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

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TABLE OF CONTENTS ~ ~ ~ s ~ ~ s ~ ~ s e ~ ~ ~ s ~ ~ ~ ~ ~ ~ s j INTRODUCTION s s s s s e e s e s e s e s ~ 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 ~ ~ s (1) LIQUID RELEASES s s ~ s ~" ~ ~ s s ~ e ~ ~ s ~ ~ e (2) AIRBORNE RELEASES s s e s s s s a s s s s s s ~ ~ s 13 (3), SOLID l'(ASTE BUR IAL s e s ~ s s s 20 (B) RADIOLOGICAL !ENVIRONMENTAL MONITORING ~ s ~ ~ ~ ~ ~ ~ ~ s ~ 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 RADIOLOG I CAL NONITOR ING e FOR THE PERIOD OF JANUARY li 1976'HROUGH JUNE 50, 1976,

Radioactive Ef fluent 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 liquots u 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 d isposal 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 1 activation gases by use of gamma spectrum analysis. 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) uarter III 1.Total Release (mCi) 7. 62. E+02 '3.96 E+02 1.80 E+02 5.58 8+00 3.34 E+02 2. 06 .E+03 (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 2.Av Concentration Durin Releases 3.Av . Concentration for Month (pCi/ml) 2.6 E-09 ~

1.5 E-09 6.0. E-10 2.1 E-ll 1.9 E-09 9. 4 E-09 (pCi/ml) 1. 1 E-'Q8 2.5 E-08 2.1. E-08 7.6 E-i.O 1.9 E-.07 7.0'-07 4.Max Concentration Released 5.Percent of Technical Specification g I P L'imit for Total Activity Released 2.68 E+Ol. 4.80 E+01 B.Tritium (Ci) 6.26 E+01 7.98 E+01 3.80 E+01 8.40 E+Ol

l. otal Release 8.38 E+01 7.03 E+01 6.6 E (pCi/ml) 2.9 E-07 2.8 E-07 6:5 E-07 1.8 E-O6 7.2 E-07 2.Av Concentration Durin Releases 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. 2 E-11 6.4 E-ll 2.4 E-10 (<7.6 E-17 1.2 E-09 . 2.1 E-'09 3.Avg Concentration for Month (pCi/ml 3. 2 E-ll 6.0 E-ll 7.8 E-ll (<1.3 E-17 3.6 E-10 1.2 E-09 D.Gross Alpha Radioactivit 1.Total Release (mci (<2.3 E-08 (<7.2 E-09 (<3.9 E-09 (< 3. 1 E-09 8. 6 E-02 1.0 E-02 Av Concentration'urin Releases ICi ml <7.9 E-20 <2.9 E-20 <4.1 E-20 <6.9 E-20 1.6 E-12 7.7 E-14 3.Av Concentration for Month (pCi/ml) (<7. 9 E-20) (<2. 7 E-20) (<1. 3 F;20) (<1.2 E-20) 4.8 E-13 4.5 E-141 E.Volumes 1.Vol of Li uid Waste to Dischar e . (Liters) 2.58 E+07 2.71 E+07 5.68 E+06 2.6 E+06 5.08 E+06 8.05 E+06 2.Vol of Dilution Water During Releases(Liters 2.9 E+ll 2.5 E+ll 9. 6 E+10 4.5 E+10 5.3 E+10 1.3 E+ll 3.Vol of Dilution Water for Month (Liters) 2.9 E+ll 2.7 E+ll- 3.0 E+11 2.6 E+11 1.8 E+ll 2.2 E+11 he s i narentheses renresent maximum sensitivity in pCi ml.

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TABLE I REPORT. OF RADIOACTIVE EFFLUENTS: LIQUID TOTAL Page 2 Isoto e Unit January 'February March April May June A -110m mCi 8.1 E-02 Ba-139 mCi 2.8 E+00 Ba-140 mCi 1.0 E+00 ~ (<1.7 E-07) (<3.9" E-07) (<1;1 E-07) (<2.4 E-07) 2.33 E+02 Ce-144 . mCi (<3.9 E-07) (<1.4 E-07) (<2.4 'E-07) (<5.9 E-08) (<1.1 E-07) (<1.9 E-07)

Co-57 mCi 3. 3 E-02 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 mCi 4.7 E+00 5.5 E+00 1.04 E+00 4.6 E-01 3.4 E+00 7.3 E+00 Cr-51 mCi 1.37 E+00 3.8 E-01 (<3 5 E-07) (<8. 2 E-08) (<1.9 E-07) (<2.1 E-07)

