ML17345A536

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Revised Semiannual Radiactive Effluent Release Rept, Jan-June 1988. W/881118 Ltr
ML17345A536
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-88-496, NUDOCS 8811220466
Download: ML17345A536 (30)
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Text

. AC(;ELERATED DI~RIBUTION DEMONSTB+TION SYSTEM REGULATO INFORMATION DISTRIBUTION~STEM (RIDE)

ACCESSION NBR:8811220466 DOC.DATE:

u/zg 88/~M- 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 STEINKE,R.N. Florida Power 6 Light Co.

CROSS,J.E. Florida Power 6 Light Co.

CONWAY,W.F. Florida Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Revised "Semiannua ctive Effluent Release Rept, Jan-June 1988." /88 ll'8 r.

DISTRIBUTION CODE: IE48D TITLE: 50.36a(a)(2)

C Semiannual S RECEIVED:LTR / ENCL Effluent Release Reports 2 SIZE: 5 NOTES'ECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 5 5 EDISONFG 1 1 INTERNAL: AEOD/DSP/TPAB 1 1 ARM TECH ADV 1 1 NRR/DEST/PSB 8D 1 1' N~- DRY/RPB 10 2 2 NUDOCS-ABSTRACT 1 F E 01 1 1 RGN2 FILE 02 1 1 GN2 DRSS/EPRPB 1 1 EXTERNAL: BNL TICHLER,J03 1 1 EGSG SIMPSONF F 2 2 LPDR 1 1 NRC PDR 1 1 R

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NOTE I0 ALL RIDS" R!XIPIENTS:

PLEASE HELP US TO REDUCE %58'ZE! (XkGRCP %HE DOCXIMEPZ CCKZfRL DESK, RDGN Pl-37 (EXT. 20079) TO EZIIMINATE KSR HAMB FKH DISTRIKTZIGN IIISTB PQR DOClKERIS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 20

1 P. X 14000, JUNO BEACH, FL 33408.0420 NOVEMBER 1 8 1988 L-88-496 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, the Radioactive Effluent Release Report for the period of January 1, 1988 through June 30, 1988 for Turkey Point Units 3 and 4 was provided in Florida Power 6 Light Company letter L-88-367, dated August 29, 1988. As stated in that letter, Sr-89/90 and Fe-55 results were not available at that time.

Attached is a resubmittal of the completed Radioactive Effluent Release Report for the period of January 1, 1988 through June 30, 1988.

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

Very truly yours, W. F. Conw Senior Vice President  ;,, Nuclear WFC/SDF/gp Attachment cc: Malcolm L. Ernst, Acting Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Og1 an FPL Group company

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TURKEY POINT PLANT UNITS 3 AND 4 REVISED SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY THROUGH JUNE 1988 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY R. N. Steinke Chemistry J. E. Cross Plant Manager-Nuclear 88112204bb 880b30 ADOCN, 05000250 PDR R

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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 RNSmd*C 1:1

TURKEY POINT UNITS 3 AND 4 EFFIJjgNT AND WASTE DISPOSAL SEMIP~NUAL REPORT I ~ I SUPPLEMENTAL INFORMA~N JANUARY 1988 THROUGH JUNE 1988 1.0 Re lato Limits 1.1 Li uid Efflue ts 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 s 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, 1-133, tritium and for all radioactive materials in particulate form with hali'ives 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 s10 mrad for beta radiation and, during any calendar year, to s10 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, 1-133, 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.

RNSlmd*C1: I

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.

RNSlmd*CI:l

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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 Bffiuents 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.

RNSlmd*C 1: I 4.3 Estimate of- rs a), Sampling Error The error associated with volume measurement devices, flow measuring devices, etc., based on calibration data and design tolerances has been

'i 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 Maximum Error Liquid 2596 Gaseous 2696 t896 5.0 BATCH RELEASES 5.1 ~Li uid 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 E+02 M>nutes c) Maximum time period for a batch release 2.40 E+02 2.40 8+02 Minutes 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 RNHAnd*CI:I V I/55 - 06/55 6.0 UNPLANNED RELEASES 6.1 LicIuid UNIT 3 UNIT 4 a) Number of releases b) Total activity releases Curies 6.2 Gaseous a) Number of releases b) Total activity releases 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.

V.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 Fuel 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 P m Revisions There were no changes to the process control program during this reporting period.

RNS/md*Cd: 1 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1988 THROUGH JUNE 1988 UNIT 3 TABLE 1 LIQUID EFFLUENTS SUMMATION OF ALI RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, '-02 al ha Ci 4.23 4.37 E-02
2. Average diluted concentration during period pCi/ml 6.94 E-10 7.78 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(priortodilution) 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 II

  • NiDAValue in pCi/ml RNStmd*C1:1 tFLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALRBPORT JANUARY 1988 THROUGH JUNB 1988 UNIT 3 TABLE 2

'LIQUID BFFLUENTS SUMMATION OF ALL RELBASES 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 1-131 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 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 Fe-55 Ci 5.69 E-03 2.96 E-03 Unidentified Ci Total for Period Above- ~ Ci 5.06 E-05 9.91 E-04 4.22 E-02 4.27 E-02 RNS/md*Cd:I TURKEY POINT PI ANT SEMIANNUALREPORT

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~ JANUARY 1988 THROUGH JUN 88 UNIT 3 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 917 E 02 394 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

