ML17339B190

Semiannual Rept of Radioactive Effluent Releases, Jul-Dec 1978

ML17339B190
Person / Time
Site:	Turkey Point
Issue date:	03/01/1979
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17339B189	List: ML17339B188 ML17339B190
References
L-79-48, NUDOCS 8007220550
Download: ML17339B190 (26)

Text

ATTACiBKNT 1 SE."lIANNUAL REPORT OF RADIOACTIVE EFFLUENT RELEASES. PTP UNITS 3 6 4, 7/78 - 12/78 Introduction All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Specification requirements. The minimum frequency of analysis as, required. by Safety Guide 21 has been met or exceeded.

'Li uid Releases Aliquots of. representative pre-release samples were either isotopically anal-yzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and anal-yzed for gross beta-gamma activity in a 2m gas flow proportional counter. The effici-ency 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 determinatioas, 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 anaysis were used to conservatively, estimate the quantity of radi'oactivity released via the steam

\

generator blowdown system.

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

1. The reported values in Table I, page 1, include in their computation the quantity of radioactivity released from both the waste disposal system and the secondary system. The secondary system releases occurred when contaminated ~ater was blown down from the steam generators during primary to secondary leakage conditions, or when the generators were drained for repair or refueling, or during lancing of the generators.

7/78 - 12/78

2. The reported values in Table I, pages 2 and 3 are the'total quantities of radio-activity for individual nuclides released from the waste disposal system and the secondary system together. The values in Table I, page 4 are for the waste disposal system only and page 5 is for the secondary system only.

3. During primary to secondary leakage, release of several short-lived nuclides occurred from the secondary system, These short-lived nuclides. are not gen-erally detected in batch releases from the waste disposal system due to the long holdup'time of processed water. Only those isotooes that were detected in the secondary system releases were reported. All non-detectable isotopes are li.sted. as ( ).

4. Weekly and monthly, co'mposite samples for the waste disposal system vere pre-pared to give proportional weight to each liquid release made during the des-ignated period of accumulation.'he composites were analyzed for gamma emit-ting isotopes on a multi.channel 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 2t/ gas flow proportional counter. Tritium was deter-mined 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 volu e of the liquid waste released to determine the total quantity of,'ach isotope and of gross alpha activity released during

'the compositing period.

5. At least one representative batch of liquid effluent from the waste disposal system- was analyzed monthly for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multi-plied by the total'olume released for the month in ord'er to estimate the total dissolved gases released. If more than one batch of effluent was analyzed, the concentrations were weighted in an appropriate manner. The results are

7/78 - 12/78 totaled on a monthly basis in Table I, page 6. Dissolved gases from secondary system releases were determined from the samples of the individual releases.

Esotopic 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 indi-vidually for gamma emitting isotopes. Analysis of a representative composite for tritium, gro'ss alpha and selected b'eta 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 curies per quarter excluding tritium.and dissolved gases.

8. The following notes have been added to help explain some of the results in Table I: '

On pages 3 and 5 an entry entitled "Unidentified" is made in the isotope listing.

This activity is the result of an analysis of blowdown water yielding a low. gross beta gamma activity value and being multiplied by a large volume of water.

The low activity of tne blowdown water often makes isotopic analysis of the ~

water unreasonable and therefore a gross beta gamma counter efficiency is chosen so that the total activity determined by gross beta gamma analysis will approxi-mate the total activity which would'e. determined using an isotopic analysis.

Airborne Releases Airborne releases to the atmosphere occurred from release of gas decay tanks, via the instrument bleedl'ne, 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-spec-I, trum analysis, Sr-89-90 determination,. gross alpha analysis, and gross I

beta-gamma analysis.

7/78 12/78 c) Absorption of halogen radionuclides on a charcoal. filter and subsequent gamma-spectrum analysis, and 1

d) Condensation of water vapor in a gas sample followed by analysis for tritium using liquid scintillation techniques.

users All sporadic gas releases from the plant. which were not accounted for by the above methods were conservatively estimated by curies of Xe-133 equivalent by of the plant vent process monitor recorder chart.

The maximum rated capacity for the hogging gets and the maximum measured flow-rate for the condenser air egectors, and an-. estimate. of the rate of exhaust. from .the atmospheric dumps were used to conservatively estimate the airborne releases from the secondary system whenever applicable.

The= following comments will aid in the interpretation and evaluation of .the airborne release data presented in Table Il.

1. Calculation of total radioactivity of noble gases, Z-131, and particulates 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 calendar quarter.

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

Total curies released in aseous waste durin uarter x 100%

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

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

E 'ec' MPCi

< 10,000 3

, where Q. ~ i release rate of th nuclide,. Ci/sec permissible concentration of and ?PC' i maximum the ith nuclide.

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

in Ci, for the th nuclide (t~ > Sd), during the calendar quarter by the seconds in the quarter.

MPC 'alues were obtained from Appendix B, Table II, Column 1; 10'FR 20.

The MPC chosen was the most conservative value of either the soluble or insol-uble MPC for each isotope.