Cs-134 mCi 7.7 E-ol 6.0 E+00 6.0 E+00 (<1.4 E-08) 5.7 E+00 7.4 E+01 ~

Cs-136 mCi 1.4 E-ol (<1.1 E-08) (<2.6 E-08) (<9.8 E-09) 1;1 E+00 1.31 E+Ol Cs-137 mCi 1.33 E+00 4.6 E+00 1.76 E+01 (<1.5 E-'08) 9.7 E+00 1.17 E+02 Cs-138 mCi 3.02 E+01 7.3 E+00 1.33 E+Ol 8.4 E+00 F-18 mCi 2.30 E+02 1.06 E+01 3.9. E+00 3. 5 E+00 ~

9.3 E+00 Fe-59 mCi 4.0 E-01 (<2.8 E-08) (<5.6 E-08) 9.2 E-02 (<3.6 E-08) (<2.4 E-08)

I-131 mCi 1.57.E+01 3.91 E+Ol 2.43 E+01 5.5 E-01 8;3 E+01 6.79 E+02 I-132 mCi 5.20 E+Ol 5.49 E+01 l. 3 E+01 3.01. E+Ol 5.8 - E+01 I-133 mCi 7.51 E+Ol 8.68 E+Ol 2.7 E+Ol 8. 8 E+01 4.57 E+02 mCi 4.44 E+Ol 5.66 E+Ol 1.54 E+Ol 3.09 E+01 1.62 E+01 I-135 mCi 8.14 E+Ol 7.77 E+Ol 2.54 E+Ol 3.93 E+01 1.05 E+02 La-140 mCi 2.8 E-01 4.1 E-02 (<2. 6 E-08) (<5. 8 E-09) (<1. 1 E-08) 3.16 E+Ol Mn-54 mCi 1.27 E+00 (<1.7 E-08) 1.1 E-01 E-08) 1.7 E+00 3.11 E+01 Mo-99 mCi 8.6 E-04 1.0 E-01 3.2 E+00 2.03 E+01 Na-2 mCi 2.13 E+02 1.52 E+Ol 8.2 E+00 3.0 E+00 7.1 E+00 ~

Nb-95 mCi <7.2 E-08 <1.3 E-08 <2.8 F-0 (<1.1 E-08 2.0 E-01 <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 Unit January February March April, May June Sb-124 mCi 3.4 E-01 6.1 E-01 7.2 E+00: (<1. 7 E-08) 8.5 E-01 8. 2 E+00 Sb-125 mCi 4.3 E-01 4,0 E+00 5.2 E-01 1. 6 E-01 Sr-89 mCi 2.6 E+00 ~

2.1 E+00 5.7 E-01 6.1 E-Ol 1.89 E+00 5.62 E+Ol Sr-90 mCi 2.4 E-ol 4. 7 E-02 1.3 ~ E-02 8.3 E-03 2.9 E-ol 1.65 E+00 Sr-91 mCi 4.09 E+01 Tc-99m mCi 1.3 E-01 1.1 =

E-01 2.0 E-01 1.77 E+Ol Zn-65 mCi (<8. 1 E-08) (<2. 8 E-08) (<6.5 E-08) (<1. 9 E-08) <3.4 E-08 <2. 6 E-08 Zr-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 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 Unit January February March April May June A -110m mCi 8.1 E-02 Ba-140 mCi (<4.8 E-07) (<1.7 E-07) (<,3. 9 E-07) (<1.1 E-07) (<2.4 E-07) (<2.1 E-07)

Ce-144 (<3. 9 E-07) (<1. 4 E-07) (<2. 4 E-07) (<5. 9 E-08) (<1. 1 E-07) (<1. 9 E-07)

Co-58 mCi 2.4 E+00 1.02 E+00 1.74 E+00 6. 1 E-Ol 2.3 E+00 2.4 EWO Co-60 mCi 1.8 E+00 3.4 E-01 4.6 E-01 6.3 E-02 4.2 E-ol 2.7 E-01 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 mCi 2.0 E-01 . (<2.1 E-08) 1.4 E-02 E-08) (<2.7 E-08) (<3.0 E-08)

(<1.1 E-08) (<2.6 E-08)'<1.4 E-09)

Cs-136 mCi (<1.9 E-07) (<9.8 (<1.7 E-08) (<1.5 E-08)

Cs-137 mCi 5.4 E-01 1.4 E-01 2.1 E-01 (<1.5 E-08) 8.8 E-02 3.4 'E-01 Fe-59 (<1. 1 E-07) (<2. 8 E&8) (<5.6 E-08) 9.2 E-02 (<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 mCi (<2. 2 E-07) 4.1 E-'02 (<2.6 E-08). (<5.8 E-09) (<1.1 E-08) 1.2 E+Ol Mn-54 mCi 3.4 E-Ol (<1.7 E-08) 1.1 =E-01 (<1. 5 E-08) 5.9 E-02. <1.5 E-08 Nb-95 mCi (<7.'2 E-08) (<1.3 E-08) (<2.8 E-08) (<1.1 E-08) (<1;9 E-08) (<1.1 E-08)

