ML12068A207

Annual Radioactive Effluent Release Report January 1, 2011 Through December 31, 2011

ML12068A207
Person / Time
Site:	Saint Lucie
Issue date:	03/01/2012
From:	Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML12068A207 (58)

Text

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 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 1,2011 THROUGH DECEMBER 31, 2011 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, 2011 THROUGH DECEMBER 31, 2011 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 2.0E-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 gtCi/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 4.11-1 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, 2011 THROUGH DECEMBER 31, 2011 The estimate of errors associated with values reported are as follows:

LIQUID GASEOUS Error Topic Avg. % Max. % Avg. % Max. %

Release Point Mixing 2 5 NA NA Sampling 1 5 2 5 Sample Preparation 1 5 1 5 Sample Analysis 3 10 3 10 Release Volume 2 5 4 15 Total % 9 30 10 35 (above values are examples only)

The predictability of error for radioactive releases can only be applied to nuclides that are predominant in sample spectrums. Nuclides that are near background relative to the predominant nuclides in a given sample could easily have errors greater than the above listed maximums.

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.

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 Gaseous Radioactive Effluents (continued)

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 2011, is retained onsite.

This data is available for review by the NRC upon request. During 2011, the goal of >90% joint data recovery was met.

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 2011 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 2011 for Unit I was 8.64 Ci, and the total amount of C-14 released in 2011 for Unit 2 was 6.48 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 1.08-01 mrem/yr.

Additionally, a "Child" consuming vegetables from the garden located at 2.0 miles in the WSW direction from the plant would have received a total combined "Bone Dose", including C-14, of 1.08E- 1 mrem/yr.

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 Carbon-14 Dose Estimation (continued)

Using the, same release values, the dose to a visitor on site (Adult Lifeguard) is found to be 2.61E-03 mrem/yr.

All C-14 dose calculations are based on Regulatory Guide 1.109 values.

This is a small fraction of the 1 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.)

2.0 SUPPLEMENTAL INFORMATION 2.1 Abnormal Releases or Abnormal Discharges There were no abnormal releases or discharges from the site during the report period.

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 There was one change to the Land Use Census during 2011. A new garden was identified at 2.0 miles WSW from the plant. This change was noted in the St. Lucie Corrective Action Program under AR 1688791.

2.5 Effluent Monitoring System Inoperability The liquid radioactive waste discharge monitor was declared out of service for greater than 30 days. Although the radiation monitor was functional, the automatic flow isolation valve associated with the radiation monitor was out of service due to a failed valve actuator. A new valve actuator assembly was purchased, installed and the liquid radioactive waste discharge monitor was restored to service.

2.6 Offsite Dose Calculation Manual Changes Two changes were made to the St. Lucie ODCM during the report period.

The first change was to add C-14 dose factors to comply with Revision 2 of Regulatory Guide 1.21. The second change was administrative in nature and revised several procedure reference numbers that had recently changed.

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 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 None 2.9 Other Four batch 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. All four 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 releases are listed below:

Release start date Volume of release August 24 7.98E6 gallons September 9 7.20E6 gallons October 31 3.29E7 gallons December 11 6.18E6 gallons

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 2.10 Groundwater Protection Program Well ID H3 Jan 2011 H3 Feb H3 Mar H3 Apr H3 May H3 June2011 H3 July H3 Aug H3 Sept H3 OCT H3 NOV H3 Dec 2011 2011 2011 2011 2011 2011 2011 2011 2011 2011 e 1,Ui &2, pCi/I pCi/I pCi/I pCi1i pCill pCilI pCi/I pCi/I pCi/I pCi/I PC ill -pCi/I MW-3 386 498 174' 381 MW-4 526 9220 , 841 612- 307 >

MW-5 -- <MDC (215) ________ <MDC (253) _ 255 -7w <MDC (218)

MW-6 1020 817 745 680 700 881 971 1010 1090 1790 829 1090 MW-7 273 <MDC (247) 268k <MDC (226)

MW-15 "..271 <MDC (253) 7 " 310 , <MDC (218)

MW-16 <MDC (249) <MDC (252) MDC (193) 421.

MW-17 446 512 374 270 610 469 416 433 <MDC (26 287 370 MW-18D 1580 1840 2000 1650 1350 1570 1350 1040 785 870 1020 MW-19 304 <MDC (253) <MDC (275) <MDC(224) 77* "

MW-22D 262 <MDC (251) - 234 7 375 MW-26 <MDC (254) <MDC (249) <MDC (190) 460 RW-2 2720 1900 3890 7930 7580 4490 2510 2190 2520 1740 1410 1440 RW-4 <MDC (190) <M DC(256) <MDC (234) -344 RW-5 214 <M DC(260) <MDC (232) -239 MW-30 <MDC(251) <MDC(260) 274- 229 MW-31 401 *; <MDC(243)

- 335 380-33i-*-.._548 611 "-

MW-32 " __ <MDC(250) ____<MC(43 .48. ___._343 MW-33 2640 3010 2840 2670 1950 2500 1800 2050 1280 <MDC(264 670 1350 Well ID H3Jan 2011 H3 Feb H3 Mar H3 Apr H3 May H3 June2011 H3 July H3 Aug H3 Sept H3 OCT H3 NOV H3 Dec 2011 2011 2011 2011 2011 2011 2011 2011 2011 2011 i1WO 1iW'-* pCiI pCi/I pCi/I pCi/I pCil/l pCi/I pCi/I pCp/ pCi/ pCi/I pCill pCi/I Unit I - MWO01 2710 1500 1650 1560 1460 1710 1590 1300 1040 740 296 190 Unit 1 - MWO02 891 578 954 744 583 696 697 596 704 288 512 505 Unit 1 - MW003 ,i41-* 357 1 ,.424 ,4 , i+ 290 q 4:

Unit 1- MWO04 , 360 377 >I-..462 "  ? 970 Unit 1-MWOO5 3110 1120 1620 3910 995 812 2600 3290 1320 2010 1270 1280 Unit 2 - MWO01 6190 5530 5530 4600 1770 3230 5680 6770 2550 2200 296 976 Unit 2 - MW002 1100 793 752 975 503 393 297 177 500 884 526 699 Unit 2 - MW003 856 822 913 626 717 862 962 739 10300 657 907 699 Unit 2- MW004 1780 1360 1660 1930 1620 1730 1380 1770 1380 1180 1560 _ . -I

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31,2011 2.10 Groundwater Protection Program (continued)

H3 Feb H3 Mar H3 Apr H3 May H3 July H3 Aug H3 Sept H3 OCT H3 NOV H3 Dec 2011 2011 2011 2011 2011 2011 2011 2011 2011 2011

=M-JRiJretPme pCi/I pCi/I pCill pC pCi pill pCIpCi pCi/I pCi/I pCill pCi/I pC ill pCi/I (S)-MW-1 <MDC (213)

(S)-MW-4 536 545 361 "_:

(S)-MW-6 394 363 4653 NIDC-22 ' ,,

(S)-MW-7A <MDC (217) -

(s)-MW-11 - ~ 728 481 6810 r"55 (S)-MW-12 (S)-MW-13D (S)-MW-14 (S)-MW-15D 325 277 i268 ...

(S)-MW-16 <MDC(228) <MDC (255) <MDC (189) <MDC (225)

(S)-MW-17 223 ,MD:(217) <M DC(258) 304 277 3

<MDC(217) 223 SS.*-MW-17: <MDC(252)

S)-MW-18  : <MDC(228) <MDC(254) <MDC (188) - <MDC (221)

(S)-MW-19 - <MDC(218) I <MDC(250) I -<MDC(193) I <MDC(225) I

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 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 2011.

VISITOR DOSE RESULTS FOR CALENDAR YEAR 2011 were:

Noble Gas Dose mrad Gamma Air Dose 3.56E-03 Beta Air Dose 3.56E-03 Gas, Particulate, Iodine, Carbon Dose mrem Bone 2.58E-03 Liver 3.80E-03 Thyroid 4.85E-03 Kidney 8.64E-04 Lung 3.75E-03 GI-LLI 3.74E-03 Total Body 4.48E-03

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 L-2012-080 ENCLOSURE 1 COMBINED ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JANUARY 1, 2011 THROUGH DECEMBER 31, 2011 (47 PAGES)

Open EMS Efuerat Muagment Soffimare Page 1 of 2 Friday, February 10, 2012 10:32:06PM Florida Power & Light St. Lucie Power Plant Table 5A and 5B - Regulatory Guide 1.21 (2011)

Batch Release Summary Unit: Site A. Liquid Releases Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Totals

1. Number of batch releases 18 12 20 27 77

2. Total time period for Batch releases (Minutes): 9.85E+03 9.11E+03 4.20E+04 4.13E+04 1.02E+05

3. Maximum time period for a batch release (Minutes): 7.05E+02 1.15E+03 1.98E+04 2.05E+04 2.05E+04

4. Average time period for a batch release (Minutes): 5.47E+02 7.59E+02 2.10E+03 1.53E+03 1.33E+03

5. Minimum time period for a batch release (Minutes): 3.87E+02 4.92E+02 1.OOE+02 5.OOE+02 1.00E+02

6. Average stream flow during periods of release of liquid Effluent into a flowing stream (LPM) 2.07E+06 3.15E+06 3.88E+06 2.09E+06 3.65E+06 Database: [Server]: PSLSA37 [Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 10:32:06PM Page 2 of 2 B. Gaseous Releases Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Totals