The percent of applicable lind.t was determined as follows:

X'f Limit ~

EMPCi x 100%

3 10,000 m /sec

4. The maximum gaseous release rate for each month is listed in Table II, page 1,

~ under section A, line 3. The applicalbe limit for maximum allowable relea'se rate is 6.7 E+04 gCi/sec..

5. All values reported in Table II, pages 2 and 3, include the particulate, gaseous, and/or halogen activity released from the containments during purging, auxi.liary building (leakage from pumps, valves, etc), the gas waste disposal system and the secondary system during conditions of primary to secondary'ystem leakage.

If a minimum detectable activity value was not calculated for an isotope, it will be listed as ( ) .

1978 Table I Report of Radioactive Effluents: Liquid Page 1 Liquid Releases July August September October November December A. Gross Radioactivity (8-y)

1. Total Release (mCi) 9.33 E+Ol 1.36 E+02 9.02 E+Ol 4.73 E+01 3.11 F+01

2. Avg Concentration During Releases(pCi/ml) 7.0 E-10 1. 3 E-09 1. 7 E-09 8.9 E-10 9.1 E-10 1.0 E-09

3. Avg Concentration for Month (pCi/ml) 3.1 E-10 7.2 E-10 4.2 E-10 1.7 E-10 1.2 E-10 2.0 E-10 (p Ci/ml) 7. 8 E-09 1.2 E-O& 7.0 E-09 3.3 E'-09 4.8 E-09 3.9 E-09

4. Max Concentration Released

5. Percent of Technical Specification Limit for Total Activit Released (X) 6.4 E+00 2. 7 E+00 H. Tr'itium

1. Total Release (Ci) 1.62 E+02 8.70 E+Ol 1.03 E+02 7.66 E+Ol 7.88 E+01 1.11 E+02 2 v Concentration Durin Releases nCi ml 1.2 E-06 8.1 E-07 2.0 E-06 1.4 E-06 2.3 E-06 2. 0 E-06 4.8 E-07 2.8 E-07 2.9 E-07 3. 9 E-07

3. Avg Concdntration for Month (pCi/ml) 5.3 E-07 4.4 E-07 ~

C. Didsolved Noble Gas

1. Total Release (mCi) 2.17 E+00 4.90 E+Ol 3.91 E+Ol 4.66 E+00 1.22 E+01 1.86 8+02

2. Av Concentration Durin Releases (pCi/ml) 1.6 E-ll 4.7 E-10 7.5 E-10 8.& E-11 3.6 E-10 3.4 8-09

3. Avg Concentration for Month (801/ml) 7. 1 8-12 2. 5 8-10 1. 8 E-10 1. 7 E-ll 4. 5 P;11 0. 5 P.-10 D. Gross Alpha Radioactivity

1. Total R'elease (mCi) (<1. 7 E-08) (<1. 7 E-08 (<2. 2 E-08) (<2.4 E-O&) (<1. 1 E-08) (<l. 0 E-OS

2. Avg Concentration During Releases(u Ci/ml) (<1.3 E-19 (<l. 6 E-19 (<4. 2 E-19) (<4. 5 E-19) (<3. 2 E-19) (<l. 8 E-1

3. Avg Concentration for Month (pCi/ml) (<5.6 E-20 (<8. 8 E-20 (<l. 0 E-19) (<8. 7 E-20) (<4. 1 E-20) (<3. 5 E-2 E. Volumes

1. Vol of Liquid Waste to Discharge (Liters) 4.50 E+06 &.08 E+06 3.45 E+06 2.10 E+06 1.35 E+06 3.43 E+06

2. Vol of Dilution Water During Rel (Liters) 1.33 E+ll 1.05 E+ll 5.22 E+10 5.30 E+10 3.43 E+10 5.53 E+10

3. Vol of Dilution Water for Month (Liters) 3.04 E+ll 1.94 E+ll 2.17 E+ll 2.76 E+11 2.69 E+ll 2.05 8+11

'21 2 ~ Et' ~ 6 '4 Iml

1978 Table I Report of Radioactive Effluents: Liquid Total Pa e 2 Isoto e Unit "'ul Au ust Se tember October November December Ag-110m mCi 6. 42 E-Ol 5.20 E-01 1.08 E+00: (<4.7 E-08) 7.63 E-Ol 1.51 E+00 Ba-140 mCi (<2.7 E-.07) (<3.5 .E-07) (<4.8 E-07) (<4. 1 E-07) (<9.9 E-OS) (<l. 1 E-07)

Co-58 6.25 E+00. 4.15 E+Ol 2.33 E+01 8.49 E+00 3.48 E+00 5 ~ 04 E+00 Co-60 mCi 3.73 E+Ol 2.72 E+Ol 3.59 E+01 2.39 E+01 1.53 E+Ol 2.61 E+Ol Cr-51 mCi E-07) 6.54 6+00 2.09 E+00 (<2.8 E-07) (<2.1 E-07) 8.06 E-01 Cs-134 mCi i..4.61 E-Ol 5.36 E+00 6.61 E+00 1.79 E+00 '.76 E+00 1.97 E+00 Cs-136 mCi. (<1.5 E-07) 4.9 E-.ol (<3.5 E-08) (<2. 8 F;08) (<3.0 E-08) (<3.0 E-08)

