ML17345B325

Radioactive Effluent Release Data,Jul-Dec 1981. W/820302 Ltr

ML17345B325
Person / Time
Site:	Turkey Point
Issue date:	12/31/1981
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-82-78, NUDOCS 8311030059
Download: ML17345B325 (64)

Text

RADIOACTIVEEFFLUENT RELEASE DATA 3ULY 1981 THROUGH DECEMBER 1981 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER R LIGHT COMPANY DISTRIBUTION 3.L. DANEK A.3. GOULD (3)

D.W. HAASE 3.K. HAYS E.R. LAPIERRE

3. S. WADE R.3. FREC HETTE FILE 83ii030059 Sii23i PDR,ADQCK 05000250 R PDR

0 lh, I"

f I

)

SEMIANNUALREPORT OF RADIOACTIVE EFFLUENT RELEA'SES PTP UNITS 3 R 0 7/81- 12/81 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.

Li uid Releases Aliquots of represen'tative 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 2m 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 estimate the quantity of radioactivity 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 7.

1. The reported values in Table I, page 1, 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 was blown down from the steam generators during primary to secondary leakage conditions, or when the generators were drained for repair or refueling. Activity that entered the plant storm drain system was also included in the secondary system activity released and in the total activity released.

~ e 0 . ~ '4. ~

7/81 - 12/81

2. The reported values in Table I, pages 2 and 3 are the total quantities of.

radioactivity for individual nuclides released from the waste disposal system and the secondary system together. The values in Table I, pages 0 and 5 are for the waste disposal system only and page 6 is for the secondary system only.

3. During primary to secondary leakage, release of several short-lived nuclides from the secondary system occurs. These short-lived nuclides are not generally detected in batch released from the waste disposal system due to the long holdup time of processed water. Only those isotopes that were detected in the secondary system releases were reported. All non-detectable isotopes are listed as ().

0. 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 Ge(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 2m 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'eleased during the compositing period.

5. 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 gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume r'eleased for the month in order to estimate the

0 7/81 - 12/81 total 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 7. Dissolved gases, if any, from secondary system releases were determined from the samples of the individual releases. Isotopic concentrations were multiplied by the volume released to determine the quantity of radiogas nuclides released.

6. Representative samples of secondary system batch releases were analyzed individually for gamma emitting isotopes. Analysis of a representative composite for tritium was made for releases which occurred due to primary to secondary leakage.

7. 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 the secondary system during conditions of primary to secondary leakage. The techniques employed in determining the radioactivity in airborne releases are:

a) Gamma spectrum analysis for fission and activation gases, b) Removal of particulate material by filtration and subsequent gamma-spectrum analysis, Sr-89-90 determination, 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.

o Q:

7/81 - 12/81 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 maximum rated capacity for the hogging jets and the maximum measured flow rate for the condenser air ejectors, and an estimate of the rate of exhaust from the atmoshperic dumps were used to conservatively estimate the airborne releases from the secondary system whenever applicable.

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.

'I

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 10096 96 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:

~ Qi 10,000 m3, where Q; = release rate of ith nuclide, Ci/sec MPCI sec and MPCI maximum permissible concentration of the ith nuclide, Ci/m3 The release rate, Qi, was determined by dividing the total activity released in Ci, for the ith nuclide (ty,> 8d), during the calendar quarter by the seconds in the quarter.

0 I 7/81 - 12/81 MPCI values were obtained from 10CFR20, Appendix B, Table II, Column 1.

The MPC chosen was the most conservative value of either the soluble or l

insoluble MPC for each isotope.

The percent of applicable limit was determined as follows:

x 100%

% of Limit = MPCI 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+04 pCi/sec, average 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), the gas waste disposal system and the secondary system during conditions of primary to secondary system leakage. If a minimum detectable activity value was not calculated for an isotope, it will be listed as ( ).

0 Vy cg

HUVLtBH q HtNliiKi 1'HVUKUVNt Al -8 PPENDIX II PREPARATION OF THE HONTE lLY "PRELIHINARY REPORT ON RADIOACTIVE RELEASES" AND THE EAR 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF'TllE SEHIANNUAL OPERATING REPORT Page 1 TABLE I Repons of lladioactttve E "fluents: Liquid A. Gross Radsoact vent g-5 Jul Au ust Se m r v m m r