1. Number of batch releases . 18 28 38 31 115

2. Total time period for batch releases (Minutes): 9.05E+03 1.06E+04 8.36E+03 5.90E+03 3.39E+04

3. Maximum time period for a batch release ( Minutes): 1.24E+03 1.44E+03 6.00E+02 6.OOE+02 1.44E+03

4. Average time period for a batch release (Minutes): 5.03E+02 3.78E+02 2.20E+02 1.90E+02 2.95E+02

5. Minimum time period for a batch release (Minutes): 2.10E+01 4.80E+01 3.00E+01 3.OOE+01 2.10E+01 END OF BATCH RELEASE

SUMMARY

REPORT User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Page 1 of 1 Op EMS EfuatMuLigemenIt S~oftware Friday, February 10, 2012 10:31:10PM Florida Power & Light St. Lucie Power Plant Table IA - Regulatory Guide ( 2011)

Gaseous Effluents - Summation Of All Releases Unit: Site Type of Effluent Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter o/o Est. Total Error A. Fission And Activation Gases

1. Total Release Curies 1.88E+01 2.01E+01 1.88E+00 7.32E+00

2. Average Release rate for period uCi/sec 2.39E+00 2.54E+00 2.39E-01 9.29E-01

3. Percent of Applicable Limit B. Radiolodines

1. Total Iodine-131 Curies 2.17E-05 9.78E-07 1.14E-05 1.35E-06

2. Average Release rate for period uCi/sec 2.75E-06 1.24E-07 1.45E-06 1.71E-07

3. Percent of Applicable Limit C. Particulates

1. Particulates ( Half-Lives > 8 Days) Curies 8.23E-01 2.21E-05 1.55E-05 8.20E-06

2. Average Release rate for period uCi/sec 1.04E-01 2.80E-06 1.97E-06 1.041E-06

3. Percent of Applicable Limit D. Tritium

1. Total Release Curies

• 4.42E+01 5.41E-01 1.61E-01 5.28E-01

2. Average Release rate for period uCi/sec 5.61E+00 6.86E-02 2.05E-02 6.70E-02

3. Percent of Applicable Limit E. Gross Alpha

1. Total Release Curies 2.50E-07 1.32E-07 2.42E-07 1.77E-07

2. Average Release rate for period uCi/sec

• 3.18E-08 1.68E-08 3.07E-08 2.25E-08

• Applicable limits are expressed in terms of dose.

User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

1Open EMS Efuent Mmuugerment S~oftware Page 1 of 4 Friday, February 10, 2012 10:31:39PM Florida Power & Light St. Lucie Power Plant Table 1C*

Annual Radioactive Effluent Release Report (2011)

Gaseous Effluents - Ground Level Releases Reactor Unit: Site Continuous Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases Kr-85m Curies O.OOE+00 5.12E-02 2.10E-01 0.OOE+00 Kr-87 Curies 1.24E-01 O.OOE+00 0.OOE+00 0.OOE+00 Kr-88 Curies O.OOE+00 7.08E-01 7.23E-01 0.OOE+00 Xe-131m Curies 1.45E+01 1.53E+01 0.00E+00 0.OOE+00 Xe-133m Curies 2.80E+00 1.98E+00 3.95E-01 1.83E+00 Xe-135 Curies 2.82E-02 1.66E-01 0.OOE+00 0.OOE+00 Xe-138 Curies 4.86E-01 1.58E+00 0.OOE+00 2.68E+00 Total For Period Curies 1.79E+01 1.98E+01 1.33E+00 4.51E+00 Iodines 1-131 Curies 2.17E-05 9.78E-07 1.14E-05 1.35E-06 1-133 Curies 0.OOE+00 0.OOE+00 2.07E-04 8.58E-06 Total For Period Curies 2.17E-05 9.78E-07 2.19E-04 9.93E-06 Particulates C-14 Curies 8.23E-01 0.OOE+00 0.OOE+00 0.OOE+00 Cr-51 Curies 0.OOE+00 3.29E-06 0.OOE+00 0.OOE+00 Co-60 Curies 2.70E-05 1.38E-05 1.26E-05 3.13E-06 Cs-137 Curies 9.87E-07 2.64E-06 2.89E-06 5.07E-06 Ce-141 Curies 5.66E-07 0.OOE+00 0.OOE+00 0.OOE+00 Ce-144 Curies 0.OOE+00 2.31E-06 0.OOE+00 0.OOE+00 Total For Period Curies 8.23E-01 2.21E-05 1.55E-05 8.20E-06 Tritium H-3 Curies 4.41E+01 O.OOE+00 O.OOE+00 O.OOE+00 Database: [Server]: PSLSA37 [Database]: NEOEMSP Al Locke User: A[ Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 10:31:39PM Page 2 of 4 Gross Alpha G-Alpha Curies 2.50E-07 1.32E-07 2.42E-07 1.77E-07 Total For Period Curies 2.50E-07 1.32E-07 2.42E-07 1.77E-07 Database: [Server]: PSLSA37 [Database]: NEOEMSP Al Locke User: Al User: Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 10:31:39PM Page 3 of 4 Table 1C*

Annual Radioactive Effluent Release Report (2011)

Gaseous Effluents - Ground Level Releases Reactor Unit: Site Batch Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases Ar-41 Curies 5.54E-01 2.54E-01 4.45E-01 2.60E+00 Kr-85m Curies 2.86E-04 2.61E-05 1.09E-03 1.25E-05 Kr-85 Curies 9.02E-03 1.97E-02 0.OOE+00 0.OOE+00 Kr-87 Curies 0.OOE+00 3.56E-05 1.36E-04 0.OOE+00 Kr-88 Curies 0.OOE+00 0.OOE+00 1.04E-03 9.71E-05 Kr-89 Curies 0.OOE+00 0.OOE+00 0.OOE+00 1.24E-02 Xe-131m Curies 1.07E-03 0.OOE+00 0.OOE+00 0.OOE+00 Xe-133m CuFies 4.86E-03 0.OOE+00 1.15E-03 1.75E-03 Xe-133 Curies 3.17E-01 8.11E-03 8.40E-02 1.88E-01 Xe-135m Curies 0.OOE+00 1.49E-03 3.95E-04 2.08E-04 Xe-135 Curies 2.99E-02 5.47E-05 1.84E-02 1.99E-03 Xe-137 Curies 0.OOE+00 8.32E-03 4.82E-03 2.20E-03 Xe-138 Curies 0.OOE+00 1.09E-04 0.OOE+00 0.OOE+00 Total For Period Curies 9.16E-01 2.91E-01 5.56E-01 2.81E+00 lodines No Nuclides Found N/A N/A N/A N/A Particulates No Nuclides Found N/A N/A N/A N/A Tritium Batch Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter H-3 Curies 1.59E-01 5.41E-01 1.61E-01 5.28E-01 Gross Alpha No Nuclides Found N/A N/A N/A N/A Database: [Server]: PSLSA37 [Database]: NEOEMSP Al Locke User: A[ Database: [Server]: PSLSA37 [Database]: NEOEIVISP

Friday, February 10, 2012 10:31:39PM 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: [Server]: PSLSA37 [Database]: NEOEMSP

OpenEMS Eflent Mm~ugernett Software Page 1 of 1 Friday, February 10, 2012 10:47:52PM Florida Power & Light St. Lucie Power Plant Table IA - Regulatory Guide ( 2011 )

Gaseous Effluents - Summation Of All Releases Unit: PSL1 Type of Effluent Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter  %/oEst. Total Error A. Fission And Activation Gases

1. Total Release Curies 1.06E+01 1.12E+01 5.92E-01 7.14E+00

2. Average Release rate for period uCi/sec 1.35E+00 1.43E+00 7.51E-02 9.05E-01

3. Percent of Applicable Limit B. Radioiodines

1. Total Iodine-131 Curies 1.01E-05 8.51E-07 1. 14E-05 1.35E-06

2. Average Release rate for period uCi/sec 1.28E-06 1.08E-07 1.45E-06 1.71E-07

3. Percent of Applicable Limit C. Particulates

1. Particulates ( Half-Lives > 8 Days) Curies 2.78E-05 1.64E-05 1.17E-05 4.80E-06

2. Average Release rate for period uCi/sec 3.53E-06 2.07E-06 1.49E-06 6.088E-07

3. Percent of Applicable Limit D. Tritium

1. Total Release Curies 2.68E+01 2.36E-01 1.09E-01 4.75E-01

2. Average Release rate for period uCi/sec 3.40E+00 2.99E-02 1.38E-02 6.03E-02

3. Percent of Applicable Limit E. Gross Alpha

1. Total Release Curies 1.44E-07 5.57E-08 1.45E-07 1.23E-07

2. Average Release rate for period uCi/sec 1.83E-08 7.07E-09 1.84E-08 1.56E-08

• Applicable limits are expressed in terms of dose.

