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1991 Annual Radiological Environ Operating Rept. W/920428 Ltr
	ML17348B479
Person / Time
Site:	Turkey Point
Issue date:	12/31/1991
From:	Plunkett T; FLORIDA POWER & LIGHT CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	L-92-100, NUDOCS 9205040068
	Download: ML17348B479 (182)
	v • d • e

...,~ACCELERATED DI UTION DEMONST TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9205040068 DOC.DATE: 91/12/31 NOTARIZED: NO DOCKET g 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 PLUNKETT,T.F. Florida Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"1991 Annual Radiological Environ Operating Rept." W/920428 ltr. D DISTRIBUTION CODE: IE25D COPIES RECEIVED:LTR TITLE: Environmental Monitoring Rept (per Tech Specs)

J ENCL L SIZE: ~~

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P.O. Box 029100, Miami, FI33102-9100 APR 28 )gq~

L-92-100 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 1991 Annual Radiological Envirohmental 0 eratin Re ort This letter transmits the subject report in accordance with Technical Specification 6.9.1.3 for Turkey Point Units 3 and 4.

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

Very truly yours, T. F. Plunkett Vice President Turkey Point Nuclear TFP/CLM/cm Enclosure cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Ross C. Butcher, Senior Resident Inspector, USNRC, Turkey Point Plant 92050400bB 911231 PDR R

ADDCK 05000250 PDR I) an FPL Group company

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Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 003723827:1

Subject:

Draft Supplemental Environmental Impact Statement DISPOSAL OF PORTIONS OF THE FO RMER HOMESTEAD AIR FORCE BASE, FLORIDA VOLUME II: APPENDICES Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML003723827.

Page 1

Distri69.txt 4%0 A001 - OR Submittal: General Distribution Docket: 05000250 Docket: 05000251 Page 2

aP DEPARTMENT OF THE AIR FORCE WASHINGTON, DC Office of the General Counsel June 8, 2000 SAF/GCN 1740 Air Force Pentagon Washington D.C. 20330-1740 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 Homestead Air Force Base Property Disposal On behalf of the Air Force and the Federal Aviation Administration (FAA), I am providing a copy of the Draft Supplemental Environmental Impact Statement (SEIS), Disposal of Portions ofthe Former Homestead Air Porce Base, Florida (December 1999). This is in response to a suggestion made to me by Mr. Kahtan Jabbour, Office of Nuclear Reactor Regulation, that it would be useful to have the Draft SEIS available as part of the NRC's document system.

Sincerely, Douglas J. Heady Associate General Counsel (Installations &, Environment)

Attachment:

Draft SEIS, Disposal of Homestead AFB

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Item: ADAMS Document Library: ML ADAMS"HQNTAD01 ID: 003695989:1

Subject:

Annual Radioactive Effluent Release Report for January through December 1999 Body:

ADAMS DISTRIBUTION NOTIFICATION.

Electronic Recipients can RIGHT CLICK and OPEN the first Attachment to View the Document in ADAMS. The Document may also be viewed by searching for Accession Number ML003695989.

IE48 - 50.36a(a)(2) Semiannual Effluent Release Reports Page 1 p,pR 04 2M9

Distri79.txt Docket: 05000250 Docket: 06000261 Page 2

MAR 2 8 2000 PlPll L-2000-074 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 Annual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of January 1, 1999, through December 31, 1999, for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.1.4 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 President Turkey Point Plant GSS Attachment cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant an FPL Group company

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Turkey Point Plant Units 3 and 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT January 1999 through December 1999 Submitted by:

NUCLEAR CHEMISTRY DEPARTMENT FLORIDA POWER AND LIGHT COMPANY

. Mend, Radiochemistry Supervisor

. M. Murray, Chemistry Supervisor T nes, Operations Manager D. E. Jer 'n nt General Manager

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 Table Of Contents 1.0 REGULATORY LIMITS ...

2.0 EFFLUENT CONCENTRATION..........

3.0 AVERAGE ENERGY 4 4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY...

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 ~ ~ ~ 9 10.0 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS 11.0 PROCESS CONTROL PROGRAM REVISIONS... ~ .... ~........... ~...........

~ . ~ 9 12.0 INOPERABLE EFFLUENT MONITORING INSTRUMENTATION ......

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 1.0 REGULATORY LIMITS l.l ~Li ld Effl (a) The concentration of radioactive material released in liquid effluent t'o unrestricted areas shall not exceed ten times the concentration specified in 10CFR20 Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained gases. For dissolved or entrained noble gases, the concentration shall not exceed 2.0E-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 ef'fluents 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.

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 2.0 EFFLUENT CONCENTRATION Water: In accordance with 10CFR20, Appendix B, Table 2, Column 2, and for entrained or dissolved noble gases as described in l.l.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 effiuents is not applicable.

4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY 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 ~ctivite 'as detected on the samples using the Plant Technical Specification analysis techniques to achieve the required Lower Limit of Detection ("LLD")

sensitivity for radioactive effiuents.

4.1 ~Li 4 ~ Effl 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 if any radioactivity was being released'via the steam generator blowdown system and the storm drain system.

4 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.

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C'URKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 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.

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 I999 THROUGH DECEMBER 1999 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 1999 through December 1999, 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 1999 THROUGH DECEMBER 1999 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 + 2+7% + 11.0%

5.0 BATCH RELEASES

5. 1 LKIUID Unit 3 Unit 4 a) Number of releases 1.60E+02 1.60E+02 b) Total time period of batch releases, minutes 1.32E+04 1.32E+04 c) Maximum time period for a batch release, minutes 1-.45E+02 1.45E+02 d) Average time period for a batch release, minutes 7.82E+01 7.82E+01 e) Minimum time for a batch release', minutes 1.00E+00 1.00E+00 f) Average stream flow during period of release of effluent into a fiowing stream, liters-per-minute 4.85E+06 4.85E+06 5.1 GASEOUS Unit 3 Unit 4 a) Number of releases 1.05E+01 1.15E+01 b) Total time period of batch releases, minutes 4.04E+02 3.70E+04 c) Maximum time period for a batch release, minutes 4.50E+01 3.66E+04 d) Average time period for a batch release, minutes 3.84E+01 3.22E+03 e) Minimum time for a batch release, minutes 3.00E+01 3.00E+01 Page 7

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 6.0 UNPLANNED RELEASES 6.1 ~Li uid There were no unplanned liquid releases this period for either Unit 3 or Unit 4.

6.2 Gaseous There were no unplanned gas releases this period for either Unit 3 or Unit 4.

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

7.2 UIUt 4 Reactor coolant activity limits of 100/E-Bar and 1.0 uCi/gram Dose Equivalent 1-131 were not exceeded.

8.0 SITE RADIATIONDOSE The assessment of radiation dose from radioactive effiuents 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 fifty weeks 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:

Adult Inhalation Child Inhalation Bone (mrem) 3.67848 6.62E-08 Liver (mrem) 1.088-06 7.90E47 Thyroid (mrem) 1.838-05 2.31E45 Kidney (mrem) ,

1 ~ 128-06 5.18E-07 Lung (mrem) 1.03E46 7.22E-07 Gi-LLI(mrem) 1.04E46 7.26E47 Total Body (mrem) 1.06E46 7.73E-07 Gamma Air Dose (mrad) 5.01E45 Beta Air Dose (mrad) 6.87E45 Page 8

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 9.0 OFFSITE DOSE CALCULATIONMANUAL ODC REVISIONS The ODCM was revised once during this reporting period. The following changes are included in Appendix A:

a. Revised Control 5.3, Interlaboratory Comparison Program.

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

I 11.0 PROCESS CONTROL PROGRAM REVISIONS Revisions were made to the process control program during this reporting period. The revisions included:

a. Deleted references and sections covering solidification of various types of wastes because of equipment obsolescence.

b. Added processing requirements for wet radioactive waste such as resins, filters, waste oil, and liquid waste.

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

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 LI'QUID EFFLUENTS SUMhfARY UNIT 3 TABLE 1 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%

1. Total Release (not including tritium,gases, alpha Ci 331 E42 4reE43 3.16E43 1.15E42

. Average diluted concentradon duri the riod uCi/ml 9.52E-10 5.79E-10 3.78E-10 9.29E-10

. Percent of applicable limit 9.52E43 5.79E43 3.78E43 929 E43 B. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Est. Error (%)

1. Total Release CI 1.66E+02 539E+01 5$ 0E+01 1A8E+02

. Average diluted concentradon during!he riod uCi/ml 4.77E46 6.36E46 6.94E46 120E45

. Percent of ap licable limit 4.77E41 6.36E41 6.94E41 120E+00 C. DISSOLVED AND ENTRAINED GASES UNITS Qtr 1 Qtr 2 Qtr3 Qtr 4 Est. Error (%

1. Total Release Ci 193E43 3AOE44 8.13E45 326E44

. Average diluted concentration during the period uCVml 5.56E-11 4.01E-11 9.73E-12 2.64E-11

. Percent of applicable timit 2.78E45 2.01E45 1.32E45 D. GROSS ALPHA RADIOACTIVITY UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%

1. Total Release CI E. UQUID VOLUMES Qtr 1 Qtr 2 Qtr 3 Qtr 4 Esl. Error (%

1. Batch waste released, prior Io dilution UTERS 1.82E+06 8.64E+05 3.34E+05 4 USE+05 10.00

. Continuous waste released, pdor to dilution UTERS

. Dilution water used durln period UTERS 3.47E+10 8.47E+09 8.36E+09 124E+10 page 10

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIYE EFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 19999 LIQUID EFFLUENTS

SUMMARY

UNIT 3 TABLE 2 NVCLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr W CI 4.97E46 1.25E46 2.56E46 1.11E43 Sr49 CI 2.60E48 2.10E48 1.40E45 1.73E45 Sr-90 CI 1.60E49 3.02E45 2.01E47 9.91E46 Na-24 CI r-51 Ci 2.31E44 4.45E45 1.12E44 Mn-54 CI 1.29E42 1.68E44 3.81E45 6.77E45 Co-57 CI 5.52E45 8.20E47 2.04E46 7.13E45 Ci 8.58E43 2.16E43 1.37E43 5.17E43 Fe-59 Ci 1.96E44 6.53E46 Ci 8.79E43 6.47E44 6A4E44 1.80E43 CI CI 3.16E41 8.20E45 8.26E45 5.57E45 Ci 5.25E45 4.11E45 1.47E45 CI Ru-103 CI 9-110 Ci 7.87E44 2.60E43 Sn-113 Ci 3.49E45 n-117 CI 3,61E46 Sb-124 CI 7.05E45 4.05E44 Sb-125 CI 6.54E44 1.27E43 1.70E44 4.00E44 l-131 CI 2.90E46 6.25E47 I-133 Cj 1-134 Ci 1.30E46 s-1 34 Ci 7.02E46 t-135 Ci s-137 3.62E45 2ASE45 La-140 Ci 1.55E45 1.52E46 1.15E45 Ce-141 CI CI

-187 Ci 2ASE45 7.45E45 1.38E44 N 239 AL FOR PKRIOO Ci 3.31E42 4.90E43 3.16E43 1,15E42 VQUID EFFLUENTS - DISSOLVED GAS

SUMMARY

NUCLIDES BATCH MODE RELEASED CI Ci 1.92E43 3.33E44 8.13E45 3.26E44 Ci 6.65E46 1.86E46 TOTAL FOR PER IOO Cj 1.93E43 8.13E45 '.26E44 VQUID EFFLUENTS - DOSE SUMMATION groop l Teenager ocation: Cool'anal Shoreline Dc 'on Dose rnrern TOTAL BODY 1.97E42 pag6 11

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 rd GASEOGr> EFFLUEHTS

SUMMARY

UNIT 3 TABLE 3 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qe2 Eea Bror (%)

1. Total Release 2.88E41 3.37E42 1.11Er00

. Average release rate for the period 3A8E42 428E43 1AOE41

. Percent of Technical Specification Limit 1.17E-12 1.31E.13 4.5IE-12 B. IODINES UNITS atr 3 E>L Bror (%)

1. Total Release 8.82E44 3A4

. Average release rate for the period 8.33E45

. Percent of Technical Specification Limit 1.14E41 C. PARTICULATES UNITS Est. Bror (%)

1. Psrticviates vrith hat(4rfe >8 da

. Average release rate for the period

. Percent of Technical S 'ation Ltm)t D. TRITIUM UNITS Est Bror ()t)

1. Total Release Average release rate for the period

. Percent of Technical Specifcaten Limit page 12

I, TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIYEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 GASEOUS EFFLUENTS

SUMMARY

UNIT 3 TABLE 4 A. FISSION GASES NUCUDES UIIIT8 BATCH MODE RELEASED Qtr1 Qtr 2 Qtr 3 Qtr 4 CI 3.23E44 2.91 E43 7.77E42 Ci 2.68E48 3.56E46 8 131m CI 3.24E43 1.30E43 Ci 2.63E41 2.93E42 1.01 E+00 CI 1.94E43 1.66E44 9.12E43 Ci 7.61E44 4.74E45 3.41 E43 TOTAL FOR PERCO CI 2.69841 3.37E42 1.10E+00 NUCUDES CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Ci Ci CI Ci CI 8-131m CI CI 8.133m CI Ci CI CI TOTAL FOR PERIOD Ci B. IODINES NUCUDES UIIIT8 CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Br42 CI I-131 Ci 2.70E44 I-133 CI TOTAL FOR PERIOD CI 2.70E44 C. PARTICULATES NUCUDES VIIIT8 CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 CI CI CI Cr%1 CI OTAL FOR PERIOD CI PBgB 13