1. Total Release 68E+Ol

. 2. Av Concentration Durin Releases mC1 Ci/ml 1.2 0 E E-lo '.0 E-11 8 8 4.9 E

E-ll 1.3 E-lo 3.8 E-10 5 6 0

3. Av Concentration for Honth Ci/ml 1;1 E-10 7.6 E-ll 4.9 E-11 1.1 E-10 3.8 E-10 5.6 10

4. Hax Concentration Released Ci/ml 2.6 E-09 2.4 E-09 7.9 E-10 6.8 E-09 1.5 E-08 2.8 E-08

5. Percent of Technlca Spec cat on Limit for Total Activit Released 8.9 E-01 3.2 E+00 Tr> ts um

1. Total Release Ci 6.47 E+01

• 3.47 E+Ol 2.57 E+01 8.31 E+00 5.30 E+00 3.30 E+Ol

2. Av Concentration Durin Releases Ci/ml 4.2 E-07 1.7 . E-07'.4 E-07 6.2 E-08 5.0 E-'08 1.8 E-07

3. Av Concentration for Honth Ci/ml 3';6 E-07 1.6 E-07 1.4 E-07 5.3 E-08 5.0 E-08 1.8 E-07 C. Dssove o e Gas

1. Total Release mCi 1.1 E+00 4.62 E+00 1.99 E-Ol 1.63 E+00 (< 4.7 E-08) (<2.1 E-07)

2. Av Concentration Durin Releases Ci/ml 6 9 E-12 2.3 E-11 1.1 E-12 1.2 E-ll (<4.5 E-19) (<1.1 E-1'8)

3. Av Concentration for Honth Ci/ml 6.0 E-12 2. 1 E-ll 1. 1 E-12 1. 0 E-ll (< 4. 5 E-19) (< 1.1 E-18)

D. Gross A ha Ra oact vasty

1. Total Release mCi << < E-02 <1 5 E 08 <2.6 08

2. Av Concentration Durin Releases Ci/ml <3.0 E-20 <2.2 E-20 <4.7 E-20 1.6 E-13 <1.4 E-19 <1.4 -19

3. Av Concentration for Honth Ci/ml <2.6 E-20 (2.1 E-20 (4.7 E-20 1.3 E-13 (1.4 E 19 (1. 19)

E. Volumes

1. Vol of Li uid Waste to Dischar e Liters 1.27 E+07 2.40 E+07 1.35 E+07. 9.56 E+06 6.45 E+06 1.73 E+07

2. Vol of Dilution Mater Durin Rel. Liters 1.55 E+11 2.05 E+11 1.83 E+11 1.33 E+ll 1.05 E+ll 1.85 E+ll

3. Vol of Dilution Mater for Honth Liters 1.79 E+ll 2.18 E+ll 1.83 E+11 1.58 E+ll 1.05 E+ll 1.85 E+11 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

~e 0 S

NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX II PREPARATION OF T)IE MONTHLY "PRELIHINARY REPORT ON RADIOACTIVE RELEASES" AND THE Page 2 YEAR 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEHIANNUAL OPERATING REPORT TMLE I Repovt of Radioactive EEEueota: Liquid - Total Isoto e un t Se tember Oc o Ag-110m mCi (<5.9 E-08) (<5.3 E-08) ( <3. 7 E-08) (<4.7 E-08) 1.37 E-01 1.73 E aa-140 mCi (<2.8 E-07) (<3.0 E-07) (<1.6 E-07) (<3.0 E-07) (<3.9 E-07) (<6.7 E Co-57 mCi <2.9 E-08 <3.2 E-08 <1;8 E-08 <2.8 E-08 1.4 E-02 <6.6 E-08 Co-58 mCi 1.54 EWO 6.85 E-01 3.22 E-01 . 2.49 E+00 l. 39 E+O1 3.68 E Co-60 mCi 4.77 E+00 3.39 E+00 2.54 E+00 3.82 E+00 6.17 E+00 1.01 EWl

(<4.2 E-07) (<4.2 E-07) (<2.5 E-07) (<4.2 E-07) 3.15 E+00 1.42 E+01 Cs-134 mCi 1.66 E+00 1.81 E+00 9.4 E-01 3.38 E+00 5.79 E+00 5.46 E+00 mCi 2.23 E-02 <6.7 E-08 <6.8 E-08 <8.8 E-08 3.7 E-02 Cs-136's-137 3.14 E+00 2.68 E+00 1.56 E&0 4.30 E&0 7.97 E&0 7.73 E&0.

F -18 mCi 2.05 E+00 1.39 E+00 3.94.E-01 5.74 E-01 3.73 E-01 Fe-59 mCi 1.61 E-01 (<1.0 E-07) (<8.2 E-08) (<9. 8 E-08) 9.0 E-02 1.05 E+00 I -131 mCi 1.66 E+00 3.46 E+00 9.23 E-01 1.25 E+00 <8.4 E-08 2.62 E I -132 mCi 87 E- 1.93 E-01 1.51 E-01 I -133 mCi 1.30 E+00 2.38 E&0 1.54 E+00 1.33 E+00 1.15 I -134 mCi 2.64 E-01 I- 135 mCi 5.28 E-Ol 1.42 E-01 La-140 2.66 E-Ol (<4.1 E-07) (<1.3 E-07) (<1.8 E-07) (<1.2 E-07 <5. 1 E-08 Mn-54 mCi 1.72 E-01 9.86 E-02 1.77 E-02 1.05 E-01 7.02 E-01 8.51 E-01 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/m1.

e '

APPENDIX YEAR 1981 II NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEHIANNUAL OPERATING REPORT Page 3 ',

TABLE I Rep'oct of Radioactive EEEueuts: Liquid - Total (ceeeieeed)

Isoto e Un Jul Au ust Se tember October November Decem er..

Na-24 mCi 2.87 E-01 2.26 E- 1 Nb-95 mCi 8.22 E-02 3.31 E-02 (<3.9 E-08) (<5.0 E-08) 6.0 E-01 2.54 Sb-124 mCi 3.01 E-02 5.2 E-08 <3.3 E-08 <4 7 E-08 Sb-125 mCi (<1.5 E-07) (<1.7 E-07) (<9.1 E-08) (<1.4 E-07), (<1.8 E-08) 1.11 E Sr-89 mCi 1.39 E-01 5.8 E-01 4.6 E-01 1.46 E-01 6.1 E-02 1.8 E+00 mCi 1.19 E-02 7.1 E-03 (<6.5 E-09) (<5.4 E-09 (<5.0 E-09) (<5. 6 E-09)

Zn-6 mCi (<1.1 E-07) (<1. 1 E-..07) (<8.4 E-08) (<9.3 E-08) 2.38 E-01 (<2.2 E-07)

Zr-95. mCi (<8.1 E-08) (<7.6 E-08) (<6 . 2 E-08) (<8.3 E-08) 3.93 E-01 8.80'-01 Zr-97 mCi 1.01 x+00 Total mCi 1.90 E+Ol 1.68 E+Ol 8.89 E&0 1.76 E+Ol 3.94 E+01 1.04 E+02 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

~ ~

NUCLEAR CllENISTRJ PROCEDURE HC-3 APPENDIX II PREPARATION OF. THE HONTllLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE Page 4 YEAR~a "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEHIANNUAL OPERATING REPORT TMLE I Report of Radioactive Efflveo~s: iqvid -.Haste Disposal System Isoto e Un t Jul August Sep tember October November December Ag-110m mCi (<5.9 E-08) (<5 .3 E-08) .(<3.7 E-08) (<4.7 E-08) 1.37 E-01 1.73 E+00 Ba-140 mCi (<2.8 E-07) (<3.0 E-07) (<1.6 E-07) (<3.0 E-07) (<3.9 E-07) (<6.7 mCi

