L-2015-052, St. Lucie, Units 1 and 2 - Annual Radioactive Effluent Release Report, January 1, 2014 Through December 31, 2014

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St. Lucie, Units 1 and 2 - Annual Radioactive Effluent Release Report, January 1, 2014 Through December 31, 2014
ML15075A154
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 02/25/2015
From: Katzman E S
Florida Power & Light Co
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Document Control Desk, Office of Nuclear Reactor Regulation
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L-2015-052
Download: ML15075A154 (59)


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L-2015-052 ENCLOSURE ENCLOSURE I COMBINED ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (58 PAGES)

FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS I AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 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, 2014 THROUGH DECEMBER 31, 2014 1.0 PROGRAM DESCRIPTION Regulatory Limits The Offsite Dose Calculation Manual (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 mrem/yr to the whole body and less than or equal to 3000 mrem/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 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad 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 mrem to any organ, and b. During any calendar year: Less than or equal to 15 mrem to any organ.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 pCi/ml total activity.

FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 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 mrem to any organ, and b. During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem 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 mrem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.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.OE-04 pCi/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 4.0.4, of the ODCM.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)

FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 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 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, Ni-63 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 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 absorbers and particulate filters. The radioiodine absorbers 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.

FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 Meteorological Monitoring Program In accordance with ODCM Administrative Control 3.11 .2.6.b., a summary of hourly meteorological data, collected during 2014, is retained onsite.This data is available for review by the NRC upon request. During 2014, the goal of >90% joint data recovery was met. Actual meteorological data collected during the year was used for the offsite dose calculations in this report.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 the PWR Section, Page 4-28 of the report, and employed the proxy generation rate values for a Combustion Engineering reactor. The actual 2014 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 2014 for Unit I was 11.53 Ci, and the total amount of C-14 released in 2014 for Unit 2 was 9.30 Ci.The highest calculated dose exposure pathway from C-14 is "Bone Dose" to a "Child" from consumption of garden produce. A "Child" consuming vegetables and produce 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 1.58E-01 mrem/yr.Using the same release values, the dose to a visitor on site (Adult Lifeguard) is found to be 4.89E-01 mrem/yr, Total Body dose. See Table 3.4, Dose Assessments, for more detail.This is a fraction of the I mrem annual whole body dose received by 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.)All C-14 dose calculations are based on Regulatory Guide 1.109 values.

FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 2.0 SUPPLEMENTAL INFORMATION 2.1 Abnormal Releases or Abnormal Discharges There were two abnormal (unplanned) releases or discharges from the site during the report period. No radioactivity or isotopes were released and neither release nor discharge had an impact to dose to the public.* On January 9, 2014, the St. Lucie Nuclear Plant performed an abnormal and unplanned emergency release from the Unit I Condensate Pump Pit to the intake canal to lower water levels in the condensate pit. The St. Lucie Nuclear Plant had declared an Unusual Event on January 9, 2014, due to significant rain which created rapidly rising water levels and the potential to exceed site storm drain capacity.

The degraded conduit failure was determined to be a reportable event in accordance with 50.73(a)(2)(ii) and the NRC was notified.

The Unusual Event was terminated on January 15, 2014, after water was consistently draining and actions were completed to ensure the site storm drain system was fully functional.

A blockage occurred in one area of our storm drain system later found to be from excess debris buildup which resulted in rising water in the I B condensate pump pit. The area had numerous electrical components which subsequently became submerged.

This condition posed a significant safety issue to our site employees and potential damage to the site equipment.

To mitigate the safety issue, rain water was pumped from the lB condensate pump pit to the intake canal, which resulted in an unanticipated bypass of our permitted outfall 1-008 at the South Settling Basin. The total estimated discharge of 60,000 gallons lasted for approximately 35-45 minutes. Once the storm drain blockage was corrected the remainder of water in the condensate pump pit was discharged through our permitted South Settling Basin outfall, 1-008.No radioactivity or isotopes were released as a result of the abnormal release from the Unit I condensate pump pit to the intake canal. Two independent condensate pit water samples were obtained and analyzed similar to Site South Settling Basin permitting requirements procedurally directed in the ODCM and site procedures.

No radioactive activity (gamma, tritium, alpha, hard to detect isotopes) was detected for the release.To prevent recurrence of the event, dredging and hardening of the storm drain system and barriers was completed to prevent future storm drain blockage.

Also, a revision was completed in May, 2014, to the ODCM to incorporate guidance for a rapid method to release water from site retention ponds either prior to or during severe weather events and emergency conditions.

This revision allows early initiation of South Settling Basin releases with prior upper management approval and eliminates the risk of sampling and analysis permitting delays which could prevent the start of the permitted release during emergency storm flooding risk conditions.

FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 On October 6, 2014, Unit I Fuel Handling Building ventilation equipment was not completely shutdown when the Fuel Handling Building Radiation Monitor, RSC-26-4, was declared inoperable.

The Fuel Handling Building Radiation Monitor had been declared inoperable on October 6, 2014, at 07:45 to start the project for replacement of the radiation monitor with a new Mirion MGPI radiation monitor. Fuel Handling Building Ventilation fans HVS-6, HVE-16A and HVE-16B were secured just prior to declaring the radiation monitor inoperable, but ventilation equipment HVE-17, HVS-7 and HVE-15 were inadvertently not secured as required and were left running. The ODCM requirement for compensatory gas grab samples every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and continuous sampling for iodine and particulates were not performed.

The Operating crew was under the assumption that all fans had been secured and that compensatory grab samples would not be required.

Ventilation fans HVS-7, HVE-15 and HVE-17 were secured upon discovery of fan operation on October 7, 2014, at 00:01. On October 6, 2014, the compensatory eight hour gas grab sample was not completed prior to 15:45 and 23:45 and continuous sampling for iodine and particulate was not performed after 07:45 as required by the ODCM.A total of 6.10E6 cubic feet of Unit 1 Fuel Handling Building Exhaust was released through ventilation exhaust fan HVS-17 for the total 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> and 16 minute duration.

No radioactivity or isotopes are estimated to have been released and there was no calculated dose impact to the public. No radioactivity was detected on the Unit I Fuel Handling Building particulate filter and iodine cartridge samples collected and analyzed for the continuous gaseous permit closed out on October 6, 2014, at 07:45 prior to declaring the monitor inoperable.

Also, no radioactivity (gamma, tritium, alpha, hard to detect isotopes) was detected for the previous two week continuous permits closed out on September 30, 2014 and September 22, 2014.To prevent recurrence of the event, procedural guidance was improved for securing Fuel Pool and Fuel Handling Ventilation on Unit I and 2. Notes and Precautions were added throughout site procedures I -NOP-25.08 and 2-NOP-25.08, Fuel Handling Building Ventilation, to better delineate which sections or fans must be secured in the event the Fuel Handling Building Exhaust Radiation Monitor is removed from service. Procedural guidance was clarified to secure all Fuel Handling Building Ventilation or comply with ODCM compensatory sampling guidance.2.2 Non-Routine Planned Discharges No non-routine planned discharges were made during the report period.

FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 2.3 Radioactive Waste Treatment System Changes No changes were made to the waste treatment system during the report period.One modification was completed during the report period for replacement of the two 40,000 gallon Waste Monitor Tanks used for discharge of radioactive liquid releases to the public. This was a like for like replacement and no changes were made to the tank volume or associated pumps, valves, or liquid radioactive waste discharge monitor.2.4 Annual Land Use Census Changes There were no changes to the Land Use Census during the report period.2.5 Effluent Monitoring System Inoperability There were four instances of effluent monitors out of service for greater than 30 days during the report period.* Steam Generator Blowdown Treatment Facility (SGBTF) Radiation Monitor (RM-45-1) was out of service for greater than thirty days. The SGBTF and associated radiation monitor, RM-45-1, lost power on December 12, 2013, due to an electrical fault on the 1B9 Motor Control Center and fire related to troubleshooting of SGBTF Fan, HVE-41 A. As a result of the fire, RM-45-1 was de-energized and declared inoperable.

Due to the loss of power, SGBTF ventilation had been secured and no release was in progress.Alternate monitoring of the SGBTF using the portable Eberline Particulate, Iodine, Noble Gas (PING) Radiation Monitor was placed in-service and continuous sampling of iodine and particulate was established within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of loss of the radiation monitor as required by Site Technical Specification and ODCM requirements.

RM-45-1 (SGBTF Radiation Monitor) was repowered and returned to service on February 24, 2014 and the SGBTF ventilation remained secured.* SGBTF Radiation Monitor (RM-45-1) was out of service for greater than 30 days. Power was secured to RM-45-1 on July 16, 2014, to complete a clearance order to return the SGBTF 1 B9 Motor Control Center (MCC)back to normal operation and service following completion of repairs.Power restoration efforts to the SGBTF MCC were delayed due to electrical equipment issues and problems which delayed restoring power to RM-45-1 and placing the radiation monitor back in-service prior to the 30-day period. Due to the loss of power to the 11B9 MCC, SGBTF ventilation had been secured and no release was in progress.Alternate monitoring of the SGBTF using the portable Eberline Particulate, Iodine, Noble Gas (PING) Radiation Monitor was placed in service and continuous sampling of iodine and particulate was established FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as required by Site Technical Specification and ODCM requirements.

RM-45-1 (SGBTF Radiation Monitor) was declared back in service on Aug. 22, 2015 following power restoration to the SGBTF.Liquid Radioactive Waste Discharge Monitor (RE-6627) was out of service for greater than thirty days. RE-6627 was removed from service on June 30, 2014, due to a clearance to change the electrical conduit size on Penetration 19 from 4 inches to 2 inches. This work was completed to harden the penetration in support of the project for flood sealing conduits as part of Storm Water Mitigation Efforts. Delays in restoring power were due to radiation monitor electrical reconnection problems and lead to the radiation monitor being out of service for greater than thirty days.RE-6627 was returned to service on August 17, 2014.* Unit I Fuel Handling Building Radiation Monitor (RSC-26-4) was out of service for greater than thirty days. RSC 26-4 was removed from service on October 6, 2014, for replacement with the new Mirion MGPI radiation monitor. Applicability to the minimum channel operability requirement of the ODCM applies only at times while making release via this pathway.Unit I Fuel Handling Building ventilation has been secured since October 7, 2014, for the remainder of the report period as per ODCM procedural requirements.

Replacement of the monitor is in progress but has not been completed as of the end of the report period.2.6 Offsite Dose Calculation Manual Changes Two revisions were made to the St. Lucie Site ODCM during the report period.* A revision was completed in May 2014 to incorporate guidance for a rapid method to release water from site retention ponds either prior to or during severe weather events and emergency conditions.

