ML17223A826

Revised Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1988.

ML17223A826
Person / Time
Site:	Saint Lucie
Issue date:	06/30/1988
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17223A825	List: ML17223A824 ML17223A826
References
NUDOCS 9006260054
Download: ML17223A826 (111)

Text

FLORIDA POHER & LIGHT COMPANY ST. LUCIE PLANT UNITS NO. 1 & 2 LICENSE NO. S DPR-67 & NPF-16 COMBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JANUARY 1, 1988 THROUGH JUNE 30, 1988 900+Pg0 m.=

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TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION,........

SITE VISITOR DOSE FROM EFFLUENTS..............

OFFSITE DOSE CALCULATION MANUAL REVISIONS ~.... ~.................

SOLID WASTE AND IRRADIATIED FUEL SHIPMENTS................. ~ ~ ~ ~ ~ 7 PROCESS CONTROL PROGRAM REVISIONS...............................

LIQUID EFFLUENT:

SUMMATION OF ALL RELEASES & NUCLIDE SUMMATION BY QUARTER U NIT 0 1 o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

U NIT,0 2o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 GASEOUS EFFLUENT:

SUMMATION OF ALL RELEASES & NUCLIDE SUMMATION BY QUARTER U NIT 0 1 e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 12 U NIT 0 2 r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 14 SOLID WASTE SHIPMENT SUMMATION 16 ATTACHMENT A ODCM revisions during the reporting period r

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EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION

1. Regulatory Limits

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

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

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

1. 2 For Gaseous Haste Effluents:

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

For Noble Gases: <= 500 mrems/yr to the total body and 3000 mrems/yr to the skin, and For Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days:

1500 mrems/yr to any organ.

.*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.

4C. The dose to a MEMBER OF THE PUBLIC from Iodine-181, 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.

I The calculated doses contained in a serai-annual report shall not

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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's per 10 CFR 20 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 named nuclides are shown as zero Curies released, this should be interpreted as "no acitvity 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. X Max. X Avg. X Max. %

Release Point Mixing 2 5 NA NA Sampling 1 5 2 5 Sample Preparation 1 5 1 5 Sample Analysis 3 10 3 10 Release Volume 2 5 4 15 Total I '0 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)

TABLE 3. 1 RADIOACTIVE LIQUID EFFI UENT SAMPLING AND ANALYSIS Liquid Sampling Type of Method of Source Frequency Analysis Analysis Each Batch Principal Gamma Emitters p. h. a.

Monitor Monthly Tritium L. S.

Tank Composite Gross Alpha G. F. P.

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

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 '.S ~

Alpha Composite Monthly G. F. P.

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

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

0>> 4 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

i FLORIDA POWER & LIGHT COMPANY ST. LUC IE UNIT 5 1 SEMIANNUAL REPORT JANUARY 1~ 1988 THROUGH JUNE SOr 1988 EFFLUENT & WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)

5. Batch Releases A. Liquid

l. Number of batch releases: 21.0

2. Total time period for batch releases: 11,650.0 minutes

3. Maximum time period for a batch release: 1,047 minutes Average time period for a batch release: 555 minutes

5. Minimum time period for a batch release: 515 minutes

6. Average dilution stream flo~ during the period: 1<027>087 gpm All liquid releases are summarized in tables B. Gaseous

1. Number of batch releases: 2

2. Total time period for batch releases: 550 minutes 3e Maximum time period for a batch release: 4~0 minutes 4 Average time period for a batch release: 275 minutes

5. Minimum time period for a batch release: 120 minutes Al I gaseous waste releases are summarized in tables

6. Unplanned Releases A. Li qui d

1. Number of releases: 0

2. Total activity released: 0 Curies B. Gaseous Number of releases: 0

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

A description of the event and equipment. involved.

2. Cause(s) for the unplanned release.

Actions taken to prevent a recurrence.

4 ~ Consequences of the unplanned release.

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FLORIDA POWER dc LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 38, 1988 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)

5. BATCH RELEASES AND UNPLANNED RELEASES LIQUIDS FOR - ST. LUCIE PLANT UNIT NO. 2 A. NUMBER OF BATCH RELEASES- 21.8 B. TOTAL TIME PERIOD OF BATCH RELEASES- 11658. MINUTES C. MAXIMUM TIME PERIOD FOR h BATCH RELEASE: 1847. MINUTES D. AVERAGE TIME PERIOD FOR A BATCH RELEASE- 555. MINUTES E. MINIMUM TIME PERIOD FOR h BATCH RELEASE: 315. MINUTES F. AVERAGE STKDlM FLOW DURING REPORTING PERIOD INTO h FLOWING STK9lH: 1827887. G. P.M.

S. GASEOUS FOR - ST. LUCIE PLANT UNIT NO. 2 A. NUMBER OF BATCH RELEASES- 22. 8 B. TOTAL TIME PERIOD OF BATCH RELEASES- S 679. MINUTES C. MhXIMUM TIME PERXOD FOR A BATCH RELEASE- 788. MINUTES D. AVERAGE TIME PERIOD FOR h BATCH RELIMHE- 384. MINUTES E. MINIMUM TIMR PERXOD FOR h BATCH REIXhSR- 28. MXNUTES UNPLANNED RELEASES LIQUIDS FOR- ST. LUCIE PLANT UNIT NO. 2 A. NUMBER OF RELEASES- 8.

B. TOTAL ACTXVITY RELEASED- 8. CURIES GASEOUS FOR - ST. LUCIE PLANT UNXT NO. 2 A. NUMEN OF RELEASES- 8 B. TOTAL ACTIVITY RELEASED- 8. CURIES SEE ATTACHMENTS (XF APPLICABLE) FOR-A. A DESCRIPTION OF'THE EVENT AND EQUIPMENT INVOLVED.

B. CAUSE(S) FOR THE UNPLANNED RELEASE.

C. ACTIONS TAKEN TO PREVENT h RECURRENCE.

D. CONSEQUENCES OF THE UNPIdQiNED RELEASE.

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANTS UNITS 1 &, 2 SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 30, 1988 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 is reported on the year endin~ Semi-Annual Report.

8. Offsite Dose Calculation Manual Revisions (ODCM):

Five typographical errror correction changes were made to the ODCM.

Four of theses errors were noted by Mr. Edward Bra'ndegan, of the U.S. NRC during his audit of the document. None of these changes affect medthodology. The changes are documented as Attachment A to this report.

9. Solid Waste and Irradiated Fuel Shipments.'o irradiated fuel shipments were made from the site. Common Solid waste from St. Lucie Units 1 and 2 were shipped jointly.

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

10. Process Control Program (PCP) Revisions:

The PCP was not revised during the reporting interval.

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FLORIDA POWER Sr, LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 3S, 1988 TABLE 3. 3-1 LIQUXD EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER 41 QUhEDKR 42 A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CI 4.28E-S2 1.89E-S2

2. AVERAGE DILUTED CONCENTRATXOH DURING PERIOD UCI/ML 8.45E-ii 3. 72E-11 B. TRITIUM

1. TOTAL RELEASE CI 3.88E Si 9.37E Si

2. AVERAGE DILUTED CONCENTRATION DURING PERXOD UCI/ML 7. 28E-SB 1.85E-S7 C. DXSSOLVED AND ENTRAINED GASES

1. TOTAL REUDlSB CI 2.S2E-S2 2.52E-S1

2. AVB248iE DILUTED CONCENTRAT IOH DURING PERIOD UCI/ML 3.99'-il 4. 98E-1S D. KKSS ALPHA RADIOACTIVITY TOTAL RELEASE CI S. SSE-Si S. SSE-Sl .

