Text

Annual Radioactive Effluent Release Reports for 2003
	ML073300651
Person / Time
Site:	Hatch, Vogtle, Farley
Issue date:	04/30/2004
From:	Gasser J; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-04-0662a
	Download: ML073300651 (289)
	v • d • e

Jeffrey T. Gasser Southern Nuclear Vice President Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.7721 A.

Fax 205.992.0403 SOUTHERN April 30, 2004 COMPANY Energy to Serve YtJur World'"

Docket Nos.: 50-321 50-348 50-424 NL-04-0662a 50-366 50-364 50-425 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Joseph M. Farley Nuclear Plant Vogtle Electric Generating Plant Annual Radioactive Effluent Release Reports for 2003 Ladies and Gentlemen:

In accordance with section 5.6.3 of the referenced plants' Technical Specifications, Southern Nuclear Operating Company hereby submits the Annual Radioactive Effluent Release Reports for 2003.

This letter contains no NRC commitments. If you have any questions, please advise.

Sincerely, Original signed by Jeff Gasser -

[ cover letter corrected to reference actual repons J

J. T. Gasser JTG/JCM

Enclosures:

1. Hatch Annual Radioactive Effluent Release Report for 2003

2. Farley Annual Radioactive Effluent Release Report for 2003

3. Vogtle Annual Radioactive Effluent Release Report for 2003

U. S. Nuclear Regulatory Commission NL-04-0662a Page 2 cc: Southern Nuclear Operating Company Mr. J. B. Beasley, Jr., Executive Vice President (w/o Enclosure)

Mr. L. M. Stinson, Vice President, Plant Farley (w/o Enclosure)

Mr. H. L. Sumner, Jr., Vice President, Plant Hatch (w/o Enclosure)

Mr. D. E. Grissette, General Manager - Plant Farley Mr. G. R. Frederick, General Manager - Plant Hatch Mr. W. F. Kitchens, General Manager - Plant Vogtle RType: CFA04.054; CHA02.004; CVC7000; LC# 14016 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. S. E. Peters, NRR Project Manager - Farley Mr. C. Gratton, NRR Project Manager - Hatch Mr. C. Gratton, NRR Project Manager - Vogtle Mr. C. A. Patterson, Senior Resident Inspector - Farley Mr. D. S. Simpkins, Senior Resident Inspector - Hatch Mr. J. Zeiler, Senior Resident Inspector - Vogtle State of Alabama Mr. K. E. Whatley, Department of Public Health, Division of Radiation Control State of Georgia Mr. J. L. Setser, Department of Natural Resources Georgia Power Company Mr. M. C. Nichols American Nuclear Insurers Mr. R. A. Oliveira

Enclosure 3 Vogtle Electric Generating Plant Annual Radioactive Effluent Release Report for 2003 L_ ----------_._------ -----------------

SOUTHERN NUCLEAR COMPANY VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 NRC DOCKET NOS. 50-424 AND 50-425 FACILITY OPERATING LICENSE NOS. NPF-68 AND* NPF-81 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1 2003 TO DECEMBER 31,2003 Page 1 of84

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VOGTLE ELECTRIC GENERAnNG PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Liquid Effluents 8 1.1 Regulatory Requirements 8 1.1.1 Concentration Limits 8 1.1.2 Dose Limits 8 1.2 Effluent Concentration Limit 8 1.3 Measurement and Approximations of Total 9 Radioactivity 1.3.1 Total Radioactivity Determination 9 1.3.2 Total Error Estimation 11 1.4 Liquid Effluent Release Data 12 1.5 Radiological Impact Due to Liquid Releases 12 1.6 Liquid Effluents - Batch Releases 12 1.7 Liquid Effluents - Abnormal Releases 12 2.0 Gaseous Effluents 34 2.1 Regulatory Requirements 34 2.1.1 Dose Rate Limits 34 Page 2 of84

SECTION TITLE PAGE 2.1.2 Air Doses Due to Noble Gases In Gaseous Releases 34 2.1.3 Doses to a Member of the Public 34 2.2 Measurements and Approximation of Totsl 35 Radioactivity 2.2.1 Sample Collection and Analysis 35 2.2.2 Totsl Quantities of Radioactivity, Dose Rates and 35 Cumulative Doses 2.2.2.1 Fission and Activation Gases 35 2.2.2.2 Radlolodlnes, Tritium, and Particulate Releases 36 2.2.2.3 Gross Alpha Release 36 2.2.3 Totsl Error Estimation 36 2.3 Gaseous Effluent Release Oats 38 2.4 Radiological Impact Due to Gaseous Releases 39 2.5 Gaseous Effluents - Batch Releases 39 2.6 Gaseous Effluents - Abnormal Releases 40 3.0 Solid Waste 72 3.1 Regulatory Requirements 72 3.1.1 Solid Radioactive Waste System 72 3.1.2 Reporting Requirements 72 3.2 Solid Waste Oats 72 Page 3 of84

SECTION TITLE PAGE 4.0 Doses to Members of the Public Inside the Site 77 Boundary 4.1 Regulatory Requirements 77 4.2 Demonstration of Compliance 77 5.0 Total Dose from Uranium Fuel Cycle (40CFR190) . 81 5.1 Regulatory Requirements 81 5.2 Demonstration of Compliance 81 6.0 Meteorological Data 81 7.0 Program Deviations 81 7.1 InoPerable Liquid or Gaseous Effluent Monitoring 81 Instrumentation 7.1.1 Regulatory Requirement 81 7.1.2 Description of Deviations 81 7.2 Tanks Exceeding Curle Content Limits 82 7.2.1 Regulatory Requirements 82 7.2.2 Description of Deviations 82 8.0 Changes to the Vogtle Electric Generating Plant 82 Offsite Dose Calculation Manual (ODeM) 8.1 Regulatory Requirement 82 8.2 Description of Changes 82 9.0 Major Changes to the Liquid, Gaseous, or Solid 83 Radwaste Treatment System 9.1 Regulatory Requirements 83 9.2 Description of Major Changes 84 Page 4 of84

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VOGTLE ELECTRIC GENERAnNG PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 TABLE LIST OF TABLES PAGE 1-1A Liquid Effluents - Summation of All Releases Unit 1 13 (Quarters 1, 2, 3, and 4) 1-1B Liquid Effluents - Summation of All Releases Unit 2 15 (Quarters 1, 2, 3, and 4) 1-1C* Liquid Effluents - Summation of All Releases Site 17 (Quarters 1, 2, 3, and 4) 1-2A Liquid Effluents";' Unit 1 (Quarters 1, 2, 3, and 4) 19 1-2B Liquid Effluents - Unit 2 (Quarters 1, 2, 3, and 4) 21 1-2C Liquid Effluents - Site (Quarters 1, 2, 3, and 4) 23 1-3A Doses to a Member of the Public Due to Liquid 25 Releases Unit 1 (Quarters 1,2, 3, and 4) 1-3B Doses to a Member of the Public Due to Liquid 27 Releases 'Unit 2 (Quarters 1,2,3, and 4) 1-4 Minimum Detectable Concentration Liquid Sample 29 Analysis 1-5A Liquid Effluents - Batch Release Summary Unit 1 30 1-5B Liquid Effluents - Batch Release Summary Unit 2 31 1-6A Liquid Effluents - Abnormal Release Summary Unit 1 32 PageS of84

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TABLE LIST OF TABLES PAGE 1-6B Liquid Effluents - Abnormal Release Summary Unit 2 33 2-1A Gaseous Effluents - Summation of All Releases - 41 Unit 1 (Quarters 1, 2, 3, and 4) 2-1B Gaseous Effluents - Summation of All Re/eases- 43 Unit 2 (Quarters 1, 2, 3, and 4) 2-1C Gaseous Effluents - Summation of All Releases - 45 Site (Quarters 1, 2, 3, and 4) 2-2A Gaseous Effluents - Mixed Mode Releases Unit 1 47 (Quarters 1, 2, 3, and 4) 2-2B Gaseous Effluents - Mixed Mode Releases Unit 2 49 (Quarters 1, 2, 3, and 4) 2-2C Gaseous Effluents - Mixed Mode Releases Site 51 (Quarters 1, 2, 3, and 4) 2-3A Gaseous Effluents - Ground Level Releases Unit 1 53 (Quarters 1, 2, 3, and 4) 2-3B Gaseous Effluents - Ground Level Releases Unit 2 55 (Quarters 1, 2, 3, and 4) 2-3C Gaseous Effluents - Ground Level Releases Site 57 (Quarters 1, 2, 3, and 4) 2-4A Air Doses Due to Noble Gases In Gaseous Releases 59 Unit 1 (Quarters 1, 2, 3, and 4) 2-4B Air Doses Due to Noble Gases In Gaseous Releases 61 Unit 2 (Quarters 1, 2, 3, and 4) 2-5A Doses to a Member of the Public Due to Radlolodlnes, 63 Tritium, and Particulates in Gaseous Releases Unit 1 (Quarters 1, 2, 3, and 4)

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TABLE LIST OF TABLES PAGE 2-5B Doses to a Member of the Public Due to Radlolodlnes, 65 Tritium, and Particulates In Gaseous Releases Unit 2 (Quarters 1, 2, 3, and 4) 2-6 Minimum Detectable Concentration - Gaseous Sample . 67 Analysis 2-7A Gaseous Effluents - Batch Release Summary Unit 1 68 2-78 Gaseous Effluents - Batch Release Summary Unit 2 68 2-8A

Gaseous Effluents - Abnormal Release Summary 70 Unit 1 2-8B Gaseous Effluents - Abnormal Release Summary 71 Unit 2 3-1 Solid Waste and Irradiated Fuel Shipments 73 4-1 Doses to a Member of the Public Due to Activities 79 Inside the Site Boundary Page? of84

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1.0 Liquid Effluents 1.1 Regulatory Requirements 1.1.1 Concentration limits In accordance with Technical Specification 5.5.4.b, the concentration .of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited at all times to ten times the concentrations specified in 10 CFR 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 1 E-04 J.1CVmf total activity. .

1.1.2 Dose limits The dose or dose commitmentto a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shall be limited as follows:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mremsto 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.

1.2 Effluent Concentration Limit (ECl)

ECl values used for determining the allowable liqUid radwaste release rates and concentrations for the principal gamma emitters, 1-131, tritium, Sr-89, Sr-90 and Fe-55 are taken from 10 CFR Part 20, Appendix B, Table 2, Column 2. A tolerance factor of up to 10 is utilized to allow flexibility in establishing practical monitor set points which can accommodate effluent releases'at concentrations higher than the ECl values stated in 10 CFR 20, AppendiX B, Table 2, Column 2.

For dissolved or entrained noble gases in liqUid radwaste, the ECl is 1E-04 J.1CVml total activity.

For gross alpha in liquid radwaste, the ECl is 2 E-09 J.1CVml.

For all the above radionuclides or categories of radioactivity, the overall ECl fraction is determined in accordance with 10 CFR Part 20, AppendiX B. The method utilizing the ECl fraction to determine release rates and liquid radwaste effluent radiation monitor set points is described in Subsection 1.3 of this report.

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1.3 Measurements and Approximations of Total Radioactivity 1.3.1 Total Radioactivity Determination Prior to the release of any tank containing liquid radwaste, and following the required recirculation, samples are collected and analyzed in accordance with the Offsite Dose Calculation Manual (ODCM) Table 2-3 "Radioactive Liquid Waste Sampling and Analysis Program-. A sample from each tank which is planned for release is analyzed for principal gamma emitters, 1-131, and dissolved and entrained noble gases by gamma spectroscopy. Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from the tanks, which are released. Liquid radwaste sample analyses are performed as follows:

MEASUREMENT FREQUENCY METHOD

1. Gamma Isotopic Each Batch Gamma Spectroscopy with computerized data reduction.

2. Dissolved or entrained Each Batch Gamma Spectroscopy noble gases with computerized data reduction

3. Tritium Monthly Distillation and Composite liquid scintillation counting

4. Gross Alpha Monthly Gas flow proportional Composite counting

5. Sr-89 & Sr-90 Quarterly Chemical separation Composite and gas flow proportional or scintillation counting

6. Fe-55 Quarterly Chemical separation Composite and liqUid scintillation counting Page 9 of 84

1.3.1 Total Radioactivity Determination cont'd Gamma isotopic measurements are performed using germanium detectors with a resolution of 2.1 keV or lower. A peak search of the resulting gamma ray spectrum is performed by the computer system. Energy and net count data for all significant peaks are determined, and a quantitative reduction or MOC calculation is performed. This ensures that the MDC's are met for the nuclides specified in ODCM Chapter 10 (i.e., Mn-54, Fe-59. Co-58, Co-60, Zn*65, Mo-99, Cs-134. Cs-137, Ce-141 and Ce-144). The quantitative calculations. corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.

Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 are, in some cases, analyzed offsite.

ECl fraction is determined usingradionuclide concentrations of a tank planned for release, the most current results available for tritium. gross alpha. Sr-89, Sr-90 and Fe-55 and the corresponding ECl values.

This ECl fraction is used, with appropriate safety factors, tolerance factors, and the minimum assured dilution stream flow to calculate maximum permissible release rates and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the Offsite Dose Calculation Manual (ODCM) are not exceeded.

A monitor reading in excess of the calculated setpoint results in an automatic termination of the liquid radwaste discharge. Uquid effluent discharge is also automatically terminated if the dilution stream flow rate falls below the minimum assured dilution flow rate used in the setpoint calculations and established as a setpoint on the dilution stream flow monitor.

Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent radiation monitor calibrations are entered into the computer and a pre-release printout is generated. If the release is not permissible, appropriate warnings will be displayed on the computer screen. If the release is permissible, it is approved by the Chemistry Department and sent to the Operations Department for approval and release. When the release Is completed, the necessary data from the release (i.e., release volume, etc.) are provided by the Operations Department to the Chemistry Department. These data are input to the computer and a post-release printout is generated. The post release printout contains the actual release rates, release concentrations and quantities, actual dilution flow, and calculated doses to an individual.

Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.

Page 100(84

1.3.2 Total Error Estimation The total or maximum error associated with the effluent measurement includes the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error is not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid effluents.

a. Fission and activation total release was calculated from sample analysis results and release point flow rates.

Sampling and statistical error 10%

Counting Equipment Calibration 10%

Tank Volumes and System Flow Rates 20%

40%

TOTAL ERROR

b. Total Tritium release was calculated from sample analysis results and release point volumes.

Sampling and statistical errors 10%

Counting equipment calibration 10%

Tank volumes and system flow rate 20%

TOTAL ERROR 40%

c. Dissolved and entrained gases were calculated from sample analysis results and release point volumes.

Sampling and statistical error 20%

Counting equipment calibration 10%

Tank volumes and system flow rate 20%

TOTAL ERROR 500/0

d. Gross alpha radioactivity was calculated from sample analysis results and release point volumes.

Sampling and statistical error 10%

Counting Equipment calibration 10%

Tank volumes and system flowrates 20%

TOTAL ERROR 40%

Page 11 of84

1.3.2 Total Error Estimation cont'd

e. Volume of waste prior to dilution was calculated from level indicators on the tanks and pump discharge flow rates and times.

Level Indicator error 10%

Operator Interpretation of gauge 10%

TOTAL ERROR 20%

f. Volume of dilution water used was calculated from flow totalizers and pump discharge flow rates and times.

Flow totalizer error 10%

Operator interpretation of gauge 10%

TOTAL ERROR 20%

g. Gross alpha, Sr-89, Sr-90, Fe-55 and H-3 radioactivity has an additional error associated with sample compositing.

Compositing sample error . 5%

1.4 Liquid Effluent Release Data Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Tables 1-1A, 1-1B, 1-1C, 1-2A, 1-2B and 1-2C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all four quarters.

1.5 Radiological Impact Due to Liquid Releases Doses to an individual due to radioactivity in liqUid effluent were calculated in accordance with the Offslte Dose Calculation Manual.

Results are presented in Table 1-3A for Unit 1 and 1-3B for Unit 2, for all four quarters.

1.6 Liquid Effluents - Batch Releases Batch release information for liquid effluents is presented in Table1-5A for Unit 1 and Table 1-5B for Unit 2.

1.7 Liquid Effluents - Abnormal Releases There were no abnormal releases for this reporting period.

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TABLE l-lA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Summation of All Releases Unit: 1 Starting: l-Jan-2003 Ending : 30-Jun-2003 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

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A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 4.49E-03 1.87E-02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD pCi/ML 3.35E-08 6.71E-08 3 I PERCENT OF APPLICABLE LIMIT

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B. TRITIUM

1. TOTAL RELEASE CURIES 7.85E+01 3.29E+02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD pCi/ML 5.86E-04 1. 18E-03

3. PERCENT OF APPLICABLE LIMIT C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 1.14E-05 6.10E-04 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD pCi/ML 8.48E-11 2.19E-09

3. PERCENT OF APPLICABLE LIMIT D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES O.OOE+OO O.OOE+OO 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 4.21E+05 7.05E+05 20 F. VOLUME OF DILUTION WATER USED LITERS 1.34E+08 2.78E+08 20

Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

Page 13 of84

TABLE l-lA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Summation of All Releases Unit: 1 Starting: 1-Jul-2003 Ending : 31-Dec-2003 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT

~OR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.84E-02 8.67E-03 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD l1Ci/ML 4.75E-08 2.5SE-08

3. PERCENT OF APPLICABLE LIMIT *

B. TRITIUM

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1. TOTAL RELEASE CURIES 4.62E+02 1.70E+02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD l1Ci/ML 1.19E-03 S.00E-04

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES S.71E-OS 3.18E-04 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD l1Ci/ML 1.47E-10 9.33E-IO

3. PERCENT OF APPLICABLE LIMIT *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES O.OOE+OO O.OOE+OO 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 9.83E+05 9.S4E+OS 20 F. VOLUME OF DILUTION WATER USED LITERS 3.87E+08 3.40E+08 20

Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

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TABLE 1-lB Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Summation of All Releases Unit: 2 Starting: 1-Jan-2003 Ending : 30-Jun-2003 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.76E-03 3.61E-03 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD ~Ci/ML 2.22E-08 3.94E-08

3. PERCENT OF APPLICABLE LIMIT % *

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B. TRITIUM

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1. TOTAL RELEASE CURIES 9.05E+01 1.11E+02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD ~Ci/ML 1.14E-03 1.21E-03

3. PERCENT OF APPLICABLE LIMIT C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 2.13E-05 3.73E-04 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD ~Ci/ML 2.68E-10 4.06E-09

3. PERCENT OF APPLICABLE LIMIT D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES O.OOE+OO O.OOE+OO 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 2.41E+05 1.94E+05 20 F. VOLUME OF DILUTION WATER USED LITERS 7.93E+07 9.16E+07 20

Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

Page IS of84

TABLE 1-lB Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Summation of All Releases Unit: 2 Starting: 1-Jul-2003 Ending : 31-Dec-2003 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR ,

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 4.13E-02 2.30E-03 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD l1Ci/ML 7.40E-08 3.35E-08

3. PERCENT OF APPLICABLE LIMIT ." ."

B. TRITIUM

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1. TOTAL RELEASE CURIES 6.74E+02 1.33E+01 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD l1Ci/ML 1.21E-03 1.94E-04

3. PERCENT OF APPLICABLE LIMIT ."

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 7.99E-04 O.OOE+OO 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD l1Ci/ML 1.43E-09 O.OOE+OO

3. PERCENT OF APPLICABLE LIMIT ."

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES O.OOE+OO O.OOE+OO 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 1.39E+06 2.65E+05 20 F. VOLUME OF DILUTION WATER USED LITERS 5.57E+08 6.84E+07 20

Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

Page 160f84

TABLE 1-lC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Summation of All Releases Unit: Site Starting: 1-Jan-2003 Ending : 30-Jun-2003 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 6.25E-03 2.23E-02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD pCi/ML 2.93E-08 6.02E-08 3.tPERCENT OF APPLICABLE LIMIT *

B. TRITIUM

1. TOTAL RELEASE CURIES 1.69E+02 4.40E+02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD PCi/ML 7.92E-04 1.19E-03

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 3.26E-05 9.83E-04 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD pCi/ML 1.53E-10 2.65E-09

3. PERCENT OF APPLICABLE LIMIT *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES O.OOE+OO O.OOE+OO 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 6.62E+05 8.99E+05 20 F. VOLUME OF DILUTION WATER USED LITERS 2.13E+08 3.70E+08 20

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Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

Page 17 of84

TABLE 1-lC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Summation of All Releases Unit: Site Starting: 1-Jul-2003 Ending : 31-Dec-2003 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ER,ROR "

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 5.97E-02 1.10E-02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD ~Ci/ML 6.31E-08 2.68E-08

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3. PERCENT OF APPLICABLE LIMIT *

B. TRITIUM

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1. TOTAL RELEASE CURIES 1.14E+03 1.83E+02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD ~Ci/ML 1.20E-03 4.48E-04

3. PERCENT OF APPLICABLE LIMIT *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 8.56E-04 3.18E-04 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD ~Ci/ML 9.05E-10 7.76E-10

3. PERCENT OF APPLICABLE LIMIT *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES O.OOE+OO O.OOE+OO 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 2.37E+06 1.22E+06 20 F. VOLUME OF DILUTION WATER USED LITERS 9.43E+08 4.08E+08 20

Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

Page 18 of84

TABLE 1-2A'*'

vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents Unit: 1 Starting: 1-Jan-2003 Ending : 30-Jun-2003 I CONTINUOUS MODE BATCH MODE

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NUCLIDE UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 I QUARTER 21 H-3 CURIES I O.OOE+OO I O.OOE+OO I 7.8sE+Ol I 3.29E+02 I FISSION & ACTIVATION PRODUCTS AG-110M CURIES O.OOE+OO O.OOE+OO 9.10E-06 O.OOE+OO BE-7. CURIES O.OOE+OO O.OOE+OO O.OOE+OO 8.27E-06 CO-57 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 6.21E-06 CO-58 CURIES O.OOE+OO O.OOE+OO 2.41E-04 1. 27E-03 CO-60 CURIES O.OOE+OO O.OOE+OO 4.87E-04 2.39E-03 CR-s1 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 4.88E-Os CS-134 CURIES O.OOE+OO O.OOE+OO 4.43E-Os 8.66E-05 CS-137 CURIES O.OOE+OO O.OOE+OO 1.83E-04 4.02E-04 FE-55 CURIES O.OOE+OO O.OOE+OO 1.93E-03 1.35E-02 MN-54 CURIES O.OOE+OO O.OOE+OO 4.s3E-Os 3.47E-04 NB-95 CURIES O.OOE+OO O.OOE+OO 9.10E-06 1. 77E-04 NB-97 CURIES O.OOE+OO O.OOE+OO 1.20E-Os 3.19E-05 SB-12s CURIES O.OOE+OO O.OOE+OO 7.43E-04 3.93E-04 SR-89 CURIES O.OOE+OO O.OOE+OO 2.73E-12 1.67E-Os SR-92 CURIES O.OOE+OO O.OOE+OO 8.6sE-07 O.OOE+OO TE-125M CURIES O.OOE+OO O.OOE+OO 7.83E-04 O.OOE+OO ZR-95 CURIES O.OOE+OO O.OOE+OO O.OOE+OO s.53E-05 TOTALS CURIES I O.OOE+OO I O.OOE+OO I 4.49E-03 I 1.87E-02 I DISSOLVED AND ENTRAINED GASES XE-133 I CURIES I O.OOE+OO I O.OOE+OO I 1.14E-Os I 6.10E-04 I TOTALS I CURIES IO.OOE+OO I O.OOE+OO I 1.14E-Os I 6.10E-04 l---

'*' Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.

Page 19 of84

TABLE 1-2A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents Unit: 1 Starting: 1-Jul-2003 Ending : 31-Dec-2003 I CONTINUOUS MODE BATCH MOQE NUCLIDE UNIT I QUARTER 3 IQUARTER 4 IQUARTER 3 I QUARTER 4 I

~---------------------- --------------------------

H-3 CURIES I O.OOE+OO I O.OOE+OO I 4.62E+02 l 1.70E+02 I FISSION & ACTIVATION PRODUCTS CO-57 CURIES O.OOE+OO O.OOE+OO 8.56E-06 2.21E-06 CO-58 CURIES O.OOE+OO O.OOE+OO 2.66E-03 9.12E-04 CO-60 CURIES O.OOE+OO O.OOE+OO 3.75E-03 1.62E-03 CR-51 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 3.04E-04 CS-134 CURIES O.OOE+OO O.OOE+OO 1.58E-04 1.99E-OS CS-137 CURIES O.OOE+OO O.OOE+OO 6.42E-04 6.14E-OS FE-55 CURIES O.OOE+OO , O.OOE+OO 5.39E-O~ 3.43E-03 FE-59 CURIES O.OOE+OO O.OOE+OO 4.16E-06 2.04E-OS 1-133 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 1.81E-06 MN-54 CURIES O.OOE+OO O.OOE+OO 5.89E-04 1.16E-04 NA-24 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 9.49E-06 NB-95 CURIES O.OOE+OO O.OOE+OO 4.S4E-OS S.99E-OS NB-97 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 1.48E-OS S5-124 CURIES O.OOE+OO O.OOE+OO 1. 65E-OS O.OOE+OO S5-125 CURIES O.OOE+OO O.OOE+OO 2.18E-03 7.46E-OS SR-89 CURIES O.OOE+OO O.OOE+OO 3.44E-OS 2.64E-06 TE-125M CURIES O.OOE+OO O.OOE+OO 2.92E-03 1. 99E-03 ZR-95 CURIES O.OOE+OO O.OOE+OO 2.63E-OS 3.60E-OS TOTALS CURIES I O.OOE+OO I O.OOE+OO I 1.84E-02 I 8.67E-03 I DISSOLVED AND ENTRAINED GASES XE-133 XE-135 CURIES CURIES I O.OOE+OO O.OOE+OO I O.OOE+OO O.OOE+OO I S.71E-OS O.OOE+OO I 3.16E-04 1.62E-06 I

TOTALS CURIES I O.OOE+OO I O.OOE+OO I S.71E-OS I 3.18E-04 I

Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 20 of 84

TABLE 1-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents Unit: 2 Starting: 1-Jan-2003 Ending : 30-Jun-2003 I CONTINUOUS MODE BATCH MODE NUCLIDE UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER 2 I H-3 CURIES I O.OOE+OO I O.OOE+OO I 9.0SE+01 I 1.11E+02 I FISSION & ACTIVATION PRODUCTS

t--------------------------------------------------------------------------

AG-110M CURIES O.OOE+OO O.OOE+OO 7.86E-06 O.OOE+OO CO-58 CURIESO.OOE+OO O.OOE+OO 1.60E-04 3.95E-04 CO-60 CURIES O.OOE+OO O.QOE+OO 2.6SE-04 1.20E-03 CS-134 CURIES O.OOE+OO O.OOE+OO 9.06E-06 2.25E-OS CS-137 CURIES O.OOE+OO O.OOE+OO 4.23E-05 5.81E-05 FE-55 CURIES O.OOE+OO O.OOE+OO 4.75E-04 1.66E-03 FE-59 CURIES O.OQE+OO O.OOE+OO O.OOE+OO 7.05E-06 MN-54 CURIES O.OOE+OO O.OOE+OO 1.34E-OS 1.09E-04 NB-95 CURIES O.OOE+OO O. OOE+OO O. OOE+OO 6. 43E-OS NB-97 CURIES O.OOE+OO O.OOE+OO 9.S1E-06 9.75E-06 SB-124 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 1.25E-OS SB-125 CURIES O.OOE+OO O.OOE+OO 1.30E-04 S.92E-OS SR-89 CURIES O.OOE+OO O.OOE+OO 2.S8E-06 6.46E-06 SR-92 CURIES O.OOE+OO O.OOE+OO 3.82E-06 O.OOE+OO TE-125M CURIES O.OOE+OO O.OOE+OO 6.44E-04 O.OOE+OO ZR-95 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 1.57E-05 TOTALS CURIES I O.OOE+OO I O.OOE+OO I 1.76E-03 I 3.61E-03 I DISSOLVED AND ENTRAINED GASES XE-133 CURIES 1. 0 . OOE+OO I O. OOE+OO I O. OOE+OO I 3. 73E-04 I XE-133M CURIES O.OOE+OO O.OOE+OO 2.13E-OS O.OOE+OO TOTALS CURIES I O.OOE+OO I O.OOE+OO I 2.13E-05 I 3.73E-04 I

Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page2! of84

TABLE 1-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents Unit: 2 Starting: l-Jul-2003 Ending : 31-Dec-2003 I CONTINUOUS MODE BATCH MODE NUCLIDE UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 I H-3 CURIES I O.OOE+OO I O.OOE+OO I 6.74E+02.1 1.33E+Ol I FISSION & ACTIVATION PRODUCTS CO-57 CURIES O.OOE+OO O.OOE+OO 3.13E-06 O.OOE+OO CO-58 CURIES O.OOE+OO O.OOE+OO 5.47E-03 1. 63E-04 CO-60 CURIES O.OOE+OO O.OOE+OO 5.19E-03 9.S7E-04 CR-51 CURIES O.OOE+OO O.OOE+OO O.OOE+OO S.90E-OS CS-134 CURIES O.OOE+OO O.OOE+OO 2.63E-05 3.9SE-06 CS-137 CURIES O.OOE+OO O.OOE+OO 1.48E-04 3.34E-OS FE-55 CURIES O.OOE+OO O.OOE+OO 2.66E-02 9.S2E-04 FE-59 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 1.6SE-OS MN-54 CURIES O.OOE+OO O.OOE+OO 8.94E-04 4.34E-OS NA-24 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 1.73E-05 NB-95 CURIES O.OOE+OO O.OOE+OO S~73E-OS 1.60E-OS NB-97 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 1.23E-06 SB-124 CURIES O.OOE+OO O.OOE+OO 9.16E-06 O.OOE+OO SB-125 CURIES O.OOE+OO O.OOE+OO 2.11E-03 2.94E-05 SR-89 CURIES O.OOE+OO O.OOE+OO 2.22E-06 2.33E-06 TE-125M CURIES O.OOE+OO O.OOE+OO 7.16E-04 O.OOE+OO TE-132 CURIES O.OOE+OO O.OOE+OO 3.88E-06 O.OOE+OO ZR-95 CURIES O.OOE+OO O.OOE+OO 2.68E-OS 6.00E-06 TOTALS CURIES I O.OOE+OO I O.OOE+OO I 4.13E-02 I 2.30E-03 I DISSOLVED AND ENTRAINED GASES XE-133 I CURIES I O. OOE+OO I O.OOE+OO I 7. 99E-04 I O. OOE+OO I TOTALS I CURIES I O. OOE+OO I O. OOE+OO I 7. 99E-04 1 O. OOE+OO I

Zeroes in this table indicate that no radioactivity was present See Table 1-.

at detectable levels.

for typical minimum detectable concentrations.

Page 22 of84

TABLE 1-2C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents Unit: Site Starting: I-Jan-2003 Ending : 30-Jun-2003 I CONTINUOUS MODE BATCH MODE

~-------------------------------- --------------------------

NUCLIDE UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 I QUARTER 2 I H-3 CURIES I O.OOE+OO I O.OOE+OO I 1.69E+02 I 4.40E+02 I

~-------------------------

FISSION & ACTIVATION PRODUCTS AG-I10M CURIES O.OOE+OO O.OOE+OO 1.70E-05 O.OOB+OO BE-7. CURIES . O.OOE+OO O.OOE+OO O.OOE+OO 8.27E-06 CO-57 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 6.21B-06 CO-58 CURIES O.OOE+OO O.OOE+OO 4.01E-04 1.66E-03 CO-60 CURIES O.OOE+OO O.OOE+OO 7.52B-04 3.59B-03 CR-51 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 4.88E-05 CS-134 CURIES O.OOE+OO O.OOE+OO 5.34E-05 1.09E-04 CS-137 CURIES O.OOE+OO O.OOE+OO 2.26B-04 4.60B-04 FE-55 CURIES O.OOE+OO O.OOE+OO 2.40B-03 1. 51B-02 FE-59 CURIES . O.OOE+OO O.OOE+OO O.OOB+OO 7.05E-06 MN-54 CURIES O.OOE+OO O.OOE+OO 5.87B-05 4.56E-04 NB-95 CURIES O.OOE+OO O.OOE+OO 9.10B-06 2.41B-04 NB-97 CURIES O.OOE+OO O.OOE+OO 2.15E-05 4.17B-05 SB-124 CURIES O.OOE+OO O.OOE+OO O.OOB+OO 1.25E-05 SB-125 CURIES O.OOE+OO O.OOE+OO 8.73B-04 4.52B-04 SR-89 CURIES O.OOE+OO O.OOE+OO 2.58B-06 2.32E-05 SR-92 CURIES O.OOE+OO O.OOE+OO 4.69B-06 O.OOB+OO TE-125M CURIES O.OOE+OO O.OOE+OO 1.43B-03 O.OOE+OO ZR-95 CURIES O.OOE+OO O.OOE+OO O.OOB+OO 7.10E-05 TOTALS CURIBS I O.OOB+OO I O.OOE+OO I 6.25B-03 I 2.23B-02 I DISSOLVED AND ENTRAINED GASES XE-133 XE-133M CURIES CURIES I O.OOE+OO O.OOE+OO I O.OOE+OO O.OOE+OO I 1.14E-05 2.13E-05 I 9.83E-04 O.OOE+OO I

TOTALS CURIES I O.OOB+OO I O.OOE+OO I 3.26E-05 I 9.83E-04 I

Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 23 of84 L __

TABLE 1-2C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT- 2003 Liquid Effluents Unit: Site Starting: l-Jul-2003 Ending : 31-Dec-2003 I CONTINUOUS MODE BATCH MO~E NUCLIDE UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 I H-3 CURIES I O.OOE+OO I O.OOE+OO I 1.14E+03.1 1.83E+02 I FISSION & ACTIVATION PRODUCTS CO-57 CURIES O.OOE+OO O.OOE+OO 1.17E-05 2.21E-06 CO-58 CURIES O.OOE+OO O.OOE+OO 8.14E-03 1.08E-03 CO-60 CURIES O.OOE+OO O.OOE+OO 8.94E-03 2.57E-03 CR-51 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 3.63E-04 CS-134 CURIES O.OOE+OO O.OOE+OO 1.85E-04 2.39E-05 CS-137 CURIES O.OOE+OO O.OOE+.QO 7.90E-04 9.47E-05 FE-55 CURIES O.OOE+OO O.OOE+OO 3.20E-02 4.38E-03 FE-59 CURIES O.OOE+OO O.OOE+OO 4.16E-06 3.70E-05 1-133 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 1.81E-06 MN-54 CURIES O.OOE+OO O.OOE+OO 1. 48E-03 1.60E-04 NA-24 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 2.68E-05 NB-95 CURIES O.OOE+OO O.OOE+OO 1.03E-04 7.59E-05 NB-97 CURIES O.OOE+OO O.OOE+OO O.OOE+OO 1.60E-05 SB-124 CURIES O.OOE+OO O.OOE+OO 2.56E-05 O.OOE+OO SB-125 CURIES O.OOE+OO O.OOE+OO 4.30E-03 1.04E-04 SR-89 CURIES O.OOE+OO O.OOE+OO 3.66E-05 4.98E-06 TE-125M CURIES O.OOE+OO O.OOE+OO 3.63E-03 1.99E-03 TE-132 CURIES O.OOE+OO O.OOE+OO 3.88E-06 O.OOE+OO ZR-95 CURIES O.OOE+OO O.OOE+OO 5.30E-05 4.20E-05 TOTALS CURIES I O.OOE+OO I O.OOE+OO I 5.97E-02 I 1.10E-02 I DISSOLVED AND ENTRAINED GASES XE-135 CURIES I O.OOE+OO I O.OOE+OO O.OOE+OO I 8.56E-04 O.OOE+OO I

XE-133 CURIES O.OOE+OO 3.16E-04 1.62E-06 I

TOTALS CURIES I O.OOE+OO I O.OOE+OO I 8.56E-04 I 3.18E-04 I

Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 24 of84

TABLE 1-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 1 Starting: 01-Jan-2003 Ending: 30-Jun-2003 Cumulative Doses per Quarter

~~-------------------------------- --------------------

Organ ODCM Units Quarter % of Quarter % of Limit 1 ODeM 2 ODCM Limit Limit Bone 5.0 mrem 1.20E-03 2.40E-02 2.65E-03 5.30E-02 Liver 5.0 mrem 4.45E-03 8.91E-02 1.30E-02 2.60E-01 TBody 1.5 mrem .3.91E-03 2.60E-01 1.18E-02 7.84E-Ol ThYroid 5.0 mrem 2.70E-03 5.39E-02 9.14E-03 1.83E-01 Kidney 5.0 mrem 3.37E-03 6.73E-02 1.04E-02 2.08E-01 Lund 5.0 mrem 4.10E-03 8.20E-02 1.03E-02 2.06E-01 GILLI 5.0 mrem 2.99E-03 5.97E-02 9.75E-03 1.95E-01

--------~-----------

cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 3.85E-03 3.85E-02 Liver 10.0 mrem 1.75E-02 1.75E-01 TBody 3.0 mrem 1.57E-02 5.22E-01 ThYroid 10.0 mrem 1.18E-02 1.18E-01 Kidney 10.0 mrem 1. 38E-02 1. 38E-01 Lung 10.0 mrem 1.44E-02 1.44E-01 GILLI 10.0 mrem 1. 27E-02 1.27E-01 Pagc2S of84

'------------,-----_._._-<'~ '-'-'---------

TABLE 1-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 1 Starting: 01-Jul-2003 Ending: 31-Dec-2003 Cumulative Doses per Quarter Organ aDeM Units Quarter % of Quarter % of Limit 3 aDeM 4 aDeM Limit Limit Bone 5.0 mrem 5.99E-03 1.20E-01 5.89E-03 1.18E-01 Liver 5.0 mrem 2.15E-02 4.31E-01 6.52E-03 1.30E-01 TBody 1.5 mrem 1.88E-02 1.25E+00 5.82E-03 3.88E-01 Thyroid 5.0 mrem 1.27E-02 2.54E-01 4.83E-03 9.66E-02 Kidney 5.0 mrem 1.62E-02 3.25E-01 5.55E-03 1.llE-01 Lung 5.0 mrem 1.82E-02 3.64E-01 5.45E-03 1.09E-01 GILLI 5.0 mrem 1.46E-02 2.92E-01 6.57E-03 1. 31E-01 Cumulative Doses per Year

------------~-------

Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 1. 57E-02 1. 57E-01 Liver 10.0 mrem 4.55E-02 4.55E-01 TBody 3.0 mrem 4.03E-02 1. 34E+00 Thyroid 10.0 mrem 2.93E-02 2.93E-01 Kidney 10.0 mrem 3.55E-02 3.55E-01 Lung 10.0 mrem 3.81E-02 3.81E-01 GILLI 10.0 mrem 3.39E-02 3.39E-01 Page 26 of84 L

TABLE 1-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jan-2003 Ending: 30-Jun-2003 Cumulative Doses per Quarter Organ ODeM Units Quarter % of Quarter % of Limit 1 ODCM 2 ODCM Limit Limit Bone 5.0 mram 2.94E-04 5.87E-03 5.60E-04 1. 12E-02 Liver 5.0 mram 3.38E-03 6.77E-.02 3.78E-03 7.57E-02 TBody 1.5 mram 3.26E-03 2.17E-01 3.53E-03 2.35E-01 Thyroid 5.0 mram 2.98E-03 5.97E-02 2.89E-03 5.79E-02 Kidney 5.0 mram 3.20E-03 6.41E-02 3.18E-03 6.37E-02 Lung. 5.0 mram 3.23E-03 6.45E-02 3.14E-03 6.28E-02 GILLI 5.0 mram 3.13E-03 6.25E-02 3.14E-03 6.28E-02 cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mram 8.54E-04 8.54E-03 Liver 10.0 mram 7.17E-03 7.17E-02 TBody 3.0 mram 6.78E-03 2.26E-01 Thyroid 10.0 mram 5.88E-03 5.88E-02 Kidney 10.0 mram 6.39E-03 6.39E-02 Lung 10.0 mram 6.37E-03 6.37E-02 GILLI 10.0 mrem 6.26E-03 6.26E-02 Page 27 of84

TABLE 1-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jul-2003 Ending: 31-Dec-2003 Cumulative Doses per Quarter Organ ODeM Units Quarter % of Quarter % of Limit 3 ODeM 4 ODCM Limit Limit Bone 5.0 mrem 1. 92E-03 3.84E-02 3.02E-04 6.0n:-03 Liver 5.0 mrem 2.15E-02 4.30E-01 7.83E-04 1. 57E-02 TBody 1.5 mrem 2.06E-02 1.37E+00 6.48E-04 4.32E-02 Thyroid 5.0 mrem 1.90E-02 3.79E-01 3.54E-04 7.08E-03 Kidney 5.0 mrem 1. 98E-02 3.97E-01 4.93E-04 9.86E-03 Lung 5.0 mrem 2.43E-02 4.86E-01 4.79E-04 9.57E-03 GILLI 5.0 mrem 2.08E-02 4.17E-01 5.12E-04 1.02E-02

~-------------- --------------------

Cumulative Doses per Year

~--------------------------------- --------------------

Organ ODeM Units Year to % of Limit Ending ODCM Date Limit

~--------------------------------- --------------------

Bone 10.0 mrem 3.08E-03 3.08E-02 Liver 10.0 mrem 2.95E-02 2.95E-01 TBody 3.0 mrem 2.81E-02 9.35E-01 Thyroid 10.0 mrem 2.52E-02 2.52E-01 Kidney 10.0 mrem 2.67E-02 2.67E-01 Lung 10.0 mrem 3.11E-02 3.llE-01 GILLI 10.0 mrem 2.76E-02 2.76E-01 Page2S of84

TABLE 1-4 VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 MINIMUM DETECTABLE CONCENTRATIONS - L1aUID SAMPLE ANALYSES JANUARY 2003 - DECEMBER 2003 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

RAIflIONUCLIDE MDC UNITS*

Mn-54 2.73E-OS J-LCVml Fe-59 S.33E-OS J-LCVml Co-5S 3.7SE-QS J-LCVml Co-60 6.76E-OS J-LCVml Zn-65 1.32E-Q7 J-LCVml Mo-99 4.31E-Q7 J-LCVml Cs-134 3.06E-OS J-LCVml Cs-137 4.51E-QS J-LCVml Ce-141 6.99E-QS J-LCVml Ce-144 2.95E-Q7 J-LCVml 1-131 5.97E-QS J-LCVml Xe-133 9.11E-OS J-LCVml Xe-135 4.27E-QS J-LCVml Fe-55 1.00E-Q6 J-LCVml Sr-S9 5.00E-QS J-LCVml Sr-90 7.00E-Q9 J-LCVml H-3 2.00E-06 J-LCVml Gross Alpha 7.00E-OS J-LCVml Page 29 of 84

TABLE 1-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Batch Release Summary Unit: 1 Starting: 1-Jan-2003 Ending : 30-Jun-2003 NUMBER OF BATCH RELEASES 33 TOTAL TIME PERIOD FOR BATCH RELEASES 5499.03 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 355.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 166.64 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 35.58 MINUTES TABLE 1-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Batch Release Summary Unit: 1 Starting: 1-Jul-2003 Ending : 31-Dec-2003 NUMBER OF BATCH RELEASES 55 TOTAL TIME PERIOD FOR BATCH RELEASES 13489.33 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 4692.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 245.26 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 23.80 MINUTES The average flow rate of the Savannah River at Augusta for the Radioactive Effluent Release Report period was obtained from the U.S. Army Corps of Engineers Savannah District Historic Data web page http://water.sas.usace.a~.mil/tdis.htm1.

The average flow rate for 2003 was 9413 cubic feet per sec.

Page 30 of 84

TABLE 1-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2{)03 Liquid Effluents - Batch Release.Summary Unit: 2 Starting: 1-Jan-2003 Ending : 30-Jun-2003 NUMBER OF BATCH RELEASES 15 TOTAL TIME PERIOD FOR BATCH RELEASES 2168.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 345.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 144.53 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 36.53 MINUTES TABLE 1-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Batch Release Summary Unit: 2 Starting: 1-Jul-2003 Ending : 31-Dec-2003 NUMBER OF BATCH RELEASES 40 TOTAL TIME PERIOD FOR BATCH RELEASES 9077.30 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 1327.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 226.93 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 21.67 MINUTES The average flow rate of the Savannah River at Augusta for the Radioactive Effluent Release Report period was obtained from the U.S. Army Corps of Engineers Savannah District Historic Data web page http://water.sas.usace.army.mil/tdis.html.

The average flow rate for 2003 was 9413 cubic feet per sec.

Page 31 of84

TABLE 1-6A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Abnormal Release SUmmary Unit: 1 Starting: l-Jan-2003 Ending' : 30-Jun-2003 NUMBER OF RELEASES o TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES O.OOE+OO CURIES TABLE 1-6A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting: l-Jul-2003 Ending : 31-Dec-2003 NUMBER OF RELEASES o TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES O.OOE+OO CURIES Pagc32of84

TABLE 1-6B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting: l-Jan-2003 Ending : 30-Jun-2003 NUMBER OF RELEASES o TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A. RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES O.OOE+OO CURIES TABLE 1-6B vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting: l-Jul-2003 Ending : 31-Dec-2003 NUMBER OF RELEASES o TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES O.OOE+OO CURIES Page 33 of84

2.0 Gaseous Effluents 2.1 Regulatory Requirements The ODCM Specifications presented in this section are for Unit 1 and Unit 2.

2.1.1 Dose Rate Limits 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 mremslyr. to the whole body and less than or equal to 3000 mremslyr. to the skin and,

b. For lodine-131, for lodine-133, for tritium and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500'mremslyr. to any organ.

2.1.2 Air Doses Due to Noble Gases in Gaseous Releases The air dose due to noble gases released in gaseous effluents, 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 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

2.1.3 Doses to a Member of the Public The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-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.

b. During any calendar year: Less than or equal to 15 mrems to any organ.

Page 34 of84

2.2 Measurements and Approximations of Total Radioactivity 2.2.1 Sample Collection and Analysis Gaseous Effluents at the Vogtle Electric Generating Plant are currently confined to six paths: plant vents (Unit 1 and Unit 2). the condenser air ejector. the steam packing exhauster systems (Unit 1 and Unit 2). Radwaste Processing Facility and the DAW (Dry Active Waste Building).

