ML17345A349

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Semiannual Radioactive Effluent Release Rept,Jan-June 1988. W/880829 Ltr
ML17345A349
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 06/30/1988
From: Conway W, Cross J, Steinke R
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
L-88-367, NUDOCS 8809070238
Download: ML17345A349 (47)
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Text

. A,C.CELEMTED DISTRIBUTION 0

DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8809070238 DOC.DATE: 88/08/29 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 AUTHOR AFFILIATION 05000251'UTH.

NAME STEINKE,R.N. . Florida Power & .Light Co.

CROSS,J.E. Florida Power & Light Co.

CONWAY,W.F. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION R

SUBJECT:

"Semiannual Radioactive Effluent Release Rept for Jan-June 1988." W/880829 ltr.

DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR ENCL SIZE: D TITLE: 50.36a(a)(2) Semiannual Effluent Release Report NOTES:

RECIPIENT COPIES RECIPIENT COPIES

/

ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL A PD2-2 LA 1 0 PD2-2 PD 5 5 EDISON,G 1 1 INTERNAL: AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 ARM TECH ADV 1 1 NRR/DEST/PSB 8D 1 1 NRR DR RPB 10 4 4 NUDOCS-ABSTRACT 1 1 01 1 1 RGN2 FILE 02 1 1 GN2/DRSS/EPRPB 1 1 EXTERNAL: BNL TICHLER, J03 1 1 LPDR 1 1 NRC PDR 1 1 j

A D

D TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 21

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. BOX 14000, JUNO BEACH, FL 33408 0420

~i4ly cz gUGUsT. 2 9 1988 L-88-367 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 Pursuant to the requirements of Technical Specification 6.9.4, attached is the Radioactive Effluent Release Report for the period of January 1, 1988 through June 30, 1988 for Turkey Point Units 3 and 4. Sr-89/90 and Fe-55 results are not available at this time. A follow-up report will be provided upon completion of analyses.

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

Very truly yours, W. . Con Senior Vi President Nuclear WFC/SDF/gp Attachment cc: Dr. J. Nelson Grace, Regional Administrator, Reg'ion II,,USNRC Senior Resident Inspector, USNRC, .Turkey'Point Plant SDF/026.RER an FPL Group company

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TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY THROUGH JUNE 1988 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY i' ~l r ~ + .AA ~ ~; '.

N. Steinke J. E. Cross Radiochemist Plant Manager-Nuclear R NS/md*C1:I 8805'070238 880 Poa AoaCK oooo 0 R PDC

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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 Site-Radiation Dose 8.0 Offsite Dose Calculation Manual Revisions 9.0 Solid Waste and Irradiated Fuel Shipments 10.0 Process Control Program Revisions RNS/md*Cd:I

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 EF~ENT AND WASTE DISPOSAL SE~NUAL REPORT SUPPLEMENTAL INFORMATION

~ 4 JANUARY 1988 THROUGH JUNE 1988 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 s1.5 mrem to the total body and to <<5 mrem to any organ, and, during any calendar year, to <<3 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 5 5 mrad for gamma radiation and 5 10 mrad for beta radiation and, during any calendar year, to sl0 mrad for gamma radiation and s20

-mrad for beta radiation.

c) The dose per reactor to a member of the public, due to 1-131, 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.

RNS/md*C l: 1

01/88 - 06/88

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s . 2.0 Maximum Permissible Concentrations The maximum permissible concentrations for liquid and airborne releases are described in Sections 1.1-a and 1.2-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 Radioactivit 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 Effluents Aliquots of representative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 2a gas flow proportional counter. The efficiency of the gas flow proportional counter is adjusted so that the activity determined by gross beta-gamma analysis approximates the isotopic activities determined by gamma spectrum analysis and selected beta determinations, exclusive of tritium and dissolved gases.

The above procedure was followed for all releases from the waste disposal system and for secondary system batch releases. Frequent 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 2a gas flow proportional counter. The quarterly composite was analyzed for Sr-89/90 and Fe-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/md*C I: 1 0

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01/88 - 06/88 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 Effluents Airborne releases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and sporadic 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 sporadic 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.

RNH/md*Cd:I 1

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4.3 Estimate of Errors

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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-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.

