ML17346A903

Radioactive Effluent Release Data,Jul-Dec 1984. W/850304 Ltr

ML17346A903
Person / Time
Site:	Turkey Point
Issue date:	12/31/1984
From:	Williams J FLORIDA POWER & LIGHT CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-85-90, NUDOCS 8503200083
Download: ML17346A903 (61)

Text

RADIOACTIVEEFFLUENT RELEASE DATA 3ULY 19SO THROUGH DECEMBER 19SO SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY 8503200083 84i231 PDR ADOCK 05000250 PDR

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~ y SEMIANNUALRPPORT OF RADIOACTIVEEFFLUENT RELEASES PTP UNITS 3 4 0 7/80 - 12/S0 Introduction All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Specification requirements. The minimum frequency of analysis as required by Safety Guide 21 was met or exceeded.

Aliquots of representative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a'multichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 2g gas flow proportional counter. The efficiency of the gas flow proportional counter is adjusted so that the activity determined by gross beta-gamma analysis approximates the isotopic activities determined by gamma spectrum analysis and selected beta determinations, exclusive of tritium and dissolved gases.

The above procedure was followed for all releases from the waste disposal system and for secondary system batch releases. Frequent periodic sampling and analysis were used to conservatively determine if any radioactivity was being released via the steam generator blowdown system.

The following comments will aid in the interpretation and evaluation of the liquid release data presented in Table I, pages 1 through 3.

The reported values in Table I, pages 1 and 2 include in their computation the quantity of radioactivity released from both the waste disposal system and the secondary system. The secondary system releases occurred when contaminated water which entered the plant storm drain system was released.

2. Weekly and monthly 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 composites were analyzed for gamma emmitting isotopes on a multichannel analyzer attached to a high resolution

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07/80 - 12/80 Qe(Li) detector, and for Sr-89 and Sr-90, using a chemical separation and subsequent beta determination with a 2m gas flow proportional counter.

Tritium was determined by use of liquid scintillation techniques and gross alpha radioactivity was determined by use of a 2> gas flow proportional counter. All concentrations for radioactivity determined from analysis of a

'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.

3. At least one representative batch of liquid effluent from the waste disposal system was analyzed monthly for dissolved fission and activation gases by use of ga'mrna spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released for the month in order to estimate the

'otal dissolved gases released. If more than one batch of effluent was analyzed, the concentrations were weighted in an appropriate manner. The results are totaled on a monthly basis in Table I, page 3.

Representative samples of secondary system batch releases were analyzed individually for gamma emitting isotopes. Tritium representative composite was made to determine if any tritium was being released due to primary to secondary leakage.

The applicable limit for release of radioactive material in liquid waste is five curies per quarter excluding tritium and dissolved gases.

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

a) Gamma spectrum analysis for fission and activation gases,

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07/80 - 12/80 b) Removal of particulate material by filtration and subsequent gamma-spect'rum analysis, Sr-89-90.determination> gross alpha analysis, and gross beta-gamma analysis, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma-spectrum analysis, and d) Condensation of water vapor in a gas sample followed by analysis for tritium using liquid scintillation techniques.

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

The following comments will aid in the interpretation and evaluation of the airborne release data presented in Table II.

1. Calculation of total radioactivity of noble gases, I-131, and particulates is based upon detectable radionuclides only.

2. The applicable limit for release of total radioactive materials in gaseous waste is 0.012 Ci/sec when averaged over the calendar quarter. The percent of the applicable limit for total gaseous release was computed as follows:

Total curies released in gaseous waste durin uarter x 100%

% of Limit =

(.012 Ci/sec) (Seconds in quarter)

3. The applicable limit for the release of I-131 and particulate radionuclides with half-lives greater than eight days in airborne waste is:

Z Qi < 10,000 m3, where Q; = release rate of it" nuclide, Ci/sec M PC; sec and MPC; = maximum permissible concentration of the 1th nuclide, Ci/m 1"

07/80 - 12/80 The release rate, Qi, was determined by dividing the total activity released in Ci, for the ith nuclide (t'ai> Sd), during the calendar quarter by the seconds in the quarter.

VtPC; values were obtained from 10CFR20, Appendix 6, Table II, Column l.

The MPC chosen was the most conservative value of either the soluble or insoluble MPC for each isotope.

The percent

% of Limit =

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of applicable limit was determined MPCI x 1009o as follows 10~000 m3 / sec

0. The maximum gaseous release rate for each month is listed in Table II, page 1, under Section A, Line 3. The applicable limit for maximum allowable release rate is 6.7 E+00 p Ci/sec, averaged over one hour.

5. All values reported in Table II, pages 2 and 3, include the particulate, gaseous, and halogen activity released from the containments during purging, auxiliary building (leakage from pumps, valves, etc), and the gas waste disposal system.

If a minimum detectable activity value was not calculated for an isotope, it will be listed as (-).

