Text

Annual Radioactive Effluent Release Report for Period of January 1, 2007 Through December 31, 2007
	ML080940605
Person / Time
Site:	Turkey Point
Issue date:	03/20/2008
From:	Jefferson W; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2008-061
	Download: ML080940605 (66)
	v • d • e

MAR 2 0 2008 L-2008-061 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, 2007, through December 31, 2007, 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 Paul Infanger at (305) 246-6632.

Very truly yours, Vice President Turkey Point Nuclear Plant SM Attachment CC: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant an FPL Group company

Florida Power and Light Turkey Point Plant Units 3 and 4 E ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 2007 through December 2007 Submitted by:

NUCLEAR CHEMISTRY DEPARTMENT FLORIDA POWER AND LIGHT COMPANY P. y knethlsr Maae Michael Kiley, Plant G(eeneral Manager

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 Table of Contents 1.0 REGULATORY LIMITS ........................................................................................................... 3 2.0 EFFLUENT CONCENTRATION .................................................................................................. 4 3.0 AV E RA GE ENE RG Y ...................................................................................................................... 4 4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY .................................. 4 5.0 B AT C H REL E A 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, ODCM Revision ................................................................................ 25 2

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 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 2.0E-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.

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TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 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.

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TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 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.

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TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 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- 13 3 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 2007 through December 2007, in the form of Joint Frequency Distribution Tables, are maintained on site.

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TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 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 6.70E+01 6.70E+01 b) Total time period of batch releases, minutes 6.62E+03 6.62E+03 c) Maximum time period for a batch release, minutes 1.65E+02 1.65E+02 d) Average time period for a batch release, minutes 9.78E+O 1 9.78E+01 e) Minimum time for a batch release, minutes 2.80E+01 2.80E+01 f) Average stream flow during period of release of effluent into a flowing stream, liters-per-minute 4.84E+06 4.84E+06 5.1 GASEOUS Unit 3 Unit 4 a) Number of releases 1.70E+01 1.30E+01 b) Total time period of batch releases, minutes. 1.18E+03 8.72E+02 c) Maximum time period for a batch release, minutes 2.40E+02 2.40E+02 d) Average time period for a batch release, minutes 1.14E+02 5.40E+O1 e) Minimum time for a batch release, minutes 2.70E+01 2.70E+01 7

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 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) 6.70E- 10 1.21E-09 Liver (mrem) 5.24E-05 3.68E-05 Thyroid (mrem) 5.27E-05 3.72E-05 Kidney (mrem) 5.24E-05 2.43E-05 Lung (mrem) 5.24E-05 3.68E-05 GI-LLI (mrem) 5.24E-05 3.68E-05 Total Body (mrem) 5.24E-05 3.68E-05 Gamma Air Dose (mrad) 2.51E-05 Beta Air Dose (mrad) 5.35E-05 8

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 9.0 OFFSITE DOSE CALCULATION MANUAL (ODCM) REVISIONS The ODCM was reviewed, and the revision was implemented in June 2007. A summary of the changes is listed on Attachment A along with the pages of the ODCM that were revised.

10.0 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS No irradiated fuel shipments or irradiated component 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 There was no inoperable effluent monitoring instrumentation requiring reportability during this period.

13.0 NEI's INDUSTRY INITIATIVE ON GROUND WATER SAMPLING In 2007 as part of the Industry Initiative on Groundwater Sampling, a minimum of 10 wells on site and adjacent to the site were sampled for tritium. The tritium results were from 360 to 4350 Pico curie per liter. 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. The results are reported in the Annual Radiological Environmental Operating Report.

During this period there was a spill of approximately 10 gallons of radioactive water from the 3A Containment Spray Pump full flow test onto the ground outside the Auxiliary Building. This is inside the owner controlled area.

A sample of the water from the spill was obtained and analyzed for gamma emitting nuclides and tritium. The spill was estimated at 10gals and an investigation was performed to determine if the Limits of Section 5.0 of the ODCM (REMP) were exceeded. The water did not enter the storm drains or the canal system; and since the water did not reach Unrestricted Areas the limits of the REMP were not exceeded. No reporting was required; however, the NRC resident inspector was notified.

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TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 LIQUID EFFLUENTS

SUMMARY

UNIT 3 TABLE I A. FISSION AND ACTIVATION PRODUCTS

_ UNITS Qtr 1 Qtr2 Qtr 3 Qtr4 Est. Error(%)]

1. Total Release (not including tritium,gases, alpha) . Ci 5.79E-03 6.32E-03 1.16E-02 5.74E-03 3.44

2. Average diluted concentration during the period uCi/ml 8.80E-10 1.22E-09 8.18E-10 9.51 E-10 Percent of applicable limit % 5.02E-02 5.135-02 4.14E-02 5.21E-02 B. TRITIUM UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)]

1. Total Release 1 Ci 9.10E+01 1.27E+02 2.01E+02 8.52E+01 2.50

2. Average diluted concentration during the period j uCi/mI 1.38E-05 2.45E-05 1.41E-0511.41E-05

3. Percent of applicable limit % 1.38E+00 I 2.45E+00 1.41E+00 [ 1.41E+00 "

C. DISSOLVED AND ENTRAINED GASES______________

UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error(%)]

1. Total Release Ci 0.00E+00 0.OOE+00 8.58E-04 2.07E-03 . 44 2.Average diluted concentration during the period IuCi/mil 0.00E+00 0.OOE+00 F6.03E-11 3.43E-10 Percent of applicable limit % 0.00E+00 I 0.00E+00 3.02E-05 1.71E-04 D. GROSS ALPHA RADIOACTIVITY I UNITS Qtr 1 1 Qtr 2 Qtr 3 Qtr 4 I Est. Error (%)

.TotalRelease Ci ........

E. LIQUID VOLUMES UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Batch waste released, prior to dilution LITERS 3.07E+05 2.31E+05 6.67E+05 I_2.74E+05 10.00..

2. Continuous waste released, prior to dilution I LITERS ...... ..

3. Dilution water used during period LITERS 6.58E+09 5.19E+09 1.42E+10 6.04E+09 10

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 LIQUID EFFLUENTS

SUMMARY

UNIT 3 TABLE 2 NUCLIDES UNITS BATCH MODE RELEASED _Qtr 1 Qtr 2 1 Qtr 3 Qtr 4 Fe-55 Ci 2.10E-03 2.43E-03 1.94E-03 4.91 E-04 Ni-63 Ci 1.01E-03 1.84E-03 2.29E-03 6.91 E-04 Sr-89 Ci ......--

Sr-90 Ci ......

Na-24 Ci ........

Cr-51 Ci 1.54E-04 -- 4.74E-05 7.80E-05 Mn-54 Ci 2.48E-05 2.16E-05 1.43E-04 4.27E-05 Co-57 Ci 6.06E-06 2.50E-06 1.62E-05 4.87E-06 Co-58 Ci 1.70E-03 1.39E-03 6.39E-03 3.98E-03 Fe-59 Ci 5.39E-06 8.85E-05 1.85E-05 --

Co-60 Ci 3.20E-04 4.OOE-04 6.48E-04 2.84E-04 Z n-6 5 Ci . ..-- --

Nb-95 Ci 1.81E-05 2.73E-06 2.49E-06 1.61 E-06 Z r-95 Ci 2 .9 1E -06 . ...- -

Mo-99 Ci 1.35E-05 ......

Ru-106 Ci ........

Ag-110 Ci 5.33E-05 2.97E-05 1.44E-06 8.73E-06 Sn-113 Ci 1.40E-06 ......

Sn-1i17m Ci .... 6.90E-06 3.29E-05 Sb-124 Ci ...... 6.60E-06 Sb-125 Ci 3.02E-04 1.08E-04 1.20E-04 1.24E-04 1-131 Ci . .. .. .. .

1-133 Ci ......

1-134 Ci ........

Cs-1 34 Ci 3.34E-06 ......

1-135 Ci ........

Cs-137 Ci 8.18E-05 2.38E-06 ....

La-140 Ci ........

Ce-141 Ci ......

Ce-144 Ci ......

W-187 Ci ......

Np-239 Ci ......

Te-129 Ci .. J

[TOTAL FOR PERIOD I Ci 1 5.795-03 II 6.32E-03 II 1.16E-02 II 5.74E-03 LIQUID EFFLUENTS - DISSOLVED GAS

SUMMARY

NUCLIDES UNITS BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci ........

Kr-85m Ci ........

Kr-85 Ci .... 8.58E-04 1.88E-03 Xe-131 Ci ......--

Xe -13 3 Ci . .. .. . 1.9 1E -0 4 Xe-133m Ci ......--

Xe-135 Ci ........

Xe-138 Ci ........

