ML17339A678

Radioactive Effluent Release Data,Jul-Dec 1979.

ML17339A678
Person / Time
Site:	Turkey Point
Issue date:	02/22/1980
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17339A677	List: ML17339A676 ML17339A678 ML17339A679
References
NUDOCS 8003180415
Download: ML17339A678 (18)

Text

RADIOACTIVE EFE'LUENT RELEASE DATA JULY 1979 THROUGH DECEZSER 1979 TURKEY POINT PLANT PLORXDA POl!ER & LIGHT CO~PAhY PEWUARY 22, 1980 r

'L, ~ ~

600318 4/6

I SEIIXAIRMAI. RRPORT OP RADXOACTXVR RPPLUPHT Rl::I P.ASIIS PTP URXTS 3 & i 7/79'- X7/7U Xn troduc tion All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Specification requixcments. The minimum frequency of analysis as required by Safety Cuide 21 was met or. exceeded..

Li uid Releases Aliquots of representative pre-release samples vore either isotopically anal.

yzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and anal-yzed for gros.", beta-gamma activity in a 2m gas flow proportional counter. The effici-ency of the gas flow proportional counter is adjusted "so that thc 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

'I followed for all releases from the waste disposal system L

and for sec'ondary system'atch releases. Frequent periodic sampling and analysis were used to conservatively estimate the quantity of radioactivity xeleased via the steam

,generator blowdown system.

The following comments will aid in the interpretation and evaluation of the liquid release data presented in Tabl'e I, pages 1 through 6:

1. The reported values'n Table I, page 1, include in their computavion 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 secondaxy leakage conditions, or when the generators were drained for repair or refueling, or during lancing of thc generators. Beginning in November, activity which hacf entered the plant storm drain system was also included in thc secondary system activity released and in the total activity released.

2. The r<<ported values in Table I, p igcs 2 and 3 arc thc Lotal quantiLics of radio-activity fox individual nuciidcs re3.cased from the vastc disposal system and the secondary syst<<m to< ether. Thc values in Table I, page 4 are for the waste dis-po .al system only and page 5 is for the secondary sy. tern only.

3. During primary to secondary leakage, release of several short-lived nuclides from the secondary system occurs. Th'esc short-lived nuclides arc not generally detecLed in batch release from the waste disposal system due to the long hold-up time of processed water. Only. those isotopes that vere detected in the second-ary system releases vere reported. All non-detectablc isotopes are listed as

( ) ~

4. Weekly and monthly composite samples for the vaste disposal system were pxc-pared to give proportional veight to each liquid release made during the des-ignatcd period of accumulatio'n. Thc composites vere analyzed for gamma Qmit-ting isotopes on a multichannel analyzer attached to a high resolution Ge(Li) detector, and for. Sr-89 and Sr-90, using a chemical cparation and subsequent beta determination vith a 2w gas flov proportional counter. Tritium was=dcter-'ined by usc of liquid scinti3.lation 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 vere multiplied by

~ N 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

".'iS" compositing period.

~

p h

5. At least one representative batch of liquid effluent fxom the waste disposal

~

' ~ ~ l syst: em vas analyzed monthly for dissolved fission and activation gases by use of gamma spectrum analysis. resulting isotope concentrations were multi-1'he plied by the total volume released for thc month in order to estimate the total di..solved gases released. If more than onc batch of effluent vas analyzed, 0 the concentrations totaled on a monthly

~~ -

werc. weight<<d basis in Table in an I,

appropiiatc manner.

page 6, Dis'solved gases,

~ 4 Thc results are if any, from

/

<<2

1

~ ~

7/79 12/79 secondary system releases werc determined from the samples of the individual release . Isotopic concentrations werc multiplied by the volume released to determine the quantity of radiogas nuclide released.

6. Representative samples of secondary syst: em batch releases were analyzed indi vidually for gamma emitting isotopes. Analysis of a representative composj.te for tritium, gross alpha and selected beta emitters was made for releases which occurred due to primary to secondary leakage.

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

8. The following notes have been added to help explain

~ ome of thc results in Table I:

On August 28, 1979, the Unit 84 Spent Puel

~ Pit was overflowed with "a resultant release of approximately 3000 gallons of water to the ground surrounding the tank. The activity released was:

Co-57 1.4 mCi Co-58 182 mCi Co-60 908 mCi Total 1091 mCi Because the dirt was collected and handled as a solid waste (drummed),

this activity was not included in our liquid activity released for August 1979. This release is documented as Reportable Occurrence 251-79-14.

