Text

Annual Radioactive Effluent Release Report - 2015
	ML16081A187
Person / Time
Site:	Saint Lucie
Issue date:	02/29/2016
From:	Katzman E; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2016-037
	Download: ML16081A187 (87)
	v • d • e

0 EPLO February 29, 2016 L-20 16-037 10 CFR 50.36 10 CFR 50.36a U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 2015 Annual Radioactive Effluent Release Report Pursuant to 10 CFR 50.36a(a)(2) and Technical Specification (TS) 6.9.1.7, enclosed is the 2015 Annual Radioactive Effluent Release Report for St. Lucie Units 1 and 2. The report provides infonmation for the 12-month period beginning January 1, 2015 and ending December 31, 2015...... .

Enclosure 1 includes the Combined Annual Radioactive Effluent Release Report.

Enclosure 2 is a copy of C-200, Offsite Dose CalculationManual (ODCM), Revision 45.

Enclosure 3 is a copy of the marked up pages from Revisions 43 and 44 of the ODCM.

Enclosure 4 is a copy of 052 0025, Process ControlProgram (PCP), Revision 16.

Enclosure 5 is a copy of the marked up pages from Revisions 14 and 15 of the PCP.

Please contact us with any questions regarding this submittal.

Sincerely, q-t"S' foa &-sk Eric S. Katzman Licensing Manager St. Lucie Plant ESK/tlt Enclosures Florida Power & Light Company !

6501 S. Ocean Drive, Jensen Beach, FL 34957

ENCLOSURE 1 COMBINED AN\NUAL RADIOACTIVE EFFLUENT RELEASE REPORT (64 PAGES)

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2015 THROUGH DECEMBER 31, 2015 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 2.60Offsite 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 and Liquid Effluents 3.2 Solid Waste Storage and Shipments 3.3 Dose Assessments 3.4 Visitor Dose

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 inrad 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-13 1, 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-13 1, 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, Colunmn 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 pCi/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 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 toremo.

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 pCi/mi 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)

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-l4 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 reactor containment buildings, samples were taken of noble gas and tritium grab samples and analyzed for gamma emitting radionuclides prior to each release. The results of the analyses and the total volume of effluent released were used to determine the total amount of radioactivity released in the batch mode.

For continuous effluent release pathways, noble gas and tritium grab samples were collected and analyzed weekly for gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques, respectively. Continuous release pathways were continuously sampled using radioiodine adsorbers and particulate filters. The radioiodine adsorbers and particulate filters were analyzed weekly for gamma emitting radionuclides using gamma spectroscopy. Results of the noble gas and tritium grab samples, radioiodine adsorber and particulate filter analyses from the current week and the average effluent flow rate for the previous week were used to determine the total amount of radioactivity released in the continuous mode. The particulate filters were analyzed weekly 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 3.11l.2.6.b., a summary of hourly meteorological data, collected during 2015, is retained onsite.

This data is available for review by the NRC upon request. During 2015, 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 2015 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 2015 for Unit 1 was 10.37 Ci, and the total amount of C-14 released in 2015 for Unit 2 was 9.47 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 West direction from the plant would have received a total combined "Bone Dose", from C-14, of 1.5 1E-1 tore!Oyr.

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 Walton Rocks Beach Recreation Area located 1 mile southeast of the site. Dose to the visitor on site for calendar year 2015 is found to be 1.13E-01 mrem/yr, Total Body dose. See Table 3.4, Dose Assessments, for more detail.

This is a fraction of the 1 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-l 4 dose calculations are based on Regulatory Guide 1.109 values.

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.

Event #1 - One abnormal (unplanned) gas decay tank discharge from the site occurred on April 17, 2015. Operations entered l-AOP-06.04, Uncontrolled Release of Radioactive Gas, due to loss of 25 psig in a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period from the lB Gas Decay Tank (GDT). Waste Gas System Leak Search identified a leak on V06824 on the lB GDT Outlet Valve.

Chemistry sampled the lB GDT and commenced a release of the remaining contents of the lB GDT in accordance with l-NOP-06.20 and Permit G-15-155-B.

The lB GDT Unplanned Release was accounted for using a separate Abnormal Gas Decay Release Permit, G- 15-194B. AR #2041288 was generated to document the unplanned GDT release to the auxiliary building which was monitored by an operable plant vent radiation monitor on the plant vent stack. Valve V06824 was repaired, passed post maintenance testing, and subsequently returned to service. No additional leaks have been identified since its return to service.

Release Estimates Are As Follows:

Nuclide uCi/cc concentration uCi released Xe-131lm 1.98E-06 28.4 Xe-133 7.86E-05 1127 Maximum Infant Dose for NW Site Boundary:

Total Body Skin Gamma Air Beta Air (mRem) (mRem) (mRad) (mRad) 1.70E-08 4.07E-08 2.05E-08 6.17E-08 Event #2 -From June 1l, 2015 at 14:15 to June 13, 2015 at 09:26, HVS-7, HVE-15, AND HVE-17 Fuel Handling Building (FHB) Ventilation Fans were in-service without an administratively operable process radiation monitor.

On June 13, 2015 at 09:26, ODCM Section 3.3.3.10 Table 3.3-13, Fuel Storage Area Ventilation System Action 47 was identified as not being met with FHB ventilation fans, HVE-15, HVS-7, and HVE-17, in operation. FHB Vent Radiation Monitor (RM-26-12) had been previously declared inoperable as per 2-NOP-25.08, FHB Ventilation System, when HVS-6 and HVE-16A and B were removed from service for scheduled maintenance. Only HVE-15, HVS-7, and HVE-17 and not HVE-6 fans had been started and placed in-service on 6/11/15. RM-26-12 was in

service and functioning during this period, but was declared inoperable.

AR #2054024 was generated and the FHB Fans were immediately secured in accordance with procedural guidance.

RM-26-12 had been returned to service by Operations on June 11, 2015 at 11:58 following a satisfactory monthly functional. On June 11, 2015 at 16:05, RM-26-12 was sampled by Chemistry as per weekly ODCM continuous gas pennit requirements and showed no gas activity. Technical Specifications were not impacted with no recently irradiated fuel in the spent fuel pool. Chemistry was notified of the issue and fleet procedure LI-AA- 102-1001, Regulatory Reporting, was referenced for reportability requirements. Licensing determined there was no reportability requirement listed for this event. Chemistry commenced 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months compensatory grab samples as required whenever HVE- 15 and/or HVE- 17 exhaust fans were placed in-service. ODCM Action 51 for continuously collecting particulate and iodine was met during this period.

On June 24, 2015, AR #2056460 was generated "No Apparent Reason for U2 FHB Effluent Monitor Declared 00S". A corrective action was generated for Operations to delete the incorrect notes and clarify procedural guidance in 1-NOP-25.08 and 2-NOP-25.08. Procedure changes AR #2059204 and AR #2059205 were implemented and incorporated improved procedural guidance that both Unit 1 and 2 Fuel Handling Building Radiation Monitors are not out of service when FHB Ventilation (HVE- 16) exhaust fans are stopped and started.

2.2 Non-Routine Planned Discharges No non-routine planned discharges were made during the report period.

2.3 Radioactive Waste Treatment System Changes One change was made to the waste treatment system during the report period:

A new vendor supplied and supported waste processing modification was completed and placed in-service in March 2015 for improved waste water processing. The new Diversified Technologies (DTS) vendor waste processing skid was placed in-service to reduce waste resin costs, effluent release quantities, and operator burdens. The new processing skid has reduced particulate and iodine isotopic release quantities in the last three quarters of 2015 by 50%.

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.

Unit 1 Fuel Handling Building (FHB) Radiation Monitor (RM-26-4) was out of service for greater than thirty days from Oct 6, 2014 to March 25, 2015 - RM-26-4 was originally removed from service on Oct 6, 2014 at 07:45 for replacement with a new Mirion MGPI radiation monitor as per EC 277010. Applicability to the minimum channel operability requirement of the ODCM applied only at times while making releases via this pathway. A locally operable, alternate radiation monitor complying with ODCM and technical specification requirements was placed in-service when fuel handling building ventilation was placed in-service and releases via this pathway were in-progress. The new radiation monitor RM-26-4

was declared operable and placed in-service on March 25, 2015 at 11:15.

U2 Fuel Handling Building Radiation Monitor (IRM-26-12) was out of service administratively for greater than 30 days from June 11, 2015 at 14:15 until July 18, 2015 at 15:30 when HVS-6 and HVE-16 fans (Spent Fuel Pool Supply and Exhaust Fans) were out of service for maintenance.

As described in Event #2 in Section 2.1, Abnormal Releases or Abnormal Discharges, a procedure change was completed which clarified administrative procedural guidance that both Unit 1 and 2 Fuel Handling Building Radiation Monitors are not out of service when FHB Ventilation (HVE-16) fans are stopped. RM-26-12 was returned to service on July 18, 2015 when maintenance was complete and ventilation fans were returned to service.

Unit 1 Plant Vent Radiation Monitor (RM-26-1) was out of service for greater than thirty days - RM 1 was originally removed from service on May 18, 2015 at 02:25 for replacement with a new Mirion MGPI radiation monitor as per EC 277011. A locally operable, alternate radiation monitor complying with ODCM and technical specification requirements was placed in-service to monitor plant stack releases via this pathway. The new radiation monitor RSC 26-1 was declared operable and placed in-service on July 2, 2015 at 23:45.

Unit 2 Fuel Handling Building Radiation Monitor (RM-26-12) was out of service for greater than thirty days - RM 12 was originally removed from service on Nov 2, 2015 for replacement with a new like for like General Atomic radiation monitor as per EC 278372. Applicability to the minimum channel operability requirement of the ODCM applies only at times while making releases via this pathway. A locally operable, alternate radiation monitor complying with ODCM and technical specification requirements was placed in-service when fuel handling building ventilation was placed in-service and releases via this pathway were in-progress. The new radiation monitor RM-26-12 was declared operable and placed in-service on Dec 31, 2015 at 10:58.

2.60Offsite Dose Calculation Manual Changes Two revision changes were made to the St. Lucie Site ODCM during the report period.

A revision was completed in June, 2015 to incorporate changes documentcd in EC 277011 for replacement of Unit 1 Plant Vent Radiation Monitor. Incorporated changes to document that the new Unit 1 Plant Vent Mirion MGPI Radiation Monitor does not have a particulate, iodine, or mid range gas detector channel. Incorporated changes to radiation monitor channel identification.

A revision was completed in August, 2015 to incorporate improved gaseous effluent monitoring guidance for the Unit 1 and 2 containment equipment hatch as a potential effluent release pathway when open during outages.

2.7 Process Control Program Changes Two revision changes were made to the St. Lucie Site Process Control Program during the report period.

A revision was completed to update references that have been superseded or no longer used.

A revision was completed to remove procedures listed in Step 3.2.1lB and Step 3.2.1 C in a previous revision, since they are no longer used here a PSL. They are used as reference material only and identified in Step 6.2 and 6.3.

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 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 Volume of release 3/2/15 4.11E6 gallons 3/27/15 1.70E6 gallons 4/21/15 1.97E6 gallons 4/28/15 4.55E6 gallons 8/2/15 5.77E6 gallons 8/14/15 2.19E6 gallons 8/29/15 5.75E3 gallons 9/16/15 1.40E7 gallons 10/24/15 2.52E6 gallons 12/6/15 3.09E6 gallons 12/18/15 3.75E5 gallons

2.10 Groundwater Protection Program

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.

2015 St. Lucie Nuclear Plant Groundwater Protection Program Tritium Results SetnlWelI 03Jn Fb Ma5p a June Juy Ag Sept OCT NOV Dec 205 21 05 21 05 21 052015 2015 2015 2015 2015 pil pil pil pil pil pil pilpCi/I pCi/I pCi/I pCi/I pCi/I MWl.-13 I ~ g Rq~f Afl A R1i ztA~A A MW-4 369 493 520 <MDA MW-5 <MDA

<MDA <MDA <MDA MW-6 1070 1020 1110 938 910 422 MW-7 <MDA

<MDA 302 <M DA MW-15 441 374 302 <MDA MW-16 234

<MDA 382 MDA <MDA <MDA MW-17 338 1350 1620 MW-18D 1430 830 1030 1910 MW-19

<MDA <M DA <MDA <MDA MW-22D

<MDA <MDA <MDA <MDA MW-26

<MDA <MDA <MDA RW-2 406 288 362 473 RW-4 <MDA

<M DA <MDA <MDA RW-5 <M DA <MDA

<MDA <MDA MW-30 <MDA 228 <M DA <MDA MW-31 316 316 368 378 MW-32 2690 16 674 1670 1560 927 1060 792 H3 H3 NOV Dec 2015 2015 303I 4915

__Unit 2-MW001 <MDA 72 357

__Unit 2-MW001 Unit 2-MW002 MD1S0 1800 46 330 4320 iS50 654

2015 St. Lucie Nuclear Plant Groundwater Protection Program Tritium Results 2015W 01 246 5 353 5 305 059 3D/ p(iI)-MW-1i/ pi/

(S)-MW-1 41 (S)-MW-35 MA<D MA<D (S)-MW-16 333<MA<DA<D (SM-AW7AM<MD (S)-MW-16 MMA<MD

3.0 TABLES 3.1 Gaseous Effluents and Liquid Effluents 3.2 Solid Waste Storage and Shipments 3.3 Dose Assessments 3.4 Visitor Dose

TABLE 3.1 GASEOUS EEFFLUENTS AND LIQURD EFFLUENTS (25 PAGES)

-~ Wednesday, February 10, 2016 11:31:04AM

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\\ .P]t ILit J~~i1VIi.J St. Lucie Power Plant Reg. Guide 1.21, Table 5A and 5B - Liquid and Gas Batch Release Summary Unit: Site Starting: 1-Jan-2015 Ending: 31-Dec-2015 A. Liquid Batch Release Totals Units 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Year Totals