1TOTAL FOR PERIOD I Ci O.OOE+oo O.OOE+00 [ 8.58E-04 2.07E-03 LIQUID EFFLUENTS - DOSE SUMMATION Age group: Teenager Location: Cooling Canal Shoreline Deposition Dose (mrem) % of Annual Limit TOTAL BODY 8.40E-05 2.80E-03 II

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 GASEOUS EFFLUENTS

SUMMARY

UNITi 3 TABLE 3 A. FISSION AND ACTIVATION PRODUCTS

1. Total Release

_ UNITS Ci Qtr 1 1.14E-03 Qtr 2 5.23E-02 Qtr3 2.18E-01

[ Qtr4 5.87E+00 Est. Error(%)

2.79

2. Average release rate for the period uCi/sec 1.47E-04 6.66E-03 2.75E-02 7.55E-01

3. Percent of Technical Specification Limit % 4.87E-15 5.06E-12 2.02E-11 4.34E-111 B. IODINES

-UNITS Qtr 1 Qtr 2 Qtr 3 Qtr4 Est. Error(%)

1. Total Release I Ci .... 2.57E-05 -- 3.44

2. Average release rate for the period

3. P e rc e nt of T e c h n ic a l S p e c ific a t io n Lim it uCi/sec 3.24E-06 4 .43 E -0 3

__ _______ J C. PARTICULATES _________ __________ __________

UNITS Qtrl Qtr2 Qtr3 Qtr4 Est. Error(

1.iParticulates with half-life >8 days Ci -- 3. 3.9115-05 -- 2.50 ...

2. Average release rate for the period uCi/sec -- L -- 4.1E-06 --

3. Percent of Technical Specification Limit % .... 6.32E-07 -_-

Gross Alpha Radioactivity Ci ........- .....

D. TRITIUM UNITS Qtr 1 Qtr2 Qtr3 Qtr4 Est. Error

1. Total Release I Ci 2.96E-01 2.50E+00 7.19E+00 4.85E-01 1 2.50 Average release rate for the period uCi/sec 3.81E-02 { 3.18E-01 9.05E-01 6.24E-02 .

3. Percent of Technical Specification Limit % J 2.97E-05 1.88E-05 5.40E-05 I 3.64E-06 12

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 GASEOUS EFFLUENTS

SUMMARY

UNIT 3 TABLE 4 A. FISSION GASES NUCLIDES UNITS _ _BATCH MODE RELEASED _ Qtr 1 1 Qtr 2 Qtr 3 I Qtr 4 Ar-41 Ci -- 3.85E-02 1.54E-01 --

Kr-85 Ci -- --

Kr-85m Ci ....- -- J --

Xe-131m Ci 1.73E-05 2.04E-05 - - 7.93E-05 Xe-133 Ci 1.12E-03 1.38E-02 6.36E-02 4.72E-03 Xe-133m Ci -- I -- 5.56E-04 I 1.29E-05 Xe-1 35 Ci -- I -- 1.45E-04 2.51E-05 Xe-135m F Ci -- I -- ! -- L --

[TOTAL FOR PERIOD I Ci 1.14E-03 5.23E-02 2.18E-01 - 4.84E-03 NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Otr 2 Q - Qtr 3 - Qtr 4 Ar-41 Ci -- -- -- --

Kr-85 Ci -- - - I -- I --

Kr-85m Ci -- I -- . ...-

Kr-87 Ci ... . 1 ....

Kr-88 Ci .. -- F --

Xe-131m Ci .... - -- F -"

Xe-133 Ci .... I -- F 5.95E+00 Xe-133m Ci .... - -- F 2.36E+00 Xe-135 Ci .... ! -- F --

Xe-135m Ci .... - -- i1.95E-01 Xe-1 38 Ci .. --1 --

[TOTAL FOR PERIOD Ci --..- -- I 8.50E+00 B. IODINES NUCLIDES [ UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 I Qtr 3 Qtr 4 Br-82 ..- ICi 2.08E-05 --

1-131 Ci ...

- - 4.94E-06 --

1-133 Ci I .... --...

[TOTAL FOR PERIOD I Ci I -... 2.57E-05 --

C. PARTICULATES NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Co-58 Ci- - .

Co-60 Ci -- -- -

Mn-54 Ci -- I -- --... .

Cr-51 Ci -- I -- I ....

[TOTAL FOR PERIODI Ci -- -- I ....

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TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 DOSES DUE TO IODINE, TRITIUM, AND PARTICULA TES UNIT 35 TABLE 5 PATHWAY BONE LIVER THYROID KIDNEY LUNG I,-LLI SKIN TOTAL BODY Cow milk - Infant (mrem) 2.03E-07 7.89E-05 ] 1.57E-04 - 3.46E-05 _7.87E-05 7.87E-05 -- 7.88E-05 Fruit &Veg Fresh (mrem) 9.73E-09 8.21 E-06 1.14E-05 5.42E-06 8.20E-06 8.20E-06 -- 8.21 E-06 Ground Plane (mrem) 1.35E-09 1.35E-09 i 1.35E-09 1.35E-09 1.35E-09 1.35E-09 1.64E-09 1.35E-09.

Inhalation -Adult (mrem) 3.94E-10 I 3.55E-05 I 3.57E-05 [ 3.55E-05 3.55E-05 3.55E-05 -- ] 3.55E-05 TOTAL (mrem) 2.15E-07 1.23E-04 2.04E-04 7.55E-05 1.22E-04 1.22E-04 1.64E-09 1.23E-04

%of Annual Limit 1.43E-06 8.18E-04 1.36E-03 5.03E-04 8.16E-04 8.16E-04 1.09E-08 8.17E-04 DOSE DUE TO NOBLE GASES mrad J%of Annual Limit Gamma Air Dose 9.69E-05 9.69E-04 Beta Air Dose 1.94E-04 9.68E-04 14

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 LIQUID EFFLUENTS

SUMMARY

UNIT 4 TABLE 1 A. FISSION AND ACTIVATION PRODUCTS I UNITS Qtr 1 Qtr2 L Qtr3 Qtr4 Est. Error(%)

1. Total Release (not including tritium,gases, alpha) Ci 5.79E-03 6.32E-03 F 1.16E-02 5.74E-03 3.44

2. Average diluted concentration during the period 8.80E-10 1 1ui/ml

.22E-09 8.18E-1 0 9.51 E-100 ..

3. Percent of applicable limit I %__ 5.02E-02 f 5.13E-02 4.14E-02 5.21 E-02 B. TRITIUM F UNITS Qtrl Qtr2 Qtr3 Qtr4 Est. Error(%)

1. Total Release Ci 9.1OE+01 1.27E+02 2.01E+02 8.52E+01 2.50

2. Average diluted concentration during the period uCi/ml 1.38E-05 2.45E-05 1.41 E-05 1.41 E-05

3. Percent of applicable limit % 1.38E+00 2.45E+00 F 1.41E+00 1.41E+00 C. DISSOLVED AND ENTRAINED GASES F UNITS Qtr 1 Qtr2 I Qtr3 Qtr4 [ Est. Error (%)

1. Total Release Ci -- -- 8.58E-04 2.07E-03 3 .44

12. Average diluted concentration during the period uCi/ml -- I -- 6.03E-1 1 3.43E-10

3. Percent of applicable limit %- - -- 3.02E-05 1.71 E-04 D. GROSS ALPHA RADIOACTIVITY I UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)i Ill. Total Release Ci E. LIQUID VOLUMES E Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Batch waste released, prior to dilution LITERS 3.07E+05 2.31 E+05 6.67E+05 2.74E+05 10.00

2. Continuous waste released, prior to dilution LITERS -- -- I ... . ...

3. Dilution water used during period LITERS I 6.58E+09 I 5.19E+09 1.42E+10 6.04E+09 .

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TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 LIQUID EFFLUENTS

SUMMARY

UNIT 4 TABLE 2 NUCLIDES UNITS BATCH MODE RELEASED Qtr 1 Qtr 2 1 Qtr 3 Qtr 4 Fe-55 Ci 2.1OE-03 2.43E-03 J 1.94E-03 4.91E-04 Ni-63 Ci 1.01E-03 1.84E-03 2.29E-03 6.91E-04 Sr-89 Ci -- -- I -- I --

Sr-90 Ci I -- _ -- _ _ _--

Na-24 " Ci ...-- -- -"

Cr-51 Ci 1.54E-04 -- 1 4.74E-05 7.80E-05 Mn-54 Ci 2.48E-05 2.16E-05 1.43E-04 4.27E-05 Co-57 Ci 6.06E-06 2.50E-06 1.62E-05 4.87E-06 Co-58 Ci 1.70E-03 1.39E-03 6.39E-03 3.98E-03 Fe-59 Ci 5.39E-06 8.85E-05 1.85E-05 - -

Co-60 Ci 3.20E-04 4.OOE-04 1 6.48E-04 2.84E-04 Zn-65 Ci .... - -- 1 --

Nb-95 T Ci 1.81E-05 2.73E-06 . 2.49E-06 1.61E-06 Zr-95 Ci 2.91 E-06 - - I ..

Mo-99 Ci 1.35E-05 - - --

Ru-106 Ci ..... 1 --

Ag-110 Ci 5.33E-05 2.97E-05 1.44E-06 1 8.73E-06 Sn-113 Ci 1.40E-06 -- ! -- 1 --

Sn-117m Ci .... 6.90E-06 I 3.29E-05 Sb-124 Ci .... I -- I 6.60E-06 Sb-125 Ci 3.02E-04 1.08E-04 1.20E-04 1.24E-04 1-131 Ci ...... .- - -

1-133 Ci ....--

1-134 Ci ...... I --

Cs-134 Ci 3.34E-06 .... -

1-135 Ci ...... - --

Cs-137 Ci 8.18E-05 2.38E-06 -- - -

La-140 Ci .....

