L-88-101, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1987
| ML17342B204 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/31/1987 |
| From: | Conway W FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| L-88-101, NUDOCS 8803070206 | |
| Download: ML17342B204 (40) | |
Text
REGULA Y INFORMATION DISTRIBUTIO
'YSTEM (RIDS)
ACCESSION NBR: 8803070206 DOC. DATE: 88/02/29 NOTARIZED:
NO DOCKET 0 FACIL: 50-250 Turkey Point Plant'nit 3i Florida Poeer and Light C
'05000250 50-251 Turkey Point Plant~
Unit 4i Florida Power and Light C
05000251 AUTH. NAME AUTHOR AFFILIATION CONWAYe W. F.
Florida Power 8c Light Co.
RECIP. NAME REC IP IENT AFFILIATION
SUBJECT:
"Semiannual Radioactive Effluent Release Rept Jul-Dec 1987. "
W 80229 l DISTRIBUTION CODE:
IE48D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: 50. 36a(a) (2) Semiannual Effluent Release Reports NOTES:
REC IP IENT ID CODE/NAME PD2-2 LA EDISON' INTERNAL: AEOD/DOA ARM TECH ADV NRR/DREP/RPB10A I,
01 RG DRM/EPRPB EXTERNAL:
BNL TICHLERi J03 NRC PDR COPIES LTTR ENCL 1
0 1
1 1
1 4
4 1
1 1
1 1
1 1
REC IP IENT ID CODE/NAME PD2-2 PD AEOD/DSP/TPAB NRR/DEST/PSBSDi NRR/PMAS/ ILRB12 RGN2 FILE 02 LPDR COPIES LTTR ENCL 5
1 1
1 1
1 1
1 1
1 1
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 22 ENCL 21
, I\\
TURKEY POINT PLANT UNITS 3 AND4 SEMIANNUALRADIOACTIVEEFFLU ENT RELEASE REPORT JULY 1987 THROUGH DECEMBER 1987 SUBMITTED BY NUCLEAR CH EMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDAPOWER AND LIGHTCOMPANY 88ps0702pb 6500p250 Ooc~ p p
R
FLORIDAPOWER AND LIGHTCOMPANY TURKEYPOINT UNITS 3 AN~
EFFLI%ATANDWASTE DISPOSAL SEMIA8%UALREPORT SUPPLEMENTAL INFORMATION JULY 1987 THROUGH DECEMBER 1987 1.0 Re ulator Limits d Effl a)
The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall not exceed 2 x 10-4 pCi/ml.
b)
The dose or dose commitment per reactor to a member of the public from any radioactive materials in liquid effluent released to unrestricted areas shall be limited, during any calendar quarter, to S1.5 mrem to the total body and to S5 mrem to any organ, and, during any calendar year, to ~3 mrem to the total body and < 10 mrem to any organ.
1.2 Gaseous Effluents a)
The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin due to noble gases and less than or equal to 1500 mrern/yr to any organ due to l-131, l-133, tritium and for all radioactive materials in particulate form with half lives greater than 8 days.
b)
The air dose per reactor to areas at and beyond the site boundary due to noble gases released in gaseous effluents shall be limited, during any calendar quarter, to < 5 mrad for gamma radiation and < 10 mrad for beta radiation and, during any calendar year, to <10 mrad for gamma radiation and < 20 mrad for beta radiation.
c)
The dose per reactor to a member of the public, due to l-131, l-133, tritium and to particulates with half-lives greater than 8 days in airborne effluents released to areas at and beyond the site boundary shall not exceed 7.5 mrem to any organ during any calendar quarter and shall not exceed 15 mrem to any organ during any calendar year.
RNSlmd*C1:I
~
C
07/87 - 12/87 2.0 Maximum Permissible Concentrations The maximum permissible concentrations for liquid and airborne releases are described in Sections 1.1-a and 1.2-a ofthis report.
3.3 The average energy of fission and activation gases in gaseous effluents is not applicable.
4.0 Measurements and A roximations ofTotal Radioactivit 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 Regulatory Guide 1.21 was met or exceeded.
4.1 ~Ud EHI Aliquots of representative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 2o 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 oftritium and dissolved gases.
The above procedure was followed for all releases from the waste disposal system and for secondary system batch releases.
Frequent periodic sampling and analysis were used to conservatively determine if any radioactivity was being released via the steam generator blowdown system.
