ML17309A696

Combined Semiannual Radioactive Effluent Release Rept for Jul-Dec 1992. W/930226 Ltr

ML17309A696
Person / Time
Site:	Saint Lucie
Issue date:	12/31/1992
From:	Sager D FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-93-049, L-93-49, NUDOCS 9303030028
Download: ML17309A696 (83)

Text

1 ACCELERATgjP DOCUVlENT DIST UTION SYSTEM Ik REGULAT~ INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION NBR:9303030028 DOC.DATE: ~J+444 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 a Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION SAGER,D.A. Florida Power !l Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Combined Semiannua dioactive Effluent Release Rept for Jul-Dec 1992." W 930226 ltr.

DISTRIBOTION CODE: IE48D TITLE: 50.36a(a)(2)

COPIES RECEIVED:LTR Semiannual l ENCL Effluent Release Reports L SIZE: 0'~

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 1 1 NRR/DRSS/PRPB11 2 2 REG FI E 01 1 1 RGN2 DRSS/RPB 2 2 RGN FILE 02 1 1 EXTERNAL: BNL TICHLERPJ03 1 1 EG&G SIMPSON,F 2 2 NRC PDR 1 1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACI'HE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 16

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P.O. Box 128, Ft. Pierce, FL 34954-0128 February 26, 1993 L-93-49 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, 1992, through December 31, 1992, for St. Lucie Units 1 and 2. This report is required by Technical Specification 6.9.1.7.

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

Very truly yours, D. A. ger Vice esident St. L ie Plant DAS:JJB:kw cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant Attachment.

DAS/PSL $ 872-93 9303030028 921231 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 i 1992 THROUGH DECEMBER 3 1 I 1992

'....9303030028

br TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION ........... 1 OFFSITE DOSE CALCULATION MANUAL REVISIONS .......-. ............

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SOLID WASTE AND IRRADIATED FUEL SHIPMENTS.......--. ...........- 7 PROCESS CONTROL PROGRAM REVISIONS......'........--...--........-.. 7 LIQUID EFFLUENTS:

Summation of all Releases Unit ¹ 1 8 Summation of all Releases Unit ¹ 2 9 Nuclide Summation by Quarter Unit ¹ 1 10 Nuclide Summation by Quarter Unit ¹ 2 12 Liquid Effluent Dose Unit ¹ 1 14 Liquid Effluent Dose Unit ¹ 2 15 GASEOUS EFFLUENT:

Summation of all Releases Unit ¹ 1 16 Summation of all Releases Unit ¹ 2 17 Nuclide Summation by Quarter Unit ¹ 1 18 Nuclide Summation by Quarter Unit ¹ 2 20 Gas Effluent Dose Unit ¹ 1 22 Gas Effluent Dose Unit ¹ 2 23 SOLID WASTE SHIPMENT SUMMATION .....................'....... 24 Attachment A UNPLANNED Gas Release of September 16, 1992 ... 28 I

Attachment B UNPLANNED Gas Release of November 04, 1992 37

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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.

• BE 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.

• CD 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 calculations 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 fi'ssion"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 Avgo o 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 0 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.

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EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

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

4.1 (Continued)

B. (Continued)

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-

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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.PE 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 Effluent Totals.

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

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EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

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

B. (Continued)

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.ST 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 6 Sr-90 CPS.

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

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 0 1 SEMIANNUAL REPORT JULY 1, 1992 THROUGH DECEMBER 31, 1992 EFFLUENT & WASTE DISPOSAL SUPPLEMENTAL~INFORMATION (CONTINUED)

5. Batch Releases A. Liquid

1. Number of batch releases: 43

2. Total time period for batch releases: 19546 minutes

3. Maximum time period for a batch release: 635 minutes

4. Average time period for a batch release: 455 minutes

5. Minimum time period for a batch release: 296 minutes

6. Average dilution stream flow during the period: 1004730 gpm All liquid releases are summarized in tables.

B. Gaseous 1 ~ Number of batch releases: 49 2 ~ Total time period for batch releases: 24597 minutes 3 ~ Maximum time period for a batch release: 2025 minutes 4 ~ Average time period for a batch release: 502 minutes

5. Minimum time period for a batch release: 110 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: 1

2. Total activity of releases: 1.17E-04 Curies C. See attachments (if applicable) for:

l. 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 UNIT 5 2 SEMIANNUAL REPORT JULY 1g 1992 THROUGH DECEMBER 31~ 1992 EFFLUENT & WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)

5. Batch Releases A. Liquid

1. Number of batch releases: 42

2. Total time period for batch releases: 19091 minutes

3. Maximum time period for a batch release: 635 minutes

4. Average time period for a batch release: 455 minutes

5. Minimum time period for a batch release: 296 minutes

6. Average dilution stream flow during the period: 1004730 gpm All liquid releases are summarized in tables.

B. Gaseous

1. Number of batch releases: 126

2. Total time period for batch releases: 35705 minutes

3. Maximum time period for a batch release: 1127 minutes

4. Average time period for a batch release: 283 minutes

5. Minimum time period for a batch release: 28 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: 1

2. Total activity of releases: 9.84E-02 Curies C. See attachments (if applicable) for:

l. 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.

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 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 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 CALENDAR YEAR 1992 were:

Gamma Air Dose 6.72E-03 Beta Air Dose 1.42E-03 GASEOUS PARTICULATE Bone 6.46E-06 Liver 2.80E-04 Thyroid 2.50E-03 Kidney 1.21E-04 Lung 2.85E-04 GI-LLI 2.72E-04 Total Body 5.47E-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 for the site. Common Solid waste from St. Lucie Units 1 and 2 were shipped jointly.

A tabulated summation of these shipments is provided in this report.

10. Process Control Program (PCP) Revisions:

The PCP was not revised during the reporting interval.

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 8 1 SEMIANNUAL REPORT JULY 1g 1992 THROUGH DECEMBER 31~ 1992 TABLE 3.3-1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTRS3 QTR54 A. Fission and Activation Products

1. Total Release (Not including Tritium, Gases, and Alpha) Ci g1 1.18E-01 5 '2E-02

2. Average Diluted Concentration During Period uci/ml 2.37E-10 1.06E-10 B. Tritium

1. Total Release Ci 1.57E+02 8.86E+01

2. Average Diluted Concentration During Period uci/ml 3.17E-07 1.73E-07 C.~ Dissolved and Entrained Gases

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~ Total Release Ci 4.71E-01 1.32E-Ol

2. Average Diluted Concentration During Period uci/ml 9.48E-10 2.59E-10 D. Gross Alpha Radioactivity

1. Total Release Ci O.OOE+00 O.OOE+00 E. Volume of Waste Released (Prior to Dilution) Liters 2.58E+06 2.72E+06 F. Volume of Dilution Water Used During Period Liters 4.97E+ll 5.11E+11

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FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT 5 2 SEMIANNUAL REPORT JULY 1g 1992 THROUGH DECEMBER 31~ 1992 TABLE 3.3-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR83 QTRN4 A. Fission and Activation Products

