ML17345B325

Radioactive Effluent Release Data,Jul-Dec 1981

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 LIGHTCOMPANY 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 I"

lh, f

I

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SEMIANNUALREPORT OF RADIOACTIVEEFFLUENT RELEA'SES PTP UNITS 3 R 0 7/81-12/81 Introduction Allliquid 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 willaid 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. Activitythat 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.

Allnon-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.

Allconcentrations 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 limitfor 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 Allsporadic 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 willaid 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 limitfor release of total radioactive materials in gaseous waste is 0.012 Ci/sec when averaged over the calendar quarter.

The percent ofthe 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 limitfor 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 limitfor 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 willbe listed as ().

0 Vy cg

PPENDIX II EAR 1981 HUVLtBH q HtNliiKi 1'HVUKUVNt Al -8 PREPARATION OF THE HONTElLY "PRELIHINARY REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF'TllE SEHIANNUAL OPERATING REPORT TABLE I Repons of lladioactttve E "fluents:

Liquid Page 1

A. Gross Radsoact vent g-5

1. Total Release Jul Au ust Se m r mC1 0 E 68E+Ol 8 8 E

v m

m r

. 2.

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

5. Percent of Technlca Spec cat on Limit for Total Activit Released Ci/ml 2.6 E-09 2.4 E-09 7.9 E-10 8.9 E-01 6.8 E-09 1.5 E-08 2.8 E-08 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 C.

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 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)

D.

E.

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)

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)

Volumes 1.

Vol of Li uid Waste to Dischar e

Liters

2. Vol of Dilution Mater Durin Rel.

Liters 3.

Vol of Dilution Mater for Honth 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 1.55 E+11 2.05 E+11 1.83 E+11 1.33 E+ll 1.05 E+ll 1.85 E+ll 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

APPENDIX II YEAR 1981 NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF T)IE MONTHLY "PRELIHINARY REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEHIANNUAL OPERATING REPORT TMLE I Repovt of Radioactive EEEueota:

Liquid - Total Page 2

Isoto e

Ag-110m aa-140 un t mCi

(<5.9 E-08) mCi

(<2.8 E-07)

(<5.3 E-08)

(<3.0 E-07)

Se tember

( <3. 7 E-08)

(<1.6 E-07)

Oc o

(<4.7 E-08)

(<3.0 E-07) 1.37 E-01

(<3.9 E-07) 1.73 E

(<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 Co-60 Cs-134 mCi mCi mCi 1.54 EWO 4.77 E+00

(<4.2 E-07) 1.66 E+00 6.85 E-01 3.39 E+00

(<4.2 E-07) 1.81 E+00 3.22 E-01 2.54 E+00

(<2.5 E-07) 9.4 E-01

. 2.49 E+00 3.82 E+00

(<4.2 E-07) 3.38 E+00 l.39 E+O1 6.17 E+00 3.15 E+00 5.79 E+00 3.68 E

1.01 EWl 1.42 E+01 5.46 E+00 Cs-136's-137 F -18 Fe-59 I -131 I -132 I -133 I -134 I-135 La-140 Mn-54 mCi mCi mCi mCi mCi mCi mCi mCi mCi 3.14 E+00 2.05 E+00 1.61 E-01 1.66 E+00 87 E-1.30 E+00 2.64 E-01 5.28 E-Ol 2.66 E-Ol 1.72 E-01 2.23 E-02 2.68 E+00 1.39 E+00

(<1.0 E-07) 3.46 E+00 2.38 E&0

(<4.1 E-07) 9.86 E-02

<6.7 E-08 1.56 E&0 3.94.E-01

(<8.2 E-08) 9.23 E-01 1.93 E-01 1.54 E+00

(<1.3 E-07) 1.77 E-02

<6.8 E-08 4.30 E&0 5.74 E-01

(<9. 8 E-08) 1.25 E+00 1.51 E-01 1.33 E+00

(<1.8 E-07) 1.05 E-01

<8.8 E-08 7.97 E&0 9.0 E-02

<8.4 E-08

(<1.2 E-07 7.02 E-01 3.7 E-02 7.73 E&0.

3.73 E-01 1.05 E+00 2.62 E

1.15 1.42 E-01

<5. 1 E-08 8.51 E-01 NOTE:

Numbers in parentheses represent maximum sensitivity in pCi/m1.

e

APPENDIX II YEAR 1981 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 TABLE I Rep'oct of Radioactive EEEueuts:

Liquid - Total (ceeeieeed)

Page 3',

Isoto e

Na-24 Un mCi Jul 2.87 E-01 Au ust Se tember October November Decem er..

