ML17348A891

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Semiannual Radioactive Effluent Release Rept Jul-Dec 1990. W/910226 Ltr
ML17348A891
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 12/31/1990
From: Plunkett T, Quinn S, Steinke R
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-91-063, L-91-63, NUDOCS 9103060077
Download: ML17348A891 (39)
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Text

..'ACCELERATED DISTRIBUTION DEMONS"AMTION SYSTEM 1 ~

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9103060077 DOC.DATE: 90/12/31 NOTARIZED: NO DOCKET' FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION PLUNKETT,T.F. Florida Power & Light Co.

QUINN,S. Florida Power & Light Co. R STEINKE,R.N. Florida Power & Light. Co.

RECIP.NAME RECIPIENT AFFILIATION I D

SUBJECT:

"Semiannual Radioactive Effluent Release Rept Jul-Dec 1990."

W/910226 ltr.

DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.36a(a)(2) Semiannual Effluent Release Reports NOTES:

RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 3 3 PD2-2 PD 1 1 AULUCK,R 1 1 INTERNAL: AEOD/DSP/TPAB 1 1 IRM D 1 1 NRR/DREP/PRPB11 2 2 R ICE ' 1 1 RES BROOKSgB 1 1 RG RSS/RPB 2 2 RGN2 FILE 02 1 1 EXTERNAL: BNL TICHLER,J03 1 1 EG&G SIMPSON,F 2 2 NRC PDR 1 1 R

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NOTE TO ALL "RIDS" RECIPIENTS:

S PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LINIS FOR DOCUMENTS YOU DON T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 18

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.. Box 029100, Miami,

~ FL,~ 33102-9100 FEB 26 1991 L-91-063 10 CFR 50.36(a)(2)

Tech. Spec. 6.9.1.4 U. S. Nuclear Regulatory Commission ATTN: Document, Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Semi-Annual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of July 1, 1990, through December 31, 1990, for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.1.4 and 10 CFR 50.36(a)(2).

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

Very truly yours, T. F. Plunkett Vice President Turkey Point Plant Nuclear TFP/DPS/ds Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 9i03060077 90i23i PDR ADOCK 05000250 R PDR an FPL GrouP comPany gl pi

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TURKEY POINT PLANT UNITS 3 At'& 4 SEMIS'AJAL RADIOACTIVEEFFLUENT RELEASE REPORT JULY 1990 THROUGH DECEMBER 1990 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TUIMEYPOINT PLANT FLORIDA POWER AND LIGHT COMPANY

. Quinn Radiochemist R. N. Steinke Chemistry Supervisor V. A. Kaminskas Operations S erintendent

. W. Pearce Plant Manager-Nuclear RADIOQIEM DlsC(l99I)

J P~AE 1.0 Regulatory Limits 1.1 Liquid Effluents ............................ ~....... 1 1.2 Gaseous Effluents ................................... 1 2.0 Maximum Permissible Concentration ............................ 2 3 .0 Average Energy ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2 4.0 Measurements and Approximations of Total radioactivity 4.1 Liquid Effluents - Discussion ................... ~........ 2

a. Unit 3 Liquid Effluents Summation .................... 7
b. Unit 4 Liquid Effluents Summation ................... 14 4.2 Gaseous Effluents - Discussion ..................... .. .. ~ ~ 3
a. Unit 3 Gaseous Effluents Summation .................. 10
b. Unit 4 Gaseous Effluents Summation ~................, 17 4.3 Estimate of Errors ~............ ~............ ~........ 3 5.0 Batch Releases 5 ~ 1 LlquNl ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 5 2

~ Gaseous ........... .................... ........

