View source for L-2007-054, Annual Radioactive Effluent Release Report for the Period January 1, 2006 Through December 31, 2006

{{Adams
| number = ML070920509
| issue date = 03/29/2007
| title = Annual Radioactive Effluent Release Report for the Period January 1, 2006 Through December 31, 2006
| author name = Jefferson W
| author affiliation = Florida Power &amp; Light Co
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000250, 05000251
| license number = 
| contact person = 
| case reference number = L-2007-054
| document type = Annual Report, Letter type:L
| page count = 27
}}

=Text=
{{#Wiki_filter:MAR 2 9 2007 L-2007-054 FPL                                                                10 CFR 50.36a(a)(2)
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-00001 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, 2006, through December 31, 2006, for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.1.4 and 10 CFR 50.36a (a)(2).
Should there be any questions or comments regarding this information, please contact James W. Connolly at (305) 246-6632.
Very truly yours, William Jefferson, Jr.
Vice President Turkey Point Nuclear Plant SM Attachment CC:      Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 4159~
an FPL Group company

Florida Power and Light Turkey Point Plant Units 3 and 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 2006 through December 2006 Submitted by:
NUCLEAR CHEMISTRY DEPARTMENT FLORIDA POWER AND LIGHT COMPANY P. E. Moe       Opemratry Supervisor W.Pell, Chemistry Supervisor
             *Molden, Operations Manager

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 Table of Contents 1.0  REGULATORY LIMITS ............................................................................................................                3 2.0  EFFLUENT CONCENTRATION ..................................................................................................                     4 3.0  AV ERA GE EN ER G Y ...................................................................................................................... 4 4.0  MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY ..................................                                                          4 5.0  BA T CH REL EA SE S ........................................................................................................................ 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 13.0 NEI's INDUSTRY INITIATIVE ON GROUND WATER SAMPLING ......................................                                                     9 UNIT 3 TABLES 1 THROUGH 5................................................................................ 10 UNIT 4 TABLES 1 THROUGH 5................................................................................ 15 SITE DOSE SUMMATION TABLE 5 ......................................................................... 20 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS TABLE 6 ...................................... 21 ATTACHMENT A, INFORMATION FOR INDUSTRY TRITIUM INIATIVE ...............................                                                           25 2

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 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 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.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, 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 1-131, 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 2006 THROUGH DECEMBER 2006 2.0  EFFLUENT 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 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 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 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, Ni-63, and Fe-55 by chemical separation.
4

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 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 2006 THROUGH DECEMBER 2006 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, b) 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 ona 50/50 basis to each unit.
Meteorological data for the period January 2006 through December 2006, 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 2006 THROUGH DECEMBER 2006 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                  MAXIMUM ERROR Liquid                             + 5.2%
* 13.0%
Gaseous                            + 3.7%
* 8.0%
5.0      BATCH RELEASES 5.1 LIQUID                                                            Unit 3     Unit 4 a)   Number of releases                                              8.55E+01    8.55E+01 b)   Total time period of batch releases, minutes                    7.52E+03    7.52E+03 c)   Maximum time period for a batch release, minutes                1.60E+02     1.60E+02 d)   Average time period for a batch release, minutes                8.91 E+O 1  8.91E+01 e)   Minimum time for a batch release, minutes                       2.50E+01    2.50E+01 f)   Average stream flow during period of release of effluent into a flowing stream, liters-per-minute                        4.77E+07    4.77E+07 5.1 GASEOUS                                                           Unit 3      Unit 4 a) Number of releases                                                1.75E+01    1.85E+01 b) Total time period of batch releases, minutes                      1.18E+03    1.64E+03 c) Maximum time period for a batch release, minutes                  2.40E+02    2.40E+02 d) Average time period for a batch release, minutes                  6.75E+01    8.87E+01 e) Minimum time for a batch release, minutes                         1.OOE+01    1.00E+01 7

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 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 1-131 were not exceeded.
7.2 Unit 4 Reactor coolant activity limits of 100/E-Bar and 1.0 uCi/gram Dose Equivalent 1-131 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:
Adult Inhalation          Child Inhalation Bone (mrem)                        O.OOE+00                   1.85E-13 Liver (mrem)                       1.36E-05                   9.5 1E-06 Thyroid (mrem)                     1.36E-05                   9.5 1E-06 Kidney (mrem)                      1.36E-05                   6.28E-06 Lung (mrem)                        1.36E-05                   9.53E-06 GI-LLI (mrem)                      1.36E-05                   9.52E-06 Total Body (mrem)                  1.36E-05                   9.5 1E-06 Gamma Air Dose (mrad)                   1.62E-05 Beta Air Dose (mrad)                    1.33E-05 8

