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 W, QUINN S, STEINKE R N FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-90-79, NUDOCS 9003130315
Download: ML17347B597 (62)

Text

-q ACCELERATED D ST1UBUYION DEMONSTIRATION SYSTEM I~I'P

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.PEARCE,L.W.

Florida Power&'ight Co.RECXP.NAME RECXPIENT AFFILIATION R

SUBJECT:

"Semiannul Radioactive Effluent Release Rept Jul-Dec 1989."'900302 ltr.DISTRIBUTION CODE:.IE48D COPIES RECEIVED:LTR ENCL t SIZE: 8'I TITLE: 50.36a(a)(2)

Semiannual Effluent Release Reports NOTES: D RECIPXENT I D CODE/NAME PD2-2 LA EDXSON, G INTERNAL: AEOD DSP/TPAB RK PB11 G FXLE 01 RGN2 FILE 02 COPIES LTTR ENCL 3 3 1.1 1 1 2 2 1 1 1 1 RECIPIENT'D CODE/NAME PD2-2 PD IRM TECH.'ADV NUDOCS-ABSTRACT RGN2 DRSS/RPB COPXES LTTR ENCL.1 1 1 1 1'1'2 EXTERNAL BNL TI CHLERg J03 LPDR 1 1 1 1 EG&G S IMPSON g F 2 2 NRC PDR 1'R~I S NOTE TO ALL"RIDS" RECIPIENTS:

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

~r ll'"I!'$t'I'*~1 Ek\~"~~1 tr~,I~r r'," r g~, r""a s l lr' 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 I I, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant I 5'003}3031 5 S9'i 231 PDR ADOCK 05000250 R PDC%f an Fpi Qroop company 0'l', P 1 938t gg AAH~g(.P.".g j~FAt"i TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUAL RADIOACTIVE EPPLUENT RELEASE REPORT JULY 1989 THROUGH DECEMBER 1989 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT I PLORIDA POWER AND LIGHT COMPANY.Quinn Radiochemist teinke Chemistry Supervisor L.W.Pearce Operations Superintendent J.L<'.ross Plant Manager-Nuclear 0 r l 1 t ly INDEX 07/89-12/89 1.0 Regulatory Limits Page 1.1 Liquid Ef fluents 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 Ef fluents-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 SEMIANNUAL REPORT 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.j(NSlalgACllh'ht IIIBKel(l J59) 2'l 1 07/89-12/89 t I~~~~~~~2.0 Maximum Permissible Concentrations Water: As per 10CPR20 Part 20, Appendix B, Table II, Column 2, except for entrained or dissolved noble gases as described in 1.1.A of this report.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.kN8A4>ACllÃbl l)lSKrl(ltV(o t 1, t 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.IlV8((LvACIIEhtl)ISP tin/Ji>)

L I 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 Gaseous+11 5.0 BATCH RELEASES 5.1~Lt<<id a)Number of batch releases b)Total time period of batch releases Unit 3 1.53 E+02 1.11 E+04 Unit'1.53 E+02 1.11 E+04 Minutes d)Average time period for a batch release e)Minimum time period for a batch release f)Average stream flow during period of release of effluent into a flowing stream 7.25 E+01 3.10 R+01 1.61 E+06 c)Maximum time period for a batch releases 1.65 E+02 1.65 E+02 Minutes 7.25 E+01 Minutes 3.10 E+01 Minutes 1.61 E+06 GP M 5.2 Gaseous a)Number of batch releases b)Total time period of batch releases c)Maximum time period for a batch release d)Average time period for a batch release e)Minimum time period for a batch release 6.00 E+00 2.28 E+02 V.50 E+01 3.80 E+01 1.50 E+01 9.00 E+00 9.48 E+02 Minutes 2.40 E+02 Minutes 1.05 E+02 Minutes 1.50 8+0 1 Minutes RNSI<LQACIIFI<l l jlSh<<I((<<:<<<>

