ML17354A852

Annual Radioactive Effluent Release Rept for Jan-Dec 1997. W/980325 Ltr

ML17354A852
Person / Time
Site:	Turkey Point
Issue date:	12/31/1997
From:	Charles Murray, Steinke R, West R FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-98-085, L-98-85, NUDOCS 9803310178
Download: ML17354A852 (41)

Text

CATEGORY j.-

a,P -" REGULAIY INFORMATION DISTRIBUTIOYSTEM (RIDE)

ACCESSX9N NBR:9803310178 DOC-DATE: 97/12/31 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey'oint Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION MURRAY,C.M. Florida Power S Light Co.

STEINKE,R.N. Florida Power S Light Co.

WEST;R.G. Florida Power 5 Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Annual Radioactive Effluent Release Rept for Jan-Dec 1997."

W/980325 ltr.

DISTRXBUTION CODE: IE48D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.36a(a) (2) Semiannual Effluent Release Reports E NOTES:

RECIPIENT COPXES RECXPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3 LA 1 1 PD2-3 PD 1 1 CROTEAU,R 1 1 INTERNA 'ILE E 1 1 1

1 1

NRR/DRPM/PERB/A RGN2 DRS/RSB 1

1 1

1 RGN2 FILE 1 1 EXTERli>AL: NRC PDR D

0 E

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9

el f

1 f

t MAR 25 t998 L-98-085 10 CFR 50.36a(a)(2)

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Attached is the Radioactive Effluent Release Report for the period of January 1, 1997, through December 31, 1997, for Turkey Point Units 3 and 4, as required by Technical Specification 6 '.1.4 and 10 CFR 50.36a (a) (2) .

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

Very truly yours, R. J. Hovey Vice Preside t Turkey Point Plant DRL Attachment cc: L. A. Reyes, Regional Administrator, Region II, USNRC T. P. Johnson, Sr. Resident Inspector, USNRC, Turkey Point Plant v J~~4

'rr803310178 'rr71231 PDR *DOCK 05000250

>DR an FPL Group company

r TURKEY POINT PLANT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid effluent releases at Turkey Point did not exceed the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2.

The limits for dissolved and entrained noble gases were not exceeded.

The dose or dose commitment limits per reactor to a member of the public from liquid effluents were not exceeded.

Dose rate limits due to radioactive materials in the gaseous effluents were not exceeded.

The dose limits per reactor to a member of the public due to I-131,

'I-133, tritium and particulates with half-lives greater than 8 days were not exceeded.

All liquid and airborne discharges to the environment were analyzed in accordance with the Technical Specifications and Regulatory Guide 1.21.

There were no unplanned liquid releases for either unit during this period.

There was one unplanned gas release during this period. The "F" Waste Gas Decay Tank was released through the unit 3 Reactor Coolant Drain Tank into the containment. building. No regulatory limits were exceeded.

Visitor dose limits were calculated and included in this report for both adult and children inhalation at the Red Barn and also children inhalation at the Satellite School.

Turkey Point Plant Units 3 and 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT January 1997 through December 1997 Submitted by:

NUCLEAR CHEMISTRY DEPARTMENT FLORIDA POWER AND LIGHT COMPANY

~ Murray, Radiochemistry Supervisor R.. Steinke, Chemistry Supervisor R . W st, Operations Manager

- .E.Jernig General Manager

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 Table Of Contents 1.0 REGULATORY LIMITS.

2.0 MAXIMUMPERMISSIBLE CONCENTRATION 3.0 AVERAGE ENERGY.

4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY. 4 5.0 BATCH RELEASES 6.0 UNPLANNED RELEASES 7.0 REACTOR COOLANT ACTIVITY 8.0 SITE RADIATIONDOSE ~ ~~ ~ ~ ~ ~~~~~~~~ ~~~ ~ ~ ~ ~~ 8 9.0 OFFSITE DOSE CALCULATIONMANUAL(ODCM) REVISIONS.

10.0 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS.