Waste gas decay tanks are batch released through the Unit 1 plant vent. The containment purges are released through their respective plant vents.

All of the paths with the exception of the DAW and RPF can be continuously monitored for gaseous radioactivity. The RPF is equipp&d with an integrated-

type sample collection device for collecting particulates. Plant vent, containment.

steam jet air ejector. steam-packing exhauster are equipped with an integrated-type sample collection device for collecting particulates and iodines. Samples of the DAW are collected using portable monitoring equipment during periods of operation. During this reporting period. there were no continuous radioactive releases through the condenser air ejector and the steam packing exhauster system vents. There were no releases from the DAW. Batch Waste Gas Decay Tank releases are analyzed for noble gases before each release. The containment atmosphere is analyzed for noble gases prior to each release and for tritium at least on a monthly basis.

Sample analyses results and release flow rates form the basis for calCUlating released quantities of radionuclide specific radioactivity. dose rates associated with gaseous releases. and cumulative doses for the current quarter and year.

With each release period and batch release. radioactivity. dose rates. and cumulative doses are calculated. Cumulative dose results are tabulated. along with the percent of the aDCM limits for each release for the current quarter and year.

Typically achieved minimum detectable concentrations for gaseous effluent sample analyses are reported in Table 2-6.

2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Dos8s The methods for determining release quantities of radioactiVity. dose rates. and cumulative doses are as follows:

2.2.2.1 Fission and Activation Gases The released radioactivity is determined from sample analyses results collected as described above and average release flow rates over the period represented by the collected sample. Dose rates due to noble gases. radioiodines. tritium.

Pagc3S of84

2.2.2.1 Fission and Activation Gases cont'd and particulates are calculated. Calculated dose rates are compared to the dose rate limits specified in ODCM 3.1.2 for noble gases, radioiodines, tritium, and particulates. Dose rate calculation methodology is presented in the ODCM.

Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the highest exposure due to gaseous releases. Air doses are calculated for each release period and cumulative totals are kept for each unit for the calendar quarter and year. Cumulative air doses are compared with the dose limits specified in aDCM 3.1.3. Current percent of the aDCM limits are shown on the printout for each release period. Air dose calculation methodology is presented in the aDCM.

2.2.2.2 Radlolodlnes, Tritium and Particulate Releases The released quantities of radioiodines, tritium and particulates are determined using the weekly samples and release flow rates for the two plant vent release points.

After each quarter, the particulate filters from each plant vent are combined, for strontium analysis. Strontium concentrations are input to the composite file of the computer to be used for release dose rate and individual dose calculations.

Doses to a Member of the Public due to radioiodines, tritium and particulates are calculated for the controlling receptor, which is described in Table 3-70fthe aDCM. Doses are calculated for each release period, and cumulative totals are kept for each unit for the current calendar quarter and year. Cumulative doses are compared to the dose limits specified In aDCM 3.1.4.

Current percent of aDCM limits are shown in this report for each release period.

2.2.2.3 Gross Alpha Release The gross alpha release is calculated each month by counting the particulate filters for each week for gross alpha activity. The four or five weeks' numbers are then recorded on a data sheet and the activity is summed at the end of the month. This concentration is used for release calculations.

2.2.3 Total Error estimation The total or maximum error associated with the effluent measurement will Include the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error are not suggested.

Page 36 of 84

2.2.3 Total Error Estimation cont'd The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste.

Estimated* errors are based on errors in counting equipment calibration, counting statistics, vent-flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.

a. Fission and activation total release was calculated from sample analysis results and release point flow rates.

Sampling and statistical error in counting Counting equipment calibration 10%

10%

Vent flow Rates 10%

Non-steady release rates 20%

TOTAL ERROR 50%

b. 1-131 releases were calculated from each weekly sample:

Statistical error in counting 10%

Counting equipment calibration 100/0 Vent Flow Rates 10%

.Vent Sample Flow Rates 50%

Non-Steady release rates 10%

Losses from charcoal cartridges 10%

TOTAL ERROR 1000/0

c. Particulates with half-lives greater than 8 day releases were calculated from sample and analysis results and release point flow rates.

Statistical error at MDC concentration 10%

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 50%

Non steady release rates 10%

TOTAL ERROR 90%

d. Total tritium releases were calculated from sample analysis results and release point flow rates.

Water vapor in sample stream determination 10%

Vent flow rates 10%

Counting calibration and statistics 10%

Non-steady release rates 10%

TOTAL ERROR 40%

2.2.3 Total Error Estimation cont'd Page 37 of84

e. Gross Alpha radioactivity was calculated from sample analysis results and release point flow rates.

Statistical error at MDC concentration 10%

Counting equipment calibration 10%

Ventflow rates 10%

Vent sample flow rates 50%

Non Steady release rates 10%

TOTAL ERROR 90%

2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Tables 1A, 18, and 1C are found in this report as Tables 2-1A, 2-18, 2-1C, 2-2A, 2-28, 2-2C, 2-3A, 2-38, and 2-3C. Data are presented

on a quarterly basis as required by Regulatory Guide 1.21 .

To complete table 2-1A, and 2-18, the total release for eachof the four categories (fission and activation gases, iodines, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in J.lCVsecond for each category. However, the percent of the ODCM limits are not applicable because VEGP has no curie limits for gaseous releases. Applicable limits are expressed in terms of dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories (tritium, radioiodines, and particulates) are limited as a group as specified in ODCM 3.1.2.

Dose rates due to noble gas releases and due to radioiodines, tritium, and particulate releases were calculated as part of the pre-release and post-release permits. No limits were exceeded for this reporting period.

Gross alpha radioactivity is reported in Table 2-1A, and 2-18 as curies released in each quarter.

Limits for cumulative beta and gamma air doses due to noble gases are specified in ODCM 3.1.3. Cumulative air doses are presented in Table 2-4A, and 2-48 along with the percent of the ODCM limits.

Limits for cumulative doses to a Member of the Public due to radiolodines, tritium and particulates, are specified in ODCM 3.1.4. Cumulative doses to a Member of the Public are presented in Table 2-5A, and 2-58 along with percent of ODCM limits.

Page 38 of84

2.4 Radiological Impact Due to Gaseous Releases Dose rates due to the release of noble gases were calculated for the site in accordance with ODCM 3.4.1.1. Dose rates due to radioiodines, tritium, and particulates in gaseous releases were calculated in accordance with ODCM 3.4.1.2.

Dose rates were calculated as part of pre-release and post release permits, no limits were exceeded for this reporting period.

Cumulative air doses due to noble gas releases were calculated for each unit in accordance with ODCM 3.4.2. These results are presented in Tables 2-4A and 2-4B.

Cumulative doses to a Member of the Public were calculated for each unit in accordance with ODCM 3.4.3. These results are presented in Tables 2-5A and 2-5B.

Dose rates and doses were calculated using the methodology presented in the Vogtle Electric Generating Plant Offsite Dose Calculation Manual.

2.5 Gaseous Effluents* Batch Releases Other data pertinent to batch releases of radioactive gaseous effluent from Unit 1 and Unit 2 are listed in Table 2-7A and 2-7B.

Page 39 of84

2.6 Gaseous Effluents - Abnormal Releases Condition Report # 2003000313 was written on 215/2003 for an unplanned release that happened on 215/2003. This resulted with a loss of 13 psig of WGDT #6 (2-1902-V6-Q06) contents. It was determined that the trouble shooting guide that was being utilized at the time gave a flow path for the waste gas decay tank through Waste Gas Decay Tank #6 vent to the plant vent by way of the auxiliary building. Once operations stopped the trouble shooting and returned the system to its normal configuration, the loss of pressure was ended. Plant Vent monitors had increased during this time. which led chemistry to sample the plant vent. Historically, Unit #2 shows no noble gases. This release from the WGDT #6 showed Xe-133 and Xe-135 in the plant vent samples collected by chemistry. Plant Vent release permit 30029 covers this WGDT #6 Unit #2

unplanned release. Permit 30029 release duration is conservative with respect to the decay tank release duration. Subsequent sample from Unit #2 Plant Vent showed no noble gas activity, which confirms no more WGDT #6 release. Total curie release from this incident is 0.055. Dose and Dose Rates from this release were well within ODCM Limits.

Condition Report # 2003000751 was written on 311812003 for an unplanned release that happened on 3116/2003. This resulted with a loss of 17 psig of WGDT #5 (1-1902-V6-Q05) contents. It was determined that the Common Recombiner Analyzer Drain Valves drain valves A-1902-U4-726 and A-1902-U4-727 were left in the OPEN position which was in error. Once the valves were returned to the correct positions the release terminated and the loss of pressure ceased. This release, while unplanned, was monitored via the plant stack monitors. Permit 30110 was issued to cover this event. Total curie release from this incident is 0.841. Dose and Dose Rates from this release were well within ODCM Limits.

Page 40 0(84

TABLE 2-1A vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Summation of All Releases Unit: 1 Starting l-Jan-2003 Ending : 30~Jun-2003 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR "

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.26E+00 7.84E-02 50

2. AVERAGE RELEASE RATE FOR PERIOD llCi/Sec 1.63E-Ol 9.98E-03

3. PERCENT OF APPLICABLE LIMIT B. RADIOIODINES

1. TOTAL IODINE-131 CURIES *O.OOE+OO O.OOE+OO 100

2. AVERAGE RELEASE RATE FOR PERIOD *llCi/Sec O.OOE+OO O.OOE+OO

3. PERCENT OF APPLICABLE LIMIT C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES O.OOE+OO O.OOE+OO 90

2. AVERAGE RELEASE RATE FOR PERIOD llCi/Sec O.OOE+OO . O.OOE+OO

3. PERCENT OF APPLICABLE LIMIT

4. GROSS ALPHA RADIOACTIVITY CURIES O.OOE+OO O.OOE+OO D. TRITIUM

1. TOTAL RELEASE CURIES 8.49E+00 4.13E+00 40

2. AVERAGE RELEASE RATE FOR PERIOD llCi/Sec 1.09E+00 5.25E-Ol

3. PERCENT OF APPLICABLE LIMIT

Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

Page 41 of84

TABLE 2-1A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Summation of All Releases Unit: 1 Starting 1-Jul-2003 Ending : 31-Dec-2003 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

------~-------------------

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE .CURIES 2.37E-01 1.02E-01 50

2. AVERAGE RELEASE RATE FOR PERIOD

_____l pCi/Sec 2.99E-02 1.28E-02 _

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES O.OOE+OO O.OOE+OO 100

2. AVERAGE RELEASE RATE FOR PERIODpCi/Sec O. OOE+OO O.OOE+OO

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 4.03E-07 8.08E-07 90

2. AVERAGE RELEASE RATE FOR PERIOD pCi/Sec 5.07E-08 1.02E-07

3. PERCENT OF APPLICABLE LIMIT * *

4. GROSS ALPHA RADIOACTIVITY CURIES O.OOE+OO O.OOE+OO D. TRITIUM

1. TOTAL RELEASE CURIES 5.81E+OO 2.07E+01 40

2. AVERAGE RELEASE RATE FOR PERIOD pCi/Sec 7.31E-01 2.61E+00

3. PERCENT OF APPLICABLE LIMIT * *

Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

Page 42 of84

TABLE 2-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Summation of All Releases Unit: 2 Starting l-Jan-2003 Ending : 30-Jun-2003 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR ,

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.01E-Ol 4.24E-02 50

2. AVERAGE RELEASE RATE FOR PERIOD ~Ci/Sec 1.29E-02 5.39E-03 3 .. PERCENT OF APPLICABLE LIMIT

B. RADIOIODINES

-----~--------------------

1. TOTAL IODINE-131 CURIES O.OOE+OO O.OOE+OO 100

--_~_---------------------

2. AVERAGE RELEASE RATE FOR PERIOD ~Ci/Sec O.OOE+OO O.OOE+OO

3. PERCENT OF APPLICABLE LIMIT C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES O~OOE+OO 7.44E-08 90

2. AVERAGE RELEASE RATE FOR PERIOD ~Ci/~ec O.OOE+OO 9.46E-09

3. PERCENT OF APPLICABLE LIMIT .,. .,.

4. GROSS ALPHA RADIOACTIVITY CURIES O.OOE+OO O.OOE+OO D. TRITIUM

--~-----------------------

1. TOTAL RELEASE CURIES 4.79E+00 4.00E+00 40

2. AVERAGE RELEASE RATE FOR PERIOD ~Ci/Sec 6.16E-Ol 5.08E-Ol

3. PERCENT OF APPLICABLE LIMIT .,. .,.

Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

Page 43 of84

'---------,-.- -"~------

TABLE 2-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT -"2003 Gaseous Effluents - Summation of All Releases Unit: 2 Starting 1-Jul-2003 Ending : 31-Dec-2003 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.20E+00 6.88E-02 so

2. t AVERAGE RELEASE RATE FOR PERIOD pCi/Sec 1.51E-01 8.65E-03

3. PERCENT OF APPLICABLE LIMIT *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES O.OOE+OO O.OOE+OO 100

2. AVERAGE RELEASE RATE FOR PERIOD pCi/Sec O.OOE+OO O.OOE+OO

3. PERCENT OF APPLICABLE LIMIT * *

~-------------------------------------------------------------

C. PARTICULATES

1. PARTICULATES(HALF-LlVES>8 DAYS) CURIES 4.61E-08 4.56E-07 90

2. AVERAGE RELEASE RATE FOR PERIOD pCi/Sec 5. 80E-09 5.73E-08

3. PERCENT OF APPLICABLE LIMIT * *

4. GROSS ALPHA RADIOACTIVITY CURIES O.OOE+OO O.OOE+OO D. TRITIUM

1. TOTAL RELEASE CURIES 9.01E+00 5.70E-03 40

2. AVERAGE RELEASE RATE FOR PERIOD pCi/Sec 1.13E+00 7.17E-04

3. PERCENT OF APPLICABLE LIMIT * *

Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

Page 44 of 84

TABLE 2-1C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Summation of All Releases Unit: Site Starting 1-Jan-2003 Ending : 30-Jun-2003 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR ,

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.37E+00 1. 21E-Ol 50

2. AVERAGE RELEASE RATE FOR PERIOD ~Ci/Sec 1.76E-01 1~5*4E-02

3. PERCENT OF APPLICABLE LIMIT *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIESO.OOE+OO O.OOE+OO 100

2. AVERAGE RELEASE RATE FOR PERIOD ~Ci/Sec O.OOE+OO O.OOE+OO

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES (HALF-LIVES>8 DAYS) CURIES O.OOE+OO 7.44E-08 90

2. AVERAGE RELEASE RATE FOR PERIOD ~C.i/Sec O.OOE+OO 9.46E-09

3. PERCENT OF APPLICABLE LIMIT * *

4. GROSS ALPHA RADIOACTIVITY CURIES O.OOE+OO O.OOE+OO D. TRITIUM

1. TOTAL RELEASE CURIES 1.33E+01 8.13E+00 40

2. AVERAGE RELEASE RATE FOR PERIOD ~Ci/Sec 1.71E+00 1.03E+00

3. PERCENT OF APPLICABLE LIMIT * *

Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

Pagc4Sof84

TABLE 2-1C Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Summation of All Releases unit: Site Starting 1-Jul-2003 Ending : 31-Dec-2003 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACT.IVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.44E+00 1.70E-01 50

2. AVERAGE RELEASE RATE FOR PERIOD pCi/Sec 1.81E-01 2.14E-02

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES O.OOE+OO O.OOE+'OO 100

~-------------------

2. AVERAGE RELEASE RATE FOR PERIODpCi/Sec O. OOE+OO O.OOE+OO

3. PERCENT OF APPLICABLE LIMIT *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 4.49E-07 1. 26E-06 90

2. AVERAGE RELEASE RATE FOR PERIOD pCi/Sec S. 6SE-08 1.S9E-07

3. PERCENT OF APPLICABLE LIMIT * *

4. GROSS ALPHA RADIOACTIVITY CURIES O.OOE+OO O.OOE+OO D. TRITIUM

1. TOTAL RELEASE CURIES 1. 48E+01 2.07E+01 40

2. AVERAGE RELEASE RATE FOR PERIOD pCi/Sec 1.86E+00 2.61E+00

3. PERCENT OF APPLICABLE LIMIT * *

Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-SA, and 2-5B of this report.

Page 46 of 84

TABLE 2-2A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Mixed-Mode Level Releases Unit: 1 Starting: l-Jan-2003 Ending : 30~Jun-2003 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER 2 I FISSION GASES

~=~~*------------------i--~~~;;--i-~~~~;~~~-i-~~~~;~~~-i-~~~;;=~;-i-~~;~;=~;-l XE-135 I CURIES I 3.58E-Ol I O.OOE+OO I O.OOE+OO I 3.95E-OS I XE-133 I CURIES I O.OOE+OO I O.OOE+OO I 8.50E-Ol I 9.65E-03 I KR-85 I CURIES I O.OOE+OO I O.OOE+OO I O.OOE+OO I 5.39E-03 I TOTAL FOR PERIOD I CURIES I 3.58E-Ol I O.OOE+OO I 9.06E-Ol I 7.84E-02 I H-3 CURIES I 8.48E+OO I 4.12E+OO I 1.27E-02 I 1.51E-02 I

~eroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 47 of84

TABLE 2-2A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Mixed-Mode Level Releases Unit: 1 Starting: l-Jul-2003 Ending: 31-Dec-2003 CONTINUOUS MODE BATCH MODE

~------------------------------------

NUCLIDES RELEASED UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 I'QUARTER 4 I FISSION GASES AR-41 I CURIES O.OOE+OO O.OOE+OO 6.S2E-02 3.41E-02 XE-135 I CURIES O.OOE+OO O.OOE+OO 2.41E-03 2.78E-04 XE-133M I CURIES O.OOE+OO O.OOE+OO O.OOE+OO 3.12E-04 XE-133 I CURIES O.OOE+OO O.OOE+OO 3.96E-0~ 5.S7E-02 KR-85 I CURIES O.OOE+OO O.OOE+OO 1.29E-Ol O.OOE+OO TOTAL FOR PERIOD I CURIES I O.OOE+OO I O.OOE+OO I 2.36E-Ol I 9.04E-02 I PARTICULATES SR-89 I CURIES I O.OOE+OO I 2.93E-07 I O.OOE+OO I O.OOE+OO I CO-58 I CURIES I 9.45E-08 I 5.16E-07 I O.OOE+OO I O.OOE+OO I CO-60 I CURIES I 3.09E-07 I O.OOE+OO I O.OOE+OO I O.OOE+OO I SR-90 I CURIES I O.OOE+OO I 6.66E-16 I O.OOE+OO I O.OOE+OO I TOTAL FOR PERIOD I CURIES I 4.03E-07 I 8.08E-07 I O.OOE+OO I O.OOE+OO I H-3 CURIES I 5.79E+OO I 2.0SE+Ol I 1.36E-02 I 2.15E-Ol I

Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 48 of84

TABLE 2-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Mixed-Mode Level Releases Unit: 2 Starting: l-Jan-2003 Ending : 30-Jun-2003 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER 2 I FISSION GASES AR-41 CURIES O.OOE+OO O.OOE+OO 2.20E-02 3.46E-02 XE-135 CURIES 1.58E-02 O.OOE+OO 9.74E-04 6.85E-05 XE-133 CURIES 3.92E-02 O.OOE+OO 1. 83E-02 7.43E-03 KR-85 CURIES O.OOE+OO O.OOE+OO 4.36E-03 2.48E-04 TOTAL FOR PERIOD CURIES I 5.50E-02 I O.OOE+OO I 4.56E-02 I 4.24E-02 I PARTICULATES SR-89 CURIES I O.OOE+OO I 7.44E-08 I O.OOE+OO I O.OOE+OO I TOTAL FOR PERIOD CURIES I O.OOE+OO I 7.44E-08 I O.OOE+OO I O.OOE+OO I H-3 CURIES I 4.77E+OO I 3.98E+00 I 1.84E-02 I 1.29E-02 I

Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page490f84

TABLE 2-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Mixed-Mode Level Releases Unit: 2 Starting: l-Jul-2003 Ending : 31-Dec-2003 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 I FISSION GASES AR-41 I CURIES O.OOE+OO O.OOE+OO 1. 49E-Ol 2.75E-02 XE-13~ I CURIES O.OOE+OO O.OOE+OO 2.33E-03 1.86E-04 XE-133 I CURIES O.OOE+OO O.OOE+OO 1.72E-Ol 2.51E-02 KR-85 I CURIES O.OOE+OO O.OOE+OO 8.76E-Ol 1.60E-02

~----------------------

TOTAL FOR PERIOD I CURIES I O.OOE+OO I O.OOE+OO I 1.20B+00 I 6.88E-02 I PARTICULATES

~--------------------------------------------------

SR-89 I CURIES I 1.25E-09 I 4.55E-07 I O.OOE+OO I O.OOE+OO I SR-90 I CURIES I 4.49E-08 I 1.78E-10 I O.OOE+OO I O.OOB+OO I

~-------------

TOTAL FOR PERIOD I CURIES I 4.61E-08 I 4.56E-07 I O.OOE+OO I O.OOE+OO I H-3 CURIES I 7.91E+00 I O.OOE+OO I 1.10B+00 I 5.70B-03 I

Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page SO of 84

TABLE 2-2C*

vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Mixed-Mode Level Releases Unit: Site Starting: 1-Jan-2003 Ending : 30-Jun-2003 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT IQUARTER 1 t QUARTER* 2 IQUARTER 1 IQUARTER 2 I FISSION GASES AR-41 I CURIES I O.OOE+OO I O.OOE+OO I 7.77B-02 I 9.80E-02 I XE-135 I CURIES I 3.74E-01 I O.OOE+OO I 9.748-04 I 1.08E-04 I XE-133 I CURIES I 3.92E-02 I 0.008+00 I 8.698-01 I 1.718-02 I KR-85 I CURIES I O.OOE+OO I O.OOE+OO I 4.368-03 I 5.638-03 I TOTAL FOR PERIOD I CURIES I 4.13E-01 I 0.008+00 I 9.528-01 I 1.218-01 I PARTICULATES SR-89 CURIES I O.OOE+OO I 7.44E-08 I O.OOE+OO I O.OOE+OO I TOTAL FOR PERIOD CURIES I O.OOE+OO I 7.448-08 I O.OOE+OO I *O.GOE+OO I H-3 CURIES I 1.33E+01 I 8.10E+00 I 3.11E-02 I 2. 80E-02* I

Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable cxmcentrations.

Page Sl of84

'~-----'--~--

TABLE 2-2C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Mixed-Mode Level Releases Unit: Site Starting: 1-Jul-2003 Ending : 31-Dec-2003 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT IQUARTER. 3 IQUARTER 4 'QUARTER 3 IQUARTER** 4 I FISSION GASES AR-41 I CURIES O.OOE+OO O.OOE+OO 2.15E-01 6.16E-02 XE-135 I CURIES O.OOE+OO O.OOE+OO 4.73E-03 4.63E-04 XE-133M I CURIES O.OOE+OO O.OOE+OO O.OOE+OO 3.12E-04 XE-133 I CURIES O.OOE+OO O.OOE+OO 2.11E-01 8.08E-02 KR-85 I CURIES O.OOE+OO O.OOE+OO 1.00E+00 1.60E-02 TOTAL FOR PERIOD I CURIES I O.OOE+OO I O.OOE+OO , 1.44E+OO , 1.59E-01 I PARTICULATES SR-89 I CURIES I 1.25E-09 , 7.48E-07 I O.OOE+OO 10.00E+00 I CO-58 I CURIES I 9.45E-08 I 5.16E-07 , O.OOE+OO I O.OOE+OO I CO-60 I CURIES I 3.09E-07 I O.OOE+OO I O.OOE+OO , O.OOE+OO I SR-90 I CURIES I 4. 49E-08 I 1.78E-10 I O. OOE+.OO , O. OOE+OO I TOTAL FOR PERIOD I CURIES I 4.49E-07 I 1.26E-06 I O.OOE+OO I O.OOE+OO I H-3 CURIES I 1.37E+01 I 2. OSE+01 I 1.12E+OO I 2. 21E-01 I

Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Pagc52of84

TABLE 2-3A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Ground Level Releases Unit: 1 Starting: l-Jan-2003 Ending : 30-Jun-2003 CONTINUOUS MODE BATCH MODE

-----~--------------------

NUCLIDES RELEASED UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER 2 I TOTAL FOR PERIOD CURIES I O.OOE+OO I O.OOE+OO I O.OOE+OO I O.OOE+OO I

tZeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

PageS30f84

TABLE 2-3A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Ground Level Releases Unit: 1 Starting: l-Jul-2003 Ending : 3l-Dec-2003 CONTINUOUS MODE BATCH MODE IQUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 I

---~----------------------

NUCLIDES RELEASED UNIT FISSION GASES i

----~--------------------_.

XE-133 CURIES I O.OOE+OO I O.OOE+OO I 1.OSE-03 1.11E-02 I

----------~---------------

TOTAL FOR PERIOD CURIES I O.OOE+OO I O.OOE+OO I 1.OSE-03 I 1.11E-02 I H-3 CURIES I O.OOE+OO I O.OOE+OO I 9.73E-04 I 1.88E-02 I

Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-6 for typical minimum detectable concentrations.

PageS4of84

TABLE 2-3B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Ground Level Releases Unit: 2 Starting: l-Jan-2003 Ending : 30-Jun-2003 CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER 2 I TOTAL FOR PERIOD CURIES I O.OOE+OO I O.OOE+OO I O.OOE+OO I O.OOE+OO I

*Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

PageSS of84

TABLE 2-3B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Ground Level Releases unit: 2 Starting: I-Jul-2003 Ending : 31-Dec-2003 CONTINUOUS MODE BATCH MODE

~-------------------------------- -----"---------------------

NUCLIDES RELEASED UNIT IQUARTER *0 IQUARTER 0 IQUARTER 0 IQUARTER 0 I TOTAL FOR PERIOD CURIES I O.OOE+OO I O.OOE+OO I O.OOE+OO I O.OOE+OO I

.zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 56 of 84

TABLE 2-3C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Ground Level Releases Unit: Site Starting: l-Jan-2003 Ending : 30-Jun-2003 CONTINUOUS MODE BATCH MODE.

NUCLIDES RELEASED UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER 2 I CURIES I O.OOE+OO I O.OOE+OO I O.OOE+OO I O.OOE+OO I

---------------~----------

TOTAL FOR PERIOD

Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 57 of 84

TABLE 2-3C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents-Ground Level Releases Unit: Site Starting: l-Jul-2003 Ending : 31-Dec-2003 CONTINUOUS MODE BATCH MODE

-----~--------------------

NUCLIDES RELEASED UNIT IQUARTER 3 IQUARTER 4 IQUARTER' 3 IQUARTER 4' I FISSION GASES Xe-133 CURIES I O.OOE+OO I O.OOE+OO I 1.OSE-03 I 1.11E-02 I

~----------------------------------- --------------------------

TOTAL tFOR PERIOD CURIES I O.OOE+OO I O.OOE+OO I 1.OSE-03 I 1.11E-02 I H-3 CURIES I O. OOE+OO I '0. OOE+OO I 9. 73E-04 I 1. SSE-02 I

Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-7 for typical minimum detectable concentrations.

PageS8of84 L

TABLE 2-4A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 AIR DOSES DUE TO GASEOUS RELEASES Unit: 1 Starting: 01-Jan-2003 Ending: 30-Jun-2003 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 1 ODCM 2 ODCM Radi- Limit Limit ation

------------------~-

Gamma 5.0 mrad 2.21E-05 4.41E-04 8.68E-06 1.742-04 Beta 10.0 mrad 2.87E-05 2.87E-04 3.35E-06 3.352-05 Cumulative Doses per Year Type ODCM Units Year to % of of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 3.08E-05 3.08E-04 Beta 20.0 mrad 3.20E-05 1.60E-()4 Page 59 of 84

TABLE 2-4A Vogtle Electric Generating plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 AIR DOSES DUE TO GASEOUS RELEASES Unit: 1 Starting: 01-Jul-2003 Ending: 31-Dec-2003 cumulative Doses per Quarter

, of ODCM Units Quarter , of Quarter Type Limit 3 ODCM 4 ODCM of Limit Radi- Limit ation

~----------------------------------- ---.----------------

5.0 mrad 9.22E-06 1. 84E-04 5.26E-06 1.05E-04 Gamma 3.46E-OS 10.0 mrad 7.60E-06 7.60E-05 3.46E-06 Beta

Cumulative Doses per Year

, of Type ODCM units Year to of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 4.09E-05 4.09E-04 Beta 20.0 mrad 3.01E-OS 1. 51E-04 Page 60 of 84

TABLE 2-4B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT "'7.2003 AIR DOSES DUE TO GASEOUS RELEASES Unit: 2 Starting: 01-Jan-2003 Ending: 30-Jun-2003 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter , of of Limit 1 ODCM 2 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 3.76E-06 7.S2E-OS 4.76E-06 9.S2E-05 Beta 10.0 mrad 2.67E-06 2.67E-OS 1. 79E-06 1.79E-OS Cumulative Doses per Year Type ODCM Units Year to , of of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 8.S2E-06 8.S2E-OS Beta 20.0 mrad 4.46E-06 2.23E-OS Page 61 of84

TABLE 2-4B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 AIR DOSES DUE TO GASEOUS RELEASES Unit: 2 Starting: 01-Jul-2003 Ending: 31-Dec-2003 Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 3 ODCM 4 ODCM Radi- Limit Limit ation Gamma S.O mrad 2.1SE-OS 4.31E-04 3.88E-06 7.77E-OS Beta 10.0 mrad 3.49E-OS 3.49E-04 2.17E-06 2.17E-OS Cumulative Doses per Year Type ODCM Units Year to % of of Limit Ending ODCM Radi- Date Limit ation

-------~.------------

Gamma 10.0 mrad 3.39E-OS 3.39E-04 Beta 20.0 mrad 4.1SE-OS 2.08E-04 Pagc62 of 84

TABLE 2-SA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jan-2003 Ending: 30-Jun-2003 Cumulative Doses per Quarter Organ ODeM Unit Quarter % of Quarter % of Limit 1 ODCM 2 ODCM Limit Limit

~--- --------------------

Bone 7.5 mrem O.OOE+OO O.OOE+OO O.OOE+OO O.OOiHOO Liver 7.5 mrem 5.46E-OS 7.28E-04 2.66E-OS 3.54E-04 TBody 7.5 mrem 5.46E-05 7.28E-04 2.66E-05 3.54E-04 Thyroid 7.5 mrem 5.46E-05 7.28E~04 2.66E-05 3.54E-04 Kidney 7.5 mrem 5.46E-05 7.28E-04 2.66E-05 3.54E-04 Lung 7.5 mrem 5.46E-05 7.28E-04 2.66E-05 3.54E-04 GILLI 7.5 mrem 5.46E-05 7.28E-04 2.66E-05 3.54E-04

~------------------------------------------------- --------------------

Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 15.0 mrem O.OOE+OO O.OOE+OO Liver 15.0 mrem 8.12E-05 5. 41E-04 TBody 15.0 mrem 8.12E-05 5.41E-04 Thyroid 15.0 mrem 8.12E-05 5.41E-04 Kidney 15.0 mrem 8.12E-05 5.41E-04 Lung 15.0 mrem 8.12E-05 5.41E-04 GILLI 15.0 mrem 8.12E-05 5.41E-04 Page 63 of84 iL- _

TABLE 2-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jul-2003 Ending: 31-Dec-2003 Cumulative Doses per"Quarter

~----- --------------------

Organ ODCM Unit Quarter , of Quarter , of Limit 3 ODCM 4 ODeM Limit Limit Bone 7.5 mrem 4.21E-08 5.62E-07 7.05E-08 9.39E-07 Liver 7.5 mrem 3.74E-05 4.99E-04 1.33E-04 1. 78E-03 TBod't 7.5 mrem 3.74E-05 4.99E-04 1. 33E-04 1. 78E-03 Thyroid 7.5 mrem 3.74E-05 4.99E-04 1.33E-04 1. 78E-03 Kidney 7.5 mrem 3.74E-05 4.99E-04 1.33E-04 1. 78E-03 Lung 7.5 mrem 3.74E-05 4.99E-04 1.33E-04 1. 78E-03 GILLI 7.5 mrem 3.74E-05 4.99E-04 1. 33E-04 1.78E-03 Cumulative Doses per Year Organ ODCM Units Year to , of Limit Ending ODCM Date Limit Bone 15.0 mrem 1. 13E-07 7.51E-07 Liver 15.0 mrem 2.52E-04 1.68E-03 TBody 15.0 mrem 2.52E-04 1.68E-03 Thyroid 15.0 mrem 2.52E-03 1. 68E-02 Kidney 15.0 mrem 2.52E-04 1. 68E-03 Lung 15.0 mrem 2.52E-04 1.68E-03 GILLI 15.0 mrem 2.52E-04 1. 68E-03 Page 64 of84

TABLE 2-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jan-2003 Ending: 30-Jun-2003 Cumulative Doses per Quarter Organ ODCM Unit Quarter % of Quarter of Limit 1 ODCM 2 ODCM Limit Limit Bone 7.5 mrem O.OOE+OO O.OOE+OO 1. 76E-08 2.3sE-07 Liver 7.5 mrem 3.08E-Os 4. llE-04 2.s7E-Os 3.43E-04 TBody 7.5 mrem 3.08E-Os 4.11E-04 2.57E-Os 3.43E-04 Thyroid 7.5 mrem 3.08E-05 4.11E-04 2.s7E-Os 3.43E-04 Kidney 7.5 mrem 3.08E-05 4.11E-04 2.s7E-Os 3.43E-04 Lung 7.5 mrem 3.08E-05 4. llE-04 .2.57E-Os 3.43E-04 GILLI 7.5 mrem 3.08E-05 4.11E-04 2.57E-Os 3.43E-04

~------ --------------------

Cumulative Doses per Year

------------~-------

Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 15.0 mrem 1. 76E-08 1.17E-07 Liver 15.0 mrem 5.65E-05 3.77E-04 TBody 15.0 mrem s.65E-05 3.77E-04 Thyroid 15.0 mrem s.65E-Os 3.77E-04 Kidney 15.0 mrem 5.65E-05 3.77E-04 Lung 15.0 mrem s.65E-Os 3*. 77E-04 GILLI 15.0 mrem 5.65E-05 3.77E-04 Page6S of84

TABLE 2-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jul-2003 Ending: 31-Dec-2003 Cumulative Doses per Quarter Organ ODCM unit Quarter % of Quarter % of Limit 3 ODCM 4 ODCM Limit Limit Bone 7.5 mrem 3.60E-07 4.79E-06 1.09E-07 1.46E-06 Liver 7.5 mrem 5.79E-05 7.72E-04 3.66E-08 4.88E-07*

TBody 7.5 mrem 5.80E-05 7.74E-04 4.00E-08 5.33E-07 Thyroid 7.5 mrem 5.79E-05 7. 72E-04 3.66E-08 4.88E-07 Kidn..., 7.5 mrem 5.79E-05 7.72E-04 3.66E-08 4.88E-07 Lung 7.5 mrem 5.79E-05 7.72E-04 3.78E-08 5.04E-07 GILLI 7.5 mrem 5.79E-05 7.72E-04 4.08E-08 5.44E-07

~-------------- --------------------

cumulative Doses per Year

~------------------------------~------ --------------------

Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 15.0 mrem 4.86E-07 3.24E-06 Liver 15.0 mrem 1.14E-04 7.63E-04 TBody 15.0 mrem 1. 15E-04 7.64E-04 Thyroid 15.0 mrem 1. 14E-04 7.63E-04 Kidney 15.0 mrem 1.14E-04 7.63E-04 Lung 15.0 mrem 1.14E-04 7.63E-04 GILLI 15.0 mrem 1.14E-04 7.63E-04 Pagc66of84

TABLE 2-6 VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES JANUARY, 2003 THROUGH DECEMBER, 2003 The values in this table represent a priori Minimum Detectable Concentrations (MOe) that are typically achieved in laboratory analyses of gaseous radwaste samples*.

Based on an estimated sample volume of 5.7E+08 ml.

P.67 of 84

TABLE 2-7A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Batch Release Summary Unit: 1 .

Starting: 1-Jan-2003 Ending : 30-Jun-2003 GASEOUS RELEASES NUMBER OF BATCH RELEASES 57 TOTAL TIME PERIOD FOR BATCH RELEASES 3642.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 152.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 63.89 MINUTES MINIMUM TIME FOR A BATCH RELEASE 14.00 MINUTES

_____ J -------------------------_

TABLE 2-7A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Batch Release Summary Unit: 1 Starting: 1-Jul-2003 Ending : 31-Dec-2003 GASEOUS RELEASES NUMBER OF BATCH RELEASES 69 TOTAL TIME PERIOD FOR BATCH RELEASES 37299.90 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 8523.98 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 540.58 MINUTES MINIMUM TIME FOR A BATCH RELEASE 10.00 MINUTES Page 68 of 84

TABLE 2-7B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: 1-Jan-2003 Ending : 30-Jun-2003 GASEOUS RELEASES NUMBER OF BATCH RELEASES 35 TOTAL TIME PERIOD FOR BATCH RELEASES 3447.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 1585.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 98.49 MINUTES MINIMUM TIME FOR A BATCH RELEASE 17.00 MINUTES

~------------~---------------

TABLE 2-7B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Batch Release Summary Unit: 2 Starting: l-Jul-2003 Ending : 31-Dec-2003 GASEOUS RELEASES NUMBER OF BATCH RELEASES 36 TOTAL TIME PERIOD FOR BATCH RELEASES 22954.83 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 7286.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 637.63 MINUTES MINIMUM TIME FOR A BATCH RELEASE 23.00 MINUTES Page 69 of 84 L

TABLE 2-8A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Abnormal Release -Summary unit: 1 Starting: 1-Jan-2003 Ending : 30-Jun-2003 NUMBER OF RELEASES 1 TOTAL TIME FOR ALL RELEASES 3620.00 MINUTES MAXIMUM TIME FOR A RELEASE 3620.00 MINUTES AVERAGE TIME FOR A RELEASE 3620.00 MINUTES MINIMUM TIME FOR A RELEASE 3620.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 8.41E-01 CURIES TABLE 2-8A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting: 1-Jul-2003 Ending : 31-Dec-2003 NUMBER OF RELEASES 1-TOTAL TIME FOR ALL RELEASES 10.12 MINUTES MAXIMUM TIME FOR A RELEASE 10.12 MINUTES AVERAGE TIME FOR A RELEASE 10.12 MINUTES MINIMUM TIME FOR A RELEASE 10.12 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 1.20E-02 CURIES Page 70 of84 L

_.. ,.~._"-----

TABLE 2-8B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Abnormal Release Summary Unit: 2 '

Starting: l-Jan-2003 Ending : 30-Jun-2003 NUMBER OF RELEASES o TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES O.OOE+OO CURIE TABLE 2-8B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting: l-Jul-2003 Ending : 31-Dec-2003 NUMBER OF RELEASES o TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES O.OOE+OO CURIES Page 71 or84

3.0 Solid Waste 3.1 Regulatory Requirements The aDCM requirements presented in this section are stated in part for Unit 1 and Unit 2.

J 3.1.1 Solid Radioactive Waste System 10.2.1 Process Control Program (PCP)

Radioactive wastes shall be solidified or dewatered in accordance with the PCP to meet shipping and transportation requirements dUring transit and disposal site requirements when received at the disposal site.

3.1.2

Reporting ReqUirements 12.1 PCP states in part:

The Radioactive Effluent Release Report, submitted in accordance with Technical Specification 5.6.3, shall include a summary of the quantities of solid radwaste released from the units, as outlined in RegUlatory Guide 1.21.

3.2 Solid Waste Data Regulatory Guide 1.21. Table 3 is found in this report as Table 3-1.

Page 72 of 84 L

TABLE 3-1 vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS units 1 and 2 Page 1 of 4 JANUARY 1, 2003 THROUGH JUNE 30, 2003

..t.

A. SOL:ID WAS'l'B n:IPPBD OITS:ITB FOR BUlUAL OR D:ISPOSAL (Rot :Irradiate<<! hel) unit 6-JDODth '1'otal

1. Type of .a.te PeZ'i04 Bn"oZ', "

m3 None

a. Spent resins, filter sludges, None N/A evaporator, bottoms, etc. Ci Dry compressible waste, contaminated m3 10.65

b. Ci 26.30 40 equip, etc.

Irradiated components, control m3

c. Ci NONE N/A rods, etc.

Other (describe) m3

d. Ci NONE N/A (by type of .a.te)

2. **tiJDate of . .joZ' nuclide compo8ition N/A % N/A

a. % N/A N/A N/A N/A %

N/A % N/A Ni-63 % 50.54

b. 21.82 Cs-137 %

Cs-134 % 11.17 All others % 16.47 N/A % N/A

c. N/A N/A %

N/A % N/A N/A % N/A N/A % N/A

d. N/A N/A %

Page?30fM

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 2 of 4 JANUARY 1, 2003 THROUGH JUNE 30, 2003 Bamber of Hb4e of Shipmentp 'l'ranpportatiop Deptipatiop 7 Tractor/Trailer Duratek, Oak Ridge, TN 1 Cask/Tractor/Trailer Studsvik, Erwin, TN

"'-ber of Hb4e of ShipmeutP 'l'rMlpOrtatiop peptinatiop None None None ADDX'l'XODL XIIFORD.'l'XOII RBQOXRBD B'I' ODelIa Shipments to a Waste Processor Shipment No, waste Class ~ Shipping Solidification Container Class Agent RVRS-03-001 B UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-03-002 °A UNSTABLE STRONG TIGHT LSA (2 ) NONE RVRS-03-003 A UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-03-004 A UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-03-00S A UNSTABLE STRONG TIGHT La NONE RVRS-03-006 A UNSTABLE STRONG TIGHT La NONE RVRS-03-007 A UNSTABLE STRONG TIGHT LQ NONE RVRS-03-008 A UNSTABLE STRONG TIGHT LSA (2) NONE Page 74 of 84 L_

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS units 1 and 2 Page 3 of 4 JULy 1, 2003 THROUGH DECEMBER 31, 2003.

A. SOLZD ~TB SBZPPBD OFFSZTB FOR BtJJU:AL OR DZSPOSAL (Bot Zrra4iatea Fuel)

Unit 6-1DODth. .at. '1'otal Type of waate

1. period Brror, Spent resins, filter sludges, m3 NONE

a. Ci NONE evaporator bottoms, etc.

Dry compressible waste, contaminated m3 10.30

b. Ci 12.80 40 equip, etc.

Irradiated components, control m3 NONE

c. Ci NONE N/A rods, etc.

d. Other (describe) m3 Ci NONE N/A

2. .stimate of major nuclide cOlllPOaitiOD (by type of waate)

,, N/A

a. N/A N/A N/A

,, N/A N/A N/A N/A

,, 47.4

b. Ni-63 Fe-55 Co-60

,, 20.1 10.4 22.1 All others N/A N/A

c. N/A N/A N/A N/A N/A N/A N/A N/A

d. N/A N/A N/A N/A Page 75 of84

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 4 of 4 JULy 1, 2003 THROUGH DECEMBER 31, 2003

3. S01i4 Waste DispositiOD HUmber of IIoc1e of Shipments '1'Z'aDsportatiOD 15 Tractor/Trailer Duratek, oak Ridge, TN 3 Cask/Tractor/Trailer Studsvik, Erwin, TN B. :tRfAI':tA'1'BD l"'DBL SB:tPlla'1'S (DispositiOD)

Humber of IIoc1e of Shipments TraDEPPrtatiop Pestipatiop None None None Shipments Sent Directly to Disposal at Barnwell, SC Shipment Waste Class ~ Shipping Solidification Volume fDirect

~ Contain§r Class Agent disposal only)

NONE Shipments to a waste processor:

Shipment Wast§ Class ~ Shipping Solidification li2..L Contain§r Class Agent RVRS-03-009 B UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-03-010 B UNSTABLE STRONG TIGHT LSA (2 ) NONE RVRS-03-011 A UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-03-012 A UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-03-013 A UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-03-014 A UNSTABLE STRONG TIGHT LQ NONE RVRS-03-015 A UNSTABLE STRONG TIGHT LQ NONE RVRS-03-016 A UNSTABLE STRONG TIGHT LQ NONE RVRS-03-017 A UNSTABLE STRONG TIGHT LQ NONE RVRS-03-018 A UNSTABLE STRONG TIGHT LSA (2 ) NONE RVRS-03-019 A UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-03-020 A UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-03-021 A UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-03-022 A UNSTABLE STRONG TIGHT LQ NONE RVRS-03-023 A UNSTABLE STRONG TIGHT LQ NONE RVRS-03-024 A UNSTABLE STRONG TIGHT LQ NONE RVRS-03-025 A UNSTABLE STRONG TIGHT LQ NONE RVRS-03-026 B UNSTABLE STRONG TIGHT LSA (2) NONE Page 76 ofM

" "'~' - '--------

4.0 Doses to Members of the Public Inside the Site Boundary 4.1 Regulatory Requirements ODCM 7.2.2.3 states in part:

"The report shall also include assessment of the radiation doses from radioactive liquid and gaseous efflLients to MEMBERS OF THE,PUBLIC due to their activities inside the SITE BOUNDARY during the report period; this assessment must be performed in accordance with Chapter 6. All assumptions used in making these assessments (i.e., specific activity, exposure time, and location) shall be included in the report-.

4.2 Demonstration of Compliance The location of concern within the site boundary is the Visitors Center. The activities at the Visitor Center consist of occasional attendance at meetings and/or short visits for informational purposes.

There will be no radiation dose at this location due to radioactive liquid effluents.

Delineated in Table 4-1 for this location are the values of the basic data assumed in the dose assessment due to radioactive gaseous effluents. Usted in this table are distance and direction from a point midway between the center of Unit 1 and the Unit 2 reactors, the dispersion and deposition factors for any releases from the plant vent (mixed mode) and from the turbine building (ground level), and the estimated maximum occupancy factor for an individual and the assumed age group of this individual.

