L-2006-090, Annual Radioactive Effluent Release Report
| ML060940646 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/31/2006 |
| From: | Jones T Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2006-090 | |
| Download: ML060940646 (25) | |
Text
FPI.
MAR 3 1 2006 L-2006-090 10 CFR 50.36a(a)(2)
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Re:
Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Annual Radioactive Effluent Release Report Attached is the Radioactive Effluent Release Report for the period of January 1, 2005, through December 31, 2005, for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.1.4 and 10 CFR 50.36a (a)(2).
Shoulk there be any questions or comments regarding this information, please contact Walter Parker at (305) 246-6632.
Very tiuly your, Terry 0. Mn Vice President Turkey Point Nuclear Plant SM Attachment cc:
Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant
--- vq an FPL Gioup company
Florida Power and Light Turkey Point Plant Units 3 and 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 2005 through December 2005 Submitted by:
NUCLEAR CHEMISTRY DEPARTMENT FLORIDA POWER AND LIGHT COMPANY Kk~'6.Q3/cgy /o M. Navin, Operations Manager
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 Table of Contents 1.0 REGULATORY LIMITS..........................................................
3 2.0 EFFLUENT CONCENTRATION..........................................................
4 3.0 AVERAGEENERGY..........................................................
4 4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY..................
4...............
5.0 BATCH RELEASES.........................................................
7 6.0 UNPLANNED RELEASES..........................................................
8 7.0 REACTOR COOLANT ACTIVITY.......................................................... 8 8.0 SITE RADIATION DOSE..........................................................
8 9.0 OFFSITE DOSE CALCULATION MANUAL (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.........................
9 UNIT 3 TABLES 1 THROUGH 5......................................................
1 0 UNIT 4 TABLES 1 THROUGH 5......................................................
1 5 SITE DOSE SUMMATION TABLE 5 20 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS TABLE 6..............................
21 2
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 1.0 REGULATORY LIMITS 1.1 Liquid Effluent (a)
The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed ten times the concentration specified in 1 OCFR20 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.OE-04 micro-curies per milliliter total activity.
(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:
> 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 1-131, 1-133, trilium, 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 1-1 31, 1-133, 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.
3
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 2.0 EFFLUENT CONCENTRATION Watei-: In accordance with 1 OCFR20, Appendix B, Table 2, Column 2, and for entrained or dissolved noble gases as described in 1..a of this report.
Air Release concentrations are limited to dose rate limits described in 1.2 of this repori:.
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 activity' was detected on the samples using the Offsite Dose Calculation Manual (ODCM) analysis techniques to achieve the required Lower Limit of Detection
("LLD") sensitivity for radioactive effluents.
4.1 Liquid 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 determine if 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 accurnulation.
The monthly composite was analyzed for tritium and gross alpha radioactivity. Tritium was detennined 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, Ni-63, and Fe-55 by chemical separation.
4
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 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 spectral 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.
5
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 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 spectral analysis for fission and activation gases, 1,) Removal of particulate material by filtration and subsequent gamma spectral 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 gaseous 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 data using the current calibration curve for that process monitor. This method was not used this reporting period.
Both units share portions of the gaseous waste treatment system and generally all gaseous releases from the shared system are allocated on a 50/50 basis to each unit.
Meteorological data for the period January 2005 through December 2005, in the form of Joint Frequency Distribution Tables, are maintained on site.
6
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 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 Liquid Gaseous AVERAGE ERROR
+ 5.2%
+/- 3.7%
MAXIMUM ERROR
+/- 13.0%
i 8.0%
5.0 BATCH RELEASES 5.1 LIQUID Unit 3 Unit 4 a) Number of releases b) Total time period of batch releases, minutes c) Maximum time period for a batch release, minutes d) Average time period for a batch release, minutes e) Minimum time for a batch release, minutes f) Average stream flow during period of release of effluent into a flowing stream, liters-per-minute 7.55E+01 6.97E+03 1.20E+02 9.22E+01 4.OOE+01 7.55E+01 6.97E+03 1.20E+02 9.22E+O1 4.OOE+0 1 5.67E+06 5.67E+06 5.1 GASEOUS Unit 3 a) Number of releases b) Total time period of batch releases, minutes c) Maximum time period for a batch release, minutes d) Average time period for a batch release, minutes e) Minimum time for a batch release, minutes 1.60E+01 1.1OE+03 5.50E+01 3.40E+01 2.OOE+01 Unit 4 2.30E+01 2.78E+03 2.40E+02 7.1OE+0l 2.OOE+01 7
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 6.0 UNPLANNED RELEASES 6.1 Liquid There were no unplanned liquid releases this period for either Unit 3 or Unit 4.
