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{{Adams
#REDIRECT [[NL-14-0659, Enclosure 3: Vogtle Annual Radioactive Effluent Release Report for 2013]]
| number = ML14125A100
| issue date = 04/16/2014
| title = Enclosure 3: Vogtle Annual Radioactive Effluent Release Report for 2013
| author name = Olive C
| author affiliation = Southern Nuclear Operating Co, Inc
| addressee name =
| addressee affiliation = NRC/NRR
| docket = 05000424, 05000425
| license number = NPF-068, NPF-081
| contact person =
| case reference number = NL-14-0659
| package number = ML14125A094
| document type = Periodic Monitoring Report (Radiological/Environmental)
| page count = 336
}}
 
=Text=
{{#Wiki_filter:Edwin I. Hatch Nuclear PlantJoseph M. Farley Nuclear PlantVogtle Electric Generating PlantAnnual Radioactive Effluent Release Reports andOffsite Dose Calculation Manuals for 2013Enclosure 3Vogtle Annual Radioactive Effluent Release Report for 2013 SOUTHERN NUCLEAR COMPANYVOGTLE ELECTRIC GENERATING PLANT- UNITS 1 AND 2NRC DOCKET NOS. 50-424 AND 50-425FACILITY OPERATING LICENSE NOS. NPF-68 AND NPF-81ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTFORJANUARY 1, 2013 TO DECEMBER 31, 2013Preparedby:
OIL) 3d11#Reviewed byoltV7 4Y4 LA/Page 85 of 503 VOGTLE ELECTRIC GENERATING PLANTRADIOACTIVE EFFLUENT RELEASE REPORT -2013TABLE OF CONTENTSTITLEPAGESECTION1.01.11.1.11.1.21.21.31.3.11.3.21.41.51.61.7Table 1-1ATable 1-1 BTable 1-1CLiquid Effluents Regulatory Requirements Concentration LimitsDose LimitsEffluent Concentration Limit (ECL)Measurements and Approximations of Total Radioactivity Total Radioactivity Determination Total Error Estimation Liquid Effluent Release DataRadiological Impact Due to Liquid ReleasesLiquid Effluents
-Batch ReleasesLiquid Effluents
-Abnormal ReleasesLiquid Effluents
-Summation of All Releases Unit 1(Quarters 1,2,3, and 4)Liquid Effluents
-Summation of All Releases Unit 2(Quarters 1,2,3, and 4)Liquid Effluents
-Summation of All Releases Site(Quarters 1,2,3, and 4)Liquid Effluents
-Unit I (Quarters 1,2,3, and 4)Liquid Effluents
-Unit I (Quarters 1,2,3, and 4)Page 86 of 5039292929292939395969696969799101102106TableTable1-2A1-2B Table 1-2CTable 1-3ATable 1-3BTable 1-3CTable 1-4Table 1-5ATable 1-5BTable 1-5CTable 1-6ATable 1-6ATable 1-6C2.02.12.1.12.1.2Liquid Effluents
-Unit I (Quarters 1,2,3, and 4) 108Doses to a Member of the Public Due to Liquid ReleasesUnit I (Quarters 1,2,3, and 4) 111Doses to a Member of the Public Due to Liquid ReleasesUnit 2 (Quarters 1,2,3, and 4) 113Doses to a Member of the Public Due to Liquid ReleasesSite (Quarters 1,2,3, and 4) 114Minimum Detectable Concentration
-Liquid 115Liquid Effluents Batch Release Summary Unit I (Quarters 1,2,3, and 4) 116Liquid Effluents Batch Release Summary Unit 2 (Quarters 1,2,3, and 4) 117Liquid Effluents Batch Release Summary Site (Quarters 1,2,3, and 4) 118Liquid Effluents Abnormal Release Summary Unit I(Quarters 1,2,3, and 4) 119Liquid Effluents Abnormal Release Summary Unit I(Quarters 1,2,3, and 4) 121Liquid Effluents Abnormal Release Summary Site (Quarters 1,2,3, and 4) 122Gaseous Effluents 123Regulatory Requirements 123Dose Rate Limits 123Air Doses Due to Noble Gases in Gaseous Releases 123Page 87 of 503 2.1.32.22.2.12.2.22.2.2.12.2.2.22.2.2.32.2.32.32.42.52.6Table 2-IATable 2-1 BTable 2-I CTable 2-2ATable 2-2BDoses to a Member of the Public 123Measurements and Approximations of Total Radioactivity 124Sample Collection and Analysis 124Total Quantities of Radioactivity, Dose Rates, andCumulative Doses 125Fission and Activation Gases 125Radioiodines, Tritium and Particulate Releases 125Gross Alpha Release 125Total Error Estimation 126Gaseous Effluent Release Data 127Radiological Impact Due to Gaseous Releases 128Gaseous Effluents
-Batch Releases 128Gaseous Effluents
-Abnormal Releases 128Gaseous Effluents Summation of All Releases Unit 1(Quarters 1,2,3, and 4) 129Gaseous Effluents Summation of All Releases Unit 2(Quarters 1,2,3, and 4) 130Gaseous Effluents Summation of All Releases Site(Quarters 1,2,3, and 4) 131Gaseous Effluents Mixed Mode Releases Unit I (Quarters 1,2,3, and 4) 133Gaseous Effluents Mixed Mode Releases Unit 2 (Quarters 1,2,3, and 4) 136Page 88 of 503 Table 2-2CTable 2-3ATable 2-3BTable 2-3CTable 2-4ATable 2-4BTable 2-4CTable 2-5ATable 2-5BTable 2-5CTable 2-6Table 2-7AGaseous Effluents Mixed Mode Releases Site (Quarters 1,2,3, and 4)Gaseous Effluents Ground Level Releases Unit I (Quarters 1,2,3, and 4)Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4)Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4)Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4)Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4)Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4)Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4)Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4)Gaseous Effluents Ground Level Releases Unit 2 (Quarters 1,2,3, and 4)Minimum Detectable Concentrations
-GaseousGaseous Effluents
-Batch Release Summary Unit 1(Quarters 1,2,3, and 4)139142145148150151152153154155157158Page 89 of 503 Table 2-7BTable 2-7CTable 2-8ATable 2-8BTable 2-8C3.03.13.1.13.1.23.2Table 3-14.04.14.2Table 4-15.05.15.2Gaseous Effluents
-Batch Release Summary Unit 2(Quarters 1,2,3, and 4) 159Gaseous Effluents
-Batch Release Summary Site (Quarters 1,2,3, and 4) 160Gaseous Effluents
-Abnormal Release Summary Unit I(Quarters 1,2,3, and 4) 161Gaseous Effluents
-Abnormal Release Summary Unit 2(Quarters 1,2,3, and 4) 162Gaseous Effluents
-Abnormal Release Summary Site(Quarters 1,2,3, and 4) 163Solid Waste 164Regulatory Requirements 164Solid Radioactive Waste System 164Reporting Requirements 164Solid Waste Data 164Solid Waste and Irradiated Fuel Shipments 165Doses to Members of the Public Inside the Site Boundary 175Regulatory Requirements 176Demonstration of Compliance 176Doses to Members of the Public Due to Activities Inside theSite Boundary 79Total Dose from Uranium Fuel Cycle (40CFR190) 180Regulatory Requirements 180Demonstration of Compliance 180Page 90 of 503 6.07.07.17.1.17.1.27.27.2.17.2.28.08.18.29.09.19.2Appendix AAppendix BAppendix CMeteorological DataProgram Deviations Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation Regulatory Requirement Description of Deviations Tanks Exceeding Curie Content LimitsRegulatory Requirements Description of Deviations Changes to the Vogtle Electric Generating Plant OffsiteDose Calculation Manual (ODCM)Regulatory Requirements Description of ChangesMajor Changes to Liquid, Gaseous, or Solid RadwasteTreatment SystemsRegulatory Requirements Description of Major ChangesCarbon-1 4Corrected ReportsVEGP ODCM Version 2918018018018018118218218218218218318318318418518591Page 91 of 503 1.0 Liquid Effluents 1.1 Regulatory Requirements 1.1.1 Concentration LimitsIn accordance with Technical Specification 5.5.4.b, the concentration ofradioactive 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 1iCi/ml totalactivity.
1.1.2 Dose LimitsThe dose or dose commitment to a MEMBER OF THE PUBLIC fromradioactive materials in liquid effluents
: released, from each unit, toUNRESTRICTED AREAS shall be limited as follows:a. During any calendar quarter to less than or equal to 1.5 mrems tothe whole body and to less than or equal to 5 mrems to any organ,andb. During any calendar year to less than or equal to 3 mrems to thewhole 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 releaserates 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 allowflexibility in establishing practical monitor set points which canaccommodate effluent releases at concentrations higher than the ECLvalues stated in 10 CFR 20, Appendix B, Table 2, Column 2.For dissolved or entrained noble gases in liquid radwaste, the ECL is1 E-04 pCi/ml total activity.
For gross alpha in liquid radwaste, the ECL is 2 E-09 ptCi/ml.For all the above radionuclides or categories of radioactivity, the overallECL fraction is determined in accordance with 10 CFR Part 20, AppendixB. The method utilizing the ECL fraction to determine release rates andliquid radwaste effluent radiation monitor set points is described inSubsection 1.3 of this report.Page 92 of 503 1.31.3.1Measurements and Approximations of Total Radioactivity Total Radioactivity Determination Prior to the release of any tank containing liquid radwaste, and following the required recirculation, samples are collected and analyzed inaccordance with the Offsite Dose Calculation Manual (ODCM) Table 2-3"Radioactive Liquid Waste Sampling and Analysis Program".
A samplefrom each tank which is planned for release is analyzed for principal gamma emitters, 1-131, and dissolved and entrained noble gases bygamma spectroscopy.
Monthly and quarterly composites are preparedfor analysis by extracting aliquots from each sample taken from thetanks, which are released.
Liquid radwaste sample analyses areperformed as follows:MEASUREMENT
: 1. Gamma Isotopic2. Dissolved or entrained noble gases3. Tritium4. Gross Alpha5. Sr-89 & Sr-90FREQUENCY Each BatchEach BatchMonthlyComposite MonthlyComposite Quarterly Composite METHODGamma Spectroscopy with computerized data reduction.
Gamma Spectroscopy with computerized data reduction Distillation andliquid scintillation countingGas flow proportional countingChemical separation and gas flowproportional orscintillation countingChemical separation and liquid scintillation counting6. Fe-55Quarterly Composite Page 93 of 503 1.3.1Total Radioactivity Determination cont'dGamma isotopic measurements are performed using germanium detectors witha resolution of 2.1 keV or lower. A peak search of the resulting gamma rayspectrum is performed by the computer system. Energy and net count data forall significant peaks are determined, and a quantitative reduction or MDCcalculation is performed.
This ensures that the MDC's are met for the nuclidesspecified in ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,Cs-1 34, Cs-1 37, Ce-141 and Ce-144).
The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detectorefficiency, baseline counts, branching ratio and MDC calculations, are madebased on the counts at the location in the spectrum where the peak for thatradionuclide would be located, if present.Tritium, Gross Alpha, Sr-89, Sr-90, Fe-55 and Ni-63 are, in some cases,analyzed offsite.ECL fraction is determined using radionuclide concentrations of a tank plannedfor release, the most current results available for tritium, gross alpha, Sr-89,Sr-90, Fe-55 and Ni-63 and the corresponding ECL values.This ECL fraction is used, with appropriate safety factors, tolerance
: factors, andthe minimum assured dilution stream flow to calculate maximum permissible release rates and a liquid effluent monitor setpoint.
The monitor setpoint iscalculated 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.
Liquid effluent discharge is alsoautomatically terminated if the dilution stream flow rate falls below the minimumassured dilution flow rate used in the setpoint calculations and established as asetpoint on the dilution stream flow monitor.Radionuclide concentrations, safety factors, dilution stream flow rate, and liquideffluent 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, thenecessary data from the release (i.e., release volume, etc.) are provided by theOperations Department to the Chemistry Department.
These data are input tothe computer and a post-release printout is generated.
The post release printoutcontains the actual release rates, release concentrations and quantities, actualdilution flow, and calculated doses to an individual.
Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.Page 94 of 503 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 samplingand measurement.
Because it may be very difficult to assign error termsfor each parameter affecting the final measurement, detailed statistical evaluation of error is not suggested.
The objective should be to obtain anoverall estimate of the error associated with measurements of radioactive materials released in effluents (Reference Reg. Guide 1.23 Rev 1). TotalError is calculated by the root mean square method. The root mean squarevalue is the square root of the arithmetic mean (average) of the squares ofthe original values.a. Fission and activation total release was calculated from sample analysisresults and release point flow rates.Sampling and statistical error 10%Counting Equipment Calibration 10%Tank Volumes and System Flow Rates 20%TOTAL ERROR 24.5%b. Total Tritium release was calculated from sample analysis results andrelease point volumes.Sampling and statistical errors 10%Counting equipment calibration 10%Tank volumes and system flow rate 20%TOTAL ERROR 24.5%c. Dissolved and entrained gases were calculated from sample analysisresults and release point volumes.Sampling and statistical error 20%Counting equipment calibration 10%Tank volumes and system flow rate 20%TOTAL ERROR 30%d. Gross alpha radioactivity was calculated from sample analysis results andrelease point volumes.Sampling and statistical error 10%Counting Equipment calibration 10%Tank volumes and system flowrates 20%TOTAL ERROR 24.5%Page 95 of 503 1.3.2Total Error Estimation cont'de. Volume of waste prior to dilution was calculated from level indicators onthe tanks and pump discharge flow rates and times.Level Indicator error 10%Operator Interpretation of gauge 10%TOTAL ERROR 14%f. Volume of dilution water used was calculated from flow totalizers andpump discharge flow rates and times.Flow totalizer error 10%Operator interpretation of gauge 10%TOTAL ERROR 14%g. Gross alpha, Sr-89, Sr-90, Fe-55, Ni-63 and H-3 radioactivity has anadditional error associated with sample compositing.
Compositing sample error 5%1.4 Liquid Effluent Release DataRegulatory Guide 1.21 Rev. 1 Tables 2A and 2B are found in this reportas Tables 1-1A, 1-1 B, 1-1 C, 1-2A, 1-2B and 1-2C. Data is presented on aquarterly basis as required by Regulatory Guide 1.21 Rev. 1 for all fourquarters.
1.5 Radiological Impact Due to Liquid ReleasesDoses to an individual due to radioactivity in liquid effluent werecalculated in accordance with the Offsite Dose Calculation Manual.Results are presented in Table 1-3A for Unit 1 and 1-3B for Unit 2, for allfour quarters.
1.6 Liquid Effluents
-Batch ReleasesBatch release information for liquid effluents is presented in Table 1-5Afor Unit 1 and Table 1-5B for Unit 2.1.7 Liquid Effluents
-Abnormal ReleasesThere were no abnormal liquid releases during 2013.Page 96 of 503 Table 1-1AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents
-Summation of All ReleasesUnit: 1Starting:
1-Jan- 2013 Ending: 31-Dec-2013 Tyve of Effluent Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterA. Fission And Activation Products1. Total Release (not including
: tritium, gases, alpha) Curies 8.92E-02 2.04E-02 1.66E-02 7.24E-032. Average diluted concentration during period uCi/mL 8.73E-09 5.78E-09 4.1OE-09 1.12E-093. Percent of Applicable Limit %* * * *B. Tritium1. Total Release Curies 7.69E+02 4.33E+02 1.37E+02 3.41E+022. Average diluted Concentration during period uCi/mL 7.53E-05 1.22E-04 3.36E-05 5.26E-053. Percent of Applicable Umit %* * * *C. Dissolved and Entrained Gases1. Total Release Curies 7.26E-03 4.18E-05 0.OOE+00 6.58E-062. Average diluted Concentration during period uCi/mL 7.11E-10 1.18E-11 0.OOE+00 1.02E-123. Percent of Applicable Limit %* * * *D: Gross Alpha Radioactivity
: 1. Total Release Curies 4.81E-04 O.OOE+00 O.OOE+00 0.OOE+00E: Waste Vol Release (Pre-Dilution)
Liters 2.68E+07 2.95E+07 2.82E+07 3.14E+07F. Volume of Dilution Water Used Liters 1.02E+10 3.50E+09 4.03E+09 6.44E+09* Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.Page 97 of 503 If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.
Page 98 of 503 Table 1-1BVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents
-Summation Of All ReleasesUnit: 2Startina:
1-Jan- 2013Endina: 31-Dec-2013 Type of EffluentA. Fission And Activation Products1. Total Release (not including
: tritium, gases, alpha)2. Average diluted concentration during period3. Percent of Applicable LimitIlnii**I CT Mlmml4=rI)Mf fmm=lr*gr
'ADf r% A M rAT- MonmmgrMCuriesuCi/mL1.21E-021.50E-098.18E-032.34E-092.71E-036.76E-10*¢1.94E-033.24E-10B. Tritium1. Total Release Curies 6.72E+01 6.95E+012. Average diluted Concentration during period uCi/mL 8.34E-06 1.99E-053. Percent of Applicable Limit %* *C. Dissolved and Entrained Gases1. Total Release Curies 3.35E-04 5.13E-062. Average diluted Concentration during period uCi/mL 4.16E-11 1.47E-123. Percent of Applicable Limit %* *D: Gross Alpha Radioactivity
: 1. Total Release Curies O.OOE+00 0.OOE+00E: Waste Vol Release (Pre-Dilution)
Liters 3.45E+07 4.55E+07F. Volume of Dilution Water Used Liters 8.02E+09 3.44E+09* Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.3.85E+019.59E-06,O.OOE+00O.OOE+000.OOE+004.18E+073.97E+094.70E+017.86E-06O.OOE+OOO.OOE+0OO.OOE+OO4.37E+075.94E+09Page 99 of 503 If Not Detected,.
Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.
Page 100 of 503 Table 1-1CVogUe Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents
-Summation Of All ReleasesUnit: SiteStarting:
1-Jan- 2013 Endinq: 31-Dec-2013 TvYe of Effluent Units 1ST Quarter 2ND Ouarter 3RD Ouarter 4TH OuarterA. Fission And Activation Products1. Total Release (not including
: tritium, gases, alpha) Curies 1.01E-01 2.86E-02 1.94E-02 9.18E-032. Average diluted concentration during period uCi/mL 5.54E-09 4.07E-09 2.40E-09 7.37E-103. Percent of Applicable Limit %* * * *B. Tritium1. Total Release Curies 8.37E+02 5.02E+02 1.75E+02 3.88E+022. Average diluted Concentration during period uCi/mL 4.58E-05 7.15E-05 2.17E-05 3.11E-053. Percent of Applicable Limit % * * * *C. Dissolved and Entrained Gases1. Total Release Curies 7.60E-03 4.70E-05 O.OOE+00 6.58E-062. Average diluted Concentration during period uCi/mL 4.16E-10 6.69E-12 O.OOE+00 5.29E-133. Percent of Applicable Limit % * * * *D: Gross Alpha Radioactivity
: 1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00E: Waste Vol Release (Pre-Dilution)
Liters 6.13E+07 7.50E+07 7.OOE+07 7.51E+07F. Volume of Dilution Water Used Liters 1.82E+10 6.95E+09 8.OOE+09 1.24E+10* Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.Page 101 of 503 If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.
Table 1-2AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid Effluents Unit: 1Startina:
1-Jan- 2013 Ending: 31-Dec-2013 Continuous ModeNuclides ReleasedUnits 1ST Quarter 2ND Quarter 3RD Quarter4TH QuarterFission & Activation ProductsFe-55Total For PeriodTritiumH-3Dissolved And Entrained GasesNo Nuclides FoundGross Alpha Radioactivity No Nuclides FoundCuriesCuriesCuriesCuriesCuries1.09E-031.09E-033.18E-02O.OOE+00O.OOE+001.64E-031.64E-034.13E-02O.OOE+O0O.OOE+005.87E-045.87E-044.15E-02O.OOE+00O.OOE+003.76E-041.27E-010.OOE+000.OOE+00*Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Page 102 of 503 Table 1-2AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid Effluents Unit: 1Starting:
1-Jan- 2013 Ending: 31-Dec-2013 Batch ModeNuclides ReleasedFission & Activation ProductsCo-58Co-60Cr-51Fe-551-1311-132Mn-54Nb-95Ni-56Ni-63Sr-89Sr-90W-187Ba-133Cs-134Cs-137Rh-105Ru-105Ru-106Sb-122Sb-124Sb-125Sb-126Te-132Sn-117MTe-125MTe-129MTotal For PeriodUnits 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuries5.69E-031.55E-037.33E-042.46E-029.94E-057.27E-053.64E-046.01E-069.91E-062.21E-032.09E-054.96E-06O.OOE+006.72E-051.90E-052.48E-042.04E-054.81E-06O.OOE+003.18E-056.17E-053.79E-023.79E-057.81E-05O.OOE+001.36E-027.87E-048.81E-022.56E-036.43E-040.OOE+007.85E-030.OOE+0O0.OOE+O01.83E-052.58E-06O.OOE+006. 13E-031.66E-066.1 IE-077.26E-060.OOE+OO4. 18E-054.36E-040.OOE+000.OOE+008.41E-060.OOE+0O4-33E-065. 34E-040.OOE+000.OOE+000.OOE+O05.37E-040.OOE+001.88E-022.33E-036.09E-040.OOE+0O4.30E-030.OOE+000.OOE+003.48E-050.OOE+000.OOE+004.69E-039.36E-071 .47E-060.OOE+000.OOE+004. 57E-053.34E-040.OOE+000.OOE+000.OOE+000.OOE+000.OOE+001. 16E-030.OOE+O00.OOE+000.OOE+O02.57E-030.OOE+O01.61E-022.03E-046.04E-040.OOE+008.38E-040.OOE+000.OOE+001.06E-050.OOE+008.40E-067.93E-040. OOE+002.64E-070.OOE+000.OOE+0O1.49E-061.14E-04O.OOE+00O.OOE+00O.OOE+0O0.OOE+0O0.OOE+003.84E-050.OOE+OO0.OOE+0O1.66E-064.25E-030.OOE+006.86E-03*Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable Page 103 of 503 concentrations.
Page 104 of 503 Table 1-2AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents Unit: 1Startinga:
1-Jan- 2013 Ending: 31-Dec-2013 Batch ModeUnits 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterNuclides ReleasedTritiumH-3Dissolved And Entrained GasesAr-41Xe-127Xe-133Xe-135Xe-133MTotal For PeriodGross Alpha Radioactivity G-AlphaCuriesCuriesCuriesCuriesCuriesCuriesCuries7.69E+02O.OOE+001.06E-056.73E-034.71E-045.53E-057.26E-034.33E+023. 19E-060.OOE+003.86E-050.OOE+000.OOE+004.18E-O51.37E+020.OOE+000.OOE+O00.OOE+000.OOE+000.OOE+000.OOE+003.41E+020.OOE+000.OOE+O06.58E-060.OOE+00a.OOE+006.5SE-06CuriesO.OOE+O0O.OOE+00O.OOE+O0O.OOE+00Page 105 of 503
*Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.
Table 1-2BVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents Unit: 2Startina:
1-Jan- 2013 Ending: 31-Dec-2013 Continuous ModeUnits 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterNuclides ReleasedFission & Activation ProductsNo Nuclides FoundTritiumH-3Dissolved And Entrained GasesNo Nuclides FoundGross Alpha Radioactivity No Nuclides FoundCuriesCuriesCuriesCuries0.OOE+003.88E-020.OOE+000.OOE+000.OOE+001.17E-010.OOE+000.OOE+000.OOE+002.92E-020.OOE+000.OOE+00O.OOE+007.56E-02O.OOE+00O.OOE+00Page 106 of 503
*Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 1-4 for typical minimum detectable concentrations.
Table 1-2BVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid Effluents Unit: 2Startina:
1-Jan- 2013 Endinq: 31-Dec-2013 Batch ModeUnits 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterNuclides ReleasedFission & Activation ProductsCo-58Co-60Cr-51Fe-551-131Mn-54Nb-95Ni-56Ni-63Sr-89W-187Cs-134Cs-137Sb-122Sb-124Sb-125Sb-126Te-132Te-125MTe-129MTotal For PeriodTritiumH-3Dissolved And Entrained GasesAr-41Xe-127CuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuriesCuries1.12E-034.35E-041.04E-041.28E-031.65E-054.99E-050.OOE+007.27E-068.73E-045.49E-060.OOE+000.OOE+007.08E-055.62E-063.47E-054.87E-039.55E-065.28E-063.09E-038.88E-051.21E-026.71E+01O.OOE+001.06E-051.57E-036.04E-040.OOE+001.37E-030.OOE+003.30E-051.24E-050.OOE+001. 12E-035.92E-066. 17E-062.25E-048.29E-040.OOE+000.OOE+005.OOE-040.OOE+000.OOE+001.91E-030.OOE+0O8.18E-036.94E+015. 13E-060.OQE+004.96E-042. 16E-040.OOE+005.96E-060.OOE+001.05E-060.OOE+O08.57E-072.0 1E-040.OOE+000.OOE+002.74E-051.42E-040.OOE+009.98E-068.99E-040.OOE+000.OOE+007.15E-040.OOE+002.71E-033.85E+010.OOE+0Q0.OOE+004.03E-056.37E-050.OOE+O01. 15E-040.OOE+000.OOE+00O.OOE+002.40E-066.41E-050.OOE+O00.OOE+001.57E-062.39E-050.OOE+000.OOE+001.11E-050.OOE+000.OOE+001.62E-030.OOE+O0IL.94E-03
: 4. 70E+010.OOE+000.OOE+O0Page 107 of 503 Xe-133 Curies 3.23E-04 O.OOE+00 O.OOE+00 O.OOE+00Xe-135 Curies 1.77E-06 O.OOE+00 O.OOE+00 O.OOE+00Total For Period Curies 3.35E-04 5.13E-06 O.OOE+00 0.OOE+00Gross Alpha Radioactivity No Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00*Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Table 1-2CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid Effluents Unit: SiteStarting:
1-Jan- 2013 Endina: 31-Dec-2013 Continuous ModeNuclides ReleasedFission & Activation ProductsFe-55Total For PeriodTritiumH-3Units 1ST Quarter2ND Quarter3RD Quarter4TH QuarterCuriesCuriesCuries1.09E-037.06E-021.64E-031.58E-015.87E-047.07E-023.76E-042.02E-01Dissolved And Entrained GasesNo Nuclides FoundGross Alpha Radioactivity No Nuclides FoundCuriesCuries0.OOE+000.OOE+000.OOE+000.OOE+00O.OOE+00O.OOE+000.OOE+000.OOE+00Page 108 of 503
*Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Table 1-2CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid Effluents Unit: SiteStartina:
1-Jan- 2013 Ending: 31-Dec-2013 Batch ModeNuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterFission & Activation ProductsCo-58 Curies 6.81E-03 4.12E-03 2.82E-03 2.43E-04Co-60 Curies 1.98E-03 1.25E-03 8.25E-04 6.67E-04Cr-51 Curies 8.37E-04 O.OOE+00 O.00E+00 O.OOE+00Fe-55 Curies 2.58E-02 9.22E-03 4.31E-03 9.53E-041-131 Curies 1.16E-04 O.OOE+00 O.OOE+00 O.OOE+001-132 Curies 7.27E-05 O.OOE+00 O.OOE+00 O.OOE+00Mn-54 Curies 4.14E-04 5.12E-05 3.59E-05 1.06E-05Nb-95 Curies 6.01E-06 1.49E-05 0.O0E+00 0.OOE+00Ni-56 Curies 1.72E-05 O.OOE+00 8.57E-07 1.08E-05Ni-63 Curies 3.08E-03 7.25E-03 4.89E-03 8.57E-04Sr-89 Curies 2.64E-05 7.58E-06 9.36E-07 0.OOE+00Sr-90 Curies 4.96E-06 6.11E-07 1.47E-06 2.64E-07W-187 Curies O.OOE+00 1.34E-05 O.OOE+00 0.OOE+00Ba-133 Curies 6.72E-05 O.OOE+00 O.OOE+00 O.OOE+00Cs-134 Curies 1.90E-05 2.67E-04 7.31E-05 3.05E-06Cs-137 Curies 3.19E-04 1.27E-03 4.75E-04 1.38E-04Rh-105 Curies 2.04E-05 O.OOE+00 O.OOE+00 O.OOE+00Ru-105 Curies 4.81E-06 O.OOE+00 O.OOE+00 0.OOE+00Ru-106 Curies 0.OOE+00 8.41E-06 0.OOE+00 O.OOE+00Sb-122 Curies 3.74E-05 0.OOE+00 0.OOE+00 O.OOE+00Sb-124 Curies 9.65E-05 4.33E-06 9.98E-06 O.OOE+00Sb-125 Curies 4.28E-02 1.03E-03 2.05E-03 4.95E-05Page 109 of 503 Sb-126 Curies 4.74E-05 0.OOE+00 O.OOE+00 0.OOE+00Te-132 Curies 8.34E-05 0.OOE+00 O.OOE+00 O.OOE+00Sn-117M Curies O.OOE+00 0.OOE+00 0.OOE+00 1.66E-06Te-125M Curies 1.66E-02 2.45E-03 3.28E-03 5.87E-03Te-129M Curies 8.75E-04 O.OOE+00 0.OOE+00 O.OOE+00Total For Period Curies 1.OOE-01 2.70E-02 1.88E-02 8.80E-03*Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Table 1-2CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents Unit: SiteStartinag 1-Jan- 2013 Endina: 31-Dec-2013 Batch ModeNuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterTritiumH-3 Curies 8.37E+02 5.02E+02 1.75E+02 3.87E+02Dissolved And Entrained GasesAr-41 Curies O.OOE+00 8.32E-06 O.OOE+00 0.OOE+00Xe-127 Curies 2.12E-05 O.OOE+00 O.OOE+00 0.OOE+00Xe-133 Curies 7.05E-03 3.86E-05 O.OOE+00 6.58E-06Xe-135 Curies 4.73E-04 0.OOE+00 O.OOE+00 0.OOE+00Xe-133M Curies 5.53E-05 O.OOE+00 0.OOE+00 O.OOE+00Total For Period Curies 7.60E-03 4.70E-05 0.OOE+00 6.58E-06Gross Alpha Radioactivity G-Alpha Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00Page 110 of 503
*Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Table 1-3AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Doses to a member of the public due to Liquid ReleasesUnit: 1Startina:
1-Jan- 2013 Endina: 31-Dec-2013 Cumulative Doses Per QuarterOrganBoneGI-LliKidneyLiverLungThyroidTotal BodyODCM Lmt5.OOE+O05.OOE+O05.OOE+O05.OOE+O05.OOE+O05.OOE+O01.50E+00UnitsmRemmRemmRemmRemmRemmRemmRem1ST Qtr3.09E-031.75E-021.38E-021.33E-025.61E-021. 15E-021.26E-02%/o ODCM6.18E-023.51E-012.76E-012.66E-011.12E+002.31E-018.42E-012ND Qtr8.21E-031.34E-021.46E-021.87E-021.45E-021.28E-021.66E-02%/o ODCM1.64E-012.68E-012.93E-013.73E-012.90E-012.55E-011.11E+003RD Qtr6.16E-034.47E-035.38E-038.12E-036.88E-033.34E-036.51E-03%/a ODCM1.23E-018.94E-021.08E-011.62E-011.38E-016.69E-024.34E-014TH Qtr1.60E-039.57E-039.85E-039.97E-038.92E-038.73E-039.51E-030/a ODCM3.19E-021.91E-011.97E-011.99E-011.78E-011.75E-016.34E-0 1Cumulative Doses per YearOrganODCM Lmt Units1.OOE+01 mRem1.00E+01 mRemYear to Ending Date% ODCM ReceptorLimitBoneGI-Lli1.91E-024.49E-021.91E-01 Maximum Individual Liquid4.49E-01 Maximum Individual LiquidLiquid Effluent Organ AnnualLiquid Effluent Organ AnnualPage 11 of 503 KidneyLiverLungThyroidTotal Body1.00E+011.00E+011.00E+011.0OE+013.OOE+00mRemmRemmRemmRemmRem4.37E-025.01E-028.64E-023.64E-024.53E-024.37E-015.01E-018.64E-013.64E-011.51E+00Maximum Individual LiquidMaximum Individual LiquidMaximum Individual LiquidMaximum Individual LiquidMaximum Individual LiquidLiquid Effluent Organ AnnualLiquid Effluent Organ AnnualLiquid Effluent Organ AnnualLiquid Effluent Organ AnnualUquid Effluent TB AnnualPage 112 of 503 Table 1-3BVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Doses to a member of the public due to Liquid ReleasesUnit: 2Startina:
1-Jan- 2013 Ending: 31-Dec-2013 Cumulative Doses Per QuarterOrganBoneGI-LliKidneyLiverLungThyroidTotal BodyODCM Lint Units1ST Qtr 0/b ODCM 2ND Qtr % ODCM 3RD Qtr %/o ODCM 4TH Qtr % ODCM5.OOE+005.OOE+005.OOE+005.OOE+005.OOE+005.OOE+001.50E+00mRemmRemmRemmRemmRemmRemmRem7.11E-041.82E-031.38E-031.33E-036.51E-039.41E-041. 18E-031.42E-023.63E-022.76E-022.66E-021.30E-011.88E-027.87E-029.40E-033.23E-037.03E-031.50E-024.66E-032.04E-031. 1OE-021.88E-016.46E-021.41E-013.OOE-019.32E-024.07E-027.35E-011.65E-031.53E-031.96E-033.29E-033.84E-031. 1OE-032.61E-033.29E-023.07E-023.91E-026.59E-027.68E-022.20E-021.74E-013.44E-041.70E-031.79E-031.67E-031.40E-031.36E-031.55E-036.88E-033.40E-023.57E-023.34E-022.80E-022.72E-021.03E-01Cumulative Doses per YearOrganODCM Lmt UnitsYear to Ending Date%/a ODCM ReceptorLimitBoneGI-LliKidneyUverLungThyroidTotal Body1.00E+011.00E+011.OOE+011.00E+011.00E+011.00E+013.OOE+00mRemmRemmRemmRemmRemmRemmRem1.21E-028.28E-031.21E-022.13E-021.64E-025.44E-031.64E-021.21E-018.28E-021.21E-012.13E-011.64E-015.44E-025.45E-01Maximum Individual LiquidMaximum Individual LiquidMaximum Individual LiquidMaximum Individual LiquidMaximum Individual ULquidMaximum Individual ULquidMaximum Individual LiquidULquid Effluent Organ AnnualLiquid Effluent Organ AnnualLiquid Effluent Organ AnnualULquid Effluent Organ AnnualULquid Effluent Organ AnnualLiquid Effluent Organ AnnualLiquid Effluent TB AnnualPage 113 of 503 Table 1-3CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Doses to a member of the public due to Liquid ReleasesUnit: SiteStarting:
1-Jan- 2013 Endina: 31-Dec-2013 Cumulative Doses Per QuarterOrganBoneGI-LliKidneyLiverLungThyroidTotal BodyODCM Lmt Units1ST Qtr % ODCM 2ND Qtr %/o ODCM 3RD Qtr 0/o ODCM 4TH Qtr 0/b ODCM5.OOE+005.OOE+005.0OEO005.OOE+005.OOE+OO5.OOE+QO1.50E+00mRemmRemmRemmRemmRemmRemmRem3.80E-031.94E-021.52E-021.47E-026.26E-021.25E-021.38E-027.61E-023.87E-013.04E-012.93E-011.25E+002.49E-019.21E-011.76E-021.66E-022.17E-023.36E-021.92E-021.48E-022.77E-023.52E-013.32E-014.33E-016.73E-013.84E-012.96E-011.84E+007.81E-036.OOE-037.34E-031.14E-021.07E-024.44E-039.12E-031.56E-011.20E-011.47E-012.28E-012. 14E-018.89E-026.08E-011.94E-031. 13E-021. 16E-021. 16E-021.03E-021.01E-021.11E-023.88E-022.25E-012.33E-012.33E-012.06E-0 12.02E-017.37E-01Cumulative Doses per YearOrganODCM Lmt UnitsYear to Ending Date% ODCM ReceptorLimitBoneGI-LliKidneyLiverLungThyroidTotal Body1.OOE+O11.OOE+011.0OE+011.OOE+O11.OOE+011.OOE+O13.OOE+00mRemmRemmRemmRemmRemmRemmRem3.12E-025.32E-025.58E-027.14E-021.03E-014.18E-026.16E-023.12E-015.32E-015.58E-017.14E-011.03E+004.18E-012.05E+00Maximum Individual LiquidMaximum Individual LiquidMaximum Individual LiquidMaximum Individual LiquidMaximum Individual LiquidMaximum Individual LiquidMaximum Individual LiquidLiquid Effluent Organ AnnualLiquid Effluent Organ AnnualLiquid Effluent Organ AnnualLiquid Effluent Organ AnnualLiquid Effluent Organ AnnualLiquid Effluent Organ AnnualLiquid Effluent TB AnnualPage 114 of 503 Table 1-4Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013MINIMUM DETECTABLE CONCENTRATIONS-LIQUID SAMPLE ANALYSESStarting:
1-Jan-2013 Ending: 31-Dec-2013 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.RADIONUCLIDE Mn-54Fe-59Co-58Co-60Zn-65Mo-99Cs-134Cs-137Ce-141Ce-1441-131Xe-133Xe-135Fe-55Sr-89Sr-90H-3Gross AlphaMDC2.73E-088.33E-083.78E-086.76E-081.32E-074.31E-073.06E-084.51E-086.99E-082.95E-075.97E-089.11E-084.27E-081.00E-065.OOE-087.OOE-092.OOE-067.OOE-08UNITSpCi/ml1tCi/mlpCi/mljiCi/mltCi/mliCi/ml,tCi/mlpCi/mlpCi/ml1Ci/mltCi/ml1Ci/mlpCi/mltCi/mlpCi/mltCi/mIpCi/mlpCi/mlPage 115 of 503 Table 1-5AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents
-Batch Release SummaryUnit: 1Startina:
1-Jan- 2013 Ending: 31 -Dec-2013 Liquid Release Units 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH Ouarter Year Totals1. Number of batch releases 43 22 12 18 952. Total time period for Batch releases (Minutes) 1.52E+04 3.80E+03 1.58E+03 6.25E+03 2.68E+043. Maximum time period for a batch release (Minutes) 1.08E+03 6.08E+02 3.41E+02 9.08E+02 1.08E+034. Average time period for a batch release (Minutes) 3.53E+02 1.73E+02 1.31E+02 3.47E+02 2.82E+025. Minimum time period for a batch release (Minutes) 6.50E+01 6.10E+01 4.90E+01 6.OOE+01 4.90E+016. Average stream flow during periodsof release of liquid effluent intoa flowing stream * (CFS) 5863 6705 17736 7121 9356*Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, Ga. 32 milesdownstream of Plant Vogtle.Page 116 of 503 Table 1-5Bi ; ;A n iI"n;4**t4UJ .ij fl~.~UC~a
.* *Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents
-Batch Release SummaryUnit: 2Startina" 1-Jan- 2013 Ending: 31-Dec-2013 1ST Quarter 2ND Quarter 3RD Quarter15 18 7es) 2.76E+03 2.96E+03 9.OOE+02es) 7.60E+02 3.48E+02 2.83E+02es) 1.84E+02 1.64E+02 1.29E+02tes) 5.20E+01 4.70E+01 6.OOE+014TH Quarter1. Number of batch releases2. Total time period for Batch releases3. Maximum time period for a batch release4. Average time period for a batch release5. Minimum time period for a batch release6. Average stream flow during periodsof release of liquid effluent intoa flowing stream *(Minut(Minut(Minut( Minut61.21E+034.41E+022.02E+028.40E+017121Year Totals467.16E+037.60E+021.70E+024.70E+019356( CFS )5863670517736*Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, Ga. 32 milesdownstream of Plant Vogtle.Page 117 of 503 Table 1-5CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid Effluents
-Batch Release SummaryUnit: SiteStartina:
1-Jan- 2013 Ending: 31-Dec-2013 I ;n..;A D0M ecIIn;i*I CT NimbrMTin% fmm:rigr'A F' rlmm or1. Number of batch releases2. Total time period for Batch releases3. Maximum time period for a batch release4. Average time period for a batch release5. Minimum time period for a batch release6. Average stream flow during periodsof release of liquid effluent intoa flowing stream *(Minutes)
(Minutes)
(Minutes)
(Minutes)
(CFS )551.73E+041.08E+033.14E+025.20E+015863406.75E+036.08E+021.69E+024.70E+016705192.48E+033.41E+021.30E+024.90E+01177364TH Ouarter247.46E+039.08E+023.11E+026.OOE+017121Year Totals1383.40E+041.08E+032.46E+024.70E+019356*Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, Ga. 32 miles downstream of Plant Vogtle.Page 118 of 503 Table 1-6AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT- 2013Liquid Effluents
-Abnormal Release SummaryUnit: 1Startina:
1-]an- 2013 Ending: 31-Dec-2013 I in,,irl IlnitcI QT nfrtar?NIl f.lmirher 2ND n"n era1. Number of Releases2. Total Time For All Releases3. Maximum Time For A Release4. Average Time For A Release5. Minimum Time For A Release6. Total activity for all releases(Minutes)
(Minutes)
(Minutes)
(Minutes)
( Curies )00.OOE÷000.OOE+000.OOE+000.OOE+OO0.OOE+000O.OOE+000.00E+000.OOE+000.OOE+000.OOE+003RD Ouarter00.OOE+000.OOE+000.OOE+000.OOE+000.OOE+004TH Ouarter00.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00Year Totals0O.OOE+00O.OOE+00O.OOE+00O.OOE+000.OOE+00*Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, Ga. 32 miles downstream of Plant Vogtle.Page 119 of 503 Page 120 of 503 Table 1-6BVogUe Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents
-Abnormal Release SummaryUnit: 2Startina:
1-Jan- 2013 Endinn: 31-Dec-2013 Liouid Releases Units 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH Ouarter Year Totals1. Number of Releases 0 0 0 0 02. Total Time For All Releases (Minutes) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+003. Maximum Time For A Release (Minutes) 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+004. Average Time For A Release (Minutes) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+005. Minimum Time For A Release (Minutes) 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+006. Total activity for all releases (Curies) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00*Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, Ga. 32 miles downstream of Plant Vogtle.Page 121 of 503 Table 1-6CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Liquid Effluents
-Abnormal Release SummaryUnit: SiteStartina:
1-lan- 2013 Endina: 31-Dec-2013 l .;Annmi DI I n;#-I CT Ml.m m ýr,11n fmm=r+A'40n nm 1. Number of Releases2. Total Time For All Releases3. Maximum Time For A Release4. Average Time For A Release5. Minimum Time For A Release6. Total activity for all releases(Minutes)
(Minutes)
(Minutes)
(Minutes)
( Curies )00.OOE+00O.OOE+000.OOE+000.O0E+000.aOE+0000.OOE+00O.OOE+000.OOE+000.OOE+0O0.OOE+0000.OOE+000.OOE+O00.OOE+00O.OOE+000.OOE+004TH Ouarter00.OOE+000.OOE+0O0.OOE+00O.OOE÷0O0.OOE+00Year Totals0O.OOE+00O.OOE+00O.OOE+0OO.OOE+0O0 O.OOE+00*Average river flowrate taken from USGS Monitoring Station 02197500, Savannah River at Burton's Ferry Bridge near Millhaven, Ga. 32 miles downstream of Plant Vogtle.Page 122 of 503 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 LimitsThe dose rate due to radioactive materials released in gaseous effluents from thesite to areas at and beyond the SITE BOUNDARY shall be limited to thefollowing:
: a. For noble gases, Less than or equal to 500 mrems/yr.
to the whole bodyand less than or equal to 3000 mrems/yr.
to the skin and,b. For Iodine-1 31, for Iodine-1 33, for tritium and for all radionuclides inparticulate form with half lives greater than 8 days: Less than or equal to1500 mrems/yr.
to any organ.2.1.2 Air Doses Due to Noble Gases in Gaseous ReleasesThe air dose due to noble gases released in gaseous effluents, from each unit, toareas at and beyond the SITE BOUNDARY shall be limited to the following:
: a. During any calendar quarter:
Less than or equal to 5 mradsfor gamma radiation and less than or equal to 10 mrads for betaradiation, andb. During any calendar year: Less than or equal to 10 mrads for gammaradiation and less than or equal to 20 mrads for beta radiation.
2.1.3 Doses to a Member of the PublicThe dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritiumand all radionuclides in particulate form with half-lives greater than 8 days ingaseous effluents
: released, from each unit, to areas at and beyond the SITEBOUNDARY shall be limited to the following.
: a. During any calendar quarter:
Less than or equal to 7.5 mrems to anyorgan.b. During any calendar year: Less than or equal to 15 mrems to any organ.Page 123 of 503 2.2Measurements and Approximations of Total Radioactivity 2.2.1 Sample Collection and AnalysisGaseous Effluents at the Vogtle Electric Generating Plant are currently confinedto five paths: plant vents (Unit 1 and Unit 2), the condenser air ejector, the steampacking exhauster systems (Unit 1 and Unit 2), and the Radwaste Processing Facility (RPF).Waste gas decay tanks are batch released through the Unit 1 plant vent. Thecontainment purges are released through their respective plant vents.Containment atmosphere is also released via the containment equipment hatchduring periods when the equipment hatch is open with containment purge/vent being stopped.
Approval was granted by the NRC to open the equipment hatchduring fuel movement; a release permit is generated when the equipment hatchis opened and the containment exhaust fan is not discharging to the plant vent.Any detected activity in the containment equipment hatch permit is included inthe Ground Release Table of the effluent report.All of the paths with the exception of the RPF can be continuously monitored forgaseous radioactivity.
The RPF is equipped with an integrated-type samplecollection device for collecting particulates.
Plant vent, containment, steam jet airejector, steam-packing exhauster are equipped with an integrated-type samplecollection device for collecting particulates and iodines.