The source term is listed in Tables 2-2A, and 2-2B for the mixed mode releases.

Similarly, It is listed in tables 2-3A and 2-3B for the ground level releases.

Page 77 of 84

4.2 Demonstration of Compliance cont'd The maximum doses in units of mrem to a MEMBER OF THE PUBLIC due to their activities inside the site boundary during the reporting period were assessed to be as follows:

. VISITOR CENTER Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Body: .. 1.73E-Q7 1.10E-07 1.76E-Q7 2.20E-07 (Direct Radiation from Plume)

VISITOR CENTER Quarter 1 Quarter 2 Quarter 3 Quarter 4 Maximum Organ 1.73E-07 1.10E-Q7 1.76E-Q7 2.20E-Q7 (Thyroid) Quarters*1 ,2,3,4 (Inhalation Ground Plane)

Page 78 of84

TABLE 4-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-2003 Ending: 30-Jun-2003 Page: 1 Location Name VISITOR CENTER Distance (kilometers) 4.47E-01 Sector SE Occupancy Factor 4.57E-04 (4.00E+OO hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 5.93E-06 Particulate X/Q (sec/m3) 5.58E-06 Particulate D/Q (m-2) 2.28E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 7.12E-07 Particulate X/Q (sec/m3) 6.74E-07 Particulate D/Q (m-2) 5.77E-09 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A particulate D/Q (m-2) N/A Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 1.69E-08 8.99E-09 2.58E-08 2.58E-08 Liver mrem 1.73E-07 1.10E-07 2.83E-07 2.83E-07 TBody mrem 1. 73E-07 1.10E-07 2.83E-07 2.83E-07 Thyroid mrem 1.73E-07 1.10E-07 2.83E-07 2.83E-07 Kidney mrem 1.73E-07 1.10E-07 2.83E-07 2.83E-07 Lung mrem 1.73E-07 1.10E-07 2.83E-07 2.83E-07 GI-LLI mrem 1.73E-07 1.10E-07 2.83E-07 2.83E-07 Page 79 of84

TABLE 4-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2003 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-2003 Ending: 31-Dec-2003 Page: 2 Location Name VISITOR CENTER Distance (kilometers) 4.47E-01 Sector SE Occupancy Factor 4.57E-04 (4.00E+OO hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 5.93E-06 Particulate X/Q (sec/m3) 5.58E-06 particulate D/Q (m-2) 2.28E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 7.12E-07 Particulate X/Q (sec/m3) 6.74E-07 Particulate D/Q (m-2) 5.77E-09 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A

----------~------------

units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending Date Bone mrem 2.11E-08 6.17E-09 2.73E-08 5.04E-08 Liver mrem 1.76E-07 2.20E-07 3.97E-07 6.77E-07 TBody mrem 1.76E-07 2.20E-07 3.97E-07 6.77E-07 Thyroid mrem 1.76E-07 2.20E-07 3.97E-07 6.77E-07 Kidney mrem 1.76E-07 2.20E-07 3.97E-07 6.77E-07 Lung mrem 1. 76E-07 2.20E-07 3.97E-07 6.77E-07 GI-LLI mrem 1.76E-07 2.20E-07 3.97E-07 6.77E-07 Page 80 of84

5.0 Total Dose from Uranium Fuel Cycle (40CFR190) 5.1 Regulatory Requirements aDeM 5.1 states in part that 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 to any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

5.2 Demonstration of Compliance The requirements of 4OCFR190 were met.

6.0 Meteorological Data aDCM 7.2.2.2 states in part:

The Radioactive Effluent Release Report shall include 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 of wind speed, wind direction, atmospheric stability. and precipitation (if measured) on magnetic tape; or in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.

In lieu of submission with the 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.

7.0 Program Deviations 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 7.1.1 . Regulatory Requirement ODCM 7.2.2.6 states in part that the report shall include deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, respectively. The report shall include an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the specified time requirement.

7.1.2 Description of Deviations The inoperability of liquid and gaseous effluent monitors was corrected within the specified time for this reporting period.

Page 81 of84

7.2 Tanks Exceeding Curie Content Limits 7.2.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the report shall include a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specifications 5.5.12.

8.0

8.1 Regulatory Requirements ODCM 7.2.2.5 states in part that changes to the aDCM shall be submitted with the Radioactive Effluent Release Report. These changes may be due to changes in the radiological environmental monitoring program sampling locations as required by aDCM 4.1.1.2.3 or changes to dose calculation locations as required by aDCM 4.1.2.2.2. Land uses and dose calculation locations within five miles of VEGP must be determined by a land use census as reqUired by aDCM 4.1.2.

8.2 Description of Changes There were* changes made to the Vogtle Electric Generating Plant aDCM for the period January 1, 2003 through December 31, 2003. Revision 20 and 21 became effective in 2003. Changes were that Table 2*1 step 3A, Table 2-2 Step 1, and Table 3-2 Step 3A&B was Updated.

The Land Use Census was conducted November 11, 2003 by Georgia Power Company Environmental Lab personnel. The results of the census for 2003 require no changes to the REMP sampling locations or to the dose calculation locations.

Page 82 of 84

9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 9.1 Regulatory Requirements aDCM 7.2.2.7 states in part:

As required by Sections 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report covering the period in which the change was reviewed and accepted for implementation.

Note 1: In lieu of inclusion in the Radioactive Effluents Release Report,

this same information may be submitted as part of the annual FSAR update.

PCP 12.1 states in part:

Licensee major initiated changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the change was implemented.

PageS30f84

9.2 Description of Major Changes Gaseous Radwaste System There were no major changes to the gaseous radwaste systems in the 2003 assessment period.

Liquid Radwaste System Major changes to the liquid radwaste facilities are those that contribute to significant changes in release; i.e., either decreases or Increases In release volume or activity/dose. This is to indicate that no major changes to the liquid radwaste systems occurred during the 2003 assessment period.

Solid Radwaste System There were no major changes to the solid radwaste*systems in the 2003 assessment period. .

Page 84 of84

OFFSITE DOSE CALCULATION MANUAL FOR SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT Revision 21 October 1, 2003

VEGPODCM DISTRIBUTION LIST Copy Number Manual Holder 1 W. F. Kitchens 3 Training Center Simulator 6 VEGP Main Control Room Podium 7 Rebecca H. Parker 8 Manager, Engineering Support 12 Manager, Health Physics & Chemistry 14 Manager, Training & Emergency Preparedness 16 John Aufdenkampe 17 Operations Department 18 VEGP Document Control 19 QA Supervisor 20 Chemistry Superintendent 21 Joe B. Sills 22 Dwight A. Hostetter 23 Michael C. Nichols 24 Shan Sundaram 25 C&T 28 Terry G. Lamb 29 Steve White s:\vogtle\odcm\dl.doc Rev. 21

VEGPODCM REVISION LOG Revision Number o 8/85 1 8/86 2 11/86 3 3/87 4 7/87 5 10/87 6 9/88 7 3/91 8 2/93 9 1/94 10 2/96 11 12/96 12 2/97 13 6/97 14 12/97 15 1/99 16 7/99 17 10/00 18 8/01 19 11/01 20 4/03 21 10/03 s:\vogtle\odcm\revision log.doc ii Rev. 21

VEGPODCM TABLE OF CONTENTS PAGE DISTRIBUTION LIST i REVISION LOG ii TABLE OF CONTENTS iii LIST OF TABLES.......... viii LIST OF FIGURES x REFERENCES xi CHAPTER 1: INTRODUCTION 1-1 CHAPTER 2: LIQUID EFFLUENTS 2-1 2.1 LIMITS OF OPERATION 2-1 2.1.1 Liguid Effluent Monitoring Instrumentation Control 2-1 2.1.2 Liguid Effluent Concentration Control 2-7 2.1.3 Liguid Effluent Dose Control 2-10 2.1.4 Liguid Radwaste Treatment System Control 2-11 2.1.5 Major Changes to Liguid Radioactive Waste Treatment Systems 2-12 2.2 LIQUID RADWASTE TREATMENT SYSTEM 2-13 2.3 LIQUID EFFLUENT MONITOR SETPOINTS 2-17 2.3.1 General Provisions Regarding Setooints 2-17 2.3.2 Setpoints for Radwaste System Discharge Monitors 2-19 2.3.3 Setpoints for Monitors on Normally Low-Radioactivity Streams 2-25 2.4 LIQUID EFFLUENT DOSE CALCULATIONS 2-26 2.4.1 Calculation of Dose 2-26 2.4.2 Calculation of At 2-27 2.4.3 Calculation of CF jy 2-28 2.5 LIQUID EFFLUENT DOSE PROJECTIONS 2-37 2.5.1 Thirty-One Day Dose Projections 2-37 2.5.2 Dose Projections for Specific Releases 2-37 2.6 DEFINITIONS OF LIQUID EFFLUENT TERMS 2-38 CHAPTER 3: GASEOUS EFFLUENTS 3-1 3.1 LIMITS OF OPERATION 3-1 3.1.1 Gaseous Effluent Monitoring Instrumentation Control 3-1 3.1.2 Gaseous Effluent Dose Rate Control 3-7 iii Rev. 18

VEGPODCM TABLE OF CONTENTS (continued) 3.1.3 Gaseous Effluent Air Dose Control 3-10 3.1.4 Control on Gaseous Effluent Dose to a Member of the Public 3-11 3.1.5 Gaseous Radwaste Treatment System Control 3-12 3.1.6 Major Changes to Gaseous Radioactive Waste Treatment Systems 3-13 3.2 GASEOUS WASTE PROCESSING SYSTEM 3-14 3.3 GASEOUS EFFLUENT MONITOR SETPOINTS 3-20 3.3.1 General Provisions Regarding Noble Gas Monitor Setooints 3-20 3.3.2 Setpoint for the Final Noble Gas Monitor on Each Release Pathway 3-22 3.3.3 Setpoints for Noble Gas Monitors on Effluent Source Streams 3-25 3.3.4 Determination of Allocation Factors. AG 3-27 3.3.5 Setpoints for Noble Gas Monitors with Special Requirements 3-29 3.3.6 Setooints for Particulate and Iodine Monitors 3-29 3.4 GASEOUS EFFLUENT COMPLIANCE CALCULATIONS 3-30 3.4.1 Dose Rates at and Beyond the Site Boundarv 3-30 3.4.2 Noble Gas Air Dose at or Beyond Site Boundarv 3-31 3.4.3 Dose to a Member of the Public at or Beyond Site Boundary 3-35 3.4.4 Dose Calculations to Supoort Other Requirements 3-38 3.5 GASEOUS EFFLUENT DOSE PROJECTIONS 3-44 3.5.1 Thirty-One Day Dose Projections 3-44 3.5.2 Dose Projections for Specific Releases 3-45 3.6 DEFINITIONS OF GASEOUS EFFLUENT TERMS 3-46 CHAPTER 4: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4-1 4.1 LIMITS OF OPERATION 4-1 4.1.1 Radiological Environmental Monitorinq 4-1 4.1.2 Land Use Census 4-9 4.1.3 Interlaboratory Comparison Program 4-10 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS 4-11 CHAPTER 5: TOTAL DOSE DETERMINATIONS 5-1 5.1 LIMIT OF OPERATION 5-1 5.1.1 Applicability 5-1 5.1.2 Actions 5-1 5.1.3 Surveillance Requirements 5-1 5.1.4 Basis 5-1 5.2 DEMONSTRATION OF COMPLIANCE 5-3 iv Rev. 18

VEGPODCM TABLE OF CONTENTS (continued)

CHAPTER 6: POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARy 6-1 6.1 REQUIREMENT FOR CALCULATION 6-1 6.2 CALCULATIONAL METHOD 6-1 CHAPTER 7: REPORTS 7-1 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT 7-1 7.1.1 Requirement for Report 7-1 7.1.2 Report Contents 7-1 7.2 RADIOACTIVE EFFLUENT RELEASE REPORT 7-3 7.2.1 Requirement for Report 7-3 7.2.2 Report Contents 7-3 7.3 MONTHLY OPERATING REPORT 7-6 7.4 SPECIAL REPORTS 7-6 CHAPTER 8: METEOROLOGICAL MODELS 8-1 8.1 ATMOSPHERIC DISPERSION 8-1 8.1.1 Ground-Level Releases 8-1 8.1.2 Elevated Releases 8-2 8.1.3 Mixed-Mode Releases 8-4 8.2 RELATIVE DEPOSITION 8-5 8.2.1 Ground-Level Releases 8-5 8.2.2 Elevated Releases 8-5 8.2.3 Mixed-Mode Releases 8-6 8.3 ELEVATED PLUME DOSE FACTORS 8-6 CHAPTER 9: METHODS AND PARAMETERS FOR CALCULATION OF GASEOUS EFFLUENT PATHWAY DOSE FACTORS, Raipj 9-1 9.1 INHALATION PATHWAY FACTOR 9-1 9.2 GROUND PLANE PATHWAY FACTOR 9-2 9.3 GARDEN VEGETATION PATHWAY FACTOR 9-3 9.4 GRASS-COW-MILK PATHWAY FACTOR 9-6 9.5 GRASS-GOAT-MILK PATHWAY FACTOR 9-9 9.6 GRASS-COW-MEAT PATHWAY FACTOR 9-12 CHAPTER 10: DEFINITIONS OF EFFLUENT CONTROL TERMS 10-1 10.1 TERMS SPECIFIC TO THE ODCM 10-1 10.2 TERMS DEFINED IN THE TECHNICAL SPECIFICATIONS 10-5 v Rev. 18

VEGPODCM LIST OF TABLES PAGE Table 2-1. Radioactive Liquid Effluent Monitoring Instrumentation 2-3 Table 2-2. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 2-5 Table 2-3. Radioactive Liquid Waste Sampling and Analysis Program 2-8 Table 2-4. Applicability of Liquid Monitor Setpoint Methodologies 2-18 Table 2-5. Parameters for Calculation of Doses Due to Liquid Effluent Releases 2-30 Table 2-6. Element Transfer Factors 2-31 Table 2-7. Adult Ingestion Dose Factors 2-32 Table 2-8. Site-Related Ingestion Dose Factors, Atr 2-35 Table 3-1. Radioactive Gaseous Effluent Monitoring Instrumentation 3-3 Table 3-2. Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3-5 Table 3-3. Radioactive Gaseous Waste Sampling and Analysis Program 3-8 Table 3-4. Applicability of Gaseous Monitor Setpoint Methodologies 3-21 Table 3-5. Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 3-33 Table 3-6. Dose Factors for Exposure to Direct Radiation from Noble Gases in an Elevated Finite Plume 3-34 Table 3-7. Attributes of the Controlling Receptor 3-37 Table 3-8. Raipj for Ground Plane Pathway, All Age Groups 3-39 Table 3-9. Raipj for Inhalation Pathway, Child Age Group 3-40 Table 3-10. Raipj for Inhalation Pathway, Adult Age Group 3-41 Table 3-11. Raipj for Cow Meat Pathway, Child Age Group 3-42 Table 3-12. Raipj for Garden Vegetation, Child Age Group 3-43 Table 4-1. Radiological Environmental Monitoring Program 4-3 vi Rev. 18

VEGPODCM LIST OF TABLES (Continued)

Table 4-2. Reporting Levels for Radioactivity Concentrations in Environmental Samples 4-7 Table 4-3. Values for the Minimum Detectable Concentration (MOC) 4-8 Table 4-4. Radiological Environmental Monitoring Locations 4-12 Table 6-1. Attributes of Member of the Public Receptor Locations Inside the Site Boundary 6-2 Table 8-1. Terrain Elevation Above Plant Site Grade 8-7 Table 9-1. Miscellaneous Parameters for the Garden Vegetation Pathway 9-5 Table 9-2. Miscellaneous Parameters for the Grass-Cow-Milk Pathway 9-8 Table 9-3. Miscellaneous Parameters for the Grass-Goat-Milk Pathway 9-11 Table 9-4. Miscellaneous Parameters for the Grass-Cow-Meat Pathway 9-14 Table 9-5. Individual Usage Factors 9-15 Table 9-6. Stable Element Transfer Data 9-16 Table 9-7. Inhalation Dose Factors for the Infant Age Group 9-17 Table 9-8. Inhalation Dose Factors for the Child Age Group 9-20 Table 9-9. Inhalation Dose Factors for the Teenager Age Group 9-23 Table 9-10. Inhalation Dose Factors for the Adult Age Group 9-26 Table 9-11. Ingestion Dose Factors for the Infant Age Group 9-29 Table 9-12. Ingestion Dose Factors for the Child Age Group 9-32 Table 9-13. Ingestion Dose Factors for the Teenager Age Group 9-35 Table 9-14. Ingestion Dose Factors for the Adult Age Group 9-38 Table 9-15. External Dose Factors for Standing on Contaminated Ground 9-41 vii Rev. 18

- ~~---~-----

VEGPODCM LIST OF FIGURES PAGE Figure 2-1. Unit 1 Liquid Radwaste Treatment System 2-14 Figure 2-2. Unit 2 Liquid Radwaste Treatment System 2-15 Figure 2-3. Liquid Radwaste Discharge Pathways 2-16 Figure 3-1. Schematic Diagram of the Gaseous Radwaste Treatment System 3-15 Figure 3-2. Schematic Diagram of the Unit 1 Plant Vent Release Pathway 3-16 Figure 3-3. Schematic Diagram of the Unit 2 Plant Vent Release Pathway 3-17 Figure 3-4. Schematic Diagram of the Turbine Building Vent Release Pathway (Typical of Both Units) 3-18 Figure 3-5. Schematic Diagram of the Dry Active Waste Processing Building Ventilation Release Pathway 3-19 Figure 3-6. Schematic Diagram of the Radwaste Processing Facility Ventilation Release Pathway 3-19a Figure 4-1. Terrestrial Stations Near Site Boundary 4-15 Figure 4-2. Terrestrial Stations and Aquatic Stations, D-5 Miles 4-16 Figure 4-3. Terrestrial Stations Beyond 5 Miles 4-17 Figure 4-4. Drinking Water Stations 4-18 Figure 8-1. Vertical Standard Deviation of Material in a Plume <<Jz) 8-8 Figure 8-2. Terrain Recirculation Factor (Kr) 8-9 Figure 8-3. Plume Depletion Effect for Ground Level Releases 8-10 Figure 8-4. Plume Depletion Effect for 3D-Meter Releases 8-11 Figure 8-5. Plume Depletion Effect for 6D-Meter Releases 8-12 Figure 8-6. Plume Depletion Effect for 100-Meter Releases 8-13 Figure 8-7. Relative Deposition for Ground-Level Releases 8-14 Figure 8-8. Relative Deposition for 30-Meter Releases 8-15 Figure 8-9. Relative Deposition for 60-Meter Releases 8-16 Figure 8-10. Relative Deposition for 100-Meter (or Greater) Releases 8-17 viii Rev. 19

VEGPODCM REFERENCES

1. J.S. Boegli, RR Bellamy, W.L. Britz, and R.L. Waterfield, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133, October 1978.

2. "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," U.S. NRC Regulatorv Guide 1.109, March 1976.

3. "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," U.S. NRC Regulatory Guide 1.109. Revision 1, October 1977.

4. "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. NRC Regulatory Guide 1.111, March 1976.

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

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

7. W.R Stokes III, T.W. Hale, J.L. Pearman, and G.R Buell, "Water Resources Data, Georgia, Water Year 1983," U.S. Geological Survey Water Data Report GA-83-1, June 1984.

8. Direct communication with the Water Resources Division, U.S. Geological Survey, U.S.

Department of the Interior, February 1985.

9. Bernd Kahn, et a/., "Bioaccumulation of P-32 in Bluegill and Catfish," NUREG/CR-3981, February 1985.

10. Memo from S.E. Ewald, Georgia Power Company, to C.C. Eckert, Georgia Power Company, May 9,1988.

11. Vogtle Electric Generating Plant Units 1 and 2 Final Safety AnalYSis Report, Georgia Power Company.

12. Vogtle Electric Generating Plant Units 1 and 2 Environmental Report - Operating License Stage, Georgia Power Company.

13. Memo from A.C. Stalker, Georgia Power Company, to D.F. Hallman, Georgia Power Company, May 9,1988.

14. Vogtle Electric Generating Plant Land Use Survey -1988, Georgia Power Company, April 1988.

ix Rev. 18

~----'-"'--'-'--- ..

VEGPODCM

15. Letter to Southern Company Services from Pickard. Lowe. and Garrick. Inc., Washington, D.C., April 27, 1988.

16. Letter to Bill Ollinger, Georgia Power Company, from T.L Broadwell, Georgia Power Company, Atlanta, Georgia, June 22, 1988.

17. Letter to Bill Ollinger, Georgia Power Company, from R.D. Just, Georgia Power Company, Atlanta, Georgia, July 8,1988.

18. L.A. Currie, Lower Limit of Detection: Definition and Elaboration of a Proposed Position of Radiological Effluent and Environmental Measurements, U.S. NRC Report NUREG/CR-4007,1984.

19. "Radiological Assessment Branch Technical Position,* U.S. Nuclear Regulatory Commission, Revision 1, November 1979.

20. D.C. Kocher, "Radioactive Decay Data Tables,* U.S. DOE Report DOEITIC-11026, 1981.

21. J.E. Till and H.R. Meyer, eds., Radiological Assessment, U.S. NRC Report NUREG/CR-3332,1983.

22. Letter to Bill Ollinger, Southern Nuclear Operating Company, from Gary D. Johnson, Georgia Power Company, December 21, 1995.

x Rev. 18

VEGPODCM CHAPTER 1 INTRODUCTION The Offsite Dose Calculation Manual is a supporting document of the Technical Specifications.

As such, it describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liqUid and gaseous effluents, and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm setpoints. In addition, it contains the following:

The controls required by the Technical Specifications, governing the radioactive effluent and radiological environmental monitoring programs.

Schematics of liquid and gaseous radwaste effluent treatment systems, which include designation of release points to UNRESTRICTED AREAS.

A list and maps indicating the specific sample locations for the Radiological Environmental Monitoring Program.

Specifications and descriptions of the information that must be included in the Annual Radiological Environmental Operating Report and the Radioactive Effluent Release Report reqUired by the Technical Specifications.

The ODCM will be maintained at the plant for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to ensure that it represents current methodology in all applicable areas. Any computer software used to perform the calculations descn'bed will be maintained current with the ODCM.

Equations and methods used in the aDCM are based on those presented in NUREG-0133 (Reference 1), in RegUlatory Guide 1.109 (References 2 and 3), in Regulatory Guide 1.111 (References 4 and 5), and in Regulatory Guide 1.113 (Reference 6).

1-1 Rev. 18

VEGPODCM CHAPTER 2 LIQUID EFFLUENTS 2.1 LIMITS OF OPERATION The following Liquid Effluent Controls implement requirements established by Technical Specifications Section 5.0. Terms printed in all capital letters are defined in Chapter 10.

2.1.1 Liquid Effluent Monitoring Instrumentation Control In accordance with Technical Specification 5.5.4.a, the radioactive liquid effluent monitoring instrumentation channels shown in Table 2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits specified in Section 2.1.2 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Section 2.3.

2.1.1.1 Applicability This limit applies at all times.

2.1.1.2 Actions With a radioactive liquid effluent monitoring instrumentation channel alarmltrip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint to a conservative value.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2-1. Restore the INOPERABLE instrumentation to OPERABLE status within 30 days, or if unsuccessful, explain in the next Radioactive Effluent Release Report, per Technical Specification 5.6.3, why this inoperability was not corrected in a timely manner.

This control does not affect shutdown requirements or MODE changes.

2.1.1.3 Surveillance Requirements Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 2-2. Specific instrument numbers are provided in parentheses for information only. The numbers apply to each unit. These numbers will help to identify associated channels or loops and are not intended to limit the requirements to the specific instruments associated with the number.

2-1 Rev. 18

VEGPODCM 2.1.1.4 Basis 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 AlarmfTrip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Section 2.3 to ensure that the alarmltrip will occur prior to exceeding the limits of Section 2.1.2. 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 Part 50.

2-2 Rev. 18

VEGPODCM Table 2-1. Radioactive Liquid Effluent Monitoring Instrumentation OPERABILITY Requirementsa Instrument Minimum Channels Operable ACTION

1. Radwaste Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Line (RE-0018) 1 37

b. Steam Generator Blowdown Effluent Line 1 38 (RE-0021)

c. Turbine Building Effluent Line (RE-0848) 1 38

2. Radwaste Monitors Providina Alarm but Not Automatic Termination of Release NSCW Effluent Line (RE-0020 A&B) 1 39

3. Flowrate Measurement Devices

a. Liquid Radwaste Effluent Line (FT-0018), 1 40 (FT-1084AJB),or(FT-1085AJB)

b. Steam Generator Blowdown Effluent Line 1 40 (FT-0021)

c. Flow to Blowdown Sump (AFQI-7620, F17620A) 1 40

a. All requirements in this table apply to each unit.

2-3 Rev. 20

VEGPODCM Table 2-1 (contd). Notation for Table 2 ACTION Statements ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Section 2.1.2.3, and

b. At least two technically qualified members of the Facility Staff independently verify the discharge line valving and the release rate calculations.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue prOVided grab samples are analyzed for gross radioactivity at a MINIMUM DETECTABLE CONCENTRATION no higher than 1 x 10- J.1CilmL using gross beta/gamma counting or 5 7

7 x 10- J.1CilmL for the principal gamma emitters using gamma-ray spectroscopy.

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 J.1Cilgram DOSE EQUIVALENT 1-131.

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 J.1Cilgram DOSE EQUIVALENT 1-131.

ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for 7

radioactivity at a MINIMUM DETECTABLE CONCENTRATION no higher than 1 x 10-J.1Ci/mLusing gross beta/gamma counting or 5 x 10- J.1CilmL for the principal gamma 7

emitters using gamma-ray spectroscopy.

ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue prOVided the flowrate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves generated in place may be used to estimate flow.

2-4 Rev. 18

VEGPODCM Table 2-2. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements d

Surveillance Requirements CHANNEL CHANNEL Instrument CHANNEL SOURCE CALIBRA- OPERATIONAL CHECK CHECK TION TEST

1. Radwaste Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Line (RE-0018) D P R b Ra(1)

b. Steam Generator Blowdown Effluent Line (RE-0021) D M Rb R8 (1)

c. Turbine Building Effluent Line (RE-0848) D M R b R8 (1)

2. Radwaste Monitors Providing Alarm, but Not Automatic Termination of Release NSCW Effluent Line (RE-0020 MB) D M R b R8 (2)

3. Flowrate Measurement Devices

a. Liquid Radwaste Effluent Line (FT-0018), (FT-1084A1B), or (FT-1085A1B) DC NA R NA

b. Steam Generator Blowdown Effluent Line (FT-0021) DC NA R NA

c. Flow to Blowdown Sump (AFQI-7620, F17620A) DC NA R Q 2-5 Rev. 21

VEGPODCM Table 2-2 (contd). Notation for Table 2-2

a. In addition to the basic functions of a CHANNEL OPERATIONAL TEST (Section 10.2):

(1) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs (for item a. below only); and control room CRT indication occurs (if any of the following conditions exist):

(a) Instrument indicates measured levels above the alarm/trip setpoint; (b) Instrument indicates an "Equipment Trouble" alarm; (c) Instrument indicates a "Low" alarm; or (d) Instrument indicates channel "Deactivated".

(2) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room annunciation occurs (for item a. below only); and that control room CRT indication occurs (if any of the following conditions exist):

(a) Instrument indicates measured levels above the alarmltrip setpoint; (b) Instrument indicates an "Equipment Trouble" alarm; (c) Instrument indicates a "Low" alarm; or (d) Instrument indicates channel "Deactivated".

b. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurements 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.

c. 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

d. All requirements in this table apply to each unit.

2-6 Rev. 18

VEGPODCM 2.1.2 Liquid Effluent Concentration Control In accordance with Technical Specifications 5.5.4.b and 5.5.4.c, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited at all times to ten times the concentrations specified in 10 CFR 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 1 x 10-4 J.1CilmL total activity.

2.1.2.1 Applicability This limit applies at all times.

2.1.2.2 Actions With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the limits stated in Section 2.1.2, immediately restore the concentration to within the stated limits.

This control does not affect shutdown requirements or MODE changes.

2.1.2.3 Surveillance Requirements The radioactivity content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with Table 2-3. The results of radioactive analyses shall be used with the calculational methods in Section 2.3 to assure that the concentration at the point of release is maintained within the limits of Section 2.1.2.

2.1.2.4 Basis This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR 20.1301 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its 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 (1959). The resulting concentration of 2 x 10-4 was then multiplied by the ratio of the effluent concentration limit for Xe-135, stated in Appendix B, Table 2, Column 1 of 10 CFR 20 (paragraphs 20.1001 to 20.2401), to the MPC for Xe-135, stated in Appendix B, Table II, Column 1 of 10 CFR 20 (paragraphs 20.1 to 20.601), to obtain the limiting concentration of 1 x 10-4 J.1CilmL.

2-7 Rev. 18

VEGPODCM Table 2-3. Radioactive Liquid Waste Sampling and Analysis Program b

Sampling and Analysis Requirements8

MINIMUM DETECTABLE CONCENTRA-Minimum Liquid Release Type of Activity TION (MDC)

Sampling Analysis Type FREQUENCY FREQUENCY Analysis (JlCi/mL)

A. BATCH RELEASES PRINCIPAL 5 E-7 GAMMA EMITTERS P P Each BATCH Each BATCH 1-131 1 E-6

1. Waste Monitor Dissolved and 1 E-5 Tank P Entrained Gases One BATCH/M M (Gamma Emitters)

2. Drainage of H-3 1 E-5 System P M Each BATCH COMPOSITE GrossAJDha 1 E-7 Sr-89, Sr-90 5 E-8 P Q Each BATCH COMPOSITE Fe-55 1 E-6 B. CONTINUOUS RELEASES PRINCIPAL 5 E-7 GAMMA EMITTERS W

Continuous COMPOSITE 1-131 1 E-6 Dissolved and 1 E-5 M Entrained Gases Grab Sample M (Gamma Emitters)

Waste Water H-3 1 E-5 Retention Basine M Continuous COMPOSITE GrossAJDha 1 E-7 Sr-89, Sr-90 5 E-8 Q

Continuous COMPOSITE Fe-55 1 E-6 2-8 Rev. 18

VEGPODCM Table 2-3 (contd). Notation for Table 2-3

a. All requirements in this table apply to each unit.

b. Terms printed in all capital letters are defined in Chapter 10.

c. The WWRB will not be considered a release point until there is a confirmed primary to secondary leak. Once a primary to secondary leak has been confirmed, this composite shall be analyzed as specified until the leak is repaired. This surveillance will continue until three consecutive weekly CQmposite samples have shown no activity above the MDC.

2-9 Rev. 18

VEGPODCM 2.1.3 Liquid Effluent Dose Control In accordance with Technical Specifications 5.5.4.d and 5.5.4.e, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

2.1.3.1 Applicability These limits apply at all times.

2.1.3.2 Actions With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the limits of Section 2.1.3., prepare and submit to the Nuclear RegUlatory Commission within 30 days a special report which identifies the cause(s) for exceeding the Iimit(s); defines the corrective actions to be taken to reduce the releases; and defines the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the limits of Section 2.1.3.

This control does not affect shutdown requirements or MODE changes.

2.1.3.3 Surveillance Requirements At least once per 31 days, cumulative dose contributions from liqUid effluents for the current calendar quarter and the current calendar year shall be determined, for each unit, in accordance with Section 2.4.

2.1.3.4 Basis This control is provided to implement the requirements of sections II.A, liLA and IV.A of Appendix I, 10 CFR Part 50. The limits stated in Section 2.1.3 implement the guides set forth in Section ILA of Appendix I. The ACTIONS stated in section 2.1.3.2 provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the reqUirements of 40 CFR Part 141. The dose calculations in Section 2.4 implement the requirements in Section liLA of Appendix I, which state 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 Section 2.4 for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the 2-10 Rev. 18

VEGPODCM methodology provided in Regulatory Guide 1.109 (Reference 3) and Regulatory Guide 1.113 (Reference 6).

This control applies to the release of liquid effluents from each unit at the site. The liquid effluents from shared LIQUID RADWASTE TREATMENT SYSTEMs are to be proportioned between the units.

2.1.4 Liquid Radwaste Treatment System Control In accordance with Technical Specification 5.5.4.f, the LIQUID RADWASTE TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the system shall be used to reduce radioactivity in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 mrem to any organ of a MEMBER OF THE PUBLIC in 31 days.

2.1.4.1 Applicability This limit applies at all times.

2.1.4.2 Actions With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion ofthe LIQUID RADWASTE TREATMENT SYSTEM not in operation, prepare and submit to the Nuclear RegUlatory Commission within 30 days a special report which includes the following information:

a. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems and the reason for the inoperability,

b. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

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

This control does not affect shutdown requirements or MODE changes.

2.1.4.3 Surveillance Requirements Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with section 2.5, during periods in which the LIQUID RADWASTE TREATMENT SYSTEMs are not being fUlly utilized.

The LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting the controls of Sections 2.1.2 and 2.1.3.

2.1.4.4 Basis The OPERABILITY 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 UNRESTRICTED AREAS. 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 2-11 Rev. 18

VEGPODCM be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objective 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 Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

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.

2.1.5 Major Changes to Liguid Radioactive Waste Treatment Systems Licensee initiated MAJOR CHANGES TO LIQUID RADIOACTIVE WASTE TREATMENT SYSTEMS:

a. Shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the change was implemented. The discussion of each change shall contain the information described in section 7.2.2.7.

b. Shall become effective upon review and approval by the General Manager - Nudear Plant.

2-12 Rev. 18

VEGPODCM 2.2 LIQUID RADWASTE TREATMENT SYSTEM The Vogtle Electric Generating Plant is located on the west bank of the Savannah River approximately 151 river miles from the Atlantic Ocean. There are two pressurized water reactors on the site. Each unit is served by a separate LIQUID RADWASTE TREATMENT SYSTEM; however, certain components are shared between the two systems. Schematics of the LIQUID RADWASTE TREATMENT SYSTEMs are presented in Figure 2-1 and Figure 2-2. Liquid discharge pathways are shown in Figure 2-3.

All liquid radwastes treated by the LIQUID RADWASTE TREATMENT SYSTEM are collected in 5,00Q-gallon or 20,000-gallon waste monitor tanks. Releases from the waste monitor tanks are to the discharge line from the blowdown sump, and from there to the Savannah River. The blowclown sump also receives input from the waste water retention basins, turbine plant cooling water blowclown, and nuclear service cooling water blowdown. Additional dilution water is available from the cooling tower makeup water bypass line.

Although no significant quantities of radioactivity are expected in the nuclear service cooling water, the steam generator blowdown processing system, or the turbine building drain system, these effluent pathways are monitored as a precautionary measure. The monitors serving the latter two pathways provide for automatic termination of releases from these systems in the event that radioactivity is detected above predetermined levels. These two systems discharge to the waste water retention basin. Sampling and analysis of releases via all three of these pathways must be sufficient to ensure that the liquid effluent dose limits specified in the controls of Section 2.1.3 are not exceeded.

2-13 Rev. 18

VEGPODCM Chemical Drain Tank Aux. Building Sumo Floor Drain Waste Holdup Laundry and Tank Tank Hot Shower Tank I

Strainer Strainer I

Filter Radwaste Processing Facility I To Unit 2

---.-.***********************I**********.***********- *.....\

I Waste Monitor Waste Monitor Waste Monitor Tank: I Filter

- I Tank: Tank:

5,000 gal 5,000 gal 20,000 gal I Demin , I

I I 1 RE-0018 I I

To Discharge Figure 2-1. Unit 1 Liquid Radwaste Treatment System 2-14 Rev. 19

._-----------------~~ ~ ..

VEGPODCM Floor Drain Waste Holdup Tank Tank Strainer from Laundry and Hot Shower Tank Radwaste (Unit 1) Processing Facility 1-****************************1***********************......

Waste Monitor I

I Waste Monitor Waste Monitor Tank: Filter Tank: Tank:

5.000 gal 5,000 gal 20,000 gal I Demin I i

I I

I 2 RE-0018 I

To Discharge Figure 2*2. Unit 2 Liquid Radwaste Treatment System 2-15 Rev. 19

VEGPODCM Unft2 Unit 1 Unit 1 Steam Steam TUlbine Generator Generator Building Blawdown Blowdown Drain 1 From Other Sumps and Drains Unft 1 Nuclear Service Cooling Water Basin 2 3 L Unit 1 Como!

BulIding Sump From Ott.- Sumps Unft 1 Turbine Plant Cooling Toww r1 Unit 2 Turbine Buldlng DraIns 1

From Unit 2 NucI_ Service Unit 1 OlIyW8Ste H Ott.- UnIt 2 Sumps and DraIns I

SepenItor Cooling Willer Basin cr='~ 1 I From Unit 2 Turbine Plant Cooling Toww Unl1 Waste Willer UnIt 2 OlIyW8Ste Retention Sepeqtor BesIn Unit 1 Uquid Waste Processing System L.t From Unit 2 Waste I

....I - - - - - - - -- fI WIIlerRetentlonBeslnI From Unil2 Liquid was:te0--

Processing 4 ... Cooling T _ MIIkeup System BkMdown BypassUne Sump L_....,__} 4 - - - From FlushIng Ponds (During Construdlon at UnI 2) oRadioactivity Monitors o

1(2)REOO20 o

1(2) REOO21 o

1(2) RE0848 1(2)REOO18 "The b1awdown sump Is common to both units.

Figure 2-3. Liquid Radwaste Discharge Pathways 2-16 Rev. 18

VEGPODCM 2.3 LIQUID EFFLUENT MONITOR SETPOINTS 2.3.1 General Provisions Regarding Setooints Liquid monitor setpoints calculated in accordance with the methodology presented in this section will be regarded as upper bounds for the actual high alarm setpoints. That is, a lower value for the high alarm setpoint may be established or retained on the monitor, if desired. Intermediate level setpoints should be established at an appropriate level to give sufficient warning prior to reaching the high alarm setpoint. If no release is planned for a particular pathway, or if there is no detectable activity in the planned release, the monitor setpoint should be established as close to background as practical to prevent spurious alarms, and yet alarm should an inadvertent release occur.

Two basic setpoint methodologies are presented below. For radwaste system discharge monitors, setpoints are determined to assure that the limits of Section 2.1.2 are not exceeded.

For monitors on streams that are not expected to contain significant radioactivity, the purpose of the monitor setpoints is to cause an alarm on low levels of radioactivity, and to terminate the release where this is possible. Section 2.1.1 establishes the requirements for liquid effluent monitoring instrumentation. Table 2-4 lists the monitors for which each of the setpoint methodologies is applicable.

2-17 Rev. 18

VEGPODCM Table 2-4. Applicability of Liquid Monitor Setpoint Methodologies Liquid Radwaste Discharge Monitors Setpoint Method: Section 2.3.2 Release Type: BATCH Unit 1 or Unit 2 Liguid Waste Treatment System Effluent Monitor: 1RE-0018/2RE-0018 Normally Low-Radioactivity Streams with Termination or Diversion upon Alarm Setpoint Method: Section 2.3.3 Release Type: CONTINUOUS Unit 1 or Unit 2 Steam Generator Blowdown Effluent Monitor: 1RE-0021 / 2RE-0021 Unit 1 or Unit 2 Turbine Building Drain Effluent Monitor: 1RE-0848 / 2RE-0848 Normally Low-Radioactivity Streams with Alarm Only Setpoint Method: Section 2.3.3 Release Type: CONTINUOUS Unit 1 or Unit 2 Nuclear Service Cooling Water System Effluent Monitors (2 per unit): 1RE-0020 A and B 2RE-0020 A and B 2-18 Rev. 18

~------ -'-'~ _. ....

VEGPODCM 2.3.2 Setpoints for Radwaste System Discharge Monitors 2.3.2.1 Overview of Method LIQUID RADWASTE TREATMENT SYSTEM effluent line radioactivity monitors are intended to provide alarm and automatic termination of release prior to exceeding the limits specified in Section 2.1.2 at the point of release of the diluted effluent into the UNRESTRICTED AREA.

Therefore, their alarmltrip setpoints are established to ensure compliance with the following equation (equation adapted from Addendum to Reference 1):

c*f

--~TF*CECL (2.1)

F+f where:

C ECL = the Effluent Concentration Limit corresponding to the mix of radionuclides in the effluent being considered for discharge, in J,lCilmL.

c = the setpoint, in J,lCilml, of the radioactivity monitor measuring the concen-tration of radioactivity in the effluent line prior to dilution and subsequent release. The setpoint represents a concentration which, if exceeded, could result in concentrations exceeding the limits of Section 2.1.2 in the UNRESTRICTED AREA.

f = the effluent fIowrate at the location of the radioactivity monitor, in gpm.

F = the dilution stream fIowrate which can be assured prior to the release point to the UNRESTRICTED AREA, in gpm. A predetermined dilution fIowrate must be assured for use in the calculation of the radioactivity monitor setpoint.

TF = the tolerance factor selected to allow flexibility in the establishment of a practical monitor setpoint which could accommodate effluent releases at concentrations higher than the ECl values stated in 10 CFR 20, Appendix B, Table 2, Column 2; the tolerance factor must not exceed a value of 10.

While equation (2.1) shows the relationships of the critical parameters that determine the setpoint, it cannot be applied practically to a mixture of radionuclides with different Effluent Concentration Limits (ECls). For a mixture of radionuclides, equation (2.1) is satisfied in a practicable manner based on the calculated ECl fraction of the radionuclide mixture and the dilution stream flowrate that can be assured for the duration of the release (Fd), by calculating the maximum permissible effluent flowrate (fm) and the radioactivity monitor setpoint (c).

The setpoint method presented below is applicable to the release of only one tank of liquid radwaste per reactor unit at a given time. Liquid releases must be controlled administratively to ensure that this condition is met; otherwise, the setpoint method may not ensure that the limits of Section 2.1.2 are not exceeded.

2-19 Rev. 18

VEGPODCM 2.3.2.2 Setpoint Calculation Steps Step 1: Determine the radionuclide concentrations in the liquid waste being considered for release in accordance with the sampling and analysis requirements of Section 2.1.2.

All liquid radwastes treated by the LIQUID RADWASTE TREATMENT SYSTEM are collected in waste monitor tanks for sampling and analysis. The 5,00Q-gallon waste monitor tanks are recirculated for a minimum of 30 minutes, and the 20,0OQ-gallon waste monitor tanks are recirculated for a minimum of 45 minutes. This mixing assures that a representative sample can be taken from the tank.

The total concentration of the liquid waste is determined by the results of all required analyses on the collected sample, as follows:

LCi =Ca + LC +Cf +C, + LCg g (2.2) g g where:

Ca = the gross concentration of alpha emitters in the liquid waste, not less than that measured in the most recent applicable composite sample.

Cs = the concentration of strontium radioisotope s (Sr-89 or Sr-90) in the liquid waste, not less than that measured in the most recent applicable composite sample.

= the concentration of FEr55 in the liquid waste, not less than that measured in the most recent applicable composite sample.

= the concentration of H-3 in the liquid waste, not less than that measured in the most recent applicable composite sample.

Cg = the concentration of gamma emitter g in the liquid waste as measured by gamma ray spectroscopy performed on the sample for the release under consideration.

The Cg term will be included in the analysis of each waste sample; terms for gross concentrations of alpha emitters, Sr-89, Sr-90, Fe-55, and tritium will be included in accordance with the sampling and analysis program required for the waste stream (see Section 2.1.2). For each analysis, only radionuclides identified and detected above background for the given measurement should be included in the calculation. When using the alternate setpoint methodology of step 5.b, the historical maximum values of Ca, Cs , Ct, and Ct shall be used.

Determine the required dilution factor for the mix of radionuclides detected in the waste.

Measured radionuclide concentrations are used to calculate ECL fractions. The ECL fractions are used along with a safety factor to calculate the required dilution factor; this is the minimum ratio of dilution f10wrate to waste f10wrate that must be maintained throughout the release to ensure that the limits of Section 2.1.2 are not exceeded at the point of discharge into the UNRESTRICTED 2-20 Rev. 18

VEGPODCM AREA. The required dilution factor, RDF, is calculated as the sum of the dilution factors required for gamma emitters (RDFy) and for non-gamma-emitters (RDFny):

RDF = [L ~]

j ECL j

+ [(SFXTF)]

(2.3)

(2.4) where:

Co L Cs Cf C,]

RDF _ [ EeL; + s EeL; + EeL; + EeL; ny - (SFXTF) (2.5)

Cj = the measured concentration of radionuclide i as defined in step 1, in ~CilmL.

The C a, Cs , Ct, and Ct terms will be incllided in the calculation as appropriate.

= the Effluent Concentration Limit for radionuclide i from 10 CFR Part 20, Appendix B, Table 2, Column 2 (except for noble gases as discussed below).

In the absence of information regarding the solubility classification of a given radionuclide in the waste stream, the solubility class with the lowest ECl shall be assumed. For dissolved or entrained noble gases, the concentration shall be limited to 1x10-t ~CilmL. For gross alpha, the ECl shall be 2x10-9 ~Cilml; if specific alpha-emitting radionuclides are measured, the ECl for the specific radionuclide(s) should be used.

SF = the safety factor selected to compensate for statistical fluctuations and errors of measurement. The value for the safety factor must be between 0 and 1.

A value of 0.5 is reasonable for liquid releases; a more precise value may be developed if desired.

TF = the tolerance factor (as defined in Section 2.3.2.1).

Step 3: Determine the release-specific assured dilution stream f1owrate.

Determine the dilution stream f10wratethat can be assured during the release period, designated Fd; this value is the setpoint for the dilution stream f10wrate measurement device.

If simultaneous radioactive releases are planned from the same or different reactor units, the dilution stream must be allocated among all the simultaneous releases. There will only be one such release per unit at a given time, unless there is detectable radioactivity in one of the normally low-radioactivity streams (see Section 2.3.3). Allocation of the dilution stream to multiple release paths is accomplished as follows:

2-21 Rev. 18

VEGPODCM (2.6) where:

Fdp = the dilution flowrate allocated to release pathway p, in gpm.

AF p = the dilution allocation factor for release pathway p. AFp may be assigned any value between 0 and 1 for each active release pathway, under the condition that the sum of the AF p for all active release pathways for the entire plant site does not exceed 1.