Monthly and quarterly composite samples for the waste disposal system were prepared to give proportional weight to each liquid release made during the designated period of accumulation.
The monthly composite was analyzed for tritium and gross alpha activity.
Tritium was determined by use of liquid scintillation techniques and gross alpha radioactivity was determined by use of a 2a gas flow proportional counter. The quarterly composite was analyzed for Sr-89/90 and Fe-55 by chemical separation.
All radioactivity concentrations determined from analysis of a pre-release 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.
RNS/md*C1: 1
~
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ll
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07/87 - 12/87 At least one representative batch of liquid ef'fluent 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 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 were weighted in an appropriate manner.
4.2 Gaseous Effluents Airborne releases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and sporadic releases incidental to operation of the plant.
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 and gross alpha analysis, c)
Absorption of halogen radionuclides on a charcoal filter and subsequent gamma-spectrum analysis, and d)
Analysis of water vapor in a gas sample 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 as curies of Xe-133 by use of the plant vent process monitor recorder chart and the current calibration curve for the monitor.
Portions of the gas waste treatment system are shared by both units and generally all gas releases from the shared system are allocated on a 50/50 basis to each unit. However, during March through November of 1987, most short lived gaseous effluents were allocated to-Unit 4. This is due to Unit 3 being shut down during these months, and thus not contributing short lived isotopes.
l(NS/md*CI:1 07/87 - 12/87 4.3 Estimate of Errors a)
Sampling Error The error associated with volume measurement devices, flow measuring devices, etc., based on calibration data and design tolerances has been conservatively estimated to be collectively less than + 10%.
b)
Analytical Error Our quarterly Q.C. cross-check program involves counting unknown samples provided by an independent external lab.
The errors associated with our analysis of these unknown samples, and reported to us by the independent lab, were used as the basis for deriving the following analytical error terms.
Nuclide T e
Liquid Gaseous
'~E
+5%
+6%
Maximum Error
+7%
+8%
RNS/md*C1: I
07/87 - 12/87 5.0 BATCH RELEASES 5.1
~Li uid a)
Number of batch releases b)
Total time period of batch releases c)
Maximum time period for a batch releases d)
Average time period for a batch release e)
Minimum time period for a batch release f)
Average stream flowduring period of release of effluent into a flowingstream Unit 3 1.90 E+ 02 1.79 E + 04 2.27 E + 02 9.40 E+ 01 3 0 E+01 1.38 E+ 06 Unit 4 1.90 E+ 02 1.79 E + 04 Minutes 2.27 E+ 02 Minutes 9.40 E + 01 Minutes 3.0 E + 01 Minutes 1.38 E+ 06 GPM 5.2 Gaseous a)
Number of batch releases b)
Total time period of batch releases c)
Maximum time period for a batch release d)
Average time period for a batch release e)
Minimum time period for a batch release 1.80 E+ 01 1.86 E+ 03 4.00 E+ 01 1.03 E+ 02 3 00 E+01 1.70 E+ 01 1.14 E + 03 Minutes 4.00 E + 01 Minutes 6.71 E + 01 Minutes 3.00 E + 01 Minutes 6.0 UNPLANNEDRELEASES 6.1
~Li uid a)
Number of releases b)
Total activity releases 6.2 Gaseous 438 E 05 0.00 E+ 00 0.00 E + 00 Curies a)
Number of releases b)
Total activity releases
'6.3 See attachments (¹1) for:
0.00 E+ 00 0 00 E+00 0.00 E + 00 0.00 E + 00 Curies a)
Adescription of the event and equipment involved.
b)
Cause(s) for the unplanned release.
RNSIind*(lI:1 07/87 - 12/87 7.0 The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundry assumes a visitor was on-site at the "Red Barn" recreational area for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> a day, 2 days each week of the year, receiving exposure from both units at Turkey Point. The "Red Barn" is located approximately 0.39 miles NNE of the plant site.
These dose calculations were made using historical meteorological data..
VISITOR DOSE SUMMATION JANUARY1987 THROUGH DECEMBER 1987 UNITS 3 AND4 Age Group: Adult Inhalation Location: Red Barn Dose mRem Bone Liver Thyroid Kidney Lung Gl-LLI Total Body 3.17 2.17 2.78 2.17 2.17 2.17 2.17 NOBLE GAS EXPOSURE E -06 E 03 E -03 E -03 E 03 E 03 E 03 Gamma AirDose Beta AirDose 3.43 E -03 mRads 5.10 E -03 mRads 8.0 Offsite Dose Calculation Manual Revisions There were no ODCM revisions during this reporting period.
