L-2020-079, 2019 Annual Radiological Environmental Operating Report for Turkey Point Units 3

2019 Annual Radiological Environmental Operating Report for Turkey Point Units 3

ML20129K061
Person / Time
Site:	Turkey Point
Issue date:	05/07/2020
From:	Hess R Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2020-079
Download: ML20129K061 (363)

Text

May 7, 2020 L-2020-079 10 CFR 50.36b U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-00001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 2019 Annual Radiological Environmental Operating Report Enclosed is the 2019 Annual Radiological Environmental Operating Report for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.1.3.

Should there be any questions or comments regarding this information, please contact Mr. Robert J.

Hess, Licensing Manager, at (305) 246-4112.

Sincerely, R~~~~e-s-s~~~~

Licensing Manager Turkey Point Nuclear Plant SM Enclosure cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Florida Power & Light Com pan y 9760 S.W. 344th Street Homestead, FL 33035

2019 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT UNITS 3 & 4 LICENSE NO. DPR-31, DPR-41 DOCKET NOS. 50-250, 50-251 Page 1 of 100

2019 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT- UNITS 3 & 4 TABLE OF CONTENTS DESCRIPTION PAGE Table of Contents 2 Executive Summary/Program Description 3-6 Discussion and Interpretation of Results 7-8 Environmental Radiological Monitoring Program Annual Analysis Summary 9-17 Deviations / Missing Data 18-19 Land Use Census 20-27 Key to Sample Locations ATTACHMENT A 28-34 Radiological Surveillance of Florida Power and ATTACHMENT B Light Companys Turkey Point Site 35 First Quarter, 2019 36-50 Second Quarter, 2019 51-64 Third Quarter, 2019 65-78 Fourth Quarter, 2019 78-91 Results from the Inter-laboratory Comparison ATTACHMENT C Program, 2019 92-94 Ground Water Protection, Industry Initiative ATTACHMENT D 95-99 ERRATA Data Section ATTACHMENT E 100- 101 Page 2 of 100

2019 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT- UNITS 3 & 4 EXECUTIVE

SUMMARY

The data obtained through the Turkey Point Radiological Environmental Monitoring Program (REMP) verifies that the levels of radiation and concentrations of radioactive materials in environmental samples are not increasing. These measurements verify that the dose or dose commitment to members of the public, due to operation of Turkey Point Units 3 & 4, during the surveillance year, is well within the limits established by 10 CFR 50, Appendix I. The sampling period was from January 1, 2019 to December 31, 2019. Additionally, supplemental samples collected by the State of Florida, DOH, do not indicate adverse trends in the radiological environment.

2019 PTN DIRECT EXPOSURE TLDs: QUARTERLY COLLECTION 6.00 Series1 Series2 5.00 Series3 Series4 4.00 EXPOSURE 3.00 2.00 1.00 0.00 Sep-15 Jun-16 Mar-17 Dec-17 Sep-18 Jun-19 Quarterly Breakdown Per Year Page 3 of 100

2019 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT- UNITS 3 & 4 Turkey Point 2019 REMP Gross Beta in Air, pCi/m3 0.08 0.07 0.06 0.05 Conc. pCi/m3 0.04 0.03 0.02 0.01 0.00 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 week of year Minimum Average Maximum I. INTRODUCTION This report is submitted pursuant to Specification 6.9 of Turkey Point Units 3 & 4 Technical Specifications. The Annual Radiological Environmental Operating Report provides information, summaries and analytical results pertaining to the Radiological Environmental Monitoring Program for the calendar year indicated. This report covers surveillance activities described in the Offsite Dose Calculation Manual (ODCM) meeting the requirements of Unit 3 and Unit 4 Technical Specifications.

II. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A. Purpose The purpose of the Radiological Environmental Monitoring Program is to provide representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of members of the public resulting from station operation. The Radiological Environmental Monitoring Program also supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

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2019 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT- UNITS 3 & 4 B. Program Description The Radiological Environmental Monitoring Program for the Turkey Point Plant is conducted pursuant to Control 5.1 of Turkey Point Unit 3 & 4 ODCM.

1. Sample Locations, Types and Frequencies:

a. Direct radiation gamma exposure rate is monitored continuously at 23 locations by thermoluminescent dosimeters (TLDs). TLDs are collected and analyzed quarterly.

b. Airborne radioiodine and particulate samplers are operated continuously at six locations.

Samples are collected and analyzed weekly. Analyses include Iodine-131, gross beta, and gamma isotopic measurements.

c. Surface water samples are collected from three locations. Samples are collected and analyzed monthly. Analyses include gamma isotopic and tritium measurements.

d. Shoreline sediment samples are collected from three locations coinciding with the locations for surface water samples. Samples are collected and analyzed semi-annually. Sediment samples are analyzed by gamma isotopic measurements.

e. Fish and invertebrate samples are collected from two locations coinciding with two of the locations for surface water samples. Samples are collected and analyzed semi-annually.

Fish and invertebrate samples are analyzed by gamma isotopic measurements.

f. Broad leaf vegetation samples are collected from three locations. Samples are collected and analyzed monthly. Broad leaf vegetation samples are analyzed by gamma isotopic measurements.

Attachment A provides specific information pertaining to sample locations, types and frequencies.

Note: Ground Water Protection, NEI Initiative: The program and results are described in Attachment D.

2. Analytical Responsibility:

Radiological environmental monitoring for the Turkey Point Plant is conducted by the State of Florida, Department of Health (DOH). Samples are collected and analyzed by DOH personnel.

Samples are analyzed at the DOH Environmental Radiation Control Laboratory in Orlando, Florida.

Note: The State is not involved in the (Industry Initiative) ground water monitoring program.

C. Analytical Results Table 1, Environmental Radiological Monitoring Program Annual Summary provides a summary for all specified samples collected during the referenced surveillance period. Deviations from the sample schedule, missing data and/or samples not meeting the specified "A PRIORI" LLD, if any, are noted and explained in Tables 1A and 1B respectively. Analysis data for all specified samples analyzed during the surveillance period is provided in Attachment B.

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2019 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT- UNITS 3 & 4 D. Land Use Census A land use census out to a distance of 5 miles radius from the Turkey Point Plant is conducted annually to determine the location of the nearest milk animal, residence, and garden producing broad leaf vegetation, in each of the sixteen meteorological sectors. A summary of the land use census for the surveillance year is provided in Table 2, Land Use Census Summary.

E. Interlaboratory Comparison Program The Interlaboratory Comparison Program consists of participating in the DOE Mixed Analyte Performance Evaluation Program (MAPEP).

This program provides similar testing (matrices, nuclides, and levels) as the former EPA Interlaboratory Comparison Program and is referred to as the Mixed Analyte Performance Evaluation Program (MAPEP).

The samples are analyzed using the methods applicable to the REMP (gamma spectroscopy, Gross Beta, and Tritium for water).

From the MAPEP handbook:

Acceptance criteria were developed from a review of precision and accuracy data compiled by other performance evaluation programs (PEPs), the analytical methods literature, from several MAPEP pilot studies, and from what is considered reasonable, acceptable, and achievable for routine analyses among the more experienced laboratories.

The results for nuclides associated with the REMP are listed in ATTACHMENT C, Results from the Interlaboratory Comparison Program.

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2019 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT- UNITS 3 & 4 III. DISCUSSION AND INTERPRETATION OF RESULTS A. Reporting of Results The Annual Radiological Environmental Operating Report contains the summaries, interpretations and information required by Control 1.4 of ODCM. Table 1 provides a summary of the measurements made for the nuclides required by ODCM Table 5.1-2, for all samples specified by Table 5.1-1. In addition, summaries are provided for other nuclides identified in the specified samples, including those not related to station operation. These include nuclides such as K-40, Th-232, Ra-226, and Be-7 which are common in the Florida environment.

B. Interpretation of Results

1. Direct Radiation:

The results of direct radiation monitoring are consistent with past measurements for the specified locations. The exposure rate data shows no indication of any trends attributed to effluents from the plant. The measured exposure rates are consistent with past historical exposure rates.

2. Air Particulates/Radioiodine:

For results attributed to plant effluents:

The results for radioactive air particulate and radioiodine monitoring are consistent with past measurements and indicate no trends attributed to plant effluents. All samples for radioiodine yielded no detectable I-131. Gamma isotopic measurements yielded no indication of any nuclides attributed to station operation. The results for air particulate/radioiodine samples are consistent with historical trends. Air particulate and radioiodine monitoring results are summarized in Table 1.

3. Waterborne, Surface Water:

The results of radioactivity measurements in surface water samples are consistent with past measurements. Tritium was reported as present in 0 of 24 indicator locations and 0 of the 12 control locations. The highest reported tritium is less than detectable, below the required reporting level of 30,000 pCi/L as specified by ODCM Table 5.1-2. Additionally, the highest reported tritium for the supplemental sampling program is 15,575 pCi/L.

4. Waterborne, Sediment:

Gamma isotopic measurements yielded no indication of any nuclides attributed to station operation.

5. Waterborne, Food Products:

The results are consistent with past measurements. Gamma isotopic measurements yielded no indication of any nuclides attributed to station operation.

6. Broad Leaf Vegetation For results attributed to plant effluents:

The results of radioactivity measurements are consistent with past measurements. Cs-137 was detected in samples collected from the indicator locations. This activity identified could be from weapons fallout testing 30-40 years ago and reactor accidents at Chernobyl and are contributors. The maximum concentration reported was 89 pCi/kg well below the Page 7 of 100

2019 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT- UNITS 3 & 4 required reporting level of 2000 pCi/kg as specified by ODCM Table 5.1-2. No other fission products were detected.

7. Land Use Census A land use census out to a distance of a five-mile radius from the Turkey Point Plant is conducted annually to determine the location of the nearest milk animal, residence, and garden producing broad leaf vegetation, in each of the 16 meteorological sectors. A summary of the land use census for the surveillance year is provided in Table 2, Land Use Census Summary.

8. Interlaboratory Comparison Program The State laboratory participated in MAPEP 40 and 41. These satisfied the requirement of Control 5.3 of the ODCM for the Interlaboratory Comparison Program. The results are listed in Attachment C.

C. Conclusions The data obtained through the Turkey Point Plant Radiological Environmental Monitoring Program verifies that the levels of radiation and concentrations of radioactive materials in environmental samples, representing the highest potential exposure pathways to members of the public, are not being increased. The measured exposure rates and air particulate/radioiodine samples are consistent with exposure rates that were observed during the pre-operational surveillance program.

The highest value of tritium in surface water was less than detectable far below the required LLD listed in ODCM Table 5.1-3. There were no indications of any other nuclides that could be attributed to plant effluents. There were no indications of any nuclides in waterborne sediment or food products attributed to plant effluents. The results of radioactivity measurements for broad leaf vegetation are consistent with past measurements. Additionally, supplemental to the ODCM program, sampling of the direct exposure, inhalation, and ingestion pathways, performed by Florida DOH, does not show adverse trends in levels of radiation and radioactive materials in unrestricted areas. The measurements verify that the dose or dose commitment to members of the public, due to operation of Turkey Point Units 3 & 4, during the surveillance year, are well within "as low as reasonably achievable (ALARA)" criteria established by 10 CFR 50, Appendix I.

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2019 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TURKEY POINT PLANT- UNITS 3 & 4 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL ANALYSIS

SUMMARY

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PATHWAY: DIRECT RADIATION SAMPLES COLLECTED: TLD UNITS: micro-R/hr Location with Highest Annual Mean Namec Mean (f)b Type and Total Number of Lower Limit of All Indicator Distance & Direction Range Control Locations Analyses Performed Detectiona (LLD) Locations Mean (f)b Range Mean (f)b Range Exposure Rate, 91 --- 3.72 (91/91) 1. NW-10 1. 4.64 (4/4) 4.04 (4/4) 2.77 - 5.05 10 mi., NW 4.05 - 5.05 3.80 - 4.30 Number of Non-routine Reported Measurements = 0 Page 10 of 100

PATHWAY: AIRBORNE SAMPLES COLLECTED: RADIOIODINE AND PARTICULATES UNITS: pCi/m3 Location with Highest Annual Mean Namec Mean (f)b All Indicator Type and Total Number of Lower Limit of Distance & Control Locations Locations Range Analyses Performed Detectiona (LLD) Direction Mean (f)b Range Mean (f)b Range 131I, 312 0.012 <MDA --- --- < MDA 0.013 (257/257) T-41 0.013 (50/50) 0.013 (52/52)

Gross Beta, 312 0.0064 0.000 - 0.030 1.6 mi, WNW 0.005- 0.030 0.004 - 0.025 Composite Gamma Isotopic, 32 7Be 0.1233 (28/28) T-41 0.1168 (4/4) 0.1000 (4/4) 0.006 0.0823 - 0.2190 1.6 mi, WNW 0.0823 - 0.1420 0.1195 - 0.1320 0.0072 (1/28) T-57 0.0072 (1/4) < MDA 40K 0.018

< MDA - 0.0072 4 mi, NW < MDA - 0.0072 134Cs 0.0008 < MDA --- --- < MDA 137Cs 0.0008 < MDA --- --- < MDA 210Pb 0.0166 (07/28) T-51 0.0267 ( 2/4) 0.0119 (2/4) 0.0073- 0.0334 2.2 mi, NNW <MDA - 0.0334 <MDA - 0.0119 Be-7, K-40 & Pb-210 are naturally occurring.

Number of Non-routine Reported Measurements = 0 Page 11 of 100

PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER UNITS: pCi/L Location with Highest Annual Mean Namec Mean (f)b Type and Total Number of Lower Limit of All Indicator Distance & Direction Range Control Locations Analyses Performed Detectiona (LLD) Locations Mean (f)b Range Mean (f)b Range Tritium, 36 172 <MDA T-81 <MDA <MDA 6 mi., S Gamma Isotopic, 36 40K 58 372 (24/24) T-42 364 (12/12) 217 (12/12) 277 - 502 <1 mi., ENE 227 - 502 101 - 318 54Mn 3 < MDA --- --- < MDA 59Fe 6 < MDA --- --- < MDA 58Co 3 < MDA --- --- < MDA 60Co 4 < MDA --- --- < MDA 65Zn 7 < MDA --- --- < MDA 95Zr-Nb 6 < MDA --- --- < MDA 131I 4 < MDA --- --- < MDA 134Cs 4 < MDA --- --- < MDA 137Cs 4 < MDA --- --- < MDA 140Ba-La 9 < MDA --- --- < MDA K-40 is naturally occurring.

Number of Non-routine Reported Measurements = 0 Page 12 of 100

PATHWAY: WATERBORNE SAMPLES COLLECTED: SHORELINE SEDIMENT UNITS: pCi/kg, DRY Location with Highest Annual Mean Namec Mean (f)b All Indicator Type and Total Number of Lower Limit of Control Locations Locations Distance & Direction Range Analyses Performed Detectiona (LLD) Mean (f)b Range Mean (f)b Range Gamma Isotopic, 6 7Be 95 (1/4) T-42 <MDA <MDA 56

<MDA -95 <1 mi., ENE 40K 203 (2/4) T-42 181 (1/2) 296 (1/2) 100 181 - 224 <1 mi., ENE <MDA - 181 172 - 420 58Co 6 <MDA --- --- < MDA 60Co 7 <MDA --- --- < MDA 134Cs 7 <MDA --- --- < MDA 137Cs 7 <MDA --- --- < MDA 210Pb

<MDA T-42

--- --- < MDA

<1 mi., ENE 226Ra 15 <MDA --- --- < MDA 235U 631 (4/4) T-42 594 (1/2) 594 - 667 <1 mi., ENE <MDA - 594 < MDA 238U 1057 (4/4) T-42 1033.5 (2/2) 491.5 (2/2) 734 - 1427 <1 mi., ENE 990 - 1077 390 - 593 Be-7, K-40, Pb-210, Ra-226, U-235 & U-238 are naturally occurring.

Number of Non-routine Reported Measurements = 0 Page 13 of 100

PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA UNITS: pCi/kg, WET Location with Highest Annual Mean Namec Mean (f)b All Indicator Type and Total Number of Lower Limit of Distance & Control Locations Locations Range Analyses Performed Detectiona (LLD) Direction Mean (f)b Range Mean (f) Range Gamma Isotopic, 2 40K 1618.25 (1/2) T-81 1586.5 (1/2) 1650 (2/2) 270 1163 - 2010 6 mi., S 1163 - 2010 1310 - 1990 226Ra 300 <MDA --- --- <MDA 54Mn 16 --- --- --- ---

59Fe 28 --- --- --- ---

58Co 15 --- --- --- ---

60Co 16 --- --- --- ---

65Zn 32 --- --- --- ---

134Cs 16 --- --- --- ---

137Cs 18 --- --- ---

Number of Non-routine Reported Measurements = 0 Page 14 of 100

PATHWAY: INGESTION SAMPLES COLLECTED: FISH UNITS: pCi/kg, WET Location with Highest Annual Mean Namec Mean (f)b All Indicator Type and Total Number of Lower Limit of Control Locations Locations Distance & Direction Range Analyses Performed Detectiona (LLD) Mean (f)b Range Mean (f) Range Gamma Isotopic, 4 7Be --- <MDA --- --- <MDA 40K 2342.5 (2/2) T-81 2888 (2/2) 1797 (2/2) 270 6 mi., S 1474 - 2342.5 2596- 3180 1474 - 2120 54Mn 16 <MDA --- --- <MDA 59Fe 28 <MDA --- --- <MDA 58Co 15 <MDA --- --- <MDA 60Co 16 <MDA --- --- <MDA 65Zn 32 <MDA --- --- <MDA 134Cs 16 <MDA --- --- <MDA 137Cs 16 <MDA --- --- <MDA 226Ra 300 <MDA --- --- <MDA 238U --- <MDA --- --- <MDA Be-7, K-40, Pb-210, Ra-226 & U-238 are naturally occurring.

Number of Non-routine Reported Measurements = 0 Page 15 of 100

PATHWAY: INGESTION SAMPLES COLLECTED: BROAD LEAF VEGETATION UNITS: pCi/kg, WET Location with Highest Annual Mean Namec Mean (f)b All Indicator Type and Total Number of Lower Limit of Distance & Control Locations Locations Range Analyses Performed Detectiona (LLD) Direction Mean (f)b Range Mean (f)Range Gamma Isotopic, 36 7Be 1593 (24/24) T-40 1702 (12/12) 1276 (12/12) 64 465 - 3340 3 mi., W 954 - 3260 336 - 2280 40K 4787 (24/24) T-41 5219 (12/12) 4595 (12/12) 120 3470 - 6580 1.6 mi., WNW 3573 - 6580 2980 - 6196 58Co 6 <MDA --- --- <MDA 60Co 8 <MDA --- --- <MDA 131I 8 <MDA --- --- <MDA 134Cs 8 <MDA --- --- <MDA 137Cs 26.8 (15/24) T-40 38 (11/12) 14 (3/12) 8 6 - 89 3 mi., W <MDA - 89 <MDA - 17 210Pb 476 (3/24) T-40 561 (1/12) 373 (2/12)

--- <MDA - 373 252 - 1050 3 mi., W 252 - 1050 226Ra 815 (2/12) 189 <MDA --- ---

339 - 1290 Be-7, K-40, Pb-210 & Ra-226 are naturally occurring.

Number of Non routine Reported Measurements = 0 Page 16 of 100

NOTES

a. The LLD is an "a priori" lower limit of detection which establishes 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. LLDs in this column are at time of measurement. The MDAs reported in Attachment B for the individual samples have been corrected to the time of sample collection.

b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f).

c. Specific identifying information for each sample location is provided in Attachment A.

d. Results were based upon the average net response of three elements in a TLD. (Thermoluminescent Dosimeter).

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(Page 1 of 1)

DEVIATIONS /MISSING DATA A) Pathway: Direct Radiation Location: W-1 -located On site north side of Discharge Canal Dates: 19-Mar-2019 Deviation: TLD was lost Description of Problem: TLD was lost due to a utility pole but was replaced Corrective action AR# 02314352 B) Pathway: Radioiodine and Particulate Location: T Siren pole 27, intersection of SW 112th Ave and SW 304th St.

Dates: 02-Feb-2019 Deviation: Gas flow meter failed but was replaced Description of Problem: Flow meter failed but was replaced Corrective action AR# 02314352 C) Pathway: Radioiodine and Particulate Location: T Entrance to Homestead Bayfront Park Dates: 02-Jan-2019 Deviation: Gas flow meter failed but was replaced Description of Problem: Flow meter failed but was replaced Corrective action AR# 02314352 D) Pathway: Radioiodine and Particulate Location: T SW corner parking lot at Black Point Marina Dates: 15-Aug-2019 Deviation: Power loss Description of Problem: Power was lost at air monitor T56 Corrective action AR 02324643 E) Pathway: Direct Radiation Location: SSE-1 Dates: 25- Sep- 2019 Deviation: Abnormal reading Description of SSE located onsite southeast side of the cooling canals*Element 3 Problem: of TLD#240 read unusually high; 20mR.

Corrective action AR 02332880 Page 18 of 100

(Page 2 of 2)

DEVIATIONS /MISSING DATA F) Pathway: Ingestion Location: T-99 Dates: 25- Feb- 2019 Deviation: Goat milk sample not collected Description of Problem: Goat milk sample unavailable for all quarters Corrective action AR 02344304 G) Pathway: Direct Radiation Location: T-56 SW corner parking lot at Black Point Marina Dates: 12- Aug- 2019 Deviation: Power loss Description of Problem: Power was lost at air monitor T56 Corrective action AR 02324643 H) Pathway: Direct Radiation Location: T-56 SW corner parking lot at Black Point Marina Dates: 6- Sep- 2019 Deviation: Power loss Description of Problem: Power was lost at air monitor T56 Corrective action AR 02328313 Page 19 of 100

TURKEY POINT 2019 ANNUAL LAND-USE CENSUS

SUMMARY

The annual land-use census identifies the nearest residences, vegetable gardens, and potential milk-producing animals within a five-mile radius from the Turkey Point nuclear plant.

The range (miles) and the bearing (degrees) from the plant are summarized for each receptor type in the table below.

(A) - Only gardens with an estimated total area of 500 square feet, or more, and producing green leafy vegetables are considered.

• - No suitable sites were located within a five-mile range.

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TURKEY POINT 2019 ANNUAL LAND-USE CENSUS

SUMMARY

The annual land-use census identifies the nearest residences and/or businesses, vegetable gardens, and potential milk-producing animals within a five-mile radius from the Turkey Point nuclear plant. The range (miles) and the bearing (degrees) from the plant are summarized for each receptor type in the table below.

SECTOR NEAREST NEAREST NEAREST RESIDENCE/BUSINESS GARDEN (A) MILK ANIMAL N 1.9 mi @ 349° *

• 1.98 mi @ 349° 2.0 mi @ 354° NNE * *

• NE * *

• ENE * *

• E * *

• ESE * *

• SE * *

• SSE * *

• S * *

• SSW * *

• SW * *

• WSW * *

• W * *

• WNW 1.7 mi @ 302° 4.5 mi @ 303°

• 3.7 mi @ 302° 6.0 mi @ 295° NW 3.6 mi @ 304° *

• 3.7 mi @ 311° 3.8 mi @ 316° 3.9 mi @ 314° NNW 4.4 mi @ 333° 4.7 mi @ 328°

• 4.5 mi @ 326° 4.7 mi @ 328° 4.9 mi @ 336° (A) - Only gardens with an estimated total area of 500 square feet, or more, and producing green leafy vegetables are considered.

• - No suitable sites were located within a five-mile range.

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TURKEY POINT RESIDENCE SURVEY RESULTS July 2019 Range Sector Bearing Nearest Residence/Business Location N (A) 1.9 miles This is the Homestead Bayfront Park complex. Contact is Jim 349° Wyath. Office hours are 8:30 to 4:30, 7 days a week. Some occasional overnight recreational occupancy (up to 4 nights) on boats at the marina. Approximately 25 workers, 7 days a week, hours and number of varies. Summer weekends can see 400+ visitors. There is always someone here 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with more workers in the summer than the rest of the year (February thru September have the highest peak of workers). LaPlaya restaurant is open at the park with 6 to 8 employees weekdays from 11am to 8:30pm. Weekends open till 10:00 and may have up to 12 employees.

N25° 27.683 W80° 20.200.

N (B) 1.98 miles South Glade Outfitters. Located on opposite side of building from 349° office of Homestead Bayfront Park. Manager is Robert and have 2 employees. Hours are M - F 7 am to 5 pm. Sat - Sun 7 am - 6 pm.

N25° 27.767 W80° 20.206.

N (C) 2.0 miles Biscayne National Park at Convoy Point. Contact is Astrid Rybeck.

354° They work 7 days a week from 7:00 am to 5:30 pm and currently have about 40 employees with a large number of volunteers. Up to four at a time may be living in a 2-story building onsite along with full-time park rangers. N25° 27.817 W80° 20.067.

NNE No residences were located within a five-mile range.

NE No residences were located within a five-mile range.

ENE No residences were located within a five-mile range.

E No residences were located within a five-mile range.

ESE No residences were located within a five-mile range.

SE No residences were located within a five-mile range.

SSE No residences were located within a five-mile range.

S No residences were located within a five-mile range.

SSW No residences were located within a five-mile range.

SW No residences were located within a five-mile range.

WSW No residences were located within a five-mile range.

W No residences were located within a five-mile range.

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TURKEY POINT RESIDENCE SURVEY RESULTS July 2019 (cont.)

Range Sector Bearing Nearest Residence/Business Location WNW (A) 1.7 miles FP&L daycare center and shooting range near the entrance to the 302° Turkey Point Plant. Contact is Angela Gill, Director. There are 11 employees with 60 children currently enrolled, ages 6 months to 5 yrs. The center is open from 6am to 6pm Monday thru Friday. The number of people and times at the shooting range varies.

N25° 26.817 W80° 21.217.