Fd = the assured minimum dilution flow for the unit, in gpm.

In the normal case in which the only release pathways with detectable radioactivity are the LIQUID RADWASTE TREATMENT SYSTEMs of each unit, AFp for each unit may be assigned the value of 0.5 to permit releases from either unit to be made without regard to any releases from the other unit; if only one unit's LIQUID RADWASTE TREATMENT SYSTEM is releasing at a given time, its AFp may be increased proportionately. If more precise allocation factor values are desired, they may be determined based on the relative radiological impact of each active release pathway; this may be approximated by multiplying the RDF of each effluent stream by its respective planned release flowrate, and comparing these values. If only one simultaneous release is being made, its AFp may be assigned the value of 1, making Fdp equal to Fd

For the case where RDF ~ 1, the planned release meets the limits of Section 2.1.2 without dilution, and could be released with any desired effluent flowrate and dilution flowrate. However, in order to maintain individual doses due to liquid effluent releases as low as is reasonably achievable, no releases with detectable radioactivity should be made if the assured dilution flowrate, Fd , is less than 12,000 gpm.

Step 4: Determine the maximum allowable waste discharge flowrate.

For the case where RDF > 1, the maximum permissible effluent discharge flowrate for this release pathway, fmp (in gpm), is calculated as follows:

_ Fdp (2.7)

Imp - (RDF-l)

For the case RDF ~ 1, equation (2.7) is not valid. However, as discussed above, when RDF ~ 1, the release may be made at full discharge pump capacity; the radioactivity monitor setpoint must still be calculated in accordance with Step 5 below.

NOTE 1: Discharge flowrates are actually limited by the discharge pump capacity. When the calculated maximum permissible release flowrate exceeds the pump capacity, the release may be made at full capacity. Discharge flowrates less than the pump capacity must be achieved by throttling if this is available; if throttling is not available, the release may not be made as planned.

NOTE 2: If, at the time of the planned release, there is detectable radioactivity due to plant operations in the dilution stream, the diluting capacity of the dilution stream is diminished. (In addition, sampling and analysis of the other radioactive effluents affecting the dilution stream must be sufficient to ensure that the liquid effluent 2-22 Rev. 18

VEGPODCM dose limits specified in the controls of Section 2.1.3 are not exceeded.) Under these conditions, equation (2.7) must be modified to account for the radioactivity present in the dilution stream prior to the introduction of the planned release:

t., = (;;_1)(1- ~[~ ~(E~LJ]J (2.8) where:

= the measured concentration of radionuclide i in release pathway r that is contributing to radioactivity in the dilution stream.

= the effluent discharge f10wrate of release pathway r.

If the entire dilution stream contains detectable activity due to plant operations,

=

whether or not its source is identified, fr Fd , and Cir is the concentration in the total dilution system. This note does not apply: a) if the RDF of the planned release is ~ 1; or b) if the release contributing radioactivity to the dilution stream has been accounted for by the assignment of an allocation factor.

SteD 5: Determine the maximum radioactivity monitor setpoint concentration.

Based on the values determined in previous steps, the radioactivity monitor setpoint for the planned release is calculated to ensure that the limits of Section 2.1.2 will not be exceeded.

Because the radioactivity monitor responds primarily to gamma radiation, the monitor setpoint Cp for release pathway p (in J.LCilmL) is based on the concentration of gamma emitters in the waste stream, as follows:

(2.9) where:

Ap = an adjustment factor which will allow the setpoint to be established in a practical manner to prevent spurious alarms while allowing a margin between measured concentrations and the limits of Section 2.1.2.

Step 5.a. If the concentration of gamma emitters in the effluent to be released is sufficient that the high alarm setpoint can be established at a level that will prevent spurious alarms, Ap should be calculated as follows:

A =_l-xADF p RDF (2.10)

= X (FdP + lap)

-'--'--~

RDF lap 2-23 Rev. 18

VEGPODCM where:

ADF = the assured dilution factor.

fap = the anticipated actual discharge f10wrate for the planned release (in gpm), a value less than f mp

The release must then be controlled so that the actual effluent discharge flowrate does not exceed f ap at anytime.

Step 5.b. Alternatively, Ap may be calculated as follows:

ADF - RDFnr Ap =

RDFr (2.11)

Step 5.c. Evaluate the computed value of Ap as follows:

If Ap ~ 1, calculate the monitor setpoint, Cp. However, if Cp is within about e

10 percent of g , it may be impractical to use this value of Cp. This situation indicates that measured concentrations are approaching values which would cause limits of Section 2.1.2 to be exceeded.

Therefore, steps should be taken to reduce potential concentrations at the point of discharge; these steps may include decreasing the planned effluent discharge fIowrate, increasing the dilution stream f1owrate, postponing simultaneous releases, and/or decreasing the effluent concentrations by further processing the liquid planned for release. Alternatively, allocation factors for the active liquid release pathways may be reassigned. When one or more of these actions has been taken, repeat Steps 1-5 to calculate a new radioactivity monitor setpoint.

If Ap < 1, the release may not be made as planned. Consider the alternatives discussed in the paragraph above, and calculate a new setpoint based on the results of the actions taken.

2.3.2.3 Use of the Calculated Setpoint The setpoint calculated above is in the units ~CilmL. The monitor actually measures a count rate, subtracts a predetermined background count rate, and multiplies by a calibration factor to convert from count rate to ~CilmL.

Initial calibration of the monitors by the manufacturer and Georgia Power Company utilized NIST-traceable liquid solutions with gamma ray emissions over the range 0.08 to 1.33 MeV, in the exact geometry of each production monitor. The calibration factor is a function of the radionuclide mix in the liquid to be released, and will be calculated for the monitor based on the results of the pre-release sample results from the laboratory gamma-ray spectrometer system. The mix-dependent calibration factor will be used as the gain factor in the PERMS monitor, or used to modify the 2-24 Rev. 18

VEGPODCM calculated base monitor setpoint so that the default calibration factor in the PERMS monitor can be left unchanged.

Notwithstanding the initial calibration, monitor calibration data for conversion between count rate and concentration may include operational data obtained from determining the monitor response to stream concentrations measured by liquid sample analysis. In all cases, monitor background must be controlled so that the monitor is capable of responding to concentrations in the range of the setpoint value.

2.3.3 Setooints for Monitors on Normally Low-Radioactivity Streams Radioactivity in these streams (listed in Table 2-4 above) is expected to be at very low levels, generally below detection limits. Accordingly, the purpose of these monitors is to alarm upon the occurrence of significant radioactivity in these streams, and to terminate or divert the release where this is possible.

2.3.3.1 Normal Conditions When radioactivity in one of these streams is at its normal low level, its radioactivity monitor setpoint should be established as close to background as practical to prevent spurious alarms, and yet alarm should an inadvertent release occur.

2.3.3.2 Conditions Requiring an Elevated Setpoint Under the following conditions, radionuclide concentrations must be determined and an elevated radioactivity monitor setpoint determined for these pathways:

For streams that can be diverted or isolated, a new monitor setpoint must be established when it is desired to discharge the stream directly to the dilution water even though the radioactivity in the stream exceeds the level which would normally be diverted or isolated.

For streams that cannot be diverted or isolated, a new monitor setpoint must be established whenever: the radioactivity in the stream becomes detectable above the background levels of the applicable laboratory analyses; or the associated radioactivity monitor detects activity in the stream at levels above the established alarm setpoint.

When an elevated monitor setpoint is required for any of these effluent streams, it should be determined in the same manner as described in Section 2.3.2. However, special consideration must be given to Step 3. An allocation factor must be assigned to the normally low-radioactivity release pathway under consideration, and allocation factors for other release pathways discharging simultaneously must be adjusted downward (if necessary) to ensure that the sum of the allocation factors does not exceed 1. Sampling and analysis of the normally low-radioactivity streams must be sufficient to ensure that the liquid effluent dose limits specified in the controls of Section 2.1.3 are not exceeded.

2-25 Rev. 18

VEGPODCM 2.4 LIQUID EFFLUENT DOSE CALCULATIONS The following sub-sections present the methods required for liquid effluent dose calculations, in deepening levels of detail. Applicable site-specific pathways and parameter values for the calculation of D"An, and CF jy are summarized in Table 2-5.

2.4.1 Calculation of Dose The dose limits for a MEMBER OF THE PUBLIC specified in Section 2.1.3 are on a per-unit basis.

Therefore, the doses calculated in accordance with this section must be determined and recorded on a per-unit basis, including apportionment of releases shared between the two units.

For the purpose of implementing Section 2.1.3, the dose to the maximum exposed individual due to radionuclides identified in liquid effluents released from each unit to UNRESTRICTED AREAS will be calculated as follows (equation from Reference 1, page 15):

(2.12) where:

D, = the cumulative dose commitment to the total body or to any organ 't, in mrem, due to radioactivity in liquid effluents released during the total of the m time periods L\~.

An = the site-related adult ingestion dose commitment factor, for the total body or for any organ 't, due to identified radionuclide i, in (mrem*mL)/(h*J.LCi).

Methods for the calculation of An are presented below in Section 2.4.2. The values of An to be used in dose calculations for releases from the plant site are listed in Table 2-8.

L\t = the length of time period I, over which Cu and F, are averaged for liquid releases, in h.

C il = the average concentration of radionuclide i in undiluted liquid effluent during time period I, in J.LCilmL. Only radionuclides identified and detected above background in their respective samples should be included in the calculation.

F/ = the near-field average dilution factor in the receiving water of the UNRESTRICTED AREA:

--L F./ - (2.13)

F,xZ where:

ft = the average undiluted liquid waste f10wrate actually observed during the period of radioactivity release, in gpm.

2-26 Rev. 18

VEGPOOCM the average dilution stream f10wrate actually observed during the period of radioactivity release, in gpm. If simultaneous releases from both units occur, the dilution stream f10wrate Ft must be allocated between them. In such cases, F, is unit-specific.

Z = the applicable dilution factor for the receiving water body, in the near field of the discharge structure, during the period of radioactivity release, from Table 2-5.

NOTE: In equation (2.13), the product (Ft x Z) is limited to 1000 cis (=

448,000 gpm) or less. (Reference 1, Section 4.3.)

2.4.2 Calculation of &.

The site-related adult ingestion dose commitment factor, A+t, is calculated as follows (equation adapted from Reference 1, page 16, by addition of the irrigated garden vegetation pathway):

An : 1.14 x 10' (~: e--+UfBF;e-J;'f+U,cpi, )VF. (2.14) where:

1.14 X 105 = a units conversion factor, determined by:

106 pCiI~Ci x 1cf mUL + 8760 hIy.

Uw = the adult drinking water consumption rate applicable to the plant site (Uy).

Ow = the dilution factor from the near field of the discharge structure for the plant site to the potable water intake location.

~ = 1 the decay constant for radionuclide i (h- ). Values of ~ used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

tw = the transit time from release to receptor for potable water consumption (h).

Uf = the adult rate of fish consumption applicable to the plant site (kgly).

BF j = the bioaccumulation factor for radionuclide i applicable to freshwater fish in

=

the receiving water body for the plant site, in (pCilkg)/(pCilL) (Llkg). For specific values applicable to the plant site, see Table 2-6.

tf = the transit time from release to receptor for fish consumption (h).

Uy = the adult consumption rate for irrigated garden vegetation applicable to the plant site (kg/y).

2-27 Rev. 18

VEGPODCM CF jy = the concentration factor for radionuclide i in irrigated garden vegetation, as applicable to the vicinity of the plant site, in (pCilkg)/(pCilL). Methods for calculation of CF jy are presented below in Section 2.4.3.

DFit = the dose conversion factor for radionuclide i for adults, in organ 't (mremlpCi).

For specific values, see Table 2-7.

2.4.3 Calculation of Cf;"

The concentration factor for radionuclide i in irrigated garden vegetation, CF jy in (Ukg), is calculated as follows:

For radionuclides other than tritium (equation adapted from Reference 3, equations A-8 and A-9):

CF =M .I [r1-( e-A t) + f.1 B (1 e-Alb)]

£1, jv - -A/A (2.15) iv y,t p,t e v Ei i

For tritium (equation adapted from Reference 3, equations A-9 and A-10):

CFjv = M*1." (2.16) where:

M = the additional river dilution factor from the near field of the discharge structure for the plant site to the point of irrigation water usage.

2 I = the average irrigation rate during the growing season (L)/(m *h).

r = the fraction of irrigation-deposited activity retained on the edible portions of leafy garden vegetation.

Y" = the areal density (agricultural productivity) of leafy garden vegetation (kg/m 2) fl = the fraction of the year that garden vegetation is irrigated.

B jy = the crop to soil concentration factor applicable to radionuclide i (pCilkg garden vegetation)/(pCilkg soil).

2 P = the effective surface density of soil (kg/m ).

1

~ = the decay constant for radionuclide i (h- ). Values of ~ used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

Aw = the rate constant for removal of activity from plant leaves by weathering (h-1).

A.Ei = the effective removal rate for activity deposited on crop leaves (h-1) calculated as: A.Ei = ~ + Aw.

2-28 Rev. 18

VEGPODCM

= the period of leafy garden vegetation exposure during the growing season (h).

tt, = the period of long-term buildup of activity in soil (h).

4, = . the time between harvest of garden vegetation and human consumption (h).

Lv = the water content of leafy garden vegetation edible parts (Ukg).

2-29 Rev. 18

_._----_ .*.~._-------

VEGPODCM Table 2-5. Parameters for Calculation of Doses Due to liquid Effluent Releases Dose Calculation Receptor Locations:

Fish: Vicinity of plant discharge Drinking Water: 112 miles downstream, at Beaufort, SC (Reference 12)

Irrigated Garden Vegetation: None (Reference 12)

Numerical Parameters:

Parameter Reference z 10, for May through December Ref. 11 20, for January through April 730Uy Ref 3 8 Ref. 7 48h Ref. 3, Sec. A.2; Ref. 8 21 kg/y Ref. 3, Table E-5 24 h Ref. 3, sec. A.2 o kg/y Ref. 12 1.0 +

No value -

0.25 Ref. 3, Table E-15.

2 2.0 kg/m Ref. 3, Table E-15 1.0 +

.240 kg/m2 Ref. 3, Table E-15 1

0.0021 h- (i.e., half-life of 14 d) Ref. 3, Table E-15 1440 h (= 60 d) Ref. 3, Table E-15 5

1.31 X 10 h (= 15 y) Ref. 3, Table E-15 24 h Ref. 3, Table E-15 0.92 Ukg Based on Ref. 21, Table 5.16 (for lettuce, cabbage, etc.)

Because there is no irrigated garden vegetation pathway downstream of the plant site, the consumption of irrigated garden vegetation is set to zero, and the other pathway parameters are defaults.

+ - There is no established default value for this parameter. The most conservative physically realistic value is 1.0.

2-30 Rev. 18

VEGPODCM Table 2-6. Element Transfer Factors Freshwater Fish Element .

BF j H 9.0 E-01 C 4.6 E+03 Na 1.0 E+02 P 3.0 E+03 Cr 2.0 E+02 Mn 4.0 E+02 Fe 1.0 E+02 Co 5.0 E+01 Ni 1.0 E+02 Cu 5.0 E+01 Zn 2.0 E+03 Br 4.2 E+02 Rb 2.0 E+03 Sr 3.0 E+01 Y 2.5 E+01 Zr 3.3 E+OO Nb 5.5 E+02 Mo 1.0 E+01 Tc 1.5 E+01 Ru 1.0 E+01 Rh 1.0 E+01 Ag 2.3 E+OO Sb 2.0 E+02 Te 4.0 E+02 I 1.5 E+01 Cs 2.0 E+03 Ba 4.0 E+OO La 2.5 E+01 Ce 1.0 E+OO Pr 2.5 E+01 Nd 2.5 E+01 W 1.2 E+03 Np 1.0 E+01

Bioaccumulation Factors for freshwater fish, in (pCi/kg)/(pCilL). They are obtained from Reference 3 (Table A-1), except as follows: Reference 9 for P; Reference 2 (Table A-

8) for Ag; and Reference 10 for Nb and Sb.

2-31 Rev. 18

VEGPODCM Table 2-7. Adult Ingestion Dose Factors Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LU H-3 No Data 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2. 17E-05 Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 No Data No Data 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.85E-06 3.40E-05 Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88E-06 Ni-65 5.28E-07 6.86E-08 3. 13E-08 No Data No Data No Data 1.74E-06 Cu-64 No Data 8.33E-08 3.91E-08 No Data 2. 1OE-07 No Data 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 Br-84 No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13 Br-85 No Data No Data 2. 14E-09 No Data No Data No Data No Data Rb-86 'No Data 2.11E-05 9.83E-06 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19 Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2. 19E-04 Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 All values are in (mrem/pCi ingested). They are obtained from Reference 3 (Table E-11),

except as follows: Reference 2 (Table A-3) for Rh-105, Sb-124, and Sb-125.

2-32 Rev. 18

VEGPODCM Table 2-7 (contd). Adult Ingestion Dose Factors Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Sr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 Y-91m 9.09E-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10 Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 Y-92 8.45E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05 Y-93 2.68E-09 No Data 7.40E-11 No Data No Data No Data 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 No Data 1.53E-08 No Data 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.10E-05 Mo-99 No Data 4.31E-06 8.20E-07 No Data 9.76E-06 No Data 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Rh-105 1.22E-07 8.86E-08 5.83E-08 No Data 3.76E-07 No Data 1.41E-05 Ag-110m 1.60E-07 1.48E-07 8.79E-08 No Data 2.91E-07 No Data 6.04E-05 Sb-124 2.81E-06 5.30E-08 1.11E-06 6.79E-09 No Data 2.18E-06 7.95E-05 Sb-125 2.23E-06 2.40E-08 4.48E-07 1.98E-Q9 No Data 2.33E-04 1.97E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 2-33 Rev. 18

VEGPODCM Table 2-7 (contd). Adult Ingestion Dose Factors Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LU Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 1-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 No Data *1.02E-07 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 No Data 2.22E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 No Data No Data No Data 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 No Data 3.65E-10 No Data 2.40E-05 2-34 Rev. 18

VEGPODCM Table 2-8. Site-Related Ingestion Dose Factors, An Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 0.00 1.32E+00 1.32E+00 1.32E+00 1.32E+00 1.32E+00 1.32E+00 C-14 3.13E+04 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 Na-24 1.36E+02 1.36E+02 1.36E+02 1.36E+02 1.36E+02 1.36E+02 1.36E+02 P-32 1.32E+06 8.22E+04 5.11E+04 0.00 0.00 0.00 1.49E+05 Cr-51 0.00 0.00 1.27E+00 7.58E-01 2.79E-01 1.68E+00 3.19E+02 Mn-54 0.00 4.41E+03 8.42E+02 0.00 1.31E+03 0.00 1.35E+04 Mn-56 0.00 1.74E-01 3.08E-02 0.00 2.21E-01 0.00 5.55E+00 Fe-55 6.86E+02 4.74E+02 1.11E+02 0.00 0.00 2.65E+02 2.72E+02 Fe-59 1.07E+03 2.51E+03 9.61E+02 0.00 0.00 7.01E+02 8.36E+03 Co-58 0.00 9.59E+01 2.15E+02 0.00 0.00 0.00 1.94E+03 Co-60 0.00 2.78E+02 6. 14E+02 0.00 0.00 0.00 5.23E+03 Ni-63 3. 25E+04 2.25E+03 1.09E+03 0.00 0.00 0.00 4.70E+02 Ni-65 1.72E-01 2.23E-02 1.02E-02 0.00 0.00 0.00 5.66E-01 Cu-64 0.00 2.75E+00 1.29E+00 0.00 6.94E+00 0.00 2.35E+02 Zn-65 2.32E+04 7.37E+04 3.33E+04 0.00 4.93E+04 0.00 4.64E+04 Zn-69 7.88E-07 1.51E-06 1.05E-07 0.00 9.79E-07 0.00 2.26E-07 Br-83 0.00 0.00 3.83E-02 0.00 0.00 0.00 5.52E-02 Br-84 0.00 0.00 1.22E-12 0.00 0.00 0.00 9.61E-18 Br-85 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Rb-86 0.00 9.75E+04 4.54E+04 0.00 0.00 0.00 1.92E+04 Rb-88 0.00 1.29E-22 6.82E-23 0.00 0.00 0.00 1.78E-33 Rb-89 0.00 1.61E-26 1.14E-26 0.00 0.00 0.00 0.00 Sr-89 2.49E+04 0.00 7.16E+02 0.00 0.00 0.00 4.00E+03 Sr-90 6.23E+05 0.00 1.53E+05 0.00 0.00 0.00 1.80E+04 Sr-91 7.25E+01 0.00 2.93E+00 0.00 0.00 0.00 3.45E+02 Sr-92 3.33E-01 0.00 1.44E-02 0.00 0.00 0.00 6.60E+00 Y-90 5.04E-01 0.00 1.35E-02 0.00 0.00 0.00 5. 34E+03 Y-91m 1.04E-11 0.00 4.01E-13 0.00 0.00 0.00 3.04E-11 Y-91 9.77E+00 0.00 2.61E-01 0.00 0.00 0.00 5.38E+03 Y-92 4.61E-04 0.00 1.35E-05 0.00 0.00 0.00 8.07E+00 Y-93 3.19E-02 0.00 8.82E-04 0.00 0.00 0.00 1.01E+03 Zr-95 5.47E-01 1.75E-01 1.19E-01 0.00 2.75E-01 0.00 5.56E+02 Zr-97 7.40E-03 1.49E-03 6.83E-04 0.00 2.26E-03 0.00 4.62E+02 Nb-95 8.09E+00 4.50E+00 2.42E+00 0.00 4.45E+00 0.00 2.73E+04 Mo-99 0.00 1.07E+02 2.04E+01 0.00 2.43E+02 0.00 2.49E+02 Tc-99m 5.70E-04 1.61E-03 2.05E-02 0.00 2.44E-02 7.89E-04 9.53E-01 All values are in (mrem*mL)/(h*IlCi). They are calculated using equation (2.14), and data from Table 2-5, Table 2-6, and Table 2-7. When "No Data" is shown for a radionuclide-organ combination in Table 2-7, An factors in this table are presented as zero.

2-35 Rev. 18

VEGPODCM Table 2-8 (contd). Site-Related Ingestion Dose Factors, At Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Tc-101 2.71E-33 3.91E-33 3.83E-32 0.00 7.03E-32 2.00E-33 0.00 Ru-103 6.21E+00 0.00 2.68E+00 0.00 2.37E+01 0.00 7.25E+02 Ru-105 8.79E-03 0.00 3.47E-03 0.00 1.14E-01 0.00 5.38E+00 Ru-106 9.42E+01 0.00 1.19E+01 0.00 1.82E+02 0.00 6.10E+03 Rh-105 2.32E+00 1.69E+00 1.11E+00 0.00 7.15E+00 0.00 2.68E+02 Ag-110m 2.53E+00 2.34E+00 1.39E+00 0.00 4.61E+00 0.00 9.56E+02 Sb-124 1.36E+03 2.56E+01 5.37E+02 3.28E+00 0.00 1.05E+03 3.84E+04 Sb-125 1.09E+03 1.17E+01 2.19E+02 9.68E-01 0.00 1.14E+05 9.63E+03 Te-125m 2.56E+03 9.29E+02 3.43E+02 7.71E+02 1.04E+04 0.00 1.02E+04 Te-127m 6.51E+03 2.33E+03 7.93E+02 1.66E+03 2.64E+04 0.00 2.18E+04 Te-127 1.78E+01 6.40E+00 3.85E+00 1.32E+01 7.25E+01 0.00 1.41E+03 Te-129m 1.09E+04 4.07E+03 1.73E+03 3.74E+03 4.55E+04 0.00 5.49E+04 Te-129 1.78E-05 6.68E-06 4.33E-06 1.36E-05 7.47E-05 0.00 1.34E-05 Te-131m 9.57E+02 4.68E+02 3.90E+02 7.42E+02 4.74E+03 0.00 4.65E+04 Te-131 8.64E-17 3.61E-17 2.73E-17 7.10E-17 3.78E-16 0.00 1.22E-17 Te-132 1.97E+03 1.27E+03 1.19E+03 1.41E+03 1.23E+04 0.00 6.02E+04 1-130 7.60E+00 2.24E+01 8.85E+00 1.90E+03 3.50E+01 0.00 1.93E+01 1-131 1.73E+02 2.48E+02 1.42E+02 8.13E+04 4.25E+02 0.00 6.55E+01 1-132 5.27E-03 1.41E-02 4.93E-03 4.93E-01 2.24E-02 0.00 2.65E-03 1-133 2.59E+01 4.51E+01 1.37E+01 6.62E+03 7.86E+01 0.00 4.05E+01 1-134 2.18E-08 5.94E-08 2.12E-08 1.03E-06 9.44E-08 0.00 5.17E-11 1-135 1.31E+00 3.44E+00 1.27E+00 2.27E+02 5.52E+00 0.00 3.89E+00 Cs-134 2.98E+05 7. 1OE+05 5.80E+05 0.00 2.30E+05 7.62E+04 1.24E+04 Cs-136 2.96E+04 1.17E+05 8.42E+04 0.00 6.51E+04 8.92E+03 1.33E+04 Cs-137 3.82E+05 5.23E+05 3.43E+05 0.00 1.78E+05 5.90E+04 1.01E+04 Cs-138 9.12E-12 1.80E-11 8.92E-12 0.00 1.32E-11 1.31E-12 7.68E-17 Ba-139 5.64E-06 4.02E-09 1.65E-07 0.00 3.76E-Q9 2.28E-09 1.00E-05 Ba-140 3.74E+02 4.69E-01 2.45E+01 0.00 1.60E-01 2.69E-01 7.69E+02 Ba-141 8.47E-25 6.40E-28 2.86E-26 0.00 5.95E-28 3.63E-28 3.99E-34 Ba-142 0.00 0.00 0.00 0.00 0.00 0.00 0.00 La-140 1.10E-01 5.56E-02 1.47E-02 0.00 0.00 0.00 4.08E+03 La-142 2. 19E-07 9.96E-08 2.48E-08 0.00 0.00 0.00 7.27E-04 Ce-141 1.15E-01 7.79E-02 8.84E-03 0.00 3.62E-02 0.00 2.98E+02 Ce-143 8.65E-03 6.39E+00 7.08E-04 0.00 2.81E-03 0.00 2.39E+02 Ce-144 6.22E+00 2.60E+00 3.34E-01 0.00 1.54E+00 0.00 2.10E+03 Pr-143 6.10E-01 2.44E-01 3.02E-02 0.00 1.41E-01 0.00 2.67E+03 Pr-144 1.48E-28 6. 14E-29 7.51E-30 0.00 3.46E-29 0.00 2.13E-35 Nd-147 4.11E-01 4.75E-01 2.84E-02 0.00 2.78E-01 0.00 2.28E+03 W-187 1.47E+02 1.23E+02 4.31E+01 0.00 0.00 0.00 4.04E+04 Np-239 2.81E-02 2.76E-03 1.52E-03 0.00 8.62E-03 0.00 5.67E+02 2-36 Rev. 18

VEGPODCM 2.5 LIQUID EFFLUENT DOSE PROJECTIONS 2.5.1 Thirty-One Day Dose Projections In order to meet the requirements for operation of the LIQUID RADWASTE TREATMENT SYSTEM (see Section 2.1.4), dose projections must be made at least once each 31 days; this applies during periods in which a discharge to UNRESTRICTED AREAS of liquid effluents containing radioactive materials occurs or is expected.

Projected 31-day doses to individuals due to liquid effluents may be determined as follows:

D'P=(~TC) x31+Dm (2.17) where:

Dtp = the projected dose to the total body or organ 't, for the next 31 days of liquid releases.

DtC = the cumulative dose to the total body or organ 't, for liquid releases that have occurred in the elapsed portion of the current quarter, plus the release under consideration.

t = the number of whole or partial days elapsed into the current quarter, including the time to the end of the release under consideration (even if the release continues into the next quarter).

D18 = the anticipated dose contribution to the total body or any organ 't, due to any planned activities during the next 31-day period, if those activities will result in liquid releases that are in addition to routine liquid effluents. If only routine liquid effluents are anticipated, D18 may be set to zero.

2.5.2 Dose'Projections for Specific Releases Dose projections may be performed for a particular release by performing a pre-release dose calculation assuming that the planned release will proceed as anticipated. For individual dose projections due to liquid releases, follow the methodology of Section 2.4, using sample analysis results for the source to be released, and parameter values expected to exist during the release period.

2-37 Rev. 18

VEGPODCM 2.6 DEFINITIONS OF LIQUID EFFLUENT TERMS The following symbolic terms are used in the presentation of liquid effluent calculations in the sub-sections above.

Section of Term Definition Initial Use Ap = the adjustment factor used in calculating the effluent monitor setpoint for liquid release pathway p: the ratio of the assured dilution to the required dilution [unitless). 2.3.2.2 ADF = the assured dilution factor for a planned release [unitless]. 2.3.2.2 AF p = the dilution allocation factor for liquid release pathway p [unitless]. 2.3.2.2 Att = the site-related adult ingestion dose commitment factor, for the total body or for any organ 't, due to identified radionuclide i

[(mrem . mL)/(h . ~Ci)]. The values of Att are listed in Table 2-8. 2.4.1 Biv = the crop to soil concentration factor applicable to radionuclide i,

[(pCilkg garden vegetation}/(pCilkg soil)]. 2.4.3 BF j = the bioaccumulation factor for radionuclide i for freshwater fISh

[(pCilkg}/(pCilL)]. Values are listed in Table 2-6. 2.4.2 c = the setpoint of the radioactivity monitor measuring the concentration of radioactivity in the effluent line, prior to dilution and subsequent release ~CilmL]. 2.3.2.1 Cp = the calculated effluent radioactivity monitor setpoint for liquid release pathway p ~CilmL]. 2.3.2.2 Ca = the gross concentration of alpha emitters in the liquid waste as measured in the applicable composite sample ~CilmL]. 2.3.2.2 CECL = the Effluent Concentration Limit stated in 10 CFR 20, Appendix B, Table 2, Column 2 ~CilmL]. 2.3.2.1 Ct = the concentration of Fe--55 in the liquid waste as measured in the applicable composite sample ~CilmL]. 2.3.2.2 Cg = the concentration of gamma emitter g in the liquid waste as measured by gamma ray spectroscopy performed on the applicable pre-release waste sample [~CilmL]. 2.3.2.2 Cj = the measured concentration of radionuclide i in a sample of liquid effluent [~Ci/mL]. 2.3.2.2 2-38 Rev. 18

VEGPODCM Section of Term Definition Initial Use C il = the average concentration of radionuclide i in undiluted liquid effluent during time period 1(J.tCilmL]. 2.4.1 C ir = the measured concentration of radionuclide i in release pathway r that is contributing to radioactivity in the dilution stream (J,1CilmL). 2.3.2.2 Cs = the concentration of strontium radioisotope s (Sr-89 or Sr-90) in the liquid waste as measured in the applicable composite sample (J.tCilmL). 2.3.2.2

c. = the concentration of H-3 in the liquid waste as measured in the applicable composite sample (J.tCilmL). 2.3.2.2 CFjy = the concentration factor for radionuclide i in irrigated garden vegetation (pCilkg}/(pCilL}). 2.4.2 Ow = the dilution factor from the near field of the discharge structure to the potable water intake location [unitless). 2.4.2 Dt = the cumulative dose commitment to the total body or to any organ 't, due to radioactivity in liquid effluents released during a given time period [mrem). 2.4.1 Dta = the anticipated dose contribution to the total body or any organ 't, due to any planned activities during the next 31-day period

[mrem). 2.5.1 DtC = the cumulative dose to the total body or organ 't, for liquid releases that have occurred in the elapsed portion of the current quarter, plus the release under consideration [mrem). 2.5.1 Dtp = the projected dose to the total body or organ 't, for the next 31 days of liquid releases [mrem). 2.5.1 DFit = the dose conversion factor for radionuclide i for adults, in organ 't

[mremJpCij. Values are listed in Table 2-7. 2.4.2 ECL; = the liquid Effluent Concentration Umit for radionuclide i from 10 CFR Part 20. Appendix B, Table 2, Column 2 (J.tCilmL). 2.3.2.2 f= the effluent f10wrate at the location of the radioactivity monitor

[gpm). 2.3.2.1 f ap = the anticipated actual discharge f10wrate for a planned release from liquid release pathway p [gpm). 2.3.2.2 2-39 Rev. 18

VEGPODCM Section of Term Definition Initial Use fl = the fraction of the year that garden vegetation is irrigated [unitless). 2.4.3 fmp = the maximum permissible effluent discharge f10wrate for release pathway p [gpm). 2.3.2.2 fr = the effluent discharge f10wrate of release pathway r [gpm). 2.3.2.2 ft = the average undiluted liquid waste f10wrate actually observed during the period of a liquid release [gpm). 2.4.1 F= the dilution stream f10wrate which can be assured prior to the release point to the UNRESTRICTED AREA [gpm). 2.3.2.1 Fd = the entire assured dilution f10wrate for the plant site dUring the release period [gpm). 2.3.2.2 Fdp = the dilution f10wrate allocated to release pathway p [gpm). 2.3.2.2 F,= the near-field average dilution factor in the receiving water of the UNRESTRICTED AREA [unitless). 2.4.1 Ft = the average dilution stream f10wrate actually observed during the period of a liquid release [gpm). 2.4.1 1= the average irrigation rate during the growing season [U(m2

h>>. 2.4.3 Lv= the water content of leafy garden vegetation edible parts [Ukg). 2.4.3 M= the additional river dilution factor from the near field of the discharge structure for the plant site to the point of irrigation water usage [unitless). 2.4.3 P= the effective surface density of soil [kglm1. 2.4.3 r= the fraction of irrigation-deposited activity retained on the edible portions of leafy garden vegetation. 2.4.3 RDF= . the required dilution factor: the minimum ratio by which liquid effluent must be diluted before reaching the UNRESTRICTED AREA, in order to ensure that the limits of Section 2.1.2 are not exceeded [unitless). 2.3.2.2 RDFy = the RDF for a liquid release due only to its concentration of gamma-emitting radionuclides [unitless). 2.3.2.2 2-40 Rev. 18

VEGPODCM Section of Term Definition Initial Use RDFny = the RDF for a liquid release due only to its concentration of non-gamma-emitting radionuclides [unitless]. 2.3.2.2 SF= the safety factor selected to compensate for statistical fluctuations and errors of measurement [unitless]. 2.3.2.2 t= the number of whole or partial days elapsed into the current quarter, including the time to the end of the release under consideration. 2.5.1

~= the period of long-term bUildup of activity in soil [h]. 2.4.3 te= the period of leafy garden vegetation exposure during the growing season [h]. 2.4.3 tf = the transit time from release to receptor for fish consumption [h]. 2.4.2

~= the time between harvest of garden vegetation and human consumption [h]. 2.4.3 tw= the transit time from release to receptor for potable water consumption [h]. 2.4.2 TF= the tolerance factor selected to allow flexibility in the establishment of a practical monitor setpoint which could accommodate effluent releases at concentrations higher than the ECl values stated in 10 CFR 20, Appendix B, Table 2, Column 2

[unitless); the tolerance factor must not exceed a value of 10. 2.3.2.1 Uf = the adult rate of fish consumption [kgly]. 2.4.2 Uv = the adult consumption rate for irrigated garden vegetation [kgly]. 2.4.2 Uw = the adult drinking water consumption rate applicable to the plant site [Uy]. 2.4.2 yv= the areal density (agricultural productivity) of leafy garden 2

vegetation [kglm ]. 2.4.3 Z= the applicable dilution factor for the receiving water body, in the near field of the discharge structure, during the period of radioactivity release [unitless]. 2.4.1

~t1 = the length of time period 1, over Which Ci1 and F1are averaged for liquid releases [h]. 2.4.1 2-41 Rev. 18

VEGPODCM Section of Definition Initial Use

= the effective removal rate for activity deposited on crop leaves A.Ei

[h-1]. 2.4.3 the decay constant for radionuclide i [h-1

].

2.4.2

~=

the rate constant for removal of activity from plant leaves by

"""= 1 weathering [h- ]. 2.4.3 2-42 Rev. 18

VEGPODCM CHAPTER 3 GASEOUS EFFLUENTS 3.1 LIMITS OF OPERATION The following Limits of Operation implement requirements established by Technical Specifications Section 5.0. Terms printed in all capital letters are defined in Chapter 10.

3.1.1 Gaseous Effluent Monitoring Instrumentation Control In accordance with Technical Specification 5.5.4.a, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Section 3.1.2.a are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Section 3.3.

3.1.1.1 Applicability These limits apply as shown in Table 3-1.

3.1.1.2 Actions With a radioactive gaseous effluent monitoring instrumentation channel alarmltrip setpoint less conservative than required by the above control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, declare the channel inoperable, or restore the setpoint to a value that will ensure that the limits of Section 3.1.2.a are met.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3-1. Restore the inoperable instrumentation to operable status within 30 days, or if unsuccessful, explain in the next Radioactive Effluent Release Report, per Technical Specification 5.6.3, why this inoperability was not corrected in a timely manner.

This control does not affect shutdown requirements or MODE changes.

3.1.1.3 Surveillance Requirements Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 3-2.

3-1 Rev. 18

~. -~_. ~---------.

VEGPODCM 3.1.1.4 Basis 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 AlarmfTrip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Section 3.3 to ensure that the alarm/trip will occur prior to exceeding the limits of Section 3.1.2.a. 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 Part 50.

3-2 Rev. 18

VEGPODCM Table 3-1. Radioactive Gaseous Effluent Monitoring Instrumentation OPERABILITY Requirements Minimum Instrument Channels OPERABLE Applicability ACTION

1. GASEOUS RADWASTE TREATMENT SYSTEM (Common)

a. Noble Gas Activity Monitor, with Alarm and Automatic Termination of Release (ARE-0014) 1 During releases* 45

b. Effluent System Flowrate Measuring Device (AFT-0014) 1 During releases* 46

2. Turbine Building Vent (Each Unit)

a. Noble Gas Activity Monitor (RE-12839C) 1 During releases* 47

b. Iodine and Particulate Samplers (RE-12839A & B) 1 During releases* 51

c. Flowrate Monitor (FT-12839 or FIS-12862)b 1 During releases* 46

d. Sampler Flowrate Monitor (FI-13211) 1 During releases* 46

3. Plant Vent (Each Unit)

a. Noble Gas Activity Monitor (RE-12442C or RE-12444C) 1 At all times 47,48

b. Iodine Sampler/Monitor (RE-12442B or RE-12444B) 1 At all times 51

c. Particulate Sampler/Monitor (RE-12442A or RE-12444A) 1 At all times 51

d. Flowrate Monitor (FT-12442 or 12835) 1 At all times 46

e. Sampler Flowrate Monitor (FI-12442 or FI-12444) 1 At all times 46

4. Radwaste Processing Facility Vent (Common)

a. Particulate Monitor (ARE-16980) 1 During Releases* 51

a. "During releases" means "During radioactive releases via this pathway."

b. During emergency filtration.

3-3 Rev. 19

VEGPODCM Table 3-1 (contd). Notation for Table 3 ACTION Statements ACTION 45 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s} may be released to the environment for up to 14 days 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 discharge line valving, and verify the release rate calculations.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 46 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the f10wrate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 47 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 48 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend containment purging of radioactive effluents via this pathway.

ACTION 49 - (Not Used)

ACTION 50 - (Not Used)

ACTION 51 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment.

3-4 Rev. 18

VEGPODCM Table 3-2. Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Surveillance Requirements CHANNEL CHANNEL OPERA-Instrument CHANNEL SOURCE CALIBRA- TIONAL c

CHECK CHECK TION TEST MODES

1. GASEOUS RADWASTE TREATMENT SYSTEM (Common)

a. Noble Gas Activity Monitor, with Alarm and Automatic Termination of Release During (ARE-0014) P P Rb Ra(1) Release

b. Effluent System Flowrate Measuring Device During (AFT-0014) P NA R NA Release

2. Turbine Building Vent (Each Unit)

a. Noble Gas Activity Monitor During (RE-12839C) D M R b Ra(2) Release

b. Iodine and Particulate During Samplers (RE-12839A&B) Wd NA NA NA Release

c. Flowrate Monitor During (FT-12839 or FIS-12862) D NA R NA Release

d. Sampler Flowrate Monitor During (FI-13211) D NA R Q Release

3. Plant Vent (Each Unit)

a. Noble Gas Activity Monitor (RE-12442C or RE-12444C) D M Rb Ra(2) All

b. Particulate and Iodine Monitors (RE-12442A&B) Wd NA R Ra(2) All

c. Particulate and Iodine Samplers (RE-12444A&B) Wd NA NA NA All

d. Flowrate Monitor (FT-12442 or 12835) D NA R NA All

e. Sampler Flowrate Monitor (FI-12442 or FI-12444) D NA R Q All

4. Radwaste Processing Facility Vent (Common)

a. Particulate Monitor During Wd Q R8 N/A (ARE-16980) Release 3-5 Rev. 21

VEGPODCM Table 3-2 (contd). Notation for Table 3-2

a. In addition to the basic functions of a CHANNEL OPERATIONAL TEST (Section 10.2):

(1) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs (for item a. below only); and control room CRT indication occurs (if any of the following conditions exist):

(a) Instrument indicates measured levels above the alarmJtrip setpoint; (b) Instrument indicates an "Equipment Trouble" alarm; (c) Instrument indicates a "Low" alarm; or (d) Instrument indicates channel "Deactivated."

(2) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room annunciation occurs (for item a. below only); and that control room CRT indication occurs (if any of the following conditions exist):

(a) Instrument indicates measured levels above the alarm/trip setpoint; (b) Instrument indicates an "Equipment Trouble" alarm; (c) Instrument indicates a "Low" alarm; or (d) Instrument indicates channel "Deactivated." ("Loss of counts" for ARE-16980 only)

b. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology, 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 any subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

c. MODES in which surveillance is required. "All" means "At all times." "During release" means "During radioactive release via this pathway."

d. The channel check shall consist of visually verifying that the collection device (Le.,

partiCUlate filter or charcoal cartridge, etc.) is in place for sampling.

e. The CHANNEL CALIBRATION verifies proper operation of the CHANNEL OPERATIONAL TEST requirements described in Notation a(2) above.

3-6 Rev. 19

VEGPODCM 3.1.2 Gaseous Effluent Dose Rate Control In accordance with Technical Specifications 5.5.4.c and 5.5.4.g, the licensee shall conduct operations so that the dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY are limited as follows:

a. For noble gases: Less than or equal to a dose rate of 500 mremly to the total body and less than or equal to a dose rate of 3000 mremly to the skin, and

b. For lodine-131, lodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem/y to any organ.

3.1.2.1 Applicability This limit applies at all times.

3.1.2.2 Actions With a dose rate due to radioactive material released in gaseous effluents exceeding the limit stated in Section 3.1.2, immediately decrease the release rate to within the stated limit.

These limits do not affect shutdown requirements or MODE changes.

3.1.2.3 Surveillance Requirements The dose rates due to radioactive materials in areas at or beyond the SITE BOUNDARY due to releases of gaseous effluents shall be determined to be within the above limits, in accordance with the methods and procedures in Section 3.4.1, by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-3.

3.1.2.4 Basis This control is provided to ensure that gaseous effluent dose rates will be maintained within the limits that historically have provided reasonable assurance that radioactive material discharged in gaseous effluents will not result in a dose to a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, eXceeding the limits specified in Appendix I of 10 CFR Part 50, while allowing operational flexibility for effluent releases. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

The dose rate limit for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days specifically applies to dose rates to a child via the inhalation pathway.

This control applies to the release of gaseous effluents from all reactors at the site.

3-7 Rev. 18

VEGPODCM Table 3-3. Radioactive Gaseous Waste Sampling and Analysis Program 8

Sampling and Analysis Requirements MINIMUM DETECTABLE Minimum CONCENTRA-Gaseous Sampling Analysis Type of Activity TION (MDC)

Release Type FREQUENCY FREQUENCY Analysis (J1CilmL)

Waste Gas P P Noble Gas 1 E-4 Decay Tank Each Tank Grab Each Tank PRINCIPAL (Common) Sample GAMMA EMITTERS pC Noble Gas 1 E-4 Containment pc Each Purge PRINCIPAL Purge Each Purge GAMMA EMITTERS 24" or 14" (Each Unit) Grab Sample M H-3 (Oxide) 1 E-6 Noble Gas 1 E-4 MC,d,f PRINCIPAL MC Plant Vent (Each Unit) Grab Sample GAMMA EMITTERS H-3 (Oxide) 1 E-6 Noble Gas 1 E-4 Condenser Air PRINCIPAL Ejector & M GAMMA EMITTERS Steam Packing Grab Sample M Exhaust (Each Unit)b H-3 (Oxide) 1 E-6 We 1-131 1 E-12 CONTINUOUSg Charcoal or Silver Zeolite Sample We Particulate 1 E-11 CONTINUOUSg Particulate PRINCIPAL Sample GAMMA EMITTERS Plant Vent, M Gross Alpha 1 E-11 Condenser Air COMPOSITE Ejector & CONTINUOUSg Particulate Steam Packing Sample Exhaust ~Each Unit)

Q Sr-89. Sr-90 1 E-11 CONTINUOUSg COMPOSITE Particulate Sample Radwaste Wh Particulate 1 E-11 Processing CONTINUOUSg Particulate PRINCIPAL Facility Vent Sample GAMMA EMITTERS (Common) 3-8 Rev. 19

- - *--'----*-"--*,-------------------*-... ,-,-,--~-----IIIIII VEGPODCM Table 3-3 (contd). Notation for Table 3-3

a. Terms printed in all capital letters are defined in Chapter 10.

b. The turbine building vent is the release point for the condenser air ejector and steam packing exhaust. All sampling and analyses may be omitted for this vent, provided the absence of a primary to secondary leak has been demonstrated, that is, if the gamma activity in the secondary water does not exceed background by more than 20%.

c. Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a one-hour period. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

d. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling cavity is flooded.

e. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in one hour, and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding MDC may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

f. Tritium grab samples shall be taken at least once per 7 days from the Unit 1 plant vent, whenever spent fuel is in the spent fuel pool (Unit 1 plant vent only).

g. The ratio of the sample flowrate to the sampled stream flowrate shall be known for the time period covered by each dose or dose rate calculation made in accordance with controls specified in Sections 3.1.2, 3.1.3, and 3.1.4.

h. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or removal of sampler).

