ML17227A325

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Semiannual Radioactive Effluent Release Rept for Jul Through Dec 1991. W/920228 Ltr
ML17227A325
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 12/31/1991
From: Sager D
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9203090465
Download: ML17227A325 (52)
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Text

ACCELERATED DISTIUBUTION DEMONSTRATION SYSTEM REGULA'I INFORMATION DISTRIBUTIO YSTEM (RIDS)

DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 50-380 St. Lucie Plant, Unit 2, Florida Power S Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION SAGERiD.A. Florida Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Semiannual Radioactive Effluent Release Rept for Jul through Dec 1991." 920228 tr.

DZSTRZBUTZON CODE: ZE4SD COPZES RECEZVED:LTR I ENCL ( SIZE'. 3E TITLE: 50.36a(a)(2) Semiannual Effluent Release Reports 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 NRR/DREP/PRPB11 2 2 Rf PILE Ol 1 1 RGN2 DRSS/RPB 2 2 RGN2 FILE 02 1 1 EXTERNAL BNL TICHLERE J03 1 1 EGEG SIMPSON,F 2 2 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 16 p~jx/

P.O. Box 128, Ft. Pierce, FL 34954-0128

%IVII February 28, 1992 L-92-43 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 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, 1991, through December 31, 1991, for St. Lucie Units 1 and 2. This report is required by Technical Specification 6.9.1.7.

Attachment A to the report is an event description that was inadvertently left out of the January 1, 1991, through June 30, 1991, Semi-Annual Radioactive Effluent Release Report.

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

Very truly yours,

~/ +D.~A. Sager Vice President St. Lucie Plant DAS:JJB:kw cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC Attachment DAS/PSL N628-92 ABOARD.-i 92030'rr0465 911231 PDR ADOCK 05000335 R PDR an FPL Group company

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNITS NO. 1 & 2 LICENSE NUMBERS DPR-67 & NPF-16 COMBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JULY 1~ 1991 THROUGH DECEMBER 3 1 ~ 1 991

I TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION OFFSITE DOSE CALCULATION MANUAL REVISIONS SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PROCESS CONTROL PROGRAM REVISIONS LIQUID EFFLUENTS:

SUMMATION OF ALL RELEASES UNIT g 1 8 SUMMATION OF"ALL RELEASES UNIT g 2 9 NUCLIDE SUMMATION BY QUARTER UNIT g 1 10 NUCLIDE SUMMATION BY QUARTER UNIT g 2 12 LIQUID EFFLUENT DOSE UNIT 0 1 14 LXQUID EFFLUENT DOSE UNIT g 2 15 GASEOUS EFFLUENT:

SUMMATION OF ALL RELEASES UNIT g 1 16 SUMMATION OF ALL RELEASES UNIT g 2 17 NUCLIDE SUMMATION BY QUARTER UNIT g 1 18 NUCLIDE SUMMATION BY QUARTER UNIT g 2 20 GAS EFFLUENT DOSE UNXT 4 1 22 GAS EFFLUENT DOSE UNIT 8 2 23 SOLID WASTE SHIPMENT SUMMATION 24 UNPLANNED GAS RELEASE ATTACHMENT A 28

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION

1. Regulatory Limits 1.1 For Liquid Waste 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 Waste 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.

  • B 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.

  • C 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 WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

2. Maximum Permissible Concentrations Water: As per 10 CFR Part 20, Appendix B, Table II, 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 effluents 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 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 5 NA NA Sampling 5 2 5 Sample Preparation 5 1 5 Sample Analysis 10 3 10 Release Volume 5 4 15 Total % 9 30 10 35 The pxedictability 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.)

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 a Fe-55 C.S.

Continuous Daily Principal Gamma Emitters Releases Grab & I-131 for p.h.a.

Samples 4/M Composite Analysis Dissolved 6 Entrained Gases One Batch/ Month p.h.a.

Tritium Composite Monthly L.S.

Alpha Composite Monthly G.F.P.

Sr-89'r 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 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 WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

4. Measurements and Approximations of Total Radioactivity (Continued) 4.1 (Continued)

B. (Continued)

TABLE 3.2 RADIOACTIVE GASEOUS 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 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

FLORIDA POWER & LIGHT COMPANY ST. lUCIE UNIT 4 1 SEMIANNUAL REPORT JULY 1g 1991 THROUGH DECEMBER 31'991 EFFLUENT & WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)

5. Batch Releases A. Liquid
1. Number of batch releases: 34
2. Total time period for batch releases: 14563 minutes
3. Maximum time period for a batch release: 571 minutes
4. Average time period for a batch release: 428 minutes

'5. Minimum time period for a batch release: 303 minutes

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

B. Gaseous

1. Number of batch releases: 24
2. Total time period for batch releases: 10622 minutes
3. Maximum time period for a batch release: 1150 minutes
4. Average time period for a batch release: 443 minutes
5. Minimum time period for a batch release: 79 minutes All gaseous waste releases are summarized in tables.
6. Unplanned Releases.

A. Liquid

1. Number of releases: 0
2. Total activity of releases: O.OOE+00 Curies B. Gaseous
1. Number of releases: 0
2. Total activity of releases: O.OOE+00 Curies C. See attachments (if applicable) 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 release.

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 0 2 SEMIANNUAL REPORT JULY 1g 1991 THROUGH DECEMBER 31'991 EFFLUENT & WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)

5. Batch Releases A. Liquid
1. Number of batch releases: 34
2. Total time period for batch releases: 14563 minutes
3. Maximum time period for a batch release: 571 minutes
4. Average time period for a batch release: 428 minutes
5. Minimum time period for a batch release: 303 minutes
6. Average dilution stream flow during the period: 850185 gpm All liquid releases are summarized in tables.

B. Gaseous

1. Number of batch releases: 73
2. Total time period for batch releases: 13766 minutes
3. Maximum time period for a batch release: 708 minutes
4. Average time period for a batch release: 189 minutes
5. Minimum time period for a batch release: 11 minutes All gaseous waste releases are summarized in tables.