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 g

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4 r DOSES DUE TO IODINE,TRITIUM, AND PARTICULATES UNIT 3 TABLE 6 PATHWAY BONE LUNG GLLLr SlON TOTAL BCOY minr - Infant (mrem 1.33E45 4.27E43 3.32E46 O.OOE+OO 4.98E47 7.77E46 1.11E45'.32E47 ruit & Veg Fresh (mrem) 5.45E47 1.77E44 3.33E47 O.OOE+00 O.OOE+00 4.11E47 7.38E48 7.38E48 7.38E48 7.38E48 8.97E48 Inhata8on - Adult mrem 2.16E48 3.06E48 1.02E45 5.26E4S O.OOE+00 5.38E49 O.OOE+00 1.75E48 TOTAL mrem 1.17E45 1.39E45 4.45E43 3.78E46 7.38E48 6.24E47 8.97E48 8.27E46

'/ of Annual Limit 7.83E45 9.28E45 2.97E42 2.52E45 . 4.92647 4.16E46 5.98E47 5.52E45 DOSE DUE TO NOBLE GASES Gamma Afr Dose 8.59E46 8.59E45 a Air Dose 2.87E45 1.43E4S page 14

I TURKEY POINT UNITS 3 AND 4

.ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 L/Q UID EFFLUENTS

SUMMARY

UNIT 4 TABLE 1 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 4 Est. Enor %)

1. Total Release (not induding tntium,gases. alpha) 3.31E4)2 4.90E43 3.16E43 1. 15E4)2

. Averagedriuted oncenttauon durin the pericd uCI/mt 9.52E 10 5.79E-10 3.78E-10 9.29E-10

. Percent ot applicable emit 9.52E43 5.79E43 3.78E4)3 9.29E4)3 B. TRITIUM UNITS Qtr 1 Qtr 2 Ctr 3 Esl Error %)

1. Total Release 1.66E+02 5.39E+01 5.80E+01 1.48E+02

. Average diluted concentration during the period 4.77E4)6 8.36E46 6.94E4)6 1.20E4)5

. Percent of applicable limit 4.77E4)I 6.36E4) I 6.94E4)I t.20E+00 C. DISSOLVED AND ENTRAINED OASES UNITS

1. Total Release

, Average di1uted concentration during the period 5.56E-11 4.01E-11 9.73E.12 2.64E-11 I-..~. 'i;I! '--i, I'.i,'i.:i

. Percent of applicable limit 2.78E45 2.01E4)5 4.86E46 D. GROSS ALPHA RADIOACTIVITY UNITS Qtr 1 Qtr4 Esl Error %

1. Total Release E. LIQUIDVOLUMES Est. Error (%)

1. Batch waste released. 'o dilution lITERS 4.95E+05 Continuous waste released, prior to dilution UTERS

. Dilution water used during period LITERS 3.47E+10 8.47&09 8.36Ei09 1.24E+10 page 15

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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 UQUID FFFI UENTS SUNNARY UNIT 4 TABLE 2 NUCLIDES UNITS BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ci 4.97E46 1.25E46 2.56E46 1.11E43 Sr@9 Ci 2.60E48 2.10E48 1 40E45 1.73E45 Sr-90 Ci 3.02E45 2.01E47 9.91E46 Na-24 Ci r-51 Ci 2.31E44 4.45E45 1.12E44 Mn-54 CI 1.29E42 1.68E44 3.81E45 6.77E45 Co-57 Ci 5.52E45 8.20E47 2.04E46 7.13E45 Ci 8.58E43 2.16E43 1.37E43 5.17E43 Fo49 Ci 1.96E44 6.53E46 CI 8.79E43 6.47E44 6A4E44 1.80E43 Ci CI 3.16E44 8.20E45 6.26E45 5.57E45 r-95 CI 5.25E45 4.11E45 1.47E45 Mo-99 Ci Ru-103 Ci 9-110 Ci 7.87E44 1.36E45 2.60E43 Sn-113 Ci 3.49E45 Sn-117 Ci 3.61E46 Sb-124 CI 7.05E45 4.05E44 Sb-125 CI 6.54E44 1.27E43 1.70E44 4.00E44 I-131 CI 2.90E46 6.25E47 I-133 Ci I-134 CI 1.30E46 Cs-134 Ci 7.02E46 I-135 CI Cs-137 Ci 4.09E44 3.62E45 6.94E46 2ASE45 La-140 Ci 1.55E45 1.52E46 1.15E45 141 CI 1.96E46

-187 CI 2.48E45 7.45E45 1.38E44 N 239 CI OTAL FOR PERIOO Ci 3.31E42 4.90E43 3.16E43 1.15E42 LIQUIDEFFLUENTS - DISSOLVED GAS SUNNARY NVCLIDES UNITS BATCH MODE RELEASED Qtr 2 Qtr 4 Ci Ci o-131m CI 1.92E43 3.33E44 8.13E45 3.26E44 o-133m CI 6.65E46 6.65E46 Ci TOTAL FOR PERIOO CI 1.93E43 3.40E44 8.13E45 '.26E44 LIQUIDEFFLUENTS - DOSE SUNNATION e gnwp: Teenager fion r Cooli Canal horeline Deposition Dose mrem % of Annual Limit OTAL BODY 5.92E44 1.97E42 page 16.

'I I J'i

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999

~ GASEOUS EFFLUENTS

SUMMARY

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

1. Total Rekrsse Ci 4.65E4)1 3.37E4)2 1.11E+00 2.79

. Average release rate for the period 5.98E4)2 4.28E4)3 (.40E4) I

. Percenl of Technical Specification Limit 2.66E 11 1.31E-13 4.51E 12 B. IODINES UNITS Qir 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (1()

1. Total Release Ci 6.62E4)4 3.44 Average rekrsse rate for the period uCilsec 8.33E4)5

. Percent of Technical Specification Limit 1.14E4)I C. PARTICULATES UNITS Quf Qtr2 Qtr 3 Qtr 4 EsL Errcr (%)

1. Psrticulates withhatf4ife >8 days 2.50

. Average release rate for the period

. Percenl of Technksl Speciyication Limit

. Gross AIpha Radioactivity Ci D. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 4 Est. Error (14)

1. Total Release Ci 3.57E4) 1

. Average release rate for the period 4.59E4)2

. Percent of Technksl Specification Limit 2.68E4)6 page 17

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVERELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 GASEOUS EFFLUENTS SUhfhfARY UNIT 4 TABLE 4 A. FISSION OASES NVCLIDES UNITS BATCH MODE RELEASED Ci 1.96E<1 7.36E48 CI 3.23E44 2.91 E43 7.77E4I2 Ci 3.56E48 2.68'.24E~

e-131m Ci 1.30E~ 1.38E4I2 Ci 2.63E%1 2.93E4I2 1.01E+00 Ci 1.94E4I3 1.66E4I4 9.12' CI 7.61E4I4 4.74&6 41E43 e-135m TOTHER fOR PFRCO Ci 4.65E<t 3.37E42 1.11E+00 O.OOE+00 NUCLIDES UNITS CONTINUOUS MODE RELEASED Ci Ci Ci Kr4S e-131m CI Ci e-135m CI TOTR FOR PFRIOO CI K IODINES NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 2 Br42 CI l-1 31 Ci 2.70E44 l-133 CI TOTAL FOR PERIOO Ci 2.70E44 C. PARTICULATES NVCLIDES CONTINUOUS MODE RELEASED Qtr 1 Qtr 4 Ci Ci Ci AL FOR PERXS Ci page 18

4

~

r

TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1999 THROUGH DECEMBER 1999 DOSEZi DUE TO IODINE, TRI TIUhl, AND PARTICULATES UNIT 4 TABLE 6 PATHWAY 8ONE LIVER THYROID IODNEY LUNG GH.U SKIM TOTAL BODY milk - intent mrem 1.11E45 4.27E43 3.18E46 O.DOE+00 ru'a a Veg Free mrem 5.32E47 8.25E47 1.78E44 5.17E47 2.80E47 3.26E47 0.00&00 6.91 E47 round Rane (mrem 7.38E48 7.38E48 T.38E48 7.38E48 7.38E48 7.38E48 8.97E48 7.38E48 Inhahtion - Adult mrem 2.16E48 1.24E46 1.14E45 1.26E46 1.21E46 1.22E46 O.OOE+00 OTAL mrem 1.17E45 1.81E45 4.46&6 6.35E48 4.25E46 4.80E46 8.97E48 1.24E45 or Annual Limit 7.83E45 1.21E44 2.97E42 4.24E45 2.83E45 3.20E45 5.98E47 8.30E45 DOSES DUE TO NOBLE GASES mma Air Dose 4.16E45 4.16E44 Beta Air Dose 4.00E45 2.00E44 page 19

f t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY1999 THROUGH DECEMBER 1999 t

'v DOSES DUE TO lODIHE',TRI77UM, AND PAR77CULATES Summation Table 5 PATHWAY BONE UVER THYROlD K$0NEY LUNG GsLLI SKIN TOTAL BODY mair- infant 2.22E45 292 E45 8.54E43 7.82E48 2.68E48 3.68E48 0.00E+00 1.82E45 ruit & V Fresh 1.06E46 1.37E48 3.55E44 8.50E47 2.80E47 3.73E47 0.00E+00 1.10E48 round Bane $ .48E47 $ .48E47 1.48E47 1.48E47 1.48E47 1.48E47 1.79E47 1.48E47 nhalaaon - Adult 4.31E48 1.27E48 2.16E45 1.21E46 0.00'0 TOTAL mrem 2.35E45 3.20E45 &91E43 1.01 E45 5.42E48 1.79E47 207E45

% of Annual Limit 1.57E44 2.13E44 5.94E42 6.76E45 3 61E45 1.20E46 1.38E44 DOSES DUE TO NOBLE GASES mma Air Dose 5.01E45 5.01E44 AlrDose 8.87E45 3.43E44 page 20

v I+ I t,

TURKEY POINT UNITS 3 AND 4 1999 ANNUALRADIOACTIVEEFFLUENTS RELEASE REPORT TABLE 6 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A. SOLID WASTE SHIPPED OFF SITE FOR BURIALOR DISPOSAL

1. TYPE OF WASTE UNITS 12 MONTH PERIOD % ERROR 3

a. Spent resin, filters m 17. 20 sludge, evaporator bottoms Ci 830.

b. Dry Compressible waste m3 33.

(Note I) Ci 1.6 20

c. Irradiated components m 0.00 Control rods, etc. Ci 0.00

d. Other non-compressible m 5. 20 Ci 2.7 'aste

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION OF TYPE OF WASTE UNITS 'ALUE C-14 MN-54 5 FE-55 25 Co-57 Co40 28 NI43 15 NI-59 5 AG-I IOM I CS-134 5 CS-137 5 CE-144 2 SR-89 I SR-90 2 Page 21

TURKEY POINT UNITS 3 AND 4 1999 ANNUALRADIOACTIVEEFFLUENTS RELEASE REPORT TABLE 6 UNITS VALUE CR-51 I MN-54 2 Co-SS 5 FE-55 36 Co-60 35 Ni-63 17 Nb-95 I SB-125 I C-14 I ZR-95 1 N/A UNITS VALUE Co-57 5 MN-54 5 Co-58 45 FE-55 10 Co-60 20 Ni-63 10 CS-137 5

3. SOLID WASTE DISPOSITION A. Number ofshi ments Destination 10 (Note 2) Sole use truck Oak Ridge, TN 5 (Note2) Sole use truck Barnwell, SC I (Note2) Sole use truck Richland, WA.

B. IRRADIATED FUEL SHIPMENTS None Page 22

TURKEY POINT UNITS 3 AND 4 l999 ANNUALRADIOACTIVEEFFLUENTS RELEASE REPORT TABLE 6 SOLID WASTE SHIPMENT Total (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) waste Volume Tocal Principal Type of R.G. 121 Type of Solidification Classification Pt3 Curie Radionuclides Waste Category Container or Absorbers Quantity Agent Class A 1165. 1.6 None Compaccible lb. Strong waste Tight N/A Class A 189. 2.7 None Non-Compressible ld. Cask N/A waste P

Class B 120.3 2 ' None Dewatered la. Cask N/A Filters Class B 481. 418 None Dewatered la. Cask N/A Resin Class C 120.3 409 None Dewatered la. Cask N/A Resin Page 23

4' TURKEY POINT UNITS 3 AND 4 1999 ANNUAL RADIOACTIVE EFFLUENTS RELEASE REPORT TABLE 6 NOTE 1: Dry compressible waste volume indicates volume shipped to a burial site following reduction by a waste processing facility was 33 Cubic Meters.

NOTE 2: 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 or Clive, Utah in accordance with the appropriate burial license activity limits. The material shipped directly to Barnwell was processed by CNSI and buried. Material transported to Richland, Washington was cosigned to a licensed processing facility.

NOTE 3: 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 (5/11/83) for these determinations.

The most frequently used techniques for determining the total activity in a package are the dose to curie method and 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.

The composition of radionuclides in the, waste is determined by periodic off-site analyses for difficult to measure isotopes. Off-site analyses are used to establish scaling factors or other estimates for difficult to measure isotopes and principle Gamma emitters.

NOTE 4: 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.

NOTE 5: Type of waste is specified as described in NUREG 0782, Draft Environment Impact Statement on 10 CFR

$ 61 "Licensing Requirements foi Land Disposal of Radioactive Waste".

NOTE 6: Type of container refers to the transport package.

