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{{#Wiki_filter:Turkey Point Plant Units 3 and 4 1 | {{#Wiki_filter:Turkey Point Plant Units 3 and 4 1 | ||
ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT January 1996 through December 1996 Submilted by: | |||
NUCLEAR CHEMISTRY DEPARTMENT FLORIDA POWER AND LIGHT COMPANY C.. Murray, Radiochemistry Supervisor R. N. Steinke, Chemistry Supervisor R G. est, Operations Manager D. E. Jernigan, ant General Manager 9704090i24 970329 PDR ADOCK 05000250 R PDR | |||
TURKEY POINT UNITS 3 AND 4 | TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RElEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 Table Of Contents 1.0 REGULATORY LIMITS 2.0 MAXIMUMPERMISSIBLE CONCENTRATION.... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 3.0 AVERAGE ENERGY . | ||
~~~~~~~~~~~~~4 3.0 AVERAGE ENERGY.4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY.............~......... | 4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY.............~......... ~ 4 5.0 BATCH RELEASES 6.0 UNPLANNED RELEASES 7.0 REACTOR COOLANT ACTIVITY. 8 8.0 SITE RADIATIONDOSE. | ||
~4 5.0 BATCH RELEASES 6.0 UNPLANNED RELEASES 7.0 REACTOR COOLANT ACTIVITY.8 8.0 SITE | 9.0 OFFSITE DOSE CALCULATIONMANUAL(ODCM) REVISIONS. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 10.0 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS . ....... 9 11.0 PROCESS CONTROL PROGRAM REVISIONS. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 12.0 INOPERABLE EFFLUENT MONITORING INSTRUMENTATION............. | ||
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~~~~~~~~~~~~~9 12.0 INOPERABLE EFFLUENT MONITORING INSTRUMENTATION............. | |||
Page 2 | TURKEY POINT UNITS 3 ANO4 ANNUALRAOIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1996 THROUGH OECEMBER 1996 1.0 REGULATORY LIMITS 1.1. L~iid Edfl (a) The concentration of radioactive material released in liquid effluent to unrestricted areas shall not exceed ten times the concentration specified in 10CFR20 Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained gases. For dissolved or entrained noble gases, the concentration shall not exceed 2.0 E-04 micro-curies per milliliter. | ||
(b) The dose or dose commitment per reactor to a member of the public from any radioactive materials in liquid effluents 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 less than or equal to 5 mrem to any organ. | |||
> During any calendar year, to less than or equal to 3.0 mrem to the total body and less than or equal to 10 mrem to any organ. | |||
1.2 Gaseous Effluent (a) The dose rate due to radioactive materials released in gaseous effluent from the site to areas at and beyond the site boundary shall be limited to the following: | |||
D Less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the skin due to noble gases. | |||
> Less than or equal to 1500 mrem per 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. | |||
(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 to: | |||
> 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 all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluent 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. | |||
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TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 2.0 MAXIMUMPERMISSIBLE CONCENTRATION Water: In accordance with 10CFR20, Appendix B, Table 2, Column 2, and for entrained or dissolved noble gases as described in 1.1.a of this report. | |||
Air: Release concentrations are limited to dose rate limits described in 1.2.a of this report. | |||
3.0 AVERAGE ENERGY The average energy of fission and activation gases in effluents is not applicable. | |||
4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY 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 activitod'as detected on the samples using the Plant Technical Specification analysis techniques to achieve the required Lower Limit of Detection ("LLD") | |||
sensitivity for radioactive effluents. | |||
4.1 Laid Edfl Aliquots of representative pre-release samples, from 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. | |||
Page 4 | |||
*I% | *I% | ||
TURKEY POINT UNITS 3 AND 4 | TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 All radioactivity concentrations determined from sample 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. | ||
There were no continuous liquid effluent releases above the lower limit of detection for either Unit 3 or Unit 4 during this reporting period and therefore these have been omitted from Table 2 of this report | Aliquots of representative samples from the waste disposal system were analyzed on a pre-release basis by 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 respectively. | |||
There were no continuous liquid effluent releases above the lower limit of detection for either Unit 3 or Unit 4 during this reporting period and therefore these have been omitted from Table 2 of this report. | |||
Page 5 | |||
TURKEY POINT UNITS 3 AND 4 | TURKEY POINT UNFFS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 4.2 Gaseous Effluents Airborne releases to the atmosphere occurred from the following sources: | ||
- Gas Decay Tanks | |||
- Containment Purges | |||
- 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 determination, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma spectral 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 monitors and the Plant Vent process monitor recorder chart and the current calibration curve for that process 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. | |||
More Gas Decay Tank Releases were performed in 1996 then in past years due to a increase in oxygen concentration in the Gas Decay Tanks. This was a result of a leak on the in-service Waste Gas Compressor. This problem was corrected and oxygen levels returned to normal. | |||
Meteorological data for the period January 1996 through December 1996, in the form of Joint Frequency Distribution Tables, are maintained on site. | |||
Page 6 | |||
~ t f | |||
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTNE EFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 4.3 Estimation 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, reported to us by the independent lab, were used as the basis for deriving the following analytical error terms: | |||
NUCLIDE TYPE AVERAGE ERROR MAXIMUMERROR Liquid x 4A% x 9.00% | |||
Gaseous x 3.1'/o a 14.0% | |||
5.0 BATCH RELEASES 5.1~LI UID Unit 3 Unit 4 a) Number of releases 1.72E+02 1.72E+02 b) Total time period of batch releases, minutes 1.27E+04 1.27E+04 c) Maximum time period for a batch release, minutes 1.30E+02 1.30E+02 d) Average time period for a batch release, minutes 7.12E+01 7.12E+01 e) Minimum time for a batch release, minutes 5.00E+00 5.00E+00 f) Average stream flow during period of release of effluent into a flowing stream, liters-per-minute 6.02E+06 6.02E+06 | |||
