ML18227A270

Semi-Annual Report of Radioactive Effluent Releases and Environmental Radiological Monitoring for January 01, 1978 Through June 30, 1978

ML18227A270
Person / Time
Site:	Turkey Point
Issue date:	08/30/1978
From:	Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML18227A270 (48)

Text

TURKEY POINT PLANT UNITS 3 AND 4 SEMI-ANNUAL REPORT OF RADIOACTIVE EFFLUENT RELEASES ENVIRONMENT."J. RADIOLOGICAL MONITORING FOR PERIOD JANUARY 1, 1978 THROUGH JUNE 30, 1978 IN COMPLIANCE WITH TECHNICAL SPECIFICATION 6.9.4

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TABLE OF CONTENTS TABLE OF CONTENTS. . . . . .' . . . . . . . . . . . . . . . . . . . . . 1 INTRODUCTION 2 (A) RADIOACTIVE EFFLUENT RELEASES. ~ 3 (1) LIQUID RELEASES. 3 (2) AIRBORNE RELEASES. 6 (3) SOLID. WASTE BURIAL 18 (B) RADIOLOGICAL ENVIROPiiENTAL MONITORING . ... . . . . . . . . . . . . . . 20

INTRODUCTXON THIS REPORT IS SUBMITTED IN ACCORDANCE HITH TUIKEY POINT PLAbT TECHNICAL SPECIFICATION SECTION 6.9.4.

THIS REPORT COVERS THE DATA NECESSARY TO MEET THE SEMI-ANNUAL REPORTING REQUIREMEiiTS FOR (A) RADIOACTXVE EFFLUENT RELEASES AND (B) ENVIROiVKKNTALRADIOLOGICAL MONITORING FOR THE PERIOD OF JANUARY 1, 1978, THROUGH JUNE 30, 1978.

SE?AIA&ai UAL REPORT OF RADIOACTIVE EFFLUENT RELEASES PTP UNITS 3 6 4 1/78 6/78 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 has been met or exceeded.

Li uid Releases Aliquots of representative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a multichannel analyzer, or evapo-rated and analyzed for gross beta-gamma activity in a 2m gas flow propor-tional 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 t 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 6:

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, or during lancing of the generators.

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1/78 6/78

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, page 4 are for the waste disposal system only and page 5 is for the secondary system only. During primary to secondary leakage, release of several short-lived nuclides occurred from the sec'ondary system. These short-lived nuclides are not generally detected in batch releases from the waste disposal system due to the long holdup time of processed water.

3. Only those isotopes that were detected in the secondary system releases were reported. All non-detectable isotopes are listed as

( ) ~

4. Weekly and monthly composite samples for the waste disposal system were prepared to give a proportional weight to each liquid release made during the designated period of accumulation. The composites were analyzed for gamma emitting 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 released during the compositing .

period.

1/78 6/78 At least one representative batch of liquid effluent from the waste disposal system P 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 released for the month in order to estimate the total dissolved gases released.

Xf more than nne batch of effluent was analyzed, the concentrations werewe'ighted in an appropriate manner. The results are totaled on a monthly basis in Table I, page 6. Dissolved gases 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 and by analysis of a representative composite for tritium, gross alpha and selected beta emitters.

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

8. The following notes have been added to help explain some of the results in Table I which have been superscripted with a lower case le tter:

Su erscri t Notes The Q/MPC for this release was 0.21.

The Q/MPC for this release was 0.077.

No primary to secondary leakage chas occurring; there fore, most short-lived isotopes were not present.

1/78 6/78 Airborne Releases Airborne releases to the atmosphere occurred from release of gas decay tanks, via the instrument bleedline, containment purges, -and from 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 and gross beta-gamma analysis. H'nalysis, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma-spectrum analysis, and k

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.

The maximum rated capacity for the hogging jets and the maximum

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measured flowrate for the condenser air ejectors, and an estimate of the rate of exhaust from the atmospheric 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.

r t limit for

2. The applicable release of total radioactive materials in gaseous waste is 0.012 Ci/sec when averaged o'ver the calendar quarter.

• 1/78 6/78

/

The percent of the applicable limit for total gaseous release was computed as follows:

Total curies released in

/ f L. it aseous waste durin quarter x 100

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

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

'E 'ec',

MPC

< 10,000 m

where Q. = release I

Ci/sec

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i rate of .th nuclide, and MPC. = maximum permissible concentration af the ith nuclide.

determined by dividing the total activity The release rate, Q.,i was released in Ci,,for the ith nuclide (tl/2 > 8d),, durin'he calendar quarter by the seconds in the quarter.

MPC i values were obtained from Appendix B,. Table.II, Column. 1, 10 CFR 20.. The MPC chosen was the most conservative value of either the soluble or insoluble MPC for each isotope.

The percent of the applicable limit was determined as follows:

% of Limit =

EQ.

MPC.

x 100%

10,000 m /sec

4. 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.