During this reporting period, there were no continuous radioactive releases through the condenser airejector and the steam packing exhauster system vents. Batch Waste Gas DecayTank releases are analyzed for noble gases before each release.
Thecontainment atmosphere is analyzed for noble gases prior to each release andfor tritium at least on a monthly basis.Sample analysis 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, andcumulative doses are calculated.
Cumulative dose results are tabulated, alongwith the percent of the ODCM limits for each release for the current quarter andyear.Typically achieved minimum detectable concentrations for gaseous effluentsample analyses are reported in Table 2-6.Page 124 of 503 2.2.2Total Quantities of Radioactivity, Dose Rates, and Cumulative DosesThe methods for determining release quantities of radioactivity, dose rates, andcumulative doses are as follows:2.2.2.1 Fission and Activation GasesThe released radioactivity is determined from sample analysis 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,and particulates are calculated.
Calculated dose rates are compared to the doserate limits specified in ODCM 3.1.2 for noble gases, radioiodines,
: tritium, andparticulates.
Dose rate calculation methodology is presented in the ODCM.Beta and gamma air doses due to noble gases are calculated for the location inthe unrestricted area with the potential for the highest exposure due to gaseousreleases.
Air doses are calculated for each release period and cumulative totalsare kept for each unit for the calendar quarter and year. Cumulative air dosesare compared with the dose limits specified in ODCM 3.1.3. Current percent ofthe ODCM limits are shown on the printout for each release period. Air dosecalculation methodology is presented in the ODCM.2.2.2.2 Radioiodines, Tritium and Particulate ReleasesThe released quantities of radioiodines, tritium and particulates are determined using the weekly samples and release flow rates for the two plant vent releasepoints.After each quarter, the particulate filters from each plant vent are combined, forstrontium analysis.
Strontium concentrations are input to the composite file of thecomputer to be used for release dose rate and individual dose calculations.
Doses to a Member of the Public due to radioiodines, tritium and particulates arecalculated for the controlling
: receptor, which is described in Table 3-7of theODCM. Doses are calculated for each release period, and cumulative totals arekept for each unit for the current calendar quarter and year. Cumulative dosesare compared to the dose limits specified in ODCM 3.1.4.Current percent of ODCM limits are shown in this report for each release period.2.2.2.3 Gross Alpha ReleaseThe 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 arethen recorded on a data sheet and the activity is summed at the end of themonth. This concentration is used for release calculations.
Page 125 of 503 2.2.3 Total Error Estimation The total or maximum error associated with the effluent measurement will includethe cumulative errors resulting from the total operation of sampling andmeasurement.
Because it may be very difficult to assign error terms for eachparameter affecting the final measurement, detailed statistical evaluation of errorare not suggested.
The objective should be to obtain an overall estimate of the error associated withmeasurements 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 ascharcoal cartridges.
Total Error is calculated by the root mean squaremethod. The root mean square value is the square root of the arithmetic mean (average) of the squares of the original values.a. Fission and activation total release was calculated from sample analysisresults and release point flow rates.Sampling and statistical error in counting 10%Counting equipment calibration 10%Vent flow Rates 10%Non-steady release rates 20%TOTAL ERROR 26.5%b. 1-131 releases were calculated from each weekly sample:Statistical error in counting 10%Counting equipment calibration 10%Vent Flow Rates 10%Vent Sample Flow Rates 50%Non-Steady release rates 10%Losses from charcoal cartridges 10%TOTAL ERROR 55%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 54%Page 126 of 503 2.2.3Total Error Estimation cont'dd. Total tritium releases were calculated from sample analysis resultsand 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 20%e. Gross Alpha radioactivity was calculated from sample analysis resultsand 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 55%2.3 Gaseous Effluent Release DataRegulatory Guide 1.21 Rev. 1 Tables 1A, 1B, and 1C are found in this report asTables 2-1A, 2-1B, 2-1C, 2-2A, 2-2B, 2-2C, 2-3A, 2-3B, and 2-3C. Data arepresented on a quarterly basis as required by Regulatory Guide 1.21 Rev. 1.To complete table 2-1A, and 2-1 B, the total release for each of the fourcategories (fission and activation gases, iodines, particulates, and tritium) wasdivided by the number of seconds in the quarter to obtain a release rate inpLCi/second for each category.
: However, the percent of the ODCM limits are notapplicable because VEGP has no curie limits for gaseous releases.
Applicable limits are expressed in terms of dose. Noble gases are limited as specified inODCM 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, andparticulate 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 2-1B as curies releasedin 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 2-4Balong with the percent of the ODCM limits.Page 127 of 503 Limits for cumulative doses to a Member of the Public due to radioiodines, tritiumand particulates, are specified in ODCM 3.1.4. Cumulative doses to a Member ofthe Public are presented in Table 2-5A, and 2-5B along with percent of ODCMlimits.2.4 Radiological Impact Due to Gaseous ReleasesDose rates due to the release of noble gases were calculated for the site inaccordance with ODCM 3.4.1.1.
Dose rates due to radioiodines,
: tritium, andparticulates in gaseous releases were calculated in accordance with ODCM3.4.1.2.Dose rates were calculated as part of pre-release and post release permits.
Nolimits were exceeded for this reporting period.Cumulative air doses due to noble gas releases were calculated for each unit inaccordance with ODCM 3.4.2. These results are presented in Tables 2-4A and2-4B.Cumulative doses to a Member of the Public were calculated for each unit inaccordance with ODCM 3.4.3. These results are presented in Tables 2-5A and2-58.Dose rates and doses were calculated using the methodology presented in theVogtle Electric Generating Plant Offsite Dose Calculation Manual.2.5 Gaseous Effluents
-Batch ReleasesOther data pertinent to batch releases of radioactive gaseous effluent from Unit 1and Unit 2 are listed in Table 2-7A and 2-7B.2.6 Gaseous Effluents
-Abnormal ReleasesThere were no abnormal releases for 2013.Page 128 of 503 Table 2-1AVogUe Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Summation Of All ReleasesUnit: 1Startina:
1-Jan- 2013 Ending: 31-Dec-2013 Tvye of Effluent Units 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH OuarterA. Fission And Activation Gases1. Total Release Curies 4.79E-02 4.75E-01 1.88E+00 9.21E+002. Average Release rate for period uCi/sec 6.07E-03 6.03E-02 2.38E-01 1.17E+003. Percent of Applicable Limit % * * * *B. Radioiodines
: 1. Total Iodine-131 Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+002. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+003. Percent of Applicable Limit %* * * *C. Particulates
: 1. Particulates
( Half-Lives
> 8 Days) Curies 1.99E-08 2.38E-08 O.OOE+00 9.14E-072. Average Release rate for period uCi/sec 2.53E-09 3.02E-09 O.OOE+00 1.159E-07
: 3. Percent of Applicable Umit % * * * *D. Tritium1. Total Release Curies 5.89E+00 8.54E+00 1.21E+01 1.30E+012. Average Release rate for period uCi/sec 7.47E-01 1.08E+00 1.53E+00 1.65E+003. Percent of Applicable Limit %* * * *E. Gross Alpha1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+002. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations.
Page 129 of 503 Table 2-1BVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Summation Of All ReleasesUnit: 2Starting:
1-Jan- 2013 Ending: 31-Dec-2013 Type of Effluent Units 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH OuarterA. Fission And Activation Gases1. Total Release Curies 5.13E+00 1.31E+00 4.91E-02 6.26E-022. Average Release rate for period uCi/sec 6.51E-01 1.66E-01 6.23E-03 7.94E-033. Percent of Applicable Limit % * * * *B. Radioiodines
: 1. Total Iodine-131 Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O02. Average Release rate for period uCi/sec O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+003. Percent of Applicable Umit %* * * *C. Particulates
: 1. Particulates
( Half-Lives
> 8 Days) Curies O.OOE+00 6.52E-08 O.OOE+00 7.80E-082. Average Release rate for period uCi/sec O.OOE+00 8.27E-09 O.OOE+00 9.893E-09
: 3. Percent of Applicable Limit %* * * *D. Tritium1. Total Release Curies 1.36E+01 2.84E+00 2.16E+00 8.95E-012. Average Release rate for period uCi/sec 1.72E+00 3.61E-01 2.74E-01 1.14E-013. Percent of Applicable Limit %* * * *E. Gross Alpha1. Total Release Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+002. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations.
Page 130 of 503 Table 2-1CVogUe Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Summation Of All ReleasesUnit: SiteStartino:
1-Jan- 2013 Ending: 31-Dec-2013 Type of Effluent Units 1ST Quarter 2ND Quarter 3RD Ouarter 4TH QuarterA. Fission And Activation Gases1. Total Release Curies 5.18E+00 1.78E+00 1.92E+00 9.27E+002. Average Release rate for period uCi/sec 6.57E-01 2.26E-01 2.44E-01 1.18E+003. Percent of Applicable Limit % * * * *B. Radioiodines
: 1. Total Iodine-131 Curies O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+002. Average Release rate for period uCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+003. Percent of Applicable Limit %* * * *C. Particulates
: 1. Particulates
( Half-Lives
> 8 Days) Curies 1.99E-08 8.89E-08 0.OOE+00 9.92E-072. Average Release rate for period uCi/sec 2.53E-09 1.13E-08 O.OOE+00 1.258E-07
: 3. Percent of Applicable Limit % * * * *D. Tritium1. Total Release Curies 1.95E+01 1.14E+01 1.43E+01 1.39E+012. Average Release rate for period uCi/sec 2.47E+00 1.44E+00 1.81E+00 1.76E+003. Percent of Applicable Limit %* * * *E. Gross Alpha1. Total Release Curies 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+002. Average Release rate for period uCi/sec O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, 2-5B of this report.Page 131 of 503 If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations.
Page 132 of 503 Table 2-2AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Mixed Mode Level ReleasesUnit: 1Starting:
1-Jan- 2013 Ending: 31-Dec-2013 Continuous ModehiU..A- .4A 0I hn;4©I .CTOrO+n n r")Nf f.n 1D.'0 En =r+0rATU fnismr.rFission GasesXe-135Total For PeriodIodinesNo Nuclides FoundParticulates Be-7Sr-90Total For PeriodTritiumH-3Gross AlphaG-AlphaTotal For PeriodCuriesCuriesCuriesCuriesCuriesCuries0.OOE+000.OOE+O00.OOE+001.99E-081.99E-085.78E+000.0OE+00O.OOE+000.OOE+000.OOE+000.OOE+002.38E-082.38E-088.46E+000.OOEO000.OOE+001.80E+001.8OE+000.OOE+0O0.OOE+000.OOE+001.20E+015. 74E-085.74E-089.15E+009.15E+00O.OOE+0O9.14E-07O.OOE+009.14E-071.30E+01O.OOE+00O.00E+00CuriesCuriesCuriesPage 133 of 503 If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations.
Table 2-2AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Mixed Mode Level ReleasesUnit: 1Startina:
1-Jan- 2013 Ending: 31-Dec-2013 Batch ModeMI n ,-I ,n Di lnc0 cI In;,.'I Cy r%. I)Jhlfm rm@m-nr2aDf rl.min 'rAT- MinrmaFission GasesAr-41Kr-85Xe-133Total For PeriodIodinesNo Nuclides FoundParticulates No Nuclides FoundTritiumH-3Gross AlphaNo Nuclides FoundCuriesCuriesCuriesCuriesCuries4.79E-02O.OOE+00O.OOE+004.79E-02O.OOE+000.00E+001.14E-010.00E+00Page 134 of 5034.75E-010.OOE+000.OOE+004.75E-010.OOE+000.00E+007.97E-020.OOE+004.85E-022.32E-026.27E-047.24E-020.OOE+000.00E+005.47E-020.OOE+005.80E-020.OOE+000.OOE+005.80E-020.OOE+000.00E+002. 54E-020.OOE+00CuriesCuriesCuries If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels. SeeTable 2-6 for typical minimum detectable concentrations.
Page 135 of 503 Table 2-2BVogUe Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Mixed Mode Level ReleasesUnit: 2Startina:
1-Jan- 2013 Endina: 31-Dec-2013 Continuous ModeI KnuIM D'aIaa'ce I Inii-c11 &-r"If o2Dn AYUW .4 2z .gua. vu. be" Mug Lý* Mug ýO ~ ..** 0Fission GasesNo Nuclides FoundIodinesNo Nuclides FoundParticulates Sr-89Sr-90Total For PeriodTritiumH-3Gross AlphaNo Nuclides FoundCuriesCuriesCuriesCuriesCuries0.OOE+000.00E+000.OOE+000.OOE+000.OOE+004.09E+000.001E+00 0.00E+000.OOE+005.24E-081.28E-086.52E-082.62E+000.OOE+000.00 E+000.OOE+000.OOE+000.OOE+00O.OOE+002.04E+000.OOE+000.OOE+000.OOE+007.80E-080.OOE+007.80E-080.OOE+000.OOE÷00CuriesCuriesIf Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels. SeeTable 2-6 for typical minimum detectable concentrations.
Page 136 of 503 Table 2-2BVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Mixed Mode Level ReleasesUnit: 2Startina:
1-Jan- 2013 Ending: 31-Dec-2013 Batch Mode1ST Quarter 2ND Quarter 3RD Qua5.67E-01 5.14E-01 3.OOE-(4.47E+00 7.93E-01 1.91E-(5.39E-02 4.77E-04 5.99E-(5.10E+00 1.31E+00 4.91E-4O.OOE+O0 O.OOE+O0 O.OOE+iLiquid ReleasesFission GasesAr-41Xe-133Xe-135Total For PeriodIodinesNo Nuclides FoundParticulates No Nuclides FoundTritiumH-3Gross AlphaNo Nuclides FoundUnitsCuriesCuriesCuriesCuriesCuriesrter)232D502004TH Quarter2.38E-023.83E-025.14E-046.26E-02O.OOE+O0CuriesCuries0.OOE+009.43E+00O.OOE+00O.OOE+002.18E-01O.OOE+O0O.00E+001.26E-01O.OOE+OOO.OOE+OO8.95E-01O.OOE+00CuriesPage 137 of 503 If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations.
Page 138 of 503 Table 2-2CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Mixed Mode Level ReleasesUnit: SiteStartina:
1-Jan- 2013 Ending: 31-Dec-2013 Continuous Mode1ST Quarter 2ND Quarter 3RD QuaNuclide ReleasesFission GasesXe-135Total For PeriodIodinesNo Nuclides FoundParticulates Be-7Sr-89Sr-90Total For PeriodTritiumH-3Gross AlphaG-AlphaTotal For PeriodUnitsirterCuriesCuriesCuriesCuriesCuriesCuriesCuriesO.OOE+00O.OOE+O0O.OOE+00O.OOE+00O.OOE+O01.99E-081.99E-089.86E+000.OOE+00O.OOE+000.OOE+00O.OOE+00O.OOE+000.OOE+005.24E-083. 66E-088.89E-081.11E+01O.OOE+00O.OOE+001.80E+001.80E+000.OOE+000.OOE+0O0.OOE+000.OOE+000.OOE+001.41E+015.74E-085.74E-084TH Quarter9.15E+009.15E+000.OOE+009.14E-077.80E-080.OOE+009.92E-071.30E+01O.OOE+000.O0E+00CuriesCuriesCuriesIf Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations.
Page 139 of 503 Table 2-2CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Mixed Mode Level ReleasesUnit: SiteStarting:
1-Jan- 2013 Endina: 31-Dec-2013 Batch ModeIu 1,,- .1 Dn_1 " I ;0-12 lu r% .4-*'II m m ATU mEU LI =LI =00I =0 ~ LIN L3 J.L I LIMUE3 LV.1 I U ju l~I ~ ~ ~ M I mdu E V§ U e U U ý ~Fission GasesAr-41Kr-85Xe-133Xe-135Total For PeriodlodinesNo Nuclides FoundParticulates No Nuclides FoundTritiumH-3Gross AlphaNo Nuclides FoundCuriesCuriesCuriesCuriesCuriesCuries6.15SE-01 0.OOE+0O4.47E+005.39E-025.14E+000.OOE+000.OOE+009.54E+000.OOE+009.89E-010.OOE+007.93E-014. 77E-041.78E+000.OOE+000.OOE+002.98E-0 10.OOE+O07.86E-022.32E-021.97E-025.99E-051.22E-01O.OOE+00O.OOE+001.81E-01O.OOE+008.18E-02O.OOE+003.83E-025.14E-041.21E-01O.OOE+00O.OOE+009.20E-01O.OOE+0OCuriesCuriesCuriesPage 140 of 503 If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.See Table 2-6 for typical minimum detectable concentrations.
Page 141 of 503 Table 2-3AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Ground Level ReleasesUnit: 1Starting:
1-Jan- 2013 Ending: 31-Dec-2013 Continuous Mode1ST Ouarter 2ND Ouarter 3RD OuaO.OOE+00 O.OOE+00 O.OOE+(Nuclide ReleasesFission GasesNo Nuclides FoundIodinesNo Nuclides FoundParticulates No Nuclides FoundTritiumNo Nuclides FoundUnitsCuriesrterO04TH OuarterO.OOE+00CuriesCuries0.OOE+000.OOE+000.OOE+00O.OOE+00O.OOE+00O.OOE+000.00E+000.OOE+000.OOE+000.OOE+000.OOE+O00.OOE+00CuriesGross AlphaNo Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.Page 142 of 503 See Table 2-6 for typical minimum detectable concentrations.
Table 2-3AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Ground Level ReleasesUnit: 1Starting:
1-Jan- 2013 Ending: 31-Dec-2013 Batch ModeNirlida Rp~lpacac==
Iinitc1 7)Nfl fl..arurlrfIl:uIrfprr 4TM Nfal~urI~
Units JQT n"n or 2ND nuarter 3RD Ong or 4TH n"garterFission GasesNo Nuclides FoundIodinesNo Nuclides FoundParticulates No Nuclides FoundTritiumNo Nuclides FoundCuriesO.OOE+O0O.OOE+00O.OOE+O0O.OOE+O0CuriesO.OOE+O0O.OOE+O0O.OOE+O0O.OOE+00CuriesO.OOE+00O.OOE+O0O.OOE+00O.OOE+00CuriesO.OOE+0oO.OOE+0OO.OOE+00O.OOE+O0Gross AlphaNo Nuclides FoundCuriesO.OOE+0OPage 143 of 503O.OOE+00O.OOE+00O.OOE+00 If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels. SeeTable 2-6 for typical minimum detectable concentrations.
Page 144 of 503 Table 2-3BVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Ground Level ReleasesUnit: 2Startina:
1-Jan- 2013 Endina: 31-Dec-2013 Continuous ModeN.rlide Ilnitc1 flh,2rter 7 Nf Amumrt~~rAmlra~r'r 4TH fliirt~rNuclide Releases Units IST nun -or 2ND inuarter 3RD nua er 4TH nuarterFission GasesNo Nuclides FoundlodinesNo Nuclides FoundParticulates No Nuclides FoundTritiumNo Nuclides FoundCuriesO.OOE+00O.OOE+00O.OOE+00O.OOE+00CuriesO.OOE+00O.OOE+00O.OOE+00O.OOE+00CuriesO.OOE+00O.OOE+00O.OOE+00O.OOE+00CuriesO.OOE+00O.OOE+00O.OOE+00O.OOE+00Gross AlphaNo Nuclides FoundCuriesO.OOE+00O.OOE+00O.OOE+00O.OOE+00If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels. SeeTable 2-6 for typical minimum detectable concentrations.
Page 145 of 503 Table 2-3BVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Ground Level ReleasesUnit: 2Startina:
1-Jan- 2013 Endina: 31-Dec-2013 Batch ModeNi ir"lign cajcIlnifc1 lNfl flnimrh~rfl.iart~r 4TH AnartprUnits IST nua er 2ND nuarter 3RD OuarterFission GasesAr-41Xe-133Xe-135Total For PeriodlodinesNo Nuclides FoundParticulates No Nuclides FoundTritiumH-3Gross AlphaNo Nuclides FoundCuriesCuriesCuriesCuries3.67E-033.01E-023.72E-043.42E-02O.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+O00.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00Curies0.OOE+000.OOE+000.OOE+000.OOE+00CuriesCuriesO.OOE+007.42E-020.OOE+00O.OOE+000.OOE+00O.OOE+000.OOE+000.OOE+00Curies0.OOE+000.OOE+000.OOE+000.OOE+00If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels. SeePage 146 of 503 Table 2-6 for typical minimum detectable concentrations.
Page 147 of 503 Table 2-3CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Ground Level ReleasesUnit: SiteStarting:
1-Jan- 2013 Ending: 31-Dec-2013 Continuous ModeNuclide Releases Units 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH OuarterFission GasesNo Nuclides Found Curies O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+O0lodinesNo Nuclides Found Curies O.OOE+O0 O.OOE+O0 O.OOE+0O O.OOE+O0Particulates No Nuclides Found Curies O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+O0TritiumNo Nuclides Found Curies O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+00Gross AlphaNo Nuclides Found Curies O.OOE+00 O.OOE+O0 O.OOE+0O O.OOE+O0If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels. SeeTable 2-6 for typical minimum detectable concentrations.
Page 148 of 503 Table 2-3CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Ground Level ReleasesUnit:Site Startino:
1-Jan- 2013 Endina: 31-Dec-2013 Batch ModeNirlida gplpacpcilnitc1 ~ Am ,rI~rlrO.artor~Rfl AmiarI~r4TH l.arn~rhUnits 1ST nua er 2ND nua er 3RD nuar+er 4TH nuarterFission GasesAr-41Xe-133Xe-135Total For PeriodIodinesNo Nuclides FoundParticulates No Nuclides FoundTritiumH-3Gross AlphaNo Nuclides FoundCuriesCuriesCuriesCuries3.67E-033.01E-023.72E-043.42E-020.OOE+000.OOE+000.OOE+O00.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00CuriesCuries0.OOE+000.OOE+O00.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00Curies7.42E-020.OOE+000.OOE+000.OOE+00Curies0.OOE+000.OOE+000.OOE+000.OOE+00If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels. SeeTable 2-6 for typical minimum detectable concentrations.
Page 149 of 503 Table 2-4AVogUe Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Ground Level ReleasesUnit: 1Startina:
1-Jan- 2013 Endina: 31-Dec-2013 Cumulative Doses Per QuarterType of Radiation ODCM Lint UnitsGamma Air 5.OOE+00 mRadBeta Air 1.OOE+01 mRad1ST Qtr6.52E-062.30E-06%/o ODCM1.30E-042.30E-052ND Qtr6.47E-052.28E-05%/a ODCM1.29E-032.28E-043RD Qtr5.73E-056.80E-050/b ODCM1. 15E-036.80E-044TH Qtr2.65E-043.33E-04%/o ODCM5.31E-033.33E-03Cumulative Doses Per YearType of Radiation ODCM LintGamma Air 1.00E+01Beta Air 2.OOE+01UnitsmRadmRadYear to End Date3.94E-044.26E-04%/c ODCM3.94E-032.13E-03ReceptorSite Boundary
/ ChildSite Boundary
/ ChildLimitAir Dose Gamma Annual 1.21Air Dose Beta Annual 1.21Page 150 of 503 Table 2-46Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Ground Level ReleasesUnit: 2Starting:
1-Jan- 2013 Endina: 31-Dec-2013 Cumulative Doses Per QuarterType of Radiation ODCM Lint UnitsGamma Air 5.OOE+00 mRadBeta Air 1.00E+01 mRad1ST Qtr1.06E-041.02E-04%/o ODCM2.11E-031.02E-032ND Qtr7.41E-053.69E-05%/o ODCM1.48E-033.69E-043RD Qtr4.19E-061.74E-060/0 ODCM8.38E-051.74E-054TH Qtr3.45E-061.75E-06%/o ODCM6.90E-051.75E-05Cumulative Doses Per YearType of Radiation ODCM LrntGamma Air 1.00E+01Beta Air 2.OOE+01UnitsmRadmRadYear to End Date1.87E-041.42E-04%/o ODCM1.87E-037. 1OE-04ReceptorSite Boundary
/ ChildSite Boundary
/ ChildLimitAir Dose Gamma Annual 1.21Air Dose Beta Annual 1.21Page 151 of 503 Table 2-4CVogUe Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Ground Level ReleasesUnit: SiteStarting:
1-lan- 2013 Endina: 31-Dec-2013 Cumulative Doses Per QuarterType of Radiation ODCM Lmt Units1ST Qtr %/a ODCM 2ND Qtr %/a ODCM 3RD Qtr %/o ODCM 4TH Qtr %/a ODCMGamma AirBeta Air5.OOE+00 mRad 1.12E-04 2.24E-03 1.39E-04 2.78E-03 6.15E-05 1.23E-03 2.69E-04 5.38E-031.00E+01 mRad 1.04E-04 1.04E-03 5.97E-05 5.97E-04 6.97E-05 6.97E-04 3.34E-04 3.34E-03Cumulative Doses Per YearType of Radiation ODCM Lmt UnitsYear to End Date% ODCM ReceptorLimitGamma AirBeta Air1.OOE+01 mRad2.OOE+01 mRad5.81E-045.68E-045.81E-03 Site Boundary
/ Child2.84E-03 Site Boundary
/ ChildAir Dose Gamma Annual 1.21Air Dose Beta Annual 1.21Page 152 of 503 Table 2-5AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Doses To a Member of the Public Due to Radioiodines,
: Tritium, and Particulates in Gaseous ReleasesUnit: 1Startina:
1-Jan- 2013 Endina: 31-Dec-2013 Cumulative Doses Per QuarterOrganBoneGI-LliKidneyUverLungThyroidTotal BodyODCM Lint7.50E+007.50E+007.50E+007.50E+007.50E+007.50E+007.50E+00UnitsmRemmRemmRemmRemmRemmRemmRemIST Qtr7.91E-071.27E-041.27E-041.27E-041.27E-041.27E-041.28E-040/0 ODCM1.05E-051.70E-031.70E-031.70E-031. 70E-031.70E-031.70E-032ND Qtr9.43E-071.85E-041.85E-041.85E-041.85E-041.85E-041.85E-040/o ODCM1.26E-052.46E-032.46E-032.46E-032.46E-032.46E-032.46E-033 RD Qtr0.00E+002.61E-042.61E-042.61E-042.61E-042.61E-042.61E-040/o ODCM0.OOE+003.49E-033.49E-033.49E-033.49E-033.49E-033.49E-034TH Qtr0.OOE+002.81E-042.81E-042.81E-042.81E-042.81E-042.81E-04%/o ODCM0.OOE+003.75E-033.75E-033.75E-033.75E-033.75E-033.75E-03Cumulative Doses per YearOrganBoneGI-LliKidneyLiverLungThyroidTotal BodyODCM Lmt1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 UnitsmRemmRemmRemmRemmRemmRemmRemYear to Ending Date/o ODCM ReceptorLimit1.734E-06 8.545E-04 8.545E-04 8.545E-04 8.545E-04 8.545E-04 8.549E-04
: 1. 156E-55.697E-03 5.697E-03 5.697E-03 5.697E-03 5.697E-03 5.700E-03 Maximum Individual Maximum Individua Maximum Individua Maximum Individua Maximum Individua Maximum Individua Maximum Individual
/ Child/ Child/ Child/ Child/ Child/ Child/ ChildIodine/Part Dose AnnualIodine/Part Dose AnnualIodine/Part Dose AnnualIodine/Part Dose AnnualIodine/Part Dose AnnualIodine/Part Dose AnnualIodine/Part Dose Annual1.211.211.211.211.211.211.21Page 153 of 503 Table 2-5BVogUe Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Doses To a Member of the Public Due to Radioiodines,
: Tritium, and Particulates in Gaseous ReleasesUnit: 2Startina:
1-Jan- 2013 Endina: 31-Dec-2013 Cumulative Doses Per QuarterOrganBoneGI-LliKidneyUverLungThyroidTotal BodyODCM Lmt7.50E+007.50E+007.50E+007.50E+007.50E+007.50E+007.50E+00UnitsmRemmRemmRemmRemmRemmRemmRem1ST QtrO.OOE+O03.OOE-043.OOE-043.OOE-043.OOE-043.OOE-043.OOE-04%/o ODCMO.OOE+O04.OOE-034.OOE-034.OOE-034.OOE-034.OOE-034.OOE-032ND Qtr5.69E-076.15E-056.15E-056.15E-056.15E-056.15E-056.16E-050/o ODCM7.59E-068.20E-048.20E-048.20E-048.20E-048.20E-048.21E-043RD QtrO.OOE+004.67E-054.67E-054.67E-054.67E-054.67E-054.67E-050/o ODCM0.OOE+006.23E-046.23E-046.23E-046.23E-046.23E-046.23E-044TH Qtr9.17E-081.94E-051.93E-051.93E-051.93E-051.93E-051.94E-050/b ODCM1.22E-062.58E-042.58E-042.58E-042.58E-042.58E-042.58E-04Cumulative Doses per YearOrganBoneGI-LliKidneyUverLungThyroidTotal BodyODCM Lmt1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 UnitsmRemmRemmRemmRemmRemmRemmRemYear to Ending Date0/a ODCM ReceptorLimit6.606E-07 4.276E-04 4.276E-04 4.276E-04 4.276E-04 4.276E-04 4.277E-04 4.404E-62.850E-03 2.850E-03 2.850E-03 2.850E-03 2.850E-03 2.851E-03 Maximum Individual Maximum Individua Maximum Individua Maximum Individua Maximum Individua Maximum Individua Maximum Individual
/ Child/ Child/ Child/ Child/ Child/ Child/ ChildIodine/Part Dose Annual 1.21Iodine/Part Dose Annual 1.21Iodine/Part Dose Annual 1.21Iodine/Part Dose Annual 1.21Iodine/Part Dose Annual 1.21Iodine/Part Dose Annual 1.21Iodine/Part Dose Annual 1.21Page 154 of 503 Table 2-5CVogUe Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Doses To a Member of the Public Due to Radioiodines,
: Tritium, and Particulates in Gaseous ReleasesUnit: SiteStarting:
1-Jan- 2013 Endina: 31-Dec-2013 Cumulative Doses Per QuarterOrganBoneGI-LliKidneyUverLungThyroidTotal BodyODCM Lint7.50E+007.50E+007.50E+007.50E+007.50E+007.50E+007.50E+00UnitsmRemmRemmRemmRemmRemmRemmRem1ST Qtr7.91E-074.27E-044.27E-044.27E-044.27E-044.27E-044.28E-04%/o ODCM1.05E-055.70E-035.70E-035.70E-035.70E-035.70E-035.70E-032ND Qtr1.51E-062.46E-042.46E-042.46E-042.46E-042.46E-042.46E-04% ODCM2.02E-053.28E-033.28E-033.28E-033.28E-033.28E-033.28E-033RD QtrO.OOE+003.08E-043.08E-043.08E-043.08E-043.08E-043.08E-04%/ ODCMO.OOE+OO4.11E-034.11E-034.11E-034.11E-034.11E-034.11E-034TH Qtr9.17E-083.OOE-043.OOE-043.OOE-043.OOE-043.OOE-043.OOE-04% ODCM1.22E-064.01E-034.01E-034.01E-034.01E-034.01E-034.01E-03Cumulative Doses per YearOrganBoneGI-LliKidneyUverLungThyroidTotal BodyODCM Lmt1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 UnitsmRemmRemmRemmRemmRemmRemmRemYear to Ending Date% ODCM Receptor2.395E-06 1.282E-03 1.282E-03 1.282E-03 1.282E-03 1.282E-03 1.283E-03 1.597E-05 8.547E-03 8.547E-03 8.547E-03 8.547E-03 8.547E-03 8.551E-03 Maximum Individual Maximum Individual Maximum Individual Maximum Individual Maximum Individual Maximum Individual Maximum Individual
/ ChildI Child/ ChildI Child/ Child/ Child/ ChildIodine/Part Dose AnnualIodine/Part Dose AnnualIodine/Part Dose AnnualIodine/Part Dose AnnualIodine/Part Dose AnnualIodine/Part Dose AnnualIodine/Part Dose AnnualLimit1.211.211.211.211.211.211.21Page 155 of 503 Page 156 of 503 Table 2-6Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013MINIMUM DETECTABLE CONCENTRATIONS GASEOUS SAMPLE ANALYSESStarting:
1-Jan-2013 Ending: 31-Dec-2013 RADIONUCLIDE MDC UNITSKr-87 1.82E-08 iiCi/mlKr-88 2.53E-08 p.Ci/mlXe-133 2.05E-08 pCi/mlXe-133m 8.63E-08 p.Ci/mlXe-135 7.12E-08 P.Ci/mlXe-138 1.05E-07 tCi/ml1-131 7.93E-15*
pCi/mlMn-54 3.94E-14*
!pCi/mlFe-59 2.45E-14*
ilCi/mlCo-58 1.39E-14*
ptCi/mlCo-60 1.75E-14*
ipCi/mlZn-65 2.82E-14*
ptCi/mlMo-99 9.57E-14*
pCi/mlCs-134 1.12E-14*
pCi/mlCs-137 8.71E-15*
ptCi/mlCe-141 8.62E-15*
ptCi/mlCe-144 2.77E-14*
pCi/mlSr-89 1.OOE-13 pCi/mlSr-90 1.OOE-13 pLCi/mlH-3 9.OOE-08 pCi/mlGross Alpha 1.00E-13 p.Ci/ml* Based on an estimated sample volume of 5.7E+08 mis for particulate filters and charcoal cartridges.
Page 157 of 503 Table 2-7AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Batch Release SummaryUnit: 1Startina:
1-Jan- 2013 Endina: 31-Dec-2013 f-, &-^.- DM-ý-eIlni4.1. Number of batch releases2. Total time period for batch releases3. Maximum time period for a batch release4. Average time period for a batch release5. Minimum time period for a batch release( Minutes)(Minutes)
(Minutes)
(Minutes) 1ST Ouarter281.55E+031.OOE+025.52E+017.OOE+002ND Quarter 3RD Quarter 4TH Ouarter42 32 323.38E+03 3.37E+03 2.05E+034.80E+02 1.03E+03 1.50E+028.06E+01 1.05E+02 6.41E+013.OOE+O0 2.10E+01 2.60E+01Year TotalsYear Totals1341.04E+041.03E+037.73E+013.OOE+O0Page 158 of 503 Table 2-7BVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Batch Release SummaryUnit: 2Startina:
1-Jan- 2013 Endina: 31-Dec-2013 r .eaue a eaI InilcICT ga'rN, t r2Nfl flf.2r4~nr 2Dfl flm.~rt~r
~TI.I fluI2rta~r
,3mn n"nr+ar 'ADD n"n or AT&i nu:%r+arb!1. Number of batch releases2. Total time period for batch releases3. Maximum time period for a batch release4. Average time period for a batch release5. Minimum time period for a batch release(Minutes)
(Minutes)
(Minutes)
(Minutes) 392.70E+048.OOE+036.93E+026.OOE+O0128.42E+037.99E+037.02E+021.00E+01117.21E+022.93E+026.55E+012.30E+01125.98E+021.39E+024.98E+012.40E+01Year Totals743.67E+048.OOE+034.97E+026.OOE+O0Page 159 of 503 Table 2-7CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Batch Release SummaryUnit: SiteStartina:
1-lan- 2013 Ending: 31-Dec-2013 gaseous Releases Units 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH Ouarter Year Totals1. Number of batch releases 67 54 43 44 2082. Total time period for batch releases (Minutes) 2.86E+04 1.18E+04 4.09E+03 2.65E+03 4.71E+043. Maximum time period for a batch release (Minutes) 8.OOE+03 7.99E+03 1.03E+03 1.50E+02 8.OOE+034. Average time period for a batch release (Minutes) 4.26E+02 2.19E+02 9.52E+01 6.02E+01 2.26E+025. Minimum time period for a batch release (Minutes) 6.OOE+0O 3.OOE+0O 2.10E+01 2.40E+01 3.OOE+0OPage 160 of 503 Table 2-8AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Abnormal Release SummaryUnit: 1Startina:
1-Jan- 2013 Ending: 31-Dec-2013 Gaseous Releases Units 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH Ouarter Year Totals1. Number of Releases 0 0 0 0 02. Total Time For All Releases (Minutes)
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+003. Maximum Time For A Release (Minutes)
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+004. Average Time For A Release (Minutes)
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+005. Minimum Time For A Release (Minutes)
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+006. Total activity for all releases (Curies ) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00Page 161 of 503 Table 2-8BVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Abnormal Release SummaryUnit: 2Startina:
1-Jan- 2013 Endina: 31-Dec-2013 Gaseous Releases Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH Quarter Year Totals1. Number of Releases 0 0 0 0 02. Total Time For All Releases (Minutes)
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+003. Maximum Time For A Release (Minutes)
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+004. Average Time For A Release (Minutes)
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+005. Minimum Time For A Release (Minutes)
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+006. Total activity for all releases (Curies ) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00Page 162 of 503 Table 2-8CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Gaseous Effluents
-Abnormal Release SummaryUnit: SiteStarting:
1-Jan- 2013 Endina: 31-Dec-2013 Gaseous Releases Units 1ST Ouarter 2ND Ouarter 3RD Ouarter 4TH Ouarter Year Totals1. Number of Releases 0 0 0 0 02. Total Time For All Releases (Minutes) 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+003. Maximum Time For A Release (Minutes) 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+004. Average Time For A Release (Minutes) 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+005. Minimum Time For A Release (Minutes) 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+006. Total activity for all releases (Curies ) 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00Page 163 of 503 3.0 Solid Waste3.1 Regulatory Requirements The ODCM requirements presented in this section are stated in part for Unit 1 andUnit 2.3.1.1 Solid Radioactive Waste System10.2.1 Process Control Program (PCP)Radioactive wastes shall be solidified or dewatered in accordance with the PCP tomeet shipping and transportation requirements during transit and disposal siterequirements 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 radwastereleased from the units, as outlined in Regulatory Guide 1.21 Rev 2.3.2 Solid Waste DataRegulatory Guide 1.21 Rev 2, Table 3 is found in this report as Table 3-1. GELLaboratories performs hard-to-detect analysis for solid waste. Final calculations fornuclides include sample analysis performed on resin from High Integrity Containers.
For Gaseous and Liquid composites, the Georgia Power Environmental Laboratory performs hard-to-detect analysis.
Page 164 of 503 Table 3-1Vogtie Electric Generating PlantRADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT -2013SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2Page 1 of 9JANUARY 1, 2013 THROUGH JUNE 30, 2013Page 165 of 503 Regulatory Guide 1.21, Effluent and Waste Disposal Semi-Annual Report ot Solid Wasteand Irradiated Fuel Shipments
¢/aT,,PERIOD COVERED:
FROM: 1/1/2.013 TO: 6="O/2013 FOR UNIT I & 2A. SOIUD WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not iradbaled tuel)I.. Type of waste UNIT 6 month Est, Total......_peiod ERROR %Dry oornpTes5fe waste, contaninated equip. fro 1ý83E2 25etc. ,V U Ci=-0s A?) Cl 5.27E-1 25Steam Generator Blow Down Resin (Seconcdary Side Resin) _e 6,43EI 252. Es-timat~e of maiom nue~ft compxosion (by peof waste)ISOTOPE PERCENT CURIES[ycaipressible waste, contaminated equip. e~c WNA N/ACo,58 46.933 2.47e-1CO-60 16.526 8.7Ne-2Cr-51 111,053 5.82e-2Fe--55 8.,50 4.48e-2Nb-95 6.288 2.78e-2NI-63 3.843 2.02e-2Mn-54 2.963 1.55e-2Zr-95 2.586 1.38e-2Fe-59 0,538 2.82a.3Zn.65 0.367 1.93e,3Sb-1 25 0.381 1.900-3Cs-137 0.260 1.37e-3Sn-1 13, H-3, U0-57, Cs-134, C-14, St-90 I.% 4,1 le-3Stoam Generator Slow Down Resin (Secondaiy Side Resin) .......Co-58 39.107 9.1 te-3CO-60 23,996 5,560-311.553 2.6N-3M-__..63 7-219 1.63e-3Ct-5I 6.460 1,.27e..3 Mn-64 3.346 7.790.4Nb-95 3.106 7.23e-42.076 4.83e4H-3 1.699 3.96-4Sb- 125 0.544 127e-4Cs- 137 ,0r.4 1,,14ea4Zn-65 0.394 9.17a-5Fe,59 0.363 6.46e-.Co-57 0.226 5.21e-50S- ,1 ,- 5.230e-Cs-1134.
C-14, Sr-90, Co-1 44, Nb-94, Sol.124 >%6-949-2 Table 3-1Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT -2013SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2JANUARY 1, 2013 THROUGH JUNE 30, 2013Page 166 of 503Page 2 of 9 NRC Regulatory Guide 1.21 ReportsPage 1ReportDate:
30812014Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and StreamOuring Period From 01101)2013 to 06&3V2013 Percent Cutaff 0Waste Siream: Resins, Fifters, and Evap BottomnsWaste Volume Curies % ErrorClass Ft^3 MA3 Shipped (Ci)A 0=00E+00 000E+00 0,00E+00
+t/ 25%B 000E+0O 0.OOE÷00 0.00E+00
÷1/ 25%C 0.00E+00 0.00E+00 0.OQE+00
+/1 25%All 0.00E+00 O.OOE+00 0.00E+00
+1- 25%Waste StreamSS DAWDry Active WasteDry Active Waste*waste Vof ure Curies %ErrorClass3Ft' 3 Shipped i CI)C 0.0OE+00 0.OOE+00 0,OOE.O0
+1-25%All ;.47E+03 1.83E+02 5.27E-01
+1 *25%Waste Stream Irradiated Components w~ipVolume Curies ý4 ErrorClass FtA3 M-%3 Shipped iCl)A O0O0E+00 0.OOE+00 0.00E+0O
+/-25%B 0.C0E+00O
.OOE+O0 0.OOE+0O
+1-25%C 0,00E+00 000OE+00 i 0.0OE+00
+1-25%All I0.OOE+00 0,O0E+00 0.OOE+00
+/-26%Table 3-1Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT -2013SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units I and 2Page 167 of 503Page 3 of 9 JANUARY 1, 2013 THROUGH JUNE 30, 2013NRC Regulatory Guide 1.21 ReportsP;UA 2Report Date" 3W/12014Solid Waste Shipped Qftsite for Disposal and Estimates of Major Nuclides by Waste Class and StreamDuring Perfiod From 0110112013 to 06130/2013 Percent Cutoff 0Waste Stream Other WasteSGDU C,.,51N (1olt) SGBO Resin (Clips)Waste Volume Curies % Errorclass FtA3 M,3 Shipped (Ci)A 2,27E+a3 6,43E+O1 2,33E-02 41-25%S 0,00E+00 0.00E+00 0.00E+00
+1-25%C 0,OOE+00 0,00E+O0 0.00E+00
+1-25%All 2,27E+03 6-43E+01 2.33E-02
+1-25%Waste Stream : Sum or A41 4 Categorfes SGBD RESIN (Bolt) SS DAWDry Active Waste* SGBD Resin (Clips)Waste Volume Curies % ErrorClass j FtA3 MA3 Shipped (CI)A [8774E+03 2.47E+02 5.50E-01
+/-25%B 0.00E+00 0.00E+-00 0,OOE+00
+/-25%C .OOE+00 0.OOE+00 0.00E+00
+1-25%AJI 8j 74 E+03 2ý47E.02 5,50E.01
+1.25%-Combined Waste Type Shipment, Major Volume Waste Type ShownTable 3-1Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT AND WASTE DISPOSAL REPORT -2013Page 168 of 503 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units I and 2JANUARY 1, 2013 THROUGH JUNE 30, 2013NRC Regulatory Guide 1.21 ReportsPage 4 of 9Page 1Report Date: 3/6I2014..... ... ..... ... ... ..... ..... .... ..............,... ... .... .. ..... ......Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and StreamDuring Period From 01/0112013 to 06/3012013 "7L .".7 "" ' .... ..... .... " "........
". ..... .... .." ........
.... ... .........
..... ... ..: .. ; .."'.....:., ', Number of Shipments Mode of Transportation Destinatlei' 5 Hittman Transport ENERGY SOLUTIONS 4 Hiftman Transport GTSD GALLAHERTABLE 3-1Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT -2013Page 169 of 503 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2JULY 1, 2013 THROUGH DECEMBER 31, 2013Page 5 of 9Regulatory Guide 1.21: Effluent and Waste Disposal Semi-Annual Report of Solid Wasteand Irradiated Fuel Shipments PERIOD COVERED:
FROM: 72013 ... TO: 12/31L21 3 FOR UNIT: !A.2 _A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)Type of waste UNIT 6 month Esi, Total...........
period ERROR %Rosins and Filters (NRC Waste Class A) m3 102 EI 25Ci 2.,3Ei 25Dry compressible waste. corntaminated equip. T -5.01 El 25etc., (NRC Waste Class A) CI 2.64E-2 25Steam Generator Blow Down Rosin (Secondary Side tm 3.70E1 25(NRC Waste Class A Ci 5.,58E,3 252. Eslimate of major nuclide composition (by tyr* of waste)ISOTOPE PERCENT CURIESResins and Filters (NRC Waste Class A)Ni-63 42.644 1.02E1Com60 28,314 5.75Fe-55 15.718 3.75Cs-137 5.080 1,21Co-68 3.604 859E.1SbI25 1.335 3.1BE-1 ,Cs-134 ................