11.0 PROCESS CONTROL PROGRAM REVISIONS 12.0 INOPERABLE EFFLUENT MONITORING INSTRUMENTATION.

Page 2

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 1.0 RE<t ULATORYLIMITS 1.1. L~iid Hffl (a) The concentration of radioactive material released in liquid effluent to unrestricted areas shall not exceed ten times the concentration specified in 10CFR20 A'ppendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained gases. For dissolved or entrained noble gases, the concentration shall not exceed 2.0 E-04 micro-curies per milliliter.

(b) The dose or dose commitment per reactor to a member of the public from any radioactive materials in liquid effluents released to unrestricted areas shall be limited as follows:

) During any calendar quarter, to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ.

> During any calendar year, to less than or equal to 3.0 mrem to the total body and less than or equal to 10 mrem to any organ.

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

> Less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the skin due to noble gases.

> Less than or equal to 1500 mrem per year 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 to:

> During any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation.

) During any calendar year, to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

(c) The dose per reactor to a member of the public, due to I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluent 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.

Page 3

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER l997 2.0 MAXIMUMPERMISSIBLE CONCENTRATION Water: In accordance with 10CFR20, Appendix B, Table 2, Column 2, and 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 of this report.

3.0 AVERAGE ENERGY The average energy of fission and activation gases in effluents is not applicable.

4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTALACTIVITY All liquid and airborne discharges to the environment during this 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.

When alpha, tritium and named nuclides are shown as "- -" curies on the following tables, this should be interpreted as '~no activit 'as detected on the samples using the Plant Technical Specification analysis techniques to achieve the required Lower Limit of Detection ("LLD")sensitivity for radioactive effluents.

4.1 c~idflffl Aliquots of representative pre-release samples, from waste disposal system, were isotopically analyzed for gamma emitting isotopes on a multichannel analyzer.

Frequent periodic sampling and analysis were used to conservatively determine ifany radioactivity was being released via the steam generator blowdown system and the storm drain 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 radioactivity. Tritium was determined by use of liquid scintillation techniques, and gross alpha radioactivity was determined by use of a solid state scintillation system. The quarterly composite was analyzed for Sr-89, Sr-90, and Fe-55 by chemical separation.

All radioactivity concentrations determined from sample 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.

Page 4

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 Aliquots of representative samples from the waste disposal system were analyzed on a pre-release basis by 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 respectively.

There were no continuous liquid effluent releases above the lower limit of detection for either Unit 3 or Unit 4 during this reporting period and therefore these have been omitted from Table 2 of this report.

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 4.2 Gaseous Effluents Airborne releases to the atmosphere occurred from the following sources:

- Gas Decay Tanks

- Containment Purges

- 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, Sr-90 determination, and gross alpha determination, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma spectral 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 SPING-4 radiation monitors and the Plant Vent process monitor recorder chart and the current calibration curve for that process 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 1997 through December 1997, in the form of Joint Frequency Distribution Tables, are maintained on site.

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 4.3 Estimation 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, reported to us by the independent lab, were used as the basis for deriving the following analytical error terms:

NUCLIDE TYPE AVERAGE ERROR MAXIMUMERROR Liquid + 5.9% + 11.0%

Gaseous + 27% + 11.0%

5.0 BATCH RKLKASKS 5.1 LHIUID Unit 3 Unit 4 a) Number of releases 2.36E+02 2.36E+02 b) Total time period of batch releases, minutes 2.02E+04 2.02E+04 c) Maximum time period for a batch release, minutes 1.38E+02 1.38E+02 d) Average time period for a batch release, minutes 8.56E+01 8.56E+01 e) Minimum time for a batch release, minutes 2.00E+01 2.00E+01 f) Average stream flow during period of release of effluent into a flowing stream, liters-per-minute 5.63E+06 5.63E+06 5.1 GASEOUS Unit 3 Unit 4 a) Number of releases 1.00E+01 1.00E+01 b) Total time period of batch releases, minutes 7.59E+02 7.59E+02 c) Maximum time period for a batch release, minutes 2.40E+02 2.40E+02 d) Average time period for a batch release, minutes 7.59E+01 7;59E+01 e) Minimum time for a batch release, minutes 1.00E+01 1.00E+01 Page 7

V TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGII DECEMBER l997 6.0 UNPLANNED RELEASES 6.1 fiuid There were no unplanned liquid releases this period for either Unit 3 or Unit 4.

