Text

Corrected 1995 Annual Radioactive Effluent Release Rept.
	ML17228B423
Person / Time
Site:	Saint Lucie
Issue date:	12/31/1995
From:	; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17228B422	List: ML17228B421; ML17228B423;
References
	L-96-42, NUDOCS 9603210332
	Download: ML17228B423 (62)
	v • d • e

9603210332 95i23i PDR ADOCK 05000335 R PDR

Florida Power 5 Light Company, P.O. Box 128, Fort Pierce, FL 34954-0128 FPL L-96-42 FEB 28 1996

'3.0 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 1995 Annual Radioactive Effluent Release Re ort Enclosed is the 1995 Annual Radioactive Effluent Release Report for St. Lucie Units 1 and 2. This report is being sent pursuant to 10 CFR 50.36(a)(2) and sections 6.9.1.7 and 6.14.3 of the St. Lucie Units 1 and 2 Technical Specifications. The report is for the twelve month period begining January 1, 1995, and ending December 31( 1995 ~

Should there be any questions on this information, please contact us ~

Very truly yours, (u'.

H. Bohlke Vice President St. Lucie Plant Enclosure WHB/SL CC'tewart D. Ebneter, Regional Administrator, Region II, USNRC, Atlanta GA.

Senior Resident Inspector, USNRC, St. Lucie Plant an FPL Group company

l

'C e

FLORIDA POWER A LIGHT COMPANY ST. LUCIE PLANT UNITS NO. 1 02 LICENSE NUMBERS DPR-67 Ec NPF-16 COMBINED ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT FOR THE PERIOD JANUARY 1, 1995 THROUGH DECEMBER31, 1995

TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMEN'I'AL INFORMATION OFFSITE DOSE CALCULATIONMANUALREVISIONS SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS PROCESS CONTROL PROGRAM REVISIONS LIQUIDEFFLUENTS:

Summation of all Releases Unit ¹ 1 8 Summation of all Releases Unit ¹ 2 10 Nuclide Summation by Quarter Unit¹ 1 12 Nuclide Summation by Quarter Unit ¹ 2 16 Liquid EfHuent Dose Unit¹ 1 20 Liquid EfHuent Dose Unit ¹ 2 21 GASEOUS EFFLUENT:

Summation of all Releases Unit 1¹ 22 Summation of all Releases Unit 2¹ 24 Nuclide Summation by Quarter Unit 1¹ 26 Nuclide Summation by Quarter Unit ¹2 30 Gas EQluent Dose Unit¹ 1 34 Gas EQluent Dose Unit 2¹ 35 SOLID WASTE DISPOSAL - TABLE 3.9 Shipment Summations 36 SOLID WASTE DISPOSAL - TABLE 3.10 Sewage Sludge Shipments 40 Attachment - A UNPLANNED Liquid Release of August 19, 1995 41 Attachment - B C-200 ODCM Revision 16 and Revision 17 43

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION

1. Regulatory Limits 1.1 For Liquid Waste EKuents A. The concentration of radioactive material released from the site shall be limited to ten times the concentrations speciffed in 10 CFR Part 20 Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 micro-Curies/ml total activity.

B. The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive material in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited to:

During any calendar quarter to <= 1.5 mrems to the Total Body and to<= 5 mrems to any organ, and During any calendar year to <= 3 mrems to the Total Body and to <= 10 mrems to any organ.

1.2 For Gaseous Waste EfBuents:

A. The dose rate in UNRESTRICTED AREAS due to radioactive materials released in gaseous effluents &om the site shall be limited to:

For Noble Gases: <= 500 mrems/yr to the total body and

<= 3000 mrems/yr to the skin, and For Iodine-13 1, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days:

<= 1500 mrems/yr to any organ.

B The air dose due to noble gases released in gaseous effluents from each unit, to areas at and beyond the SITE BOUNDARYshall be limited to the following:

During any calendar quarter, to<= 5 mrads for gamma radiation, and

<= 10 mrads for beta radiation and, During any calendar year, to <= 10 mrads for gamma radiation and

<= 20 mrads for beta radiation.

The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form, with half-lives > 8 Days in gaseous effluents released, &om each unit to areas at and beyond the site boundary, shall be limited to the following:

During any calendar quarter to <= 7.5 mrem to any organ, and During any calendar year to <= 15 mrem to any organ.

The calculated doses contained in an annual report shall not apply to any ODCM Control.

The reported values are based on actual release conditions instead of historical conditions that the ODCM Control dose calculations are based on. The ODCM Control dose limits are therefore included in Item 1 of the report, for information only

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION(Continued)

2. EQluent Concentration Limits(ECL)

Water: Ten times the 10 CFR Part 20, Appendix B, Table 2, Column 2, except for entrained or dissolved noble gases as described in 1.1.A of this report.

Air: Release concentrations are limited to dose rate limits described in 1.2.A. of this report.

3. Average Energy of fission and activation gases in gaseous eQluents is not applicable.

4. Measurements and approximations of total radioactivity Where alpha, tritium, and listed nuclides are shown as zero Curies released, this should be interpreted as "no activity was detected on the samples using the ODCM Control analyses techniques to achieve required Lower Limit ofDetection (LLD)sensitivity for radioactive eQluents".

A summary of liquid eQluent accounting methods is described in Table 3.1.

A summary of gaseous eQluent accounting methods is described in Table 3.2.

4.1 Estimate of Errors 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 5 Total% 9 30 10 35 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.

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION(Continued)

4. Measurements and Approximations of Total Radioactivity (Cont.)

TABLE 3.1 RADIOACTIVELIQUIDEFFLUENT SAMPLING AND ANALYSIS Liquid Sampling Type of Method of Source Frequency Analysis Analysis Each Batch . Principal Ganima Emitters p.h.a.

Monitor Monthly Tritium L.S.

Tank Composite Gross Alpha G.F.P.

1 Releases Quarterly Sr-89, Sr-90, Composite & Fe-55 Continuous Daily Principal Gamma Emitters Releases Grab & I-131 for p.h.a.

Samples 4/M Composite Analysis Dissolved & Entrained Gases One Batch/ Month p.h.a.

Tritium Composite Monthly L.S.

Alpha Composite Monthly G.F.P.

Sr-89, Sr-90, & Fe-55 Composite Quarterly C.S.

1- Boric Acid Evaporator Condensate is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and does not contribute to Liquid Waste EQluent Totals.

p.h.a.- Gamma Spectrum Pulse Height Analysis using Germanium Detectors. All peaks are identified and quanti6ed.

L.S.- Liquid Scintillation Counting C.S.- Chemical Separation G.F.P.- Gas Flow Proportional Counting 4/M - Four per Month

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION(Continued)

4. Measurements and Approximations of Total Radioactivity (Continued)

TABLE 3.2 RADIOACTIVEGASEOUS WASTE SAMPLING AND ANALYSIS Gaseous Sampling Type of Method of Source Frequency Analysis Analysis Waste Gas Decay Tank Each Batch Principal Gamma Emitters p.h.a.

Releases Containment Principal Gamma Emitters p.h.a.

Purge Each Purge Tritium L.S.

Releases 4/M Principal Gamma Emitters p.h.a.

Tritium L.S.

Plant Monthly Particulate Vent Composite Gross Alpha G.F.P.

Quarterly Particulate Composite Sr-89 & Sr-90 C.S.

p.h.a.- Gamma Spectrum Pulse Height Analysis using Germanium Detectors. All peaks are identified and quantified.

L.S.- Liquid Scintillation Counting C.S.- Chemical Separation G.F.P.- Gas Flow Proportional Counting 4/M - Four per Month

FLORIDAPOWER &, LIGHT COMPANY ST. LUCIE 1 & 2 ANNUALREPORT 1, 1995 THROUGH DECEMBER 31, 1995

'ANUARY EFFLUENT & WASTE DISPOSAL - SUPPLEMENTAL INFORMATION(CONTINUED)

5. Batch Releases Unit 1 Unit 2 A. Liquid

1. Number of batch releases: 48 47

2. Total time period for batch releases: 23343 22850 minutes

3. Maximum time period for a batch release: 744 744 minutes

4. Average time period for a batch release: 486 486 minutes

5. Minimum time period for a batch release: 35 35 minutes

6. Average dilution stream flow during the period: 802636 802636 gpm Allliquid releases are summarized in tables.

B. Gaseous

1. Number of batch releases 29 69

2. Total time period for batch releases: 11922 6038 minutes

3. Maximum time period for a batch release: 600 600 minutes

4. Average time period for a batch release: 411 88 minutes

5. Minimum time period for a batch release: 160 27 minutes Allgaseous waste releases are summarized in tables.

6. Unplanned Releases A'. Liquid

1. Number of releases: 1 0

2. Total activity of releases: 9.88E-06 0 Curies B. Gaseous

1. Number of releases: 0 0

2. Total activity of releases: 0.00E 00 0 Curies C. See attachments (ifapplicable) for:

1. A description of the event and equipment involved.

2. Cause(s) for the unplanned release.

3. Actions taken to prevent a recurrence.

4. Consequences of the unplanned relea

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION(Continued)

Assessment of radiation dose &om radioactive eQluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARYassumes the visitor 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 1.6 kilometers in the South East Sector. The VISITOR received exposure from each of the two reactors on the Site.