Airborne Releases Airborne releases to the atmosphere occurred from: 'elease of gas decay tanks, the instrument bleedline, containment purges, and the secondary system during con-C ditions of primary to secondary leakage. The techniques employed in determining the gadioactivity in airborne releases are':

-a) Gamma spectrum analysis for fission and activation gases.

/

<<3

~ ~ ~ A~ y I I

b)'emoval oc 'potticugo cantorial by fiIttatton snt oqcont taooa-spac-trum analy"is, Sr-89-90 determination, gross a3.pha analysis, and gross beta-gamma ana3ysis.

c) Absorption of ha3ogen radionuclides on a.charcoal filter and subsequent gamma-spec txum 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 I

above method". were con.,ervatively estimated as curies of Xe-133 equivalent by use.

of the plant vent process monitor recorder chart and the current calibration curve fox. the monitor.

The ma..imum xated capacity fox the hogging jets and the maximum measured flow-rate for. the condenser air ejectoxs, and an estimate of the rate of exhaust from the atmospheric dumps werc used to conservatively estimate the airborne releases from the secondary system whenever applicable.

The i 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 xadionuclides only.

2. The applicable limit for re3.ease of total radioactive materials in gas'eous waste is 0.012 Ci/sec when averaged over the calendar quarter. The percent of the applicable limit for total gaseous release was computed as follows:

Total curies released in gaseous waste durin uarter x 3.00%

% of Limit ~

(.012 Ci/scc) (seconds-in quarter)

3. The applicable limit for the release of 1-131 and particulate radionuclides with half-lives greater than eight days in airborne waste is:

'ec' HVC 10,000 n'

, where Q. = release rate of i.th nuclide, Ci/scc and 1fPC. = maximum permissible concentration of

.th the i nuc3ide, Ci/m 3

/

-I)-

~ ~ ~

1 P ~

</ I J J.// I'J

~ The rclcasc rate, Q., determined by dividing thc t activity released in Ci, for thc i.th nucl'idc (tj~ > 8d), during the calendar. quarter by the seconds 0 in the quarter.

MPC.

i. values were obtained fr'om 10CFIi20,. Appcixdix 8, Table II, Column I. The HPC chosen was the most conservative value oi either the soluble or insoluble HPC for each isotope.

The percent of applicablc limit was determined as follows

% of Limit ~

Z 1IPC.

i x 100%

10,000 m3/sec

4. The maximum gaseous release rate for each month is listed in Table II, page l, under Section A,'ine 3. Thc applicable limit for maximum allowable release rate is 6.7 E+04 pCi/scc.

II, 0'. All values reported'n and halogen Table activity released pages 2 and 3, include the particulate, gaseous, from the containments'uring 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 will be listed as ( ).

1979 Table I Report of Radi ive Effluents: Liquid Pgel Liquic'. Re" eases JULY AUGUST SEPT .ABER OCTOBER ~

ZO) EyBER'EC"-i1BER.

A, . ross Ra o<>>c ~ ivn t) (P-g)

l. Tote'elease (mCi) 5.60 E+01 -'.37 E+Ol:" 5.4l E-:02) 2.09 E+01 2.30 E+01 4.64 E-:Cl

2. 5 E-10 2. 5 E-10 1. 7 E-lo 8.4 E-11 S.6 E-11 3.1 E-10 2, .6~g Concentration During Releases(uCi/nl) 2.5 E-10 2.5 E-10 1.7 E-10 8.4 E-11 8.6 E-ll 1.9 "-10

3. Av{; Conccntra'cion for ~4!onth (uCi/ml) 2.5 E-09 1,1 E-08 1.1 E-09 2. S E-09 2. 2 E-09 3.4 E-09

4. '!ax C>ncentration Released (pci/ml)

5. Percc"..t o Technical Specif ication 3.3 E+00 1 8~ E+00

i...it for Total Active ty Released (%)

B. Tr'tium

.oral Release (Ci) 4.64 E+01 1.26 E+02 S.52 E+Ol 1.45 E+02 8.48 E+01 1.55 E-:02

5. 9 E-07 2. 7 E-07 5. 9 E-07 3. 2 E-07 1. 0 E-06

2. Avp Concentration During Releases(pCi/nl) 2. 1 E-07 E-07 2. 7 E-07 5. 9 E-07 3. 2 E-07 6. 4 E-07

3. Avg Concentration for 1<onth (pCi/ml) 2.1 E-07 5. 9 .

C. Disso~ ved: oblc Gas

l. Total 'release (mCi) 2.59 E+00 2.61 E+01 3.18 E-Oll 2.40 E+01 3.68 E-Ol 3.34 E-:00

