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.

(1)

LIQUID RELEASES.

(2)

AIRBORNE RELEASES.

(3)

SOLID. WASTE BURIAL

~

3 3

6 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 was analyzed monthly for dissolved fission and P

,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 letter:

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 H'nalysis, and gross beta-gamma analysis.

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

= 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 2.

The applicable limit for release of total radioactive materials t

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 m

.th

'E

< 10,000,where Q.

= release rate of i

nuclide, MPC 'ec'

~ I Ci/sec and MPC. = maximum permissible concentration af the ith nuclide.

The release

rate, Q., was determined by dividing the total activity i

released in Ci,,for the i nuclide (tl/2 > 8d),, durin'he calendar th quarter by the seconds in the quarter.

MPC values were obtained from Appendix B,. Table.II, Column. 1, i

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:

Q.

E x 100%

MPC.

% of Limit =

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 Li uid Releases Table I Report of Radioactive Effluents:

Liquid Feb ruarv March Page 1

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 4.

Max Concentration Released S. Percent of Technical Specification Limit for Total Activit Released Ci ml

2. Avg Concentration During Releases(yCi/ml)

3. Avp Concentration for Month (uCi/ml) 7.1 E-09

5. 8 H-09

1. 1 H-07 1.0 E-08

l. 8 E-09

7. 4 E-09

2. 2 E-10 5.55 E+01

8. 3 H-10 8.9 E-11 6.5 E-lo

1. 3 E-10 4.

H-O 1.73 E+00 5.6 E-10 8.3 E-11 32

.-9 B. Tritium

1. Total Release (Ci)

2. Avg Concentration During Releases(gCi/ml)

3. Avg Concentration for Month (pCi/ml) 6.19 E+01 8.61 E+01 4.42 E+Ol 4.1 H-07 5..3 E-07 1.7 E-06 3.3 E-07 3.9 E-07 2.1: H-07

4. 3 E<<06

l. 7 E-06 46 E07 34 E07 2.9 E-06

4. 3 E-07 1.56 E+02 9.08 E+Ol 1.16 E+02 C. Dissolved Noble Gas

1. Total Release (mCi) 6.02 H+00

2. Avg Concentration During Releases(pCi/ml) 4.0 E-ll

3. Avg Concentration for Month (pCi/ml) 3.2 F,-ll 4.10 E+01

-2.5 E-10 1.8 E-10 3.27 E+00 3.71 E+02

l. 3 E-10 1.0 E-08 1.5 H-ll 1.1 H-09 3.25 E+02 6.3 H-09 1.2 E-09 7.43 H+00 1 9 E-10 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)

3. Av Concentration for Month (uCi/ml) 8.0 E-14

(<5.4 E-20)

(<4.3 E-19) (<4. 7 E-19) (<4.2 E-19)

(<5.2 E-20) (<5.0 E-20) (<8. 3 E-20)

(<2.5 E-19)

(<3.7 E-20)

E. Volumes

. Vol of Li uid Haste to'ischar e (Liters)

2. Vol of Dilution plater During Rel (Liters)

3. Vol of Dilution Hater for Honth (Liters) 1.21 E+07 7.84 E+06 1.45 E+06 1.50 E+ll 1.62 E+11 2.57 E+10 1.86 E+11 2.23 E+11 2.11 E+ll 1.57 E&6 3.64 E+10 3.39 H+11 2.66 E+11

.2.70 8+11 2.25 E+06 1.54 E+06 5.19 E+10 3.97 E+10

19 78

~-

Table I Report of Radioactive Effluents:

Liquid Total

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Page 2

Isotope Ag-110m Ba-140 Co-58 Co-60 Cr-51 Cs-134 Cs-136 Cs-137 Cs-138 F-18 Fe-59 I-131 I-132 I-133 I-134 Unit mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi.