L P e

.s,.~6.0 UNPLANNED RELEASES 07/89-12/896.1 Liciuid a)Number of releases b)Total activity released 6.2 Gaseous UNIT 3 5.00 E-01 1.02 E-05 UNIT 4 5.00 E-01 1.02 E-05 Curies a)Number of releases b)Total activity released 6.3 See Attachment 1 for:~0 0 Curies 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 Inhalation Location: Red Barn Bone Liver Thyroid Kidney Lung GI-LLI Total Body 3.43 E-08 1.75 E-05 3.19 E-05 1.76 E-OS 1.78 E-05 1.75 E-05 1.75 E-05 NOBLE GAS EXPOSURE , Gamma Air Dose Beta Air Dose 2.92 E-03 mRads 8.62 E-03 mRads llNSlil<<ld (lilac'.ll l>ISKllll1irai1 l oP C~V~l 07/89-12/89 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.l(IV8libi L~

)0 t FLORIDA POWER AND LIGHT CQ+PANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 3 TABLE 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Units Quarter 3 Quarter 4 A.Fission and Activation Products 1.Total Release (not including tritium, gases, al ha 2.Average diluted concentration during period Ci pCi/ml 3.97 E-02 6.47 E-10 4.35 E-02 5.86 E-10 B.Tritium 1.Total Release 2.Average diluted concentration during period Ci pCi/ml 6.68 E+01 1.31 E+02 1.09 E-06 1.76 E-06 C.Dissolved and Entrained Gases 1.Total Release Average diluted concentration during period Ci pCi/ml 7.49 E-02 1.22 E-09 7.69 E-01 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*MDA Value in pCi/ml lr NSIDA J+Clll"'hf l)ISK P l(l iJ90) l 0 ORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 3 TABLE 2 LIQUID EPPLUENTS-SUMMATION OP ALL RELEASES Nuclides Released Units Quarter 3 Quarter 4 Continuous Mode Quarter 3 Quarter 4 Batch Mode Na-24 Cr-51 Mn-54 Fe-55 Co-57 Co-58 Fe-59 Co-60 Zn-65 Sr-90 Nb-95 Zr-97 Ag-110-1 17m-124 Sb-125 I-131 Cs-134 Cs-137 unidentified Total for Period Above Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 4.88 E-06 8.29 E-05 1.46 E-03 1.35 E-02 1.40 E-05 1.94 E-03 7.91 E-03 1.11 E-05 6.57 E-05 1.31 E-05 2.58 E-06 9.46 E:04 5.01 E-04 6.73 E-03 2.49 E-04 1.61 E-03 ,4.64 E-03 3.97 E-02 2.87 E-05 1.60 E-04 1.05 E-03 1.49 E-02 3.78 E-03 1.78 E-05 1.01 E-02 5.45 E-06 4.72 E-04 3.53 E-06 8.94 E-05 1.23 E-02 1.00 E-04 6.43 E-05 4.62 E-04 4.35 E-02 RNSIDh J*Clll)ht DISK//l(1990) i.~1

~W~ORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 3 TABLE 2 (Continued)

LIQUID EPPLUENTS Liquid Dissolved Gas Nuclides Released Units V Quarter 3 Quarter 4 Continuous Mode Quarter 3 Quarter 4 Batch Mode Kr-85 Kr-85m Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Total for Period Above Ci Ci Ci Ci Ci Ci Ci Ci 5.18 E-04 7.44 E-02 7.60 E-06 1.33 E-05 1.51 E-06 7.49 E-02 7.55 E-07 3.73 E-05 1.25 E-02 7.51 E-01 4.52 E-03 5.55 E-04 3.34 E-05 7.69 E-01LIQUID EFFLUENTS-DOSE SUMMATION JANUARY 1989 THROUGH DECEMBER 1989 UNIT 3 Age Group: Teenager Shoreline De osition Total Body Dose mRem 1.93 E-03 Location: Cooli'ng Canal%of Annual Limit 6.43 E-02 RQSII)h JA CllEh1 1)ESKER l(l J'J'0) l 0'I(, A ORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 3 TABLE 3 GAS EPPLUENTS-SUMMATION Op ALL RELEASES Units Quarter 3 Quarter 4 A.Fission and Activation Products 1.Total Release 2.Average Release Rate for Period Ci 5.79 E+02 5.47 E+02 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 2.Average Release Rate for Period 3.Gross Alpha Radioactvity Ci pCi/sec Ci<1.00 E-13*(5.99 E-16*(1.76 E-144 (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*(MDA Values Expressed in pci/ml IIHSIDA J AS CII Yhl DISh;1I I(1990)