VISITOR DOSE RESULTS FOR CALENDARYEAR 1995 were:

EOB EGAD EEBDBBBEE ~DOBE d Gamma Air Dose 9.55E-03 Beta AirDose 7.3 1E-03 GASEOUS PARTICULATE A IODINE EXPOSURE DOSE mRem Bone 2.54E-06 Liver 2.96E-04 Thyroid 7.78E-04 Kidney 1.28E-04 Lung 2.96E-04 GI-LLI 2.92E-04 Total Body 3.92E-04

8. Offsite Dose Calculation Manual Revisions (ODCM):

The ODCM was revised two times during the reporting interval. A complete copy of each revision is provided per Attachment - B.

Revision 16 was implemented on January 26, 1995.

The purpose ofthe revision was to provide for more frequent monitoring by personnel when a Radioactive EfHuent Instrument CHANNEL has an INOPERABLE "control room alarm annunciation" condition as defined by the CHANNELFUNCTIONALTEST criteria. The revision qualifies two conditions: 1) INOPERABLE due to loss of radioactivity detection capability and 2) all CHANNEL functions OPERABLE except for"'control room, alarm annunciation" is INOPERABLE.

For condition

1) above, no changes to the existing requirements of the ODCM Control ACTION 47. Grab samples shall be taken per new ACTION 47a etc.

2) above, Revision 16 of the ODCM ACTION 47b now requires CHANNEL CHECKS be performed once per hour instead ofperforming a grab sample every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ifthe required "control room alarm annunciation" is the only cause of the INOPERABLE condition.

The justification for this revision is to provide a higher level of protection by requiring hourly CHANNEL CHECKS instead of only providing for one grab sample per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when only the "alarm annunciation" is INOPERABLE. This increased surveillance method should insure that the CHANNEL is indicating normal concentrations and that it is not exceeding its alarm set points.

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION(Continued)

8. Offsite Dose Calculation Manual Revisions (ODCM) (continued)

Revision 17 was implemented on May 30, 1995.

The purpose ofthe revision was to allow the Gaseous Pathway required two year evaluation to be based on a one year, or longer interval(to include a refueling outage), instead of the previous six month interval.

The justification(s) for the longer interval are:

The controlling age group determined &om a six month non-refueling outage interval is not as conservative as a 6 month interval with a refueling outage. This is due to the presence of more iodine emissions during a refueling interval and the higher dose impact on younger age groups. An evaluation of all age groups could yield a controlling age group that would only be valid for non-refueling conditions. To insure that the potential maximum exposed individual was protected at all times from receiving greater than a ODCM Control Limit, a more representative(longer) evaluation interval was required. The new interval should provide equal protection for all age groups over all plant conditions that may exist in an annual dose interval.

2) The revision should provide consistent dose evaluations based on all plant conditions and not have revisions to the ODCM based on whether there was a refueling outage in the last six months. It should also minimize the ODCM having different controlling age groups for each reactor on site and will help reduce confusion and procedural changes.

9. Solid Waste and Irradiated Fuel Shipments:

No irradiated fuel shipments were made for the site.

Common Solid waste from St. Lucie Units 1 and 2 were shipped jointly. A tabulated summation ofthese shipments is provided in this report as Table 3.9 Solid Waste Shipments as Sewage Sludge were made off-site. These Shipments are summarized in Table 3.10.

10. Process Control Program (PCP) Revisions:

During the reporting period there were no significant changes to the Process Control Program. However, revisions to the vendor procedures for the drying of bead resins were reviewed by the Facility Review Group and approved for use by the Plant General Manager.

FLORIDA POWER Ec LIGHT COMPANY ST. LUCIE UNIT ¹ 1 ANNUALREPORT JANUARY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3.3-1 LIQUID EFFLUENTS - SUMMATIONOF ALLRELEASES UNIT QTR¹1 QTR¹2 A. Fission and Activation Products

1. Total Release - (Not including Tritium, Gases, and Alpha) Ci 5.33E-02 6.47E-02

2. Average Diluted Concentration During Period uci/ml 1.08E-10 1.27E-10 B. Tritium

1. Total Release Ci 6.53E 01 4.91E 01

2. Average Diluted Concentration During Period uci/ml 1.32E-07 9.67E-08 C. Dissolved and Entrained Gases

1. Total Release Ci 3.12E-01 2.38E-04

2. Average Diluted Concentration During Period uci/ml 6.31E-10 4.68E-13 D. Gross Alpha Radioactivity I. Total Release Ci 5.60E-05 0.00E 00 E. Volume of Waste Released (Prior to Dilution) Liters 1 44E 07 2.04E 07 F. Volume of Dilution Water Used During Period Liters 4.94E 11 5.08E 11

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT ¹ 1 ANNUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.3-1 LIQUID EFFLUENTS - SUMMATIONOF ALLRELEASES UNIT QTR¹3 QTR¹4 A.. Fission and Activation Products

1. Total Release - (Not including Tritium, Gases, and Alpha) Ci 9.95E-02 3. 12E-01

2. Average Diluted Concentration During Period uci/ml 2.06E-10 9.71E-10 B. Tritium

1. Total Release Ci 1.85E 02 7.82E 01

2. Average Diluted Concentration During Period uci/ml 3.83E-07 2.43E-07 C. Dissolved and Entrained Gases

1. Total Release Ci 1.26E-01 6.40E-02

2. Average Diluted Concentration During Period uci/ml 2.61E-10 1.99E-10 D. Gross Alpha Radioactivity

1. Total Release Ci 0.00E 00 0.00E 00 E. Volume of Waste Released (Prior to Dilution) Liters 1.77E 06 1.11E07 F. Volume of Dilution Water Used During Period Liters 4.83E 11 3.22E 11

FLORIDA POWER A LIGHT COMPANY ST. LUCIE UNIT ¹ 2 ANNUALREPORT JANUARY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3.3-2 LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES UNIT QTFA1 QTR¹2 A. Fission and Activation Products

1. Total Release - (Not including Tritium, Gases, and Alpha) Ci 5.31E-02 6.39E-02

2. Average Diluted Concentration During Period uci/ml 1.07E-10 1.26E-10 B. Tritium

1. Total Release Ci 6.53E 01 4.91E 01

2. Average Diluted Concentration During Period uci/ml 1.32E-07 9.67E-08 C. Dissolved and Entrained Gases

1. Total Release Ci 3.12E-01 2.38E-04

2. Average Diluted Concentration 6.31E-10 4.68E-13 During Period uci/ml D. Gross Alpha Radioactivity

1. Total Release Ci 5.60E-05 0.00E 00 Volume of Waste Released (Prior to Dilution) Liters 1.22E 06 9.61E 05 F. Volume of Dilution Water Used During Period Liters 4.94E 11 5.08E 11 10

FLORIDA POWER R LIGHT COMPANY ST. LUCIE UNIT ¹ 2 ANNUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.3-2 LIQUID EFFLUENTS - SUIvMATIONOF ALLRELEASES UNIT QTR¹3 QTR¹4 A. Fission and Activation Products

1. Total Release - (Not including Tritium, Gases, and Alpha) Ci 9.95E-02 3.12E-01

2. Average Diluted Concentration During Period uci/ml 2.06E 10 9.70E-10 B. Tritium

1. Total Release Ci 1.81E 02 7.82E 01

2. Average Diluted Concentration During Period uci/ml 3.74E-07 2.43E-07 C. Dissolved and Entrained Gases

1. Total Release Ci 1.26E-01 6.40E-02

2. AverageDiluted Concentration 2.61E-10 1.99E-10 During Period uci/ml D. Gross Alpha Radioactivity

1. Total Release Ci 0.00E 00 0.00E 00 E. Volume of Waste Released (Prior to Dilution) Liters 1.77E 06 1.66E 06 F. Volume of Dilution Water Used During Period Liters 4.83E 11 3.22E 11

FLORIDAPOWER & LIGHT COMPANY ST. LUCIE UNIT 8 1 ANNUALREPORT JANUARY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3.4-1 LIQUIDEFFLUENTS Continuous Mode Batch Mode NUCLIDES QTEQl QTEQ2 QTPA1 QTEQ2 RELEASED UNIT NA-24 Ci 0.00E 00 0.00E 00 6.88E-06 2.09E-05 CR-51 Ci '0.00E 00 0.00E 00 1.07E-03 1.41E-04 MN-54 Ci 0.00E 00 0.00E 00 1.26E-03 5.10E-04 FE-55 Ci 0.00E 00 5.82E-04 5.02E-03 2.83E-02 MN-56 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO-57 Ci 0.00E 00 0.00E 00 1.47E-05 0.00E 00 CO-58 Ci 0.00E 00 0.00E 00 1.24E-02 3.91E-03 FE-59 Ci 0.00E 00 0.00E 00 2.62E-05 0.00E 00 CO-60 Ci 0.00E'00 0.00E 00 1.58E-02 9.44E-03 ZN-65 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NI-65 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 BR-82 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 RB-88 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-89 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-90 Ci 3.95E-05 1.09E-04 9.17E-06 8.94E-06 Y-90 Ci 3.95E-05 1.09E-04 9.17E-06 8.94E-06 SR-91 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-92 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Y-92 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 ZR-95 Ci 0.00E 00 0.00E 00 3.31E-04 '.40E-04 NB-95 Ci 0.00E 00 0.00E 00 1.10E-03 1.18E-03 ZR-97 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NB-97 Ci 0.00E 00 0.00E 00 2.19E-04 4.73E-05 TC-99M Ci 0.00E 00 0.00E 00 6.93E-06 0.00E 00 MO-99 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 RU-103 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 AG-110 Ci 0.00E 00 0.00E 00 1.01E-03 3.98E-03 SN-113 Ci 0.00E 00 0.00E 00 6.82E-05 0.00E 00 SB-122 Ci 0.00E 00 0.00E 00 3.85E-05 1.81E-06 SB-124 Ci 0.00E 00 0.00E 00 2.98E-03 7.82E-03 SB-125 Ci 0.00E 00 0.00E 00 6.64E-03 7.86E-03 12