0.849 2.02E-1C-14 , 0.815 1.94E-1Mn-54 0.749 1-78E-lNb-95 0.199 4.73E-2Ni-59 0,194 4.62E-2Zr-95 0.130 3.11 E-27n-65 0,106 2.53E-2H-3,Co-57,Sr-9.0,Cr-51
,Tc-99,Fe-.9Sn.1-13,Nb-94.Ce-144,Pu-241
>0.1% 6.25E-2Dry compressible waste, contaminated equip. etc NA .A(NRC Waste Class A)_________
________Co058 46.319 1.22E-2Co-60 1-199 4.80E-3Fe-5, 9,334 2,46E-3Cr-5i 9-137 2.41E-3Nb-95 4.647 1.23E-3NI-63 4.249 2.02E-2Mn,54 3.183 1.12E-3_____________________________
2.522 6.65E-4Fe-59 0.495 1.31E-4Sb'125 0.396 1.04E-40.3w 1.04E-4Cs-137 0.287 7.57E-5Sn-I 13, K-.3, Co-57, Cs-134, C-14, S-90 .. I1% 2.12E-4TABLE 3-1Page 170 of 503 Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT -2013SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units I and 2Page 6 of9JULY 1, 2013 THROUGH DECEMBER 31, 2013Steam Oenerator Blow Down Resin (Secondary Side Resin)ANRC Waste Class A) ........Co-58 36.717 2,05E-3Co-60 28.398 1,5aE.3Fe-55 14.106 7.78E-4Ni-63 6.85. " 3-E-4Mn-54 4.234 2.36E-4Cr-51 2,871 160,E-,4Nb-95 1.990 iE11-4Zr-95 T.871 1.04E-4Sb-I25 0.599 3.34E-5Zn-66 0,499 2,78E-5Cs-137 0.461 2.57E-5H--3 0.359 2.OOE-50.275 1.53E-5Fe-59 0274 1 ,53E-5Sn-i 13 0.244 1.38E-6Cs-134, C-14,.St-.90
.A. .1% 1.3GE-53. Solid Waste, Visposiflon NuMkhe o ý pmnt3 Re,-*ntidqqouTr!ý ordatiwTransler Truck with CaskDotnationSolutions Barmvell Processing Facility16043 Dunbarton BlvdBarnwall, SC2 Filler1 DAWTransfer Ttuck with CaskExclusive use transfaT truck~Energy Solutions 1560 Bear Creek RdOak Ridge, TNEnergy Soluions1560 Bear Creek Rd?Oak Ridge, TNEnergy Soluilons
,628 Gallahei RdEKingston.
TN2 Otier (SeM Resin)transfer Truck13. IRRADIATED FUEL SHIPMENTS (Disp~osition)
NUmbot of ShiuMents Mgde gf TrMnsportation None NIA,Nglirjation NIATABLE 3-1Page 6 of 503 Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT -2013SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2Page 172 of9JULY 1, 2013 THROUGH DECEMBER 31, 2013Page 172 of 5003 NRC Regulatory Guide 1.21 ReportsNogeReport Date: 3*12014Solid Waste Shipped Offsite for Disposal and Estimates of Ma~or Nuclides by Waste Class and StreamDuring Period From 0710112013 to 1213012013 Percent Cutoff: 0Waste Stream, Resins, Filters, and Evap BottomsHIC 11743-01 SFP FILTERS 07-08 RPF Resin TUFS Membranes 3698-13Waste Volume Cures % ErrorClass FtA3 M^3 Shipped (Cl)A 316iE+02 1.02E+01 2.38E*01
+f- 25%B 0.00E+00 0,00E+O0 0.OOE+00
+1- 25%C 0O.0E+00 0,00E+00 0.OOE+00
+1- 25%All 3.61E+02 1.02E+01 2.38E+01
+/-25%Waste Stream : Dry Active WasteDry Actve WastekWaste Volume CuriesI %ErrorCl~ass FtA3 M113 Shipped j (CIqA 1,77E+03 6-01 E+01 2,64&~02
-5a 0.0QE+00 O.0OE+00 0.0OE+00 f 1-25%C 0.O0Q4-00 0O0OE+00 0.00E+00 j +1-25%All 1.77E+0~3 5.01 E+01 2.641202
+1-25%Waste Stream ,Irradiated Components Waste Volume Curies % ErrorClass FtA3 MA3 Shipped (Ci)A 0=00E+00 0.00E.00 0.00E+00
+/-25%B 0-OOE+00 O.OOE+00 0.00E+00
+1-25%C 0.002E+00 0.OOE+00 0.00E+O0
+-25%All 0.0oE+00 o 0,0E1+O0
.OOE+00 +/-25%TABLE 3-1Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT -2013SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2Page 8 of 9Page 173 of 503 JULY 1, 2013 THROUGH DECEMBER 31, 2013NRC Regulatory Guide 1.21 ReportsTPege 2Date: W362914Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and StreamDuring Peiod From 07t01/2013 to 12130/2013 Percent Cutoff' 0Waste Stream Other WasteSGBD RESIN (Bolt) SGBD Resin (Clips)Waste Volume Curies % ErrorClass FtA3 MA3 Shipped ICi)A 1,31E+03 3,70E+01 5.58E-03
+1-25%B O.00E+00 O.00E+00 O.OE+0-25%
C Q,00E+O0 0.OOE+00 O,OOE+00
+/-25%All 1,31E+03 3.70E+01 6.68E-O3
+/-25%Waste Stream : Sum of All 4 Categories SGBD RESIN (Bolt) HIC 11743-OIRPF Resin TUFS Membranes SFP FILTERS 07-08 Dry Active Waste*3698-13 SGBD Resin (Clips)waste Volume Curies % ErrorClass Ft&3 MA3 Shipped P)iA 144E+03 9.73E+01 2,39E+01
+1-25%B O-0OE+00 04012+00 0.00E+00
+/-25%C 0.00E+O0 O.00E+00 OOOE.+00
+1-25"AAli 3,44E+.03 9.73E+01 2.39E+0O1
+1-25%-Combined Waste Type Shipment, Major Volume Waste ae ShownTABLE 3-1Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT -2013SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Page 174 of 503 Urits I ard 2AllY 1,2013 THROIiH IJECEI'IJER 31,2013NRC Regulatory Guide 1.21 ReportsPage9 d 9Page IReport Date: :lill 01Solid Waste Shipped Offsite for 15sposaland Estimatesof Major Nuclides by Waste Class and StreamDurtng Period From 0710112013 to 1213012013 Number of Shlpmetats
,_of Transportation Destination 3 Hittman Transport O'tQC<Koong Facity.3 HlttmanTransport L T1 10 N"2 HillmanTransport IGT IGALLAHER 4.0 Doses to Members ofthe Public inside the Site BoundaryPage 175 olf503 4.1 Regulatory Requirements ODCM 7.2.2.3 states in part:"The report shall also include assessment of the radiation doses fromradioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due totheir activities inside the SITE BOUNDARY during the report period; thisassessment must be performed in accordance with Chapter 6. All assumptions used in making these assessments
( i.e., specific
: activity, exposure time, andlocation) shall be included in the report".4.2 Demonstration of Compliance The location of concern within the site boundary is the Visitors Center. Theactivities at the Visitor Center consist of occasional attendance at meetingsand/or short visits for informational purposes.
There will be no radiation dose at this location due to radioactive liquideffluents.
Delineated in Table 4-1 for this location are the values of the basicdata assumed in the dose assessment due to radioactive gaseous effluents.
Listed in this table are distance and direction from a point midway between thecenter of Unit 1 and the Unit 2 reactors, the dispersion and deposition factorsfor any releases from the plant vent (mixed mode) and from the turbinebuilding (ground level), and the estimated maximum occupancy factor for anindividual and the assumed age group of this individual.
The source term is listed in Tables 2-2A, and 2-2B for the mixed modereleases.
Similarly, it is listed in tables 2-3A and 2-3B for the ground levelreleases.
The maximum doses in units of mrem to a MEMBER OF THE PUBLIC due totheir activities inside the site boundary during the reporting period arepresented in Table 4-1.Page 176 of 503 Table 4-1Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Doses to a Member of the Public Due to Activities Inside the Site BoundaryUnit: SiteStarting:
1-Jan-2013 Ending: 31-Dec-2013 Location Name:Distance (kilometers):
Sector:Occupancy Factor:Age Group:Ground Level ReleaseGround Level ReleaseMixed Mode ReleaseMixed Mode ReleaseVisitor's Center Receptor4.47E-01SE4.57E-04ChildNoble GasParticulate and Radioiodine Noble GasParticulate and Radioiodine X/Q (sec/m3):
5.93E-06X/Q (sec/m3):
5.58E-06X/Q (sec/m3):
7.12E-07X/Q (sec/m3):
6.74E-07D/Q (m-2): 2.28E-08D/Q (m-2): 5.77E-09BoneLiverTotal BodyThyroidKidneyLungGI-LliNG Total BodyWhole Body DoseUnitsmRemmRemmRemmRemmRemmRemmRemmRemmRem1ST Quarter1.97E-112.33E-072.33E-072.33E-072.33E-072.33E-072.33E-077.43E-083.07E-072ND Quarter3.65E-111.32E-071.32E-071.32E-071.32E-071.32E-071.32E-079.26E-082.25E-073RD Quarter0.OOE+001.66E-071.66E-071.66E-071.66E-071.66E-071.66E-074.09E-082.07E-074TH Quarter4.57E-131.62E-071.62E-071.62E-071.62E-071.62E-071.62E-071.78E-073.40E-07Year5.66E-116.92E-076.92E-076.92E-076.92E-076.92E-076.92E-073.86E-071.08E-06Page 177 of 503 Table 4-1Vogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2013Doses to a Member of the Public Due to Activities Inside the Site BoundaryUnit: SiteStarting:
1-Jan-2013 Ending: 31-Dec-2013 Location Name:Distance (kilometers):
Sector:Occupancy Factor:Age Group:Ground Level ReleaseGround Level ReleaseGround Level ReleaseMixed Mode ReleaseMixed Mode ReleaseUnits 3&4 Construction 4.83E-01SW2.37E-01AdultNoble GasParticulate and Radioiodine Particulate and Radioiodine Noble GasParticulate and Radioiodine X/Q (sec/m3):
1.81E-05X/Q (sec/m3):
6.93E-06X/Q (sec/m3):
6.96E-06X/Q (sec/m3):
9.75E-07X/Q (sec/m3):
9.17E-07D/Q (m-2): 2.88E-08D/Q (m-2): 2.88E-08D/Q (m-2): 7.14E-09BoneUverTotal BodyThyroidKidneyLungGI-LliNG Total BodyWhole Body DoseUnitsmRemmRemmRemmRemmRemmRemmRemmRemmRem1ST Quarter1.37E-081.93E-041.93E-041.93E-041.93E-041.93E-041.93E-045.60E-052.49E-042ND Quarter2.52E-081.06E-041.06E-041.06E-041.06E-041.06E-041.06E-046.59E-051.72E-043RD QuarterO.OOE+001.32E-041.32E-041.32E-041.32E-041.32E-041.32E-042.91E-051.62E-044TH Quarter1.64E-101.29E-041.29E-041.29E-041.29E-041.29E-041.29E-041.27E-042.56E-04Year3.91E-085.61E-045.61E-045.61E-045.61E-045.61E-045.61E-042.78E-048.39E-04Page 178 of 503 Page 179 of 503 5.0Total Dose from Uranium Fuel Cycle (40CFRI90) 5.1 Regulatory Requirements ODCM 5.1 states in part that the annual (calendar year) dose or dosecommitment to any MEMBER OF THE PUBLIC due to releases ofradioactivity and to radiation from uranium fuel cycle sources shall belimited to less than or equal to 25 mrems to the whole body or to anyorgan, except the thyroid, which shall be limited to less than or equal to75 mrems.5.2 Demonstration of Compliance No dose limits stated in ODCM Sections 2.1.3, 3.1.3, and 3.1.4 were exceeded.
Therefore, compliance with 40 CFR 190 dose limits was demonstrated inaccordance with the requirements of ODCM Section 5.1.3.6.0 Meteorological DataODCM 7.2.2.2 states in part:The Radioactive Effluent Release Report shall include an annualsummary of hourly meteorological data collected over the previous year.This annual summary may be either in the form of an hour-by-hour listingof wind speed, wind direction, atmospheric stability, and precipitation (ifmeasured) 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, thelicensee has the option of retaining this summary of requiredmeteorological data on site in a file that shall be provided to the NRCupon 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 fromthe liquid and gaseous effluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, respectively.
Thereport shall include an explanation as to why the inoperability of liquid orgaseous effluent monitoring instrumentation was not corrected within thespecified time requirement.
Page 180 of 503 7.1.2Description of Deviations The inoperability of liquid and gaseous effluent monitors not corrected within the specified time for this reporting period is detailed below.Overall, resources and major projects effected the amount resources thatwere allocated to repairing the monitors.
During the first half of the year,there were two new radiation monitors installed and a forced maintenance outage. When applicable, compensatory measures were utilized:
: a. 1RE-12839 This monitor was out of service due to a failed sample pump and abad heat trace circuit.
Work to return to service overlapped with workfor 2RE-1 2839.This monitor was returned to service after 36 days.b. 1FT-1085A This transmitter has been delayed with repair because of theunavailability of parts. A new transmitter arrived in September 2013and was returned to service.c. IFT-12839 Due to a failed calibration, the transmitter was sent offsite for repair.As a result, it was out of service greater than 30 days.d. 1FIS-12862 The flow switch was discovered malfunctioning while performing awork order. Repair will be targeted for this year.e. 2RE-0018The flow balance valve malfunctioned preventing the throttle of flow forthe radiation monitor.
The original work instructions were revised toinclude a total valve rebuild.
The time that it took to develop new workinstructions and create a clearance for the system extended the out ofservice time for the monitor.
It has been returned to service.f. 2RE-0020B The radiation monitor's skid pump would trip intermittently.
Troubleshooting and replacement of the pump lasted forapproximately a week from the start date. As a result, the monitor wasreturned to service in 33 days.Later in the year, the motor and starter switch was replaced.
This wasdelayed as a result of the forced maintenance outage. It has beenreturned to service.g. 2RE-0848This monitor was declared out of service when the low voltage powersupply failed. The CPU board was replaced.
Work orders related torepairing Turbine Drain Header valves extended the out of servicetime beyond 30 days. The monitor is now in service.Page 181 of 503
: h. 2FT-12442 At the beginning of the year, this transmitter was declared out ofservice when it was found out of tolerance for voltage.
The transmitter was sent offsite for repair which caused it to be out of service for > 30days.This flow transmitter was taken out of service after failing acomparison with 2FT-12835 in September 2013. The transmitter is inservice.i. AF17620ADilution flow indication was reading incorrectly.
It is planned to berepaired this year.j. AFQ17620This totalizer was not incrementing correctly.
Due to partsobsolescence, an equivalency determination had to be performed tomake the repair. It has been returned to service.7.2 Tanks Exceeding Curie Content Limits7.2.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the report shall include a description ofthe events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specifications 5.5.12.7.2.2 Description of Deviations Limits for outdoor liquid hold-up tanks used for radioactive liquids werenot exceeded during this reporting period.Limits for the gas storage tanks were not exceeded during this reporting period.8.0 Changes to the Vogtle Electric Generating Plant Offsite DoseCalculation Manual (ODCM)8.1 Regulatory Requirements ODCM 7.2.2.5 states in part that changes to the ODCM shall be submitted with the Radioactive Effluent Release Report. These changes may bedue to changes in the radiological environmental monitoring programsampling locations as required by ODCM 4.1.1.2.3 or changes to dosecalculation locations as required by ODCM 4.1.2.2.2.
Land usesPage 182 of 503 and dose calculation locations within five miles of VEGP must bedetermined by a land use census as required by ODCM 4.1.2.8.2 Description of ChangesVersion 29 of the "OFFSITE DOSE CALCULATION MANUAL FORSOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRICGENERATING PLANT" was released in February 2013. The following changes were made:1) A correction to the Dose Equivalent 1-131 definition for thyroidconversion factors.
The ODCM reference stated that the factors werefrom Table E-7 of NRC Regulatory Guide 1.109, Revision 1, 1977 whileChapter 15 of the VEGP FSAR, Table 15A-5 has a footnote that statesthese factors are from Table 2.1 of the EPA Federal Guidance Report 11(EPA-520/1-88-020).
The FSAR definition takes precedence over theODCM definition.
The software that uses these dose conversion factorsalready contained the correct conversion factors.2) Equation 2.7 contained a typo with operational signs. Variables fas andXis should be multiplied instead of summed for the desired results.3) Action Statement 51 was revised to account for the ability to analyzefixed filter paper with gamma spectroscopy after new radiation monitorswere installed for the Plant Vent System.9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems9.1 Regulatory Requirements ODCM 7.2.2.7 states in part:As required by Sections 2.1.5 and 3.1.6, licensee initiated MAJORCHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (liquidand gaseous) shall be reported to the Nuclear Regulatory Commission inthe Radioactive Effluent Release Report covering the period in which thechange 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 FSARupdate.PCP 12.1 states in part:Page 183 of 503 Licensee major initiated changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in theRadioactive Effluent Release Report for the period in which the changewas implemented.
9.2 Description of Major ChangesGaseous Radwaste SystemThere were no major changes to the gaseous radwaste systems in the 2013assessment period.Liquid Radwaste SystemMajor changes to the liquid radwaste facilities are those that contribute tosignificant changes in release; i.e., either decreases or increases inrelease volume or activity/dose.
There were no major changes to the liquid radwaste systems occurredduring the 2013 assessment period.Solid Radwaste SystemThere were no major changes to the solid radwaste systems in the 2013assessment period.Page 184 of 503 Appendix AVogtle Electric Generating PlantCARBON- 14Carbon-14 (C-14) is a naturally-occurring radionuclide with a 5730 year half life. Nuclear weaponstesting in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere.
Nuclearpower plants also produce C-14, but the amount is infinitesimal compared to what has been distributed in the environment due to weapons testing and what is produced by natural cosmic ray interactions.
As nuclear plants have improved gaseous waste processing systems and improved fuel performance, thepercentages of "principal radionuclides" in gaseous effluents have changed, and C-14 has become alarger percentage.
"Principal radionuclides" are determined based on public dose contribution or theamount of activity discharged compared to other radionuclides of the same effluent type. In Revision 2(June 2009) of Regulatory Guide 1.21 (RG 1.21), "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," the NRC recommended re-evaluating "principal radionuclides" and reporting C-14 as appropriate.
In 2010 Radioactive Effluent ReleaseReports, virtually all U. S. nuclear power plants started reporting C-14 amounts released and resulting doses to the maximally exposed member of the public.Because C-14 is considered a hard-to-detect radionuclide which must be chemically separated from theeffluent stream before it can be measured, RG 1.21 provides the option of calculating the C-14 sourceterm based on power generation.
The Electric Power Research Institute (EPRI) developed an acceptedmethodology for calculating C-14, and published the results in Technical Report 1021106 (December 2010), "Estimation of Carbon- 14 in Nuclear Power Plant Gaseous Effluents."
Evaluation of C- 14 inradioactive liquid effluents is not required because the quantity and dose contribution has beendetermined to be insignificant.
At Plant Vogtle, the annual quantity of C-14 released in gaseous effluents was estimated to be 12.08Curies (per unit). Approximately 30% of the C-14 released is in the form of 14C02 and is incorporated into plants through photosynthesis.
Ingestion dose results from this pathway.
The remaining 70% isestimated to be organic.
Both the organic and inorganic forms of C-14 contribute to inhalation dose. Achild is the maximally exposed individual, and bone dose is the highest organ dose. Using the dosecalculation methodology from the Vogtle ODCM, the resulting bone dose to a child located at thecontrolling receptor location would be 8.46E-02 mrem in a year which is 0.56% of the regulatory limitof 15 mrem per year (per unit) to any organ due to gaseous effluents.
The resulting total body dose to achild located at the controlling receptor location would be 1.69E-02 mrem in a year which is 0. 11% ofthe regulatory limit of 15 mrem per year (per unit) total body dose due to gaseous effluents Page 185 of 503 Appendix BVogtle Electric Generating PlantCORRECTED REPORTSThis section contains corrected reports for typos contained in the 2011 and 2012 Annual Radiological Effluent Release Reports:2011 ReportTable 2-5A/U 1 Year to Date -The exponential term for Organ doses were truncated due toformatting.
The values should be E-07/E-04.
Table 2-5C/Site Year to Date -Bone dose is the same as U I2012 ReportTable I-2A/U I (continuous) 3rd quarter -Gross Alpha value should be 0.Table 2-2C/Site (continuous) 4th quarter -The gas total value should be 1.19E+O 1.Table 2-3B/U2 (batch) 3rd and 4th quarters
-H-3 values should be zero> Table 2-5C/Site Year to Date -All values were from the 2011 ARERR. They were updated tocorrect to 2012 values.Page 186 of 503 Table 2-5AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2011Doses To A Member Of The Public Due To Radioiodines,
: Tritium, and Particulates in Gaseous ReleasesUnit: 1Starting:
1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per QuarterOrganBoneGI-LliKidneyLiverLungThyroidTotal BodyODCM Units7.50E+00 mRem7.50E+00 mRem7.50E+00 mRem7.50E+00 mRem7.50E+00 mRem7.50E+00 mRem7.50E+00 mRem1ST Qtr3.13E-071.10E-041.10E-041.10E-041. 1OE-041. 10E-041. 10E-040/h ODCM4.18E-061.46E-031.46E-031.46E-031.46E-031.46E-031.46E-032ND Qtr6.64E-092.43E-052.43E-052.43E-052.43E-052.43E-052.43E-050/o ODCM8.86E-083.24E-043.24E-043.24E-043.24E-043.24E-043.24E-043RD Qtr0.OOE+003.06E-053.06E-053.06E-053.06E-053.06E-053.06E-050/0 ODCMO.OOE+004.08E-044.08E-044.08E-044.08E-044.08E-044.08E-044TH Qtr4.26E-071.11E-041.11E-041.11E-041.11E-041.11E-041.11E-04%/c ODCM5.69E-061.48E-031.48E-031.48E-031.48E-031.48E-031.48E-03Cumulative Doses per YearOrgan ODCMBone 1.500E+01 GI-Lli 1.500E+01 Kidney 1.500E+01 Liver 1.500E+01 Lung 1.500E+01 Thyroid 1.500E+01 Total Body 1.500E+01 UnitsmRemmRemmRemmRemmRemmRemmRemYear to Ending7.465E-07 2.751E-04 2.751E-04 2.751E-04 2.751E-04 2.751E-04 2.751E-04 0/04.977E-06 1.834E-03 1.834E-03 1.834E-03 1.834E-03 1.834E-03 1.834E-03 ReceptorLimitMaximumMaximumMaximumMaximumMaximumMaximumMaximumIndividual Individual Individual Individual Individual Individual Individual
///////ChildChildChildChildChildChildChildIodine/Part Iodine/Part Iodine/Part Iodine/Part Iodine/Part Iodine/Part Iodine/Part Dose AnnualDose AnnualDose AnnualDose AnnualDose AnnualDose AnnualDose Annual1.211.211.211.211.211.211.21Page 187 of 503 Table 2-5CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2011Doses To A Member Of The Public Due To Radioiodines,
: Tritium, and Particulates in Gaseous ReleasesUnit: SiteStarting:
1-Jan- 2011 Ending: 31-Dec-2011 Cumulative Doses Per QuarterOrgan ODCM UnitsBone 7.50E+00 mRemGI-Lli 7.50E+00 mRemKidney 7.50E+00 mRemLiver 7.50E+00 mRemLung 7.50E+00 mRemThyroid 7.50E+00 mRemTotal Body 7.50E+00 mRem1ST Qtr3.13E-071.62E-041.62E-041.62E-041.62E-041.62E-041.62E-04%/o ODCM4.18E-062.17E-032.17E-032.17E-032.17E-032.17E-032.17E-032ND Qtr6.64E-091.03E-041.03E-041.03E-041.03E-041.03E-041.03E-04%/o ODCM8.86E-081.38E-031.38E-031.38E-031.38E-031.38E-031.38E-033RD QtrO.OOE+002.52E-042.52E-042.52E-042.52E-042.52E-042.52E-04% ODCM0.0OE+003.36E-033.36E-033.36E-033.36E-033.36E-033.36E-034TH Qtr4.26E-073.37E-043.37E-043.37E-043.37E-043.37E-043.37E-040/a ODCM5.96E-064.97E-034.97E-034.97E-034.97E-034.97E-034.97E-03Cumulative Doses per YearOrgan ODCMBone 1.500E+01 GI-Lli 1.500E+01 Kidney 1.500E+01 Liver 1.500E+01 Lung 1.500E+01 Thyroid 1.500E+01 Total Body 1.500E+01 UnitsmRemmRemmRemmRemmRemmRemmRemYear to Ending Date6.164E-04 8.909E-04 8.908E-04 8.908E-04 8.908E-04 8.908E-04 8.909E-04
%/o ODCM Receptor4.109E-03 Maximum Individual 5.939E-03 Maximum Individual 5.939E-03 Maximum Individual 5.939E-03 Maximum Individual 5.939E-03 Maximum Individual 5.939E-03 Maximum Individual 5.939E-03 Maximum Individual
/ Child/ Child/ ChildI ChildI Child/ Child/ ChildLimitIodine/Part Iodine/Part Iodine/Part Iodine/Part Iodine/Part Iodine/Part Iodine/Part Dose AnnualDose AnnualDose AnnualDose AnnualDose AnnualDose AnnualDose Annual1.211.211.211.211.211.211.21Page 188 of 503 Nuclides ReleasedFission & Activation ProductsNo Nuclides FoundTritiumH-3Dissolved And Entrained GasesNo Nuclides FoundGross Alpha Radioactivity G-AlphaTable 1-2AVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2012Liquid Effluents Unit: 1Starting:
1-Jan- 2012 Ending: 31-Dec-2012 Continuous ModeUnits 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterCuries O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0Curies 9.82E-02 1.07E-01 6.30E-02 4.84E-02Curies O.OOE+O0 O.OOE+O0 O.OOE+0O O.0OE+O0Curies O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0*Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-4 for typical minimum detectable concentrations.
Page 189 of 503 Table 2-2CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2012Gaseous Effluents
-Mixed Mode Level ReleasesUnit: SiteStarting:
1-Jan- 2012 Ending: 31-Dec-2012 Continuous ModeNuclides ReleasedFission GasesKr-85MXe-133Xe- 135Total For PeriodUnitsCuriesCuriesCuries1ST Quarter2ND Quarter3RD Quarter4TH Quarter0.OOE+000.OOE+000.OOE+00O.OOE+00O.OOE+00O.OOE+009.46E-024.75E+005.37E+001.10E-015.52E+006.24E+00Curies O.OOE+00 0.OOE+00 1.02E+01 1.19E+01lodines1-131Curies0.OOE+000.DOE+000.OOE+000.OOE+008.94E-068.94E-060.OOE+00O.OOE+00Total For PeriodParticulates Co-58Sr-89Sr-90CuriesCuriesO.OOE+001.13E-070.OOE+004.41E-073. 13E-084.73E-071.08E-073.07E-071.86E-084.34E-07O.OOE+004.19E-08O.OOE+004.19E-08Curies O.OOE+00Curies 1.13E-07Total For PeriodTritiumH-3Curies2.62E+011.66E+018.38E+00Gross AlphaNo Nuclides Found Curies O.OOE+00 O.OOE+00 O.OOE+00*If Not Detected, Nuclide is Not Reported.
Zeroes in this table indicate that no radioactivity was present at detectable levels.6.83E+000.OOE+00Page 190 of 503 See Table 2-6 for typical minimum detectable concentrations.
Table 2-3BVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2012Gaseous Effluents
-Ground Level ReleasesUnit: 2Starting:
1-Jan- 2012 Ending: 31-Dec-2012 Batch ModeNuclides Released Units 1ST Quarter 2ND Quarter 3RD Quarter 4TH QuarterFission GasesNo Nuclides Found Curies 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00IodinesNo Nuclides Found Curies 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00Particulates No Nuclides Found Curies 0.OOE+O0 0.OOE+00 0.OOE+00 O.OOE+O0TritiumH-3 Curies 0.OOE+00 0.OOE+O0 O.OOE+00 O.O0E+00Gross AlphaNo Nuclides Found Curies 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00Page 191 of 503 Table 2-5CVogtle Electric Generating PlantRADIOACTIVE EFFLUENT RELEASE REPORT -2012Doses To A Member Of The Public Due To Radioiodines,
: Tritium, and Particulates in Gaseous ReleasesUnit: SiteStarting:
1-Jan- 2012 Ending: 31-Dec-2012 Cumulative Doses Per QuarterOrgan ODCM UnitsBone 7.50E+00 mRemGI-Lli 7.50E+00 mRemKidney 7.50E+00 mRemLiver 7.50E+00 mRemLung 7.50E+00 mRemThyroid 7.50E+00 mRemTotal Body 7.50E+00 mRem1ST Qtr1.33E-075.68E-045.68E-045.68E-045.68E-045.68E-045.68E-04% ODCM1.78E-063.63E-043.63E-043.63E-043.63E-043.63E-043.63E-042ND Qtr1.76E-063.63E-043.63E-043.63E-043.63E-043.63E-043.63E-04% ODCM2.35E-054.84E-034.84E-034.84E-034.84E-034.84E-034.84E-033RD Qtr1. 15E-061.90E-041.90E-041.90E-041.90E-042.05E-041.90E-040/b ODCM1.54E-052.53E-032.53E-032.53E-032.53E-032.74E-032.53E-034TH Qtr4.93E-081.57E-041.57E-041.57E-041.57E-041.57E-041.57E-040/b ODCM6.57E-072.09E-032.09E-032.09E-032.09E-032.09E-032.09E-03Cumulative Doses per YearOrgan ODCMUnits Year to Ending Date0/b ODCMReceotorLimitBoneGI-LliKidneyLiverLungThyroidTotal Body1.500E+01 mRem1.50015+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 1.500E+01 mRemmRemmRemmRemmRemmRem7.465E-07 8.909E-04 8.908E-04 8.908E-04 8.908E-04 8.908E-04 8.909E-04 2.064E-05 5.939E-03 5.939E-03 5.939E-03 5.939E-03 5.939E-03 5.939E-03 Maximum Individual Maximum Individual Maximum Individual Maximum Individual Maximum Individual Maximum Individual Maximum Individual
/ Child/ Child/ Child/ Child/ ChildI Child/ ChildIodine/Part Iodine/Part Iodine/Part Iodine/Part Iodine/Part Iodine/Part Iodine/Part Dose Annual 1.21Dose Annual 1.21Dose Annual 1.21Dose Annual 1.21Dose Annual 1.21Dose Annual 1.21Dose Annual 1.21Page 192 of 503 Appendix CVEGP ODCM Version 29OFFSITE DOSE CALCULATION MANUALFORSOUTHERN NUCLEAR OPERATING COMPANYVOGTLE ELECTRIC GENERATING PLANTVersion 29February 2013Page iii of 503 TABLE OF CONTENTSPAGET A B LE O F C O N T E N T S ...............................................................................................................
iL IS T O F T A B L E S ......................................................................................................................
ivL IS T O F F IG U R E S ....................................................................................................................
viR E F E R E N C E S ........................................................................................................................
v iiC H A PT E R 1: IN T R O D U C T IO N .............................................................................................
1-1C HA PTER 2: LIQ U ID EFFLU ENTS .......................................................................................
2-12.1 LIMITS OF OPERATION 2-12.1.1 Liquid Effluent Monitoring Instrumentation Control 2-12.1.2 Liquid Effluent Concentration Control 2-72.1.3 Liquid Effluent Dose Control 2-102.1.4 Liquid Radwaste Treatment System Control 2-112.1.5 Major Changes to Liquid Radioactive Waste Treatment Systems 2-122.2 LIQUID RADWASTE TREATMENT SYSTEM 2-132.3 LIQUID EFFLUENT MONITOR SETPOINTS 2-172.3.1 General Provisions Regarding Setpoints 2-172.3.2 Setpoints for Radwaste System Discharge Monitors 2-192.3.3 Setpoints for Monitors on Normally Low-Radioactivity Streams 2-252.4 LIQUID EFFLUENT DOSE CALCULATIONS 2-262.4.1 Calculation of Dose 2-262.4.2 Calculation of Ai, 2-272.4.3 Calculation of CF~v 2-282.5 LIQUID EFFLUENT DOSE PROJECTIONS 2-372.5.1 Thirty-One Day Dose Projections 2-372.5.2 Dose Proiections for Specific Releases 2-372.6 DEFINITIONS OF LIQUID EFFLUENT TERMS 2-38CHAPTER 3: GASEO US EFFLUENTS
.................................................................................
3-13.1 LIMITS OF OPERATION 3-13.1.1 Gaseous Effluent Monitoring Instrumentation Control 3-13.1.2 Gaseous Effluent Dose Rate Control 3-73.1.3 Gaseous Effluent Air Dose Control 3-103.1.4 Control on Gaseous Effluent Dose to a Member of the Public 3-113.1.5 Gaseous Radwaste Treatment System Control 3-123.1.6 Manor Changes to Gaseous Radioactive Waste Treatment Systems 3-13iVER 29 TABLE OF CONTENTS (continued)
PAGE3.2 GASEOUS WASTE PROCESSING SYSTEM 3-143.3 GASEOUS EFFLUENT MONITOR SETPOINTS 3-203.3.1 General Provisions Regarding Noble Gas Monitor Setpoints 3-203.3.2 Setpoint for the Final Noble Gas Monitor on Each Release Pathway 3-223.3.3 Setpoints for Noble Gas Monitors on Effluent Source Streams 3-253.3.4 Determination of Allocation
: Factors, AG 3-273.3.5 Setpoints for Noble Gas Monitors with Special Requirements 3-293.3.6 Setpoints for Particulate and Iodine Monitors 3-293.4 GASEOUS EFFLUENT COMPLIANCE CALCULATIONS 3-303.4.1 Dose Rates at and Beyond the Site Boundary 3-303.4.2 Noble Gas Air Dose at or Beyond Site Boundary 3-313.4.3 Dose to a Member of the Public at or Beyond Site Boundary 3-353.4.4 Dose Calculations to Support Other Requirements 3-383.5 GASEOUS EFFLUENT DOSE PROJECTIONS 3-443.5.1 Thirty-One Day Dose Proiections 3-443.5.2 Dose Proiections for Specific Releases 3-453.6 DEFINITIONS OF GASEOUS EFFLUENT TERMS 3-46CHAPTER 4: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ....................
4-14.1 LIMITS OF OPERATION 4-14.1.1 Radiological Environmental Monitoring 4-14.1.2 Land Use Census 4-94.1.3 Interlaboratory Comparison Program 4-104.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS 4-11CHAPTER 5: TOTAL DOSE DETERMINATIONS
..................................................................
5-15.1 LIMIT OF OPERATION 5-15.1.1 Applicabilitv 5-15.1.2 Actions 5-15.1.3 Surveillance Requirements 5-15.1.4 Basis 5-15.2 DEMONSTRATION OF COMPLIANCE 5-3CHAPTER 6: POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIRACTIVITIES INSIDE THE SITE BOUNDARY
...................................................
6-16.1 REQUIREMENT FOR CALCULATION 6-16.2 CALCULATIONAL METHOD 6-12VER 29 TABLE OF CONTENTS (continued)
PAGEC H A PT E R 7: R E P O R T S .......................................................................................................
7-17.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT 7-17.1.1 Requirement for Report 7-17.1.2 Report Contents 7-17.2 RADIOACTIVE EFFLUENT RELEASE REPORT 7-37.2.1 Requirement for Report 7-37.2.2 Report Contents 7-37.3 MONTHLY OPERATING REPORT 7-67.4 SPECIAL REPORTS 7-6CHAPTER 8: METEOROLOGICAL MODELS .......................................................................
8-18.1 ATMOSPHERIC DISPERSION 8-18.1.1 Ground-Level Releases 8-18.1.2 Elevated Releases 8-28.1.3 Mixed-Mode Releases 8-48.2 RELATIVE DEPOSITION 8-58.2.1 Ground-Level Releases 8-58.2.2 Elevated Releases 8-58.2.3 Mixed-Mode Releases 8-68.3 ELEVATED PLUME DOSE FACTORS 8-6CHAPTER 9: METHODS AND PARAMETERS FOR CALCULATION OF GASEOUSEFFLUENT PATHWAY DOSE FACTORS, Raipj ...........................................
9-19.1 INHALATION PATHWAY FACTOR 9-19.2 GROUND PLANE PATHWAY FACTOR 9-29.3 GARDEN VEGETATION PATHWAY FACTOR 9-39.4 GRASS-COW-MILK PATHWAY FACTOR 9-69.5 GRASS-GOAT-MILK PATHWAY FACTOR 9-99.6 GRASS-COW-MEAT PATHWAY FACTOR 9-12CHAPTER 10: DEFINITIONS OF EFFLUENT CONTROL TERMS ........................................
10-110.1 TERMS SPECIFIC TO THE ODCM 10-110.2 TERMS DEFINED IN THE TECHNICAL SPECIFICATIONS 10-53VER 29 LIST OF TABLESTable 2-1.Table 2-2.Table 2-3.Table 2-4.Table 2-5.Table 2-6.Table 2-7.Table 2-8.Table 3-1.Table 3-2.Table 3-3.Table 3-4.Table 3-5.Table 3-6.Table 3-7.Table 3-8.Table 3-9.Table 3-10.Table 3-11.Table 3-12.Table 4-1.Radioactive Liquid Effluent Monitoring Instrumentation Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Radioactive Liquid Waste Sampling and Analysis ProgramApplicability of Liquid Monitor Setpoint Methodologies Parameters for Calculation of Doses Due to Liquid Effluent ReleasesElement Transfer FactorsAdult Ingestion Dose FactorsSite-Related Ingestion Dose Factors, AT,Radioactive Gaseous Effluent Monitoring Instrumentation Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Radioactive Gaseous Waste Sampling and Analysis ProgramApplicability of Gaseous Monitor Setpoint Methodologies Dose Factors for Exposure to a Semi-Infinite Cloud of Noble GasesDose Factors for Exposure to Direct Radiation from Noble Gases inan Elevated Finite PlumeAttributes of the Controlling ReceptorRaipj for Ground Plane Pathway, All Age GroupsRaipj for Inhalation
: Pathway, Child Age GroupRaipj for Inhalation
: Pathway, Adult Age GroupRaipj for Cow Meat Pathway, Child Age GroupRaipj for Garden Vegetation, Child Age GroupRadiological Environmental Monitoring ProgramPAGE2-32-52-82-182-302-312-322-353-33-53-83-213-333-343-373-393-403-413-423-434-34VER 29 LIST OF TABLES (Continued)
Table 4-2.Table 4-3.Table 4-4.Table 4-5Table 6-1.Table 8-1.Table 9-1.Table 9-2.Table 9-3.Table 9-4.Table 9-5.Table 9-6.Table 9-7.Table 9-8.Table 9-9.Table 9-10.Table 9-11.Table 9-12.Table 9-13.Table 9-14.Table 9-15.Reporting Levels for Radioactivity Concentrations in Environmental SamplesValues for the Minimum Detectable Concentration (MDC)Radiological Environmental Monitoring Locations Groundwater Monitoring Locations Attributes of Member of the Public Receptor Locations Inside the SiteBoundaryTerrain Elevation Above Plant Site GradeMiscellaneous Parameters for the Garden Vegetation PathwayMiscellaneous Parameters for the Grass-Cow-Milk PathwayMiscellaneous Parameters for the Grass-Goat-Milk PathwayMiscellaneous Parameters for the Grass-Cow-Meat PathwayIndividual Usage FactorsStable Element Transfer DataInhalation Dose Factors for the Infant Age GroupInhalation Dose Factors for the Child Age GroupInhalation Dose Factors for the Teenager Age GroupInhalation Dose Factors for the Adult Age GroupIngestion Dose Factors for the Infant Age GroupIngestion Dose Factors for the Child Age GroupIngestion Dose Factors for the Teenager Age GroupIngestion Dose Factors for the Adult Age GroupExternal Dose Factors for Standing on Contaminated GroundPAGE4-74-84-124-156-28-79-59-89-119-149-159-169-179-209-239-269-299-329-359-389-415VER 29 LIST OF FIGURESFigure 2-1.Figure 2-2.Figure 2-3.Figure 3-1.Figure 3-2.Figure 3-3.Figure 3-4.Figure 3-5.Figure 4-1.Figure 4-2.Figure 4-3.Figure 4-4.Figure 4-5Figure 8-1.Figure 8-2.Figure 8-3.Figure 8-4.Figure 8-5.Figure 8-6.Figure 8-7.Figure 8-8.Figure 8-9.Figure 8-10.Unit 1 Liquid Radwaste Treatment SystemUnit 2 Liquid Radwaste Treatment SystemLiquid Radwaste Discharge PathwaysSchematic Diagram of the Gaseous Radwaste Treatment SystemSchematic Diagram of the Unit 1 Plant Vent Release PathwaySchematic Diagram of the Unit 2 Plant Vent Release PathwaySchematic Diagram of the Turbine Building Vent Release Pathway(Typical of Both Units)Schematic Diagram of the Radwaste Processing Facility Ventilation Release PathwayTerrestrial Stations Near Site BoundaryTerrestrial Stations and Aquatic Stations, 0-5 MilesTerrestrial Stations Beyond 5 MilesDrinking Water StationsGroundwater Monitoring WellsVertical Standard Deviation of Material in a Plume (a,)Terrain Recirculation Factor (Kr)Plume Depletion Effect for Ground Level ReleasesPlume Depletion Effect for 30-Meter ReleasesPlume Depletion Effect for 60-Meter ReleasesPlume Depletion Effect for 100-Meter ReleasesRelative Deposition for Ground-Level ReleasesRelative Deposition for 30-Meter ReleasesRelative Deposition for 60-Meter ReleasesRelative Deposition for 100-Meter (or Greater)
ReleasesPAGE2-142-152-163-153-163-173-183-194-164-174-184-194-208-88-98-108-118-128-138-148-158-168-176VER 29 REFERENCES
: 1. J.S. Boegli, R.R. 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 thePurpose of Evaluating Compliance with 10 CFR 50, Appendix I," U.S. NRC Regulatory Guide 1.109, March 1976.3. "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for thePurpose 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 inRoutine 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 inRoutine 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 ReactorReleases for the Purpose of Implementing Appendix I," U.S. NRC Regulatory Guide1.113, April 1977.7. W.R. Stokes Ill, 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, June1984.8. Direct communication with the Water Resources
: Division, U.S. Geological Survey, U.S.Department of the Interior, February 1985.9. Bernd Kahn, et al., "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 PowerCompany, May 9, 1988.11. Voqtle Electric Generating Plant Units 1 and 2 Final Safety Analysis Report, GeorgiaPower Company.12. Voqtle Electric Generating Plant Units 1 and 2 Environmental Report -Operating LicenseStage, Georgia Power Company.13. Memo from A.C. Stalker, Georgia Power Company, to D.F. Hallman, Georgia PowerCompany, May 9, 1988.14. Voaqtle Electric Generating Plant Land Use Survey -1988, Georgia Power Company, April1988.15. Letter to Southern Company Services from Pickard, Lowe, and Garrick, Inc., Washington, D.C., April 27,1988.7VER 29
: 16. Letter to Bill Ollinger, Georgia Power Company, from T.L. Broadwell, Georgia PowerCompany,
: 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 ofRadiolo-gical 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 DOE/TIC-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, 1995.23. Letter to Mary Beth Lloyd, Southern Nuclear Operating
: Company, from Steven Bearce,Southern Company Services, February 2, 2009.8VER 29 VEGP ODCMCHAPTER 1INTRODUCTION The Offsite Dose Calculation Manual is a supporting document of the Technical Specifications.
Assuch, it describes the methodology and parameters to be used in the calculation of offsite dosesdue to radioactive liquid and gaseous effluents, and in the calculation of liquid and gaseouseffluent monitoring instrumentation alarm setpoints.
In addition, it contains the following:
* The controls required by the Technical Specifications, governing the radioactive effluentand radiological environmental monitoring programs.
* Schematics of liquid and gaseous radwaste effluent treatment
: systems, which includedesignation 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 AnnualRadiological Environmental Operating Report and the Radioactive Effluent ReleaseReport required by the Technical Specifications.
The ODCM will be maintained at the plant for use as a reference guide and training document ofaccepted 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 allapplicable areas. Any computer software used to perform the calculations described will bemaintained current with the ODCM.Equations and methods used in the ODCM 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).1-1VER 29 VEGP ODCMCHAPTER 2LIQUID 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 ControlIn 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 ActionsWith a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint lessconservative 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 thesetpoint 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 nextRadioactive Effluent Release Report, per Technical Specification 5.6.3, why this inoperability wasnot 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, CHANNELCALIBRATION, and CHANNEL OPERATIONAL TEST operations at the frequencies shown inTable 2-2. Specific instrument numbers are provided in parentheses for information only. Thenumbers apply to each unit. These numbers will help to identify associated channels or loops andare not intended to limit the requirements to the specific instruments associated with the number.2-1 VER 292-1VER 29 VEGP ODCM2.1.1.4 BasisThe 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 liquideffluents.
The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted inaccordance with the methodology and parameters in Section 2.3 to ensure that the alarm/trip willoccur prior to exceeding the limits of Section 2.1.2. The OPERABILITY and use of thisinstrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 ofAppendix A to 10 CFR Part 50.2-2VER 29 VEGP ODCMTable 2-1. Radioactive Liquid Effluent Monitoring Instrumentation OPERABILITY Requirementsa Instrument MinimumChannelsOperable ACTION1. Radwaste Monitors Providing Alarm and Automatic Termination of Releasea. Liquid Radwaste Effluent Line (RE-0018) 1 37b. Steam Generator Blowdown Effluent Line 1 38(RE-0021)
: c. Turbine Building Effluent Line (RE-0848) 1 382. Radwaste Monitors Providing Alarm, but Not Automatic Termination of ReleaseNSCW Effluent Line (RE-0020 A) 1 39NSCW Effluent Line (RE-0020 B) 1 393. Flowrate Measurement Devicesa. Liquid Radwaste Effluent Line (FT-0018),
1 40(FT-1084A1B),
or (FT-1085A/B)
: b. Steam Generator Blowdown Effluent Line 1 40(FT-0021)
: c. Flow to Blowdown Sump (AFQI-7620, F17620A) 1 40a. All requirements in this table apply to each unit.2-3VER 29 VEGP ODCMTable 2-1 (contd).
