ML17339B190
| ML17339B190 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/01/1979 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17339B189 | List: |
| 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.
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 users 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:
3 E
< 10,000
, where Q.
MPCi
'ec'
~ release rate of i nuclide,. Ci/sec th and ?PC' maximum permissible concentration of i
the ith nuclide.
The release rate, Q, was determined by dividing in Ci, for the i nuclide (t~ > Sd), during the th in the quarter.
the total activity released calendar quarter by the seconds 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:
E x 100%
MPCi X'f Limit ~
10,000 m /sec 3
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
- 3. Avg Concentration for Month (pCi/ml) 3.1 E-10 4.
Max Concentration Released (pCi/ml)
- 7. 8 E-09
- 5. Percent of Technical Specification Limit for Total Activit Released (X)
- 1. 3 E-09
- 1. 7 E-09 7.2 E-10 4.2 E-10 1.2 E-O&
7.0 E-09 6.4 E+00 8.9 E-10 9.1 E-10 1.7 E-10 1.2 E-10 3.3 E'-09 4.8 E-09
- 2. 7 E+00 1.0 E-09 2.0 E-10 3.9 E-09 H. Tr'itium
- 1. Total Release (Ci) 1.62 E+02 8.70 E+Ol 1.03 E+02 2
v Concentration Durin Releases nCi ml 1.2 E-06 8.1 E-07 2.0 E-06
- 3. Avg Concdntration for Month (pCi/ml) 5.3 E-07 4.4 E-07 4.8 E-07 7.66 E+Ol 1.4 E-06
~2.8 E-07 7.88 E+01 2.3 E-06 2.9 E-07 1.11 E+02
- 2. 0 E-06
- 3. 9 E-07 C. Didsolved Noble Gas
- 1. Total Release (mCi) 2.
Av Concentration Durin Releases (pCi/ml) 2.17 E+00 4.90 E+Ol 1.6 E-ll 4.7 E-10 3.91 E+Ol 4.66 E+00 1.22 E+01 7.5 E-10 8.&
E-11 3.6 E-10 1.86 8+02 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) 2.
Avg Concentration During Releases(u Ci/ml) (<1.3 E-19
(<1. 7 E-08
(<l. 6 E-19
(<2. 2 E-08) (<2.4 E-O&) (<1. 1 E-08)
(<4. 2 E-19) (<4. 5 E-19) (<3. 2 E-19)
(<l.0 E-OS
(<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)
- 2. Vol of Dilution Water During Rel (Liters)
- 3. Vol of Dilution Water for Month (Liters) 4.50 E+06
&.08 E+06 3.45 E+06 1.33 E+ll 1.05 E+ll 5.22 E+10 3.04 E+ll 1.94 E+ll 2.17 E+ll
'21 2
~ Et'
~
6 '4 Iml 2.10 E+06 1.35 E+06 3.43 E+06 5.30 E+10 3.43 E+10 5.53 E+10 2.76 E+11 2.69 E+ll 2.05 8+11
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 Co-58 mCi
(<2.7 6.25 E-.07)
E+00.
(<3.5.E-07) 4.15 E+Ol
(<4.8 E-07) 2.33 E+01
(<4. 1 E-07) 8.49 E+00
(<9.9 E-OS) 3.48 E+00
(<l. 1 E-07) 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 Cs-134 Cs-136 mCi E-07) mCi.