~ ~ 4 6.0 Unplanned Releases ...................................... 5 7.0 Reactor Coolant Activity ~......... ~................. ~ . ~.... 5 8.0 Site Radiation Dose ...................................... 5 9.0 Offsite Dose Calculation Manual Revisions ........................ 6 10.0 Solid Waste and Irradiated Fuel Shipments ........................ 6 11.0 Process Control Program Revisions .........,......,....... ~.... 6

IDA POWER AND LIGHT CO Y POINT UNITS 3 AND EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT SUPPLEMENTAL INFORMATION JULY 1990 THROUGH DECEMBER 1990 1.0 ~U l.l ~ii ffl a) The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentration specified in 10CFR20 Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall not exceed 2.0 E-04 pCi/ml.

b) The dose or dose commitment per reactor to a member of the public from any radioactive materials in liquid effluent released to unrestricted areas shall be limited, during any calendar quarter, to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and, during any calendar year, to less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ.

1.2 Gaseou Effluent a) The dose rate due to radioactive materials released in. gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin due to noble gases and less than or equal to 1500mrem/year to any organ due to I-131, I-133, tritium and for all radioactive materials in particulate form with half lives greater than 8 days.

b) The air dose per reactor to areas at and beyond the site boundary due to noble gases released in gaseous effluents shall be limited, during any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, during any calendar year, to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

c) The dose per reactor to a member of the public, due to I-131, I-133, tritium and to particulates with half-lives greater than 8 days in airborne effluents released to areas at and beyond the site boundary shall not exceed 7.5 mrem to any organ during any calendar quarter and shall not exceed 15 mrem to any organ during any calendar year.

2.0 xim m Permi ncn in Water: As per 10CFR20, 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 3.0 The average energy of fission and activation gases in effluents is not applicable.

4.0 Meas remen n A r xim ti n fT 1Ra i activit All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Specification requirements. The minimum frequency of analysis as required by Regulatory Guide 1.21 was met or exceeded.

Where alpha, tritium and named nuclides are shown as curies, this should be interpreted as "no activity was detected on the samples using the Plant Technical Specification analyses techniques to achieve required Lower Level of Detection (LLD) sensitivity for radioactive effluents".

4. I ~ii ffl Aliquots of representative pre-release samples were isotopically analyzed for gamma emitting isotopes on a multichannel analyzer.

The above procedure was followed for all releases from the waste disposal system.

Frequent periodic sampling and analysis were used to conservatively determine if any radioactivity was being released via the steam generator blowdown system and the storm drain system.

Monthly and quarterly composite samples for the waste disposal system were prepared to give proportional weight to each liquid release made during the designated period of accumulation. The monthly composite was analyzed for tritium and gross alpha activity.

Tritium was determined by use of liquid scintillation techniques and gross alpha radioactivity was determined by use of a 2n gas flow proportional counter and a solid state scintillation system. The quarterly composite was analyzed for Sr-89/90 and Fe-55 by chemical separation.

Allradioactivity concentrations determined from analysis of a pre-release composite were multiplied by the total represented volume of the liquid waste released to determine the total quantity of each isotope and of gross alpha activity released during the compositing period.

Aliquots of representative pre-release samples from the waste disposal system were analyzed on a per release basis for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released in order to estimate the total dissolved gases released.

The liquid waste treatment system is shared by both units at the site and generally all liquid releases are allocated on a 50/50 basis to each unit.

4.2 Eft n Airborne releases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and releases incidental to operation of the plant. The techniques employed in determining the radioactivity in airborne releases are:

a) Gamma spectrum analysis for fission and activation gases, b) Removal of particulate material by filtration and subsequent gamma-spectrum analysis, Sr-89/90 determination and gross alpha analysis, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma-spectrum analysis, and d) Analysis of water vapor in a gas sample for tritium using liquid scintillation techniques.

All gas releases from the plant which were not accounted for by the above methods were conservatively estimated as curies of Xe-133 by use of the SPING-4 radiation monitor and the plant vent process monitor recorder chart and the current calibration curve for the monitor.

Portions of the gas waste treatment system are shared by both units and generally all gas releases from the shared system are allocated on a 50/50 basis to each unit.

Meteorological data for the period January 1990 to December 1990, in the form of Joint Frequency Distribution Tables is maintained on-site.