Ce-141 Ci - ....

Ce-144 j Ci I ......

W-187 ci I -- 1 -- --

Np-239 Ci I -- I "" _ --

Te-129 Ci -- -- I -- --

TOTAL FOR PERIOD Ci 5.79E-03 II 6.32E-03 1.16E-02 II 5.74E-03 LIQUID EFFLUENTS - DISSOLVED GAS

SUMMARY

NUCLIDES UNITS [ BATCH MODE RELEASED Qtr 1 Qtr 2 Qtr 3 Qtr 4 Ar-41 Ci .... ! " --

Kr-85m Ci .... - -- I --

Kr-85 Ci .... I 8.58E-04 1.88E-03 Xe-131 Ci .... 1 ....

Xe-133 Ci -- -- 1.91E-04 1.--

Xe-133m Ci .... I -- --

Xe-135 Ci -- -,- _ -- I --

Xe-138 Ci -- -- -- I --

FTOTAL FOR PERIOD I Ci I -- -- J 8.58E-04 I 2.07 E-03 LIQUID EFFLUENTS - DOSE SUMMATION Age group: Teenager Location : Cooling Canal Shoreline Deposition Dose (mrem) % of Annual Limit

[TOTAL BODY 8.40E-05 2.80E-03 16

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 GASEOUS EFFLUENTS

SUMMARY

UNIT 43 TA13LE 3 A. FISSION AND ACTIVATION PRODUCTS I UNITS Qtr 1 Qtr2 Qtr 3 Qtr4 Est. Error (%)

1. Total Release Ci 8.63E-03 4.42E-04 7.28E-02 6.OOE+00 2 .79

2. Average release rate for the period uCi/sec 1.11E-03 5.62E-05 L 9.16E-03 7.72E-01 ...............

3. Percent of Technical Specification Limit % 9.78E-13 i 1.85E-15 ! 4.92E-12 I 3.02E-11 ................

B. IODINES I UNITS Qtr 1 Qtr2 Qtr 3 Qtr4 Est. Error (%)

1. Total Release Ci ....

- 2.57E-05 - 3.44

2. Average release rate for the period uCi/sec .... 3.24E-06 _____. ........

3. Percent of Technical Specification Limit % .... 4.43E-03 -- -

C. PARTICULATES I UNITS Qtrl Qtr2 Qtr3 Qtr4 Est. Error(%)

1. Particulates with half-life >8 days Ci - - - - 3.91 E-05 - 2.50

2. Average release rate for the period uCi/sec -- -- 4.91 E-06 -..............

3. Percent of Technical Specification Limit 1 %__ .. I -- 6.32E-07 -

4. Gross Alpha Radioactivity I Ci -- i -- -- I - _______

D. TRITIUM F -UNITS Qtr 1 Qtr 2 Qtr 3 Qtr 4 Est. Error (%)

1. Total Release j Ci 3.16E-01 2.50E+00 3.16E+00 1.72E+00 2.50

2. Average release rate for the period uCi/sec 4.07E-02 3.18E-01 3.97E-01 2.21E-01 I

3. Percent of Technical Specification Limit % 2.38E-06 1.88E-05 2.37E-05 1.29E-05 17

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 GASEOUS EFFLUENTS

SUMMARY

UNIT 4 TABLE 4 A. FISSION GASES NUCLIDES UNITS BATCH MODE RELEASED Qtr1 I Qtr 2 Qtr 3 I Qtr 4 Ar-41 Ci 7.49E-03 - - 3.66E-02 - -

Kr-85 Ci -- I .... --

Kr-85m Ci --........

Xe-131m Ci 1.73E-05 I 2.04E-05 2.42E-04 7.93E-05 Xe-133 Ci 1.12E-03 I 4.21E-04 3.52E-02 4.72E-03 Xe-133m Ci --. . I 5.37E-04 1.29E-05 Xe-135 Ci .... - 1.45E-04 2.51 E-05 Xe-1 35m Ci -- -- -....

ITOTAL FOR PERIODI Ci 8.63E-03 - 4.42E-04 7.28E-02 1 4.84E-03 NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 I Qtr 3 Qtr 4 Ar-41 Ci . ... I Kr-85 Ci . .

Kr-85m Ci ..

Kr-87 Ci ....

Kr-88 Ci ..

Xe-131m Ci I .... -

Xe-133 Ci 5.80E+00 Xe-133m Ci I .... ..

Xe-135 Ci I ...... 1.95E-01 Xe-135m Ci -...... --

Xe-138 Ci I ...... - --

[TOTAL FOR PERIOD I Ci -- -- -- 6.OOE+00 B. IODINES NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr1 I Qtr 2 Qtr 3 I Qtr 4 Br-82 Ci -- [ -- 2.08E-05 --

1-131 Ci -- I -- 4.94E-06 --

1-133 Ci -- I -- I ....

ITOTAL FOR PERIOD1 Ci I - - - - 2.57E-05 I --

C. PARTICULATES NUCLIDES UNITS CONTINUOUS MODE RELEASED Qtr 1 Qtr 2 Otr 3 Q ( Qtr 4 Co-58 I c_ -- I -- I -- I --

Co-60 C i ........

Mn-54 Ci ........

Cr-51 Ci ...... I --

ITOTAL FOR PERIODI Ci -- -- -- --

18

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 DOSES DUE TO IODINE, TRITIUM, AND PARTICULATES UNIT 4 TABLE 5 PATHWAY BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY Cow milk - Infant (mrem) 2.03E-07 5.80E-05 1.36E-04 2.54E-05 5.78E-05 5.78E-05 -- 5.79E-05 Fruit & Veg Fresh (mrem) 9.73E-09 6.03E-06 9.26E-06 3.98E-06 6.02E-06 6.02E-06 -- 6.03E-06 Ground Plane (mrem) 1.35E-09 I 1.35E-09 1.35E-09 1.35E-09 1.35E-09 1.35E-09 1.64E-09 1.35E-09 Inhalation - Adult (mrem) 3.94E-10 I 2.61E-05 2.63E-05 2.61E-05 2.61E-05 2.61E-05 I -- 2.61E-05 TOTAL (mrem) 2.15E-07 9.01 E-05 1.71E-04 5.55E-05 8.99E-05 8.99E-05 1.64E-09 9.OOE-05

% of Annual Limit 1.43E-06 6.01 E-04 1.14E-03 3.70E-04 5.99E-04 5.99E-04 1.09E-08 6.OOE-04 DOSES DUE TO NOBLE GASES I mrad o% of Annual Limit GammaAirDose 5.16E-05 5.16E-04 Beta ArDose 1.23E-04 6.16E-04 19

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 DOSES DUE TO IODINE, TRITIUM, AND PARTICULATES Summation Table 5 PATHWAY BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY Cow milk - Infant 4.06E-07 1 1.37E-04 2.92E-04 6.OOE-05 I 1.36E-04 1.36E-04 -- 1.37E-04 Fruit & Veg Fresh 1.95E-08 1.42E-05 2.07E-05 9.40E-06 I 1.42E-05 1.42E-05 -- 1.42E-05 Ground Plane I 22.70E-09E 2.70E-09 2.70E-09 2.70E-09 I 2.70E-09 3.28E-09 2.70E-09 Inhalation -Adult I 7.88E-10 I 6.16E-05 6.20E-05 ] 6.16E-05 I 6.16E-05 I 6.16E-05 -- 6.16E-05 TOTAL (mrem) 4.29E-07 2.13E-04 3,75E-04 1.31 E-04 2.12E-04 2.12E-04 3.28E-09 2.13E-04

% of Annual Limit 2.86E-06 1.42E-03 2.50E-03 8.73E-04 1.42E-03 1.42E-03 2.19E-08 1.42E-03 DOSES DUE TO NOBLE GASES I mrad % of Annual Limit GammaAir Dose 1.49E-04 1.49E-03 Beta Air Dose 3.17E-04 1.58E-03 20

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 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 7.65 E +00 2.00 E+00 evaporator bottoms, etc. Ci 4.37 E +02 m3

b. Dry compressible waste 6.32 E+02 2.00 E+00 (Note 1) Ci 4.82 E+00 m3

c. Irradiated components, 0.00 E+00 2.00 E+00 control rods, etc. Ci 0.00 E+00 m3

d. Other: 2.83 E+01 2.00 E+00 non-compressed Ci 2.66 E-02

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by type of waste)

a. NUCLIDE UNITS VALUE Fe-55 12.42 Co-60 70.67 Cs-137 1.29

b. NUCLIDE UNITS VALUE Fe-55 77.85 Co-60 5.22 Ni-63 15.33 21

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 TABLE 6

c. NUCLIDE UNITS VALUE None shipped

d. NUCLIDE UNITS VALUE Co-60 5.37 Ni-63 % 16.23 Fe-55 % 77.93

3. SOLID WASTE DISPOSITION (Note 2)

Number of Shipments Mode of Transportation Destination 11 Sole use truck Energy Solutions (Oak Ridge, Tn)

Sole use truck Clive Disposal Facility (Bulk) Clive, Utah 3 Sole use truck Studsvik (Erwin, Tn) 1 Sole use truck Studsvik/RACE LLC (Memphis, Tn)

B. IRRADIATED FUEL SHIPMENTS (Disposition)

None.