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 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. One irradiated component, a core exit thermocouple, was shipped 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 the Radioactive Liquid Effluent Monitor (R-18) was out of service once where it exceeded the reporting threshold of 30 days (CR 2006-4100). The detector displayed a higher than expected background reading and during troubleshooting it was determined that the detector required replacement. An exact match for the detector was not readily available and procuring a new detector and radioactive -calibration sources delayed the return to service. The calibration procedure was also revised to ensure optimum and consistent performance. Compensatory sampling as stated in the ODCM was performed during the time the detector was out of service. A new detector was procured, calibrated and the monitor was returned to service. The monitor was out of service for 49 days.
13.0    NEI's INDUSTRY INITIATIVE ON GROUND WATER SAMPLING In 2006 as part of the Industry Initiative on Groundwater Sampling, 22 wells on the site and adjacent to the site were sampled for tritium. Tritium was detected in ten of the wells. The levels of tritium were from 3.60E-07 to 4.40E-06 micro curie per milliliter. Three of the wells, that had detectable tritium, were also analyzed for Ni63 and Fe55, and the results were less than minimum detectable activity. All results were less than the limits of the Offsite Dose Calculation Manual, Table 5.1-2, Reporting Levels for Radioactivity Concentrations in Environmental Samples. There were also no reportable spills of radioactive liquids during 2006 on the Turkey Point site. The results of the first set of well samples are included in Attachment A, Information for Industry Tritium Initiative.
9

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 LIQUID EFFLUENTS 

==SUMMARY==

UNIT 3I TABLE A. FISSION AND ACTIVATION PRODUCTS                                                                                                                                                          (%
Qtr3           Qtr 4     Est Error UNITS                       Qtr 1                   Qtr Qtr 2 I                      I 1.i1-2                                            Qtr 3
                                                                                                                                             .6E0      -.i 9.32E-03               3.44                    I t       Ci             I . . . E-02..
1.41                      8.43E-03           1.518E-03    I 6.92E-10   '''i''''i''                   il I __ . I                               -  2.61 E-1 1 I.2.Average   diluted concentration during the period Total Release (not including tritium,gases, alpha) 3.Percent of applicable limit I uCi/ml               t 8.86E-1 l . .- . T ..t I % i 4,83E-02 0
1 .28E-03      I   1.51E-09       5 56E-02   iiiiiiiiiiiiiit I'                                                                                                                                     ..                                . . T. . . . . . . . .         .I B. TRITIUM UNITS                      Qtr 1           I Qtr 2                     Qtr 3     I                                       %
6.90E+01 I 1.50E+02                    2.50                   I UNTSQr.            .Qr4..st.Err
: 1. Total Release                                                        Ci                 1.84E+02             II 5.07E01
    ,*Average diluted concentration during the period              Il                     r                 --                          I      .   . .
uCi/ml                1.15E-05 4I 1 .57E-07                        1 .07E-05 I4--
: 3. Pe-rcentof applicable limit"                             -. 4                        4-                                                               1.11E+00............1)iiiiiil I       %"*             I  1.15E+00
                                                                                               .....           . rI 1.57E-02
                                                                                                                            ...      . i  1 .07E+00.
* w w II I'                                                                                                                                                                                                       'l C. DISSOLVED AND ENTRAINED GASES Qtr 4    Est Error UNITS                      Qtr 1
* Qtr2                 Qtr 3     I          I Est. Error (%) I I
1.13E-03      F2.05E-05 L1. Total Release 2.Averaoe  diluted concentration dumnb the senod              It Ci uCi/ml 4.45E-04 2.79E-11 1.10E-03 3.42E-12          1.74E-10F       1.52E-12 iiiii!ii::ili::ili*:iii:*iiiiiill:
3.44 3.Pretof applicable limit                                 I       %              b 1.40E-05                     1.71E-06      1 8.69E-05          7.61E-07   li;iii!iii iii                      I D. GROSS ALPHA RADIOACTIVITY I UNITS I                       Otr 1                    Qtr2        I-Qtr3           I    Qtr4  I Est. Error (%))1 I1. Total Retease                                               I Cii                                --                      --..                   --      --
E. LIQUID VOLUMES IUNITS                        Qtrl            tQtr2               I       Qtr3      I Qtr4 lEst. Error 0/0 iI. Batch waste released, prior to dilution                          LITERS                  8.07E+05 I4.60E+05                           2.56E+05        6.76E+05             10.00 1
: 2. Continuous waste released, prior to dilution                     LITERS                            ........-                                                 -                                     i
: 3. Dilution water used durin period                                 LITERS                  1.59E+10                  3.23E+11           6.47E+09        1.35E+10                   ..
10

