ML17347B301

Semiannual Radioactive Effluent Release Rept Jan-June 1989. W/890830 Ltr

ML17347B301
Person / Time
Site:	Turkey Point
Issue date:	06/30/1989
From:	Cross J, Pearce L, Woody C FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-89-315, NUDOCS 8909050240
Download: ML17347B301 (36)

Text

AC4 EISRATED 93 BUTJON DEMONS TION SYSTEM j

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8909050240 DOC.DATE: 89/06/30 NOTARIZED: NO DOCKET g 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 CROSS,J.E. Florida Power & Light Co.

STEINKE,R.N. Florida Power & Lights Co.

PEARCE,L.W'. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Semiannual Radioactive Effluent Release Rept Jan-June ltr.

1989 >> W/890830 DISTRIBUTION CODE: IE48D TITLE: 50.36a(a)(2)

COPIES RECEIVED: LTR Semiannual f ENCL Effluent Release Reports I SIZE:

r /

NOTES: A.

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 3 3 PD2-2 PD 1 1 EDISON,G 1 1 INTERNAL: AEOD/DSP/TPAB 1 1 IRM TECH ADV 1 1 Rg/3) RPB 10 2 2 NUDOCS-ABSTRACT 1 1 G F-. 01 1 1 RGN2 DRSS/RPB 2 2 RGN2 FILE 02 1 1 EXTERNAL: BNL TICHLER, J03 1 1 EG&G SIMPSON, F 2 2 LPDR 1 1 NRC PDR 1 1 h

TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 19

P.O. Box14000, Juno Beach, FL 33408-0420

, AUGUST g P ~g8g L-89-315 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 January 1989 through June 1989 for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.4.

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

Very truly yours, C. 0. Woody Acting Senior Vice President Nuclear COW/TCG/gp Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 8909050240 S90630 PDR ADOCK 05000250 R PDC an FPL Group company

TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUALRADIOACTIVEEPPLUENT RELEASE REPORT JANUARY THROUGH JUNE 1989 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT PLORIDA POWER AND LIGHT COMPANY J. E. ross R.N. teirp e Plant Manager-Nuclear Chemistry Supervisor L. W. Pearc'e . Quinn Operations Superintendent Radiochemist RNS/yrzk Cl: 1

01/89 - 06/89 INDEX Page 1.0 Regulatory Limits 1.1 Liquid Effluents 1.2 Gaseous Effluents 2.0 Maximum Permissable Concentrations 3.0 Average Energy 4.0 Measurements and Approximation of Total Radioactivity 4.1 Liquid Effluents - discussion

a. Unit 3 Liquid Effluents Summation

b. Unit 4 Liquid Effluents Summation 13 4.2 Gaseous Effluents discussion

a. 'Unit 3 Gaseous Effluent Summation

b. Unit 4 Gaseous Effluent Summation 15 5.0 Batch Releases 5.1 Liquid 5.2 Gaseous 6.0 Unplanned Releases V.O Reactor Coolant Activity 8.0 Site Radiation Dose 9.0 Offsite Dose Calculation Manual Revisions 10.0 Solid Waste and Irradiated Puel Shipments 11.0 Process Control Program Revisions RNS/yrr*C1: 1

FLORIDA POWER AND LIGHT C ANY TURKEY POINT UNITS 3 AN 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT SUPPLEMENTAL INFORMATION JANUARY 1989 THROUGH JUNE 1989 1.0 Re lato Limits 1.1 Li uid Effluents a) The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentrations 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 x 10-4 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 ~1.5 mrem to the total body and to ~5 mrem to any organ, and, during any calendar year, to s3 mrem to the total body and s10 mrem to any organ.

1.2 Gaseous Effluents 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/yr to the total body and less than or equal to 3000 mrem/yr to the skin due to noble gases and less than or equal to 1500 mrem/yr 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 s5 mrad for gamma radiation and ~10 mrad for beta radiation and, during any calendar year, to ~10 mrad for gamma radiation and s20 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 mreni to any organ during any calendar year.

RNS/yrz*Cl:1

J 01/89 06/89 2.0 Maximum Permissible Concentrations The maximum permissible concentrations for liquid releases are described in Section l.l-a of this report.

The average energy of fission and activation gases in gaseous effluents is not applicable.