3-9 Rev. 19

~._-_. .~--_.- ~-----------_._-------

VEGPODCM 3.1.3 Gaseous Effluent Air Dose Control In accordance with Technical Specifications 5.5.4.e and 5.5.4.h, the air dose due to noble gases released in gaseous effluents, from each reactor 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 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.

3.1.3.1 Applicability This limit applies at all times.

3.1.3.2 Actions With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Nuclear Regulatory Commission within 30 days a special report which identifies the cause(s) for exceeding the Iimit(s); defines the corrective actions that have been taken to reduce the releases; and defines the proposed corrective actions to be taken to assure that subsequent releases of radioactive noble gases in gaseous effluents will be in compliance with the limits of Section 3.1.3.

This control does not affect shutdown requirements or MODE changes.

3.1.3.3 Surveillance Requirements Cumulative air dose contributions from noble gas radionuclides released in gaseous effluents from each unit to areas at and beyond the SITE BOUNDARY, for the current calendar quarter and current calendar year, shall be determined in accordance with Section 3.4.2 at least once per 31 days.

3.1.3.4 Basis This control is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix 1,10 CFR Part 50. Section 3.1.3 implements the guides set forth in Section II.B of Appendix I.

The ACTION statements in Section 3.1.3.2 provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I, assuring that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance requirements in Section 3.1.3.3 implement the requirements in Section III.A of Appendix I, which require 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 dose calculations established in Section 3.4.2 for calculating the doses due to the actual releases of noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109 (Reference 3), and Regulatory Guide 1.111 (Reference 5). The equations in Section 3.4.2 provided for determining the air doses at the SITE BOUNDARY are based upon the historical annual average atmospheric conditions.

3-10 Rev. 18

VEGPODCM 3.1.4 Control on Gaseous Effluent Dose to a Member of the Public In accordance with Technical Specifications 5.5.4.e and 5.5.4.i, the dose to a MEMBER OF THE PUBLIC from 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor 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 mrem to any organ, and

b. During any calendar year: less than or equal to 15 mrem to any organ.

3.1.4.1 Applicability This limit applies at all times.

3.1.4.2 Actions With the calculated dose from the release of 1-131,1-133, tritium, or 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 Nuclear Regulatory Commission within 30 days a special report which identifies the cause(s} for exceeding the limit; defines the corrective actions that have been taken to reduce the releases of radioiodines and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents; and defines proposed corrective actions to assure that subsequent releases will be in compliance with the limits stated in Section 3.1.4.

This control does not affect shutdown requirements or MODE changes.

3.1.4.3 Surveillance Requirements Cumulative organ dose contributions to a MEMBER OF THE PUBLIC from 1-131, 1-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents from each unit to areas at and beyond the SITE BOUNDARY, for the current calendar quarter and current calendar year, shall be determined in accordance with Section 3.4.3 at least once per 31 days.

3.1.4.4 Basis This control is provided to implement the requirements of Section II.C,III.A and IV.A of Appendix I, 10 CFR Part 50. The limits stated in Section 3.1.4 are the guides set forth in Section II.C of Appendix I. The ACTION statements in Section 3.1.4.2 provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of 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 calculational methods specified in the Surveillance Requirements of Section 3.1.4.3 implement the requirements in Section III.A of 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 calculational methods in Section 3.4.3 for calculating the doses due to the actual releases of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109 (Reference 3), and Regulatory Guide 1.111 (Reference 5). These equations provide for determining the actual doses 3-11 Rev. 18

VEGPODCM based upon the historical annual average atmospheric conditions. The release specifications for radioiodines, radioactive materials in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways which were examined in the development of these calculations were:

1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy garden 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.

3.1.5 Gaseous Radwaste Treatment SYStem Control In accordance with Technical Specification 5.5.4.1, the GASEOUS WASTE PROCESSING SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEOUS WASTE PROCESSING SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous wastes prior to their discharge when the projected doses in 31 days due to gaseous effluent releases, from each reactor unit, to areas at and beyond the SITE BOUNDARY would exceed 0.2 mrad to air from gamma radiation, 0.4 mrad to air from beta radiation, or 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

3.1.5.1 Applicability These limits apply at all times.

3.1.5.2 Actions With gaseous waste being discharged without treatment and in excess of the limits in Section 3.1.5, prepare and submit to the Nuclear Regulatory Commission within 30 days a special report which includes the following information:

a. Identification of any inoperable equipment or subsystem and the reason for inoperability,

b. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

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

This control does not affect shutdown requirements or MODE changes.

3.1.5.3 Surveillance Requirements 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 Section 3.5.1, when the GASEOUS WASTE PROCESSING SYSTEM or the VENTILATION EXHAUST TREATMENT SYSTEM is not being fully utilized.

The GASEOUS WASTE PROCESSING SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE:

3-12 Rev. 18

VEGPODCM by meeting the controls of Sections 3.1.2, and either 3.1.3 (for the GASEOUS WASTE PROCESSING SYSTEM) or 3.1.4 (for the VENTILATION EXHAUST TREATMENT SYSTEM).

3.1.5.4 Basis The OPERABILITY of the GASEOUS WASTE PROCESSING SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system 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 Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in section 11.0 of Appendix I to 10 CFR Part SO. The specified limits governing the use of appropriate portions of the system were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

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.

3.1.6 Major Changes to Gaseous Radioactive Waste Treatment Systems Licensee initiated MAJOR CHANGES TO GASEOUS RADIOACTIVE WASTE TREATMENT SYSTEMS:

a. Shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluents Release Report for the period in which the change was implemented. The discussion of each change shall contain the information described in Section 7.2.2.7.

b. Shall become effective. upon review and approval by the General Manager - Nuclear Plant.

3-13 Rev. 18

VEGPODCM 3.2 GASEOUS WASTE PROCESSING SYSTEM At Plant Vogtle, there are six potential points where radioactivity may be released to the atmosphere in gaseous discharges. These six potential release pathways are the Unit 1 and Unit 2 Plant Vents; the Unit 1 and Unit 2 Turbine Building Vents; the Radwaste Processing Facility Vent; and the Dry Active Waste Processing Building Vent. However, the Turbine Building Vents are not normal release pathways unless a primary-ta-secondary leak exists. The Radwaste Processing Facility Vent is not a normal release pathway unless a spill occurs. The figures on the following pages give schematic diagrams of the Gaseous Waste Treatment System and the Ventilation Exhaust Treatment Systems (Reference 11).

The Unit 1 Plant Vent release pathway includes two release sources that are common to the two units: ventilation air from the Fuel Handling Building, and discharges from the GASEOUS WASTE PROCESSING SYSTEM. Otherwise, discharges from the two reactor units are separated. Reactor Containment Building ventilation releases are through the respective plant vents. The Turbine Building Vent serves as the discharge point for both the condenser air ejector and the steam packing exhauster system. The Radwaste Processing Facility Vent includes sources from the Radwaste Processing Facility Process area.

Releases from the two Turbine Building Vents, the Radwaste Processing Facility Vent, and the Dry Active Waste Processing Building Vent are considered to be ground-level releases, whereas releases from the two Plant Vents are considered mixed-mode releases. Chapter 8 discusses the calculation of atmospheric dispersion parameters using the ground-level and mixed-mode (i.e.,

split-wake) models. All six potential release pathways are considered to be continuous (as opposed to batch) in nature.

3-14 Rev. 19

VEGPODCM Radioactivity Monitor......... ~

.--.t--- via ARE-Q014 ~ -. To Unit 1 Plant Vent Auxiliary Building Ventilation System 1-".__

Catalytic Recombiner and Waste Gas Compressor Gas Analyzer Package To Chemical Volume I Control Tank I

I I I I 1-".-- To Waste Gas Decay Tank Header I------J}---~

Waste Gas Decay Tank Waste Gas Decay Tank (Shutdown)

(Seven per Unit)

(Two Shared)

Volume Control Tank Purge Recycle Evaporator Vent Condenser Waste Evaporator Vent Condenser Recycle Holdup Tank Eductor Reector Coolant Drain Tank "Dotted line operational between 20 and 100 psig NOTE: This is typical of both units. However. Unit 2 GWPS releases via Unit 1 plant vent.

Figure 3-1. Schematic Diagram of the Gaseous Radwaste Treatment System 3-15 Rev. 18

VEGPODCM Plant Vent Radioactivity Monitor 1RE12442A,B,C

+

HEPA HEPA HEPA CF CF CF HEPA HEPA HEPA HC HC Radioactivity Monitor REOO39A ME ME Auxiliary Building Radioactivity Monitor 1RE2565A,B,C Fuel Handli ng Building (Shared)*

Radioactivity Monitor Reactor Containment ARE-0014 Building From Waste Gas Processing Area and System HEPA - High-Efficiency Particulate Air Filter CF - Activated Charcoal Filter HC - Heating Coil ME - Moisture Eliminator

Prior to treatment by the Fuel Handling Building Ventilation Exhaust Treatment System, Exhaust from Unit 1 Spent Fuel Pool Area is monitored by ARE2532B and ARE2533B; exhaust from Unit 2 Spent Fuel Pool Area is monitored by ARE2532A and ARE2533A.

Figure 3*2. Schematic Diagram of the Unit 1 Plant Vent Release Pathway 3-16 Rev. 18

VEGPODCM Plant Vent Radioactivity Monitor 2 RE12442A,B,C I

liL HEPA HEPA I

CF CF I

HEPA HEPA I HC Auxiliary Building ME Radioactivity Monitor 2RE2565A,B,C Reactor Containment Building HEPA - High-Efficiency Particulate Air Filter CF - Activated Charcoal Filter HC - Heating Coil ME - Moisture Eliminator Figure 3-3. Schematic Diagram of the Unit 2 Plant Vent Release Pathway 3-17 Rev. 18

VEGPODCM Turbine Building Vent

+ ...

~ 9 Radioactivity Monitor 1(2)RE12839A,B,C

~

HEPA HEPA CF CF HEPA HEPA HC HC DE DE

~

- .... - ~ '--

- NO

- ~ NC _NO

- NC Steam Jet Air Ejector Steam Packing Exhauster HEPA - High-Efficiency Particulate Air Filter CF - Activated Charcoal Filter HC - Heating Coil DE - Demister NO - Normally Open NC - Normally Closed NOTE: This is typical of both units.

Figure 3-4. Schematic Diagram of the Turbine Building Vent Release Pathway (Typical of Both Units) 3-18 Rev. 18

VEGPODCM

?

Dry Active Waste Processing Building Vent Radioaclivily Monitor ARE 13256 HEPA HEPA Rooms Trash Compactor Figure 3-5. Schematic Diagram of the Dry Active Waste Processing Building Ventilation Release Pathway 3-19 Rev. 18

VEGPODCM

........... * .FIlCilltyV. .

BllPA 1lIIlI.... PJlII QI ' . FecIIity ~ AIa- ..... IOI Figure 3-6. Schematic Diagram of the Radwaste Processing Facility Ventilation Release Pathway 3-19a Rev. 19

VEGP ODCM 3.3 GASEOUS EFFLUENT MONITOR SETPOINTS 3.3.1 General Provisions Regarding Noble Gas Monitor Setooints Noble gas radioactivity monitor setpoints calculated in accordance with the methodology presented in this section are intended to ensure that the limits of Section 3.1.2.a are not exceeded. They will be regarded as upper bounds for the actual high alann setpoints. That is, a lower high alann setpoint may be established or retained on the monitor, if desired. Intennediate level setpoints should be established at an appropriate level to give sufficient warning prior to reaching the high alann setpoint.

If no release is planned for a given pathway, or if there is no detectable activity in the gaseous stream being evaluated for release, the setpoint should be calculated in accordance with the methods presented below, based on an assumed concentration of Kr-88 that leads to a practical setpoint. A practical setpoint in this context is one which prevents spurious alanns, and yet produces an alann should a significant inadvertent release occur.

Section 3.1.1 establishes the requirements for gaseous effluent monitoring instrumentation, and Section 3.2 describes the VENTILATION EXHAUST TREATMENT SYSTEM and the GASEOUS WASTE PROCESSING SYSTEM. From those Sections, it can be seen that certain monitors are located on final release pathways, that is, streams that are being monitored immediately before being discharged from the plant; the setpoint methodology for these monitors is presented in Section 3.3.2. Other monitors are located on source streams, that is, streams that merge with other streams prior to passing a final monitor and being discharged; the setpoint methodology for these monitors is presented in Section 3.3.3. Table 3-4 identifies which of these setpoint methodologies applies to each monitor. Some additional monitors with special setpoint requirements are discussed in Section 3.3.5.

As established in Section 3.1.1 , gaseous effluent monitor setpoints are required only for the noble gas monitors on certain potential release streams: the two Plant Vents, the two Turbine Building Vents, and the GASEOUS WASTE PROCESSING SYSTEM discharge. However, because of the potential significance of releases from other sources, Section 3.3 discusses setpoint methodologies for certain additional monitors, as well.

3-20 Rev. 18

VEGPODCM Table 3-4. Applicability of Gaseous Monitor Setpoint Methodologies Final Release Pathways with no Monitored Source Streams Setpoint Method: Section 3.3.2 Release Elevation: Ground-level Unit 1 or Unit 2 Turbine Building Vent Monitor: 1RE-12839C/2RE-12839C Maximum Flowrate: 900 cfm (4.25 E+05 mUs)

Dry Active Waste Building Vent Monitor: ARE-13256 Maximum Flowrate: 2,200 cfm (1.04 E+06 mUs)

Final Release Pathways with One or More Monitored Source Streams Release Elevation: Mixed-Mode Unit 1 Plant Vent Monitors: 1RE-12442C,1RE-12444C Maximum Flowrate: 187,000 cfm (8.83 E+07 mUs)

Setpoint Method: Section 3.3.2 Release Type: CONTINUOUS Source Stream: Unit 1 Reactor Containment Purge Monitor: 1RE-2565C Maximum Flowrate: release-dependent Setpoint Method: Section 3.3.3 Release Type: BATCH Source Stream: Gaseous Waste Treatment SYStem Monitor: ARE-0014 Maximum Flowrate: release-dependent Setpoint Method: Section 3.3.3 Release Type: BATCH Unit 2 Plant Vent Monitors: 2RE-12442C,2RE-12444C Maximum Flowrate: 112,500 cfm (5.31 E+07 mUs)

Setpoint Method: Section 3.3.2 Release Type: CONTINUOUS Source Stream: Unit 2 Reactor Containment Purge Monitor: 2RE-2565C Maximum Flowrate: release-dependent Setpoint Method: Section 3.3.3 Release Type: . BATCH (XlQ)vb Values for Use in Setpolnt Calculations Ground-Level Releases: 2.55 x 1O~ s/m 3 [NE Sector]

Mixed-Mode Releases: 4.62 x 10-7 s/m 3 [NE Sector]

Maximum flowrate values are from Reference 11, Table 11.5.2-1 and Table 11.5.5-1.

3-21 Rev. 18

VEGPODCM 3.3.2 Setooint for the Final Noble Gas Monitor on Each Release Pathway 3.3.2.1 Overview of Method Gaseous effluent radioactivity monitors are intended to alarm prior to exceeding the limits of Section 3.1.2.a. Therefore, their alarm setpoints are established to ensure compliance with the following equation:

AG.SF.X.Rt c=the lesser of{ AG.SF.X . Ric (3.1) where:

c = the setpoint, in JlCilmL, of the radioactivity monitor measuring the concen-tration of radioactivity in the effluent line prior to release. The setpoint represents a concentration which, if exceeded, could result in dose rates exceeding the limits of Section 3.1.2.a at or beyond the SITE BOUNDARY.

AG = an administrative allocation factor applied to divide the release limit among all the gaseous release pathways at the site.

SF = the safety factor selected to compensate for statistical fluctuations and errors of measurement.

x = the noble gas concentration for the release under consideration.

Rt = the ratio of the dose rate limit for the total body, 500 mremly, to the dose rate to the total body for the conditions of the release under consideration.

= the ratio of the dose rate limit for the skin, 3000 mremly, to the dose rate to the skin for the conditions of the release under consideration.

Equation (3.1) shows the relationships of the critical parameters that determine the setpoint.

However, in order to apply the methodology presented in the equation to a mixture of noble gas radionuclides, radionuclide-specific concentrations and dose factors must be taken into account under conditions of maximum f10wrate for the release point and annual average meteorology.

The basic setpoint method presented below is applicable to the radioactivity monitor nearest the point of release for the release pathway. For monitors measuring the radioactivity in source streams that merge with other streams prior to subsequent monitoring and release, the modifications presented in Section 3.3.3 must be applied.

3.3.2.2 Setpoint Calculation Steps Step 1: Determine the concentration, Xnt, of each noble gas radionuclide i in the gaseous stream v being considered for release, in accordance with the sampling and analysis requirements of Section 3.1.2. Then sum these concentrations to determine the total noble gas concentration, D<w.

I 3-22 Rev. 18

VEGPODCM Step 2: Determine Rio the ratio of the dose rate limit for the total body, 500 mrernly, to the total body dose rate due to noble gases detected in the release under consideration, as follows:

Rt = 500 (3.2)

(X / Q) vb L [x; . Q,.]

i where:

500 = the dose rate limit for the total body, 500 mrernly.

(XlO)vb = the highest annual average relative concentration at the SITE BOUNDARY for the discharge point of release pathway v. Table 3-4 includes an indication of what release elevation is applicable to each release pathway; release elevation determines the appropriate value of (XlOlvb

~ = the total-body dose factor due to gamma emissions from noble gas radio-nuclide i, in (mremly)/(~Cilm3), from Table 3-5.

Oiv = the release rate of noble gas radionuclide i from the release pathway under consideration, in ~Cils, calculated as the product of Xw and fav , where:

= the concentration of noble gas radionuclide i for the particular release, in ~CilmL.

fav = the maximum anticipated f10wrate for release pathway v during the period of the release under consideration, in mUs.

Step 3: Determine ~, the ratio of the dose rate limit for the skin, 3000 mremly, to the skin dose rate due to noble gases detected in the release under consideration, as follows:

Rk = 3000 (3.3)

(XlQ)vb I,[(L; + 1.1M;)* Qiv]

where:

3000 = the dose rate limit for the skin, 3000 mremly.

~ = the skin dose factor due to beta emissions from noble gas radionuclide i, in (mrem/y)/(~Cilm3), from Table 3-5.

M = the air dose factor due to gamma emissions from noble gas radionuclide i, in (mrad/y)/(~Cilm3), from Table 3-5.

1.1 = the factor to convert air dose in mrad to skin dose in mrem.

All other terms were defined previously.

3-23 Rev. 18

VEGPODCM Step 4: Determine the maximum noble gas radioactivity monitor setpoint concentration.

Based on the values determined in previous steps, the radioactivity monitor setpoint for the planned release is calculated to ensure that the limits of Section 3.1.2.a will not be exceeded.

Because the radioactivity monitor responds primarily to radiation from noble gas radionuclides, the monitor setpoint Cnv (in JlCilmL) is based on the concentration of all noble gases in the waste stream, as follows:

where:

Cnv = the calculated setpoint, in JlCilmL, for the noble gas monitor serving gaseous release pathway v.

AGV *SF* LXiv *R, C nv =the lesser of i (3.4)

{

AGv .SF*Lxiv *Rk AGy = the administrative allocation factor for gaseous release pathway v, applied to divide the release limit among all the gaseous release pathways at the site.

The allocation factor may be assigned any value between 0 and 1, under the condition that the sum of the allocation factors for all simultaneously-active final release pathways at the entire plant site does not exceed 1. A1temative methods for determination of AGv are presented in Section 3.3.4.

SF = the safety factor selected to compensate for statistical fluctuations and errors of measurement. The value for the safety factor must be between 0 and 1.

A value of 0.5 is reasonable for gaseous releases; a more precise value may be developed if desired.

Xv = the measured concentration of noble gas radionudide i in gaseous stream v, as defined in Step 1, in JlCilmL.

The values of Rt and ~ to be used in the calculation are those which were determined in Steps 2 and 3 above.

Step 5: Determine whether the release is permissible, as follows:

If Cnv ~ D<n" the release is permissible. However, if Cnv is within about 10 percent of D<n" it I I may be impractical to use this value of Cnv. This situation indicates that measured concentrations are approaching values which would cause the limits of section 3.1.2.a to be exceeded. Therefore, steps should be taken to reduce contributing source terms of gaseous radioactive material, or to adjust the allocation of the limits among the active release points. The setpoint calculations (steps 1-4) must then be repeated with parameters that reflect the modified conditions.

3-24 Rev. 18

VEGPODCM If em < IXiv' the release may not be made as planned. Consider the alternatives I

discussed in the paragraph above, and calculate a new setpoint based on the results of the actions taken.

3.3.2.3 Use of the Calculated Setpoint The setpoint calculated above is in the units ~CilmL. The monitor actually measures a count rate, subtracts a predetermined background count rate, and multiplies by a calibration factor to convert from count rate to ~CilmL.

Initial calibration by the manufacturer and Georgia Power Company of the gaseous effluent monitors specified in Section 3.1.1 utilized at least one NIST-traceable gaseous radionuclide source in the exact geometry of each production monitor. The point and gaseous sources used covered the beta particle end point energy range from 0.293 MeV to at least 1.488 MeV. The calibration factor is a function of the radionuclide mix in the gas to be released, and normally will be calculated for the monitor based on the results of the sample results from the laboratory gamma-ray spectrometer system. The mix-dependent calibration factor will be used as the gain factor in the PERMS monitor, or used to modify the calculated base monitor setpoint so that the default calibration factor in the PERMS monitor can be left unchanged.

Notwithstanding the initial calibration, monitor calibration data for conversion between count rate and concentration may include operational data obtained from determining the monitor response to stream concentrations measured by sample analysis.

In all cases, monitor background must be controlled so that the monitor is capable of responding to concentrations in the range of the setpoint value. Contributions to the monitor background may include any or all of the following factors: ambient background radiation, plant-related radiation levels at the monitor location (which may change between shutdown and power conditions), and internal background due to contamination of the monitor's sample chamber.

3.3.3 Setooints for Noble Gas Monitors on Effluent Source Streams Table 3-4 lists certain gaseous release pathways as being source streams. As may be seen in the figures of Section 3.2, these are streams that merge with other streams, prior to passing a final radioactivity monitor and being released. Unlike the final monitors, the source stream monitors measure radioactivity in effluent streams for which flow can be terminated; therefore, the source stream monitors have control logic to terminate the source stream release at the alarm setpoint.

3.3.3.1 Setpoint of the Monitor on the Source Stream Step 1: Determine the concentration Xe of each noble gas radionuclide i in source stream s (in ~CilmL) according to the results of its required sample analyses [see Section 3.1.2].

Step 2: Determine rb the ratio of the dose rate limit for the total body, 500 mrernly, to the total body dose rate due to noble gases detected in the source stream under consideration. Use the Xe values and the maximum anticipated source stream 3-25 Rev. 18

VEGPODCM flowrate f as in equation (3.2) to determine the total body dose rate for the source stream, substituting rt for Rt.

The SITE BOUNDARY relative dispersion value used in Steps 2 and 3 for the source stream is the same as the (XlQ)vb that applies to the respective merged stream. This is because the (XlQ) value is determined by the meteorology of the plant site and the physical attributes of the release point, and is unaffected by whether or not a given source stream is operating.

Step 3: Determine rk, the ratio of the dose rate limit for the skin, 3000 mremly, to the skin dose rate due to noble gases detected in the source stream under consideration.

Use the X. values and the maximum anticipated source stream flow rate f as in equation (3.3) to determine the skin dose rate for the source stream, substituting rk for~.

Step 4: Determine the maximum noble gas radioactivity monitor setpoint concentration, as follows:

ens = the lesser (3.5) where:

Cns = the calculated setpoint (in J1CilmL) for the noble gas monitor serving gaseous source stream s.

AG s = the administrative allocation factor applied to gaseous source stream s. For a given final release point v, the sum of all the AG. values for source streams contributing to the final release point must not exceed the release point's allOcation factor Agy

Xis = the measured concentration of noble gas radionuclide i in gaseous source stream s, as defined in Step 1, in J1CilmL.

The values of rt and rk to be used in the calculation are those which were determined in Steps 2 and 3 above. The safety factor, SF, was defined previously.

Step 5: Determine whether the release is permissible, as follows:

If Cns ~ Ix., the release is permissible. However, if Cns is within about 10 percent of Ix., it I I may be impractical to use this value of Cns. This situation indicates that measured concentrations are approaching values which would cause the limits of Section 3.1.2.a to be exceeded. Therefore, steps should be taken to reduce contributing source terms of gaseous radioactive material, or to adjust the allocation of the limits among the active release points. The setpoint calculations (steps 1-4) must then be repeated with parameters that reflect the modified conditions.

3-26 Rev. 18

VEGPODCM If Cos < IXs, the release may not be made as planned. Consider the altematives I

discussed in the paragraph above, and calculate a new setpoint based on the results of the actions taken.

3.3.3.2 Effect on the Setpoint of the Monitor on the Merged Stream Before beginning a release from a monitored source stream, a setpoint must be determined for the source stream monitor as presented in Section 3.3.3.1. In addition, whether or not the source stream has its own effluent monitor, the previously-determined maximum allowable s~tpoint for the downstream final monitor on the merged stream must be redetermined. This is accomplished by repeating the steps of Section 3.3.2, with the following modifICations.

Modification 1: The new maximum anticipated fIowrate of the merged stream is the sum of the old merged stream maximum flowrate, and the maximum flowrate of the source stream being considered for release.

(3.6)

Modification 2: The new concentration of noble gas radionuclide i in the merged stream includes both the contribution of the merged stream without the source stream, and the source stream being considered for release.

(X.) = (fav )old .(Xiv)old + fas + Xis (3.7)

IV new (fav )new 3.3.4 Determination of Allocation Factors. AG When simultaneous gaseous releases are conducted, an administrative allocation factor must be applied to divide the release limit among the active gaseous release pathways. This is to assure that the dose rate limit for areas at and beyond the SITE BOUNDARY (see Section 3.1.2) will not be exceecled by simultaneous releases. The allocation factor for any pathway may be assigned any value between 0 and 1, under the following two conditions:

1. The sum of the allocation factors for all simultaneously-active final release paths at the plant site may not exceecl 1.

2. The sum of the allocation factors for all simultaneously-active source streams merging into a given final release pathway may not exceed the allocation factor of that final release pathway.

Any of the following three methods may be used to assign the allocation factors to the active gaseous release pathways:

1. For ease of implementation, AGy may be equal for all release pathways:

AG V

=~ N (3.8) 3-27 Rev. 18

~ .. ..

VEGPODCM where:

N = the number of simultaneously active gaseous release pathways.

2. AGy for a given release pathway may be selected based on an estimate of the portion of the total SITE BOUNDARY dose rate (from all simultaneous releases) that is contributed by the release pathway. During periods when a given building or release pathway is not subject to gaseous radioactive releases, it may be assigned an allocation factor of zero.

3. AG y for a given release pathway may be selected based on a calculation of the portion of the total SITE BOUNDARY dose rate that is contributed by the release pathway, as follows:

(x IQtb L(KjQiv)

AGv= j (3.9)

~[(XIQ).. ~(KIQ.)]

where:

(XlQ)vb = the annual average SITE BOUNDARY relative concentration applicable to the gaseous release pathway v for which the allocation factor is being determined, in 81m3 *

~ = the total-body dose factor due to gamma emissions from noble gas radio-nuclide i, in (mremly)/(IlCVm3), from Table 3-5.

Qiv = the release rate of noble gas radionucJide i from release pathway v, in IlCVS, calculated as the product of Xw and fav, where:

= the concentration of noble gas radionucJicle i applicable to the gaseous release pathway v for which the allocation factor is being determined, in IlCVmL.

fav = the discharge fIowrate applicable to gaseous release pathway v for which the allocation factor is being determined, in mUs.

the annual average SITE BOUNDARY relative concentration applicable to active gaseous release pathway r, in 81m 3.

Qir = the release rate of noble gas radionucJide i applicable to active release pathway r, in IlCi/s, calculated as the product of)4 and far, where:

= the concentration of noble gas radionuclide i applicable to active gaseous release pathway r, in IlCVmL.

far = the discharge f10wrate applicable to active gaseous release pathway r, in mUs.

3-28 Rev. 18

--- - ._--_.~-----.....

VEGPODCM N = the number of simultaneously active gaseous release pathways (including pathway v that is of interest).

NOTE: Although equations (3.8) and (3.9) are written to illustrate the assignment of the allocation factors for final release pathways, they may also be used to assign allocation factors to the source streams that merge into a given final release pathway.

3.3.5 Setooints for Noble Gas Monitors with Special Requirements At present, VEGP has no noble gas monitors for which setpoint methodologies are to be presented in the ODCM, and that require methods other than those in Section 3.3.2 or Section 3.3.3.

3.3.6 Setooints for Particulate and Iodine Monitors In accordance with Section 5.1.1 of NRC NUREG-D133 (Reference 1), the effluent controls of Section 3.1.1 do not require that the aDCM establish setpoint calculation methods for particulate and iodine monitors. Therefore, the following is provided for information only: Initial setpoints for the particulate channels of effluent monitors RE-12442, RE-2565, and ARE-13256 were determined as described in Reference 13.

3-29 Rev. 18

VEGPODCM 3.4 GASEOUS EFFLUENT COMPLIANCE CALCULATIONS 3.4.1 Dose Rates at and Beyond the Site Boundary Because the dose rate limits for areas at and beyond the SITE specified in Section 3.1.2 are site limits applicable at any instant in time, the summations extend over all simultaneously active gaseous final release pathways at the plant site. Table 3-4 identifies the gaseous final release pathways at the plant site, and indicates the (XlO)vb value for each.

3.4.1.1 Dose Rates Due to Noble Gases For the purpose of implementing the controls of section 3.1.2.a, the dose rates due to noble gas radionuclides in areas at or beyond the SITE BOUNDARY, due to releases of gaseous effluents, shall be calculated as follows:

For total body dose rates:

DR, = ~{(XIQ),. ~[K&..]} (3.10)

For skin dose rates:

DR, = ~{(X IQ),. ~[(Li +l.lM i)Qi.J} (3.11) where:

DRt = the total body dose rate at the time of the release, in mremly.

D~ = the skin dose rate at the time of the release, in mremly.

Oiv = the release rate of noble gas radionuclide i, in J.lCils, equal to the product of fty and ~, where:

= the actual average f10wrate for release pathway v during the period of the release, in mUs.

All other terms were defined previously.

3.4.1.2 Dose Rates Due to lodine-131,lodine-133, Tritium, and Radionuclides in Particulate Form with Half-Lives Greater than 8 Days For the purpose of implementing the controls of Section 3.1.2.b, the dose rates due to lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in areas at or beyond the SITE BOUNDARY, due to releases of gaseous effluents, shall be calculated as follows:

(3.12) 3-30 Rev. 18

VEGPODCM where:

DRo = the dose rate to organ 0 at the time of the release, in mremly.

Pia = the site-specific dose factor for radionuclide i and organ 0, in (mrem/y)/(J.lCilm 3). Since the dose rate limits specified in Section 3.1.2.b apply only to the child age group exposed to the inhalation pathway, the values of Pia may be obtained from Table 3-9, .. ~ for Inhalation Pathway, Child Age Group."

Q'jv = the release rate of radionuclide i from gaseous release pathway v, in J.lCils.

For the purpose of implementing the controls of Section 3.1.2.b, only 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days should be included in this calculation.

All other terms were defined previously.

3.4.2 Noble Gas Air Dose at or Bevond Site Boundary For the purpose of implementing the controls of Section 3.1.3, air doses in areas at or beyond the SITE BOUNDARY due to releases of noble gases from each unit shall be calculated as follows (adapted from Reference 1, page 28, by including only long-term releases):

Dp =3017XlO-8~{(xJQ),. ~[Nd'i .. l} (3.13)

Dr=3.l7XlO-8~ {(x IQ),. ~[M, oil..l} (3.14) where:

3.17 X 10-8 =a units conversion factor: 1 y/(3.15 x 107 s).

D~ = the air dose due to beta emissions from noble gas radionuclides, in mrad.

D., = the air dose due to gamma emissions from noble gas radionuclides, in mrad.

Nj = the air dose factor due to beta emissions from noble gas radionuclide i (mrad/y)/(J.lCilm 3), from Table 3-5.

M = the air dose factor due to gamma emissions from noble gas radionuclide i (mradly)/(J.lCilm1, from Table 3-5.

Oiv = the cumulative release of noble gas radionuclide i from release pathway v (J.lCi), during the period of interest.

and all other terms are as defined above.

3-31 Rev. 18

VEGPODCM Because the air dose limit is on a per-reactor-unit basis, the summations extend over all gaseous final release pathways for a given unit. For a release pathway discharging materials originating in both reactor units, the activity discharged from the release point may be apportioned to the two units in any reasonable manner, provided that all activity released via the particular shared release pathway is apportioned to one or the other unit.

The gaseous final release pathways at the plant site, and the (XlQ)vb for each, are identified in Table 3-4.

3-32 Rev. 18

VEGPODCM Table 3-5. Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases y- Body (K) ~ - Skin (L) y- Air (M) ~ - Air (N)

Nuclide (mrem/y) per (mradly) per (mrad/y) per (mremly) per

(~Cilm3) (~Cilm3) (~Ci/m3) (~Cilm3)

Kr-83m 7.56 E-02 0.00 E+OO 1.93 E+01 2.88 E+02 Kr-85m 1.17 E+03 1.46 E+03 1.23 E+03 1.97 E+03 Kr-85 1.61 E+01 1.34 E+03 1.72 E+01 1.95 E+03 Kr-87 5.92 E+03 9.73 E+03 6.17 E+03 1.03 E+04 Kr-88 1.47 E+04 2.37 E+03 1.52 E+04 2.93 E+03 Kr-89 1.66 E+04 1.01 E+04 1.73 E+04 1.06 E+04 Kr-90 1.56 E+04 7.29 E+03 1.63 E+04 7.83 E+03 Xe-131m 9.15 E+01 4.76 E+02 1.56 E+02 1.11 E+03 Xe-133m 2.51 E+02 9.94 E+02 3.27 E+02 1.48 E+03 Xe-133 2.94 E+02 3.06 E+02 3.53 E+02 1.05 E+03 Xe-135m 3.12 E+03 7.11 E+02 3.36 E+03 7.39 E+02 Xe-135 1.81 E+03 1.86 E+03 1.92 E+03 2.46 E+03 Xe-137 1.42 E+03 1.22 E+04 1.51 E+03 1.27 E+04 Xe-138 8.83 E+03 4.13 E+03 9.21 E+03 4.75 E+03 Ar-41 8.84 E+03 2.69 E+03 9.30 E+03 3.28 E+03 All values in this table were obtained from Reference 3 (Table B-1), with units converted.

3-33 Rev. 18

VEGPODCM Table 3-6. Dose Factors for Exposure to Direct Radiation from Noble Gases in an Elevated Finite Plume The contents of this table are not applicable to VEGP.

3-34 Rev. 18

VEGPODCM 3.4.3 Dose to a Member of the Public at or Beyond Site Boundary The dose received by an individual due to gaseous releases from each reactor unit, to areas at or beyond the SITE BOUNDARY, depends on the individual's location, age group, and exposure pathways. The MEMBER OF THE PUBLIC expected to receive the highest dose in the plant vicinity is referred to as the controlling receptor. The dosimetrically-significant attributes of the currently-defined controlling receptor are presented in Table 3-7.

Doses to a MEMBER OF THE PUBLIC due to gaseous releases of 1-131, 1-133, tritium, and all radionuclides in particulate form from each unit shall be calculated as follows (equation adapted from Reference 1, page 29, by considering only long-term releases):

(3.15) where:

Dja = the dose to organ j of an individual in age group a, due to gaseous releases of 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in mrem.

7 3.17 x 10-8 = a units conversion factor: 1 y/(3.15 x 10 s).

Rmpj = the site-specific dose factor for age group a, radionuclide i, exposure pathway p, and organ j. For the purpose of implementing the controls of Section 3.1.4, the exposure pathways applicable to calculating the dose to the currently-defined controlling receptor are included in Table 3-7; values of

~ for each exposure pathway and radionuclide applicable to calculations of dose to the controlling receptor are included in Tables 3-8 through 3-12.

A detailed discussion of the methods and parameters used for calculating

~ for the plant site is presented in Chapter 9. That information may be used for recalculating the Reipj values if the underlying parameters change, or for calculating Reipj values for special radionuclides and age groups when performing the assessments discussed in Section 3.4.4 below.

W vip = the annual average relative dispersion or deposition at the location of the controlling receptor, for release pathway v, as appropriate to exposure pathway p and radionuclide i.

For all tritium pathways, and for the inhalation of any radionuclide: W viP is (XlO}VP, the annual average relative dispersion factor for release pathway v, at the location of the controlling receptor (simi. For the ground-plane exposure pathway, and for~estion-related pathways for radionuclides other than tritium: W viP is (D7OJ;, the annual average relative deposition factor for release pathway v, at the location of the controlling receptor (m-2).

Values of (XlO)vp and (D/Q)vp for use in calculating the dose to the currently-defined controlling receptor are included in Table 3-7.

3-35 Rev. 18

VEGPODCM Q'iv = the cumulative release of radionuclide i from release pathway v, during the period of interest (~Ci). For the purpose of implementing the controls of Section 3.1.4, only 1-131,1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days should be included in this calculation.

In any dose assessment using the methods of this sub-section, only radio-nuclides detectable above background in their respective samples should be included in the calculation.

Because the member of the public dose limit is on a per-unit basis, the summations extend over all gaseous final release pathways for a given unit. For a release pathway discharging materials originating in both reactor units, the activity discharged from the release point may be apportioned between the two units in any reasonable manner, provided that all activity released from the plant site is apportioned to one or the other unit.

The gaseous final release pathways at the plant site, and the release elevation for each, are identified in Table 3-4.

3-36 Rev. 18

VEGPODCM Table 3-7. Attributes of the Controlling Receptor The locations of members of the public in the vicinity of the plant site, and the exposure pathways associated with those locations, are determined in the Annual Land Use Census.

Dispersion and deposition values were calculated based on site meteorological data collected for the period January 1, 1985 through December 31, 1987.

Based on an analysis of this information, the current controlling receptor for the plant site is described as follows (References 15 and 22).

~: ssw Distance: 4.7 miles Age Group: Child Exposure Pathways: Inhalation, ground plane, cow meat, and garden vegetation Dispersion Factors iX;Q)vp:

Ground-Level release points: 7.78 X 10-8 51m 3 Mixed-Mode release points: 3.78 x 10-8 s/m 3 Deposition Factors cDiQ)vp:

Ground-Level release points: 3.43 X 10-10 m-2 Mixed-Mode release points: 1.99 x 10-10 m-2 3-37 Rev. 18

VEGPODCM 3.4.4 Dose Calculations to Support Other Requirements Case 1: A radiological impact assessment may be required to support evaluation of a reportable event.

Dose calculations may be performed using the equations in Section 3.4.3, with the substitution of the dispersion and deposition parameters [(XlO) and (0/0)] for the period covered by the report, and using the appropriate pathway dose factors (~ for the receptor of interest. Methods for calculating (XlO) and (0/0) from meteorological data are presented in Chapter 8.

Values of ~ other than those presented in Tables 3-8 through 3-12 may need to be calculated. Methods and parameters for calculating values of R.iR are presented in Chapter 9. When calculating Raipj for evaluation of an event, pathway and usage factors specific to the receptor involved in the event may be used in place of the values in Chapter 9, if the specific values are known.

Case 2: A dose calculation is required to evaluate the results of the Land Use Census, under the provisions of Section 4.1.2.

In the event that the Land Use Census reveals that exposure pathways have changed at previously-identified locations, or if new locations are identified, it may be necessary to calculate doses at two or more locations to determine which should be designated as the controlling receptor. Such dose calculations may be performed using the equations in Section 3.4.3, with the substitution of the annual average dispersion and deposition values

[(X70) and (OK:Ul for the locations of interest, and using the appropriate pathway dose factors (~) for the receptors of interest.

Methods for calculating (XlO) and (0/0) from meteorological data are presented in Chapter 8. The values of Reipj other than those presented in Tables 3-8 through 3-12 may need to be calculated. Methods and parameters for calculating values of Raipj are presented in Chapter 9.

Case 3: Under ~ction 5.2, a dose calculation may be required to support the determination of a component of the total dose to a receptor other than that currently defined as the controlling receptor.

Dose calculations would be performed using the equations in Section 3.4.3, with the dispersion and deposition parameters and appropriate values of (Reipj) for the receptor of interest.

Appropriate values of the dispersion and deposition parameters, if not found in Table 3-7, would need to be calculated. Methods for calculating (XlO) and (0/0) from meterological data are presented in Chapter 8.

Appropriate values of RaiR, if not found in Tables 3-8.through 3-12, would need to be calculated. Methods and parameters for calculating values of ~ are presented in Chapter 9.