'.2 Gaseous There was one unplanned release during this reporting period. On 3/26/97 the "F" Gas Decay Tank was released through the unit 8 3 Reactor Coolant Drain Tank (RCDT) into the containment building. The "F" GDT was sampled, a permit was prepared and no limits were exceeded.

7.0 REACTOR COOLANT ACTIVITY 7.1 Unit 3 Reactor coolant activity limits of 100/E-Bar and 1.0 uCi/gram Dose Equivalent I-131 were not exceeded.

7.2 Unit 4 Reactor coolant activity limits of 100/E-Bar and 1.0 uCi/gram Dose Equivalent I-131 were not exceeded.

8.0 SITE RADIATIONDOSE The assessment of radiation dose from radioactive efHuents to the general public due to their activities inside the site boundary assumes a visitor was at the child development center/fitness center for ten hours a day, five days each week for fiftyweeks of the year, receiving exposure from both Unit 3 and Unit 4 at Turkey Point. The child development center/fitness center is located approximately 1.75 miles WNW of the plant. Specific activities used in these calculations are the sum of the activities listed in Unit 3 Table 3 and Unit 4 Table 3. The following dose calculations were made using historical, meteorological data:

Liver (mrcm) 1.91E46 1.34E-06 Thyroid (mrem) 1.91E-06 1.34E46 Kidney (mrcm) 1.91E46 8.88E47 Lung (mrcin) 1.91E46 1.34E46 GI-LLI(mrcm) 1.91E-06 1.34E-06 Total Body (mrcm) 1.91E46 1.34E-06 Gamma AirDose (mrad) 3.09E-06 Beta AirDose (mrad) 1.64E46 Fagc 8

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 9.0 OFFSITE DOSE CALCULATIONMANUAL ODC REVISIONS No revisions were made to the ODCM during this reporting period.

10.0 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS No irradiated fuel shipments were made from the site. Common solid waste &om Turkey Point Units 3 and 4 was shipped jointly. A summation of these shipments is given in Table 6 of this report.

11.0 PROCESS CONTROL PROGRAM REVISIONS No revisions were made to the process control program during this reporting period.

12.0 INOPERABLE EFFLUENT MONITORING INSTRUMENTATION No inoperable effluent monitoring instrumentation requiring reportability during this period.

Page 9

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 LIQUIDEFFLUENTS

SUMMARY

UNIT 3 TABLE 1 A. FISSION AND ACTIVATIONPRODUCTS UNITS . Qtr1 Qtr 2 Qtr 3 Qlr 4 Est. Error (%)

1. Total Release (nol including tritium, ases, alpha) Ci 1.44E4I2 1.84E4I2 3.56E42 3.18E4)2 3.44

. Avera o diluted concentration durin !he riod uCVml 4.27E-10 7.92E-10 9.83E-10 1.54E4)9

. Porcent of spplicablo limit 4.27E4>>3 7.92E4I3 9.83E4I3 1.54E42 ..".:.,-':; ~,';='.;,;, .I',

B. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Qlr 4 Esl. Error (%)

1. Total Rolease CI 2.02E+02 6.1 8E+01 1.13E+02 4.16E+01

. Aversgo diluted concentration during the pedod uCVml 5.97E4)6 2.66E4I6 3.13E4)6 2.02E4S

. Percent of applicablo limit 5.97E4t1 2.66E4t1 3.13E<t 2.02E4I1 C. DISSOLVED AND ENTRAINED GASES UNITS Qtr 1 Qtr 2 Qlr 3 Qtr 4 Esl. Error (%)

1. Total Release Ci 8.69E4)5 1.29E4)4 6.14E4)6 9.62MI7 3.44

. Average dilutod concontration during tho riod uCVmt 2.57E-12 5.53E-12 1.69E-13 '.66E-14