4.0 Measurements and A roximations of Total Radioactivi 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.

4.1 Li uid Hffluents 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.

Prequent periodic sampling and analysis were used to conservatively determine if any radioactivity was being released via the steam generator blowdown 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. The quarterly composite was analyzed for Sr-89/90 and Pe-55 by chemical separation.

All radioactivity 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.

RNS/yn*CI:I 01/89 06/89 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 Gaseous Rffluents 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 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.

RNSyrz*C1:1

01/89 - 06/89 4.3 Estimate of Errors 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+ 1096.

b) Analytical Error Our quarterly Q.C. cross-cheek 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.

Nuclide e Maximum Error Liquid Gaseous +10 X +11 X 5.0 BATCH RELEASES 5.1 Liciuid Unit 3 Unit 4 a) Number of batch releases 1.76 E+02 1.76 E+02 b) Total time period of batch releases 1.59 E+04 1 59 E+04 Minutes c) Maximum time period for a batch releases 2.00 E+02 2.00 E+02 Minutes d) Average time period for a batch release 9.03 R+01 9.03 R+01 Minutes e) Minimum time period for a batch release 5.50 E+01 5.50 E+01 Minutes f) Average stream flow during period of 1.04 E+06 1.04 E+06 GP M release of effluent into a flowing stream 5.2 Gaseous a) Number of batch releases 1.V5 E+01 1.85 E+O1 b) Total time period of batch releases 2.10 E+03 2.24 R+03 Minutes c) Maximum time period for a batch release 2.40 E+02 2.40 E+02 Minutes d) Average time period for a batch release 1.14 E+02 1.21 E+02 Minutes e) Minimum time period for a batch release 2.00 E+01 2.00 E+01 Minutes RNS/yrz*C I: 1 01/89 - 06/89 6.0 UNPLANNED RELEASES 6.1 ~Li uId UNIT 3 UNIT 6 a) Number of releases b) Total activity released Curies 6.2 Gaseous a) Number of releases b) Total activity released ~

0 Curies 6.3 See attachments (if applicable) for:

a) A description of the event and equipment involved.

b) Cause(s) for the unplanned release.

V.O Reactor Coolant Activit Reactor Coolant activity limits of 100/E and 1.0 pCi/gm Dose Equivalent I-131 were not exceeded.

8.0 The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary is part of the Year Ending Semiannual Report.

9.0 Offsite Dose Calculation Manual Revisions There were no ODCM revisions during this reporting period.

10.0 Solid Waste and Irradiated Fuel Shi mentsNo 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 5 of this report.

11.0 Process Control Pro am Revisions There were no changes to the process control program during this reporting period.

RNS/yrz*C I: 1

i PLORIDA POWER AND LIGHT C~ANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 3 TABLE 1 LIQUID EPPLUENTS SUMMATIONOF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, al ha Ci 4.29 E-02 3.20 E-02

2. Average diluted concentration during period pCi/ml 5.80 E-10 6.18 E-10 B. Tritium

1. Total Release Ci 1.81 E+ 01 1.33 E + 01

2. Average diluted concentration during period pCi/ml 2.45 E-07 2.57 E-07 C. Dissolved and Entrained Gases

1. Total Release Ci 5.04 E-02 6.80 E-03

2. Average diluted concentration during period pCi/ml 6 81 E-10 1.31 E-10 D. Gross Alpha Radioactivity

1. Total Release Ci (1.49 E-08* (1.00 E-07*

E. Volume of Batch Waste Released (prior to dilution) Liters 2.34 E+06 1.68 E+06 F. Volume of Continuous Waste Released (priortodilution) Liters 5.94 E+ 06 G. Volume of Dilution Water Used During Period Liters 7.40 E+10 5.18 E+10

• MDAValue in pCi/ml RNS/yrz*C1:1 ORIDA POWER AND LIGHT COMFY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 3 TABLE 2 LIQUID EPPLUENTS SUMMATIONOP ALL RELEASES Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Ag-110 Ci 1.48 E-04 5.56 E-04 Ce-144 Ci 4 S6 E-06 Co-57 Ci 5.30 E-07 Co-58 Ci 5.23 E-03 1.67 E-03 Co-60 Ci 7.35 E-03 5.92 E-03 Cr-S1 Ci 2.81 E-04 Cs-134 Ci 2.41 E-03 1.24 E-03 Cs-137 Ci 6.84 E-03 3.83 E-03 Fe-55 Ci 5.15 E-03 1.38 E-03