4.3 timate f Err r a) Sampling Error The error associated with volume measurement devices, flow measuring devices, etc., based on calibration data and design tolerances has been conservatively estimated to be collectively less than + 10%.

b) Analytical Error Our quarterly Q.C. cross-check program involves counting unknown samples provided by an independent external lab. The errors associated with our analysis of these unknown samples, and reported to us by the independent lab, were used as the basis for deriving the following analytical error terms.

Nuli eT A E Mxim mErr r Liquid Gaseous +10

5.0 5.1 ~Lt uid licit 4 a) Number of batch releases ~17 E+ 2 ~17 E+ 2 b) Total time period of batch releases, ~14 E+ 4 ~14 E+ 4 minutes c) Maximum time period for a batch ~14 E+ 2 ~14 E+ 2 release, minutes d) Average time period for a batch ~12 E+ 1 ~12 E+ 1 release, minutes e) Minimum time period for a batch ~g E+OQ ~00 E+0 release, minutes

1) Average stream flow during period 9 42~E+ 5 ~42 E+0 of release of effluent into a flowing stream, LPM 5.2 g~a~u ~ni '3 gni~4 a) Number of batch releases 2~0E+ 1 2rt0 E+01 b) Total time period of batch releases, ~11 E+ 3 2~57 E+0 minutes c) Maximum time period for a batch 2~40 E+ 2 2~40 E+ 2 release, minutes d) Average time period for a batch 4 991E+ 1 gJ)fr E~+1 release, minutes e) Minimum time period for a batch 2~0E+ 1 2~0E+ 1 release, minute

6.1 ~Li uid grani4 a) Number of releases b) Total activity released, curies 6.2 Qggggyg a) Number of releases b) Total activity released, curies 6.3 See Attachment 1, if applicable, for:

a) A description of the event and equipment involved.

b) Cause(s) for the unplanned release.

7.0 React r lant A tivi 7.1 gnat Reactor coolant activity limits of 100/E-Bar and 1.0 pCi/gm Dose Equivalent I-131 were not exceeded.

7.2 @nit 4 Reactor coolant activity limits of 100/E-Bar and 1.0 pCi/gm Dose Equivalent I-131 were not exceeded.

8.0 Site Radiati n D e The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary assumes a visitor was on-site at the "Red Barn" recreational area for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> a day, 2 days each week of the year, receiving exposure from both units at Turkey Point. The "Red Barn" is located approximately 0.39 miles NNE of the plant site.

Specific activities used in these calculations are the sum of activities in Unit 3, table 3 and Unit 4, Table 3. These dose calculations were made using historical meteorological data.

VISITOR DOSE SUMMATION JANUARY 1990 THROUGH DECEMBER 1990 UNITS 3 AND 4 Age Group: Adult I~nhalati n Bone D~

Location: Red Barn 3.59 E-07 Liver 1.63 E-04 Thyroid 3.11 E-04 Kidney 1.63 E-04 Lung 1.64 E-04 GI-LLI 1.63 E-04 Total Body 1.63 E-04 NOBLE GAS EXPOSURE Gamma Air Dose 1.19 E-03 mRads Beta Air Dose 3.31 E-03 mRads 90 ff ieD 1 1 inMn 1Reviin There were no ODCM revisions during this reporting period.

10.0 olid Wa te and Irradiated F el Shi ments No irradiated fuel shipments were made from the site. Common solid waste from Turkey Point Units 3 and 4 were shipped jointly. A summation of these shipments is given in Table 6 (pg. 21) of this report.