WNW (B) 3.7 miles Two people (a couple) live at 11790 Canal Drive on the south side 302° of Canal Drive (SW 328 St) west of SW 117th Ave (no gardens).

Next door, to the east, is a makeshift produce stand which sells coconuts, limes, melons, sugar cane, ginger root and ornamental plants. Is not associated with the house next door. Up to two people may be working there during normal hours.

N25° 27.767 W80° 22.867.

NW (A) 3.6 miles The Waste Management Homestead Landfill is located north of 304° Canal Drive (SW 328th St) and east of SW 117th Ave. There are 8 full time workers onsite Monday thru Friday usually from 7 am to 5:00 pm and Saturdays from 7 am to 12 pm.

N25° 27.833 W80° 22.767.

NW (B) 3.7 miles 11000 SW 320th St. Per property records, this house is on land 311° zoned agriculture and the owners live in Texas. Unable to verify if anyone lives there because the gate is locked and the residence is too far from the road to see anything. N25° 28.217 W80° 22.567.

NW (C) 3.8 miles High Hope Nursery at 11400 SW 316th St. Contact is George 316° Sprinkle, General Manager. This nursery currently has 30 employees. Hours of operations are 7am to 5pm Monday thru Friday, with some work on Saturdays until noon. A couple lives here that also provide security. N25° 28.441 W80° 22.430.

NW (D) 3.9 miles Snapper Creek Nursery at 11600 SW 316th Street. 14 workers that 314° work Monday thru Friday 7 am to 5 pm. Contact is Elmer.

Security is provided by another person who lives onsite.

N25° 28.444 W80° 22.560.

NNW (A) 4.4 miles 29800 SW 107th Ave. Per property records, this is a small one 333° bedroom residence on land zoned as mixed use agricultural. Gate locked but appears lived in. N25° 29.450 W80° 21.817.

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Range Sector Bearing Nearest Residence/Business Location NNW (B) 4.5 miles Accessible from entrance to SFM Tree Farm. No property 326° address. No residence per worker onsite.

N25° 29.372 W80° 22.292.

NNW (C) 4.7 miles SFM Tree Farm. Entrance at SW 107th Ave & SW 296th St. Four 328° people work on the property Mon-Fri 6:30-5:30. Contact is Mario.

Owner lives off property in Miami. N25° 29.564 W80° 22.264.

NNW (D) 4.9 miles Oceanus Seafood, LLC. Fish farm at 29055 SW 107th Ave 336° Homestead. Business appears to be closed down.

N25° 29.920 W80° 21.808.

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TURKEY POINT GARDEN SURVEY RESULTS July 2019 Range Nearest Garden Location (with estimated total area of 500 Sector Bearing square feet, or more, and producing green leafy vegetables).

N No suitable gardens were located within a five-mile range.

NNE No suitable gardens were located within a five-mile range.

NE No suitable gardens were located within a five-mile range.

ENE No suitable gardens were located within a five-mile range.

E No suitable gardens were located within a five-mile range.

ESE No suitable gardens were located within a five-mile range.

SE No suitable gardens were located within a five-mile range.

SSE No suitable gardens were located within a five-mile range.

S No suitable gardens were located within a five-mile range.

SSW No suitable gardens were located within a five-mile range.

SW No suitable gardens were located within a five-mile range.

WSW No suitable gardens were located within a five-mile range.

W No suitable gardens were located within a five-mile range.

Page 25 of 100

TURKEY POINT GARDEN SURVEY RESULTS July 2019 (cont.)

Range Nearest Garden Location (with estimated total area of 500 Sector Bearing square feet, or more, and producing green leafy vegetables).

WNW (A) 4.5 miles Thai Farms. Guava (mostly) and Dragon Fruit being grown at 303° present. Small farm run by an Asian family south of Mowry Drive (SW 320th St) and about 0.6 miles west of Allapattah Rd (SW 117th Ave). N25° 28.217 W80° 23.467.

WNW (B) 6.0 miles Farm Share, Inc at 14125 SW 320th St, where farmers donate 295° locally grown produce to be given to charitable organizations.

Produce donations usually start in November and run through April. About 20 workers present from 8 am to 4:30 pm Monday thru Friday. The produce donated is usually tomatoes, squash, green beans, okra, corn, potatoes, watermelon and zucchini. The contact is C.O.O. Stephen Shelley. N25° 28.255 W80° 25.111.

NW No suitable gardens were located within a five-mile range.

NNW 4.7 miles SFM Tree Farm. Entrance at SW 107th Ave & SW 296th St.

328° Noticed bananas, plantain tress, coconuts and mangoes growing in various areas on the farm. Owner lives off property in Miami.

N25° 29.564 W80° 22.264.

Note: At the time of our survey, many fields in the area surveyed were bare soil or cover crops.

Other than the sites already described above, the only non-ornamental crops known to have been grown in the survey area were: bananas, beans, corn, guava, malanga, papaya, eggplant, sorghum, squash, sugar cane, tambis, okra and melon.

Page 26 of 100

TURKEY POINT MILK ANIMAL SURVEY RESULTS July 2019 Sector Nearest Milk Animals (cows or goats).

N No potential milk animals were located within five miles.

NNE No potential milk animals were located within five miles.

NE No potential milk animals were located within five miles.

ENE No potential milk animals were located within five miles.

E No potential milk animals were located within five miles.

ESE No potential milk animals were located within five miles.

SE No potential milk animals were located within five miles.

SSE No potential milk animals were located within five miles.

S No potential milk animals were located within five miles.

SSW No potential milk animals were located within five miles.

SW No potential milk animals were located within five miles.

WSW No potential milk animals were located within five miles.

W No potential milk animals were located within five miles.

WNW No potential milk animals were located within five miles.

NW No potential milk animals were located within five miles.

NNW No potential milk animals were located within five miles.

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ATTACHMENT A KEY TO SAMPLE LOCATIONS Page 28 of 100

ATTACHMENT A NEAR SITE SAMPLING LOCATIONS (Page 1 of 6)

Page 29 of 100

ATTACHMENT A DISTANT REMP SAMPLING LOCATIONS (Page 2 of 6)

Page 30 of 100

ATTACHMENT A (Page 3 of 6)

PATHWAY: DIRECT RADIATION SAMPLES COLLECTED: TLD SAMPLE COLLECTION FREQUENCY: QUARTERLY Location (a)

Name Description N-2 Convey Point, Parking Area N-7 Black Point Marina Parking Lot N-10 Old Cutler Rd. approx. 196th Street NNW-2 East End North Canal Road NNW-10 Bailes Road & U.S. #1 NW-1 Turkey Point Entrance Road NW-5 Mowry Drive & 117th Avenue NW-10 Newton Road, North of Coconut Palm Drive WNW-2 Satellite School WNW-10 Homestead Middle School W-1 On-Site, North Side of Discharge Canal W-5 Palm Drive & Tallahassee Road W-9 Card Sound Road, 0.6 mile from U.S. #1 WSW-8 Card Sound Road, 3.4 miles from U.S. #1 SW-1 On-Site near Land Utilization Offices SW-8 Card Sound Road, 5 miles from U.S. #1 SSW-5 On-Site, Southwest Corner of Cooling Canals SSW-10 Card Sound Road, west side of Toll Plaza S-5 On-Site, South East Corner of Cooling Canals S-10 Card Sound Road at Steamboat Creek SSE-1 Turtle Point SSE-10 Ocean Reef Control NNE-22 Natoma Substation, 2475 SW 16 Ct.

a The location name is the direction sector - approximate distance (miles)

Page 31 of 100

ATTACHMENT A (Page 4 of 6)

PATHWAY: AIRBORNE SAMPLES COLLECTED: RADIOIODINE AND PARTICULATES SAMPLE COLLECTION FREQUENCY: WEEKLY Location Direction Approximate Description Name Sector Distance (miles)

T-51 NNW 2 Entrance Area to Biscayne National Park T-57 NW 4 Siren pole 27, intersection of SW 112th Ave and SW 304th St.

T-58 NW 1 Turkey Point Entrance Road T-72 WSW <1 Just before entrance to Land Utilization's access gate.

T-41 WNW 1.6 Palm Dr. West of FPL Satellite School near the site boundary Control:

T-64 NNE 22 Natoma Substation , 2475 SW 16 Ct.

Page 32 of 100

ATTACHMENT A (Page 5 of 6)

PATHWAY: WATERBORNE SAMPLES COLLECTED: SURFACE WATER (OCEAN)

SAMPLE COLLECTION FREQUENCY: MONTHLY Location Direction Approximate Description Name Sector Distance (miles)

T-42 ENE <1 Biscayne Bay at Turkey Point T-81 S 6 Card Sound, near Mouth of Old Discharge Canal Control:

T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park SAMPLES COLLECTED: SHORELINE SEDIMENT SAMPLE COLLECTION FREQUENCY: SEMI-ANNUALLY Location Direction Approximate Description Name Sector Distance (miles)

T-42 ENE <1 Biscayne Bay at Turkey Point T-81 S 6 Card Sound, near Mouth of Old Discharge Canal Control:

T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park Page 33 of 100

ATTACHMENT A (Page 6 of 6)

PATHWAY: INGESTION SAMPLES COLLECTED: CRUSTACEA AND FISH SAMPLE COLLECTION FREQUENCY: SEMI-ANNUALLY Location Direction Approximate Description Name Sector Distance (miles)

T-81 S 6 Card Sound Vicinity of Turkey Point Facility Control:

T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park SAMPLES COLLECTED: BROAD LEAF VEGETATION SAMPLE COLLECTION FREQUENCY: MONTHLY Location Direction Approximate Description Name Sector Distance (miles)

T-40 W 3 South of Palm Dr. on S.W. 117th Street Extension T-41 WNW 2 Palm Dr. West of FPL Satellite School near the site boundary Control:

T-67 N, NNE 13-18 Near Biscayne Bay, Vicinity of Cutler Plant, North to Matheson Hammock Park Page 34 of 100

ATTACHMENT B RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY'S TURKEY POINT SITE 2019 First Quarter, 2019 Second Quarter, 2019 Third Quarter, 2019 Fourth Quarter, 2019 Page 35 of 100

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY TURKEY POINT SITE FIRST QUARTER 2019 BUREAU OF RADIATION CONTROL Page 36 of 100

TURKEY POINT SITE Offsite Dose Calculation Manual Sampling First Quarter, 2019 Number of Number of Sample Type Collection Frequency Sample Locations Samples

1. Direct Radiation Quarterly 23 44

2. Airborne 2.a. Air Iodines Weekly 6 78 2.b. Air Particulates Weekly 6 78

3. Waterborne 3.a. Surface Water Monthly 3 9 3.b. Shoreline Sediment Semiannually 3 3

4. Ingestion 4.a. Fish and Invertebrates 4.a.1. Crustacea Semiannually 2 1 4.a.2. Fish Semiannually 2 2 4.b. Broadleaf Vegetation Monthly 3 9 Total: 224 NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.

Measurement results that are not significantly above background are reported as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 95% confidence) for the true activity in the sample.

The marine fauna listed in this report were collected in part, under Florida FWC SAL030.

Page 37 of 100

1. DIRECT RADIATION - DUAL DEPLOYED TLDs - (µR/hr)

Sample Deployment 11-Dec-18 Site Collection 19-Mar-19 Old New N-2 4.87 +/- 0.57 3.96 +/- 0.31 N-7 3.33 +/- 0.34 3.37 +/- 0.07 N-10 3.67 +/- 0.07 3.90 +/- 0.08 NNW-2 3.58 +/- 0.09 3.54 +/- 0.27 NNW-10 3.98 +/- 0.35 3.83 +/- 0.33 NW-1 4.04 +/- 0.05 4.26 +/- 0.13 NW-5 3.29 +/- 0.20 3.34 +/- 0.34 NW-10 4.43 +/- 0.43 4.62 +/- 0.37 WNW-2 3.46 +/- 0.16 3.65 +/- 0.25 WNW-10 4.23 +/- 0.28 4.28 +/- 0.37 W-1 (A)

W-5 3.87 +/- 0.19 3.88 +/- 0.29 W-9 3.39 +/- 0.29 3.25 +/- 0.13 WSW-8 3.54 +/- 0.10 3.59 +/- 0.32 SW-1 3.75 +/- 0.04 3.82 +/- 0.28 SW-8 3.06 +/- 0.23 2.85 +/- 0.33 SSW-5 3.34 +/- 0.22 3.10 +/- 0.16 SSW-10 3.38 +/- 0.20 3.67 +/- 0.46 S-5 3.03 +/- 0.12 3.00 +/- 0.07 S-10 3.65 +/- 0.50 3.64 +/- 0.23 SSE-1 2.85 +/- 0.22 2.94 +/- 0.46 SSE-10 3.43 +/- 0.44 3.27 +/- 0.25 NNE-22 4.10 +/- 0.16 3.99 +/- 0.20 (A) TLDs lost due to utility pole being replaced.

Page 38 of 100

2.a. IODINE-131 IN WEEKLY AIR CARTRIDGES - (pCi/m³)

Collection Date T41 T51 T57 T58 T64 T72 02-Jan-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 08-Jan-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 15-Jan-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 21-Jan-19 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 29-Jan-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 05-Feb-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 12-Feb-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 18-Feb-19 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 26-Feb-19 <0.02 <0.01 <0.01 <0.02 <0.02 <0.02 05-Mar-19 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 12-Mar-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 19-Mar-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 26-Mar-19 <0.02 <0.02 <0.03 <0.02 <0.02 <0.02 Page 39 of 100

2.b.1. AIR PARTICULATES - GROSS BETA - (pCi/m³)

Collection Date T41 T51 T57 T58 T64 T72 02-Jan-19 0.014 +/- 0.002 0.010 +/- 0.002 0.008 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.010 +/- 0.002 08-Jan-19 0.014 +/- 0.002 0.016 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 15-Jan-19 0.016 +/- 0.002 0.018 +/- 0.002 0.021 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002 0.012 +/- 0.002 21-Jan-19 0.016 +/- 0.002 0.018 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.002 0.022 +/- 0.003 0.017 +/- 0.002 29-Jan-19 0.014 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.010 +/- 0.002 0.007 +/- 0.002 05-Feb-19 0.014 +/- 0.002 0.009 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 12-Feb-19 0.014 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 18-Feb-19 0.010 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 26-Feb-19 0.010 +/- 0.002 0.011 +/- 0.002 0.011 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.008 +/- 0.002 05-Mar-19 0.005 +/- 0.002 0.007 +/- 0.002 0.006 +/- 0.002 0.007 +/- 0.002 0.006 +/- 0.002 0.004 +/- 0.002 12-Mar-19 0.013 +/- 0.002 0.015 +/- 0.002 0.017 +/- 0.002 0.014 +/- 0.002 0.017 +/- 0.002 0.010 +/- 0.002 19-Mar-19 0.014 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.016 +/- 0.002 0.013 +/- 0.002 26-Mar-19 0.019 +/- 0.002 0.015 +/- 0.002 0.021 +/- 0.003 0.019 +/- 0.002 0.018 +/- 0.002 0.019 +/- 0.002 Average: 0.013 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 0.012 +/- 0.001 2.b.2. AIR PARTICULATES - GAMMA ANALYSIS OF QUARTERLY COMPOSITES - (pCi/m³)

Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T41 0.1260 +/- 0.0086 <0.0131 <0.0012 <0.0009 <0.0151 T51 0.1239 +/- 0.0086 <0.0209 <0.0011 <0.0008 <0.0313 T57 0.1196 +/- 0.0081 <0.0160 <0.0011 <0.0009 0.0073 +/- 0.0032 T58 0.1268 +/- 0.0092 <0.0193 <0.0009 <0.0008 <0.0334 T64 0.1218 +/- 0.0085 <0.0156 <0.0012 <0.0009 <0.0156 T72 0.1227 +/- 0.0087 <0.0213 <0.0012 <0.0010 <0.0316 Page 40 of 100

3.a. SURFACE WATER - (pCi/L)

Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)

T42 10-Jan-19 <146 399 +/- 24 <3 <4 <7 <4 <8 <6 <5 <3 <3 <5 21-Feb-19 <142 301 +/- 24 <3 <4 <8 <3 <7 <6 <7 <3 <4 <5 21-Mar-19 <141 337 +/- 25 <3 <3 <8 <3 <7 <6 <5 <3 <3 <5 T67 09-Jan-19 <146 128 +/- 17 <3 <4 <7 <3 <7 <7 <6 <3 <4 <6 21-Feb-19 <142 267 +/- 40 <6 <6 <13 <7 <13 <11 <12 <6 <7 <10 20-Mar-19 <141 245 +/- 39 <6 <6 <12 <5 <12 <9 <9 <5 <7 <10 T81 10-Jan-19 <146 502 +/- 45 <5 <6 <12 <6 <14 <11 <7 <6 <6 <10 21-Feb-19 <142 277 +/- 39 <6 <7 <14 <7 <13 <10 <10 <6 <7 <9 21-Mar-19 <141 331 +/- 45 <5 <6 <12 <7 <15 <12 <8 <5 <7 <9 (A) - These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) - These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

Page 41 of 100

3.b. SHORELINE SEDIMENT - (pCi/kg, dry weight)

Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Pb-210 Ra-226 Th-232 U-235 U-238 T42 10-Jan-19 95 +/- 30 <136 <11 <10 <10 <10 <1050 1077 +/- 109 <46 68 +/- 7 469 +/- 52 T67 09-Jan-19 <80 172 +/- 41 <8 <8 <7 <9 <635 390 +/- 72 <45 25 +/- 5 251 +/- 35 T81 10-Jan-19 <132 <190 <16 <12 <12 <14 <1076 1427 +/- 135 <62 90 +/- 8 720 +/- 65 4.a.1. CRUSTACEA - Blue Crab - (pCi/kg, wet weight)

Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 This sample to be collected.

T81 14-Jan-19 1163 +/- 163 <27 <27 <72 <29 <53 <21 <27 <445 <117 4.a.2. FISH - Mixed Species - (pCi/kg, wet weight)

Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 09-Jan-19 1474 +/- 202 <27 <28 <71 <27 <60 <27 <31 <559 <105 T81 16-Jan-19 2596 +/- 170 <22 <22 <46 <21 <51 <23 <25 <405 <84 Page 42 of 100

4.b. BROADLEAF VEGETATION - Brazilian Pepper - (pCi/kg, wet weight)

Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 Pb-210 Pb-212 Ra-226 Ra-228 T40 10-Jan-19 1180 +/- 77 4107 +/- 208 <17 <13 <23 <1142 <32 <344 <75 21-Feb-19 1675 +/- 79 4467 +/- 198 <24 <11 20 +/- 4 <905 <22 <315 <54 21-Mar-19 954 +/- 67 4655 +/- 222 <20 <13 <18 <1053 <26 <313 <68 T41 10-Jan-19 1100 +/- 49 4862 +/- 178 <10 <9 <12 <381 <19 <221 <42 21-Feb-19 1506 +/- 58 5213 +/- 182 <16 <7 <10 358 +/- 85 <17 <197 <37 21-Mar-19 1532 +/- 76 3573 +/- 181 <19 <13 23 +/- 5 <971 30 +/- 7 <334 <69 T67 09-Jan-19 753 +/- 57 4333 +/- 204 <15 <12 <13 <1023 14 +/- 7 339 +/- 97 <72 21-Feb-19 1340 +/- 77 6196 +/- 260 <25 <13 <17 <1021 <27 <300 <63 20-Mar-19 336 +/- 28 4577 +/- 169 <15 <8 10 +/- 2 <357 <17 <182 <37 Page 43 of 100

TURKEY POINT SITE Supplemental Sampling First Quarter, 2019 Number of Number of Sample Type Collection Frequency Sample Locations Samples

1. Direct Radiation Quarterly 9 18

2. Airborne 2.a. Air Iodines Weekly 2 26 2.b. Air Particulates Weekly 2 26

3. Waterborne 3.a. Surface Water Monthly 4 12 3.b. Shoreline Sediment Semiannually 9 9

4. Ingestion 4.a. Milk Semiannually 1 0 4.b. Food Crops At Harvest 3 2 Total: 93 NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term.

Measurement results that are not significantly above background are reported as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 95% confidence) for the true activity in the sample.

Page 44 of 100

1. DIRECT RADIATION - DUAL DEPLOYED TLDs - (µR/hr)

Sample Deployment 11-Dec-18 Collection 19-Mar-19 Site Old New NNW-6 3.50 +/- 0.45 3.55 +/- 0.26 NW-7 4.04 +/- 0.38 4.06 +/- 0.14 NW-8 4.04 +/- 0.46 3.96 +/- 0.06 WNW-3 3.53 +/- 0.24 3.90 +/- 0.19 WNW-6 3.59 +/- 0.29 3.54 +/- 0.13 W-8 3.62 +/- 0.13 3.90 +/- 0.33 ENE-1 2.96 +/- 0.20 3.00 +/- 0.27 T72 3.60 +/- 0.14 3.65 +/- 0.52 PTN-1 3.62 +/- 0.18 3.49 +/- 0.27 2.a. IODINE-131 IN WEEKLY AIR CARTRIDGES - (pCi/m³)

Collection Date T52 T56 02-Jan-19 <0.02 <0.02 08-Jan-19 <0.02 <0.02 15-Jan-19 <0.02 <0.02 21-Jan-19 <0.03 <0.03 29-Jan-19 <0.02 <0.02 05-Feb-19 <0.02 <0.02 12-Feb-19 <0.02 <0.02 18-Feb-19 <0.03 <0.03 26-Feb-19 <0.02 <0.02 05-Mar-19 <0.01 <0.01 12-Mar-19 <0.02 <0.02 19-Mar-19 <0.02 <0.02 26-Mar-19 <0.02 <0.03 Page 45 of 100

2.b.1. AIR PARTICULATES - GROSS BETA - (pCi/m³)

Collection Date T52 T56 02-Jan-19 0.009 +/- 0.002 0.013 +/- 0.002 08-Jan-19 0.014 +/- 0.002 0.017 +/- 0.002 15-Jan-19 <0.007 0.020 +/- 0.002 21-Jan-19 0.021 +/- 0.003 0.015 +/- 0.002 29-Jan-19 0.006 +/- 0.001 0.010 +/- 0.002 05-Feb-19 0.011 +/- 0.002 0.014 +/- 0.002 12-Feb-19 0.014 +/- 0.002 0.011 +/- 0.002 18-Feb-19 0.009 +/- 0.002 0.014 +/- 0.002 26-Feb-19 0.009 +/- 0.002 0.009 +/- 0.002 05-Mar-19 0.010 +/- 0.002 0.007 +/- 0.002 12-Mar-19 0.012 +/- 0.002 0.015 +/- 0.002 19-Mar-19 0.018 +/- 0.002 0.020 +/- 0.002 26-Mar-19 0.021 +/- 0.002 0.024 +/- 0.003 Average: <0.012 0.015 +/- 0.001 2.b.2. AIR PARTICULATES GAMMA ANALYSIS OF QUARTERLY COMPOSITES - (pCi/m³)

Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T52 0.1148 +/- 0.0080 <0.0121 <0.0013 <0.0011 <0.0142 T56 0.1277 +/- 0.0095 <0.0198 <0.0010 <0.0010 <0.0332 Page 46 of 100

3.a. SURFACE WATER - (pCi/L)

Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)

T08 10-Jan-19 10701 +/- 149 514 +/- 31 <4 <3 <9 <4 <8 <7 <6 <4 <4 <5 21-Feb-19 7634 +/- 128 595 +/- 33 <4 <4 <7 <4 <9 <7 <6 <4 <4 <6 21-Mar-19 6985 +/- 122 509 +/- 31 <4 <4 <8 <3 <8 <6 <5 <3 <4 <5 T75 10-Jan-19 <146 <93 <5 <6 <11 <6 <14 <9 <8 <5 <6 <9 18-Feb-19 <144 <97 <6 <7 <11 <6 <11 <10 <13 <5 <6 <14 21-Mar-19 <141 <40 <3 <3 <8 <3 <6 <6 <5 <3 <3 <6 T84 10-Jan-19 11854 +/- 156 513 +/- 32 <4 <4 <8 <4 <8 <7 <5 <4 <4 <5 21-Feb-19 7262 +/- 125 559 +/- 33 <3 <3 <8 <4 <7 <7 <6 <3 <3 <5 21-Mar-19 7290 +/- 125 492 +/- 31 <3 <3 <7 <4 <8 <6 <5 <4 <4 <6 T97 10-Jan-19 11742 +/- 156 649 +/- 49 <6 <6 <14 <6 <14 <11 <9 <6 <7 <9 21-Feb-19 7329 +/- 125 601 +/- 35 <3 <4 <7 <4 <8 <5 <4 <3 <3 <10 21-Mar-19 6910 +/- 122 555 +/- 33 <3 <3 <7 <4 <9 <6 <6 <3 <4 <6 (A) - These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) - These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

Page 47 of 100

3.b. SHORELINE SEDIMENT - (pCi/kg, dry weight)

Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Pb-210 Ra-226 Th-232 U-235 U-238 T01 10-Jan-19 118 +/- 36 259 +/- 52 <10 <12 <10 <12 <1028 1294 +/- 132 44 +/- 12 81 +/- 8 566 +/- 40 T02 10-Jan-19 70 +/- 25 657 +/- 51 <13 <13 <12 13 +/- 2 1276 +/- 102 <286 57 +/- 8 58 +/- 19 332 +/- 25 T03 10-Jan-19 212 +/- 33 967 +/- 63 <16 10 +/- 2 <14 39 +/- 3 1466 +/- 103 735 +/- 340 89 +/- 8 81 +/- 20 396 +/- 26 T04 10-Jan-19 457 +/- 55 362 +/- 59 11 +/- 3 <14 <11 <14 1945 +/- 554 1363 +/- 120 <62 86 +/- 7 486 +/- 59 T07 10-Jan-19 61 +/- 24 635 +/- 59 <14 <11 <12 42 +/- 4 545 +/- 108 984 +/- 94 <53 62 +/- 6 113 +/- 21 T08 10-Jan-19 <131 1095 +/- 68 <11 <12 <12 18 +/- 3 533 +/- 187 1231 +/- 105 87 +/- 9 78 +/- 7 <187 T10 10-Jan-19 <117 820 +/- 62 <15 <11 <12 9+/-2 550 +/- 93 880 +/- 94 <56 <16 <174 T84* 10-Jan-19 <131 539 +/- 62 <14 <13 <11 <13 <1147 1738 +/- 127 60 +/- 12 109 +/- 8 493 +/- 40 T85* 10-Jan-19 322 +/- 39 600 +/- 52 <17 53 +/- 4 <15 11 +/- 2 2657 +/- 220 1864 +/- 240 93 +/- 11 46 +/- 13 506 +/- 33

• Note that site T84 is the same location as site T05, and site T85 is the same location as site T06.