I P LORIDA POWER AND LIGHT CO NY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 3 TABLE 4 GASI?OUS EPPLUENTS Nuclides Released 1.Fission Gases Units Continuous Mode Quarter 3 Quarter 4 Batch Mode Quarter 3 Quarter 4 Ar-41 Kr-85 Kr-85m Ci Ci Ci 1.49 E-01 1.44 E-03 1.36 E-01 1.33 E+00 3.42 E-03 2.48 E-01 3.31 E-01 3.38 E-05 Xe-131m Xe-133 Xe-133m Ci Ci Ci 9.49 E-02 5 59 E+02 6.85 E-02 3.70 E-01 2.89 E-01 2.84 E-01 5.29 E+02 1.95 E+01 1.53 E+01 6.81, E-02 8.76 E-02 9.28 E-02 Xe-135 Xe-135m Unidentified Ci Ci Ci Ci 4.46 E-02 4.74 E-02 6.12 E-03 4.18 E-03 Total for Period Above Ci 5.59 E+02 5.31 E+02 1.99 E+01 1.63 E+01 2.Iodines I-131 I-133 Total for Period Above Ci Ci Ci Ci 4.22 E-05 1.98 E-05 6.20 E-05 6.89 E-05 5.60 E-05 1.25 E-04 ltNS/I Ji1 J 4CII I.'hf l)lSK 4 l(l J'90)

'l I LORIDA POWER AND LIGHT CO~NY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 3 TABLE 4 (Continued)

GASEOUS EPPLUENTS Nuclides Released Units Continuous Mode Quarter 3 Quarter 4 3.Particulates I-131 Unidentified Total for Period Above Ci Ci Ci Ci Ci Ci Ci Ci Ci (1.00 E-134 (1.00 E-13*(1.76 E-14*(1.76 E-14**(MDA Values Expressed in pCi/ml llNSIDA J)t CllEhf DISK&1(1J'90)

~4 IJ t 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 Cow Milk-Infant 1.37 E-05 Fruit 8 Veg-Fresh 5.75 E-07 Liver Thyroid Kidney 4.81 E-05 4.67 E-03 1.76 E-05 3 92 E 05 2 16 E 04 3 94 E 05 Lung Gl-LLI 3.20 E-05 3.24 E-05 3.84 E-05 3.90 E-05 Skin Total Body 4.04 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 Totals (mRem)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%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 Beta Air Dose 1.12 E-02 mRad 3.31 E-02 mRad%of Annual Limit%of Annual Limit 1.12 E-01%/Yr 1.65 E-01%/Yr

'13 e ORIDA POWER AND LIGHT CO NY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 4 TABLE 1 LIQUID EPPLUENTS-SUMMATION OP ALL RELEASES A.Fission and Activation Products Units Quarter 3 Quarter 4 1.Total Release (not including tritium, gases, al ha 2.Average diluted concentration during period Ci pCi/ml 3.97 E-02 6.47 E-10 4.35 E-02 5.86 E-10 B.Tritium 1.Total Release 2.Average diluted concentration during period Ci pCi/ml 6.68 E+01 1.31 E+02 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*MDA Value in pCi/ml Liters 6.14 E+10 7.43 E+10 ltNSIDA J kClll: Af lJISK 41(19J'0)

