ML17348B411
| ML17348B411 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/31/1991 |
| From: | Berg J, Kaminskas V, Steinke R FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17348B410 | List: |
| References | |
| NUDOCS 9203040170 | |
| Download: ML17348B411 (36) | |
Text
TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY 1991 THROUGH DECEMBER 1991 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY-E. Berg Radiochemis R. N. Steinke Chemistry Supervisor V. A. K minskas Operations Manager L. W. Pearce Plant General Manager e203040170 9~0~04 PDR ADOCK 05000250 R PDR
l INDEX 1.0 Regulatory Limits 1.1 Liquid Effluents 1.2 Gaseous Effluents 2.0 Maximum Permissible Concentration 3.0 Average Energy 4.0 Measurements and Approximation of Total Radioactivity 4.1 Liquid Effluents Discussion
- a. Unit 3 Liquid Effluents Summation
- b. Unit 4 Liquid Effluents Summation 4.2 Gaseous Effluents Discussion
- a. Unit 3 Gaseous Effluents Summation t 5.0
- b. Unit 4 Gaseous Effluents Summation 4.3 Estimate of Error Batch Releases 5.1 5.2 Liquid Gaseous 6.0 Unplanned Releases 7.0 Reactor Coolant Activity 8.0 Site Radiation Dose 9.0 Offsite Dose Calculation Manual Revisions 10.0 Solid Waste and Irradiated Fuel Shipments 11.0 Process Control Program Revisions
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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION JULY 1991 THROUGH DECEMBER 1991 1.0 REGULATORY LIMITS 1.1 Li uid Effluents a) The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentration 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 2.0 E-04 microcuries per milliliter.
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 as follows:
During any calendar quarter, to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.
During any calendar year, to less than or equal to 3 mrem to the total body and less than or equal to 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/year to the total body and less than or equal to 3000 mrem/'year to the skin due to noble gases.
Less than or equal to 1500 mrem/year to any organ due to I-131, I-133, tritium and for all radioactive materials in particulate form with half-lives greater than 8 days.
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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 less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation.
During any calendar year, to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
c) The dose per reactor to a member of the public, due to I-131, I-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.
2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS Water: As per 10CFR20, Appendix B, Table II, Column entrained or dissolved noble gases as described in 2, for 1.1.A of this report.
Air: Release concentrations are limited to dose rate limits described in 1.2.A.
3.0 AVERAGE ENERGY The average energy of fission and activation gases in effluents is not applicable.
4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY All liquid and airborne discharges to the environment during this 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.
When alpha, tritium and named nuclides are shown as curies on the following tables, this should be interpreted as "no activity was detected on the samples using the Plant Technical Specification analyses techniques to achieve required Lower Level of Detection (LLD) sensitivity for radioactive effluents".
4.1 Li uid Effluents Aliquots of representative pre-release samples, from the waste disposal system, were isotopically analyzed for gamma emitting isotopes on a multichannel analyzer.
Frequent periodic sampling and analysis were used to conservatively determine if any radioactivity was being released via the steam generator blowdown system and the storm drain 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 radioactivity. Tritium was determined by use of liquid scintillation techniques and gross alpha radioactivity was determined by use of a solid state scintillation system. The quarterly composite was analyzed for Sr-89, Sr-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.
Aliquots of representative pre-release samples from the waste disposal system were analyzed on a per release basis for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released in order to estimate the total dissolved gases released.
The liquid waste treatment system is shared by both units at the site and generally all liquid releases are allocated on a 50/50 basis to each unit.
4.2 Gaseous Ef fluents Airborne releases to the atmosphere occurred from:
release of gas decay tanks, the instrument bleedline, containment purges, and 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, Sr-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 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 SPING-4 radiation monitor and 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.
Meteorological data for the period January 1991 through December 1991, in the form of Joint Frequency Distribution Tables is maintained on-site.