1. Total Release (Not including Tritium, Gases, and Alpha) Ci 1.18E-01 5.42E-02

2. Average Diluted Concentration During Period uci/ml 2.37E-10 1.06E-10 B. Tritium

1. Total Release Ci 1.57E+02 8.86E+01

2. Average Diluted Concentration During Period uci/ml 3. 17E-07 1. 73E-07 C.~ Dissolved and Entrained Gases 1.

~ Total Release Ci 4. 71E-01 1. 32E-01

2. Average Diluted Concentration 9.48E-10 2.59E-10 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 2.58E+06 2.72E+06 F. Volume of Dilution Water Used During Period Liters 4.97E+11 5.11E+11

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FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT ¹ 1 SEMIANNUAL REPORT JULY 1, 1992 THROUGH DECEMBER 31, 1992 TABLE 3.4-1 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES QTR¹3 QTR¹4 QTR¹3 QTR¹4 RELEASED UNIT NA-24 Ci O.OOE+00 O.OOE+00 2.51E-04 1.72E-04 CR-51 Ci O.OOE+00 O.OOE+00 5.99E-03 2.46E-03 MN-54 Ci O.OOE+00 O.OOE+00 3.96E-04 3.11E-04 FE-55 Ci O.OOE+00 O.OOE+00 1.43E-02 9.05E-03 MN-56 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-57 Ci O.OOE+00 O.OOE+00 1.35E-05 1.99E-05 CO-58 Ci O.OOE+00 O.OOE+00 1.79E-02 1.79E-02 FE-59 Ci O.OOE+00 O.OOE+00 4.44E-04 1.39E-04 CO-60 Ci O.OOE+00 O.OOE+00 9.03E-03 .3..54E-03 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 RB-88 Ci O.OOE+00 O.OOE+00 O.OOE+00 3.22E-04 SR-89 Ci O.OOE+00 O.OOE+00 3.92E-04 2.49E-04 SR-90 Ci O.OOE+00 O.OOE+00 1.22E-05 9.57E-06 Y-90 Ci O.OOE+00 O.OOE+00 1.22E-05 9.57E-06 SR-91 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-92 Ci O.OOE+00 O.OOE+00 1.44E-04 O.OOE+00 Y-92 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 Ci O.OOE+00 O.OOE+00 1.04E-03 5.75E-04 NB-95 Ci O.OOE+00 O.OOE+00 1.45E-03 8.99E-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 5.55E-04 2.38E-04 TC-99M Ci O.OOE+00 O.OOE+00 8.87E-05 O.OOE+00 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 O.OOE+00 AG-110 Ci O.OOE+00 O.OOE+00 5.62E-04 1.64E-04 SN-113 Ci O.OOE+00 O.OOE+00 1.18E-04 2.20E-05 SB-122 Ci O.OOE+00 O.OOE+00 1.38E-03 3.36E-05 SB-124 Ci O.OOE+00 O.OOE+00 6.37E-03 6.50E-03 SB-125 Ci O.OOE+00 O.OOE+00 1.27E-02 5.91E-03 10

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FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT ¹ 1 SEMIANNUAL REPORT JULY lg 1992 THROUGH DECEMBER 31, 1992 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 1.69E-03 3.37E-04 TE-129M Ci O.OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 I-131 Ci O.OOE+00 O.OOE+00 1.05E-03 2.74E-04 TE-132 Ci O.OOE+00 O.OOE+00 6.61E-05 O.OOE+00 I-132 Ci O.OOE+00 O.OOE+00 1.96E-04 4.69E-06 I-133 Ci O.OOE+00 O.OOE+00 3.47E-03 1.55E-04 I-134 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-134 Ci O.OOE+00 O.OOE+00 1.73E-02 1.59E-03 I-135 Ci O.OOE+00 O.OOE+00 1.47E-03 O.OOE+00 CS-136 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-137 Ci O.OOE+00 O.OOE+00 1.48E-02 1.64E-03 CS-138 Ci O.OOE+00 O.OOE+00 2.20E-04 1.24E-04 BA-140 Ci O.OOE+00 O.OOE+00 8.87E-05 O.OOE+00 LA-140 Ci O.OOE+00 O.OOE+00 3.26E-03 7.12E-04 CE-141 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 Ci '.OOE+00 O.OOE+00 O.OOE+00 6.59E-05 PR-144 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 W-187 Ci O.OOE+00 O.OOE+00 1.10E-03 8.23E-04 NP-239 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD CI 0 OOE+00 O.OOE+00 1.18E-01 5.42E-02 AR-41 CI O.OOE+00 O.OOE+00 O.OOE+00 1.08E-05 KR-85M CI O.OOE+00 O.OOE+00 1.32E-04 1 '4E-04 KR-85 CI O.OOE+00 O.OOE+00 O.OOE+00 1.68E-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 8.00E-05 XE-131M CI O.OOE+00 O.OOE+00 2.37E-03 2.66E-04 XE-133M CI O.OOE+00 O.OOE+00 5.63E-03 1.66E-03 XE-133 CI O.OOE+00 O.OOE+00 4.46E-01 1.19E-01 XE-135M CI O.OOE+00 O.OOE+00 8.76E-04 O.OOE+00 XE-135 CI O.OOE+00 O.OOE+00 1.58E-02 9.11E-03 11

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FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT ¹ 2 SEMIANNUAL REPORT JULY 1g 1992 THROUGH DECEMBER 31'992 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- 2.51E-04 1.72E-04 CR-51 CI O.OOE+00 O.OOE+00 5.99E-03 2.46E-03 MN-54 CI O.OOE+00 O.OOE+00 3.96E-04 3 '1E-04 FE-55 CI O.OOE+00 O.OOE+00 1.43E-02 9.05E-03 MN-56 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-57 CI O.OOE+00 O.OOE+00 1.35E-05 1.99E-05 CO-58 CI O.OOE+00 O.OOE+00 1.79E-02 1.79E-02 FE-59 CI O.OOE+00 O.OOE+00 4.44E-04 1.39E-04 CO-60 CI O.OOE+00 O.OOE+00 9.03E-03 3.54E-03 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 RB-88 CI O,.OOE+00 O.OOE+00 O.OOE+00 3.22E-04 SR-89 CI O.OOE+00 O.OOE+00 3.92E-04 2.49E-04 SR-90 CI O.OOE+00 O.OOE+00 1.22E-05 9.57E-06 Y-90 CI O.OOE+00 O.OOE+00 1.22E-05 9.57E-06 SR-91 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-92 CI O.OOE+00 O.OOE+00 1.44E-04 O.OOE+00 Y-92 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 CI O.OOE+00 O.OOE+00 1.04E-03 5 '5E-04 NB-95 CI O.OOE+00 O.OOE+00 1.45E-03 8.99E-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 5.55E-04 2.38E-04 TC-99M CI O.OOE+00 O.OOE+00 8.87E-05 O.OOE+00 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 O.OOE+00 AG-110 CI O.OOE+00 O.OOE+00 5.62E-04 1.64E-04 SN-113 CI O.OOE+00 O.OOE+00 1.18E-04 2.20E-05 SB-122 CI O.OOE+00 O.OOE+00 1.38E-03 3.36E-05 SB-124 CI O.OOE+00 O.OOE+00 6.37E-03 6.50E-03 SB-125 CI O.OOE+00 O.OOE+00 1.27E-02 5.91E-03 1 2