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT ¹ 1 ANNIJAL REPORT JANUARY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3.4-1 LIQUID EFFLUENTS (CONTINUED)

Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTR¹1 QTR¹1 QTR¹2 TE-129 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TE-129M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 2.86E-04 0.00E 00 TE-132 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 I-132 Ci 0.00E 00 0.00E 00 0.00E 00 5.92E-05 I-133 Ci 0.00E 00 0.00E 00 5.97E-05 0.00E 00 I-134 Ci O.OOE 00 0.00E 00 0.00E 00 0.00E 00 CS-134 Ci 0.00E 00 0.00E 00 1.21E-03 1.38E-04 I-135 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CS-136 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CS-137 Ci 6.62E-05 0.00E 00 3.23E-03 3.53E-04 CS-138 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 BA-140 Ci O.OOE 00 0.00E 00 0.00E 00 0.00E 00 LA-140 Ci 0.00E 00 0.00E 00 4.23E-04 0.00E 00 CE-141 Ci O.OOE 00 0.00E 00 0.00E 00 0.00E 00 CE-144 Ci O.OOE 00 0.00E 00 0.00E 00 00 '.00E PR-144 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 W-187 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NP-239 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TOTAL FOR PERIOD Ci 1.45E-04 8.00E -04 5.31E-02 6.39E-02 AR-41 Ci O.OOE 0.00E 00 0.00E 00 0.00E 00 KR-85M Ci 0.00E 0.00E 00 7.98E-05 0.00E 00 KR-85 Ci 0.00E 0.00E 00 0.00E 00 0.00E 00 KR-87 Ci 0.00E 0.00E 00 0.00E 00 0:00E 00 KR-88 Ci 0.00E 0.00E 00 0.00E 00 0.00E 00 XE-131M Ci 0.00E 0.00E 00 9.55E-04 0.00E 00 XE-133M Ci 0.00E 0.00E 00 5.97E-03 . 0.00E 00 XE-133 Ci 0.00E 0.00E 00 3.0IE-01 2.26E-04 XE-135M Ci 0.00E 0.00E 00 0.00E 00 0.00E 00 XE-135 Ci 0.00E 0.00E 00 3.87E-03 1.14E-05 13

FLORIDA POWER 2 LIGHT COMPANY ST. LUCIE UNIT ¹ 1 ANNUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3A-1 LIQUIDEFFLUENTS Continuous Mode Batch Mode NUCLIDES QTR¹3 QTR¹4 QTR¹3 QTR¹4 RELEASED UNIT NA-24 Ci 0.00E 00 0.00E 00 1.51E-04 2.46E-04 CR-51 Ci 0.00E 00 0.00E 00 6.80E-03 1.63E-02 MN-54 Ci 0.00E 00 0.00E 00 8.78E-04 1.46E-03 FE-55 Ci 0.00E 00 0.00E 00 1.49E-02 2.41E-02 MN-56 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO-57 Ci 0.00E 00 0.00E 00 0.00E 00 2.95E-04 CO-58 Ci 0.00E 00 0.00E 00 9.16E-03 1.82E-01

.FE-59 Ci 0.00E 00 0.00E 00 2.90E-04 2.35E-03 CO-60 Ci 0.00E 00 0.00E 00 1.05E-02 4.99E-03 ZN-65 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NI-65 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 BR-82 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 RB-88 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-89 Ci 0.00E 00 1.89E-06 4.47E-05 3.99E-05 SR-90 Ci 0.00E 00 8.67E-05 6.37E-06 1.66E-05 Y-90 Ci 0.00E 00 8.67E-05 6.37E-06 1.66E-05 SR-91 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-92 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Y-92 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 ZR-95 Ci 0.00E 00 0.00E 00 1.50E-03 2.47E-03 NB-95 Ci 0.00E 00 0.00E 00 2.37E-03 3.88E-03 ZR-97, Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NB-97 Ci 0.00E 00 0.00E 00 3.07E-05 8.61E-05 TC-99M Ci 0.00E 00 0.00E 00 1.03E-05 0.00E 00 MO-99 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 RU-103 Ci 0.00E 00 0.00E 00 0.00E 00 3.08E-05 AG-110 Ci 0.00E 00 0.00E 00 2.57E-03 9.09E-04 SN-113 Ci 0.00E 00 0.00E 00 1.32E-04 1.22E-03 SB-122 Ci 0.00E 00 0.00E 00 8.75E-04 4.20E-04 SB-124 Ci, 0.00E 00 0.00E 00 1.74E-02 1.59E-02 SB-125 Ci 0.00E 00 0.00E 00 2.35E-02 3.74E-02 14

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 8 1 ANNUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3A-1 LIQUID EFFLUI&TS (continued)

Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTRP3 QTf83 QTRf4 TE-129 Ci 0.00E 00 0.00E 00 1.73E-03 4.65E-03 TE-129M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 9.55E-05 7.40E-05 TE-132 Ci 0.00E 00 0.00E 00 0.00E 00 1.62E-05 I-132 Ci 0.00E 00 0.00E 00 6.71E-05 9.58E-05 I-133 Ci 0.00E 00 0.00E 00 2.03E-04 0.00E 00 I-134 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CS-134 Ci 0.00E 00 5.47E-05 2.59E-03 6.54E-03 I-135 Ci 0.00E 00 0.00E 00 9.85E-05 0.00E 00 CS-136 Ci 0.00E 00 0.00E 00 0.00E 00 1.13E-05 CS-137 Ci 0.00E 00 5.12E-05 2.71E-03 6.40E-03 CS-138 Ci 0.00E 00 0.00E 00 9.63E-05 1.34E-04 BA-140 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 LA-140 Ci 0.00E 00 0.00E 00 8.70E-04 2.67E-04 CE-141 Ci 0.00E 00 0.00E 00 0.00E 00 6.55F 05 CE-144 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 PR-144 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 W-187 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NP-239 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00'OTAL FOR PERIOD Ci 0.00E 00 2.81E-04 9.95E-02 3.12E-01 AR-41 Ci 0.00E 00 0.00E 00 2.46E-05 0.00E 00 KR-85M Ci 0.00E 00 0.00E 00 1.58E-05 0.00E 00 KR-85 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-87 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-88 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-131M Ci 0.00E 00 0.00E 00 9.96E-04 2.28E-04 XE-133M Ci 0.00E 00. 0.00E 00 2.13E-03 4.53E-04 XE-133 Ci 0.00E 00 0.00E 00 1.19E-01 6.32E-02 XE-135M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-135 -Ci 0.00E 00 0.00E 00 3.77E-03 1.17E-04 15

FLORIDA POWER &, LIGHT COMPANY ST. LUCIE UNIT ¹ 2 ANNUALREPORT JANUARY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3A-2 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTR¹1 QTR¹2 QTR¹l QTR¹2 NA-24 Ci 0.00E 00 0.00E 00 6.88E-06 2.09E-05 CR-51 Ci 0.00E 00 0.00E 00 1.07E-03 1.41E-04 MN-54 Ci 0.00E 00 0.00E 00 1.26E-03 5.10E-04 FE-55 Ci 0.00E 00 0.00E 00 5.02E-03 2.83E-02 MN-56 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO-57 Ci 0.00E 00 0.00E 00 1.47E-05 0.00E 00 CO-58 Ci 0.00E 00 0.00E 00 1.24E-02 3.91E-03 FE-59 Ci 0.00E 00 0.00E 00 2.62E-05 0.00E 00 CO-60 Ci 0.00E 00 0.00E 00 1.58E-02 944&03 ZN-65 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NI-65 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 BR-82 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 RB-88 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-89 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-90 Ci 0.00E 00 0.00E 00 9.17E-06 8.94E-06 Y-90 Ci 0.00E 00 0.00E 00 9.172-06 8.94E-06 SR-91 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-92 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Y-92 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 ZR-95 Ci 0.00E 00 0.00E 00 3.31E-04 1.40E-04 NB-95 Ci 0.00E 00 0.00E 00 1 10E-03

