ML17347A318

Semiannual Radioactive Effluent Release Rept,Jul - Dec 1986. W/870302 Ltr

ML17347A318
Person / Time
Site:	Turkey Point
Issue date:	12/31/1986
From:	Woody C FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-87-105, NUDOCS 8703050057
Download: ML17347A318 (41)

Text

BETS MASTER FlLE RESULATORY INFORNATION DISTRIBUTI N SYSTEM <RI Qk NOTARIZE 'b~F- ~~

1 ACCESSION NBR: 8703050057 DOC. DATE: 86/IE/3I CKET FACIL: 50-250 Turkey Point Plant> Unit 37 Florida Power an xght C 05000250 50-251 Turkey Point Plants Unit 47 Flori da Potoer and Light C 05000p51 AUTH. NAME AUTHOR AFFILIATION NOODYi C. O. '

Florida Poeer 5 Light Co.

RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

"Semiannual Radioactive Effluent Release Rept:

Jul 86 Dec 86. " N/870302 ltr.

DISTRIBUTION CODE: IE48D COPIES RECEIVED: LTR ENCL

50. 36a(a) (2) Semiannual Ef fluent Release Reports SI2E'ITLE:

NOTES:

RECIPIENT COPIES RECIPIENT COP IEB ID CODE/NAME ID CODE/NAKE PMR-A PD2 LA PMR-A PSB LTTR ENCL

3 1 0 3

PAR-A PD2 PD 04 LTTR ENCL 5,5 INTERNAL: AEOD 1 1 AEOD/PTB 1 1 IE FILE 1 NRR BWR ADTS 1 1 NRR PhlR-A ADTS 1 1 NRR PAR-B *DTS 1 1 NRR/DSRO/RRAB 1 1 RGN2 =.

FILE 01 1 1 RGN2/DRSS/EPRPB 1 RM/DDAMI/NIB 1 1 EXTERNAL: LPDR NRC PDR 02 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 20

TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JULY I 986 THROUGH DECEMBER I 986 SU3MITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY (gj) g(g qg 870+050057 86 1 Z3 1 PDR ADOCK 05000Z50 R PDR C8:3

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT SLPPLEMENTAL INFORMATION JULY I 986 THROUGH DECEMBER I 986 .

I.O R viator Limits L~ii Effl a) The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentrations specified in IOCFR20, 8, Table II, Column 2 for radionuclides other than dissolved or 'ppendix entrained noble gases. For dissolved or entrained noble'ases, the concentration shall not exceed 2 x IO<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'<l.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'<I 0 mrem to any organ.

l.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 fol lowing:

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 l500 mrem/yr to any organ due to I-I3I, l-l33, 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'<IO mrad for beta radiation and, during any calendar year, to'<IO mrad for gamma radiation and'<20 mrad for beta radiation.

c) The dose per reactor to a member of the public, due to l-l3I, l-l33, 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 I5 mrem to any organ during any calendar year.

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07/86 - l 2/86 2.0 Maximum Permissible Concentrations The maximum permissible concentrations for liquid and airborne releases are described in Sections l.l-a and l.2-a of this report.

1.4 ~AE 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 l.2l was met or exceeded.

4.1 ~Li 144111 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 2m 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'nalysis 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'ach 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 2m 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.

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I I

07/86 - I 2/86 At least one representative batch of liquid effluent 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'onth 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 k

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-l33 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 July and August of l986, all short lived gaseous effluents were allocated to Unit 3 alone. This is due to Unit 4 being shut down during these months, and thus not contributing short lived isotopes.

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%t 07/86 - l2/86 .

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 + l 0%.