. Percent of applicable limit 1.29E46 2.76E4I6 8.47E4m 2.33E4I8 i>>tii rtii'v.i li'lii'it)l.i D. GROSS ALPHA RADIOACTIVITY UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Total Release Ci E. LIQUIDVOLUMES Qtr1 Qtr 2 Qtr 3 Qtr 4 Esl. Error %)

1. Batch wasto released, rior to ditution LITERS 1.71E+06 9.87E+05 1.77E+06 9.95E+05 10.00

. Continuous wasto released, prior to dilution LITERS

. Difution water used during riod UTERS 338 E+10 2.32E+10 3.62E+10 2.06E+10 page 10

lg TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 LIQUID EFFLUENTS

SUMMARY

UNIT 3 TABLE 2 NUCLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Fe-55 Ci 2.13E%3 1.68E<3 5.84E-03 2.78E%3 Sr-89 Ci 3.55E-OS 2.19E415 Sr-90 Ci 2.96E416 5.32E416 2.99E416 Na-24 Ci Cr-51 Cl 1.62E-04 3.48E-04 2.79E-03 1.64E-03 Mn-54 Ci 3.61E-04 3.52E-04 1.68E43 1.21E-03 Co-57 Ci 5.83E-OS 1.56E415 4.87E45 1.18E-OS Co-58 Ci 4,52E-03 8.42E-03 1.50E%2 8.57E-03 Fe-59 Ci 1.40E-05 8.13E<5 7.98E-06 Cote Ci 3.85E-03 1.51E-03 4.00E%3 1.96E-03 Ci 9.39E45 1.18E-OS Nb.95 Ci 3.33E-OS 6.17E-OS 2.41E4I4 2.09E-04

-97 Ci 2i16E-05 1.03E-04 2.35E45 5.18E~

Mo-99 Ci 6.69E46 Ru-103 Ci 9-110 Ci 1.44E%3 2.58E%3 1.71E.03 6.01E-04 Sn-113 Ci Sn-117 Ci Sb-124 Ci 6.70E45 6.37EZS 2.54E-05 Sb-125 Ci 9.93E-04 9.35E-04 7.53E.04 1.64E44 I-131 Ci I-133 Ci 1-134 Ci Cs-134 Ci 1.32E-04 4.68E4t4 6.76E-04 3.23E-03 1-135 Ci Cs-137 Ci 6.13E-04 1.60E-03 2.48E-03 1.13E-02 La-140 'Ci 4.47E-06 1.71E-06 Ce-141 Ci Ce-144 Ci

-187 Ci 9.61E45 2.62E-04 1.25E-04 8.57E-06 Np-239 Ci OTAL FOR PERIOO Cl 1.44E4I2 1,84E4I2 3.58EZ2 3.18E-02 LIQUID EFFLUENTS - DISSOLVED GAS

SUMMARY

NUCLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ci 9.62E47 Kr-85m Ci Kr-85 Ci 1.16E44 e 133 Ci 7.96E-OS 8.54E-06 6.14E-06 e-133m Ci Xe-135 Ci 7.28E-06 3.80E46 e-138 Ci TOTAL FOR PERIOO Ci 8.69E-05 1.29E44 6.14E-06 9.62E-07 LIQUIDEFFLUENTS - DOSE SUMMATION Age grotip r Teeneger Locegonl Cooling Cenel Shoreline Deposition Dose (mrem)  % of Annual Limit TOTAL BODY 9.48E-04 3.16E42 page 11

TURKEY POINT UNITS 3 AND 4 ANhlUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 T11ROUGH DECEMBER 1997 42ASEOUS ZFFLUENTS SIJAf MARY UNIT 3 TABLE 3 A. FISSION AND ACTIVATIONPRODUCTS UNITS Est. Errcr %

