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: L-90-201, Forwards Revised Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1988 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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DESCRIPTION TABLE OF CONTENTS PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION,........

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

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

SOLID WASTE AND IRRADIATIED FUEL SHIPMENTS.................

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7 PROCESS CONTROL PROGRAM REVISIONS...............................

LIQUID EFFLUENT:

SUMMATION OF ALL RELEASES

& NUCLIDE SUMMATION BY QUARTER NIT 0 1

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10 GASEOUS EFFLUENT:

SUMMATION OF ALL RELEASES

& NUCLIDE SUMMATION BY QUARTER NIT 0 1

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U SOLID WASTE

SHIPMENT SUMMATION 12 14 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 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 Sampling Sample Preparation Sample Analysis Release Volume Total I 2

1 1

3 2

5 5

5 10 5'0 NA 2

1 3

4 10 NA 5

5 10 15 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 Source Sampling Frequency Type of Analysis Method of Analysis Each Batch Principal Gamma Emitters

p. h. a.

Monitor Tank 1

Releases Continuous Releases Monthly Composite Quarterly Composite Daily Grab Samples Tritium Gross Alpha Sr-89, Sr-90,

& Fe-55 Principal Gamma Emitters

& I-131 for 4/M Composite Analysis Dissolved

& Entrained Gases One Batch/ Month Tritium Composite Monthly Alpha Composite Monthly Sr-89, Sr-90-;

& Fe-55 Composite Quarterly L. S.

G. F. P.

C. S.

p. h. a.

p. h. a.

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C

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

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

All peaks are identified and quantified.

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

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EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued) 4.

Measurements and Approximations of Total Radioactivity (Continued)

4. 1 (Continued)

B.

(Continued)

TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS Gaseous Source Sampling Frequency Type of Analysis Method of Analysis Waste Gas Decay Tank Releases Containment Purge Releases Each Batch Principal Gamma Emitters Principal Gamma Emitters Each Purge Tritium

p. h. a.

p. h. a.

L.S

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4/M Principal Gamma Emitters Tritium

p. h. a.

L. S.

Plant Vent Monthly Composite Quarterly Composite Particulate Gross Alpha Particulate Sr-89

& Sr-90 G. F. P.

C. S.

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

All peaks are identified and quantified.

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

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FLORIDA POWER

& LIGHT COMPANY ST.

LUCIE UNIT 5 1

SEMIANNUAL REPORT JANUARY 1~

1988 THROUGH JUNE SOr 1988 EFFLUENT & WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED) 5.

Batch Releases A.

Liquid l.

2.

3.

5.

6.

Number of batch releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for a batch release:

Minimum time period for a batch release:

Average dilution stream flo~ during the period:

21.0 11,650.0 minutes 1,047 minutes 555 minutes 515 minutes 1<027>087 gpm All liquid releases are summarized in tables B.

Gaseous 1.

2.

3e 4

5.

Number of batch releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for a batch release:

Minimum time period for a batch release:

2 550 minutes 4~0 minutes 275 minutes 120 minutes AlI gaseous waste releases are summarized in tables 6.

Unplanned Releases A.

Liqui d 1.

Number of releases:

2.

Total activity released:

0 0

Curies B.

Gaseous Number of releases:

2.

Total acti vity released:

0 0 Curies C.

See attachments (if applicable) for:

2.

4 ~

A description of the event and equipment. involved.

Cause(s) for the unplanned release.

Actions taken to prevent a recurrence.

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-B.

TOTAL TIME PERIOD OF BATCH RELEASES-C.

MAXIMUMTIME PERIOD FOR h BATCH RELEASE:

D.

AVERAGE TIME PERIOD FOR A BATCH RELEASE-E.

MINIMUM TIME PERIOD FOR h BATCH RELEASE:

F.

AVERAGE STKDlM FLOW DURING REPORTING PERIOD INTO h FLOWING STK9lH:

21.8 11658.

MINUTES 1847.

MINUTES 555.

MINUTES 315.

MINUTES 1827887.

G. P.M.

S.

GASEOUS FOR ST.

LUCIE PLANT UNIT NO.

2 A.

NUMBER OF BATCH RELEASES-B.

TOTAL TIME PERIOD OF BATCH RELEASES-C.

MhXIMUM TIME PERXOD FOR A BATCH RELEASE-D.

AVERAGE TIME PERIOD FOR h BATCH RELIMHE-E.

MINIMUMTIMR PERXOD FOR h BATCH REIXhSR-UNPLANNED RELEASES

22. 8 S 679.

MINUTES 788.

MINUTES 384.

MINUTES 28.

MXNUTES LIQUIDS FOR-ST.

LUCIE PLANT UNIT NO.

2 A.

NUMBER OF RELEASES-B.

TOTAL ACTXVITYRELEASED-GASEOUS FOR ST.

LUCIE PLANT UNXT NO.

2 A. NUMEN OF RELEASES-B.

TOTAL ACTIVITYRELEASED-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.

8.8.

CURIES 88.

CURIES

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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 A. FISSION AND ACTIVATION PRODUCTS 1.

TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) 2.

AVERAGE DILUTED CONCENTRATXOH DURING PERIOD B. TRITIUM CI 4.28E-S2 1.89E-S2 UCI/ML 8.45E-ii

3. 72E-11 UNIT QUARTER 41 QUhEDKR 42 1.

TOTAL RELEASE 2.

AVERAGE DILUTED CONCENTRATION DURING PERXOD C.

DXSSOLVED AND ENTRAINED GASES 1.

TOTAL REUDlSB 2.

AVB248iE DILUTED CONCENTRATIOH DURING PERIOD D. KKSS ALPHA RADIOACTIVITY CI 3.88E Si CI 2.S2E-S2 UCI/ML 3.99'-il UCI/ML

7. 28E-SB 9.37E Si 1.85E-S7 2.52E-S1

4. 98E-1S TOTAL RELEASE CI S. SSE-Si S. SSE-Sl.