9.0 Solid Waste and lrratiated Fuel Shi ments No irradiated fuel shipments were made from the site.
Common solid waste from Turkey Point Units 3 and 4 were shipped jointly. A summation of these shipments is given in Table 5 of this report.
10.0 Process Control Pro ram Revisions There were no changes to the process control program during this reporting period.
RNS/md*C1: 1 LORIDAPOWER AND LIGHTCOM NY TURKEYPOINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT3 TABLE 1 LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products
- 1. Total Release (not including tritium, gases, al ha Ci 8 85 E-02 4.88 E 02
- 2. Average diluted concentration during period pCi/ml 7.50 E 10 7.17 E 10 B. Tritium
- 1. Total Release Ci 1.98 E+ 01 6.40 E + 01
- 2. Average diluted concentration during period pCi/ml 1.68 E 07 9.40 E 07 C. Dissolved and Entrained Gases
- 1. Total Release
- 2. Average diluted concentration during period Ci pCi/ml 6.90 E 04 3.91 E + 00 585 E 12 574 E 08 D. Gross Alpha Radioactivity
- 1. Total Release Ci (4.81 E -08'7.20 E -09*
E. Volume of Waste Released (priorto dilution)
Liters 2.87 E+06 1.78 E+ 06 F. Volume of DilutionWater Used During Period Liters 1.18 E+11 6.81 E+10
- MDAValue in pCi/ml Approved by Date l4NS/md*Cl:1
< ORIDA POWER AND LIGHTCOMPLY TURKEYPOINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT3 TABLE 2 LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES Nuclides Released Units Continuous Mode Batch Mode Ag-110m Ce-141 Co-57 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-59 I-131 La-140 Mn-54 Mo-99/Tc-99m Na-24 Nb-95 Ru-103 Sb-124 Sb-125 Zn-65 Zr-95 Zr-97 Sr-89 Sr-90 Fe-55 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 3 Quarter 4 Quarter 3 3.18 E-03 2.00 E-06 1.95 E-05 2.35 E-02 3.09 E-02 2.20 E-03 3.05 E-03 9.55 E-03 2.59 E-04 2.23 E-03 1.18 E-03 6.00 E-06 2.15 E-04 5.00 E-04 5.40 E-05 2.04 E-04 7.25 E-06 1.10 E-02 Quarter 4 4.25 E-03 4.00 E-05 8.25 E-03 1.94 E-02 7.10 E-04 5.20 E-04 2.01 E-03 6.85 E-06 3.52 E-05 7.50 E-06 1.64 E-03 1.20 E-05 3.61 E-04 5.90 E-05 8.35 E-04 3.33 E-03 3.68 E-06 1.34 E-04 7.55 E-03 Unidentified Total for Period Above Ci Ci 8.85 E-02 4.88 E-02 Approved by Date
& ltNS/md*C1:I 0
I I
F< ORIDA POWER AND LIGHTCOMP Y
TURKEYPOINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT3 TABLE2 (Continued)
LIQUIDEFFLUENTS Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Xe-133
'e-133m Xe-135 Units Ci Ci Ci Quarter 3 Quarter 4 Quarter 3 6.90 E-04 Quarter 4 3.91 E+ 00 1.04 E-04 1.09 E-05 Total for Period Above Ci 6.90 E-04 3.91 E+ 00 LIQUIDEFFLUENTS -DOSE SUMMATION JANUARY1987 THROUGH DECEMBER 1987 UNIT3 Age Group: Teenager Location: Cooling Canal Shoreline De osition Total Body Dose mRern 1.57 E-02
% of Annual Limit 5.24 E-01 Approved by Date RNS/md*ol:I F] ORIDA POWER AND LIGHTCOMPA Y
TURKEYPOINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT3 TABLE3 GAS EFFLUENTS - SUMMATIONOF ALLRELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products
- 1. Total Release
- 2. Average Release Rate for Period Ci pCi/sec 1.19 E + 02 1.50 E + 01 B. Iodines
- 1. Total Iodine-131
- 2. Average Release Rate for Period Ci pCi/sec 2.47 E 03 3.11 E -04 C. Particulates 1.
Particulates T-1/2)8 Days
- 2. Average Release Rate for Period 3.