Page 48 of 100

4.a. GOATS MILK - (pCi/L)

Sample Collection Ba-140 Site Date K-40 I-131 Cs-134 Cs-137 La-140 (A)

T99 This sample to be collected.

(A) - This tabulated LLD value is for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity.

4.b. FOOD CROPS - Corn - (pCi/kg, wet weight)

Sample Collection Site Date Be-7 K-40 Mn-54 Co-58 Co-60 Ag-110m I-131 Cs-134 Cs-137 Ra-226 Ra-228 T43 21-Jan-19 <59 2243 +/- 97 <5 <7 <7 <5 <12 <6 <6 <136 <27 2394 +/-

T44 06-Feb-19 <34 105 <7 <7 <8 <7 <8 <7 <8 <164 <28 T45 This sample to be collected.

Page 49 of 100

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY TURKEY POINT SITE SECOND QUARTER 2019 BUREAU OF RADIATION CONTROL Page 50 of 100

TURKEY POINT SITE Offsite Dose Calculation Manual Sampling Second Quarter, 2019 Number of Number of Sample Type Collection Frequency Sample Locations Samples

1. Direct Radiation Quarterly 23 46

2. Airborne 2.a. Air Iodines Weekly 6 78 2.b. Air Particulates Weekly 6 78

3. Waterborne 3.a. Surface Water Monthly 3 9 3.b. Shoreline Sediment Semiannually 3 0

4. Ingestion 4.a. Fish and Invertebrates 4.a.1. Crustacea Semiannually 2 1 4.a.2. Fish Semiannually 2 0 4.b. Broadleaf Vegetation Monthly 3 9 Total: 221 NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term. Measurement results that are not significantly above background are reported as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 95% confidence) for the true activity in the sample.

The marine fauna listed in this report were collected in part, under Florida FWC SAL030.

Page 51 of 100

1. DIRECT RADIATION - DUAL DEPLOYED TLDs - (µR/hour)

Sample Deployment 19-Mar-19 Site Collection 12-Jun-19 Old New N-2 4.15 +/- 0.46 4.58 +/- 0.24 N-7 3.36 +/- 0.08 3.76 +/- 0.19 N-10 3.76 +/- 0.04 4.17 +/- 0.41 NNW-2 3.60 +/- 0.15 3.94 +/- 0.12 NNW-10 3.82 +/- 0.20 4.19 +/- 0.31 NW-1 4.22 +/- 0.13 4.47 +/- 0.32 NW-5 3.35 +/- 0.24 3.58 +/- 0.14 NW-10 4.44 +/- 0.21 4.80 +/- 0.25 WNW-2 3.57 +/- 0.25 3.91 +/- 0.08 WNW-10 4.03 +/- 0.24 4.37 +/- 0.18 W-1 3.96 +/- 0.06 4.35 +/- 0.46 W-5 3.55 +/- 0.15 3.76 +/- 0.38 W-9 3.32 +/- 0.41 3.61 +/- 0.07 WSW-8 3.45 +/- 0.19 3.97 +/- 0.23 SW-1 3.79 +/- 0.18 4.16 +/- 0.26 SW-8 2.85 +/- 0.19 3.10 +/- 0.30 SSW-5 3.15 +/- 0.22 3.33 +/- 0.13 SSW-10 4.42 +/- 0.69 3.79 +/- 0.23 S-5 3.09 +/- 0.31 3.18 +/- 0.32 S-10 3.48 +/- 0.17 3.72 +/- 0.18 SSE-1 2.95 +/- 0.34 3.19 +/- 0.43 SSE-10 3.14 +/- 0.02 3.49 +/- 0.20 NNE-22 3.75 +/- 0.11 4.26 +/- 0.16 Page 52 of 100

2.a. IODINE-131 IN WEEKLY AIR CARTRIDGES - (pCi/m³)

Collection Date T41 T51 T57 T58 T64 T72 02-Apr-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 08-Apr-19 <0.03 <0.03 <0.02 <0.03 <0.03 <0.03 16-Apr-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 23-Apr-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 01-May-19 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 07-May-19 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 14-May-19 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 21-May-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 29-May-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 05-Jun-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 11-Jun-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 19-Jun-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 25-Jun-19 <0.02 <0.03 <0.02 <0.02 <0.03 <0.02 Page 53 of 100

2.b. AIR PARTICULATES - GROSS BETA - (pCi/m³)

Collection Date T41 T51 T57 T58 T64 T72 02-Apr-19 0.012 +/- 0.002 0.011 +/- 0.002 0.014 +/- 0.002 0.011 +/- 0.002 0.015 +/- 0.002 0.009 +/- 0.002 08-Apr-19 0.013 +/- 0.002 0.014 +/- 0.002 0.013 +/- 0.002 0.014 +/- 0.002 0.009 +/- 0.002 0.013 +/- 0.002 16-Apr-19 0.010 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 0.012 +/- 0.002 0.007 +/- 0.001 0.010 +/- 0.002 23-Apr-19 0.013 +/- 0.002 0.018 +/- 0.002 0.010 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 0.014 +/- 0.002 01-May-19 0.016 +/- 0.002 0.010 +/- 0.002 0.007 +/- 0.002 0.014 +/- 0.002 0.009 +/- 0.002 0.015 +/- 0.002 07-May-19 0.008 +/- 0.002 0.012 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.007 +/- 0.002 0.010 +/- 0.002 14-May-19 0.012 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.010 +/- 0.002 21-May-19 <0.006 0.015 +/- 0.002 0.019 +/- 0.002 0.021 +/- 0.002 0.020 +/- 0.002 0.019 +/- 0.002 29-May-19 0.030 +/- 0.002 0.017 +/- 0.002 0.019 +/- 0.002 0.020 +/- 0.002 0.025 +/- 0.002 0.018 +/- 0.002 05-Jun-19 0.010 +/- 0.002 0.008 +/- 0.002 0.006 +/- 0.002 0.009 +/- 0.002 0.011 +/- 0.002 0.009 +/- 0.002 11-Jun-19 0.012 +/- 0.002 0.011 +/- 0.002 0.009 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.002 0.010 +/- 0.002 19-Jun-19 0.010 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.001 0.009 +/- 0.002 0.009 +/- 0.002 0.013 +/- 0.002 25-Jun-19 0.023 +/- 0.003 0.022 +/- 0.003 0.023 +/- 0.003 0.021 +/- 0.003 0.025 +/- 0.003 0.028 +/- 0.003 Average: <0.013 0.013 +/- 0.001 0.012 +/- 0.001 0.014 +/- 0.001 0.013 +/- 0.001 0.014 +/- 0.001 2.b. AIR PARTICULATES - GAMMA ANALYSIS OF QUARTERLY COMPOSITES - (pCi/m³)

Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T41 0.1420 +/- 0.0087 <0.0149 <0.0013 <0.0009 0.0108 +/- 0.0030 T51 0.1340 +/- 0.0092 <0.0193 <0.0010 <0.0008 0.0267 +/- 0.0079 T57 0.1320 +/- 0.0085 <0.0130 <0.0012 <0.0009 0.0097 +/- 0.0026 T58 0.1310 +/- 0.0093 <0.0237 <0.0012 <0.0010 0.0334 +/- 0.0086 T64 0.1240 +/- 0.0087 <0.0130 <0.0012 <0.0008 <0.0085 T72 0.1210 +/- 0.0098 <0.0193 <0.0011 <0.0009 <0.0294 Page 54 of 100

3.a. SURFACE WATER - (pCi/L)

Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)

T42 24-Apr-19 <143 384 +/- 27 <4 <4 <8 <3 <6 <6 <4 <3 <3 <7 15-May-19 <139 414 +/- 28 <3 <3 <8 <4 <7 <6 <5 <3 <4 <5 12-Jun-19 <135 417 +/- 46 <6 <5 <12 <6 <13 <10 <10 <5 <7 <11 T67 22-Apr-19 <143 277 +/- 23 <3 <4 <6 <3 <7 <6 <4 <3 <4 <6 13-May-19 <139 101 +/- 33 <5 <6 <13 <6 <14 <11 <11 <5 <6 <8 11-Jun-19 <135 177 +/- 18 <3 <3 <7 <4 <7 <6 <6 <3 <4 <5 T81 24-Apr-19 <143 387 +/- 45 <5 <6 <14 <7 <13 <10 <9 <5 <6 <11 16-May-19 <139 440 +/- 46 <6 <6 <12 <7 <14 <11 <9 <5 <6 <7 12-Jun-19 <135 425 +/- 46 <6 <6 <14 <6 <14 <9 <10 <5 <6 <8 (A) - These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) - These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

Page 55 of 100

3.b. SHORELINE SEDIMENT - (pCi/kg, dry weight)

Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Pb-210 Ra-226 Th-232 These samples were previously collected.

4.a.1. CRUSTACEA - Blue Crabs - (pCi/kg, wet weight)

Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 24-Apr-19 1990 +/- 200 <27 <27 <48 <30 <60 <23 <27 <476 <105 T81 This sample previously collected.

4.a.2. FISH - (pCi/kg, wet weight)

Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 This sample previously collected.

T81 This sample previously collected.

Page 56 of 100

4.b. BROADLEAF VEGETATION - Brazilian Pepper - (pCi/kg, wet weight)

Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 Pb-210 Pb-212 Ra-226 Ra-228 T40 22-Apr-19 1070 +/- 69 3850 +/- 198 <16 <13 <18 <978 <25 <311 <62 15-May-19 1350 +/- 54 4390 +/- 162 <13 <8 13 +/- 2 381 +/- 82 <16 <194 <32 11-Jun-19 1550 +/- 85 3880 +/- 203 <27 <13 26 +/- 5 1050 +/- 353 <24 <307 <64 T41 22-Apr-19 1230 +/- 53 5740 +/- 199 <12 <9 7+/-2 <375 <18 <220 <38 15-May-19 999 +/- 63 4680 +/- 218 <21 <10 <18 <1000 <24 <301 <68 11-Jun-19 465 +/- 34 5140 +/- 186 <16 <8 7+/-2 <358 <17 <195 <36 T67 22-Apr-19 1210 +/- 49 3720 +/- 140 <10 <7 17 +/- 2 373 +/- 72 <15 <179 <30 15-May-19 1090 +/- 49 3830 +/- 146 <15 <8 <10 <350 <16 <175 <34 11-Jun-19 940 +/- 46 2980 +/- 125 <14 <7 14 +/- 2 <351 <16 <184 <38 Page 57 of 100

TURKEY POINT SITE Supplemental Sampling Second Quarter, 2019 Number of Number of Sample Type Collection Frequency Sample Locations Samples

1. Direct Radiation Quarterly 9 18

2. Airborne 2.a. Air Iodines Weekly 2 26 2.b. Air Particulates Weekly 2 26

3. Waterborne 3.a. Surface Water Monthly 4 12 3.b. Shoreline Sediment Semiannually 9 0

4. Ingestion 4.a. Milk Semiannually 1 0 4.b. Food Crops At Harvest 3 1 Total: 83 NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term. Measurement results that are not significantly above background are reported as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 95% confidence) for the true activity in the sample.

Page 58 of 100

1. DIRECT RADIATION - DUAL DEPLOYED TLDs - (µR/hour)

Sample Deployment 19-Mar-19 Site Collection 12-June-19 Old New NNW-6 3.50 +/- 0.37 3.95 +/- 0.50 NW-7 4.19 +/- 0.18 4.36 +/- 0.25 NW-8 3.73 +/- 0.34 4.27 +/- 0.38 WNW-3 3.40 +/- 0.21 3.87 +/- 0.10 WNW-6 3.32 +/- 0.19 4.01 +/- 0.25 W-8 3.72 +/- 0.31 4.19 +/- 0.28 ENE-1 2.79 +/- 0.26 3.31 +/- 0.05 T72 3.53 +/- 0.13 3.78 +/- 0.26 PTN-1 3.43 +/- 0.34 3.73 +/- 0.28 2.a. IODINE-131 IN WEEKLY AIR CARTRIDGES - (pCi/m³)

Collection Date T52 T56 02-Apr-19 <0.02 <0.02 08-Apr-19 <0.03 <0.03 16-Apr-19 <0.02 <0.02 23-Apr-19 <0.02 <0.02 01-May-19 <0.01 <0.01 07-May-19 <0.01 <0.01 14-May-19 <0.01 <0.01 21-May-19 <0.02 <0.02 29-May-19 <0.02 <0.02 05-Jun-19 <0.02 <0.02 11-Jun-19 <0.02 <0.02 19-Jun-19 <0.02 <0.02 25-Jun-19 <0.02 <0.02 Page 59 of 100

2.b. AIR PARTICULATES - GROSS BETA - (pCi/m³)

Collection Date T52 T56 02-Apr-19 0.009 +/- 0.002 0.013 +/- 0.002 08-Apr-19 0.016 +/- 0.002 0.015 +/- 0.002 16-Apr-19 0.010 +/- 0.002 0.015 +/- 0.002 23-Apr-19 0.015 +/- 0.002 0.017 +/- 0.002 01-May-19 0.015 +/- 0.002 0.014 +/- 0.002 07-May-19 0.010 +/- 0.002 0.010 +/- 0.002 14-May-19 0.012 +/- 0.002 0.011 +/- 0.002 21-May-19 0.018 +/- 0.002 0.020 +/- 0.002 29-May-19 0.023 +/- 0.002 0.024 +/- 0.002 05-Jun-19 0.007 +/- 0.002 0.008 +/- 0.002 11-Jun-19 0.013 +/- 0.002 0.008 +/- 0.002 19-Jun-19 0.012 +/- 0.002 0.007 +/- 0.001 25-Jun-19 0.024 +/- 0.003 0.027 +/- 0.003 Average: 0.014 +/- 0.001 0.014 +/- 0.001 2.b. AIR PARTICULATES - GAMMA ANALYSIS OF QUARTERLY COMPOSITES - (pCi/m³)

Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T52 0.1350 +/- 0.0089 <0.0147 <0.0013 <0.0010 <0.0147 T56 0.1240 +/- 0.0090 <0.0190 <0.0010 <0.0009 <0.0313 Page 60 of 100

3.a. SURFACE WATER - (pCi/L)

Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)

T08 24-Apr-19 11652 +/- 154 611 +/- 35 <4 <4 <7 <4 <7 <7 <4 <4 <4 <7 16-May-19 7840 +/- 128 719 +/- 40 <4 <4 <9 <4 <10 <7 <6 <4 <4 <5 12-Jun-19 6265 +/- 116 712 +/- 37 <3 <4 <7 <4 <9 <6 <6 <3 <4 <5 T75 24-Apr-19 <143 <93 <6 <5 <10 <6 <14 <9 <6 <5 <6 <13 15-May-19 <139 <90 <6 <6 <11 <5 <11 <10 <9 <5 <6 <10 12-Jun-19 <135 <38 <3 <3 <7 <3 <7 <5 <5 <3 <4 <6 T84 24-Apr-19 12049 +/- 156 664 +/- 36 <4 <4 <7 <4 <8 <6 <6 <4 <4 <4 16-May-19 7645 +/- 127 599 +/- 34 <3 <3 <8 <3 <8 <7 <5 <3 <4 <4 12-Jun-19 5034 +/- 106 634 +/- 35 <3 <4 <8 <4 <9 <7 <6 <4 <4 <5 T97 24-Apr-19 11782 +/- 155 587 +/- 52 <6 <6 <13 <6 <15 <10 <9 <6 <7 <9 15-May-19 7903 +/- 129 616 +/- 35 <4 <4 <8 <4 <9 <6 <6 <3 <4 <6 12-Jun-19 4816 +/- 104 580 +/- 52 <7 <7 <11 <8 <16 <12 <9 <6 <7 <9 (A) - These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) - These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

Page 61 of 100

3.b. SHORELINE SEDIMENT - (pCi/kg, dry weight)

Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Pb-210 Ra-226 Th-232 These samples were previously collected.

Page 62 of 100

4.a. GOATS MILK - (pCi/L)

Sample Collection Date Ba-140 Site K-40 I-131 Cs-134 Cs-137 La-140 (A)

T99 This sample unavailable during the quarter.

(A) - This tabulated LLD value is for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity.

4.b. FOOD CROPS - Coconuts - (pCi/kg, wet weight)

Sample Collection Site Date Be-7 K-40 Mn-54 Co-58 Co-60 Ag-110m I-131 Cs-134 Cs-137 Ra-226 Ra-228 T43 This sample previously collected.

T44 This sample previously collected.

T45 2770 +/-

24-Apr-19 <63 118 <9 <7 <9 <7 <12 <7 <8 <172 <29 Page 63 of 100

RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY TURKEY POINT SITE THIRD QUARTER 2019 BUREAU OF RADIATION CONTROL Page 64 of 100

TURKEY POINT SITE Offsite Dose Calculation Manual Sampling Third Quarter, 2019 Number of Sample Type Collection Frequency Locations Sampled Samples

1. Direct Radiation Quarterly 23 46

2. Airborne 2.a. Air Iodines Weekly 6 78 2.b. Air Particulates Weekly 6 78

3. Waterborne 3.a. Surface Water Monthly 3 9 3.b. Shoreline Sediment Semiannually 3 3

4. Ingestion 4.a. Fish and Invertebrates 4.a.1. Crustacea Semiannually 2 0 4.a.2. Fish Semiannually 2 0 4.b. Broadleaf Vegetation Monthly 3 9 Total: 223 NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term. Measurement results that are not significantly above background are reported as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 95% confidence) for the true activity in the sample.

The marine fauna listed in this report were collected in part, under Florida FWC SAL030.

Page 65 of 100

1. DIRECT RADIATION - TLDs - (µR/hour)

Sample Deployment 12-Jun-19 Site Collection 25-Sep-19 Old New N-2 4.86 +/- 0.30 4.45 +/- 0.11 N-7 3.87 +/- 0.17 3.50 +/- 0.08 N-10 4.38 +/- 0.20 3.90 +/- 0.18 NNW-2 3.98 +/- 0.19 3.81 +/- 0.23 NNW-10 4.46 +/- 0.19 3.90 +/- 0.45 NW-1 4.86 +/- 0.07 4.37 +/- 0.22 NW-5 3.94 +/- 0.54 3.50 +/- 0.16 NW-10 5.26 +/- 0.12 4.83 +/- 0.20 WNW-2 4.16 +/- 0.28 3.79 +/- 0.37 WNW-10 4.81 +/- 0.29 4.41 +/- 0.25 W-1 4.80 +/- 0.24 4.10 +/- 0.20 W-5 4.32 +/- 0.28 4.08 +/- 0.07 W-9 3.96 +/- 0.42 3.57 +/- 0.71 WSW-8 3.84 +/- 0.07 3.71 +/- 0.39 SW-1 4.50 +/- 0.35 3.97 +/- 0.25 SW-8 3.51 +/- 0.44 3.07 +/- 0.06 SSW-5 3.60 +/- 0.21 3.21 +/- 0.38 SSW-10 3.92 +/- 0.21 3.44 +/- 0.24 S-5 3.45 +/- 0.46 3.24 +/- 0.14 S-10 3.99 +/- 0.30 3.80 +/- 0.43 SSE-1 *3.87 +/- 4.46 3.14 +/- 0.24 SSE-10 3.77 +/- 0.45 3.43 +/- 0.18 NNE-22 4.40 +/- 0.24 4.10 +/- 0.48

• Element 3 of TLD#240 read unusually high; 20mR. Element 3 not used for dose rate calculation.

Page 66 of 100

2.a. IODINE-131 IN WEEKLY AIR CARTRIDGES - (pCi/m³)

Collection Date T41 T51 T57 T58 T64 T72 02-Jul-19 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 09-Jul-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 16-Jul-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 23-Jul-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 30-Jul-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 06-Aug-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 14-Aug-19 <0.05 <0.05 <0.05 <0.05 <0.05 <0.05 20-Aug-19 <0.04 <0.04 <0.04 <0.04 <0.04 <0.04 27-Aug-19 <0.03 <0.03 <0.03 <0.04 <0.03 <0.03 04-Sep-19 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 11-Sep-19 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 18-Sep-19 <0.02 <0.01 <0.01 <0.01 <0.02 <0.02 25-Sep-19 <0.01 <0.01 <0.02 <0.02 <0.01 <0.02 Page 67 of 100

2.b. AIR PARTICULATES - GROSS BETA - (pCi/m³)

Collectio n Date T41 T51 T57 T58 T64 T72 02-Jul-19 0.014 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.002 0.017 +/- 0.002 0.015 +/- 0.002 09-Jul-19 0.014 +/- 0.002 0.018 +/- 0.002 0.012 +/- 0.002 0.017 +/- 0.002 0.015 +/- 0.002 0.015 +/- 0.002 16-Jul-19 0.022 +/- 0.002 0.018 +/- 0.002 0.018 +/- 0.002 0.019 +/- 0.002 0.025 +/- 0.002 0.016 +/- 0.002 23-Jul-19 0.016 +/- 0.002 0.010 +/- 0.002 0.011 +/- 0.002 0.013 +/- 0.002 0.013 +/- 0.002 0.012 +/- 0.002 30-Jul-19 0.010 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.002 0.008 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 06-Aug-19 0.010 +/- 0.002 0.008 +/- 0.002 0.011 +/- 0.002 0.008 +/- 0.002 0.012 +/- 0.002 0.010 +/- 0.002 14-Aug-19 0.012 +/- 0.002 0.015 +/- 0.002 0.011 +/- 0.002 0.014 +/- 0.002 0.015 +/- 0.002 0.013 +/- 0.002 20-Aug-19 0.011 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.015 +/- 0.002 0.017 +/- 0.002 0.014 +/- 0.002 27-Aug-19 0.005 +/- 0.002 0.004 +/- 0.001 0.006 +/- 0.002 0.004 +/- 0.002 0.006 +/- 0.002 0.003 +/- 0.001 04-Sep-19 0.008 +/- 0.002 0.009 +/- 0.002 0.010 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 0.011 +/- 0.002 11-Sep-19 0.020 +/- 0.002 0.024 +/- 0.002 0.022 +/- 0.002 0.025 +/- 0.002 0.022 +/- 0.002 0.022 +/- 0.002 18-Sep-19 0.015 +/- 0.002 0.012 +/- 0.002 0.013 +/- 0.002 0.016 +/- 0.002 0.018 +/- 0.002 0.014 +/- 0.002 25-Sep-19 0.015 +/- 0.002 0.017 +/- 0.002 0.022 +/- 0.003 0.014 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 02-Jul-19 0.014 +/- 0.002 0.015 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.002 0.017 +/- 0.002 0.015 +/- 0.002 2.b. AIR PARTICULATES - GAMMA ANALYSIS OF QUARTERLY COMPOSITES - (pCi/m³)

Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T41 0.0823 +/- 0.0080 <0.0223 <0.0010 <0.0010 <0.0306 T51 0.1010 +/- 0.0078 <0.0149 <0.0010 <0.0009 <0.0150 T57 0.0860 +/- 0.0076 <0.0119 <0.0013 <0.0007 0.0118 +/- 0.0030 T58 0.0990 +/- 0.0084 <0.0191 <0.0010 <0.0009 <0.0269 T64 0.1000 +/- 0.0079 <0.0132 <0.0012 <0.0009 <0.0144 T72 0.0954 +/- 0.0083 <0.0233 <0.0010 <0.0009 <0.0289 Page 68 of 100

3.a. SURFACE WATER - (pCi/L)

Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)

T42 17-Jul-19 <139 426 +/- 46 <5 <6 <12 <7 <14 <9 <9 <4 <7 <11 15-Aug-19 <138 378 +/- 26 <4 <4 <7 <3 <8 <7 <9 <3 <4 <7 26-Sep-19 <134 309 +/- 37 <5 <5 <12 <6 <15 <10 <8 <5 <5 <9 T67 15-Jul-19 <139 135 +/- 17 <3 <4 <8 <3 <6 <7 <14 <3 <3 <9 13-Aug-19 <143 113 +/- 26 <6 <6 <13 <5 <13 <11 <16 <5 <6 <12 23-Sep-19 <134 281 +/- 36 <6 <6 <11 <6 <12 <8 <10 <5 <7 <10 T81 17-Jul-19 <139 370 +/- 49 <7 <6 <14 <6 <13 <11 <10 <5 <7 <9 15-Aug-19 <138 483 +/- 43 <6 <7 <15 <6 <14 <9 <15 <5 <6 <12 26-Sep-19 <134 350 +/- 25 <3 <3 <8 <4 <7 <5 <5 <3 <3 <5 (A) - These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) - These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

Page 69 of 100

3.b. SHORELINE SEDIMENT - (pCi/kg, dry weight)

Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Pb-210 Ra-226 Th-232 U-235 U-238 T42 17-Jul-19 <84 181 +/- 24 <8 <7 <8 <8 594 +/- 84 990 +/- 75 <32 62 +/- 5 374 +/- 21 T67 15-Jul-19 <104 420 +/- 48 <10 <9 <9 <8 <736 593 +/- 79 <49 37 +/- 5 168 +/- 45 T81 17-Jul-19 <61 224 +/- 28 <9 <7 <9 <9 667 +/-103 734 +/- 246 <39 43 +/- 14 584 +/- 27 4.a.1. CRUSTACEA - Blue Crab - (pCi/kg, wet weight)

Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 This sample not yet collected.