This revision allows early initiation of South Settling Basin releases from the permitted outfall 1-008 with prior upper management approval.

The revision eliminates the risk of sampling, analysis, and permitting delays which could prevent the start of the permitted release during emergency storm flooding risk conditions.

  • A revision was completed in December 2014 to incorporate the following four changes: o Revision of ODCM procedural requirements for placing the new Unit 1 Mirion MGPI Fuel Handling Building Radiation Monitor in service.o Clarification of ODCM procedural guidance for compensatory sampling of gaseous process radiation monitors related to loss of FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 control room annunciation and use of alternate radiation monitoring.

o Removal of the goat from ODCM, Figure 1-2, St. Lucie Nuclear Environmental Radiological Environmental Monitoring Program (REMP) Sample Locations (10 Miles). The goat is no longer located at the REMP environmental sample location.o Addition of improved ODCM procedural guidance for conducting St. Lucie Nuclear Site REMP Program Supplemental Sampling.2.7 Process Control Program Changes A revision to the Process Control Program was made in August, 2014, that incorporated the following changes:* Changed the position titles from Health Physics Supervisor to Radiation Protection Manager.* Changed the Facility Review Group title to Onsite Review Group.* Added the reference to vendor procedure CS-OP-PR-008-161049,"Setup, Operation, and Dewatering Using Energy Solutions Self-Engaged Dewatering System Fill Head at St. Lucie."" Removed reference to deleted Technical Specification section 6.10.2.q." Changed the procedure reference for record retention from QI-17-PSL-1, "Quality Assurance Records" to RM-AA-100-1000, "Processing Quality Assurance Records."* Changed the procedure reference from HP-40, "Shipment of Radioactive Materials" toRP-AA-108-1002, "Radioactive Shipping Procedure."* Removed reference to the Barnwell disposal facility.* Removed the requirement to list the container types in the Annual Radioactive Effluent Release Report.* Added the words "as applicable" when discussing the solidification agent use.

FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 2.8 Corrections to Previous Reports There were no corrections to previous reports during the report period.2.9 Other Eleven batch releases were made from the South Settling Basin to the Intake Canal during the report period to lower the water level from periods of higher than normal rainfall.

All eleven releases were analyzed according to the ODCM and site procedural requirements and were found to have no detectable gamma, tritium, alpha or hard to detect isotopes.

The releases are listed below: Release start date January 9 January 29 February 13 March 6 May 15 June 5 June 19 July 1 July 23 July 31 September 29 Volume of release I.70E7 gallons 7.75E6 gallons 6.36E6 gallons 6.22E6 gallons 4.43E6 gallons 1.81 E6 gallons 9.40E5 gallons.1 7E6 gallons 1.42E6 gallons 6.62E6 gallons 4.39E4 gallons 2.10 Groundwater Protection Program (next 2 pages)* No limits were exceeded for the analyzed St. Lucie Nuclear Site Groundwater Protection Program for the report period.* St. Lucie Nuclear Site Groundwater Protection Program results for the report period are contained in the following tables.

2014 PSL Ground Water Well Results for Annual Report H3 Jan H3 Feb H3 Mar H3 Apr H3 May H3 June H3 July H3 Aug H3 Sept H3 OCT H3 NOV H3 Dec 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 EiID. eU 'iRtI1&2, pCiIl pCi/I pCi/I pCi/I pCi pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I MW-3 709 1040 571 703 706 946 592 802 MW-4 427 621 743 614 MW-5 <MDC <MDC <MDC <MDC MW-6 1340 1190 1780 1460 MW-7 <MDC <MDC 342 348 MW-15 3530 535 363 398 413 220 475 MW-16 232 285 479 413 MW-17 1560 1100 281 355 MW-18D 909 1390 1180 793 MW-19 <MDC <MDC <MDC <MDC MW-22D 188 369 <MDC <MDC MW-26 <MDC <MDC <MDC <MDC RW-2 310 541 392 291 RW-4 <MDC <MDC <MDC <MDC RW-5 <MDC <MDC <MDC <MDC MW-30 539 295 378 269 MW-31 277 400 406 268 MW-32 360 460 643 355 MW-33 1390 1140 1160 1090 H3 Jan H3 Feb H3 Mar H3 Apr H3 May H3 June H3 July H3 Aug H3 Sept H3 OCT H3 NOV H3 Dec 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014, ,ells 11111 pCi/I pCi/I pCi/pl / pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I pCi/ I Unit 1-MWO01 <MDC <MDC <MDC 417 Unit 1-MWO02 <MDC <MDC <MDC 228 Unit 1-MWO03 <MDC <MDC <MDC 304 Unit 1-MWO04 444 450 <MDC 246 Unit 1-MWO05 647 757 558 1620 Unit 2-MWO01 <MDC <MDC <MDC <MDC Unit 2-MWO02 527 529 1920 <MDC 622 1010 Unit 2-MWO03 582 410 782 379 Unit 2-MWO04 645 610 746 870 2014 PSL Ground Water Well Results for Annual Report M I H3 Jan H3 Feb H3 Mar H3 Apr ne H3July H3Aug H3 OCT H3 NOV Monitor Well ID 2014 2014 014 2014 2014 2014 2014 l .dlJ,, l pCi/I pCi I piIl pCi/I pCi/I pCi/I *~il pi (S)-MW-1 <MDC 281 <MDC (S)-MW-2 MN (S)-MW-3 (S)-MW-4 1555 388 377 275 (S)-MW-5 (S)-MW-6 265 289 312 (S)-MW-7A

<MDC 10 <MDC MDC (S)-MW-11 (S)-MW-1 1 446 335 325 (S)-MW-13D (S)-MW-14 (S)-MW-15D MDC <MDC (S)-MW-16

<MDC <MDC <MDC <MDC (S)-MW-16i 286 40358 297 (S)-Mw-17

<MDC <MDC (S)-MW-18

<MDC <MDC (S)-MW-19

<MDC <MDC H3 Jan H3 Feb H3 Mar H3 Apr H3 May H3 June H3 July H3 Aug H3 Sept H3 OCT H3 NOV H3 Dec 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 I pCi/I pgi/ pCi/I p~/ p~i/I pCi/I pCi/I p~/ ~ / pCi/I p~iI p~i/I PSLED-2 <MDC NB-MW-1 <MDC NB-MW-2 <MDC FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 3.0 TABLES 3.1 Gaseous Effluents

& Liquid Effluents (Enclosure 1, 22 pages)3.2 Solid Waste Storage and Shipments (Enclosure 1, 6 pages)3.3 Dose Assessments (Enclosure 1, 15 pages)3.4 Visitor Dose (Enclosure 1, 1 page)

L~Thicm Ma ~cm~m Sof~v~.-4rc Wednesday, February 11, 2015 10:52:12AM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 5A and 5B -Liquid and Gas Batch Release Summary A. Liquid Batch Release Totals 1. Number of Batch Releases 2. Total duration of batch releases 3. Maximum batch release duration 4. Average batch release duration 5. Minimum batch release duration B. Gas Batch Release Totals 1. Number of Batch Releases 2. Total duration of batch releases 3. Maximum batch release duration 4. Average batch release duration 5. Minimum batch release duration Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014 Units 1st Quarter 2nd Quarter 3rd Quarter 33 12 16 min 2.22E+04 1.07E+04 1.78E+04 min 2.47E+03 4.79E+03 8.64E+03 min 6.74E+02 8.88E+02 1.11E+03 min 2.75E+02 2.75E+02 3.90E+02 Units 1st Quarter 2nd Quarter 3rd Quarter 49 74 72 min 1.45E+04 1.75E+04 2.71E+04 min 6.45E+02 5.61E+02 1.11E+04 min 2.97E+02 2.37E+02 3.76E+02 min 2.OOE+01 7.OOE+00 2.30E+01 4th Quarter 9 3.87E+03 6.70E+02 4.30E+02 2.21E+02 4th Quarter 69 2.49E+04 6.75E+03 3.60E+02 1.80E+01 Year Totals 70 5.46E+04 8.64E+03 7.80E+02 2.21E+02 Year Totals 264 8.40E+04 1.11E+04 3.18E+02 7.OOE+00 User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP EMS--.i Ef~fluent, Managameinr Softi arc Wednesday, February 11, 2015 10:54:50AM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 6A and 6B -Liquid and Gas Abnormal Release Summary Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014 se Totals Units 1st Quarter 2nd Quarter 3rd Quarter 4th QL ases 0 0 0 0 releases Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE A. Liquid Abnormal Relea 1. Number of Abnormal Rele 2. Total Activity of abnormal marter"+00 Year Totals 0 0.OOE+00 Year Totals 0 0.00E+00 B. Gas Abnormal Release Totals 1. Number of Abnormal Releases 2. Total Activity of abnormal releases Units 1st Quarter 2nd Quarter 3rd Quarter 0 0 0 Ci 0.00E+00 0.OOE+00 0.OOE+00 4th Quarter 0 O.OOE+00 User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP IL a1uccz MXnMQcnSofmwjre Page 1 of 1 Wednesday, February 11, 2015 11:02:45AM Florida Power & Ught St. Lucie Power Plant Reg. Guide 1.21, Table 1A, Gaseous Effluents

-Summation of All Releases Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014 Total Release A. Fission and Activation Gases 1. Total Release 2. Average Release Rate for Period 3. Percent of Limit B. Iodines and Halogens 1. Total Release 2. Average Release Rate for Period 3. Percent of Limit C. Particulates

1. Total Release 2. Average Release Rate for Period 3. Percent of Limit D. Tritium 1. Total Release 2. Average Release Rate for Period 3. Percent of Umit E. Gross Alpha 1. Total Release F. Carbon-14 1. Total Release 2. Average Release Rate for Period 3. Percent of Limit Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Uncertainty a uCi/s a uCi/s uOi/s Ci UOl/s 0 0 UCi1/s 1.61E+01 2.07E+00 8.95E-04 1.15E-04 1.01E-07 1.30E-08 4.28E4-00 5.51E-01 O.OOE+O0 4.77E+00 6. 13E-01 9.26E-01 1.18E-01 3.84E-06 4.88E-07 1.05E-06 1.34E-07 3.57E+00 4.54E-01 2.75E-09 4.99E+00 6.35E-01 5.22E+00 6.57E-01 O.OOE+O0 0.ODE+0Q 0.OOE+00 0.OOE+00 2.55E+01 3.20E+00 3.70E-08 5.47E+00 6.88E-01 9.68E-01 1.22E-01.1.25E-06 1.57E-07 0.OOE+00 0-OOE+00 1.19E+01 1.49E+00 5.97E-08 5.61E+00 7.06E-01 2.32E+01 7.36E-01 9.OOE-04 2.85E-05 1.15E-06 3.65E-08 4.52E+01 1.43E+00 9.95E-08 2.08E+01 6.61E-01 User: 3ira Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP T':1 AC" Page 1 of 3 V.! -' !..- " Wednesday, February 11, 2015 11:05:37AM E.f-u. t Mmabgemnt.S e Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 1B, Gaseous Effluents