Sb-124 mCi 3. 4 E-01 6.1 E-01 7.2 E+00 (<l. 7 E-08) . 8. 5 E-01 1.0 E+00 Sb-125 mCi 4."3 E-01 4.0 E+'00 5.2 E-01 1.6. E-01 Sr-.89 mCi 1.4 E-02 7.4 E-03 (<5.9 E-09) 2.3 E-02 3.1 E-Ol 6.0 E+00 Sr-90 mCi 4.9 E-03 4.0 E-03 (<1.5 E-09) 8.3 E-03 1.0 E-02 <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 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

'r-95 Total 8.15 E+00 2.26 E+Ol 2.97 F+ 1 6.62 E+Ol NOTE: Numbers, in parentheses represent maximum sensitivity in pCi/ml.

TABLE I REPORT OF RADIOACTIVE RELEASES: LIQUID - SECONDARY SYSTEM Page 5 Isotope 'Unit January February March April May June Ba-139 mCi 2.8 E+00 Ba-140 mCi 1.0 E+00 '2.33 E+02 Co-57 mCi 3. 3 E-02 Co-58 mCi 5.4 E+00 1.4 E+00 3.5 E-01 5.7 E+00 3.58 E+0 Co-60 mCi 2.9 E+00 5. 2 E+00 5.8 E-01 4.0 E-Ol 3.0 E+00 .0 E+00 Cs-134 mCi 5.7 E-01 6.0 E+00 6.0 E+00 5.7 E+00 7.4 E+01 Cs-136 mCi 1.4 E-01 1.1 E+00 1.31 E+Ol Cs-137 mCi 7.9 E-01 4.5 E+00 1.74 E+01 9.6 E+00 1.17 E+02 Cs-138 3.02 E+Ol 7.3 E+00 1.33 E+Ol 8.4 'E+00 F-18 mCi 2.30 E+02 1.06 E+Ol 3.9 E+00 3.5 E+00 9. 3 E+OO Fe-59 4.0 E-01 I-131 mCi 1.46 E+01 1.95 E+Ol 8.3 E+00 ~ +

I-132 5.20 E+01 5.49 E+01 . 1.3 E+01 3.01 E+01. 5. 8 E+Ol I-133 mCi 7.51 E+Ol 8.68 E+01 2.7 E+Ol 8;8 E+01 4.57 E+02 I-134 mCi 4.44 E+01 5.66 E+01 1:54 E+01 3.09 E+Ol 1.62 E+01 I-135 mCi 8.14 E+Ol 7.77 E+01 2.54 E+t)1 3.93 E+Ol 1.05 E+02 La-140 mCi 2.8 E-01 1.96 E+01 Mn-54 mCi 9.3 E-ol 1.6 E+00 . l. +Ol Mo-99 mCi 8.6 E-04 1.0 E-01 3.2 E+00 2.03 E+Ol Na-24 2.13 E+02 1.52 E+01 8.2 3.0

'.1 mCi E+00 E+00 E+00 Nb-95 mCi 2.0 E-OI Sb-124 mCi Sr-89 mCi 2.6 E+00 2.1 E+00 5.7 E-01 5.9 E~01 1.58 E+00 5.02 F+01 Sr-90 mCi. 2.4 E-01 4.3 E-02 1.3 E-02 .6 F+00

TABLE I REPORT OF RADIOACTIVE RELEASES: LIQUID SECONDARY SYSTEM (CONT) Pa e 6 Isotope 'Unit January -February March A ril Ma June Sr-91 4.09 E+Ol Tc-99m 'mCi 1.3 E-01 1.1 E-01 2.0 E-01 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 d d Total January . February March April Ma June Ki-85 mCi 3.6 E+00 7.1 E+00 . (<5.1 E-06) (<3.4 E-06) 2.09 E+01 (<3.3 E-06 i

Xe-131m mCi 9.7 E-01 (<4.0 E-06) 1.6 E+01 (<5.1 E-07) 2.8 E+01 8.5. E-01 Xe-133 mCi 3.6 E+00 . 7.1- .E+00 1.32 E+00 (<3.8 E-08) 4.9 E+00 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 January February March April May JQne Kr-85 mCi 2. 6 E+00 7.1 E+00 (<5.1 E-06) <3.4 E-06 <3.5 E-06 Xe-131m mCi (<3. 7 E-06) (<4.0 E-06) 1.6 E+01 (<5.1 E-07) (<4.4 E-07 8.5 E-01 Xe-133 mCi 2. 6 E+00 7.1 E+00 7.7 E-01 (<3.8 E-08 2.9 E-01 6 E+

Xe-133m mCi (<1.3 E-07) (<6.4 E-07) 5.8 E+00 <1.0 E-07 .2 F-Xe-135 mCi 7.3 E-01 1. 7 E+00 1.2 E-01 (<1.2 E-08) 9;5 E-02 (<1.3 E-08)

