Text

Submittal of 2018 Annual Radioactive Effluent Release Report
	ML19070A111
Person / Time
Site:	Turkey Point
Issue date:	02/27/2019
From:	Stamp B; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2019-017
	Download: ML19070A111 (308)
	v • d • e

{{#Wiki_filter:FEB 2 7 2019 L-2019-017 10 CFR 50.36a(a)(2) U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-00001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 2018 Annual Radioactive Effluent Release Report Attached is the Radioactive Effluent Release Report for the period of January 1, 2018, through December 31, 2018, 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 Robert Hess at (305) 246-4112. Sincerely, jJ.'2)~ Brian Stamp Plant General Manager Turkey Point Nuclear Plant SM Attachments cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Florida Power & Light Company 9760 S.W. 3441n Street Homestead, FL 33035

Florida Power and Light Turkey Point Plant Units 3 and 4

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 2018 through December 2018 Submitted by. NUCLEAR CHEMISTRY DEPARTMENT FLORIDA POWER AND ANY Brian Stamp, Plant General Manager

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table of Contents 1.0 REGULATORY LIMITS.................................................................................................... 3 2.0 EFFLUENT CONCENTRATION...................................................................................... 4 3.0 AVERAGE ENERGY ....................................................................................................... 4 4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY .......................... 4-6 5.0 BATCH RELEASES......................................................................................................... 6 6.0 UNPLANNED RELEASES*............................................................................................... 6 7.0 REACTOR COOLANT ACTIVITY ...........................................................*......................... *7 8.0 SITE RADIATION DOSE.............................................................................................. 7-8 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 GROUND WATER SAMPLING....................................................................................... 9 14.0 ERRATA DATA ..................................................................... ................................. 9 UNIT 3 TABLES *..................................................................... ................................. 10-21 UNIT 4 TABLES .................................................................... ...................................22-33 SITE DOSE TABLE ....................................................................... ............................. 34-36 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS TABLE .................................... 37-41 ERRATA DATA .................................................................................................. ATTACHMENT A OFFSITE DOSE CALCULATION MANUAL (ODCM) ........................................ ATTACHMENT B Page 2 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report 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, Carbon-14 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 Page 3 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report calendar quarter and shall not exceed 15 mrem to any organ during any calendar year. Carbon-14 dose was calculated using the guidance of Regulatory Guide 1.109, Calculations of Annual Doses to Man from Routine Releases of Reactor Effluents for the purpose of Evaluation Compliance with 10CFR Part 50, Appendix I, Rev1, Oct 1977. 2.0 EFFLUENT CONCENTRATION Water: In accordance with 10CFR20, Appendix 8, Table 2, Column 2, and for entrained or dissolved noble gases as described in 1.1 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. 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. Canal Evaporation dose calculations were done in accordance with the ODCM Control 2.5 as return/reuse of previous discharged radioactive effluents.

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2018 -- Turkey Point Annual Radioactive Effluent Release Report 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 ba~is by gamma spectral analysis. The resulting isotope concentrations were multiplied by the total volume released in order to estimate the total dissolved gases relea*sed. 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. 4.2 Gaseous Effluents Airborne releases to the atmosphere occurred from the following sources:

          - Gas Decay Tanks
          - Containment Purges
          - RWST via vent line
          - U3 and U4 Equipment hatch during outages
          - 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. d) Analysis of water vapor in a gas sample for tritium using liquid scintillation techniques. e) Carbon-14 curies were calculated using the guidance of "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents", TR 1021106, EPRI, Palo Alto, CA: 2010 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 2018 through December 2018, in the form of Joint Frequency Distribution Tables, are maintained on site. Page 5 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report 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 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 ERROR MAXIMUM ERROR Liquid +/- 3.32% +/-6.34% Gaseous +/- 2.67% +/-4.57% 5.0 BATCH RELEASES See attached Open Effluent Management Software report. 6.0 UNPLANNED RELEASES 6.1 Liquid Release Occurrences On 1/21/2018, during a clearance hang on the 40 Demineralizer resin fill isolation valve 4-241 (located on Auxiliary building roof), operators removed the weather-protective housing on top of the valve to check valve position. Upon removing the housing, approximately 1/2 gallon of water leaked onto the roof. The volume release to the roof is estimated to be 0.5 gallons. The calculated activity released was 4.12E-09 curies. Based on the activity of 2.177E-06 uCi/ml the total estimated dose for this release is calculated to be 6.55E-07 mRem, well below any ODCM limits. (AR # 2245523) On 8/8/18 weepage was identified from two RWST locations on the Unit 4 drain line. The leak was not identified as an active leak, however, the soil was sampled around the drain location and identified an activity of 9.37E-05 uCi/mL. The calculated activity released was 2.45E-06 curies. The total.estimated dose for this release calculated to be 3.32E-06 mRem, well below any ODCM limits. (AR# 2275357) Page 6 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report 6.2 Gaseous Release Occurrences There were no unplanned gaseous release occurrences. 7 .0 REACTOR COOLANT ACTIVITY 7.1 Unit3 Reactor coolant activity limits of 0.25 µCi/gram Dose Equivalent 1-131 and 447.7

        µCi/gram Dose Equivalent Xe-133 were not exceeded during this reporting period.

7.2 Unit4 Reactor coolant activity limits of 0.25 µCi/gram Dose Equivalent 1-131 and 447.7

        µCi/gram Dose Equivalent Xe-133 were not exceeded during this reporting period.

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 the attached Unit 3 and Unit 4 Reg. Guide 1.21 tables. All dose to the public where a fraction of the limits and dose were maintained as low as reasonably achievable. The total calculated off site dose to the public is summarized in the following Table A-5 per EPA 40 CFR 190 "Individual in the Unrestricted Area." Page 7 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-5. EPA 40 CFR Part 190 Individual in the Unrestricted Area Total Dose Visitor Dose Limit Total Dose Visitor Dose Percent of Percent of (mrem) (mrem) (mrem) Limit(%) Limit(%) Bone (mrem) l.88E-01 l.60E-01 25 7.SlE-01 6.38E-01 Liver (mrem) l.88E-01 1.60E-oi: 25 7.52E-01 6.40:E-01 Thyroid (mrem) l.88E-01 l.60E-01 75 2.51E-01 -2.13E-Ol

,(*

Kidney (mrem) 3.56E-02 .3.03E-02 25 l.42E-01 L21E-Ol Lung (ntrem) . l.88E-01 L60E-01' 25 , 7.52E-01 6.40E-Ol< GI-LLI (mrem) l.88E-01 l.60E-Ol 25 7.52E-01 6.40:E:..01 Skin(mrem) l.14E-05 9.69E-06 ,;,* 25 4.56E-05 3.88E-05 Total Body (mrem) l.88E-01 'l.60:B-01 25 7.52E-01 6.40B-o'.1 GJ~ Afr Dose (mrad) 7.73E-05 1.31E-05 10 - 7.73E-04 l.31E-04

                                                                            **1.37E-04 1

Beta Air Dose (mrad) 2.74E-05 4.63E-06, 20 -2.32E-05 *, Noble Gas Total Body Air Dose 7.46E-05 1.26&05 500 1.49E-05 2.52E-06 (mrad) Noble Gas Skin Air Dose (mrad) l.OSE-04 l.83E-05 3000 , 3.61E-06 ,6.IOE-07-' Page 8 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report 9.0 OFFSITE DOSE CALCULATION MANUAL (ODCM) REVISIONS The ODCM was revised in 2018 a complete copy is attached. 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 were no inoperable effluent monitoring instrumentation for greater than 7 days during the 2018 reporting period. 13.0 GROUND WATER SAMPLING In 2018 as part of the procedural requirements on Groundwater Sampling, wells on site and adjacent to the site were sampled for tritium. The tritium results were from 2.0 pico curies per liter to 3390 pico curies per liter. Selected wells which met the criteria stipulated in the ODCM were analyzed for hard to detect beta emitters (Fe-59, Ni-63, Sr-89/90) and alpha. All results were less than the limits of the Offsite Dose Calculation Manual, Table s.1-2; Reporting Levels for Radioactivity Concentrations in Environmental Samples. The results are reported in the Annual Radiological Environmental Operating Report. 14.0 ERRATA DATA An administrative error was identified in the 2017 Annual Radiological Effluent Release report, section 6.1 and 6.2 correctly lists on page 6 the abnormal release of 1.3879 E-06 and 5.51 SE-03 curies, but Table 6A, Liquid and Gas Abnormal Release Summary, on page 33 lists the value from the same incident as 1.83 E -06 and 2.98E-08 curies. Table 6A was corrected to list the activity as 1.39 E-06 and 5.52E-03 curies instead of mRem units; Additionally, Table A-4 was corrected to include the annual dose limit and percentage for NG Total Body and NB Skin. This is included as Attachment A. (AR# 02290698, 02302513) Page 9 of 45

2018 -- Turkey Point Annual Ra"dioactive Effluent Release Report Unit 3 Reg. Guide 1.21 Tables:

1. Table A-1: Gaseous Effluents - Summation of all Releases-

2. Table A-1 E: Gaseous Effluents - Mixed Mode Release - Batch Mode

3. Table A-1 F: Gaseous Effluents - Mixed Mode Release - Continuous Mode

4. Table A-2: Liquid Effluents - Summation of all Releases

5. Table A-2A: Liquid Effluents - Batch Mode

6. Table A-4: Dose Assessments 10 CFR Part 50, Appendix I: Dose to a Member of the Public due to Liquid Release

7. Table A-4: Dose Assessments 10 CFR Part 50, Appendix I: Air Dose Due to Gaseous Releases

8. Table A-4: Dose Assessments 10 CFR Part 50, Appendix I: Dose due to Radioiodines, Tritium, and Particulates in Gaseous Releases

9. Table 5A and 58: Liquid and Gas Batch Release Summary

10. Table 6A and 68: Liquid and Gas Abnormal Release Summary Only tables that pertain to mixed mode release are included. Unit 3 does not have ground level or elevated releases therefore, tables A-1A, 18, 1C, 1D are not included.

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2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-1, Gaseous Effluents - Summation of All Releases Unit: 3 January 2018 through December 2018 1ST 2N> 3RD 4TI-I Total Release lklits Annual Quarter guarter Quarter Quarter A. Fission and Activation Gases

1. Total Release Ci 2.40E-03 1.SSE-04 4.47E-05 2.13E-01 2.lSE-01

2. Average Release Rate for Period uCi/s 3.0SE-04 1.98E-05 5.62E-06 2.68E-02 6.83E-03

3. Percent of Limit % N/A N/A N/A N/A N/A B. Iodines and Halogens

1. Total Release Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO

2. Average Release Rate for Period uCi/s O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO

3. Percent of Limit % N/A N/A N/A N/A N/A C. Particulates

1. Total Release Ci O.OOE+oO O.OOE+oO O.OOE+oO 5.41E-05 5.41E-05

2. Average Release Rate for Period uCi/s O.OOE+oO O.OOE+oO O.OOE+oO 6.SOE-06 1.71E-06

3. Percent of Limit % N/A N/A N/A N/A N/A D. Tritium

1. Total Release Ci 2.85E-01 3.89E-01 9.20E-01 3.30E+o0 4.89E+o0

2. Average Release Rate for Period uCi/s 3.67E-02 4.94E-02 1.16E-01 4.lSE-01 1.SSE-01

3. Percent of Limit % N/A N/A N/A N/A N/A E. Gross Alpha

1. Total Release Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO F. carbon-14

1. Total Release Ci 1.77E+o0 1.81E+o0 1.82E+o0 5.74E-01 5.97E+o0

2. Average Release Rate for Period uCi/s 2.28E-01 2.30E-01 2.29E-01 7.22E-02 1.89E-01

3. Percent of Limit % N/A. N/A N/A N/A N/A Page 11 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-1E, Gaseous Effluents - Mixed Mode Release - Batch Mode Unit: 3 January 2018 through December 2018 1ST 2N) 3RD 41H Nuclides Released lklits Annual Quarter Quarter Quarter Quarter A. Fission and Activation Gases Ar-41 Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 2.04E-01 2.04E-01 Xe-133 Ci 2.40E-03 1.SSE-04 4.47E-05 8.68E-03 1.13E-02 xe-ns* Ci 8.87E-07 O.OOE-t-00 O.OOE-t-00 1.0lE-05 1.lOE-05 Total For Period Ci 2.40E-03 1.SSE-04 4.47E-05 2.13E-01 2.lSE-01 B. Iodines and Halogens No Nuclides Found Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00

c. Particulates Cr-51 Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 9.83E-06 9.83E-06 Mn-54 Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 1.21E-06 1.21E-06 Co-58 Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00

7.27E-06 7.27E-06 Co-60 Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 4.42E-06 4.42E-06 Zn-65 Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 1.43E-05 1.43E-05 Zr-95 Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 3.14E-06 3.14E-06 Nb-95 Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 1.31E-05 1.31E-OS Tc-99m Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 7.71E-07 7.71E-07 Total For Period Ci O.OOE+OO O.OOE+OO O.OOE+OO 5.41E-05 5.41E-05 D. Tritium H-3 Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 4.66E-01 4.66E-01
E. Gross Alpha No Nuclides Found Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 F. carbon-14 No Nuclides Found Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 Page 12 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-lF, Gaseous Effluents - Mixed Mode Release - Continuous Mode Unit: 3 January 2018 through December 2018 1ST 2N> 3RD 4TH Nuclides Released lktits Annual Quarter Quarter Quarter Quarter A. Rssion and Activation Gases No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO B. Iodines and Halogens No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE-tOO O.OOE+oO O.OOE+oO C. Particulates No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO D. Tritium H-3 Ci 2.SSE-01 3.89E-01 9.20E-01 2.83E+o0 4.43E-t00 E. Gross Alpha No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO F. carbon-14 C-14 Ci 1.77E+o0 1.81E+o0 1.82E-t00 5.74E-01 5.97E-t00 Page 13 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-2, Liquid Effluents - Summation of All Releases Unit: 3 January 2018 through December 2018 1ST 2N> 3RD 41H Total Release lklits Annual Quarter Quarter Quarter Quarter A. Rssion and Activation Products

1. Total Release Ci 9.60E-03 6.68E-03 1.99E-02 1.87E-02 5.49E-02

2. Average Concentration uCi/mL 2.45E-09 1.09E-09 2.72E-09 2.lOE-09 2.09E-09 B. Tritium

1. Total Release Ci 2.lOE+ol 2.70E+ol 2.64E+o2 2.76E+o2 5.88E+o2

2. Average Concentration uCi/mL 5.36E-06 4.44E-06 3.60E-05 3.lOE-05 2.24E-05 C. Dissolved and Entrained Gases

1. Total Release Ci O.OOE+oO O.OOE+oO O.OOE+oO l.98E-06 l.98E-06

2. Average Concentration uCi/mL O.OOE+oO O.OOE+oO O.OOE+oO 2.22E-13 7.55E-14 D. Gross Algha Activit¥

1. Total Release Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO

2. Average Concentration uCi/mL O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO E. Liguid Release Volume

1. Total Release Liters 2.45E+o5 2.37E+o5 4.34E+o5 7.57E+o5 l.67E+o6 F. Dilution Volume

1. Total Release Liters 3.92E+o9 6.10E+o9 7.33E+o9 8.91E+o9 2.62E+10 G. Average Stream Row

1. Total Release m"3/s O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO Page 14 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-2A, Liquid Effluents - Batch Mode Unit: 3 January 2018 through December 2018 1ST 2Nl 3RD 41H Nuclides Released Ulits Annual Quarter Quarter Quarter Quarter A. Fission and Activation Products Na-24 Ci O.OOE+oO O.OOE+oO O.OOE+oO 3.41E-06 3.41E-06 Cr-51 Ci O.OOE+oO O.OOE+oO O.OOE+oO 7.32E-04 7.32E-04 Mn-54 Ci O.OOE+oO 1.23E-06 1.03E-05 7.83E-06 1.94E-05 Fe-55 Ci 2.97E-04 4.lBE-04 3.91E-03 2.83E-03 7.46E-03 Fe-59 Ci O.OOE+oO O.OOE+oO O.OOE+oO 1.0lE-05 l.OlE-05 Co-57 Ci 9.69E-07 1.69E-06 8.68E-06 O.OOE+oO l.13E-05 Co-58 Ci . 2.74E-03 1.62E-03 2.76E-03 4.19E-03 1.13E-02 Co-60 Ci 1.07E-04 1.61E-04 4.71E-04 2.44E-04 9.83E-04 Ni-63 Ci 6.14E-03 9.59E-04 7.12E-03 3.78E-03 1.BOE-02 Sr-92 Ci O.OOE+oO O.OOE+oO 1.40E-06 0.00E+oO 1.40E-06 Zr-95 Ci O.OOE+oO 4.00E-06 O.OOE+oO 1.lSE-05 l.SSE-05 Nb-95 Ci O.OOE+oO 8.93E-06 1.74E-05 6.62E-05 9.25E-05 Nb-97 Ci O.OOE+oO 6.45E-06 2.lSE-05 2.30E-05 5.lOE-05 Ag-llOm Ci O.OOE+oO 3.89E-05 1.49E-04 4.94E-05 2.38E-04 Sn-113 Ci O.OOE+oO O.OOE+oO O.OOE+oO 1.70E-06 1.70E-06 Sn-117m Ci O.OOE+oO 0.00E+oO O.OOE+oO 1.75E-05 1.75E-05 Sb-122 Ci O.OOE+oO O.OOE+oO O.OOE+oO 3.87E-05 3.87E-05 Sb-124 Ci 1.33E-06 O.OOE+oO 1.92E-05 2.SSE-04 2.76E-04 Sb-125 Ci 2.98E-04 2.39E-03 3.03E-03 6.00E-03 l.17E-02 Te-129 Ci O.OOE+oO O.OOE+oO O.OOE+oO 1.57E-04 1.57E-04 Te-132 Ci O.OOE+oO O.OOE+oO O.OOE+oO 1.97E-05 l.97E-05 1-131 Ci 1.27E-05 O.OOE+oO O.OOE+oO 0.00E+oO l.27E-05 I-132 Ci O.OOE+oO O.OOE+oO O.OOE+oO 1.68E-05 l.68E-05 I-133 Ci 1.09E-06 O.OOE+oO O.OOE+oO 0.00E+oO 1.09E-06 Cs-134 Ci O.OOE+oO 1.75E-05 1.09E-05 O.OOE+oO 2.84E-05 Ba-140 Ci O.OOE+oO O.OOE+oO 4.63E-06 0.00E+oO 4.63E-06 Cs-137 Ci O.OOE+oO 1.0SE-03 2.39E-03 2.23E-04 3.65E-03 Total For Period Ci 9.60E-03 6.68E-03 1.99E-02 1.87E-02 5.48E-02 Page 15 of45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-2A, Liquid Effluents - Batch Mode Unit: 3 January 2018 through December 2018 1ST 2N) 3RD 411-1 Nuclides Released lklits Annual Quarter Quarter Quarter Quarter B. Tritium H-3 Ci 2.10E-t-01 2.70E-t-01 2.64E+o2 2.76E+o2 5.88E+o2 C. Dissolved and Entrained Gases Xe-133 Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 1.98E-06 1.98E-06 D. Gross Alpha Activity No Nuclides Found Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 Page 16 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report TABLE A-4: Dose Assessments 10 CFR Part 50, Appendix I Doses to a member of the public due to Liquid Releases Unit: 3 January 2018 through December 2018 1ST 2N> 3RD 4TH Annual Organ Dose lklits Quarter Quarter Quarter Quarter Bone mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit O/o 1.53E-04 8.02E-04 1.69E-03 8.98E-04 1.77E-03 Liver mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit O/o 1.53E-04 8.02E-04 1.69E-03 8.98E-04 1.77E-03 Total Body mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 1.5 1.5 1.5 1.5 3 Percent of Limit _O/o 5.09E-04 2.67E-03 5.62E-03 2.99E-03 5.90E-03 Thyroid mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit O/o 1.53E-04 8.02E-04 1.69E-03 8.98E-04 1.77E-03 Kidney mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit O/o 1.53E-04 8.02E-04

1.69E-03 8.98E-04 1.77E-03 Lung mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit O/o 1.53E-04 8.02E-04 1.69E-03 8.98E-04 1.77E-03 GI-Ui mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit O/o 1.53E-04 8.02E-04 1.69E-03 8.98E-04 1.77E-03 Skin mRem 8.90E-06 4.64E-05 9.SOE-05 5.14E-05 2.05E-04 Limit mRem 5 5 5 5 10 Percent of Limit O/o 1.78E-04 9.28E-04 1.96E-03 1.03E-03 2.05E-03 Page 17 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report TABLE A-4: Dose Assessments 10 CFR Part 50, Appendix I Air Doses Due To Gaseous Releases Unit: 3 January 2018 through December 2018 1ST 2N> 3RD 41H Annual NG Dose Ulits Quarter Quarter Quarter Quarter Gamma Air mRad 1.53E-08 9.92E-10 2.86E-10 7.72E-05 7.72E-05 Limit mRad 5 5 5 5 10 Percent of Limit % 3.06E-07 1.98E-08 5.72E-09 1.54E-03 7.72E-04 Beta Air mRad 4.59E-08 2.98E-09 8.57E-10 2.69E-05 2.70E-05 Limit mRad 10 10 10 10 20 Percent of Limit % 4.59E-07 2.98E-08 8.57E-09 2.69E-04 1.35E-04 NG Total Body mRem l.30E-08 8.38E-10 2.41E-10 7.45E-05 7.45E-05 Limit mRem N/A N/A N/A N/A 500 Percent of Limit % N/A N/A N/A N/A l.49E-05 NG Skin mRem 3.0SE-08 l.98E-09 5.69E-10 l.OBE-04 l.OBE-04 Limit mRem N/A N/A N/A N/A 3000 Percent of Limit % N/A N/A N/A N/A 3.60E-06 Page 18 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report TABLE A-4: Dose Assessments 10 CFR Part SO, Appendix I Doses due to Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 3 January 2018 through December 2018 1ST 2111> 3RD 411-1 Organ Dose lhits Annual Quarter Quarter Quarter Quarter Bone mRem 2.51E-02 2.57E-02 2.58E-02 8.15E-03 8.47E-02 Limit mRem 7.5 7.5 7.5 7.5 15.0 Percent of Limit % 3.35E-01 3.43E-01 3.44E-01 1.09E-01 5.65E-01 Liver mRem 2.51E-02 2.57E-02 2.59E-02 8.42E-03 8.51E-02 Limit mRem 7.5 7.5 7.5 7.5 15.0 Percent of Limit % 3.35E-01 3.43E-01 3.45E-01 1.12E-01 5.67E-01 Total Body mRem 2.51E-02 2.57E-02 2.59E-02 8.42E-03 8.51E-02 Limit mRem N/A N/A N/A N/A N/A Percent of Limit % N/A N/A N/A N/A N/A Thyroid mRem 2.51E-02 2.57E-02 2.59E-02 8.42E-03 8.51E-02 Limit mRem 7.5 7.5 7.5 7.5 15.0 Percent of Limit % 3.35E-01 3.43E-01 3.45E-01 1.12E-01 5.67E-01 Kidney mRem 4.73E-03 4.84E-03 4.90E-03 1.74E-03 1.62E-02 Limit mRem 7.5 7.5 7.5 7.5 15.0 Percent of Limit % 6.31E-02 6.45E-02 6.53E-02 2.32E-02 1.0BE-01 Lung mRem 2.51E-02 2.57E-02 2.59E-02 8.42E-03 8.51E-02 Limit mRem 7.5 7.5 7.5 7.5 15.0 Percent of Limit % 3.35E-01 3.43E-01 3.45E-01 1.12E-01 5.67E-01 GI-Lli mRem 2.51E-02 2.57E-02 2.59E-02 8.42E-03 8.51E-02 Limit mRem 7.5 7.5 7.5 7.5 15.0 Percent of Limit % 3.35E-01 3.43E-01 3.45E-01 1.12E-01 5.67E-01 Skin mRem O.OOE+oO O.OOE+oO O.OOE+oO 1.14E-05 1.14E-05 Limit mRem 7.5 7.5 7.5 7.5 15.0 Percent of Limit % O.OOE+oO O.OOE+oO O.OOE+oO 1.52E-04 7.60E-05 Page 19 of45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table SA and SB - Liquid and Gas Batch Release Summary Unit: 3 January 2018 through December 2018 1st 2nd 3rd 4th A. Liquid Batch Release Totals Units Year Totals Quarter Quarter Quarter Quarter

1. Number of Batch Releases 20 19 33 57 129

2. Total duration of batch releases min 1.81E-t-03 1.69E-t-03 3.19E-t-03 6.03E-t-03 1.27E-t-04

3. Maximum batch release duration min 1.24E-t-02 1.0BE-t-02 1.06E-t-02 1.38E-t-02 1.38E-t-02

4. Average batch release duration min 9.04E-t-01 8.91E-t-01 9.67E-t-01 1.06E-t-02 9.86E-t-01

5. Minimum batch release duration min 6.50E-t-01 5.40E-t-01 7.00E-t-01 4.50E-t-01 4.50E-t-01 1st 2nd 3rd 4th B. Gas Batch Release Totals Units Year Totals Quarter Quarter Quarter Quarter

1. Number of Batch Releases 10 2 4 31 47

2. Total duration of batch releases min 3.02E-t-02 6.90E-t-01 1.96E-t-02 1.26E-t-04 1.32E-t-04

3. Maximum batch release duration min 3.90E-t-01 3.70E-t-01 8.30E-t-01 1.70E-t-03 1.70E-t-03

4. Average batch release duration min 3.02E-t-01 3.45E-t-01 4.90E-t-01 4.06E-t-02 2.BOE-t-02

5. Minimum batch release duration min 2.50E-t-01 3.20E-t-01 3.50E-t-01 2.30E-t-01 2.30E-t-01 Page 20 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table 6A and 68 - Liquid and Gas Abnormal Release Summary Unit: 3 January 2018 through December 2018 1st 2nd 3rd 4th A. Liquid Abnormal Release Totals Units Year Totals Quarter Quarter Quarter Quarter There were no abnormal releases during this period. 1st 2nd 3rd 4th B. Gas Abnormal Release Totals Units Year Totals Quarter Quarter Quarter Quarter There were no abnormal releases during this period. Page 21 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Unit 4 Reg. Guide 1.21 Tables:

1. Table A-1: Gaseous Effluents - Summation of all Releases

2. Table A-1 E: Gaseous Effluents - Mixed Mode Release - Batch Mode

3. Table A-1 F: Gaseous Effluents - Mixed Mode Release - Continuous Mode

4. Table A-2: Liquid Effluents - Summation of all Releases

5. Table A-2A: Liquid Effluents - Batch Mode

6. Table A-4: Dose Assessments 10 CFR Part 50, Appendix I: Dose to a member of the public due to Liquid Release

7. Table A-4: Dose Assessments 10 CFR Part 50, Appendix I: Air Dose Due to Gaseous Releases

8. Table A-4: Dose Assessments 10 CFR Part 50, Appendix I: Dose due to Radioiodines, Tritium, and Particulates in Gaseous Releases

9. Liquid and Gas Batch Release Summary

10. Table 6: Liquid and Gas Abnormal Release Summary Only tables that pertain to mixed mode release are included. Unit 4 does not have ground level or elevated releases therefore, tables A-1A, 18, 1C, 1D are not included.

Page 22 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-1, Gaseous Effluents - Summation of All Releases Unit: 4 January 2018 through December 2018 1ST 2N> 3RD 41ll Total Release lltits Annual Quartet Quarter Quarter Quarter A. Fission and Activation Gases

1. Total Release Ci 2.40E-03 1.SSE-04 4.47E-05 8.69E-03 1.13E-02

2. Average Release Rate for Period uCi/s 3.0SE-04 1.98E-05 5.62E-06 1.09E-03 3.SSE-04

3. Percent of Limit % N/A N/A N/A N/A N/A B. Iodines and Halogens

1. Total Release Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO

2. Average Release Rate for Period uCi/s O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO

3. Percent of Limit % N/A N/A N/A N/A N/A C. Particulates

1. Total Release Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO

2. Average Release Rate for Period uCi/s O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO

3. Percent of Limit % N/A N/A N/A N/A N/A D. Tritium

1. Total Release Ci 2.SSE-01 2.89E-01 7.24E-01 1.88E+o0 3.18E+o0

2. Average Release Rate for Period uCi/s 3.67E-02 3.68E-02 9.11E-02 2.37E-01 1.0lE-01

3. Percent of Limit % N/A N/A N/A N/A N/A E. Gross Alpha

1. Total Release Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO F. carbon-14

1. Total Release Ci 1.77E+o0 1.81E+o0 1.80E+o0 l.8SE+o0 7.23E+o0

2. Average Release Rate for Period uCi/s 2.28E-01 2.30E-01 2.26E-01 2.33E-01 2.29E-01

3. Percent of Limit % N/A N/A N/A N/A N/A Page 23 of 45

2018 --Turkey Point Annual Radioactive Effluent Release Report Table A-1E, Gaseous Effluents - Mixed Mode Release - Batch Mode Unit: 4 January 2018 through December 2018 1ST 2N> 3RD 4TH Nuclides Released lklits Annual Quarter Quarter Quarter

Quarter A. Rssion and Activation Gases Xe-133 Ci 2.40E-03 1.SSE-04 4.47E-05 8.68E-03 1.13E-02 Xe-135 Ci 8.87E-07 O.OOE+oO O.OOE+oO 1.0lE-05 1.lOE-05 Total For Period Ci 2.40E-03 1,SSE-04 4.47E-05 8.69E-03 1,13E-02 B, Iodines and Halogens No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO C. Particulates .

No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO D, Tritium No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO E. Gross Alpha No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO F. Carbon-14 No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO Page 24 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-lF, Gaseous Effluents - Mixed Mode Release - Continuous Mode Unit: 4 January 2018 through December 2018 1ST 2N> 3RD 4TH Nuclides Released lklits Annual Quarter Quarter Quarter Quarter A. Rssion and Activation Gases No Nuclides Found . Ci O.OOE+DO O.OOE+DO O.OOE+DO O.OOE+DO O.OOE+DO B. Iodines and Halogens No Nuclides Found Ci O.OOE+DO O.OOE+DO O.OOE+DO O.OOE+DO O.OOE+DO C. Particulates No Nuclides Found Ci O.OOE+DO O.OOE+DO O.OOE+DO O.OOE+DO O.OOE+DO D. Tritium H-3 Ci 2.SSE-01 2.89E-01 7.24E-01 1.88E+DO 3.18E+DO E. Gross Alpha No Nuclides Found

Ci O.OOE+DO O.OOE+DO O.OOE+DO O.OOE+DO O.OOE+DO F. carbon-14 C-14 Ci 1.77E+DO 1.81E+DO 1.SOE+DO 1.85E+o0 7.23E+DO Page 25 of 45.

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-2, Liquid Effluents - Summation of All Releases Unit: 4 January 2018 through December 2018 1ST 2N> 3RD 41H Total Release Ulits Annual Quarter Quarter Quarter Quarter A. Rssion and Activation Products

1. Total Release Ci 9.60E-03 6.68E-03 1.99E-02 1.87E-02 5.49E-02

2. Average Concentration uCi/mL 2.45E-09 1.09E-09 2.72E-09 2.lOE-09 2.09E-09 B. Tritium

1. Total Release Ci 2.lOE-t-01 2.70E-t-01 2.64E+o2 2.76E-t-02 5.88E-t-02

2. Average Concentration uCi/mL 5.36E-06 4.44E-06 3.60E-05 3.10E-05 2.24E-05 C. Dissolved and Entrained Gases

1. Total Release Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 1.98E-06 1.98E-06

2. Average Concentration uCi/mL O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 2.22E-13 7.SSE-14 D. Gross AIRha Activit¥

1. Total Release Ci O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00

2. Average Concentration uCi/mL O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 E. Liguid Release Volume

1. Total Release Liters 2.45E-t-05 2.37E-t-05 4.34E-t-05 7.57E-t-05 1.67E-t-06 F. Dilution Volume

1. Total Release Liters 3.92E-t-09 6.10E-t-09 7.33E-t-09 8.91E-t-09 2.62E+10 G. Average Stream Row

1. Total Release m"3/s O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 O.OOE-t-00 Page 26 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-2A, Liquid Effluents - Batch Mode Unit: 4 January 2018 through December 2018 1ST 2M> 3RD 4TH Nuclides Released lklits Annual Quarter Quarter Quarter Quarter A. Fission and Activation Products Na-24 Ci O.OOE+oO O.OOE+oO O.OOE+oO 3.41E-06 3.41E-06 Cr-51 Ci O.OOE+oO O.OOE+oO O.OOE+oO 7.32E-04 7.32E-04 Mn-54 Ci O.OOE+oO l.23E-06 l.03E-05 7.83E-06 1.94E-05 Fe-55 Ci 2.97E-04 4.18E-04 3.91E-03 2.83E-03 7.46E-03 Fe-59 Ci O.OOE+oO 0.00E+oO O.OOE+oO 1.0lE-05 1.0lE-05 Co-57 Ci 9.69E-07 l.69E-06 8.68E-06 O.OOE+oO 1.13E-05 Co-58 Ci 2.74E-03 1.62E-03 2.76E-03 4.19E-03 1.13E-02 Co-60 Ci 1.07E-04 1.61E-04 4.71E-04 2.44E-04 9.83E-04 Ni-63 Ci 6.14E-03 9.59E-04 7.12E-03 3.78E-03 1.80E-02 Sr-92 Ci O.OOE+oO 0.00E+oO 1.40E-06 O.OOE+oO 1.40E-06 Zr-95 Ci O.OOE+oO 4.00E-06 O.OOE+oO 1.lSE-05 1.55E-05 Nb-95 Ci O.OOE+oO 8.93E-06 1.74E-05 6.62E-05 9.25E-05 Nb-97 Ci O.OOE+oO 6.45E-06 2.lSE-05 2.30E-05 5.lOE-05 Ag-llOm Ci O.OOE+oO 3.89E-05 l.49E-04 4.94E-05 2.38E-04 Sn°113 Ci O.OOE+oO O.OOE+oO O.OOE+oO 1.70E-06 1.70E-06 Sn-117m Ci O.OOE+oO 0.00E+oO O.OOE+oO 1.75E-05 1.75E-05 Sb-122 Ci O.OOE+oO 0.00E+oO O.OOE+oO 3.87E-05 3.87E-05 Sb-124 Ci 1.33E-06 0.00E+oO 1.92E-05 2.55E-04 2.76E-04 Sb-125 Ci 2.98E-04 2.39E-03 3.03E-03 6.00E-03 1.17E-02 Te-129 Ci O.OOE+oO O.OOE+oO O.OOE+oO 1.57E-04 1.57E-04 Te-132 Ci O.OOE+oO 0.00E+oO O.OOE+oO 1.97E-05 1.97E-05 1-131 Ci 1.27E-05 0.00E+oO O.OOE+oO O.OOE+oO 1.27E-05 1-132 Ci O.OOE+oO O.OOE+oO O.OOE+oO 1.68E-05 1.68E-05 1-133 Ci 1.09E-06 O.OOE+oO O.OOE+oO O.OOE+oO 1.09E-06 Cs-134 Ci O.OOE+oO 1.75E-05 l.09E-05 O.OOE+oO 2.84E-05 Cs-137 Ci O.OOE+oO l.OSE-03 2.39E-03 2.23E-04 3.65E-03 Ba-140 Ci O.OOE+oO O.OOE+oO 4.63E-06 O.OOE+oO 4.63E-06 Total For Period Ci 9.60E-03 6.68E-03 1.99E-02 1.87E-02 5.48E-02 Page 27 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table A-2A, Liquid Effluents - Batch Mode Unit: 4 January 2018 through December 2018 1ST 2N> 3RD 4TH Nuclides Released Units Annual Quarter Quarter Quarter Quarter .e. Tritium H-3 Ci 2.lOE-l-01 2.70E+o1 2.64E+o2 2.76E+o2 5.88E+o2 C. Dissolved and Entrained Gases Xe-133 Ci O.OOE-l-00 O.OOE+oO O.OOE+oO 1.98E-06 1.98E-06 D. Gross Alpha Activity No Nuclides Found Ci O.OOE-l-00 O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO Page 28 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report TABLE A-4: Dose Assessments 10 CFR Part SO, Appendix I Doses to a member of the public due to Liquid Releases Unit: 4 January 2018 through December 2018 lklits 1ST 2111) 3RD 411-1 Annual Organ Dose Quarter Quarter Quarter Quarter Bone mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit % 1.53E-04 8.02E-04 1.69E-03 8.98E-04 1.77E-03 Liver mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit % 1.53E-04 8.02E-04 1.69E-03 8.98E-04 1.77E-03 Total Body mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 1.5 1.5 1.5 1.5 3 Percent of Limit % 5.09E-04 2.67E-03 5.62E-03 2.99E-03 5.90E-03 Thyroid mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit % 1.53E-04 8.02E-04 1.69E-03 8.98E-04 1.77E-03 Kidney mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit % 1.53E-04 8.02E-04 1.69E-03 8.98E-04 1.77E-03 Lung mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit % 1.53E-04 8.02E-04 1.69E-03 8.98E-04 1.77E-03 GI-Lli mRem 7.63E-06 4.0lE-05 8.43E-05 4.49E-05 1.77E-04 Limit mRem 5 5 5 5 10 Percent of Limit % 1.53E-04 8.02E-04 1.69E-03 8.98E-04 1.77E-03 Skin mRem 8.90E-06 4.64E-05 9.BOE-05 5.14E-05 2.05E-04 Limit mRem 5 5 5 5 10 Percent of Limit % 1.78E-04 9.28E-04 1.96E-03 1.03E-03 2.05E-03 Page 29 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report TABLE A-4: Dose As*sessments 10 CFR Part 50, Appendix I Air Doses Due To Gaseous Releases Unit: 4 January 2018 through December 2018 1ST 2N) 3RD 4TH Annual NG Dose lktits Quarter Quarter Quarter Quarter Gamma Air mRad 1.53E-08 9.92E-10 2.86E-10 1.25E-07 1.42E-07 Limit mRad 5 5 5 5 10 Percent of Limit % 3.06E-07 1.98E-08 5.72E-09 2.SOE-06 1.42E-06 Beta Air mRad 4.59E-08 2.98E-09 8.57E-10 3.74E-07 4.24E-07 Limit mRad 10 10 10 10 20 Percent of Limit % 4.59E-07 2.98E-08 8.57E-09 3.74E-06 2.12E-06 NG Total Body mRem 1.30E-08 8.38E-10 2.41E-10 1.06E-07 1.20E-07 Limit mRem N/A N/A N/A N/A 500 Percent of Limit O/o N/A N/A N/A N/A 2.40E-08 NG Skin mRem 3.0SE-08 1.98E-09 5.69E-10 2.49E-07 2.82E-07 Limit mRem N/A N/A N/A N/A 3000 Percent of Limit % N/A N/A N/A N/A 9.40E-09 Page 30 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report TABLE A-4: Dose Assessments 10 CFR Part SO, Appendix I Doses due to Radioiodines, Tritium, and Particulates in Gaseous Releases Unit: 4 January 2018 through December 2018 1ST 2N> 3RD 4TH Annual Organ Dose lktits Quarter Quarter Quarter Quarter Bone mRem 2.51E-02 2.57E-02 2.55E-02 2.62E-02 1.03E-01 Limit mRem 7.5 7.5 7.5 7.5 15 Percent of Limit % 3.35E-01 3.43E-01 3.40E-01 3.49E-01 6.87E-01 Liver mRem 2.SlE-02 2.57E-02 2.56E-02 2.64E-02 l.03E-01 Limit mRem 7.5 7.5 7.5 7.5 15 Percent of Limit % 3.35E-01 3.43E-01 3.41E-01 3.52E-01 6.87E-Ol Total Body mRem 2.51E-02 2.57E-02 2.56E-02 2.64E-02 l.03E-01 Limit mRem N/A N/A N/A N/A N/A Percent of Limit % N/A N/A N/A N/A N/A Thyroid mRem 2.SlE-02 2.57E-02 2.56E-02 2.64E-02 l.03E-01 Limit mRem 7.5 7.5 7.5 7.5 15 Percent of Limit % 3.35E-01 3.43E-01 3.41E-01 3.52E-01 6.87E-01 Kidney mRem 4.73E-03 4.84E-03 4.84E-03 5.04E-03 l.94E-02 Limit mRem 7.5 7.5 7.5 7.5 15 Percent of Limit % 6.31E-02 6.45E-02 6.45E-02 6.72E-02 l.29E-01 Lung mRem 2.SlE-02 2.57E-02 2.56E-02 2.64E-02 1.03E-01 Limit mRem 7.5 7.5 7.5 7.5 15 Percent of Limit % 3.35E-01 3.43E-01 3.41E-01 3.52E-01 6.87E-01 GI-Ui mRem 2.51E-02 2.57E-02 2.56E-02 2.64E-02 l.03E-01 Limit mRem 7.5 7.5 7.5 7.5 15 Percent of Limit % 3.35E-01 3.43E-01 3.41E-01 3.52E-01 6.87E-01 Skin mRem O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO 0.00E+oO Limit mRem 7.5 7.5 7.5 7.5 15 Percent of Limit % O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO 0.00E+oO Page 31 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table SA and SB - Liquid and Gas Batch Release Summary Unit: 4 January 2018 through December 2018 1st 2nd 3rd 4th A. Liquid Batch Release Totals lllits Year Totals Quarter Quarter Quarter Quarter

1. Number of Batch Releases 20 19 33 57 129

2. Total duration of batch releases min 1.81E+o3 1.69Et-03 3.19Et-03 6:03Et-03 1.27E+o4

3. Maximum batch release duration min 1.24E+o2 1.08Et-02 1.06E+o2 1.38Et-02 1.38Et-02

4. Average batch release duration min 9.04Et-01 8.91Et-01 9.67Et-01 1.06Et-02 9.86Et-01

5. Minimum batch release duration min 6.50Et-01 5.40Et-01 7.00Et-01 4.50Et-01 4.50Et-01 1st 2nd 3rd 4th B. Gas Batch Release Totals lllits Year Totals Quarter Quarter Quarter Quarter

1. Number of Batch Releases 10 2 4 14 30

2. Total duration of batch releases min 3.02Et-02 6.90Et-01 1.96Et-02 4.75Et-02 1.04Et-03

3. Maximum batch release duration min 3.90E+o1 3.70Et-01 8.30Et-01 4.50Et-01 8.30Et-01

4. Average batch release duration min 3.02E+o1 3.45Et-01 4.90Et-01 3.39Et-01 3.47Et-01

5. Minimum batch release duration min 2.50E+ol 3.20Et-01 3.50Et-01 2.30Et-01 2.30Et-01 Page 32 of45

2018 --Turkey Point Annual Radioactive Effluent Release Report Table 6A and 68 - Liquid and Gas Abnormal Release Summary Unit: 4 January 2018 through December 2018 1st 2nd 3rd 4th A, Liquid Abnormal Release Totals Ulits Year Totals Quarter Quarter Quarter Quarter

1. Number of Abnormal Releases 1 0 1 0 2

2. Tot.al Activity of abnormal releases Ci 4.12E-09 O.OOE+oO 2.45E-06 O.OOE+oO 2.45E-06 1st 2nd 3rd 4th B, Gas Abnormal Release Totals Ulits Year Totals Quarter Quarter Quarter Quarter There were no abnormal gaseous release for this period.

Page 33 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Site Dose Reg. Guide 1.21 Tables: Canal Reuse/Return tritium Only tables that pertain to site ground mode release are included. Unit 3 and Unit 4 combine their effluent to the canal system. The tables for continuous release from evaporation from the canal are considered ground releases are included.