2.26 E-1 Nb-95 Sb-124 Sb-125 mCi mCi mCi 8.22 E-02 3.01 E-02

(<1.5 E-07) 3.31 E-02 5.2 E-08

(<1.7 E-07)

(<3.9 E-08)

<3.3 E-08

(<9.1 E-08)

(<5.0 E-08)

<4 7

E-08 6.0 E-01

(<1.4 E-07),

(<1.8 E-08) 2.54 1.11 E

Sr-89 Zn-6 Zr-95.

mCi mCi mCi mCi 1.39 E-01 1.19 E-02

(<1.1 E-07)

(<8.1 E-08) 5.8 E-01 7.1 E-03

(<1. 1 E-..07)

(<7.6 E-08) 4.6 E-01

(<6.5 E-09)

(<8.4 E-08)

(<6. 2 E-08) 1.46 E-01

(<5.4 E-09

(<9.3 E-08)

(<8.3 E-08) 6.1 E-02

(<5.0 E-09) 2.38 E-01 3.93 E-01 1.8 E+00

(<5. 6 E-09)

(<2.2 E-07) 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.

~ ~

APPENDIX II YEAR~a NUCLEAR CllENISTRJ PROCEDURE HC-3 PREPARATION OF. THE HONTllLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEHIANNUAL OPERATING REPORT TMLE I Report of Radioactive Efflveo~s:

iqvid -.Haste Disposal System Page 4

Isoto e

Ag-110m Un t mCi Jul

(<5.9 E-08)

August Sep tember

(<5.3 E-08)

.(<3.7 E-08)

October

(<4.7 E-08)

November 1.37 E-01 December 1.73 E+00 Ba-140 mCi mCi

(<2.8 E-07)

(<2.9 E-08)

(<3.2 E-08)

(<1.8'-08)

(<3.0 E-07)

(<1.6 E-07)

(<2.8 E-08) 1.4 E-02

(<3.0 E-07)

(<3.9 E-07)

(<6.7

(<6.6 E-8)

Co-58 Co-60 mCi mCi 1.54 E+00 6.78 E-01 2.44 E-01 2.94 E+00 2 E+00 1.39 E+01 5.95 E+00 3.67 9.03 E+00 Cr-5 Cs-134 Cs-136 mCi mCi

<4.2 E-07 8.01 H-01 4.39 E-02

<4.2 E-07 7.46 E-.ol 2.23 E-02

<2.5 E-07) 1.60 E-Ol

<6.7 E-08

(<4.2 E-07) 5.68 E-01 3.15 E+00 1-04 E+00

<6.8 E-08)

(<8.8 E-08) 1.42 E+01 1.24 E-01

(<1.6 E-07)

Cs-137 mCi 1.73 E+00 1.61 E-01 2.82 E-01 1.17 E&0

(<1.0 E-07) 1.11 E-01 3.55 E-01

(<8.2 E-08)

(<4.2 E-08) 8.39 E-01

(<9.8 E-08) 2.8 E-02 1.60 E+00 9.0 E-02

(<8.4 E-08) 4.28 E-01 1.05 E+00

, (<1. 6 E-07)

Z.a-140 Mn-54 mCi mCi 2.66 E-01 1.72 E-01

<4.1 E-07 9.86 E-02

<1.3 E-07) 1.77 E-02 1.05 E-01 7.02 E-01

(<1.8 E-07)

(<1 2 E-07)

(<5 1 8.51 E-0.1 Nb-95 Sb-124 mCi mCi 8.22 E-02 3.01-E-02 3.19 E-02

(<5.2 E-08)

(<3. 9 E-08)

(<3.3 E-08)

(<5.0 E-08)

(<4.7'-08) 6.0 E-01 1.71 E-'01 2.54 4;19 E+00 Sb-125 Sr-89 Sr-90 mCi mCi mCi

(<1.5 E-07) 3 E-Ol 1.19 E-"02

(<1.7 E-07) 26 E-7.1 E-03

(<9.1 E-08)

(<6.5 E-09)

(<1.4 E-07)

(<1.8 E-08)

(<5.4 E-09)

(<5.0 E-09) 1.11 E+Ol 8

EWO

(<5.6 E-09)

NOTE:

Numbers in parentheses represent maximum sensitivity in pCi/ml.

