ML18227A272

Semiannual Operating Report of Radioactive Effluent Releases and Environmental Radiological Monitoring for Period Januay 1, 1976 Through June 30, 1976

ML18227A272
Person / Time
Site:	Turkey Point
Issue date:	08/31/1976
From:	Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML18227A272 (74)

Text

TURKEY POINT PLANT UNITS 5 AND 0 SEMIANNUAL OPERATING REPORT OF RADIOACTIVE EFFLUENT RELEASES AND ENVIRONMENTAL RADIOLOGICAL MONITORING FOR PERIOD JANUARY 1, 1976, THROUGH JUNE 50, 1976 IN COMPLIANCE WITH TECHNICAL SPECIFICATION 6,9, 0

f

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B 0

TABLE OF CONTENTS

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INTRODUCTION s

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s s

e e

s e

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e s

s e

e s

s 2

(A)

RADIOACTIVE EFFLUENT RELEASES s

e s

s s

s s

s s

e s

s e

(1)

LIQUID RELEASES s

s

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(2)

AIRBORNE RELEASES s

s e

s s

s s

a s

s s

s s

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s 13 (3),

SOLID l'(ASTE BUR IAL s

e s

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s s

s 20 (B)

RADIOLOGICAL!ENVIRONMENTAL MONITORING

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s 21

v III

0 THIS REPORT IS SUBMITTED IN ACCORDANCE WITH TURKEY POINT PLANT TECHNICAL SPECIFICATION SECTION 6e9,4,-

THIS REPORT COVERS THE DATA NECESSARY TO MEET THE SEMI-ANNUAL REPORTING REQUIREMENTS FOR (A) RADIOACTIVE EFFLUENT RELEASES AND (B) ENVIRONMENTAL RADIOLOGI CAL NONITOR ING e FOR THE PERIOD OF JANUARY li 1976'HROUGH JUNE 50,

1976,

Radioactive Effluent Releases 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 Ali u liquots of representative pre-release samples were either isotopica13 analyzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 2m gas flow proportional counter.

The efficiency of the gas flow proportional counter is adjusted so that the activity determined by gross beta-gamma analysis approximates the isotopic activities determined, by gamma spectrum analysis and selected beta determinations, exclusive of tritium and dissolved gases.

The above procedure was followed for all releases from the waste disposal system and for secondary system batch releases.

Frequent periodic sampling and analysis were used to conservatively estimate the quantity of radioactivity released via the steam generator blowdown system.

The following comments will aid in the interpretation and evaluation of the liquid release data presented in Table I, pages 1 through 7:

1.

The reported values in Table E, 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 generators during primary to secondary leakage conditions in the steam gener'ators.

I Cl

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 pages 5 and 6 are for the secondary system only.

During primary to secondary

leakage, release of several short-lived nuclides occurred from the secondary 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.

Meekly 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 ana'lyzed 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.

I

I At least one representative batch of liquid effluent from the waste 0

disposal system was analyzed monthly for dissolved fission and activation gases by use of gamma spectrum analysis.

/

1 The resulting isotopic concentrations were multiplied by the total volume released for the month in order to estimate the total dissolved gases released.

If more than one batch of effluent was analyzed, the concentrations are weighted in an appropriate manner.

The results are totaled on a monthly basis in Table I, page 7.

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 tr'itium, gross alpha and selected beta emitters.

7.

A page of notes has been added, following Table II, to help explain some of the results in Table I which have been superscripted with a lower case letter.

TABLE I REPORT OF RADIOACTIVE EFFLUENTS:

LIQUID Page 1

Liquid Peleases January February

'!arch April

)fan '.

June A.Gross Radioactivity (B,y) 1.Total Release (mCi)

7. 62. E+02 uarter III

'3.96 E+02 1.80 E+02 5.58 8+00 3.34 E+02

2. 06.E+03 2.Av Concentration Durin Releases (pCi/ml) 2.6 E-09 1.6 E-09 1.9 E-09 1.2 E-10 6.3 E-09 1.6 E-08 4.Max Concentration Released (pCi/ml)

1. 1 E-'Q8 3.Av. Concentration for Month (pCi/ml) 2.6 E-09

~ 1.5 E-09 2.5 E-08 6.0. E-10 2.1 E-ll 2.1. E-08 7.6 E-i.O 1.9 E-09 1.9 E-.07

9. 4 E-09 7.0'-07 5.Percent of Technical Specification L'imit for Total Activity Released 2.68 E+Ol.

g I

P 4.80 E+01 B.Tritium

l. otal Release (Ci) 8.38 E+01 7.03 E+01 6.26 E+01 7.98 E+01 3.80 E+01 8.40 E+Ol 2.Av Concentration Durin Releases (pCi/ml) 2.9 E-07 2.8 E-07 6:5 E-07 1.8 E-O6 7.2 E-07 6.6 E 3.Av Concentration for Month (pCi/ml) 2.9 E-O 2.6 E-07 2.1'-07',1 E-07 2.1 E-07 3.8 E-07 C.Dissolved 1toble Gases 1.Total Release mCi 9.34 E+00 1.61 E+Ol 2.34 L+Ol (<3.4 F.-06 6.44 E+01 2.71 E+02 2..~v

. Concentratio Duri Re eases pCi/ml 3.Avg Concentration for Month (pCi/ml

3. 2 E-11

3. 2 E-ll 6.4 E-ll 2.4 E-10 (<7.6 E-17 6.0 E-ll 7.8 E-ll (<1.3 E-17 3.6 E-10 1.2 E-09 1.2 E-09 2.1 E-'09 D.Gross Alpha Radioactivit 1.Total Release (mci 3.Av Concentration for Month (pCi/ml)

Av Concentration'urin Releases ICi ml

(<2.3 E-08 (<7.2 E-09 (<3.9 E-09

<7.9 E-20

<2.9 E-20

<4.1 E-20

(<7. 9 E-20) (<2. 7 E-20) (<1. 3 F;20)

(< 3. 1 E-09

8. 6 E-02

<6.9 E-20 1.6 E-12

(<1.2 E-20) 4.8 E-13 1.0 E-02 7.7 E-14 4.5 E-141 E.Volumes 1.Vol of Li uid Waste to Dischar e

. (Liters) 2.58 E+07 2.Vol of Dilution Water During Releases(Liters 2.9 E+ll 2.71 E+07 2.5 E+ll 2.7 E+ll-3.Vol of Dilution Water for Month (Liters) 2.9 E+ll he s i narentheses renresent maximum sensitivity in pCi ml.