I 0 LORIDA POWER AND LIGHT CO~NY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 4 TABLE 2 LIQUID EPPLUENTS-SUMMATION OP ALL RELEASES Nuclides Released Units Quarter 3 Quarter 4 Continuous Mode Batch Mode Quarter 3 Quarter 4 Na-24 Cr-51 Mn-54 Fe-55 Co-57 Co-58 Fe-59 Co-60 Zn-65 Sr-90 Nb-95 Zr-97 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 1.11 E-05 6.57 E-05 1.31 E-05 2.58 E-06 5.45 E-06 4.88 E-06 2.87 E-05 8.29 E-05 1.60 E-04 1.46 E-03 1.05 E-03 1.35 E-02 1.49 E-02 1.40 E-05 1.94 E-03 3.78 E-03 1.78 E-05 7.91 E-03 1.01 E-02 Ag-110-124 Sb-125 1-131 Cs-134 Cs-137 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 9.46 E-04 5.01 E-04 6.73 E-03 2.49 E-04 1.61 E-03 4.64 E-03 4.72 E-04 3.53 E-06 8.94 E-05 1.23 E-02 1.00 E-04 6.43 E-05 4.62 E-04 Unidentified Total for Period Above Ci Ci 3.97 E-02 4.35 E-02 RNSllM J)0 Clll"'hf l)ISK k'I(l J'90)

\((

I LORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 4 TABLE 2 (Continued)

LIQUID EPPLUENTS Liquid Dissolved Gas Kr-85 Kr-85m Xe-131m Ci Ci Ci Nuclides Released Units Quarter 3 Quarter 4 Continuous Mode Quarter 3 5.18 E-04 Quarter 4 7.55 E-07 3.73 E-05 1.25 E-02 Batch Mode Xe-133 Xe-133m Xe-135 Xe-135m Total for Period Above Ci Ci Ci Ci Ci 7.44 E-02 7.60 E-06 1.33 E-05 1.51 E-06 7.49 E-02 7.51 E-01 4.52 E-03 5.55 E-04 3.34 E-05 7.69 E-01 LIQUID EFFLUENTS-DOSE SUMMATION JANUARY 1989 THROUGH DECEMBER 1989 UNIT 4 Age Group: Teenager Shoreline De osition Total Body Dose mRem 1.93 E-03 Location: Cooling Canal%of Annual Limit 6.43 E-02 lfNS/l)A J+CflEAf l)ISK Pl(l 9 J'0) 0 1y LORIDA POWER AND LIGHT CO~NY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 4 TABLE 3 GAS EPPLUENTS-SUMMATION OP 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 2.Average Release Rate for Period Ci pCi/sec 4.22 E-05 5.31 E-06 6.89 E-05 8.67 E-06 articulates 1.Particulates T-1/2>8 Days 2.Average Release Rate for Period 3.Gross Alpha Radioactvity Ci pCi/sec Ci (1.00 E-13*(5.99 E-16" 9.04 E-08 1.14 E-08 (7.37 E-16*D.Tritium 1.Total Release 2.Average Release Rate for Period Ci pC%iec 1.53 E+00 2.31 E+00 1.93 E-01 2.91 E-01*MDA Values Expressed in pCi/ml IIHSIDA J+Cllklhl I)ISK III(IOJ'0) 0 0 14 e~'

~~0 LORIDA POWER AND LIGHT CO NY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1989 THROUGH DECEMBER 1989 UNIT 4 TABLE 4 GASEOUS EPPLUI?NTS Nuclides Released 1~Fission Gases Units Continuous Mode Quarter 3 Quarter 4 Batch Mode Quarter 3 Quarter 4 Ar-41 Kr-85 Kr-85m Kr-87 Ci Ci Ci Ci 1.03 E-01 1.15 E-03 2.64 E-01 1.74 E-02 1.40 E-03 1.90 E-02 2.68 E-03 4.24 E-01 3.31 E-01 2.09 E-02 Xe-131m Xe-133 Xe-133m Xe-135 Unidentified Total for Period Above Ci Ci Ci Ci Ci Ci Ci 6.52 E-02 6.00 E-02 5.57 E+02 5.31 E+02 4.19 E-02 1.24 E-01 4.59 E-02 7.04 E-01 5.57 E+02 5.32 E+02 2.89 E-01 3.02 E+01 1.98 E-01 8.87 E-02 3.08 E+01 2.84 E-01 1.63 E+01 1.44 E-01 4.26 E-01 1.79 E+01 2.lodines I-131 Ci 4.22 E-05 6.89 E-05 l-133 Total for Period Above Ci Ci Ci 1.98 E-05 6.20 E-05 5.60 E-05 1.25 E-04 IINSIDA J A CIII ht DISK III(l 3'90) 0 I LORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1988 THROUGH DECEMBER 1988 UNIT 4 TABLE 4 (Continued)

