ML17347B597

Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989. W/900302 Ltr

ML17347B597
Person / Time
Site:	Turkey Point
Issue date:	12/31/1989
From:	Pearce L, Quinn S, Steinke R FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-90-79, NUDOCS 9003130315
Download: ML17347B597 (62)

Text

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REGULATORY INFORMATION DISTRXBUTION SYSTEM '(RIDS)

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 QUXNN,S. Florida Power & Light Co.

STEXNKE,R.N. Florida Power & Light Co. R PEARCE,L.W. Florida Power &'ight Co.

RECXP.NAME RECXPIENT AFFILIATION

SUBJECT:

"Semiannul Radioactive Effluent Release Rept Jul-Dec 1989." D 900302 ltr.

DISTRIBUTION CODE:.IE48D COPIES RECEIVED:LTR ENCL t SIZE: 8'I TITLE: 50.36a(a)(2) Semiannual Effluent Release Reports NOTES:

RECIPXENT COPIES RECIPIENT COPXES ID CODE/NAME PD2-2 LTTR ENCL CODE/NAME PD2-2 PD

'D LTTR ENCL LA 3 3 . 1 1 EDXSON, G 1 . 1 INTERNAL: AEOD DSP/TPAB 1 1 IRM TECH.'ADV 1 1 RK PB11 2 2 NUDOCS-ABSTRACT 1 '1' G FXLE 01 1 1 RGN2 DRSS/RPB 2 RGN2 FILE 02 1 1 EXTERNAL BNL TICHLERg J03 1 1 EG&G S IMPSON g F 2 2 LPDR 1 1 NRC PDR 1 R

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D NOTE TO ALL "RIDS" RECIPIENTS:

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PLEASE HELP US TO REDUCE %ASFEl CONTACT THE.DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL g 1 19 (2 gZ/

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P.. Box 029100, Miami, FI33102-9100 L-9 0-7 9 MAR O 2 $ 990 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 50-25 1 Semi-Annual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of July 1, 1 9 89, through December 3 1, 1 9 89, for Turkey Point Units 3 and 4, as required by Technical Specif ication 6~9~4 ~

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

Very tru ly yours, K. N. Harris Site Vice President Turkey Point Plant Nuclear KNH / DPS / dp s Attachment cc: Stewart D ~ Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant I

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TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUALRADIOACTIVEEPPLUENT RELEASE REPORT JULY 1989 THROUGH DECEMBER 1989 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT I

PLORIDA POWER AND LIGHT COMPANY

. Quinn teinke Radiochemist Chemistry Supervisor L. W. Pearce J. L<'. ross Operations Superintendent Plant Manager-Nuclear

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07/89 12/89 INDEX Page 1.0 Regulatory Limits 1.1 Liquid Effluents 1.2 Gaseous Effluents 2.0 Maximum Permissable Concentrations 3.0 Average Energy 4.0 Measurements and Approximation of Total Radioactivity 4.1 Liquid Effluents - discussion

a. Unit 3 Liquid Effluents Summation

b. Unit 4 Liquid Effluents Summation 14 4.2 Gaseous Effluents discussion

a. Unit 3 Gaseous Effluent Summation 10

b. Unit 4 Gaseous Effluent Summation 4.3 Estimate of Errors 5.0 Batch Releases 5.1 Liquid 5.2 Gaseous 6.0 Unplanned Releases 7.0 Reactor Coolant Activity 8.0 Site Radiation Dose 9.0 Offsite Dose Calculation Manual Revisions 10.0 Solid Waste and Irradiated Puel Shipments 11.0 Process Control Program Revisions

1 j r PLORIDA POWER AND LIGHT C~ANY TURKEY POINT UNITS 3 A~4 EFPLUENT AND WASTE DISPOSAL SEMIANNUALREPORT SUPPLEMENTAL INPORMATION JULY 1989 THROUGH DECEMBER 1989 1.0 Re lato Limits 1.1 Li uid Effluents a) The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentrations specified in 10CPR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. Por 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 s3 mrem to the total body and s10 mrem to any organ.