~ 1.18E-03 ZR-97 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NB-97 Ci 0.00E 00 0.00E 00 2.19E-04 4.73E-05 TC-99M Ci 0.00E 00 0.00E 00 6.93E-06 0.00E 00 MO-99 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 RU-103 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 AG-110 Ci 0.00E 00 0.00E 00 1.01E-03 3.98E-03 SN-113 Ci 0.00E 00 0.00E 00 6.82E-05 0.00E 00 SB-122 Ci 0.00E 00 0.00E 00 3.85E-05 1.81E-06 SB-124 Ci 0.00E 00 0.00E 00 2.98E-03 7.82F 03 SB-125 Ci 0.00E 00 0.00E 00 6.64E-03 7.86E-03 16

)I FLORIDA POWER A LIGHT COMPANY ST. LUCIE UNIT ¹ 2 ANNUALREPORT JANUARY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3.4-2 LIQUIDEFFLUENTS (continued)

Continuous Mode Batch Mode RELEASED. UNIT QTR¹1 QTR¹2 QTIQ1 QTR¹2 TE-129 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TE-129M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 2.86E-04 0.00E 00 TE-132 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 I-132 Ci 0.00E 00 0.00E 00 0.00E 00 5.92E-05 I-133 Ci 0.00E 00 0.00E 00 5.97E-05 0.00E 00 I-134 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00

, CS-134 Ci 0.00E 00 0.00E 00 1.21E-03 1.38E-04 I-135 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CS-136 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CS-137 Ci 0.00E 00 0.00E 00 3.23E-03 3.53E-04 CS-138 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 BA-140 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 LA-140 Ci 0.00E 00, 0.00E 00 '.23E-04 0.00E 00 CE-141 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CE-144 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 PR-144 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 W-187 Ci 0.00E 00 0.00E'00 0.00E 00 0.00E 00 NP-239 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TOTALFOR PERIOD Ci 0.00E 00 0.00E 00 5.31E-02 6.39E-02 AR-41 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-85M Ci 0.00E 00 0.00E 00 7.98E-05 0.00E 00 KR-85 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-87 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-88 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-131M Ci 0.00E 00 0.00E 00 9.55E-04 0.00E 00 XE-133M Ci 0.00E 00 0.00E 00 5.97E-03 0.00E 00 XE-133 Ci 0.00E 00 0.00E 00 3.'01E-01 2.26E-04 XE-135M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-135 Ci 0.00E 00 0.00E 00 3.87E-03 1.14E-05 P

17

I ~I FLORIDA PO%ER 8r, LIGHT COMPANY ST. LUCIE UNIT ¹ 2 ANNUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3A-2 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTR¹3 QTR¹4 QTR¹3 QTR¹4 NA-24 Ci 0.00E 00 0.00E 00 1.51E-04 2.46E-04 CR-51 Ci -

0.00E 00 0.00E 00 6.80E-03 1.638-02 MN-54 Ci 0.00E 00 0.00E 00 8.78E-04 1.46E-03 FE-55 Ci 0.00E 00 0.00E 00 1.49E-02 2.41E-02 MN-56 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00.

CO-57 Ci 0.00E 00 0.00E 00 0.00E 00 2.95E-04 CO-58 Ci 0.00E 00 0.00E 00 9.16E-03 1.82E-01 FE-59 Ci 0.00E 00 0.00E 00 2.90E-04 2.35E-03 CO-60 Ci 0.00E 00 0.00E 00 1.05E-02 4.99E-03 ZN-65 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NI-65 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 BR-82 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 RB-88 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-89 Ci 0.00E 00 0.00E 00 4.42E-05 3.99E-05 SR-90, Ci 0.00E 00 0.00E 00 6.37E-06 1.66E-05

.Y-90 Ci 0.00E 00 0.00E 00 6.37E-06 1.66E-05 SR-91 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-92 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Y-92 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 ZR-95 Ci 0.00E 00 0.00E 00 1.50E-03 2.47E 03 NB-95 Ci 0.00E 00 0.00E 00 2'.37E-03 3.88E 03 ZR-97 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NB-97 Ci 0.00E 00 0.00E 00 3.07E-05 8.61E-05 TC-99M Ci 0.00E 00 0.00E 00 1.03E-05 0.00E 00 MO-99 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 RU-103 Ci 0.00E 00 0.00E 00 0.00E 00 3.08E-05 AG-110 Ci 0.00E 00 0.00E 00 2.57E-03 9.09E-04 SN-113 Ci 0.00E 00 0.00E 00 1.32E-04 1.22E-03 SB-122 Ci 0.00E 00 0.00E 00 8.75E-04 4.20E-04 SB-124 Ci 0.00E 00 0.00E 00 1.74E-02 1.59E-02 SB-125 Ci 0.00E 00 0.00E 00 2.35E-02 3.74E-02 18,

FLORIDA POWER 4 LIGHT COMPANY ST. LUCIE UNIT ¹ 2 ANNUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.4-2 LIQUIDEFFLUENTS (continued)

Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTR¹3 QTR¹3 QTR¹4 TE-129 Ci 0.00E 00 0.00E 00 1.73E-03 4.65E-03 TE-129M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 I-131 Ci 0.00E 00 0.00E 00 9.55E-05 7.40E-05 TE-132 Ci 0.00E 00 0.00E 00 0.00E 00 1.62E-05 I-132 Ci 0.00E 00 0.00E 00 6.71E-05 9.58E-05 I-133 Ci 0.00E 00 0.00E 00 2.03E-04 0.00E 00 I-134 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CS-134 Ci 0.00E 00 0.00E 00 2.59E-03 6.54E-03 I-135 Ci 0.00E 00 0.00E 00 9.85E-05 0.00E 00 CS-136 Ci 0.00E 00 0.00E 00 0.00E 00 1.13E-05 CS-137 Ci 0.00E 00 0.00E 00 2.71E-03 6.40E-03 CS-138 Ci 0.00E 00 '.00E 00 9.63E-05 1.34E-04 BA-140 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 LA-140 Ci 0.00E 00 0.00E 00 8.70E-04 2.67B.04 CE-141 Ci 0.00E 00 0.00E 00 0.00E 00 6.55E-05 CE-144 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 PR-144 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 W-187 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NP-239 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TOTAL FOR PERIOD Ci 0.00E 00 0.00E 00 9.95E-02 3.12E-01 AR-41 Ci 0.00E 00 0.00E 00 2.46E-05 0.00E 00 KR-85M Ci 0.00E 00 0.00E 00 1.58E-05 0.00E 00 KR-85 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-87 Ci 0.00E 00 0.00E 00 0.00E 00 '.00E 00 KR-88 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-131M Ci 0.00E 00 0.00E 00 9.54E-04 2.28E-04 XE-133M Ci 0.00E 00 0.00E 00 2.13E-03 4.53E-04 XE-133 Ci 0.00E 00 0.00E 00 1.19E-01 6.32E-02 XE-135M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-135 Ci 0.00E 00 0.00E 00 3.77E-03 1.17E-04 19

FLORIDAPOWER Ec LIGHT COMPANY ST. LUCIE UNIT 8 1 ANNUALREPORT JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.5-1 LIQUIDEFFLUENTS - DOSE SUMMATION AGE GROUP: ADULT LOCATION: ANYADULT

'XPOSURE INTERVAL: JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 FISH AND SHELLFISH ORGAN mrem Bone 4.30E-02 Liver 1.89E-01 Thyroid 9.17E-04 Kidney 1.35E-03 Lung 2.22E-01 GI-LLI 1.90E-01 Total Body 5.31E-02 20

FLORIDAPOWER 2 LIGHT COMPANY ST. LUCIE UNIT 8 2 ANNUALREPORT JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.5-2 LIQUIDEFFLUENTS - DOSE SUMMATION AGE GROUP: ADULT LOCATION: ANYADULT EXPOSURE INTERVAL: JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 FISH AND SHELLFISH DOSE ORGAN mrem Bone 4.25E-02 Liver 1.88E Thyroid 9.17E-04 Kidney 1.34E-03 Lung 2.21E-01 GI-LLI 1.89E-01 Total Body 5.26E-02 21

t I FLORIDA POWER 8'c LIGHT COMPANY ST. LUCIE UNIT 8 1 ANNUALREPORT JANUARY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3.6-1 GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES UNIT QTfQ1 QTIQ2 A. Fission and Activation Gases

1. Total Release Ci 9.97E 01 2.88E 01

2. Average Release Rate For Period uci/sec 1.28E 01 3.66E 00 B. Iodines 1., Total Iodine-131 Ci 2.61E-04 1.20E-04

2. Average Release Rate For Period uCi/sec 3.36E-05 1.52E-05 C. Particulates

1. Particulates (Half Life > 8 days) Ci 2.76E-05 1.09E-05

2. Average Release Rate For Period uCi/sec 3.55E-06 1.39E-06

3. Gross Alpha Radioactivity =

Ci 1.15E-07 6.81E-08 D. Tritium

1. Total Release Ci 2.06E 00 5.35E 00

2. Average Release Rate For Period uCi/sec 2.65E-01 6.80E-01 22

FLORIDA POWER 8h LIGHT COMPANY ST. LUCIE UNIT ¹ 1 ANNUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.6-1 GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES UNIT QTlN3 QTR¹4 A. Fission and Activation Gases