Notation for Table 2-1 -ACTION Statements ACTION 37 -With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases may continueprovided that prior to initiating a release:a. The local radiation monitor reading (if functional) is recorded at leastonce per 12 hours during the release or at least two independent samples are analyzed in accordance with Section 2.1.2.3, andb. At least two technically qualified members of the Facility Staffindependently verify the discharge line valving and the release ratecalculations.
Otherwise, suspend release of radioactive effluents via this pathway.ACTION 38 -With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases via this pathwaymay continue provided the local radiation monitor reading (if functional) isrecorded at least once per 12 hours or grab samples are analyzed for grossradioactivity at a MINIMUM DETECTABLE CONCENTRATION no higher than 1x 10-7 ltCi/mL using gross beta/gamma counting or 5 x 10-7 &#xfd;iCi/mL for theprincipal gamma emitters using gamma-ray spectroscopy.
: a. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 pCi/gram DOSE EQUIVALENT 1-131.b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 fiCi/gram DOSE EQUIVALENT I-131.ACTION 39 -With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases via this pathwaymay continue provided that, at least once per 12 hours, the local radiation monitor reading (if functional) is recorded or grab samples are collected andanalyzed for radioactivity at a MINIMUM DETECTABLE CONCENTRATION nohigher than 1 x 10-7 ItCi/mL using gross beta/gamma counting or 5 x 10-7 RtCi/mLfor the principal gamma emitters using gamma-ray spectroscopy.
ACTION 40 -With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases via this pathway2-4VER 29 VEGP ODCMmay continue provided the flowrate is estimated at least once per 4 hours duringactual releases.
Pump curves generated in place may be used to estimate flow.2-5 VER292-5VER 29 VEGP ODCMTable 2-2. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Surveillance Requirementsd CHANNEL CHANNELInstrument CHANNEL SOURCE CALIBRA-OPERATIONAL CHECK CHECK TION TEST1. Radwaste Monitors Providing Alarm and Automatic Termination of Releasea. Liquid RadwasteEffluent Line(RE-0018)
D P Rb Ra(l)b. Steam Generator Blowdown EffluentLine (RE-0021)
D M Rb Ra(l)c. Turbine BuildingEffluent Line(RE-0848)
D M Rb Ra(l)2. Radwaste Monitors Providing Alarm, but Not Automatic Termination of ReleaseNSCW Effluent Line(RE-0020 A&B) D M Rb Ra(2)3. Flowrate Measurement Devicesa. Liquid RadwasteEffluent Line(FT-001 8),(FT-1084A/B),
or(FT- 1085A/B)
Dc NA R NAb. Steam Generator Blowdown EffluentLine (FT-0021)
Dc NA R NAc. Flow to BlowdownSump (AFQI-7620, F17620A)
Dc NA R Q2-5VER 29 VEGP ODCMTable 2-2 (contd).
Notation for Table 2-2a. In addition to the basic functions of a CHANNEL OPERATIONAL TEST (Section10.2):(1) The CHANNEL OPERATIONAL TEST shall also demonstrate thatautomatic isolation of this pathway and control room annunciation occurs(for item a. below only); and control room CRT indication occurs (if any ofthe 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 thatcontrol room annunciation occurs (for item a. below only); and thatcontrol 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".
: b. The initial CHANNEL CALIBRATION shall be performed using one or more of thereference standards certified by the National Institute of Standards andTechnology or using standards that have been obtained from suppliers thatparticipate in measurements assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy andmeasurement range. For subsequent CHANNEL CALIBRATION, sources thathave been related to the initial calibration shall be used.c. CHANNEL CHECK shall consist of verifying indication of flow during periods ofrelease.
CHANNEL CHECK shall be made at least once per 24 hours on dayson which continuous,
: periodic, or batch releases are made.2-6VER 29 VEGP ODCMd. All requirements in this table apply to each unit.2-7VER 29 VEGP ODCM2.1.2 Liquid Effluent Concentration ControlIn accordance with Technical Specifications 5.5.4.b and 5.5.4.c, the concentration ofradioactive material released in liquid effluents to UNRESTRICTED AREAS shall belimited 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. Fordissolved or entrained noble gases, the concentration shall be limited to 1 x 10 -4 pCi/mLtotal activity.
2.1.2.1 Applicability This limit applies at all times.2.1.2.2 ActionsWith the concentration of radioactive material released in liquid effluents toUNRESTRICTED 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 theconcentration at the point of release is maintained within the limits of Section 2.1.2.2.1.2.4 BasisThis control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than tentimes 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 inbodies of water in UNRESTRICTED AREAS will result in exposures within (1) theSection II.A design objectives of Appendix 1, 10 CFR 50, to a MEMBER OF THEPUBLIC, and (2) the limits of 10 CFR 20.1301 to the population.
The concentration limitfor dissolved or entrained noble gases is based upon the assumption that Xe-1 35 is thecontrolling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission onRadiological Protection (ICRP) Publication 2 (1959). The resulting concentration of 2 x104 was then multiplied by the ratio of the effluent concentration limit for Xe-1 35, statedin Appendix B, Table 2, Column 1 of 10 CFR 20 (paragraphs 20.1001 to 20.2401),
tothe 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 104 ptCi/mL.2-7VER 29 VEGP ODCM2-8 VER292-8VER 29 VEGP ODCMTable 2-3.Radioactive Liquid Waste Sampling and Analysis Program_-_ Sam pling and Analysis Requirementsa b MINIMUMMINIMUMDETECTABLE CONCENTRA-Minimum TO MCLiquid Release Sampling Analysis Type of Activity TION (MDC)Type FREQUENCY FREQUENCY Analysis (jiCi/mL)
A. BATCH RELEASESPRINCIPAL 5 E-7GAMMAEMITTERSP PEach BATCH Each BATCH 1-131 1 E-61. Waste Monitor Dissolved and 1 E-5Tank p Entrained GasesOne BATCH/M M (Gamma Emitters)
: 2. Drainage of H-3 I E-5System P MEach BATCH COMPOSITE Gross Alpha 1 E-7Sr-89, Sr-90 5 E-8P QEach BATCH COMPOSITE Fe-55 I E-6B. CONTINUOUS RELEASESPRINCIPAL 5 E-7GAMMAEMITTERSWContinuous COMPOSITE 1-131 1 E-6Dissolved and 1 E-5M Entrained GasesGrab Sample M (Gamma Emitters)
Waste Water H-3 1 E-5Retention Basinc MContinuous COMPOSITE Gross Alpha 1 E-7Sr-89, Sr-90 5 E-8QContinuous COMPOSITE Fe-55 1 E-62-8VER 29 VEGP ODCMTable 2-3 (contd).
Notation for Table 2-3a. All requirements in this table apply to each unit.b. Terms printed in all capital letters are defined in Chapter 10.c. The VVWRB will not be considered a release point until there is a confirmed primary to secondary leak. Once a primary to secondary leak has beenconfirmed, this composite shall be analyzed as specified until the leak isrepaired.
This surveillance will continue until three consecutive weeklycomposite samples have shown no activity above the MDC.2-10VER 29 VEGP ODCM2-10VER 29 VEGP ODCM2.1.3 Liquid Effluent Dose ControlIn accordance with Technical Specifications 5.5.4.d and 5.5.4.e, the dose or dosecommitment to a MEMBER OF THE PUBLIC from radioactive materials in liquideffluents
: 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 bodyand to less than or equal to 5 mrem to any organ, andb. During any calendar year to less than or equal to 3 mrem to the total body and toless than or equal to 10 mrem to any organ.2.1.3.1 Applicability These limits apply at all times.2.1.3.2 ActionsWith 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 NuclearRegulatory Commission within 30 days a special report which identifies the cause(s) forexceeding the limit(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 thecurrent calendar quarter and the current calendar year shall be determined, for eachunit, in accordance with Section 2.4.2.1.3.4 BasisThis control is provided to implement the requirements of Sections II.A, III.A and IV.A ofAppendix 1, 10 CFR Part 50. The limits stated in Section 2.1.3 implement the guides setforth in Section Il.A of Appendix I. The ACTIONS stated in Section 2.1.3.2 provide therequired operating flexibility and at the same time implement the guides set forth inSection IV.A of Appendix I to assure that the releases of radioactive material in liquideffluents will be kept "as low as is reasonably achievable."
Also, for fresh water siteswith drinking water supplies that can be potentially affected by plant operations, there isreasonable 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 40CFR Part 141. The dose calculations in Section 2.4 implement the requirements in2-10VER 29 VEGP ODCMSection III.A of Appendix I, which state that conformance with the guides of Appendix Ibe shown by calculational procedures based on models and data, such that the actualexposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely tobe 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 areconsistent with the2-11VER 29 VEGP ODCMmethodology provided in Regulatory Guide 1.109 (Reference
: 3) and Regulatory Guide1.113 (Reference 6).This control applies to the release of liquid effluents from each unit at the site. Theliquid effluents from shared LIQUID RADWASTE TREATMENT SYSTEMs are to beproportioned between the units.2.1.4 Liquid Radwaste Treatment System ControlIn accordance with Technical Specification 5.5.4.f, the LIQUID RADWASTETREATMENT SYSTEM shall be OPERABLE.
The appropriate portions of the systemshall be used to reduce radioactivity in liquid wastes prior to their discharge when theprojected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREASwould exceed 0.06 mrem to the total body or 0.2 mrem to any organ of a MEMBER OFTHE PUBLIC in 31 days.2.1.4.1 Applicability This limit applies at all times.2.1.4.2 ActionsWith radioactive liquid waste being discharged without treatment and in excess of theabove limits and any portion of the LIQUID RADWASTE TREATMENT SYSTEM not inoperation, prepare and submit to the Nuclear Regulatory Commission within 30 days aspecial 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 theinoperability,
: b. Action(s) taken to restore the inoperable equipment to OPERABLE status, andc. 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 leastonce per 31 days, in accordance with Section 2.5, during periods in which the LIQUIDRADWASTE TREATMENT SYSTEMs are not being fully utilized.
The LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLEby meeting the controls of Sections 2.1.2 and 2.1.3.2-11VER 29 VEGP ODCM2.1.4.4 BasisThe OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensures thatthis system will be available for use whenever liquid effluents require treatment prior torelease to the UNRESTRICTED AREAS. The requirement that the appropriate portionsof this system be used when specified provides assurance that the releases ofradioactive materials in liquid effluents will be kept "as low as is reasonably achievable."
This control implements the requirements of 10 CFR Part 50.36a, General DesignCriterion 60 of Appendix A to 10 CFR Part 50, and the design objective given in SectionlI.D of Appendix I to 10 CFR Part 50. The specified limits governing the use ofappropriate 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 Appendix1, 10 CFR Part 50, for liquid effluents.
This control applies to the release of radioactive materials in liquid effluents from eachunit at the site. For units with shared radwaste
: systems, the liquid effluents from theshared system are to be proportioned among the units sharing that system.2.1.5 Major Changes to Liquid Radioactive Waste Treatment SystemsLicensee initiated MAJOR CHANGES TO LIQUID RADIOACTIVE WASTETREATMENT 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 Section7.2.2.7.b. Shall become effective upon review and approval by the Vice President
-Plant.2-12VER 29 VEGP ODCM2.2 LIQUID RADWASTE TREATMENT SYSTEMThe Vogtle Electric Generating Plant is located on the west bank of the Savannah Riverapproximately 151 river miles from the Atlantic Ocean. There are two pressurized waterreactors on the site. Each unit is served by a separate LIQUID RADWASTETREATMENT SYSTEM; however, certain components are shared between the twosystems.
Schematics of the LIQUID RADWASTE TREATMENT SYSTEMs arepresented in Figure 2-1 and Figure 2-2. Liquid discharge pathways are shown in Figure2-3.All liquid radwastes treated by the LIQUID RADWASTE TREATMENT SYSTEM arecollected in 5,000-gallon or 20,000-gallon waste monitor tanks. Releases from thewaste monitor tanks are to the discharge line from the blowdown sump, and from thereto the Savannah River. The blowdown sump also receives input from the waste waterretention basins, turbine plant cooling water blowdown, and nuclear service coolingwater blowdown.
Additional dilution water is available from the cooling tower makeupwater bypass line.Although no significant quantities of radioactivity are expected in the nuclear servicecooling water, the steam generator blowdown processing system, or the turbine buildingdrain system, these effluent pathways are monitored as a precautionary measure.
Themonitors serving the latter two pathways provide for automatic termination of releasesfrom these systems in the event that radioactivity is detected above predetermined levels. These two systems discharge to the waste water retention basin. Sampling andanalysis of releases via all three of these pathways must be sufficient to ensure that theliquid effluent dose limits specified in the controls of Section 2.1.3 are not exceeded.
2-13VER 29 VEGP ODCMTo Unit 2FilterDeminWaste Monitor Waste MonitorTank: Tank:5,000 gal 20,000 galI IToFigure 2-1. Unit 1 Liquid Radwaste Treatment System2-14VER 29 VEGP ODCMfrom Laundry and Hot ShowerTank(Unit 1)FilterD ni n iWaste Monitor Waste MonitorTank: Tank:5,000 gal 20,000 galTo Discharge Figure 2-2. Unit 2 Liquid Radwaste Treatment System2-15VER 29 VEGP ODCMRiverRadioactivity Monitors0 1(2) RE00200 1(2) REO0210 1(2) RE0848G 1(2) RE0018*The blowdown gump is common to both units.Figure 2-3. Liquid Radwaste Discharge Pathways2-16VER 29 VEGP ODCM2.3 LIQUID EFFLUENT MONITOR SETPOINTS 2.3.1 General Provisions Regarding Setpoints Liquid monitor setpoints calculated in accordance with the methodology presented inthis section will be regarded as upper bounds for the actual high alarm setpoints.
Thatis, a lower value for the high alarm setpoint may be established or retained on themonitor, 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 isplanned for a particular
: pathway, or if there is no detectable activity in the plannedrelease, 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 systemdischarge
: monitors, setpoints are determined to assure that the limits of Section 2.1.2are 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 ofradioactivity, and to terminate the release where this is possible.
Section 2.1.1establishes the requirements for liquid effluent monitoring instrumentation.
Table 2-4lists the monitors for which each of the setpoint methodologies is applicable.
2-17VER 29 VEGP ODCMTable 2-4. Applicability of Liquid Monitor Setpoint Methodologies Liquid Radwaste Discharge MonitorsSetpoint Method: Section 2.3.2Release Type: BATCHUnit I or Unit 2 Liquid Waste Treatment System EffluentMonitor:
1RE-0018
/ 2RE-0018Normally Low-Radioactivity Streams with Termination or Diversion upon AlarmSetpoint Method: Section 2.3.3Release Type: CONTINUOUS Unit 1 or Unit 2 Steam Generator Blowdown EffluentMonitor:
1 RE-0021 / 2RE-0021Unit 1 or Unit 2 Turbine Building Drain EffluentMonitor:
1 RE-0848 / 2RE-0848Normally Low-Radioactivity Streams with Alarm OnlySetpoint Method: Section 2.3.3Release Type: CONTINUOUS Unit 1 or Unit 2 Nuclear Service Cooling Water System EffluentMonitors (2 per unit): 1RE-0020 A and B2RE-0020 A and B2-18VER 29 VEGP ODCM2.3.2 Setpoints for Radwaste System Discharge Monitors2.3.2.1 Overview of MethodLIQUID RADWASTE TREATMENT SYSTEM effluent line radioactivity monitors areintended to provide alarm and automatic termination of release prior to exceeding thelimits specified in Section 2.1.2 at the point of release of the diluted effluent into theUNRESTRICTED AREA. Therefore, their alarm/trip setpoints are established to ensurecompliance with the following equation (equation adapted from Addendum to Reference 1):c'f- <- TF" CECL (2.1)F+fwhere:CECL = the Effluent Concentration Limit corresponding to the mix of radionuclides in the effluent being considered for discharge, in g.Ci/mL.c = the setpoint, in jgCi/mL, of the radioactivity monitor measuring theconcentration of radioactivity in the effluent line prior to dilution andsubsequent release.
The setpoint represents a concentration which, ifexceeded, could result in concentrations exceeding the limits of Section2.1.2 in the UNRESTRICTED AREA.f = the effluent flowrate at the location of the radioactivity
: monitor, in gpm.F = the dilution stream flowrate which can be assured prior to the releasepoint to the UNRESTRICTED AREA, in gpm. A predetermined dilutionflowrate 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 apractical monitor setpoint which could accommodate effluent releases atconcentrations higher than the ECL values stated in 10 CFR 20,Appendix B, Table 2, Column 2; the tolerance factor must not exceed avalue 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) issatisfied in a practicable manner based on the calculated ECL fraction of theradionuclide mixture and the dilution stream flowrate that can be assured for the2-19VER 29 VEGP ODCMduration of the release (Fd), by calculating the maximum permissible effluent flowrate(fin) and the radioactivity monitor setpoint (c).The setpoint method presented below is applicable to the release of only one tank ofliquid 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 maynot ensure that the limits of Section 2.1.2 are not exceeded.
2.3.2.2 Setpoint Calculation StepsStep 1: Determine the radionuclide concentrations in the liquid wastebeing considered for release in accordance with the sampling andanalysis requirements of Section 2.1.2.All liquid radwastes treated by the LIQUID RADWASTE TREATMENT SYSTEM arecollected in waste monitor tanks for sampling and analysis.
The 5,000-gallon wastemonitor tanks are recirculated for a minimum of 30 minutes, and the 20,000-gallon waste monitor tanks are recirculated for a minimum of 45 minutes.
This mixing assuresthat a representative sample can be taken from the tank.The total concentration of the liquid waste is determined by the results of all requiredanalyses on the collected sample, as follows:YZCi = C + ZC +Cf + + c + YICg (2.2)s gwhere:C, = the gross concentration of alpha emitters in the liquid waste, not less thanthat measured in the most recent applicable composite sample.Cs = the concentration of strontium radioisotope s (Sr-89 or Sr-90) in theliquid waste, not less than that measured in the most recent applicable composite sample.Cf = the concentration of Fe-55 in the liquid waste, not less than thatmeasured in the most recent applicable composite sample.Ct = the concentration of H-3 in the liquid waste, not less than that measuredin the most recent applicable composite sample.Cg = the concentration of gamma emitter g in the liquid waste as measured bygamma ray spectroscopy performed on the sample for the release underconsideration.
The Cg term will be included in the analysis of each waste sample; terms for grossconcentrations of alpha emitters, Sr-89, Sr-90, Fe-55, and tritium will be included in2-20VER 29 VEGP ODCMaccordance with the sampling and analysis program required for the waste stream (seeSection 2.1.2). For each analysis, only radionuclides identified and detected abovebackground for the given measurement should be included in the calculation.
Whenusing the alternate setpoint methodology of step 5.b, the historical maximum values ofCa, Cs, Cf, and Ct shall be used.Step 2: Determine the required dilution factor for the mix ofradionuclides detected in the waste.Measured radionuclide concentrations are used to calculate ECL fractions.
The ECLfractions are used along with a safety factor to calculate the required dilution factor; thisis the minimum ratio of dilution flowrate to waste flowrate that must be maintained throughout the release to ensure that the limits of Section 2.1.2 are not exceeded at thepoint of discharge into the UNRESTRICTED AREA. The required dilution factor, RDF,is calculated as the sum of the dilution factors required for gamma emitters (RDFy) andfor non-gamma-emitters (RDFny):RDF = YCL+ [(SF)(TF)I (2.3)= RDFY + RDF,,yRDF), = (sFCr) (2.4)(SFXTF)where:SC" Cf C,'C+ + +RDF,,, = ECL, ECL,. ECL ECL,j (2.5)(SF)(TF )C = the measured concentration of radionuclide i as defined in step 1, inJ4Ci/mL.
The Ca, Cs, Cf, and Ct terms will be included in the calculation asappropriate.
ECL = 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- ptCi/mL.
Forgross alpha, the ECL shall be 2x1 0-9 tCi/mL; if specific alpha-emitting radionuclides are measured, the ECL for the specific radionuclide(s) should be used.2-21VER 29 VEGP ODCMSF = the safety factor selected to compensate for statistical fluctuations anderrors of measurement.
The value for the safety factor must be between0 and 1. A value of 0.5 is reasonable for liquid releases; a more precisevalue 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 streamflowrate.
Determine the dilution stream flowrate that can be assured during the release period,designated Fd; this value is the setpoint for the dilution stream flowrate measurement device.If simultaneous radioactive releases are planned from the same or different reactorunits, the dilution stream must be allocated among all the simultaneous releases.
Therewill 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:F:O, = Fd (AFP) (2.6)where:Fdp = the dilution flowrate allocated to release pathway p, in gpm.AFp = the dilution allocation factor for release pathway p. AFn may beassigned any value between 0 and 1 for each active release pathway,under the condition that the sum of the AFp for all active releasepathways 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 arethe LIQUID RADWASTE TREATMENT SYSTEMs of each unit, AFp for each unit maybe assigned the value of 0.5 to permit releases from either unit to be made withoutregard to any releases from the other unit; if only one unit's LIQUID RADWASTETREATMENT SYSTEM is releasing at a given time, its AFp may be increased proportionately.
If more precise allocation factor values are desired, they may bedetermined based on the relative radiological impact of each active release pathway;this may be approximated by multiplying the RDF of each effluent stream by itsrespective planned release flowrate, and comparing these values. If only onesimultaneous release is being made, its AFp may be assigned the value of 1, making Fdpequal to Fd.2-22VER 29 VEGP ODCMFor the case where RDF < 1, the planned release meets the limits of Section 2.1.2without dilution, and could be released with any desired effluent flowrate and dilutionflowrate.
: However, in order to maintain individual doses due to liquid effluent releasesas low as is reasonably achievable, no releases with detectable radioactivity should bemade 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 forthis release pathway, fm.p (in gpm), is calculated as follows:Fd&deg; (2.7)P (RDF- 1)For the case RDF _< 1, equation (2.7) is not valid. However, as discussed above, whenRDF < 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 thepump capacity, the release may be made at full capacity.
Discharge flowrates less than the pump capacity must be achieved by throttling ifthis is available; if throttling is not available, the release may not be madeas planned.NOTE 2: If, at the time of the planned release, there is detectable radioactivity dueto plant operations in the dilution stream, the diluting capacity of thedilution stream is diminished.
(In addition, sampling and analysis of theother radioactive effluents affecting the dilution stream must be sufficient to ensure that the liquid effluent dose limits specified in the controls ofSection 2.1.3 are not exceeded.)
Under these conditions, equation (2.7)must be modified to account for the radioactivity present in the dilutionstream prior to the introduction of the planned release:fp =(RDF- 1) r dF ,ECLJ(2.8) where:Cir the measured concentration of radionuclide i in releasepathway r that is contributing to radioactivity in thedilution stream.fr = the effluent discharge flowrate of release pathway r.If the entire dilution stream contains detectable activity due to plantoperations, whether or not its source is identified, fr = Fd, and Cir is the2-23VER 29 VEGP ODCMconcentration in the total dilution system. This note does not apply: a) ifthe RDF of the planned release is _< 1; or b) if the release contributing radioactivity to the dilution stream has been accounted for by theassignment of an allocation factor.Step 5: Determine the maximum radioactivity monitor setpointconcentration.
Based on the values determined in previous steps, the radioactivity monitor setpoint forthe planned release is calculated to ensure that the limits of Section 2.1.2 will not beexceeded.
Because the radioactivity monitor responds primarily to gamma radiation, the monitor setpoint cp for release pathway p (in [tCi/mL) is based on the concentration of gamma emitters in the waste stream, as follows:cP = AP Cg (2.9)where:Ap an adjustment factor which will allow the setpoint to be established ina practical manner to prevent spurious alarms while allowing amargin between measured concentrations and the limits of Section2.1.2.Step 5.a. If the concentration of gamma emitters in the effluent to be releasedis sufficient that the high alarm setpoint can be established at a levelthat will prevent spurious alarms, Ap should be calculated as follows:1Ap = x ADFRDF(2.10)1- (F,1P + f,,P)RDF Alpwhere:ADF = the assured dilution factor.fap the anticipated actual discharge flowrate for theplanned release (in gpm), a value less than fmp.The release must then be controlled so that theactual effluent discharge flowrate does notexceed fap at any time.Step 5.b. Alternatively, Ap may be calculated as follows:ADF- RDF,,nAP =RDFy (2.11)2-24VER 29 VEGP ODCMStep 5.c. Evaluate the computed value of Ap as follows:If Ap > 1, calculate the monitor setpoint, cp. However, if cp is within about10 percent of Cg, it may be impractical to use this value of cp.This situation indicates that measured concentrations areapproaching values which would cause limits of Section 2.1.2to be exceeded.
Therefore, steps should be taken to reducepotential concentrations at the point of discharge; these stepsmay include decreasing the planned effluent discharge
: flowrate, increasing the dilution stream flowrate, postponing simultaneous
: releases, and/or decreasing the effluentconcentrations by further processing the liquid planned forrelease.
Alternatively, allocation factors for the active liquidrelease pathways may be reassigned.
When one or more ofthese actions has been taken, repeat Steps 1-5 to calculate anew radioactivity monitor setpoint.
If Ap < 1, the release may not be made as planned.
Consider thealternatives 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 SetpointThe setpoint calculated above is in the units jtCi/mL.
The monitor actually measures acount rate, subtracts a predetermined background count rate, and multiplies by acalibration factor to convert from count rate to [tCi/mL.Initial calibration of the monitors by the manufacturer and Georgia Power Companyutilized NIST-traceable liquid solutions with gamma ray emissions over the range 0.08to 1.33 MeV, in the exact geometry of each production monitor.
The calibration factor isa function of the radionuclide mix in the liquid to be released, and will be calculated forthe 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 asthe gain factor in the PERMS monitor, or used to modify the calculated base monitorsetpoint so that the default calibration factor in the PERMS monitor can be leftunchanged.
Notwithstanding the initial calibration, monitor calibration data for conversion betweencount rate and concentration may include operational data obtained from determining the monitor response to stream concentrations measured by liquid sample analysis.
Inall cases, monitor background must be controlled so that the monitor is capable ofresponding to concentrations in the range of the setpoint value.2-25VER 29 VEGP ODCM2.3.3 Setpoints for Monitors on Normally Low-Radioactivity StreamsRadioactivity in these streams (listed in Table 2-4 above) is expected to be at very lowlevels, generally below detection limits. Accordingly, the purpose of these monitors is toalarm 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 preventspurious alarms, and yet alarm should an inadvertent release occur.2.3.3.2 Conditions Requiring an Elevated SetpointUnder the following conditions, radionuclide concentrations must be determined and anelevated radioactivity monitor setpoint determined for these pathways:
For streams that can be diverted or isolated, a new monitor setpoint must beestablished when it is desired to discharge the stream directly to the dilution watereven though the radioactivity in the stream exceeds the level which would normallybe diverted or isolated.
* For streams that cannot be diverted or isolated, a new monitor setpoint must beestablished whenever:
the radioactivity in the stream becomes detectable above thebackground 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, itshould 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 tothe normally low-radioactivity release pathway under consideration, and allocation factors for other release pathways discharging simultaneously must be adjusteddownward (if necessary) to ensure that the sum of the allocation factors does notexceed 1. Sampling and analysis of the normally low-radioactivity streams must besufficient to ensure that the liquid effluent dose limits specified in the controls of Section2.1.3 are not exceeded.
2-26VER 29 VEGP ODCM2.4 LIQUID EFFLUENT DOSE CALCULATIONS The following sub-sections present the methods required for liquid effluent dosecalculations, in deepening levels of detail. Applicable site-specific pathways andparameter values for the calculation of De, A1j, and CFiv are summarized in Table 2-5.2.4.1 Calculation of DoseThe 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 bedetermined and recorded on a per-unit basis, including apportionment of releasesshared between the two units.For the purpose of implementing Section 2.1.3, the dose to the maximum exposedindividual due to radionuclides identified in liquid effluents released from each unit toUNRESTRICTED AREAS will be calculated as follows (equation from Reference 1,page 15):D,=Z rI ('At, CiF,) (2.12)where:D, = the cumulative dose commitment to the total body or to any organ T, inmrem, due to radioactivity in liquid effluents released during the total ofthe m time periods At,.Aj, = the site-related adult ingestion dose commitment factor, for the total bodyor for any organ T, due to identified radionuclide i, in (mrem.mL)/(h.plCi).
Methods for the calculation of A, are presented below in Section 2.4.2.The values of Aj, to be used in dose calculations for releases from theplant site are listed in Table 2-8.At, = the length of time period I, over which C,/ and F, are averaged for liquidreleases, in h.Ci, = the average concentration of radionuclide i in undiluted liquid effluentduring time period I, in [tCi/mL.
Only radionuclides identified anddetected above background in their respective samples should beincluded in the calculation.
F, = the near-field average dilution factor in the receiving water of theUNRESTRICTED AREA:2-27VER 29 VEGP ODCMF, f (2.13)F, xZwhere:ft = the average undiluted liquid waste flowrate actually observed duringthe period of radioactivity
: release, in gpm.Ft = the average dilution stream flowrate actually observed during theperiod of radioactivity
: release, in gpm. If simultaneous releases fromboth units occur, the dilution stream flowrate 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 nearfield 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 cfs(= 448,000 gpm) or less. (Reference 1, Section 4.3.)2.4.2 Calculation of A,The site-related adult ingestion dose commitment factor, Aij, is calculated as follows(equation adapted from Reference 1, page 16, by addition of the irrigated gardenvegetation pathway):
,= 1. 14x 1' U+fBFi e-,'s + U,,CF., DF., (2.14)where:1.14 x 105 = a units conversion factor, determined by:106 pCi/pCi x 103 mL/L + 8760 h/y.U= the adult drinking water consumption rate applicable to the plant site(L/y).Dw= the dilution factor from the near field of the discharge structure forthe plant site to the potable water intake location.
= the decay constant for radionuclide i (h-1). Values of ki used ineffluent calculations should be based on decay data from arecognized and current source, such as Reference 20.tw= the transit time from release to receptor for potable water2-28VER 29 VEGP ODCMconsumption (h).Uf = the adult rate of fish consumption applicable to the plant site (kg/y).BFj = the bioaccumulation factor for radionuclide i applicable to freshwater fish in the receiving water body for the plant site, in (pCi/kg)/(pCi/L)
= (L/kg). For specific values applicable to the plant site, see Table2-6.tf = the transit time from release to receptor for fish consumption (h).U= the adult consumption rate for irrigated garden vegetation applicable to the plant site (kg/y).CFiv = the concentration factor for radionuclide i in irrigated gardenvegetation, as applicable to the vicinity of the plant site, in(pCi/kg)/(pCi/L).
Methods for calculation of CFiv are presented below in Section 2.4.3.DFi, = the dose conversion factor for radionuclide i for adults, in organ T(mrem/pCi).
For specific values, see Table 2-7.2.4.3 Calculation of CfivThe concentration factor for radionuclide i in irrigated garden vegetation, CFiv in (L/kg),is calculated as follows:For radionuclides other than tritium (equation adapted from Reference 3, equations A-8 and A-9):iv=M fJ (2.15)For tritium (equation adapted from Reference 3, equations A-9 and A-10):CFjv = M. L, (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.= the average irrigation rate during the growing season (L)/(m2.h).r = the fraction of irrigation-deposited activity retained on the edible portions2-29VER 29 VEGP ODCMof leafy garden vegetation.
Y, = the areal density (agricultural productivity) of leafy garden vegetation (kg/Mr2)f, = the fraction of the year that garden vegetation is irrigated.
B1v = the crop to soil concentration factor applicable to radionuclide i (pCi/kggarden vegetation)/(pCi/kg soil).P = the effective surface density of soil (kg/m2).ki = the decay constant for radionuclide i (h-1). Values of k, used in effluentcalculations should be based on decay data from a recognized andcurrent source, such as Reference 20.Xw = the rate constant for removal of activity from plant leaves by weathering (h-1).XEi = the effective removal rate for activity deposited on crop leaves (h-1)calculated as: XEi = Xi + Xw.te = the period of leafy garden vegetation exposure during the growingseason (h).tb = the period of long-term buildup of activity in soil (h).th = the time between harvest of garden vegetation and human consumption (h).Lv = the water content of leafy garden vegetation edible parts (Llkg).2-30VER 29 VEGP ODCMTable 2-5.Parameters for Calculation of Doses Due to Liquid Effluent ReleasesDose 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 ValueReference ZUwDwtwUftfUvMIrYvf,Pxwt.tbthL,10, for May through December20, for January through April730 L/y848 h21 kg/y24 h0 kg/y1.0+No value0.252.0 kg/m21.0+240 kg/m20.0021 h-1 (i.e., half-life of 14 d)1440 h (= 60 d)1.31 x 105 h (= 15 y)24 h0.92 L/kgRef. 11Ref 3Ref. 7Ref. 3, Sec. A.2; Ref. 8Ref. 3, Table E-5Ref. 3, Sec. A.2Ref. 12Ref. 3, Table E-15.Ref. 3, Table E-1 5Ref. 3, Table E-15Ref. 3, Table E-15Ref. 3, Table E-15Ref. 3, Table E-15Ref. 3, Table E-15Based on Ref. 21, Table 5.16(for lettuce,
: cabbage, etc.)* -Because there is no irrigated garden vegetation pathway downstream of the plant site, theconsumption of irrigated garden vegetation is set to zero, and the other pathwayparameters are defaults.
+ -There is no established default value for this parameter.
The most conservative physically realistic value is 1.0.2-31VER 29 VEGP ODCMTable 2-6.Element Transfer FactorsFreshwater FishElementBFj*H 9.0 E-01C 4.6 E+03Na 1.0 E+02P 3.0 E+03Cr 2.0 E+02Mn 4.0 E+02Fe 1.0 E+02Co 5.0 E+01Ni 1.0 E+02Cu 5.0 E+01Zn 2.0 E+03Br 4.2 E+02Rb 2.0 E+03Sr 3.0 E+01Y 2.5 E+01Zr 3.3 E+00Nb 5.5 E+02Mo 1.0 E+01Tc 1.5 E+01Ru 1.0 E+01Rh 1.0 E+01Ag 2.3 E+00Sb 2.0 E+02Te 4.0 E+02I 1.5 E+01Cs 2.0 E+03Ba 4.0 E+00La 2.5 E+01Ce 1.0 E+00Pr 2.5 E+01Nd 2.5 E+01W 1.2 E+03Np 1.0 E+01Bioaccumulation Factors for freshwater fish, in (pCi/kg)/(pCi/L).
They are obtained fromReference 3 (Table A-I), except as follows:
Reference 9 for P; Reference 2 (Table A-8)for Ag; and Reference 10 for Nb and Sb.2-32VER 29 VEGP ODCMTable 2-7. Adult Ingestion Dose FactorsNuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLIH-3 No Data 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06Fe-55 2.75E-06 1.90E-06 4.43E-07 No Data No Data 1.06E-06 1.09E-06Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.85E-06 3.40E-05Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88E-06Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.1OE-07 No Data 7.1OE-06Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08Br-84 No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13Br-85 No Data No Data 2.14E-09 No Data No Data No Data No DataRb-86 No Data 2.11E-05 9.83E-06 No Data No Data No Data 4.16E-06Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05All values are in (mrem/pCi ingested).
They are obtained from Reference 3 (Table E-1 1),except as follows:
Reference 2 (Table A-3) for Rh-105, Sb-124, and Sb-125.2-33VER 29 VEGP ODCMTable 2-7 (contd).
Adult Ingestion Dose FactorsNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLISr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04Y-91m 9.09E-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05Y-92 8.45E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05Y-93 2.68E-09 No Data 7.40E-1 1 No Data No Data No Data 8.50E-05Zr-95 3.04E-08 9.75E-09 6.60E-09 No Data 1.53E-08 No Data 3.09E-05Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04Nb-95 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.1OE-05Mo-99 No Data 4.31E-06 8.20E-07 No Data 9.76E-06 No Data 9.99E-06Tc-99m 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.1OE-21Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31 E-06 No Data 1.78E-04Rh-105 1.22E-07 8.86E-08 5.83E-08 No Data 3.76E-07 No Data 1.41 E-05Ag-110m 1.60E-07 1.48E-07 8.79E-08 No Data 2.91 E-07 No Data 6.04E-05Sb-124 2.81E-06 5.30E-08 1.11E-06 6.79E-09 No Data 2.18E-06 7.95E-05Sb-125 2.23E-06 2.40E-08 4.48E-07 1.98E-09 No Data 2.33E-04 1.97E-05Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05Te-127 1.1OE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5.79E-05Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-092-34VER 29 VEGP ODCMTable 2-7 (contd).
Adult Ingestion Dose FactorsNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLITe-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-051-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-061-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-061-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 No Data 1.02E-071-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 No Data 2.22E-061-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-101-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31E-06Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13Ba-139 9.70E-08 6.91E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.OOE-26La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05La-142 1.28E-10 5.82E-11 1.45E-11 No Data No Data No Data 4.25E-07Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05Pr-144 3.01E-11 1.25E-11 1.53E-12 No Data 7.05E-12 No Data 4.33E-18Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05Np-239 1.19E-09 1.17E-10 6.45E-11 No Data 3.65E-10 No Data 2.40E-052-35VER 29 VEGP ODCMTable 2-8. Site-Related Ingestion Dose Factors, A1.Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLIH-3 0.00 1.32E+00 1.32E+00 1.32E+00 1.32E+00 1.32E+00 1.32E+00C-14 3.13E+04 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03Na-24 1.36E+02 1.36E+02 1.36E+02 1.36E+02 1.36E+02 1.36E+02 1.36E+02P-32 1.32E+06 8.22E+04 5.11E+04 0.00 0.00 0.00 1.49E+05Cr-51 0.00 0.00 1.27E+00 7.58E-01 2.79E-01 1.68E+00 3.19E+02Mn-54 0.00 4.41E+03 8.42E+02 0.00 1.31E+03 0.00 1.35E+04Mn-56 0.00 1.74E-01 3.08E-02 0.00 2.21E-01 0.00 5.55E+00Fe-55 6.86E+02 4.74E+02 1.11E+02 0.00 0.00 2.65E+02 2.72E+02Fe-59 1.07E+03 2.51E+03 9.61E+02 0.00 0.00 7.01E+02 8.36E+03Co-58 0.00 9.59E+01 2.15E+02 0.00 0.00 0.00 1.94E+03Co-60 0.00 2.78E+02 6.14E+02 0.00 0.00 0.00 5.23E+03Ni-63 3.25E+04 2.25E+03 1.09E+03 0.00 0.00 0.00 4.70E+02Ni-65 1.72E-01 2.23E-02 1.02E-02 0.00 0.00 0.00 5.66E-01Cu-64 0.00 2.75E+00 1.29E+00 0.00 6.94E+00 0.00 2.35E+02Zn-65 2.32E+04, 7.37E+04 3.33E+04 0.00 4.93E+04 0.00 4.64E+04Zn-69 7.88E-07 1.51E-06 1.05E-07 0.00 9.79E-07 0.00 2.26E-07Br-83 0.00 0.00 3.83E-02 0.00 0.00 0.00 5.52E-02Br-84 0.00 0.00 1.22E-12 0.00 0.00 0.00 9.61E-18Br-85 0.00 0.00 0.00 0.00 0.00 0.00 0.00Rb-86 0.00 9.75E+04 4.54E+04 0.00 0.00 0.00 1.92E+04Rb-88 0.00 1.29E-22 6.82E-23 0.00 0.00 0.00 1.78E-33Rb-89 0.00 1.61E-26 1.14E-26 0.00 0.00 0.00 0.00Sr-89 2.49E+04 0.00 7.16E+02 0.00 0.00 0.00 4.OOE+03Sr-90 6.23E+05 0.00 1.53E+05 0.00 0.00 0.00 1.80E+04Sr-91 7.25E+01 0.00 2.93E+00 0.00 0.00 0.00 3.45E+02Sr-92 3.33E-01 0.00 1.44E-02 0.00 0.00 0.00 6.60E+00Y-90 5.04E-01 0.00 1.35E-02 0.00 0.00 0.00 5.34E+03Y-91m 1.04E-11 0.00 4.01E-13 0.00 0.00 0.00 3.04E-11Y-91 9.77E+00 0.00 2.61E-01 0.00 0.00 0.00 5.38E+03Y-92 4.61E-04 0.00 1.35E-05 0.00 0.00 0.00 8.07E+00Y-93 3.19E-02 0.00 8.82E-04 0.00 0.00 0.00 1.01E+03Zr-95 5.47E-01 1.75E-01 1.19E-01 0.00 2.75E-01 0.00 5.56E+02Zr-97 7.40E-03, 1.49E-03 6.83E-04 0.00 2.26E-03 0.00 4.62E+02Nb-95 8.09E+00 4.50E+00 2.42E+00 0.00 4.45E+00 0.00 2.73E+04Mo-99 0.00 1.07E+02 2.04E+01 0.00 2.43E+02 0.00 2.49E+02Tc-99m 5.70E-04 1.61E-03 2.05E-02 0.00 2.44E-02 7.89E-04 9.53E-01All values are in (mrem.mL)/(h.[tCi).
They are calculated using equation (2.14), and data fromTable 2-5, Table 2-6, and Table 2-7. When "No Data" is shown for a radionuclide-organ combination in Table 2-7, A1, factors in this table are presented as zero.2-36VER 29 VEGP ODCMTable 2-8 (contd).
Site-Related Ingestion Dose Factors, Aj,Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLITc-101 2.71E-33 3.91E-33 3.83E-32 0.00 7.03E-32 2.00E-33 0.00Ru-103 6.21E+00 0.00 2.68E+00 0.00 2.37E+01 0.00 7.25E+02Ru-105 8.79E-03 0.00 3.47E-03 0.00 1.14E-01 0.00 5.38E+00Ru-106 9.42E+01 0.00 1.19E+01 0.00 1.82E+02 0.00 6.1OE+03Rh-105 2.32E+00 1.69E+00 1.11E+00 0.00 7.15E+00 0.00 2.68E+02Ag-110m 2.53E+00 2.34E+00 1.39E+00 0.00 4.61E+00 0.00 9.56E+02Sb-124 1.36E+03 2.56E+01 5.37E+02 3.28E+00 0.00 1.05E+03 3.84E+04Sb-125 1.09E+03 1.17E+01 2.19E+02 9.68E-01 0.00 1.14E+05 9.63E+03Te-125m 2.56E+03 9.29E+02 3.43E+02 7.71E+02 1.04E+04 0.00 1.02E+04Te-127m 6.51E+03 2.33E+03 7.93E+02 1.66E+03 2.64E+04 0.00 2.18E+04Te-127 1.78E+01 6.40E+00 3.85E+00 1.32E+01 7.25E+01 0.00 1.41E+03Te-129m 1.09E+04 4.07E+03 1.73E+03 3.74E+03 4.55E+04 0.00 5.49E+04Te-129 1.78E-05 6.68E-06 4.33E-06 1.36E-05 7.47E-05 0.00 1.34E-05Te-131m 9.57E+02 4.68E+02 3.90E+02 7.42E+02 4.74E+03 0.00 4.65E+04Te-131 8.64E-17 3.61E-17 2.73E-17 7.10E-17 3.78E-16 0.00 1.22E-17Te-132 1.97E+03 1.27E+03 1.19E+03 1.41E+03 1.23E+04 0.00 6.02E+041-130 7.60E+00 2.24E+01 8.85E+00 1.90E+03 3.50E+01 0.00 1.93E+011-131 1.73E+02 2.48E+02 1.42E+02 8.13E+04 4.25E+02 0.00 6.55E+011-132 5.27E-03 1.41E-02 4.93E-03 4.93E-01 2.24E-02 0.00 2.65E-031-133 2.59E+01 4.51E+01 1.37E+01 6.62E+03 7.86E+01 0.00 4.05E+011-134 2.18E-08 5.94E-08 2.12E-08 1.03E-06 9.44E-08 0.00 5.17E-111-135 1.31E+00 3.44E+00 1.27E+00 2.27E+02 5.52E+00 0.00 3.89E+00Cs-134 2.98E+05 7.1OE+05 5.80E+05 0.00 2.30E+05 7.62E+04 1.24E+04Cs-136 2.96E+04 1.17E+05 8.42E+04 0.00 6.51E+04 8.92E+03 1.33E+04Cs-137 3.82E+05 5.23E+05 3.43E+05 0.00 1.78E+05 5.90E+04 1.01E+04Cs-138 9.12E-12 1.80E-11 8.92E-12 0.00 1.32E-11 1.31E-12 7.68E-17Ba-139 5.64E-06 4.02E-09 1.65E-07 0.00 3.76E-09 2.28E-09 1.00E-05Ba-140 3.74E+02 4.69E-01 2.45E+01 0.00 1.60E-01 2.69E-01 7.69E+02Ba-141 8.47E-25 6.40E-28 2.86E-26 0.00 5.95E-28 3.63E-28 3.99E-34Ba-142 0.00 0.00 0.00 0.00 0.00 0.00 0.00La-140 1.10E-01 5.56E-02 1.47E-02 0.00 0.00 0.00 4.08E+03La-142 2.19E-07 9.96E-08 2.48E-08 0.00 0.00 0.00 7.27E-04Ce-141 1.15E-01 7.79E-02 8.84E-03 0.00 3.62E-02 0.00 2.98E+02Ce-143 8.65E-03 6.39E+00 7.08E-04 0.00 2.81E-03 0.00 2.39E+02Ce-144 6.22E+00 2.60E+00 3.34E-01 0.00 1.54E+00 0.00 2.1OE+03Pr-143 6.10E-01 2.44E-01 3.02E-02 0.00 1.41E-01 0.00 2.67E+03Pr-144 1.48E-28 6.14E-29 7.51E-30 0.00 3.46E-29 0.00 2.13E-35Nd-147 4.11E-01 4.75E-01 2.84E-02 0.00 2.78E-01 0.00 2.28E+03W-187 1.47E+02 1.23E+02 4.31E+01 0.00 0.00 0.00 4.04E+04Np-239 2.81E-02 2.76E-03 1.52E-03 0.00 8.62E-03 0.00 5.67E+022-37VER 29 VEGP ODCM2.5 LIQUID EFFLUENT DOSE PROJECTIONS 2.5.1 Thirty-One Day Dose Projections In order to meet the requirements for operation of the LIQUID RADWASTETREATMENT SYSTEM (see Section 2.1.4), dose projections must be made at leastonce each 31 days; this applies during periods in which a discharge toUNRESTRICTED AREAS of liquid effluents containing radioactive materials occurs or isexpected.