Page 24

APPENDIX A ODCM CHANGES 1999

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQU)D EFFLUENTS FROM THE TURKEY POINT PLANT UNITS 3 AND 4 REVISION 8 CHANGE DATED 03/02/99 Florida Power and Light Company PNSC

~vpaovAt.f S~ ~ (ir t

rL-..MGR.

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TURKEY POINT UNIT 3 8 4 OFFSITE DOSE CALCULATIONMANUAL LIST OF EFFECTIVE PAGES Offsite Dose Calculation Manual Revision Revision Revision

~Pa e Date ~Pa e Date ~Pa e Date I 3/02/99 2-13 2/14/96 3-15 2/14/96 II 3/02/99 2-14 2/14/96 3-16 2/14/96 III 3/02/99 2-15 2/14/96 3-17 2/14/96 IV 3/02/99 2-16 2/14/96 3-18 2/14/96 v 3/02/99 2-17 2/14/96 3-19 2/14/96 VI 3/02/99 2-18 2/14/96 3-20 2/14/96 VII 3/02/99 2-19 2/14/96 3-21 1/30/98 VIII 3/02/99 2-20 2/14/96 3-22 2/14/96 1-1 2/14/96 2-21 2/14/96 3-23 2/14/96 1-2 2/14/96 2-22 2/14/96 3-24 2/14/96 1-3 2/14/96 2-23 2/14/96 3-25 2/14/96 1-4 2/14/96 2-24 2/14/96, 3-26 2/14/96 1-5 2/14/96 2-25 2/14/96 . 3-26 2/14/96 1-6 2/14/96 2-26 2/14/96 3-28 2/14/96 1-7 2/14/96 2-27 2/14/96 3-29 2/14/96 1-8 2/14/96 2-28 1/30/98 3-30 2/14/96 1-9 2/14/96 2-29 2/14/96 3-31 2/14/96 1-10 2/14/96 2-30 2/14/96 3-32 2/14/96 1-11 2/14/96 2-31 2/14/96 3-33 2/14/96 1-12 2/14/96 2-32 2/14/96 3-34 2/14/96 1-13 2/14/96 2-33 2/14/96 3-35 2/14/96 1-14 2/14/96 2-34 2/14/96 3-36 2/14/96 1-15 2/14/96 3-1 2/14/96 3-37 2/14/96 1-16 2/14/96 3-2 1/30/98 3-38 2/14/96 2-1 2/14/96 3-3 2/14/96 3-39 2/14/96 2-2 2/14/96 3P 2/14/96 3-40 2/14/96 2-3 2/14/96 3-5 2/14/96 3-41 2/14/96 2-4 2/14/96 3-6 2/14/96 3-42 2/14/96 2-5 2/14/96 3-7 2/14/96 3-43 2/14/96 2-6 2/14/96 3-8 2/14/96 3-44 2/14/96 2-7 1/30/98 3-9 2/14/96 3-45 2/14/96 2-8 2/14/96 3-10 2/14/96 3-46 2/14/96 2-9 2/14/96 3-11 2/14/96 3-47 2/14/96 2-10 2/14/96 3-12 2/14/96 3-48 2/14/96 2-11 2/14/96 3-13 2/14/96 3-49 2/14/96 2-12 2/14/96 3-14 2/14/96 3-50 2/14/96 03/02/99 Rev 8

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATIONMANUAL e

1 I LIST OF EFFECTIVE PAGES Offsite Dose Calculation Manual Revision Revision Revision

~Pa e Date Pacae Date Pacae Date 3-51 2/14/96 5-9 2/14/96 38-12 2/14/96 3-52 2/14/96 5-10 2/14/96 38-13 2/14/96 3-53 2/14/96 5-11 2/14/96 38-14 2/14/96 3-53 2/14/96 5-12 2/14/96 38-15 2/14/96 3-54 2/14/96 5-13 2/14/96 38-16 2/14/96 3-55 2/14/96 5-14 2/14/96 38-17 2/14/96 3-56 2/14/96 5-15 2/14/96 38-18 2/14/96 3-57 2/14/96 5-16 2/14/96 38-19 2/14/96 3-58 2/14/96 5-17 2/14/96 38-20 2/14/96 3-59 2/14/96 5-18 2/14/96 38-21 2/14/96 3-60 2/14/96 5-19 2/14/96 38-22 2/14/96 3-61 2/14/96 5-20 2/14/96 =-

38-23 2/14/96 3-62 2/14/96 5-21 3/02/99 38-24 2/14/96 3-63 2/14/96 5-22 3/02/99 38-25 2/14/96 3-64 2/14/96 5-23 3/02/99 38-26 2/14/96 3-65 2/14/96 5-24 3/02/99 38-27 2/14/96 3-67 2/14/96 2A-1 2/14/96 38-28 2/14/96 3-68 2/14/96 2A-2 2/14/96 38-29 2/14/96 3-69 2/14/96 2A-4 2/14/96 38-30 2/14/96 3-70 2/14/96 3A-1 2/14/96 38-31 2/14/96 4-1 2/14/96 3A-2 2/14/96 38-32 2/14/96 4-2 2/14/96 3A-3 2/14/96 38-33 2/14/96 4-3 2/14/96 3A-4 2/14/96 3B-34 2/14/96 4-4 2/14/96 3A-5 2/14/96 38-35 2/14/96 4-5 2/14/96 3A-6 2/14/96 38-36 2/14/96 4-6 2/14/96 3A-7 2/14/96 3B-37 2/14/96 4-7 2/14/96 38-1 2/14/96 38-38 2/14/96 4-8 2/14/96 3B-2 2/14/96 3B-39 2/14/96 4-9 2/14/96 38-3 2/14/96 38-40 2/14/96 5-1 2/14/96 38-4 2/14/96 38-41 2/14/96 5-2 2/14/96 38-5 2/14/96 38-42 2/14/96 5-3 2/14/96 38-6 2/14/96 38-43 2/14/96 5-4 2/14/96 3B-7 2/14/96 38-44 2/14/96 5-5 2/'I4/96 3B-8 2/14/96 38-45 2/14/96 5-6 2/14/96 38-9 2/14/96 38-46 2/14/96 5-7 2/14/96 38-10 2/14/96 38-47 2/14/96 5-8 2/14/96 38-11 2/14/96 38-48 2/14/96 03/02/99 Rev 8

TURKEY POINT UNIT 3 8 4 OFFSITE DOSE CALCULATIONMANUAL LIST OF EFFECTIVE PAGES Offsite Dose Calculation Manual

~Pa e Date 3B-49 2/14/96 3B-50 2/14/96 3B-51 2/14/96 3B-52 2/14/96 3B-53 2/14/96 3B-54 2/14/96 3B-55 2/14/96 3B-56 2/14/96 3B-57 2/14/96 3C-1 2/14/96 3C-2 2/14/96 3C-3 2/14/96 5A-1 2/14/96 5A-2 2/14/96 5A-3 2/14/96 5A-4 2/14/96 03/02/99 Rev 8

TURKEY POINT UNIT 3 8 4 OFFSITE DOSE CALCULATIONMANUAL

'ABLE OF CONTENTS Introduction IV 1.0 Administrative Controls Control 1.1 ODCM Review and Approval .

Control 1.2 Major Changes to Liquid and Gaseous Radwaste Treatment Systems . 1-2 Control 1.3 Annual Radioactive Release Report. 1-3 Control 1.4 Annual Radiological Environmental Operating Report ... 1-5 Control 1.5 Definitions 1-6 Control 1.6 Applicability of Controls 1-14 Control 1.7 Surveillance Requirements 1-15 Figure 1.5-1 Site Area Map 1 -12 Figure 1.5-2 Plant Area Map 1-13 2.0 Li uid Effluents 2.0 Liquid Effluent System Description 2-1 Control 2.1 Radioactive Liquid Effluent Monitoring Instrumentation ... ...2-5 Control 2.2 Liquid Effluent Concentration . 2-14 Control 2.3 Dose From Liquid Effluents 2-25 Control 2.4 Requirements For Use Of Liquid Radwaste Treatment System 2-32 Figure 2 -1 Radioactive Liquid Waste 2-4 Appendix 2A Radioactive Liquid Waste Pathway dose Transfer Factors .......... 2A - 1 3.V 03/02/99 Rev 8

TURKEY POINT UNIT 3 8 4 OFFSITE DOSE CALCULATIONMANUAL TABLE OF CONTENTS continued 3.0 Gaseous Effluents 3.0 Gaseous Effluent System Description . 3-1 Control 3.1 Radioactive Gaseous Effluent Monitoring Instrumentation 3 - 10 Control 3.2 Dose Rate From Gaseous Effluents 3- 27 Control 3.3 Dose From Noble Gas In Gaseous Effluents .................... 3-44 Control 3.4 Dose From Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form 3- 52 Control 3.5 Requirements For Use Of Gaseous Radwaste Treatment System . 3- 67 Figure 3 - 1 Radioactive Gaseous Waste '-8 Figure 3-2 Locations of Airborne Effluent Dose Calculations ... 3-9

- Appendix 3A Reference Meteorology Annual Atmospheric Dispersion Factors 3A-1 Appendix 3B Pathway Dose Transfer Factors 3B -1 Appendix 3C Technical basis for A, 3C -1

4. Total Dose Control 4.1 Annual Dose From the Uranium Fuel Cycle ... 4-1 03/02/99 Rev 8

C TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATIONMANUAL TABLE OF CONTENTS continued

5. Radiolo icalEnvironmentalMonitorin Pro ram Control 5.1 Sampling and Analysis Program 5-1 Control 5.2 Land Use Census ........................ 5-19 Control 5.3 Interlaboratory Comparison Program 5-21 Figure 5.1-1 Near Site sampling Locations 5-17 t

Figure 5.1-2 Distant REMP sampling Locations 5- 18 Appendix 5A Supplemental Radiological Environmental Sampling Program 5A - 1 Vl 03/02/99 Rev 8

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATIONMANUAL

'NTRODUCTION PURPOSE This manual describes methods which are acceptable for calculating radioactivity concentrations in the environment and potential offsite doses associated with liquid and gaseous effluents from the Turkey Point Nuclear Units. These calculations are performed to satisfy Technical Specifications and to ensure that the radioactive dose or dose commitment to any member of the public is not exceeded.

The radioactivity concentration calculations and dose estimates in this manual are used to demonstrate compliance with the Technical Specifications required by 10 CFR 50.36. The methods used are acceptable for demonstrating operational compliance with 10 CFR 20.1302, 10CFR50 Appendix I, and 40CFR190. Only the doses attributable to Turkey Point Units 3 and 4 are determined in demonstrating compliance with 40CFR190 since there are no other nuclear facilities within 50 miles of the plant. Monthly calculations are performed to verify that potential offsite releases do not exceed Technical Specifications and to provide guidance for the management of radioactive effluents. The dose receptor is described such that the exposure of any member of the public is not likely to be substantially underestimated.

Quarterly and annual calculations of committed dose are also performed to verify compliance with regulatory limits of offsite dose. For. these calculations, the dose receptor is chosen on the basis of applicable exposure pathways identified in a land use survey and the maximum ground level atmospheric dispersion factor (X/Q) at a residence, or on the basis of more conservative conditions such that the dose to any resident near the plant is not likely to be underestimated.

The radioactive effluent controls set forth in this ODCM are designed to allow operational flexibilitybut still maintain releases and doses "as low as is reasonably achievable"; that is, within the objectives of Appendix I, 10 CFR Part 50 and comply with the limits in 10 CFR 20.1302.

The methods specified in the OFFSITE DOSE CALCULATIONMANUAL(ODCM) for calculating doses due to planned or actual releases are consistent with the guidance and methods provided in:

Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1. October 1977.

Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.

V11 03/02/99 Rev 8

TURKEY POINT UNIT 3 8 4 OFFSITE DOSE CALCULATIONMANUAL

'NTRODUCTION, continued Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

The required detection capabilities for radioactive materials in liquid and gaseous waste samples are tabulated in terms of the lower limits of detection (LDD's). Detailed discussion of the LLD and other detection limits, can be found in Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements,"

NUREG/CR-4077 (September 1984), in HASL Procedures Manual, HASL300 and in Hartwell, J. K "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

V3.3.3. 03/02/99 Rev 8

r TURKEY POINT UNIT 3 8 4 OFFSITE DOCSE CALCULATIONMANUAL 0 )

'.0 'ADILOGICALENVIRONMENTALMONITORING PROGRAM CONTROL 5.3: INTERLABORATORYCOMPARISON PROGRAM Analyses shall be performed on all samples, supplied as part of an Interlaboratory Comparison Program, that correspond to the matrices shown on Table 5.3-1

,I This control may be satisfied by participation in a government sponsored radiological measurements Intercomparison program that involves at least three of the matrices shown in Table 5.3-1 k

APPLICABILITY: At all times.

ACTION:

With analysis not being performed as required above, report the corrective actions taken to prevent recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Control 1.4.

b. The provisions of Control 1.6.3 are not applicable.

SURVEILLANCE REQUIREMENTS:

5.3.1 A summary of the results obtained, as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 1.4.

METHOD 5.3:

5.3.1 The Program shall be conducted such that on an annual basis:

At least three of the matrices will be involved, and at least two of the analytical methods will be evaluated, and for Gamma Spectroscopy, a majority of the nuclides shown in Table 5.3-1 will be included.

5.3.2 Any laboratory approved by FP8 L may provide samples for the Intercomparison Program provided that the radioisotopes used for sample preparation are traceable to the National Institute of Standards and Technology (MIST).