Cs-137 9.95 E-01 8.45 E+00 1.39 E+Ol 2.80 E+00 4.76 E+00 3.52 E+00 Cs-138 mCi 2.06 E+00 F-18 3.92 E-01 Fe-59 mCi (<6. 3 E-08) 6.01 E-,01 (<7. 5 E-08) (<5. 8 E-08) (<4. 9 E-08) (<5. 5 E-08)

I-131 mCi 1. 09 E+00 3.09 E+01 1.50 E+00 4.67 E-01 1.75 E-02 5.66 E+00 I-132 mCi 7.92 E+00 I-133 mCi 9.'05 E+00 7.64 E+00 (<4. 3 E-08) (<3.6 E-'8) (<2.8 E-08 6.64 E+OO I-134 7.29 E+00 I-135 mCi 9.10 E+00 La-140 mCi (<1. 8 E-08) (<2.5 E-08) (<l. 2 E-08) '(<8. 3 E-09) (<l. 1 F;08) '8.51 E-Ol Mn-54 ~ mCi.: ;3;95 E-01 1.29 E+00 1.40 E-Ol 5.75 E-02 3.49 E-02 2.35 E-ol Mo-99/Tc-99m mCi. 1.07 E-01 8.27 E-01 (<2.4 E-07) (<2. 1 E-07) (<1.7 E-07) (<1.6 E-07)

Na-24 mCi. 1.48 K+00 Nb-95 mCi (<1.2 6.0 E-Ol 3.92 E-01 (<3.3 E-08) (<3. 2 E-OS) (<3.2 E-08) 5'-07)

Ru-103 mCi (.<2. E-08) 3.06 F.-ol (<4.5 E-OS) (<3.4 E-OS) (<2. 6 E-OS) (<2.8 E-08)

Sb-124 mCi (<3.1 E-08) 6.95 E-Ol 3.88 E+00 3.21 E-01 3.19 F;02 2.07 E-Ol Sb-125 mCi 2.96 E-Ol (<9.9 F.-08) 1.43 E+00 2.54 E-01 2.12 E-Ol 1.81 E-01 MATl" ~ Neinibns ~: 4n nirr nl bnsn~ rr nrem anni ns r ln>>m ~nn,.l I Cia& ii 4>>>>Ci /ml

8.

1978 .'gable I Report pf Radioactive Effluents: Liquid Total Page 3 Isotope Unit July August September November December E-03'ctober Sr-89 mCi l. 3 E+00 1. 3 E-01 6.0 8.4 E-02 1.8 E-02 (<2.7 E-09)

Sr-90 mCi (<6.7 E-09) (<3.0 .E-09) '<2.9 E-09) (<3.0 E-09) 7. 3 E-03 (<2.7 E-09)

Unidentified mCi 7.16 E+00. 2.71 E+00 9.11 E+00 4.71 E+00 3.37 E+00 Total mCi 9.33 E+Ol 1.36 E+02 9.02 E+01 4.73 E+01 3.11 E+Ol 5.61 E+01 NATE: Number.. in nnrrnthesos rrnresont maximum sensitivitv $ n uCi/ml.

9.

~ ~

1978 Table I Report of Radioactive Effluents: Liquid Haste Disposal System Page 4 Isoto e Unit 'ul August September October November December

~

ii

~

Ag-ll0m mCi 6,42 E-01 5.20 E-01 1.08 E+00.'<4.7 E-OS) 7.63 E-01 ~

1.51 E+00 Ba-140 mCi (<2.7 H-07) (<3.5 E-07) (<4. 8 E-07) (<4. 1 E-07) (<9.9 E-08) (<1. 1 E-07)

Co-5& mCi, 2..58 E+00. 3.16 E+01 2.25 E+01 7.36 E+00 3.48 E+00 5.04 E+00 Co-60 mCi 6.61 H+00 4.77 F+00 6. 2 8+00 3.55 8+00 .23 F+0 4 .+

Cr-51 mCi (<1.9 E-07) 6.54 E+00 2.09 E+00,(<2.8 E-07) (<2. 1 E-07) 8.06 E-Ol Cs-134 mCi 4.61 E-01 1.86 E+00 1.12 E+00 1.79 E+00 .1.44 E+00 1.97 E+00 Cs-137 mCii: 8.81 E-01 2.95 E+00 1.80 E+00 2.80 E+00 2.42 E+00 2.95 E+00 Fe-59 mCi (<6.3 E-OS) 6.01 E-Ol (<7. 5 E-OS) (<5. 8 E-08) (<4.9 E-08) (<5. 5 E-08)

I-131 mCi. 7:94 E-02 1.93 E+01 1.50 E+00 4.67 E-Ol 1.75 E-02 3.41 E+00 I-133 7.84 E-02 5.74 8+00 (<4. 3 E-08) (<3. 6 E-OS) (<2.'8 E-08) (<2. 8 E-OS)