Unplanned Releases A. Liquid

1. Number of releases: 0
2. Total activity of releases: O.OOE+00 Curies B. Gaseous
1. Number of releases: 0
2. Total activity of releases: 0.00E+00 Curies C. See attachments (if applicable) 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 release.

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANTS UNITS 1 & 2 SEMIANNUAL REPORT JULY 1 g 1 991 THROUGH DECEMBER 3 1 ~ 1 991 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 assumes the visitor onsite for 6 hours per day for 180 days per year at a distance of 1.6 kilometers in the South East Sector. The VISITOR received exposure from each of the two reactor units on the Site.

VISITOR DOSE RESULTS FOR CALENDAR YEAR 1991 were:

NOBLE GAS EXPOSURE DOSE (mrad)

Gamma Air Dose 1.07 E-02 Beta Air Dose 2.02 E-02 GASEOUS PARTICULATE &

IODINE EXPOSURE DOSE (mRem)

Bone 3.85 E-06 Liver 2.70 E-04 Thyroid 1.65 E-03 Kidney 1.17 E-04 Lung 2.69 E-04 GI-LLI 2.65 E-04 Total Body 3.49 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 are provided on Page 24.
10. Process Control Program (PCP) Revisions: The PCP was not revised during the reporting interval.

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 8 1 SEMIANNUAL REPORT JULY 1~ 1991 THROUGH DECEMBER 31~ 1991 TABLE 3.3-1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTRg3 QTR$ 4 A. ,Fission and Activation Products

1. Total Release (Not including Tritium, Gases, and Alpha) Ci 1.02E-01 2.21E-01
2. Average Diluted Concentration During Period uci/ml 2.01E-10 6.40E-10 B. Tritium
1. Total Release Ci 1.35E+02 8.28E+01
2. Average Diluted Concentration During Period uci/ml 2.66E-07 2.40E-07 C. Dissolved and Entrained Gases
1. Total Release Ci 1. 16E-02 1. 02E-02
2. Average Diluted Concentration During Period uci/ml 2.28E-11 2.95E-11 D. Gross Alpha Radioactivity
1. Total Release Ci O.OOE+00 O.OOE+00 E. Volume of Waste Released (Prior to Dilution) Liters 2.59E+07 1.73E+07 F. Volume of Dilution Water Used During Period Liters 5.07E+11 3.45E+11

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 8 2 SEMIANNUAL REPORT JULY 1~ 1991 THROUGH DECEMBER 31'991 TABLE 3.3-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTRg3 QTR$ 4 A. Fission and Activation Products

1. Total Release (Not including Tritium, Gases, and Alpha) Ci 2.82E-02 2.19E-01
2. Average Diluted Concentration During Period uci/ml 5.55E-11 6.34E-10 B. Tritium
1. Total Release Ci 1.35E+02 8.28E+01
2. Average Diluted Concentration During Period uci/ml 2. 66E-07 2. 40E-07 C. Dissolved and Entrained Gases
1. Total Release Ci 1.16E-02 7.43E-03
2. Average Diluted Concentration 2.28E-11 2.15E-11 During Period uci/ml D. Gross Alpha Radioactivity
1. Total Release Ci O.OOE+00 O.OOE+00 E. Volume of Waste Released (Prior to Dilution) Liters 1.89E+06 1.99E+06 F. Volume of Dilution Water Used During Period Liters 5.07E+11 3.45E+11

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT S,1 SEMIANNUAL REPORT JULY 1i 1991 THROUGH DECEMBER 31i 1991 TABLE 3.4-1 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES QTRg3 ,

QTR$ 4 QTRg3 QTR$ 4 RELEASED UNIT NA-24 Ci O.OOE+00 O.OOE+00 O.OOE+00 1.24E-03 CR-51 Ci O.OOE+00 O.OOE+00 5.61E-05 9.57E-03 MN-54 Ci O.OOE+00 O.OOE+00 2.11E-04 5.86E-04 FE-55 Ci 7.40E-02 O.OOE+00 4.93E-03 O.OOE+00 MN-56 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-57 Ci O.OOE+00 O.OOE+00 O.OOE+00 1.84E-05 CO-58 Ci O.OOE+00 O.OOE+00 6.24E-04 2.72E-02 FE-59 Ci O.OOE+00 O.OOE+00 O.OOE+00 1.04E-04 CO-60 Ci O.OOE+00 O.OOE+00 1.30E-02 2.44E-02 ZN-65 Ci O.OOE+00 O.OOE+00 O.OOE+00 0.'OOE+00 NI-65 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 BR-82 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 RB-88 Ci O.OOE+00 O.OOE+00 5.00E-04 O.OOE+00 SR-89 Ci O.OOE+00 O.OOE+00 O.OOE+00 3.70E-05 SR-90 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-90 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-91 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-92 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-92 Ci O.OOE+00 O.OOE+00 1.61E-05 O.OOE+00 ZR-95 Ci O.OOE+00 O.OOE+00 4.32E-05 6.37E-04 NB-95 Ci O.OOE+00 O.OOE+00 1.82E-04 1.81E-03 ZR-97 Ci O.OOE+00 O.OOE+00 6.50E-05 O.OOE+00 NB-97 Ci O.OOE+00 O.OOE+00 9.64E-04 5.75E-03 TC-99M Ci O.OOE+00 O.OOE+00 6.13E-06 3.81E-06 MO-99 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 RU-103 Ci O.OOE+00 O.OOE+00 O.OOE+00 4.84E-05 AG-110 Ci O.OOE+00 O.OOE+00 7.77E-04 4.98E-03 SN-113 Ci O.OOE+00 O.OOE+00 3.71E-05 2.73E-05 SB-122 Ci O.OOE+00 O.OOE+00 O.OOE+00 3.54E-03 SB-124 Ci O.OOE+00 O.OOE+00 2.17E-05 4.26E-02 SB-125 Ci O.OOE+00 O.OOE+00 4.80E-03 2.68E-02 10