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 LIQUID EFFLUENTS 

==SUMMARY==

S TABLE UNIT 32 NUCLIDES            UNITS                                               BATCH MODE RELEASED                           Qtr I                      Qtr 2           [     Qtr 3                   Qtr 4 Fe-55                       Cl          1.27E-03                  6.58E-04               3.53E-03               1.54E-03 Ni-63                       Ci          8.39E-03                  3.86E-03               3.00E-03               3.58E-03 Sr-89                       Ci               ........
Sr-90                       Ci               ........
Na-24                       Ci               .........
Cr-51                       Ci                --                        ....                                    6.79E-05 Mn-54                       Cl          5.17E-04                  4.56E-05               5.OOE-05               3.38E-05 Co-57                       Ci          2.06E-05                  8.54E-06               1.70E-05               6.84E-06 Co-58                       Ci          1.98E-03                  2.63E-03               1.05E-03               2.53E-03 Fe-59                       Ci               ......                                                             5.75E-06 CO-60                       Ci          1.36E-03                  5.98E-04               9,1BE-04               7.05E-04 Zn-65                       Ci              -.-.....
Nb-95                       CI          6.01 E-06                      - -               2.29E-05               3.66E-06 Zr-95                       Ci              --......
Mo-99                       Ci          2.14E-06                        ......
Ru-106                      Ci               ....-.-.
   ,g-110m                    Ci          6.92E-05                  6.21 E-06              2.OOE-04               3.16E-05 Sn-113                       Ci               ...--...
Sn-1177m                     Ci              -                     2.*ioE-06                 --                      - -
Sb-124                       Ci              --                    5.35E-05              5.25E-06               3.73E-05 Sb-125                       Ci         4.29E-04                   5.67E-04              4.98E-04               4.69E-04 1-131                       Ci              ........
1-133                       Ci              ........
  -134                 J      Ci               ........
Cs-134                 I     Ci         5,53E-06                       - -               4.25E-05               3.30E-05 1-135                       Ci              - .......
Cs-137                       Ci         7.17E-05                   6.73E-06              4.54E-04               2.72E-04 La-140                       Ci                ........
Ce-141                       Ci              ........
Ce-14                        Ci              .........
W-187                        Ci               ........
Np-239                       Ci              ........
Te-129                       Ci              ........
[TOTAL FOR PERIOD      ]      Ci    [I1.41E-02                II    8.43E-03              9.78E-03         II    9.32E-03 LIQUID EFFLUENTS - DISSOLVED GAS 

==SUMMARY==

NUCLIDES            UNITS                                                BATCH MODE RELEASED                            Qtr 1                     Qtr 2                  Qtr 3                   Qtr 4 Ar-41                        Ci               ........
Kr-85m                       Cl              ........
Kr-85                        Ci         4.36E-04                   1.10E-03                  ....
Xe-131                      Ci               ........
Xe-133                      Ci          9.80E-06                       ....                                     2.05E-05 Xe-133m                     Ci              ........
Xe-135                      Ci              ........
Xe-138                      Ci              ........
rTOTAL FOR PERIOD           Ci    ]     4.45E-04                   1.10E-03          [   O.00E+00               2.05E-05 LIQUID EFFLUENTS - DOSE SUMMATION ge group: Teenager 1Location: Cooling Canal Shoreline Deposition                           Dose (mrem)                                % of Annual Limit TOTAL BODY                                    1.85E-04                                      6.17E-03 II

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 GASEOUS EFFLUENTS 

==SUMMARY==
[ UNIT 3 TABLE 3 A. FISSION AND ACTIVATION PRODUCTS
[ UNITS         Qtr 1           Qtr2            Qtr3          Qtr4    1 Est. Error(%)
: 1. Total Release                             1   Ci        3.62E-01        1.54E-03        2.20E-03      8.95E-03         2179
: 2. Average release rate for the period         uCi/sec    4.65E-02         1.95E-04        2.77E-04  L-1.15E-03
: 3. Percent of Technical Specification Limit  I   %        2.68E-11         1.25E-14        3.OOE-14      6.47E-14                   '1' B. IODINES
_ UNITS   [     Qtr 1           Qtr2            Qtr3   I      Qtr4      Est. Error (%)
: 1. Total Release                                 Ci           ......                                     1.13E-04         3.44
: 2. Average release rate for the period         uCi/sec        .....                                      1.42E-05
: 3. Percent of Technical Specification Limit       %                                    ..                 1.94E-02 C. PARTICULATES UNITS         Qtr 1       F   Qtr 2           Qtr 3         Qtr 4  I Est. Error (%)
: 1. Particulates with half-life >8 days            Ci       4.92E-06      T      ......                                     2.50
: 2. Average release rate for the period          uCi/sec    6.33E-07      T                j    - -
: 3. Percent of Technical Specification Limit       %             ......                                       --
: 4. Gross Alpha Radioactivity                      Ci            ..-      I      --
D. TRITIUM UNITS   J     Qtr 1      1    Qtr2        I   Qtr3   1      Qtr4   I Est. Error (%)
: 1. Total Release                                  Ci       1.74E+00            ......                              I       2.50
: 2. Average release rate for the period          uCi/sec    2.24E-01            .......
: 3. Percent of Technical Specification Limit       %        1.75E-04            .-              --
12