6.2 Gaseous There were no unplanned gaseous releases this period for either Unit 3 or Unit 4.
7.0 REACTOR COOLANT ACTIVITY 7.1 Unit 3 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 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 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:
1 Adult Inhalation l
Child Inhalation Bone (mrem) 5.25E-14 9.48E-14 Liver (mrem) 3.71 E-06 2.61 E-06 Thyroid (mrem) 3.71 E-06 2.61 E-06 Kidney (mrem) 3.71 E-06 1.72E-06 Lung (mrem) 3.71 E-06 2.611E-06 GI-LLI (mrem) 3.71 E-06 2.61 E-06 Total Body (mrem) 3.71 E-06 2.61 E-06 Gamma Air Dose (mrad) 1.69E-06 Beta Air Dose (mrad) 1.1 8E-06 8
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 9.0 OFFSITE DOSE CALCULATION MANUAL (ODCM) REVISIONS The ODCM was reviewed, but not revised during this reporting period.
10.0 SOLID WASTE AND IRRADIATED FUEL 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 There were no revisions to the Process Control Program during this reporting period.
12.0 INOPERABLE EFFLUENT MONITORING INSTRUMENTATION During this period it was discovered that sample tubing used for collection of particulates from the Plant Vent Stack did not meet isokinetic sample requirements of ANSI N13.1-1969.
This was due to a 90 elbow in the sample tubing (CR 2005-11953). This condition was corrected in October 2005. The continuous monitoring of particulates was also interrupted for approx imately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> due to isolation of the monitor for leak testing (CR 2005-22700). There is only a single monitoring pathway which had to be isolated for this test. The monitor was restored when the conditions were noted and alternate means to collect samples was implemented. Actions to correct this condition and prevent reoccurrence were documented in the plants corrective action program.
9
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 LIQUID EFFLUENTS
SUMMARY
[-UNT3 -
TABLE 1 A. FISSION AND ACTIVATION PRODUCTS I UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4.
Est. _rror (%)
1.TotalReleas3(notincludingtritium,gases.alpha)
Ci 1.59E-02 2.54E-02 2.58E-03 3.28E-03 3.44
- 2. Averagedilutedconcentrationduringtheperiod uCi/il 1.31E-09 1.74E-09 7.14E-10 3.56E-1 3.Percentof applicablelimit 1.10E-01 7.67E-02 3.22E-02 4.07E-02 B. TRITIUM l UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error
[. Total Release Ci 9.65E+01 6.45E+01 1.16E+01 1.18E+02 2.50
- 2. Average diluted concentration during the period uCi/ml 7.92E-06 4.43E-06 3.21 E-06 1.28E-05......
- 3. Percentofarpplicablelimit 7.92E-01 4.43E-01 3.21E-01 1.28E+00 C.