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 Avera e.Error Maximum Error Liquid +S% +l3%

Gaseous +6% + l 2%

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07/86 - I 2/86 5.0 BATCH RELEASES 5.I '~i uid Unit 3 Unit 4 a) Number of batch releases l.27 E+02 l.27 E+02 b) Total time period of batch releases I.I9 E+04 I.I9 E+04 Minutes c) Maximum time period for a batch release l.40 E+02 I .40 E+02 Minutes d) Average time period for a batch release 9.37 E+Ol 9.37 E+0 I Minutes e) Minimum time period for a batch release 5.50 E+Ol 5.50 E+Ol Minutes f) Average stream flow during periods of l.38 E+06 I.38 E+06'PM release of effluent into a flowing stream 5.2 Gaseous a) Number of batch releases 4.50 E+00 5.50 E+00 b) Total time period of batch releases l.28 E+04 5.55 E+02 Minutes')

Maximum time period for a batch release 6.00 E+02 2.40 E+02 Minutes d) Average time period for a batch release 2.83 E+02 I.O I E+02 Minutes e) Minimum time period for a batch release 3.00 E+Ol 3.00 E+0 I Minutes 6.0 UNPLANNED RELEASES

6. I ~Li uid a) Number of releases 0.00 E+00 0.00 E+00 b) Total activity released 0.00 E+00 0.00 E+00 Curies 6.2 Gaseous a) Number of releases 0.00 E+00 0.00 E+00 b) Total acti.vity released 0.00 E+00 0.00 E+00 Curies 6.3 See attachments (if applicable) for:

a) A description of the event and equipment involved.

b) Cause(s) for the unplanned release.

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07/86 - I 2/86 7.0 The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary assumes a visitor was on-site at the "Red Barn" recreational area for l2 hours 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 averaged hourly l986 meteorological data.

VISITOR DOSE SUMMATION JANUARY I 986 THROUGH DECEMBER l 986 UNITS 3 AND 4 Age Group: Adul t Location: Red Barn Inhalation Dose (mRem)

Bone 3.02 E-06 Liver I.I I E-03 Thyroid l.55 E-03 Kidney I. I I E-03 Lung I.I I E-03 GI-LLI I.IO E-03 Total Body I.I I E-03 NOBLE GAS EXPOSURE Gamma Air Dose 3.05 E-03 mRads Beta Air Dose 8.88 E-03 mRads 8.0 Offsite Dose Calculation Mcnual Revisions:

There were no ODCM revisions during this reporting period.

9.0 'olid Waste and Irratiated 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 6 of this report.

I 0.0 Process Control Pr ram Revisions There were no changes to the process control program during this reporting period.

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JLI Y. l 986 THROUGH DECEMBER I 986 UNIT3 TABLE I LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products I. otal elease not including tritium, gases, Ci al ha 4.64 E-02 3.5 I E-02

2. Average diluted concentration during period pCi/ml 7.00 E- I I 4.87 E-I I B. Tritium I. Total Release Ci 7.50 E+0 I 1.35 E+02

2. Average diluted concentration during period pCi/ml 6.04 E-06 8.II E-06'.

Dissolved and Entrained Gases I. Total Release Ci 3.80 E-02 3.76 E-02

2. Average diluted concentration during period pCi/ml 5.70 E-I I 5.20 E-I I D. Gross Alpha Radioactivity I. Total Release Ci <I.OI E-08 <8.64 E-09 E. Volume of Waste Released (prior to dilution) Liters I.87 E+06 l.37 E+06 F. Volume of Dilution Water Used During Period Liters 6.65 E+ I I 7.20 E+ I I h Based on Cooling Canal Tritium Concentration

+ MDA value in pCi/ml C8:3

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT

'EMIANNUALREPORT JQ Y l 986 THROUGH DECEMBER l 986 UNIT 3 TABLE 2 LIQUID EFFLUENTS Nucl ides Released Units Continuous Mode atch Mode Quarter Quarter Quarter 3 Quarter 4 Ag-I IOm Ci 4.IO E-04 2.25 E-05 Co-57 Ci 4.85 E-05 3.90 E-05 Co-58 Ci I.I I E-02 4.08 E-03 Co-60 Ci l.45 E-02 l.44 E-02 Cr-5 I Ci l.42 E-03 2.68 E-04 Cs-l34 Ci 5.IO E-04 l.08 E-03 7 l.62 E-03 2.99 E-03