III NUCLEAR CHEMISTRY PROCEDURE NC-3 PPENDIX II PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE 7/30/81 EAR~~ "RADIOACTIVE EFFLUENT REI EASES" PORTION OF TIIE SEMIANNUAL OPERATING REPORT PAGE I TABLE I Report of Radioactttve E fluents: Liquid

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A. Gross Rad>oactivst g-5 3ULY AUGUST S P 0 N

1. Total Release mCi 9 66E+ 00 I I.OIE+ OI 2.18E+ 01 6 35E+ 00 1.38E+ 01 0 OSE+ Ol (

z. Av Concentration Duri n Releases Ci/ml 1.60E - 10 2.08E 10 2.51E - 10 1.31E - 10 2.70E 10 1.01E 09 I

3. Av Concentration for Month Ci/ml 3.01E 11 5.20E - 11 6.59E 11 2.76E 11 5.36E - 11 1.67E - 10 (

4. Max Concentration Released Ci/ml 2.6 E-09 1.6 E-09 1.9 E-09 IA E-09 O.SE-09 1.0 E-08 S. Percent of Technical Spec fscat on Limit for Total Activit Released 9.11E - Ol 1.22E + 00 Tr> tium

1. Total Release Ci 1.32E + 02 9A6E + 01 1.28E + 02 6.92E + 01 6.35E + 01 7.35E + Ol (

2. Av Concentration Durin Releases Ci/ml 2.19E - 06 1.67E - 06 1.07E 06 1.03E - 06 1.20E 06 1.81E 06

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3. Av Concentration for Month Ci/ml 0;IIE - 07 3.52E 07 3.85E 07 3.01E - 07 2.07E - 07 3.01E - 07 (

) C. D> sso ve No e Gas I

1. Total Release mCi Oe07E + 02 le21E + 02 7e30E + 01 OeSOE + 01 Oe03E + 00 2e28E + 01 Av Concentration Duri n Releases Ci/ml 7.03E 09 2.11E - 09 8.02E - 10 9.90E 10 7.89E I I 5.62E 10 C)/m] le39E 09 Oe06E 10 2e21E 10 2eOSE 10 1e57E II 9e35E II

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D. Gross Al ha Rad> oacts v> ty

1. Total Release mCi <9.80E -09 (<3.31E - 09) (<6.80E - 09 (< I.OOE 08) < 9,86E p9) (<6.p6E 08

2. Av Concentrati on Duri n Rel eases Ci/ml (<O. ICE -13) (<1.31E - 13) (<2.78E -13 (<0.59E -13 (<0.13E 13) (<3.33E -12)(

3. Av Concentration for Month Ci/ml (<7.76E IO) (<2.77E - 10) (<7.28E -10) (<9.65E -10) (<8.20E - 10) (<5.53E -13))

Volumes

1. Vol of Li uid Waste to Dischar e Liters 2.53E+06 2.25E+06 3.55E+06 2.22E+06 2.10E+06 2.22E+06(

2. Vol of Dilution-Water Durin Rel. Liters 6.02E+ 10 5.68E+ 10 8.67E+ 10 0.80E+ 10 5.11E+ 10 0.05E+ lp)

3. Vol of Dilution Water for Month Liters 3.21E+ 11 . 2.69E+ 11 3.31E+ 11 2.30E+ ll 2.57E+ 11 2.00E+ ll)

NOTE: Numbers in parentheses represent maximum sensitivity in ljCi/ml;

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NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX II PREPARATION OF THE'MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE 7/30/81 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE 2 YEAR 1980 TABLE I Report of Radioactivetttf ueots: Liquid - Total Isoto e Un) t U y ugust eptem er October November December Ag-110M mCi 2.32E-01 1.06E-01 1.30E-01 (<0.3 E-08) S.OOE-02 1.01E-01 Ba-100 mCi (<7.6 E-07) (< 5.8 E-07) (<.0'0 E-07) (<2.3 E-07) (<5.1 E-07) (<5.7 E-O7)

Co-57 mCi (<5.S E-OS) (<7.5 E-08) (<0.9 E-08) (<2.6 E-08) (<3.7 E-08) 1.97E-02 Co-58 mCi 2.07E+00 5.52E+00 1.50E+01 Co-60 mCi 2.72E+00 2.66E+00 2.93E+00 1.18E+00 2.27E+00 1.62E+01 C r-51 mCi 7.06E-01 3.30E-OI (<6.5 E-07) 0.20E-01 1.06E+00 (<1.5 E-O6)

Cs-130 mCi 9.50E-01 2.60E-01 3.20E&0 3.66E-01 9.33E-01 2.22E+00 Cs-137 mCi 1.50E+Ool 0.36E-01 7.07E+00 7.70E-01 1.91E+00 0.28E+00 Fe-59 mCi (<2.1 E-07) (<2.0 E-07) (<1.1 E-07) (<9.6 E-08) 1.17E-01 1.70E-01 I-131 mCi 5.56E-02 (<1.6 E-07) 1.67E-01 7.28E-01 1.12E-01 (<2.8 E-07)

La-100 mCi 6.52E-02 1.00E-02 (<3.0 E-08) (<2.3 E-08) (<0.2 E-08) 2.12E-02 Mn-50 mCi 6.50E-02 (<1.1 E-07) 0.97E-02 (<3.8 E-08) 2.00E-01 1.01E+00 Nb-95 mCi (<1.2 E-07) (<1.1 E-07) (<5.7 E-08) 3.79E-02 (<7.7 E-08) 2.37E-02 Ru-103 mCi (<1.2 E-07) (<9.6 E-08) (<9.2 E-08) (<0.9 E-08) 3$ 3E-02 (<2.3 E-07)

Sb-120 mCi (<1,3E -07) 5.51E-01 0.03E-01 ( 3.8 E-OS) 2.52E-01 (<1.5 E-07)

Sb-125 mCi 7.58E-01 8.73E+00 6.70E+00 1.13E+00 1.27E+00 1.77E+00 Sr-89 mCi 1.00E-OI 2.19E-02 (<8.02E-09) 5.99E-02 (<9.08E-09) 7.19E-02 Total mCi 9.66E+00 1.01E+01 2.18E+Ol ~

6.35E+00 1.38E+01 0.08E+01 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml..