User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

p0 P EMIS EzTt Ivbit igLienweln 'ofrware Page 1 of 2 Friday, February 10, 2012 10:49:00PM Florida Power & Light St. Lucie Power Plant Table IC*

Annual Radioactive Effluent Release Report (2011)

Gaseous Effluents - Ground Level Releases Reactor Unit: PSLI Continuous Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases Kr-87 Curies 1.24E-01 O.OOE+00 O.OOE+00 O.OOE+00 Kr-88 Curies O.OOE+00 7.08E-01 O.OOE+00 O.OOE+00 Xe-131m Curies 7.19E+00 7.18E+00 O.OOE+00 O.OOE+00 Xe-133m Curies 2.60E+00 1.60E+00 3.95E-01 1.83E+00 Xe-138 Curies 4.86E-01 1.58E+00 O.OOE+00 2.68E+00 Total For Period Curies 1.04E+01 1.11E+01 3.95E-01 4.51E+00 Iodines 1-131 Curies 1.01E-05 8.51E-07 1. 14E-05 1.35E-06 1-133 Curies O.OOE+00 O.OOE+00 2.07E-04 8.58E-06 Total For Period Curies 1.01E-05 8.51E-07 2.19E-04 9.93E-06 Particulates Cr-51 Curies O.OOE+00 3.29E-06 O.OOE+00 0.OOE+00 Co-60 Curies 2.70E-05 8.79E-06 1.15E-05 2.82E-06 Cs-137 Curies 8.29E-07 2.54E-06 2.64E-07 1.98E-06 Ce-144 Curies O.OOE+00 1.73E-06 O.OOE+00 0.OOE+00 Total For Period Curies 2.78E-05 1.64E-05 1.17E-05 4.80E-06 Tritium H-3 Curies 2.67E+01 0.OOE+00 ----- 0.OOE-i00- O.OOE+00 Gross Alpha G-Alpha Curies 1.44E-07 5.57E-08 1.45E-07 1.23E-07 Total For Period Curies 1.44E-07 5.57E-08 1.45E-07 1.23E-07 Database: [Server]: PSLSA37 [Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 10:49:00PM Page 2 of 2 Table 1C*

Annual Radioactive Effluent Release Report (2011)

Gaseous Effluents - Ground Level Releases Reactor Unit: PSL1 Batch Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases Ar-41 Curies 2.15E-01 1.64E-01 1.69E-01 2.46E+00 Kr-85m Curies 0.OOE+00 0.OOE+00 0.OOE+00 1.25E-05 Xe-133m Curies 0.OOE+00 0.OOE+00 1.60E-04 1.39E-03 Xe-133 Curies 6.72E-03 5.10E-03 2.25E-02 1.63E-01 Xe-135m Curies 0.OOE+00 1.49E-03 3.95E-04 0.OOE+00 Xe-135 Curies 1.67E-04 0.OOE+00 2.45E-04 1.57E-03 Xe-137 Curies 0.OOE+00 8.32E-03 4.82E-03 2.20E-03 Total For Period Curies 2.22E-01 1.79E-01 1.97E-01 2.63E+00 Podines No Nuclides Found - - - - - - - - - - - - - N/A N/A N/A N/A Particulates No Nuclides Found N/A N/A N/A N/A Tritium Batch Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter H-3 Curies 1.59E-01 2.36E-01 1.09E-01 4.75E-01 Gross Alpha No Nuclides Found N/A N/A N/A N/A

• Zeroes in this table indicate that no radioactivity was present at detectable levels.

END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Ar- th 1 A Page 1 of 1 Friday, February 10, 2012 10:50:15PM rJjpeinEMS~y.~

Efflue~nt Mvamiugetrwrt Softm are Florida Power & Light St. Lucie Power Plant Table IA - Regulatory Guide ( 2011 )

Gaseous Effluents - Summation Of All Releases Unit: PSL-2 Type of Effluent Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter  %/aEst. Total Error A. Fission And Activation Gases

1. Total Release Curies 8.21E+00 8.80E+00 1.29E+00 1.84E-01

2. Average Release rate for period uCi/sec 1.04E+00 1.12E+00 1.64E-01 2.33E-02

3. Percent of Applicable Limit B. Radioiodines

1. Total Iodine-131 Curies 1.16E-05 1.27E-07 0.OOE+00 0.OOE+00

2. Average Release rate for period uCi/sec 1.47E-06 1.62E-08 0.OOE+00 0.OOE+00

3. Percent of Applicable Limit C. Particulates

1. Particulates ( Half-Lives > 8 Days) Curies 8.23E-01 5.72E-06 3.80E-06 3.40E-06

2. Average Release rate for period uCi/sec 1.04E-01 7.26E-07 4.82E-07 4.317E-07

3. Percent of Applicable Limit D. Tritium

1. Total Release Curies

• 1.74E+01 3.05E-01 5.24E-02 5.31E-02

2. Average Release rate for period uCi/sec

• 2.21E+00 3.87E-02 6.64E-03 6.74E-03

3. Percent of Applicable Limit E. Gross Alpha

1. Total Release Curies

• 1.06E-07 7.65E-08 9.71E-08 5.40E-08

2. Average Release rate for period uCi/sec

• 1.35E-08 9.70E-09 1.23E-08 6.85E-09

• Applicable limits are expressed interms of dose.

User: AI Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

OýpeiEMS Efuerat IMluugemcia SoffiAure Page 1 of 3 Friday, February 10, 2012 10:50:36PM Florida Power & Light St. Lucie Power Plant Table IC*

Annual Radioactive Effluent Release Report (2011)

Gaseous Effluents - Ground Level Releases Reactor Unit: P51-2 Continuous Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases Kr-85m Curies O.OOE+00 5.12E-02 2.10E-01 O.OOE+00 Kr-88 Curies O.OOE+00 O.OOE+00 7.23E-01 O.OOE+00 Xe-131m Curies 7.29E+00 8.10E+00 0.OOE+00 O.OOE+00 Xe-133m Curies 2.02E-01 3.77E-01 0.OOE+00 O.OOE+00 Xe-135 Curies 2.82E-02 1.66E-01 0.OOE+00 0.OOE+00 Total For Period Curies 7.52E+00 8.69E+00 9.32E-01 O.OOE+O0 lodines 1-131 Curies 1.16E-05 1.27E-07 0.OOE+00 0.OOE+00 Total For Period Curies 1.16E-05 1.27E-07 O.OOE-I-O O.OOE+O0 Particulates C-14 Curies 8.23E-01 O.OOE+00 0.OOE+00 0.OOE+00 Co-60 Curies O.OOE+00 5.06E-06 1.17E-06 3. 1OE-07 Cs-137 Curies 1.58E-07 9.30E-08 2.63E-06 3.09E-06 Ce-141 Curies 5.66E-07 O.OOE+00 0.OOE+00 O.OOE+00 Ce-144 Curies O.OOE+00 5.71E-07 0.OOE+00 O.OOE+00 Total For Period Curies 8.23E-01 5.72E-06 3.80E-06 3.40E-06 Tritium H-3 Curies 1.74E+01 O.OOE+00 O.OOE+00 O.OOE+00 Gross Alpha G-Alpha Curies *1.06E-07 7.65E-08 9.71E-08 5.40E-08 Total For Period Curies 1.06E-07 7.65E-08 9.71E-08 5.40E-08 Database: [Server]: PSLSA37 [Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 10:50:36PM Page 2 of 3 Table 1C*

Annual Radioactive Effluent Release Report (2011)

Gaseous Effluents - Ground Level Releases Reactor Unit: PSL2 Batch Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases Ar-41 Curies 3.39E-01 8.99E-02 2.76E-01 1.45E-01 Kr-85m Curies 2.86E-04 2.61E-05 1.09E-03 0.OOE+00 Kr-85 Curies 9.02E-03 1.97E-02 0.OOE+00 0.OOE+00 Kr-87 Curies 0.OOE+00 3.56E-05 1.36E-04 0.OOE+00 Kr-88 Curies 0.OOE+00 O.OOE+00 1.04E-03 9.71E-05 Kr-89 Curies 0.OOE+00 O.OOE+00 0.OOE+00 1.24E-02 Xe-131m Curies 1.07E-03 O.OOE+00 0.OOE+00 0.OOE+00 Xe-133m Curies 4.86E-03 O.OOE+00 9.87E-04 3.54E-04 Xe-133 Curies 3.10E-01 3.01E-03 6.15E-02 2.48E-02 Xe-135m Curies 0.00E+00 O.OOE+00 0.OOE+00 2.08E-04 Xe-135 Curies 2.98E-02 5.47E-05 1.81E-02 4.22E-04 Xe-138 Curies 0.OOE+00 1.09E-04 0.OOE+00 0.00E+00 Total For Period Curies 6.94E-01 1.13E-01 3.59E-01 1.84E-01 Iodines No Nuclides Found N/A N/A N/A N/A Particulates No Nuclides Found N/A N/A N/A N/A Tritium Batch Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter H-3 Curies 0.OOE+00 3.05E-01 5.24E-02 5.31E-02 Gross Alpha No Nuclides Found N/A N/A N/A N/A Database: [Server]: PSLSA37 [Database]: NEOEMSP User: Al Locke User: Database: [Server]: PSLSA37 [Database]: NEOEIVISP

Friday, February 10, 2012 10:50:36PM Page 3 of 3

• Zeroes in this table indicate that no radioactivity was present at detectable levels.