-Ground Level Release -Continuous Mode Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014

.Continuous Mode Nuclides Released A. Fission and Activation Gases ArA-1 Xe-133 Total For Period B. lodines and Halogens 1-131 1-133 Total For Period C. Particulates Cs-137 D. Tritium H-3 E. Gross Alpha G-Alpha F. Carbon-14 C-14 Units Ci Ci Ci a a Ci 1ST Quarter O.OOE+00 6.65E-01 6.65E-01 8.71E-04 2.35E-05 8.95E-04 1.01E-07 2,88E+00 0.OOE+00 4.77E+00 2ND Quarter O.OOE+00 0.OOE+00 O.OOE+O0 3.84E-06 0.OOE+00 3.84E-06 1.05E-06 3.31E+00 2.75E-09 4.99E+00 3RD Quarter 4TH Quarter 1.71E+00 O.OOE-'0O 1.71E+00 0.OOE+OQ 0.OOE+00 O.OOE+OO 0.OOE+0O 2.48E+01 3.70E-08 5.47E+0O 0.OOE+00 0.OOE+00 O.OOE+OO 1.25E-06 0.OOE+00 1.25E-06 0.OOE+OO 1.16E+01 5.97E-08 5 .61E+00 Annual 1.71E+00 6-65E-01 2.37E+00 8.76E-04 2.35E-05 9.OOE-04 1.15E-06 4.25E+01 9.95E-08 2.08E+01 0 Ci Ci Ci If Not Detected, Nuclide is Not Reported.

Zeroes in this talkie indicates that no radioactivity was present at detectable levels.User: Jim Hunt [Server]:

PSLSA134 [Database]:

NEPSOEMP Florida Power & Light, St. Lucie Power Plant 2/11/2015 11:05 Page 2 of 3 Reg. Guide 1.21, Table 1B, Gaseous Effluents

-Ground Level Release -Batch Mode Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released A. Fission and Activation Gases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Ar-41 Kr-85m Kr-85 Kr-87 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-138 Total For Period B. lodines and Halogens No Nuclides Found C. Particulates No Nuclides Found Qi Ci Ci Ci aj Ci Ci Ci 6.90E-01 0.00E+00 1.90E-01 0.00E+00 0.OOE+00 1.19E-02 1.49E-01 1.44E+01 0.00E+00 8.47E-03 0.00E+00 1.54E+01 7.34E-01 0.00E+00 1.35E-01 1.78E-04 0.00E+00 5.78E-03 4.46E-04 5.07E-02 2.45E-04 3.57E-04 0.00E+00 9.26E-01 3.08E+00 0.00E+00 0.00E+00 0.OOE+00 1.08E-02 0.00E+00 3.05E-03 4.08E-01 0.OOE+00 1.25E-02 4.73E-04 3.51E+00 8.26E-01 5.26E-05 0.00E+00 1.26E-04 0.00E+00 0.OOE+00 7.61E-04 1.36E-01 4.13E-04 2.18E-03 5.33E+00 5.26E-05 3.25E-01 3.05E-04 1.08E-02 1.77E-02 1.53E-01 1.50E+01 6.58E-04 2.35E-02 2.33E-03 2.80E-03 9.68E-01 2.09E+01 D. Tritium Ci Ca a Ci 0.00E+00 0.00E+00 1.40E+00 0.00E+00 0.00E+00 0.00E+00 2.61E-01 0.00E+00 O.OOE+00 O.OOE+00 6.77E-01 O.OOE+00 0.00E+00 0.00E+00 2.87E-01 0.00E+00 0.00E+00 0.OOE+00 2.62E+00 0.00E+00 H-3 E. Gross Alpha No Nudides Found If Not Detected, Nuclide is Not Reported.

Zeroes in this table indicates that no radioactivity was present at detectable levels.User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Florida Power & Light, St. Lucie Power Plant 2/11/2015 11:05 Reg. Guide 1.21, Table 1B, Gaseous Effluents

-Ground Level Release -Batch Mode Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014 Page 3 of 3 Batch Mode Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Nuclides Released F. Carbon-14 No Nuclides Found a 0.00E+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: Jim Hunt [Server]:

PSLSA134 [Database]:

NEPSOEMP Effluat Mm1vbnh~cn Sofma~re Page 1 of 1 Wednesday, February 11, 2015 11:13:17AM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table IA, Gaseous Effluents

-Summation of All Releases Unit: PSL1 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Total Release Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter A. Fission and Activation Gases 1. Total Release 2. Average Release Rate for Period 3. Percent of Limit B. Iodines and Halogens 1. Total Release 2. Average Release Rate for Period 3. Percent of Limit C. Particulates

1. Total Release 2. Average Release Rate for Period 3. Percent of Limit D. Tritium 1. Total Release 2. Average Release Rate for Period 3. Percent of Limit E. Gross Alpha 1. Total Release F. Carbon-14 1. Total Release 2. Average Release Rate for Period 3. Percent of Limit Ci uCi/s Ci uCi/s%Ci uCi/s a Ci Ci uC7i/s 4.37E-01 S.62E-02 1.29E-06 1.66E-07 O.OOE+00 0.OOE+OO 4.71E-02 6.OSE-03 O.OOE+00 2.85E+00 3.67E-01 5.19E-01 6.60E-02 1.11 E-06 1.42E-07 1.05E-06 1.34E-07 3.52E+00 4.48E-01 O.OOE+00 2.87E+00 3.65E-01 3.48E-01 4.37E-02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.50E+01 3.14E+00 0.OOE+00 2.90E+00 3.64E-01 4.51E-01 5.68E-02 0.OOE+O0 0.OOE+00 0.OOE+Q0 O.OOE+O0 5.93E+00 7.47E-01 0.OOE+OO 2.92E+00 3.67E-01 Annual Uncertainty 1.75E+00 5.56E-02 2.41E-06 7.63E-08 1.05E-06 3.33E-08 3.45E+01 1.09E+00 0.00E+00 1.15E+01 3.66E-01 User: 3im Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Page 1 of 2"77'"":',:-'; .I-Wednesday, February 11, 2015 11:16:06AMSofe Florida Power & Light St Lucie Power Plant Reg. Guide 1.21, Table 1B, Gaseous Effluents

-Ground Level Release -Continuous Mode Unit: PSL1 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A. Fission and Activation Gases No Nuclides Found Ci 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 B. Iodines and Halogens 1-131 Ci 1.29E-06 1.11E-06 O.OOE+O0 O.OOE+O0 2.41E-06 C. Particulates Cs-137 Ci O.OOE+00 1.05E-06 O.OOE+O0 O.OOE+00 1.05E-06 D. Tritium H-3 Ci 0.OOE+00 3.31E+00 2.48E+01 5.77E+00 3.39E+01 E. Gross Alpha No Nuclides Found Ci O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 F. Carbon-14 C-14 Ci 2.85E+00 2.87E+00 2.90E+00 2.92E+00 1.15E+01 If Not Detected, Nuclide is Not Reported.

Zeroes in this table indicates that no radioactivity was present at detectable levels.User: Jim Hunt [Server]:

PSLSA134 [Database]:

NEPSOEMP Florida Power & light, St. Lucie Power Plant 2/11/2015 11:16 Page 2 of 2 Reg. Guide 1.21, Table 1B, Gaseous Effluents

-Ground Level Release -Batch Mode Unit: PSL1 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released A. Fission and Activation Gases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Ar-41 Kr-85m Kr-87 Xe-133m Xe-133 Xe-135m Xe-135 Total For Period Ci Ci 4-35E-01 0-OOE+00 O.QOE+00 0.QOE+O0 2.OOE-03 0.OOE+00 0.OOE+00 4.37E-01 4.88E-01 0.OOE+00 1.78E-04 4.46E-04 3.02E-02 2.45E-04 3.57E-,04 5.19E-01 3.16FE-01 0.OOE+00 0.OOE+00 2.42E-04 3.14E-02 0.OOE+00 2.17E-04 3.48E-01 4.23E-01 5.26E-05 1.26E-04 0.OOE+O0 2.82E-02 0-0OE+00 8.95E-05 4.51E-01 Annual 1.66E+00 5.26E-05 3.O5E-04 6.88E-04 9.17E-02 2.45E-04 6.64E-04 1.75E+00 B. lodines and Halogens No Nuclides Found C. Particulates No Nuclides Found D. Tritium H-3 E. Gross Alpha No Nuclides Found F. Carbon-14 No Nuclides Found ci a ci ci ci 0.COE+00 O.OOE+O0 4.71E-02 0.COE+O0 O.OOE+00 0.OOE+0C 0.OOE+0O 2. 15E-01 0.OOE+00 0.OOE+O0 0.OOE-'00 0.OOE+00 2.OOE-01 0.OOE+00 O.OOE+00 0.OOE+00 0.COE+O0 1.64E-01 O.OOE-i00 0.OOE+O0 0.OOE+OO 0.OOE+00 6.27E-01 O.OOE+00 0.OOE+O0 If Not Detected, Nuclide is Not Reported.