K. VOLUME OF WASTE RELEhSED (PRIOR TO DILUTXON)- LITERS 2.92E S7 2.59E S7 F. VOLUME OF DXLUTIOH WhTER USED DURING REPORTING PERIOD LITERS 5.S7E 11 S.SSE 11

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FLORIDA POWER 8c LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 38, 1988 TABLE 3.4-1 LIQUID EFFLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. Oa QTR. 02 QTR.01 QTR.02 I-131 CI 2.54E-84 e.eez-ea 1.89E-83 9. 11E-84 I-133 CI H.HHE-Sl 8. SSE-Sl 3.83E-84 1.41E-84 NA-24 CI S.SSE-81 8. HHE-81 1.85E-85 H.SHE-ea CR-51 CI S.SSE-81 8. SHE-81 4.83E-84 S.SSE-81 MN-54 CI S.SSE-81 8. SSE-81 3.68E-84 3.76E-85 FE-55 CI S.SSE-81 8. SSE-81 1 ~ 36E-82 5.6HE-83 CO-58 CI S.SSE-81 8. SSE-81 5.38E-83 4.38E-83 FE-59 CI H.SHE-81 8. SSE-Sl 3.28E-85 H.HSE-81 CO-68 CI H.SHE-81 8. SSE-81 3.77E-83 2.42E-83 hG-aae CI S.HSE-81 S. SSE-81 3.81E-84 8.13E-85 SN-113 CI H.HHE-81 8. HHE-81 2.64E-85 H.HSE-81 SB-122 CI H.SSE-81 8. HSE-Sl 1.86E-85 S.SHE-81 SB-124 CI S.SSE-81 8. SSE-81 2.89E-83 1.34E-84 SR-98 CI 7.92E-84 8. SHE-81 1.25E-86 2.55E-85 Y-98 CI 7.92E-84 8. SSE-81 1.25E-86 2.55E-H5 ZR-95 CI 8. SHE-81 8. SHE-Hl 3.69E-84 H.SHE-81 NB-95 CI 8. SHE-81 H.eeE-ea 7.51E-84 9.29E-H5 NB-97 CI S.SSE-ea 8. SSE-81 4.66E-84 8.72E-85 TC-99M CI 8. HSE-81 8. HHE-81 8.88E-81 1 ~ 37E-85 SB-125 CI 8. SHE-81 8. SSE-81 7.93E-83 3.87E-83 CS-134 CI 8. HHE-81 8. SHE-81 1.13E-83 6.68E-84 CS-137 CI 6. 79E-85 8. SSE-81 1.88E-83 a.a8E-83 LA-148 CI S.HHE-ea S.eeE-ea 1.97E-84 4.98E-H5 TOTAL FOR PERIOD CI 1.91E-83 H.SHE-el 4.89E-82 1.89E-82 AR-41 CI H. SSE-Hl H. SSE-81 2.75E-85 S.eez-ea XE-13aM CI 8. SHEMa 8. SSE-81 S.eeE-ea 1.98E-83 XE-133 CI S. SSE-81 H. SSE-81 1.73E-82 2.46E-ei XE-133M CI 8. SHE-81 8. SHE-81 2.55E-84 2.23E-83 XE-135 CI S.eeE-ea 8. SSE-81 2.62E-83 1.78K-83 TOTAL FOR PERIOD CI S.HSE-el S.SHE-81 2.82E-82 2~52E-ea

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FLORIDA POWER 5 LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY 1, 19S8 THROUGH JUNE '8, 1988 TABLE 3. 3-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER 41 QUARTER 02 A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CI 4. 89E-82 1.89E-82

2. AVERAGE DXLUTED CONCENTRATION DURING PERIOD UCI/ML 8.88E-ii 3.72E-11 B. TRITIUM

1. TOTAL RELEASE CI 3.88E 81 9.37E 81

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 7. 26E-88 1.85E-87 C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CX 2.82E-82 2. 52E-S1

2. AVERAGE DILUTED CONCENTfQTION DURING PKRIOD OCI/ML 3.99E-11 4.98E-18 D. GROSS ALPHA RADIOACTIVXTY

1. TOTAL RELEASE CX S.SHE-81 8. SHE-81 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS -

1.84E 88 1.57E 88 F. VOLUME OF DILUTION MATER USED DURING REPORTXNG PERIOD LITERS 5.87E 11 5.86E il

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FLORIDA POWER 8c LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT 1, 1988 THROUGH JUNE 38, 1988 TABLE 3.4-2 LIQUID EFFLUENTS NUCLIDES CONTINUOUS NODE BATCH MODE RELEASED UNIT QTR.¹l QTR.¹2 QTR.¹1 QTR.¹2 I-131 CI 8. HSE-81 e.eeE-ea 1.89E-H3 9.11E-H4 I-133 CI 8. SSE-81 H.HHE-81 3.83E-84 1.41E-H4 NA-24 CI 8. HHE-81 S.HHE-81 1.85E-85 H.HSE-81 CR-51 CI S. SHE-Hl H.SSE-81 4.83E-84 H.HHE-81 NN-54 CI S. HHE-81 H.SHE-81 3.68E-84 3.76E-85 FE-55 CI 8. SSE-81 H.SHE-81 1.36E-82 5.68E-83 CO-58 CI 8. HHE-81 H.HHE-81 5.38E-83 4.38E-83 FE-59 CI 8. HHE-81 S.HHE-81 3.28E-85 H.SSE-81 CO-68 CI 8. HHE"81 H.HHE-81 3.77E-83 2.42E-83 AG-118 CI 8. HHE-Sa S.SHE-81 3.81E-84 8.13E-85 SN-113 CI H. HHE-81 H.SHE-81 2.64E-85 H.HHE-81 SB-122 CI S. SHE-81 S.SHE-81 a.86E-es S.HHE-81 SB-124 CI H.eeE-ea S.SSE-81 2.89E-83 1.34E-84 SR-98 CI H. SSE-81 S.SHE-ea 1.25E-86 2.55E-85 Y-98 CI 8. HSE-81 H.HHE-81 1.2SE-86 2.55E-85 ZR-95 CI 8. HHE-81 H.HSE-81 3.69E-84 S.SSE-81 NB-95 CI 8. HHE-81 H.HHE-el 7.51E-84 9.29E-85 NB-97 CI S. HHE-81 H.HHE-81 4.66E-84 8.72E-85 TC-99M CI 8. HHE-81 H.HHE-81 H.SHE-81 1.37E-H5 SB-125 'CI 8. SHE-81 S.SSE-81 7.93E-83 3.87E-83 CS-134 CI 8; eeE-ea S.HHE-el 1.13E-83 6.68E-H4 CS-137 CI S. SHE-81 H.SSE-Ha 1. SSEM3 1.18E-83 LA-148 CI 8. SSE-81 H.SHE-81 1.97E-84 4.98E-S5 TOTAL FOR PERIOD CI H.HHE-81 H.HHE-81 4.89E-82 1.89E-H2 AR-41 CI 8. SHE-81 8. HSE-81 2.75E-85 8. SSE-81 XE-131M CI S. HHE-81 8. HHE-81 S.HHE-81 1.9HE-83 XE-133 CI 8. SHEMa 8. SSE-81 1.73E-82 2.46E-81 XE-133M CI 8. SHE-81 8. HHEMa 2.55E-84 2.23E-83 XE-135 CI 8. SHE-81 8. SSE-81 2. 62EM3 1.78E-83 TOTAL FOR PERIOD CI S.HSE-81 H.HHE-81 2.82E-82 2.52E-81

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FLORIDh POWER Ir, LIGHT COHPhNY ST. LUCIE PLhNT UNIT NO. 1 SEMIhNNUAL REPORT JANUhRY 1, 1988 THROUGH . JUNE 38, 1988 ThSLE 3.6-1 GASEOUS EFFLUENTS SUMHhTION OF hLL RXLEhSES NUCLIDES RELEhSED UNIT QUhRTER 41 QUhRTER S2 A. FISSION hND hCTXVhTXON GhSES