1.2 Gaseous Effluents a) The dose rate due to radioactive materials released in gaseous,effluents from the site to areas at and beyond the site boundary shall be, limited to the following:

Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin due to noble gases and less than or equal to 1500 mrem/yr to any organ due to I-131, I-133, tritium and for all radioactive materials in particulate form with half lives greater than 8 days.

b) The air dose per reactor to areas at and beyond the site boundary due to noble gases released in gaseous effluents shall be limited, during any calendar quarter, to (5 mrad for gamma radiation and ~10 mrad for beta radiation and, during any calendar year, to s10 mrad for gamma radiation and ~20 mrad for beta radiation.

c) The dose per reactor to a member of the public, due to I-131, I-133, tritium and to particulates with half-lives greater than 8 days in airborne effluents released to areas at and beyond the site boundary shall not exceed 7.5 mrem to any organ during any calendar quarter and shall not exceed 15 mrem to any organ during any calendar year.

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~ Maximum Permissible Concentrations Water: As per 10CPR20 Part 20, Appendix B, Table II, Column 2, except for entrained or

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dissolved noble gases as described in 1.1.A of this report.

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Air: Release concentrations are limited to dose rate limits described in 1.2.A.

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.

Where alpha, tritium and named nuclides are shown as - curies, this should be interpreted as "no activity was detected on the samples using the Plant Technical Specification analyses techniques to achieve required Lower Level of Detection (LLD) sensitivity for radioactive effluents".

4.1 Li uid Hffluents Aliquots of representative pre-release samples were isotopically analyzed for gamma emitting isotopes on a multichannel analyzer.

The above procedure was followed for all releases from the waste disposal system.

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 2n gas flow proportional counter. The quarterly composite was analyzed for Sr-89/90 and Pe-55 by chemical separation.

All radioactivity concentrations determined from analysis of a pre-release composite were multiplied by the total represented volume of the liquid waste released to determine the total quantity of each isotope and of gross alpha activity released during the compositing period.

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07/89 12/89 Aliquots of representative pre-release samples from the waste disposal system were analyzed on a per release basis for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released in order to estimate the total dissolved gases released.

The liquid waste treatment system is shared by both units at the site and generally all liquid releases are allocated on a 50/50 basis to each unit.

4.2 Gaseous Effluents Airborne releases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and releases incidental to operation of the plant. The techniques employed in determining the radioactivity in airborne releases are:

a) Gamma spectrum analysis for fission and activation gases, b) Removal of particulate material by filtration and subsequent gamma-spectrum analysis, Sr-89/90 determination and gross alpha analysis, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma-spectrum analysis, and d) Analysis of water vapor in a gas sample for tritium using liquid scintillation techniques.

All gas releases from the plant which were not accounted for by the above methods were conservatively estimated as curies of Xe-133 by use of the plant vent process monitor recorder chart and the current calibration curve for the monitor.

Portions of the gas waste treatment system are shared by both units and generally all gas releases from the shared system are allocated on a 50/50 basis to each unit.

Meteorological data for the period January, 1989 to December, 1989, in the form of Joint Prequency Distribution Tables is maintained on-site.

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07/89 - 12/89 4.3 Estimate of Errors a) Sampling Error The error associated with volume measurement devices, flow measuring devices, etc., based on calibration data and design tolerances has been conservatively estimated to be collectively less than 2 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 e Maximum Error Liquid +11 Gaseous 5.0 BATCH RELEASES 5.1 ~Lt <<id Unit 3 Unit' a) Number of batch releases 1.53 E+02 1.53 E+02 b) Total time period of batch releases 1.11 E+04 1.11 E+04 Minutes c) Maximum time period for a batch releases 1.65 E+02 1.65 E+02 Minutes d) Average time period for a batch release 7.25 E+01 7.25 E+01 Minutes e) Minimum time period for a batch release 3.10 R+01 3.10 E+01 Minutes f) Average stream flow during period of 1.61 E+06 1.61 E+06 GP M release of effluent into a flowing stream 5.2 Gaseous a) Number of batch releases 6.00 E+00 9.00 E+00 b) Total time period of batch releases 2.28 E+02 9.48 E+02 Minutes c) Maximum time period for a batch release V.50 E+01 2.40 E+02 Minutes d) Average time period for a batch release 3.80 E+01 1.05 E+02 Minutes e) Minimum time period for a batch release 1.50 E+01 1.50 8+0 1 Minutes RNSI<LQACIIFI<lljlSh <<I((<<:<<<>