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I NUCLEAR CHEMISTRY PROCEDURE NC-3 PPENDIX I I PREPARATION Of TllE HONTIILY "PltELlllINARY REPORT ON RADIOACTIVE RELEASES" AND TllE EAR 1980 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF TllE SEMIANNUAL OPERATING REPORT. PAGE 3 TABLE I geport oi Radioactive Effluents: Liquid - Dissolved Gas Iota july Au ust Se tember October November December Kr 85 mCi (<1.01E-05) (<6.6 E-06) (<8.59E-06) (<1.95E-05) (<7.18E-06) (<1.29E-05 Kr 85m 2.38E-01 (<6.9E-08) (<5.11E-OS) (<1.00E-07) (<5.00E-OS) (<6.00E-OS)

Xe-131 m mCi 3.11E+00 (<1.17E-06) (<1.02E-06) (<2.88E-06) (<9.50E-07) (<1.23E-06)

Xe-133 0.28E+02 1.18E+02 7.10E+01 0.80E+01 2.91E+00 2.26E+01.

Xe-133m mCi 6.81E+00 1.39E+00 1.20E+00 (<6.02E-07) (<2.18E-07) (<2.88E-07)

Xe-135 mCi 8.69E+00 1.00E+00 7.31E-01 (<8.16E-OS) 7.09E-01 1.73E-01 mCi mCi mCi mCi mCi

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NOTE: Numbers in parentheses represent maximum sensitivity in pCi/m1.

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NUCLEAR CHEMISTRY PROCEDURE NC-3 7/'30/S.t APPENDIX III PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE YEAR 198FF. "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE TABLE II Report of Radioactvive k 7uents: Airborne

. Fission and Actsvatlon Gases U y ugust eptem er cto er Novem er 0'ecember

1. Total Release 9.98E+02 FF.16E+02 1.01E+03 1.39E+02 8.17E+01 1.55E+02

2. Av Release Rate for Period Ci/sec 3 30E+02 1.73E+02 3.3FF E+02 5.7FF E+01 3.38E+01 5.FF FF E+01

• 3. Max Release Rate for Period Ci /sec 5.19E+03 F.53E+03 7.75E+03 1.57E+03 1.53E+OFF 2.97E+03

• Maximum air orne re ease rate average over one our or eac mont . Tec n ca Spec catlons lmlt s 6.7 E&4 AC s averaged over one hour.

B. Io ne - 131

1. Total Iodine - 131 2.50E-03 1.10E-03 1.70E-03 5.63E-03 1.2FF E-03 6.69E-OFF

~2.A R1 II f P id Ci/sec 8.28E-OFF FF.55E-OFF 5.63E-OFF 2.33E-03 5.12E-OFF 2.35E-OFF C. Particulates

1. Particulates with t 1/ >8 days 2.58E-05 8.9FF E-06 1.37E-05 1.25E-05 2.27E-06 I

5-83E-06

2. Av Release Rate for Period Ci /sec Se5FE 06 3.69E-06 FF.50E-06 5.17E-06 9.38E-07 2.01E-06

3. Gross Al ha Radioactivit 9.02E-OS 1.08E-07 1.10E-07 2.60E-08 7.83E-OS FF.80E-OS D. Tr tium

1. Total Release 1.01E-OI 2.68E-02 9. 2E-0

2. Av Release Rate for Period Ci/sec 3.3FFE-02 '.11E-02 3.09E-03 7.36E-03 9 FF 6E-03 9.02E-03 Percent o A sca e smlt 2.5FF E+00 3.9IF E-01

1. Fission and Activation Gases 2- I-131 and Part tl/2>8d 6.68E-02 9.FF SE-02 NOTE: Num ers n parent eses represent maximum'sens t v ty n ltC1 Ill ..

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NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX III PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE 7/30/8I YEAR 1980 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE 2 TABLE II Airborne Releases - Particulates Isoto e Unit U y Au ust Se tember October Novemb December Ba-100 Ci (<1.5 E-13) (<1.3 E-13) (<0.8 E-10) (<6.0 E-10) (<5.O E-ie) (<5.6 E-10)

Co-58 Ci 1.3E-06 1.10E-06". 2.30E-06 5.61E-06 (<1.6E -10) 3. 29E-06 Co-60 Ci 1.15E-05 0.02E-06 . 5.00E 8.00E-07 2A E-07 (<3.5E-10)

Cs-130 Ci 1.6 E-06 (<3.5 E-10) 1.30E-06 (<2.2 E-10) (<2.i E-le) (<7.2 E-10)

Cs-137 Ci 6.0 E-06 2.89E-06 2.86E-06 2.91E-06 7.5 E-07 2.06E-06 1-131 Ci 1.2 E-06 (<3.0 E-le) 1.75E-06 2.07E-06 6.1E-07 3.70E-07 La-100 Ci 3.7 E-06 (<O.O E-i.e) (<1.0 E-10) (<1.8 E-IO) (<1.8 E-le) (<2.1 E-IO)

Sr-89 Ci 0.88E-07 0.88E-07 (<8.11E-06) 6.7 E-07 6.7 E-07 1.08 E-07 Total Ci 2.58E-05 8.90E-06 2.27E-06 5.83E-06 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml..

