ML17223A536

Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989. W/900301 Ltr

ML17223A536
Person / Time
Site:	Saint Lucie
Issue date:	12/31/1989
From:	Sager D FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-90-82, NUDOCS 9003080363
Download: ML17223A536 (49)

Text

ACCELERATED DISTP+UTION DEMONSTRAON SYSTEM F'.

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I REGULATORY INFORMATION DXSTRXBUTION SYSTEM (RIDS)

ACCESSION NBR:9003080363 DOC.DATE: 89/12/31 NOTARIZED: NO DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power 6 Light Co. 05000335 50-389 St. Lucie Plant, Unit 2, Florida Power S Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION SAGER,D.A. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATXON

SUBJECT:

"Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989." W/900301 ltr.

Effluent Release$ Reports DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR ENCL ( SIZE:

TITLE: 50.36a(a)(2) Semiannual NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 3 3 PD2-2 PD 1 1 NORRIS,J 1 1 INTERNAL: ACRS 1 1 AEOD/DS P/TPAB 1 1 IRM TECH ADV 1 1 N /DR PRPB11 2 2 NUDOCS-ABSTRACT 1 1 E 01 1 1 RGN2 DRSS/RPB 2 2 GN2 E 02 1 1 EXTERNAL I BNL T CHLER i J0 3 1 1 EGGG S IMPSON i F 2 2 LPDR 1 1 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE I CONTACT THE. DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELMINATEYOUR NAME FROM DISHUBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 20

P.O. Box14000, Juno Beach, FL 33408-0420 MARCH 0 4 ]ggp L-90-82 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: St. Lucie Units 1 and 2 Docket. Nos. 50-335 and 50-389 Semi-Annual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of July 1, 1989 through December 31, 1989 for St. Lucie Units 1 and

2. This report is required by Technical Specification 6.9.1.7.

Should there be any questions regarding this information, please contact us.

Very truly yours, 488 D. A. Sa Vice Pre 'dent St. Lucie Plant DAS/DMB/gp Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant 9003080363 891231 PDR ADOCK 05000335 PDC an FPL Group company

FLORIDA POHER 8c LIGHT COMPANY ST. LUCIE PLANT UNITS NO. 1 8c 2 LICENSE NUMBERS DPR-67 & NPF-16 COMBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JULY 1, 1989 THROUGH DECEMBER 31, 1989

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TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION.......

OFFSITE DOSE CALCULATION MANUAL REVISIONS. ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ 7 SOLID HASTE AND IRRADIATIED FUEL SHIPMENTS PROCESS CONTROL PROGRAM REVISIONS..

LIQUID EFFLUENTS:

Summation of all Releases Unit ¹ 1 8 Summation of all Releases Unit ¹ 2 ~ ~ 0 ~ 9 Nuclide Summation by Quarter Unit ¹ 1 10 Nuclide Summation by Quarter Unit 2 11 Liquid Pathway Dose Unit ¹ 1 12 Liquid Pathway Dose Unit ¹ 2 13 GASEOUS EFFLUENT:

Summation of all Releases Unit ¹ 1 14 Summation of all Releases Unit ¹ 2 15 Nuclide Summation by Quarter Unit ¹ 1 Nuclide Summation by Quarter Unit ¹ 2 Gaseous Pathway Dose Unit ¹ 1 18 Gaseous Pathway Dose Unit ¹ 2 ~ ~ ~ ~ ~ ~ 19 SOLID HASTE SHIPMENT SUMMATION 20

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-EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION

1. Regulatory Limits

1. 1 For Liquid Haste Effluents A. The concentration of radioactive material released from the site shall be limited to the concentrations specified in 10 CFR Part 20 Appendix B, Table II, 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 Haste Effluents:

A. The dose rate in UNRESTRICTED AREAS due to radioactive materials released in gaseous effluents from 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-131, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days:

1500 mrems/yr to any organ.

4B. The air dose due to noble gases released in gaseous effluents from each reactor unit, to areas at and beyond the SITE BOUNDARY shall 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.

4C. 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, from each reactor 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 a semi-annual report shall not apply to any STS LCO. The reported values are based on actual release conditions instead of historical conditions that the STS LCO dose calcuations are based on. The STS LCO dose limits are therefore included in Item 1 of the report, for information only.