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~ 07/89 - 12/89 6.0 UNPLANNED RELEASES 6.1 Liciuid UNIT 3 UNIT 4 a) Number of releases 5.00 E-01 5.00 E-01 b) Total activity released 1.02 E-05 1.02 E-05 Curies 6.2 Gaseous a) Number of releases b) Total activity released ~ 0 0 Curies 6.3 See Attachment 1 for:

a) A description of the event and equipment involved.

b) Cause(s) for the unplanned release.

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

8.0 The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site 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. Specific activities used in these calculations are the sum of activities in Unit 3, Table 3 and Unit 4, Table 3. These dose calculations were made using historical meteorological data.

VISITOR DOSE SUMMATION JANUARY 1989 THROUGH DECEMBER 1989 UNITS 3 AND 4 Age Group: Adult Location: Red Barn Inhalation Bone 3.43 E-08 Liver 1.75 E-05 Thyroid 3.19 E-05 Kidney 1.76 E-OS Lung 1.78 E-05 GI-LLI 1.75 E-05 Total Body 1.75 E-05 NOBLE GAS EXPOSURE

, Gamma Air Dose 2.92 E-03 mRads Beta Air Dose 8.62 E-03 mRads llNSlil<<ld (lilac'.ll l>ISKllll1irai1 l o P

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~ l 9.0 Offsite Dose Calculation Manual Revisions See Attachment 2 10.0 Solid Waste and Irradiated Puel Shi mentsNo irradiated fuel shipments were made from the site. Common solid waste from Turkey Point Units 3 and 4 were shipped jointly. A summation of these shipments is given in Table 6 of this report.

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

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t FLORIDA POWER AND LIGHT CQ+PANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1989 THROUGH DECEMBER 1989 0 UNIT 3 TABLE 1 LIQUID EFFLUENTS SUMMATIONOF ALL RELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release (not including tritium, gases, 3.97 E-02 al ha Ci 4.35 E-02

2. Average diluted concentration during period pCi/ml 6.47 E-10 5.86 E-10 B. Tritium

1. Total Release Ci 6.68 E + 01 1.31 E + 02

2. Average diluted concentration during period pCi/ml 1.09 E-06 1.76 E-06 C. Dissolved and Entrained Gases

1. Total Release Ci 7.49 E-02 7.69 E-01 Average diluted concentration during period pCi/ml 1.22 E-09 1.03 E-08 D. Gross Alpha Radioactivity

1. Total Release Ci (6.95 E-08* (1.31 E-08*

E. Volume of Batch Waste Released (prior to dilution) Liters 1.37 E+06 1.63 E+ 06 F. Volume of Continuous Waste Released (prior to dilution) Liters G. Volume of Dilution Water Used During Period Liters 6.14 E+10 7.43 E+10

• MDAValue in pCi/ml lrNSIDAJ+Clll"'hfl)ISK P l(liJ90) l 0

ORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 3 TABLE 2 LIQUID EPPLUENTS - SUMMATIONOP ALL RELEASES Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Na-24 Ci 4.88 E-06 2.87 E-05 Cr-51 Ci 8.29 E-05 1.60 E-04 Mn-54 Ci 1.46 E-03 1.05 E-03 Fe-55 Ci 1.35 E-02 1.49 E-02 Co-57 Ci 1.40 E-05 Co-58 Ci 1.94 E-03 3.78 E-03 Fe-59 Ci 1.78 E-05 Co-60 Ci 7.91 E-03 1.01 E-02 Zn-65 Ci 1.11 E-05 Sr-90 Ci 6.57 E-05 Nb-95 Ci 1.31 E-05 5.45 E-06 Zr-97 Ci 2.58 E-06 Ag-110 Ci 9.46 E:04 4.72 E-04

-1 17m Ci 3.53 E-06

-124 Ci 5.01 E-04 8.94 E-05 Sb-125 Ci 6.73 E-03 1.23 E-02 I-131 Ci 2.49 E-04 1.00 E-04 Cs-134 Ci 1.61 E-03 6.43 E-05 Cs-137 Ci ,4.64 E-03 4.62 E-04 unidentified Ci Total for Period Above Ci 3.97 E-02 4.35 E-02 RNSIDh J*Clll)htDISK//l(1990) i.