5-21 03/02/99

TURKEY POINT UNIT 3 8 4 OFFSITE DOCSE CALCULATIONMANUAL 4'i w

'.0 'ADILOGICALENVIRONMENTALMONITORING PROGRAM METHOD 6.3: ( continued )

5.3.3 Analysis of Matrix samples shall be capable of achieving ODCM Table 5.1-3 prescribed Lower Limit of Detection (LLD) on a blank sample.

5.3.4 Results within 20% of expected should be considered acceptable. Results exceeding 20% but within 35% require a description of probable cause and actions performed to bring the analysis into conformance. Results exceeding 35% are considered Not Acceptable; the Matrix shall be replaced and reanalyzed.

BASIS 6.3: INTERLABORATORYCOMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR 50. tt The Interlaboratory Comparison Program described herein provides an independent check on the precision and accuracy of the radiological monitoring measurements conducted as part of the Radiological Environmental Monitoring Program. The purpose of the Interlaboratory Comparison Program described in this appendix is to provide adequate confidence in the results of Turkey Point's radiological monitoring measurements, by providing an independent test of the ability to measure radionuclides in the sample medium.

5-22 03/02/99

TURKEY POINT UNIT 3 8 4 OFFSITE DOCSE CALCULATIONMANUAL 5.0 RADILOGICALENVIRONMENTALMONITORING PROGRAM TABLE 5.3-1 INTERLABORATORYCOMPARISON PROGRAM SAMPLE ANALYSIS "i Analytical ANALYSIS WATER P) AIRBORNE PARTICULATE OR SOIL VEGETATION Method < ~

GASES GB Gross Beta X H3 H-3 X Co-57 X Co-60 X X Cs-134 X Cs-137 X X X Ce-144 X GS Mn-54 K-40 Ru-106 Sb-125 X 5-23 03/02/99

gl TURKEY POINT UNIT 3 8 4 OFFSITE DOSE CALCULATIONMANUAL

~

5X) . RADIOLOGICALENVIRONMENTALMONITORING PROGRAM TABLE NOTATIONS .

The sample matrices shown on table 5.3-1 correspond to the matrices shown in Tables 5.1-1 8 5.1-2, with the following exceptions:

Milk is not currently in the REMP sampling program; there are no milk animals in the area encompassed by the Land Use Census. Therefore, inclusion of milk samples in the Interlaboratory Comparison Program is not required. Continued exclusion of milk in the lnterlaboratory Comparison Program is acceptable until the Land Use Census indicates the existence of milk producing animals within the geographic area covered by REMP; see note 3, below.

b. The INGESTION exposure pathway is represented by inclusion of Broad Leaf

-Vegetation in the Interlaboratory Comparison Program cross checks. Fish and Invertebrate samples are not included in the cross check program due to the instability of maintaining radioactivity in a fixed matrix due to decaying tissue and refrigeration limitations, The analytical methods to be evaluated are those applied in the current REMP:

a. GB Gross Beta analysis of an Air Filter matrix

b. H3- Tritium in water, using method employed in REMP

c. GS Gamma Spectroscopy, Quantitative.

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3. The Gamma Spectroscopy method for water will suffice for Gamma Spectroscopy of Milk, should milk samples become available. Milk is over 98 % water.

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1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 5 4 LICENSE NOS. DPR-31,. DPR-41 DOCKET NOS. 50-250, 50-251 DATA SUBMITTED BY: Ft.ORZDA DHRS PREPARED BY: 38>e a REVIEWED BY: ~/-z

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1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 & 4 TABLE OF CONTENTS DESCRIPTION PAGE Introduction Radiological Environmental Monitoring Program Discussion and Interpretation of Results Environmental Radiological Monitoring Program TABLE 1 Annual Summary t Deviations/Missing Data Analyses with LLDs Above Table 4.12-1 Detection Capabilities TABLE 1A TABLE 1B Land Use Census TABLE 2 Key to Sample Locations ATTACHMENT A Radiological Surveillance of Florida Power ATTACHMENT B and Light Company's Turkey Point Site First Quarter, 1991 Second Quarter, 1991 Third Quarter,,1991 Fourth Quarter, 1991 Results from the Interlaboratory Comparison ATTACHMENT C Program, 1991 REPORT/RADENVOP.PTN

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1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 6 4 EXECUTIVE

SUMMARY

The data obtained through the Turkey Point Radiological Environmental Monitoring Program verifies the levels of radiation and concentrations of radioactive material in environmental samples is not increasing. These measurements verify that the dose or dose commitment to members of the public, due to operation of Turkey Point Units 3 & 4, during the surveillance year, is well within the limits established by 10 CFR 50, Appendix I.

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1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 & 4 I'NTRODUCTION This report is submitted pursuant to Specification 6.9 of Turkey Point Units 3 & 4 Technical Specifications. The Annual Radiological Environmental Operating Report provides information, summaries and analytical results pertaining to the Radiological Environmental Monitoring Program for the calendar year indicated.

This report covers surveillance activities meeting the requirements of Unit 3, and Unit 4 Technical Specifications.

II'ADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A. ~Pur ose The purpose of the radiological environmental monitoring program is to provide representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of members of the public resulting from station operation. The radiological environmental monitoring program also supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

B. Pro ram Descri tion The Radiological Environmental Monitoring Program for the Turkey Point Plant is conducted pursuant to Technical Specifications 3/4.12 of Turkey Point Unit 3 & 4 Technical Specifications.

1. Sample Locations, Types and Frecpxencies:

a. Direct radiation gamma exposure rate is monitored continuously at 21 locations by thermoluminescent dosimeters (TLDs). TLDs are collected and analyzed quarterly.

b. Airborne radioiodine and particulate samplers are operated continuously at five locations. Samples are collected and analyzed weekly. Analyses include Iodine-131, gross beta, and gamma isotopic measurements.

REPORT/RADENVOP.PTN

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1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 & 4

c. Surface water samples are collected from three locations. Samples are collected and analyzed monthly. Analyses include gamma isotopic and tritium measurements.

d. Shoreline sediment samples are collected from three locations coinciding with the locations for surface water samples. Samples are collected and analyzed semi-annually. Sediment samples are analyzed by gamma isotopic measurements.

e. Fish and invertebrate samples are collected from the two locations coinciding with two of the locations for surface water samples. Samples are collected and analyzed semi-annually. Fish and invertebrate samples are analyzed by gamma isotopic measurements.

f. Broad leaf vegetation samples are collected from three locations. Samples are collected and analyzed monthly. Broad leaf vegetation samples are analyzed by gamma isotopic measurements.

Attachment A provides specific information pertaining to sample locations, types and frequencies.

2. Analytical Responsibility:

Radiological environmental monitoring for the Turkey Point Plant is conducted by the State of Florida, Department of Health and Rehabilitative Services (HRS).

Samples are collected and analyzed by HRS personnel.

Samples are analyzed at the HRS Environmental Radiation Control Laboratory in Orlando, Florida.

C. Anal tical Results Table l, Environmental Radicle ical Monitorin Procrram Annual ~Summar provides a summary for all specified samples collected during the referenced surveillance period.

Deviations from the sample schedule, missing data and/or samples not meeting the specified "A PRIORI" LLD, noted and explained in Tables 1A and 1B respectively.

if any, are Analysis data for all specified samples analyzed during the surveillance period is provided in Attachment B.

REPORT/RADENVOP,PTN (2)

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1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 & 4 D. Land Use Census A land use census out to a distance of 5 miles radius from the Turkey Point Plant is conducted annually to determine the location of the nearest milk animal, residence, and garden producing broad leaf vegetation in each of the sixteen meteorological sectors. A summary of the land use census for the surveillance year is provided in Table 2, Land Use Census

~summa No locations yielding a calculated dose or dose commitment greater than the values currently being calculated were identified by the land use census.

No locations yielding a calculated dose or dose commitment (via the same exposure pathway) 20% greater than locations currently being sampled in the radiological environmental monitoring program were identified by the land use census.

E. Interlaborator Com arison Pro ram The State of Florida HRS Environmental Radiation Control Laboratory participates in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by the Environmental Protection Agency. Results from the Interlaboratory Comparison Program are provided in Attachment C.

III'ISCUSSION AND INTERPRETATION OP RESULTS A. Re ortin of Results The Annual Radiological Environmental Operating Report contains the summaries, interpretations and information recpxired by the Turkey Point Units 3 & 4 Technical Specifications. Table 1 provides a summary of the measurements made for the nuclides required by Technical Specifications, Table 3.12-2, for all samples specified by Table 3.12-1. In addition, summaries are provided for other nuclides identified in the specified samples, including those not related to station operation. These include nuclides such as K-'40, Th-232, Ra-226, and Be-7 which are common in the Florida environment.

REPORT/RADENVOP.PTN (3)

0 1991 ANNUAL RADIOLOGICAL ENVIROHMENTAL OPERATING REPORT TURKEY POINT PLANT ' UNITS 3 8 4 B. Inte retation of Results

1. Direct Radiation:

The results for direct radiation monitoring are consistent with past measurements for the specified locations. The exposure rate data shows no indication of any trends attributed to effluents from the plant. The measured exposure rates are consistent with exposure rates that were observed during the preoperational surveillance program. Direct radiation monitoring results are summarized in Table 1.

2. Air Particulates/Radioiodine:

Results of gross beta measurement are consistent with past measurements. No radioiodine was detected. The only identified isotope is cosmic-ray produced Be-7 at levels consistent with past measurements.

3. Waterborne; Surface Water:

The results for radioactivity measurements in surface water samples are consistent with past measurements.

Tritium was reported as present in the surface water samples collected from sites T-81 and T-42. These results are consistent with the known subsurface interchange that occurs between the closed cooling canal and its surrounding waters, and the pressure gradients caused by the flow of aquifer subsurface waters in South Florida. The highest reported tritium is about 1.54 of the reporting value specified by Technical Specifications, Table 3.12-2.

'4. Waterborne; Sediment, and Food Products:

4.1 Sediment

The results are consistent with past measurements; only naturally occurring radionuclides were detected.

REPORT/RADENVOP.PTN (4)

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'ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT - UNITS 3 & 4 4.2 Food Products: The results are consistent with past measurements; only naturally occurring radionuclides were detected.

5. Broad Leaf Vegetation:

The results for radioactivity measurements are consistent with past measurements. Cs-137 was detected, as in the past, in samples collected from all locations. The maximum value, occurring at location T-40 (3 mi. W), is about 194 of the table 3.12-2 reporting level. No other fission products were detected.

C. Conclusions The data obtained through the Turkey Point Plant Radiological Environmental Monitoring Program verifies that the levels of radiation and concentrations of radioactive materials in environmental samples, representing the highest potential exposure pathways to members of the public, are not being increased. The measurements verify that the dose or dose commitment to members of the public, due to operation of Turkey Point Units 3 & 4, during the surveillance year, are well within "as low as reasonably achievable (ALARA)"

criteria established by 10 CFR 50, Appendix I.

REPORT/RADENVOP.PTN (5)

TAlI Pa elf 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 & 4, Docket No(s). 50-250 & 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1991 (County, State)

PATHWAY: DIRECT RA'DIATION SAMPLES COLLECTED TLD UNITS: MICRO R/hr Location with Highest Type and Lower Limit All Indicator Annual Mean Total Number of Locations Name Mean f Control Iacationp of Analyses Detection Mean (f) Distance & Mean (f)

Performed (LLD) Range Direction Range Range Exposure 5.8 (84/84) NW-10 7. 7 (4/4)

Rate, 84 4' 7.9 10 mi., NW 7.5 7.9 Number of Nonroutine Reported Measurements = 0 HP3: 1/RADENVOP . PTN

'. ~ a Pa cff 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL 8UMMARY

.Name of Facility Turke Point Units 3 & 4 , Docket No(s). 50>>250 8 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1991 (County, 8tate)

PATHWAY~ AIRBORNE SAMPLES COLLECTED: RADIOIODINE AND PARTICULATES UNITS: PICO Ci/M Location with Highest Type and Lower Limit All Indicator Annual Mean Total Number of Locations Name Mean f b Oantml Iocationp of Analyses Detection Mean (f) Distance & Mean (f)

Performed (LLD) Range Direction Range Range I, 265 0. 024 <MDA <MDA Gross Beta, 265 0. 0025 0 ~ 010 (259/265) T-57 0. 011 (52/53) 0. 010 (52/53) 0.004 0.030 4 mi., NW 0.004 0.023 0.004 0.026 Composite Gamma Isotopic, 20 7

Be 0.0052 0 100 (20/20) T-58 0. 108 (4/4) 0. 097 (4/4)

0. 068 0. 129 1 mi., NW 0.094 0.129 0 068 0.113 134 Cs 0.00069 <MDA <MDA 137C 0.00066 <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3: 1/RADENVOP . PTN

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Pa cff 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 & 4 , Docket No(s). 50-250 & 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1991 (County, State)

PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER UNITS: PICO Ci/LITER Location with Highest Type and Lower Limit , All Indicator Annual Mean Total Number of Locations Name Mean f Control Zocati~

of Analyses Detection Mean (f) Distance & Mean (f)

Performed (LLD) Range Direction Range Range Tritium, 36 230 188 (4/36) T-81 217 (3/12) <MDA 98 421 6 mi., S 103 421 Gamma Isotopic, 36 K 60 285 (36/36) T-81 306 (12/12) 256 (12/12) 164 391 6 mi., S 215 367 187 335'MDA 54Mn <MDA 59 Fe <MDA <MDA 58 Co <MDA <MDA 60

<MDA <MDA 65Z <MDA <MDA 95 Zr-Nb <MDA <MDA 131I <MDA <MDA C =

<MDA <MDA 137 Cs <MDA <MDA 140 Ba-La <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3:1/RADENVOP.PTN-

I Pa cd 8 ENVIRONMENTAL RAD1OLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Pacility Turke Point Units 3 & 4 , Docket No(s). 50>>250 & 50-251 Location of Pacility Dade Florida , Reporting Period Janua 1 >> December 31 1991

( Count+ ~ State )

PATHWAY: WATERBORNE SAMPLES COLLECTED: SHORELINE SEDIMENT UNITS: -PICO Ci/Kg, DRY Location with Highest e and Lower Limit All Indicator ,Annual Mean f

Total Number of Locations Name Mean Control Locatiogs of Analyses Performed Detection Mean Range (f) xs ance Direction Range Mean (f)

Range (LLD)

Gamma Isotopic, 6 Be 100 382 (1/6) T-42 382 (1/2) <MDA

<1 mi., ENE 40K 140 375 (6/6) T-42 623 (2/2) 233 (2/2) 221 892 <1 mi., ENE 354 892 221 248 52 111 (1/6) T-42 111 (1/2) <MDA

<1 mi., ENE 226 Ra 49 466 (4(6) T-42 656 (2/2) <MDA

<1 mi., ENE 609-703 724 (1/6) T-42 724 (1/6) <MDA

<1 mi., ENE 58 Co <MDA <MDA

~co 12 <MDA <MDA 134 Cs 14 <MDA <MDA 13?