Projected 31-day doses to individuals due to liquid effluents may be determined asfollows:Dpj x31+ D,, (2.17)where:D~p = the projected dose to the total body or organ r, for the next 31 days ofliquid releases.
Dec = the cumulative dose to the total body or organ c, for liquid releases thathave occurred in the elapsed portion of the current quarter, plus therelease 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 ifthe release continues into the next quarter).
Dia = the anticipated dose contribution to the total body or any organ ',, due toany 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, Dta may be set to zero.2.5.2 Dose Projections for Specific ReleasesDose projections may be performed for a particular release by performing a prerelease dose calculation assuming that the planned release will proceed as anticipated.
Forindividual 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 valuesexpected to exist during the release period.2-38VER 29 VEGP ODCM2.6 DEFINITIONS OF LIQUID EFFLUENT TERMSThe following symbolic terms are used in the presentation of liquid effluent calculations in the subsections above.Section ofTerm Definition Initial UseAp= the adjustment factor used in calculating the effluentmonitor setpoint for liquid release pathway p: the ratio ofthe assured dilution to the required dilution
[unitless].
2.3.2.2ADF = the assured dilution factor for a planned release [unitless].
2.3.2.2AFp = the dilution allocation factor for liquid release pathway p 2.3.2.2[unitless].
A, = the site-related adult ingestion dose commitment factor, forthe total body or for any organ T, due to identified radionuclide i [(mrem
* mL)/(h * &#xfd;tCi)]. The values of Ai, arelisted in Table 2-8. 2.4.1Biv = the crop to soil concentration factor applicable toradionuclide i, [(pCi/kg garden vegetation)/(pCi/kg soil)]. 2.4.3BFi = the bioaccumulation factor for radionuclide i for freshwater fish [(pCilkg)/(pCi/L)].
Values are listed in Table 2-6. 2.4.2c = the setpoint of the radioactivity monitor measuring theconcentration of radioactivity in the effluent line, prior to dilutionand subsequent release [ptCi/mL].
2.3.2.1Cp= the calculated effluent radioactivity monitor setpoint for liquidrelease pathway p [gCi/mL].
2.3.2.2Ca -the gross concentration of alpha emitters in the liquid waste asmeasured in the applicable composite sample [giCi/mL].
2.3.2.2CECL -the Effluent Concentration Limit stated in 10 CFR 20, AppendixB, Table 2, Column 2 [giCi/mL].
2.3.2.1Cf= the concentration of Fe-55 in the liquid waste asmeasured in the applicable composite sample [gCi/mL].
2.3.2.22-39VER 29 VEGP ODCMSection ofTerm Definition Initial UseCg= the concentration of gamma emitter g in the liquid wasteas measured by gamma ray spectroscopy performed onthe applicable prerelease waste sample [pfCi/mL].
2.3.2.2C = the measured concentration of radionuclide i in a sampleof liquid effluent
[VtCi/mL].
2.3.2.2CQ = the average concentration of radionuclide i in undiluted liquid effluent during time period / [jiCi/mL].
2.4.1Cir = the measured concentration of radionuclide i in releasepathway r that is contributing to radioactivity in the dilution 2.3.2.2stream [(,Ci/mL].
Cs = the concentration of strontium radioisotope s (Sr-89 orSr-90) in the liquid waste as measured in the applicable composite sample [jiCi/mL].
2.3.2.2Ct = the concentration of H-3 in the liquid waste as measuredin the applicable composite sample [[tCi/mL].
2.3.2.2CFi, = the concentration factor for radionuclide i in irrigated garden vegetation
[(pCi/kg)/(pCi/L)].
2.4.2Dw= the dilution factor from the near field of the discharge structure to the potable water intake location
[unitless].
2.4.2D = the cumulative dose commitment to the total body or toany organ c, due to radioactivity in liquid effluents releasedduring a given time period [mrem]. 2.4.1DOa = the anticipated dose contribution to the total body or anyorgan T, due to any planned activities during the next31-day period [mrem]. 2.5.1Dec = the cumulative dose to the total body or organ r, for liquidreleases that have occurred in the elapsed portion of thecurrent quarter, plus the release under consideration 2.5.1[mrem].2-40VER 29 VEGP ODCMTerm Definition D= the projected dose to the total body or organ c, for the next31 days of liquid releases
[mrem].DFi = the dose conversion factor for radionuclide i for adults, inorgan t [mrem/pCi].
Values are listed in Table 2-7.ECL = the liquid Effluent Concentration Limit for radionuclide ifrom 10 CFR Part 20, Appendix B, Table 2, Column 2[gC i/m L.f = the effluent flowrate at the location of the radioactivity monitor [gpm].fap = the anticipated actual discharge flowrate for a plannedrelease from liquid release pathway p [gpm].f= the fraction of the year that garden vegetation is irrigated
[unitless].
fmp = the maximum permissible effluent discharge flowrate forrelease pathway p [gpm].fr = the effluent discharge flowrate of release pathway r [gpm].ft = the average undiluted liquid waste flowrate actuallyobserved during the period of a liquid release [gpm].F = the dilution stream flowrate which can be assured prior tothe release point to the UNRESTRICTED AREA [gpm].Fd = the entire assured dilution flowrate for the plant site duringthe release period [gpm].Fdp = the dilution flowrate allocated to release pathway p [gpm].F, = the near-field average dilution factor in the receiving waterof the UNRESTRICTED AREA [unitless].
Ft = the average dilution stream flowrate actually observedduring the period of a liquid release [gpm].I = the average irrigation rate during the growing season[L/(m2.h)].Section ofInitial Use2.5.12.4.22.3.2.22.3.2.12.3.2.22.4.32.3.2.22.3.2.22.4.12.3.2.12.3.2.22.3.2.22.4.12.4.12.4.32-41VER 29 VEGP ODCMSection ofTerm Definition Initial UseLv = the water content of leafy garden vegetation edible parts 2.4.3[L/kg].M = the additional river dilution factor from the near field of thedischarge structure for the plant site to the point ofirrigation water usage [unitless].
2.4.3P = the effective surface density of soil [kg/M2]. 2.4.3r = the fraction of irrigation-deposited activity retained on theedible portions of leafy garden vegetation.
2.4.3RDF = the required dilution factor: the minimum ratio by whichliquid effluent must be diluted before reaching theUNRESTRICTED AREA, in order to ensure that the limitsof Section 2.1.2 are not exceeded
[unitless].
2.3.2.2RDFy = the RDF for a liquid release due only to its concentration ofgamma-emitting radionuclides
[unitless].
2.3.2.2RDFr = the RDF for a liquid release due only to its concentration ofnon-gamma-emitting radionuclides
[unitless].
2.3.2.2SF = the safety factor selected to compensate for statistical fluctuations and errors of measurement
[unitless].
2.3.2.2t = the number of whole or partial days elapsed into thecurrent quarter, including the time to the end of the releaseunder consideration.
2.5.1tb = the period of long-term buildup of activity in soil [h]. 2.4.3te = the period of leafy garden vegetation exposure during thegrowing season [h]. 2.4.3tf = the transit time from release to receptor for fish 2.4.2consumption
[h].th = the time between harvest of garden vegetation and humanconsumption
[h]. 2.4.3tw= the transit time from release to receptor for potable waterconsumption
[h]. 2.4.22-42VER 29 VEGP ODCMSection ofTerm Definition Initial UseTF = the tolerance factor selected to allow flexibility in theestablishment of a practical monitor setpoint which couldaccommodate effluent releases at concentrations higherthan the ECL values stated in 10 CFR 20, Appendix B,Table 2, Column 2 [unitless];
the tolerance factor must not 2.3.2.1exceed a value of 10.Uf = the adult rate of fish consumption
[kg/y]. 2.4.2Uv= the adult consumption rate for irrigated gardenvegetation
[kg/y]. 2.4.2Uw= the adult drinking water consumption rate applicable to theplant site [L/y]. 2.4.2YV = the areal density (agricultural productivity) of leafy gardenvegetation
[kg/M2]. 2.4.3Z = the applicable dilution factor for the receiving water body,in the near field of the discharge structure, during theperiod of radioactivity release [unitless].
2.4.1At1 = the length of time period 1, over which Ci and F, areaveraged for liquid releases
[h]. 2.4.1,Ei = the effective removal rate for activity deposited on cropleaves [h-1]. 2.4.3= the decay constant for radionuclide i [h-1]. 2.4.2k= the rate constant for removal of activity from plant leavesby weathering
[h-1]. 2.4.32-43VER 29 VEGP ODCMCHAPTER 3GASEOUS 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 ControlIn accordance with Technical Specification 5.5.4.a, the radioactive gaseous effluentmonitoring instrumentation channels shown in Table 3-1 shall be OPERABLE with theiralarm/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 withSection 3.3.3.1.1.1 Applicability These limits apply as shown in Table 3-1.3.1.1.2 ActionsWith a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend therelease of radioactive gaseous effluents monitored by the affected
: channel, declare thechannel inoperable, or restore the setpoint to a value that will ensure that the limits ofSection 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. Restorethe 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 bedemonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCECHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 3-2.3-1VER 29 VEGP ODCM3.1.1.4 BasisThe radioactive gaseous effluent instrumentation is provided to monitor and control, asapplicable, the releases of radioactive materials in gaseous effluents during actual orpotential releases of gaseous effluents.
The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters inSection 3.3 to ensure that the alarm/trip will occur prior to exceeding the limits ofSection 3.1.2.a.
The OPERABILITY and use of this instrumentation is consistent withthe requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFRPart 50.3-2VER 29 VEGP ODCMTable 3-1. Radioactive Gaseous Effluent Monitoring Instrumentation OPERABILITY Requirements MinimumInstrument ChannelsOPERABLE Applicability ACTION1. GASEOUS RADWASTE TREATMENT SYSTEM (Common)a. Noble Gas Activity
: Monitor, withAlarm and Automatic Termination ofRelease (ARE-0014) 1 During releases' 45b. Effluent System Flowrate Measuring Device (AFT-0014) 1 During releasesa 462. Turbine Building Vent (Each Unit)a. Noble Gas Activity Monitor(RE-1 2839C) 1 During releasesa 4ab. Iodine and Particulate Samplers(RE-12839A
& B) 1 During releases' 51c. Flowrate Monitor (FT-1 2839 orFIS-12862)b 1 During releasesa 46d. Sampler Flowrate Monitor(1FI-13211, 2FIT-13211) 1 During releasesa 463. Plant Vent (Each Unit)a. Noble Gas Activity Monitor(RE-1 2442C or RE-1 2444C) 1 At all times 47,48b. Iodine Sampler/Monitor (RE-12442B or RE-12444B) 1 At all times 51c. Particulate Sampler/Monitor (RE-1 2442A or RE-12444A) 1 At all times 51d. Flowrate Monitor (FT-12442 or12835) 1 At all times 46e. Sampler Flowrate Monitor (FI-12442 or FI-12444) 1 At all times 464. Radwaste Processing Facility Vent (Common)a. Particulate Monitor(ARE-1 6980) 1 1 During releasesa 51a. "During releases" means "During radioactive releases via this pathway."
: b. During emergency filtration.
3-3VER 29 VEGP ODCMTable 3-1 (contd).
Notation for Table 3-1 -ACTION Statements ACTION 45 -With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, the contents of the tank(s) may bereleased to the environment for up to 14 days provided that prior to initiating therelease:a. The local radiation monitor reading (if functional) is recorded at leastonce per 12 hours or at least two independent samples of the tank'scontents are analyzed, andb. At least two technically qualified members of the Facility Staffindependently verify the discharge line valving, and verify the releaserate calculations.
Otherwise, suspend release of radioactive effluents via this pathway.ACTION 46 -With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases via this pathwaymay continue provided the flowrate is estimated at least once per 4 hours.ACTION 47 -With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, effluent releases via this pathwaymay continue provided the local radiation monitor reading (if functional) isrecorded at least once per 12 hours or grab samples are taken at least once per12 hours and these samples are analyzed for radioactivity within 24 hours. Withthe plant vent radiation monitor iodine and particulate channels inoperable duringthe loss of sample line heat tracing, the noble gas channel of RE-1 2442 and RE-12444 would still be considered valid.ACTION 48 -With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, record the local radiation monitorreading (if functional) for RE-2565C at least once per 12 hours or 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 theMinimum Channels OPERABLE requirement, effluent releases via the affectedpathway may continue provided one of the following options is available (1) the3-4VER 29 VEGP ODCMlocal radiation monitor reading (if functional) is recorded at least once per 12hours (2) samples are continuously collected with the installed skid or (3)samples are continuously collected with auxiliary sampling equipment.
RE-12444A and B may be verified functional by recording local radiation monitor skidflow once per 12 hours. With the plant vent radiation monitor particulate andiodine channels inoperable during the loss of sample line heat tracing, estimateradioactive releases for up to 48 hours while continuing to monitor noble gasactivity from RE-1 2442 and RE-1 2444.3-5VER 29 VEGP ODCMTable 3-2. Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Surveillance Requirements CHANNELInstrument CHANNEL OPERA-CHANNEL SOURCE CALIBRA-TIONALCHECK CHECK TION TEST MODESc1. GASEOUS RADWASTE TREATMENT SYSTEM (Common)a. Noble Gas Activity Monitor,with Alarm and Automatic Termination of Release During(ARE-0014)
P P Rb Ra(') Releaseb. Effluent System FlowrateMeasuring Device During(AFT-0014)
P NA R NA Release2. Turbine Building Vent (Each Unit)a. Noble Gas Activity Monitor During(RE-12839C)
D M Rb Ra(2) Releaseb. Iodine and Particulate DuringSamplers (RE-12839A&B)
Wd NA NA NA Releasec. Flowrate Monitor During(FT-12839 or FIS-12862)
D NA R NA Released. Sampler Flowrate Monitor During(1FI-13211, 2FIT-13211)
D NA R Q Release3. Plant Vent (Each Unit)a. Noble Gas Activity Monitor(RE-1 2442C orRE-12444C)
D M Rb Ra(2) Allb. Particulate and IodineMonitors (RE-12442A&B)
Wd NA R Ra(2) Allc. Particulate and IodineSamplers (RE-12444A&B)
'Nd NA NA NA Alld. Flowrate Monitor(FT-12442 or 12835) D NA R NA Alle. Sampler Flowrate Monitor(FI-12442 or Fl-12444)
D NA R Q All4. Radwaste Processing Facility Vent (Common)a. Particulate Monitor Wd Q Re N/A During(ARE-16980)
Release3-6VER 29 VEGP ODCMTable 3-2 (contd).
Notation for Table 3-2a. In addition to the basic functions of a CHANNEL OPERATIONAL TEST (Section10.2):(1) The CHANNEL OPERATIONAL TEST shall also demonstrate thatautomatic isolation of this pathway and control room annunciation occurs(for item a. below only); and control room CRT indication occurs (if any ofthe 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 thatcontrol room annunciation occurs (for item a. below only); and thatcontrol 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 thereference standards certified by the National Institute of Standards andTechnology, or using standards that have been obtained from suppliers thatparticipate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy andmeasurement range. For any subsequent CHANNEL CALIBRATION, sourcesthat have been related to the initial calibration shall be used.c. MODES in which surveillance is required.
"All" means "At all times." "Duringrelease" means "During radioactive release via this pathway."
3-7VER 29 VEGP ODCMd. The channel check shall consist of visually verifying that the collection device(i.e., particulate filter or charcoal cartridge, etc.) is in place for sampling.
: e. The CHANNEL CALIBRATION verifies proper operation of the CHANNELOPERATIONAL TEST requirements described in Notation a(2) above.3-8VER 29 VEGP ODCM3.1.2 Gaseous Effluent Dose Rate ControlIn accordance with Technical Specifications 5.5.4.c and 5.5.4.g, the licensee shallconduct operations so that the dose rates due to radioactive materials released ingaseous effluents from the site to areas at and beyond the SITE BOUNDARY arelimited as follows:a. For noble gases: Less than or equal to a dose rate of 500 mrem/y to the totalbody and less than or equal to a dose rate of 3000 mrem/y to the skin, andb. For Iodine-1 31, Iodine-1 33, tritium, and for all radionuclides in particulate formwith half-lives greater than 8 days: Less than or equal to a dose rate of 1500mrem/y to any organ.3.1.2.1 Applicability This limit applies at all times.3.1.2.2 ActionsWith 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 thestated 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 BOUNDARYdue to releases of gaseous effluents shall be determined to be within the above limits, inaccordance with the methods and procedures in Section 3.4.1, by obtaining representative samples and performing analyses in accordance with the sampling andanalysis program specified in Table 3-3.3.1.2.4 BasisThis 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 THEPUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, exceeding the limits specified in Appendix I of 10 CFR Part 50, while allowingoperational flexibility for effluent releases.
For MEMBERS OF THE PUBLIC who may attimes be within the SITE BOUNDARY, the occupancy of the MEMBER OF THEPUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.
3-9VER 29 VEGP ODCMThe dose rate limit for Iodine-1 31, Iodine-1 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days specifically applies to dose rates to a child viathe inhalation pathway.This control applies to the release of gaseous effluents from all reactors at the site.3-10VER 29 VEGP ODCMTable 3-3. Radioactive Gaseous Waste Sampling and Analysis ProgramSampling and Analysis Requirementsa MINIMUMDETECTABLE Minimum CONCENTRA-Gaseous Sampling Analysis Type of Activity TION (MDC)Release Type FREQUENCY FREQUENCY Analysis (jtCi/mL)
Waste Gas P P Noble Gas 1 E-4Decay Tank Each Tank Grab Each Tank PRINCIPAL (Common)
Sample GAMMA EMITTERSpi Noble Gas 1 E-4Containment pC Each Furge PRINCIPAL Purge 14, Each Purge GAMMA EMITTERS24" or14(Each Unit) Grab SampleM H-3 (Oxide) 1 E-6Noble Gas 1 E-4Plant Vent Mc'd'f MC PRINCIPAL (Each Unit) Grab Sample GAMMA EMITTERSH-3 (Oxide) 1 E-6Condenser Air Noble Gas 1 E-4PRINCIPAL Ejector & MGAMMA EMITTERSSteam Packing Mple MExhaust Grab Sample(Each Unit)b H-3 (Oxide) 1 E-6we Charcoal 1-131 1 E-12CONTINUOUS 8  or SilverZeoliteSampleWe Particulate 1 E-11CONTINUOUS Particulate PRINCIPAL Sample GAMMA EMITTERSPlant Vent, M Gross Alpha 1 E-1 1Condenser Air COMPOSITE Ejector & Particulate Steam Packing CONTINUOUS 8  arileExhaust (Each SampleUnit)bQ Sr-89, Sr-90 1 E-1 1CONTINUOUS 8  COMPOSITE Particulate SampleRadwaste Wh Particulate 1 E-11Processing Particulate PRINCIPAL Facility Vent CONTINUOUS 8  Sample GAMMA EMITTERS(Common)3-11VER 29 VEGP ODCMTable 3-3 (contd).
Notation for Table 3-3a. 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 andsteam 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 aTHERMAL POWER change exceeding 15% of the RATED THERMAL POWERwithin a one-hour period. This requirement does not apply if (1) analysis showsthat the DOSE EQUIVALENT 1-131 concentration in the primary coolant has notincreased more than a factor of 3; and (2) the noble gas monitor shows thateffluent activity has not increased more than a factor of 3.d. Tritium grab samples shall be taken at least once per 24 hours when therefueling cavity is flooded.e. Samples shall be changed at least once per 7 days and analyses shall becompleted within 48 hours after changing (or after removal from sampler).
Sampling shall also be performed at least once per 24 hours for at least 7 daysfollowing each shutdown,
: startup, or THERMAL POWER change exceeding 15%of RATED THERMAL POWER in one hour, and analyses shall be completed within 48 hours of changing.
When samples collected for 24 hours 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 1-131concentration 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 morethan a factor of 3.f. Tritium grab samples shall be taken at least once per 7 days from the Unit 1 plantvent, 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 knownfor the time period covered by each dose or dose rate calculation made inaccordance 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 becompleted within 48 hours after changing (or removal of sampler).
3-12VER 29 VEGP ODCM3-13VER 29 VEGP ODCM3.1.3 Gaseous Effluent Air Dose ControlIn accordance with Technical Specifications 5.5.4.e and 5.5.4.h, the air dose due tonoble gases released in gaseous effluents, from each reactor unit, to areas at andbeyond 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, andb. 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 ActionsWith 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 limit(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 thelimits 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 gaseouseffluents from each unit to areas at and beyond the SITE BOUNDARY, for the currentcalendar quarter and current calendar year, shall be determined in accordance withSection 3.4.2 at least once per 31 days.3.1.3.4 BasisThis control is provided to implement the requirements of Sections 1I.B, III.A and IV.A ofAppendix I, 10 CFR Part 50. Section 3.1.3 implements the guides set forth in Sectionll.B of Appendix I. The ACTION statements in Section 3.1.3.2 provide the requiredoperating flexibility and at the same time implement the guides set forth in Section IV.Aof Appendix I, assuring that the releases of radioactive material in gaseous effluents toUNRESTRICTED AREAS will be kept "as low as is reasonably achievable."
TheSurveillance requirements in Section 3.1.3.3 implement the requirements in Section III.Aof Appendix I, which require that conformance with the guides of Appendix I be shown3-14VER 29 VEGP ODCMby calculational procedures based on models and data such that the actual exposure ofa MEMBER OF THE PUBLIC through appropriate pathways is unlikely to besubstantially underestimated.
The dose calculations established in Section 3.4.2 forcalculating the doses due to the actual releases of noble gases in gaseous effluents areconsistent with the methodology provided in Regulatory Guide 1.109 (Reference 3), andRegulatory Guide 1.111 (Reference 5). The equations in Section 3.4.2 provided fordetermining the air doses at the SITE BOUNDARY are based upon the historical annualaverage atmospheric conditions.
3.1.4 Control on Gaseous Effluent Dose to a Member of the PublicIn accordance with Technical Specifications 5.5.4.e and 5.5.4.i, the dose to a MEMBEROF THE PUBLIC from 1-131, 1-133, tritium, and all radionuclides in particulate form withhalf-lives greater than 8 days in gaseous effluents
: released, from each reactor unit, toareas 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, andb. 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 ActionsWith the calculated dose from the release of 1-131, 1-133, tritium, or radionuclides inparticulate form with half-lives greater than 8 days, in gaseous effluents exceeding anyof the above limits, prepare and submit to the Nuclear Regulatory Commission within 30days a special report which identifies the cause(s) for exceeding the limit; defines thecorrective actions that have been taken to reduce the releases of radioiodines andradionuclides 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 incompliance 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 daysreleased in gaseous effluents from each unit to areas at and beyond the SITEBOUNDARY, for the current calendar quarter and current calendar year, shall bedetermined in accordance with Section 3.4.3 at least once per 31 days.3.1.4.4 Basis3-15VER 29 VEGP ODCMThis control is provided to implement the requirements of Section II.C, III.A and IV.A ofAppendix 1, 10 CFR Part 50. The limits stated in Section 3.1.4 are the guides set forthin Section II.C of Appendix I. The ACTION statements in Section 3.1.4.2 provide therequired operating flexibility and at the same time implement the guides set forth inSection IV.A of Appendix I to assure that the releases of radioactive materials ingaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."
The calculational methods specified in the Surveillance Requirements ofSection 3.1.4.3 implement the requirements in Section III.A of Appendix I thatconformance with the guides of Appendix I be shown by calculational procedures basedon models and data, such that the actual exposure of a MEMBER OF THE PUBLICthrough appropriate pathways is unlikely to be substantially underestimated.
Thecalculational methods in Section 3.4.3 for calculating the doses due to the actualreleases of the subject materials are consistent with the methodology provided inRegulatory Guide 1.109 (Reference 3), and Regulatory Guide 1.111 (Reference 5).These equations provide for determining the actual doses based upon the historical annual average atmospheric conditions.
The release specifications for radioiodines, radioactive materials in particulate form and radionuclides other than noble gases aredependent on the existing radionuclide pathways to man, in the areas at and beyondthe SITE BOUNDARY.
The pathways which were examined in the development ofthese calculations were: 1) individual inhalation of airborne radionuclides,
: 2) deposition of radionuclides onto green leafy garden vegetation with subsequent consumption byman, 3) deposition onto grassy areas where milk animals and meat producing animalsgraze with consumption of the milk and meat by man, and 4) deposition on the groundwith subsequent exposure of man.3.1.5 Gaseous Radwaste Treatment System ControlIn accordance with Technical Specification 5.5.4.f, the GASEOUS WASTEPROCESSING SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEMshall be OPERABLE.
The appropriate portions of the GASEOUS WASTEPROCESSING SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEMshall 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 eachreactor unit, to areas at and beyond the SITE BOUNDARY would exceed 0.2 mrad toair from gamma radiation, 0.4 mrad to air from beta radiation, or 0.3 mrem to any organof a MEMBER OF THE PUBLIC.3.1.5.1 Applicability These limits apply at all times.3.1.5.2 Actions3-16VER 29 VEGP ODCMWith gaseous waste being discharged without treatment and in excess of the limits inSection 3.1.5, prepare and submit to the Nuclear Regulatory Commission within 30days a special report which includes the following information:
: a. Identification of any inoperable equipment or subsystem and the reason forinoperability,
: b. Action(s) taken to restore the inoperable equipment to OPERABLE status, andc. 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 SITEBOUNDARY shall be projected at least once per 31 days, in accordance with Section3.5.1, 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 EXHAUSTTREATMENT SYSTEM shall be demonstrated OPERABLE:
by meeting the controls of Sections 3.1.2, and either 3.1.3 (for the GASEOUSWASTE PROCESSING SYSTEM) or 3.1.4 (for the VENTILATION EXHAUSTTREATMENT SYSTEM).3.1.5.4 BasisThe OPERABILITY of the GASEOUS WASTE PROCESSING SYSTEM ensures that thesystem will be available for use whenever gaseous effluents require treatment prior torelease to the environment.
The requirement that the appropriate portions of thissystem be used, when specified, provides reasonable assurance that the releases ofradioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."
This control implements the requirements of 10 CFR Part 50.36a, GeneralDesign Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given inSection IL.D of Appendix I to 10 CFR Part 50. The specified limits governing the use ofappropriate portions of the system were specified as a suitable fraction of the dosedesign objectives set forth in Section II.B and II.C of Appendix 1, 10 CFR Part 50, forgaseous effluents.
This control applies to the release of radioactive materials in gaseous effluents fromeach unit at the site. For units with shared radwaste treatment
: systems, the gaseouseffluents from the shared system are proportioned among the units sharing that system.3-17VER 29 VEGP ODCM3.1.6 Major Changes to Gaseous Radioactive Waste Treatment SystemsLicensee initiated MAJOR CHANGES TO GASEOUS RADIOACTIVE WASTETREATMENT 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 Section7.2.2.7.b. Shall become effective upon review and approval by the Vice President
-Plant.3-18VER 29 VEGP ODCM3.2 GASEOUS WASTE PROCESSING SYSTEMAt Plant Vogtle, there are five potential points where radioactivity may be released tothe atmosphere in gaseous discharges.
These five potential release pathways are theUnit 1 and Unit 2 Plant Vents; the Unit 1 and Unit 2 Turbine Building Vents; and theRadwaste Processing Facility Vent. However, the Turbine Building Vents are notnormal release pathways unless a primary-to-secondary leak exists. The RadwasteProcessing Facility Vent is not a normal release pathway unless a spill occurs. Thefigures on the following pages give schematic diagrams of the Gaseous WasteTreatment System and the Ventilation Exhaust Treatment Systems (Reference 11).The Unit 1 Plant Vent release pathway includes two release sources that are commonto the two units: ventilation air from the Fuel Handling
: Building, and discharges from theGASEOUS WASTE PROCESSING SYSTEM. Otherwise, discharges from the tworeactor units are separated.
Reactor Containment Building ventilation releases arethrough 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. TheRadwaste Processing Facility Vent includes sources from the Radwaste Processing Facility Process area.Releases from the two Turbine Building Vents and the Radwaste Processing FacilityVent are considered to be ground-level
: releases, whereas releases from the two PlantVents are considered mixed-mode releases.
Chapter 8 discusses the calculation ofatmospheric dispersion parameters using the ground-level and mixed-mode (i.e., split-wake) models. All five potential release pathways are considered to be continuous (asopposed to batch) in nature.3-19VER 29 VEGP ODCMRadioactivity MonitorARE-0014To Unit 1 Plant Ventvia Auxiliary BuildingVentilation SystemTo Chemical VolumeControl TankTo Waste Gas DecayTank HeaderIIIIUnit 2 Waste GasVolume ControlTank PurgeRecycle Evaporator Vent Condenser Waste Evaporator Vent Condenser Recycle HoldupTank EductorReactor CoolantDrain Tank*Dotted line operational between 20 and 100 psigNOTE: This is typical of both units. However, Unit 2 GWPS releasesvia Unit 1 plant vent.Figure 3-1.Schematic Diagram of the Gaseous Radwaste Treatment System3-20VER 29 VEGP ODCMPlant VentRadioactivity MonitorI RE12442A,B,C HEARE 255,,C Fe HEanlgiT I ICF I CF I CFI I IHEPA /HEPAI HEPARadioactivi R Ctorty Monitor I IRE 0039A MAuxiliary
)Building Radioactivity MonitorI RE2565A,B,C Fuel Handling( ) ( )Building CF (Shared)*
HC HetingCiReactor ME Moistur ElMinator t tr y Mthe FuContainment ARE-0014From Waste GasProcessing Area andtemSystem HEPA -High-Efficiency Particulate Air FilterCF -Activated Charcoal FilterHC -Heating CoilME -Moisture Eliminator
* Prior to treatment by the Fuel Handling Building Ventilation ExhaustTreatment System, Exhaust from Unit I Spent Fuel Pool Area ismonitored by ARE2532B and ARE2533B; exhaust from Unit 2 SpentFuel Pool Area is monitored by ARE2532A and ARE2533A.
Figure 3-2. Schematic Diagram of the Unit 1 Plant Vent Release Pathway3-21VER 29 VEGP ODCMPlant VentI3-22VER 29 VEGP ODCM0Radioactivity Monitor2RE12442A,B,C Auxiliary BuildingRadioactivity MonitorReactorContainment HEPA -High-Efficiency Particulate Air FilterCF -Activated Charcoal FilterHC -Heating CoilME -Moisture Eliminator Figure 3-3. Schematic Diagram of the Unit 2 Plant Vent Release Pathway3-23VER 29 VEGP ODCMTurbine BuildingRadioactivity MonitorI(2)RE12839A,B,C NCSteam Jet Air Steam PackingHEPA -High-Efficiency Particulate Air FilterCF -Activated Charcoal FilterHC -Heating CoilDE -DemisterNO -Normally OpenNC -Normally ClosedNOTE: This is typical of both units.Figure 3-4.Schematic Diagram of the Turbine Building Vent Release Pathway (Typical ofBoth Units)3-24VER 29 VEGP ODCMRaciwaste Proc:cssing Facility VentRadioaclivity Monitor ARE 16980IIEPARadwastc PJOcclsiDs Facility Proee:u Area-Room 101Figure 3-5. Schematic Diagram of the Radwaste Processing Facility Ventilation ReleasePathway3-25VER 29 VEGP ODCM3.3 GASEOUS EFFLUENT MONITOR SETPOINTS 3.3.1 General Provisions Regarding Noble Gas Monitor Setpoints 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 notexceeded.
They will be regarded as upper bounds for the actual high alarm setpoints.
That is, a lower high alarm setpoint may be established or retained on the monitor, ifdesired.
Intermediate level setpoints should be established at an appropriate level togive sufficient warning prior to reaching the high alarm setpoint.
If no release is planned for a given pathway, or if there is no detectable activity in thegaseous stream being evaluated for release, the setpoint should be calculated inaccordance with the methods presented below, based on an assumed concentration ofKr-88 that leads to a practical setpoint.
A practical setpoint in this context is one whichprevents spurious alarms, and yet produces an alarm 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. Othermonitors are located on source streams, that is, streams that merge with other streamsprior to passing a final monitor and being discharged; the setpoint methodology forthese monitors is presented in Section 3.3.3. Table 3-4 identifies which of thesesetpoint methodologies applies to each monitor.
Some additional monitors with specialsetpoint requirements are discussed in Section 3.3.5.As established in Section 3.1.1, gaseous effluent monitor setpoints are required only forthe noble gas monitors on certain potential release streams:
the two Plant Vents, thetwo Turbine Building Vents, and the GASEOUS WASTE PROCESSING SYSTEMdischarge.
: However, because of the potential significance of releases from othersources, Section 3.3 discusses setpoint methodologies for certain additional
: monitors, as well.3-20VER 29 VEGP ODCMTable 3-4. Applicability of Gaseous Monitor Setpoint Methodologies Final Release Pathways with no Monitored Source StreamsSetpoint Method:Release Elevation:
Section 3.3.2Ground-level Unit 1 or Unit 2 Turbine Building VentMonitor:Maximum Flowrate:
1 RE-12839C/2RE-12839C 900 cfm (4.25 E+05 mL/s)Final Release Pathways with One or More Monitored Source StreamsRelease Elevation:
Mixed-Mode Unit 1 Plant VentMonitors:
Maximum Flowrate:
Setpoint Method:Release Type:1 RE-12442C, 1 RE-12444C 187,000 cfm (8.83 E+07 mL/s)Section 3.3.2CONTINUOUS Source Stream: Unit 1 Reactor Containment PuraqeMonitor:
1 RE-2565CMaximum Flowrate:
release-dependent Setpoint Method: Section 3.3.3Release Type: BATCHSource Stream: Gaseous Waste Treatment SystemMonitor:Maximum Flowrate:
Setpoint Method:Release Type:Unit 2 Plant VentMonitors:
Maximum Flowrate:
Setpoint Method:Release Type:ARE-0014release-dependent Section 3.3.3BATCH2RE-12442C, 2RE-12444C 112,500 cfm (5.31 E+07 mL/s)Section 3.3.2CONTINUOUS Source Stream: Unit 2 Reactor Containment PurgeMonitor:Maximum Flowrate:
Setpoint Method:Release Type:2RE-2565C release-dependent Section 3.3.3BATCH(X3-Q-vb Values for Use in Setpoint Calculations Ground-Level Releases:
Mixed-Mode Releases:
2.55 x 10-6 s/m3 [NE Sector]4.62 x 10-7s/m3[NE Sector]Maximum flowrate values are from Reference 11, Table 11.5.2-1 and Table 11.5.5-1.
3-21VER 29 VEGP ODCM3.3.2 Setpoint for the Final Noble Gas Monitor on Each Release Pathway3.3.2.1 Overview of MethodGaseous effluent radioactivity monitors are intended to alarm prior to exceeding thelimits of Section 3.1.2.a.
Therefore, their alarm setpoints are established to ensurecompliance with the following equation:
flAG. ~SF .X .Rtc =the lesser of AG. (3.1)LAG.SF.X.Rk where:c = the setpoint, in jtCi/mL, of the radioactivity monitor measuring theconcentration of radioactivity in the effluent line prior to release.
Thesetpoint represents a concentration which, if exceeded, could resultin dose rates exceeding the limits of Section 3.1.2.a at or beyond theSITE BOUNDARY.
AG = an administrative allocation factor applied to divide the release limitamong 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 mrem/y, to thedose rate to the total body for the conditions of the release underconsideration.
Rk = the ratio of the dose rate limit for the skin, 3000 mrem/y, to the doserate to the skin for the conditions of the release under consideration.
Equation (3.1) shows the relationships of the critical parameters that determine thesetpoint.
: However, in order to apply the methodology presented in the equation to amixture of noble gas radionuclides, radionuclide-specific concentrations and dosefactors must be taken into account under conditions of maximum flowrate for therelease point and annual average meteorology.
The basic setpoint method presented below is applicable to the radioactivity monitornearest the point of release for the release pathway.
For monitors measuring theradioactivity 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.3-22VER 29 VEGP ODCM3.3.2.2 Setpoint Calculation StepsStep 1: Determine the concentration, Xjv, of each noble gasradionuclide i in the gaseous stream v being considered for release, inaccordance with the sampling and analysis requirements of Section3.1.2. Then sum these concentrations to determine the total noble gasconcentration, YXjv.Step 2: Determine Rt, the ratio of the dose rate limit for the total body,500 mrem/y, to the total body dose rate due to noble gases detected inthe release under consideration, as follows:Rt= 500 (3.2)(7-)vb y K-Qvwhere:500 = the dose rate limit for the total body, 500 mrem/y.FXIQ)vb = the highest annual average relative concentration at the SITEBOUNDARY for the discharge point of release pathway v. Table 3-4includes an indication of what release elevation is applicable to eachrelease pathway; release elevation determines the appropriate value ofFxQ)Vb *Ki = the total-body dose factor due to gamma emissions from noble gasradionuclide i, in (mrem/y)/(p.Ci/m 3), from Table 3-5.Qiv = the release rate of noble gas radionuclide i from the release pathwayunder consideration, in [tCi/s, calculated as the product of Xiv and fav,where:Xi = the concentration of noble gas radionuclide i for the particular release,in p.Ci/mL.fav = the maximum anticipated flowrate for release pathway v during theperiod of the release under consideration, in mL/s.Step 3: Determine Rk, the ratio of the dose rate limit for the skin, 3000mrem/y, to the skin dose rate due to noble gases detected in the releaseunder consideration, as follows:3000 (3.3)(X/Q-),h Y_ [(L' + 1. 1M).QI3-23VER 29 VEGP ODCMwhere:3000 = the dose rate limit for the skin, 3000 mrem/y.Li = the skin dose factor due to beta emissions from noble gasradionuclide i, in (mrem/y)/(ptCi/m3),
from Table 3-5.= the air dose factor due to gamma emissions from noble gasradionuclide i, in (mrad/y)I(&#xfd;.Ci/m3),
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.
Step 4: Determine the maximum noble gas radioactivity monitorsetpoint concentration.
Based on the values determined in previous steps, the radioactivity monitor setpoint forthe planned release is calculated to ensure that the limits of Section 3.1.2.a will not beexceeded.
Because the radioactivity monitor responds primarily to radiation from noblegas radionuclides, the monitor setpoint Cnv (in [tCi/mL) is based on the concentration ofall noble gases in the waste stream, as follows:where:Cnv = the calculated
: setpoint, in &#xfd;.Ci/mL, for the noble gas monitor servinggaseous release pathway v.SAG
* SF" YX,, " R,c,,,,= the lesser of (3.4)LAG
* SF.EXiV ARAiAGv = the administrative allocation factor for gaseous release pathway v,applied to divide the release limit among all the gaseous releasepathways at the site. The allocation factor may be assigned anyvalue between 0 and 1, under the condition that the sum of theallocation factors for all simultaneously-active final release pathwaysat the entire plant site does not exceed 1. Alternative methods fordetermination 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 bebetween 0 and 1. A value of 0.5 is reasonable for gaseous releases; a more precise value may be developed if desired.3-24VER 29 VEGP ODCMXiv = the measured concentration of noble gas radionuclide i in gaseousstream v, as defined in Step 1, in [tCi/mL.The values of Rt and Rk 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 Xiv, the release is permissible.
: However, if Cnv is within about 10 percentof YZXi,, itImay be impractical to use this value of Cnv. This situation indicates thatmeasured concentrations are approaching values which would cause thelimits of Section 3.1.2.a to be exceeded.
Therefore, steps should betaken to reduce contributing source terms of gaseous radioactive
: material, or to adjust the allocation of the limits among the active releasepoints. The setpoint calculations (steps 1-4) must then be repeated withparameters that reflect the modified conditions.
If Cnv < Y-Xiv, the release may not be made as planned.
Consider the alternatives discussed in the paragraph above, and calculate a new setpoint basedon the results of the actions taken.3.3.2.3 Use of the Calculated SetpointThe setpoint calculated above is in the units p.Ci/mL.
The monitor actually measures acount rate, subtracts a predetermined background count rate, and multiplies by acalibration factor to convert from count rate to 1LCi/mL.Initial calibration by the manufacturer and Georgia Power Company of the gaseouseffluent monitors specified in Section 3.1.1 utilized at least one NIST-traceable gaseousradionuclide source in the exact geometry of each production monitor.
The point andgaseous sources used covered the beta particle end point energy range from 0.293MeV to at least 1.488 MeV. The calibration factor is a function of the radionuclide mix inthe gas to be released, and normally will be calculated for the monitor based on theresults of the sample results from the laboratory gamma-ray spectrometer system. Themix-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 betweencount rate and concentration may include operational data obtained from determining the monitor response to stream concentrations measured by sample analysis.
3-25VER 29 VEGP ODCMIn all cases, monitor background must be controlled so that the monitor is capable ofresponding to concentrations in the range of the setpoint value. Contributions to themonitor background may include any or all of the following factors:
ambient background radiation, plant-related radiation levels at the monitor location (which may changebetween shutdown and power conditions),
and internal background due tocontamination of the monitor's sample chamber.3.3.3 Setpoints for Noble Gas Monitors on Effluent Source StreamsTable 3-4 lists certain gaseous release pathways as being source streams.
As may beseen 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 finalmonitors, the source stream monitors measure radioactivity in effluent streams for whichflow can be terminated; therefore, the source stream monitors have control logic toterminate the source stream release at the alarm setpoint.
3.3.3.1 Setpoint of the Monitor on the Source StreamStep 1: Determine the concentration XIs of each noble gasradionuclide i in source stream s (in 1.Ci/mL) according to the results ofits required sample analyses
[see Section 3.1.2].Step 2: Determine rt, the ratio of the dose rate limit for the total body,500 mrem/y, to the total body dose rate due to noble gases detected inthe source stream under consideration.
Use the Xis values and themaximum anticipated source stream flowrate fas in equation (3.2) todetermine the total body dose rate for the source stream, substituting rtfor Rt.The SITE BOUNDARY relative dispersion value used in Steps 2 and 3 for thesource stream is the same as the (X--Q)vb that applies to the respective mergedstream. This is because the (xlQ) value is determined by the meteorology ofthe plant site and the physical attributes of the release point, and is unaffected bywhether or not a given source stream is operating.
Step 3: Determine rk, the ratio of the dose rate limit for the skin, 3000mrem/y, to the skin dose rate due to noble gases detected in the sourcestream under consideration.
Use the Xis values and the maximumanticipated source stream flow rate fas in equation (3.3) to determine theskin dose rate for the source stream, substituting rk for Rk.Step 4: Determine the maximum noble gas radioactivity monitorsetpoint concentration, as follows:3-26VER 29 VEGP ODCM{AGs SF -Y Xis" rtCns = the lesser of (3.5)AGs *SF .Xis.rkwhere:Cns = the calculated setpoint (in [tCi/mL) for the noble gas monitor servinggaseous source stream s.AGs = the administrative allocation factor applied to gaseous source streams. For a given final release point v, the sum of all the AGs values forsource streams contributing to the final release point must notexceed the release point's allocation factor Agv.Xis = the measured concentration of noble gas radionuclide i in gaseoussource stream s, as defined in Step 1, in pCi/mL.The values of rt and rk to be used in the calculation are those which were determined inSteps 2 and 3 above. The safety factor, SF, was defined previously.
Step 5: Determine whether the release is permissible, as follows:If Cns > ZXis, the release is permissible.
: However, if Cns is within about 10 percentof ZX8s, it may be impractical to use this value of Cns. This situation indicates that measured concentrations are approaching values whichwould cause the limits of Section 3.1.2.a to be exceeded.
Therefore, steps should be taken to reduce contributing source terms of gaseousradioactive
: material, or to adjust the allocation of the limits among theactive release points. The setpoint calculations (steps 1-4) must then berepeated with parameters that reflect the modified conditions.
If Cns < EXis, the release may not be made as planned.
Consider the alternatives discussed in the paragraph above, and calculate a new setpoint basedon the results of the actions taken.3.3.3.2 Effect on the Setpoint of the Monitor on the Merged StreamBefore beginning a release from a monitored source stream, a setpoint must bedetermined 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 setpoint for the downstream final monitor on themerged stream must be redetermined.
This is accomplished by repeating the steps ofSection 3.3.2, with the following modifications.
3-27VER 29 VEGP ODCMModification 1:The new maximum anticipated flowrate of the merged streamis the sum of the old merged stream maximum flowrate, andthe maximum flowrate of the source stream being considered for release.(Janew = (Li. l + fa,(3.6)Modification 2:The new concentration of noble gas radionuclide i in themerged stream includes both the contribution of the mergedstream without the source stream, and the source streambeing considered for release.tv ' _ (fa, )"/d,, .(X, )o,,, + fas* Xi ,.s -tiv nmew(Jav),ne, t -I3.3.4 Determination of Allocation
: Factors, AGWhen simultaneous gaseous releases are conducted, an administrative allocation factormust 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 exceeded 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 pathsat the plant site may not exceed 1.2. The sum of the allocation factors for all simultaneously-active source streamsmerging into a given final release pathway may not exceed the allocation factorof that final release pathway.Any of the following three methods may be used to assign the allocation factors to theactive gaseous release pathways:
: 1. For ease of implementation, AG, may be equal for all release pathways:
'1AG, = -(3.8)where:N = the number of simultaneously active gaseous release pathways.