4 E

gl

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

TMLE I Report of Radioactive Effluen7sSiquid - Waste Disposal System ic0eaz<<eai Pa'ge 5

Isoto e

Zn-65 Un t Jul

(<1. 1 E-07)

Au ust

(<1.1 E-07)

Se tember

<8.4 E-08 Oct

<9.3 E-08 2.38 E-01

<2.2.

E-07 Zr-95 Zr-97 mCi

(<8.1 E-08)

(<7.6 E-08)

(<6.2 E-08)

(<8.3 E-08) 3.93 E-01 8.8 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

/

PPENDIX II EAR 1981 HUCLEM CHEHISTRY PROCEDURE NC-3 PREPARATION OF TklE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND TkK "RADIOACTIVE EFFLUENT RELEASES" PORTION OF TklE SEMIANNUAL OPERATING REPORT TABLE I Report of Radioactive Efflu~en s:

Liquid - Secondary System Page 6

Isoto e

Co-58 Co-60 Cs-134 Cs-136 Cs-137 Uns mCi mCi mCi mCi Jul 2.34 E&0 8.62 E-01 1.41 E+00 August 7.2 E-03 1.59 E+00 1.06 E+00 1.51 E+00 Sep tember 7.8 E-02 1.18 EWO 7.8 E-01

~ 1.20 E+00 October 1.70 E+00 2.81 E+00 3.46 E+00 November 8.5 E-03 2.18 E-01 4.75 E+00 6.37 E&0

'ecember 1.1 E-01 1.10 5.34 E+00 3.7'-

2 7.30 E+00 F-18 I-131 I-132 I-133 I-134 I-135 Mn-54 Na-24 Nb-95 Sr-89 mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi 1.38 'E&0 8.7 E-01 1.30 E&0 2.64 E-01 2.87 E-01 3.35 EWO 2.47 E-01 2.38 E+00 1.2 E-03 3.2 E-01 9.23 E-01 1.93 E-01 1.54 E+00 2.3 E-01 1.22 E+00 1.51 E-01 1.33 E400 7.9 E-02 1.46 E-Ol 2.62 E+00 1.15 E+00 2.26 E-01 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.

PPENDI X 11 YEAR~~

NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF TKE MONTKLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND TKE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF TKE SEMIANNUAL OPERATING REPORT TABLE I Report of Radtoacttve Ef~uen s:

Liquid - Dissolved Gas Page -7 Tota Kr-85 Xe-131m Xe-133 mCi mCi Jul

(<4.9 E-06)

(<5. 3 E-07) 1.07 E+00 Au ust

(<5.6 E-06

1. 30.E+00 3.32 EWO Se tember

<9.7 E-06

(<9.3 E-07) 1.99 E-01

<5.1 E-06

(<5.5 E-07) 1.54 E&0

<43 E-6

<4.6 E-07

<4.7 E-08

<3. 2

<2.1 E-07 Xe-133m Xe-135 mCi

(<1.3 E-07)

(<1.8 E-08)

(<1.4 E-07)

(<2.6 E-07)

(<2.4 E-08)

(<4.2 E-08)

(<1.6 E-07) 9.2 "E-02

( <1. 2 E-07)

(<1.4 E-08)

(<7.5 F

7)

( <9.5 E-08)

Haste D s osa S stem Kr-85 Xe-131m Xe-133 Xe-133m Xe-135 S

mCi mCi mCi E-'0

(<5.3 E-07) 1.07 EWO

(<1.3 E-07)

(<1.8 E-08) 1.30 E+00 3.32 E+00

(<1'.4 E-07)

(<2.4 E-08)

(<9.3 E-07) 1.99 E-01

(<2.6 E-07)

(<4.2 E-08)

<5.1 E-06

(<5.5 E-07

(<3.8 E-08)

(<1.6 E-O7)

(<1.9 E-08)

<4.3 E-06

(<4.6 E-07

(<4.7 E-O8)

(<1.2 E-07)

(<1.4 E-08)

<4

<3.2 E-06

(<2.1. E-07)

(<7.5 E-07)

(<9.5

'E-08 Kr-85 Xe-131m Xe-133 Xe-133m Xe-135 NOTE; mCi mCi mCi Numbers in parentheses represent maximum sensitivity in AC)/ml.