Nuclide Maximum Error Liquid Gaseous +696 +896 5.0 BATCH RELEASES 5.1 ~Li did Unit 3 Unit 4 a) Number of batch releases 1.14 E+02 1.14 E+02 b) Total time period of batch releases 1.09 E+04 1.09 E+04 Minutes c) Maximum time period for a batch releases 2.25 E+02 2.25 E+02 Minutes d) Average time period for a batch release 9.56 E+01 9.56 E+01 Minutes e) Minimum time period for a batch release 5.70 E+01 5.70 E+01 Minutes f) Average stream flow during period of 2.84 E+06 2.84 E+06 GPM release of effluent into a flowing stream 5.2 Gaseous a) Number of batch releases 1.95 E+01 1.85 E+01 b) Total time period of batch releases 1.10 E+03 8.63 8+02 Minutes c) Maximum time period for a batch release 2.40 E+02 2.40 E+02 M inutes d) Average time period for a batch release 5.66 E+01 4.66 E+01 Minutes e) Minimum time period for a batch release 2.00 E+01 2.00 E+01 Minutes RNH/md*Cd:I

01/88 - 06/88 6.0 UNPLANNED RELEASES 6.1 Liciuid UNIT 3 UNIT 4 a) Number of releases b) Total activity releases 0 Curies 6.2 Gaseous a) Number of releases b) Total activity releases 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.

NOTE: No unplanned releases during this period.

Z.O 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.

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

9.0 Solid Waste and Irradiated Puel 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 5 of this report.

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

RNS/md*CI:1

t FLORIDA POWER AND I IGHT COMPAN Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY THROUGH JUNE 1 88 UNIT 3 TABLE 1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 4.23 E-02 4.07 E-02 al ha
2. Average diluted concentration during period pCi/ml 6.94 E-10 7.24 E-10 B. Tritium
1. Total Release Ci 5.45 E + 01 5.15 E + 01
2. Average diluted concentration during period pCi/ml 8.95 E-07 9.15 E-07 C. Dissolved and Entrained Gases
1. Total Release Ci 9.45 E-02 4.00 E-02
2. Average diluted concentration during period pCi/ml 1.55 E-09 7.12 E-10 D. Gross Alpha Radioactivity
1. Total Release Ci (7.12 E-09* (7.12 E-09*

E. Volume of Batch Waste Released (prior to dilution) Liters 1.47 E+06 1.02 E+06 F. Volume of Continuous Waste Released(priortodilution) Liters 6.85 E+06 1.47 E+07 G. Volume of Dilution Water Used During Period Liters 6.09 E+10 5.62 E+ 10

  • MDAValue in pCi/ml RNS/md*C1:1 1

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t FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1988 THROUGH JUNE 1988 UNIT 3 TABLE 2

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LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Ag-110m Ci 1.15 f-03 6 48 E-04 Ba-139 Ci 2.41 E-05 Co-57 Ci 1.59 E-06 Co-58 Ci 5.81 E-03 7.69 E-03 Co-60 Ci 1.74 E-02 1.18 E-02 Cr-51 Ci 3.94 E-04 4.51 E-03 Cs-134 Ci 1.15 E-03 1.98 E-03 Cs-136 Ci 7.45 E-06 Cs-137 Ci 3.60 E-03 6.04 E-03 l-131 Ci 3.56 E-05 8.14 E-04 3.75 E-04 1.86 E-04 I-133 Ci 1.50 E-05 1.77 E-04 Fe-59 Ci 1.94 E-04 La-140 Ci 1.34 E-03 7.31 E-04 Mn-54 Ci 1.80 E-03 Mo-99/Tc-99m Ci 1.92 E-04 1.04 E-04 Nb-95 Ci 4.58 E-06 1.48 E-04 Nb-97 Ci 3.34 E-06 Na-24 Ci 4.31 E-06 4.11 E-06 Sb-124 Ci 5.73 E-05 2.23 E-04 Sb-125 Ci 327 E03 539 E-03 Ru-103 Ci 4.00 E-05 Sn-117m Ci 1.63 E-05 Zr-95 2.01 E-05 5.69 E-03

  • Fe-55 Ci Unidentified Ci Total for E-02 Period Above Ci 5.06 E-05 9.91 E-04 4.22 E-02 3.97
  • Sr-89/90 and Fe-55 analyses unavailable at present time RNS/md*Cd:1

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t FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1988 THROUGH JUNE 1988 UNIT 3 TABLE 2 (Continued)

LIQUID EFFLUENTS

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Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Kr-85m Ci 1.53 E-06 Xe-131m Ci 1.67 E-04 4.34 E-04 Xe-133 Ci 9.17 E-02 3 94 E-02 Xe-133m Ci 2.40 E-03 1.20 E-04 Xe-135 Ci 2.33 E-04 1 40 E-05 Total for Period Above Ci 9.45 E-02 4.00 E-02 LIQUID EFFLUENTS -DOSE SUMMATION JANUARY 1988 THROUGH JUNE 1988 UNIT 3 Age Group: Teenager Location: Cooling Canal Shoreline De ition Dose mRem  % of Annual Limit Total Body 3.48 E-03 1.16 E-01 RNS/md*C1:1 0