GASEOUS EPPLUENTS Nuclides Released Units Continuous Mode Quarter 3 Quarter 4 3.Particulates Co-60 l-131 Unidentified Total for Period Above Ci Ci Ci Ci Ci Ci Ci Ci (1.00 E-13*<1.00 E-13*9.04 E-08 9.04 E-08*(MDA Values Expressed in pCi/ml 0 IPNSIIM J*Cllh'h1 l)ISK k'l(l J'3'0)

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 Fruit&Veg-Fresh 5.64 E-07 4.89 E-05 4.54 E-03 4.03 E-05 2.12 E-04 1.08 E-05 3.30 E-05 4.05 E-05 3.95 E-05 3.34 E-05 4.01 E-05 4.12 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 Totals (mRem)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%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 Beta Air Dose 1.12 E-02 mRad 3.31 E-02 mRad%of Annual Limit%of Annual Limit 1.12 E-01%/Yr 1.65 E-01%/Yr I

~LORIDA POWER AND LIGHT CO NY TURKEY POINT PLANT SEMIANNUAL REPORT 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.<<ntsaina+caeat we~'z i(iaido)

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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.22 f~J l,'t 0 C P wsc APPROV PLT.MGR APPROVA DATE~<DATE~~PLORIDA POWE LIGHT COMPANY TURKE NT PLANT SEMIAN L REPORT JULY 1989 THROUGH DECEMBER 1989 ATTACHMENT 2 (Cont'd)Turbines on ensers GQeNto Pr lmary oop Unit 3 Reactor Unit 4 Reactor Primary oop Steam Generator Turbines Condensers I C CL P-X-I'I Vent to Atmosphere B lowdown B 1owd own flash tank CVCS 3 Reactor Coolant Drain Tank Reactor Coolant Drain Tank Hakeup water and chemicals cvcs Slowdown flash tank p-v-I'p Vent to Atmosphere m I LO h g C n rt Spent Fuel Pits Holdup Tanks Boric Acid Waste Holdup Tanks Chemical Laboratory Containment Sumps Floor Drains Laundry 6 Showers Intake Canal Laundry Mater Honltor Tanks Boric Acid Recovery System Evaporator Bottoms Concentrates Holding Tank Solid Maste Drunming Facility Deminera I izer System Intake Canal hJ C)00 R-18 Discharge Cana'l Waste Monitor Tanks Shipment Off-site Discharge Canal

~~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 a.Spent resin, filters sludge evaporator (note 1)UNIT m Ci 6 MO PERIOD 0.00 EO 0.00 EO b.Dry compressible waste m (note 2)Ci 6.28 E1 1.51 E-1 20 c.Irradiated components Control rods, etc.d.Other non-compressible Waste (Note 3)m'i m Ci 0.00 EO 0.00 EO 5.02 E1 3.94 E-1 20 2.ESTIMATE OF MAJOR NUCLIDE COMPOSITION BY TYPE OF WASTE a~b.Co-60 Fe-55 Ni-63 Cs-137 Sb-125 H-3 Co-58 Mn-54 Cs-134 Co-57 60 19 11 3 2 1 1 1 1 1 co d.Co-60 Cs-137 Ni-63 Fe-55 C-14 Ag-110m 46 36 12 3 2 1 o~~s~/~

~~~~~i 3.SOLID WASTE DISPOSITION NUMBER OF SHIPMENTS 16 (Note 4)MODE OF TRANSPORT Sole use truck DESTINATION 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 Classification Total Volusl.Ft3 (NOTE 5)Total Curie guantity (NOTE 6)Principal.

Radionuclides (NOTE 7)Type of Haste R.G.1.21 Category (NOTE 8)Type of Container Solidification or Absorbent Agent Class A 4053.7 0.55 None Compactable and Non-Compactable Trash l.b,d Strong, Tight Package N/A

('~~s 0!l qk 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.

4 r.,

Page 2 Note 6: 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.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.RKR/eb/024 q'I~..c.l