1/78 6/78

5. All values reported in Table II, pages 2 and 3, include the particulate, gaseous, and/or 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 ( ).

e 19 78 Table I Report of Radioactive Effluents: Liquid Page 1 Li uid Releases Feb ruarv March June A. Gross Radioactivit

1. Total Release mci) 1.07 E+03 1.66 E+03 4.62 E+01 3.01 H+01 3.39 F+01 22. H

2. Avg Concentration During Releases(yCi/ml) 7.1 E-09 1.0 E-08 l. 8 E-09 8. 3 H-10 6.5 E-lo 5 .6 E-10

3. Avp Concentration for Month (uCi/ml) 5. 8 H-09 7. 4 E-09 2. 2 E-10 8.9 E-11 1. 3 E-10 8.3 E-11

4. Max Concentration Released Ci ml 1. 1 H-07 4. H-O 32 .-9 S. Percent of Technical Specification Limit for Total Activit Released 5.55 E+01 1.73 E+00 B. Tritium

1. Total Release (Ci) 6.19 E+01 8.61 E+01 4.42 E+Ol 1.56 E+02 9.08 E+Ol 1.16 E+02

2. Avg Concentration During Releases(gCi/ml) 4.1 H-07 5..3 E-07 1.7 E-06 4. 3 E<<06 l. 7 E-06 2.9 E-06

3. Avg Concentration for Month (pCi/ml) 3.3 E-07 3.9 E-07 2.1: H-07 46 E07 34 E07 4. 3 E-07 C. Dissolved Noble Gas

1. Total Release (mCi) 6.02 H+00 4.10 E+01 3.27 E+00 3.71 E+02 3.25 E+02 7.43 H+00

2. Avg Concentration During Releases(pCi/ml) 4.0 E-ll -2.5 E-10 l. 3 E-10 1.0 E-08 6.3 H-09 1 9 E-10

3. Avg Concentration for Month (pCi/ml) 3.2 F,-ll 1.8 E-10 1.5 H-ll 1.1 H-09 1.2 E-09 2.8 E-ll D. Gross Al'a Radioactivit R (mCi) 1. 49 E-02 (<1. 2 E-08) (<1.1 E-08) (<1.7 E-'08) (<2.2 E-08) ( 1.0 E-08)

2. Av Concentration During Releases(uCi/ml) 9.9 E-14 (<7.4 H-20) (<4.3 E-19) (<4. 7 E-19) (<4.2 E-19) (<2.5 E-19)

3. Av Concentration for Month (uCi/ml) 8.0 E-14 (<5.4 E-20) (<5.2 E-20) (<5.0 E-20) (<8. 3 E-20) (<3.7 E-20)

E. Volumes

. Vol of Li uid Haste to'ischar e (Liters) 1.21 E+07 7.84 E+06 1.45 E+06 1.57 E&6 2.25 E+06 1.54 E+06

2. Vol of Dilution plater During Rel (Liters) 1.50 E+ll 1.62 E+11 2.57 E+10 3.64 E+10 5.19 E+10 3.97 E+10

3. Vol of Dilution Hater for Honth (Liters) 1.86 E+11 2.23 E+11 2.11 E+ll 3.39 H+11 2.66 E+11 .2.70 8+11

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19 78 Table I R eport of Radioactive Effluents: Liquid Total Page 2 c c c c Isotope Unit January .February March April May June Ag-110m mCi 3.16 E-01 1.11 E+00 2.65 E-Ol: 1.91 E-01 3.55 E-01 ~

Ba-140 mCi (<3. G E-07) 7.95 E-01 (<3.2 E-07) (< 2. 1 E-07) (<2.7 E-07) (<4.1- E-07)

Co-58 mCi 4.19 E+00 3.07 E+01 5.14 E+00 1.66 E+00 4.50 E+00 1.81 E+00 Co-60 mCi 9,32 E+00 1.21 E+01 2.Gl E+00 1.33 E+00 8.90 E+00 6.51 E+00 Cr-51 mCi 2.81 E+00 1.59 E+00 1.03 E+00 Cs-134 mCi 1.43 E+01 3.78 E+01 1.47 E+00 3.42 E-02 1.43 E-01 Cs-136 mCi 3.13 E+DD Cs-137 mCi 1.73 E+Ol 7.73 E+Ol 3.19 E+00 2.30 E-01 5.14 E-ol 3.41 E-01 Cs-138 mCi 4.49 E+Ol 9.13 E+01 F-18 mCi. 1.37 E+02 3.27 E+02 Fe-59 mCi.- 5.19 E-02 2.2G E-01 I-131 mCi 3.39 E+02 2.47 E+02 8.61 E+00 8.77 E+00 1.78 E+00 1.0 E- 1 I-132 mCi 6.66 E+01 1.22 E+02 I-133 2.63 E+02 3.19 E+02 I-134 mCi 2.33 E+01 5.36 E+01 I-135 mCi 1.00 K+02 1.85 E+02

'Ci (<l. 4

-La-140 mCi (<2. 1 E-08) (<1, 8. E-08) E-08) (<1.6 E-08) (<1.1 E-08) (<1. 3 E-08)