1. Number of Batch Releases 28 29 25 16 98

2. Total duration of batch releases mai 1.48E+04 1.80E+04 2.42E+04 1.79E+04 7.50E+04

3. Maximum batch release duration min 1.86E+03 2.22E+03 5.81E+03 7.56E+03 7.56E+03

4. Average batch release duration min 5.29E+02 6.22E+02 9 .68E+02 1.12E+03 7.65E+02

5. Minimum batch release duration , min 2.45E+02 1.75E+02 1.30E+02 2.82E+02 1.30E+02 B. Gas Batch Release Totals Units 2nd Quarter 3rd Quarter *4th Quarter Year Totals 1st Quarter

1. Number of Batch Releases 76 75 69 50 270

2. Total duration of batch releases min 1.77E+04 1.43E+04 1.72E+04 1. 19E+04 6.10E+04

3. Maximum batch release duration min 6.60E+02 5.82E+02 7.20E+02 4.90E+02 7.20E+02

4. Average batch release duration min 2.33E+02 1 .90E+02 2.49E+02 2.37E+02 2.26E+02

5. Minimum batch release duration min 1.50E+01 4.00E+01 2.00E+01 1.50E+01 1.50E+01 User: 3im Hunt User JimHunt[Server]:

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3ruary 11, 2016 9:30:59AM ACM Thursday, FeL 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-2015 Ending: 31-Dec-2015 A. Liquid Abnormal Release Totals Units 1st Quarter 2nd Quarter 3rd Quarter 4th QIJarter Year Totals

1. Number of Abnormal Releases 0 0 0 (C 0

2. Total Activity of abnormal releases Ci 0.00E+00 0.00E+00 0.00E+00 0.00E~+00 0.00E+00 B. Gas Abnormal Release Totals Units 1st Quarter 2nd Quarter 3rd Quarter 4th QI.zarter Year Totals

1. Number of Abnormal Releases 0 1 0 C 1

2. Total Activity of abnormal releases Ci 0.00E+00 2.42E-03 0.00E+00 0.00E~+00 2.42E-03 User: Jim Hunt User JimHunt[Server]:

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(DaEM4S Page 1 of 1 Wednesday, February 10, 2016 11:33:59AM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 1A, Gaseous Effluents - Summation of All Releases Unit: Site Starting: 1-]an-2015 Ending: 31-Dec-2015 Total Release Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Uncertainty A. Fission and Activation Gases

1. Total Release Ci 2.86E+00 3.54E+0O 1.28E+01 2.09E+00 2.13E+01

2. Average Release Rate for Period uCi/s 3.68E-01 4.50E-01 1.61E+00 2.63E-01 6.75E-01

3. Percent of Limit B. Iodines and Halogens

1. Total Release 7.41E-06 3.36E-05 1.59E-04 9.64E-06 2. 10E-04

2. Average Release Rate for Period 9.53E-07 4.27E-06 2.00E-05 6.64E-06 1.21E-06

3. Percent of Limit Ci C. Particulates uCi/s

1. Total Release 6.50E-06 3.00E-05 0.00E+00 5.23E-06 4. 17E-05

2. Average Release Rate for Period 8.36E-07 3.81E-06 0.00E+00 1.32E-06 6.58E~07

3. Percent of Limit Ci D. Tritium uCi/s

1. Total Release 1.84E+01 1 .78E+01 1.73E+01 5.13E+01 1.05E+02

2. Average Release Rate for Period 2.36E+00 2.27E+00 2. 17E+00 3.32E+00 6.45E+0O

3. Percent of Limit E. Gross AlPha

1. Total Release Ci 3.35E-08 6.31E-08 4.35E-08 1.98E-07 5.78E-08 F. Carbon-14

1. Total Release Ci 5.21E+00 4.65E+00 4.99E+00 4.99E+00 1.98E+01

2. Average Release Rate for Period uCi/s 6.70E-01 5.92E-01 6.28E-01 6.28E-01 6.29E-01

3. Percent of Limit User: Jim Hunt User JimHunt[Server]:

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Page 1 of 4 UIEMS "-~~ .,~.L Wednesday, February 10, 2016 11:35:35AM 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-2015 Ending: 31-Dec-2015 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A. Fission and Activation Gases Kr-85m Ci 2.O1E-01 0.00E+00 0.00E+00 0.OOE+00 2.01E-01 Kr-88 Ci 0.00E+00 0.00E+00 9.90E-01 0.OOE+00 9.90E-01 Xe-133 Ci 0.00E+00 0.00E+00 5.65E+00 5.65E+00 0.OOE+O0 Total For Period Ci 0.OOE+O0 5.65E+00 6.84E+00 2.O1E-O1 9.90E-O1 B. Iodines and Halogens 1-131 Ci 7.41E-06 1.34E-06 9.46E-05 1. 13E-04 9.64E-06 1-133 Ci 3.23E-05 6.43E-05 9.65E-05 0.OOE+00 0.OOE+00 Total For Period Ci 3.36E-05 1.59E-04 2.10E-04 7.41E-06 9.64E-06 C. Particulates Mn-54 0.OOE+00 2.83E-07 0.00E+00 2.83E-07 Ci 0.OOE+00 Co-58 Ci 1.61E-06 2.97E-05 0.00E+00 3.13E-05 0.OOE+00 Co-60 Ci 2.98E-06 0.00E+00 0.00E+00 2.98E-06 0.OOE+00 Zr-95 Ci 0.OOE+0O 0.00E+00 0.00E+00 2.01E-06 2.O1E-06 Nb-95 Ci 0.00E+00 0.00E+00 3.22E-06 0.OOE+00 3.22E-06 Cs- 137 Ci 1.90E-06 0.00E+00 0.00E+00 1.90E-06 0.OOE+00 Total For Period Ci 3.00E-05 0.00E+00 4.17E-05 6.50E-06 5.23E-06 D. Tritium H-3 Ci 1.70E+01 1.75E+01 1 .26E+0 1 5.1OE+01 9.81E+01 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

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Florida Power & Light, St. Lucie Power Plant 2/10/2016 11:35 Page 2 of 4 Reg. Guide 1.21, Table 1B, Gaseous Effluents - Ground Level Release - Continuous Mode Unit: Site Starting: 1-Jan-2015 Ending: 31-Dec-2015 Continuous Mode Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Nuclides Released E. Gross Alpha G-Alpha Ci 3.35E-08 6.3 1E-08 4.35E-08 5.78E-08 1.98E-07 F. Carbon-14 C-14 Ci 5.21E+00 4.65E+00 4.99E+00 4.99E+00 1.98E+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

Reg. Guide 1.21, Table 1B, Gaseous Effluents - Ground Level Release - Batch Mode Unit: Site Starting: 1-Jan-2015 Ending: 31-Dec-2015 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A. Fission and Activation Gases Ar-41 Ci 2.30E+00 5.31E-01 2. 12E+00 3.27E-01 5.28E+00 Kr-85m Ci 3.73E-05 7.43E-06 0.00E+00 2.GOE-04 3.05E-04 Kr-85 Ci 2.40E-02 3.13E-01 1.90E-01 1.83E-01 7.1OE-01 Kr-87 Ci 3,35E-05 1,32E-04 0,00E+00 0.OOE+00 1.66E-04 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 2.22E-04 2.22E-04 Xe-127 Ci 0.00E+00 6.89E-05 0.00E+00 0.OOE+OO 6.89E-05 Xe- 131im Ci 0.00E+00 2.58E-02 1.65E-02 1.53E-02 5.77E-02 Xe-135 Ci 2.48E-03 3.26E-03 5.73E-02 8.42E-03 7. 15E-02 Xe- 133 m Ci 1.79E-03 1.46E-02 1,26E-03 7.30E-04 1.84E-02 Xe- 133 Ci 3.31E-01 2.65E+00 4.75E+00 5.61E-01 8.29E+00 Xe- 137 Ci 0.00E+00 4.58E-03 0.00E+00 0.OOE+00 4.58E-03 Xe-135m Ci 3.88E-04 2.66E-04 1.97E-04 1.20E-04 9.72E-04 Xe-138 Ci 4.28E-04 0.00E+00 0.00E+00 0.OOE+00 4.28E-04 Total For Period Ci 2.66E+00 3.54E+00 7. 14E+00 1.1OE+OO 1.44E+01 B. lodines and Halogens No Nuclides Found Ci 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 C. Particulates No Nuclides Found Ci 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 D. Tritium H-3 Ci 1.42E+00 2.92E-01 4.65E+00 2.72E-O1 6.63E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

User: Jim Hunt User:Jim iunt[Server]:

PSLSA134 [Database]: NEPSOEMP

Florida Power & Light, St. Lucie Power Plant 2/10/2016 11:35 Page 4 of 4 Reg. Guide 1.21, Table 1B, Gaseous Effluents - Ground Level Release - Batch Mode Unit: Site Starting: 1-Jan-2015 Ending: 31-Dec-2015 Batch Mode Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Nuclides Released E. Gross Alpha No Nuclides Found Ci 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+O0 F. Carbon-14 No Nucldes Found Ci 0.OOE+O0 0.OOE+00 0.OOE+O0 0.00E+0O 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]: PSLSA$34 [Database]: NEPSOEMP

Jpen EMS Effl1kflt vLuu4 rn~nt Softv~trL Page 1 of 1 Wednesday, February 10, 2016 11:40:48AM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 1A, Gaseous Effluents - Summation of All Releases Unit: PSL1 Starting: l-Jan-2015 Ending: 31-Dec-2015 Total Release Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Uncertainty A. Fission and Activation Gases

1. Total Release Ci 2.38E+00 1.50E-01 2.58E-01 2.35E-01 3.02E+00

2. Average Release Rate for Period uCi/s 3.06E-01 1.91E-02 3.24E-02 2.95E-02 9.59E-02

3. Percent of Limit 0/

B. Iodines and Halogens

1. Total Release Ci 6.80E-06 1.34E-06 0.00E+00 5. 18E-07 8.66E-06

2. Average Release Rate for Period uCi/s 8.74E-07 1.71E-07 0.00E+00 6.52E-08 2.75E-07

3. Percent of Limit C. Particulates

1. Total Release Ci 1.84E-06 1 .76E-05 0.00E+00 0.00E+00 1 .94E-05

2. Average Release Rate for Period uCi/s 2.36E-07 2.24E-06 0.00E+00 0.00E+00 6. 16E-07

3. Percent of Limit D. Tritium

1. Total Release Ci 6.70E+00 9.13E+00 1.45E-01 1.56E+01 3.16E+01

2. Average Release Rate for Period uCi/s 8.61E-01 1.16E+00 1.83E-02 1.97E+00 1.00E+00

3. Percent of Limit E. Gross Alpha

1. Total Release 0.00E+00 2.37E-08 2.63E-08 2.65E-08 7.65E-08 F. Carbon-14 Ci

1. Total Release 2.54E+00 2.09E+00 2.83E+00 2.91E+00 1.04E+01

2. Average Release Rate for Period uCi/s 3.26E-01 2.66E-01 3.57E-01 3.67E-01 3.29E-01

3. Percent of Limit User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

p~e EMS

.t1_E In'cuettMm.*m et SiOftv-art Wednesday, February ic'1 2016 Page 1 of 2 11:42:27AM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 1B, *Gaseous Effluents - Ground Level Release - Continuous Mode

Unit: PSL11 Starting: 1-Jan-2015 Ending: 31-Dec-2015 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A. Fission and Activation Gases Kr-85m Ci 2.O1E-01 0 .00E+00 0.OOE+00 0.OOE+00 2.O1E-01 B. Iodines and Halogens 1-131 Ci 6.80E-06 1.34E-06 O.OOE+00 5.18E-07 8.66E-06 C. Particulates Mn-54 Ci 0.OOE+00 2.83E-07 0.00E+00 0.OOE+00 2.83E-07 Co-58 Ci 0.OOE+00 1.73E-05 0.OOE+00 0.OOE+00 1.73E-05 Co-60 Ci 1.40E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.40E-06 Cs-137 Ci 4.36E-07 0.OOE+00 0.OOE+00 O.OOE+00 4.36E-07 Total For Period Ci 1.84E-06 1.76E-05 O.OOE+OO O.OOE+OO 1.94E-05 D. Tritium H-3 Ci 5.41E+00 9.11E+00 0.00E+00 1.54E+01 3.OOE+01 E. Gross Alpha Ci 0.OOE+00 2.37E-08 2.63E-08 2.65E-08 7.65E-08 FA Carbn1 F. Carbon-14 C-14 Ci 2.54E+00 2.09E+00 2.83E+00 2.91E+00 1.04E+01 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

User: Jim Hunt

Reg. Guide 1.21, Table 1B, Gaseous Effluents - Ground Level Release - Batch Mode Unit: PSL11 Starting: 1-Jan-2015 Ending: 31-Dec-2015 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A, Fission and Activation Gases Ar-41 Ci 1.93E+00 1.24E-01 1.85E-01 1.70E-01 2.41E+00 Kr-85m Ci 3.73E-05 0.00E+00 3.73E-05 0.OOE+00 0.OOE+00 Kr-85 Ci 3.11E-03 0.00E+00 3.11E-03 0.OOE+00 0.OOE+00 Kr-87 Ci 3.35E-05 0.00E+00 3.35E-05 O.OOE+00 0.OOE+00 Xe-131m Ci 0.00E+00 9.30E-05 9.30E-05 0.OOE+00 0.OOE+00 Xe-133m Ci 1.79E-03 0.00E+00 1.79E-03 0.OOE+O0 0.OOE+00 Xe-135 Ci 2.11E-03 8.60E-04 8.09E-03 2.73E-03 2.40E-03 Xe-133 Ci 2.45E-01 2.47E-02 4.01E-01 6.96E-02 6.19E-02 Xe-135m Ci 3.88E-04 1.41E-04 5.30E-04 0.OOE+00 0.OOE+00 Total For Period Ci 2. 18E+00 1.50E-01 2.82E+00 2.58E-O1. 2.35E-O1 B. Iodines and Halogens No Nuclides Found Ci 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 C. Particulates No Nuclides Found Ci 0 .00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 D, Tritium Ci 1.29E+00 2.59E-02 1.45E-01 H-3 1.86E-01 1.64E+00 E. Gross Alpha No Nuclides Found Ci O.OOE+0O 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 F. Carbon-14 No Nuclides Found Ci 0.OOE+00 0.OOE+00 0.00E+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 User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