K.

VOLUME OF WASTE RELEhSED (PRIOR TO DILUTXON)-

F.

VOLUME OF DXLUTIOH WhTER USED DURING REPORTING PERIOD LITERS 2.92E S7 LITERS 5.S7E 11 2.59E S7 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 RELEASED UNIT CONTINUOUS MODE QTR. Oa QTR. 02 BATCH MODE QTR.01 QTR.02 I-131 I-133 NA-24 CR-51 MN-54 FE-55 CO-58 FE-59 CO-68 hG-aae SN-113 SB-122 SB-124 SR-98 Y-98 ZR-95 NB-95 NB-97 TC-99M SB-125 CS-134 CS-137 LA-148 CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI 2.54E-84 H.HHE-Sl S.SSE-81 S.SSE-81 S.SSE-81 S.SSE-81 S.SSE-81 H.SHE-81 H.SHE-81 S.HSE-81 H.HHE-81 H.SSE-81 S.SSE-81 7.92E-84 7.92E-84

8. SHE-81

8. SHE-81 S.SSE-ea

8. HSE-81

8. SHE-81

8. HHE-81

6. 79E-85 S.HHE-ea e.eez-ea

8. SSE-Sl

8. HHE-81

8. SHE-81

8. SSE-81

8. SSE-81

8. SSE-81

8. SSE-Sl

8. SSE-81 S. SSE-81

8. HHE-81

8. HSE-Sl

8. SSE-81

8. SHE-81

8. SSE-81

8. SHE-Hl H.eeE-ea

8. SSE-81

8. HHE-81

8. SSE-81

8. SHE-81

8. SSE-81 S.eeE-ea 1.89E-83 3.83E-84 1.85E-85 4.83E-84 3.68E-84 1

~ 36E-82 5.38E-83 3.28E-85 3.77E-83 3.81E-84 2.64E-85 1.86E-85 2.89E-83 1.25E-86 1.25E-86 3.69E-84 7.51E-84 4.66E-84 8.88E-81 7.93E-83 1.13E-83 1.88E-83 1.97E-84

9. 11E-84 1.41E-84 H.SHE-ea S.SSE-81 3.76E-85 5.6HE-83 4.38E-83 H.HSE-81 2.42E-83 8.13E-85 H.HSE-81 S.SHE-81 1.34E-84 2.55E-85 2.55E-H5 H.SHE-81 9.29E-H5 8.72E-85 1

~ 37E-85 3.87E-83 6.68E-84 a.a8E-83 4.98E-H5 TOTAL FOR PERIOD AR-41 XE-13aM XE-133 XE-133M XE-135 TOTAL FOR PERIOD CI CI CI CI CI CI CI H. SSE-Hl

8. SHEMa S. SSE-81

8. SHE-81 S.eeE-ea H. SSE-81

8. SSE-81 H. SSE-81

8. SHE-81

8. SSE-81 2.75E-85 S.eeE-ea 1.73E-82 2.55E-84 2.62E-83 S.eez-ea 1.98E-83 2.46E-ei 2.23E-83 1.78K-83 S.HSE-el S.SHE-81 2.82E-82 2~52E-ea 1.91E-83 H.SHE-el 4.89E-82 1.89E-82

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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) 2.

AVERAGE DXLUTED CONCENTRATION DURING PERIOD B. TRITIUM 1.

TOTAL RELEASE 2.

AVERAGE DILUTED CONCENTRATION DURING PERIOD C.

DISSOLVED AND ENTRAINED GASES 1.

TOTAL RELEASE 2.

AVERAGE DILUTED CONCENTfQTION DURING PKRIOD D.

GROSS ALPHA RADIOACTIVXTY CI

4. 89E-82 CI 3.88E 81 UCI/ML

7. 26E-88 CX 2.82E-82 OCI/ML 3.99E-11 UCI/ML 8.88E-ii 1.89E-82 3.72E-11 9.37E 81 1.85E-87

2. 52E-S1 4.98E-18 1.

TOTAL RELEASE CX S.SHE-81

8. SHE-81 E.

VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)

F.

VOLUME OF DILUTION MATER USED DURING REPORTXNG PERIOD LITERS

- 1.84E 88 LITERS 5.87E 11 1.57E 88 5.86E il

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I-131 I-133 NA-24 CR-51 NN-54 FE-55 CO-58 FE-59 CO-68 AG-118 SN-113 SB-122 SB-124 SR-98 Y-98 ZR-95 NB-95 NB-97 TC-99M SB-125 CS-134 CS-137 LA-148 TOTAL FOR PERIOD CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI

'CI CI CI CI CI NUCLIDES RELEASED UNIT CONTINU QTR.¹l OUS NODE QTR.¹2 e.eeE-ea H.HHE-81 S.HHE-81 H.SSE-81 H.SHE-81 H.SHE-81 H.HHE-81 S.HHE-81 H.HHE-81 S.SHE-81 H.SHE-81 S.SHE-81 S.SSE-81 S.SHE-ea H.HHE-81 H.HSE-81 H.HHE-el H.HHE-81 H.HHE-81 S.SSE-81 S.HHE-el H.SSE-Ha H.SHE-81

8. HSE-81

8. SSE-81

8. HHE-81 S. SHE-Hl S. HHE-81

8. SSE-81

8. HHE-81

8. HHE-81

8. HHE"81

8. HHE-Sa H. HHE-81 S. SHE-81 H.eeE-ea H. SSE-81

8. HSE-81

8. HHE-81

8. HHE-81 S. HHE-81

8. HHE-81

8. SHE-81 8; eeE-ea S. SHE-81

8. SSE-81 BATCH MODE QTR.¹1 QTR.¹2 1.89E-H3 3.83E-84 1.85E-85 4.83E-84 3.68E-84 1.36E-82 5.38E-83 3.28E-85 3.77E-83 3.81E-84 2.64E-85 a.86E-es 2.89E-83 1.25E-86 1.2SE-86 3.69E-84 7.51E-84 4.66E-84 H.SHE-81 7.93E-83 1.13E-83

