O 1.72E+00 0.OOE÷00 0.OOE+00 4.34E+00 Total For Period Curies........................................

Iodines 1-131 1-133 Curies Curies Curies 1.76E-05 2.51E-04 2.69E-04 Total For Period User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 8:01:09PM Page 2 of 4 Particulates Cr-51 Co-57 Co-58 Cs-134 Cs-137 Ce-141 Ce-144 Total For Period Curies Curies Curies Curies Curies Curies Curies Curies 0.OOE+00 1.28E-05 0.OOE+00 0.00E+00 2.23E-07 0.OOE+00 4.93E-06 1.79E-05 6.22E-07 1.90E-07 2.51E-06 O.OOE+00 5.16E-06 1.37E-07 O.OOE+00 8.62E-06 O.OOE+00 1 .60E-07 0.OOE÷00 1.53E-08 7.87E-07 0.OOE+00 0.OOE+00 9.62E-07 0.OOE+00 0.00E+00 0.OOE+00 0.OOE-i00 3.40E-06 0.OOE+00 0.OOE+00 3.40E-06 Tritium No Nuclides Found N/A N/A N/A N/A Gross Alpha G-Alpha Total For Period Curies Curies 2.20E-06 2.20E-06 4.59E-08 4.59E-08 2.57E-08 2.57E-08 8.96E-08 8.96E-08 User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 8:01:09PM Page 3 of 4 Table 1C*Annual Radioactive Effluent Release Report (2010)Gaseous Effluents

-Ground Level Releases Reactor Unit: PSL2 Batch Mode Nuclides Released Fission Gases Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Ar-41 Curies 2 Kr-85m Curies 1 Kr-85 Curies 1 Kr-87 Curies 1, Kr-88 Curies 1, Xe-131m Curies 6, Xe-133m Curies 2 Xe-133 Curies 7, Xe-135m Curies 2 Xe-135 Curies 1, Total For Period Curies 3.lodines No Nuclides Found.25E-01 2.29E-01 2.64E-01 2.34E-01.58E-05 0.OOE+00 0.OOE+O0 5.94E-05.43E-02 1 .86E-02 2.01E-02 0.OOE+00.37E-04 0.OOE+00 3.02E-04 0.OOE+00.88E-04 1.29E-04 0.OOE+00 0.OOE+00.82E-04 2.64E-04 0.OOE+00 2.07E-03.80E-04 0.OOE+00 4.42E-04 6.71E-03.58E-02 8.35E-02 6.53E-02 4.59E-01.79E-04 5.72E-04 4.38E-04 4.90E-04.27E-03 2.97E-03 1.64E-03 4.49E-03 18E-01 3.35E-OI 3.52E-01 7.07E-01 N/A Particulates Ag-110rn Curies 0.OOE+00 Total For Period Curies O.OOE+O0 Tritium N/A N/A N/A 0.OOE+00 6.55E-03 0.OOE+00 O.OOE+O0 6.55E-03 O.OOE+O0 Batch Mode Nuclides Released Unit 1st Quarter H-3 Curies 5.39E-02 2nd Quarter 3rd Quarter 4th Quarter 1.99E-01 3.53E-01 5.75E-02 Gross Alpha No Nuclides Found-----------------------------

N/A N/A N/A N/A User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 8:01:09PM Page 4 of 4* Zeroes in this table indicate that no radioactivity was present at detectable levels.L END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database:

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NEOEMSP Page 1 of 1 E M VSunday, February 13, 2011 7:57:41PM Efthierit Sofmwarv Florida Power & Light St. Lucie Power Plant Sunday, February 13, 2011 7:57:41PM Page 1 of 1 Table 2A -Regulatory Guide 1.21 (2010)Liquid Effluents

-Summation Of All Releases Unit: Site Type of Effluent Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 0 Est. Total Error A. Fission And Activation Products 1. Total Release (not including tritium, gases, alpha) Curies 3.02E-02 3.99E-02 1.28E-02 5.22E-02 2. Average diluted concentration during period uCi/ml 8.12E-10 1.02E-09 2.40E-10 1.46E-09 3. Percent of Applicable Limit %* * * *B. Tritium 1. Total Release Curies 5.96E+01 1.12E+02 3.31E+01 6.68E+01 2. Average diluted Concentration during period uCi/ml 1.60E-06 2.87E-06 6.20E-07 1.87E-06 3. Percent of Applicable Limit %* * *C. Dissolved and Entrained Gases 1. Total Release Curies 1.82E-02 1.05E-02 7.39E-04 1.18E-02 2. Average diluted Concentration during period uCi/ml 4.88E-10 2.68E-10 1.38E-11 3.29E-10 3. Percent of Applicable Limit %* *D: Gross Alpha Radioactivity

1. Total Release Curies O.OOE+00 1.31E-05 0.OOE+00 0.OOE+00 E: Waste Vol Release (Pre-Dilution)

Liters 1.59E+06 1.87E+07 2.54E+07 1.43E+06 F. Volume of Dilution Water Used Liters 3.73E+10 3.90E+10 5.34E+10 3.58E+10* Applicable limits are expressed in terms of dose.User: AI Locke Database:

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NECIFMSP imiutMai ~ia. mo.nx Sotma Page 1 of 4 Sunday, February 13, 2011 7:58:14PM Florida Power & Light St. Lucie Power Plant Table 2B -Regulatory Guide 1.21 (2010)Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: Site Continuous Mode Nuclides Released Unit 1st Quarter Fission & Activation Products No Nuclides Found N/A 2nd Quarter N/A 3rd Quarter 4th Quarter N/A N/A Tritium No Nuclides Found Dissolved And Entrained Gases No Nuclides Found N/A N/A N/A N/A N/A N/A N/A N/A If Not Detected, Nuclide is Not Reported User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 7:58:14PM Page 2 of 4 Table 2B -Regulatory Guide 1.21 (2010)Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: Site Batch Mode 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Unit User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 7:58:14PM Page 3 of 4 Fission & Activation Products Fe-55 Curies 9.53E-04 1.61E-02 3.46E-03 8.13E-03 Nb-97 Curies 6.56E-05 5.37E-04 1.14E-04 9.50E-06 1-133 Curies O.OOE+00 O.OOE+00 O.OOE+O0 7.73E-06 C-14 Curies 2.53E-02 1.07E-02 4.42E-03 3.98E-02 Sn-113 Curies 1.13E-05 3.07E-05 0.OOE+00 0.OOE+00 Ag-110m Curies 2.60E-04 1.08E-03 8.81E-04 9.OOE-04 Sb-124 Curies 0.OOE+D0 4.13E-04 2.01E-04 0.OOE+00 W-187 Curies O.OOE+00 0.OOE+00 0.OOE+00 1.24E-05 Co-57 Curies 6.11E-06 1.10E-05 7.79E-06 2.39E-06 Te-129m Curies 0.OOE+00 6.86E-04 O.OOE+00 0.OOE+00 Fe-59 Curies 7.75E-06 1.16E-03 7.64E-05 8.80E-05 Cs-136 Curies O.OOE+0O 5.19E-06 3.06E-06 1.15E-05 Nb-95 Curies 7.26E-05 3.88E-04 3.10E-05 9.22E-05 Co-60 Curies 9.38E-04 1.21E-03 6.03E-04 1.21E-03 1-134 Curies O.OOE+0O 8.63E-06 0.OOE+00 3.50E-06 Cs-138 Curies O.OOE+00 5.36E-05 1.28E-05 1.02E-05 Sr-91 Curies 6.82E-06 2.29E-05 1.33E-05 0.OOE+00 Cs-134 Curies 4.51E-06 7.78E-06 0.OOE+00 0.OOE+00 Sb-122 Curies 0.OOE+00 2.60E-06 8.20E-06 O.OOE+00 1-132 Curies O.OOE+00 3.10E-06 O.OOE+0O O.OOE+O0 Zn-65 Curies 6.77E-06 4.15E-05 2.47E-05 6.41E-06 Tc-99m Curies O.OOE+O0 O.OOE+O0 O.OOE+0O 1.56E-06 Co-58 Curies 7.86E-04 3.74E-03 1.42E-03 1.08E-03 Zr-95 Curies 5.84E-05 2.66E-04 4.53E-05 9.43E-05 Br-82 Curies 1.17E-06 O.OOE+00 O.OOE+00 2.44E-06 1-135 Curies 0.OOE+00 9.23E-06 0.OOE+00 O.OOE+00 Zr-97 Curies 4.60E-04 2.10E-04 1.02E-04 1.48E-04 La-140 Curies O.OOE+00 6.02E-06 0.OOE+00 6.28E-06 Cs-137 Curies 1.63E-04 4.37E-05 6.89E-05 8.05E-05 Mn-54 Curies 1.59E-04 1.80E-04 9.38E-05 1.83E-04 1-131 Curies 3.92E-06 3.85E-06 8.43E-06 5.72E-06 Sr-89 Curies 0.OOE+00 1.41E-04 O.OOE+00 O.OOE+00 Ru-103 Curies 3.52E-06 2.85E-06 3.74E-06 O.OOE+00 Sb-125 Curies 9.49E-04 1.13E-03 1.18E-03 1.79E-04 Cr-51 Curies 2.78E-05 1.67E-03 O.OOE+00 1.11E-04 Ba-140 Curies 3.69E-05 6.57E-06 0.OOE+00 O.OOE+00 Te-132 Curies 0.OOE+00 6.89E-06 0.OOE+00 O.OOE+00 User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 7:58:14PM Page 4 of 4 1-130 Total For Period------------------------------