: 5. 1 GASEOUS Unit 3 Unit 4 a) Number of releases 4.70E+01 5.10E+01 b) Total time period of batch releases, minutes 1.88E+03 2.71E+03 c) Maximum time period for a batch release, minutes 7.30E+01 2.40E+02 d) Average time period for a batch release, minutes 4.01E+01 4.69E+01 e) Minimum time for a batch release, minutes 1.00E+01 1.00E+01 Page 7 | |||
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 6.0 UNPLANNED RELEASES 6.1 ~Li uid There were no unplanned liquid releases this period for either Unit 3 or Unit 4. | |||
6.2 Gaseous There was one unplanned release during this reporting period. During the planned release of the "A" Gas Decay Tank (GDT) a valve failure allowed the contents of the "F" GDT to be released through the "A" GDT. The "F" GDT was sampled and accounted for and no limits were exceeded. | |||
7.0 REACTOR COOLANT ACTIVITY 7.1 Unit3 Reactor coolant activity limits of 100/E-Bar and 1.0 uCi/gram Dose Equivalent I-131 were not exceeded. | |||
7.2 Unit 4 Reactor coolant activity limits of 100/E-Bar and 1.0 uCi/gram Dose Equivalent I-131 were not exceeded. | |||
8.0 SITE RADIATIONDOSE The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary assumes a visitor was at the child development center/fitness center for ten hours a day, five days each week for fifty weeks of the year, receiving exposure from both Unit 3 and Unit 4 at Turkey Point. The child development center/fitness center is located approximately 1.75 miles WNW of the plant. Specific activities used in these calculations are the sum of the activities listed in Unit 3 Table 3 and Unit 4 Table 3. The following dose calculations were made using historical, meteorological data: | |||
Liver (mrem) 4.73E.08 3.32E.08 Thyroid (mrem) 4.73E 08 3.32E 08 Kidney (mrem) 4.73E 08 3.32E 08 Lung (mrem) 4.73E 08 3.32E.08 Gl LLI (mrem) 4.73E.08 3.32E 08 TotaI Body (mrem) 4.73E.08 3.32E 08 Gamma Air Dose (mrad) 2.02E.06 Beta Air Dose (mrad) 2.73E 06 Page 8 | |||
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 9.0 OFFSITE DOSE CALCULATIONMANUAL ODC REVISIONS The ODCM was revised in its entirety and included as part of "Proposed License Amendments Relocation of Radiological Effluent Technical Specifications Using the Guidance of Generic Letter 89-01," ( L-96-018 date March 27, 1996). No other revisions were made during 1996. | |||
10.0 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS No irradiated fuel shipments were made from the site. Common solid waste from Turkey Point Units 3 and 4 was shipped jointly. A summation of these shipments is given in Table 6 of this report. | |||
11.0 PROCESS CONTROL PROGRAM REVISIONS The Process Control Program was revised as a part of the proposed license amendment discussed in section 9.0 above, and transmitted to the NRC as a part of that request. | |||
12.0 INOPERABLE EFFLUENT MONITORING INSTRUMENTATION No inoperable effluent monitoring instrumentation requiring reportability during this period. | |||
Page 9 | |||
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT a | |||
JANUARY 1996 THROUGH DECEMBER 1996 LIQUID EFFLUENTS | |||
==SUMMARY== | ==SUMMARY== | ||
>r t TURKEY POINT UNITS 3 AND 4 | UNIT 3 TABLE 1 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%) | ||
: 1. Total Release (not including tritium,gases, alpha) CI 2.71E42 2.05E42 6.53E43 2.30E42 | |||
: 2. Average diluted concentration during the period uCI/ml 8.05E-10 1.14E49 6.31E-10 1.59E49 | |||
. Percent of applicable limit 8.05E43 1.14E42 6.31E43 1.59E42 B. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%) | |||
: 1. Total Release CI 1.24E+02 4.25E+01 6 40E+Ot 1.29E+02 | |||
: 2. Average diluted concentration during the period uCVml 3.67E46 2.36E46 6.1 9E46 8.93E46 | |||
. Percent of applicable limit 3.67E42 2.36E42 6.19E42 8.93E42 C. DISSOLVED AND ENTRAINED GASES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%) | |||
: 1. Total Release Cl 3.21E45 6.48E45 1.27E44 | |||
: 2. Average diluted concentration during the period uCVml 9.54E-13 3.59E-12 8.81E-12 | |||
. Percent of applicable limit 4.77E47 1.80E46 4.41 E46 D. GROSS ALPHA RADIOACTIVITY UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%) | |||
: 1. Total Release CI E. LIQUID VOLUMES Qtr1 Qtr 2 Qtr3 Qtr 4 Est. Error (%) | |||
: 1. Batch waste released, prior to dilution LITERS 5.72E+05 5.94E+05 3.72E+05 5.57E+05 10.00 | |||
. Continuous waste released, prior to dilution LITERS | |||
. Dilution water used during period LITERS 3.36E+10 1.80E+10 1.03E+10 1 44E+10 page 10 | |||
>r t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 LIQUIDEFFLUENTS | |||
==SUMMARY== | ==SUMMARY== | ||
UNIT 3 TABLE 2 NUCLIDES RELEASED Qtr 1 | |||
UNIT 3 TABLE 2 NUCLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Fo-55 CI 3.23E<3 4.41E4a3 1.49E43 3.11E43 Sr<9 Ci Sr-90 Ci Na-24 CI Cr-51 CI 6.78E44 7.13E44 1.05E45 Mn-54 CI 1.06E42 1.81E4M 1.45E4M 1.70E43 CI 2.98E46 8.69E4N 2.11E415 Co.58 CI 5.86E43 8.40E43 2.26E4L3 3.98E4Lt Fo-59 CI 5.79E%5 2.63E4M 6.94E46 CI 2.43E43 8.94E44 8.64E4M 4.37E43 n%5 CI Nb-95 CI 5.20E44 2.82E44 7.03E46 1.02E44 r-97 Ci 6.66E45 1.81E4I4 4.96E4I5 6.44E4I5 CI Ru-103 CI | |||
-110 CI 2.27E43 4.18E4t3 1.06E43 2.13E43 Sn-113 CI 3.65E46 Sn-117 CI Sb-124 Ci 7.49E415 4.41 EBS Sb-125 Ci 7.13E4M 2.50E44 1.46E4M I-131 CI I-133 CI I-134 Ci Cs-134 Ci 8.41E46 5.75E4N 4.14E45 9.61E44 I-1 35 CI Cs-137 CI 2.27E44 3.29E415 2.30E4M 2.68E4Lt La-140 CI 4.98E46 4.91E45 2 47E46 Co-141 Ci Co-144 Ci | |||
-187 CI 3.12E44 6.17E44 2.03E44 3.60E44 Np-239 CI TAL FOR PERIOD CI 2.71 E42 6.53E43 LIQUIDEFFLUENTS - DISSOLVED GAS | |||
==SUMMARY== | ==SUMMARY== | ||
NUCLIDES RELEASED | |||
NUCLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 4 CI 2.10E45 6.27E45 CI CI 5.38E46 2.11E46 9.62E45 o-133m CI CI 2.70E4$ 3.10E45 e.138 Ci 2.97E46 TOTAL FOR PERIOD Cl 3.21E415 6.48E45 O.OOE+00 1.27E44 LIQUIDEFFLUENTS - DOSE SUMMATION Age grotrp I Teenager LocaIIbnr Cooling Canal Shoreline Deposition Dose mrom) % of Annual Limit TOTAL BODY 5.69E44 1.90E%2 page 11 | |||
pd I | |||
a | |||
TURKEY POINT UNITS 3 AND 4 O | |||
ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 GASEOUS EFFLUENTS | |||
==SUMMARY== | ==SUMMARY== | ||
UNIT 3 TABLE 3 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error 4/o) | |||
: 1. Total Release Ci 9.33E42 1.64E41 5.11E42 4.21E43 | |||
. Avorago release cato for tho poriod uCVsec 1.20E42 2.09E42 6.42E43 5.41E44 | |||
: 3. Percent of Technical Specification Limit 6.16E-13 1.79E-12 2.97E-13 1.83E-1 4 B. IODINES UNITS Qtr 1 Qtr 3 Qtr 4 Est. Error (4/) | |||