22

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 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 2.3 E+04 4.84 E+00 None Compressible 1.b General Design Waste Class B 2.77 E+02 4.37 E+02 None Primary 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 2007 THROUGH DECEMBER 2007 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 analyses 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 61.5 5.

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 2007 THROUGH DECEMBER 2007 Attachment A ODCM Revision 25

TURKEY POINT UNITS 3 AND 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 2007 THROUGH DECEMBER 2007 Summary of Changes to the ODCM following the annual review:

1. Insert 1, page 1-4, change to Control 1.4, explains the addition of new section to the Annual Radioactive Effluent Release Report. This details information about the NEI Industry Initiative on Groundwater and what is to be reported in the Annual Radioactive Effluent Release Report (ARERR).

2. Insert 2, page 1-5, Information to be included in the Annual Radiological Environmental Operating Report (AREOR).

3. Insert 3, page 1-7, Definition of the Industry Initiative. (CR2006-17093, CA#1,2 and CR2006-17607 CA#1l1)

4. Insert 4, page 1-9, Definition of Sampling Evolution.

5. Insert 5, page 1-16, Adds a Reference Section to the ODCM

6. Typographic error correction page 2-14. Corrects the Figure referenced.

7. Insert 6, page 3-3. Adds a paragraph to Subsection C of Section 3, Radioactive Gaseous Effluents. This paragraph summarizes the change to Iodine and Particulate sampling of the SJAE pathway due to PTN-ENG-SENS-06-048, The Calculation Developing the Iodine and Particulate Activity Compensation Factors for the Steam Jet Air Ejector Vent Monitors. (CR2006-20742 CA#5)

8. Page 3-5, Typographical correction, missing subscript on equation.

9. Change numbering to actions on pages 3-11 and 3-12, to account for changes in Insert 7.

10. Insert 7, page 3-13, Clarifies actions and implements PTN-ENG-SENS-06-048, The Calculation Developing the Iodine and Particulate Activity Compensation Factors for the Steam Jet Air Ejector Vent Monitors. Adds Sampling Evolution to the actions as necessary to perform planned samples and not violate the continuous sampling expectation. This is in accordance with industry practice.

(CR2006-20742 CA#5)

11. On page 3-14, Eliminate Iodine and Particulate sampling in accordance with PTN-ENG-SENS 048, The Calculation Developing the Iodine and Particulate Activity Compensation Factors for the Steam Jet Air Ejector Vent Monitors. (CR2006-20742 CA#5)

12. Delete page 3-21, this table was added to the ODCM in previous revisions as a convenient location for a table describing the set points of effluent monitors, however non-effluent monitors were listed and this caused some confusion. The information is below the level of detail of the ODCM and is already included in plant procedures.

13. Page 3-28 adds notation to Table 3.2-1, Radioactive Gaseous Waste Sampling and Analysis Program to implement PTN-ENG-SENS-06-048, The Calculation Developing the Iodine and Particulate Activity Compensation Factors for the Steam Jet Air Ejector Vent Monitors. (CR2006-20742 CA#5)

14. Insert 8, page 3-31, the notes referenced in item number 11.

15. Insert 9, page 5-9, Change in wording to follow NUREG-1301. (CR2005-17141, CA#2)

16. Insert 10, page 5A-3, addition of a sample point into the Waterborne, Surface Water table.

17. Inserts a new Appendix to Section 5, Radiological Environmental Monitoring Program (REMP).

This Appendix implements the actions necessary for PTN to meet the requirements of the NEI Industry Initiative on Groundwater Sampling. (CR2006-17093, CA#1,2 and CR2006-17607 CA#11) Also includes recommendations from review by ANI.

26

OFFSITE DOSE CALCULATION MANUAL FOR GASEOUS AND LIQUID EFFLUENTS FROM THE TURKEY POINT PLANT UNITS 3 AND 4 REVISION 14 CHANGE DATED 6/4/07 Florida Power and Light Company

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL LIST OF EFFECTIVE PAGES Offsite Dose Calculation Manual Page Revision Date Page Revision Date Page Revision Date i 06/04/07 2-13 11/22/02 3-15 06/04/07 ii 06/04/07 2-14 06/04/07 3-16 06/04/07 iii 06/04/07 2-15 11/22/02 3-17 06/04/07 iv 06/04/07 2-16 11/22/02 3-18 06/04/07 v 11/22/02 2-17 11/22/02 3-19 06/04/07 vi 06/04/07 2-18 11/22/02 3-20 06/04/07 vii 11/22/02 2-19 11/22/02 3-21 06/04/07 viii 11/22/02 2-20 11/22/02 3-22 11/22/02 1-1 11/22/02 2-21 11/22/02 3-23 11/22/02 1-2 11/22/02 2-22 11/22/02 3-24 11/22/02 1-3 11/22/02 2-23 11/22/02 3-25 11/22/02 1-4 06/04/07 2-24 11/22/02 3-26 11/22/02 1-5 06/04/07 2-25 11/22/02 3-27 11/22/02 1-6 11/22/02 2-26 11/22/02 3-28 06/04/07 1-7 06/04/07 2-27 11/22/02 3-29 11/22/02 1-8 06/04/07 2-28 11/22/02 3-30 11/22/02 1-9 06/04/07 2-29 11/22/02 3-31 06/04/07 1-10 06/04/07 2-30 11/22/02 3-32 11/22/02 1-11 11/22/02 2-31 11/22/02 3-33 11/22/02 1-12 11/22/02 2-32 11/22/02 3-34 11/22/02 1-13 11/22/02 2-33 11/22/02 3-35 11/22/02 1-14 11/22/02 2-34 11/22/02 3-36 11/22/02 1-15 11/22/02 3-1 11/22/02 3-37 11/22/02 1-16 06/04/07 3-2 11/22/02 3-38 11/22/02 2-1 11/22/02 3-3 06/04/07 3-39 11/22/02 2-2 11/22/02 3-4 11/22/02 3-40 11/22/02 2-3 11/22/02 3-5 06/04/07 3-41 11/22/02 2-4 11/22/02 3-6 11/22/02 3-42 11/22/02 2-5 11/22/02 3-7 11/22/02 3-43 11/22/02 2-6 11/22/02 3-8 11/22/02 3-44 11/22/02 2-7 11/22/02 3-9 11/22/02 3-45 11/22/02 2-8 11/22/02 3-10 11/22/02 3-46 11/22/02 2-9 11/22/02 3-11 06/04/07 3-47 11/22/02 2-10 11/22/02 3-12 06/04/07 3-48 11/22/02 2-11 11/22/02 3-13 06/04/07 3-49 11/22/02 2-12 11/22/02 3-14 06/04/07 3-50 11/22/02 6/4/07 Rev 13

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL LIST OF EFFECTIVE PAGES Offsite Dose Calculation Manual Page Revision Date Page Revision Date Page Revision Date 3-51 11/22/02 5-13 11/22/02 3B-18 11/22/02 3-52 11/22/02 5 11/22/02 3B-19 11/22/02 3-53 11/22/02 5-15 11/22/02 3B-20 11/22/02 3-54 11/22/02 5-16 11/22/02 3B-21 11/22/02 3-55 11/22/02 5-17 11/22/02 3B-22 11/22/02 3-56 11/22/02 5-18 11/22/02 3B-23 11/22/02 3-57 11/22/02 5-19 11/22/02 3B-24 11/22/02 3-58 11/22/02 5-20 11/22/02 3B-25 11/22/02 3-59 11/22/02 5-21 11/22/02 3B-26 11/22/02 3-60 11/22/02 5-22 11/22/02 3B-27 11/22/02 3-61 11/22/02 5-23 11/22/02 3B-28 11/22/02 3-62 11/22/02 5-24 11/22/02 3B-29 11/22/02 3-63 11/22/02 2A-1 11/22/02 3B-30 11/22/02 3-64 11/22/02 2A2 11/22/02 3B-31 11/22/02 3-65 11/22/02 2A3 11/22/02 3B-32 11/22/02 3-67 11/22/02 2A-4 11/22/02 3B-33 11/22/02 3-68 11/22/02 3A-1 11/22/02 3B-34 11/22/02 3-69 11/22/02 3A-2 11/22/02 3B-35 11/22/02 3-70 11/22/02 3A-3 11/22/02 3B-36 11/22/02 4-1 11/22/02 3A-4 11/22/02 3B-37 11/22/02 4-2 11/22/02 3A-5 11/22/02 31B-38 11/22/02 4-3 11/22/02 3A-6 11/22/02 3B-39 11/22/02 4-4 11/22/02 3A-7 11/22/02 3B-40 11/22/02 4-5 11/22/02 3B-1 11/22/02 3B-41 11/22/02 4-6 11/22/02 3B-2 11/22/02 3B-42 11/22/02 4-7 11/22/02 3B-3 11/22/02 3B-43 11/22/02 4-8 11/22/02 3B-4 11/22/02 3B-44 11/22/02 4-9 11/22/02 3B-5 11/22/02 3B-45 11/22/02 5-1 11/22/02 3B-6 11/22/02 3B-46 11/22/02 5-2 11/22/02 3B-7 11/22/02 3B-47 11/22/02 5-3 11/22/02 3B-8 11/22/02 3B-48 11/22/02 5-4 11/22/02 3B-9 11/22/02 3B-49 11/22/02 5-5 11/22/02 3B-10 11/22/02 3B-50 11/22/02 5-6 11/22/02 3B-11 11/22/02 3B-51 11/22/02 5-7 11/22/02 3B-12 11/22/02 3B-52 11/22/02 5-8 11/22/02 3B-13 11/22/02 3B-53 11/22/02 5-9 06/04/07 3B-14 11/22/02 3B-54 11/22/02 5-10 11/22/02 3B-15 11/22/02 3B-55 11/22/02 5-11 11/22/02 3B-16 11/22/02 3B-56 11/22/02 5-12 11/22/02 3B-17 11/22/02 ii 6/4/07 Rev 12