11.0 Pr e ntr I Pr m R visi n There were no changes to the process control program during this reporting period.

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FLORIDA POWER dk LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JUNE 1990 THROUGH DECEMBER 1990 LIQUID EFFLUENTS - SUM'NATION OF ALL RELEASES UNIT 3 TABLE 1 Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release(not including tritium, gases, alpha) Ci 2.76 E-02 2.09 E-02
2. Average diluted concentration during period pCi/ml 6.16 E-10 6.63 F 10 B. Tritium
1. Total Release Ci 7.85 K+01 7.65 E+01
2. Average diluted concentration during period pCi/ml 1.75 E-06 2.43 Ei-06 C. Dissolved and Entrained Gases
1. Total Release Ci 7.25 E-03 1.31 E-02
2. Average diluted concentration during period pCi/ml 1.62 E-10 4.16 E-10 D. Gross Alpha Radioactivity
1. Total Release Ci (2.22 E-08~ (5.73 E-08>>

E. Volume of Batch Waste Released (prior to dilubon) Liters 1.66 E+06 1.71 E+06 F. Volume of Continuous Waste Released (prior to dilution) Liters G. Volume of Dilution Water Used During Period Liters 4.48 K+10 3.15 E+10

  • MDAValues in pCi/ml.

FL A POWER & LIGHT COMP TURKEY POINT PLANT JULY 1990 THROUGH DECEMBER 1990 LIQUID EFFLUENTS-SUMMATION OF ALLRELEASES UNIT 3 TABLE 2 Continuous Mode Batch Mode Nudides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Cr-51 Ci 1.05 E-05 1.00 E44 Mn-54 Ci 8.65 E43 5.60 E-03 Fe-55 Ci 5.05 E43 5.15 E-03 Co-58 Ci 5.65 E-03 1.28 E43 Co40 Ci 6.80 E-03 5.10 E-03 Sr49 Ci Sr-90 Ci Nb-95 Ci 1.58 E-05 1.33 E46 Zr-97 Ci 4.40 E47 AQ-110 Ci 2.78 E44 4.48 E44 Sb-124 Ci 1.83 E45 2.31 E-04 Sb-125 Ci 4.31 E44 2.47 E43 I-131 Ci 1.77 E45 9.75 E46 I-133 Ci 5.40 E46 Cs-134 Ci 1.51 E44 1.15 E44 Cs-137 Ci 5.15 E44 3.35 E44 La-140 Ci 5.75 E46 1.64 E45 Ce-144 Ci 3.68 E-06 Unidentified Ci Total for period Ci 2.76 E42 2.09 E42

1 f

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A POWER & LIGHT COMPAt TURKEY POINT PLANT SEMIANNUALREPORT JULY 1990 THROUGH DECEMBER 1990 LIQUID EFFLUFATS UNIT 3 TABLE 2 (Continued)

Liquid Dissolved Gas Continuous Mode Batch Mode Nudides Released Units Quarter 3 Quarter 3 Quarter 4 Ci Xe-131m Ci Xe-133 Ci 7.25 E43 1.31 E42 Xe-133m Ci Xe-135 Ci Xe-135m Ci Total for Period Ci 7.25 E-03~ 1.31 E-02 LIQUID EFFLUENTS-DOSE SUMMATION JANUARY 1990 THROUGH DECEMBER 1990 UNIT 3 Age Group: Teenager Location: Cooling Canal Shoreline Deposition Dose (mRem)  % of Annual limit Total Body 1.43 E43 4.77 E-02

FLORIDA POWER & LIGHT COMPANY TURNKEY POINT PLANT SEMIANNUALREPORT JUNE 1990 THROUGH DECEMBER 1990 GAS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 3 TABLE 3 Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release Ci 1.14 E+02 5.27 E+01
2. Average Release Rate for Period pCi/sec 1.43 E+01 6.63 E+00 B. Iodines
1. Total Iodine-131 Ci 1.96 E-04 3.68 E-05
2. Average Release Rate for Period pCi/sec 1.21 E-05 4.63 E-06 C. Particulates
1. Particulates T-1/2) 8 days Ci 1.19 E-05 1.49 E-06
2. Average Release Rate for Period pCi/sec 1.50 E-06 1.87 E-07
3. Gross Alpha Radioactivity Ci (5.74 E-164 (1.92 E-154 D. Tritium
1. Total Release Ci 1.11 K+01 6.69 E+00
2. Average Release Rate for Period pCi/sec 1AO E+00 8.42 E-01
  • MDAValues in pCi/ml.

