ML17342B204

Semiannual Radioactive Effluent Release Rept,Jul-Dec 1987. W/880229 Ltr

ML17342B204
Person / Time
Site:	Turkey Point
Issue date:	12/31/1987
From:	Conway W FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
L-88-101, NUDOCS 8803070206
Download: ML17342B204 (40)

Text

REGULA Y INFORMATION DISTRIBUTIO 'YSTEM (RIDS)

ACCESSION NBR: 8803070206 DOC. DATE: 88/02/29 NOTARIZED: NO DOCKET 0 FACIL: 50-250 Turkey Point P lant'nit 3i Florida Poeer and Light C '05000250 50-251 Turkey Point Plant~ Unit 4i Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION CONWAYe W. F. Florida Power 8c Light Co.

RECIP. NAME REC IP IENT AFFILIATION

SUBJECT:

"Semiannual Radioactive Effluent Release Rept Jul-Dec 1987. "

W 80229 l DISTRIBUTION CODE: IE48D COPIES RECEIVED: LTR ENCL SIZE:

TITLE: 50. 36a(a) (2) Semiannual Effluent Release Reports NOTES:

REC IP IENT COPIES REC IP IENT COPIES '

ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 5 EDISON' 1 1 INTERNAL: AEOD/DOA 1 AEOD/DSP/TPAB 1 1 ARM TECH ADV 1 NRR/DEST/PSBSDi 1 1 RG I,

NRR/DREP/RPB10A DRM/EPRPB 01 4

1 4

1 1

NRR/PMAS/ ILRB 12 RGN2 FILE 02 1

1 1

1 EXTERNAL: BNL TICHLERi J03 1 1 LPDR 1 1 NRC PDR 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 21

, I\

TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUALRADIOACTIVEEFFLU ENT RELEASE REPORT JULY 1987 THROUGH DECEMBER 1987 SUBMITTED BY NUCLEAR CH EMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY 88ps0702pb 6500p250 Ooc~ p p R

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AN~

EFFLI%AT AND WASTE DISPOSAL SEMIA8%UALREPORT SUPPLEMENTAL INFORMATION JULY 1987 THROUGH DECEMBER 1987 1.0 Re ulator Limits d Effl 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 S5 mrem to any organ, and, during any calendar year, to ~3 mrem to the total body and < 10 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 mrern/yr to any organ due to l-131, l-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 mrad for gamma radiation and < 10 mrad for beta radiation and, during any calendar year, to <10 mrad for gamma radiation and < 20 mrad for beta radiation.

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

~ C 07/87 - 12/87 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.

3.3 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 ~Ud EHI 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 2o 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*C1: 1

~ )

07/87 - 12/87 ll ~

At least one representative batch of liquid ef'fluent from the waste disposal system was analyzed monthly for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released for the month in order to estimate the total dissolved gases released. If more than one batch of effluent was analyzed, the concentrations were weighted in an appropriate manner.

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. However, during March through November of 1987, most short lived gaseous effluents were allocated to-Unit 4. This is due to Unit 3 being shut down during these months, and thus not contributing short lived isotopes.

l(NS/md*CI:1 07/87 - 12/87 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 + 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.

Nuclide T e '~E Maximum Error Liquid +5% +7%

Gaseous +6% +8%

RNS/md*C1: I

07/87 - 12/87 5.0 BATCH RELEASES 5.1 ~Li uid Unit 3 Unit 4 a) Number of batch releases 1.90 E+ 02 1.90 E+ 02 b) Total time period of batch releases 1.79 E + 04 1.79 E + 04 Minutes c) Maximum time period for a batch releases 2.27 E + 02 2.27 E+ 02 Minutes d) Average time period for a batch release 9.40 E+ 01 9.40 E + 01 Minutes e) Minimum time period for a batch release 3 0 E+01 3.0 E + 01 Minutes f) Average stream flow during period of 1.38 E+ 06 1.38 E+ 06 GPM release of effluent into a flowing stream 5.2 Gaseous a) Number of batch releases 1.80 E+ 01 1.70 E+ 01 b) Total time period of batch releases 1.86 E+ 03 1.14 E + 03 Minutes c) Maximum time period for a batch release 4.00 E+ 01 4.00 E + 01 Minutes d) Average time period for a batch release 1.03 E+ 02 6.71 E + 01 Minutes e) Minimum time period for a batch release 3 00 E+01 3.00 E + 01 Minutes 6.0 UNPLANNED RELEASES 6.1 ~Li uid a) Number of releases 0.00 E+ 00 b) Total activity releases 438 E 05 0.00 E + 00 Curies 6.2 Gaseous a) Number of releases 0.00 E+ 00 0.00 E + 00 b) Total activity releases 0 00 E+00 0.00 E + 00 Curies

'6.3 See attachments (¹1) for:

a) A description of the event and equipment involved.

b) Cause(s) for the unplanned release.