(<2.9 E-08) (<3.2 E-08) (<1.8'-08) (<2.8 E-08) 1.4 E-02 (<6.6 E- 8)

Co-58 mCi 1.54 E+00 6.78 E-01 2.44 E-01 2.94 E+00 1.39 E+01 3.67 Co-60 mCi 2 E+00 5.95 E+00 9.03 E+00 Cr-5 <4.2 E-07 <4.2 E-07 <2.5 E-07) (<4.2 E-07) 3.15 E+00 1.42 E+01 Cs-134 mCi 8.01 H-01 7.46 E-.ol 1.60 E-Ol 5.68 E-01 1-04 E+00 1.24 E-01 Cs-136 mCi 4.39 E-02 2.23 E-02 <6.7 E-08 <6.8 E-08) (<8.8 E-08) (<1.6 E-07)

Cs-137 mCi 1.73 E+00 1.17 E&0 3.55 E-01 8.39 E-01 1.60 E+00 4.28 E-01 1.61 E-01 (<1.0 E-07) (<8.2 E-08) (<9.8 E-08) 9.0 E-02 1.05 E+00 2.82 E-01 1.11 E-01 (<4.2 E-08) 2.8 E-02 (<8.4 E-08) , (<1. 6 E-07)

Z.a-140 mCi 2.66 E-01 <4.1 E-07 <1.3 E-07) (<1.8 E-07) (<1 2 E-07) (<5 1 Mn-54 mCi 1.72 E-01 9.86 E-02 1.77 E-02 1.05 E-01 7.02 E-01 8.51 E-0.1 Nb-95 mCi 8.22 E-02 3.19 E-02 (<3. 9 E-08) (<5.0 E-08) 6.0 E-01 2.54 Sb-124 mCi 3.01- E-02 (<5.2 E-08) (<3.3 E-08) (<4.7'-08) 1.71 E-'01 4;19 E+00 Sb-125 mCi (<1.5 E-07) (<1.7 E-07) (<9.1 E-08) (<1.4 E-07) (<1.8 E-08) 1.11 E+Ol Sr-89 mCi 3 E-Ol 26 E- 8 EWO Sr-90 mCi 1.19 E-"02 7.1 E-03 (<6.5 E-09) (<5.4 E-09) (<5 .0 E-09) (<5 .6 E-09)

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

4 E

gl

NUCLEAR CHENISTRY FiiOCEDURE NC-3 PPENDI X II PREPARATION OF. THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE YEAR 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT Pa'ge 5

TMLE I Report of Radioactive Effluen7sSiquid - Waste Disposal System ic0eaz<<eai Isoto e Un t Jul Au ust Se tember Oct Zn-65 (<1. 1 E-07) (<1.1 E-07) <8.4 E-08 <9.3 E-08 2.38 E-01 <2.2. E-07 Zr-95 (<8.1 E-08) (<7.6 E-08) (<6.2 E-08) (<8.3 E-08) 3.93 E-01 8.8 Zr-97 mCi 1.01 E+00 Total mCi 7.69 E+00 4.92 E+00 2.37 EWO 6.15 E+00 2.81 E+01 8.56 E+0 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

/

o

HUCLEM CHEHISTRY PROCEDURE NC-3 PPENDIX II PREPARATION OF TklE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND TkK EAR 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF TklE SEMIANNUAL OPERATING REPORT Page 6 TABLE I Report of Radioactive Efflu~en s: Liquid - Secondary System Isoto e Uns Jul August Sep tember October November 'ecember Co-58 mCi 7.2 E-03 7.8 E-02 8.5 E-03 1.1 E-01 Co-60 mCi 2.34 E&0 1.59 E+00 1.18 EWO 1.70 E+00 2.18 E-01 1.10 Cs-134 mCi 8.62 E-01 1.06 E+00 7.8 E-01 2.81 E+00 4.75 E+00 5.34 E+00 Cs-136 3.7'- 2 Cs-137 mCi 1.41 E+00 1.51 E+00 ~

1.20 E+00 3.46 E+00 6.37 E&0 7.30 E+00 F-18 mCi I-131 mCi 1.38 'E&0 3.35 EWO 9.23 E-01 1.22 E+00 2.62 E+00 I-132 mCi 8.7 E-01 2.47 E-01 1.93 E-01 1.51 E-01 I-133 mCi 1.30 E&0 2.38 E+00 1.54 E+00 1.33 E400 1.15 E+00 I-134 mCi 2.64 E-01 I-135 mCi Mn-54 mCi Na-24 mCi 2.87 E-01 7.9 E-02 2.26 E-01 Nb-95 . mCi 1.2 E-03 Sr-89 mCi 3.2 E-01 2.3 E-01 1.46 E-Ol Total 1.13 EWl 1.19 E+Ol 6.52 E+00 1.15 E+Ol 1.13 Et01 1.84 E+01 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

NUCLEAR CHEMISTRY PROCEDURE NC-3 PPENDI X 11 PREPARATION OF TKE MONTKLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND TKE Page -7 YEAR~~ "RADIOACTIVE EFFLUENT RELEASES" PORTION OF TKE SEMIANNUAL OPERATING REPORT TABLE I Report of Radtoacttve Ef~uen s: Liquid - Dissolved Gas Tota Jul Au ust Se tember Kr-85 mCi (<4.9 E-06) (<5.6 E-06 <9.7 E-06 <5.1 E-06 <43 E-6 Xe-131m mCi (<5. 3 E-07) 1. 30 .E+00 (<9.3 E-07) (<5.5 E-07) <4.6 E-07 <3. 2 Xe-133 1.07 E+00 3.32 EWO 1.99 E-01 1.54 E&0 <4.7 E-08 <2.1 E-07 Xe-133m mCi (<1.3 E-07) (<1.4 E-07) (<2.6 E-07) (<1.6 E-07) ( <1. 2 E-07) (<7.5 F 7)