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL LIST OF EFFECTIVE PAGES Offsite Dose Calculation Manual PAGE DATE 3B-57 11/22/02 3C-1 11/22/02 3C-2 11/22/02 3C-3 11/22/02 5A-1 11/22/02 5A-2 11/22/02 5A-3 06/04/07 5A-4 11/22/02 5B-1 06/04/07 5B-2 06/04/07 iii 11/22/02 Rev 11

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Introduction vii 1.0 Administrative Controls Control 1.1 ODCM Review and Approval ................................................. 1-1 Control 1.2 Major Changes to Liquid, Gaseous and Solid Radwaste Treatment Systems ................................................... 1-2 Control 1.3 Annual Radioactive Effluent Release Report ............................. 1-3 Control 1.4 Annual Radiological Environmental Operating Report ............... 1-5 Control 1.5 D e fi n itio n s .................................................................................. 1-6 Control 1.6 Applicability of Controls ............................................................. 1 -14 Control 1.7 Surveillance Requirements ........................................................ 1 -15 Control 1.8 R e fe re n ce s ..................................................................... 1 - 16 Figure 1.5-1 S ite A re a Ma p ............................................................................ 1 -12 Figure 1.5-2 P la nt A re a Ma p .......................................................................... 1 -13 2.0 Radioactive Liquid Effluents Control 2.1 Liquid Effluent Monitoring Instrumentation, Operability and Alarm/Trip Setpoints ........................................... 2-5 Control 2.2 Concentrations in Radioactive Effluents ...................................... 2-14 Control 2.3 Dose From Radioactive Liquid Effluent ....................................... 2 - 24 Control 2.4 Liquid Radwaste Treatment System .......................................... 2-31 Figure 2 - 1 Radioactive Liquid Waste ........................................................... 2-4 Appendix 2A Radioactive Liquid Effluents Pathway Dose Transfer Factors ............................................................... 2A- 1 iv 6/4/07 Rev 11

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (continued 5.0 Radiological Environmental Monitoring Program Control 5.1 Conduct of Sam pling and Analysis .............................................. 5- 1 C ontrol 5.2 Land Use C ensus ........................................................................ 5 - 19 Control 5.3 Interlaboratory Comparison Program ........................ 5 - 21 Figure 5.1-1 Near Site Sam pling Locations ..................................................... 5 -17 Figure 5.1-2 Distant REMP Sampling Locations ............................................. 5- 18 Appendix 5A Turkey Point Supplemental Radiological Environm ental Monitoring Program ............................................. 5A - 1 Appendix 5B Turkey Point Groundwater Sampling Program to support the INDUSTRY INITIATIVE on Groundwater Protection ................................ 5B - 1 vi 6/4/07 Rev 12

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (continued 5.0 Radioloqical Environmental Monitoring Program Control 5.1 Conduct of Sampling and Analysis .............................................. 5-1 C ontrol 5.2 Land Use C ensus ....................................................................... 5 - 19 Control 5.3 Interlaboratory Comparison Program .......................................... 5 - 21 Figure 5.1-1 Near Site Sam pling Locations ..................................................... 5 - 17 Figure 5.1-2 Distant REMP Sampling Locations ............................................. 5- 18 Appendix 5A Turkey Point Supplemental Radiological Environmental Monitoring Program ............................................. 5A- 1 Appendix 5B Turkey Point Groundwater Sampling Program to support the INDUSTRY INITIATIVE on G roundw ater Protection ..................................................... 5B - 1 vi 6/4/07 Rev 12

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (continued) 3.0 Radioactive Gaseous Effluents Control 3.1 Radioactive Gaseous Effluent Monitoring Instrumentation; Operability and Alarm/Trip Setpoints .......................................... 3-10 Control 3.2 Dose Rate From Radioactive Gaseous Effluents ....................... 3 - 27 Control 3.3 Air Dose From Noble Gases ...................................................... 3 - 45 Control 3.4 Dose Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form .................................... 3 - 53 Control 3.5 Gaseous Radwaste Treatment System ...................................... 3 - 68 Figure 3 - 1 Radioactive Gaseous Waste ...................................................... 3-8 Figure 3 - 2 Locations of Airborne Effluent Dose Calculations ...................... 3-9 Appendix 3A Reference Meteorology Annual Average Atmospheric Dispersion Factors ................................................ 3A- 1 Appendix 3B Pathway-Dose Transfer Factors .................................................. 3B1-1 Appendix 3C Technical Bases for Aeff and TG 131 .................... . . . . . . . . . . . . . . . . . . . . . . .... 3C- 1 4.0 Total Dose Control 4.1 Limits of Total Dose to Members of the Public ............................ 4-1 v 11/22/02 Rev 11

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL INTRODUCTION PURPOSE This manual describes methods which are acceptable for calculating radioactivity concentrations in the environment and potential offsite doses associated with liquid and gaseous effluents from the Turkey Point Nuclear Units. These calculations are performed to satisfy Technical Specifications and to ensure that the radioactive dose or dose commitment to any member of the public is not exceeded.

The radioactivity concentration calculations and dose estimates in this manual are used to demonstrate compliance with the Technical Specifications required by 10 CFR 50.36. The methods used are acceptable for demonstrating operational compliance with 10 CFR 20.1302, 10CFR50 Appendix I, and 40CFR190. Only the doses attributable to Turkey Point Units 3 and 4 are determined in demonstrating compliance with 40CFR190 since there are no other nuclear facilities within 50 miles of the plant. Monthly calculations are performed to verify that potential offsite releases do not exceed Technical Specifications and to provide guidance for the management of radioactive effluents. The dose receptor is described such that the exposure of any member of the public is not likely to be substantially underestimated.

Quarterly and annual calculations of committed dose are also performed to verify compliance with regulatory limits of offsite dose. For these calculations, the dose receptor is chosen on the basis of applicable exposure pathways identified in a land use survey and the maximum ground level atmospheric dispersion factor (y/Q) at a residence, or on the basis of more conservative conditions such that the dose to any resident near the plant is not likely to be underestimated.

The radioactive effluent controls set forth in this ODCM are designed to allow operational flexibility but still maintain releases and doses "as low as is reasonably achievable"; that is, within the objectives of Appendix 1,10 CFR Part 50 and comply with the limits in 10 CFR 20.1302.

The methods specified in the OFFSITE DOSE CALCULATION MANUAL (ODCM) for calculating doses due to planned or actual releases are consistent with the guidance and methods provided in:

Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1. October 1977.

Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.

vii 11/22/02 Rev 11

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL INTRODUCTION, (continued)

Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

The required detection capabilities for radioactive materials in liquid and gaseous waste samples are tabulated in terms of the lower limits of detection (LDD's). Detailed discussion of the LLD and other detection limits, can be found in Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements,"

NUREG/CR-4077 (September 1984), in HASL Procedures Manual, HASL300 and in Hartwell, J. K.,

"Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

viii 11/22/02 Rev 11

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS CONTROL 1.3: Annual Radioactive Effluent Release Report *, (continued)

c. An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases from the previous calendar year and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1, October 1977.

d. A list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.

e. Any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM), pursuant to Technical Specification 6.14, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment Systems pursuant to Control 1.2. It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Control 5.2.

f. An explanation, if applicable, as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Control 2.1 or 3.1, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.7.9.

g. Beginning with the Report that is due April 1, 2007, the Annual Radioactive Effluent Release Reports shall include the following information for the previous year:

A listing description of all leaks or spills that have been communicated to State and Local Officials in accordance with the INDUSTRY INITIATIVE (Nuclear Policy NP-922).

ii. Groundwater sample results that have been taken in support of the INDUSTRY INITIATIVE (Nuclear Policy NP-922), unless they are from locations that are described in the Radiological Environmental Monitoring Program (REMP) and will therefore be reported in the Annual Radiological Environmental Operating Report. See Appendix 5B for details.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

1-4 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS CONTROL 1.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of the following year and shall include :

a. Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls, as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census required by Control 5.2

b. The results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in Control 5.1, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

c. A summary description of the Radiological Environmental Monitoring Program; at least two legible maps ** covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Control 5.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Control 5.1, and discussion of all deviations from the sampling schedule of Table 5.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 5.1-2 but are not the result of plant effluents, pursuant to ACTION b. of Control 5.1; and discussion of all analyses in which the LLD required by Table 5.1-3 was not achievable.

d. Results from the Turkey Point Groundwater Sampling Program for the samples and locations in Appendix 5B.