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT ¹ 1 SEMIANNUAL REPORT JULY 1~ 1991 THROUGH DECEMBER 31~ 1991 TABLE 3.4-1 LIQUID EFFLUENTS (CONTINUED)

Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTR¹3 QTR¹4 QTR¹3 QTR¹4 TE-129 Ci O.OOE+00 O.OOE+00 O.OOE+00 4.59E-03 TE-129M Ci O.OOE+00 O.OOE+00 O.OOE+00 3.02E-04 I-131 Ci O.OOE+00 1.67E-04 6.54E-04 2.15E-03 TE-132 Ci O.OOE+00 O.OOE+00 O.OOE+00 2.07E-04 I-132 Ci O.OOE+00 O.OOE+00 O.OOE+00 4.30E-04 I-133 Ci O.OOE+00 O.OOE+00 '1.35E-04 5.99E-05 I-134 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-134 Ci O.OOE+00 8.29E-04 3.77E-04 2.22E-02 I-135 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-136 Ci O.OOE+00 O.OOE+00 O.OOE+00 1.58E-04 CS-137 Ci O.OOE+00 8.45E-04 7.27E-04 2.83E-02

'CS-138 Ci O.OOE+00 0. OOE+00, 6.40E-06 1.30E-03 BA-140 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 LA-140 Ci O.OOE+00 O.OOE+00 2.07E-05 5.03E-04 CE-141 Ci O.OOE+00 '.QOE+00 O.OOE+00 O.OOE+00 CE-144 Ci O.OOE+00 O.OOE+00 1.36E-05 O.OOE+00 PR-144 Ci O.OOE+00 O.OOE+00 O.OOE+00 9.49E-03 W-187 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 NP-239 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD CI 7.40E-02 1.84E-03 2.82E-02 2.19E-01 AR-41 CI O.OOE+00 O.OOE+00 O.OOE+00 4.13E-06 KR-85M CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-85 CI O.OOE+00 O.OOE+00 O.OOE+00 3.10E-03 KR-87 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-88 CI O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 XE-131M CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00, XE-133M CI O.OOE+00 O.OOE+00 4.63E-05, O.OOE+00 XE-133 CI O.OOE+00 2.75E-03 1.11E-02 4.20E-03 XE-135M CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-135 CI O.OOE+00 O.OOE+00 4.87E-04 1.22E-04 11

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FLORIDA POWER &,LIGHT COMPANY ST. LUCIE UNIT ¹ 2 SEMIANNUAL REPORT JULY 1I 1991 THROUGH DECEMBER 31I 1991 TABLE 3.4-2 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTR¹3 QTR¹4 QTR¹3 QTR¹4 NA-24 CI O.OOE+00 O.OOE+00 O.OOE+00 1.24E-03 CR-51 CI O.OOE+00 O.OOE+00 5.61E-05 9.57E-03 MN-54 CI '0.00E+00 O.OOE+00 2.11E-04 5.86E-04 FE-55 CI O.OOE+00 O.OOE+00 4.93E-03 O.OOE+00 MN-56 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-57 CI O.OOE+00 O.OOE+00 O.OOE+00 1.84E-05 CO-58 CI O.OOE+00 O.OOE+00 6.24E-04 2.72E-02 FE-59 CI O.OOE+00 O.OOE+00 O.OOE+00 1.04E-04 CO-60 CI O.OOE+00 O.OOE+00 1.30E-02 2.44E-02 ZN-65 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 NI-65 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 BR-82 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 as-88 CI O.OOE+00 O.OOE+00 5.00E-04 O.OOE+00 SR-89 CI O.OOE+00 O.OOE+00 O.OOE+00 3.70E-05 SR-90 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-90 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-91 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-92 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-92 CI O.OOE+00 O.OOE+00 1.61E-05 O.OOE+00 ZR-95 CI O.OOE+00 O.OOE+00 4.32E-05 6.37E-04 NB-95 CI O.OOE+00 O.OOE+00 1.82E-04 1.81E-03 ZR-97 CI O.OOE+00 O.OOE+00 6.50E-05 O.OOE+00 NB-97 CI O.OOE+00 0.00E+00 9.64E-04 5.75E-03 TC-99M CI O.OOE+00 O.OOE+00 6.13E-06 3.81E-06 MO-99 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 RU-103 CI O.OOE+00 O.OOE+00 O.OOE+00 4.84E-05 AG-110 CI O.OOE+00 O.OOE+00 7.77E-04 4.98E-03 SN-113 CI O.OOE+00 O.OOE+00 3.71E-05 2.73E-05 SB-122 CI O.OOE+00 O.OOE+00 O.OOE+00 3.54E-03 SB-124 CI O.OOE+00 O.OOE+00 2.17E-05 4.26E-02 SB-125 CI O.OOE+00 O.OOE+00 4.80E-03 2.68E-02 12

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 0 2 SEMIANNUAL REPORT JULY 1g 1991 THROUGH DECEMBER 31'991 TABLE 3.4-2 LIQUID EFFLUENTS (CONTINUED)

Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTRg3 QTRg4 QTRg3 QTRg4 TE-129 CI O.OOE+00 O.OOE+00 O.OOE+00 4.59E-03 TE-129M CI O.OOE+00 O.OOE+00 O.OOE+00 3.02E-04 I-131 CI O.OOE+00 O.OOE+00 6.54E-04 2.15E-03 TE-132 CI O.OOE+00 O.OOE+00 O.OOE+00 2.07E-04 I-132 CI O.OOE+00 O.OOE+00 O.OOE+00 4.30E-04 I-133 CI O.OOE+00 O.OOE+00 1.35E-04 5.99E-05 I-134 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-134 CI O.OOE+00 O.OOE+00 3.77E-04 2.22E-02 I-135 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-136 CI O.OOE+00 O.OOE+00 O.OOE+00 1.58E-04 CS-137 CI O.OOE+00 O.OOE+00 7.27E-04 2.83E-02 CS-138 CI O.OOE+00 O.OOE+00 6.40E-06 1.30E-03 BA-140 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 LA-140 CI O.OOE+00 O.OOE+00 2.07E-05 5.03E-04 CE-141 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 CI O.OOE+00 O.OOE+00 1.36E-05 O.OOE+00 PR-144 CI O.OOE+00 O.OOE+00 O.OOE+00 9.49E-03 W-187 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 NP-239 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD CI O.OOE+00 O.OOE+00 2.82E-02 2.19E-01 AR-41 CI O.OOE+00 O.OOE+00 O.OOE+00 4.13E-06 KR-85M CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-85 CI O.OOE+00 O.OOE+00 O.OOE+00 3.10E-03 KR-87 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-88 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-131M CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-133M CI O.OOE+00 O.OOE+00 4.63E-05 O.OOE+00 XE-133 CI O.OOE+00 O.OOE+00 1.11E-02 4.20E-03 XE-135M CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-135 CI O.OOE+00 O.OOE+00 4.87E-04 1.22E-04 13

FLORIDA POWER AND LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMI-ANNUAL REPORT JULY 1 ~ 1 991 THROUGH DECEMBER 3 1 g 1 991 TABLE 3.5-1 LIQUID EFFLUENTS DOSE SUMMATION AGE GROUP: ADULT LOCATION: ANY ADULT EXPOSURE INTERVAL 'ANUARY 1g 1 9 9 1 THROUGH DECEMBER 3 1 g 1 991 FISH AND SHELLFISH CALENDER YEAR ORGAN DOSE (mrem)

BONE 5.56E-02 LIVER 2.45E-01 THYROID 2.52E-03 KIDNEY 2.13E-03 LUNG 2.84E-01 GI-LLI 1.52E-01 TOTAL BODY 6.79E-02 14

FLORIDA POWER AND LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMI-ANNUAL REPORT JULY 1 i 1 99 1 THROUGH DECEMBER 3 1 I 1 9 91 TABLE 3.5-1 LIQUID EFFLUENTS DOSE SUMMATION AGE GROUP: ADULT LOCATION: ANY ADULT EXPOSURE INTERVAL 'ANUARY 1 I 1 99 1 THROUGH DECEMBER 3 1 I 1 99 1 FISH AND SHELLFISH CALENDER YEAR ORGAN DOSE (mrem)

BONE 8.45E-03 LIVER 3.26E-02 THYROID 2.42E-03 KIDNEY 2.09E-03 LUNG 3.75E-02 GI-LLI 6.87E-02 TOTAL BODY 1.20E-02 15

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 8 1 SEMIANNUAL REPORT JULY 1 ~ 1 9 9 1 THROUGH DECEMBER 3 1 g 1 991 TABLE 3.6-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTRg3 QTR$ 4 A. Fission and Activation Gases

1. 'otal Release Ci 1.04E+03 3.69E+02
2. Average Release Rate For Period uCi/sec 1.31E+02 4.64E+01 B. Iodines
1. Total Iodine-131 Ci 4.10E-04 1.50E-03
2. Average Release Rate For Period uCi/sec 5.15E-05 1.88E-04 C. Particulates
1. Particulates (Half Life > 8 days) Ci 2.03E-05 8.05E-05
2. Average Release Rate For Period uCi/sec 2.55E-06 1.01E-05
3. Gross Alpha Radioactivity Ci 3.07E-08 2.81E-08

,D. Tritium

1. Total Release Ci 3.26E+00 9.87E+00
2. Average Release Rate For Period uCi/sec 4.10E-01 1.24E+00 16

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 8 2 SEMIANNUAL REPORT JULY 1~ 1 99 1 THROUGH DECEMBER 3 1 ~ 1 99 1 TABLE 3.6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR$ 3 QTRg4 A. Fission and Activation Gases

1. Total Release Ci 1.44E+02 1.47E+02
2. Average Release Rate For Period uCi/sec 1.81E+01 1.84E+01 B. Iodines 1.. Total Iodine-131 Ci 9.28E-04 3.69E-04
2. Average Release Rate For Period uCi/sec 1.17E-04 4.64E-05 C. Particulates
1. Particulates (Half Life > 8 days) Ci O.OOE+00 O.OOE+00
2. Average Release Rate For Period uCi/sec O.OOE+00 O.OOE+00
3. Gross Alpha Radioactivity Ci 1.35E-08 4.15E-08 D. Tritium
1. Total Release Ci 2.14E+01 2.77E+01
2. Average Release Rate For Period uCi/sec 2.70E+00 3.49E+00 17

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT ¹ 1 SEMIANNUAL REPORT JULY 1, 1991 THROUGH DECEMBER 31, 1991 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclides Continuous Mode Batch Mode Released Unit QTR¹3 QTR¹4 QTR¹3 QTR¹4

1. Fission Gases AR-41 Ci O.OOE+00 O.OOE+00 4.92E-03 1.35E-01 KR-85M Ci 1.33E+01 1.38E+00 1.59E-01 3.99E-01 KR-85 Ci O.OOE+00 O.OOE+00 1.08E+01 2.49E+01 KR-87 Ci 1.22E+00 O.OOE+00 1.06E-03 1.30E-02 KR-88 Ci 1.47E+01 O.OOE+00 3.70E-02 2.95E-01 KR-89 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-90 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00,,

XE-127 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-131M Ci O.OOE+00 O.OOE+00 1.22E+00 9.11E-01 XE-133M Ci 1.06E+01 O.OOE+00 3.09E+00 2.16E+00 XE-133'E-135M Ci, 6.43E+02 2.00E+02 1.78E+02 1.08E+02 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-135 Ci 1.58E+02 2.30E+01 4.27E+00 7.51E+00 XE-137 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-138 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci 8.41E+02 2.24E+02 1.97E+02 1.44E+02