~u i~i& EMS Mu Lkcrntfl~ Soktv~Art Page 1 of 1 Wednesday, February 10, 2016 12:09:10PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 1A, Gaseous Effluents - Summation of All Releases Unit: PSL2 Starting: 1-Jan-2015 Ending: 31-Dec-2015 Total Release Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Uncertainty A. Fission and Activation Gases

1. Total Release Ci 4.82E-01 3.39E+00 1.25E+01 1.85E+00 1.83E+01

2. Average Release Rate for Period uCi/s 6.20E-02 4.31lE-01 1.58E+00 2.33E-01 5.79E-01

3. Percent of Limit B. Iodines and Halogens

1. Total Release 6.10E-07 3.23E-05 1.59E-04 9.12E-06 2.01E-04

2. Average Release Rate for Period 7.84E-08 4. 10E-06 2.00E-05 1. 15E-06 6.37E-06

3. Percent of Limit Ci C. Particulates uCi/s

1. Total Release 4.66E-06 1.24E-05 0.00E+00 5.23E-06 2.23E-05

2. Average Release Rate for Period 5.99E-07 1.57E-06 0.00E+00 6.58E-07 7.06E-07

3. Percent of Limit Ci D. Tritium uCi/s

1. Total Release 1.17E+01 8.68E+00 1.71E+01 3. 57E+0 1 7.31E+01

2. Average Release Rate for Period %i 1.50E+00 1.10E+00 2.15E+00 4.48E+00 2.32E+00

3. Percent of Limit E. Gross Alpha Ci

1. Total Release uCi/s 3.35E-08 3.94E-08 1.72E-08 3. 13E-08 1.21E-07 F. Carbon-14

1. Total Release 2.67E+00 2.56E+00 2. 16E+00 2.08E+00 9.47E+00

2. Average Release Rate for Period 3.43E-01 3.26E-01 2.72E-01 2.62E-01 3.00E-01

3. Percent of Limit User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

~Th~1TNAC Page 1 of 4 K ~ Wednesday, February 10, 2016 12:09:34PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 1B, Gaseous Effluents - Ground Level Release - Continuous Mode Unit: PSL2 Star-ting: 1-Jan-2015 Ending: 31-Dec-2015 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A. Fission and Activation Gases Kr-88 Ci 0.00E+00 0.00E+00 O.OOE+O0 9.90E-01 9.90E-01 Xe-133 Ci 0.00E+00 0.00E+00 5.65E+00 5.65E+00 0.00E+00 Total For Period Ci O.OOE+O0 O.OOE+O0 5,65E+00 6.64E+00 9.90E-O1 B. Iodines and Halogens 1-131 Ci 6. 10E-07 0.00E+00 9.46E-05 1.04E-04 9.12E-06 1-133 Ci 0.00E+00 3.23E-05 6.43E-05 0.00E+00 9.65E-05 Total For Period Ci 6.10E-07 3.23E-05 1,59E-04 2.01E-04 9.12E-06 C. Particulates Co-58 Ci 1.61E-06 1.24E-05 O.OOE+00 0.00E+00 1 .40E-05 Co-60 Ci 1.58E-06 O.OOE+00 O.OOE+00 0.00E+00 1.58E-06 Zr-95 Ci O.OOE+00 0O.OOE+O0 O.OOE+00 2.O1E-06 2.01E-06 Nb-95 Ci O.OOE+00 O.0OE+00 3.22E-06 3.22E-06 O.OOE+00 Cs- 137 Ci 1.47E-06 O.0OE+00 0.00E+00 1.47E-06 O.OOE+O0 Total For Period Ci 4.66E-06 1. 24E-05 5.23E-06 2.23E-05 D. Tritium H-3 Ci 1.16E+O1 8.41E+00 1.26E+01 3.56E+01 6.81E+01 E. Gross Alpha G-Alpha Ci 3.35E-08 3.94E-08 1.72E-08 3.13E-08 1.21E-07 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Databasej: NEPSOEMP

Florida Power & Light, St. Lucie Power Plant 2/10/20 16 12:09 Page 2 of 4 Reg. Guide 1.21, Table iB, Gaseous Effluents - Ground Level Release - Continuous Mode Unit: PSL2 Starting: l-Jan-2015 Ending: 31-Dec-2015 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual F. Carbon-14 C-14 Ci 2.67E+00 2.56E+00 2.16E+00 2.08E+00 9.47E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

User: Jim H-unt [Server]: PSLSA134 [Database]: NEPSOEMP

Flrdowr&LghS.Lui oerPat2/10/2016 12:09 Page 3of 4 Reg. Guide 1.21, Table 1B, Gaseous Effluents - Ground Level Release - Batch Mode Unit: PSL2 Starting: 1-Jan-2015 Ending: 31-Dec-2015 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A. Fission and Activation Gases Ar-41 Ci 4.07E-01 2.87E+00 3.74E-01 1.93E+00 1.57E-01 Kr-85m Ci 7.43E-06 O.OOE+O0 2.68E-04 0.OOE+00 2.60E-04 Kr-85 Ci 3.13E-01 1.90E-01 7.07E-01 2.08E-02 1.83E-01 Kr-87 Ci 1.32E-04 O.OOE+00 1.32E-04 0.OOE+00 0.OOE+00 Kr-88 Ci O.OOE+00 O.OOE+00 2.22E-04 0.OOE+00 2.22E-04 Xe-127 Ci 6.89E-05 O.OOE+O0 6.89E-05 0.OOE+00 0.OOE+00 Xe-131m Ci 2.58E-02 1.65E-02 5.76E-02 0.OOE+00 1.53E-02 Xe- 133m Ci 1.46E-02 1.26E-03 1.66E-02 0.OOE+00 7.30E-04 Xe- 13 5 Ci 2.40E-03 5.46E-02 6.34E-02 3.69E-04 6.03E-03 Xe- 137 Ci 4.58E-03 O.OOE+00 4.58E-03 0.OOE+00 0.OOE+00 Xe- 133 Ci 2.62E+00 4.68E+00 7.89E+00 8.66E-02 4.99E-01 Xe- 13 5m Ci 1.25E-04 1.97E-04 4.42E-04 0.OOE+O0 1.20E-04 Xe- 138 Ci 4.28E-04 O.OOE+O0 O.OOE+O0 0.OOE+00 4.28E-04 Total For Period Ci 4.82E-O1 3.39E+00 6.88E+00 1.16E+01 8.62E-O1 B. Iodines and Halogens Found Ci 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 No Nuclides C. Particulates No Nuclides Found Ci 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 D. Tritium H-3 Ci 1.36E-01 2.66E-01 4.50E+00 8.60E-02 4.99E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

Florida Power & Light, St. Lucie Power Plant 2/10/2016 12:09 Page 4 of 4 Reg. Guide 1.21, Table 1B, Gaseous Effluents - Ground Level Release - Batch Mode Unit: PSL2 Starting: 1-Jan-2015 Ending: 31-Dec-2015 Batch Mode Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Ci 0.OOE+O0 0.00E+00 0.OOE+0O 0.OOE+00 0.00E+00 Found No Nuclides F. Carbon-14 No Nuclides Found Ci O.OOE+00 0.OOE+O0 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

Page 1 of 1 Qp~~ EMS K

IVLuu..,'emu2~ SckwarL Wednesday, February 101 2016 12:10:48PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 2A, Liquid Effluents - Summation of All Releases

Unit: Site Starting: 1-Jan-2015 Ending: 31-Dec-2015 Total Release Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Uncertainty A. Fission and Activation Products

1. Total Release Ci 1.22E-02 5.01E-03 6.47E-03 1.22E-03 2.49E-02

2. Average Concentration uCi/mL 1.18E-10 1.08E-11 6.0 1E-1 1 1.13E-10 4.28EKt1

3. Percent of Limit B. Tritium

1. Total Release 1.04E+02 4.36E+01 5.41E+02 2.62E+02 1.31E+02

2. Average Concentration 2.45E-06 3.85E-07 1.30E-06 2.43E-06 8.66E-07

3. Percent of Limit Ci C. Dissolved and Entrained Gases uCi/mL

1. Total Release 6.95E-03 6.86E-03 1.13E-01 7.93E-03 9.11E-02

2. Average Concentration 1.64E-10 6.07E-11 2.72E-10 7.34E-11 6.02E-10

3. Percent of Limit Ci D. Gross Alpha Activity uCi/mL

1. Total Release 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Average Concentration 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Primary Liquid Release Volume

1. Total Release Liters 2.68E+07 2.37E+07 1.59E+08 2.38E+07 8.45E+07 F. Dilution Volume

1. Total Release Liters 4.23E+10 1.13E+11 4.15E+11 1.08E+11 1.51E+11 G. Average Stream Flow

1. Total Release m^3/s 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

Page 1 of 1

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Wednesday, February 10, 2016 12:14:01PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 2A, Liquid Effluents - Summation of All Releases Unit: PSL1 Starting: 1-Jan-2015 Ending: 31-Dec-2015 Total Release Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Uncertainty A. Fission and Activation Products

1. Total Release Ci 6.11E-03 2.51E-03 3.24E-03 6.11E-04 1.25E-02

2. Average Concentration uCi/mL 1.13E-10 1.18E-10 4.28E-11 1.08E-11 6.0 1E-1 1

3. Percent of Limit B. Tritium

1. Total Release 1.31E+02 5.18E+01 6.55E+01 2.18E+01 2.70E+02

2. Average Concentration 2.43E-06 2.45E-06 8.66E-07 3.85E-07 1.30E-06

3. Percent of Limit Ci C. Dissolved and Entrained Gases uCi/mL

1. Total Release 3.97E-03 3.47E-03 4.55E-02 3.43E-03 5.64E-02

2. Average Concentration 7.34E-11 1.64E-10 6.02E-10 6.07E-11 2.72E-10

3. Percent of Limit Ci D. Gross Alpha Activity uCi/mL

1. Total Release 0.OOE÷00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Average Concentration 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Primary Liquid Release Volume

1. Total Release Liters 1.19E+07 1.34E+07 4.23E+07 1. 18E+07 7.94E+07 F. Dilution Volume

1. Total Release Liters 5.40E+10 2. 12E+ 10 7.56E+10 5.65E+10 2.07E+11 G. Average Stream Flow

1. Total Release mA3/S 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

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Page 1 of 1 Wednesday, February 10, 2016 12:14:40PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, Table 2A, Liquid Effluents - Summation of All Releases Unit: PSL2 Starting: 1-Jan-2015 Ending: 31-Dec-2015 Total Release Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Uncertainty A. Fission and Activation Products

1. Total Release Ci 6.11E-03 2.51E-03 3.24E-03 6.11E-04 1.25E-02

2. Average Concentration uCi/mL 1. 13E-10 1.18SE-10 4.28E-11 1.08E-11 6.0 1E-1 1

3. Percent of Limit B. Tritium

1. Total Release 1.31E+02 5.18E+01 6.55E+01 2.18E+01 2.70E+02

2. Average Concentration 2.43E-06 2.45E-06 8.66E-07 3.85E-07 1 .30E-06

3. Percent of Limit Ci C. Dissolved and Entrained Gases uCi/mL

1. Total Release 3.97E-03 3.47E-03 4.55E-02 3.43E-03 5.64E-02

2. Average Concentration 7.34E-11 1.64E-10 6.02E-10 6.07E-11 2.72E-10

3. Percent of Limit Ci D. Gross Alpha Activity uCi/mL

1. Total Release 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Average Concentration 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Primary Liquid Release Volume

1. Total Release Liters 1. 19E+07 1.34E+07 4.23E+07 1. 18E+07 7.94E+07 F. Dilution Volume

1. Total Release Liters 5.40E+ 10 2.12E+10 7.56E+10 5.65E+10 2.07E+11 G. Average Stream Flow

1. Total Release m^3/s 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEM P

Up~TL F Page 1 of 3 Wednesday, February 10, 2016 12:15:18PM Florida Power & Light M~n ~untn~

St. Lucie Power Plant Reg. Guide 1.21, Table 2B, Liquid Effluents - Continuous Mode Unit: Site Starting: 1-Jan-2015 Ending: 31-Dec-2015 Continuous Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A. Fission and Activation Products No Nuclides Found 0.OOE+00 0.00E+00 0.00E+00 Ci 0.OOE+0O 0.OOE+00 B. Tritium No Nuclides Found Ci 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 O.OOE+00 C. Dissolved and Entrained Gases No Nuclides Found Ci 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 D. Gross Alpha Activity No Nuclides Found Ci 0.OOE+00 0.00E+00 0.00E+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

FlrdaPwr iht t.Lce oePat2/10/2016 12:15 Page 2 of 3 Reg. Guide 1.21, Table 2B, Liquid Effluents Batch Mode -

Unit: Site Starting: l-Jan-2015 Ending: 31-Dec-2015 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A. Fission and Activation Products C-14 1.00E-02 2.26E-03 1 .89E-02 5.43E-03 1.18E-03 Na-24 O.OOE+O0 4.40E-06 4.40E-06 0.OOE+00 0.OOE+00 Be-7 1.69E-05 O.OOE+O0 1.69E-05 0.OOE+00 0.OOE+00 Cr-5i 2.06E-05 4.47E-05 6.53E-05 0.OOE+00 0.OOE+O0 Mn-54 2. 15E-05 2.43E-05 6.76E-05 2.18E-05 0.OOE+00 Fe-59 9.20E-06 O.OOE+O0 9.20E-06 0.OOE÷00 0.OOE+00 Co-58 3.08E-04 2.40E-04 7. 12E-04 1.64E-04 0.OOE+00 Co-60 4.48E-04 2.80E-04 1.02E-03 2.76E-04 1.92E-05 Zn-65 2. 18E-05 3.21E-06 3.82E-05 1.32E-05 0.OOE+00 Br-82 3.13E-06 O.OOE+O0 3.13E-06 0.OOE+00 0.OOE+00 Sr-91 3.35E-06 4.31E-06 7.66E-06 0.OOE+00 0.OOE+00 Zr-95 2. 19E-05 1.61E-05 4.24E-05 4.37E-06 0.OOE+00 Nb-95 5.14E-05 2. 19E-05 7.46E-05 1.31E-06 0.OOE+00 Nb-97 3.01E-04 4. 19E-04 1.02E-03 2.85E-04 1.27E-05 Ru-103 O.OOE+O0 O.OOE+O0 1.79E-06 0.OOE+00 1.79E-06 Ag-i110m 2.41E-04 3.59E-04 8.61E-04 2.57E-04 4.37E-06 Sn-113 8.41E-06 O.OOE+O0 8.41E-06 0.OOE+00 0.OOE+00 Sn-117m 3.62E-05 1 .20E-04 1.57E-04 1.14E-06 0.OOE+00 Sb-124 4.46E-06 1.79E-04 1 .84E-04 0.OOE+00 0.OOE+00 Sb-122 0.OOE+O0 3.57E-05 3.57E-05 0.OOE+00 0.OOE+00 Sb-125 5.30E-04 1.47E-04 6.78E-04 0.OOE+00 0.OOE+00 Te-123m 6.33E-06 9.56E-05 1 .02E-04 0.OOE+00 0.OOE+00 Te-129m O.OOE+O0 3.85E-04 3.85E-04 0.OOE+00 0.OOE+00 Te-129 O.OOE+O0 1.16E-04 1.16E-04 0.OOE+00 0.OOE+00 Te-132 4.94E-05 1 .02E-04 1.52E-04 0.OOE+00 0.OOE+00 1-130 1.72E-06 O.OOE+O0 1.72E-06 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.