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EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION ontxnue

2. Maximum Permissible Concentrations Hater: As per 10 CFR Part 20, Appendix B, Table II, Column 2, except for entrained or dissolved noble gases as described in

l. l. 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 effluents is not applicable.

4. Measurements and approximations of total radioactivity Hhere 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 Plant Technical Specification analyses techniques to achieve required Lower Limit of Detection (LLD) sensitivity for radioactive effluents.

A summary of liquid effluent accounting methods is described in Table 3. 1.

A summary of gaseous effluent 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 15 Total % 9 30 10 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.

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EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

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

4. 1 (Continued)

B. (Continued)

TABLE 3. 1 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS Liquid Sampling Type of Method of Source Frequency Analysis Analysis Each Batch Principal Gamma 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 8c Entrained Gases One Batch/ Month p. h. a.

Tritium Composite Monthly L. S.

Alpha Composite Monthly G. F. P.

Sr-89, Sr-90, 8c 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 Effluent Totals.

p. h.a.-Gamma Spectrum Pulse Height Analysis using Lithium 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

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EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continue

4. Measurements and Approximations of Total Radioactivity (Continued)

4. 1 (Continued)

B. (Continued)

TABLE 3.2 RADIOACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS Gaseous Sampling Type of Method of Source Frequency Analysis Analys is Waste Gas Decay Tank Each Batch Principal Gamma Emitters p. h. a.

Releases ontainment 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 Lithium 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

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FLORIDA PONER 8c LIGHT COMPANY ST. LUCIE UNIT ¹ 1 SEMIANNUAL REPORT JULY 1 s 1989 THROUGH DECEMBER 31 s 1989 EFFLUENT 8c NASTE DISPOSAL SUPPLEMENTAL INFORMATION ( CONT I NUED )

5. Batch Releases A. Liquid Number of batch releases: 23.0

2. Total time period for batch releases: 10800.0 minutes

3. Maximum time period for a batch release: 602 minutes 4 ~ Average time period for a batch release: 470 minutes

5. Minimum time period for a batch release: 345 minutes

6. Average dilution stream f l ow during the period: 951,650 gpm All liquid releases are summarized in tables B. Gaseous Number of batch releases: 6

2. Total time period for batch releases: 946 minutes

3. Maximum time period for a batch release: 345 minutes 4 ~ Average time period for a batch release: 158 minutes

5. Minimum time period for a batch release: 27 minutes Al l gaseous waste releases are summarized in tables

6. Unplanned Releases A L1 quid

1. Number of releases: 0

2. Total activity released: 0 Curies B. Gaseous

i. Number of releases: 0

2. Total activi ty released: 0 Curies C. See attachments (if applicable) for:

l. A description of the event and equipment involved.

2. Cause(s) for the unplanned release.

3 ~ Ac tions taken to prevent. a recurrence.

4 ~ Consequences of the unplanned release.

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FLORIDA PONER & LIGHT COMPANY ST. LUCIE UNIT ¹ 2 BENI ANNUAL REPORT JULY 1, 1989 THROUGH DECENBER 1,1989 EFFl UENT 8( WASTE DISPOSAL SUPPLENENTAL INFORNATION (CONTINUED)

5. Batch Releases A. Liquid

1. Number of batch releases: 22.0

2. Total time period for batch releases: 9900.0 minutes maximum time period for a batch release: 602 minutes 4 ~ Average time period for a batch release: 450 minutes

5. Ninimum time period for a batch release: 345 minutes

6. Average dilution stream flow during the period: 951,650 gpm All liquid releases are summarized in tables B. Gaseous

1. Number of batch releases: 46 2~ Total time period for batch releases: 6159 minutes Naximum time period for a batch release: 694 minutes 4 ~ Average time period for a batch release: 134 ~

minutes

5. Ninimum time period for a batch release: 30 minutes Al l gaseous ~aste releases are summarized in tables

6. Unplanned Releases A. Liquid

1. Number of releases: 0

2. Total activity released: 0 Curies B. Gaseous

1. Number of releases: 0

2. - Total activity released: 0 Curies C. See attachments (i f applicable) for:

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 release.