(<1.5 E-07) mCi i..4.61 E-Ol 6.54 6+00 5.36 E+00 4.9 E-.ol 2.09 E+00 6.61 E+00
(<3.5 E-08)
(<2.8 E-07) 1.79 E+00
(<2. 8 F;08)
(<2.1 E-07)
'.76 E+00
(<3.0 E-08) 8.06 E-01 1.97 E+00
(<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 Fe-59 I-131 mCi mCi 3.92
(<6. 3
- 1. 09 E-01 E-08)
E+00 6.01 E-,01 3.09 E+01
(<7. 5 E-08) 1.50 E+00
(<5. 8 E-08) 4.67 E-01
(<4. 9 E-08) 1.75 E-02
(<5. 5 E-08) 5.66 E+00 I-132 I-133 I-134 I-135 mCi mCi mCi 7.92 E+00 9.'05 E+00 7.29 E+00 9.10 E+00 7.64 E+00
(<4. 3 E-08)
(<3.6 E-'8)
(<2.8 E-08 6.64 E+OO La-140 Mn-54
~
mCi mCi.:
(<1. 8
- 3;95 E-08)
E-01
(<2.5 E-08) 1.29 E+00
(<l. 2 E-08) 1.40 E-Ol 5.75 E-02 3.49 E-02
'(<8. 3 E-09)
(<l. 1 F;08)
'8.51 E-Ol 2.35 E-ol Mo-99/Tc-99m Na-24 Nb-95 Ru-103 mCi.
mCi.
mCi mCi 1.07 E-01
(<1.2
(.<2.
5'-07)
E-08) 1.48 K+00 8.27 E-01 6.0 E-Ol 3.06 F.-ol
(<2.4 E-07) 3.92 E-01
(<4.5 E-OS)
(<2. 1 E-07)
(<3.3 E-08)
(<3.4 E-OS)
(<1.7 E-07)
(<3. 2 E-OS)
(<2. 6 E-OS)
(<1.6 E-07)
(<3.2 E-08)
(<2.8 E-08)
Sb-124 Sb-125 mCi mCi
(<3.1 2.96 E-08)
E-Ol 6.95 E-Ol
(<9.9 F.-08) 3.88 E+00 1.43 E+00 3.21 E-01 2.54 E-01 3.19 F;02 2.12 E-Ol 2.07 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 Sr-89 Unit mCi July
- l. 3 E+00
. August
- 1. 3 E-01 September 6.0 E-03'ctober 8.4 E-02 November 1.8 E-02 December
(<2.7 E-09)
Sr-90 Unidentified mCi mCi
(<6.7 E-09) 7.16 E+00.
2.71 E+00 9.11 E+00
(<3.0.E-09) '<2.9 E-09)
(<3.0 E-09)
- 7. 3 E-03 4.71 E+00
(<2.7 E-09) 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
~
~
i i Ag-ll0m Ba-140 mCi mCi 6,42 E-01
(<2.7 H-07) 5.20 E-01
(<3.5 E-07) 1.08 E+00.'<4.7 E-OS)
(<4. 8 E-07)
(<4. 1 E-07) 7.63 E-01
~
(<9.9 E-08) 1.51 E+00
(<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 Cr-51 Cs-134 Cs-137 Fe-59 I-131 I-133 La-140 Mn-54 Mo-99/Tc-99m mCi mCi mCi mCii:
mCi mCi.
mCi mCi 6.61 H+00
(<1.9 E-07) 4.61 E-01 8.81 E-01
(<6.3 E-OS) 7:94 E-02 7.84 E-02
(<1.8 E-08) 3.95 E-01 1.07 E-01 4.77 F+00 6.54 E+00 1.86 E+00 2.95 E+00 6.01 E-Ol 1.93 E+01 5.74 8+00
(<2.5 E-08) 1,27 E+00 8.27 E-Ol
- 6. 2 8+00 3.55 8+00 2.09 E+00,(<2.8 E-07) 1.12 E+00 1.80 E+00 1.79 E+00 2.80 E+00
(<7. 5 E-OS)
(<5. 8 E-08) 1.50 E+00 4.67 E-Ol 1.40 E-Ol 5.75 E-02
(<2.4 E-07)
(<2.1 E-07)
(<4. 3 E-08)
(<3. 6 E-OS)
(<l. 7 E-08)
(<8. 3 E-09)
.23 F+0
(<2. 1 E-07)
.1.44 E+00 2.42 E+00
(<4.9 E-08) 1.75 E-02
(<2.'8 E-08)
(<1. 1 E-08) 3.49 E-02
(<1. 7 E-07 4
.+
8.06 E-Ol 1.97 E+00 2.95 E+00
(<5. 5 E-08) 3.41 E+00
(<2. 8 E-OS) 8.51 E-Ol 2.35 E-ol
<1.6 E-07 Nb-95 RU-103 Sb-124 Sb-125 mCi mCi mCi mCi.