Hn-54 3.91 E-ol 4.4 E+00 . 1.65 E-01 4.6 E-02 5.26 E-Ol 2.6 E-D1 Na-24 mCi 3.47 E+01 1.02 E+02 Nb-95 mCi 1.43 E-01 8.99 E-ol 2.70 E-01 3.76 E-01 6.36 H-02 Ru-103 mCi 7.1 E-02 Sb-124 mCi ~ 1.7 E+00 2.77 E+00 8.26 E-01 4.95 E-01 4.82 E-01 2.2 E-01

.Sb-125 mCi 1.24 E+00 2.84 E+00 7.05 E-01 .30 E-0 Sr-89, mCi 4.1 E+DD 1.96 E+00 1.9 E-01 1.3 E-02 7.4 E-02 9. 3 E-02 NOTE: Numbers in parenthesis represent maximum sensitivity in uCi/ml.

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1978 Table I Report of Radioactive Effluents: Liquid Total Page 3 iso tope Unit January Feb rua Harch c

h ril c c Hav June Sr-90 mCi (<3.1 E-09) . (<3.1 E-09) (<3.1 E-09)'<3.0 E-09) 2.5 E-02 ~

(<3.4 E-09)

Zr-95 mCi 6.54 E-01 3.26 E-Ol Unidentified mCi 5.84 E+00 3.33 E&1 2.02 E&l 1.68 E+Ol

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1.44 E+Ol 1.19 E+01 Total NOTE: Numbers mCi 1.07 E&3 in parenthesis represent maximum 1.66 E+03 4.62 E+01 sensitivity in uCi/ml.

3.01 E+01 11

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3.39 E+01 2.23 E+01

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19 78 Table l Report of Radioactive Effluents: Liquid - ~rlaste Disposal S stem Pa e 4 Xso tope Unit January February Harch A ril June Ag-110m mCi 3.16 E-01 1.11 E+00 2.65 E-Ol: (<3.4 E-08) 1.91 E-01 3.55 E-01 Ba-140 mCi (<3.6 E-07) 7.95 E-01 (<3.2 E-07) (<2.1 F.-07) (<2.7 E-07) (<4.1 E-07)

Co-58 mCi 3.67 E+00 2.83 E+01 3.96 E+00 1.66 H+00

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4.20 E+00 1.74 E+00 Co-60 mCi 3.82 H+00 9. 3 E+00 2.08 E+00 1.33 F+00 6.25 H+0 Cr-.51 mCi (<2. 8 E-07) 2.81 E+00 1.59 E+00 {<1.8 E-07) 1.03 E+00 {<2.8 E-07)

Cs-134 mCi 1.02 E+00 1.67 E+Ol 2.29 F.-Ol 3.42 E-02 1.43 E-Ol <5.3 E-08 Cs-137 mCi 2.02 E+00 4.48 E+Ol ,6. 7 E-01 2.3 '-01 5.14 E-01 3.41 E-01 Fe-59 mCi 5.19 E-02 (<9 .2 H-08) 2.26 E-01 (<4.1 E-08) (<5.4 E-08) (<9 .6 H-08)

I-131 mCi 1.67 E+01 2.13 E+01 4.4 E+00 8. 77'+00 1.78 E+00 1.05 E-01 La-140 mCi. (<2.1 E-08) (<1. 8 E-08) (<1. 4 E-08) (<1. 6 E-.08) <1.1 E-08 < .3 H-08 Hn-54 mCi .3.91 E-01 7.04 E-Ol 1.65 H<<ol 4.6 E-02 5.26 E-Ol 2.47 E-Ol Nb-95 mCi 1.43 E-01 8.99 E-01 2.7 E-01 {<2.3 E-08 3.76 H-01 6.36 H-Ru-103 mCi (<3.5 '-08) (<7.3 E-08) 7.1'-02 (<1.9 E~08 <2.8 E- 8 Sb-124 mCi 1.7 E+00 2.77 E+00 8.26 E-01 4.95 E-01 4.82 E-Ol 2.29 E-01 Sb-125 mCi 1.14 E+00 2.84 E+00 1.37 E+00 7.05 E-01 9.30 E-01 6.77 E-ol Sr-89 mCi 3.51 E-02 (<2.9 E-09) 9.8 E-02 1. 3 H-02 7.4 9.3 'E-02 Sr-90 mCi (<3.0 E-09) (<2.9. E-09) (<3. 1 E-09) (<3.0 E-09). 2.5 E-02 <3.4 H-09 Zr-95 mCi (<6.2 E-08) 3.26 E-01 (<5. 7 E-08) (<3.4 E-08) (<5. 7 E-08) (<8.2 E-08)

To tal mCi 3. 1 E+01 1.33 E+02 1.62 E+01 1.33 E+Ol 1.65 8+01 9.71 E+00 NOTE: Numbers in parenthesis represent maximum sensitivity in pCi/ml.