1. SSEM3 1.97E-84 9.11E-H4 1.41E-H4 H.HSE-81 H.HHE-81 3.76E-85 5.68E-83 4.38E-83 H.SSE-81 2.42E-83 8.13E-85 H.HHE-81 S.HHE-81 1.34E-84 2.55E-85 2.55E-85 S.SSE-81 9.29E-85 8.72E-85 1.37E-H5 3.87E-83 6.68E-H4 1.18E-83 4.98E-S5 H.HHE-81 H.HHE-81 4.89E-82 1.89E-H2 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 AR-41 XE-131M XE-133 XE-133M XE-135 CI CI CI CI CI

8. SHE-81 S. HHE-81

8. SHEMa

8. SHE-81

8. SHE-81

8. HSE-81

8. HHE-81

8. SSE-81

8. HHEMa

8. SSE-81 2.75E-85 S.HHE-81 1.73E-82 2.55E-84

2. 62EM3

8. SSE-81 1.9HE-83 2.46E-81 2.23E-83 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 A. FISSION hND hCTXVhTXON GhSES UNIT QUhRTER 41 QUhRTER S2 1.

TOThL RELEASE CI 4.11E 82

i. TOThL IODINE-131 CI 2.

hVERAGE RELEASE RATE FOR PERIOD UCI/SEC C.

PhRTXCULATES 1.

PhRTXCULATES T-1/2

> 8 DhYS CI

1. 91E-83

2. 45E~

8. 88EMl 2.

hVERAGE RELEASE RATE FOR PERIOD UCI/SEC 8.88EM1 3.

GROSS hLPHh RADIOhCTIVITY CI D. TRITIUM

2. 62EW7 2.

hVKRAGK RELEhSE RATE FOR PERIOD UCX/SEC

5. 28E 81 B.

IODINES 4.66E 82 5.92E 81 1.82E-83

1. 38EM4

8. 88E-81

8. 88EM1

1. 88EM7 1.

TOThL REUQlSR CI 2.

hVXRAGE RELEASE RATE FOR PERIOD UCI/SEC 5.82E 81 6.46E 88 2.81E 81 2.56E 88

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JANUARY PLORIDh P0%6t 8c LIQHT COMPANY ST.

LUCIE PLANT UNIT NO.

1 SEMIANNUAL REPORT 1,

1988 THROUGH JUNE 38, 1988 TABLE 3. 7-1 GASEOUS EFFLOENTS GROUND LEVEL RELEASES NOCLIDES RELEASED UNIT 1.'OBLE GASES CONTINUOUS MODE QTR. 01 QTR. 02 BATCH MODE QTR. 01 QTR. 42 KR-85M CI KR-88 CI XE-131M CI XE-133 CI XE-133M CI XE-135 CI TOTAL FOR PERIOD CI 2.29E HS 4.14E 88

8. SHE-81 3.2HE 82 4.81E-81 8.41E Sl 1.85E HS 1.35E 88 S.SSE-81 3.8SE 82 3.14E 88 7.95E Sl

8. SSEW1 S. SSEM1

1. 38EW3

2. 59EM1 S. SSEW1

8. SSEMl

8. HSE-81

8. SSEM1

8. SSE"81

3. 82EM3

8. SHE-81

8. HSEW1

4. 1HE 82 4.88E 82 2.8SEM1 3.82EM3 2.

IODINE I-131 I-133 TOTAL FOB PERIOD CI

1. 91EM3

1. 82EM3 CI

1. 87EM2

8. 15EM3 CI

1. 28EM2

9. 17EM3 3.

PARTICULATE TOTAL FOR PERIOD CI

8. SSEM1

8. SSEW1

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~ t'6 la

14 FLORIDA POWER & LIGHT COMPANY ST.

LUCIE PLANT UNIT NO.

2 SEMIANNUAL REPORT JANUARY 1,

1988 THROUGH JUNE 38, 1988 TABLE 3.6-2 GASEOUS EFFLUENTS SUMMhTION OF ALL RELEASES NUCLIDES RELEASED h.

FISSION AND ACTIVATION GASES UNIT QUARTER Si QUARTER 02 1.

TOTAL RELEASE CI 1.54E 83 2:

AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 1.97E 82 B.

IODINES 2.68E 83 3.31E 82 1.

TOTAL IODINE-131 2.

AVERAGE RELEASE RATE FOR PERIOD 0

C.

PARTICULATES CI 4.15E-83 UCI/SEC 5.34E~

9.71E-83

l. 23EW3 1.

PARTICULATES T-1/2

> 8 DAYS CI

8. 88E-81 2.

AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 8.88EM1 3.

GROSS ALPHA RADIOACTIVITY D. TRITIUM 1.

TOTAL REUSE CI CI 8.78E-88 2.34E 81 2.

AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 3.81E 88 3.84E-85 3.86E-88 2.88K-88 2.56E 81 3.25E 88

tU U

It

ee FLORIDA POWER Bc LIGHT COMPANY 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 ONIT QTR. ¹1 QTR. ¹2 QTR. ¹1 QTR. ¹2 1

NOBLE GASES AR-41 KR"85M KR-88 XE-131M XE-133 XE-133M XE-135 TOTAL FOR PERIOD 2.

IODINE I-131 I-133 TOTAL FOR PERIOD 3.