Seconda S stem Januar Februa March A ril Ma June Kr-85 mCi 9;7 E-01 2.09 E+01 e-1 9.7 E-01 Xe-133 mCi 9.7 E-01 6.3 E-03 5.5 E-01 4. 6 E+00 1 91 E+02 Xe-133m mCi Xe-135 mCi 4.4 E-01 1.8 E-01 1.8 E-01 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

Airborne Releases Airborne releases to the atmosphere occurred from release of gas decay

~

tanks a 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 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 for t

gas releases from the plant which were not accounted 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 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 1 00%

(.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 E~Qc

.iPCg <

'3 10,000 where

'ec'i/sec ,

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(

Qi = release rate of ith nuclide, and MPCi = maximum permissable concentration of the ith nuclide.

The release rate, Qi, was determined by dividing the total activity i

released in Ci, for the th nuclide (t 2 > 8d) in the calendar quarter by 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 PC x100%

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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0 TABLE II AIRBORNE RELEASES PARTICULATE PAGE 2 e

Isotope Unit January February e March April May June Ba-140 Ci (<3. 3 E-13) (<7.7 E-14) (< 1. 4 E-13) (<3. 7 E-13) (<1.5 E-12) <7.8 E-13 Ce-141 Ci (<8.1 E-15) (<1.9 E-14) 2.7 E-05 (<4.9 E-14)

Ce-144 Ci. 1.2 E-05 (<3.4 E-14) (<8.3 E-14) 2.5 E-05 <1.9 E-13 Co-57 Ci 1.5 E-06 (<4. 6 E-15) (<1. 2 E-14) 4.8 ~ E-06 (<2.3 E-14)

'o-58 Ci 1.9 E-04 7.5 .E-04 5.0 E-04 6. 9 E-05 1. 7 E-03 2. 5 E-04 Co-60 3.4 E-05 6.8 E-04 5.9 E-04 5.1 E 4.8 E-04 9. 9 E-05 Cr-51 Ci 1.3 E-04 1.7 E-04 1.1 E-04 9.4 E-05 1.4 E-04 Cs-134 Ci 9; 4 E-06 2.2 E-05 1. 5 E-06 (<4. 2 E-14) 5.8 E-05 5. 3 E-05 Cs-136 Ci (<1.2 E-13) (<5.4 E-14) (<l. 1 E-14) (<3.6 E-14) (<9.4 E-14 (<5. 2 E-14 Cs-137 Ci 1.5 E-05 3.9 E-05 3.7 E-06 2;5 E-06 1.7 E-04 9.2 E-05 Fe-59 Ci 1. 5 E-05 2.0 E-05 2.0 E-05 3. 9 E-05 .0 E-I-131 Ci 4.7 E-04 1.4 E-05 1.4 E-05 (<2.5 E-14) 4.5 E 05 5.0 E-04 La-140 Ci <1.5 E-13 9.5 E-06 (<7.1 E-15) <1.2 E-13 1. 6 E-05 2.4 E- 5 Mn-54 Ci 4. 6 E-05 2.7 E-05 1.6 E-05 4.2 E-05 8. 5 E-05 2.0 E-05 Nb-95 Gi 2.9 E-05 2.6 E-'05 (<3.1 E-14) 8.4 E-05 2.3 E-05 Nd-147 Ci 1.4 E-05 4. 2 E-06

. Ru-103 3.2 E-05 1.1 E-04 (<2.9 E-14) 2.6'-04 3.5 E-05 Sb-124 4.0 E-05 <3.6 E-14 < .0 E-1 Sb-125 1.8 E-05 1.7 E-05 <1.6 E-13 Sr-89 8.7 E-07 -06 6.4 E-06 3.2 E-06 Sr-90 6.2 E-08 2. 4 E-07 1.5 E-07 4.7 E-08 2.5 E-07 3.2 E-08 Zn-65 - Ci ,(<2.3 E-14) 5.2 E-06 (<3. 1 E-13) (<1.3 '-13)

Zr-95 Ci 2.4 E-05 2.3 E-05 (<5.1 E-14) 6.7 E-05 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 p tenth esca represent maximum sensitivity in pCi/ml ~