T81 This sample not yet collected.

4.a.2. FISH - (pCi/kg, wet weight)

Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 This sample not yet collected.

T81 This sample not yet collected.

Page 70 of 100

4.b. BROADLEAF VEGETATION - Brazilian Pepper - (pCi/kg, wet weight)

Sample Collection Site Date Be-7 K-40 I- Cs- Cs- Pb- Pb- Ra- Ra-131 134 137 210 212 226 228 T40 15-Jul-19 1960 +/- 70 5210 +/- 185 <17 <8 63 +/- 4 252 +/- 66 <18 <205 <33 15-Aug-19 3260 +/- 128 4120 +/- 202 <48 <12 14 +/- 4 <1380 <27 <338 <52 26-Sep-19 2540 +/- 109 4870 +/- 222 <24 <14 89 +/- 8 <1320 <28 <324 <63 T41 15-Jul-19 1540 +/- 58 6580 +/- 216 <17 <7 6+/-2 <355 <17 <188 <35 15-Aug-19 3340 +/- 103 5870 +/- 207 <31 <9 <14 <435 <19 <152 <42 26-Sep-19 2370 +/- 80 5950 +/- 208 <17 <9 <13 340 +/- 86 <19 <225 <39 T67 15-Jul-19 774 +/- 55 3970 +/- 185 <20 <11 13 +/- 4 <810 <21 <247 <49 13-Aug-19 2280 +/- 110 4950 +/- 226 <43 <12 <21 <1090 <25 <448 <68 23-Sep-19 2190 +/- 105 5400 +/- 242 <30 <13 <19 <1150 <28 <407 <66 Page 71 of 100

TURKEY POINT SITE Supplemental Sampling Third Quarter, 2019 Number of Sample Type Collection Frequency Locations Sampled Samples

1. Direct Radiation Quarterly 9 18

2. Airborne 2.a. Air Iodines Weekly 2 26 2.b. Air Particulates Weekly 2 26

3. Waterborne 3.a. Surface Water Monthly 4 12 3.b. Shoreline Sediment Semiannually 2 2

4. Ingestion 4.a. Milk Semiannually 1 0 4.b. Food Crops At Harvest 3 0 Total: 84 NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term. Measurement results that are not significantly above background are reported as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 95% confidence) for the true activity in the sample.

The marine fauna listed in this report were collected in part, under Florida FWC SAL030.

Page 72 of 100

1. DIRECT RADIATION - TLDs - (µR/hour)

Sample Deployment 12-Jun-19 Site Collection 25-Sep-19 Old New NNW-6 4.16 +/- 0.18 3.78 +/- 0.24 NW-7 4.58 +/- 0.18 4.26 +/- 0.18 NW-8 4.51 +/- 0.62 4.05 +/- 0.12 WNW-3 4.21 +/- 0.35 3.71 +/- 0.11 WNW-6 4.09 +/- 0.15 3.76 +/- 0.37 W-8 4.31 +/- 0.13 4.08 +/- 0.11 ENE-1 3.44 +/- 0.27 3.15 +/- 0.38 T72 4.41 +/- 0.29 3.71 +/- 0.02 PTN-1 4.05 +/- 0.11 3.75 +/- 0.22 2.a. IODINE-131 IN WEEKLY AIR CARTRIDGES - (pCi/m³)

Collection +/- Date T52 T56 02-Jul-19 <0.01 <0.01 09-Jul-19 <0.02 <0.02 16-Jul-19 <0.02 <0.02 23-Jul-19 <0.02 <0.02 30-Jul-19 <0.02 <0.02 06-Aug-19 <0.02 <0.02 14-Aug-19 <0.05 <0.07 20-Aug-19 <0.04 <0.04 27-Aug-19 <0.03 <0.03 04-Sep-19 <0.01 <0.02 11-Sep-19 <0.01 <0.02 18-Sep-19 <0.01 <0.01 25-Sep-19 <0.01 <0.02 Page 73 of 100

2.b. AIR PARTICULATES GROSS BETA (pCi/m³)

Collection +/-

Date T52 T56 02-Jul-19 0.016 +/- 0.002 0.017 +/- 0.002 09-Jul-19 0.014 +/- 0.002 0.018 +/- 0.002 16-Jul-19 0.015 +/- 0.002 0.019 +/- 0.002 23-Jul-19 0.012 +/- 0.002 0.013 +/- 0.002 30-Jul-19 0.009 +/- 0.002 0.010 +/- 0.002 06-Aug-19 0.011 +/- 0.002 0.013 +/- 0.002 14-Aug-19 0.012 +/- 0.002 0.016 +/- 0.002 20-Aug-19 0.018 +/- 0.002 0.010 +/- 0.002 27-Aug-19 0.008 +/- 0.002 0.004 +/- 0.001 04-Sep-19 0.008 +/- 0.002 0.008 +/- 0.002 11-Sep-19 0.024 +/- 0.002 0.024 +/- 0.003 18-Sep-19 0.013 +/- 0.002 0.013 +/- 0.002 25-Sep-19 0.014 +/- 0.002 0.022 +/- 0.002 2.b. AIR PARTICULATES GAMMA ANALYSIS OF QUARTERLY COMPOSITES (pCi/m³)

Sample +/- Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T52 0.0936 +/- 0.0076 <0.0122 <0.0010 <0.0009 <0.0147 T56 0.0964 +/- 0.0084 <0.0186 <0.0011 <0.0009 <0.0320 Page 74 of 100

3.a. SURFACE WATER (pCi/L)

Sample Collection Zr-95 Ba-140 Site +/- Date H-3 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)

T08 17-Jul-19 2991 +/- 86 684 +/- 37 <3 <4 <<8 <4 <9 <6 <6 <3 <4 <5 15-Aug-19 3524 +/- 93 603 +/- 48 <6 <6 <13 <7 <14 <12 <15 <5 <7 <13 26-Sep-19 2094 +/- 75 623 +/- 35 <3 <3 <<8 <4 <8 <6 <5 <3 <4 <4 T75 15-Jul-19 <139 <92 <6 <6 <13 <5 <13 <11 <10 <5 <6 <11 15-Aug-19 <143 <97 <6 <6 <12 <6 <12 <10 <15 <5 <6 <11 26-Sep-19 <134 <43 <3 <3 <5 <3 <6 <6 <4 <3 <3 <4 T84 16-Jul-19 2989 +/- 86 603 +/- 34 <3 <4 <7 <4 <8 <7 <6 <4 <4 <5 15-Aug-19 3537 +/- 93 558 +/- 48 <6 <7 <14 <6 <11 <11 <16 <5 <6 <11 26-Sep-19 2322 +/- 78 536 +/- 33 <4 <3 <8 <3 <8 <6 <5 <3 <4 <4 T97 17-Jul-19 2862 +/- 85 646 +/- 36 <4 <4 <7 <4 <8 <6 <7 <3 <4 <4 15-Aug-19 3685 +/- 94 540 +/- 45 <6 <7 <17 <6 <14 <11 <16 <6 <7 <12 26-Sep-19 2540 +/- 81 601 +/- 49 <5 <5 <13 <6 <13 <9 <8 <5 <7 <10 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity fora given sample.

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3.b. SHORELINE SEDIMENT - (pCi/kg, dry weight)

Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Pb-210 Ra-226 Th-232 U-235 U-238 T84 15-Jul-19 <157 201 +/- 38 <16 25 +/- 3 <17 <17 2320 +/- 202 2980 +/- 179 <69 188 +/- 11 437 +/- 33 T85 17-Jul-19 <123 698 +/- 50 <13 <11 <11 <13 877 +/- 86 1950 +/- 123 <54 123 +/- 7 557 +/- 30 4.a. GOATS MILK - (pCi/L)

Ba-140 Sample Collection Date La-140 (A)

Site K-40 I-131 Cs-134 Cs-137 T99 This sample not yet collected.

(A) - This tabulated LLD value is for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity.

4.b. FOOD CROPS - (pCi/kg, wet weight)

Sample Collection Site Date Be-7 K-40 Mn-54 Co-5<8 Co-60 Ag-110m I-131 Cs-134 Cs-137 Ra-226 Ra-22<8 T43 This sample was previously collected.

T44 This sample was previously collected.

T45 This sample was previously collected.

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RADIOLOGICAL SURVEILLANCE OF FLORIDA POWER AND LIGHT COMPANY TURKEY POINT SITE FOURTH QUARTER 2019 BUREAU OF RADIATION CONTROL Page 77 of 100

TURKEY POINT SITE Offsite Dose Calculation Manual Sampling Fourth Quarter, 2019 Number of Sample Type Collection Locations Sampled Samples Frequency

1. Direct Radiation Quarterly 23 46

2. Airborne 2.a. Air Iodines Weekly 6 84 2.b. Air Particulates Weekly 6 84

3. Waterborne 3.a. Surface Water Monthly 3 9 3.b. Shoreline Sediment Semiannually 3 0

4. Ingestion 4.a. Fish and Invertebrates 4.a.1. Crustacea Semiannually 2 2 4.a.2. Fish Semiannually 2 2 4.b. Broadleaf Vegetation Monthly 3 9 Total: 236 NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term. Measurement results that are not significantly above background are reported as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 95% confidence) for the true activity in the sample.

The marine fauna listed in this report were collected in part, under Florida FWC SAL030.

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1. DIRECT RADIATION - TLDs - (µR/hour)

Sample Deployment 25-Sep-19 Site Collection 11-Dec-19 Old New N-2 4.16 +/- 0.35 4.47 +/- 0.72 N-7 3.18 +/- 0.53 3.61 +/- 0.46 N-10 3.82 +/- 0.30 4.15 +/- 0.10 NNW-2 3.46 +/- 0.39 3.81 +/- 0.15 NNW-10 3.89 +/- 0.77 4.02 +/- 0.50 NW-1 3.92 +/- 0.25 4.43 +/- 0.24 NW-5 3.12 +/- 0.20 3.40 +/- 0.30 NW-10 4.32 +/- 0.31 4.43 +/- 0.57 WNW-2 3.66 +/- 0.20 3.24 +/- 0.36 WNW-10 4.16 +/- 0.31 4.36 +/- 0.61 W-1 3.60 +/- 0.25 4.08 +/- 0.21 W-5 3.39 +/- 0.39 3.67 +/- 0.27 W-9 3.03 +/- 0.15 3.03 +/- 0.34 WSW-8 3.25 +/- 0.91 3.19 +/- 0.35 SW-1 3.75 +/- 0.17 2.87 +/- 0.26 SW-8 2.75 +/- 0.05 3.42 +/- 0.41 SSW-5 3.19 +/- 0.15 3.72 +/- 0.17 SSW-10 3.39 +/- 0.54 3.81 +/- 0.67 S-5 2.87 +/- 0.44 3.05 +/- 0.20 S-10 2.91 +/- 0.29 2.90 +/- 0.24 SSE-1 2.71 +/- 0.11 2.83 +/- 0.11 SSE-10 2.96 +/- 0.05 2.76 +/- 0.51 NNE-22 4.07 +/- 0.30 3.53 +/- 0.57 Page 79 of 100

2.a. IODINE-131 IN WEEKLY AIR CARTRIDGES - (pCi/m³)

Collection Date T41 T51 T57 T58 T64 T72 02-Oct-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 09-Oct-19 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 15-Oct-19 <0.03 <0.02 <0.03 <0.02 <0.03 <0.03 24-Oct-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 30-Oct-19 <0.03 <0.02 <0.03 <0.03 <0.03 <0.03 06-Nov-19 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 13-Nov-19 <0.02 <0.01 <0.01 <0.01 <0.02 <0.02 19-Nov-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 26-Nov-19 <0.02 <0.01 <0.01 <0.01 <0.01 <0.01 03-Dec-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 11-Dec-19 <0.02 <0.01 <0.01 <0.01 <0.01 <0.01 19-Dec-19 <0.01 <0.01 <0.01 <0.01 <0.01 <0.01 24-Dec-19 <0.02 <0.02 <0.02 <0.02 <0.02 <0.02 30-Dec-19 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 Page 80 of 100

2.b. AIR PARTICULATES - GROSS BETA - (pCi/m³)

Collection Date T41 T51 T57 T58 T64 T72 02-Oct-19 0.019 +/- 0.002 0.018 +/- 0.002 0.022 +/- 0.002 0.019 +/- 0.002 0.022 +/- 0.002 0.018 +/- 0.002 09-Oct-19 0.008 +/- 0.002 0.008 +/- 0.002 0.010 +/- 0.002 0.007 +/- 0.002 0.005 +/- 0.002 0.007 +/- 0.002 15-Oct-19 0.011 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 0.009 +/- 0.002 0.008 +/- 0.002 24-Oct-19 0.010 +/- 0.002 0.010 +/- 0.001 0.010 +/- 0.001 0.011 +/- 0.002 0.013 +/- 0.002 0.008 +/- 0.001 30-Oct-19 <0.008 0.008 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 0.008 +/- 0.002 06-Nov-19 0.006 +/- 0.002 0.005 +/- 0.002 0.006 +/- 0.002 0.007 +/- 0.002 0.009 +/- 0.002 0.007 +/- 0.002 13-Nov-19 0.006 +/- 0.002 0.004 +/- 0.002 0.005 +/- 0.002 0.007 +/- 0.002 0.006 +/- 0.002 <0.008 19-Nov-19 0.005 +/- 0.002 0.008 +/- 0.002 0.006 +/- 0.002 0.008 +/- 0.002 0.008 +/- 0.002 0.009 +/- 0.002 26-Nov-19 0.025 +/- 0.003 0.022 +/- 0.002 0.018 +/- 0.002 0.020 +/- 0.002 0.021 +/- 0.002 0.027 +/- 0.003 03-Dec-19 0.014 +/- 0.002 0.014 +/- 0.002 0.021 +/- 0.002 0.017 +/- 0.002 0.016 +/- 0.002 0.018 +/- 0.002 11-Dec-19 0.014 +/- 0.002 0.020 +/- 0.002 0.018 +/- 0.002 0.015 +/- 0.002 0.020 +/- 0.002 0.018 +/- 0.002 19-Dec-19 0.011 +/- 0.002 0.008 +/- 0.002 0.007 +/- 0.002 0.011 +/- 0.002 0.008 +/- 0.002 0.010 +/- 0.002 24-Dec-19 0.009 +/- 0.002 0.007 +/- 0.002 0.007 +/- 0.002 0.006 +/- 0.002 0.004 +/- 0.002 0.008 +/- 0.002 30-Dec-19 <0.008 <0.008 0.006 +/- 0.002 0.005 +/- 0.002 <0.009 0.004 +/- 0.002 Average: <0.011 <0.011 0.011 +/- 0.001 0.011 +/- 0.001 <0.011 <0.011 Page 81 of 100

2.b. AIR PARTICULATES - GAMMA ANALYSIS OF QUARTERLY COMPOSITES - (pCi/m³)

Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T41 0.1170 +/- 0.0084 <0.0149 <0.0010 <0.0010 <0.0139 T51 0.1110 +/- 0.0091 <0.0202 <0.0009 <0.0008 <0.0279 T57 0.1110 +/- 0.0077 0.0072 +/- 0.0027 <0.0012 <0.0009 0.0098 +/- 0.0027 T58 0.1120 +/- 0.0089 <0.0223 <0.0010 <0.0008 <0.0295 T64 0.1320 +/- 0.0089 <0.0125 <0.0010 <0.0008 0.0119 +/- 0.0026 T72 0.1370 +/- 0.0094 <0.0199 <0.0012 <0.0010 <0.0293 Page 82 of 100

3.a. SURFACE WATER - (pCi/L)

Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)

T42 23-Oct-19 <140 399 +/- 39 <6 <6 <10 <6 <12 <10 <10 <5 <7 <9 20-Nov-19 <140 283 +/- 23 <3 <3 <7 <3 <8 <6 <6 <3 <3 <5 12-Dec-19 <137 319 +/- 24 <3 <3 <7 <3 <9 <5 <7 <3 <3 <6 T67 24-Oct-19 <140 314 +/- 35 <7 <6 <11 <5 <14 <11 <9 <5 <6 <9 21-Nov-19 <140 251 +/- 22 <3 <3 <7 <3 <7 <6 <5 <3 <3 <4 11-Dec-19 <137 318 +/- 24 <4 <3 <7 <3 <7 <5 <4 <3 <4 <6 T81 23-Oct-19 <140 357 +/- 39 <6 <6 <13 <6 <14 <11 <9 <5 <7 <9 18-Nov-19 <140 305 +/- 25 <3 <3 <8 <3 <7 <5 <5 <3 <3 <5 12-Dec-19 <137 339 +/- 26 <3 <4 <8 <3 <8 <6 <7 <4 <4 <4 (A) - These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) - These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity for a given sample.

Page 83 of 100

3.b. SHORELINE SEDIMENT - (pCi/kg, dry weight)

Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Pb-210 Ra-226 Th-232 U-235 U-238 T42 This sample was previously collected.

T67 This sample was previously collected.

T81 This sample was previously collected.

4.a.1. CRUSTACEA - Blue Crab - (pCi/kg, wet weight)

Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 27-Dec-19 1310 +/- 118 <18 <20 <40 <21 <43 <22 <22 <454 <82 T81 26-Dec-19 2010 +/- 211 <27 <27 <58 <26 <64 <22 <26 <501 <117 4.a.2. FISH - Mixed Species - (pCi/kg, wet weight)

Sample Collection Site Date K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Ra-228 T67 21-Nov-19 2120 +/- 153 <23 <21 <50 <23 <52 <22 <32 <471 <100 T81 20-Nov-19 3180 +/- 244 <24 <24 <50 <28 <65 <22 <25 <423 <108 Page 84 of 100

4.b. BROADLEAF VEGETATION - Brazilian Pepper - (pCi/kg, wet weight)

Sample Collection Site Date Be-7 K-40 I-131 Cs-134 Cs-137 Pb-210 Pb-212 Ra-226 Ra-228 T40 23-Oct-19 2100 +/- 74 4290 +/- 162 <15 <7 16 +/- 3 <347 <18 <215 <35 20-Nov-19 1500 +/- 76 3470 +/- 175 <16 <10 18 +/- 6 <957 <23 <270 <60 12-Dec-19 1290 +/- 80 4950 +/- 231 <24 <14 <20 <1040 <28 <357 <61 T41 23-Oct-19 2110 +/- 98 5540 +/- 241 <24 <13 19 +/- 5 <1090 <26 <332 <66 20-Nov-19 646 +/- 55 4870 +/- 224 <20 <12 <17 <1010 <23 <286 <66 12-Dec-19 971 +/- 60 4610 +/- 205 <22 <12 <16 <1180 <22 <301 <57 T67 24-Oct-19 2280 +/- 96 4320 +/- 199 <19 <12 <18 1290 +/- 393 <23 <310 <54 21-Nov-19 1160 +/- 74 5090 +/- 230 <21 <13 <16 <1060 <30 <313 <71 11-Dec-19 960 +/- 70 5770 +/- 251 <16 <13 14 +/- 5 <1060 <19 <320 <68 Page 85 of 100

TURKEY POINT SITE Supplemental Sampling Fourth Quarter, 2019 Number of Sample Type Collection Frequency Locations Sampled Samples

1. Direct Radiation Quarterly 9 18

2. Airborne 2.a. Air Iodines Weekly 2 28 2.b. Air Particulates Weekly 2 28

3. Waterborne 3.a. Surface Water Monthly 4 12 3.b. Shoreline Sediment Semiannually 2 0

4. Ingestion 4.a. Milk Semiannually 1 0 4.b. Food Crops At Harvest 3 0 Total: 86 NOTE: Measurement results having magnitudes that are significantly above the background of the measurement system are reported as net values plus or minus a one-standard-deviation error term. Measurement results that are not significantly above background are reported as less than a Lower Limit of Detection (<LLD), which is an estimated upper limit (with at least 95% confidence) for the true activity in the sample.

The marine fauna listed in this report were collected in part, under Florida FWC SAL030.

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1. DIRECT RADIATION - TLDs - (µR/hour)

Sample Deployment 25-Sep-19 Site Collection 11-Dec-19 Old New NNW-6 3.59 +/- 0.60 3.37 +/- 0.45 NW-7 3.87 +/- 0.66 4.63 +/- 0.21 NW-8 4.25 +/- 0.25 4.22 +/- 0.46 WNW-3 3.69 +/- 0.30 3.65 +/- 0.41 WNW-6 3.59 +/- 0.60 3.90 +/- 0.50 W-8 3.68 +/- 0.20 3.85 +/- 0.23 ENE-1 2.64 +/- 0.23 2.64 +/- 0.36 T72 3.44 +/- 0.46 3.60 +/- 0.49 PTN-1 3.52 +/- 0.31 3.92 +/- 0.36 2.a. IODINE-131 IN WEEKLY AIR CARTRIDGES - (pCi/m³)

Collection Date T52 T56 02-Oct-19 <0.02 <0.02 09-Oct-19 <0.01 <0.01 15-Oct-19 <0.03 <0.03 24-Oct-19 <0.02 <0.02 30-Oct-19 <0.03 <0.03 06-Nov-19 <0.01 <0.01 13-Nov-19 <0.02 <0.01 19-Nov-19 <0.02 <0.02 26-Nov-19 <0.01 <0.01 03-Dec-19 <0.02 <0.02 11-Dec-19 <0.01 <0.01 19-Dec-19 <0.01 <0.01 24-Dec-19 <0.02 <0.02 30-Dec-19 <0.03 <0.03 Page 87 of 100

2.b. AIR PARTICULATES GROSS BETA (pCi/m³)

Collection Date T52 T56 02-Oct-19 0.015 +/- 0.002 0.019 +/- 0.002 09-Oct-19 0.007 +/- 0.002 0.007 +/- 0.002 15-Oct-19 0.009 +/- 0.002 0.011 +/- 0.002 24-Oct-19 0.008 +/- 0.001 0.009 +/- 0.001 30-Oct-19 0.007 +/- 0.002 0.009 +/- 0.002 06-Nov-19 0.005 +/- 0.002 0.007 +/- 0.002 13-Nov-19 <0.008 <0.002 19-Nov-19 0.009 +/- 0.002 0.010 +/- 0.002 26-Nov-19 0.023 +/- 0.002 0.021 +/- 0.002 03-Dec-19 0.016 +/- 0.002 0.020 +/- 0.002 11-Dec-19 0.017 +/- 0.002 0.015 +/- 0.002 19-Dec-19 0.009 +/- 0.002 0.010 +/- 0.002 24-Dec-19 <0.009 0.009 +/- 0.002 30-Dec-19 <0.008 0.005 +/- 0.002 Average: <0.011 <0.011 2.b. AIR PARTICULATES GAMMA ANALYSIS OF QUARTERLY COMPOSITES (pCi/m³)

Sample Site Be-7 K-40 Cs-134 Cs-137 Pb-210 T52 0.1240 +/- 0.0086 <0.0142 <0.0010 <0.0008 <0.0131 T56 0.1310 +/- 0.0092 <0.0214 <0.0012 <0.0007 <0.0275 Page 88 of 100

3.a. SURFACE WATER (pCi/L)

Sample Collection Zr-95 Ba-140 Site Date H-3 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 I-131 Cs-134 Cs-137 La-140 (A) (B)

T08 23-Oct-19 3455 +/- 92 518 +/- 44 <6 <6 <13 <7 <14 <10 <9 <5 <7 <10 18-Nov-19 7603 +/- 128 549 +/- 32 <3 <3 <8 <4 <7 <7 <7 <3 <4 <5 12-Dec-19 15575 +/- 178 624 +/- 35 <4 <3 <7 <4 <8 <6 <7 <3 <4 <4 T75 23-Oct-19 <140 85 +/- 20 <6 <5 <11 <6 <12 <9 <9 <5 <7 <10 20-Nov-19 <140 <28 <3 <3 <6 <3 <7 <5 <6 <3 <3 <5 12-Dec-19 <137 <41 <3 <3 <7 <3 <8 <5 <6 <3 <3 <5 T84 23-Oct-19 3370 +/- 91 598 +/- 50 <7 <6 <13 <7 <14 <11 <10 <5 <6 <10 18-Nov-19 6261 +/- 118 553 +/- 33 <3 <4 <8 <3 <8 <6 <7 <3 <3 <5 12-Dec-19 13722 +/- 167 594 +/- 50 <7 <6 <13 <7 <15 <10 <10 <6 <7 <11 T97 23-Oct-19 3314 +/- 90 617 +/- 49 <6 <6 <13 <5 <15 <9 <10 <5 <8 <11 20-Nov-19 5722 +/- 113 616 +/- 51 <5 <6 <13 <7 <14 <11 <10 <6 <7 <11 12-Dec-19 13802 +/- 168 654 +/- 36 <4 <4 <9 <4 <8 <7 <12 <4 <4 <9 (A) These tabulated LLD values for Zr/Nb-95 are the higher of the individual parent or daughter LLDs.

(B) These tabulated LLD values are for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity fora given sample.

Page 89 of 100

3.b. SHORELINE SEDIMENT - (pCi/kg, dry weight)

Sample Collection Site Date Be-7 K-40 Co-58 Co-60 Cs-134 Cs-137 Pb-210 Ra-226 Th-232 U-235 U-238 T84 This sample was previously collected.

T85 This sample was previously collected.

4.a. GOATS MILK - (pCi/L)

Ba-140 Sample Collection Date La-140 (A)

Site K-40 I-131 Cs-134 Cs-137 T99 This sample not collected; no goats milk available.

(A) - This tabulated LLD value is for Ba-140, either based on direct measurement of Ba-140 or based on ingrowth of La-140, whichever method yields the greater sensitivity.