Zeroes in this table indicates that no radioactivity was present at detectable levels.User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Effluent NI=-,a~n Sofcwre Page 1 of 1 Wednesday, February 11, 2015 11:17:28AM Florida Power & Light St Lucie Power Plant Reg. Guide 1.21, Table IA, Gaseous Effluents

-Summation of All Releases Unit: PSL2 Starting:

1-3an-2014 Ending: 31-Dec-2014 Total Release A. Fission and Activation Gases 1. Total Release 2. Average Release Rate for Period 3. Percent of Limit B. Iodines and Halogens 1. Total Release 2. Average Release Rate for Period 3. Percent of Limit C. Particulates

1. Total Release 2. Average Release Rate for Period 3. Percent of Limit D. Tritium 1. Total Release 2. Average Release Rate for Period 3. Percent of Limit E. Gross Alpha 1. Total Release F. Carbon-14 1. Total Release 2. Average Release Rate for Period 3. Percent of Limit Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Uncertainty 2.15E+01 6.81E-01 Ci ua/s%uCi/s uCi/s Ci uCi/s Ci uCi/s 1.57E+01 2.02E+00 8.93E-04 1-15E-04 1.01E-07 1.30E-08 4.23E+00 5.45E-01 0.OOE+0O 1.92E+00 2.47E-01 4.07E-01 5.18E-02 2.73E-06 3.47E-07 0.OOE+00 O.OOE+00 4.58E-02 5.82E-03 2.75E-09 2.12E+00 2.69E-01 4.87E+00 6.13E-01 O.OOE+00 0.OQE+QO O.COE+00 O.OOE--00 4.84E-01 6.09E-02 3.70E-08 2.57E+00 3.24E-01 5.16E-01 6.50E-02 1.25E-06 1.57E-07 0.OOE+O0 O.00E+00 5.92E+00 7.45E-01 5.97E-08 2.69E+00 3.39E-01 8.97E-04 2.85E-05 1.O1E-07 3.20E-09 1.07E+01 3.39E-01 9.95E-08 9.30E+00 2.95E-01 User: Jim Hunt (Server]:

PSLSA134 [Database]:

NEPSOEMP

.V ~LI~i Page I of 2 Wednesday, February 11, 2015 11:18:48AM Florida Power & Ught St. Lucie Power Plant Reg. Guide 1.21, Table 1B, Gaseous Effluents

-Ground Level Release -Continuous Mode Unit: PSL2 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released A. Fission and Activation Gases Ar-41 Xe-133 Total For Period Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter B. Iodines and Halogens 1-131 1-133 Total For Period C. Particulates Cs-137 D. Tritium H-3 E. Gross Alpha G-Alpha F. Carbon-14 C-14 Ci 0i Ci Ci CA Ci Ci 0i Ci 0.OOE+0O 6.65E-01 6.65E-01 8.70E-04 2.35E-:05 8.93E-04 1 .01E-07 2.88E+00 0.COE+0O 1.92E+00 0.OOE+O0 0.OOE+O0 O.OOE+OO 2.73E-06 O.OOE+0O 2.73E-06 O.OOE+OO O.OOE--00 2.75E-09 2.12E+00 1.71E+00 0.OOE+O0 1.71E+00 0.OOE--00 0.OOE+0O O.OOE+OO Q.OOE+OO 7.18E-03 3.70E-08 2.57E+00 0.OOE+00 0.OOE+G0 O.OOE+OO 1.25E-06 0.OOE+OO 1.25E-06 O.OOE+O0 5.80E+00 5.97E-08 2.69E+00 Annual 1.71E+00 6.65E-01 2-37E+00 8.74E-04 2.35E-05 8.97E-04 1-OIE-07 8.69E+00 9.95E-08 9.30E+00 Ci If Not Detected, Nuclide is Not Reported.

Zeroes in this table indicates that no radioactivity was present at detectable levels.User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Florida Power & Ught, St. Lucie Power Plant 2/11/2015 11:18 Page 2 of 2 Reg. Guide 1.21, Table 1B, Gaseous Effluents

-Ground Level Release -Batch Mode Unit: PSL2 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released A. Fission and Activation Gases Ar-41 Kr-85 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-138 Total For Period B. lodines and Halogens No Nuclides Found C. Particulates No Nuclides Found D. Tritium H-3 E. Gross Alpha No Nuclides Found F. Carbon-14 No Nuclides Found Units Ci Ci Ci Ci a Ci a Ci 0 Ci Ci Ci 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter 2.55E-01 1.90E-01 0.OOE+00 1.19 E-02 1.49E-01 1.44E+01 O.00E4-00 8.47E-03 O.OOE+O0 1.SOE+OI.0.OOE+00 0.COE+00 1.35E+00 0.OOE+00 2.46E-01 1-35E-01 Q.OOE+O0 5.78E-03 0-OOE+00 2.05E-02 0.OOE+O0 0-OOE+00 0-0OE+00 4.07E-01 0.OOE+00 0.OOE+00 4.58E-02 0.OOE+00 2.76E+00 0.OOE+/-00 1 .08E-02 O.OOE+0O 2.81E-03 3.76E-01 0.OOE+O0 1.23E-02 4.73E-04 3.16E+00 0.OOE+00 0.OOE+0O 4.77E-01 0.OOE+O0 4-03E-01 0.OOE+00 0.OOE+Q0 O.OOE+Q0 7.61E-04 1.08E-01 4. 13E-04 2.09E-03 2.33E-03 5-16E-01 Q.OOE+00 C.COE+00 1.23E-01 Q.OOE+00 Annual 3.67E+00 3.25E-01 1.08E-02 1.77E-02 1.53E-01 1.49E+01 4.13E-04 2.29E-02 2.80E-03 1.91E+01 O.OOE+OO O.OOE+0O 2.OOE+00 0.OOE+OO a O.OOE+00 0.OOE+00 O.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: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP EflYucnt Nbnag~ment Sofiv.-.re Page 1 of 1 Wednesday, February 11, 2015 1:33:03PM Florida Power & Light St. Lude Power Plant Reg. Guide 1.21, Table 2A, Liquid Effluents

-Summation of All Releases Unit: Site Starting:

1-3an-2014 Ending: 31-Dec-2014 Total Release Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Uncertainty A. Fission and Activation Products 1. Total Release 2. Average Concentration

3. Percent of Limit B. Tritium 1. Total Release 2. Average Concentration
3. Percent of Limit C. Dissolved and Entrained Gases 1. Total Release 2. Average Concentration
3. Percent of Umit D. Gross Alpha Activity 1. Total Release 2. Average Concentration E. Primary Liquid Release Volume 1. Total Release F. Dilution Volume 1. Total Release G. Average Stream Flow 1. Total Release Ci uCi/mL a Ci uCi/mL Ci uCi/mL uCi/mL Liters Liters mA3/s 2.65E-02 2.13E-10 1. 16E+ 02 9.29 E-07 2.69E-01 2.16E-09 O.OOE+O0 O.OOE--00 1.44E+08 1.24E+11 0.OOE+00 2.04E-03 6.OSE-11 2.08E+01 6.19E-07 1.62E-04 4.8 1E-12 0.OOE+00 0.00E+C0 2.78E+07 3.37E+10 O.OOE+C0 3.72E-03 5.60E-11 9.87E+01 1.49E-06 1.25E-05 1.88E-13 0.QOE+00 O.OOE+Q0 3.59E+07 6.64E+10 0.OOE+00 2.65E-02 1.78E-09 1.18E+02 7.97E-06 8.08E-05 5.44E-12 0.OOE+00 0.00E+00 6.2-5E+'05 1.49E+10 0.OOE+00 5.88E-02 2.46E-10 3.54E+i02 1.48E-06 2.69E-01 1.13E-09 0.OOE+00 O.00E+00 2.08E+08 2.39E+11 0.OOE-i00 User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP I- 7-~ II -EtiTh~nt M~in~m~rK Sotrwire Page 1 of 1 Wednesday, February 11, 2015 1:34:37PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 2A, Liquid Effluents

-Summation of All Releases Unit: PSL1 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Total Release A. Fission and Activation Products 1. Total Release 2. Average Concentration

3. Percent of Limit B. Tritium 1. Total Release 2. Average Concentration
3. Percent of Limit C. Dissolved and Entrained Gases 1. Total Release 2. Average Concentration
3. Percent of Limit D. Gross Alpha Activity 1. Total Release 2. Average Concentration E. Primary Liquid Release Volume 1. Total Release F. Dilution Volume 1. Total Release G. Average Stream Flow 1. Total Release Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Uncertainty 2.94E-02 2.46E-10 Ci uCi/mL Ci uCi/mL%uCi/mL uCi/mL Liters Liters mA3/s 1.33E-02 2.13E-10 5.78E+01 9.29E-07 1.34E-01 2. 16E-09 O.00E+00 0.COE+00 7.18E+.07 6.22E+10 0.OOE+00 1.02E-03 6.05E-11 1.04E+01 6. 19E-07 8.10E-05 4.81E-12 0.OOE+00 0.OOE+00 1.39 E+07 1.68E+10 0.OOE+00 1.86E-03 5.60E-11 4.93E+01 1.49E-06 6.24E-06 1.88E-13 O.OOE+00 0.OOE+00 1.80E+07 3.32E+10 O.OOE+00 1.32E-02 1.78E-09 5.92E+01 7.97E-06 4.04E-05 5.44E-12 O.OOE+00 0.OOE+00 3. 13E+05 7.43E+09 0.OOE+O0 1.77E+02 1.48E-06 1-35E-01 1.13E-09 O.OOE+00 0.OOE+O0 1.04E+08 1.19E+11 0.QOE+0O User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Page 1 of 1 E M S .Wednesday, February 11, 2015 1:35:03PM E'flumne Soefimire Florida Power & Light St Lucie Power Plant Reg. Guide 1.21, Table 2A, Liquid Effluents

-Summation of All Releases Unit: PSL2 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Total Release Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Uncertainty A. Fission and Activation Products 1. Total Release 2. Average Concentration

3. Percent of Limit B. Trtium 1. Total Release 2. Average Concentration
3. Percent of Limit C. Dissolved and Entrained Gases 1. Total Release 2. Average Concentration
3. Percent of Limit D. Gross Alpha Activity 1. Total Release 2. Average Concentration E. Primary Uquid Release Volume 1. Total Release F. Dilution Volume 1. Total Release G. Average Stream Flow 1. Total Release Ca uCi/mL a uCi/mL%uCi/mL uCimL Liters Liters mA3/s 1.33E-02 2.13E-10 5.78E+01 9.29E-07 1.34E-01 2.16E-09 0.QDE+00 0.OOE+00 7.18E+07 6.22E+10 0.OOE+O0 1-02E-03 6-05E-11 1.04E+01 6. 19E-07 8.-10E-05 4.81E-12 1.86E-03 5.60E-11 4.93E+01 1.49E-06 6.24E-06 1.88E-13 Q.OOE+00 Q.OOE+0O 1.80E+07 3.32E+10 0.00E+00 1.32E-02 1.78E-09 5.92E+01 7.97E-06 4.04E-05 5.44E-12 0.00E+O0 0.OOE+O0 3. 13E+05 7.43E+09 0.00E+00 2.94E-02 2.46E-10 1.77E+02 1.48E-06 1.35E-01 1.13E-09 O.OOE+OQ Q.OOE+O0 1.04E+08 1.19E+11 0.00E+Q0 0.OOE+00 0.OOE+Q0 1.39E+07 1.68E+10 O.OOE+00 User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Page 1 of 3..J./. -.Wednesday, February 11, 2015 12:22:40PM Ji. :,Thrnt M- et Soi'v.are Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 2B, Liquid Effluents

-Continuous Mode Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A. Fission and Activation Products No Nuclides Found Ci O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+00 B. Trtium No Nuclides Found Ci 0.OOE+00 0.O0E+00 O.O0E+00 0.OOE+00 O.OOE+00 C. Dissolved and Entrained Gases No Nuclides Found Ci O.OOE+00 0.0OE+00 0.00E+00 0.OOE+00 0.OOE+00 D. Gross Alpha Activity No Nuclides Found C5 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 If Not Detected, Nudide is Not Reported.