RNSIind*(lI:1 07/87 - 12/87 7.0 The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundry 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. These dose calculations were made using historical meteorological data..

VISITOR DOSE SUMMATION JANUARY 1987 THROUGH DECEMBER 1987 UNITS 3 AND 4 Age Group: Adult Location: Red Barn Inhalation Dose mRem Bone 3.17 E -06 Liver 2.17 E 03 Thyroid 2.78 E -03 Kidney 2.17 E -03 Lung 2.17 E 03 Gl-LLI 2.17 E 03 Total Body 2.17 E 03 NOBLE GAS EXPOSURE Gamma Air Dose 3.43 E -03 mRads Beta Air Dose 5.10 E -03 mRads 8.0 Offsite Dose Calculation Manual Revisions There were no ODCM revisions during this reporting period.

9.0 Solid Waste and lrratiated 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 Pro ram Revisions There were no changes to the process control program during this reporting period.

RNS/md*C1: 1 LORIDA POWER AND LIGHT COM NY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT 3 TABLE 1 LIQUID EFFLUENTS - SUMMATIONOF ALLRELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 8 85 E-02 4.88 E 02 al ha

2. Average diluted concentration during period pCi/ml 7.50 E 10 7.17 E 10 B. Tritium

1. Total Release Ci 1.98 E+ 01 6.40 E + 01

2. Average diluted concentration during period pCi/ml 1.68 E 07 9.40 E 07 C. Dissolved and Entrained Gases

1. Total Release Ci 6.90 E 04 3.91 E + 00

2. Average diluted concentration during period pCi/ml 585 E 12 574 E 08 D. Gross Alpha Radioactivity

1. Total Release Ci (4.81 E -08'7.20 E -09*

E. Volume of Waste Released (prior to dilution) Liters 2.87 E+06 1.78 E+ 06 F. Volume of Dilution Water Used During Period Liters 1.18 E+11 6.81 E+10

• MDAValue in pCi/ml Approved by Date l4NS/md*C l: 1 ORIDA POWER AND LIGHT COMPLY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT 3 TABLE 2 LIQUID EFFLUENTS - SUMMATIONOF ALLRELEASES Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Ag-110m Ci 3.18 E-03 4.25 E-03 Ce-141 Ci 2.00 E-06 Co-57 Ci 1.95 E-05 4.00 E-05 Co-58 Ci 2.35 E-02 8.25 E-03 Co-60 Ci 3.09 E-02 1.94 E-02 Cr-51 Ci 2.20 E-03 7.10 E-04 Cs-134 Ci 3.05 E-03 5.20 E-04 Cs-137 Ci 9.55 E-03 2.01 E-03 Fe-59 Ci 6.85 E-06 I-131 Ci 3.52 E-05 La-140 Ci 2.59 E-04 7.50 E-06 Mn-54 Ci 2.23 E-03 1.64 E-03 Mo-99/Tc-99m Ci 1.20 E-05 Na-24 Ci 3.61 E-04 Nb-95 Ci 1.18 E-03 5.90 E-05 Ru-103 Ci 6.00 E-06 Sb-124 Ci 2.15 E-04 8.35 E-04 Sb-125 Ci 5.00 E-04 3.33 E-03 Zn-65 Ci 5.40 E-05 3.68 E-06 Zr-95 Ci 2.04 E-04 1.34 E-04 Zr-97 Ci 7.25 E-06 Sr-89 Ci Sr-90 Ci Fe-55 Ci 1.10 E-02 7.55 E-03 Unidentified Ci Total for Period Above Ci 8.85 E-02 4.88 E-02 Approved by Date & ltNS/md*C1: I 0 I I F< ORIDA POWER AND LIGHT COMP Y TURKEY POINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT 3 TABLE 2 (Continued)

LIQUID EFFLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Xe-133 Ci 6.90 E-04 3.91 E+ 00