La-140 mCi (<1.8 E-08) (<2.5 E-08) (<l. 7 E-08) (<8. 3 E-09) (<1. 1 E-08) 8.51 E-Ol Mn-54 3.95 E-01 1,27 E+00 1.40 E-Ol 5.75 E-02 3.49 E-02 2.35 E-ol Mo-99/Tc-99m mCi 1.07 E-01 8.27 E-Ol (<2.4 E-07) (<2.1 E-07) (<1. 7 E-07 <1.6 E-07 Nb-95 mCi (<1:2 E-07) 6.0 E-01 3.92 E-01 (<3.3 E-08) (<3.2 E-08) (<3.2 E-08)

RU-103 mCi (<2. 5 E-08) 3.06 E-Ol (<4. 5 E-08) (<3.<i E-OII). (<2. 6 E-OS) (<2. 8 H-0&~

Sb-124 mCi (<3.1'E-08) 6.95 E-01 3.88 H+00 3.21 F.-01 3.19 E-02 2 07 Sb-125 mCi. , 2.96 E-01 (<9.9 E-08) 1.43 E+00 2.54 E-Ol 2.12 E-Ol 1.81 E-01 Sr-89 mCi 1. 3 E+00 9.55 E-02 (<2. 9 E-09) . 8. 4 E-02 1.8 E-02 <2. 7 E-09 Sr-90 mCi (<6.7 E-09) (<3.0 E-09) '<2.9 E-09) (<3.0 E-09 7. 3 E-03 (2.7 F.-09 Total mCi 1.34 E+01 7.77 8+01 '.21 E+Ol 1.67 E+Ol 1.17 E+Ol 2.12 E+Ol HA't'tt ~ titinr lir.i r in n i~not.hn~nc. 1'nnvnr nnt ms ii~ian nntt ~ '.9 t Air i t't ~ 4n itPj ltnl

1978 Table I Re'port of Radioactive Effluents: Liquid - Secondary System Page 5

' ' October I Isotope Unit Jul Au ust Se tember November December Co-58' 'mCi 3.67 E+00 9.86 E+00 8.3. 1.13 E+00 E-01.'.97 i Co-60 mCi 3.07 E+Ol 2.24 E+01 E+Ol 2.03 E+01 1.21 E+Ol 2.20 E+01 Cs-134 mCi 3.5 E+00 5.49 E+00 3. 2 E-01 Cs-136 mCi 4.9 E-Ol Cs-137 mCi 1.14 E-Ol 5.5 E+00 1.21 E+01 2.34 E+00 5.73 E-Ol Cs-138 mCi 2.06 E+00 F-18 mCi 3.92 E-Ol I-131 mCi 1.01 8+00 1.16 E+01 2.25 E+00 I-132 mCi 7.92 E+00 I-133 mCi. 8.97 E+00 1.9 E+00 6.64 E+00 I-134 mCi 7.29 E+00 I-135 mCi 9.10 E+00 Hn-54 2.48 E-02 Na-24 mCi 1.'48 E+00 Sr-&9 mCi (<2. 9 E-09) 3.34 E-02 6. 0 E-03 Sr-90 mCi <2.9 E-09 <2.9 E-09 <2.9 E-09 Unident'ified mCi 7.16 E+00 2.71 E+00 9.11 E+00 4.7l E+00 3.37 E+00 Total mCi 7.99 E+01 5.80 E+01 4.81 E+Ol 3.05 E+Ol 1.95 F+01 3.48 8+01 NA'I'F: Wnmbr rn in norman(hnses rnnrr srnl mnximnm srnsitiirit I in>>Ci lml

1978 Table .1 Report of Radioactive Effluents: Liquid Dissolved Gas Page 6 Total Jul Au ust Se tember October November December Kr-85 mCi (<4. 7 E-06) 3.47 E+01 3.91 E+Ol'<9.

(<6.3 E-06) (<4.6 E-06) '<5. 9 . E-06)

Xe-131m mCi '(<6. 9 E-.07) (<2. 1 E-06) 9 E-07) (<7. 1 E-07) (<6. 3 E-07) (<9. 5 E-07)

Xe-133 mCi 2.17 E+00 1.35 E+01 (<5. 9'-08) 3.99 E+00 1.13 E+Ol '1.81 E+02 Xe-133m (<1.3 E-07) (<3.7 E-07) (<2.'1 E-.07) (<1. 6 E-07) (<1.5 E-07) 2.48 E+00 l

Xe-135 mCi (<1.7 E-08) 8.03 E-Ol (<2. 5 E-08) 6.72 E-01 8.5 E-01 3.00 E+00 Waste Dis osal S stem Kr-85 mOi (<4.7 E-06) 3.47 E+01 3.91 E+Ol (<6.3 E-06 <4.6 E-06 ~<5. 9 'H-0 Xe-131m mCi (<6;9 E-07) (<2.1 E-06) (<9. 9 E-07) (<7. 1 E-07) (<6.3 E-07) (<9. 5 E-07)

Xe-133 mCi 2.17 E+00 1.35 E+01 (<5.9 E-08) 3.99 E+00 1.13 E+01 1.80 E+02 mCi (<1.3 E-07) (<3.7 E-07) (<2.1 E-07 <1. 6 E-07 Xe-135 mCi (<1.7 E-08) 8.03 E-01 (<2.5 E-08) 6.72 E-01 8i5 E-Ol 2.53 E+00 Secondary System Kr-85 mCi Xe-131m mCi.