1. Total Release tAOE41 tME4Q 3d7E4ss

2. Avera e release rate for the 244E~ 1.72603 2M&03 459844 '! r>>t" I."- I;"I

3. Percent of Technical 'cation Umit 1.26E 11 5.76E-14 6.02E-14 163E 14 B. IODINES UNITS Qlr 3

1. Total Release

2. Avefa e rehrase rate fof the nod

3. Percent of Technical 'abon Lbnit C. PARTICULATES UNITS EsL Enor %

1. Particulates with half4de >8 da

2. Avera e release rate for the dod

3. Percent of Technical frcadon Umit

4. Gross Al Radioactivi D. TRITIUM UNITS

1. Total Release 1.65E412 323E+I

2. Avera e release rate for the riod 2. 13E4I3 4.1IFAQ

3. Percent of Technical S 'fication Limit 324E415 ~i V.i f~ivrttt.',

P390 12

1 k

t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 GASEOUS EFFI UENTS

SUMMARY

UNIT 3 TABLE 4 A. FISSION GASES NUCLIDES UNITS BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ci 9.34E-02 Kr-85 Ci Kr-85m Ci 1.50E-08 e-131m Ci 2.91E-04 1.90E-04 9.15E-05 e 133 Ci 9.57E-02 1.32E-02 1.84E-02 3.45E-03 e-133m Ci 3.73E-04 1.23E-04 1.19E-04 1.86E-05 e-135 Ci 1.36E-04 9.43E-06 1.72E-06 6.85E-06 TOTAL FOR PERIOD Ci 9 65E-02 1 35E-02 1 85E42 I 3 57E-03 NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr4 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci e-131m Ci e-133 Ci e-133m Ci e-135 Ci e-135m Ci e-138 Ci TOTAL FOR PERIOD Ci B. IODINES NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr4 Br-82 Ci 1-131 Ci 1-133 CI TOTALFOR PERIOD Ci I I C. PARTICULATES NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr1 Qtr 2 Qtr 3 Qtr 4 Co-58 Ci CO%0 Ci Mn-54 Ci Cr-51 Ci OTAl. FOR PERIOD Ci page 13

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 DOSES DUE TO IODINE,TRITIUM,AND PARTICULATES UNIT 3 TABLE 5 PATHWAY BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY Cow milk - Infant (mrem) O.OOE+00 2.55E-06 2.55E+6 1.1 2E-06 2.55E-06 2.55E-06 0.00E+00 2.55E-06 Fruit 8 Veg Fresh (mrem) O.OOE+00 2.66E-07 2.66E-07 1.75E-07 2.66E-07 2.66E-07 O.OOE+00 2.66E-07 Ground Plane (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Inhalation - Adult (mrem) O.OOE+00 1.15E-06 1.15E-06 1.15E-06 1.15E-06 1.15E-06 O.OOE+00 1.1 5E-06 TOTAL (mrem) O.OOE+00 3.97E-06 3.97E-06 2.45E-06 3.97E-06 3.97E46 0.00E+00 3.97E-06

% of Annual Limit O.OOE+00 2.65E-05 2.65E-05 1.63E-05 2.65E-05 2.65E%5 O.DOE+00 2.65E-05 DOSE DUE TO NOBLE GASES mrad ~/o of Annual Llmil Gamma Air Dose 1.66E-05 1.66E-04 Beta Air Dose 7.96E-06 3.98E-05 page 14

LIQUID EFFLUENTS

SUMMARY

t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 UNIT 4 TABLE 1 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Total Release (not induding tritium,gases, alpha) Cl 1.44E4)2 1.84')2 3.56E4)2 3.18E-02 3.44

. Average dguted concentration during the pedod uCirml 4.27E-10 7.92E-10 9.83E-10 1.54E48

. Percent of applicable Ikntt 4.27E4)3 7.92')3 9.83')3 1.54E4)2 B. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

t. Total Release CI 2.02E+02 6.18Et01 1.13Et02 4.16E+01

2. Average diluted concentration during the period uCI/ml 5.97E46 2.66E4$ 3.13E46 2.02E4)6

. Percent of applicable limit 5.97E-OI 2.66E4)1 3.13E-01 2.02')1 C. DISSOLVED AND ENTRAINED GASES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%t)