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1. Total Release Ci 2 02 E+02 2 31 E+02
2. Average Release Rate for Period pCi/sec 2.57 E + 01 2.93 E + 01 B. lodines
1. Total iodine-131 Ci 1.70 E-03 1.17 E-03
2. Average Release Rate for Period pCi/sec 2.16 E-04 1.49 E-04 C. Particulates
1. Particulates T-1/2>8 Days Ci 6.19 E-05 2.54 E-05
2. Average Release Rate for Period pCi%ec 7.88 E-06 3.23 E-06
3. Gross Alpha Radioactvity Ci 1.62 E-07 2.06 E-07 D. Tritium
1. Total Release Ci 5.15 E + 01 3.60 E + 01
2. Average Release. Rate for Period pC%iec . 6.55 E-00 4.58 E-00 RNS/md*Ci: i

t FLORIDA POWER AND I IGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1988 THROUGH JUNE 1988 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 1.11 E-01 2.11 E-01 1.45 E-01 Kr-85 Ci 4.04 E-01 Kr-85m Ci 7.86 E-03 2.48 E-02 1.44 E-02 Kr-87 Ci 9.65 E-04 4 49 E-05 Kr-88 Ci 3.15 E-03 6.05 E-03 5.90 E-03 Xe-131m Ci 8.96 E-03 2.49 E + 00 1.28 E + 00 1.94 E-01 Xe-133 Ci 1.27 E+ 02 2.06 E+02 7.06 E+ 01 1.55 &+ 01 Xe-133m Ci 2.20 E-02 8.74 E-02 1.50 E + 00 3.67 E + 00 Xe-135 Ci 1.41 E-02 1.33 E-01. 9.72 E-01 1.93 E + 00 Unidentified Ci Total for Ci Period Above 1.27 E+ 02 2.09 E+ 02 7.48 E+ 01 2.15 E+ 01
2. Iodines Br-82 Ci 1.08 E-04 2.28 E-04 I-131 Ci 1.70 E-03 1.17 E-03 I-133 Ci 2.74 E-03 1.03 E-03 l-135 Ci 7.00 E-04 1.27 E-03 Total for Ci Period Above 5.25 E-03 3.70 E-03 RNS/md*C1: I t FLORIDA POWER AND LIGHT COMPANX TURKEY POINT PLANT SEMIANNUALREPOR JANUARY 1988 THROUGH JUN 1988 UNIT 3 TABLE 4 (Continued)

GASEOUS EFFLUENTS Continuous Mode Nuclides Released Units Quarter 1 Quarter 2

3. Particulates Ba-140 Ci 7.70 E-06 8.60 E-06 Ce-144 Ci 1.20 E-05 Co-58 Ci 1.01 E-06 Co-60 Ci 2.25 E-06 1.91 E-06 Cs-134 Ci 1.17 E-05 8.45 E-07 Cs-136 Ci 2.58 E-06 Cs-137 Ci 1.64 E-05 1.18 E-05 1-131 Ci 6.52 E-06 1.19 E-06 La-140 Ci 1.90 E-06 Sr-89 Ci 8.90 E-07 Unidentified Ci Total for Period Above Ci 6.19 E-05 2.54 E-05
  • Sr-89/90 and Fe-55 analyses unavailable at present RNS/md*Cd: I

c LORIDA POWER AND LIGHT CO ANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1988 THROUGH JUNE 1988 UNIT 4 TABLE 1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, 4.22 E-02 E-02 al ha Ci 3.97
2. Average diluted concentration during period pCi/ml 6.93 E-10 7.06 E-07 B. Tritium
1. Total Release Ci 5.45 E + 01 5.14 E + 01
2. Average diluted concentration during period pCi/ml 8.95 E-07 9.15 E-07 C. Dissolved and Entrained Gases
1. Total Release Ci 9.45 E-02 4.00 E-02
2. Average diluted concentration during period pCi/ml 1.55 E-09 7.12 E-10 D. Gross Alpha Radioactivity
1. Total Release Ci <7.12 E-09* (7.12 E-09*

E. Volume of Batch Waste Released {priorto dilution) Liters 1.47 E + 06 1.02 E + 06 F. Volume of Continuous Waste Released {priorto dilution) Liters G. Volume of Dilution Water Used During Period Liters 6.09 E + 10 5.62 E + 10