1. Table A-18: Gaseous Effluents - Ground Level Release --Return - Continuous Mode

2. Table A-4: Dose Assessments 10 CFR Part 50, Appendix I: Dose due to Radioiodines, Tritium, and Particulates in Gaseous Releases Page 34 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Reg. Guide 1.21, Table A-1B, Gaseous Effluents - Canal Ret~rn/Re-Use Ground Level Continuous Mode Unit: Site Starting: 1-Jan-2018 Ending: 31-Dec-2018 Nuclides Released lklits 1STQuarter 2Nl Quarter 3RD Quarter 4TH Quarter Annual A. Rssion and Activation Gases No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+DO O.OOE+oO O.OOE+oO B. Iodines and Halogens No Nuclides Found Ci O.OOE+DO O.OOE+oO O.OOE+DO O.OOE+oO O.OOE+oO C. Particulates No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+DO O.OOE+oO O.OOE+oO D. Tritium H-3 Ci 3.33E+ol 2.60E+ol 6.77E+ol 1.33E+o2 2.60E+o2 E. Gross Alpha No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO F. Ca rbon-14 No Nuclides Found Ci O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO O.OOE+oO Page 35 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report TABLE A-4: Dose Assessments 10 CFR Part SO, Appendix I Doses due to Tritium Return From Closed Cooling Canal Evaporation Unit: Site January 2018 through December 2018 Organ Dose lklits 1STQuarter 2N> guarter 3RDQuarter 411i Quarter Annual Liver mRem 1.75E-03 1.37E-03 3.SSE-03 6.96E-03 1.36E-02 Limit mRem 5 5 5 5 10 Percent of Limit % 3.49E-02 2.73E-02 7.lOE-02 1.39E-01 1.36E-01 Thyroid mRem 1.75E-03 1.37E-03 3.SSE-03 6.96E-03 1.36E-02 Limit mRem 5 5 5 5 10 Percent of Limit % 3.49E-02 2.73E-02 7.lOE-02 1.39E-01 1.36E-01 Kidney mRem 1.75E-03 1.37E-03 3.SSE-03 6.96E-03 1.36E-02 Limit mRem 5 5 5 5 10 Percent of Limit % 3.49E-02 2.73E-02 7.lOE-02 1.39E-01 1.36E-01 Lung mRem 1.75E-03 1.37E-03 3.SSE-03 6.96E-03 1.36E-02 Limit mRem 5 5 5 5 10 Percent of Limit % 3.49E-02 2.73E-02 7.lOE-02 1.39E-01 1.36E-01 Gi-W mRem 1.75E-03 1.37E-03 3.SSE-03 6.96E-03 1.36E-02 Limit mRem 5 5 5 5 10 Percent of Limit % 3.49E-02 2.73E-02 7.lOE-02 1.39E-01 1.36E-01 Page 36 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Page 37 of 45

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, ms 2.00 E+OO 2.37 E+01 sludge, evaporator Ci 2.23 E+02 bottoms, etc.

b. Dry compressible ms 2.84 E+02 2.00 E+OO waste (Note 1) Ci 3.27 E+OO C. Irradiated components, ms 6.25 E-02 2.00 E+OO control rods, etc. Ci 9.07 E-01

d. Other: ms 0.00 E+OO 2.00 E+OO non-compressed Ci 0.00 E+OO

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

a. NUCLIDE UNITS VALUE Fe-55 % 12.57 Co-60 % 6.52 Ni-63 % 75.01 Cs-137 % 2.35

b. NUCLIDE UNITS VALUE Fe-55 % 14.21 Co-58 % 1.64 Co-60 % 7.36 Ni-63 % 72.2 Page 38 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report TABLE 6 C. NUCLIDE UNITS VALUE Fe-55 % 49.09 Co-60 % 46.57 Ni-63 % 4.04

d. NUCLIDE UNITS VALUE None Shipped

3. SOLID WASTE DISPOSITION (Note 2)

Number of Shipments Mode of Transportation Destination 12 Sole use truck Energy Solutions Bear Creek Road Facility (Oak Ridge, TN) 1 Sole use truck Energy Solutions Gallaher Road Facility (Kingston, TN) 2 Sole use truck Energy Solutions Erwin Resin Solutions Facility (Erwin, TN) B. IRRADIATED FUEL SHIPMENTS (Disposition) None. Page 39 of 45

2018 -- Turkey Point Annual Radioactive Effluent Relea~e Report TABLE 6 SOLID WASTE SHIPMENTS Type of Type of Waste Total Total Curies Principal R.G. Waste Container Classification Volume (Note 3) Radionuclides 1.21 Cubic (Note 4) (Note 5) Category (Note 6) Feet Class A 1.09 E+04 2.27 E+02 None Compressible 1.b, 1.d General W~ste Design Class 8/C None Shipped No solidification or absorbing agents were used or needed in the shipment of these waste types Page 40 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report 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 Clive, Utah in accordance with the appropriate burial license activity limits. 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. NOTE4: Principle radionuclide refers to those radionuclides contained in the waste in concentrations greater than 0.01 times the concentration of the nuclide listed in Table 1 or 0.01 times the smallest concentration of the nuclide listed in Table 2 of 10 CFR 61.55. NOTE 5: Type of waste is specified as described in NUREG 0782, Draft Environment Impact Statement on 10 CFR 61 "Licensing Requirements for Land Disposal of Radioactive Waste". NOTE 6: Type of container refers to the transport package. Page 41 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report ATIACHMENTA Errata Data Section Page 42 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report Table 6A and 68 - Liquid and Gas Abnormal Release Summary Unit: 4 January 2017 through December 2017 1st 2nd 3rd 4th A. Liquid Abnormal Release Totals Units Year Totals Quarter Quarter Quarter Quarter

1. Number of Abnormal Releases 0 0 0 1 1

2. Total Activity of abnormal releases Ci O.OOE+oO O.OOE+oO O.OOE+oO 1.39E-06 1.39E-06 1st 2nd 3rd 4th B. Gas Abnormal Release Totals Units Year Totals Quarter Quarter Quarter Quarter

1. Number of Abnormal Releases 0 0 0 1 1

2. Total Activity of abnormal releases Ci O.OOE+oO O.OOE+oO O.OOE+oO 5.52E-03 5.52E-03 Page 43 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report TABLE A-4: Dose Assessments 10 CFR Part SO, Appendix I Air Doses Due To Gaseous Releases Unit: 4 January 2017 through December 2017 1ST 2N> 3RD 4TH Annual NG Dose ~its Quarter Quarter Quarter guarter Gamma Air mRad 2.36E-08 3.86E-08 8.64E-06 3.23E-07 9.02E-06 Limit mRad 5 5 5 5 10 Percent of Limit % 4.72E-07 7.72E-07 1.73E-04 6.46E-06 9.02E-05 Beta Air mRad 7.02E-08 1.15E-07 2.59E-05 9.SlE-07 2.70E-05 Limit mRad 10 10 10 10 20 Percent of Limit % 7.02E-07 1.15E-06 2.59E-04 9.SlE 1.35E-04 NG Total Body mRem 2.00E-08 3.27E-08 7.30E-06 2.74E-07 7.63E-06 Limit mRem N/A N/A N/A N/A 500 Percent of Limit % N/A N/A N/A N/A 1.53E-06 NG Skin mRem 4.71E-08 7.73E-08 1.72E-05 6.54E-07 1.SOE-05 Limit mRem N/A N/A N/A N/A 3000 Percent of Lim it % N/A N/A N/A N/A 6.00E-07 Page 44 of 45

2018 -- Turkey Point Annual Radioactive Effluent Release Report ATTACHMENT B Offsite Dose Calculation Manual {ODCM) Revision 26 Issued 12/06/18 Page 45 of 45

OFF':SITE DOSE CALCULATION MANUAL FQR GASEOUS AND LIQUID EFFLUENTS FROM THE TURKEY POINT PLANT UNITS 3 AND 4 REVISJGN ,26 GHANGE DATED 12/6/18 Florida Power*and LightCompany 12 /.6 / 18 Date

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL LIST OF EFFECTIVE PAGES Offsite Dose Calculation Manual Page Revision Page Revision Page Revision i 26 2-15 26 3-10 26 ii 26 2-16 26 3-11 26 iii 26 2-17 26 3-12 26 iv 26 2-18 26 3-13 26 V 26 2-19 26 3-14 26 vi 26 2-20 26 3-15 26 vii 26 2-21 26 3-16 26 viii 26 2-22 26 3-17 26 1-1 26 2-23 26 3-18 26 1-2 26 2-24 26 3-19 26 1-3 26 2-25 26 3-20 26 1-4 26 2-26 26 3-21 26 1-5 26 2-27 26 3-22 26 1-6 26 2-28 26 3-23 26 1-7 26 2-29 26 3-24 26 1-8 26 2-30 26 3-25 26 1-9 26 2-31 26 3-26 26 1-10 26 2-32 26 3-27 26 1-11 26 2-33 26 3-28 26 1-12 26 2-34 26 3-29 26 1-13 26 2-35 26 3-30 26 1-14 26 2-36 26 3-31 26 1-15 26 2-37 26 3-32 26 2-1 26 2-38 26 3-33 26 2-2 26 2A-1 26 3-34 26 2-3 26 2A-2 26 3-35 26 2-4 26 2A-3 26 3-36 26 2-5 26 2A-4 26 3-37 26 2-6 26 3-1 26 3-38 26 . 2-7 26 3-2 26 3-39 26 2-8 26 3-3 26 3-40 26 2-9 26 3-4 26 3-41 26 2-10 26 3-5 26 3-42 26 2-11 26 3-6 26 3-43 26 2-12 26 3-7 26 3-44 26 2-13 26 3-8 26 3-45 26 2-14 26 3-9 26 3-46 26 Rev26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL LIST OF EFFECTIVE PAGES Offsite Dose Calculation Manual Page Revision Page Revision Page Revision 3-47 26 3A-6 26 3B-39 26 3-48 26 3A-7 26 3B-40 26 3-49 26 3B-1 26 3B-41 26 3-50 26 3B-2 26 3B-42 26 3-51 26 3B-3 26 3B-43 26 3-52 26 3B-4 26 3B-44 26 3-53 26 3B-5 26 3B-45 26 3-54 26 3B-6 26 3B-46 26 3-55 26 3B-7 26 3B-47 26 3-56 26 3B-8 26 3B-48 26 3-57 26 3B-9 26 3B-49 26 3-58 26 3B-10 26 3B-50 26 3-59 26 3B-11 26 3B-51 26 3-60 26 3B-12 26 3B-52 26 3-61 26 3B-13 26 3B-53 26 3-62 26 3B-14 26 3B-54 26 3-63 26 3B-15 26 3B-55 26 3-64 26 3B-17 26 3B-56 26 3-65 26 3B-18 26 3B-57 26 3-67 26 3B-19 26 3C-1 26 3-68 26 3B-20 26 3C-2 26 3-69 26 3B-21 26 3C-3 26 3-70 26 3B-22 26 4-1 26 3-71 26 3B-23 26 4-2 26 3-72 26 3B-24 26 4-3 26 3-73 26 3B-25 26 4-4 26 3-74 26 3B-26 26 4-5 26 3-75 26 3B-27 26 4-6 26 3-76 26 3B-28 26 4-7 26 3-77 26 3B-29 26 4-8 26 3-78 26 3B-30 26 4-9 26 3-79 26 3B-31 26 5-1 26 3-80 26 3B-32 26 5-2 26 3-81 26 3B-33 26 5-3 26 3A-1 26 3B-34 26 5-4 26 3A-2 26 3B-35 26 5-5 26 3A-3 26 3B-36 26 5-6 26 3A-4 26 3B-37 26 5-7 26 3A-5 26 3B-38 26 5-8 26 ii Rev26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL LIST OF EFFECTIVE PAGES Offsite Dose Calculation Manual Page Revision 5-9 26 5-10 26 5-12 26 5-13 26 5-14 26 5-15 26 5-16 26 5-17 26 5-18. 26 5-19 26 5-20 26 5-21 26 5-22 26 5-23 26 5-24 26 5A-1 26 5A-2 26 5A-3 26 5A-4 26 5B-1 26 iii Rev 26

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 Definitions ..... .. .... ......... .. ........ .. ......... .. ..... ... .. ... .. .. ... ... .... .... ... ..... 1-6 Control 1.6 Applicability of Controls .. .... ........... .. .. .. ...... .. .. ... ...... ..... ... .... .... ... . 1 - 13 Control 1.7 Surveillance Requirements ........................................................ 1 - 14 Control 1.8 References..................................................................... 1 - 15 Figure 1.5-1 Deleted Figure 1.5-2 Plant Area Map 1 - 12 2.0 Radioactive Liquid Effluents Control 2.1 Liquid Effluent Monitoring Instrumentation, Functionality 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 Control 2.5 Doses from Return/ Reuse of Previously Discharged Radioactive Effluents .. .. ....... ... ........ .. ......... .. .. ... .. ...... .. .... ... .... ..... 2 - 35 Figure 2 - 1 Radioactive Liquid Waste ......... ,................................................. 2-4 Appendix 2A Radioactive Liquid Effluents Pathway Dose Transfer Factors ............................................................... 2A - 1 iv Rev 26

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/ Functionality and Alarm/Trip Setpoints .. ..... .. ... ....... 3 - 11 Control 3.2 Dose Rate from Radioactive Gaseous Effluents ........................ 3 - 28 Control 3.3 Air Dose from Noble Gases .... ... .. .. .. .. .. .. .... ... .... .... .... ... .. .. .......... 3 - 46 Control 3.4 Dose lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form .................................... 3 - 54 Control 3.5 Gaseous Radwaste Treatment System .. ..... .. .... .... .. .. .... .... ... ...... 3 - 69 Control 3.6 Radioactive Gaseous Effluent Accident Monitoring Instrumentation.......................................................... 3 - 72 Control 3.7 Explosive Gas Monitoring Program............................................. 3 - 78 Figure 3 - 1 Radioactive Gaseous Waste ...................................................... 3-9 Figure 3 - 2 Locations of Airborne Effluent Dose Calculations ...................... 3 - 10 Appendix 3A Reference Meteorology Annual Average Atmospheric Dispersion Factors ................................................ 3A - 1 Appendix 38 Pathway-Dose Transfer Factors.................................................. 38 - 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 Rev26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (continued 5.0 Radiological Environmental Monitoring Program Control 5.1 Conduct of Sampling and Analysis.............................................. 5-1 Control 5.2 Land Use Census........................................................................ 5 - 19 Control 5.3 lnterlaboratory Comparison Program.......................................... 5 - 21 Figure 5.1-1 Near Site Sampling Locations..................................................... 5 -17 Figure 5.1-2 Distant REMP Sampling Locations ............................................. 5 - 18 Appendix SA Turkey Point Supplemental Radiological Environmental Monitoring Program............................................. 5A - 1 Appendix 58 Turkey Point Groundwater Sampling Program to Support the Industry Initiative on Groundwater Protection..................................................... 58 - 1 vi Rev 26

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 (x/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 I, 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 Rev26

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 (LLDs). 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 Rev26

SECTION 1 ADMINISTRATIVE CONTROLS Rev26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS CONTROL 1.1 : ODCM REVIEW AND APPROVAL 1.1.1 Responsibility for Review The Chemistry Department Supervisor or designee shall perform a review of the ODCM annually. 1.1.2 Documentation of Reviews Following the performance of the annual review required by Section 1.1.1, the individual performing the review shall submit a report for PNSC approval. This report should contain the following information:

1. A copy of any requested changes to the ODCM.

2. Information necessary to support the rationale for the requested changes.

3. A determination that the requested changes will not reduce the accuracy or reliability of dose calculations or setpoint .

determinations.

4. If no changes are being requested, no actions are required.

1.1.3 Institution of Changes Changes to the ODCM shall become effective upon review and approval by the Plant General Manager, (PGM). 1.1.4 Licensee Initiated Changes to the ODCM

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

a. Sufficient information to support the changes together with the appropriate analysis or evaluation justifying the changes, and

b. A determination that the changes maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and Appendix 1 to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective after approval of the Plant General Manager, and

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

1- 1 Rev26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS CONTROL 1.2 : MAJOR CHANGES TO LIQUID, GASEOUS AND SOLID RADWASTE TREATMENT SYSTEMS* Licensee-initiated major changes to the Liquid, Gaseous, and Solid Radwaste Treatment Systems:

a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant General Manager. The discussion of each change shall contain:

(1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; (2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; (3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems; (4) An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License application and amendments thereto; (5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto; (6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the change is to be made; (7) An estimate of the exposure to plant operating personnel as a result of the change; and (8) Documentation of the fact that the change was reviewed and found acceptable by the PGM.

b. Shall become effective upon review and acceptance by the PGM.

Licensees may choose to submit the information called for in this Control as part of the annual FSAR update.

1-2 Rev26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS CONTROL 1.3: ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

An Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted by March 1 of each year and shall include:

a. A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B the_reof.

For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g., strong tight package, Type A, Type B) and solidification agent or absorbent (e.g., cement).

b. An annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.** This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous-effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time, and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. Approximate and conservative methods may be used in lieu of actual meteorological measurements. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in this OFFSITE DOSE CALCULATION MANUAL (ODCM).

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.

1-3 Rev26

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

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 non-functionality 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 tanl

~~0 C~~
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~~-a 0~~
i R-3-19 R-4-19 m Ilill eves 3 eves 4 IIIl I r z A
~ Iru I I I- -; .... 17 Slowdown Makeup waler and chemicals I Slowdown irn Vent to Atmosphere C
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TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.1: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION, FUNCTIONALITY AND ALARM/TRIP SETPOINTS The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.1-1 shall be FUNCTIONAL with their Alarm/Trip Setpoints set to ensure that the limits of Control 2.2 are not exceeded. The Alarm/ Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in this OFFSITE DOSE CALCULATION MANUAL (ODCM). APPLICABILITY : At all times, except as indicated in Table 2.1-1 ACTION:
a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel non-functional, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels FUNCTIONAL, take the ACTION shown in Table 2.1-1. Restore the non-functional instrumentation to FUNCTIONAL status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report pursuant to Administrative Control 1.3, why this non-functionality was not corrected in a timely manner.

c. The provisions of Administrative Control section 1.6.3 are not applicable.
SURVEILLANCE REQUIREMENTS 2.1.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 2.1-2. 2-5 REV. 26
TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.1 : RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION, FUNCTIONALITY AND ALARM/TRIP SETPOINTS (continued) TABLE 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT FUNCTIONAL ACTION
1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Line 1* 2.1.1

b. Steam Generator Slowdown Effluent Line 1 ** 2.1.2

2. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line 1* 2.1.3

b. Steam Generator Slowdown Effluent Line 1 *** 2.1.3 per Steam generator
Applicable during liquid effluent releases.
Applicable during blow down operations.
Applicable during blow down operations when Primary to Secondary Leakage is detected.
2-6 REV. 26
TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.1 : RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION, FUNCTIONALITY AND ALARMffRIP SETPOINTS, (continued) TABLE 2.1-1, (Continued) TABLE NOTATION ACTION 2.1.1 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided that prior to initiating a release:
a. At least two independent samples are analyzed in accordance with the surveillance requirement of Control 2.2.1, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve line-up; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 2.1.2 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross (beta or gamma) radioactivity at a lower limit of detection of no more than 1 X 10-7 microcuries/ml or analyzed isotopically (Gamma) at a lower limit of detection of at least 5 x 10-7 microcuries/ml :
a. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT 1-131, or b: At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curies/gram DOSE EQUIVALENT 1-131.
ACTION 2.1.3 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may co.ntinue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves may be used to estimate flow. 2-7 REV. 26
TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.1 : RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION, FUNCTIONALITY AND ALARM/TRIP SETPOINTS (continued) TABLE 2.1-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluents Line D p R (2) Q (1)

b. Steam Generator Blowdown D M R (2) Q (1)
~~Effluent Line~~
2. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line D (3) N.A. R Q

b. Steam Generator Blowdown D (3) N.A. R Q Effluent Lines TABLE NOTATIONS (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 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. 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. (3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. 2-8 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.1 : RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION, FUNCTIONALITY AND ALARM/TRIP SETPOINTS (continued) METHOD 2.1.1: LIQUID EFFLUENT MONITOR SURVEILLANCES The surveillances of Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release and Flow Rate Measurement Devices are scheduled by a site procedure. METHOD 2.1.2: ESTABLISHING LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS The alarm/trip setpoint for each liquid effluent radiation monitor is derived from 10 times the effluent concentration limits provided in 10 CFR Part 20, Appendix B, Table 2, Column 2 applied in the condenser cooling water mixing basin outflow. Radiation monitoring and isolation points are located in the steam generator blowdown lines, R-3-19, R-4-19, and the liquid waste disposal system line, R-18, through which radioactive waste effluent is eventually discharged into the canal basin (see Figure 2-1 ). The alarm/trip setpoint for each liquid effluent monitor is based upon the measurements of radioactivity in a batch of liquid to be released or in the continuous aqueous discharge. Sample measurements are performed according to ODCM Table 2.2-1. If the. calculated setpoint is less than the existing setpoint, the setpoint shall be reduced to the new setpoint. If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or be increased to the calculated value. Typically, the setpoint calculated using equation 2.1-1 yields a value that exceeds the range of the monitor. A. Setpoint for a Batch Release The liquid radwaste effluent line radiation monitor alarm setpoint for a batch release is determined with the equation below or a method which gives a lower setpoint value, as described in approved plant procedures. Sb = Ab S1
~~g + Bkg FEG b Eqn2.1-1 where:~~
Sb= radiation monitor alarm setpoint for a batch release, (cpm) laboratory counting rate (cpm/ml) or activity concentration (µCi/ml) of sample from batch tank 2-9 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.1 : RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION, FUNCTIONALITY AND ALARMffRIP SETPOINTS (continued) METHOD 2.1.2: ESTABLISHING LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS (continued) FECb= fraction of unrestricted area Effluent Concentration (EC) present in the condenser cooling water mixing basin outflow due to a batch release, determined in method 2.2.A. gb = detection efficiency of monitor detector; ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given batch sample (cpm per cpm/ml or cpm per
~~µCi/ml) which ever units are consistent with the units Ab.~~
8kg = background (cpm) St= A factor to allow for multiple sources from different or common release points. The allowable operating setpoints are administratively controlled by assigning a fraction of the total allowable release to each of the release sources. The assigned fraction for releases made from the Liquid Radwaste System is 0.7. B. Setpoint for a Continuous Release The liquid effluent line radiation monitor alarm setpoint for a continuous release is determined with the equation below or by a method which gives a lower setpoint value, as described in approved plant procedures. Eqn2.1-2 where: Sc = radiation monitor alarm setpoint for a continuous release, (cpm) Ac = laboratory counting rate (cpm/ml) or activity concentration (µCi/ml) of sample from continuous release FECc = fraction of unrestricted area EC present in the condenser cooling water mixing basin outflow due to a continuous release determined in method 2.2.B. 2-10 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.1 : RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION, FUNCTIONALITY AND ALARMffRIP SETPOINTS (continued) METHOD 2.1.2: ESTABLISHING LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, (continued) gc = detection efficiency of monitor detector; ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given continuous release sample, (cpm per cpm/ml or cpm per µCi/ml), whichever units are consistent with the units Ac. St = 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. The assigned fraction for releases made from each unit's Steam Generator Slowdown System is 0.1. BASIS 2.1 : RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarmff rip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten times the limits of 10 CFR Part 20. Equations 2.1-1 and 2.1-2 ensure that this limit is not exceeded. Since the resulting count rate of these equations typically yields a value higher than the monitor is capable of measuring, the actual trip, high, and alert alarm setpoints are set as described in approved plant procedures. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The factors established for St are based on allowing 10% of all releases to be made from each unit's Steam Generator Slowdown System, 70% from the Liquid Radwaste System, and 10% from unmonitored releases such as storm drains. 2-11 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.1 : RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION, FUNCTIONALITY AND ALARM!TRIP SETPOINTS (continued) METHOD 2.1.2: ESTABLISHING LIQUID EFFLUENT MONITOR ALARM AND TRIP SETPOINTS (continued) EXAMPLE CALCULATION : Liquid Radwaste Effluent Monitor Alarm Setpoint for a Batch Release The monitor alarm setpoint for liquid batch releases is based on the fraction of the unrestricted area EC (FEC) that will be present in the condenser cooling water mixing basin as a result of the activity concentration present in the liquid radwaste to be released. The monitor setpoint can be determined using equation from Method 2.1.2 for batch and continuous releases respectively. Example: where: radiation monitor alarm setpoint for a batch release, (cpm) laboratory counting rate (cpm/ml) or activity concentration (µCi/ml) of sample from batch tank FECb= fraction of unrestricted area EC present in the condenser cooling water mixing basin outflow due to a batch release; determined from equation 2.2-2. gb = detection response of monitor detector; ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given batch sample (cpm per cpm/ml or cpm per µCi/ml which ever units are consistent with the units Ab)- Bkg = background, (cpm) St=* 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. The assigned fraction for releases made from the Liquid Radwaste System is 0.7. 2-12 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.1 : RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION, FUNCTIONALITY AND ALARM/TRIP SETPOINTS (continued) Determine the monitor setpoint when: 6 X 10-4 8.85 x 10-5 µCi/ml 15,000 cpm/µCi/ml 0.7 Bkg = 10,000 cpm Sb = 8 85 10
~~X -5/ *7 6 X 10-X 1.5 X 10 4 + 1 X 104 = 11,550 cpm 2-13 REV. 26~~
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 DEFINITIONS) 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. 2.2.2 The 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 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.2: CONCENTRATIONS IN RADIOACTIVE LIQUID EFFLUENTS, (continued) TABLE 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF LOWER LIMIT LIQUID RELEASE SAMPLING ANALYSIS ACTIVITY OF DETECTION TYPE FREQUENCY FREQUENCY ANALYSIS (LLD)<1 1 , µCi/ml p p Principle Gamma 5 X 10*7
1. Batch Waste Emitters (3l Each Batch Each Batch Release Tanks(2l 1-131 1 X 10-6 p Dissolved and One Batch/M M Entrained Gases 1 X 10*5 (Gamma Emitters) p M H-3 1 X 10"5 Each Batch Composite (4l Gross Alpha 1 X 10*7 p Q Sr-89, Sr-90 5 X 10-8 Each Batch Composite (4l Fe-55 1 X 10-6

2. Continuous 5 X 10*7 Principal Gamma Releases <5l Emitters (3l w w

a. Steam Generator BlowdownC7l 1-131 1 X 10-6 Dissolved and Entrained M (8l M C8l Gases 1 X 10-5 (Gamma Emitters)
M (8l H-3 1 X 10-5 W(8) Composite (6l Gross Alpha 1 X 10*7 Q (8) Sr-89, Sr-90 5 X 10-8 W(8) Composite (6l Fe-55 1 X 10-6
~~b. Storm Drain 5 X 10*7 Principle Gamma M M Emitters C3l 1-131 1 X 10-6 2-15 REV. 26~~
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.2: CONCENTRATIONS IN RADIOACTIVE LIQUID EFFLUENTS, (continued) TABLE 2.2-1 (continued) TABLE NOTATIONS (1) The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radio chemical separation : LLD = 4.66 Sb 6 E
V * (2.22 x 10 )

Y * [exp (-11,Llt)]
Where: LLD = the "a priori" lower limit of detection as defined above for a blank sample (microCurie per unit mass or volume), sb = the counting rate of a blank sample, or the standard deviation of the background counting rate, as appropriate (counts per minute) E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 2.22 x 106 = the number of disintegrations per minute per micro Curie, Y = the fractional radio chemical yield, when applicable, 11, = the radioactive decay constant for the particular radionuclide, and Llt = the elapsed time between the midpoint of sample collection and the time of counting (for plant effluents, not environmental samples). Typical values of E, V, Y, and Lit should be used in the calculation. 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. (2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling. 2-16 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.2: CONCENTRATIONS IN RADIOACTIVE LIQUID EFFLUENTS, (continued) TABLE 2.2-1 (Continued) TABLE NOTATIONS (Continued) (3) The principal gamma emitters for which the LLD specification exclusively applies are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 1.3. Nuclides, which are below the LLD for the analysis, should not be reported as being present at the LLD for that nuclide. When a radionuclide's calculated LLD is greater than it's listed LLD limit, the calculated LLD should be assigned as the activity of the radionuclide; or, the activity of the radionuclide .should be calculated using measured ratios with those radionuclides which are routinely identified and measured. (4) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. (5) A continuous release is the discharge of liquid wastes of a non discrete volume, e.g., from a volume of a system that has an input flow during the continuous release. (6) Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release. (7) Sampling and analysis of steam generator blowdown is not required during Mode 5 or 6. (8) Sampling and analysis of steam generator blowdown on the applicable unit is only necessary for these species when primary to secondary leakage is occurring as indicated by the condenser air ejector noble gas activity monitor. (See Control 3.1, Table 3.1-1, Item 2a). 2-17 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.2: CONCENTRATIONS IN RADIOACTIVE LIQUID EFFLUENTS. (continued) METHOD 2.2 : AQUEOUS CONCENTRATION The diluted concentration of radionuclides in the condenser cooling water mixing basin outflow is estimated with the equation : Cz; = C; * ;; Eqn. 2.2-1 where: Czi = concentration of radionuclide i in the condenser cooling water mixing basin outflow, (µCi/ml) Ci = concentration of radionuclide i in liquid radwaste released, (µCi/ml) F1 / F2 = dilution F1 = flow in radioactive liquid discharge line, (gal/min).* F2 = total condenser cooling water flow, (gal/min).* This value has been conservatively estimated at 156,000 gpm per circulating water pump for units 3 & 4, and 134,000 gpm per circulating water pump for units 1 & 2, based on expected condenser fouling and pump curves.
~~F1 and F2 may have any suitable but identical units of flow, (volume/time).~~
A. Batch Release A sample of each batch of liquid radwaste is analyzed before release for 1-131 and other principal gamma emitters. With the activity concentration in a batch sample, b, based on the total isotopic activity, the fraction of the unrestricted area effluent concentration (FEC) due to a batch release is derived by using the ratio of the individual isotopic concentrations and their related effluent concentration (EC). 2-18 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.2 : CONCENTRATIONS IN RADIOACTIVE LIQUID EFFLUENTS, (continued) METHOD 2.2 : Aqueous Concentration, batch release, (continued) FECb is estimated with the equation :
~~= I Cz; for gamma emitting isotopes + I Cz; for beta emitting isotopes ; EC; ; EC; Eqn 2.2-2 where:~~
FECb = fraction of the unrestricted area EC present in the condenser cooling water mixing basin outflow due to a batch release. C2 i = concentration of radionuclide i in the water in the condenser cooling water mixing basin out flow, (µCi/ml); determined from equation 2.2-1. ECi = ten times the activity concentration limit in water of radionuclide i according to 10 CFR 20, Appendix B, Table 2, Column 2, (µCi/ml). The factor for beta emitting isotopes is an adjustment to account for radionuclides not measured prior to release but measured in the quarterly and monthly samples per ODCM Table 2.2-1, i.e., Sr-89, Sr-90, Fe-55, H-3. This value is calculated from previously measured data. A gross beta-gamma analysis of a batch release may be performed when an isotopic analysis is not available. The fraction of the unrestricted EC due to a batch release using the gross beta-gamma analysis can be estimated by: FEG = Cb Eqn. 2.2-3 5x10-7 where: Cb = Concentration of radioactivity in the water in the condenser cooling water mixing basin outflow due to a batch release. 5x10-7 = The activity concentration limit in water of the most restrictive isotope routinely released in liquid effluents, from a pressurized water reactor, according to 10 CFR 20, Appendix B, Table 2, Column 2, (µCi/ml). 2-19 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.2: CONCENTRATIONS IN RADIOACTIVE LIQUID EFFLUENTS. (continued) METHOD 2.2 : Aqueous Concentration, batch release, (continued) B. Continuous Release Continuous aqueous discharges are sampled and analyzed according to the schedule in ODCM Table 2.2-1. The fraction of the unrestricted area EC present in a continuously discharged radioactive stream, FECc, is derived from an isotopic analyses. The fraction of the unrestricted area EC can be derived using the ratio of the individual isotopic concentrations and their related ECs. FE Cc is estimated with the equation: FECc = L C,; for gamma emitting isotopes + L C,; for beta emitting isotopes
~~; EC; ; EC; Eqn 2.2-4 where:~~
FECc = fraction of the unrestricted area EC present in the condenser cooling water mixing basin outflow due to a continuous release Czi = concentration of radionuclide i in the water in the condenser cooling water mixing basin outflow determined from equation 2.2-1, (µCi/ml) ECi = ten times the activity concentration limit in water of radionuclide i according to 10CFR20, Appendix B, Table 2, Column 2, (µCi/ml) The factor for beta*emitting isotopes is an adjustment to account for radionuclides not measured prior to release but measured in the quarterly and monthly samples per ODCM Table 2.2-1, i.e., Sr-89, Sr-90, Fe-55, H-3. This value is calculated from previously measured data. A gross beta-gamma analysis of a continuous release may be performed when an isotopic analysis is not available. The fraction of the unrestricted EC due to a continuous release using the gross beta-gamma analysis can be estimated by: FECc=
~~. Cc Sxl0-1 Eqn. 2. 2-5 where:~~
Cc = Concentration of radioactivity in the water in the condenser cooling water mixing basin outflow due to a continuous release. 5x10-7 = The activity concentration limit in water of the most restrictive isotope routinely released in liquid effluents, from a pressurized water reactor, according to 10 CFR 20, Appendix B, Table 2, Column 2, (µCi/ml). 2-20 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.2 : CONCENTRATIONS IN RADIOACTIVE LIQUID EFFLUENTS, (continued) METHOD 2.2 : Aqueous Concentration, continuous, (continued) C. Cumulative Release To ensure that the unrestricted area EC is not exceeded during periods of multiple releases, the fraction of EC determined for each type of release is summed to determine a total release fraction using the following equation: FECr = FECb + FECc Eqn 2.2-6 Where: FE Cr = the total fraction of the unrestricted area EC released. FECb = the fraction of the unrestricted area EC due to batch releases FECc = the fraction of the unrestricted area EC due to continuous releases. BASIS 2.2: This control applies to the release of radioactive materials in liquid effluents from all units at the site. The specification of "10 times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2" provides the datum against which the liquid effluent monitor setpoints are determined pursuant to Control 2.1. In essence, Control 2.2 is an instantaneous limit.
The concentration limit for "dissolved or entrained noble gases" is based upon the assumption that Xe-135 is the controlling radioisotope and its associated Maximum Permissible Concentration (MPC) in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
Adherence to Controls 2.3 and 2.4 provide assurance that levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will, on the average, be a small fraction of the concentration limits and result in exposures to MEMBERS OF THE PUBLIC within the objectives of Appendix I of 10 CFR Part 50 and 40 CFR 190. Control 2.2 permits the flexibility of operation, compatible with considerations of health and safety, to provide a dependable source of power even under circumstances that temporarily result in elevated releases, but still within the limit as specified in 10 CFR Part 20.1302 (b)(2)(ii). 2-21 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.2: CONCENTRATIONS IN RADIOACTIVE LIQUID EFFLUENTS, (continued) EXAMPLE CALCULATION: Determination of Radionuclide Concentration in the Condenser Cooling Water Mixing Basin. Czi, from a Liquid Release. where: Ci = concentration of radionuclide i in the liquid radwaste released, µCi/ml, obtained from nuclide analyses report for the liquid release sample taken prior to release. F1 = Flow rate from monitor tank= 100 gal/min. F2 = Total condenser cooling water flow= 156,000 gpm/circulating pump; total capacity Units 3 and 4 = 8 pumps x 156,000 = 1,248,000 gal/min. Note: When determining actual release concentrations, contact units 1 and 2 to determine how many, if any, circulating pumps were running during release. The flow of these pumps must be included when determining F2. Example: For a monitor tank analysis (from Nuclide Analysis Report), Ci is equal to the following concentrations: Ci F1/F2 Czi Co-60 8 X 10-5 8 X 10-5 6.4 X 10-9 Co-58 2 X 10-6 8 X 10-5 1.6 X 10-10 Cr-51 7 X 10-7 8 X 10-5 5.6 X 10-11 Mn-54 5 X 10-6 8 X 10-5 4.0 X 10-1o Cs-137 5 X 10-7 8 X 10-5 4.0 X 10-11 1-131 3 X 10-7 8 X 10-5 2.4 X 10-11 Fe-55 4 X {o-s 8 X 10-5 3.2 X 10-og Sr-90 2 X 10-7 8 X 10-5 1.6 X 10-11 H-3 7 X 10-2 8 X 10-5 5.6 X 10-6 F1/F2 -- 100 gpm/1,248,000 gpm -- 8 x 10-0 2-22 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.2: CONCENTRATIONS IN RADIOACTIVE LIQUID EFFLUENTS, (continued) EXAMPLE CALCULATION: Determination of the Fraction of the Unrestricted Area EC from a Batch Release of Liquid Radwaste, FECb FECb = L C,; for gamma emitting isotopes + L C,; for beta emitting isotopes I EC; i EC; where: Czi = Radionuclide concentration in condenser cooling water mixing basin,
~~µCi/ml ECi = Ten times the effluent concentration from 10 CFR 20 Appendix B, Table 2, Column 2, µCi/ml Example:~~
1: FEC for a release must be less than 1 or the release cannot be made. 1: FEC for the batch release in example 1 above is calculated as follows: Nuclide Czi ECt C2/ECi FECb 9 5 4 Co-60 6.4 X 10- 3 X 10- 2.1 X 10- 2.1 X 10-4 Co-58 1.6 X 10-10 8 X 10-5 2.0 X 10-6 2.0 X 10-6 11 Cr-51 5.6 X 10- 5 X 10-3 1.1x10-8 1.1 X 10-8 Mn-54 4.0 X 10-10 3 X 10-4 1.3 X 10-6 1.3 X 10-5 Cs-137 4.0 X 10-11 1x10-5 4.0 X 10-6 4.0 X 10-6 1-131 2.4 X 10-11 1 X 10-5 2.4 X 10-6 2.4 X 10-6 09 5 5 Fe-55 3.2 X 10- 1 X 10-4 3.2 X 10- 3.2 X 10-11 Sr-90 1.6 X 10- 5 X 10-7 3.2 X 10-5 3.2 X 10-5 H-3 5.6 X 10-6 1 X 10-3 5.6 X 10-3 5.6 X 10-3 1: 5.6 X 10-6 -- 5.9 X 10-3 5.9 X 10-3
~~Use ten times the value of the Effluent Concer)tration (EC) values given in 10 CFR 20, Appendix B, Table 2, Column 2.~~
The fraction of unrestricted area EC from a continuous release is calculated in the same manner as the batch release shown above. 2-23 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.3: DOSE FROM RADIOACTIVE LIQUID EFFLUENT The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see DEFINITIONS) shall be limited:
a. During any calendar quarter to less than or equal to 1.5 mRem to the whole body and to less than or equal to 5 mRems to any organ, and

b. During any calendar year to less than or equal to 3 mRems to the whole body and to less than or equal to 10 mRems to any organ.
~~APPLICABILITY : At all times. ACTION:~~
a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant Control 1.6.6, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Administrative Control section 1.6.3 are not applicable.
SURVEILLANCE REQUIREMENTS 2.3.1 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in this ODCM at least once per 31 days. 2-24 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.3: DOSE FROM RADIOACTIVE LIQUID EFFLUENT, (continued) METHOD 2.3: Control 2.3 requires the dose or dose commitment to a member of the public from radioactive materials released in liquid effluents from each unit to unrestricted areas be limited to s 1.5 mRem to the whole body and s 5 mRem to any organ during any calendar quarter and to s 3 mRem to the whole body and s*10 mRem to any organ during any calendar year. Surveillance 2.3.1 requires the dose or dose commitment to a member of the public due to radioactive material released in liquid effluent to be calculated on a cumulative quarterly and annual basis at least once per 31 days. The condenser cooling water basin and closed canal system which receives aqueous effluent is entirely on FP&L property, without surface discharge off site, and FP&L does not permit members of the public to use the water. As a result, potential exposure of a member of the public to radioactive material originating in aqueous effluent is limited to irradiation of persons by canal shoreline deposits. Surveillance 2.3.1 is satisfied by calculating the cumulative total body dose to a
- person who may be irradiated by radionuclides deposited on the cooling canal shoreline from radioactive liquid effluent. Compliance with the organ dose limit is assured as long as the total body dose is below its limit.
~~The model that is used to evaluate doses due to radioactivity in liquid effluent is : D = 0.23 LL Afliore/ine~~
~~Ck* F1k*tk k V*Af Eqn. 2.3-1 where:~~
D* = total body or organ dose due to irradiation by radionuclides on the shorelines which originated in a liquid effluent release, (mRem) ICi 60min 3785ml 0.23 = units conversion constant = ---x x--- 106 uCi hr
gal transfer factor relating a unit aqueous concentration of radionuclide i to a dose commitment rate to specific organs and the total body of an exposed person. Values for Ai are tabulated in Appendix 2A, (mReni/Ci*gal/min) the concentration of radionuclide i in the undiluted liquid waste to be discharged that is represented by sample k, (µCi/ml) 2-25 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.3: DOSE FROM RADIOACTIVE LIQUID EFFLUENT, (continued) METHOD 2.3, (continued) F1k = liquid waste discharge flow during release represented by sample k, (gal/min) V = cooling canal effective volume, approximately 3. 75 X 109 gallons
~~= period of time (hours) during which liquid waste represented by sample k is discharged = effective decay constant (A.i + F3N, min-1).~~
where: A.j = The radioactive decay constant F3 = Canal-ground water interchange flow, approximately 2.25 x 105 gal/min Radionuclide concentrations (Cik) in effluent are measured by the sampling and analysis program specified in Control 2.2 Table 2.2-1. Typically, more than 90 percent of the potential irradiation from radionuclides deposited along the shoreline is due to Mn-54, Co-58, Co-60, Cs-134, and Cs-137. Of these radionuclides, Co-60 has the maximum dose transfer factor, Ai. Thus, for the purpose of assessing compliance with Surveillance 2.3.1, the radioactive effluent source term may be either: a) principal gamma emitters measured by the effluent sampling and analysis program, or b) all gamma emitters measured by the effluent sampling and analysis program assumed to be Co-60. The dose that is calculated for the purpose of assessing compliance with Surveillance 2.3.1 is based on all gamma emitting isotopes being Co-60. The dose calculated when preparing the Annual Radioactive Effluent Release Report uses the concentration of principal gamma emitters measured by the effluent sampling and analysis program. 2-26 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.3: DOSE FROM RADIOACTIVE LIQUID EFFLUENT, (continued) BASIS 2.3: This specification applies to the release of radioactive materials in liquid effluents from each unit at the site. For units with shared Radwaste Systems, the liquid effluents from the shared system are to be proportional among the units sharing that system. This Control is provided to implement the requirements and guidelines of Appendix I, 10 CFR Part 50. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dose calculation methodology and parameters in this ODCM implement the requirements in Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology 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 and 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 Radiological Environmental Monitoring Program verifies, other than periodic trace levels of tritium, exposure to members of the public due to the canal-ground water interchange through the hydrological shift into the ocean is not a significant pathway. The usage factors contained in Reg Guide 1.109, table E-5, show that the teenager is the most exposed receptor for shoreline deposition. For purposes of calculating dose due to liquid effluents to a member of the public, the teenager will be considered the target receptor. Since Florida Power & Light restricts access to the canal system, and does not allow drinking, fishing, or bathing in the canals; the only exposure pathway is to the total body from shoreline deposition. 2-27 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.3: DOSE FROM RADIOACTIVE LIQUID EFFLUENT. (continued) Example Calculation: Determination of Cumulative Dose from Radioactive Liquid Effluents. The dose or dose commitment to a member of the public from radioactive liquid effluent shall be calculated on a cumulative quarterly and cumulative annual basis at least once per 31 days. The dose or dose commitment from radioactive liquid releases at Turkey Point is based on the irradiation of a teenager on the canal shoreline, the most restrictive age group and is calculated using equation 2.3-1. D= 0.23 LL k Atoreline
C;k

V*X F1k

fk where:
D= total body or organ dose due to irradiation by radionuclides on the shoreline which originated in a liquid effluent release, (mRem). lCi 60min 3785ml 0.23 = units conversion constant = ---x x--- 106 uCi hr gal Ai = transfer factor relating a unit aqueous concentration of radionuclide i (µCi) to dose commitment rate to specific organs and the total body of an exposed person tabulated in Appendix A, (mRem/Ci . min/gal). Cik = the concentration of radionuclide in the undiluted liquid waste to be discharged that is represented by sample k, (uCi/ml). F1k = liquid waste discharge flow during release represented by sample k, (gal/min) V = cooling canal effective volume, approximately 3. 75 x 109 gallons. tk = period of time (hours) during which liquid waste represented by sample k is discharged.
~~;!,~ = effective decay constant (Ai + F3/ V, minute -1 ).~~
where: Ai = the radioactive decay constant F3 = canal-ground water interchange flow, approximately 2.25 x 105 gal/min 2-28 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.3: DOSE FROM RADIOACTIVE LIQUID EFFLUENT (continued) Example Calculation: Determination of Cumulative Dose from Radioactive Liquid Effluents, (continued). Example: The concentration of radionuclides in the undiluted liquid waste discharges to the condenser cooling water mixing basin during the month of February was determined by summing the results of the radionuclide analysis sheets for each sample taken prior to the release. The total concentration of each radionuclide was: Radionuclide Cus(µCi/ml) Co-60 4 X 10-4 Co-58 1X 10-5 Cr-51 4X 10-6 Cs-134 5X 10-6 Cs-137 2X 10-6 Mn-54 2X 10-5 1-131 1X 10-6 Note that the above data represents ~k ; that is, the sum over the number of releases for the period of February. The average flow rate from the monitor tanks during the releases (F1k) = 100 gpm. The total period of time for the releases (tk) was 15 hours. The cumulative whole body dose to a teen due to these releases is determined by summing the dose from each radionuclide as shown in the following worksheet. 2-29* REV. 26
~~. TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.3 : DOSE FROM RADIOACTIVE LIQUID EFFLUENT, (continued}~~
Example Calculation: Determination of Cumulative Dose from Radioactive Liquid Effluents, (continued) WORKSHEET FOR DOSE TO WHOLE BODY FROM LIQUID RELEASE Radio-nuclide C;k A1 F1k !1 (0.23)A;xC;kx F1kxt1 AJ F3'V A.*1 V'A.*1 D Co-60 4E-4 9.45E+3 100 15 1.30E+3 2.53E-7 6.0E-5 6.02E-5 2.26E+5 5.BE-3 Co-58 1E-5 1.67E+2 100 15 5.76E-1 6.BOE-6 6.0E-5 6.68E-5 2.50E+5 2.3E-6 Cr-51 4E-6 2.06E+O 100 15 2.84E-3 1.74E-5 6.0E-5 7.74E-5 2.90E+5 9.BE-9 Cs-134 5E-6 3.08E+3 100 15 5.31E+O 6.39E-7 6.0E-5 6.06E-5 2.27E+5 2.3E-5 Cs-137 2E-6 4.54E+3 100 15 3.13E+O 4.37E-8 6.0E-5 6.00E-5 2.25E+5 1.4E-5 Mn-54 2E-5 6.09E+2 100 15 4.20E+O 1.54E-6 6.0E-5 6.15E-5 2.31E+5 1.BE-5 1-131 1E-6 7.59E+O 100 15 2.62E-3 5.98E-5 6.0E-5 1.19E-4 4.46E+5 5.9E-9 Dose to Teenager from all Nuclides, L; = 5.9E-3 Total whole body dose to teen from irradiation by radionuclides on the shoreline from radioactivity released in month of February is 5.9E-3 mRem. Cumulative dose for first quarter would be sum of January dose + February dose. Cumulative annual dose in this example would be the same as the quarterly dose.
~~In this case the organ dose is the same as the whole body dose since the dose transfer factors for direct radiation is the same.~~
REV. 26 2-30
TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.4: LIQUID RADWASTE TREATMENT SYSTEM The Liquid Radwaste Treatment System shall be FUNCTIONAL and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see DEFINITIONS) would exceed 0.06 mRem to the whole body or 0.2 mRem to any organ in a 31-day period. APPLICABILITY : At all times. ACTION:
a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Control 1.6.6, a Special Report that includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any non-functional equipment or subsystems, and the reason for the non-functional,

2. Action(s) taken to restore the non-functional equipment to FUNCTIONAL status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Administrative Control section 1.6.3 are not applicable.
SURVEILLANCE REQUIREMENTS 2.4.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized. 2.4.2 The installed Liquid Radwaste Treatment System shall be consjdered FUNCTIONAL by meeting Controls 2.2 and 2.3. 2-31 REV. 26
TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.4: LIQUID RADWASTE TREATMENT SYSTEM, (continued) METHOD 2.4 : Projected Dose Control 2.4 requires that the Liquid Radwaste Treatment System be functional and appropriate subsystems of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses from each unit to unrestricted areas due to liquid effluents, when averaged over a 31 day period, would exceed 0.06 mRem to the total body or 0.2 mRem to any organ. Surveillance 2.4.1 requires the doses, to unrestricted areas, due to radioactive material released in liquid effluent to be projected at least once per 31 days unless the liquid radwaste treatment system is being fully utilized. The monthly dose is normally projected by computing the doses to the total body and most exposed organ accumulated during the most recent month and assuming the result represents the projected doses for the current month. The dose during the preceding month will be computed as described in Method 2.3. Alternately, this requirement may be satisfied by extrapolating the dose to date during the current month to include the entire month. The dose to date is calculated as described in Method 2.3 The dose is projected with the relation: 3l*D P= X Eqn 2.4-1 where: P = the projected total body or organ dose during the month, (mRem). 31 = number of days in a calendar month, (days) X = number of days in current month to date represented by available radioactive effluent sample, (days) D = total body or organ dose to date during current month calculated according to Method 2.3, (mRem) REV. 26 2-32
TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.4: LIQUID RADWASTE TREATMENT SYSTEM, (continued) BASIS 2.4: LIQUID RADWASTE TREATMENT SYSTEM This control applies to the release of radioactive materials in liquid effluents from each unit at the site. For units with shared Radwaste Systems, the liquid effluents from the shared system are to be proportioned among the units sharing that system. The FUNCTIONALITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the objectives given in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Appendix I, 10 CFR Part 50 for liquid effluents. REV. 26 2-33
TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.4: LIQUID RADWASTE TREATMENT SYSTEM, (continued) Example Calculation: Determination of the Projected Dose The dose, to unrestricted areas, from liquid effluent must be projected at least once per 31 days when the liquid radwaste treatment system is not being fully utilized. The dose projection can be made using the equation: 31
~~D P=~~
X where: p = the projected total body or organ dose during the month (mRem) 31 = number of days in a calendar month, (days) X = number of days in current month to date represented by available radioactive effluent sample, (days) D = total body or organ dose to date during current month calculated according to section 2.4, (mRem). Example: The whole body dose calculated as of March 15 was 7.5 x 10-2 mRem. The projected dose for the 31 day period in March would be:
*p __ 31 x D __ 31 x 7.5 x10-2 mrem 1 = 1. 55 x 10- mrem 15 15 Thus, in accordance with Control 2.4, appropriate portions of the liquid radwaste treatment system must be used to reduce releases of radioactivity since the dose from each unit would exceed 0.06 mRem.
REV. 26 2-34
TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS CONTROL 2.5: Doses from Return/Reuse of Previously Discharged Radioactive Effluents The dose contribution from return/re-use of previously radioactive effluents (tritium from the cooling canals) should be calculated at the end of each year. If the dose form this particular pathway is greater than 10 percent of the total dose from all pathways from plant release (liquid, gaseous, iodine and particulates with
>8 day half life's) the dose from the return of previously discharged effluents is to be reported in the annual effluent report. The total body, each organ and each age group dose should be calculated at the end of the year unless it is known to be less than 10 percent of all doses.
BASIS 2.5: As stated in Regulatory Guide 1. 109. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents forthe Purpose of Evaluation Compliance with 10CFR 50.59, Appendix 1, an effluent pathway becomes significant if an evaluation yields an additional dose increment equal to or more than 10 percent of the total from all pathways considered. The cooling canals for Turkey Point Nuclear Power Plant are used for heat rejection from 4 of the 5 electric power generating units on site. The cooling canals cover an area of 5,900 acres and evaporation is the process that removes heat from the cooling canal system. The cooling canals are also the release point for liquid radioactive effluents from the nuclear units. Tritium exists in the cooling canals due to release from the nuclear units. The cooling canals are totally on FPL owned property and access is limited. Members of the public do not spend time regularly in the vicinity of the canals. Exposure to the general public by direct exposure is unlikely. The site uses a teenager as the target receptor, with the pathway being total body from shoreline deposition. No drinking, fishing or bathing is allowed in the canals. No drinking water pathway is available in the owner controlled area. The most likely pathway is inhalation of evaporated tritium by a person offsite. REV. 26 2-35
TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS METHOD 2.5: Tritium dose due to inhalation is calculated using the meteorology form the current year (using the ground level mode of release), the periodic tritium analysis of the cooling canals and the evaporation rate for the cooling canal system.
~~1. Calculation for release from Evaporation .for each month:~~
~~Three methods can be used to calculate monthly evaporation from the cooling canal system~~
~~a. The Analytical formula used to calculate monthly evaporation rate was developed by Meyer (1905) based on Dalton's Law. This is an empirical formula.~~
Ev= C * (Es - Ed) x (1 + U25/10) Where: Ev = evaporation from a lake or pond in inches water per month Es = saturation vapor pressure (inches of Hg) of air at the water temperature (1 foot depth) Ed = actual vapor pressure (inches of Hg) of air. Equal to Es x Relative Humidity (RH) U25 = average wind velocity (miles/hr) at a height of 25 feet above the lake or surrounding area C = Coefficient that equals 15 for shallow ponds like the cooling canals.
b. Derive the average evaporation rate from historical data or using the Penman-Monteith evapotranspiration (ET) rate for the local area.