Cs 12 <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3: 1/RADENVOP . PTN

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TAB Pa if 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 & 4 , Docket No(s). 50-250 8 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1991 (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA UNITS: PICO Ci/Kg, WET Location w'ith Highest Type and Lower of Limit All Indicator ,Annual Mean f b Total Number Locations Name Mean CoIItrol Iocatiog of Analyses Detection Mean (f) xs ance & Mean (f)

Performed (LLD) Range Direction Range Range Gamma Isotopic, 4

"'K 130 1674 (4/4) T-81 1778 (2/2) 1569 (2/2) 1517 1832 6 mi., S 1724 1832 1517 1621 226 224 (4/4) T-81 Ra 20 98 508 6mi., S 348 188 -(2/2) 508 99 (2/2) 98 100 228 Ra 94 (1/4) T-81 94 (1/2) <MDA 6 mi., S 54

<MDA <MDA 59F 16 <MDA <MDA 58 Co <MDA <MDA

~Co 19 <MDA <MDA 65 Zn 17 <MDA <MDA 134 Cs <MDA <MDA 137C <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3: 1/RADENVOP . PTN

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Pa c5f 8 EHVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 & 4, Docket No(s). 50-250 & 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1991 (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: FISH UNITS PICO Ci/Kg, WET Location with Highest e and Lower of Limit All Indicator Locations

,Annual Mean f

Total Number Name Mean Control Incationl of Analyses Detection Mean (f) Dz.s ance Direction

& Mean (f)

Performed (LLD) Range Range Range Gamma Isotopic, 4 40K 130 2400 (4/4) T-81 2477 (2/2) 2322 (2/2) 2004 2641 6 mi., S 2343 2611 2004 2641 226 Ra 18 90 (1/4) T-81 90 (1/2) <MDA 6 mi. S

'4Mn <MDA <MDA 59F 16 <MDA <MDA 58co <MDA <MDA 60Co 10 <MDA <MDA 65 Zn 17 <MDA <MDA

'134 Cs <MDA <MDA 137 Cs <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3:1/RADENVOP.PTN

J I Pa of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 3 & 4 , Docket No(s). 50-250 & 50-251 Location of Facility Dade Florida , Reporting Period Janua 1 - December 31 1991 (County, State)

PATHWAY: INGESTION SAMPLES COLLECTED: BROAD LEAF VEGETATION UNITS: PICO Ci/Kg, WET Location with Highest T e and Lower Limit All Indicator ,Annual Mean f b Total. Number of Analyses of Detection Locations Name Mean Control Iacati~

Performed Mean Range (f) Dms Direction-ance &

Range Mean (f)

(LLD) Range Gamma Isotopic, 36 7

Be 1211 (36/36) T-41 1320 (12/12) 1177 (12/12) 435 3548 2 mi., W/NW 504 3548 760 1569 40K 100 3516 (36/36) T-40 4128 (12/12) 1920 (12/12) 1284 5261 3 mi., W 2902 5261 1284 2982 137 Cs 159 (36/36) T-67 275 (12/12) 275 (12/12) 16 583 6 mi., S 33 583 33 583 226 Ra 19 46 (3/36) T-40 52 (2/12) 36 (1/12) 36 - 52 3mi. W 51-52 131

<MDA <MDA 134 Cs <MDA <MDA Number of Nonroutine Reported Measurements = 0 HP3: 1/RADENVOP . PTN

J, 1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTq UNITS 3 8 4 TABLE 1 Page 8 of 8 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Turke Point Units 1 & 2 Docket No. (s) 50-250 and 50-251 Location of Facility Dade Florida (County, State)

Reporting Period Janua 1 December 31 1991 NOTES

a. The LLD is an "a priori" lower limit of detection which establishes the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 954 probability with only 54 probability of falsely concluding that a blank observation represents a real signal.

LLDs in this column are at time of measurement. The MDAs reported in Attachment B for the individual samples have been corrected to the time of sample collection.

b. Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (f).

c. Specific identifying information for each sample location is provided in Attachment A.

d. Results are based upon the average net response of two TLDs.

(Thermoluminescent dosimeters).

MDA refers to minimum detectable activity.

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~ I 1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTi UNITS 3 & 4

'ABLE 1A DEVIATIONS/MISSING DATA A) Pathway: Airborne Location: T-58 (1 mile, NW)

Date: 4/25/91 to 4/30/91 Deviation: Failure to continuously provide air sampling at this location.

Description Mechanical failure of sampling apparatus; of Problem: estimated to have sampled for 40 out of the 166 hours0.00192 days 0.0461 hours 2.744709e-4 weeks 6.3163e-5 months of this period.

Corrective Replacement of sampling apparatus.

Action:

B) Pathway: Airborne Location: T-58 (1 mile, NW)

Date: 4/30/91 to 5/6/91 Deviation: Failure to continuously provide air sampling at this location.

Description Electrical failure, motor burnout of replacement of Problem: sampling apparatus. Estimated to have run for 117 hours0.00135 days 0.0325 hours 1.934524e-4 weeks 4.45185e-5 months out of the 143 hours0.00166 days 0.0397 hours 2.364418e-4 weeks 5.44115e-5 months of this period.

Corrective Replacement of sampling apparatus.

Action:

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1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTg UNITS 3 & 4 TABLE 1B ANALYSES MITE LLDS MOVE TABLE 4

'2-1 DETECTION CAPABILITIES 1/1/91 12/31/91 The values specified in Table 4.12-1, Detection Capabilities, were achieved for all samples.

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1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTi UNITS 3 & 4 TABLE 2 LAND USE CENSUS Distance to Nearest a b 5/9 1 Milk (c) 5/9 1 5/9 1 Sector Animal Residence Garden (d)

N L (e) 2 1/350 (9) L NNE 0 (f) 0 NE 0 ENE 0 E 0 ESE 0 0 0 SE 0 SSE 0 L L (e)

SSW L L L SW L L WSW L L L L L L L L L 3.8/305 NNW L L (e) 4.0/328 HP3:1/RADENVOP.PTN

t 1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTg UNITS 3 8 4 TABLE 2 LAND USE CENSUS NOTES a ~ All categories surveyed out to 5 miles radius from the Turkey Point Plant.

b. The following format is used to denote the location:

distance (miles)/bearing (degrees)

For example, a residence located in the north sector at a distance of 2.1 miles bearing 350 degrees is recorded as 2.1/350.

~ '. Potential milk animal locations.

Gardens with an estimated growing area of 500 square feet or more.

e. L denotes that the sector area is predominantly a land area unoccupied by the category type.

0 denotes that the sector area is predominantly an ocean area.

gi Non-residential occupied buildings in these sectors include the following:

C'ector Distance N 1.8/349 24-hour Security Staffing Building

4. 9/171 Small building/boat dock

. not considered a residence NNW 4. 5/327 2 mobile homes used for field offices NNW 1. 8/345 Security booth at park entrance HP3:1/RADENVOP.PTN

1991

,ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTg UNITS 3 6 4 ATTACHMENT A KEY TO SAMPLE LOCATIONS HP3:1/RADENVOP.PTN

1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

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1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTi UNITS 3 & 4 ATTACHMENT A Page 1 of 4 PATHWAY: DIRECT RADIATION SAMPLES COLLECTED: TLD SAMPLE COLLECTION FREQUENCY: QUARTERLY Approximate Location Direction Distance Name Descri tion N-1 N 1 Convoy Point N-5 N 6 North of Moody Drive N-10 N 12 Old Cutler Rd. at S.W. 87 Avenue NNW-1 NNW (1 Turkey Point Entrance Rd.

NNW-10 NNW 9 Burr Rd. at Hainlin Mill Dr.

NW/WNW-1 WNW 1 Turkey Point Entrance Rd.

NW-5 NNW 4 Dolan's Farm on Kings Hwy.

-10 NW 10 Intersec Farm Lite & Coconut Palm WNW-5 W 5 Palm Dr. at Tallahassee Rd.

-10 WNW 9 Homestead near Vehicle Inspect. Station W-1 W 1 On-Site near Cooling Tower W-10 W 10 Florida City near Fire Tower WSW-10 WSW 12 Old Hawk Missile Site, South of Florida City SW/SSW-1 SSW 1 On-Site near Land Utilization Offices SW-10 SW 10 U.S. 1 South of Florida City SSW/SW-5 SSW 5 On-Site, Southeast Corner of Cooling Canals SSW-10 SSW 10 At Card Sound Bridge S-5 S 5 On-Site, South End of Cooling Canals S-10 S 10 Card Sound Road at Steamboat Creek SSE/S-1 SSE 1 Turtle Point SSE-10 SSE 8 Ocean Reef 0

HP3: 1/RADENVOP . PTN

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1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTi UNITS 3 & 4 ATTACHMENT A Page 2 of 4 PATHWAY: AIRBORNE SAMPLES COLLECTED: RADIOIODINE AND PARTICULATES SAMPLE COLLECTION FREQUENCY: WEEKLY Approximate Location Direction Distance Name Sector miles Descri tion T-51 NNW 2 Homestead Bayfront Park T-57 NW 4 Tree Nursery on 316th Street T-58 NW 1 Turkey Point, Entrance Road T-72 WSW (1 Turkey Point Boy Scout Camp Control:

NNE 22 Natoma Substation HP3:1/RADENVOP.PTN

n 1991 ANNUAL RAD1OLOGICAL ENVIRONMENTAL OPERATING REPORT 0 TURKEY POINT PLANTg UNITS 3 8 4 ATTACHMENT A Page 3 of 4 PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER (OCEAN)

SAMPLE COLLECTION FREQUENCY: MONTHLY Approximate Location Direction Distance Name Sector iles Descri tion T-42 ENE <1 Biscayne Bay at Turkey Point T-81 S 6 Card Sound, near Mouth of Old Discharge Canal Control:

-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park SAMPLES COLLECTED: SHORELINE SEDIMENT SAMPLE COLLECTION FREQUENCY: SEMI-ANNUALLY Approximate Location Direction Distance Name Descri tion T-42 ENE <1 Biscayne Bay at Turkey Point A1A T-81 S 6 Card Sound, near Mouth of Old Discharge Canal Control:

T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park HP3:1/RADENVOP.PTN

1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTi UNITS 3 & 4 ATTACHMENT A Page 4 of 4 PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA AND FISH SAMPLE COLLECTION FREQUENCY: SEMI-ANNUALLY Approximate Location Direction Distance Name Sector miles Descri tion T-81 Card Sound Vicinity of Turkey Point Facility Control:

N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Park, North to Matheson Hammock Park SAMPLES COLLECTED: BROAD LEAF VEGETATION SAMPLE COLLECTION FREQUENCY: MONTHLY Approximate Location Direction Distance Name Sector miles Descri tion T-40 South of Palm Dr. on S.W. 117th Street Extension T-41 Palm Dr., West of Old Missile Site near Plant Site Boundary Control:

T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Park, North to Matheson Hammock Park HP3:1/RADENVOP.PTN

1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANTq UNITS 3 5 4 ATTACHMENT B RADIOLOGICAL SURVEILLANCE OF FLORIDA POSER AND LIGHT COMPANYIS TURKEY POINT SITE 1991 First Quarter, 1991 Second Quarter, 1991 Third Quarter, 1991 Fourth Quarter, 1991 HP3:1/RADENVOP.PTN

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE I

First Quarter, 1991 Office of Radiation Control Florida Department of Health and Rehabilitative Services

~ \

TURKEY POINT SITE Technical Specifications Sampling First Quarter, 1991 Collection Locations Number of Sam le T e Fre uenc

1. Direct Radiation Quarterly 42

2. Airborne 2.a Air Iodines Weekly 65 2.b Air Particulates Weekly 69*

3. Waterborne 3.a Surface Water Monthly 3.b Shoreline Sediment Semiannually t 4. Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea 4.a.2 Fish 4.b Food Products 4.b.l Broadleaf Vegetation Semiannually Semiannually Monthly Total: 201

Includes NRC split samples.

NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.

Measurement results that are not significantly above background are reported as "non-detectable" (ND) or as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 954 confidence) for the true activity in the sample.

D ECT RADIA IO '

TLDs 'cro-R hou Each result is the average net response of two dosimeters.