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FLORIDA POWER 8c LIGHT COMPANY ST. GUC'IE PLANTS UNITS 1 8c 2 SEMIANNUAL REPORT

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JULY 1, 1989 THROUGH DECEMBER.31,1989 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

7. Assessment of radiation dose from radioactive effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY assume the visitor onsite for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> per day for 180 days in the Southeast Sector at 1. 1 miles as per the LAND USE CENSUS REPORT of a seasonal lifeguard on the beach.

VISITOR DOSE RESULTS FOR THE CALENDAR YEAR 1989 WERE:

Gaseous Particulates Bc Iodine Exposure Noble Gas Exposure ORGAN Dose (mrem) Dose in mrad Bone 4. 75 E-06 Gamma Air Dose 1.89 E-02 Giver 6. 67 E-04 Beta Air Dose 3.69 E-02 Thyroid 2. 32 E-03 Kidney 2,91 E-04 Gung 6. 62 E-04 Gi-GLI 6. 63 E-04 Total Body 6. 78 E-04

8. Offsite Dose Calculation Manual Revisions (ODCM):

The ODCM was not revised during the reporting interval.

9. Solid Waste and Irradiated Fuel Shipments:

No irradiated fuel shipments were made from the site. Common Solid waste from St. Lucie Units 1 and 2 were shipped jointly.

A summation of these shipments is given in Table 3.9 of this report.

10. Process Control Program (PCP) Revisions:

The PCP was not revised during the reporting interval.

FLOR I DA POMER & LIGHT CONPANY ST. LUCI E UNIT ¹ 1 SENIANNUAL REPORT

~ULY 1 s 1989 THROUGH DECENBER 31 s 1989 TABLE 3.3-,,1 LIQUID EFFLUENTS SUNNATION OF ALL RELEASES UNIT QTR¹3 QTR¹4 A. Fission and Activation Products Total Release (Not including Tri tium, Gases, Alpha) 6. 81E-02 3. 28E-02

2. Average Diluted Concentration During Period UCl /ml 1.42E-10 6.47E-il B. Tritium

1. Total Release 8. 45E 01 1 . 38E 02

2. Average Diluted Concentration During Period uCi/ml 1.79E-07 2.72E-07 C. Dissolved and Entrained Gases

1. Total Release 6.65E-03 1.31E-02

2. Average Diluted Concentration During Period uCi /ml 1.41E-11 2. 58E-13 D. Gross Alpha Radioactivity

1. Total Release 3.37E-05 5.90E-06 E. Volume of Maste released (Prior to Dilution ) Liters 1. 14E 07 2. 19E 07 F. Volume of Dilution Mater Used During Period Liters 5.07E 11

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FLORIDA PONER & LIGHT COMPANY ST. LUCIE UNIT ¹ 2 SEMIANNUAL REPORT JULY 1 s 1989 THROUGH DECEMBER 31 t 1989 TABLE 3.3, 2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR¹3 QTR¹4 A. Fission and Activation Products

1. Total Release (Not including Tritium, Gases, Alpha) 6.75E-02 3.00E-02

2. Average Diluted Concentration During Period uCi/ml 1.43E-10 5.92E-ii B. Tri tium

1. Total Release 8.45E 01 1.38E 02

2. Average Diluted Concentration During Period uCi/ml 1 ~ 79E-07 2.72E-07 C. Dissolved and Entrained Gases

1. Total Release Ci 6. 65E-03 1 . 31E-02

2. Average Diluted Concentration During Period uCi/ml 1.41E-11 2. 58E-13 D. Gross Alpha Radioactivity

1. Total Release Ci 3.37E-05 5.90E-06 E. Volume of Naste released (Prior to Dilution) Liters 1.36E 06 1.37E 06 F. Volume of Dilution Mater Used During Period Li ters 4.73E 11 5.07E 11

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FLORIDA POWER & LIGHT CONP ANY ST. LUCIE UNIT ¹ 1 SENIANNUAL REPORT JULY 1, 1989 THROUGH DECENBER 31, 1989 TABLE 3.4.1 LIQUID EFFLUENTS Continuous Node Batch Node NUCL I DES RELEASED UNIT QTR¹3 QTR¹4 QTR¹3 QTR¹4 NA-24 O.OOE 00 O.OOE 00 5.60E-05 3.74E-05 CR-51 Ci O.OOE 00 O.OOE 00 4.77E-03 2.70E-03 NN-54 Ci O.OOE 00 O.OOE 00 4.63E-04 3.04E-04 FE-55 Ci O.OOE 00 0 OOE