1. Total Release CI 8.69')5 1.29E4)4 6.14E4S 9.62E4)7 3.44

. Average dguted concentratke during the pened uCIlml 2.57E-12 5.53E-12 1.69E-13 4.66E-14

. Percent of appticabkr limit 1.29E4S 2.76E4)8 8.47E4S 2.33E48 D. GROSS ALPHA RADIOACTIVITY UNITS Qu 1 Qtr3 Qtr 4 Est. Error (t/t)

1. Total Release CI E. LIQUIDVOLUMES Qtr 1 Qtr 2 Qtr 4 Est. Enor (%)

1. Batch waste released, pdor to ditutkn LITERS 1.71Et06 9.87E+05 1.77Et06 9.95Et05 10.00

2. Continuous waste released, pdor to dilution LITERS

. Dihtion water used durktg period LITERS 3.38E+10 2.32E+10 3.62E+10 2.06E+10 page 15

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 LIQUID EFFLUENTS

SUMMARY

UNIT 4 TABLE 2 NUCLIDES UNITS BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ci 2.13E~ 1.68E~ 5.84E43 2.78MQ Ci 3.55E4I5 2.19E~

Sr-90 Ci 2.96E4XI 5.32E~ 2.99MXi Na-24 Ci Cr-51 Ci 1.62E~ 3.48E~ 2.79E~ 1.64')3 Mn~ Ci 3.61E~ 3.52M)4 1.68E~ 1.21E<3 Co-57 CI 5.83E4XI 1.56 MS 4.87E~ 1.18M6 Ci 4.52M6 8.42E43 1.50E%2 8.57E~

Fe-59 Ct 1.40E~ 8.13E~ 7.98E~

Ci 3.85&0 1.51EZ3 4.DOE%3 1.96E43 CI 9.39E4I5 1.18E4XI Nb-95 Ci 3.33E~ 6.17E~ 2.41E~ 2.09E~

-97 Ci 2.16E~ 1.03E~ 2.35E4I5 5.18E~

Ci 6.69E~

Ru-103 Ci AQ-110 CI 1.44MB 1.71E46 6.01E~

Sn-113 CI 5.84 MS Sn-117 CI Sb-124 Ci 6.70E~ 6.37E4I5 2.54E4I5 Sb-125 Ci 9.93E~ 9.35E~ 7.53E~ 1.64E~

l-131 , Ci 1-133 Ci 1-134 Ci Cs-134 Ci 1.32EC4 4.68E~ 6.76E~ 3.23E43 1-135 Ci Cs-137 CI 1.60E43 2.48E~ 1.13E4I2 La-140 Ci 4.47E4XI Ce-141 CI 6.13'.61E4$ 1.71'.57E~

Ce-144 Ci

-187 CI 2.62E~ 1.25E<4 N 239 Ci OTAL FOR PERIOD Ci 1.44 Eat 1.84E~ 3.56E%2 3.18E4I2 LIQUIDEFFLUENTS - DISSOLVED GAS

SUMMARY

NUCLIDES UNITS BATCH MODE RELEASED Qtr1 Qtr 2 Qtr 3 Qtr 4 Ar<1 Ci 9.62EZ7 Ci Ci 1.16E-04 Xe-131m CI Xe-133 CI 7.96E~ 8.54E4M 6.14E46 Xe-133m CI e-135 7.28 MS 3.80E~

CI TOTAL FOR PERIOD CI 8.69E4I5 1.29EC4 6.14E4XI 9.62E<7 LIQUIDEFFLUENTS - DOSE SUMMATION Age group r Teenager Locaffort: Cooahg Canal Shoreline Deposition Dose mrem)  % of Annual Umit TOTAL BODY 9.48E44 3.16E%2 page 16

1 TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 GASEOUS EFFLUENTS

SUMMARY

UNIT 4 TABLE 3 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 2 Qtr 4 EsL Enor (~l)

1. Total Release Ci 3.14E4)2 1.35E472 2.66E4)2 3.57E4)3 2.79

. Average release rate for the period 4.04E4)3 1.72E4)3 3.35E4)3 4.59E4)4

. Percent of Technical Specification Limit 1.37E 13 5.78E-14 1.09E 12 1.53E 14 B. IODINES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 EsL Bror (~4)