10

A POWER 4 LIGHT COMPAi TURKEY POINT PLANT SEMIANNUALREPORT JULY 1990 THROUGH DECEMBER 1990 GASEOUS EFFLU1<2TTS UNIT 3 TABLE 4 A. Fission Gases Continuous Mode Batch Mode Nudides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Ar<1 Ci 2.19 E-01 5.27 E-01 1.23 E41 Kr-85 Ci 3.76 E-04 Kr-85m Ci 2.83 E-05 1.19 E43 Kr-87 Ci Xe-131m Ci 6,39 E+00 7.58 E42 4.44 E42 1.34 E-01 Xe-133 Ci 1.03 E+02 3.09 E+01 2.91 E+00 1.62 E+01 Xe-133m Ci 2.44 E43 1.36 E42 2,27 E42'.10 E41 Xe-135 Ci 3.18 E41 3.96 E+00 5.84 E43 5.51 E41 Xe-135m Ci Total for Period Ci 1.10 E+02 3.55 E+01 3.98 E+00 1.72 E+01 B. Iodines Continuous Mode Nudides Released Units Quarter 3 Quarter 4 Br-82 Ci 6,30 E45 3.47 E45 I-131 Ci 1.95 E44 3.68 E45 I-133 Ci 2.46 E-04 5.55 E4l6 Total for Period Ci 5.04 E4l4 7.71 E-05 11

FLORIDA POWER & LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1990 THROUGH DECEMBER 1990 GASEOUS EFFLUENTS UNIT 3 TABLE 4 (Continued)

C. Particulates Continuous Mode Nudides Released Units Quarter 4 Co-58 Ci 1.49 E-06 I-131 Ci 1.37 E-06 Cs-134 Ci 4.05 E46 Cs-136 Ci 9.45 E-07 Cs-137 Ci 5.50 E46 Cs-138 Ci 3.41 E49 Ci Ci Total for Period Ci 1.19 E-05 1.49 E-06 12

FLORIDA POWER & LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1990 THROUGH DECEMBER 1990 UNIT 3 TABLE 5 DOSES DUE TO IODINE, H3, AND PARTICULATES PATHWAY BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY Cow milk-Infant: 2.09 E-04 5.95 E-04 7.16 E-02 2.08 E-04 3.48 E-04 3.54 E-04 4.77 E-04 Fruit & Veg-Fresh 8.59 E-06 4.28 E-04 3.11 E-03 4.31 E-04 4.16 E-04 4.21 E-04 4.24 E-04 Ground Plane 1.99 E-05 1.99 E-05 1.99 E-05 1.99 E-05 1.99 E-05 1.99 E-05 2.33 E-05 1.99 E-05 Inhalation-Adult 4.07 E-07 1.57 E-04 3.31 E-04 1.57 E-04 1.57 E-04 1.56 E-04 1.56 E-04 Unit Totals 2.38 E-04 1.20 E-03 7.51 E-02 8.16 E-04 9.41 E-04 9 '1 E-04 2.33 E-05 1.08 E-03 (mRem)

% Annual Limit 1.59 E-03 8.00 E-03 5.01 E-Ol 5.44 E-03 6.27 E-03 6.34 E-03 1.55 E-04 7.20 E-03 DOSE NOBLE GASES Gamma Air Dose Beta Air Dose

FLORIDA POWER & LIGHT COMPANY TURKEY POINT PLANT SEMIANI'AJALREPORT JUNE 1990 THROUGH DECEMBER 1990 LIQUID EFFLUENTS - SUMIUIATIONOF ALL RELEASES UNIT 4 TABLE 1 Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release(not including tritium, gases, alpha) Ci 2.76 E-02 2.09 E-02
2. Average diluted concentration during period pCi/ml 6.16 E-10 6.63 E-10 B. Tritium
1. Total Release Ci 7.85 K+01 7.65 E+01
2. Average diluted concentration during period pCi/ml 1.75 E-06 2.43 E-06 C. Dissolved and Entrained Gases
1. Total Release Ci 7.25 F 03 1.31 E-02
2. Average diluted concentration during period pCi/ml 1.62 E-10 4.16 E-10 D. Gross Alpha Radioactivity
1. Total Release Ci (2.22 E-08~ (5.73 E48~