2. Avg Concen" ration During Releases(pCi/ml) 1.2 E-ll 1.2 E-10 1.0 E-1 9.7 E-ll 1.4 E-12 2. 2 E-ll

3. <'.vg concent'ation fo" Yionth (1<Cijml) 1.2 E-ll 1.2 E-10 1.0 E-l~ 9.7 E-ll 1.4 E-12 1. >> E-ll D. Gross Alpha Radioactivity

1. Total Release (nCi) (,1.0 E-OS) (< 6. 2 E-09) (<6.2 E-0 (<9.4 E-09 (<7.8 E-09) (<9.0 E-09)

(< 2. 9 E-20) (<2. 0 E-20 (<3. 8 E-20'<2. 9 E-20) (<6. 0 E-20',

2. Pvg Concentration During Releases(pCi/ml) {<4.5 E-20'4.

3. h'v8 Concencrccion for <<onch (pCi/ml) 5 E-20) <2. 9 E-20) (<2. 0 E-20 (<3. 8 E-20) (<2. 9 F-20) (<3.8 E-20 E. Volumes 1.63 F+07 1.85 E+07 1.29 E+07 1.19 E+07

1. Vol of Liquid Haste to Discharge (Liters) 2.13 E+07 1.65 E+07 2.48 E+11 2,66 E+ll 1.50 E+ll

2. Vol of Dilution (later During Rel (Liters) 2.20 E+11 2.14 E+ll 3.14 E+11 3, Vol of Pilution Hater for ifonth (Liters) 2.20 F+11 2.14 E+11 3.14 E+11 2.li8 Elll 2.66 F;:ll 2.40 E~ll 3 4 r <'I <1 ere <<en~<or. ll>>y q<>>>>wig'

'2 Q79 able I Resort oZ Radioactive Effluents: Li uid - Total Page 2 isotope Unit JULY AUGUST SEPTEHBER OCTOBER Y,OVP!BER DECZ).'HER Ap-110m mCi 1.84 E-02 8.36 E-02 3.77 E-02: 6.95 E-'Ol 3. 2 E-02 6.12 E-01'<l.

Ba-140 mCi (<8.9 E-08) (<1.6 E-07) (<8. 8 . E-08) (<1.4 E-07) 0 E-07) (<l. 2 E-07)

Co- 7 mCi {<1.6 E-08). {<2.4 E-08) (<1.5 E-08) 1.36 E-02 ( <1. 7- E-08) ( <1. 9 E-08)

Co-58 2.19 E+00 3.22 E+00 5.79 Z-Ol 1.94 E+00 7 49 F-Al z r~nn Co-60 mCi 4.32 E+00 7.42 E+00 4.21 E-:00 6.41 8+00 3.92 B-00 1.18 E+Ql Cr-51 mCi { <2. 0 E-07) (<3.3 E-07) (<l. 9 E-07) ( <3. 0 E-07) (<2.3 E-07) 3.43 i+00 Cs-134 mCi 6.97 E-Ol 6.36 E+00 2. 18 E+00 3.23 E-ol 2.35 E+00 . 5.47 E+

Cs-137 mCi 1.07 Z+00 9.47 E+00 2. 60 E-:00 8.32 E-01 3.19 i+00 8.44 E-:00 E-18 mCi 6.59 i+00 4.65 E-01 4.37 E+00 7.18 E-Ol 5.58 E-01 1-131 . mCi 2.43 E+00 3.85 E+00 3. 33 E+00 1.29 E+00 3.42 i+00 3.89 i+CO

"-132 nCi 5.42 E+00 1.53 E+00 5.23 E+00 4.80 E-Ol 6.4 E-02

'Z-133 nCi 1.36 E+01 1.01 E+01 1.56 E+01 5.94 E-:00 6.29 i+00 2.19 i+CO T-134 nCi 8.52 E-Ol 2. E+00 0'.69 I-135 mCi 1.38 E+01 7.05 E+00 E+00 (