DISSOLVED AND ENTRAINED GASES l UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1.Tota ReleasB Ci 7.40E-04 2.80E-03 4.31E-04 3.44
- 2. Average dilued concentration during the period uCiiml 6.08E-1 1 1.93E-10 4.68E-11
- 3. Percent of applicable limit 3.04E-05 9.63E-05 2.34E-05 D. GROSS ALPHA RADIOACTIVITY I UNITS Qtr1 Qtr2 Qtr3 Qtr4 l Est. _rror(%
Total Release Ci E. LIQUID VOLUMES I UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
1.Batch wa.te released, prior to dilution LITERS 5.91E+05 7.58E+05 1.47E+05 4.59E+05 0.00
- 2. Continutot.s waste released, prior to dilution LITERS
- 3. Dilution water used duringperiod LITERS 1.22E+10 1.46E+i0 3.61E+09 9.21E+09 10
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 LIQUID EFFLUENTS
SUMMARY
UNIT 3 TABLE 2 NUCLIDES UNITS BATCH MODE RELEASED Qtr 1 I
Qtr 2 I
Qtr 3 O
Qtr 4 Fe-55 Ci 1.96E-03 3.46E-03 2.05E-04 j
Ni-63 Ci 5.64E-03 6.05E-03 1.42E-03 1.65E-03 Sr-89 Ci i
Sr-90 Ci l
Na-24 Ci 1.78E-06 Cr-51 Ci 3.44E-05 5.12E-04 Mn-54 Ci 3.62E-04 1.06E-03 3.50E-05 5.95E-05 Co-57 Ci 6.35E-05 5.09E-05 4.97E-06 8.55E-07 Co-58 Ci 2.72E-03 9.43E-03 5.36E-04 3.83E-04 Fe-59 Ci 1.40E-04 Co-60 Ci 2.07E-03 9.69E-04 1.83E-04 2.73E-04 Zn-65 Ci 2.18E-05 Nb-95 Ci 5.25E-05 3.41E-06 l
Zr-95 Ci Mo-99 Ci i
Ru-106 Ci Aq-11 0 Ci 1.79E-04 5.64E-05 Sn-113 Ci 8.1OE-06 l
Sn-117m Ci 1.47E-05 3.57E-06 iSb-124 Ci 3.87E-05 i
2.19E-04 1.67E-06 5.40E-07 Sb-125 Ci 2.46E-03 3.34E-03 1.93E-04 6.85E-04 i-131 1
Ci L
6.34E-06 1-133 I
Ci I
I
-134 j
Ci l
Cs-134 Ci 5.97E-05 i
2.23E-05
-135 j
Ci j
Cs-137 I
Ci 2.40E-04 i
1.35E-05 4.38E-06 1.98E-04 La-140 j
Ci i
Ce-141 1
Ci 9.35E-07 l
l Ce-144 Ci W-187 Ci Np-239 Ci Te-129 Ci
=
Be-7 Ci 2.64E-05 l
I 1-132 Ci 1.26E-06 l
Sr-91 j
Ci 3.78E-06 Te-132
[
Ci 3.01E-06 Ba-140 Ci 3.23E-06 i
Br-82 I
Ci 1.02E-06 lTOTAL FOR PERIOD I Ci I
1.59E-02 I
2.54E-02
][
2.58E-03 li 3.28E-03 l
LIQUID EFFLUENTS - DISSOLVED GAS
SUMMARY
NUCLIDES UNITS BATCH MODE RELEASED Otr I Otr 2 O
Otr 3 i
Qtr 4 Ar-41 Ci Kr-85m Ci Kr-85 Ci 7.20E-04 2.79E-03 4.31E-04 Xe-131 Ci Xe-133 Ci 2.02E-05 1.11E-05 Xe-133m Ci Xe-135 Ci Xe-138 Ci I
TOTAL FOR PERIOD I Ci I
7.40E-04 1
2.80E-03 I
0.00E+00 1
4.31 E-04 LIQUID EFFLUENTS - DOSE SUMMATION
[lge group: Teenager ILocation : Cooling Canal li Shoreline Deposition Dose (mrem) l
% of Annual Limit I
TOTAL BODY 2.01 E-04 6.70E-03 I I
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 GASEOUS EFFLUENTS
SUMMARY
UNIT 3 ITABLE 3 A. FISSION AND ACTIVATION PRODUCTS I
UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
[1.
Total Release Ci 1.88E-02 6.36E-02 3.11E-03 2.70E-03 2.79
- 2. Average release rate for the period uCi/sec 2.42E-03 8.1OE-03 3.91E-04 3.47E-04 3.Percent of Technical Specification Limit 5.29E214 2.49E-13 1.05E-14 1.16E-14..