c. If, available use evaporation rates published by the State Department of Agriculture or other government agency.
REV. 26 2-36
TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS
~~2. Calculate the Annual Release from the Cooling Canals:~~
Calculation of monthly evaporation rate using the analytical methods above or derive using the Penman-Monteith evapotranspiration rate. Use of the monthly evaporation rate, the effective canal evaporation area (sq. meters) and the average tritium concentration (pCi/liter) is used to determine the monthly tritium release (Ci/month) from the cooling canals.
~~a. Effective Canal Evaporation Area in square meters (m2). The canal is divided into 4 areas.~~
~~Section 1: 1,861,781 m2 Section 2: 4,181,745 m2 Section 3: 5,008,982 m2 Section 4: 9,388,080 m2~~
b. Average tritium concentration is determined using REMP samples of the cooling canal surface water.

c. Calculate the Annual Release of Tritium:
~~Or = L ( Larea~~
EVave * (Lrconc

1.0E-09 ))
Where: Or = Annual Tritium Release from Cooling Canals (Ci) Larea = Effective Canal Evaporation Area in the section EVave = Evaporation in inches per month times 25.4mm/inch times meter/1000mm, meters of evaporation. Lrcanc = Average tritium concentration. 3 1.0E-09 = Ci/1.0E12 pCi
~~liter/1000cm 3 *1.0E6cm 3/meter REV. 26 2-37~~
~~TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS~~
~~3. Calculate the Dose Due to Evaporation from the Cooling Canals:~~
~~Calculation of dose due to evaporation from each segment of the canal uses the methodology from NUREG-0133, Preparation of Radiological Effluent Technical Specification for Nuclear Plants.~~
~~a. Calculate the Tritium concentration from each section.~~
~~Otsect = I:(Ot~~
X/Q

3.17E+04)
Where: Otsect = Total tritium concentration from the individual section at point of interest (pCi/m3) 01 = Yearly Tritium Release for the individual section (Ci/yr) X/Q = Atmospheric dispersion factor at the off-site location of interest. 3.17E+04 = Conversion factor, (1.0e12 pCi/Ci)/(8760 hr/yr)*3600 sec/hr)
~~b. Calculate the dose for the individual age groups at the point of interest.~~
Dosea,poi = (Otsect )* (DFA)a * (BR)a Where: Dosea,poi = Total tritium dose for age group (a) at point of interest (mRem) for the year Qtsect = Total tritium concentration from the individual section at point of interest (pCi/m3) (DFA)a = Organ inhalation factor for tritium at the point of interest of age group "a" (mRem/pCi). For tritium the dose factor is same for the liver, thyroid, kidney, lung and Gi-LLI (no bone does). Infant= 4.62E-07, Child= 3.04E-7, Teen= 1.59E-7, and Adult = 1.58E-07 (mRem/pCi). Values for inhalation dose factor were taken from Table E-7, 8, 9 and 10 of Regulatory Guide 1.109. (BR)a = Breathing rate of age group "a". Infant= 1400, Child= 3700, Teen = 8000, and Adult= 8000 (m3/yr). Values for breathing rate were taken from Table E-5 of Regulatory Guide 1.109. REV. 26 2-38
APPENDIX 2A RADIOACTIVE LIQUID EFFLUENTS PATHWAY DOSE TRANSFER FACTORS REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS APPENDIX2A RADIOACTIVE LIQUID EFFLUENTS PATHWAY DOSE TRANSFER FACTORS The following page lists the Shoreline Dose Transfer Factors used for the calculation of doses for demonstrating compliance with Controls 2.3 and 2.4. The exposure pathway of concern is Whole Body Dose from Shoreline Deposits. The Drinking Water, Fish, and Shellfish pathways do not exist. The water is saline, non potable. Access to the canals is restricted to authorized personnel; fishing and collection of canal borne items is prohibited, except for collection of material in support of environmental monitoring activities. The skin dose factors, listed in table E-6 of RG 1.109<1), are, at worst, 50 % greater than the external dose factors; the dose limits to the skin ("any organ", Control 2.3) are at least 3 times greater; therefore, the external pathway is 'most limiting'. The Shoreline Dose Transfer Factors were calculated in accordance with the methodology described in Appendix A.2.c of RG 1.109, with the appropriate dimensional conversions to incorporate Curies, gallons, etc. The dimensions of the following factors are mRem in a year per curie released in an effluent release rate of 1 gallon per minute.
1. Regulatory Guide 1.109, Revision 1, October 1977; "Calculation of annual doses to man from routine releases of reactor effluents for the purpose of evaluating compliance with 10 CFR 50, Appendix I".
REV. 26 2A-1
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS DOSE FACTORS FOR LIQUID DISCHARGES BASED ON 1 Cl/YR RELEASE OF EACH ISOTOPE IN DISCHARGE FLOW OF 1 GPM WITH NO ADDITIONAL DILUTION PATHWAY- DISCHARGE CANAL SHORLINE DEPOSITS AGE GROUP - ADULT ORGAN DOSE (MREM) NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 0. 0. 0. 0. 0. 0. 0. CR-51 3.69-01 3.69E-01 3.69E-01 3.69E-01 3.69E-01 3.69E-01 4.36E-01 3.69E-01 MN-54 1.09E+02 1.09E+02 1.09E+02 1.09E+02 1.09E+02 1.09E+02 1.28+02 1.09E+02 FE-55 0. 0. 0 0. 0. 0. 0. 0. FE-59 2.17E+01 2.17E+01 2.17E+01 2.17E+01 2.17E+01 2.17E+01 2.55E+01 2.17E+01 C0-58 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 3.51E+01 3.00E+01 C0-60 1.69E+03 1.69E+03 1.69E+03 1.69E+03 1.69E+03 1.69E+03 1.99E+03 1.69E+03 ZN-65 5.86E+01 5.86E+01 5.86E+01 5.86E+01 5.86E+01 5.86E+01 6.74E+01 5.86E+01 RB-88 7.11E-01 7.11E-01 7.11E-01 7.11E-01 7.11 E-01 7.11E-01 8.12E-01 7.11E-01 SR-89 1.71E-03 1.71 E-03 1.71E-03 1.71 E-03 1.71 E-03 1.71 E-03 1.98E-03 1.71 E-03 SR-90 4.23E-01 4.23E-01 4.23E-01 4.23E-01 4.23E-01 4.23E-01 4.99E-01 4.23E-01 Y-91 8.54E-02 8.54E-02 8.54E-02 8.54E-02 8.54E-02 8.54E-02 9.61E-02 8.54E-02 ZR-95 3.96E+01 3.96E+01 3.96E+01 3.96E+01 3.96E+01 3.96E+01 4.62E+01 3.96E+01 ZR-97 4.32E-01 4.32E-01 4.32E-01 4.32E-01 4.32E-01 4.32E-01 5.04E-01 4.32E-01 NB-95 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.27E+01 1.08E+01 M0-99 4.66E-01 4.66E-01 4.66E-01 4.66E-01 4.66E-01 4.66E-01 5.37E-01 4.66E-01 RU-103 8.69E+OO 8.69E+OO 8.69E+OO 8.69E+OO 8.69E+OO 8.69E+OO 1.01 E+01 8.69E+OO RU-106 3.30E+01 3.30E+01 3.30E+01 3.30E+01 3.30E+01 3.30E+01 3.97E+01 3.30E+01 AG-110M 2.82E+02 2.82E+02 2.82E+02 2.82E+02 2.82E+02 2.82E+02 3.29E+02 2.82E+02 SB-124 4.72E+01 4.72E+01 4.72E+01 4.72E+01 4.72E+01 4.72E+01 5.45E+01 4.72E+01 SB-125 1.81E+02 1.81E+02 1.81E+02 1.81E+02 1.81 E+02 1.81E+02 2.05E+02 1.81E+02 TE-125M 1.22E-01 1.22E-01 1.22E-01 1.22E-01 1.22E-01 1.22E-01 1.68E-01 1.22E-01 TE-127M 6.94E-02 6.94E-02 6.94E-02 6.94E-02 6.94E-02 6.94E-02 7.68E-02 6.94E-02 TE-129M 3.04E+OO 3.04E+OO 3.04E+OO 3.04E+OO 3.04E+OO 3.04E+OO 3.57E+OO 3.04E+OO TE-131M 8.41 E-01 8.41 E-01 8.41 E-01 8.41 E-01 8.41E-01 8.41 E-01 3.68E+01 8.41 E-01 TE-132 3.66E+OO 3.66E+OO 3.66E+OO 3.66E+OO 3.66E+OO 3.66E+OO 4.31E+OO 3.66E+OO 1-131 1.36E+OO 1.36E+OO 1.36E+OO 1.36E+OO 1.36E+OO 1.36E+OO 1.65E+OO 1.36E+OO 1-133 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-01 2.38E-01 1.95E-01 CS-134 5.51E+02 5.51E+02 5.51E+02 5.51E+02 5.51E+02 5.51E+02 6.43E+02 5.51E+02 CS-136 1.18E+01 1.18E+01 1.18E+01 1.18E+01 1.18E+01 1.18E+01 1.33E+01 1.18E+01 CS-137 8.13E+02 8.13E+02 8.13E+02 8.13E+02 8.13E+02 8.13E+02 9.48E+02 8.13E+02 BA-140 1.32E+01 1.32E+01 1.32E+01 1.32E+01 1.32E+01 1.32E+01 1.50E+01 1.32E+01 LA-140 1.52E+OO 1.52E+OO 1.52E+OO 1.52E+OO 1.52E+OO 1.52E+OO 1.72E+OO 1.52E+OO CE-141 1.08E+OO 1.08E+OO 1.08E+OO 1.08E+OO 1.08E+OO 1.08E+OO 1.22E+OO 1.08E+OO CE-143 1.82E-01 1.82E-01 1.82E-01 1.82E-01 1.82E-01 1.82E-01 2.07E-01 1.82E-01 CE-144 8.94E+OO 8.94E+OO 8.94E+OO 8.94E+OO 8.94E+OO 8.94E+OO 1.03E+01 8.94E+OO NP-239 1.35E-01 1.35E-01 1.35E-01 1.35E-01 1.35E-01 1.35E-01 1.56E-01 1.35E-01 2A-2 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS PATHWAY - DISCHARGE CANAL SHORELINE DEPOSITS AGE GROUP - TEENAGER ORGAN DOSE (MREM) NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 0. 0. 0. 0. 0. 0. 0. CR-51 2.06E+OO 2.06E+OO 2.06E+OO 2.06E+OO 2.06E+OO 2.06E+OO 2.43E+OO 2.06E+OO MN-54 6.09E+02 6.09E+02 6.09E+02 6.09E+02 6.09E+02 6.09E+02 7.15E+02 6.09E+02 FE-55 0. 0. 0. 0. 0. 0. 0. 0. FE-59 1.21E+02 1.21E+02 1.21E+02 1.21E+02 1.21E+02 1.21E+02 1.42E+02 1.21E+02 C0-58 1.67E+02 1.67E+02 1.67E+02 1.67E+02 1.67E+02 1.67E+02 1.96E+02 1.67E+02 C0-60 9.45E+03 9.45E+03 9.45E+03 9.45E+03 9.45E+03 9.45E+03 1.11 E+04 9.45E+03 ZN-65 3.27E+02 3.27E+02 3.27E+02 3.27E+02 3.27E+02 3.27E+02 3.76E+02 3.27E+02 RB-88 3.97E+OO 3.97E+OO 3.97E+OO 3.97E+OO 3.97E+OO 3.97E+OO 4.53E+OO 3.97E+OO SR-89 9.54E-03 9.54E-03 9.54E-03 9.54E-03 9.54E-03 9.54E-03 1.11E-02 9.54E-03 SR-90 2.36E+OO 2.36E+OO 2.36E+OO
2.36E+OO 2.36E+OO 2.36E+OO 2.79E+OO 2.36E+OO Y-91 4.??E-01 4.??E-01 4.??E-01 4.??E-01 4.??E-01 4.??E-01 5.35E-01 4.??E-01 ZR-95 2.21E+02 2.21E+02 2.21E+02 2.21E+02 2.21E+02 2.21E+02 2.58E+02 2.21E+02 ZR-97 2.41E+OO 2.41E+OO 2.41 E+OO 2.41E+OO 2.41E+OO 2.41E+OO 2.82E+OO 2.41E+OO NB-95 6.01E+01 6.01E+01 6.01E+01 6.01E+01 6.01E+01 6.01E+01 7.07E+01 6.01 E+01 M0-99 2.60E+OO 2.60E+OO 2.60E+OO 2.60E+OO 2.60E+OO 2.60E+OO 3.00E+OO 2.60E+OO RU-103 4.85E+01 4.85E+01 4.85E+01 4.85E+01 4.85E+01 4.85E+01 5.66E+01 4.85E+01 RU-106 1.85E+02 1.85E+02 1.85E+02 1.85E+02 1.85E+02 1.85E+02 2.21E+02 1.85E+02 AG-110M 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.84E+03 1.58E+03 SB-124 2.64E+02 2.64E+02 2.64E+02 2.64E+02 2.64E+02 2.64E+02 3.04E+02 2.64E+02 SB-125 1.01E+03 1.01E+03 1.01E+03 1.01E+03 1.01E+03 1.01E+03 1.14E+03 1.01E+03 TE-125M 6.84E-01 6.84E-01 6.84E-01 6.84E-01 6.84E-01 6.84E-01 9.38E-01 6.84E-01 TE-127M 3.B?E-01 3.B?E-01 3.B?E-01 3.B?E-01 3.87E-01 3.B?E-01 4.29E-01 3.87E-01 TE-129M 1.70E+01 1.70E+01 1.70E+01 1.70E+01 1.70E+01 1.70E+01 1.99E+01 1.70E+01 TE-131M 4.69E+OO 4.69E+OO 4.69E+OO 4.69E+OO 4.69E+OO 4.69E+OO 2.05E+02 4.69E+OO TE-132

2.05E+01 2.05E+01 2.05E+01 2.05E+01 2.05E+01 2.05E+01 2.41 E+01 2.05E+01 1-131 7.59E+OO 7.59E+OO 7.59E+OO 7.59E+OO 7.59E+OO 7.59E+OO 9.22E+OO 7.59E+OO 1-133 1.09E+OO 1.09E+OO 1.09E+OO 1.09E+OO 1.09E+OO 1.09E+OO 1.33E+OO 1.09E+OO CS-134 3.08E+03 3.08E+03 3.08E+03 3.08E+03 3.08E+03 3.08E+03 3.59E+03 3.08E+03 CS-136 6.57E+01 6.57E+01 6.57E+01 6.57E+01 6.57E+01 6.57E+01 7.44E+01 6.57E+01 CS-137 4.54E+03 4.54E+03 4.54E+03 4.54E+03 4.54E+03 4.54E+03 5.29E+03 4.54E+03 BA-140 7.38E+01 7.38E+01 7.38E+01 7.38E+01 7.38E+01 7.38E+01 8.36E+01 7.38E+01 LA-140 8.46E+OO 8.46E+OO 8.46E+OO 8.46E+OO 8.46E+OO 8.46E+OO 9.59E+OO 8.46E+OO CE-141 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.79E+OO 6.02E+OO CE-143 1.02E+OO 1.02E+OO 1.02E+OO 1.02E+OO 1.02E+OO 1.02E+OO 1.16E+OO 1.02E+OO CE-144 4.99E+01 4.99E+01 4.99E+01 4.99E+01 4.99E+01 4.99E+01 5.76E+01 4.99E+01 NP-239 7.52E-01 7.52E-01 7.52E-01 7.52E-01 7.52E-01 7.52E-01 8.71E-01 7.52E-01 2A-3 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS PATHWAY- DISCHARGE CANAL SHORELINE DEPOSITS AGE GROUP - CHILD ORGAN DOSE (MREM) NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 0. 0. 0. 0. 0. 0. 0. CR-51 4.30E-01 4.30E-01 4.30E-01 4.30E-01 4.30E-01 4.30E-01 5.09E-01 4.30E-01 MN-54 1.27E+02 1.27E+02 1.27E+02 1.27E+02 1.27E+02 1.27E+02 1.49E+02 1.27E+02 FE-55 0. 0. 0. D. 0. D. D. D. FE-59 2.53E+01 2.53E+01 2.53E+01 2.53E+D1 2.53E+01 2.53E+01 2.98E+01 2.53E+01 C0-58 3.50E+01 3.50E+01 3.50E+D1 3.50E+01 3.50E+01 3.50E+01 4.10E+D1 3.50E+01 C0-60 1.97E+03 1.97E+D3 1.97E+D3 1.97E+03 1.97E+03 1.97E+03 2.32E+03 1.97E+03 ZN-65 6.84E+01 6.84E+01 6.84E+D1 6.84E+01 6.84E+01 6.84E+01 7.87E+01 6.84E+01 RB-88 8.29E-01 8.29E-01 8.29E-01 8.29E-01 8.29E-D1 8.29E-01 9.47E-01 8.29E-01 SR-89 1.99E-03 1.99E-03 1.99E-03 1.99E-03 1.99E-03 1.99E-03 2.31 E-03 1.99E-03 SR-90 4.93E-01 4.93E-01 4.93E-01 4.93E-01 4.93E-01 4.93E-01 5.83E-01 4.93E-01 Y-91 9.96E-02 9.96E-02 9.96E-02 9.96E-02 9.96E-02 9.96E-02 1.12E-01 9.96E-02 ZR-95 4.62E+01 4.62E+01 4.62E+01 4.62E+01 4.62E+01 4.62E+01 5.39E+01 4.62E+01 ZR-97 5.03E-01 5.03E-01 5.03E-01 5.03E-01 5.03E-01 5.03E-01 5.88E-01 5.03E-01 NB-95 1.26E+01 1.26E+01 1.26E+01 1.26E+01 1.26E+01 1.26E+01 1.48E+01 1.26E+01 M0-99 5.43E-01 5.43E-01 5.43E-01 5.43E-01 5.43E-01 5.43E-01 6.27E-01 5.43E-01 RU-103 1.01 E+01 1.01E+01 1.01 E+01 1.01E+01 1.01 E+01 1.01 E+01 1.18E+01 1.01 E+01 RU-106 3.86E+01 3.86E+01 3.86E+01 3.86E+01 3.86E+01 3.86E+01 4.83E+01 3.86E+01 AG-11DM 3.29E+02 3.29E+02 3.29E+02 3.29E+02 3.29E+02 3.29E+02 3.84E+02 3.29E+02 SB-124 5.51E+01 5.51E+01 5.51E+01 5.51E+01 5.51E+01 5.51E+D1 6.35E+01 5.51E+01 SB-125 2.11E+02 2.11E+02 2.11 E+02 2.11E+02 2.11 E+02 2.11E+02 2.39E+02 2.11E+02 TE-125M 1.43E-01 1.43E-01 1.43E-01 1.43E-01 1.43E-01 1.43E-01 1.98E-01 1.43E-01 TE-127M 8.09E-02 8.09E-02 8.09E-02 8.09E-02 8.09E-02 8.09E-02 8.97E-02 8.09E-02 TE-129M 3.54E+DO 3.54E+DO 3.54E+DD 3.54E+OD 3.54E+OO 3.54E+OO 4.18E+DO 3.54E+DO TE-131M 9.80E-01 9.80E-01 9.80E-01 9.80E-01 9.8DE-01 9.80E-01 4.28E+01 9.BOE-01 TE-132 4.28E+OO 4.28E+OO 4.28E+OO 4.28E+OO 4.28E+OO 4.28E+OO 5.03E+OO 4.28E+OO 1-131 1.59E+DO 1.59E+OD 1.59E+OO 1.59E+OO 1.59E+OO 1.59E+OO 1.93E+OO 1.59E+OO 1-133 2.28E-01 2.28E-01 2.28E-01 2.28E-01 2.28E-01 2.28E-01 2.77E-01 2.28E-01 CS-134 6.43E+02 6.43E+02 6.43E+02 6.43E+02 6.43E+02 6.43E+02 7.50E+02 6.43E+02 CS-136 1.37E+01 1.37E+01 1.37E+01 1.37E+01 1.37E+01 1.37E+01 1.58E+01 1.37E+01 CS-137 9.48E+02 9.48E+D2 9.48E+02 9.48E+02 9.48E+02 9.48E+02 1.11E+D3 9.48E+D2 BA-140 1.54E+01 1.54E+01 1.54E+01 1.54E+01 1.54E+01 1.54E+01 1.75E+01 1.54E+01 LA-140 1.77E+OO 1.77E+OO 1.77E+OO 1.77E+OO 1.77E+OO 1.77E+OO 2.00E+OO 1.77E+OO CE-141 1.26E+DD 1.26E+OD 1.26E+DD 1.26E+OO 1.26E+DD 1.26E+OO 1.42E+DD 1.28E+DD CE-143 2.13E-01 2.13E-01 2.13E-01 2.13E-01 2.13E-01 2.13E-01 2.42E-01 2.13E-01 CE-144 1.04E+01 1.04E+01 1.04E+01 1.04E+D1 1.04E+01 1.04E+01 1.20E+01 1.04E+01 NP-239 1.57E-01 1.57E-01 1.57E-01 1.57E-01 1.57E-01 1.57E-01 1.82E-01 1.57E-01 2A-4 REV. 26
SECTION 3 RADIOACTIVE GASEOUS EFFLUENTS REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT OBJECTIVES and SYSTEM DESCRIPTION A. OBJECTIVES To provide calculational methodology needed to assure compliance with 10 CFR 20 and 10 CFR 50, which requires the following determinations and surveillances: o Radionuclide concentrations in gaseous effluents o The dose rate, due to radioactive gaseous effluents to areas at and beyond the site boundary are maintained within the limits of Control 3.2
~~Total body dose rate from radioactive noble gases Skin dose rate from radioactive noble gases Organ dose rate from radioiodines, tritium, and particulates with half-lives greater than 8 days.~~
o Determine that the cumulative quarterly and annual doses per reactor at and beyond the site boundary, due to noble gases, are maintained below the limits of Control 3.3 at least once per 31 days. o Determine that the cumulative quarterly and annual doses per reactor at and beyond the site boundary from radioiodines, tritium, and particulates with half-lives greater than 8 days, are maintained below the limits of Control 3.4 at least once per 31 days. o Project the doses due to gaseous releases from each unit at least once per 31 days when gaseous radwaste treatment systems are not being fully utilized.
8. BASES Radioactive gaseous effluents from Turkey Point Units 3 and 4 are released through two monitored release points; a common plant vent via a stack above the Containment Building (-200 ft.) and the Unit 3 spent fuel pit vent (-110 ft.). Unmonitored radioactive airborne releases can also occur from the secondary steam systems of each unit if primary to secondary leakage is occurring. Accounting for the quantity of these unmonitored airborne releases, during periods of primary to secondary leakage, are performed using approved plant procedures and the most accurate means available.
The effluent sources (refer to Figure 3-1) for each release point are tabulated in Table 3-1. The airborne releases from all these sources are treated as a mixed mode release from a single location for dose calculational purposes. They are considered a release from a single location due to their close proximity to one another relative to the distance to the site boundary. 3-1 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS* EFFLUENT OBJECTIVES and SYSTEM DESCRIPTION (Cont'd) B. BASIS, (Cont'd) A mixed mode release is selected since the majority of the releases made from the site fit the mixed mode release model as described in Regulatory Guide 1.111. Compliance for beta and gamma dose limits at and beyond the site boundary for noble gas effluents is determined by assessing the dose rate and/or dose at the location where the minimum atmospheric dispersion occurs at the site boundary since the atmospheric dispersion will be higher at all other points off-site. This minimum dispersion occurs at the site boundary 1950 meters WNW of the plant where the dispersion factor is 1.3 x 10-6 sec/m 3 (see Figure 3-2). This value was extrapolated from the tables in Appendix 3A and are periodically evaluated against actual meteorological data to ensure the validity of these tables. The dose rate due to tritium, 1-131, 1-133, and radioactive particulates with half lives greater than 8 days at and beyond the site boundary is assessed by determining the dose rate to a hypothetical infant's thyroid via the inhalation pathway. The basis for this approach is NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" which states: the dose factors are dependent on the specific organ and on the age group. The infant is the most restrictive age group for the dose rate calculations and the most restrictive organ is the thyroid via eitherthe inhalation or grass-cow-milk pathway. The dose from tritium, 1-131, 1-133, and particulate is calculated by assuming a cow on pasture 4.5 miles West of the plant unless there is a milk producer in a more conservative location. At that location the reference atmospheric deposition factor, D/Q, is equal to 5 x 10-10 m-2 (see Figure 3-2). This value was extrapolated from the tables in Appendix 3A and are periodically evaluated against actual meteorological data to ensure the validity of these tables. The estimate of carbon-14 (C-14) released from the Turkey Point Nuclear Plant is derived from the EPRI document, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents", Report 1021106, issued December 2010. The site specific source term values used in the Turkey Point calculations are taken from Section 4-28 of this report, and employ the proxy generation rate values for a Westinghouse reactor. The actual annual operating data for the units is employed for the calculations to derive the total curies released for each unit. Dose calculations for C-14 were obtained by using the methodology provided in Regulatory Guide (RG) 1.109 Rev 1-1977, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I", for the applicable pathways. These calculations used the respective X/Q values for the sectors from the ODCM. 3-2 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT* OBJECTIVES and SYSTEM DESCRIPTION (Cont'd) B. BASIS, (Cont'd) For the on-site visitor close from C-14, the actual occupancy factor for annual inhalation rate is applied for determining inhalation (Use in lieu of the Regulatory Guide (RG) 1.109 annual inhalation rate. The reference document used for determination of the inhalation rate in RG 1.109 is International Commission on Radiological Protection (ICRP) 23 - 1975, "Report of the Task Group on Reference Man", 1975. Sampling and analysis is performed as outlined in ODCM Table 3.2-1. Principal gamma emitters for batch gaseous effluents, from Gas Decay Tanks or Containment Purges, which are released via the Plant Vent are Noble Gases only. The iodines and particulates are collected on filter elements in the effluent monitors and are considered continuous releases. This method of accounting for iodine and particulate in batch releases is performed to preclude over accounting for these emissions since the ventilation path is the same as for continuous releases. C. GASEOUS RADWASTE SYSTEM Radioactive and potentially radioactive gases from units 3 and 4 Containment Buildings, the Auxiliary Building, unit 4 Spent Fuel Pit, and Radwaste Building 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 and 4 Spent Fuel Pit, and the Radwaste Building 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 the monitored plant vent. 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 two release points. The gaseous effluent streams monitoring points, and effluent discharge points are illustrated schematically in Figure 3-1. 3-3 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT OBJECTIVES and SYSTEM DESCRIPTION (Cont'd) C. GASEOUS RADWASTE SYSTEM (Cont'd) 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 and Unit 3 Spent Fuel Pit vent). Tritium activity is determined on monthly grab samples from the plant vent and Unit 3 Spent Fuel Pit and by a grab sample from each containment purge. During Refueling outages, the affected unit's Containment Equipment Hatch and Refueling Water Storage Tank vent are potential effluent pathways. Both locations are monitored by use of grab samples and reported in the annual report. 3-4 REV. 26
OBJECTIVES and SYSTEM DESCRIPTION (Cont'd) C. GASEOUS RADWASTE SYSTEM, (Cont'd) Additional grab samples are obtained and analyzed if the conditions identified in Notes 4,5,6 and 7 of ODCM Table 3.2-1 exist, i.e., tritium grab samples once per 24 hours when the refueling canal is flooded, tritium grab samples at least weekly from the spent fuel pool ventilation exhaust when spent fuel is in the spent fuel pool, and sampling shall also be performed at least once per day for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one (1) hour and analyses shall be completed within 48 hours of changing if both the following conditions are met: (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 the effluent activity has increased by more than a factor of 3. Activities measured by these additional samples should be included in the cumulative dose calculations. Noble gas activity released is measured by continuous noble gas monitors installed in each discharge point for release types listed in ODCM Table 3.2-1. The quantity of radioactive noble gas activity not accounted for by grab samples can be determined by integrating the release rate measurement from each effluent noble gas monitor. 3-5 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT OBJECTIVES and SYSTEM DESCRIPTION (Cont'd) C. GASEOUS RADWASTE SYSTEM, (Cont'd) 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 Oj - h where:
Qj = total measured gaseous radioactivity release via a stack or vent during counting interval j, (µCi) 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; (cm3 /ft3 ) h = effluent noble gas monitor calibration or counting rate response for noble gas gamma radiation,* ~pm
µCi/cm 3 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.
where: C = The concentration of the individual isotope released. Fj = The mass of unmonitored water and steam released through unmonitored pathways. Mw = Mass rate of make up water Mb = Mass rate of blowdown Ms = Mass rate of steam from monitored sources Tj = Time interval for the period being quantified 3-6 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT OBJECTIVES and SYSTEM DESCRIPTION (Cont'd) C. GASEOUS RADWASTE SYSTEM, (Cont'd) The distribution of radioactive noble gases in a gaseous effluent stream is determined by gamma spectrum analysis of gas samples from that stream. Results of previous analyses may be averaged to obtain a representative distribution. When necessary, due to an uncontrolled release, samples from similar components in the same system can be used to determine a representative distribution. If fi represents the fraction of radionuclide i in a given effluent stream, based on the isotopic distribution of that stream, then the quantity of radionuclide i released in a given gaseous effluent stream during counting interval j is: where: Qii = quantity of radionuclide i released in a given gaseous effluent stream during counting interval j, (µCi) fi = the fraction of radionuclide i released in a given effluent stream In the event the radioactive noble gas distribution is not obtainable from sample(s) taken during the current period the distribution will be obtained from recent data if available. Some gaseous effluents from both Units 3 and 4, whose sources are identified in Table 3-1, discharge in common through the plant vent. To assure that the effluents are within allowable limits per reactor, the measured release are allocated equally to both Units 3 and 4 for Gas Decay Tanks, Steam Jet Air Ejector Vents and all ventilc;1tion systems exhausting into the Plant Vent Stack. Unit 3 Spent Fuel Pit Vent, Containment purges, and Steam Generator Slowdown Vents are allocated to each unit as appropriate. 3-7 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT OBJECTIVES and SYSTEM DESCRIPTION (Cont'd) Table 3-1 Atmospheric Gaseous Release Points at the Turkey Point Units 3 and 4 Effluent Source Release Point Gas decay tanks Plant vent Radwaste Building Plant vent Auxiliary Building Plant vent Containment Purge Plant vent No. 4 spent fuel pit Plant vent No. 3 spent fuel pit Spent Fuel Pit vent Air ejectors Plant vent Steam generator Slowdown vent blowdown 3-8 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT FIGURE 3-1 RADIOACTIVE GASEOUS WASTE Steam Steam Safeties Durn"ps Unit 3 Unit 4 Dt!mps Safatlas Vent l'rimary Go~lcinf E~haust Biowdown S.J:A.E. ** *slowdown flash and Gland Flosh Tank Se~I Exh_au~t Tank 7,000 cfm Unit 3 Unit 4 c11nfoinni!fnt ContoinmeM. 7,000
~~~----'cfm To eves Holcjup Tanks - - - ~ - -1 for reuse'. . ---;::::===:;::--,~~
525 cu.ft. - I--------~ Layl']dry
~~.Area Ga_s Decay Tonk (6) eves* Waste 9'!~~~
Hole@, cOrflPre~:(ors 1.nl~akage HEPA f(lt,er Tanks cfm ~ - - - ~ - - - ~ J\uxilfa*fy Bldg, cfm Ventilation* ,system Roughing 'i-iEPA Filter Filters icioo cfm Unlf 3 Uriit 4 Fuei Pit Fuel Pit Area Area Prefilter 2000 cfm lf!l.ea~.<ige New Rad Wcste Building HEPA Filter
** '.CYCS - Ch~m..lc~I ;1:ind Volume Control System ** .SJl>,E - ;Steam Jet A.ir Ejecto'r .' . - - Etflu'e'nt M'onltorln;/ .lnstrumeritiltlori ,@,, CaskHandlirig Facility,'2000 cfm 3-9 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT FIGURE 3-2 LOCATIONS OF AIRBORNE EFFLUENT DOSE CALCULATIONS Locations at which doses due to airborne effluent the Turkey Point Nuclear Plant are calculated:
1. Beta and gamma doses to air, 1950 meters WNW.

2. Maximally exposed person, 5800 meters WNW.

3. Assumed beef and milk cow, 7250 meters W.
~~'51!'1W .,,. ,~~
3 -10 REV. 26
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 .. The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.1-1 shall be OPERABLE/ FUNCTIONAL with their Alarm/ Trip Setpoints set to ensure that. the limits of Control 3.2 are not exceeded. The Alarm I Trip Setpoints of these channels meeting Control 3.2 shall be determined and adjusted in accordance with the methodology and parameters in this ODCM. APPLICABILITY: As shown in Table 3.1-1 ACTION:
a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable / non-functional or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE/ FUNCTIONAL, take the ACTION shown in Table 3.1-1. Restore the inoperable I non-functional instrumentation to OPERABLE/ FUNCTIONAL status within 30 days and, if unsuccessful explain in the next Annual Radioactive Effluent Release Report pursuant to Administrative Control 1.3 why this in operability/ non-functional was not corrected in a timely manner.

c. The provisions of Administrative Control section 1.6.3 are not applicable.
SURVEILLANCE REQUIREMENTS Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE/ FUNCTIONAL by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 3.1-2. 3 - 11 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL3.1 Radioactive Gaseous Effluent Monitoring Instrumentation, Operability/ Functionality and Alarm/Trip Setpoints, (Cont'd) TABLE 3.1-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE/ FUNCTIONAL 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 (PRMS) 1 # 3.1.3

d. Effluent System Flow Rate Measuring Device 1 ## 3.1.2 3 -12 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability/ Functionality and Alarm I Trip Setpoints, (Cont'd)
~~TABLE 3.1-1 (Cont'd)~~
~~RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE/ FUNCTIONAL APPLICABILITY ACTION~~
3. Plant Vent System (Include Unit 4's Spent Fuel Pool, Unit 3 and Unit 4 Steam Jet Air Ejector Vents)

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 - 13 REV. 26~~
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability/ Functionality and Alarm / Trip Setpoints (Cont'd) TABLE 3.1-1 (Cont'd) 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 FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, the contents of the tank(s) may be relea_sed 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 FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours. ACTION 3.1.3 - With the number of channels OPERABLE/ FUNCTIONAL less than required by the Minimum Channels OPERABLE/ FUNCTIONAL requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for radioactivity within 24 hours. These monitors may have Technical Specification requirements and action statements. ACTION 3.1.4 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL 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 hours of the channel being declared non-functional, and analyzed at least weekly. 3 - 14 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability/ Functionality and Alarm / Trip Setpoints (Cont'd) TABLE 3.1-1 (Cont'd) TABLE NOTATION ACTION 3.1.5 With the number of channels FUNCTIONAL less than required by the Minimum Channels FUNCTIONAL 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 hours. 3 - 15 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability/ Functionality and Alarm I Trip Setpoints, (Cont'd) 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 (PRMS) D M R (3) Q (2) #

b. Effluent System Flow Rate Measuring Device D (4) N.A. R N.A. ##
3 - 16 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation: Operability/ Functionality and Alarm/ Trip Setpoints, (Cont'd) TABLE 3.1-2 (Cont'd) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL MODES FOR WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE IS INSTRUMENT.T CHECK CHECK CALIBRATION TEST REQUIRED
3. Plant Vent System (Include Unit 4's Spent Fuel Pool, Unit 3 and Unit 4 Steam Jet Air Ejector Vents)

a. Noble Gas Activity Monitor (SPING or PRMS) 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. 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 - 17 REV. 26~~
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation: Operability/ Functionality and Alarm / Trip Setpoints, (Cont'd) TABLE 3.1-2 (Cont'd) TABLE NOTATIONS
~~At all times during periods of release.~~
~~# Applies during MODE 1, 2, 3, and 4. ## 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 if the 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 hours 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 - 18 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation: Operability/ Functionality and Alarm/ Trip Setpoints, (Cont'd) METHOD 3.1.1: GASEOU.S 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 O-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 an~lysis 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-133 contributes about 99% of the noble gas activity. 3 -19 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation: Operability/ Functionality and Alarm / Trip Setpoints. (Cont'd) METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS (Cont'd) 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. Eqn 3.1-1 where: S = The alarm setpoint, (cpm) 1.06 = conversion constant (500 mRem/yr*60 sec/min
35.32 ft3/m 3

1m3/10 6 cm 3 )
h = monitor response to activity concentration of effluent, cpm (µCi/cc) F = flow of gaseous effluent stream, i.e., flow past the monitor, (ft3/min) xto = atmospheric dispersion factor at the off-site location of interest, (sec/m3 ) Ci = concentration of r~dionuclide i in gaseous effluent (µCi/cc). DFi = Dose factor for exposure to a semi-infinite cloud of noble gas, mRem See Table 3.1-3. (yr*µCi/m 3) St = 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: 0.8 for the Plant Vent (which includes 0.1 for each Unit SJAE vent) , 0.1 for the 3 Spent Fuel Pit Vent, and 0.1 for unmonitored gas releases. Bk = Instrument background count rate, cpm 3 - 20 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability/ Functionality and Alarm / Trip Setpoints, (Cont'd) METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, (Cont'd) 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, xtQ, will be based on prevailing meteorological conditions or on reference meteorological conditions. The minimum atmospheric dispersion off site 6 derived from reference meteorological conditions at the site boundary is 1.3 x 10-3 sec/m at .a location 1950 meters West of the plant. The applicable dose conversion factors, DFi, 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-133. 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 - 21 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability/ Functionality and Alarm / Trip Setpoints, (Cont'd) METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS (Cont'd) S = DR
h

S1

3600

t

V R + BKG Eqn 3.1-2 TAa11ip

Xa IQ 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
~~38. mRem/yr~~
(µCi/m 3 ) 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).
~~= 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: 0.8 for the Plant Vent (which includes 0.1 for each Unit SJAE), 0.1 for the 3 Spent Fuel Pit Vent, and 0.1 for unmonitored gas releases.
~~VR = Ratio of sample volume to release volume.~~
3-22 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability/ Functionality and Alarm / Trip Setpoints, (Cont'd) METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, (Cont'd) BASIS 3.1: The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/ trip will occur prior to exceeding the limits of 10 CFR Part 20. The noble gas effluent monitors Alarm I Trip setpoint is calculated using equation 3.1-1. It is shown in example calculation 3.1.2, that for continuous releases, the calculated setpoint exceeds the range of the monitor. Lower setpoints are therefore set in accordance with approved plant procedures. Typically, the Alarm setpoint for continuous releases is set at a small fraction of the instrument's range to alert operators of an adverse trend. During continuous releases there is no process to trip; therefore, a trip setpoint is not determined for a continuous release. The sensitivity of any noble gas activity monitors used to show compliance with the gaseous effluent 6 release requirements of Control 3.3 shall be such that concentrations as low as 1 x 10-
~~µCi/ml _are measurable.~~
This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the Gas Decay Tank System. The OPERABILITY/ FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. 3-23 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability/ Functionality and Alarm / Trip Setpoints, (Cont'd) METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, (Cont'd) TABLE 3.1-3 DOSE FACTORS, DFi , FOR EXPOSURE TO A SEMI-INFINITE CLOUD OFNOBLE GAS mRem yr µCi/ m 3 Radionuclide Kr-83m 7.56 E-2 Kr-85m 1.17 E3 Kr-85 1.61 E1 Kr-87 5.92 E3 Kr-88 1.47 E4 Kr-89 1.66 E4 Kr-90 1.56 E4 Xe-131m 9.15 E1 Xe-133m 2.51 E2 Xe-133 2.94 E2 Xe-135m 3.12 E3 Xe-135 1.81 E3 Xe-137 1.42 E3 Xe-138 8.83 E3 Xe-139 5.02 E3 Ar-41 8.84 E3 Source: RG1.109 Table B-1, values multiplied by 1.0 x 106 to convert pCi to uCi. 3-24 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability/ Functionality and Alarm / Trip Setpoints, (Cont'd) METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, (Cont'd) EXAMPLE CALCULATION: Determining the Noble Gas Monitor Alarm Setpoint Control 3.1 requires release setpoints to be based on a dose rate. Derivations used to determine setpoints assume that noble gas releases occur at ground level. The noble gas effluent monitor setpoint, based on dose rate is calculated using Equation 3.1-1. h
s, LC; S = 1.06 F

XIQ Z:(c/

OF;) + Bkg i
~~where: s = The alarm setpoint (CPM). 1.06 = Conversion factor; 500 mRem~~
60 sec

35.32 ft 3

1m3 yr min m3 106cc h = Monitor response to activity concentration of effluent cpm
(µCi/cc). F = Flow of gaseous effluent stream past the monitor ft3 (min). x!Q = atmospheric dispersion factor at the offsite location of interest, sec (m3) St = a factor to allow for multiple sources from different or common release points. The allowable operating setpoints will be controlled by assigning a fraction of the allowable release to each of the release sources. For gas releases, this fraction is assigned as follows: 0.8 for the Plant Vent (which includes 0.1 for each Unit SJAE) , 0.1 for the 3 Spent Fuel Pit Vent, and 0.1 for unmonitored gas releases. 3-25 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability/ Functionality and Alarm I Trip Setpoints, (Cont'd) METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, (Cont'd) EXAMPLE CALCULATION: Determining the Noble Gas Monitor Alarm Setpoint, (Cont'd) factor for exposure to a semi-infinite cloud of noble gas mRem see Table 3.1-3. (yr-µCi/m 3) concentration of radionuclide, i, in gaseous effluent (µCi/cc). 8kg = monitoring instrument background (cpm). Example: The measured concentration of noble gases to be discharged to the atmosphere are: Radionuclide C;(µCi/cc) Kr-85m 3.6 X 10-6 Kr-85 2.8 X 10-4 Kr-87 2.5 X 10-6 Kr-88 1.4 X 10-5 Xe-131m 1.0x1ff2 Xe-133 4.3 X 1ff2 Xe-135 6.0x10-4 Ar-41 7.7 X 10-5 Determine the alarm setpoint, S (cpm) when: h = 2.5 X 10 8 .....QQ!!!
~~µCi/cc F = 8.0 X 104 ft3 min xto = 1 .3 x 10-6 sec m3 St = 0.8 8kg = 600 cpm 3- 26 REV. 26~~
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.1: Radioactive Gaseous Effluent Monitoring Instrumentation; Operability/ Functionality and Alarm I Trip Setpoints, (Cont'd) METHOD 3.1.2: ESTABLISHING GASEOUS EFFLUENT MONITOR ALARM AND TRIP SETPOINTS, (Cont'd) EXAMPLE CALCULATION: Determining the Noble Gas Monitor Alarm Setpoint, (Cont'd) Calculate the effect of a ground level release as follows: Rad ion uelide Ci DFi CixDFi 5 3 2 Kr-85m 3.6 X 10- 1.17 X 10 4.2 X 10-Kr-85 2.8 X 10-4 1.61x101 4.5 X 10-3 6 3 2 Kr-87 2.5 X 10- 5.92 X 10 1.5 X 10-4 1 Kr-88 1.4 X 10-5 1.47 X 10 2.1 X 10-1 Xe-131m 1.0 X 10-2 9.15x10 1 9.1 X 10-2 Xe-1-33 4.3 X 10- 2.94 X 102 1.3 X 10 1 Xe-135 6.0 X 10-4 1.81 X 103 1.1 X 10° 5 3 1 Ar-41 7.7x10- 8.85 X 10 6.8 X 10-2 1:Ci = 5.4 X 10-Calculate the setpoint as follows: S = 1.06 [ 2.5 X 10 S 8.0 X JO 4 0.8 5.8 X 10* 7 J[ 5.4 X 10" 2 1.6 X 10 1 J+ 600 9 3
= 1.06 [ 4.31 X 10 ] [ 3.4 X 10- ] + 600 = 1.54 E+o7 cpm Note: The range of the installed monitor is 300,000 cpm; therefore, the alarm setpoint is set in accordance with plant procedures.
3 -27 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:
a. For noble gases: Less than or equal to 500 mRem/yr to the whole body and less than or equal to 3000 mRem/yr to the skin, and

b. For lodine-131, for lodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mRem/yr to any organ.
APPLICABILITY: At all times. ACTION: With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s). SURVEILLANCE REQUIREMENTS 3.2.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in this ODCM. 3.2.2 The dose rate due to Iodine 131, Iodine 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in this ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3.2-1. 3-28 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) 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 (LLot>, (µCi/cc) p p Principal Gamma Emitters !2l 4
~~1. Gas Decay Tank 1 X 10"~~
~~( Batch) Each Tank, Grab Sample Each Tank p p (6) Principal Gamma Emitters !2>~~
~~2. Containment Purge or (6) 1 X 104 Venting (Batch)~~
~~Grab Sample Each PURGE H-3 1 X 10-6~~
~~3. Plant Vent (includes Unit 4 M (6) M (6> 2 Principal Gamma Emitters ! > 1 X 10 4~~
Spent Fuel Pit Building Grab Sample Gas Sample Vent and U3 & U4 SJAE vents) M (4),(s> M 1 X 10-6 H-3 Grab Sample
~~4. Unit 3 Spent Fuel Pit M M Principal Gamma Emitters !2> 1 X 10 4~~
~~Building Vent Grab Sample Gas Sample M (4),(5) M H-3 1 X 10-6 Grab Sample~~
~~5. All Release Types as w(1>~~
Continuous !3> 1-131 1 X 10-12 listed in 3 and 4 (above) Charcoal Sample Continuous 101 wm Principal Gamma Emitters !2> 1 X 10-11 Particulate Sample 01 Continuous ' M Gross Alpha Composite Particulate sample 1 X 10-11 101 Continuous Q Composite Particulate sample Sr-89, Sr-90 1 X 10-11 01 Continuous ' Noble Gas Monitor Noble Gas Gross Beta or Gamma 1 X 10-6 3 -29 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) TABLE 3.2-1, (Cont'd) TABLE NOTATIONS (1) The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radio chemical separation: LLD= 4.66 Sb E x V x (2.22 x 106) x Y x [exp (-lilt)] Where: LLD = The "a priori" lower limit of detection as defined above as a blank sample (microCurie per unit mass or volume),
~~= The counting rate of a blank sample or the standard deviation of the background counting rate as appropriate (counts per minute),~~
E = The counting efficiency (counts per disintegration) V = The sample size (units of mass or volume), 2.22 x 106 = The number of disintegrations per minute per microCurie, Y = The fractional radio chemical yield, when applicable, 1c = The radioactive decay constant for the particular radionuclide, and flt = The elapsed time between the midpoint of sample collection and the time of counting (for plant effluents, not environmental samples) Typical values of E, V, Y, and flt shall be used in the calculation. 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. 3 - 30 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) TABLE 3.2-1 (Cont'd) TABLE NOTATIONS (Cont'd) (2) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other gamma peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported pursuant to Administrative Control 1.3. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD for that nuclide. When a radionuclide's calculated LLD is greater than its listed LLD limit, the calculated LLD should be assigned as the activity of the radionuclide; or, the activity of the radionuclide should be calculated using measured ratios with tho_se radionuclides which are routinely identified and measured. (3) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 3.2, 3.3, and 3.4. (4) When a Unit's refueling canal is flooded, Tritium grab samples shall be taken on that Unit only from the following respective area(s) at least once per 24 hours: For Unit 3 sample the plant vent and the Unit 3 spent fuel pool area ventilation exhaust. For Unit 4 sample the plant vent only. (5) When spent fuel is in the spent fuel pool, tritium grab samples shall be taken from the following respective area at least once per 7 days: For Unit 3, sample the Unit 3 spent fuel pool area ventilation exhaust For Unit 4, sample the plant vent. 3 - 31 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) TABLE 3.2-1 (Cont'd) TABLE NOTATIONS (Cont'd) (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 hour 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 hours after changing, or after removal from sampler. Sample collection media on the applicable Unit shall also be changed at least once per 24 hours for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1 hour period and analyses shall be completed within 48 hours 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 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. 3-32 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent Compliance with the limits on dose rate from noble gases is demonstrated by establishing effluent monitor alarm setpoints such that an alarm will occur at or before a dose rate limit of the combined releases for noble gases is reached for the release types listed in ODCM Table 3.2-1. If an alarm occurs when the monitor setpoint is at or below the limit, compliance may be assessed by comparing the monitor record with the setpoint (limit) calculated in accordance with Method 3.1.2 or a more conservative method calculated in accordance with approved plant procedures. In the event an alarm occurs and the monitored release exceeds the setpoint limit, then compliance shall be evaluated by calculating dose rates in accordance with Methods A and B. below. The alarm setpoints shall be derived on the basis of the radionuclide distribution from a measured gamma spectrum, or by assuming the total noble gas activity is Xe-133. If Xe-133 is the dominant radioactive gas in the airborne effluent, the gamma dose rate to a person's body is expected to be a larger fraction of the 500 mRem/year limit than is the sum of beta and gamma dose rates to the skin limit of 3000 mRem/year. Thus, a gaseous effluent monitor setpoint may be derived on the basis of whole body gamma dose rate alone such that an alarm occurs at or before the whole body dose rate off site exceeds 500 mRem/year as given in Control 3.2. 3-33 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) A. TOTAL BODY DOSE RATE The total body dose rate from radioactive noble gases may be calculated at any location off-site by assuming a person is immersed in and irradiated by a semi-infinite cloud of the noble gases. The dose rate is calculated using the equation Dm Eqn 3.2-1 where: Orn = Dose rate to total body from noble gases, (mRem/year) xlO = atmospheric dispersion factor at the off-site location of interest, (sec/m 3) t = Averaging time of release, i.e., increment of time during which Qi was released, (year) quantity of noble gas radionuclide i released during the averaging time, (µCi) Pyi = factor converting time integrated concentration of noble gas radionuclide, i, at ground level to total body dose, mRem - m3 ; see Table 3.2-2. (µCi - sec) Since dose rate limits for airborne effluents apply everywhere off-site, compliance is assessed and alarm setpoints determined at the site boundary where the minimum atmospheric dispersion from the plant (maximum x/Q) occurs. That location is selected on the basis of reference meteorology data in Appendix 3A-1. According to those data, the minimum dispersion off-site occurs at the site boundary 1950 meters WNW of the plant where x/Q = 1.3 x 10-6 sec/m 3
~~3-34 REV. 26~~
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) B. Skin Dose Rate The dose rate to skin from radioactive noble gases may be calculated at any location off-site by assuming a person is immersed in ano irradiated by a semi-infinite cloud of the noble gases. The dose rate to skin is calculated using the equation: Ds = i *7ffQ
Sp + 1.11Q

A,d Eqn. 3.2-2 where:
Drn = dose rate to skin from radioactive noble gases, (mRem/year) s13 i = factor converting time integrated concentration of noble gas radionuclide i at ground level, to skin dose from beta radiation, mRem , see Table 3.2-2 (µCi*sec/m 3 ) 1.11 = ratio of tissue dose equivalent to air dose in a radiation field, (mRem/mRad) Ayi = factor for converting time integrated concentration of noble gas radionuclide, i, in a semi-infinite cloud, to air dose from its gamma radiation, mRad , listed in Table 3.2-3 (µCi*sec/m 3) Since dose rate limits for airborne effluents apply everywhere off-site, compliance is assessed and alarm setpoints determined at the site boundary where the minimum atmospheric dispersion from the plant (maximum x/Q) occurs. That location is selected on the basis of reference meteorology data in Appendix 3A-1. According to those data, the minimum dispersion off-site occurs at the site boundary 1950 meters WNW of the plant where x/Q = 1.3 x 1o-e sec/m 3 . 3 -35 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2:. DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS. (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) C. H-3, 1-131, 1-133 and PARTICULATE DOSE RATE The dose rate to any organ due to H-3, 1-131, 1-133 and radioactive material in particulate form with a half-life of more than 8 days is calculated with the equation: Eqn 3.2-3 where: Danp = dose equivalent rate to body organ, n, of a person in age group, a, exposed via pathway, p, to radionuclide, i, identified in analysis, k, of effluent air, (mRem/year) 3600 = conversion constant, (sec/hr) t = period of time over which the effluent releases are averaged, (hr) xiQ = atmospheric dispersion factor, adjusted for depletion by deposition(sec/m3).(Alternately x!Q, unadjusted, may be used). Qik = quantity of radionuclide, i, released during time increment, t, based on analysis, k (µCi). T Aanip = 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 (air-grass-cow-milk), mRem/yr ; See Appendix 38. 3 (µCi/m ) When the dose rate due to H-3, 1-131, 1-133 and radionuclides in particulate form is calculated for the purpose of assessing compliance with Control 3.2, a hypothetical infant located where the minimum atmospheric dispersion from the plant occurs is assumed as the receptor. 3 - 36 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) C. H-3, 1-131, 1-133 and PARTICULATE DOSE RATE, (Cont'd) For the radioiodines and particulates with half-lives greater than eight days, the effective dose transfer factor, TAanip, is based solely on the radioiodines (1-131, 1-133). This approach was selected because the radioiodines contribute essentially all of the dose to the infant's thyroid via the inhalation and the grass-cow-milk pathway. The infant's thyroid via the grass-cow-milk pathway is the critical organ and controlling pathway respectively for the releases of radioiodines and particulates. The dose rate calculation will be based on the location of minimum dispersion adjusted for deposition according to the reference meteorology data in Appendix 3A-2. According to those data, the minimum dispersion offsite occurs at 7 the site boundary 1950 meters WNW of the plant and the Xd/Q value is 5.0 x 10-sec/m 3* That location is identified in Figure 3-2. Alternately, averaged meteorological dispersion data coincident with the period of release may be used to evaluate the dose rate. These radionuclide concentrations in airborne effluents, Qik, are measured according to the sample and analysis schedule in ODCM Table 3.2-1 BASIS 3.2: This control applies to the release of radioactive materials in gaseous effluents from all units at the site. The specified gamma and beta dose rates, above background, provides the datum against which the gaseous effluent monitor setpoints are determined, using the methods described in this ODCM, pursuant to Control 3.1. In essence, Control 3.2 is an instantaneous limit. Adherence to Controls 3.3 through 3.5 provide assurance that levels of radioactive materials in air in UNRESTRICTED AREAS will, on the average, be a small fraction of the concentration limits and result in exposures to MEMBERS OF THE PUBLIC within the objectives of Appendix I to 10 CFR Part 50 and 40 CFR 190. Control 3.2 permits the flexibility of operation, compatible with considerations of health and safety, to provide a dependable source of power even under circumstances that temporarily result in elevated releases, but still within the limit as specified in 10 CFR Part 20.1302 (b)(2)(ii). 3-37 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) Table 3.2-2 Transfer Factors for Maximum Dose to a Person Offsite due to Radioactive Noble Gases Air Dose Transfer Factors Pyi S13i mRem mRem Radionuclide (µCi sec/m 3 ) (µCi sec/m 3 ) Kr-83m 2.4E-9 Kr-85m 3.7E-5 4.6E-5 Kr-85 5.1 E-7 4.2E-5 Kr-87 1.9E-4 3.1E-4 Kr-88 4.7E-4 7.5E-5 Kr-89 5.3E-4 3.2E-4 Kr-90 4.9E-4 2.3E-4 Xe-131m 2.9E-6 1.5E-5 Xe-133m 8.0E-6 3.1 E-5 Xe-133 9.3E-6 9.7E-6 Xe-135m 9.9E-5 2.3E-5 Xe-135 5.7E-5 5.9E-5 Xe-137 4.5E-5 3.9E-4 Xe-138 2.8E-4 1.3E-4 Ar-41 2.8E-4 8.5E-5 Ref: Regulatory Guide 1.109, Revision 1, Table 8-1. Note: Values in the regulatory guide are quoted in units of pCi*yr, to convert to units of
~~µCi*sec multiply by a factor of 3.171 E-2.~~
3 - 38 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) Table 3.2-3 Transfer Factors for Maximum Offsite Air Dose Air Dose Transfer Factors Ayj Api mRad mRad Radionuclide (µCi sec/m3 ) (µCi sec/m 3 ) Kr-83m 6.1E-7 9.1 E-6 Kr-85m 3.9E-5 6.2E-5 Kr-85 5.4E-7 6.2E-5 Kr-87 2.0E-4 3.3E-4 Kr-88 4:8E-4 9.3E-5 Kr-89 5.SE-4 3.4E-4 Kr-90 5.2E-4 2.SE-4 Xe-131m 4.9E-6 3.SE-5 Xe-133m 1.0E-5 4.7E-5 Xe-133 1.1 E-5 3.3E-5 Xe-135m 1.1 E-4 2.3E-5 Xe-135 6.1 E-5 7.8E-5 Xe-137 4.8E-5 4.0E-4 Xe-138 2.9E-4 1.SE-4 Ar-41 2.9E-4 1.0E-4 Ref: Regulatory Guide 1.109, Revision 1, Table B-1 Note: Values in the regulatory guide are in units of pCi*yr, to convert to units of µCi*sec multiply by a factor of 3.171 E-2. 3- 39 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) EXAMPLE CALCULATIONS: Dose Rate Due to Gaseous Effluent Determining the Total Body Dose Rate from Noble Gas The total body dose rate from the radioactive noble gases may be calculated at any location by assuming a person is immersed in and irradiated by a semi-infinite cloud of the noble gases. Compliance is assessed and alarm setpoints established based on the dose rate at the site boundary where the minimum atmospheric dispersion from the plant occurs. This location is 1950 meters W to NW of the plant where x!Q = 1.3 x 10-6 sec/m 3
~~The dose rate D may be calculated using equation 3.2-1.~~
~~Example: During a 31 day period, the following noble gas activity was released from Unit 3. The total body dose rate is calculated by: DTE X * !_ "L.... Q.~~
~~Pr; Q t i J where:~~
Orn = Dose rate to total body from noble gases, (mRem/year) x!O = atmospheric dispersion factor at the off-site location of interest, (sec/m 3) t = Averaging time of release, i.e., increment of time during which Qi was released, (year)
~~= quantity of noble gas radionuclide i released during the averaging time,~~
~~(µCi)~~
~~= factor converting time integrated concentration of noble gas radionuclide, i, at ground level, to total body dose, mRem ; See Reference Table 3.2-2~~
(µCi*sec/m 3 ) 3 -40 . REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) EXAMPLE CALCULATIONS: Dose Rate Due to Gaseous Effluent, (Cont'd) The total body dose is summarized in the following table: Radionuclide Qi Pyi OPri Kr-85m 3.6E-2 3.7E-5 1.33E-6 Kr-85 2.8E-1 5.1 E-7 1.43E-7 Kr-87 2.5E-3 1.9E-4 4.75E-7 Kr-88 1.4E-2 4.7E-4 6.58E-6 Xe-131m 1.0E+1 2.9E-6 2.90E-5 Xe-133 4.3E+1 9.3E-6 4.00E-4 Xe-135 6.0E-1 5.7E-5 3.42E-5 Ar-41 7.7E-2 2.6E-4 2.00E-5 The value of L0Pri is equal to 4.92 E-4 Note: The time (t) is for 31 day period stated as years which equals 31d/365d/yr or 0.085 yr. The value of 1/t, in the equation, is 1/0.085 = 11.77. D =1.3E-6 x 11.77 x 4.94 E-4 =7.62 E-9 mRem/yr 3 -41 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) EXAMPLE CALCULATIONS: Dose Rate Due to Gaseous Effluent, (Cont'd) Determination of Skin Dose Rate from Noble Gases Example: Using the noble gas release data given in the previous .example, the skin dose rate is calculated by:
X 1 Ora = Q

t ff 0;

S /Ji + 1.11 Q;

Ai.;]
where: dose rate to skin from radioactive noble gases (mRem/year) Spi= factor converting time integrated concentration of noble gas radionuclide i at ground-level, to skin dose from beta radiation, mRem ; Reference Table 3.2-2 3 (µCi*sec/m )
~~1.11 = ratio of tissue dose equivalent to air dose in a radiation field, (mRem/mRad).~~
Ayi = factor for converting time integrated concentration of noble gas radionuclide i in a semi-infinite cloud, to air dose from its gamma radiation, mRad ; Listed in Table 3.2-3 3 (µCi*sec/m ) 3 -42 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) EXAMPLE CALCULATIONS: Dose Rate Due to Gaseous Effluent, (Cont'd) The skin dose rate is summarized in the following table: Nuclide Qi Spi QiSpi Ar; OAri Kr-85m 3.6E-2 4.6E-5 1.7E-6 3.9E-5 1.40E-6 Kr-85 2.8E-1 4.2E-5 1.2E-5 5.4E-7 1.51 E-7 Kr-87 2.5E-3 3.1 E-4 7.8E-7 2.0E-4 5.00E-7 Kr-88 1.4E-2 7.5E-5 1.1 E-6 4.8E-4 6.72E-6 Xe-131m 1.0E+1 1.5E-5 1.5E-4 4.9E-6 4.90E-5 Xe-133 4.3E-1 9.7E-6 4.2E-6 1.1 E-5 4.73E-6 Xe-135 6.0E-1 5.9E-5 3.5E-5 6.1 E-5 3.66E-5
Ar-41 7.6E-2 8.5E-5 6.5E-6 2.9E-4 2.20E-5 The value of LOiSpi = 2.11 E-4 and the value of LOiAyi = 1.21 E-4 D =1.3E-6 x 11.77 (2.11 E-4 + [1.11 x 1.21 E-4]) = 5.32 E-9 mRem/yr Note: The value of 1/t is 11.77 (see previous Example table note), and x!Q is 1.3E-6 sec/m 3 3-43 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) EXAMPLE CALCULATIONS: Dose Rate Due to Gaseous Effluent, (Cont'd) Determining Dose Rate from Tritium, Iodines, and Particulates The total body and/or organ dose rate due to tritium, radioiodines, and radioactive particulates with half-lives greater than 8 days released in the effluent air may be calculated at any location off-site using equation 3.2-3. For assessing compliance with Control 3.2, the thyroid dose rate for a hypothetical infant located at the site boundary where the minimum atmospheric dispersion from the plant occurs is the assumed receptor. Example: During a calendar quarter (2184 hrs) the following activities were released from Unit 4. The dose rate from activity is calculated by: Danp = 36
~~~Qt * ~ f f Qik~~
~~TAanip where:~~
Danp = dose equivalent rate to body organ, n, of a person in age group, a, exposed via pathway, p, to radionuclide, i, identified in analysis, k, of effluent air, (mRem/year) 3600 = conversion constant, (sec/hr) t = period of time over which the effluent releases are averaged, (2184 hrs/qtr) quantity of radionuclide, i, released during time increment, t, based on analysis, k, (µCi). quantity of radionuclide, i, released during increment time, t, based on analysis, k, (µCi). 3-44 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.2: DOSE RATE FROM RADIOACTIVE GASEOUS EFFLUENTS, (Cont'd) METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Cont'd) EXAMPLE CALCULATIONS: Dose Rate Due to Gaseous Effluent, (Cont'd) 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 (infant), exposed via pathway, p (air-cow-grass-milk). mRem/yr ; See Appendix 38 (µCi/m 3 ) The dose rate from tritium; iodine and particulate is summarized in the following table. Radionuclide Qik TAanip QikTAanip H-3 1.6E+5 2.37E+3 3.79E+8 Cr-51 8.0E-6 1.8E+4 1.44E-1 Co-58 5.0E-7 0 0 Co-60 9.5E-7 0 0 1-131 3.5E-7 9.94E+11 3.48E+5 Cs-137 2.0E-6 0 0 Notes: = The time factor 1/360ot 1.27E-7 where t =2184hrs/qtr The value oO::QikTAanip = 3.8E+8 The value of xiO = 1.3E-06 Danp = 1.27E-7 x 1.3E-6 x 3.8E+8 = 6.3E-5 mRem/yr 3-45 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.3: AIR DOSE FROM NOBLE GASES The air dose due to noble gases released in gaseous effluent, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 1.5 - 1) shall be limited to the following:
a. During any calendar quarter: Less than or equal to 5 mRad for gamma radiation and less than or equal to 10 mRad for beta radiation, and