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ORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 3 TABLE 2 (Continued)

LIQUID EPPLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units V

Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85 Ci 7.55 E-07 Kr-85m Ci 3.73 E-05 Xe-131m Ci 5.18 E-04 1.25 E-02 Xe-133 Ci 7.44 E-02 7.51 E-01 Xe-133m Ci 7.60 E-06 4.52 E-03 Xe-135 Ci 1.33 E-05 5.55 E-04 Xe-135m Ci 1.51 E-06 3.34 E-05 Total for Period Above Ci 7.49 E-02 7.69 E-01 LIQUID EFFLUENTS-DOSE SUMMATION JANUARY 1989 THROUGH DECEMBER 1989 UNIT 3 Age Group: Teenager Location: Cooli'ng Canal Shoreline De osition Dose mRem  % of Annual Limit Total Body 1.93 E-03 6.43 E-02 RQSII)h JA CllEh1 1)ESKER l(lJ'J'0) l 0'

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ORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 3 TABLE 3 GAS EPPLUENTS - SUMMATIONOp ALL RELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release Ci 5.79 E + 02 5.47 E + 02

2. Average Release Rate for Period pCi/sec 7.28 E + 01 6.88 E + 01 B. lodines

1. Total Iodine-131 Ci 4 22 E-05 6 89 E-05

2. Average Release Rate for Period pCi/sec 5.31 E-06 8.67 E-06 articulates

1. Particulates T-1/2)8 Days Ci <1.00 E-13* (1.76 E-144

2. Average Release Rate for Period pCi/sec

3. Gross Alpha Radioactvity Ci (5.99 E-16* (7.37 E-16*

D. Tritium

1. Total Release Ci 1.46 E+ 00 2.22 E + 00

2. Average Release Rate for Period pCi/sec 1.84 E-01 2.79 E-01

• (MDAValues Expressed in pci/ml IIHSIDAJ AS CII Yhl DISh; 1I I(1990)

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LORIDA POWER AND LIGHT CO NY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 3 TABLE 4 GASI?OUS EPPLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission Gases Ar-41 Ci 1.49 E-01 1.36 E-01 2.48 E-01 Kr-85 Ci 1.33 E+ 00 3.31 E-01 Kr-85m Ci 1.44 E-03 3.42 E-03 3.38 E-05 Xe-131m Ci 9.49 E-02 3.70 E-01 2.89 E-01 2.84 E-01 Xe-133 Ci 5 59 E+02 5.29 E+ 02 1.95 E+ 01 1.53 E+ 01 Xe-133m Ci 6.85 E-02 6.81, E-02 8.76 E-02 9.28 E-02 Xe-135 Ci 4.46 E-02 4.74 E-02 6.12 E-03 4.18 E-03 Xe-135m Ci Ci Unidentified Ci Total for Ci Period Above 5.59 E + 02 5.31 E+ 02 1.99 E+ 01 1.63 E+ 01

2. Iodines I-131 Ci 4.22 E-05 6.89 E-05 I-133 Ci 1.98 E-05 5.60 E-05 Ci Total for Ci Period Above 6.20 E-05 1.25 E-04 ltNS/IJi1 J 4CIII.'hf l)lSK 4 l(lJ'90)

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LORIDA POWER AND LIGHT CO~NY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 3 TABLE 4 (Continued)

GASEOUS EPPLUENTS Continuous Mode Nuclides Released Units Quarter 3 Quarter 4

3. Particulates I-131 Ci (1.00 E-134 (1.76 E-14*

Ci Ci Ci Ci Ci Ci Unidentified Ci Total for Period Above Ci ( 1.00 E-13* (1.76 E-14*

• (MDAValues Expressed in pCi/ml llNSIDAJ)t CllEhf DISK&1(1J'90)