END OF ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

ip iEMVS lieMx.e=nt Software Page Iofi1 2012 10:51:44PM Friday, February 10, odaPower ih Florida Power & Light St. Lucie Power Plant Friday, February 10, 2012 10:51:44PM Page 1 of 1 Table 2A - Regulatory Guide 1.21 (2011)

Liquid Effluents - Summation Of All Releases Unit: Site Type of Effluent Uinits 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter  %/oEst. Total Error A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Ciuries 1.43E-02 2.82E-02 4.13E-02 9.02E-02

2. Average diluted concentration during period u Ci/ml 7.02E-10 9.83E-10 2.53E-10 1.04E-09

• k

3. Percent of Applicable Limit  %

B. Tritium

1. Total Release Curies 6.06E+01 4.22E+01 1.09E+02 6.57E+01

2. Average diluted Concentration during period u(Ci/ml 2.97E-06 1.47E-06 6.67E-07 7.61E-07

3. Percent of Applicable Limit OX C. Dissolved and Entrained Gases

1. Total Release Curies 9.04E-03 7.86E-05 7.68E-03 3.32E-02

2. Average diluted Concentration during period uCi/ml 4.44E-10 2.75E-12 4.71E-11 3.85E-10

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

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

Liters 1.43E+06 1.04E+06 5.88E+07 1.50E+08 F. Volume of Dilution Water Used Liters 2.04E+10 2.86E+10 1.63E+11 8.64E+10

• Applicable limits are expressed in terms of dose.

User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

.Page 1 of 4 Op pE1 M~ S Friday, February 10, 2012 Power Florida 10:52:01PM

& Light St. Lucie Power Plant Table 2B - Regulatory Guide 1.21 (2011)

Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: Site 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 N/A N/A N/A N/A Dissolved And Entrained Gases No Nuclides Found N/A N/A N/A N/A If Not Detected, Nuclide is Not Reported Database: [Server]: PSLSA37 [Database]: NEOEMSP Locke User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 10:52:01PM Page 2 of 4 Table 2B - Regulatory Guide 1.21 (2011)

Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: Site Batch Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP User: Al Locke User: Al Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 10:52:01PM Page 3 of 4 Fission & Activation Products Sb-125 Curies 5.OOE-04 5.18E-04 5.71E-04 9.14E-04 Cs-137 Curies 0.OOE+00 4.91E-06 1.14E-05 1.47E-05 1-130 Curies 0.OOE+00 2.84E-06 0.OOE+00 0.OOE+00 C-14 Curies 4.23E-03 5.07E-03 2.80E-02 7.02E-02 Ba-140 Curies 0.OOE+00 9.06E-06 0.OOE+00 1.90E-05 Cs-136 Curies 5.19E-06 5.10E-06 6.72E-06 0.OOE+00 Ag-110m Curies 5.99E-04 3.47E-04 5.37E-04 9.50E-04 Fe-59 Curies 9.50E-05 2.98E-04 9.01E-05 8. lE-05 Mn-54 Curies 1.04E-04 8.76E-05 2.17E-04 2.52E-04 Zr-97 Curies 1.78E-04 0.OOE+00 1.63E-04 3.25E-04 Br-82 Curies 5.05E-06 4.38E-06 0.OOE+00 0.OOE+00 1-135 Curies 1.37E-05 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 Curies 4.97E-03 1.48E-03 1.93E-03 3.71E-03 La-140 Curies 0.OOE+00 0.OOE+00 9.91E-05 3.38E-05 Ru-103 Curies 0.OOE+00 3.78E-06 0.OOE+00 0.OOE+00 Zn-65 Curies 5.45E-06 4.54E-06 0.OOE+00 2.37E-05 Nb-97 Curies 8.43E-05 1.68E-04 6.46E-04 1.64E-03 Co-57 Curies 0.OOE+00 6.24E-06 8.13E-06 2.64E-06 Co-60 Curies 7.16E-04 4.47E-04 1.66E-03 2.48E-03 Sb-124 Curies 5.73E-06 7.18E-06 0.OOE+00 0.OOE+00 Cs-138 Curies 9.67E-06 0.OOE+00 8.68E-06 2.71E-05 Cr-51 Curies 4.38E-04 5.22E-04 1.48E-04 3.12E-04 Rb-88 Curies 0.OOE+00 0.OOE+00 0.OOE+00 2.84E-04 Te-129 Curies 5.24E-05 0.OOE+00 0.OOE+00 0.OOE+00 Ni-63 Curies 0.OOE+00 0.OOE+00 4.67E-04 8.90E-04 Sb-122 Curies 0.OOE+00 0.OOE+00 0.OOE+00 5.76E-06 Sr-91 Curies 7.01E-06 1.76E-05 0.OOE+00 0.OOE+00 Nb-95 Curies 6.96E-05 1.96E-04 2.77E-04 2.30E-04 Fe-55 Curies 2.13E-03 1.87E-02 6.24E-03 7.49E-03 1-131 Curies 5.28E-06 0.OOE+00 0.OOE+00 0.00E+00 Zr-95 Curies 8.16E-05 1.48E-04 1.37E-04 5.49E-05 Te-129m Curies 0.OOE+00 1.04E-04 9.70E-05 2.69E-04 Sn-113 Curies 5.89E-06 2.01E-05 0.OOE+00 9.67E-06 Total For Period Curies 1.43E-02 2.82E-02 4.13E-02 9.02E-02 Tritium H-3 Curies 6.06E+01 4.22E+01 1.09E+02 6.57E+01 User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 10:52:01PM Page 4 of 4 Dissolved And Entrained Gases Xe-133 Curies 8.96E-03 7.86E-05 7.63E-03 2.07E-02 Kr-88 Curies 0.OOE+00 0.OOE+00 0.OOE+00 9.09E-05 Kr-87 Curies 0.OOE+00 0.OOE+00 O.OOE+00 8.13E-06 Xe-133m Curies 7.44E-05 0.00E+00 2.72E-05 1.47E-04 Xe-135 Curies 3.43E-06 0.OOE+00 1.39E-05 1.33E-03 Ar-41 Curies 0.OOE+00 0.OOE+00 4.05E-06 1.09E-02 Kr-85m Curies 0.OOE+00 0.OOE+00 0.OOE+00 6.05E-05 Total For Period Curies 9.04E-03 7.86E-05 7.68E-03 3.32E-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 Database: [Server]: PSLSA37 [Database]: NEOEMSP Al Locke User: Al Database: [Server]: PSLSA37 [Database]: NEOEMSP

Page 1 of 1 0 Pent EMS Effluet uugenwtit Softwa~re Friday, February 10, 2012 10:53:21PM Florida Power & Light St. Lucie Power Plant Friday, February 10, 2012 10:53:21PM Page 1 of 1 Table 2A - Regulatory Guide 1.21 (2011)

Liquid Effluents - Summation Of All Releases Unit: PSL1 Type of Effluent Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 0/6 Est. Total Error A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 7.15E-03 1.41E-02 2.06E-02 4.51E-02

2. Average diluted concentration during period u Ci/ml 7.02E-10 9.83E-10 2.53E-10 1.04E-09

3. Percent of Applicable Limit 0/

B. Tritium

1. Total Release Curies 3.03E+01 2.11E+01 5.44E+01 3.29E+01

2. Average diluted Concentration during period u Ci/ml 2.97E-06 1.47E-06 6.67E-07 7.61E-07

3. Percent of Applicable Limit 0/

C. Dissolved and Entrained Gases

1. Total Release Curies 4.52E-03 3.93E-05 3.84E-03 1.66E-02

2. Average diluted Concentration during period uCi/ml 4.44E-10 2.75E-12 4.71E-11 3.85E-10

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

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

Liters 7.14E+05 5.19E+05 2.94E+07 7.51E+07 F. Volume of Dilution Water Used Liters 1.02E+10 1.43E+10 8.16E+10 4.32E+10

• Applicable limits are expressed in terms of dose.

User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

o-,penEMS Eflent M~uugemei t Sofmu~re Page 1 of 4 Friday, February 10, 2012 10:53:44PM Florida Power & Light St. Lucie Power Plant Table 2B - Regulatory Guide 1.21 (2011)

Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: PSLI 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 N/A N/A N/A N/A Dissolved And Entrained Gases No Nuclides Found N/A N/A N/A N/A If Not Detected, Nuclide is Not Reported Database: [Server]: PSLSA37 [Database]: NEOEMSP User: Al Locke Al Locke Database: [Server): PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 10:53:44PM Page 2 of 4 Table 2B - Regulatory Guide 1.21 (2011)

Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: PSL1 Batch Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Database: [Server]: PSLSA37 [Database]: NEOEMSP User: Al Locke Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 10:53:44PM Page 3 of 4 Fission & Activation Products Cs-138 Curies 4.83E-06 0.OOE+00 4.34E-06 1.36E-05 Ba-140 Curies 0.OOE+00 4.53E-06 0.OOE+00 9.52E-06 Te-129m Curies 0.OOE+00 5.22E-05 4.85E-05 1.34E-04 1-135 Curies 6.86E-06 0.OOE+00 0.00E+00 0.OOE+00 Fe-59 Curies 4.75E-05 1.49E-04 4.50E-05 4.05E-05 Sb-125 Curies 2.50E-04 2.59E-04 2.86E-04 4.57E-04 Sr-91 Curies 3.51E-06 8.81E-06 0.OOE+00 0.OOE+00 Co-60 Curies 3.58E-04 2.24E-04 8.32E-04 1.24E-03 Nb-95 Curies 3.48E-05 9.82E-05 1.38E-04 1. 15E-04 Zr-95 Curies 4.08E-05 7.40E-05 6.85E-05 2.74E-05 Co-57 Curies 0.00E+00 3.12E-06 4.07E-06 1.32E-06 Nb-97 Curies 4.22E-05 8.42E-05 3.23E-04 8.22E-04 Ag-110m Curies 2.99E-04 1.74E-04 2.68E-04 4.75E-04 Cs-137 Curies 0.00E+00 2.46E-06 5.71E-06 7.37E-06 Cs-136 Curies 2.59E-06 2.55E-06 3.36E-06 0.OOE+00 Zr-97 Curies 8.90E-05 0.OOE+00 8.17E-05 1.62E-04 Te-129 Curies 2.62E-05 0.OOE+00 0.OOE+00 0.OOE+00 Cr-51 Curies 2.19E-04 2.61E-04 7.42E-05 1.56E-04 La-140 Curies 0.OOE+00 0.00E+00 4.96E-05 1.69E-05 Sb-122 Curies 0.OOE+00 0.OOE+00 0.OOE+00 2.88E-06 C-14 Curies 2.11E-03 2.53E-03 1.40E-02 3.51E-02 Zn-65 Curies 2.73E-06 2.27E-06 0.OOE+00 1.18E-05 Fe-55 Curies 1.06E-03 9.35E-03 3.12E-03 3.75E-03 1-130 Curies 0.OOE+00 1.42E-06 0.00E+00 0.OOE+00 Mn-54 Curies 5.20E-05 4.38E-05 1.09E-04 1.26E-04 Co-58 Curies 2.48E-03 7.40E-04 9.66E-04 1.85E-03 Sn-113 Curies 2.95E-06 1.OOE-05 0.OOE+00 4.83E-06 Rb-88 Curies 0.OOE+00 0.OOE+00 0.OOE+00 1.42E-04 Sb-124 Curies 2.87E-06 3.59E-06 0.OOE+00 0.OOE+00 Ru-103 Curies 0.OOE+00 1.89E-06 0.OOE+00 0.OOE+00 Br-82 Curies 2.53E-06 2.19E-06 0.OOE+00 0.OOE+00 Ni-63 Curies 0.OOE+00 0.OOE+00 2.33E-04 4.45E-04 1-131 Curies 2.64E-06 0.OOE+00 0.OOE+00 0.OOE+00 Total For Period Curies 7.15E-03 1.41E-02 2.06E-02 4.51E-02 Tritium H-3 Curies 3.03E+01 2.11E+01 5.44E+01 3.29E+01 User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 10:53:44PM Page 4 of 4 Dissolved And Entrained Gases Kr-88 Curies 0.OOE+00 0.00E+00 0.OOE+00 4.55E-05 Xe-135 Curies 1.71E-06 0.OOE+00 6.97E-06 6.63E-04 Kr-87 Curies O.OOE+00 0.OOE+00 0.OOE+00 4.06E-06 Xe-133 Curies 4.48E-03 3.93E-05 3.82E-03 1.03E-02 Kr-85m Curies 0.OOE+00 0.OOE+00 0.OOE+00 3.03E-05 Ar-41 Curies 0.OOE+00 0.OOE+00 2.03E-06 5.46E-03 Xe-133m Curies 3.72E-05 0.OOE+00 1.36E-05 7.33E-05 Total For Period Curies 4.52E-03 3.93E-05 3.84E-03 1.66E-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 Database: [Server]: PSLSA37 [Database]: NEOEMSP User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Page 1 of 1 OpeiaiEMS Efuent Mnaigemient Software Friday, February 10, 2012 11:02:57PM Florida Power & Light St. Lucie Power Plant Friday, February 10, 2012 11:02:57PM Page 1 of 1 Table 2A - Regulatory Guide 1.21 (2011)

Liquid Effluents - Summation Of All Releases Unit: PSL2 Type of Effluent Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter  %/oEst. Total Error A. Fission And Activation Products

1. Total Release (not including tritium, gases, alpha) Curies 7.15E-03 1.41E-02 2.06E-02 4.51E-02

2. Average diluted concentration during period u Ci/ml 7.02E-10 9.83E-10 2.53E-10 1.04E-09

3. Percent of Applicable Limit OX B. Tritium

1. Total Release Curies 3.03E+01 2.11E+01 5.44E+01 3.29E+01

2. Average diluted Concentration during period u Ci/ml 2.97E-06 1.47E-06 6.67E-07 7.61E-07

3. Percent of Applicable Limit °/

C. Dissolved and Entrained Gases

1. Total Release Curies 4.52E-03 3.93E-05 3.84E-03 1.66E-02

2. Average diluted Concentration during period uCi/ml 4.44E-10 2.75E-12 4.71E-11 3.85E-10

3. Percent of Applicable Limit D: Gross Alpha Radioactivity

1. Total Release 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 E: Waste Vol Release (Pre-Dilution)

Liters 7.14E+05 5.19E+05 2.94E+07 7.51E+07 F. Volume of Dilution Water Used Liters 1.02E+10 1.43E+10 8.16E+10 4.32E+10

• Applicable limits are expressed in terms of dose.

User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Page 1 of 4 QOCTIEMS .1 Effluent Mmuugement Softwire Friday, February 10, 2012 11:03:10PM Florida Power & Light St. Lucie Power Plant Table 2B - Regulatory Guide 1.21 (2011)

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 N/A N/A N/A N/A Dissolved And Entrained Gases No Nuclides Found N/A N/A N/A N/A If Not Detected, Nuclide is Not Reported Database: [Server]: PSLSA37 [Database]: NEOEMSP User: Al Locke Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 11:03:10PM Page 2 of 4 Table 2B - Regulatory Guide 1.21 (2011)

Annual Radioactive Effluent Release Report Liquid Effluents Reactor Unit: PSL2 Batch Mode Nuclides Released Unit 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Database: [Server]: PSLSA37 [Database]: NEOEMSP User: AI Locke Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 11:03:10PM Page 3 of 4 Fission & Activation Products Ba-140 Curies 0.OOE+00 4.53E-06 0.00E+00 9.52E-06 Nb-95 Curies 3.48E-05 9.82E-05 1.38E-04 1.15E-04 Sr-91 Curies 3.51E-06 8.81E-06 0.OOE+00 0.00E+00 Br-82 Curies 2.53E-06 2.19E-06 0.OOE+00 0.OOE+00 Ru-103 Curies 0.OOE+00 1.89E-06 0.OOE+00 0.OOE+00 Cs-136 Curies 2.59E-06 2.55E-06 3.36E-06 0.OOE+00 Sb-122 Curies 0.OOE+00 0.00E+00 0.OOE+00 2.88E-06 Cr-51 Curies 2.19E-04 2.61E-04 7.42E-05 1.56E-04 Sb-125 Curies 2.50E-04 2.59E-04 2.86E-04 4.57E-04 Te-129m Curies 0.00E+00 5.22E-05 4.85E-05 1.34E-04 Fe-55 Curies 1.06E-03 9.35E-03 3.12E-03 3.75E-03 La-140 Curies 0.OOE+00 0.00E+00 4.96E-05 1.69E-05 Fe-59 Curies 4.75E-05 1.49E-04 4.50E-05 4.05E-05 Co-60 Curies 3.58E-04 2.24E-04 8.32E-04 1.24E-03 Ni-63 Curies O.OOE+00 0.O0E+00 2.33E-04 4.45E-04 Cs-137 Curies 0.OOE+00 2.46E-06 5.71E-06 7.37E-06 Zn-65 Curies 2.73E-06 2.27E-06 0.OOE+00 1.18E-05 Te-129 Curies 2.62E-05 0.OOE+00 0.OOE+00 0.OOE+00 1-135 Curies 6.86E-06 0.OOE+00 0.OOE+00 0.OOE+00 1-131 Curies 2.64E-06 0.OOE+00 0.OOE+00 0.OOE+00 Sn-113 Curies 2.95E-06 1.OOE-05 0.OOE+00 4.83E-06 Mn-54 Curies 5.20E-05 4.38E-05 1.09E-04 1.26E-04 Rb-88 Curies 0.OOE+00 0.OOE+00 0.OOE+00 1.42E-04 Nb-97 Curies 4.22E-05 8.42E-05 3.23E-04 8.22E-04 Zr-95 Curies 4.08E-05 7.40E-05 6.85E-05 2.74E-05 1-130 Curies 0.OOE+00 1.42E-06 0.OOE+00 0.OOE+00 Co-58 Curies 2.48E-03 7.40E-04 9.66E-04 1.85E-03 Ag-110m Curies 2.99E-04 1.74E-04 2.68E-04 4.75E-04 Cs-138 Curies 4.83E-06 0.OOE+00 4.34E-06 1.36E-05 Zr-97 Curies 8.90E-05 0.00E+00 8.17E-05 1.62E-04 C-14 Curies 2.11E-03 2.53E-03 1.40E-02 3.51E-02 Co-57 Curies 0.OOE+00 3.12E-06 4.07E-06 1.32E-06 Sb-124 Curies 2.87E-06 3.59E-06 0.OOE+00 0.OOE+00 Total For Period Curies 7.15E-03 1.41E-02 2.06E-02 4.51E-02 Tritium H-3 Curies 3.03E+01 2.11E+01 5.44E+01 3.29E+01 User: Al Locke Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 11:03:10PM Page 4 of 4 Dissolved And Entrained Gases Xe-133 Curies 4.48E-03 3.93E-05 3.82E-03 1.03E-02 Kr-85m Curies O.OOE+00 O.OOE+00 O.OOE+00 3.03E-05 Xe-133m Curies 3.72E-05 O.OOE+00 1.36E-05 7.33E-05 Xe-135 Curies 1.71E-06 O.OOE+00 6.97E-06 6.63E-04 Ar-41 Curies O.OOE+00 O.OOE+00 2.03E-06 5.46E-03 Kr-87 Curies O.OOE+00 O.OOE+00 O.OOE+00 4.06E-06 Kr-88 Curies O.OOE+00 O.OOE+00 O.OOE+00 4.55E-05 Total For Period Curies 4.52E-03 3.93E-05 3.84E-03 1.66E-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 Database: [Server]: PSLSA37 [Database]: NEOEMSP Al Locke User: A[ Database: [Server]: PSLSA37 [Database]: NEOEMSP