B. IODINES l
UNITS Qtr 1 Qtr 2 Qtr 3 QIr 4 Est. Error (%)
- 1. Total Release Ci 3.44
- 2. Average release rate for the period uCilsec -
.. ii
- 3. Percent of Te;hnical Specification LImit C. PARTICULATES I UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Particulates with half-life >8 days Ci 2.50
- 2. Average release rate for the period uCi/sec
- 3. Percent of Technical Specification Limit Gross Alpha Radioactivity Ci D. TRITIUM l
UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release Ci 5.93E-01 2.50
- 2. Average release rate for the period uCi/sec 7.46E-02
- 3. Percent of Technical Specification Limit 4.46E-06 12
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 GASEOUS EFFLUENTS
SUMMARY
UNIT 3 1
TABLE 4 I
A. FISSION GASES NUCLIDES UNITS l
BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci 3.48E-09 2.45E-07 Kr-85 Ci 6.98E-03 6.15E-03 6.61E-04 Kr-85m Ci 6.70E-08 7.50E-07 Xe-1 31 m Ci 1.64E-04 4.37E-04 Xe-133 Ci 1.17E-02 5.64E-02 2.37E-03 2.69E-03 Xe-133m Ci 1.89E-05 5.97E-04 3.21E-06 Xe-135 Ci 2.26E-05 6.95E-05 1.38E-10 1.12E-09 Xe-1 35m Ci ITOTAL FOR PERIOD Ci 1.88E-02 6.36E-02 3.03E-03 2.70E-03 l
NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-131m Ci Xe-133 Ci Xe-133m Ci Xe-135 Ci Xe-1 35m Ci Xe-1 38 Ci
[TOTAL FOR PERIOD Ci B. IODINES NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Br-82 Ci 1-131 Ci 1-133 Ci lTOTAL FOR PERIOD Ci C. PARTICULATES NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Co-58 Ci Co-60 Ci Mn-54 Ci Cr-51 Ci
[TOTAL FOR PERIOD Ci 11 13
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 DOSES DUE TO IODINETRITIUM, AND PARTICULATES l UNIT 3 l
TABLE 5 IZ THVIAY BONE LIVER THYROID KIDNEY LUNG Gl-LLI SKIN T.AODr r-cowmi k-gnant(mrem) 0.OOE+OO 4.46E-06 4.46E-06 1.96E-06 4.46E-06 4.46E-06
.3.46E-06 Fruit & Veg Fresl_(mrem)
I 0.OOE+00 4.64E-07 4.64E-07 3.06E-07 4.64E-07 4.64E-07 4.64E-07 Ground Plane (m em)
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 lInhalation-Adult(mrem)
I 0.00E+00 2.01E-06 2.01E406 2.01E-06 2.01E-06 2.01E-06 2.01E-06 TOTAL (Inrem)
I O.OOE+0O I 6.93E-06 I
6.93E06 4.27E-06 I
6.93E-06 I
6.93E-06 I
O.OOE+00 Il.93E-06
% of Annu31 Limit I O.OOE+0O I 4.62E-05 I
4.62E-05 I
2.85E-05 I
4.62E-05 I
4.62E-05 I
O.OOE+00 I
41.62E-05 DOSE DUE 70 NOBLE GASES I
mrad
%of Annual Limit Gamm Air Do e l
-07 I
4.80E-06 BietaAirDose I
1[93E-06 I
9.65E-06 14
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 LIQUID EFFLUENTS
SUMMARY
UNIT 4 l
TABLE 1 A. FISSION AND ACTIVATION PRODUCTS Qtr Otr 4.
_Est
_. Ero.(..
I UNITS O
Qtr 1 Otr 2 Qtr3 Qtr 4
. Est. Error(%)
l1.TotalReleasr (not including tritiumgases, alpha)
Ci 1.59E-02 2.54E-02 2.58E-03 3.28E-03 1
- 12.
Average dilut 3d concentration during the period uCi/mI 1.31 E-09 1.74E-09 7.14E-10 3.56E-1_0
- 3. Percent of applicable limit 1.10E-01 7.67E-02 3.22E-02 4.07E-02 B. TRITIUM l
UNITS Qtr 1 Qtr2 Qtr3 Qtr4 E0t. Error(%)
l a1.