'e-133m Ci 1.04 E-04 Xe-135 Ci 1.09 E-05 Total for Period Above Ci 6.90 E-04 3.91 E+ 00 LIQUID EFFLUENTS -DOSE SUMMATION JANUARY 1987 THROUGH DECEMBER 1987 UNIT 3 Age Group: Teenager Location: Cooling Canal Shoreline De osition Dose mRern  % of Annual Limit Total Body 1.57 E-02 5.24 E-01 Approved by Date RNS/md*ol:I F] ORIDA POWER AND LIGHT COMPA Y TURKEY POINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT 3 TABLE 3 GAS EFFLUENTS - SUMMATIONOF ALLRELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release Ci 1.19 E + 02

2. Average Release Rate for Period pCi/sec 1.50 E + 01 B. Iodines

1. Total Iodine-131 Ci 2.47 E 03

2. Average Release Rate for Period pCi/sec 3.11 E -04 C. Particulates

1. Particulates T-1/2)8 Days Ci 2.10 E 05

2. Average Release Rate for Period pCi/sec 2.64 E 06

3. Gross Alpha Radioactvity Ci 5.89 E 08 D. Tritium

1. Total Release Ci 3.45 E+ 01 2.83 E+ 02

2. Average Release Rate for Period pCi/sec 4.49 E+ 00 3.56 E+ 01 Approved by Date RNS/md+Cl:1 0 t

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ORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT

)ULY 1987 THROUGH DECEMBER 1987 UNIT 3 TABLE 4 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 1 ~ Fission Gases Ar-41 Ci 5 30 E 02 1.09 E 02 Kr-85 Ci 5.10 E 01 Kr-85m Ci 5 20 E 03 1.96 E -02 Kr-87 Ci Kr-88 Ci 1.34 E 03 Xe-131m Ci 865 E 02 5.24 E 01 Xe-133 Ci 7.63 E + 01 4.08 E + 01 Xe-133m Ci 7.40 E -02 2.95 E 01 Xe-135 Ci 1.08 E 01 -'

4.48 E 01 Unidentified Ci Total for Ci Period Above 66 E+01 4.26 E + 01

2. Iodine I-131 Ci 2.47 E 03 I-133 Ci 1.28 E 03 Total for Period Above 3.75 E 03 Approved by Date IF ORIDA POWER AND LIGHT COMP45Y TURKEY POINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT 3 TABLE 4(Continued)

GASEOUS EFFLUENTS Continuous Mode Nuclides Released Units Quarter 3 Quarter 4

3. Particulates Co-60 Ci 625 E 06 Cs-137 Ci 1.21 E 05 Cs-134 Ci 1.97 E 06 Sr-89 Ci Sr-90 Ci Fe-55 Ci I-131 Ci 650 E 07 Ci Unidentified Ci Total for Ci Period Above 2.10 E 05 Approved by Date RNS/nid*C1: I FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SE MIANNUALR E PORT J~AHy 1987 THROUGH DECEMBER 1987 UNIT 3 TABLE 5 DOSE DUE TO IODINE, H-3, AND PARTICULATES Pathway Bone Liver Thyroid Kidney Lung GI-LLI Total Body 1.96 E 6 1.39 E 3 1.85 E 3 1.39 E 3 1.39 E 3 1.39 E 3 1.39 E 3 Inhalation-Adult 1.07 E 3 4.42 E 3 1.83 E 1 1.53 E 3 3.16 E 3 3.09 E 3 345 E-3 Cow Milk - Infant 7.86 E 5 3.83 E 3 1.05 E 2 3.78 E 3 3.72 E 3 3.72 E 3 3.80 E Fruit 8 Veg - Adult 7.70 E-5 7.70 E 5 7.70 E-5 7.70 E 5 7.70 E 5 7.70 E-5 8.62 E-5 7.70 E-5 Ground Plane Unit Totals (mRem) 1.23 E -3 9.72 E 3 1.95 E 1 6.78 E -3 8.35 E -3 8.28 E -3 8.62 E -5 8.72 E -3

% Annual Limit 8.23 E -3 648 E -2 1.30 E +0 4.52 E -2 5.56 E -2 5.52 E -2 5.75 E -4 5.81 E -2 DOSE - NOBLE GASES Gamma Air Dose 1.87 2 mRad  % of Annual Limit 1,87 -1 %/Yr Beta Air Dose 2.03 -2 mRad  % of Annual Limit 1.02-1 %/Yr Approved by Date . -HD -S

RIDA POWER AND LIGHT COMP TURKEY POINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT 4 TABLE 1 LIQUID EFFLUENTS - SUMMATIONOF ALLRELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release (not including tritium, gases, Ci 8.85 E 02 4.88 E 02 al ha