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FLORIDA POWER AND LIGHT COMPANY TURKBY POINT PLANT SBMIANNUALRBPORT JANUARY 1988 THROUGH JUNE 1988 UNIT 3 TABLE 3 GAS EFFLUBNTS " SUMMATIONOF ALL RBLBASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release Ci 2.02 E + 02 2.31 E+ 02
2. Average Release Rate for Period pCi%ec 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 2.66 E-05
2. Average Release Rate for Period pCi%ec 7.88 E-06 3.38 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 6.55 E-00 4.58 E-00 RNS/md*C1: i TURKEY POINT PI ANT SEMIANNUALREPORT JANUARY 1988 THROUGH JUN 88 UNIT 3 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 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. lodines Br-82 Ci 1.08 E-04 2.28 E-04 l-l31 Ci 1.70 E-03 1.17 E-03 1-133 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 RNSmd*C1:1 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1988 THROUGH JUNE 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 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 1.24 E-06 Unidentified 'Ci Total for Period Above Ci 6.19 E-05 2.66 E-05 RNShnd*C1:L

RIDA POWER AND LIGHT COMPLY TURKEY POINT PLANT SEMIANNUALREPORT-JANUARY 1988 THROUGH JUNE 1988 UNIT 4 TABLE 1 LIQUID EFFLUENTS SUMMATIONOF ALL RELEASES Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, al ha Ci 4.22 E-02 4.27 E-02
2. Average diluted concentration during period pCi/ml 6.93 E-10 7.59 E-10 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 '.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 (prior to dilution) Liters 0 G. Volume of DilutioriWater used During Period Liters 6.09 E+ 10 5.62 E+ 10

  • NiDAValue in pCi/ml ftNS/md*C1: 1 t

FLORIDA POWER AND LIGHT COMPANY TURKBY POINT PLANT SBhflANNUALRBPORT JANUARY 1988 THROUGH JUNE 19SS UNIT 4 TABLB 2 LIQUID BFFLUBNTS Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Ag-110m Ci ].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 I-131 Ci 3.75 E-04 1.86 E-04 Fe-59 Ci 1.94 E-04 i.a-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 Fe-55 Ci 5.69 E-03 2.96 E-03 Unidentified Ci Total for Period Above Ci 4.22 E-02 4.27 E-02 RNS/md*C1: 1 iuzar.x eucrci rueai SEMIANNUALREPORT

~ JANUARY 1988 THROUGH JUN~88 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 8-02 RNS/md*Cd:I FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT 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 E+ 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 2.61 E-05
2. Average Release Rate for Period pCi/sec 7.89 E-06 3.32 E-06
3. Gross Alpha Radioactvity Ci 1.62 E-07 2.06 E-07 D. Tritium 1.-. Total Release Ci 515 E + 01 360 E + 01
2. Average Release Rate for Period pCi/sec 6.56 E+00 4.58 E+00 RNS/md*C I: I S EMIANNUALREPORT JANUARY 1988 THROUGH JUN 988 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 l-131 Ci 1.70 E-03 1.12 E-03 l-133 Ci 2.74 E-03 1.02 E-03 1-135 Ci 7.00 E-04 1.27 E-03 Total for Period Above Ci 5.25 E-03 3.64 E-03 RNS/md*CI:l t

PLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1988 THROUGH JUNE 1988 UNIT 4 TABLE 4 (Continued)

GASEOUS EPPLUENTS 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 1.24 E-06 Unidentified Ci Total for Period Above Ci 6.20 E-05 2.61 E-05 RNS/md*C1:1 0 FLORIDA POHER G LIGHT CORP TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1988 THROU6H JUNE 1988 UNITS 3 AND 4 TABLE SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSIDE FOR BURIAL OR DISPOSAL
1. TYPE OF WASTE UNIT 6 MO PERIOD %ERR
a. Spent resin, filter, sludge 3.13 El bottoms, etc. Ci m'vaporator 4.23 E2 20
b. Dry compressable waste m'i 1.59 El (NOTE 1) 2.67 E-2 20
c. Irradiated components, m 0.00 EO control rods, etc. Ci 0.00 EO 20
d. Other non-compressabl e m 1.80 EO metal waste (NOTE 2) Ci 2.34 E-2 20
2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION BY TYPE OF WASTE 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 Mn-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 So1e use truck Barnwe11, SC 2 (NOTE 3) So1e use truck Oak Ridge, TN B. IRRADIATED FUEL SHIPMENTS NONE

FLORIDA POMER 5 LIGHT COHPANY TURKEY POINT PLANT SEHIANNUAL REPORT JANUARY 1988 THROUGH JUNE 1988 UNITS 3 AND 4 TABLE SOLID WASTE SUPPLEHENT 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 Maste Container i)uantity Class A 2896.3 38.78 Ni-63, Cs-137 PMR Ion Exchange l.a.b Certified NRC N/A (Note 4) Sr-90 Resins and LSA, > Type A, and PMR Compactable Non-Spec and Non- Strong. Tight Compactable Trash Package (Note 9)

Class 8 500.4 384.0 Sr.90, Ni-63 PMR Ion I.a NRC Certified N/A Co-60, Cs-137 Exchange LSA > Type A-TI/2 ( 5 yr. Resins

FLORIDA POWER AND LIGHT COt1PANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1988 THROUGH JUNE 1988 UNITS 3 AND 4 TABLE Dry Compressable Waste Volume indicates volume shipped to burial site following reduction by a waste processing facility. Volume shipped to the waste processing facility was 2.86 E1 m'.

Other Noncompressable t/etal 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 8 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 galena eomitters 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.

~ 0 c

Note 6: Principal radionuclides 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 7: Type of waste is specified as described in HUREG 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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