Gross Alpha Radioactvity Ci pCi/sec Ci 2.10 E 05 2.64 E 06 5.89 E 08 D. Tritium
- 1. Total Release
- 2. Average Release Rate for Period Ci pCi/sec 3.45 E+ 01 2.83 E+ 02 4.49 E+ 00 3.56 E+ 01 Approved by Date RNS/md+Cl:1 0
t
~
~
ORIDA POWER AND LIGHTCOMPANY TURKEYPOINT PLANT SEMIANNUALREPORT
)ULY1987 THROUGH DECEMBER 1987 UNIT3 TABLE4 GASEOUS EFFLUENTS Nuclides Released 1 ~ Fission Gases Units Continuous Mode Quarter 3 Quarter 4 Batch Mode Quarter 3 Quarter 4 Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Unidentified Total for Period Above Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 5 30 E 02 5 20 E 03 1.34 E 03 865 E 02 7.63 E + 01 7.40 E -02 1.08 E 01 66 E+01 1.09 E 02 5.10 E 01 1.96 E -02 5.24 E 01 4.08 E + 01 2.95 E 01 4.48 E 01 4.26 E + 01
F ORIDA POWER AND LIGHTCOMP45Y TURKEYPOINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT3 TABLE4(Continued)
GASEOUS EFFLUENTS Nuclides Released
- 3. Particulates Units Continuous Mode Quarter 3 Quarter 4 Co-60 Cs-137 Cs-134 Sr-89 Sr-90 Fe-55 I-131 Unidentified Total for Period Above Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 625 E 06 1.21 E 05 1.97 E 06 650 E 07 2.10 E 05 Approved by Date RNS/nid*C1: I FLORIDAPOWER AND LIGHTCOMPANY TURKEYPOINT PLANT S E MIANNUALR E PORT J~AHy 1987 THROUGH DECEMBER 1987 UNIT 3 TABLE 5 DOSE DUE TO IODINE, H-3, AND PARTICULATES Pathway Inhalation-Adult Cow Milk-Infant Fruit 8 Veg - Adult Ground Plane Bone Liver Thyroid Kidney Lung GI-LLI Total Body 1.96 E 6 1.39 E 3 1.85 E 3 1.39 E 3 1.39 E 3 1.39 E 3 1.07 E 3 4.42 E 3 1.83 E 1 1.53 E 3 3.16 E 3 3.09 E 3 7.86 E 5 3.83 E 3 1.05 E 2 3.78 E 3 3.72 E 3 3.72 E 3 1.39 E 3 345 E-3 3.80 E
7.70 E-5 7.70 E 5 7.70 E-5 7.70 E 5 7.70 E 5 7.70 E-5 8.62 E-5 7.70 E-5 Unit Totals (mRem) 1.23 E -3 9.72 E 3 1.95 E 1 6.78 E -3 8.35 E -3 8.28 E -3 8.62 E -5 8.72 E -3
% Annual Limit 8.23 E -3 648 E -2 1.30 E +0 4.52 E -2 5.56 E -2 5.52 E -2 5.75 E -4 5.81 E -2 DOSE - NOBLE GASES Beta AirDose 2.03 -2 mRad Gamma AirDose 1.87 2 mRad
% of Annual Limit 1,87 -1 %/Yr
% of Annual Limit 1.02-1 %/Yr Approved by Date
. -HD -S
RIDAPOWER AND LIGHTCOMP TURKEYPOINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT4 TABLE 1 LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES A. Fission and Activation Products Units Quarter 3 Quarter 4
- 1. Total Release (not including tritium, gases, al ha Ci 8.85 E 02 4.88 E 02
- 2. Average diluted concentration during period pCi/ml 7.50 E 10 7.17 E 10 B. Tritium
- 1. Total Release
- 2. Average diluted concentration during period Ci pCi/ml 1.98 E+ 01 1.68 E 07 6.40 E + 01 9.40 E -07 C. Dissolved and Entrained Gases
- 1. Total Release Ci 6.90 E 04 3.91 E + 00
- 2. Average diluted concentration during period pCi/ml 5.85 E 12 5.74 E 08 D. Gross Alpha Radioactivity
- 1. Total Release Ci (4.81 E 08* (7.20 E 09'.