2. Iodines I-131 Ci 4.10E-04 1.50E-03 I-132 Ci O.OOE+00 2.34E-03 I-133 Ci 1.75E-03'.OOE+00 5.05E-03 I-134 Ci O.OOE+00 I-135 Ci O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci 2.16E-03 8.89E-03
3. Particulates ( > 8 Days)

Cr-51 Ci O.OOE+00 O.OOE+00 Mn-54 Ci O.OOE+00 O.OOE+00 Fe-55 Ci O.OOE+00 O.OOE+00 Co-57 Ci O.OOE+00 O.OOE+00 Co-58 Ci O.OOE+00 4.38E-05 Fe-59 Ci O.OOE+00 O.OOE+00 Co-60 Ci 2.03E-05 2.70E-05 Zn-65 Ci O.OOE+00 O.OOE+00 Zr-95 Ci O.OOE+00 O.OOE+00 Nb-95 Ci O.OOE+00 O.OOE+00 18

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 8 1 SEMIANNUAL REPORT JULY 1g 1991 THROUGH DECEMBER 31'991 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)

Nuclides Continuous Mode Released Unit QTR$ 3 QTRg4

3. Particulates ( > 8 Days) (continued)

Sr-89 Ci O.OOE+00 O.OOE+00 Sr-90 Ci O.OOE+00 O.OOE+00 Y-90 Ci O.OOE+00 O.OOE+00 Ru-103 Ci O.OOE+00 O.OOE+00 Ag-110 Ci O.OOE+00 O.OOE+00 Sn-113 Ci O.OOE+00 O.OOE+00 Sb-124 Ci O.OOE+00 O.OOE+00 Sb-125'e-129m Ci O.OOE+00 O.OOE+00 Ci O.OOE+00 O.OOE+00 Cs-134 Ci O.OOE+00 O.OOE+00 Cs-136 Ci O.OOE+00 O.OOE+00 Cs-137 Ci O.OOE+00 9. 76E-06 Ba-140 Ci O.OOE+00 O.OOE+00 Ce-141 Ci O.OOE+00 O.OOE+00 Ce-144 Ci O.OOE+00 O.OOE+00 TOTAL'OR PERIOD Ci 2.03E-05 8.05E-05

4. -Particulates ( < 8 Days)

Mn-56 Ci O.OOE+00 O.OOE+00 Ni-65 Ci O.OOE+00 O.OOE+00 Br-82 Ci O.OOE+00 O.OOE+00 Rb-88 Ci O.OOE+00 O.OOE+00 Rb-89 Ci O.OOE+00 O.OOE+00 Sr-91 Ci O.OOE+00 O.OOE+00 Sr-92 Ci O.OOE+00 O.OOE+00

'-92 Ci O.OOE+00 O.OOE+00 Zr Ci O.OOE+00 O.OOE+00 Nb-97 Ci O.OOE+00 O.OOE+00 Tc-99m Ci O.OOE+00 O.OOE+00 Mo-99 Ci O.OOE+00 O.OOE+00 Sb-122 Ci O.OOE+00 O.OOE+00 Te-129 Ci O.OOE+00 O.OOE+00 Te-132 Ci O.OOE+00 O.OOE+00 Cs-138 Ci O.OOE+00 O.OOE+00 La-140 Ci O.OOE+00 O.OOE+00 Pr-144 Ci O.OOE+00 O.OOE+00 W-187 Ci O.OOE+00 O.OOE+00 Np-239 Ci O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci O.OOE+00 O.OOE+00

($ 9

<e FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 4 2 SEMIANNUAL REPORT JULY 1i 1991 THROUGH DECEMBER 31i 1991 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclides Released Unit Continuous Mode QTRg3 QTR44 QTR$ 3, Batch Mode QTRg4

1. Fission Gases AR-4 1 Ci O.OOE+00 O.OOE+00 2.53E-01 2.49E-01 KR-85M Ci O.OOE+00 0.00E+00 2.00E-02 2.83E-02 KR-85 Ci O.OOE+00 O.OOE+00 8.62E-01 1.86E+00 KR-87 Ci O.OOE+00 O.OOE+00 2.05E-04 O.OOE+00 KR-88 Ci O.OOE+00 O.OOE+00 9.98E-03 4.26E-03 KR-89 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-90 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-127 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-131M Ci O.OOE+00 O.OOE+00 4.53E-01 1.12E+00 XE-133M Ci O.OOE+00 O.OOE+00 2.95E-01 8.04E-01 XE-133 Ci 1.05E+02 5.56E+01 2.91E+01 8.20E+01 XE-135M Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-135 Ci 7.22E+00 4.52E+00 4.43E-01 3.61E-01 XE-137 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-138 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci 1.12E+02 '.02E+01 3.14E+01 8.65E+01
2. Iodines I-131 Ci 9.28E-04 3'.69E-04 I-132 Ci O.OOE+00 O.OOE+00 I-133 Ci 3.35E-03 1.28E-03 I-134 Ci O.OOE+00 O.OOE+00 I-135 Ci O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci 4.28E-03 1.65E-03
3. Particulates ( ) 8 Days)

Cr-51 Ci O.OOE+00 O.OOE+00 Mn-54 Ci O.OOE+00 O.OOE+00 Fe-55 Ci O.OOE+00 O.OOE+00 Co-57 Ci O.OOE+00 O.OOE+00 Co-58 Ci O.OOE+00 O.OOE+00 Fe-59 Ci O.OOE+00 O.OOE+00 Co-60 Ci O.OOE+00 O.OOE+00 Zn-65 Ci O.OOE+00 O.OOE+00 Zr-95 Ci O.OOE+00 O.OOE+00 Nb-95 Ci O.OOE+00 O.OOE+00 20

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 4 2 SEMIANNUAL REPORT JULY 1g 1991 THROUGH DECEMBER 31~ 1991 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)