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1978 Table I Re ort of Radioactive Effluents: Liquid Secondar S stem Pa e 5 Isotope Unit January February March April May June Co-58 mCi 5. 2 E-01 2.42 E+00 1.18 E+00. 3.0 E-01 6.88 E-02 Co-60 mCi 5.50 E+00 2.79 E+00 5.26 E-01 2.65 E+00 6.5 E-01 Cs-134 mCi 1,.33 E+01. 2.X1 E+01 1.24 E&0 Cs-136 mCi 3.13 E+00 Cs-137 mCi 1.53 E+Ol 3.25 E+01 2.52 E+00 Cs-138 mCi 4.49 E+01 9.13 E+Ol P-18 mCi :1.37 E+02 3.27 E+02 I-131 '.3.22 E+02 2.26 E+02 4.21 E+00 I-132 '6.66 E+01 1.22 E+02 mCi'Ci.

I-133 2.63 E+02 3.19 F+02 I-134 mCi 2.33 E+Ol 5.36 E+Ol I-135 mCi 1.00 E+02 1.85 E+02 Mn-54 mCi 3. 7 E+00 1.21 E-02 Na-24 mCi 3.47 E+Ol 1.02 E+92 Sr-89 'Ci 4.06 E+00 1.96 E+00 9.5 E-02 Sr-90 mCi (<3.1 E-09) (<3.1 E-09) (<3.1 E-09) 7.r-95 mCi 6.54 E>>01 Unidentified mCi 5.84 E+00 3.33 E+01 2.02 E&1 1.68 E+01 1.44 E&1 1.19 E+Ol Total mCi 1.04 EW3 1.52 EW3 3.00 E+01 1.68 E+01 1.74 E+Ol 1.26 E+01 NOTE; Numbers in parenthesis represent maximum sensitivity in pCi/ml. - 13

978 Table 1 Report of Radioactive Effluents: Liquid Dissolved Gas Page 6 Total January February Harch April Hay June Kr-85m mCi (<2.1 E-08) . (<3.0 E-08 (<1.8 E-Og) (<2.9 E-08) 1.04 E+00 (<1.6 E-.08)

Xe-133 mCi 3.88 E+00 3.93 E+01 2.6G E+00 3.61 E+02 2.70 E+02 7.14 E+00 Xe-133m mCi (<2.5 E-07.) (<2.5 E-07) (<1.7 E-07) 6.12 E+00 8.76 E+00 (<1.6 E-07)

Xe-135 mCi 2.14 E+00 1.71 E+00 6.05 E-01 3.45 E+00 4.5 8+01 2.89 E-01 Haste Disposal Svstem Kr-85m mCi (<2.1 E-08) (<3.0 E-08) (<1. 8 E-08) <2. 9 .E-08) 1.04 E+00 <1.G E-08 Xe-133 mCi 4.46 E-01 3.36 E+Ol 2.66 E+00 3.61 E+02." 2.70 E+02 7.14 E+00 Xe'-133m mCi (<2.5 E-07) (<2.5 E-07) (<1. 7 E-07) 6.12 E+00 8.76 E+00 (<1.6 E-07 Xe-135 -'mCi (<2.8 E-08). 8,16 E-01 6.05 E-01 3.45 E+00 4.5 E+01 2.89 E-01

'Secondarv Svstem Xe-133 mCi 3.43 E+00 5.71 E+00 Xe-135 mCi 2.14 E+00 8.95 E-01 NOTE: Numbers-in parenthesis represent maximum sensitivity in pCi/ml. 14

I 978 Table II Report of Radioactive Ef fluents: Airborne Page 1 January February March April Hay June Fissi6n and Activation Gases

1. Total Release (Ci) 1.22 E+03 l.'23 E+03 1.88 E+03 2.43 E+03 2.09 E+03 1.30 E+03

2. Avg Rel Rate for Period(pCi:/sec) 4.5 E+02 5. 1 E+02 , 7;0 E+02 9.4 E+02 7. 7 E+02 5.0 E+02

<3. Max Rel Rate for Period(pCi/sec) 5.0 E+04 2.3 H+04 6.6 E+03 2.0 H+04 3.5 H+04 4.3 E+04 I

<<Haximum airborne release rate averaged over one hour for each month. Technical Specification limit is 6.7 E+04 pCi/sec averaged over one hour.