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PLORIDA POWE LIGHT COMPANY TURK INT PLANT SEMIA AL REPORT JULY 1989 THROUGH DECEMBER 1989 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- Infant 1.37 E-05 4.81 E-05 4.67 E-03 1.76 E-05 3.20 E-05 3.24 E-05 4.04 E-05 Fruit 8 Veg - Fresh 5.75 E-07 3 92 E 05 2 16 E 04 3 94 E 05 3.84 E-05 3.90 E-05 3.89 E-05 Ground Plane 3.46 E-06 3.46 E-06 3.46 E-06 3A6 E-06 3.46 E-06 3A6 E-06 4.05 E-06 3.46 E-06 Inhalation - Adult 2.88 E-08 1.43 E-05 2 64 E-05 1.44 E-05 1.45 E-05 1 A3 E-05 1.43 E-05 Unit 1.78 E-05 1.05 E-04 4 92 E-03 7 49 E-05 8.84 E-05 8.92 E-05 4.05 E-06 9.71 E-05 Totals (mRem)

% Annual Limit 1.19 E-04 7.00 E-04 3.28 E-02 4.99 E-04 5.89 E-04 5.95 E-04 2.70 E-05 6.47 E-04 DOSE NOBLE GASES Gamma Air Does 1.12 E-02 mRad  % of Annual Limit 1.12 E-01 %/Yr Beta Air Dose 3.31 E-02 mRad  % of Annual Limit 1.65 E-01 %/Yr

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ORIDA POWER AND LIGHT CO NY TURKEY POINT PLANT SEMIANNUALREPORT e JULY 1989 THROUGH DECEMBER 1989 UNIT 4 TABLE 1 LIQUID EPPLUENTS SUMMATIONOP ALL RELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release (not including tritium, gases, 3.97 E-02 al ha Ci 4.35 E-02

2. Average diluted concentration during period pCi/ml 6.47 E-10 5.86 E-10 B. Tritium

1. Total Release Ci 6.68 E+ 01 1.31 E+ 02

2. Average diluted concentration during period pCi/ml 1.09 E-06 1.76 E-06 C. Dissolved and Entrained Gases

1. Total Release Ci 7.49" E-02 7.69 E-01 Average diluted concentration during period pCi/ml 1.22 E-09 1.03 E-08 D. Gross Alpha Radioactivity

1. Total Release Ci <6.95 E-08* <1.31 E-08*

E. Volume of Batch Waste Released (prior to dilution) Liters 1.37 E+06 1.63 E+ 06 F. Volume of Continuous Waste Released (prior to dilution) Liters G. Volume of Dilution Water Used During Period Liters 6.14 E+10 7.43 E+10

• MDAValue in pCi/ml ltNSIDAJ kClll:Af lJISK 41(19J'0)

I LORIDA POWER AND LIGHT CO~NY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1989 THROUGH DECEMBER 1989 0 Nuclides Released Units UNIT 4 TABLE 2 LIQUID EPPLUENTS SUMMATIONOP ALL RELEASES Continuous Mode Batch Mode Quarter 3 Quarter 4 Quarter 3 Quarter 4 Na-24 Ci 4.88 E-06 2.87 E-05 Cr-51 Ci 8.29 E-05 1.60 E-04 Mn-54 Ci 1.46 E-03 1.05 E-03 Fe-55 Ci 1.35 E-02 1.49 E-02 Co-57 Ci 1.40 E-05 Co-58 Ci 1.94 E-03 3.78 E-03 Fe-59 Ci 1.78 E-05 Co-60 Ci 7.91 E-03 1.01 E-02 Zn-65 Ci 1.11 E-05 Sr-90 Ci 6.57 E-05 Nb-95 Ci 1.31 E-05 5.45 E-06 Zr-97 Ci 2.58 E-06 Ag-110 Ci 9.46 E-04 4.72 E-04 Ci 3.53 E-06