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PSLSA134 [Database]: NEPSOEM P

Reg. Guide 1.21, Table 2B, Liquid Effluents - Batch Mode Unit: Site Starting: 1-Jan-2015 Ending: 31-Dec-2015 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual 1-13 1 Ci 0.00E+00 0.00E+00 2.00E-05 0.00E+00 2.00E-05 1-132 Ci 4.52E-05 1.09E-04 0.00E+00 0.00E+00 1.55E-04 1-134 Ci 0.00E+00 0,00E+00 1,45E-06 0,00E+00 1.45E-06 1-135 Ci 0.00E+00 8.26E-06 0.00E+00 0.O0E+00 8.26E-06 Cs- 137 Ci 3.26E-06 3.72E-05 o0.00E+00 0.00E+00 4.04E-05 Cs- 138 Ci 1.09E-05 0.00E+00 0.00E+00 0,00E+00 1.09E-05 La-140 Ci 3.97E-05 0.00E+00 0.00E+00 0.00E+00 3.97E-05 Total For Period Ci 1.22E-02 5,01E-03 6,47E-03 1.22E-03 2,49E-02 B. Tritium H-3 Ci 2.62E+02 1.04E+02 1.31E+02 4.36E+01 5.41E+02 C. Dissolved and Entrained Gases Kr-85 Ci 0.OOE+00 O.OOE+O0 O.OOE+O0 2.84E-03 2.84E-03 Xe-131m Ci 0.OOE+00 6.28E-05 1.15E-03 2.50E-04 1.46E-03 Xe-133m Ci 7.94E-05 2.56E-05 5.02E-04 0.OOE+00 6.07E-04 Xe- 135 Ci 1.46E-05 O.OOE+O0 1 .42E-05 0.OOE+00 2.88E-05 Xe-133- Ci 7.84E-03 6.86E-03 8.94E-02 3.77E-03 1.08E-01 Total For Period Ci 7.93E-03 6.95E-03 9.11E-02 6.86E-03 1,13E-01 D, Gross Alpha Activity No Nuclides Found Ci 0.00E+00 0O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

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PSLSA134 [Database]: NEPSOEMP

Reg. Guide 1.21, Table 2B, Liquid Effluents - Batch Mode Unit: PSL1 Starting: 1-Jan-2015 Ending: 31-Dec-2015 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A. Fission and Activation Products C-14 5.01E-03 1.13E-03 2.71E-03 9.45E-03 5.92E-04 Na-24 0.00E+00 2.20E-06 0.00E+00 2.20E-06 0.OOE+00 Be-7 8.47E-06 0.00E+00 0.00E+00 8.47E-06 0.00E+00 Cr-5i 1.03E-05 2.23E-05 0.00E+00 3.26E-05 0.OOE+00 Mn-54 1.08E-05 1.22E-05 1.09E-05 3.38E-05 0.OOE+00 Fe-59 4.60E-06 0.00E+00 0.00E+00 4.60E-06 0.OOE+00 Co-58 1.54E-04 1.20E-04 8. 18E-05 3.56E-04 0.OOE+00 Co-60 2.24E-04 1.40E-04 i.38E-04 5.11E-04 9.59E-06 Zn-65 1.09E-05 1.60E-06 6.61E-06 1.91E-05 0.OOE+00 Br-82 1.57E-06 0.00E+00 0.00E+00 1.57E-06 0.OOE+0O Sr-91 1.67E-06 2.16E-06 0.00E+00 3,83E-06 0.OOE+00 Zr-95 1 .09E-05 8.05E-06 2. 19E-06 2. 12E-05 O.OOE+00 Nb-95 2.57E-05 1.09E-05 6.54E-07 0.OOE+00 3.73E-05 Nb-97 1.51E-04 2. 10E-04 1.43E-04 6.33E-06 5.09E-04 Ru-103 0.00E+00 0.00E+00 0.00E+00 8.93E-07 8.93E-07 Ag-110m 1.21E-04 1.80E-04 1.28E-04 4.31E-04

2. 19E-06 Sn-i113 4.20E-06 0.00E+00 0.00E+00 0.OOE+00 4.20E-06 Sn-i117m 1.81E-05 5.98E-05 5.70E-07 7.85E-05 0.OOE+00 Sb-i24 2,23E-06 8.97E-05 0.00E+00 9. 19E-05 0.OOE+00 Sb-122 0.00E+00 1.79E-05 0.00E+00 0.OOE+00 1.79E-05 Sb-125 2.65E-04 7.36E-05 0.00E+00 3.39E-04 0.OOE+00 Te-123m 3. 17E-06 4.78E-05 0.00E+00 5. 10E-05 0.OOE+00 Te-129m 0.00E+00 1.93E-04 0.00E+00 0.OOE+00 1.93E-04 Te-129 0.00E+00 5.78E-05 0.00E+00 5.78E-05 0.OOE+00 Te- 132 2.47E-05 5.11iE-05 0.00E+00 0.OOE+00 7.58E-05 1-130 8.59E-07 0.00E+00 0.00E+00 0.OOE+00 8.59E-07 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

Flrd owr&LghS.Lui oerPat2/10/2016 12:17 Page 3of 3 Reg. Guide 1.21, Table 2B, Liquid Effluents - Batch Mode Unit: PSL11 Starting: 1-Jan-2015 Ending: 31-Dec-2015 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual 1-131 Ci O.OOE+O0 O.OOE+O0 9.98E-06 O.OOE+O0 9.98E-06 1-132 Ci 2.26E-05 5.47E-05 O.OOE+O0 O.OOE+O0 7.73E-05 1-134 Ci O.OOE+O0 O.OOE+O0 7.27E-07 O.OOE+O0 7.27E-07 1-135 Ci O.OOE+O0 4. 13E-06 O.OOE+O0 O.OOE+O0 4. 13E-06 Cs- 137 Ci 1.63E-06 1.86E-05 O.OOE+O0 O.OOE+O0 2.02E-05 Cs-138 Ci 5.47E-06 0.00E+00 O.OOE+00 O.OOE+O0 5.47E-06 La-140 Ci 1.99E-05 0.00E+00 O.OOE+O0 O.OOE+O0 1.99E-05 Total For Period Ci 6,11E-03 2.51E-03 3,24E-03 6.11E-04 1.25E-02 B. Tritium H-3 Ci 1.31E+02 5.18E+01 6.55E+01 2. 18E+01 2.70E+02 C. Dissolved and Entrained Gases Kr-85 Ci 0.OOE+00 0.00E+00 0.OOE+00 1.42E-03 1.42E-03 Xe- 131im Ci 3. 14E-05 1.25E-04 0.OOE+00 5.73E-04 7.30E-04 Xe- 133m Ci 1.28E-05 0.00E+00 3.97E-05 2.51E-04 3.03E-04 Xe-135 Ci 0.00E+00 0.00E+00 7.32E-06 7.08E-06 1.44E-05 Xe-133 Ci 3 .43E-03 1.89E-03 3.92E-03 4.47E-02 5.39E-02 Total For Period Ci 3,47E-03 3.43E-03 3.97E-03 4.55E-02 5.64E-02 D. Gross Alpha Activity No Nuclides Found Ci 0.00E+00 0.00E+00 O.OOE+O0 0.00E+00 0.00E+00 If Not Detected, Nuclide is Not Reported. Zeroes in this table indicates that no radioactivity was present at detectable levels.

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PSLSA134 [Database]: NEPSOEMP

Florida Power & Light, St. Lucie Power Plant Reg. Guide 1.21, Table 2B, Liquid Effluents Batch 2/10/2016

- Mode 12:18 Page2of3 Unit: PSL2 Starting: 1-Jan-2015 Ending: 31-Dec-2015 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual A. Fission and Activation Products C-14 5.01E-03 1.13E-03 2.71E-03 5.92E-04 9.45E-03 Na-24 0.00E+00 2.20E-06 0.00E+00 2.20E-06 0.OOE+00 Be-7 8.47E-06 0.00E+00 0.00E+00 8.47E-06 0.OOE+00 Cr-51 1.03E-05 2.23E-05 0.00E+00 3.26E-05 0.OOE+00 Mn-54 1.08E-05 1.22E-05 1.09E-05 3.38E-05 0.OOE+00 Fe-59 4.60E-06 0.00E+00 0.00E+00 4.60E-06 0.OOE+00 Co-58 1 .54E-04 1.20E-04 8. 18E-05 3.56E-04 0.OOE+00 Co-60 2.24E-04 1.40E-04 1.38E-04 5.11E-04 9.59E-06 Zn-65 1.09E-05 1.60E-06 6.61E-06 1.91E-05 0.OOE+00 Br-82 1 .57E-06 0.00E+00 0.00E+00 1.57E-06 0.OOE+00 Sr-91 1.67E-06 2. 16E-06 0.00E+00 3.83E-06 0.OOE+00 Zr-95 1.09E-05 8.05E-06 2. 19E-06 2. 12E-05 0.OOE+00 Nb-95 2.57E-05 1.09E-05 6.54E-07 3.73E-05 0.OOE+00 Nb-97 1.51E-04 2. 10E-04 1.43E-04 5.09E-04 6.33E-06 Ru-103 0.00E+00 0.00E+00 0.00E+00 8.93E-07 8.93E-07 Ag-i1l0i 1.21E-04 1.80E-04 1.28E-04 4.31E-04 2.19E-06 Sn-113 4.20E-06 0.00E+00 0.00E+00 4.20E-06 0.OOE+00 Sn-117m 1.81E-05 5.98E-05 5.70E-07 7.85E-05 0.OOE+00 Sb-124 2.23E-06 8.97E-05 0.00E+00 9.19E-05 0.OOE+00 Sb-122 0.00E+00 1.79E-05 0.00E+00 1.79E-05 0.OOE+00 Sb-125 2.65E-04 7.36E-05 0.00E+00 3.39E-04 0.OOE+00 Te-123m 3.17E-06 4.78E-05 0.00E+00 0.OOE+00 5.10OE-05 Te-129m 0.00E+00 1.93E-04 0.00E+00 1.93E-04 0.OOE+00 Te-129 0.00E+00 5.78E-05 0.00E+00 0.OOE+00 5.78E-05 Te- 132 2.47E-05 5.11E-05 0.00E+00 7.58E-05 0.OOE+00 1-130 8.59E-07 0.00E+00 0.00E+00 8.59E-07 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 User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEM P

Reg. Guide 1.21, Table 2B, Liquid Effluents - Batch Mode Unit: PSL2 Starting: 1-Jan-2015 Ending: 31-Dec-2015 Batch Mode Nuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual 1-131 Ci O.OOE+O0 O.OOE+O0 9.98E-06 O.OOE+O0 9.98E-06 1-132 Ci 2.26E-05 5.47E-05 O.OOE+O0 O.OOE+O0 7.73E-05 1-134 Ci O.OOE+00 O.OOE+O0 7.27E-07 O.OOE+O0 7.27E-07 1-135 Ci O.OOE+00 4.13E-06 0O.OOE+O0 O.OOE+O0 4.13E-06 Cs-137 Ci 1.63E-06 1.86E-05 O.OOE+00 O.OOE+O0 2.02E-05 Cs-138 Ci 5.47E-06 O.OOE+O0 O.OOE+O0 0.OOE+O0 5.47E-06 La-140 Ci 1.99E-05 O.OOE+O0 O.OOE+O0 O.OOE+O0 1.99E-05 Total For Period Ci 6.11E-03 2.51E-03 3,24E-03 6.11E-04 1.25E-02 B. Tritium H-3 Ci 1.31E+02 5.18E+01 6.55E+01 2.18E+01 2.70E+02 C. Dissolved and Entrained Gases Kr-85 Ci 0.OOE+00 0.OOE+00 0.OOE+00 1.42E-03 1.42E-03 Xe-131m Ci 0.OOE+00 3.14E-05 5.73E-04 1.25E-04 7.30E-04 Xe-135 Ci 7.32E-06 0.OOE+00 7.08E-06 0.00E+00 1.44E-05 Xe-133m Ci 3.97E-05 1.28E-05 2.51E-04 0.OOE+00 3.03E-04 Xe- 133 Ci 3.92E-03 3.43E-03 4.47E-02 1.89E-03 5.39E-02 Total For Period Ci 3.97E-03 3.47E-03 4.55E-02 3.43E-03 5.64E-02 D. Gross Alpha Activity No Nuclides Found Ci O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+O0 O.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 User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

TABLE 3.2 SOLID WASTE STORAGE AND SHIPMENTS (6 PAGES)

NRC Regulatory Guide 1.21 Reports Page 1 Report Date:* 2/8/2016 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2015 to 12/31/2015 Percent Cutoff: 1 Waste Stream : Resins, Filters, and Evap Bottoms Waste Volume Curies % Error Class Ft^3 M^3 Shipped (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +1-25%

B 0.00E+00 0.00E+00 0.00E+00 +/- 25%

C 0.00E+00 0.00E+00 0.00E+00 +/- 25%

All 0.00E+00 0.00E+00 0.O0E+00 +1-25%

Waste Stream : Dry Active Waste DAW 48' Overpack DAW 20' Sealand DAW 40' Sealand IP-1 Bag Waste Volume Curies %Error Class Ft^3 MA3 Shipped (Ci)