PARTICOLATE CS"137 TOTAL FOR PERIOD CI CI CI CI CI CI CI

8. 88E-81 9.83E 88 3.5BE 88 8.88E-81 1.3BE 83 8.88E-Sl 1.57E 82

8. 88EM1 2.88E 81 1.28E 81 8.88E-81 2.19E 83

8. 88EM1 2.91E 82 2.87E-81

4. 79EM3

3. 24E-83

5. 72EM2 3.97E 88

2. 93EM2 7.14E-82 2.35E-81 9.97E-82 B.77E-82 3.93E-81 8.12E 81 1.27E 88 2.43E 88 CI

4. 15E-83

9. 71E-83 CI

5. 89EM3

1. 24E-82 CI

1. 88E-82

2. 21E-82 CI 8.88E-81 3.84E-85 CI 8.88E-81 3.84E-85 CI 1.53E 83 2.52E 83 4.34E 88 8.57E 81

~v Rv I

0

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 of Waste a.

Spent resin, Process filters Unit M3 Ci 6 Mo. Period 2.434 E+

5.803 E+2 'rror 8

2.0E+1 b.

Dry compressible Waste (Note 5)

M3 Ci 1.396 E+2 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 Metal (DAW)

(Note 6) 3.322 E-1 2.0E+1 2 ~

Estimate of Ma)or Nuclide Composition (By Type of Waste)

Category a ~

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

8.18E 1

6.42E-1 b.

CS 137 Co,60 Co 58 Fe 55 Cs 134 H

3 Ni 63 Nb 95 Mn 54 Zr 95 Cr 51 C 14 Ce 144 2.57E+1 2.44E+1 1.53E+1 1.07E+1 9.33E+o 5.84E+o 2 '3E+o 1.74E+o 1.42E+o 1 22E+o 7.90E 1

4.40E-1 3.80E 1

~ ~

I 1

e 1

Category Co Nuclides Fe 55 Mn 54 Co 58 Co 60 Ni 63 4.16E+1 2.19E+1 1.73E+1 1.61E+1 3.20E+o d 0 Co 60 Fe 55 Mn 54 Ni 63 Sb 125 CG 137 Co 58 8.28E+1 1.08E+1 3.28E+o 1.27E+o 4.79E-1 4.00E"1 3 46E-1 3.

Solid Waste Disposition Number of Shipments Mode of Transportation 38 Sole Use Truck Destination 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)

Waste Class Total Total Volume Curies Cubic Ft.

(Note 1)

Principal Radionuclides (Notes 1

a 2)

Type of Waste (Note 3)

Category Reg-Guide 1.21 Type of Container (Note 4)

Solidification A ent Class A

4932.50 1.48 NA PWR Compactible Trash (Note 5) l.b.

Non-Specification Strong Tight Package None Class A

774.10 3.32E-1 NA PWR Non-Compactible Trash (Note 6) l.d.

Non-Specification Strong Tight Package None Class B

Class C

531.90 83.4 114.43 91.53 Ni63, Sr90, Csl37 Co60, Ni63, Sr90, Csl37, Sum of Nuclides with T9

< 5 years PWR Ion-Exchange Resin PWR Ion-Exchange Resin l.a.

NRC Certified LSA

> Type A NRC Certified LSA

> Type A None None Class C

120.3 366.87 C14, Ni63,

Sr90, C137, Sum of Nuclides with T4

< 5 years PWR Ion-Exchange Resin l.a.

NRC Certified Type B

None Class C

120.3

=

7.43 Ni63 ~ Pu241 g

Sum of Nuclides with T4 5 years PWR Process Filters l.a.

NRC Certified Type B

None Class C

57.4 10,144.0

C14, Co60,

Ni63, Sum of Nuclides with T4

< 5 years PWR

.Incore Detectors 1.c.

NRC Certified Type B

None

I II

,Jki 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 Approved by C.

We RBvlsiotl~R6visw6d F R G Plant Manager Plant Manager 1982 7

19~8 197

> /~9 RM f rmz

/ ms I

t S

OPS I

I I

I I

I I

l t

I

'k IV

~,i

~

k

~

~

4 ~

L I 4

~ %

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

TAHLE 1.3 Page 12 of 88 NUCLIDE b~L 1978 UNDIZUHK) uCi/ml1 Mi (no units) 7

<<7

.6

<<7

-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

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

2.2 tl... l~

fran nable gaum in aizhozne releases to <500 mragyr - tatml body and <3000 Itu~yr - skin.

Technical Specificatian 3.3.3.10 zequires lg g

~

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

~l g

zates to the tatal body and skin~ noble gases in aizbozne zeleases.

'Ihe alarm'trip setpoints aze based an the dose rate calculations.

Ihe Technical Specificaticn IlX)'s ~ly to all aizborne releases on the site but all zeleases may be treated as if discharged fran a single release point.

Only those nable gases a~ring in Table G-2 willbe cansidezed.

'Ihe calculation amLhads

're based on Sections 5.1 and 5.2 of NUHE~133, Naveaher 3978.

'Ihe equations are:

Far 1UZAL BC'ose Rate:

K( (X/Q)

(Q COP}g Revd9 Por 'KRAAL SKIN Dose Rate~

n DRsj~

~

[Li + 1.1 Mi] (+Q)

(Q DOZ)i 3.

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 release rate (Q DVI')i to verify that the dose rate is within the

!1 b>>'

~

W~

~ilitp1 radionuclide di.~ibutian, a conservatism factor of 0.8 is introduced into the calculation.

'Ihe simplified equation is:

~ 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 ~~

allowable release to each of the release saurces.

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 body dose is more limiting than tbe caIculated st dose.

(Refer to AppauBx C for a detaLIed evaluaticn.)

Iheref(xe, the skin dose rate 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 folIowingoutline 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 if the actual reIeases ~ the vaIne of 3.S X 10 tKX/sec.

A.