: 1. Total Release | |||
: 2. Averago rolease rato for tho period | |||
: 3. Porcont of Technical SpocITication Limit C. PARTICULATES UNITS Qtr 4 Est, Error (4/) | |||
: 1. Particulates with half-life >8 da | |||
: 2. Averago release rate for tho poriod | |||
: 3. Porcent of Tochnical S ificatlon Limit | |||
: 4. Gross Alpha Radioactivi D. TRITIUM UNITS Qtr 4 Est. Error (4/o | |||
: 1. Total Releaso | |||
: 2. Average release rate for the riod uCI/sec | |||
: 3. Percent of Technical S cification Limit page 12 | |||
pN l TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 GASEOUS EFFLUENTS SUIMMARY UNIT 3 TABLE 4 A. FISSION GASES NUCLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 CI 5.81E~ 2.13E%3 1.47E~ | |||
CI Cl 1.01E~ 9.68E~ 1.97E%5 e-131m Cl 1.85E~ 5.13E<4 7.23E~ 3.91EZ5 Cl 8.15M)2 1.30E<1 4.67E-02 4.15E~ | |||
Xe-133m CI 2.11E~ 2.49E~ 8.42M'l 6.02 MS Xe-135 9.33E~ 2.76E<2 3.43E<3 1.16E~ | |||
roruroer aeeo CI 9.32M)2 1.61M)1 5.10E&2 4.21E~ | |||
NUCUDES CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 CI CI Ci CI CI Xe-131m CI CI e-133m Ci e-135 CI e-135m Ci roru roe muoo Cl B. IODINES NUCUDES rirra CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Br%2 CI I-131 Ci 1-133 Ci roru foe pBreo Cl C. PARTICULATES NUCUDES Narc CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 4 CI CI MrI44 CI Cr<1 CI u FoR pEReo CI page 13 | |||
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 DOSES DUE TO IODINE,TRITIUIM,AND PARTICULATES UNIT 3 TABLE 5 PATHWAY BONE LIVER TNYROIO KIONEY WNG GILU SKIN TOTALBOOY Cow milk - Infant (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Fruit & Veg Fresh (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ground Plane (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 lnhalatlon - Adult (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 TOTAL (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 | |||
% of Annual Limit O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 DOSE DUE TO NOBLE GASES K of Annool Uinit Gamma Air Dose 3.78E46 3.78 EM Beta Air Dose 7.23E46 3.62'age 14 | |||
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 | |||
~ | |||
LIQUID EFFLUENTS | |||
==SUMMARY== | ==SUMMARY== | ||
UNIT 4 TABLE 1 A.FISSION AND | |||
%~4 TURKEY POINT UNITS 3 AND 4 | UNIT 4 TABLE 1 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtf 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%) | ||
: 1. Total Release (not Including tritium,gases, alp CI 2.71E42 2.05E42 6.53E43 2.30E42 | |||
. Average diluted concentration during the perio uCI/ml 8.05E-10 1.14E49 6.31E-10 1.59E49 | |||
. Percent of applicable limit 8.05E43 1.14E42 6.31 E43 1.59E42 B. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%) | |||
: 1. Total Release CI 1.24E+02 4.25E+01 640E+01 1.29E+02 | |||
: 2. Average diluted concentration during the perlo uCVml 3.67E46 2.36E46 6.19E46 8.93E46 | |||
. Percent of applicable limit 3.67E41 2.36E41 6.19E41 8.93E41 C. DISSOLVED AND ENTRAINED GASES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%) | |||
: 1. Total Release CI 3.21E45 6.48E45 1.27E44 | |||
. Average diluted concentration during the perio uCVml 9.54E-13 3.59E-12 8.81E 12 | |||
. Percent of applicable limit 4.77E47 1.80E46 4.41 E46 D. GROSS ALPHA RADIOACTIVITY UNITS Qtr 1 Qtr2 Qtr 3 Qtr 4 Est. Error (%) | |||
: 1. Total Release Ci E. LIQUIDVOLUMES Qtr1 Qtr 2 Qtr3 Qtr 4 Est. Error (%) | |||
: 1. Batch waste released, prior to dilution LITERS 5.72E+05 5.94E+05 3.72E+05 5.57E+05 10.00 | |||
. Continuous waste released, prior to dilution LITERS | |||
. Dilution water used during period LITERS 3.36E+10 1.80E+10 1.03E+10 1A4E+10 page 15 | |||
% ~ | |||
4 | |||
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 LIQUIDEFFLUENTS | |||
==SUMMARY== | ==SUMMARY== | ||
UNIT 4 TABLE 2 NUCLIDES earls RELEASED Qtr 1 | |||
UNIT 4 TABLE 2 NUCLIDES earls BATCH MODE RELEASED Qtr 1 Qtr 3 Qtr 4 Fo-55 Ci 3.23E%3 4.41E<3 1.49E43 3.11E43 Sr<9 CI Sr-90 Ci Na-24 CI Cr-51 CI 6.78E414 7.13E4j4 1.05E4I5 Mn-54 Ci 1.08E4j2 1.81E4I4 1.45E~ 1.70E43 Co-57 CI 2.98E46 8.69E46 2.11E415 CI 5.86E%3 8.40E43 2.26E4I3 3.98E473 Fo-59 CI 5.79E4I5 2.63E44 6.94E46 CI 2.43E4I3 8.94E44 8.64E44 4.37E43 n-65 Ci Nb-95 CI 5.20E44 2.82')4 7.03E46 1.02E4I4 | |||
-97 CI 6.66')5 1.81 EM 4.96E45 6A4E4I5 Ci Ru-103 CI 9-110 Ci 2.27E4I3 4.18E43 1.06E43 2.13E43 Sn-113 CI 3.65E46 Sn-117 CI Sb-124 CI 7.49E4I5 4.41E45 . 1.30E4I5 6.50E415 Sb-125 CI 7.13E44 2.50E44 1.46E44 3.44E4I3 l-131 CI I-133 CI I-134 Ci Cs-134 CI 8.41E4M 5.75E4IS 4.14E45 9.61M'-135 CI Cs-137 CI 3.29E45 2.30E4I4 2.68E43 2.27'.98E46 La-140 Cj 4.91E415 2.47E46 Co-141 Ci Co-144 Ci | |||
-187 CI 3.12E~ 6.17E44 2.03E4j4 N 239 CI AL FOR PEROO Cl 2.71E4I2 2.05E4I2 6.53E43 2.30E412 LIQUIDEFFLUENTS - DISSOLVED GAS | |||
==SUMMARY== | ==SUMMARY== | ||
NUCLIDES RELEASED Kr45m o-131m | |||
TURKEY POINT UNITS 3 AND 4 | NUCLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 CI 2.10E4I5 6.27E4I5 Kr45m CI o-131m CI CI 5.38E46 2.11E46 9.62E45 Cj Cl 2.70E4I6 3.10E4j5 o-138 Ci 2.97E46 TOTAL FOR PERIOO CI 3.21'.48E4I5 1.27E44 LIQUIDEFFLUENTS . DOSE SUMMATION Ags gnwp: Teenager Location: CooilCanai Shorelins Deposition Doss (mrem) OA of Annual Umlt TOTAL BODY 5.69E44 1.90E42 page 16 | ||
n TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 GASEOUS EFFI UENTS | |||
==SUMMARY== | ==SUMMARY== | ||
UNIT 4 TABLE 3 A.FISSION AND | |||
t TURKEY POINT UNITS 3 AND 4 | UNIT 4 TABLE 3 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%) | ||
: 1. Total Release Ci 1.28E41 1.64E41 5.11E42 4.21E43 | |||
. Averago release rate for the period uCi/sec 1.65E42 2.09E42 6.42E43 5.41E44, ~'",,': ll,'lii'i',I | |||
. Percent of Technical Spocification Limit 4.01E-12 1.79E-12 2.97E-13 1.83E-14 B. IODINES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%) | |||
: 1. Total Reieaso Ci | |||
. Average release rate for tho period uCI/soc | |||
: 3. Percent of Tochnical Specification Limit C. PARTICULATES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%) | |||
: 1. Particulates with half-lifo >8 days Ci | |||
. Averago roleaso rato for tho porlod uCVsoc | |||
: 3. Percent of Technical Specification Limit | |||
: 4. Gross Alpha RadioactMty Cl D. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%) | |||
: 1. Total Reloaso Ci 1.64E42 | |||
. Averago roleaso rate for tho poriod uCI/sec 2.11E43 il:!II/!II"'";";I | |||
. Percent of Technical Specification Limit 1.64E46 "i.I'age 17 | |||
1 t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVERELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 GASEOUS EFFLUENTS | |||
==SUMMARY== | ==SUMMARY== | ||
UNIT 4 TABLE 4 A.FISSION GASES NIICLIDES RELEASED | |||