Zeroes in this table indicates that no radioactivity was present at detectable levels.User: Jim Hunt [Server]:

PSLSA134 [Database]:

NEPSOEMP Florida Power & Light, St. Lucie Power Plant 2/11/2015 13:35 Page 2 of 3 Reg. Guide 1.21, Table 2B,, Liquid Effluents

-Batch Mode Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released A. Fission and Activation Products C-14 Na-24 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Zn-65 Sr-91 Zr-95 Nb-95 Nb-97 Tc-99m Ru-103 Ag-110m Sb-122 Sb-124 Sb-125 Te-12n3m Te-129m Te-132 1-130 1-131 1-132 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Ci ci ci Ci ci Ci Ci Ci Ci Ci Ci a Ci Ci C, 2.14E-02 0.OOE+00 5.89E-04 1.35E-04 0.OOE+00 1.60E-05 Q.OOE+00 1.12E-03 1.57E-03 1.50E-05 1.02E-05 4.67E-05 1.62E-G4 3.36E-04 0.OOE+00 1.70E-06 2.59E-04 0.OOE+O0 2.61E-05 1-10E-04 3.72E-G4 1.29E-04 4.65E-05 0.OOE+O0 1.OSE-04 4.99E-05 6.52E-04 O.OOE+00 7.81E-05 2.39E-05 0.OOE+00 O.OOE+00 2.17E-06 5.41E-04 2.24E-04 9.18E-06 0.QOE+0O 5.33E-06 1.13E-05 7.46E-05 0.OOE+O0 0.OOE+00 5.71E-05 1.94E-06 1.73E-05 5.40E-05 1.45E-04 1.26E-04 2.07E-06 0.OOE+O0 0.OOE+00 0.OOE+QO 1.63E-03 0.OOE+00 3.82E-05 7.18E-05 0.COE+O0 3.62E-06 0.OOE+00 6.64E-04 6.46E-04 3.54E-05 0.OOE+00 5.27E-05 1.13E-04 1-69E-04 3.28E-06 O.OOE+00 1.48E-04 0.COE+00 2.40E-05 8.85E-05 5.67E-06 0.OOE+00 O.OOE-.00 3.17E-06 0.00E+00 0.OOE+00 2.28E-02 1.87E-05 1.03E-04 1.63E-04 9.26E-D4 4.43E-06 8.82E-07 1.09E-03 5.75E-04 5.94E-05 O.OQE+00 2.68E-05 7.11iE-05 1. 11E-04 1.77E-05 0.OOE+00 9. 10E-05 2. 13E-06 7.78E-06 1.28E-04 0.OOE+O0 4.09E-05 0.OOE+O0 O.OOE+/-00 1.96E-05 0.OOE+00 Annual 4.65E-02 1.87E-05 8.08E-04 3.94E-04 9.26E-04 2.40E-05 3.05E-06 3.41E-03 3.02E-03 1.19E-04 1.02E-05 1.32E-04 3.57E-04 6.90E-04 2.10E-05 1.70E-06 5.55E-04 4.07E-06 7.52E-05 3.80E-04 5.23E-04 2.97E-04 4.86E-05 3.17E-06 1.28E-04 4.99E-05 If Not Detected, Nuclide is Not Reported.

Zeroes in this table indicates that no radioactivity was present at detectable levels.User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Florida Power & Light, St. Lucie Power Plant 2/11/2015 13:35 Page 3 of 3 Reg. Guide 1.21, Table 2B, Liquid Effluents

-Batch Mode Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released 1-133 1-134 CS-137 Cs-138 Ba-140 La-140 Total For Period Units a Ci Ci a Ci 1ST Quarter 6.70E-06 3.95E-06 3.03E-05 0.OOE+00 1.37E-05 4.50E-06 2.65E-02 2ND Quarter O.OOE+O0 O.OOE+O0 1.24E-05 O.OOE+O0 O.OOE+O0 O.OOE+00 2.04E-03 3RD Quarter Q.00E+O0 0.00E+00 1.05E-05 0.OOE+00 O.00E+00 1.05E-05 3.72E-03 4TH Quarter 2.87E-05 O.OOE+00 7.16E-06 1.49E-04 4.21E-06 0.OOE+00 2.65E-02 Annual 3.54E-05 3.95E-06 6.04E-05 1.49E-04 1.79E-05 1.50E-05 5-88E-02 B. Tritium H-3 1.16E+02 2.08E+01 9.87E+01 1.18E+02 3.54E+02 C. Dissolved and Entrained Gases Ar-41 Xe-131rm Xe-133m Xe-133 Xe-135 Total For Period a Ci O.OOE+OO 3.58E-03 1.45E-03 2.64E-01 0.OOE+0O 2.69 E-01 O.OCE+O0 0.OOE+00 0.OOE+00 1.62E-04 0.00E+00 1.62E-04 0.00E÷00 0.OOE+00 0.00 E+00 1.25E-05 0.OOE+00 1.25E-05 1.24E-05 0-00E+i00 0.OOE+00 6.56E-05 2.89E-06 8.08E-05 1.24E-05 3.58E-03 1.45E-03 2.64E-0 1 2.89E-06 2.69 E-O1L D. Gross Alpha Activity No Nuclides Found a 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 If Not Detected, Nuclide is Not Reported.

Zeroes in this table indicates that no radioactivity was present at detectable levels.User: 3imn Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Florida Power & Lightý St. Lucie Power Plant 2/11/2015 13:36 Page 2 of 3 Reg. Guide 1.21, Table 2B, Liquid Effluents

-Batch Mode Unit: PSL1 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Batch Mode 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Nuclides Released A. Fission and Activation Products C-14 Na-24 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Zn-65 Sr-91 Zr-95 Nb-95 Nb-97 Tc-99m Ru-103 Ag-110m Sb-122 Sb-124 Sb-125 Te-123m Te-129m Te-132 1-130 1-131 1-132 Units Ci Ci ci Ci ci C, Ci Ci ci Ci Ci ci Ci Ci C, ci 1.07E-02 0 .OOE+00 2.94E-04 6.77E-05 0.OOE+00 8.OOE-06 0.COE+0O 5.60E-04 7.85E-04-7.52E-06 5.11E-06 2.34E-05 8.09E-05 1.68E-04 0.OOE+00 8.50E-07 1.29E-04 0.OOE+0O 1.31E-05 5.48E-05 1.86E-04 6.47E-05 2.33E-05 0.OOE+00 5.39 E-05 2.50E-05 3.26E-04 0.OOE+0O 3.91E-05 1.20E-05 0.OOE+0O 0-00E+00 1.09E-06 2.70 E-04 1. 12E-04 4.59E-06 0.OOE+00 2.66E-06 5.63E-06 3.73E-05 0.OOE+00 O.OOE+00 2.86E-05 9.70E-07 8.63E-06 2.70E-05 7.25E-05 6.32E-05 1.04E-06 O.OOE+00 0.OOE+00 0.OOE+00 8.17E-04 0.OOE+O0 1.91E-05 3.59E-05 0.OOE+00 1-81E-06 O.OOE+00 3.32E-04 3.23E-04 1.77E-05 0.OOE+00 2.64E-05 5.66E-05 8.45E-05 1.64E-06 0.OOE+O0 7.39E-05 0.OOE+00 1.20E-05 4.42E-05 2.84E-06 0.OOE+00 0.OOE+00 1.59E-06 0.OOE+00 0.OOE+00 1.14E-02 9.37E-06 5. 14E-05 8.14E-05 4.63E-04 2.2-2E-06 4.41E-07 5.45E-04 2.88E-04 2.97E-05.0.OOE+00 1.34E-05 3.55E-05 5.55E-05 8.86E-06 0.OOE+O0 4.55E-05 1.07E-06 3.89E-06 6.40E-05 0.OOE+O0 2.04E-05 O.OOE+00 0.GOE+00 9.82E-06 0.00E+00 2.32E-02 9-37E-06 4.04E-04 1.97E-04 4.63E-04 1.20E-05 1.53E-06 1.71E-03 1.5 1E-03 5.95E-05 5.11E-06 6.58E-05 1.79E-04 3.45E-04 1.05E-05 8.50E-07 2.77E-04 2.04E-06 3 .76E-05 1 .90E-04 2.61E-04 1.48E-04 2.43E-05 1.59E-06 6.38E-05 2.50E-05 If Not Detected, Nuclide is Not Reported.

Zeroes in this table indicates that no radioactivity was present at detectable levels.User: Jima Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Florida Power & Light, St. Lucie Power Plant 2/11/2015 13:36 Page 3 of 3 Reg. Guide 1.21, Table 2B, Liquid Effluents

-Batch Mode Unit: PSL1 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released 1-133 1-134 CS-137 CS-138 Ba-140 La-140 Total For Period Units a Ci Ci Ci Ci Ci 1ST Quarter 3.35E-06 1.98E-06 1.52E-05 0.OOE+00 6.83E-06 2.25E-06 1.33E-02 2ND Quarter 0.00E+00 0.00E+00 6.22E-06 0.00E+00 0.OOE+00 O.OOE+00 1.02E-03 3RD Quarter 0.OOE+00 0.OOE+O0 5.24E-06 0.QOE+00 O.DOE+00 5.24E-06 1-86E-03 4TH Quarter 1.44E-05 0.OOE+00 3.58E-06 7.46E-05 2.10E-06 0.OOE+00 1.32E-02 Annual 1.77E-05 1.98E-06 3.02E-05 7.46E-05 8.94E-06 7.49E-06 2.94E-02 B. Tritium H-3 C. Dissolved and Entrained Gases a 5.78E+01 1.04E+01 4.93E+01 5.92E+01 1.77E+02 Ar-41 Xe-131m Xe-133m Xe-133 Xe-135 Total For Period ai ai Ci 0.OOE+0O 1.79E-03 7.27E-04 1.32E-01 0.QOE+00 1.34E-01 0-00E+00 0.OQE+0Q 0.OOE+00 8.10QE-05 0.OOE+0O 8.1OE-05 0.OOE+00 0.OOE+00 0.OOE+00 6.24E-06 0.OOE+0O 6.24E-06 6.19E-06 0.OOE+00 0.OOE+0O 3.28E-05 1.45E-06 4.04E-05 6.19E-06 1.79E-03 7.27E-04 1.32E-01 1.45E-06 1.35E-01 D. Gross Alpha Activity No Nudides Found Ca 0.OOE+00 0.-OE+00 0.OOE+00 O.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: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Florida Power & Light, St. Lucie Power Plant 2/11/2015 13:37 Page 2 of 3 Reg. Guide 1.21, Table 2B, Liquid Effluents