's-l3 Fe-55 Ci 8.20 E-03 2.73 E-03 I-I3 I Ci I.OI E-03 l.20 E-03 I;l33 Ci 3.55 E-05 4.90 E-05 La- l40 Ci 2.28 E-04 2.59 E-04 Mn-54 Ci 3.34 E-04 l.86 E-03 Mo-99/Tc-99m Ci 5.25 E-05 I.85 E-05 Na-24 Ci 5.85 E-05 Nb-95 Ci 4.37 E-04 Ru- l03 Ci 5.I5 E-05 Sb-I 25 Ci 6.35 E-03 6.00 E-03 Sr-89 Ci < 3.00 E-08 <2.00 E-08 Sr-90 Ci < 5.00 E-09 <4.00 E-09 Te-l32 Ci 4.50 E-06 Zn-65 Ci 5.20 E-05 Zr-95 Ci 9.40 E-05 Ci Ci Ci Unidentified Ci otal for Period Above Ci '.64 E-02 3.5I E-02 (NOTE: Indicates Less than detectable activity)

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V FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY I 986 THROUGH DECEMBER I 986 UNIT 3 TABLE 2 (Continued)

LIQUIDEFFLUENTS Liquid Dissolved Gas Nuclides Released Units Continuous Mode Batch Mode Quarter 3 Quarter 4 Quarter 3 Quarter 4 Xe- I 3 I m 7.IO E-04 Xe- I 33 Ci 3.68 E-02 .3.49 E-02 Xe-'I 33m Ci I.95 E-04 8.70 E-04 Xe- I 35 Ci 2.69 E-04 l.79 E-03 Ci Ci Ci Ci otal for Period Above Ci 3.80 E-02 '.76 E-02 (NOTE: - Indicates Less than detectable activity)

LIQUID EFFLUENTS DOSE SUMMATION JANUARY I 986 THROUGH DECEMBER I 986 UNIT 3 Age,Group: Teenager Location: Cooling Canal Shoreline De osition Dose mRem)  % of Annual Limit Total Body 3.27 E-03 l.09 E-Ol C8:3

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JU Y l986 THROUGH DECEMBER l986 UNIT 3 TABLE 3 GASEOUS EFFLLXNTS SUMMATIONOF ALL RELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Gases I. Tota I Release Ci 7.30 E+02 8.64 E+02

2. Average Release Rate for Period iiCi/sec 9.29 E+0 I I.IO E+02

'B. 'Iodines I. Total Iodine- I 3 I Ci 3.06 E-03 l.25 E-02

2. Average Release Rate for Period Ii Ci/sec 3.89 E-04 l.59 E-03 C. Particulates I. Particulates T - I/2 )8 Days Ci 4.77 E-04 l.50 E-03

2. Average Release Rate for Period iiCi%ec 6.07 E-05 l.9 I E-04

3. Gross Alpha Radioactivity Ci 5.05 E-08 5.08 E-08 D. Tritium I. Total Release Ci 8.60 E+Ol 1.28 E+02

2. Average Release Rate for Period Ii C%iec l.09 E+Ol l.63 E+Ol

-IO-C8:3

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY I 986 THROUGH DECEMBER I 986 UNIT 3 TABLE 4 GASEOUS EFFLUENTS Nuclides Released Units Continuous Mode Batch Mode Q f 3 Quar fer 4 Quar fer 3 Quar fer 4 I. Fission and Activation Gases Ar-4 I Ci -l.59 E-0 I- 2.27 E-0 I 2.6 I E+00 l.9I E-Ol Kr-85 Ci 2. I 0 E-0 I Kr-85m Ci 6.9l E-02 I.20 E-0 I 7.04 E-02 l.23 . E-0 I Kr-87 Ci 2.I9 E-03 Kr-88 Ci 4.66 E-02 9.46 E-02 6. I 2 E-02 l.2I E-Ol Xe- l3 I m Ci 9.66 E-0 I 3. I 7 E+00 l.60 E+00 3.03 E+00 Xe- l33 Ci 5.39 E+02 5.3 I E+02 I.80 E+02 3.I7 E+02 Xe- I 33m Ci l.36 E+00 2.64 E+00 l.36 E+00 2.5l E+00 Xe- l35 Ci l.08 E+00 l.93 E+00 I. I 3 E+00 l.77 E+00 Ci Ci Unidentified Ci