UNIT 4 TABLE 4 A. FISSION GASES NIICLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 CI 2.58E42 2.13E43 1.47E46 Ci CI 1.01E44 9.68E44 1.97E45 Xo-131m CI 1.85E44 5.13E44 9.05E45 3.91 E45 Xo-133 Ci 9.07E42 1.30E41 4.67E42 4.15E43 Xo-133m Ci 2.11E43 2.49E43 8.42E44 6.02E46 Xo-135 CI 9.33E43 2.76E42 3.43E43 1.16E-05 o-135m Ci TOTAL roR ffReo Ci 1.28E41 1.63E41 5.11E42 4.21E43 NUCLIDES CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 4 Ci Kr45 Ci Kr45m Ci Ci CI o-131m Ci CI o-133m CI o-135 Ci o-135m CI CI rarAL foR SSReo Ci B. IODINES NUCLIDES umrs CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 4 Br42 Ci 1-131 Ci 1-133 Ci TOTAL fOR PBUOO Cl C. PARTICULATES NUCLIDES usrs CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ci CI Mn44 Ci Cr41 CI TAL FOR PERIOO Ci Psge18 | |||
t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 DOSES DUE TO IODINE,TRITIUNI,AND PARTICULATES UNIT 4 TABLE 5 PATHWAY BONE llYER THYROID KfONEY LUNG Gl.ill SKIN TOTAL BOOT Cow milk - Infant (mrem) O.OOE+00 1.23E<7 1.23E&7 5.41E~ 1.23E%7 1.23E-07 O.OOE+00 1.23E<7 Fruit & Veg Fresh (mrem O.OOE+00 1.28 MS 1.28E~ 8.47E~ 1.28E~ O.OOE+00 1.28E%8 Ground Plane (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Inhalation - Adult (mrem) O.OOE+00 5.56E~ 5.56E~ 5.56E~ 5.56E~ 5.56M% O.OOE+00 5.56E<8 TOTAL (mrem) O.OOE+00 1.92E<7 1.92E%7 1.18E%7 1.92M)7 1.92&)7 O.OOE+00 1.92E<7 | |||
Dry compressible waste volume indicates volume shipped to burial site following reduction by a waste processing facility was 192.8m'.Material transported to Oak Ridge, Tennessee, was consigned to licensed processing facilities for volume reduction and decontamination activities. | % of Annual Limit O.OOE+00 1.28MS 1.28E~ 7.88E<7 1.28E~ O.OOE+00 1.28E46 DOSES DUE TO NOBLE GASES Y ol Aoooof Lloff Gamma Alr Dose 8.18E~ 8.18E~ | ||
The material remaining after processing was transported by the processor to Barnwell, South Carolina for burial.The material shipped to Kingston, Tennessee was waste oil, which was destroyed by burning.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. | Beta Air Dose 8.90E~ 4.45E~ | ||
The Turkey Point Plant follows the guidelines in the Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (5/11/83)for these determinations. | page 19 | ||
The most frequently used techniques for determining the total activity in a package are the dose to curie method and interference 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.The composition of radionuclides in the waste is determined by both on-site analysis for principle gamma emitters and periodic off-site analyses for | I a ~ | ||
* k | |||
~ ~ | |||
~ t ', S. | |||
~ 5 C | |||
. 1 | |||
t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT o | |||
JANUARY 1996 THROUGH DECEMBER 1996 DOSES DUE TO IODINE,TRITIUM, AND PARTICULATES r | |||
Summation Table 5 PATHWAY BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY Cow milk - Infant O.OOE+00 1.23E47 1.23E47 5.41E48 1.23E47 1.23E47 O.OOE+00 1.23E47 Fruit 8 Vog Fresh O.OOE+00 1.28E4S 1.28E48 8.47E49 1.28E48 1.28E48 O.OOE+00 1.28E48 Ground Plane O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Inhalation - Adult O.OOE+00 5.56E48 5.56E48 S.56E48 5.56E48 5.S6E48 O.OOE+00 5.56E48 TOTAL (mrem) O.OOE+00 1.92E47 1.92E47 1.18E47 1.92E47 1.92E47 O.OOE+00 1.92E47 | |||
% of Annual Limit O.OOE+00 1.28E46 1.28E46 7.88E47 1.28E46 1.28E46 O.OOE+00 1.28E46 DOSES DUE TO NOBLE GASES II of Aoooof thit Gamma Air Doso 1.20E45 1.20E44 Beta Air Doso 1.61 E45 8.07E45 page 20 | |||
TURKEY POINT UNTTS 3 AND 4 ANNUAL RADIOACTIVE EPPLUENTS RELEASE REPORT TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFP SITE POR BURIAL OR DISPOSAL | |||
: 1. TYPE OP WASTE UNITS 12 MONTH PERIOD ERROR a Spent resin, filters m 2.19 El sludge, evaporator bottoms Ci 1.25 BO 20 (Note 1) | |||
Dry Compressible waste m 5.49E1 (Note 2) Ci 7.69 B-l 20 Irradiated components m 0.00 EO Control rods, etc. Ci 0.00 EO Other non-compressible m 1.77 Bl 20 Waste Ci 8.74 B-l | |||
: 2. ESTIMATE OP MAJOR NUCLIDE COMPOSITION OF TYPE OP WASTE UNITS VALUE a ~ Ni-63 0 44 Co-60 ~o 38 Cs-137 4 Fe-55 0 3 | |||
Mn-54 2 | |||
: b. Cr-51 oz 0 26 Co-58 O~ | |||
0 17 Fe-55 O~ | |||
0 15 Co-60 O~ | |||
0 11 Zr-95 6 Ni-59 0 | |||
~o 6 Ni-63 ~O 0 5 Ni-95 ~O 0 5 Ba-140 ~O 0 3 Np-237 O~ | |||
0 2 Ce-144 O~ | |||
0 1 Cs-137 O~ | |||
0 1 Page 21 | |||
I' TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENTS RELEASE REPORT TABLE 6 | |||
: c. N/A UNITS VALUE | |||
: d. Fe-55 60 H-3 18 Co-60 15 Ni-63 3 Zn-65 2 Ni-59 1 3 ~ SOLID WASTE DISPOSITION Number of shi ments Mode of trans ort Destination 3 (Note 3) Sole use truck Oak Ridge, TN 8 Sole use truck Barnwell, SC 1 (Note 3) Sole use truck Kingston, TN B. IRRADIATED FUEL SHIPMENTS None Page 22 | |||
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EPRLUENT RELEASE REPORT TABLE 6 SOLID WASTE SUPPLEMENT Wasto ClassiTication Ft'NOTE Total Volume Total Curio | |||
: 4) (NOTE 5) | |||
Principal Rad ionuclidcs (NOTE 6) | |||
Type of Waste R.O. 121 Category (NOTE 7) | |||
Type of Container Solidification of Absorbcrs Quantity Agent Chas A 1938.4 0.769 None Compactablc Strong Waste Tight NIA Chss A 652.2 1.24 None Dcwatcrcd Strong Resin Tight N/A Class A 123.2 2>270 None Dcwatcrcd Cask NIA Filters Chss A 420 .016 Noae Waste ld. Stroag N/A Oil Tight Chss A 205.8 None Noa-Compactible 1 d. N/A Waste Page 23 | |||
t | |||
'I l | |||
P | |||
TURKEY POINT UNITS 3 AHD 4 ANNUAL RADIOACTIVE EFFLUENTS RELEASE REPORT TABLE 6 Spent resin, filters, sludge, and evaporator bottoms. Volume indicates volume shipped to burial site thru waste processor. | |||
Dry compressible waste volume indicates volume shipped to burial site following reduction by a waste processing facility was 192.8m'. | |||
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. The material shipped to Kingston, Tennessee was waste oil, which was destroyed by burning. | |||
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 (5/11/83) for these determinations. | |||
The most frequently used techniques for determining the total activity in a package are the dose to curie method and interference 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. | |||
The composition of radionuclides in the waste is determined by both on-site analysis for principle gamma emitters and periodic off-site analyses for difficultto 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 difficultto measure isotopes. | |||
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 105CFR 61.55. | |||
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". | |||
Type of container refers to the transport package. | |||
Page 24 | |||
t t A}} |
Revision as of 07:11, 22 October 2019