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 8 2 SEMIANNUAL REPORT JULY 1~ 1992 THROUGH DECEMBER 31'992 TABLE 3.4-2 LIQUID EFFLUENTS (CONTINUED)

Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTR53 QTR54 QTR53 QTRg4 TE-129 CI O.OOE+00 O.OOE+00 1.69E-03 3.37E-04 TE-129M CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 I-131 CI O.OOE+00 O.OOE+00 1.05E-03 2.74E-04 TE-132 CI O.OOE+00 O.OOE+00 6.61E-05 O.OOE+00 I-132 CI O.OOE+00 O.OOE+00 1.96E-04 4.69E-06 I-133 CI O.OOE+00 O.OOE+00 3.47E-03 1.55E-04 I-134 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-134 CI O.OOE+00 O.OOE+00 1.73E-02 1.59E-03 I-135 CI O.OOE+00 O.OOE+00 1.47E-03 O.OOE+00 CS-136 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-137 CI O.OOE+00 O.OOE+00 1.48E-02 1.64E-03 CS-138 CI O.OOE+00 O.OOE+00 2.20E-04 1.24E-04 BA-140 CI O.OOE+00 O.OOE+00 8.87E-05 O.OOE+00 LA-140 CI O.OOE+00 O.OOE+00 3.26E-03 7.12E-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 O.OOE+00 6.59E-05 PR-144 CI O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 W-187 CI O.OOE+00 O.OOE+00 1.10E-03 8.23E-04 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 1.18E-01 5.42E-02 AR-4 1 CI O.OOE+00 O.OOE+00 O.OOE+00 1.08E-05 KR-85M CI O.OOE+00 O.OOE+00 1.32E-04 1.04E-04 KR-85 CI O.OOE+00 O.OOE+00 O.OOE+00 1.68E-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 8.00E-05 XE-131M CI O.OOE+00 O.OOE+00 2.37E-03 2.66E-04 XE-133M CI O.OOE+00 O.OOE+00 5.63E-03 1.66E-03 XE-133 CI O.OOE+00 O.OOE+00 4.46E-01 1.19E-01 XE-135M CI O.OOE+00 O.OOE+00 8.76E-04 O.OOE+00 XE-135 CI O.OOE+00 O.OOE+00 1.58E-02 9.11E-03 13

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FLORIDA POWER AND LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMI-ANNUAL REPORT JULY 1 g 1 992 THROUGH DECEMBER 3 1 g 1 992 TABLE 3.5-1 LIQUID EFFLUENTS DOSE SUMMATION AGE GROUP: ADULT LOCATION: ANY ADULT EXPOSURE INTERVAL: JANUARY 1, 1992 THROUGH DECEMBER 31, 1992 FISH AND SHELLFISH CALENDER YEAR ORGAN DOSE (mrem)

BONE 8.57E-02 LIVER 3.76E-01 THYROID 5.19E-03 KIDNEY 3.24E-03 LUNG 4.30E-01 GI-LLI 1.98E-01 TOTAL BODY 1.04E-01 14

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lg FLORIDA POWER AND LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMI-ANNUAL REPORT JULY lg 1992 THROUGH DECEMBER 31'992 TABLE 3.5-1 LIQUID EFFLUENTS DOSE SUMMATION AGE GROUP: ADULT LOCATION: ANY ADULT EXPOSURE INTERVAL: JANUARY lg 1992 THROUGH DECEMBER 31'992 FISH AND SHELLFISH CALENDER YEAR ORGAN DOSE (mrem)

BONE 8.57E-02 LIVER 3.76E-01 THYROID 5.19E-03 KIDNEY 3.24E-03 LUNG 4.30E-01 GI-LLI 1.98E-01 TOTAL BODY 1.04E-01 15

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FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT 8 1 SEMIANNUAL REPORT JULY 1 ~ 1 992 THROUGH DECEMBER 3 1 ~ 1 992 TABLE 3.6-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR53 gTRN4 A. Fission and Activation Gases

1. Total Release Ci 1.73E+02 4.32E+01

2. Average Release Rate For Period uCi/sec 2.17E+Ol 5.44E+00 B. Iodines

1. Total Iodine-131 Ci 3.48E-04 1.35E-04

2. Average Release Rate For Period uCi/sec 4.38E-05 1.69E-05 C. Particulates

1. Particulates (Half Life > 8 days) Ci 1.39E-04 8.87E-05

2. Average Release Rate For Period uCi/sec 1.75E-05 1.12E-05

3. Gross Alpha Radioactivity Ci 2.65E-07 2.49E-07 D. Tritium

1. Total Release Ci 4.79E+00 7.98E-01

2. Average Release Rate For Period uCi/sec 6.03E-01 1.00E-01

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FLORIDA POWER S( LIGHT COMPANY ST. LUCIE UNIT ¹ 2 SEMIANNUAL REPORT JULY lg 1992 THROUGH DECEMBER 31, 1992 TABLE 3.6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR¹3 gTR¹4 A. Fission and Activation Gases

1. Total Release Ci 6.42E+01 3.52E+Ol

2. Average Release Rate For Period uCi/sec 8.08E+00 4.43E+00 B. Iodines

1. Total Iodine-131 Ci 5.42E-04 1.04E-03

2. Average Release Rate For Period uCi/sec 6.81E-05 1.31E-04 C. Particulates Particulates (Half Life > 8 days) Ci 0-OOE+00 O.OOE+00

2. Average Release Rate For Period uCi/sec O.OOE+00 O.OOE+00

3. Gross Alpha Radioactivity Ci 6 '5E-08 6.41E-08 D. Tritium

1. Total Release Ci 3.44E-01 1.31E+00

2. Average Release Rate For Period uCi/sec 4.33E-02 1.64E-01 17

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 5 1 SEMIANNUAL REPORT JULY 1g 1992 THROUGH DECEMBER 31'992 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclides Continuous Mode Batch Mode Released Unit QTR53 QTRg4 QTR53 QTRg4

1. Fission Gases AR-4 1 Ci O.OOE+00 O.OOE+00 8.01E-01 O.OOE+00 KR-85M Ci 5.40E-01 O.OOE+00 1.75E-01 1.27E-03 KR-85 Ci O.OOE+00 O.OOE+00 6.59E+00 2.18E-01 KR-87 Ci O.OOE+00 O.OOE+00 2.73E-02 O.OOE+00 KR-88 Ci 6.52E-01 O.OOE+00 1.85E-01 O.OOE+00 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 7.82E-01 8.63E-02 XE-133M Ci O.OOE+00 O.OOE+00 1.05E+00 9.94E-02 XE-133 Ci 6.53E+01 2.45E+01 7.74E+Ol 1.10E+Ol XE-135M Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-135 Ci 1.56E+01 7.25E+00 3.67E+00 6.48E-02 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 8.21E+01 '.18E+01 9.07E+Ol 1.14E+01