!-131 Ci '.SS E-04 3.22 E-06 4.88 E-05 I-133 Ci 6.56 E-05 1.54 E-06 Mn-54 Ci 1.35 E-02 2.72 E-03 Nb-95 Ci 2.15 E-05 4.12 E-05 Sb-124 Ci 8.60 E-05 3.46 E-04 Sb-125 Ci 1.94 E'3 1.35 E-02 Sr-89 Ci Sr-90 Ci 2.34 E-05 3.96 E-04 W-187 Ci 2.87 E-06 Zn-65 ,Ci 2.07 E-05 5.25 E-06 Unidentified Ci Total for Period Above Ci 2.21 E-04 4.27 E-02 3.20 E-02 lhNS/yrz*C1:1

't ORIDA POWER AND LIGHT COMFY TURKEY POINT PLANT s SEMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 3 TABLE 2 (Continued)

LIQUID EPPLVENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuciides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Xe-131m Ci 1.41 E-04 Xe-133 Ci 1.61 E-02 3.39 E-02 6.46 E-03 Xe-133m Ci 3.97 E-05 Xe-135 Ci 3.59 E-04 1.66 E-05 2.02 E-04 Xe-135m Ci 1.44 E-06 1.43 E-06 Total for Period Above Ci 1.64 E-02 3.40 E-02 6.80 E-03 RNS/yrz*C1:1 ORIDA POWER AND LIGHT COMI'Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 3 TABLE 3 GAS EPPLUENTS SUMMATIONOP ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release Ci 1.98 E+ 02 3 80 E+02

2. Average Release Rate for Period pCi/sec 2.55 E + 01 4.83 E+ 01 B. lodines

1. Total iodine-131 Ci 3.60 E-05 1.46 E-04

2. Average Release Rate for Period pCi/sec 4.63 E-06 1.86 E-05 C. Particulates

1. Particulates T - 1/2 >8 Days Ci 2.45 E-05 7.15 E-07

2. Average Release Rate for Period pCi/sec 3.15 E-06 9.09 E-08

3. Gross Alpha Radioactvity Ci <6.91 E-16* <6.91 E-16*

D. Tritium

1. Total Release Ci 1.09 E-02 5.37 E-01

2. Average Release Rate for Period pCi/sec 1.40 E-03 6.83 E-02

• (MDAValues Expressed in pCi/ml RNS/yn*C1:I ORIDA POWER AND LIGHT COM Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 3 TABLE 4 GASEOUS EPPLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 1 ~ Fission Gases Ar-41 Ci 2.30 E-01 1.06 E-02 Kr-85 Ci 2.65 E-01 8.90 E-01 Kr-85m Ci 2.53 E-02 7.42 E-04 5.12 E-03 Xe-131m Ci 6.90 E-01 8.38 E-01 Xe-133 Ci 1.85 E+ 02 3.05 E+ 02 1.14 E+ 01 7.14 E + 01 Xe-133m Ci 4.16 E-02 2.60 E-01 6.40 E-01 Xe-135 Ci 7.92 E-01 7.77 E-03 2.97 E-01 2.11 E-02 Xe-135m Ci 4.55 E-03 Ci Unidentified Ci Total for Ci Period Above 1.86 E + 02 3.06 E + 02 1.22 E:+ 01 7.38 E+ 01

2. lodines Br-82 Ci 4.03 E-05 I-131 Ci 2.78 E-05 1 46 E-04 l-133 Ci 2.56 E-05 4.73 E-06 Total for Ci Period Above 9.37 E-05 1.51 E-04 RNS/yrz*C1:1 ORIDA POWER AND LIGHT COMI'Y" TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 3 TABLE 4 (Continued)

GASEOUS EPPLUENTS Continuous Mode Nuclides Released Units Quarter 1 Quarter 2

3. Particulates Co-58 Ci 3.70 E-06 Co-60 Ci 9.06 E-06 Cs-137 Ci 8.71 E-07 7.15 E-07 I-131 Ci 8.18 E-06 I-133 Ci 2.69 E-06 Ci Ci Unidentified Ci Total for Period Above Ci 2.45 E-05 7.15 E-07 RNS/yrz*C1:1 1 1 ~