'otal for Period Above Ci 5.43 E+02 5.39 E+02 I.87 E+02 3.25 E+02

2. Iodines I-I3 I I-l33 Ci 3.06 E-03 '.25 E-02 Ci 2.80 E-03 3.46 E-03 Ci Total for Period Above Ci 5.86 E-03 l.60 E-02 (NOTE: - Indicates Less than detectable activity)

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY I 986 THROUGH DECEMBER I 986 UNIT 3 TABLE 4 (Continued)

GASEOUS EFFLUENTS Nuclides Released Units Continuous Mode Quarter 3 Quarter 4

3. Particulates Ba- l40 Ci 5.85 E-05 l.59 E-04

. Co-58 Ci 3.55 E-05 2.75 E-05 Co-60 Ci 7.20 E-06 l.70 E-06 Cs-I 34 Ci 6.50 E-05 4.42 E-04 Cs- I 36 Ci 2.33 E-05 l.63 E-04 Cs- I 37 Ci 2.38 E04 5.20 E-04 I-I 3 I Ci l.38 E-OS 4.26 E-05 La- I 40 Ci 2.63 E-05 l.03 E-04 Mn-54 Ci 5.70 E-06 l.27 E-05 Sr-89 Ci 3.84 E-06 2.I4 E-OS Sr-90 Ci '< 3.79 E- I 6 '< I.26 E-I6 Ci Ci Ci Ci Ci Ci Ci Ci Unidentified Ci otal for Period Above Ci 4.77 E-04 l.50 E-03 (NOTE: - Indicates Less than detectable activity)

+ MDA in pCI/cc

- I 2-C8:3

'I APPENDIX 3 (Continued)

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY I 986 THROUGH DECEMBER I 986 UNIT 3 TABLE 5 DOSE DUE TO IODINE, H-3, AND PARTICULATES Pathway -

Bone Liver Thyroid Kidney Lung Gl-LLI Skin Total Body Cow Milk l.66 E-03 4.24 E03 2.42 E-Ol l.20 E-03 2.30, E-03 2.I7 E-03 2.67 E-03 ruit and 3.34 E-05 4. I 3 'E-04 8.83 E-03 4. I 6 E-04 3.66 E-04 V . Fresh 3.73 E-04 3.95 E-04 Ground Plane l.73 E-04 ~ I.73 E-04 l.73 E-04 I.73 E-04 I.73 E-04 l.73 E-04 l.98 E-04 .

I.73 E-04 Inhalation 3.I3 E-06 9.23 E-04 l.57. E-03 9.23 E-04 9.20 E-04 9.I7 E-04 9.20 E-04 Unit Totals mRem I.87 E-03 5.75 E-03 . 2.53 E-Ol 2.7I E-03 3.76 E-03 3.63 E-03 l.98 E-04 4.I6 E-03

% Annual Limit l.69 E+00 DOSE NOBLE GASES Gamma Air Dose (E) I.83 E-02 mRad I.83 E-0 I % of annual Limit Air Dose (E)

'eta 5.36 E-02 mRad 2.68 E-Ol % of annual Limit (A) 'ssumed cow 4.5 miles W of plant.

Age Group: Infant (B)(C)(D) Maximally exposed individual at garden (residence assumed), 3.6 miles WNW of plant.

Age Group: Adult (E) Maximum air dose occurs at 0.87 miles NW of plant.

k.