5.68 E+06

9. 6 E+10 3.0 E+11 2.6 E+06 5.08 E+06 4.5 E+10 5.3 E+10 2.6 E+11 1.8 E+ll 8.05 E+06 1.3 E+ll 2.2 E+11

~ '

TABLE I REPORT. OF RADIOACTIVE EFFLUENTS:

LIQUID TOTAL Page 2

Isoto e

Unit January

'February March April May June A -110m Ba-139 Ba-140 Ce-144 Co-57 mCi mCi mCi

. mCi mCi 1.0 E+00

~

(<1.7 E-07)

(<3.9 E-07)

(<1.4 E-07) 8.1 E-02

(<3.9" E-07)

(<1;1 E-07)

(<2.4 E-07)

(<2.4 'E-07)

(<5.9 E-08)

(<1.1 E-07)

3. 3 E-02 2.8 E+00 2.33 E+02

(<1.9 E-07)

Co-58 mCi 7.8 E+00 2.4 E+00 1.74 E+00 9.6 E-01 8.0 E+00 3.82 E+Ol Co-60 Cr-51 Cs-134 Cs-136 Cs-137 Cs-138 mCi mCi mCi mCi mCi mCi 4.7 E+00 1.37 E+00 7.7 E-ol 1.4 E-ol 1.33 E+00 5.5 E+00 3.8 E-01 6.0 E+00

(<1.1 E-08) 4.6 E+00 3.02 E+01 1.04 E+00 4.6 E-01 1.76 E+01 7.3 E+00

(<1.5 E-'08)

(<3 5 E-07)

(<8. 2 E-08) 6.0 E+00

(<1.4 E-08)

(<2.6 E-08)

(<9.8 E-09) 3.4 E+00

(<1.9 E-07) 5.7 E+00 1;1 E+00 9.7 E+00 1.33 E+Ol 7.3 E+00

(<2.1 E-07) 7.4 E+01

~

1.31 E+Ol 1.17 E+02 8.4 E+00 F-18 Fe-59 I-131 I-132 I-133 mCi mCi mCi mCi mCi mCi 2.30 E+02 4.0 E-01 1.57.E+01 5.20 E+Ol 7.51 E+Ol 4.44 E+Ol 1.06 E+01

(<2.8 E-08) 3.91 E+Ol 5.49 E+01 8.68 E+Ol 5.66 E+Ol 3.9.

E+00

(<5.6 E-08) 2.43 E+01 l.3 E+01 2.7 E+Ol 1.54 E+Ol 9.2 E-02 5.5 E-01

3. 5 E+00

~

(<3.6 E-08) 8;3 E+01 3.01. E+Ol

8. 8 E+01 3.09 E+01 9.3 E+00

(<2.4 E-08) 6.79 E+02 5.8

- E+01 4.57 E+02 1.62 E+01 I-135 La-140 mCi mCi 8.14 E+Ol 2.8 E-01 7.77 E+Ol 4.1 E-02 2.54 E+Ol 3.93 E+01

(<2. 6 E-08)

(<5. 8 E-09)

(<1. 1 E-08) 1.05 E+02 3.16 E+Ol Mn-54 Mo-99 Na-2 Nb-95 mCi mCi mCi mCi 1.27 E+00 2.13 E+02

<7.2 E-08

(<1.7 E-08) 8.6 E-04 1.52 E+Ol

<1.3 E-08 1.1 E-01 1.0 E-01 8.2 E+00

<2.8 F-0 E-08)

(<1.1 E-08 1.7 E+00 3.2 E+00 3.0 E+00 2.0 E-01 3.11 E+01 2.03 E+01 7.1 E+00

~

<1.1 E-08 NOTE:

Numbers in parentheses represent maximum sensitivity in pCi/ml.

TABLE I REPORT OF RADIOACTIVE EFFLUENTS:

LI UID TOTAL CONT Pa e 3 Isotope Sb-124 Sb-125 Sr-89 Sr-90 Sr-91 Tc-99m Unit mCi mCi mCi mCi mCi mCi January 3.4 E-01 2.6 E+00

~

2.4 E-ol February 6.1 E-01 4.3 E-01 2.1 E+00

4. 7 E-02 1.3 E-01 March 7.2 E+00:

4,0 E+00 5.7 E-01 1.3

~ E-02 1.1

= E-01

April,

(<1. 7 E-08) 6.1 E-Ol 8.3 E-03 May 8.5 E-01 5.2 E-01 1.89 E+00 2.9 E-ol 2.0 E-01 June

8. 2 E+00

1. 6 E-01 5.62 E+Ol 1.65 E+00 4.09 E+01 1.77 E+Ol Zn-65 Zr-95 mCi mCi

(<8. 1 E-08)

(<2. 8 E-08)

(<6.5 E-08)

(<1.1 E-07)

(<2.0 E-08)

(<4.5 E-08)

(<1. 9 E-08)

(<1.8 E-08

<3.4 E-08

<3;0 E-08

<2. 6 E-08

<2.0 E-08 Unidentified mCi

2. 8 E+01 2.4 E+00

l. 7 E+01 2.9

-K+00

5. 8 E+00 2.4 E+01 Total mCi 7.62 E+02 3.96 E+02 1.80

+

5.58 E+00 NOTE:

Numbers in parentheses represent maximum sensitivity in pCi/ml.

TABLE I REPORT OF RADIOACTIVE EFFLUENTS:

LIQUIDS.WASTE DISPOSAL SYSTEM PAGE 4 Isoto es A -110m Unit mCi January February March April May 8.1 E-02 June Ba-140 Ce-144 Co-58 Co-60 mCi mCi mCi 2.4 E+00 1.8 E+00 1.02 E+00 3.4 E-01

(<4.8 E-07)

(<1.7 E-07)

(<3. 9 E-07)

(<1. 4 E-07)

(<,3. 9 E-07)

(<2. 4 E-07) 1.74 E+00 4.6 E-01

6. 1 E-Ol 6.3 E-02 2.3 E+00 4.2 E-ol 2.4 EWO 2.7 E-01

(<1.1 E-07)

(<2.4 E-07)

(<2.1 E-07)

(<5. 9 E-08)

(<1. 1 E-07)

(<1. 9 E-07)

Cr-51 1.37 E+00 3.8 E-ol

(<3. 5 E-07)

(<8.2 E-08)

(<1.9 E-07)

(<2.1 E-07)

Cs-134 Cs-136 mCi mCi 2.0 E-01

(<2.1 E-08)