1. Total Release Ci

. Average release rate for the period

. Percent of Technical Specifcation Limit C. PARTICULATES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (14)

1. PartMiates with hat(4ife >8 days Ci

. Average release rate for the period

. Percent of Technical SpecTication Limit

. Gross Alpha Rad'oact)vity Ci D. TRITIUM UNITS Qtr1 Qtr 2 Qtr3 Qtr4 Est. Bror (~4)

1. Total Release Ci 3.23E4)1 1.64E4)3

. Average release rate for the period 4.11E4)2 2.06E4)4

. Percent of Technical Specification Limit 3.24E4)5 1.64E%7 page 17

1 TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVERELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 GASEOUS EFFLUENTS

SUMMARY

UNIT 4 TABLE 4 A. FISSION GASES NUCLIDES UNITS BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ci 7.81 EZ3 Kr-85 Ci Kr-85m Ci 1.50E-08 e-131m Ci 2.91E44 1.90E414 2.69E4I4 9.15 EBS e-133 Ci 3.06E-02 1.32E4I2 1.84E-02 3.45E<3 e-133m Ci 3.73E-04 1.23E-04 1.19E4I4 1.86E4I5 e-135 Ci 1.36E-04 9.43E4N 1.72E-OB B.85E-OB e-135m CI TOTAL FOR PERIOO CI 3.14EW2 1.35E%2 2.66E-02 3.57E.03 NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ci Kr-85 Ci Kr-85m Ci Kr.87 Ci Kr-88 CI e-131m Ci e-133 Ci e 133m Ci e-135 Ci e-135m Ci e-138 Ci TOTAL FOR PERNO CI B. IODINES NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr2 I Qtr3 Qtr 4 Br-82 Ci I-131 Ci I-133 CI TOTAL FOR PERNO Ci C. PARTICULATES NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 O-58 CI CO40 Ci n-54 CI Cr.51 Ci OTAL FOR PERIOO Ci page 18

'OSES t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 DUE TO IODINE,TRITIUIrf,AND PARTICULATES UNIT 4 TABLE 5 ~

PATHWAY UVER THYROID IQDNEY LUNG GI4.LI SKIN TOTAL BODY Cow milk - Infant (mrem) O.OOEa00 2.44E-OB 2A4E4)6 1.07E48 2A4E46 2A4E4)8 O.OOEa00 2A4E46 Fruit 6 Ve9 Fresh (mrem) O.OOE400 254E47 2.54E4)7 1.68E4)7 2.54E4)7 2$ 4E<7 O.OOE+00 254')7 Ground Plane (mrem) O.OOE+00 O.OOEa00 O.OOEa00 O.OOEa00 0.00&00 O.OOE+00 O.OOE+00 O.OOE+00 InhalaBon - Adult (mrem) O.OOE+00 1.1 OE4)8 I.t BED 1.10E46 1.1 OE4)8 1.1 OE4)8 O.OOE+00 1.10')8 TDTAI.(mrem) O.OOE+00 3.79E-OB 3.79E4)B 2.34E.OB 3.79E46 3.79E4KI O.OOE+00 3.79E46

% of Annual Limit O.OOEa00 2.53E4)5 2.53E4)5 1.56E4L5 2.53E4)5 2.53E<5 O.OOEa00 2.53E4)5 DOSES DUE TO NOBLE GASES Gamma Air Dose 1.74E4)8 L74E45 Beta Air Dose 1.75E4)8 8.75E4)8 page 19