1. TOThL RELEASE CI 4.11E 82 4.66E 82

2. hVKRAGK RELEhSE RATE FOR PERIOD UCX/SEC 5. 28E 81 5.92E 81 B. IODINES

i. TOThL IODINE-131 CI 1. 91E-83 1.82E-83

2. hVERAGE RELEASE RATE FOR PERIOD UCI/SEC 2. 45E~ 1. 38EM4 C. PhRTXCULATES

1. PhRTXCULATES T-1/2 > 8 DhYS CI 8. 88EMl 8. 88E-81

2. hVERAGE RELEASE RATE FOR PERIOD UCI/SEC 8.88EM1 8. 88EM1

3. GROSS hLPHh RADIOhCTIVITY CI 2. 62EW7 1. 88EM7 D. TRITIUM

1. TOThL REUQlSR CI 5.82E 81 2.81E 81

2. hVXRAGE RELEASE RATE FOR PERIOD UCI/SEC 6.46E 88 2.56E 88

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PLORIDh P0%6t 8c LIQHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 38, 1988 TABLE 3. 7-1 GASEOUS EFFLOENTS GROUND LEVEL RELEASES NOCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. 01 QTR. 02 QTR. 01 QTR. 42 1.'OBLE GASES KR-85M CI 2.29E HS 1.85E HS 8. SSEW1 8. HSE-81 KR-88 CI 4.14E 88 1.35E 88 S. SSEM1 8. SSEM1 XE-131M CI 8. SHE-81 S.SSE-81 1. 38EW3 8. SSE"81 XE-133 CI 3.2HE 82 3.8SE 82 2. 59EM1 3. 82EM3 XE-133M CI 4.81E-81 3.14E 88 S. SSEW1 8. SHE-81 XE-135 CI 8.41E Sl 7.95E Sl 8. SSEMl 8. HSEW1 TOTAL FOR PERIOD CI 4. 1HE 82 4.88E 82 2.8SEM1 3.82EM3

2. IODINE I-131 CI 1. 91EM3 1. 82EM3 I-133 CI 1. 87EM2 8. 15EM3 TOTAL FOB PERIOD CI 1. 28EM2 9. 17EM3

3. PARTICULATE TOTAL FOR PERIOD CI 8. SSEM1 8. SSEW1

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14 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMI ANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 38, 1988 TABLE 3.6-2 GASEOUS EFFLUENTS SUMMhTION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER Si QUARTER 02

h. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE CI 1.54E 83 2.68E 83 2: AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 1.97E 82 3.31E 82 B. IODINES

1. TOTAL IODINE-131 CI 4.15E-83 9.71E-83

2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 5.34E~ l. 23EW3 0

C. PARTICULATES

1. PARTICULATES T-1/2 > 8 DAYS CI 8. 88E-81 3.84E-85

2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 8.88EM1 3.86E-88

3. GROSS ALPHA RADIOACTIVITY CI 8.78E-88 2.88K-88 D. TRITIUM

1. TOTAL REUSE CI 2.34E 81 2.56E 81

2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 3.81E 88 3.25E 88

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FLORIDA POWER Bc LIGHT COMPANY ee ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 38, 1988 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED ON IT QTR. ¹1 QTR. ¹2 QTR. ¹1 QTR. ¹2 1 NOBLE GASES AR-41 CI 8. 88E-81 8. 88EM1 2.87E-81 2.35E-81 KR"85M CI 9.83E 88 2.88E 81 4. 79EM3 9.97E-82 KR-88 CI 3.5BE 88 1.28E 81 3. 24E-83 B.77E-82 XE-131M CI 8.88E-81 8.88E-81 5. 72EM2 3.93E-81 XE-133 CI 1.3BE 83 2.19E 83 3.97E 88 8.12E 81 XE-133M CI 8.88E-Sl 8. 88EM1 2. 93EM2 1.27E 88 XE-135 CI 1.57E 82 2.91E 82 7.14E-82 2.43E 88 TOTAL FOR PERIOD CI 1.53E 83 2.52E 83 4.34E 88 8.57E 81

2. IODINE I-131 CI 4. 15E-83 9. 71E-83 I-133 CI 5. 89EM3 1. 24E-82 TOTAL FOR PERIOD CI 1. 88E-82 2. 21E-82

3. PART ICOLATE CS"137 CI 8.88E-81 3.84E-85 TOTAL FOR PERIOD CI 8.88E-81 3.84E-85

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16 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 30, 1988 UNITS 1 AND 2, TABLE 3.9 A. Solid Waste Shipped Qff-site for- Burial or Disposal Type a.

of Waste Spent resin, Unit M3 6 Mo.

2.434 E+

'rror Period 8 Process filters Ci 5.803 E+2 2.0E+1

b. Dry compressible M3 1.396 E+2 Waste (Note 5) Ci 1.479 Eoo 2.0E+1

c. Irradiated M3 1 625 Eoo Components Ci 1.014 E+4 2.0E+1

d. Other M3 2.192 E+1

1. Non-Compressible Ci 3.322 E-1 2.0E+1 Metal (DAW)

(Note 6) 2 ~ Estimate of Ma)or Nuclide Composition (By Type of Waste)

Category Nuclide s a~ Cs 137 3 ~ 46E+1 Cs 134 2.60E+1 Co 58 2 55E+1 Co 60 4.87E+o Ni 63 2 41E+o Fe 55 1.48E+o Mn 54 1.33E+o Cr 51 8.59E 1 Nb 95 8.18E 1 I 131 6.42E-1

b. CS 137 2.57E+1 Co,60 2.44E+1 Co 58 1.53E+1 Fe 55 1.07E+1 Cs 134 9.33E+o H 3 5.84E+o Ni 63 2 '3E+o Nb 95 1.74E+o Mn 54 1.42E+o Zr 95 1 22E+o Cr 51 7.90E 1 C 14 4.40E-1 Ce 144 3.80E 1

~~

I 1 e

1

Category Nuclides Co Fe 55 4.16E+1 Mn 54 2.19E+1 Co 58 1.73E+1 Co 60 1.61E+1 Ni 63 3.20E+o d0 Co 60 8.28E+1 Fe 55 1.08E+1 Mn 54 3.28E+o Ni 63 1.27E+o Sb 125 4.79E-1 CG 137 4.00E"1 Co 58 3 46E-1

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 38 Sole Use Truck Barnwell, S.C.

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

FLORIDA POWEi LIGHT NY ST. LUCIE PLAN SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 30, 1988 UNITS 1 AND 2, TABLE 3.9 (CONT'D)

Total Total Principal Type of Category Type of Waste Volume Curies Radionuclides Waste Reg-Guide Container Solidification Class Cubic Ft. (Note 1) (Notes 1 a 2) (Note 3) 1.21 (Note 4) A ent Class A 4932.50 1.48 NA PWR l.b. Non-Specification None Compactible Strong Tight Trash Package (Note 5)

Class A 774.10 3.32E-1 NA PWR l.d. Non-Specification None Non-Compactible Strong Tight Trash Package (Note 6)

Class B 531.90 114.43 Ni63, Sr90, PWR Ion- NRC Certified None Csl37 Exchange LSA Resin > Type A Class C 83.4 91.53 Co60, Ni63, PWR Ion- l.a. NRC Certified None Sr90, Csl37, Exchange LSA Sum of Resin > Type A Nuclides with T9 < 5 years Class C 120.3 366.87 C14, Ni63, PWR Ion- l.a. NRC Certified None Sr90, C137, Exchange Type B Sum of Resin Nuclides with T4 < 5 years Class C 120.3 = 7.43 Ni63 ~ Pu241 g PWR l.a. NRC Certified None Sum of Process Type B Nuclides with Filters T4 < 5 years Class C 57.4 10,144.0 C14, Co60, PWR 1.c. NRC Certified None Ni63, Sum of .Incore Type B Nuclides with Detectors T4 < 5 years

I II

,J ki C

e c~

FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT SEMIANNUAL REPORT JANUARY 1 ~ 1988 THROUGH JUNE 30 g 1988 UNITS 1 AND 2 TABLE 3.9 (CON'T)

SOLID WASTE SUPPLEMENT Note 1: The total curie quantity and radionuclide composition of solid waste shipped from the St. Lucie Plant, Units 1 8 2 are determined using a combination of qualitative and quantitative techniques. In general, the St. Lucie Plant follows the guidelines outlined in the Low Level Waste Licensing Branch Technical Position (BTP) on Radioactive Waste Classification (5/ll/83) for these determinations.

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

The composition of radionuclides in the waste is determined by both on-site analyses for principal gamma emitters and periodic off-site analyses for other radionuclides. The on-site analyses are performed either on a batch basis or on a routine basis using reasonably representative samples as appropriate for the waste type. Off-site analyses are used to establish scaling factors or other estimates for "radionuclides such as 3H, 14C, 99Tc, 129I, TRU, 241Pu, 242Cm, 63Ni, 55Fe, and 90Sr.