(<1.9 E-07)

(<1.1 E-08) 1.4 E-02

(<2.6 E-08)'<1.4 E-08)

(<2.7 E-08)

(<3.0 E-08)

(<9.8 E-09)

(<1.7 E-08)

(<1.5 E-08)

Cs-137 Fe-59 mCi 5.4 E-01 1.4 E-01

(<1. 1 E-07)

(<2. 8 E&8) 2.1 E-01

(<5.6 E-08)

(<1.5 E-08) 9.2 E-02 8.8 E-02 3.4 'E-01

(<3;6 E-08)

(<2. 4 E-08)

I-131 1.14 E+00 1.96 E+01 1.60 E+Ol 5.5 E-ol 2.2 E-01 4.4 E+Ol La-140 Mn-54 Nb-95 mCi mCi mCi

(<2. 2 E-07) 4.1 E-'02 3.4 E-Ol

(<1.7 E-08)

(<7.'2 E-08)

(<1.3 E-08)

(<2.6 E-08).

1.1

=E-01

(<2.8 E-08)

(<5.8 E-09)

(<1.1 E-08) 1.2 E+Ol

<1.5 E-08

(<1. 5 E-08) 5.9 E-02.

(<1.1 E-08)

(<1;9 E-08)

(<1.1 E-08)

Sb-124 Sb-125 mCi mCi

3. 4 E-01 6.1 E-01 4."3 E-01 7.2 E+00 4.0 E+'00

(<l. 7 E-08)

8. 5 E-01 5.2 E-01 1.0 E+00 1.6.

E-01 Sr-.89 Sr-90 mCi mCi 1.4 E-02 4.9 E-03 7.4 E-03 4.0 E-03

(<5.9 E-09)

(<1.5 E-09) 2.3 E-02 8.3 E-03 3.1 E-Ol 1.0 E-02 6.0 E+00

<8.3 E-09 Zn-65 Kci

(<8.1 E-08)

(<2.8 E-08)

(<6.5 E-08)

(<1.9 E-08)

<3.4 E-08

<2. 6 E-08

'r-95 mCi

(<1.1 E-07)

(<2.0 E-08)

(<4.5 E-08)

(<1.8

. E-08)

(<3.0 E-08)

<2.0 E-08 8.15 E+00 2.26 E+Ol 2.97 F+

1 Total NOTE:

Numbers, in parentheses represent maximum sensitivity in pCi/ml.

6.62 E+Ol

TABLE I REPORT OF RADIOACTIVE RELEASES:

LIQUID - SECONDARY SYSTEM Page 5

Isotope Ba-139 Ba-140 Co-57 Co-58 Co-60 Cs-134 Cs-136 Cs-137 Cs-138 F-18 Fe-59 I-131 I-132 I-133 I-134 I-135 La-140 Mn-54 Mo-99 Na-24 Nb-95 Sb-124 Sr-89 Sr-90

'Unit mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi mCi.

January 1.0 E+00 5.4 E+00 2.9 E+00 5.7 E-01 1.4 E-01 7.9 E-01 2.30 E+02 4.0 E-01 1.46 E+01 5.20 E+01 7.51 E+Ol 4.44 E+01 8.14 E+Ol 2.8 E-01 9.3 E-ol 2.13 E+02 2.6 E+00 2.4 E-01 February 1.4 E+00

5. 2 E+00 6.0 E+00 4.5 E+00 3.02 E+Ol 1.06 E+Ol 1.95 E+Ol 5.49 E+01 8.68 E+01 5.66 E+01 7.77 E+01 8.6 E-04 1.52 E+01 2.1 E+00 4.3 E-02 March 5.8 E-01 6.0 E+00 1.74 E+01 7.3 E+00 3.9 E+00 8.3 E+00 1.3 E+01 2.7 E+Ol 1:54 E+01 2.54 E+t)1 1.0 E-01 8.2 E+00 5.7 E-01 1.3 E-02 April 3.5 E-01 4.0 E-Ol 5.9 E~01 May

3. 3 E-02 5.7 E+00 3.0 E+00 5.7 E+00 1.1 E+00 9.6 E+00 1.33 E+Ol 3.5 E+00

~

+

3.01 E+01.

8;8 E+01 3.09 E+Ol 3.93 E+Ol 1.6 E+00 3.2 E+00 3.0 E+00 2.0 E-OI 1.58 E+00 June 2.8 E+00

'2.33 E+02 3.58 E+0

.0 E+00 7.4 E+01 1.31 E+Ol 1.17 E+02 8.4

'E+00

9. 3 E+OO

5. 8 E+Ol 4.57 E+02 1.62 E+01 1.05 E+02 1.96 E+01

. l.

+Ol 2.03 E+Ol

'.1 E+00 5.02 F+01

.6 F+00

TABLE I REPORT OF RADIOACTIVE RELEASES:

LIQUID SECONDARY SYSTEM (CONT)

Pa e

6 Isotope Sr-91 Tc-99m

'Unit

'mCi January

-February 1.3 E-01 March 1.1 E-01 A ril Ma 2.0 E-01 June 4.09 E+Ol Unidentified mCi 2.8 E+Ol 2.4 E+00 1.7 E+Ol

2. 9

.+00 Total mCi 7.54 E+02 3.73 E+02 1.5 E+02 4.2

. E+00 3.29 E+02 1.99 E+03

'1

'ABLE 1 REPORT OF RADIOACTIVE EFFLUENTS:

LIQUID DISSOLVED GAS Pae7 Total Ki-85 Xe-131m Xe-133 mCi mCi mCi d

January 3.6 E+00 9.7 E-01 3.6 E+00 d

. February 7.1 E+00

(<4.0 E-06) 7.1-.E+00 March

(<5.1 E-06) 1.6 E+01 1.32 E+00 April

(<3.4 E-06)

(<5.1 E-07)

(<3.8 E-08)

Ma 2.09 E+01 2.8 E+01 4.9 E+00 June

(<3.3 E-06 i

8.5.