-124 Ci 5.01 E-04 8.94 E-05 Sb-125 Ci 6.73 E-03 1.23 E-02 1-131 Ci 2.49 E-04 1.00 E-04 Cs-134 Ci 1.61 E-03 6.43 E-05 Cs-137 Ci 4.64 E-03 4.62 E-04 Ci Ci Ci Ci Unidentified Ci Total for Period Above Ci 3.97 E-02 4.35 E-02 RNSllMJ )0 Clll"'hfl)ISKk'I(lJ'90)

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TURKEY POINT PLANT SEMIANNUALREPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 4 TABLE 2 (Continued)

LIQUID EPPLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85 Ci 7.55 E-07 Kr-85m Ci 3.73 E-05 Xe-131m Ci 5.18 E-04 1.25 E-02 Xe-133 Ci 7.44 E-02 7.51 E-01 Xe-133m Ci 7.60 E-06 4.52 E-03 Xe-135 Ci 1.33 E-05 5.55 E-04 Xe-135m Ci 1.51 E-06 3.34 E-05 Total for Period Above Ci 7.49 E-02 7.69 E-01 LIQUID EFFLUENTS-DOSE SUMMATION JANUARY 1989 THROUGH DECEMBER 1989 UNIT 4 Age Group: Teenager Location: Cooling Canal Shoreline De osition Dose mRem  % of Annual Limit Total Body 1.93 E-03 6.43 E-02 lfNS/l)AJ+CflEAf l)ISK Pl(l 9 J'0) 0 1 y

LORIDA POWER AND LIGHT CO~NY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 4 TABLE 3 GAS EPPLUENTS SUMMATIONOP ALL RELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products

1. Total Release Ci 5.89 E+ 02 5.50 E+ 02

2. Average Release Rate for Period pCi/sec 7.40 E + 01 6.92 E + 01 B. lodines

1. Total Iodine-131 Ci 4.22 E-05 6.89 E-05

2. Average Release Rate for Period pCi/sec 5.31 E-06 8.67 E-06 articulates

1. Particulates T-1/2>8 Days Ci (1.00 E-13* 9.04 E-08

2. Average Release Rate for Period pCi/sec 1.14 E-08

3. Gross Alpha Radioactvity Ci (5.99 E-16" (7.37 E-16*

D. Tritium

1. Total Release Ci 1.53 E+00 2.31 E+00

2. Average Release Rate for Period pC%iec 1.93 E-01 2.91 E-01

• MDAValues Expressed in pCi/ml IIHSIDAJ+Cllklhl I)ISK III(IOJ'0) 0 0 1 4

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LORIDA POWER AND LIGHT CO NY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1989 THROUGH DECEMBER 1989 0 UNIT 4 TABLE 4 GASEOUS EPPLUI? NTS Continuous Mode Batch Mode Nuclides Released Units Quarter 3 Quarter 4 Quarter 3 Quarter 4 1 ~ Fission Gases Ar-41 Ci 1.03 E-01 2.64 E-01 1.90 E-02 4.24 E-01 Kr-85 Ci 3.31 E-01 Kr-85m Ci 1.15 E-03 1.74 E-02 2.68 E-03 2.09 E-02 Kr-87 Ci 1.40 E-03 Xe-131m Ci 6.52 E-02 6.00 E-02 2.89 E-01 2.84 E-01 Xe-133 Ci 5.57 E+ 02 5.31 E+ 02 3.02 E+ 01 1.63 E + 01 Xe-133m Ci 4.19 E-02 1.24 E-01 1.98 E-01 1.44 E-01 Xe-135 Ci 4.59 E-02 7.04 E-01 8.87 E-02 4.26 E-01 Ci Unidentified Ci Total for Period Above Ci 5.57 E+ 02 5.32 E+ 02 3.08 E+ 01 1.79 E+ 01

2. lodines I-131 Ci 4.22 E-05 6.89 E-05 l-133 Ci 1.98 E-05 5.60 E-05 Ci Total for Period Above Ci 6.20 E-05 1.25 E-04 IINSIDAJ A CIII ht DISK III(l3'90) 0 I

LORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 4 TABLE 4 (Continued)