Iodine 131

! 1. Total Iodine 131 Ci 1.5 E-01 9.1 E-02 2. 7 E-02 6.5 E-02 7.9 E-03 2;3 E-03

2. Av Rel Rate for Period pCi/sec) 5. 6 E-02 3. 8 E-02 1.0 E-02 2.5 E-02 2.9 H-03 8.8 E-04

Particulates

1. Particulates with tl/2>8d (Ci) 5.35 E-03 2.60 E-02 1.85 E-02 6.98 E-04 2.34 E-04 1.14 E-04

2. Avg Rel Rate for Period(pCi/sec) 2.0 E-03 1.1 E-02 6.9 E-03 2.7 E-04 8.7 E-05 4.4 E-05

3. Gross Alpha Radioactivity (Ci) 1.7 E-07 8. 6 E-08 6.2 E-08 <3.2 E-09) 6.3 E-09 . 1.9 E-09

. Tritium

1. Tothl Release (Ci) 5.74 E-01 1.50 E+00 ~

7.29 E-02 1.61 E-01 1.72 E-01 2.27 H-

2. Av Rel Rate for Period( Ci/sec) 2.1 E-01 6. 3 E-01 2. 7 E-02 6. 2 E-02 6.4 E-02 8. 7 E-02 uarter I

1. Fission and Activation Gases (%) 4.6 H+00 6.2 H+00

2. I-131 and Part.(tl/2>8d) (%) 3.5 E+00 9.6 E-01 3TE: Numbers in parenthesis represent maximum sensitivity in pCi/cc.

19 78 Table II ~

Airborne Releases Particu ate

=Isotope Unit January .February March A ril June Ag-110m Ci (<4. 1 E-13) 1.5 E-04 (<8. 8 E-3.3) (<9.1 E-14) (<4.4 E-14) (<2.6 E-14 Ba-140 Ci (<2.7 E-12) (<9.4 F.-12) 3.6 E-05 (<8.6 E-13) 3.2 H-05 (<2.9 E-13)

Ce-141 Ci 3.9 E-os (<4.8 H-13) 2. 3 E-05 (<4.8 E-14) (<2.4 E-14) (<2.7 E-14)

Ce-144 Ci 3.5 E-05 (<2.1 E-12) (<1.8 E-12) (<2.1 E-13) (<1.0 E-13) (<1.3 E-13)

Co'-.57 7.1 H-06 4.2 E-05 3.2 E-05 (<3.0 E-14) (<1.3 E-14) (<1.7 E-14)

-Co-58 1.8 E-03 1.8 E-n2 1. 3 H-02 4.6 H-04 6.0 E-05 2.4 E-05 Co-60 2.8 E-03 3.5 E-03 , 2.8 E-03 1. 4 E-04 4. 2 E-05 6.6 E-OS Cr-51 Ci 1.2 E-04 2.6 E-03 1.4 E-03 (<4.8 E-13 (<2.6 E-13 <1.6 F.-13 Cs='134 Ci l. 1 E-05 1.0 E-05 3.5 E'-05 2.5 E-05 2.0 E-05 4.2 E-06 Cs-136 Cg 5.9 E-06 (<6.1 E-13) 1.2 E-05 (<6.1 H-14) (<5.'5 E-14) (< 2. 2 E-14)

Cs-137 3.1 E-05 2.7 E-05 5.2 E-05 5. 3 E-05 3.2 E-05 8.7 E-Fe-59 Ci (<6.5 E-13) 2.0 E-04 1.4 E-04 (<1.5 E-13) (<5.6 E-14) (<3.1 E-14)

"I'-131 Ci 2.2 E-05 9.9 E-05 3.2 E-05 6.8 F.-O i L"a-140 Ci (<1. 1 E-13) (<2.3 E-13) 2.0 E-05 (<S.4 E-14) 2;6 E-05 3.9 F.-06 Mn-54 Ci 7.6 E-05 4.8 E-04 3.6 E-04 1.1 E-05 2.9 E-06 1.8 E-06 Nb-95 1.5 E-04 3.8 E-04 2.4 E-04 ~

(<8.3 H-14) (<4.0 E-14) <1.9 E-14)

Ru-103 1.5 H-04 (<8.1 E-13) (<6,9 E-13) '(<7. 1 E-14) (<4.0 E-14 <1 9 E-14 Sb-124 Ci ~ <2.5 E-13) 2. 7 H-04 1.5 E-04 ,(<8.9 E-14) (<2.0 E-14) <1.4 H-14 Sb-125 Ci <5.8 E-13) 1.3 (<1. 7 E-12) (<1.9 H-13) (<9 .8 E-14) (<5.4 E-14)

Sr-89 Ci 6.8 E-06 6.9 E-06 1.1 H-OS 1.7 E-06 2.9 'H-06 7 H-07 Sr-90 Ci 6. 7 H-07 4.4 E-07 1.6 E-08 (<2.5 E-16) 1.4 E-07 (<2.5 E-16)

Zr-95 Ci '9.1 E-05 1.5 E-04 1. 3 E-04 (<1. 2 E-13) (<5.4 E-14) <3.0 E-14 Total Ci 5.35 E-03 2.60 E-02 1.85 H-02 6.98 E-04 2. 34 E-04 1.14 E-04 Numbers in parenthesis represent maximum sensit vity in NCi/cc.