Friday, February 10, 2012 11:14:59PM Florida Power & Light 0 uL1,.,'nEMtS~fw St. Lucie Power Plant Table A-2B, Liquid Effluents - Continuous Mode Unit: Site Starting: 1-Jan-2011 Ending: 31-Dec-2011 Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Total A. Particulates and Iodines No Nuclides Found Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 B. Dissolved and Entrained Gase No Nuclides Found Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 C. Tritium No Nuclides Found Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 D. Gross Alpha Activity No Nuclides Found Ci 0.OOE+00 0.OOE+00 0.OOE+00 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: [Server]: PSLSA37 [Database]: NEOEMSP

Opep EMS Efuent Mm.ug-emcnt Software Page 1 of 2 Friday, February 10, 2012 11:06:11PM Florida Power & Light St. Lucie Power Plant Table 6A and 6B - Regulatory Guide 1.21 Annual Liquid Effluents - Abnormal Release Summary No Data Found for Selected Search Criteria

[Server]: PSLSA37 [Database]: NEOEMSP User: Al Locke [Server]: PSLSA37 [Database]: NEOEMSP

NRC Regulatory Guide 1.21 Reports Page 1 Report Date : 2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Percent Cutoff: 1 Waste Stream : Resins, Filters, and Evap Bottoms Waste Volume Curies  % Error Class FtA3 MA3 Shipped (Ci)

A 3.39E+02 9.60E+00 2.12E+01 +/-25%

B 2.67E+02 7.56E+00 8.65E+01 +/- 25%

C 0.OOE+00 0.OOE+00 0.OOE+00 +/- 25%

All 6.06E+02 1.72E+01 1.08E+02 +/-25%

Waste Stream : DryActive Waste DAW 20' Sealand DAW 40' Sealand DAW 8-120 Liner Waste Volume Curies %Error Class FtA3 MA3 Shipped (Ci)

A 4.07E+04 1.15E+03 1.61E+01 +/-25%

B 0.OOE+00 0.00E+00 0.OOE+00 +/-25%

C 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%

All 4.07E+04 1.15E+03 1.61E+01 +/-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 0.00E+00 +/-25%

All 0.00E+00 0.OOE+00 0.OOE+00 +/-25%

NRC Regulatory Guide 1.21 Reports Page 2 Report Date : 2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Percent Cutoff: 1 Waste Stream : Other Waste Combined Packages Oil 07-01 Waste Volume Curies  % Error Class FtA3 MA3 Shipped (Ci)

A 5.49E+03 1.55E+02 2.27E+00 +/-25%

B 0.OOE+00 0.OOE+00 0.00E+00 +/-25%

C 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%

All 5.49E+03 1.55E+02 2.27E+00 +/-25%

Waste Stream : Sum of All 4 Categories Combined Packages DAW 20' Sealand DAW 40' Sealand Oil 07-01 DAW 8-120 Liner Waste Volume Curies  % Error Class FtA3 MA3 Shipped (Ci)

A 4.66E+04 1.32E+03 3.96E+01 +/-25%

B 2.67E+02 7.56E+00 8.65E+01 +/-25%

C 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%

All 4.68E+04 1.33E+03 1.26E+02 +/-25%

-Combined Waste Type Shipment, Major Volume Waste Type Shown

NRC Regulatory Guide 1.21 Reports Page 1 Report Date : 2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Number of Shipments Mode of Transportation Destination 25 Hittman Transport (TN) EnergySolutions Bear Creek 4 Hittman Transport (SC) EnergySolutions LLC.

1 Hittman Transport (TN) EnergySolutions LLC.

2 Hittman Transport (SC) Studsvik Processing Facility LLC -

Erwin

NRC Regulatory Guide 1.21 Reports Page 1 Report Date : 2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Percent Cutoff: 1 Resins, Filters, and Evap Bottom Waste Class A Nuclide Name Percent Abundance Curies H-3 4.109% 8.72E-01 C-14 4.000% 8.49E-01 Cr-51 1.404% 2.98E-01 Mn-54 1.690% 3.59E-01 Fe-55 17.859% 3.79E+00 Co-58 39.157% 8.31 E+00 Co-60 9.829% 2.09E+00 Ni-63 16.492% 3.50E+00 Sb-125 2.563% 5.44E-01 Resins, Filters, and Evap Bottom Waste Class B Nuclide Name Percent Abundance Curies H-3 2.646% 2.29E+00 Mn-54 4.836% 4.18E+00 Fe-55 14.337% 1.24E+01 Co-58 6.813% 5.89E+00 Co-60 11.586% 1.OOE+01 Ni-63 43.009% 3.72E+01 Cs-137 13.299% 1.15E+01 Resins, Filters, and Evap Bottom Waste Class All Nuclide Name Percent Abundance Curies H-3 2.934% 3.16E+00 C-14 1.423% 1.53E+00 Mn-54 4.216% 4.54E+00 Fe-55 15.031% 1.62E+01 Co-58 13.186% 1.42E+01 Co-60 11.240% 1.21E+01 Ni-63 37.785% 4.07E+01 Cs-137 10.748% 1.16E+01 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 1.614% 2.60E-01 Cr-51 2.338% 3.77E-01 Mn-54 1.617% 2.61 E-01 Fe-55 35.046% 5.66E+00 Co-58 19.183% 3.1OE+00 Co-60 10.756% 1.74E+00 Ni-63 12.754% 2.06E+00 Zr-95 2.101% 3.39E-01 Nb-95 3.568% 5.76E-01 Sn-113 1.176% 1.90E-01 Sb-125 1.434% 2.31E-01

NRC Regulatory Guide 1.21 Reports Page 2 Report Date: 2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Percent Cutoff: 1 Cs-137 2.845% 4.59E-01 Ce-144 3.789% 6.11E-01 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 1.614% 2.60E-01 Cr-51. 2.338% 3.77E-01 Mn-54 1.617% 2.61E-01 Fe-55 35.046% 5.66E+00 Co-58 19.183% 3.1OE+00 Co-60 10.756% 1.74E+00 Ni-63 12.754% 2.06E+00 Zr-95 2.101% 3.39E-01 Nb-95 3.568% 5.76E-01 Sn-113 1.176% 1.90E-01 Sb-125 1.434% 2.31E-01 Cs-1 37 2.845% 4.59E-01 Ce-144 3.789% 6.11E-01 Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 16.734% 3.80E-01 C-14 9.782% 2.22E-01 Fe-55 27.002% 6.13E-01 Co-58 9.417% 2.14E-01 Co-60 6.348% 1.44E-01 Ni-63 23.105% 5.25E-01 Ag-110m 1.055% 2.40E-02 Sb-125 2.639% 5.99E-02 Cs-137 1.480% 3.36E-02 Other Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 16.734% 3.80E-01 C-14 9.782% 2.22E-01 Fe-55 27.002% 6.13E-01 Co-58 9.417% 2.14E-01 Co-60 6.348% 1.44E-01 Ni-63 23.105% 5.25E-01 Ag-110m 1.055% 2.40E-02 Sb-125 2.639% 5.99E-02 Cs-137 1.480% 3.36E-02 Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 3.816% 1.51 E+00 C-14 2.703% 1.07E+00

NRC Regulatory Guide 1.21 Reports Page 3 Report Date : 2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Percent Cutoff: 1 Cr-51 1.704% 6.75E-01 Mn-54 1.598% 6.33E-01 Fe-55 25.381% 1.01E+01 Co-58 29.320% 1.16E+01 Co-60 10.007% 3.97E+00 Ni-63 15.349% 6.08E+00 Nb-95 1.774% 7.03E-01 Sb-125 2.108% 8.35E-01 Cs-137 1.431% 5.67E-01 Ce-144 1.699% 6.73E-01 Sum of All 4 Categories Waste Class B Nuclide Name Percent Abundance Curies H-3 2.646% 2.29E+00 Mn-54 4.836% 4.18E+00 Fe-55 14.337% 1.24E+01 Co-58 6.813% 5.89E+00 Co-60 11.586% 1.00E+01 Ni-63 43.009% 3.72E+01 Cs-137 13.299% 1.15E+01 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies H-3 3.013% 3.80E+00 C-14 1.391% 1.75E+00 Mn-54 3.819% 4.82E+00 Fe-55 17.807% 2.25E+01 Co-58 13.886% 1.75E+01 Co-60 11.090% 1.40E+01 Ni-63 34.318% 4.33E+01 Cs-137 9.570% 1.21 E+01