4.b. FOOD CROPS - (pCi/kg, wet weight)

Sample Collection Site Date Be-7 K-40 Mn-54 Co-5<8 Co-60 Ag-110m I-131 Cs-134 Cs-137 Ra-226 Ra-22<8 T43 This sample was previously collected.

T44 This sample was previously collected.

T45 This sample was previously collected.

Page 90 of 100

ATTACHMENT C RESULTS FROM THE 2019 INTERLABORATORY COMPARISON PROGRAM CONDUCTED BY DEPARTMENT OF ENERGY Page 91 of 100

DOE-MAPEP 40 RESULTS Program Result Ref. Flag Acceptance status Radionuclide Value (Evaluation) Range Matrix: RdF Air Filter Bq/filter Required MN54 0.596 0.547 A 0.383-0.711 Required CO57 0.416 0.411 A 0.288-0.534 Required CO60 0.357 0.340 A 0.238-0.442 ZN65 0.010 A False Positive Test Required CS134 0.213 0.216 A 0.151-0.281 Required CS137 0.307 0.290 A 0.203-0.377 Matrix: GrF Air Filter pCi/filter Required Gross Beta 0.61 0.528 A 0.158-0.898 Gross Required 0.96 0.948 A 0.474-1.422 Alpha Matrix: MaS Soil Bq/kg Required K40 564.68 585 A 410-761 MN54 1016.57 1027 A 719-1335 CO57 0.35 A False Positive Test CO60 822.15 855 A 599-1112 ZN65 697.73 668 A 468-868 CS134 0.29 A False Positive Test Required CS137 1137.78 1164 A 815-1513 Matrix: MaW Water Bq/L Required H3 NR 421 295-547 MN54 8.262 8.4 A 5.9-10.9 CO57 9.148 10 A 7.0-13.0 Required CO60 6.360 6.7 A 4.7-8.7 ZN65 0.136 A False Positive Test Required CS134 5.412 5.99 A 4.19-7.79 Required CS137 0.108 A False Positive Test SR90 NR 6.35 4.45-8.26 Matrix: RdV Vegetation, Bq/sample :

MN54 0.20 A False Positive Test CO57 2.359 2.07 A 1.45-2.69 Required CO60 0.62 A False Positive Test ZN65 1.795 1.71 A 1.2-2.22 CS134 2.446 2.44 A 1.71-3.17 Required CS137 2.522 2.3 A 1.61-2.99 Evaluation : A = Acceptable, W = Acceptable with Warning, N = Not Acceptable, NR = Not Reported A false positive test with an A designation flag identifies the result as less than the detectable activity, since MAPEP does not report zero values. Sensitivity Evaluation has no acceptance range but an identified value at low activity.

Page 92 of 100

DOE-MAPEP 41 RESULTS Program Ref. Flag Acceptance Result status Radionuclide Value (Evaluation) Range Matrix: RdF Air Filter Bq/filter Required MN54 1.448 1.37 A 0.96 - 1.78 Required CO57 1.128 1.16 A 0.81 - 1.51 Required CO60 0.898 0.815 A 0.571 - 1.060 ZN65 1.142 1.06 A 0.74 - 1.38 Required CS134 0.030 A False Positive Test Required CS137 1.642 1.58 A 1.11 - 2.05 Matrix: GrF Air Filter pCi/filter Required Gross Beta 1.13 0.937 A 0.469 - 1.406 Gross Required 0.68 0.528 A 0.158 - 0.898 Alpha Matrix: MaS Soil Bq/kg Required K40 525.33 555 A 389 - 722 MN54 721.33 745 A 522 - 969 CO57 0.14 A False Positive Test CO60 715.67 760 A 532 - 988 ZN65 1.80 A False Positive Test CS134 999.60 1020 A 714 - 1326 Required CS137 762.50 789 A 552 - 1026 Matrix: MaW Water Bq/L Required H3 189.51 175 A 123-228 MN54 21.150 20.6 A 14.4 - 26.8 CO57 15.613 15.6 A 10.9 - 20.3 Required CO60 8.786 8.8 A 6.2 - 11.4 ZN65 21.950 20.3 A 14.2 - 26.4 Required CS134 0.047 A False Positive Test Required CS137 19.275 18.4 A 12.9 - 23.9 SR90 9.549 10.6 A 7.4 - 13.8 Matrix: RdV Vegetation, Bq/sample :

MN54 5.010 4.49 A 3.14 - 5.84 CO57 5.588 4.57 W 3.20 - 5.94 Required CO60 5.555 5.30 A 3.71 - 6.89 ZN65 3.360 2.85 A 2.00 - 3.71 CS134 0.054 A False Positive Test Required CS137 3.578 3.28 A 2.30 - 4.26 Evaluation : A = Acceptable, W = Acceptable with Warning, N = Not Acceptable A false positive test with an A designation flag identifies the result as less than the detectable activity, since MAPEP does not report zero values. Sensitivity Evaluation has no acceptance range but an identified value at low activity.

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ATTACHMENT D Industry Initiative Ground Water Protection Program Tritium in Ground Water Monitoring 2019 Page 94 of 100

A. Description of Program:

Turkey Point maintains a sampling and analysis program to meet procedural requirements. The procedures that govern the performance are EV-AA-100-1001, Fleet Ground Water Protection Program Implementing Guideline and 0-ADM-654, Ground Water Protection Program.

The sampling frequency is quarterly; more often if conditions warrant.

Sample assay is performed by a private contractor GEL labs.

B. Discussion The Turkey Point Nuclear site is surrounded on three sides by the closed cooling canal system. This canal system, in addition to being the source of tertiary cooling, is the body of water receiving permitted liquid radiological waste the canal system tritium level averages was 7002 pCi/L in 2019 with a max concentration of 15,575 pCi/L. This supports the expectation to see tritium in subsurface water collected either on-site or off-site close to the (within the Owner Controlled Area) cooling canal system.

Twenty eight (28) wells were involved in the 2019 monitoring program; some locations have multiple (two or three) depths.

Samples are analyzed for Tritium & Gamma emitters. As conditions warrant, analysis included Fe-55, Ni-63, Sr-89/90 and alpha (all were < LLD).

C. Results The tritium results for the groundwater wells were from <MDA to 4200 pCi/L. All results were less than the limits of the Offsite Dose Calculation Manual, Table 5.1-2, Reporting Levels for Radioactivity Concentrations in Environmental Samples. Storm drain outfalls occasionally are below the tidal mark of the canal and will have ingress of canal water into the storm drain. The higher levels of tritium in the storm drain section are due to the canal water ingress into the storm drain.

Tabular results follow:

Page 95 of 100

Groundwater Well Sampling Results 2019 First Second Third Fourth Well number Quarter Quarter Quarter Quarter 2019 2019 2019 2019 H-3 H-3 H-3 H-3 PTPED-1 244 294 315 237 CD-1 439 195 279 327 P-94-2 562 --- 710 ---

P-94-4 717 692 755 554 STP-1 123 --- -3 ---

PTN-MW-1s --- --- 67 ---

PTN-MW-1i 303 --- 250 ---

PTN-MW-1d 2010 --- 1570 ---

PTN-MW-2s 84 --- 70 ---

PTN-MW-3s 172 --- 235 ---

PTN-MW-4s 141 27 100 80 PTN-MW-4i 2580 2640 2310 ---

PTN-MW-4d --- 2830 164 ---

PTN-MW-5s 381 234 107 2 PTN-MW-5i 86 172 119 208 PTN-MW-5d 1960 1870 1670 1810 PTN-MW-6s 45 --- 8 ---

PTN-MW-6i --- --- --- ---

PTN-MW-6d 1820 --- 1590 ---

PTN-MW-7s 859 804 661 563 PTN-MW-7i 1880 2330 1060 528 PTN-MW-7d 91 306 115 27 PTN-MW-8s 530 392 1710 4200 PTN-MW-9s 926 902 886 633 PTN-MW-10s --- --- 58 ---

PTN-MW-10i 1190 --- 1080 ---

PTN-MW-10d --- --- 24 ---

PTN-MW-11s 507 527 515 58 PTN-MW-12s 582 401 686 726 NE StrmDrain --- 1120 1010 ---

SE StrmDrain 2750 1290 1010 ---

W StrmDrain 327 118 3170 2900 CRF StrmDrain --- --- --- 0.194 Page 96 of 100

D. List of wells and their locations Well Name Location PTN-MW-1s PTN-MW-1i Northeast of Switch Yard, South of entrance road to Fossil Plant PTN-MW-1d PTN-MW-2s South Switch Yard by parking lot PTN-MW-3s Northeast of new Issues Warehouse PTN-MW-4s PTN-MW-4i SW corner of parking lot South of Training Bldg PTN-MW-4d PTN-MW-5s PTN-MW-5i SW of CRF, by canal PTN-MW-5d PTN-MW-6s NE of site in the berm for fossil oil tanks PTN-MW-6d PTN-MW-7s PTN-MW-7i NE of RCA, by Neutralization Tank PTN-MW-7d PTN-MW-8s Near U3 RWST PTN-MW-9s Near U4 RWST PTN-MW-10s PTN-MW-10i SE of Radwaste Bldg by S/G Bldg PTN-MW-10d PTN-MW-11s South of truck entrance to Rad Waste Bldg PTN-MW-12s West of Condenser Polisher road STP-1 West of Maintenance Bldg on corner or road into parking lot P-94-4 East of Dressout Building, under delay fence P-94-2 By Neutralization Basin, East of the RCA CD-1 By Neutralization Basin, East of the RCA PTPED-1 By Neutralization Basin, East of the RCA Note: s, i and d refer to well depth: shallow - 20 ft., intermediate - 40 ft. and deep - 60 ft Maps depicting the well locations follow.

Page 97 of 100

Onsite Tritium Monitoring Wells Page 98 of 100

ATTACHMENT E ERRATA Data Section 2019 ERRATA Data Section Page 99 of 100

• The ODCM - OFFSITE DOSE CALCULATIONS MANUAL/ ODCM Basis section 4.1: Limits of Total Dose Members of The Public section referenced 10 CFR 20.1301 (d) instead of (e) for EPA requirements. The typo was corrected. AR # 02343841

• The Land-Use summary table in the 2017 AREOR corrected to include WNW 6.0 miles which is the nearest area of plants within the 5.0 miles radius as per the ODCM.

TURKEY POINT 2017 ANNUAL LAND-USE CENSUS

SUMMARY

The annual land-use census identifies the nearest residences, vegetable gardens, and potential milk producing animals within a five-mile radius from the Turkey Point nuclear plant. The range (miles) and the bearing (degrees) from the plant are summarized for each receptor type in the table below.

SECTOR NEAREST NEAREST NEAREST RESIDENCE/BUSINESS GARDEN (A) MILK ANIMAL N 1.9 mi @ 349° *

• 1.98 mi @ 349° 2.0 mi @ 354° NNE * *

• NE * *

• ENE * *

• E * *

• ESE * *

• SE * *

• SSE * *

• S * *

• SSW * *

• SW * *

• WSW * *

• W * *

• WNW 1.7 mi @ 302° 4.5 mi @ 303°

• 3.7 mi @ 302° 4.8 mi @ 302° NW 3.6 mi @ 304° *

• 3.7 mi @ 311° 3.8 mi @ 316° 3.9 mi @ 314° NNW 4.4 mi @ 333° 4.7 mi @ 328°

• 4.5 mi @ 326° 4.7 mi @ 328° 4.9 mi @ 336° Page 100 of 100

OFFSITE DOSE CALCULATION MANUAL FOR GASEOUS AND LIQUID EFFLUENTS FROM THE TURKEY POINT PLANT UNITS 3 AND 4 REVISION 26 CHANGE DATED 12/6/18 Florida Power and Light Company 12/6/18 Plant deneral Manager/Site Director 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 i Rev 26

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 Rev 26

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 Iodine-131, Iodine-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 3B Pathway-Dose Transfer Factors.................................................. 3B - 1 Appendix 3C Technical Bases for Aeff and TG131 .............................................. 3C - 1 4.0 Total Dose Control 4.1 Limits of Total Dose to Members of the Public ............................ 4-1 v Rev 26

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 Interlaboratory 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 5A Turkey Point Supplemental Radiological Environmental Monitoring Program ............................................. 5A - 1 Appendix 5B Turkey Point Groundwater Sampling Program to Support the Industry Initiative on Groundwater Protection>>>>>>>>>>>>>>>>>.. 5B - 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 (/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 Rev 26

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 Rev 26

SECTION 1 ADMINISTRATIVE CONTROLS Rev 26

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 Rev 26

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 Rev 26

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 thereof.

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 Rev 26

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

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 tanks exceeding the limits of Technical Specification 3.7.9.

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

i. A list with a description of all leaks or spills that have been communicated to State and Local Officials in accordance with the INDUSTRY INITIATIVE (EV-AA-100-1000, Ground Water Protection Program, Communication/Notification Plan).

ii. Groundwater sample results that have been taken in support of the INDUSTRY INITIATIVE (EV-AA-100, Fleet Ground Water Protection Program), unless they are from locations that are described in the Radiological Environmental Monitoring Program (REMP) and will therefore be reported in the Annual Radiological Environmental Operating Report. See Appendix 5B for details.

1-4 Rev 26

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

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

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

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

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

d. Results from the Turkey Point Groundwater Sampling Program taken to comply with Industry initiative.

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

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

1-5 Rev 26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS 1.5 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout the Offsite Dose Calculation Manual.

ACTION 1.5.1 An ACTION shall be that part of a control which prescribes remedial measures required under designated conditions.

ANALOG CHANNEL OPERATIONAL TEST 1.5.2 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, interlock, and/or Trip Setpoints such that the setpoints are within the required range and accuracy CHANNEL CALLIBRATION 1.5.3 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.5.4 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

1-6 Rev 26

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

DOSE EQUIVALENT I-131 1.5.5 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microCurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those as referenced in the Technical Specifications.

FREQUENCY NOTATION 1.5.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.5-1 FUNCTIONAL - FUNCTIONALITY 1.5.7 Functional / Functionality - Functionality is an attribute of systems, structures, and components (SSC) that is not controlled by the Technical Specifications (TS). An SSC is functional or has functionality when it is capable of performing its specified current licensing basis (CLB) function, as set forth in the CLB. Functionality does not apply to specified TS functions, but does apply to the ability of non-TS SSCs to perform specified CLB functions that have a necessary support function.

GAS DECAY TANK SYSTEM 1.5.8 A GAS DECAY TANK SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System off gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

INDUSTRY INITIATIVE 1.5.9 Nuclear Energy Institute Initiative on Managing Situations Involving Inadvertent Radiological Releases into Groundwater (The INDUSTRY INITIATIVE has been adopted through EV-AA-01, Fleet Ground Water Protection Program).

INITIAL CALIBRATION 1.5.10 INITIAL CALIBRATION - An INITIAL CALIBRATION is the determination of the detector sensitivity when the detector is exposed in a known geometry to radiation from sources of known energies and activity levels traceable to National Institute of Standards & Technology (NIST). The vendor usually performs this calibration. Furthermore, subsequent CHANNEL CALIBRATIONS should include the use of a TRACEABLE SOURCE positioned in a reproducible geometry with respect to the sensor whose effect on the system was established at the time of the initial calibration. This CHANNEL CALIBRATION will establish the dynamic capabilities of a detector, electronics and power supplies in such a way as to ensure that the detector will perform its basic task of sensing radiation at the predetermined minimum detectable concentration based on the Initial Calibration.

1-7 Rev 26

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

MEMBER(S) OF THE PUBLIC 1.5.11 MEMBER(S) OF THE PUBLIC shall mean any individual except when that individual is receiving an occupational dose.

OFFSITE DOSE CALCULATION MANUAL 1.5.12 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Tech Spec Section 6.8.4.F and (2) descriptions of the information that should be included in the Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Operating Report required by Controls 1.3 and 1.4.

OPERABLE - OPERABILITY 1.5.13 A system, subsystem, division, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified TS function(s), and when all necessary attendant instrumentation, controls, normal and emergency electrical power, cooling and seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, division, component, and device to perform its function(s) are also capable of performing their related support function(s).

Operability is defined in the site TS.

OPERATIONAL MODE - MODE 1.5.14 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in the Technical Specifications.

PROCESS CONTROL PROGRAM 1.5.15 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analysis, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and Federal and State regulations, burial ground requirements, and other requirements governing the disposal of radioactive waste.

1 -8 Rev 26

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

PURGE - PURGING 1.5.16 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER 1.5.17 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant as stated in the Technical Specifications.

REPORTABLE EVENT 1.5.18 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

SITE BOUNDARY 1.5.19 The SITE BOUNDARY shall mean that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee, see UFSAR Chapter 2.

Figure 2.2-4, Site Area Map.

SITE ENVIRONS 1.5.20 The SITE ENVIRONS are the locations outside of the nuclear power plant systems, structures, or components as described in the final safety analysis report or the ODCM.

SOURCE CHECK 1.5.21 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

THERMAL POWER 1.5.22 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRACEABLE SOURCE 1.5.23 TRACEABLE SOURCE - Radiation sources that are related not only to the reference sources that were used for the INITIAL CALIBRATION but also certified by the National Institute of Standards & Technology (NIST). These transfer sources will calibrate the detector by positioning it in a reproducible geometry as prescribed by the INITIAL CALIBRATION.

1-9 Rev 26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS UNPLANNED DISCHARGE 1.5.24 An UNPLANNED DISCHARGE is the unintended or unexpected discharge of liquid or airborne radioactive material to the unrestricted area. Examples of an unplanned discharge would include:

1. The unintentional discharge of a wrong gas decay tank.

2. The unintentional discharge of a bulk liquid radioactive waste tank to the unrestricted area.

3. The failure of a radiation monitor to perform the automatic alarm/trip function and radioactive material is discharged to the environment.

UNPLANNED RELEASE 1.5.25 An UNPLANNED RELEASE is the unintended or unexpected release of liquid or airborne radioactive material to the onsite environment. Examples would include:

1. A plant occurrence that requires reporting under 10CFR50.72 or 10CFR 50.73 limits.

2. Releases that do not have prepared documentation and reach the site environs, but are not anticipated operational occurrences.

UNRESTRICTED AREA 1.5.26 An UNRESTRICTED AREA shall mean an area, access to which is neither limited nor controlled by the licensee.

1 - 10 Rev 26

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

VENTILATION EXHAUST TREATMENT SYSTEM 1.5.27 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioactive iodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodine or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING 1.5.28 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

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

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

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

NA Not applicable.

P Completed prior to each batch release 1 - 11 Rev 26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS FIGURE 1.5 - 2 PLANT AREA MAP Gaseous Effluent Release Points Liquid Effluent Release Points

1. Plant Vent (Unit 4 Spent Fuel Pool Vent) 5. Effluent from Liquid Radwaste System

2. Unit 3 Spent Fuel Pool Vent 6. Effluent from Liquid Radwaste System

7. Unit 3 Steam Generator Blowdown

8. Unit 4 Steam Generator Blowdown

9. Storm Drain

10. Storm Drain

11. Storm Drain

12. Storm Drain 1 - 12 Rev 26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS 1.6 APPLICABILITY OF CONTROLS 1.6.1 Compliance with the Controls, contained in this ODCM, is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met, except as provided in Control 1.6.7.

1.6.2 Noncompliance with a specification shall exist when the requirements of the Control and associated ACTION requirements are not met within the specified time intervals, except as provided in Control 1.6.7. If the Control is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

1.6.3 When a Control associated with a Technical Specification is not met, except as provided in the associated ACTION requirements, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to place the unit, as applicable, in:

a. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

b. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

c. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Control. Exceptions to these requirements are stated in the individual control.

This control is not applicable in MODES 5 or 6.

1.6.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for a Control associated with a Technical Specification are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual controls.

1 - 13 Rev 26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 1.0 ADMINISTRATIVE CONTROLS 1.6 APPLICABILITY OF CONTROLS (continued) 1.6.5 Controls including the associated ACTION requirements shall apply to each unit individually unless otherwise indicated as follows:

a. Whenever the Control refers to systems or components which are shared by both units, the ACTION requirements will apply to both units simultaneously.

b. Whenever the Control applies to only one unit, this will be identified in the APPLICABILITY section of the Control: and

c. Whenever certain portions of a Control contain operating parameters, Setpoints, etc., which are different for each unit, this will be identified in parentheses, footnotes or body of the requirement.

1.6.6 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report as stated in the Controls within sections 2.0, 3.0, 4.0, or 5.0.

1.6.7 Equipment removed from service or declared inoperable / non-functional to comply with ACTION requirements may be returned to service under administrative controls solely to perform testing required to demonstrate its OPERABILITY / FUNCTIONALITY or the OPERABILITY / FUNCTIONALITY of other equipment. This is an exception to Controls 1.6.1 and 1.6.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY / FUNCTIONALITY .

1.7 SURVEILLANCE REQUIREMENTS 1.7.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement.

1.7.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

1.7.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Control 1.7.2, shall constitute noncompliance with the OPERABILITY / FUNCTIONALITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Surveillance Requirements do not have to be performed on inoperable / non-functional equipment.

1 - 14 Rev 26

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

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

1.8 REFERENCES

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

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

3. No document is listed for this reference.

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

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

6. EV-AA-01, Fleet Ground Water Protection Program

7. PC/M 08-046, Auxiliary Exhaust Duct Removal and CR 2008-36865, Abandon Laundry Ductwork

8. CR 2009-11943, SPING Operability

9. CR 2008-22263, Site Boundary Changes 1 - 15 Rev 26

SECTION 2 RADIOACTIVE LIQUID EFFLUENTS REV. 26

TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS OBJECTIVES & SYSTEM DESCRIPTION A. Objectives To provide calculational methodology needed to assure compliance with 10CFR20 and 10CFR50, which require the following determinations and surveillance:

o The concentration of radioactive materials released in liquid effluents.

o The concentrations of radioactive materials released are maintained within the limits of Control 2.2.

o Quarterly and annual cumulative dose contributions to a member of the public from radioactivity in liquid effluents released from each unit to unrestricted areas are maintained within the limits of Control 2.3.

o Projected doses due to liquid releases to unrestricted areas are maintained within the limits of Control 2.4.

o Operation of appropriate portions of the Liquid Radwaste Treatment System when projected doses exceed limits of Control 2.4.

o The functionality of Liquid Radwaste System is verified by meeting Controls 2.2 and 2.3 B. Bases Radioactive liquid effluents from Turkey Point Units 3 and 4 are released through radiation monitors which provide an alarm and automatic termination of radioactive releases. There are three discharge points from the units: steam generator blowdown from each unit and a common radwaste monitor tank discharge. The liquid effluent monitoring instrumentation and controls at Turkey Point for controlling and monitoring normal radioactive releases in accordance with Turkey Point Technical Specification 6.8.4.f consist of the following :

1 Liquid Radwaste System Potentially radioactive liquid waste from Units 3 and 4 Chemistry laboratories, containment sumps, floor drains, showers, and miscellaneous sources are collected in waste hold up tanks. These wastes are processed through a demineralizer system and the effluent stored in one of the three waste monitor tanks or one of two monitor tanks (Refer to Figure 2-1). Laundry wastes are normally segregated and sent to one of two monitor tanks.

2-1 REV. 26

TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS OBJECTIVES & SYSTEM DESCRIPTION (continued)

B. Bases, Liquid Radwaste System, continued Liquid waste in the waste monitor tanks and monitor tanks are isolated and recirculated for a minimum of one (1) tank volume prior to sampling.

Liquids in these tanks are released after sampling and analysis in accordance with ODCM Table 2.2-1. The discharge from the waste monitor and monitor tanks is monitored by a radioactive liquid effluent monitor. Since these liquid effluents are a mixture from both Units 3 and 4, the measured releases from the common discharge point are apportioned equally to both Units 3 & 4. The dose limit per reactor is applied to the common discharge point when routine releases are made.

This ensures that the dose limit of any single unit is not exceeded by the site.

2 Steam Generator Blowdown Units 3 and 4 steam generator blowdown can be discharged directly from the blowdown flashtanks to the condenser cooling water mixing basin. The activity of each steam generator blowdown discharge (a composite) is monitored prior to the Blowdown Flash Tank for Unit 3 and 4 respectively.

Releases from the steam generator blowdown are sampled and analyzed in conformance with ODCM Table 2.2-1.

3 Storm Drains Storm drains from Units 3 and 4 discharge into both the circulating water intake and the condenser cooling water mixing basin. Storm drains are sampled and analyzed in accordance with ODCM Table 2.2-1.

4 Radioactivity Concentration in Liquid Waste The concentration of radionuclides in liquid waste is determined by sampling and analysis in accordance with ODCM Table 2.2-1. If a radionuclide is below its LLD, and the calculated LLD concentration is below the LLD concentration value specified in ODCM Table 2.2-1 then it is not reported as being present in the sample. When the radionuclide's calculated LLD is greater than the LLD listed in ODCM Table 2.2-1, the calculated LLD should be assigned as the activity of the radionuclide.

2-2 REV. 26

TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS OBJECTIVES & SYSTEM DESCRIPTION (continued)

Bases, Liquid Radwaste System (continued)

5. Radioactivity Concentration in Water at the Restricted Area Boundary Control 2.2 requires that the concentration of radioactive material, other than noble gases, in liquid effluent released into an unrestricted area not exceed 10 times the effluent concentration specified in 10 CFR Part 20, Appendix B, Table 2, Column 2.

A maximum concentration, 2 x 10-4 µCi/ml, for noble gas entrained in aqueous releases into an unrestricted area applies separately since the potential exposure route, immersion in water, differs from that upon which Part 20, Appendix B is based.