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'I V

ORIDA POWER AND LIGHT COM Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 4 TABLE 1 LIQUID EFPLUENTS SUMMATIONOP ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, al ha Ci 4.27 E-02 3.20 E-02

2. Average diluted concentration during period pCi/ml 5.77 E-10 6.18 E-10 B. Tritium

1. Total Release Ci 1.81 E+ 01 1.33 E + 01

2. Average diluted concentration during period pCi/ml 2 45 E-07 2.57 E-07 C. Dissolved and Entrained Gases

1. Total Release Ci 3.40'* E-02 6';80 E-3

2. Average diluted concentration during period pCi/ml 4.59 E-10 1.31 E-10" D. Gross Alpha Radioactivity

1. Total Release Ci (1.49 E-08* (1.00 E-07*

E. Volume of Batch Waste Released(priortodilution) Liters 2.34 E+06 1.68 E+06 F. Volume of Continuous Waste Released (prior to dilution) Liters N/A N/A G. Volume of Dilution Water Used During Period Liters 7.40 E+10 5.18 E+10

• MDAValue in pCi/ml RNS/yrz*C1:1 1

I

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ORIDA POWER AND LIGHT COM~Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 4 TABLE 2 LIQUID EPPLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Ag-110 Ci 1.48 E-04 5.56 E-04 Ce-144 Ci 4.56 E-06 Co-57 Ci 5.30 E-07 Co-58 Ci 5 23 E-03 1.67 E-03 Co-60 Ci 7.35 E-03 5.92 E-03 Cr-51 Ci 2.81 E-04 Cs-134 Ci 2.41 E-03 1.24 E-03 Cs-137 Ci 6.84 E-03 3.83 E-03 Fe-55 Ci 5.15 E-03 1.38 E-03 I-131 Ci 3.22 E-06 4.88 E-05 l-133 Ci 1.54 E-06 Mn-54 Ci 1.35 E-02 2.72 E-03 Nb-95 Ci 2.1 5 E.-05 4.12 E-05 Sb-124 Ci 8.60 E-'05 3.46 E-04 Sb-125 Ci 1.94 E-03 1.35 E-02 Sr-89 Ci Sr-90 Ci 2.34 E-05 3.96 E-04 W-187 Ci 2.87 E-06 Zn-65 Ci 2.07 E-05 5.25 E-06 Unidentified Ci Total for Period Above Ci 4.27 E-02 3.20 E-02 RNS/yrz*C1:1

ORIDA POWER AND LIGHT COM~Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 4 TABLE 2 (Continued)

LIQUID EFPLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Xe-131m Ci 1.41 E-04 Xe-133 Ci 3.39 E-02 6.46 E-03 Xe-133m Ci 3.97 E-05 Xe-135 Ci 1.66 E-05 2.02 E-04 Xe-135m Ci 1.43 E-06 Total for Period Above Ci 3.40 E-02 6.80 E-03 RNSyn*C1:1 ORIDA POWER AND LIGHT COMFY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 4 TABLE 3 GAS EFFLUENTS SUMMATIONOF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release Ci 1.90 E+ 02 3.78 E + 02

2. Average Release Rate for Period pCi/sec 2.42 E + 01 4 81 E+01 B. lodines

1. Total iodine-131 Ci 2.76 E-05 1.46 E-04

2. Average Release Rate for Period pCi/sec 3.55 E-06 1.86 E-05 C. Particulates

1. Particulates T-1/2>8 Days Ci 1.36 E-05 7.15 E-07

2. Average Release Rate for Period pCi/sec 1.75 E-06 9.09 E-08

3. Gross Alpha Radioactvity Ci (6.91 E-16* (6.91 E-16*

D. Tritium

1. Total Release Ci 2.19 E 03 5 20 E-01

2. Average Release Rate for Period pCi/sec 2.82 E-04 6.61 E-02

• MDAValues Expressed in pCi/ml RNS/yn*C1:1 ORIDA POWER AND LIGHT COM Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 4 TABLE 4 GASEOUS EPPLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 1 ~ Fission Gases Ar-41 Ci 1.81 E-02 Kr-85 Ci 2.65 E-01 8.90 E-01 Kr-85m Ci 1.40 E-04 6.06 E-03 Xe-131m Ci 6.90 E-01 8.38 E-01 Xe-133 Ci 1.81 E+ 02 3.05 E+ 02 7.89 E+ 00 6 94 E+01 Xe-133m Ci 1.22 E-02 2.03 E-01 6.40 E-01 Xe-135 Ci 4.03 E-03 1.57 E-03 3.10 E-01 1.08 E-02 Xe-135m Ci Ci Unidentified Ci Total for Period Above Ci 1.81 E+ 02 3.06 E+ 02 8.67 E + 00 7.18 E+ 01