: 2. AG, for a given release pathway may be selected based on an estimate of theportion of the total SITE BOUNDARY dose rate (from all simultaneous releases) that is contributed by the release pathway.
During periods when a given building3-28VER 29 VEGP ODCMor release pathway is not subject to gaseous radioactive
: releases, it may beassigned an allocation factor of zero.3. AG, for a given release pathway may be selected based on a calculation of theportion of the total SITE BOUNDARY dose rate that is contributed by the releasepathway, as follows:(XI/Qlb (K Q1N)AGv = N (3.9)where:(ROQ)vb = the annual average SITE BOUNDARY relative concentration applicable to the gaseous release pathway v for which the allocation factor is being determined, in s/m3.Ki = the total-body dose factor due to gamma emissions from noble gasradionuclide i, in (mremly)I(
jiCi/m3), from Table 3-5.QiV = the release rate of noble gas radionuclide i from release pathway v,in ACi/s, calculated as the product of X1v and fav, where:Xiv = the concentration of noble gas radionuclide i applicable to thegaseous release pathway v for which the allocation factor is beingdetermined, in &#xfd;.Ci/mL.fav = the discharge flowrate applicable to gaseous release pathway v forwhich the allocation factor is being determined, in mL/s.= the annual average SITE BOUNDARY relative concentration applicable to active gaseous release pathway r, in s/m3.Qir = the release rate of noble gas radionuclide i applicable to activerelease pathway r, in ItCi/s, calculated as the product of Xir and far,where:Xir = the concentration of noble gas radionuclide i applicable to activegaseous release pathway r, in pICi/mL.far = the discharge flowrate applicable to active gaseous release pathwayr, in mL/s.N = the number of simultaneously active gaseous release pathways(including pathway v that is of interest).
3-29VER 29 VEGP ODCMNOTE: Although equations (3.8) and (3.9) are written to illustrate theassignment of the allocation factors for final release pathways, theymay also be used to assign allocation factors to the source streamsthat merge into a given final release pathway.3.3.5 Setpoints for Noble Gas Monitors with Special Requirements At present, VEGP has no noble gas monitors for which setpoint methodologies are to bepresented in the ODCM, and that require methods other than those in Section 3.3.2 orSection 3.3.3.3.3.6 Setpoints for Particulate and Iodine MonitorsIn accordance with Section 5.1.1 of NRC NUREG-0133 (Reference 1), the effluentcontrols of Section 3.1.1 do not require that the ODCM establish setpoint calculation methods for particulate and iodine monitors.
Therefore, the following is provided forinformation only: Initial setpoints for the particulate channels of effluent monitors RE-12442 and RE-2565 were determined as described in Reference 13.3-30VER 29 VEGP ODCM3.4 GASEOUS EFFLUENT COMPLIANCE CALCULATIONS 3.4.1 Dose Rates at and Beyond the Site BoundaryBecause the dose rate limits for areas at and beyond the SITE specified in Section 3.1.2are site limits applicable at any instant in time, the summations extend over allsimultaneously active gaseous final release pathways at the plant site. Table 3-4identifies the gaseous final release pathways at the plant site, and indicates the (XlQ)Vbvalue for each.3.4.1.1 Dose Rates Due to Noble GasesFor the purpose of implementing the controls of Section 3.1.2.a, the dose rates due tonoble gas radionuclides in areas at or beyond the SITE BOUNDARY, due to releases ofgaseous effluents, shall be calculated as follows:For total body dose rates:DRt =y_&#xfd;(XIQ)Vb, y[KjQij1 (3.10)For skin dose rates:where:DRt = the total body dose rate at the time of the release, in mrem/y.DRk = the skin dose rate at the time of the release, in mrem/y.Qiv = the release rate of noble gas radionuclide i, in &#xfd;tCi/s, equal to theproduct of ft, and Xv, where:fry = the actual average flowrate for release pathway v during the period ofthe release, in mL/s.All other terms were defined previously.
3.4.1.2 Dose Rates Due to Iodine-1 31, Iodine-1 33, Tritium, andRadionuclides in Particulate Form with Half-Lives Greaterthan 8 DaysFor the purpose of implementing the controls of Section 3.1.2.b, the dose rates due toIodine-1 31, Iodine-1 33, 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 ofgaseous effluents, shall be calculated as follows:3-31VER 29 VEGP ODCMDRVk =(5Y_,b ZVO LY IP Q', i, (3.12)where:DRo = the dose rate to organ o at the time of the release, in mrem/y.Pio = the site-specific dose factor for radionuclide i and organ o, in(mrem/y)/(&#xfd;LCi/m 3). Since the dose rate limits specified in Section3.1.2.b apply only to the child age group exposed to the inhalation
: pathway, the values of Pi,, may be obtained from Table 3-9, "Raipj forInhalation
: Pathway, Child Age Group."Qqv = the release rate of radionuclide i from gaseous release pathway v, inpCi/s. For the purpose of implementing the controls of Section3.1.2.b, only 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days should be included in thiscalculation.
All other terms were defined previously.
3.4.2 Noble Gas Air Dose at or Beyond Site BoundaryFor the purpose of implementing the controls of Section 3.1.3, air doses in areas at orbeyond the SITE BOUNDARY due to releases of noble gases from each unit shall becalculated as follows (adapted from Reference 1, page 28, by including only long-term releases):
D,6 = 3.17x 10 {Yi&#xfd;2Qb Nj .iv (3.13)Dy =3.17x 10{X /Q),Vb [Mi , Qiv (3.14)where:3.17 x 10-8 = a units conversion factor: 1 y/(3.15 x 107 s).D&#xfd; = the air dose due to beta emissions from noble gas radionuclides, inmrad.Dy = the air dose due to gamma emissions from noble gas radionuclides, in mrad.Ni = the air dose factor due to beta emissions from noble gas radionuclide i (mrad/y)/(jxCi/m 3), from Table 3-5.3-32VER 29 VEGP ODCMMi = the air dose factor due to gamma emissions from noble gasradionuclide i (mrad/y)I(ptCi/m 3), from Table 3-5.Oil = the cumulative release of noble gas radionuclide i from releasepathway v (&#xfd;iCi), during the period of interest.
and all other terms are as defined above.Because the air dose limit is on a per-reactor-unit basis, the summations extend over allgaseous final release pathways for a given unit. For a release pathway discharging materials originating in both reactor units, the activity discharged from the release pointmay be apportioned to the two units in any reasonable manner, provided that all activityreleased via the particular shared release pathway is apportioned to one or the otherunit.The gaseous final release pathways at the plant site, and the --Q)vb for each, areidentified in Table 3-4.3-33VER 29 VEGP ODCMTable 3-5.Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gasesy -Body (K) 13- Skin (L) 7- Air (M) 3 -Air (N)Nuclide (mrem/y) per (mrem/y) per (mrad/y) per (mrad/y) per(&#xfd;tCilm3) (1iCilm3) (gCilm3) ([LCi/m3)Kr-83m 7.56 E-02 0.00 E+00 1.93 E+01 2.88 E+02Kr-85m 1.17 E+03 1.46 E+03 1.23 E+03 1.97 E+03Kr-85 1.61 E+01 1.34 E+03 1.72 E+01 1.95 E+03Kr-87 5.92 E+03 9.73 E+03 6.17 E+03 1.03 E+04Kr-88 1.47 E+04 2.37 E+03 1.52 E+04 2.93 E+03Kr-89 1.66 E+04 1.01 E+04 1.73 E+04 1.06 E+04Kr-90 1.56 E+04 7.29 E+03 1.63 E+04 7.83 E+03Xe-131m 9.15 E+01 4.76 E+02 1.56 E+02 1.11 E+03Xe-1 33m 2.51 E+02 9.94 E+02 3.27 E+02 1.48 E+03Xe-133 2.94 E+02 3.06 E+02 3.53 E+02 1.05 E+03Xe-1 35m 3.12 E+03 7.11 E+02 3.36 E+03 7.39 E+02Xe-135 1.81 E+03 1.86 E+03 1.92 E+03 2.46 E+03Xe-137 1.42 E+03 1.22 E+04 1.51 E+03 1.27 E+04Xe-138 8.83 E+03 4.13 E+03 9.21 E+03 4.75 E+03Ar-41 8.84 E+03 2.69 E+03 9.30 E+03 3.28 E+03All values in this table were obtained from Reference 3 (Table B-i), with units converted.
3-34VER 29 VEGP ODCMTable 3-6.Dose Factors for Exposure to Direct Radiation from Noble Gases in anElevated Finite PlumeThe contents of this table are not applicable to VEGP.3-35VER 29 VEGP ODCM3-36VER 29 VEGP ODCM3.4.3 Dose to a Member of the Public at or Beyond Site BoundaryThe dose received by an individual due to gaseous releases from each reactor unit, toareas at or beyond the SITE BOUNDARY, depends on the individual's
: location, agegroup, and exposure pathways.
The MEMBER OF THE PUBLIC expected to receivethe highest dose in the plant vicinity is referred to as the controlling receptor.
Thedosimetrically-significant attributes of the currently-defined controlling receptor arepresented 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):
Dja = 3.17x 10-" Y{ZiE R [J-W,, [ QKip 1 (3.15)where:Dja = the dose to organ j of an individual in age group a, due to gaseousreleases of 1-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in mrem.3.17 x 10-8 = a units conversion factor: 1 y/(3.15 x 107 s).Raipj the site-specific dose factor for age group a, radionuclide i, exposurepathway p, and organ j. For the purpose of implementing thecontrols of Section 3.1.4, the exposure pathways applicable tocalculating the dose to the currently-defined controlling receptor areincluded in Table 3-7; values of Raipj for each exposure pathway andradionuclide 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 forcalculating Raipj for the plant site is presented in Chapter 9. Thatinformation may be used for recalculating the Raipj values if theunderlying parameters change, or for calculating Raipm values forspecial radionuclides and age groups when performing theassessments discussed in Section 3.4.4 below.Wvi = the annual average relative dispersion or deposition at the location ofthe controlling
: receptor, for release pathway v, as appropriate toexposure pathway p and radionuclide i.3-37VER 29 VEGP ODCMFor all tritium pathways, and for the inhalation of any radionuclide:
Wjp is (XIQ),, , the annual average relative dispersion factor forrelease pathway v, at the location of the controlling receptor (s/m3).For the ground-plane exposure
: pathway, and for all ingestion-related pathways for radionuclides other than tritium:
Wvip is FJIQ-)vP, theannual average relative deposition factor for release pathway v, atthe location of the controlling receptor (m-2). Values of (x-Q)vp and(DI-Q-)vp for use in calculating the dose to the currently-defined controlling receptor are included in Table 3-7.'iv = the cumulative release of radionuclide i from release pathway v,during the period of interest (ptCi). For the purpose of implementing the controls of Section 3.1.4, only 1-131, 1-133, tritium, and allradionuclides in particulate form with half-lives greater than 8 daysshould be included in this calculation.
In any dose assessment usingthe methods of this subsection, only radionuclides detectable abovebackground in their respective samples should be included in thecalculation.
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 pathwaydischarging materials originating in both reactor units, the activity discharged from therelease 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 otherunit.The gaseous final release pathways at the plant site, and the release elevation for each,are identified in Table 3-4.3-38 VER293-38VER 29 VEGP ODCMTable 3-7.Attributes of the Controlling ReceptorThe locations of members of the public in the vicinity of the plant site, and the exposurepathways 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 isdescribed as follows.Sector:Distance:
Age Group:WSW1.2 milesChildExposure Pathways:
Inhalation, ground plane, cow meat, and garden vegetation Dispersion Factors (-XIQvb:Ground-Level release points:Mixed-Mode release points:6.20 E-7 s/m31.27 E-7 s/m3Deposition Factors (DI-Qvb:Ground-Level release points:Mixed-Mode release points:2.80 E-9 m29.90 E-10 m-23-39VER 29 VEGP ODCM3-40VER 29 VEGP ODCM3.4.4 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, withthe substitution of the dispersion and deposition parameters
[(X/Q) and (D/Q)] forthe period covered by the report, and using the appropriate pathway dose factors(Raipj) for the receptor of interest.
Methods for calculating (X/Q) and (D/Q) frommeteorological data are presented in Chapter 8.Values of Raipj other than those presented in Tables 3-8 through 3-12 may needto be calculated.
Methods and parameters for calculating values of Raipj arepresented in Chapter 9. When calculating Raipo for evaluation of an event,pathway and usage factors specific to the receptor involved in the event may beused 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 UseCensus, under the provisions of Section 4.1.2.In the event that the Land Use Census reveals that exposure pathways havechanged at previously-identified locations, or if new locations are identified, itmay be necessary to calculate doses at two or more locations to determine whichshould be designated as the controlling receptor.
Such dose calculations may beperformed using the equations in Section 3.4.3, with the substitution of theannual average dispersion and deposition values [-j-Q-) and (D-I-Q)]
for thelocations of interest, and using the appropriate pathway dose factors (Raipj) forthe receptors of interest.
Methods for calculating (X/Q) and (D/Q) from meteorological data are presented in Chapter 8. The values of Raio other than those presented in Tables 3-8through 3-12 may need to be calculated.
Methods and parameters forcalculating values of Raipj are presented in Chapter 9.Case 3: Under Section 5.2, a dose calculation may be required to support thedetermination of a component of the total dose to a receptor other thanthat currently defined as the controlling receptor.
Dose calculations would be performed using the equations in Section 3.4.3, withthe dispersion and deposition parameters and appropriate values of (Raipj) for thereceptor of interest.
Appropriate values of the dispersion and deposition parameters, if not found inTable 3-7, would need to be calculated.
Methods for calculating (X/Q) and (D/Q)from meterological data are presented in Chapter 8.3-41VER 29 VEGP ODCMAppropriate values of Raipj, if not found in Tables 3-8 through 3-12, would need tobe calculated.
Methods and parameters for calculating values of Raipj arepresented in Chapter 9.3-42VER 29 VEGP ODCMTable 3-8. Raipj for Ground Plane Pathway, All Age GroupsNuclide T. Body SkinH-3 0.00 0.00C-14 0.00 0.00P-32 0.00 0.00Cr-51 4.66E+06 5.51 E+06Mn-54 1.39E+09 1.63E+09Fe-55 0.00 0.00Fe-59 2.73E+08 3.21 E+08Co-58 3.79E+08 4.44E+08Co-60 2.15E+10 2.53E+10Ni-63 0.00 0.00Zn-65 7.47E+08 8.59E+08Rb-86 8.99E+06 1.03E+07Sr-89 2.16E+04 2.51E+04Sr-90 0.00 0.00Y-91 1.07E+06 1.21 E+06Zr-95 2.45E+08 2.84E+08Nb-95 1.37E+08 1.61 E+08Ru-103 1.08E+08 1.26E+08Ru-106 4.22E+08 5.07E+08Ag-110m 3.44E+09 4.01E+09Sb-124 5.98E+08 6.90E+08Sb-125 2.34E+09 2.64E+09Te-125m 1.55E+06 2.13E+06Te-127m 9.16E+04 1.08E+05Te-129m 1.98E+07 2.31E+071-131 1.72E+07 2.09E+071-133 2.45E+06 2.98E+06Cs-134 6.86E+09 8.OOE+09Cs-136 1.51E+08 1.71E+08Cs-137 1.03E+10 1.20E+10Ba-140 2.05E+07 2.35E+07Ce-141 1.37E+07 1.54E+07Ce-144 6.95E+07 8.04E+07Pr-143 0.00 0.00Nd-147 8.39E+06 1.01E+071. Units are m2.(mremlyr)l([tCifs).
: 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 6.2.3-43VER 29 VEGP ODCMTable 3-9. Raipj for Inhalation
: Pathway, Child Age GroupNuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLIH-3 0.00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03P-32 2.60E+06 1.14E+05 9.88E+04 0.00 0.00 0.00 4.22E+04Cr-51 0.00 0.00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03Mn-54 0.00 4.29E+04 9.51E+03 0.00 1.OOE+04 1.58E+06 2.29E+04Fe-55 4.74E+04 2.52E+04 7.77E+03 0.00 0.00 1.11E+05 2.87E+03Fe-59 2.07E+04 3.34E+04 1.67E+04 0.00 0.00 1.27E+06 7.07E+04Co-58 0.00 1.77E+03 3.16E+03 0.00 0.00 1.11E+06 3.44E+04Co-60 0.00 1.31E+04 2.26E+04 0.00 0.00 7.07E+06 9.62E+04Ni-63 8.21E+05 4.63E+04 2.80E+04 0.00 0.00 2.75E+05 6.33E+03Zn-65 4.26E+04 1.13E+05 7.03E+04 0.00 7.14E+04 9.95E+05 1.63E+04Rb-86 0.00 1.98E+05 1.14E+05 0.00 0.00 0.00 7.99E+03Sr-89 5.99E+05 0.00 1.72E+04 0.00 0.00 2.16E+06 1.67E+05Sr-90 1.01E+08 0.00 6.44E+06 0.00 0.00 1.48E+07 3.43E+05Y-91 9.14E+05 0.00 2.44E+04 0.00 0.00 2.63E+06 1.84E+05Zr-95 1.90E+05 4.18E+04 3.70E+04 0.00 5.96E+04 2.23E+06 6.11E+04Nb-95 2.35E+04 9.18E+03 6.55E+03 0.00 8.62E+03 6.14E+05 3.70E+04Ru-103 2.79E+03 0.00 1.07E+03 0.00 7.03E+03 6.62E+05 4.48E+04Ru-106 1.36E+05 0.00 1.69E+04 0.00 1.84E+05 1.43E+07 4.29E+05Ag-110m 1.69E+04 1.14E+04 9.14E+03 0.00 2.12E+04 5.48E+06 1.OOE+05Sb-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00Sb-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00Te-125m 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00 4.77E+05 3.38E+04Te-127m 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+051-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00 2.84E+031-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00 5.48E+03Cs-134 6.51E+05 1.01E+06 2.25E+05 0.00 3.30E+05 1.21E+05 3.85E+03Cs-136 6.51E+04 1.71E+05 1.16E+05 0.00 9.55E+04 1.45E+04 4.18E+03Cs-137 9.07E+05 8.25E+05 1.28E+05 0.00 2.82E+05 1.04E+05 3.62E+03Ba-140 7.40E+04 6.48E+01 4.33E+03 0.00 2.11E+01 1.74E+06 1.02E+05Ce-141 3.92E+04 1.95E+04 2.90E+03 0.00 8.55E+03 5.44E+05 5.66E+04Ce-144 6.77E+06 2.12E+06 3.61E+05 0.00 1.17E+06 1.20E+07 3.89E+05Pr-143 1.85E+04 5.55E+03 9.14E+02 0.00 3.OOE+03 4.33E+05 9.73E+04Nd-147 1.08E+04 8.73E+03 6.81E+02 0.00 4.81E+03 3.28E+05 8.21E+041.2.Units are (mremlyr)I(p Cilm3) for all radionuclides.
This table also supports the calculations of section 6.2.3-44VER 29 VEGP ODCMTable 3-10.Raipj for Inhalation
: Pathway, Adult Age GroupNuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLIH-3 0.00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03C-14 1.82E+04 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03P-32 1.32E+06 7.71E+04 5.01E+04 0.00 0.00 0.00 8.64E+04Cr-51 0.00 0.00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03Mn-54 0.00 3.96E+04 6.30E+03 0.00 9.84E+03 1.40E+06 7.74E+04Fe-55 2.46E+04 1.70E+04 3.94E+03 0.00 0.00 7.21E+04 6.03E+03Fe-59 1.18E+04 2.78E+04 1.06E+04 0.00 0.00 1.02E+06 1.88E+05Co-58 0.00 1.58E+03 2.07E+03 0.00 0.00 9.28E+05 1.06E+05Co-60 0.00 1.15E+04 1.48E+04 0.00 0.00 5.97E+06 2.85E+05Ni-63 4.32E+05 3.14E+04 1.45E+04 0.00 0.00 1.78E+05 1.34E+04Zn-65 3.24E+04 1.03E+05 4.66E+04 0.00 6.90E+04 8.64E+05 5.34E+04Rb-86 0.00 1.35E+05 5.90E+04 0.00 0.00 0.00 1.66E+04Sr-89 3.04E+05 0.00 8.72E+03 0.00 0.00 1.40E+06 3.50E+05Sr-90 9.92E+07 0.00 6.1OE+06 0.00 0.00 9.60E+06 7.22E+05Y-91 4.62E+05 0.00 1.24E+04 0.00 0.00 1.70E+06 3.85E+05Zr-95 1.07E+05 3.44E+04 2.33E+04 0.00 5.42E+04 1.77E+06 1.50E+05Nb-95 1.41E+04 7.82E+03 4.21E+03 0.00 7.74E+03 5.05E+05 1.04E+05Ru-103 1.53E+03 0.00 6.58E+02 0.00 5.83E+03 5.05E+05 1.10E+05Ru-106 6.91E+04 0.00 8.72E+03 0.00 1.34E+05 9.36E+06 9.12E+05Ag-110m 1.08E+04 1.OOE+04 5.94E+03 0.00 1.97E+04 4.63E+06 3.02E+05Sb-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 0.00 2.48E+06 4.06E+05Sb-125 6.61E+04 7.13E+02 1.33E+04 5.87E+01 0.00 2.20E+06 1.01E+05Te-125m 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04Te-127m 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05Te-129m 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+051-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00 6.28E+031-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.00 8.88E+03Cs-134 3.73E+05 8.48E+05 7.28E+05 0.00 2.87E+05 9.76E+04 1.04E+04Cs-136 3.90E+04 1.46E+05 1.1OE+05 0.00 8.56E+04 1.20E+04 1.17E+04Cs-137 4.78E+05 6.21E+05 4.28E+05 0.00 2.22E+05 7.52E+04 8.40E+03Ba-140 3.90E+04 4.90E+01 2.57E+03 0.00 1.67E+01 1.27E+06 2.18E+05Ce-141 1.99E+04 1.35E+04 1.53E+03 0.00 6.26E+03 3.62E+05 1.20E+05Ce-144 3.43E+06 1.43E+06 1.84E+05 0.00 8.48E+05 7.78E+06 8.16E+05Pr-143 9.36E+03 3.75E+03 4.64E+02 0.00 2.16E+03 2.81E+05 2.OOE+05Nd-147 5.27E+03 6.1OE+03 3.65E+02 0.00 3.56E+03 2.21E+05 1.73E+051. Units are (mremlyr)l(gCilm
: 3) for all radionuclides.
: 2. This table is included to support the calculations of section 6.2.3-45VER 29 VEGP ODCMTable 3-11. Raipj for Cow Meat Pathway, Child Age GroupNuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLIH-3 0.00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02C-14 5.29E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05P-32 7.41E+09 3.47E+08 2.86E+08 0.00 0.00 0.00 2.05E+08Cr-51 0.00 0.00 8.79E+03 4.88E+03 1.33E+03 8.91E+03 4.66E+05Mn-54 0.00 8.01E+06 2.13E+06 0.00 2.25E+06 0.00 6.72E+06Fe-55 4.57E+08 2.42E+08 7.51E+07 0.00 0.00 1.37E+08 4.49E+07Fe-59 3.76E+08 6.09E+08 3.03E+08 0.00 0.00 1.77E+08 6.34E+08Co-58 0.00 1.64E+07 5.02E+07 0.00 0.00 0.00 9.58E+07Co-60 0.00 6.93E+07 2.04E+08 0.00 0.00 0.00 3.84E+08Ni-63 2.91E+10 1.56E+09 9.91E+08 0.00 0.00 0.00 1.05E+08Zn-65 3.75E+08 1.OOE+09 6.22E+08 0.00 6.30E+08 0.00 1.76E+08Rb-86 0.00 5.77E+08 3.55E+08 0.00 0.00 0.00 3.71E+07Sr-89 4.82E+08 0.00 1.38E+07 0.00 0.00 0.00 1.87E+07Sr-90 1.04E+10 0.00 2.64E+09 0.00 0.00 0.00 1.40E+08Y-91 1.80E+06 0.00 4.82E+04 0.00 0.00 0.00 2.40E+08Zr-95 2.66E+06 5.85E+05 5.21E+05 0.00 8.38E+05 0.00 6.11E+08Nb-95 3.1OE+06 1.21E+06 8.62E+05 0.00 1.13E+06 0.00 2.23E+09Ru-103 1.55E+08 0.00 5.96E+07 0.00 3.90E+08 0.00 4.01E+09Ru-106 4.44E+09 0.00 5.54E+08 0.00 5.99E+09 0.00 6.90E+10Ag-110m 8.39E+06 5.67E+06 4.53E+06 0.00 1.06E+07 0.00 6.74E+08Sb-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00Sb-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00Te-125m 5.69E+08 1.54E+08 7.59E+07 1.60E+08 0.00 0.00 5.49E+08Te-127m 1.77E+09 4.78E+08 2.11E+08 4.24E+08 5.06E+09 0.00 1.44E+09Te-129m 1.79E+09 5.OOE+08 2.78E+08 5.77E+08 5.26E+09 0.00 2.18E+091-131 1.65E+07 1.66E+07 9.46E+06 5.50E+09 2.73E+07 0.00 1.48E+061-133 5.67E-01 7.02E-01 2.66E-01 1.30E+02 1.17E+00 0.00 2.83E-01Cs-134 9.22E+08 1.51E+09 3.19E+08 0.00 4.69E+08 1.68E+08 8.16E+06Cs-136 1.62E+07 4.46E+07 2.88E+07 0.00 2.37E+07 3.54E+06 1.57E+06Cs-137 1.33E+09 1.28E+09 1.88E+08 0.00 4.16E+08 1.50E+08 7.99E+06Ba-140 4.38E+07 3.84E+04 2.56E+06 0.00 1.25E+04 2.29E+04 2.22E+07Ce-141 2.22E+04 1.11E+04 1.64E+03 0.00 4.86E+03 0.00 1.38E+07Ce-144 2.32E+06 7.26E+05 1.24E+05 0.00 4.02E+05 0.00 1.89E+08Pr-143 3.34E+04 1.OOE+04 1.66E+03 0.00 5.43E+03 0.00 3.60E+07Nd-147 1.17E+04 9.47E+03 7.33E+02 0.00 5.19E+03 0.00 1.50E+07Units are (mremlyr)l(,
Cilm3) for tritium, and m2.(mremlyr)I(&#xfd;,Cils) for all otherradionuclides.
3-46VER 29 VEGP ODCMTable 3-12. Raipj for Garden Vegetation
: Pathway, Child Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLIH-3 0.00 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03 4.01E+03C-14 8.89E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08P-32 3.37E+09 1.58E+08 1.30E+08 0.00 0.00 0.00 9.31E+07Cr-51 0.00 0.00 1.17E+05 6.50E+04 1.78E+04 1.19E+05 6.21E+06Mn-54 0.00 6.65E+08 1.77E+08 0.00 1.86E+08 0.00 5.58E+08Fe-55 8.01E+08 4.25E+08 1.32E+08 0.00 0.00 2.40E+08 7.87E+07Fe-59 3.98E+08 6.43E+08 3.20E+08 0.00 0.00 1.86E+08 6.70E+08Co-58 0.00 6.44E+07 1.97E+08 0.00 0.00 0.00 3.76E+08Co-60 0.00 3.78E+08 1.12E+09 0.00 0.00 0.00 2.1OE+09Ni-63 3.95E+10 2.11E+09 1.34E+09 0.00 0.00 0.00 1.42E+08Zn-65 8.13E+08 2.16E+09 1.35E+09 0.00 1.36E+09 0.00 3.80E+08Rb-86 0.00 4.52E+08 2.78E+08 0.00 0.00 0.00 2.91E+07Sr-89 3.60E+10 0.00 1.03E+09 0.00 0.00 0.00 1.39E+09Sr-90 1.24E+12 0.00 3.15E+11 0.00 0.00 0.00 1.67E+10Y-91 1.86E+07 0.00 4.99E+05 0.00 0.00 0.00 2.48E+09Zr-95 3.86E+06 8.48E+05 7.55E+05 0.00 1.21E+06 0.00 8.85E+08Nb-95 4.1OE+05 1.60E+05 1.14E+05 0.00 1.50E+05 0.00 2.96E+08Ru-103 1.53E+07 0.00 5.90E+06 0.00 3.86E+07 0.00 3.97E+08Ru-106 7.45E+08 0.00 9.30E+07 0.00 1.01E+09 0.00 1.16E+10Ag-110m 3.21E+07 2.17E+07 1.73E+07 0.00 4.04E+07 0.00 2.58E+09Sb-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00Sb-1 25 0.00 0.00 0.00 0.00 0.00 0.00 0.00Te-125m 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00 0.00 3.38E+08Te-127m 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.00 1.07E+09Te-129m 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 0.00 1.03E+091-131 1.43E+08 1.44E+08 8.17E+07 4.75E+10 2.36E+08 0.00 1.28E+071-133 3.53E+06 4.37E+06 1.65E+06 8.11E+08 7.28E+06 0.00 1.76E+06Cs-134 1.60E+10 2.63E+10 5.55E+09 0.00 8.15E+09 2.93E+09 1.42E+08Cs-136 8.24E+07 2.27E+08 1.47E+08 0.00 1.21E+08 1.80E+07 7.96E+06Cs-137 2.39E+10 2.29E+10 3.38E+09 0.00 7.46E+09 2.68E+09 1.43E+08Ba-140 2.77E+08 2.42E+05 1.61E+07 0.00 7.89E+04 1.45E+05 1.40E+08Ce-141 6.56E+05 3.27E+05 4.86E+04 0.00 1.43E+05 0.00 4.08E+08Ce-144 1.27E+08 3.98E+07 6.78E+06 0.00 2.21E+07 0.00 1.04E+10Pr-143 1.46E+05 4.37E+04 7.23E+03 0.00 2.37E+04 0.00 1.57E+08Nd-147 7.15E+04 5.79E+04 4.48E+03 0.00 3.18E+04 0.00 9.17E+07Units are (mremlyr)I(p.Cilm
: 3) for tritium, andradionuclides.
2m .(mrem/yr)/(jiCi/s) for all other3-47VER29 VEGP ODCM3.5 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 radwastetreatment system (see Section 3.1.5), dose projections must be made at least onceeach 31 days; this applies during periods in which a discharge to areas at or beyond theSITE BOUNDARY of gaseous effluents containing radioactive materials occurs or isexpected.
Projected 31-day air doses and doses to individuals due to gaseous effluents may bedetermined as follows:For air doses:= 7 Doc x 31+/-+ Dpa(3.16)Dy = ("- x 31 + DyaFor individual doses:D=- -D-RZJ 31,+ D (3.17)where:Dpp = the projected air dose due to beta emissions from noble gases, forthe next 31 days of gaseous releases.
Dpc = the cumulative air dose due to beta emissions from noble gasreleases that have occurred in the elapsed portion of the currentquarter, plus the release under consideration.
DOa = the anticipated air dose due to beta emissions from noble gasreleases, contributed by any planned activities during the next 31-day period, if those activities will result in gaseous releases that arein addition to routine gaseous effluents.
If only routine gaseouseffluents are anticipated, DOa may be set to zero.Dyp = the projected air dose due to gamma emissions from noble gases forthe next 31 days of gaseous releases.
Dyc = the cumulative air dose due to gamma emissions from noble gasreleases that have occurred in the elapsed portion of the currentquarter, plus the release under consideration.
3-48VER 29 VEGP ODCMDya = the anticipated air dose due to gamma emissions from noble gasreleases, contributed by any planned activities during the next 31-day period, if those activities will result in gaseous releases that arein addition to routine gaseous effluents.
If only routine gaseouseffluents are anticipated, Dya may be set to zero.Dop = the projected dose to the total body or organ o, due to releases of I-131, 1-133, tritium, and particulates for the next 31 days of gaseousreleases.
Doc = the cumulative dose to the total body or organ o, due to releases of1-131, 1-133, tritium, and particulates that have occurred in theelapsed portion of the current quarter, plus the release underconsideration.
Doa = the anticipated dose to the total body or organ o, due to releases of1-131, 1-133, tritium, and particulates, contributed by any plannedactivities during the next 31-day period, if those activities will result ingaseous releases that are in addition to routine gaseous effluents.
Ifonly routine gaseous effluents are anticipated, Doa may be set tozero.t = the number of whole or partial days elapsed into the current quarter,including the time to the end of the release under consideration (evenif the release continues into the next quarter).
3.5.2 Dose Projections for Specific ReleasesDose 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 airdose and individual dose projections due to gaseous effluent
: releases, follow themethodology of Section 3.4, using sample analysis results for the gaseous stream to bereleased, and parameter values expected to exist during the release period.3-49VER 29 VEGP ODCM3.6 DEFINITIONS OF GASEOUS EFFLUENT TERMSSectionof InitialTerm Definition UseAG = the administrative allocation factor for gaseous streams,applied to divide the gaseous release limit among all therelease pathways
[unitless].
3.3.2.1AGs = the administrative allocation factor for gaseous sourcestream s, applied to divide the gaseous release limitamong all the release pathways
[unitless].
3.3.3AGv = the administrative allocation factor for gaseous releasepathway v, applied to divide the gaseous release limitamong all the release pathways
[unitless].
3.3.2.2c = the setpoint of the radioactivity monitor measuring theconcentration of radioactivity in the effluent line prior torelease [jiCi/mL].
3.3.2.1Cns = the calculated noble gas effluent monitor setpoint forgaseous source stream s [gCi/mL].
3.3.3Cnv = the calculated noble gas effluent monitor setpoint forrelease pathway v [giCi/mL].
3.3.2.2Dja = the dose to organ j of an individual in age group a, due togaseous releases of 1-131, 1-133, tritium, andradionuclides in particulate form with half-lives greater than 3.4.38 days [mrem].Doa = the anticipated dose to organ o due to releases of non-noble-gas radionuclides, contributed by any plannedactivities during the next 31-day period [mrem]. 3.5.1Do= the cumulative dose to organ o due to releases of non-noble-gas radionuclides that have occurred in the elapsedportion of the current quarter, plus the release under 3.5.1consideration
[mrem].Dop= the projected dose to organ o due to the next 31 days ofgaseous releases of non-noble-gas radionuclides
[mrem]. 3.5.1D= the air dose due to beta emissions from noble gasradionuclides
[mrad]. 3.4.23-50VER 29 VEGP ODCMSectionof InitialTerm Definition UseDoa = the anticipated air dose due to beta emissions from noblegas releases, contributed by any planned activities duringthe next 31-day period [mrad]. 3.5.1Doc = the cumulative air dose due to beta emissions from noblegas releases that have occurred in the elapsed portion ofthe current quarter, plus the release under consideration 3.5.1[mrad].DIp = the projected air dose due to beta emissions from noblegases, for the next 31 days of gaseous releases
[mrad]. 3.5.1DY= the air dose due to gamma emissions from noble gasradionuclides
[mrad]. 3.4.2Dya = the anticipated air dose due to gamma emissions fromnoble gas releases, contributed by any planned activities during the next 31-day period [mrad]. 3.5.1Dyc = the cumulative air dose due to gamma emissions fromnoble gas releases that have occurred in the elapsedportion of the current quarter, plus the release under 3.5.1consideration
[mrad].Dyp = the projected air dose due to gamma emissions from noblegases, for the next 31 days of gaseous releases
[mrad]. 3.5.1(DIQ)vp = the annual average relative deposition factor for releasepathway v, at the location of the controlling
: receptor, from 3.4.3Table 3-7 [m-2].DRk = the skin dose rate at the time of the release [mrem/y].
3.4.1.1DRo = the dose rate to organ o at the time of the release 3.4.1.2[mrem/y].
DRt = the total body dose rate at the time of the release 3.4.1.1[mrem/y].
fav = the maximum anticipated actual discharge flowrate forrelease pathway v during the period of the planned release 3.3.2.2[mL/s].fas = the maximum anticipated actual discharge flowrate forgaseous source stream s during the period of the planned 3.3.33-51VER 29 VEGP ODCMSectionof InitialTerm Definition Userelease [mL/s].Ki = the total body dose factor due to gamma emissions fromnoble gas radionuclide i, from Table 3-5 3.3.2.2[(mrem/y)l([.C i/m3)].Li = the skin dose factor due to beta emissions from noble gasradionuclide i, from Table 3-5 [(mrem/y)/(&#xfd;.Cilm 3)]. 3.3.2.2M= the air dose factor due to gamma emissions from noblegas radionuclide i, from Table 3-5 [(mradly)/(jICi/m 3)]. 3.4.2N = the number of simultaneously active gaseous releasepathways
[unitless].
3.3.4N = the air dose factor due to beta emissions from noble gasradionuclide i, from Table 3-5 [(mradly)/([iCilm 3)]. 3.4.2Pio = the site-specific dose factor for radionuclide i (I-131, 1-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days) and organ o. The values of P0,are equal to the site-specific Raipj values presented in 3.4.1.2Table 3-9 [(mrem/y)/(jiCi/m 3)].Q= the release rate of noble gas radionuclide i from releasepathway v during the period of interest
[pCi/s].
3.3.2.2Q'iv= the release rate of radionuclide i (1-131, 1-133, tritium, andradionuclides in particulate form with half-lives greater than8 days) from gaseous release pathway v during the periodof interest
[pCi/s].
3.4.1.2v= the cumulative release of noble gas radionuclide i fromrelease pathway v during the period of interest
[ptCi]. 3.4.2the cumulative release of non-noble-gas radionuclide ifrom release pathway v, during the period of interest
[pCi]. 3.4.3Raipj = the site-specific dose factor for age group a, radionuclide i,exposure pathway p, and organ j. Values and units of Raipjfor each exposure
: pathway, age group, and radionuclide that may arise in calculations for implementing Section3.1.4 are listed in Table 3-8 through Table 3-9. 3.4.33-52VER 29 VEGP ODCMSectionof InitialTerm Definition UseRk = the ratio of the skin dose rate limit for noble gases, to theskin dose rate due to noble gases in the release underconsideration
[unitless].
3.3.2.1Rt = the ratio of the total body dose rate limit for noble gases, tothe total body dose rate due to noble gases in the releaseunder consideration
[unitless].
3.3.2.1rk = the ratio of the skin dose rate limit for noble gases, to theskin dose rate due to noble gases in the source streamunder consideration
[unitless].
3.3.3.1rt = the ratio of the total body dose rate limit for noble gases, tothe total body dose rate due to noble gases in the sourcestream under consideration
[unitless].
3.3.3.1SF = the safety factor used in gaseous setpoint calculations tocompensate for statistical fluctuations and errors ofmeasurement
[unitless].
3.3.2.2t =the number of whole or partial days elapsed in the currentquarter, including the period of the release under 3.5.1consideration.
Wvip = the annual average relative dispersion
[(X-IQ--)P]
ordeposition
[(IQ-)-Pv]
at the location of the controlling
: receptor, for release pathway v, as appropriate to 3.4.3exposure pathway p and radionuclide i.X = the noble gas concentration for the release underconsideration
[pCi/mL].
3.3.2.1Xir = the concentration of radionuclide i applicable to activegaseous release pathway r [pCi/mL].
3.3.4Xis = the measured concentration of radionuclide i in gaseoussource stream s [pCi/mL].
3.3.33-53VER 29 VEGP ODCMSectionof InitialTerm Definition UseA= the measured concentration of radionuclide i in gaseousstream v [IuCi/mL].
3.3.2.2(X/Q) = the highest relative concentration at any point at or beyondthe SITE BOUNDARY
[s/m3]. 3.3.2.1(x-'-IQ),=
the annual average SITE BOUNDARY relativeconcentration applicable to active gaseous release 3.3.4pathway r [s/m3].= the highest annual average relative concentration at theSITE BOUNDARY for the discharge point of releasepathway v, from Table 3-4 [s/m3]. 3.3.2.2I-Q-)IP = annual average relative dispersion factor for releasepathway v, at the location of the controlling
: receptor, from 3.4.3Table 3-7 [s/m3].3-54VER 29 VEGP ODCMCHAPTER 4RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM4.1 LIMITS OF OPERATION The following limits are the same for both units at the site. Thus, a single programincluding 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 asspecified in Table 4-1.4.1.1.1 Applicability This control applies at all times.4.1.1.2 Actions4.1.1.2.1 With the REMP not being conducted as specified in Table 4-1, submit tothe Nuclear Regulatory Commission (NRC), in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program asrequired and the plans for preventing a recurrence.
Deviations from the requiredsampling schedule are permitted if specimens are unobtainable due to hazardous conditions, unavailability, inclement
: weather, equipment malfunction, or other justreasons.
If deviations are due to equipment malfunction, efforts shall be made tocomplete corrective action prior to the end of the next sampling period.4.1.1.2.2 With the confirmed 1 measured level of radioactivity as a result of planteffluents in an environmental sampling medium specified in Table 4-1 exceeding thereporting levels of Table 4-2 when averaged over any calendar
: quarter, submit within 30days a special report to the NRC. The special report shall identify the cause(s) forexceeding the limit(s) and define the corrective action(s) to be taken to reduceradioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLICis less than the calendar year limits of Sections 2.1.3, 3.1.3, and 3.1.4. Themethodology and parameters used to estimate the potential annual dose to a MEMBEROF THE PUBLIC shall be indicated in the special report.When more than one of the radionuclides in Table 4-2 are detected in the samplingmedium, this report shall be submitted if:Defined as confirmed by reanalysis of the original sample, or analysis of a duplicate or newsample, as appropriate.
The results of the confirmatory analysis shall be completed at theearliest time consistent with the analysis.
4-1VER 29 VEGP ODCMconcentrat ion (1) concentrat ion (2) + ... > 1.0reporting level (1) reporting level (2)When radionuclides other than those in Table 4-2 are detected and are the result ofplant effluents, this special report shall be submitted if the potential annual dose to aMEMBER OF THE PUBLIC is equal to or greater than the calendar year limits stated inSections 2.1.3, 3.1.3, and 3.1.4. This special report is not required if the measured levelof radioactivity was not the result of plant effluents;
: however, in such an event, thecondition shall be described in the Annual Radiological Environmental Operating Report. The levels of naturally-occurring radionuclides which are not included in theplant's effluent releases need not be reported.
4.1.1.2.3 If adequate samples of milk, or during the growing season, grass or leafyvegetation, 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, effortsshall 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 theREMP. Pursuant to Technical Specification 5.5.1, documentation shall be submitted inthe next Radioactive Effluent Release Report for the change(s) in the ODCM, including revised figure(s) and table(s) reflecting the changes to the location(s),
with supporting information identifying the cause of the unavailability of samples and justifying theselection of any new location(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 Table4-1 and Table 4-3. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with therecommendations of Regulatory Guide 4.13. Program changes may be initiated basedon 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 circumstances may render these MDCsunachievable.
In such cases, the contributing factors will be identified and described inthe Annual Radiological Environmental Operating Report.4.1.1.4 Basis4-2VER 29 VEGP ODCMThe 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 PUBLICresulting from the plant operation.
The REMP implements Section IV.B.2, Appendix I,10 CFR 50, and thereby supplements the radiological effluent monitoring program bymeasuring concentrations of radioactive materials and levels of radiation, which maythen be compared with those expected on the basis of the effluent measurements andmodeling of the environmental exposure pathways.
The detection capabilities required by Table 4-3 are within state-of-the-art for routineenvironmental measurements in industrial laboratories.
4-3VER 29 VEGP ODCMTable 4-1. Radiological Environmental Monitoring ProgramExposure Number of Representative Samples and Sample Sampling and Type andPathway Locations(l)
Collection Frequency ofand/or Sample Frequency Analysis1. DIRECT RADIATION Direct Thirty-six or more routine monitoring
: stations, either Quarterly.
Gamma doseRadiation(2) with two or more dosimeters, or with one instrument quarterly.
for measuring and recording dose rate continuously, placed as follows:An inner ring of stations, one in each meteorological sector in the general area of the site boundary.
An outer ring of stations, one in each meteorological sector at approximately 5 miles from the site.The balance of the stations to be placed in specialinterest areas such as population
: centers, nearbyresidences,
: schools, and in one or more areas toserve as control stations.
: 2. AIRBORNERadioiodine Samples from 5 or more locations as follows:
Continuous Radioiodine and sampler operation Canister:
1-131Particulates Three or more samples from close to the three site with sample analysis weekly.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:
Grossthe highest calculated annual average ground-level
: loading, beta radioactivity D/Q. analysis following filter change, andOne sample from a control location, as, for example, gamma isotopica population center 10 to 20 miles distant and in the analysis ofleast prevalent wind direction.
composite (bylocation) quarterly.(3)(4) 4-4VER 29 VEGP ODCMTable 4-1. Radiological Environmental Monitoring ProgramExposure Number of Representative Samples Sampling and Collection Type and Frequency ofPathway and Sample Locations(I)
Frequency Analysisand/or Sample3. WATERBORNE Surface(5)
One sample upstream.
Composite sample over Gamma isotopic analysis1-month period.(6) monthly; composite forOne sample downstream.
tritium analysisquarterly.(4)
Drinking Two samples at each of the one to Composite sample of river 1-131 analysis on eachthree nearest water treatment plants water near intake at each sample when the dosethat could be affected by discharges water treatment plant over calculated for thefrom the facility.
2-week period when 1-131 consumption of the water isanalysis is performed, greater than 1 mrem perTwo samples at a control location, monthly composite year. Composite for grossotherwise; and grab sample beta and gamma isotopicof finished water at each analyses monthly.water treatment plant every Composite for tritium2 weeks or monthly, as analysis quarterly.(4)(7) appropriate.(6)
Sediment from One sample from downstream area Semiannually.