b. During any calendar year: Less than or equal to 10 mRad for gamma radiation and less than or equal to 20 mRad for beta radiation.
~~APPLICABILITY: At all times. ACTION~~
a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 1.6.6, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that
~~subsequent releases will be in compliance with the above limits.~~
~~b. The provisions of Administrative Control section 1.6.3 are not applicable.~~
SURVEILLANCE REQUIREMENTS 3.3.1 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in this ODCM at least once per 31 days. 3-46 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.3: AIR DOSE FROM NOBLE GASES, (Cont'd) METHOD 3.3.1: NOBLE GAS GAMMA RADIATION DOSE The gamma radiation dose to air off site as a consequence of noble gas discharged from each unit can be calculated with the equation: Eqn 3.3-1 where: Dy =
~~noble gas gamma dose to air, (mRad)~~
Ayi = factor converting time integrated, ground level concentration of noble gas radionuclide i to air dose from gamma radiation listed in Table 3.3-1, mRad (µCi* sec/m 3) 3 x/Q = atmospheric dispersion factor at the off-site location of interest, (sec/m ) Qi = the measured gaseous radioactivity released via a stack or vent during a single counting interval, j, (µCi) Surveillance 3.3.1 is satisfied by calculating the noble gas gamma radiation dose to air at the location identified in Figure 3-2. At that location, 1950 meters WNW of the Plant, the reference atmospheric dispersion factor to be used is x/Q = 1.3 x 10-6 3 sec/m
Alternately, Surveillance 3.3.1 may be satisfied, when authorized for estimating doses due to an unplanned release, by calculating the gamma dose to air with the equation Dr =-1-* X 0.8 Q Eqn 3.3-2 where:
0.8 = a conservative factor which, in effect, increases the estimated dose to compensate for variability in radionuclide distribution 3-47 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.3: AIR DOSE FROM NOBLE GASES, (Cont'd) METHOD 3.3.1: Noble Gas Gamma Radiation Dose, (Cont'd) Ayeff = effective gamma air dose factor converting time integrated, ground level, total activity concentration of radioactive noble gas, to air dose due-to gamma radiation. This factor has been derived from noble gas radionuclide distributions in routine operational releases. (Refer to Appendix 3C for a detailed explanation). The effective gamma air dose factor is: 5 Ayeff = 1.4 x 10- mRad (µCi
~~sec/m 3)~~
The remaining factors have been defined previously. METHOD 3.3.2: NOBLE GAS BETA RADIATION DOSE The beta radiation dose to air off site as a consequence of noble gas discharged from each unit can be calculated with the equation: Eqn 3.3-3 where: D13 = noble gas beta dose to air, (mRad) A 13 i = factor converting time-integrated, ground level concentration of noble gas radionuclide i to air dose from beta radiation, listed in Table 3.3-1, mRad (µCi
~~sec/m 3) x!Q = atmospheric dispersion factor at the off-site location of interest, (sec/m 3)~~
Surveillance 3.3.1 is satisfied by calculating the noble gas beta radiation dose to air at the location identified in Figure 3-2. At that location, 1950 meters WNW of the Plant, the reference atmospheric dispersion factor to be used is x/Q = 1.3 x 10-6 sec/m 3 . 3-48 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.3: AIR DOSE FROM NOBLE GASES, (Cont'd) METHOD 3.3.2Noble Gas Beta Radiation Dose, (Cont'd) Alternately, Control 3.3 may be satisfied, when authorized for estimating doses due to an unplanned release, by calculating the beta radiation dose to air with the equation _ 1 X Op--*-* Ape"* I:Qj 0.8 Q I Eqn 3.3-4 where 0.8 = a conservative factor which, in effect, increases the estimated dose to compensate for variability in radionuclide distribution A13eff = effective beta air dose factor converting time integrated, ground level, total activity concentration of radioactive noble gas to air dose due to beta radiation. This factor bas been derived from noble gas radionuclide distributions in routine operational releases. (Refer to Appendix 3C for a detailed explanation.) The effective beta air dose factor is: 5 A13eff = 3.4 X 10- mRad (µCi
~~sec/m3)~~
The remaining factors have been defined previously. 3-49 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.3 : AIR DOSE FROM NOBLE GASES, (Cont'd) BASIS 3.3: DOSE - NOBLE GASES This Control applies to the release of radioactive materials in gaseous effluent from each unit at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system. This control is provided to implement the requirements of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be *kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based 6n models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially under estimated. The dose calculation methodology and parameters established in this ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluent are consistent with the methodology 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 and 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. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. 3 - 50 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.3: AIR DOSE FROM NOBLE GASES, (Cont'd) METHODS 3.3.1 and 3.3.2: Noble Gas Gamma and Beta Radiation Dose, (Cont'd) Table 3.3-1 Transfer Factors for Maximum Off site Air Dose Air Dose Transfer Factors Ayi A~i mRad. mRad Radionuclide (µCi sec/m 3 ) (µCi sec/m 3) Kr-83m 6.1E-7 9.1E-6 Kr-85m 3.9E-5 6.2E-5 Kr-85 5.4E-7 6.2E-5 Kr-87 2.0E-4 3.3E-4 Kr-88 4.BE-4 9.3E-5 Kr-89 5.SE-4 3.4E-4 Kr-90 5.2E-4 2.SE-4 Xe-131m 4.9E-6 3.SE-5 Xe-133m 1.0E-5 4.7E-5 Xe-133 1.1 E-5 3.3E-5
.xe-135m 1.1 E-4 2.3E-5 Xe-135 6.1E-5 7.8E-5 Xe-137 4.8E-5 4.0E-4 Xe-138 2.9E-4 1.SE-4 Ar-41 2.9E-4 1.0E-4 Ref.: Regulatory Guide 1.109, Revision 1, Table 8-1 Note: Values in the regulatory guide are in units of pCi*yr, to convert to units of µCi*sec multiply by a factor of 3.171 E-2.
3 - 51 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.3: AIR DOSE FROM NOBLE GASES, (Cont'd) EXAMPLE CALCULATION: AIR DOSE FROM NOBLE GASES Determining the Noble Gas Gamma Radiation Dose The cumulative dose due to gamma radiation from radioactive noble gases discharged from the plant shall be calculated once per 31 days to verify the quarterly and annual limits will not be exceeded. The gamma radiation dose from noble gases are calculated at the site boundary where the minimum atmospheric dispersion occurs, i.e., 1950 meters WNW of the plant where x!Q = 1.3 x 10-6 sec/m 3
~~The gamma dose is calculated using equation 3.3-1 or 3.3-2. The example given here uses equation 3.3-1.~~
Example: The noble gas activity discharged during a 31 day period from gas decay tanks, containment purges, and the spent fuel pit vent were totaled as tabulated below. The gamma dose from the noble gas release is calculated as follows: (Eqn 3.3-1) where: Dr = The noble gas dose to air, (mRad). xlO = The atmospheric dispersion factor for a mixed-mode discharge, (sec/m3). Qi = The measured radioactivity released via stack or vent during a single counting interval, j (µCi). Ayi = Factor converting time integrated, ground-level concentration of noble gas radionuclide i to air dose from gamma radiation listed in Table 3.3-1 mRad (µCi*sec/m 3) 3 - 52 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.3: AIR DOSE FROM NOBLE GASES, (Cont'd} EXAMPLE CALCULATION: AIR DOSE FROM NOBLE GASES, (Cont'd} The noble gas gamma radiation dose is summarized in the following table. Radionuclide Qi Ayi QiAri Kr-85m 5.4E+1 3.9E-5 2.1 E-3 Kr-85 5.4E+1 5.4E-7 2.9E-5 Kr-87 5.4E+1 2.0E-4 1.1 E-2 Kr-88 5.4E+1 4.BE-4 2.6E-2 Xe-131m 5.4E+1 4.9E-6 2.6E-4 Xe-133 5.4E+1 1.1 E-5 5.9E-4 Xe-135 5.4E+1 6.1 E-5 3.3E-3 Ar-41 5.4E+1 2.9E-4 1.6E-2 The value of :EQiAyi = 5.93E-2 Dy= 5.93E-2 x 1.3E-6 = 7.77E-8 mRad Determining Noble Gas Beta Radiation Dose The beta air dose due to noble gases discharged from the plant shall be determined for the current calendar quarter and current calendar year at least once per 31 days. The beta air dose is calculated in the same manner as the gamma air dose using the beta air dose factors from Table 3.3-1 and Equation 3.3-3 or 3.3-4. 3 -53 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE- IODINE-131, IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM The dose to a MEMBER OF THE PUBLIC from Iodine 131, Iodine 133, tritium, and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
a. During any calendar quarter: Less than or equal to 7.5 mRems to any organ and,

b. During any calendar year: Less than or equal to 15 mRems to any organ.
~~APPLICABILITY: At all times. ACTION:~~
a. With the calculated dose from the release of Iodine 131, Iodine 133, tritium, and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 1.6.6, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Administrative Control Section 1.6.3 are not applicable.
SURVEILLANCE REQUIREMENTS 3.4.1 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine 131, Iodine 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in this ODCM at least once per 31 days. 3 -54 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE - IODINE-131, IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS A. Determining the Quantity of Iodine, Tritium, and Particulates Radionuclides, other than noble gases, in gaseous effluents that are measured by the radioactive gaseous waste sampling and analysis program, described in ODCM Table 3.2-1, are used as the release term in dose calculations. Airborne releases are discharged either via a stack above the top of the Containment Building or via other vents and are treated as a mixed mode release from a single location. Releases of steam from the secondary system concurrent with primary to secondary leakage will also result in the release of activity to the atmosphere. For steam generator blowdown, using a blowdown sample analysis, it is assumed that 5% of the 1-131 and 1-133 and 33% of the tritium in the blowdown stream become airborne with the remainder staying in the liquid phase. For other unmonitored releases, the quantity of airborne releases may be determined by performing a steam mass balance. For each of these release combinations, samples are analyzed weekly, monthly, quarterly, or for each batch releases according to Table 3.2-1 Each sample provides a measure of the concentration of specific radionuclides, Ci, in gaseous effluent discharged at flow rate, F, during a time increment, t. Thus, each release is quantified according to the relation Qik = C;k
~~I: Fi* ti Eqn 3.4-1 i~~
where: Qik = the quantity of radionuclide i released in a given effluent stream based on a single analysis, k, (µCi) cik = concentration of radionuclide i in a gaseous effluent identified by* analysis, k, (µCi/cc) Fj = effluent stream discharge rate during time increment, tj, (cc/sec) ti = time increment, t, during which radionuclide i at concentration Cik is being discharged, (sec). 3 -55 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE - IODINE-131, IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Cont'd) A. Determining the Quantity of Iodine, Tritium, and Particulates, (Cont'd) Note: A steam mass to determine other unmonitored releases may be determined using the following: where: Mw = the measured mass of makeup water entering the secondary system during time interval, tj , (gm /sec). Mi = the measured mass of water discharged from the secondary system as liquid during time interval, tj, e.g. steam generator blowdown. Ms = the measured mass of steam or non"-condensable gases discharged from the secondary system during time interval, tj, e.g. air ejector discharge. Note: It is assumed that all of the 1-131, 1-133, and tritium in the other unmonitored releases are discharged as airborne species. It also assumed that gm/sec is equivalent to cc/sec. B. Calculating the Dose Due to Iodine, Tritium, and Particulates A person may be exposed directly to an airborne concentration of radioactive material discharged in an effluent gaseous stream and indirectly via pathways involving deposition of radioactive material onto the ground. Dose estimates should account for the exposure via the following pathways: o direct radiation from airborne radionuclides (except noble gases) o inhalation o direct radiation from ground plane deposition o fruits and vegetables o air-grass-cow-meat o air-grass-cow-milk 3 - 56 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE- IODINE-131, IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Cont'd)
~~8. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Cont'd)~~
~~Of all these pathways, the air-grass-cow-milk pathway is by far the controlling dose contributor. The radioiodines contribute essentially all of the dose, by this pathway, with~~
~~1-131 typically contributing greater than 95%. The dose transfer factors for the radioiodines are much greater than for any of the other radionuclides. The critical organ is the infant's thyroid.~~
For this reason, the potential critical.organ dose via airborne effluents can be estimated by determining an effective dose transfer factor for the radioiodines based on the typical radioactive effluent distribution, the air-grass-cow-milk pathway, and the infant thyroid as the receptor. Then for conservatism the total cumulative release of all radioiodines and particulates can be used along with the effective dose transfer factor to determine a conservative estimate of the infant thyroid dose. Surveillance 3.4.1, requires an evaluation be performed once per 31 days to verify that the accumulated total body or organ dose for the current calendar quarter and calendar year does not exceed the limit as given in Control 3.4. Dose commitment due to iodine and particulates may be calculated by using the following equation: 3.17x10- 8 D DMk = O.B
~~Q *TG 131 *I.O;k Eqn 3.4-2 where:~~
DMk = the dose commitment to an infant's thyroid received from exposure via the air-grass-cow-milk pathway and attributable to iodine identified in analysis k of effluent air, (mRem) 3.17 x 1o-8 = conversion constant, (yr/sec) 0.8 = a conservatism factor which, in effect, increases the estimated dose to compensate for variability in the radionuclide distribution. D/Q = relative deposition rate onto ground from a mixed mode atmospheric release (m-2) 3- 57 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE- IODINE-131, IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Cont'd) B. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Cont'd) TG131 = factor converting ground deposition of radioiodines to the dose commitment to an infant's thyroid exposed via the grass-cow-milk pathway, mRem/yr (µCi/m 2 *sec) Qik = the quantity of radionuclide, i (1-131 and 1-133), released in a given effluent stream based on a single analysis, k, (µCi). Surveillance 3.4.1 is satisfied by calculating the dose to an infant from iodine and particulates discharged as airborne effluents via the air-grass-cow-milk pathway and is evaluated by assuming a cow is on a pasture 4.5 miles West of the plant. (There are no milk or meat animals within 5 miles). At that location the reference atmospheric deposition factor is D/Q = 5 x 1O -10 m -2
~~When equation 3.4-2 is used to estimate the critical organ dose commitment, the effective dose transfer factor is:~~
TG131 = 6.5 x 10 11 mRem/yr (µCi/m 2 *sec) The reference data from which TG 131 was derived are summarized in Table 3C-2 of Appendix 3C. 3 - 58 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE- IODINE-131, IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Cont'd) B. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Cont'd) Alternately, the requirement of Surveillance 3.4.1, to perform once per 31 days determinations of dose commitments due to radioiodine, tritium, and radioactive particulates in effluent air may be made by using equations 3.4-3 through 3.4-5. These equations are normally used when calculating doses for the Annual Radioactive Effluent Release Report. The dose commitment from exposure to airborne concentrations of radioactive material other than noble gas from a release, Qik, via the inhalation and irradiation pathways is calculated with the equation where: Dank = 3.17x10-8
Xd

I;Q;k

ITAanip Eqn 3.4-3 Q i p Dank = the dose commitment to organ n of a person in age group a due to radionuclides identified in analysis k of an air effluent, (mRem).
conversion constant, (yr/sec) xiO= atmo$pheric dispersion factor adjusted for depletion by deposition, (sec/m3). the quantity of radionuclide i released in a given effluent stream based on analysis k, (µCi). TAanip= a factor converting airborne concentration of radionuclide i to dose commitment to organ n of a person in age group, a, where exposure is directly due to airborne material via pathway, p (inhalation, or external expo$ure to the plume), mRem/yr; (See Appendix 38). (µCi/m 3) 3- 59 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE - IODINE-131, IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Cont'd)
~~8. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Cont'd)~~
The dose to a person from iodine and particulates discharged as airborne effluents via the inhalation and irradiation pathways is evaluated at the nearest garden, 3.6 miles west northwest of the plant. At that location, the reference atmospheric dispersion factor adjusted for depletion by deposition is Xd/Q = 1 x 10-7 sec/m 3 , (Table 3A-2). The dose commitment via exposure pathways involving radionuclide deposition from the atmosphere onto vegetation or the ground is calculated with the equation D Dank = 3.17x1o*a * - * '2:Q;k * '2:TGanip Eqn 3.4-4 Q i p where: D/Q = relative deposition rate onto ground from a mixed mode atmospheric release, (m-2) TGanip = factor converting ground deposition of radionuclide i to dose commitment to organ n of a person in age group a where exposure is due to radioactive material via pathway p (direct radiation from ground plane deposition, fruits and vegetables, air-grass-cow-meat, or air-grass-cow-milk), mRem/yr See Appendix 38. (µCi/m 2 *sec), 3 -60 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE - IODINE-131, IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Cont'd) B. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Cont'd) The dose to a person from iodine and particulates discharged as airborne effluents via the air-grass-cow-milk pathway is evaluated by assuming a cow is on a pasture 4.5 miles West of the plant. (There are no milk or meat animals within 5 miles). At 10 2 this location, the reference atmospheric deposition factor is D/Q = 5 x 10 - m - (Table 3A-3). The concentration of tritium in vegetation is a function of the airborne concentration rather than the deposition. Thus, the dose commitment from airborne tritium via vegetation, (fruits and vegetables), air- grass-cow-milk, or air-grass-cow-meat pathways is calculated with the equation Dank = 3.17x1o*B * ~
LO;k

f TAanip Eqn 3.4-5 where:
x!O = atmospheric dispersion factor at the off-site location of interest (sec/m 3) The dose to a person from tritium via the vegetation, (fruits and vegetables), air-grass-cow-milk, or air-grass-cow-meat pathways is evaluated at the nearest garden (with residence assumed) 3.6 miles West Northwest of the plant. At that location, the 7 3 reference atmospheric dispersion factor is x!Q = 1 x 10- sec/m . 3 - 61 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE - IODINE-131, IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Cont'd) B. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Cont'd) The dose commitment via a given pathway as a result of measured discharges from a release point is accumulated with Dan = LDank Eqn 3.4-6 k where: Dan = the dose commitment to organ n of a person in age group, a. k = the counting index; it may represent either: p, analysis of a grab sample w, a weekly sample analysis m, a monthly composite analysis, or q, a quarterly composite analysis 3 - 62 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE - IODINE 131, IODINE 133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) BASIS 3.4: DOSE-IODINE 131, IODINE 133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared systems are proportioned among the units sharing that system. This control is provided to implement the requirements of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculation methods specified in the Surveillance Requirements implement the requirements in Appendix I that cor:iformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology 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 and 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. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man. 3 -63 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE-IODINE-131, IODINE-133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) EXAMPLE CALCULATIONS: Determining Dose Due to Iodine, Tritium, and Particulates Dose estimate should account for exposure of a person via the following pathways involving deposition of radioactivity on the ground. direct radiation from airborne radionuclides except noble gases inhalation direct radiation from ground plane deposition fruits and vegetables air-grass-cow-meat air-grass-cow-milk The requirement to determine the dose commitments due to radioiodine, tritium, and radioactive particulates once per 31 days may be satisfied by using Equations 3.4-2, 3.4-3, 3.4-4, and 3.4-5. Example: Calculate the organ and total body dose to an infant from tritium inhalation and irradiation pathways and from radioiodine and particulates via the grass-cow-milk pathway using Equations 3.4-4 and 3.4-5. The major non-noble gas activities released over a 31 day period were used for the calculation. The atmospheric dispersion factor and deposition rate values for a mixed mode release at 3.6 miles WNW and 4.5 miles West of the plant respectively were obtained from Tables 3A-2 and 3A-3. Factors TAanip and TGanip converting airborne activity to dose commitment are obtained from Appendix 38 for the organ, age group, and pathway. For Iodine and Particulate: D Dank =3.17x10*a
Q

IQik * ~TGanip Eqn 3.4-4 For Tritium; 8
Dank = 3.17x10*
X

IQ;k

ITAan1p Eqn 3.4-5 Q I p 3-64 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS EXAMPLE CALCULATIONS: Determining Dose Due to Iodine, Tritium, and Particulates, (Cont'd) where: x!Q = atmospheric dispersion factor for a mixed mode release, (sec/m3). D/Q =relative deposition rate onto ground from a mixed mode atmospheric release (m-2).
~~= the quantity of radionuclide i released in a given effluent stream based on analysis k, (µCi).~~
TAanip = a factor conv~rting airborne concentration of radionuclide i to a dose commitment to organ n of a person in age group a where exposure is directly due to airborne material via pathway P (inhalation or external exposure to the plume), mRem/yr (µCi/m 3 ). TGanip = factor converting ground deposition of radionuclide i to dose commitment to organ n of a person in age group a where exposure is due to radioactive material via pathway P (direct radiation from ground plane deposition, fruits and vegetables, air-grass-cow-mec;1t, or air-grass-cow-milk) mRem/yr (µCi/m 2
~~sec)~~
Dank = the dose commitment to organ n of a person in age group a due to radionuclides identified in analysis k of an air effluent, (mRem). The organ and total body dose to an infant from radioiodines and particulates via the grass-cow-milk pathway is shown in the following worksheet. 3- 65 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE - IODINE 131, 133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) EXAMPLE CALCULATIONS: Determining Dose Due to Iodine, Tritium, and Particulates, (Cont'd) GRASS-COW-MILK PATHWAY Organ Radionuclide TGan;p Total Dose Sum of Qik xtQ or D/Q 3.17E-8 Dank Dank (mRem) Bone H-3 2.0E+B 0 0 Co-58 2.0E+1 0 0 Co-60 1.7E+1 0 0
- 1-131 3.9E+3 2.59E+9 SE-10 3.17E-8 1.6E-4 Cs-137 6.1E+1 6.44E+10 SE-10 3.17E-8 6.2E-5 2.2E-4 Liver H-3 2.0E+B 2.37E+3 1E-7 3.17E-8 1.5E-3 Co-58 2.0E+1 2.55E+7 SE-10 3.17E-8 8.1E-9 Co-60 1.7E+1 8.73E+7 SE-10 3.17E-8 2.4E-8 1-131 3.9E+3 3.09E+9 SE-10 3.17E-8 1.9E-4 Cs-137 6.1E+1 7.21E+10 SE-10 3.17E-8 7.0E-5 1.BE-3 Thyroid H-3 2.0E+B 2.37E+3 1E-7 3.17E-8 1.5E-3 Co-58 2.0E+1 0 Co-60 1.7E+1 0 1-131 3.9E+3 9.94E-11 SE-10 3.17E-8 6.1E-1 Cs-137 6.1E+1 0 6.1 E-1 3 - 66 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE- IODINE-131, 133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) EXAMPLE CALCULATIONS: Determining Dose Due to Iodine, Tritium, and Particulates, (Cont'd) GRASS-COW-MILK PATHWAY Total Dose Sum of Organ Radionuclide Qik TGanip xtQ or D/Q 3.17E-8 Dank Dank(mRem) Kidney H-3 2.0E+B 1.04E+3 1E-7 3.17E-8 6.6E-4 Co-58 2.0E+1 0 Co-60 1.7E+1 0 1-131 3.9E+3 7.74E+8 5E-10 3.17E-8 4.BE-5 Cs-137 6.1E+1 3.66E+9 5E-10 3.17E-8 3.5E-6 7.1E-4 Lung H-3 2.0E+B 2.37E+3 1E-7 3.17E-8 1.5E-3 Co-58 2.0E+1 0 Co-60 1.7E+1 0 1-131 3.9E+3 0 Cs-137 6.1E+1 8.69E+9 5E-10 3.17E-8 8.4E-6 1.5E-3 GI/LI H-3 2.0E+B 2.37E+3 1E-7 3.17E-8 1.5E-3 Co-58 2.0E+1 6.6E+7 Co-60 1.7E+3 2.16E+8 1-131 3.9E+3 1.16E+8 Cs-137 6.1E+1 1.86E+8 5E-10 3.17E-8 1.83E-7 1.5E-3 3 - 67 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.4: DOSE- IODINE-131, 133. TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM, (Cont'd) EXAMPLE CALCULATIONS: Determining Dose Due to Iodine, Tritium, and Particulates, (Cont'd) GRASS-COW-MILK PATHWAY Total Dose Sum of Organ Radionuclide Qik TGan;p y}Q or D/Q 3.17E-8 Dank Dank(mRem) Total Body H-3 2.0E+8 2.37E+3 1E-7 3.17E-8 1.5E-3 Co-58 2.0E+1 6.24E+7 Co-60 1.7E+3 2.09E+8 1-131 3.8E+3 1.81E+9 Cs-137 6.1E+1 4.14E+9 5E-7 3.17E-8 4.0E-6 1.5E-3 Skin H-3 2.0E+8 0 0 Co-58 2.0E+1 0 0 Co-60 ~.7E+1 0 0 1-131 3.9E+3 0 0 Cs-137 6.1E+1 0 0 0 3-68 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.5 : Gaseous Radwaste Treatment System The VENTILATION EXHAUST TREATMENT SYSTEM and the GAS DECAY TANK SYSTEM shall be FUNCTIONAL and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY would exceed:
a. 0.2 mRad to air from gamma radiation, or

b. 0.4 mRad. to air from beta radiation, or

c. 0.3 mRem to any organ of a MEMBER OF THE PUBLIC.
~~APPLICABILITY: At all times. ACTION:~~
a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 1.6.6, a Special Report that includes the following information:

1. Identification of any non-functional equipment or subsystems, and the reason for the non-functionality,

2. Action(s) taken to restore the non-functional equipment to FUNCTIONAL status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Administrative Control section 1.6.3 are not applicable.
SURVEILLANCE REQUIREMENTS 3:5. 1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being f~lly utilized. 3.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and GAS DECAY TANK SYSTEM shall be considered FUNCTIONAL by meeting Controls 3.2 and either 3.3 or 3.4. 3-69 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.5: Gaseous Radwaste Treatment System, (Cont'd) METHOD 3.5: Projected Dose for Gaseous Effluents The monthly dose is normally projected by computing the dose accumulated during the most recent month and assuming the result represents the projected dose for the current month. The dose during the proceeding month will be computed as described in Methods 3.3.1, 3.3.2, and 3.4 Alternately, Control 3.5 is satisfied by extrapolating the dose to date during the current month to include the entire month. The dose to date is calculated as described in Methods 3.3.1, 3.3.2, and 3.4. This method may be used when a more accurate projection is required and sufficient data is available to make this determination. The dose is projected with the relation: 31
~~D P=~~
X Eqn 3.5-1 where: P = the projected dose during the month, (mRem) 31 = number of days in a calendar month, (days) X = number of days in current month to date represented by available radioactive effluent sample, (days) D = dose to date during current month calculated according to Methods 3.3.1, 3.3.2, and 3.4 (mRem), i.e., gamma, beta, or organ dose respectively. 3- 70 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.5: Gaseous Radwaste Treatment System, (Cont'd) BASIS 3.5: Gaseous Radwaste Treatment System This control applies to the release of radioactive materials in gaseous effluents from each unit at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system. The FUNCTIONALITY of the Gas Decay Tank System and the Ventilation Exhaust Treatment System ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the objectives given in Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose objectives set forth in Appendix I, 10 CFR Part 50, for gaseous effluents. 3 - 71 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.6: Radioactive Gaseous Effluent Accident Monitoring Instrumentation The Radioactive Gaseous Effluent Accident Monitoring Instrumentation channels shown in Table 3.6-1 shall be OPERABLE/FUNCTIONAL. APPLICABILITY: As shown in Table 3.6-1 ACTION:
a. As shown in Table 3.6-1.

b. The provisions of Administrative Control section 1.6.4 are not applicable to ACTIONS in Table 3.6-1 that require a shutdown.

c. Separate Action entry is allowed for each instrument.
SURVEILLANCE REQUIREMENTS Each Radioactive Gaseous Effluent Accident Monitoring Instrumentation channel shall be demonstrated OPERABLE/FUNCTIONAL by performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 3.6-2. BASIS 3.6 Radioactive Gaseous Effluent Accident Monitoring Instrumentation Radiation Accident Monitoring Instrumentation is provided to monitor, as required, the releases of Radioactive Material in gaseous effluents during actual or potential releases of gaseous effluents. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50. Table 3.6-1, Instrument 1a, High Range Noble Gas Plant Vent (PV) Exhaust Table 3.6.1, Radioactive Gaseous Effluent Accident Monitoring Instrumentation, Item 1.a, requires one Channel of High Range Noble Gas Effluent Monitoring for PV Exhaust to be OPERABLE/FUNCTIONAL in ALL MODES. The PV Special Particulat~, Iodine, and Noble Gas SPING (RAD-6304) provides this function. 3 - 72 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS CONTROL 3.6: Radioactive Gaseous Effluent Accident Monitoring Instrumentation (Cont'd) BASIS 3.6 Radioactive Gaseous Effluent Accident Monitoring Instrumentation (Cont'd) Table 3.6-1, Instrument 1.a, High Range Noble Gas Plant Vent (PV) Exhaust (Cont'd) The PV SPING utilizes an internal sample pump to continuously sample and monitor the PV Effluent Flow (Discharge from Unit 3 & 4 Containment Purge Systems, Gas Decay Tanks, Auxiliary Building Ventilation System, Unit 4 Spent Fuel Pit Ventilation, Radwaste Building Ventilation System, Unit 4 Cask Handling Facility, and Unit 3 & 4 Steam Jet Air Ejectors Vent Systems). The PV SPING includes piping, valves, and connections to permit normal sampling and to allow for connecting portable sampling equipment or obtaining grab samples. The PV SPING includes multiple detection channels that provide monitoring of the range of noble gases required by Regulatory Guide 1.97, Revision 3 (1.0E-06 to 1.0E-02 µCi/cc) and the extended range prescribed in NUREG-0737 (to a maximum of 1.0E+05 µCi/cc). The PV SPING is capable of providing continuous sampling and periodic monitoring of radioiodines and particulates using filter cartridges. The PV SPING provides three separate detection channels of noble gas. The ranges include the upper range Channel 9 (1.0E+OO to 1.0E+05
µCi/cc), the mid range Channel 7 (2.5E-02 to 4.0E+02 µCi/cc), and the low range Channel 5 (1.0E-07 to 6.0E-02 µCi/cc). lnoperability of any one of the three noble gas detection channels requires entry in Action 3.6.1 which requires initiation of a preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours.
Due to multiple detector channels and sampling configurations provided by the PV SPING, the preplanned alternate methods vary with the condition c1nd extent of the

inoperability. The inoperability of any single detection channel does NOT render the entire PV SPING inoperable as long as sample flow to the remaining detection channels is maintained.
Failure of the PV SPING sample pump (or any failure which prevents the required sample air from flowing through the detectors) disables all PV SPING monitoring capabilities and requires entry into Action 3.6.1 and implementation of alternate preplanned methods for each of the noble gas detection channels. With the sample flow path to the PV SPING still available, installation of the alternate sample rig to the PV SPING sample inlet line provides the capability to obtain radioiodine and particulate samples, monitor flow, and obtain gas grab samples. Note that installation of the alternate sampling rig provides a preplanned alternate method for obtaining samples, but does NOT restore OPERABILITY/FUNCTIONALITY of the PV SPING high range noble gas monitoring function. 3 - 73 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.6: Radioactive Gaseous Effluent Accident Monitoring Instrumentation (Cont'd) BASIS 3.6 Radioactive Gaseous Effluent Accident Monitoring Instrumentation (Cont'd) Table 3.6-1. Instrument 1.a. High Range Noble Gas Plant Vent (PV) Exhaust (Cont'd) Failure of PV SPING Channel 5 requires entry into Action 3.6.1. An alternate method of monitoring the noble gas is to use Process Radiation Monitoring System (PRMS) R-14 (1.0E-06 to 1.0E-03 µCi/cc) until the channel range is exceeded. With the PV SPING Channel 5 inoperable and the range of PRMS R-14 exceeded, obtain grab samples every 12 hours. Failure of PV SPING Channel 7 requires. entry into Action 3.6.1. An alternate method of monitoring the noble gas is to use PV SPING Channel 5 or PRMS R-14 until the range of these channels is exceeded. With the PV SPING Channel 5 and PRMS R-14 inoperable, or their ranges exceeded, obtain grab samples every 12 hours until the level is within the monitoring range provided by detection Channel 9. Failure of PV SPING Channel 9 requires entry into Action 3.6.1. An alternate method of monitoring the noble gas is to use PV SPING Channel 5 or PRMS R-14 until the range of these channels is exceeded. With the PV SPING Channel 5 and PRMS R-14 inoperable or their ranges exceeded, obtain grab samples every 12 hours. In Plant Mode 1, 2 or 3, Failure of the Plant Vent SPING to monitor the Steam Jet Air Ejector (SJAE) Vent for Noble Gases requires entry into Action 3.6.2. An alternate method of monitoring the noble gas is to use PRMS R-15 (1.0E-06 to 1.0E-03 µCi/cc) until the range of this channel is exceeded. With the PRMS R-15 range exceeded or inoperable, obtain grab samples every 12 hours until the Plant Vent SPING Monitoring of the SJAE Vent function is restored. 3-74 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL3.6 Radioactive Gaseous Effluent Accident Monitoring Instrumentation, (Cont'd) TABLE 3.6-1 RADIOACTIVE GASEOUS EFFLUENT ACCIDENT MONITORING INSTRUMENTATION TOTAL MINIMUM CHANNELS APPLICABLE INSTRUMENT No. OF OPERABLE/FUNCTIONAL MODES ACTION CHANNELS
1. High Range-Noble Gas Effluent Monitors

a. Plant Vent Exhaust 1 1 ALL 3.6.1 3.6.2

b. Unit 3 -Spent Fuel Pit Exhaust 1 1 ALL 3.6.1 3 - 75 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL 3.6: Radioactive Gaseous Effluent Accident Monitoring Instrumentation (Cont'd) TABLE 3.6-1 (Cont'd) TABLE NOTATION ACTION 3.6.1 - With the number of OPERABLE/FUNCTIONAL channels less than required by the Minimum Channels OPERABLE/FUNCTIONAL requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours. ACTION 3.6.2 - In Plant Mode 1, 2 or 3, with the SJAE Vent flow to the Plant Vent SPING RAD-6304 bypassed or not available, initiate the preplanned alternate method of monitoring the SJAE vent High Range Noble Gas Monitoring Function within 72 hours. 3 - 76 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT CONTROL3.6 Radioactive Gaseous Effluent Accident Monitoring Instrumentation, (Cont'd) TABLE 3.6-2 RADIOACTIVE GASEOUS EFFLUENT ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIMENTS INSTRUMENT CHANNEL CHANNEL CHECK CALIBRATION
1. High Range-Noble Gas Effluent Monitors

a. Plant Vent Exhaust M R

b. Unit 3-Spent Fuel Pit Exhaust M R 3 - 77 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT Control 3. 7 - EXPLOSIVE GAS MONITORING PROGRAM 1.0 PURPOSE The Gas Decay Tank Explosive Gas Monitoring Program for the Turkey Point Nuclear Plant (PTN) provides controls for potentially explosive gas mixtures and the quantity of radioactivity contained in the Gas Decay Tanks. 2.0 PROGRAM OWNER The Turkey Point Chemistry Group has overall responsibility for the Gas Decay Tank Explosive Gas Monitoring Program.
~~3.0 REFERENCES~~
O-ADM-651, Chemistry Parameters Manual

UFSAR Section 12 4.0 DEFINITIONS AND/OR ACRONYMS

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.