3}a (2/(}) value sec/u scn}

ls the nose lfnftfc8sectnc 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

2.3 ST.

ZDCIE PZAÃZ CKMrSrRY OPEBATJ2G PBQCEIXRE NO. C-200, REVISION 10 OFFS DOSE CAICUIATI the Radioiodine

& Particulate Page 25 of 88 133, tritium ard all radionuclides in particulate form with half 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:

n

~I&SD&Z = 4 RfT (D/Q) (Q ~)i Tritium Releases Inhalat

~ Rev@9 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-ANNUALEFFLUENT 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....................

LIQUID EFFLUENTS:

~

~

~

~

~

~

7 Summation of all Releases

- Unit ¹ 1

Summation of all Releases Unit ¹ 2

Nuclide Summation by Quarter - Unit' Nuclide Summation by Quarter Unit ¹ Liquid Pathway Dose Unit ¹ 1

Liquid Pathway Dose - Unit ¹ 2

1 2

~

~

~

~

~

~

~

~

~

~

~

0

~

~

~

~

8 9

10 11 12 13 GASEOUS EFFLUENT:

Summation of all Releases Unit ¹ 1

Summation of all Releases Unit ¹ 2 Nuclide Summation by Quarter Unit ¹ Nuclide Summation by Quarter Unit ¹ Gaseous Pathway Dose Unit ¹ 1

Gaseous Pathway Dose Unit ¹ 2=......

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

1 2

14 15 16 17 18 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 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 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

1C$

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

Sampling 1

Sample Preparation 1

Sample Analysis 3

Release Volume 2

Total 9

5 5

5 10 5

30 NA 2

1 3

10 NA 5

5 10 15 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

~ ~

lf 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 Source Sampling Frequency Type of Analysis Method of Analysis Each Batch Principal Gamma Emitters

p. h. a.

Monitor Tank 1

Releases Continuous Releases Monthly Composite Quarterly Composite Daily Grab Samples Tritium Gross Alpha Sr-89, Sr-90,

& Fe-55 Principal Gamma Emitters

& I-13'1 for 4/M Composite Analysis Dissolved

& Entrained Gases One Batch/ Month Tritium Composite Monthly Alpha Composite Monthly Sr-89, Sr-90,

& Fe-55 Composite Quarterly L. S.

G. F. P.

C. S.

p. h. a.

p. h. a.

L'. S.

G. F. P.

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 Source Haste Gas Decay Tank Releases Sampling Frequency Each Batch Type of Analysis Principal Gamma Emitters Method of Analysis

p. h. a.

onta inment Purge Releases Each Purge Principal Gamma Emitters Tritium

p. h. a.

L. S.

Plant Vent 4/M Monthly Composite Quarterly Composite Prin'cipal Gamma Emitters Tritium Particulate Gross Alpha Particulate Sr-89 8c Sr-90

p. h. a.

L. S.

G. F. P.

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.

LUCIE UNIT 0 1

SEMIANNUAL REPORT DULY 1 s 1988 THROUGH DECEMBER 31 s

1988 EFFLUENT & NASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED) 5.

Batch Releases A

Liquid 2.

4 ~

5.

6.

Number of ba tc h releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for a batch release:

Minimum time period for a batch release:

Average dilution stream flow during the pet 1od e

4.0 18,865.0 minutes 800 minutes 563 minutes 140 minutes 889,306 gpm All liquid releases are summarized in tables B.

Gaseous 1.

Number of batch releases:

2.

Total time period for batch releases:

Maximum time period for a batch release:

4.

- Average time period for a batch release:

5.

Minimum time period for a batch release:

11 R

2, 506 minutes R

708 minutes 228 minutes R

1 minute R

All gaseous waste releases are summarized in tables 6.

Unplanned Releases A.

Liquid 1.

Number of releases:

2.

Total activity released:

0 0

Curies B.

Gaseous 1.

Number of re 1 eases:

2.

Total activity released:

0 0 Curies C.

See attachments (if applicable) for:

1.

2.

3

~

4 ~

A description of the event and equipment involved.

Cause(s) for the unplanned release.

Actions taken to prevent a recurrence.

Consequences of the unplanned release.

8

FLORIDA PONER

& LIGHT 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 2.

4, 5.

6.

Number of batch releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for a batch release:

Minimum time period for a batch release:

Average dilution stream flow during the period:

33.0 18,865.0 minutes 800 minutes 563 minutes 140 minutes 889,306 gpm All liquid releases are summarized in tables B.

Gaseous, 1.

2.

4 5.

Number of batch releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for a batch release:

Minimum time period for a batch release:

21 10,285 1,380 490 12 R

minutes R

minutes minutes R

minutes R

Al 1 gaseous waste releases are summarized in tables 6.

Unplanned Releases A.

Liquid 1.

Number of releases:

2.

Total activity released:

0 0

Curies B.

Gaseous 1.

Number of releases:

2.

Total activity released:

0 0 Curies C.

See attachments (if applicable) for:

2.

4 A description of the event and equipment involved.

Cause(s) for the unplanned release.

Actions taken to prevent a recurrence.

Consequences of the unplanned release.

4 V

V y

I V

V V

4 v=

4, ~

I I

V

+I '

v' 4

V

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 ORGAN Dose (mrem)

Noble Gas Exposure Dose in mrad Bone Liver Thyroid Kidney Lung Gi-LLI Total Body 4.75 E-06

6. 67'-04 2.32 E-03

2. 91 E-04

6. 62 E-04

6. 63 E-04 6.78 E-04 Gamma Air Dose 1.89 E-02 Beta Air Dose 3.69 E-02 8.

Offs 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.

LUCI E UNIT ¹ 1

SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECENBER 31, 1989 TABLE 3.3 1

LIQUID EFFLUENTS SUNNATION OF ALL RELEASES UNI T A.

Fission and Activation Products QTR¹3 QTR¹4 1.

Total Release (Not including Tritium, Gases, Alpha)

Ci

6. 81E-02

3. 28E-02 2.

Average Diluted Concentration During Period B.