Radioactive material in liquid effluent from Turkey Point is diluted by condenser cooling water from fossil units 1 and 2 and from nuclear units 3 and 4 in the condenser cooling water mixing basin. Water in the basin flows into an on site closed cooling canal system. Liquid effluent does not actually leave the site in a surface discharge. For the purpose of compliance with Control 2.2, the total condenser cooling water flow from operating condenser cooling water pumps at the four units is assumed for dilution and the restricted area boundary is assumed to be at the end of the condenser cooling water mixing basin where water enters the cooling canal system.

Methods 2.2.1 and 2.2.2 describe methods used to assess compliance with Control 2.2. Effluent monitor alarm/trip setpoints are computed on the same basis as described in Methods 2.1.1 and 2.1.2. If an alarm/trip setpoint is not exceeded, aqueous effluents are deemed to comply with Control 2.2.

The functionality of the Liquid Radwaste System is considered verified by virtue of meeting Controls 2.1 and 2.2. Normally, batch releases from the Laundry, and continuous releases from Steam Generator Blowdown are not processed. When necessary, the Laundry and the Steam Generator Blowdown can be diverted to the Liquid Radwaste System for processing.

2-3 REV. 26

TURKEY POINT UNITS 3 & 4 OFFSITE DOSE CALCULATION MANUAL 2.0 RADIOACTIVE LIQUID EFFLUENTS FIGURE 2-1 RADIOACTIVE LIQUID WASTE Molybdate Holdup Tank Unit 3 Tendon Gallery Sump East Storm Drain 2-4 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 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 Blowdown Effluent Line 1 ** 2.1.2

2. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line 1* 2.1.3

b. Steam Generator Blowdown 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 ALARM/TRIP 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQUIVALENT I-131, or

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curies/gram DOSE EQUIVALENT I-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 continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

Ab S f Sb =

• gb + Bkg FECb Eqn 2.1-1 where:

Sb = radiation monitor alarm setpoint for a batch release, (cpm)

Ab = 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 ALARM/TRIP 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.

Bkg = background (cpm)

Sf = 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.

Ac S f Sc =

• g c + Bkg FECc Eqn 2.1-2 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 ALARM/TRIP 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.

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. The assigned fraction for releases made from each units Steam Generator Blowdown 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 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 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 Sf are based on allowing 10% of all releases to be made from each units Steam Generator Blowdown 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:

Ab

• S f Sb =

• gb + Bkg FECb where:

Sb = radiation monitor alarm setpoint for a batch release, (cpm)

Ab = 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)

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. 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:

FECb = 6 x 10-4 Ab = 8.85 x 10-5 µCi/ml gb = 15,000 cpm/µCi/ml Sf = 0.7 Bkg = 10,000 cpm 8 .85 x 10 -5 x . 7 Sb = x 1.5 x 10 4 + 1 X 10 4 = 11, 550 cpm 6 x 10 -4 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) , µCi/ml P P Principle Gamma 5 x 10-7

1. Batch Waste Each Batch Each Batch Emitters (3)

Release Tanks(2)

I-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 (4)

Gross Alpha 1 x 10-7 P Q Sr-89, Sr-90 5 x 10-8 Each Batch Composite (4)

Fe-55 1 x 10-6

2. Continuous Principal Gamma 5 x 10-7 Releases (5)

W W Emitters (3)

a. Steam Generator Blowdown(7)

I-131 1 x 10-6 Dissolved and Entrained Gases M (8) M (8) 1 x 10-5 (Gamma Emitters)

M (8) H-3 1 x 10-5 (8)

W Composite (6)

Gross Alpha 1 x 10-7 Q (8) Sr-89, Sr-90 5 x 10-8 W (8) Composite (6)

Fe-55 1 x 10-6

b. Storm Drain Principle Gamma 5 x 10-7 M M Emitters (3)

I-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 E V (2.22 x 106) Y [exp (-t)]

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,

= the radioactive decay constant for the particular radionuclide, and t = 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 t 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.

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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 :

F1 C Zi = C i

• Eqn. 2.2 1 F2 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 I-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 :

C zi C zi FEC b = for gamma emitting isotopes + for beta emitting isotopes i

EC i i EC i 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.

Czi = 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:

Cb FECb = Eqn. 2.2-3 5 x10 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. FECc is estimated with the equation:

C zi C zi FEC c = for gamma emitting isotopes + for beta emitting isotopes i

EC i i EC i 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:

Cc FECc = Eqn. 2.2-5 5 x10 7 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:

FECT = FECb + FECc Eqn 2.2-6 Where:

FECT = 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 .

F1 C zi = Ci

• F2 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 10-10 Cs-137 5 x 10-7 8 x 10-5 4.0 x 10-11 I-131 3 x 10-7 8 x 10-5 2.4 x 10-11 Fe-55 4 x 10-5 8 x 10-5 3.2 x 10-09 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 10-5 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 C zi C zi FEC b = for gamma emitting isotopes + for beta emitting isotopes i

EC i i EC i 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:

FEC for a release must be less than 1 or the release cannot be made. FEC for the batch release in example 1 above is calculated as follows:

Nuclide Czi ECi* Czi/ECi FECb Co-60 6.4 x 10-9 3 x 10-5 2.1 x 10-4 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 Cr-51 5.6 x 10-11 5 x 10-3 1.1 x 10-8 1.1 x 10-8 Mn-54 4.0 x 10-10 3 x 10-4 1.3 x 10-6 1.3 x 10-6 Cs-137 4.0 x 10-11 1 x 10-5 4.0 x 10-6 4.0 x 10-6 I-131 2.4 x 10-11 1 x 10-5 2.4 x 10-6 2.4 x 10-6 Fe-55 3.2 x 10-09 1 x 10-4 3.2 x 10-5 3.2 x 10-5 Sr-90 1.6 x 10-11 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 5.6 x 10-6 -- 5.9 x 10-3 5.9 x 10-3

• Use ten times the value of the Effluent Concentration (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 1.5 mRem to the whole body and 5 mRem to any organ during any calendar quarter and to 3 mRem to the whole body and 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 :

Cik

• F lk

• t k D = 0.23 shoreline Ai

• V

• ie k i 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) 1Ci 60 min 3785ml 0.23 = units conversion constant = 6 x x 10 uCi hr gal Ai = 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, (mRem/Ci*gal/min)

Cik = 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)

Flk = 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 ie = effective decay constant (i + F3/V, min-1).

where:

i = 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.

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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.

Cik

• F lk

• t k D = 0.23 k i Ai shoreline V

• ie where:

D= total body or organ dose due to irradiation by radionuclides on the shoreline which originated in a liquid effluent release, (mRem).

1Ci 60 min 3785ml 0.23 = units conversion constant = 6 x x 10 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).

Flk = 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.

ei = effective decay constant (i + F3/ V, minute -1 ).

where:

i = 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 Cik(µCi/ml)

Co-60 4 x 10-4 Co-58 1 x 10-5 Cr-51 4 x 10-6 Cs-134 5 x 10-6 Cs-137 2 x 10-6 Mn-54 2 x 10-5 I-131 1 x 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 (Flk) = 100 gpm.

The total period of time for the releases (tk) was 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.

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 Cik Ai Flk tt (0.23)AixCikx Flkxtt i F3/V ei Vei 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 5.8E-3 Co-58 1E-5 1.67E+2 100 15 5.76E-1 6.80E-6 6.0E-5 6.68E-5 2.50E+5 2.3E-6 Cr-51 4E-6 2.06E+0 100 15 2.84E-3 1.74E-5 6.0E-5 7.74E-5 2.90E+5 9.8E-9 Cs-134 5E-6 3.08E+3 100 15 5.31E+0 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+0 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+0 1.54E-6 6.0E-5 6.15E-5 2.31E+5 1.8E-5 I-131 1E-6 7.59E+0 100 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, i = 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 considered 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:

31

• 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 II.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:

31 x D 31 x 7 .5 x 10 -2 mrem P = = = 1.55 x 10 -1 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 lifes) 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 for the 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 Daltons 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:

QT = ( Larea

• EVave * (LTConc

• 1.0E-09 ))

Where:

QT = 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.

LTConc = Average tritium concentration.

1.0E-09 = Ci/1.0E12 pCi

• liter/1000cm3 *1.0E6cm3/meter3 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.

Qtsect = (Qt

• X/Q

• 3.17E+04)

Where:

Qtsect = Total tritium concentration from the individual section at point of interest (pCi/m3)

Qt = 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 = (Qtsect )* (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 APPENDIX 2A 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 CI/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 CO-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 CO-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 7.11E-01 7.11E-01 8.12E-01 7.11E-01 SR-89 1.71E-03 1.71E-03 1.71E-03 1.71E-03 1.71E-03 1.71E-03 1.98E-03 1.71E-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 MO-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+00 8.69E+00 8.69E+00 8.69E+00 8.69E+00 8.69E+00 1.01E+01 8.69E+00 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-11OM 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 1.81E+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+00 3.04E+00 3.04E+00 3.04E+00 3.04E+00 3.04E+00 3.57E+00 3.04E+00 TE-131M 8.41E-01 8.41E-01 8.41E-01 8.41E-01 8.41E-01 8.41E-01 3.68E+01 8.41E-01 TE-132 3.66E+00 3.66E+00 3.66E+00 3.66E+00 3.66E+00 3.66E+00 4.31E+00 3.66E+00 I-131 1.36E+00 1.36E+00 1.36E+00 1.36E+00 1.36E+00 1.36E+00 1.65E+00 1.36E+00 I-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+00 1.52E+00 1.52E+00 1.52E+00 1.52E+00 1.52E+00 1.72E+00 1.52E+00 CE-141 1.08E+00 1.08E+00 1.08E+00 1.08E+00 1.08E+00 1.08E+00 1.22E+00 1.08E+00 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+00 8.94E+00 8.94E+00 8.94E+00 8.94E+00 8.94E+00 1.03E+01 8.94E+00 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+00 2.06E+00 2.06E+00 2.06E+00 2.06E+00 2.06E+00 2.43E+00 2.06E+00 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 CO-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 CO-60 9.45E+03 9.45E+03 9.45E+03 9.45E+03 9.45E+03 9.45E+03 1.11E+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+00 3.97E+00 3.97E+00 3.97E+00 3.97E+00 3.97E+00 4.53E+00 3.97E+00 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+00 2.36E+00 2.36E+00 2.36E+00 2.36E+00 2.36E+00 2.79E+00 2.36E+00 Y-91 4.77E-01 4.77E-01 4.77E-01 4.77E-01 4.77E-01 4.77E-01 5.35E-01 4.77E-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+00 2.41E+00 2.41E+00 2.41E+00 2.41E+00 2.41E+00 2.82E+00 2.41E+00 NB-95 6.01E+01 6.01E+01 6.01E+01 6.01E+01 6.01E+01 6.01E+01 7.07E+01 6.01E+01 MO-99 2.60E+00 2.60E+00 2.60E+00 2.60E+00 2.60E+00 2.60E+00 3.00E+00 2.60E+00 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 3.87E-01 3.87E-01 3.87E-01 3.87E-01 3.87E-01 3.87E-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+00 4.69E+00 4.69E+00 4.69E+00 4.69E+00 4.69E+00 2.05E+02 4.69E+00 TE-132 2.05E+01 2.05E+01 2.05E+01 2.05E+01 2.05E+01 2.05E+01 2.41E+01 2.05E+01 I-131 7.59E+00 7.59E+00 7.59E+00 7.59E+00 7.59E+00 7.59E+00 9.22E+00 7.59E+00 I-133 1.09E+00 1.09E+00 1.09E+00 1.09E+00 1.09E+00 1.09E+00 1.33E+00 1.09E+00 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+00 8.46E+00 8.46E+00 8.46E+00 8.46E+00 8.46E+00 9.59E+00 8.46E+00 CE-141 6.02E+00 6.02E+00 6.02E+00 6.02E+00 6.02E+00 6.02E+00 6.79E+00 6.02E+00 CE-143 1.02E+00 1.02E+00 1.02E+00 1.02E+00 1.02E+00 1.02E+00 1.16E+00 1.02E+00 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-LLI 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. 0. 0. 0. 0. 0.

FE-59 2.53E+01 2.53E+01 2.53E+01 2.53E+01 2.53E+01 2.53E+01 2.98E+01 2.53E+01 CO-58 3.50E+01 3.50E+01 3.50E+01 3.50E+01 3.50E+01 3.50E+01 4.10E+01 3.50E+01 CO-60 1.97E+03 1.97E+03 1.97E+03 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+01 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-01 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 2.31E-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 MO-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 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.18E+01 1.01E+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-110M 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+01 6.35E+01 5.51E+01 SB-125 2.11E+02 2.11E+02 2.11E+02 2.11E+02 2.11E+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+00 3.54E+00 3.54E+00 3.54E+00 3.54E+00 3.54E+00 4.18E+00 3.54E+00 TE-131M 9.80E-01 9.80E-01 9.80E-01 9.80E-01 9.80E-01 9.80E-01 4.28E+01 9.80E-01 TE-132 4.28E+00 4.28E+00 4.28E+00 4.28E+00 4.28E+00 4.28E+00 5.03E+00 4.28E+00 I-131 1.59E+00 1.59E+00 1.59E+00 1.59E+00 1.59E+00 1.59E+00 1.93E+00 1.59E+00 I-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+02 9.48E+02 9.48E+02 9.48E+02 9.48E+02 1.11E+03 9.48E+02 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+00 1.77E+00 1.77E+00 1.77E+00 1.77E+00 1.77E+00 2.00E+00 1.77E+00 CE-141 1.26E+00 1.26E+00 1.26E+00 1.26E+00 1.26E+00 1.26E+00 1.42E+00 1.28E+00 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+01 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.

B. 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 (Contd)

B. BASIS, (Contd)

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/m3 (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, I-131, I-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 either the inhalation or grass-cow-milk pathway. The dose from tritium, I-131, I-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 (Contd)

B. BASIS, (Contd)

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 (Contd)

C. GASEOUS RADWASTE SYSTEM (Contd)

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 units 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 (Contd)

C. GASEOUS RADWASTE SYSTEM, (Contd)

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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing if both the following conditions are met:

(1) Analysis shows that the DOSE EQUIVALENT I-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 (Contd)

C. GASEOUS RADWASTE SYSTEM, (Contd)

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

N j

• F

• 28317 Qj =

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 cpm noble gas gamma radiation,

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.

Qj = C x Fj x Tj where:

C = The concentration of the individual isotope released.

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

Fj = Mw - (Mb + Ms)

Mw = Mass rate of make up water Mb = Mass rate of blowdown 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 (Contd)

C. GASEOUS RADWASTE SYSTEM, (Contd)

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:

Qij = Qj

• fi where:

Qij = 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 ventilation systems exhausting into the Plant Vent Stack. Unit 3 Spent Fuel Pit Vent, Containment purges, and Steam Generator Blowdown 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 (Contd)

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 Blowdown 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 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.

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 / 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 / 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 CONTROL 3.1 Radioactive Gaseous Effluent Monitoring Instrumentation, Operability / Functionality and Alarm/Trip Setpoints, (Contd)

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 / Trip Setpoints, (Contd)

TABLE 3.1-1 (Contd)

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 (Contd)

TABLE 3.1-1 (Contd)

TABLE NOTATION

• At all times.

1. Applies during Mode 1, 2, 3, and 4.

1. 1. 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 released to the environment provided that prior to initiating the release:

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

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 3.1.2 - With the number of channels 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the channel being declared non-functional, and analyzed at least weekly.

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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 (Contd)

TABLE 3.1-1 (Contd)

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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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 / Trip Setpoints, (Contd)

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, (Contd)

TABLE 3.1-2 (Contd)

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

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

TABLE 3.1-2 (Contd)

TABLE NOTATIONS

• At all times during periods of release.

1. Applies during MODE 1, 2, 3, and 4.

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

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

(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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, (Contd)

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

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

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

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

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

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

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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, (Contd)

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

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.

Ci h

• Sf i Eqn 3.1-1 S = 1.06 + Bkg F * /Q (Ci

• DFi )

i where:

S = The alarm setpoint, (cpm) 1.06 = conversion constant (500 mRem/yr*60 sec/min

• 35.32 ft3/m3*

1m3/106cm3) 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)

/Q = atmospheric dispersion factor at the off-site location of interest, (sec/m3)

Ci = concentration of radionuclide 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/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 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, (Contd)

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

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, /Q, will be based on prevailing meteorological conditions or on reference meteorological conditions. The minimum atmospheric dispersion off site derived from reference meteorological conditions at the site boundary is 1.3 x 10-6 sec/m3 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.

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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, (Contd)

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

DR

• h

• S f

• 3600

• t

• V R S = + BKG Eqn 3.1-2 TA anip

• d / Q where:

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

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

(µCi/m3 )

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).

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

Sf = A factor to allow for multiple sources from different or common release points. The allowable operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the release sources. For gas releases, this fraction is assigned as follows: 0.8 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, (Contd)

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

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 / 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 instruments 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 release requirements of Control 3.3 shall be such that concentrations as low as 1 x 10-6

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, (Contd)

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

TABLE 3.1-3 DOSE FACTORS, DFi , FOR EXPOSURE TO A SEMI-INFINITE CLOUD OFNOBLE GAS mRem yr µCi/ m3 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, (Contd)

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

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.

Ci h

• Sf i S = 1. 06 + Bkg F * /Q (C i

• DF i )

i where:

S = The alarm setpoint (CPM).

1.06 = Conversion factor; 500 mRem

• 60 sec

• 35.32 ft3

• 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).

/Q = atmospheric dispersion factor at the offsite 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 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 / Trip Setpoints, (Contd)

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

EXAMPLE CALCULATION: Determining the Noble Gas Monitor Alarm Setpoint, (Contd)

DFi = factor for exposure to a semi-infinite cloud of noble gas mRem see Table 3.1-3. (yr-µCi/m3)

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

Bkg = monitoring instrument background (cpm).

Example:

The measured concentration of noble gases to be discharged to the atmosphere are:

Radionuclide Ci(µCi/cc)

-5 Kr-85m 3.6 x 10

-4 Kr-85 2.8 x 10

-6 Kr-87 2.5 x 10

-5 Kr-88 1.4 x 10

-2 Xe-131m 1.0 x 10

-2 Xe-133 4.3 x 10

-4 Xe-135 6.0 x 10

-5 Ar-41 7.7 x 10 Determine the alarm setpoint, S (cpm) when:

h = 2.5 x 108 cpm

µCi/cc F = 8.0 x 104 ft3 min

/Q = 1.3 x 10-6 sec m3 Sf = 0.8 Bkg = 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 / Trip Setpoints, (Contd)

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

EXAMPLE CALCULATION: Determining the Noble Gas Monitor Alarm Setpoint, (Contd)

Calculate the effect of a ground level release as follows:

Radionuclide Ci DFi Ci x DFi Kr-85m 3.6 x 10-5 1.17 x 103 4.2 x 10-2 Kr-85 2.8 x 10-4 1.61 x 101 4.5 x 10-3 Kr-87 2.5 x 10-6 5.92 x 103 1.5 x 10-2 Kr-88 1.4 x 10-5 1.47 x 104 2.1 x 10-1 Xe-131m 1.0 x 10-2 9.15 x 101 9.1 x 10-1 Xe-133 4.3 x 10-2 2.94 x 102 1.3 x 101 Xe-135 6.0 x 10-4 1.81 x 103 1.1 x 100 Ar-41 7.7 x 10-5 8.85 x 103 6.8 x 10-1 Ci = 5.4 x 10-2 CiDFi = 1.6 x 101 Calculate the setpoint as follows:

-2 S = 1.06 2.5 x 10 8

• 0.8 5.4 x 10 + 600 8.0 x 10 4

• 5.8 x 10 -7 1.6 x 10 1

= 1.06 [ 4.31 x 109 ] [ 3.4 x 10-3 ] + 600

= 1.54E+07 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 Iodine-131, for Iodine-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.

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

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

1. Gas Decay Tank P P Principal Gamma Emitters (2) 1 x 10-4

( Batch) Each Tank, Grab Sample Each Tank

2. Containment Purge or P (6) P (6) Principal Gamma Emitters (2) 1 x 10-4 Venting (Batch)

Grab Sample Each PURGE H-3 1 x 10-6

3. Plant Vent (includes Unit 4 M (6) M (6) Principal Gamma Emitters (2) 1 x 10-4 Spent Fuel Pit Building Grab Sample Gas Sample Vent and U3 & U4 SJAE vents )

M (4), (5) M H-3 1 x 10-6 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 Continuous (3) W (7) I-131 1 x 10-12 listed in 3 and 4 (above)

Charcoal Sample Continuous (3)

W (7) Principal Gamma Emitters (2) 1 x 10-11 Particulate Sample Continuous (3)

M Gross Alpha Composite Particulate sample 1 x 10-11 Continuous (3) Q Composite Particulate sample Sr-89, Sr-90 1 x 10-11 (3)

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, (Contd)

TABLE 3.2-1, (Contd)

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 s b E x V x (2.22 x 106) x Y x [exp (-t)]

Where:

LLD = The "a priori" lower limit of detection as defined above as 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 microCurie, Y = The fractional radio chemical yield, when applicable,

= The radioactive decay constant for the particular radionuclide, and t = 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 t 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, (Contd)

TABLE 3.2-1 (Contd)

TABLE NOTATIONS (Contd)

(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, I-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 those 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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

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, (Contd)

TABLE 3.2-1 (Contd)

TABLE NOTATIONS (Contd)

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

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

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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

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 Eqn 3.2-1 where:

TB = Dose rate to total body from noble gases, (mRem/year)

/Q = atmospheric dispersion factor at the off-site location of interest, (sec/m3) t = Averaging time of release, i.e., increment of time during which Qi was released, (year)

Qi = quantity of noble gas radionuclide i released during the averaging time,

(µCi)

Pi = 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 /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 /Q = 1.3 x 10-6 sec/m3.

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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

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 and irradiated by a semi-infinite cloud of the noble gases. The dose rate to skin is calculated using the equation:

Eqn. 3.2-2 where:

TB = dose rate to skin from radioactive noble gases, (mRem/year)

Si = 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/m3 )

1.11 = ratio of tissue dose equivalent to air dose in a radiation field, (mRem/mRad)

Ai = 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 )

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 /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 /Q = 1.3 x 10-6 sec/m3.

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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

C. H-3, I-131, I-133 and PARTICULATE DOSE RATE The dose rate to any organ due to H-3, I-131, I-133 and radioactive material in particulate form with a half-life of more than 8 days is calculated with the equation:

1 Danp =

• d Qik

• TA anip Eqn 3.2-3 3600t Q k i 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) d/Q = atmospheric dispersion factor, adjusted for depletion by deposition(sec/m3).(Alternately /Q, unadjusted, may be used).

Qik = quantity of radionuclide, i, released during time increment, t, based on analysis, k (µCi).

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 (air-grass-cow-milk), mRem/yr  ; See Appendix 3B.

3

(µCi/m )

When the dose rate due to H-3, I-131, I-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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

C. H-3, I-131, I-133 and PARTICULATE DOSE RATE, (Contd)

For the radioiodines and particulates with half-lives greater than eight days, the effective dose transfer factor, TAanip, is based solely on the radioiodines (I-131, I-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 the site boundary 1950 meters WNW of the plant and the d/Q value is 5.0 x 10-7 sec/m3. 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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

Table 3.2-2 Transfer Factors for Maximum Dose to a Person Offsite due to Radioactive Noble Gases Air Dose Transfer Factors Pi Si mRem mRem Radionuclide (µCi sec/m3) (µCi sec/m3)

Kr-83m 2.4E-9 --

Kr-85m 3.7E-5 4.6E-5 Kr-85 5.1E-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 3.1E-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 B-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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

Table 3.2-3 Transfer Factors for Maximum Offsite Air Dose Air Dose Transfer Factors Ai Ai mRad mRad Radionuclide (µCi sec/m3 ) (µCi sec/m3 )

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 4.8E-4 9.3E-5 Kr-89 5.5E-4 3.4E-4 Kr-90 5.2E-4 2.5E-4 Xe-131m 4.9E-6 3.5E-5 Xe-133m 1.0E-5 4.7E-5 Xe-133 1.1E-5 3.3E-5 Xe-135m 1.1E-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 1.5E-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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

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 /Q = 1.3 x 10-6 sec/m3. 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:

1 DTB =

• Q i

• P i Q t i where:

TB = Dose rate to total body from noble gases, (mRem/year)

/Q = atmospheric dispersion factor at the off-site location of interest, (sec/m3) t = Averaging time of release, i.e., increment of time during which Qi was released, (year)

Qi = quantity of noble gas radionuclide i released during the averaging time,

(µCi)

Pi = 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/m3 )

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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

EXAMPLE CALCULATIONS: Dose Rate Due to Gaseous Effluent, (Contd)

The total body dose is summarized in the following table:

Radionuclide Qi Pi QiPi Kr-85m 3.6E-2 3.7E-5 1.33E-6 Kr-85 2.8E-1 5.1E-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 QiPi 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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

EXAMPLE CALCULATIONS: Dose Rate Due to Gaseous Effluent, (Contd)

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:

1 TB = * [ Qi

• S i + 1.11 Qi

• Ai ]

Q t i where:

TB = dose rate to skin from radioactive noble gases (mRem/year)

Si= 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).

Ai = 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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

EXAMPLE CALCULATIONS: Dose Rate Due to Gaseous Effluent, (Contd)

The skin dose rate is summarized in the following table:

Nuclide Qi Si QiSi A i QiAi 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 1.51E-7 Kr-87 2.5E-3 3.1E-4 7.8E-7 2.0E-4 5.00E-7 Kr-88 1.4E-2 7.5E-5 1.1E-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 1.1E-5 4.73E-6 Xe-135 6.0E-1 5.9E-5 3.5E-5 6.1E-5 3.66E-5 Ar-41 7.6E-2 8.5E-5 6.5E-6 2.9E-4 2.20E-5 The value of QiSi = 2.11 E-4 and the value of QiAi = 1.21 E-4 D =1.3E-6 x 11.77 (2.11E-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 /Q is 1.3E-6 sec/m3 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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

EXAMPLE CALCULATIONS: Dose Rate Due to Gaseous Effluent, (Contd)

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:

1 D anp =

• d Qik

• TAanip 3600 t Q k i 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) d/Q = quantity of radionuclide, i, released during time increment, t, based on analysis, k, (µCi).