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 GASEOUS EFFLUENTS 

==SUMMARY==

UNIT 3i TABLE 4 A. FISSION GASES NUCLIDES          UN-T                                     BATCH MODE Ar-41 RELEASED Ci Qtr 1 2.00E-01 Qtr 2 3.92E-05, Qtr 3 1.19E-04 T    Qtr 4 Kr-85                   Ci                ......                                      I     --
Kr-85m                  Ci          1.05E-04         2.63E-06           6.89E-06            --
Xe-131m                 Ci          4.03E-04         2.46E-04           7.73E-06        3.89E-03 Xe-133                  Ci          1.53E-01         1.21 E-03          1.85E-03        4,87E-03 Xe-133m                 Ci          1.72E-03               --                    .      6.14E-06 Xe-135.                 Ci          4.18E-03         3.20E-05           1.73E-04        8.64E-06 Xe-1 35m                Ci          1.88E-03               ....                      t        .
TrOTAL FORPERIODI       Ci    j     3.60E-01       I 1.53E-03        -  2.16E-03. I 8.78E-03 NUCLIDES         UNITS                             CONTINUOUS MODE RELEASED                         Qtr 1        F    Qtr 2         1   Qtr 3           Qtr 4 At-41                    Ci               --                ......
Kr-85                   Ci                            .........
Kr-85m     .      ... Ci                                 -.                --            --
Kr-87                    Ci               ........
Kr-88                    Ci               --                ......
Xe-131m                  Ci               ........
Xe-133                   Ci               .......                                           --
Xe-133m                  Ci               .....                                  ...
e-135                 Ci                ........
e-135m                Ci                ........
Xe-138                  Ci                ........
[TOTAL FOR PERIODI       Ci      I         ""               --         L       --       I    -"
B. IODINES NUCLIDES         UNITS                            CONTINUOUS MODE RELEASED   jQtr                          1        Qtr 2              Qtr 3           Qtr 4 Br-82                   Ci               ....                         i      --          1.13E-04 1-131                   Ci                 ....                       I       ""
1-133                   Ci               --                --                --...
1TOTAL FOR PERIODI       Ci     i         --        I      --          I      --          1.13E-04 C. PARTICULATES NUCLIDES         UNITS                            CONTINUOUS MODE RELEASED                          Qtr 1       {    Qtr 2              Qtr 3           Qtr 4 Co-58              _       _Ci      4.92E-06               ......
Co-60            I      Ci Mn-54                   Ci              ........
Cr-51             L      Ci              ......                                       I      --
[TOTAL FOR PERIODI        Ci          4.92E-06              "           -     -        -       -
13

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 DOSES DUE TO IODINE, TRITIUM, AND PARTICULA TES TABLE S PATHWAY                BONE        LIVER          THYROID     KIDNEY      LUNG         GI-LLI     SKiN   TOTAL BODY Cow milk - Infant (mrem)          --      1.31E-05    I    1.31E-05    5.75E-06   1.31E-05 [  1.31E-05  I     --    1.31E-05 Fruit &Veg Fresh (nrem)           -       1.37E-06         137E-06     9.02E-07   1.37E-06  j 1.37E-06         -    1.37E-06 Ground Plane (torem)           2.97E-08   2.97E-08          2.97E-08    2.97E-O8   8 2.97E-    2.97E-08    3.4E-08   2.97E-08 Inhalation - Adult (mrem)          --     5.92E-06          5.92E-06    5.92E-06   5.93E-06    5.92E-06        -     5.92E-06 TOTAL (mram)           2.97E-08   2.04E-05          2.04E-05    1.26E-05   2.04E-05    2.04E-05      4       2.04E-05
      % of Annual Limit        l.98E-D7    136E-04          1.36E-04    8.40E-05   1.36E-04    1.36E-04    2.32EL-1.36E-04 DOSE DUE TO NOBLE GASES I   mrad   % of Annual ULmit Gamma Air Dose                 3.50E-05   3.50E-04 Beta Airose        *1.51E-05              7.54E-05 14