Trtium H-3------------------------------

Dissolved And Entrained Gases Xe-135m Ar-41 Xe-133 Xe-138 Xe-133m Xe-135 Total For Period Curies Curies 0.OOEi-00 3.02E-02 O.OOE+00 3.99E-02 3.88E-06 1.28E-02 0.OOE+00 5.22E-02 Curies 5.96E+01 1.12E+02 3.31E+01 6.68E+01 Curies Curies Curies Curies Curies Curies Curies 0.00E+00 3.86E-06 1.79E-02 1.43E-05 2.03E-04 1.60E-05 1.82E-02 1.84E-05 0.OOE+O0 1.01E-02 0.OOE+/-00 1 .30E-04 1 .67E-04 1L.05E-02 0.OOE+00 0.OOE+00 7.39E-04 0.OOE+00 0.OQE+O0 0.OOE+00 7.39E-04 0.00E+OO 0.OOE+00 1.16E-02 1.59E-05 1.07E-04 2.91E-06 1.18E-02 If Not Detected, Nuclide is Not Reported* Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-7 for typical minimum detectable concentrations.

END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database:

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.......Page 1ofI.~.. 21 I)Sunday, February 13, 2011 8:43:05PM.ffluent wtia-,L 1it 'k.t'.ar.

Florida Power & Light St. Lucie Power Plant Sunday, February 13, 2011 8:43:05PM Page 1 of 1 Table 2A -Regulatory Guide 1.21 (2010)Liquid Effluents

-Summation Of All Releases Unit: PSL1 Type of Effluent Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter / Est. Total Error A. Fission And Activation Products 1. Total Release (not including tritium, gases, alpha) Curies 1.51E-02 2.OOE-02 6.40E-03 2.61E-02 2. Average diluted concentration during period uCi/ml 8.12E-10 1.02E-09 2.40E-10 1.46E-09 3. Percent of Applicable Limit %* * * *B. Tritium 1. Total Release Curies 2.98E+01 5.61E+01 1.66E+01 3.34E+01 2. Average diluted Concentration during period uCi/mI 1.60E-06 2.87E-06 6.20E-07 1.87E-06 3. Percent of Applicable Umit %* * *C. Dissolved and Entrained Gases 1. Total Release Curies 9.09E-03 5.23E-03 3.70E-04 5.88E-03 2. Average diluted Concentration during period uCi/ml 4.88E-10 2.68E-10 1.38E-11 3.29E-10 3. Percent of Applicable Limit %* * * *D: Gross Alpha Radioactivity

1. Total Release Curies 0.OOE+00 6.53E-06 0.OOE+00 0.OOE+00 E: Waste Vol Release (Pre-Dilution)

Liters 7.94E+05 9.35E+06 1.27E+07 7.15E+05 F. Volume of Dilution Water Used Liters 1.86E+10 1.95E+10 2.67E+10 1.79E+10* Applicable limits are expressed in terms of dose.User: Al Locke Database:

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NEOEMSP Effflitrt MuIana-icti Sha-Page I of 4 Sunday, February 13, 2011 8:43:42PM Florida Power & Light St. Lucie Power Plant Table 2B -Regulatory Guide 1.21 (2010)Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: P511 Continuous Mode Nuclides Released Fission & Activation Products No Nuclides Found Unit 1st Quarter 2nd Quarter N/A 3rd Quarter N/A 4th Quarter N/A N/A Tritium No Nuclides Found N/A N/A N/A................................................................................