1.27 E+00 ~ 1;S2 E+00 Lz-140 mCi (<8. 2 Z-09) (<9. 5 Z-.09) . (<1. 0 E-OS) (<1.6 E-08) (<S.9 E-09) (<1.5 i-CS)

Nn-54 mCi (<2. 7 Z-08) 1.82 E-01 .(<3.4 E-08) 1.36 E-01 (<3. 2 E-08) 2.81 E-

-Na-24 mCi 1.45 Z+00 9. 9 E-01 2.59 E+00 mCi (<2.2 Z-OS) (<3. 9 E-08) (<2. 8 E-08) 5.26 E-02 {<2.5 E-08) ~

-. 2.76 2-01 Ru-103 mCi (<2.4 Z-08) (<4. 0 E-08) ~

(<2. 2 E-08) (<3.7 E-08) (<<2.7 8-08) ~

2.69 8-02 Sb-124 mCi 5..94 E-01 1.10 E+00 5,50 E-01 6.07 E-02 2.11 E-02 1.81 E-:00 Sb-125 mCi 8.87 Z-01 1.86 Z+00 1.06 Z+00 1.83 E-Ol 1';5S Z-01 1.19 E~OO Sr-.S9 mCi ~ 8.87 Z-Ol 1.0 H-02 2.4 E-02 4.96 Z-01 4.23 Z-Ol 3.08 F-01 Sr-90 mCi 1.16 E+00 5. 6 H-03 (<2. 9 E-09) 5.06 E-.02 3.53 E-02 .8.1 i-03 e-132 mCi (<1.9 E-08) (<3.1 Z-OS) (<1.8 E-08) (<2.8 E-08) (<2.2 E-CS) . 1.46 E-01

1979 Table l Re ort of Radioactive'Eff1 uents: Li uid - Total Page 3 Tsotoj)e Unit JULY AUGUST SEPTDIBER OCTOBER hOV&IB>% DECE~!BER ~

Zv 05 mCi ~

(<4. 1 E-08) (<6.5 E-08) (<4.3 E-08) ~

(<7.0 E-08) (<4.4 E-OS). 2.78 E-Ol To tel mCi 5.60 E+01 5.37 E+01 5.41 E+01 2.09 E+01 2.30 E&01 4. 64:--:~1

~ I

1979 0 able I Re ort oZ Radioactive Efflnents: Li @id kAqste Dis~osel Svstcm

'sotope Unit DULY AUGUST S EP TE14lBEB. OCTOBER VOVEitBER T)'7 PV:7,.'P Ag-110m mCi 1.84 E-02 8.36 E-02 3.77 E-02: 6.95 E-Ol 3.2 E-02 6.12 E-01 B=140 (<8.9 E-08) (<1.6 E-07) (<8.8 E-08) (<1.4 E-07) (<l. 0 E-Q7) (<1. 2 E-07)

Cc-57 mCi (<1. 6 E-08). (<2. 4 E-OS) (<1. 5 E-08) 1.36 E-02 (< l. 7 E-08) (<1.9 E,-OS)

Co-58 mCi 6.33 E-01 1.53 E+00 5.79 E-01 1.94 E+00 4.18 E-01 6.03 E-:00 Co-50 1.93 E+00 5.87 E+00 1.94 E+00 3.09 E+00 1.47 E-:00 7.25 E+00 mCi (<2.0 E-07) (<3. 3 E-07) (<1. 9 E-07) (<3.0 E-07) (<2.3 E-0/) 3 ~ < Q ~ 00 Cs-134 mCi 6.97 E-Ol 3.97 E+00 2.53 E-01 1.39 E-01 1.18 E+00 2.77 E-.'.01 Cs-137 mCi 1.07 E+00 6.35 E+00 3.54 E-01 3.35 E-01 1.80 E+00 E+00 T.-131 mCi (<2.3 E-08) (<3-9 E-08) ( 2 1 E-08) 7.78 E-02 (<2.9 E-08) 6.12 E-01 L"-140 mCi (<8. 2 E-09) (<9. 5 E-09) (<l. 0 E-08) (<1.6 E-08) (<8:9 .E-09) (<1.5 E-08)

>:~-54 (<2. 7 E-08) 1.82 E-Ol (<3.4 E-08) 1.18 E-01 (<3. 2 E-08) 2.81 E-01 4Kb~95 mCi (<2.2 E-08) (<3.9 E-08) (<2.8 E-08) 5.26 E-02 (<2. 5 E-08) 2.76 E-Ol RU-103 mCi (<2. 4 E-08) (<4. 0 E-OS) (<2; 2. E-08) (<3.7 E-08) (<2. 7 E-08) 2.69 E-01 Sb-124 nCi 5.94 E-01 1.10 E+00 5.50 E-01 6.07 E-02 2:ll E-02 1.81 "-+00 Sb-125 8.87 E-01 1.86 6+00 1,06 2+00 1.83 E-01 1.58 E-Ol 1.19 ~-:00.