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 TYPE AVERAGE ERROR MAXIMUM ERROR Liquid +2-7 +14 Gaseous +2.5 +4 5.0 BATCH RELEASES 5.1 Liciuid Unit 3 Unit 4 a ) Number of releases, 1.94E+02 1.94E+02 b) Total time period of batch releases, minutes 1.71E+04 1.71E+04 c) Maximum time period for a batch release, minutes 1.80E+02 1.80E+02 d) Average time period for a batch release, minutes 8.97E+01 8.97E+01 e) Minimum time period for a batch release, minutes 2.10E+01 2.10E+01 f) Average stream flow during period of release of effluent into a flowing stream, LPM 2.99E+06 2.99E+06 5.2 Gaseous Unit 3 Unit 4 a) Number of batch releases 8.50E+00 9.50E+00 b) Total time period of batch releases, minutes 1.23E+03 1.47E+03 c) Maximum time period for a batch release, minutes 6.40E+02 6.40E+02 d) Average time period for a batch release, minutes 1.45E+02 1.55E+02 e) Minimum time period for a batch release, minutes 3.00E+01 3.00E+01
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6.0 UNPLANNED RELEASES 6.1 ~iciuid Unit 3 Unit 4 a) Number of releases 0 0 b) Total activity released, curies 6.2 Gaseous a) Number of releases b) Total activity released, curies 6.3 See Attachment 1, if applicable, for:
a) A description of the event and equipment involved.
b) Cause(s) for the unplanned event.
7.0 REACTOR COOLANT ACTIVITY 7.1 Unit 3 Reactor coolant activity limits of 100/E-bar and 1.0 microCurie pe,r gram Dose Equivalent I-131 were not exceeded.
7.2 Unit 4 Reactor coolant activity limits of 100/E-bar and 1.0 microCurie per gram Dose Equivalent I-131 were not exceeded.
8.0 SITE RADIATION DOSE The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary 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. Specific activities used in these calculations are the sum of activities in Unit 3, Table 4 and Unit 4, Table 4.
These dose calculations 'ere made using historical meteorological data.
VISITOR DOSE SUMMATION JANUARY 1991 THROUGH DECEMBER 1991 UNITS 3 AND 4 Age Group: Adult Location: Red Barn Inhalation Dose mrem Bone 6.82 E-08 Liver 6.90 E-07 Thyroid 2.98 E-05 Kidney 7.48 E-07 Lung 7.77 E-07 GI-LLI 6.21 E-07 Total Body 6.50 E-07 NOBLE GAS EXPOSURE Gamma Air Dose 1.70 E-05 mrads Beta Air Dose 4.79 E-05 mrads 9.0 OFFSITE DOSE CALCULATION MANUAL REVISIONS t There were no 10.0 SOLID No ODCM revisions during this reporting period.
WASTE AND IRRADIATED FUEL SHIPMENTS irradiated fuel shi p ments were made from the site. Common solid waste from Turkey this report.
Point Units 3 and 4 were shipped jointly. A summation of these shipments is given in Table 6 of 11.0 PROCESS CONTROL PROGRAM REVISIONS Changes to the Process Control Program are summarized in Attachment 1.
TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNIT 3 TABLE 1 LI UID EFFLUENTS
SUMMARY
A. FISSION AND ACTIVATION PRODUCTS Units Quarter 3 quarter 4
- 1. Total Release(not including tritium, gases, alpha Ci 1.35 E-01 1.25 E-01
- 2. Average diluted concentration during period y Ci/ml 9.31 E-09 3.34 E-09 B. TRITIUM
- 1. Total Release 4.21 E+01 4.95 E+01
- 2. Average diluted concentration during period yCi/ml 2.90 E-06 1.32 E-06 C. DISSOLVED AND ENTRAINED GASES
- 1. Total Release Ci 5.60 E-04 1.04 E-02
- 2. Average diluted concentration during period yci/ml 3 86 E 11 2 78 E 10 D. GROSS ALPHA RADIOACTIVITY
- 1. Total Release
- Ci <6.20E-08 <4.07E-08 E. LI UID VOLUMES 1 ~ Batch waste released, prior to dilution liters 2.39 E+06 1.82 E+06 2 ~ Continuous waste released, prior to dilution liters
- 3. Dilution water used during period liters 1.45 E+10 3.74 E+10
- MDA Values in units of pCi/ml.
TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNIT 3 TABLE 2 LI UID EFFLUENTS
SUMMARY
Nuclides Units Continuous Mode Batch Mode Released Quarter 3 Quarter 4 Quarter 3 Quarter 4 Cr-51 Ci 1.03 E-05 Mn-54 Ci 2.39 E-02 8.70 E-03 Fe-55 Ci 9.32 E-02 8.26 E-02 Co-57 Ci 4.00 E-07 1.03 E-05 Co-58 Ci 1.45 E-03 2 '9 E-03 Fe-59 Ci 2.86 E-06 Co-60 Ci 5.95 E-03 1 '7 E-02 Sr-89 Ci 1.02 E-04 Sr-90 Ci 1.10 E-04 1.08 E-04 Nb-95 F 57 E-05 Tc-99 2 ~ 02 E-06 A -110 Ci 5.15 E-04 6 '0 E-04 Sn-113 Ci 5.25 E-06 Sb-124 Ci 1.14 E-04 Sb-125 Ci 3.56 E-03 2.02 E-03 I-131 Ci 2.30 E-04 I-133 Ci 3 '9 E-04 Cs-134 Ci 1.31 E-03 1 '8 E-03 I-135 Ci 1.97 E-05 Cs-137 Ci 4.84 E-03 7.00 E-03 W-187 Ci 2.85 E-OS 1.08 E-05 Total for period Ci 1.35 E-01 1 '5 E-01
SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNIT 3 TABLE 2 (continued)
LI UID EFFLUENTS
SUMMARY
LIQUID DISSOLVED GAS Nuclides Units Continuous Mode Batch Mode Released Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85 Ci 2.26 E-03 Xe-131 Ci Xe-131m Ci Xe-133 Ci 1 ~ 04 E-02 Xe-133m Ci Xe-135 Ci 5 '0 E-06 Xe-135m Ci Total for Period Ci 2.26 E-03 1.04 E-02 LIQUID EFFLUENTS-DOSE SUMMATION JANUARY 1991 THROUGH DECEMBER 1991 UNIT 3 Age group: Teenager Location: Cooling Canal Shoreline Deposition Dose (mrem) of Annual Limit Total Bod 2.76 E-03 9.20 E-02 10
SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNIT 3 TABLE 3 GASEOUS EFFLUENTS
SUMMARY
A. FISSION AND ACTIVATION PRODUCTS Units uarter 3 uarter 4
- 1. Total Release Ci 8.87 E+00
- 2. Average Release Rate for Period yCi/sec 1-12 E+00 B. IODINES
- 1. Total Iodine-131 Ci 5.85 E-04
- 2. Average Release Rate for Period yCi/sec 7 '6 E-05 C. PARTICULATES
- 1. Particulates Tl/2 > 8 days Ci 1.15 E-06 F 55 E-06
- 2. Average Release Rate for Period yCi/sec 1.45 E-07 3 '1 E-07
- 3. Gross Alpha Radioactivity
- 1. Total Roloase Ci
- 2. Average Release Rate for Period yCi/sec
- MDA values in units of pCi/ml 11
SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNIT 3 TABLE 4 GASEOUS EFFLUENTS
SUMMARY
A. FISSION GASES Nuclides Units Continuous Mode Batch Mode Released Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85m Ci 1 ~ 94 E-04 Kr-87 Ci Xe-131m Ci 2.91 E-02 Xe-133 Ci 5 '0 E+00 3.42 E+00 Xe-133m Ci 2.63 E-02 Xe-135 Ci 1.86 E-01 8.55 E-03 Xe-135m Ci Total for period Ci 5.39 E+00 3.48 E+00 Nuclides Units Continuous Mode Released Quarter 3 Quarter 4 I-131 Ci 5.85 E-04 I-133 Ci 2.95 E-05 Total for period Ci 6.15 E-04 C. PARTICULATES Nuclides Units Continuous Mode Released Quarter 3 Quarter 4 Co-60 Ci 2.04 E-06 Cs-137 Ci 1.15 E-06 5.05 E-07 Total for period Ci 1. 15 E-06 2.55 E-06 12
TURKEY PLANT SEMIAN REPORT JANUARY 1991 THROUGH DECEMBER 1991 UNIT 3 TABLE 5 DOSES DUE TO IODINE, TRITIUM, AND PARTICULATES Pathway Bone Liver Thyroid Kidney Lung GI-LLI Skin Total Body Cow milk- 2.96 E-05 3.62 E-05 1.00 E-02 8 - 51 E-06 1.63 E-06 2-38 E-06 1.97 E-05 Infant FruitGVeg 1.23 E-06 3.07 E-06 3.84 E-04 3.56 E-06 1.46 E-06 2. 14 E-06 2.43 E-06 Fresh Ground 3. 11 E-06 3.11 E-06 3.11 E-06 3.11 E-06 3.11 E-06 3.11 E-06 3.65 E-06 3.11 E-06 Plane Inhalation 5.67 E-08 6.06 E-07 2.48 E-05 6.54 E-07 6.78 E-07 5 '8 E-07 5.72 E-07 Adult Totals 3.40 E-05 4.30 E-05 1.04 E-02 1.58 E-05 6.88 E-06 8.17 E-06 3.65 E-06 2.58 E-05 (mrem)
%Annual 2.26 E-04 2.87 E-04 6.95 E-02 1 . 06 E-04 4.59 E-05 5.45 E-05 2.43 E-05 1.72 E-04 Limit Dose due to Noble Gases Gamma Air Dose 6.34 E-05 mrad 0 of Annual Limit 6.34 E-04 0/yr Beta Air Dose 1.79 E-04 mrad 0 of Annual Limit 8.93 E-04 0/yr 13
SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNIT 4 TABLE 1 LI UID EFFLUENTS
SUMMARY
A. FISSION AND ACTIVATION PRODUCTS Units guarter 3 quarter 4
- 1. Total Release(not including tritium, gases, alpha Ci 1.35 E-01 1.25 E-01
- 2. Average diluted concentration during period yci/ml 9.31 E-09 3.34 E-09 B. TRITIUM 1 . Total Release Ci 4.21 E+01 4. 95 E+01
- 2. Average diluted concentration during period yci/ml 2.90 E-06 1.32 E-06 C. DISSOLVED AND ENTRAINED GASES
- 1. Total Release C1 5. 60 E-04 1.04 E<<02
- 2. Average diluted concentration during period yCi/ml 3.86 E-ll 2.78 E-10 D. GROSS ALPHA RADIOACTIVITY
- 1. Total Release
- C1 <6.20E-08 <4.07E-08 E. LI UID VOLUMES 1 . Batch waste released, prior to dilution liters 2.39 E+06 1.82 E+06 2 . continuous waste released, prior to dilution liters
- 3. Dilution water used during period liters 1.45 E+10 3.74 E+10
- MDA Values in units of pCi/ml.
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SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNIT 4 TABLE 2 LI UID EFFLUENTS
SUMMARY
Nuclides Units Continuous Mode Batch Mode Released Quarter 3 Quarter 4 Quarter 3 Quarter 4 Cr-51 Ci 1.03 E-05 Mn-54 Ci 2 '9 E-02 8.70 E-03 Fe-55 Ci 9.32 E-02 8.26 E-02 Co-57 Ci F 00 E-07 1 '3 E-05 Co-58 Ci 1 '5 E-03 2.69 E-03 Fe-59 Ci 2 '6 E-06 Co-60 Ci 5.95 E-03 1.87 E-02 Sr-89 Ci 1.02 E-04 Sr-90 Ci 1.10 E-04 1.08 E-04 Nb-95 Ci 1.57 E-05 Tc-99 Ci 2 '2 E-06 A -110 Ci 5 '5 E-04 6.10 E-04 Sn-113 Ci 5.25 E-06 Sb-124 Ci 1.14 E-04 Sb-125 Ci 3.56 E-03 2 '2 E-03 I-131 Ci 2.30 E-04 I-133 Ci 3.29 E-04 Cs-134 Ci 1 '1 E-03 1 '8 E-03 Ci 1.97 E-05 Cs-137 4.84 E-03 F 00 E-03 W-187 Ci 2.85 E-05 1.08 E-05 Total for period Ci 1.35 E-01 1.25 E-01 15
SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNIT 4 TABLE 2 (continued)
LI UID EFFLUENTS
SUMMARY
LIQUID DISSOLVED GAS Nuclides Units Continuous Mode Batch Mode Released Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85 Ci 2.26 E-03 Xe-131 Xe-131m Ci Ze-133 Ci 1. 04 E-02 Xe-133m Ci Ze-135 Ci 5.40 E-06 Xe-135m Ci Total for Period Ci 2.26 E-03 F 04 E-02 LIQUID EFFLUENTS-DOSE SUMMATION JANUARY 1991 THROUGH DECEMBER 1991 UNIT 4 Age group: Teenager Location: Cooling Canal Shoreline Deposition Dose (mrem) of Annual limit Total Body 1.80 E-3 6.00 E-02 16
SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNIT 4 TABLE 3 GASEOUS EFFLUENTS
SUMMARY
A. FISSION AND ACTIVATION PRODUCTS Units uarter 3 Quarter 4
- 1. Total Release Ci 9 '6 E+00
- 2. Average Release Rate for Period yCi/sec 1.19 E+00 B. IODINES
- 1. Total Zodine-131 Ci 5.85 E 04
- 2. Average Release Rate for Period yCi/sec 7.36 E-05 C. PARTICULATES
- 1. Particulates Tl/2 > 8 days Ci 1.15 E-06 2.55 E-06
- 2. Average Release Rate for Period yCi/sec 1.45 E-07 3 '1 E-07
- 3. Gross Alpha Radioactivity
- Ci <2.60E-15 <2.03E-15
- 1. Total Release Ci 1 ~ 99 E-02
- 2. Average Reloaso Rate for Period yCi/sec 2.50 E-03
- MDA values in units of pCi/ml 17
SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNIT 4 TABLE 4 GASEOUS EFFLUENTS
SUMMARY
A. FISSION GASES Nuclides Units Continuous Mode Batch Mode Released Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85m Ci 1.94 E-04 Kr-87 Ci Xe-131m Ci 2.91 E-02 Xe-133 Ci 5.20 E+00 4.01 E+00 Xe-133m Ci 2.63 E-02 Xe-135 Ci 1.86 E-01 8.55 E-03 Xe-135m Ci Total for period Ci 5.39 E+00 4.07 E+00 Nuclides Units Continuous Mode Released Quarter 3 Quarter 4 I-131 Ci 5.85 E-04 I-133 Ci 2.95 E-05 Total for period Ci 6.15 E-04 C. PARTICULATES Nuclides Units Continuous Mode Released Quarter 3 Quarter 4 Co-60 Ci 2.04 E-06 Cs-137 Ci 1.15 E-06 5.05 E-07 Total for period Ci 1.15 E-06 2.55 E-06 18