NRC Regulatory Guide 1.21 Reports Page 1 Report Date : 2/17/2012 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2011 to 12/31/2011 Manifest Number Date Shipped Waste Volume Used Burial volume Used FPL/PSL 11-147 12/8/2011 Yes FPL/PSL 11-146 11/9/2011 Yes FPL/PSL 11-138 10/20/2011 Yes FPL/PSL 11-124 7/27/2011 Yes FPL/PSL 11-123 7/22/2011 Yes FPL/PSL 11-122 7/19/2011 Yes FPL/PSL 11-119 6/30/2011 Yes FPL/PSL 11-116 6/22/2011 Yes FPL/PSL 11-115 6/17/2011 Yes FPL/PSL 11-114 6/16/2011 Yes FPL/PSL11-113 6/9/2011 Yes FPL/PSL 11-111 6/6/2011 Yes FPL/PSL 11-110 6/2/2011 Yes FPL/PSL 11-109 6/1/2011 Yes FPL/PSL 11-106 5/26/2011 Yes FPL/PSL 11-105 5/26/2011 Yes FPL/PSL 11-102 5/12/2011 Yes FPL/PSL 11-101 5/11/2011 Yes FPL/PSL 11-100 5/10/2011 Yes FPL/PSL 11-85 4/7/2011 Yes FPL/PSL 11-68 3/17/2011 Yes FPL/PSL 11-61 3/3/2011 Yes FPL/PSL 11-54 2/23/2011 Yes FPL/PSL 11-55 2/22/2011 Yes FPL/PSL 11-48 2/15/2011 Yes FPL/PSL 11-40 2/14/2011 Yes FPL/PSL 11-26 2/7/2011 Yes FPL/PSL 11-25 1/27/2011 Yes FPL/PSL 11-22 1/24/2011 Yes PSL/FPL-11-13 1/19/2011 Yes FPL/PSL 11-6 1/7/2011 Yes FPL/PSL-11-163 1/5/2011 Yes

Gas Status Summary Report Tuesday, February 14, 2012 04:26 Page 12 of 13 Period: Ann, 2011 Site/Unit/Discharge Point: Site 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 1.573E-05 1.573E-05 1.573E-05 1.573E-05 1.573E-05 1.573E-05 1.573E-05 0.OOOE+00 NW Site Boundary - In Infant 6.510E-03 9.302E-03 9.170E-03 1.164E-02 2.042E-03 9.178E-03 9.159E-03 0.OOOE+00 Maximum Doserate by Organ: 6.510E-03 9.302E-03 9.170E-03 1.164E-02 2.042E-03 9.178E-03 9.159E-03 O.O00E+00 Maximum Organ Doserate (mRem/yr): 1. 164E-02 Maximum Total Body Doserate (mRem/yr): 9.170E-03 Site Boundary NG Doserate Summary Gas Receptor Location Gamma (mRad/yr) Beta (mRad/yr) Total Body (mRem/yr) Skin (mRem/yr)

WNW Site Boundary 1.103E-03 1.103E-03 1.034E-03 1.784E-03 NW Site Boundary 1.280E-03 1.280E-03 1.200E-03 2.071E-03 User: A[ Locke [Server]: PSLSA37 [Database]: NEOEMSP

Gas Status Summary Report Tuesday, February 14, 2012 04:26 Page 13 of 13 Period: Ann, 2011 Site/Unit/Discharge Point: Site Maximum Individual NNG Dose Summary - Note: All Doses in mRem Receptor Agegroup Bone Liver Total Body Thyroid Kidney Lung GI-Ili Skin SE Nearest Res - Adult Adult 1.170E-04 1.170E-04 1.168E-04 1.365E-04 1.169E-04 1.234E-04 1.171E-04 0.OOOE+O0 SE Nearest Res - Child Child 1.170E-04 1.170E-04 1.168E-04 1.474E-04 1.168E-04 1.246E-04 1.168E-04 0.OOOE+00 SE Nearest Res - Infant Infant 1.169E-04 1.170E-04 1.167E-04 1.450E-04 1.167E-04 1.232E-04 1.167E-04 0.OOOE+00 SE Nearest Res - Teenager Teenager 1.169E-04 1.170E-04 1.168E-04 1.415E-04 1.169E-04 1.264E-04 1.170E-04 0.OOOE+00 SE Visitor - Adult Adult 5.432E705 5.431E-05 5.425E-05 6.285E-05 5.429E-05 5.713E-05 5.435E-05 0.OOOE+00 SSW Near Garden - Adult Adult 9.060E-06 9.059E-06 9.049E-06 1.040E-05 9.054E-06 9.501E-06 9.065E-06 0.OOOE+00 SSW Near Garden - Child Child 9.060E-06 9.059E-06 9.045E-06 1.115E-05 9.046E-06 9.583E-06 9.048E-06 0.OOOE+00 SSW Near Garden Teenager 9.054E-06 9.059E-06 9.046E-06 1.074E-05 9.054E-06 9.708E-06 9.062E-06 0.OOOE+00 WSW Near Milk - Adult Adult 2.515E-05 2.672E-05 2.468E-05 1.211E-04 2.331E-05 2.233E-05 2.117E-05 0.OOOE+00 WSW Near Milk - Child Child 3.851E-05 3.801E-05 2.399E-05 3.194E-04 2.346E-05 2.375E-05 2.114E-05 0.OOOE+00 WSW Near Milk - Infant Infant 5.770E-05 6.227E-05 2.443E-05 7.350E-04 2.345E-05 2.640E-05 2.114E-05 0.OOOE+0Q WSW Near Milk - Teenager Teenager 7.474E-06 1.013E-05 3.775E-06 1.524E-04 3.175E-06 2.450E-06 9.531E-07 0.OOOE+00 Maximum Dose by Organ: 1.170E-04 1.170E-04 1.168E-04 7.350E-04 1.169E-04 1.264E-04 1.171E-04 0.OOOE+00 Maximum Organ Dose (mRem): 7.35C)E-04 Maximum Total Body Dose (mRem): 1.1683E-04 Maximum Individual NG Dose Summary Gas Receptor Location Gamma (mRad) Beta (mRad) Total Body (mRem) Skin (mRem)

WSW Near Milk 3.43 mi 248 deg 3.352E-04 2.620E-04 3.143E-04 5.422E-04 SE Visitor 1.078E-03 8.426E-04 1.011E-03 1.743E-03 SE Nearest Res 1.52 mi 142 deg 2.489E-03 1.946E-03 2.334E-03 4.027E-03 SSW Near Gard 4.4 mi 207 deg 1.888E-04 1.476E-04 1.771E-04 3.055E-04 User: Al Locke [Server]: PSLSA37 [Database]: NEOEMSP

Gas Status Summary Report Tuesday, February 14, 2012 03:51 Page 6 of 7 Period: Ann, 2011 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 2.955E-05 2.955E-05 2.955E-05 2.955E-05 2.955E-05 2.955E-05 2.955E-05 0.OOOE+00 NW Site Boundary - In Infant 2.723E-04 3.970E-03 3.829E-03 7.578E-03 1.749E-03 3.838E-03 3.815E-03 0.OOOE+00 Maximum Doserate by Organ: 2.723E-04 3.970E-03 3.829E-03 7.578E-03 1.749E-03 3.838E-03 3.815E-03 O.OOOE+00 Maximum Organ Doserate (mRem/yr): 7.578E-03 Maximum Total Body Doserate (mRem/yr): 3.829E-03 Site Boundary NG Doserate Summary Gas Receptor Location Gamma (mRad/yr) Beta (mRad/yr) Total Body (mRem/yr) Skin (mRem/yr)

NW Site Boundary 2.212E-03 2.212E-03 2.086E-03 3.545E-03 WNW Site Boundary 1.906E-03 1.906E-03 1.797E-03 3.054E-03 User: Al Locke [Server]: PSLSA37 [Database]: NEOEMSP

Gas Status Summary Report Tuesday, February 14, 2012 03:51 Page 7 of 7 Gas Status Summary Report Tuesday, February 14, 2012 03:51 Page 7 of 7 Period: Ann, 2011 Site/Unit/Discharge Point: PSL1 Maximum Individual NNG Dose Summary - Note: All Doses in mRem Receptor Agegroup Bone Liver Total Body Thyroid Kidney Lung GI-Ili Skin SE Nearest Res - Adult Adult 9.923E-05 9.923E-05 9.912E-05 1.163E-04 9.921E-05 1.049E-04 9.936E-05 0.000E+00 SE Nearest Res - Child Child 9.922E-05 9.922E-05 9.909E-05 1.264E-04 9.911E-05 1.060E-04 9.915E-05 0.OOOE+00 SE Nearest Res - Infant Infant 9.918E-05 9.921E-05 9.907E-05 1.243E-04 9.906E-05 1.047E-04 9.907E-05 O.OOOE+00 SE Nearest Res - Teenager Teenager 9.917E-05 9.922E-05 9.910E-05 1.208E-04 9.921E-05 1.076E-04 9.932E-05 O.OOOE+00 SE Visitor - Adult Adult 4.608E-05 4.608E-05 4.603E-05 5.351E-05 4.607E-05 4.857E-05 4.613E-05 O.OOOE+00 SSW Near Garden - Adult Adult 7.686E-06 7.685E-06 7.678E-06 8.853E-06 7.684E-06 8.076E-06 7.694E-06 O.OOOE+00 SSW Near Garden - Child Child 7.685E-06 7.685E-06 7.676E-06 9.546E-06 7.677E-06 8.147 E-06 7.680E-06 O.OOOE+00 SSW Near Garden Teenager 7.681E-06 7.685E-06 7.676E-06 9.165E-06 7.684E-06 8.257E-06 7.691E-06 O.000E+00 WSW Near Milk - Adult Adult 1.985E-05 2.063E-05 1.960E-05 8.716E-05 1.902E-05 1.875E-05 1.792E-05 O.OOOE+00 WSW Near Milk - Child Child 2.646E-05 2.624E-05 1.937E-05 2.257E-04 1.910E-05 1.949E-05 1.790E-05 0.OOOE+00 WSW Near Milk - Infant Infant 3.597E-05 3.828E-05 1.971E-05 5.144E-04 1.909E-05 2.071E-05 1.790E-05 0.000E+00 WSW Near Milk - Teenager Teenager 3.705E-06 5.053E-06 1.942E-06 1.058E-04 1.698E-06 1.651E-06 7.743E-07 O.000E+00 Maximum Dose by Organ: 9..923E-05 9.923E-05 9.912E-05 5.144E-04 9.921E-05 1.076E-04 9.936E-05 0.OOOE+00 Maximum Organ Dose (mRem): 5.14*IE-04 Maximum Total Body Dose (mRem): 9.91 2E-05 Maximum Individual NG Dose Summary Gas Receptor Location Gamma (mRad) Beta (mRad) Total Body (mRem) Skin (mRem)