1. Total Release Ci 5.71E 00 1.06E 01

2. Average Release Rate For Period uCi/sec 7.19E-01 1.34E 00 B. Iodines

1. Total Iodine-131 Ci 9.60E-05 3.74E-06

2. Average Release Rate For Period uCi/sec 1.21E-05 4.71E-07 C. Particulates

1. Particulates (Half Life > 8 days) Ci 5.51E-05 5.81E'-05

2. Average Release. Rate For Period uCi/sec 6.94E-06 7.31E-06

3. Gross Alpha Radioactivity Ci 6.74E-08 5.21E-08 D. Tritium

1. Total Release Ci 3.63E 01 2.94E 00

2. Average Release Rate For Period uCi/sec 4.57E 00 3.69E-01 23

FLORIDA POWER 2 LIGHT COMPANY ST. LUCIE UNIT ¹ 2 ANNUALREPORT JURY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3.6-2 GASEOUS EFFLUENTS - SUMMATION OF ALLREL&BES UNIT QTfS1 QTf82 A. Fission and Activation Gases

1. Total Release Ci 2.37E 01 2.42E 01

2. Average Release Rate For Period uCi/sec 3.05E 00 3.08E 00 B. Iodines

1. Total Iodine-131 Ci 2.35E-03 8.56E-06

2. Average Release Rate For Period uCi/sec 3.02E-04 1.09E-06 C. Particulates

1. Particulates (Half Life > 8 days) Ci 6.68E-06 1.21E-06

2. Average Release Rate For Period uCi/sec 8.59E-07 1.53E-07

3. Gross Alpha Radioactivity Ci 9.48E-08 1.06E-07 D. Tritium I. Total Release Ci 3.85E 00 3.08E 00

2. Average Release Rate For Period uCi/sec 4.95E-01 3.91E-01 24

FLORIDA POWER & LIGHT COMPAbK ST. LUCIE UNIT ¹ 2 ANNUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.6-2 GASEOUS EFFLUENTS - SVIvMATIONOF ALLRELEASES UNIT QTf@3 QTR¹4 A. Fission and Activation Gases

1. Total Release Ci 1.85E 02 8.35E 00

2. Average Release Rate For Period uCi/sec 2.33E 01 1.05E 00 B. Iodines

. 1. Total Iodine-131 Ci 1.28E-05 1.14E-04

2. Average Release Rate For Period uCi/sec 1.61E-06 1.43E-05 C. Particulates

1. Particulates (Half Life ) 8 days) Ci 1.54E-05 3.82E-05

2. Average Release Rate For Period uCi/sec 1.93E-06 4.81E-06

3. Gross Alpha Radioactivity Ci 1.39E-08 1.50E-07 D. Tritium

1. Total Release Ci 1.39E 01 6.94E 00

2. Average Release Rate For Period uCi/sec 1.75E 00 8.73E-01 25

FLORIDAPOWER &, LIGHT COMPANY ST. LUCIE UNIT ¹ 1 ANNUALREPORT JANUARY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3.7-1 GASEOUS EFFLUENTS - GROUND LEVELRELEASES Nuclides Continuous Mode Batch Mode Released Unit QTR¹l QTR¹2 QTR¹1 QTR¹2

1. Fission Gases AR-41 Ci 0.00E 00 0.00E 00 1.27E-01 0.00E 00 KR-85M Ci 0.00E 00 0.00E 00 2.02E-02 0.00E 00 KR-85 Ci 1.64E-01 0.00E 00 5.08E-01, 0.00E 00 KR-87 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-88 Ci 0.00E 00 0.00E 00 1.32E-03 0.00E 00 KR-89 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-90 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-127 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-131M Ci 0.00E 00 0.00E 00 3.31E-01 6.46E-03 XE-133M Ci 0.00E 00 1.83E 00 1.09E 00 3.45E-03 XE-133 Ci . 2.83E 01 2.43E 01 6.51E 01 5.02E-01 XE-135M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-135 Ci 2.68E 00 2.18E 00 1.33E 00 0.00E 00 XE-137 Ci 0.00E 00 0.00E 00 . 0.00E 00 0.00E 00 XE-138 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Total for Period Ci 3.11E 01 2.83E 01 6.85E 01 5.12E-01

2. Iodines I-131 Ci 2.61E-04 1.20E-04 I-132 Ci 0.00E 00 0.00E 00 I-133 Ci 5.86E-04 8.67E-04 I-134 Ci 0.00E 00 0.00E 00 I-135 Ci 0.00E 00 0.00E 00 Total for Period Ci 8.47E-04 9.87E-04 Particulates (> 8 Days)

Cr-51 Ci 0.00E 00 0.00E 00 Mn-54 Ci 0.00E 00 0.00E 00 Fe-55 Ci 0.00E 00 0.00E 00 Co-57 Ci 0.00E 00 0.00E 00 Co-58 Ci 0.00E 00 0.00E 00 Fe-59 Ci 0.00E 00 0.00E 00 Co-60 Ci 5.20E-06 9.98E-06 Zn-65 Ci 0.00E 00 0.00E 00 Zr-95 Ci 0.00E 00 0.00E 00 Nb-95 Ci 0.00E 00 0.00E 00 26

FLORIDAPOWER & LIGHT COMPANY ST. LUCIE UNIT ¹ 1 ANNUALREPORT JANUARY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3.7-1 GASEOUS EFFLUENTS - GROUND LEVELRELEASES (continued)

Nuclides Continuous Mode Released Unit QTR¹l QTR¹2

3. Particulates (> 8 Days) (continued)

Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 4.70E-07 Y-90 Ci 0.00E 00 4.70E-07 RU-103 Ci 0.00E 00 0.00E 00 Ag-110 Ci 0.00E 00 0.00E 00 Sn-113 Ci 0.00E 00 0.00E 00 Sb-124 Ci 0.00E 00 0.00E 00 Sb-125 Ci 0.00E 00 0.00E 00 Te-129m Ci 0.00E 00 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00 Cs-136 Ci 0.00E 00 0.00E 00 Cs-137 Ci 2.24E-05 0.00E 00 Ba-140 Ci 0.00E 00 0.00E 00 Total for Period Ci 2.76E-05 1.09E-05

4. Particulates (< 8 Days)

Mn-56 Ci 0.00E 00 0.00E 00 Ni-65 Ci 0.00E 00 0.00E 00 Br-82 Ci 0.00E 00 0.00E 00 Rb-88 Ci 0.00E 00 0.00E 00 Rb-89 Ci 0.00E 00 0.00E 00 Sr-91 Ci 0.00E 00 0.00E 00 Sr-92 Ci 0.00E 00 0.00E 00 Y-92 Ci 0.00E 00 0.00E 00 Zr-97 Ci 0.00E 00 0.00E 00 Nb-97 Ci 0.00E 00 00 '.00E Tc-99m Ci 0.00E 00 0.00E 00 Mo-99 Ci 0.00E 00 0.00E 00 Sb-122 Ci 0.00E 00 0.00E 00 Te-129 Ci 0.00E 00 0.00E 00 Te-132 Ci 0.00E 00 0.00E 00 Cs-138 Ci 0.00E 00 0.00E 00 La-140 Ci 0.00E 00 0.00E 00 Pr-144 Ci 0.00E 00 0.00E 00 W-187 Ci 0.00E 00 0.00E 00 Np-239 Ci 0.00E 00 0.00E 00 Total for Period Ci 0.00E 00 0.00E 00 27

FLORIDAPOWER 8'c LIGHT COMPANY ST. LUCIE UNIT ¹ 1 ANNUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.7-1 GASEOUS EFFLUENTS - GROUND LEVELRELEASES Nuclides Continuous Mode Batch Mode Released Unit QTR¹3 QTR¹4 QTR¹3 QTR¹4

1. Fission Gases AR-41 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-85M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-85 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-87 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-88 Ci 0.00E 00 O.OOE 00 0.00E 00 0.00E 00 KR-89 Ci 0.00E 00 O.OOE 00 0.00E 00 0.00E 00 KR-90 Ci 0.00E 00 0.00E 00 .0.00E 00 0.00E 00 XE-127 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-131M Ci 0.00E 00 0.00E 00 6.01E-02 0.00E 00 XE-133M Ci 0.00E 00 0.00E 00 4.57E-02 6.49E-04 XE-133 Ci 2.12E 00 6.11E 00 2.66E 00 2.25E-02 XE-135M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-135 Ci 7.80E-01 4.49E 00 4.81E-02 1.98E-03 XE-137 Ci 0.00E 00 0.00E 00 O.OOE 00 0.00E 00 XE-138 Ci 0.00E 00 0.00E 00 O.OOE 00 0.00E 00 Total for Period Ci 2.90E 00 1.06E 01 2.81E 00 2.52E-02

2. Iodines I-131 Ci 9.60E-05 3.74E-06 I-132 Ci 0.00E 00 0.00E 00 I-133 Ci 0.00E 00 0.00E 00 I-134 Ci 0.00E 00 0.00E 00 I-135 Ci 0.00E 00 0.00E 00 Total for Period Ci 9.60E-05 3.74E-06