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 LIQUID EFFLUENTS 

==SUMMARY==

UNIT 4]
TABLE 1 A. FISSION AND ACTIVATION PRODUCTS I  UNITS    I     Qtr 1   i     Qtr2    !    Otr 3      Qtr 4    1 Est. Error(%)
11.Total Release (not including tritium,gases, alpha)         Ci        1.41 E-02    8.43E-03      9.78E-03  9.32E-03    I       3.44 12.Average diluted concentration during the period          uCi/ml      8.86E-10      2.615-11   f  1.515-09  6.92E-10 13.Percent of applicable  limit                                %        4.83E-02      1.285E-03     1.51E-01  5.56E-02     I B. TRITIUM
_    UNITS          Qtr 1i       Qtr 2         Qtr 3      Qtr 4       Est. Error(%)
1.Total Release                                              Ci        1.84E+02     5.07E+01      6.90E+01  1.50E+02             2.50 2.Average diluted concentration during the period         ui/m~l      1.15E-05      1.57E-07      1.07E-05  1.11 E-05 3.Percent of applicable limit                                %        1.15E+00      1.57E-02     1.07E+00  1.11 E+00
{
C. DISSOLVED AND ENTRAINED GASES UNITS          atr 1   !    Qtr 2         Qtr 3     Qtr 4       Est. Error (%)
: 1. Total Release                                              Ci        4.45E-04      1.10E-03      1.13E-03 2.05E-05             344
: 2. Average diluted concentration during the period          uCi/ml      2.79E-11      3.42E-12      1.74E-10  1.52E-12__'
: 3. Percent of applicable limit                                %         1.40E-05      1.71E-06     8.69E-05  7.61 E-07 D. GROSS ALPHA RADIOACTIVITY I UNITSc  i       Qtr.1        Qtr.2   I     Qtr.3     Qtr.4     I Est. Error(%)"]
Il. Total Release                                              Ci            -             ----
E. LIQUID VOLUMES Otr 1         Qtr 2         Qtr 3     Qtr 4     ; Est. Error(%)
: 1. Batch waste released, prior to dilution                 LITERS      8.07E+05      4.60E+05      2.56E+05  6.76E+05            10.00     1
: 2. Continuous waste released, prior to dilution            LITERS           .--
13.Dilution water used during period        ,               LITERS      1.59E+10      3.23E+1 1     6.47E+09  1.35E+100     ........
15

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 LIQUID EFFLUENTS 

==SUMMARY==

UNIT 4 TABLE 2 NUCLIDES            UNITS                                                  BATCH MODE RELEASED                             Q___
tr1                       Qtr 2                          Qtr 3                      Qtr4 Fe-55                      Ci           1.27E-03           j        6.58E-04                       3.53E-03                  1.54E-03 Ni-63                      Ci           8.39E-03           J        3.86E-03                       3.OOE-03                  3.58E-03 Sr-89                      Ci               --                          --......
Sr-90                     Ci                 ....
Na-24                      Ci                ....
Cr-51                      Ci                .                                                                               6.79E-05 Mn-54                      Ci           5.17E-04                    4.56E-05           I           5.O0E-05                  3.38E-05 Co-57                 I    Ci           2.06E-05                    8.54E-06                       1.70E-05                  6.84E-06 Co-58                f     Ci           1.98E-03           1        2.63E-03                       1.05E-03                  2.53E-03 Fe-59                      Ci               --              I           --               I              --            I      5.75E-06 Co-60                ]     Ci           1.36E-03                    5.98E-04       -        -      9.18E-04                  7.05E-04 Zn-65                      Ci               --                                                           --                 __"-       _- _
Nb-95                      Ci           6.01E-06              __         -- _                      2.29E-05                  3.66E-06 Zr-95                       Ci               --              I                        -- i. ..        .-
Mo-99                      Ci           2.14E-06__-                                                     --...
Ru-lOB6               I                     --                           -.                                                       --
Ag-110m                     Ci           6.92E-05                    6.21E-06                       2.O0E-04                  3.16E-05 Sn-113                     Ci                --              -             I                            __            I           --
Sn-117m                    Ci               --                      2.10E-06                                                       -_-
Sb-124                     Ci               - -                     5.35E-05                       5.25E-06                  3.73E-05 Sb-125                I    Ci           4.29E-04                    5.67E-04                       4.98E-04                  4.69E-04 1-131                      Ci                ........
1-133                1     Ci                ....                                        I              ....
1-134                      Ci                ...                                                          - ..
Cs-1 34                    Ci           5.53E-06                         -                         4.25E-05                  3.30E-05 1-135                      ci    I           ....                                        I              --            I           --
Cs-137                I    Ci           7.17E-05      ___  1        6.73E-06            j          4.54E-04                  2.72E-04 La-140                [    Ci,   1...                                                                   --                        --
Ce-141                     Ci    1           ..                                          l-             --                        --
Ce-144                     Ci   _l           ....                        -                              --
W-187                      Ci                ....                                        I               ....
Np-239                     Ci                ....-                                                                     I Te-129                     Ci               --.--                                                                     I            --
[TOTAL FOR PERIOD      -     Ci         i 1.41E-02                    8.43E-03                       9.78E-03                  9.32E-03 LIQUID EFFLUENTS - DISSOLVED GAS 