19 78 Table II Airborne Releases Gaseous Fage 3 Fission and Activation Gases Isotope Uni t January February March April May June Ar-41 2.27 E+00 3.31 E+00 4.08 E+00 1.35 E+Ol 5.56 E+00 4.01 E&0 Kr-85 Ci 2.45 E-01 1.34 E+00 2.49 E-02 4.03 E-01 1.70 E-01 (< 3.6 E-05)

Kr-85m Ci 1.86 E&0 2.87 E+00 .9.53 E-02 2. 8 E-01 4.30 E-Ol 2.70 E-Ol Kr-87 1.94 E+00 3.10 E+00 (<3. 7 E-07) (<2.6 E-06) (<3.0 E-06) (< 2. 7 E-07)

'r-88 Ci 2.29 E+00 3.57 E+00 (<1.0 E-06) 1.07 E-01 3.35 E-01 1.55 E-01 Xe-131m 4.97 E+00 1.18 E+00 3.38 E-02 1.21 E-Ol 1.37 E+00 1.17 E+00 Xe-133 Ci 1.18 E+03 1.18 E+03 1.87 8+03 2.41 E+03 2.07 E+03 1.28 E+03 Xe-133m 3.99 E+00 2.29 E+00 3.4 E-01 1.01 E+00 4.13 E+00 3.19 E+00 Xe-135 Ci 1.32 E+01 1.78 E+01 1.77 E+00 5.32 E+00 8.98 E+00 6.37 E+00 Xe-135m - Ci 3.41 E+00 6.05 E+00 (<5.8 E-07) 1.74 E-01 (<1.4 E-06) (<1. 6 E-07)

Xe-138 Ci 1.96 E+00 3.72 E+00 (<8. 4 E-07) (<1.1 E-05) (<8.4 E-06) (< 2. 7 E-07)

Total 1.22 E+03 1.23 E+03 1.88 F+'03 2.43 E+03 2.09 E+03 1.30 E+03

.Halo ens Gaseous Isoto e Unit Januarv February March A ril Mav June

'I-131 1.5 E-01 9.1 E-02 2.7 E-02 6.5 E-02 7.9 E-03 2. 3 E-03 I-133 3.5 E-02 2.8 E-n2 l. 2 E-02 2.1 E-02 1. 8 E-03 6,8 E-04 I-135 7.3 E-03 1.1 E-02 2;2 E-03 7.6 H-03 (<1.2 E-13) (<1.4 E-13)

'. Br-82 3,0 E-04 2,5 E-04 4. 1 E-04 1.0 E-03 3.0 E-04 1.30 E-ol 4.2 E-02 9.5 E-02 1.00 E-02 3,0 E-

Total Ci 1.9 E-01 NOTE: Numbers in parenthesis represent maximum sensitivity in pCi/cc.

RADlOACTZVE HASTE January 1, 1978 to June 30, 1978 Packed Ci Cu. Ft.

Total 419.263 40,035.7 On site as of 6. 617 689 '

July 1, 1978 Dat es of Shipment and Disposition 5 January 1978 .Buried in Barnwell, South Carolina ll January 1978 13 January 1978 17 January 1978 19 January 1978 20 Ja'nuary 1978 23 January 1978 26 January 1978 28 January'978 2 February 1978 6 February 1978 8 February 1978 .

10 February 1978 13 February 1978 16 February 1978 23 February 1978 6 Iarch 1978 9 March 1978 13 Maxch 1978 14 March 1978 15 March 1978 16 March 1978 17 March 1978 20 March 1978 21 March 1978 22 March 1978 23 March 1978 25 March 1978 10 April 1978 12 April 1978 12 April 1978 19 April 1978 20 April 1978 21 April 1978 24 Apx'il 1978 28 April 1978 3 May 1978 4 May 1978 5 May 1978 9 May 1978 10 May 1978 12 May 1978 15 May 1978 16 May 1978 16 May 1978 19 May 1978 19 May 1978

t Dates 20 23 23 31 of Shipment and Disposition May 1978 May 1978 May 1978 May 1978 Buried, in Barnwell, South Carolina 13 June 1978 13 June 1978 20 June 1978 22 June 1978 22 June 1978 I~

26 June 1978 28 June 1978 30 June 1978 Total Shipments 59

TURKEY POINT: Units 3 8 4 Environmental 'Radi olo i cal Honitorin

{l-01-78 to 6-30-78)

Introduction This report is submitted in accordance with Turkey Point Plant Techni ca 1 Speci ficati ons.

All environmental samples were collected and analyzed in confor-mance with the requirements of the Technical Specifications.

The minimum frequency of collection and analyses for specific radionuclides and sample types as required by these specifications has been met or exceeded.

The Moni torin Pro ram t

~y,1 Period Covered:

8 This current repor J 0.178.

covers the period from Anal tical Res onsibilit: Environmental radiological monitoring at Turkey Po~nt Plant is carried out by the Orlando Radiological Laboratory of the Department of Health and Rehabilitati.on Services of Florida (DHRS). All samples are collected and analyzed by DHRS personnel.

Number of Sam les Anal zed: A total of 706 analyses on samples collected from 35 different sampling locations were performed during the period of this report. TABLE 1 summarizes the mean and range values of these analyses.

S lit-Sam le Anal ses: At least 10 samples were collected to be analyzed by the DHRS/ERDA Split-Sampling Program.