3-38 Rev. 18

VEGPODCM Table 3-8. RaiPj for Ground Plane Pathway, All Age Groups Nuclide T. Body Skin H-3 0.00 0.00 C-14 0.00 0.00 P-32 0.00 0.00 Cr-51 4.66E+06 5.51E+06 Mn-54 1.39E+09 1.63E+09 Fe-55 0.00 0.00 Fe-59 2.73E+08 3.21E+08 Co-58 3.79E+08 4.44E+08 Co-60 2.15E+10 2.53E+10 Ni-63 0.00 0.00 Zn-65 7.47E+08 8.59E+08 Rb-86 8.99E+06 1.03E+07 Sr-89 2. 16E+04 2.51E+04 Sr-90 0.00 0.00 Y-91 1.07E+06 1.21E+06 Zr-95 2.45E+08 2.84E+08 Nb-95 1.37E+08 1.61E+08 Ru-103 1.08E+08 1.26E+08 Ru-106 4.22E+08 5.07E+08 Ag-110m 3.44E+09 4.01E+09 Sb-124 5.98E+08 6.90E+08 Sb-125 2.34E+09 2.64E+09 Te-125m 1.55E+06 2.13E+06 Te-127m 9. 16E+04 1.08E+05 Te-129m 1.98E+07 2.31E+07 1-131 1.72E+07 2.09E+07 1-133 2.45E+06 2.98E+06 Cs-134 6.86E+09 8.00E+09 Cs-136 1.51E+08 1.71E+08 Cs-137 1.03E+10 1.20E+10 Ba-140 2.05E+07 2.35E+07 Ce-141 1.37E+07 1.54E+07 Ce-144 6.95E+07 8.04E+07 Pr-143 0.00 0.00 Nd-147 8.39E+06 1.01E+07

1. Units are m2 .(mrem/yr)/(J.lCi/s).

2. The values in the Total Body column also apply to the Bone, Liver, Thyroid, Kidney, Lung, and GI-LLI organs.

3. This table also supports the calculations of section 6.2.

3-39 Rev. 18

VEGPODCM Table 3-9. Raipj for Inhalation Pathway, Child Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 P-32 2.60E+06 1.14E+05 9.88E+04 0.00 0.00 0.00 4.22E+04 Cr-51 0.00 0.00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 Mn-54 0.00 4.29E+04 9.51E+03 0.00 1.00E+04 1.58E+06 2.29E+04 Fe-55 4.74E+04 2.52E+04 7.nE+03 0.00 0.00 1.11E+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 1.67E+04 0.00 0.00 1.27E+06 7.07E+04 Co-58 0.00 1.77E+03 3.16E+03 0.00 0.00 1.11E+06 3.44E+04 Co-60 0.00 1.31E+04 2.26E+04 0.00 0.00 7.07E+06 9.62E+04 Ni-63 8.21E+05 4.63E+04 2.80E+04 0.00 0.00 2.75E+05 6.33E+03 Zn-65 4.26E+04 1.13E+05 7.03E+04 0.00 7. 14E+04 9.95E+05 1.63E+04 Rb-86 0.00 1.98E+05 1.14E+05 0.00 0.00 0.00 7.99E+03 Sr-89 5.99E+05 0.00 1.72E+04 0.00 0.00 2.16E+06 1.67E+05 Sr-90 1.01E+08 0.00 6.44E+06 0.00 0.00 1.48E+07 3.43E+05 Y-91 9.14E+05 0.00 2.44E+04 0.00 0.00 2.63E+06 1.84E+05 Zr-95 1.90E+05 4. 18E+04 3.70E+04 0.00 5.96E+04 2.23E+06 6.11E+04 Nb-95 2.35E+04 9. 18E+03 6. 55E+03 0.00 8.62E+03 6.14E+05 3.70E+04 Ru-103 2.79E+03 0.00 1.07E+03 0.00 7.03E+03 6.62E+05 4.48E+04 Ru-106 1.36E+05 0.00 1.69E+04 0.00 1.84E+05 1.43E+07 4.29E+05 Ag-110m 1.69E+04 1.14E+04 9.14E+03 0.00 2.12E+04 5.48E+06 1.00E+05 Sb-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Sb-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Te-125m 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00 4.77E+05 3.38E+04 Te-127m 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 1-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7. 88E+04 0.00 2.84E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3. 38E+04 0.00 5.48E+03 Cs-134 6.51E+05 1.01E+06 2.25E+05 0.00 3.30E+05 1.21E+05 3.85E+03 Cs-136 6.51E+04 1.71E+05 1.16E+05 0.00 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 1.28E+05 0.00 2.82E+05 1.04E+05 3.62E+03 Ba-140 7.40E+04 6.48E+01 4.33E+03 0.00 2.11E+01 1.74E+06 1.02E+05 Ce-141 3.92E+04 1.95E+04 2.90E+03 0.00 8.55E+03 5.44E+05 5.66E+04 Ce-144 6.77E+06 2.12E+06 3.61E+05 0.00 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04 5.55E+03 9.14E+02 0.00 3.00E+03 4.33E+05 9.73E+04 Nd-147 1.08E+04 8.73E+03 6.81E+02 0.00 4.81E+03 3.28E+05 8.21E+04

1. Units are (mrem/yr)/(JlCilm; for all radionuclides.

2. This table also supports the calculations of section 6.2.

3-40 Rev. 18

VEGPODCM Table 3-10. Raipj for Inhalation Pathway, Adult Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00 1.26E+03 1.26E+03 1'.26E+03 1.26E+03 1.26E+03 1.26E+03 C-14 1.82E+04 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 P-32 1.32E+06 7.71E+04 5.01E+04 0.00 0.00 0.00 8.64E+04 Cr-51 0.00 0.00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 Mn-54 0.00 3.96E+04 6.30E+03 0.00 9.84E+03 1.40E+06 7.74E+04 Fe-55 2.46E+04 1.70E+04 3.94E+03 0.00 0.00 7.21E+04 6.03E+03 Fe-59 1.18E+04 2.78E+04 1.06E+04 0.00 0.00 1.02E+06 1.88E+05 Co-58 0.00 1.58E+03 2.07E+03 0.00 0.00 9.28E+05 1.06E+05 Co-60 0.00 1.15E+04 1.48E+04 0.00 0.00 5.97E+06 2.85E+05 Ni-63 4.32E+05 3.14E+04 1.45E+04 0.00 0.00 1.78E+05 1.34E+04 Zn-65 3.24E+04 1.03E+05 4.66E+04 0.00 6.90E+04 8.64E+05 5.34E+04 Rb-86 0.00 1.35E+05 5.90E+04 0.00 0.00 0.00 1.66E+04 Sr-89 3.04E+05 0.00 8.72E+03 0.00 0.00 1.40E+06 3.50E+05 Sr-90 9.92E+07 0.00 6. 1OE+06 0.00 0.00 9.60E+06 7.22E+05 Y-91 4.62E+05 0.00 1.24E+04 0.00 0.00 1.70E+06 3.85E+05 Zr-95 1.07E+05 3.44E+04 2.33E+04 0.00 5.42E+04 1.77E+06 1.50E+05 Nb-95 1.41E+04 7.82E+03 4.21E+03 0.00 7.74E+03 5.05E+05 1.04E+05 Ru-103 1.53E+03 0.00 6.58E+02 0.00 5.83E+03 5.05E+05 1.10E+05 Ru-106 6.91E+04 0.00 8.72E+03 0.00 1.34E+05 9.36E+06 9.12E+05 Ag-110m 1.08E+04 1.00E+04 5.94E+03 0.00 1.97E+04 4.63E+06 3.02E+05 Sb-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 0.00 2.48E+06 4.06E+05 Sb-125 6.61E+04 7.13E+02 1.33E+04 5.87E+01 0.00 2.20E+06 1.01E+05 Te-125m 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 Te-127m 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 Te-129m 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 1-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00 6.28E+03 1-133 8.64E+03 1.48E+04 4.52E+03 2. 15E+06 2.58E+04 0.00 8. 88E+03 Cs-134 3.73E+05 8.48E+05 7.28E+05 0.00 2.87E+05 9.76E+04 1.04E+04 Cs-136 3.90E+04 1.46E+05 1.10E+05 0.00 8.56E+04 1.20E+04 1.17E+04 Cs-137 4.78E+05 6.21E+05 4.28E+05 0.00 2.22E+05 7.52E+04 8.40E+03 Ba-140 3.90E+04 4.90E+01 2.57E+03 0.00 1.67E+01 1.27E+06 2.18E+05 Ce-141 1.99E+04 1.35E+04 1.53E+03 0.00 6.26E+03 3.62E+05 1.20E+05 Ce-144 3.43E+06 1.43E+06 1.84E+05 0.00 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 0.00 2.16E+03 2.81E+05 2.00E+05 Nd-147 5.27E+03 6.10E+03 3.65E+0.2 0.00 3.56E+03 2.21E+05 1.73E+05

1. Units are (mrem/yr)/(IlCi/m3) for all radionuclides.

2. This table is included to support the calculations of section 6.2.

3-41 Rev. 18

VEGPODCM Table 3-11. Raipj for Cow Meat Pathway, Child Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 0.00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 C-14 5.29E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 P-32 7.41E+09 3.47E+08 2.86E+08 0.00 0.00 0.00 2.05E+08 Cr-51 0.00 0.00 8.79E+03 4.88E+03 1.33E+03 8.91E+03 4.66E+05 Mn-54 0.00 8.01E+06 2.13E+06 0.00 2.25E+06 0.00 6.72E+06 Fe-55 4.57E+08 2.42E+08 7.51E+07 0.00 0.00 1.37E+08 4.49E+07 Fe-59 3.76E+08 6.09E+08 3.03E+08 0.00 0.00 1.77E+08 6.34E+08 Co-58 0.00 1.64E+07 5.02E+07 0.00 0.00 0.00 9.58E+07 Co-60 0.00 6.93E+07 2.04E+08 0.00 0.00 0.00 3.84E+08 Ni-63 2.91E+10 1.56E+09 9.91E+08 0.00 0.00 0.00 1.05E+08 Zn-65 3.75E+08 1.00E+09 6.22E+08 0.00 6.30E+08 0.00 1.76E+08 Rb-86 0.00 5.77E+08 3.55E+08 0.00 0.00 0.00 3.71E+07 Sr-89 4.82E+08 0.00 1.38E+07 0.00 0.00 0.00 1.87E+07 Sr-90 1.04E+10 0.00 2.64E+09 0.00 0.00 0.00 1.40E+08 Y-91 1.80E+06 0.00 4.82E+04 0.00 0.00 0.00 2.40E+08 Zr-95 2.66E+06 5.85E+05 5.21E+05 0.00 8.38E+05 0.00 6.11E+08 Nb-95 3.10E+06 1.21E+06 8.62E+05 0.00 1.13E+06 0.00 2.23E+09 Ru-103 1.55E+08 0.00 5.96E+07 0.00 3.90E+08 0.00 4.01E+09 Ru-106 4.44E+09 0.00 5.54E+08 0.00 5.99E+09 0.00 6.90E+10 Ag-110m 8.39E+06 5.67E+06 4.53E+06 0.00 1.06E+07 0.00 6.74E+08 Sb-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Sb-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Te-125m 5.69E+08 1.54E+08 7.59E+07 1.60E+08 0.00 0.00 5.49E+08 Te-127m 1.77E+09 4.78E+08 2.11E+08 4.24E+08 5.06E+09 0.00 1.44E+09 Te-129m 1.79E+09 5.00E+08 2.78E+08 5.77E+08 5.26E+09 0.00 2.18E+09 1-131 1.65E+07 1.66E+07 9.46E+06 5.50E+09 2.73E+07 0.00 1.48E+06 1-133 5.67E-01 7.02E-01 2.66E-01 1.30E+02 1.17E+00 0.00 2.83E-01 Cs-134 9.22E+08 1.51E+09 3. 19E+08 0.00 4.69E+08 1.68E+08 8.16E+06 Cs-136 1.62E+07 4.46E+07 2.88E+07 0.00 2.37E+07 3.54E+06 1.57E+06 Cs-137 1.33E+09 1.28E+09 1.88E+08 0.00 4.16E+08 1.50E+08 7.99E+06 Ba-140 4.38E+07 3.84E+04 2.56E+06 0.00 1.25E+04 2.29E+04 2.22E+07 Ce-141 2.22E+04 1.11E+04 1.64E+03 0.00 4.86E+03 0.00 1.38E+07 Ce-144 2.32E+06 7.26E+05 1.24E+05 0.00 4.02E+05 0.00 1.89E+08 Pr-143 3.34E+04 1.00E+04 1.66E+03 0.00 5.43E+03 0.00 3.60E+07 Nd-147 1.17E+04 9.47E+03 7.33E+02 0.00 5.19E+03 0.00 1.50E+07 Units are (mrem/yr)/(~Ci/m3) for tritium, and m2*(mrem/yr)/(~Ci/s) for all other radionuclides.

3-42 Rev. 18

VEGPODCM Table 3-12. Raipj for Garden Vegetation Pathway, Child Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 0.00 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 C-14 8.89E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 P-32 3.37E+09 1.58E+08 1.30E+08 0.00 0.00 0.00 9.31E+07 Cr-51 0.00 0.00 1. 17E+05 6.50E+04 1.78E+04 1.19E+05 6.21E+06 Mn-54 0.00 6.65E+08 1.77E+08 0.00 1.86E+08 0.00 5.58E+08 Fe-55 8.01E+08 4.25E+08 1.32E+08 0.00 0.00 2.40E+08 7.87E+07 Fe-59 3.98E+08 6.43E+08 3.20E+08 0.00 0.00 1.86E+08 6.70E+08 Co-58 0.00 6.44E+07 1.97E+08 0.00 0.00 0.00 3.76E+08 Co-60 0.00 3.78E+08 1.12E+09 0.00 0.00 0.00 2.10E+09 Ni-63 3.95E+10 2.11E+09 1.34E+09 0.00 0.00 0.00 1.42E+08 Zn-65 8.13E+08 2.16E+09 1.35E+09 0.00 1.36E+09 0.00 3.80E+08 Rb-86 0.00 4.52E+08 2.78E+08 0.00 0.00 0.00 2.91E+07 Sr-89 3.60E+10 0.00 1.03E+09 0.00 0.00 0.00 1.39E+09 Sr-90 1.24E+12 0.00 3.15E+11 0.00 0.00 0.00 1.67E+10 Y-91 1.86E+07 0.00 4.99E+05 0.00 0.00 0.00 2.48E+09 Zr-95 3.86E+06 8.48E+05 7.55E+05 0.00 1.21E+06 0.00 8.85E+08 Nb-95 4. 1OE+05 1.60E+05 1.14E+05 0.00 1.50E+05 0.00 2.96E+08 Ru-103 1.53E+07 0.00 5.90E+06 0.00 3.86E+07 0.00 3.97E+08 Ru-106 7.45E+08 0.00 9.30E+07 0.00 1.01E+09 0.00 1.16E+10 Ag-110m 3.21E+07 2. 17E+07 1.73E+07 0.00 4.04E+07 0.00 2.58E+09 Sb-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Sb-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Te-125m 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00 0.00 3.38E+08 Te-127m 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00 1.07E+09 Te-129m 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 0.00 1.03E+09 1-131 1.43E+08 1.44E+08 8. 17E+07 4.75E+10 2.36E+08 0.00 1.28E+07 1-133 3.53E+06 4.37E+06 1.65E+06 8.11E+08 7.28E+06 0.00 1.76E+06 Cs-134 1.60E+10 2.63E+10 5.55E+09 0.00 8.15E+09 2.93E+09 1.42E+08 Cs-136 8.24E+07 2.27E+08 1.47E+08 0.00 1.21E+08 1.80E+07 7.96E+06 Cs-137 2.39E+10 2.29E+10 3.38E+09 0.00 7.46E+09 2.68E+09 1.43E+08 Ba-140 2.77E+08 2.42E+05 1.61E+07 0.00 7.89E+04 1.45E+05 1.40E+08 Ce-141 6.56E+05 3.27E+05 4.86E+04 0.00 1.43E+05 0.00 4.08E+08 Ce-144 1.27E+08 3.98E+07 6.78E+06 0.00 2.21E+07 0.00 1.04E+10 Pr-143 1.46E+05 4.37E+04 7.23E+03 0.00 2.37E+04 0.00 1.57E+08 Nd-147 7.15E+04 5.79E+04 4.48E+03 0.00 3. 18E+04 0.00 9.17E+07 Units are (mrem/yr)/(~Ci/m3) for tritium, and m2'(mrernlyr)/(~Ci/s) for all other radionuclides. .

3-43 Rev. 18

VEGPODCM 3.5 GASEOUS EFFLUENT DOSE PROJECTIONS 3.5.1 Thirty-One Day Dose Projections In order to meet the requirements of the limit for operation of the gaseous radwaste treatment system (see Section 3.1.5), dose projections must be made at least once each 31 days; this applies during periods in which a discharge to areas at or beyond the SITE BOUNDARY of gaseous effluents containing radioactive materials occurs or is expected.

Projected 31-day air doses and doses to individuals due to gaseous effluents may be determined as follows:

For air doses:

D~ =[ D; ]XJl+DJ' (3.16)

D", =[ D; ]XJJ+D,.

For individual doses:

(3.17) where:

Dllp = the projected air dose due to beta emissions from noble gases. for the next 31 days of gaseous releases.

Dllc = the cumulative air dose due to beta emissions from noble gas releases that have occurred in the elapsed portion of the current quarter. plus the release under consideration.

Dlla = the anticipated air dose due to beta emissions from noble gas releases, contributed by any planned activities dUring the next 31-day period. if those activities will result in gaseous releases that are in addition to routine gaseous effluents. If only routine gaseous effluents are anticipated, Dlla may be set tQ zero.

Ow = the projected air dose due to gamma emissions from noble gases for the next 31 days of gaseous releases.

D'l'C = the cumulative air dose due to gamma emissions from noble gas releases that have occurred in the elapsed portion of the current quarter. plus the release under consideration.

0 18 = the anticipated air dose due to gamma emissions from noble gas releases, contributed by any planned activities during the next 31-day period, if those activities will result in gaseous releases that are in addition to routine 3-44 Rev. 18

VEGP aDeM gaseous effluents. If only routine gaseous effluents are anticipated, 0 18 may be set to zero.

Dop = the projected dose to the total body or organ 0, due to releases of 1-131, 1-133, tritium, and particulates for the next 31 days of gaseous releases.

Doc = the cumulative dose to the total body or organ 0, due to releases of 1-131, 1-133, tritium, and particulates that have occurred in the elapsed portion of the current quarter, plus the release under consideration.

Doa = the anticipated dose to the total body or organ 0, due to releases of 1-131, 1-133, tritium, and particulates, contributed by any planned activities during the next 31-day period, if those activities will result in gaseous releases that are in addition to routine gaseous effluents. If only routine gaseous effluents are anticipated, Doe may be set to zero.

t = the number of whole or partial days elapsed into the current quarter, including the time to the end of the release under consideration (even if the release continues into the next quarter).

3.5.2 Dose Projections for Soecific Releases Dose projections may be performed for a particular release by performing a pre-release dose calculation assuming that the planned release will proceed as anticipated. For air dose and individual dose projections due to gaseous effluent releases, follow the methodology of Section 3.4, using sample analysis results for the gaseous stream to be released, and parameter values expected to exist during the release period.

3-45 Rev. 18

m

-~--~._"_._'--------------

VEGPODCM 3.6 DEFINITIONS OF GASEOUS EFFLUENT TERMS Section of Definition Initial Use AG= the administrative allocation factor for gaseous streams, applied to divide the gaseous release limit among all the release pathways [unitless]. 3.3.2.1 AG s = the administrative allocation factor for gaseous source stream s, applied to divide the gaseous release limit among all the release pathways [unitless]. 3.3.3 AG y = the administrative allocation factor for gaseous release pathway v, applied to divide the gaseous release limit among all the release pathways [unitless]. 3.3.2.2 c= the setpoint of the radioactivity monitor measuring the concentration of radioactivity in the effluent line prior to release

[J.LCilmL]. 3.3.2.1 ens = the calculated noble gas effluent monitor setpoint for gaseous source stream s [J.LCilmL]. 3.3.3 em= the calculated noble gas effluent monitor setpoint for release pathway v [J.LCilmL]. 3.3.2.2 the dose to organ j of an individual in age group a, due to gaseous releases of 1-131, 1-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days [mrem]. 3.4.3 Doe = the anticipated dose to organ 0 due to releases of non-noble-gas radionuclides, contributed by any planned activities during the next 31-day period [mrem]. 3.5.1 Doc = the cumulative dose to organ 0 due to releases of non-noble-gas radionuclides that have occurred in the elapsed portion of the current quarter, plus the release under consideration [mrem]. 3.5.1 Dop = the projected dose to organ 0 due to the next 31 days of gaseous releases of non-noble-gas radionuclides [mrem]. 3.5.1 the air dose due to beta emissions from noble gas radionuclides

[mrad]. 3.4.2 Dlia = the anticipated air dose due to beta emissions from noble gas releases, contributed by any planned activities dUring the next 31-day period [mrad]. 3.5.1 3-46 Rev. 18

VEGPODCM Section of Definition Initial Use

°lk= the cumulative air dose due to beta emissions from noble gas releases that have occurred in the elapsed portion of the current quarter, plus the release under consideration [mrad]. 3.5.1 O~p = the projected air dose due to beta emissions from noble gases, for the next 31 days of gaseous releases [mrad]. 3.5.1 the air dose due to gamma emissions from noble gas radionuclides [mrad]. 3.4.2 0 18 = the anticipated air dose due to gamma emissions from noble gas releases, contributed by any planned activities during the next 31-day period [mrad]. 3.5.1 D"jC = the cumulative air dose due to gamma emissions from noble gas releases that have occurred in the elapsed portion of the current quarter, plus the release under consideration [mrad]. 3.5.1 the projected air dose due to gamma emissions from noble gases, for the next 31 days of gaseous releases [mrad]. 3.5.1 (D/Q)vp = the annual average relative deposition factor for release pathway v, at the location of the controlling receptor, from Table 3-7 [m4. 3.4.3 D~= the skin dose rate at the time of the release [mremly]. 3.4.1.1 ORo = the dose rate to organ 0 at the time of the release [mremly]. 3.4.1.2 DRl = the total body dose rate at the time of the release [mremly]. 3.4.1.1 faY = the maximum anticipated actual discharge fIowrate for release pathway v during the period of the planned release [mUs]. 3.3.2.2 f as = the maximum anticipated actual discharge fIowrate for gaseous source stream s during the period of the planned release [mUs]. 3.3.3

~= the total body dose factor due to gamma emissions from noble gas radionuclide i, from Table 3-5 [(mremly)/(IJ.Cilm3)]. 3.3.2.2 It= the skin dose factor due to beta emissions from noble gas radio-3 nuclide i, from Table 3-5 [(mremly)/(IJ.Cilm )]. 3.3.2.2 M= the air dose factor due to gamma emissions from noble gas radionuclide i, from Table 3-5 [(mrad/Y)/(IJ.Cilm;]. 3.4.2 3-47 Rev. 18

VEGPODCM Section of Definition Initial Use N= the number of simultaneously active gaseous release pathways

[unitless]. 3.3.4 N;= the air dose factor due to beta emissions from noble gas radio-nuclide i, from Table 3-5 [(mradly)/blCilm;]. 3.4.2 Pio = the site-specific dose factor for radionuclide i (1-131,1-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days) and organ o. The values of Pio are equal to the site-specific ~ values presented in Table 3-9 [(mremly)/blCilm;]. 3.4.1.2 the release rate of noble gas radionuclide i from release pathway v during the period of interest hJ,Cils]. 3.3.2.2 the release rate of radionuclide i (1-131,1-133, tritium, and radio-nuclides in particulate form with half-lives greater than 8 days) from gaseous release pathway v during the period of interest hJ,Cils]. 3.4.1.2 the cumulative release of noble gas radionuclide i from release pathway v during the period of interest hJ,Cij. 3.4.2 the cumulative release of non-noble-gas radionuclide i from release pathway v, during the period of interest hJ,Cij. 3.4.3

~= the site-specific dose factor for age group a, radionuclide i, exposure pathway p, and organ j. Values and units of ~ for each exposure pathway, age group, and radionuclide that may arise in calculations for implementing section 3.1.4 are listed in Table 3-8 through Table 3-9. 3.4.3

~= the ratio of the skin dose rate limit for noble gases, to the skin dose rate due to noble gases in the release under consideration

[unitless]. 3.3.2.1 Rt= the ratio of the total body dose rate limit for noble gases, to the total body dose rate due to noble gases in the release under consideration [unitless]. 3.3.2.1 the ratio of the skin dose rate limit for noble gases, to the skin dose rate due to noble gases in the source stream under consideration [unitless]. 3.3.3.1 the ratio of the total body dose rate limit for noble gases, to the total body dose rate due to noble gases in the source stream under consideration [unitless]. 3.3.3.1 3-48 Rev. 18

D VEGPODCM Section of Definition Initial Use SF= the safety factor used in gaseous setpoint calculations to compensate for statistical fluctuations and errors of measurement

[unitless]. 3.3.2.2 t= the number of whole or partial days elapsed in the current quarter, including the period of the release under consideration. 3.5.1 W vip = the annual average relative dispersion [(XlQ)VP] or deposition

[(D/Q)vp] at the location of the controlling receptor, for release pathway v, as appropriate to exposure pathway p and radionuclide i. 3.4.3 X= the noble gas concentration for the release under consideration lIJ.Ci/mL]. 3.3.2.1 Xir = the concentration of radionuclide i applicable to active gaseous release pathway r lIJ.CilmL]. 3.3.4 Xis = the measured concentration of radionuclide i in gaseous source stream s lIJ.CilmL]. 3.3.3 Xiv = the measured concentration of radionuclide i in gaseous stream v lIJ.CilmL]. 3.3.2.2 (XlQ) = the highest relative concentration at any point at or beyond the SITE BOUNDARY [s1m~. 3.3.2.1 the annual average SITE BOUNDARY relative concentration applicable to active gaseous release pathway r [s1m~. 3.3.4 (XlQ)vb = the highest annual average relative concentration at the SITE BOUNDARY for the discharge point of release pathway v, from Table 3-4 [s1m~.* 3.3.2.2 (XlQ)vp = annual average relative dispersion factor for release pathway v, at the location of the controlling receptor, from Table 3-7 [s1m~. 3.4.3 3-49 Rev. 18 L

VEGPODCM CHAPTER 4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4.1 LIMITS OF OPERATION The following limits are the same for both units at the site. Thus, a single program including monitoring, land use survey, and quality assurance serves both units.

4.1.1 Radiological Environmental Monitoring The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in Table 4-1.

4.1.1.1 Applicability This control applies at all times.

4.1.1.2 Actions 4.1.1.2.1 With the REMP not being conducted as specified in Table 4-1, submit to the Nuclear Regulatory Commission (NRC), in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as reqUired and the plans for preventing a recurrence. Deviations from the required sampling schedule are permitted if specimens are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction, or other just reasons. If deviations are due to equipment malfunction, efforts shall be made to complete corrective action prior to the end of the next sampling period.

1 4.1.1.2.2 With the confirmed measured level of radioactivity as a result of plant effluents in an environmental sampling medium specified in Table 4-1 exceeding the reporting levels of Table 4-2 when averaged over any calendar quarter, submit within 30 days a special report to the NRC.

The special report shall identify the cause(s} for exceeding the limit(s} and define the corrective action(s} 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 Sections 2.1.3, 3.1.3, and 3.1.4. The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in the special report.

When more than one of the radionuclides in Table 4-2 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 4-2 are detected and are the result of plant effluents, this special report shall be submitted if the potential annual dose to a MEMBER OF THE Defined as confirmed by reanalysis of the original sample, or analysis of a duplicate or new sample, as appropriate. The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis.

4-1 Rev. 18

VEGPODCM PUBLIC is equal to or greater than the calendar year limits stated in Sections 2.1.3, 3.1.3, and 3.1.4. This special 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 described in the Annual Radiological Environmental Operating Report. The levels of naturally-occurring radionuclides which are not included in the plant's effluent releases need not be reported.

4.1.1.2.3 If adequate samples of milk, or during the growing season, grass or leafy vegetation, can no longer be obtained from one or more of the sample locations required by Table 4-1, or if the availability is frequently or persistently wanting, efforts shall be made: to identify specific locations for obtaining suitable replacement samples; and to add any replacement locations to the REMP given in the ODCM within 30 days. The specific locations from which samples became unavailable may be deleted from the REMP. Pursuant to Technical Specification 5.5.1, documentation shall be submitted in the next Radioactive Effluent Release Report for the change(s) in the ODCM, including revised flQure(s) and table(s) reflecting the changes to the location(s), with supporting information identifying the cause of the unavailability of samples and justifying the selection of any new Iocation(s).

4.1.1.2.4 This control does not affect shutdown requirements or MODE changes.

4.1.1.3 Surveillance Requirements The REMP samples shall be collected pursuant to Table 4-1 from the locations described in Section 4.2, and shall be analyzed pursuant to the requirements of Table 4-1 and Table 4-3.

Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

Program changes may be initiated based on operational experience.

Analyses shall be performed in such a manner that the stated MINIMUM DETECTABLE CONCENTRATIONs (MDCs) will be achieved under routine conditions. OCCasionally background fluctuations, unavoidable small sample sizes, the presence of interfering radionuclides, or other uncontrollable circum~nces may render these MDCs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

4.1.1.4 Basis The REMP required by this control provides 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 the plant operation. The REMP implementsSection IV.B.2, Appendix 1,10 CFR SO, and thereby supplements the radiological effluent monitoring program by measuring concentrations of radioactive materials and levels of radiation, which may then be compared with those expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

The detection capabilities required by Table 4-3 are within state-of-the-art for routine environmental measurements in industrial laboratories.

4-2 Rev. 18

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Exposure Sampling and Type and CD Number of Representative Samples and Sample Pathway Collection Frequency of ~

Locations(1) .....

I andlor Sample FreQuency Analysis

1. DIRECT RADIATION Direct Radia- Thirty-six or more routine monitoring stations, either Quarterly. Gamma dose tion(2) with two or more dosimeters, or with one instrument quarterly. ?1a.

for measuring and recording dose rate continuously, 0' 5"

placed as follows: co

[

An inner ring of stations, one in each meteorological m

J sector in the general area of the site boundary. <

a'

J An outer ring of stations, one in each meteorological 3(l) sector at approximately 5 miles from the site.

3-

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UJ The balance of the stations to be placed in special s:

o s:

interest areas such as population centers, nearby ::J residences, schools, and in one or more areas to serve as control stations. ::J co

2. AIRBORNE ""0 Radioiodine Samples from 5 or more locations as follows: Continuous Radioiodine a co and Partic- sampler operation Canister: 1-131 OJ ulates Three or more samples from close to the three site with sample analysis weekly. 3 boundary locations, in different sectors. collection weekly, or more frequently Particulate One sample from the vicinity of a community having if required by dust Sampler: Gross the highest calculated annual average ground-level loading. beta radioactivity D/Q. analysis following filter change, and One sample from a control location, as, for example, gamma isotopic

~..... a population center 10 to 20 miles distant and in the least prevalent wind direction.

analysis of composite (by m

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-I Q) ro Exposure 0-Number of Representative Samples Sampling and Collection Type and Frequency of Pathway

-Iloo and Sample Locations(1) Frequency Analysis

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and/or Sample

3. WATERBORNE

J Surface(5) One sample upstream, Composite sample over 1- Gamma isotopic analysis ~

month period.(6) monthly; composite for One sample downstream. tritium analysis auarterlv.(4) ;0 Q)

Drinking Two samples at each of the one to Composite sample of river 1-131 analysis on each a.

three nearest water treatment plants water near intake at each sample when the dose o' 5"

that could be affected by discharges water treatment plant over calculated for the 0 from the facility. 2-week consumption of the water [

period when 1-131 analysis is greater than 1 mrem per m

J Two samples at a control location. is performed. monthly year. Composite for gross <

composite otherwise; and beta and gamma isotopic (3'

J

-Iloo J:,.. grab sample of finished analyses monthly. 3 (l) water at each water Composite for tritium :J treatment plant every 2 analysis quarterly.(4)(7) ~

weeks or monthly. as ~

0 appropriate.(6) :J Sediment from One sample from downstream area Semiannually. Gamma isotopic analysis ..,

0 Shoreline with existing or potential recreational semiannually.(4) :i" value.

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--8 Locations(1) ~

I and/or Sample FreQuencv Analvsis -0.

4. INGESTION

3 Milk Samples from milking animals in three locations within 3 Semimonthly. Gamma .....

r+

miles distance having the highest dose potential; if there are isotopic none. then one sample from milking animals in each of three analysis semi-areas between 3 and 5 miles distance where doses are monthly.(4)(8) ~

Q) calculated to be greater than 1 mrem per year.(7) cr 0.

5" One sample from milking animals at a control location about 0 10 miles distant or beyond. and preferably in a wind [

direction of low prevalence. m

3 Fish At least one sample of any commercially and recreationally Semiannually. Gamma <

important species in vicinity of plant discharge area. isotopic ci'

3 analyses on 3

~

I 01 CD At least one sample of any species in areas not influenced edible ::3 by plant discharge. portions.(4) ~

3:

0 At least one sample of any anadromous species in vicinity of During spring Gamma ::3 plant discharge. spawning isotopic 6' season. analyses on ::i" edible portion.(4)

Grass or One sample from two onsite locations near the site Monthly during Gamma Leafy boundary in different sectors. growing season. isotopic.(4)(8)

Vegetation One sample from a control location about 15 miles distant. Monthly during Gamma growing season. isotopic.(4)(8)

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(1) For each sample location in this table, specific parameters of distance and direction sector from a point midway betwl 8:3 the center of the two reactors, and additional description where pertinent, are provided in Table 4-4, and in Figure 4-1 ~

through Figure 4-4 of this ODCM.

(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously, n be used in place of or in addition to integrating dosimeters. For the purpose of this table, a thermoluminescent dosirr ~

0.

(TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimete o' 0"

Film badges shall not be used as dosimeters for measuring direct radiation.

~

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to all m for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yea ~

mean of control samples, gamma isotopic analysis shall be performed on the individual samples. c3'

3

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(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. [

s::

o (5) The upstream sample shall be taken at a distance beyond significant influence of the discharge. The downstream :3 sample shall be taken in an area beyond but near the mixing zone. S..,

S' (6) Composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the composi period (e.g., monthly) in order to assure obtaining a representative sample.

(7) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

(8) If gamma isotopic analysis is not sensitive enough to meet the required MDC for 1-131, a separate analysis for 1-131 \

be performed. .

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-I Q) 0-ro Airborne Grass or Leafy ~ ,

Water Fish Milk Analysis Particulate or Vegetation I\)

(pCi/L) (pCi/kg, wet) (pCi/L)

Gases (pCi/m3) (pCi/kg, wet)

~

H-3 2 E+48 "8 Mn-54 1 E+3 3 E+4 2:

J

<0 Fe-59 4 E+2 1 E+4 Co-58 1 E+3 3E+4 ~

CD Co-60 3 E+2 1 E+4 iii Zn-65 3 E+2 2E+4 ..,0'

0 Zr-95 4 E+2 Q) a.

Nb-95 7 E+2 o' Q) 1-131 2 E+Ob 9 E-1 3E+0 1 E+2 Q:

~ Cs-134 3 E+1 1 E+1 1 E+3 6 E+1 1 E+3 ~

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Cs-137 5 E+1 2 E+1 2E+3 7 E+1 2 E+3 0 Ba-140 2E+2 3 E+2 S~

La-140 1 E+2 4E+2 Ql c:

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a. This is the 40 CFR 141 value for drinking water samples. If no drinking water pathway exists, a value of 3 E+04 :r pCi/L may be used. m

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b. If no drinking water pathway exists, a value of 20 pCi/L may be used. a::::J 3

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Minimum Detectable Concentration MDC)8 ar 0-Airborne Grass or Leafy ~

Water Fish Milk Sediment I Analysis Particulate or Vegetation ~

(pCi/L) (pCi/kg, wet) (pCi/L) (pCi/kg, dry)

Gases (pCi/m 3) (pCi/kg, wet)

Gross Beta 4E+0 1 E-2 b ~

H-3 2 E+3 c (1)

Mn-54 1.5 E+1 1.3 E+2 CIl Fe-59 Co-58, Co-60 Zn-65 3 E+1 1.5 E+1 3 E+1 2.6 E+2 1.3 E+2 2.6 E+2

-is::

0-5' Zr-95 3 E+1 3' c:

Nb-95 1.5 E+1 3 1-131 1 E+Oc 7E-2 1 E+O 6 E+1 o

~ Cs-134 1.5 E+1 5E-2 1.3 E+2 1.5 E+1 6 E+1 1.5 E+2 ~

fit0-0)

Cs-137 1.8 E+1 6 E-2 1.5 E+2 1.8 E+1 8 E+1 1.8 E+2 Ba-140 6 E+1 6 E+1 ar fi La-140 1.5 E+1 1.5 E+1 g

a. See the definition of MINIMUM DETECTABLE CONCENTRATION in Section 10.1. Other peaks which are measurable and identifiable as plant effluents, together with the radionuclides in this table, shall be analyzed and reported in accordance with Section 7.1.

3-01 o'

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b. If no drinking water pathway exists, a value of 3 E+3 pCi/L may be used.

c. If no drinking water pathway exists, a value of 1.5 E+1 pCill may be used.

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VEGPODCM 4.1.2 Land Use Census A land use census shall be conducted and shall identify the following within a distance of 5 miles in each of the 16 meteorological sectors: the location of the nearest milk animal,1 the nearest permanent residence, and the nearest garden of greater than 500 square feet producing broad leafy vegetation. Land within the Savannah River Site is excluded from this census.

4.1.2.1 Applicability This control applies at all times.

4.1.2.2 Actions 4.1.2.2.1 With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than values currently being calculated in accordance with Section 3.4.3, identify the new location(s) in the next Radioactive Effluent Release Report.

4.1.2.2.2 With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Section 4.1.1, add the new location(s) to the REMP within 30 days if samples are available. The sampling location, excluding control station location(s), having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from the REMP if new sampling locations are added. Pursuant to Technical Specification 5.5.1 submit in the next Radioactive Effluent Release Report any change(s) in the ODCM, including the revised figure(s) and table(s) reflecting any new location(s) and information supporting the change(s).

4.1.2.2.3 This control does not affect shutdown requirements or MODE changes.

4.1.2.3 Surveillance Requirements The land use census shall be conducted annually, using that information which will provide good results, such as a door-to-door census, a visual census from automobile or aircraft, consultation with local agriculture authorities, or some combination of these methods, as feasible. Results of the land use census shall be included in the Annual Radiological Environmental Operating Report.

4.1.2.4 Basis This control is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the REMP are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part SO.

Restricting the census to gardens of greater than 500 tr 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 kgly) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the Defined as a cow or goat that is producing milk for human consumption.

4-9 Rev. 18 l

_.,~--,------

VEGPODCM following assumptions were made: (1) 20 percent of the garden was used for growing broad leaf 2

vegetation (i.e., similar to lettuce and cabbage) and (2) a vegetation yield of 2 kg/m was obtained.

4.1.3 Interlaboratory Comparison Program Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison P.rogram which satisfies the requirements of Regulatory Guide 4.15, Revision 1, February, 1979.

4.1.3.1 Applicability This control applies at all times.

4.1.3.2 Actions With analyses not being performed as required by Section 4.1.3, report the corrective actions taken to prevent a recurrence in the Annual Radiological Environmental Operating Report.

This control does not affect shutdown requirements or MODE changes.

4.1.3.3 Surveillance Requirements A summary of the results obtained as part of the required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.

4.1.3.4 ~sis 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 material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring, in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2, Appendix I, 10 CFR 50.

4-10 Rev. 18

VEGPODCM 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Table 4-4, and Figure 4-1 through Figure 4-4 specify the locations at which the measurements and samples are taken for the REMP required by Section 4.1.1.

4-11 Rev. 18

VEGPODCM Table 4-4. Radiological Environmental Monitoring Locations Location Descriptive Location Direction Distance Sample Number (miles) Type(1) 1 River Bank N 1.1 D 2 River Bank NNE 0.8 D 3 Discharge Area NE 0.6 A 3 River Bank NE 0.7 D 4 River Bank ENE 0.8 D 5 River Bank E 1.0 D 6 Plant Wilson ESE 1.1 D 7 Simulator Building SE 1.7 D,V,A 8 River Road SSE 1.1 D 9 River Road S 1.1 D 10 Met Tower SSW 0.9 A 10 River Road SSW 1.1 D 11 River Road SW 1.2 D 12 River Road WSW 1.2 D,A 13 River Road W 1.3 D 14 River Road WNW 1.8 D 15 Hancock Landing Road NW 1.5 D,V 16 Hancock Landing Road NNW 1.4 D,A 17 Savannah River Site, River Road N 5.4 D 18 Savannah River Site, D Area NNE 5.0 D 19 Savannah River Site, Road A.13 NE 4.6 D 20 Savannah River Site, Road A.13.1 ENE 4.8 D 21 Savannah River Site, Road A.17 E 5.3 D 22 River Bank Downstream of Buxton ESE 5.2 D Landing 23 River Road SE 4.6 D 24 Chance Road SSE 4.9 D 25 Chance Road near Highway 23 S 5.2 D 26 H~hway 23 and Ebenezer Church SSW 4.6 D R.

4-12 Rev. 18

VEGP ODCM Table 4-4 (contd). Radiological Environmental Monitoring Locations Location Descriptive Location Direction Distance Sample Number (miles) Type(1) 27 Highway 23, opposite Boll Weevil SW 4.7 D Road 28 Thomas Road WSW 5.0 D 29 Claxton-Lively Road W 5.1 D 30 Nathaniel Howard Road WNW 5.0 D 31 River Road at Allen's Chapel Fork NW 5.0 D 32 River Bank NNW 4.7 D 35 Girard SSE 6.6 D,A 36 GPC Waynesboro Operating WSW 13.9 D,A Headquarters 37 Substation; Waynesboro, GA WSW 16.7 D,V 43 Employees Recreation Area SW 2.2 D 47 Oak Grove Church SE 10.4 D 48 McBean Cemetery NW 10.2 D 51 SGA School; Sardis, GA S 11.0 D 52 Oglethorp Substation; SW 10.7 D Alexander, GA 80 Augusta Water Treatment Plant NNW 29.0 W(2) 81 Savannah River N 2.5 F(3),S(4) 82 Savannah River (RM 151.2) NNE 0.8 R 83 Savannah River (RM 150.4) ENE 0.8 R,S(4) 84 Savannah River (RM 149.5) ESE 1.6 R 85 Savannah River ESE 4.3 F(3) 87 Beaufort - Jasper Water Treatment SE 76.0 W(5)

Plant; Beaufort, SC 88 Cherokee Hill Water Treatment SSE 72.0 W(6)

Plant; Port Wentworth, GA 98 W.C. Dixon Dairy SE 9.8 M 99 Boyceland Dairy W 20.9 M 4-13 Rev. 18

VEGPODCM Table 4-4 (cont.) Radiological Environmental Monitoring Locations TABLE NOTATIONS (1) Sample Types:

A - Airborne Radioactivity o - Direct Radiation F - Fish M-Milk R - River Water S - River Shoreline Sediment W - Drinking Water (at water treatment plant)

V - Vegetation (2) The intake for the Augusta Water Treatment Plant is located on the Augusta Canal. The entrance to this canal is at river mile (RM) 207 on the Savannah River. The canal effectively parallels the river. The intake to the pumping station is about 4 miles down the canal and only 0.1 mile from the river (across land).

(3) About a 5-mile stretch of the river is generally needed to obtain adequate fish samples.

Samples are normally gathered between RM 153 and 158 for upriver collections and between RMs 144 and 149.4 for downriver collections.

(4) Sediment is collected at locations with existing or potential recreational value. High water shifting of the river bottom or other reasons could cause a suitable location for sediment collection to become unavailable or unsuitable. Thus, a stretch of river between RM 148.5 and 150.5 is designated for downriver sediment collections, while a stretch between RM 153 and 154 is designated for upriver collections. In practice, collections are normally made at RM 150.2 for downriver collections and at RM 153.3 for upriver collections.

(5) The intake for the Beaufort-Jasper Water Treatment Plant is located at the end of a canal which begins at RM 39.3 on the Savannah River. This intake is about 16 miles by line of sight down the canal from its beginning on the Savannah River.

(6) The intake for the Cherokee Hill Water Treatment Plant is located on Abercorn Creek, which is about one and a quarter creek miles from its mouth on the Savannah River at RM 29.

4-14 Rev. 18

VEGPODCM r - - - - - - - - - - - - - - - - .- - - - - - - - - - - - - - ,

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Figure 4-1. Terrestrial Stations Near Site Boundary 4-15 Rev. 18

VEGPODCM

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, *I WILa Figure 4-2. Terrestrial Stations and Aquatic Stations, 0-5 Miles 4-16 Rev. 18 L

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Figure 4-3. Terrestrial Stations Beyond 5 Miles 4-17 Rev. 18

VEGPODCM rAUGUSTA WATI" IATMINT PLANT

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SOUTH CAROLINA c.... , ., A...,

GEORGIA o '0 JO JO @

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_ATIA TREATMENT PL.ANT 1t'O'" WEWTWO"TMI

'AVAWfIIA Figure 4-4. Drinking Water Stations 4-18 Rev. 18

VEGPODCM CHAPTERS TOTAL DOSE DETERMINATIONS 5.1 LIMIT OF OPERATION In accordance with Technical Specification 5.5.4.j, the dose or dose commitment to any MEMBER OF THE PUBLIC over a calendar year, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

5.1.1 Applicability This limit applies at all times.

5.1.2 Actions With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Section 2.1.3, 3.1.3, or 3.1.4, calculations shall be made according to Section 5.2 methods to determine whether the limits of Section 5.1 have been exceeded. If these limits have been exceeded, prepare and submit a special report to the Nudear Regulatory Commission within 30 days, which defines the corrective actions to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of section 5.1 and indudes the schedule for achieving conformance with the limits of Section 5.1. This special report, as defined in 10 CFR 20.2203, shall also indude an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources (induding all effluent pathways and direct radiation) for the calendar year that indudes the release(s) covered by this report. This special report shall also describe the 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 limits of Section 5.1, and if the release condition resulting in violation of the provisions of 40 CFR 190 has not already been corrected, the special report shall indude a request for variance in accordance with the provisions of 40 CFR 190 and induding the specified information of 40 CFR 190.11 (b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

This control does not affect shutdown requirements or MODE changes.

5.1.3 Surveillance Requirements Cumulative dose contributions from liqUid and gaseous effluents and from direct radiation shall be determined in accordance with Section 5.2. This requirement is applicable only under the conditions set forth above in Section 5.1.2.

5.1.4 Basis This control is provided to meet the dose limitations and reporting requirements of 40 CFR 190.

The control requires the preparation and submittal of a special report whenever the calculated doses from plant radioactive effluents exceed the limits of Section 5.1. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design 5-1 Rev. 18

VEGPODCM objectives of Appendix I and if direct radiation doses from the units, such as direct exposure from outside storage tanks, are kept small. The special report will describe a course of action which should result in the limitation of dose to a MEMBER OF THE PUBLIC for a calendar year to within the 40 CFR 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 uranium fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the special report with a request for variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203(a)(4),

is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation as addressed in other sections of this ODCM. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.

5-2 Rev. 18

VEGPODCM 5.2 DEMONSTRATION OF COMPLIANCE There are no other uranium fuel cycle facilities within 5 miles of the plant site. Therefore, for the purpose of demonstrating compliance with the limits of Section 5.1, the total dose to a MEMBER OF THE PUBLIC in the vicinity of the plant site due to uranium fuel cycle sources shall be determined as follows:

(5.1) where:

On< = the total dose or dose commitment to the total body or organ k, in mrem.

DL = the dose to the same organ due to radioactivity discharged from the plant site in liquid effluents, calculated in accordance with Section 2.4.1, in mrem.

DG = the dose to the same organ due to non-noble-gas radionuclides discharged from the plant site in gaseous effluents, calculated for the controlling receptor in accordance with Section 3.4.3, in mrem.

Do = the direct radiation dose to the whole body of an individual at the controlling receptor location, due to radioactive materials retained within the plant site, in mrem. Values of direct radiation dose may be determined by measurement, calculation, or a combination of the two.

ON = the external whole body dose to an individual at the controlling receptor location, due to gamma ray emissions from noble gas radionuclides discharged from the plant site in gaseous effluents, in mrem. ~ is calculated as follows (equation adapted from Reference 1, page 22, by re-casting in cumulative dose form):

DN =3.17Xl0-8~{(XIQ).. ~[KI.Q..l} (5.2) where:

3.17 x 10-a =a units conversion factor: 7 1 y/(3.15 x 10 s).

Oiv = the cumulative release of noble gas radionuclide i from release pathway v (J1Ci), during the period of interest.

~ = the total-body dose factor due to gamma emissions from noble gas radionuclide i (mrem/y)/(I1CVm;, from Table 3-5.

(XlQ)vp = annual average relative dispersion factor for release pathway v, at the location of the controlling receptor, from Table 3-7 [sImi.

5-3 Rev. 18

VEGPODCM As defined above, DL and DG are for different age groups, while Do and DN are not age group specific. When a more precise determination of OTk is desired, values of DL and DG may be calculated for all four age groups, and those values used in equation (5.1) to determine age group specific values of ~; the largest value of ~ for any age group may then be compared to the limits of Section 5.1.

5-4 Rev. 18

VEGPODCM CHAPTER 6 POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY 6.1 REQUIREMENT FOR CALCULATION To support the reporting requirements of Section 7.2.2.3, 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 shall be performed as specified in Section 6.2, at least once per calendar year.

6.2 CALCULATIONAL METHOD For the purpose of performing the calculations reqUired in Section 6.1, the dose to a member of the public inside the SITE BOUNDARY shall be determined at the locations, and for the receptor age groups, defined in Table 6-1. The dose to such a receptor at anyone of the defined locations shall be determined as follows:

(6.1) where:

D1k = the total dose to the total body or organ k, in mrem.

DA = the dose to the same organ due to inhalation of non-noble-gas radionuclides discharged from the plant site in gaseous effluents, calculated in accordance with Section 3.4.3, in mrem. The (X1Q) value to be used is given for each receptor location in Table 6-1; depleted (X1Q) values may be used in calculations for non-noble-gas radionuclides.

Os = the dose to the same organ due to ground Diane deoos"ion of non-noble-gas radionuclides discharged from the plant site in gaseous effluents, calculated in accordance with Section 3.4.3, in mrem. The (D/Q) value to be used is given for each receptor location in Table 6-1.

Dp = the external whole body dose due to gamma ray emissions from noble gas radio-nuclides discharged from the plant site in gaseous effluents, calculated using equation (5.2), in mrem. The (XiO) values that are to be used are given for each receptor location in Table 6-1.

Fa = the occupancy factor for the given location, which is the fraction of the year that one individual MEMBER OF THE PUBLIC is assumed to be present at the receptor location [unitless). Values of Fa for each receptor location are included in Table 6-1.