2. Iodines I-131 Ci 3. 48E-04 1.35E-04 I-132 Ci 0; OOE+00 O.OOE+00 I-133 Ci 1.67E-03 7.22E-04 I-134 Ci O.OOE+00 O.OOE+00 I-135 Ci O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci 2.02E-03 8.56E-04

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 1.33E-04 8.87E-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

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT ¹ 1 SEMIANNUAL REPORT JULY 1i 1992 THROUGH DECEMBER 31i 1992 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)

Nuclides Continuous Mode Released Unit QTR¹3 QTR¹4

3. Particulates ( > 8 Days) (continued)

Sr-89 Ci 2.63E-06 O.OOE+00 Sr-90 Ci 1.73E-06 O.OOE+00 Y-90 Ci 1.73E-06 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 Ci O.OOE+00 O.OOE+00 Te-129m Ci O.OOE+00 O.OOE+00 Cs-134 Ci O.OOE+00 0.00E+00 Cs-136 Ci 0-OOE+00 O.OOE+00 Cs-137 Ci O.OOE+00 2.39E-19 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 1.39E-04 8.87E-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 Y-92 Ci O.OOE+00 O.OOE+00 Zr-97 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 19

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 5 2 SEMIANNUAL REPORT JULY 1, 1992 THROUGH DECEMBER 31i 1992 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclides Continuous Mode Batch Mode Released Unit QTR53 QTRg4 QTRN3 QTR54

1. Fission Gases AR-4 1 Ci O.OOE+00 O.OOE+00 3.45E-01 2.70E-01 KR-85M Ci 1.60E-01 O.OOE+00 7.05E-02 3.87E-02 KR-85 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-87 Ci O.OOE+00 O.OOE+00 2.96E-03 4.62E-03 KR-88 Ci O.OOE+00 O.OOE+00 6.47E-02 2.90E-02 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 0;OOE+00 O.OOE+00 2.25E-02 XE-133M Ci O.OOE+00 O.OOE+00 2.78E-01 4.87E-01 XE-133 Ci 3.69E+Ol 1.81E+00 1.34E+Ol 2.04E+01 XE-135M Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-135 Ci 1.10E+Ol 3.70E+00 1.97E+00 1.93E+00 XE-137 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-138 Ci O.OOE+00 6.51E+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci 4.80E+01 1.20E+Ol 1.62E+01 2.32E+01

2. Iodines I-131 Ci 5.42E-04 1.04E-03 I-132 Ci 1.93E-03 1.02E-02 I-133 Ci 4.49E-03 8.93E-03 I-134 Ci O.OOE+00 1.14E-02 I-135 Ci 2.26E-03 1.19E-02 TOTAL FOR PERIOD Ci 9.22E-03 4.35E-02

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

J FLORIDA POWER S( LIGHT COMPANY ST. LUCIE UNIT 8 2 SEMIANNUAL REPORT JULY 1~ 1992 THROUGH DECEMBER 31~ 1992 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)

Nuclides Continuous Mode Released Unit QTR83, QTRN4

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 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 0.00E+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 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 21

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FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT UNIT 5 1 TABLE 3.8-1 GASEOUS EFFLUENTS DOSE SUMMATION AGE GROUP: INFANT EXPOSURE INTERVAL JANUARY 1 ~ 1 992 THROUGH DECEMBER 3 1 g 1 9 92 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) 3.85E-05 1.67E-04 1.28E-02 6.54E-05 INHALATION (A) 2.24E-06 2.55E-04 8.84E-04 1.11E-04 TOTAL 4.08E-05 4.22E-04 1.37E-02 1.77E-04 LUNG GI-LLI T. BODY PATHWAY mrem mrem mrem GROUND PLANE (A) 4.66E-04 COW -MILK (B) 1.26E-04 1.29E-04 1.51E-04 INHALATION (A) 2.78E-04 2.53E-04 2.54E-04 TOTAL 4.04E-04 3.82E-04 8.71E-04 (A) SECTOR: SE RANGE: 1.5 (B) SECTOR: WEST RANGE 4.25 NOBLE GASES CALENDER YEAR (mrad)

GAMMA AIR DOSE 4.32E-03 BETA AIR DOSE 9.51E-03 SECTOR- SE RANGE: 1.5 MILES 22

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FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT UNIT I 2 TABLE 3.8-1 GASEOUS EFFLUENTS DOSE SUMMATION AGE GROUP: INFANT EXPOSURE INTERVAL JANUARY 1 g 1 992 THROUGH DECEMBER 3 1 ~ 1 9 92 NOTE: The below dose results were calculated using actual meterological data during the specified time interval with Met data reduced as per Reg. Guide l.ill, March 1976.

BONE LIVER THYROID KIDNEY PATHWAY mrem mrem mrem mrem GROUND PLANE (A)

C -MILK (B) 2.02E-04 3.73E-04 7.69E-02 1.18E-04 ATION (A) 9.98E-06 2.74E-04 3.85E-03 1.18E-04 TOTAL 2.12E-04 6.47E-04 8.08E-02 2.35E-04 LUNG GI-LLI T. BODY PATHWAY mrem mrem mrem GROUND PLANE (A) 1.94E-05 COW -MILK (B) 1.30E-04 1.41E-04 2.67E-04 INHALATION (A) 2.60E-04 2.62E-04 2.65E-04 TOTAL 3.90E-04 4.03E-04 5.52E-04 (A) SECTOR: SE RANGE: 1.5 (B) SECTOR: WEST RANGE: 4.25 NOBLE GASES CALENDER YEAR (mrad)

GAMMA AIR DOSE 8.82E-03 BETA AIR DOSE 1.83E-02 SECTOR: SE RANGE: 1.5 MILES 23

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FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT SEMI-ANNUAL REPORT JULY 1, 1992 THROUGH DECEMBER 31, 1992 UNITS 1 AND 2, TABLE 3.9 A. Solid Waste Shipped Off-Site for Burial or Disposal