Dissolved And Entrained Gases No Nuclides Found N/A N/A N/A N/A N/A If Not Detected, Nuclide is Not Reported User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 8:43:42PM Page 2 of 4 Table 2B -Regulatory Guide 1.21 (2010)Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: PSL1 Batch Mode 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Unit User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 8:43:42PM Page 3 of 4 Fission & Activation Products Zr-97 Curies 2.30E-04 1.05E-04 5.08E-05 7.41E-05 C-14 Curies 1.26E-02 5.37E-03 2.21E-03 1.99E-02 Zn-65 Curies 3.38E-06 2.08E-05 1.24E-05 3.20E-06 Sb-125 Curies 4.74E-04 5.64E-04 5.92E-04 8.94E-05 1-134 Curies 0.OOE+00 4.32E-06 0.OOE+00 1.75E-06 Sb-122 Curies 0.OOE+00 1.30E-06 4.10E-06 O.OOE+00 Sr-91 Curies 3.41E-06 1.15E-05 6.63E-06 O.OOE+00 Ag-110m Curies 1.30E-04 5.38E-04 4.40E-04 4.50E-04 Nb-95 Curies 3.63E-05 1.94E-04 1.55E-05 4.61E-05 Cs-136 Curies 0.00E+00 2.60E-06 1.53E-06 5.77E-06 Te-132 Curies 0.OOE+00 3.45E-06 0.00E+00 O.OOE+00 La-140 Curies 0.OOE+O0 3.01E-06 0.00E+00 3.14E-06 Co-57 Curies 3.05E-06 5.52E-06 3.90E-06 1.19E-06 Sb-124 Curies O.OOE+00 2.07E-04 1.OOE-04 0.O0E+00 Sr-89 Curies 0.OOE+00 7.04E-05 O.OOE+00 0.OOE+00 1-132 Curies 0.OOE+00 1.55E-06 O.OOE+00 0.OOE+00 Cs-134 Curies 2.25E-06 3.89E-06 O.OOE+00 0.OOE+00 Ba-140 Curies 1.85E-05 3.28E-06 O.OE+00 0.OOE+00 1-133 Curies O.OOE+00 O.0OE+00 0.00E+00 3.87E-06 Co-58 Curies 3,93E-04 1.87E-03 7.10E-04 5.42E-04 Cs-138 Curies 0.OOE+00 2,68E-05 6.39E-06 5.09E-06 1-131 Curies 1.96E-06 1,92E-06 4.22E-06 2.86E-06 Ru-103 Curies 1.76E-06 1.43E-06 1.87E-06 O.OOE+00 Co-60 Curies 4.69E-04 6.03E-04 3.02E-04 6.07E-04 1-130 Curies 0.OOE+00 0.OOE+00 1.94E-06 0.OOE+00 Tc-99m Curies 0.OOE+00 0.00E+00 0.OOE+00 7.79E-07 Mn-54 Curies 7.96E-05 9.02E-05 4.69E-05 9.14E-05 Nb-97 Curies 3.28E-05 2.68E-04 5.71E-05 4.75E-06 1-135 Curies 0.OOE+00 4.62E-06 0.OOE+00 0.OOE+00 Zr-95 Curies 2.92E-05 1.33E-04 2.26E-05 4.72E-05 Te-129m Curies 0.OOE+00 3,43E-04 0.OOE+00 0.OOE+00 Fe-55 Curies 4.77E-04 8.06E-03 1.73E-03 4.06E-03 Fe-59 Curies 3.87E-06 5.82E-04 3.82E-05 4.40E-05 Sn-113 Curies 5.66E-06 1.53E-05 0.OOE+00 0.OOE+00 W-187 Curies 0.OOE+00 0.OOE+00 0.OOE+00 6.18E-06 Cr-51 Curies 1.39E-05 8.34E-04 0.OOE+00 5.57E-05 Br-82 Curies 5.87E-07 0,00E+00 0.00E+00 1.22E-06 User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 8:43:42PM Page 4 of 4 Cs-137 Total For Period Tritium H-3 Dissolved And Entrained Gases Xe-133 Xe-135 Xe-133m Xe-138 Ar-41 Xe-135m Total For Period Curies Curies Curies Curies Curies Curies Curies Curies Curies Curies 8.16E-05 1.51E-02 2.18E-05 2.OOE-02 3.44E-05 6.40E-03 4.02E-05 2.61E-02 2.98E+01 5.61E+01 1.66E-+01

.3.34E+01 8.97E-03 8.02E-06 1.01E-04 7.17E-06 1.93E-06 O.OOE+0O 9.09E-03 5.07E-03 8,37E-05 6.49E-05 0.OOE+0O 0.OOE+00 9.21E-06 5.23E-03 3.70E-04 0.OQE+0O 0.OOE+QD 0.OOE+O0 0.OOE+0O 0.OOE+O0 3.70E-04 5.82E-03 1.46E-06 5.33E-05 7.95E-06 0.OOE+00 0.00E+00 5.88E-03 If Not Detected, Nuclide is Not Reported* Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-7 for typical minimum detectable concentrations.

END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database:

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NEOEMSP Effluentt M qan pmcnni~~*tarv Page 1 of 1 Sunday, February 13, 2011 8:03:15PM Florida Power & Light St. Lucie Power Plant Sunday, February 13, 2011 8:03:15PM Page 1 of 1 Table 2A -Regulatory Guide 1.21 (2010)Liquid Effluents

-Summation Of All Releases Unit: PSL2 Type of Effluent U A. Fission And Activation Products 1. Total Release (not including tritium, gases, alpha) C 2. Average diluted concentration during period u 3. Percent of Applicable Limit 01 nits 1st Quarter uries Ci/ml ao B. Tritium 1. Total Release Curies 2. Average diluted Concentration during period uCi/mi 3. Percent of Applicable Limit %C. Dissolved and Entrained Gases 1. Total Release Curies 2. Average diluted Concentration during period uCi/ml 3. Percent of Applicable Limit %D: Gross Alpha Radioactivity

1. Total Release Curies 1.51E-02 8.12E-10 2.98E+01 1 .60E-06 9.09E-03 4.88E-10 0.OOE+00 7.94E+05 1.86E+10 2nd Quarter 2.OOE-02 1.02E-09 3rd Quarter 6.40E-03 2.40E-10 4th Quarter%/o Est. Total Error 5.61E+01 2.87E-06 5.23E-03 2.68E-10 6.53E-06 9.35E+06 1.95E+10 1.66E+01 6.20E-07 3.70E-04 1.38E-11 O.OOE+00 1.27E+07 2.67E+10 2.61E-02 1.46E-09 3.34E+01 1.87E-06 5.88E-03 3.29E-10 0.OOE+00 7.15E+05 1.79E+10 E: Waste Vol Release (Pre-Dilution)

F. Volume of Dilution Water Used Liters Liters* Applicable limits are expressed in terms of dose.User: Al Locke Databse:rSerxr]essedAin[Darbas]:

dose.Database:

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'EMS Sunday, February Page 1 of 4 13, 2011 8:03:37PM Florida Power & Light St. Lucie Power Plant Table 2B -Regulatory Guide 1.21 (2010)Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: PSL2 Continuous Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission & Activation Products No Nuclides Found N/A N/A N/A N/A................................................................................................................................

Tritium No Nuclides Found Dissolved And Entrained Gases No Nuclides Found N/A N/A N/A N/A N/A N/A N/A N/A If Not Detected, Nuclide is Not Reported User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 8:03:37PM Page 2 of 4 Table 2B -Regulatory Guide 1.21 (2010)Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: PSL-2 Batch Mode 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Unit User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 8:03:37PM Page 3 of 4 Fission & Activation Products La-140 Curies O.OOE+00 3.01E-06 O.OOE+00 3.14E-06 Zr-97 Curies 2.30E-04 1.05E-04 5.08E-05 7.41E-05 Sb-124 Curies 0.OOE+00 2.07E-04 1.00E-04 0.OOE+00 1-135 Curies 0.OOE+00 4.62E-06 O.OOE+00 O.OOE+00 Fe-55 Curies 4.77E-04 8.06E-03 1.73E-03 4.06E-03 Ru-103 Curies 1.76E-06 1.43E-06 1.87E-06 0.OOE+00 1-130 Curies O.OOE+00 O.OOE+00 1.94E-06 O.OOE+00 Cs-137 Curies 8.16E-05 2.A8E-05 3.44E-05 4.02E-05 Co-58 Curies 3.93E-04 1.87E-03 7.10E-04 5.42E-04 Sr-89 Curies O.OOE+00 7.04E-05 O.OOE+00 0.OOE+00 Te-129m Curies O.OOE+O0 3.43E-04 O.OOE+O0 O.OOE+00 Sb-122 Curies 0.00E+00 1.30E-06 4.10E-06 O.OOE+00 Fe-59 Curies 3.87E-06 5.82E-04 3.82E-05 4.40E-05 W-187 Curies O.OOE+00 O.OOE+00 O.OOE+00 6.18E-06 1-133 Curies O.OOE+00 O.OOE+00 O.OOE+O0 3.87E-06 Co-57 Curies 3.05E-06 5.52E-06 3.90E-06 1.19E-06 Cs-136 Curies O.OOE+00 2.60E-06 1.53E-06 5.77E-06 Nb-95 Curies 3.63E-05 1.94E-04 1.55E-05 4.61E-05 Ba-140 Curies 1.85E-05 3.28E-06 O.OOE+00 O.OOE+00 1-131 Curies 1.96E-06 1.92E-06 4.22E-06 2.86E-06 Sr-91 Curies 3.41E-06 1.15E-05 6.63E-06 O.OOE+00 Cs-134 Curies 2.25E-06 3.89E-06 O.OOE+00 O.OOE+00 Cs-138 Curies O.OOE+00 2.68E-05 6.39E-06 5.09E-06 Zr-95 Curies 2.92E-05 1.33E-04 2.26E-05 4.72E-05 1-134 Curies 0.OOE+00 4.32E-06 0.OOE+00 1.75E-06 Tc-99m Curies O.OOE+00 O.OOE+O0 O.OOE+00 7.79E-07 Mn-54 Curies 7.96E-05 9.02E-05 4.69E-05 9.14E-05 Br-82 Curies 5.87E-07 O.OOE+O0 0.OOE+00 1.22E-06 Zn-65 Curies 3.38E-06 2.08E-05 1.24E-05 3.20E-06 Nb-97 Curies 3.28E-05 2.68E-04 5.71E-05 4.75E-06 Te-132 Curies 0.OOE+00 3.45E-06 0.00E+00 0.OOE+00 C-14 Curies 1.26E-02 5.37E-03 2.21E-03 1.99E-02 Cr-51 Curies 1.39E-05 8.34E-04 0.OOE+00 5.57E-05 1-132 Curies O.OOE+O0 1.55E-06 O.OOE+00 O.OOF+00 Sb-125 Curies 4.74E-04 5.64E-04 5.92E-04 8.94E-05 Sn-113 Curies 5.66E-06 1.53E-05 O.OOE+00 O.OOE+O0 Ag-110m Curies 1.30E-04 5.38E-04 4.40E-04 4.50E-04 User: Al Locke Database:

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NEOEMSP Sunday, February 13, 2011 8:03:37PM Page 4 of 4 Co-60 Total For Period Curies Curies 4.69E-04 6.03E-04 1.51E-02 2.OOE-O2 3.02E-04 6.40E-03 6.07E-04 2.61E-02 Tritium H-3 Curies 2.98E+01 5,61E+01 1.66E+01 Dissolved And Entrained Gases Ar-41 Curies 1.93E-06 0.00E+00 0.OOE+00 Xe-135rn Curies 0.00E+00 9.21E-06 0.OOE+00 Xe-135 Curies 8.02E-06 8.37E-05 0.00E+00 Xe-133 Curies 8.97E-03 5.07E-03 3.70E-04 Xe-133m Curies 1.01E-04 6.49E-05 O.OOE+0O Xe-138 Curies 7.17E-06 O.OOE+O0 O.OOE+0O Total For Period Curies 9.09E-03 5.23E-03 3.70E-04 3.34E+01 0.QOE+00 O.OOE+O0 1 .46E-06 5.82E-03 5.33E-05 7.95E-06 5.88E-03 If Not Detected, Nuclide is Not Reported* Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-7 for typical minimum detectable concentrations.

END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database:

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NEOEMSP Effluent Sunday, February 13, 2011 8:17:26PM Florida Power & Light St. Lucie Power Plant Nuclides Released A. Particulates and Iodines No Nuclides Found B. Dissolved and Entrained Gase No Nuclides Found C. Tritium No Nuclides Found D. Gross Alpha Activity No Nuclides Found Table A-2B, Liquid Effluents

-Continuous Mode Unit: Site Starting:

l-Jan-2010 Ending: 31-Dec-2010 Units 1ST Quarter 2ND Quarter 3RD Quarter Ci O.OOE+0O O.OOE+00 O.OOE+00 Ci O.OOE+00 O.OOE+00 O.OOE+00 Ci O.OOE+00 O.OOE+00 O.OOE+O0 Ci O.OOE+00 O.OOE+00 O.OOE+00 4TH Quarter O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Total O.OOE+00 0.OOE-i00 0.OOE+00 0.OOE+00 If Not Detected, Nuclide is Not Reported.

Zeroes in this table indicates that no radioactivity was present at detectable levels.User: Al Locke Database:

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.EMS Page 1 of 2 Sunday, February 13, 2011 7:59:12PM Florida Power & Light St. Lucie Power Plant Table 6A and 6B -Regulatory Guide 1.21 (2010)Annual Liquid Effluents

-Abnormal Release Summary Unit: Site A. Liquid Releases Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Totals 1. Number of Releases .0 0 0 0 0 2. Total Time For All Releases (Minutes):

0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 3. Maximum Time For A Release (Minutes):

0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 4. Average Time For A Release (Minutes):

0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 5. Minimum Time For A Release (Minutes):

0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6. Total activity for all releases (Curies) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 User: Al Locke [Server]:

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NEOEMSP Sunday, February 13, 2011 7:59:12PM Page 2 of 2 B. Gaseous Releases Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Totals 1. Number of Releases -0 1 0 0 1 2. Total Time For All Releases (Minutes):

0.OOE+00 2.40E+02 0.OOE+00 0.OOE+00 2.40E+02 3. Maximum Time For A Release (Minutes):

0.OOE+00 2.40E+02 0.OOE+00 0.OOE+00 2.40E+02 4. Average Time For A Release (Minutes):

0.OOE+00 2.40E+02 O.OOE+00 O.OOE+00 2.40E+02 5. Minimum Time For A Release (Minutes):

0.OOE+00 2.40E+02 0.OOE+00 O.OOE+00 2.40E+02 6. Total activity for all releases (Curies ) 0.OOE+00 9.13E-03 0.OOE+00 0.OOE+00 9.13E-03 SI End of Annual Liquid Effluents

-Abnormal Release Summary User: Al Locke [Server]:

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NEOEMSP NRC Regulatory Guide 1.21 Reports Page 1 Report Date: 2/17/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: 1 Waste Stream: Resins, Filters, and Evap Bottoms Ul SRT in 8-120 Unit 2 SRT 2009 Waste Volume Curies % Error Class FtA3 MA3 Shipped (Ci)A 3.27E+03 9.25E+01 5.04E+01 +/- 25%B 2.72E+02 7.70E+00 2.13E+02 +/- 25%C 9.80E+01 2.78E+00 9.76E+01 +1- 25%All 3.64E+03 I 1.03E+02 3.61 E+02 +/- 25%Waste Stream : Dry Active Waste Waste Volume Curies %Error Class Ft^3 MA3 Shipped (Ci)A i 2.38E+04 { 6.74E+02 7.24E+00 +/-25%B 0.OOE+00 0.00E+00 0.OOE+00 +/-25%C 0.00E+00 0.OOE+00 0.OOE+00 +/-25%All 2.38E+04 6.74E+02 7.24E+00 +/-25%Waste Stream : Irradiated Components Waste Volume Curies % Error Class FtA3 MA3 Shipped (Ci)A 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%B 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%C 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%All 0.00E+00 .OOE+00 0.OOE+00 +1-25%