Unrestricted Area - shall mean an area, access to which is neither limited nor controlled by the licensee.

An explosive gas mixture is a mixture that contains > 4% by volume of oxygen, as measured by inline instrumentation or laboratory analysis of a grab sample.
3- 78 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT 5.0 PROGRAM DESCRIPTION Manual sampling and laboratory analysis is conducted to monitor the concentrations of oxygen and hydrogen in the cover gas of various Waste Disposal System tanks, Chemical and Volume Control System tanks and the pressurizer relief tank. Upon indication of a high oxygen level, provisions are made to purge the equipment to the gaseous waste system with an inert gas. Continuous sampling of the gas decay tank being filled is performed by on line equipment. A local alarm warns of a potentially explosive condition. Gaseous wastes will be stored in decay tanks for natural decay. Gases will be released thrnugh the monitored plant vent, and at the site boundary the annual dose will be a small fraction of 10 CFR 20 limits. Cover gases in the nitrogen blanketing system will be reused to minimize the number of tanks released. The quantity of radioactivity contained in each gas decay tank is restricted to provide (a) assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem, and (b) assurance that the concentration of potentially explosive gas mixtures contained in the Gas Decay Tank System is maintained below the flammability limits of hydrogen and oxygen. 6.0 PROGRAM IMPLEMENTATION The Explosive Gas Monitoring Program is implemented by the PTN Chemistry group with assistance from Operations and Engineering. 7 .0 ACCEPTANCE CRITERIA The concentration of oxygen in the gas decay tank system (as measured in the in-serviqe gas decay tank) shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume. A minimum of one channel of plant vent monitor is required to be operable. 3- 79 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENT 8.0 LCO REQUIRED ACTIONS/COMPENSATORY MEASURES If the number of channels is fewer than the minimum required, 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.
With the concentration of oxygen in the in-service gas decay tank greater than 2% by volume, but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours. With the concentration of oxygen in the in-service gas decay tank greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the gas decay tanks and reduce the concentration of oxygen to less than or equal to 4% by volume, then take ACTION a., above. 9.0 REPORTING REQUIREMENTS/MEASURES OF EFFECTIVENESS With the quantity of radioactive material in any gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive Effluent Release Report, pursuant to Technical Specification 6.9.1.4. 10.0 CHANGE CONTROL Changes to the Explosive Gas Monitoring Program shall be the responsibility of the Chemistry Manager. Revisions to the referenced procedures follow the guidance as contained in the applicable sections of the Nuclear Power Business Unit Procedures Manual. Changes to the procedure require 10 CFR 50.59 considerations and Onsite Review Group (ORG) review and approval as appropriate. 3- 80 REV. 26
APPEND1X3A REFERENCE METEOROLOGY ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS APPENDIX3A REFERENCE METEOROLOGY ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS Contents Table Description 3A-1 Atmospheric Dispersion Factors (x/Q) 3A-1 3A-2 Deposition Depleted Atmospheric Dispersion Factors (Xd /Q) 3A-4 (gaseous releases corrected for depletion from the plume by fallout and deposition) 3A-3 Relative Deposition Rate (D/Q) 3A-6 (fraction of airborne release which is deposited on a square meter area of land) Source of Data: Met data source: Turkey Point Nuclear Plant Met Tower Met Data Period: 01 Jan 2013 to 31 Dec 2017 Total Hours in the 5 year period: 43,824 Number of valid hourly observations: 43,301 at 10-m level Number of invalid hourly observations: 523 at 10-m level Number of Calms: 3 at 10-m level Number of valid hourly observations: 42,253 at 60-m level Number of invalid hourly observations: 1571 at 60-m level Number of Calms: 22 at 60-m level The factors include Standard Terrain/Recirculation corrections. Mixed Mode Release is assumed from the Plant Vent. The tables were reviewed in 2018 following a review of data from 2013 to 2017. Murray and Trettel, Inc. (MIT) performed XOQDOQ analysis for the Turkey Point Nuclear Plant (PTN) using 2013-17 meteorological data for two major plant sources: the Plant Vent and the Plant Stack. Five years (2013-17) of 10 m and 60 m level hourly meteorological data from the on-site meteorological monitoring tower were used for this analysis. 3A-1 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS Table 3A -1 REFERENCE METEOROLOGY -ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS 3 x/ Q sec/ m BASE DISTANCE IN MILES/ KILOMETERS SECTOR Miles 0.25 0.75 0.79 1.00 1.21 1.50 2.00 2.50 2.75 3.50 4.00 Km. 0.40 1.21 1.27 1.61 1.95 2.41 3.22 4.02 4.42 5.63 6.44 NNE 1.24E-06 6.11E-07 5.73E-07 4.07E-07 3.02E-07 2.15E-07 1.33E-07 9.20E-08 7.86E-08 5.29E-08 4.26E-08 NE 9.42E-07 5.29E-07 4.99E-07 3.61E-07 2.73E-07 1.98E-07 1.26E-07 8.87E-08 7.63E-08 5.23E-08 4.25E-08 ENE 5.88E-07 3.87E-07 3.69E-07 2.83E-07 2.22E-07 1.66E-07 1.lOE-07 7.86E-08 6.82E-08 4.74E-08 3.89E-08 E 6.83E-07 4.18E-07 4.02E-07 3.18E-07 2.56E-07 1.96E-07 1.32E-07 9.65E-08 8.42E-08 5.95E-08 4.91E-08 ESE 7.03E-07 4.75E-07 4.59E-07 3.68E-07 2.99E-07 2.32E-07 1.59E-07 1.18E-07 1.03E-07 7.36E~os 6.11E-08 SE 1.05E-06 5.40E-07 5.17E-07 4.07E-07 3.30E-07 2.56E-07 1.78E-07 1.33E-07 1.17E-07 8.42E-08 7.03E-08 SSE 1.98E-06 7.98E-07 7.57E-07 5.77E-07 4.61E-07 3.57E-07 2.49E-07 1.87E-07 1.65E-07 1.20E-07 1.0lE-07 s 3.41E-06 1.30E-06 1.22E-06 8.87E-07 6.87E-07 5.16E-07 3.50E-07 2.59E-07 2.28E-07 1.64E-07 1.37E-07 SSW 8.42E-07 3.90E-07 3.68E-07 2.72E-07 2.11E-07 1.58E-07 1.06E-07 7.71E-08 6.74E-08 4.78E-08 3.95E-08 SW 2.23E-06 8.21E-07 7.59E-07 5.11E-07 3.69E-07 2.56E-07 1.57E-07 1.07E-07 9.15E-08 6.15E-08 4.96E-08 WSW 3.87E-06 1.59E-06 1.47E-06 9.98E-07 7.16E-07 4.91E-07 2.93E-07 1.97E-07 1.67E-07 1.lOE-07 8.74E-08 w 5.75E-06 2.68E-06 2.51E-06 1.75E-06 1.28E-06 8.89E-07 5.38E-07 3.64E-07 3.08E-07 2.03E-07 1.62E-07 WNW 6.47E-06 2.77E-06 2.58E-06 1.79E-06 1.31E-06 9.09E-07 5.51E-07 3.73E-07 3.16E-07 2.09E-07 1.67E-07 NW 3.97E-06 2.04E-06 1.92E-06 1.36E-06 1.00E-06 7.05E-07 4.31E-07 2.94E-07 2.SOE-07 1.66E-07 1.33E-07 .NNW 2.21E-06 1.21E-06 1.14E-06 8.04E-07 5.93E-07 4.16E-07 2.55E-07 1.73E-07 1.47E-07 9.79E-08 7.83E-08 N 2.20E-06 9.19E-07 8.SOE-07 5.76E-07 4.15E-07 2.87E-07 1.74E-07 1.18E-07 1.00E-07 6.67E-08 5.35E-08 3A-2 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS Table 3A-1 REFERENCE METEOROLOGY -ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS 3 x IQ sec/ m BASE DISTANCE IN MILES/ KILOMETERS SECTOR Miles 4.30 4.50 5.00 5.50 7.00 9.00 10.00 11.00 15.00 20.00 25.00 Km. 6.92 7.24 8.05 8.85 11.26 14.48 16.09 17.70 24.14 32.18 40.23 NNE 3.80E-08 3.53E-08 2.99E-08 2.58E-08 1.83E-08 1.30E-08 1.13E-08 1.00E-08 6.82E-09 4.77E-09 3.61E-09 NE 3.81E-08 3.55E-08 3.03E-08 2.63E-08 1.88E-08 1.36E-08 1.18E-08 1.06E-08 7.27E-09 5.14E-09 3.92E-09 ENE 3.49E-08 3.26E-08 2.80E-08 2.44E-08 1.76E-08 1.28E-08 1.12E-08 9.99E-09 6.93E-09 4.92E-09 3.77E-09 E 4.42E-08 4.14E-08 3.57E-08 3.12E-08 2.28E-08 1.67E-08 1.46E-08 1.31E-08 9.16E-09 6.55E-09 5.03E-09 ESE 5.53E-08 5.19E-08 4.49E-08 3.94E-08 2.90E-08 2.14E-08 1.88E-08 1.69E-08 1.19E-08 8.60E-09 6.65E-09 SE 6.38E-08 6.00E-08 5.21E-08 4.59E-08 3.41E-08 2.54E-08 2.24E-08 2.02E-08 1.44E-08 1.04E-08 8.09E-09 SSE 9.17E-08 8.64E-08 7.53E-08 6.65E-08 4.97E-08 3.73E-08 3.29E-08 2.98E-08 2.13E-08 1.56E-08 1.21E-08 s 1.25E-07 1.17E-07 1.02E-07 8.99E-08 6.69E-08 5.0lE-08 4.42E-08 4.00E-08 2.86E-08 2.08E-08 1.63E-08 SSW 3.57E-08 3.35E-08 2.90E-08 2.54E-08 1.87E-08 1.38E-08 1.21E-08 1.09E-08 7.70E-09 5.55E-09 4.30E-09 SW 4.42E-08 4.11E-08 3.49E-08 3.0lE-08 2.14E-08 1.53E-08 1.33E-08 1.18E-08 8.07E-09 5.68E-09 4.32E-09 WSW 7.74E-08 7.18E-08 6.04E-08 5.18E-08 3.60E-08 2.53E-08 2.18E-08 1.93E-08 1.30E-08 8.95E-09 6.73E-09 w -1.44E-07 1.33E-07 1.12E-07 9.59E-08 6.67E-08 4.68E-08 4.03E-08 3.56E-08 2.38E-08 1.64E-08 1.23E-08 WNW 1.48E-07 1.37E-07 1.15E-07 9.90E-08 6.90E-08 4.85E-08 4.18E-08 3.70E-08 2.48E-08 1.71E-08 1.29E-08 NW 1.18E-07 1.09E-07 9.22E-08 7.92E-08 5.54E-08 3.90E-08 3.37E-08 2.98E-08 2.00E-08 1.39E-08 1.04E-08 NNW 6.95E-08 6.45E-08 5.44E-08 4.68E-08 3.27E-08 2.30E-08 1.99E-08 1.76E-08 1.18E-08 8.19E-09 6.16E-09 N 4.75E-08 4.41E-08 3.73E-08 3.21E-08 2.26E-08 1.61E-08 1.39E-08 1.24E-08 8.40E-09 5.88E-09 4.46E-09 3A-3 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS Table 3A-2 REFERENCE METEOROLOGY - DEPOSITION DEPLETED ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS xiQ sec/ m3 BASE DISTANCE IN MILES/ KILOMETERS SECTOR Miles 0.25 0.75 0.79 1.00 1.21 1.50 2.00 2.50 2.75 3.50 4.00 Km. 0.40 1.21 1.27 1.61 1.95 2.41 3.22 4.02 4.42 5.63 6.44 NNE 1.19E-06 5.87E-07 5.SlE-07 3.92E-07 2.91E-07 2.07E-07 1.28E-07 8.82E-08 7.53E-08 5.05E-08 4.06E-08 NE 9.03E-07 5.08E-07 4.79E-07 3.48E-07 2.63E-07 1.90E-07 1.21E-07 8.52E-08 7.32E-08 5.0lE-08 4.06E-08 ENE 5.63E-07 3.74E-07 3.58E-07 2.75E-07 2.16E-07 1.62E-07 1.07E-07 7.64E-08 6.62E-08 4.60E-08 3.76E-08 E 6.54E-07 4.0SE-07 3.90E-07 3.lOE-07 2.49E-07 1.91E-07 1.29E-07 9.43E-08 8.22E-08 5.80E-08 4.77E-08 ESE 6.72E-07 4.61E-07 4.46E-07 3.59E-07 2.92E-07 2.27E-07 1.56E-07 1.15E-07 1.0lE-07 7.19E-08 5.95E-08 SE 1.00E-06 5.21E-07 5.00E-07 3.95E-07 3.21E-07 2.50E-07 1.74E-07 1.29E-07 1.14E-07 8.21E-08 6.84E-08 SSE 1.89E-06 7.63E-07 7.24E-07 5.55E-07 4.45E-07 3.46E-07 2.42E-07 1.81E-07 1.60E-07 1.17E-07 9.76E-08 s 3.25E-06 1.24E-06 1.16E-06 8.48E-07 6.58E-07 4.96E-07 3.37E-07 2.49E-07 2.19E-07 1.58E-07 1.32E-07 SSW 8.06E-07 3.74E-07 3.53E-07 2.62E-07 2.04E-07 1.53E-07 1.02E-07 7.44E-08 6.50E-08 4.60E-08 3.80E-08 SW 2.14E-06 7.78E-07 7.19E-07 4.84E-07 3.49E-07 2.42E-07 1.48E-07 1.0lE-07 8.61E-08 5.77E-08 4.64E-08 WSW 3.70E-06 1.SlE-06 1.40E-06 9.SlE-07 6.82E-07 4.67E-07 2.78E-07 1.86E-07 1.57E-07 1.03E-07 8.18E-08 w 5.SOE-06 2.57E-06 2.40E-06 1.68E-06 1.23E-06 8.52E-07 5.14E-07 3.46E-07 2.93E-07 1.93E-07 1.53E-07 WNW 6.20E-06 2.65E-06 2.47E-06 1.72E-06 1.25E-06 8.71E-07 5.26E-07 3.55E-07 3.0lE-07 1.98E-07 1.58E-07 NW 3.80E-06 1.96E-06 1.84E-06 1.31E-06 9.66E-07 6.78E-07 4.14E-07 2.82E-07 2.39E-07 1.58E-07 1.26E-07 NNW 2.12E-06 1.17E-06 1.lOE-06 7.74E-07 5.71E-07 4.00E-07 2.44E-07 1.66E-07 1.41E-07 9.32E-08 7.44E-08 N 2.12E-06 8.79E-07 8.13E-07 5.50E-07 3.96E-07 2.73E-07 1.65E-07 1.12E-07 9.46E-08 6.27E-08 5.0lE-08 3A-4 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS Table 3A-2 REFERENCE METEOROLOGY - DEPOSITION DEPLETED ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS xctfQ sec/ m 3 BASE DISTANCE IN MILES/ KILOMETERS SECTOR Miles 4.30 4.50 5.00 5.50 7.00 9.00 10.00 11.00 15.00 20.00 25.00 Km. 6.92 7.24 8.05 8.85 11.26 14.48 16.09 17.70 24.14 32.18 40.23 NNE 3.61E-08 3.36E-08 2.83E-08 2.44E-08 1.70E-08 1.19E-08 1.02E-08 9.03E-09 5.93E-09 3.96E-09 2.88E-09 NE 3.63E-08 3.38E-08 2.88E-08 2.49E-08 1.76E-08 1.25E-08 1.08E-08 9.58E-09 6.38E-09 4.31E-09 3.17E-09 ENE 3.38E-08 3.15E-08 2.70E-08 2.34E-08 1.67E-08 1.20E-08 1.04E-08 9.21E-09 6.19E-09 4.20E-09 3.lOE-09 E 4.30E-08 4.03E-08 3.46E-08 3.02E-08 2.18E-08 1.57E-08 1.37E-08 1.22E-08 8.23E-09 5.63E-09 4.17E-09 ESE 5.38E-08 5.04E-08 4.35E-08 3.81E-08 2.77E-08 2.02E~08 1.76E-08 1.57E-08 1.08E-08 7.41E-09 5.52E-09 SE 6.20E-08 5.82E-08 5.04E-08 4.43E-08 3.25E-08 2.38E-08 2.08E-08 1.86E-08 1.28E-08 8.85E-09 6.61E-09 SSE 8.86E-08 8.34E-08 7.24E-08 6.38E-08 4.70E-08 3.46E-08 3.03E-08 2.71E-08 1.87E-08 1.28E-08 9.53E-09 s 1.19E-07 1.12E-07 9.72E-08 8.54E-08 6.27E-08 4.59E-08 4.0lE-08 3.59E-08 2.45E-08 1.67E-08 1.23E-08 SSW 3.43E-08 3.22E-08 2.77E-08 2.42E-08 1.76E-08 1.28E-08 1.llE-08 9.92E-09 6.75E-09 4.62E-09 3.42E-09 SW 4.12E-08 3.83E-08 3.24E-08 2.79E-08 1.95E-08 1.37E-08 1.18E-08 1.04E-08 6.86E-09 4.59E-09 3.35E-09 WSW 7.23E-08 6.69E-08 5.60E-08 4.78E-08 3.27E-08 2.25E-08 1.91E-08 1.68E-08 1.07E-08 6.97E-09 4.97E-09 w 1.35E-07 1.25E-07 1.05E-07 8.94E-08 6.llE-08 4.19E-08 3.56E-08 3.llE-08 1.98E-08 1.28E-08 9.04E-09 WNW 1.39E-07 1.29E-07 1.08E-07 9.24E-08 6.34E-08 4.36E-08 3.71E-08 3.25E-08 2.08E-08 1.35E-08 9.62E-09 NW 1.12E-07 1.04E-07 8.71E-08 7.45E-08 5.13E-08 3.54E-08 3.02E-08 2.65E-08 1.71E-08 1.llE-08 7.97E-09 NNW 6.59E-08 6.llE-08 5.13E-08 4.39E-08 3.03E-08 2.09E-08 1.79E-08 1.57E-08 1.02E-08 6.68E-09 4.81E-09 N 4.45E-08 4.12E-08 3.47E-08 2.98E-08 2.07E-08 1.44E-08 1.24E-08 1.09E-08 7.16E-09 4.78E-09 3.48E-09 3A-5 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS Table 3A-3 REFERENCE METEOROLOGY -ANNUAL AVERAGED RELATIVE DEPOSITION RATE D IQ 1/M2 BASE DISTANCE IN MILES/ KILOMETERS SECTOR Miles 0.25 0.75 0.79 1.00 1.21 1.50 2.00 2.50 2.75 3.50 4.00 Km. 0.40 1.21 1.27 1.61 1.95 2.41 3.22 4.02 4.42 5.63 6.44 NNE 3.53E-08 6.SlE-09 5.73E-09 3.07E-09 1.89E-09 1.12E-09 5.63E-10 3.37E-10 2.73E-10 1.64E-10 1.27E-10 NE 2.52E-08 5.24E-09 4.61E-09 2.48E-09 l.53E-09 9.09E-10 4.57E-10 2.73E-10 2.21E-10 l.33E-10 1.03E-10 ENE 1.22E-08 2.69E-09 2.38E-09 1.29E-09 8.03E-10 4.80E-10 2.43E-10 1.47E-10 l.20E-10 7.39E-11 5.86E-11 E 1.42E-08 2.77E-09 2.45E-09 l.32E-09 8.18E-10 4.88E-10 2.48E-10 1.50E-10 1.23E-10 7.74E-11 6.24E-11 ESE l.26E-08 2.80E-09 2.47E-09 l.35E-09 8.40E-10 5.03E-10 2.56E-10 1.56E-10 1.28E-10 8.15E-11 6.65E-11 SE 1.68E-08 3.42E-09 3.02E-09 l.64E-09 l.02E-09 6.llE-10 3.12E-10 l.91E-10 1.57E-10 l.02E-10 8.37E-11 SSE 2.93E-08 5.81E-09 5.12E-09 2.77E-09 1.71E-09 1.02E-09 5.18E-10 3.18E-10 2.62E-10 l.71E-10 1.42E-10 s 4.81E-08 9.97E-09 8.79E-09 4.74E-09 2.94E-09 1.75E-09 8.86E-10 5.41E-10 4.44E-10 2.87E-10 2.37E-10 SSW 1.57E-08 3.22E-09 2.84E-09 1.54E-09 9.59E-10 5.73E-10 2.91E-10 1.76E-10 1.44E-10 8.96E-11 7.16E-11 SW 6.17E-08 l.17E-08 1.03E-08 5.49E-09 3.36E-09 l.98E-09 9.90E-10 5.89E-10 4.76E-10 2.84E-10 2.18E-10 WSW l.02E-07 1.94E-08 l.71E-08 9.07E-09 5.55E-09 3.27E-09 1.64E-09 9.76E-10 7.89E-10 4.76E-10 3.69E-10 w 1.43E-07 2.71E-08 2.38E-08 l.27E-08 7.74E-09 4.57E-09 2.29E-09 1.37E-09 1.llE-09 6.82E-10 5.38E-10 WNW 1.82E-07 3.19E-08 2.81E-08 1.49E-08 9.lOE-09 5.36E-09 2.69E-09 1.61E-09 1.31E-09 7.92E:-10 6.19E-10 NW 9.52E-08 1.82E-08 1.60E-08 8.55E-09 5.25E-09 3.llE-09 1.57E-09 9.40E-10 7.64E-10 4.68E-10 3.69E-10 NNW 5.28E-08 1.06E-08 9.36E-09 5.04E-09 3.llE-09 l.85E-09 9.34E-10 5.60E-10 4.54E-10 2.75E-10 2.15E-10 N 6.46E-08 1.17E-08 1.03E-08 5.48E-09 3.36E-09 1.99E-09 1.00E-09 5.98E-10 4.83E-10 2.88E-10 2.21E-10 3A-6 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS Table 3A- 3 REFERENCE METEOROLOGY - ANNUAL AVERAGED RELATIVE DEPOSITION RATE D/Q 1/M 2 BASE DISTANCE IN MILES/ KILOMETERS SECTOR Miles 4.30 4.50 5.00 5.50 7.00 9.00 10.00 11.00 15.00 20.00 25.00 Km. 6.92 7.24 8.05 8.85 11.26 14.48 16.09 17.70 24.14 32.18 40.23 NNE l.12E-10 l.03E-10 8.73E-11 7.60E-11 5.33E-11 3.86E-11 3.35E-11 2.98E-11 1.98E-11 l.28E-11 8.80E-12 NE 9.04E-11 8.37E-11 7.09E-11 6.19E-11 4.37E-11 3.17E-11 2.77E-11 2.46E-11 1.63E-11 1.05E-11 7.14E-12 ENE 5.23E-11 4.89E-11 4.26E-11 3.82E-11 2.83E-11 2.15E-11 1.90E-11 l.71E-11 1.16E-11 7.46E-12 5.04E-12 E 5.63E-11 5.31E-11 4.69E-11 4.28E-11 3.26E-11 2.52E-11 2.25E-11 2.03E-11 l.39E-11 9.04E-12 6.llE-12 ESE 6.04E-11 5.72E-11 5.12E-11 4.73E-11 3.67E-11 2.88E-11 2.57E-11 2.34E-11 l.61E-11 l.04E-11 7.00E-12 SE 7.65E-11 7.27E-11 6.57E-11 6.llE-11 4.80E-11 3.80E-11 3.41E-11 3.lOE-11 2.15E-11 1.40E-11 9.39E-12 SSE l.31E-10 l.25E-10 l.14E-10 1.07E-10 8.52E-11 6.82E-11 6.14E-11 5.60E-11 3.90E-11 2.53E-11 l.70E-11 s 2.17E-10 2.07E-10 l.88E-10 l.75E-10 l.39E-10 l.llE-10 9.93E-11 9.0SE-11 6.28E-11 4.07E-11 2.72E-ll SSW 6.41E-11 6.02E-11 5.27E-11 4.76E-11 3.56E-11 2.72E-11 2.41E-11 2.17E-11 1.48E-11 9.57E-12 6.46E-12 SW l.91E-10 1.76E-10 1.48E-10 l.28E-10 8.86E-11 6.36E-11 5.53E-11 4.90E-ll 3.22E-11 2.07E-11 1.41E-11 WSW 3.25E-10 3.02E-10 2.56E-10 2.25E-10 l.60E-10 l.17E-10 l.03E-10 9.17E-11 6.llE-11 3.95E-11 2.68E-11 w 4.79E-10 4.47E-10 3.87E-10 3.46E-10 2.55E-10 1.93E-10 1.70E-10 l.53E-10 1.04E-10 6.69E-11 4.52E-11 WNW 5.47E-10 5.08E-10 4.34E-10 3.82E-10 2.74E-10 2.02E-10 1.77E-10 l.59E-10 1.06E-10 6.91E-11 4:72E-11 NW 3.28E-10 3.06E-10 2.65E-10 2.36E-10 l.73E-10 l.30E-10 l.14E-10 l.03E-10 6.94E-11 4.49E-11 3.04E-11 NNW l.89E-10 l.76E-10 1.SOE-10 l.32E-10 9.41E-11 6.91E-11 6.04E-11 5.39E-11 3.60E-11 2.33E-11 1.58E-11 N l.92E-10 l.77E-10 1.47E-10 1.26E-10 8.56E-11 6.0lE-11 5.18E-11 4.57E-11 2.98E-11 l.94E-11 l.35E-11 3A- 7 REV. 26
APPENDIX 38 PATHWAY-DOSE TRANSFER FACTORS REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS APPEND1X3B PATHWAY-DOSE TRANSFER FACTORS Environmental pathway transfer factors, usage factors, and dose commitment factors appropriate for each exposure pathway, age, and organ are combined into integrated environmental concentration-to-dose factors for each radionuclide. This appendix includes tables of values of the transfer factors calculated in accord with equations and values recommended in NUREG-0133 1 for individual environmental pathways. In the event a single, composite transfer factor is desired for a given organ and age group, it can be obtained by summing the factors for appropriate pathways. Appropriate transfer factors from Appendix A are used in performing dose assessment calculations prescribed in the ODCM.
~~1. J. Boegli, et. al., eds., 1978, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133, USNRC, Office of Nuclear Reactor Regulation.~~
38 -1 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - GROUND PLANE DEPOSITION AGE GROUP -ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 0. 0. 0. 0. 0. 0. 0. P~32 0. 0. 0. 0. 0. 0. 0. 0. CR-51 4.68E+06 4.68E+06 4.68E+06 4.68E+06 4.68E+06 4.68E+06 5.53E+06 4.68E+06 MN-54 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.62E+09 1.38E+09 FE-59 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 3.23E+08 2.75E+08 C0-57 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 2.08E+08 1.89E+08 C0-58 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 4.45E+08 3.80E+08 C0-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.52E+10 2.15E.10 Nl-63 0. 0. 0. 0. 0. 0. 0. 0. ZN-65 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 8.54E+08 7.43E+08 RB-86 9.01E+06 9.01E+06 9.01E+06 9.01E+06 9.01E+06 9.01 E+06 1.03E+07 9.01E+06 SR-89 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.51E+04 2.17E+04 SR-90 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 6.33E+06 5.35E+06 Y-91 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.22E+06 1.08E+06 ZR-95 5.01E+08 5.01E+08 5.01E+08 5.01E+08 5.01E'f-08 5.01E+08 5.86E+08 5.01E+08 NB-95 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.61E+08 1.36E+08 RU-103 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.28E+08 1.10E+08 RU-106 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 5.03E+08 4.19E+08 AG-110M 3.58E+09
~~3.58E+09 3.58E+09 3.58E+09 3.58E+09 3.58E+09 4.17E+09 3.58E+09 CD-115M 0. 0. 0. 0. 0. 0. 0. 0.~~
BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/0, Xci/Q, AND D/Q. 38 -2 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - GROUND PLANE DEPOSITIONAGE GROUP-ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 1.37E+06 0. SN-126 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.76E+10 5.16E+10 SB-124 5.98E+08 5.98E+09 5.98E+08 5.98E+08 5.98E+08 5.98E+08 6.90E+08 5.98E+08 SB-125 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.59E+09 2.30E+09 TE-125M 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 2.13E+06 1.55E+06 TE-127M 8.79E+05 879E+05 8.79E+05 8.79E+05 8.79E+05 8.79E+05 9.74E+05 8.79E+05 TE-129M 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 4.52E+07 3.85E+07 1-130 5.53E+06 5.53E+06 5.53E+06 5.53E+06 5.53E+06 5.53E+06 6.71E+06 5.53E+06 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2.09E+07 1.72E+07 1-132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.47E+06 1.25E+06 1-133 2.48E+06 2.48E+06 2.48E+06 2.48E+06 2.48E+06 2.48E+06 3.01E+06 2.48E+06 1-134 4.50E+05 4.50E+05 4.50E+05 4.50E+05 4.50E+05 4.50E+05 5.35E+05 4.50E+05 1-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.99E+06 2.56E+06 CS-134 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 8.15E+09 6.99E+09 CS-136 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 1.49E+08 CS-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 1.03E+10 BA-140 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.90E+08 1.68E+08 CE-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.54E+07 1.37E+07 CE-144 1.13E+08 1.13E+08 1.13E+08 1.13E+08 1.13E+08 1.13E+08 1.31E+08 1.13E+08 PR-143 0. 0. 3.58E+09 0. 0. 0. 0. 0. ND-147 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 1.02E+07 8.48E+06 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x!Q, xctiO, AND D/Q. 38-3 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITEOOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - GROUND PLANE DEPOSITION AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. ' 0. 0. 0. 0. 0. 0. 0. P-32 0. 0. 0. 0. 0. 0. 0. 0. CR-51 4.68E+06 4.68E+06 4.68E+06 4.68E+06 4.68E+06 4.68E+06 5.53E+06 4.68E+06 MN-54 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.62E+09 1.38E+09 FE-59 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 3.23E+08 2.75E+08 C0-57 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 2.0BE+OB 1.89E+08 C0-58 3.BOE+OB 3.BOE+OB 3.BOE+OB 3.BOE+OB 3.BOE+OB 3.80E+08 4.45E+08 3.80E+08 C0-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.52E+10 2.15E+10 Nl-63 0. 0. 0. 0. 0. 0. 0. 0. ZN-65 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 8.54E+08 7.43E+08 RB~86 9.01E+06 9.01E+06 9.01E+06 9.01E+06 9.01E+06 9.01E+06 1.03E+07 9.01E+06 SR-89 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.51E+04 2.17E+04 SR-90 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 6.33E+06 5.35E+06 Y-91 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.22E+06 1.08E+06 ZR-95 5.01E+08 5.01E+08 5.01E+08 5.01E+08 5.01E+08 5.01E+08 5.86E+08 5.01E+08 NB-95 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.61E+08 1.36E+08 RU-103 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.28E+08 1.10E+08 RU-106 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 5.03E+08 4.19E+08 . AG-110M 3.58E+09 3.58E+09 3.58E+09 3.58E+09 3.58E+09 3.58E+09 4.17E+09 3.58E+09 CD-115M 0. 0. 0. 0. 0. 0. 0. 0. BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xiQ, AND D/Q. 3B-4 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - GROUND PLANE DEPOSITION AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 1.37E+06 0. SN-126 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.76E+10 5.16E+10 SB-124 5.98E+08 5.98E+08 5.98E+08 5.98E+08 5.98E+08 5.98E+08 6.90E+08 5.98E+08 SB-125 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.59E+09 2.30E+09 TE-125M 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 2.13E+06 1.55E+06 TE-127M 8.79E+05 8.79E+05 8.79E+05 8.79E+05. 8.79E+05 8.79E+05 9.74E+05 8.79E+05 TE-129M 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 4.52E+07 3.85E+07 1-130 5.53E+06 5.53E+06 5.53E+06 5.53E+06 5.53E+06 5.53E+06 6.71E+06 5.53E+06 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2.09E+07 1.72E+07 1-132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.47E+06 1.25E+06 1-133 2.48E+06 2.48E+06 2.48E+06 2.48E+06 2.48E+06 2.48E+06 3.01E+06 2.48E+06 1-134 4.50E+05 4.50E+05 4.50E+05 4.50E+05 4.50E+05 4.50E+05 5.35E+05 4.50E+05 1-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.99E+06 2.56E+06 CS-134 6.99E+09 . 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 8.15E+09 6.99E+09 CS-136 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 1.49E+08 CS-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 1.03E+10 BA-140 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.90E+08 1.68E+08 CE-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.54E+07 1.37E+07 CE-144 1.13E+08 1.13E+08 1.13E+08 1.13E+08 1.13E+08 1.13E+08 1.31E+08 1.13E+08 PR-143 0. 0. 0. 0. 0. 0. 0. 0. ND-147 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 1.02E+07 8.48E+06 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, Xci/Q, AND D/Q. 38 - 5 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - GROUND PLANE DEPOSITION AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 0. 0. 0. 0. 0. 0. 0. P-32 0. 0. 0. 0. 0. 0. 0. 0. CR-51 4.68E+06 4.68E+06 4.68E+06 4.68E+06 4.68E+06 4.68E+06 5.53E+06 4.68E+06 MN-54 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.62E+09 1.38E+09 FE-59 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 3.23E+08 2.75E+08 C0-57 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 2.08E+08 1.89E+08 C0-58 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 4.45E+08 3.80E+08 C0-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.52E+10 2.15E+10 Nl-63 0. 0. 0. 0. 0. 0. 0. 0. ZN-65 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 8.54E+08 7.43E+08 RB-86 9.01E+06 9.01E+06 9.01E+06 9.01E+06 9.01E+06 9.01E+06 1.03E+07 9.01E+06 SR-89 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.51E+04 2.17E+04 SR-90 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 6.33E+06 5.35E+06 Y-91 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.22E+06 1.08E+06 ZR-95 5.01E+08 5.01 E+08 5.01E+08 5.01E+08 5.01E+08 5.01E+08 5.86E+08 5.01E+08 NB-95 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.61E+08 1.36E+08 RU-103 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.28E+08 1.10E+08 RU-106 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 5.03E+08 4.19E+08 AG-110M 3.58E+09 3.58E+09 3.58E+09 3.58E+09 3.58E+09 3.58E+09 4.17E+09 3.58E+09 CD-115M 0. 0. 0. 0. 0. 0. 0. 0. BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, Xci/Q, AND D/Q. 3B-6 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - GROUND PLANE DEPOSITION AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 1.37E+06 0. SN-126 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.76E+10 5.16E+10 SB-124 5.98E+08 5.98E+08 5.98E+08 5.98E+08 5.98E+08 5.98E+08 6.90E+08 5.98E+08 SB-125 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.59E+09 2.30E+09 TE-125M 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 2.13E+06 1.55E+06 TE-127M 8.79E+05 8.79E+05 8.79E+05 8.79E+05 8.79E+05 8.79E+05 9.74E+05 8.79E+05 TE-129M 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 4.52E+07 3.85E+07 1-130 5.53E+06 5.53E+06 5.53E+06 5.53E+06 5.53E+06 5.53E+06 6.71E+06 5.53E+06 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2.09E+07 1.72E+07 1-132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.47E+06 1.25E+06 1-133 2.48E+06 2.48E+06 2.48E+06 2.48E+06 2.48E+06 2.48E+06 3.01E+06 2.48E+06 1-134 4.50E+05 4.50E+05 4.50E+05 4.50E+05 4.50E+05 4.50E+05 5.35E+05 4.50E+05 1-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.99E+06 2.56E+06 CS-134 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 8.15E+09 6.99E+09 CS-136 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 1.49E+08 CS-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 1.03E+10 BA-140 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.90E+08 1.68E+08 CE-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.54E+07 1.37E+07 CE-144 1.13E+08 1.13E+08 1.13E+08 1.13E+08 1.13E+08 1.13E+08 1.31E+08 1.13E+08 PR-143 0. 0. 0. 0. 0. 0. 0. 0. ND-147 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 1.02E+07 8.48E+06 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xiO, AND D/Q. 38 -7 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - GROUND PLANE DEPOSITION AGE GROUP - INFANT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC)
*BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 0. 0. 0. 0. 0. 0. 0.
P-32 0. 0. 0. 0. 0. 0. 0. 0. CR-51 4.68E+06 4.68E+06 4.68E+06 4.68E+06 4.68E+06 4.68E+06 5.53E+06 4.68E+06 MN-54 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.62E+09 1.38E+09 FE-59 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 3.23E+08 2.75E+08 C0-57 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 2.08E+08 1.89E+08 C0-58 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 4.45E+08 3.80E+08 C0-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.52E+10 2.15E+10 Nl-63 0. 0. 0. 0. 0. 0. 0. 0. ZN-65 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 8.54E+08 7.43E+08 RB-86 9.01E+06 9.01E+06 9.01E+06 9.01E+06 9.01E+06 9.01E+06 1.03E+07 9.01E+06 SR-89 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.51E+04 2.17E+04 SR-90 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 6.33E+06 5.35E+06 Y-91 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.22E+06 1.08E+06 ZR-95 5.01E+08 5.01E+08 5.01E+08 5.01E+08 5.01E+08 5.01E+08 5.86E+08 5.01 E+08 NB-95 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.61E+08 1.36E+08 RU-103 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.28E+08 1.10E+08 RU-106 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 5.03E+08 4.19E+08 AG-110M 3.58E+09 3.58E+09 3.58E+09 3.58E+09 3.58E+09 3.58E+09 4.17E+09 3.58E+09 CD-115M o. 0. 0. 0. 0. 0. 0. 0. BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xiQ, AND D/Q. 38-8 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - GROUND PLANE DEPOSITION AGE GROUP - INFANT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 1.37E+06 0. SN-126 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.76E+10 5.16E+10 SB-124 5.98E+08 5.98E+08 5.98E+08 5.98E+08 5.98E+08 - 5.98E+08 6.90E+08 5.98E+08 SB-125 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.30E+09 2.59E+09 2.30E+09 TE-125M 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 2.13E+06 1.55E+06 TE-127M 8.79E+05 8.79E+05 8.79E+05 8.79E+05 8.79E+05 8.79E+05 9.74E+05 8.79E+05 TE-129M 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 4.52E+07 3.85E+07 1-130 5.53E+06 5.53E+06 5.53E+06 5.53E+06 5.53E+06 5.53E+06 6.71E+06 5.53E+06 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2.09E+07 1.72E+07 1-132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.47E+06 1.25E+06 1-133 2.48E+06 2.48E+06 2.48E+06 2.48E+06 2.48E+06 2.48E+06 3.01E+06 2.48E+06 1-134 4.50E+05 4.50E+05 4.50E+05 4.50E+05 4.50E+05 4.50E+05 5.35E+05 4.50E+05 1-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.99E+06 2.56E+06 CS-134 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 8.15E+09 6.99E+09 CS-136 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 1.49E+08 CS-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 1.03E+10 BA-140 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.90E+08 1.68E+08 CE-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.54E+07 1.37E+07 CE-144 1,13E+08 1.13E+08 1.13E+08 1.13E+08 1.13E+08 1.13E+08 1.31E+08 1.13E+08 PR-143 0. 0. 0. 0. 0. 0. 0. 0. ND-147 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 1.02E+07 8.48E+06 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, Xci/Q, AND D/Q. 38- 9 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY- INHALATION AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (MREM/YR PER UGI/CU.METER) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 0. 1.26E+03 P-32 1.32E+06 7.72E+04 0. 0. 0. 8.64E+04 0. 5.02E+04 CR-51 0. 0. 5.95E+01 2.28E+01 *1.44E+04 3.32E+03 0. 1.00E+02 MN-54 0. 3.96E+04 0. 9.84E+03 1.40E+06 7.74E+04 0. 6.30E+03 FE-59 1.18E+04 2.78E+07 0. 0. 1.02E+06 1.88E+05 0. 1.06E+04 C0-57 0. 6.92E+02 0. 0. 3.70E+05 3.14E+04 0. 6.71E+02 C0-58 0. 1.58E+03 0. 0. 9.28E+05 1.06E+05 0. 2.07E+03 C0-60 0. 1.15E+04 0. 0. 5.98E+06 2.85E+05 0. 1.48E+04 Nl-63 4.32E+05 3.14E+04 0. 0. 1.78E+05 1.34E+04 0. 1.45E+04 ZN-65 3.24E+04 1.03E+05 0. 6.90E+04 8.72E+05 5.34E+04 0. 4.66E+04 RB-86 0. 1.35E+05 0. 0. 0. 1.66E+04 0. 5.90E+04 SR-89 3.04E+05 0. 0. 0. 1.40E+06 3.50E+05 0. 8.72E+03 SR-90 9.92E+07 0. 0. 0. 9.60E+06 7.22E+05 0. 6.10E+06 Y-91 4.62E+05 0. 0. 0. 1.70E+06 3.85E+05 0. 1.24E+04 ZR-95 1.07E+05 3.44E+04 0. 5.42E+04 1.78E+06 1.50E+05 0. 2.33E+04 NB-95 1.41 E+04 7.82E+03 0. 7.74E+03 5.06E+05 1.04E+05 0. 4.21E+03 RU-103 1.58E+03 0. 0. 5.83E+03 5.06E+05 1.10E+05 0. 6.58E+02 RU-106 6.91E+04 0. 0. 1.34E+05 9.44E+06 9.12E+05 0. 8.72E+03 AG-110M 1.08E+04 1.00E+04 0. 1.97E+04 4.64E+06 3.02E+05 0. 5.94E+03 CD-115M 0. 1.97E+05 0. 1.50E+05 1.41E+06 3.84E+05 0. 6.36E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q AND Xd/Q 38 -10 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY- INHALATION AGE GROUP -ADULT NUCLIDE ORGAN DOSE FACTORS (MREM/YR PER UCI/CU.METER) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-123 2.42E+05 5.33E+03 4.53E+03 0. 2.30E+06 3.14E+05 0. 7.86E+03 SN-126 1.26E+06 3.34E+04 9.84E+03 0. 9.36E+06 1.27E+05 0. 4.80E+04 SB-124 3.12E+04 5.89E+02 7.55E+01 0. 2.48E+06 4.06E+05 0. 1.24E+04 SB-125 6.61E+04 7.13E+02 5.87E+01 0. 2.20E+06 1.01E+05 0. 1.33E+04 TE-125M 3.42E+03 1.58E+03 1.05E+03 1.24E+04 3.14E+05 7.06E+04 0. 4.67E+02 TE-127M 1.26E+04 5.62E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 0. 1.57E+03 TE-129M 9.76E+03 4.67E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 0. 1.58E+03 1-130 4.58E+03 1.34E+04 1.74E+06 2.09E+04 0. 7.69E+03 0. 5.29E+03 1-131 2.52E+04 3.58E+04 1.19E+07 6.14E+04 0. 6.28E+03 0. 2.05E+04 1-132 1.16E+03 3.26E+03 4.38E+05 5.19E+03 0. 4.06E+02 0. 1.16E+03 1-133 8.64E+03 1.49E+04 2.93E+06 2.60E+04 0. 8.72E+03 0. 4.54E+03 1-134 6.45E+02 1.73E+03 2.30E+05 2.75E+03 0. 1.01E+OO 0. 6.16E+02 1-135 2.89E+03 6.99E+03 9.36E+05 1.11 E+04 0. 5.25E+03 0. 2.58E+03 CS-134 3.74E+05 8.48E+05 0. 2.88E+05 9.76E+04 1.04E+04 0. 7.29E+05 CS-136 3.91E+04 1.46E+05 0. 8.56E+04 1.20E+04 1.17E+04 0. 1.11E+05 CS-137 4.78E+05 6.22E+05 0. 2.22E+05 7.53E+04 8.40E+03 0. 4.29E+05 BA-140 3.90E+04 4.90E+01 0. 1.67E+01 1.27E+06 2.18E+05 0. 2.57E+03 CE-141 1.99E+04 1.35E+04 0.
6.26E+03 3.62E+05 1.20E+05 0. 1.53E+03 CE-144 3.43E+06 1.43E+06 0. 8.48E+05 7.78E+06 8.16E+05 0. 1.84E+05 PR-143 9.36E+03 3.75E+03 0. 2.16E+03 2.81E+05 2.00E+05 0. 4.63E+02 ND-147 5.27E+03 6.10E+03 0. 3.56E+03 2.21E+05 1.73E+05 0. 3.65E+02 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q AND xiQ 38 - 11 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY- INHALATION AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (MREM/YR PER UCI/CU.METER) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 1.27E+02 1.27E+02 1.27E+03 1.27E+02 1.27E+02 0. 1.27E+02 P-32 1.32E+06 7.72E+04 0. 0. 0. 8.64E+04 0. 5.02E+04 CR-51 0. 0. 5.95E+01 2.28E+01 1.44E+04 3.32E+03 0. 1.00E+02 MN-54 0. 3.96E+04 0. 9.84E+03 1.40E+06 7.74E+04 0. 6.30E+03 FE-59 1.18E+04 2.78E+07 0. 0. 1.02E+06 1.88E+05 0. 1.06E+04 C0-57 0. 6.92E+02 0. 0. 3.70E+05 3.14E+04 0. 6.71E+02 C0-58 0. 1.76E+02 0. 0. 1.37E+06 9.52E+04 0. 2.34E.02 C0-60 0. 1.24E+03 0. 0. 8.56E+06 2.35E+05 0. 1.65E+34 Nl-63 4.32E+05 3.14E+04 0. 0. 1.78E+05 1.34E+04 0. 1.45E+04 ZN-65 3.24E+04 1.03E+05 0. 6.90E+04 8.72E+05 5.34E+04 0. 4.66E+04 RB-86 0. 1.35E+05 0. 0. 0. 1.66E+04 0. 5.90E+04 SR-89 3.37E+04 0. 0. 0. 2.50E+06 3.54E+05 0. 1.11E+03 SR-90 1.18E+07 0. 0. 0. 1.66E+07 7.24E+05 0. 7.23E+05 Y-91 5.38E+04 0. 0. 0. 2.86E+06 3.74E+05 0. 1.44E+03 ZR-95 1.09E+04 3.663+03 0. 5.42E+04 2.56E+06 1.33E+05 0. 2.54E+03 NB-95 1.36E+03 8.24E+02 0. 7.74E+03 7.17E+05 8.80E+04 0. 4.62E+02 RU-103 1.63E+02 0. 0. 5.83E+03 7.51E+05 9.44E+04 0. 7.32E+01 RU-106 8.40E+03 0. 0. 1.34E+D5 1.64E+07 9.28E+05 0. 1.06E+03 AG-110M 1.08E+04 1.00E+04 0. 1.97E+04 4.64E+06 3.02E+05 0. 5.94E+03 CD-115M 0. 1.97E+05 0. 1.58E+05 1.41E+06 3.84E+05 0. 6.36E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x!Q AND xiQ. 38 -12 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY- INHALATION AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (MREMNR PER UGI/CU.METER) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 2.79E+04 6.14E+02 4.92E+02 0. 3.91E+06 3.13E+05 0. 9.20E+02 SN-126 1.26E+06 3.34E+04 9.84E+03 0. 9.36E+06 1.27E+05 0. 4.80E+04 SB-124 3.12E+04 5.89E+02 7.55E+01 0. 2.48E+06 4.06E+05 0. 1.24E+04 SB-125 6.61E+04 7.13E+02 5.87E+01 0. 2.20E+06 1.01E+05 0. 1.33E+04 TE-125M 4.07E+02 1.86E+02 1.17E+02 1.24E+04 5.36E+05 7.08E+04 0. 5.53E+01 TE-127M 1.26E+04 5.62E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 0. 1.57E+03 TE-129M 1.19E+03 5.64E+02 3.90E+02 3.66E+04 2.03E+06 3.84E+05 0. 1.92E+02 1-130 4.58E+03 1.34E+04 1.74E+06 2.09E+04 0. 7.69E+03 0. 5.29E+03 1-131 3.37E+04 4.72E+04 1.39E+07 6.14E+04 0. 5.96E+03 0. 2.82E+04 1-132 1.16E+03 3.26E+03 4.38E+05 5.19E+03 0. 4.06E+02 0. 1.16E+03 1-133 1.23E+04 2.06E+04 3.83E+06 2.60E+04 0. 1.00E+04 0. 6.34E+03 1-134 6.45E+03 1.73E+03 2.30E+05 2.75E+03 0. 1.01 E+OO 0. 6.16E+02 1-135 2.69E+03 6.99E+03 9.36E+05 1.11E+04 0. 5.25E+03 0. 2.58E+03 CS-134 4.83E+Q5 1.10E+06 0. 2.88E+05 1.44E+05 8.96E+03 0. 5.44E+05 CS-136 3.91E+04 1.46E+05 0. 8.56E+04 1.20E+04 1.17E+04 0. 1.11 E+05 CS-137 6.42E+05 8.24E+05 0. 2.22E+05 1.18E+05 7.68E+03 0. 3.03E+05 BA-140 5.30E+03 4.85E+OO 0. 1.67E+01 2.02E+06 2.12E+04 0. 3.42E+02 CE-141 2.27E+03 1.52E+03 0. 6.26E+03 5.83E+05 1.14E+05 0. 1.74E+02 CE-144 4.19E+05 1.74E+05 0. 8.48E+05 1.. 38E+07 8.40E+05 0. 2.24E+04 PR-143 9.36E+03 3.75E+03 0. 2.16E+03 2.81E+05 2.00E+05 0. 4.63E+02 ND-147 5.27E+03 6.10E+03 0. 3.56E+03 2.21E+05 1.73E+05 0. 3.65E+02 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q AND Xci/Q. 38 -13 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - INHALATION AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (MREM/YR PER UGI/CU.METER) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 0. 1.12E+03 P-32 6.11 E+05 3.57E+04 0. 0. 0. 4.00E+04 0. 2.32E+04 CR-51 0. 0. 2.75E+01 1.06E+01 6.66E+03 1.54E+03 0. 4.63E+01 MN-54 0. 1.83E+04 0. 4.55E+03 6.48E+05 3.58E+04 0. 2.91E+03 FE-59 5.44E+03 1.28E+07 0. 0. 4.70E+05 8.70E+04 0. 4.88E+03 C0-57 0. 3.20E+02 0. 0. 1.71E+05 1.45E+04 0. 3.10E+02 C0-58 0. 1.52E+02 0. 0. 1.13E+06 3.62E+04 0. 2.68E+02 C0-60 0. 1.07E+03 0. 0. 6.92E+06 9.36E+04 0. 1.88E+03 Nl-63 2.00E+05 1.45E+04- 0. 0. 8.25E+04 6.18E+03 0. 6.70E+03 ZN-65 1.50E+04 4.77E+04 0. 3.19E+04 4.03E+05 2.47E+04 0. 2.15E+04 RB-86 0. 6.25E+04 0. 0. 0. 7.70E+03 0. 2.73E+04 SR-89 5.37E+04 0. 0. 0. 2.24E+06 1.69E+05 0. 1.54E+03 SR-90 1.64E+07 0. 0. 0. 1.48E+07 3.45E+05 0. 9.99E+05 Y-91 7.44E+04 0. 0. 0. 2.55E+06 1.78E+05 0. 1.98E+03 ZR-95 1.41E+04 3.28E+03 0. 2.51E+04 2.12E+06 5.74E+04 0. 2.98E+03 NB-95 1.70E+03 7.25E+02 0. 3.58E+03 5.85E+05 3.32E+04 0. 5.33E+02 RU-103 2.16E+02 0. 0. 2.70E+03 6.33E+05 4.22E+04 0. 8.73E+01 RU-106 1.15E+04 0. 0. 6.18E+04 1.45E+07 4.37E+05 0. 1.44E+03 AG-110M 5.00E+03 4.63E+03 .o. 9.10E+03 2.15E+06 1.40E+05 0. 2.75E+03 CD-115M 0. 9.10E+04 0. 7.33E+04 6.51E+05 1.78E+05 0. 2.94E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/0 AND Xci/Q. 38 -14 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - INHALATION AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (MREM/YR PER UGI/CU.METER) BONE;_ LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 3.85E+04 6.44E+02 6.81E+02 0. 3.50E+06 1.49E+05 0. 1.27E+03 SN-126 5.85E+05 1.55E+04 4.55E+03 0. 4.33E+06 5.88E+04 0. 2.22E+04 SB-124 1.44E+04 2.72E+02 3.49E+01 0. 1.15E+06 1.88E+05 0. 5.74E+03 SB-125 3.06E+04 3.30E+02 2.72E+01 0. 1.02E+06 4.66E+04 0. 6.14E+03 TE-125M 5.62E+02 1.94E+02 1.61E+02 5.74E+03 4.81E+05 3.38E+04 0. 7.62E+01 TE-127M 5.85E+03 2.60E+03 1.52E+03 2.12E+04 4.44E+05 6.92E+04 0. 7.25E+02 TE-129M 1.64E+03 5.85E+02 5.40E+02 1.69E+04 1.80E+06 1.82E+05 0. 2.60E+02 1-130 2.12E+03 6.22E+03 8.07E+05 9.66E+03 0. 3.56E+03 0. 2.45E+03 1-131 4.55E+04 4.63E+04 1.54E+07 2.84E+04 0. 2.65E+03 0. 3.50E+04 1-132 5.37E+02 1.51E+03 2.03E+05 2.40E+03 0. 1.88E+02 0. 5.37E+02 1-133 1.68E+04 2.05E+04 5.03E+06 1.20E+04 0. 5.55E+03 0. 8.03E+02 1-134 2.98E+02 7.99E+02 1.06E+05 1.27E+03 0. 4.66E-01 0. 2.85E+02 1-135 1.24E+03 3.23E+03 4.33E+05 5.14E+03 0. 2.43E+03 0. 1.19E+03 CS-134 6.22E+05 9.95E+05 0. 1.33E+05 1.19E+05 3.77E+03 0. 2.23E+05 CS-136 1.81E+04 6.77E+04 0. 3.96E+04 5.55E+03 5.40E+03 0. 5.14E+04 CS-137 8.66E+05 7.99E+05 0. 1.03E+05 1.00E+05 3.41E+03 0. 1.25E+05 BA-140 7.14E+03 4.66E+OO 0. 7.73E+OO 1.74E+06 9.92E+03 0. 4.22E+02 CE-141 3.13E+03 1.57E+03 0. 2.90E+03 5.14E+05 5.44E+04 0. 2.33E+02 CE-144 5.81E+05 1.82E+05 0. 3.92E+05 1.23E+07 4.00E+05 0. 3.10E+04 PR-143 4.33E+03 1.74E+03 0. 9.99E+02 1.30E+05 9.25E+04 0. 2.14E+02 ND-147 2.44E+03 2.82E+03 0. 1.65E+03 1.02E+05 7.99E+04 0. 1.69E+02 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q AND xiO. 3B - 15 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY- INHALATION AGE GROUP - INFANT NUCLIDE ORGAN DOSE FACTORS (MREM/YR PER UGI/CU.METER) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 0. 6.47E+02 P-32 2.31 E+05 1.35E+04 0. 0. 0. 1.51 E+04 0. 8.78E+03 CR-51 0. 0. 1.94E+01 3.99E+OO 2.52E+03 5.81 E+02 0. 1.75E+01 MN-54 0. 6.93E+03 0. 1.72E+03 2.45E+05 1.35E+04 0. 1.10E+03 FE-59 2.06E+03 4.86E+06 0. 0. 1.78E+05 3.29E+04 0. 1.85E+03 C0-57 0. 1.21 E+02 0. 0. 6.47E+04 5.50E+03 0. 1.18E+02 C0-58 0. 1.18E+02 0. 0. 8.79E+05 1.21 E+04 0. 1.68E+02 C0-60 0. 8.40E+02 0. 0. 5.57E+06 3.28E+04 0. 1.17E+03 Nl-63 7.56E+04 5.49E+03 0. 0. 3.12E+04 2.34E+03 0. 2.53E+03 ZN-65 5.67E+03 1.81E+04 0. 1.21E+04 1.53E+05 9.35E+03 0. 8.15E+03 RB-86 0. 2.37E+04 0. 0. 0. 2.91E+03 0. 1.03E+04 SR-89 4.31E+04 0. 0. 0. 2.31E+06 6.80E+04 0. 1.24E+03 SR-90 1.32E+07 0. 0. 0. 1.53E+07 1.39E+05 0. 8.06E+05 Y-91 5.98E+04 0. 0. 0. 2.63E+06 7.17E+04 0. 1.60E+03 ZR-95 1.08E+04 2.73E+03 0. 9.48E+03 1.81E+06 1.41 E+04 0. 1.95E+03 NB-95 1.28E+03 5.75E+02 0. 1.35E+03 4.77E+05 1.21 E+04 0. 3.37E+02 RU-103 1.69E+02 0. 0. 1.02E+03 5.66E+05 1.58E+04 0. 5.85E+01 RU-106 9.31 E+03 0. 0. 2.34E+04 1.50E+07 1.76E+05 0. 1.14E+03 AG-110M 1.89E+03 1.75E+03 0. 3.44E+03 8.12E+05 5.29E+04 0. 1.04E+03 CD-115M 0. 3.44E+04 0. 2.77E+04 2.46E+05 6.72E+04 0. 1.11E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q AND xiQ. 3B - 16 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY- INHALATION AGE GROUP - INFANT NUCLIDE ORGAN DOSE FACTORS (MREMNR PER UGI/CU.METER) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-123 3.11E+04 6.45E+02 6.45E+02 0. 3.61E+06 5.99E+04 0. 1.02E+03 SN-126 2.21E+05 5.85E+03 1.72E+03 0. 1.64E+06 2.23E+04 0. 8.40E+03 SB-124 5.46E+03 1.03E+02 1.32E+01 0. 4.34E+05 7.11E+04 0. 2.17E+03 SB-125 1.16E+04 1.25E+02 1.03E+01 0. 3.85E+05 1.76E+04 0. 2.32E+03 TE-125M 4.54E+02 1.95E+02 1.53E+02 2.17E+03 4.96E+05 1.36E+04 0. 6.16E+01 TE-127M 2.21 E+03 9.83E+02 5.75E+02 8.01E+03 1.68E+05 2.62E+04 0. 2.74E+02 TE-129M 1.32E+03 5.80E+02 5.08E+02 6.40E+03 1.83E+06 7.32E+04 0. 2.06E+02 1-130 8.02E+02 2.35E+03 3.05E+05 3.65E+03 0. 1.35E+03 0. 9.25E+02 1-131 3.63E+04 4.27E+04 1.41E+07 1.07E+04 0. 1.07E+03 0. 2.51E+04 1-132 2.03E+02 5.70E+02 7.67E+04 9.09E+02 0. 7.11E+01 0. 2.03E+02 1-133 1.34E+04 1.93E+04 4.66E+06 4.55E+03 0. 2.28E+03 0. 5.87E+03 1-134 1.13E+02 3.02E+02 4.02E+04 4.82E+02 0. 1.76E-01 0. 1.08E+02 1-135 4.70E+02 1.22E+03 1.64E+05 1.95E+03 0. 9.18E+02 0. 4.51E+02 CS-134 4.80E+05 8.25E+05 0. 5.04E+04 1.01E+05 1.37E+03 0. 7.32E+04 CS-136 6.85E+03 2.56E+04 0. 1.50E+04 2.10E+03 2.04E+03 0. 1.95E+04 CS-137 6.86E+05 7.31 E+05 0. 3.89E+04 9.45E+04 1.32E+03 0. 4.41E+04 BA-140 5.70E+03 4.27E+OO 0. 2.93E+OO 1.64E+06 3.88E+03 0. 2.95E+02 CE-141 2.52E+03 1.55E+03 0. 1.10E+03 5.24E+05 2.06E+04 0. 1.81E+02 CE-144 4.68E+05 1.82E+05 0. 1.48E+05 1.27E+07 1.61E+05 0. 2.49E+04 PR-143 1.64E+03 6.57E+02 0. 3.78E+02 4.91E+04 3.50E+04 0. 8.11E+01 ND-147 9.28E+02 1.07E+03 0. 6.28E+02 3.86E+04 3.02E+04 0. 6.38E+01 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x!Q AND xct/Q. 38 - 17 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-COW-MEAT (CONTAMINATED FORAGE) AGE GROUP -ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 4.13E+02 4.13E+02 4.13E+02 4.13E+02 4.13E+02 0. 4.13E+02 P-32 4.67E+09 2.93E+08 0. 0. 0. 5.25E+08 0. 1.81E+08 CR-51 0. 0. 4.23E+03 1.56E+03 9.38E+03 1.78E+06 0. 7.07E+03 MN-54 0. 9.18E+06 0. 2.73E+06 0. 2.81E+07 0. 1.75E+06 FE-59 2.67E+08 6.33E+08 0. 0. 1.76E+08 2.09E+09 0. 2.41E+08 C0-57 0. 5.64E+06 0. 0. 0. 1.43E+08 0. 9.38E+06 C0-58 0. 1.83E+07 0. 0. 0. 3.70E+08 0. 4.09E+07 C0-60 0. 7.55E+07 0. 0. 0. 1.41 E+09 0. 1.66E+08 Nl-63 1.89E+09 1.31E+08 0. 0. 0. 2.73E+07 0. 6.33E+07 ZN-65 3.56E+08 1.13E+09 0. 7.57E+08 0. 7.13E+08 0. 5.12E+08 RB-86 0. 4.89E+08 0. 0. 0. 9.64E+07 0. 2.28E+08 SR-89 3.03E+08 0. 0. 0. 0. 4.84E+07 0. 8.67E+06 SR-90 1.25E+10 0. 0. 0. 0. 1.45E+09 0. 3.05E+09 Y-91 1.14E+06 0. 0. 0. 0. 6.26E+08 0. 3.05E+04 ZR-95 3.78E+06 1.67E+06 0. 2.01E+06 0. 8.30E+09 0. 8.26E+05 NB-95 2.30E+06 1.20E+06 0. 1.27E+06 0. 7.75E+09 ...___, 0. 5.02E+05 RU-103 1.06E+08 0. 0. 4.06E+08 0. 1.24E+10 0. 4.59E+07 RU-106 2.80E+09 0. 0. 5.41E+09 0. 1.81E+11 0. 3.54E+08 AG-110M 6.71E+06 6.21E+06 0. 1.22E+07 0. 2.53E+09 0. 3.69E+06 CD-115M 0. 1.46E+06 0. 1.16E+06 0. 6.15E+07 0. 4.67E+04 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xiQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREMNR PER UC I/CU.METER) 38 -18 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-COW-MEAT (CONTAMINATED FORAGE) AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 1.86E+10 3.69E+08 1.08E+08 0. 6.46E+06 6.19E+09 0. 5.33E+08 SB-124 1.99E+07 3.75E+05 4.80E+04 0. 1.54E+07 5.62E+08 0. 7.85E+06 SB-125 6.65E+07 1.58E+07 1.29E+07 1.74E+08 2.49E+09 3.80E+08 0. 1.05E+07 TE-125M 3.59E+08 1.30E+08 1.08E+08 1.46E+09 0. 1.43E+09 0. 4.81E+07 TE-127M 1.13E+Q.9 3.93E+08 2.96E+08 4.56E+09 0. 5.11 E+09 0. 1.39E+08 TE-129M 1.14E+09 4.29E+08 3.95E+08 4.79E+09 0. 5.76E+09 0. 1.82E+08 1-130 2.38E-06 7.0SE-06 8.96E-04 1.10E-05 0. 6.04E-06 0. 2.77E-06 1-131 1.08E+07 1.55E+07 5.06E+09 2.65E+07 0. 4.07E+06 0. 8.85E+06 1-132 0. 0. 0. 0. 0. 0. 0. 0. 1-133 4.40E-01 7.63E-01
~~1.47E+02 1.33E+OO 0. 6.71E-01 0. 2.33E-01 1-134 0. 0. 0. 0. 0. 0. 0. 0.~~
1-135 8.60E-02 7.94E-02 0. 3.01E-02 9.04E-03 1.86E-03 0. 3.53E-02 CS-134 6.58E+08 1.57E+09 0. 5.08E+08 1.68E+08 2.74E+07 0. 1.28E+09 CS-136 1.18E+07 4.67E+07 0. 2.60E+07 3.56E+06 5.31E+06 0. 3.36E+07 CS-137 8.73E+08 1.19E+09 0. 4.06E+08 1.35E+08 2.30E+07 0. 7.82E+08 BA-140 2.88E+07 3.63E+04 0. 1.23E+04 2.07E+04 6.87E+07 0. 1.90E+06 CE-141 1.41 E+04 9.52E+03 0. 4.41E+03 0. 3.63E+07 0. 1.08E+03 CE-144 1.46E+06 6.10E+05 0. 3.62E+05 0.. 4.93E+08 0. 7.83E+04 PR-143 2.13E+04 8.57E+03 0. 4.94E+03 0. 9.34E+07 0. 1.06E+03 ND-147 1.72E+04 9.29E+03 0. 6.64E+03 0. 4.13E+07 0. 8.76E+02 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 ANb H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -19 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-COW-MEAT (CONTAMINATED FORAGE) AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 1.93E+02 1.93E+02 2.44E+02 1.93E+02 1.93E+02 0. 1.93E+02 P-32 2.76E+09 1.73E+08 0. 0. 0. 3.10E+08 0. 1.07E+08 CR-51 0. 0. 2.50E+02 9.22E+02 5.55E+03 1.05E+06 0. 4.18E+03 MN-54 0. 5.42E+06 0. 1.61 E+06 0. 1.66E+07 0. 1.04E+06 FE-59 1.58E+08 3.74E+08 0. 0. 1.04E+08 1.24E+09 0. 1.42E+OB C0-57 0. 3.33E+06 0. 0. 0. 8.45E+07 0. 5.54E+06 C0-58 0. 1.44E+07 0. 0. 0. 1.94E+08 0. 3.27E+07 C0-60 0. 5.73E+07 0. 0. 0. 6.87E+08 0. 1.31E+08 Nl-63 1.12E+09 7.74E+07 0. 0. 0. 1.61 E+07 0. 3.74E+07 ZN-65 2.11E+08 6.69E+08 0. 4.47E+08 0. 4.21E+08 0. 3.03E+08 RB-86 0. 2.89E+08 0. 0. 0. 5.69E+07 0. 1.35E+08 SR-89 2.66E+08 0. 0. 0. 0. 2.89E+07 0. 7.64E+06 SR-90 1.01E+10 0. 0. 0. 2.79E+08 1.02E+09 0. 2.49E+09 Y-91 9.34E+05 0. 0. 0. 0. 3.59E+08 0. 2.49E+04 ZR-95 2.67E+06 1.24E+06 0. 1.18E+06 0. 4.20E+09 0. 7.61E+05 NB-95 1.58E+05 9.51E+05 0. 7.48E+05 0. 3.88E+09 0. 5.37E+05 RU-103 8.05E+07 0. 0. 2.40E+08 0. 6.28E+09 0. 3.60E+07 RU-106 2.40E+09 0. 0. 3.20E+09 0. 1.09E+11 0. 3.02E+08 AG-110M 3.97E+06 3.67E+06 0. 7.21E+06 0. 1.50E+09 0. 2.18E+06 CD-115M 0. 8.64E+05 0. 6.85E+05 0. 3.63E+07 0. 2.76E+04 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -20 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-COW-MEAT (CONTAMINATED FORAGE) AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UGI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 1.10E+10 2.18E+08 6.38E+07 0. 3.82E+06 3.66E+09 0. 3.14E+08 SB-124 1.17E+07 2.21E+05 2.84E+04 0. 9.11 E+06 3.32E+08 0. 4.64E+06 SB-125 5.01 E+07 1.31E+07 1.02E+07 1.03E+08 1.47E+09 2.25E+08 0. 7.60E+06 TE-125M 3.03E+08 1.08E+08 8.55E+07 8.63E+08 0. 8.47E+08 0. 4.02E+07 TE-127M 6.60E+08 2.34E+08 1.77E+08 2.69E+09 0. 3.35E+09 0. 8.28E+07 TE-129M 9.78E+08 3.63E+08 3.13E+08 2.83E+09 0. 3.41E+09 0. 1.53E+08 1-130 1.41E-06 4.16E-06 5.30E-04 6.47E-06 0. 3.57E-06 0. 1.64E-06 1-131 8.54E+06 1.21E+07 3.48E+09 1.56E+07 0. 2.28E+06 0. 7.19E+06 1-132 0. 0. 0. 0. 0. 0. 0. 0. 1-133 3.69E-01 6.26E-01 1.14E+02 7.88E-01 0. 4.55E-01 0. 1.93E-01 1-134 0. 0. 0. 0. 0. 0. 0. 0. 1-135 5.0BE-02 4.69E-02 0. 1.78E-02 5.34E-03 1.10E-03 0. 2.0BE-02 CS-134 5.03E+08 1.21E+09 0. 3.00E+08 1.47E+08 1.40E+07 0. 5.66E+08 CS-136 6.99E+06 2.76E+07 0. 1.54E+07 2.11 E+06 3.14E+06 0. 1.99E+07 CS-137 6.92E+08 9.31 E+08 0. 2.40E+08 1.24E+08 1.24E+07 0. 3.27E+08 BA-140 2.37E+07 2.93E+04 0. 7.20E+04 1.95E+04 9.19E+06 0. 1.53E+06 CE-141 1.12E+04 7.51 E+03 0. 2.61E+03 0. 2.03E+07 0. 8.61E+02 CE-144 1.28E+06 5.23E+05 0. 2.14E+05 0. 3.00E+08 0. 6.76E+04 PR-143 1.26E+04 5.07E+03 0. 2.92E+03 0. 5.52E+07 0. 6.26E+02 ND-147 1.01E+04 5.49E+03 0. 3.92E+03 0. 2.44E+07 0. 5.18E+02 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -21 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-COW-MEAT (CONTAMINATED FORAGE) AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 2.33E+02 2.33E+02 1.54E+02 2.33E+02 2.33E+02 0. 2.33E+02 P-32 1.74E+09 1.09E+08 0. 0. 0. 1.96E+08 0. 6.73E+07 CR-51 0. 0. 1.58E+03 5.82E+02 3.50E+03 6.63E+05 0. 2.64E+03 MN-54 0. 3.42E+06 0. 1.02E+06 0. 1.05E+07 0. 6.54E+05 FE-59 9.95E+07 2.37E+08 0. 0. 6.55E+07 7.79E+08 0. 8.93E+07 C0-57 0. 2.10E+06 0. 0. 0. 5.33E+07 0. 3.50E+06 C0-58 0. 1.69E+07 0. 0. 0. 1.00E+OB 0. 5.10E+07 C0-60 0. 6.77E+07 0. 0. 0. 3.75E+08 0. 2.03E+08 Nl-63 7.04E+08 4.88E+07 0. 0. 0. 1.02E+07 0. 2.36E+07 ZN-65 1.33E+08 4.22E+08 0. 2.82E+08 0. 2.66E+08 0. 1.91E+08 RB-86 0. 1.82E+08 0. 0. 0. 3.59E+07 0. 8.50E+07 SR-89 5.04E+08 0. 0. 0. 0. 1.88E+07 0. 1.44E+07 SR-90 1.05E+10 0. 0. 0. 0. 7.02E+08 0. 2.67E+09 Y-91 1.76E+06 0. 0. 0. 0. 2.33E+08 0. 4.69E+04 ZR-95 4.62E+06 1.51E+06 0. 7.47E+05 0. 2.22E+09 0. 1.20E+06 NB-95 2.68E+06 1.15E+06 0. 4.72E+05 0. 1.98E+09 0. 8.41E+05 RU-103 1.54E+08 0. 0. 1.51E+08 0. 3.81 E+09 0. 5.87E+07 RU-106 4.51E+09 0. 0. 2.02E+09 0. 7.01E+10 0. 5.61E+08 AG-110M 2.50E+06 2.31E+06 0. 4.55E+06 0. 9.44E+08 0. 1.38E+06 CD-115M 0. 5.45E+05 0. 4.32E+05 0. 2.29E+07 0. 1.74E+04 NOTE - T BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 38 -22 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY -AIR-GRASS-COW-MEAT (CONTAMINATED FORAGE) AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 6.92E+09 1.37E+08 4.02E+07 0. 2.41E+06 2.31E+09 0. 1.98E+08 SB-124 7.40E+06 1.40E+05 1.79E+04 0. 5.74E+06 2.10E+08 0. 2.93E+06 SB-125 7.66E+07 1.84E+07 1.90E+07 6.47E+07 9.26E+08 1.44E+08 0. 1.08E+07 TE-125M 5.69E+08 1.54E+08 1.60E+08 5.44E+08 0. 5.49E+08 0. 7.59E+07 TE-127M 4.40E+08 1.51E+08 1.24E+08 1.70E+09 0. 2.54E+09 0. 5.61E+07 TE-129M 1.84E+09 5.12E+08 5.87E+08 1.78E+09 0. 2.21E+09 0. 2.84E+08 1-130 8.87E-07 2.63E-06 3.34E-04 4.0BE-06 0. 2.25E-06 0. 1.03E-06 1-131 1.58E+07 1.62E+07 5.25E+09 9.86E+06 0. 1.38E+06 0. 1.22E+07 1-132 0. 0. 0. 0. 0. 0. 0. 0. 1-133 6.86E-01 8.47E-01 2.04E+02 4.97E-01 0. 3.43E-01 0. 3.33E-01 1-134 0. ,;
~~0. 0. 0. 0. 0. 0. 0.~~
1-135 3.21E-02 2.96E-02 0. 1.12E-02 3.37E-03 6.92E-04 0. 1.32E-02 CS-134 8.83E+08 1.49E+09 0. 1.89E+08 1.65E+08 8.04E+06 0. 3.16E+08 CS-136 4.41E+06 1.74E+07 0. 9.69E+06 1.33E+06 1.98E+06 0. 1.25E+07 CS-137 1.27E+09 1.23E+09 0. 1.51 E+08 1.44E+08 7.50E+06 0. 1.84E+08 BA-140 4.37E+07 3.84E+04 0. 4.59E+03 2.29E+04 6.03E+06 0. 2.57E+06 CE-141 2.10E+04 1.05E+04 0. 1.65E+03 0. 1.32E+07 0. 1.57E+03 CE-144 2.38E+06 7.46E+05 0. 1.35E+05 0. 1.94E+08 0. 1.27E+05 PR-143 7.96E+03 3.20E+03 0. 1.84E+03 0. 3.48E+07 0. 3.95E+02 ND-147 6.40E+03 3.47E+03 0. 2.48E+03 0. 1.53E+07 0. 3.27E+02 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xr/Q, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -23 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY -AIR-GRASS-COWS-MILK (CONTAMINATED FORAGE) AGE GROUP -ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 9.73E+02 9.73E+02 9.73E+02 9.73E+02 9.73E+02 0. 9.73E+02 P-32 1.71E+10 1.07E+09 0. 0. 0. 1.92E+09 0. 6.62E+08 CR-51 0. 0. 1.71E+04 6.32E+03 3.80E+04 7.20E+06 0. 2.86E+04 MN-54 0. 8.41E+06 0. 2.50E+06 0. 2.58E+07 0. 1.61E+06 FE-59 2.98E+07 7.06E+07 0. 0. 1.96E+o7* 2.33E+08 0. 2.69E+07 C0-57 0. 1.28E+06 0. 0. 0. 3.25E+07 0. 2.13E+06 C0-58 0. 4.72E+06 0. 0. 0. 9.56E+07 0. 1.06E+07 C0-60 0. 1.65E+07 0. 0. 0. 3.08E+08 0. 3.62E+07 Nl-63 6.73E+09 4.67E+08 0. 0. 0. 9.73E+07 0. 2.26E+08 ZN-65 1.37E+09 4.36E+09 0. 2.92E+09 0. 2.75E+09 0. 1.98E+09 RB-86 0. 2.60E+09 0. 0. 0. 5.12E+08 0. 1.21E+09 SR-89 1.46E+09 0. 0. 0. 0. 2.33E+08 0. 4.17E+07 SR-90 4.70E+10 0. 0. 0. 0. 6.37E+08 0. 1.15E+10 Y-91 . 8.60E+03 0. 0. 0. 0. 4.73E+06 0. 2.31 E+02 ZR-95 3.18E+04 1.75E+04 0. 1.75E+04 0. 1.05E+08 0. 6.95E+03 NB-95 8.26E+04 4.59E+04 0. 4.55E+04 0. 2.79E+08 0. . 1.80E+04 RU-103 1.02E+03 0. 0. 3.91E+03 0. 1.19E+05 0. 4.41E+02 RU-106 2.04E+04 0. 0. 3.95E+04 0. 1.32E+06 0. 2.58E+03 AG-110M 5.84E+07 5.40E+07 0.