Tritium uCi/ml 1.42E-10 6.47E-11 2 ~

Total Release Average Diluted Concentration During Period Ci UCl/ml

8. 45E 01 1. 38E 02 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 D.

Gross Alpha Radioactivity Total Release uCi/ml 1.41E-11

2. 58E-13 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 1 1 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 UNIT A.

Fission and Activation Products QTR¹3 QTR¹4 Total Release (Not including Tritium, Gases, Alpha) 2.

Average Diluted Concentration During Period B.

Tritium 1.

Total Release 2.

Average Diluted Concentration During Period C.

Dissolved and Entrained Gases uCi/ml Ci uCi/ml 6.75E-02 3.,00E-02

1. 43E-10

5. 92E-11 8.45E 01 1.38E 02 1.79E-07 2.72E-07 1.

Total Release

6. 65E-03 1. 31E-02 2.

Average Diluted Concentration During Period D.

Gross Alpha Radioactivity 1.

Total Release

= E.

Volume of Maste released (Prior to Dilution)

F.

Volume of Dilution Mater Used During Period h

uCi/ml Ci Liters Liters 1.41E-11

2. 58E-13 3.37E-05 5.90E-06 1.36E 06 1.37E 06 4.73E 11 5.07E 11 h

A 1.

il~

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 NUCLIDES RELEASED UNIT Con tinuous Mode QTR¹3 QTR¹4 Batch Mode QTR¹3 QTR¹4 NA-24 CR-51 MN-54 FE-55 CO-57

.CO-58 FE-59

'CO-60 AG-110 SN-113 SB-122 SB-124 NP-239 RB-88 SR-89 SR-90 ZR-95 NB-95 ZR-97 NB-97 TC-99M RU-103 SB-125 I-131 TE-132 I-132 I-133 CS-134 CS-137 CS-138 BA-140 LA-140 CE-141 CE-144 TOTAL FOR (ABOVE)

PERIOD Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 3.05E-04 O.OOE 00 O.OOE 00 O.OOE 00 8.95E-OS 2.49E-04 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE

0. OOE O.OOE O.OOE O.OOE 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 1.97E-03 O.OOE 00 O.OOE 00 O.OOE 00

3. 71E-04 4.38E-04 O.OOE 00 O.OOE 00 O.OOE O.OOE O.OOE 00 00 00 5.60E-05 4.77E-03 4.63E-04 1.30E-02 2.00E-05

8. 15E-03 a.03E-04 5.00E-03 7.55E-04 2.30E-04 6.50E-04 2.33E-03 O.OOE 00 2.65E-04 O.OOE 00 O.OOE 00 1.06E-03 2.02E-03 O.OOE 00 9.05E-04 6 ~ 1 SE-06 3.60E-05 7.65E-03 3.62E-04 2.74E-05 O.OOE 00

1. 71E-05 7.90E-03 1.09E-02 3.87E-05 O.OOE 00 1.26E-04 O.OOE 00 6.75E-04 3.74E-05 2.70E-03 3.04E-04 7.25E-03 1.22E-05 3.32E-03 1.31E-OS

4. 21E-03 6.45E-04 1.56E-04 4.00E-05 1.46E-03 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 3.55E-04 7.65E-04 O.OOE 00

8. 15E-04 6.45E-06 O.OOE 00 5.45E-03 5.90E-04 O.OOE 00 O.OOE 00 8.45E-05 8.00E-04

8. 15E-04 O.OOE 00 O.OOE 00 7.65E-05 O.OOE 00 O.OOE 00 6.44E-04 2.78E..03 6.75E-02 3.00E-02 AR-41 KR-BSM XE-131M XE-a XE-133M XE-135 Ci Ci Ci Ci Ci Ci O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE 00 00 00 00 00 00 O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE 00 00 00 00 00 00 3.26E-05 O.OOE 00 O.OOE 00 6.20E-03 O.OOE 00

.4.02E-04 3.23E-06 O.OOE 00, O.OOE 00 1.28E-02 O.OOE 00 3.22E-04 10

<<ko t' ~

f I J EÃ'

FLQR IDA PQNER Sr LIGHT COMPANY ST -

LUGIE,,UNIT ¹ 2 SEMIANNUAL REPORT JULY 1, 1989 THROUGH DECEMBER 31, 1989 TABLE 3.4 2 LIQUID EFFLUENTS NUCLIDEB RELEASED UNIT Continuous Mode QTR¹3

'QTR¹4 Batch QTR¹3 Mode QTR¹4 NA-24 CR-51 MN-54 FE-55 CO-57 CQ-58 FE-59 CO-60 AG-110 SN-113 SB-122 SB-124 NP-239 RB-88 SR-89 SR-90 ZR-95 NB-95 ZR-97 NB-97 TC-99M RU-103 SB-125 I-131 TE-132 I-132 I-133 CS-134 CS-137 CS-138 BA-140 LA-140 CE-141 CE-144 TOTAL FO (ABOVE)

R PERIOD Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE 0

OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 O.OOE 00 O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE

0. OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00

~

00 00 00 O.OOE.00 O.OOE 00 O.OOE 00 O.OOE 00 5.60E-05 4.77E-03 4.63E-04 1.30E-02 2.00E-05

8. 15E-03 1.03E-04 5.00E-03 7.55E-04 2.30E-04 6.50E-04 2.33E-03 O.OOE 00 2.65E-04 O.OOE 00 O.OOE 00 1.06E-03 2.02E-03 O.OOE 00 9.05E-04 6.15E-06 3.60E-05 7.65E-03 3.62E-04 2.74E-05 O.OOE 00 1.71E-05 7.90E-03 1.09E-02 3.87E-05 O.OOE 00 1.26E-04 O.OOE 00 6.75E-04 3.74E-05 2.70E-03 3.04E-04 7.25E-03 1.22E-05 3.32E-03 1. 31E-05