ML17354A462 | |
Person / Time | |
---|---|
Site: | Turkey Point |
Issue date: | 12/31/1996 |
From: | Charles Murray, Steinke R, West R FLORIDA POWER & LIGHT CO. |
To: | |
Shared Package | |
ML17354A461 | List: |
References | |
NUDOCS 9704090124 | |
Download: ML17354A462 (39) | |
Text
Turkey Point Plant Units 3 and 4 1
ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT January 1996 through December 1996 Submilted by:
NUCLEAR CHEMISTRY DEPARTMENT FLORIDA POWER AND LIGHT COMPANY C.. Murray, Radiochemistry Supervisor R. N. Steinke, Chemistry Supervisor R G. est, Operations Manager D. E. Jernigan, ant General Manager 9704090i24 970329 PDR ADOCK 05000250 R PDR
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RElEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 Table Of Contents 1.0 REGULATORY LIMITS 2.0 MAXIMUMPERMISSIBLE CONCENTRATION.... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 3.0 AVERAGE ENERGY .
4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY.............~......... ~ 4 5.0 BATCH RELEASES 6.0 UNPLANNED RELEASES 7.0 REACTOR COOLANT ACTIVITY. 8 8.0 SITE RADIATIONDOSE.
9.0 OFFSITE DOSE CALCULATIONMANUAL(ODCM) REVISIONS. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 10.0 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS . ....... 9 11.0 PROCESS CONTROL PROGRAM REVISIONS. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 12.0 INOPERABLE EFFLUENT MONITORING INSTRUMENTATION.............
Page 2
TURKEY POINT UNITS 3 ANO4 ANNUALRAOIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1996 THROUGH OECEMBER 1996 1.0 REGULATORY LIMITS 1.1. L~iid Edfl (a) The concentration of radioactive material released in liquid effluent to unrestricted areas shall not exceed ten times the concentration specified in 10CFR20 Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained gases. For dissolved or entrained noble gases, the concentration shall not exceed 2.0 E-04 micro-curies per milliliter.
(b) The dose or dose commitment per reactor to a member of the public from any radioactive materials in liquid effluents 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 less than or equal to 5 mrem to any organ.
> During any calendar year, to less than or equal to 3.0 mrem to the total body and less than or equal to 10 mrem to any organ.
1.2 Gaseous Effluent (a) The dose rate due to radioactive materials released in gaseous effluent from the site to areas at and beyond the site boundary shall be limited to the following:
D Less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the skin due to noble gases.
> Less than or equal to 1500 mrem per 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.
(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 to:
> 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 all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluent 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.
Page 3
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 2.0 MAXIMUMPERMISSIBLE CONCENTRATION Water: In accordance with 10CFR20, Appendix B, Table 2, Column 2, and for entrained or dissolved noble gases as described in 1.1.a of this report.
Air: Release concentrations are limited to dose rate limits described in 1.2.a of this report.
3.0 AVERAGE ENERGY The average energy of fission and activation gases in effluents is not applicable.
4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY 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 activitod'as detected on the samples using the Plant Technical Specification analysis techniques to achieve the required Lower Limit of Detection ("LLD")
sensitivity for radioactive effluents.
4.1 Laid Edfl Aliquots of representative pre-release samples, from 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.
Page 4
- I%
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 All radioactivity concentrations determined from sample 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 samples from the waste disposal system were analyzed on a pre-release basis by 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 respectively.
There were no continuous liquid effluent releases above the lower limit of detection for either Unit 3 or Unit 4 during this reporting period and therefore these have been omitted from Table 2 of this report.
Page 5
TURKEY POINT UNFFS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 4.2 Gaseous Effluents Airborne releases to the atmosphere occurred from the following sources:
- Gas Decay Tanks
- Containment Purges
- 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 determination, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma spectral 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 monitors and the Plant Vent process monitor recorder chart and the current calibration curve for that process 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.
More Gas Decay Tank Releases were performed in 1996 then in past years due to a increase in oxygen concentration in the Gas Decay Tanks. This was a result of a leak on the in-service Waste Gas Compressor. This problem was corrected and oxygen levels returned to normal.
Meteorological data for the period January 1996 through December 1996, in the form of Joint Frequency Distribution Tables, are maintained on site.
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~ t f
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTNE EFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 4.3 Estimation 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, reported to us by the independent lab, were used as the basis for deriving the following analytical error terms:
NUCLIDE TYPE AVERAGE ERROR MAXIMUMERROR Liquid x 4A% x 9.00%
Gaseous x 3.1'/o a 14.0%
5.0 BATCH RELEASES 5.1~LI UID Unit 3 Unit 4 a) Number of releases 1.72E+02 1.72E+02 b) Total time period of batch releases, minutes 1.27E+04 1.27E+04 c) Maximum time period for a batch release, minutes 1.30E+02 1.30E+02 d) Average time period for a batch release, minutes 7.12E+01 7.12E+01 e) Minimum time for a batch release, minutes 5.00E+00 5.00E+00 f) Average stream flow during period of release of effluent into a flowing stream, liters-per-minute 6.02E+06 6.02E+06
- 5. 1 GASEOUS Unit 3 Unit 4 a) Number of releases 4.70E+01 5.10E+01 b) Total time period of batch releases, minutes 1.88E+03 2.71E+03 c) Maximum time period for a batch release, minutes 7.30E+01 2.40E+02 d) Average time period for a batch release, minutes 4.01E+01 4.69E+01 e) Minimum time for a batch release, minutes 1.00E+01 1.00E+01 Page 7
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 6.0 UNPLANNED RELEASES 6.1 ~Li uid There were no unplanned liquid releases this period for either Unit 3 or Unit 4.