==SUMMARY==

NUCLIDES            UNITS                                                  BATCH MODE RELEASED                             Qtr I                       Qtr2                              tr 3                    Qtr 4 Ar-41                      Ci       _    _  --              !            --                             --                          -      _
Kr-85m                     Ci                --                          --                             --
Kr-85                 I    Ci           4.36E-04                 I1.10E-03                         1.13E-03           I           --
Xe-131                     Ci                --            1             --              L               ""           I            --
Xe-133                     Ci           9.80E-06                         --....                                              2.05E-05 Xe-133m              j     Ci                  "           j             ..                                                        --
Xe-135               j     Ci                --                                             __.._-
Xe-138                     Ci                --                          --
1TOTAL FOR PERIOD       I    Ci           4.45E-04                    11.10E-03            -         1.13E-03           i      2.05E-05 LIQUID EFFLUENTS - DOSE SUMMATION
 &#xfd;ge group: Teenager
[Location: Cooling Canal_____
[Shoreline Deposition              [                   Dose (mrem)                                              % of Annual Limit
[TOTAL BODY                                               1.85E-04                                                   6.17E-03 16

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 GASEOUS EFFLUENTS 

==SUMMARY==

UNIT 4 TABLE 3 A. FISSION AND ACTIVATION PRODUCTS F UNITS            Qtr 1               Qtr2        Qtr 3          I    Qtr4      ]   Est. Error (%)
[1. Average 3,Percent release rate for the period Total Release of Technical Specification Li-mit uCi/sec Ci 1.33E-02 1.04E-01 5.23E-1 3 1.95E-04 1.54E-03 1.25E-14 2.77E-04 2.20E-03 3.00E-14 j  9.41  E-02 7.32E-01 4.57E-1 1 2.79 B. IODINES F   UNITS          Qtr 1               Qtr 2       Qtr 3               Qtr4          Est. Error (%)
[1.Total Release                                       Ci    1          --                             -2.02E-04                           3.44
: 2. Average   release rate for the period           uCi/sec          --         f        --   1       - -           2.54E-05        ...........
: 3. Percent of Technical Specification Limit           %--                                --   -        I           3.47E-02 C. PARTICULATES UNITS
                                                       -           Qtr 1               Qtr2        Qtr 3          I    Qtr4          Est. Error (%)
: 1. Particulates with half-life >8 days                C2.            ...                           '                    -       "       . 2.50
: 2. Average release rate for the period             uCi/sec           ........                                                     .
: 3. Percent of Technical Specification Limit           %
Gross Alpha Radioactivity                         Ci             .                       I       -,                   ---
D. TRITIUM F    UNITS         Qtr 1               Qtr2        Qtr3                Qtr4          Est. Error (%)
I1. Total Release                                      Ci    -   6.99E-01                ....           -           2.26E+00   -           2.50
  -2.Average release rate for the period            uCi/sec      8.98E-02-1        -    -..             -            2.90E-01
: 3. Percent of Technical Specification Limit      __%_     _     5.25E-06       L.                      -            1.70E-05 17