mCi.-

mCi mCi mCi January 3.16 E-01

(<3. G E-07) 4.19 E+00 9,32 E+00 1.43 E+01 3.13 E+DD 1.73 E+Ol 4.49 E+Ol 1.37 E+02 5.19 E-02 3.39 E+02 6.66 E+01 2.63 E+02 2.33 E+01

.February 1.11 E+00 7.95 E-01 3.07 E+01 1.21 E+01 2.81 E+00 3.78 E+01 7.73 E+Ol 9.13 E+01 3.27 E+02 2.47 E+02 1.22 E+02 3.19 E+02 5.36 E+01 March c 2.65 E-Ol:

(<3.2 E-07) 5.14 E+00 2.Gl E+00 1.59 E+00 1.47 E+00 3.19 E+00 2.2G E-01 8.61 E+00 Aprilc

(< 2. 1 E-07) 1.66 E+00 1.33 E+00 3.42 E-02 2.30 E-01 8.77 E+00 Mayc 1.91 E-01

(<2.7 E-07) 4.50 E+00 8.90 E+00 1.03 E+00 1.43 E-01 5.14 E-ol 1.78 E+00 c

June 3.55 E-01

~

(<4.1-E-07) 1.81 E+00 6.51 E+00 3.41 E-01 1.0 E-1 I-135

-La-140 mCi 1.00 K+02 mCi

(<2. 1 E-08) 1.85 E+02

(<1, 8.

E-08)

(<l.4 E-08)

(<1.6 E-08)

(<1.1 E-08)

(<1. 3 E-08)

Hn-54 Na-24 Nb-95 Ru-103 Sb-124

.Sb-125 Sr-89,'Ci mCi mCi mCi mCi mCi mCi 3.91 E-ol 3.47 E+01 1.43 E-01

~ 1.7 E+00 1.24 E+00 4.1 E+DD 4.4 E+00 1.02 E+02 8.99 E-ol 2.77 E+00 2.84 E+00 1.96 E+00 1.65 E-01 2.70 E-01 7.1 E-02 8.26 E-01 1.9 E-01 4.6 E-02 4.95 E-01 7.05 E-01 1.3 E-02 5.26 E-Ol 3.76 E-01 4.82 E-01

.30 E-0 7.4 E-02 2.6 E-D1 6.36 H-02 2.2 E-01

9. 3 E-02 NOTE:

Numbers in parenthesis represent maximum sensitivity in uCi/ml.

~ ~

1978 Table I Report of Radioactive Effluents:

Liquid Total Page 3

iso tope Unit January Feb rua Harch c h ril Havc c

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 Unidentified mCi mCi 6.54 E-01 5.84 E+00

~

3.26 E-Ol 3.33 E&1 2.02 E&l 1.68 E+Ol 1.44 E+Ol 1.19 E+01 Total mCi 1.07 E&3 1.66 E+03 4.62 E+01 NOTE:

Numbers in parenthesis represent maximum sensitivity in uCi/ml.

3.01 E+01

~

11 3.39 E+01 2.23 E+01 ~

e

0' 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 Ba-140 mCi mCi 3.16 E-01

(<3.6 E-07) 1.11 E+00 7.95 E-01 2.65 E-Ol:

(<3.4 E-08)

(<3.2 E-07)

(<2.1 F.-07) 1.91 E-01

(<2.7 E-07) 3.55 E-01

(<4.1 E-07)

Co-58 Co-60 Cr-.51 Cs-134 Cs-137 Fe-59 I-131 mCi mCi mCi mCi mCi mCi mCi 3.67 E+00

~

3.82 H+00

(<2. 8 E-07) 1.02 E+00 2.02 E+00 5.19 E-02 1.67 E+01 2.83 E+01

9. 3 E+00 2.81 E+00 1.67 E+Ol 4.48 E+Ol

(<9.2 H-08) 2.13 E+01 3.96 E+00 2.08 E+00 1.59 E+00 2.29 F.-Ol

,6. 7 E-01 2.26 E-01 4.4 E+00 1.66 H+00 1.33 F+00

{<1.8 E-07) 3.42 E-02 2.3 '-01

(<4.1 E-08)