XG-133 mCi 1.35 E+00 Xe-133m mCi Xe-135 mCi 4. 7 E-01 HOT E: Numbers in parentheses represen t maximum sensitivit y in p Ci/ml

'12 1978 Table II Report of Radioactive Effluents: Airborne Page 1 July August September October November December A;- Fission & Activation Gases.

1.. Total Release (Ci 2.25 E+03'.

2.48 E+03 1.87 E+03 2.38 E+03 2.13 E+03 2.23 E+03 Av 'Rel Rate for Period(liCi/Sec) 8.3 E+02 9.2 E+02 7.2 E+02 8.8 E+02 8.2 ':E+02 8.3 E+02

+3. Max Rel Rate for Period( Ci/Sec) 4.1 E+04 1.1 E+04 8.9 E+02 2.5 E+04 5.3 E+04 2.8 E+04

• Maximum airborne release rate averaged over one hour for each month. Technical Specification limit is 6.7 E+04 yCi/Sec averaged over one hour.

B. Iodine-131

~~meal hZUn C

2. Avg Rel Rate for Period( Ci/Sec) 1. 5 E-03 3.7 E-03 6.2 E-04 1.3 E-03 1. 4 E-04 6.7 E-03 C. Particulates

1. Particulates with tq>8d (Ci) 4.07 E-04 '.75 E-02 9.26 E-03 2.78 E-04 2.71 E-05 . 2.01 F.-04

2. Av Rel Rate for Period iCi/Sec) 1.5 E-04 6. 5 E-03 3. 6 E-03 1.0 E-04 l. 0 P.-05 7.4 E-05

3. Gross Al ha Radioactivit Ci ~

3. 1 E-09 3. 7 E-08 7. 3 E-08 <2.8 P.-12 <2. 8 F.-12 <3. 1 F;12 Tritium

1. Total Release (Ci) 1.67 E-Ol 7.9 E-02 1.52 E-Ol 5.27 E-02 1.27 E-Ol 1.63 E-01

2. Avg Rel Rate for Period(pCi/Sec) 6.2 E-02 2.9 E-02 5.8 E-02 2.0 E-02 4.9 E-02 6. 0 E-02 E. Percent of A licable Limit uarter III uarter IV

1. Fission & Activation Gases (%) 6.9 E+00 7.0 E+00

2. I-131 and Part. (t> >8d) (%) 2.2 E-01 2. 7 E-01 NOTE: Numbers. in parentheses represent maximum sensitivity in pCi/cc.

13 1978 Table II. Airborne Releases Particulate Page 2 Isoto e Unit Jul August September October November December ."

Ag-110m Ci (<4.7 E-14) 4. 8 E-05 (<4. 8 E-13).'<

(<3.3 E-14) (<1.9 E-14) ~

(<5.0 E-14)

Ba-140 Ci 7.5 E-06 7. g H-12) (<5. 2 E-12) 2.0 E-05 (<7. 0 E-14) (<1. 3 E-13)

Ce-141 Ci (<3.7 E-14) 2.6 E-05 (<2.5 E-13) (<2. 1 F.-14) (<1. 6 E-14) (<2. 3 E-14)

Co-57 (<1.7 E-14) 3.2 H-05 2.1 E-05 (<1. 3 E-14) (<9. 4 E-15) (<l. 4 E-14)

Co-58 Ci 2.5 E-04 1. 3 E-02 6.9 E-03 9. 2 E-05 1.4 E-05 5. 5 E-05 Co-60 9. 2 E-05 1. 8 H-03 1. 1 E-03 3. 5 E-05 1.3 E-05 2. 1 E-05 Cr-51 (<2.4 E-13) l. 5 H-03 6.0 E-04 (<2. 1 E-13) (<8.0 E-14) 1. 5 E-05 Cs-134 Ci 1.5 E-05 1.1 E-05 4. 3 E-05 3.8 E-05 (<2.1 E-14) 3.6 E-05 Cs-136 Ci (<3.8 E-14) (<4.2 H-13) (<3,0 E-13) 6.9 E-06 , (<1. 1 E-14) (<4. 2 E-14)

Cs-137 2.4 '-05 2. 1 H-05 6,7 E-05 5.0 E-05 (<2.0 E-14) 5.9 E-05 Fe-59 Ci (<4. 6 E-14) 1.2 E-.04 6.2 E-05 (<4. 6 'E-14) (<3. 0 E-14) (<5. 9 E-14)

I-131 Ci 5. 6 E-06 6.3 H-06 1.3 E-05 1.5 E-05 (<1.1 E-14) '.2 E-05 La-140 7.5 E-06 (<1.9 H-13) (<1.3 E-13) 1.2 E-05 (< l. 2 E-14) (<4. 4 E-14) 1fn-54 (<3.4 E-14) 3.4 E-04 2.0 E-04 S. 0 H-06 (<2.2 E-14) 2. 1 E-06 Nb-95 Ci (<3.0' 14) 2.6 = E-04 1. 3 E-04 (<2. 5 . E-14) (<1. 3 H-14) (<2. 9 E-14)