E-01 2.01 E+02 Xe-133m mCi

(<1. 3 E-07)

(<6. 4 E-07) 5.8 E+00

(<1.0 E-07

<9.2 E-08

<1 1 E-Xe-135 mCi 1.17 E+00 1.9 E+00 3.0 E-.ol

(<1.2 E-08) 1.06 E+01

6. 9 E+01 Waste Disposal System Kr-85 mCi January

2. 6 E+00 February 7.1 E+00 March

(<5.1 E-06)

April

<3.4 E-06 May

<3.5 E-06 JQne Xe-131m Xe-133 mCi mCi

(<3. 7 E-06)

2. 6 E+00

(<4.0 E-06) 7.1 E+00 7.7 E-01

(<3.8 E-08 1.6 E+01

(<5.1 E-07)

(<4.4 E-07 2.9 E-01 8.5 E-01 6

E+

Xe-133m Xe-135 mCi mCi

(<1.3 E-07) 7.3 E-01

(<6.4 E-07)

1. 7 E+00 5.8 E+00 1.2 E-01

<1.0 E-07

(<1.2 E-08)

.2 F-9;5 E-02

(<1.3 E-08)

Seconda S stem Kr-85 e-1 Xe-133 Xe-133m Xe-135 mCi mCi mCi mCi Januar 9;7 E-01 9.7 E-01 9.7 E-01 4.4 E-01 Februa 6.3 E-03 1.8 E-01 March 5.5 E-01 1.8 E-01 A ril Ma 2.09 E+01

4. 6 E+00 June 1 91 E+02 NOTE:

Numbers in parentheses represent maximum sensitivity in pCi/ml.

Airborne Releases Airborne releases to the atmosphere occurred from release of gas decay tanks via the instrument bleedline, containment

purges, and from the secondary

~ a 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.

All sporadic gas releases from the plant which were not accounted for by the t

above methods were conservatively estimated as curies of Xe-133 equivalent by use of the plant vent process monitor recorder chart.

The maximum rated capacities for the hogging jets and condenser air egectors, and an estimate of the rate of exhaust, from the atmospheric dumps was used to conservatively estimate the airborne releases from the secondary system whene'ver 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 for noble gases, I-131, and parti-culates is based upon detectable radionuclides only.

2.

The applicable limit for release of total radioactive materials in gaseous waste is 0.012 Ci/sec when averaged over the calender quarter.

13

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

Total curies released in f Li aseous waste durin uarter x 100%

(.012 Ci/sec)(seconds in quarter) 3.

The applicable limi.t for the release of I-131 and particulate radio-s nuclides with half-lives greater than eight days in airborne waste is i Qc

'3

~

(

th E~

< 10,000 where Qi = release rate of i

nuclide,

.iPCg 'ec'i/sec and MPCi = maximum permissable concentration of the ith nuclide.

The release rate, Qi, was determined by dividing the total activity released in Ci, for the i nuclide (t 2

> 8d) in the calendar quarter by th the seconds in the quarter.

MPCi 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:

E x

100%

PC I

4.

All values reported in Table II, page 2, include the particulate activity released from both 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

().

5.

All values for gaseous radionuclides reported in Table II, page 3,

include the quantity of gaseous nuclides released via the waste disposal system and secondary system.

14.

6.

A page of notes has been added following Table II, to help explain some of the results in Table II, which have been superscripted with a lower case letter.

15

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o II I

0

TABLE II AIRBORNE RELEASES PARTICULATE PAGE 2

Isotope Unit January e February e March April May June Ba-140 Ce-141 Ce-144 Co-57 Ci

(<3. 3 E-13)

Ci Ci.

Ci

(<7.7 E-14) 1.2 E-05 1.5 E-06

(<1. 4 E-13)

(<3. 7 E-13)

(<8.1 E-15)

(<1.9 E-14)

(<3.4 E-14)

(<8.3 E-14)

(<4. 6 E-15)

(<1. 2 E-14)

(<1.5 E-12) 2.7 E-05 2.5 E-05 4.8

~ E-06

<7.8 E-13

(<4.9 E-14)

<1.9 E-13

(<2.3 E-14)

'o-58 Co-60 Cr-51 Ci Ci 1.9 E-04 3.4 E-05 7.5.E-04 6.8 E-04 1.3 E-04 5.0 E-04 5.9 E-04 1.7 E-04

6. 9 E-05 5.1 E 1.1 E-04

1. 7 E-03 4.8 E-04 9.4 E-05

2. 5 E-04

9. 9 E-05 1.4 E-04 Cs-134 Cs-136 Cs-137 Fe-59 I-131 La-140 Mn-54 Nb-95 Nd-147

. Ru-103 Sb-124 Ci Ci Ci Ci Ci Ci Ci Gi Ci 9; 4 E-06

(<1.2 E-13) 1.5 E-05 4.7 E-04

<1.5 E-13

4. 6 E-05 2.2 E-05

(<5.4 E-14) 3.9 E-05

1. 5 E-05 1.4 E-05 9.5 E-06 2.7 E-05 2.9 E-05 3.2 E-05 3.7 E-06 2.0 E-05 2;5 E-06 2.0 E-05 1.4 E-05

(<2.5 E-14)

(<7.1 E-15)

<1.2 E-13 1.6 E-05 4.2 E-05 2.6 E-'05

(<3.1 E-14) 1.1 E-04

(<2.9 E-14) 4.0 E-05

<3.6 E-14

1. 5 E-06

(<4. 2 E-14)

(<l. 1 E-14)

(<3.6 E-14) 5.8 E-05

(<9.4 E-14 1.7 E-04

3. 9 E-05 4.5 E 05

1. 6 E-05

8. 5 E-05 8.4 E-05 1.4 E-05 2.6'-04

<.0 E-1

5. 3 E-05

(<5. 2 E-14 9.2 E-05

.0 E-5.0 E-04 2.4 E-5 2.0 E-05 2.3 E-05

4. 2 E-06 3.5 E-05 Sb-125 Sr-89 Sr-90 8.7 E-07 6.2 E-08

-06

2. 4 E-07 1.8 E-05 1.5 E-07 4.7 E-08 1.7 E-05 6.4 E-06 2.5 E-07

<1.6 E-13 3.2 E-06 3.2 E-08 Zn-65 Zr-95

- Ci Ci 2.4 E-05

,(<2.3 E-14) 5.2 E-06 2.3 E-05

(<5.1 E-14)

(<3. 1 E-13) 6.7 E-05

(<1.3 '-13) 1.7 E-05 Total 7.7 E-04 1.79 E&3 1.53 E-03 3.00 E-04

3. 1 E-03 1.27 E-03 NOTE Numbers in tenth in pCi/

p esca represent maximum sensitivity ml ~

Fission and Activation Gases TABLE II AIRBORNE RELEASES GASEOUS PAGE 3

Isotope Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Unit Ci Ci Ci Janua'ry 1.14 E+Ol 1.2 E+00 6.9 E-Ol 6.6 E-Ol 1.09 E+00 5.5 E-ol February 4.2 2+00 5.0 E+Ol 1.7 E+00 1.9 E+00 1.4 E+00 1.04 E+01 March 7.6 E+00 5.7 E&l

'.7 E-ol 3.7 E-01

4. 7 E-Ol

'2.2 E-02 April 2.5 E+00 5.5 E-01

. 6.0 E-02

<1

.-0 1.5 E-02 1.3 E+00 May 1.34 E+00 1.14 E+00 1.68 E+00 8.5 E-01 2.2 E-01 June 1.66 E+Ol 1.