8. 77'+00 4.20 E+00 6.25 H+0 1.03 E+00 1.43 E-Ol 5.14 E-01

(<5.4 E-08) 1.78 E+00 1.74 E+00

{<2.8 E-07)

<5.3 E-08 3.41 E-01

(<9.6 H-08) 1.05 E-01 La-140 Hn-54 mCi.

mCi

(<2.1 E-08)

.3.91 E-01 7.04 E-Ol 1.65 H<<ol 4.6 E-02

(<1. 8 E-08)

(<1. 4 E-08)

(<1. 6 E-.08)

<1.1 E-08 5.26 E-Ol

<.3 H-08 2.47 E-Ol Nb-95 Ru-103 Sb-124 mCi mCi mCi 1.43 E-01

(<3.5 '-08) 1.7 E+00 8.99 E-01

(<7.3 E-08) 2.77 E+00 2.7 E-01 7.1'-02 8.26 E-01

{<2.3 E-08

(<1.9 E~08 4.95 E-01 3.76 H-01

<2.8 E-8 4.82 E-Ol 6.36 H-2.29 E-01 Sb-125 Sr-89 Sr-90 Zr-95 mCi mCi mCi mCi 1.14 E+00 3.51 E-02

(<3.0 E-09)

(<6.2 E-08) 2.84 E+00

(<2.9 E-09) 1.37 E+00 9.8 E-02 7.05 E-01

1. 3 H-02 3.26 E-01

(<5. 7 E-08)

(<3.4 E-08)

(<2.9.

E-09)

(<3. 1 E-09)

(<3.0 E-09).

9.30 E-01 7.4 2.5 E-02

(<5. 7 E-08) 6.77 E-ol 9.3 'E-02

<3.4 H-09

(<8.2 E-08)

Total 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.

1978 Table I Re ort of Radioactive Effluents:

Liquid Secondar S stem

~

Pa e

5 Isotope Co-58 Co-60 Cs-134 Cs-136 Cs-137 Cs-138 P-18 I-131 I-132 I-133 I-134 I-135 Mn-54 Na-24 Unit mCi mCi mCi mCi mCi mCi mCi mCi'Ci.

mCi mCi mCi mCi January

5. 2 E-01 5.50 E+00 1,.33 E+01.

3.13 E+00 1.53 E+Ol 4.49 E+01

1.37 E+02

'.3.22 E+02

'6.66 E+01 2.63 E+02 2.33 E+Ol 1.00 E+02 3.47 E+Ol February 2.42 E+00 2.79 E+00 2.X1 E+01 3.25 E+01 9.13 E+Ol 3.27 E+02 2.26 E+02 1.22 E+02 3.19 F+02 5.36 E+Ol 1.85 E+02

3. 7 E+00 1.02 E+92 March 1.18 E+00.

5.26 E-01 1.24 E&0 2.52 E+00 4.21 E+00 April May 3.0 E-01 2.65 E+00 June 6.88 E-02 6.5 E-01 1.21 E-02 Sr-89 Sr-90 7.r-95

'Ci mCi mCi 4.06 E+00

(<3.1 E-09) 6.54 E>>01 1.96 E+00 9.5 E-02

(<3.1 E-09)

(<3.1 E-09)

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 Kr-85m mCi January

(<2.1 E-08)

February

(<3.0 E-08 Harch

(<1.8 E-Og)

April

(<2.9 E-08)

Hay June 1.04 E+00

(<1.6 E-.08)

Xe-133 Xe-133m Xe-135 mCi mCi mCi 3.88 E+00

(<2.5 E-07.)