The dose values above were calculated using averaged hourly l 986 meterological data.

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I FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY I 986 THROUGH DECEMBER I 986 UNIT-4 TABLE I

" LIQUID EFFLUENTS - SUMMATIONOF ALL RELEASES Units Quarter 3, Quarter 4 A. Fission and Activation Products I. otal elease not including tritium, gases, al ha Ci 4.64 E-02 3.5I E-02

2. Average diluted concentration during period p Ci/ml 7.00 E-I I- 4.87 E-I I B. Tritium I. Total Release Ci 7.50 E+OI I.35 E+02

2. Average diluted concentration during period pCI/ml 6.04 E-06 8. I I E-Od C. Dissolved and Entrained Gases I. Total Release Ci 3.80 E-02 3.76 E-02

2. Average diluted concentration during period pCi/ml 5.70 E-I I 5.20 E-I I D. Gross Alpha Radioactivity I. Total Release Ci < I.OI E-08 <8.64 E-09 E. Volume of Waste Released (prior to dilution) Liters l.87 E+06 l.37 E+06 F. Volume of Dilution Water Used During Period Liters 6.65 E+ I I 7.20 E+ I I h Based on Coofing Canal Tritium Concentration

+ MDA value in pCi/ml

- l4-C8:3

E

FLORIDA POWER AND LIGHT COMPANY POINT PLANT 'URKEY SEMIANNUALREPORT JULY I 986 THROUGH DECEMBER I 986 UNIT 4 TABLE 2 (Continued)

LIQUID EFFLUENTS Liquid Dissolved Gas Nuclides Released ~ Units ontinuous Mode atch Mode Quarter 3 Quarter 4 Quarter 3 Quarter 4 Xe- I 3 lm Ci 7.IO E-04 Xe- I 33 Ci 3.68 E-02 3.49 E-02 Xe- I 33m Ci l.95 E-04 8.70 E-04 Xe- I 35 Ci 2.69 E-04 l.79 E-03 Ci Ci Ci Ci otal for Ci Period Above 3.80 E-02 3.76 E-02 (NOTE: -- Indicates Les's than detectable activity)

LIQUID EFFLUENTS - DOSE SUMMATION JANUARY I 986 THROUGH DECEMBER I 986 UNIT 4 Age Group: Teenager Location'. Cooling Canal Shoreline De osition Dose mRem)  % of Annual Limit

'otal Body 3.27 E-03 l.09 E-0 I

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY I 986 THROUGH DECEMBER I 986 UNIT 4 TABLE 3 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Gases I. Total Release Ci 5.37 E+Ol 2.73 E+02

2. Average Release Rate for Period pCi/sec ~ 6.83 E+00 3.47 E+0 I B. Iodines I. Total Iodine- I 3 I Ci 2.82 E-04 4.87 E-04

2. Average Release Rate for Period p Ci/sec 3.59 E-05 6.20 E-05 C. Particulates I. Particulates T - I/2 >8 Days Ci 4.62 E-04 I.50 E-03

2. Average Release Rate for Period 'pCi/sec 5.88 E-05 l.9I E-04

3. Gross Alpha Radioactivity Ci 5.05 E-08 5.08 E-08 D. Tritium I. Total Release Ci 8.60 E+Ol l.28 E+02

2. Average Release Rate for Period p Ci/sec I.09 E+0 I 1.63 E+0 I

-I 7-C8:3

FLORIDA POWER AND LIGHT COMPANY

~

TURKEY POINT PLANT SEMIANNUALREPORT JULY I 986 THROUGH DECEMBER I 986 UNIT 4 TABLE 4 GASEOUS EFFLUENTS ontinuous ode atch ode Quarter 3 Quarter 4 Quarter 3 Quarter 4 I. Fission and Activation Gases Ar-4 I Ci I.29 E-Ol 2.53 E-0 I 2.87 E-02 2.06 E-Ol Kr-85m Ci l.93 E-02 Kr-87 Ci 2. I 7 E-03 Kr-88 Ci l.68 E-02 Xe- I 3 lm Ci 3.83 E-0 I Xe-l33 Ci 5.29 E+Ol 2.70 E+02 5.48 E-0l 2.40 E+00 Xe- I 33m Ci 2.75 E-Ol Xe- I 35 Ci 3.9I E-02 3.69 E-Ol 6.86 E-02 8.20 E-02 Ci Ci Unidentified Ci otal for Ci 5.3I E+Ol 2.7I E+02 6.45 E-0I 2.69 E+00 Period Above