Xe-135 (<1.8 E-08) (<2.4 E-08) (<4.2 E-08) 9.2 "E-02 (<1.4 E-08) ( <9 .5 E-08)

Haste D s osa S stem Kr-85 E-'0 <5.1 E-06 <4.3 E-06 <4 Xe-131m mCi (<5.3 E-07) 1.30 E+00 (<9.3 E-07) (<5.5 E-07 (<4.6 E-07 <3.2 E-06 Xe-133 1.07 EWO 3.32 E+00 1.99 E-01 (<3.8 E-08) (<4.7 E-O8) (<2.1. E-07)

Xe-133m mCi (<1.3 E-07) (<1'.4 E-07) (<2.6 E-07) (<1.6 E-O7) (<1.2 E-07) (<7.5 E-07)

Xe-135 mCi (<1.8 E-08) (<2.4 E-08) (<4.2 E-08) (<1.9 E-08) (<1.4 E-08) (<9.5 'E-08 S

Kr-85 Xe-131m mCi Xe-133 1.54 EWO Xe-133m mCi Xe-135 mCi 9.2 E-02 NOTE; Numbers in parentheses represent maximum sensitivity in AC)/ml.

J 5 ~ a t

nul LtnlrvnlUvl~al~l> i ul n APPENDIX III PREPARATION OF TflE MONTHLY "PRELINIHARY REPORT ON RADIOACTIVE RELEASES" AND THE

'YEAR 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT Page- 1 TABLE II Report of Radioactive t Tuenta: Airborne

. Fssslon an ctlvatson Gases

1. Total Release Ci 4.13 E+02 2.55 E+02 1.34.E+02 8.56 E+02 3.87 E+02 3.03 E+02

2. Av Release Rate for Period Ci sec 1.7" E+02 8.5 E+01 5.5 EWl 3.5 E+02 1.3 E+02 1. 2

• 3. Max Release Rate for period Ci/sec 3 0 E+04 2 ~3 E+04 1. 3 E+04 1. 7 E+04 5 .6 E+02 2. 1 E+03

• Haxsmum a>r orne re ease rate average over one our or eac mont . Tec n ca Spec cat ons mit s 6-7 EK4 pC se averaged over one hour.

B. Io ne - 131

1. Total Iodine - 131 5.9 E-03 1.2 E-03 1.6 E-04 1.7 E-03 1.6 E-03 5.4 E-04

2. Av Release Rate for Period . Ci/sec 2.4 E-03 4.0 E-04 6.6 E-05 7.0 E-04 5. 3 E-04 2.2 E-04 C. Part cu ates

1. Particulates with t 1/ >8 days 2.51 E-04 5.8 E-05 2.0 E-04 4.2 E-05 1.64 E-04 1.9 E-04

2. Av Release Rate for period Ci/sec 1.0 E-04 1.9 E-05 8.3 E-05 1.7 E-05 5.4 E-05 7.9 E-05

3. Gross Al ha Radioactivit 1.7 E-09 7.4 E-09 (<2.5 E-12) (<3.2 E-09 1.4 E-08 1.2 E-08 D. Tr t um

1. Total Release Ci 5. 76 E-02 3.58 E-02 3 E-0

2. Av Release Rate for period Ci/sec 2.38 E-02 1.2 E-02 1.6 E-02 9.9 E-03 0.0 E+00 1.4 E-02 E. Percen o ca e sm

1. Fission and Activation Gases 8.5 E-01 1.6 E+00

2. I-131 and Part tl/2>8d 9.3 E-02 4.9 E-02 NOTE: Num ers n paren eses represent max mum sens t v y n pC m .

~

I

~

• NUCLM CHEHISTRY PROCEDURE NC-3 APPENDIX III PREPARATION OF THE MONTHLY "PRELIMINARY.REPORT ON RADIOACTIVE RELEASES" AND THE Page 2 YEAR 1981 "RADIOACTIVE EFFLUENT RELEASES" POR'TION OF THE SEHIANNUAL OPERATING REPORT TABLE II Airborne Releases - Particulates Isoto e Un t Jul Au ust Se tember October November ecem er Ba-140 1.6 E-05 (<1.6 E-13) <2.0 E-13) (<1.6 E-13) (<1.5 E-13) (<3.0 E-13)

Co-57 Ci (<1.5 E-14) (<1.6 E-14) (<1.7 E-14) (<1.4 E-14) ( <1.4 E-14)

Co-58 Ci 7.2 E-05 5.3 E-06 1.0 E-04 1.8 E-05 6.6 E-05 1.7 E-05 Co-60 5.1 E-05 3.5 E-05 8.5 E-05 . 1.2 E-05 4.4 E-05 1.4 E-04 Cr-51 (<2.4 E-13) (<2.8 E-13) (<2.4 E-13) (<2.2 .E-13) 9.4 E-06 (<4. 2 E-13)

Cs-134 Ci 2.5 E-05 3.8 E-06 4.1 E-06 2.7 E-06 1.2 E-05 7.1 E-06 Cs-136 . 2. 7 E-06 (<6.4 E-14) (<8.5 E-14) (<6. 4 E-14) (<6.4 E-14) (<1. 9 E-13)

Cs-137 Ci 3.7 E-05 1.3 E-05 7.0 E-06 6.1 E-06 2.4 E-05 2.1'-05 I -131 Ci 1.6 E-05 9;6 E-07 (<3.3 E-14) 1.9 E-06 1.3 E-06 (<5.4 E-14)

Ci 1.3 E-05 (<5.4 E-14) (<2. 8 E-14) (<3.4 E-14) (<3.9 E-14) (<6.9 E-14)

La-1 0 Ci 1.5 E-05 (<7.0 E-14) 1.1 E-06 (<4.8 E-14) 3.6 E-06 1.1 E-06 Mn-54

(<4.6 E-14) (<5. 5 E-14) (<6.1 E-14) (<4.3 E-14) 2.0 E-06 (<1.0 3)