Volume of Waste Released (prior to dilution)
Liters 2.87 E+06 1.78 E+06 F. Volume of DilutionWater Used During Period Liters 1.18 E+11 6.81 E+10
'MDAValue in pCi/ml Approved by Date RNS/md*C1:1 I
F ORIDA POWER AND LIGHTCOMP Y
TURKEYPOINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT4 TABLE 2 LIQUIDEFFLUENTS Nuclides Released Units Quarter 3 Quarter 4 Continuous Mode Quarter 3 Quarter 4 Batch Mode Ag-110m Ce-141 Co-57 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-59 1-131 La-140 Mn-54 Mo-99/Tc-99m Na-24 Nb-95 Ru-103 Sb-124 Sb-125 Zn-65 Zr-95 Zr-97 Sr-89 Sr-90 Fe-55 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 3.18 E-03 2.00 E-06 1.95 E-05 2.35 E-02 3.09 E-02 2.20 E-03 3.05 E-03 9.55 E-03 2.59 E-04 2.23 E-03 1.18 E-03 6.00 E-06 2.15 E-04 5.00 E-04 5.40 E-05 2.04 E-04 7 25 E-06 1 ~ 10 E-02 4.25 E-03 4.00 E-05 8.25 E-03 1.94 E-02 7.10 E-04 5.20 E-04 2.01 E-03 6.85 E-06 3.52 E-05 7.50 E-06 1.64 E-03 1.20 E-05 3.61 E-04 5.90 E-05 8.35 E-04 3.33 E-03 3.68 E-06 1.34 E-04 7.55 E-03 Unidentified Total for Period Above Ci Ci 8.85 E-02 4.88 E-02 Approved by Oate B-gZ -88 RNS/nul*C1: l
~
~
FLORIDA POWER AND LIGHTCOMPLY TURKEYPOINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT4 TABLE2 (Continued)
LIQUIDEFFLUENTS Liquid Dissolved Gas Nuclides Released Units Quarter 3 Quarter 4 Continuous Mode Quarter 3 Quarter 4 Batch Mode Xe-133 Xe-133m Xe-135 Ci Ci Ci 6.90 E 04 3.91 E + 00 1.04 E -04 1.09 E -05 Total for Period Above Ci 6.90 E-04 3.91 E + 00 LIQUIDEFFLUENTS -DOSE SUMMATION JANUARY1987 THROUGH DECEMBER 1987 UNIT4 Age Group: Teenager Location: Cooling Canal Shoreline De osition Total Body
.Dose mRem 1.57 E-02
% of Annual Limit 5.24 E-01 Approved by Date RNSlind*(:l:I FJRDRIDA POWER AND LIGHTCOMPANY TURKEYPOINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT4TABLE3 GAS EFFLUENTS - SUMMATIONOF ALLRELEASES Units Quarter 3 Quarter 4 A. Fission and Activation Products
- 1. Total Release
- 2. Average Release Rate for Period Ci 7.69 E+ 01 1.19 E + 02 pCi/sec 1.00 E+01 1.50 E+01 B. Iodines
- 1. Total Iodine-131 2.'verage Release Rate for Period Ci 1,34 E -03 pCi/sec 1.74 E -04 2.47 E 03 3.11 E 04 C. Particulates
- 1. Particulates T-1/2)8 Days
- 2. Average Release Rate for Period Ci 6.30 E 06 pCi/sec 8.19 E -07 2.10 E 05 2.64 E 06 3.