-Batch Mode Unit: PSL-2 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released A. Fission and Activation Products C-14 Na-24 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Zn-65 Sr-91 Zr-95 Nb-95 Nb-97 Tc-99m Ru-103 Ag-110m Sb-122 Sb-124 Sb-125 Te-123m Te-129m Te-132 1-130 1-131 1-132 Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter ai ci Ci Ci a Ci Ci Ci 1.07E-02 0.OOE+00 2.94E-04 6.77E-05 0.OOE+00 8.00E-06 0.OOE+00 5.60E-04 7.85E-04 7.52E-06 5.11E-06 2.34E-05 8.09E-05 1.68E-04 O.OOE+00 8.50E-07 1.29E-04 0.00E+00 1.31E-05 5.48E-05 1.86E-04 6.47E-05 2.33E-05 0.00E+00 5.39E-05 2.50E-05 3.26E-04 0.00E+00 3.91E-05 1.20E-05 0.00E+00 0.00E+00 1.09E-06 2.70E-04 1. 12E-04 4.59E-06 0.00E+00 2.66E-06 5.63E-06 3.73E-05 0.00E+00 0.OOE+00 2.86E-05 9.70E-07 8.63E-06 2.70E-05 7.25E-05 6.32E-05 1.04E-06 0.OOE+00 O.OOE+00 O.OOE+00 8.17E-04 0.00E+00 1.91E-05 3.59E-05 0.OOE+00 1.81E-06 0.00E+00 3.32E-04 3.23E-04 1.77E-05 O.OOE+00 2.64E-05 5.66E-05 8.45E-05 1.64E-06 0.OOE+00 7.39E-05 0.00E+00 1.20E-05 4.42E-05 2.84E-06 0.OOE+00 0.00E+00 1.59E-06 0.OOE+00 0.00E+00 1.14E-02 9.37E-06 5.14E-05 8.14E-05 4.63E-04 2.22E-06 4.41E-07 5.45E-04 2.88E-04 2.97E-05 O.OOE+00 1.34E-05 3.55E-05 5.55E-05 8.86E-06 0.00E+00 4.55E-05 1.07E-06 3.89E-06 6.40E-05 0.00E+00 2.04E-05 O.OOE+00 O.OOE+00 9.82E-06 O.OOE+00 Annual 2.32E-02 9.37E-06 4.04E-04 1.97E-04 4.63E-04 1.20E-05 1.53E-06 1.71E-03 1.51E-03 5.95E-05 5.11E-06 6.58E-05 1.79E-04 3.45E-04 1.05E-05 8.50E-07 2.77E-04 2.04E-06 3.76E-05 1.90E-04 2.61E-04 1.48E-04 2.43E-05 1.59E-06 6.38E-05 2.50E-05 If Not Detected, Nuclide is Not Reported.

Zeroes in this table indicates that no radioactivity was present at detectable levels.User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Florida Power & Ught, St. Lucie Power Plant 2/11/2015 13:37 Page 3 of 3 Reg. Guide 1.21, Table 28, Liquid Effluents

-Batch Mode Unit: PSL2 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Batch Mode Nuclides Released 1-133 1-134 Cs-137 Cs-138 Ba-140 La-140 Total For Period Units Ci Ci Ci ci 1ST Quarter 3.35E-06 1.98E-06 1.52E-05 O.OOE+00 6.83E-06 2.25E-06 1.33E-02 2ND Quarter 0.OOE+00 O.OOE+00 6.22E-06 O.OOE+00 0.OOE+00 0.OOE+00 1.02E-03 3RD Quarter 0.OOE+00 0.OOE+00 5.24E-06 0.00E+00 0.OOE+00 5.24E-06 1.86E-03 4TH Quarter 1.44E-05 0.OOE+00 3.58E-06 7.46E-05 2.10E-06 0.OOE+00 1.32E-02 Annual 1.77E-05 1.98E-06 3.02E-05 7.46E-05 8.94E-06 7.49E-06 2.94E-02 B. Tritium H-3 C. Dissolved and Entrained Gases ci 5.78E+01 1.04E+01 4.93E+01 5.92E+01 1.77E+02 Ar-41 Xe-131m Xe-133m Xe-133 Xe-135 Total For Period Ci C, Ci Ci Ci ci 0.OOE+OO 1.79E-03 7.27E-04 1.32E-01 0.OOE+C0 1.34E-01 0.OOE+0O 0.OOE+0O 0-00E+00 8.IOE-05 0.OOE+Q0 8.10E-05 0.OOE+0O 0.OOE--00 0.OOE+00 6-24E-06 0.OOE+00 6.24E-06 6.19E-06 O.OOE+00 0.OOE+O0 3.28E-05 1.45E-06 4.04E-05 6.19E-06 1.79E-03 7.27E-04 1.32E-01 1.45E-06 1.35E-01 D. Gross Alpha Activity No Nuclides Found Ci 0.OOE+00 O.OOE+00 0.OOE+00 O.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: 3imn Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP NRC Regulatory Guide 1.21 Reports Page 1 Report Date : 2/24/2015 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2014 to 12/31/2014 Percent Cutoff: 1 Waste Stream: Resins, Filters, and Evap Bottoms (container types listed below)General Design Cask Waste Volume Curies % Error Class FtA3 MA3 Shipped (Ci)A 4.50E+02 1.27E+01 1.26E+01 +/- 25%B 0.00E+00 0.00E+00 0.00E+00 +/- 25%C 0.00E+00 0.OOE+00 0.OOE+00 +/- 25%All 4.50E+02 1.27E+01 1.26E+01 +/- 25%Waste Stream: Dry Active Waste (container types listed below )48' Sealand Overpack 20' Sealand 40' Sealand Waste Volume Curies %Error Class FtA3 MA3 Shipped (Ci)A 5.39E+04 1.53E+03 2.21E+00 +/-25%B 0.OOE+00 0.00E+00 0.OOE+00 +/-25%C 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%All 5.39E+04 1.53E+03 2.21E+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.OOE+00 0.OOE+00 0.OOE+00 +/-25%

NRC Regulatory Guide 1.21 Reports Page 2 Report Date : 2/24/2015 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2014 to 12/31/2014 Percent Cutoff: 1 Waste Stream: Other Waste (container types listed below)20' Shielded Sealand General Design Tank Waste Volume Curies % Error Class FtA3 MA3 Shipped (Ci)A 1.68E+03 4.76E+01 2.59E-01 +/-25%B 0.00E+00 0.00E+00 0.00E+00 +/-25%C 0.00E+00 0.00E+00 0.00E+00 +/-25%All 1.68E+03 4.76E+01 2.59E-01 +/-25%Waste Stream: Sum of All 4 Categories (container types listed below)48' Sealand Overpack 20' Sealand 40' Sealand General Design Cask 20' Shielded Sealand General Design Tank Waste Volume Curies % Error Class FtA3 MA3 Shipped (Ci)A 5.60E+04 1.59E+03 1.50E+01 +/-25%B 0.00E+00 0.00E+00 0.00E+00 +/-25%C 0.OOE+00 0.00E+00 0.OOE+00 +/-25%All 5.60E+04 1.59E+03 1.50E+01 +/-25%

NRC Regulatory Guide 1.21 Reports Page 3 Report Date : 2/24/2015 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2014 to 12/31/2014 Number of Shipments Mode of Transportation Destination 1 CAST Transportation EnergySolutions Bear Creek 14 Hittman Transport (TN) EnergySolutions Bear Creek 12 Landstar EnergySolutions Bear Creek 2 Southern Pines Trucking EnergySolutions Bear Creek 1 Tri-State Motor Transit EnergySolutions Bear Creek 2 Hittman Transport (SC) EnergySolutions LLC.1 Hittman Transport (TN) EnergySolutions LLC.