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1997 THROUGH DECEMBER 1997 DOSES DUE TO IODINE,TRITIUIrtI,AND PARTICULATES Summation Table 5 PATHWAY BONE LIVER THYROID KIDNEY LUNG Gl-LLI SKIN TOTAL BODY Cow mNk - Infant O.OOEsOO 4.99E46 4.99E48 2.19E46 4.99E48 4.99E46 OOOE+00 4.99548 Fruit 6 Vee Fresh 0.00&00 5.20E47 5.20E47 3.43E47 5.20E47 5.20E47 O.OOE+00 5.20547 Ground Plane O.COE+00 O.OOE+00 0.00&00 0.005+00 O.DOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Inhalation - Adult O.OOE+00 2.25E46 2.25E46 2.25E46 2.25E46 2.25E46 O.OOE+00 2.25E46 TOTAL Imrem) 0.00&00 7.76E46 7.76E46 4.79E46 7.76E46 7.76E46 O.OOE+00 7.76E46

'A of Annual Umlt O.OOE+00 5.18E45 5.18E45 3.19E45 5.18E45 5.18545 O.DOE+00 5.18545 DOSES DUE TO NOBLE GASES Gamma Air Dose 1.83E45 1.83E44 Beta Atr Dose 9.71E46 4.86E45 page 20

TURKEY POINT UNITS,3 AND 4 1997 ANNUAL RADIOACTIVE EPPLUENTS RELEASE REPORT TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.'OLID WASTE SHIPPED OPP SITE FOR BURIAL OR DISPOSAL

1. TYPE OF WASTE UNITS 12 MONTH PERIOD ~o ERROR Spent resin, filters m~ 0.00 EO sludge, evaporator bottoms Ci 0.00 EO Dry Compressible waste m 4. 14 E1 (Note 1) Ci 9.27 E-1 20 Irradiated components m 0.00 EO Control rods, etc. Ci. 0.00 EO Other non-compressible m 1.86 El 20 Waste Ci 2. 02 E-4

2. ESTIMATE OP MAJOR NUCLIDE COMPOSITION OF TYPE OP WASTE UNITS VALUE

a. N/A

b. Cr-51 0 26 Co-58 ~O 0 17 Fe-55 ~O 0 15 Co-60 O~

0 13 Zr-95 O~

0 6 Ni-59 0 6

Ni-63 ~O 0 5 Ni-95 ~O 0 5 Ba-140 ~O 0 3 Np-237 O~

0 2 Ce-144 0

~o 1 Cs-137 O~

0 1 Page 21

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EPRLUENTS RELEASE REPORT TABLE 6

c. N/A UNITS VALUE

d. Fe-55 50 H-3 15 Co-60 15 Ni-63 5 Zn-65 5 Ni-59 5 Sb-125 5

3. SOLID WASTE DISPOSITION Number of shi ments Mode of trans ort Destination 7 (Note 2) Sole use truck Oak Ridge, TN 1 (Note 2) Sole use truck Barnwell, SC 1 (Note 2) Sole use truck Kingston, TN B. IRRADIATED FUEL SHIPMENTS None Page 22

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 6 SOLID WASTE SUPPLEMENT Total (NOTE 3) (NOTE 4) (NOTE S) (NOTE 6)

Waste Volume Total Principal Type of R.G. 121 Type of Solidification ClassiEcation pts Curie Radionuclidcs Waste Category Container of Absorbcrs Quantity Agent Cbss A 1462.8 0.927 None Compactable lb. Strong Waste Tight N/A Class A 658 None Waste ld. Strong NIA Oil Tight Page 23

1

'

'lv

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EPRLUENTS RELEASE REPORT TABLE 6 Dry compressible waste volume indicates volume shipped to burial site following reduction by a waste processing facility was 41.4m'.

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 material shipped to Kingston, Tennessee was waste oil, which was destroyed by burning. The material shipped directly to Barnwell was processed by Chem Nuclear Systems Incorporated at the Chem Nuclear Consolidation Facility and buried.

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 quantitive techniques. The Turkey Point Plant follows the guidelines in the Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (5/11/83) for these determinations.

The most frequently used techniques for determining the total activity in a package are the dose to curie method and interference from specific activity and mass or activity concentration and volume. Activation analysis may be applied when it is appropriate.

The total activity determination by any of these methods is considered to be an estimate.

The composition of radionuclides in the waste is determined by both on-site analysis for principle gamma emitters and periodic off-site analyses for difficultto 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 61.55.

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".

Type of container refers to the transport package.

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