6.2 Gaseous There was one unplanned release during this reporting period. During the planned release of the "A" Gas Decay Tank (GDT) a valve failure allowed the contents of the "F" GDT to be released through the "A" GDT. The "F" GDT was sampled and accounted for and no limits were exceeded.
7.0 REACTOR COOLANT ACTIVITY 7.1 Unit3 Reactor coolant activity limits of 100/E-Bar and 1.0 uCi/gram Dose Equivalent I-131 were not exceeded.
7.2 Unit 4 Reactor coolant activity limits of 100/E-Bar and 1.0 uCi/gram Dose Equivalent I-131 were not exceeded.
8.0 SITE RADIATIONDOSE The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary assumes a visitor was at the child development center/fitness center for ten hours a day, five days each week for fifty weeks of the year, receiving exposure from both Unit 3 and Unit 4 at Turkey Point. The child development center/fitness center is located approximately 1.75 miles WNW of the plant. Specific activities used in these calculations are the sum of the activities listed in Unit 3 Table 3 and Unit 4 Table 3. The following dose calculations were made using historical, meteorological data:
Liver (mrem) 4.73E.08 3.32E.08 Thyroid (mrem) 4.73E 08 3.32E 08 Kidney (mrem) 4.73E 08 3.32E 08 Lung (mrem) 4.73E 08 3.32E.08 Gl LLI (mrem) 4.73E.08 3.32E 08 TotaI Body (mrem) 4.73E.08 3.32E 08 Gamma Air Dose (mrad) 2.02E.06 Beta Air Dose (mrad) 2.73E 06 Page 8
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 9.0 OFFSITE DOSE CALCULATIONMANUAL ODC REVISIONS The ODCM was revised in its entirety and included as part of "Proposed License Amendments Relocation of Radiological Effluent Technical Specifications Using the Guidance of Generic Letter 89-01," ( L-96-018 date March 27, 1996). No other revisions were made during 1996.
10.0 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS No irradiated fuel shipments were made from the site. Common solid waste from Turkey Point Units 3 and 4 was shipped jointly. A summation of these shipments is given in Table 6 of this report.
11.0 PROCESS CONTROL PROGRAM REVISIONS The Process Control Program was revised as a part of the proposed license amendment discussed in section 9.0 above, and transmitted to the NRC as a part of that request.
12.0 INOPERABLE EFFLUENT MONITORING INSTRUMENTATION No inoperable effluent monitoring instrumentation requiring reportability during this period.
Page 9
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT a
JANUARY 1996 THROUGH DECEMBER 1996 LIQUID EFFLUENTS
SUMMARY
UNIT 3 TABLE 1 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release (not including tritium,gases, alpha) CI 2.71E42 2.05E42 6.53E43 2.30E42
- 2. Average diluted concentration during the period uCI/ml 8.05E-10 1.14E49 6.31E-10 1.59E49
. Percent of applicable limit 8.05E43 1.14E42 6.31E43 1.59E42 B. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release CI 1.24E+02 4.25E+01 6 40E+Ot 1.29E+02
- 2. Average diluted concentration during the period uCVml 3.67E46 2.36E46 6.1 9E46 8.93E46
. Percent of applicable limit 3.67E42 2.36E42 6.19E42 8.93E42 C. DISSOLVED AND ENTRAINED GASES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release Cl 3.21E45 6.48E45 1.27E44
- 2. Average diluted concentration during the period uCVml 9.54E-13 3.59E-12 8.81E-12
. Percent of applicable limit 4.77E47 1.80E46 4.41 E46 D. GROSS ALPHA RADIOACTIVITY UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release CI E. LIQUID VOLUMES Qtr1 Qtr 2 Qtr3 Qtr 4 Est. Error (%)
- 1. Batch waste released, prior to dilution LITERS 5.72E+05 5.94E+05 3.72E+05 5.57E+05 10.00
. Continuous waste released, prior to dilution LITERS
. Dilution water used during period LITERS 3.36E+10 1.80E+10 1.03E+10 1 44E+10 page 10
>r t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 LIQUIDEFFLUENTS
SUMMARY
UNIT 3 TABLE 2 NUCLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Fo-55 CI 3.23E<3 4.41E4a3 1.49E43 3.11E43 Sr<9 Ci Sr-90 Ci Na-24 CI Cr-51 CI 6.78E44 7.13E44 1.05E45 Mn-54 CI 1.06E42 1.81E4M 1.45E4M 1.70E43 CI 2.98E46 8.69E4N 2.11E415 Co.58 CI 5.86E43 8.40E43 2.26E4L3 3.98E4Lt Fo-59 CI 5.79E%5 2.63E4M 6.94E46 CI 2.43E43 8.94E44 8.64E4M 4.37E43 n%5 CI Nb-95 CI 5.20E44 2.82E44 7.03E46 1.02E44 r-97 Ci 6.66E45 1.81E4I4 4.96E4I5 6.44E4I5 CI Ru-103 CI
-110 CI 2.27E43 4.18E4t3 1.06E43 2.13E43 Sn-113 CI 3.65E46 Sn-117 CI Sb-124 Ci 7.49E415 4.41 EBS Sb-125 Ci 7.13E4M 2.50E44 1.46E4M I-131 CI I-133 CI I-134 Ci Cs-134 Ci 8.41E46 5.75E4N 4.14E45 9.61E44 I-1 35 CI Cs-137 CI 2.27E44 3.29E415 2.30E4M 2.68E4Lt La-140 CI 4.98E46 4.91E45 2 47E46 Co-141 Ci Co-144 Ci
-187 CI 3.12E44 6.17E44 2.03E44 3.60E44 Np-239 CI TAL FOR PERIOD CI 2.71 E42 6.53E43 LIQUIDEFFLUENTS - DISSOLVED GAS
SUMMARY
NUCLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 4 CI 2.10E45 6.27E45 CI CI 5.38E46 2.11E46 9.62E45 o-133m CI CI 2.70E4$ 3.10E45 e.138 Ci 2.97E46 TOTAL FOR PERIOD Cl 3.21E415 6.48E45 O.OOE+00 1.27E44 LIQUIDEFFLUENTS - DOSE SUMMATION Age grotrp I Teenager LocaIIbnr Cooling Canal Shoreline Deposition Dose mrom) % of Annual Limit TOTAL BODY 5.69E44 1.90E%2 page 11
pd I
a
TURKEY POINT UNITS 3 AND 4 O
ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 GASEOUS EFFLUENTS
SUMMARY
UNIT 3 TABLE 3 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error 4/o)
- 1. Total Release Ci 9.33E42 1.64E41 5.11E42 4.21E43
. Avorago release cato for tho poriod uCVsec 1.20E42 2.09E42 6.42E43 5.41E44
- 3. Percent of Technical Specification Limit 6.16E-13 1.79E-12 2.97E-13 1.83E-1 4 B. IODINES UNITS Qtr 1 Qtr 3 Qtr 4 Est. Error (4/)
- 1. Total Release
- 2. Averago rolease rato for tho period
- 3. Porcont of Technical SpocITication Limit C. PARTICULATES UNITS Qtr 4 Est, Error (4/)