E+00 9.8 E+00 1.56 E+Ol 1.0 E+00 Xe-133 Ci 3.32 E+02 3.76 E+02 4.03 E+02 2.81 E+02 4.66 E+02

'1.28 E+03 Xe-133m Xe-135 Xe-135m Xe-138 Ci Ci Ci 1.4 E+00 7.6 E+00 E+00 2.4 E+00 2.62 E+00

l. 7 E+01 1.74 E+Ol 5.7 E+00 4.2 E-Ol 3.7 E+00 2.0 E+00

1. 1 E+00 l.5 E&0 2.1 E+00.

(<8. 8 E-07)

(<4.6 E-06) 2.6 E+00 8.3 E+00 3.3 E+00 2.4 E+00 3.4 E+00 9.95 E+Ol 1.40 E+02 5.58 E+01 Total Ci'.63 E+02 4.88 E+02 4.20 E+02 2.89 E+02 '.89 E+02 1.64 E+03

NOTE

Numbers in parentheses represent maximum sensitivity in pCi/cc.

I Halo ens Gaseous Isoto e

I-131 Unit Ci Janua

4. 4 E-03 February 4.7 E-02 March 1.9 E-02 A ril 3.9 E-03 May 6.0 E-03 June 2.4 E-02 I-133

~ I-135 Ci Ci

3. 5 E-03 3.0 E-02 1.7 E-03

(<2.6 E-12) 2.7 E-03 5.1 E-04

9. 8 E-04 1.5 E-04 1.9 E-03 1.3 E-03

(<1. 8 E-13)

(<8.6 E-14)

Br-82

.Total Ci Ci 9.6 E-03

7. 7 E-02

<1.0 E-12)

(<5.4 E-13) 2.2 E-02 5.0 E-03

<6. 4 E-13)

(<5. 0

'E-14)

<5.7 E-14 7.9 E-n

<8.1 E-14

Notes For Li uid Release Section

/

t a.

The Q/MPC for this release was 0.25.

b.

The Q/MPC for'his release was 0.67.

c.

No primary to secondary leakage was occurring; therefore, no shortlived isotopes were present.

d.

For the dissolved gas calculation in January and February, the activities for Xe-131m and Kr-85 were given as a ratio to the Xe-133 activity.

A ratio of 100% was used.

Also, see note "e" below.

Notes For Airborne Release Section A new higher resolution detector and computerized PHA system was put into service in late February, 1976.

This system allowed us to separate doublet peaks more readily and calculates the minimum detectable activity for all peaks of interest.

Therefore, most of the isotopes listed as

() in January and February have minimum detectable activity values listed from March through June.

19

"SOLID WASTE BURIAL" Waste January 1, to June 30, 1976 Packed'ota3, Ci 97.170 CU ~ Ft 49779.-.45 On site as og July lp 4976 2.986 1043.7 Dates of S14pment and, Disposition 8 January, 1976 14 January, 1976 16 January, 1976 21 January, 1976 29 January, 1976 17 February, 1976 3 March, 1976 4 March, 1976 8 March, 1976 8 March, 1976 27 March, 1976 27 March, 1976 7 April, 1976 9 April, 1976 15 April, 1976 26 April, 1976 30 April, 1976 4 May, 1976 9 May, 1976 18 May, 1976 22 May, 197.6 25 May, 1976 9 June, 1976 ll June, 1976 17 June, 1976 21 June, 1976 22 June, 1976 Buried in Barnwell, South Carolina 26 June, 1976 Total 28 Shipments 20

TURKEY POINT UNITS. 3 AND 4 RADIOLOGICAL ENVIRONMENTAL MONITORING During this report'eriod, 1/Ol/76 to 6/30/76, radiological surveillance at Units 3 and 4 was carried out by the Orlando Radiological Laboratory of the Department of Health and Re-habilitative Services of Florida.

All samples were collected and analyzed in accordance with the Technical Specifications.

A total of 673 samples from 35 different. sampling locations

'ere collected and analyzed.

TABLE REM-PTP-1 summarizes the mean and range values of these analyses.

Since K,

Ra and Th are naturally occurring radionuclides, no data for these species are, recorded in this table.

The gross beta data re-ported is representative of these and other naturally occurring radionuclides.

I

~

'ABLE REM-PTP-2 reports on those sampling locations that showed evidence of having concentrations of a particular radionuclide in a specific sample material higher than the observed mean for

'- '" " that radionuclideat all sampling locations.'oweve'r,'none'f these concentrations exceed the limits established by APPENDIX. B, TABLE II, 10 'CFR 2'0.

With some specificity about'hese

data, H concentr'ations in the Discharge Canal at. location T-84 continue at levels con-

"sistent with 'those reporte'd in earlie'r Semiannual Reports.'ow ground water table levels and temperature and salinity differences are viewed as being contributors to the increased levels of 3H in the Ground Water Wells at locations T-87, T-91 and T-92.

~ In those instances where Sr concentrations

'are in excess of the reported

mean, the value of these data is limited because of the" statistical variations encountered when only a few Sr atoms are being counted.

The Co content of sponges is being studied with assistance from the Orlando Radiological Laboratory.

So far in this effort, sponges harvested from Jewfish Creek (22 miles SSW of the plant) show a similar concentration of 6 Co (about 120 pCi/kg) to that determined in specimens taken from locations closer to the plant (at least 4.5 miles away).

Such results as these indi-cate that the Co being observed in this surveillance program is resulting from sources'ther than plant release, possibly fallout.

The Cs and Ce results reported are considered to originate also from a similar source.

The Split Sampling Program, being carried out by the State' Orlando Radiological Laboratory and ERDA's Health and Safety Laboratory, Idaho Falls, has analyzed several types of samples taken from locations used in the monitoring program for Turkey Point Units 3 and 4.