GASEOUS EPPLUENTS Continuous Mode Nuclides Released Units Quarter 3 Quarter 4

3. Particulates Co-60 Ci 9.04 E-08 l-131 Ci (1.00 E-13*

Ci Ci Ci Ci Unidentified Ci Total for Period Above Ci <1.00 E-13* 9.04 E-08

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PLORIDA POWE LIGHT COMPANY TURK INT PLANT SEMIA AL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 4 TABLE 5 DOSE DUE TO IODINE, H-3, AND PARTICULATES Pathway Bone Liver Thyroid Kidney Lung Gl-LLI Skin Total Body Cow Milk- Infant 1.29 E-05 4.89 E-05 4.54 E-03 1.08 E-05 3.30 E-05 3.34 E-05 4.12 E-05 Fruit & Veg - Fresh 5.64 E-07 4.03 E-05 2.12 E-04 4.05 E-05 3.95 E-05 4.01 E-05 4.00 E-05 Ground Plane 3.48 E-06 3.48 E-06 3.48 E-06 3.48 E-06 3.48 E-06 3.48 E-06 '4.08 E-06 3.48 E-06 Inhalation - Adult 2.81 E-08 1.48 E-05 2.66 E-05 1.49 E-05 1.50 E-05 1.48 E-05 1.48 E-05 Unit 1.70 E-05 1.07 E-04 4.78 E-03 6 97 E-05 9.10 E-05 9.18 E-05 4.08 E-06 9.95 E-05 Totals (mRem)

% Annual Limit 1.13 E-04 7.13 E-04 3.19 E-02 4.65 E-04 6.07 E-04 6.12 E-04 2.72 E-05 6.63 E-04 DOSE NOBLE GASES Gamma Air Does 1.12 E-02 mRad  % of Annual Limit 1.12 E-01 %/Yr Beta Air Dose 3.31 E-02 mRad  % of Annual Limit 1.65 E-01 %/Yr I

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LORIDA POWER AND LIGHT CO NY TURKEY POINT PLANT SEMIANNUALREPORT JULY 1989 THROUGH DECEMBER 1989 ATTACHMENT 1 On December 18, 1989 B Monitor Tank (B-MT) was inadvertently released instead of B-Waste Monitor Tank (B-WMT) (Reference Florida Power and light Letter L-90-65, dated February 16, 1990).

The inadvertent release of the B-MT liquid waste instead of the B-WMT was personnel error. The Nuclear Operator (NO) made a log entry that the B-WMT was to be released. However, the NO had earlier observed that the B-MT was on recirculation prior to release; the NO upon being notified that the B-WMT was to be released, inadvertently went to the B-MT section of procedure OP-5163.3, Waste Disposal System Controlled Liquid Release to the Circulating Water, which resulted in the release of the B-MT Tank.

Contributing factors were the similarity in names of the two tanks along with the NO previously observing the B-MT on recirculation. Additionally, the procedure did not 'require an independent verification of the tank to be released against the Liquid Release Permit.

Corrective steps which have been taken and the results achieved:

a. The responsible operator was disciplined.

b. This incident was recorded in the night order book to inform all operations personnel.

Procedures OP-5163.3, Waste Disposal System - Controlled Liquid Release to the Circulating Water and OP-5523.1, Waste Disposal System Gas Decay Tank,Controlled Release to Atmosphere, have each been revised to include an independent verification to validate the tank to be released against the appropriate Release Permit.

d. The Liquid Release Permit form was modified by replacing "tank" entry portion of the form with check boxes for each tank. The Gas Release Permit was reviewed and no changes were deemed necessary.

The "B" Monitor Tank had been sampled at 2254 EST on December 17, 1989 in preparation for release after the "B" Waste Monitor Tank. The "B" Monitor Tank sample was well within Technical Specification limits for a legal waste release.

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 ATTACHMENT 2 On November 9, 1989, the Offsite Dose Calculation Manual revision was PNSC approved, clarifying the location of the Steam Generator Blowdown Radiation Monitors (R-3/4-19). No changes to the calculational methods contained in the Offsite Dose Calculation Manual were instituted during this period.