Ru-103 (<3.7 E-14) 8. 3 E-05 (<4. 6 E-13) (<2. 9 E-14) . (<1.1 L'-14) (<2.9 - H-1 Sb-'.124 (<3.7 E-14) 1, 7 E-04 6. 2 E-05 (<2. 8 E-14) (<2. 1 E-14) (<5. 5 E-14)

Sr-89 5. 2 E-06 5.9 E-06 2.7 E-06 4. 4 E-06 6.5 H-08 1. 0 E-06 Sr-90 Ci 1. 0 H-07 4. 3 H-07 6. 6 H-07 (<1.5 H-15) (<G. 5 E-16) (<1. 2 E-15)

Zr-95 Ci (<4.9 E-14) 1. 1 E-04 6.2 E 05 (<4.0 E-14) (<2. 4 E-14) (<4. 2 E-14)

Total Ci 4.07 E-04. 1.75 E-02 9.26 E-03 2.78 E-04 2.71 E-05 2.01 H-04 NATE: Ninnbnrs 1n pnrentbese. represent ma::1nnw sensitivity in pCi/cc.

1978 Table II Airborne Releases Gaseous pae3 Fission 6 Activation Gases Isotope Unit July August September October November December Ar-41 Ci 1.27 E+Ol 4.41 8+00 1.94 E+01 8.19 E+00. 1.05 E+01 2.12 E+01 Kr-85 Ci (<3. 8 E-05) 3.34 E-02 '<3.5 E-05) (<3. 7- E-05) (<3. 4 E-05) 6.64 E-02 Kr-85m 3.58 E-01 7. 3 E-06 (<1.1 E-O?) 2.17 E-01 2.77 E-01 6.85 E-Ol Kr-87 Ci (<2.6'-O?) (k2.5 E-06) (<2.4 E-07) (<2.9 E-07) (<3.1 E-07) 6.17 E-01 Kr-88 1.38 E-01 (<5.2 E-06) (<2.5 E-07) 1.44 E-01 2.34 E-01 5.81 E-01 Xe-131m Ci 3.61 E+00 1.32'-02 (<4.8 E-06) (<6. 2 E-06) (<7. 2 E-06) 1. 1 E-02 Xe-133 Ci 2.22 E+03 2.47 E+03 1.85 E+03 2.36 E+03 2.11 E+03 2.19 E+03 Xe-133m Ci 3.70 E+00 5.49 E-01 7.01 E-02 2'22 E+00 1.58 E+00 2.30 E+00 Xe-135 Ci 7.38 E+00 1.08 E+00 2.37 E-01 5.09 E+00 4.78 E+00 1.26 E+Ol Xe-135m Ci 9.81 E-02 (<1. 3 E-06) (<1. 6 E-07) (<1.8 '-07) (<1.7 E-07) (<2.9 E-06)

Xe-138 Ci (<3.0 E-07) (<5.5 E-06) (<3.0 E-O?) (<3.5 E-O?) (<2.7 E-07) (<5.1 E-06)

Total 2.25 E+03 2.48 E+03 1.87 E+03 2.38 E+03 '.13 K+03 2.23 E+03

~

~

Ilalo ens (Gaseous)

Isoto e Unit Jul Au ust Se tember October November e em e I-131 4. 1 E-03 1.0 E-02 1.6 E-03 3.4 E-03 3.7 E-04 l. 8 E-02

. I-133 Ci 5.3 E-03 1.3 E-03 7.8 E-03 6. 1 E-03 6. 8 E-04 1.0 E-02

. I-135 Ci 1. 2 E-03 (< 2. 0 E-13) 6.7 E-03 8.8 E-04 (<7.7 E-14) 7. 2 E-03

Hr-82 Ci 3.5 E-04 1.6 E-04 1.4 E-04 ~

4.6

'otal 1.1 E-02 1.13 E-02 1.61 E-02 1.05 E-02 1.19 E-03 3. 6 E-02 NOTE: Aumbers in parentheses represent maximum sensitivity in >iC1/cc.

ATTACHMENT 2 COACTIVE HASTE REPORT .

I July 1, 1978 to December 31, 1978 Date of Shipment Cmies CQ Ft 7-12-78 3.000 60 Buried in Barnve11, SC 7-18-78 0.007 1 5750 I~

7-20-78 0. 792 100

'-22-78 108.000 100 7-28-78 53.919'.001 100 7-28-78 1, 700 8-OS-78 0.002 1,700

'-25-78 425.000 100 8-31-78 547.000 . laO 9-01-78'-07-78 0.820 '1,095 2.260 I~

110 9-12-78 3.000 100 9-13-78 3.646 195 9-13-7S, 5.352 100 9-18<<78 0.420 610 9-22-78 0.325 850 9-26-78 1.076 1,132 9<<28-78 3.200 90 9-28-78 0.027 1,300 9-29-78 . 1.892 1,700 10-03-78 0.801 1,262 10-03-78 4. 285'.965 195 10-09-78 100 10-10-78 2.983 1, 700 10-12-78 2.075 110 10-16-78 0.550 100 10-16-78 0.540 150 10-18-78 1.080 150 10>>'19-78 '0.504 300 10-20-78 0.432 150 10-23-78 0.658 195 10-25-78 6.466 110 10-25-78 1.260 150 10-27-78 1.277 240 10-27-78 0'. 360 '50 11-01-78 0.540 150 11-03-78 0.504 300 11-03-78 1.462 195 11-09-78, 0.511 195 11-13-78 0.038 195',113-11-28-78 0.459 11-29 0.694 1,000 12-02-78 110.000 100 12-04-78 1.152 100 12-07-78 0.612 300 12-11-78 0.318 100 12-13-78 0.058 195 47 Shipments 1,301.323 Ci 21,997 Cu.. Ft.