~ 00 1.30E-02 7.25E-03 CO-57 Ci O.OOE 00 O.OOE 00 2.00E-05 1.22E-05 CO-58 Ci O.OOE 00 O.OOE 00 8. 15E-03 3.32E-03 FE-59 Ci O.OOE 00 O.OOE 00 1.03E-04 1. 31E-05 CO-60 Ci O.OOE 00 O.OOE 00 5.00E-03 4. 21E-03 AG-110 Ci O.OOE 00 O.OOE 00 7.55E-04 6.45E-04 SN-113 Ci O.OOE 00 O.OOE 00 2.30E-04 1.56E-04 SB-122 Ci O.OOE 00 O.OOE 00 6.50E-04 4.00E-05 SB-124 Ci O.OOE 00 O.OOE 00 2.33E-03 1.46E-03 NP-239 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 RB-88 Ci O.OOE 00 O.OOE 00 2.65E-04 O.OOE 00 SR-89 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 SR-90 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 ZR-95 Ci O.OOE 00 O.OOE 00 1.06E-03 3.55E-04 NB-95 Ci O.OOE 00 O.OOE 00 2.02E-03 7.65E-04 ZR-97 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 NB-97 Ci O.OOE 00 O.OOE 00 9.05E-04 8. 15E-04 TC-99M Ci O.OOE 00 O.OOE 00 6.15E-06 6.45E-06 RU-103 Ci O.OOE 00 O.OOE 00 3.60E-05 O.OOE 00 SB-125 Ci O.OOE 00 O.OOE 00 7.65E-03 5.45E-03 I-131 Ci 3.05E-04 1.97E-03 3.62E-04 5.90E-04 TE-132 Ci O.OOE 00 O.OOE 00 2.74E-05 O.OOE 00 I-132 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 I-133 Ci O.OOE 00 O.OOE 00 1.71E-05 8.45E-OS CS-134 Ci 8.95E-05 3.71E-04 7.90E-03 8.00E-04 CS-137 Ci 2.49E-04 4.38E-04 1.09E-02 8. 15E-04 CS-138 Ci O.OOE 00 O.OOE 00 3.87E-05 O.OOE 00 BA-140 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 LA-140 Ci O.OOE 00 O.OOE 00 1.26E-04 7.65E-05 CE-141 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 CE-144 Ci O.OOE 00 O.OOE 00 6.75E-04 O.OOE 00 TOTAL FOR PERIOD (ABOVE) Ci 6.44E-04 2.78E-03 6.75E-02 3.00E-02 AR-41 Ci O.OOE 00 O.OOE 00 3.26E-05 3.23E-06 KR-85M Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 XE-131N Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 XE-133 Ci O.OOE 00 O.OOE 00 6.20E-03 1.28E-02 XE-133N Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 XE-135 Ci O.OOE 00 O.OOE 00 4.02E-04 3.22E-04 10

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FLORIDA POWER & LIGHT CONPANY ST. LUCIE UNIT ¹ 2 SENI ANNUAL REPORT

~ULY 1 s 1989 THROUGH DECEMBER 31 i 1989 TABLE 3.4 2 LIQUID EFFI UENTS Continuous Node Batch Node NUCLIDES RELEASED UNIT QTR¹3 QTR¹4 QTR¹3 QTR84 NA-24 Ci O.OOE 00 O.OOE 00 5.60E-05 3.74E-05 CR-51 Ci O.OOE 00 O.OOE 00 4.77E-03 2.70E-03 NN-54 Ci O.OOE 00 O.OOE 00 4.63E-04 3.04E-04 FE-55 Ci O.OOE 00 O.OOE 00 1.30E-02 7.25E-03 CO-57 Ci O.OOE 00 O.OOE 00 2.00E-05 1.22E-05 CO-58 Ci O.OOE 00 O.OOE 00 8. 15E-03 3.32E-03 FE-59 Ci O.OOE 00 O.OOE 00 1.03E-04 1.31E-05 CO-60 Ci 0 OOE