Note 2: "Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than .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.

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

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

Note 5: The volume and activity listed for Dry Compressible Waste represent the quantity of material that to date has been sent to the Barnwell, South Carolina burial facility. This material was shipped to a contracted vendor for volume reduction prior to final disposal at the Barnwell, South Carolina burial facility. During the reporting period, five shipments of Dry Compressible Waste (5157 cubic feet, 7.28E 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.

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

I

~'

Page l,of 88

~ J' I

1 A)tachment -I Res 49 changes QG lKCOROS, CK24ISQK OPl&AT32JG ESOCECURE NO. C-200 REVISION 10 T3~:

Offsite Dose Calculation Manual {ODCH)

ReYiewed by Facility Review Group 1982 Approved by C. We Plant Manager 7 19~8 RBvlsiotl~R6visw6d F R G 197 Plant Manager > /~9 RM S OPS I I f rmz I I

I

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Page 12 of 88 ST. ZIZZ OPERRH2G PKjCECURE NO. C-200, REVISION 10 PZAMI'SEHISQK DOS ON 1.3 (cantinued)

TAHLE 1.3 1978 NUCLIDE UNDIZUHK) Mi b~L uCi/ml1 (no units)

<<7 7

<<7

.6

-110 6 0 <<7 ~levd9 6 <<7 4.01 E<<4 ////////////////

1.33 E<<3 (1) 1978 Uhdiluted Release Volund ~ 7 E 9 mls.

(2) Mi~ 7 MPCi (f~mle r 1) 121000 gpa (dil rate)

I

,1 r.

'4

~ '44 l

I Vg f,

E

Page 20 of 88 ST. IIJCIE PUTZ CHEMISTRY OPERATING HKCECURE NO. C-200, BEVISICN 10 0

2.1 (cantinued)

'Ihe St. Zucie site uses the long tezm gzrauxl release model for all gaseous effluents. Only those radionuclides that appear in the gaseous effluent dose factor tables will be considered in any dose calculations. Radioiodines are defined as Iodine-131 and I-133 for application to S.T.S. M3's. Other nuclides of Iodine may be included in dose calculations for ease of perfozmCkg calculations, year following the year that the

~

but their dose contribution does nat have to be included in the SIS tl census was taJcen tggly in ta avoid spli~tng quarters, etc.

2.2 fran nable gaum in tl aizhozne releases to <500 l~

mragyr - tatml body and <3000 lg g ~

Itu~yr - skin. Technical Specificatian 3.3.3.10 zequires t &yt cpezable with alanq/trip setpoints set to ensure that these dose rate limits aze not exceeded. 'Ihe results of the sampling and analysis pzagzam of Technica1 Specificatian Table 4.11-2 aze used to demanstrate canpliance with these limits.

l zates to the tatal body and skin

~l~ g noble gases in aizbozne zeleases. 'Ihe alarm'trip setpoints aze based an the dose rate calculations. Ihe Technical Specificaticn IlX)'s ~ly aizborne releases on the site but all zeleases may be treated as to all if discharged fran a single release point. Only those nable gases a~ring in Table G-2 will be cansidezed. 'Ihe calculation

're amLhads based on Sections 5.1 and 5.2 of NUHE~133, Naveaher 3978. 'Ihe equations are:

Far 1UZAL BC'ose Rate:

Revd9 K( (X/Q) (Q COP}g Por 'KRAAL SKIN Dose Rate~

n DRsj~ ~ $3. [Li + 1.1 Mi] (+Q) (Q DOZ) i

N l' ~

l'S+@'5 t

P

- iP

'L

Page 22 of 88 ST. rIXZE PTAS CKMFQK OE%PPZING PRQCEIXRE NO. C-200, REVZS1CN 10 0 DOSE

2. 2 (continued)

1. (continued)

'Ihis value may be used in conjunction with the total nchle gas

!1 b>>' .

i~ W~

release rate (Q DVI') to verify that the dose rate is within the radionuclide di.~ibutian, a conservatism factor of 0.8 is introduced into the calculation. 'Ihe simplified equation is:

~ilitp1

~ g.<v 59 To further simplify the determinatian, the 1delxxical annual average meteorological +Q of 1.6 X 106 sec/m (Fran Table M-1) may be substituted into the equation. Also, the dose limit of 500 mrengyr may be substituted for ~. Making these substitutions yields a single cumulative (or gross) nable gas release rate limiS. 'Ibis value is:

Noble gas release rate limit ~ 3.5 X 10 uCi/sec As long as the nable gas release rates do not m0=eed this value (3.5 X 105 uCi/sec), no additional dose rate calculations are needed to verify cxmpliance with Technical Specification

3. 11.2.1.

2. Setpoint Deterrninatian To caaply with Tech. Spec. 3.3.3.10, the alarm/trip setpoints are established to ensure that the nable gas releases do not exceed

~d

~

dose rate of 500 @tram/yr. 'Ihe method that foU.ows is a step-by-step procedure for establishing the setpoints. To allow for aaltiple sources of releases fran different or ccaaxm release points, the allowable operating setpoints will be controlled tl ty tlW ~

of the release saurces.

allowable release to each A. Determine (V) the aaximm> volume release rate potent~ fran the in-plant procedures for the release source under consideration. 'Ihe units of (V) are ft3/min.

B. Solve for A, the activity concentration in uCi/cc that would produce the Y dose rate IlD X X 60 spy sec (V) ft 2.8317 X 10 cc min A~ uCi/cc

~I IL

~ H ' i ~

'll '

I I" Es

Page 20 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 8 OFFSIT DOSE CALCULATION MANUAL (ODCM) 2.2 (ccatinued)

(continued)

B. Salve for A, the activity (zncentratifn in uCi/cc that would produce the Y dose rate UD 8 3.5 X 1(} nfX X aiu X ft X 6(} sec sec 7VV ~f 2.8317 X 1 cc mlu A = CX/cc C. Refer to the Mi/cc vs. cpm curve f(x'he Release Source's Gaseous EfQnent Mcaitor cpn mIue (C), ccrzespcnding to the vaiue of A above.

I D. C is M IEK setpofnt~ assundng that them are m other mlease s(uzces cn the site.

E. Obtain the cunaut X allocated to this xeIease sance from the Nsexm waste (lBTBge(lent Iogse Fe Ttm Operating setpoint SP SP ~ (C) cpm X X allotted in lant roceduzes IKR The total AppauBx C body dose is more limiting than tbe caIculated for a detaLIed evaluaticn.) Iheref(xe, the skin dose rate st dose. (Refer to caIrulatims are not required if the sinpliffed dose rate calculaticn is used (i.e., use of +f to detenafne mlease rate limits).

'Ihe caIaQaticn process of the follmdng Secticn (2.2.3) is to be used if actual zehases of nobIe gees exceed the ebon liatt of 3.5 X 10 uCi/sec.

Uader these ccnditicns, a uucli<~mclide evaInaticn is reouired to evatuate ccupliauce with the dose ate lied.ts of Technical SPecificatiax 3.11.2.1.

3. Total Body and Bdn Nuclide ~inc Dose Rate Calculaticns

~

'Ihe folIowing outline provides a ste'p-by-step explanation of hw.the total lady dose ate is cal}c(x1ated cn a uuclide~xJfde basis to emtuate coapliance with Tech. Spec. 3.11.'g.l. 'Ms nathcd is cnly used vaIne of 3.S X 10 tKX/sec.

if the actual reIeases the A. 3}a (2/(}) value sec/u scn} ls the nose lfnftfc8 sectnc at the enclusicn ates. Ysee lab}a N-1 for vn}ue aa} sector.)

B. Enter t',m mlease rate in ft /mfn of the re~se sanee and cavort it to: ( )ft X ".8317 18 cc X nfu lUtIl ftc nu sec

I 4

D 1

g5

Page 25 of 88 ST. ZDCIE PZAÃZ CKMrSrRY OPEBATJ2G PBQCEIXRE NO. C-200, REVISION 10 OFFS DOSE CAICUIATI 2.3 the Radioiodine & Particulate tritium ard all radionuclides in particulate form with half 133, lives >eight days to <1500 axergyr to any organ. ~ following radioiodines (see 2.1) and particulates and is based an Sectian 5.2.1 ard 5.2.1.1 through 5.2.1.3 in NUR~133, November 1978. 'Ihe Infant is the controlling age group in the inhalatian, ground plane, and cow/goat milk pathways, which are the anly pathways cansidmed for releases. 'Ihe long term (+Q)D (depleted) arxi (D/Q) values are based on hi.~rical MEZ data prior to implementing Appendix I. Only those nuclides that appear on their respective table will be cansicMxd.