NRC Regulatory Guide 1.21 Reports Page 4 Report Date 2/24/2015 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2014 to 12/31/2014 Percent Cutoff: 1 Resins, Filters, and Evap Bottoms Waste Class A Nuclide Name Percent Abundance Curies H-3 42.732% 5.37E+00 C-14 2.198% 2.76E-01 Mn-54 1.366% 1.72E-01 Fe-55 15.019% 1.89E+00 Co-58 10.761% 1.35E+00 Co-60 10.228% 1.29E+00 Ni-63 13.734% 1.73E+00 Sb-125 1.633% 2.05E-01 Resins, Filters, and Evap Bottoms Waste Class All Nuclide Name Percent Abundance Curies H-3 42.732% 5.37E+00 C-14 2.198% 2.76E-01 Mn-54 1.366% 1.72E-01 Fe-55 15.019% 1.89E+00 Co-58 10.761% 1.35E+00 Co-60 10.228% 1.29E+00 Ni-63 13.734% 1.73E+00 Sb-125 1.633% 2.05E-01 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 47.773% 1.06E+00 Cr-51 2.328% 5.14E-02 Fe-55 17.590% 3.89E-01 Co-58 2.531% 5.59E-02 Co-60 10.029% 2.22E-01 Ni-63 6.918% 1.53E-01 Zr-95 2.432% 5.37E-02 Nb-95 4.289% 9.47E-02 Ag-11Om 3.606% 7.97E-02 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 47.773% 1.06E+00 Cr-51 2.328% 5.14E-02 Fe-55 17.590% 3.89E-01 Co-58 2.531% 5.59E-02 Co-60 10.029% 2.22E-01 Ni-63 6.918% 1.53E-01 Zr-95 2.432% 5.37E-02 Nb-95 4.289% 9.47E-02 Ag-110m 3.606% 7.97E-02 NRC Regulatory Guide 1.21 Reports Page 5 Report Date: 2/24/2015 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2014 to 12/31/2014 Percent Cutoff: 1 Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 9.984% 2.58E-02 Cr-51 4.612% 1,19E-02 Mn-54 1.339% 3.47E-03 Fe-55 29.497% 7.64E-02 Co-58 4.540% 1.18E-02 Co-60 16.773% 4.34E-02 Ni-63 11.539% 2.99E-02 Zr-95 4.395% 1.14E-02 Nb-95 8.226% 2.13E-02 Ag-110m 6.144% 1.59E-02 Other Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 9.984% 2.58E-02 Cr-51 4.612% 1.19E-02 Mn-54 1.339% 3.47E-03 Fe-55 29.497% 7.64E-02 Co-58 4.540% 1.18E-02 Co-60 16.773% 4.34E-02 Ni-63 11.539% 2.99E-02 Zr-95 4.395% 1.14E-02 Nb-95 8.226% 2.13E-02 Ag-110m 6.144% 1.59E-02 Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 42.909% 6.45E+00 C-14 1.901% 2.86E-01 Mn-54 1.281% 1.93E-01 Fe-55 15.646% 2.35E+00 Co-58 9.445% 1.42E+00 Co-60 10.312% 1.55E+00 Ni-63 12.695% 1.91E+00 Sb-125 1.455% 2.19E-01 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies H-3 42.909% 6.45E+00 C-14 1.901% 2.86E-01 Mn-54 1,281% 1.93E-01 Fe-55 15.646% 2.35E+00 Co-58 9.445% 1.42E+00 Co-60 10.312% 1.55E+00 Ni-63 12.695% 1.91E+00 Sb-125 1.455% 2.19E-01 NRC Regulatory Guide 1.21 Reports Page 6 Report Date: 2/24/2015 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2014 to 12/31/2014 Manifest Number Date Shipped Waste Volume Used Burial volume Used FPL/PSL 14-112 10/10/2014 Yes FPL/PSL 14-108 9/22/2014 Yes FPL/PSL 14-106 9/17/2014 Yes FPL/PSL 14-107 9/15/2014 Yes FPL/PSL 14-104 9/10/2014 Yes FPL/PSL 14-102 9/8/2014 Yes FPUPSL 14-103 9/8/2014 Yes FPUPSL 14-095 9/3/2014 Yes FPL/PSL 14-096 9/3/2014 Yes FPL/PSL 14-098 9/3/2014 Yes FPL/PSL 14-097 9/3/2014 Yes FPL/PSL 14-094 8/27/2014 Yes FPL/PSL 14-093 8/27/2014 Yes FPL/PSL 14-088 8/11/2014 Yes FPLIPSL 14-089 8/11/2014 Yes FPUPSL 14-084 8/6/2014 Yes FPUPSL 14-083 8/6/2014 Yes FPL/PSL 14-082 8/4/2014 Yes FPUPSL 14-081 8/4/2014 Yes FPL/PSL 14-077 7/28/2014 Yes FPL/PSL 14-078 7/28/2014 Yes FPL/PSL 14-075 7/23/2014 Yes FPL/PSL 14-074 7/21/2014 Yes FPL/PSL 14-073 7/21/2014 Yes FPL/PSL 14-070 7/16/2014 Yes FPL/PSL 14-071 7/16/2014 Yes FPL/PSL 14-069 7/14/2014 Yes FPL/PSL 14-068 7/14/2014 Yes FPL/PSL 14-067 7/9/2014 Yes FPL/PSL 14-066 7/9/2014 Yes FPL/PSL 14-064 7/9/2014 Yes FPL/PSL 14-058 5/28/2014 Yes FPL/PSL 14-038 3/28/2014 Yes Effluent NIM~zet~l a-r Page 1 of 1 Wednesday, February 11, 2015 1:46:04PM Florida Power & Light St Lucie Power Plant Reg. Guide 1.21, App B, Sec E3 -Doses due to Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014 Organ Dose Bone Limit Percent of Limit Units mRem mRem 1ST Quarter 1.60E-01 2ND Quarter 1.67E-01 3RD Quarter 1.83E-01 4TH Quarter Annual 1.88E-01 6.99E-01 Liver mRem 1.61E-01 1.68E-01 1.90E-01 1.91E-01 7.10E-01 Limit mRem Percent of Limit %Total Body mRem 1.61E-01 1.68E-01 1.90E-01 1.91E-01 7.10E-01 limit mRem Percent of Limit %Thyroid mRem 4.07E-01 1.69E-01 1.90E-01 1.91E-01 9.57E-01 Limit mRem Percent of Limit %Kidney mRem 1.96E-02 2.02E-02 2.46E-02 2.36E-02 8.80E-02 Limit mRem Percent of Limit %Lung mRem 1.61E-01 1.68E-01 1.90E-01 1.91E-01 7.09E-01 Limit mRem Percent of Limit %GI-Ui mRem 1.61E-01 1.68E-01 1.90E-01 1.91E-01 7.09E-01 Limit mRem Percent of Limit %User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Gas Status Summary Report Wednesday, February 11, 2015 15,23 Page 14 of 15 Period: Ann, 2014 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 NW Site Boundary -In Infant 6.985E-01 7.100E-01 7.096E-01 9.572E-01 8.804E-02 7.091E-01 7.092E-01 O.OOOE+0O WNW Site Boundary -I Infant 5.970E-06 5.970E-06 5.970E-06 5.970E-06 5.970E-06 5.970E-06 5.970E-06 O.OOOE+0O Maximum Doserate by Organ: 6.985E-01 7.100E-01 7.096E-01 9.572E-01 8.804E-02 7.091E-01 7.092E-01 O.OOOE+00 Maximum Organ Doserate (mRem/yr):

9.572E-01 Maximum Total Body Doserate (mRem/yr):

7.096E-01 Site Boundary NG Doserate Summary Gas Receptor Location Gamma (mRadlyr)

Beta (mRad/yr)

Total Body (mRemlyr)

Skin (mRem/yr)NW Site Boundary 3.616E-03 2.059E-03 3.404E-03 5.219E-03 WNW Site Boundary 3.115E-03 1.774E-03 2.932E-03 4.496E-03 Maximum NG Dose Rate: 3.616E-03 2.059E-03 3.404E-03 5.219E-03 User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP ENN-L Effluient M~uu~emcmn Sofmwae Page I of 1 Wednesday, February 11, 2015 3:33:17PM Florida Power & Light St Lucie Power Plant Reg. Guide 1.21, App B, Sec E3 -Doses due to Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: PSL1 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Organ Dose Bone Limit Units mRem mRern 1ST Quarter 9.55E-02 2ND Quarter 9.62E-02 3RD Quarter 9.70E-02 4TH Quarter Annual 9.78E-02 3.86E-01 Percent of Limit %Liver mRem 9.54E-02 9.70E-02 1.04E-01 9.92E-02 3.95E-01 Limit mRem Percent of Limit %Total Body mRem 9.54E-02 9.70E-02 1.04E-01 9.92E-02 3.95E-01 Limit mRem Percent of Limit %Thyroid mRem 9.57E-02 9.73E-02 1.04E-01 9.92E-02 3.96E-01 Limit mRem Percent of Limit %Kidney mRem 1.13E-02 1.18E-02 1.44E-02 1.23E-02 4.97E-02 Limit mRem Percent of Limit %Lung mRem 9.54E-02 9.70E-02 1.04E-01 9.92E-02 3.95E-01 Limit mRem Percent of Limit %GI-Ui mRem 9.54E-02 9.70E-02 1.04E-01 9.92E-02 3.95E-01 Limit mRem Percent of Limit %User: lim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Gas Status Summary Report Wednesday, February 11, 2015 14:50 Page 8 of 9 Period: Ann, 2014 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 G1-Lli Skin NW Site Boundary -In Infant 3.865E-01 3.952E-01 3.952E-01 3.959E-01 4.975E-02 3.952E-01 3.952E-01 0.OOOE+00 WNW Site Boundary -I Infant 3.297E-07 3.297E-07 3.297E-07 3.297E-07 3.297E-07 3.297E-07 3.297E-07 0.OOOE+00 Maximum Doserate by Organ: 3.865E-01 3.952E-01 3.952E-01 3.959E-01 4.975E-02 3.952E-01 3.952E-0I O.OOE+00 Maximum Organ Doserate (mRem/yr):

3.959E-01 Maximum Total Body Doserate (mRem/yr):

3.952E-01 Site Boundary NG Doserate Summary Gas Receptor Location Gamma (mRad/yr), Beta (mRad/yr)

Total Body (mRem/yr)

Skin (mRem/yr)NW Site Boundary 7.857E-04 2.816E-04 7.466E-04 1.093E-03 WNW Site Boundary 6.768E-04 2.426E-04 6.432E-04 9.412E-04 Maximum NG Dose Rate: 7.857E-04 2.816E-04 7.466E-04 1.093E-03 User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP I. Effluent MNt=,enetn Sofmvrc Page 1 of 1 Wednesday, February 11, 2015 3:33:37PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, App B, Sec E3 -Doses due to Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: PSL2 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Organ Dose Bone Limit Percent of Limit Units mRem mRem 1ST Quarter 6.49E-02 2ND Quarter 7.09E-02 3RD Quarter 8.62E-02 4TH Quarter 9.01E-02 Annual 3.12E-01 Liver mRem 6.61E-02 7.09E-02 8.62E-02 9.16E-02 3.15E-01 Limit mRem Percent of Limit %Total Body mRem 6.57E-02 7.09E-02 8.62E-02 9.16E-02 3.14E-01 Limit mRem Percent of Limit %Thyroid mRem 3.11E-01 7.16E-02 8.62E-02 9.19E-02 5.61E-01 Limit mRem Percent of Limit %Kidney mRern 8.29E-03 8.40E-03 1.03E-02 1.14E-02 3.83E-02 Limit mRemn Percent of Limit %Lung mRem 6.53E-02 7.OSE-02 8.62E-02 9.16E-02 3.14E-01 Limit mRem Percent of Limit %GI-Ui mRem 6.53E-02 7.08E-02 8.62E-02 9.16E-02 3.14E-01 Umit mRem Percent of Limit %User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Gas Status Summary Report Wednesday, February 11, 2015 14,51 Page 8 of 9 Period: Ann, 2014 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-LUi Skin NW Site Boundary -In Infant 3.121E-01 3.147E-01 3.144E-01 5.613E-01 3.829E-02 3.139E-01 3.140E-01 O.OOOE+00 WNW Site Boundary -I Infant 5.641E-06 5.641E-06 5.641E-06 5.641E-06 5.641E-06 5.641E-06 5.641E-06 O.OOOE+00 Maximum Doserate by Organ: 3.121E-01 3.147E-01 3.144E-01 5.613E-01 3.829E-02 3.139E-01 3.140E-01 O.OOOE+00 Maximum Organ Doserate (mRem/yr):

5.613E-01 Maximum Total Body Doserate (mRem/yr):

3.144E-01 Site Boundary NG Doserate Summary Gas Receptor Location Gamma (mRad/yr)

Beta (mRad/yr)

Total Body (mRem/yr)