Sample Deployment 12-18-90 Site Collection 03-13-91 N-1 6.7 + 0.4 N-5 6.1 + 0.3 N-10 5.8 + 0.3 NNW-1 6.5 + 0.3 NNW-10 6.4 + 0.3 NW/WNW-1 5.3 + 0.3 NW-5 5.7 + 0.3 NW-10 7.9 + 0.4 W/WNW-5 4.9 + 0.3 WNW-10 6.5 + 0.3 W-1 5.2 + 0.3 W-10 6.5 + 0.3 WSW-10 4.9 + 0.3 SW/SSW-1 4 ' + 0.2 SW-10 4.9 + 0.3 SSW/SW-5 5.8 + 0.3 SSW-10 6.0 + 0.3 S-5 5.5 + 0.3 S-10 6.1 + 0.3 SSE/S-1 5.9 + 0.3 SSE-10 5.1 + 0.3 2.a IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72 01-02-91 <0.03 <0.03 <0.03 <0.03 <0.03 01-08-91 <0.03 <0.02 <0.02 <0.02 <0.02 01-15-91 <0.03 <0.03 <0.03 <0.03 <0.03 01-23-91 <0.02 <0.02 <0.02 <0.02 <0.02 01-29-91 <0.03 <0.03 <0.03 <0.03 <0.03 02-05-91 <0.02 <0.02 <0.02 <0.02 <0.02 02-12-91 <0.03 <0.03 <0.03 <0.03 <0.03 02-18-91 <0.03 <0.04 <0.03 <0.03 <0.03 02-27-91 <0. <0.02 <0'. 02 <0.02 <0.02 02'0.

03-04-91 04 <0. 04 <0.04 <0.04 <0.04 03-12-91 03-20-91

<0. 03

<0.02

<0.03

<0.02

<0.03

<0.02

<0 '2

<0.03 0 03-26-91 <0.03 <0.03 <0.03 <0.03 <0.03

~ ~

0

2.b AIR PARTICULATES GROSS BETA Ci m3 Collection Sam le Site Date T51 T57 T58 T64 T72 01-02-91 0.008 + 0.002 0.004 + 0. 001 0.007 + 0. 002 0.005 + 0. 001 0.007 + 0.002 01-08-91 <0 .005 0.004 + 0.002 <0 .005 <0 .005 <0. 005 01-15-91 0.010 + 0.002 0.007 + 0.002 0.007 + 0.002 0.008 + 0.002 0.010 + 0.002 01-23-91 0:015 + 0.002 0.015 + 0.002 0.010 + 0.002 0.014 + 0.002 0.010 + 0.002 01-29-91 0.010 + 0.002 0.014 + 0.002 0.012 + 0.002 0.012 + 0.002 0.019 + 0.002 02-05-91 0. 013 + 0 . 002 0.008 + 0.002 *0.006 + 0.002 0.007 + 0.002 0.008 + 0.002 02-12-91 0. 013 + 0 .002 0.016 + 0.002 *0.015 + 0.002 0.013 + 0.002 0.013 + 0.002 02-18-91 0.016 + 0 .002 0.015 + 0.002 *0.016 + 0.002 0.016 + 0.002 0.015 + 0.002 02-27-91 0.007 + p .001 0.008 + 0.001 *0.007 + 0.001 0.003 + 0.001 0.005 + 0.001 03-04-91 0.009 + p .002 0. 012 + 0. 002 0.017 + 0.002 0-010 + 0.002 0.012 + 0.002 03-12-91 0.016 + p .002 0. 015 + 0. 002 0.014 + 0.002 0.016 + 0.002 0.016 + 0.002 03-20-91 0.015 + 0 .002 0. 016 + 0. 002 0.015 + 0.002 0.011 + 0.002 0.012 + 0.002 03-26-91 0.019 + p .002 0.015 + 0.002 0.019 + 0.002 0.013 + 0.002 0.018 + 0.002 Means: 0.013 + 0.001 0.011 + 0.001 0.012 + 0.001 0.011 + 0.001 0.012 + 0.001

NRC split samples.

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 First Quarter, 1991 Sample Site Be-7 K-40 Cs-134 Cs-137 T51 0.1199 + 0.0112 <0.0205 <0.0011 <0.0010 T57 0.0929 + 0.0105 <0.0207 <0.0010 <0.0011 T58 0.1286 + 0.0108 <0.0189 <0.0010 <0.0010 T64 0.1116 + 0.0109 <0.0155 <0.0010 <0.0011 T72 0.1253 + 0.0122 <0.0200 <0.0008 <0.0010

~ ~ k 0

3.a SURFACE WATER Ci l Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)

T42 01-28-91 <145 364 + 39 <4 <8 <4 <4 <8 <6 <5 <4 <3 <6 02-18-91 <163 391 + 44 <2 <9 <4 <4 <8 <7 <7 <4 <5 <7 03-18-91 -

<138 274 + 40 <4 '8 <4 <5 <11 <8 <6 <4 <4 <5 T67 01-28-91 <145 262 + 35 <4 <9 <4 <5 <9 <5 <6 <4 <5 <6 02-15-91 <163 274 + 41 <4 <6 <4 <5 <10 <7 <9 <5 <4 <6 03-18-91 <138 279 + 36 <4 <8 <4 <4 <10 <8 <6 <3 <5 <5 T81 01-24-91 <145 321 + 39 <4 <7 <3 <5 <8 <8 <6 <5 <4 <8 02-15-91 <163 367 + 38 <4 <8 <4 <5 <6 <7 <8 <5 <5 <8 03-18-91 103 + 45 321 + 35 <4 <9 <4 <5 <9 <6 <7 <5 <4 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

' ~ ~

0

3.b SEDIMENT Ci k dr wei ht Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Others T42 01-17-91 <127 354 + 64 <12 <11 <13 <12 Ra-226: 609 + *15 U-238: 724 + 98 01-16-91 <49 221 + 41 <6 <4 <8 ND T81 01-14-91 <72 227 + 50 <9 <6 <9 <8 Ra-226: 212 + 8 4.a.l CRUSTACEA T67: Mixed Crab S ecies T81: Blue Crab Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 02-12-91 1517 + 102 <11 <24 <8 <12 <22 <10 <10 100 + 8 ND T81 01-25-91 1724 + 126 <10 <26 <11 <15 <24 <15 <14 508 + 14 94 + 21 4.a.2 FISH Mixed S ecies Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-55 Co-60 Zn-65 Cs-134 Cs-137 T67 02-12-91 2004 + 122 <11 <22 <10 <12 <27 <9 T81 02-25-91 2611 + 136 <11 <49 <18 <14 <26 <11 <13 ND Non-detectable.

4.b.l BROADLEAF VEGETATIO Bra i an er C'et we'ample Collection Site Date Be-7 K-4 0 I-131 Cs-134 Cs-137 T40 01-28-91 996 + 69 5261 + 197 <12 <15 71+ 7 02-18-91 963 + 60 4907 + 167 <17 38 + 7 03-18-91 1256 + 69 4093 + 158 <16 <11 31+ 6 T41 01-28-91 989 + 67 3013 + 141 <12 <10 107 + 9 02-18-91 1018 + 78 3689 + 171 <17 <14 46+7 03-18-91 975 + 76 3939 + 161 <18 <11 105 + 9 T67 01-28-91 899 + 74 2982 + 150 <15 <10 510 + 16 02-15-91 1232 + 72 2077 + 113 <23 <10 171 + 10 03-18-91 1412 + 83 1456 + 105 <18 <12 115 + 8

p ~

~

RADIOLOGICAL SURVEILLANCE OF FLORIDA, POWER AND LIGHT COMPANY'S TURKEY POINT SITE Second Quarter, 1991 Office of Radiation Control Florida Department of Health and Rehabilitative Services

1

~

I 4

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TURKEY POINT SITE 0 Technical Specifications Sampling Second Quarter, 1991 Collection Locations Number of

1. Direct Radiation Quarterly 21 42

2. Airborne 2.a Air Iodines Weekly 65 2.b Air Particulates Weekly 69*

3. Waterborne 3.a Surface Water Monthly 3.b Shoreline Sediment Semiannually 4 ~ Ingestion 4.a Fish and Invertebrates 4.a.l Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.l Broadleaf Monthly 10*

Vegetation Total: 195

Includes NRC split samples.

NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.

Measurement results that are not significantly above background are reported as "non-detectable" (ND) or as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 954 confidence) for the true"activity in the sample.

0 I t

0

DIRECT RADIATION TLDs micro-R hour Each result is the average net response of two dosimeters.

Sample Deployment 03-13-91 Site Collectio 06-18-91 N-1 6.6 + 0.3 N-5 5.8 + 0.3 N-10 5.6 + 0.3 NNW-1 (A) 5.9 + 0.3 NNW-10 6.'3 + 0.3 NW/WNW-1 5.1 + 0.3 NW-5 5.5 0.3 NW-10 7.7 + 0' W/WNW-5 4.9 + 0.3 WNW-10 6.5 + 0.3 W-1 ( B)

W-10 6.6 0.3 WSW-10 4.9 + 0.3 SW/SSW-1 4.7 + 0.2 SW-10 4.8 + 0.3 SSW/SW-5 5.7 + 0.3 SSW-10 '5.7 + 0.3 S-5 5. 0" + 0.3 S-10 5.6 + 0.3 SSE/S-1 5.5 + 0.3 SSE-10 4.9 + 0 '

(A) -'he dosimeters at site NNW-1 were found lying on the ground.

They had apparently fallen -from their mounting, which had come loose.

(B) The dosimeters at site W-1 and the chain link fence on which they were mounted were missing when collection was attempted on 06-19-91. The fence had been removed on 03-25-91. The dosimeters were found lying on a concrete slab near the de-ployment site during a search of the area on 06-20-91. The result from these dosimeters was 5.9 + 0.3 micro-R per hour.

This is slightly higher than the normal readings at this site, which have a long-term average of 5.2 micro-R per hour. This difference is probably due to the dosimeters having been moved when the fence was taken down.

2.a IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date ~T5 ~T5 ~58 T64 04-02-91 <0. 02 <0. 02 <0.02 <0 '2 <0.02 04-09-91 <0.02 <0.02 <0.02 <0 '2 <0 '2 04-16-91 <0.03 <0.03 <0.03 <0.03 <0.03 04-23-91 <0 '2 <0.02 <0 '2 <0 '2 <0 '2 04-30-91 <0.03 <0.03 <0.06(A) <0.03 <0.03 05-06-91 <0.04 <0.04 <0.04(B) <0.04 <0.04 05-16-91 <0.01 <0.01 <0.01 <0.01 <0.01 05-22-91 <0.02 <0.02 <0.02 <0.02 <0.02 05-29-91 <0.03 <0.03 <0.03 <0.03 <0.03 06-04-91 <0.02 <0 '2 <0.02 <0 '2 <0 '2 06-12-91 <0.03 <0.03 <0.03 <0.03 <0.03 06-19-91 <0.02 <0 '2 <0.02 <0 '2 <0 '2 06-25-91 <0.03 <0.03 <0.03 <0.03 <0.03 (A) - This sample had a low collected volume due to mechanical failure of the air pump. The equipment is estimated to have run for 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months out of the 166 total hours for this sampling interval.

'B)

This sample had a low collected volume due to electrical failure of the replacement air pump. The equipment is .estimated to have run for 117 hours0.00135 days 0.0325 hours 1.934524e-4 weeks 4.45185e-5 months out of the 143 total hours for this sampling interval.

2. AIR PARTICULATES SS BETA Ci m3 Collection Sam le Site Date T51 T57 T58 T64 T72 04-02-91 0.014 + 0.002 0. 017 + 0. 002 0. 012 + 0.002 0.011 + 0.002 0. 014 + 0.002 04-09-91 0.011 + 0.002 0.011 + 0. 002 0.009 + 0.002 0.010 + 0.002 0.010 + 0.002 04-16-91 0.012 + 0.002 0.017 + 0. 002 0.014 + 0.002 0.013 + 0.002 0.015 + 0.002

,04-23-91 0.016 + 0.002 0.013 + 0. 002 0.014 + 0.002 0.011 + 0.002 0.015 + 0.002 04-30-91 0.010 + 0.002 0.012 + 0. 002 (A0.013 + 0.005 0.008 + 0.002 0.013 + 0.002 05-06-91 0.018 + 0.002 0.018 + 0. 002 (B*0.022 + 0.003 0.014 + 0.002 0.017 + 0.002 05-16-91 0.014 + 0.002 0.017 + 0. 002 *0.015 + 0.002 0.012 + 0.002 0.013 + 0.002 05-22-91 0.005 + 0.002 0.008 + 0. 002 *0.005 + 0.002 0.007 + 0.002 0.007 + 0.002 05-29-91 0.007 + 0.002 0 011 + 0. 002 *0.012 + 0.002 0.007 + 0.002 0.008 + 0.002 06-04-91 0.011 + 0.002 0.015 + 0. 002 0.010 + 0.002 0.012 + 0.002 0.012 + 0.002 06-12-91 0.007 + 0.001 0.006 + 0. 001 0.004 + 0.001 0.008 + 0.001 0.008 + 0.001 06-19-91 0.008 + 0.002 0.012 + 0.002 0.007 + 0.001 0.009 + 0.002 0.011 + 0.002 06-25-91 0.006 + 0.002 0.008 + 0.002 0.008 + 0.002 0.008 + 0.002 0.012 + 0.002 Means: 0.011 + 0.001 0.013 + 0.001 0.011 + 0-001 0.010 + 0.001 0.012 + 0.001

NRC split samples.