A 5.70E+04 1.61E+03 1.13E+00 +/-25%

B 0.00E+t00 0.00E+00 0.00E+i00 +/-25%

C 0.00E+00 0.O0E+00 0.00E+00 +/-25%

All 5.70E+04 1.61E+03 1.13E+00 +/-25%

Waste Stream Irradiated Components Waste Volume Curies % Error Class FtA3 M^3 Shipped (Ci)

A 0.OOE+00 0.O0E+00 0.00E+0O +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 0.00E+O0 0.00E+00 0.00E+00 +1-25%

NRC Regulatory Guide 1.21 Reports Page 2 Report Date: 2/1/2016 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2015 to 1213112015 Percent Cutoff: 1 Waste Stream : Other Waste Waste Volume Curies % Error Class FtA3 MA3 Shipped (Ci)

A 0.00E+00 0.00E+00 0.00E+00 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 0.00E+00 0.00E+00 0.00E+00 +/-25%

Waste Stream : Sum of All 4 Categories DAW 48' Overpack DAW 20' Sealand DAW 40' Sealand IP-1 Bag Waste Volume Curies % Error Class FtA3 MA3 Shipped *(Ci)

A 5.70E+04 1.61E+03 1.13E+00 +/-25%

B 0.O0E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 5.70E+04 1.61E+03 1.13E+00 +1-25%

NRC Regulatory Guide 1.21 Reports Page 3 Report Date: 2/8/2016 Report Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2015 to i123112015 Number of Shipments Mode of Transportation Destination 17 Hittman Transport (TN) EnergySolutions Bear Creek 2 Landstar EnergySolutions Bear Creek 2 Hittman Transport (TN) Memphis Processing LLC

NRC Regulatory Guide 1.21 Reports Page 4 Report Date : 2/8/2016 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2015 to 12/31/2015 Percent Cutoff: 1 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 29.407% 3.32E-01 Cr-51 8.221% 9.29E-02 Mn-54 1.199% 1.35E-02 Fe-55 21.190% 2.39E-01 Co-58 6.791% 7.67E-02 Co-60 12.680% 1.43E-01 Ni-63 6.759% 7.64E-02 Zr-95 3.180% 3.59E-02 Nb-95 5.348% 6.04E-02 Ag-110m 3.021% r.3.41 E-02 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 29.407% 3.32E-01 Cr-51 8.221% 9.29E-02 Mn-54 1.199% 1.35E-02 Fe-55 21.190% 2.39E-01 Co-58 6.791% 7.67E-02 0o-60 12.680% 1.43E-01 Ni-63 6.759% 7.64E-02 Zr-95 3.180% 3.59E-02 Nb-95 5.348% 6.04E-02 Ag-110m 3.021% 3.41 E-02 Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 29.407% 3.32E-01 Cr-51 8.221% 9.29E-02 Mn-54 1.199% 1.35E-02 Fe-55 21.190% 2.39E-01 Co-58 6.791% 7.67E-02 Co-60 12.680% 1.43E-01 Ni-63 6.759% 7.64E-02 Zr-95 3.180% 3.59E-02 Nb-95 5.348% 6.04E-02 Ag-110m 3.021% 3.41E-02 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies H-3 29.407% 3.32E-01 Cr-5i 8.221% 9.29E-02 Mn-54 1.199% 1.35E-02 Fe-55 21.190% 2.39E-01 Co-58 6.791% 7.67E-02

NRC Regulatory Guide 1.21 Reports Page 5 Report Date : 2/8/2016 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2015 to 1213112015 Percent Cutoff: 1 Co-60 12.680% 1.43E-01 Ni-63 6.759% 7.64E-02 Zr-95 3.180% 3.59E-02 Nb-95 5.348% 6.04E-02 Ag-1I0m 3.021% 3.41E-02

NRC Regulatory Guide 1.21 Reports Page 6 Report Date : 2/8/2016 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2015 to 12/31/2015 Manifest Number Date Shipped Waste Volume Used Burial volume Used FPL/PSLI15-119 10/8/2015 Yes FPLIPSLI15-120 10/8/2015 Yes FPLIPSLI15-110 9/24/2015 Yes FPLIPSLI15-108 9/23(2015 Yes FPLIPSLI15-093 8/20/2015 Yes FPLIPSL 15-083 7/20/2015 Yes FPLIPSL 15-079 7/15/2015 Yes FPL/PSL 15-080 7/15/2015 Yes FPLIPSL 15-074 7/13/2015 Yes FPLJPSL 15-075 7/13/2015 Yes FPL/PSL 15-072 7/9/2015 Yes FPLJPSL 15-071 7/9/2015 Yes FPL/PSL 15-069 6/29/2015 Yes FPL/PSL 15-068 6/29/2015 Yes FPL'PSL 15-044 4/8/2015 Yes FPIJPSL 15-029 3/11/2015 Yes FPL\PSL 15-028 3/11/2015 Yes FPL/PSL 15-022 3/3/2015 Yes FPL/PSL 15-013 2/11/2015 Yes FPL/PSL 15-003 1/14/2015 Yes FPLJPSL 15-002 1/12/2015 Yes

TABLE 3.3 DOSE ASSESSMENTS (15 PAGES)

Page 1 of 1

!{ *OC~jEjN'It meei Soair Wednesday, February 10, 2016 12:19:38PM 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-2015 Ending: 31-Dec-2015 Organ Dose Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Bone mRem 1.75E-01 1.56E-01 1.67E-01 1.67E-01 6.65E-01 Limit mRem Percent of Limit Liver mRem 1.79E-01 1.60E-01 1.72E-01 1.81E-01 6.92E-01 Limit mRem Percent of Limit%

Total Body mRem 1.79E-01 1.60E-01 1.72E-01 1.81E-01 6.92E-01 Limit mRem Percent of Limit%

Thyroid mRem 1.81E-01 1.61E-01 1.98E-01 1.83E-01 7.24E-01 Limit mRem Percent of Limit%

Kidney mRem 2.28E-02 2.05E-02 2.18E-02 2.58E-02 9.09E-02 Limit mRem Percent of Limit%

Lung mRem 1.79E-01 1.60E-01 1.72E-01 1.81E-01 6.92E-01 Limit mRem Percent of Limit%

GI-Lli mRem 1.79E-01 1.60E-01 1.72E-01 1.81E-01 6.92E-01 Limit mRem Percent of Limit%

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Period: Ann, 2015 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 6.649E-01 6.922E-01 6.920E-01 7.243E-01 9.091E-02 6.920E-01 6.920E-01 0.000E+00 WNW Site Boundary - I Infant 9.689E-06 9.689E-06 9.689E-06 9.689E-06 9.689E-06 9.689E-06 9.689E-06 0.000E+00 Maximum Doserate by Organ: 6.649E-01 6.922E-01 6.920E-O1 7.243E-01 9.091E-02 6.920E-01 6.920E-01 0.000E+00 Maximum Organ Doserate (mRem/yr): 7.243E-01 Maximum Total Body Doserate (mRem/yr): 6.920E-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 3.527E-03 1.876E-03 3.335E-03 5.011E-03 WNW Site Boundary 3.038E-03 1.616E-03 2.873E-03 4.317E-03 Maximum NG Dose Rate: 3.527E-03 1 .876E-03 3.335E-03 5.011E-03 User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

Page 1 of 1 J'pen ElVISEkThitnt M~i n~ta~ S~ftwar~

Wednesday, February 10, 2016 12:21:18PM 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-2015 Ending: 31-Dec-2015 Organ Dose Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Bone mRem 8.50E-02 7.00E-02 9.49E-02 9.76E-02 3.48E-01 Limit mRem Percent of Limit Liver mRem 8.67E-02 7.24E-02 9.48E-02 1.02E-01 3.56E-01 Limit m Rem Percent of Limit%

Total Body mRem 8.67E-02 7.24E-02 9.48E-02 1.02E-01 3.56E-01 Limit mRem Percent of Limit%

Thyroid mRem 8.86E-02 7.28E-02 9.48E-02 1.02E-01 3.58E-01 Limit mRem Percent of Limit%

Kidney mRem 1.09E-02 9.35E-03 1.12E-02 1.34E-02 4.48E-02 Limit mRem Percent of Limit%

Lung mRem 8.67E-02 7.24E-02 9.48E-02 1.02E-01 3.56E-01 Limit mRem Percent of Limit%

GI-Lli mRem 8.67E-02 7.24E-02 9.48E-02 1.02E-01 3.56E-01 Limit mRem Percent of Limit%

User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

Page 8 of 9 Period: Ann, 2015 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 NW Site Boundary - In Infant 3.476E-01 3.556E-01 3.556E-01 3.580E-01 4.482E-02 3.556E-01 3.556E-01 0.000E+00 WNW Site Boundary - I Infant 4.240E-06 4.240E-06 4.240E-06 4.240E-06 4.240E-06 4.240E-06 4.240E-C06 0.000E+00 Maximum Doserate by Organ: 3.476E-O1 3.556E-01 3.556E-01 3.580E-01 4.482E-02 3.556E-01 3.556E-01 0.000E+00 Maximum Organ Doserate (mRem/yr): 3.580E-01 Maximum Total Body Doserate (mRem/yr): 3.556E-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 1. 157E-03 4.438E-04 1.099E-03 1.624E-03 WNW Site Boundary 9.968E-04 3.823E-04 9.468E-04 1.399E-03 Maximum NG Dose Rate: 1. 157E-03 4.438E-04 1.099E-03 1.624E-03 User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEM P

i1jf Zj/I Wednesday, February 10, 2016 12:22:04PM Jl, n *~~ *'. 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-2015 Ending: 31-Dec-2015 Organ Dose Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Bone mRem 8.95E-02 8.58E-02 7.24E-02 6.96E-02 3.17E-01 Limit mRem Percent of Limit Liver mRem 9.25E-02 8.80E-02 7.69E-02 7.91E-02 3.37E-01 Limit mRem Percent of Limit%

Total Body mRem 9.24E-02 8.80E-02 7.69E-02 7.91E-02 3.36E-01 Limit mRem Percent of Limit%

Thyroid mRem 9.26E-02 8.80E-02 1.04E-01 8.17E-02 3.66E-01 Limit mRem Percent of Limit%

Kidney mRem 1.20E-02 1.12E-02 1.06E-02 1.24E-02 4.61E-02 Limit mRem Percent of Limit%

Luhg mRem 9.24E-02 8.80E-02 7.69E-02 7.91E-02 3.36E-01 Limit mRem Percent of Limit%

GI-Lli mRem 9.24E-02 8.80E-02 7.69E-02 7.91E-02 3.36E-01 Limit mRem Percent of Limit%

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PSLSA134 [Database]: NEPSOEMP

Gas Status Smmary ReportWednesday, February 10, 2016 12:34 Pg f1 Period: Ann, 2015 Site/Unit/Discharge Point: PSL2 Site Boundary NNG Doserate Summary - Note: All Doses in mRem/yr Receptor Agegroup Bone Liver Total Body GI-Li Skin Thyroid Kidney Lung NW Site Boundary - In Infant 3.173E-01 3.365E-01 3.364E-01 3.663E-01 4.610E-02 3.364E-01 3.364E-01 0.000E+00 WNW Site Boundary - I Infant 5.448E-06 5.448E-06 5.448E-06 5.448E-06 5 .448E-06 5 .448E-06 5.448E-06 0.000E+00 Maximum Doserate by Organ: 3.173F-01 3.365E-01 3.364E-O1 3.663E-01 4.610E-02 3.364E-O1 3.364E-01 0.OODOE+O0 Maximum Organ Doserate (mRem/yr): 3.663E-01 Maximum Total Body Doserate (mRem/yr): 3.364E-O1 Site Boundary NG Doserate Summary Gas Receptor Location Gamma (mRad/yr) Beta (mRad/yr) Total Body (mRem/yr) Skin (mRem/yr)

NW Site Boundary 2.370E-03 1.432E-03 2.236E-03 3.387E-03 WNW Site Boundary 2.041E-03 1.234E-03 1.927E-03 2.918E-03 Maximum NG Dose Rate: 2.370E-03 1.432E-03 2.236E-03 3.387E-03 User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

p~9i EMS vLmzuner~t ~kwu~t Page 1 of 1 Wednesday, February 10, 2016 12:23:28PM Florida Power & Light St. Lucie Power Plant Reg. Guide 1.21, App B, Sec E2 - Air Doses Due To Gaseous Releases Unit: Site Starting: 1-Jan-2015 Ending: 31-Dec-2015 NG Dose Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Gamma Air mRad 1.11E-03 2.99E-04 1.19E-03 9.29E-04 3.53E-03 Limit mRad Percent of Limit Beta Air mRad 4.24E-04 2.66E-04 9.34E-04 2.52E-04 1.88E-03 Limit mRad Percent of Limit%

NG Total Body mRem 1.05E-03 2.79E-04 1.11E-03 8.95E-04 3.34E-03 Limit mRem Percent of Limit%

NG Skin mRem 1.55E-03 4.69E-04 1.78E-03 1.21E-03 5.01E-03 Limit mRem Percent of Limit%

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U. I~IUI.