TURKEY PLANT SEMI REPORT JANUARY 1991 THROUGH DECEMBER 1991 UNIT 4 TABLE 5 DOSES DUE TO IODINE, TRITIUM, AND PARTICULATES Pathway Bone Liver Thyroid Kidney Lung GI-LLI Skin Total Body Cow milk- 2.95 E-05 3.60 E-05 F 00 E-02 8.43 E-06 1.49 E-06 2.23 E-06 1.95 E-05 Infant Fruit&Veg 1.23 E-06 2.89 E-06 3.83 E-04 3.39 E-06 1.28 E-06 1.96 E-06 2.25 E-06 Fresh Ground 3. 11 E-06 3.11 E-06 3.11 E-06 3. 11 E-06 3.11 E-06 3. 11 E-06 3.65 E-06 3.11 E-06 Plane Inhalation 5.66 E-08 5.41 E-07 2.47 E-05 5.89 E-07 6.13 E-07 4 '3 E-07 5.08 E-07 Adult Totals 3.39 E-05 4.26 E-05 1.04 E-02 1.55 E-05 6.50 E-06 7.79 E-06 3.65 E-06 2.54 E-05 (mrem)
%Annual Linit 2.26 E-04 2.84 E-04 6.94 E-02 1.03 E-04 4.33 E-05 5.19 E-05 2 '3 E-05 1.69 E-04 Dose due to Noble Gases Gamma Air Dose 6.69 E-05 mrad 0 of Annual Limit 6.69 E-04 0/yr Beta Air Dose 1.89 E-04 mrad 0 of Annual Limit 9.44 E-04 4/yr 19
FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNITS 3 AND 4 TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Ao SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL
- 1. TYPE OF WASTE UNITS 6 MONTH PERIOD %ERR a ~ Spent resin, filters m 5.52 EO sludge, evaporator bottoms Ci 1.27 EO 20
- b. Dry Compressible waste m~ 8.29 E1 (Note 1) Ci 1.17 EO 20
m'ontrol
- d. Other non-compressible m~ 9.98 EO Waste (Note 2) Ci 4.62 E-3 20
- 2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION BY TYPE OF WASTE UNITS VALUE a e Cs-137 44 Co-60 18 Cs-134 11
'0 Fe-55 9 Ni-63 7 Co-58 7 Sb-125 2 Mn-54 2
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Page 2 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNITS 3 AND 4 TABLE 6 UNITS VALUE
- d. Fe-55 52 H-3 39 C-14 3 Cs-137 2 Co-60 2 Sb-125 1 Cs-134 1 NUMBER OF SHIPMENTS MODE OF TRANSPORT DESTINATION 11 (Note 3) Sole use truck Oak Ridge, TN 1 Sole use truck Barnwell, SC 2 (Note 4) Sole use truck Kingston, TN B. IRRADIATED FUEL SHIPMENTS None 21
FLORIDA POWER G LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNITS 3 G 4 TABLE 6 SOLID WASTE SUPPLEMENT (NOTE 5) (HOTE 6) (HOTE 7) (NOTE 8)
Total Total Principal Type of R.G. 1.2'I Type of Solidification Waste Voipe Curie Radionuclides Waste Category Container or Absorbent Classification Ft Ouantity Agent Class A 195. 'I 1.27 Ni-63 Dewatered 1a >Type A, N/A Sr-90 Resin LSA Cs-137 Cask Class A 2926.9 1 '7 Hone Compactable 1b. Strong N/A and Hon- Tight Compactable Trash Class A 352.5 0.0046 None Waste Oil 1d. Strong H/A Tight FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1991 THROUGH DECEMBER 1991 UNITS 3 AND 4 TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Ao SOLID WASTE SHIPMENT OFFSITE FOR BURIAL OR DISPOSAL Note 1: Dry compressible waste volume indicates volume shipped to burial site following reduction by a waste processing facility. Volume shipped to the waste processing facility was 797.4 m Note 2: Other noncompressible waste indicates volume shipped to a waste processing facility for disposal via incineration.
Material transported to Oak Ridge, Tennessee, was consigned to licensed processing facilities for volume reduction and decontamination activities. The material remaining after processing was transported by the processor to Barnwell, South Carolina, for burial.