(<1:2 E-07)
(<2. 5 E-08)
(<3.1'E-08)
, 2.96 E-01 6.0 E-01 3.06 E-Ol 6.95 E-01
(<9.9 E-08) 3.92 E-01
(<4. 5 E-08) 3.88 H+00 1.43 E+00
(<3.3 E-08)
(<3.<i E-OII).
3.21 F.-01 2.54 E-Ol
(<3.2 E-08)
(<2. 6 E-OS) 3.19 E-02 2.12 E-Ol
(<3.2 E-08)
(<2. 8 H-0&~
2 07 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 HA't'tt ~
titinrlir.i r in n i~not.hn~nc.
1'nnvnr nnt ms ii~ian nntt ~'.9 t Air i t't ~ 4n itPj ltnl 1.67 E+Ol 1.17 E+Ol 2.12 E+Ol
1978 Table I Re'port of Radioactive Effluents:
Liquid - Secondary System Page 5
I Isotope Co-58' i
Co-60 Cs-134 Cs-136 Unit
'mCi mCi mCi mCi Jul 3.67 E+00 3.07 E+Ol Au ust 9.86 E+00 2.24 E+01 3.5 E+00 4.9 E-Ol Se tember 8.3.
E-01.'.97 E+Ol 5.49 E+00 October 1.13 E+00 2.03 E+01 November 1.21 E+Ol
- 3. 2 E-01 December 2.20 E+01 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 F-18 I-131 mCi mCi mCi 2.06 E+00 3.92 E-Ol 1.01 8+00 1.16 E+01 2.25 E+00 I-132 I-133 mCi 7.92 E+00 mCi.
8.97 E+00 1.9 E+00 6.64 E+00 I-134 I-135 mCi mCi 7.29 E+00 9.10 E+00 Hn-54 Na-24 Sr-&9 Sr-90 Unident'ified mCi 1.'48 E+00 mCi mCi
<2.9 E-09 7.16 E+00 mCi
(<2. 9 E-09) 2.48 E-02 3.34 E-02
<2.9 E-09 2.71 E+00
- 6. 0 E-03
<2.9 E-09 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 NA'I'F:
Wnmbr rn in norman(hnses rnnrr srnl mnximnm srnsitiirit I in>>Ci lml 3.05 E+Ol 1.95 F+01 3.48 8+01
1978 Table.1 Report of Radioactive Effluents:
Liquid Dissolved Gas Page 6
Total Jul Au ust Se tember October November December Kr-85 Xe-131m Xe-133 mCi mCi mCi
(<4. 7 E-06)
'(<6. 9 E-.07) 2.17 E+00 3.47 E+01
(<2. 1 E-06) 1.35 E+01 3.91 E+Ol'<9.
9 E-07)
(<5. 9'-08) 3.99 E+00 1.13 E+Ol
'1.81 E+02
(<6.3 E-06)
(<4.6 E-06)'<5. 9
. E-06)
(<7. 1 E-07)
(<6. 3 E-07)
(<9. 5 E-07)
Xe-133m Xe-135 mCi
(<1.3 E-07)
(<1.7 E-08)
(<3.7 E-07) 8.03 E-Ol
(<2.'1 E-.07)
(<2. 5 E-08)
(<1. 6 E-07) 6.72 E-01
(<1.5 E-07) 2.48 E+00 l
8.5 E-01 3.00 E+00 Waste Dis osal S stem Kr-85 Xe-131m Xe-133 mOi mCi mCi
(<4.7 E-06)
(<6;9 E-07) 2.17 E+00 3.47 E+01
(<2.1 E-06) 1.35 E+01 3.91 E+Ol
(<6.3 E-06
(<9. 9 E-07)
(<7. 1 E-07)
(<5.9 E-08) 3.99 E+00
<4.6 E-06
(<6.3 E-07) 1.13 E+01
~<5. 9
'H-0
(<9. 5 E-07) 1.80 E+02 Xe-135 mCi mCi
(<1.3 E-07)
(<1.7 E-08)
(<3.7 E-07) 8.03 E-01
(<2.1 E-07
(<2.5 E-08)
<1. 6 E-07 6.72 E-01 8i5 E-Ol 2.53 E+00 Secondary System Kr-85 Xe-131m XG-133 Xe-133m Xe-135 mCi mCi.