TABLE II AIRBORNE RELEASES GASEOUS PAGE 3 Fission and Activation Gases Isotope Unit Janua'ry February March April May June Ar-41 1.14 E+Ol 4.2 2+00 7.6 E+00 2.5 E+00 1.34 E+00 1.66 E+Ol Kr-85 1.2 E+00 5.0 E+Ol 5.7 E&l 5.5 E-01 1.14 E+00 1. E+00 Kr-85m Ci 6.9 E-Ol 1.7 E+00 '.7 E-ol . 6.0 E-02 1.68 E+00 9.8 E+00 Kr-87 6.6 E-Ol 1.9 E+00 3.7 E-01 <1 .-0 Kr-88 Ci 1.09 E+00 1.4 E+00 4. 7 E-Ol 1.5 E-02 8.5 E-01 1.56 E+Ol Xe-131m Ci 5.5 E-ol 1.04 E+01 '2.2 E-02 1.3 E+00 2.2 E-01 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 Ci 1.4 E+00 2.62 E+00 4.2 E-Ol l. 5 E&0 - 2.6 E+00 3.4 E+00 Xe-135 Ci 7.6 E+00 l. 7 E+01 3.7 E+00 2.1 E+00. 8.3 E+00 9.95 E+Ol Xe-135m Ci E+00 1.74 E+Ol 2.0 E+00 (<8. 8 E-07) 3.3 E+00 1.40 E+02 Xe-138 2.4 E+00 5.7 E+00 1. 1 E+00 (<4.6 E-06) 2.4 E+00 5.58 E+01 To tal 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 Unit Janua February March A ril May June I-131 Ci 4. 4 E-03 4.7 E-02 1.9 E-02 3.9 E-03 6.0 E-03 2.4 E-02 I-133 Ci 3. 5 E-03 3.0 E-02 2.7 E-03 9. 8 E-04 1.9 E-03 1.3 E-03

~

I-135 Ci 1.7 E-03 (<2.6 E-12) 5.1 E-04 1.5 E-04 (<1. 8 E-13) (<8.6 E-14)

Br-82 Ci <1.0 E-12) (<5.4 E-13) <6. 4 E-13) (<5. 0 'E-14) <5.7 E-14 <8.1 E-14

.Total Ci 9.6 E-03 7. 7 E-02 2.2 E-02 5.0 E-03 7.9 E-n

Notes For Li uid Release Section t a.

b.

c.

The Q/MPC The Q/MPC No for'his

/

for this release release primary to secondary leakage was was 0.25.

0.67.

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 Ci CU ~ Ft Packed'ota3, 97.170 49779.-.45 On site as og July lp 4976 2.986 1043.7 Dates of S14pment and, Disposition 8 January, 1976 Buried in Barnwell, South Carolina 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 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 I

radionuclides.

~

REM-PTP-2 reports on those sampling locations that showed

'ABLE 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 ground water table levels and temperature and salinity Reports.'ow 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 0.068 + 0.005 pCi/m 0.05 + 0.01 pCi/m3 culates Beta

~ ~ ~ ~ 0.023 + 0.003 pCi/m3 0.022 + 0.004 pCi/m3 T-66 Malanga 90Sr 4.5 + 0.5 pCi/kg 2.3 pCi/kg T-68 Barracuda 13 Cs 130 + 50 pCi/kg 130 + 10 pCi/kg T-73. Malanga 4 K 3100 + 500 pCi/kg 3600 + 100 pCi/kg a a T-81 1600 + 500 pCi/kg 1300 + 100 pCi/kg T-58 TLD-'s Total, 28.3 + 1.48, mrad 32.4 mrad "Exposure' T-71 ~ ~ . '27.8 +'1.59 33.6 miad

'-72 T-78':"

mrad'8.7

\

+ 1.44 mrad '3.2 mrad

~ ~ ~

"29..+ 1".53,'mrad""' 34;1 mra'd';

'"-'-64

~ ~ ~ ~ 30.8 + 1.60 mrad 36.3 mrad

~ I I

\ e e ~

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: -

Turkey Point RADIOLOGICAL ENVIRONMENTAL Facility . Units 3 .& 4 Docket Numbers 50-250,-251 1-01-76 to MONITORING Pro ram Summar

~

Location Dade County, Plorida "'P' 9 MEDIUM or ANALYSIS ALL SAMPLE LOCATXONS P

PATHWAY SAMPLED PERFORMED ,LLDa PRE-OP 1976c 1975 76'EAN (Units' Type Number BG RANGE MEAN

1. AIR PARTICULATES Gross . 206 . '0.002 . 1.0 . 0.0121 0.0- 0.055 0.007-Beta- 0.053 0.179 (pCi/m3) ,r r r

2. AIR IODINES 131Z 206 ~

0.008. 1.0 All locations had no detectable 13 I.

(pCi/m3)

3. DIRECT-RADIATION 66 '0.001". 0. 005 0.005  :

0.002- 0.005 -, 0.002-0.007 0. 007 (mRem/hr)

4. PRECIPITATION Gross 14. .'0.8 9.0 1.6 ND - 9.6 4.0 ND 58. 0 Beta (pCi/1) 219 3H 14 199; <200 <200 206 ND

5. WATER ESTAURINE 3H 20 199; <200 220 ND 490 232

ND 1190 (pCi/1) 89Sr 20 '1.6'. (1.6) All locations had no detectable,. 89Sr l

r 90Sr 20 0.8 (0. 8) All locations had no detectable Sr

t I

D

TABLE REM-PTP-1 PAGE 2 MEDIUM or ANALYSXS ALL SAMPLE LOCA lONS PATHWAY SAMPLED PERFORMED

LLD+. PRE-OP 1976c 1975-766 (Units) TYpe Number SGb RANGE MEAN RANGE

6. WATER COOLING 3H 12 199. <200 4054. 3200-

~

3872 1610-11,800 CANAL 6900 (pCi/1) 89Sr 12 1.6 (1.6) All locations had no detectable 89Sr 90sr 12 0.8 (0.8) All locations had no detectable 90Sr