(A) This sample had a low collected volume due to mechanical failure of the air pump. The equipment is estimated to have run for 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months out of the 166 total hours for this sampling interval.

(B) This sample had a low collected volume due to electrical failure of the replacement air pump. The equipment is estimated to have run for 117 hours0.00135 days 0.0325 hours 1.934524e-4 weeks 4.45185e-5 months out of the 143 total hours for this sampling interval.

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 Second Quarter, 1991 Sample r Site Be-7 K-40 Cs-134 Cs-137 T51 0.0986 + 0.0104 <0.0209 <0.0013 <0.0009 T57 0.1014 + 0.0107 <0.0193 <0.0012 <0.0008 T58 0.1108 + 0.0114 <0.0162 <0.0010 <0.0009 T64 0.0939 + 0.0107 <0.0229 <0.0009 <0.0011 T72 0.1170 + 0.0114 <0.0213 <0.0007 <0.0009

~ ~

3.a SURFACE WATER Ci 1 Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 I (B)

T42 04-12-91 <145 307 + 40 <4 <8 <5 <5 <9 <5 <6 <5 <4 <7 05-22-91 <126 330 + 35 <3 <8 <3 <5 <9 <7 <4 <4 <4 <8 06-19-91 <128 317 + 37 <4 '<7 <4 <3 <10 <5 <5 <4 <4 <8 T67 04-12-91 <145 335 + 38 <4 <7 <4 <4 . <8 <8 <7 <4 <4 <6 05-22-91 <126 333 + 35 <4 <10 <3 . <4 <8 <6 <4 <4 <5 <8 06-14-91 <128 187 + 39 <4 <9 <4 <4 <9 <6 <8 <4 <4 <5 T81 04-12-91 <145 354 + 41 <4 <10 <4 <5 <8 <5 <6 <5 <5 <6 05-22-91 <126 309 + 36 <3 <5 -<4 <5 <11 <6 <6 <4 <3 <5 06-19-91 <128 275 + 35 <3 <9 <4 <5 <9 <5 <4 <4 <4 <7 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

L I ~

0

4.b OAD VGATN-B wet e' Sample Collection Site Date Be-7 K-4 0 I-131 Cs-134 Cs-137 T40 04-12-91 435 + 54 5005 + 178 <21 <12 <14

05-22-91 719 + 43 3859 + 131 <7 <8 28+4 06-19-91 1388 + 74 4269 + 157 <13 <9 348 + 12 T4 1 04-12-91 504 + 67 4706 + 177 <23 <12 152 + ll 05-22-91 766 + 59 3246 + 147 <10 <10 26+ 6 06-19-91 949 + 62 3352 + 152 <12 <10 93+8 T67 04-12-91 1354 + 86 1583 + 114 <27 <9 100 + 9 05-22-91 760 + 73 2826 + 153 <10 <13 33+7 06-19-91 1246 + 71 1473 + 104 <15 <7 220 + 12

NRC split sample.

I r

1'l

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Third Quarter, 1991 Office of Radiation Control Florida Department of Health and Rehabilitative Services

P TURKEY POINT SITE Technical Specifications Sampling Third Quarter, 1991 Collection Locations Number of Sam le T e Fre uenc

1. Direct Radiation Quarterly 21 42

2. Airborne 2.a Air Iodines Weekly 65 2.b Air Particulates Weekly 69*

3. Waterborne 3.a Surface Water Monthly 3.b Shoreline Sediment Semiannually

4. Ingestion 4.a Fish and Invertebrates 4.a.1 Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.l Broadleaf Monthly Vegetation Total: 201

Includes NRC split samples.

NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.

Measurement results that are not significantly above background are reported as "non-detectable" (ND) or as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 954 confidence) for the true activity in the sample.

DIRECT RADIATION TLDs micro-R hour Each result is the average net response of two dosimeters.

Sample Deployment 06-18-91 Site Collection 09-17-91 N-1 6.4 + 0.3 N-5 6.0 + 0.3 N-10 5.5 + 0.3 NNW-1 5.7 + 0.3 NNW-10 6.3 + 0.3 NW/WNW-1 4.9 + 0.3 NW-5 5.6 + 0.3 NW-10 7.7 + 0.4 W/WNW-5 4.8 + 0.3 WNW-10 6.6 + 0.3 W-1 (A) 6.2 + 0.3 W-10 6.6 + 0.3 WSW-10 SW/SSW-1 4.9 4.8 i+ 0.3 0.3 SW-10 4.7 + 0.2 SSW/SW-5 5.7 + 0.3 SSW-10 5.6 + 0.3 S-5 5.3 + 0.3 S-10 5.9 + 0.3 SSE/S-1 5.7 + 0.3 SSE-10 4.9 + 0.3 (A) The dosimeters at site W-1 were mounted on the side of a small concrete block utility building on 06-19-91. The chain link fence previously used to hold these dosimeters had been removed, and this was the only other secure structure in the area. The measurement result obtained in the new configura-tion is significantly higher than the previous long-term average of 5.2 micro-R per hour at this site. This is believed to be due to the presence of naturally-occurring radioactivity in the materials of which this utility building is constructed.

0 2.a D NE- C Sam le Site Collection Date T51 T57 T58 T64 T72 07-02-91 <0. 03 <0. 03 <0.,03 <0.03 <0.03 07-09-91 <0.02 <0 '2 <0.02 <0.03 <0 '2 07-16-91 <0 '2 <0.02 <0.02 <0.02 <0.02 07-23-91 <0.02 <0.02 <0.02 <0 '2 <0.02 07-30-91 <0 '2 <0.02 <0.02 <0.02 <0.02 08-06-91 <0.03 <0.03 <0.03 <0.03 <0.03 08-13-91 <0.03 <0.03 <0.03 <0.03 <0. 03 08-20-91 <0.02 <0.02 <0.02 <0.02 <0. 02 08-28-91 <0.02 <0.02 <0.02 <0.02 <0. 02 09-03-91 <0.03 <0.03 <0.03 <0. 03 <0. 03 09-11-91 <0.03 <0.03 <0.03 <0.03 <0. 03 09-17-91 <0.03 <0.03 <0.03 <0.03 <0.03 09-25-91 <0.03 <0.03 <0.03 <0.03 <0.03

l 2.b

~-

AIR PARTICULATES GROSS BETA Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72 07-02-91 0.007 + p 001 0.008 + 0.002 0.008 + 0. 002 0.008 + 0. 001 0.009 + 0. 002 07-09-91 0.012 + p ~ 002 0.015 + 0.002 0.010 + 0. 002 0.012 + 0. 002 0.010 + 0 ~ 002 07-16-91 0.008 + Q 002 0.005 + 0.001 0.009 + 0. 002 0.012 + 0.002 0.010 + 0. 002 07-23-91 0.009 + p 002 0.009 + 0.002 0.007 + 0. 002 0.008 + 0.002 0.010 + 0. 002 07-30-91 0.007 + p ~ 002 0.005 + 0.001 0.008 + 0. 002 0.004 + 0.001 0.008 + 0. 002 08-06-91 ,0. 006 + p ~ 001 0.006 + 0.001 *0.007 + 0. 001 0.005 + 0.001 0.004 + 0.001 08-13-91 0.009 + p ~ 002 0.007 + 0.002 *0.007 + 0. 002 0.004 + 0.001 0.007 + 0.002 08-20-91 0.013 + p 002 0.018 + 0.002 *0.015 + 0. 002 0.013 + 0.002 0.019 + 0 ~ 002 08-28-91 0.009 + p 002 0.008 + 0.001 *0.008 + 0.001 0.009 + 0.001 0.008 + 0.002 09-03-91 0.007 + p 002 0.007 + 0.002 0.006 + 0.002 0.006 + 0.002 0.006 + 0.002 09-11-91 0.005 + Q ~ 001 0.007 + 0.002 0.006 + 0.001 0.009 + 0.002 0.007 + 0.001 09-17-91 0.008 + p 002 0.010 + 0.002 0.009 + 0.002 0.009 + 0.002 0.009 + 0.002 09-25-91 0.014 + p ~ 002 0.015 +,0. 002 0.012 + 0.002 0.014 + 0.002 0.013 + 0 '02 Means: 0.009 + 0.001 0.009 + 0.001 0.009 + 0.001 0.009 + 0.001 0.009 + 0.001 NRC split samples.

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m Third Quarter, 1991 Sample Site Be-7 K-40 Cs-134 Cs-137 T51 0.0870 + 0.0093 <0. 0199 <0. 0012 <0.0011 T57 0.0750 + 0.0087 <0. 0171 <0.0012 <0.0009 T58 0.0936 + 0.0101 <0.0155 <0.0010 <0.0008 T64 0.0682 + 0.0084 <0.0174 <0.0013 <0.0010 T72 0.0760 + 0.0094 <0.0212 <0.0014 <0.0009

~ p 1 0

3.a SURFACE WATER Ci l Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (B)

T42 07-19-91 <132 297 + 32 <4 <8 <4 <4 <8 <9 <6 <4 <6 08-20-91 <136 366 + 36 <4 <9 <4 <4 <8 <6 <4 <4 <4 <5 09-18-91 98 + 44 260 + 40 <3 <7 <4 <4 <10 <7 <5 <4 T67 07-19-91 <132 202 + 33 <4 <10 <4 <4 <9 <7 <7 <5 <4 <5 08-19-91 <136 238 + 41 <3 <7 <4 <4 <10 <6 <4 <5 <3 <2 09-17-91 <137 298 + 35 <4 <8 <3 <4 <10 <7 <6 <4 <5 <5 T81 07-17-91 421 + 51 324 + 39 <4 <10 <4 <4 <8 <6 <6 <5 <7 08-19-91 128 + 45 326 + 39 <3 <10 <5 <5 <8 <7 <4 <5 <4 <4 09-13-91 <137 324 + 37 <4 <10 <4 <5 <10 <6 <9 <4 <5 <7 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

3.b SEDIMENT Ci k dr wei ht 0

Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Ra-226 Th-232 T42 07-19-91 382 + 58 892 + 107 <13 .<15 <18 <15 . 703 + 17 111 + 22 T67 07-19-91 <59 245 + 39 <7 <6 <5 <7 ND ND T81 07-17-91 <79 312 + 44 <8 <9 <8 <7 342 + 10 ND 4.a.1 CRUSTACEA Blue Crab Ci k wet wei ht Sample Collection Site Date K-4 0 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 09-11-91 1621 + 114 <10 <25 <8 <11 <22 <12 <10 , 98 + 7 ND T81 09-28-91 1832 + 156 <14 <28 <12 <18 <29 <12 <12 188 + 12 ND 4.a.2 FISH T67: Mixed S ecies T81: Catfish Ci k wet wei ht Sample Collection Site Date K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 09-13-91 2641 + 140 <9 <28 <10 <14 <23 <12 <12 ND ND T81 09-18-91 2343 + 157 <13 <36 <10 <13 <28 <9 <15 90 + 10 ND ND Non-detectable.

0 RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE Fourth Quarter, 1991 Office of Radiation Control Florida Department of Health and Rehabilitative Services

TURKEY POINT SITE Technical Specifications Sampling Fourth Quarter, 1991 Collection Locations Number of Sam le T e Fre uenc

1. Direct Radiation Quarterly 21 42

2. Airborne 2.a Air Iodines Weekly 70 2.b Air Particulates Weekly 74*

3. Waterborne 3.a Surface Water Monthly 3.b Shoreline Sediment Semiannually

4. Ingestion 4.a Fish and Invertebrates 4.a.1 Crustacea Semiannually 4.a.2 Fish Semiannually 4.b Food Products 4.b.l Broadleaf Monthly 10*

Vegetation Total: 205

Includes NRC split samples.

NOTE: Measurement results having magnitudes that are significantly above the"background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.

Measurement results that are not significantly above background are reported as "non-detectable" (ND) or as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 95~ confidence) for the true activity in the sample.

0 DIRECT RADIATION TLDs micro-R hour Each result is the average net response of two dosimeters.

Sample Deployment 09-17-91 Site Collection 12-03-91 N-1 6.7 + 0.4 N-5 5.7 + 0.3 N-10,(A) 5. 7 + 0. 3 NNW-1 5.5 + 0.3 NNW-10 6.4 + 0.3 NW/WNW-1 5.2 + 0.3 NW-5 5.4 + 0.3 NW-10 7.5 + 0.4 W/WNW-5 5.1 + 0.3 WNW-10 6.8 + 0.4 6.4 + 0.3 W-10 6.9 + 0.4 WSW-10 5.1 + 0.3 SW/SSW-1 4.7 + 0.2 SW-10 4.9 + 0.3 SSW/SW-5 5.9 + 0.3 SSW-10 6.1 + 0.3 S-5 5.0 + 0.3 S-10 5.5 + 0.3 SSE/S-1 5.5 + 0.3 SSE-10 4.8 + 0.3 (A) The result for site N-10 is based on a single dosimeter due to an anomalous response from the other.

I

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2.a IODINE-131 IN WEEKLY AIR FILTERS Ci m3 Sam le Site Collection Date T51 T57 T58 T64 T72 10-01-91 <0. 03 <0. 03 <0.03 <0.03 <0. 03 10-09-91 <0. 02 <0.02 <0.02 <0.02 <0. 02 10-15-91 <0.02 <0.02 <0.02 <0.02 <0. 02.