TOae ease Ci 9.65E+01 6.45E+01 1.16E+01 1.18E+02 2.50
- 2. Average dilut 3d concentration during the period uCi/mr 7.92E-06 4.43E-06 3.21 E-06 1.28E-05
- 3. Percentof applicable limit 7.92E-0l 4.43E-01 3.21E-01 1.28E+00.JJ C. DISSOLVED AND ENTRAINED GASES l
UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total ReleasE' Ci 7.40E-0-_
2.80E-03 4.31 E-04 3.44
- 2. Average diluted concentration during the period uCi/ml 6.08E-1 1 1.93E-1 0 4.68E-1 1
- 3. Percent of apolicable limit 3.04E-05 9.63E-05 2.34E-05 D. GROSS ALPHA RADIOACTIVITY l
UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
l1.Total ReleasE Ci E. LIQUID VOLUMES I
Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
1.Batch waste ieleased. prior to dilution LITERS 5.91 E+05 7.58E+05 1.47E+05 4.59E+05 10.00
- 2. Continuous waste released. prior to dilution LITERS 3 Dilution water used during period LITERS 1.22E+10 1.46E+10 3.61E+09 9.21E+09 15
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 LIQUID EFFLUENTS
SUMMARY
UNIT 4 l
TABLE 2 l
NUCLIDES UNITS I
BR RELEASED Qtr I Qtr 2 Fe-55 Ci 1.96E-03 3.46E-03 Ni-63 Ci 5.64E-03 6.05E-03 Sr-89 Ci ISr-90 Ci Na-24 Ci 1.78E-06 Cr-51 Ci 3.44E-05 5.12E-04 Mn-54 Ci 3.62E-04 1.06E-03 Co-57 Ci 6.35E-05 5.09E-05 Co-58 Ci 2.72E-03 9.43E-03 Fe-59 Ci 1.40E-04 Co-60 Ci 2.07E-03 5.69E-04 Zn-65 Ci 2.18E-05 kTCH MODE Qtr 3 Qtr 4 2.05E-04 1.42E-03 1.65E-03 3.50E-05 5.95 E.05 4.97E-06 8.55E-07 5.36E-04_
3.83E-04 1.83E-04 2.73E-04 Nb-95 Ci 5.25E-05 3.41 E-06----
Zr-95 Ci M o-99 Ci---
Ru-1 06 C i Ag-lI0 Ci 1.79E-04 E.64E-05 Sn-1 13 Ci 8I10E-06 Sn-1 17m Ci 1.47E-05 3.57E-06 Sb-124 Ci 3.87E-D5 2.19E-04 1.67E-06 5.40E-07 Sb-1l25 Ci 2.46E-0'3 3.34E-03 1.93E-04 6.85E-04 1-131 Ci 6.34E-06 1-133 C i-1-134 Ci Cs-1 34 Ci 5.97E-05
-2.23E-05 1-135 C
Cs-1 37 Ci 2.40E-04 1.35E-05 4.38E-06 1:98E.04 La-140 Ci Ce-141 Ci 9.35E Ce-1l44 C i W -187.
C i Np-239 Ci Te-1l29 C i--
Be-7 Ci
__2.64E-05------
1-132 Ci--
1.26E-06 Sr9 i--3.78E-06 -
Te-132 Ci 3.01 E-06 Ba-140 Ci 3.23E-06 Ci 1.02E
[TOTAL FOR PERIOD Ci I
1.59E-02 254E-02 2.58E-03 3.28E-03
]j LIQUID EFFLUENTS - DISSOLVED GAS
SUMMARY
NUCLIDES l
UNITS I
BATCH MODE RELEASED I
I Qtr 1 Qtr 2 Qtr 3 Qtr 4 I
Ar-41 Ci
- l Kr-85m Ci Kr-85 Ci 7.20E-04 2.79E-03 4.31E-04 Xe-131 Ci I
Xe-133 Ci 2.02E-05 1.11E-05 Xe-133m Ci Xe-135 Ci Xe-138 Ci lTOTAL FOR PERIOD Ci 7.40E-04 2.80E-03 4.31E-04_
LIQUID EFFLUENTS - DOSE SUMMATION egroup: Teenager lLocation: Cooling Canal lhoreline Deposition Dose (mrem)
% of Annual Limit lTOTAL BODY 2.01 E-04 6.70E-03 1 6
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 GASEOUS EFFLUENTS
SUMMARY
UNIT 4 )
I TABLE 3 A. FISSION AND ACTIVATION PRODUCTS I
UNITS Qtr 1 Qtr. 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release Ci 1.88E-02 1.17E-01 3.11E-03 2.70E-03 2.79
- 2. Average release rate for the period uCi/sec 2.42E-03 1.49E-02 3.91 E-04 3.47E-04
- 3. Percent of Te :hnical Specification Limit 5.29E-14 7.22E-12 1.05E-14 1.16E-14 B. IODINES l
UNITS Qtr I Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release Ci 7.73E-10 3.44
- 2. Average relea se rate for the period uCisec
-19.83E-11 j
- 3. Percent of Te:hnical Specification Limit 1.33E-07 C. PARTICUATES l
UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Particulates with half-life >8 days Ci 2.50
- 2. Average releE se rate for the period uCi/sec
- 3. Percent of Tezhnical Specification Limit
- 4. Gross Alpha Radioactivity Ci D. TRITIUM l
UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)
- 1. Total Release Ci 7.78E-02 6.17E-01 2.50
- 12.