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

12 199. <200 202 ND 700 313 ND 710 I

8. WATER POTABLE Gross 0.8 5 6 ND-13 6.4 ND - 13 NNLLN Beta (pci/1) 3H 199. -

<200 <200 <200 213 ND 490

9. WATER GROUND, 3H 12 199A <200 802 ND - 1730 744 ND - 1900 WATER WELLS (pci/1) 89Sr 12 1.6 (1.6) All locations had no detectable Sr 90Sr 12 0.8 All locations had no detectable 90Sr A

~I TABLE REM-PTP-1 PAGE 3 MEDIUM or ANALYSIS ALL SAMPLE LOCATIONS PATHWAY SAMPLED PERFORMED .:LLD+'RE-OP 1976c .1975-76~

(Units) Type Number. aGb MEAN RANGE MEAN RANGE

10. BOTTOM SEDIMENT >8co 43 '. 1-220 (43) < (1-220) t COOLING CANAL (pCi/kg) 60Co 4 31 . 1-160 (31) '- (1-160) 89sr ..l. 6 (1.6) All locations had no detectable 89Sr 90sr 4 '0. 8'. (0.8) All locations had no detectable 90Sr ll. BOTTOM SEDIMENT- 89Sr 1.6 (1. 6) All locations had no detectable 89Sr ESTAURINE (pCi/kg) 90Sr 7 0.8 (0 8) All locations had no detectable 90Sr

12. BIOTA CRIIRTACRA 89sr '.8 All samples analyzed had no detectable (8)'4). Sr'; samples vere not biologically (pCi/kg) 90Sr 4 available at 4 other locations.

13. BIOTA FISH 137Cs l8 (18) 17 ND 130 (17) (ND 130)

Carnivore *

(pCi/kg) 89Sr (8) All samples showed no detectable 9Sr 90sr 4 (4) All samples showed no detectable 9 Sr

LE REM"PTP-1 PAGE 4 MEDIUM or ANALYSIS ALL SAMPLE LOCATIONS PATHNAY SAMPLED PERFORMED .'LD+ P.RE-OP 1976c 1975-76~

.(Units) Type Number . SGb MEAN RANGE MEAN RANGE

'4.

BIOTA FISH None 0 Species not biologically available during Herbivore this report period (pci/kg)

15. BIOTA Manatee 89Sr 6 (5) All locations had no detectable 89Sr Grass 90sr (5) All locations had no detectable 90Sr (pci/kg)"

I 60co 1 23 ND 150 65 ND 280 (pci/kg) 144ce 6 10g 340 445 ND - 1010 2625 ND 11,200

17. SMALL ANIMAL None 0 , Species not biologically available

~

during this report period .

(pci/kg)

0

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

MEDIUM or ANALYSIS ALL SAMPLE LOCA IONS PATHWAY SAMPLED PERFORMED ,'. LLD~ PRE-OP 1976c 1975-76~

aGb ..'.

(Units) Type Number MEAN 'ANGE MEAN RA'NGE

18. FOOD CROP- 89sr (5) No detectable 89Sr

~Malan a 90Sr (2)- 29 '-

28-30 27 . ND 38.

(pci/kg)

19. FOOD CROP '-

(pCi/kg)

Corn 89Sr-90sr a

5 (5)

(2)

Location had no detectable 'r

20. MANGROVE LEAVES 89sr (5). All locations had no detectable 89Sr (pCi/kg) 90Sr 7 (2) 7, .ND 26 12 ND 48 f

21. SOIL 89sr (5) All locations had no detectable 9Sr (pCi/kg) 90Sr 7 2 (2) 40 ND 230 , 68 ND 230

"'6 137Cs 7 (26) 334 - ND 860 . 235 ND 860 144Ce

'og.

200 214 ND 300 .245 ND - 520

0 TABLE REM-PTP-1 PAGE 6

'EDIUM or ANALYSIS ALL SAMPLE LOCATIONS PATHWAY SAMPLED PERFORMED ':LLD+:

, P.RE-OP 1976c 1975-768-'EAN (Units) TYpe Number;. aGb

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

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 estimates of

.radioactivity detected in PRE-OP BG.