10-22-91 <0.03 <0.03 <0.03 <0. 03, <0. 03 10-28-91 <0.04 <0.04 <0.04 <0.04 <0. 04 1'1-05-91 <0.03 <0.03 <0.03 <0.03 <0.03 11-13-91 <0.03 <0.03 <0.03 <0.03 <0.03 11-20-91 <0.03 <0.03 <0.02 <0.02 <0.02 11-26-91 <0.04 ,<0.04 <0.04 <0.04 <0.04 12-03-91 <0.04 <0.04 <0.04 <0.05 <0.04 12-10-91" <0.03 <0.03 <0.03 <0.02 <0.03 12-17-91 <0.03 <0.03 <0.03 <0.03 <0.03 12-23-91 <0.02 <0.02 <0.02 <0.02 <0.02 12-30-91 <0.02 <0.02 <0.02 <0.02 <0.02

~ ~

2.b AIR PARTICULATES GROSS BETA Ci m3 Collection Sam le Site Date T51 T57 T58 T64 T72 10-01-91 0.010 + 0.002 0.016 + 0.002 0.014 + 0.002 0.019 + 0.002 0. 017 + 0.002 10-09-91 <0.004 0.007 + 0.002 0.006 + 0.002 0.005 + 0.002 0.005 + 0.001 10-15-91 0.013 + 0.002 0.013 + 0.002 0.015 + 0.002 0.012 + 0.002 0.015 + 0.002 10-22-91 0.009 + 0.002 0.012 + 0.002 0.007 + 0.002 0.008 + 0.002 0.011 + 0.002 10-28-91 0.006 + 0.002 0.007 + 0.002 0.005 + 0.002 0.005 + 0.002 0.008 + 0.002 11-05-91 0.015 + 0.002 0. 017 + 0. 002 *0. 014 + 0. 002 0.013 + 0.002 0.018 + 0.002 11-13-91 0.022 + 0.002 0.023 + 0.002 *0. 030 + 0. 003 0.026 + 0.002 0.021 + 0.002 11-20-91 0.016 + 0.002 0.016 + 0.002 *0.016 + 0.002 0.016 + 0.002 0.017 + 0.002 11-26-91 0.005 + 0.002 0.011 + 0.002 *0.010 + 0.002 0.010 + 0.002 0.009 + 0.002 12-03-91 0.005 + 0.001 <0 . 004 0.004 + 0.001 0.006 + 0.002 0. 0.05 + 0.001 12-10-91 0.009 + 0.002 0. 007 + 0.002 0.009 + 0.002 0.008 + 0.001 0. 012 + 0.002 12-17-91 0.010 + 0.002 0.009 + 0.002 0.007 + 0.002 0.011 + 0.002 0. 011 + 0.002 12-23-91 0.015 + 0.002 0.013 + 0.002 0.007 + 0.002 0.017 + 0.002 0. 015 + 0.002 12-30-91 0.008 + 0.002 0.009 + 0.002 0.007 + 0.002 0.011 + 0.002 0. 010 + 0.002 Means: 0.011 + 0.001 0.012 + 0.001 0.011 + 0.001 0.012 + 0.001 0.012 + 0.001 NRC split samples.

2.b AIR PARTICULATES GAMMA SCANS OF UARTERLY COMPOSITES Ci m3 Fourth Quarter, 1991 Sample Site Be-7 K-40 Cs-134 Cs-137 T51 0.0947 + 0.0117 <0.0156 <0.0008 <0.0008 T57 0.0949 + 0.0094 <0.0144 <0.0007 <0.0008 T58 0.1006 + 0.0093 <0.0172 <0.0008 <0.0005 T64 0.1126 + 0.0111 <0.0162 <0.0008 <0.0006 T72 0.0988 + 0.0104 <0.0198 <0.0007 <0.0011

0 0

0

3.a SURFACE MATER Ci l Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)

T42 10-14-91 <136 224 + 33 <3 <8 <4 <4 <8 <6 <4 <4 <4 11-15-91 <133 210 + 32 <4 <10 <5 <4 <7 <8 <6 <4 <3 <6 12-13-91 <132 164 + 28 <4 <9 <4 -

<4 <8 <7 <9 <4 <4 <7 T67 10-14-91 <136 216 + 32 <4 <9 <4 <4 <10 <7 <4 <4 <4 <6 11-18-91 <133 229 + 40 <3 <8 <4 <3 <7 <8 <5 <4 <4 <6 12-16-91 <132 225 + 33 <4 <9 <4 <5 <9 <6 <5 <4 <6 T81 10-14 <136 279 + 34 <4 <8 <4 '5 <8 <7 <4 <5 <4 <5 11-15-91 <133 215 + 31 <3 <10 <4 <4 <10 <8 <5 <4 <5 12-13-91 <132 262 + 40 <4 <11 <4 <4 <10 <8 <12 <4 <4 <5 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

I 0

4.b.1 BROADLEAF VEGETATION Brazilian Pe er Ci k wet wei ht Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 T40 10-14-91 1646 + '89 3444 + 160 <12 <10 262 + 13 ND

11-18-91 931 + 56 3025 + 125 <10 <8 16+4 ND 12-16-91 1800 + 80 4705 + 154 <22 <9 367 + 11 ND T41 10-14-91 1275 + 70 2848 + 134 <10 <8 64+ 6 ND 11-18-91 3548 + 108 3307 + 150 <13 <10 93+ 8 ND 12-16-91 1474 + 70 3567 + 159 <23 <12 87+8 ND T67 10-14-91 909 + 68 1389 + 108 197 + 10 ND 11-18-91 1569 + 76 1944 + 112 <13 <9 440 + 13 ND 12-16-91, 1212 + 86 2929 + 139 <23 <10 583 + 16 36 + 9

NRC split sample.

ND Non-detectable.

~ I 4

4.b.l BROADLEAF VEGETATION Brazilian Pe er Ci k wet wei ht Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 Ra-226 T40 07-23-91 1296 + 82 4785 + 179 <17 <13 97+9 52+ 8 08-19-91 842 + 52 2902 + 129 <9 <10 24+5 51+ 6 09-18-91 1344 + 66 3279 + 126 <15 <8 27+5 ND T41 07-23-91 1095 + 76 2866 + 150 <14 <12 138 + 11 ND 08-19-91 1040 + 64 3103 + 147 <10 <10 124 + 9 ND 09-18-91 2216 + 94 3403 + 154 <17 73+7 ND T67 07-22-91 1174 + 73 1661 + 112 <14 <8 298 + 13 ND 08-19-91 1252 + 73 1441 + 104 <13 344 + 13 ND 09-17-91 1103 + 72 1284 + 97 <19 <9 285 + 11 ND ND Non-detectable.

1 ~

0

1991 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT~ UNITS 3 & 4 ATTACHMENT C RESULTS PROM, THE INTERLABORATORY COMPARISON PROGRAM 1991 HP3:1/RADENVOP.PTN

V, ~

FLORIDA DEPT. OF HRS EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA January through June, 1991 Media Nuclide Collection EPA Units Normal. Mean of N.D.K. Action Mon Day Yr Known Range Analyses Level FILTER Alpha 03 29 91 25 pCi/F 0. 098 30.67 1.64 FILTER Beta 03 29 91 124 pCi/F 0. 098 117.33 -1.92 FILTER Cs-137 03 29 91 40 pCi/F 0. 354 58.33 6.35 FILTER Sr-90 03 29 91 40 pCi/F 0. 354 34.33 -1.96 MILK I-131 04 26 91 60 pCi/L 0. 000 59.00 -0.29 MILK Cs-137 04 26 91 49 pCi/L 0. 118 50.67 0.58 MILK K 04 26 91 1650 mg/L 0. 157 1617.00 -0.69 MILK Sr-89 04 26 91 32 pCi/L 0. 118 11.67 -7.04 MILK Sr-90 04 26 91 32 pCi/L 0.354 14.33 -6.12 WATER Alpha 01 25 91 5 pCi/L 0.118 5.67 0. 23 WATER Alpha 05 17 91 24 pCi/L 0.098 20.67 -0. 96 WATER Beta 01 25 91 5 pCi/L 0.118 6.67 0.58 WATER Beta 05 17 91 46 pci/L 0.118 49.33 1.15 WATER Co-60 02 08 91 40 pCi/L 0.118 39.33 -0.23 WATER Co-60 06 07 91 10 pci/L 0.000 10.00 0.00 WATER Zn-65 02 08 91 149 pCi/L 0.118 145.33 -0.42 I

WATER Zn-65 06 07 91 108 pCi/L 0.215 106.33 -0.26 WATER Ru-106 02 08 91 186 pCi/L 0.528 195.00 0.82 WATER RQ-106 06 07 91 149 pCi/L 0.591 141.67 -0.85 WATER Ba-133 02 08 91 75 pCi/L 0.148 71.. 33 -0.79 WATER Ba-133 06 07 91 62 pCi/L 0.098 59.67 -0.67 WATER Cs-134 02 08 91 8 pCi/L 0.118 7.33 -0. 23 WATER Cs-134 06 07 91 15 pCi/L 0.118 14.33 -0.23 WATER Cs-137 02 08 91 8 pCi/L 0.000 9.00 0.35 WATER Cs-137 06 07 91 14 pCi/L 0.236 15.33 0.46 WATER H-3 02 22 91 4418 pCi/L 0.277 4880.33 1.81 WATER H-3 06 21 91 12480 pCi/L 0.142 12274.33 -0.29 WATER I-131 02 15 91 75 pCi/L 0.148 74.67 -0.07 WATER Sr-89 01 11 91 5 pCi/L 0.118 3.67 -0.46 WATER Sr-89 05 10 91 39 pCi/L 0.118 31.67 -2.54 WATER Sr-90 01 11 91 5 pCi/L 0.236 4.00 -0.35 WATER Sr-90 05 10 91 24 pCi/L 0.354 21.67 -0.81

NOTES:

Normal.: Normalized range. As defined in "Environmental Range Radioactivity Laboratory Intercomparison Studies Program Fiscal Year 1981 1982", Environmental Monitoring Systems Laboratory, U. S. Environmental Protection Agency, P. O. Box 93478, Las Vegas, Nevada, 89193-3478.

EPA-600/4-81-004, February, 1981.

NOD.K.: Normalized deviation of the mean from the known value, as defined in EPA-600/4-81-004.

NDP: No data provided. No data was provided to EPA for inclusion in their report.

NA: Not available. Report containing this data has not yet been received from EPA, Las Vegas.

ACTION LEVEL:

(1) Ca use: Very poor, new calibration of detector.

Co rrective Action: Recalibrate the detector for this nuclide, and, in the future, always compare a new calibration with previous calibrations for similarity.

(2) Cause: Erroneously over estimated chemical recovery of strontium carrier.

Corrective Action: Try to improve purity of isolated strontium carrier.

(3) Cause: Erroneously over estimated chemical recovery of strontium carrier.

Corrective Action: Try to improve purity of isolated strontium carrier.

g h FLORIDA DEPT. OF HRS EPA INTERLABORATORY CROSS-CHECK PROGRAM DATA I

July through December, 1991 Media Nuclide Collection EPA Units Normal. Mean of N.D.K. Action Mon Day Yr Known Range Analyses Level FILTER Alpha 08 30 91 25 pCi/F 0.197 32.00 2.02 FILTER Beta 08 30 91 92 pCi/F 0.177 89.33 -0.46 FILTER Cs-137 08 30 91 30 pCi/F 0.000 34.00 1.39 FILTER Sr-90 08 30 91 30 pCi/F 0.236 28.00 -0.69 MILK I-131 09 27 91 108 pCi/L 0.161 103.67 -0.68 MILK Cs-137 09 27 91 30 pCi/L 0.236 30.67 0.23 MILK K 09 27 91 1740 mg/L 0.068 1583.33 3 ~ 12 1 MILK Sr-89 09 27 91 25 pCi/L 0.354 17.67 -2.54 MILK Sr-90 09 27 91 25 pCi/L 0.236 19.00 -2.08 WATER Alpha 09 20 91 10 pCi/L 0.236 11.00 0.35 WATER Beta 09 20 91 . 20 pCi/L 0.118 24.33 1.50 WATER Co-60 10 04 91 29 pCi/L 0.354 30.33 0.46 WATER Zn-65 10 04 91 73 pCi/L 0.422 72.33 -0.16 WATER RQ-106 10 04 91 199 pCi/L 0.384 198.00 -0.09 WATER Ba-133 10 04 91 98 pCi/L 0.059 93.67 -0.75 WATER Cs-134 10 04 91 10 pCi/L 0. 118 9.67 -0.12 WATER Cs-137 10 04 91 10 pCi/L 0. 236 10.67 0.23 WATER H-3 10 18 91 2454 pCi/L 0. 144 2470.67 0.08 WATER I-131 08 09 91 20 pCi/L 0. 098 18.33 -0.48 WATER Sr-89 09 13 91 49 pCi/L 0.473 46.67 -0.81 WATER Sr-90 09 13 91 25 pCi/L 0.118 22.33 -0.92

)fJ ~

4

NOTES:

Normal.: Normalized range. As defined in "Environmental Range Radioactivity Laboratory Intercomparison Studies Program Fiscal Year 1981 1982", Environmental Monitoring Systems Laboratory, U. S. Environmental Protection Agency, P. O. Box 93478, Las Vegas, Nevada, 89193-3478.

EPA-600/4-81-004, February, 1981.

N.D.K.: Normalized deviation of the mean from the known value, as defined in EPA-600/4-81-004.

NDP: No data provided. No data was provided to EPA for inclusion in their report.

NA: Not available. Report containing this data has not yet been received from EPA, Las Vegas.

tACTION LEVEL:

(1) Ca use: Unknown. Examination of the input data, raw counting data, efficiency file, and calculations did not reveal the cause of the problem.

Corrective Action: None at this time.

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