2.14 E+00 3.93 E+01

(<2.5 E-07) 1.71 E+00 2.6G E+00

(<1.7 E-07) 6.05 E-01 3.61 E+02 6.12 E+00 3.45 E+00 2.70 E+02 8.76 E+00 4.5 8+01 7.14 E+00

(<1.6 E-07) 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 Xe-135

-'mCi

(<2.8 E-08).

mCi

(<2.5 E-07) 8,16 E-01 6.05 E-01

(<2.5 E-07)

(<1. 7 E-07) 6.12 E+00 3.45 E+00 8.76 E+00 4.5 E+01

(<1.6 E-07 2.89 E-01

'Secondarv Svstem Xe-133 Xe-135 mCi mCi 3.43 E+00 2.14 E+00 5.71 E+00 8.95 E-01 NOTE:

Numbers-in parenthesis represent maximum sensitivity in pCi/ml.

14

I 978 Table II Report of Radioactive Effluents:

Airborne Page 1

January February March April Hay June Fissi6n and Activation Gases

1. Total Release (Ci)

2. Avg Rel Rate for Period(pCi:/sec) 4.5 E+02

5. 1 E+02 1.22 E+03 l.'23 E+03 1.88 E+03

, 7;0 E+02 2.43 E+03 9.4 E+02 2.09 E+03

7. 7 E+02 1.30 E+03 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

2. Av Rel Rate for Period pCi/sec) 1.5 E-01

5. 6 E-02 9.1 E-02

3. 8 E-02

2. 7 E-02 1.0 E-02 6.5 E-02 2.5 E-02 7.9 E-03 2.9 H-03 2;3 E-03 8.8 E-04

Particulates

1. Particulates with tl/2>8d (Ci)

2. Avg Rel Rate for Period(pCi/sec) 5.35 E-03 2.0 E-03 2.60 E-02 1.1 E-02 1.85 E-02 6.9 E-03 6.98 E-04 2.7 E-04 2.34 E-04 8.7 E-05 1.14 E-04 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

1. Fission and Activation Gases

(%)

2. I-131 and Part.(tl/2>8d)

(%)

uarter I 4.6 H+00 3.5 E+00 6.2 H+00 9.6 E-01 3TE:

Numbers in parenthesis represent maximum sensitivity in pCi/cc.

19 78 Table II ~ Airborne Releases Particu ate

=Isotope Ag-110m Unit January Ci

(<4. 1 E-13) 1.5 E-04

.February March A ril

(<8. 8 E-3.3)

(<9.1 E-14)

(<4.4 E-14)

June

(<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 Co'-.57

-Co-58 Ci 3.5 E-05 7.1 H-06 1.8 E-03

(<2.1 4.2 E-12)

E-05 1.8 E-n2 3.2 E-05

1. 3 H-02

(<3.0 E-14) 4.6 H-04

(<1.8 E-12)

(<2.1 E-13)

(<1.0 E-13)

(<1.3 E-14) 6.0 E-05

(<1.3 E-13)

(<1.7 E-14) 2.4 E-05 Co-60 Cr-51 Ci 2.8 E-03 1.2 E-04 3.5 2.6 E-03 E-03

, 2.8 E-03 1.4 E-03

1. 4 E-04

(<4.8 E-13

4. 2 E-05

(<2.6 E-13 6.6 E-OS

<1.6 F.-13 Cs='134 Cs-136 Cs-137 Ci

l. 1 E-05 Cg 5.9 E-06 3.1 E-05 1.0

(<6.1 2.7 E-05 E-13)

E-05 3.5 E'-05 1.2 E-05 5.2 E-05 2.5 E-05

(<6.1 H-14)

5. 3 E-05 2.0 E-05

(<5.'5 E-14) 3.2 E-05 4.2 E-06

(< 2. 2 E-14) 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 Ru-103 1.5 E-04 1.5 H-04 3.8

(<8.1 E-04 E-13) 2.4 E-04

~

(<8.3 H-14)

(<6,9 E-13)

'(<7. 1 E-14)

(<4.0 E-14)

(<4.0 E-14

<1.9 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 Sr-89 Sr-90 Ci Ci Ci

<5.8 E-13) 6.8 E-06

6. 7 H-07 1.3 6.9 4.4 E-06 E-07

(<1. 7 E-12) 1.1 H-OS 1.6 E-08

(<1.9 H-13) 1.7 E-06

(<2.5 E-16)