- 1. Particulates with half-life >8 da
- 2. Averago release rate for tho poriod
- 3. Porcent of Tochnical S ificatlon Limit
- 4. Gross Alpha Radioactivi D. TRITIUM UNITS Qtr 4 Est. Error (4/o
- 1. Total Releaso
- 2. Average release rate for the riod uCI/sec
- 3. Percent of Technical S cification Limit page 12
pN l TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 GASEOUS EFFLUENTS SUIMMARY UNIT 3 TABLE 4 A. FISSION GASES NUCLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 CI 5.81E~ 2.13E%3 1.47E~
CI Cl 1.01E~ 9.68E~ 1.97E%5 e-131m Cl 1.85E~ 5.13E<4 7.23E~ 3.91EZ5 Cl 8.15M)2 1.30E<1 4.67E-02 4.15E~
Xe-133m CI 2.11E~ 2.49E~ 8.42M'l 6.02 MS Xe-135 9.33E~ 2.76E<2 3.43E<3 1.16E~
roruroer aeeo CI 9.32M)2 1.61M)1 5.10E&2 4.21E~
NUCUDES CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 CI CI Ci CI CI Xe-131m CI CI e-133m Ci e-135 CI e-135m Ci roru roe muoo Cl B. IODINES NUCUDES rirra CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Br%2 CI I-131 Ci 1-133 Ci roru foe pBreo Cl C. PARTICULATES NUCUDES Narc CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 4 CI CI MrI44 CI Cr<1 CI u FoR pEReo CI page 13
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 DOSES DUE TO IODINE,TRITIUIM,AND PARTICULATES UNIT 3 TABLE 5 PATHWAY BONE LIVER TNYROIO KIONEY WNG GILU SKIN TOTALBOOY Cow milk - Infant (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Fruit & Veg Fresh (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ground Plane (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 lnhalatlon - Adult (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 TOTAL (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
% of Annual Limit O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 DOSE DUE TO NOBLE GASES K of Annool Uinit Gamma Air Dose 3.78E46 3.78 EM Beta Air Dose 7.23E46 3.62'age 14
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996
~
LIQUID EFFLUENTS
SUMMARY
UNIT 4 TABLE 1 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtf 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release (not Including tritium,gases, alp CI 2.71E42 2.05E42 6.53E43 2.30E42
. Average diluted concentration during the perio uCI/ml 8.05E-10 1.14E49 6.31E-10 1.59E49
. Percent of applicable limit 8.05E43 1.14E42 6.31 E43 1.59E42 B. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release CI 1.24E+02 4.25E+01 640E+01 1.29E+02
- 2. Average diluted concentration during the perlo uCVml 3.67E46 2.36E46 6.19E46 8.93E46
. Percent of applicable limit 3.67E41 2.36E41 6.19E41 8.93E41 C. DISSOLVED AND ENTRAINED GASES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release CI 3.21E45 6.48E45 1.27E44
. Average diluted concentration during the perio uCVml 9.54E-13 3.59E-12 8.81E 12
. Percent of applicable limit 4.77E47 1.80E46 4.41 E46 D. GROSS ALPHA RADIOACTIVITY UNITS Qtr 1 Qtr2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release Ci E. LIQUIDVOLUMES Qtr1 Qtr 2 Qtr3 Qtr 4 Est. Error (%)
- 1. Batch waste released, prior to dilution LITERS 5.72E+05 5.94E+05 3.72E+05 5.57E+05 10.00
. Continuous waste released, prior to dilution LITERS
. Dilution water used during period LITERS 3.36E+10 1.80E+10 1.03E+10 1A4E+10 page 15
% ~
4
TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 LIQUIDEFFLUENTS
SUMMARY
UNIT 4 TABLE 2 NUCLIDES earls BATCH MODE RELEASED Qtr 1 Qtr 3 Qtr 4 Fo-55 Ci 3.23E%3 4.41E<3 1.49E43 3.11E43 Sr<9 CI Sr-90 Ci Na-24 CI Cr-51 CI 6.78E414 7.13E4j4 1.05E4I5 Mn-54 Ci 1.08E4j2 1.81E4I4 1.45E~ 1.70E43 Co-57 CI 2.98E46 8.69E46 2.11E415 CI 5.86E%3 8.40E43 2.26E4I3 3.98E473 Fo-59 CI 5.79E4I5 2.63E44 6.94E46 CI 2.43E4I3 8.94E44 8.64E44 4.37E43 n-65 Ci Nb-95 CI 5.20E44 2.82')4 7.03E46 1.02E4I4
-97 CI 6.66')5 1.81 EM 4.96E45 6A4E4I5 Ci Ru-103 CI 9-110 Ci 2.27E4I3 4.18E43 1.06E43 2.13E43 Sn-113 CI 3.65E46 Sn-117 CI Sb-124 CI 7.49E4I5 4.41E45 . 1.30E4I5 6.50E415 Sb-125 CI 7.13E44 2.50E44 1.46E44 3.44E4I3 l-131 CI I-133 CI I-134 Ci Cs-134 CI 8.41E4M 5.75E4IS 4.14E45 9.61M'-135 CI Cs-137 CI 3.29E45 2.30E4I4 2.68E43 2.27'.98E46 La-140 Cj 4.91E415 2.47E46 Co-141 Ci Co-144 Ci
-187 CI 3.12E~ 6.17E44 2.03E4j4 N 239 CI AL FOR PEROO Cl 2.71E4I2 2.05E4I2 6.53E43 2.30E412 LIQUIDEFFLUENTS - DISSOLVED GAS
SUMMARY
NUCLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 CI 2.10E4I5 6.27E4I5 Kr45m CI o-131m CI CI 5.38E46 2.11E46 9.62E45 Cj Cl 2.70E4I6 3.10E4j5 o-138 Ci 2.97E46 TOTAL FOR PERIOO CI 3.21'.48E4I5 1.27E44 LIQUIDEFFLUENTS . DOSE SUMMATION Ags gnwp: Teenager Location: CooilCanai Shorelins Deposition Doss (mrem) OA of Annual Umlt TOTAL BODY 5.69E44 1.90E42 page 16
n TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 GASEOUS EFFI UENTS
SUMMARY
UNIT 4 TABLE 3 A. FISSION AND ACTIVATIONPRODUCTS UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release Ci 1.28E41 1.64E41 5.11E42 4.21E43
. Averago release rate for the period uCi/sec 1.65E42 2.09E42 6.42E43 5.41E44, ~'",,': ll,'lii'i',I
. Percent of Technical Spocification Limit 4.01E-12 1.79E-12 2.97E-13 1.83E-14 B. IODINES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Reieaso Ci
. Average release rate for tho period uCI/soc
- 3. Percent of Tochnical Specification Limit C. PARTICULATES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Particulates with half-lifo >8 days Ci
. Averago roleaso rato for tho porlod uCVsoc
- 3. Percent of Technical Specification Limit
- 4. Gross Alpha RadioactMty Cl D. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Reloaso Ci 1.64E42
. Averago roleaso rate for tho poriod uCI/sec 2.11E43 il:!II/!II"'";";I
. Percent of Technical Specification Limit 1.64E46 "i.I'age 17