E. Volume of Batch Waste Released (prior to dilution) Liters 1.66 E+06 1.71 E+06 F. Volume of Continuous Waste Released (prior to diiution) Liters G. Volume of Dilution Water Used During Period Liters 4.48 E+10 3.15 E+10

  • MDAValues in pCi/ml.

14

F A POWER & LIGHT COMP TURKEY POINT PLANT JULY 1990 THROUGH DECEMBER 1990 LIQUID EFFLUEN'rS-SUM14IATION OF ALLRELEASES UNIT 4 TABLE 2 Continuous Mode Batch Mode Nudides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Cr-51 Ci 1.05 E45 1.00 E44 Ci 8.65 E48 5.60 E-03 Fe-55 Ci'i 5.05 FA3 5.15 E-03 Co-58 5.65 E43 1.28 E43 CWO Ci 6.80 E43 5.10 E03 Sr-89 Ci Sr-90 Ci Nb-95 Ci 1.58 E45 1.33 E06 Zr-97 Ci 4AO E47 AQ-110 Ci 2.78 E-04 4A8 E44 Sb-124 Ci 1.83 B05 2.31 E-04 Sb-125 Ci 4,31 E44 2.47 E43 I-131 Ci 1.77 E45 9.75 E46 I-133 Ci 5.40 E46 Cs-134 Ci 1.51 E44 1.15 E-04 Cs-137 Ci 5.15 E-04 3.35 E04 La-140 Ci 5.75 E46 1.64 E45 Ce-144 Ci 3.68 E46 Unidentified Ci Total for period Ci 2.76 E42 2.09 E02 15

RIDA POWER & LIGHT COMP TURKEY POINT PLANT SEMIANNUALREPORT JULY 1990 THROUGH DECEMBER 1990 LIQUID EFFLUENTS UNIT 4 TABLE 2 (Continued)

Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Ci Xe-131m Ci Xe-133 Ci 7.25 E43 1.31 E42 Xe-133m Ci Xe-135 Ci Xe-135m Ci Total for Period Ci 7.25 E-03 1.31 E42 LIQUID EFFLUENTS-DOSE SUMMATION JANUARY 1990 THROUGH DECEMBER 1990 UNIT 4 Age Group: Teenager Location: Cooling Canal Shoreline Deposition Dose (mRem)  % of Annual limit Total Body 1.43 E-03 4.77 E-02 16

FLORIDA POWER 4 LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JUNE 1990 THROUGH DECEMBER 1990 GAS EFFLUENTS-SUM'NATION OF ALLRELEASES UNIT 4 TABLE 3 Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release Ci 1.06 E+02 6.26 E+01
2. Average Release Rate for Period pCi/sec 1.33 E+01 7.88 E+00 B. Iodines
1. Total Iodine-131 Ci 1.96 E-04 3.68 E-05
2. Average Release Rate for Period pCi/sec 1.21 E-05 4.63 E-06 C. Particulates
1. Particulates T-1/2>8 days Ci 1.19 E-05 1.49 E-06
2. Average Release Rate for Period pCi/sec 1.50 E-06 1.87 E-07
3. Gross Alpha Radioactivity Ci (5.74 E-16>> (1.92 E-15>>

D. Tritium

1. Total Release Ci 6.95 E+00 5.85 E+00
2. Average Release Rate for Period pCi/sec 8.74 E-01 7.36 E-01
  • MDAValues in pCi/ml.