Sv 89 mCi 8.87 E-Ol 1. 0 E-02 2. 4 P,-02 l. 5 E-02 1.4 E-02 15 Sr-90 mCi 1.16 E+00 5. 6 E-03 '<2.'9 E-09) 9.'0 E-03 (<2. 6 E-09) {<2. 6 E- )

Te-132 mCi (<l. 9 E-08) (<3. 1 E-OS) (<1. 8 E-08)  !, (<2. 8 E 08)- (<2.2 8-08) I 1.48 E-O" Zr-95 mCi (<4. 1 E-08) {<6.5 E-08) . {<4.3 E-OS) {<7. 0 E-08) (<4. 4 8-08)  ! 2. 78:"-01 Total mCi 7.88 E+00 2.10 E+Ol .4,.80 2+00 6.73 E+00 5.09 E-:00 3,02 E+01

1079 Table I Re ort of Radioactive Effli<ents: Liouid - Seoondarv S stem Page 5 Iso ope Unit JULY AUGUST SEPTEHBER OCTOBER cvOVEHBER DEC~':BE"..

Co-58 mCi '.56 F~OO 1 69 E+00

~ 3.31 E-Ol Cc-60 'Ci 2.39 F+00 1.55 E+00 2.27 E+00 3.32 E+00 2.45 E~OO 4.57 E+00 Cs-134 2.39 E+00 1.93 E+00 1.84 E-01 1.17 E+00 2.70 2+00 Cs-137 n:Ci 3.12 E+00 2.25 E+00 4.97 E-01 1;39 E+00 3.43 ":00 10 mCi 6.59 E+00 4.65 E-01 4.37 E+00 7.18 E-.01 5.5S E-01 I-] 31 2.43 E+00 3.85 E+00 3.33 E+00 1.21 E+00 3.42 E-:00 3.2$ E-:00 I-132 mCi 5.42 E+00 1.53 E-:00 5.23 E.OO 4.80 E-Ol 6.4 E-02 I-133 mCi 1.36 E+Ol 1.01 E+01 1.56 E+01 5.94 E+00 6.29 E-:00 2.19 "=-:00 I-134 mCi 8.52 E-Ol 2. 0 E+00 I-135 mCi. 1.38 E+01 7.05 E+00 9.69 E+00 l. 27 .E+00 3.S2 F=:

1.8 - E-02 ia-24 1.45 E+00 9. 9 E-01 2.59 E+00

$0 mCi (<2. 9 E-09) (<2.9 E-09) (<2. 9. E-09) 4.Sl E-01. 4.09 E-Ol 9.34 E-02 J

S-.-90 mCi (<2.9 E-09) (<2. 9 E-09) (< 2. 9 E-09) 4.'6 E-02 3.53 E-02 8 1 03 Tot..l mCi 4.81 E+01 3.27 E-:01 4.93 E+01 1,42 E+01 1.78 E+01 '.63 =--:O 1

II i 1979 Table 1 Rcport oZ Raaioactiv Efflucats: Liqu d Dissolved Gas Page 6 3ULY AUGUST SEPTEHBER OCTOBER Xi10VEt~i BER DECEMBER:

(<5.1 E-06) . (<6.1 E-06) ('<8.7 E-06) . 1.82 E+01 '<8.7 E-06). (<S.7 "-06).

vn 13 l ~ (<7. 2 E-07) (<9. 7 E-07), (<3.. 1 E-.06) (<1. 3 E-06) . (<9. 6 E-07) (<9 6 E-07)

"-J 33 '"Ci 1.99 E+00 2.59 E+Ol 3.18 E-01 5.78 E-:00 '3.68 E-01 2. 96:--:00 Xe-133I.. r..C i (<l. 6 E-07) (<1 9 E-07) (<2'.3 E-07) (<2. 9 E-07) (<2. 1 E-07) (< 2. 2 E-07)

':"-135 nCi 6.0 E-01 2.35 E-01 (<2.6 E-OS) (<3. 3 E-08) (<2. 4 E-08) 3.77 E-01

~~>'astc Disl..osal S:stcn Kr-85  ;:lC L (<5. 1 E-06) (<6. 1 E-06) (<8.7 E-06) 1.S2 E+Ol (<8:7 E-06) (<8.7 E-06) nCi (<7. 2 E-07) (<9. 7 E-07) (< l. 1 E-06') (<1. 3 E-06) (<9. 6 E-07) (<9 6