1. T e of Waste Unit 6 Mo. Period Error X Spent Resin, M3 1.603E+1 2.0 E+1 Process Filters Ci 1.438E+2 Dry Compressible M3 7.948E+1 2.0 E+1 Waste (Note 5) Ci 1.963E+0 Irradiated M3 Com onents Ci

d. Other

1. Non-Compressible Waste M3. 2. 941E+0 2.0 E+1 (DAW) (Note 6) Ci 6.496E-3

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

Cate or Nucli des

a. Cs 137 3. 92E+1 CS 134 2.78E+1 Co 58 1.31E+1 Co 60 1.17E+1 Ni 63 3.09E+0 Fe 55. 2.21E+0 Sb 125 1. 13E+0 Mn54 1.02E+0

b. Co 60 2.93E+1 Cs 137 2.30E+1 Fe 55 1.41E+1 Ni 63 1. 06E+1 Co 58 8.68E+0 Cs 134 5.80E+0 CR 51 2. 01E+0 Nb 95 1.66E+0 ZI 95 1.53E+0 Sb 125 7. OOE-1 N/A N/A Co 58 3.48E+1 Fe 55 1.95E+1 Cs 137 1. 81E+1 Co 60 1. 44E+1 Cs 134 8.93E+0 Ni 63 2.52E+0

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

Sole Use Truck S.E.G. Oak Rid e, TN Sole Use Truck Quadrex, Oak Rid e, TN Irradiated Fuel Shipments Number of Mode of Transportation Destination Shi ments N/A N/A N/A = Not Applicable

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SEHI-ANNUAL REPORT e-JULY 1, 1992 THROUGH DECEMBER 31, 1992 UNITS 1 AND 2, TABLE 3.9 (CONTINUED)

Waste Total Total Principal Type of Waste Category Type of Container Solidification Class Volume Curies Radionuclides (Note 3) Reg-Guide (Note 4) Agent Cubic Ft. (Note 1) (Notes 1 8 2) 1.21 Class A 2.806.75 1.963E+0 N/A PWR Compactibl e 1.b Non-Speci ficati on None Trash (Note 5) Strong Tight Packa e Class A 103.86 6.496E-3 N/A PWR Non- 1.d.l Non-Specification None Compactible Trash Strong Tight (Note 6) Packa e Class A 41.60 3. 115E-4 N/A PWR Ion-Exchange 1.a Hon-Specification Hone Resin Strong Tight Packa e Class A 404.20 1.561E+1 Ni 63. Sr 90, Cs PWR Ion-Exchange l.a NRC Certified LSA None 137 Resin T eA Class B 120.30 1.281E+2 Cs 137. Sr 90, Co PWR Ion-Exchange l.a NRC Certified LSA Hone

60. Ni 63. Sum of Resin Type A Huclides with T 1/2 < 5 ears

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FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT SEMI-ANNUAL REPORT JULY 1, 1992 THROUGH DECEMBER 31, 1992 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 and 2 are determined using a combination of ualitative and quantitative techniques. In general, the St. Lucie Plant ollows 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 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 ar used to establish scaling factors or other estimates for radionuclides such as 3H, 14C, 99TC, 129I, TRU, 241Pu, 242Cm, 63Ni, 55Fe, and 90Sr.'Principal NOTE 2: 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 .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 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 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, three shipments of Dry Compressible Waste (2,392 cubic feet, 9.51 E-1 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.

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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. seven shipments of non-compressible metal waste (5,320 cubic feet, 3.44 E-2 curies),secondary resin (857.39 cubic feet, 1.79 E-4 curies) and grit (308.49 cubic feet. 1.62 E-4 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.

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ATTACHMENT A UNPLANNED GASEOUS EFFLUENT RELEASE of SEPTEMBER 16, 1992

1) Description and analysis of event

2) Hourly average site meteorological for September 16, 1992 28

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Attachment A

1) Description and analysis of event Gas Decay Tank 2A (GDT 2A) 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.

2-92-130 at a starting pressure of 151 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 as GDT 2A was being released. The SNPO terminated the release and rechecked the valve line up which would have included checking shut valves in shut direction.. The most probable cause was a valve outlet from GDT 2B (to the release header) was not fully seated during the release of GDT 2A (Permit 2-92-130). At this time the ANPS wrote a Plant Work Order to have Valve Number V-6594 handwheel operating linkage adjusted to ensure full valve closure.

a) The normal practice is to check the non-releasing GDT's drop when a release is initiated. Since the starting for'ressure tank (2A) was 14 psig higher than GDT 2B, the 2B tank did not appear to change at the time 2A started it's release. When the two tanks equalized in pressure, both started to release to the plant vent.

b ) The releas e path was administratively controlled in that the release rate was throttled to maintain less than the prescribed rate on the permit for 2A and the path was set to automatically trip if the concentration in the path exceeded 20 uCi/cc (28.5-'o of the Site Limit) as measured by the Gas.Release Effluent Monitor and it's set points as per the permit controlling the 2A 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 3.6 times higher than the permitted GDT 2A, but only 0.007 percent of the Administrative Limit allowed for this pathway.

Both tanks together only achieved 0.013 percent of the Administrative Limit (28.5% of the site limit).

29

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Attachment A (Continued) d) Mechanical Maintenance readjusted the remote handwheel assembly for Valve V-6594 as per Plant Work Order N92048806-01. This event is being investigated for further corrective action to prevent a recurrence.

e) Given the normal (and maximum historical) activity levels of these tanks and the Procedural and Administrative Conservative Setpoints involved with this release path, no Administrative Release Activity Limit or Site Limit was exceeded.

age o ST. LUCIE UNIT 2 OPERATING PROCEDURE NO. 2-0530021, REVISION 15 CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE GASEOUS RELEASE PERMIT I. GASEOUS PERMIT NUMBER SAMPLE DATE AND TIME GDT NAME OR PURGE 8- 'M- JSI /I $ -/&-gQ /cu5'6 NQ 6N LIMITS ACTUAL CONCENTRATION REMARKS GDT <<OI 20.0 uCI/cc ~dL alK uCVcc Containmqpt Purge 4.76 X 10 uCI/cc /oJ~ uCI/cc Containment Mini-purge 0.1 uCI/cc uCVcc axtmum isc arge ow a e GDT ¹/hr. GDT Decreases or 8i 6C.F.M. Flow Settln Waste Gas Monitor Set pints Alert: /O uCI/cc Hi h: d?0 uCI/cc Waste Gas Monitor SOURCE CHECK Performed by III. REVIEW - APPROVAL PRIOR TO RELEASE SIGNATURE Main purge, or Mini-purge 2 5E-3 uCI/cc Chemi Su ervisor Mini-purge c 5E-3 uCI/cc and meets the re uirements of STS 3.6.1.7.b Permit Pre arer GDT >OR~25% of Section Il Chemist Su ervisor GDT <25% of Section Il Permit Pre arer Assistant Nuclear Plant Su rvisor IV. Start Date 0- l(p- 8. Time/>'3 Sto Date '7- lt -'PQ- Time / 0 Start GDT Pressure j /S Sto GDT Pressure 9'9 V. REVIEW - APPROVAL POST-AFTER RELEASE SIGNATURE Assistant Nuclear Plant Su rvisor Chemist Su ervisor Notation of rmit s mbols: 2OPS GDT uCi/cc

¹/hr.