Nuclides Continuous Mode Released Unit QTRg3 QTRg4

3. Particulates ( > 8 Days) (continued)

Sr-89 Ci O.OOE+00 O.OOE+00 Sr-90 Ci O.OOE+00 O.OOE+00 Y-90 Ci 0.00E+00 O.OOE+00 RU-103 Ci 0.00E+00 O.OOE+00 A'g-110 Ci O.OOE+00 O.OOE+00 Sn-113 Ci O.OOE+00 O.OOE+00 Sb-124 Ci O.OOE+00 O.OOE+00 Sb-125 Ci O.OOE+00 O.OOE+00 Te-129m Ci O.OOE+00 O.OOE+00 Cs-134 Ci O.OOE+00 O.OOE+00 Cs-136 Ci O.OOE+00 O.OOE+00 Cs-137 Ci O.OOE+00 O.OOE+00 Ba-140 Ci O.OOE+00 O.OOE+00 Ce-141 Ci O.OOE+00 O.OOE+00 Ce-144 Ci O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci O.OOE+00 O.OOE+00

4. Particulates ( < 8 Days)

Mn-56 Ci O.OOE+00 O.OOE+00 Ni-65 Ci O.OOE+00 O.OOE+00 Br-82 Ci O.OOE+00 O.OOE+00 Rb-88 Ci O.OOE+00 O.OOE+00 Rb-89 Ci O.OOE+00 O.OOE+00 Sr-91 Ci O.OOE+00 O.OOE+00 Sr-92 Ci O.OOE+00 O.OOE+00 Y-92 Ci O.OOE+00 O.OOE+00 Zr-97 Ci O.OOE+00 0'.OOE+00 Nb-97 Ci O.OOE+00 O.OOE+00 Tc-99m Ci O.OOE+00 O.OOE+00 Mo-99 Ci O.OOE+00 O.OOE+00 Sb-122 Ci O.OOE+00 O.OOE+00 Te-129 Ci O.OOE+00 O.OOE+00 Te-132 Ci O.OOE+00 O.OOE+00 Cs-138 Ci 0.00E+00 0.00E+00 La-140 Ci O.OOE+00 O.OOE+00 Pr-144 Ci O.OOE+00 O.OOE+00 W-187 Ci O.OOE+00 O.OOE+00 Np-239 Ci O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci O.OOE+00 O.OOE+00 21

l Iq

FLORIDA'OWER AND LIGHT COMPANY ST. LUCIE PLANT UNIT 8 1 TABLE 3.8-1 GASEOUS EFFLUENTS DOSE SUMMATION AGE GROUP: INFANT EXPOSURE INTERVAL JANUARY 1 ~ 1 9 9 1 THROUGH DECEMBER 3 1 g 1991 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 PATHWAY mrem mrem mrem mrem GROUND PLANE (A)

COW -MILK (B) 1.47E-04 3.63E-04 5.16E-02 1.23E-04 INHALATION (A) 4.67E-06 2.97E-04 1.94E-03 1.28E-04 TOTAL 1.52E-04 6.59E-04 5.35E-02 2.51E-04 LUNG GI-LLI T. BODY PATHWAY mrem mrem mrem GROUND P LANE (A) 2.86E-04 COW -MILK (B) 1.88E-04 1.94E-04 2.80E-04 INHALATION (A) 3.07E-04 2.91E-04 2.93E-04 TOTAL 4.95E-04 4.85E-04 8.59E-04 (A) SECTOR'E RANGE 1.5 (B) SECTOR: WEST 'ANGE:

4.25 NOBLE GASES CALENDER YEAR (mrad)

GAMMA AIR DOSE 3.66E-02 BETA AIR DOSE 6.57E-02 SECTOR: SE RANGE: 1.5 MILES 22

FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT UNIT t 2 TABLE 3.8-1 GASEOUS EFFLUENTS DOSE SUMMATION AGE GROUP: INFANT EXPOSURE INTERVAL JANUARY 1 I 1 9 9 1 THROUGH DECEMBER 3 1 I 1 9 9 1 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 PATHWAY mrem mrem mrem mrem GROUND PLANE (A)

COW -MILK (B) 2.65E-04 7.78E-04 1.02E-01 2.80E-04 INHALATION (A) 9.92E-06 7.26E-04 4.31E-03 3.15E-04 TOTAL 2.75E-04 1.50E-03 1.06E-01 5.95E-04 LUNG GI-LLI T. BODY PATHWAY mrem mrem mrem GROUND PLANE (A) 1.30E-05 COW -MILK (B) 4.57E-04 4.72E-04 6.38E-04 INHALATION (A) 7.13E-04 7.14E-04 7.18E-04 TOTAL 1.17E-03 1.19E-03 1.37E-03 (A) SECTOR: SE RANGE: 1.5 (B) SECTOR: WEST RANGE 4.25 NOBLE GASES CALENDER YEAR (mrad)

GAMMA AIR DOSE 5.35E-03 BETA AIR DOSE 1.36E-02 SECTOR: SE RANGE: 1.5 MILES 23

) I ~

ORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT SEMI-ANNUAL REPORT JULY 1, 1991 THROUGH DECEtiBER 31, 1991

, 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 a'. Spent Resin, M3 3.293 E+1 Process Filters Ci 7.067 E+2
b. Dry Compressible H3 2.365 E+1 Waste (Note 5) Ci 5.621 E-1
c. Irradiated H3 Components Ci
d. Other
1. Non-Compres- H3 2.501 E+0 sible Metal Ci 2.244 E-2 (DAW) (Note 6)
2. Estimate of Major Nuclide Composition (By Type of Waste)

Category Nuclides  %%u4

a. Cs 137 3.90 E+1 Cs 134 3.67 E+1 Co 60 1.02 E+1 Fe 55 5.20 E+0 Ni 63 2.87 E+0 Co 58 2.03 E+0 Be 7 1.50 E+0 Mn 54 6.90 E-1
b. Cs 137 3.31 E+1 Fe 55 2.46 E+1 Co 60 1.99 E+1 Cs 134 8.28 E+0 Co 58 4.81 E+0 H 3 2.37 E+0 Ni 63 2.26 E+0 Sb 125 1.59 E+0 c~ N/A N/A 24

t j\ IP ~

l fl ls

Page 2 St. Lucie Plant Semi Annual Report

d. Fe 55 3.83 E+1 Co 60 2.87 E+1 Co 58 1.06 E+1 I 131 4.92 E+0 H 3 3.91 E+0 Cs 137 3.23 E+0 Ni 63 3.20 E+0 Mn 54 2.33 E+0 Nb 95 1.92 E+0 Sn 113 1.51 E+0
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Sole Use Truck Barnwell, S. C.