2. Average diluted concentration during period pCi/ml 7.50 E 10 7.17 E 10 B. Tritium

1. Total Release Ci 1.98 E+ 01 6.40 E + 01

2. Average diluted concentration during period pCi/ml 1.68 E 07 9.40 E -07 C. Dissolved and Entrained Gases

1. Total Release Ci 6.90 E 04 3.91 E + 00

2. Average diluted concentration during period pCi/ml 5.85 E 12 5.74 E 08 D. Gross Alpha Radioactivity

1. Total Release Ci (4.81 E 08* (7.20 E 09'.

Volume of Waste Released (prior to dilution) Liters 2.87 E+06 1.78 E+06 F. Volume of Dilution Water Used During Period Liters 1.18 E+11 6.81 E+10

'MDAValue in pCi/ml Approved by Date RNS/md*C1:1 I

F ORIDA POWER AND LIGHT COMP TURKEY POINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT 4 TABLE 2 Y

LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Ag-110m Ci 3.18 E-03 4.25 E-03 Ce-141 Ci 2.00 E-06 Co-57 Ci 1.95 E-05 4.00 E-05 Co-58 Ci 2.35 E-02 8.25 E-03 Co-60 Ci 3.09 E-02 1.94 E-02 Cr-51 Ci 2.20 E-03 7.10 E-04 Cs-134 Ci 3.05 E-03 5.20 E-04 Cs-137 Ci 9.55 E-03 2.01 E-03 Fe-59 Ci 6.85 E-06 1-131 Ci 3.52 E-05 La-140 Ci 2.59 E-04 7.50 E-06 Mn-54 Ci 2.23 E-03 1.64 E-03 Mo-99/Tc-99m Ci 1.20 E-05 Na-24 Ci 3.61 E-04 Nb-95 Ci 1.18 E-03 5.90 E-05 Ru-103 Ci 6.00 E-06 Sb-124 Ci 2.15 E-04 8.35 E-04 Sb-125 Ci 5.00 E-04 3.33 E-03 Zn-65 Ci 5.40 E-05 3.68 E-06 Zr-95 Ci 2.04 E-04 1.34 E-04 Zr-97 Ci 7 25 E-06 Sr-89 Ci Sr-90 Ci Fe-55 Ci 1 ~ 10 E-02 7.55 E-03 Unidentified Ci Total for Period Above Ci 8.85 E-02 4.88 E-02 Approved by Oate B-gZ -88 RNS/nul*C1: l

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FLORIDA POWER AND LIGHT COMPLY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT 4 TABLE 2 (Continued)

LIQUID EFFLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Xe-133 Ci 6.90 E 04 3.91 E + 00 Xe-133m Ci 1.04 E -04 Xe-135 Ci 1.09 E -05 Total for Period Above Ci 6.90 E-04 3.91 E + 00 LIQUID EFFLUENTS -DOSE SUMMATION JANUARY 1987 THROUGH DECEMBER 1987 UNIT 4 Age Group: Teenager Location: Cooling Canal Shoreline De osition .Dose mRem  % of Annual Limit Total Body 1.57 E-02 5.24 E-01 Approved by Date RNSlind*(:l:I FJRDRIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT4TABLE3 GAS EFFLUENTS - SUMMATIONOF ALLRELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release Ci 7.69 E+ 01 1.19 E + 02

2. Average Release Rate for Period pCi/sec 1.00 E+01 1.50 E+01 B. Iodines

1. Total Iodine-131 Ci 1,34 E -03 2.47 E 03 2.'verage Release Rate for Period pCi/sec 1.74 E -04 3.11 E 04 C. Particulates

1. Particulates T-1/2)8 Days Ci 6.30 E 06 2.10 E 05

2. Average Release Rate for Period pCi/sec 8.19 E -07 2.64 E 06

3. Gross Alpha Radioactvity Ci 1.54 E 07 5.89 E 08 D. Tritium

1. Total Release Ci 3.45 E+ 01 2.83 E+ 02

2. Average Release Rate for Period pCi/sec 4.49 E+ 00 3.56 E+01 Approved by Date RNS/md*C1: 1 F RIDA POWER AND LIGHT COMPP Y TURKEY POINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT 4 TABLE 4 GASEOUS EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 1 ~ Fission Gases Ar-41 Ci 2.80 E 01 530 E 02 615 E 02 1.09 E 02 Kr-85 Ci 9.70 E 01 5.10 E 01 Kr-85m Ci 3.77 E 02 5.20 E -03 3.84 E -04 1.96 E -02 Kr-87 Ci 3.18 E -03 Kr-88 Ci 2.33 E -02 1.34 E 03 Xe-131m Ci 3 82 E-01 8 65 E 02 7 60 E 02 5.24 E 01 Xe-133 Ci 6.10 E+01 7 63 E+01 1 26 E+01 4.08 E+ 01 Xe-133m Ci E 01 '.36 7AO E 02 1 39 E 01 2.95 E 01 Xe-135 Ci 6.51 E -01 1.08 E 01 2.51 E 01 4A8 E 01 Unidentified Ci Total for Period Above Ci 6.28 E+ 01 7.66 E + 01 .1.41 E + 01 4 26 E+01