Average relez se rate for the period_
uCi/sec 9.89E-03 7.76E-02 3. PQ 2
Q 3.
Err.. (E) 4 63E:::
[3. Percent of Te hnical Specification Limit 5.84E-07 4.63E-06
.J.
17
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 GASEOUS EFFLUENTS
SUMMARY
UNIT 4 LTABLE 4 A. FISSION GASES NUCLIDES UNITS I
BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci 3.48E-09 5.36E-02 Kr-85 Ci 6.98E-03 6.15E-03 6.61E-04 Kr-85m Ci 6.70E-08 7.50E-07 Xe-1 31 m Ci 1.64E-04 4.37E-04 7.67E-05 Xe-133 Ci 1.17E-02 5.64E-02 2.37E-03 2.69E-03 Xe-133m Ci 1.89E-05 5.97E-04 3.21E-06 Xe-135 Ci 2.26E-05 6.95E-05 1.38E-10 1.12E-09 Xe-1 35m Ci TOTALFORPERIOD Ci 1.88E-02 1.17E-01 3.11E-03 2.70E-03_l NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Otr 3 Qtr 4 Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-131 m Ci Xe-1 33 Ci Xe-1 33m Ci Xe-135 Ci Xe-1 35m Ci Xe-1 38 Ci TOTAL FOR PERIOD Ci B. IODINES NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Br-82 C-1-131 i
Ci 7.73E-10 1-133 Ci i
JTOTAL FOR PERIOD Ci 7.73E-10 C. PARTICULATES NUCLIDES l
UNITS l
CONTINUOUS MODE RELEASED Otr 1 Qtr 2 Qtr 3 Otr 4 Co-58 Ci Co-60 Ci Mn-54 Ci Cr-51 Ci
[TOTAL FOR PERIOD ci I8
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 DOSES DUE TO IOOINETRITIUM, AND PARTICULATES UNIT 4 l
TABLE 5 PATHWAY l
BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY Cow milk-Infant (mremn) 3.18E-11 5.22E-06 5.23E-06 2.29E-06 5.22E-06 5.22E-06 5.22E-06 Fruit & Veg Fresh (mr(.m) 1.52E-12 5.44E-07 5.44E-07 3.59E-07 5.44E-07 5.44E-07 5.44E-07 Ground Plane (mrem)
- 2. 11E-13 2.11E-13 2.1 1E-13 2.11E-13 2.11E-13 2.1 1E-13 2.57E-13 2.11E-13 Inhalation-Adult (mren) 6.17E-14 2.36E-06 2.36E-06 2.36E-06 2.36E-06 2.36E-06 2.36E-06 TOTAL(mrem)
=
3.36E-11 8.12E-06 8.13E-06 5.OOE-06 8.12E-06 8.12E-06 2.57E-13 l
8.12E-06 l%of Annual Limit I
2.24E-10 5.41E-05 5.42E-05 3.34E-05 5.41E-05 5.41E-05 1.71E-12 l5.41E-05[
DOSES DUE TO NOBLE GASES I
mrad I % of Annual Limit Iam Ai 9.50E-06 I
9.50E-05 Air os 5.04E-06 I
2.52E-05 19
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 DOSES DUE TO IODINE,TRITIUM, AND PARTICULATES
[TSmmtionl PATHWAY l
BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY Cow milk -Infant 3.18E-11 9.67E-06 9.68E-06 4.24E-06 9.67E-06 9.67E-06 9.67E-06 Fruit&Veg Fresh 1.52E-12 1.01E-06 1.01E-06 6.65E-07 1.01E-06 l.lE-06 1.01E-06 Ground Plane 2.11E-13 2.11E-13 2.11E-13 2.11E-13 2.11E-13 2.11E-13 2.57E-13 2.11E-13 Inhalation -Adult 6.17E-14 4.37E-06 4.37E-06 4.37E-06 4.37E-06 4.37E-06 4.37E-06 TOTAL (mrerr) 3.36E-11 1.50E-05 1.51 E-05 9.28E-06 1.50E-05 1.50E-05 2.57E-13 1.50E-05
% of Annual Limit 2.24E-10 1.00E-04 1.00E-04 6.18E-05 1.OOE-04 1.OOE-04 1.71E-12 1.00E-04 DOSES DUE TO NOBLE GASES I