Sole Use Truck S.E.G.

Oak Ridge, Tenn.

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

/jat 25

~ ~

0

l. A ~

n

~ 0

S'il "ANNUAL REPORT JULY 1, 1991 THROUGH DEC. 31, 1991 UNITS 1 AND 2, 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 & 2) (Note 3) 1.21 (Note 4) Agent Class A 835.30 5.621 E"1 N/A PWR l.b. Non- None Compactible specification Trash Strong Tight (Note 5) Package Class A 88.31 2.444 E-2 N/A PWR l.d. Non- None Non-Compactible specification Trash Strong Tight (Note 6) Package Class A 390.30 3.793 E-4 N/A PWR l.a. Non- None Ion-Exchange specification Resin (Note 5) Strong Tight Package Class A 411.60 4. 363 CS137, Sr90 PWR l.a. NRC Certified None Ion-Exchange LSA Resin Type A Class C 120.30 103.647 C14, Pu241, TRU, PWR 10a ~ NRC Certified None C060, Ni63, Sr90, Ion"Exchange LSA CS137, Sum of Resin Type A Nuclides T~> < 5 yr.

Class C 120.30 33.913 C14, Pu241, TRU, PWR l.a. NRC Certified None C060, Ni63, Sr90, Process Type B CS137, Sum of Filters Nuclides T~> < 5 yr.

Class C 120.30 564.772 C14, C060, Ni63, PWR l.a. NRC Certified None Sr90, CS137, Sum of Ion-Exchange Type B Nuclides T~~ < 5 yr. Resin

A ORIDA POWER AND LIGHT COMPANY ST- LUCIE PLANT SEMI-ANNUAL REPORT JULY 1, 1991 THROUGH DEC&iBER 31, 1991 UNITS 1 AND 2 TABLE 3.9 (CONTINUED)

SOLID WASTE SUPPLIANT 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 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 radionculides. 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.

"Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than .Ol 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.

"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".

"Type of Container" refers to the transport package.

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, seven shipments of Dry Compressible Waste (3,680 cubic feet, 9.46E-1 curies), dewatered secondary resin (904.4 cubic feet, 1.09 E-2 curies), sewage treatment plant solids (828 cubic feet, 4.48 E"2 curies), and waste oil (4757 gallons, 6.78 E-8 curies) were made from the St. Lucie Plant to the volume reduction facility. This material was shipped via "Sole Use Truck" in non-specification strong tight packages.

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 at the Barnwell, South Carolina burial facility. During the reporting period, no shipments of non-compressible metal waste was made from the St.

Lucie Plant to the volume reduction facility.

27

ATTACHMENT A UNPLANNED GASEOUS EFFLUENT RELEASE of February 5 & 6, 1991

1) Description and analysis of event
2) Hourly average site meteorological data for February 5 and February 6, 1991.

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Attachment A

1) Description and analysis of event Gas Decay Tank 2C (GDT 2C) was aligned to the Plant Vent for a scheduled batch release under the Control of Operating Procedure No. 2-0530021, Rev. 15 as Gas Release Permit No. 2-91-18 at a starting pressure of 165 psig. The Senior Nuclear Plant Operator,(SNPO) made the alignment as per the procedure.

Upon rechecking the progress of the release he noted that Gas Decay Tank 2B had decreased in pressure from 159 psig to 73 psig as GDT 2C was being released. The SNPO terminated the release and rechecked the valve line up which would have included checking shut valves in shut direction. Subsequent to the above event, GDT 2A was released and GDT 2B did not reduce in pressure during this release, indicating the most probable cause was a valve outlet from GDT 2B (to the release header) was not fully seated during the release of GDT 2C (Permit 2-91-18), but was fully seated during the SNPO's recheck of the valve lineup.

a) The normal practice is to check the non-releasing GDT's for pressure drop when a release is initiated. Since the starting tank (2C) was 6 psig higher than GDT 2B, the 2B tank did not appear to change at the time 2C started it' release. When the two tanks equalized in pressure, both started to release to the plant vent.

b) The release path was administratively controlled in that the release rate was throttled to maintain less than the prescribed rate on the permit for 2C and the path was set to automatically trip if the concentration in the path exceeded 20 uCi/cc (28.5% of the Site Limit) as measured by the Gas Release Effluent Monitor and it's set points as per the permit controlling the 2C release. In addition, the Monitor was Source Checked prior to the release as per procedure for each release. The release path is also monitored by the Plant Vent Gas Monitor where the setpoints would alarm prior to exceeding the Site Limit for Gaseous Releases. In this sense the additional release from GDT 2B was not uncontrolled due to the administrative and physical controls used for this release path.

c) The Chemistry Radioassay of GDT 2B indicated an activity level 3.8 times higher than the permitted GDT 2C, but only 0.05 percent of the Administrative Limit allowed for this pathway. Both tanks together only achieved 0.06 percent of the Administrative Limit (28.54 of the site limit) .

29

e

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Attachment A (Continued) d) The SNPO was instructed on the importance of verifying LOCKED CLOSED Valves fully closed on these tanks.

e) Given the normal (and maximum historical) activity levels of these tanks and the Procedural and Administrative Conservative Setpoints involved with this release path, an Administrative Release Activity Limit or a Site Limit was not exceeded.

f) The Gaseous Release Procedures for both Units were revised to verify that the outlet valves for the two Gas Decay Tanks not being released are verified closed.