1.96E+08 0. 2.20E+10 0. 3.21 E+07 CD-115M 0. 1.25E+06 0. 9.89E+05 0. 5.24E+07 0. 3.98E+04 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q.
NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 38-24 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY -AIR-GRASS-COWS-MILK (CONTAMINATED FORAGE) AGE GROUP -ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 1.65E+09 3.27E+07 9.56E+06 0. 4.67E+06 1.09E+09 0. 4.94E+07 SB-124 2.58E+07 4.87E+05 6.24E+04 0. 2.00E+07 7.31E+08 0. 1.02E+07 SB-125 2.84E+07 6.06E+05 2.99E+05 3.72E+06 2.66E+09 2.29E+08 0. 5.23E+06 TE-125M 1.63E+07 5.91E+06 4.91E+06 6.63E+07 0. 6.50E+07 0. 2.18E+06 TE-127M 4.63E+07 1.63E+07 1.21E+07 1.88E+08 0. 2.11 E+08 0. 5.72E+06 TE-129M 8.06E+07 2.27E+07 2.09E+07 2.53E+08 0. 3.04E+08 0. 9.61E+06 1-130 4.27E+05 1.26E+08 1.61E+08 1.96E+06 0. 1.08E+06 0. 4.97E+05 1-131 2.96E+08 4.25E+08 1.39E+11 7.27E+08 0. 1.12E+08 0. 2.43E+08 1-132 1.67E-01 4.47E-01 5.88E+01 7.12E-01 0. 8.39E-02 0. 1.59E-01 1-133 4.00E+06 6.94E+06 1.33E+09 1.21E+07 0. 6.10E+06 0. 2.12E+06 1-134 0. 0. 9.98E-10 0. 0. 0. 0. 0. 1-135 1.40E+04 3.70E+04 4.84E+06 5.88E+04 7.58E-02 4.14E+04 0. 1.36E+04 CS-134 5.66E+09 1.35E+10 0. 4.36E+09 1.45E+09 2.36E+08 0. 1.10E+10 CS-136 2.61E+0.8 1.03E+09 0. 5.74E+08 7.87E+07 1.17E+08 0. 7.43E+08 CS-137 7.39E+09 1.01E+10 0. 3.44E+09 1.14E+09 1.95E+08 0. 6.62E+09 BA-140 2.69E+07 3.38E+04 0. 1.15E+04 1.93E+04 5.70E+07 0. 1.78E+06 CE-141 2.91E+04 1.97E+04 0. 9.13E+03 0. 7.52E+07 0. 2.23E+03 CE-144 2.15E+06 8.97E+05 0. 5.32E+05 0. 7.26E+08 0. 1.15E+05 PR-143 1.59E+02 6.39E+01 0. 3.68E+01 0. 6.96E+05 0. 7.89E+OO ND-147 1.16E+02 1.12E+02 0. 6.77E+01 0. 5.28E+05 0. 7.34E+OO BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -25 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-COWS-MILK (CONTAMINATED FORAGE) AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 9.93E+02 9.93E+02 1.26E+03 9.93E+02 9.93E+02 0. 9.93E+02 P-32 2.21E+10 1.38E+09 0. 0. 0. 2.48E+09 0. 8.54E+08 CR-51 0. 0. 2.21E+04 8.15E+03 4.90E+04 9.29E+06 0. 3.69E+04 MN-54 0. 1.09E+07 0. 3.32E+06 0. 3.33E+07 0. 2.07E+06 FE-59 3.84E+07 9.12E+07 0. 0. 2.53E+07 3.01 E+08 0. 3.47E+07 C0-57 0. 1.65E+06 0. 0. 0. 4.19E+07 0. 2.75E+06 C0-58 0. 8.10E+06 0. 0. 0. 1.10E+08 0. 1.85E+07 C0-60 0. 2.73E+07 0. 0. 0. 3.27E+08 0. 6.23E+07 Nl-63 8.68E+09 6.02E+08 0. 0. 0. 1.26E+08 0. 2.91E+08 ZN-65 1.77E+09 5.63E+09 0. 3.77E+09 0. 3.55E+09 0. 2.55E+09 RB-86 0. 3.35E+09 0. 0. 0. 6.61E+08 0. 1.56E+09 SR-89 2.80E+09 0. 0. 0. 0. 3.03E+08 0. 8.03E+07 SR-90 8.29E+10 0. 0. 0. 3.38E+06 1.76E+09 0. 2.05E+10 Y-91 1.54E+04 0. 0. 0. 0. 5.93E+06 0. 4.12E+02 ZR-95 4.78E+04 2.84E+04 0. 2.25E+04 0. 1.15E+08 0. 1.60E+04 NB-95 1.24E+05 7.46E+04 0. 5.87E+04 0. 3.05E+08 0. 4.21E+04 RU-103 1.69E+03 0. 0. 5.04E+03 0. 1.32E+05 0. 7.56E+02 RU-106 3.83E+04 0. 0. 5.09E+04 0. 1.73E+06 0. 4.81E+03 AG-110M 7.53E+07 6.97E+07 0. 1.37E+08 0. 2.84E+10 0. 4.14E+07 CD-115M 0. 1.61E+06 0. 1.28E+06 0. 6.77E+07 0. 5.14E+04 BASED ON 1 µCi/SEC RELEASE RATE OF EACH IS~TOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 3B-26 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-COWS-MILK (CONTAMINATED FORAGE) AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 2.12E+09 4.21E+07 1.24E+07 0. 6.03E+06 1.41 E+09 0. 6.37E+07 SB-124 3.33E+07 6.29E+05 8.05E+04 0. 2.59E+07 9.43E+08 0. 1.32E+07 SB-125 3.45E+07 9.58E+05 5.05E+05 4.80E+06 3.43E+09 2.95E+08 0. 6.82E+06 TE-125M 3.00E+07 1.08E+07 8.47E+06 8.55E+07 0. 8.39E+07 0. 3.98E+06 TE-127M 6.02E+07 2.11E+07 1.59E+07 2.43E+08 0. 3.02E+08 0. 7.45E+06 TE-129M 1.13E+08 4.18E+07 3.61E+07 3.27E+08 0. 3.93E+08 0. 1.78E+07 1-130 5.51 E+05 1.63E+06 2.07E+08 2.53E+06 0. 1.40E+06 0. 6.41E+05 1-131 5.12E+08 7.24E+08 2.09E+11 9.38E+08 0. 1.37E+08 0. 4.31E+08 1-132 2.16E-01 5.76E-01 7.59E+01 9.19E-01 0. 1.0BE-01 0. 2.05E-01 1-133 7.33E+06 1.24E+07 2.26E+09 1.56E+07 0. 9.02E+06 0. 3.83E+06 1-134 0. 0. 1.29E-09 0. 0. 0. 0. 0. 1-135 1.81E+04 4.77E+04 6.24E+06 7.58E+04 9.79E-02 5.34E+04 0. 1.75E+04 CS-134 9.44E+09 2.28E+10 0. 5.63E+09 2.76E+09 2.63E+08 0. 1.06E+10 CS-136 3.37E+08 1.33E+09 0. 7.41E+08 1.02E+08 1.51E+08 0.. 9.58E+08 CS-137 1.28E+10 1.72E+10 0. 4.43E+09 2.28E+09 2.29E+08 0. 6.04E+09 BA-140 4.84E+07 5.95E+04 0. 1.48E+04 3.98E+04 9.16E+06 0. 3.11E+06 CE-141 5.05E+04 3.39E+04 0. 1.18E+04 0. 9.18E+07 0. 3.89E+03 CE-144 4.10E+06 1.68E+06 0. 6.87E+05 0. 9.65E+08 0. 2.17E+05 PR-143 2.05E+02 8.25E+01 0. 4.75E+01 0. 8.98E+05 0. 1.02E+01 ND-147 1.49E+02 1.44E+02 0. 8.74E+01 0. 6.82E+05 0. 9.48E+OO BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xc/Q, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 3B-27 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-COWS-MILK (CONTAMINATED FORAGE) AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 1.57E+03 1.57E+03 1.04E+03 1.57E+03 1.57E+03 0. 1.57E+03 P-32 1.82E+10 1.14E+09 0. 0. 0. 2.05E+09 0. 7.05E+08 CR-51 0.. 0. 1.82E+04 6.72E+03 4.04E+04 7.66E+06 0. 3.05E+04 MN-54 0. 8.96E+06 0. 2.67E+06 0. 2.74E+07 0. 1.71E+06 FE-59 3.17E+07 7.52E+07 0. 0. 2.09E+07 2.48E+08 0. 2.86E+07 C0-57 0. 1.36E+06 0. 0. 0. 3.46E+07 0. 2.27E+06 C0-58 0. 1.25E+07 0. 0. 0. 7.41 E+07 0. 3.76E+07 C0-60 0. 4.22E+07 0. 0. 0. 2.33E+08 0. 1.27E+08 Nl-63 7.16E+09 4.97E+08 0. 0. 0. 1.04E+08 0. 2.40E+08 ZN-65 1.46E+09 4.65E+09 0. 3.11E+09 0. 2.93E+09 0. 2.10E+09 RB-86 0. 2.77E+09 0. 0. 0. 5.45E+08 0. 1.29E+09 SR-89 6.92E+09 0. 0. 0. 0. 2.58E+08 0. 1.98E+08 SR-90 1.13E+11 0. 0. 0. 0. 1.52E+09 0. 2.87E+10 Y-91 3.80E+04 0. 0. 0. 0. 5.05E+06 0. 1.01E+03 ZR-95 1.06E+05 4.47E+04 0. 1.86E+04 0. 7.68E+07 0. 3.29E+04 NB-95 2.75E+05 1.18E+05 0. 4.84E+04 0. 2.03E+08 0. 8.63E+04 RU-103 3.99E+03 0. 0. 4.16E+03 0. 1.05E+05 0. 1.61E+03 RU-106 9.39E+04 0. 0. 4.20E+04 0. 1.46E+06 0. 1.17E+04 AG-110M 6.21E+07 5.75E+07 0. 1.13E+08 0. 2.35E+10 0. 3.42E+07 CD-115M 0. 1.33E+06 0. 1.05E+b6 0. 5.58E+07 0. 4.24E+04 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38-28 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-COWS-MILK (CONTAMINATED FORAGE) AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UGI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 1.75E+09 3.48E+07 1.01E+07 0. 4.97E+06 1.16E+09 0. 5.25E+07 SB-124 2.75E+07 5.19E+05 6.64E+04 0. 2.13E+07 7.78E+08 0. 1.09E+07 SB-125 3.13E+07 1.41 E+05 1.18E+06 3.96E+06 2.83E+09 2.43E+08 0. 5.99E+06 TE-125M 7.38E+07 2.00E+07 2.07E+07 7.05E+07 0. 7.12E+07 0. 9.84E+06 TE-127M 5.18E+07 1.78E+07 1.46E+07 2.00E+08 0. 2.99E+08 0. 6.60E+06 TE-129M 2.77E+08 7.73E+07 8.85E+07 2.70E+08 0. 3.33E+08 0. 4.28E+07 1-130 4.54E+05 1.35E+06 1.71E+08 2.09E+06 0. 1.15E+06 0. 5.29E+05 1-131 1.24E+09 1.27E+09 4.12E+11 7.74E+08 0. 1.09E+08 0. 9.56E+08 1-132 1.18E-01 4.76E-01 6.26E+01 7.58E-01 0. 8.93E-02 0. 1.69E-01 1-133 1.78E+07 2.20E+07 5.30E+09 1.29E+07 0. 8.90E+06 0. 8.63E+06 1-134 0. 0. 1.06E-09 0. 0. 0. 0. 0. 1-135 1.49E+04 3.94E+04 5.15E+06 6.26E+04 8.07E-02 4.41E+04 0. 1.44E+04 CS-134 2.17E+10 3.65E+10 0. 4.65E+09 4.06E+09 1.97E+08 0. 7.76E+09 CS-136 2.78E+08 1.10E+09 0. 6.11E+08 8.37E+07 1.25E+08 0. 7.90E+08 CS-137 3.08E+10 2.98E+10 0. 3.66E+09 3.49E+09 1.81E+08 0. 4.44E+09 BA-140 1.17E+08 1.02E+05 0. 1.22E+04 6.09E+04 7.75E+06 0. 6.84E+06 CE-141 1.24E+05 6.22E+04 0. 9.72E+03 0. 7.80E+07 0. 9.26E+03 CE-144 1.00E+07 3.14E+06 0. 5.67E+05 0. 8.15E+08 0. 5.34E+05 PR-143 1.69E+02 6.80E+01 0. 3.92E+01 0. 7.41 E+05 0. 8.40E+OO ND-147 1.23E+02 1.19E+02 0. 7.21 E+01 0. 5.63E+05 0. 7.81E+OO BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -29 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-COWS-MILK (CONTAMINATED FORAGE) AGE GROUP - INFANT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 2.37E+03 2.37E+03 1.04E+03 2.37E+03 2.37E+03 0. 2.37E+03 P-32 1.82E+10 1.14E+09 0. 0. 0. 2.05E+09 0. 7.05E+08 CR-51 0. 0. 1.82E+04 6.72E+03 4.04E+04 7.66E+06 0. 3.05E+04 MN-54 0. 8.96E+06 0. 2.67E+06 0. 2.74E+07 0. 1.71E+06 FE-59 3.17E+07 7.52E+07 0. 0. 2.09E+07 2.48E+08 0. 2.86E+07 C0-57 0. 1.36E+06 0. 0. 0. 3.46E+07 0. 2.27E+06 C0-58 0. 2.55E+07 0. 0. 0. 6.60E+07 0. 6.24E+07 C0-60 0. 8.73E+07 0. 0. 0. 2.16E+08 0. 2.09E+08 Nl-63 7.16Ef09 4.97E+08 0. 0. 0. 1.04E+08 0. 2.40E+08 ZN-65 1.46E+09 4.65E+09 0. 3.11E+09 0. 2.93E+09 0. 2.10E+09 RB-86 0. 2.77E+09 0. 0. 0. 5.45E+08 0. 1.29E+09 SR-89 1.47E+10 0. 0. 0. 0. 2.75E+08 0. 4.22E+08 SR-90 1.65E+11 0. 0. 0. O.* 1.61 E+09 0. 4.21E+10 Y-91 8.12E+04 0. 0. 0. 0. 5.37E+06 0. 2.16E+03 ZR-95 2.12E+05 9.41E+04 0. 1.86E+04 0. 7.47E+07 0. 5.56E+04 NB-95 5.49E+05 2.47E+05 0. 4.84E+04 0. 1.98E+08 0. 1.45E+05 RU-103 8.30E+03 0. 0. 4.16E+03 0. 1.04E+05 0. 2.86E+03 RU-106 2.01E+05 0. 0. 4.20E+04 0. 1.56E+06 0. 2.46E+04 AG-110M 6.21E+07 5.75E+07 0. 1.13E+08 0. 2.35E+10 0. 3.42E+07 CD-115M 0. 1.33E+06 0. 1.05E+06 0. 5.58E+07 0. 4.24E+04 BASED ON 1 µCl/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38-30 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY -AIR-GRASS-COWS-MILK (CONTAMINATED FORAGE) AGE GROUP - INFANT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 1.75E+09 3.48E+07 1.01E+07 0. 4.97E+06 1.16E+09 0. 5.25E+07 SB-124 2.75E+07 5.19E+05 6.64E+04 0. 2.13E+07 7.78E+08 0. 1.09E+07 SB-125 3.59E+07 3.17E+06 2.93E+06 3.96E+06 2.83E+09 2.43E+08 0. 6.62E+06 TE-125M 1.57E+08 5.30E+07 5.18E+07 7.05E+07 0. 7.57E+07 0. 2.10E+07 TE-127M 5.54E+07 1.93E+07 1.79E+07 2.00E+OB 0.. 3.24E+08 0. 7.38E+06 TE-129M 5.87E+08 2.02E+08 2.21E+08 2.70E+08. 0. 3.54E+08 0. 8.95E+07 1-130 4.54E+05 1.35E+06 1.71E+08 2.09E+06 0. 1.15E+06 0. 5.29E+05 1-131 2.59E+09 3.09E+09 9.94E+11 7.74E+08 0. 1.16E+08 0. 1.81E+09 1-132 1.78E-01 4.76E-01 6.26E+01 7.58E-01 0. 8.93E-02 0. 1.69E-01 1-133 3.75E+07 5.48E+07 1.30E+10 1.29E+07 0. 9.74E+06 0. 1.66E+07 1-134 0. 0. 1.06E-09 0. 0. 0. 0. 0. 1-135 1.49E+04 3.94E+04 5.15E+06 6.26E+04 8.0?E-02 4.41E+04 0. 1.44E+04 CS-134 4.48E+10 7.97E+10 0. 4.65E+09 9.12E+09 1.90E+08 0. 6.75E+09 CS-136 2.78E+08 1.10E+09 0. 6.11 E+OB 8.37E+07 1.25E+08 0. 7.90E+08 CS-137 6.44E+10 7.21E+10 0. 3.66E+09 8.69E+09 1.86E+08 0. 4.14E+09 BA-140 2.45E+08 2.47E+05 0. 1.22E+04 1.51E+05 8.13E+06 0. 1.27E+07 CE-141 2.65E+05 1.62E+05 0. 9.72E+03 0. 7.87E+07 0. 1.90E+04 CE-144 2.10E+07 8.29E+06 0. 5.67E+05 0. 8.66E+08 0. 1.13E+06 PR-143 1.69E+02 6.80E+01 0. 3.92E+01 0. 7.41 E+05 0. 8.40E+OO ND-147 1.23E+02 1.19E+02 0. 7.21 E+01 0. 5.63E+05 0. 7.81E+OO BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xr/Q, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 - 31 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY -AIR-GRASS-GOATS-MILK (CONTAMINATED FORAGE) AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 1.99E+03 1.99E+03 1.99E+03 1.99E+03 1.99E+03 0. 1.99E+03 P-32 2.05E+10 1.29E+09 0. 0. 0. 2.31 E+09 0. 7.94E+08 CR-51 0. 0. 2.05E+08 7.58E+02 4.56E+03 8.64E+05 0. 3.43E+03 MN-54 0. 1.01E+06 0. 3.00E+05 0. 3.09E+06 0. 1.93E+05 FE-59 3.87E+05 9.18E+05 0. 0. 2.55E+05 3.03E+06 0. 3.50E+05 C0-57 0. 1.54E+05 0. 0. 0. 3.90E+06 0. 2.55E+05 C0-58 0. 5.67E+05 0. 0. 0. 1.15E+07 0. 1.27E+06 C0-60 0. 1.98E+06 0. 0. 0. 3.70E+07 0. 4.34E+06 Nl-63 8.07E+08 5.60E+07 0. 0. 0. 1.17E+07 0. 2.71E+07 ZN-65 1.65E+08 5.24E+08 0. 3.50E+08 0. 3.30E+08 0. 2.37E+08 RB-86 0. 3.12E+08 0. 0. 0. 6.15E+07 0. 1.45E+08 SR-89 3.06E+09 0. 0. 0. 0. 4.89E+08 0. 8.76E+07 SR-90 9.87E+10 0. 0. 0. 0. 1.32E+09 0. 2.41 E+10 Y-91 1.03E+03 0. 0. 0. 0. 5.68E+05 0. 2.77E+01 ZR-95 3.82E+03 2.10E+03 0. 2.10E+03 0. 1.26E+07 0. 8.34E+02 NB-95 9.92E+03 5.51E+03 0. 5.46E+03 0. 3.34E+07 0. 2.173+03 RU-103 1.23E+02 0. 0. 4.69E+02 0. 1.43E+04 0. 5.30E+01 RU-106 2.45E+03 0. 0. 4.73E+03 0. 1.58E+05 0. 3.10E+02 AG-110M 7.00E+06 6.48E+06 0. 1.27E+07 0. 2.64E+09 0. 3.85E+06 CD-115M 0. 1.50E+05 0. 1.19E+05 0. 6.29E+06 0. 4.78E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38-32 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY -AIR-GRASS-GOATS-MILK (CONTAMINATED FORAGE) AGE GROUP -ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 1.97E+08 3.92E+06 1.15E+06 0. 5.61E+05 1.31 E+08 0. 5.92E+06 SB-124 3.10E+06 5.85E+04 7.49E+03 0. 2.40E+06 8.77E+07 0. 1.22E+06 SB-125 3.16E+06 7.28E+04 3.58E+04 4.47E+05 3.19E+08 2.74E+07 0. 6.29E+05 TE-125M 1.96E+06 7.10E+05 . 5.89E+05 7.95E+06 0. 7.81E+06 0. 2.62E+05 TE-127M 5.57E+06 1.94E+06 1.47E+06 2.26E+07 0. 2.52E+07 0. 6.86E+05 TE-129M 7.27E+06 2.72E+06 2.51E+06 3.04E+07 0. 3.65E+07 0. 1.15E+06 1-130 5.12E+05 1.52E+06 1.93E+08 2.36E+06 0. 1.30E+06 0. 5.96E+05 1-131 3.56E+08 5.10E+08 1.67E+11 8.72E+08 0. 1.34E+08 0. 2.92E+08 1-132 2.00E-01 5.36E-01 7.06E+01 8.55E-01 0. 1.01 E-01 0. 1.91E-01 1-133 4.80E+06 8.32E+06 1.60E+09 1.45E+07 0. 7.32E+06 0. 2.54E+06 1-134 0. 0. 1.20E-09 0. 0. 0. 0. 0. 1-135 1.68E+04 4.44E+04 5.80E+06 7.05E+04 2.28E-01 4.97E+04 0. 1.63E+04 CS-134 1.78E+10 4.04E+10 0. 1.31E+10 4.34E+09 7.06E+08 0. 3.30E+10 CS-136 7.84E+08 3.09E+09 0. 1.72E+09 2.36E+08 3.52E+08 0. 2.23E+09 CS-137 2.22E+10 3.03E+10 0. 1.03E+10 3.42E+09 5.83E+08 0. 1.99E+10 BA-140 3.23E+06 4.05E+03 0. 1.38E+03 2.32E+03 6.84E+06 0. 2.13E+05 CE-141 3.49E+03 2.36E+03 0. 1.10E+03 0. 9.02E+06 0. 2.68E+02 CE-144 2.58E+05 1.08E+05 0. 6.39E+04 0. 8.71E+07 0. 1.38E+04 PR-143
1.91 E+01 7.67E+OO 0. 4.42E+OO 0. 8.35E+04 0. 9.47E-01 ND-147 1.39E+01 1.34E+01 0. 8.13E+OO 0. 6.35E+04 0. 8.81 E-01 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q.
NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 3B-33 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY -AIR.-GRASS-GOATS-MILK (CONTAMINATED FORAGE) AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 2.03E+03 2.03E+03 2.56E+03 2.03E+03 2.03E+03 0. 2.03E+03 P-32 2.65E+10 1.66E+09 0. 0. 0. 2.98E+09 0. 1.03E+09 CR-51 0. 0. 2.65E+03 9.78E+02 5.88E+03 1.11 E+06 0. 4.43E+03 MN-54 0. 1.30E+06 0. 3.88E+05 0. 3.99E+06 0. 2.49E+05 FE-59 4.99E+05 1.19E+06 0. 0. 3.29E+05 3.91E+06 0. 4.51E+05 C0-57 0. 1.98E+05 0. 0. 0. 5.03E+06 0. 3.30E+05 C0-58 0. 9.72E+05 0. 0. 0. 1.31E+07 0. 2.22E+06 C0-60 0. 3.28E+06 0. 0. 0. 3.93E+07 0. 7.48E+06 Nl-63 1.04E+09 7.23E+07 0. 0. 0. 1.51E+07 0. 3.49E+07 ZN-65 2.13E+08 6.7BE+08 0. 4.52E+08 0. 4.26E+08 0. 3.06E+08 RB-86 0. 4.02E+08 0. 0. 0. 7.93E+07 0. 1.88E+08 SR-89 5.87E+09 0. 0. 0. 0. 6.37E+08 0. 1.69E+08 SR-90 1.74E+11 0. 0. 0. 4.05E+05 3.68E+09 0. 4.30E+10 Y-91 1.85E+03 0. 0. 0. 0. 7.11 E+05 0. 4.94E+01 ZR-95 5.74E+03 3.41E+03 0. 2.70E+03 0. 1.38E+07 0. 1.93E+03 NB-95 1.49E+04 8.96E+03 0. 7.05E+03 0. 3.66E+07 0. 5.05E+03 RU-103 2.03E+02 0. 0. 6.05E+02 0. 1.58E+04 0. 9.08E+01 RU-106 4.59E+03 0. 0. 6.11 E+03 0. 2.08E+05 0. 5.78E+02 AG-110M 9.04E+06 8.36E+06 0. 1.64E+07 0. 3.41E+09 0. 4.97E+06 CD-115M 0. 1.93E+05 0. 1.53E+05 0. 8.12E+06 0. 6.17E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -34 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-GOATS-MILK (CONTAMINATED FORAGE) AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 2.54E+08 5.05E+06 1.48E+06 0. 7.23E+05 1.69E+08 0. 7.64E+06 SB-124 4.00E+06 7.54E+04 9.66E+03 0. 3.10E+06 1.13E+08 0. 1.58E+06 SB-125 4.14E+06 1.15E+05 6.06E+04 5.77E+05 4.12E+08 3.54E+07 0. 8.19E+05 TE-125M 3.61E+06 1.29E+06 1.02E+06 1.03E+07 0. 1.01 E+07 0. 4.78E+05 TE-127M 7.23E+06 2.52E+06 1.91E+06 2.92E+07 0. 3.63E+07 0. 8.94E+05 TE-129M 1.35E+07 5.02E+06 4.34E+06 3.92E+07 0. 4.72E+07 0. 2.13E+06 1-130 6.61E+05 1.96E+06 2.49E+08 3.04E+06 0. 1.68E+06 0. 7.69E+05 1-131 6.15E+08 8.68E+08 2.50E+11 1.13E+09 0. 1.64E+08 0. 5.17E+08 1-132 2.59E-01 6.92E-01 9.11 E+01 1.10E+OO 0. 1.30E-01 0. 2.46E-01 1-133 8.79E+06 1.49E+07 2.71E+09 1.88E+07 0. 1.08E+07 0. 4.59E+06 1-134 0. 0. 1.55E-09 0. 0. 0. 0. 0. 1-135 2.17E+04 5.73E+04 7.49E+06 9.10E+04 2.94E-01 6.41E+04 0. 2.10E+04 CS-134 2.88E+fo 6.83E+10 0. 1.69E+10 8.27E+09 7.88E+08 0. 3.19E+10 CS-136 1.01E+09 3.99E+09 0. 2.22E+09 3.05E+08 4.54E+08 0. 2.87E+09 CS-137 3.84E+10 5.16E+10 0. 1.33E+10 6.85E+09 6.88E+08 0. 1.81E+10 BA-140 5.81E+06 7.14E+03 0. 1.78E+03 4.78E+03 1.10E+06 0. 3.73E+05 CE-141 6.06E+03 4.07E+03 0. 1.41 E+03 0. 1.10E+07 0. 4.66E+02 CE-144 4.92E+05 2.02E+05 0. 8.24E+04 0. 1.16E+08 0. 2.61E+04 PR-143 2.46E+01 9.90E+OO 0. 5.70E+OO 0. 1.08E+05 0. 1.22E+OO ND-147 1.79E+01 1.73E+01 0. 1.05E+01 0. 8.19E+04 0. 1.14E+OO BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE -THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B-35 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY -AIR-GRASS-GOATS-MILK (CONTAMINATED FORAGE) AGE GROUP - CHILD NUCLIDE .. ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 3.20E+03 3.20E+03 2.11 E+03 3.20E+03 3.20E+03 0. 3.20E+03 P-32 2.19E+10 1.37E+09 0. 0. 0. 2.46E+09 0. 8.46E+08 CR-51 0. 0. 2.19E+03 8.07E+02 4.85E+03 9.19E+05 0. 3.66E+03 MN-54 0. 1.08E+06 0. 3.20E+05 0. 3.29E+06 0. 2.0SE+OS FE-59 4.12E+05 9.78E+05 0. 0. 2.72E+05 3.23E+06 0. 3.72E+05 C0-57 0. 1.64E+05 0. 0. 0. 4.15E+06 0. 2.72E+05 C0-58 0. 1.SOE+OS 0. 0. 0. 8.90E+06 0. 4.51E+06 C0-60 0. 5.06E+06 0. 0. 0. 2.80E+07 0. 1.52E+07 Nl-63 8.60E+08 5.96E+07 0. 0. 0. 1.24E+07 0. 2.88E+07 ZN-65 1.76E+08 5.57E+08 0. 3.73E+08 0. 3.51 E+08 0. 2.52E+08 RB-86 0. 3.32E+08 0. 0. 0. 6.54E+07 0. 1.55E+08 SR-89 1.45E+10 0. 0. 0. 0. 5.43E+08 0. 4.16E+08 SR-90 2.37E+11 0. 0. 0. 0. 3.16E+09 0. 6.02E+10 Y-91 4.56E+03 0. 0. 0. 0. 6.06E+05 0. 1.22E+02 ZR-95 1.27E+04 5.37E+03 0. 2.23E+03 0. 9.22E+06 0. 3.96E+03 NB-95 3.30E+Q4 1.41 E+04 0. 5.81E+03 0. 2.44E+07 0. 1.04E+04 RU-103 4.79E+02 0. 0. 4.99E+02 0. 1.26E+04 0. 1.94E+02 RU-106 1.13E+04 0. 0. 5.04E+03 0. 1.75E+05 0. 1.40E+03 AG-110M 7.45E+06 6.90E+06 0. 1.36E+07 0. 2.81E+09 0. 4.10E+06 CD-115M 0. 1.59E+05 0. 1.26E+05 0. 6.70E+06 0. 5.09E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -36 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY -AIR-GRASS-GOATS-MILK (CONTAMINATED FORAGE) AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE. LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 2.10E+08 4.17E+06 1.22E+06 0. 5.97E+05 1.40E+08 0. 6.30E+06 SB-124 3.30E+06 6.22E+04 7.97E+03 0. 2.56E+06 9.33E+07 0. 1.30E+06 SB-125 3.75E+06 1.70E+05 1.43E+05 4.76E+05 3.40E+08 2.92E+07 0. 7.19E+05 TE-125M 8.85E+06 2.40E+06 2.49E+06 8.46E+06 0. 8.54E+06 0. 1.18E+06 TE-127M 6.21E+06 2.14E+06 1.75E+06 2.40E+07 0. 3.58E+07 0. 7.92E+05 TE-129M 3.32E+07 9.27E+06 1.06E+07 3.23E+07 0. 4.00E+07 0. 5.15E+06 1-130 5.45E+05 1.61E+06 2.05E+08 2.51E+06 0. 1.38E+06 0. 6.35E+05 1-131 1.48E+09 1.52E+09 4.94E+11 9.28E+08 0. 1.30E+08 0. 1.15E+09 1-132 2.18E-01 5.71 E-01 7.51E+01 9.10E-01 0. 1.0?E-01 0. 2.03E-01 1-133 2.14E+07 2.64E+07 6.36E+09 1.55E+07 0. 1.07E+07 0. 1.04E+07 1-134 0. 0. 1.27E-09 0. 0. 0. 0. 0. 1-135 1.79E+04 4.72E+04 6.18E+06 7.51 E+04 2.42E-01 5.29E+04 0. 1.73E+04 CS-134 6.50E+10 1.10E+11 0. 1.39E+10 1.22E+10 5.92E+08 0. 2.33E+10 CS-136 8.34E+08 3.29E+09 0. 1.83E+09 2.51E+08 3.74E+08 0. 2.37E+09 CS-137 9.28E+10 8.93E+10 0. 1.10E+10 1.05E+10 5.44E+08 0. 1.33E+10 BA-140 1.48E+07 1.23E+04 0. 1.48E+03 7.31E+03 9.30E+05 0. 8.21E+05 CE-141 1.49E+04 7.46E+03 0. 1.17E+03 0. 9.36E+06 0. 1.11E+03 CE-144 1.20E+06 3.76E+05 0. 6.80E+04 0. 9.78E+07 0. 6.41E+04 PR-143 2.03E+01 8.16E+OO 0. 4.70E+OO 0. 8.89E+04 0. 1.01E+OO ND-147 1.47E+01 1.42E+01 0. 8.66E+OO 0. 6.75E+04 0. 9.38E-01 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38-37 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY -AIR-GRASS-GOATS-MILK (CONTAMINATED FORAGE) AGE GROUP - INFANT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 4.84E+03 4.84E+03 2.11E+03 4.84E+03 4.84E+03 0. 4.84E+03 P-32 2.19E+1,0 1.37E+09 0. 0. 0. 2.46E+09 0. 8.46E+08 CR-51 0. 0. 2.19E+03 8.07E+02 4.85E+03 9.19E+05 0. 3.66E+03 MN-54 0. 1.08E+06 0. 3.20E+05 0. 3.29E+06 0. 2.05E+05 FE-59 4.12E+05 9.78E+05 0. 0. 2.72E+05 3.23E+06 0. 3.72E+05 C0-57 0. 1.64E+05 0. 0. 0. 4.15E+06 0. 2.72E+05 C0-58 0. 3.06E+06 0. 0. 0. 7.92E+06 0. 7.49E+06 C0-60 0. 1.05E+07 0. 0. 0. 2.59E+07 0. 2.51E+07 Nl-63 8.60E+08 5.96E+07 0. 0. 0. 1.24E+07 0. 2.88E+07 ZN-65 1.76E+08 5.57E+08 0. 3.73E+08 0. 3.51E+08 0. 2.52E+08 RB-86 0. 3.32E+08 0. 0. 0. 6.54E+07 0. 1.55E+08 SR-89 3.09E+10 0. 0. 0. 0. 5.77E+08 0. 8.87E+08 SR-90 3.46E+11 0. 0. 0. 0. 3.35E+09 0. 8.83E+10 Y-91 9.74E+03 0. 0. 0. 0. 6.45E+05 0. 2.60E+02 ZR-95 2.54E+04 1.13E+04 0. 2.23E+03 0. 8.95E+06 0. 6.67E+03 NB-95 6.59E+04 2.97E+04 0. 5.81E+03 0. 2.37E+07 0. 1.75E+04 RU-103 9.96E+02 0. 0. 4.99E+02 0. 1.24E+04 0. 3.43E+02 RU-106 2.41E+04 0. 0. 5.04E+03 0. 1.87E+05 0. 2.96E+03 AG-110M 7.45E+06 6.90E+06 0. 1.36E+07 0. 2.81E+09 0. 4.10E+06 CD-115M 0. 1.59E+05 0. 1.26E+05 0. 6.70E+06 0. 5.09E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xc/Q, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -38 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY-AIR-GRASS-GOATS-MILK (CONTAMINATED FORAGE) AGE GROUP - INFANT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 2.10E+08 4.17E+06 1.22E+06 0. 5.97E+05 1.40E+08 0. 6.30E+06 SB-124 3.30E+06 6.22E+04 7.97E+03 0. 2.56E+06 9.33E+07 0. 1.30E+06 SB-125 4.31E+06 3.92E+05 3.52E+05 4.76E+05 3.40E+08 2.92E+07 0. 7.94E+05 TE-125M 1.89E+07 6.36E+06 6.21E+06 8.46E+06 0. 9.09E+06 0. 2.52E+06 TE-127M 6.64E+06 2.31 E+06 2.15E+06 2.40E+07 0. 3.88E+07 0. 8.85E+05 TE-129M 7.05E+07 2.42E+07 2.66E+07 3.23E+07 0. 4.25E+07 0. 1.07E+07 1-130 5.45E+05 1.61E+06 2.05E+08 2.51 E+06 0. 1.38E+06 0. 6.35E+05 1-131 3.11E+09 3.70E+09 1.19E+12 9.28E+08 0. 1.39E+08 0. 2.17E+09 1-132 2.13E-01 5.71 E-01 7.51E+01 9.10E-01 0. 1.07E-01 0. 2.03E-01 1-133 4.50E+07 6.57E+07 1.55E+10 1.55E+07 0. 1.17E+07 0. 1.99E+07 1-134 0. 0. 1.27E-09 0. 0. 0. 0. 0. 1-135 1.79E+04 4.72E+04 6.18E+06 7.51 E+04 2.42E-01 5.29E+04 0. 1.73E+04 CS-134 1.33E+11 2.39E+11 0. 1.39E+10 2.74E+10 5.69E+08 0. 2.02E+10 CS-136 8.34E+08 3.29E+09 0. 1.83E+09 2.51E+08 3.74E+08 0. 2.37E+09 CS-137 1.93E+11 2.16E+11 0. 1.10E+10 2.61E+10 5.59E+08 0. 1.24E+10 BA-140 2.95E+07 2.96E+04 0. 1.47E+03 1.81E+04 9.76E+05 0. 1.52E+06 CE-141 3.17E+04 1.95E+04 0. 1.17E+03 0. 9.44E+06 0. 2.28E+03 CE-144 2.52E+06 9.95E+05 0. 6.80E+04 0. 1.04E+08 0. 1.36E+05 PR-143 2.03E+01 8.16E+OO 0. 4.70E+OO 0. 8.89E+04 0. 1.01E+OO ND-147 1.47E+01 1.42E+01 0. 8.66E+OO 0. 6.75E+04 0. 9.38E-01 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR y}Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 38 -39 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - FRESH AND STORED FRUITS AND VEGETABLES AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 2.86E+03 2.86E+03 2.86E+03 2.86E+03 2.86E+03 0. 2.86E+03 P-32 1.41 E+09 8.81E+07 0. 0. 0. 1.58E+08 -0. 5.44E+07 CR-51 0. 0. 2.78E+04 1.03E+04 6.19E+04 1.17E+07 0. 4.66E+04 MN-54 0. 3.13E+08 0. 9.31 E+07 0. 9.58E+08 0. 5.97E+07 FE-59 1.27E+08 3.01E+08 0. 0. 8.37E+07 9.95E+08 0. 1.15E+08 C0-57 0. 1.17E+07 0. 0. 0. 2.97E+08 0. 1.95E+07 C0-58 0. 3.08E+07 0. 0. 0. 6.24E+08 0. 6.90E+07 C0-60 0. 1.68E+08 0. 0. 0. 3.14E+09 0. 3.68E+08 Nl-63 1.04E+10 7.22E+08 0. 0. 0. 1.50E+08 0. 3.49E+08 ZN-65 3.18E+08 1.01E+09 0. 6.75E+08 0. 6.35E+08 0. 4.56E+08 RB-86 0. 2.20E+08 0. 0. 0. 4.34E+07 0. 1.03E+08 SR-89 1.00E+10 0. 0. 0. 0. 1.60E+09 0. 2.86E+08 SR-90 6.07E+11 0. 0. 0. 0. 1.61E+10 0. 1.49E+11 Y-91 5.14E+06 0. 0. 0. 0. 2.83E+09 0. 1.38E+05 ZR-95 1.40E+06 5.02E+05 0. 7.21 E+05 0. 1.92E+09 0. 3.06E+05 NB-95 1.42E+05 7.90E+04 0. 7.83E+04 0. 4.79E+08 0. 3.10E+04 RU~103 4.84E+06 0. 0. 1.86E+07 0. 5.66E+08 0. 2.09E+06 RU-106 1.93E+08 0. 0. 3.72E+08 0. 1.25E+10 0. 2.43E+07 AG-110M 1.06E+07 9.81E+06 0. 1.93E+07 0. 4.01E+09 0. 5.84E+06 CD-115M 0. 5.17E+07 0. 4.10E+07 0. 2.17E+09 0. 1.65E+06 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJO, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 3B-40 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - FRESH AND STORED FRUITS AND VEGETABLES AGE GROUP -ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 1.00E-05 1.66E-07 1.41 E-07 0. 0. 2.04E-05 0. 2.45E-07 SN-126 6.16E+09 1.37E+08 3.99E+07 0. 5.16E+07 8.84E+09 0. 2.23E+08 SB-124 1.04E+08 1.97E+06 2.51E+05 0. 8.06E+07 2.94E+09 0. 4.10E+07 SB-125 1.94E+08 1.06E+07 7.39E+07 9.77E+07 1.78E+10 1.59E+09 0. 3.73E+07 TE-125M 9.65E+07 3.51 E+07 2.91E+07 3.93E+08 0. 3.85E+08 0. 1.29E+07 TE-127M 3.50E+08 1.22E+08 9.18E+07 1.42E+09 0. 1.59E+09 0. 4.31E+07 TE-129M 2.55E+08 9.54E+07 8.79E+07 1.06E+09 0. 1.28E+09 0. 4.05E+07 1-130 3.93E+05 1.16E+06 1.48E+08 1.81E+06 0. 9.98E+05 0. 4.58E+05 1-131 8.83E+07 1.16E+08 3.79E+10 1.98E+08 0. 3.05E+07 0. 6.63E+07 1-132 5.57E+01 1.49E+02 1.96E+04 2.38E-02 0. 2.80E+01 0. 5.29E+01 1-133 2.13E+06 3.69E+06 7.10E+08 6.44E+06 0. 3.24E+06 0. 1.13E+06 1-134 1.03E-04 2.79E-04 3.63E-02 4.45E-04 0. 2.43E-07 0. 9.99E-05 1-135 4.04E+04 1.07E+05 1.40E+07 1.70E+05 6.27E-02 1.19E+05 0. 3.91 E+04 CS-134 4.87E+09 1.11E+10 0. 3.61 E+09 1.19E+09 1.94E+08 0. 9.09E+09 CS-136 4.20E+07 1.66E+08 0. 9.23E+07 1.27E+07 1.89E+07 0. 1.19E+08 CS-137 6.37E+09 8.70E+09 0. 2.96E+09 9.81 E+08 1.67E+08 0. 5.71E+09 BA-140 1.29E+08 1.70E+05 0. 5.50E+04 9.25E+04 8.54E+08 0. 8.48E+06 CE-141 1.98E+05 1.34E+05 0. 6.19E+04 0. 5.09E+08 0. 1.51E+04 CE-144 3.30E+07 1.38E+07 0. 8.16E+06 0. 1.11 E+10 0. 1.77E+06 PR-143 6.35E+04 2.55E+04 0. 1.47E+04 0. 2.78E+08 0. 3.15E+03 ND-147 9.68E+04 4.50E+04 0. 3.40E+04 0. 1.95E+08 0. 4.73E-03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xrlQ, AND D/Q. NOTE -THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -41 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - Fresh and Stored Fruits and Vegetables AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE (SQ METER - MREH/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 2.57E+03 2.57E+03 3.24E+03 2.57E+03 2.57E+03 0. 2.57E+03 P-32 1.13+09 7.06E+07 0. 0. 0. 1.27E+08 0. 4.36E+07 CR-51 0. 0. 2.74E+04 1.01E+04 6.0BE-04 1.15E+07 0. 4.58E+04 MN-54 0. 3.52E+08 0. 1.05E+08 0. 1.08E+09 0. 6.72E+07 FE-59 1.34E+08 3.18E+08 0. 0. 8.80E+07 1.05E+09 0. 1.21E+08 C0-57 0. ' 1.31E+07 0. 0. 0. 3.34E+08 0. 2.19E+07 C0-54 0. 4.45E+07 0. 0. 0. 6.02E+08 0. 1.02E+08 C0-60 0. 2.44E+08 0. 0. 0. 2.93E+09 0. 5.57E+08 Nl-63 1.18E-10 8.18E+08 0. 0. 0. 1.71E+08 0. 3.96E+08 ZN-65 3.57E+08 1.14E+09 0. 7.57E+08 0. 7.13E+08 0. 5.12E+08 RB-86 0. 1.94E+08 0. 0. 0. 3.83E+07 0. 9.06E+07 SR-89 1.58E+10 0. 0. 0. 0. 1.72E+09 0. 4.55E+08 SR-90 9.40E+11 0. 0. 0. 3.36E+09 2 ..97E+10 0. 2.33E+11 Y-91 7.69E+06 0. 0. 0. 0. 2.95E+09 0. 2.06E+05 ZR-95 1.87E+06 7.03E+05 0. 7.90E+05 0. 1.86E+09 0. 4.66E+05 NB-95 1.69E+05 1.02E+05 0. 8.00E+04 0. 4.15E+08 0. 5.73E+04 RU-103 6.46E+06 0. 0. 1.93E+07 0. 5.04E+08 0. 2.89E+06 RU-106 3.15E+08 0. 0. 4.20E+08 0. 1.43E+10 0. 3.96E+07 AG-110M 1.19E+07 1.10E+07 0. 2.17E+07 0. 4.50E+09 0. 6.56E+06 CD-115M 0. 5.41E+07 0. 4.29E+07 0. 2.28E+09 0. 1.73E+06 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 3B-42 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - Fresh and Stored Fruits and Vegetables AGE GROUP-TEENAGER NUCLIDE ORGAN DOSE (SQ. METER MREH/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 9.25E-06 1.53E-07 1.22E-07 0. 0. 1.33E-05 0. 2.28E-07 SN-126 7.79E+09 1.54E+08 4.53E+07 0. 6.01E+07 1.02E+10 0. 2.54E+08 SB-124 1.12E+08 2.11 E+06 2.71E+05 0. 8.69E+07 3.17E+09 0. 4.42E+07 SB-125 2.33E+08 1.66E+07 1.16E+07 1.15E+08 2.01E+10 1.82E+09 0. 4.40E+07 TE-125M 1.48E+08 5.30E+07 4.18E+07 4.22E+08 0. 4.14E+08 0. 1.97E+07 TE-127M 3.88E+08 1.36E+08 1.03E+08 1.56E+08 0. 1.95E+09 0. 4.81E+07 TE-129M 3.74E+08 1.39E+08 1.20E+08 1.08E+09 0. 1.31E+09 0. 5.90E+07 1-130 2.58E+05 7.64E+05 9.72E+07 1.19E+06 0. 6.55E+05 0. 3.00E+05 1-131 7.33E+07 1.03E+08 2.99E+10 1.34E+08 0. 1.96E+07 0. 6.17E+07 1-132 3.65E+01 9.77E+01 1.29E+04 1.56E+02 0. 1.84E+01 0. 3.47E+01 1-133 1.98E+06 3.36E+06 6.10E+08 4.23E+06 0. 2.44E+06 0. 1.04E+06 1-134 p.75E-05 1.83E-04 2.38E-02 2.92E-04 0. 1.60E-07 0. 6.56E-05 1-135 2.65E+04 7.00E+04 9.15E+06 1.11 E+05 7.12E-02 7.84E+04 0. 2.57E+04 CS-134 6.84E+09 1.65E+10 0. 4.08E+09 2.00E+09 1.90E+08 0. 7.69E+09 CS-136 3.25E+07 1.28E+08 0. 7.13E+07 9.78E+06 1.46E+07 0. 9.21E+07 CS-137 9.68E+09** 1.31E+10 0. 3.35E+09 1.73E+09 1.74E+08 0. 4.57E+09 BA-140 1.33E+08 1.78E+05 0. 4.22E+04 1.13E+05 4.94E+08 0. 8.86E+06 CE-141 2.68E+05 1.79E+05 0. 6.25E+04 0. 4.87E+08 0. 2.07E+04 CE-144 5.47E+07 2.25E+07 0. 9.17E+06 0. 1.29E+10 0. 2.91 E+06 PR-143 5.00E+04 2.20E+04 0. 1.16E+04 0. 2.19E+08 0. 2.49E+03 ND-147 9.80E+04 3.55E+04 0. 2.97E+04 0. 1.45E+08 0. 4.50E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -43 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - Fresh and Stored Fruits and Vegetables AGE GROUP - CHILD NUCLIDE ORGAN DOSE (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 3.98E+03 3.98E+03 2.62E+03 3.98E+03 3.98E+03 0. 3.98E+03 P-32 7.89E+08 4.94E+07 0. 0. 0. 8.87E+07 0. 3.05E+07 CR-51 0. 0. 2.10E+04 7.76E+03 4.67E+04 8.84E+06 0. 3.51E+04 MN-54 0. 2.84E+08 0. 8.45E+07 0. 8.70E+08 0. 5.42E+07 FE-59 1.05E+08 2.50E+08 0. 0. 6.95E+07 8.26E+08 0. 9.52E+07 C0-57 0. 1.06E+07 0. 0. 0. 2.69E+08 0. 1.77E+07 C0-58 0. 6.62E+07 0. 0. 0. 3.94E+08 0. 2.00E+08 C0-60 0. 3.69E+08 0. 0. 0. 2.05E+09 0. 1.11E+09 Nl-63 9.54E+09 6.62E+08 0. 0. 0. 1.38E+08 0. 3.20E+08 ZN-65 2.88E+08 9.12E+08 0. 6.10E+08 0. 5.75E+08 0. 4.13E+08 RB-86 0. 1.43E+08 0. 0. 0. 2.82E+07 0. 6.66E+07 SR-89 3.76E+10 0. 0. 0. 0. 1.40E+09 0. 1.08E+09 SR-90 1.26E+12 0. 0. 0. 0. 2.54E+10 0. 3.19E+11 Y-91 1.82E+07 0. 0. 0. 0. 2.42E+09 0. 4.87E+05 ZR-95 4.15E+06 1.09E+06 0. 6.33E+05 0. 1.32E+09 0. 9.43E+05 NB-95 3.55E+05 1.51E+05 0. 6.24E+04 0. 2.26E+08 0. 1.11 E+05 RU-103 1.45E+07 0. 0. 1.51E+07 0. 3.81E+08 0. 5.86E+06 RU-106 7.57E+08 0. 0. 3.38E+08 0. 1.18E+10 0. 9.42E+07 AG-110M 9.61E+06 8.89E+06 0. 1.75E+07 0. 3.63E+09. 0. 5.29E+06 CD-115M 0. 4.26E+07 0. 3.38E+07 0. 1.79E+09 0. 1.36E+06 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38 -44 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - Fresh and Stored Fruits and Vegetables AGE GROUP - CHILD NUCLIDE ORGAN DOSE (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 1.71E-05 2.14E-07 2.26E-07 0. 0. 8.503-06 0. 4.21E-07 SN-126 6.29E+09 1.25E+08 3.66E+07 0. 4.91E+07 8.33E+09 0. 2.06E+08 SB-124 8.90E+07 1.68E+06 2.15E+05 0. 6.90E+07 2.52E+09 0. 3.51E+07 SB-125 2.54E+08 2.86E+07 2.80E+07 9.47E+07 1.62E+10 1.46E+09 0. 4.44E+07 TE-125M 3.50E+08 9.50E+07 9.84E+07 3.35E+08 0. 3.38E+08 0. 4.67E+07 TE-127M 3.25E+08 1.12E+08 9.15E+07 1.26E+09 0. 1.87E+09 0. 4.14E+07 TE-129M 8.69E+08 2.42E+08 2.77E+08 8.43E+08 0. 1.05E+09 0. 1.34E+08 1-130 1.60E+05 4.73E+05 6.02E+07 7.35E+05 0. 4.05E+05 0. 1.86E+05 1-131 1.36E+08 1.39E+08 4.52E+10 8.48E+07 0. 1.19E+07 0. 1.05E+08 1-132 2.26E+01 6.05E+01 7.97E+03 9.65E+01 0. 1.14E+01 0. 2.15E+01 1-133 3.61E+06 4.46E+06 1.08E+09 2.62E+06 0. 1.81E+06 0. 1.75E+06 1-134 4.18E+05 1.14E+04 1.47E-02 1.81 E-04 0. 9.89E-08 0. 4.06E-05 1-135 1.64E+04 4.33E+04 5.67E+06 6.89E+04 5.75E-02 4.85E+04 0. 1.59E+04 CS-134 1.54E+10 2.59E+10 0. 3.29E+09 2.88E+09 1.40E+08 0. 5.51E+09 CS-136 2.23E+07 8.80E+07 0. 4.90E+07 6.72E+06 1.00E+07 0. 6.34E+07 CS-137 2.28E+10 2.21E+10 0. 2.72E+09 2.59E+09 1.34E+08 0. 3.29E+09 BA-140 2.76E+08 2.54E+05 0. 2.89E+04 1.44E+05 3.60E+08 0. 1.62E+07 CE-141 6.21 E+05 3.10E+05 0. 4.85E+04 0. 3.89E+08 0. 4.62E+04 CE-144 1.31E+08 , 4.10E+07 0. 7.39E+06 0. 1.06E+10 0. 6.97E+06 PR-143 3.48E+04 1.40E+04 0. 8.03E+03 0. 1.52E+08 0. 1.72E+03 ND-147 7.61E+04 2.46E+04 0. 2.17E+04 0. 9.80E+07 0. 3.40E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR xtQ, xJQ, AND D/Q. NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UGI/CU.METER) 38-45 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - Stored Fruits and Vegetables AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 2.46E+03 2.46E+03 2.46E+03. 2.46E+03 2.46E+03 0. 2.46E+03 P-32 3.67E+08 2.30E+07 0. 0. 0. 4.13E+07 0. 1.42E+07 CR-51 0. 0. 1.63E+04 6.03E+03 3.63E+04 6.87E+06 0. 2.73E+04 MN-54 0.. 2.64E+08 0. 7.86E+07 0. 8.09E+08 0. 5.04E+07 FE-59 9.06E+07 2.15E+08 0. 0. 5.97E+07 7.10E+08 0. 8.18E+07 C0-57 0. 9.85E+06 0. 0. 0. 2.50E+08 0. 1.64E+07 C0-58 0. 2.39E+07 0. 0. 0. 4.84E+08 0. 5.36E+07 C0-60 0. 1.44E+08 0. 0. 0. 2.69E+09 0. 3.16E+08 Nl-63 8.95E+09 6.21 E+08 0. 0. 0. 1.29E+08 0. 3.00E+08 ZN-65 2.67E+08 8.46E+08 0. 5.66E+08 0. 5.33E+08 0. 3.83E+08 RB-86 0. 9.00E+07 0. 0. 0. 1.78E+07 0. 4.20E+07 SR-89 7.34E+09 0. 0. 0. 0. 1.17E+09 0. 2.10E+08 SR-90 5.22E+11 0. 0. 0. 0. 1.40E+10 0. 1.28E+11 Y-91 3.88E+06 0. 0. 0. 0. 2.14E+09 0. 1.04E+05 ZR-95 1.11E+06 4.04E+05 0. 5.72E+05 0. 1.59E+09 0. 2.42E+05 NB-95 9.35E+04 5.19E+04 0. 5.15E+04 0. 3.15E+08 0. 2.04E+04 RU-103 3.34E+06 0. 0. 1.28E+07 0. 3.90E+08 0. 1.44E+06 RU-106 1.63E+08 0. 0. 3.15E+08 0. 1.06E+10 0. 2.06E+07 AG-110M 8.92E+06 8.25E+06 0. 1.62E+07 0. 3.37E+09 0. 4.91E+06 CD-115M 0. 3.64E+07 0. 2.89E+07 0. 1.53E+09 0. 1.16E+06 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. 38 -46 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - Stored Fruits and Vegetables AGE GROUP -ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 5.91E+09 1.18E+08 3.44E+07 0. 4.73E+07 7.99E+09 0. 1.94E+08 SB-124 7.88E+07 1.49E+06 1.90E+05 0. 6.11 E+07 2.23E+09 0. 3.11E+07 SB-125 1.68E+08 9.84E+06 6.99E+06 9.26E+07 1.52E+10 1.37E+09 0. 3.23E+07 TE-125M 7.27E+07** 2.64E+07 2.19E+07 2.96E+08 0. 2.90E+08 0. 9.74E+06 TE-127M 2.82E+08 9.87E+07 7.41E+07 1.15E+09 0. 1.28E+09 0. 3.48E+07 TE-124M 1.25E+08 6.20E+07 5.72E+07 6.92E+08 0. 8.32E+08 0. 2.63E+07 1-130 0. 0. 0. 0. 0. 0. 0. 0. 1-131 2.99E+06 4.28E+06 1.40E+09 7.33E+06 0. 1.13E+06 0. 2.45E+06 1-132 0. 0. 0. 0. 0. 0. 0. 0. 1-133 0. 0. 0. 0. 0. 0. 0. 0. 1-134 0. 0. 0. 0. 0. 0. 0. 0. 1-135 5.14E-01 4.74E-01 0. 1.BOE-01 5.40E-02 1.11 E-02 0. 2.11 E-01 CS-134 3.99E+09 9.50E+09 0. 3.08E+09 1.02E+09 1.66E+08 0. 7:76E+09 CS-136 8.82E+06 3.48E+07 0. 1.94E+07 2.66E+06 3.96E+06 0. 2.51E+07 CS-137 5.48E+09 7.48E+09 0. 2.55E+09 8.44E+08 1.44E+08 0. 4.91E+09 BA-140 2.60E+07 3.45E+04 0. 1.11E+04 1.87E+04 1.89E+08 0. 1.71E+06 CE-141 1.26E+05 8.50E+04 0. 3.94E+04 0. 3.24E+08 0. 9.63E+03 CE-144 2.78E+07 1.16E+07 0. 6.87E+06 0. 9.37E+09 0. 1.49E+06 PR-143 1.51E+04. 6.06E+03 0. 3.49E+03 0. 6.60E+07 0. 7.49E+02 ND-147 6.19E+04 1.06E+04 0. 1.33E+04 0. 3.19E+07 0. 2.49E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR xtQ, x.JQ, AND D/Q. 38-47 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - Stored Fruits and Vegetables AGE GROUP-TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 2.36E+03 2.36E+03 2.98E+03 2.36E+03 2.36E+03 0. 2.36E+03 P-32 4.45E+08 2.79E+07 0. 0. 0. 5.00E+07 0. 1.72E+07 CR-51 0. 0. 1.98E+04 7.31E+03 4.40E+04 8.33E+06 0. 3.31E+04 MN-54 0. 3.20E+08 0. 9.52E+07 0. 9.80E+08 0. 6.11E+07 FE-59 1.10E+08 2.61E+08 0. 0. 7.23E+07 8.60E+08 0. 9.91E+07 C0-57 0. 1.19E+07 0. 0. 0. 3.03E+08 0. 1.99E+07 C0-58 0. 3.85E+07 0. 0. 0. 5.21E+08 0. 8.78E+07 C0-60 0. 2.24E+08 0. 0. 0. 2.69E+09 0. 5.11E+08 Nl-63 1.08E+10 7.52E+08 0. 0. 0. 1.57E+08 0. 3.64E+08 ZN-65 3.23E+08 1.03E+09 0. 6.86E+08 0. 6.46E+08 0. 4.64E+08 RB-86 0. 1.09E+08 0. 0. 0. 2.15E+07 0. 5.09E+07 SR-89 1.32E+10 0. 0. 0. 0. 1.44E+09 0. 3.80E+08 SR-90 8.64E+11 0. 0. 0. 3.12E+09 2.74E+10 0. 2.14E+11 Y-91 6.54E+06 0. 0. 0. 0. 2.51E+09 0. 1.75E+05 ZR-95 1.63E+06 6.21 E+05 0. 6.92E+05 0. 1.67E+09 0. 4.10E+05 NB-95 1.32E+05 7.93E+04 0. 6.24E+04 0. 3.24E+08 0. 4.47E+04 RU-103 5.19E+06 0. 0. 1.55E+07 0. 4.05E+08 0. 2.32E+06 RU-106 2.87E+08 0. 0. 3.28E+08 0. 1.30E+10 0. 3.61E+07 AG-110M 1.08E+07 1.00E+07 0. 1.97E+07 0. 4.08E+09 0. 5.95E+06 CD-115M 0. 4.41E+07 0. 3.50E+07 0. 1.86E+09 0. 1.41 E+06 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR yjQ, xJQ, AND D/Q. 3B-48 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - Stored Fruits and Vegetables AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ. METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 7.16E+09 1.42E+08 4.17E+07 0. 5.73E+07 9.67E+09 0. 2.35E+08 SB-124 9.55E+07 1.80E+06 2.31 E+05 0. 7.41E+07 2.70E+09 0. 3.77E+07 SB-125 2.15E+08 1.60E+07 1.13E+07 1.12E+08 1.84E+10 1.67E+09 0. 4.06E+07 TE-125M 1.26E+08 4.50E+07 3.55E+07 3.58E+08 0. 3.52E+08 0. 1.67E+07 TE-127M 3.43E+08 1.21E+08 9.09E+07 1.38E+09 0. 1.73E+09 0. 4.26E+07 TE-129M 2.90E+08 1.07E+08 9.27E+07 8.38E+08 0. 1.01E+09 0. 4.56E+07 1-130 0. 0. 0. 0. 0. 0. 0. 0. 1-131 4.85E+06 6.85E+06 1.98E+09 8.88E+06 0. 1.30E+06 0. 4.08E+06 1-132 0. 0. 0. 0. 0. 0. 0. 0. 1-133 0. 0. 0. 0. 0. 0. 0. 0. 1-134 0. 0. 0. 0. 0. 0. 0. 0. 1-135 6.23E-01 5.75E-01 0. 2.18E-01 6.55E-02 1.34E-02 0. 2.55E-01 CS-134 6.26E+09 1.51E+10 0. 3.73E+09 1.83E+09 1.74E+08 0. 7.04E+09 CS-136 1.07E+07 4.22E+07 0. 2.35E+07 3.22E+06 4.79E+06 0. 3.04E+07 CS-137 8.90E+09 ,; 1.20E+10 0. 3.08E+09 1.59E+09 1.60E+08 0. 4.20E+09 BA-140 4.38E+07 5.70E+04 0. 1.34E+04 3.61E+04 1.75E+08 0. 2.82E+06 CE-141 2.05E+05 1.37E+05 0. 4.78E+04 0. 3.72E+08 0. 1.58E+04 CE-144 4.97E+07 2.04E+07 0. 8.33E+06 0. 1.17E+10 0. 2.64E+06 PR-143 1.83E+04 7.35E+03 0. 4.23E+03 0. 8.00E+07 0. 9.07E+02 ND-147 7.51E+04 1.29E+04 0. 1.61E+04 0. 3.86E+07 0. 3.03E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR xtQ, xJQ, AND D/Q. 38-49 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - Stored Fruits and Vegetables AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ. METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 3.73E+03 3.73E+03 2.46E+03 3.73E+03 3.73E+03 0. 3.73E+03 P-32 3.67E+08 2.30E+07 0. 0. 0. 4.13E+07 0. 1.42E+07 CR-51 0. 0. 1.63E+04 6.03E+03 3.63E+04 6.87E+06 0. 2.73E+04 MN-54 0. 2.64E+08 0. 7.86E+07 0. 8.09E+08 0. 5.04E+07 FE-59 9.06E+07 2.15E+08 0. 0. 5.97E+07 7.10E+08 0. 8.18E+07 C0-57 0. 9.85E+06 0. 0. 0. 2.50E+08 0. 1.64E+07 C0-58 0. 5.93E+07 0. 0. 0. 3.53E+08 0. 1.79E+08 C0-60 0. 3.46E+08 0. 0. 0. 1.92E+09 0. 1.04E+09 Nl-63 8.95E+09 6.21E+08 0. 0. 0. 1.29E+08 0. 3.00E+08 ZN-65 2.67E+08 8.46E+08 0. 5.66E+08 0. 5.33E+08 0. 3.83E+08 RB-86 0. 9.00E+07 0. 0. 0. 1.78E+07 0. 4.20E+07 SR-89 3.28E+10 0. 0. 0. 0. 1.22E+09 0. 9.38E+08 SR-90 1.18E+12 0. 0. 0. 0. 2.39E+10 0. 2.99E+11 Y-91 1.61E+07 0. 0. 0. 0. 2.14E+09 0. 4.30E+05 ZR-95 3.74E+06 9.93E+05 0. 5.72E+05 0. 1.21E+09 0. 8.55E+05 NB-95 2.93E+05 1.25E+05 0. 5.15E+04 0. 2.16E+08 0. 9.17E+04 RU-103 1.23E+07 0. 0. 1.28E+07 0. 3.22E+08 0. 4.95E+06 RU-106 7.05E+08 0. 0. 3.15E+08 0. 1.10E+10 0. 8.77E+07 AG-110M 8.92E+06 8.25E+06 0. 1.62E+07 0. 3.37E+09 0. 4.91E+06 CD-115M 0. 3.64E+07 0. 2.89E+07 0. 1.53E+09 0. 1.16E+06 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. 38 -50 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - Stored Fruits and Vegetables AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ. METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0. SN-126 5.91E+09 1.18E+08 3.44E+07 0. 4.73E+07 7.99E+09 0. 1.94E+08 SB-124 7.88E+07 1.49E+06 1.90E+05 0. 6.11E+07 2.23E+09 0. 3.11E+07 SB-125 2.42E+08 2.79E+07 2.73E+07 9.26E+07 1.52E+10 1.37E+09 0. 4.21E+07 TE-125M 3.09E+08 8.38E+07 8.68E+07 2.96E+08 0. 2.98E+08 0. 4.12E+07 TE-127M 2.96E+08 1.02E+08 8.34E+07 1.15E+09 0. 1.71E+09 0. 3.77E+07 TE-129M 7.12E+08 1.98E+08 2.27E+08 6.92E+08 0. 8.57E+08 0. 1.10E+08 1-130 0. 0. 0. 0. 0. 0. 0. 0. 1-131 1.17E+07 1.20E+07 3.90E+09 7.33E+06 0. 1.03E+06 0. 9.05E+06 1-132 0. 0. 0. 0. 0. 0. 0. 0. 1-133 0. 0. 0. 0. 0. 0. 0. 0. 1-134 0. 0. 0. 0. 0. 0. 0. 0. 1-135 5.14E-01 4.74E-01 0. 1.BOE-01 5.40E-02 1.11E-02 0. 2.11E-01 CS-134 1.44E+10 2.42E+10 0. 3.08E+09 2.69E+09 1.31E+08 0. 5.15E+09 CS-136 8.82E+06 3.48E+07 0. 1.94E+07 2.66E+06 3.96E+06 0. 2.51E+07 CS-137 2.14E+10 2.07E+10 0. 2.55E+09 2.43E+09 1.26E+08 0. 3.09E+09 BA-140 1.06E+08 9.79E+04 0. 1.11 E+04 5.52E+04 1.52E+08 0. 6.20E+06 CE-141 5.04E+05 2.52E+05 0. 3.94E+04 0. 3.16E+08 0. 3.75E+04 CE-144 1.22E+08 3.81E+07 0. 6.87E+06 0. 9.89E+09 0. 6.48E+06 PR-143 1.51E+04 6.06E+03 0. 3.49E+03 0. 6.60E+07 0. 7.49E+02 ND-147 6.19E+04 1.06E+04 0. 1.33E+04 0. 3.19E+07 0. 2.49E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR y}Q, xJQ, AND D/Q. 3B - 51 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY- FRESH FRUITS AND VEGETABLES AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 4.02E+02 4.02E+02 4.02E+02 4.02E+02 4.02E+02 0. 4.02E+02 P-32 1.04E+09 6.51E+07 0. 0. 0. 1.17E+08 0. 4.02E+07 CR-51 0. 0. 1.15E+04 4.25E+03 2.56E+04 4.85E+06 0. 1.93E+04 MN-54 0. 4.87E+07 0. 1.45E+07 0. 1.49E+08 0. 9.31E+06 FE-59 3.64E+o7* 8.64E+07 0. 0. 2.40E+07 2.85E+08 0. 3.29E+07 C0-57 0. 1.85E+06 0. 0. 0. 4.70E+07 0. 3.08E+06 C0-58 0. 6.89E+06 0. 0. 0. 1.40E+08 0. 1.54E+07 C0-60 0. 2.38E+07 0. 0. 0. 4.46E+08 0. 5.23E+07 Nl-63 1.45E+09 1.01E+08 0. 0. 0. 2.10E+07 0. 4.87E+07 ZN-65 5.11E+07 1.62E+08 0. 1.09E+08 0. 1.02E+08 0. 7.34E+07 RB-86 0. 1.30E+08 0. 0. 0. 2.56E+07 0. 6.06E+07 SR-89 2.67E+09 0. 0. 0. 0. 4.26E+08 0. 7.64E+07 SR-90 8.49E+10 0. 0. 0. 0, 2.14E+09 0. 2.07E+10 Y-91 1.26E+06 0. 0. 0. 0. 6.92E+08 0. 3.37E+04 ZR-95 2.93E+05 9.82E+04 0. 1.49E+05 0. 3.34E+08 0. 6.38E+04 NB-95 4.87E+04 2.71E+04 0. 2.68E+04 0. 1.64E+08 0. 1.06E+04 RU-103 1.50E+06 0. 0. 5.75E+06 0. 1.76E+08 0. 6.49E+05 RU-106 .2.95E+07 0. 0. 5.71E+07 0. 1.91E+09 0. 3.74E+06 AG-110M 1.69E+06 1.56E+06. 0. 3.08E+06 0. 6.38E+08 0. 9.30E+05 CD-115M 0. 1.53E+07 0. 1.21E+07 0. 6.42E+08 0. 4.88E+05 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. 3B-52 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY- FRESH FRUITS AND VEGETABLES AGE GROUP-ADULT NUCLIDE ORGAN DOSE FACTORS (SQ. METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-123* 1.00E-05 1.66E-07 1.41 E-07 0. 0. 2.04E-05 0. 2.45E-07 SN-126 4.52E+08 1.89E+07 5.54E+06 0. 4.31E+06 8.46E+08 0. 2.94E+07 SB-124 2.52E+07 4.75E+05 6.08E+04 0. 1.95E+07 7.12E+08 0. 9.94E+06 SB-125 2.58E+07 7.23E+05 4.03E+05 5.14E+06 2.56E+09 2.22E+08 0. 5.10E+06 TE-125M 2.38E+07 8.65E+06 7.17E+06 9.69E+07 0. 9.51 E+07 0. 3.19E+06 TE-127M 6.75E+07 2.36E+07 1.77E+07 2.73E+08 0. 3.06E+08 0. 8.32E+06 TE-129M 8.93E+07 3.34E+07 3.08E+07 3.73E+08 0. 4.49E+08 0. 1.42E+07 1-130 3.93E+05 1.16E+06 1.48E+08 1.81E+06 0. 9.98E+05 0. 4.58E+05 1-131 7.78E+07 1.12E+08 3.65E+10 1.91E+08 0. 2.94E+07 0. 6.38E+07 1-132 5.57E+01 1.49E+02 1.96E+04 2.38E+02 0. 2.80E+01 0. 5.29E+01 1-133 2.13E+06 3.69E+06 7.10E+08 6.44E+06 0. 3.24E+06 0. 1.13E+06 1-134 1.03E-04 2.79E-04 3.63E-02 4.45E-04 0. 2.43E-07 0. 9.99E-05 1-135 4.04E+04 1.07E+05 1.40E+07 1.70E+05 8.65E-03 1.19E+05 0. 3.91E+04 CS-134 6.82E+08 1.62E+09 0. 5.26E+08 1.74E+08 2.84E+07 0. 1.33E+09 CS-136 3.32E+07 1.31E+08 0. 7.29E+07 9.99E+06 1.49E+07 0. 9.43E+07 CS-137 8.90E+08 1.22E+09 0. 4.14E+08 1.37E+08 2.34E+07 0. 7.98E+08 BA-140 1.03E+08 1.35E+05 0. 4.39E+04 7.38E+04 6.65E+08 0. 6.77E+06 CE-141 7.16E+04 4.85E+04 0. 2.25E+04 0. 1.85E+08 0. 5.49E+03 CE-144 5.19E+06 2.17E+06 0. 1.29E+06 0. 1.75E+09 0. 2.78E+05 PR-143 4.84E+04 1.94E+04 0. 1.12E+04 0. 2.12E+08 0. 2.40E+03 ND-147 3.49E+04 3.43E+04 0. 2.07E+04 0. 1.63E+08 0. 2.24E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. 38-53 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSl1E DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY- FRESH FRUITS AND VEGETABLES AGE GROUP-TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ. METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 2.09E+02 2.09E+02 2.64E+02 2.09E+02 2.09E+02 0. 2.09E+02 P-32 6.81E+08 4.27E+07 0. 0. 0. 7.66E+07 0. 2.64E+07 CR-51 0. 0. 7.56E+03 2.79E+03 1.68E+04 3.18E+06 0. 1.27E+04 MN-54 0. 3.20E+07 0. 9.52E+06 0. 9.80E+07 0. 6.11E+06 FE-59 2.39E+07 5.67E+07 0. 0. 1.57E+07 1.87E+07 0. 2.16E+07 C0-57 0. 1.22E+06 0. 0. 0. 3.09E+07 0. 2.02E+06 C0-58 0. 6.01E+06 0. 0. 0. 8.12E+07 0. 1.37E+07 C0-60 0. 2.01E+07 0. 0. 0. 2.41 E+OB 0. 4.58E+07 Nl-63 9.52E+08 6.61E+07 0. 0. 0. 1.38E+07 0. 3.19E+07 ZN-65 3.35E+07 1.06E+08 0. 7.12E+07 0. 6.70E+07 0. 4.82E+07 RB-86 0. 8.52E+07 0. 0. 0. 1.68E+07 0. 3.97E+07 SR-89 2.61E+09 0. 0. 0. 0. 2.83E+08 0. 7.48E+07 SR-90 7.61E+10 0. 0. 0. 2.41E+08 2.31E+09 0. 1.88E+10 Y-91 1.15E+06 0. 0. 0. 0. 4.41 E+08 0. 3.06E+04 ZR-95 2.35E+05 8.19E+04 0. 9.81E+04 0. 1.92E+08 0. 5.61E+04 NB-95 3.72E+04 2.24E+04 0. 1.76E+04 0. 9.14E+07 0. 1.26E+04 RU-103 1.27E+06 0. 0. 3.77E+06 0. 9.87E+07 0. 5.66E+05 RU-106 2.82E+07 0. 0. 3.75E+07 0. 1.28E+09 0. 3.54E+06 AG-110M 1.11E+06 1.03E+06 0. 2.02E+06 0. 4.19E+08 0. 6.10E+05 CD-115M 0. 1.00E+07 0. 7.94E+06 0. 4.21E+08 0. 3.20E+05 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. 38-54 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY- FRESH FRUITS AND VEGETABLES AGE GROUP-TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ. METER-MREH/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-123 9.25E-06 1.53E-07 1.22E-07 0. 0. 1.33E-05 0. 2.28E-07 SN-126 6.25E+08 1.24E+07 3.64E+06 0. 2.83E+06 5.55E+08 0. 1.94E+07 SB-124 1.65E+07 3.12E+05 3.99E+04 0. 1.28E+07 4.67E+08 0. 6.53E+06 SB-125 1.73E+07 5.97E+05 3.48E+05 3.38E+06 1.68E+09 1.45E+08 0. 3.40E+06 TE-125M 2.23E+07 7.99E+06 6.30E+06 6.36E+07 0. 6.24E+07 0. 2.96E+06 TE-127M 4.46E+07 1.55E+07 1.18E+07 1.80E+08 0. 2.23E+08 0. 5.51 E+06 TE-129M 8.46E+07 3.14E+07 2.71E+07 2.45E+07 0. 2.95E+08 0. 1.33E+07 1-130 2.58E+05 7.64E+05 9.72E+07 1.19E+06 0. 6.55E+05 0. 3.00E+05 1-131 6.84E+07 9.66E+07 2.79E+10 1.25E+08 0. 1.83E+07 0. 5.76E+07 1-132 3.65E+01 9.77E+01 1.29E+04 1.56E+02 0. 1.84E+01 0. 3.47E+01 1-133 1.98E+06 3.36E+06 6.10E+08 4.23E+06 0. 2.44E+06 0. 1.04E+06 1-134 6.75E-05 1.83E-04 2.38E-02 2.92E-04 0. 1".60E-07 0. 6.56E-05 1-135 2.65E+04 7.00E+04 9.15E+06 1.11 E+05 5.67E-03 7.84E+04 0. 2.57E+04 CS-134 5.79E+08 1.40E+09 0. 3.45E+08 1.69E+08 1.61 E+07 0. 6.52E+08 CS-136 2.18E+07 8.60E+07 0. 4.78E+07 6.56E+06 9.77E+06 0. 6.19E+07 CS-137 7.83E+08 1.05E+09 0. 2.72E+08 1.40E+08 1.41 E+07 0. 3.70E+08 BA-140 9.38E+07 1.21E+05 0. 2.88E+04 7.73E+04 3.19E+08 0. 6.04E+06 CS-141 6.32E+04 4.24E+04 0. 1.47E+04 0. 1.15E+08 0. 4.86E+03 CS-144 5.03E+06 2.06E+06 0. 8.43E+05 0. 1.19E+09 0. 2.67E+05 PR-143 3.17E+04 1.28E+04 0. 7.34E+03 0. 1.39E+08 0. 1.58E+03 ND-147 2.29E+04 2.26E+04 0. 1.36E+04 0. 1.06E+08 0. 1.47E+03 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xr/Q, AND D/Q. 38-55 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY - FRESH FRUITS AND VEGETABLES AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREMNR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY H-3 0. 2.47E+02 2.47E+02 1.63E+02 2.47E+02 2.47E+02 0. 2.47E+02 P-32 4.22E+08 2.64E+07 0. 0. 0. 4.74E+07 0. 1.63E+07 CR-51 0. 0. 4.68E+03 1.73E+03 1.04E+04 1.97E+06 0. 7.83E+03 MN-54 0. 1.98E+07 0. 5.89E+06 0. 6.07E+07 0. 3.78E+06 FE-59 1.48E+07 3.51E+07 0. 0. 9.75E+06 1.16E+08 0. 1.34E+07 C0-57 0. 7.53E+05 0. 0. 0. 1.91E+07 0. 1.25E+06 C0-58 0. 6.94E+06 0. 0. 0. 4.13E+07 0. 2.09E+07 C0-60 0. 2.33E+07 0. 0. 0. 1.29E+08 0. 6.98E+07 Nl-63 5.90E+08 4.09E+07 0. 0. 0. 8.53E+06 0. 1.98E+07 ZN-65 2.08E+07 6.59E+07 0. 4.41E+07 0. 4.15E+07 0. 2.98E+07 RB-86 0. 5.28E+07 0. 0. 0. 1.04E+07 0. 2.46E+07 SR-89 4.84E+09 0. 0. 0. 0. 1.81E+08 0. 1.39E+08 SR-90 7.79E+10 0. 0. 0. 0. 1.52E+09 0. 1.98E+10 Y-91 2.12E+06 0. 0. 0. 0. 2.82E+08 0. 5.65E+04 ZR-95 4.06E+05 9.87E+04 0. 6.07E+04 0. 1.08E+08 0. 8.81E+04 NB-95 6.20E+04 2.64E+04 0. 1.09E+04 0. 4.58E+07 0. 1.94E+04. RU-103 2.24E-06 0. 0. 2.34E+06 0. 5.88E+07 0. 9.05E+05 RU-106 5.19E+07 0. 0. 2.32E+07 0. 8.07E+08 0. 6.46E+06 AG-110M 6.87E+05 6.36E+05 0. 1.25E+06 0. 2.59E+08 0. 3.78E+05 CD-115M 0. 6.20E+06 0. 4.92E+06 0. 2.61E+08 0. 1.98E+05 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR x/Q, xJQ, AND D/Q. 38-56 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS PATHWAY- FRESH FRUITS AND VEGETABLES AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.METER-MREM/YR PER UCI/SEC) BONE LIVER THYROID KIDNEY LUNG GI-LU SKIN TOTAL BODY SN-123 1.17E-05 2.14E-07 2.26E-07 0. 0. 8.50E-06 0. 4.21E-07 SN-126 3.87E+08 7.68E+06 2.25E+06 0. 1.75E+06 3.44E+08 0. 1.19E+07 SB-124 1.02E+07 1.93E+05 2.47E+04 0. 7.93E+06 2.89E+08 0. 4.40E+06 SB-125 1.22E+07 6.99E+05 6.22E+05 2.09E+06 1.04E+09 9.02E+07 0. 2.29E+06 TE-125M 4.12E+07 1.12E+07 1.16E+07 3.94E+07 0. 3.97E+07 0. 5.49E+06 TE-127M 2.88E+07 9.90E+06 8.09E+06 1.11 E+08 0. 1.65E+08 0. 3.67E+06 TE-129M 1.56E+08 4.35E+07 4.99E+07 1.51E+08 0. 1.88E+08 0. 2.41E+07 1-130 1.60E+05 4.73E+05 6.02E+07 7.35E+05 0. 4.05E+05 0. 1.86E+05 1-131 -1.24E+08 1.27E+08 4.13E+10 7.75E+07 0. 1.09E+07 0. 9.58E+07 1-132 2.26E+01 6.05E+01 7.97E+03 9.65E+01 0. 1.14E+01 0. 2.15E+01 1-133 3.61E+06 4.46E+06 1.08E+09 2.62E+06 0. 1.81E+06 0. 1.75E+06 1-134 4.18E-05 1.14E-04 1.47E-02 1.81 E-04 0. 9.89E-08 0. 4.06E-05 1-135 1.64E+04 4.33E+04 5.67E+06 6.89E+04 3.51E-03 4.85E+04 0. 1.59E+04 CS-134 9.97E+08 1.68E+09 0. 2.14E+08 1.87E+08 9.08E+06 0. 3.57E+08 CS-136 1.35E+07 5.32E+07 0. 2.96E+07 4.06E+06 6.05E+06 0. 3.83E+07 CS-137 1.41 E+09 1.37E+09 0. 1.68E+08 1.60E+08 8.34E+06 0. 2.04E+08 BA-140 1.70E+08 1.56E+05 0. 1.78E+04 8.87E+04 2.08E+08 0. 9.96E+06 CE-141 1.17E+05 5.84E+04 0. 9.13E+03 0. 7.33E+07 0. 8.69E+03 CE-144 9.23E+06 2.89E+06 0. 5.22E+05 0. 7.51E+08 0. 4.92E+05 PR-143 1.97E+04 7.89E+03 0. 4.54E+03 0. 8.60E+07 0. 9.75E+02 ND-147 1.42E+04 1.39E+04 0. 8.42E+03 0. 6.61E+07 0. 9.08E+02 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR xtQ, xJQ, AND D/Q. 3B-57 REV. 26
APPEND1X3C TECHNICAL BASIS FOR Aett AND TG131 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS APPEND1X3C Technical Bases for Aett and TG131 Overview The eyaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific. These effective factors, which are based on the typical radionuclide distribution in the releases, can be applied to the total radioactivity released to approximate the dose in the environment, i.e., instead of having to sum the isotopic distribution multiplied by the isotope specific dose factor only a single multiplication (Aett times the total quantity of radioactive material released) would be needed. This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculational technique. Determination of Aett The effective dose transfer factor is based on past operating data. The radioactive effluent distribution for the past years can be used to derive a single effective factor by the following equation: Aett = I A
f;
; (Eq. 3C-1) = the effective dose transfer factor = the dose transfer factor for radionuclide i = the fractional abundance of radionuclide i in the radioactive effluents This equation yields a single dose factor, weighted by the typical radionuclide distribution.
To determine the appropriate effective factor to be used and to evaluate the degree of variability, the atmospheric radioactive effluents for 3 years have been evaluated. An effective dose transfer factor has been determined for the gaseous effluents for all pathways of interest. Tables 3C-1 and 3C-2 present the results of this evaluation. For the radioiodines and particulates with half-lives greater than 8 days, the effective dose transfer factor is based solely on the radioiodines (1-131, and 1-133). This approach was selected because the radioiodines contribution essentially all of the dose to the infant's thyroid via the cow-milk pathway. The infant's thyroid and the cow-milk pathway are the critical organ and controlling pathway, respectively, for the releases of radioiodine and particulates. 3C -1 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS Determination of Aeff. , (Cont'd) All other particulates contribute less than 1% of the dose. The effective dose transfer factor is determined by applying equation 3C-1 to the radioiodines. However, in determining the dose, this effective dose transfer factor should be applied to the total release of all radioiodines and to particulates with half lives greater than 8 days. This uniform application is conservative in providing reasonable assurance that the actual dose will not be underestimated by the use of this simplified method. The determination of Aeff is limited to three years (1978, 1979, and 1980) because of the changes that occurred in the waste processing system. A demineralizer system replaced the previously used evaporator in the liquid Wqste processing system. Aeff was re-evaluated using gas radwaste data from 1992, 1993, and 1994. The re-evaluation indicated that no significant changes have occurred in the radioactive distribution of the release mixture from the Gaseous Radwaste System. As can be seen from Tables 3C-1 and 3C-2, the effective dose transfer factor varies little from year to year. The maximum observed variability from the average value is 13% for the noble gases and 25% for the radioiodines. This variability is min.or considering other areas of uncertainty and conservatism inherent in the environmental dose calculational models. To provide an additional degree of conservatism, a factor of 0.8 is introduced into the dose calculational process when the effective dose transfer factor is used. This added conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment. 3C-2 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS Table 3C-1 Effective Dose Transfer Factors: Noble Gases-Air Dose Ayeff A~eff Year mRad mRad 3 3 (µCi
sec/m ) (µCi