(<9.8 E-14) 2.9

'H-06 1.4 E-07

(<5.4 E-14) 7 H-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 Fission and Activation Gases Table II Airborne Releases Gaseous Fage 3

Isotope Ar-41 Kr-85 Kr-85m Kr-87

'r-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Unit Ci Ci Ci Ci Ci

- Ci Ci January 2.27 E+00 2.45 E-01 1.86 E&0 1.94 E+00 2.29 E+00 4.97 E+00 1.18 E+03 3.99 E+00 1.32 E+01 3.41 E+00 1.96 E+00 February 3.31 E+00 1.34 E+00 2.87 E+00 3.10 E+00 3.57 E+00 1.18 E+00 1.18 E+03 2.29 E+00 1.78 E+01 6.05 E+00 3.72 E+00 March 4.08 E+00 2.49 E-02

.9.53 E-02

(<3. 7 E-07)

(<1.0 E-06) 3.38 E-02 1.87 8+03 3.4 E-01 1.77 E+00

(<5.8 E-07)

(<8. 4 E-07)

April 1.35 E+Ol 4.03 E-01

2. 8 E-01

(<2.6 E-06) 1.07 E-01 1.21 E-Ol 2.41 E+03 1.01 E+00 5.32 E+00 1.74 E-01

(<1.1 E-05)

May 5.56 E+00 1.70 E-01 4.30 E-Ol

(<3.0 E-06) 3.35 E-01 1.37 E+00 2.07 E+03 4.13 E+00 8.98 E+00

(<1.4 E-06)

(<8.4 E-06)

June 4.01 E&0

(< 3.6 E-05) 2.70 E-Ol

(< 2. 7 E-07) 1.55 E-01 1.17 E+00 1.28 E+03 3.19 E+00 6.37 E+00

(<1. 6 E-07)

(< 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

'I-131 Unit Januarv 1.5 E-01 February 9.1 E-02 March 2.7 E-02 A ril 6.5 E-02 Mav 7.9 E-03 June

2. 3 E-03 I-133 I-135 3.5 E-02 7.3 E-03 2.8 E-n2 1.1 E-02

l. 2 E-02 2;2 E-03 2.1 E-02

1. 8 E-03 6,8 E-04 7.6 H-03

(<1.2 E-13)

(<1.4 E-13)

'. Br-82

Total 3,0 E-04 Ci 1.9 E-01 2,5 E-04 1.30 E-ol

4. 1 E-04 4.2 E-02 1.0 E-03 9.5 E-02 3.0 E-04 1.00 E-02 3,0 E-

> NOTE:

Numbers in parenthesis represent maximum sensitivity in pCi/cc.

Packed Total RADlOACTZVE HASTE January 1, 1978 to June 30, 1978 Ci 419.263 Cu. Ft.

40,035.7 On site as of July 1, 1978

6. 617 689 '

Dat 5ll 13 17 19 20 23 26 28 2

6 8

10 13 16 23 6

9 13 14 15 16 17 20 21 22 23 25 10 12 12 19 20 21 24 28 3

4 5

9 10 12 15 16 16 19 19 es of Shipment and Disposition January 1978 January 1978 January 1978 January 1978 January 1978 Ja'nuary 1978 January 1978 January 1978 January'978 February 1978 February 1978 February 1978 February 1978 February 1978 February 1978 February 1978 Iarch 1978 March 1978 Maxch 1978 March 1978 March 1978 March 1978 March 1978 March 1978 March 1978 March 1978 March 1978 March 1978 April 1978 April 1978 April 1978 April 1978 April 1978 April 1978 Apx'il 1978 April 1978 May 1978 May 1978 May 1978 May 1978 May 1978 May 1978 May 1978 May 1978 May 1978 May 1978 May 1978

.Buried in Barnwell, South Carolina

Dates of Shipment and Disposition t

20 May 1978 23 May 1978 23 May 1978 31 May 1978 13 June 1978 13 June 1978 20 June 1978 22 June 1978 22 June 1978 26 June 1978 28 June 1978 30 June 1978 Buried, in Barnwell, South Carolina I~

Total Shipments 59

TURKEY POINT:

Units 3

8 4

Environmental 'Radi olo ical 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 Monitorin Pro ram Period Covered:

This current repor t covers the period from

~y,1 8

J 0.178.