'Ihe equations are:

or nha tion Pathwa exclud -3:

n

~I&SDBP ~ RiT ( /Q)D (Q ~)i 0 lan:

n

~I&SD&P ~ iT (D/Q) (Q ~) i or ss~ Goat~1:

~I&SD&Z = 4 n

RfT (D/Q) (Q ~) i ~ Rev@9 Tritium Releases Inhalat &

H3T Vf-3T ( /Q)D (Q ~)H-3

~Z (DRX&SDBp + H

• Normally should be PiT, but RiT values are the same,'thus use tables in AppencLix A.

~

tachm n REVISED SEMI-ANNUAL EFFLUENT RELEASE REPORT JULY 1, 1988 THROUGH DECEMBER 31, 1988

FLORIDA POHER & 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, 1989 THROUGH DECEMBER 31, 1989

TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION............ 1 OFFSITE DOSE CALCULATION MANUAL REVISIONS....................... 7 SOLID WASTE AND IRRADIATIED FUEL SHIPMENTS.................... ~

PROCESS CONTROL PROGRAM REVISIONS.................... ~ ~ ~ ~ ~ ~ 7 LIQUID EFFLUENTS:

Summation of all Releases - Unit ¹ 1 8 all

~ ~ ~

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

Summation of all Releases Unit ¹ 1 14 Summation of all Releases Unit ¹ 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 15 Nuclide Summation by Quarter Unit ¹ 1 16 Nuclide Summation by Quarter Unit ¹ 2 17 Gaseous Pathway Dose Unit ¹ 1 18 Gaseous Pathway Dose Unit ¹ 2=...... 19 SOLID WASTE SHIPMENT SUMMATION 20

7

~ 'ff a,'f 4

4

'l It 0' gf a J) k 'P+

N 6L4

EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION

1. Regulatory Limits

1. 1 f For Liquid Haste Ef luents A. The concentration of radioactive material released from the site shall be limited to the concentrations specified otherin 10 CFR Part 20 Appendix B, Table II, Column 2 for radionuclides than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 micro-Curies/ml total activity.

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

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

1.2 For Gaseous Haste Effluerrts:

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.

4C. The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate fozm, 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'o 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.

P lilt

~ 4p 9 I' II I

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T~ I t A L

P~

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION ontxnue

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

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 P1ant Technical Specification analyses techniques to achieve required Lower Limit of Detection (LLD) sensitivity for radioactive effluents.

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

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

4. 1 Estimate of Errors LIQUID GASEOUS Error Topic Avg. % Max. % Avg. % Max. %

Release Point Mixing 2 5 NA NA Sampling 1 5 2 5 Sample Preparation 1 5 1 5 Sample Analysis 3 10 3 10 Release Volume 2 5 15 Total % 9 30 10 35 The predictability of error for radioactive releases can only be applied to nuclides that are predominant in sample spectrums.

Nuclides that are near background relative to the predominant nuclides in a given sample could easily have errors greater than the above listed maximums.

0

%P

~ ~

l f Al e

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION

( ontinued)

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

4. 1 (Continued)

B. (Continued)

TABLE 3. 1 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS Liquid Sampling Type of Method of Source Frequency Analysis Analysis Each Batch Principal Gamma Emitters p. h. a.

Monitor Monthly Tritium L. S.

Tank Composite Gross Alpha G. F. P.

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

Continuous Daily Principal Gamma Emitters Releases Grab & I-13'1 for p. h. a.

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

Tritium Composite Monthly L'. S.

Alpha Composite Monthly G. F. P.

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

1-Boric Acid Evaporator Condensate is normally recovered to the

,. Primary Water Storage Tank for recycling into the reactor coolant system and does not contribute to Liquid Waste 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

i4 b tE 4 \

( 'r

EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION ontinue

4. Measurements and Approximations of Total Radioactivity (Continued)

4. 1 (Continued):

B. (Continued)

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

Releases onta inment Principal Gamma Emitters p. h. a.

Purge Each Purge Tritium L. S.

Releases 4/M Prin'cipal Gamma Emitters p. h. a.

Tritium L. S.

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

Quarterly Particulate Composite Sr-89 8c 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 Flo'w Proportional Counting 4/M-Four per Month

0 0

FLOR1 DA POWER & LIGHT COMPANY ST. LUC IE UNI T 0 1 SEMIANNUAL REPORT DULY 1 s 1988 THROUGH DECEMBER 31 s 1988 EFFLUENT & NASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)

5. Batch Releases A Liquid Number of ba tc h releases: 4.0

2. Total time period for batch releases: 18,865.0 minutes Maximum time period for a batch release: 800 minutes 4~ Average time period f or a batch release: 563 minutes

5. Minimum time period f or a batch release: 140 minutes

6. Average dilution stream f low during the pet 1od e 889,306 gpm Al l liquid releases are summarized in tables B. Gaseous

1. Number of batch releases: 11 R

2. Total time period for batch releases: 2, 506 minutes R Maximum time period for a batch release: 708 minutes

4. Average time period for a batch release:

228 minutes R

5. Minimum time period for a batch release: 1 minute R All gaseous waste releases are summarized in tables

6. Unplanned Releases A. Liquid 1 . Number of releases: 0

2. Total activity released: 0 Curies B. Gaseous 1 . Number o f re 1 eases: 0

2. Total activity released: 0 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.

8 FLORIDA PONER & L I GHT COMPANY ST. LUCIE UNIT 8 2 SEMIANNUAL REPORT JULY 1, 1988 THROUGH DECEMBER 31, 1988 EFFLUENT & NASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)

5. Batch Releases A. Liquid Number of batch releases: 33.0

2. Total time period for batch releases: 18,865.0 minutes Maximum time period for a batch release: 800 minutes 4, Average time period for a batch release: 563 minutes

5. Minimum time period for a batch release: 140 minutes

6. Average dilution stream flow during the period: 889,306 gpm All liquid releases are summarized in tables B. Gaseous,

1. Number of batch releases: 21 R

2. Total time period for batch releases: 10,285 minutes R Maximum time period for a batch release: 1,380 minutes 4 Average time period for a batch release: 490 minutes R

5. Minimum time period for a batch release: 12 minutes R Al 1 gaseous waste releases are summarized in tables

6. Unplanned Releases A. Liquid

1. Number of releases: 0

2. Total activity released: 0 Curies B. Gaseous

1. Number of releases: 0

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

A description of the event and equipment involved.

2. Cause(s) for the unplanned release.

Actions taken to prevent a recurrence.

4 Consequences of the unplanned release.

4 V

V y

I V

V V 4

v= 4, ~

I I V

+I '

v' V 4

FLORIDA POWER & LIGHT COMPANY ST. LUC'IE PLANTS UNITS 1 8r, 2 SEMIANNUAL REPORT

~

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

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

VISITOR DOSE RESULTS FOR THE CALENDAR YEAR 1989 WERE:

Gaseous Particulates 8c Iodine Exposure Noble Gas Exposure ORGAN Dose (mrem) Dose in mrad Bone 4.75 E-06 Gamma Air Dose 1.89 E-02 Liver 6. 67'-04 Beta Air Dose 3.69 E-02 Thyroid 2.32 E-03 Kidney 2. 91 E-04 Lung 6. 62 E-04 Gi-LLI 6. 63 E-04 Total Body 6.78 E-04

8. Of fs ite Dose Calculation Manual Revisions (ODCM):

The ODCM was not revised during the reporting interval.

9 ~ Solid Waste and Irradiated Fuel Shipments:

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

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

10. Process .Control Program (PCP) Revisions:

The PCP was not revised during the reporting interval.