2. Iodines I- I 3 I Ci 2.82 E-04 4.87 E-04 I-I 33 9.90 E-04 '.6I E-04 Ci Total for Ci l.27 E-03 8.48 E-04 Period Above (NOTE: - - Indicates less than detectable activity)

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-I 8-

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY l 986 THROUGH DECEMBER I 986 UNIT 4 TABLE 4 (Continued)

GASEOUS EFFLUENTS Nuclides Released Continuous Mode Units Quarter 3 Quarter 4

3. Particulates Ba-l40 Ci 5.85 E-05 I.59 E-04 Co-58 Ci 3.55 E-05 2.75 E-05 Co-60 Ci 7.20 E-06 l.70 E-06 Cs- I 34 Ci 6.50 E-05 4.42 E-04 Cs- I 36 Ci 2.33 E-05 l.63 E-04 Cs- I 37 Ci 2.38 E-04 5.20 E-04 I- I 3 I Ci 4.26 E-05 L~I40 Ci 2.63 E-05 I.03 E-04 Mn-54 Ci 5.70 E-06 l.27 E-05 Sr-89 3.84 E-06 2. I 4 E-05 Sr-90 Ci '<3.79 E-I6 '< I.26 E-I6 Ci Ci Ci Unidentified Ci ota or Above

'eriod Ci 4.62 E-04 l.50 E-03 (NOTE: - - Indicates Less than detectable activity)

+ MDA in pCI/cc

-l9-C8:3

l APPENDIX 3 (Continued)

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY I 986 THROUGH DECEMBER I 986 UNIT 4 TABLE 5 DOSE DUE TO IODINE, H-3, AND PARTICULATES Pathway Bone Liver Thyroid Kidney Lung Gl-LLI Skin Total Body (A I.IO E-03 3.59 E-03 E-02 Cow Milk . 2.92 l.04 E-03 2.30 E-03 2.I5 E-03 2.29 E-03 ruit and '.72 E-05 3.90 E-04 V .(Fresh) l.23 E-03 3.76 E-04 3.66 E-04 3.67 E-04 3.82 E-04 Ground P Jane l.66 E-04 l.66 E-04 l.66 E-04 l.66 E-04 l.66 E-04 l.66 E-04 l.93 E-04 I.66 E-04 Inhalation I.88 E-06 9.20 E04'.99 E-04 9.20 E-04 9.20 E-04 9.I7 E-04 9.20 E-04 Unit Totals (mRem 1.29 E-03 ~ 5.07 -E-03 3.I6 E-02 2.50 E-03 3.75 E-03 3.60 E-03 l.93 E-04 3.76 E-03

% Annual Limit 2.1 I E-Ol DOSE NOBLE GASES Gamma Air Dose(E) 5.08 E-03mRad 5.08 E-02% of annual Limit Beta Air Dose( ) l.46 E-02 mRad 7.30 E-02 % of annual Limit (A) Assumed cow 4.5 miles W of plant.

Age Group: Infant (B)(C)(D) Maximally exposed individual at garden (residence assumed), 3.6 miles WNW of plant.

Age,Group. Adult (E) Maximum air dose occurs at 0.87 miles NW of plant.

The dose values above were calculated using averaged hourly l 986 meterological data.