PRE-OP analysis. 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 Facility r

Location Dade Turkey Point Units 3 & 4

.County, Florida II g d~

Docket Numbers 50-250 -251 i/01/76 to LOCATION WITH HIGHEST ANNUAL MEAN MEDIUM or DATA PATHWAY SAMPLED ANALYSIS NUMBER NUMBER l976a 1975-76b MEAN (Units) of r HIGH

. FOR S ITF " ("'

MEAN RANGE SITES (Range) SITES MEAN RANGE CONTROL LOCATIONR

a. Air Parti- Gross 0.0137 NA<

culates Beta (0.0-(pCi/m3) 0.033).

b. Direct Ra- Gamma 0.005 . NA diation (0.004-(mRem/hr) 0.006)'.

Gross ND~ NA (pCi/1) Beta 3H <200 NA Gross 7h 0.0121 3 T-52: Florida City 0.0135 0.002- 0.059 0.002-

1. AIR PARTICU- .

LATES Beta', (0 0- Sub-Station (W, 8 0.037 0.350 0.053) miles)

(pCL/mE)

T-57: Dolan's Farm 0.013 0.002- 0.052 ~ 0.001-

'(WNW, 4.'5 miles) 0.025 0.320 T-71: Girl Scout 0.0135 0.001- 0.057 . 0.001-

'Camp (on site) . 0.050 ,0.330

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

SITES~;

SITE MEAN RANGE SITESc (Range) MEAN RANGE

2. AIR IODINES 131I ND 0 v All locatioys had no detectable. I (p Ci/m3)

3. DIRECT RADIA- ~ 0. 005 0 All-locations had no TION (0.002- significant'devia-..

0.007) tions from mean (m .em/hr)

4. PRECIPITATION Gross 4 1.6 ': 0 All locations had:no Beta (ND-9. 6 significant-devia-.

(pCi/1) tions from mean

'r 3H <200 0

'PATFR . 3H 10 '220 T-81: Card Sound, 410 271 ND 490

5. 330-'90 Estaurine (330-490 New. Discharge Canal, ~

(South, 6 miles) .

(pCi/1) 89Sr 10 ~

0 (1 analysis'.3/10/76) 90Sr 10 ~ ND All.locations had no significant Sr

'll locations had no I ~

significant. Sr .

/

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 HIGH SITE SITES (Rangh) SITES MEAN RANGE MEAN RANGE 3H 4483 T-84; Discharge '4,217 3,400- 4,233 1610-Canal (3400- Canal, Southside of Sc 100 11,600 7000) Onsite Bridge (pci/1) 89Sr ND All locations had no detectable 9Sr 90Sr ND 0 All locations had no detectable 9 Sr

7. WATER - Fresh Gross 205 T-75: Florida City 405 260- 369 19-650 Water Canals Beta (1-65o) Canal; NNW, 1.5 mile 650 (pci/1) 3H 202 T-75: Florida City 372 ND- 426 ND - 710 (ND-7oo) Canal; NNW, 1.5 mile 700

8. WATER Potable Gross 6 T-57: Dolan's Farm; 9.5 6-13 8.5 1-13 Wells Beta (ND-13) WNW, 4.5 miles (pCi/1) T-73: City of Home- 6.5 ~ 5-9 4-11 stead; WNW, 9.0 mile 3H <200 0 <200 <200 241 ND-490

I I

TABLE REM- 2 ~ ~

I PAGE 4 MEDIUM or DATA LOCATION WITH HIGHEST ANNUAL MEAN PATHWAY SAMPLED ANALYSIS NUMBER MEAN NUMBER 1976a 1975-76b

{Units) FOR of 'HIGH S ITE r SITES+

~

{Range) SITES MEAN RANGE MEAN RANGE

9. HATER Ground 3H 838 3 T-87: Well- E-10 .on 1520; 1430- 1464 910-Water Wells 'J New. Discharge Canal; 1610 1900 (pCi/1) Onsite T-91: Well G-10 on 1060" 970- - 616 ND-1150

~~ New Dischaige Canal; 1150 Onsite

'T-92:

New, Well G24A on Dischar'ge Canal; 1640 1550-1730

'336 750-1730 Ons'ite r r 89Sr ,ND All locatio~s had no detectable'r 90Sr ND 0 All.: locations had no detectable .90Sr r

10. BOTTOM SEDI- 58Co .43 T-84: Discharge 170. 120- 170i 120-MENTS Coolin South Side of 'Canal, 220 220 Canal Onsite Bridge (pCi/kg) 60co ~ 31 ~

' 120 80- 120i'0-(1-160) 160 160i 89Sr =ND 0 s All'ocatio'ns had no r detectable,89Sr 90Sr ND 0. All'ocations had no 90

TABLE R&f -2 PAGE 5 I

MEDIUM or DATA LOCATION WITH HIGHEST ANNUAL MEAN PATHWAY SAMPLED ANALYSIS NUMBER MEAN NUMBER 19,76 a 1975-76b (Units) FOR of .HIGH SITE SITES c (Range) SITES MEAN RANGE MEAN RANGE ll. BOTTOM SEDI- 89sr 0 All locations detectable had no 9Sr MENTS Estaurine (pCi/kg) 90Sr 7 ND 0. All locations had no detectable 90Sr