A single submittal may be made for a multiple unit station.

One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.

1-5 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS 1.5 DEFINITIONS (continued)

DOSE EQUIVALENT 1-131 1.5.5 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microCurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites" or Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.

FREQUENCY NOTATION 1.5.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.5-1 GAS DECAY TANK SYSTEM 1.5.7 A GAS DECAY TANK SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

INDUSTRY INITIATIVE 1.5.8Nuclear Energy Institute Initiative on Managing Situations Involving Inadvertent Radiological Releases into Groundwater (The INDUSTRY INITIATIVE has been adopted through Nuclear Policy, NP-922).

INITIAL CALIBRATION 1.5.9 INITIAL CALIBRATION -An INITIAL CALIBRATION is the determination of the detector sensitivity when the detector is exposed in a known geometry to radiation from sources of known energies and activity levels traceable to National Institute of Standards & Technology (NIST). The vendor usually performs this calibration.

Furthermore, subsequent CHANNEL CALIBRATIONS should ,include the use of a TRACEABLE SOURCE positioned in a reproducible geometry with respect to the sensor whose effect on the system was established at the time of the initial calibration. This CHANNEL CALIBRATION will establish the dynamic capabilities of a detector, electronics and power supplies in such a way as to ensure that the detector will perform its basic task of sensing radiation at the predetermined minimum detectable concentration based on the Initial Calibration.

MEMBER(S) OF THE PUBLIC 1-7 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS 1.5.10 MEMBER(S) OF THE PUBLIC shall mean any individual except when that individual is receiving an occupational dose.

1-7 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS 1.5 DEFINITIONS (continued)

OFFSITE DOSE CALCULATION MANUAL 1.5.11 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Tech Spec Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Operating Report required by Controls 1.3 and 1.4.

OPERABLE - OPERABILITY 1.5.12 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

OPERATIONAL MODE - MODE 1.5.13 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.5-2 PROCESS CONTROL PROGRAM 1.5.14 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analysis, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and Federal and State regulations, burial ground requirements, and other requirements governing the disposal of radioactive waste.

1-8 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS 1.5 DEFINITIONS (continued)

PURGE - PURGING 1.5.15 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER 1.5.16 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2300 MWt REPORTABLE EVENT 1.5.17 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

SAMPLING EVALUATION 1.5.18 A SAMPLING EVOLUTION is the exchange of iodine cartridge or particulate filter or the attachment of a sample rig to obtain a noble gas or tritum sample.

SITE BOUNDARY 1.5.19 The SITE BOUNDARY shall mean that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee, see figure 1.5 - 1.

SOURCE CHECK 1.5.20 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

THERMAL POWER 1.5.21 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRACEABLE SOURCE 1.5.22 TRACEABLE SOURCE - Radiation sources that are related not only to the reference sources that were used for the INITIAL CALIBRATION but also certified by the National Institute of Standards & Technology (NIST). These transfer sources will calibrate the detector by positioning it in a reproducible geometry as prescribed by the INITIAL CALIBRATION.

UNRESTRICTED AREA 1.5.23 An UNRESTRICTED AREA shall mean an area, access to which is neither limited nor controlled by the licensee.

1-9 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS 1.5 DEFINITIONS (continued)

VENTILATION EXHAUST TREATMENT SYSTEM 1.5.24 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioactive iodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodine or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING 1.5.25 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

TABLE 1.5-1 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

NA Not applicable.

P Completed prior to each batch release.

1-10 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS 1.7 SURVEILLANCE REQUIREMENTS (continued) 1.7.4Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement(s) associated with a Control has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

1.7.6Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in Control 1.6.5 for individual controls or whenever certain portions of a control contain surveillance parameters different for each unit, which will be identified in parentheses, footnotes or body of the requirement.

1.8 REFERENCES

1. Condition Report (CR) 2005-17141, REMP QA Audit

2. PTN-ENG-SENS-05-049, Temporary Suspension of Continuous Monitoring via the Plant Vent and Unit 3 Spent Fuel Pool SPINGS for the performance of Required Maintenance.

3. PTN-ENG-SENS-06-048, The Calculation Developing the Iodine and Particulate Activity Compensation Factors for the Steam Jet Air Ejector Vent Monitors. This Engineering Evaluation is valid through 31 Dec. 2009.

4. Condition Report (CR) 2006-17093, Nuclear Energy Institute Industry Initiative on Managing Situations Involving Inadvertent Radiological Releases into Groundwater.

5. Condition Report (CR) 2006-17607, Sampling and Monitoring Groundwater at PTN.

6. Nuclear Policy NP-922, Managing Situations Involving Inadvertent Radological Releases into Groundwater. (Implements the INDUSTRY INITIATIVE).

1-16 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.2: CONCENTRATIONS IN RADIOACTIVE LIQUID EFFLUENTS The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 1.5-1) shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10- 4 micro Curie/ml total activity.

APPLICABILITY: At all times.

ACTION : With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS 2.2.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 2.2-1.

2.2.2The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of this Control.

2-14 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS C. GASEOUS RADWASTE SYSTEM Radioactive and potentially radioactive gases from units 3 and 4 containment buildings, the auxiliary building, unit 4 spent fuel pit, radwaste building and laundry area are released via the monitored plant vent after passing through filter systems.

Radioactive waste gases from the primary systems (CVCS hold-up tanks) are stored in gas decay tanks to reduce activity levels by radioactive decay prior to release via the plant vent. The unit 3 spent fuel pit area is ventilated via its' own monitored vent after passing through a filtering system. The filtration systems for the Auxiliary Building, 3 & 4 Spent fuel Pit, the Radwaste Building, and the Laundry consist of a pre-filter and a HEPA filter. The Containment Buildings have roughing filters only.

The steam jet air ejectors from each unit are vented through monitored release pathways. Other steam losses concurrent with primary to secondary leakage are unmonitored and gaseous activity must be accounted for.

Radionuclides other than noble gases in the gaseous effluents are measured by the radioactive gaseous waste sampling and analysis program described in ODCM Table 3.2-1. Noble gas radionuclides are measured by continuous monitors in the four release points. The gaseous effluent streams monitoring points, and effluent discharge points are illustrated schematically in Figure 3-1.

The measured radionuclide concentrations in gaseous effluents from the plant are used for estimating offsite radionuclide concentrations and radiation doses.

Sampling and analyses are performed consistent with the requirements of ODCM Table 3.2-1.

The radioactive iodines and particulate radionuclides from continuous releases and batch releases ( Containment Purges and Gas Decay Tanks are released via the Plant Vent ) are determined by charcoal and filter samples removed weekly from continuous sample trains installed at each release point (plant vent, condenser air ejectors and Unit 3 Spent Fuel Pit vent). Tritium activity is determined on monthly grab samples from the plant vent, condenser air ejector, and Unit 3 Spent Fuel Pit and by a grab sample from each containment purge.

The Condenser Air Ejector Exhaust pathway is not conducive to collection of iodine and particulate in that the pathway is not capable of isokinetic sampling. The exhaust flow rate varies, doesn't have an isokinetic nozzle and when condenser air in leakage is at very low flow rates emits puffs versus a constant flow rate.

Therefore the Steam Jet Air Ejector SPING will be sampling a mixture of Condenser off gas and the atmosphere, and not gathering a representative sample. To account for the inability to perform isokinetic sampling, compensation factors were developed to relate the estimated concentration of particulates and iodine to the concentration of noble gas emitted. Calculation dose, from this pathway, from particulates is performed assuming that all curies released are Co-60 and all iodine curies released is 1-131. No analysis for alpha or Sr-89 and Sr-90 will be performed.

The compensation factors developed using PTN-ENG-SENS-06-048, The Calculation Developing the Iodine and Particulate Activity Compensation Factors for the Steam Jet Air Ejector Vent Monitor,are valid until 31 Dec. 2009.

3-3 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS OBJECTIVES & SYSTEM DESCRIPTION (continued)

C. GASEOUS RADWASTE SYSTEM, (continued)

The total measured radioactivity discharged via a stack or vent during a specific time period can be determined from the effluent monitors by:

N j

F

28317 Qj hh where:

Qj = total measured gaseous radioactivity release via a stack or vent during counting interval j, ([tCi)

Nj = counts accumulated during counting interval j, (counts = N(cpm) x t (min))

F = discharge rate of gaseous effluent stream, (ft3/min) 28317 = conversion constant, (cm 3 /ft3) h = effluent noble gas monitor calibration or counting rate response for noble gas gamma radiation, cpm 3

PCi / cm During periods of primary to secondary leakage, the activity released through unmonitored pathways can be estimated using the following methods. Other more accurate methods may be used, when appropriate and with the proper level of management approval.

Qj=CxFj xmj where:

C = The concentration of the individual isotope released.

Fj = The mass of unmonitored water and steam released through unmonitored pathways.