mrad l % of Annual Limit Gamma Air Dose 9.98E-06 9.98E-05 Air Dose 6.97E-06 3.49E-05 20
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL
- 1.
TYPE OF WASTE UNITS 12 MONTH PERIOD
% ERROR
- a.
Spent resin, filters, sludge, evaporator bottoms, etc.
- b.
Dry compressible waste (Note 1)
- c.
Irradiated components, control rods, etc.
m3 Ci mn3 Ci m3 ci 5.30 E +00 8.53 E +01 5.61 E+02 1.13 E+02 (None shipped) 2.OOE +00 2.OOE+00
- d.
Other:
ron-compressed m3 Ci (None shipped)
- 2.
ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by type of waste)
- a.
NUCLIDE Mn-54 Fe-55 Co-60 Ni-63 Cs-137 UNITS VALUE 3.00 E+00 3.00 E+01 1.40 E+01 4.80 E+01 2.00 E+00
- b.
NUCLIDE Fe-55 Co-60 Ni-63 UNITS VALUE 5.17 E+01 1.22 E+01 3.35 E+01 21
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 TABLE 6
- c.
(None shipped)
- d.
(None shipped)
- 3.
SOLID WASTE DISPOSITION (Note 2)
Number of Shipments 153 15 Mode of Transportation Sole use truck Sole use truck Destination Envirocare (Clive, Utah)
Barnwell, (Barnwell, South Carolina)
B.
IRRADIATED FUEL SHIPMENTS (Disposition)
None.
22
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 TABLE 6 SOLID WASTE SHIPMENTS Waste Classification Class A Total Volume Cubic Feet 1.98 E+04 (Note 3) Total Curies 1.14 E+02 (Note 4)
Principal Radionuclides None (Note 5)
Type of Waste Compressible Waste R.G. 1.21 Category L.b (Note 6)
Type of Container General Design Class B 1.87 E+00 8.53 E+01 None Spent Resin 1.b.
Type B No solidification or absorbing agents were used or needed in the shipment of these waste types 23
TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2005 THROUGH DECEMBER 2005 TABLE 6 NOTE 1:
Dry compressible waste volume indicates volume shipped to a burial site following reduction by a waste processing facility.
NOTE 2:
Material transported to 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 or Clive Utah in accordance with the appropriate burial license activity limits. The material shipped directly to Barnwell was processed by CNSI / Duratek Inc. and buried.
NOTE 3:
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 quantitative 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 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.
The composition of radionuclides in the waste is determined by periodic off-site analysis for difficult to measure isotopes. Off-site analysis are used to establish scaling factors or other estimates for difficult to measure isotopes and principle Gamma emitters.
NOTE 4:
Principle radionuclide refers to those radionuclides contained in the waslte 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 61.55.
NOTE 5:
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 6:
Type of container refers to the transport package.
24