Page 1 of 1 Wednesday, February 10, 2016 12:24:08PM

~ ~

Florida Power & Light I Eflbt t fvLu itmt t SQhw~rt St. Lucie Power Plant Reg. Guide 1.21, App B, Sec E2 - Air Doses Due To Gaseous Releases Unit: PSL1 Starting: 1-Jan-2015 Ending: 31-Dec-2015 NG Dose Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Gamma Air mRad 9.27E-04 5.93E-05 8.90E-05 8. 17E-05 1. 16E-03 Limit m Rad Percent of Limit%

Beta Air mRad 3.55E-04 2.21E-05 3.49E-05 3.20E-05 4.44E-04 Limit m Rad Percent of Limit%

NG Total Body mRem 8.81E-04 5.63E-05 8.45E-05 7.76E-05 1.10E-03 Limit m Rem Percent of Limit%

NG Skin mRem 1.30E-03 8.27E-05 1.25E-04 1.14E-04 1.62E-03 Limit m Rem Percent of Limit%

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PSLSA134 [Database]: NEPSOEMP

Open EMS Page 1 of 1 Wednesday, February 101 2016 12:24:47PM Florida Power & Light EmtRt1~ Man ~ Soflv~

St. Lucie Power Plant Reg. Guide 1.21, App B, Sec E2 - Air Doses Due To Gaseous Releases Unit: PSL2 Starting: 1-Jan-2015 Ending: 31-Dec-2015 NG Dose Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Gamma Air mRad 1.78E-04 2.40E-04 1.10E-03 8.48E-04 2.37E-03 Limit mRad Percent of Limit Beta Air mRad 6.91E-05 2.44E-04 8.99E-04 2.20E-04 1.43E-03 Limit mRad Percent of Limit%

NG Total Body mRem 1.69E-04 2.23E-04 1.03E-03 8.17E-04 2.24E-03 Limit mRem Percent of Limit%

NG Skin mRem 2.50E-04 3.86E-04 1.66E-03 1.09E-03 3.39E-03 Limit mRem Percent of Limit%

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Open EMS Page 1 of 1 Wednesday, February 10, 2016 12:25:31PM Florida Power & Light Efflutn~ IvLu ~tmen~ ~oftw~rt 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-2015 Ending: 31-Dec-2015 Ogan Dose Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Bone mRem 8. 18E-04 2.90E-04 5.44E-04 1.19E-04 1.77E-03 Limit mRem Percent of Limit%

Liver mRem 1.94E-03 8.82E-04 1.22E-03 3.54E-04 4.39E-03 Limit mRem Percent of Limit%

Total Body mRem 1.86E-03 8.74E-04 1.16E-03 3.55E-04 4.26E-03 Limit mRem Percent of Limit%

Thyroid mRem 1.75E-03 8.34E-04 1.13E-03 3.53E-04 4.05E-03 Limit mRem Percent of Limit%

Kidney mRem 2.00E-03 1.00E-03 1.25E-03 4.00E-04 4.65E-03 Limit mRem Percent of Limit%

Lung mRem 1.91E-03 9.00E-04 1.09E-03 3.53E-04 4.25E-03 Limit mRem Percent of Limit%

GI-Lli mRem 5.06E-03 4.33E-03 3.74E-03 4.34E-04 1.36E-02 Limit mRem Percent of Limit%

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Page 7 of 7 Period: Ann, 2015 Site/Unit/Discharge Point: Site Liquid Dose Summary - Note: All Doses in mRem Receptor Aaecirouo Bone Liver Total Body Thy roid Kidney un GI-Lli Skin Liquid Receptor - Teenager Teenager 1.445E-03 4.392E-03 4.256E-03 4.051E-03 4.649E-03 4.248E-03 1.356E-02 0.000E+00 Liquid Recptor - Child Child 1.772E-03 4.139E-103 4.119E-03 3.986E-03 2.020E-03 4.045E-03 7.954E-03 0.000E+00 Maximum Dose by Organ: 1.772E-03 4.392E-03 4.256E-03 4.051E-03 4.649E-03 4.248E-03 1.356E-02 0.000E+00 Maximum Organ Dose (mRem): 1.356E-02 Maximum Total Body Dose (mRem): 4.256E-03 User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

(O~'p~ EMS Page 1 of 1 Wednesday, February 10, 2016 12:26:26PM Florida Power & Light IvLnii~,'4.m~ II Softv~ r~

St. Ludie 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-2015 Ending: 31-Dec-2015 Ogan Dose Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Bone mRem 4.09E-04 1.45E-04 2.72E-04 5.95E-05 8.86E-04 Limit mRem Percent of Limit Liver mRem 9.70E-04 4.41E-04 6.08E-04 1.77E-04 2.20E-03 Limit mRem Percent of Limit%

Total Body mRem 9.31E-04 4.37E-04 5.82E-04 1.78E-04 2.13E-03 Limit mRem Percent of Limit%

Thyroid mRem 8.73E-04 4.17E-04 5.64E-04 1.76E-04 2.03E-03 Limit mRem Percent of Limit%

Kidney mRem 9.98E-04 5.02E-04 6.25E-04 2.00E-04 2.32E-03 Limit mRem Percent of Limit%

Lung mRem 9.57E-04 4.50E-04 5.45E-04 1.76E-04 2.12E-03 Limit mRem Percent of Limit%

GI-Lli mRem 2.53E-03 2.16E-03 1.87E-03 2.17E-04 6.78E-03 Limit mRem Percent of Limit%

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Page 7 of 7 Period: Ann, 2015 Site/Unit/Discharge Point: PSL1 Liquid Dose Summary - Note: All Doses in mRem Receptor AclegrouD Bone Liver Total Body Thyroid, Kidney Lume GI-Lli Skin Liquid Receptor - Teenager Teenager 7.226E-04 2.196E-03 2.128E-03 2.025E-03 2.325E-03 2.124E-03 6.781E-03 0.000E+00 Liquid Recptor - Child Child 8.859E-04 2.070E-03 2.060E-03 1.993E-03 1.010E-03 2.023E-03 3.9772-03 0.000E+00 Maximum Dose by Organ: 8.859E-04 2.196E-03 2.128E-03 2.0252-03 2.325E-03 2.124E-03 6.781E-03 0.000E+00 Maximum Organ Dose (mRem): 6.781E-03 Maximum Total Body Dose (mRem): 2. 128E-03 User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

~iEMS fVLULL~UnL It ~O1tV. U~t Page 1 of 1 Wednesday, February 10, 2016 12:29:05PM 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: PSL2 Star-ting: l-Jan'2015 Ending: 31-Dec-2015 Ogan Dose Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Annual Bone mRem 4.09E-04 1 .45E-04 2.72E-04 5.95E-05 8.86E-04 Limit mRem Percent of Limit Liver mRem 9,70E-04 4,41E-04 6.08E-04 1.77E-04 2,20E-03 Limit mRem Percent of Limit%

Total Body mRem 9.31E-04 4.37E-04 5.82E-04 1.78E-04 2.13E-03 Limit mRem Percent of Limit%

Thyroid mRem 8.73E-04 4.17E-04 5.64E-04 1.76E-04 2.03E-03 Limit mRem Percent of Limit%

Kid ney m Rem 9.98E-04 5.02E-04 6.25E-04 2.00 E-04 2.32 E-03 Limit mRem Percent of Limit%

Lu ng m Rem 9.57 E-04 4.50 E-04 5.45E-04 1.76 E-04 2.12E-03 Limit mRem Percent of Limit%

GI-Lli mRem 2.53E-03 2.16E-03 1.87E-03 2.17E-04 6.78E-03 Limit mRem Percent of Limit%

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Page 7 of 7 Period: Ann, 2015 Site/Unit/Discharge Point: PSL2 Liquid Dose Summary - Note: All Doses in mRem Receptor AaeclrouD Bone Liver Total Body Thyroid Kidney Lung GI-Li Skin Liquid Receptor - Teenager Teenager 7.226E-04 2.196E-03 2.128E-03 2.025E-03 2,325E-03 2,124E-03 6,781E-03 0,000E+00 Liquid Recptor - Child Child 8.859E-04 2.070E-03 2.060E-03 1.993E-03 1.010E-03 2.023E-03 3.977E-03 0.000E+OO Maximum Dose by Organ: 8.859E-04 2,196E-03 2.128E-03 2.025E-03 2.325E-03 2.124E-03 6.781E-03 0.000E+00 Maximum Organ Dose (toRemo): 6.781E-03 Maximum Total Body Dose (mRem): 2. 128E-03 User: Jim Hunt User JimHunt[Server]:

PSLSA134 [Database]: NEPSOEMP

TABLE 3.4 VISITOR DOSE (1 PAGE)

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 TI-E 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months per day for 312 days per year at a distance of 1 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 2015.

VISITOR DOSE RESULTS FOR CALENDAR YEAR 2015 were:

Noble Gas Dose mrad t Gamma AirDose Beta Air Dose 1.09E-03 5.77E-04 Gas, Particulate, Iodine, Carbon Dose mrem Bone 1.08E-01 Liver 1.13E-01 Thyroid 1.18E-01 Kidney 1.48E-02 Lung 1.13E-01 GI-LLI 1.13E-01 Total Body 1.13E-01

ENCLOSURE 3 C-200, OFFSITE DOSE CALCULATION MANUAL REVISION 44 (PCR 1974178) AND REVISION 45 (PCR 2067790)

MARKED UP~ PAGES (8 PAGES excludes blank page)

ST. LUCIE PLANT c-200

~Procedure No.

CHEMISTRY OPERATING Current Revision No.

PROCEDURE C

0 F PL SAEYRLTD44

___________REFERENCE USE_ _ _ _ _ _

~.I ~

Title:

z a OFFSITE DOSE CALCULATION MANUAL z ~ *~ ~

(ODCM)

I-v 0)

~cC Responsible Department: CHEMISTRY c~ a 0 o .~

LL. REVISION

SUMMARY

Revision 45 - Incorporated PCR 2067790 for addition of Unit 1 and 2 containment equipmentI w hatch monitoring as potential effluent pathways during outages.I

'.-w F- Revision 44 - Incorporated PCR 1974178 to implement changes documented in EC 277011

0) ~- 0 for replacement of UI PV Radiation Monitor. Updated monitor channel IDs. The new U1 PV Mirion MGP Radiation Monitor does not have a particulate, iodine, or mid range gas detector channel. (Author: J. Hunt)

Revision 43 - Incorporated PCR 1971488 to incorporate changes documented in EC 277010 for replacement of U1 FHB Rad Monitor. Updated monitor channel IDs. The new U1 FHB Rad Monitor does not have an iodine channel. (Author: J. Hunt)

AND Incorporated PCR 1970406 to provide improved guidance during gaseous radiation monitor inoperability and when annunciation is lost to the control room. Removed unclear guidance that releases may continue during inoperability for up to 30 days. (Author: J. Hunt)

AND Incorporated PCR 1994917 to remove the goat from Figure 1-2 located at "WSW-3.5, GOAT".

The goat is no longer at this location as documented in the Annual Land Use Census.

(Author: J. Hunt)

AND Incorporated PCR 2002584 to improve guidance for conducting REMP Program Supplemental Sampling. (Author: J. Hunt)

Revision 42 - Incorporated PCR 1966270 per AR 1932155 to add changes for development of a strateav that ensures a rapid method to release water from retention ponds either prior or Revision Approved By Approval Date UNIT # ________

DATE _______

0C.M. Wethy 04/27/82 DOCT PROCEDURE DOCN c-2o0 SYS ______

44 R. Coffey 06/24/15 STATUS COMPLETED REV 44

OF PGS

REVISION NO.: PROCEDURE TITLE: ~PAGE:

44 OFFSITE DOSE CALCULATION MANUAL (00CM) 41 of 231 PROCEDURE NO.:I C-200 ST. LUCIE PLANT I_____

TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM (Page 1 of 3)

Sampling Minimum Analysis Type of Activity' Lower Limit of Detection Gaseous Release Type Frequency Frqunynalysis_____________

FreqencyLLD(1) (p.Ci/ml)

P Noble Gas

1. Waste Gas Storage Tank Each Tank 1.E-04 Grab Sample Each Tank P.G.E. (2)

P P Noble Gas 1E0

2. Containment Purge (9) Each Purge (6) Each Purge (6) P.G.E. (2)

Grab Sample (7) H-3 1.E-06

3. Vents:(9) 4/M 4/M (7) Noble Gas Grab Sample P.G.E. (2) 1.E-04

a. Plant (8)

b. Fuel Bldg (5) H-3 1.E-06

c. S/G Blowdown Bldg.

4. All Release Types as listed in 3. Continuous (3) 4/M above (9) (8) Charcoal 1-1311.2 Sample (4) 1___.E-12__

4/M Particulate P.G.E. I.E-11 Sample (4) ________________

4/M Particulate Gross Alpha 1 .E-11I Sample Q

Composite Sr-89, Sr-90 1.E-1 1 Particulate Sample Noble Gas Noble Gases Gross .E6 Monitor Beta or Gamma

5. Cask Handling Facility Vent (8) W Noble Gas1.-4 Grab Sample WP.G.E. (2)

(8) H-3 1.E-06 W

Charcoal 1-131 1.E-12 Sample W

Particulate P.G.E. I .E-l1 Sample ________

Continuous (8) W Particulate Gross Alpha I .E-l1 Sample ________

Q Composite Sr-89, Sr-90 1i.E-il Particulate Sample P.G.E. - Denotes Principal Gamma Emitter

REVISION NO.: PROCEDURE TITLE: PAGE:

44 OFFSITE DOSE CALCULATION MANUAL (ODCM) 43o21 PROCEDURE NO.:

TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM (Page 3 of 3)

TABLE NOTATIONS (continued)

(2) The principal gamma emitters for which the LLD control applies include the following radionuclides: Kr-87, Kr-88, Xe-i133, Xe-I133m, Xe-I135 and Xe-I138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-i134, Cs-I137, Ce-141 and Ce-144 in Iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 3.11.2.6 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3) The ratio of the sample flow rate to the sampled stream flow rate shall be known

for the time period covered by each dose or dose rate calculation made in accordance with Controls 3.11.2.1, 3.11.2.2 and 3.11.2.3.

(4) Samples shall be changed at least four times per month and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing or after removal from sampler.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15%

of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (I) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased by more than a factor of 3.

(5) Tritium grab samples shall be taken at least 4/M from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

(6) Sampling and analysis shall also be performed following shutdown, startup or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

(7) Tritium analysis may be delayed for up to 14 days if the LLD is still attainable at the new counting time.

(8) Frequencies applicable only when the ventilation system is operating.

REVISION NO.: PROCEDURE TITLE: PAGE:

PRCEUR NO.: OS ACLAINMNUL(DM 44 of 231 44CEUR OFSTNOSOACLAINMNUL(DM 0-200 ST. LUCIE PLANT j_____

(9) During outages, the affected unit's containment equipment hatch is a potential effluent pathway. Monitoring of the open containment equipment hatch is performed as per procedural guidance. Any calculated release quantity will be reported in the annual report.

ST. LUCIE PLANT c-200

i Procedure No.

CHEMISTRY OPERATING Current Revision No.