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 concentration levels of '"i~1n, "Co, "Co, 'r,

'"Cs, 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 had been a continuous exposure to radionuclides having concentration 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 tledium or, Pathway Sampled l.

Air Filters Unit Analysis for Number of Sites Samples Analyses than Range All Indicator Locations Sample Location Distance and Direction ttean Location with Hihest tiean Control Location Range Hean Range tier "al')

Ncnrout:aa

,"ae paOI'teed at aSOI't,',aan 1.1 Air Particu-latess l.l.a Air'odines pCi/m'Ci/m'B 1$ 1I 214 212 214 212 0.08 ND

.02-0.28 T-71: Girl Scout Camp; Hone 0.12 0.04-0.28 ND

0.11 0.05-0.26'OIIO HoIIe 1.2 Direct Radia-tson 1.3 ~Preci itatica pRem/

hr pCi/L GarIma scan 132 23 132 23 5.0 ND 2-8 T-64: Natoma Substation, Hiami, ENE, 30 miles None 6.2 5-7 6.2 ND 5-7 teone Nolle GB-DS GB-UDS sH 23 23 23 23 23 23 7.0

<200 3-22 T-571 Dolan's

Farms, WtiW,

~4.

miles Hone None 8.5 4-22 6.5 ND

<200 3-15 Hedivm or Pathway Samoled Unit Analysis for Sites Number of Samples Analyses Nean Range All Indicator Locations Sample Location Distance and Direction Hean Range Location with Hi hest Wean Range Hean Control Location~

~

2.

Water

,2.1 Estuarine pCi/L

'H Sr-89 Sr-90 10 10 10 20 20 20 20 20 20 276 ND 5200-1200 T-81: Card Sound, New

~isc arge Canal; South, 6 miles None None 960 720-1200 None 2.1.2 Coolinq

~ana pCi/L

'H 69Sr 90Sr 12 12 12 12 12 12 5792 ND 3700-9000 ND-2 T-84:

Discharge Canal, southside of bridge None T-97: Loch Rosetta; on-site 6400 5000-9000 1.5-2.5 None 2.1.3 Fresh Water pCi/L GB-DS Canals Gg-UDS 12 12 12 12 178 ND 3-400 T-75: Florida City Canal 351 NNW, 1.5 miles None 290-400 None.

12 12 330

<200-660 None 460 380-660 3-

Medium or PathMay Samoled Unit'nalysis f01 Sites Number of All indicator Locations Range Samples Analyses than Sample Location Distance and Direction llean Range Location Mith Hi hest Mean Hean Range Control Location

,r.n w,

~ c

~ a v

4

.Qas~s',.',

2.3 Ground Water ueuus pCi/L

'H 2.2 Potable Mater pCi/L GB-DS M~As GB-UDS 12 12 4.6 ND

<200 711 ND-8

<200-2200 T-73: City of Homestead Water System; MNW, 9 mi.

None None T-91: Well G10A, SW, 2.0 850

~1&s 5-7 200-1800 None t

I I

None OSSr

'oSr 12 12 12 12 ND T-92: Mell G24A;

SSW,

~4.

miles None None 2100 2000-2200 64

tledium or Pathway Samnled Unit Analysis for Sites Number of All Indicator Locations Range Samples Analyses Nean Sample Location Distance and Direction Ilean Range Location with Hi hest Nean Control Location~

Hean Range

>>C~9.a"Ga 0l.