~ =-0/)

Xp~133 >Ci 1.99 E+00 2.59 E+01 3.18 E-Ol 5.78 E+00 3.68 E-Ol 2.96 2-:00

.c-l33.-.. (<1. 6 E-07) (<1. 9 E-07) (< 2. 3 E-'07) (<2.9 E-07) (<2. 1 E-07) (<2. 2 E-07)

.Ie-135 I Ci 6I 0 E-01 2.35 E-01 (<2. 6 E-OS) (<3. 3 E-08) (< 2. 4 E-08) 3.77 E-OI Kr-85 7 -131ri: nCi Zc-133 nCi Zc-133~ nCi Xe-135

1979 Ta!!I.c II Rcport of Radioactive Hfflucnts: Airborne Page 1 JULY 'UGUST SEPT5IBER OCTOBER NOVI'.HBER DECDSER I ....-:-=:.=-..--...

A. Piss'.n".. and Activation =:.- Gases 1 ~

~

o. c(:ic

+ ] 9 c...iv a 1cn (Ci) 3.33 E+02 2.27 E+02 1.40 E+02 2.49 E+02 1.20 E+02 3.52 E+02

?. /.vg R I. R..t.. for Period (pCi/scc) l. 1 E+02 9. 5 E+01 4. 7 E+Ol 1.0 E+02 5.0 E-:01 1. 2 E+02

3. '::.-.;: ".;c'at~ for period (uCi/scc) 5. 9 L'-:02 2. 6 E+03 4.3 E+03 1.3 K+04 9.2 E+03 ~ 0 E+04

"'.a@i-,un "- rbor"..c release rate averaged over onc hour for each month. Technical Specification lir;.it is 6.7 E+04 pCi/s averaged .>ver one hour.

ic.line 13'

~ To ta 1:-odin 131 (Ci) 7.1 E-04 2. 5 E-03 1.2 E-03 9. 7 E-04 2. 3 E-03 6.8 E-03

2. i'.v~ ":.cl Rate for Period (pCi/scc) 2. 4 E-04 1.0 E-03 4.0 E-04 4. 0 E-04 9.6 E-04 2.3 E-03 C. Particulate".

Particjlatcs with tl/?>Gd (Ci) 1.21 E-04 3.66 E-03 3.42 E-03 1.34 E-03 ,2.55 E-04 ~ 1.42 E-03

2. Avg "..cl I'atc for Period (pCi/sec)

. 4.0 E-05 1. 5 E-03 1. 1 E-03 5. 6 E-04 1.1 E-04 4.7 E-04

3. G o ."  !.1~ha Radio ctivity (Ci) 3. 1 E-09 (<2.4 E-12) 1. 1 E-09 3. 8 E-09 (< 2. 4 E-12) 3.4 E-08 D.

1.

~ rr:t iur!

otal

2. Av;.. ":..1 Rcl"ase Rate for Period (pCi/scc)

(c ) 9.17 E-02 3.1 E-02

9. 9 4.1 E-02 E-02 1.03 E-Ol 3.4 E-02

', 5.3 27'-Ol E-02 1.'9 5.0 E-01 E-02

)

)

1.44 E-0 4.8 E-02 E. Percent o Applicablc Limit Quarter III Quarter IV

l. Pissicn and Activation Gases (%) 7. 3 E-01 7.6 E-Ol

2. I-131 and Part (tl/2>8'(I) 2.5 E-01 3.9 E-01

~O E: '.iu:"..be s in parenthcscs represent nazimum sensitivity ir; pCi/cc.

1979 ~b r r 1n~~ne Tsoiopc Unit JULY'UGUST SEP EIBER. OCTOBER YOVn"iBER DECEMBER B=-140 {<7. 6 E-14) (<1. 2 E-13)! (<6. 9 E-14) 1.4 E-04 {<8. 0 F-14 l. 9 E-04 Co-58 Ci 3. 7 ~

E-05 4. 3 E-05 9. 2 E-06 1.5 E-05 1.3 E-05 1.2 E-04 Co-60 6. 7 E-05 3.6 E-03 ~ 3.4 E-03 8.2 E-04 2.0 E-04 6.3 E-04 C"-51 (<l. 5 E-13) (<2. 4 E-13) E-l3) (<4. 1 E-13) (< 1. 9:"-13)

'<1.