On site as of January 1, 1979:

1.599 868 Cu. Ft.

ATTA~iT 3 '16 TURKEY POINT: Units 3 & 4 Environmental Radiolo ical Monitorin (7-01-78 to 12-31-78)

1. Xntroduction This report is submitted in accordance with Turkey Point Plant Technical Specifications.

All environmental samples were collected and analyzed in conformance with the requirements of the Technical Specifications. The minimum frequency of collection and analyses for specific radionuclides and sample types as required by these specifications has been met or exceeded.

2. The Monitorin Program Period Covered: This current report covers the period 1, 1978 to December 31, 1978.

from'uly Anal tical Res onsibilit : Environmental'adiological monitors.ng at Turkey Point Plant is carried out by the Orlando Radiological Laboratory of the Department of Health and Rehabilitation Services of Florida (DHRS). All samples are collected and analyze'd by DHRS personnel.

Number of Samples Analyzed: A total of 702 analyses on samples collected, from 35 different sampling locations weze per-formed during the period of this report. TABLE 1 summarizes the mean and range values of these analyses.

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

3. Evaluation of Data a) As applicable, TABLE 1 reports data for sampling locations that have concentrations of a particular

=-

radionuclide higher than 'the observed mean for all sampling locations where the same type of sample materia'1 was collected and analyzed for that parti-cular radionuclide.

b) The "

Zr, Ru, and '""Ce found in sponges collected at locations T-5'9 T 69I T 86' 93/ T 94 and T-95 could be attributable to fallout. Similary, these radionuclides were noted also in the assay of samples from soil samples at locations T-52, T-S7, T-,.58, T-5S, T-'56, T-57 and .could also be 'attributa3Qe to weapons testing fallout.

c) Recognition must. be given that data reported herein could be influenced by the residual fallout from the. Chinese weapons "ests of March, 1978.

d) The ~H concentration at sampling location T-84 is consistent with ~H levels previously observed in

.the Cooling Canal System. The other canal location, T-97, had a slightly lower concentration of ~H. ~

e) No increases above previously reported data have been observed in GB-DS and ~H concentrations at location T-75" in the Fresh Water Canals.

f) The ~H concentrations in the Ground Water Wells at sampling locations T-88, T-91 and T-92 continue to be of the same magnitude as previously reported.

4

g) No significant increases aboveyreviously reported concentration levels of Co, Co, ' Cs, and

""Ce have been observed. in. the- bottom sediments in the Cooling Canal at sampling location T-84.

h) Trend plotting of air particulate and direct radiation data, reveal. no plant-related, variations.

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

j) Where applicable, comparisons of test sample location data with that of. the control sample show no differences in concentration levels except as. noted in TABLE 1..

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

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

,r 5

~ ~ a 18 TA8LE 1 ENVIRONHENTAL RAOIOLOGlCAL HONITORlNG PROGRAH SUtgtARY NAIIE OF FACILITlf amrsr Foltttsraur Dstr 2 5 DOCKET II0.55-255 Florida

-252'OCATION OF FAClLITY Dade Count Location with Ni hest Hean Control Number of All Indicator Nonroutine Number of Locations Sample Location Location~a ~

Analysis Reported Hedium or Patt+ay Sampled Unit for Sites Samples Analyses Hean Range Oistance and Oirection Elean Range Hean Range Heasurements

l. Air Filters

- 0.004- Boy Soout CMTp .022 .004- .020 .007" Air pci/aP att .02 .041 1.1 .

0.047 .047 Particulates .

4-7'Ll-72E ND(b) 208 Bone l.l.a Air Zodines pCi/h a$ 1Z 208 5-7 '

V-64 a Natcjjja Substaticn, 5.8 5-7 5.8 , None 132 ttlami, Etg, 30 miles ial t tell ~ Ilr 1.3 Preoi ita- r 23, t on.

24 2.7 tG-22 T-52E PlorMa City 4.8 ND-22 1,3 ND-4 Suustaticaj, WestF 8 mQe 24 (1' 'ti-52E Florida City SuustationD West,8mQes 2.7 ND-8 ttD P

~

5 I l.t j."J;"i 24 200 Nore ~:," < 200 )'I

( a ~

5

4 M 19

'Location with Hi hest Hean Control Huaher of All indicator Honroutine "Humber of Locations Sample Location Location~ ~

Reported fledium or Pathi~ay Analysis Heasureaents Samoled Unit for Sites Samples Analyses Hean Range Distance and Direction Ilean Range ~

Hean Range

2. Water 20 20 < 200- 9-51; Ilaaastead Bayfront 350 . < 200-2.1 Estusl'Lna 10 500 Parf, NN4, 2 mQes '00; C

Sr-89 10 19 Sr-90 10 20 19 2870-2.1.2 Cool Cana 14 14 298 2700-8800 T-84~ Discharge Canal