1.54 EWO 9.2 E-02

J 5 ~

a t

APPENDIX III

'YEAR 1981 nul LtnlrvnlUvl~al~l>

i ul n

PREPARATION OF TflE MONTHLY "PRELINIHARY REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT TABLE II Report of Radioactive t Tuenta:

Airborne Page-1

. 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 2.

Av Release Rate for Period Ci/sec 5.9 E-03 2.4 E-03 1.2 E-03 4.0 E-04 1.6 E-04 6.6 E-05 1.7 E-03 1.6 E-03 7.0 E-04

5. 3 E-04 5.4 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 3.

Gross Al ha Radioactivit Ci/sec 1.0 E-04 1.7 E-09 1.9 E-05 7.4 E-09 8.3 E-05 1.7 E-05

(<2.5 E-12)

(<3.2 E-09 5.4 E-05 7.9 E-05 1.4 E-08 1.2 E-08 D. Tr t um

1. Total Release 2.

Av Release Rate for period Ci

5. 76 E-02 3.58 E-02 Ci/sec 2.38 E-02 1.2 E-02 3

E-0 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

2. I-131 and Part tl/2>8d 9.3 E-02 NOTE:

Num ers n paren eses represent max mum sens t v y

n pC m.

1.6 E+00 4.9 E-02

~

~

I

APPENDIX III YEAR 1981 NUCLM CHEHISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY.REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELEASES" POR'TION OF THE SEHIANNUAL OPERATING REPORT TABLE II Airborne Releases

- Particulates Page 2

Isoto e

Ba-140 Co-57 Co-58 Co-60 Cr-51 Cs-134 Cs-136 Cs-137 I -131 La-1 0 Mn-54 Nb-95 Sr-89 Sr-90 Un t Ci Ci Ci Ci Ci Ci Ci Ci Cj Cj Jul 1.6 E-05

(<1.5 E-14) 7.2 E-05 5.1 E-05

(<2.4 E-13) 2.5 E-05

2. 7 E-06 3.7 E-05 1.6 E-05 1.3 E-05 1.5 E-05

(<4.6 E-14) 2.9 E-06 1.4 E-07 Au ust

(<1.6 E-13)

(<1.6 E-14) 5.3 E-06 3.5 E-05

(<2.8 E-13) 3.8 E-06

(<6.4 E-14) 1.3 E-05 9;6 E-07

(<5.4 E-14)

(<7.0 E-14)

(<5. 5 E-14) 1.9 E-07

3. 1 E-08 Se tember

<2.0 E-13)

(<1.7 E-14) 1.0 E-04 8.5 E-05

(<2.4 E-13) 4.1 E-06

(<8.5 E-14) 7.0 E-06

(<3.3 E-14)

(<2. 8 E-14) 1.1 E-06

(<6.1 E-14) 1.8 E-07 1.2 E-08 October

(<1.6 E-13)

(<1.4 E-14) 1.8 E-05

. 1.2 E-05

(<2.2

.E-13) 2.7 E-06

(<6. 4 E-14) 6.1 E-06 1.9 E-06

(<3.4 E-14)

(<4.8 E-14)

(<4.3 E-14) 1.3 E-06 7.0 E-08 November

(<1.5 E-13)

( <1.4 E-14) 6.6 E-05 4.4 E-05 9.4 E-06 1.2 E-05

(<6.4 E-14) 2.4 E-05 1.3 E-06

(<3.9 E-14) 3.6 E-06 2.0 E-06 1.2 E-06 4.8 E-08 ecem er

(<3.0 E-13) 1.7 E-05 1.4 E-04

(<4. 2 E-13) 7.1 E-06

(<1. 9 E-13) 2.1'-05

(<5.4 E-14)

(<6.9 E-14) 1.1 E-06

(<1.0 3) 1.5

.E-06 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.