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NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX I II PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE 7/30/8)

YEAR 1980 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE II 3'ABLE Airborne ree eases Gaseous Fission and Activation Gases Isoto e Unit 3uly August September October November December Ar-41 Ci 6.01E-OI 2.53E-OI- 6.20E-OI 1.90E-OI 5.70E-OI 6.83E 01 5.01E+00 3.17E+00 0.39E+00 5.75E+00 2.27E+00 9.39E+00 Kr-85 Ci 5.38E-02 1.77E-02 2.99E-02 1.13E-02 0.00E-03 8.51E-03 Kr-85m Ci

\ (<6.57E-05) (<5.02E-05) 3.30E-06

(<9.21E-05) (<3.11E-05). (<3.93E-06)

Kr-87 Ci 7.38E-03 5.23E-03 0.02E-00 1.87E-05 1.78E-05 (<9.23E-05)

Kr-88 Ci 2.29E+00 1.50E+00 . 1.97E+00 1.31E+00 2.61E-OI 1.12E+00 Xe-131m Ci 9.86E+02 0.09E+02 I.OOE+03 1.31E+02 7.70E+Ol 1.02E+02 Xe-133 Ci Xe-133m Ci 1.81E+00 1.79E+00 1.95E+00 2.00E-OI 8.00E-OI 5A6E-Ol Xe.-135 Ci 2.38E+00 6.86E-OI 7.82E-OI 0.2 1 E-01 3.95E-OI 0.00E-OI Xe-135m Ci (<2.99E-00) (<0.93E-05) (<7.0 I E-05) (<9.05E-05) (<8.06E-05) 7.69E-05 Xe-138 Ci (<1.37E-03) (<9.75E-05) (<9.32E-05) (<9.03E-05) (<8.18E-05) (<8.06E-05 Total Ci 9.98E+02 0.16E+02 I.OIE+03 1.39E+02 8.17E+01 1.55E+02 Halo ens Gaseous Isoto e Unit 3uly August September October November December I-131 2.5 E-03 1.10E-03 1.70E-03 5.63E-03 1.20E-03 6.69E-OV I-133 7.0 E-00 0.05E-OV 5.06E-00 1.12E-OO 0.05E-OO 1.18E-OO I-135 Ci (<2.1 E-13) (<1.9 E-13) (<3.2 E-13) (<1.6 E-13) '(<2.3 E-13) (<2.1 E-13)

Br-82 Ci 1.09E-00 1.70E-OO 6.50E-05 (<9.3 E-10) I.59E-OO 0.97E-05 Total Ci 2.39E-03 1.72E-03 2.31E-03 5.70E-03 1.80E-03 8.37E-00 Note: um ers n parer, eses represen maximum sens ivi y )n p i r

Wl TURKEY POINT UNITS NO- 3 6 4 RADIOACTIVE EFFLUENT RELEASE DATA JULY 1984 THROUGH DECEMBER 1984 SOLID WASTE DATE OF SHIPMENT CURIES CUBIC FEET SHIPPED TO:

07-06-84 151.4 84 BARNWELLi S.C.

07-13-84 75.93 84 BARNWELL, S .C.

07-16-84 1.508 200 BARNWELL, S .C.

07-18-84 .094 1050 HANFORD, WA ~

07-20-84 4.379 170 BARNWELL, S . C.

08-06-84 60.8 84 BARNWELL, S .C.

08-07-84 1.963 170 BARNWELL, S .C.

08-09-84 .548 170 BARNWELL, S. C.

08-22-84 .122 1050 BARNWELL, S. C.

09-12-84 .040 1050 BARNWELL, 'S.C.

09-17-84 154 42

~ 84 BARNWELL, S . C.

09-27-84 . 073 1050 HANFORD g WA.

10-04-84 . 044 1050 BARNWELL, S ~ C.

10-10-84 . 048 1050 HANFORD i WA.

10-22-84 1. 192 84 BAH%'JELL, S .C.

10-25-84 .134 1050 HANFORD i WA 11-01-84 3. 002 170 BARNWELL, S. C.

11-08-84 4.201 170 BARNWELL, S .C.

11-13-84 2.510 '70.

BARNWELL, S .C.

11-20-84 .098 1050 BARNWELL, S . C.

12-04-84 .036 1050 HANFORD, WA.

12-11-84 9.114 170 BARNWELL, S . C.

12-21-84 .056 1050 BARNWELL, S .C.