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 GASEOUS EFFLUENTS 

==SUMMARY==

UNIT 4 TABLE 4 A. FISSION GASES NUCLIDES       UNITS                                      BATCH MODE RELEASED                    Qtr 1                  Qtr 2        I        Qtr 3            Qtr 4 Ar-41                 Ci        8.70E-06              3.92E-05               1.19E-04        1.60E-01 Kr-85                 Ci             ....                                        --        l      ..
Kr-85m_               Ci        2.58E-05              2.63E-06        J      6.89E-06        1.45E+00 Xe-131m               Ci     F  4.03E-04              2.46E-04        I      4.13E-05        3.72E-04 Xe-133                Ci        9.81E-02            i1.21E-03              i1.85E-03         11.35E-02 Xe-133m           I   Ci        1.72E-03         [--                             --              --
Xe-135                Ci        3.41E-03              3.20E-05               1.73E-04         1.48E-05 Xe-1 35m              ci     I       ....                             I          --        I     --
TOTAL FOR PERIOD1     Ci    ]   1.04E-01               1.53E-03              2.19E-03        1.62E+00 NUCLIDES       UNITS                               CONTINUOUS MODE RELEASED                    Qtr 1        I         Qtr 2       1         Qtr 3            Qtr 4 Ar-41             I   Ci            --      J             -          1-                           "-
Kr-85                 aCi   JI-                            ..                                    --
Kr-85m            I    Ci           --            --          -- i -                 -           --
Kr-87                  Ci           --     -               ....                           1      --
Kr-88                  Ci             --                  --                     --              -
Xe-131m                Ci           --                    --                     --       I      --
Xe-1 33                Ci           ....                                                            __-__-
Xe-1 33m               Ci            .... _!                                 --              - -
Xe-135                 Ci    I       ..                              --                    i     --
Xe-135m                Ci           --                    --                     --        I     --
Xe-138                 Ci           --         I          --                     --       -       --
TOTAL FOR PERIODI      Ci           --         I          --                     --              --
B. IODINES NUCLIDES      UNITS                                CONTINUOUS MODE RELEASED                    Qtr 1I                 Qtr 2                 Qtr 3      1     Qtr 4 Br-82                  Ci  -         .....                                                 I     --
1-131                  Ci            --                       ..      1                    I  1.51E-09 1-133               CIC-_i          --         I          --           ! _       --    _          --
TOTAL FOR PERIOD &#xfd;     Ci            ....                   I        - -           I          1.51E-09 C. PARTICULATES NUCLIDES       UNITS                               CONTINUOUS MODE RELEASED                    Qtr 1                  Qtr 2                 Qtr 3            Qtr 4 Co-58                  Ci    I      --         I          -        -     _       --     _         -
Co-60                  Ci    L      --                    --           !         --               --
Mn-54                  Ci           --        I           --          I          --               --
Cr-51                  ci           --        I            --         I          --       I       --
[TOTAL FOR PERIODI      Ci           --         I          --          T          --               --
18

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 DOSES DUE TO IODINE, TRITIUM, AND PARTICULATES UNIT 4 PATHWAY               BONE        LIVER          THYROID   I     KIDNEY     LUNG     GI-LLI      SKIN  TOTAL BODY Cow milk - Infant (mrem)    6.22E-1 1   2.22E-05         2.22E-05_j     9.75E-06   2.22E-05 2.22E-05       --    2.22E-05 Fruit & Veg Fresh (mrem)    2.98E-12    2.32E-06         2.32E-06       1.53E-06   2.32E-06 2.32E-06 F     --    2.32E-06 Ground Plane (mrem)         4.13E-13    4.13E-13         4.13E-13       4.13E-13   4.13E-13 4.13E-13   5.02E-13  4.13E-13 Inhalation - Adult (mrem)   1.21E-13     1.OOE-05        1.00E-05       1.00E-05 J 1.00E-05 1.00E-05       -_    1.00E-05 ITOTAL (mrem)                6.57E-11    3.46E-05         3.46E-05       2.13E-05   3.46E-05 3.46E-05   5.02E-13  3.46E-05
 %of Annual Limit          I 4.38E-10    2.30E-04         2.31 E-04      1.42E-04   2.30E-04 2.30E-04   3.35E-12  2.30E-04 DOSES DUE TO NOBLE GASES mrad   % of Annual Limit Gamma Air Dose              6.06E-05    6.06E-04 Beta Air Dose               6.37E-05    3.19E-04 19

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 DOSES DUE TO IODINE, TRITIUM, AND PARTICULATES Summation Table 5 PATHWAY         BONE         LIVER         THYROID      KIDNEY          LUNG       GI-LLI   SKIN          TOTAL BODY Cow milk- Infant    6.22E-11     3.53E-05        3.53E-05     1.55E-05      3.53E-05   3.53E-05      --           3.53E-05 Fruit & Veg Fresh   2.98E-12     3.68E-06        3.68E-06              ---------
                                                                 - E-0          6   3.68E-06       -3.68E-06 Ground Plane        2.97E-08     2.97E-08        2.97E-08    2.97E-08     I 2.97E-08   2.97E-08 3.48E-08          2.97E-08 IaiAl2--3                        1.59E0-05       1.59E-05 L   1.59E-05      1.60E-05 J 1.59E-05     --            1.59E     TOTAL (mrem)    2.98E-08     5.50E-05        5.50E-05    3.39E-05       5.50E-05   5.50E-05 3.48E-08          5.50E-05
  % of Annual Limit 1.99E-07     3.67E-04        3.67E-04    2.26E-04       3.67E-04   3.67E-04 2.32E-07          3.67E-04 DOSES DUE TO NOBLE GASES mrad  1% of Annual Limit Gamma Air Dose      9.56E-05     9.56E-04 Beta Air Dose       7.88E-05     3.94E-04 20