17

RIDA POWER & LIGHT COMPAt TURKEY POINT PLANT SEMIANNUALREPORT JULY 1990 THROUGH DECEMBER 1990 GASEOUS EFFLMi22lTS UNIT 4 TABLE 4 A. Hssion Gases Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 3 Quarter 4 Areal Ci 2A6 E-01 1.81 E41 1.61 E4l1 2.69 E42 Ci 3.76 E-04 1.15 E-03 Kr-85m Ci 4,57 E43 1.84 E43 2.04 E-02 3.24 E-03 Ci 1.01 E-03 Xe-131m Ci 4,92 E42 6.54 E42 1.46 E-01 3.40 E41 Xe-133 Ci 9.24 E+01 3.19 E+01 1.17 E+01 2.56 E+01 Xe-133m Ci 4.28 E42 4.06 E42 1A6 E41 2.91 E-01 Xe-135 Ci 3.77 E41 3.97 E+00 3.10 E-01 1.32 E41 Xe-135m Ci Total for Period Ci 9.31 E+01 3.62 E+01 1.25 E+01 2.64 E+01 B. Iodines Continuous Mode Nuclides Released Units Quarter 4 Br-82 Ci 6.30 E-05 3.47 E-05 I-131 Ci 1.95 E-04 3.68 E45 I-133 Ci 2.46 E44 5.55 E46 Total for Period Ci 5.04 E-04 7.71 E45 18

~ I, RIDA POWER & LIGHT COMPAt TURKEY POINT PLANT SEMIANNUALREPORT JULY 1990 THROUGH DECEMBER 1990 GASEOUS EFFLVENTS UNIT 4 TABLE 4 (Continued)

C. Particulates Continuous Mode Nudides Released Units Quarter 3 Quarter 4 Co-58 Ci 1.49 E-06 I-131 Ci 1.37 E46 Cs-134 Ci 4.05 E46 Cs-136 Ci 9.45 E47 Cs-137 Ci 5.50 E46 Cs-138 Ci Ci Ci Total for Period Ci 1.19 E45 1.49 E-06 19

FLORIDA POWER & LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1990 THROUGH DECEMBER 1990 UNIT 4 TABLE 5 DOSES DUE TO IODINE, H3, AND PARTICULATES PATHWAY BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY Cow milk-Infant 9.64 E-05 3.69 E-04 2.87 E-02 1.34 E-04 2.55 E-04 2.56 E-04 3.06 E-04 Fruit & Veg-Fresh 4.78 E-06 3.11 E-04 1.39 E-03 3.11 E-04 3.04 E-04 3.07 E-04 3.09 E-04 Ground Plane 1.91 E-05 1.91 E-05 1.91 E-05 1.91 E-05 1.91 E-05 1.91 E-05 2.24 E-05 1.91 E-05 Inhalation-Adult 1 89

~ E-07 1.14 E-04 1.86 E-04 1.14 E-04 1.15 E-04 1.14 E-04 1.14 E-04 Unit Totals 1.20 E-04 8.13 E-04 3.03 E-02 5.78 E-04 6.93 E-04 6.96 E-04 2.24 E-05 7.48 E-04 (mRem) t Annual Limit 8.00 E-04 5.42 E-03 2.02 E-Ol 3.85 E-03 4.62 E-03 4.64 E-03 1.49 E-04 4.99 E-03 DOSE NOBLE GASES Gamma Air Dose 4.26 E-03 mRad Beta Air Dose 1.17 E-02 mRad 20

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1990 THROUGH DECEMBER 1990 UNITS 3 AND 4 TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. TYPE OF WASTE 6 MONTH PERIOD
a. Spent resin, filters m 1.91 E1 sludge, evaporator bottoms Ci 3.86 E2 20 b.

c.