  • MDAValue in pCi/ml l(NS/md*ol:1 r

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FLORJUA POWl'R AND LJCiH'1'VMPANX TURKEY POINT PLANT SEMIANNUALREPOR JANUARY 1988 THROUGH JUN 1988 UNIT 4 TABLE 2 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Ag-110m Ci 1.15 E-03 6 48 E-04 Ba-139 Ci 2.41 E-05 Co-57 Ci 1.59 E-06 Co-58 Ci 5.81 E-03 7.69 E-03 Co-60 Ci 1.74 E-02 1.18 E-02 Cr-51 Ci 3 94 E-04 4 51 E-03 Cs-134 Ci 1.15 E-03 1.98 E-03 Cs-136 Ci 7.45 E-06 Cs-137 Ci 3.60 E-03 6.04 E-03 l-131 Ci 3.75 E-04 1.86 E-04 Fe-59 Ci 1.94 -E-04 La-140 Ci 1.34 E-03 7.31 E-04 Mn-54 Ci 1.80 E-03 Mo-99/Tc-99m Ci 1.92 E-04 1.04 E-04 Nb-95 Ci 4.58 E-06 1.48 E-04 Nb-97 Ci 3.34 E-06 Na-24 Ci 4.31 E-06 4.11 E-06 Sb-124 Ci 5.73 E-05 2.23 E-04 Sb-125 Ci 3.27 E-03 5.39 E-03 Ru-103 Ci 4.00 E-05 Sn-117m Ci 1.63 E-05 Zr-95 Ci 2.01 E-05 5.69 E-03

  • Fe-55 Unidentified Ci Total for Period Above Ci 4.22 E-02 3.97 E-02
  • Sr-89/90 and Fe-55 analyses unavailable at present time RNSlmd*C1:1 J ~

t ravKluA rvwL:K eau Liur1l ( UMr At( l TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1988 THROUGH JUN 1988 UNIT 4 TABLE 2 (Continued)

LIQUID EFFLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Kr-85m Ci 1.53 E-06 Xe-131m Ci 1.67 E-04 4.34 E-04 Xe-133 Ci 9.17 E-02 3 94 E-02 Xe-133m Ci 2.40 E-03 1.20 E-04 Xe-135 Ci 2 33 E-04 1.40 E-05 Total for Period Above Ci 9.45 E-02 4.00 E-02 LIQUID EFFLUENTS -DOSE SUMMATION JANUARY 1988 THROUGH JUNE 1988 UNIT 4 Age Group: Teenager Location: Cooling Canal Shoreline De ition Dose mRem  % of Annual Limit Total Body 1.67 E-03 5.56 E-02 RNS/md*el u E P ~

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SEMIANNUALREPOR'1~

JANUARY 1988 THROUGH JUNE 1988 UNIT 4 TABLE 3 GAS EFFLUENTS - SUMMATION OF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release Ci 2.12 E+02 2.36'+02
2. Average Release Rate for Period pCi/sec 2.69 E + 01 3.00 E + 01 B. lodines
1. Total iodine-131 Ci 1.70 E-03 1.12 E-03
2. Average Release Rate for Period pCi/sec 2.16 E-04 1.42 E-04 C. Particulates
1. Particulates T - 1/2 >8 Days Ci 6.20 E-05 2.49 E-05
2. Average Release Rate for Period pCi/sec 7.89 E-06 3.17 E-06
3. Gross Alpha Radioactvity Ci 1.62 E-07 2.06 E-07 D. Tritium
1. Total Release Ci 5.15 E+ 01 3.60 E + 01
2. Average Release Rate for Period pCi/sec 6 56 E+00 4.58 E + 00 RNS/md*Cd: I I J ~

r~vzau~ rvw J'h aalu LLUt1'l l 'UMPAN Y TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1988 THROUGH JUN 1988 UNIT 4 TABLE 4 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Ar-41 Ci 2.47 E-01 2.81 E + 01 Kr-85 Ci 1.43 E-01 4.04 E-01 Kr-85m Ci 1.18 E-03 7.28 E-03 2.16 E-02 1.44 E-02 Kr-87 Ci 4.49 E-05 Kr-88 Ci 4.59 E-03 6.05 E-03 5.90 E-03 Xe-131m Ci 1.76 E-02 1.39 E-01 1.28 E+ 00 1.94 E-01 Xe-133 Ci 1.32 E + 02 1.86 E + 02 7.45 E + 01 1.55 8+ 01 Xe-133m Ci 5.83 E-02 1.12 E-01 1.53 E+ 00 3 67 E+00 Xe-135 Ci 6.78 E-02 1.47 E-01 9.35 E-01 1.81 E + 00 Unidentified Ci Total for Period Above Ci 1.33 E+ 02 2.15 E+ 02 7.87 E+ 01 2.12 E+ 01
2. lodines Br-82 Ci 1.08 E-04 2.28 E-04 I-131 Ci 1.70 E-03 1.12 E-03 I-133 Ci 2.74 E-03 1.02 E-03 I-135 Ci 7.00 E-04 1.27 E-03 Total for Period Above Ci 5.25 E-03 3.64 E-03 RNS/md*C I: I zsvzau~ t ver a, aalu j xerox vvmrza z TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1988 THROUGH JUN 1988 a E ~ UNIT 4 TABLE 4 (Continued)