6 3.6 E-C5 Cs-134 Ci 4. 7 E-06 2.9 E-06 1.8 E-Oo 9.0 E-05 li3 E-03 6.8 E-05 Cs-136 Ci (<1.8 E-14) (<4.6 E-14) (<2.0 E-14) (<7.1 E-14) 3. 2 E-06 (<S. 7 E-14)

Ci l. 2 E-05 9.4 E-06 8.0 E-06 1. 3 E-04 1.9 E-05 l. 2 E-04

(<2.3 E-14) 1.7 Z-06 (<1.7 E-14) 3.8 E-06 4.7 E-06 l.. 4 E-05.

La-140 (< l. 7 E-14) (<2. 5 E-14) (<1.4 E-14) l. 3 E-04 (<3.1 E-14) l. 9 E-04 Ha-54 Ci (<2. 6 E-14) {<5. 8 E-14) 1.8 E-06 2.S E-06 (<3.6 E-14) 2.4 E-05 Xb-95 Ci (<2. 1 E-14) (<4.1 E-14) (<1.9 E-14) (<3.3 E-14) i (<2.4 o-14) 3.7 E-06 Ru-103 (<1.5 E-14) (<2.9 E-14)- (<1.6 E-14) (<4.1 E-14) (<1.9 E-14)

Sr-89 Ci 5. 5 E-07 7. 0 E-07 3.4 E-07 <3.8 E-16 3.6 E-07 -2 6 E-Sr-90 Ci (<2. 0 E-16) (<2. 5 E-16) (<2.0 E-16) 4.6 E-06 8.2 E-09 8. 2 E-09 q'nt. pl 1.21 E-04 s.oo o-os 3.42 E-03 1.34 E-03 2.55 E-04

19 Table XZ Airvo cleases Gaseous Page Fissio;. and Activation Gases Xso ope Unit AUGUST 'EPTE~~fBER OCTOBER NOVEL!BER DECEa~lBER JULY'.39 A -Ll Ci E+00 4.61 E+00'.48 E+00 2.03 E+00 7.66 E-Ol 1.45 E+OC

'i 7.78 E-02 8. 7 E-02 (<3. 2 E-05) (<3.1 E-05) 1.82 E-02 3.23 E-01

<"-"5" 5. 9. E-02 6.58 E-02 .5.0 E-02 3.16 E-02 3.1 E-03 9.2 E-03 Ci 1.63 E-02 (<7. 1 E-06) 5.5S E-02 1.4 E-02. (<9.5 E-07) '(<2. 1 i-06)

~ i, an0 ti"-0 5.05 E-02 9.16 E-02 7.06 E-02 1.0 E-02 (<1. 1 E-06) (<3. S E-06)

C'i ge I 3I 1.51 E-02 3.45 E-02 (<4. 3 E-06) (<4. 5 E-06) 1.52 E-02 1. 76 E+00 33 3.23 E-:02 2.20 E+02 1.34 E+02 2.44 8+02 1.18 E+02 3.46 E-:02

~We- '3.a. Ci 3.31 E-02 2.21 E-01 2.64 E-Ol 7.62 E-01 4.9 E-01 8.79 E-01

.':"-135 Ci E+00 1.60 E+00 S.S9 E-Ol 1.37 E+00 6.05 E-Ol 1.06 E+00

~ 'w. ~ C"'.68 Ci 2.23 E-01 3.37 E-01 7.18 E-01 3.33 E-01 2.34 E-01 (<1. 4 E-06) 2.38 E-02 4. 2 E-02 4.70 E-01 1.71 E-Ol <1. 4 E-06 (<4. 7 E-C5 TG"al 3.33 E+02 2.27 E+02 1.40 8+02 2.49 E+02 1.20 E+02 3.52 E-:02 lialope"..s (Gaseous)

T.so'to Unit AUGUST SEPT~ ABER OCTOBER iNOVi~ (BER DECVJBER Ci 7. 1 E-04 2.5 E-03 1.2, E-03 9.7 E-04 2. 3 E-03 6. 8 E-03 T-- 33 1. 8 E-03 l.'4 E-03 1,6 E-03 l. 4 E.-03 1.3 E-03 l. I E-03 I- ~

35 Ci 7. 0 P;04 3.7 E-04 5.1 E-04 7.0 E-05 '1.0 E-04 (<1.5 E-13)

Bv-S2 Ci 9.0 E-05 (<5.6 E-14 1.7 E-04 3.9 E-04 l

Ci 4.36 E-03 3.84 E-03 2.44 E-C3 3.S7 E-03 2G

~ 4 ~ (I ~ A

~

~'

~

~ ATTACHt1EtlT I I

)/ADXOACT HASTE Pl'.POKZ July 1, 1979 to Deceiiiber 31, 1979 Daaa at sh~t. ~ >ant Caatas Cu. Pt.