Skin (mRem/yr)NW Site Boundary 2.830E-03 1.777E-03 2.657E-03 4.127E-03 WNW Site Boundary 2.438E-03 1.531E-03 2.289E-03 3.555E-03 Maximum NG Dose Rate: 2.830E-03 1.777E-03 2.657E-03 4.127E-03 User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP H-lEMS Page 1 of 1 Wednesday, February 11, 2015 1:51:13PM Florida Power & Light St. Lude Power Plant Reg. Guide 1.21, App B, Sec E2 -Air Doses Due To Gaseous Releases Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014 NG Dose Gamma Air Limit Percent of Limit Units mRad mRad 1ST Quarter 5.99E-04 2ND Quarter 3.47E-04 3RD Quarter 2.28E-03 4TH Quarter Annual 3.94E-04 3.62E-03 Beta Air mRad 9.49E-04 1-39E-04 8.26E-04 1.46E-04 2.06E-03 Limit mRad Percent of Limit %NG Total Body mRem 5.37E-04 3.30E-04 2.16E-03 3.74E-04 3.40E-03 Limit mRem Percent of Limit %NG Skin mRem 1.01E-03 4.93E-04 3.17E-03 5.49E-04 5.22E-03 Limit mRem Percent of Limit %User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Efflue-i twuc~ t Sdiuvi Page 1 of 1 Wednesday, February 11, 2015 1:52:24PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, App B, Sec E2 -Air Doses Due To Gaseous Releases Unit: PSL1 Starting:

1-Jan-2014 Ending: 31-Dec-2014 NG Dose Gamma Air Limit Percent of Limit Units mRad mRad 1ST Quarter 2.05E-04 2ND Quarter 2.31E-04 3RD Quarter 1.50E-04 4TH Quarter 2.O0E-04 Annual 7.86E-04 Beta Air mRad 7.24E-05 8.29E-05 5.43E-05 7.20E-05 2.82E-04 Limit mRad Percent of Limit %NG Total Body mRem 1.95E-04 2.19E-04 1.42E-04 1.90E-04 7.47E-04 Limit mRem Percent of Limit %NG Skin mRem 2.85E-04 3.21E-04 2.08E-04 2.78E-04 1.09E-03 Limit mRem Percent of Limit 0 User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP i.1 Fffluent M -,n~c~tnc Sofmwre Page 1 of 1 Wednesday, February 11, 2015 1:51:51PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, App B, Sec E2 -Air Doses Due To Gaseous Releases Unit: PSL2 Starting:

1-Jan-2014 Ending: 31-Dec-2014 NG Dose Gamma Air Limit Percent of Limit Units mRad mRad 1ST Quarter 3.94E-04 2ND Quarter 1-17E-04 3RD Quarter 2.13E-03 4TH Quarter Annual 1.93E-04 2.83E-03 Beta Air mRad 8.76E-04 5.57E-05 7.71E-04 7.37E-05 1.78E-03 Limit mRad Percent of Limit %NG Total Body mRem 3.42E-04 1.11E-04 2.02E-03 1.84E-04 2.66E-03 Limit mRem Percent of Limit %NG Skin mRem 7.23E-04 1.72E-04 2.96E-03 2.70E-04 4.13E-03 Limit mRem Percent of Limit %User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP 7" "" iiflE* .N4 Page 1 of I Wednesday, February 11, 2015 2:46:57PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, App B, Sec El -Doses to a member of the public due to Liquid Releases Unit: Site Starting:

1-Jan-2014 Ending: 31-Dec-2014 Ogan Dose Bone Limit Percent of Limit Units mRem mRem 1ST Quarter 1.81E-03 2ND Quarter 6.54E-05 3RD Quarter 1.60E-04 4TH Quarter 2.74E-03 Annual 4.38E-03 Liver mRem 2.31E-03 2.05E-04 7.07E-04 8.48E-03 1.15E-02 Limit mRem Percent of Limit 0 Total Body mRem 2.38E-03 1.84E-04 6.02E-04 3.55E-03 6.41E-03 Limit mRem Percent of Limit 0 Thyroid mRem 2.39E-03 1.27E-04 4.37E-04 1.94E-03 4.86E-03 Limit mRem Percent of Limit %Kidney mRem 1.73E-03 1.92E-04 6.69E-04 1.71E-03 4.31E-03 Limit mRem Percent of Limit %Lung mRem 2.20E-03 1.42E-04 4.64E-04 9.09E-03 1.16E-02 Limit mRem Percent of Limit %GI-UI mRem 9.29E-03 1.O1E-03 3.90E-03 6.76E-03 2.10E-02 Limit mRem Percent of Limit %User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Liquid Status Summary Report Wednesday, February 11, 2015 14:50 Page 6 of 6 Period: Ann, 2014 SitelUnitlDischarge Point: Site Liquid Dose Summary -Note: All Doses in mRem Receptor Aaclgroup Bone Liver Total Body Thyroid Kidney Lung GI-Lli Skin Liquid Receptor -Teenager Teenager 4.383E-03 1.146E-02 6.411E-03 4.278E-03 4.305E-03 1.159E-02 2.095E-02 O.OOOE+00 Liquid Recptor -Child Child 4.233E-03 7.936E-03 5.848E-03 4.860E-03 1.872E-03 7.938E-03 1.130E-02 0.000E+00 Maximum Dose by Organ: 4.383E-03 1.146E-02 6.411E-03 4.860E-03 4-305E-03 1.159E-02 2.095E-02 O.OOOE+O0 Maximum Organ Dose (mRem): Maximum Total Body Dose (mRem): 2.095E-02 6.411E-03 User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP

-.~ jiEMNS Effluent.u gMen't2~l Sofmc~.r Page 1 of 1 Wednesday, February 11, 2015 2:46:15PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, App B, Sec El -Doses to a member of the public due to Liquid Releases Unit: PSL1 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Ogan Dose Bone limit Percent of Limit Units mRem mRern 1ST Quarter 9.03E-04 2ND Quarter 3.27E-05 3RD Quarter 8.01E-05 4TH Quarter Annual 1.37E-03 2.19E-03 Liver mRem 1.15E-03 1.03E-04 3.53E-04 4.24E-03 5.73E-03 Limit mRem Percent of Limit %Total Body mRem 1.19E-03 9.21E-05 3.01E-04 1.78E-03 3.21E-03 Limit mRem Percent of Limit %Thyroid mRem 1.20E-03 6.33E-05 2.18E-04 9.71E-04 2.43E-03 Limit mRem Percent of Limit %Kidney mRem 8.67E-04 9.60E-05 3.35E-04 8.55E-04 2.15E-03 Limit mRem Percent of Limit %Lung mRem 1.1OE-03 7.08E-05 2.32E-04 4.54E-03 5.79E-03 Limit mRem Percent of Limit %GI-Uli mRern 4.64E-03 5.04E-04 1.95E-03 3.38E-03 1.05E-02 Limit mRern Percent of Limit %User. Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Liquid Status Summary Report Wednesday, February 11, 201S ISA1 Page 6 of 6 Period: Ann, 2014 Site/Unit/Discharge Point: PSLI Liquid Dose Summary -Note: All Doses in mRem Receptor Agegroup Bone Liver Total Body Thyroid Kidney Lung GI-LIi Skin Liquid Receptor -Teenager Teenager 2.192E--03 5.731E-03 3.205E-03 2.139E-03 2.153E-03 5.795E-03 1.048E-02 O.OOE+DO Liquid Recptor -Child Child 2.116E-03 3.968E-03 2.924E-03 2.430E-03 9.361E-04 3.969E-03 5.648E-03 O.OOOE+00 Maximum Dose by Organ: 2.192E-03 5.731E-03 3.205E-03 2.430E-03 2.153E-03 5.795E-03 1.048E-02 0.000E+00 Maximum Organ Dose (mRem): Maximum Total Body Dose (mRem): 1.048E-02 3.205E-03 User: Jim Hunt sServer]:

PSLSA134 [Database]:

NEPSOEMP Effluent Mina.zeen~az Sofm%-rte Page 1 of 1 Wednesday, February 11, 2015 2:46:40PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, App B, Sec El -Doses to a member of the public due to Liquid Releases Unit: PSI2 Starting:

1-Jan-2014 Ending: 31-Dec-2014 Ogan Dose Bone Limit Percent of Limit Units mRem mRem 1ST Quarter 9.03E-04 2ND Quarter 3.27E-05 3RD Quarter 8.O1E-05 4TH Quarter Annual 1.37E-03 2.19E-03 Liver mRem 1.15E-03 1.03E-04 3.53E-04 4.24E-03 5.73E-03 Limit mRem Percent of Limit %Total Body mRem 1.19E-03 9.21E-05 3.01E-04 1.78E-03 3.21E-03 Limit mRem Percent of Limit %Thyroid mRem 1.20E-03 6.33E-05 2.18E-04 9.71E-04 2.43E-03 Limit mRem Percent of Limit %Kidney mRem 8.67E-04 9.60E-05 3.35E-04 8.55E-04 2.15E-03 Limit mRem Percent of Limit %Lung mRemn 1.10E-03 7.08E-05 2.32E-04 4.54E-03 5.79E-03 Limit mRem Percent of Limit %GI-Lli mRem 4.64E-03 5.04E-04 1.95E-03 3.38E-03 1.05E-02 Limit mRem Percent of Limit %User: Jim Hunt[Server]:

PSLSA134 [Database]:

NEPSOEMP Liquid Status Summary Report Wednesday, February 11, 2015 15:42 Page 6 of 6 Period: Ann, 2014 Site/Unit/Discharge Point: PSL2 Liquid Dose Summary -Note: All Doses in mRem Receptor AcegrouR Bone Liver Total Body Thyroid Kidney LunS GI-Lli Skin Uquid Receptor -Teenager Teenager 2-192E-03 5.731E-03 3.205E-03 2.139E-03 2.1S3E-03 5.79SE-03 1.048E-02 O.OOOE+00 Uquid Recptor -Child Child 2.116E-03 3.968E-03 2.924E-03 2.430E-03 9.361E-04 3.969E-03 5.648E-03 O.OOOE+00 Maximum Dose by Organ: 2.192E-03 5.731E-03 3.205E-03 2.430E-03 2.153E-03 5.795E-03 1.048E-02 O.OOOE+00 Maximum Organ Dose (mRem): Maximum Total Body Dose (mRem): 1.048E-02 3.205E-03 User: Jim Hunt[Server):

PSLSA134 [Database]:

NEPSOEMP FLORIDA POWER & LIGHT COMPANY -ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2014 THROUGH DECEMBER 31, 2014 3.4 Visitor Dose 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 I mile 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 2014.VISITOR DOSE RESULTS FOR CALENDAR YEAR 2014 was: Noble Gas Dose mrad Gamma Air Dose 2.32E-03 Beta Air Dose 1.32E-03 Gas, Particulate, Iodine, Carbon Dose mrem Bone 4.82E-01 Liver 4.90E-01 Thyroid 6.61E-0 I Kidney 6.08E-02 Lung 4.89E-01 GI-LLI 4.89E-01 Total Body 4.89E-0I