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FLORIDA POWER AND LIGHT CONPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY'1986 THROUGH DECBSER 1986 UNITS 3 AND 4 TABLE 6A SOLID WASTE AND IRRADIATED FUEL SHIPHENTS A. SOLID 'WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. Type of Waste UNIT 6 NONTH PERIOD ERROR%

a ~ Spent Resins, Filter sludges m 5.72 EO evaporator bottoms, etc. Ci 9.44 E-1 2.0 ~

E+1

b. Dry Compressible Waste m3 1.58 E+2 Ci 8.48 E-1 2.0 E+1 C ~ Irradiated Components m3 0.00 EO Control rods, etc. Ci O.OO,EO

d. Other m3 0.00 EO Ci 0.00 EO

2. Estimate of Ha)or Nuclide Composition (by type of waste)

'a 0 Fe55 26 H3 24 Co60 23 17" Co 58 Ni 4 Csl 37 2 Hn54 1

b. Co60 35 Csl37 23 Fe55 16 Co58 10 Csl34 7 Ni63 6 Sb125 1 C ~

d.

3. Solid Waste Disposition Number of Shi ments Node of Trans ortation Destination 10 Sole Use Truck Barnwell, S.C.

B. IRRADIATED FUEL SHIPKIITS Number of Shi ments Node of Trans ortation Destination 0 N/A N/A H/A - Not applicable GLL/eb/016

FLORIDA POWER 5 LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1986 THROUGH DECENER 19&6 UNITS 3 AND 4 TABLE 6B SOLID WASTE SUPPLEHENT (Note 1)

Total Total (Notes 1.2) (Note 3) (Note 4)

Waste Volume Curie Principal Type of R.G. 1.21 Type of Solidification or

'Cl assi fi cation . Ft3 quantity Radionuclides Waste Category Container Absorbent Agent Class A 5581 .85 None PWR l.b Non-Spec N/A Trash Strong, Tight Package Class A 202 .94 None PWR Ion 1.a NRC Certified N/A Exchange LSA ) Type A Resins GLL/eb/022/1

FLORIDA POWER 5 LIGHT COMPANY TURKEY, POINT UNIT NOS. 3 5 4 SEMI-ANNUAL REPORT JULY 1986 THROUGH DECEMBER 1986 TABLE 6B (CONTINUED)

SOLID WASTE SUPPLEMENT NOTE I: The total curie quantity and radionuclide composition of solid waste shipped from. the Turkey Point Units 3 8 4 are determined 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/ll/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. ttass) calculations. Where appropriate, engineering type activation analyses may be applied.

Since each of the above methodologies involves to some extent qualitative parameters, the total curie quantity is considered to be an estimate.

The composition of radionuclides in the waste is determined by both on-site analyses for principal gamma emitters and periodic off-site analyses for other radionuclides. The on-site analyses are performed either on a batch basis or on a routine basis using reasonably representative samples as appropriate for the waste type. Offiste analyses are used to establish scaling factors or other estimates for radionuclides such as 3H, 1IC, 99Tc 1291, TRU 241Pu 242Cm, 63Ni and 55Fe NOTE 2: ,"Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than .Ol times the concentration of the nuclide listed in Table 1 or .Ol times the smallest concentration of that nuclide listed in Table 2 of 10CFR61.

NOTE 3: "Type of Waste" is generally specified as described in- NUREG 0782, Draft Environment Impact Statement on 10CFR61 "Licensing Requirements for Land Disposal of Radioactive Waste".

NOTE 4: "Type of Container" refers to the transport package.

GLL/eb/003

P, O. BOX 14000, JUNO BEACH, FL 33408 0420 MARCH 02 1987 L I 05 U. S. Nuclear Regulatory Commission Attn: 'Document Control Desk Washington, D. C. 20555 Gent lemen:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-25 I-Semi-Annual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of July I, l986 through December 3l, l986 for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.4.

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

Very truly yours,

~ C.O. W y

++ Group Vice President Nuclear Energy COW/PLP/gp Attachment cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant

~q8 i I an FPL Group company PLP I /04 I / I

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