23 SHIPMENTS 471.712 CURIES 12,310 CUBZC FEET ON SITE AS OF JANUARY 1, 1985 20.200 CURIES 3830 CUBIC FEET

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RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TURKEY POINT UNITS 3 5 4 DOCKET NOS. 50-250, 251 DADE COUNTY, FLORIDA 7-1-84 TO 12-31-84 PREPARED FEBRUARY 1984 DATA SUBMITTED BY: FLA. DHRS DATA REVIEWED AND REPORT PREPAR BY:

REPORT REVIEWED BY:

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0 4 I. INTRODUCTiON This report is submitted pursuant to Section 6.9* of the Turkey Point Plant Units 3 5 4 Technical Specifications and provides information and results for environmental samples specified .by Table 4.12-1.*

Radiological environmental surveillance for the Turkey Point Plant is conducted in accordance with Section 4.12* of the plant's Technical Specifications. A summary of the samples collected and analyses performed during the period July 1, 1984 through December 31, 1984 is provided in Table l.

1. THE MONITORING PROGRAM Period Covered: This report covers the period from July 1, 1984 through December 31, 1984.

Analytical Responsibilit  : Radiological environmental monitoring for the Turkey Point Plant is conducted by the State of Florida, Department of Health and Rehabilitative Services (DHRS). Samples are collected and analyzed by DHRS personnel.

• The contents and format of this report conform to the

.Technical Specifications that were in effect during the period, July 1, 1984 - December 31, 1984.

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~f samples were collected from 46 different sample locations to be analyzed for radioactivity. Table 1 summarizes the highest, lowest and mean results for all sample locations and; where applicable, the highest, lowest and mean results for the sample locations yielding the highest mean levels. The values in Table 1 are based upon only those analyses which yielded detectable measurements.

I Split-Sample: During the period July 1, 1984 - December 31, 1984, in addition to the samples identified in Table 1, twelve (12) samples were submitted for comparative analysis by the DOE in accordance with the DHRS/DOE split-sampling program.

3. MISSING DATA A description and explanation for missing data is contained in Table l.

4. nlscuSSION AND INTERPRETATION OF DATA Air Monitoring: Continuous air sampling was conducted at 8 different locations surrounding the Turkey Point Plant. Samples were collected and analyzed by Florida DHRS for gross radioactivity and radioiodines (I-131) on a weekly basis. Air samples from this reporting period were within the range expected for background measurements. Table 1 provides a summary of these results.

P Direct Radiation Monitoring: Continuous monitoring of ambient radiation exposure rate was provided routinely at eleven different sample locations surrounding the Turkey Point Plant. Samples were collected and analyzed by Florida DHRS on a monthly basis. Results are based upon the average readings of two dosimeters at each location. All results from this

,.reporting period were within the normal range expected for background measurements. Table 1 provides a summary of these results.

Other Samples:, In addition to the samples described above, several other environmental samples were collected from areas around the Turkey Point Nuclear Plant. These samples included precipitation, surface water, drinking water, sediment, fish, crustacea, food crops, vegetation, milk, soil and other terrestrial biota. Table 1 provides a summary of the results of these samples from July 1, 1984 through December 31, 1984.

As in the past, tritium was the predominant radionuclide to be detected in samples around the Turkey Point Plant. The highest values for tritium were from water samples taken from within the plant's closed cooling system. The highest tritium concentration measured during this surveillance period was only about 0.235 of the concentration which would be permitted continuously in unrestricted area waters (10CFR20, Appendix B, Table II.) The highest tritium observed in'samples from outside of the closed cooling system was only about 0.01$ of the unrestricted area concentration. Trend analysis indicates that tritium is not increasing.

tp In. addition to waterborne tritium, trace concentrations of fission and activation products were detected in some of the samples taken from within the closed cooling system. These results are consistent with past measurements and data indicate no discernable increase in radioactivity in these samples.

The results of radiological measurements for other media and other locations surrounding the Turkey Point Plant do not yield evidence of build-up in the environment when compared to past measurements, including samples collected during the preoperational surveillance program, and e]sewhere within the State of Florida.

5. DAIRY HERD SURVEY The results of a Dairy Herd Survey conducted by the Department of Health and Rehabilitative Services in August 1984 is provided in Table 2, ~Dair Herd Surve Summary.

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SUMMARY

AND CONCLUSIONS July 1, - December 31, 1984 Continuous air sampling measurements are all within the range expected for background values.

Continuous ambient radiation exposure rate measurements are all within the range expected for background values.

Tritium concentrations in water samples collected around the Turkey Point Plant are consistent with past measurements and are not increasing. The highest observed tritium concentrations are found within the plant's closed cooling system. All measurements are well below the concentration permitted by 10CfR20 for unrestricted area waters.

Radioactivity measured in sediment and biota samples from within the closed cooling system is consistent with past measurements, with no discernable increase noted.

,Measurements for other media and samples are consistent with past measurements including those taken during the preoperational surveillance program.