sec/m )
1978 1.3 X 10-5 3.4 X 10-5 5 5 1979 1.3x10- 3.4 X 10-5 5 1980 1.6 X 10- 3.4 X 10-5 5 Average 1.4 X 10- 3.4 X 10-Table 3C-2 Effective Dose Transfer Factor for Air-Grass-Cow-Milk-Infant-Thyroid Pathway, TG131 8 Weighted Dose Factor-Dose Factor Annual Airborne TG131 Radio nuclide Fraction mRem/yr Release (Ci) 2 mRem/yr (µCi/(m *sec)) 2 (µCi/(m *sec)) 1978 1-131 0.381 0.688 9.9E11 6.9E11 1-133 0.129 0.233 1.3E10 1-135 0.044 0.079 5.2E6 1979 1-131 0.0188 0.520 9.9E11 5.2E11 1-133 0.0156 0.432 1.3E10 1-135 0.0018 0.048 5.2E6 1980 1-131 0.0518 0.756 9.9E11 7.5E11 1-133 0.0124 0.181 1.3E10 1-135 0.0043 0.063 5.2E6 Averageb 6.5E11 a-Air-grass-cow-milk-infant-thyroid dose transfer factor. b-Effective dose commitment transfer factor is the average of weighted dose transfer factor over three years. 3C-3 REV. 26
SECTION 4 TOTAL DOSE FROM RADIOACTIVE EFFLUENTS, LIQUID AND GASEOUS REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 4.0 TOTAL DOSE CONTROL 4.1 :LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. APPLICABILITY : At all times. ACTION:
~~a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.3a., 2.3b., 3.3a., 3.3b.,~~
3.4a., or 3.4b., calculations shall be made including direct radiation contributions from the units to determine whether the above limits of Control 4.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Control 1.6.6, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203(a)(4), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
~~b. The provisions of Administrative Control section 1.6.3 are not applicable.~~
4-1 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 4.0 TOTAL DOSE CONTROL 4.1 :LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC (Cont'd) SURVEILLANCE REQUIREMENTS 4.1.1. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 2.3, 3.3, and 3.4, and in accordance with the methodology and parameters in this ODCM. 4.1.2. Cumulative dose contributions from direct radiation from the units, the Independent Spent Fuel Storage Installation (ISFSI), and the methodology used shall be indicated in the Annual Radioactive Effluent Release Report. This requirement is applicable only under conditions set forth in ACTION a. of Control 4.1 METHOD 4.1: LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC DISCUSSION: Control 4.1 implements 40 CFR Part 190.1 Oa. It requires the annual (calendar year) dose or dose commitment to any member of the public from all uranium fuel cycle operations to be limited to less than or equal to 75 mRem to the thyroid and 25 mRem to the total body or any other organ. Fuel cycle sources or nuclear power reactors other than the Turkey Point Plant itself do not measurably or significantly increase the radioactivity concentration in the vicinity of the Plant; therefore, only radiation and radioactivity in the environment attributable to the Plant itself are considered in the assessment of compliance with 40 CFR Part 190.102. In the event a dose calculated for the purpose of assessing compliance with Control 2.3, 3.3, or 3.4 exceeds 2 times the limit stated therein, then a calculation shall be made to determine whether any limit in Control 4.1 has been exceeded. The total dose calculated pursuant to Control 4.1 must include direct radiation contributions and the methodology for calculating direct radiation contribution must be indicated in the Annual Radioactive Effluent Release Report. These calculations should be made on the basis of radioactive effluents during the year-to-date and reference meteorological data or averaged meteorological data during completed quarters of the year-to-date. Separately, an evaluation of doses due to effluents during the year is performed annually and reported in the Annual Radioactive Effluent Release Report submitted each year. This evaluation uses reference meteorological data or annual averaged meteorological data concurrent with the annual gaseous releases to evaluate atmospheric dispersion, deposition, and plume gamma exposure. 4-2 REV.26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 4.0 TOTAL DOSE CONTROL 4.1 :LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC (continued) METHOD 4.1: LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC, (continued) DISCUSSION , (continued) To assess compliance with Control 4.1, evaluations of dose due to liquid and gaseous effluents are calculated as described by the equations for: o total body dose due to liquid effluent via irradiation by radionuclides deposited on cooling canal shoreline (equation 2.3-1) o total body dose due to noble gas gamma radiation (equation 4.1-1) o skin dose due to noble gas beta radiation (equation 4.1-2) o total body and maximally exposed organ doses due to gaseous effluents of radioactive 1-131, 1-133, tritium, and radioactive material in particulate form having a half-life greater than 8 days (equation 3.4-2). The doses are calculated on the basis of liquid and gaseous effluents from the Plant, sampled and analyzed in accordance with ODCM Tables 2.2-1 and 3.2-1. The receptor of the dose is described such that the dose to any member of the public is not likely to be underestimated. The receptor is selected on the basis of the combination of applicable pathways of exposure to gaseous effluent identified in the annual land use census and maximum ground level x/Q at the residence. Conditions more conservative than appropriate for the maximally exposed person may be assumed in the dose assessment. Environmental pathway-to-dose transfer factors used in the dose calculations appear in Appendix 38. When assessing compliance with 40 CFR Part 190 or 10 CFR Part 50 Appendix I dose limits, Radiological Environmental Monitoring Program results may be used to indicate actual radioactivity levels in the environment attributable to the Turkey Point Plant as an alternate to calculating the concentrations from radioactive effluent measurements. The measured environmental activity levels may thus be used to supplement the evaluation of doses to real persons for assessing compliance with 40 CFR Part 190 or 10 CFR Part 50 Appendix I. 4-3 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 4.0 TOTAL DOSE CONTROL 4.1 :LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC (continued) METHOD 4.1: LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC, (continued) DOSE TO A PERSON FROM NOBLE GASES Control 4.1 requires the calculation of the annual (calendar year) do,se or dose commitment to a member of the public exposed to radioactive liquid and gaseous effluents from the plant. One component of personal dose is total body irradiation by gamma rays from noble gases. Another is irradiation of skin by beta and gamma radiation from noble gases. The methods for calculating these doses are presented below. The amount of radioactive noble gas discharged is determined in the manner described in Method 3.2. GAMMA DOSE TO TOTAL BODY The gamma radiation dose to the whole body of a member of the public as a consequence of noble gas released from the Plant is calculated with the equation: Eqn4.1-1 where:
~~= noble gas gamma dose to total body, (mrem) = quantity of radioactive noble gas i discharged in gaseous effluent,~~
~~(µCi) x!O = atmospheric dispersion factor at the off-site location of interest, 3 (sec/m ) .~~
~~= factor converting time integrated, ground level concentration of noble gas nuclide, I, to total body dose from gamma radiation listed in Table 4.1-1, mrem~~
(µCi*sec/m 3) 4-4 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 4.0 TOTAL DOSE CONTROL 4.1 :LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC, (continued) METHOD 4.1: LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC, (continued) DOSE TO A PERSON FROM NOBLE GASES, (continued) When the total body dose due to gamma radiation from noble gas required by Control 4.1 is calculated, the most exposed receptor is located 1. 75 miles west northwest of the plant where the reference meteorological dispersion factor, x/Q, is 2.75 x 10-7 sec/m 3 . This calculation is the same technique used in Control 3.2, Equation 3.2-1, but is extrapolated to an annual release and the x/Q value is for the most exposed receptor, not the minimum dispersion point off-site. DOSE TO SKIN The radiation dose to the skin of a member of the public due to noble gas released from the Plant may be calculated with the equation : D- ~ [ 7Q;* S fe+ l.llLQ;* Ap] Eqn 4.1-2 where: D = dose to skin due to noble gases, (mrem) xto = atmospheric dispersion factor at the off-site location of interest, (sec/m3). Qi = quantity of radioactive noble gas i discharged in gaseous effluent, (µCi). Spi = factor converting time integrated ground level concentration of noble gas to skin dose from beta radiation listed in Table 4.1-1, mrem (µCi*sec/m 3 ) 1.11 = ratio of tissue dose equivalent to air dose in a radiation field, (mrem/mrad) Ayi = factor for converting time integrated, ground-level concentration of noble gas radionuclide i to air dose from its gamma radiation listed in Table 4.1-2, mrad (µCi*sec/m3). 4-5 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 4.0 TOTAL DOSE CONTROL 4.1 :LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC, (continued) METHOD 4.1: LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC, (continued) DOSE TO A PERSON FROM NOBLE GASES, (continued) When the skin beta dose due to noble gas required by Control 4.1 is calculated, the most exposed receptor is located 1. 75 miles west northwest of the Plant where the reference 7 3 meteorological dispersion factor, x!Q, is 2.75 x 10- sec/m . The total dose to the skin from noble gases is approximately equal to the beta radiation dose to the skin plus the gamma radiation dose to the total body. This is the same technique used in Control 3.2, Equation 3.2-3, but is extrapolated to an annual release, and the x!Q value is for the most exposed receptor rather than the minimum dispersion point off-site. DOSE TO A PERSON DUE TO DIRECT RADIATION When the dose due to direct radiation required by Control 4.1 is required to be calculated, the most appropriate TLD reading from the Radioactive Environmental Monitoring Program shall be used. This TLD reading shall be summed with the dose to a person from noble gas to obtain the total dose to Members of the Public. Specific methodology and which TLD measurement(s) used shall be described in the Annual Radioactive Effluent Release Report. 4-6 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 4.0 TOTAL DOSE CONTROL 4.1 :LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC (continued) METHOD 4.1: LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC, (continued) .BASIS 4.1 : LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR 20.1301 (d). The control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER of the PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2 and 3.2. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 4-7 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 4.0 TOTAL DOSE CONTROL 4.1 :LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC (continued) METHOD 4.1: LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC, (continued) Table 4.1-1 Transfer Factors for Maximum Dose to a Person Offsite due to Radioactive Noble Gases Air Dose Transfer Factors Pyi Spi mrem mrem Radionuclide ( µCi sec/m 3 ) ( µCi sec/m 3 ) Kr-83m 2.4 E-9 Kr-85m 3.7 E-5 4.6 E-5 Kr-85 5.1 E-7 4.2 E-5 Kr-87 1.9 E-4 3.1 E-4 Kr-88 4.7 E-4 7.5 E-5 Kr-89 5.3 E-4 3.2 E-4 Kr-90 4.9 E-4 2.3 E-4 Xe-131m 2.9 E-6 1.5 E-5 Xe-133m 8.0 E-6 3.1 E-5 Xe-133 9.3 E-6 9.7 E-6 Xe-135m 9.9 E-5. 2.3 E-5 Xe-135 5.7 E-5 5.9 E-5 Xe-137 4.5 E-5 3.9 E-4 Xe-138 2.8 E-4 1.3 E-4 Ar-41 2.8 E-4 8.5 E-5 Ref: Regulatory Guide 1.109, Revision 1, Table 8-1. Note: Values in the regulatory guide are quoted in units of pCi yr, to convert to units of µCi sec multiply by a factor of 3.171 E-2. 4-8 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 4.0 TOTAL DOSE CONTROL 4.1 :LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC (continued) METHOD 4.1: LIMITS OF TOTAL DOSE TO MEMBERS OF THE PUBLIC, (continued) Table 4.1-2 Transfer Factors for Maximum Offsite Air Dose Air Dose Transfer Factors Ayi A13i mrad mrad Radionuclide (µCi sec/m 3) (µCi sec/m 3) Kr-83m 6.1 E-7 9.1 E-6 Kr-85m 3.9 E-5 6.2 E-5 Kr-85 5.4 E-7 6.2 E-5 Kr-87 2.0 E-4 3.3 E-4 Kr-88 4.8 E-4 9.3 E-5 Kr-89 5.5 E-4 3.4 E-4 Kr-90 5.2 E-4 2.5 E-4 Xe-131m 4.9 E-6 3.5 E-5 Xe-133m 1.0 E-5 4.7 E-5 Xe-133 1.1 E-5 3.3 E-5 Xe-135m 1.1 E-4 2.3 E-5 Xe-135 6.1 E-5 7.8 E-5 Xe-137 4.8 E-5 4.0 E-4 Xe-138 2.9 E-4 1.5 E-4 Ar-41 2.9 E-4 1.0 E-4 Ref: Regulatory Guide 1.109, Revision 1, Table B-1 Note : Values in the regulatory guide are in units of pCi*yr, to convert to units of µCi*sec multiply by a factor of 3.171 E-2. 4-9 REV. 26
SECTION 5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.1 : CONDUCT OF SAMPLING AND ANALYSIS The Radiological Environmental Monitoring Program shall be conducted as specified in Table 5.1-1. APPLICABILITY: At all times. ACTION:
a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 5.1-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Control 1.4, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of confirmed ** radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 5.1-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Control 1.6.6, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Controls 2.3, 3.3, or 3.4. When more than one of the radionuclides in Table 5.1-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) + .... ~ 1.0 reporting level (1) reporting level (2) When radionuclides other than those in Table 5.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Control 2.3, 3.3, or 3.4.
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Control 1.4