Nb-95 Ci Sr-89 Cj 2.9 E-06 1.9 E-07 1.8 E-07 1.3 E-06 1.2 E-06 1.5 .E-06 Sr-90 Cj 1.4 E-07 3. 1 E-08 1.2 E-08 7.0 E-08 4.8 E-08 1.6 Total Ci 2.51 E-04 5.8 E-05 2;0 E-04 4.2 '-05 1.64 E-04 1.9 E-04 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

~ ~

NUCLEAR CHEMISTRY PROCEDURE NC-3 PPENDIX III PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE EAR 1981 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SENIANNUAL OPERATING REPORT Page 3 TABLE II N rborne Pee eases - Gaseous Floss on an Act vat on Gases Isoto e Un>t July August September October November December Ar-41 Ci 1.63 E&l 4.14 E+00 4.87 E+00 6.86 E-01 1.6 Kr-85 6.8 E-02 1.76 E-01 (-<9.0 E-05) 1.68 E-Ol (<8.2 Kr-85m 5.93 E-02 1.44 E-01 7.8 E-02 3.78 E-02 1.1 E-02 Kr-87 (< 2.6 E-06) ( <1.0 E-05) 9.3 E-03 4.36 E-02 (<8.2 )

Kr-88 3.22 E-02 1.38 E-Ol 6.14 E-02 (<9.7 E-06) ( <8. 4 E-07)

Xe-131m Ci 1.36 EWO 1.25 E+00 7.70 E-01 1.46 E+00 ( <8.9 E-06)

Xe-133 3.93 E+02 2.45 I+02 1.26 E+02 8.52 E+02 3.87 E+02 3.02 EW2 Xe-133m 1.36 EWO 1.53 E&0 1.15 E+00 8.00 E-01 4.08 E-01 Xe-135 . Ci 9.01 E-01 2.86 E+00 1.26 E+00 6.51 E-01 2.50 E-01 Xe-135m 2.44 E-02 7.78 E-02 8.2 E-02 5.95 E-02 ( <3. 2 E-06)

Xe-138 Ci (<6.6 E-06) ( <4. 2 E-05) (<6.2 E-06) ( <l. 7 E-05) (<6.0 E-06)

Total E+02 8 E 2 3.87 E+02 3.03 E+02 Halo ens Gaseous Isoto e Un t July August September October November Dece I-131 5.9 E-03 1.2 E-03 1.6 E-04 1.7 E-03 1.6 E-03 5.4 E-04 I-133 1.1 E-03 4.6 E-04 1.9 E-04 1.4 E-03 (<4.3 E-14) 5. 2 E-04 I-135 2.3 E-04 2.4. E-04 1.0 E-04 (<9.7 E-14) (<1.9 E-13) 7.0 E-06 Br-82 6.6 E-04 5. 2 E-04 1.7 E-04 4.8 E-04 (<6.8 E-14) 1.2 E-04 Total 7.9 E-03 2.4 E-03 . 6.2 E-04 3.6 E-03 1.6 E-03 1.19 E-03 Note: um ers n paren eses represen max>mum sens v y ln p i m .

r l t

RADLOACTIVE WASTE REPOP.T July I, 1981, through December 3 I, 198 1 DATE OF SI)XPMENT CIJRIES CU. FT. DLSPOSITXO)i 7/07/8 I 0.00) 24 525 Buried in Barnwell, S.C.

7/09/8 I 0.00105 532.5 Richland, Ha.

7/09/8 I 0.00800 517.5 7/ )4/8 I 0.0064 I 525 Barnwell, S.C.

7/16/81 0.002485 540 Richland, Ha.

7/16/81 0.00129 540 ll 7/2i/81 0.00927 525 Barnwell, S.C ~

7/23/8 I 0.04716 765 Richland, Ha.

7/28/81 0.09351 1050 Barnwell, S.C.

7/30/81 0. 04960 1050 Richland, Wa.

0.09)88 II II 7/30/8) 1050 8/04/81 0.10920 1050 Barnwell, S.C.

8/10/8 I 0.51455 170 8/11/81 0.59200 150 8/12/81 2:<<'20000 170 8/13/8) 0.88400 170 8/25/81 0.04072 1050 8/28/81 2.38000 170 9/14/81 0.13200 1050 9/21/81 2.77000 200 9/23/8 I 0.21000 170 9/26/8 I 0.45600 170 9/28/8 I 10'17000 200 .

9/30/81 0.069195 1050 Richland, Ha.

II 9/30/81 0 ~ 18513 1050 10/05/8] 2.28000 170 Barnwell, S.C.

10/07/81 0.76100 170 IO/09/81 0.95200 170 10/13/81 0.05990 1050 Richland, Ha.

10/13/81 1.23000 85 Barnwell, S.C.

10/15/8 I 1.38600 85 io/i9/s 1 1.08000 85 10/20/81 0.06010 1050 Richland, Ha.

10/21/81 0.92400 85 Barnwell, S.C ~

tl 10/27/81 1.85000 200 10/29/81 0.23398 1050 Richland, Ma.

11/04/81 0,.)74765 1050 Barnwell, S.C.

II II 11/10/81 1.85000 200 11/17/81 0.09200 200 12/04/8 I '.24600 1050 Richland, Va.

12/08/sl 0. )9500 1050 Barnwell, S.C.

ll II 12/14/8) 0.61600 85 12/)7/81 1.23200 85 II 11 12/19/81 0.92400 85 12/09/81 0.26870 1100 Richland, Ha ~

II 12/IO/Sl 0.25200 1050 12/10/81 0. 14800 1050 12/29/81 0. 17100 1050 12/31/81 0.30640 1050 49 Shipments 38:317 27,745 site <<s'f.

On

. Januar, I, 1982 5.376 3, 148

RADIOLOGICAL fNVIRONMENTAL MONITORING REPORT TURKEY POINT UNITS 3 5 4 DOCKET NOS. 50-250, 251-DADE COUNTY, FLORIDA 7-1-81 TO 12-31-81 PREPARED 2/ll/82

~ ~

cg" v t' nr

.< ~

I I!