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. The concentrations of all radionuclides reported in Table 1 are much

- less than that permitted for release to unrestricted areas as specified in 10 CFR'0, Appendix 8, Table II. The Radiological Environmental Monitoring Program substantiates that radioactivity released as a result of operation of the Turkey Point Plant, Units 3 8 4 is not contributing significantly to the radiation exposure to any member of the public.

t' TABLE 1 ENVIRONMENTAL RADIOLOGICAL HONITORING PROGRAM SCARY NAME OF FACILITY TURKEY POINT PLANT UNITS 3 5 4 DOCKET NO. 50-250. 251 LOCATION OF FACILITY DADE C U Y L Page 1 of f0 All Indicator Location with Highest Mean Control ) No. of Number of Locations Location Nonroutine Hedium or Pathway Analysis amp e ocat on Reported Sam led Unit for Sites Sam les Anal ses Mean ) Ran e ) Distance a Direction Mean ) Ran e ) Hean ) Ran e ) Heasurement 1.1 AIR

1. Particulates pCi/m Gross 8 8 208 208 .014 .006- T51: Homestead .015 .007- .014 .006-

'(208/208) .042 Bayfront Park (26/26) .042 (26/26) .020 (2 miles - NN)

2. Radioiodine pCi/m3 13 I 8 208 208 ND NA NA NA ND NA 1.2 DIRECT RADIATION

1. TLD uRem/hr Exposure 11 132 66 4.7 2.4-6.9 T64: Natoma Substation 6.2 4.9- 6.2 4.9-Rate (66/66) (22 miles - N) (6/6) 6.9 (6/6) 6,9 1.3 PRECIPITATION

l. Rainwater pCi/1 Gross 8-DS 4 23 ) 23 4.0 3.3-5.2 T57: Dolan's Farm 4.2 4.2- 3.3 NA (7/23) (4 miles - NN) (2/6) 4. 2 (1/6)

Gross 8-UDS ND N NA N ND NA Tritium 23 250 NA T72: Boy Scout Camp 250 NA ND NA (1/23) (On-Stte - NSM) (1/5)

Y emitting ) 23 ND isotopes OS - Dissolved Solids UDS - Undissolved Solids ND - Not Detectable NA - Not Applicable

TABLE 1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAH SUMHARY NAHE OF FACILITY TURKEY POINT PLANT UNITS 3 8I 4 DOCKET NO. 50-250, 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY 1, 1984 - DECEMBER 31, 1984 Page 2 of 10 All Indicator Location with Highest Mean Control2) No. of Number of Locations Location Nonroutine Medium or Pathway Analysis amp e Locat on Reported Sam led Unit for Sites Sam les Anal ses Mean ) Ran e ) Distance'S Direction Hean1) Ran e ) Mean ) Ran e ) Measurements 2.1 SURFACE WATERS

l. Estuarine 10 20 (Surface Water) . pCi/1 Tritium 20 270 NA T81:Card Sound 270 NA NA NA (1/20) (6 miles - S) (I/2) 89Sr 20 ND NA NA NA NA NA NA 90Sr 20 ND NA NA NA NA NA NA Y emitting3) 20 ND NA NA NA NA NA NA isotopes

2. Closed Cooling 2 12 Canal (Surface Water) pCi/I Tritium 12 6100 5400- T84:Closed Cooling 6200 5800- NA NA (12/12) 6800 Canal (Onsite- SW) (6/6) 6500 89Sr 12 ND NA NA NA NA. NA NA 90Sr 12 ND NA '.NA NA NA NA NA Y emitting ) 12 ND NA NA NA NA NA NA isotopes DS - Dissolved Solids UOS '-'ndissolved Solids ND - Not Detectable NA - Not Applicable

TABLE 1 ENVIRONMENTAL RADIOLOGICAL HONITORING PROGRAH

SUMMARY

NAME OF FACILITY TURKEY POINT PLANT UNITS 3 8 4 DOCKET NO. 50-250 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY 1 1984 - DECEMBER 31, 1984 Page 3 of 10 All Indicator Location with Highest Mean Control2) No. of Number of Locations Location Honroutine Medium or Pathway Analysis Samp e Locat on Reported Sam led Unit for Sites Sam les Anal ses anl) Ran el) Distance 8 Direction Mean ) Ran e ) Meanl) Ran el) Heasurranents

3. Fresh Water Drainage Canals 2 12 (Surface Water) pCi/I Tritium 12 330 T75 - Florida City 330 HA NA HA (1/12) Canal (2 miles - MHM) (1/6)

Gross 8-DS 12 150 3.0- T75: Florida City 300 250- NA HA (12/12) 370 Canal (2 miles - MNM) (6/6) 370 Gross 8-UDS 12 ND NA NA N NA NA 2.2 WELLS

1. Potable Mell Mater (Drinking Mater) pCi/1 Tri tirmr 6 ND NA NA NA NA NA N N

Gross 8-OS 6 6.8 5.4-8.2 T57: Dolan's Farm 7.0 6.7-7.4 HA NA (6/6) (4 miles - HM) (2/2)

Gross 8-UDS 6 ND HA NA NA HA NA N

2. Ground Mater Hells 6 12 (Ground Hater) pCi /1 Tritium 12 280 NA T87: Groundwater well 280 HA HA NA (I/12) E-10 (2 miles - S) (1/2) 89Sr 12 ND HA HA NA NA NA NA

>>Sr 12 ND HA NA NA HA NA N Y emitting ) 12 ND NA NA NA HA HA NA isotopes DS - Oi ssol ved Solids UOS - UndissolIved Solids ND - Not Detectable NA - Not Applicable