Gamma isotopic analysisShoreline with existing or potential recreational semi-annually.(4) value.Groundwater An adequate number of onsite wells Quarterly Tritium and gammato provide detection of radioactive isotopic quarterly.
Otherliquid releases into the groundwater analyses based on resultsfrom tanks, underground piping, and of tritium and gamma.other plant equipment.
At least onewell at a control location.
4-5VER 29 VEGP ODCMTable 4-1. Radiological Environmental Monitoring ProgramExposure Number of Representative Samples and Sample Sampling and Type andPathway Locations(I)
Collection Frequency ofand/or Sample Frequency Analysis4. INGESTION Milk Samples from milking animals in three locations within Semimonthly.
Gamma3 miles distance having the highest dose potential; if there isotopicare none, then one sample from milking animals in each of analysis semi-three areas between 3 and 5 miles distance where doses monthly.(4)(8) are calculated to be greater than 1 mrem per year.(7)One sample from milking animals at a control location about10 miles distant or beyond, and preferably in a wind direction of low prevalence.
Fish At least one sample of any commercially and recreationally Semiannually.
Gammaimportant species in vicinity of plant discharge area. isotopicanalyses onAt least one sample of any species in areas not influenced edibleby plant discharge.
portions.(4)
At least one sample of any anadromous species in vicinity of During spring Gammaplant discharge.
spawning isotopicseason. analyses onedibleportion.(4)
Grass or One sample from two onsite locations near the site boundary Monthly during GammaLeafy in different sectors.
growing season. isotopic.(4)(8)
Vegetation____________
____One sample from a control location about 15 miles distant.
Monthly during Gammagrowing season, isotopic.(4)(8) 4-6VER 29 VEGP ODCMTable 4-1. Radiological Environmental Monitoring ProgramTABLE NOTATIONS (1) For each sample location in this table, specific parameters of distance and direction sector from a pointmidwaybetween 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 ratecontinuously, may be used in place of or in addition to integrating dosimeters.
For the purpose of this table, athermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet areconsidered as two or more dosimeters.
Film badges shall not be used as dosimeters for measuring directradiation.
(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more aftersamplingto allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than10 timesthe yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides thatmay be attributable to the effluents from the facility.
(5) The upstream sample shall be taken at a distance beyond significant influence of the discharge.
Thedownstream sample shall be taken in an area beyond but near the mixing zone.(6) Composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to thecompositing 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 for1-131 will be performed.
4-7VER 29 VEGP ODCMTable 4-2. Reporting Levels for Radioactivity Concentrations in Environmental SamplesWater Airborne Fish Milk Grass or LeafyApalyLi Particulate or Vegetation
______ Gases (pCi/m3) (pCi/kg, wet) (pCi/L) (pCi/kg, wet)H-3 2 E+4aMn-54 1 E+3 3 E+4Fe-59 4 E+2 1 E+4Co-58 1 E+3 3 E+4Co-60 3 E+2 1 E+4Zn-65 3 E+2 2 E+4Zr-95 4 E+2Nb-95 7 E+21-131 2 E+Ob 9 E-1 3 E+0 1 E+2Cs-134 3 E+1 1 E+1 1 E+3 6 E+1 1 E+3Cs-137 5 E+1 2 E+1 2 E+3 7 E+1 2 E+3Ba-140 2 E+2 3 E+2La-140 1 E+2 0 E+2a. This is the 40 CFR 141 value for drinking water samples.
If no drinking water pathway exists, a value of 3 E+04 pCi/Lmay be used.b. If no drinking water pathway exists, a value of 20 pCi/L may be used.4-8VER 29 VEGP ODCMTable 4-3. Values for the Minimum Detectable Concentration (MDC)Minimum Detectable Concentration (MDC)aWater Airborne Fish Milk Grass or Leafy SedimentAnlssParticulate or Vegetation Analysis (pCi/L) G ase p r (pCi/kg, wet) (pCi/L) (iget) (pCi/kg, dry)Gases (p Ci/m3) (C(pCi/kg, wet)Gross Beta 4 E+O 1 E-2H-3 2 E+3bMn-54 1.5 E+1 1.3 E+2Fe-59 3 E+1 2.6 E+2Co-58, Co-60 1.5 E+1 1.3 E+2Zn-65 3 E+1 2.6 E+2Zr-95 3 E+1Nb-95 1.5 E+11-131 1 E+Oc 7 E-2 1 E+0 6 E+1Cs-134 1.5 E+1 5 E-2 1.3 E+2 1.5 E+1 6 E+1 1.5 E+2Cs-137 1.8 E+1 6 E-2 1.5 E+2 1.8 E+1 8 E+1 1.8 E+2Ba-140 6 E+1 6 E+1La-140 1.5 E+1 1.5 E+1a. See the definition of MINIMUM DETECTABLE CONCENTRATION in Section 10.1. Other peaks which aremeasurable and identifiable as plant effluents, together with the radionuclides in this table, shall be analyzed andreported in accordance with Section 7.1.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 pCi/L may be used.4-9VER 29 VEGP ODCM4.1.2 Land Use CensusA land use census shall be conducted and shall identify the following within a distance of 5miles in each of the 16 meteorological sectors:
the location of the nearest milk animal,1 thenearest permanent residence, and the nearest garden of greater than 500 square feetproducing broad leafy vegetation.
Land within the Savannah River Site is excluded from thiscensus.4.1.2.1 Applicability This control applies at all times.4.1.2.2 Actions4.1.2.2.1 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 withSection 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 alocation 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 samplinglocation, excluding control station location(s),
having the lowest calculated dose or dosecommitment (via the same exposure pathway) may be deleted from the REMP if newsampling locations are added. Pursuant to Technical Specification 5.5.1 submit in the nextRadioactive Effluent Release Report any change(s) in the ODCM, including the revisedfigure(s) and table(s) reflecting any new location(s) and information supporting thechange(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 providegood 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, asfeasible.
Results of the land use census shall be included in the Annual Radiological Environmental Operating Report.4.1.2.4 BasisThis control is provided to ensure that changes in the use of UNRESTRICTED AREAS areidentified and that modifications to the REMP are made if required by the results of thiscensus. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR1 Defined as a cow or goat that is producing milk for human consumption.
4-9VER 29 VEGP ODCMPart 50. Restricting the census to gardens of greater than 500 ft2 provides assurance thatsignificant exposure pathways via leafy vegetables will be identified and monitored since agarden of this size is the minimum required to produce the quantity (26 kg/y) of leafyvegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20 percent of thegarden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage) and(2) a vegetation yield of 2 kg/M2 was obtained.
4.1.3 Interlaboratory Comparison ProgramAnalyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which satisfies the requirements of Regulatory Guide 4.15, Revision1, February, 1979.4.1.3.1 Applicability This control applies at all times.4.1.3.2 ActionsWith 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 BasisThe requirement for participation in an approved Interlaboratory Comparison Program isprovided to ensure that independent checks on the precision and accuracy of themeasurements of radioactive material in environmental sample matrices are performed aspart 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 1, 10 CFR50.4-10VER 29 VEGP ODCM4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Table 4-4 and Table 4-5 and Figure 4-1 through Figure 4-5 specify the locations at which themeasurements and samples are taken for the REMP required by Section 4.1.1.4-i 1 VER294-11VER 29 VEGP ODCMTable 4-4. Radiological Environmental Monitoring Locations Location Descriptive Location Direction Distance SampleNumber (miles) Type(1)1 River Bank N 1.1 D2 River Bank NNE 0.8 D3 Discharge Area NE 0.6 A3 River Bank NE 0.7 D4 River Bank ENE 0.8 D5 River Bank E 1.0 D6 Plant Wilson ESE 1.1 D7 Simulator Building SE 1.7 D,V,A8 River Road SSE 1.1 D9 River Road S 1.1 D10 Met Tower SSW 0.9 A10 River Road SSW 1.1 D11 River Road SW 1.2 D12 River Road WSW 1.2 D,A13 River Road W 1.3 D14 River Road WNW 1.8 D15 Hancock Landing Road NW 1.5 D,V16 Hancock Landing Road NNW 1.4 D,A17 Savannah River Site, River Road N 5.4 D18 Savannah River Site, D Area NNE 5.0 D19 Savannah River Site, Road A.13 NE 4.6 D20 Savannah River Site, Road A.13.1 ENE 4.8 D21 Savannah River Site, Road A.17 E 5.3 D22 River Bank Downstream of Buxton ESE 5.2 DLanding23 River Road SE 4.6 D24 Chance Road SSE 4.9 D25 Chance Road near Highway 23 S 5.2 D26 Highway 23 and Ebenezer Church SSW 4.6 DRd.4-12VER 29 VEGP ODCMTable 4-4 (contd).Radiological Environmental Monitoring Locations Location Descriptive Location Direction Distance SampleNumber (miles) Type(l)27 Highway 23, opposite Boll Weevil SW 4.7 DRoad28 Thomas Road WSW 5.0 D29 Claxton-Lively Road W 5.1 D30 Nathaniel Howard Road WNW 5.0 D31 River Road at Allen's Chapel Fork NW 5.0 D32 River Bank NNW 4.7 D35 Girard SSE 6.6 D,A36 GPC Waynesboro Operating WSW 13.9 D,AHeadquarters 37 Substation; Waynesboro, GA WSW 16.7 D,V43 Employees Recreation Area SW 2.2 D47 Oak Grove Church SE 10.4 D48 McBean Cemetery NW 10.2 D51 SGA School; Sardis, GA S 11.0 D52 Oglethorp Substation; SW 10.7 DAlexander, GA80 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 R83 Savannah River (RM 150.4) ENE 0.8 R, S(4)84 Savannah River (RM 149.5) ESE 1.6 R85 Savannah River ESE 4.3 F(3)87 Beaufort
-Jasper Water Treatment SE 76.0 W(5)Plant; Beaufort, SC88 Cherokee Hill Water Treatment SSE 72.0 W(6)Plant; Port Wentworth, GA89 Purrysburg Water Treatment Plant; SSE 76.0 W(7)Purrysburg, SC101 Girard Dairy S 5.5 M102 Seven Oaks Dairy w 7.5 M4-13VER 29 VEGP ODCMTable 4-4 (cont.) Radiological Environmental Monitoring Locations TABLE NOTATIONS (1) Sample Types:A -Airborne Radioactivity D -Direct Radiation F -FishM -MilkR -River WaterS -River Shoreline SedimentW -Drinking Water (at water treatment plant)V -Vegetation (2) The intake for the Augusta Water Treatment Plant is located on the Augusta Canal. Theentrance 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 andonly 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 andbetween RMs 144 and 149.4 for downriver collections.
(4) Sediment is collected at locations with existing or potential recreational value. High watershifting of the river bottom or other reasons could cause a suitable location for sedimentcollection to become unavailable or unsuitable.
Thus, a stretch of river between RM 148.5and 150.5 is designated for downriver sediment collections, while a stretch between RM 153and 154 is designated for upriver collections.
In practice, collections are normally made atRM 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 canalwhich begins at RM 39.3 on the Savannah River. This intake is about 16 miles by line ofsight 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, whichis about one and a quarter creek miles from its mouth on the Savannah River at RM 29.(7) The intake for the Purrysburg Water Treatment Plant is located on the same canal as theBeaufort-Jasper Water Treatment Plant. The Purrysburg intake is nearer to the SavannahRiver at the beginning of the canal.4-14 VER 294-14VFR 29 VEGP ODCMTable 4-5. Groundwater Monitoring Locations WELL AQUIFER MONITORING PURPOSELT-1 B Water Table NSCW related tankLT-7A Water Table NSCW related tankLT-1 2 Water Table NSCW related tankLT-1 3 Water Table NSCW related tank802A Water Table Southeastern potential leakage803A* Water Table Up gradient to rad waste buildingDown gradient from rad waste bldgand NSCW related facilities 806B Water Table Dilution line808 Water Table Up gradient; along Pen Branch FaultNSCW related tank; western potential RI Water Tablelekg leakageR2 Water Table Southern potential leakageR3 Water Table Eastern potential leakageR4 Water Table Dilution lineR5 Water Table Dilution lineR6 Water Table Dilution lineR7 Water Table Dilution lineR8 Water Table Dilution line1014 Tertiary Up gradient1015 Water Table Vertically up gradient27 Tertiary Down gradient tertiary29 Tertiary Down gradient tertiaryMU-1 Tertiary/Cretaceous Facility water supplyRiver N/A Surface water* May need to be abandoned in the future due to construction activities (REF 23).4-15VER 29 VEGP ODCMj4w~91-65,,.) -"4FAFigure 4-1. Terrestrial Stations Near Site Boundary4-16 VER294-16VER 29 VEGP ODCM-I .IFigure 4-2. Terrestrial Stations and Aquatic Stations, 0-5 Miles4-17 VER294-17VER 29 VEGP ODCMFigure 4-3. Terrestrial Stations Beyond 5 Miles4-18 VER294-18VER 29 VEGP ODCMSOVEGP.Canal to SupWater to BGEORGIAPURRYSBURG WATER TREATMENT PLANT0 10 2V 30CHEROKEE HILLWATER TREATMENT PLANT(PORT WENTWORTH)
UTH CAROLINAply RivereaufortBeaufort Jasper CountyWater Treatment PlantC.,V,0Figure 4-4. Drinking Water Stations4-19VER 29 VEGPODCM11>6'4 5"NEV BARGE rALMJ1 OPTION I0,. ST DOMRIS BASIN DiAM,'-..0OW-1005179051927A\ "9ElOw-r0OW. 1009m-- p!ont-30 0oO-0Cp101t -2 _"--j .520OW W27% I.-t Te~rt~a ocd or mon.Ier.P wi.OV--1 -1012ULi-2\2' ,V,' V.i L3c L"c. -dc01cr,9,'- c m o cl 911ic'14-20VER 29 VEGPODCMFigure 4-5 Groundwater Monitoring Wells4-21 VER294-21VER 29 VEGP ODCMCHAPTER 5TOTAL DOSE DETERMINATIONS 5.1 LIMIT OF OPERATION In accordance with Technical Specification 5.5.4.j, the dose or dose commitment to anyMEMBER OF THE PUBLIC over a calendar year, due to releases of radioactivity and toradiation from uranium fuel cycle sources, shall be limited to less than or equal to 25mrem to the total body or any organ, except the thyroid, which shall be limited to lessthan or equal to 75 mrem.5.1.1 Applicability This limit applies at all times.5.1.2 ActionsWith the calculated doses from the release of radioactive materials in liquid or gaseouseffluents exceeding twice the limits of Section 2.1.3, 3.1.3, or 3.1.4, calculations shall bemade according to Section 5.2 methods to determine whether the limits of Section 5.1have been exceeded.
If these limits have been exceeded, prepare and submit a specialreport to the Nuclear Regulatory Commission within 30 days, which defines thecorrective actions to be taken to reduce subsequent releases to prevent recurrence ofexceeding the limits of Section 5.1 and includes the schedule for achieving conformance with the limits of Section 5.1. This special report, as defined in 10 CFR20.2203, shall also include an analysis which estimates the radiation exposure (dose) toa MEMBER OF THE PUBLIC from uranium fuel cycle sources (including all effluentpathways and direct radiation) for the calendar year that includes the release(s) coveredby this report. This special report shall also describe the levels of radiation andconcentrations of radioactive material
: involved, and the cause of the exposure levels orconcentrations.
If the estimated dose(s) exceeds the limits of Section 5.1, and if therelease condition resulting in violation of the provisions of 40 CFR 190 has not alreadybeen corrected, the special report shall include a request for variance in accordance with the provisions of 40 CFR 190 and including the specified information of 40 CFR190.11 (b). Submittal of the report is considered a timely request, and a variance isgranted 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 directradiation shall be determined in accordance with Section 5.2. This requirement isapplicable only under the conditions set forth above in Section 5.1.2.5.1.4 Basis5-1VER 29 VEGP ODCMThis control is provided to meet the dose limitations and reporting requirements of 40CFR 190. The control requires the preparation and submittal of a special reportwhenever the calculated doses from plant radioactive effluents exceed the limits ofSection 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 theindividual reactors remain within twice the dose design objectives of Appendix I and ifdirect radiation doses from the units, such as direct exposure from outside storagetanks, are kept small. The special report will describe a course of action which shouldresult in the limitation of dose to a MEMBER OF THE PUBLIC for a calendar year towithin the 40 CFR 190 limits. For the purposes of the special report, it may be assumedthat the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuelcycle sources is negligible with the exception that dose contributions from other uraniumfuel cycle facilities at the same site or within a radius of 5 miles must be considered.
Ifthe dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of40 CFR 190, the special report with a request for variance (provided the releaseconditions resulting in violation of 40 CFR 190 have not already been corrected),
inaccordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203(a)(4),
isconsidered to be a timely request and fulfills the requirements of 40 CFR 190 until NRCstaff action is completed.
The variance only relates to the limits of 40 CFR 190, anddoes not apply in any way to the requirements for dose limitation as addressed in othersections of this ODCM. An individual is not considered a MEMBER OF THE PUBLICduring any period in which he/she is engaged in carrying out any operation which is partof the nuclear fuel cycle.5-2VER 29 VEGP ODCM5.2 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 touranium fuel cycle sources shall be determined as follows:DTk = DL + DG +Do + DN (5.1)where:DTk = 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 plantsite in liquid effluents, calculated in accordance with Section 2.4.1, inmrem.DG = the dose to the same organ due to non-noble-gas radionuclides discharged from the plant site in gaseous effluents, calculated for thecontrolling receptor in accordance with Section 3.4.3, in mrem.DD = the direct radiation dose to the whole body of an individual at thecontrolling receptor
: location, due to radioactive materials retained withinthe plant site, in mrem. Values of direct radiation dose may bedetermined by measurement, calculation, or a combination of the two.DN = the external whole body dose to an individual at the controlling receptorlocation, due to gamma ray emissions from noble gas radionuclides discharged from the plant site in gaseous effluents, in mrem. DN iscalculated as follows (equation adapted from Reference 1, page 22, byrecasting in cumulative dose form):DN =3.17x1O8Z{X/Q)vp[K.j (5.2)where:3.17 x 10-8 = a units conversion factor: 1 y/(3.15 x 107 s).(iv = the cumulative release of noble gas radionuclide i fromrelease pathway v (pICi), during the period of interest.
Ki =the total-body dose factor due to gamma emissions from noblegas radionuclide i (mrem/y)/(&#xfd;t Ci/m3), from Table 3-5.5-3 VER295-3VER 29 VEGP ODCM(XE-Q-)I
= annual average relative dispersion factor for release pathwayv, at the location of the controlling
: receptor, from Table 3-7[s/m3].As defined above, DL and DG are for different age groups, while DD and DN are not agegroup specific.
When a more precise determination of DTk is desired, values of DL andDG may be calculated for all four age groups, and those values used in equation (5.1) todetermine age group specific values of DTk; the largest value of DTk for any age groupmay then be compared to the limits of Section 5.1.5-4VER 29 VEGP ODCMCHAPTER 6POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TOTHEIR ACTIVITIES INSIDE THE SITE BOUNDARY6.1 REQUIREMENT FOR CALCULATION To support the reporting requirements of Section 7.2.2.3, an assessment of theradiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THEPUBLIC due to their activities inside the SITE BOUNDARY shall be performed asspecified in Section 6.2, at least once per calendar year.6.2 CALCULATIONAL METHODFor the purpose of performing the calculations required in Section 6.1, the dose to amember 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 atany one of the defined locations shall be determined as follows:Dik = [DA +DS +DP]'F. (6.1)where:Dik = 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 FX1Q) valueto be used is given for each receptor location in Table 6-1; depletedAM values may be used in calculations for non-noble-gas radionuclides.
Ds = the dose to the same organ due to ground plane deposition of non-noble-gas radionuclides discharged from the plant site in gaseous effluents, calculated in accordance with Section 3.4.3, in mrem. The (LjQ) valueto be used is given for each receptor location in Table 6-1.Dp = the external whole body dose due to gamma ray emissions from noblegas radionuclides discharged from the plant site in gaseous effluents, calculated using equation (5.2), in mrem. The AM values that are tobe used are given for each receptor location in Table 6-1.6-1 VER296-1VER 29 VEGP ODCMFo = the occupancy factor for the given location, which is the fraction of theyear that one individual MEMBER OF THE PUBLIC is assumed to bepresent at the receptor location
[unitless].
Values of Fo for each receptorlocation are included in Table 6-1.6-2VER 29 VEGP ODCMTable 6-1. Attributes of Member of the Public Receptor Locations Inside the Site BoundaryLocation:
Visitors Center, SE at 447 metersAge Group:ChildOccupancy Factor: 4.57 x 10-4 (based on 4 hours per year)Dispersion and Deposition Parameters:
Parameter Ground-Level Mixed-Mode Undepleted (57U', s/m3  5.93 E-6 7.12 E-7Depleted (X7Q-, s/m3  5.58 E-6 6.74 E-7(DM7Q), m22.28 E-8 5.77 E-96-3VER 29 VEGP ODCMCHAPTER 7REPORTS7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT7.1.1 Requirement for ReportIn accordance with Technical Specification 5.6.2, the Annual Radiological Environmental Operating Report covering the REMP activities during the previous calendar year shallbe submitted before May 15 of each year. (A single report fulfills the requirements forboth units.) The material provided shall be consistent with the objectives outlined insection 4.1 and section 7.1.2 of the ODCM, and in SectionsIV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.7.1.2 Report ContentsThe materials specified in the following subsections shall be included in each AnnualRadiological Environmental Operating Report:7.1.2.1 DataThe report shall include summarized and tabulated results of all REMP samplesrequired by Table 4-1 taken during the report period, in a format similar to thatcontained in Table 3 of the Radiological Assessment Branch Technical Position(Reference 19); the results for any additional samples shall also be reported.
In theevent that some results are not available for inclusion with the report, the report shall besubmitted noting and explaining the reasons for the missing results; the missing datashall be submitted as soon as possible in a supplementary report. The results fornaturally-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:
(as appropriate) comparisons with preoperational studies,operational
: controls, and previous environmental reports; and an assessment of anyobserved impacts of the plant operation on the environment.
If the measured level ofradioactivity in an environmental sampling medium exceeding the reporting levels ofTable 4-2 is not the result of plant effluents, the condition shall be described as requiredby 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 theREMP; a map(s) of all sampling locations keyed to a table giving distances and7-1VER 29 VEGP ODCMdirections from a point midway between the centers of the two reactors; the results ofland use censuses required by Section 4.1.2; and the results of licensee participation inthe 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 eachreport, as follows:7.1.2.4.1 If the REMP is not conducted as required in Table 4-1, a description ofthe reasons for not conducting the program as required, and the plans for preventing arecurrence, 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 asrequired by Section 4.1.3, the corrective actions taken to prevent a recurrence must beincluded in the report.7-2VER 29 VEGP ODCM7.2 RADIOACTIVE EFFLUENT RELEASE REPORT7.2.1 Requirement for ReportIn accordance with Technical Specification 5.6.3, the Radioactive Effluent ReleaseReport covering the operation of the units during the previous calendar year ofoperation shall be submitted in accordance with 10 CFR Part 50.36a. (A singlesubmittal may be made for Units 1 and 2. However, the submittal shall specify thereleases of radioactive material in liquid and gaseous effluents from each unit and solidradioactive waste from the site.) The report shall include a summary of the quantities ofradioactive liquid and gaseous effluents and solid waste released from the units. Thematerial provided shall be consistent with the objectives outlined throughout this ODCMand the Process Control Program (PCP) and in conformance with 10 CFR Part 50.36aand Section IV.B.1 of Appendix I to 10 CFR Part 50.7.2.2 Report ContentsThe materials specified in the following subsections shall be included in eachRadioactive Effluent Release Report:7.2.2.1 Quantities of Radioactive Materials ReleasedThe report shall include a summary of the quantities of radioactive liquid and gaseouseffluents and solid waste released from the units as outlined in NRC Regulatory Guide1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes andReleases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,"
Revision 1, June 1974, with liquid and gaseous effluentdata summarized on a quarterly basis and solid radioactive waste data summarized ona semiannual basis following the format of Appendix B thereof.
Unplanned releases ofradioactive 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. Forgamma 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 DataThe 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 (ifmeasured) on magnetic tape; or in the form of joint frequency distributions of windspeed, wind direction, and atmospheric stability.
In lieu of submission with theRadioactive Effluent Release Report, the licensee has the option of retaining thissummary of required meteorological data on site in a file that shall be provided to theNRC upon request.7-3VER 29 VEGP ODCM7.2.2.3 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 withthe time of release of radioactive materials in gaseous effluents (as determined bysampling frequency and measurement) shall be used for determining the gaseouspathway doses. This assessment of 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 anassessment of radiation doses to the likely most exposed MEMBER OF THE PUBLICfrom reactor releases and other nearby uranium fuel cycle sources (including dosesfrom primary effluent pathways and direct radiation) for the previous calendar year toshow conformance with 40 CFR 190, Environmental Radiation Protection Standards forNuclear Power Operation; this dose assessment must be performed in accordance withChapter 5. The report shall also include an assessment of the radiation doses fromradioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to theiractivities inside the SITE BOUNDARY during the report period; this assessment mustbe performed in accordance with Chapter 6. All assumptions used in making theseassessments (i.e., specific
: activity, exposure time, and location) shall be included in thereport.7.2.2.4 Solid Radwaste DataFor 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 orestimate),
: 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) andg. Class of solid wastes (as defined by 10 CFR Part 61.)7.2.2.5 Licensee Initiated Document ChangesLicensee initiated changes shall be submitted to the Nuclear Regulatory Commission asa part of or concurrent with the Radioactive Effluent Release Report for the period inwhich any changes were made. Such changes to the ODCM shall be submitted pursuant to Technical Specification 5.5.1. This requirement includes:
7-4VER 29 VEGP ODCM7.2.2.5.1 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 anychanges 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:7.2.2.6.1 The report shall include deviations from the liquid and gaseous effluentmonitoring instrumentation operability requirements included in Sections 2.1.1 and3.1.1, respectively.
The report shall include an explanation as to why the inoperability ofthe liquid or gaseous effluent monitoring instrumentation was not corrected within thespecified time requirement.
7.2.2.6.2 The report shall include a description of the events leading to liquidholdup tanks or gas storage tanks exceeding the limits of Technical Specification 5.5.12.7.2.2.7 Major Changes to Radioactive Waste Treatment SystemsAs required by Sections 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TORADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall bereported to the Nuclear Regulatory Commission in the Radioactive Effluent ReleaseReport covering the period in which the change was reviewed and accepted forimplementation.
1 The discussion of each change shall contain:a. A summary of the evaluation that led to the determination that the change couldbe made in accordance with 10 CFR 50.59;b. Sufficient detailed information to totally support the reason for the change withoutbenefit of additional supplemental information;
: c. A detailed description of the equipment, components, and processes involvedand the interfaces with other plant systems;In lieu of inclusion in the Radioactive Effluents Release Report, this same information may besubmitted as part of the annual FSAR update.7-5VER 29 VEGP ODCMd. 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 toindividuals in the UNRESTRICTED AREA and to the general population thatdiffer from those previously estimated in the license applications andamendments thereto;f. A comparison of the predicted releases of radioactive materials, in liquid andgaseous effluents, to the actual releases for the period prior to when the changesare to be made;g. An estimate of the exposure to plant operating personnel as a result of thechange; andh. Documentation of the fact that the change was reviewed and found acceptable by the PRB.7-6VER 29 VEGP ODCM7.3 MONTHLY OPERATING REPORTThis ODCM establishes no requirements pertaining to the Monthly Operating Report.7.4 SPECIAL REPORTSSpecial reports shall be submitted to the Nuclear Regulatory Commission as requiredby 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 5.1.2.7-7VER 29 VEGP ODCMCHAPTER 8METEOROLOGICAL MODELSThe models presented in this chapter are those which were used to compute thespecific values of meteorology-related parameters that are referenced throughout thisODCM. 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 theODCMs 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 eitherat ground-level,
: elevated, or mixed-mode.
Facility release elevations for each gaseousrelease point are as indicated in Table 3-4.8.1.1 Ground-Level ReleasesRelative concentration calculations for ground-level
: releases, or for the ground-level portion of mixed-mode
: releases, shall be made as follows:(X/Q)-= 2.O325-K, rE nk (8.1)N r Xjk IUj Ywhere:(X/Q)G = the ground-level sector-averaged relative concentration for a given winddirection (sector) and distance (s/mi3).2.032 = (2/h)112 divided by the width in radians of a 22.50 sector, which is 0.3927radians.8 = the plume depletion factor for all radionuclides other than noble gases at adistance r shown in Figure 8-3. For noble gases, the depletion factor isunity. 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.
Kr = the terrain recirculation factor corresponding to a distance r, taken fromAppendix A of Reference 15.8-1VER 29 VEGP ODCMnjk = the number of hours that wind of wind speed class j is directed into thegiven sector during the time atmospheric stability category k existed.N = the total hours of valid meteorological data recorded throughout theperiod of interest for all sectors, wind speed classes, and stability categories.
u= 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 asfollows:zk ,.YZzk = the lesser q OR (8.2)ORF3(azk=zk the vertical standard deviation of the plume concentration distribution (m)for a given distance and stability category k as shown in Figure 8-1. Thestability category is determined by the vertical temperature gradientAT/Az (0C/100 m).r = 3.1416b = the maximum height of adjacent plant structure (55 m).8.1.2 Elevated ReleasesRelative dispersion calculations for elevated
: releases, or for the elevated portion ofmixed-mode
: releases, shall be made as follows:(X/Q)E _ 2.032KY ,k ujk _(N rO (8.3)8-2VER 29 VEGP ODCMwhere:(X/Q)E = the elevated release sector-averaged relative concentration for a givenwind direction (sector) and distance (s/m3).8k= the plume depletion factor for all radionuclides other than noble gases ata 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 anundepleted 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.
njk = the number of hours that wind of wind speed class j is directed into thegiven sector during the time atmospheric stability category k existed.uj= the wind speed (mid-point of wind speed class j) at the effective releaseheight h (m/s).h = the effective height of the release (m), which is calculated as follows:h = h,, + hpr -h, -c,. (8.4)hv= the height of the release point (m).ht= the maximum terrain height between the release point and the point ofinterest (m), from Table 8-1.hpr = the additional height due to plume rise (m) which is calculated as followsand limited by hpr(max):
1," 2/3 I/hPr=14 4c{UJ diI/ (8.5)((w'31 -JdSU )hpr(max)=
the lesser of: OR (8.6)ofj5O.R,-
-I/6d = the inside diameter of the vent (m).8-3VER 29 VEGP ODCMCv= the correction for low vent exit velocity (m), which is calculated asfollows:311.5W- 1.d for-W&deg; <1.5CV OR (8.7)cv={ u)for Wo 1. 5UFm = the momentum flux parameter (m4/s2), which is calculated as follows:Fm =WO ).d2  (8.8)S 2)S = the stability parameter:
= 8.75 x 10-4s-2 for -0.5 < 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 > 4.0All other symbols are as previously defined in Section 8.1.1.8.1.3 Mixed-Mode ReleasesRelative dispersion calculations for mixed-mode releases shall be made as follows:(X/Q)A, = (I -E) .(X/Q)E + E .(X/Q)G (8.9)where:(X/Q)M = the mixed-mode release sector-averaged relative concentration for agiven wind direction (sector) and distance (s/mi3).E = the fraction of hours during which releases are considered as ground-level releases, calculated as follows:8-4VER 29 VEGP ODCM1.0 for W <1.0uj0.3-0.06. w wo 5.0for 1.5<) u0 for W0 > 5.0UjAll other symbols are as previously defined.8-5VER 29 VEGP ODCM8.2 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 atground-level,
: elevated, or mixed-mode.
Facility release elevations for each gaseousrelease points are as indicated in Table 3-4.8.2.1 Ground-Level ReleasesRelative deposition calculations for ground-level
: releases, or for the ground-level portionof mixed-mode
: releases, shall be made as follows:(DQ) = 2.55D, KNr kwhere:(D/Q)G = the ground-level sector-averaged relative deposition for a given winddirection (sector) and distance (m-2).2.55 = the inverse of the number of radians in a 22.5' sector [= (2 7T /16)-1].Dg = the deposition rate at distance r, taken from Figure 8-7 for ground-level releases (m-1).nk= the number of hours in which the wind is directed into the sector ofinterest, and during which stability category k exists.All other symbols are as defined previously in Section 8.1.8.2.2 Elevated ReleasesRelative deposition calculations for elevated
: releases, or for the elevated portion ofmixed-mode
: releases, shall be made as follows:(D/Q)F = 2.55K, Z (n1 Dk (8.12)Nr kwhere:(D/Q)E = the elevated-plume sector-averaged relative deposition for a given winddirection (sector) and distance (m-2).Dek = the elevated plume deposition rate at distance r, taken from Figure 8-8,Figure 8-9, or Figure 8-10, as appropriate to the plume effective releaseheight h defined in Section 8.1.2, for stability class k (m-1).All other symbols are as defined previously.
8-6VER 29 VEGP ODCM8.2.3 Mixed-Mode ReleasesRelative deposition calculations for mixed-mode releases shall be made as follows:(D/Q)0 = (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 givenwind 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 FACTORSThese factors are not required in effluent dose calculations for VEGP.8-7VER 29 VEGP ODCMTable 8-1. Terrain Elevation Above Plant Site GradeDist. NENNESNE ENE EWESE TSW W SNSSWW NNW(m) 1500 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 3.51,000 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 6.81,500 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 7.32,000 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 7.32,500 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 7.33,000 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 7.33,500 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 7.34,000 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 7.35,000 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 7.36,000 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 7.37,000 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 7.38,000 0.0 0.0 21.1 13.9 0.0 0.0 11.8 0.0 14.6 4.7 26.8 18.6 7.3 12.2 16.9 7.39,000 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 7.310,000 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 7.312,000 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 7.314,000 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 7.316,000 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 7.3Data in this table are obtained from Reference 11.8-8VER 29 VEGPODCMI UI.: ".'.-f--' I A' II II-1,N0V -/0CI I-01 E "1-01L., 00 1 4010'00.11 10PLUME TRAVEL DISTANCE (KILOMETERS) 100Range of Vertical Range of VerticalCategory Temperature Gradient Temperature Gradient(0C/100 m) (&deg;F/100 ft)A AT/AZ < -1.9 AT/AZ < -1.0B -1.9 s AT/AZ < -1.7 -1.0 s AT/AZ < -0.9C -1.7 s AT/AZ < -1.5 -0.9 s AT/AZ < -0.8D -1.5 s AT/AZ < -0.5 -0.8 s AT/AZ < -0.3E -0.5 s AT/AZ < 1.5 -0.3 s AT/AZ < 0.8F 1.5 s AT/AZ < 4.0 0.8 s AT/AZ < 2.2G 4.0 s AT/AZ 2.2 s AT/AZmTh caranh is reproduced from Reference 5(Figure 1)5Figure 8-1. Vertical Standard Deviation of Material in a Plume (crz)8-9VER 29 VEGP ODCM8-10VER 29 VEGP ODCMThis figure intentionally left blank.Refer to the definition for Kr (terrain recirculation factor) insection 8.1.1 for applicable plant data.Figure 8-2. Terrain Recirculation Factor (Kr)8-11VER 29 VEGPODCMzw6t=a:1.00.90.70.60.40.20.10.11.0 1 0PLUME TRAVEL DISTANCE (KILOMETERS) 100.0 200.0This graph is reproduced from Reference 5 (Figure 2).Figure 8-3. Plume Depletion Effect for Ground Level Releases8-12VER 29 VEGPODCM1.00.1I&#xa3;0.7I ,o,c 0.10.4CU. 0".30.20.10.11.0 10.0PLUMETRAVEL DISTANCE (KILOMETERS) 100.0' IOQ.0This graph is reproduced from Reference 5 {Figure 3)Fiaure 8-4. Plume Depletion Effect for 30-Meter Releases8-13VER 29 VEGPODCM1.00.8r-: -:::1:..STABLE-r-t-- J -&#xfd; EUTR.A.L' 0.8'g- 0.7z o.e0.20.30.11.0 10.0PLUMETRAVEL DISTANCE (KILOMETERSJ This graph isreproduced fromReference 5(Figure 4).8-14VER 29 VEGPODCM100.0 200.0Figure 8-5. Plume Depletion Effect for 60-Meter Releases8-15VER 29 VEGPODCM1.0S.,-IiV 0.80.7iZ 0.1CIt 0.5Q= OAac0.3--o-0 NEUTRAL CDJ _UNSTABLESTABLE CE.F,G) lA.B.C)IR L I I. ) I I(FRACTI{N
-EIIJN i 1.fi L I,,IG.20.10.11.0 10.0PLUME.TRAVEL DISTANCE CKILOMETERSJ 100.0 200.0This graph is reproduced from Reference 5 (Figure 5).8-16VER 29 VEGPODCM---I ~-*r--~I IIlo-wa:w!:V-- uI II I l IIIa:zo to-illA.WCwa:Io-70.11.0 10.0PLUME TRAVEL DISTANCE (KILOMETERS) 100.0 200.0This graph is reproduced from Reference 5 (Figure 6)Figure 8-6. Plume Depletion Effect for 100-Meter Releases8-17VER 29 VEGP ODCMFigure 8-7. Relative Deposition for Ground-Level Releases8-18VER 29 VEGPODCM1o-4 " t' I I I 11ic -j IH' I ... I I I :Ea: '"' I NEUTRALz NEUTRALUME thi g a-5 is rc 7..en 8 e D I fr0MeR0 ' i i:a: JrAL(EFG10-6 -"l I I : :: :F:0.1 1.0 10.0 100.0 200.0PLUME TRAVEL DISTANCE (KILOM4ETERS)
This graph is reproduced from Reference 5 (Figure 7).Figure 8-8. Relative Deposition for 30-Meter Releases8-19VER 29 VEGPODCMIo-5wwa::.wa:z Io-6Io-7.,STABLE EFGi! IFLJ I0.11.0I0.Ot100.0- 200.0PLUME TRAVEL DISTANCE (KILOMETERS)
This graph is reproduced from Reference 5 [Figure 8).8-20VER 29 VEGPODCMI-igure b-9. Relative IUeposition tor (bu-Meter Releases8-21VER 29 VEGPODCM10lo-s%Va:C(zIIIi--wCwa:10-6IIIUNSTABLE (A,B C1if wSTABLE (E,FG)PLUME TRAVEL DISTANCE (KILOMETERS) 10-8This graph is reproduced from Reference 5 (Figure 9).Figure 8-10. Relative Deposition for 100-Meter (or Greater)
Releases8-22VER 29 VEGP ODCMCHAPTER 9METHODS AND PARAMETERS FOR CALCULATION OFGASEOUS EFFLUENT PATHWAY DOSE FACTORS, Raipj9.1 INHALATION PATHWAY FACTORFor the inhalation
: pathway, Raipj in (mrem/y) per ( iCi/m3) is calculated as follows(Reference 1, Section 5.3.1.1):
Raipj = K1 * (BR)a .(DFA)a~j (9.1)where:K1  = the units conversion factor: 106 pCi/ltCi.
(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 mrem/pCi, from Table 9-7 through Table 9-10.9-1VER 29 VEGP ODCM9.2 GROUND PLANE PATHWAY FACTORFor the ground plane external exposure
: pathway, Raipj in (m2.mrem/y) per (&#xfd;tCi/s)is calculated as follows (Reference 1, Section 5.3.1.2):
Rapj= K, .-K2 .(SHF). (DFG j1-e') (9.2)where:K1  = the units conversion factor: 106 pCi/pCi.K2  = the units conversion factor: 8760 h/y.(SHF) = the shielding factor due to structure (dimensionless).
The valueused for (SHF) is 0.7, from (Reference 3, Table E-15).(DFG)ij = the ground plane dose factor for radionuclide i and organ j, in(mrem/h) per (pCi/m2), from Table 9-15. Dose factors are thesame for all age groups, and those for the total body also apply toall organs other than skin.= the radioactive decay constant for radionuclide i, in s-1. Values ofXi used in effluent calculations should be based on decay datafrom a recognized and current source, such as Reference 20.t = the exposure time, in s. The value used fort is 4.73 x 108 s (= 15y), from (Reference 1, Section 5.3.1.2).
9-2VER 29 VEGP ODCM9.3 GARDEN VEGETATION PATHWAY FACTORFor radionuclides other than tritium in the garden vegetation consumption
: pathway, Rapj in (m2.mrem/y) per (pICi/s) is calculated as follows (Reference 1,Section 5.3.1.5):
R,,,pj = K, .MA (DFLT),,
(UfLe-' + e (9.3)where:K1  = the units conversion factor: 106 pCi/lCi.r = the fraction of deposited activity retained on the edible parts ofgarden vegetation (dimensionless).
The value used for r is 1.0for radioiodines and 0.2 for particulates, from (Reference 3,Table E-1).Yv the areal density (agricultural productivity) of growing leafygarden vegetation, in kg/M2, from Table 9-1.= the radioactive decay constant for radionuclide i, in s-1. Valuesof Xq used in effluent calculations should be based on decaydata from a recognized and current source, such as Reference 20.x = the rate constant for removal of activity on leaf and plantsurfaces by weathering, in s-1, from Table 9-1.(DFL)aij
-the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mrem/pCi, from Table 9-11 through Table 9-14.UaL the consumption rate of fresh leafy garden vegetation by areceptor in age group a, in kg/y, from Table 9-5.Uas = the consumption rate of stored garden vegetation by a receptorin age group a, in kg/y, 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.tL = the average time between harvest of fresh leafy garden9-3VER 29 VEGP ODCMvegetation and its consumption, in s, from Table 9-1.thv = the average time between harvest of stored garden vegetation and its consumption, in s, from Table 9-1.For tritium in the garden vegetation consumption
: pathway, Raipj in (mrem/y) per(pLCi/i3) is calculated as follows (Reference 1, Section 5.3.1.5),
based on theconcentration in air rather than deposition onto the ground:(0.5,)Ra,rj = K, .K3* (DFL),I -*(U,.flI
+ Uasf, )O. 75. -- 1 (9.4)~Hwhere:K3 = = the units conversion factor: 103 g/kg.H = = the absolute humidity of atmospheric air, in g/m3, 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.9-4VER 29 VEGP ODCMTable 9-1.Miscellaneous Parameters for the Garden Vegetation PathwayThe 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 Yv 2.0 kg/M2  Ref. 3, Table E-15Xw 5.73 x 10-7s1  Ref. 1, page 33(14-day half-life) fL 1.0 Ref. 1, page 36f9 0.76 Ref. 1, page 33tL 8.6 x 104S Ref. 3, Table E-15(1 day)thy 5.18 x 106 S Ref. 3, Table E-15(60 days)H 8 g/m3Ref. 39-5VER 29 VEGP ODCM9.4 GRASS-COW-MILK PATHWAY FACTORFor radionuclides other than tritium in the grass-cow-milk
: pathway, Raipj in(m2.mrem/y) per (gCi/s) is calculated as follows (Reference 1, Section 5.3.1.3):
R,,,m = K, r .Q p. .U,,p .F,,, .(DFL),,,j
.&#xfd;fpf, + (I*fm -' (9.6)Y Y(+) .,where:K1  = the units conversion factor: 106 pCi/gCi.r = the fraction of deposited activity retained on the edible parts ofvegetation (dimensionless).
The value used for r is 1.0 forradioiodines and 0.2 for particulates, from (Reference 3, TableE-1).x = the radioactive decay constant for radionuclide i, in s-1. Valuesof Xj used in effluent calculations should be based on decaydata from a recognized and current source, such asReference 20.w = the rate constant for removal of activity on leaf and plantsurfaces by weathering, in s-1, from Table 9-2.QF = 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 L/y, from Table 9-5.Fmi the stable element transfer coefficient applicable to radionuclide i, for cow's milk, in d/L, from Table 9-6.(DFL)aij
= the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mrem/pCi, from Table 9-11 through Table 9-14.fp the fraction of the year that the cow is on pasture(dimensionless),
from Table 9-2.fs the fraction of the cow's feed that is pasture grass while the cowis on pasture (dimensionless),
from Table 9-2.Y1 = the areal density (agricultural productivity) of growing pasturefeed grass, in kg/mi, from Table 9-2.9-6VER 29 VEGP ODCMY = the areal density (agricultural productivity) of growing storedfeed, in kg/M2, from Table 9-2.thin = the transport time from harvest of stored feed to its consumption by the cow, in s, from Table 9-2.tf = the transport time from consumption of feed by the cow, toconsumption of milk by the receptor, in s, from Table 9-2.For tritium in the grass-cow-milk
: pathway, Raipj in (mrem/y) per (ltCi/m3) iscalculated as follows (Reference 1, Section 5.3.1.5),
based on the concentration in air rather than deposition onto the ground:R,,Pi=K, K3 .QF .Up ' F,, .(DFL)ao .0. 75.1 (05) (9.6)where:K3 = the units conversion factor: 103 g/kg.H = the absolute humidity of atmospheric air, in g/m3,from Table 9-2.0.75 = the fraction of the mass of total vegetation that iswater (dimensionless).
0.5 = the ratio of the specific activity of tritium invegetation water to that in atmospheric water(dimensionless).
and other parameters are as defined above.9-7VER 29 VEGP ODCMTable 9-2.Miscellaneous Parameters for the Grass-Cow-Milk PathwayThe following parameter values are for use in calculating only. The terms themselves are defined in section 9.4.Raipj for the grass-cow-milk pathwayParameter Value Reference 5.73 x 10-7 s-1 Ref. 1, page 33(14-day half-life)
QF 50 kg/d Ref. 3, Table E-3fp 1.0 Ref. 1, page 33fs 1.0 Ref. 1, page 33YP 0.7 kg/M2  Ref. 3, Table E-15YS 2.0 kg/M2  Ref. 3, Table E-15thin 7.78 x 106 S Ref. 3, Table E-15(90 days)tf 1.73 x 10s Ref. 3, Table E-15(2 days)H 8 g/m3Ref. 39-8VER 29 VEGP ODCM9.5 GRASS-GOAT-MILK PATHWAY FACTORFor radionuclides other than tritium in the grass-goat-milk
: pathway, Rapj in(m2.mrem/y) per ([tCi/s) is calculated as follows (Reference 1, Section 5.3.1.3):
Fff(1-f~fj)-''''
Ra=pi K, + r F .F,,, (DFLL. i + (Pf + (97)where:K1  = the units conversion factor: 106 pCi/pCi.r = the fraction of deposited activity retained on the edible parts ofvegetation (dimensionless).