mCi mCi mCi 1.35 E+00
- 4. 7 E-01 t maximum sensitivit in Ci/ml HOTE:
Numbers in parentheses represen y
p
'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'.
Av
'Rel Rate for Period(liCi/Sec) 8.3 E+02 2.48 E+03 9.2 E+02 1.87 E+03 7.2 E+02 8.8 E+02 8.2
':E+02 2.38 E+03 2.13 E+03 2.23 E+03 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)
- 3. Gross Al ha Radioactivit Ci 1.5 E-04
~3. 1 E-09
- 6. 5 E-03
- 3. 7 E-08
- 3. 6 E-03
- 7. 3 E-08 1.0 E-04
<2.8 P.-12
- l. 0 P.-05
<2. 8 F.-12 7.4 E-05
<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
- 1. Fission
& Activation Gases
(%)
- 2. I-131 and Part.
(t> >8d)
(%)
uarter III 6.9 E+00 2.2 E-01 uarter IV 7.0 E+00
- 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 Ba-140 Ci Ci
(<4.7 E-14) 7.5 E-06
- 4. 8 E-05
(<4. 8 E-13).'<
- 7. g H-12)
(<5. 2 E-12)
(<3.3 E-14) 2.0 E-05
(<1.9 E-14)
~
(<5.0 E-14)
(<7. 0 E-14)
(<1. 3 E-13)
Ce-141 Co-57 Ci
(<3.7 E-14)
(<1.7 E-14) 2.6 E-05 3.2 H-05
(<2.5 E-13) 2.1 E-05
(<2. 1 F.-14)
(<1. 3 E-14)
(<1. 6 E-14)
(<2. 3 E-14)
(<9. 4 E-15)
(<l. 4 E-14)
Co-58 Co-60 Cr-51 Cs-134 Ci Ci 2.5 E-04
- 9. 2 E-05
(<2.4 E-13) 1.5 E-05
- 1. 3 E-02
- 1. 8 H-03
- l. 5 H-03 1.1 E-05 6.9 E-03
- 1. 1 E-03 6.0 E-04
- 4. 3 E-05
- 9. 2 E-05
- 3. 5 E-05
(<2. 1 E-13) 3.8 E-05 1.4 E-05 1.3 E-05
(<8.0 E-14)
(<2.1 E-14)
- 5. 5 E-05
- 2. 1 E-05
(<3.8 E-14) 2.4 '-05
(<4. 6 E-14)
- 5. 6 E-06 7.5 E-06
(<4.2 H-13)
(<3,0 E-13)
- 2. 1 H-05 1.2 E-.04 6.3 H-06 6,7 E-05 6.2 E-05 1.3 E-05
(<1.9 H-13)
(<1.3 E-13) 6.9 E-06 5.0 E-05
(<4. 6
'E-14) 1.5 E-05 1.2 E-05
(<2.0 E-14) 5.9 E-05
(<3. 0 E-14)
(<5. 9 E-14)
(<1.1 E-14)
'.2 E-05
(<l. 2 E-14)
(<4. 4 E-14)
, (<1. 1 E-14)
(<4. 2 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 Ru-103 Sb-'.124 Ci
(<3.0' 14)
(<3.7 E-14)
(<3.7 E-14) 2.6
= E-04
- 8. 3 E-05 1, 7 E-04
- 1. 3 E-04
(<4. 6 E-13)
- 6. 2 E-05
(<2. 5
. E-14)
(<2. 9 E-14)
(<2. 8 E-14)
(<1. 3 H-14)
(<2. 9 E-14)
(<1.1 L'-14)
(<2.9
- H-1
(<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 Zr-95 Ci Ci
- 1. 0 H-07
(<4.9 E-14)
- 4. 3 H-07
- 1. 1 E-04
- 6. 6 H-07 6.2 E 05
(<1.5 H-15)
(<4.0 E-14)
(<G. 5 E-16)
(<1. 2 E-15)
(<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 Fission 6 Activation Gases Table II Airborne Releases Gaseous pae3 Isotope Unit July August September October November December Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Ci Ci Ci Ci Ci 1.27 E+Ol
(<3. 8 E-05) 3.58 E-01
(<2.6'-O?)