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
** A confirmatory reanalysis of the original, a duplicate, or a new sample may be desirable, as appropriate. The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis, but in any case within 30 days.
5-1 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.1 : CONDUCT OF SAMPLING AND ANALYSIS (continued) ACTION (continued)
c. With milk or broad leaf vegetation samples unavailable from one or more of the sample locations required by Table 5.1-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in this ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program.
Pursuant to Control 1.3, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for this ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.
~~d. The provisions of Administrative Control section 1.6.3 are not applicable.~~
SURVEILLANCE REQUIREMENTS 5.1.1 The radiological environmental mo"nitoring samples* shall be collected pursuant to Table 5.1-1 from the specific locations given in the table and figure(s) in this ODCM, and shall be analyzed pursuant to the requirements of Table 5.1-1 and the detection capabilities required by Table 5.1-3. 5-2 REV. 26
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 5.1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM<1> 4 EXPOSURE NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY OF ANALYS1s< > PATHWAY AND/OR SAMPLES AND SAMPLE COLLECTION SAMPLE LOCATIONs<2 ><3 > FREQUENcy<4> 5
1. Direct Radiation< > Continuous Monitoring with Gamma Exposure Rate - quarterly 23 Monitoring Locations 6 Sample Collection Quarter1y< >

2. Airborne Continuous Sampler Radioiodine Filter-Analysis for 1-131 weekly Radioiodine and Operation with sample Particulate filter - Gross beta radioactivity analysis ;?:
Particulates Six Locations collection at least weekly or 24 hours following filter change<7>; ; Gamma isotopic 8 more frequently if required by analysis< > of composite<7 >(by location) quarterly. dust loading 10
3. Waterborne< >

a. Surface<8> Three Locations<
9
~~> Monthly 8~~
~~Gamma isotopic< >and tritium analysis monthly. 0~~
~~b. Sediment from Three Locations Semiannually Gamma isotopic analysis< > semiannually.~~
~~Shoreline~~
4. Ingestion

a. Fish and Invertibrates

1. Crustacea Two Locations Semiannually Gamma isotopic analysis<8>semiannually.
8
2. Fish Two Locations Semiannually Gamma isotopic analysis< > semiannually.

b. Food Products 9

1. Broad Leaf Three Locations (11) Monthly when available Gamma isotopic analysis <>and 1-131 analysis Vegitation monthly.
5-3 REV. 26
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 -TABLE 5.1-1 (Continued) (1) Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment or other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, corrective action shall be taken prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Control 1.4 (2) Specific parameters of distance and direction sector from the centerline of the plant vent stack and additional description where pertinent, shall be provided for each and every sample location in Table 5.1-1 in a table and figure(s) in this ODCM. (3) At times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in this ODCM. (4) The following definition of frequencies shall apply to Table 5.1-1 only: Weekly - Not less than once per calendar week. A maximum interval of 11 days is allowed between the collection of any two consecutive samples. Semi-Monthly - Not less than 2 times per calendar month with an interval of not less than 7 days between sample collections. A maximum interval of 24 days is allowed between collection of any two consecutive samples. Monthly - Not less than once per calendar month with an interval of not less than 10 days between collection of any two consecutive samples. Quarterly - Not less than once per calendar quarter. Semiannually - One sample each between calendar dates (January 1 - June 30) and (July 1 - December 31). An interval of not less than 30 days will be provided between sample collections. The frequency of analyses is to be consistent with the sample collection frequency. 5-4 REV. 26
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 - TABLE 5.1-1 (continued) (5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent
dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters (6) Refers to normal collection frequency. More frequent sample collection is permitted when conditions warrant it.
(7) Airborne particulate sample filters are analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. In addition to the requirement for a gamma isotopic on a composite sample, a gamma isotopic is also required for each sample having a gross beta radioactivity which is > 1.0 pCi/m 3 and which is also > 10 times that of the most recent control sample. (8) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. (9) Off-shore grab samples. (10) Discharges from the Turkey Point Plant do not influence drinking water or ground water pathways. (11) Samples of broad leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground level D/Q, and one sample of similar broad leaf vegetation at an available location 15-30 km distant in the least prevalent wind direction based upon historical data in this ODCM. 5-5 REV. 26
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 5.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES ANALYSIS WATER AIRBORNE FISH MILK FOOD PRODUCTS (pCi/1) PARTICULATE (pCi/kg, wet) (pCi/1) (pCi/kg, wet) 3 OR GASES (pCi/m ) H-3 30,000 Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95
... 400 1-131 2 .. 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 ... 200 300
~~Since no drinking water pathway exists, a value of 30,000 pCi/1 is used. For drinking water samples a value of 20,000 pCi/1 is used.~~
~~This is a 40 CFR 141.16 Table A value.~~
~~Applies to drinking water~~
~~'*** An equilibrium mixture of the parent and daughter isotopes which corresponds to the reporting value of the parent isotope 5-6 REV. 26~~
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 5.1-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYS1s<1> (2)(3) LOWER LIMIT OF DETECTION (LLD) ANALYSIS WATER AIRBORNE PARTICULATE FISH SEDIMENT MILK FOOD PRODUCTS (pCi/1) OR GASES (pCi/m 3) (pCi/kg, wet) (pCi/kg, dry) (pCi/1) (pCi/kg, wet) Gross Beta 4 0.01 H-3 3,000 Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-Nb-95
... 15< 5 1-131 1(4) 0.07 1 60 Cs-134 15 0.05 130 150 15 60 Cs-137 18 0.06 150 180 18 80 Ba-La-140 ... 15<5> 15<5>
Since no drinking water pathway exists, a value of 3,000 pCi/1 is used. For drinking water samples a value of 2,000 pCi/1 is used. Source NUREG-0472, Rev. 3. +
*** An equilibrium mixture of the parent and daughter isotopes which corresponds to the reporting value of the parent isotope 5-7 REV. 26
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-TABLE 5.1-3 (Continued) (1) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 1.4. (2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13. (3) The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: LLD = 4.66 (Sg} E
V

2.22

Y * [exp(-'A,Llt)]
Where: LLD = the "a priori" lower limit of detection as defined above as picoCuries per unit mass or volume, the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 2.22 = the number of disintegrations per minute per picoCurie, y = the fractional radiochemical yield, when applicable, A, = the radioactive decay constant for the particular radionuclide Llt = the elapsed time between environmental collection, or end of the sample collection period, and time of counting (sec). Typical values of E, V, Y, and Llt should be used in the calculation. 5-8 REV. 26
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/l may
~~be used.~~
(5) An equilibrium mixture of the parent and daughter isotopes which corresponds to 15 pCi/1 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 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.1 : CONDUCT OF SAMPLING AND ANALYSIS (continued) RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE Key to Sample Locations Sample Approx. Samples Direction Pathway Location Description Collection Distance Collected Sector Frequency (miles) Direct Convoy N-2 TLD Quarterly 2 N Radiation Point Direct Black Point Marina parking N-7 TLD Quarterly 7.1 N Radiation lot on siren pole Direct Old Cutler Rd across from Radiation N-10 Perdue Med. Ctr. on siren TLD Quarterly 10.6 N pole. East end of N. Canal Dr. on Direct TLD Quarterly 2.2 NNW NNW-2 siren pole E. of 117th Ave. Radiation Direct Bailes Rd. E. of US 1 on NNW-10 TLD Quarterly 9.2 NNW Radiation siren pole. Direct Turkey Point NW-1 TLD Quarterly 1.4 NW Radiation Entrance Rd Direct Intersection of Mowry Dr. and NW-5 TLD Quarterly 3.9 NW Radiation 117th Ave. on siren pole. 5-10 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.1: CONDUCT OF SAMPLING AND ANALYSIS (continued) RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE Key to Sample Locations Pathway Location Description Samples Sample Approx. Direction Collected Collection Distance Sector Frequency (miles) Direct NW-10 On Newtown Rd. N. of TLD Quarterly 10 NW Radiation Coconut Palm Drive on siren pole. Direct W-5 Palm Drive 0.3 mi. west of TLD Quarterly 5.3 w Radiation Tallahassee Rd. Direct WNW-10 NW 2nd Ave. S. of Campbell TLD Quarterly 9.8 WNW Radiation Dr. at Hmstd. Middle School on siren pole. Direct W-1 On site north side of TLD Quarterly 0.7 w Radiation Discharge Canal. Direct W-9 Card Sound Rd. 0.6 mi. SSE TLD Quarterly 8.6 w Radiation of US 1 on siren pole. Direct WSW-8 Card Sound Rd. 3.4 mi. SSE TLD Quarterly 7.8 WSW Radiation of US 1 on siren pole. Direct SW-1 On site near .land TLD Quarterly 1 SW Radiation utilization offices 5-11 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.1 : CONDUCT OF SAMPLING AND ANALYSIS (continued) RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE Key to Sample Locations Pathway Location Description Samples Sample Approx. Direction Collected Collection Distance Sector Frequency (miles) SSE-1 On site South East side of TLD Quarterly 1 Direct SSE cooling canals at "Turtle Radiation -- Point" Direct SW-8 Card Sound Rd. 5 mi. SSE TLD Quarterly 8 SW Radiation of US 1 at entrance to Navy facility. Direct SSW-5 On site, southwest corner TLD Quarterly 5 SSW Radiation of cooling canals Direct SSW-10 At Card Sound TLD Quarterly 10 SSW Radiation Bridge on siren pole. Direct S-5 On site, south east end of TLD Quarterly 5 s Radiation cooling canals. Direct S-10 Card Sound Road at TLD Quarterly 10 s Radiation Steamboat Creek. 5-12 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.1: CONDUCT OF SAMPLING AND ANALYSIS (continued) RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE Key to Sample Locations Sample Approx. Samples Distance Direction Sector Pathway Location Description Collection Collected (miles) Frequency Direct Radiation SSE-10 Ocean Reef TLD Quarterly 9 SSE Direct Radiation NNE-22* Natoma Substation TLD Quarterly 22.6 NNE Palm Dr. West of FPL Direct Radiation WNW2 Satellite School, near Site TLD Quarterly 1.6 Boundary WNW Airborne Entrance to Homestead Radioiodine and T51 Bayfront Park Particulate Weekly 2.2 NNW Siren pole 27, intersection of Radioiodine and Airborne T57 SW 11ih Ave and Particulate Weekly 4 NW SW 3041h St. Turkey Point Radioiodine and Airborne T58 Particulate Weekly 1.3 NW Entrance Rd Palm Dr. West of FPL Radioiodine and Airborne T41 Satellite School, near Site Particulate Weekly 1.6 WNW Boundary
~~Denotes control sample 5-13 REV. 26~~
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.1 : CONDUCT OF SAMPLING AND ANALYSIS (continued) RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE Key to Sample Locations Pathway Location Description Samples Sample Approx. Direction Collected Collection Distance Sector Frequency (miles) T64* Natoma Substation Radioiodine Weekly 22 NNE Airborne and Particulate Airborne T72 Turkey Point Land Utilization Radioiodine Weekly <1 WSW Entrance and Particulate T42 Biscayne Bay, at Turkey Point Surface Water Monthly <1 ENE Waterborne Shoreline Semi-Sediment annually Waterborne T67* Biscayne Bay, vicinity of Cutler Surface Water Monthly 13-18 N,NNE Plant north to Matheson Hammock Park Shoreline Semi-Sediment annually Waterborne T81 Card Sound, near mouth of old . Surface Water Monthly 6 s discharge canal Shoreline Semi-Sediment annually
~~Denotes control sample.~~
5-14 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.1 : CONDUCT OF SAMPLING AND ANALYSIS (continued) RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE Key to Sample Locations Sample Approx. Samples Direction Pathway Location Description Collection Distance Collected Sector Frequency (miles) Semi-Biscayne Bay, vicinity of Crustacea annually Food Products T67* Cutler Plant north to 13-18 N,NNE Matheson Hammock Park Semi-Fish annually Semi-Crustacea annually Card Sound near mouth of Food Products T81 old Discharge Canal. 6 s Semi-Fish annually South of Palm Dr. on SW Broad Food Products T40 leaf Monthly 3 W/WNW 117th St extension vegetation Palm Dr. West of FPL Broad Food Products T41 Satellite School near the site leaf Monthly 1.6 boundary vegetation WNW Near Biscayne Bay, Vicinity Broad Monthly Food Products T67* of Cutler Plant North to leaf 13 -18 N,NNE Matheson Hammock Park vegetation
~~Denotes control sample.~~
5-15 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.1 : CONDUCT OF SAMPLING AND ANALYSIS (continued) BASES 5.1 : MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not high~r than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 5.1-3 are considered optimum for routine environmental measurements in industrial laboratories. 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. 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-4007 (September 1984), in HASL Procedures Manual, HASL-300 and Hartwell, J. K. "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). 5-16 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NEAR SITE SAMPLING LOCATIONS Figure 5.1-1
~~City o Direct Radlillion (1LD) 5-17 REV. 26~~
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5 .0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DISTANT REMP SAMPLING LOCATIONS Figure 5 .1-2 REMP Figure 5.1*2 NNE-22 and T-64 are 22 miles from Turkey Point and outside the map area 5-18 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.2 : LAND USE CENSUS A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location, in each of the 16 meteorological sectors, of the nearest milk animal, the nearest residence, and the nearest gardens* of greater than 50 m 2 (500 ft2) producing broad leaf vegetation. APPLICABILITY : At all times. ACTION:
a. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Control 3.4, pursuant to Controi 1.3, identify the new location(s) in the next Annual Radioactive Effluent Release Report.

b. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Control 5.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in this ODCM. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to Control 1.3, submit in the next Annual Radioactive Effluent Release Report documentation for a change to this ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

c. The provisions of Administrative Control section 1.6.3 are not applicable.
Broad leaf vegetation sampling may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 5.1-1, Part 4.b., shall be followed, including analysis of control samples.
5-19 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SURVEILLANCE REQUIREMENTS 5.2.1 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 1.4 BASIS 5.2 : LAND USE CENSUS This control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.8.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2. 5-20 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM CONTROL 5.3: INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on all samples, supplied as part of an lnterlaboratory Comparison Program, that correspond to the matrices shown on Table 5.3-1 This control may be satisfied by participation in a government sponsored radiological measurements lntercomparison program that involves at least three of the matrices shown in Table 5.3-1 APPLICABILITY: At all times. ACTION:
a. With analysis not being performed as required above, report the corrective actions taken to prevent recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Control 1.4.

b. The provisions of Control 1.6.3 are not applicable.
SURVEILLANCE REQUIREMENTS: 5.3.1 A summary of the results obtained, as part of the above required lnterlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 1.4. METHOD 5.3: 5.3.1 The Program shall be conducted such that on an annual basis: At least three of the matrices will be involved, and at least two of the analytical methods will be evaluated, and for Gamma Spectroscopy, a majority of the nuclides shown in Table 5.3-1 will be included. 5.3.2 Any laboratory approved by FP&L may provide samples for the lntercomparison Program provided that the radioisotopes used for sample preparation are traceable to the National Institute of Standards and Technology (NIST). 5-21 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM METHOD 5.3: ( continued ) 5.3.3 Analysis of Matrix samples shall be capable of achieving ODCM Table 5.1-3 prescribed Lower Limit of Detection (LLD) on a blank sample. 5.3.4 Results within. 20% of expected should be considered acceptable. Results exceeding 20% but within 35% require a description of probable cause and actions performed to bring the analysis into conformance. Results exceeding 35% are considered Not Acceptable; the Matrix shall be replaced and reanalyzed. BASIS 5.3: INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved lnterlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR 50. The lnterlaboratory Comparison Program described herein provides an independent check on the precision and accuracy of the radiological monitoring measurements conducted as part of the Radiological Environmental Monitoring Program. The purpose of the lnterlaboratory Comparison Program described in this appendix is to provide adequate confidence in the results of Turkey Point's radiological monitoring measurements, by providing an independent test of the ability to measure radionuclides in the sample medium. 5-22 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE 5.3-1 1 INTERLABORATORY COMPARISON PROGRAM SAMPLE ANALYSIS <> Analytical ANALYSIS WATER l<lJ AIRBORNE PARTICULATE OR SOIL VEGETATION Method <2> GASES GB Gross Beta X H3 H-3 X Co-57 X Co-60 X X X Cs-134 X X Cs-137 X X X X Ce-144 X GS Mn-54 X K-40 X X Ru-106 X Sb-125 X 5-23 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS
1. The sample matrices shown on table 5.3-1 correspond to the matrices shown in Tables 5.1-1 & 5.1-2, with the following exceptions:

a. Milk is not currently in the REMP sampling program; there are no milk animals in the area encompassed by the Land Use Census. Therefore, inclusion of milk samples in the lnterlaboratory Comparison Program is not required. Continued exclusion of milk in the lnterlaboratory Comparison Program is acceptable until the Land Use Census indicates the existence of milk producing animals within the geographic area covered by REMP; see note 3, below.

b. The INGESTION exposure pathway is represented by inclusion of Broad Leaf Vegetation in the lnterlaboratory Comparison Program cross checks. Fish and Invertebrate samples are not included in the cross check program due to the instability of maintaining radioactivity in a fixed matrix due to decaying tissue and refrigeration limitations. *

2. The analytical methods to be evaluated are those applied in the current REMP:

a. GB - Gross Beta analysis of an Air Filter matrix

b. H3 - Tritium in water, using method employed in REMP

c. GS - Gamma Spectroscopy, Quantitative.

3. The Gamma Spectroscopy method for water will suffice for Gamma Spectroscopy of Milk, should milk samples become available. Milk is over 98 % water.
5-24 REV. 26
Turkey Point Supplemental Radiological Environmental Monitoring Program Appendix 5A REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Turkey Point Supplemental REMP Sampling The sampling and analysis program outlined in this appendix is performed in addition to the sample and analysis program required by Control 5.1. The sample sites, frequency, and analyses have been agreed upon by the State of Florida Department of Health and Florida Power and Light Co. These samples are not required to be performed, but based on this agreement, are performed to provide a broader data base for the Radiological Environmental Monitoring Program. 5A-1 REV. 26
TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Turkey Point Supplemental REMP Sampling Pathway: Direct Exposure via TLD Sampling and Collection Frequency: Continuous monitoring with sample collection and analysis performed quarterly. Name# Description NNW-6 Siren S29 pole, NE corner Moody Dr (SW 268 St) and Allapattah (SW 112 Ave) NW-7 Siren S28 pole, E side Pine Island Rd (SW 132 Ave) and N ofWaldin Dr (SW 280 St) NW-8 Siren S7 pole, SW 152 Ave at E end of SW 248 St WNW-3 Siren S21 pole, NW corner Palm Dr and Allapattah Rd (SW 117 Ave) WNW-6 Siren S25 pole, W side Tallahassee Rd (SW 137 Ave), N of Moody Dr W-8 Florida City Substation ENE-1 E end of Turkey Point, past Ranger Station T71 On site Red Barn picnic area T72 On site, just outside LU entrance
# name = bearing - approx range, miles Pathway: Airborne Radioiodines and particulates Sampling and Collection Frequency: Continuous monitoring with sample collection and analysis performed weekly .
~~Name Sector Distance~~
. Description T52 w 8 Florida City Substation T56 N 7 SW corner parking lot at Black Point Marina T71 NNE 0.5 On site Red Barn picnic area
~~Approximate Distance from plant in miles 5A-2 REV. 26~~
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, 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 T10 A SE corner of canal system 5A-3 REV. 26
Turkey Point Supplemental REMP Sampling Pathway: Ingestion, Milk Sampling and Collection Frequency: Semiannual collection and Gamma-Spec analysis Name Sector Distance
~~. Description T99 WNW 12 183rd block of SW 262nd St.~~
(alt) w 10 134th block of SW 2241h St. Pathway: Ingestion, Fish Pathway: Ingestion, Food Crop Sampling and Collection Frequency: Annual collection (@ harvest) and Gamma-Spec analysis Name# Sector I Distance* Description T43 Various locations: Various locations : 'truck farm' point of sale Nthru NWtoW growing fields, miscellaneous other sources of locally typically 2 to 10 miles grown food crops (e.g., corn, potato, sugar cane, greens, from plant etc) T44 T45
~~Although the Name remains the same, the locations can vary with sample availability.~~
~~Approximate Distance from plant in miles.~~
5A-4 REV. 26
Turkey Point Groundwater Sampling Program to Support the INDUSTRY INITIATIVE on Groundwater Protection Appendix SB REV. 26
Turkey Point Nuclear established and maintains a sampling and analysis program to meet the requirements of NEI 07-07, Industry Ground Water Protection Initiative, and future revisions to the document. Specific actions and requirements of the program will be controlled by site and corporate procedures. Periodic reviews of the program will be performed to.meet the recommendations of NEI 07-07, Industry Ground Water Protection Initiative. Locations of the monitoring wells and the depths and construction were chosen following a study of geology and hydrology of the site. 58-1 REV. 26}}

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