Fj = Mw - (Mb + Ms)

Mw = Mass rate of make up water Mb = Mass rate of blowdown M, = Mass rate of steam from monitored sources Tj = Time interval for the period being quantified 3-5 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation, Operability and Alarm/Trip Setpoints, (continued)

TABLE 3.1-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. GAS DECAY TANK SYSTEM

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release 1 3.1.1 (Plant Vent Monitor)

b. Effluent System Flow Rate Measuring Device 1

3.1.2

2. Condenser Air Ejector Vent System

a. Noble Gas Activity Monitor (SPING or PRMS) 1 3.1.3

b. Iodine Sampler 1 3.1.6

c. Particulate Sampler 1 3.1.6

d. Effluent System Flow Rate Measuring Device 1 3.1.2

e. Sampler Flow Rate Measuring Device 1 3.1.5 3-11 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.11: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability and Alarm/Trip Setpoints, (continued)

TABLE 3.1-1 (continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OFPERABLE APPLICABILITY ACTION

3. Plant Vent System (Include Unit 4's Spent Fuel Pool)

a. Noble Gas Activity Monitor (SPING or PRMS) 1

3.1.3

b. Iodine Sampler 1

3.1.4

c. Particulate Sampler 1

3.1.4

d. Effluent System Flow Rate Measuring Device 1 3.1.2

e. Sampler Flow Rate Measuring Device 1 3.1.5

4. Unit 3 Spent Fuel Pit Building Vent

a. Noble Gas Activity Monitor 1

3.1.3

b. Iodine Sampler 1

3.1.4

c. Particulate Sampler 1

3.1.4

d. Sampler Flow Rate Measuring Device 1

3.1.5 3-12 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation: Operability and Alarm/Trip Setpoints, (continued)

TABLE 3.1-1 (Continued)

TABLE NOTATION

At all times.

Applies during MODE 1, 2, 3 and 4.

Applies during MODE 1, 2, 3 and 4 when primary to secondary leakage is detected.

ACTION 3.1.1 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup;

,Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 3.1.2 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 3.1.3 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SAMPLING EVOLUTIONS are not an interruption of the continuous sample collection requirement and do not render the channel INOPERABLE. Ifa SAMPLE EVOLUTION is unable to be completed, THEN perform the actions for an INOPERABLE channel within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the start of the SAMPLING EVOLUTION.

ACTION 3.1.4 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided continuous sample collection with auxiliary equipment as required by Table 3.2-1 is installed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the channel being declared INOPERABLE, and analyzed at least weekly.

3-13 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT SAMPLING EVOLUTIONS are not an interruption of the continuous sample collection requirement and do not render the channel INOPERABLE. If a SAMPLING EVOLUTION is unable to be completed, THEN perform the actions for an INOPERABLE channel within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the start of the SAMPLING EVOLUTION.

ACTION 3.1.5 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided auxiliary equipment is installed, AND the sample flow rate is verified at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 3.1.6 Continuous collection of iodine and particulate in the Condenser Air Ejector is not required. If Primary to Secondary leakage is detected,

.effluent releases via the affected pathway may continue provided that the iodine and particulate curies released are determined using the methodology of Reference 3.

SAMPLING EVOLUTIONS are not an interruption of the continuous sample collection requirement and do not render the channel INOPERABLE. If a SAMPLING EVOLUTION is unable to be completed, THEN perform the actions for an INOPERABLE channel within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the start of the SAMPLING EVOLUTION.

3-14 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability and Alarm/Trip Setpoints, (continued)

TABLE 3.1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE IS INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

1. GAS DECAY TANK SYSTEM

a. Noble Gas Activity Monitor Providing Alarm and Automatic Termination of Release P P R (3) Q (1)

(Plant Vent Monitor)

b. Effluent System Flow Rate Measuring Device P (4) N.A. R N.A.

2. Condenser Air Ejector Vent System

a. Noble Gas Activity Monitor (SPING or PRMS) [) M R (3) Q (2)

b. Effluent System Flow Rate Measuring Device D (4) N.A. R N.A.

c. Sample Flow Rate Measuring Device [ (4) N.A. R N.A.

3-15 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 30v RADIOACTIVE GASEOUS EFFLUENT 30 CONTROL 3.1: Radioactive Gaseous Effluent Monitorinq Instrumentation; OperabilitV and Alarm/Trip Setpoints, (continued)

TABLE 3.1-2 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE IS INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED

3. Plant Vent System (Include Unit 4's Spent Fuel Pool)

a. Noble Gas Activity Monitor (SPING or PRMS) D (5) M R (3) Q (2)

b. Iodine Sampler W N.A. N.A. N.A.

c. Particulate Sampler W (5) N.A. N.A. N.A.

d. Effluent System Flow Rate Measuring Device D (4) N.A. R N.A.

e. Sampler Flow Rate Measuring Device D (4) N.A. R N.A.

4. Unit 3 Spent Fuel Pit Building Vent

a. Noble Gas Activity Monitor D M R (3) Q (2)

b. Iodine Sampler W (5) N.A. N.A. N.A. "*

c. Particulate Sampler W (5) N.A. N.A. N.A.

d. Sampler Flow Rate Measuring Device D (4) N.A. R N.A.

3-16 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.11: Radioactive Gaseous Effluent Monitorinq Instrumentation: Operability and Alarm/Trip Setpoints, (continued)

TABLE 3.1-2 (Continued)

TABLE NOTATIONS

At all times during periods of release.

Applies during MODE 1, 2, 3 and 4.

1. Applies during MODE 1, 2, 3 and 4 when primary to secondary leakage is detected.

(1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the Alarm/Trip Setpoint.

(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that ifthe instrument indicates measured levels above the Alarm Setpoint, alarm annunciation occurs in the control room (for PRMS only) and in the computer room (for SPING only).

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. When practical, these standards shall

,permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

(5) The CHANNEL CHECK shall consist of changing and analyzing the filter on a weekly basis.

3-17 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1: Radioactive Gaseous Effluent Monitorinq Instrumentation: Operability and Alarm/Trip Setpoints, (continued)

METHOD 3.1.1: GASEOUS EFFLUENT MONITOR SURVEILLANCES The surveillances of Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release and Flow Rate Measurement Devices are scheduled by procedure 0-ADM-215, Plant Surveillance Tracking Program.

METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS The radioactive gaseous effluent monitoring instrumentation channels alarm setpoints and trip setpoints are set in accordance with Control 3.1 to ensure the limits of Control 3.2 are not exceeded.

Each radioactive noble gas effluent monitor setpoint is derived on the basis of total body dose equivalent rate at or beyond the site boundary.

For the purpose of deriving a setpoint, the distribution of radioactive noble gases in an effluent stream may be determined in one of the following ways:

o Preferably, the radionuclide distribution is obtained by gamma spectrum analysis of identifiable noble gases in effluent gas samples. Results of analysis of one or more samples may be averaged to obtain a representative spectrum.

o Alternately, the total activity concentration of radioactive noble gases may be assumed to be Xe-133. This approach is valid because Xe-1 33 contributes about 99% of the noble gas activity.

3-18 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1 : Radioactive Gaseous Effluent Monitoring Instrumentation; Operability and Alarm/Trip Setpoints, (continued)

METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS (continued)

A noble gas effluent monitor alarm and trip setpoint, based on dose rate, is calculated with the equation below, or a method which gives a lower setpoint value in accordance with approved plant procedures.

Kh. K S =1.-06-- + 8kg Eqn 3.1 -1 where:

S = The alarm setpoint, (cpm) 1.06 = conversion constant (500 mrem/yr.60 sec/min m 35.32 ft3 /m 3 " 1 m 3/10 6cm 3 )

h = monitor response to activity concentration of effluent, cpm

([tCi/cc)

F = flow of gaseous effluent stream, i.e., flow past the monitor, (ft3/min)

X/Q = atmospheric dispersion factor at the off-site location of interest, (sec/m 3)

Ci= concentration of radionuclide i in gaseous effluent (pCi/cc).

DFj = Dose factor for exposure to a semi-infinite cloud of noble gas, mrem See Table 3.1-3. (yr iCi/m3 )

S = A factor to allow for multiple sources from different or common release points. The allowable operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the release sources. For gas releases, this fraction is assigned as follows: 0.6 for the Plant Vent, 0.1 for the 3 Spent Fuel Pit Vent, 0.1 for each SJAE Vent, and 0.1 for unmonitored gas releases.

Bk = Instrument background count rate, cpm 3-19 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability and Alarm/Trip Setpoints, (continued)

METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, (continued)

Each monitoring channel has a unique response, h, which is determined by the instrument calibration.

Atmospheric dispersion depends upon the local atmospheric conditions. For the purpose of calculating a radioactive noble gas effluent monitor setpoint, the atmospheric dispersion factor, x/Q, will be based on prevailing meteorological conditions or on reference meteorological conditions. The minimum atmospheric dispersion off site 3 derived from reference meteorological conditions at the site boundary is 5.8 x 10-7 sec/m at a location 1950 meters south southeast of the plant.

The applicable dose conversion factors, DFj, for deriving setpoints are in Table 3.1-3.

The limiting factor for equation 3.1-1 is the total body dose rate limit of 500 mrem/year which is included in the 1.06 conversion factor. The use of the total body dose assumes that the total body dose will be the controlling dose rate and the dominant contributor to this dose will be Xe-1 33.

Each iodine and particulate effluent monitor setpoint may be calculated using equation 3.1-2, or a method which gives a lower setpoint value. Since the iodine and particulate channels are not required by Control 3.1, the primary method to ensure Control 3.2 is met is the performance of the sampling and analysis program in table 3.2-1 and the noble gas alarm setpoints.