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PLORIDA POWE LIGHT COMPANY wsc TURKE NT PLANT APPROV DATE SEMIAN L REPORT JULY 1989 THROUGH DECEMBER 1989 PLT. MGR ~< DATE~~

APPROVA ATTACHMENT2 (Cont'd)

Pr lmary Primary Turbines Turbines oop Unit 3 Unit 4 oop on ensers Reactor Reactor Steam GQeNto Generator Condensers B lowdown CVCS 3 cvcs p-v-I'p P- X-I'I B 1owd own Hakeup water Slowdown Vent to flash and chemicals flash Vent to Atmosphere tank tank Atmosphere I Reactor Reactor Coolant Coolant C

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Chemical Laboratory rt Containment Sumps Spent Fuel Holdup Boric Acid Waste Pits Tanks Holdup Floor Drains Tanks Laundry 6 Showers Laundry Mater Boric Acid Evaporator Concentrates Deminera I izer Recovery Holding Tank System System Bottoms Intake Intake Canal Canal Honltor Solid Maste Tanks Drunming Facility hJ C) 00 Shipment Off-site R-18 Waste Monitor Discharge Canal Tanks Discharge Cana'l

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNITS 3 AND 4 TABLE 6 SOLID WASTE AND IRRAD1ATED FUEL SHZPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL 1~ TYPE OF WASTE UNIT 6 MO PERIOD

a. Spent resin, filters m 0.00 EO sludge evaporator Ci 0.00 EO (note 1)

b. Dry compressible waste m 6.28 E1 (note 2) Ci 1.51 E-1 20

c. Irradiated components m'i 0. 00 EO Control rods, etc. 0. 00 EO

d. Other non-compressible m 5.02 E1 Waste (Note 3) Ci 3.94 E-1 20

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

b. Co-60 60 Fe-55 19 Ni-63 11 Cs-137 3 Sb-125 2 H-3 1 Co-58 1 Mn-54 1 Cs-134 1 Co-57 1 co

d. Co-60 46 Cs-137 36 Ni-63 12 Fe-55 3 C-14 2 Ag-110m 1

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3. SOLID WASTE DISPOSITION NUMBER OF SHIPMENTS MODE OF TRANSPORT DESTINATION 16 (Note 4) Sole use truck Oak Ridge, TN B. IRRADIATED FUEL SHIPMENTS none

FLORIDA POMER 5 LIGHT CNPANY TURKEY POINT PUNT SEHIANNUAL REPORT JULY 1989 THROUGH DECENBER 1989 UNITS 3 AND 4 TABLE 6 SOLID WASTE SUPPLENENT Haste Total (NOTE 5) (NOTE 6) (NOTE 7) R.G. 1.21 (NOTE 8) Solidification or Classification Volusl. Total Principal. Type of Category Type of Absorbent Agent Ft3 Curie Radionuclides Haste Container guantity Class A 4053.7 0.55 None Compactable and l.b,d Strong, Tight N/A Non-Compactable Package Trash

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNITS 3 AND 4 TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPMENT OFFSITE FOR BURIAL OR DISPOSAL Spent resin waste volume indicates volume shipped to a burial site directly from Turkey Point Plant or following volume reduction by a waste processing facility. Volume shipped to the waste processing facility was 16.6 m .

Dry compressible waste volume indicates volume shipped to burial site following reduction by a waste processing facility. Volume shipped to the waste processing facility was 111.6 m Other noncompressible 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 319 m .

Material transported to Oak Ridge, Tennessee, was consigned to licensed processing facilities for volume reduction and decontamination activities. The material remaining after processing was transported by the processor to Barnwell, South Carolina, for burial.

The total curie quantity and radionuclide composition of solid waste shipped from the Turkey point Plant Units 3 and 4 are determined using a combination of qualitative and quantitative techniques. The Turkey Point Plant follows the guidelines in the Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (5/ll/83) for these determinations.

The most frequent 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.

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Page 2 The composition of radionuclides in the waste is determined by both on-site analysis for principle gamma emitters and periodic off-site analyses for difficult to measure isotopes. The on-site analyses are performed either on a batch basis or on a routine basis using representative samples appropriate for the waste type.

Off-site analyses are used to establish scaling factors or other estimates for difficult to measure isotopes.

Note 6: Principle radionuclide 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 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.

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