~

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PPENDIX III EAR 1981 NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SENIANNUAL OPERATING REPORT TABLE II N rborne Pee eases - Gaseous Page 3

Un>t Isoto e

Floss on an Act vat on Gases July August September October November December Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Total Ci Ci

. Ci Ci 1.63 E&l 6.8 E-02 5.93 E-02

(< 2.6 E-06) 3.22 E-02 1.36 EWO 3.93 E+02 1.36 EWO 9.01 E-01 2.44 E-02

(<6.6 E-06) 4.14 E+00 1.76 E-01 1.44 E-01

( <1.0 E-05) 1.38 E-Ol 1.25 E+00 2.45 I+02 1.53 E&0 2.86 E+00 7.78 E-02

( <4. 2 E-05) 4.87 E+00

(-<9.0 E-05) 7.8 E-02 9.3 E-03 6.14 E-02 7.70 E-01 1.26 E+02 1.15 E+00 1.26 E+00 8.2 E-02

(<6.2 E-06)

E+02 6.86 E-01 1.68 E-Ol 3.78 E-02 4.36 E-02

(<9.7 E-06) 1.46 E+00 8.52 E+02 8.00 E-01 6.51 E-01 5.95 E-02

(<l. 7 E-05) 8 E

2 3.87 E+02 3.87 E+02 1.6

(<8.2 1.1 E-02

(<8.2 )

( <8. 4 E-07)

( <8.9 E-06) 3.02 EW2 4.08 E-01 2.50 E-01

( <3. 2 E-06)

(<6.0 E-06) 3.03 E+02 Halo ens Gaseous Isoto e

Un t July August September October 5.9 E-03 1.2 E-03 1.6 E-04 I-131 1.7 E-03 I-133 I-135 Br-82 Total Note:

4.6 E-04 2.4. E-04 1.9 E-04 1.0 E-04 1.4 E-03

(<9.7 E-14) 1.1 E-03 2.3 E-04 6.6 E-04

5. 2 E-04 1.7 E-04 4.8 E-04 3.6 E-03

. 6.2 E-04 2.4 E-03 7.9 E-03 um ers n paren eses represen max>mum sens v

y ln p i m.

November 1.6 E-03

(<4.3 E-14)

(<1.9 E-13)

(<6.8 E-14) 1.6 E-03 Dece 5.4 E-04

5. 2 E-04 7.0 E-06 1.2 E-04 1.19 E-03

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

7/09/8 I 7/09/8 I 7/ )4/8 I 7/16/81 7/16/81 7/2i/81 7/23/8 I 7/28/81 7/30/81 7/30/8) 8/04/81 8/10/8 I 8/11/81 8/12/81 8/13/8) 8/25/81 8/28/81 9/14/81 9/21/81 9/23/8 I 9/26/8 I 9/28/8 I 9/30/81 9/30/81 10/05/8]

10/07/81 IO/09/81 10/13/81 10/13/81 10/15/8 I

io/i9/s 1 10/20/81 10/21/81 10/27/81 10/29/81 11/04/81 11/10/81 11/17/81 12/04/8 I 12/08/sl 12/14/8) 12/)7/81 12/19/81 12/09/81 12/IO/Sl 12/10/81 12/29/81 12/31/81 49 Shipments On site <<s'f.

. Januar, I,

1982 0.00) 24 0.00105 0.00800 0.0064 I 0.002485 0.00129 0.00927 0.04716 0.09351

0. 04960 0.09)88 0.10920 0.51455 0.59200 2:<<'20000 0.88400 0.04072 2.38000 0.13200 2.77000 0.21000 0.45600 10'17000 0.069195 0 ~ 18513 2.28000 0.76100 0.95200 0.05990 1.23000 1.38600 1.08000 0.06010 0.92400 1.85000 0.23398 0,.)74765 1.85000 0.09200

'.24600

0. )9500 0.61600 1.23200 0.92400 0.26870 0.25200

0. 14800

0. 17100 0.30640 38:317 5.376 525 532.5 517.5 525 540 540 525 765 1050 1050 1050 1050 170 150 170 170 1050 170 1050 200 170 170 200.

1050 1050 170 170 170 1050 85 85 85 1050 85 200 1050 1050 200 200 1050 1050 85 85 85 1100 1050 1050 1050 1050 27,745 3, 148

Barnwell, Richland, ll

Barnwell, Richland,

Barnwell, Richland, II S.C.

Ha.

S.C

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S.C.

Wa.

II Barnwell, S.C.

Richland, II Ha.

Barnwell, S.C.

Richland, Ha.

Barnwell, S.C.

Richland, Barnwell, tl Ha.

S.C

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Barnwell, S.C.

II II

Richland, Va.

Barnwell, S.C.

ll II II 11

Richland, II Ha

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Buried in Barnwell, S.C.

Richland, Ha.

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

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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

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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.

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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 Monitorin 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.

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

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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 tritium 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.

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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.