3. Particulates (> 8 Days)

Cr-51 Ci 0.00E 00 0.00E 00 Mn-54 Ci 0.00E 00 0.00E 00 FE-55 Ci 0.00E 00 0.00E 00 Co-57 Ci 0.00E 00 0.00E 00 Co-58 Ci 0.00E 00 0.00E 00 FE-59 Ci 0.00E 00 4.10E-05 Co-60 Ci 1.21E-05 5.98E-06 Zn-65 Ci 0.00E 00 0.00E 00 Zr-95 Ci O.OOE 00 0.00E 00 Nb-95 Ci 0.00E 00 0.00E 00 28

FLORIDAPOWER & LIGHT COMPANY ST. LUCIE UNIT 8 1 ANNUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE3.7-1 GASEOUS EFFLUENTS - GROUND LEVELRELEASES (continued)

Nuclides Continuous Mode Released Unit QTRP3 QTRu4

3. Particulates ( > 8 Days) (continued)

Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 0.00E 00 1.89E-06 Y-90 Ci 0.00E 00 1.89E-06 Ru-103 Ci 0.00E 00 0.00E 00 Ag-110 Ci 0.00E 00 0.00E 00 Sn-113 Ci 0.00E 00 0.00E 00 Sb-124 Ci 0.00E 00 0.00E 00 Sb-125 Ci 0.00E 00 0.00E 00 TE-129m Ci 2.71E-05 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00 Cs-136 Ci 0.00E 00 8.74E-07 Cs-137 Ci 1.60E-05 6.48E-06 Ba-140 Ci 0.00E 00 0.00E 00 Total for Period Ci 5.51E-05 5.81E-05

4. Particulates (< 8 Days)

Mn-56 Ci 0.00E 00 0.00E 00 Ni-65 Ci 0.00E 00 0.00E 00 Br-82 Ci 0.00E 00 0.00E 00 Rb-88 Ci 0.00E 00 0.00E 00 Rb-89 Ci 0.00E 00 0.00E 00 Sr-91 Ci 0.00E 00 0.00E 00 Sr-92 Ci 0.00E 00 0.00E 00 Y-92 Ci 0.00E 00 0.00E 00 Zr-97 Ci 0.00E 00 0.00E 00 Nb-97 Ci 0.00E 00 0.00E 00 Tc-99m Ci 0.00E 00 0.00E 00 Mo-99 Ci 0.00E 00 0.00E 00 Sb-122 Ci 0.00E 00 0.00E 00 TE-129 Ci 0.00E 00 0.00E 00 TE-132 Ci 0.00E 00 0.00E 00 Cs-138 Ci 0.00E 00 0.00E 00 La-140 Ci 0.00E 00 0.00E 00 Pr-144 Ci 0.00E 00 0.00E 00 W-187 Ci 0.00E 00 0.00E 00 Np-239 Ci 0.00E 00 0.00E 00 Total for Period Ci 0.00E 00 0.00E 00 29

FLORIDAPOWER & LIGHT COMPANY ST. LUCIE UNIT 8 2 ANNUALREPORT JANUARY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3.7-2 GASEOUS EFFLUEN'I'S - GROUND LEVELRELEASES Nuclides Continuous Mode Batch Mode Released Unit QTE$ 1 QTEQ2 QTEQ1 QT1@2

1. Fission Gases AR-41 Ci 0.00E 00 2.37E 00 2.26E-01 1.98E-01 KR-85M Ci 0.00E 00 0.00E 00 5.75E-04 2.45E-03 KR-85 Ci 0.00E 00 0.00E 00 6.74E-02 0.00E 00 KR-87 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-88 Ci 2.11E-01 0.00E 00 0.00E 00 1.52E-03 KR-89 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-90 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-127 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-131M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-133M Ci 0.00E 00 0.00E 00 0.00E 00 6.40E-03 XE-133 Ci 1.69E 01 1.44E 01 3.40E-01 6.44E-01 XE-135M Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-135 Ci 5.89E 00 6.59E 00 2.73E-02 5.05E-02 XE-138 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Total for Period Ci 2.30E 01 2.33E 01 6.61/-01 9.04E-01

2. Iodines I-131 Ci 2.35E-03 8.56E-06 I-132 Ci 0.00E 00 0.00E 00 I-133 Ci 1.84E-04 4.91E-05 I-134 Ci 0.00E 00 0.00E 00 I-135 Ci 0.00E 00 0.00E 00 Total for Period Ci 2.53E-03 5.76E-05

3. Particulates (> 8 Days)

Cr-51 Ci 0.00E 00 0.00E 00 Mn-54 Ci O.OOE 00 0.00E 00 Fe-55 Ci 0.00E 00 0.00E 00 Co-57 Ci O.OOE 00 0.00E 00 Co-58 Ci 0.00E 00 0.00E 00 Fe-59 Ci 0.00E 00 . 0.00E 00 Co-60 Ci 4.16E-06 0.00E 00 Zn-65 Ci O.OOE 00 0.00E 00 Zr-95 Ci 0.00E 00 0.00E 00 Nb-95 Ci 0.00E 00 0.00E 00 30

~ 4 FLORIDAPOWER & LIGHT COMPANY ST. LUCIE UNIT 4 2 ANNUALREPORT JANUARY 1, 1995 THROUGH JUNE 30, 1995 TABLE 3.7-2 GASEOUS EFFLUENTS - GROUND LEVELRELEASES (continued)

Nuclides Continuo us Mode Released Unit QTEQ1 QTEUf2

3. Particulates (> 8 Days) (continued)

Sr-89 Ci 0.00E 00 0.00E 00 Sr-90 Ci 1.26E-06 6.03E-07 Y-90 Ci 1.26E-06 6.03E-07 Ru-103 Ci 0.00E 00 0.00E 00 Ag-110 Ci 0.00E 00 0.00E 00 Sn-113 Ci 0.00E 00 0.00E 00 Sb-124 Ci 0.00E 00 0.00E 00 Sb-125 Ci 0.00E 00 0.00E 00 Te-129m Ci 0.00E 00 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00 Cs-136 Ci 0.00E 00 0.00E 00 Cs-137 Ci 0.00E 00 0.00E 00 Ba-140 Ci 0.00E 00 0.00E 00 Total for Period Ci 6.68E-06 1.21E-06

4. Particulates (< 8 Days)

Mn-56 Ci 0.00E 00 0.00E 00 Ni-65 Ci 0.00E 00 0.00E 00 Br-82 Ci 0.00E 00 0.00E 00 Rb-88 Ci 0.00E 00 0.00E 00 Rb-89 Ci 0.00E 00 0.00E 00 Sr-91 Ci 0.00E 00 0.00E 00 Sr-92 Ci 0.00E 00 0.00E 00 Y-92 Ci 0.00E 00 0.00E 00 Zr-97 Ci 0.00E 00 0.00E 00 Nb-97 Ci 0.00E 00 0.00E 00 Tc-99m Ci 0.00E 00 0.00E 00 Mo-99 Ci 0.00E 00 0.00E 00 Sb-122 Ci 0.00E 00 0.00E 00 Te-129 Ci 0.00E 00 0.00E 00 Te-132 Ci 0.00E 00 0.00E 00 Cs-138 Ci 0.00E 00 0.00E 00 La-140 Ci 0.00E 00 0.00E 00 Pr-144 Ci 0.00E 00 0.00E 00 W-187 Ci 0.00E 00 0.00E 00 Np-239 Ci 0.00E 00 0.00E 00 Total for Period Ci 0.00E 00 0.00E 00 31

FLORIDAPOWER Ec LIGHT COMPANY ST. LUCIE UNIT ¹ 2 AIWUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.7-2 GASEOUS EFFLUENTS - GROUND LEVELRELEASES Nuclides Continuous Mode Batch Mode Released Unit QTR¹3 QTR¹4 QTR¹3 QTR¹4

1. Fission Gases AR-41 Ci 4.72E 01 0.00E 00 2.15E-01 3.33E-02 KR-85M Ci 3.73E 00 0.00E 00 3.66E-03 4.61E-04 KR-85 Ci 0.00E 00 0.00E 00 1.72E-02 0.00E 00 KR-87 Ci 3.60E 00 0.00E 00 2.51E-04 0.00E 00 KR-88 Ci 6.63E 00 0.00E 00 4.45E-03 0.00E 00 KR-89 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-90 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-127 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-131M Ci 1.70E 01 0.00E 00 0.00E 00 0.00E 00 XE-133M Ci 0.00E 00 0.00E 00 8.03E-03 2.21E-02 XE-133 Ci 3.09E 01 5.61E 00 5.53E-01 1.22E 00 XE-135M Ci 1.26E 01 0.00E 00 0.00E 00 0.00E 00 XE-135 Ci 5.89E 01 1.42E 00 7.14E-02 4.30E-02 XE-137 Ci 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-138 Ci 3.85E 00 0.00E 00 0.00E 00 0.00E 00 Total for Period Ci 1.84E 02 7.03E 00 8.73E-01 1.32E 00

2. Iodines I-131 Ci 1.28E-.05 1.14E-04 I-132 Ci 0.00E 00 0.00E 00 I-133 Ci 7.36E-05 6.86E-04 I-134 Ci 0.00E 00 0.00E 00 I-135 Ci 0.00E 00 0.00E 00 Total for Period Ci 8.64E-05 8.00E-04