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 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,         m3                0.00 E +00 2.00 E+00 evaporator bottoms, etc.              Ci                0.00 E +00
: b. Dry compressible waste                m3                8.70 E+02  2.00 E+00 (Note 1)                              Ci                6.78 E+02
: c. Irradiated components,                m3                3.68 E+00  2.00 E+00 control rods, etc.                    Ci                3.38 E+00
: d. Other:                                m3                1.95 E+01  2.00 E+00 non-compressed                       Ci                 1.18 E-03
: 2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by type of waste)
: a.                              (none shipped)
: b. NUCLIDE                 UNITS                     VALUE Fe-55                                        7.74 E+01 Co-60                                        5.15 E+00 Ni-63                                         1.50 E+01 21

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 TABLE 6
: c. NUCLIDE            UNITS                     VALUE Cr-51                                    4.92 E+O1 Fe-55                                    3.88 E+O1 Co-60                                    8.82 E+00
: d. NUCLIDE            UNITS                    VALUE Co-60                                    7.84 E+01 Cs-137                                    2.16 E+O1
: 3. SOLID WASTE DISPOSITION (Note 2)
Number of Shipments    Mode of Transportation             Destination 1                 Sole use truck              Energy Solutions (Oak Ridge, Tn) 1                 Sole use truck            Studsvik (Erwin, Tn) 13                 Sole use truck            StudsvikiRACE LLC (Memphis, Tn)
B. IRRADIATED FUEL SHIPMENTS (Disposition)
None.
22

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 TABLE 6 SOLID WASTE SHIPMENTS Waste        Total Volume    (Note 3) Total       (Note 4)           (Note 5)    R.G. 1.21     (Note 6)
Classification    Cubic Feet          Curies          Principal       Type of Waste  Category  Type of Container Radionuclides Class A         3.14 E+04       6.78 E+00             None          Compressible     1.b     General Design Waste Class B         1.30 E+02       3.68 E+00             None           Core Exit       1.b.        Type B Thermocouples 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 2006 THROUGH DECEMBER 2006 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 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 61.55.
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

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 Attachment A Information for Industry Tritium Initiative 25

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2006 THROUGH DECEMBER 2006 Well ID            Locations               H3 (Spring 2006)       Notes
_Ci/ml PW- I            Near Unit 5                  <3.60E-07           n/a PW-3             Near Unit 5                  <3.60E-07           n/a PW-4             Near Unit 5                  <3.60E-07           n/a CD- 1             East of U4                  9.OOE-07            n/a CU- 1             East of U4                   5.80E-07           n/a PTPED-3             East of U4                  <3.60E-07           n/a PTPED-4             East of U4                  <3.60E-07           n/a PTPED-8            East of U4                   6.70E-07            n/a PTPED-9            East of U4                   5.1OE-07            n/a P-94-2            East of U4                   3.60E-07     Ni63, Fe55 <MDA P-94-3            East of U4                  <3.60E-07            n/a P-94-4            East of U4                   7.90E-07     Ni63, Fe55 <MDA STP-1 Bottom        West of Plant                 7.70E-07     Ni63, Fe55 <MDA STP-1 Top          West of Plant                 5.30E-07            n/a G-21 Bottom    West of Cooling Canals            <3.60E-07            n/a G-21 Top     West of Cooling Canals            <3.60E-07            n/a G-28 Bottom    West of Cooling Canals             5.60E-07            n/a G-28 Top     West of Cooling Canals            <3.60E-07            n/a L-3 Bottom    West of Cooling Canals             4.40E-06            n/a L-3 Top      West of Cooling Canals            <3.60E-07            n/a L-5 Bottom    West of Cooling Canals             3.80E-06            n/a L-5 Top      West of Cooling Canals            <3.60E-07            n/a OBS-1             Near Unit 5                 <3.60E-07            n/a Monitoring Well Northeast of Fossil Plant         <3.60E-07            n/a Fuel Oil 1 Monitoring Well Northeast of Fossil Plant         <3.60E-07            n/a Fuel Oil 2 Monitoring Well Northeast of Fossil Plant         <3.60E-07            n/a Fuel Oil 3 Monitoring Well Northeast of Fossil Plant         <3.60E-07            n/a Fuel Oil 4 26}}