1 t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVERELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 GASEOUS EFFLUENTS
SUMMARY
UNIT 4 TABLE 4 A. FISSION GASES NIICLIDES BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 CI 2.58E42 2.13E43 1.47E46 Ci CI 1.01E44 9.68E44 1.97E45 Xo-131m CI 1.85E44 5.13E44 9.05E45 3.91 E45 Xo-133 Ci 9.07E42 1.30E41 4.67E42 4.15E43 Xo-133m Ci 2.11E43 2.49E43 8.42E44 6.02E46 Xo-135 CI 9.33E43 2.76E42 3.43E43 1.16E-05 o-135m Ci TOTAL roR ffReo Ci 1.28E41 1.63E41 5.11E42 4.21E43 NUCLIDES CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 4 Ci Kr45 Ci Kr45m Ci Ci CI o-131m Ci CI o-133m CI o-135 Ci o-135m CI CI rarAL foR SSReo Ci B. IODINES NUCLIDES umrs CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 4 Br42 Ci 1-131 Ci 1-133 Ci TOTAL fOR PBUOO Cl C. PARTICULATES NUCLIDES usrs CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ci CI Mn44 Ci Cr41 CI TAL FOR PERIOO Ci Psge18
t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1996 THROUGH DECEMBER 1996 DOSES DUE TO IODINE,TRITIUNI,AND PARTICULATES UNIT 4 TABLE 5 PATHWAY BONE llYER THYROID KfONEY LUNG Gl.ill SKIN TOTAL BOOT Cow milk - Infant (mrem) O.OOE+00 1.23E<7 1.23E&7 5.41E~ 1.23E%7 1.23E-07 O.OOE+00 1.23E<7 Fruit & Veg Fresh (mrem O.OOE+00 1.28 MS 1.28E~ 8.47E~ 1.28E~ O.OOE+00 1.28E%8 Ground Plane (mrem) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Inhalation - Adult (mrem) O.OOE+00 5.56E~ 5.56E~ 5.56E~ 5.56E~ 5.56M% O.OOE+00 5.56E<8 TOTAL (mrem) O.OOE+00 1.92E<7 1.92E%7 1.18E%7 1.92M)7 1.92&)7 O.OOE+00 1.92E<7
% of Annual Limit O.OOE+00 1.28MS 1.28E~ 7.88E<7 1.28E~ O.OOE+00 1.28E46 DOSES DUE TO NOBLE GASES Y ol Aoooof Lloff Gamma Alr Dose 8.18E~ 8.18E~
Beta Air Dose 8.90E~ 4.45E~
page 19
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t TURKEY POINT UNITS 3 AND 4 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT o
JANUARY 1996 THROUGH DECEMBER 1996 DOSES DUE TO IODINE,TRITIUM, AND PARTICULATES r
Summation Table 5 PATHWAY BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY Cow milk - Infant O.OOE+00 1.23E47 1.23E47 5.41E48 1.23E47 1.23E47 O.OOE+00 1.23E47 Fruit 8 Vog Fresh O.OOE+00 1.28E4S 1.28E48 8.47E49 1.28E48 1.28E48 O.OOE+00 1.28E48 Ground Plane O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Inhalation - Adult O.OOE+00 5.56E48 5.56E48 S.56E48 5.56E48 5.S6E48 O.OOE+00 5.56E48 TOTAL (mrem) O.OOE+00 1.92E47 1.92E47 1.18E47 1.92E47 1.92E47 O.OOE+00 1.92E47
% of Annual Limit O.OOE+00 1.28E46 1.28E46 7.88E47 1.28E46 1.28E46 O.OOE+00 1.28E46 DOSES DUE TO NOBLE GASES II of Aoooof thit Gamma Air Doso 1.20E45 1.20E44 Beta Air Doso 1.61 E45 8.07E45 page 20
TURKEY POINT UNTTS 3 AND 4 ANNUAL RADIOACTIVE EPPLUENTS RELEASE REPORT TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFP SITE POR BURIAL OR DISPOSAL
- 1. TYPE OP WASTE UNITS 12 MONTH PERIOD ERROR a Spent resin, filters m 2.19 El sludge, evaporator bottoms Ci 1.25 BO 20 (Note 1)
Dry Compressible waste m 5.49E1 (Note 2) Ci 7.69 B-l 20 Irradiated components m 0.00 EO Control rods, etc. Ci 0.00 EO Other non-compressible m 1.77 Bl 20 Waste Ci 8.74 B-l
- 2. ESTIMATE OP MAJOR NUCLIDE COMPOSITION OF TYPE OP WASTE UNITS VALUE a ~ Ni-63 0 44 Co-60 ~o 38 Cs-137 4 Fe-55 0 3
Mn-54 2
- b. Cr-51 oz 0 26 Co-58 O~
0 17 Fe-55 O~
0 15 Co-60 O~
0 11 Zr-95 6 Ni-59 0
~o 6 Ni-63 ~O 0 5 Ni-95 ~O 0 5 Ba-140 ~O 0 3 Np-237 O~
0 2 Ce-144 O~
0 1 Cs-137 O~
0 1 Page 21
I' TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENTS RELEASE REPORT TABLE 6
- c. N/A UNITS VALUE
- d. Fe-55 60 H-3 18 Co-60 15 Ni-63 3 Zn-65 2 Ni-59 1 3 ~ SOLID WASTE DISPOSITION Number of shi ments Mode of trans ort Destination 3 (Note 3) Sole use truck Oak Ridge, TN 8 Sole use truck Barnwell, SC 1 (Note 3) Sole use truck Kingston, TN B. IRRADIATED FUEL SHIPMENTS None Page 22
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EPRLUENT RELEASE REPORT TABLE 6 SOLID WASTE SUPPLEMENT Wasto ClassiTication Ft'NOTE Total Volume Total Curio
- 4) (NOTE 5)
Principal Rad ionuclidcs (NOTE 6)
Type of Waste R.O. 121 Category (NOTE 7)
Type of Container Solidification of Absorbcrs Quantity Agent Chas A 1938.4 0.769 None Compactablc Strong Waste Tight NIA Chss A 652.2 1.24 None Dcwatcrcd Strong Resin Tight N/A Class A 123.2 2>270 None Dcwatcrcd Cask NIA Filters Chss A 420 .016 Noae Waste ld. Stroag N/A Oil Tight Chss A 205.8 None Noa-Compactible 1 d. N/A Waste Page 23
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TURKEY POINT UNITS 3 AHD 4 ANNUAL RADIOACTIVE EFFLUENTS RELEASE REPORT TABLE 6 Spent resin, filters, sludge, and evaporator bottoms. Volume indicates volume shipped to burial site thru waste processor.
Dry compressible waste volume indicates volume shipped to burial site following reduction by a waste processing facility was 192.8m'.
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. The material shipped to Kingston, Tennessee was waste oil, which was destroyed by burning.
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 (5/11/83) for these determinations.
The most frequently used techniques for determining the total activity in a package are the dose to curie method and interference 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.
The composition of radionuclides in the waste is determined by both on-site analysis for principle gamma emitters and periodic off-site analyses for difficultto 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 difficultto measure isotopes.
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 105CFR 61.55.
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".
Type of container refers to the transport package.
Page 24
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