3. Particulates (> 8 Days)

Cr-51 Ci 0.00E 00 0.00E 00 Mn-54 Ci 0.00E 00 0.00E 00 FE-55 Ci 0.00E 00 0.00E 00 Co-57 Ci 0.00E 00 0.00E 00 Co-58 Ci 0.00E 00 4.88E-06 FE-59 Ci 0.00E 00 0.00E 00 Co-60 Ci 0.00E 00 8.56E-06 Zn-65 Ci 0.00E 00 0.00E 00 Zr-95 Ci 0.00E 00 0.00E 00 Nb-95 Ci 0.00E 00 0.00E 00 32

FLORIDAPOWER Bc LIGHT COMPANY ST. LUCIE UNIT 8 2 ANNUALREPORT JULY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.7-2 GASEOUS EFFLUENTS - GROUND LEVELRELEASES (continued)

Nuclides Continuous Mode Released Unit QTRu3 QTRu4

3. Particulates (> 8 Days) (continued)

Sr-89 Ci 0.00E 00 4.08E-07 Sr-90 Ci 0.00E 00 2.14E-06 Y-90 Ci 0.00E 00 2.14E-06 Ru-103 Ci 0.00E 00 0.00E 00 Ag-110 Ci 0.00E 00 0.00E 00 Sn-113 Ci 0.00E 00 0.00E 00 Sb-124 Ci 0.00E 00 0.00E 00 Sb-125 Ci 0.00E 00 0.00E 00 TE-129m Ci 0.00E 00 0.00E 00 Cs-134 Ci 0.00E 00 0.00E 00 Cs-136 Ci 0.00E 00 0.00E 00 Cs-137 Ci 1.54E-05 1.76E-05 Ba-140 Ci 0.00E 00 0.00E 00 Total for Period Ci 1.54E-05 3.82E-05

4. Particulates (< 8 Days)

Mn-56 Ci 0.00E 00 0.00E 00 Ni-65 Ci 0.00E 00 0.00E 00 Br-82 Ci 0.00E 00 0.00E 00 Rb-88 Ci 0.00E 00 0.00E 00 Rb-89 Ci 0.00E 00 0.00E 00 Sr-91 Ci 0.00E 00 0.00E 00 Sr-92 Ci 0.00E 00 0.00E 00 Y-92 Ci 0.00E 00 0.00E 00 Zr-97 Ci 0.00E 00 0.00E 00 Nb-97 Ci 0.00E 00 0.00E 00 Tc-99m Ci 0.00E 00 0.00E 00 Mo-99 Ci 0.00E 00 0.00E 00 Sb-122 Ci 0.00E 00 0.00E 00 TE-129 Ci 0.00E 00 0.00E 00 TE-132 Ci 0.00E 00 0.00E 00 Cs-138 Ci 0.00E 00 0.00E 00 La-140 Ci 0.00E 00 0.00E 00 Pr-144 Ci 0.00E 00 0.00E 00 W-187 Ci 0.00E 00 0.00E 00 Np-239 Ci 0.00E 00 0.00E 00 Total for Period Ci 0.00E 00 0.00E 00 33

I I FLORIDAPOWER & LIGHT COMPANY ST. LUCIE UNIT 8 1 ANNUALREPORT JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.8-1 GASEOUS EFFLUENTS - DOSE SUMMATION AGE GROUP: INFANT EXPOSURE INTERVAL:JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 Note: The below dose results were calculated using actual meteorological data during the specified time interval with Met data reduced as Per Reg. Guide 1.111, March 1976 Bone Liver Thyroid Kidney Pathway mrem mrem mrem mrem GROUND PLANE(a)

COW- MILK (b) 7.54E-05 4.75E-04 8.54E-03 1.83E-04 INHALATION(a) 1.99E-06 4.08E-04 6.74E-04 1.76E-04

'OTAL 7.74E-05 8.83E-04 9.21E-03 3.59E-04 LUNG GI-LLI T.BODY Pathway mrem mrem mrem GROUND PLANE(a) 1.33E-04 COW - MILK (b) 4.03E-04 3.98E-04 4.16E-04 INHALATION (a) 4.08E-04 4.03E-04 4.03E-04 TOTAL 8.11E-04 8.01E-04 9.52E-04 (a) Sector: SE Range: 1.5 miles (b) Sector: SE Range: 4.25 miles(default)

NOBLE GASES mrad GAMMAAIR DOSE 1.66E-03 BETA AIR DOSE 4.05E-03 Sector: SE Range: 1.5 miles 34

s FLORIDAPOWER 8c LIGHT COMPANY

.ST. LUCIE UNIT 8 2 ANNUALREPORT JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.8-2 GASEOUS EFFLUENTS - DOSE SUhBMTION AGE GROUP: INFANT EXPOSURE INTERVAL:JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 Note: The below dose results were calculated using actual meteorological data during the speciQed time interval with Met data reduced as Per Reg. Guide 1.111, March 1976 Bone Liver Thyroid Kidney Pathway mrem mrem mrem mrem GROUND PLANE (a)

COW - MILK (b) 1.52E-04 4.01E-04 4.10E-02 1.37E-04 INHALATION(a) 3.59E-06 2.42E-04 1.04E-03 1.05E-04 TOTAL 1.55E-04 6.44E-04 4.20E-02 2.42E-04 LUNG GI-LLI T.BODY Pathway mrem mrem mrem GROUND PLANE(a) 7.32E-05 COW - MILK (b) 2.40E-04 2.41E-04 3.15E-04 INHALATION(a) 2.42E-04 2.40E-04 2.41E-04 TOTAL 4.83E-04 4.80E-04 6.29E-04 (a) Sector: SE Range: 1.5 miles (b) Sector: SE Range: 4.25 miles(default)

NOBLE GASES mrad GAh9rfA AIR DOSE 2.00E-02 BETA AIRDOSE 1.26E-02 Sector: SE Range: 1.5 miles 35

E I 0

FLORIDAPOWER AND LIGHT COMPANY ST. LUCIE PLANT ANNUALREPORT JANUARY, 1995 THROUGH DECEMBER 31, 1995 UNITS 1 AND 2, TABLE 3.9 A. Solid Waste Shipped Off-Site for Burial or Disposal

1. Type of Waste Unit 12 Mo. Period Error %

a. Spent Resin, M3 2.92 E+ 1 Process Filters Ci 1.43 E+ 2 2.0E+ 1

b. Dry Compressible M3 5.46 E+ 1 Waste (Note 5) Ci 911E+0 2.0E+ 1

c. Irradiated M3 0.00 E+ 0 Components Ci 0.00 E+ 0 N/A *

d. Other M3 0.00 E+ 0 Ci 0.00 E+ 0 N/A *

2. Estimate of Major Nuclide Composition (By Waste Type)

Category Nuclides

a. Ni 63 3.30 E+ 1 Cs 137 1.85 E+ 1 Fe 55 1.82 E+ 1 Co 60 9.88 E+ 0 Cs 134 5.77 E+ 0 Sb 125 5.40 E+ 0 Co 58 4.68 E+ 0 Mn 54 3.13 E+ 0 Fe 55 3.97E+ 1 Cs 137 1.98 E+ 1 Co 60 1.86 E+ 1 Ni 63 7.73 E+ 0 Co 58 3.80 E+ 0 Cs 134 2.61 E+ 0 Mn 54 2.08 E+ 0 Sb 125 1.61 E+ 0 Nb 95 1.28 E+ 0 C 14 7.26E- 1 36

FLORIDA POWER AND LIGHT COMPAbK ST. LUCIE PLANT ANNUALREPORT JANUARY, 1995 THROUGH DECEMBER 31, 1995 UNITS 1 AND 2, TABLE 3.9 A. Solid Waste Shipped Off-Site for Burial or Disposal (continued)

2. Estimate of Major Nuclide Composition (continued)

Category Nuclide C. N/A

N/A *

d. N/A* N/A *

3. Solid Waste Disposition Number of Mode of Transportation Destination Shipments Sole Use Truck Bamwell, S.C.

Sole Use Truck S.E.G., Oak Ridge, TN B. hradiated Fuel Shipments Number of . Mode of Transportation Destination Shipments N/A *

N/A= Not Applicable 37

I \

ANNUA 0RT JANUARY 1, 1996 THROUGH DECEMBER 31, 1996 UNITS 1 AND 2, TABLE 3.9 (CONTINUED)

Waste Total Total Curies Principal Type of Waste Category Type of Container Solidification Class Volume (Note 1) Radio nuclides (Note 3) Reg-Guide (Note 4) Agent Cubic Ft. (Notes 1 8 2) 1.21 Class A 1524.6 3.287 N/A PWR Compactible. 1.b Non-Specification None Trash (Note 5) Strong Tight Package Class A 32.6 3.05E-04 N/A PWR lon Exchange 1.a Non-SpecNcation None Resin Strong Tight Package Class A 404.2 5.825 NP, Cs'" PWR Compactible NRC Certified LSA None Trash Type A Class A 411.6 4.014 NI63 CS137 PWR lon Exchange 1.a NRC Certified LSA None Resin > Type A Class B 385.1 135.806 NP, Sr, Cs'" PWR lon Exchange 1.a NRC CeNffed LSA None C", Sum Nuclides Resin > Type A T'~ ( 5 Years Class C 202.1 2.934 Ni~, Tru, Sr PWR Process 1.a NRC Certified LSA None Cs137 Pu241 Co60 Filters > Type A Sum Nuclides T'5 Years 38

FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT ANNUALREPORT JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 UNITS 1 AND 2, TABLE 3.9 (CONTINUED)

SOLID WASTE SUPPLEMIWT NOTE 1: The total curie quantity and radionuclide composition of solid waste shipped from the St. Lucie Plant, Units 1 and 2 are determined using a combination of qualitative and quantitative techniques. In general, the St. Lucie Plant follows the guidelines outlined in the Low Level Waste Licensing Branch Technical Position (BTP) on Radioactive Waste Classification (5/11/83) for these determinations.