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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

=

Hedium or Pathway Sam led Unit Analysis for Sites Sam les Ana~lses Number of All Indicator Locations Location with Nighest Hean Hean1)

Hean1)

Sample Location Ran e

Distance 5 Direction Control

)

Location Ran e

)

Hean

)

Na~n e

No. of Nonruutine Reported tkasurene 1.1 AIR

1. Particulates pCi/m Gross B

432 216

)

216

.OZ8 (216/216)

.00b-

.123 l58-Entrance Road on Site (1 Hile-WSW)

.031 (27/27)

.008-

.123

.UBU (27/27)

.UxZ-

.l09

2. Radioiodine pCi/m3 1311 216

)

216 ND 1.2 DIRECT RADIATION 1.

TLD Rem/hr Exposure Rate 1306) 130 130 4.7 (130/130) 2.3-9.2 T5Z-Fla City Sub-station (7 miles-W) b.8 (6/6) 4.0-9.2 b.5 (e/6) 4.7-e:6 1.3 PRECIPITATION

1. Rainwater pCi/1 Gross B-DS Gross B-UO Tritium Y -emitting isotopes 236) 23 23 23 23 4.2 (8/23) 3.2 (1/23) 340 (2/23)

ND )

3.0-10.1 210-470 T52-Florida City Sub-station (7 Hiles-W)

T57-Dolan's Farm (4 Hiles-NW)

T5Z-Florida City Sub-station (7 Hi les-W)

NA 4.8 (4/6) 3.2 (1/6) 410 (1/6)

=NA 3.0-10.1 3'

(2/4)

NU ND d,l-3.4 S - Dissolved Solids UDS - Undis olved Solids ND - Non Detect ble NA - Not plicabl

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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 Number of All Indicator Locations Location with Nighest Mean ontrol2>

ocation No, ot Nonrouti Medium or Pathway 5~am led 2.2 MELLS

1. Potable Mell Nater Unit Analysis for Sites 9

3 Sam les Anal ses Mean )

18 6

Ran e1 ample Location Distance 6 Direction Mean )

Ran e )

M anL)

Reports Ran e )

HeasuremE:

Drinking Nater pci/1 Gross 8-D Gross B-DS Tritium 7.3 (5/6)

ND ND 4.4-13.0 T57-Dolan's Farm.

(4 Msies-NX)

~

NA LUUL (2/2)

N NA 791-139 2.

Ground Mater Ground Mater Wells 99 YU pCi/1 Tritium "9Sr 90Sr Y emitting isotopes 12 12 12 12 12 L130 (7/12)

ND4) 290-2600

'N N

NA T90-Groundwater Neil E-20 (6 Miles -SSE)

NA N

N 2bu0 (1/2)

NA N

N FAj 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 Number of All Indicator Locations Location with Highest Mean Contrul2)

Location No, ut Nonruut>

Hedium or Pathway

~Sam l ed Analysis Unit for ites Samples Anal ses Mean )

Ran e

Sample Location Distance G Direct>on Heanl)

Ran e1)

Heanl)

Nan e')

Report Heasur 3.0 BOTTOM SEDIHENTS

1. Cooling Canal Bottom Sediments pCi/kg Sr 90Sr Y emitting isotopes 1 ~ 60Co Z. 95Zr

3. Others 9

2 23) 23) 4 31U (3/4)90-580 230 (1/4)

ND4')

NA T84-Cooling canal South of bridge (0 Miles - SW7 T85-Cooling canal West of 90'end (0 Miles - SW)

~

NA 42U (2/2) 230 il/2) 2bU-NA NA

2. Estuarine Bottom Sediments N

pCi/kg Sr 90Sr Y emitting isotopes

1. >>Zr

2. Others ND 7U (2/7)

ND4) bU-70 I'69-Elliott Key (7 Miles-ESE)

NA 7U (I/IJ 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 Medium or Pathway Sampled Un1t Analysis for Sites Number of Sam les All Indicator Locations Anal ses Meanl)

Ran el

<<ontroi2)

Location Location with Highest Mean Sample Location Distance 6 Direction Meanl)

Ran el)

Meanl)

Ran el)

Nu. ut Nonruutl Keporte Measure 4.0 A)VATIC BIOTA

l. Crustacea (Blue Crab, pC1/kg Horseshoe Crab 89Sr

'"Sr Y Emitting isotopes 9

6 33 7

63) 63) 7 ND4)

2. Fish. Carnivore (Mixed Spec1es) pCi/kg N

89Sr 9OSr Y emitting isotopes 1.