Note 4: Material transported to Kingston, Tennessee was consigned to a licensed processing facility for incineration.
Note 5: The total curie quantity and radionuclide composition of solid waste shipped from the Turkey Point Plant Units 3 and 4 are determined using a combination of qualitative and quantitive techniques. The Turkey Point Plant follows the guidelines in the Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (5/ll/83) for these determinations.
The most frequently used techniques for determining the total activity in a package are the dose to curie method and inference from specific activity and mass or activity concentration and volume. Activation analysis may be applied when it is appropriate. The total activity determination by any of these methods is considered to be an estimate.
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Page 2 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 19 9 1 THROUGH DECEMBER 199 1 UNITS 3 AND 4 'TABLE 6 The composition of radionuclides in the waste is determined by both on-site analysis for principle gamma emitters and periodic off-site analyses for difficult to measure isotopes. The on-site analyses are performed either on a batch basis or on a routine basis using representative samples appropriate for the waste type.
Off-site analyses are used to establish scaling factors or other estimates for difficult to measure isotopes.
Note 6: Principle radionuclide refers to those radionuclides contained in the waste in concentrations greater than 0.01 times the concentration of the nuclide listed in Table 1 or 0.01 times the smallest concentration of the nuclide listed in Table 2 of 10 CFR 61.
Note 7: Type of waste is specified as described in NUREG 0782, Draft Environment Impact Statement on 10 CFR 61 "Licensing Requirements for Land Disposal of Radioactive Waste".
Note 8: Type of container refers to the transport package.
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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 19 9 1 THROUGH DECEMBER 19 9 1 UNITS 3 AND 4 ATTACHMENT 1
SUMMARY
OF CHANGES TO THE PROCESS CONTROL PROGRAM During this reporting period, Turkey Point Operating Procedure 11550.48, Process Control Program for Dewatering Radioactive Waste Liners, was cancelled and replaced with Procedure O-HPS-042.8, Dewatering Controls for Radioactive Waste Liners.
t This change is only to revise the Process Control Program to Turkey Point s upgraded procedure format.
technical content of the procedure.
These changes are degree of assurance No change was made to the administrative only. They have no impact, on the that the waste form produced under the Process Control Program will conform to the requirements of 10CFR61 and the disposal site licenses.
NuPac Services, Inc. Procedure PT-51, Solidification Process Control Procedure, Revision 8, March 30, 1988, was approved for use at Turkey Point Nuclear Plant during this reporting period. This procedure was subsequently cancelled following completion of a waste solidification campaign.
This vendor process control program, together with the supporting Topical Report, provides assurance that the waste form produced con forms to the requirements of 10CFR61 and the disposal site licenses.
Copies of the above procedures are attached.
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