PROCEDURE C

0 _ FPL SAFETY RELATED 4,344

___________REFERENCEUSE

Title:

~I o~.

z .~ a OFFSITE DOSE CALCULATION MANUAL z

.~

C.) -~

(ODCM)

I-v a~

Responsible Department: CHEMISTRY o

o~ *0

.~

0 U- ~ -c REVISION

SUMMARY

z ~Q Revision 44 - Incorporated PCR 1974178 to implement changes documented in EC 277011

~ 4) 4)

U- ~ij~

for replacement of Ul PV Radiation Monitor. Updated monitor channel IDs. The new U1 PV Mirion MGP Radiation Monitor does not have a particulate, iodine, or mid range gas detector i-Cu I- channel. (Author: J. Hunt)

4) '-' Q m Revision 43 - Incorporated PCR 1971488 to incorporate changes documented in EC 277010 for replacement of Ul FHB Rad Monitor. Updated monitor channel IDs. The new U1 FHB Rad Monitor does not have an iodine channel. (Author: J. Hunt)

AND Incorporated PCR 1970406 to provide improved guidance during gaseous radiation monitor inoperability and when annunciation is lost to the control room. Removed unclear guidance that releases may continue during inoperability for up to 30 days. (Author: J. Hunt)

AND Incorporated PCR 1994917 to remove the goat from Figure 1-2 located at "WSW-3.5, GOAT".

The goat is no longer at this location as documented in the Annual Land Use Census.

(Author: J. Hunt)

AND Incorporated PCR 2002584 to improve guidance for conducting REMP Program Supplemental Sampling. (Author: J. Hunt)

Revision 42 - Incorporated PCR 1966270 per AR 1932155 to add changes for development of a strategy that ensures a rapid method to release water from retention ponds either prior or during severe weather events and emergency conditions. (Author: J. Hunt)

R*_viinn 44 - Inr~nrnonrted PCR 1R39250 to uindaite nroc~edure number reference.

Revision Approved By Approval Date UNIT # ________

DATE _______

0 C.M. Wethy 04/27/82 DOCT PROCEDURE DOCN c-20o____

SYS ______

43 R. Coffey 12/04/14 STATUS COMPLETED REV 43

OF PGS

REVISION NO.: PROCEDURE TITLE: PAGE:

4344 OFFSlTE DOSE CALCULATION MANUAL (ODCM) 27 of 231 PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 3.3-14 RADIOACTIVE EFFLUENT MONITOR SETPOINT BASIS (Page 1 of 4)

ODCM Effluent Gas Channels CANL BSSAETHG

_____________ ID DOCUMENT SETPOINVe SETPOINVe 1PV LOW RANGE GAS RSC26_IL C-200a 5 X Bkg*q Allotted % Of Site 9

~Limit 1FHB LOW RANGE GAS RSC26._4L C-200a 5 x Bkg.q Allotted % Of Site Limit9 2A PV PIG LOW RANGE GAS 423 C-200a 5 x Bkg.q Allotted % Of Site 2BP IGLWRAG AS43 C-200a 5 x Bkg. Limit9 For Plant P PIGLOWRANG 2BGAS433Vent #2 2FHB LOW RANGE GAS 413 0-200a 5 X Bkg. Allotted % Of Site Limit9 SGBDB LOW RANGE GAS 45-6 C-200a 5 x Bkg. Allotted % Of Site Limit9 I CONDENSER AIR EJECTOR 35 C-200 2 x Bkg.b 3 x Bkg.

2 CONDENSER AIR EJECTOR 403 C-200 2 x Bkg.b 3 x 8kg.

1 BATCH GAS EFFLUENT 42 C-200a As Per As Per CY-SL-1 02-0105 CY-SL-1 02-01 05 a'h 2 BATCH GAS EFFLUENT 203 C-200a As Per As Per CY-SL-102-0105 CY-SL-102-0105a' 2PV WRGM Chan Low Range Gas 621 62P C-200a 5 x Bkg)e uCi/sec Allotted % Of Site Mid Range Gas 622 LimitP uCi/sec High Range Gas 623 2A ECCS WRGM Chan Low Range Gas 601 60p C_200a 0.75 x HighP Allotted % Of Site Mid Range Gas 602 uCi/sec LimitP uCilsec High Range Gas 603 28 ECCS WRGM Chan Low Range Gas 611 61P C_200a 0.75 x Highp Allotted % Of Site Mid Range Gas 612 uCi/sec LimitP uCi/sec High Range Gas 613 CHANNEL BASIS HG ODCM Related Particulate Channels ID DOCUMENT AETSPONe SETPOINTe

!PVPARTICL'J\*TE g-4-g4 *USAR 5000 CP-M !90,000PM° 1FHB PARTICULATE RSC26_4P FUSAR & TSd 5000 CPM 10,000 CPMC 2A PV PIG PARTICULATE 421 FUSAR 5000 CPM 10,000 CPMC 2B PV PIG PARTICULATE 431 FUSAR 5000 CPM 10,000 CPM0 2FHB PARTICULATE 411 FUSAR &TSd 5000 CPM 10,000 CPMc SGBDB PARTICULATE 45-4 FUSAR 5000 CPM 10,000 CPMc

REVISION NO.: ~ PROCEDURE TITLE: PAGE:

4344 OFFSITE DOSE CALCULATION MANUAL (00CM) 28 of 231 PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 3.3-14 RADIOACTIVE EFFLUENT MONITOR SETPOINT BASIS (Page 2 of 4)

ODCM Related Iodine Channels CANL BSSAETHG ID DOCUMENT SETPOINTe SETPOINTe LIDI/rNEt l 0-1--0 F-USAR 5000 CP-M 49n nnn P-PtA 2A PV PIG IODINE 422 FUSAR 5000 CPM 10,000 CPMC 2B PV PIG IODINE 432 FUSAR 5000 CPM 10,000 CPMC 2FHB IODINE 412 FUSAR 5000 CPM 10,000 CPMC SGBDB IODINE 45-5 FUSAR 5000 CPM 10,000 CPMC ODCM Related Liquid Channels CANL BSSAETHG ID DOCUMENT SETPOINVe SETPOINTe 1A S/G BLOWDOWN 44 C-200 2 x Bkg. 2.E-04 uCi/mIf'm 1B SG BOWDWN 4 C-00 x kg. .E-4 ui/mf'm 2B S/G BLOWDOWN 451 C-200 2 x Bkg. 2.E-04 uCi/mim 2A S/G BLOWDOWN 121 C-200 2 x Bkg. 2.E-04 uCi/mlt m 1 BATCH LIQUID EFFLUENT As Per CY-SL-1 02- As Per CY-SL-1 02-R6627 C-200014104 2 BATCH LIQUID EFFLUENT As Per CY-SL-1 02- As Per CY-SL-1 02-301 C-200014104 Monitor channels not listed are covered per CY-SL-104-01 12, Determination of Process Radiation Monitor Setpoints TABLE NOTATIONS a - 00CM Control 3.11.2.1a b - ODCM Table 4.11-1 Note (7) c - 0DCM Control 3.11.2.1.b d - TS Table 3.3-6 required instrument 2.a.ii with setpoint per 0DCM e - Setpoints may be rounded for analog and digital display input limitations.

f - The channel setpoint to be in cpm equivalent to this activity g - per 00CM Methodology Step 2.2.2 h - Batch Gaseous Release Rate and Maximum activity limits shall be used such that Plant Vent (PV) Release HIGH setpoints should not be exceeded.

i, j, k, and I not used in notation for clarity

REVISION NO.: fPROCEDURE TITLE: PAGE:

43,44 OFFSITE DOSE CALCULATION MANUAL (00CM) 104 of 231 PROCEDURE NO.:

C-200 [ST. LUCIE PLANT METHODOLOGY SECTION 2.2 Determiningq the Total Body and Skin Dose Rates for Noble Gas Releases And Establishing Setpoints for Effluent Monitors (continued)

1. (continued)

B. No Particulate or Iodine Radioactivity Channels are required by the 0DCM. Table 3.3-13 requires Iodine and Particulate Samplers only.

Technical Specification Table 3.3-6 requires a Fuel Building Vent Particulate Channel (the bases for the setpoint on the Fuel Building Vent Particulate Channel is described in 2.2.1 .C). The Unit 2 FUSAR does describe Particulate and Iodine Radioactivity Channels. These Channels are listed in ODCM Table 3.3-14 and ALERT and HIGH Setpoints are provided. The intent of providing these setpoints is to provide early warning that the effluent pathway conditions have increased such that a grab sample should be obtained if a HIGH Alarm Setpoint is reached or exceeded. The Particulate and Iodine HIGH Alarm Setpoint bases is that the collection mediums are fixed filter where continuing deposition of radioactivity would cause a increase in the channel count rate up to the setpoint level(s), the resulting dose rate can be shown to be less than 1 percent of the site limit for 0DCM Control 3.11.2.1 .b for Iodine-131, Iodine-I133, and all radionuclides in particulate from with half-lives greater than 8 days, is that these channel detectors are gross activity monitors of the scintillation type where the count rate is not dependent (above threshold) on the energy of the isotope entrained on the collection medium, and that these channels are qualitative trend indicators since the channel count rate cannot be corrected for the accrued sample collection volume. Plant historical trends have shown that Noble Gas Activity may contribute to the count rate of the Reactor Auxiliary Building (Plant) Vent Particulate and Iodine Channel(s).

In this event the Noble Gas contribution may be added to the Table 3.3-14 Alert and High Setpoints for Unit 2 Plant Vents only.

The sampling mediums associated with the Particulate and Iodine Channels in Table 3.3-14 are also controlled by the requirements of 00CM Table 4.11-2 which requires 4/M Minimum Analysis Frequency of the sampling mediums. These analysis are used to confirm and quantify the isotopic composition of the radioactivity being monitored by these channels. The presence of Noble Gas on collection medium would be confirmed by these analysis.

ENCLOSURE 5 0520025, PROCESS CONTROL PROGRAM REVISION 14 (PCR 2042572) AND REVISION 15 (PCR 2062643)

MARKED UP PAGES (11 PAGES excludes blank page)

ST. LUCIE PLANT 0520025

- Procedure No.

ADMINISTRATIVE PROCEDURE Current Revision No.

13C C

0 _

C F PL NON-SAFETY RELATED Effective Date

_______REFERENCE USE 12104109

Title:

~.i z o 0.~~

PROCESS CONTROL PROGRAM O~

z 0-C w.~ ~ Responsible Department: HEALTH PHYSICS I-vo -o a

REVISION

SUMMARY

c~

~CC o 0 REVISION 13D - Changed HPS to RPM and FRG to ORG, removed reference to deleted LI.. 5c~

~1, -c T.S 6.10.2q, replaced HP-40 with RP-AA-1 08-1 002 radioactive shipment procedure, z removed Barnwell facilty (no longer used), rc~mo,-cd containcr t'pe from. effue'-nt repor"t U) U) IL not.. required.by rcg 1.21..and added as applicable for solidification agent and remove ret U.. ~ procedure OM-048-WS&

U)0W

'-w F- REVISION 13C - Incorporated PCR 09-3004 for CR 2007-21553. Several steps reference the U) 0 m old FRG terminology and need to be updated to reflect ORG instead.

(Author: Nathan Rightmer)

REVISION 13B - Incorporated PCR 05-3003 for CR 2005-1 861.4 to add Level of Use to procedure cover page. (Helga Baranowsky, 09/29/05)

REVISION 13A - Incorporated PCR 03-3437 to change delegation of procedure from Safety Related to Non-Safety Related. (Bonnie Wooldridge, 12/04/03)

REVISION 13 - Made changes to References Section. (Bruce Somers, 07/20/99)

Revision FRG Review Date Approved By Approval Date S OPS 0 12/28/82 J.H. Barrow (for) 12/28/82 DATE ______

Plant General Manager DOCT PROCEDURE Revision FRG Review Date Approved By Approval Date DOCN 0520025 13C 07/20/99 R.G. West 07/20/99 SYS _______

Plant General Manager COM COMPLETED N/A _______ ITM 13C Authorized Approver Eric Katzman 11/13/09 Authorized Approver (Minor Correction)

REVISION NO.: ~ PROCEDURE TITLE: PAGE:

13C JPROCESS CONTROL PROGRAM3of1 PROCEDURE NO.:

0520025 1ST. LUCIE PLANT I_____

1.0 TITLE PROCESS CONTROL PROGRAM 2.0 REVIEW AND APPROVAL See cover page 3.0 SCOPE 3.1 Purpose The St. Lucie Plant Process Control Program (PCP) implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR 50. Specifically, the PCP applies to waste form classification of all radioactive waste destined for land burial in accordance with 10 CFR 20.2006.

In addition, the specific requirements are provided for dewatering of bead resins for disposal and for vendor supplied processes for solidification, encapsulation or absorption of liquid or wet solid radioactive wastes when performed on site and under the licenses issued to the St. Lucie Plant by the Nuclear Regulatory Commission.

tifthe Rfadioactive waste that is shipped to a licensed radioactive waste disposal facility for disposal, the St. Lucie Plant is responsible to meet all of the license conditions, including waste form and waste classification requirements of the disposal sites radioactive material license.

I-f--the R~adioactive waste that is shipped to a radioactive waste processor for further processing of the waste prior to disposal, the St Lucie Plant is responsible to meet all of the license conditions of the radioactive waste processor. In this case, however, it is the responsibility of the radioactive waste processor to meet the requirements of the radioactive waste disposal site license for the radioactive waste shipped to the disposal site.

REVISION NO.: ~ PROCEDURE TITLE: PAGE:

13C PROCESS CONTROL PROGRAM1 4of2 PROCEDURE NO.: I 0520025 1ST. LUCIE PLANT j_____

3.2 Discussion

1. The PCP contains provisions to assure that dewatering of bead resins results in a waste form with characteristics that meet the requirements of 10 CFR 61 as implemented by 10 CFR 20 and of the low level radioactive waste disposal site. The PCP rocess'* Cotrol,+, Progr..m includes in addition to this procedure the following related procedures:

A. St. Lucie Plant Health Physics Procedure No. HP-49, "Dewatering Radioactive Bead Resins."

B. CHEM-NUCLEAR SYSTEMS, INC. Test procedure for Dewatering Conical Bottom Demineralizers and Resin Liners -Project No. 11118.