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FLOR I DA POWERFUL I GHT COMPANY ST. LUCIE METEOROLOGICAL DATA FEB 5, 1991 HOUR WIND DRCTN. 0 SPEED TEMPERATURE DELTA-T SIGMA THETA RAIN ENDING 60-METER 10"METER SYS TENP SYS CAT CAT E.S. T. DEG NPH DEG NPH DEG. F DEG. C/100M DEG IN.

93 15.7 86 8.7 A 70 3

~ A -0 ' E 10.0 D 0.00 83 lb.9 76 8.7 A 70.4 A "0.2 E 10 ' D 0.00 89 17.0 82 8.9 A 70.4 A -0.2 E 11.6 D 0.00 89 15.2 83 8.2 A 70.5 A -0.3 E >> .8 D 0.00 87 15.0 80 8.1 A 70.5 A -0.3 E 12.3 D 0. 00 91 12 ~ 6 84 6.9 A 70.3 A -0.3 E 12 ~ 0 D 0. 00 85 12 ~ 1 78 6.4 A 70.2 A -0.2 E 12.5 D 0,00 92 12.5 83 6.7 A 70.6 A -0.3 E 12.8 C 0. 00 95 12.5 88 7.4 A 71.7 A -0.7 D 10.1 D 0. 00" 10 96 NISG 85 NISB A 72.8 A -1.2 D 11.7 D 0.00 '

96 NISG 89 NISG 72.9 A-1 ~ 2 D 9.8 D 0. 00 12 97 NISG 92 NISG A 73.7 A -1.7 B 8.5 D 0 ~ 00 97 NI SG 90 NI.SG A 73.1 A "1.5 C 9.5 D 0.00 14 100 NISG 95 NISG A 73.3 A -2.0 A 7.5 D 0. 00 15 101 NISG 95 NISG 73. 2 A "2.0 A 7.5 D 0 ~ 00 16 95 NISB 91. NISG A 72.6 A-16. C 87 D 000 17 99 15.8 92 9.9 A 72.0 A -1.2 D 7.5 E 0.00 18 106 14. 0 99 8. 4 A 71.6 A -0.9 D 10.1 D 0. 00 107 14.2 100 8.1 A 71.1 A -.0.4 E 9.8. D 0.00 20 106 14 ' 98 8.3 A 71.0 A -0.4 E 11.1 D 0 ~ 00 21 110 14. 9 102 8. 5 A 70.9 A-04 E 103 D 0. 00 22 116 15 0

~ 109 8. 6 A 70.7 A -0.3 f 10.0 D 0.00 lih 13 ' 109 7.6 A 70 6

~ A -0.3 E 11.8 D 0.00 24 115 14.1 107 7.9 A 70.6 A "0 ~ 4 E 123 9 0.00

-SUNNARY OF DAY NAX!NUN: 17.0 9.9 73.7 TOTAL: 0 00 F

MEAN 14.4 8.1 71.5 MINIMUM: 12.1 6.4 70.2 30

cr "

ST. LUCIE METEOROLOGICAL DATA FEB 6) 1991 HOUR MIND DRCTN. 0 SPEED TEMPERATURE DELTA-T SIGNA THETA RAIN ENDING 60-METER 10-METER SYS TEMP SYS CAT CAT EBS.T. DEG NPH DEG NPH DEG. F DEG. C/100M DEG IN.

114 11.8 107 6.9 A 70.5 A -0.3 E 9~8 D 0. 00 129 11.4 121 F 1 A 70.2 A "0.2 E 9.4 D 0. 00 121 12.4 114 7.0 A 70.2 A -0.2 E 10.5 D 0. 00 120 12.5 112 7.0 A 70.0 A -0.2 E 10.1 D 0 ~ 00 121 10 6

~ 113 6. 0 A 69 ' A -0.2 E 11.8 D 0. 00 120 8. 5 112 4. 6 A 69.8 A -0.0 E 13.2 C 0.00 7 124 75 119 38 A 69.5 A 0.3 E 10.8 D 0.00 8 177 5.1 223 2.7 A 66.8 A 1.8 F N/A 0. 00 9 173 4.0 222 1.9 A 68.0 A 1.1 E N/A 0. 00 ~

4 10 NISG 7.7 NISG 5' A 71.9 A -1.1 D NISG 0.00 =

11 NISG 7. 7 NISG 6. 0 A 73.4 A-1 ~ 9 A NI SG - 0. 00 12 NI SG 7. 5 Nl SG 5. 8 A 73.5 A -1.7 C NISG - 0.00 NI SG 7. 3 NI SG 6 ..2 A 73.9 A -1.8 8 NISG - 0.00 MISS 6~5 NI SG 5. 4 A 73.4 A -1.7 C 58.2 A 0. 00 15 111 7 0 98 6 2 A 73.2 A -1 6 C ii 6 D 0.00 16 iii 7.9 104 6.3 A 73.1 A -1.6 C ii 6 F D 0.00 17 109 8.1 98 6.1 A 72.6 A -1.4 D 10.9 D 0. 00 18 108 8.4 98 5.3 A 71.8 A -1 ~ 0 D ii 0 D 0. 00 109 8..7 105 4.9 A 71.0 A -0 ~ 4 E 11..5 D 0. 00 20 108 6.7 105 3.2 A 70.6 A -0.0 E N/A 0. 00 21 111 6.1 106 3.2 A 70.6 A 0.0 E N/A 0. 00 22 103 8. 5 98 4 ~ 8 A 70.7 A 0.0 E 10.4 D 0.00 109 8.8 105 5.0 A 71 0

~ A -0.1 E 10.9 D 0 ~ 00 24 110 9 ' 104 5.1 A 71.1 A -0.1 E 13.6 C 0. 00

SUMMARY

OF DAY MAX INUN: 12.5 7.0 73.9 TOTAL: 0.00 MEAN 8.3 5.2 71. 1 NININUN: 4.0 1.9 66.8 31

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