SSW Near Gard 4.4 mi 207 deg 1.500E-04 1.055E-04 1.415E-04 2.405E-04 SE Nearest Res 1.52 mi 142 deg 1.978E-03 1.391E-03 1.865E-03 3.170E-03 WSW Near Milk 3.43 mi 248 deg 2.663E-04 1.873E-04 2.511E-04 4.268E-04 SE Visitor 8.563E-04 6.023E-04 8.074E-04 1.372E-03 User: Al Locke [Server]: PSLSA37 [Database]: NEOEMSP

Gas Status Summary Report Tuesday, February 14, 2012 03:52 Page 7 of 8 Period: Ann, 2011 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 3.965E-06 3.965E-06 3.965E-06 3.965E-06 3.965E-06 3.965E-06 3.965E-06 0.OOOE+00 NW Site Boundary - In Infant 1.182E-02 1.384E-02 1.371E-02 1.511E-02 2.291E-03 1.372E-02 1.371E-02 0.OOOE+00 Maximum Doserate by Organ: 1.182E-02 1.384E-02 1.371E-02 1.511E-02 2.291E-03 1.372E-02 1.371E-02 0.000E+00 Maximum Organ Doserate (mRem/yr): 1.511E-02 Maximum Total Body Doserate (mRem/yr): 1.371E-02 Site Boundary NG Doserate Summary Gas Receptor Location Gamma (mRad/yr) Beta (mRad/yr) Total Body (mRem/yr) Skin (mRem/yr)

NW Site Boundary 4.869E-04 4.869E-04 4.468E-04 8.157E-04 WNW Site Boundary 4.194E-04 4.194E-04 3.849E-04 7.026E-04 User: Al Locke [Server]: PSLSA37 [Database]: NEOEMSP

Gas Status Summary Report Tuesday, February 14, 2012 03:52 Page 8 of 8 Period: Ann, 2011 Site/Unit/Discharge Point: PSL2 Maximum Individual NNG Dose Summary - Note: All Doses in mRem Receptor Agegroup Bone Liver Total Body Thyroid Kidney Lung GI-Lli Skin SE Nearest Res - Adult Adult 1.775E-05 1.774E-05 1.771E-05 2.027E-05 1.770E-05 1.848E-05 1.770E-05 0.000E+00 SE Nearest Res - Child Child 1.776E-05 1.775E-05 1.767E-05 2.104E-05 1.767E-05 1.865E-05 1.767E-05 0.OOaE+00 SE Nearest Res - Infant Infant 1.774E-05 1.774E-05 1.766E-05 2.075E-05 1.766E-05 1.849E-05 1.766E-05 0.OOOE+00 SE Nearest Res - Teenager Teenager 1.773E-05 1.775E-05 1.769E-05 2.071E-05 1.770E-05 1.887E-05 1.769E-05 0.OOOE+00 SE Visitor - Adult Adult 8.239E-06 8.238E-06 8.221E-06 9.340E-06 8.217E-06 8.560E-06 8.217E-06 0.OOOE+00 SSW Near Garden - Adult Adult 1.374E-06 1.374E-06 1.371E-06 1.547E-06 1.371E-06 1.424E-06 1.371E-06 0.OOOE+00 SSW Near Garden - Child Child 1.375E-06 1.374E-06 1.369E-06 1.600E-06 1.369E-06 1.436E-06 1.368E-06 0.OOOE+00 SSW Near Garden - Teenager 1.373E-06 1.374E-06 1.370E-06 1.577E-06 1.371E-06 1.45 1E-06 1.370E-06 0.OOOE+00 WSW Near Milk - Adult Adult 5.306E-06 6.089E-06 5.075E-06 3.393E-05 4.285E-06 3.580E-06 3.249E-06 0.OOOE+O0 WSW Near Milk - Child Child 1.205E-05 1.178E-05 4.614E-06 9.366E-05 4.357E-06 4.260E-06 3.240E-06 0.OOOE+00 WSW Near Milk - Infant Infant 2.173E-05 2.398E-05 4.715E-06 2.205E-04 4.355E-06 5.695E-06 3.242E-06 0.0001E+00 WSW Near Milk - Teenager Teenager 3.768E-06 5.077E-06 1.833E-06 4.660E-05 1.477E-06 7.990E-07 1.788E-07 0.OOOE+00 Maximum Dose by Organ: 2.173E-05 2.398E-05 1.771E-05 2.205E-04 1.770E-05 1.887E-05 1.770E-05 0.OOOE+00 Maximum Organ Dose (mRem): 2.20!5E-04 Maximum Total Body Dose (mRem): 1.77.1E-05 Maximum Individual NG Dose Summary Gas Receptor Location Gamma (mRad) Beta (mRad) Total Body (mRem) Skin (mRem)

WSW Near Milk 3.43 mi 248 deg 6.889E-05 7.474E-05 6.322E-05 1.154E-04 SE Visitor 2.215E-04 2.403E-04 2.033E-04 3.711E-04 SE Nearest Res 1.52 mi 142 deg 5.116E-04 5.550E-04 4.694E-04 8.570E-04 SSW Near Gard 4.4 mi 207 deg 3.881E-05 4.211E-05 3.561E-05 6.501E-05 User: Al Locke [Server]: PSLSA37 [Database]: NEOEMSP

Liquid Status Summary Report Tuesday, February 14, 2012 03:51 Page 6 of 6 Period: Ann, 2011 Site/Unit/Discharge Point: Site Liquid Dose Summary - Note: All Doses in mRem Receptor AaearouD Bone Liver Total Body Thyroid Kidney Lung GI-Lli Skin Liquid Recptor - Child Child 3.003E-02 1.068E-01 3.500E-02 8.364E-03 2.524E-03 1.217E-01 6.432E-02 O.OOOE+00 Liquid Receptor - Teenager Teenager 5.679E-02 2.300E-01 6.638E-02 6.786E-03 5.823E-03 2.632E-01 1.369E-01 O.OOOE+00 Maximum Dose by Organ: 5.679E-02 2.300E-01 6.638E-02 8.364E-03 5.823E-03 2.632E-01 1.369E-01 O.OOOE+00 Maximum Organ Dose (mRem): 2.632E-01 Maximum Total Body Dose (mRem): 6.638E-02 User: Al Locke [Server]: PSLSA37 [Database]: NEOEMSP

Liquid Status Summary Report Tuesday, February 14, 2012 03:54 Page 6 of 6 Period: Ann, 2011 Site/Unit/Discharge Point: PSL1 Liquid Dose Summary - Note: All Doses in mRem Receptor AaearouD Bone Liver Total Body Thyroid Kidney Lung GI-Lli Skin Liquid Recptor - Child Child 1.502E-02 5.340E-02 1.750E-02 4.182E-03 1.262E-03 6.085E-02 3.216E-02 0.OOOE+00 Liquid Receptor - Teenager Teenager 2.839E-02 1.150E-01 3.319E-02 3.393E-03 2.912E-03 1.316E-01 6.843E-02 0.000E+00 Maximum Dose by Organ: 2.839E-02 1.150E-01 3.319E-02 4.182E-03 2.912E-03 1.316E-01 6.843E-02 0.000E+00 Maximum Organ Dose (mRem): 1.316E-01 Maximum Total Body Dose (mRem): 3.319E-02 User: Al Locke [Server]: PSLSA37 [Database]: NEOEMSP

Liquid Status Summary Report Tuesday, February 14, 2012 03:55 Page 6 of 6 Period: Ann, 2011 Site/Unit/Discharge Point: PSL2 Liquid Dose Summary - Note: All Doses in mRem Receptor AaearouD Bone Liver Total Body Thyroid Kidne kjn GI-Lli Skin Liquid Recptor - Child Child 1.502E-02 5.340E-02 1.750E-02 4.182E-03 1.262E-03 6.085E-02 3.216E-02 O.OOOE+00 Liquid Receptor - Teenager Teenager 2.839E-02 1.150E-01 3.319E-02 3.393E-03 2.912E-03 1.316E-01 6.843E-02 O.OOOE+00 Maximum Dose by Organ: 2.839E-02 1.150E-01 3.319E-02 4.182E-03 2.912E-03 1.316E-01 6.843E-02 0.000E+00 Maximum Organ Dose (mRem): 1.316E-01 Maximum Total Body Dose (mRem): 3.319E-02 User: Al Locke [Server]: PSLSA37 [Database]: NEOEMSP