1. INTRODUCTION This report is submitted pursuant to Section 6.9 of the Turkey Point Plant Units 3 5 4 Technical Specifications.

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, 1981 through December 31, 1981 is provided in Table 1.

2. THE MONITORING PROGRAM Period Covered: This report covers the period from July 1, 1981 through December 31, 1981.

Analytical Respon'sibility: Environmental radiological monitoring for the Turkey Point Plant is conducted by the State of Florida, Department of Health and Rehabilitative Services (DHRS). All samples are collected and analyzed by DHRS personnel.

Number of Sam les: During the period, a total of 708 samples were collected from 35 different 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 control location and for sample locations which yielded the highest

4 t ~-

<<C>>

0t'<<f<<M . (.If<<

1 ~

0 ~ I 1 M!

1 <<~

mean levels. The values in Table 1 are based upon only those analyses which yielded detectable measurements. The numbers of samples which yielded detectable measurements compared to the total numbers of samples collected are also indicated.

p 1 1 . >> - 8 samples were collected for comparative analysis by the DOE in accordance with the DHRS/DOE split-sampling program.

p1 1 1 89 1 sample media were not available to be included with this report. When received these results will be transmitted in a supplemental report. In addition, one direct radiation measurement, two precipitation samples, and the semi-annual small animal specimen were not obtained. Based upon the results that were obtained during this period, as well as the historical data for Turkey Point 3 8 4, the missing data is not expected to alter any of the conclusions of this report. Nore detailed information concerning delayed or missing data is contained in Table lA.

Change in Sam le Location: Due to r epeated acts of vandalism, the sample station identified as Location T-57, Dolan's Farm, was moved approximately 200 yards to the southeast to a protected area. The NRC was notified prior to moving the sample station.

I N V t I

WC

>> tt V t '.>> II, V

VII>> ..'5v>><<

C t

I" %1

" N lt "I VII II ~ >, "II I

'V ~ I t Pt Vf t'I'NVNtt '*[ IIN, t .>>

V Hi Iglt u V N>>. VV I ~ <<N ~ I t ' Ut I It>>

>> N I'>>

VNV>>

V

3. Discussion and Interpretation of Data for gross beta particulates in air are down significantly from the levels which were reported during the previous two surveillance periods.

Generally higher than normal levels for gross beta particulates in air were observed from November 1980 through May 1981. These observations were not a result of operation of the Turkey Point Nuclear units. The levels for gross beta particulates in air during this period are comparable to the levels considered normal for the local environment.

There continues to be no measurable levels of I-131 in any of the air samples around the Turkey Point Plant.

Direct Radiation Monitori n  : An anomolous exposure rate reading was obtained from the dosimeters (TLD's) located at the Florida City Substation (7 miles West) during the period 8/6/81 to 9/6/81. The reading which was obtained is considered to be approximately twice normal and is statistically above the mean value of all of the other dosimeter readings representing the same period. Upon finding the anomalous reading, a very sensitive gamma instrument was dispatched to the Florida City Substation. All readings were confirmed to be normal. Data on plant releases was reviewed along with other environmental surveillance data.

It was concluded that the anomalous reading was not related to effluents from the Turkey Point nuclear units. At least two other feasible explanations were offered. These are as follows:

The TLD's might not have been zeroed prior to being deployed.

4 'I Ifl 4" 'I 44 I

PF

~, K

~ . ~ 'I I I glff<< " f K

II >>4 44 lf 4 4

4 4

f>> f ~ f "l f KF' l o '"

P 4 I>> 4 Jill I 'I fl 44

~ C 4 I'

~ P<<~r t 4' ft, *t 4 I I'I 4 I t f II ilk II flf' 4~ I I4,4 II If II, 4 II *44 4 ~ ll I

A radiation source may have tempo arily been in the vicinity of the Florida City Substation long enough to influence the dosimeter reading.

k t

units, small quantities of radioactivity are periodically released into the closed facility cooling system. As a result tritium is detectable in cooling canal surface water samples. Because there is some ground water interchange, tritium may also be detectable in ground water monitoring'ells located adjacent to the cooling canal system. As indicated in Table 1, the highest concentration measured during this surveillance period was a cooling canal system water sample. The tritium level was 5100 pCi/1.

This level of tritium is equal to only 0.2g, of the allowable limit for tritium in water in unrestricted areas. In fact, this amount of triti um is only about 25$ of that allowable in drinking water . No other radioi sotopes which could be attributed to the operation of the Turkey Point nuclear units were detected in water samples from the cooling canal system or envi ronment surrounding the Turkey Point Plant.

Other Environmental Sam les: As indicated in Table 1, detectable measurements for 60Co were reported for the cooling canal bottom sediment shnples and in a sample of sponge collected at Elliot Key (10 miles-NE). These levels are very low and are consistent with past measurements.

I a I

t rh c

'l It'

~

N rlt c a I I ',I (

It V t C

%IV a II r 'q4 a V,a I c ~

II F

M VJC qf I ~ a It tl ff t

'l,

$ Vt. a I

a, 'la c (a Il a

Measurements of radionuclides and/or radioactivity ,for all other environmental samples provided in Table 1 are consistent with levels which were measured during the preoperational environmental surveillance program.

4. Conclusions Operation of the Turkey Point nuclear units is not contributing significantly to the presence or buildup of radioactivity in the environment around the Turkey Point Plant. Oper ation of the Turkey Point nuclear units is not contributing significantly to the exposure of any individual or population group or to any radiological consequence involving the health or safety of any individual or population group. The concentrations of any radionuclides reported in Table 1 are much less than that permitted for those r adionuclides in unr estricted areas as provided in 10CFR20, Appendix B.