1.38 E-01 3.61 E+00 2.22 E+03 4.41 8+00 1.94 E+01 3.34 E-02 '<3.5 E-05)
- 7. 3 E-06
(<1.1 E-O?)
1.32'-02 2.47 E+03
(<4.8 E-06) 1.85 E+03 (k2.5 E-06)
(<2.4 E-07)
(<5.2 E-06)
(<2.5 E-07) 8.19 E+00.
1.05 E+01
(<3. 7-E-05)
(<3. 4 E-05) 2.17 E-01 2.77 E-01
(<2.9 E-07)
(<3.1 E-07) 1.44 E-01 2.34 E-01 2.36 E+03 2.11 E+03
(<6. 2 E-06)
(<7. 2 E-06) 2.12 E+01 6.64 E-02 6.85 E-Ol 6.17 E-01 5.81 E-01
- 1. 1 E-02 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 Xe-135m Ci Ci 7.38 E+00 9.81 E-02 1.08 E+00 2.37 E-01
(<1. 3 E-06)
(<1. 6 E-07) 5.09 E+00
(<1.8 '-07) 4.78 E+00
(<1.7 E-07) 1.26 E+Ol
(<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
. I-133 Unit Ci Jul
- 4. 1 E-03 5.3 E-03 Au ust 1.0 E-02 1.3 E-03 Se tember 1.6 E-03 7.8 E-03 October 3.4 E-03
- 6. 1 E-03 November 3.7 E-04
- 6. 8 E-04 e
em e
l.8 E-02 1.0 E-02
. I-135
- Hr-82
'otal Ci Ci
- 1. 2 E-03 3.5 E-04 1.1 E-02
(< 2. 0 E-13) 1.13 E-02 6.7 E-03 1.61 E-02 1.05 E-02 1.19 E-03 8.8 E-04
(<7.7 E-14) 1.6 E-04 1.4 E-04
~
- 7. 2 E-03 4.6
- 3. 6 E-02 NOTE:
Aumbers in parentheses represent maximum sensitivity in >iC1/cc.
ATTACHMENT 2 COACTIVE HASTE REPORT.
IJuly 1, 1978 to December 31, 1978 Date of Shipment 7-12-78 7-18-78 7-20-78
'-22-78 7-28-78 7-28-78 8-OS-78
'-25-78 8-31-78 9-01-78'-07-78 9-12-78 9-13-78 9-13-7S, 9-18<<78 9-22-78 9-26-78 9<<28-78 9-28-78 9-29-78 10-03-78 10-03-78 10-09-78 10-10-78 10-12-78 10-16-78 10-16-78 10-18-78 10>>'19-78 10-20-78 10-23-78 10-25-78 10-25-78 10-27-78 10-27-78 11-01-78 11-03-78 11-03-78 11-09-78, 11-13-78 11-28-78 11-29 12-02-78 12-04-78 12-07-78 12-11-78 12-13-78 Cmies 3.000 0.007
- 0. 792 108.000 53.919'.001 0.002 425.000 547.000 0.820 2.260 3.000 3.646 5.352 0.420 0.325 1.076 3.200 0.027
. 1.892 0.801 4.