~ 00 O.OOE 00 5.00E-03 4. 21E-03 AG-110 Ci O.OOE 00 0.'OOE 00 7.55E-04 6.45E-04 SN-113 Ci O.OOE 00 O.OOE 00 2.30E-04 1.56E-04 SB-122 Ci 0 OOE

~ 00 O.OOE 00 6.50E-04 4 'OE-05 SB-124 Ci O.OOE 00 O.OOE 00 2.33E-03 1.46E-03 NP-239 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 RB-88 Ci O.OOE 00 O.OOE 00 2.65E-04 O.OOE 00 SR-89 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 SR-90 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 ZR-95 Ci O.OOE 00 O.OOE 00 1.06E-03 3.55E-04 NB-95 Ci O.OOE 00 O.OOE 00 2.02E-03 7.65E-04 ZR-97 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 NB-97 Ci O.OOE 00 O.OOE 00 9.05E-04 8. 1 5E-04 TC-99N Ci O.OOE 00 O.OOE 00 6.15E-06 6. 45E-06 RU-103 Ci O.OOE 00 O.OOE 00 3.60E-05 O.OOE 00 SB-125 Ci O.OOE 00 O.OOE 00 7.65E-03 5.45E-03 I-131 Ci O.OOE 00 O.OOE 00 3.62E-04 5.90E-04 TE-132 Ci O.OOE 00 O.OOE 00 2.74E-05 O.OOE 00 I-132 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 I-133 Ci O.OOE 00 O.OOE 00 1. 71E-05 8.45E-05 CS-134 Ci O.OOE 00 O.OOE 00 7.90E-03 8.00E-04 CS-137 Ci O.OOE 00 O.OOE 00 1.09E-02 8. 15E-04 CS-138 Ci O.OOE 00 O.OOE 00 3.87E-05 O.OOE 00 BA-140 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 LA-140 Ci O.OOE 00 O.OOE 00 1.26E-04 7.65E-05 CE-141 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 CE-144 Ci O.OOE 00 O.OOE 00 6.75E-04 O.OOE 00 TOTAL FOR PERIOD (ABOVE) O.OOE 00 O.OOE 00 6.75E-02 3.00E-02 AR-41 Ci O.OOE 00 O.OOE 00 3.26E-05 3.23E-06 KR-85N Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 XE-131N Ci O.OOE 00 O.OOE 00 0 ~ OOE 00 O.OOE 00 XE-133 Ci O.OOE 00 O.OOE 00 6.20E-03 1.28E-02 XE-133N Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 XE-135 Ci O.OOE 00 O.OOE 00 4.02E-04 3.22E-04 11

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMI-ANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3.5-1 LIQUID EFFLUENTS DOSE SUMMATION Age Group: ADULT Location: Any ADULT Exposure Interval: January 1, 1989 through December 31, 1989 FISH & SHELI FISH Calendar Year ORGAN Dose (mrem)

Bone 3. 29 E-02 Liver 1. 44 E-01 Thyroid 6. 49 E-03 Kidney 1. 41 E-03 Lung 1 ~ 66 E-01 GI-LLI 1. 42 E-01 Total Body 4. 01 E-02 12

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FLORIDA POWER &, LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMI-ANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3.5-2 LIQUID EFFLUENTS DOSE SUMMATION Age Group: ADULT Location: Any ADULT Exposure Interval: January 1, 1989 through December 31, 1989 FISH & SHELLFISH Calendar Year ORGAN Dose (mrem)

Bone 3. 28 E-02 Liver 1. 44 E-01 Thyroid 5. 35 E-03 Kidney 1. 37 E-03 Lung 1~ 66 E-01 GI-LLI 1. 42 E-01 Total Body 4. 00 E-02 13

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FLORIDA PONEH 5 LIGHT COMPANY ST. LUCIE UNIT ¹ 1 SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3.6;.1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTB¹3 A. Fission and Activation Gases

1. Total Release 8.59E 02 1.67E 03

2. Avg. Release Hate For Period uCi/sec 1.08E 02 2.10E 02

b. Iodines

1. Total Iodine 131 1.10E-03 6 ~ 53K-04

2. Avg. Release Rate For Period uCi/sec 1.38E-04 8.22E-05 C. Particulates

1. Particulates T 1/2 > 8 Days 2.30E-05 O,OOE 00

2. Avg. Release Rate For Period uCi/sec 2.89E-06 O.OOE 00

3. Gross Alpha Radioactivity 9.21E-08 1.15E-07 D. Tritium

1. Total Release 2.42E 02 3.48E 01

2. Avg. Release Rate For Period uCi/sec 3.04E 01 4.38E 00 14

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FLORIDA POHEB & LIGHT COMPANY ST. LUCIE UNIT 0 2 SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECENBEB 31, 1989 TABLE 3.6,".2 GASEOUS EFFLUENTS SUHHATION OF ALL RELEASES UNIT A. Fission and Activation Gases