C. CHEM-~NUCLEAR SYSTEMS, INC. Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners - Project No. 11118.

D. ,ecta.-P-÷Erocedure* No,., O 0I WS,-÷Q Oper'-atn Procdurfo aE.E CS-OP-PR-008-161049 Ener~gy Solutions Self-Engaging Dewatering System Fill Head at St Lucie.

2. Vendor supplied processes for solidification, encapsulation or absorption of liquid radioactive waste are conducted in accordance with a vendor PCP process.. conro program and appropriate operating procedures specific to the process to be used and are reviewed and accepted by the On-Site Review Group (ORG).FaGilit-y RevewGfu and approved by the Plant General Manager. Once approved for use at the St. Lucie Plant, changes to the vendor's process control program must be documented in accordance with Technical Specification 6.13 and as shown in Section 4.4. and be reviewed and accepted by the ORG Fclt,-'"*+,.,,j Review..Group.

m.,...,

.. and approved by the Plant General Manager prior to continued use at the St. Lucie Plant.

3. All radioactive waste shipped for land burial must meet the requirements of 10 CFR 20.2006 regarding waste form classification and packaging. This is implemented through procedure HP-47, "Classification of Radioactive Waste Material for Land Disposal."

R*EVISION NO.: ~ PROCEDURE TITLE: PAGE:

130C PROCESS CONTROL PROGRAM1 6of2 PROCEDURE NO.:I 0520025 jST. LUCIE PLANT j_____

4.0 PRECAUTIONS 4.1 Process Control Procedures used for the dewatering of radioactive bead resins that establish the conditions that must be met shall be based on full scale testing.

This is to provide reasonable assurance that the dewatering drying of the resin and disposal container will result in volumes of free standing water, at the time of disposal, within the limits of 10 CFR, Part 61 as implemented by 10 CFR 20 and of the low level radioactive waste disposal site.

4.2 Vendor supplied solidification, encapsulation and absorption processes performed on site shall be based on process control procedures, operating procedures and full scale testing that ensures that the final waste form will meet the applicable requirements of 10 CFR 61 and of the disposal site license.

Evidence that the vendor's process control program will meet the applicable waste form requirements of 10 CFR 61 and the disposal site license may be in the form of topical reports, NRC approved documentation, vendor test reports, inspection reports and/or other documentation as appropriate for the specific waste form requirements that must be met (e.g., Class A unstable, Class A stable, Class B or Class C). Procedures which are to be used must be controlled per the vendor's QA program.

4.3 All changes to the St. Lucie Plant POP rocesz Control Program shall become ity,,. Revi..e,.w Group*,.......

effective after review and acceptance, by the ._,RG - '*aci"... and approval of the Plant General Manager.

4.4 All changes to the St. Lucie Plant POP rccess Control Program shall be documented in accordance with Technical Specification 6.13. This documentation shall contain the following:

1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

2. A determination that the change will maintain the overall conformance of the solidified or dewatered waste product to existing requirements of Federal, State or other applicable regulations.

REVISION NO.: TPROCEDURE TITLE: PAGE:

13C jPROCESS CONTROL PROGRAM7of1 PROCEDURE NO.:

0520025 1ST. LUCIE PLANT 5.0 RESPONSIBILITES 5,1 It is the responsibility of the Plant General Manager to assure that all necessary procedures, equipment and support are provided to properly implement the PCP.

5.2 It is the responsibility of the Radiation Protection Manager (RPM)HelhPhse 8up*vse or his designee to assure that the radioactive bead resin will be dewatered in accordance with the PCP.

5.3 It is the responsibility of the RPM Hcalth Physics Supe,"-isor or his designee to assure that radioactive waste material is classified in accordance with the PCP.

5.4 FPL Dewatering equipment shall be operated by or under the direction of FPL personnel.

6.0 REFERENCES

NOTE One or more of the following symbols may be used in this procedure:

§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without the required Focus review and appropriate approval.

¶] Indicates a management directive, vendor recommendation, plant practice

or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

W- Indicates a step that requires a sign off on an attachment.

6.1 Bead Resin/Activated Carbon Dewatering Procedure for CNS 14-215 or smaller liners - FO-OP-023.

6,2 Test Instruction for Dewatering Conical Bottom Resin Liners and Atmospheric Demineralizers - Zero FSW - Project 11118-A (CNS).

6.3 Test Report for Dewatering Conical Bottom Resin Liners and Atmospheric Demineralizers - Zero Water - Project 11118-A (CNS).

6.4 HP-47, "Classification of Radioactive Waste Material for Land Disposal.

6.5 HP-49, "Dewatering Radioactive Bead Resins."

6.6 Vectra Procedure No. OM-048-WS, Operating Procedure for Vectra/Waste Services Group Resin Drying (Dewatering) System at Florida Power & Light, -

St. Lucie Plant.

REVISION NO.: PROCEDURE TITLE: PAGE:

13C PROCESS CONTROL PROGRAM1 8of2 PROCEDURE NO.:I 0520025 ST. LUCIE PLANT j_____

6A66.7 CS-OP-PR-008-161049 Energy Solutions Self-Engaging Dewatering System Fill Head at St Lucie.

64-6.8 Nuclear Packaging, Inc., Proprietary Topical Report No. TP-02-P-A covering Nuclear Packaging, Inc. Dewatering System.

686.9 RP-AA-1 08-1002 14P-40, "Shipment of Radioactive Materials."

6T96.1O HP-48, "Activity Determination for Radioactive Material Shipments."

7.0 RECORDS AND NOTIFICATIONS 7.1 Records shall be as per St. Lucie Plant Health Physics Procedure No. HP-49, "Dewatering Radioactive Bead Resins."

7.2 Records of vendor supplied solidification, encapsulation or absorption processes for liquid radioactive wastes.

7.3 . Annual Radioactive Effluent Release Reports.

7.4 Notifications

1. If it is suspected that the free standing water requirements may not be met for any container of radioactive bead resin shipped to a disposal site, notify the Plant General Manager and the RPM .HelhPh*~

2. If the process control procedures have not been followed or if free standing water may be present in the final shipping container of bead resin in amounts greater than allowed by regulations, notify the RPM HelhPhyic Su..... '-'- or his designee.

7.5 Records

1. Records of reviews performed for changes shall be retained as required by TS-1 61..q-and shall be maintained in the plant files in accordance with QI-1 7-PSL-1, "Quality Assurance Records."

REVISION NO.: TPROCEDURE TITLE: PAGE:

13C jPROCESS CONTROL PROGRAM1 9of2 PROCEDURE NO.:

0520025 1ST. LUCIE PLANT I_____

8.0 INSTRUCTIONS 8.1 Dewatered radioactive bead resins:

1. Disposal of dewatered radioactive bead resins is limited to the containers for which full scale dewatering tests have been conducted..

the.. State*÷ of Sout+h Carolina fo use.. at the* B....e.., Sou.th Caro.ina..,la.nd*.4,.,

disp~osarol fa,"ilit', habeen establ,",ished."

2. Dewater the container as per St. Lucie Health Physics Procedure No. HP-49, "Dewatering of Radioactive Bead Resins." . And/or CS-OP-P R-008-1 61049 Energy Solutions Self-Engaging Dewatering System Fill Head at St Lucie.

3. Only containers compatible with FPL owned or leased resin transfer/dewatering equipment may be used.

2-,4. Radioactive bead resins shall be dewatered, as appropriate, to meet shipping and transportation requirements during transit and disposal site requirements when received at the disposal site.

A. With dewatering not meeting disposal site, shipping and transportation requirements, suspend shipment of the inadequately dewatered bead resin and correct the PCP ROCtESS CON~lkTRl~t PlROGRAM-,Al the applicable procedures(s) and/or the dewatering system as necessary to prevent recurrence.

B. With dewatering not performed in accordance with the PCP:

(1) if the dewatered bead resin has not already been shipped for disposal, verify each container to ensure that it meets burial ground, shipping and transportation requirements and (2) take appropriate administrative action to prevent recurrence.

3.~5. Prior to disposal, each container of radioactive bead resins shall be tested for free standing liquids to assure that it meets shipping, transportation and disposal site requirements.

4-6. Close the container as per the manufacturer's instructions.

REVISION NO.: PROCEDURE TITLE: PAGE:

13C PROCESS CONTROL PROGRAM 1 f1 PROCEDURE NO.: 1 f1 0520025 1ST. LUCIE PLANT 8.2 Solidification, encapsulation or absorption of radioactive waste materials shall be performed in accordance with FPL approved vendor procedures. These procedures shall provide for the following:

1. Vendor's procedures, checksheets, checklists, etc., shall be FPL site specific and reviewed and accepted by the ORG and approved by Plant General Manager prior to implementation.

2. These procedures shall include Hold Points for FPL-PSL verification of crucial steps within the process. These steps may include, but are not limited to the following:

A. Sampling of the waste stream B. Review and acceptance of waste analyses C. Verification of process test specimens

0. Verification of waste additions E. Verification of chemical additions F. Verification of mixing G. Verification of final waste form and H. Verification of free standing liquid

3. These procedures shall also include steps for testing the final waste form to ensure that all burial site and NRC waste form characteristics requirements are met.

8.3 All radioactive waste material packaged and destined for land disposal shall conform to the requirements of 10 CFR 20.2006 as implemented by procedure HP-47. If waste form classification exceeds Class C or packaging does not meet the requirements of the waste form class, the RPM He-alth Physic-s Su..... i-,r shall be notified and shipment shall not be made.

REVISION NO.: PROCEDURE TITLE: PAGE:

130C PROCESS CONTROL PROGRAM 11 of 12 PROCEDURE NO.:

0520025 1ST. LUCIE PLANT 8.4 The annual Radioactive Effluent Release Reports shall include:

1. The following information for each class of solid waste (as defined by 10 CFR Part 61) shipped off site during the report period:

A. Volume B. Total curie quantity (specify whether determined by measurement or estimate)

C. Principal radionuclides (specify whether determined by measurement or estimate)

D. Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms)

D%.E. Type of container (e.g. LSA, Type A, Type B, Large Quantity) and T .pe.of.ont.ine (e.g., ... , Type. A, Type B, Large Quanti..) and,,

B.F. Solidification agent or absorbent (e.g., cement, bitumen, vinyl chloride) =as applicable

2. The following information for major changes to the solid radioactive waste system:

A. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; B. Sufficient detailed information to totally support the reason for the change with benefit of additional or supplemental information; C. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; D. An evaluation of the change which shows the predicted quantity of solid waste that differs from those previously predicted and in the license application and amendments thereto; E. A comparison of the predicted releases of radioactive materials in solid waste to the actual releases for the period prior to when the changes are to be made; F. An estimate of the exposure to plant operating personnel as a result of the change;

ST. LUCIE PLANT 0520025

i Procedure No.

ADMINISTRATIVE PROCEDURE Current Revision No.

FPLNON-SAFETY RELATED 16 FPL C

0 _

~REFERENCE USE _____

Title:

~j z

o 0,~-

-o o PROCESS CONTROL PROGRAM z

Responsible Department: RADIATION PROTECTION

<CO REVISION

SUMMARY

z o *0

~

0 Revision 16 - Section3.2 step 16 and 1C are not PSL use procedures they are reference LL ~ 5W-c material only and identified in Section 6.2 and 6.3.

z -

c~ ) Revision 15 - Incorporated PCR 2042572 to update references that have been superseded or LL a~ W no longer used. (Author: J. Simon)

(A, W0~W

~-W H Revision 14 - Incorporated PCR 1722646 to change HPS to RPM and FRG to ORG, to

0) 0 remove reference to deleted T.S 6.10.2q, to replace HP-40 with RP-AA-1 08-1 002 radioactive m

shipment procedure, to remove Barnwell facility, to remove container type from effluent report not required by Reg 1.21 and to add as applicable for solidification agent. (Author: J. Simon)

Revision 13C - Incorporated PCR 09-3004 for CR 2007-21553. Several steps reference the old ERG terminology and need to be updated to reflect ORG instead.

(Author: Nathan Rightmer)

Revision 136 - Incorporated PCR 05-3003 for CR 2005-1 8614 to add Level of Use to procedure cover page. (Helga Baranowsky, 09/29/05)

Revision 13A - Incorporated PCR 03-3437 to change delegation of procedure from Safety Related to Non-Safety Related. (Bonnie Wooldridge, 12/04/03)

Revision 13 - Made changes to References Section. (Bruce Somers, 07/20/99)

Revision Approved By Approval Date UNIT # ________

DATE _______

0 J.H. Barrow 12/28/82 DOCT PROCEDURE DOCN 0520025 SYS ______

16 R. Coffey 06/04/15 STATUS COMPLETED REV 16

OF PGS

R.EVISION NO.:. PROCEDURE TITLE: PAGE:

16 JPROCESS CONTROL PROGRAM1 4of1 PROCEDURE NO.:

0520025 1ST. LUCIE PLANT 3.2 Discussion

1. The PCP contains provisions to assure that dewatering of bead resins results in a waste form with characteristics that meet the requirements of 10 CFR 61 as implemented by 10 CFR 20 and of the low level radioactive waste disposal site. The PCP includes in addition to this procedure the following related procedures:

A. St. Lucie Plant Health Physics Procedure No. HP-49,

"'Dewatering Radioactive Bead Resins."

B. CHEr, NUCLEAR SYSTEMS, INC. Tespocedur.. , f...,o,-,

C. CHEMA NUCLEAR SYSTEMS,I.M. INC La Reod Sheet, for,-'.,-

a*B. CS-OP-PR-008-161 049 Energy Solutions Self-Engaging Dewatering System Fill Head at St Lucie.

2. Vendor supplied processes for solidification, encapsulation or absorption of liquid radioactive waste are conducted in accordance with a vendor PCP and appropriate operating procedures specific to the process to be used and are reviewed and accepted by the On-Site Review Group (ORG) and approved by the Plant General Manager. Once approved for use at the St. Lucie Plant, changes to the vendor's process control program must be documented in accordance with Technical Specification 6.13 and as shown in Section 4.4. and be reviewed and accepted by the ORG and approved by the Plant General Manager prior to continued use at the St. Lucie Plant.