285'.965 2.983 2.075 0.550 0.540 1.080
'0.504 0.432 0.658 6.466 1.260 1.277 0'. 360 0.540 0.504 1.462 0.511 0.038 0.459 0.694 110.000 1.152 0.612 0.318 0.058 CQ Ft 60 1 5750 100 100 100 1, 700 1,700 100 laO
'1,095 110 100 195 100 610 850 1,132 90 1,300 1,700 1,262 195 100 1, 700 110 100 150 150 300 150 195 110 150 240
'50 150 300 195 195 195',113-1,000 100 100 300 100 195 Buried in Barnve11, SC I~
I~
47 Shipments On site as of January 1,301.323 1, 1979:
Ci 21,997 Cu.. Ft.
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.
2.
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.
The Monitorin Program Period Covered:
This current report covers the period from'uly 1,
1978 to December 31, 1978.
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 TA8LE 1 ENVIRONHENTAL RAOIOLOGlCAL HONITORlNG PROGRAH SUtgtARY NAIIE OF FACILITlf amrsr Foltttsraur Dstr 2 5 DOCKET II0.55-255
-252'OCATION OF FAClLITY Dade Count Florida 18 Hedium or Patt+ay Sampled Analysis Unit for Sites Number of All Indicator Locations Range Samples Analyses Hean Location with Ni hest Hean Control Location~a ~
Sample Location Oistance and Oirection Elean Range Hean Range Number of Nonroutine Reported Heasurements l.
Air Filters 1.1 Air pci/aP
. att Particulates l.l.a Air Zodines pCi/h ialt tell
~
Ilr 1.3 Preoi ita-t on.
a$ 1Z 208 132 23, r
208
.02 :-
0.004-0.047 4-7'Ll-72E Boy Soout CMTp Bone V-64 a Natcjjja Substaticn, ttlami, Etg, 30 miles
.022 5.8
.004-
.047 ND(b) 5-7
.020
.007"
.041 5.8 5-7 '
None 24 24 24 2.7 (1'
200 tG-22 T-52E PlorMa City Suustaticaj, WestF 8 mQe
'ti-52E Florida City SuustationD West,8mQes Nore 4.8 2.7
~
I 5
ND-8 ttD P
l.t
~:,"
< 200 j."J;"i
( )'I ND-22 1,3 ND-4 a
~
5
4 M
19 fledium or Pathi~ay Samoled Unit Analysis for Sites Samples Analyses Hean Range All indicator "Humber of Locations Sample Location Distance and Direction Ilean Range
'Location with Hi hest Hean
~ Hean Range Control Location~
~
Huaher of Honroutine Reported Heasureaents 2.
Water 2.1 Estusl'Lna Sr-89 Sr-90 10 10 10 20 20 20 19 19
< 200-9-51; Ilaaastead Bayfront 500 Parf, NN4, 2 mQes C
350.
< 200-
'00; 2.1.2 Cool Cana 14 14 298 2700-8800 T-84~ Discharge Canal
~ soReide.of Sedge "..
412 2870-
- 8800, Sr-89
r-90 2
HD-2 T-97:
loch-Msetta, cn-Rte l
< l.'D-2 2,1.3 Fresh Hater>
Ca GQ.DS GS-UPS 12 12 12 12.
12 12 135 287.
t&-460 T-75<. Florida City
~taW
.5 miles
< 200-
~
~
T-75<
Flnrida City'Cana H00 RR, 1,5 miles 268 573 160 460 250-
=
1100
0 20 I
fledium or Pathway Sampled
~ =
Unit Analysis for Number of Sites Samples Analyses Pl 1 Indicator Locations Hean
- Range, Sample Location Distance and Direction ilean Range
'ocation with Hi hest Hean Control Location~a~
Hean Range Number of Nonroutine Reported HeasureLents 2.2 Potabla Waxer mila loi8 6-15
~ T-57'olan's Faxms, QW, K5 ad.les 14 2.3 Gruml Hater Wells I
~
I08r 6
12 12 12
< 200 979
< 200-
'&92) Hall 024K~. SSH~
inQes
'I 2020.