Gross Alpha Radioactvity Ci 1.54 E 07 5.89 E 08 D. Tritium
- 1. Total Release
- 2. Average Release Rate for Period Ci pCi/sec 3.45 E+ 01 2.83 E+ 02 4.49 E+ 00 3.56 E+01 Approved by Date RNS/md*C1: 1 F
RIDA POWER AND LIGHTCOMPP Y
TURKEYPOINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT4 TABLE4 GASEOUS EFFLUENTS Nuclides Released 1 ~ Fission Gases Units Continuous Mode Quarter 3 Quarter 4 Batch Mode Quarter 3 Quarter 4 Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Unidentified Total for Period Above Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 2.80 E 01 3.77 E 02 3.18 E -03 2.33 E -02 3 82 E-01 6.10 E+01
'.36 E 01 6.51 E -01 6.28 E+ 01 530 E 02 615 E 02 9.70 E 01 5.20 E -03 3.84 E -04 1.34 E 03 8 65 E 02 7 60 E 02 7 63 E+01 1 26 E+01 7AO E 02 1 39 E 01 1.08 E 01 2.51 E 01 7.66 E + 01
.1.41 E + 01 1.09 E 02 5.10 E 01 1.96 E -02 5.24 E 01 4.08 E+ 01 2.95 E 01 4A8 E 01 4 26 E+01
- 2. Iodine Br-82 I-131 I-133 I-135 Total for Period Above Ci Ci Ci Ci Ci 1.13 E 02 1.34 E 03 3.11 E -03 3.54 E-03 1.93 E 02 2.47 E 03 1.28 E -03 375 E 03 Approved by Date 8NS/md*ol:I FfgQRIDAPOWER AND LIGHTCOMPLY TURKEYPOINT PLANT SEMIANNUALREPORT JULY 1987 THROUGH DECEMBER 1987 UNIT4 TABLE4 (Continued)
GASEOUS EFFLUENTS Nuclides Released
- 3. Particulates Units Continuous Mode Quarter 3 Quarter 4 Ce-144 Co-58 Co-60 Cs-134 Cs-137 Mo-99 Sr-89 Sr-90 Fe-55 I-131 Unidentified Total for Period Above Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 8.84 E 07 6.14 E 07 1.76 E 07 1.77 E -06 654 E 09 2.57 E -06 2.80 E 07 6.30 E 06 6.25 E 06 1.97 E 06 1.21 E 05 6.50 E -07 2.10 E 05 Approved by Date cQ-RNS/md*o1: I 0
FLORIDA POWER AND LIGHTCOMPANY TURKEYPOINT PLANT SEMIANNUALREPORT amtnRY 1987 THROUGH DECEMBER 1987 UNIT4 TABLE 5 DOSE DUE TO IODINE, H-3, AND PARTICULATES Pathway Bone Liver Thyroid Kidney Lung GI-LLI Skin Total Body Cow Milk-Infant Fruit 8 Veg - Fresh 1.13 E 3 4.49 E -3 2.04 E 1 1.54 E -3 3.15 E -3 3.09 E 3 855 E 5 382 E 3 114 E 2 376 E 3 370 E 3 370 E 3 3.48 E -3 378 E-3 Ground Plane 1.06 E -4 1.06 E -4 1.06 E 2 1.06 E -4 1.06 E -4 1.06 E -4 1.24 E -4 1.06 E -4 Inhalation-Adult 2.30 E 6 1.38 E -3 1.93 E -3 1.38 E 3 1.38 E 3 1.38 E 3 1.38 E -3 Unit Totals (mRem) 132 E 3 980 E 3 217 E 1 679 E 3 834 E 3 828 E 3 124 E 4 875 E 3
% Annual Limit 8.80 E 3 6.53 E 2 1.45 E + 0 4.53 E 2 5.56 E 2 5.52 E 2 8.27 E - 4 5.83 E 2 DOSE - NOBLE GASES Gamma AirDose Beta AirDose 5.29-3 mRad 1.54-2 mRad
% of Annual Limit
% of Annual Limit 5.29 - 2 %/Yr 7.69 2 %/Yr Approved by Date ATTACHMENT1 UNPLANNEDRELEASES A)
Description of the event and equipment involved. On November 12, 1987 a leak was detected in the Unit 3B Component Cooling,Water Heat Exchanger.
This allowed an estimated 8100 gallons of component cooling water contaminated to a level of 1.428 E 6 pCi/ml, to be released to the cooling canal.
B)
Causes forthe unplanned release were:
1)
Contamination of the component cooling water system
-with Cs-137 and Cs-134.
2)
Tube failure in the heat exchanger.
FZDRIDA POWER 6 IZGHT OQMP KUEKEY EOINT EKANT SEMIANNUALREPORT JULY 1987 THFKU2i DZCEK31& 1987 UNITS 3 AND 4 TABIE 5A SOLZD WASTE AND IEKADIATEDFUEL SHIBKNTS A.
SOIZD MME SHIPPED OFFSZXK FOR H3RIAL OR DISKSAL l.
TYPE OF WASTE UNIT 6 MNHK PERIOD a0 b.
co Spent resins, Filter sludges evaporator bottoms, etc.
Dry Campressible Waste (NOIE 1)
Irradiated Ccaqmnent Control rods, etc.
m3 Ci 3
Ci 3
Ci 1.18 El 4.93 E2 2.15 E2 6.80 E-1 0.00 EO 0.00 EO d.
Other NonCcmpressible Metal Waste (NOTE 1) 3 Ci 1.49 El 2.48 El 2.