Dry Compressible waste (note 1)

Irradiated components Control rods, etc.

m'.

m3 Ci Ci 5.27

1. 08 00 0.00 El E1 EO EO 20
d. Other non-compressible m 8.10 EO Waste (Note 2) Ci 3.01 E-2 20 2 ~ ESTIMATE OF MAJOR NUCLIDE COMPOSITION BY TYPE OF WASTE a ~ Co-60 69 Ni-63 20 Cs-137 6 Fe-55 2 Cs-134 1 Mn-54 1 Sb-125 1
b. Fe-55 37 Co-60 31 Ni-63 15 Cs-137 9 Co-58 2 Cs-134 2 Cr-51 Ag-110m 1 Sb-125 1 Nb-95 1 c

21

d. Fe-55 37 Co-60 31 Ni-63 15 Cs-137 9 CO-58 2 Cs-134 2 Cr-51 1 Ag-110m 1 Sb-125 1 Nb-95 1
3. SOLID WASTE DISPOSITION NUMBER OP SHIPMENTS MODE OP TRANSPORT DESTINATION 9 (Note 3) Sole use truck Oak Ridge, TN 5 Sole use truck Barnwell, SC B. IRRADIATED PUEL SHIPMENTS None RKR/eb/055

FLORIDA POMER & LIGHT COHPAHY TURKEY POINT PLANT SEHIANNUAL REPORT JULY 1990 THROUGH DECEHBER 1990 UNITS 3 & 4 TABLE 6 SOLID HASTE SUPPLEHENT (NOTE 4) (HOTE 5) (HOTE 6) (NOTE 7)

Total Total Principal Type of R.G ~ 1.21 Type of Solidification

'Maste Volune Curie Radionuclides llaste Category Container or Absorbent Classif ication Ft3 Quantity Agent Class A 2148.8 10.77 Compactable 1.b,d Strong, N/A and Hon- Tight Coapactabi e Package, Trash Cask Type A LSA Class A 404.2 5.17 Oe~atered Bead 1.a Cask N/A Resin >Type A LSA Class 8 271.6 381 Co-60, Cs-137 Degatered Bead 1.a Cask N/A Ni-63, Sr-90 Resin >Type A C-14, Pu-241 LSA Tru RKR/eb/056

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT ZULY 1990 THROUGH DECEMBER 1990 UNITS 3 AND 4 TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPMENT OFFSITE FOR BURIAL OR DISPOSAL Note 1: Dry compressible waste volume indicates volume shipped to burial site following reduction by a waste processing facility. Volume shipped to the waste processing facility was 507. 4 m .

Note 2: Other noncompressible waste indicates volume shipped to burial site following decontamination and volume reduction by a waste processing facility. Volume shipped to the waste processing facility was 108.7 m .

Note 3: Material transported to Oak Ridge, Tennessee, was consigned to licensed processing facilities for volume reduction and decontamination activities. The material remaining after processing was transported by the processor to Barnwell, South Carolina, for burial.

Note 4: The total curie quantity and radionuclide composition of solid waste shipped from the Turkey Point Plant Units 3 and 4 are determined using a combination of qualitative and quantitive techniques. The Turkey Point Plant follows the guidelines in the Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (5/ll/83) for these determinations.

The most frequent used techniques for determining the total activity in a package are the dose to curie method and inference from specific activity and mass or activity concentration and volume. Activation analysis may be applied when it is appropriate. The total activity determination by any of these methods is considered to be an estimate.

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The composition of radionuclides in the waste is determined by both on-site analysis for principle gamma emitters and periodic off-site analyses for difficult to measure isotopes. The on-site analyses are performed either on a batch basis or on a routine basis using representative samples appropriate for the waste type.

Off-site analyses are used to establish scaling factors or other estimates for difficult to measure isotopes.

Note 5: Principle radionuclide refers to those radionuclides contained in the waste in concentrations greater than 0.01 times the concentration of the nuclide listed in Table 1 or 0.01 times the smallest concentration of the nuclide listed in Table 2 of 10 CFR 61.

Note 6: Type of waste is specified as described in NUREG 0782, Draft Environment Impact Statement on 10 CFR 61 "Licensing Requirements for Land Disposal of Radioactive Waste".

Note 7: Type of container refers to the transport package.

RKR/eb/058

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