4. 21E-03 6.45E-04 1.56E-04 4.00E-05 1.46E-03 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 3.55E-04 7.65E-04 O.OOE 00 8.15E-04 6.45E-06 O.OOE 00 5.45E-03 5.90E-04 O.OOE 00 O.OOE 00 8.45E-05 8.00E-04

8. 15E-04 O.OOE 00 O.OOE 00 7.65E-05 O.OOE 00 O.OOE 00 6.75E-02 3.00E-02 AR-41 KR-85M XE-131M XE-133 XE-133M XE-135 Ci Ci Ci Ci Ci Ci O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE 00 00 00 00 00 00 O.OOE O.OOE O.OOE O.OOE O.OOE O.OOE 00 00 00 00 00 00 3.26E-05 O.OOE 00 O.OOE 00 6.20E-03 O.OOE 00 4.02E-04,,

3.23E-06 O.OOE 00 O.OOE 00 1.28E-02 O.OOE 00 3.22E-04 11

I Sg

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 ORGAN Bone Liver Thyroid Kidney Lung GI-LLI Total Body Calendar Year Dose (mrem)

3. 29 E-02

1. 44 E-01

6. 49 E-03

1. 41 E-03

1. 66 E-01

1. 42 E-01

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 HELLFISH ORGAN Bone Liver Thyroid Kidney Lung GI-LLI Total Body Calendar Year Dose (mrem)

3. 28 E-02

1. 44 E-01

5. 35 E-03

1. 37 E-03

1. 66 E-01

1. 42 E-01

4. 00 E-02

i 1

e

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

-A, Fission and Activation Gases UNIT QTR03 QTR44

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 2.

Avg. Release Rate For Period C. Particulates

1. Particulates T 1/2 8 Days

2. Avg. Release Rate For Period

3. Gross Alpha Radioactivity D. Tritium 1, Total, Release 2.

Avg. Release Rate For Period 1.10E-03 6,53E-04 uCi/sec 1.38E-04 8.22E-05 2.30E-05 O.OOE 00 uCi/sec 2.89E-06 O.OOE 00 9.21E-08 1.15E-OV Ci

. 2.42E 02 3.48E 01 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 A. Fission and Activation Gases UNIT QTR¹3 QTR¹4

1. Total Release 2.

Avg. Release Rate For Period

b. Iodines

1. Total Iodine - 131 2.

Avg. Release Rate For Period C. Particulates

i. Particulates T 1/2 8 Days 2.

Avg. Release Rate For Period 3

~ Gross Alpha Radioactivity D. Tritium

1. Total Release

2. Avg. Release Rate For Period Ci 1.56E 02 8.38E 01 uCi/sec 1.96E 01 1.05E 01 3.50E-04 4.80E-04 uCi/sec 4.40E-05 6.04E-05 O.OOE 00 5.65E-05 uCi/sec O.OOE 00 7.11E-06 9.65E-08 1.26E-08 1.27E 01 1.06E 01 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 A. Fission and Activation Gases UNIT QTR¹3 QTR¹4

1. Total Release

2. Avg. Release Bate For Period

b. Iodines 2.07E 03 2.95E 03 uCi/sec 2.60E 02 3.71E 02

1. Total Iodine 131

2. Avg. Release Rate For Period Particulates

1. Particulates T 1/2 8 Days 2.

Avg. Release Bate For Period

3. Gross. Alpha Radioactivity 1.28E-02 1.88E-03 uCi/sec 1.61E-03 2.36E-04 0

~ OOE 00 0

~ OOE 00 uCi/sec O.OOE 00 O.OOE 00 1.81E-08 2.70E-07 D. Tritium

1. Total Release 2.

Avg. Release Rate For Period Ci 1.72E 01 1.93E 01 R

uCi/sec 2.16E 00 2.43E 00 R

'I I w> y e <

WkA I

'"; lie AL V

k 4

'gt

~IJ f

l H

R

(

II k

4 lt h

H ll I

f I

~t I' p

a w

w n

'I t

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 Released Unit.

Continuous Mode QTR53 QTR04 Batch Mode QTB03 QTB04

1. Fission Gases AB-41 KR-85 KR-85M KB-87 KR-88 XE-131M XE-133 XE-133M XE-135 XE-135M XE-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE 00 O.OOE 00 8.57E 00 O.OOE 00 3.91E 00 O.OOE 00 7.27E 02 3.32E 00 8.66E 01 O,.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 1.53E 01 O.OOE 00

'.01E 00 O.OOE 00 1.45E 03 6.71E 00 1.90E 02 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 2.47E-02 O.OOE 00 O.OOE 00 2 '0E-01 2.90E 01 5.43E-01 2.10E-01 O.OOE 00 O.OOE 00 O.OOE 00 00, O.OOE 00 O.OOE 00 0

~ OOE 00 O.OOE 00 O.OOE 00 O.OOE 00, O.OOE 00 O.OOE 00 O.OOE 00 TOTAL FOR PERIOD

2. Iodines Ci 8.29E 02 1.67E 03 3.00E Oi O.OOE 00 I-131 I-132.

I-133 I-134 I-135 Ci Ci Ci Ci Ci 1,10E-03 4.43E-03 6.42E-03 O.OOE 00 O.OOE 00 6.53E-04 O.OOE 00 4.71E-03 O.OOE 00 O,OOE 00 TOTAL FOR PERIOD

3. Particulates SR-89 SR-90 Y-90 Ci Ci Ci Ci 1.20E-02 5.36E-03 1.49E-05 O.OOE 00 4.03E-06 O.OOE 00 4.03E-06

. O.OOE 00

D C'e de lt pl 4%

~

'+

Sg

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 Released Unit Continuous Mode QTR¹3 QTR¹4 Batch Mode QTR¹3 QTR¹4