1. Total Release 1 '6K 02 8.38E 01

2. Avg. Release Rate For Period uCi/sec 1.96E 01 1.05E 01

b. Iodines

1. Total Iodine 131 3.50E-04 4.80E-04

2. Avg. Release Rate For Period uCi/sec 4.40E-05 6.04E-05 C. Particulates

1. Particulates T 1/2 > 8 Days 0.00E 00 5.65E-05

2. Avg. Release Bate For Period uCi/sec O.OOE 00 7.11E-06

3. Gross Alpha Radioactivity 9 '5K-08 1.26E-08 D. Tritium 1, Total Release 1 '7E 01 1.06E 01

2. Avg. Release Rate For Period uCi/sec 1.60E 00 1 '3E 00 15

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FLORIDA POHER 5 LIGHT COMPANY ST. LUCIE UNIT 0 1 SEHIANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3.7.".,1 GAsE0Us EFFLUENTS GROUND LEVEL RELEASES Nuclides Continuous Mode Batch Mode Released Unit QTR03 QTR04 QTR53 QTR04

i. Fission Gases AB-41 Ci O.OOE 00 O.OOE 00 0 OOE 00

~ O.OOE 00 KB-85 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 KB-85M Ci 8.57E 00 1.53E 01 2.47E-02 O.OOE 00 KR-87 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 KR-88 Ci 3.9aE oo 6.oaE oo O.OOE 00 O.OOE 00 XE-131M Ci O.OOE 00 O.OOE 00 2.10E-Oi O.OOE 00 XE-133 Ci 7.27E 02 1.45E 03 2.90E 01 O.OOE 00 XE-133M Ci 3.32E 00 6.71E 00 5.43E-oi O.OOE 00 XE-135 Ci 8.66E 01 1.90E 02 2.10E-01 O.OOE 00 XE-135M Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 XE-138 Ci O.OOE 00 0 OOE 00

~ O.OOE 00 O.OOE 00 TOTAL FOR PERIOD 8.29E 02 1.67E 03 3.00E 01 O.OOE 00 2 ~ Iodines I-131 Ci 1.10E-03 6.53E-04 I-132 Ci 4.43E-03 0 OOE 00

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I-133 Ci 6.42E-03 4.71E-03 I-134 Ci O.OOE 00 O.OOE 00 I-135 Ci O.OOE 00 O.OOE 00 TOTAL FOR PERIOD 1 '0E-02 5.36E-03

3. Particulates SR-89 Ci 1.49E-05 O.OOE 00 SR-90 Ci 4.03E-06 O.OOE 00 Y-90 Ci 4.03E-06 O.OOE 00 16

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FLORIDA POWER 8c LIGHT COMPANY ST, LUCIE UNIT 0 2 SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989'ABLE 3.7".,2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclides Continuous Mode Batch Mode Released QTR53 QTR04 QTR53 QTR54 1 ~ Fission Gases AB-41 Ci O.OOE 00 0 OOE 00

~ 3.68E-01 4.32E-01 KB-85 Ci O.OOE 00 0 OOE 00

~ O.OOE 00 3.57E-01 KB-85M Ci 1.71E 00 2.67E-01 3 '7K-02 6.35E-02 KR-87 Ci 0 OOE 00

~ O.OOE 00 3.84E-03 6.83E-03 KR-88 Ci O.OOE 00 O.OOE 00 3.48E-02 6.40E-02 XE-131M Ci O.OOE 00 O.OOE 00 2.29E-01 3 '0K-01 XE-133 Ci 1.11E 02 4.21E 01 1.57E 01 3.15E Oi XE-133M Ci O.OOE 00 O.OOE 00 1.83E-01 4.44E-01 XE-135 Ci 2.60E 01 6.71E 00 4.56E-01 1 '5E 00 XE-135M Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 XE-137 Ci O.OOE 00 O.OOE 00 2.10E-02 0 OOE 00