- Gas Decay'"Fa

- micro-Caries per cuSih centimeter'-'-"

- pounds per our;.~

' DATE >8@9/t DOCT PROCEDURE DOCN 2-0530021 C.F.M. - cubic feht er TrlInute" '

>or= - Greater han'ar'e'qual'to' ro<<vs SYS COMP COMPLETED C - less than ITM GRP

- percent um F Pl A~i'l ED - b."- I. <'l -"l'J. ~t4%/

4 'il r..-.Tr ". ~ ".I-.Ti l' I li<<O-0% I"'ei'AL g QQ P'..:"

31

C FLORIDA POWER 6 LIGHT CO. ST LUCIE PLANT CHEMISTRY DEPARTMENT GASEOUS RELEASE PERMIT 2 1316 FOR GAS DECAY TANK FINAL ACTIVITY REPORT FOR POSTRELEASE CALCULATIONS REACTOR UNITS: 2 FILE GDT2.DAT SAMPLE 5 44 SAMPLE I ~ D. 2-92-131A 2B GDT SAMPLE TYPE GAS SAMPLE TIME 9-16-1992 9 16:50 SAMPLE VOLUME 3.0200E+01 cc.s ACQUIRE TIME 9-16-1992 8 16:56 LIVE TIME 1.0000E+03 sec.

EFF.FILE NAME: GT22-CNF ACT MULT FACTOR 1.0000E+00 (8 )

RELEASE START: 9-16-1992 8 12:31 RELEASE VOLUME 3.0513E+06 cc.s RELEASE END 9-16-1992 8 16: 6 RELEASE MINUTES 2.1500E+02 min START PRESS 110 psig STOP PRESS 99 psig

• • POST GRP Program Q.C. O.K. **

(8)

NUCLIDE SAMPLE milli-Ci(0) KEYLINE PEAK PEAK SYMBOL uCi/cc RELEASED KEV EFF ABUND AR-41 KR-85M 3.008E-04 2.367E-04 9.178E-01 7.222E-01 1293 '4 151.18 6.94E-02 6.56E-01

+o 99.16 75.50 KR-87 1.567E-04 4.781E-01 402.58 2.46E-01 49.50 KR-88 3.217E-04 9.816E-01 196.32 5.27E-01 26.30 XE-133 2."436E-02 7.433E+01 81.00 5.86E-01 37.60 XE-133M 5.682E-04 1.734E+00 233.18 4.41E-01 10.30 XE-135 6.307E-03 1.924E+01 249.79 4-10E-01 89.90 TOTALS : 3.225E-02 9.841E+01 TOPIC RESULTS UNITS PERCENT REACTOR LIMIT LIMIT TAL BODY DOSE RATE: 1.03367E-02 mRem/Yr 0.00725 142.5 mRem/Yr KIN DOSE RATE 2.11994E-02 mRem/Yr 0.00248 855.0 mRem/Yr

'AMMA AIR DOSE 4.61803E-06 mRad 0.00009 5.0 mRad/Qtr BETA AIR DOSE 7.11033E-06 mRad 0.00007 10.0 mRad/Qtr EQUIVALENT XE-133 1.86759E+00 Curies 0.00066 285000. Curies CHI OVER Q 1.60000E-06 sec/M3 N.A. per O.D.C.M.

EST RELEASE VOLUME 3.05130E+06 CC as N.A. N.A.

RELEASE RATE 5.01187E-01 SCFM N.A. N.A.

RELEASE RATE 3.06977E+00 8/Hour N.A. N.A.

Denotes Post reported uCi/cc and milli-Ci released were calculated by back decaying the results of the tank sample at 9-16-92 1650 to the activities that would have existed at 9-16-92 1231 (the estimated start time of the release).

After reviewi'ng the post release results of GDT 2A(Permit 2-92-130) and GDT 2B(Permit 2-92-131A), no release limits were exceeded by either tank release individually, or during their concurrent release interval.

9 -(7-9~

R.E. Cox E fluent Supervisor

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FLORIDA POWER & LIGHT CO. ST. LUCIE PLANT CHEMISTRY DEPARTMENT GASEOUS RELEASE PERMIT 2 130 FOR GAS DECAY TANK FINAL ACTIVITY REPORT FOR POSTRELEASE CALCULATIONS REACTOR UNITS: 2 FILE GDT2.DAT SAMPLE g 43 SAMPLE I.D. 2A GDT SAMPLE TYPE 'AS SAMPLE TIME 9-16-1992 8 9:20 SAMPLE VOLUME 3.0000E+01 cc.s ACQUIRE TIME 9-16-1992 8 9:32 LIVE TIME 1.0000E+03 sec.

EFF.FILE NAME: GT22.CNF ACT MULT FACTOR 1.0000E+00 RELEASE 9-16-1992 9 11:55 RELEASE VOLUME 2.6907E+07 cc.s END START'ELEASE 9-16-1992'8 16: 6 RELEASE MINUTES 2.5100E+02 min START PRESS 124 psig STOP PRESS 27 psig

• • POST GRP Program Q.C. O.K. **

NUCLIDE SAMPLE milli-Ci KEYLINE NET PEAK PEAK PEAK SYMBOL uCi/cc RELEASED KEV. AREA EFF 0 ABUND XE-133 8.826E-03 2.375E+02 81.00 21547. 5.86E-01 37.60 XE-133M 1.461E-04 3.932E+00 233.18 73. 4.41E-01 10.30 XE-135 7.702E-05 2.072E+00 249.79 307. 4.10E-01 89.90 TOTALS  : 9.049E-03 2.435E+02 TOP IC RESULTS UNITS PERCENT REACTOR LIMIT LIMIT TOTAL BODY DOSE RATE: 7.92103E-03 mRem/Yr 0.00556 142.5 mRem/Yr SKIN DOSE RATE 1.89574E-02 mRem/Yr 0.00222 855.0 mRem/Yr GAMMA AIR DOSE 4.51889E-06 mRad 0.00009 5.0 mRad/Qtr BETA AIR DOSE 1.32009E-05 mRad 0.00013 10.0 mRad/Qtr EQUIVALENT XE-133 3.54083E-01 Curies 0.00012 285000. Curies CHI OVER Q 1.60000E-06 sec/M3 N.A. per O.D.C.M.

EST. RELEASE VOLUME 2.69069E+07 cc.s N.A. N.A.

RELEASE RATE 3.78567E+00 SCFM N.A. N.A.

RELEASE RATE 2.31873E+01 g/Hour N.A. N.A.

~ I oW)

Page 9 of 9 ST. LUCIE UNIT 2 CHEMISTRY PROCEDURE NO. 2-C-62B, REVISION 7 GENERAL ATOMIC SINGLE STAGE GASEOUS S.S.G. AND STEAM LINE PROCESS MONITOR OPERATION SOURCE CHECK CERTlFlCATE Procedure Title and Number Frequency Monthly Maximum Time Between Source Checks 38 days Toleranc'e NA

'quipment Name Equipment I.D. number (channel)

Date of Last Source Check Date of This Source Check SPECIAL INSTRUCTIONS: Channel must.res ond to radiation source.

Source Check A. Channel responded to radiation source. ~es o s W ops P.",'li"V>>STRY DEPT.