6-1 Rev. 18

VEGPODCM Table 6-1. Attributes of Member of the Public Receptor Locations Inside the Site Boundary Location: Visitors Center, SE at 447 meters Age Group: Child Occupancy Factor: 4.57 x 10-4 (based on 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per year)

Dispersion and Deposition Parameters:

Parameter Ground-Level Mixed-Mode Undepleted (XlO), slm 3 5.93 E-6 7.12 E-7 Depleted (XlO), slm3 5.58 E-6 6.74 E-7 (0/0), m-2 2.28 E-8 5.77 E-9 6-2 Rev. 18

D VEGPODCM CHAPTER 7 REPORTS 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 7.1.1 Requirement for Report In accordance with Technical Specification 5.6.2, the Annual Radiological Environmental Operating Report covering the REMP activities during the previous calendar year shall be submitted before May 15 of each year. (A single report fulfills the requirements for both units.)

The material provided shall be consistent with the objectives outlined in section 4.1 and section 7.1.2 of the ODCM, and in Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

7.1.2 Report Contents The materials specified in the following sub-sections shall be included in each Annual Radiological Environmental Operating Report:

7.1.2.1 Data The report shall include summarized and tabulated results of all REMP samples required by Table 4-1 taken during the report period, in a format similar to that contained in Table 3 of the Radiological Assessment Branch Technical Position (Reference 19); the results for any additional samples shall also be reported. In the event that some 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. The results for naturally-occurring radionuclides not included in plant effluents need not be reported.

7.1.2.2 Evaluations Interpretations and analyses of trends of the results shall be included in the report, including the following: (a~ appropriate) comparisons with pre-operational studies, operational controls, and previous environmental reports; and an assessment of any observed impacts of the plant operation on the environment. If the measured level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 4-2 is not the result of plant effluents, the condition shall be described as required by Section 4.1.1.2.2.

7.1.2.3 Programmatic Information Also to be included in each report are the following: a summary description of the REMP; a map(s) of all sampling locations keyed to a table giving distances and directions from a point midway between the centers of the two reactors; the results of land use censuses required by Section 4.1.2; and the results of licensee participation in the Interlaboratory Comparison Program reqUired by Section 4.1.3.

7.1.2.4 Descriptions of Program Deviations Discussions of deviations from the established program must be included in each report, as follows:

7-1 Rev. 18

VEGPODCM 7.1.2.4.1 If the REMP is not conducted as required in Table 4-1, a description of the reasons for not conducting the program as required, and the plans for preventing a recurrence, must be included in the report.

7.1.2.4.2 If the MDCs required by Table 4-3 are not achieved, the contributing factors must be identified and described in the report.

7.1.2.4.3 If Interlaboratory Comparison Program analyses are not performed as required by Section 4.1.3, the corrective actions taken to prevent a recurrence must be included in the report.

7-2 Rev. 18

VEGPODCM 7.2 RADIOACTIVE EFFLUENT RELEASE REPORT 7.2.1 Requirement for Report In accordance with Technical Specification 5.6.3, the Radioactive Effluent Release Report covering the operation of the units during the previous calendar year of operation shall be submitted in accordance with 10 CFR Part 50.36a. (A single submittal may be made for Units 1 and 2. However, the submittal shall specify the releases of radioactive material in liquid and gaseous effluents from each unit and solid radioactive waste from the site.) The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units. The material provided shall be consistent with the objectives outlined throughout this aDCM and the Process Control Program (PCP) and in conformance with 10 CFR Part 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part SO.

7.2.2 Report Contents The materials specified in the following sub-sections shall be included in each Radioactive Effluent Release Report:

7.2.2.1 Quantities of Radioactive Materials Released The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units as outlined in NRC 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 liquid and gaseous effluent data summarized on a quarterly basis and solid radioactive waste data summarized on a semiannual basis following the format of Appendix B thereof.

Unplanned releases of radioactive materials in gaseous and liquid effluents from the site to UNRESTRICTED AREAS shall be included in the report, tabulated either by quarter or by event.

For gamma emitters released in liquid and gaseous effluents, in addition to the principal gamma emitters for which MDCs are specifically established in Table 2-3 and Table 3-3, other peaks which are measurable and identifiable also shall be identified and reported.

7.2.2.2 Meteorological Data The report shall include 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 of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape; or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the 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.

7.2.2.3 Dose Assessments The report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from each unit during the previous calendar year. Historical annual average meteorology or 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. This assessment of 7-3 Rev. 18

VEGPODCM radiation doses shall be performed in accordance with Sections 2.1.3, 2.4, 3.1.3, 3.1.4, 3.4.2, 3.4.3, 5.1, and 5.2.

If a determination is required by Section 5.1.2, the report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases 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 190, Environmental Radiation Protection Standards for Nuclear Power Operation; this dose assessment must be performed in accordance with Chapter 5. The 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; this assessment must be performed in accordance with C\:1apter 6. All assumptions used in making these assessments (i.e., specific activity, exposure time, and location) shall be included in the report.

7.2.2.4 Solid Radwaste Data For each type of solid waste shipped offsite during the report period, the following information shall be included:

a. Waste volume,

b. Total curie quantity (specify whether determined by measurement of estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity),

f. Solidification agent (e.g., cement, urea formaldehyde) and

g. Class of solid wastes (as defined by 10 CFR Part 61.)

7.2.2.5 Licensee Initiated Document Changes Licensee initiated changes shall be submitted to the Nuclear Regulatory Commission as a part of or concurrent with the Radioactive Effluent Release Report for the period in which any changes were made. Such changes to the ODCM shall be submitted pursuant to Technical Specification 5.5.1. This requirement includes:

7.2.2.5.1 Any changes to the sampling locations in the radiological environmental monitoring program, including any changes made pursuant to Section 4.1.1.2.3. Documentation of changes made pursuant to Section 4.1.1.2.3 shall include supporting information identifying the cause of the unavailability of samples.

7.2.2.5.2 Any changes to dose calculation locations or pathways, including any changes made pursuant to Section 4.1.2.2.2.

7.2.2.6 Descriptions of Program Deviations Discussions of deviations from the established program shall be included in each report, as follows:

7-4 Rev. 18

VEGPODCM 7.2.2.6.1 The report shall include deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, respectively. The report shall include an explanation as to why the inoperability of the liquid or gaseous effluent monitoring instrumentation was not corrected within the specified time requirement.

7.2.2.6.2 The report shall include a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 5.5.12.

7.2.2.7 Major Changes to Radioactive Waste Treatment Systems As required by Sections 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report covering the period in which the change was reviewed and accepted for implementation. 1 The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional supplemental information;

c. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;

d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license applications and amendments thereto;

e. An evaluation of the change which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license applications and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;

g. An estimate of the exposure to plant operating personnel as a result of the change; and

h. Documentation of the fact that the change was reviewed and found acceptable by the PRB.

In lieu of inclusion in the Radioactive Effluents Release Report, this same information may be submitted as part of the annual FSAR update.

7-5 Rev. 18

VEGPODCM 7.3 MONTHLY OPERATING REPORT This ODCM establishes no requirements pertaining to the Monthly Operating Report.

7.4 SPECIAL REPORTS Special reports shall be submitted to the Nuclear Regulatory Commission as required by Sections 2.1.3.2, 2.1.4.2, 3.1.3.2, 3.1.4.2, 3.1.5.2, 4.1.1.2.2, and 5.1.2.

7-6 Rev. 18

VEGPODCM CHAPTER 8 METEOROLOGICAL MODELS The models presented in this chapter are those which were used to compute the specific values of meteorology-related parameters that are referenced throughout this ODCM. These models should also be used whenever it is necessary to calculate values of these parameters for new locations of interest.

Note: Although Plant Vogtle has no pure elevated releases, the sections on elevated-mode calculations (8.1.2 and 8.2.2) are included for convenience in calculating mixed-mode values, and to preserve section number compatibility with the ODCMs of the other Southern Company nuclear power plants.

8.1 ATMOSPHERIC DISPERSION Atmospheric dispersion may be calculated using the appropriate form of the sector-averaged Gaussian model. Gaseous release elevations may be considered to be either at ground-level, elevated, or mixed-mode. Facility release elevations for each gaseous release point are.as indicated in Table 3-4.

8.1.1 Ground-Level Releases Relative concentration calculations for ground-level releases, or for the ground-level portion of L[

mixed-mode releases, shall be made as follows:

(XlQ)G = 2.032oKr n jk ] (8.1)

Nr jk uj LZk where:

(X1Q)G =the ground-level sector-averaged relative concentration for a given wind direction (sector) and distance (slm3).

2.032 =(2ht) 1/2 divided by the width in radians of a 22.50 sector, which is 0.3927 radians.

o= the plume depletion factor for all radionuclides other than noble gases at a distance r shown in Figure 8-3. For noble gases, the depletion factor is unity. If an undepleted relative concentration is desired, the depletion factor is unity. Only depletion by deposition is considered since depletion by radioactive decay would be of little significance at the distances considered.

K,. = the terrain recirculation factor corresponding to a distance r, taken from Appendix A of Reference 15.

njk = the number of hours that wind of wind speed class j is directed into the given sector during the time atmospheric stability category k existed.

N= the total hours of valid meteorological data recorded throughout the period of interest for all sectors, wind speed classes, and stability categories.

8-1 Rev. 18

VEGPODCM Uj = the wind speed (mid-point of wind speed class j) at ground level (m/s).

r = the distance from release point to location of interest (m).

Lzk = the vertical standard deviation of the plume concentration distribution considering the initial dispersion within the building wake, calculated as follows:

2 b 2)1/2 l1zk +-

( 2n LZk = the lesser of OR (8.2)

J3(l1 zk )

(Jzk = the vertical standard deviation of the plume concentration distribution (m) for a given distance and stability category k as shown in Figure 8-1. The stability category is determined by the vertical temperature gradient liT/liz (oC/100 m).

7t = 3.1416 b= the maximum height of adjacent plant structure (55 m).

8.1.2 Elevated Releases Relative dispersion calculations for elevated releases, or for the elevated portion of mixed-mode releases, shall be made as follows:

(8.3) where:

(X1Q)E =the elevated release sector-averaged relative concentration for a given wind direction (sector) and distance (slm1.

~ = the plume depletion factor for all radionuclides other than noble gases at a distance r for elevated releases, as shown in Figure 8-4, Figure 8-5, and Figure 8-6. For an elevated release, this factor is stability dependent. For noble gases, the depletion factor is unity. If an undepleted relative concentration is desired, the depletion factor is unity. Only depletion by deposition is considered since depletion by radioactive decay would be of little significance at the distances considered.

8-2 Rev. 18

VEGPODCM njk = the number of hours that wind of wind speed class j is directed into the given sector during the time atmospheric stability category k existed.

Uj = the wind speed (mid-point of wind speed class j) at the effective release height h (m/s).

h= the effective height of the release (m), which is calculated as follows:

(8.4) hv = the height of the release point (m).

hI = the maximum terrain height between the release point and the point of interest (m), from Table 8-1.

hpr = the additional height due to plume rise (m) which is calculated as follows and limited by hPltmax):

h =1.44 Wo

)2/3 . (x)/3

- (8.5) pr { u d d =

hpr (max) = the lesser of:

the inside diameter of the vent (m).

OR 1.5(F; r _s-1I6 (8.6)

+5-:-)

Cv= the correction for low vent exit velocity (m), which is calculated as follows:

-d for:- <1.5 cv = OR (8.7)

W o for ---!!.. ~ 1.5 u

Fm = the'momentum flux parameter (m4/s 2), which is calculated as follows:

Fm =(w .!!..)2 0 2 (8.8)

S = the stability parameter:

8-3 Rev. 18

VEGPODCM

= 8.75 X 10-4 S-2 for-Q.5 < aT < 1.5

= 1.75 x 10-3 S-2 for 1.5 < aT <4.0

= 2.45 X 10-3 s-2 for aT> 4.0 -

All other symbols are as previously defined in Section 8.1.1.

8.1.3 Mixed-Mode Releases Relative dispersion calculations for mixed-mode releases shall be made as follows:

(XlQ)M =(1- E)* (X/Q)E + E* (XlQ)G (8.9) where:

(X1Q)M = the mixed-mode release sector-averaged relative concentration for a given wind direction (sector) and distance (slm\

E = the fraction of hours during which releases are considered as ground-level releases, calculated as follows:

W 1.0 for _0_ ~ 1.0 Uj 2.58 -1.58* (Wo uj

) for 1.0 < Wo Uj

~ 1.5 E= (8.10) 0.3-0.06'(WO uj

) for 1.5< Wo uj

~5.0 W

o for _0_ > 5.0 Uj All other symbols are as previously defined.

8-4 Rev. 18

VEGPODCM 8.2 RELATIVE DEPOSITION Plume depletion may be calculated using the appropriate form of the sector-averaged Gaussian model. Gaseous release elevations may be considered to be either at ground-level, elevated, or mixed-mode. Facility release elevations for each gaseous release points are as indicated in Table 3-4.

8.2.1 Ground-Level Releases Relative deposition calculations for ground-level releases, or for the ground-level portion of mixed-mode releases, shall be made as follows:

2.55D K (D/Q) = g r ~n (8.11)

G Nr ~ k k

where:

(D/Q)G =the ground-level sector-averaged relative deposition for a given wind direction (sector) and distance (m-2).

2.55 = the inverse of the number of radians in a 22.5° sector

[= (21t 116f1].

the deposition rate at distance r, taken from Figure 8-7 for ground-level releases (m-1).

the number of hours in which the wind is directed into the sector of interest, and during which stability category k exists.

All other symbols are as defined previously in Section Section 8.1.

8.2.2 Elevated Releases Relative deposition calculations for elevated releases, or for the elevated portion of mixed-mode releases, shall be made as follows:

(8.12) where:

(D/Q)E =the elevated-plume sector-averaged relative deposition for a given wind direction (sector) and distance (m-2).

Oak = the elevated plume deposition rate at distance r, taken from Figure 8-8, Figure 8-9, or Figure 8-10, as appropriate to the elume effective release height h defined in Section 8.1.2, for stability class k (m- ).

All other symbols are as defined previously.

8-5 Rev. 18

VEGPODCM 8.2.3 Mixed-Mode Releases Relative deposition calculations for mixed-mode releases shall be made as follows:

(D/Q)M =(1- E) . (D/Q)E + E . (D/Q)G (8.13) where:

(D/Q)M =the mixed-mode release sector-averaged relative deposition for a given wind direction (sector) and distance (m-2).

E= the fraction of hours during which releases are considered as ground-level releases, defined in section 8.1.3.

All other symbols are as previously defined.

8.3 ELEVATED PLUME DOSE FACTORS These factors are not required in effluent dose calculations for VEGP.

8-6 Rev. 18

~-

I I I I

-l Dist.

(m)

N I NNE NE ENE E ESE SE SSE S ISSW SW IWSW W WNW NW INNW Ql cr CD ex>

I 500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 8.7 5.7 1.4 5.8 5.7 3.5 1,000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 16.7 13.4 3.3 10.4 11.8 6.8 -t (1) 1,500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 21.7 18.6 7.3 12.2 14.3 7.3 Ql S'

2,000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 21.7 18.6 7.3 12.2 14.3 7.3 m CD 2,500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 21.7 18.6 7.3 12.2 14.3 7.3 <

!!1.

c)'

3,000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 23.7 18.6 7.3 12.2 14.3 7.3 ::J 0"

3,500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 24.4 18.6 7.3 12.2 16.9 7.3 0 (1) 4,000 0.0 0.0 0.0 0.0 0.0 0.0 4.5 0.0 0.0 4.7 24.4 18.6 7.3 12.2 16.9 7.3 "0 5,000 0.0 0.0 0.0 0.0 0.0 0.0 11.1 0.0 0.0 4.7 24.7 18.6 7.3 12.2 16.9 7.3 ...enm

J ep 6,000 0.0 0.0 0.0 0.0 0.0 0.0 11.1 0.0 0.0 4.7 26.8 18.6 7.3 12.2 16.9 7.3 ;:::0:

(1)

'"'-l G) 7,000 0.0 0.0 0.0 7.8 0.0 0.0 11.1 0.0 3.6 4.7 26.8 18.6 7.3 12.2 16.9 7.3 ii3 0.

8,000 0.0 0.0 21.113.9 0.0 0.0 11.8 0.0 14.6 4.7 26.8 18.6 7.3 12.2 16.9 7.3 (1) 9,000 0.0 0.0 24.4 14.6 0.0 0.0 12.7 7.1 14.6 5.1 26.8 18.6 7.3 12.2 16.9 7.3 10,000 0.0 10.2 24.4 20.2 0.0 0.0 17.1 17.0 14.6 6.8 26.8 18.6 7.3 12.2 16.9 7.3 12,000 0.0 15.9 26.8 20.2 0.0 0.0 17.1 19.5 14.6 6.8 34.1 28.9 13.4 12.2 16.9 7.3 14,000 0.0 15.9 26.8 20.2 0.0 0.0 17.1 19.5 14.6 6.8 34.1 28.9 13.4 16.5 19.7 7.3 16,000 0.0 15.9 26.8 21.7 13.2 0.0 17.1 19.5 14.6 6.8 34.1 28.9 13.4 16.5 25.7 7.3 m

G)

Data in this table are obtained from Reference 11. "lJ o

o w

()

s:

ex>

i J. , I

VEGPODCM 1000 I'

I I'

1I / 1.;0 ....

/

~

/ vv V io"~

~

IA) ~

~

100

'./ .....

V' ./

i

~ .JJ V V i

V~ 10-'

/ V V V V v:;:

l.- ~

V ~ ~

~

10' V :....'~ V

\0

./ 10' 1-' -'

/ ./ i"'"

./ V V/ V V

1 0.1 1.0 10 100 PLUME TRAVEL DISTANCE IKIL.OIIETERSJ Range of vertical Range of Vertical Category Temperature Gradient Temperature Gradient (OC/l00 m) (OF/l00 ft)

A AT/Az < -1.9 AT/Az < -1.0 B -1.9 s AT/AZ < -1.7 -1.0 s AT/Az < -0.9 C -1. 7 s AT/AZ < -1.5 -0.9 s AT/Az < -0.8 D -1.5 s AT/Az < -0.5 -0.8 s AT/Az < -0.3 E -0.5 s AT/Az < 1.5 -0.3 s AT/AZ < 0.8 F 1.5 s AT/Az < 4.0 0.8 s AT/Az < 2.2 G 4.0 s AT/Az 2.2 s AT/Az This Figure 8-1. Vertical Standard Deviation of Material in a Plume (crz) 8-8 Rev. 18

VEGPODCM This figure Intentionally left blank.

Refer to the definition for I<,. (terrain recirculation factor) in section 8.1.1 for applicable plant data.

Figure 8-2. Terrain Recirculation Factor (1<,.)

8-9 Rev. 18

VEGPODCM U .... '" ..-..... r---..

III U ~

~ 1""01'00

I 0.7

u 1'0..

ic

~

D.I ic CIA

0... .

o.z 0.1 0.1 This graph is reproduced from Reference 5 (Figure 2).

Figure 8*3. Plume Depletion Effect for Ground Level Releases 8-10 Rev. 18

VEGPODCM

,.0 U

lu cOol t--+--+--+-++++-H---+--+-+-+-II-H++--~

UNIT_~~~

I'

~

I~ o.s a.z \

0.'

This graph is reproduced from Reference 5 (Figure 3).

Figure 8-4. Plume Depletion Effect for 30-Meter Releases 8-11 Rev. 18

VEGPODCM Ut I'I'MLI i""'l

~J u I'ii ~

~-ur::

.~~ .....

ra- ""' ~ "'I-.

"- ~

lr..

.\.

\

0.1 0.1 .... -.0 This graph is reproduced from Reference 5 (Figure 4) .

Figure 8-5. Plume Depletion Effect for 50-Meter Releases 8-12 Rev. 18

VEGPODCM

... r-... ~

~

i"'- ~ ... IIIIUntAL D)

~ r--..... .....

u.TMU CA.8.m ~ ~ !"lll

..,.MUI",,,,I NO D8'LITlON ~ ~

CPMC'I'ICiN IlIMAININCI. , ~

I\.

\.

\

0.,

PLUMI.'nAYiL Dll'tAJICI IICILGMITIIIII This graph is reproduced from Reference 5 (Figure 5) .

Figure 8*6. Plume Depletion Effect for 1DO-Meter Releases 8-13 Rev. 18

VEGPODCM

~~

'" "" I'~

I""ilo..

'" I"

~

10-7 D.1 ,~ 'D~ '00.0 zao.o PLUME TRAVEL DISTANCE (KILOMETERSI This graph is reproduced from Reference 5 (Figure 6) .

Figure 8*7. Relative Deposition for Ground-Level Releases 8-14 Rev. 18

VEGPODCM

,,!!!!A8LE 'IJ 10-4 C

Iii 2

c

'"" ~

~

If' "'" NEUTRAL

~

1/ .....

c i= 10-6 I NEUTRAL ~~

~ STABLE I

UI ~

Q

~ i""'o

~ I .....

S

...a:: I I' ~

1~ / ~ STABLE CU.G) ~

I

~

1.0 10.0 PLUME TRAVEL DISTANCE (KILOMETERS)

This graph is reproduced from Reference 5 (Figure 7).

Figure 8-8. Relative Deposition for 30-Meter Releases 8-15 Rev. 18

VEGPODCM UNSTABLE fa If'" ~

/ " """" --.. ~

/

~

10-& NEUTRAL Dt

~

"'11 C

ti

..,a::

~ I

"'0.: I"loo..

~

,I NE~--' ~

a::

~ 10-4 J ~

iii 2.., **

0 S I In IU a::

,0-7 ABLE (E"F.,(It t

,0-8 I 0.1 ,~ ,o~

PLUME TRAVEL DISTANCE (KILOMETERS)

This graph is reproduced from Reference 5 (Figure 8).

Figure 8*9. Relative Deposition for 60-Meter Releases 8-16 Rev. 18 l

VEGPODCM

,~

I/~

UNSTABLE CA.B.c

,0-5 V """

'" ~

C

...*a:

Iii I I

I NEUTRAL CDt .......

I I

~

~a:

~ ,cre / ~

I.c..

~

I I

I

~

&U STABLE (E.F.ot a:

,0-7 ~ NO DEPLETION II J

10-8 0.1

/ 1~ 'O~ 100.0 2DD~

PLUME TRAVEL DIST'ANCE (KILOMETERSt This graph is reproduced from Reference 5 (Figure 9).

Figure 8-10. Relative Deposition for 100-Meter (or Greater) Releases 8-17 Rev. 18 L

VEGPODCM CHAPTER 9 METHODS AND PARAMETERS FOR CALCULATION OF GASEOUS EFFLUENT PATHWAY DOSE FACTORS, Rmpj 9.1 INHALATION PATHWAY FACTOR For the inhalation pathway, Reipj in (mremly) per (IJ.Cilm; is calculated as follows (Reference 1, Section 5.3,1,1):

(9.1) where:

K1 = 6 the units conversion factor: 10 pCillJ.Ci.

(BR)a = the breathing rate of receptor age group a, in m3/y, from Table 9-5, (DFA)aij = the inhalation dose factor for receptor age group a, radionuclide i, and organ j, in mremlpCi, from Table 9-7 through Table 9-10.

9-1 Rev. 18

VEGPODCM 9.2 GROUND PLANE PATHWAY FACTOR 2

For the ground plane external exposure pathway, Raipj in (m .mremly) per (J.LCils) is calculated as follows (Reference 1, Section 5.3.1.2):

1 -).;t) (9.2)

Ra;pj =K J

K 2 . (SHF)' (DFG); j .

(

-~

where:

6 the units conversion factor: 10 pCilJ.LCi.

the units conversion factor: 8760 hly.

(SHF) = the shielding factor due to structure (dimensionless). The value used for (SHF) is 0.7, from (Reference 3, Table E-15).

(DFG), = the ground plane dose factor for radionuclide i and organ j, in (mremlh) per (pCilm2), from Table 9-15. Dose factors are the same for all age groups, and those for the total body also apply to all organs other than skin.

~=

the radioactive decay constant for radionuclide i, in S-1. Values of ~

used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

8 t= the exposure time, in s. The value used fort is 4.73 x 10 s (= 15 y),

from (Reference 1, Section 5.3.1.2).

9-2 Rev. 18 L

VEGPODCM 9.3 GARDEN VEGETATION PATHWAY FACTOR For radionuclides other than tritium in the garden vegetation consumption pathway, Raipj in (m2.mremly) per (J.LCi/s) is calculated as follows (Reference 1, Section 5.3.1.5):

(9.3) where:

the units conversion factor: 106 pCVJ.LCi.

r= the fraction of deposited activity retained on the edible parts of garden vegetation (dimensionless). Thevalue used for r is 1.0 for radioiodines and 0.2 for particulates, from (Reference 3, Table E-1).

Yv-- the areal density (a9ricultural productivity) of growing leafy garden vegetation, in kg/m ,from Table 9-1.

~= the radioactive decay constant for radionuclide i, in S-1. Values of ~

used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

"-w= the rate constant for removal of activity on leaf and plant surfaces by weathering, in s-t, from Table 9-1.

(DFL)aij = the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mremlpCi, from Table 9-11 through Table 9-14.

UaL = the consumption rate of fresh leafy garden vegetation by a receptor in age group a, in kg/y, from Table 9-5.

UaS = the consumption rate of stored garden vegetation by a receptor in age group a, in kgly, from Table 9-5.

fL = the fraction of the annual intake of fresh leafy garden vegetation that is grown locally (dimensionless), from Table 9-1.

fg = the fraction of the annual intake of stored garden vegetation that is grown locally (dimensionless), from Table 9-1.

l = the average time between harvest of fresh leafy garden vegetation and its consumption, in s, from Table 9-1.

tm. = the average time between harvest of stored garden vegetation and its consumption, in s, from Table 9-1.

9-3 Rev. 18

VEGPODCM 3

For tritium in the garden vegetation consumption pathway, Raipj in (mrem/y) per (J.lCilm ) is calculated as follows (Reference 1, Section 5.3.1.5), based on the concentration in air rather than deposition onto the ground:

(9.4) where:

3

~= the units conversion factor: 10 gikg.

3 H= the absolute humidity of atmospheric air, in glm , from Table 9-1.

0.75= the fraction of the mass of total garden vegetation that is water (dimensionless).

0.5= the ratio of the specific activity of tritium in garden vegetation water to that in atmospheric water (dimensionless).

and other parameters are as defined above.

9-4 Rev. 18

VEGPODCM Table 9-1. Miscellaneous Parameters for the Garden Vegetation Pathway The following parameter values are for use in calculating RaiPj for the garden vegetation pathway only. The terms themselves are defined in section 9.3.

Parameter Value Reference Y y 2.0 kg/m 2

Ref. 3, Table E-15 AW 5.73 x 10.7 S*1 Ref. 1, page 33 (14-day half-life) fL 1.0 Ref. 1, page 36 fg 0.76 Ref. 1, page 33

~ 8.6 x 104 s Ref. 3, Table E-15 (1 day) thY 5.18 x 106 s Ref. 3, Table E-15 (60 days) 3 H 8g/m Ref. 3 9-5 Rev. 18

VEGP ODCM 9.4 GRASS-CaW-MILK PATHWAY FACTOR For radionuclides other than tritium in the grass-cow-milk pathway, Raipj in (m 2.mremly) per (J.1.Cils) is calculated as follows (Reference 1, Section 5.3.1.3):

(9.5) where:

the units conversion factor: 106 pCilJ.1.Ci.

r= the traction of deposited activity retained on the edible parts of vegetation (dimensionless). The value used for r is 1.0 for radioiodines and 0.2 for particulates, from (Reference 3, Table E-1).

~= the radioactive decay constant for radionuclide i, in S-1. Values of ~ used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

A.w= the rate constant for removal of activity on leaf and plant surfaces by weathering, in S-1, from Table 9-2.

the cow's consumption rate of feed, in kg/d, from Table 9-2.

Uap = the consumption rate of cow milk by a receptor in age group a, in Uy, from Table 9-5.

Fmi = the stable element transfer coeffICient applicable to radionuclide i, for cow's milk, in cIIL, from Table 9-6.

(DFL)aij = the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mremlpCi, from Table 9-11 through Table 9-14.

the fraction of the year that the cow is on pasture (dimensionless),

from Table 9-2.

the fraction of the cow's feed that is pasture grass while the cow is on pasture (dimensionless), from Table 9-2.

the areal dens!!}' (agricultural productivity) of growing pasture feed grass, in kg/m 2, from Table 9-2.

the areal density (agricultural productivity) of growing stored feed, in kg/m 2, from Table 9-2.

tt,,;, = the transport time from harvest of stored feed to its consumption by the cow, in s, from Table 9-2.

9-6 Rev. 18

VEGPODCM tf = the transport time from consumption of feed by the cow, to consumption of milk by the receptor, in s, from Table 9-2.

For tritium in the grass-cow-milk pathway, RaiPi in (mremly) per (~CVm3) is calculated as follows (Reference 1, Section 5.3.1.5), based on the concentration in air rather than deposition onto the ground:

Raipj=KJ *Kj 'QF *Uap *Fmi . (DFL)ajj 'O.75{~) (9.6) where:

3

~= the units conversion factor: 10 glkg.

3 H= the absolute humidity of atmospheric air, in glm , from Table 9-2.

0-.75= the fraction of the mass of total vegetation that is water (dimensionless).

0.5= the ratio of the specific activity of tritium in vegetation water to that in atmospheric water (dimensionless).

and other parameters are as defined above.

9-7 Rev. 18

VEGPODCM Table 9-2. Miscellaneous Parameters for the Grass-Cow-Milk Pathway The following parameter values are for use in calculating Raipj for the grass-row-milk pathway only. The terms themselves are defined in section 9.4.

Parameter Value Reference A.w 5.73 x 10-7 S-1 Ref. 1, page 33 (14-day half-life)

OF 50 kg/d Ref. 3, Table E-3 fp 1.0 Ref. 1, page 33 fs 1.0 Ref. 1, page 33 Yp 0.7 kg/m 2

Ref. 3, Table E-15 Ys 2.0 kg/m 2

Ref. 3, Table E-15 6

t.,m 7.78 X 10 s Ref. 3, Table E-15 (90 days) tf 1.73 x 105 s Ref. 3, Table E-15 (2 days) 3 H 8g/m Ref. 3 9-8 Rev. 18

VEGPODCM 9.5 GRASS-GOAT-MilK PATHWAY FACTOR For radionuclides other than tritium in the grass-goat-milk pathway, Raipj in (m 2.mremly) per

(/lCi/s) is calculated as follows (Reference 1, Section 5.3.1.3):

Raipj -- K l ' r (A. +Aw)'

i Q U F' ap' F I'V,F:L1 mi '\, T. '/aij'

[!p!.

--y;-+ (1- !p!J e-}.,I'.]

y. *e

-}.,I/ (9.7) where:

K1 = 6 the units conversion factor: 10 pCV/lCi.

r = the fraction of deposited activity retained on the edible parts of vegetation (dimensionless). The value used for r is 1.0 for radioiodines and 0.2 for particulates, from (Reference 3, Table E-1).

~ = the radioactive decay constant for radionuclide i, in S-1. Values of ~

used in effluent calCl:llations should be based on decay data from a recognized and current source, such as Reference 20.

Aw = the rate constant for removal of activity on leaf and plant surfaces by weathering, in S-1, from Table 9-3.

OF = the goat's consumption rate of feed, in kg/d, from Table 9-3.

Uap = the consumption rate of goat milk by a receptor in age group a, in Uy, from Table 9-5.

Fmi = the stable element transfer coefficient applicable to radionuclide i, for goat's milk, in dll, from Table 9-6.

(DFl)aIj = the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mremlpCi, from Table 9-11 through Table 9-14.

fp = the fraction of the year that the goat is on pasture (dimensionless),

from Table 9-3.

fs = the fraction of the goat's feed that is pasture grass while the goat is on pasture (dimensionless), from Table 9-3.

Yp = the areal dens~ (agricultural productivity) of growing pasture feed 2

grass, in kg/m , from Table 9-3.

Ys = the areal density (agricultural productivity) of growing stored feed, in 2

kg/m , from Table 9-3.

t.,m = the transport time from harvest of stored feed to its consumption by the goat, in s, from Table 9-3.

9-9 Rev. 18

, _ .... _~---, -------

VEGPODCM tf = the transport time from consumption of feed by the goat, to consumption of milk by the receptor, in s, from Table 9-3.

3 For tritium in the grass-goat-milk pathway, Raipj in (mremly) per (J.1Cilm ) is calculated as follows (Reference 1, Section 5.3.1.5), based on the concentration in air rather than deposition onto the ground:

R .. =K *K .Q *U OIP] J 3 F op

F mj

. (DFL) .. .

01}

0.75.(°*5)

H (9.8) where:

3

~= the units conversion factor: 10 glkg.

3 H= the absolute humidity of atmospheric air, in glm , from Table 9-3.

0.75= the fraction of the mass of total vegetation that is water (dimensionless).

0.5= the ratio of the specific activity of tritium in vegetation water to that in atmospheric water (dimensionless).

and other parameters are as defined above.

9-10 Rev. 18

. . .,~._~-_._._._----------_._----_._.~------

VEGPODCM Table 9-3. Miscellaneous Parameters for the Grass-Goat-Milk Pathway The following parameter values are for use in calculating Raipj for the grass-goat-milk pathway only. The terms themselves are defined in section 9-5.

Parameter Value Reference A.w 5.73 x 10.7 S*1 Ref. 1, page 33 (14-day half-life)

OF 6 kg/d Ref. 3, Table E-3 fp 1.0 Ref. 1, page 33 fs 1.0 Ref. 1, page 33 Yp 0.7 kg/m 2

Ref. 3, Table E-15 Ys 2.0 kg/m 2

Ref. 3, Table E-15 6

tt,m 7.78 X 10 s Ref. 3, Table E-15 (90 days) tf 1.73 x 105 s Ref. 3, Table E-15 (2 days) 3 H 8g1m Ref. 3 9-11 Rev. 18

VEGPODCM 9.6 GRASS-CaW-MEAT PATHWAY FACTOR For radionuclides other than tritium in the grass-cow-meat pathway, ~ in (m2.mrernly) per (J.1Ci/s) is calculated as follows (Reference 1, Section 5.3.1.4):

(9.9) where:

the units conversion factor: 106 pCVJ.1Ci.

r= the fraction of deposited activity retained on the edible parts of vegetation (dimensionless). The value used for r is 1.0 for radioiodines and 0.2 for particulates, from (Reference 3, Table E-1).

~= the radioactive decay constant for radionuclide i, in S-1. Values of ~

used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

A.w= the rate constant for removal of activity on leaf and plant surfaces by weathering, in s-1, from Table 9-4.

the cow's consumption rate of feed, in kg/d, from Table 9-4.

Uap= the consumption rate of meat by a receptor in age group a, in kg/y, from Table 9-5.

the stable element transfer coefficient applicable to radionuclide i, for meat, in dlkg, from Table 9-6.

(DFL}aij = the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mrernlpCi, from Table 9-11 through Table 9-14.

the fraction of the year that the cow is on pasture (dimensionless),

from Table 9-4.

the fraction of the cow's feed that is pasture grass while the cow is on pasture (dimensionless), from Table 9-4.

the areal dens!t)t (agricultural productivity) of growing pasture feed grass, in kg/m2, from Table 9-4.

Ys = the areal density (agricultural productivity) of growing stored feed, in kg/m 2 , from Table 9-4.

It,m = the transport time from harvest of stored feed to its consumption by the cow, in s, from Table 9-4.

9-12 Rev. 18

VEGPODCM It = the transport time from consumption of feed by the cow, to consumption of meat by the receptor, in s, from Table 9-4.

3 For tritium in the grass-cow-meat pathway, ~j in (mremly) per (JlCilm ) is calculated as follows (Reference 1, Section 5.3.1.4), based on the concentration in air rather than deposition onto the ground:

Raipj =KJ *K3 'QF *Uap .Ffi * (DFL)aij 'O.75{~) (9.10) where:

3 1<:3= the units conversion factor: 10 glkg.

3 H= the absolute humidity of atmospheric air, in g/m , from Table 9-4.

0.75= the fraction of the mass of total vegetation that is water (dimensionless).

0.5= the ratio of the specific activity of tritium in vegetation water to that in atmospheric water (dimensionless).

and other parameters are as defined above.

9-13 Rev. 18

VEGPODCM Table 9-4. Miscellaneous Parameters for the Grass-Caw-Meat Pathway The following parameter values are for use in calculating RaiPj for the grass-caw-meat pathway only. The terms themselves are defined in section 9-6.

Parameter Value Reference A..v 5.73 x 10.7 S*1 Ref. 1, page 33 (14-day half-life)

OF 50 kg/d Ref. 3, Table E-3 fp 1.0 Ref. 1, page 33 fs 1.0 Ref. 1, page 33 Yp 0.7 kg/m 2

Ref. 3, Table E-15 Ys 2.0 kglm 2 Ref. 3, Table E-15 6

1tJm 7.78 X 10 s Ref. 3, Table E-15 (90 days) tf 1.73 x106 s Ref. 3, Table E-15 (20 days) 3 H 8g/m Ref. 3 9-14 Rev. 18

VEGPODCM Table 9-5. Individual Usage Factors Receptor Age Group Usage Factor Infant Child Teenager Adult Milk Consumption Rate, Uap 330 330 400 310 (Uy)

Meat Consumption Rate, Uap 0 41 65 110 (kg/y)

Fresh Leafy Garden Vegetation 0 26 42 64 Consumption Rate, UaL (kg/y)

Stored Garden Vegetation 0 520 630 520 Consumption Rate, UaS (kg/y)

Breathing Rate, (BR)a 1400 3700 8000 8000 3

(m /y)

All values are from Reference 3, Table E-5.

9-15 Rev. 18

VEGPODCM Table 9-6. Stable Element Transfer Data Cow Milk Goat Milk Meat Element Fm (d/Lf Fm (d/Lt Ff (d/kg)

H 1.0 E-02 1.7 E-01 1.2 E-02 C 1.2 E-02 1.0 E-01 3.1 E-02 Na 4.0 E-02 4.0 E-02 3.0 E-02 P 2.5 E-02 2.5 E-01 4.6 E-02 Cr 2.2 E-03 2.2 E-03 2.4 E-03 Mn 2.5 E-04 2.5 E-04 8.0 E-04 Fe 1.2 E-03 1.3 E-04 4.0 E-02 Co 1.0 E-03 1.0 E-03 1.3 E-02 Ni 6.7 E-03 6.7 E-03 5.3 E-02 Cu 1.4 E-02 1.3 E-02 8.0 E-03 Zn 3.9 E-02 3.9 E-02 3.0 E-02 Br 5.0 E-02 5.0 E-02 2.6 E-02 Rb 3.0 E-02 3.0 E-02 3.1 E-02 Sr 8.0 E-04 1.4 E-02 6.0 E-04 y 1.0 E-05 1.0 E-05 4.6 E-03 Zr 5.0 E-06 5.0 E-06 3.4 E-02 Nb 2.5 E-03 2.5 E-03 2.8 E-01 Mo 7.5 E-03 7.5 E-03 8.0 E-03 Tc 2.5 E-02 2.5 E-02 4.0 E-01 Ru 1.0 E-06 1.0 E-06 4.0 E-01 Rh 1.0 E-02 1.0 E-02 1.5 E-03 Ag 5.0 E-02 5.0 E-02 1.7 E-02 Sb 1.5 E-03 1.5 E-03 4.0 E-03 Te 1.0 E-03 1.0 E-03 7.7 E-02 I 6.0 E-03 6.0 E-02 2.9 E-03 Cs 1.2 E-02 3.0 E-01 4.0 E-03 Ba 4.0 E-04 4.0 E-04 3.2 E-03 La 5.0 E-06 5.0 E-06 2.0 E-04 Ce 1.0 E-04 1.0 E-04 1.2 E-03 Pr 5.0 E-06 5.0 E-06 4.7 E-03 Nd 5.0 E-06 5.0 E-06 3.3 E-03 W 5.0E-04 5.0 E-04 1.3 E-03 Np 5.0 E-06 5.0 E-06 2.0 E-04

Values from Reference 3 (Table E-1) except as follows: Reference 2 (Table C-

5) for Br and Sb.

+- Values from Reference 3, Table E-2 for H, C, P, Fe, Cu, Sr, I, and Cs in goat milk, and Table E-1 for all other elements in cow milk, except as follows:

Reference 2 (Table C-5) for Br and Sb in cow milk.

9-16 Rev. 18

VEGP aDCM Table 9-7. Inhalation Dose Factors for the Infant Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 No Data 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 No Data No Data No Data 1.15E-05 Cr-51 No Data No Data 6.39E-Q8 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 No Data 1.81E-05 3.56E-06 No Data 3.56E-Q6 7. 14E-04 5.04E-06 Mn-56 No Data 1.10E-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 Co-58 No Data 8.71E-07 1.30E-06 No Data No Data 5.55E-04 7.95E-06 Co-60 No Data 5.73E-06 8.41E-06 No Data No Data 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 No Data No Data 5.80E-06 3. 58E-05 Cu-64 No Data 1.34E-09 5.53E-10 No Data 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 No Data 2.87E-11 1.05E-06 9.44E-06 Br-83 No Data No Data 2.72E-07 No Data No Data No Data No Data Br-84 No Data No Data 2.86E-07 No Data No Data No Data No Data Br-85 No Data No Data 1.46E-08 No Data No Data No Data No Data Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06 Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07 Rb-89 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.87E-08 Sr-89 2.84E-04 No Data 8.15E-06 No Data No Data 1.45E-03 4.57E-05 Sr-90 2.92E-02 No Data 1.85E-03 No Data No Data 8.03E-03 9.36E-05 Sr-91 6.83E-08 No Data 2.47E-09 No Data No Data 3.76E-05 5.24E-05 All values are in (mremlpCi inhaled). They are obtained from Reference 3 (Table E-10). Neither Reference 2 nor Reference 3 contains data for Rh-105, Slr124, or S1r125.