Some of the typical data obtained in this cooperative program are shown in the summary that follows:

21

TURKEY POINT UNITS 3

AND 4 RADIOLOGICAL ENVIRONMENTAL MONITORING Pa e

2 Turkey Point Plant Type Analysis Sam lin Location

~Sam le For ERDA-HSL Results State Results T-72 Air Parti-Gross culates Beta 0.068 + 0.005 pCi/m 0.05 + 0.01 pCi/m3

~ ~

~ ~

0.023 + 0.003 pCi/m3 0.022 + 0.004 pCi/m3 T-66 T-68 T-73.

a a

T-81 T-58 T-71

~ '-72 Malanga 90Sr 4.5 + 0.5 pCi/kg Barracuda 13 Cs 130 + 50 pCi/kg

~ ~

\\

~ ~

. '27.8 +'1.59 mrad'8.7

+ 1.44 mrad Malanga 4 K 3100 + 500 pCi/kg 1600 + 500 pCi/kg TLD-'s

Total, 28.3 + 1.48, mrad "Exposure' 2.3 pCi/kg 130 + 10 pCi/kg 3600 + 100 pCi/kg 1300 + 100 pCi/kg 32.4 mrad 33.6 miad

'3.2 mrad T-78':" "29..+ 1".53,'mrad""'

34;1 mra'd';

'"-'-64

~ ~

~ ~

30.8 + 1.60 mrad 36.3 mrad

~I

\\

e e

~

I a

These data show a reasonable agreement between laboratories and demonstrate that the analytical methods used in the radiological en-.

v'ironmental surveillance pro'gram'for Units 3 'and 4 meet the requirements of the Technical Specifications.

22

J

TABLE REM-PTP-1:

RADIOLOGICAL ENVIRONMENTAL MONITORING Pro ram Summar

- Turkey Point Facility

. Units 3.& 4

~Location Dade County, Plorida Docket Numbers 50-250,-251 1-01-76 to

"'P' 9

MEDIUM or PATHWAY SAMPLED (Units' Type Number ANALYSIS PERFORMED P

,LLDa PRE-OP BG 1976c 1975 76'EAN RANGE MEAN ALL SAMPLE LOCATXONS 1.

AIR PARTICULATES (pCi/m3)

Gross Beta-206

. '0.002

,r r

1.0

. 0.0121 0.0-0.053 0.055 0.007-0.179 2.

AIR IODINES (pCi/m3) 131Z 206 r

~ 0.008.

1.0 All locations had no detectable 13 I.

3.

DIRECT-RADIATION (mRem/hr) 66

'0.001".

0. 005 0.005 0.002-

• 0.007 0.005

-, 0.002-

0. 007 4.

PRECIPITATION (pCi/1)

Gross Beta 3H 14.

14

.'0.8 199; 9.0

<200 1.6

<200 ND - 9.6 4.0 206 ND 58. 0 ND 219 5.

WATER ESTAURINE (pCi/1) 3H 89Sr 90Sr 20 20 20 199;

'1.6'.

0.8

<200 (1.6)

(0. 8) 220 ND 490 232 ND 1190 All locations had no detectable,.

89Sr r

l All locations had no detectable Sr

t I

D

TABLE REM-PTP-1 PAGE 2

MEDIUM or PATHWAY SAMPLED (Units)

TYpe Number ANALYSXS PERFORMED

LLD+.

PRE-OP SGb 1976c 1975-766 RANGE MEAN RANGE ALL SAMPLE LOCA lONS 6.

WATER COOLING CANAL (pCi/1) 3H 89Sr 90sr 12 12 12 199.

1.6 0.8

~ <200 (1.6)

(0.8) 4054.

3200-3872 1610-11,800 6900 All locations had no detectable 89Sr All locations had no detectable 90Sr 7.

WATER FRESH WATER CANALS Gross Beta 12 0.8 (0.8) 205 1-650 249 ND - 680 (pCi/1) 3H 12 199.

<200 202 ND 700 313 ND - 710 I

8.

WATER POTABLE NNLLN (pci/1)

Gross Beta 3H 0.8 199.

5

<200 6

ND-13

<200

<200 6.4 ND - 13 213 ND - 490 9.

WATER GROUND, WATER WELLS (pci/1) 3H 89Sr 90Sr 12 12 12 199A 1.6 0.8

<200 (1.6) 802 ND - 1730 744 ND - 1900 All locations had no detectable Sr All locations had no detectable 90Sr A

~I

TABLE REM-PTP-1 PAGE 3

MEDIUM or PATHWAY SAMPLED (Units)

ANALYSIS Type Number.

PERFORMED

.:LLD+'RE-OP aGb 1976c

.1975-76~

MEAN RANGE MEAN RANGE ALL SAMPLE LOCATIONS 10.

BOTTOM SEDIMENT COOLING CANAL (pCi/kg)

>8co 60Co 89sr 90sr 4

4

..l. 6

'0. 8'.

(1.6)

(0.8) 43 1-220 (43) <

(1-220) t 31 1-160 (31) '-

(1-160)

All locations had no detectable 89Sr All locations had no detectable 90Sr ll.

BOTTOM SEDIMENT-ESTAURINE (pCi/kg) 89Sr 90Sr 7

1.6 0.8 (1. 6)

(0 8)

All locations had no detectable 89Sr All locations had no detectable 90Sr 12.

BIOTA CRIIRTACRA (pCi/kg) 89sr 90Sr

'.8 4

(8)'4).

All samples analyzed had no detectable Sr';

samples vere not biologically available at 4 other locations.

13.

BIOTA FISH Carnivore (pCi/kg) 137Cs 89Sr 90sr l8 4

(18)

(8)

(4) 17 ND 130 (17)

(ND 130)

All samples showed no detectable 9Sr All samples showed no detectable 9 Sr

LE REM"PTP-1 PAGE 4

MEDIUM or PATHNAY SAMPLED

.(Units)

Type Number ANALYSIS PERFORMED.'LD+

P.RE-OP SGb 1976c MEAN RANGE 1975-76~

MEAN RANGE ALL SAMPLE LOCATIONS

'4.

BIOTA FISH Herbivore (pci/kg)

None 0

Species not biologically available during this report period 15.

BIOTA Manatee Grass (pci/kg)"

89Sr 90sr 6

(5)

(5)

All locations had no detectable 89Sr All locations had no detectable 90Sr (pci/kg) 60co 144ce 6

1 10g 340 I

23 ND 150 65 ND 280 445 ND - 1010 2625 ND 11,200 17.

SMALL ANIMAL (pci/kg)

None 0

, Species not biologically available

~

during this report period

0

~

E

'REM-'PTP-1 PAGE a (f., ~

MEDIUM or PATHWAY SAMPLED (Units)

Type Number ANALYSIS PERFORMED

,'. LLD~

PRE-OP aGb 1976c 1975-76~

MEAN'ANGE MEAN RA'NGE ALL SAMPLE LOCA IONS 18.