OAT E P~~A~

OOCTt uf SYS COMP~>

lTitll Performed b Approved by Date~9~+ ~ 2.

35

FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE METEROROLOGICAL DATA SEP 16, 1992 HOUR WIND DRCTN. 6 SPEED TEMPERATURE DELTA-T SIGMA THETA RAIN ENDING 60-METER 10-METER SYS TEMP SYS CAT CAT E.S.T. DEG MPH DEG MPH DEG. F DEG. C/100M DEG IN.

1 MISG MISG 108 6.7 81.2 -0.2 E MISG 0.00 2 MISG MISG 132 5.0 81.0 -0.2 E MISG 0.00 3 MISG MISG 120 3.0 80.0 -0.1 E MISG 0.00 4 MISG MISG . 96 2.8 80.0 -0.1 E MISG 0.00 5 MISG MISG 84 3.1 80.0 -0.2 E MISG 0.00 6 MISG MISG 72 3.1 80.0 -0.1 E MISG 0.00 7 MISG MISG 54 2.8 80.2 -0.2 E MISG 0.00 8 MISG MISG 60 4.5 81.2 -0.9 D MISG 0.00 9 MISG MISG 54 4.8 82.0 -1.4 D MISG 0.00 10 MISG MISG 30 5.5, 82.5 -1.6 C MISG 0.00 11 MISG MISG 54 6.1 83.7 -1.8 B MISG 0.00 12 MISG MISG 54 6.6 84.0 -1.9 B MISG 0.00 13 MISG MISG 48 6.7 84.1 -2.0 A MISG 0.00 14 MISG MISG 54 6.0 83.2 -1.3 D MISG 0.00 15 MISG MISG 58 8.0 84.7 -2.2 A MISG 0.00 16 MISG MISG 58 8.5 84.7 -2.2 A MISG 0.00 17 MISG MISG 60 8 ' 84.0 -1.9 B MISG 0.00 Note Average values for hours 1 through 17 above, were hand calculated from Reactor Control Room strip chart recorder data.

18 54 9.2 62 5.8 A 79.9 A -0.9 D 20.4 B MISG 19 49 12.8 55 7.5 A 80.6 A -0.9 D 17.3 C 0.00 20 47 12.0 53 6.7 A 80.5 A -0.7 D 18.0 B MISG 21 52 13.1 60 7.5 A 80.3 A -0.6 D 17.8 B 0.00 22 64 14.1 73 8 ' A 80.5 A -0.6 D 14.9 C MISG 23 84 14.2 91 9.1 A 80.6 A -0.6 D 18.2 B MISG 24 118 18.3 130 10.5 A 77.5 A -0.4 E 17.6 B 0.00 Note Values for hours 18 through 24 are from digital processor.

SUMMARY

OF DAY MAXIMUM: 18.3 NP NP TOTAL: 0.00 MEAN  : 13.4 NP NP MINIMUM: 9.2 NP NP Note Summary of Day information for hours 18 through 24 only.

NP Denotes summary not provided Explanation The Corportate Meteorologist's data logger lost data for hours 1 through 17. The data for hours 1 through 17 was obtained from the OPERABLE Control Room Chart Recorder.

ATTACHMENT B UNPLANNED GASEOUS EFFLUENT RELEASE of NOVEMBER 4, 1992

1) Description and analysis of event

2) Hourly average site meteorological for November 4, 1992 37

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Attachment B

1) Description and analysis of event On November 4, 1992 the nitrogen system was isolated at the bulk gas house to repair a safety relief valve that was lifting prematurely. During the time that nitrogen was isolated, the nitrogen system pressure in the downstream piping decreased.

Sometime later the Steam jet Air Ejector (SJAE) Rad Monitor alarmed and Control Room personnel alerted Chemistry personnel.

Chemistry began sampling the Steam Generators for radioactivity and obtained negative results. A grab sample on the SJAE exhaust gases indicated radioactivity was present. The SJAE exhaust was confirmed to be aligned to the Plant Vent Exhaust, it's normal exhaust path preceding this event. The Plant Vent Pathway is a Technical Specification Continuous Release Monitored Pathway.

An investigation by Chemistry and Operations personnel indicated that Gas Decay Tank(GDT) 1B was backpressuring(with flow) the nitrogen system through the normally closed valve V-6596. This valve is the nitrogen supply to GDT 1B. The nitrogen system to,the "

GDT's was isolated by closing root nitrogen supply valve V-6788 and a Plant Work Order (PWO I 92047980) was issued to repair V-6596.

The Chemistry Radioassay of the Air Ejector Exhaust indicated an activity level of 1.1E-07 Curies per second which is 0.00003 percent of the Site Limit of 0.35 Curies per second as per the ODCM. No noticeable increase, or alarm condition, was detected by the Plant Vent Monitor due to the low concentrations in the Plant Vent during this event. No Technical Specification Limits were exceeded.

Plant Management directed a root cause analysis be performed with corrective action to prevent a recurrence. The finding and recommendation was to install a double check valve on the nitrogen supply line to the Reactor Auxiliary Building(RAB) I 1, as per the original design of the Unit I 2 RAB nitrogen supply, to prevent back flow from the. potentially radioactive RAB 0 1 side to the Secondary Plant side of the nitrogen system. Unit I 1 was not designed with a double check valve to the RAB side. This design change was submitted as per the Plant Change Modification(PCM) process and is currently being reviewed by Engineering. The final design change PCM will be submitted to the FRG for approval.

In addition, plant management has emphasized the need for precautions to be taken prior to any planned maintenance on the Nitrogen System until the PCM is completed.

38

Page 11 of 11 t )

~0 ST. LUCIE UN!T 1 OPERATING PROCEDURE NO. 1-0530021, REVISION 34 CQNTRO~D GASEOUS BATCH RELEASE TO ATMQSPHERE GASEOUS RELEASE PERMIT ERMIT NUtAEER SAMPLE DATE AND TIME GDT NAME QR, URGE fh + +Xl+RLcs t ACTUAL CON CENTRATICN REMARKS l 0'7* NiMqW ea et-htr F>e PI<<f Peat ~i <<<< ~-~CI/ PI.,.,l u> law~k Lease, .

20.0 uCVcc ~~pleK ~4le iw prorjreSS.

Containment Purge uCI/cc eltttatilie4 ~far n re,s'lh.uaL gas Llew.