7- 2-79 0. 510 1/IO Buried in Harnwe3.1, SC 7-1/i-79 0. 164 1,23/ It 7-16-79 1. 295 140 7-31-79 0. 633 1; 17/t 8- 3-/9 0. /t00 1/i0 8-15-79 Os102 195 S- 2/i-79 0.219 195 8-28-79 0. 454. 662 .

8-28-'79 0. 2/1 1/i 0 9- 6-79 0. 325 70.

9-1S-79 0.673 1/IO

'-26-79 0.569 556 10- lt-79 0. 36/I 165 10-11-79 0.009 195 10 /9 0./i86 1,065

~

, 10-18-79 l. /I 25 1/t0.

l0-24-79 0 266 768 10-25-79 0.070 517 11-29-79 0.297 1,330 12-1/I-7 9 1. /t/IO 150 12-2?-79 0. 096 123 21 shipments 10.068 Ci 9,242 Cu. Ft.

On site as of January 1, 1979 8.891 Ci 2,069 Cu. Ft.

ATTACHliEHT II I a

TURKEY PQINT: Uni ts 3 6 4 Environmenta'l Radiolo ical Honitorin

'(7-01-79 to 12-31-79)

l. Introduction This report is submitted in accordance with Turkey Point Plant Technical Specifications, 'I Environmental samoles were collected and analysed in conformance with the requirements of the Technical Soeci fications, The minimum frequency of collection and analyses for specific radionuclides and sample types as required by these specifications has been met or exceeded except where samples were biologically un-available.

Strontium analyses for this reoorting period have been

.delayed due to the relocation of'he State's Radiological Laboratory; these results will be shown in a separate report when analyses in prooress are completed.

2. The honitorin Pro ram Period Covered: This current report covers the period A 1~F1 R ~it'll: E i, from July 1, 1979 to December 31, 1979, I; 1 di monitoring at Turkey Point Plant is carried out by the Dept" of Health and Rehabilitation Services of Florida (DHRS).

All samples are collected and analysed by QHRS personnel.

Number of Sam les Analyzecl: A total of 770 analyses were performed on 606 samples collected from 35 different samplina locations during the period of this report, TABLE 1 summarizes the s>ean and range values of these analyses.

Split-Sa~m'le Aoalgses. Tv<eIve samples were collected to be analyzed by the QHRS/ERDA Split-sampling orogram.

3. Evaluation of Data a) Table I compares,'here applicable, the analyses of media sampled at various locations. with similar analyses of con-trol location samples; shows the mean and range of similar analyses 'at all samnlinz locations; lists the location with th'e highest values noted for th'e type of analysis made.

b) The higher Cs 137 value noted at sample location, T-56, on July ll, 1979 is attributed to the un-usually large amount of organic material in the sample.

3 c) The Il concen)ration at sampling location T-ge is con-sistent with H levels previously observed in the cooling canal system, The other canal location, T-97, had a slightly 1 ower concentrati on of>>l, d) Ho significant increases above oreviously reported data have been observed in Gross Beta-'S and 3H concentrations at location T-75 in the Fresh Water Canals.

e) The H concentrations in the ~round Hater !Hells at sampling locations T-91 and T-92 continue to be of.

the same magnitude as previously repor d.

d f) The concentration levels of Co and Co in the bottom sediments of the cooling canal at sample location T-B4 continue to be of tne same order of

.Oagnitude as previously reported, g) All da'ta have been compared with pre-operational data and have been found to be >>ithin previously observed limits.

r h) Where applicable, comparisons of test sample location data with that of the control sample sho;I no differences in concentration levels except as noted in TABLE 1, Conclusions The concentration level of any radionuclide reported in TABLE 1 will contribute much less than the maximum permissible limits of individual or population group exposure that could result i; there had been a continuous intake of radionuclides having concentration values equal to those oermi tted by APPEHDIK B, TABLE I I, 10-CFR-20. Therefore, the ooerations of Turkey Point Plant Units 3 8 4 are not contributing harmful effects or irreversible damage to either th environment or to the health and safety of individuals or population groups in the regions surrounding Turkey Point Plant,