FOOD CROP-

~Malan a

(pci/kg) 89sr 90Sr (5)

(2)-

No detectable 89Sr 29 28-30 27 ND 38.

19.

FOOD CROP '- Corn (pCi/kg) 89Sr-90sr a

5 (5)

(2)

Location had no detectable 'r 20.

MANGROVE LEAVES (pCi/kg) 89sr 90Sr 7

(5).

(2)

All locations had no detectable 89Sr 7,

.ND 26 12 ND 48 21.

SOIL (pCi/kg) 89sr 90Sr 137Cs 144Ce 7

7 2

"'6

'og.

(5)

(2)

(26) 200 334 ND 860 235 214 ND 300

.245 ND 860 ND - 520 f

All locations had no detectable 9Sr 40 ND 230

, 68 ND 230

0 TABLE REM-PTP-1 PAGE 6

'EDIUM or PATHWAY SAMPLED (Units)

TYpe Number;.

ANALYSIS PERFORMED

, ':LLD+:

P.RE-OP aGb 1976c 1975-768-'EAN RANGE MEAN RANGE ALL SAMPLE LOCATIONS NOTES:

a ~

LLD nominal lower limits of detection as defined in.HASL (Rev. 8/73) D-08-1 to 3..

Delineations from this are given in Note g.

b.

Mhere applicable, mean'proportional BG data is derived P ~

c.

For the period of 1/Ol/76 to 6/30/76.

d.

For the period of 1/01/75 to 6/30/76.

e.

(

)

no.radioactivity detected in PRE-OP analysis.

estimates of PRE-OP BG.

from;analyses made during the period of 1/01/72 to 12/31/72.

All'values appearing in (.. )'s are LLD's used as f.

(

) ~ no "mean" or-"range" data were available in 1975 for this radionuclide; 1976 data'used as inputs for these entries.

g.

Used HASL computation method to determine this value..

.1

0

TABLE ARM-PTP-2:

SAMPLING LOCATIONS WITH IIIGHEST ANNUAL MEAN Turkey Point Facility Units 3

& 4 r

Location Dade.County, Florida Docket Numbers 50-250 -251 i/01/76 to II g d~

MEDIUM or PATHWAY SAMPLED

. (Units)

FOR of SITES DATA ANALYSIS NUMBER MEAN r

(Range)

NUMBER HIGH SITES l976a 1975-76b S ITF "

("'

MEAN RANGE MEAN RANGE LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONR a.

Air Parti-culates (pCi/m3) b.

Direct Ra-diation (mRem/hr)

(pCi/1)

Gross Beta Gamma Gross Beta 3H 0.0137 (0.0-0.033).

0.005 (0.004-0.006)'.

ND~

<200 NA<

NA NA NA 1.

AIR PARTICU-LATES (pCL/mE)

Gross Beta',

7h 0.0121 (0 0-0.053)

. 3 T-52:

Florida City Sub-Station (W, 8 miles)

T-57:

Dolan's Farm

'(WNW, 4.'5 miles)

T-71:

Girl Scout

'Camp (on site) 0.0135 0.002-0.037 0.013 0.002-0.025 0.0135 0.001-0.050 0.059 0.002-0.350 0.052

~

0.001-0.320 0.057 0.001-

,0.330

I E

REM-PTP-2 PAGE MEDIUM or DATA LOCATION WITH HIGHEST ANNUAL MEAN PATHWAY SAMPLED ANALYSIS NUMBER MEAN NUMBER 1976a 1975-76b (Units)

FOR of SITESc (Range)

HIGH.

SITES~;

SITE MEAN RANGE MEAN RANGE 2.

AIR IODINES (pCi/m3) 131I ND 0

v All locatioys had no detectable.

I 3.

DIRECT RADIA-

~

TION (m.em/hr)

0. 005 (0.002-0.007) 0 All-locations had no significant'devia-..

tions from mean 4.

PRECIPITATION (pCi/1)

Gross Beta 3H 4

1.6 (ND-9. 6

<200

': 0 0

'r All locations had:no significant-devia-.

tions from mean 5.

'PATFR.

Estaurine (pCi/1) 3H 89Sr 90Sr 10 10 10

'220 (330-490

~ND

~ 0 I

~

T-81:

Card Sound, New. Discharge

Canal, (South, 6 miles)

(1 analysis'.3/10/76)

All.locations had no significant Sr

'll locations had no significant.

Sr 410 330-'90

~

271 ND 490

1/

TABLE REM-

-2 PAGE 3

MEDIUM or DATA LOCATION WITH HIGHEST ANNUAL MEAN PATHWAY'SAMPLED ANALYSIS NUMBER NUMBER 1976a 1975-76 (Units)

FOR of SITES HIGH (Rangh)

SITES SITE MEAN RANGE MEAN RANGE Canal (pci/1) 3H 89Sr 90Sr 4483 (3400-7000)

ND ND 0

T-84; Discharge

Canal, Southside of Onsite Bridge All locations had no detectable 9Sr All locations had no detectable 9 Sr

'4,217 3,400-Sc 100 4,233 1610-11,600 7.

WATER - Fresh Water Canals (pci/1)

Gross Beta 3H 205 (1-65o) 202 (ND-7oo)

T-75:

Florida City Canal; NNW, 1.5 mile T-75:

Florida City Canal; NNW, 1.5 mile 405 260-650 372 ND-700 369 19-650 426 ND - 710 8.

WATER Potable Wells (pCi/1)

Gross Beta 3H 6

(ND-13)

<200 0

T-57:

Dolan's Farm; WNW, 4.5 miles T-73:

City of Home-stead; WNW, 9.0 mile 9.5 6-13 6.5

~

5-9

<200

<200 8.5 1-13 4-11 241 ND-490

TABLE REM-2 I

I

~

~

I PAGE 4

MEDIUM or

{Units)

FOR PATHWAY SAMPLED ANALYSIS DATA NUMBER of SITES+

MEAN

{Range)

NUMBER

'HIGH SITES 1976a 1975-76b S ITE

~r MEAN RANGE MEAN RANGE LOCATION WITH HIGHEST ANNUAL MEAN 9.