TABLE 1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

NAME OF FACILITY TURKEY POINT PLANT UNITS 3 5 4 DOCKET NO. 50-250, 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY 1, 1984 - DECEMBER 31, 1984 Page 4 of 10 All Indicator Location with Highest Mean Control ) No. of Number of Locations Location Nonroutine Medium or Pathway Analysi s amp e Locat on Reported Sam led Unit for Sites Sam les Anal ses Meanl) Ran e1) Distance 5 Direction Mean1) Ran e ) Mean ) Ran e ) Meas rement 3.0 BOTTOM SEDIMENTS

1. Closed Cooling Canal (Sediment) pCi/kg Sr ND NA NA NA ~ NA NA II 90Sr '

ND NA NA NA NA NA emitting )

isotopes

1. 60Co 290 220- T84: Closed Cooling 330 290- NA NA (4/4) 370 Canal (Onsite-SW) (2/2) 370 137Cs 25 24 T84: Closed Cooling 25 NA NA NA (3/4) 25 Canal (Onsite-SW) (1/2) 95Hb T84: Closed Cooling 46 - NA

3. 46 HA NA NA (I/4) Canal (Onsite-SW) (1/2)

2. Estuarine 7 7 (Sediment) pCi/kg Sr ND NA NA NA NA NA 90Sr ND HA NA NA NA NA Y emitting3) ND NA HA HA NA HA isotopes DS - Dissolved Solids UDS - Undissolved Solids ND -- Not Detectable NA - Not Applicable

0 t~

TABLE 1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

NAHE OF FACILITY TURKEY POINT PLANT UNITS 3 5 4 'OCKET NO. 50-250 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY 1 1984 - DECEMBER 31 1984 Page 5 of 10

~r All Indicator Location with Highest Hean Control2) No. of Number of Locations Location Nonroutine Medium or Pathway Analysis amp e ocat on Reported Sampled Uni t for Sites Samples Anal ses Hean ) Ran e ) Distance 5 Direction Hean ) Ran e ) eanl) Ran el) Measurements 4.0 AQUATIC BIOTA

1. Crustacea 6 4)

(Blue Crab) pCi/kg Sr 5 ND NA NA NA NA NA gOSr 54) ND NA NA NA

- NA NA y emitting ) 6 ND NA NA NA NA NA isotopes

2. Fish, Carnivore 7 7 (Mixed Species) pCi/kg Sr 5 ND NA NA

~~

5 ND NA NA y emitting ) ~

7 isotopes 137Cs 140 NA T84 - Closed Cooling 140 NA N NA (I/7) Canal.(Onsite - SW) (1/1) 134Cs 20 NA T84 - Closed Cooling 20 N N (I/7) Canal (Onsite - SW) (1/1) 3 60Co 28 N T84-Closed Cooling 28 NA N (I/7) Canal (Onsite - SW) (I/1)

DS - Dissolved Solids UDS - Undissolved Solids ND - Not Detectable NA - Not Applicable

II t, TABLE 1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

NAME OF FACILITY TURKEY POINT PLANT UNITS 3 5 4 . DOCKET HO. 50-250, 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY 1, 1984 - DECEMBER 31, 1984 Page 6 of 10 All Indicator Location with Highest Mean Control2) Ho. of Number of Locations Location Nonroutine Medium or Pathway Analysis Samp e Locat on Reported Unit for Sites les Anal ses Meanl) Ran e ) Distance 5 Direction Meanl) Ran el) Meanl) Ran el) Measurements Sam led Sam

3. Fish, Herbivore 6 6

4) NA NA NA NA NA (Mullet) pCi/kg Sr 5 ND NA

4) HA HA 90Sr 5 ND NA NA HA NA Y emitting3) 6 ND NA NA NA NA HA HA isotopes

4. Turtle Grass NA HA NA HA (Turtle Grass) pCi/kg Sr ND HA N 90Sr ND HA NA =

NA NA NA emitting3) ND HA HA NA NA NA Y

isotopes

5. Sponges NA NA (Sponge) pCi/kg ~ emitting ) ND NA HA NA isotopes DS - Dissolved Solids UDS - Undissolved Solids ND - Not Detectable NA - Not Applicable

TABLE 1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

NAME OF FACILITY TURKEY POINT PLANT UNITS 3 5 4 DOCKET NO. 50-250, 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY I, 1984 - DECEMBER 31, 1984 Page 7 of 10 All Indicator Location with Highest Mean Control2) No. of Number of Locations Location Nonroutine Medium or Pathway Ana lysi s amp e ocation Reported Sam led Unit for Sites Sam les Anal ses Mean ) Ran e ) Distance g Direction Mean ) Ran el) Meanl) Ran el) Measurement 5.0 TERRESTRIAL

1. Small Animal (Racoon) pCi/kg Sr ND NA NA NA. NA HA NA 90Sr ND HA NA HA NA NA NA Y emitting ) ND NA HA NA NA NA NA isotopes

2. Food Crops (Malanga, pCi/kg 89Sr ND NA . NA NA -

HA NA NA Sorghum) 90Sr 3 4.2 4.1- T57: Dolan's 'Farm 4.3 HA NA NA (3/3) 4.3 (4 miles - NN) (I/1)

Y emitting3) 3 HD NA NA NA NA HA NA isotopes DS - Dissolved Solids UDS - Undissolved Solids ND - Hot Detectable NA - Not Applicable