4.76 X 10 uCI/cc Maxinum Discharge Row Rate for Gas Decay Tanks GDT Ahr. /t/A GDT Decrease or h"< C.F.M. Flo.tv Setting Waste Gas Monitor Setpornts Alert: ~~ CP'A High: ~g CPM Wite Gas Monitor Source Check performed by (Initials):

Revtew - Approval (Prior to Release) Signature Containment Purge Chemistry Supervisor GDT > or ~ 25.o of Section II Cherristry Supervisor NA GDT ~'/o of Sectfon II

",pgj't NudeBf Plpflt SUPBIYISDr IV. Stan Date I gg.gW Time oooo Slop Date II-~- 9~ Time o'f2 0 Stan GDT Pressure N6 Slop GDT Prmsure V. Revtew - Approval (Post - After Release) Signature Assistant Nuclear Plant Supervisor E N~ Q+ 0" VLSA" Chemtstry Supervisor NOTATION OF PERMIT SYMBCLS SrOPS GDT Gas Decay Tank DATE I ~~

uCi.'cc micro-Curie ic centimeter DQCT

¹/hr. pounds pe our P - '- CHEhli=TRY DE SYS I CQMP t=O~r LIED:

C.F.M. cubic feet er miHuQ .';:FOB,-:"-,q! f4:.j Q~=,'I g ITM

. <:9 oo ". -... ts HO. " Y..".ot.LEO  ?:--.M VpE CPM counts per ~ - -: .,'~Fo<" .. y, 4tTH ~ ~ RC?t.sD '~ '.tENT.

>or= greater thalII or gqQ:,~'GM'2; ~:"'0 LIC,"H: "0.

T. LUC!:- PLANT percent aAT=- vs im << tel <~ rNITiAL putz vczF:w ~1+ 7 <>

FLORIDA POWER 6 LIGHT CO. ST. LUCIE PLANT CHEMISTRY DEPARTMENT GASEOUS RELEASE PERMIT 1 58A FOR AIR EJECTOR EXHAUST FINAL ACTIVITY REPORT FOR POSTRELEASE CALCULATIONS REACTOR UNITS 1 FILE GDT2.DAT SAMPLE S N.A.

SAMPLE I 1-92-58A Air Eject. SAMPLE TYPE GAS AD.

SAMPLE TIME ll- 4-1992 11- 4-1992 9 12:30 SAMPLE VOLUME 12:46 LIVE TIME 4.60E+03 cc.s

5.00E+02 sec.

ACQUIRE TIME 8 EFF.FILE NAME: GT46.CNF ACT MULT FACTOR 1.00E+02 RELEASE START: 11-04-1992 8 10:00 RELEASE VOLUME 1.18E+07 cc.s RELEASE END 11-05-1992 8 04:20 RELEASE MINUTES 110 + min START PRESS N.A. STOP PRESS N.A. psig (1) (2)

NUCLIDE SAMPLE milli-Ci KEYLINE NET PEAK PEAK PEAK SYMBOL uCi/cc RELEASED KEV AREA EFF +o, ABUND XE-131M .6..665E-07 1.245E-03 163.93 15. 1.34E+00 1.96.

XE-133 6.114E-05 1.142E-01 81.00 22385. 1.15E+00 37.60 XE-133M 5.420E-07 1.013E-03 233.18 48. 1.01E+00 l,0. 30 XE-135 5.316E-08 9.935E-05 249.79 38. 9.47E-01 89.90 Totals: 6.240E-05 1.166E-01 Notes: (1) From Grab Sample obtained from the Air Ejector Exhaust during the event. This sample was used to determine the percent mix of isotopes present.

(2) The milli-Curies were calculated by using:

a) Air Ejector exhaust flow rate of 3.8 cfm.

b) Using 10 minute average Air Ejector Monitor readings above background during the event.

c) Applying the 4 mix of isotopes present to the gross milli-Curies.

Review of Technical Specification Release Rate Limits:

The Air Effector Exhaust was aligned to the Plant Vent Exhaust Path, a Technical Specification Monitored Pathway, with Control Room Alarm for Noble Gas Levels Set to Alarm well below the Site Limit. No noticable increase was noted in the Plant Vent and at the Air Ejector Exhaust Concentration Levels, none would be expected since the estimated rate was 1.1E-07 Ci/sec and.the Site Limit, as per the ODCM, is 0.35 Ci/sec.

No Technical Specification Release Rate Limits were exceeded during this event.

No Source Check is applicable for this event.

-Om.+eS ~inures of Ae+e~&b[~ release r, i&ivtml hh, e 4a +e resih~aL 8 gas +rappe~

R. . Cox Effluent Supervisor cd.W'wg g~ event M1480w ~

40

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE METEROROLOGICAL DATA NOV 4, 1992 HOUR WIND DRCTN. & SPEED TEMPERATURE DELTA-T SIGMA THETA RAIN ENDING 60-METER 10-METER SYS TEMP SYS CAT CAT E.S.T. DEG MPH DEG MPH DEG. F DEG. C/100M DEG IN.

1 125 17.0 129 8.9 A 79.3 A -0.2 E 14.7 C 0.00 2 121 17.3 124 F 1 A 79.2 A -0.2 E 14.2 C 0.00 3 114 18.5 116 9 ' A 79.3 A -0.4 E 14.6 C 0.00 4 129 16.5 134 8.8 A 78.9 A -F 1 E 14.7 C 0.00 5 125 15.8 129 8.4 A 79.0 A -0.1 E 14 ~ 5 C 0.00 6 126 18.4 128 9.9 A 79.1 A -0.3 E 13.7 C 0.00 7 131 18.3 137 10.5 A 79.4 A -0.5 E 15.5 C 0.00 8 139 17.6 146 10.6 A 80.0 A -0.5 D 13.1 C 0.00 9 141 16. 6 148 11.2 A 81.1 A -1 ' D 13.8 C 0.00 10 143 17. 5 153 12.6 A 81.6 A -1 ~ 2 D 12.8 C 0.00 11 145 21. 0 153 15.6 A 82.5 A -1.6 C 13.7 C 0.00 12 144 21.3 150 15.0 A 81.6 A -1.3 D 13.8 C 0.00 144 21. 2 154 15.7 A 81.6 A -1 ' D 12.5 C 0.00

-1.3 e '6 17 143 145 145 145 21.0 21.0 20.0 20.0 150 14. 6 155 14. 8 152 13.6 151 13.6 A

A A

A 81.4 81.3 81.0 81.1 A

A A

A

-1.2

-1.0

-0.9 D

D D

D 13.6 12.0 12.6 12.2 C

D C

D 0.00 0.00 0.00 0.00 18 150 17.0 155 11.3 A 80.2 A -0.5 D 11.5 D 0.00 19 153 15.0 157 9.5 A 79.7 A -0.3 E 10.8 D 0.00 20 157 14.7 161 9.8 A 79.3 A -0.4 E 10.3 D 0.00 21 164 13.7 170 10.2 A 79.3 A -0.5 D 10.1 D 0.00 22 175 11. 8 179 10.2 A 78.8 A -0.5 D 9.9 D 0.00 23 176 9.8 183 8.6 A 77.8 A -0.4 E 11.2 D 0.00 24 178 9.6 190 8.5 A 77.1 A -0.3 E 8.2 D 0.00

SUMMARY

OF DAY MAXIMUM: 2 1. 3 15.7 82.5 TOTAL: 0.00 MEAN  : 17.1 11.3 80.0 MINIMUM: 9.6 8.4 77.1 41

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