Qik = 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, (Contd)

METHOD 3.2: Dose Rate Due to Gaseous Effluent, (Contd)

EXAMPLE CALCULATIONS: Dose Rate Due to Gaseous Effluent, (Contd)

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 3B

(µCi/m3 )

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 I-131 3.5E-7 9.94E+11 3.48E+5 Cs-137 2.0E-6 0 0 Notes: The time factor 1/3600t = 1.27E-7 where t = 2184hrs/qtr The value of QikTAanip = 3.8E+8 The value of d/Q = 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, (Contd)

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:

D = Q j

• Ai Eqn 3.3-1 Q j i where :

D = noble gas gamma dose to air, (mRad)

Ai = 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/m3)

/Q = atmospheric dispersion factor at the off-site location of interest, (sec/m3)

Qj = 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 /Q = 1.3 x 10-6 sec/m3.

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 1

D = *

• A eff

• Qj 0 .8 Q j 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, (Contd)

METHOD 3.3.1: Noble Gas Gamma Radiation Dose, (Contd)

Aeff = 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:

Aeff = 1.4 x 10-5 mRad

(µCi

• sec/m3)

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:

D = Q j

• Ai Eqn 3.3-3 Q j i where:

D = noble gas beta dose to air, (mRad)

Ai = 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/m3)

/Q = atmospheric dispersion factor at the off-site location of interest, (sec/m3)

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 /Q = 1.3 x 10-6 sec/m3.

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, (Contd)

METHOD 3.3.2 Noble Gas Beta Radiation Dose, (Contd)

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

D = *

• Aeff

• Q j 0 .8 Q j Eqn 3.3-4 where 0.8 = a conservative factor which, in effect, increases the estimated dose to compensate for variability in radionuclide distribution Aeff = 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 has 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:

Aeff = 3.4 x 10-5 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, (Contd)

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 on 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, (Contd)

METHODS 3.3.1 and 3.3.2: Noble Gas Gamma and Beta Radiation Dose, (Contd)

Table 3.3-1 Transfer Factors for Maximum Off site Air Dose Air Dose Transfer Factors Ai Ai mRad mRad Radionuclide (µCi sec/m3 ) (µCi sec/m3)

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 4.8E-4 9.3E-5 Kr-89 5.5E-4 3.4E-4 Kr-90 5.2E-4 2.5E-4 Xe-131m 4.9E-6 3.5E-5 Xe-133m 1.0E-5 4.7E-5 Xe-133 1.1E-5 3.3E-5 Xe-135m 1.1E-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 1.5E-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 - 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, (Contd)

EXAMPLE CALCULATION: AIR D0SE 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 /Q = 1.3 x 10-6 sec/m3. 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:

D = Q j

• Ai (Eqn 3.3-1)

Q j i where:

D = The noble gas dose to air, (mRad).

/Q = The atmospheric dispersion factor for a mixed-mode discharge, (sec/m3).

Qj = The measured radioactivity released via stack or vent during a single counting interval, j (µCi).

Ai = 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/m3) 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, (Contd)

EXAMPLE CALCULATION: AIR D0SE FROM NOBLE GASES, (Contd)

The noble gas gamma radiation dose is summarized in the following table.

Radionuclide Qj Ai QjAi Kr-85m 5.4E+1 3.9E-5 2.1E-3 Kr-85 5.4E+1 5.4E-7 2.9E-5 Kr-87 5.4E+1 2.0E-4 1.1E-2 Kr-88 5.4E+1 4.8E-4 2.6E-2 Xe-131m 5.4E+1 4.9E-6 2.6E-4 Xe-133 5.4E+1 1.1E-5 5.9E-4 Xe-135 5.4E+1 6.1E-5 3.3E-3 Ar-41 5.4E+1 2.9E-4 1.6E-2 The value of QjAi = 5.93E-2 D = 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, (Contd)

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 I-131 and I-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 ik

• F j

• t j Eqn 3.4-1 j

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) tj = 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, (Contd)

METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Contd)

A. Determining the Quantity of Iodine, Tritium, and Particulates, (Contd)

Note: A steam mass to determine other unmonitored releases may be determined using the following:

Fj = Mw - (Ml + Ms) where:

Mw = the measured mass of makeup water entering the secondary system during time interval, tj , (gm /sec).

Ml = 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 I-131, I-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, (Contd)

METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Contd)

B. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Contd)

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 I-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 DM k = *

• TG131

• Q ik Eqn 3.4 2 0.8 Q i 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 10-8 = 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, (Contd)

METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Contd)

B. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Contd)

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/m2 *sec)

Qik = the quantity of radionuclide, i (I-131 and I-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 10 -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 1011 mRem/yr

(µCi/m2 *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, (Contd)

METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Contd)

B. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Contd)

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 d

where:

-8 D ank = 3 .17 x 10 *

• Q ik

• TAanip 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).

3.17 x 10-8 = conversion constant, (yr/sec) d/Q = atmospheric dispersion factor adjusted for depletion by deposition, (sec/m3).

Qik = 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 exposure to the plume),

mRem/yr; (See Appendix 3B).

(µCi/m3) 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, (Contd)

METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Contd)

B. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Contd)

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 d/Q = 1 x 10-7 sec/m3, (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

-8 Dank = 3 .17 x 10 *

• Qik

• TG anip 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 3B. (µCi/m2 *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, (Contd)

METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Contd)

B. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Contd)

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 this location, the reference atmospheric deposition factor is D/Q = 5 x 10 -10 m -2 (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

-8 Dank = 3 .17 x 10 *

• Q ik

• TAanip Eqn 3.4-5 Q i p where:

/Q = atmospheric dispersion factor at the off-site location of interest (sec/m3)

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 reference atmospheric dispersion factor is /Q = 1 x 10-7 sec/m3.

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, (Contd)

METHOD 3.4.1: DOSE DUE TO IODINE, TRITIUM, AND PARTICULATES IN GASEOUS EFFLUENTS, (Contd)

B. Calculating the Dose Due to Iodine, Tritium, and Particulates, (Contd)

The dose commitment via a given pathway as a result of measured discharges from a release point is accumulated with Dan = Dank 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, (Contd)

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 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 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 Iodine-131, Iodine-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, (Contd)

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 3B for the organ, age group, and pathway.

For Iodine and Particulate:

D

-8 D ank = 3 .17 x 10 *

• Qik

• TG anip Eqn 3.4-4 Q i p For Tritium;

-8 Dank = 3 .17 x 10 *

• Qik

• TAanip 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, (Contd) where:

/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).

Qik = 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 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/m3 ).

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

(µCi/m2

• 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, (Contd)

EXAMPLE CALCULATIONS: Determining Dose Due to Iodine, Tritium, and Particulates, (Contd)

GRASS-COW-MILK PATHWAY Total Dose Sum of Organ Radionuclide Qik TGanip /Q or D/Q 3.17E-8 Dank Dank (mRem)

Bone H-3 2.0E+8 0 0 Co-58 2.0E+1 0 0 Co-60 1.7E+1 0 0 I-131 3.9E+3 2.59E+9 5E-10 3.17E-8 1.6E-4 Cs-137 6.1E+1 6.44E+10 5E-10 3.17E-8 6.2E-5 2.2E-4 Liver H-3 2.0E+8 2.37E+3 1E-7 3.17E-8 1.5E-3 Co-58 2.0E+1 2.55E+7 5E-10 3.17E-8 8.1E-9 Co-60 1.7E+1 8.73E+7 5E-10 3.17E-8 2.4E-8 I-131 3.9E+3 3.09E+9 5E-10 3.17E-8 1.9E-4 Cs-137 6.1E+1 7.21E+10 5E-10 3.17E-8 7.0E-5 1.8E-3 Thyroid H-3 2.0E+8 2.37E+3 1E-7 3.17E-8 1.5E-3 Co-58 2.0E+1 0 Co-60 1.7E+1 0 I-131 3.9E+3 9.94E-11 5E-10 3.17E-8 6.1E-1 Cs-137 6.1E+1 0 6.1E-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, (Contd)

EXAMPLE CALCULATIONS: Determining Dose Due to Iodine, Tritium, and Particulates, (Contd)

GRASS-COW-MILK PATHWAY Total Dose Sum of Organ Radionuclide Qik TGanip /Q or D/Q 3.17E-8 Dank Dank (mRem)

Kidney H-3 2.0E+8 1.04E+3 1E-7 3.17E-8 6.6E-4 Co-58 2.0E+1 0 Co-60 1.7E+1 0 I-131 3.9E+3 7.74E+8 5E-10 3.17E-8 4.8E-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+8 2.37E+3 1E-7 3.17E-8 1.5E-3 Co-58 2.0E+1 0 Co-60 1.7E+1 0 I-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+8 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 I-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, (Contd)

EXAMPLE CALCULATIONS: Determining Dose Due to Iodine, Tritium, and Particulates, (Contd)

GRASS-COW-MILK PATHWAY Total Dose Sum of Organ Radionuclide Qik TGanip /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 I-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 1.7E+1 0 0 I-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 fully 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, (Contd)

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, (Contd)

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 II.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 Particulate, 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 (Contd)

BASIS 3.6 Radioactive Gaseous Effluent Accident Monitoring Instrumentation (Contd)

Table 3.6-1, Instrument 1.a, High Range Noble Gas Plant Vent (PV) Exhaust (Contd)

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+00 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). Inoperability 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 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Due to multiple detector channels and sampling configurations provided by the PV SPING, the preplanned alternate methods vary with the condition and 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 (Contd)

BASIS 3.6 Radioactive Gaseous Effluent Accident Monitoring Instrumentation (Contd)

Table 3.6-1, Instrument 1.a, High Range Noble Gas Plant Vent (PV) Exhaust (Contd)

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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 CONTROL 3.6 Radioactive Gaseous Effluent Accident Monitoring Instrumentation, (Contd)

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 (Contd)

TABLE 3.6-1 (Contd)

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 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

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 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3 - 76 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, (Contd)

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

• 0-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 online 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 through 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-service 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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

APPENDIX 3A REFERENCE METEOROLOGY ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS REV. 26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS APPENDIX 3A REFERENCE METEOROLOGY ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS Contents Table Description Page 3A-1 Atmospheric Dispersion Factors (/Q) 3A - 1 3A-2 Deposition Depleted Atmospheric Dispersion Factors (d /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: 43,301at 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. (M/T) 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

/ Q 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 1.24E-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 1.10E-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-08 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 1.01E-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 1.10E-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 2.50E-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 8.50E-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

/Q sec/ m3 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 5.01E-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 3.01E-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 d/Q 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 5.51E-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 5.01E-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 4.05E-07 3.90E-07 3.10E-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 1.01E-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 1.01E-07 8.61E-08 5.77E-08 4.64E-08 WSW 3.70E-06 1.51E-06 1.40E-06 9.51E-07 6.82E-07 4.67E-07 2.78E-07 1.86E-07 1.57E-07 1.03E-07 8.18E-08 W 5.50E-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 3.01E-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 1.10E-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 5.01E-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 d/Q sec/ m3 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 3.10E-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 4.01E-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 1.11E-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 6.11E-08 4.19E-08 3.56E-08 3.11E-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 1.11E-08 7.97E-09 NNW 6.59E-08 6.11E-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 /Q 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 6.51E-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 1.53E-09 9.09E-10 4.57E-10 2.73E-10 2.21E-10 1.33E-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 1.20E-10 7.39E-11 5.86E-11 E 1.42E-08 2.77E-09 2.45E-09 1.32E-09 8.18E-10 4.88E-10 2.48E-10 1.50E-10 1.23E-10 7.74E-11 6.24E-11 ESE 1.26E-08 2.80E-09 2.47E-09 1.35E-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 1.64E-09 1.02E-09 6.11E-10 3.12E-10 1.91E-10 1.57E-10 1.02E-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 1.71E-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 1.17E-08 1.03E-08 5.49E-09 3.36E-09 1.98E-09 9.90E-10 5.89E-10 4.76E-10 2.84E-10 2.18E-10 WSW 1.02E-07 1.94E-08 1.71E-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 1.27E-08 7.74E-09 4.57E-09 2.29E-09 1.37E-09 1.11E-09 6.82E-10 5.38E-10 WNW 1.82E-07 3.19E-08 2.81E-08 1.49E-08 9.10E-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 3.11E-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 3.11E-09 1.85E-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/M2 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 1.12E-10 1.03E-10 8.73E-11 7.60E-11 5.33E-11 3.86E-11 3.35E-11 2.98E-11 1.98E-11 1.28E-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 1.71E-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 1.39E-11 9.04E-12 6.11E-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 1.61E-11 1.04E-11 7.00E-12 SE 7.65E-11 7.27E-11 6.57E-11 6.11E-11 4.80E-11 3.80E-11 3.41E-11 3.10E-11 2.15E-11 1.40E-11 9.39E-12 SSE 1.31E-10 1.25E-10 1.14E-10 1.07E-10 8.52E-11 6.82E-11 6.14E-11 5.60E-11 3.90E-11 2.53E-11 1.70E-11 S 2.17E-10 2.07E-10 1.88E-10 1.75E-10 1.39E-10 1.11E-10 9.93E-11 9.05E-11 6.28E-11 4.07E-11 2.72E-11 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 1.91E-10 1.76E-10 1.48E-10 1.28E-10 8.86E-11 6.36E-11 5.53E-11 4.90E-11 3.22E-11 2.07E-11 1.41E-11 WSW 3.25E-10 3.02E-10 2.56E-10 2.25E-10 1.60E-10 1.17E-10 1.03E-10 9.17E-11 6.11E-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 1.53E-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 1.59E-10 1.06E-10 6.91E-11 4.72E-11 NW 3.28E-10 3.06E-10 2.65E-10 2.36E-10 1.73E-10 1.30E-10 1.14E-10 1.03E-10 6.94E-11 4.49E-11 3.04E-11 NNW 1.89E-10 1.76E-10 1.50E-10 1.32E-10 9.41E-11 6.91E-11 6.04E-11 5.39E-11 3.60E-11 2.33E-11 1.58E-11 N 1.92E-10 1.77E-10 1.47E-10 1.26E-10 8.56E-11 6.01E-11 5.18E-11 4.57E-11 2.98E-11 1.94E-11 1.35E-11 3A - 7 REV. 26

APPENDIX 3B PATHWAY-DOSE TRANSFER FACTORS REV. 26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS APPENDIX 3B 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-01331 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.

3B - 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-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 CO-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 CO-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 CO-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 NI-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 /Q, d/Q, AND D/Q.

3B - 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-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+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 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 I-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 I-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 I-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 I-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 I-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 I-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 /Q, d/Q, AND D/Q.

3B - 3 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-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 CO-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 CO-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 CO-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 NI-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 /Q, d/Q, 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-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 I-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 I-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 I-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 I-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 I-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 I-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 /Q, d/Q, AND D/Q.

3B - 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-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 CO-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 CO-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 CO-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 NI-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 /Q, d/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 I-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 I-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 I-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 I-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 I-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 I-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 /Q, d/Q, AND D/Q.

3B - 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-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 CO-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 CO-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 CO-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 NI-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 /Q, d/Q, AND D/Q.

3B - 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 I-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 I-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 I-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 I-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 I-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 I-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 /Q, d/Q, AND D/Q.

3B - 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 UCI/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 CO-57 0. 6.92E+02 0. 0. 3.70E+05 3.14E+04 0. 6.71E+02 CO-58 0. 1.58E+03 0. 0. 9.28E+05 1.06E+05 0. 2.07E+03 CO-60 0. 1.15E+04 0. 0. 5.98E+06 2.85E+05 0. 1.48E+04 NI-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 1.41E+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 /Q AND d/Q 3B - 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 I-130 4.58E+03 1.34E+04 1.74E+06 2.09E+04 0. 7.69E+03 0. 5.29E+03 I-131 2.52E+04 3.58E+04 1.19E+07 6.14E+04 0. 6.28E+03 0. 2.05E+04 I-132 1.16E+03 3.26E+03 4.38E+05 5.19E+03 0. 4.06E+02 0. 1.16E+03 I-133 8.64E+03 1.49E+04 2.93E+06 2.60E+04 0. 8.72E+03 0. 4.54E+03 I-134 6.45E+02 1.73E+03 2.30E+05 2.75E+03 0. 1.01E+00 0. 6.16E+02 I-135 2.89E+03 6.99E+03 9.36E+05 1.11E+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 /Q AND d/Q 3B - 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 CO-57 0. 6.92E+02 0. 0. 3.70E+05 3.14E+04 0. 6.71E+02 CO-58 0. 1.76E+02 0. 0. 1.37E+06 9.52E+04 0. 2.34E.02 CO-60 0. 1.24E+03 0. 0. 8.56E+06 2.35E+05 0. 1.65E+34 NI-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+05 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 /Q AND d/Q.

3B - 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 (MREM/YR PER UCI/CU.METER)

BONE LIVER THYROID KIDNEY LUNG GI-LLI 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 I-130 4.58E+03 1.34E+04 1.74E+06 2.09E+04 0. 7.69E+03 0. 5.29E+03 I-131 3.37E+04 4.72E+04 1.39E+07 6.14E+04 0. 5.96E+03 0. 2.82E+04 I-132 1.16E+03 3.26E+03 4.38E+05 5.19E+03 0. 4.06E+02 0. 1.16E+03 I-133 1.23E+04 2.06E+04 3.83E+06 2.60E+04 0. 1.00E+04 0. 6.34E+03 I-134 6.45E+03 1.73E+03 2.30E+05 2.75E+03 0. 1.01E+00 0. 6.16E+02 I-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+05 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. 1.11E+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+00 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 /Q AND d/Q.

3B - 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 UCI/CU.METER)

BONE LIVER THYROID KIDNEY LUNG GI-LLI 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 6.11E+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 CO-57 0. 3.20E+02 0. 0. 1.71E+05 1.45E+04 0. 3.10E+02 CO-58 0. 1.52E+02 0. 0. 1.13E+06 3.62E+04 0. 2.68E+02 CO-60 0. 1.07E+03 0. 0. 6.92E+06 9.36E+04 0. 1.88E+03 NI-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 0. 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 /Q AND d/Q.

3B - 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 UCI/CU.METER)

BONE LIVER THYROID KIDNEY LUNG GI-LLI 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 I-130 2.12E+03 6.22E+03 8.07E+05 9.66E+03 0. 3.56E+03 0. 2.45E+03 I-131 4.55E+04 4.63E+04 1.54E+07 2.84E+04 0. 2.65E+03 0. 3.50E+04 I-132 5.37E+02 1.51E+03 2.03E+05 2.40E+03 0. 1.88E+02 0. 5.37E+02 I-133 1.68E+04 2.05E+04 5.03E+06 1.20E+04 0. 5.55E+03 0. 8.03E+02 I-134 2.98E+02 7.99E+02 1.06E+05 1.27E+03 0. 4.66E-01 0. 2.85E+02 I-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+00 0. 7.73E+00 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 /Q AND d/Q.

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 UCI/CU.METER)

BONE LIVER THYROID KIDNEY LUNG GI-LLI 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 2.31E+05 1.35E+04 0. 0. 0. 1.51E+04 0. 8.78E+03 CR-51 0. 0. 1.94E+01 3.99E+00 2.52E+03 5.81E+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 CO-57 0. 1.21E+02 0. 0. 6.47E+04 5.50E+03 0. 1.18E+02 CO-58 0. 1.18E+02 0. 0. 8.79E+05 1.21E+04 0. 1.68E+02 CO-60 0. 8.40E+02 0. 0. 5.57E+06 3.28E+04 0. 1.17E+03 NI-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 1.41E+04 0. 1.95E+03 NB-95 1.28E+03 5.75E+02 0. 1.35E+03 4.77E+05 1.21E+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 9.31E+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 /Q AND d/Q.

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 (MREM/YR PER UCI/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 2.21E+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 I-130 8.02E+02 2.35E+03 3.05E+05 3.65E+03 0. 1.35E+03 0. 9.25E+02 I-131 3.63E+04 4.27E+04 1.41E+07 1.07E+04 0. 1.07E+03 0. 2.51E+04 I-132 2.03E+02 5.70E+02 7.67E+04 9.09E+02 0. 7.11E+01 0. 2.03E+02 I-133 1.34E+04 1.93E+04 4.66E+06 4.55E+03 0. 2.28E+03 0. 5.87E+03 I-134 1.13E+02 3.02E+02 4.02E+04 4.82E+02 0. 1.76E-01 0. 1.08E+02 I-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 7.31E+05 0. 3.89E+04 9.45E+04 1.32E+03 0. 4.41E+04 BA-140 5.70E+03 4.27E+00 0. 2.93E+00 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 /Q AND d/Q.

3B - 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-MREM/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI 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 CO-57 0. 5.64E+06 0. 0. 0. 1.43E+08 0. 9.38E+06 CO-58 0. 1.83E+07 0. 0. 0. 3.70E+08 0. 4.09E+07 CO-60 0. 7.55E+07 0. 0. 0. 1.41E+09 0. 1.66E+08 NI-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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-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 1.86E+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+09 3.93E+08 2.96E+08 4.56E+09 0. 5.11E+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 I-130 2.38E-06 7.05E-06 8.96E-04 1.10E-05 0. 6.04E-06 0. 2.77E-06 I-131 1.08E+07 1.55E+07 5.06E+09 2.65E+07 0. 4.07E+06 0. 8.85E+06 I-132 0. 0. 0. 0. 0. 0. 0. 0.

I-133 4.40E-01 7.63E-01 1.47E+02 1.33E+00 0. 6.71E-01 0. 2.33E-01 I-134 0. 0. 0. 0. 0. 0. 0. 0.

I-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 1.41E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-MREM/YR 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. 1.61E+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+08 CO-57 0. 3.33E+06 0. 0. 0. 8.45E+07 0. 5.54E+06 CO-58 0. 1.44E+07 0. 0. 0. 1.94E+08 0. 3.27E+07 CO-60 0. 5.73E+07 0. 0. 0. 6.87E+08 0. 1.31E+08 NI-63 1.12E+09 7.74E+07 0. 0. 0. 1.61E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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 UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0.

SN-126 1.10E+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. 9.11E+06 3.32E+08 0. 4.64E+06 SB-125 5.01E+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 I-130 1.41E-06 4.16E-06 5.30E-04 6.47E-06 0. 3.57E-06 0. 1.64E-06 I-131 8.54E+06 1.21E+07 3.48E+09 1.56E+07 0. 2.28E+06 0. 7.19E+06 I-132 0. 0. 0. 0. 0. 0. 0. 0.

I-133 3.69E-01 6.26E-01 1.14E+02 7.88E-01 0. 4.55E-01 0. 1.93E-01 I-134 0. 0. 0. 0. 0. 0. 0. 0.

I-135 5.08E-02 4.69E-02 0. 1.78E-02 5.34E-03 1.10E-03 0. 2.08E-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 2.11E+06 3.14E+06 0. 1.99E+07 CS-137 6.92E+08 9.31E+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 7.51E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-LLI 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 CO-57 0. 2.10E+06 0. 0. 0. 5.33E+07 0. 3.50E+06 CO-58 0. 1.69E+07 0. 0. 0. 1.00E+08 0. 5.10E+07 CO-60 0. 6.77E+07 0. 0. 0. 3.75E+08 0. 2.03E+08 NI-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. 3.81E+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 /Q, d/Q, AND D/Q.

THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-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 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 I-130 8.87E-07 2.63E-06 3.34E-04 4.08E-06 0. 2.25E-06 0. 1.03E-06 I-131 1.58E+07 1.62E+07 5.25E+09 9.86E+06 0. 1.38E+06 0. 1.22E+07 I-132 0. 0. 0. 0. 0. 0. 0. 0.

I-133 6.86E-01 8.47E-01 2.04E+02 4.97E-01 0. 3.43E-01 0. 3.33E-01 I-134 0. 0. 0. 0. 0. 0. 0. 0.

I-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. 1.51E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-MREM/YR 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+07 2.33E+08 0. 2.69E+07 CO-57 0. 1.28E+06 0. 0. 0. 3.25E+07 0. 2.13E+06 CO-58 0. 4.72E+06 0. 0. 0. 9.56E+07 0. 1.06E+07 CO-60 0. 1.65E+07 0. 0. 0. 3.08E+08 0. 3.62E+07 NI-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. 2.31E+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. 3.21E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-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 1.65E+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. 2.11E+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 I-130 4.27E+05 1.26E+08 1.61E+08 1.96E+06 0. 1.08E+06 0. 4.97E+05 I-131 2.96E+08 4.25E+08 1.39E+11 7.27E+08 0. 1.12E+08 0. 2.43E+08 I-132 1.67E-01 4.47E-01 5.88E+01 7.12E-01 0. 8.39E-02 0. 1.59E-01 I-133 4.00E+06 6.94E+06 1.33E+09 1.21E+07 0. 6.10E+06 0. 2.12E+06 I-134 0. 0. 9.98E-10 0. 0. 0. 0. 0.

I-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+08 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+00 ND-147 1.16E+02 1.12E+02 0. 6.77E+01 0. 5.28E+05 0. 7.34E+00 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-LLI 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 3.01E+08 0. 3.47E+07 CO-57 0. 1.65E+06 0. 0. 0. 4.19E+07 0. 2.75E+06 CO-58 0. 8.10E+06 0. 0. 0. 1.10E+08 0. 1.85E+07 CO-60 0. 2.73E+07 0. 0. 0. 3.27E+08 0. 6.23E+07 NI-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 ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/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-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 2.12E+09 4.21E+07 1.24E+07 0. 6.03E+06 1.41E+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 I-130 5.51E+05 1.63E+06 2.07E+08 2.53E+06 0. 1.40E+06 0. 6.41E+05 I-131 5.12E+08 7.24E+08 2.09E+11 9.38E+08 0. 1.37E+08 0. 4.31E+08 I-132 2.16E-01 5.76E-01 7.59E+01 9.19E-01 0. 1.08E-01 0. 2.05E-01 I-133 7.33E+06 1.24E+07 2.26E+09 1.56E+07 0. 9.02E+06 0. 3.83E+06 I-134 0. 0. 1.29E-09 0. 0. 0. 0. 0.