2. Iodine Br-82 Ci 1.13 E 02 I-131 Ci 1.34 E 03 2.47 E 03 I-133 Ci 3.11 E -03 1.28 E -03 I-135 Ci 3.54 E-03 Total for Ci Period Above 1.93 E 02 375 E 03 Approved by Date 8NS/md*o l: I ,

FfgQRIDA POWER AND LIGHT COMPLY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT 4 TABLE 4 (Continued)

GASEOUS EFFLUENTS Continuous Mode Nuclides Released Units Quarter 3 Quarter 4

3. Particulates Ce-144 Ci 8.84 E 07 Co-58 Ci 6.14 E 07 Co-60 Ci 1.76 E 07 6.25 E 06 Cs-134 Ci 1.97 E 06 Cs-137 Ci 1.77 E -06 1.21 E 05 Mo-99 Ci 654 E 09 Sr-89 Ci 2.57 E -06 Sr-90 Ci 2.80 E 07 Fe-55 Ci I-131 Ci 6.50 E -07 Ci Unidentified Ci Total for Period Above Ci 6.30 E 06 2.10 E 05 Approved by Date cQ-RNS/md*o1: I 0

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT amtnRY 1987 THROUGH DECEMBER 1987 UNIT 4 TABLE 5 DOSE DUE TO IODINE, H-3, AND PARTICULATES Pathway Bone Liver Thyroid Kidney Lung GI-LLI Skin Total Body Cow Milk - Infant 1.13 E 3 4.49 E -3 2.04 E 1 1.54 E -3 3.15 E -3 3.09 E 3 3.48 E -3 855 E 5 382 E 3 114 E 2 376 3 370 3 370 3 378 E-3 Fruit 8 Veg - Fresh E E E Ground Plane 1.06 E -4 1.06 E -4 1.06 E 2 1.06 E -4 1.06 E -4 1.06 E -4 1.24 E -4 1.06 E -4 2.30 6 1.38 E -3 1.93 -3 1.38 3 1.38 3 1.38 3 E -3 Inhalation-Adult E E E E E 1.38 Unit Totals (mRem) 132 E 3 980 E 3 217 E 1 679 E 3 834 E 3 828 E 3 124 E 4 875 E 3

% Annual Limit 8.80 E 3 6.53 E 2 1.45 E +0 4.53 E 2 5.56 E 2 5.52 E 2 8.27 E -4 5.83 E 2 DOSE - NOBLE GASES Gamma Air Dose 5.29-3 mRad  % of Annual Limit 5.29 - 2 %/Yr Beta Air Dose 1.54- 2 mRad  % of Annual Limit 7.69 2 %/Yr Approved by Date ATTACHMENT1 UNPLANNED RELEASES A) Description of the event and equipment involved. On November 12, 1987 a leak was detected in the Unit 3B Component Cooling, Water Heat Exchanger. This allowed an estimated 8100 gallons of component cooling water contaminated to a level of 1.428 E 6 pCi/ml, to be released to the cooling canal.

B) Causes for the unplanned release were:

1) Contamination of the component cooling water system

-with Cs-137 and Cs-134.

2) Tube failure in the heat exchanger.

FZDRIDA POWER 6 IZGHT OQMP KUEKEY EOINT EKANT SEMIANNUAL REPORT JULY 1987 THFKU2i DZCEK31& 1987 UNITS 3 AND 4 TABIE 5A SOLZD WASTE AND IEKADIATED FUEL SHIBKNTS A. SOIZD MME SHIPPED OFFSZXK FOR H3RIAL OR DISKSAL

l. TYPE OF WASTE UNIT 6 MNHK PERIOD 3

a0 Spent resins, Filter sludges m 1.18 El evaporator bottoms, etc. Ci 4.93 E2 3

b. Dry Campressible Waste 2.15 E2 (NOIE 1) Ci 6.80 E-1 3

co Irradiated Ccaqmnent 0.00 EO Control rods, etc. Ci 0.00 EO 3

d. Other 1.49 El NonCcmpressible Metal Ci 2.48 El Waste (NOTE 1)