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XE-138 Ci .O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 TOTAL FOR PERIOD 1.39E 02 4.91E Oi 1 '0E 01 3.47E 01

2. Iodines I-131 Ci 3 '0E-04 4.80E-04 I-132 Ci O.OOE 00 O.OOE 00 I-133 Ci 6 '9E-04 2.07E-03 I-134 Ci O.OOE 00 0 OOE 00

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I-135 Ci O.OOE 00 O.OOE 00 TOTAL FOR PERIOD 1.01E-03 2 '5K-03

3. Particulates SR-89 Ci O.OOE 00 O.OOE 00 SB-90 Ci O.OOE 00 O.OOE 00 Y-90 Ci 0 OOE

~ 00 O,OOE 00 Tc-99M Ci O.OOE 00 5.65E-05

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FLORlDA POHER &, LIGHT COMPANY ST. LUCIE PLANT UNIT 0 1 TABLE 3.8-1 GASEOUS EFFLUENTS DOSE SUMMATION Age Group: INFANT Exposure Interval: January 1, 1989 through December 31, 1989 NOTE: The below dose results were calculated using actual meterological data during the specified time interval with Met data reduced as per Reg. Guide 1. 111, March 1976 BONE LIVER THYROID KIDNEY PATHHAY mrem mrem mrem mrem Ground Plane (A) 0. 00 E-01 0. 00 E-01 0. 00 E-01 0. 00 E-01 Grass-Goat-Milk(B) 4.75 E-04 5.62 E-03 1.70 E-01 2.35 E-03 Inhalation (A) 1. 10 E-05 2. 03 E-03 5.69 E-03 8.87 E-04 TOTAL 4.86 E-04 7.65 E-03 1.76 E-01 3.24 E-03 LUNG GI-LLI T. BODY PATHWAY mrem mrem mrem Ground Plane (A) 0. 00 E 00 0. 00 E 00 3. 25 E-05 Grass-Goat-Milk(B) 5. 10 E-03 5. 13 E-03 5.40 E-03 Inhalation (A) 2. 02 E-03 2. 02 E-03 2. 03 E-03 TOTAL 7. 12 E-03 7. 15 E-03 7. 46 E-03 (A)-Sector  : SE Range: 1.50 miles (B)-Sector  : HNW Range: 3.75 miles (Actual Goat)

CALENDAR YEAR NOBLE GASES (mrad)

Gamma Air Dose 4. 68 E-02 Beta Air Dose 9. 76 E-02 Sector  : SE Range: 1. 50 miles 18

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FLORIDA POHER & LIGHT COMPANY ST. LUCIE PLANT UNIT 0 2 TABLE 3.8-2 GASEOUS EFFLUENTS DOSE SUMMATION AGE GROUP  : INFANT Exposure Interval: January 1, 1989 through December 31, 1989 NOTE: The below dose results were calculated using actual meterological data during the specified time interval with Met data reduced as per Reg. Guide 1 '11, March 1976 BONE LIVER THYROID KIDNEY PATHHAY mrem mrem mrem mrem Ground Plane (A) 0. 00 E-01 0. 00 E-01 0. 00 E-01 0. 00 E-01 Grass-Goat-Milk(B) 5.91 E-04 1.99 E-03 2.27 E-01 7.34 E-04 Inhalation (A) 7 13

~ E-06 5. 15 E-04 3. 17 E-03 2.23 E-04 TOTAL 5.98 E-04 2 '1 E-03 2.30 E-01 9.57 E-04 LUNG GI-LLI T. BODY PATHHAY mrem mrem mrem Ground Plane (A) 0. 00 E 00 0. 00 E 00 1.91 E-05 Grass-Goat-Milk(B) 1.28 E-03 1.31 E-03 1.69 E-03 Inhalation (A) 5. 06 E-04 5. 07 E-04 5. 10 E-04 TOTAL 1.79 E-03 1.82 E-03 2.22 E-03 (A)-Sector  : SE Range: 1.50 miles (B)-Sector  : HNH Range: 3.75 miles (Actual Goat)

CALENDAR YEAR NOBLE GASES (mrad)