NRC Regulatory Guide 1.21 Reports Page 2 Report Date: 2/17/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: 1 Waste Stream : Other Waste Combined Packages Waste Volume Curies % Error Class Ft^3 MA3 Shipped (Ci)A 6.22E+03 1.76E+02 1.05E+01 +/-25%B 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%C 2.94E+01 8.33E-01 1.17E+02 +/-25%All 6.25E+03 j 1.77E+02 1.27E+02 +/-25%Waste Stream : Sum of All 4 Categories Combined Packages Ul SRT in 8-120 Unit 2 SRT 2009 Waste Volume Curies 1 % Error Class FtA3 MA3 Shipped (Ci)A 3.33E+04 9.43E+02 6.81 E+01 +/-25%B 2.72E+02 7.70E+00 2.13E+02 +/-25%C 1.27E+02 3.61E+00 2.14E+02 +/-25%All 3.37E+04 9.54E+02 4.96E+02 +/-25%-Combined Waste Type Shipment, Major Volume Waste Type Shown NRC Regulatory Guide 1.21 Reports Page 1 Report Date: 2/17/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Number of Shipments Mode of Transportation Destination 2 Hittman Transport (SC) EnergySolutions Bear Creek 18 Hittman Transport (TN) EnergySolutions Bear Creek 1 Southern Pines Trucking EnergySolutions Bear Creek 2 Hittman Transport (SC) EnergySolutions LLC.1 Hittman Transport (TN) EnergySolutions LLC.2 Hittman Transport (SC) Studsvik Processing Facility LLC -Erwin 3 Hittman Transport (TN) Studsvik Processing Facility LLC -Erwin NRC Regulatory Guide 1.21 Reports Page 1 Report Date: 2/17/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: 1 Resins, Filters, and Evap Bottom Waste Class A Nuclide Name Percent Abundance Curies Mn-54 1.108% 5.58E-01 Fe-55 47.276% 2.38E+01 Co-60 26.600% 1.34E+01 Ni-63 21.552% 1.09E+01 Sb-125 1.065% 5.37E-01 Resins, Filters, and Evap Bottom Waste Class B Nuclide Name Percent Abundance Curies H-3 1.125% 2.40E+00 Mn-54 3.350% 7.14E+00 Fe-55 14.920% 3.18E+01 Co-58 20.275% 4.32E+01 Co-60 6.731% 1.43E+01 Ni-63 36.300% 7.74E+01 Sb-125 1.095% 2.33E+00 Cs-134 1.282% 2.73E+00 Cs-137 8.951% 1.91E+01 Ce-144 5.158% 1.10E+01 Resins, Filters, and Evap Bottom Waste Class C Nuclide Name Percent Abundance Curies H-3 1.085% 1.06E+00 Mn-54 2.540% 2.48E+00 Fe-55 16.107% 1.57E+01 Co-58 1.614% 1.58E+00 Co-60 6.871% 6.71 E+00 Ni-63 16.139% 1.58E+01 Cs-1 34 2.373% 2.32E+00 Cs-137 33.893% 3.31E+01 Ce-144 17.833% 1.74E+01 Resins, Filters, and Evap Bottom Waste Class All Nuclide Name Percent Abundance Curies Mn-54 2.818% 1.02E+01 Fe-55 19.757% 7.13E+01 Co-58 12.538% 4.53E+01 Co-60 9.542% 3.45E+01 Ni-63 28.793% 1.04E+02 Cs-1 34 1.398% 5.05E+00 Cs-I 37 14.451% 5.22E+01 Ce-144 7.898% 2.85E+01 Dry Active Waste Waste Class A NRC Regulatory Guide 1.21 Reports Page 2 Report Date : 2/17/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: I Nuclide Name Percent Abundance Curies Cr-51 4.320% 3.13E-01 Fe-55 34.944% 2.53E+00 Co-58 23.267% 1.69E+00 Co-60 10.028% 7.26E-01 Ni-63 12.695% 9.19E-01 Zr-95 2.316% 1.68E-01 Nb-95 3.750% 2.72E-01 Sn-1 13 1.373% 9.94E-02 Cs-137 2.284% 1.65E-01 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies Cr-51 4.320% 3.13E-01 Fe-55 34.944% 2.53E+00 Co-58 23.267% 1.69E+00 Co-60 10.028% 7.26E-01 Ni-63 12.695% 9.19E-01 Zr-95 2.316% 1.68E-01 Nb-95 3.750% 2.72E-01 Sn-113 1.373% 9.94E-02 Cs-137 2.284% 1.65E-01 Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 4.080% 4.28E-01 Mn-54 1.577% 1.65E-01 Fe-55 29.193% 3.06E+00 Co-58 32.027% 3.36E+00 Co-60 10.100% 1.06E+00 Ni-63 13.066% 1.37E+00 Ag-110m 1.515% 1.59E-01 Sb-125 4.179% 4.38E-01 Ce-144 1.357% 1.42E-01 Other Waste Waste Class C Nuclide Name Percent Abundance Curies Fe-55 40.155% 4.69E+01 Co-60 9.562% 1.12E+01 Ni-63 49.077% 5.73E+01 Other Waste Waste Class All Nuclide Name Percent Abundance Curies Fe-55 39.252% 4.99E+01 Co-58 2.642% 3.36E+00 Co-60 9.607% 1.22E+01 Ni-63 46.109% 5.87E+01 NRC Regulatory Guide 1.21 Reports Page 3 Report Date: 2/17/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: 1 Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies Mn-54 1.138% 7.75E-01 Fe-55 43.182% 2.94E+01 Co-58 8.125% 5.54E+00 Co-60 22.299% 1.52E+01 Ni-63 19.305% 1.32E+01 Sb-125 1.530% 1.04E+00 Sum of All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 1.125% 2.40E+00 Mn-54 3.350% 7.14E+00 Fe-55 14.920% 3.18E+01 Co-58 20.275% 4.32E+01 Co-60 6.731% 1.43E+01 Ni-63 36.300% 7.74E+01 Sb-125 1.095% 2.33E+00 Cs-134 1.282% 2.73E+00 Cs-137 8.951% 1.91 E+01 Ce-144 5.158% 1.10E+01 Sum of All 4 Categories Waste Class C Nuclide Name Percent Abundance Curies Mn-54 1.235% 2.65E+00 Fe-55 298206% 6.26E+01 Co-60 8.337% 1.79E+01 Ni-63 34.080% 7.30E+01 Cs-134 1.087% 2.33E+00 Cs-137 15.906% 3.41E+01 Ce-144 8.128% 1.74E+01 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies Mn-54 2.131% 1.06E+01 Fe-55 24.984% 1.24E+02 Co-58 10.154% 5.03E+01 Co-60 9.566% 4.74E+01 Ni-63 33.004% 1.64E+02 Cs-134 1.022% 5.07E+00 Cs-1 37 10.789% 5.35E+01 Ce-144 5.800% 2.87E+01 Gas Status Summary Report Sunday, February 13, 201120:09 Page 14 of 15 Period: Ann, 2010 Site/Unit/Discharge Point: Site Site Boundary NNG Doserate Summary -Note: All Doses in mRem/yr Receptor Agegroup Bone Uver Total Body Thyroid Kidney Lung GI-Lli Skin NW Site Boundary -In Infant 1.215E-03 1.860E-03 1.739E-03 5.643E-03 1.383E-03 1.783E-03 2.581E-03 0.OOOE+00 WNW Site Boundary -I Infant 1.059E-03 1.059E-03 1.059E-03 1.059E-03 1.059E-03 1.059E-03 1.059E-03 0.OOOE+00 Maximum Doserate by Organ: 1.215E-03 1.860E-03 1.739E-03 5.643E-03 1.383E-03 1.783E-03 2.581E-03 O.OOOE+00 Maximum Organ Doserate (mRem/yr):

5.643E-03 Maximum Total Body Doserate (mRem/yr):