0 W

FLORIDA POWER 8r LIGHT COMPANY ST. LUC I E UNIT ¹ 1 SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECENBER 31, 1989 TABLE 3.3 1 LIQUID EFFLUENTS SUNNATION OF ALL RELEASES UN I T QTR¹3 QTR¹4 A. Fission and Activation Products

1. Total Release (Not including Tritium, Gases, Alpha) Ci 6. 81E-02 3. 28E-02

2. Average Diluted Concentration During Period uCi/ml 1.42E-10 6.47E-11 B. Tritium Total Release Ci 8. 45E 01 1 . 38E 02 2 ~ Average Diluted Concentration During Period UCl /ml 1.79E-07 2.72E-07 C. Dissolved and Entrained Gases

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

2. Average Diluted Concentration Dur ing Period uCi/ml 1.41E-11 2. 58E-13 D. Gross Alpha Radioactivity Total Release 3.37E-05 5.90E-06 E. Volume of Waste released (Prior to Dilution) Liters 1. 14E 07 2. 19E 07 F. Volume of Dilution Water Used During Period Liters 4.73E 11 5.07E "11

~I I ~

FLORIDA POMER & LIGHT COMPANY ST. LUCIE UNIT ¹ 2 SEMI ANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3.3 2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES

" QTR¹4 UNIT QTR¹3 A. Fission and Activation Products Total Release (Not including Tritium, Gases, Alpha) 6.75E-02 3.,00E-02

2. Average Diluted Concentration During Period uCi/ml 1. 43E-10 5. 92E-11 B. Tritium

1. Total Release Ci 8.45E 01 1.38E 02

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

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

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

1. Total Release Ci 3.37E-05 5.90E-06

=

E. Volume of Maste released (Prior to Dilution) Liters 1.36E 06 1.37E 06 F. Volume of Dilution Mater Used During Period Liters 4.73E 11 5.07E 11 h

h

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FLORIDA PONER 8c LIGHT COMPANY ST. LUCIE UNIT ¹ 1 SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3.4.1 LIQUID EFFLUENTS Con t inuous Mode Batch Mode NUCLIDES RELEASED UNIT QTR¹3 QTR¹4 QTR¹3 QTR¹4 NA-24 Ci O.OOE 00 O.OOE 00 5.60E-05 3.74E-05 CR-51 Ci O.OOE 00 O.OOE 00 4.77E-03 2.70E-03 MN-54 Ci O.OOE 00 O.OOE 00 4.63E-04 3.04E-04 FE-55 Ci O.OOE 00 O.OOE 00 1.30E-02 7.25E-03 CO-57 Ci O.OOE 00 O.OOE 00 2.00E-05 1.22E-05

.CO-58 Ci O.OOE 00 O.OOE 00 8. 15E-03 3.32E-03 FE-59 Ci O.OOE 00 O.OOE 00 a.03E-04 1.31E-OS

'CO-60 Ci O.OOE 00 O.OOE 00 5.00E-03 4. 21E-03 AG-110 Ci O.OOE 00 O.OOE 00 7.55E-04 6.45E-04 SN-113 Ci O.OOE 00 O.OOE 00 2.30E-04 1.56E-04 SB-122 Ci O.OOE 00 O.OOE 00 6.50E-04 4.00E-05 SB-124 Ci O.OOE 00 O.OOE 00 2.33E-03 1.46E-03 NP-239 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 RB-88 Ci O.OOE 00 O.OOE 00 2.65E-04 O.OOE 00 SR-89 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 SR-90 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 ZR-95 Ci O.OOE 00 O.OOE 00 1.06E-03 3.55E-04 NB-95 Ci O.OOE 00 O.OOE 00 2.02E-03 7.65E-04 ZR-97 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 NB-97 Ci O.OOE 00 0. OOE 00 9.05E-04 8. 15E-04 TC-99M Ci O.OOE 00 O.OOE 00 6 ~ 1 SE-06 6.45E-06 RU-103 Ci O.OOE 00 O.OOE 00 3.60E-05 O.OOE 00 SB-125 Ci O.OOE 00 O.OOE 00 7.65E-03 5.45E-03 I-131 Ci 3.05E-04 1.97E-03 3.62E-04 5.90E-04 TE-132 Ci O.OOE 00 O.OOE 00 2.74E-05 O.OOE 00 I-132 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 I-133 Ci O.OOE 00 O.OOE 00 1. 71E-05 8.45E-05 CS-134 Ci 8.95E-OS 3. 71E-04 7.90E-03 8.00E-04 CS-137 Ci 2.49E-04 4.38E-04 1.09E-02 8. 15E-04 CS-138 Ci O.OOE 00 O.OOE 00 3.87E-05 O.OOE 00 BA-140 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 LA-140 Ci O.OOE 00 O.OOE 00 1.26E-04 7.65E-05 CE-141 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 CE-144 Ci O.OOE 00 O.OOE 00 6.75E-04 O.OOE 00 TOTAL FOR PERIOD (ABOVE) Ci 6.44E-04 2.78E.

.03 6.75E-02 3.00E-02 AR-41 Ci O.OOE 00 O.OOE 00 3.26E-05 3.23E-06 KR-BSM 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-a Ci O.OOE 00 O.OOE 00 6.20E-03 1.28E-02 XE-133M Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 XE-135 Ci O.OOE 00 O.OOE 00 .4.02E-04 3.22E-04 10

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FLQR I DA PQNER Sr LIGHT COMPANY ST - LUG IE,,UNI T ¹ 2 SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3.4 2 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDEB RELEASED UNIT QTR¹3 'QTR¹4 QTR¹3 QTR¹4 NA-24 Ci O.OOE 00 O.OOE 00 5.60E-05 3.74E-05 CR-51 Ci O.OOE 00 O.OOE 00 4.77E-03 2.70E-03 MN-54 Ci O.OOE 00 O.OOE 00 4.63E-04 3.04E-04 FE-55 Ci O.OOE 00 O.OOE 00 1.30E-02 7.25E-03 CO-57 Ci O.OOE 00 O.OOE 00 2.00E-05 1.22E-05 CQ-58 Ci O.OOE 00 O.OOE 00 8. 15E-03 3.32E-03 FE-59 Ci O.OOE 00 O.OOE 00 1.03E-04 1 . 31E-05 CO-60 Ci O.OOE 00 O.OOE 00 5.00E-03 4. 21E-03 AG-110 Ci O.OOE 00 O.OOE 00 7.55E-04 6.45E-04 SN-113 Ci O.OOE 00 O.OOE 00 2.30E-04 1.56E-04 SB-122 Ci O.OOE 00 O.OOE 00 6.50E-04 4.00E-05 SB-124 Ci 0 OOE 00 O.OOE 00 2.33E-03 1.46E-03 NP-239 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 RB-88 Ci O.OOE 00 O.OOE 00 2.65E-04 O.OOE 00 SR-89 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 SR-90 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 ZR-95 Ci O.OOE 00 0. OOE 00 1.06E-03 3.55E-04 NB-95 Ci O.OOE 00 O.OOE 00 2.02E-03 7.65E-04 ZR-97 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 NB-97 Ci O.OOE 00 O.OOE 00 9.05E-04 8.15E-04 TC-99M Ci O.OOE 00 O.OOE 00 6.15E-06 6.45E-06 RU-103 Ci O.OOE 00 O.OOE 00 3.60E-05 O.OOE 00 SB-125 Ci O.OOE 00 O.OOE 00 7.65E-03 5.45E-03 I-131 Ci O.OOE 00 O.OOE 00 3.62E-04 5.90E-04 TE-132 Ci O.OOE 00 O.OOE 00 2.74E-05 O.OOE 00 I-132 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 I-133 Ci O.OOE 00 O.OOE 00 1.71E-05 8.45E-05 CS-134 Ci O.OOE 00 O.OOE 00 7.90E-03 8.00E-04 CS-137 Ci O.OOE 00 O.OOE 00 1.09E-02 8. 15E-04 CS-138 Ci O.OOE 00 O.OOE 00 3.87E-05 O.OOE 00 BA-140 Ci O.OOE 00 O.OOE 00 ~