1840-2200' I
~j
21 fledlum or pathway Sampled
'Uni (
Analysis for Humber of Sites Samples Analyses All indicator Locations Hean Sample Location Distance and 'Oirection llean Range Location with Hi hest Hean Hean Range Control Location~
~
~
'umber of Honroutine Reported Heasurements 3.0
~
Bottrm Sea\\mnts 3.1 Cool c% ICe c sos
$ cCo c OCo
".Sr
$ 0g c,c ICs "Sr
$ 4g 7
4 4
2 4
2 7'33
- 220, 93 925 70 600 440 230 3400.
140 T 84i Dhu8carge.Canal,
~ttside of Bridge T-84c Discharge Canal,
~ttside of Bridge T-84c Disdcarge Canal, 8~su ide of Bridge T-84c Discharge Canal<
8~su ide of Bridge Hone 84c Discharge Canal, Southside of Bridge 500 440 93 70 400-.
00
, 230 3400
'140
I
~\\
I 2
)ledium or. Pathway Sampled Unit Analysis for Sites Number of Samples Analyses Hean Range All Indicator Locations Control Locationta~
Sample Location Nstance and Oirection iiean Range Hean Range Location 44ith Hi hest Hean Numher of Honroutine Reported Heasurements 4.0 Biota 4.1 Ccustacea
/kg 'e 6
4.2.a Fish UIIRNlm 44sr
~
'444'kg
"'au 5
I 6
.6:
6
~
180 230 ND +00 ND-800 T-94> Pa~n Key, S93, Fables T-69> Elliott Key, South eiB, ESE, 7 miles (o) 900 N),
800 lllCe 400 200-500 T-81! Cml Sound, Hat
~ DI9chaÃgo Canal (d) 400
I 1
~
I
~
l, I
I
'I l
I
.'23 alodium or. Patlway Sampled Analysis Unit for Sites Humber of Samples Analyses
. Range Bean All.Indicator Locations Control Location~a~
Sample Location Distance and Direction Range llean Range Bean ocation With Hi hest Hean Humber of Honroutine Reported Heasurements 4.2.b Pish Herbal are
$ 08r 302 16 '-59a Elliott KCb Ei 8 mmles (e) 16
.3.s Hanstee Grass
.3.b ~Sees l)ICe pCi/kg Ce
~'Sr a 08r a 1lCe a 0agn
.6 6
6 4
1783
. 20 4500 00 tQ-120 59a Elliott Key, E>
8 T 86a least Arsenid~.
Key, Card Sounds ~i 3
miles'-93a Pelican Bank East X.S miles 500 120
~ o
~o
~
~
0 fhdium or Pathway Samoled Unit Analysis for Sites Humber of All Indicator Locations Range Samples Analyses iIean Sample Location Gistance and Direction IIean Range Location'with Hi hest Haan Control Location liean Range Hunker of Honroutine Reported Heasurements 5.0 Terrestrial B~oth 5.2.1 Small Bniiioxo c sos 210 25 190-230 18-32 T-58< On Site Entrance T-58< On Site Entrance (f) 210
~ 25
'2.3 Maxirove Iaavea
~nSr s OSr 1
7'
~ 7
- 6.7 21 teens 51c Haaestead Bayfmnt Par N%4, 2 miles 21
.3 Soil 1le lb%Os 4~Sr
$ 0Sr 7
7 7
. '94 243 90-950 700 56'rinceton Sub-
- statitn, NQ9, 8 miles 57'olan's Parms,R4f, miles 950 700
25 Flediun or Pathway Sampled Unit Analysis for I
Humber of Sites Samples Analyses All Indicator Locations Range Location with Hi hest Flean Sample Location Distance and Direction llean Control Location~-
Range Hean Range
~
'umberof Honroutine Reported Heasurement Notes i'>T-64'ae s
"'m-Nno t
">ma.>et
<'la
, Hiemal,
, 30 les