1.739E-03 Site Boundary NG Doserate Summary Gas Receptor Location NW Site Boundary WNW Site Boundary Gamma (mRad/yr)2.228E-03 1.919E-03 Beta (mRad/yr)2.228E-03 1.919E-03 Total Body (mRem/yr)2.117E-03 1.824E-03 Skin (mRem/yr)3.463E-03 2.983E-03 User: Al Locke[Server]:

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NEOEMSP Gas Status Summary Report Sunday, February 13, 201120:09 Page 15 of 15 Gas Status Summary Report Sunday, February 13, 2011 20:09 Page 15 of 15 Period: Ann, 2010 Site/Unit/Discharge Point: Site Maximum Individual NNG Dose Summary -Note: All Doses in mRem Receptor SE Nearest Res -Adult SE Nearest Res -Child SE Nearest Res -Infant SE Nearest Res -Teenager SE Visitor -Adult SSW Near Garden -Adult SSW Near Garden -Child SSW Near Garden -WSW Near Milk -Adult WSW Near Milk -Child WSW Near Milk -Infant WSW Near Milk -Teenager Agegroup Adult Child Infant Teenager Adult Adult Child Teenager Adult Child Infant Teenager Bone 2.062E-03 2.061E-03 2.061E-03 2.062E-03 9.577E-04 1.597E-04 1.597E-0J4 1.597E-04 3.743E-0J4 3.887E-04 Liver 2.062E-03 2.061E-03 2.061E-0J3 2.062E-03 9.576E-04 1.597E-04 1.597E-04 1.597E-04 3.760E-04 3.882E-04 Total Body 2.061E-03 2.061E-03 2.061E-03 2.061E-03 9.572E-04 1.597E-04 1.596E-04 1.597E-04 3.734E-04 3.730E-04 Thyroid 2.119E-03 2.156E-03 2.149E-03 2.136E-03 9.826E-04 1.637E-04 1.662E-04 1.648E-04 5.521E-04 9.225E-04 Kidney 2.063E-03 2.062E-03 2.061E-03 2.063E-03 9.581E-04 1.598E-04 1.597E-04 1.598E-0J4 3.734E-04 3.735E-04 3.734E-04 6.641E-06 Lung 2.634E-03 2.328E-03 2.162E-03 2.635E-03 1.207E-03 1.990JE-04 1.779E-04 1.990E-04 4.394E-04 4.033E-04 3.862E-04 7.13 1E-05 GI-LiI 2.098E-03 2.078E-03 2.067E-03 2.098E-03 9.732E-04 1.622E-04 1.608E-04 1.622E-04 6.43BE-04 6.587E-04 6.574E-04 5.073E-04 Skin O.OOOE-e-O O.OOO1E+00 O.OOO1E+00 0.00O1E+ 00 0.00O1E+00 0.00O1E+00 0.OOO1E+00 0.0001E+00 0.00DE+00 0.OO01E+00 0.00O1E+f00 O.OOOE+00 4.094E-04 4.145E-0J4 9.578E-06 1.234E-05 3.739E-04 1.688E-03 4.865E-06 2.802E-G4 Maximum Dose by Organ: Maximum Organ Dose (mRem): 2.062E-03 2.062E-03 2.061E-03 2.156E-03 2.063E-03 2.635E-03 2.098E-03 0.OOOE+00 2.635E-03 Maximum Total Body Dose (mRem): 2.061E-03 Maximum Individual NG Dose Summary Gas Receptor Location SSW Near Gard 4.4 mi 207 deg SE Nearest Res 1.52 mi 142 deg SE Visitor WSW Near Milk 3.43 mi 248 deg Gamma (mRad)3.854E-04 5.080E-03 2.200E-03 6.841E-04 Beta (mRad)2.279E-04 3.005E-03 1.301E-03 4.046E-04 Total Body (mRem)3.663E-04 4.829E-03 2.091E-03 6.502E-04 Skin (mRem)5.990E-04 7.896E-03 3.419E-03 1.063E-03 User: Al Locke[Server]:

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NEOEMSP Gas Status Summary Report Sunday, February 13, 201120:10 Page 6 of 7 Period: Ann, 2010 Site/Unit/

Discharge Point: PSL1 Site Boundary NNG Doserate Summary -Note: All Doses in mRem/yr Receptor Agegroup Bone Liver Total Body Thyroid Kidney Lung GI-Lli Skin WNW Site Boundary -I Infant 1.595E-06 1.595E-06 1.595E-06

.1.595E-06 1.595E-06 1.595E-06 1.595E-06 0.000E+00 NW Site Boundary -In Infant 6.233E-05 1.550E-03 1.492E-03 1.606E-03 6.566E-04 1.497E-03 1.489E-03 0.OOOE+00 Maximum Doserate by Organ: 6.233E-05 1.550E-03 1.492E-03 1.606E-03 6.566E-04 1.497E-03 1.489E-03 O.OOOE+00 Maximum Organ Doserate (mRem/yr):

1.606E-03 Maximum Total Body Doserate (mRem/yr):

1.492E-03 Site Boundary NG Doserate Summary Gas Receptor Location NW Site Boundary WNW Site Boundary Gamma (mRad/yr)2.683E-03 2.311E-03 Beta (mRad/yr)2.683E-03 2.311E-03 Total Body (mRem/yr)2.541E-03 2.189E-03 Skin (mRem/yr)3.957E-03 3.409E-03 User: Al Locke[Server]:

PSLSA37 [Database]:

NEOEMSP Gas Status Summary Report Sunday, February 13, 201120:10 Page 7 of 7 Gas Status Summary Report Sunday, February 13, 2011 20:10 Page 7 of 7 Period: Ann, 2010 Site/Unit/Discharge Point: PSL1 Maximum Individual NNG Dose Summary -Note: All Doses in mRem Receptor SE Nearest Res -Adult SE Nearest Res -Child SE Nearest Res -Infant SE Nearest Res -Teenager SE Visitor -Adult SSW Near Garden -Adult SSW Near Garden -Child SSW Near Garden -WSW Near Milk -Adult WSW Near Milk -Child WSW Near Milk -Infant WSW Near Milk -Teenager Agegroup Adult ChIld Infant Teenager Adult Adult Child Teenager Adult Child Infant Teenager Bone 5.K796E-06 5.726E-06 5.714E-06 5.710E-06 2.68SE-06 4.478E-07 4.430E-07 4.420E-07 1.884E-06 4.571E-06 8.443E-06 1.509E-06 Liver 5.741E-06 5.710E-06 5.707E-06 5.711E-06 2.664E-06 4.441E-07 4.420E-07 4.420E-07 2.189E-06 4.456E-06 9.330E-06 2.029E-06 Total Body 5.694E-06 5.674E-06 5.670E-06 5.682E-06 2.643E-06 4.408E-07 4.395E-07 4.401E-07 1.783E-06 1.540E-06 1.519E-06 7.193E-07 Thyroid 5.858E-06 5.914E-06 5.894E-06 5.890E-06 2.715E-06 4.521E-07 4.560E-07 4.543E-07 3.260E-06 7.618E-06 1.688E-05 3.400E-06 Kidney 5.705E-06 5.684E-06 5.674E-06 5.705E-06 2.648E-06 4.416E-07 4.402E-07 4.416E-07 1.425E-06 1.450E-06 1.448E-06 5.377E-07 Lung 6.172E-06 6.356E-06 6.307E-06 6.475E-06 2.852E-06 4.736E-07 4.863E-07 4.944E-07 1.207E-06 1.500E-06 2.091E-06 3.650E-07 GI-Lli 5.709E-06 5.685E-06 5.674E-06 5.708E-06 2.650E-06 4.419E-07 4.403E-07 4.418E-07 1.048E-06 1.043E-06 1.042E-06 7.585E-08 Skin 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 0.000E+00 0.000E+00 Maximum Dose by Organ: Maximum Organ Dose (mRem): 8.443E-06 9.330E-06 5.694E-06 1.688E-05 5.705E-06 6.475E-06 5.709E-06 0.000E+00 1.688E-05 Maximum Total Body Dose (mRem): 5.694E-06 Maximum Individual NG Dose Summary Gas Receptor Location Gamma (mRad) Beta (mRad) Total Body (mRem)3.312E-04 1.646E-04 3.137E-04 WSW Near Milk 3.43 mi 248 deg SSW Near Gard 4.4 mi 207 deg SE Visitor SE Nearest Res 1.52 mi 142 deg 1.866E-04 1.065E-03 2.459E-03 9.270E-05 5.291E-04 1.222E-03 1.767E-04 1.009E-03 2.329E-03 Skin (mRem)4.884E-04 2.752E-04 1.571E-03 3.627E-03 User: Al Locke[Server]:

PSLSA37 [Database]:

NEOEMSP Gas Status Summary Report Sunday, February 13, 201120:11 Page 10 of 11 Period: Ann, 2010 Site/Unit/Discharge Point: PSL2 Site Boundary NNG Doserate Summary -Note: All Doses in mRem/yr Receptor Agegroup Bone Liver Total Body Thyroid Kidney Lung GI-Lli Skin WNW Site Boundary -I Infant 1.769E-03 1.769E-03 1.769E-03 1.769E-03 1.769E-03 1.769E-03 1.769E-03 0.OOOE+00 NW Site Boundary -In Infant 1.989E-03 2.068E-03 1.905E-03 8.357E-03 1.871E-03 1.975E-03 3.315E-03 0.OOOE+00 Maximum Doserate by Organ: 1.989E-03 2.068E-03 1.905E-03 8.357E-03 1.871E-03 1.975E-03 3.315E-03 O.OOOE+00 Maximum Organ Doserate (mRem/yr):

Maximum Total Body Doserate (mRem/yr):

Site Boundary NG Doserate Summary Gas Receptor Location 8.357E-03 1.905E-03 WNW Site Boundary NW Site Boundary Gamma (mRad/yr)1.656E-03 1.922E-03 Beta (mRad/yr)1.656E-03 1.922E-03 Total Body (mRem/yr)1.579E-03 1.833E-03 Skin (mRem/yr)2.697E-03 3.130E-03 User: Al Locke[Server]:

PSLSA37 [Database]:

NEOEMSP Gas Status Summary Report Sunday, February 13, 201120:11 Page 11 of 11 Gas Status Summary Report Sunday, February 13, 2011 20:11 Page 11 of 11 Period: Ann, 2010 Site/Unit/Discharge Point: PSL2 Maximum Individual NNG Dose Summary -Note: All Doses In mRem Receptor SE Nearest Res -Adult SE Nearest Res -Child SE Nearest Res -Infant SE Nearest Res -Teenager SE Visitor -Adult SSW Near Garden -Adult SSW Near Garden -Child SSW Near Garden -WSW Near Milk -Adult WSW Near Milk -Child WSW Near Milk -Infant WSW Near Milk -Teenager Agegroup Adult Child Infant Teenager Adult Adult Child Teenager Adult Child Infant Teenager Bone 2.056E-03 2.056E-03 2.055E-03 2.056E-03 9.550E-04 1 .593E-04 1.592E-04 1 .593E-04 3.725E-04 3.84IE-04 4.009E-04 8.069E-06 Liver 2.056E-03 2.056E-03 2.055E-03 2.056E-03 9.549E-04 1.593E-04 1 .592E-04 1.593E-04 3.73SE-04 3.837E-04 4.052E-04 1 .031E-05 Total Body 2.056E-03 2.055E-03 2.055E-03 2.056E-03 9.546E-04 1.592E-04 1.592E-04 1.592E-04 3.7 16E-04 3.715E-04 3.724E-04 4.145E-06 Thyroid 2.114E-03 2. 150E-03 2.14315-03 2.130E-03 9.799E-04 1.632E-04 1.657E-04 1.643E-04 5.489E-04 9.149E-04 1.671E-03 2.768E-04 Kidney 2.058E-03 2.056E-03 2.055E-03 2.058E-03 9.555E-04 1.594E-041 1.593E-04 1.594E-04 3.720E-04 3.721 E-04 3.720E-04 6.103E-06 Lung 2.628E-03 2.321E-03 2.156E-03 2.629E-03 1.205E-03 1.985E-04 1.774E-04 1.985E-04 4.382E-04 4.018E-04 3.841E-04 7.095E-05 GI-Ili1 2.092E-03 2.072E-03 2.06IE-03 2.092E-03 9.705E-04 1.617E-04 1.604E-04 1.617E-04 6.427E-04 6.577E-04 6.564E-04 5.072E-04 Skin O.OOOE+O0 O.OOOE+0D O.OOOE+O0 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+OO O.OOOE+OO O.OOOE+00 0.OOOE+00 Maximum Dose by Organ: Maximum Organ Dose (mRem): 2.056E-03 2.056E-03 2.056E-03 2.150E-03 2.058E-03 2.629E-03 2.092E-03 0.OOOE+00 2.629E-03 Maximum Total Body Dose (mRem): 2.056E-03 Maximum Individual NG Dose Summary Gas Receptor Location WSW Near Milk 3.43 mi 248 deg SSW Near Gard 4.4 mi 207 deg SE Nearest Res 1.52 mi 142 deg SE Visitor Gamma (mRad) Beta (mRad) Total Body (mRem)3.530E-04 2.401E-04 3.366E-04 1.988E-04 2.621E-03 1.135E-03 1.352E-04 1.783E-03 7.719E-04 1.896E-04 2.499E-03 1.082E-03 Skin (mRem)5,749E-04 3.239E-04 4.269E-03 1.848E-03 User: Al Locke[Server]:

PSLSA37 [Database]:

NEOEMSP Liquid Status Summary Report Sunday, February 13, 201120:12 Page 6 of 6 Period: Ann, 2010 Site/Unit/Discharge Point: Site Liquid Dose Summary -Note: All Doses in mRem Receotor Aoecroup Bone Uver Total Body Thyroid Kidney Lung GI-Lli Skin Uquid Receptor -Teenager Teenager 5.112E-02 2.152E-01 6.081E-02 4.234E-03 4.350E-03 2.442E-01 1.425E-01 O.OOOE+00 Uquid Recptor -Child Child 2.532E-02 9.804E-02 3.017E-02 5.009E-03 1.891E-03 1.110E-01 6.449E-02 O.OOOE+00 Maximum Dose by Organ: 5.112E-02 2.152E-O1 6.081E-02 5.009E-03 4.350E-03 2.442E-01 1.425E-01 O.OOOE+00 Maximum Organ Dose (mRem): Maximum Total Body Dose (mRem): 2.442E-01 6.081E-02 User: Al Locke[Server]:

PSLSA37 [Database]:

NEOEMSP Liquid Status Summary Report Sunday, February 13, 201120:13 Page 6 of 6 Period: Ann, 2010 Site/Unit/Discharge Point: PSL1 Liquid Dose Summary -Note: All Doses in mRem Receptor AecrouD Done Liver Total Body Thyroid Kidney Lung GI-Li Skin Liquid Recptor -Child Child 1.266E-02 4.902E-02 1.509E-02 2.505E-03 9.455E-04 5.552E-02 3.224E-02 OOOOE+00 Liquid Receptor -Teenager Teenager 2.556E-02 1.076E-01 3.041E-02 2.117E-03 2.175E-03 1.221E-01 7.127E-02 O.OOOE+00 Maximum Dose by Organ: 2.556E-02 1.076E-01 3.041E-02 2.505E-03 2.175E-03 1.221E-01 7.127E-02 O.OOOE+00 Maximum Organ Dose (mRem): Maximum Total Body Dose (mRem): 1.221E-01 3.041E-02 User: All Locke[Server]:

PSLSA37 [Database]:

NEOEMSP Liquid Status Summary Report Sunday, February 13, 201120:14 Page 6 of 6 Period: Ann, 2010 Site/Unit/Discharge Point: PSL2 Liquid Dose Summary -Note: All Doses in mRem Receptor AgearouD Bone Liver Total Body Thyroid Kidne Lu"n GI-Li Skin Uquid Receptor -Teenager Teenager 2.556E-02 1.076E-01 3.041E-02 2.117E-03 2.175E-03 1.221E-01 7.127E-02 O.OOOE+00 Uquid Recptor -Child Child 1.266E-02 4.902E-02 1.509E-02 2.505E-03 9.455E-04 5.552E-02 3.224E-02 O.OOOE+00 Maximum Dose by Organ: 2.556E-02 1.076E-01 3.041E-02 2.505E-03 2.175E-03 1.221E-01 7.127E-02 O.OOOE+00 Maximum Organ Dose (mRem): Maximum Total Body Dose (mRem): 1.221E-01 3.041E-02 User: Al Locke[Server]:

PSLSA37 [Database]:

NEOEMSP FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 THROUGH DECEMBER 31, 2010 L-2011-064 ENCLOSURE

]INFORMATION FOR GROUND WATER PROTECTION PROGRAM (1 PAGE)

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS I AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2010 THROUGH DECEMBER 31,2010 L-2011 -064 ENCLOSU(RE I PAGE I OF I Well ID H3 Jan 2010 H3Feb2010 H3Mar H3Apr2010 H3 May H3 June201 H3 July H3 Aug H3 Sept H3 OCT H3 NOV H3 Dec 2010 2010 2010 2010 2010 2010 2010 2010 li l U ii&W21 pCilI pCil pClIl pCIl pCpC pCp1 pCpil pCpl OCI pCll pCvI pCIv MW-3 .'MDA (470) , , MDA(500) .508 :, C.: : ". 308 MW-4 <MDA (420) 410 75(0 'MDA,(500)

<MDA (500) 'MDA (500) 400 439 405 479 308 MW-5 DA(470) , -'MDA (500) 225. <MDC (218)MW-6 2420 1750 2720 1470 860 1430 1200 1030 1530 1550 1220 <1300" MW-7 MDA (470) .. MDA (500) 237 <MDC (229)MW-15 4MDA (420) <MDA (500) "21 3, .. .MW-16 ,,_ ",- MDA (420) ..... ,... ,... -... <MDA (500) -MDC (238) .MD. (221)MW 1 °", : /,, ,-, <MDC (221) .....MW-17 <MDA (420) 'MDA (420) 460 'MDA (5000) <MDA (500) 680 399 447 636 445 495 '1200" MW-18D 4MDA (420) 780 8800 MDA (500) 590 610 415 499 425 010 967 <1200" MW-19 W. ' MDA (410) 'MDA (500) 372.- 272 MW"22D ": DA (470) <MDA (500) <MDC (200) 303 *MW-26 MDA (470) .<MDA (500) <MDC (198) MDC (210)" RW-2 4460 2580 4140 2290 1240 3300 1580 1720 2630 2470 757 1510 RW-4 -MDA (470) '<MDA (500) "MDC (203) 'MDC (221)RW-5 MDA (470) 'MDA (500) <MDC (197) 'MDC: (219)MW-30 D"MDA (500) "MDC (199)M MW-31 430 600 481 23 MW-32 MDA (410) ' MDA (500) "MDC (232) '"... <MDC (204)MW-33 6270 6100 6130 4680 4320 47j00 3490 32 50 4200 2870 2890 2840*anlay-zed by PSL Well ID H3 Jan 2010 H3 Feb 2010 H3 Mar H3Apt2010 H3 May H3 June2010 H3 July H3 Aug H3 Sept H3 OCT H3 NOV H13 Dec 2010 2010 2010 2010 2010 2010 2010 2010____________

PCUI pCinl pCil pCiII pCOi pCil PCOI pCOi pCvl pCil pCin pCu Unit 1 -MWoo1 4060 3740 3760 3340 2120 3550 1980 1800 2940 1980 1780 1970 Und 1 -MVV002 1120 890 1260 850 930 1130 633 733 891 808 819 833 Unit 1 -MWO03 .440 850 900 .MDA (500) <MDA (500) 630 321 427 450 243 Unit 1 -MWO04 490 .... .MDA (500) ..... .237 .. .. .... 237 Unit 1-MWO05 4240 3010 .617 1050 1700 2070 851 1100 2950 2440 1310 2240 Unit2-MW001 2310 3630 43.00 3370 1520 1390 943 1570 1480 1080 3670 4790 Uni 2 -MWO02 2410 1990 2240 1700 1960 2230 1600 1450 1720 1140 1340 704 Unit 2 -MWO03 1870 1830 1750 1380 1680 1530 2130 1210 1300 1340 1190 1040 Unit 2- MWO04 1900 1750 1770 1720 18000 2050 1890 1660 1770 100 1520 1590 Well ID H3 Jan 2010 1H3 Feb 2010 H3 Mar H3 Apr 2010 H3 May H3 June2010 H3 July H3 Aug H3 Sept H3 OCT H3 NOV H3 Dec 2010 2010 2010 2010 2010 2010 2010 2010 MlI l1IpCi l pCi l pCi l pCbC pC pCpl Ct11 pCil pC pCt pCCl pCtL pC91 (S)-MW-1 <MDA (420)(S)-MW-3 (S)-MW-4 .60 1030 950 540 720 929 (S)-MW-5 (S)-MW-S ýMDA (420) :MDA (500) 576 93. ..... ..... ..(S)-MW-7A

<DA (420)(S)-MW-iS (S-MW-il 630 960 9 (S)-MW-12 (S MW-13D (S)-MW-14 (S)-MW-15D DA")460 48 (S)-MW-16

<MDA (420) '<MDA (500) 'MDC (200) <MDC (222)(S)-MW-16i

<MDA (420) 'MDA (500) "MDC (283) 'MDC: (225)(S)-MW-17

'MDA (420) <MDA (470) <'MDA (500 MDA (500) <MDA (500) 316 264 (S)-MW-B MDA (420) MDA (500) 'MDC (197) .<MDC (207)(S)-MW-;1 440 <MDA (500) 261 232__:__ " Well ID H3 Jan 10 H3 Feb 2010 H3 Mar 2 H3 May June2 H3,July H3 Aug H3 Sept H3 OCT H3 NOV H3 Dec 2010 H3 20r2010 261 H3 2010 2010 2010 2010 2010 2010 2010 lmN ei iti iBi i pCIA , pC l/I pCill pCl 1 pCi.I pCvl pCl /I pCi, pC9/ pCi/I pCIn pCl11 PSLED 2 .<'MDA (470) "" ," N B -M W -i ' .' M D A (4 7 0 ) "': ...N8-MW-2 -<MDA (470) _______