O.OOE 00 O.OOE 00 LA-140 Ci O.OOE 00 O.OOE 00 1.26E-04 7.65E-05 CE-141 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 CE-144 Ci O.OOE 00 O.OOE 00 6.75E-04 O.OOE 00 TOTAL FO R PERIOD (ABOVE) Ci O.OOE 00 O.OOE .00 6.75E-02 3.00E-02 AR-41 Ci O.OOE 00 O.OOE 00 3.26E-05 3.23E-06 KR-85M 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-133 Ci O.OOE 00 O.OOE 00 6.20E-03 1.28E-02 XE-133M Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 XE-135 Ci O.OOE 00 O.OOE 00 4.02E-04,, 3.22E-04 11

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

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

1 FLORIDA POWER 8c LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMI-ANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3.5-2 LIQUID EFFLUENTS DOSE SUMMATION Age Group: ADULT Location: Any ADULT Exposure Interval: January 1, 1989 through December 31, 1989 F ISH 8c S HELLF ISH Calendar Year ORGAN Dose (mrem)

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

i 1

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FLORIDA POWER 8r LIGHT COMPANY ST. LUCIE UNIT O 1 SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3.6"1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR03 QTR44

-A, Fission and Activation Gases

1. Total Release Ci 8.59E 02 1.67E 03

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

b. Iodines 1 ~ Total Iodine 131 1.10E-03 6,53E-04

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

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

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

3. Gross Alpha Radioactivity 9.21E-08 1.15E-OV D. Tritium 1, Total, Release Ci . 2.42E 02 3.48E 01

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

0 FLORIDA POHER & LIGHT COMPANY ST. LUCIE UNIT ¹ 2 SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3,6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR¹3 QTR¹4 A. Fission and Activation Gases

1. Total Release Ci 1.56E 02 8.38E 01

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

b. Iodines

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

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

i. Particulates T 1/2 > 8 Days O.OOE 00 5.65E-05

2. Avg. Release Rate For Period uCi/sec O.OOE 00 7.11E-06 3 ~ Gross Alpha Radioactivity 9.65E-08 1.26E-08 D. Tritium

1. Total Release 1.27E 01 1.06E 01

2. Avg. Release Rate For Period uCi/sec 1.60E,00 1.33E 00

0 FLORIDA POWER 5 LIGHT CONPANY ST. LUCIE UNIT ¹ 2 SEHIANNUAL REPORT JULY 1, 1988 THROUGH DECEMBER 31, 1988 TABLE 3.6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR¹3 QTR¹4 A. Fission and Activation Gases

1. Total Release 2.07E 03 2.95E 03

2. Avg. Release Bate For Period uCi/sec 2.60E 02 3.71E 02

b. Iodines

1. Total Iodine 131 1.28E-02 1.88E-03

'. 2. Avg. Release Particulates Rate For Period uCi/sec 1.61E-03 2.36E-04

1. Particulates T 1/2 > 8 Days 0 OOE 00

~ 0 OOE 00

~

2. Avg. Release Bate For Period uCi/sec O.OOE 00 O.OOE 00

3. Gross. Alpha Radioactivity 1.81E-08 2.70E-07 D. Tritium

1. Total Release Ci 1.72E 01 1.93E 01 R

2. Avg. Release Rate For Period uCi/sec 2.16E 00 2.43E 00 R

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FLORIDA POHER & LIGHT COMPANY ST. LUCIE UNIT 0 1 SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3.7"1 GASEOUS EFFLUENTS GROUND LEVEE RELEASES Nuclides Continuous Mode Batch Mode Released Unit. QTR53 QTR04 QTB03 QTB04

1. Fission Gases AB-41 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 00, '.

KR-85M Ci 8.57E 00 1.53E 01 2.47E-02 O.OOE 00 KB-87 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 KR-88 Ci 3.91E 00 '.01E 00 O.OOE 00 0 OOE 00

~

XE-131M Ci O.OOE 00 O.OOE 00 2 '0E-01 O.OOE 00 XE-133 Ci 7.27E 02 1.45E 03 2.90E 01 O.OOE 00 XE-133M Ci 3.32E 00 6.71E 00 5.43E-01 O.OOE 00, XE-135 Ci 8.66E 01 1.90E 02 2.10E-01 O.OOE 00 XE-135M Ci O,.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 XE-138 Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 TOTAL FOR PERIOD Ci 8.29E 02 1.67E 03 3.00E Oi O.OOE 00

2. Iodines I-131 Ci 1,10E-03 6.53E-04 I-132. Ci 4.43E-03 O.OOE 00 I-133 Ci 6.42E-03 4.71E-03 I-134 Ci O.OOE 00 O.OOE 00 I-135 Ci O.OOE 00 O,OOE 00 TOTAL FOR PERIOD Ci 1.20E-02 5.36E-03

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

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FLORIDA POHER 5 LIGHT COMPANY ST. LUCIE UNIT ¹ 2 SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989

,TABLE 3.7-2 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 3.68E-01 4,32E-01 KR-85 Ci O.OOE 00 O.OOE 00 O.OOE 00 3.57E-01

-'KR-85M Ci 1.71E 00 2.67E-01 3.07E-02 6.35E-02 KR-87 Ci O.OOE 00 O,OOE 3.84E-03 6.83E-03 KR-88 Ci O.OOE 00 00 00'.OOE 3.48E-02 6.40E-02 XE-131M Ci O.OOE 00 O.OOE 00 2,29E-01 3.50E-01 XE-133 Ci 1.11E 02 4.21E 01 1.57E 01 3.15E 01 XE-133M Ci Q.OOE 00 O.OOE 00 1.83E-01 4.44E-01 XE-135 Ci 2.60E 01 6.71E 00 4 '6K-01 1.45E 00 XE-135M Ci O.OOE 00 O.OOE 00 0 OOE 00

~ O.OOE 00 XE-137 Ci 0;OOE 00 O.OOE 00 2.10E-02 O.OOE 00

.- XE-138 Ci 0;OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 TOTAL FOR PERIOD Ci 1.39E 02 4.91E 01 1. 70E 01 3. 47E Oi

2. Iodines I-131 Ci 3.50E-04 4.80E-04 I-132 Ci O.OOE 00 O.OOE 00 I-133 Ci 6.59E-04 2.07E-03 I-134 Ci O.OOE 00 O.OOE 00 I-135 Ci O.OOE 00 O.OOE 00 TOTAL FOR PERIOD Ci 1.01E-03 2.55E-03

3. Particulates 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 Tc-99M Ci O.OOE 00 5.65E-05 17

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FLORIDA POWER 8c LIGHT COMPANY ST. LUCIE PLANT UNIT 0 1 TABLE 3.8-1 GASEOUS EFFLUENTS DOSE SUMMATION - Age Group: INFANT Exposure Interval: January 1, 1989 through December 31, 1989 NOTE: The below dose results were calculated using actual meterological data during the specified time interval with Met data reduced as per Reg. Guide 1. 111, March 1976 BONE LIVER THYROID KIDNEY PATHWAY mrem mrem mrem mrem Ground Plane (A) 0. 00 E-01 0. 00 E-01 0. 00 E-01 0. 00 E-01 Grass-Goat-Milk(B) 4. 75 E-04 5. 62 E-03 1. 70 E-01 2. 35 E-03 Inhalation (A) 1. 10 E-05 2. 03 E-03 5 69

~ E-03 8. 87 E-04 TOTAL 4. 86 E-04 7. 65 E-03 1. 76 E-01 3. 24 E-03 LUNG GI-LLI T. BODY PATHWAY mrem mrem mrem Ground Plane (A) 0. 00 E 00 0. 00 E 00 3.25 E-05 Grass-Goat-Milk(B) 5. 10 E-03 5. 13 E-03 5.40 E-03 Inhalation (A) 2. 02 E-03 2. 02 E-03 2. 03 E-03 TOTAL 7. 12 E-03 7. 15 E-03 7. 46 E-03 (A) -Sector: SE Range: 1. 50 miles (B)-Sector  : WNW Range: 3. 75 miles (Actual Goat)

CALENDAR YEAR NOBLE GASES (mrad)

Gamma Air Dose 4.68 E-02 Beta Air Dose 9. 76 E-02 Sector  : SE Range: 1.50 miles 18