GASEOUS EFFLUENTS Continuous Mode Nuclides Released Units Quarter 1 Quarter 2

3. Particulates Ba-140 Ci 7.70 E-06 8.60 E-06 Ce-144 Ci 1.20 E-05 Co-58 Ci 1.01 E-06 Co-60 Ci 2.25 E-06 1.69 E-06 Cs-134 Ci 1.17 E-05 8.45 E-07 Cs-136 Ci 2.58 E-06 Cs-137 Ci 1.64 E-05 1.16 E-05 I-131 Ci 6.52 E-06 1.19 E-06 La-140 Ci 1.90 E-06 Sr-89 Ci 8.90 E-07 Unidentified Ci Total for Period Above Ci 6.20 E-05 2.49 E-05
  • Sr-89/90 and Fe-55 not available at present time RNS/md*(l 1: I fLORIDA POMER 5 LIGHT COt1PANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1988 THROUGH JUNE 1988 UNITS 3 AND 4 TABLE SOLID MASTE AND IRRADIATED FUEL SHIPNENTS A. SOLID MASTE SHIPPED OFFSIDE FOR BURIAL OR DISPOSAL
1. TYPE OF WASTE UNIT 6 NO PERIOD %ERR
a. Spent resin, filter, sludge 3.13 El bottoms, etc. Ci m'vaporator 4.23 E2 20
b. Dry compressable waste m 1.59 E1 (NOTE 1) Ci 2.67 E-2 20
c. Irradiated components, m 0.00 EO control rods, etc. Ci 0.00 EO 20
d. Other non-compressable m'i 1.80 EO metal waste (NOTE 2) 2.34 E-2 20
2. ESTIMATE OF NJOR NUCLIDE COMPOSITION BY TYPE OF MASTE a ~ Co-60 54 Fe-55 17 Ni-63 9 Cs-137 9 Cs-134 3 I-131 3 Co-58 2 Sb-125 1 Mn-54 1
b. Fe-55 41 Co-60 38 Co-58 7 Ni-63 7 Hn-54 2 TRU 1 Sb-125 1 Nb-95 1 C.
d. Cs-137 100

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3. SOLID MASTE DISPOSITION No. of Shipments Node of Transporation Destination Sole use truck Barnwel 1, SC 2 (NOTE 3) Sole use truck Oak Ridge, TN B. IRRADIATED FUEL SHIPMENTS NONE

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! SEMIANNUAL REPORT JANUARY 1988 THROUGH JUNE 1988 UNITS 3 AND 4 TABLE 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 2896.3 38.78 Ni-63, Cs-137 PWR Ion Exchange l.a,b NRC Certified N/A (Note 4) Sr-90 Resins and LSA, > Type A, and PWR Compactable Non-Spec and Non- Strong, Tight Compactable Trash Package (Note 9)

Class B 500.4 384.0 Sr.90, Ni-63 PXR Ion l.a NRC Certified N/A Co-60, Cs-137 Exchange LSA > Type A TI/2 ( 5 yr. Resins

FLORIDA POWER AND LIGHT COI1PANY TURKEY POINT PLANT SEHIANNUAL REPORT JANUARY 1988 THROUGH JUNE 1988 UNITS 3 AND 4 TABLE Dry Compressable 'aste Volume indicates volume shipped to burial site following reduction by a waste processing facility. Volume shipped to the waste processing facility was 2.86 El m'.

Other Noncompressable t1etal 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 3.62 El m'.

11aterial 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.

Volume listed is composed of waste shipped to burial site by contracted waste processing and volume reduction facilities and dewatered ion exchange resins shipped from Turkey Point Plant.

The total curie quantity and radionuclide composition of solid waste shipped from the Turkey Point Plant Units 3 5 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 (5/11/83) 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.

The composition of radionuclides in the waste is determined by both on-site analyses for principle gamma emmitters 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.

4 Note 6: Principal radionucl ides refers to those r adionucl ides 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 7: 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 8: Type of container refers to the transport package.

Note 9: PWR secondary resins shipped in casks. DAW shipped in non-specification, strong, tight containers.

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