I TABLE I

,ENVIRONHENTAL RADIOLOGICAL MONITORING PROGRAH SUHMARY NAME OF FACILITY TURKEY POINT PLANT UNITS 3 8I 4 DOCKET NO. 50-250 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY 1. 1984 - DECEMBER 31, 1984 Page 8 of 10 All Indicator Location with Highest Hean Control2) Ho. of Number of Locations Location Nonroutine Medium or Pathway Analysis amp e ocat on Reported Sampled Unf t for Sites Sam les Anal ses Hean ) Ran e ) Distance h Direction Heanl) Ran e ) Heanl) Ran el) Heasurements

3. Hilk 1 2 (Goat Hilk) pCf/1 Y emitting )

isotopes 1 1311 ND NA NA HA NA NA NA 2 137Cs ll N T99: 24000 SM 167 Ave ll HA N N (1/2) (11 miles - HM) (1/2) 3.Others ND NA HA NA N NA HA

4. Vegetation 7 7 (Hangrove leaves) pCi/kg Sr 7 ND NA NA NA NA ND N 90Sr 7 4.7 NA T58: Entrance Road 4.7 NA ND HA (I/7) (Onsfte - NM) (I/1) y emi t t I ng3) 7 isotopes I 137Cs 7 NA T51: Homestead 7 HA ND (I/7) Bayfront Park (1/1)

(2 miles - NSI)

DS - Dissolved Solids UDS - Undissolved Solids ND - Not Detectable NA - Not Applicable

I TABLE 1 ENVIRONHENTAL RADIOLOGICAL HONITORING PROGRAH SUHHARY NAHE OF FACILITY TURKEY POINT PLANT UNITS 3 II 4 DOCKET NO. 50-250, 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY 1, 1984 - DECEHBER 31, 1984 Page 9 of 10 All Indicator Location with Highest Hean Control2) No. of Number of Locations Location Nonroutine Hedium or Pathway Analysi s amp e Locat on Reported Sam led Unit for Sites Sam les Anal ses Hean ) Ran e ) Distance 5 Direction Hean ) Ran e ) eanl) Ran el) Heasurement

5. Soil (Soil) pCi/kg Sr ND NA NA NA NA ND NA n 90Sr ND NA NA NA NA ND NA emitting )

isotopes 137Cs 172 . 39- T56: Princeton 390 NA 39 NA (7/7) 390 Substation (1/1) (1/1)

(8 miles - NNN) 2.Others NA NA NA ND NA DS - Dissolved Solids UDS - Undissolved Solids ND - Not Detectable NA - Not Applicable

'1+

Page 10 of 10 TABLE 1 NOTES

1) Mean and Range values based upon data with detectable results only.

( / ) Indicates the number of analyses with detectable results compared to the'umer of analyses performed.

2) Control location - T64, Florida Power 5 Light Company - Natoma Substation (22 Miles - N).

3) Egg),uding Potassium - $ 0 ( K), Radon - ggp ( Ra), Thorium - 232

(~ "Th), Beryllium-7 ('e) and Uranium ( >

U) which are naturally occurring radi oisotopes commonly found in the Florida environment.

4) ~N<<

SAMPLE DATE LOCATION* TYPE REASON MISSING 12-18-84 T72 Precipitation Insufficient Precipitation for sample at this location The following >

Sr sample results are missing because of incomplete analyses. If positive results are obtained, they will be provided in a supplement to this report.

12-10-84 T81 Fish, Kerbivore Incompl ete >

Sr analysi s 12-27-84 T81 Fish, Carnivore Incompl ete ~

Sr analysi s 12-27-84 T81 Crustacea Incomplete Sr analysis

• A key to the sample locations is provided in Turkey Point Units 3 5 4 Technical Specifications.

lof2 TABLE 2 Turkey Point Plant Unit Nos. 3 5 4 Dairy Herd Survey Summary August 1-3, 1984 The following information is summarized from a Dairy Herd Survey that was conducted by the State of Florida, Department of Health and Rehabilitative Services.

COWS (Potentially) milk producing cows were observed at the following referenced locations.

Sector Oistance miles from lant No. Observed Address NNW 11.6 0.1 mile West of intersection of S.W. 248 St. and S.W. 117 Ave.

10.2 Corner of SW 264 St. and SW 167 Ave.

13.0 17905 SW 216 St.

NW 15.3 20600 SW 198 Ave.

15.7 10 0.05 miles South of 21250 SW 198 Ave.

15.8 21401 SW 216 St.

WNW 14. 2 . 25000 SW 207'Ave.

WNW 14. 3 One block North of SW 248 St. at House No. 20790 WNW 15.0 24745 SW 217 Ave.

'W C

2of2 Goats (potentially) milk producing goats were observed at the following referenced locations.

Sector Distance miles . from lant No. Observed Address 9.8 60 13401 SW 224 St.

NW 10.2 Corner of SW 264 St. and SW 167 Ave.

11.2 24000 SW 167 Ave.

NW 11.2 16630 SW 234 St.

NW 14. 0 0.2 miles West of-intersection of SW 192 Ave. and SW 216 St.

15.8 17 21401 SW 216 St.

WNW 15. 2 Count not 24401 SW 217 Ave.

available WNW 19.8 25254 SW 207 Ave.

WNW 20.1 20930 SW 248 St.

• Site of HRS milk sample,

Al e