V Cps

,4 sd,

TAULE 1 ENVIRONHENTAL RADIOLOGICAL HONITORING PROGRAH SUHHARY NAME OF FACILITY TURKEY POINT PLANT UNITS 3 6 4 DOCKET NO. b0-250, 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD dULY 1 1981 - DECEH8ER 31 .1981 =

All Indicator Location with Nighest Hean Control ) No. of Number of Locations Location Nonruutine Hedium or Pathway Analysis Sample Location Reported Unit for Sites les Ana~lses Hean1) Ran e Distance 5 Direction Hean1) Ran e ) Hean ) Na~n e > tkasurene Sam led Sam 1.1 AIR 432

1. Particulates pCi/m Gross B 216 ) 216 .OZ8 .00b- l58-Entrance Road on .031 .008- .UBU .UxZ-(216/216) .123 Site (1 Hile-WSW) (27/27) .123 (27/27) .l09

2. Radioiodine pCi/m3 1311 216 ) 216 ND 1.2 DIRECT RADIATION 1306)

1. TLD Rem/hr Exposure 130 130 4.7 2.3- T5Z-Fla City Sub- b.8 4.0- b.5 4.7-Rate (130/130) 9.2 station (7 miles-W) (6/6) 9.2 (e/6) e:6 1.3 PRECIPITATION 236)

1. Rainwater pCi/1 Gross B-DS 23 4.2 3.0- T52-Florida City Sub- 4.8 3.0- 3 ' d,l-(8/23) 10.1 station (7 Hiles-W) (4/6) 10.1 (2/4) 3.4 Gross B-UO 23 3.2 T57-Dolan's Farm 3.2 NU (1/23) (4 Hiles-NW) (1/6)

Tritium 23 340 210- T5Z-Florida City Sub- 410 ND (2/23) 470 station (7 Hi les-W) (1/6)

Y -emitting 23 ND ) NA =NA isotopes S - Dissolved Solids UDS - Undis olved Solids ND - Non Detect ble NA - Not plicabl

~ ~ ~

\

~, ~,

~ ~

~ I ~, I ~ . ~

~

' ~

~ I ~

~

t I ' I ~ I I ~

I ~

~ ~

I I ~ ~

~ ~ I

~

~ ~

TABLE 1 ENVIRONMEliTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

NAME OF FACILITY TURKEY PDINT PLANT UNITS 3 6 4 DOCKEl'O. 50-25~0251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD dULY I 1981 - DECDIGER 31 1981 All Indicator Location with Nighest Mean ontrol2> No, ot Number of Locations ocation Nonrouti Medium or Pathway Analysis ample Location Reports Unit for Sites les Anal ses Mean ) Ran e1 Distance 6 Direction Mean ) Ran e ) M anL) Ran e ) HeasuremE:

5~am led Sam 2.2 MELLS 9 18

1. Potable Mell 3 6 Nater Drinking pci/1 Gross 8-D 7.3 4.4- T57-Dolan's Farm . LUUL 791-139 Nater (5/6) 13.0 (4 Msies-NX) ~

(2/2)

Gross B-DS ND NA N Tritium ND NA

2. Ground Mater 12 Ground Mater pCi/1 Tritium 12 L130 290- T90-Groundwater Neil 2bu0 Wells (7/12) 2600 E-20 (6 Miles -SSE) (1/2) 99 YU "9Sr 12 'N NA NA 90Sr 12 N N N Y emitting 12 ND4) NA N N isotopes FA j

9 14

TABLE 1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUMHARY NAME OF FACILITY TURKEY POINT PLANT UNITS 3 5 4 DOCKET NU. bU-250~2bl LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY 1 1981 - OECEHBER 31 .198i All Indicator Location with Highest Mean Contrul2) No, ut Number of Locations Location Nonruut>

Hedium or Pathway Analysis Sample Location Report Unit for ites Samples Anal ses Mean ) Ran e Distance G Direct>on Heanl) Ran e1) Heanl) Nan e') Heasur

~Sam l ed 3.0 BOTTOM SEDIHENTS 9

1. Cooling Canal 2 Bottom pCi/kg Sr 23)

Sediments 90Sr 23)

Y emitting 4 isotopes 1 ~ 60Co 31U 90- T84-Cooling canal 42U 2bU- NA (3/4) 580 South of bridge (2/2)

(0 Miles - SW7 Z. 95Zr 230 T85-Cooling canal 230 (1/4) West of 90'end il/2)

(0 Miles - SW) ~

ND4') NA NA

3. Others NA

2. Estuarine Bottom pCi/kg Sr Sediments N 90Sr ND Y emitting isotopes

1. >>Zr 7U bU-70 I'69-Elliott Key 7U (2/7) (7 Miles-ESE) (I/IJ

2. Others ND4) NA NA

o -

TABLt 1 ENVIRONMENIAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

NAME OF FACILITY TURKEY POINT PLANT UNITS 3 6 4 . DOCKET NU,bU-25U~25L LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY 1 lgul -'ECEMBER 31 198l All Indicator Location with Highest Mean <<ontroi2) Nu. ut Number of Locations Location Nonruutl Analysis Sample Location Keporte Medium or Pathway el) el)

Un1t for Sites Sam les Anal ses Meanl) Ran el Distance 6 Direction Meanl) Ran Meanl) Ran Measure Sampled 4.0 A)VATIC BIOTA 9 33

l. Crustacea 6 7 89Sr 63)

(Blue Crab, pC1/kg Horseshoe Crab

'"Sr 63)

Y Emitting 7 ND4) isotopes

2. Fish. Carnivore 8')

89Sr U3)

(Mixed Spec1es) pCi/kg N 9OSr O3)

Y emitting isotopes

1. 1 7CQ 50 (1/6)

2. Other ND4)

3. F1sh, Herbivore (Mullet) pC1/kg 89Sr w 9OSr N Y emitting ND4) isotopes

o TABLE 1 ENVIRONHENTAL RADIOLOGICAL HONITORING PROGRAH SUHHARY NAHE OF FACILITY TURKEY POINT PLANT UNITS 3 6 4 DOCKET NU. 5U-2bU~ 2bl LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY 1 1981 - DECEHBER 31 198L All Indicator Location with Highest Hean Cuntrol2) No. of Number of Locations Locat>on Nonruur.i edium or Pattway Analysis Sample Location Keporte Hean1) Distance 6.Direction Hean ) Ran e ) Hean ) Kan e ) Heasur Sam led Unit for Sites Sam les Anal ses Ran e

4. Turtle Grass 89Sr 53)

Turtle Grass pCi/kg 9OSr

'Y emitting 53) 6 ND ND 0

isotopes

1. "Zr 240 130- T59-El liott Key 32U (5/6) 320 (10 Hiles-NE) (I/1)

2. Other NO4) NA NA

5. Sponges Sponge Y emitting isotopes

1. 95Zr 860 7U- T94-Pumpkin Key lbUU pCi/kg (5/6) 1500 (8 Hiles-SSE) (1/1).