Esthnate of Major Nuclide Gcm~ositicjn (by type of waste) ao Co-60 Co-58 Fe-55 Ni-63 Cs-137 Mn-54 Cs-134 Sb-125 Cr-51 42 25 10 7
7 3
3 1
1 b.
Co-60 Co-58 Fe-58 Ni-63 Cs-137 Sb-125 49 17 16 9
3 1
c d+
v
~<
a
~ 3.
"Solid Na.~ D
'tian Nimiber of Shi ts 5
16 (NOZE 2)
Mode of Sole Use Truck Sole Use Truck rtation Destination Barnwall, S.C.
Oak Ridge, TN B.
IHRADIKZDH3Ef SfKEKWlS Number of Shi ts Mode of rtation Destination N/A N/A N/A = Not Applicable FIDRIDA RSER
& LIGHZ CCHPANY
'IURKEY POINZ PIANZ SBGANNUALREKRZ JULY 1987 'IKKVGH DECEMBER 1987 UNITS 3 AND 4 TABIE 5B SOLID WASZE SUPPZZHEÃZ Waste Total (NOZE 4)
Classification Volume Total Ft3 Curie Quantity (NOTES 5)
Principal Radionuclides (NOZE 6)
Type of Waste R.G. 1.21 Category (NOZE 7)
Type of Container Solidification or Absorbent Agent 8115.6 (NOZE 3)
.93 None IWR Ocapactable
- 1. b and Non-Oarpactable Trash (Note 5)
Non-Spec N/A Strong, Tight Package Class B 417 492.9 S~O, NiW3
~0, Cs-137, Tl/2 < 5 yr.
ISR Ion B<clmnge Resins
- l. a NRC Certified N/A ISA > Type A v
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FIDRIDA POWER & LIGHZ COMP TURKEY POINT UNIT NOS.
3
& 4 SEMI-ANNUALREPORT JULY 1987 'QBKUGH DEEMS% 1987 TABI1" 5B (OONTINUED)
SOLID WASTE SUPPLEMENTS Dry Ooapressible Waste Volume indicates volume shipped to burial site following volume reduction by a waste processing facility.
Volume shipped to the was~ processing facility was 4.29 E2 m.
Material transported to Oak Ridge, Tennesmm, was consigned to licensed processing facilities for volume reduction activities.
The remaining material after processing is transported by the processor to Barnwell, S.C. for burial.
Volume listed is composed of waste shipped to the burial site by contracted waste processing and volume reduction facilities.
The total curie quantity and radionuclide composition of solid waste shipped from the Turkey Point Plant Units 3
& 4 are determuned using a combination of qualitative and quantitive techniques.
In general, the Turkey Point Plant follows the guidelines outlined in the Low Level Waste Licensing Branch Technical Position (BTP) on Radioactive Waste Classification (5/11/83) for these determinations.
The most frequently used techniques for determining the total curie quantity in a
package are the dose to curie methods and the (concentration) x (Volume or Mass) calculations.
Where appropriate, engineering type activation analyses may be applied.
Since each of the above methodologies involves to some exit qualitative parameters, the total curie quantity is considered to be an estimate.
The cxzqposition of radionuclides in the waste is determined by both on-site analyses for principal ganma emittms and periodic off-site analyses for other radionuclides.
The on-site analyses are performed either on a
batch basis or on a
routine basis using reasonably representative samples as appropriate for the waste ~.
Offsite analyses are used to establish scaling factors or other estimates for radionuclides such as 3H, 14C, 99Tc, 129I, TRO, 241Pu, 242Cm, 63Ni, and 55Fe.
"Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than.Ol time+ the concentration of the nuclide listed in Table 1 or.01 times the smallest concentration of that nuclide listed in Table 2 of 10 CFR 61.
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""Type of
" is generally specified escribed in NUR1K 0782, Draft Envirorment Impact Statement on 10 CFR 61 "Licensing Recpirements for land Disposal of Radioactive Waste".
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" "Type of Container" refers to the transport package.
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14000, JUNO BEACH, FL 33408.0420
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FEBRUARY 2 9 1988 L-88-101 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.
C.
20555 Gentlemen:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 Semi-Annual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of July 1 1987 through December 1987 for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.4.
Should there be any questions regarding this information, please contact us.
Very truly yours F.
Conw y nior Vice President Nuclear WFC/SDF/gp Attachment cc:
Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant SDF/02 6. RER an FPL Group company
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