12. BIOTA- 89sr .ND 0 All locations either Crustacea had no detectable 90Sr 89. 90Sr or samples (pCi/kg) were not available (4 biologi-'ally sites)

13. BIOTA PISH 137Cs 17 T-84: Discharge .. 100: '0-130 100 70-130i Carnivore (ND-200) canal, Southside of Onsite Bridge (pCi/kg) 89Sr ND 0 All: samples had no.

det'ectable'r 90sr ND 0 All samples had no detectable 'Sr

~0 I ~

TABLE -REM-PTP-2 PAGE

~ .I MEDIUM (Units) or PATHWAY SAMPLED FOR DATA ANALYSIS NUMBER of SITES MEAN (Range)

NUMBER

'. HIGH'-

SITES~

'976a SITE

\

LOCATION WITH. HIGHEST ANNUAL MEAN MEAN RANGE 1975-76 MEAN RANGE

14. BIOTA FISH None None None Species not biologi-Herbivore cally available dur-ing this re'port:.

(pci/kg) period g ~

I

15. BIOTA Manatee 89Sr . 0 All locations had no Grass detectable 89Sr g 'I ~

90Sr 6 '0 All.locations had no (pci/kg) detectable Sr

16. BIOTA S on es 60co 23 T-86: Wes't Arse- 130, 110- 130i 110-(ND-150) nicker Key; ESE, 3 150 150i (pci/kg) miles 144Ce 6 445 T-59: Elliott Key; 970 930- 2625 ND -. 11,20 (ND-1010) " East, 9 miles 1010

'one:

~ ~

17. SMALL ANIMAL None 0 None Samples not biologi-cally available (pci/kg)

I I

TABLE REM- ZP-2 I

0 I PAGE 7 MEDIUM or DATA ~ a LOCATION WITH= HIGHEST ANNUAL MEAN PATHWAY SAMPLED ANALYSIS NUMBER ,MEAN NUMBER 1-976 a 19i5-76b (Units) FOR of HIGH SITESc- (Range} SITES, SITE MEAN RANGE MEAN RANGE

18. POOD CROP- 89sr ND 0 No, detectable Sr

~Malaa a 90Sr '29 T-5'2: Plorida City 29. -

28-30 27 ND-- 38 (pCi/kg) 28-30) Substation; Q, 8 miles

19. POOD CROP 89sr ND 0 Location had no Corn detectable . ~ Sr (pCi/kg) . 90sr -ND 0

20. MANGROVE 89sr ND 0.-.: A11 locatiol had no LEAVES detectable. Sr (pCi/kg) 9.osr 7 7 2. T-51: . Homestead Bay 26 22-30 3Z 21-48 (ND - 26) front Park NORTH, 2 miles C

T-64: PPL Natoma 12; 10-14 12 10-26 Substation; NNE, 30 miles

~- TABLE REM- xP-2

~ 0 PAGE 8

~ ~

MEDIUM or DATA LOCATION WITH:HIGHEST ANNUAL MEAN PATHWAY SAMPLED ANALYSXS NUMBER NUMBER 1976a 1975-76 (Units) FOR of HIGH SITESc SITES SITE (Range) MEAN RANGE MEAN RANGE

21. SOIL 89Sr All locations had no detectable. Sr (pci/kg) 90Sr '40 T-58: Onsite 90.70-110 78 . ND 180 (ND-230) Entrance Road 137Cs 334 T-52: Florida City 830 800-860 549 -: - ND 860 (ND-860) .' Substation; NEST 8 miles T-56: Princeton 570 530-610 416. ND 720 Substation, Cocoanut Diive; NW,:8 miles T-57: Dolan's Farm; 350 320-380 182 ND-380 M%l, 5 miles 144Ce '14 1 .: T-58: Onsite 300 290-310'20 200-500 (ND-300) r Entrance Road I

PAGE 9 -~.

MEDIUM or DATA LOCATION KITH HIGHEST ANNUAL M@AN PATHWAY SAMPLED ANALYSIS NUMBER NUMBER 1976a 19i5-76b MEAN (Units)'OR of SITESc (Range)

HIGH, SITES.~

SITE.

MEAN RANGE MEAN RANGE NOTES:

a. From Table REM-PTP-1 and State of Florida Division of Health Reports for first and second quarters, 1976.

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

c~ Number of sampling locations used to obtain data.,

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

e. 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.

'I

h. Includes CONTROL LOCATION (T-64) samples.

i. No data from 1/Ol/75 to *12/31/75 recorded; data from 1/01/76 to 6/30/76 accepted: as "Mean" and "Range" values.

S