3 - 20 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1 Radioactive Gaseous Effluent Monitoring Instrumentation: Operability and Alarm/Trip Setpoints, (continued)

METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS (continued)

S =t. DR he 8~ 3600 V" + BKG Eqn 3.1-2 TAa.,p Xci /Q where:

DR = the dose rate limit the effluent pathway is limited to; 1500 mrem/year.

Taanip = a factor relating the airborne concentration time integral of radionuclide i to the dose equivalent to organ, n, of a person in age group, a, exposed via pathway, p (inhalation), as described in Method 3.2, See Appendix 3B. mrem/yr (pCi/mi3 )

3600 = conversion constant, (sec/hr).

h = monitor response to activity deposited on the sample collection media, cpm/uCi.

t = period of time over which the effluent release takes place, (hours).

Xd/Q = atmospheric dispersion factor adjusted for depletion by deposition at the off-site location of interest (sec/m3).

Sf= A factor to allow for multiple sources from different or common release points. The allowable operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the release sources. For gas releases, this fraction is assigned as follows: 0.6 for the Plant Vent, 0.1 for the 3 Spent Fuel Pit Vent, 0.1 for each SJAE Vent, and 0.1 for unmonitored gas releases.

VR = Ratio of sample volume to release volume.

3-21 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (continued)

TABLE 3.2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS SAMPLING MINIMUM ANALYSIS TYPE OF LOWER LIMIT OF DETECTION RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (LLD)"1), (jaCi/cc)

1. Gas Decay Tank P P Principal Gamma Emitters (2) 1 x 10-(Batch) Each Tank, Grab Sample Each Tank p (6) Principal Gamma Emitters (2) 1 x 104

2. Containment Purge or p (6)

Venting (Batch)

Grab Sample Each PURGE H-3 l x 10,

3. Condenser Air Ejectors M (6) M (6) Principal Gamma Emitters (2) 1 x 10-Grab Sample Gas Sample H-3 1 x 106 4

4. Plant Vent (includes Unit 4 M (6) M (6) Principal Gamma Emitters (2) 1 x 10 Spent Fuel Pit Building Grab Sample Gas Sample Vent)

M H-3 1 x 10-6 M (4)(5)

Grab Sample

5. Unit 3 Spent Fuel Pit M M Principal Gamma Emitters (2) 1 x 10-Building Vent Grab Sample Gas Sample M (4).(6) M H-3 1 x 106 Grab Sample

6. All Release Types as listed Continuous (3)(9) W (7)(8) 1-131 1 x 10-12 in 3,4, and 5 (above) Charcoal Sample Continuous (3)(9) W (7)(8) Principal Gamma Emitters (2) 1 x 10711 Particulate Sample Continuous (3)(9) M (8) Gross Alpha Composite Particulate sample 1 x 1011 Continuous (3)(9) Q (8) Sr-89, Sr-90 Composite Particulate sample 1 x 101 Continuous 73);)7 Noble Gas Monitor Noble Gas Gross Beta or Gamma 1 x 106 3 - 28 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (continued)

TABLE 3.2-1 (Continued)

TABLE NOTATIONS (Continued)

(6) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period if (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has increased by more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has increased by more than a factor of 3.

(7) Sample collection media on the applicable Unit shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler. Sample collection media on the applicable Unit shall also be changed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing if: (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has increased more than a factor of 3. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10.

(8) The condenser Air Ejectors pathway is not isokinetic and therefore monitoring of iodine and particulate is not representative. The iodine and particulate curies released are determined using the methodology of Reference 3.

(9) SAMPLING EVOLUTIONS are not an interruption of the continuous sample collection requirement and do not render the channel INOPERABLE. If a SAMPLING EVOLUTION is unable to be completed, THEN perform the actions for an INOPERABLE channel within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the start of the SAMPLING EVOLUTION.

3-31 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.1 : CONDUCT OF SAMPLING AND ANALYSIS (continued)

TABLE NOTATIONS (continued) - TABLE 5.1-3 (continued)

(3) The LLD is defined (continued)

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Control 1.4.

(4) LLD for drinking water. If no drinking water pathway exists, a value of 15pCi/I may be used.

(5) An equilibrium mixture of the parent and daughter isotopes which corresponds to 15 pCi/I of the parent isotope.

METHOD 5.1: RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE - TURKEY POINT PLANT It is the policy of Florida Power and Light Company (FPL) that the Turkey Point 3 and 4, Radiological Environmental Monitoring Programs, (REMP), are conducted by the State of Florida Department of Health (DOH), pursuant to an Agreement between FPL and DOH. The policy also states that the coordination of the REMP with DOH and compliance with the REMP requirements are the responsibility of the Nuclear Division Health Physics/Chemistry Staff.

The following pages describe the actual sampling and analysis program implemented to satisfy ODCM Table 5.1-1.

5-9 6/4/07

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Turkey Point Supplemental REMP Sampling Pathway: Waterborne, Surface Water Sampling and Collection Frequency: Monthly Name Sector Distance Description T75 NW 1.2 Florida City Canal (- cross-street from satellite school)

T84 WSW 0.5 Cooling canal, discharge, - by bridge to parking lot T97 E 0.2 Cooling Canal, intake, - Air Force school area T08 S 5.5 Southern shore of canal system, west of Grand Canal Bridge

Approximate Distance from plant in miles Pathway: Waterborne, Vegetation Sampling and Collection Frequency: Quarterly Name Description T84 'Seaweed' from any location in the cooling canal Pathway: Waterborne, Sediment Sampling and Collection Frequency: A = Annual S = Semiannual (All Locations are the Cooling Canals)

Name SCF Description T01 A - Air Force school area T02 A West side of dam @ 'old intake' T03 A North end of collector canals, west of 'Grand Canal' T04 A In front (east) of LU offices T05 / T84 S Cooling canal, discharge, - by bridge to parking lot T06 / T85 S NW corner of canal system T07 A SW corner of canal system T08 A South end of main canal, near bridge T09 A 'Old Discharge Canal' at bend south of earth dam T10 A SE corner of canal system 5A - 3 6/4/07

Turkey Point Groundwater Sampling Program to Support the INDUSTRY INITIATIVE on Groundwater Protection Appendix 5B 6/4/0 7

The following sampling and analysis program is performed to meet the INDUSTRY INITIATIVE on Groundwater Sampling. The sample points are the minimum recommended and other points may be sampled in addition. The following notes apply:

1. The sample locations apply after January 1, 2007.

2. All sample results taken in support of the INDUSTRY INITIATIVE (NP-922) for the previous calendar year and required to be included in the Annual Radiological Environmental Operating Report (AREOR) to the NRC due May 1 st shall be reported to the Radiological Environmental Monitoring Program Specialist, Juno Nuclear Operations Support for inclusion in the AREOR.

3. All sample results taken in support of the INDUSTRY INITATIVE (NP-922) for the previous calendar year and required to be included in the Annual Radiological Effluent Release Report to the NRC shall be provided to the Chemistry Department for inclusion in the Annual Radioactive Effluent Release Report due April 1 st.

4. No drinking water pathway exists from groundwater at Turkey Point. Since on-site groundwater at Turkey Point Nuclear Plant does not provide a path to drinking water, the criterion in Section 2.2 of the INDUSTRY INITATIVE (NP-922) is not applicable.

5. All well and water samples taken as required by Appendix 5B will be analyzed for tritum and Principal Gamma Emitters (PGE). PGE's are those as described in Table 2.2-1, Note (3). All well and water sample taken as required by Appendix 5B will, at a minimum, be analyzed to meet the Lower Limit of Detection (LLD) on the Water Column of Table 5.1-3. In addition the LLD for tritum will be as low as practical that can be achieved for the equipment and sampling methods being used.

6. All well and water samples taken as required by Appendix 5B with a confirmed level of tritum activity, or PGE greater than the Lower Limit of Detection (LLD) on the Water Column of Table 5.1-3, determined during the current years sampling will be analyzed at least once per year for Sr-89, Sr-90, Fe-55 and Ni-63.

5B-1 6/4/07

7. The following wells will be sampled quarterly. Other wells and water samples may be added based on engineering analysis, hydrological assessments or sample results and trends.

Well Location G-21 Tallahassee Road extension, west of FPL property.

Sample from top and bottom.

G-28 Tallahassee Road extension, west of FPL property.

Sample from top and bottom.

L-3 West of Interceptor Canal, on Land-U property.

Sample from top and bottom.

L-5 West of Interceptor Canal, on Land-U property.

Sample from top and bottom.

STP-1 Northeast of PTN Sewage Plant.

P-94-2 North of Solids Settling Basin, east of PTN intake.

P-94-4 East of Dress-out Building, in the RCA.

PTPED-9 Northeast Corner of Neutralization Basin.

CD-1 Northeast Corner of Neutralization Basin.

5B-2 6/4/07

L-2008-061, Annual Radioactive Effluent Release Report for Period of January 1, 2007 Through December 31, 2007

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1.8 REFERENCES

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L-2008-061, Annual Radioactive Effluent Release Report for Period of January 1, 2007 Through December 31, 2007

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1.8 REFERENCES

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