2. lodines Br-82 Ci 4.03 E-05 1-131 Ci 2.76 E-05 1.46 E-04 I-133 Ci 2 48 E-05 4.73 E-06 Total for Period Above Ci 9.27 E-05 1.51 E-04 RN8/yn*C1:1 ORIDA POWER AND LIGHT COMP Y

~ g TURKBY POINT PLANT

~ i SBMIANNUALREPORT JANUARY 1989 THROUGH JUNE 1989 UNIT 4 TABLB 4 (Continued)

GASEOUS BFFLUBNTS Continuous Mode Nuclides Released Units Quarter 1 Quarter 2

3. Particulates Co-58 Ci 3.70 E-06 Co-60 Ci 9.06 E-06 Cs-137 Ci 8.71 E-07 7.15 E-07 Ci Ci Ci Unidentified Ci Total for Period Above Ci 1.36 E-05 7.15 E-07 RNSyrz*C I:1 g

I I

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1989 THROUGH JUNE 1989 UNITS 3 AND 4 TABLE 5 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Ao SOLID WASTE SHZPPED OFFSZTE FOR BURIAL OR DISPOSAL TYPE OF WASTE UNIT 6 MO PERIOD %ERR a ~ Spent resin, filters, m 0.00 EO sludge evaporator Ci 0.00 EO (Note 1)

b. Dry compressible waste 1.63 E2 (Note 2) 7-39 E-1 20 c Irradiated components 0.00 EO Control rods, etc. 0.00 EO

d. Other non-compressible m 7.04 El Waste (Note 3) Ci 9.76 E-1 20

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION BY TYPE OF WASTE a ~

b. Co-60 40 Fe-55 17 Co-58 14 C-14 10 Ni-63 7 Cs-137 5 Sb-125 9.

2 Cs-134 0 2.

Mn-54 1 Nb-95 1 c ~

d. Co-60 54 Cs-137 22 Ni-63 16 Fe-55 3 C-14 3 Ag-110m 1

3. SOLID WASTE DISPOSITION NUMBER OF SHIPMENTS MODE OF'TRANSPORT DESTINATION 19 (Note 4) Sole use truck Oak Ridge, TN BE IRRADIATED FUEL SHIPMENTS None RKR/eb/004 19

FLORIDA POWER 5 LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1989 THROUGH JUNE 1989 UNITS 3 AND 4 TABLE 5 SOLID WASTE SUPPLEMENT Waste Total (NOTE 5) (NOTE 6) (NOTE 7) R.G. 1.21 (NOTE 8) Solidification or Classification Volume Total Principal Type of Category Type of Absorbent Agent Ft3 Curie Radionuclides Waste Container guantity Class A 8242.3 1.72 None Compactable and Strong, Tight N/A Non-Compactable Package Trash RKR/044/1 20

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FLORXDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1989 THROUGH JUNE 1989 UNITS 3 AND 4 TABLE 5 SOLID WASTE AND XRRADXATED FURL SHIPMENTS SOLID WASTE SHXPPED OFFSZTE FOR BURXAL OR DISPOSAL Spent resins waste volume indicates volume shipped to a burial site directly from Turkey Point Plant or following volume reduction by a waste processing facility. Volume shipped to the waste processing facility was 60.7 m 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 148.3 m noncompressible waste indicates volume shipped to

'ther burial site following decontamination and volume reduction by a waste processing facility. Volume shipped to the waste processing facility was 2.77 E2 m 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.

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 quantitative 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 frequently 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.

21

a L g

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.

Principle radionuclides refers to those radionuclides contained in the waste in concentrations greater than 0.0l times the concentration of the nuclide listed in Table l or 0.01 times the smallest concentration of the nuclide listed in Table 2 of 10 CFR 61.

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".

Type of container refers to the transport package.

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