1. Fission Gases AR-41 KR-85

-'KR-85M KR-87 KR-88 XE-131M XE-133 XE-133M XE-135 XE-135M XE-137

.- XE-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE 00 O.OOE 00 1.71E 00 O.OOE 00 O.OOE 00 O.OOE 00 1.11E 02 Q.OOE 00 2.60E 01 O.OOE 00 0;OOE 00 0;OOE 00 O.OOE 00 O.OOE 00 2.67E-01 O,OOE 00'.OOE00 O.OOE 00 4.21E 01 O.OOE 00 6.71E 00 O.OOE 00 O.OOE 00 O.OOE 00 3.68E-01 O.OOE 00 3.07E-02 3.84E-03 3.48E-02 2,29E-01 1.57E 01 1.83E-01 4 '6K-01 0

~ OOE 00 2.10E-02 O.OOE 00 4,32E-01 3.57E-01 6.35E-02 6.83E-03 6.40E-02 3.50E-01 3.15E 01 4.44E-01 1.45E 00 O.OOE 00 O.OOE 00 O.OOE 00 TOTAL FOR PERIOD

2. Iodines Ci 1.39E 02 4.91E 01

1. 70E 01

3. 47E Oi I-131 I-132 I-133 I-134 I-135 Ci Ci Ci Ci Ci 3.50E-04 O.OOE 00 6.59E-04 O.OOE 00 O.OOE 00 4.80E-04 O.OOE 00 2.07E-03 O.OOE 00 O.OOE 00 TOTAL FOR PERIOD

3. Particulates SR-89 SR-90 Y-90 Tc-99M Ci Ci Ci Ci Ci 1.01E-03 2.55E-03 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 O.OOE 00 5.65E-05 17

r

~ $

NO gt goal 4.

=P

't

~ I

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 PATHWAY BONE mrem LIVER mrem THYROID KIDNEY 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 PATHWAY LUNG mrem GI-LLI T.

BODY 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)

TOTAL

2. 02 E-03

2. 02 E-03

2. 03 E-03

7. 12 E-03

7. 15 E-03

7. 46 E-03 (A)-Sector:

SE (B)-Sector WNW Range:

Range:

1. 50 miles

3. 75 miles (Actual Goat)

NOBLE GASES Gamma Air Dose Beta Air Dose Sector SE CALENDAR YEAR (mrad) 4.68 E-02

9. 76 E-02 Range:

1.50 miles 18

i 4

F>>

ga h =q

~4v

~

4 I4%

k f&l

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 PATHWAY BONE mrem LIVER mrem THYROID KIDNEY 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 PATHWAY LUNG mrem GI-LLI mrem T.

BODY 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 (A)-Sector:

SE (B)-Sector WNW

1. 79 E-03

1. 82 E-03

2. 22 E-03 Range:

1.50 miles Range:

3.75 miles (Actual Goat)

NOBLE GASES Gamma Air Dose Beta Air Dose Sector SE CALENDAR YEAR (mrad)

.2. 78 E-02

4. 80 E-02 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 ~

b.

c ~

d.

Spent resin, Process filters Dry Compressible Waste (Note 5)

Irradiated Components Other

1. Non-Compres" sible Metal (DAW) (Note 6)

M3 Ci M3 Ci M3 Ci M3

-Ci 3.546 E+1 S.S9O E+1 9.813 E+1 5.701 E

1 3.119 E+1 5.284 E

1 2.O E+1 0 E+1 2.O E+1 2.O E+1 2.

Estimate of Major Nuclide Composition (By Type of Waste)

Category a ~

Nuclides Cs 137 Co 60 Cs 134 Ni 63 Co 58 Fe 55 Sb 125 Sb 122 Mn 54 H 3 3 57 E+1 1.59 E+1 1.S7 E+1 1.OS E+1

9. 91 E~

5.05 E+0 2.85 E+0 1.18 E+0 1.10 E+0 1.08 E+0 b.

H 3 Co 60 Cs 137 Cs 134 Fe 55 Co 58 Ni 63 Ce 144 Sb 125 Zr 95 Mn 54 3.45 E+1 2.11 E+1 1.88 E+1 6 ~ 12 E~

5.96 E+0 4.77 E+0 2.46 E~

2.09 Eo 1.01 E+0 8.09 E

1 7.o6 E"1 20

t i

+C 0

A.

2.

Estimate of Ma)or Nuclide Composition (By Type of Waste)

(continued)

Category Nuclides

.CD d ~

N/A Co 60 Cs 137 Fe 55 Cs 134 Ni 63 Mn 54 Co 58 N/A 4.11 E+1 2.58 E+1 1.52 E+1 9.91 E+0 3.87 E+0 1.84 E+0 1.54 E+0 3.

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

Number of Shipments 0

Mode of Transportation N/A Destination N/A N/A Not Applicable 21

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

Waste Class Total Total Principal Type of Vol[me Curies Radionuclides Waste Cubic Ft.

(Rote 1)

(Notes 1 0 2)

(Rote 3)

Category Rag&aide 1.21 Type of Container (Rote 4)

Solldificatior.

Agent

~ Class A

Class A

3465.5 1101.4 5.701 E-l 5 284 B 1 NA NA PWR Compactible Trash (Note 5)

PWR Non-Compactible Trash (Nota 6) l.b.

l.d.

No'n-Specification Strong Tight Package Non-Specification Strong Tight Package None None ClasS A

926.2 3.95 Cs 137, Hi 63 PMR Ion-Exchange Resin

).a.

NRC Certified LSA T

A None Class 8

326.1 51.95 Cs 137, Sr 90, Ni 63, PU 24li TRU PWR Ion Exchange Resin l.a.

NRC Certified LSA T

A Nona

l la'}

q El C.

t lz

~4 v~

gr*

tl lg

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

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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.

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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

ao l

'\\$ll A

f

'I ~

o a.

b.

C.

d.

e.

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

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

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

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~

AOHINISTRATIVE CONTROLS 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:

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

p C0 4