HATER Ground Water Wells (pCi/1) 3H 838

'J

~ ~

3 T-87:

Well-E-10.on New. Discharge Canal; Onsite T-91:

Well G-10 on New Dischaige Canal; Onsite 1520; 1430-1464 910-1610 1900 1060" 970-616 ND-1150 1150 10.

BOTTOM SEDI-MENTS Coolin Canal (pCi/kg) 89Sr 90Sr 58Co 60co 89Sr 90Sr r

,ND ND

.43

~ 31 (1-160)

=ND r

ND 0

~'

0 s

0.

'T-92:

Well G24A on New, Dischar'ge Canal; Ons'ite r

All locatio~s had no detectable'r All.:locations had no detectable

.90Sr T-84:

Discharge

'Canal, South Side of Onsite Bridge All'ocatio'ns had no detectable,89Sr All'ocations had no 90 r

170.

120-220 120 80-160 1640 1550-1730 '336 750-1730 170i 120-220 120i'0-160i

TABLE R&f

-2 PAGE 5

MEDIUM or I

DATA LOCATION WITH HIGHEST ANNUAL MEAN (Units)

FOR of SITES c PATHWAY SAMPLED ANALYSIS NUMBER MEAN (Range)

NUMBER

.HIGH SITES SITE 19,76 a 1975-76b MEAN RANGE RANGE MEAN ll. BOTTOM SEDI-MENTS Estaurine (pCi/kg) 89sr 90Sr 7

ND 0

0.

All locations had no detectable 9Sr All locations had no detectable 90Sr

12. BIOTA-Crustacea (pCi/kg) 89sr 90Sr

.ND 0

All locations either had no detectable 89.

90Sr or samples were not biologi-'ally available (4

sites) 13.

BIOTA PISH Carnivore (pCi/kg) 137Cs 89Sr 90sr 17 (ND-200)

ND ND 0

0 T-84:

Discharge..

canal, Southside of Onsite Bridge All:samples had no.

det'ectable'r All samples had no detectable 'Sr

~ 0 100:

'0-130 100 70-130i I

~

TABLE

-REM-PTP-2 PAGE

~

.I MEDIUM or PATHWAY SAMPLED DATA ANALYSIS NUMBER MEAN NUMBER'976a 1975-76

\\

LOCATION WITH.HIGHEST ANNUAL MEAN (Units)

FOR of SITES (Range)

'. HIGH'-

SITES~

SITE MEAN RANGE MEAN RANGE 14.

BIOTA FISH Herbivore (pci/kg) 15.

BIOTA Manatee Grass (pci/kg)

None 89Sr 90Sr 6

None None I

0

'0 Species not biologi-cally available dur-ing this re'port:.

period g ~

All locations had no detectable 89Sr All.locations had no detectable Sr g 'I

~

16.

BIOTA S on es (pci/kg) 60co 144Ce 6

23 (ND-150) 445 (ND-1010) "

T-86:

Wes't Arse-nicker Key; ESE, 3

miles T-59:

Elliott Key;

East, 9 miles

130, 110-150 130i 110-150i 970 930-2625 ND

-. 11,20 1010 17.

SMALL ANIMAL (pci/kg)

None 0

None

'one:

~ ~

Samples not biologi-cally available

TABLE REM-ZP-2 I

I I

0 I

PAGE 7

MEDIUM or PATHWAY SAMPLED DATA ANALYSIS NUMBER

,MEAN

~ a NUMBER 1-976 a 19i5-76b LOCATION WITH= HIGHEST ANNUAL MEAN (Units)

FOR of SITESc-(Range}

HIGH

SITES, SITE MEAN RANGE MEAN RANGE 18.

POOD CROP-

~Malaa a

(pCi/kg) 89sr 90Sr ND

'29 28-30) 0 No, detectable Sr T-5'2:

Plorida City Substation; Q,

8 miles

29. 30 27 ND-- 38 19.

POOD CROP Corn (pCi/kg) 89sr 90sr ND

-ND 0

0 Location had no detectable

~

Sr 20.

MANGROVE LEAVES (pCi/kg) 89sr 9.osr 7

ND 7

(ND - 26) 0.-.:

2.

C A11 locatiol had no detectable.

Sr T-51:

. Homestead Bay front Park

NORTH, 2 miles T-64:

PPL Natoma Substation; NNE, 30 miles 26 22-30 12; 10-14 3Z 21-48 12 10-26

~-

TABLE REM-xP-2

~ 0 PAGE 8

~

~

MEDIUM or PATHWAY SAMPLED ANALYSXS DATA NUMBER NUMBER 1976a 1975-76 LOCATION WITH:HIGHEST ANNUAL MEAN (Units)

FOR of SITESc (Range)

HIGH SITES SITE MEAN RANGE MEAN RANGE 21.

SOIL (pci/kg) 89Sr 90Sr 137Cs

'40 (ND-230) 334 (ND-860).'

All locations had no detectable.

Sr T-58:

Onsite Entrance Road T-52:

Florida City Substation; NEST 8 miles 90.70-110 78 ND 180 830 800-860 549

-: - ND 860 144Ce

'14 (ND-300) 1.:

r T-56:

Princeton Substation, Cocoanut Diive; NW,:8 miles T-57:

Dolan's Farm; M%l, 5 miles T-58:

Onsite Entrance Road 570 530-610 416.

ND 720 350 320-380 182 ND-380 300 290-310'20 200-500 I

PAGE 9 -~.

MEDIUM or DATA LOCATION KITH HIGHEST ANNUAL M@AN (Units)'OR PATHWAY SAMPLED ANALYSIS NUMBER of SITESc MEAN (Range)

NUMBER

HIGH, SITES.~

SITE.

1976a MEAN RANGE 19i5-76b MEAN RANGE NOTES:

a.

From Table REM-PTP-1 and State of Florida Division of b.

.For the period 1/Ol/75 to 6/30/76.

Health Reports for first and second quarters, 1976.

c ~

d.

e.

Number of sampling locations used to obtain data.,

Above MEAN value of data reported for::the period 1/Ol/76.to 6/30/76.

T-64 FPL's NATOMA Substation (ENE, 30 miles);"relevant only to Air Particulate, Direct Radiation and Pre-cipitation analyses.

NA Not Applicable.

g.

ND Not Detectable.

h.

Includes CONTROL LOCATION (T-64) i.

No data from 1/Ol/75 to *12/31/75 values.

'I samples.

recorded; data from 1/01/76 to 6/30/76 accepted: as "Mean" and "Range"

S