Evaluation of Data a) As applicable, TABLE 1 reports data for sampling locations that have concentrations of a particular radionuclide higher than the observed mean for all sampling locations where the same type of sample material was collected and analyzed for that parti-cular radionuclide.

b) Recognition must be given that data reported herein could be influenced by the residual fallouts from the Chinese weapons tests of September, 1977 and the fallout from new Chinese tests carried out in Harch, 1978.

c) The Zr, '"Ru, and '""Ce found in sponges collected at locations T-59, T-69, T-86, T-93, T-94, and T-95 are due to fallout. Similar ly, these radionuclides were noted'lso in the assay of samples from these other locations:

Estaurine Sediments: T-66, -94 Mangrove Leaves: T-51, -58, -72, -86 Soils: T-52, -57, -55, -56, -58 and could be attributable to weapons testing fallouts.

d) The 'H concentration at sampling location T-84 is consistent with 'H levels previously observed in the Cooling Canal System. The other canal location, T-97, had a slightly lower concentration of 'H.

e) No significant increases above previously reported data have been observed in GB-DS and 'H concentrations at location T-75 in the Fresh Water Canals.

f) The 'H concentrations in the Ground Water Wells at sampling locations T-91 and T-92 continue to be of the same magnitude as previously reported.

g) The

'"Cs, concentration levels of '"i~1n, "Co, "Co, 'r, and '""Ce in the bottom sediments of the Cooling Canal at sampling location T-84 continue to be of the same order of magnitude as previously reported.

h) Trend plotting of air particulate and direct radiation data, especially in those periods when fallout occurrences have been observed, reveal no plant-related variations.

i) All data have been compared with pre-operational data and have been found to be within the +2a limits observed.

j) Where applicable, comparisons of test sample location data with that of the control sample show no differences in concentration levels except as noted in TABLE l.

Conclusions The concentration level'f any radionuclide reported in TABLE 1. will contribute much less than the maximum permissible limits of individual or population group intake that could result if there concentration had been a continuous exposure to radionuclides having values equal to those permitted by APPENDIX B, TABLE II, 10CFR20.

Therefore, the operations of Turkey Point Plant Units 3 5 4 are not contributing harmful effects or irreversible damage to either the environment or to the health and safety to individuals or population groups in the regions surrounding Turkey Point Plant.

e l

t ~

TABLE 1 ENVIRONttENTAL RADIOLOGICAL ttONITORIHG PROGRlN SUtNARY .

NAME OF FACILITY TURKEY POINT PLANT UNIT 3tt4 DOCKET NO. 50-250. -251 LOCATION OF FACILITY Dade County, Florida REPORTIHG PERIOD 1-01-78 to 6-30-78 All Indicator Location with Hihest tiean Control tier "al')

Ncnrout:aa Number of Locations Sample Location Location ,"ae paOI'teed tledium or, Pathway Analysis Sampled Unit for Sites Samples Analyses than Range Distance and Direction t tean Range Hean Range at aSOI't,',aan latess

l. Air Filters 1.1 Air Particu- 214 214 0.08 .02-0.28 T-71: Girl Scout Camp; 0.12 0.04- 0.11 0.05-0.26'OIIO pCi/m'Ci/m'B 0.28 ND HoIIe l.l.a Air'odines 1$ 1I 212 212 ND Hone 132 5.0 2-8 T-64: Natoma Substation, 6.2 5-7 6.2 5-7 teone 1.2 Direct Radia- pRem/ 132 tson hr Hiami, ENE, 30 miles ND Nolle 1.3 ~Preci itatica pCi/L GarIma scan 23 23 ND None GB-DS 23 23 7.0 3-22 T-571 Dolan's Farms, WtiW, 8.5 4-22 6.5 3-15

~4. miles 23 23 Hone ND GB-UDS sH 23 23 <200 None <200 Location with Hi hest Wean Control All Indicator Number of Locations Sample Location Location~ ~

Hedivm or Pathway Analysis Samoled Unit for Sites Samples Analyses Nean Range Distance and Direction Hean Range Hean Range

2. Water

,2.1 Estuarine pCi/L 'H 10 20 20 276 5200-1200 T-81: Card Sound, New 960 720- None

~isc arge Canal; South, 1200 6 miles Sr-89 10 20 20 ND None Sr-90 10 20 20 None 3700-9000 T-84: Discharge Canal, 5000- None 2.1.2 Coolinq pCi/L 'H 12 12 5792 6400

~ana southside of bridge 9000 69Sr 12 12 ND None 90Sr 12 12 ND-2 T-97: Loch Rosetta; on- 1.5-site 2.5 178 3-400 T-75: Florida City Canal 351 290- None.

2.1.3 Fresh Water pCi/L GB-DS 12 12 Canals NNW, 1.5 miles 400 Gg-UDS 12 12 ND None 12 12 330 <200- None 460 380-660 660 3-

All indicator Location Mith Hi hest Mean Control Number of Locations Sample Location Location Medium or PathMay Samoled Uni t'nalysis f01 Sites Analyses than Range Distance and Direction llean Range Hean

~

,r.n a vw, 4

.Qas~s',.',

~

c Samples Range 2.2 Potable Mater pCi/L GB-DS 4.6 ND-8 T-73: City of Homestead 5-7 None M~A s Water System; MNW, 9 mi.