The most fiequently used techniques for determiiung the total curie quantity in a package are the dose to curie methods and the (concentration) x (volume or mass) calculations. Where appropriate, engineering type activation analyses may be applied. Since each of the above methodologies involves to some extent qualitative parameters, the total curie quantity is considered to be an estimate.

The composition of radionuclides in the waste is determined by both on-site analyses for principal gamma emitters and periodic off-site analyses for other radionuclides. The on-site analyses are performed either on a batch basis or on a routine basis using reasonably representative sample as appropriate for the waste type. Off-site analyses are used to establish scaling factors or other estimates for radionuclides such as FP, C'", Fe", Ni~, Sr, Tc, I'~,

P 238 ~9/240 P 241 A 241 Cm242 and Cm243fA4 NOTE 2: "Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than 0.01 times the concentration of the nuclides listed in Table 1 or 0.01 times the smallest concentration of the nuclides listed in Table 2 of 10 CFR 61.

NOTE 3: "Type of Waste" is generally specified as described in NUREG 0782, Draft Environmental Impact Statement on 10 CFR 61, "Licensing Requirements for Land Disposal of Radioactive Waste".

NOTE 4: "Type of Container" refers to the transport package.

NOTE 5: The volume and activity listed for Dry Compressible Waste represent the quantity of material that during the reporting period was sent to the Barnwell, South Carolina burial facility.

This material was shipped to a contracted vendor for volume reduction prior to final disposal at the Barnwell, South Carolina burial facility. During the reporting period, six shipments of Dry Compressible Waste ( 11,600 cubic feet, 1.283 curies) were made &om the St. Lucie Plant to the volume reduction facility. This material was shipped via "Sole Use Truck" in non-specification strong tight packages.

39

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT ¹ 1 ANNUALREPORT JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 TABLE 3.10 SEWAGE SLUDGE SHIPMENTS Number of Shipments: 6 Sample and analyses by Florida Department of Health and Rehabilitative Services(HRS):

Shipment No: 1 2 3 4 5 6 Sample Date Jan 13 Feb 28 Feb 28 May 02 Aug 17 Aug 17 Isotope conc.: pCi/gm pCi/gm pCi/gm pCi/gm pCi/gm pCi/gm K-40 8.00E-2 7.00E-2 7.00E-2 7.00E-2 7.00E-2 7.00E-2 Mn-54 1.17E-2 6.00E-3 6.00E-3 8.00E-3 <3.00E-3 <3.00E-3 Co-58 1.20E-2 1.20E-2 1.20E-2 5.00E-3 5.00E-3 Co-60 2.09E-1 3.09E-1 3.09E-1 2.17E-1 1.14E-1 1.14E-1 I-131 <2.40E-3 1.30E-2 1.30E-2 Cs-134 3.60E-3 <2.60E-3 3.50E-3 3.50E-3 Cs-137 2.24E-2 3.60E-2 3.60E-2 3.80E-2 2.30E-2 2.30E-2 Tl-201 1.50E-2 1.50E-2 < 6.70E-3 <6.00E-3 <6.00E-3 Tl-202 1.70E-3 1.70E-3 <2.70E-3 <2.00E-3 <2.00E-3, Ra-226 1.30E-2 <5.00E-2 <5.00E-2 Average of Multiple Sample Concentrations used. when provided.

FPL Calculated Curies by Shipment and Total(s):

Shipment No: 1 2 3 4 5 6 Date shipped Feb 01 Mar 14 Apr 14 May 22 Sep 20 Oct 13 Isotope Volume gals.: 2500 2500 800 5000 5000 4000 Total Curies Ci Ci Ci Ci Ci Ci Ci K-40 7.67E-7 6.69E-7 2.14E-7 1.34E-6 1.34E-6 1.07E-6 5.40E-6 Mn-54 1.12E-7 5.73E-8 1.84E-8 1.53E-7 0.00E 0 0.00E 0 3.41E-7 Co-58 0.00E 0 1.15E-7 3.67E-8 2.29E-7 9.56E-8 7.65E-8 5.53E-7 Co-60 2.00E-6 2.95E-6 9.45E-7 4.15E-6 2.18E-6 1.74E-6 1.40E-S I-131 0.00E 0 0.00E 0 0.00E 0 0.00E 0 2.49E-7 1.99E-7 4.48E-7 Cs-134 3.44E-8 0.00E 0 0.00E 0 0.00E 0 6.69E-8 5.35E-8 1.55E-7 Cs-137 2. 14E-7 3.44E-7 1.10E-7 7.26E-7 4.40E-7 3.52E-7 2.19E-6 Tl-201 0.00E 0 1.43E-7 4.59E-8 0.00E 0 0.00E 0 0.00E 0 1.89E-7 Tl-202 0.00E 0 1.62E-8 5.20E-9 0.00E 0 0.00E 0 0.00E 0 2.14E-8 Ra-226 0.00E 0 0.00E 0 0.00E 0 2.49E-7 0.00E 0 0.00E 0 2.49E-7 Total of all isotopes for all Shipments: 2.35E-5 Ci 40

FLORIDAPOWER k LIGHT COMPANY ST. LUCIE UNIT ¹ 1 AbMJALREPORT JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 Attachment - A UNPLANNED Liquid Release of August 19, 1995 Overfilling of the Primary Water Tank ¹ 1 Due to Personnel Error Description of the Event:

Event 95-50 documents this event. The following is a brief summary.

'n-house The Primary Water Tank(PWT) is an outdoor tank with an overflow line to the ground inside the Radiation Controlled Area. The tank normally consists of Tritium and trace isotopes Rom recycling of Boric Acid Distillate from the Boric Acid Recovery System. Clean make up water was being added to the Primary Water Tank using manual valves. Annunciator F-23 "Primary Water Tank Level High/Low" alarmed in the control room. The reactor operator instructed the Senior Nuclear Plant Operator(SNPO) to contact the AuxiliaryNuclear Plant Operator(ANPO) to secure the fillvalve to the PWT. About 45 minutes. later, personnel near the PWT reported to the control room that the PWT was overflowing. The SNPO was immediately dispatched to close V15106, the manual isolation to LCV 15-6 level control valve to the PWT, which stopped the overflow.

Cause(s) for the unplanned release:

The root cause of the event was the operators did not respond in a timely manner to the high level alarm in the PWT.

2) The LCV 15-6 valve had historically been unreliable, hence operators were normally dispatched to manually open or close either V15106 or V15105, to provide makeup via the manual bypass line around LCV 15-6.

Actions taken to prevent a recurrence:

\

The operating crew and the Operations Supervisor convened at the end of the shift for a post event debrief. Immediate counseling was provided to members of the crew involved in this event.

2) Members of the operating crew involved in this event received disciplinary actions.

3) A Nuclear Plant Work Order and St. Lucie Action Report (STAR) were written to investigate the operability problems with LCV 15-6. The level control valve (LCV) was adjusted to ensure complete closure of the valve at 100% of the level control signal and the identical Unit 2 LCV was examined.

4) Plant Management emphasized the need to identify all plant deficiencies and has prioritized the resolution of deficiencies involving Operator Work Arounds 41

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FLORIDAPOWER & LIGHT COMPANY ST. LUCIE UNIT ¹ 1 ANNUALREPORT JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 Attachment - A (continued)

Consequences of the unplanned release:

Based on a Tank Grab Sample and calculated release volume, the release to ground was:

Nuclide Assay Release Symbol uCi/ml Curies Xe-131m 9.825E-7 4.184E-05 Xe-133 1.025E-S 4.365E-04 Co-58 7.294E-8 3.106E-06 Co-60 9.572E-8 4.076E-06 H-3 9.240E-2 3.935E 00 Alpha <1.6 E-08 0.00 E 00 Fe-55 5.2 E-08 2.2 E-06 Sr-89 1.2 E-08 5.0 E-07 Sr-90 < 1.27 E-08 0.000E 00

=

Release Volume 11,250 gallons There was no release ofF-site and no site release limits were exceeded. There are no drinking wells located on the barrier island on which the plant is sited. Therefore, there was no pathway to the general public due to salt-water intrusion of the Atlantic Ocean.

The release of radioactive material to the ground from this event was identified in the Site Decommissioning Plan.

42

r, FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT ¹ 1 ANNUALREPORT JANUARY 1, 1995 THROUGH DECEMBER 31, 1995 Attachment - B Copies of C-200 O.D.C.M Revision 16 and Revision 17 43

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ML17228B423

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