3.0 Bottom 3.1

~Cool i~

Canal 3.2 Estuarine pCi/k 88Co 80Co 9SZr

'"Nn 148Ce 197Cs 89 Sr 905r pCi/kg '""Ce 98Zr 89Sr

9051, 308 1606 205 100 300

'40 ND ND 226 40 ND HD ND-1000 ND-3400 ND-700 ND-200 ND-600 ND-720 ND-140 T-84: Discharge Canal, Southside of bridge None Hone T-94: Pumpkin Key; SSE, 88m1 les Hone None 308 HD-100 1606 ND-340 205 ND-700 100 HD-200 300 ND-600 440 680 640-72 110 80-140 Hone Hone 9 an

lledium or Pathway Samoled Unit

- Analysis for Number of Sites Samples Analyses Mean Range All Indicator Locations Sample Location Distance and Direction llean Location with Hi hest Nean Range Control Location~a~

Hean Range llu!'.QQ< o; nOnl il:cap eel g" 4.0 Biota 4.1 Crustacea 4.2.A Fish Carnivore 4.2.8 Fish Herbivore pCi/k pCi/kg pCi/kg 1% 4Ce

4951, 905r 106Ru 49Sr 90Sr 104Ru 4 95r 90Sr 100Ru 6

6 160 ND ND ND ND ND 800 ND 1.3 ND ND-400 700-900 ND-8 T-951 Long Arsenicker Key; ESE, 4.3 miles None Hone None None Hone T-81:

Card Sound, Hew

~isc arge Canal Hone T-95: Long Arsenicker Key; Card Sound,

ESE, 4.3 miles Hone 400~c~

Booed>

8(e) 300-500 700-900 5-11 None hone Hone

tledium or Pathway Samnled Unit Analysis for Sites Humber of All Indicator Locations Range Samples Analyses Hean Sample Location Distance and Direction llean Range Location with Hi hest Hean Hean Range Control Location I

4: '4 I

'. '4 sue e 4.3.A llanatee brass pCi/k 9S Zr 095r 90Sr 162 ND ND 120-200 T-69; Elliott Key, South 200 nd,

ESE, 7 miles Hone Hone 150-250 Hone 4,3.B

~Son es pCS/kg 9SZr 196 D-400

-69: Elliott Key, South 400 n

, ESE, 7 miles00-500

~

ekone LI 4

14444Ce 10eRu 2366 300 00-3400 D-700

-59: El 1 iott Key; E, 8 1 es 3400 700 200-3600 00>>

1000

Vedium or Pathway Sampled 5.0 Terrestrial 510th Analysis for Number of Sites Samples Analyses Hean Range All Indicator Locations Sample Location Distance and Direction llean Range Location with Hi hest Hean Hean Range Control l.ocation(

)

~ \\

FVead, vie j 5.2.1 Small (f)

Animals pCi/kg '"Cs 49Sr 90Sr 80 ND 70-90 T-58: Onsite Entrance Road None None 80 70-90 Nor o 5.2.2

~pood Cro pgi/kg e'Sr 90Sr ND 1-29 None T-52: Florida City Sub-station; West, 8 miles 2g(g) 27-31 None 5.2.3

~Man rove Leaves pCi/kg 99Zr 09Sl 7

7 146 100-220 T-58: Onsite Entrance Road

'one 220 170-270 None

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

- 28

tlediun or Pathway Samnled Unit Analysis for Number of Si tes Sampl es Analyses than Range All Indicator Locations Location with Hi hest Hean Sample Location Distance and Direction flean Control l.ocation~

~

Range Mean Range 5.3 Soil pCi/kg rs7Cs lbbCe 106Ru ssZ 89Sr s4Sr 397 ND-660 389 ND-900 71 ND-500 196 tiD-520 ND T-52: Florida City Sub-

station, West, 8 miles T-58: Onsite Entrance Road None None 660 900 500 520 640-68 800-1000 300-70 460-58 hotes

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

T'