GB-UDS ND None t

<200 I None I 2.3 Ground Water pCi/L 'H 12 12 711 <200- T-91: Well G10A, SW, 2.0 850 200- None ueuus 2200 ~1&s 1800 T-92: Mell G24A; SSW, 2100 2000-

~4. miles 2200 OSSr 12 12 None

'oSr 12 12 ND None 64

Location with Hi hest Nean Control All Indicator Number of Locations Sample Location Location~

tledium or Pathway Analysis Samnled Uni t for Sites Samples Analyses Nean Range Distance and Direction Ilean Range Hean Range >>C~9.a"Ga 0l.

3.0 Bottom 3.1 i

~Cool ~ Canal pCi/k 88Co 308 ND-1000 T-84: Discharge Canal, 308 HD-100 Hone Southside of bridge 80Co 1606 ND-3400 1606 ND-340 9SZr 205 ND-700 205 ND-700

'"Nn 100 ND-200 100 HD-200 148Ce 300 ND-600 300 ND-600

'40 197Cs 440 89 None Sr ND 905r ND Hone T-94: Pumpkin Key; SSE, 680 640-72 Hone 3.2 Estuarine pCi/kg '""Ce 226 ND-720 8 m1 les 98Zr 40 ND-140 110 80-140 89Sr ND Hone 9051, HD None 9 an

Location with Hi hest Nean Control llu!'.QQ< o; All Indicator nOnl Number of Locations Sample Location Location~a~

lledium or Pathway Analysis il:cap eel g" Samoled Unit for Sites Samples Analyses Mean Range Distance and Direction llean Range Hean Range 4.0 Biota 1% 4Ce 160 ND-400 T-951 Long Arsenicker 400~c~ 300- None 4.1 Crustacea pCi/k Key; ESE, 4.3 miles 500 4951, ND None 905r ND Hone 106Ru ND None hone 4.2.A Fish pCi/kg 49Sr ND None Carnivore 90Sr ND Hone 104Ru 800 700-900 T-81: Card Sound, Hew Booed> 700-

~isc arge Canal 900 Hone Hone 4.2.8 Fish pCi/kg 4 95r 6 6 ND Herbivore 8(e) 5-11 90Sr 1.3 ND-8 T-95: Long Arsenicker Key; Card Sound, ESE, 4.3 miles 100Ru ND Hone

Location with Hi hest Hean Control All Indicator Humber of Locations Sample Location Location I 4: '4 I tledium or Pathway Analysis Samnled Unit for Sites Samples Analyses Hean Range Distance and Direction llean Range Hean Range '. '4 sue e 4.3.A llanatee pCi/k 9S Zr 162 120-200 T-69; Elliott Key, South 200 150-250 Hone brass nd, ESE, 7 miles 095r ND Hone 90Sr ND Hone 4,3.B ~Son es pCS/kg 9SZr 196 D-400 -69: Elliott Key, South 400 00-500 ~

4 LI ekone n , ESE, 7 miles 14444Ce 2366 00-3400 -59: El 1 iott Key; E, 8 3400 200-1 es 3600 10eRu 300 D-700 700 00>>

1000

Location with Hi hest Hean Control All Indicator Vedium or Pathway Number of Locations Sample Location l.ocation( )

Analysis ~ \

Sampled for Sites Samples Analyses Hean Range Distance and Direction llean Range Hean Range FVead, .

vie 5.0 Terrestrial 510th j 5.2.1 Small pCi/kg '"Cs 80 70-90 T-58: Onsite Entrance 80 70-90 Nor o Animals (f) Road 49Sr None 90Sr ND None 5.2.2 ~pood Cro pgi/kg e'Sr ND None None 90Sr 1-29 T-52: Florida City Sub- 2g(g) 27-31 station; West, 8 miles 5.2.3 ~Man rove pCi/kg 99Zr 146 100-220 T-58: Onsite Entrance 220 170-270 None Leaves Road

'one 09Sl 7 7

'OSr 0-22 T-51: Homestead Bayfront 22 18-26 Paar; NNW, 2 miles

- 28

Location with Hi hest Hean Control All Indicator Number of Locations Sample Location l.ocation~ ~

tlediun or Pathway Analysis Samnled Uni t for Si tes Sampl es Analyses than Range Distance and Direction flean Range Mean Range 5.3 Soil pCi/kg rs7Cs 397 ND-660 T-52: Florida City Sub- 660 640-68 station, West, 8 miles lbbCe 389 ND-900 T-58: Onsite Entrance 900 800-Road 1000 106Ru 71 ND-500 500 300-70 ssZ 196 tiD-520 520 460-58 89Sr ND None s4Sr None hotes

~a>T-64: Nato Subst tion, Hiam, EttE, 0 miles tlD = Non-de ectabl Lobster Fish Mul let Raccoon 9 Halanga

T'