2. Esthnate of Major Nuclide Gcm~ositicjn (by type of waste) ao Co-60 42 Co-58 25 Fe-55 10 Ni-63 7 Cs-137 7 Mn-54 3 Cs-134 3 Sb-125 1 Cr-51 1

b. Co-60 49 Co-58 17 Fe-58 16 Ni-63 9 Cs-137 3 Sb-125 1 c

d+

v ~< a ~

3. "Solid Na.~ D 'tian Nimiber of Shi ts Mode of rtation Destination 5 Sole Use Truck Barnwall, S.C.

16 (NOZE 2) Sole Use Truck Oak Ridge, TN B. IHRADIKZDH3Ef SfKEKWlS Number of Shi ts Mode of rtation Destination N/A N/A N/A = Not Applicable FIDRIDA RSER & LIGHZ CCHPANY

'IURKEY POINZ PIANZ SBGANNUAL REKRZ JULY 1987 'IKKVGH DECEMBER 1987 UNITS 3 AND 4 TABIE 5B SOLID WASZE SUPPZZHEÃZ Waste Total (NOZE 4) (NOTES 5) (NOZE 6) R.G. 1.21 (NOZE 7) Solidification or Classification Volume Total Principal Type of Category Type of Absorbent Agent Ft3 Curie Radionuclides Waste Container Quantity 8115.6 .93 None IWR Ocapactable 1. b Non-Spec N/A (NOZE 3) and Non- Strong, Tight Oarpactable Trash Package (Note 5)

Class B 417 492.9 S~O, NiW3 ISR Ion l. a NRC Certified N/A

~0, Cs-137, Tl/2 < 5 yr.

B<clmnge Resins ISA > Type A v ~ >

FIDRIDA POWER & LIGHZ COMP TURKEY POINT UNIT NOS. 3 & 4 SEMI-ANNUAL REPORT JULY 1987 'QBKUGH DEEMS% 1987 TABI1" 5B (OONTINUED)

SOLID WASTE SUPPLEMENTS Dry Ooapressible Waste Volume indicates volume shipped to burial site following volume reduction by a waste processing facility. Volume shipped to the was~ processing facility was 4.29 E2 m .

Material transported to Oak Ridge, Tennesmm, was consigned to licensed processing facilities for volume reduction activities. The remaining material after processing is transported by the processor to Barnwell, S.C. for burial.

Volume listed is composed of waste shipped to the burial site by contracted waste processing and volume reduction facilities.

The total curie quantity and radionuclide composition of solid waste shipped from the Turkey Point Plant Units 3 & 4 are determuned using a combination of qualitative and quantitive techniques. In general, the Turkey Point Plant follows the guidelines outlined in the Low Level Waste Licensing Branch Technical Position (BTP) on Radioactive Waste Classification (5/11/83) for these determinations.

The most frequently used techniques for determining the total curie quantity in a package are the dose to curie methods and the (concentration) x (Volume or Mass) calculations. Where appropriate, engineering type activation analyses may be applied. Since each of the above methodologies involves to some exit qualitative parameters, the total curie quantity is considered to be an estimate.

The cxzqposition of radionuclides in the waste is determined by both on-site analyses for principal ganma emittms and periodic off-site analyses for other radionuclides. The on-site analyses are performed either on a batch representative samples analyses are used to basis as or establish on a appropriate for the waste scaling factors or other

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routine basis using reasonably Offsite estimates for radionuclides such as 3H, 14C, 99Tc, 129I, TRO, 241Pu, 242Cm, 63Ni, and 55Fe.

"Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than .Ol time+ the concentration of the nuclide listed in Table 1 or .01 times the smallest concentration of that nuclide listed in Table 2 of 10 CFR 61.

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NOZE 6 ""Type of " is generally specified escribed in NUR1K 0782, Draft Envirorment Impact Statement on 10 CFR 61 "Licensing Recpirements for land Disposal of Radioactive Waste".

NOZE 7: " "Type of Container" refers to the transport package.

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P. O. 14000, JUNO BEACH, FL 33408.0420

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FEBRUARY 2 9 1988 L-88-101 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 1987 through December 1987 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 F. Conw y nior Vice President Nuclear WFC/SDF/gp Attachment cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant SDF/02 6. RER an FPL Group company

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