~

soReide.of Sedge " .. 412 8800, Sr-89

r-90 2 HD-2 T-97: loch- Msetta, cn- < l.'D-2 Rte l 12 12. 135 t&-460 -

T-75<. Florida City 268 160 2,1.3 Fresh Hater> GQ.DS

~taW .5 miles 460 Ca GS-UPS 12 12 12 12 287. < 200- ~ ~ T-75< Flnrida City'Cana 573 250- =

H00 RR, 1,5 miles 1100

0 20

'ocation with Hi hest Hean Control Number of Pl 1 Indicator Nonroutine I Number of Locations Sample Location Location~a~

fledium or Pathway Reported Analysis Sampled Unit for Sites Samples Analyses Hean Range, Distance and Direction ilean Range Hean Range HeasureLents

~ =

2.2 Potabla loi8 6-15 ~

T-57'olan's Faxms, QW, 14 Waxer mila K5 ad.les

< 200 'I 6 12 12 979 . < 200- '&92) Hall 024K~. SSH~ 2020. 1840-2.3 Gruml inQes 2200' Hater Wells I ~ I 08r 12 . ~

I j

21

~

Location with Hi hest Hean of

'umber All indicator Control Location~ ~ Honroutine Humber of Locations Sample Location Reported fledlum or pathway Analysis Distance and 'Oirection llean Range Hean Range Heasurements Sampled 'Uni

( for Sites Samples Analyses Hean 3.0 ~ Bottrm Sea\mnts c% ICe 600 T 84i Dhu8carge.Canal, 500 400- .

3.1 Cool

~ttside of Bridge 00 c

sos 220, 440 T-84c Discharge Canal, 440

~ttside of Bridge

$ cCo 93 230 T-84c Disdcarge Canal, 93 , 230 8~su ide of Bridge T-84c Discharge Canal< 3400 c OCo 7'33 925 3400.

8~su ide of Bridge

".Sr 4 4 Hone

$ 0g 4 c,c ICs 2 2 70 140 84c Discharge Canal, 70 '140 Southside of Bridge "Sr

$ 4g 7

)ledium or. Pathway 4.0 4.1 Sampled Biota Ccustacea Uni

/kg t

'e Analysis for Sites 6

Number Samples of Analyses

~

I

\

All Indicator Locations Hean I

Range

'2 Location 44ith Hi hest Hean Sample Location Nstance and Oirection iiean Range Control Locationta~

Hean Range Numher of Honroutine Reported Heasurements 44sr 5 I

(o)

~

6 180 ND +00 T-94> Pa~n Key, S93, 900 Fables

'444'kg

"'au N),

4.2.a Fish .6: 6 ~ 230 ND-800 T-69> Elliott Key, South 800 UIIRNlm eiB, ESE, 7 miles (d) lllCe 400 200-500 T-81! Cml Sound, Hat 400

~ DI9chaÃgo Canal

I

'I 1

~ l I I

~

l, I .'23 I

ocation With Hi hest Hean Control Humber of All.Indicator Honroutine Humber of Locations Sample Location Location~a~

alodium or. Patlway Analysis Reported Sampled Unit for Sites Samples Analyses Bean . Range Distance and Direction llean Range Bean Range Heasurements 4.2.b Pish Herbal are (e)

$ 08r 302 16 '-59a Elliott KCb Ei 16 8 mmles l)ICe

.3.s Hanstee pCi/kg Ce .6 6 Grass

~ 'Sr 4 a 08r

.3.b ~Sees

• a 1lCe 1783 4500 59a Elliott Key, E> 500 8

a 0agn 6 00 T 86a least Arsenid~.

Key, Card Sounds 3

~i miles'-93a

. 20 tQ-120 Pelican Bank East 120 X.S miles

~o

~o ~ ~

Location'with Hi hest Haan Hunker of 0

All Indicator Control Humber of Locations Location Location Honroutine Sample fhdium or Pathway Analysis Reported Samoled Unit for Sites Samples Analyses iIean Range Gistance and Direction IIean Range liean Range Heasurements 5.0 Terrestrial B~oth (f) 5.2.1 Small c sos 210 190-230 T-58< On Site Entrance 210 Bniiioxo 25 18-32 T-58< On Site Entrance ~

25 1

'2.3 Maxirove ~ nSr 7' teens Iaavea s OSr ~ 7 :6.7 21 51c Haaestead Bayfmnt 21 Par N%4, 2 miles

.3 Soil 1 le 7 . '94 90-950 56'rinceton Sub- 950 statitn, NQ9, 8 miles lb%Os 7 243 700 57'olan's Parms,R4f, 700 miles 4~Sr 7

$ 0Sr

25

~

Location with Hi hest Flean Control of

'umber I All Indicator Honroutine Humber of Locations Sample Location Location~-

Flediun or Pathway Analysis Reported Sampled Unit for Sites Samples Analyses Range Distance and Direction llean Range Hean Range Heasurement Notes i'>T-64'ae s , Hiemal, , 30 les

"'m-Nno t

">ma.>et

<'la