1 7CQ

2. Other 8')

U3)

O3) 50 (1/6)

ND4)

3. F1sh, Herbivore (Mullet)

N pC1/kg w

89Sr 9OSr Y emitting isotopes ND4)

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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 Number of All Indicator Locations Location with Highest Hean Cuntrol2)

Locat>on No. of Nonruur.i edium or Pattway Sam led

4. Turtle Grass Unit Analysis for Sites Sam les Anal ses Hean1)

Sample Location Ran e

Distance 6.Direction Hean )

Ran e )

Keporte Hean )

Kan e )

Heasur Turtle Grass pCi/kg 89Sr 9OSr

'Y emitting isotopes

1. "Zr

2. Other 53) 53) 6 ND ND 240 (5/6)

NO4) 130-320 T59-El liott Key (10 Hiles-NE)

NA 32U (I/1)

NA 0

5. Sponges Sponge pCi/kg Y emitting isotopes

1. 95Zr 2

144Ce 3

60Co 4

106Ru

5. Others 860 (5/6) 3600 (1/6) 70 (1/6) 550 (3/6)

ND4) 7U-1500 NA 360-

, 590 NA T94-Pumpkin Key (8 Hiles-SSE)

T59-Elliott Key (10 Hiles-NE)

T59-Elliott Key (10 Hiles-NE)

T93-Pelican Bank (1.5 Hiles-E)

NA lbUU (1/1).

BbUU (I/I) 7U (1/1) b9U (1/1)

NA NA NA

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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 Number of All Indicator Locations Location with Nighest Mean ControlZ)

Locat>un

'Nu. ot Nonrout>ne Medium or Patt+ay Sam led Unit Analysis for Sites Sam les Anal ses Hean1)

Sample Location Ran e

Distance 5 Direct>on Mean )

Ran e )

Wan )

Ran eI)

Reports Heasur 5,0 TERRESTREAL

1. Small Animal 2.

Food Crops (Corn, Potatoes)

3. Vegetation (Hangrove Leaves

4. Ground Samples Soil pCi/kg N

pCi/kg EE pCi/kg 55 89Sr 90Sr Y emitting isotopes O'Sr 90Sr Y emitting isotopes

1. 9'Zr

2. Others 89Sr 90Sr Y emitting iostopes 137Cs

2. "Zr

3. Otners 12 1

17 06) 3 43) 43) 7 63) 63) 7 N04) 190 (5/7)

ND4)

ND ND 170 (5/7)

(z5)

ND4).

110-270 80-290 ZZU-290 NA T64-Natoma Substation (22 Miles-N) Control Sample Location NA T56-Princeton Sub-station(8 Miles-WNW)

T56-Princeton Sub-station(8 Hs les-WNW)

NA 27U (1/1) 29U (I/I) 290 (I/I)

NA 27U LI/I)

~

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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 Pathwa Sam led 1.

Surface Water, Analysis For

9Sr, Sr II II Location/Date T66/11-19-81 T81/11-19-81 T84/12-03-81 T97/12-03-81 Reason for Analyses incomplete 2.

Bottom Sediment ll ll 89Sr 90Sr T84/10-16-81

.T85/10-29-81 Analyses incomplete 3.

Crustacea 4.

Fish, Carnivore Sr, Sr 89Sr 90Sr T81/12-17-81 T81/12-17-81 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 Analyses incomplete Analyses incomp'lete

.5.

Turtle Grass 89Sr 90Sr T81/11-19-81 Analyses incomplete 6.

Food Crop (Potatoes)

89Sr, 90Sr.

II II II II II f52/09/25-81 T57/12-17-81 Analyses incomplete

~I

~I 7.

Mangrove Leaves 8"Sr, 9"Sr T71/09-30-81 T72/09-30-81 T51/10-29-81.

T86/10-29-81 Analyses incompl'ete 8.

Soi l

""Sr, Sr T52/09-25-81 Analyses incompl ete

~ 0

II.. Nissing Data e

Nedium or Path@a~

Analysis Location Date Reason for 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 (1.3)

T64/12-81 T64/8-81

'Sample apparatus found dismantled Sample apparatus found dismantled Small Animal Tabl e 4-12-1 (5.2.1)

T/58 All attempts to collect sample were

- unsuccessful

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. BOX 14000, JUNO BEE~, Pa+3408 4($'@

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

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