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT ¹ 2 TABLE 3.8-2 GASEOUS EFFLUENTS DOSE SUMMATION AGE GROUP  : INFANT Exposure Interval: January 1, 1989 through December 31, 1989 NOTE: The below dose results were calculated using actual meterological data during the specified time interval with Met data reduced as per Reg. Guide 1. 111, March 1976 BONE LIVER THYROID KIDNEY PATHWAY mrem mrem mrem mrem Ground Plane (A) 0.00 E-01 0.00 E-01 0.00 E-01 0.00 E-01 Grass-Goat-Milk(B) 5. 91 E-04 1. 99 E-03 2. 27 E-01 7. 34 E-04 Inhalation (A) 7. 13 E-06 5. 15 E-04 3. 17 E-03 2.23 E-04 TOTAL 5.98 E-04 2.51 E-03 2.30 E-01 9.57 E-04 LUNG GI-LLI T. BODY PATHWAY mrem mrem mrem Ground Plane (A) 0. 00 E 00 0. 00 E 00 1.91 E-05 Grass-Goat-Milk(B) 1.28 E-03 1.31 E-03 1.69 E-03 Inhalation (A) 5. 06 E-04 5. 07 E-04 5. 10 E-04 TOTAL 1. 79 E-03 1. 82 E-03 2. 22 E-03 (A) -Sector: SE Range: 1.50 miles (B)-Sector  : WNW Range: 3.75 miles (Actual Goat)

CALENDAR YEAR NOBLE GASES (mrad)

Gamma Air Dose .2. 78 E-02 Beta Air Dose 4. 80 E-02 Sector  : SE Range'. 1.50 miles 1 9

FLORIDA POWER AND LIGHT COMPANY ST. LUCIB PLANT SEMI"ANNUAL RBPORT JULY 1, 1989 THROUGH DECEMBBR 31, 1989 UNITS 1 AND 2, TABLB 3.9 A. Solid Waste Shipped Off-Site for Burial or Disposal Type of Waste Unit 6 Mo. Period Error  %

a ~ Spent resin, M3 3.546 E+1 Process filters Ci S.S9O E+1 2.O E+1

b. Dry Compressible M3 9.813 E+1 0 E+1 Waste (Note 5) Ci 5.701 E 1 c~ Irradiated M3 Components Ci 2.O E+1

d. Other M3 3.119 E+1

1. Non-Compres" -Ci 5.284 E 1 2.O E+1 sible Metal (DAW) (Note 6)

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

Category Nuclides a~ Cs 137 3 57 E+1 Co 60 1.59 E+1 Cs 134 1.S7 E+1 Ni 63 1.OS E+1 Co 58 9. 91 E~

Fe 55 5.05 E+0 Sb 125 2.85 E+0 Sb 122 1.18 E+0 Mn 54 1.10 E+0 H 3 1.08 E+0

b. H 3 3.45 E+1 Co 60 2.11 E+1 Cs 137 1.88 E+1 Cs 134 6 ~ 12 E~

Fe 55 5.96 E+0 Co 58 4.77 E+0 Ni 63 2.46 E~

Ce 144 2.09 Eo Sb 125 1.01 E+0 Zr 95 8.09 E 1 Mn 54 7.o6 E"1 20

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

Category Nuclides

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

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

Number of Shipments Mode of Transportation Destination 0 N/A N/A N/A Not Applicable 21

FLORIDA POWER AND T COHPANY ST LUCIE PLANT BENI-ANNUAL REPORT JULY lg 1989 THROUGH DECEMBER 31'989 UNITS 1 AND 2g TABLE 3.9 (COHTIHUED)

Total Total Principal Type of Category Type of Waste Vol[me Curies Radionuclides Waste Rag&aide Container Solldificatior.

Class Cubic Ft. (Rote 1) (Notes 1 0 2) (Rote 3) 1.21 (Rote 4) Agent

~

Class A 3465.5 5.701 E-l NA PWR l.b. No'n-Specification None Compactible Strong Tight Trash Package (Note 5)

Class A 1101.4 5 284 B 1 NA PWR l.d. Non-Specification None Non-Compactible Strong Tight Trash Package (Nota 6)

ClasS A 926.2 3.95 Cs 137, PMR ).a. NRC Certified None Hi 63 Ion-Exchange LSA Resin T A Class 8 326.1 51.95 Cs 137, Sr 90, PWR l.a. NRC Certified Nona Ni 63, PU 24li Ion Exchange LSA TRU Resin T A

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

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

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

The composition of radionuclides in the waste is determined by both on-site analyses for principal gamma emitters and periodic off-site analyses for other radionuclides. The on-site analyses are performed either on a batch basis or. on a routine basis using reasonably representative samples as appropriate f'r the waste type. Off-site analyses are used to establish scaling factors or other estimates for radionuclides such as 3H,. 14C, 99Tc, 129I, TRU, 241Pu, 242Cm, 63Ni, 55Fe, and 90Sr.

Note 2: "Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than .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.

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

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

Note 5: The volume and activity listed for Dry Compressible Waste represent the quantity of material that to date has'een sent to the Barnwell, South Carolina burial facility. This material was shipped to a contracted vendor for volume reduction prior to final disposal at the Barnwell, South Carolina burial facility. During the reporting period, five shipments of Dry Compressible Waste (5,152 cubic feet, 5.49 E 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.

23

~ y 'I Note 6: The volume and activity listed for non-compressible metal represent 1 the quantity of material that during the reporting period could not be recycled by the contracted vendor and required disposal.

24

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DATE FINAL SUBMITTAL 4

AFFIDAVIT REQUIRED: YES Q M) Q RECEIVED BY JNL:

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AOMIHISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUEHT RELEASE REPORT 6.9.1.7 Routine Radioactive Effluent Release'epor ts covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial critfcalfty.

The Radioactive Effluent Release Reports sha)l fnclude a sunxnary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide l.'21, "Measuring,. Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents form Light-Mater Cooled Nuclear Power Plants,"

Revision 1, June 1974, with data suamarfzed on a quarterly basis following the format of Appendix B thereof.

The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual sundry of hourly meteorological data collected over the previous year. This annual suaaary may be either in the form of an hour by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (ff measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmos-pheric stability."" This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report .

shall also include an assessment of the radiation doses from radioactive 1iquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNOARY (Figure 5.1-1) during the report period. All assump-tions used in making these assessments, f.e., specific activity, exposure time and location, shall be included in these reports. The meteorological condi-tions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE OOSE CALCULATION MANUAL (OOCM).

Every 2 years using the previous 6 months release history for isotopes and historical meteorolgical data determine the controlling age group for both liquid and gaseous pathways. If changed from current submit change to OOCM to reflect new tables for these groups and use the new groups fn subsequent dose calculations.

The Radfoactfve Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases for the previous 7C A single submftta) may be made for a multiple unit station. The submittal should combine those sections that are coaeen to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material 'from each unit.

In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

.ST. LUCIE " UNIT 2 6-18 Amendment No. L8. 18

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AOHINISTRATI VE CONTROLS o SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) calendar year. Acceptable methods for calculating the dose contribution from iiquid and gaseous effluents are given in Regulatory Guide 1.109, .March 1976.

The Radioactive Effluent Release Reports shall include the following information for each class of solid ~aste (as defined by 10 CFR Part 61) shipped offsite during the report period:

a. ,Volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

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

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

e. Type of container (e. g., LSA, Type A, Type S, Large guantity), and Solidification agent or a5sorbent (e. g.', cement, urea formaldehyde).

The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from thi site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCUlATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3, 12.2.

ANNUAL RADIOLOGICAL ENVIRONHENTAL OPERATING REPORT~

6.9.1.8 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to Hay 1 of each year. The initial report shall be submitted prio~ to Hay 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Reports shall include sunmaries, interpretations, and information based on trend analysis of the results of the r adiological environmental surveillance activities for the report period, including a comparison, as appropriate, with preoperational studies, with operational controls and. with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of land uie censuses required by Specification 3. 12.2.

The Annual Radiological Environmental Operating Reports shall include the results of ahalysis of all radiological environmental samples and qf all environmental radiation measurements taken during the period pursuant,to the A single submittal may be aide for a multiple unit station:

ST. LUCIE - UNIT 2 6- lg Amendment No. I3

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