I-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+00 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/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-LLI 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 CO-57 0. 1.36E+06 0. 0. 0. 3.46E+07 0. 2.27E+06 CO-58 0. 1.25E+07 0. 0. 0. 7.41E+07 0. 3.76E+07 CO-60 0. 4.22E+07 0. 0. 0. 2.33E+08 0. 1.27E+08 NI-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+06 0. 5.58E+07 0. 4.24E+04 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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 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 3.13E+07 1.41E+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 I-130 4.54E+05 1.35E+06 1.71E+08 2.09E+06 0. 1.15E+06 0. 5.29E+05 I-131 1.24E+09 1.27E+09 4.12E+11 7.74E+08 0. 1.09E+08 0. 9.56E+08 I-132 1.18E-01 4.76E-01 6.26E+01 7.58E-01 0. 8.93E-02 0. 1.69E-01 I-133 1.78E+07 2.20E+07 5.30E+09 1.29E+07 0. 8.90E+06 0. 8.63E+06 I-134 0. 0. 1.06E-09 0. 0. 0. 0. 0.

I-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. 7.41E+05 0. 8.40E+00 ND-147 1.23E+02 1.19E+02 0. 7.21E+01 0. 5.63E+05 0. 7.81E+00 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-LLI 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 CO-57 0. 1.36E+06 0. 0. 0. 3.46E+07 0. 2.27E+06 CO-58 0. 2.55E+07 0. 0. 0. 6.60E+07 0. 6.24E+07 CO-60 0. 8.73E+07 0. 0. 0. 2.16E+08 0. 2.09E+08 NI-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 1.47E+10 0. 0. 0. 0. 2.75E+08 0. 4.22E+08 SR-90 1.65E+11 0. 0. 0. 0. 1.61E+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 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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+08 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 I-130 4.54E+05 1.35E+06 1.71E+08 2.09E+06 0. 1.15E+06 0. 5.29E+05 I-131 2.59E+09 3.09E+09 9.94E+11 7.74E+08 0. 1.16E+08 0. 1.81E+09 I-132 1.78E-01 4.76E-01 6.26E+01 7.58E-01 0. 8.93E-02 0. 1.69E-01 I-133 3.75E+07 5.48E+07 1.30E+10 1.29E+07 0. 9.74E+06 0. 1.66E+07 I-134 0. 0. 1.06E-09 0. 0. 0. 0. 0.

I-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 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. 6.11E+08 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. 7.41E+05 0. 8.40E+00 ND-147 1.23E+02 1.19E+02 0. 7.21E+01 0. 5.63E+05 0. 7.81E+00 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-MREM/YR 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. 2.31E+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 CO-57 0. 1.54E+05 0. 0. 0. 3.90E+06 0. 2.55E+05 CO-58 0. 5.67E+05 0. 0. 0. 1.15E+07 0. 1.27E+06 CO-60 0. 1.98E+06 0. 0. 0. 3.70E+07 0. 4.34E+06 NI-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. 2.41E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-LLI 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 1.31E+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 I-130 5.12E+05 1.52E+06 1.93E+08 2.36E+06 0. 1.30E+06 0. 5.96E+05 I-131 3.56E+08 5.10E+08 1.67E+11 8.72E+08 0. 1.34E+08 0. 2.92E+08 I-132 2.00E-01 5.36E-01 7.06E+01 8.55E-01 0. 1.01E-01 0. 1.91E-01 I-133 4.80E+06 8.32E+06 1.60E+09 1.45E+07 0. 7.32E+06 0. 2.54E+06 I-134 0. 0. 1.20E-09 0. 0. 0. 0. 0.

I-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 1.91E+01 7.67E+00 0. 4.42E+00 0. 8.35E+04 0. 9.47E-01 ND-147 1.39E+01 1.34E+01 0. 8.13E+00 0. 6.35E+04 0. 8.81E-01 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/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-LLI 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 1.11E+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 CO-57 0. 1.98E+05 0. 0. 0. 5.03E+06 0. 3.30E+05 CO-58 0. 9.72E+05 0. 0. 0. 1.31E+07 0. 2.22E+06 CO-60 0. 3.28E+06 0. 0. 0. 3.93E+07 0. 7.48E+06 NI-63 1.04E+09 7.23E+07 0. 0. 0. 1.51E+07 0. 3.49E+07 ZN-65 2.13E+08 6.76E+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. 7.11E+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. 6.11E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-LLI 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. 1.01E+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 I-130 6.61E+05 1.96E+06 2.49E+08 3.04E+06 0. 1.68E+06 0. 7.69E+05 I-131 6.15E+08 8.68E+08 2.50E+11 1.13E+09 0. 1.64E+08 0. 5.17E+08 I-132 2.59E-01 6.92E-01 9.11E+01 1.10E+00 0. 1.30E-01 0. 2.46E-01 I-133 8.79E+06 1.49E+07 2.71E+09 1.88E+07 0. 1.08E+07 0. 4.59E+06 I-134 0. 0. 1.55E-09 0. 0. 0. 0. 0.

I-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+10 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. 1.41E+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+00 0. 5.70E+00 0. 1.08E+05 0. 1.22E+00 ND-147 1.79E+01 1.73E+01 0. 1.05E+01 0. 8.19E+04 0. 1.14E+00 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, 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 2.11E+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. 2.05E+05 FE-59 4.12E+05 9.78E+05 0. 0. 2.72E+05 3.23E+06 0. 3.72E+05 CO-57 0. 1.64E+05 0. 0. 0. 4.15E+06 0. 2.72E+05 CO-58 0. 1.50E+05 0. 0. 0. 8.90E+06 0. 4.51E+06 CO-60 0. 5.06E+06 0. 0. 0. 2.80E+07 0. 1.52E+07 NI-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 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+04 1.41E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-LLI 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 I-130 5.45E+05 1.61E+06 2.05E+08 2.51E+06 0. 1.38E+06 0. 6.35E+05 I-131 1.48E+09 1.52E+09 4.94E+11 9.28E+08 0. 1.30E+08 0. 1.15E+09 I-132 2.18E-01 5.71E-01 7.51E+01 9.10E-01 0. 1.07E-01 0. 2.03E-01 I-133 2.14E+07 2.64E+07 6.36E+09 1.55E+07 0. 1.07E+07 0. 1.04E+07 I-134 0. 0. 1.27E-09 0. 0. 0. 0. 0.

I-135 1.79E+04 4.72E+04 6.18E+06 7.51E+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+00 0. 4.70E+00 0. 8.89E+04 0. 1.01E+00 ND-147 1.47E+01 1.42E+01 0. 8.66E+00 0. 6.75E+04 0. 9.38E-01 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-MREM/YR 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+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. 2.05E+05 FE-59 4.12E+05 9.78E+05 0. 0. 2.72E+05 3.23E+06 0. 3.72E+05 CO-57 0. 1.64E+05 0. 0. 0. 4.15E+06 0. 2.72E+05 CO-58 0. 3.06E+06 0. 0. 0. 7.92E+06 0. 7.49E+06 CO-60 0. 1.05E+07 0. 0. 0. 2.59E+07 0. 2.51E+07 NI-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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-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 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 2.31E+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 I-130 5.45E+05 1.61E+06 2.05E+08 2.51E+06 0. 1.38E+06 0. 6.35E+05 I-131 3.11E+09 3.70E+09 1.19E+12 9.28E+08 0. 1.39E+08 0. 2.17E+09 I-132 2.13E-01 5.71E-01 7.51E+01 9.10E-01 0. 1.07E-01 0. 2.03E-01 I-133 4.50E+07 6.57E+07 1.55E+10 1.55E+07 0. 1.17E+07 0. 1.99E+07 I-134 0. 0. 1.27E-09 0. 0. 0. 0. 0.

I-135 1.79E+04 4.72E+04 6.18E+06 7.51E+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+00 0. 4.70E+00 0. 8.89E+04 0. 1.01E+00 ND-147 1.47E+01 1.42E+01 0. 8.66E+00 0. 6.75E+04 0. 9.38E-01 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-LLI 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 1.41E+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. 9.31E+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 CO-57 0. 1.17E+07 0. 0. 0. 2.97E+08 0. 1.95E+07 CO-58 0. 3.08E+07 0. 0. 0. 6.24E+08 0. 6.90E+07 CO-60 0. 1.68E+08 0. 0. 0. 3.14E+09 0. 3.68E+08 NI-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. 7.21E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/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-MREM/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-123 1.00E-05 1.66E-07 1.41E-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 3.51E+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 I-130 3.93E+05 1.16E+06 1.48E+08 1.81E+06 0. 9.98E+05 0. 4.58E+05 I-131 8.83E+07 1.16E+08 3.79E+10 1.98E+08 0. 3.05E+07 0. 6.63E+07 I-132 5.57E+01 1.49E+02 1.96E+04 2.38E-02 0. 2.80E+01 0. 5.29E+01 I-133 2.13E+06 3.69E+06 7.10E+08 6.44E+06 0. 3.24E+06 0. 1.13E+06 I-134 1.03E-04 2.79E-04 3.63E-02 4.45E-04 0. 2.43E-07 0. 9.99E-05 I-135 4.04E+04 1.07E+05 1.40E+07 1.70E+05 6.27E-02 1.19E+05 0. 3.91E+04 CS-134 4.87E+09 1.11E+10 0. 3.61E+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 9.81E+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. 1.11E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-LLI 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 6.08E-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 CO-57 0. 1.31E+07 0. 0. 0. 3.34E+08 0. 2.19E+07 CO-54 0. 4.45E+07 0. 0. 0. 6.02E+08 0. 1.02E+08 CO-60 0. 2.44E+08 0. 0. 0. 2.93E+09 0. 5.57E+08 NI-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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/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-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 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 2.11E+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 I-130 2.58E+05 7.64E+05 9.72E+07 1.19E+06 0. 6.55E+05 0. 3.00E+05 I-131 7.33E+07 1.03E+08 2.99E+10 1.34E+08 0. 1.96E+07 0. 6.17E+07 I-132 3.65E+01 9.77E+01 1.29E+04 1.56E+02 0. 1.84E+01 0. 3.47E+01 I-133 1.98E+06 3.36E+06 6.10E+08 4.23E+06 0. 2.44E+06 0. 1.04E+06 I-134 6.75E-05 1.83E-04 2.38E-02 2.92E-04 0. 1.60E-07 0. 6.56E-05 I-135 2.65E+04 7.00E+04 9.15E+06 1.11E+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. 2.91E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-LLI 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 CO-57 0. 1.06E+07 0. 0. 0. 2.69E+08 0. 1.77E+07 CO-58 0. 6.62E+07 0. 0. 0. 3.94E+08 0. 2.00E+08 CO-60 0. 3.69E+08 0. 0. 0. 2.05E+09 0. 1.11E+09 NI-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. 1.11E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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-MREM/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI 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 I-130 1.60E+05 4.73E+05 6.02E+07 7.35E+05 0. 4.05E+05 0. 1.86E+05 I-131 1.36E+08 1.39E+08 4.52E+10 8.48E+07 0. 1.19E+07 0. 1.05E+08 I-132 2.26E+01 6.05E+01 7.97E+03 9.65E+01 0. 1.14E+01 0. 2.15E+01 I-133 3.61E+06 4.46E+06 1.08E+09 2.62E+06 0. 1.81E+06 0. 1.75E+06 I-134 4.18E+05 1.14E+04 1.47E-02 1.81E-04 0. 9.89E-08 0. 4.06E-05 I-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 6.21E+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 /Q, d/Q, AND D/Q.

NOTE - THE UNITS FOR C-14 AND H-3 ARE (MREM/YR PER UCI/CU.METER) 3B - 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 CO-57 0. 9.85E+06 0. 0. 0. 2.50E+08 0. 1.64E+07 CO-58 0. 2.39E+07 0. 0. 0. 4.84E+08 0. 5.36E+07 CO-60 0. 1.44E+08 0. 0. 0. 2.69E+09 0. 3.16E+08 NI-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 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 /Q, d/Q, AND D/Q.

3B - 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-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 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 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 I-130 0. 0. 0. 0. 0. 0. 0. 0.

I-131 2.99E+06 4.28E+06 1.40E+09 7.33E+06 0. 1.13E+06 0. 2.45E+06 I-132 0. 0. 0. 0. 0. 0. 0. 0.

I-133 0. 0. 0. 0. 0. 0. 0. 0.

I-134 0. 0. 0. 0. 0. 0. 0. 0.

I-135 5.14E-01 4.74E-01 0. 1.80E-01 5.40E-02 1.11E-02 0. 2.11E-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 /Q, d/Q, AND D/Q.

3B - 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-MREM/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI 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 CO-57 0. 1.19E+07 0. 0. 0. 3.03E+08 0. 1.99E+07 CO-58 0. 3.85E+07 0. 0. 0. 5.21E+08 0. 8.78E+07 CO-60 0. 2.24E+08 0. 0. 0. 2.69E+09 0. 5.11E+08 NI-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 6.21E+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. 1.41E+06 BASED ON 1 µCi/SEC RELEASE RATE OF EACH ISOTOPE AND A VALUE OF 1 FOR /Q, d/Q, 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-LLI 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 2.31E+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 I-130 0. 0. 0. 0. 0. 0. 0. 0.

I-131 4.85E+06 6.85E+06 1.98E+09 8.88E+06 0. 1.30E+06 0. 4.08E+06 I-132 0. 0. 0. 0. 0. 0. 0. 0.

I-133 0. 0. 0. 0. 0. 0. 0. 0.

I-134 0. 0. 0. 0. 0. 0. 0. 0.

I-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 /Q, d/Q, AND D/Q.

3B - 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-LLI 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 CO-57 0. 9.85E+06 0. 0. 0. 2.50E+08 0. 1.64E+07 CO-58 0. 5.93E+07 0. 0. 0. 3.53E+08 0. 1.79E+08 CO-60 0. 3.46E+08 0. 0. 0. 1.92E+09 0. 1.04E+09 NI-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 /Q, d/Q, AND D/Q.

3B - 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-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 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 I-130 0. 0. 0. 0. 0. 0. 0. 0.

I-131 1.17E+07 1.20E+07 3.90E+09 7.33E+06 0. 1.03E+06 0. 9.05E+06 I-132 0. 0. 0. 0. 0. 0. 0. 0.

I-133 0. 0. 0. 0. 0. 0. 0. 0.

I-134 0. 0. 0. 0. 0. 0. 0. 0.

I-135 5.14E-01 4.74E-01 0. 1.80E-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. 1.11E+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 /Q, d/Q, 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+07 8.64E+07 0. 0. 2.40E+07 2.85E+08 0. 3.29E+07 CO-57 0. 1.85E+06 0. 0. 0. 4.70E+07 0. 3.08E+06 CO-58 0. 6.89E+06 0. 0. 0. 1.40E+08 0. 1.54E+07 CO-60 0. 2.38E+07 0. 0. 0. 4.46E+08 0. 5.23E+07 NI-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 /Q, d/Q, 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 1.41E-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. 9.51E+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 I-130 3.93E+05 1.16E+06 1.48E+08 1.81E+06 0. 9.98E+05 0. 4.58E+05 I-131 7.78E+07 1.12E+08 3.65E+10 1.91E+08 0. 2.94E+07 0. 6.38E+07 I-132 5.57E+01 1.49E+02 1.96E+04 2.38E+02 0. 2.80E+01 0. 5.29E+01 I-133 2.13E+06 3.69E+06 7.10E+08 6.44E+06 0. 3.24E+06 0. 1.13E+06 I-134 1.03E-04 2.79E-04 3.63E-02 4.45E-04 0. 2.43E-07 0. 9.99E-05 I-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 /Q, d/Q, AND D/Q.

3B - 53 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-MREM/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI 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 CO-57 0. 1.22E+06 0. 0. 0. 3.09E+07 0. 2.02E+06 CO-58 0. 6.01E+06 0. 0. 0. 8.12E+07 0. 1.37E+07 CO-60 0. 2.01E+07 0. 0. 0. 2.41E+08 0. 4.58E+07 NI-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. 4.41E+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 /Q, d/Q, AND D/Q.

3B - 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. 5.51E+06 TE-129M 8.46E+07 3.14E+07 2.71E+07 2.45E+07 0. 2.95E+08 0. 1.33E+07 I-130 2.58E+05 7.64E+05 9.72E+07 1.19E+06 0. 6.55E+05 0. 3.00E+05 I-131 6.84E+07 9.66E+07 2.79E+10 1.25E+08 0. 1.83E+07 0. 5.76E+07 I-132 3.65E+01 9.77E+01 1.29E+04 1.56E+02 0. 1.84E+01 0. 3.47E+01 I-133 1.98E+06 3.36E+06 6.10E+08 4.23E+06 0. 2.44E+06 0. 1.04E+06 I-134 6.75E-05 1.83E-04 2.38E-02 2.92E-04 0. 1.60E-07 0. 6.56E-05 I-135 2.65E+04 7.00E+04 9.15E+06 1.11E+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 1.61E+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 1.41E+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 /Q, d/Q, AND D/Q.

3B - 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-MREM/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI 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 CO-57 0. 7.53E+05 0. 0. 0. 1.91E+07 0. 1.25E+06 CO-58 0. 6.94E+06 0. 0. 0. 4.13E+07 0. 2.09E+07 CO-60 0. 2.33E+07 0. 0. 0. 1.29E+08 0. 6.98E+07 NI-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 /Q, d/Q, AND D/Q.

3B - 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-LLI 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 1.11E+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 I-130 1.60E+05 4.73E+05 6.02E+07 7.35E+05 0. 4.05E+05 0. 1.86E+05 I-131 1.24E+08 1.27E+08 4.13E+10 7.75E+07 0. 1.09E+07 0. 9.58E+07 I-132 2.26E+01 6.05E+01 7.97E+03 9.65E+01 0. 1.14E+01 0. 2.15E+01 I-133 3.61E+06 4.46E+06 1.08E+09 2.62E+06 0. 1.81E+06 0. 1.75E+06 I-134 4.18E-05 1.14E-04 1.47E-02 1.81E-04 0. 9.89E-08 0. 4.06E-05 I-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 1.41E+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 /Q, d/Q, AND D/Q.

3B - 57 REV. 26

APPENDIX 3C TECHNICAL BASIS FOR Aeff AND TG131 REV. 26

TURKEY POINT UNIT 3 & 4 OFFSITE DOSE CALCULATION MANUAL 3.0 RADIOACTIVE GASEOUS EFFLUENTS APPENDIX 3C Technical Bases for Aeff and TG131 Overview The evaluation 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 (Aeff 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 Aeff 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:

Aeff = Ai

• f i i (Eq. 3C-1) where:

Aeff = the effective dose transfer factor Ai = the dose transfer factor for radionuclide i fi = 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 (I-131, and I-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 , (Contd)

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 waste 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 minor 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 Aeff Aeff Year mRad mRad 3 3

(µCi

• sec/m ) (µCi

• sec/m )

-5 -5 1978 1.3 x 10 3.4 x 10

-5 -5 1979 1.3 x 10 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 a Weighted Dose Factor -

Dose Factor TG131 Annual Airborne mRem/yr Radio nuclide Fraction Release (Ci) 2 mRem/yr

(µCi/(m *sec)) 2

(µCi/(m *sec))

1978 I-131 0.381 0.688 9.9E11 6.9E11 I-133 0.129 0.233 1.3E10 I-135 0.044 0.079 5.2E6 1979 I-131 0.0188 0.520 9.9E11 5.2E11 I-133 0.0156 0.432 1.3E10 I-135 0.0018 0.048 5.2E6 1980 I-131 0.0518 0.756 9.9E11 7.5E11 I-133 0.0124 0.181 1.3E10 I-135 0.0043 0.063 5.2E6 b

Average 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 (Contd)

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 190.10a. 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 I-131, I-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 /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 3B.

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) dose 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:

D = Q

• Pi Eqn 4.1-1 Q i i where:

D = noble gas gamma dose to total body, (mrem)

Qi = quantity of radioactive noble gas i discharged in gaseous effluent,

(µCi)

/Q = atmospheric dispersion factor at the off-site location of interest, (sec/m3)

Pi = 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/m3) 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, /Q, is 2.75 x 10-7 sec/m3.

This calculation is the same technique used in Control 3.2, Equation 3.2-1, but is extrapolated to an annual release and the /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= Q i

• S i + 1.11 Q i

• Ai Eqn 4.1-2 Q i where:

D = dose to skin due to noble gases, (mrem)

/Q = atmospheric dispersion factor at the off-site location of interest, (sec/m3).

Qi = quantity of radioactive noble gas i discharged in gaseous effluent,

(µCi).

Si = 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/m3 )

1.11 = ratio of tissue dose equivalent to air dose in a radiation field, (mrem/mrad)

Ai = 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 meteorological dispersion factor, /Q, is 2.75 x 10-7 sec/m3.

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 /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 Pi Si mrem mrem Radionuclide ( µCi sec/m3 ) ( µCi sec/m3 )

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 B-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 Ai Ai mrad mrad Radionuclide (µCi sec/m3) (µCi sec/m3)

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 5.1.1The radiological environmental monitoring 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 ANALYSIS PATHWAY AND/OR SAMPLES AND SAMPLE COLLECTION (2)(3) (4)

SAMPLE LOCATIONS FREQUENCY (5)

1. Direct Radiation Continuous Monitoring with Gamma Exposure Rate - quarterly 23 Monitoring Locations (6)

Sample Collection Quarterly

2. Airborne Continuous Sampler Radioiodine Filter- Analysis for I-131 weekly Radioiodine and Operation with sample Particulate filter - Gross beta radioactivity analysis (7);

Particulates Six Locations collection at least weekly or 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change ; Gamma isotopic (8) (7) more frequently if required by analysis of composite (by location) quarterly.

dust loading (10)

3. Waterborne (8) (9) (8)

a. Surface Three Locations Monthly Gamma isotopic and tritium analysis monthly.

(8)

b. Sediment from Three Locations Semiannually Gamma isotopic analysis semiannually.

Shoreline

4. Ingestion

a. Fish and Invertibrates (8)

1. Crustacea Two Locations Semiannually Gamma isotopic analysis semiannually.

(8)

2. Fish Two Locations Semiannually Gamma isotopic analysis semiannually.

b. Food Products (8)

1. Broad Leaf Three Locations (11) Monthly when available Gamma isotopic analysis and I-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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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/m3 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/l) PARTICULATE (pCi/kg, wet) (pCi/l) (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 I-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/l is used. For drinking water samples a value of 20,000 pCi/l 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 ANALYSIS(1)

LOWER LIMIT OF DETECTION (LLD) (2)(3)

ANALYSIS WATER AIRBORNE PARTICULATE FISH SEDIMENT MILK FOOD PRODUCTS 3

(pCi/l) OR GASES (pCi/m ) (pCi/kg, wet) (pCi/kg, dry) (pCi/l) (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

• • • (5)

Zr-Nb-95 15 (4)

I-131 1 0.07 1 60 Cs-134 15 0.05 130 150 15 60 Cs-137 18 0.06 150 180 18 80

• • • (5) (5)

Ba-La-140 15 15

• Since no drinking water pathway exists, a value of 3,000 pCi/l is used. For drinking water samples a value of 2,000 pCi/l 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 (Sb)

E V 2.22 Y [exp(-t)]

Where:

LLD = the "a priori" lower limit of detection as defined above as picoCuries per unit mass or volume, Sb = 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,

= the radioactive decay constant for the particular radionuclide t = 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 t 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/l 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.

Direct East end of N. Canal Dr. on NNW-2 siren pole E. of 117th Ave. TLD Quarterly 2.2 NNW 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)

Direct SSE-1 On site South East side of TLD Quarterly 1 SSE Radiation cooling canals at "Turtle 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 Weekly 2.2 NNW Bayfront Park Particulate Siren pole 27, intersection of Radioiodine and th Airborne T57 SW 112 Ave and Particulate Weekly 4 NW th SW 304 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)

Airborne T64* Natoma Substation Radioiodine Weekly 22 NNE and Particulate Airborne T72 Turkey Point Land Utilization Radioiodine Weekly <1 WSW Entrance and Particulate Waterborne T42 Biscayne Bay, at Turkey Point Surface Water Monthly <1 ENE 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 Food Products Card Sound near mouth of T81 6 S old Discharge Canal.

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 implementsSection 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 higher 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 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 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 m2 (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 Control 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.B.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 Interlaboratory 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 Intercomparison 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 Interlaboratory 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 Intercomparison 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 Interlaboratory 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 Interlaboratory 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 Interlaboratory Comparison Program described in this appendix is to provide adequate confidence in the results of Turkey Points 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 INTERLABORATORY COMPARISON PROGRAM SAMPLE ANALYSIS (1)

Analytical ANALYSIS WATER (3) 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 Interlaboratory Comparison Program is not required. Continued exclusion of milk in the Interlaboratory 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 Interlaboratory 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 of Waldin 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

1. 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 rd nd T99 WNW 12 183 block of SW 262 St.

th th (alt) W 10 134 block of SW 224 St.

Pathway: Ingestion, Fish Pathway: Ingestion, Food Crop Sampling and Collection Frequency: Annual collection (@ harvest) and Gamma-Spec analysis Name Sector Distance Description T43 Various locations: Various locations : 'truck farm' point of sale N thru NW to W 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

1. 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 5B 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.

5B-1 REV. 26