2 144Ce 3600 NA T59-Elliott Key BbUU NA (1/6) (10 Hiles-NE) (I/I) 3 60Co 70 T59-Elliott Key 7U NA NA (1/6) (10 Hiles-NE) (1/1) 4 106Ru 550 360- T93-Pelican Bank b9U (3/6) , 590 (1.5 Hi les-E) (1/1)

5. Others ND4) NA NA

~ 0 Iy ll

TABLE 1 ENVIRONMENTAL RADIOLOGICAL HONITORING PROGRAM

SUMMARY

NAME OF FACILITY TURKEY POINT PLANT UNITS 3 h 4 DOCKET NO. bU-ZSU, 251 LOCATION OF FACILITY DADE COUNTY FLORIDA REPORTING PERIOD JULY L LWBl - DECEMBER 31 Igul All Indicator Location with Nighest Mean ControlZ) 'Nu. ot Number of Locations Locat>un Nonrout>ne Medium or Patt+ay Analysis Sample Location Reports Sam led Unit for Sites Sam les Anal ses Hean1) Ran e Distance 5 Direct>on Mean ) Ran e ) Wan ) Ran eI) Heasur 5,0 TERRESTREAL 12 17

1. Small Animal 1 06)

2. Food Crops (Corn, Potatoes) pCi/kg 89Sr N 90Sr Y emitting 3 N04) isotopes

3. Vegetation (Hangrove Leaves pCi/kg O'Sr 43)

EE 90Sr 43)

Y emitting 7 isotopes

1. 9'Zr 190 110- T64-Natoma Substation 27U 27U (5/7) 270 (22 Miles-N) Control (1/1) LI/I)

Sample Location

2. Others ND4) NA

4. Ground Samples Soil pCi/kg 89Sr 63) ND 55 90Sr 63) ND Y emitting 7 iostopes 137Cs 170 80- T56-Princeton Sub- 29U (5/7) 290 station(8 Miles-WNW) (I/I)

2. "Zr ZZU- T56-Princeton Sub- 290 (z5) 290 station(8 Hs les-WNW) (I/I)

3. Otners ND4) . NA NA NA

~ ~

TABLE 1 NOTES

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

Numbers in parentheses indicate the ratio of analyses which yielded detectable results to the total number of analyses performed for that medium.

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

3. Some analyses incomplete Refer to Table 1A.

4. E~r doing.Potassium - 40 (40K). Radon - 226 ( 6Ra) and Thorium - 232

( Th) which are naturally occurring radioisotopes detectable in many, environmental specimens.

Does not include split samples analyzed by DOE.

6. Refer to Taole 1A for explanation of missing data.-

0 4

I

TABLE 1 A

~ ~

Radiological Environmental Monitoring Report Delayed or Missing Data I..- Delayed Results \

Due to incomplete analyses, results for the following 8 Sr, Sr samples could not be included in this report.

Medium or Analysis Reason for Pathwa Sam led For Location/Date

1. Surface Water, 9Sr, Sr T66/11-19-81 Analyses incomplete T81/11-19-81 T84/12-03-81 II II T97/12-03-81

2. Bottom Sediment 89Sr 90Sr T84/10-16-81 Analyses incomplete ll ll

.T85/10-29-81

3. Crustacea Sr, Sr T81/12-17-81 Analyses incomplete

4. Fish, Carnivore 89Sr 90Sr T81/12-17-81 Analyses incomp'lete TU4/12-17-81 T59/09-24-81 T66/09-24-81 T69/09-24-81 T84/09-28-81 T94/09-24-81 T95/09-24-81

.5. Turtle Grass 89Sr 90Sr T81/11-19-81 Analyses incomplete

6. Food Crop (Potatoes) 89Sr, 90Sr. f52/09/25-81 Analyses incomplete II II II II II I I T57/12-17-81 ~ ~

7. Mangrove Leaves 8"Sr, 9"Sr T71/09-30-81 Analyses incompl'ete T72/09-30-81 T51/10-29-81.

T86/10-29-81

8. Soi l ""Sr, Sr T52/09-25-81 Analyses incompl ete

~ 0 e

II.. Nissing Data Nedium or Analysis Location Reason for Path@a~ Date Del a

1. TLD Exposure Rate T78/7-16-81 Laboratory error-This location not required by Technical Specifications

2. Precipitation Table 4-12-1 T64/12-81 'Sample apparatus (1.3) found dismantled T64/8-81 Sample apparatus found dismantled Small Animal Tabl e 4-12-1 T/58 All attempts to (5.2.1) collect sample were

- unsuccessful

~ ~ ~

'\

4($

'@. BOX 14000, JUNO BEE~, Pa+3408 41 4'/'LORIDA POWER 8( LIGHT CQ1UIQPNY-August 31, 1982 L-82-379 Mr. James P. O'Reilly Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101.Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Mr. 0.'Rei lly:

Re: Turkey Point U 3 5 4 0ocket Nos. 0-25 and 50-251 Radiolo ical ronmental Monitorin Re ort Please find attached our Radiological Environmental Monitoring Report and Report of Radioactive Effluent Releases for the period of January, 1982 to June, 1982. This is submitted in accordance with Technical Specification 6.9.4.

'ery truly yours, Robert E. Uhrig Vice President Advanced Systems 8 Technology REU/JEM/mbd Attachment cc,: Harold F. Reis, Esquire PEOPLE... SERVING PEOPLE

h