Gamma Air Dose 2. 78 E-02 Beta Air Dose 4. 80 E-02 Sector  : SE Range: 1. 50 miles 19

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FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT SEMI-ANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 UNITS 1 AND 2, TABLE 3.9 A. Solid Waste Shipped Off-Site for Burial or Disposal

1. Type of Waste Unit 6 Mo. Period Error %

a. Spent resin, M3 3.546 E+1 Process filters Ci 5.590 E+1 2.0 E+1

b. Dry Compressible M3 9 813 E+1 2.0 E+1 Waste (Note 5) Ci 5.701 E c~ Irradiated M3 Components Ci 2.0 E+1

d. Other 3.119 E+1

1. Non-Compres- Ci 5.284 E"1 2.0 E+1 sible Metal (DAW) (Note 6)

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

Category Nuclides a ~ Cs 137 3.57 E+1 Co 60 1.59 E+1 Cs 134 1.57 E+1 Ni 63 1.05 E+1 Co 58 9.91 E+0 Fe 55 5.05 E+0 Sb 125 2.85 E+0 Sb 122 1.18 E+0 Mn 54 1.10 E+0 H 3 1.08 E+0

b. H 3 3.45 E+1 Co 60 2.11 E+1 Cs 137 1.88 E+1 Cs 134 6.12 E+0 Fe 55 5.96 E+0 Co 58 4.77 E+0 Ni 63 2.46 E+0 Ce 144 2.09 E+0 Sb 125 1.01 E+0 Zr 95 8.09 E 1 Mn 54 7.06 E 1 20

A.

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

Category Nuclides c ~ N/A N/A Co 60 4.11 E+1 Cs 137 2.58 E+1 Fe 55 1.52 E+1 Cs 134 9.91 E+0 Ni 63 3.87 E+0 Mn 54 1.84 E+0 Co 58 1.54 E+0

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 41 Sole Use Truck Barnwell, S.C.

B. Irradiated Fuel Shipments Number of Shipments Mode of Transportation Destination 0 N/A N/A N/A = Not Applicable

FLORIDA POWER AND LIGHT COMPANY ST LUCIE PLANT SEMI-ANNUAL REPORT JULY lg 1989 THROUGH DECEMBER 31, 1989 UNITS 1 AND 2g TABLE 3 9 (CONTINUED)

Total Total Principal Type of Category Type of Waste Volume Curies Radionuclides Waste Reg-Guide Container Solidification Class Cubic Ft. (Note 1) (Notes 1 a 2) (Note 3) 1.21 (Note 4) Agent Class A 3465.5 5.701 E 1 . NA PWR l.b. Non-Specification None Compactible Strong Tight Trash Package (Note 5)

Class A 1101.4 5.284 E 1 NA PWR l.d. Non-Specification None Non-Compactible Strong Tight Trash Package (Note 6)

ClasS A 926.2 3.95 Cs 137, PWR l.a. NRC Certified None Ni 63 Ion-Exchange LSA Resin T e A Class B 326.1 51.95 Cs 137, Sr 90, PWR l.a. NRC Certified None Ni 63, PU 241'RU Ion Exchange LSA Resin T e A

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FLORIDA POWER AND LIGHT COMPANY ST LUCIE PLANT SEMI-ANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 UNITS 1 AND 2 TABLE 3 9 (CONTINUED)

SOLID WASTE SUPPLEMENT Note 1: The total curie quantity and radionuclide composition of solid waste shipped from the St. Lucie Plant, Units 1 & 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/ll/83) for these determinations.

The most frequently used techniques for determining 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 samples as appropriate for the waste type. Off-site analyses are used to establish scaling factors or other estimates for radionuclides such as 3H, 14C, 99Tc, 129I, TRU, 241Pu, 242Cm, 63Ni, 55Fe, and 90Sr.

Note 2: "Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than .01 times the concentration of the nuclides listed in Table 1 or .Ol 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 Environment 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 to date has been 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, five shipments of Dry Compressible Waste (5,152 cubic feet, 5.49 E 1 Curies) were made from the St. Lucie Plant to the volume reduction facility. This material was'hipped via "Sole Use Truck" in non-specification strong tight packages.

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Note 6: The volume and activity listed for non-compressible metal represent the quantity of material that during the reporting period could not be recycled by the contracted vendor and required disposal.

24