9-17 Rev. 18

~~~--~--,--~---_._-~~- -----------------

VEGPODCM Table 9-7 (contd). Inhalation Dose Factors for the Infant Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Sr-92 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.00E-04 Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05 Y-91m 2.91E-10 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 No Data 1.12E-05 No Data No Data 1.75E-03 5.02E-05 Y-92 1.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 Y-93 1.07E-07 No Data 2.91E-09 No Data No Data 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06 Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 No Data 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 No Data 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 No Data 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 No Data 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No Data 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-Q9 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2. 14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 9-18 Rev. 18

VEGPODCM Table 9-7 (contd). Inhalation Dose Factors for the Infant Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3. 1SE-OS 1-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-OS No Data 1.42E-06 1-131 2.71E-OS 3.17E-OS 1.40E-OS 1.06E-02 3.70E-OS No Data 7.S6E-07 1-132 1.21E-06 2.S3E-06 8.99E-07 1.21E-04 2.82E-06 No Data 1.36E-06 1-133 9.46E-06 1.37E-OS 4.00E-06 2.54E-03 1.60E-OS No Data 1.54E-06 1-134 6.S8E-07 1.34E-06 4.7SE-07 3. 18E-QS 1.49E-06 No Data 9.21E-07 1-13S 2.76E-06 S.43E-06 1.98E-06 4.97E-04 6.0SE-06 No Data 1.31E-06 Cs-134 2.83E-04 S.02E-04 S.32E-OS No Data 1.36E-04 S.69E-OS 9.S3E-07 Cs-136 3.4SE-OS 9.61E-OS 3.78E-OS No Data 4.03E-OS 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.2SE-OS No Data 1.23E-04 S.09E-OS 9.S3E-07 Cs-138 3.61E-07 S.S8E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 No Data 4.23E-13 4.2SE-06 3.64E-OS Ba-140 4.00E-OS 4.00E-08 2.07E-06 No Data 9.S9E-09 1.14E-03 2.74E-OS Ba-141 1.12E-10 7.70E-14 3.SSE-12 No Data 4.64E-14 2. 12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 No Data 1.36E-14 1.11E-06 4.9SE-07 La-140 3.61E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-Q4 6.06E-QS La-142 7.36E-10 2.69E-10 6.46E-11 No Data No Data S.87E-06 4.2SE-OS Ce-141 1.98E-OS 1.19E-OS 1.42E-06 No Data 3.7SE-06 3.69E-04 1.54E-OS Ce-143 2.09E-07 1.38E-07 1.S8E-08 No Data 4.03E-08 8.30E-OS 3.SSE-OS Ce-144 2.28E-03 8.6SE-04 1.26E-04 No Data 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-OS 3.74E-06 4.99E-07 No Data 1.41E-06 3.09E-04 2.66E-OS Pr-144 3.42E-11 1.32E-11 1.72E-12 No Data 4.80E-12 1.1SE-06 3.06E-06 Nd-147 S.67E-06 S.81E-06 3.S7E-07 No Data 2.2SE-06 2.30E-04 2.23E-OS W-187 9.26E-09 6.44E-09 2.23E-09 No Data No Data 2.83E-OS 2.54E-OS Np-239 2.6SE-07 2.37E-08 1.34E-08 No Data 4.73E-08 4.2SE-OS 1.78E-OS 9-19 Rev. 18 L

VEGPODCM Table 9-8. Inhalation Dose Factors for the Child Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 Cr-51 No Data No Data 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71E-06 4.26E-04 6.19E-06 Mn-56 No Data 4.48E-10 8.43E-11 No Data 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 No Data No Data 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 No Data No Data 3.43E-04 1.91E-05 Co-58 No Data 4.79E-07 8.55E-07 No Data No Data 2.99E-04 9.29E-06 Co-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 No Data No Data 2.21E-06 2.27E-05 Cu-64 No Data 5.39E-10 2.90E-10 No Data 1.63E-09 2. 59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 No Data 1.58E-11 3.84E-07 2.75E-06 Br-83 No Data No Data 1.28E-07 No Data No Data No Data No Data Br-84 NO,Data No Data 1.48E-07 No Data No Data No Data No Data Br-85 No Data No Data 6.84E-09 No Data No Data No Data No Data Rb-86 No Data 5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06 Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 Rb-89 No Data 9.33E-08 7.83E-08 No Data No Data No Data 5.11E-10 Sr-89 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 4.52E-05 Sr-90 2.73E-02 No Data 1.74E-03 No Data No Data 3.99E-03 9.28E-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 All values are in (mrem/pCi inhaled). They are obtained from Reference 3 (Table E-9). Neither Reference 2 nor Reference 3 contains data for Rh-105, Sb-124, or Sb-125.

9-20 Rev. 18

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VEGPODCM Table 9-8 (contd). Inhalation Dose Factors for the Child Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Sr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05 Y-90 1.11E-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05 Y-91m 1.37E-10 No Data 4.98E-12 No Data No Data 7.60E-07 4.64E-07 Y-91 2.47E-04 No Data 6.59E-06 No Data No Data 7.10E-04 4.97E-05 Y-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 6.46E-05 Y-93 5.04E-08 No Data 1.38E-09 No Data No Data 2.01E-05 1.05E-04 Zr-95 5. 13E-05 1.13E-05 1.00E-05 No Data 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 No Data 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 No Data 2.33E-06 1.66E-04 1.00E-05 Mo-99 No Data 4.66E-08 1.15E-08 No Data 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 No Data 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 No Data 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 No Data 2.90E-07 No Data 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 No Data 1.50E-10 No Data 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.16E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-Q6 1.48E-03 2.71E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5. 19E-06 . 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5. 55E-07 3.60E-07 9-21 Rev. 18

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VEGPODCM Table 9-8 (contd). Inhalation Dose Factors for the Child Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Te-132 1.30E-07 7.36E-08 7. 12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 1-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 No Data 1.38E-06 1-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 No Data 7.68E-07 1-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 No Data 8.65E-07 1-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 No Data 1.48E-06 1-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2.58E-07 1-135 1.33E-06 2.36E-06 1.12E-06 2. 14E-04 3.62E-06 No Data 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 No Data 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3. 14E-05 No Data 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 No Data 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 No Data 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 No Data 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 No Data 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6. 1OE-05 La-142 3.50E-10 1.11E-10 3.49E-11 No Data No Data 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3. 12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 No Data 3. 17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-13 No Data 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Data 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 9-22 Rev. 18

VEGPODCM Table 9-9. Inhalation Dose Factors for the Teenager Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-08 8.95E-06 No Data No Data No Data 1.16E-05 Cr-51 No Data No Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 No Data 6.39E-06 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06 Mn-56 No Data 2.12E-10 3.15E-11 No Data 2.24E-10 1.90E-06 7.18E-06 Fe-55 4. 18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data *1.91E-04 2.23E-05 Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.68E-04 1.19E-05 Co-60 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 No Data No Data 1.17E-06 4.59E-06 Cu-64 No Data 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 No Data 7.53E-12 1.98E-07 3.56E-08 Br-83 No Data No Data 4.30E-08 No Data No Data No Data No Data Br-84 No Data No Data 5.41E-08 No Data No Data No Data No Data Br-85 No Data No Data 2.29E-09 No Data No Data No Data No Data Rb-86 No Data 2.38E-05 1.05E-05 No Data No Data No Data 2.21E-06 Rb-88 No Data 6.82E-08 3.40E-08 No Data No Data No Data 3.65E-15 Rb-89 No Data 4.40E-08 2.91E-08 No Data No Data No Data 4.22E-17 Sr-89 5.43E-05 No Data 1.56E-06 No Data No Data 3.02E-04 4.64E-05 Sr-90 1.35E-02 No Data 8.35E-04 No Data No Data 2.06E-03 9.56E-05 Sr-91 1.10E-08 No Data 4.39E-10 No Data No Data 7.59E-06 3.24E-05 All values are in (mremJpCi inhaled). They are obtained from Reference 3 (Table E-8). Neither Reference 2 nor Reference 3 contains data for Rh-105, Sb--124, or Sb--125.

9-23 Rev. 18

VEGPODCM Table 9-9 (contd). Inhalation Dose Factors for the Teenager Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Sr-92 1.19E-09 No Data 5.08E-11 No Data No Data 3.43E-06 1.49E-05 Y-90 3.73E-07 No Data 1.00E-08 No Data No Data 3.66E-05 6.99E-05 Y-91m 4.63E-11 No Data 1.77E-12 No Data No Data 4.00E-07 3.77E-09 Y-91 8.26E-05 No Data 2.21E-06 No Data No Data 3.67E-04 5.11E-05 Y-92 1.84E-09 No Data 5.36E-11 No Data No Data 3.35E-06 2.06E-05 Y-93 1.69E-08 No Data 4.65E-10 No Data No Data 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 No Data 5. 15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21E-05 Mo-99 No Data 2.11E-08 4.03E-09 No Data 5. 14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 No Data 1.12E-07 No Data 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 No Data 5.42E-11 No Data 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 No Data 1.55E-06 No Data 2.38E-05 2.01E-03 1.20E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 1.73E-06 1.64E-06 9.99E-07 No Data 3. 13E-06 8.44E-04 3.41E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8. 17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-Q6 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 9-24 Rev. 18

VEGPODCM Table 9-9 (contd). Inhalation Dose Factors for the Teenager Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Te-132 4.S0E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 S.61E-OS S.79E-OS 1-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 No Data 1.14E-06 1-131 4.43E-06 6. 14E-06 3.30E-06 1.83E-03 1.0SE-OS No Data 8.11E-07 1-132 1.99E-07 S.47E-07 1.97E-07 1.89E-OS 8.6SE-07 No Data 1.S9E-07 1-133 1.S2E-06 2.S6E-06 7.78E-07 3.6SE-04 4.49E-06 No Data 1.29E-06 1-134 1.11E-07 2.90E-07 1.0SE-07 4.94E-06 4.58E-07 No Data 2.SSE-09 1-13S 4.62E-07 1.18E-06 4.36E-07 7.76E-OS 1.86E-06 No Data 8.69E-07 Cs-134 6.28E-OS 1.41E-04 6.86E-OS No Data 4.69E-OS 1.83E-OS 1.22E-06 Cs-136 6.44E-06 2.42E-OS 1.71E-OS No Data 1.38E-OS 2.22E-06 1.36E-06 Cs-137 8.38E-OS 1.06E-04 3.89E-OS No Data 3.80E-OS 1.S1E-OS 1.06E-06 Cs-138 S.82E-08 1.07E-07 S.S8E-08 No Data 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.8SE-09 2.54E-04 2.86E-OS Ba-141 1.78E-11 1.32E-14 S.93E-13 No Data 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-1S 2.84E-13 No Data 3.92E-1S 2.39E-07 S.99E-20 La-140 S.99E-08 2.9SE-08 7.82E-09 No Data No Data 2.68E-OS 6.09E-OS La-142 1.20E-10 S.31E-11 1.32E-11 No Data No Data 1.27E-06 1.S0E-06 Ce-141 3.SSE-06 2.37E-06 2.71E-07 No Data 1.11E-06 7.67E-OS 1.S8E-OS Ce-143 3.32E-08 2.42E-08 2.70E-09 No Data 1.08E-08 1.63E-QS 3.19E-OS Ce-144 6.11E-04 2.S3E-04 3.28E-OS No Data 1.S1E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 No Data 3.86E-07 6.04E-OS 2.67E-OS Pr-144 S.37E-12 2.20E-12 2.72E-13 No Data 1.26E-12 2. 19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 No Data 6.28E-07 4.6SE-OS 2.28E-OS W-187 1.S0E-09 1.22E-09 4.29E-10 No Data No Data S.92E-06 2.21E-OS Np-239 4.23E-08 3.99E-09 2.21E-09 No Data 1.2SE-08 8.11E-06 1.6SE-OS 9-2S Rev. 18

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VEGPODCM Table 9-10. Inhalation Dose Factors for the Adult Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data No Data 1.08E-05 Cr-51 No Data No Data 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 Mn-56 No Data 1.55E-10 2.29E-11 No Data 1.63E-10 1.18E-06 2. 53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 No Data No Data 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 Co-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 No Data No Data 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 No Data No Data 7.00E-07 1.54E-06 Cu-64 No Data 1.83E-10 7.69E-11 No Data 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 Br-83 No Data No Data 3.01E-08 No Data No Data No Data 2.90E-08 Br-84 No Data No Data 3.91E-08 No Data No Data No Data 2.05E-13 Br-85 No Data No Data 1.60E-09 No Data No Data No Data No Data Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06 Rb-88 No Data 4.84E-08 2.41E-08 No Data No Data No Data 4.18E-19 Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.16E-21 Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75E-04 4.37E-05 Sr-90 1.24E-02 No Data 7.62E-04 No Data No Data 1.20E-03 9.02E-05 Sr-91 7.74E-09 No Data 3.13E-10 No Data No Data 4.56E-06 2.39E-05 All values are in (mrem/pCi inhaled). They are obtained from Reference 3 (Table E-7), except as follows: Reference 2 (Table G-1) for Rh-105, Sb-124, and Sb-125.

9-26 Rev. 18

VEGPODCM Table 9-10 (contd). Inhalation Dose Factors for the Adult Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Sr-92 8.43E-10 No Data 3.64E-11 No Data No Data 2.06E-06 5. 38E-06 Y-90 2.61E-07 No Data 7.01E-09 No Data No Data 2.12E-05 6.32E-05 Y-91m 3.26E-11 No Data 1.27E-12 No Data No Data 2.40E-07 1.66E-10 Y-91 5.78E-05 No Data 1.55E-06 No Data No Data 2.13E-04 4.81E-05 Y-92 1.29E-09 No Data 3.77E-11 No Data No Data 1.96E-06 9.19E-06 Y-93 1.18E-08 No Data 3.26E-10 No Data No Data 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 No Data 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 No Data 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 6.31E-05 1.30E-05 Mo-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 No Data 8.23E-08 No Data 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 No Data 3.89E-11 No Data 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 No Data 1.09E-06 No Data 1.67E-05 1.17E-03 1.14E-04 Rh-105 9.24E-10 6.73E-10 4.43E-10 No Data 2.86E-09 2.41E-06 1.09E-05 Ag-110m 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 No Data 3.10E-04 5.08E-05 Sb-125 8.26E-06 8.91E-08 1.66E-06 7.34E-09 No Data 2.75E-04 1.26E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7. 17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 9-27 Rev. 18

VEGPODCM Table 9-10 (contd). Inhalation Dose Factors for the Adult Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 No Data 9.61E-07 1-131 3. 15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 1-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.11E-06 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-10 1-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07 Cs-134 4.66E-05 1.06E-04 9. 1OE-05 No Data 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 No Data 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 8a-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2. 17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 No Data No Data 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 No Data 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 No Data 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 No Data 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 No Data 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 No Data 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 No Data No Data 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 No Data 8.75E-09 4.70E-06 1.49E-05 9-28 Rev. 18

VEGPODCM Table 9-11. Ingestion Dose Factors for the Infant Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 No Data 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 No Data No Data No Data 2.30E-05 Cr-51 No Data No Data 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 No Data 1.99E-05 4.51E-06 No Data 4.41E-06 No Data 7.31E-06 Mn-56 No Data 8. 18E-07 1.41E-07 No Data 7.03E-07 No Data 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 No Data No Data 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2. 12E-05 No Data No Data 1.59E-05 2.57E-05 Co-58 No Data 3.60E-06 8.98E-06 No Data No Data No Data 8.97E-06 Co-60 No Data 1.08E-05 2.55E-05 No Data No Data No Data 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 No Data No Data No Data 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 No Data No Data No Data 4.05E-05 Cu-64 No Data 6.09E-07 2.82E-07 No Data 1.03E-06 No Data 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 No Data 3.06E-05 No Data 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 No Data 6.98E-08 No Data 1.37E-05 Br-83 No Data No Data 3.63E-07 No Data No Data No Data No Data Br-84 No Data No Data 3.82E-Q7 No Data No Data No Data No Data Br-85 No Data No Data 1.94E-08 No Data No Data No Data No Data Rb-86 No Data 1.70E-04 8.40E-05 No Data No Data No Data 4.35E-06 Rb-88 No Data 4.98E-07 2.73E-07 No Data No Data No Data 4.85E-07 Rb-89 No Data 2.86E-07 1.97E-07 No Data No Data No Data 9.74E-08 Sr-89 2.51E-03 No Data 7.20E-05 No Data No Data No Data 5.16E-05 Sr-90 1.85E-02 No Data 4.71E-03 No Data No Data No Data 2.31E-04 Sr-91 5.00E-05 No Data 1.81E-06 No Data No Data No Data 5.92E-05 All values are in (mrem/pCi ingested). They are obtained from Reference 3 (Table E-14). Neither Reference 2 nor Reference 3 contains data for Rh-105, Sb-124, or Sb-125.

9-29 Rev. 18

VEGPODCM Table 9-11 (contd). Ingestion Dose Factors for the Infant Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Sr-92 1.92E-OS No Data 7.13E-07 No Data No Data No Data 2.07E-04 Y-90 8.69E-08 No Data 2.33E-09 No Data No Data No Data 1.20E-04 Y-91m 8.10E-10 No Data 2.76E-11 No Data No Data No Data 2.70E-06 Y-91 1.13E-06 No Data 3.01E-08 No Data No Data No Data 8. 1OE-OS Y-92 7.6SE-09 No Data 2.1SE-10 No Data No Data No Data 1.46E-04 Y-93 2.43E-08 No Data 6.62E-10 No Data No Data No Data 1.92E-04 Zr-9S 2.06E-07 S.02E-08 3.56E-08 No Data S.41E-08 No Data 2.S0E-oS Zr-97 1.48E-08 2.54E-09 1.16E-09 No Data 2.S6E-09 No Data 1.62E-04 Nb-9S 4.20E-08 1.73E-08 1.00E-08 No Data 1.24E-08 No Data 1.46E-OS Mo-99 No Data 3.40E-OS 6.63E-06 No Data S.08E-OS No Data 1.12E-OS Tc-99m 1.92E-09 3.96E-09 S.10E-08 No Data 4.26E-08 2.07E-09 1.1SE-06 Tc-101 2.27E-09 2.86E-09 2. 83E-08 No Data 3.40E-08 1.S6E-09 4.86E-07 Ru-103 1.48E-06 No Data 4.9SE-07 No Data 3.08E-06 No Data 1.80E-OS Ru-10S 1.36E-07 No Data 4.S8E-08 No Data 1.00E-06 No Data S.41E-OS Ru-106 2.41E-OS No Data 3.01E-06 No Data 2.8SE-OS No Data 1.83E-04 Rh-10S No Data No Data No Data No Data No Data No Data No Data Ag-110m 9.96E-07 7.27E-07 4.81E-07 No Data 1.04E-06 No Data 3.77E-OS Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-12S No Data No Data No Data No Data No Data No Data No Data Te-12Sm 2.33E-OS 7.79E-06 3.1SE-06 7.84E-06 No Data No Data 1.11E-OS Te-127m S.8SE-OS 1.94E-OS 7.08E-06 1.69E-OS 1.44E-04 No Data 2.36E-OS Te-127 1.00E-06 3.3SE-07 2. 1SE-07 8. 14E-07 2.44E-06 No Data 2. 1OE-OS Te-129m 1.00E-04 3.43E-OS 1.54E-OS 3.84E-OS 2.S0E-04 No Data S.97E-OS Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 No Data 2.27E-OS Te-131m 1.S2E-OS 6.12E-06 S.OSE-06 1.24E-OS 4.21E-OS No Data 1.03E-04 Te-131 1.76E-07 6.S0E-08 4.94E-08 1.S7.E-07 4.S0E-07 No Data 7.11E-06 9-30 Rev. 18

VEGPODCM Table 9-11 (contd). Ingestion Dose Factors for the Infant Age Group Nuclide Bone Liver T.Body Thyroid Kidney lung GI-lll Te-132 2.08E-05 1.03E-05 9.S1E-OS 1.52E-05 S.44E-05 No Data 3.81E-05 1-130 S.OOE-OS 1.32E-05 5.30E-OS 1.48E-03 1.45E-05 No Data 2.83E-OS 1-131 3.59E-05 4.23E-05 1.8SE-05 1.39E-02 4.94E-05 No Data 1.51E-OS 1-132 1.SSE-OS 3.37E-OS 1.20E-OS 1.58E-04 3.7SE-OS No Data 2.73E-OS 1-133 1.25E-05 1.82E-05 5.33E-OS 3.31E-03 2.14E-05 No Data 3.08E-OS 1-134 8.S9E-07 1.78E-OS S.33E-07 4. 15E-05 1.99E-OS No Data 1.84E-OS 1-135 3. 64E-OS 7.24E-OS 2.64E-OS S.49E-04 8.07E-OS No Data 2.S2E-OS Cs-134 3.77E-04 7.03E-04 7.10E-05 No Data 1.81E-04 7.42E-05 1.91E-OS Cs-13S 4.59E-05 1.35E-04 5.04E-05 No Data 5.38E-05 1.10E-05 2.05E-OS Cs-137 5.22E-04 S.11E-04 4.33E-05 No Data 1.64E-04 S.64E-05 1.91E-OS Cs-138 4.81E-07 7.82E-07 3.79E-07 No Data 3.90E-07 S.09E-08 1.25E-OS Ba-139 8.81E-07 5.84E-10 2.55E-08 No Data 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-OS No Data 4.0SE-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 No Data 1.75E-10 1.77E-10 5.19E-OS Ba-142 1.84E-07 1.53E-10 9.0SE-09 No Data 8.81E-11 9.2SE-11 7.59E-07 la-140 2.11E-08 8.32E-09 2. 14E-09 No Data No Data No Data 9.77E-05 la-142 1.10E-09 4.04E-10 9.S7E-11 No Data No Data No Data S.8SE-05 Ce-141 7.87E-08 4.80E-08 5.S5E-09 No Data 1.48E-08 No Data 2.48E-05 Ce-143 1.48E-08 9.82E-OS 1.12E-09 No Data 2.8SE-09 No Data 5.73E-05 Ce-144 2.98E-OS 1.22E-oS 1.S7E-07 No Data 4.93E-07 No Data 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 No Data 1.13E-08 No Data 4.29E-05 Pr-144 2.74E-10 1.0SE-10 1.38E-11 No Data 3.84E-11 No Data 4.93E-OS Nd-147 5.53E-08 5.S8E-08 3.48E-09 No Data 2. 19E-08 No Data 3.S0E-05 W-187 9.03E-07 S.28E-07 2.17E-07 No Data No Data No Data 3.S9E-05 Np-239 1.11E-08 9.93E-10 5.S1E-10 No Data 1.98E-09 No Data 2.87E-05 9-31 Rev. 18

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VEGPODCM Table 9-12. Ingestion Dose Factors for the Child Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLJ H-3 No Data 2.03E-07 2.03E-07 2.03E-Q7 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-OS 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 S.80E-06 S.80E-06 S.80E-06 S.80E-Q6 S.80E-06 S.80E-06 S.80E-06 P-32 8.2SE-04 3.86E-OS 3.18E-OS No Data No Data No Data 2.28E-OS Cr-S1 No Data No Data 8.90E-09 4.94E-09 1.3SE-09 9.02E-09 4.72E-07 Mn-54 No Data 1.07E-OS 2.8SE-06 No Data 3.00E-06 No Data 8.98E-06 Mn-S6 No Data 3.34E-07 7.54E-08 No Data 4.04E-07 No Data 4.84E-OS Fe-SS 1.1SE-OS 6.10E-06 1.89E-06 No Data No Data 3.4SE-06 1.13E-06 Fe-S9 1.6SE-OS 2.67E-OS 1.33E-OS No Data No Data 7.74E-06 2.78E-OS Co-S8 No Data 1.80E-06 S.S1E-06 No Data No Data No Data 1.0SE-OS Co-60 No Data S.29E-06 1.S6E-OS No Data No Data No Data 2.93E-OS Ni-63 S.38E-04 2.88E-OS 1.83E-OS No Data No Data No Data 1.94E-06 Ni-6S 2.22E-06 2.09E-07 1.22E-07 No Data No Data No Data 2.56E-OS Cu-64 No Data 2.4SE-07 1.48E-07 No Data S.92E-07 No Data 1.1SE-OS Zn-6S 1.37E-OS 3.6SE-OS 2.27E-OS No Data 2.30E-QS No Data 6.41E-06 Zn-69 4.38E-08 6.33E-08 S.8SE-09 No Data 3.84E-08 No Data 3.99E-06 Br-83 No Data, No Data 1.71E-07 No Data No Data No Data No Data Br-84 No Data No Data 1.98E-07 No Data No Data No Data No Data Br-8S No Data No Data 9. 12E-09 No Data No Data No Data No Data Rb-86 No Data 6.70E-OS 4. 12E-OS No Data No Data No Data 4.31E-06 Rb-88 No Data 1.90E-07 1.32E-07 No Data No Data No Data 9.32E-09 Rb-89 No Data 1.17E-07 1.04E-07 No Data No Data No Data 1.02E-09 Sr-89 1.32E-03 No Data 3.77E-OS No Data No Data No Data S.11E-OS Sr-90 1.70E-02 No Data 4.31E-03 No Data No Data No Data 2.29E-04 Sr-91 2.40E-OS No Data 9.06E-07 No Data No Data No Data S.30E-OS All values are in (mrem/pCi ingested). They are obtained from Reference 3 (Table E-13). Neither Reference 2 nor Reference 3 contains data for Rh-10S, Sb-124, or Sb-12S.

9-32 Rev. 18

VEGPODCM Table 9-12 (contd). Ingestion Dose Factors for the Child Age Group Nuclide Bone Liver T.Bocly Thyroid Kidney Lung GI-LLI Sr-92 9.03E-06 No Data 3.62E-07 No Data No Data No Data 1.71E-04 Y-90 4.11E-08 No Data 1.10E-09 No Data No Data No Data 1.17E-04 Y-91m 3.82E-10 No Data 1.39E-11 No Data No Data No Data 7.48E-07 Y-91 6.02E-07 No Data 1.61E-08 No Data No Data No Data 8.02E-OS Y-92 3.60E-09 No Data 1.03E-10 No Data No Data No Data 1.04E-04 Y-93 1.14E-08 No Data 3.13E-10 No Data No Data No Data 1.70E-04 Zr-9S 1.16E-07 2.SSE-08 2.27E-08 No Data 3.6SE-Q8 No Data 2.66E-OS Zr-97 6.99E-09 1.01E-09 S.96E-10 No Data 1.4SE-Q9 No Data 1.S3E-04 Nb-9S 2.2SE-08 8.76E-09 6.26E-09 No Data 8.23E-09 No Data 1.62E-OS Mo-99 No Data 1.33E-OS 3.29E-06 No Data 2.84E-OS No Data 1.10E-OS Tc-99m 9.23E-10 1.81E-09 3.00E-08 No Data 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 No Data 1.91E-08 S.92E-10 3.S6E-09 Ru-103 7.31E-07 No Data 2.81E-07 No Data 1.84E-06 No Data 1.89E-OS Ru-10S 6.4SE-08 No Data 2.34E-08 No Data S.67E-07 No Data 4.21E-OS Ru-106 1.17E-OS No Data 1.46E-06 No Data 1.58E-QS No Data 1.82E-04 Rh-10S No Data No Data No Data No Data No Data No Data No Data Ag-110m S.39E-07 3.64E-07 2.91E-07 No Data 6.78E-Q7 No Data 4.33E-OS Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-12S No Data No Data No Data No Data No Data No Data No Data Te-12Sm 1.14E-OS 3.09E-06 1.S2E-06 3.20E-06 No Data No Data 1.10E-OS Te-127m 2.89E-OS 7.78E-06 3.43E-06 6.91E-06 8.24E-OS No Data 2.34E-OS Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 No Data 1.84E-OS Te-129m 4.87E-OS 1.36E-OS 7.S6E-06 1.S7E-OS 1.43E-04 No Data S.94E-OS Te-129 1.34E-07 3.74E-08 3.18E-08 9.S6E-08 3.92E-07 No Data 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.6SE-06 S.12E-06 2.41E-OS No Data 1.01E-04 Te-131 8.30E-08 2.S3E-08 2.47E-08 6.3SE-08 2.S1E-07 No Data 4.36E-07 9-33 Rev. 18

VEGPODCM Table 9-12 (contd). Ingestion Dose Factors for the Child Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 No Data 4.50E-05 1-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 No Data 2.76E-06 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 No Data 1.54E-06 1-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 No Data 1.73E-06 1-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 No Data 2.95E-06 1-134 4. 19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 No Data 5.16E-07 1-135 1.75E-06 3. 15E-06 1.49E-06 2.79E-04 4.83E-06 No Data 2.40E-06 Cs-134 2.34E-04 3.84E-04 8. 1OE-05 No Data 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 No Data 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3. 13E-04 4.62E-05 No Data 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3. 17E-07 2.01E-07 No Data 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 No Data 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 No Data 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 No Data 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 No Data 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 No Data No Data No Data 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 No Data No Data No Data 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 No Data 8.68E-09 No Data 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 No Data 1.59E-09 No Data 5.55E-05 Ce-144 2.08E-06 6.52E-Q7 1.11E-07 No Data 3.61E-Q7 No Data 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 No Data 6.39E-09 No Data 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 No Data 2.11E-11 No Data 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 No Data 1.24E-08 No Data 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 No Data No Data No Data 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Data 2.79E-05 9-34 Rev. 18

VEGPODCM Table 9-13. Ingestion Dose Factors for the Teenager Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8. 12E-07 8.12E-07 8.12E-07 8. 12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 No Data No Data No Data 2.32E-05 Cr-51 No Data No Data 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 No Data 5.90E-06 1.17E-06 No Data 1.76E-06 No Data 1.21E-05 Mn-56 No Data 1.58E-07 2.81E-08 No Data 2.00E-07 No Data 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-Q7 No Data No Data 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 No Data No Data 4.32E-06 3.24E-05 Co-58 No Data 9.72E-07 2.24E-06 No Data No Data No Data 1.34E-05 Co-60 No Data 2.81E-06 6.33E-06 No Data No Data No Data 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00'E-06 No Data No Data No Data 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 No Data No Data No Data 5.19E-06 Cu-64 No Data 1.15E-07 5.41E-08 No Data 2.91E-07 No Data 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 No Data 1.28E-05 No Data 8.47E-06 Zn-69 1.47E-08 2.80E-Q8 1.96E-09 No Data 1.83E-08 No Data 5.16E-08 Br-83 No Data No Data 5.74E-08 No Data No Data No Data No Data Br-84 No Data No Data 7.22E-08 No Data No Data No Data No Data Br-85 No Data No Data 3.05E-09 No Data No Data No Data No Data Rb-86 No Data 2.98E-05 1.40E-05 No Data No Data No Data 4.41E-06 Rb-88 No Data 8.52E-08 4.54E-08 No Data No Data No Data 7.30E-15 Rb-89 No Data 5.50E-08 3.89E-08 No Data No Data No Data 8.43E-17 Sr-89 4.40E-04 No Data 1.26E-05 No Data No Data No Data 5.24E-05 Sr-90* 8.30E-03 No Data 2.05E-03 No Data No Data No Data 2.33E-04 Sr-91 8.07E-06 No Data 3.21E-07 No Data No Data No Data 3.66E-05 All values are in (mrem/pCi ingested). They are obtained from Reference 3 (Table E-12). Neither Reference 2 nor Reference 3 contains data for Rh-105, S1r124, or S1r125.

9-35 Rev. 18

VEGPODCM Table 9-13 (contd). Ingestion Dose Factors for the Teenager Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Sr-92 3.05E-06 No Data 1.30E-07 No Data No Data No Data 7.77E-05 Y-90 1.37E-08 No Data 3.69E-10 No Data No Data No Data 1.13E-04 Y-91m 1.29E-10 No Data 4.93E-12 No Data No Data No Data 6.09E-09 Y-91 2.01E-07 No Data 5.39E-09 No Data No Data No Data 8.24E-05 Y-92 1.21E-09 No Data 3.50E-11 No Data No Data No Data 3.32E-05 Y-93 3.83E-09 No Data 1.05E-10 No Data No Data No Data 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 No Data 1.91E-08 No Data 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 No Data 7.11E-10 No Data 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 No Data 4.42E-09 No Data 1.95E-05 Mo-99 No Data 6.03E-06 1.15E-06 No Data 1.38E-05 No Data 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 No Data 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 No Data 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 No Data 1.09E-07 No Data 8.99E-07 No Data 2.13E-05 Ru-105 2.18E-08 No Data 8.46E-09 No Data 2.75E-07 No Data 1.76E-05 Ru-106 3.92E-06 No Data 4.94E-07 No Data 7.56E-OS No Data 1.88E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 2.05E-07 1.94E-07 1.18E-07 No Data 3.70E-07 No Data 5.45E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 3.83E-06 1.38E-06 5. 12E-07 1.07E-06 No Data No Data 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 No Data 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 No Data 1.22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 No Data 6. 12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 No Data 2.45E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 No Data 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 No Data 2.29E-09 9-36 Rev. 18

VEGPODCM Table 9-13 (contd). Ingestion Dose Factors for the Teenager Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 No Data 7.00E-05 1-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 No Data 2.29E-06 1-131 5.85E-06 8. 19E-06 4.40E-06 2.39E-03 1.41E-05 No Data 1.62E-06 1-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 No Data 3.18E-07 1-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 No Data 2.58E-06 1-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6. 1OE-07 No Data 5.10E-09 1-135 6. 1OE-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 No Data 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 No Data 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 No Data 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1:49E-04 5.19E-05 No Data 5.07E-05 1.97E-05 2. 12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 No Data 1.10E-Q7 1.28E-08 6.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 No Data 9.22E-11 6.74E-11 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 No Data 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 No Data 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 No Data 2.53E-11 1.99E-11 9. 18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 No Data No Data No Data 9.82E-05

. La-142 1.79E-10 7.95E-11 1.98E-11 No Data No Data No Data 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 No Data 4. 18E-09 No Data 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 No Data 7.67E-10 No Data 5. 14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 No Data 1.72E-Q7 No Data 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 No Data 3.04E-09 No Data 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 No Data 1.01E-11 No Data 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 No Data 5.99E-09 No Data 3.68E-05 W-187 1.46E-07 1.19E-07 4. 17E-08 No Data No Data No Data 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 No Data 5.21E-10 No Data 2.67E-05 9-37 Rev. 18

VEGPODCM Table 9-14. Ingestion Dose Factors for the Adult Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2. 17E-05 Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 No Data No Data 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.85E-06 3.40E-05 Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-60 No Data 2. 14E-06 4.72E-06 No Data No Data No Data 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06 Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.10E-07 No Data 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 Br-84 No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13 Br-85 No Data No Data 2. 14E-Q9 No Data No Data No Data No Data Rb-86 No Data 2.11E-05 9.83E-06 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19 Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 All values are in (mremJpCi ingested). They are obtained from Reference 3 (Table E-11), except as follqws: Reference 2 (Table A-3) for Rh-105, Sb-124, and Sb-125.

9-38 Rev. 18

VEGPODCM Table 9-14 (contd). Ingestion Dose Factors for the Adult Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Sr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 Y-91m 9.09E-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10 Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 Y-92 8.45E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05 Y-93 2.68E-09 No Data 7.40E-11 No Data No Data No Data 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 No Data 1.53E-08 No Data 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.10E-05 Mo-99 No Data 4.31E-Q6 8.20E-07 No Data 9.76E-06 No Data 9.99E-Q6 Tc-99m 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2. 16E-05 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Rh-105 1.22E-07 8.86E-08 5.83E-08 No Data 3.76E-07 No Data 1.41E-05 Ag-110m 1.60E-07* 1.48E-07 8.79E-08 No Data 2.91E-07 No Data 6.04E-05 Sb-124 2.81E-06 5.30E-08 1.11E-06 6.79E-Q9 No Data 2.18E-06 7.95E-05 Sb-125 2.23E-06 2.40E-08 4.48E-07 1.98E-09 No Data 2.33E-04 1.97E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.0GE-07 1.09E-05 No Data 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 9-39 Rev. 18

VEGPODCM Table 9-14 (contd). Ingestion Dose Factors for the Adult Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 1-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 1-131 4. 16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 No Data 1.02E-07 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 No Data 2.22E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-Q6 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 8a-139 9.70E-08 6.91E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05 8a-141 4.71E-08 3.56E-11 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 No Data No Data No Data 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 No Data 3.65E-10 No Data 2.40E-05 9-40 Rev. 18

VEGPODCM Table 9-15. External Dose Factors for Standing on Contaminated Ground Nuclide T. Body Skin Nuclide T.Body Skin H-3 0.00 0.00 Sr-91 7.10E-09 8.30E-09 C-14 0.00 0.00 Sr-92 9.00E-09 1.00E-08 Na-24 2.50E-08 2.90E-08 Y-90 2.20E-12 2.60E-12 P-32 0.00 0.00 Y-91m 3.80E-09 4.40E-09 Cr-51 2.20E-10 2.60E-10 Y-91 2.40E-11 2.70E-11 Mn-54 5.80E-09 6.80E-09 Y-92 1.60E-09 1.90E-09 Mn-56 1.10E-08 1.30E-08 Y-93 5.70E-10 7.80E-10 Fe-55 0.00 0.00 Zr-95 5.00E-09 5.80E-09 Fe-59 8.00E-09 9.40E-09 Zr-97 5.50E-09 6.40E-09 Co-58 7.00E-09 8.20E-09 Nb-95 5.10E-09 6.00E-09 Co-60 1.70E-08 2.00E-08 Mo-99 1.90E-09 2.20E-09 Ni-63 0.00 0.00 Tc-99m 9.60E-10 1.10E-09 Ni-65 3.70E-09 4.30E-09 Tc-101 2.70E-09 3.00E-09 Cu-64 1.50E-09 1.70E-09 Ru-103 3.60E-09 4.20E-09 Zn-65 4.00E-09 4.60E-09 Ru-105 4.50E-09 5.10E-09 Zn-69 0.00 0.00 Ru-106 1.50E-09 1.80E-09 Br-83 6.40E-11 9.30E-11 Rh-105 6.60E-10 7.70E-10 Br-84 1.20E-08 1.40E-08 Ag-110m 1.80E-08 2. 1OE-08 Br-85 0.00 0.00 Sb-124 1.30E-08 1.50E-08 Rb-86 6.30E-10 7.20E-10 Sb-125 3. 1OE-09 3.50E-09 Rb-88 '3.50E-09 4.00E-09 Te-125m 3.50E-11 4.80E-11 Rb-89 1.50E-08 1.80E-08 Te-127m 1.10E-12 1.30E-12 Sr-89 5.60E-13 6.50E-13 Te-127 1.00E-11 1.10E-11 Sr-90 0.00 0.00 Te-129m 7.70E-10 9.00E-10 2

All values are in (mrem/h) per (pCilm ). They are obtained from Reference 3 (Table E-6), except as follows: Reference 2 (Table A-7) for Rh-105, Sb-124, and Sb-125.

9-41 Rev. 18

._.--._--""'"'-----~

VEGPODCM Table 9-15 (contd). External Dose Factors for Standing on Contaminated Ground Nuclide T.80dy Skin Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 1-130 1.40E-08 1.70E-08 1-131 2.80E-09 3.40E-09 1-132 1.70E-08 2.00E-08 1-133 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2. 1OE-08 2.40E-08 8a-139 2.40E-09 2.70E-09 8a-140 2.10E-09 2.40E-09 8a-141 4.30E-09 4.90E-09 8a-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.00 0.00 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187. 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 9-42 Rev. 18

VEGPODCM CHAPTER 10 DEFINITIONS OF EFFLUENT CONTROL TERMS The terms defined in this chapter are used in the presentation of the above chapters. These terms are shown in all capital letters to indicate that they are specifically defined.

10.1 TERMS SPECIFIC TO THE ODCM The following terms are used in the ODCM, but are not found in the Technical Specifications:

ACTION(S)

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

BATCH RELEASE A BATCH RELEASE is the discharge of wastes of a discrete volume. Prior to sampling for analyses, each liquid batch shall be isolated and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

COMPOSITE SAMPLE A COMPOSITE SAMPLE is one which contains material from multiple waste releases, in which the quantity of sample is proportional to the quantity of waste discharged, and in which the method of sampling employed results in a specimen that is representative of the wastes released. Prior to analyses, all liquid samples that are to be aliquotted for a COMPOSITE SAMPLE shall be mixed thoroughly, in order for the COMPOSITE SAMPLE to be representative of the effluent release.

When assessing the consequences of a waste release at the pre-release or post-release stage, the most recent available COMPOSITE SAMPLE results for the applicable release pathway may be used.

CONTINUOUS RELEASE A CONTINUOUS RELEASE is the discharge of wastes of a non-discrete volume, e.g.,

from a volume within a system that has an input flow during the continuous release. To be representative of the quantities and concentrations of radioactive materials in CONTINUOUS RELEASES of liquid effluents, samples shall be collected in proportion to the rate of flow of the effluent stream or to the quantity of liquid waste discharged.

FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of surveillance requirements shall correspond to the intervals defined below, with a maximum allowable extension not to exceed 25% of the surveillance interval.

NOTATION FREQUENCY S (Once per shift) At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

W (Weekly) At least once per 7 days.

M (Monthly) At least once per 31 days.

Q (Quarterly) At least once per 92 days.

10-1 Rev. 18

VEGPODCM SA (Semi--annually) At least once per 184 days.

R (Refueling) At least once per 18 months.

S/U (Startup) Prior to each reactor startup.

NA Not applicable.

P (Prior) Completed prior to each release.

GASEOUS WASTE PROCESSING SYSTEM A GASEOUS WASTE PROCESSING SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases 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.

LIQUID RADWASTE TREATMENTSYSTEM A LIQUID RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive materials in liquid effluents by systematic collection, retention, and processing through filtration, evaporation, separation and/or ion exchange treatment. This system consists of at least one collection tank, one evaporator or demineralizer system, one post-treatment tank and associated components providing for treatment flow and functional control.

MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS For the purposes of the ODCM, MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS include the following changes to such systems:

(1) Major changes in process equipment, components, structures, or effluent monitoring instrumentation as described in the Final Safety Analysis Report (FSAR) or as evaluated in the Nuclear Regulatory Commission statrs Safety Evaluation Report (SER) (e.g., deletion of evaporators and installation of demineralizers);

(2) Changes in the design of radwaste treatment systems that could significantly increase quantities of effluents released from those previously considered in the FSAR and SER; (3) Changes in system design which may invalidate the accident analysis as described in the SER (e.g., changes in tank capacity that would alter the curies released); or (4) Changes in system design that could potentially result in a significant increase in occupational exposure of operating personnel (e.g., use of temporary equipment without adequate shielding provisions).

10-2 Rev. 18

VEGPODCM 1

MEMBER'S) OF THE PUBLlC A MEMBER OF THE PUBLIC means any individual except when that individual is 2

receiving an occupational dose

This category may include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

MINIMUM DETECTABLE CONCENTRATION The MINIMUM DETECTABLE CONCENTRATION (MDC) is defined, for purposes of the controls in this ODCM, as the smallest concentration of radioactive material in a sample that will yield a net count above system backgroUnd and that will be detected with 95-percent probability, with only 5-percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation, the MDC for a given radionuclide is determined as follows (Reference 18):

where:

MDC= the a priori MINIMUM DETECTABLE CONCENTRATION (J.1Ci per unit mass or volume).

MDC =

E . v . 2.22 x 106 . Y . e - A. M

~= the background counting rate, or the counting rate of a blank sample, as appropriate (counts per minute).

ts = the length afthe sample counting period (minutes).

it, = the length of the background counting period (minutes).

E= the counting efficiency (counts per disintegration)

V= the sample size (units of mass or volume).

2.22 x 10 6

= the number of disintegrations per minute per J.1Ci.

Y = the fractional radiochemical yield, when applicable.

A. = the radioactive decay constant for the given radionuclide (h- ).

1 Values of A. used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

at = for effluent samples, the elapsed time between the midpoint of sample collection and the time of counting (h); for environmental samples, the elapsed time between the end of sample collection and the time of counting (h).

1 The italicized terms in this definition, which are not otherwise used in this ODCM, shall have the definitions assigned to them by 10 CFR 20.1003.

2 Except as delineated in other parts of 10 CFR chapter I.

10-3 Rev. 18

VEGPODCM Typical values of E, V, Y, and At should be used in the calculation. It should be recognized that the MDC 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.

PRINCIPAL GAMMA EMITTERS The PRINCIPAL GAMMA EMITTERS for which the MINIMUM DETECTABLE CONCENTRATION (MDC) limit applies include exclusively the following radionuclides:

For liquid radioactive effluents: Mn-54, Fe-59, C0-58, Co-6O, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an MDC of 5 x 1O~ J.1CilmL.

For gaseous radioactive effluents: In noble gas releases, Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-138; and in particulate releases, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-gg, Cs-134, Cs-137, Ce-141 , and Ce-144.

For environmental media: The gamma emitters specifically listed in Table 4-3.

These lists do 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 Radioactive Effluent Release Report, the Annual Radiological Environmental Operating Report, or other applicable report(s).

SITE BOUNDARY For the purpose of effluent controls defined in the ODCM, the SITE BOUNDARY shall be as shown in Figure 4-1.

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

UNRESTRICTED AREA The UNRESTRICTED AREA shall be any area access to which is neither limited nor controlled by the licensee, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM The VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents, by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters, for the purpose of removing iodines 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 any noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. .

10-4 Rev. 18

VEGPODCM 10.2 TERMS DEFINED IN THE TECHNICAL SPECIFICATIONS The following terms are defined in the Technical Specifications, Section 1.0. Because they are used throughout the Limits of Operation sections of the ODCM, they are presented here for convenience. In the event of discrepancies between the definitions below and those in the Technical Specifications, the Technical Specification definitions shall take precedence.

CHANNEL CALIBRATION 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 required sensor, alarm, inter1ock, and/or trip functions and may be performed by any series of sequential, over1apping, or total channel steps, so that the entire channel is calibrated.

CHANNEL CHECK 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.

CHANNEL OPERATIONAL TEST (COn A CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as dose to the sensor as practicable to verify operability of required alarm, inter1ock, and/or trip functions. The CHANNEL OPERATIONAL TEST shall. include adjustments, as necessary, of the required alarm, interlock, and/or trip setpoints, so that the setpoints are within the required range and accuracy.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (J.lCilg) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131,1-132,1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of NRC Regulatory Guide 1.109, Revision 1, 1977.

MODE (or OPERATIONAL MODEl An OPERATIONAL MODE shall correspond to anyone inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head dosure bolt tensioning specified in Section 1.0 of the Technical Specifications with fuel in the reactor vessel.

OPERABLE (or OPERABILITY)

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

10-5 Rev. 18 L..

VEGPODCM RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3565 MWt.

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

10-6 Rev. 18

VEGPODCM VOGTLE ELECTRIC GENERATING PLANT OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING i 21 2-33 18 ii 21 2-34 18 iii 18 2-35 18 iv 18 2-36 18 v 18 2-37 18 vi 18 2-38 18 vii 18 2-39 18 viii 19 2-40 18 ix 18 2-41 18 x 18 2-42 18 1-1 18 2-43 Deleted 2-1 18 2-44 Deleted 2-2 18 2-45 Deleted 2-3 20 2-46 Deleted 2-4 18 2-47 Deleted 2-5 21 2-48 Deleted 2-6 18 2-49 Deleted 2-7 18 3-1 18 2-8 18 3-2 18 2-9 18 3-3 19 2-10 18 3-4 18 2-11 18 3-5 21 2-12 18 3-6 19 2-13 18 3-7 18 2-14 19 3-8 19 2-15 19 3-9 19 2-16

18 3-10 18 2-17 18 3-11 18 2-18 18 3-12 18 2-19 18 3-13 18 2-20 18 3-14 19 2-21 18 3-15 18 2-22 18 3-16 18 2-23 18 3-17 18 2-24 18 3-18 18 2-25 18 3-19 18 2-26 18 3-19a 19 2-27 18 3-20 18 2-28 18 3-21 18 2-29 18 3-22 18 2-30 18 3-23 18 2-31 18 3-24 18 2-32 18 1 of 3 Rev. 21

VEGPODCM 3-25 18 4-17 18 3-26 18 4~18 18 3-27 18 4-19 Deleted 3-28 18 4-20 Deleted 3-29 18 5-1 18 3-30 18 5-2 18 3-31 18 5-3 18 3-32 18 5-4 18 3-33 18 6-1 18 3-34 18 6-2 18 3-~5 18 6-3 Deleted 3-36 18 7-1 18 3-37 18 7-2 18 3-38 18 7-3 18 3-39 18 7-4 18 3-40 18 7-5 18 3-41 18 7-6 18 3-42 18 7-7 ................*..............................Deleted 3-43 18 8-1 18 3-44 18 8-2 18 3-45 18 8-3 18 3-46 18 8-4 18 3-47 18 8-5 18 3-48 18 8-6 18 3-49 18 8-7 18 3-50 Deleted 8-8 18 3-51 Deleted 8-9 18 3-52 Deleted 8-10 ~ 18 3-53 Deleted 8-11 18 3-54 Deleted 8-12 18 3-55 Deleted 8-13 18 3-56 Deleted 8-14 18 3-57 Deleted 8-15 18 3-58 Deleted 8-16 .....*........................*...................... 18 4-1 18 8-17 18 4-2 18 8-18 Deleted 4-3 18 9-1 18 4-4 18 9-2 18 4-5 18 9-3 18 4-6 18 9-4 18 4-7 ~ 18 9-5 18 4-8 18 9-6 18 4-9 18 9-7 18 4-10 18 9-8 18 4-11 18 9-9 18 4-12 18 9-10 18 4-13 18 9-11 18 4-14 18 9-12 18 4-15 18 9-13 18 4-16 18 9-14 18 2 of 3 Rev. 21

VEGPODCM 9-15 18 9-34 18 9-16 18 9-35 18 9-17 18 9-36 18 9-18 18 9-37 18 9-19 18 9-38 18 9-20 18 9-39 18 9-21 18 9-40 18 9-22 18 9-41 18 9-23 18 9-42 ; 18 9-24 18 9-43 Deleted 9-25 18 9-44 Deleted 9-26 18 9-45 Deleted 9-27 18 10-1 18 9-28 18 10-2 18 9-29 18 10-3 18 9-30 18 10-4 18 9-31 18 10-5 18 9-32 18 10-6 18 9-33 18 10-7 Deleted s:lvogtlelodanlEpl.doc 30f3 Rev. 21

NL-04-0662, Annual Radioactive Effluent Release Reports for 2003

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NL-04-0662, Annual Radioactive Effluent Release Reports for 2003

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