The value used for r is 1.0 forradioiodines and 0.2 for particulates, from (Reference 3, TableE-1).= the radioactive decay constant for radionuclide i, in s-1.Valuesof Xi used in effluent calculations should be based on decaydata from a recognized and current source, such as Reference 20.the rate constant for removal of activity on leaf and plantsurfaces by weathering, in s-1, from Table 9-3.QF = 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 L/y, from Table 9-5.Fmi = the stable element transfer coefficient applicable to radionuclide i, for goat's milk, in d/L, from Table 9-6.(DFL)aij
= the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mrem/pCi, 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.f, = the fraction of the goat's feed that is pasture grass while thegoat is on pasture (dimensionless),
from Table 9-3.Yp = the areal density (agricultural productivity) of growing pasturefeed grass, in kg/m , from Table 9-3.9-9VER 29 VEGP ODCMYs = the areal density (agricultural productivity) of growing storedfeed, in kg/M2, from Table 9-3.thm = the transport time from harvest of stored feed to its consumption by the goat, in s, from Table 9-3.tf = the transport time from consumption of feed by the goat, toconsumption of milk by the receptor, in s, from Table 9-3.For tritium in the grass-goat-milk
: pathway, Raipj in (mrem/y) per (AjCi/m3) iscalculated as follows (Reference 1, Section 5.3.1.5),
based on the concentration in air rather than deposition onto the ground:Ra,pj = K.
* K3 .Q, .'U .Fm, .(DFL),j .0. 75. (05) (9.8)where:K3 = the units conversion factor: 103 g/kg.H = the absolute humidity of atmospheric air, in g/m3, from Table9-3.0.75 = 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 tothat in atmospheric water (dimensionless).
and other parameters are as defined above.9-10VER 29 VEGP ODCMTable 9-3.Miscellaneous Parameters for the Grass-Goat-Milk PathwayThe following parameter values are for use in calculating Raipj for the grass-goat-milk pathwayonly. The terms themselves are defined in section 9-5.Parameter Value Reference 5.73 x 107 s-I Ref. 1, page 33(14-day half-life)
QF 6 kg/d Ref. 3, Table E-3fp 1.0 Ref. 1, page 33fs 1.0 Ref. 1, page 33Yp 0.7 kg/M2  Ref. 3, Table E-15Ys 2.0 kg/M2  Ref. 3, Table E-15thin 7.78 x 106 S Ref. 3, Table E-15(90 days)tf 1.73 x 105 s Ref. 3, Table E-15(2 days)H 8 g/m3Ref. 39-11VER 29 VEGP ODCM9.6 GRASS-COW-MEAT PATHWAY FACTORFor radionuclides other than tritium in the grass-cow-meat
: pathway, Raipj in(m2-mrem/y) per (.Ci/s) is calculated as follows (Reference 1, Section 5.3.1.4):
RaTV, r .FK1.QL -,f,)*Uap
* 1 je- + (9.9)+ L11r:where:K1 = the units conversion factor: 106 pCi/pCi.r = the fraction of deposited activity retained on the edible parts ofvegetation (dimensionless).
The value used for r is 1.0 forradioiodines and 0.2 for particulates, from (Reference 3, TableE-1).i= the radioactive decay constant for radionuclide i, in s-1.Values of ki used in effluent calculations should be based ondecay data from a recognized and current source, such asReference 20.x= the rate constant for removal of activity on leaf and plantsurfaces by weathering, in s-1, from Table 9-4.QF = 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, inkg/y, from Table 9-5.F,= the stable element transfer coefficient applicable toradionuclide i, for meat, in d/kg, from Table 9-6.(DFL)aij
= the ingestion dose factor for receptor age group a,radionuclide i, and organ j, in mrem/pCi, from Table 9-11through Table 9-14.fp = the fraction of the year that the cow is on pasture(dimensionless),
from Table 9-4.fs = the fraction of the cow's feed that is pasture grass while thecow is on pasture (dimensionless),
from Table 9-4.9-12VER 29 VEGP ODCMYp = the areal density (agricultural productivity) of growing pasturefeed grass, in kg/mr, from Table 9-4.Ys = the areal density (agricultural productivity) of growing storedfeed, in kg/M2, from Table 9-4.thrn = the transport time from harvest of stored feed to itsconsumption by the cow, in s, from Table 9-4.tf = the transport time from consumption of feed by the cow, toconsumption of meat by the receptor, in s, from Table 9-4.For tritium in the grass-cow-meat
: pathway, Raapj in (mrem/y) per (lLCi/m3) iscalculated as follows (Reference 1, Section 5.3.1.4),
based on the concentration in air rather than deposition onto the ground:Ra,j =K, .K3 "QF U,,p .Ff .(DFL), (0.75.( 59.10)where:K3 = the units conversion factor: 103 g/kg.H = the absolute humidity of atmospheric air, in g/m3, from Table9-4.0.75 = 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 tothat in atmospheric water (dimensionless).
and other parameters are as defined above.9-13VER 29 VEGP ODCMTable 9-4.Miscellaneous Parameters for the Grass-Cow-Meat PathwayThe following parameter values are for use in calculating Rapj for the grass-cow-meat pathwayonly. The terms themselves are defined in section 9-6.Parameter Value Reference xw 5.73 x 10-7 s-1 Ref. 1, page 33(14-day half-life)
QF 50 kg/d Ref. 3, Table E-3fp 1.0 Ref. 1, page 33f. 1.0 Ref. 1, page 33Yp 0.7 kg/M2  Ref. 3, Table E-15YS 2.0 kg/M2  Ref. 3, Table E-15thin 7.78 x 106 s Ref. 3, Table E-15(90 days)tf 1.73 x106 s Ref. 3, Table E-15(20 days)H 8 g/m3Ref. 39-14VER 29 VEGP ODCMTable 9-5. Individual Usage FactorsReceptor Age GroupUsage FactorInfant Child Teenager AdultMilk Consumption Rate, Uap 330 330 400 310(L/y)Meat Consumption Rate, Uap 0 41 65 110(kg/y)Fresh Leafy Garden Vegetation 0 26 42 64Consumption Rate, UaL(kg/y)Stored Garden Vegetation 0 520 630 520Consumption Rate, Uas(kg/y)Breathing Rate, (BR), 1400 3700 8000 8000(m3/y) I IAll values are from Reference 3, Table E-5.9-15VER 29 VEGP ODCMTable 9-6.Stable Element Transfer DataCow Milk Goat Milk MeatElementFm (d/L)" Fm (d/L)&#xf7; Ff (d/kg)*H 1.0 E-02 1.7 E-01 1.2 E-02C 1.2 E-02 1.0 E-01 3.1 E-02Na 4.0 E-02 4.0 E-02 3.0 E-02P 2.5 E-02 2.5 E-01 4.6 E-02Cr 2.2 E-03 2.2 E-03 2.4 E-03Mn 2.5 E-04 2.5 E-04 8.0 E-04Fe 1.2 E-03 1.3 E-04 4.0 E-02Co 1.0 E-03 1.0 E-03 1.3 E-02Ni 6.7 E-03 6.7 E-03 5.3 E-02Cu 1.4 E-02 1.3 E-02 8.0 E-03Zn 3.9 E-02 3.9 E-02 3.0 E-02Br 5.0 E-02 5.0 E-02 2.6 E-02Rb 3.0 E-02 3.0 E-02 3.1 E-02Sr 8.0 E-04 1.4 E-02 6.0 E-04Y 1.0 E-05 1.0 E-05 4.6 E-03Zr 5.0 E-06 5.0 E-06 3.4 E-02Nb 2.5 E-03 2.5 E-03 2.8 E-01Mo 7.5 E-03 7.5 E-03 8.0 E-03Tc 2.5 E-02 2.5 E-02 4.0 E-01Ru 1.0 E-06 1.0 E-06 4.0 E-01Rh 1.0 E-02 1.0 E-02 1.5 E-03Ag 5.0 E-02 5.0 E-02 1.7 E-02Sb 1.5 E-03 1.5 E-03 4.0 E-03Te 1.0 E-03 1.0 E-03 7.7 E-021 6.0 E-03 6.0 E-02 2.9 E-03Cs 1.2 E-02 3.0 E-01 4.0 E-03Ba 4.0 E-04 4.0 E-04 3.2 E-03La 5.0 E-06 5.0 E-06 2.0 E-04Ce 1.0 E-04 1.0 E-04 1.2 E-03Pr 5.0 E-06 5.0 E-06 4.7 E-03Nd 5.0 E-06 5.0 E-06 3.3 E-03W 5.0 E-04 5.0 E-04 1.3 E-03Np 5.0 E-06 5.0 E-06 2.0 E-04* -Values from Reference 3for Br and Sb.(Table E-1) except as follows:
Reference 2 (Table C-5)+ -Values from Reference 3, Table E-2 for H, C, P, Fe, Cu, Sr, I, and Cs in goatmilk, 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.9-16VER 29 VEGP ODCMTable 9-7. Inhalation Dose Factors for the Infant Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLIH-3 No Data 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06P-32 1.45E-03 8.03E-05 5.53E-05 No Data No Data No Data 1.15E-05Cr-51 No Data No Data 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07Mn-54 No Data 1.81E-05 3.56E-06 No Data 3.56E-06 7.14E-04 5.04E-06Mn-56 No Data 1.1OE-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-05Fe-55 1.41 E-05 8.39E-06 2.38E-06 No Data No Data 6.21 E-05 7.82E-07Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05Co-58 No Data 8.71 E-07 1.30E-06 No Data No Data 5.55E-04 7.95E-06Co-60 No Data 5.73E-06 8.41E-06 No Data No Data 3.22E-03 2.28E-05Ni-63 2.42E-04 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06Ni-65 1.71E-09 2.03E-10 8.79E-11 No Data No Data 5.80E-06 3.58E-05Cu-64 No Data 1.34E-09 5.53E-10 No Data 2.84E-09 6.64E-06 1.07E-05Zn-65 1.38E-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05Zn-69 3.85E-11 6.91E-11 5.13E-12 No Data 2.87E-11 1.05E-06 9.44E-06Br-83 No Data No Data 2.72E-07 No Data No Data No Data No DataBr-84 No Data No Data 2.86E-07 No Data No Data No Data No DataBr-85 No Data No Data 1.46E-08 No Data No Data No Data No DataRb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07Rb-89 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.87E-08Sr-89 2.84E-04 No Data 8.15E-06 No Data No Data 1.45E-03 4.57E-05Sr-90 2.92E-02 No Data 1.85E-03 No Data No Data 8.03E-03 9.36E-05Sr-91 6.83E-08 No Data 2.47E-09 No Data No Data 3.76E-05 5.24E-05All values are in (mrem/pCi inhaled).
They are obtained from Reference 3(Table E-10). Neither Reference 2 nor Reference 3 contains data for Rh-105,Sb-124, or Sb-125.9-17VER 29 VEGP ODCM9-18VER 29 VEGP ODCMTable 9-7 (contd).
Inhalation Dose Factors for the Infant Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLISr-92 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.OOE-04Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05Y-91m 2.91E-10 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06Y-91Y-92Y-934.20E-041.17E-081.07E-07No DataNo DataNo Data1.12E-053.29E-102.91 E-09No DataNo DataNo DataNo DataNo DataNo Data1.75E-031.75E-055.46E-055.02E-059.04E-051.19E-04Zr-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05Zr-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.OOE-04Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05Tc-99m 9.98E-13 2.06E-12 2.66E-11 No Data 2.22E-11 5.79E-07 1.45E-06Tc-101 4.65E-14 5.88E-14 5.80E-13 No Data 6.99E-13 4.17E-07 6.03E-07Ru-103 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05Ru-105 8.74E-10 No Data 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05Ru-106 6.20E-05 No Data 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04Rh-105 No Data No Data No Data No Data No Data No Data No DataAg-110m 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05Sb-124 No Data No Data No Data No Data No Data No Data No DataSb-125 No Data No Data No Data No Data No Data No Data No DataTe-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No Data 3.19E-04 9.22E-06Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05Te-131rm 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-069-19VER 29 VEGP ODCMTable 9-7 (contd).
Inhalation Dose Factors for the Infant Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLITe-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-051-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 No Data 1.42E-061-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 No Data 7.56E-071-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 No Data 1.36E-061-133 9.46E-06 1.37E-05 4.OOE-06 2.54E-03 1.60E-05 No Data 1.54E-061-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 No Data 9.21E-071-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 No Data 1.31E-06Cs-134 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-04 5.69E-05 9.53E-07Cs-136 3.45E-05 9.61E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.02E-06Cs-137 3.92E-04 4.37E-04 3.25E-05 No Data 1.23E-04 5.09E-05 9.53E-07Cs-138 3.61E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.26E-07Ba-139 1.06E-09 7.03E-13 3.07E-11 No Data 4.23E-13 4.25E-06 3.64E-05Ba-140 4.OOE-05 4.OOE-08 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05Ba-141 1.12E-10 7.70E-14 3.55E-12 No Data 4.64E-14 2.12E-06 3.39E-06Ba-142 2.84E-11 2.36E-14 1.40E-12 No Data 1.36E-14 1.11E-06 4.95E-07La-140 3.61E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-04 6.06E-05La-142 7.36E-10 2.69E-10 6.46E-11 No Data No Data 5.87E-06 4.25E-05Ce-141 1.98E-05 1.19E-05 1.42E-06 No Data 3.75E-06 3.69E-04 1.54E-05Ce-143 2.09E-07 1.38E-07 1.58E-08 No Data 4.03E-08 8.30E-05 3.55E-05Ce-144 2.28E-03 8.65E-04 1.26E-04 No Data 3.84E-04 7.03E-03 1.06E-04Pr-143 1.OOE-05 3.74E-06 4.99E-07 No Data 1.41E-06 3.09E-04 2.66E-05Pr-144 3.42E-11 1.32E-11 1.72E-12 No Data 4.80E-12 1.15E-06 3.06E-06Nd-147 5.67E-06 5.81E-06 3.57E-07 No Data 2.25E-06 2.30E-04 2.23E-05W-187 9.26E-09 6.44E-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05Np-239 2.65E-07 2.37E-08 1.34E-08 No Data 4.73E-08 4.25E-05 1.78E-059-20VER 29 VEGP ODCMTable 9-8.Inhalation Dose Factors for the Child Age GroupNuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLIH-3 No Data 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06P-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05Cr-51 No Data No Data 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71E-06 4.26E-04 6.19E-06Mn-56 No Data 4.48E-10 8.43E-11 No Data 4.52E-10 3.55E-06 3.33E-05Fe-55 1.28E-05 6.80E-06 2.1OE-06 No Data No Data 3.OOE-05 7.75E-07Fe-59 5.59E-06 9.04E-06 4.51 E-06 No Data No Data 3.43E-04 1.91 E-05Co-58 No Data 4.79E-07 8.55E-07 No Data No Data 2.99E-04 9.29E-06Co-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91E-03 2.60E-05Ni-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data 7.43E-05 1.71E-06Ni-65 8.08E-10 7.99E-11 4.44E-11 No Data No Data 2.21 E-06 2.27E-05Cu-64 No Data 5.39E-10 2.90E-10 No Data 1.63E-09 2.59E-06 9.92E-06Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41 E-06Zn-69 1.81E-11 2.61E-11 2.41E-12 No Data 1.58E-11 3.84E-07 2.75E-06Br-83 No Data No Data 1.28E-07 No Data No Data No Data No DataBr-84 No Data No Data 1.48E-07 No Data No Data No Data No DataBr-85 No Data No Data 6.84E-09 No Data No Data No Data No DataRb-86 No Data 5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09Rb-89 No Data 9.33E-08 7.83E-08 No Data No Data No Data 5.11 E-1 0Sr-89 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 4.52E-05Sr-90 2.73E-02 No Data 1.74E-03 No Data No Data 3.99E-03 9.28E-05Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05All 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-1 24, or Sb-1 25.9-21VER 29 VEGP ODCM9-22VER 29 VEGP ODCMTable 9-8 (contd).Inhalation Dose Factors for the Child Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLISr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05Y-90 1.11E-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05Y-91m 1.37E-10 No Data 4.98E-12 No Data No Data 7.60E-07 4.64E-07Y-91 2.47E-04 No Data 6.59E-06 No Data No Data 7.1OE-04 4.97E-05Y-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 6.46E-05Y-93 5.04E-08 No Data 1.38E-09 No Data No Data 2.01 E-05 1.05E-04Zr-95 5.13E-05 1.13E-05 1.OOE-05 No Data 1.61E-05 6.03E-04 1.65E-05Zr-97 5.07E-08 7.34E-09 4.32E-09 No Data 1.05E-08 3.06E-05 9.49E-05Nb-95 6.35E-06 2.48E-06 1.77E-06 No Data 2.33E-06 1.66E-04 11.00E-05 Mo-99 No Data 4.66E-08 1.15E-08 No Data 1.06E-07 3.66E-05 3.42E-05Tc-99m 4.81E-13 9.41E-13 1.56E-11 No Data 1.37E-11 2.57E-07 1.30E-06Tc-101 2.19E-14 2.30E-14 2.91E-13 No Data 3.92E-13 1.58E-07 4.41E-09Ru-103 7.55E-07 No Data 2.90E-07 No Data 1.90E-06 1.79E-04 1.21E-05Ru-105 4.13E-10 No Data 1.50E-10 No Data 3.63E-10 4.30E-06 2.69E-05Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.16E-04Rh-105 No Data No Data No Data No Data No Data No Data No DataAg-1 10m 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-06 1.48E-03 2.71 E-05Sb-124 No Data No Data No Data No Data No Data No Data No DataSb-125 No Data No Data No Data No Data No Data No Data No DataTe-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-04 9.13E-06Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-079-23VER 29 VEGP ODCMTable 9-8 (contd).
Inhalation Dose Factors for the Child Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLITe-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-051-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 No Data 1.38E-061-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 No Data 7.68E-071-132 5.72E-07 1.1OE-06 5.07E-07 5.23E-05 1.69E-06 No Data 8.65E-071-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 No Data 1.48E-061-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2.58E-071-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 No Data 1.20E-06Cs-134 1.76E-04 2.74E-04 6.07E-05 No Data 8.93E-05 3.27E-05 1.04E-06Cs-136 1.76E-05 4.62E-05 3.14E-05 No Data 2.58E-05 3.93E-06 1.13E-06Cs-137 2.45E-04 2.23E-04 3.47E-05 No Data 7.63E-05 2.81E-05 9.78E-07Cs-138 1.71E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08Ba-139 4.98E-10 2.66E-13 1.45E-11 No Data 2.33E-13 1.56E-06 1.56E-05Ba-140 2.OOE-05 1.75E-08 1.17E-06 No Data 5.71E-09 4.71E-04 2.75E-05Ba-141 5.29E-11 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E-08Ba-142 1.35E-11 9.73E-15 7.54E-13 No Data 7.87E-15 4.44E-07 7.41 E-10La-140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.1OE-05La-142 3.50E-10 1.11E-10 3.49E-11 No Data No Data 2.35E-06 2.05E-05Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data 2.31E-06 1.47E-04 1.53E-05Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05Ce-144 1.83E-03 5.72E-04 9.77E-05 No Data 3.17E-04 3.23E-03 1.05E-04Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.11E-07 1.17E-04 2.63E-05Pr-144 1.61E-11 4.99E-12 8.10E-13 No Data 2.64E-12 4.23E-07 5.32E-08Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E-06 8.87E-05 2.22E-05W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Data 1.11E-05 2.46E-05Np-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-059-24VER 29 VEGP ODCMTable 9-9. Inhalation Dose Factors for the Teenager Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLIH-3 No Data 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06P-32 2.36E-04 1.37E-08 8.95E-06 No Data No Data No Data 1.16E-05Cr-51 No Data No Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07Mn-54 No Data 6.39E-06 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06Mn-56 No Data 2.12E-10 3.15E-11 No Data 2.24E-10 1.90E-06 7.18E-06Fe-55 4.18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91 E-04 2.23E-05Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.68E-04 1.1 9E-05Co-60 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05Ni-63 7.25E-05 5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06Ni-65 2.73E-10 3.66E-11 1.59E-11 No Data No Data 1.17E-06 4.59E-06Cu-64 No Data 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.68E-06Zn-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06Zn-69 6.04E-12 1.15E-11 8.07E-13 No Data 7.53E-12 1.98E-07 3.56E-08Br-83 No Data No Data 4.30E-08 No Data No Data No Data No DataBr-84 No Data No Data 5.41 E-08 No Data No Data No Data No DataBr-85 No Data No Data 2.29E-09 No Data No Data No Data No DataRb-86 No Data 2.38E-05 1.05E-05 No Data No Data No Data 2.21 E-06Rb-88 No Data 6.82E-08 3.40E-08 No Data No Data No Data 3.65E-15Rb-89 No Data 4.40E-08 2.91E-08 No Data No Data No Data 4.22E-17Sr-89 5.43E-05 No Data 1.56E-06 No Data No Data 3.02E-04 4.64E-05Sr-90 1.35E-02 No Data 8.35E-04 No Data No Data 2.06E-03 9.56E-05Sr-91 1.1OE-08 No Data 4.39E-10 No Data No Data 7.59E-06 3.24E-05All values are in (mrem/pCi inhaled).
They are obtained from Reference 3(Table E-8). Neither Reference 2 nor Reference 3 contains data for Rh-1 05,Sb-124, or Sb-125.9-25VER 29 VEGP ODCMTable 9-9 (contd).
Inhalation Dose Factors for the Teenager Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLISr-92 1.19E-09 No Data 5.08E- 11 No Data No Data 3.43E-06 1.49E-05Y-90 3.73E-07 No Data 1.OOE-08 No Data No Data 3.66E-05 6.99E-05Y-91m 4.63E-11 No Data 1.77E-12 No Data No Data 4.OOE-07 3.77E-09Y-91 8.26E-05 No Data 2.21E-06 No Data No Data 3.67E-04 5.11E-05Y-92 1.84E-09 No Data 5.36E-1 1 No Data No Data 3.35E-06 2.06E-05Y-93 1.69E-08 No Data 4.65E-10 No Data No Data 1.04E-05 7.24E-05Zr-95 1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05Zr-97 1.72E-08 3.40E-09 1.57E-09 No Data 5.15E-09 1.62E-05 7.88E-05Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21E-05Mo-99 No Data 2.11E-08 4.03E-09 No Data 5.14E-08 1.92E-05 3.36E-05Tc-99m 1.73E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-16Ru-103 2.63E-07 No Data 1.12E-07 No Data 9.29E-07 9.79E-05 1.36E-05Ru-105 1.40E-10 No Data 5.42E-11 No Data 1.76E-10 2.27E-06 1.13E-05Ru-106 1.23E-05 No Data 1.55E-06 No Data 2.38E-05 2.01E-03 1.20E-04Rh-105 No Data No Data No Data No Data No Data No Data No DataAg-110m 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41E-05Sb-124 No Data No Data No Data No Data No Data No Data No DataSb-125 No Data No Data No Data No Data No Data No Data No DataTe-125m 6.1OE-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.38E-06Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-099-26VER 29 VEGP ODCMTable 9-9 (contd).
Inhalation Dose Factors for the Teenager Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLITe-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-051-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 No Data 1.14E-061-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 No Data 8.11E-071-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 No Data 1.59E-071-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 No Data 1.29E-061-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 No Data 2.55E-091-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-07Cs-134 6.28E-05 1.41E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06Cs-136 6.44E-06 2.42E-05 1.71E-05 No Data 1.38E-05 2.22E-06 1.36E-06Cs-137 8.38E-05 1.06E-04 3.89E-05 No Data 3.80E-05 1.51E-05 1.06E-06Cs-138 5.82E-08 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-11Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.11E-13 8.08E-07 8.06E-07Ba-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-05Ba-141 1.78E-11 1.32E-14 5.93E-13 No Data 1.23E-14 4.11E-07 9.33E-14Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20La-140 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05La-142 1.20E-10 5.31E-11 1.32E-11 No Data No Data 1.27E-06 1.50E-06Ce-141 3.55E-06 2.37E-06 2.71E-07 No Data 1.11E-06 7.67E-05 1.58E-05Ce-143 3.32E-08 2.42E-08 2.70E-09 No Data 1.08E-08 1.63E-05 3.19E-05Ce-144 6.11E-04 2.53E-04 3.28E-05 No Data 1.51E-04 1.67E-03 1.08E-04Pr-143 1.67E-06 6.64E-07 8.28E-08 No Data 3.86E-07 6.04E-05 2.67E-05Pr-144 5.37E-12 2.20E-12 2.72E-13 No Data 1.26E-12 2.19E-07 2.94E-14Nd-147 9.83E-07 1.07E-06 6.41E-08 No Data 6.28E-07 4.65E-05 2.28E-05W-187 1.50E-09 1.22E-09 4.29E-10 No Data No Data 5.92E-06 2.21E-05Np-239 4.23E-08 3.99E-09 2.21E-09 No Data 1.25E-08 8.11E-06 1.65E-059-27VER 29 VEGP ODCMTable 9-10. Inhalation Dose Factors for the Adult Age GroupNuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLIH-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data No Data 1.08E-05Cr-51 No Data No Data 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06Mn-56 No Data 1.55E-10 2.29E-11 No Data 1.63E-10 1.18E-06 2.53E-06Fe-55 3.07E-06 2.12E-06 4.93E-07 No Data No Data 9.01E-06 7.54E-07Fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05Co-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05Ni-63 5.40E-05 3.93E-06 1.81E-06 No Data No Data 2.23E-05 1.67E-06Ni-65 1.92E-10 2.62E-11 1.14E-11 No Data No Data 7.OOE-07 1.54E-06Cu-64 No Data 1.83E-10 7.69E-11 No Data 5.78E-10 8.48E-07 6.12E-06Zn-65 4.05E-06 1.29E-05 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09Br-83 No Data No Data 3.01E-08 No Data No Data No Data 2.90E-08Br-84 No Data No Data 3.91 E-08 No Data No Data No Data 2.05E-13Br-85 No Data No Data 1.60E-09 No Data No Data No Data No DataRb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06Rb-88 No Data 4.84E-08 2.41E-08 No Data No Data No Data 4.18E-19Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.16E-21Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75E-04 4.37E-05Sr-90 1.24E-02 No Data 7.62E-04 No Data No Data 1.20E-03 9.02E-05Sr-91 7.74E-09 No Data 3.13E-10 No Data No Data 4.56E-06 2.39E-05All values are in (mrem/pCi inhaled).
They are obtained from Reference 3(Table E-7), except as follows:
Reference 2 (Table C-1) for Rh-105, Sb-124,and Sb-125.9-28VER 29 VEGP ODCMTable 9-10 (contd).
Inhalation Dose Factors for the Adult Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLISr-92 8.43E-1 0 No Data 3.64E-1 1 No Data No Data 2.06E-06 5.38E-06Y-90 2.61E-07 No Data 7.01 E-09 No Data No Data 2.12E-05 6.32E-05Y-91m 3.26E-11 No Data 1.27E-12 No Data No Data 2.40E-07 1.66E-10Y-91 5.78E-05 No Data 1.55E-06 No Data No Data 2.13E-04 4.81 E-05Y-92 1.29E-09 No Data 3.77E-11 No Data No Data 1.96E-06 9.19E-06Y-93 1.18E-08 No Data 3.26E-10 No Data No Data 6.06E-06 5.27E-05Zr-95 1.34E-05 4.30E-06 2.91E-06 No Data 6.77E-06 2.21E-04 1.88E-05Zr-97 1.21E-08 2.45E-09 1.13E-09 No Data 3.71E-09 9.84E-06 6.54E-05Nb-95 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 6.31E-05 1.30E-05Mo-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.1OE-05Tc-99m 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21Ru-103 1.91 E-07 No Data 8.23E-08 No Data 7.29E-07 6.31E-05 1.38E-05Ru-105 9.88E-11 No Data 3.89E-11 No Data 1.27E-10 1.37E-06 6.02E-06Ru-106 8.64E-06 No Data 1.09E-06 No Data 1.67E-05 1.17E-03 1.14E-04Rh-105 9.24E-10 6.73E-10 4.43E-10 No Data 2.86E-09 2.41E-06 1.09E-05Ag-110m 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 No Data 3.1OE-04 5.08E-05Sb-125 8.26E-06 8.91E-08 1.66E-06 7.34E-09 No Data 2.75E-04 1.26E-05Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08Te-131rm 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-099-29VER 29 VEGP ODCMTable 9-10 (contd).
Inhalation Dose Factors for the Adult Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLITe-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-051-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 No Data 9.61 E-071-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-071-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-081-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.11E-061-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-101-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07Cs-134 4.66E-05 1.06E-04 9.1OE-05 No Data 3.59E-05 1.22E-05 1.30E-06Cs-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06Cs-138 4.14E-08 7.76E-08 4.05E-08 No Data 6.OOE-08 6.07E-09 2.33E-13Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07Ba-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05Ba-141 1.25E-11 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26La-140 4.30E-08 2.17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05La-142 8.54E-11 3.88E-11 9.65E-12 No Data No Data 7.91E-07 2.64E-07Ce-141 2.49E-06 1.69E-06 1.91E-07 No Data 7.83E-07 4.52E-05 1.50E-05Ce-143 2.33E-08 1.72E-08 1.91E-09 No Data 7.60E-09 9.97E-06 2.83E-05Ce-144 4.29E-04 1.79E-04 2.30E-05 No Data 1.06E-04 9.72E-04 1.02E-04Pr-143 1.17E-06 4.69E-07 5.80E-08 No Data 2.70E-07 3.51E-05 2.50E-05Pr-144 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 1.27E-07 2.69E-18Nd-147 6.59E-07 7.62E-07 4.56E-08 No Data 4.45E-07 2.76E-05 2.16E-05W-187 1.06E-09 8.85E-10 3.10E-10 No Data No Data 3.63E-06 1.94E-05Np-239 2.87E-08 2.82E-09 1.55E-09 No Data 8.75E-09 4.70E-06 1.49E-059-30VER 29 VEGP ODCMTable 9-11. Ingestion Dose Factors for the Infant Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLIH-3 No Data 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05P-32 1.70E-03 1.OOE-04 6.59E-05 No Data No Data No Data 2.30E-05Cr-51 No Data No Data 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07Mn-54 No Data 1.99E-05 4.51E-06 No Data 4.41 E-06 No Data 7.31E-06Mn-56 No Data 8.18E-07 1.41 E-07 No Data 7.03E-07 No Data 7.43E-05Fe-55 1.39E-05 8.98E-06 2.40E-06 No Data No Data 4.39E-06 1.14E-06Fe-59 3.08E-05 5.38E-05 2.12E-05 No Data No Data 1.59E-05 2.57E-05Co-58 No Data 3.60E-06 8.98E-06 No Data No Data No Data 8.97E-06Co-60 No Data 1.08E-05 2.55E-05 No Data No Data No Data 2.57E-05Ni-63 6.34E-04 3.92E-05 2.20E-05 No Data No Data No Data 1.95E-06Ni-65 4.70E-06 5.32E-07 2.42E-07 No Data No Data No Data 4.05E-05Cu-64 No Data 6.09E-07 2.82E-07 No Data 1.03E-06 No Data 1.25E-05Zn-65 1.84E-05 6.31E-05 2.91E-05 No Data 3.06E-05 No Data 5.33E-05Zn-69 9.33E-08 1.68E-07 1.25E-08 No Data 6.98E-08 No Data 1.37E-05Br-83 No Data No Data 3.63E-07 No Data No Data No Data No DataBr-84 No Data No Data 3.82E-07 No Data No Data No Data No DataBr-85 No Data No Data 1.94E-08 No Data No Data No Data No DataRb-86 No Data 1.70E-04 8.40E-05 No Data No Data No Data 4.35E-06Rb-88 No Data 4.98E-07 2.73E-07 No Data No Data No Data 4.85E-07Rb-89 No Data 2.86E-07 1.97E-07 No Data No Data No Data 9.74E-08Sr-89 2.51E-03 No Data 7.20E-05 No Data No Data No Data 5.16E-05Sr-90 1.85E-02 No Data 4.71 E-03 No Data No Data No Data 2.31E-04Sr-91 5.OOE-05 No Data 1.81 E-06 No Data No Data No Data 5.92E-05All 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-125.9-31VER 29 VEGP ODCMTable 9-11 (contd).
Ingestion Dose Factors for the Infant Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLISr-92 1.92E-05 No Data 7.13E-07 No Data No Data No Data 2.07E-04Y-90 8.69E-08 No Data 2.33E-09 No Data No Data No Data 1.20E-04Y-91m 8.10E-10 No Data 2.76E-11 No Data No Data No Data 2.70E-06Y-91 1.13E-06 No Data 3.01E-08 No Data No Data No Data 8.1OE-05Y-92 7.65E-09 No Data 2.15E-10 No Data No Data No Data 1.46E-04Y-93 2.43E-08 No Data 6.62E-10 No Data No Data No Data 1.92E-04Zr-95 2.06E-07 5.02E-08 3.56E-08 No Data 5.41 E-08 No Data 2.50E-05Zr-97 1.48E-08 2.54E-09 1.16E-09 No Data 2.56E-09 No Data 1.62E-04Nb-95 4.20E-08 1.73E-08 1.OOE-08 No Data 1.24E-08 No Data 1.46E-05Mo-99 No Data 3.40E-05 6.63E-06 No Data 5.08E-05 No Data 1.12E-05Tc-99m 1.92E-09 3.96E-09 5.1OE-08 No Data 4.26E-08 2.07E-09 1.15E-06Tc-101 2.27E-09 2.86E-09 2.83E-08 No Data 3.40E-08 1.56E-09 4.86E-07Ru-103 1.48E-06 No Data 4.95E-07 No Data 3.08E-06 No Data 1.80E-05Ru-105 1.36E-07 No Data 4.58E-08 No Data 1.OOE-06 No Data 5.41 E-05Ru-106 2.41 E-05 No Data 3.01E-06 No Data 2.85E-05 No Data 1.83E-04Rh-105 No Data No Data No Data No Data No Data No Data No DataAg-110m 9.96E-07 7.27E-07 4.81E-07 No Data 1.04E-06 No Data 3.77E-05Sb-124 No Data No Data No Data No Data No Data No Data No DataSb-125 No Data No Data No Data No Data No Data No Data No DataTe-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 No Data No Data 1.11E-05Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 No Data 2.36E-05Te-127 1.OOE-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 No Data 2.1OE-05Te-129m 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 No Data 5.97E-05Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 No Data 2.27E-05Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 No Data 1.03E-04Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 No Data 7.11E-069-32VER 29 VEGP ODCMTable 9-11 (contd).
Ingestion Dose Factors for the Infant Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLITe-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 No Data 3.81 E-051-130 6.OOE-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 No Data 2.83E-061-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 No Data 1.51E-061-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 No Data 2.73E-061-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 No Data 3.08E-061-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 No Data 1.84E-061-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 No Data 2.62E-06Cs-134 3.77E-04 7.03E-04 7.1OE-05 No Data 1.81E-04 7.42E-05 1.91 E-06Cs-136 4.59E-05 1.35E-04 5.04E-05 No Data 5.38E-05 1.1OE-05 2.05E-06Cs-137 5.22E-04 6.11E-04 4.33E-05 No Data 1.64E-04 6.64E-05 1.91E-06Cs-138 4.81E-07 7.82E-07 3.79E-07 No Data 3.90E-07 6.09E-08 1.25E-06Ba-139 8.81E-07 5.84E-10 2.55E-08 No Data 3.51E-10 3.54E-10 5.58E-05Ba-140 1.71E-04 1.71E-07 8.81E-06 No Data 4.06E-08 1.05E-07 4.20E-05Ba-141 4.25E-07 2.91E-10 1.34E-08 No Data 1.75E-10 1.77E-10 5.19E-06Ba-142 1.84E-07 1.53E-10 9.06E-09 No Data 8.81E-11 9.26E-11 7.59E-07La-140 2.11E-08 8.32E-09 2.14E-09 No Data No Data No Data 9.77E-05La-142 1.1OE-09 4.04E-10 9.67E-11 No Data No Data No Data 6.86E-05Ce-141 7.87E-08 4.80E-08 5.65E-09 No Data 1.48E-08 No Data 2.48E-05Ce-143 1.48E-08 9.82E-06 1.12E-09 No Data 2.86E-09 No Data 5.73E-05Ce-144 2.98E-06 1.22E-06 1.67E-07 No Data 4.93E-07 No Data 1.71E-04Pr-143 8.13E-08 3.04E-08 4.03E-09 No Data 1.13E-08 No Data 4.29E-05Pr-144 2.74E-10 1.06E-10 1.38E-11 No Data 3.84E-11 No Data 4.93E-06Nd-147 5.53E-08 5.68E-08 3.48E-09 No Data 2.19E-08 No Data 3.60E-05W-187 9.03E-07 6.28E-07 2.17E-07 No Data No Data No Data 3.69E-05Np-239 1.11E-08 9.93E-10 5.61E-10 No Data 1.98E-09 No Data 2.87E-059-33VER 29 VEGP ODCMTable 9-12. Ingestion Dose Factors for the Child Age GroupNuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLIH-3 No Data 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06P-32 8.25E-04 3.86E-05 3.18E-05 No Data No Data No Data 2.28E-05Cr-51 No Data No Data 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07Mn-54 No Data 1.07E-05 2.85E-06 No Data 3.OOE-06 No Data 8.98E-06Mn-56 No Data 3.34E-07 7.54E-08 No Data 4.04E-07 No Data 4.84E-05Fe-55 1.15E-05 6.1OE-06 1.89E-06 No Data No Data 3.45E-06 1.13E-06Fe-59 1.65E-05 2.67E-05 1.33E-05 No Data No Data 7.74E-06 2.78E-05Co-58 No Data 1.80E-06 5.51 E-06 No Data No Data No Data 1.05E-05Co-60 No Data 5.29E-06 1.56E-05 No Data No Data No Data 2.93E-05Ni-63 5.38E-04 2.88E-05 1.83E-05 No Data No Data No Data 1.94E-06Ni-65 2.22E-06 2.09E-07 1.22E-07 No Data No Data No Data 2.56E-05Cu-64 No Data 2.45E-07 1.48E-07 No Data 5.92E-07 No Data 1.15E-05Zn-65 1.37E-05 3.65E-05 2.27E-05 No Data 2.30E-05 No Data 6.41 E-06Zn-69 4.38E-08 6.33E-08 5.85E-09 No Data 3.84E-08 No Data 3.99E-06Br-83 No Data No Data 1.71 E-07 No Data No Data No Data No DataBr-84 No Data No Data 1.98E-07 No Data No Data No Data No DataBr-85 No Data No Data 9.12E-09 No Data No Data No Data No DataRb-86 No Data 6.70E-05 4.12E-05 No Data No Data No Data 4.31 E-06Rb-88 No Data 1.90E-07 1.32E-07 No Data No Data No Data 9.32E-09Rb-89 No Data 1.1 7E-07 1.04E-07 No Data No Data No Data 1.02E-09Sr-89 1.32E-03 No Data 3.77E-05 No Data No Data No Data 5.11 E-05Sr-90 1.70E-02 No Data 4.31 E-03 No Data No Data No Data 2.29E-04Sr-91 2.40E-05 No Data 9.06E-07 No Data No Data No Data 5.30E-05All 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-105,Sb-124, or Sb-125.9-34VER 29 VEGP ODCMTable 9-12 (contd).
Ingestion Dose Factors for the Child Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLISr-92 9.03E-06 No Data 3.62E-07 No Data No Data No Data 1.71 E-04Y-90 4.11E-08 No Data 1.10E-09 No Data No Data No Data 1.17E-04Y-91m 3.82E-10 No Data 1.39E-11 No Data No Data No Data 7.48E-07Y-91 6.02E-07 No Data 1.61 E-08 No Data No Data No Data 8.02E-05Y-92 3.60E-09 No Data 1.03E-10 No Data No Data No Data 1.04E-04Y-93 1.14E-08 No Data 3.13E-10 No Data No Data No Data 1.70E-04Zr-95 1.16E-07 2.55E-08 2.27E-08 No Data 3.65E-08 No Data 2.66E-05Zr-97 6.99E-09 1.01E-09 5.96E-10 No Data 1.45E-09 No Data 1.53E-04Nb-95 2.25E-08 8.76E-09 6.26E-09 No Data 8.23E-09 No Data 1.62E-05Mo-99 No Data 1.33E-05 3.29E-06 No Data 2.84E-05 No Data 1.1 OE-05Tc-99m 9.23E-10 1.81E-09 3.OOE-08 No Data 2.63E-08 9.19E-10 1.03E-06Tc-101 1.07E-09 1.12E-09 1.42E-08 No Data 1.91E-08 5.92E-10 3.56E-09Ru-103 7.31 E-07 No Data 2.81E-07 No Data 1.84E-06 No Data 1.89E-05Ru-105 6.45E-08 No Data 2.34E-08 No Data 5.67E-07 No Data 4.21E-05Ru-106 1.17E-05 No Data 1.46E-06 No Data 1.58E-05 No Data 1.82E-04Rh-105 No Data No Data No Data No Data No Data No Data No DataAg-110m 5.39E-07 3.64E-07 2.91E-07 No Data 6.78E-07 No Data 4.33E-05Sb-124 No Data No Data No Data No Data No Data No Data No DataSb-125 No Data No Data No Data No Data No Data No Data No DataTe-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 No Data No Data 1.10E-05Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 No Data 2.34E-05Te-127 4.71 E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 No Data 1.84E-05Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 No Data 5.94E-05Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 No Data 8.34E-06Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 No Data 1.01E-04Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 No Data 4.36E-079-35VER 29 VEGP ODCMTable 9-12 (contd).
Ingestion Dose Factors for the Child Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLITe-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 No Data 4.50E-051-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 No Data 2.76E-061-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 No Data 1.54E-061-132 8.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 No Data 1.73E-061-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 No Data 2.95E-061-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 No Data 5.16E-071-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 No Data 2.40E-06Cs-134 2.34E-04 3.84E-04 8.1OE-05 No Data 1.19E-04 4.27E-05 2.07E-06Cs-136 2.35E-05 6.46E-05 4.18E-05 No Data 3.44E-05 5.13E-06 2.27E-06Cs-137 3.27E-04 3.13E-04 4.62E-05 No Data 1.02E-04 3.67E-05 1.96E-06Cs-138 2.28E-07 3.17E-07 2.01E-07 No Data 2.23E-07 2.40E-08 1.46E-07Ba-139 4.14E-07 2.21E-10 1.20E-08 No Data 1.93E-10 1.30E-10 2.39E-05Ba-140 8.31E-05 7.28E-08 4.85E-06 No Data 2.37E-08 4.34E-08 4.21E-05Ba-141 2.OOE-07 1.12E-10 6.51E-09 No Data 9.69E-11 6.58E-10 1.14E-07Ba-142 8.74E-08 6.29E-11 4.88E-09 No Data 5.09E-11 3.70E-11 1.14E-09La-140 1.01E-08 3.53E-09 1.19E-09 No Data No Data No Data 9.84E-05La-142 5.24E-10 1.67E-10 5.23E-11 No Data No Data No Data 3.31E-05Ce-141 3.97E-08 1.98E-08 2.94E-09 No Data 8.68E-09 No Data 2.47E-05Ce-143 6.99E-09 3.79E-06 5.49E-10 No Data 1.59E-09 No Data 5.55E-05Ce-144 2.08E-06 6.52E-07 1.11E-07 No Data 3.61E-07 No Data 1.70E-04Pr-143 3.93E-08 1.18E-08 1.95E-09 No Data 6.39E-09 No Data 4.24E-05Pr-144 1.29E-10 3.99E-11 6.49E-12 No Data 2.11E-11 No Data 8.59E-08Nd-147 2.79E-08 2.26E-08 1.75E-09 No Data 1.24E-08 No Data 3.58E-05W-187 4.29E-07 2.54E-07 1.14E-07 No Data No Data No Data 3.57E-05Np-239 5.25E-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Data 2.79E-059-36VER 29 VEGP ODCMTable 9-13. Ingestion Dose Factors for the Teenager Age GroupNuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLIH-3 No Data 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06P-32 2.76E-04 1.71 E-05 1.07E-05 No Data No Data No Data 2.32E-05Cr-51 No Data No Data 3.60E-09 2.OOE-09 7.89E-10 5.14E-09 6.05E-07Mn-54 No Data 5.90E-06 1.17E-06 No Data 1.76E-06 No Data 1.21E-05Mn-56 No Data 1.58E-07 2.81E-08 No Data 2.OOE-07 No Data 1.04E-05Fe-55 3.78E-06 2.68E-06 6.25E-07 No Data No Data 1.70E-06 1.16E-06Fe-59 5.87E-06 1.37E-05 5.29E-06 No Data No Data 4.32E-06 3.24E-05Co-58 No Data 9.72E-07 2.24E-06 No Data No Data No Data 1.34E-05Co-60 No Data 2.81E-06 6.33E-06 No Data No Data No Data 3.66E-05Ni-63 1.77E-04 1.25E-05 6.OOE-06 No Data No Data No Data 1.99E-06Ni-65 7.49E-07 9.57E-08 4.36E-08 No Data No Data No Data 5.19E-06Cu-64 No Data 1.15E-07 5.41E-08 No Data 2.91 E-07 No Data 8.92E-06Zn-65 5.76E-06 2.OOE-05 9.33E-06 No Data 1.28E-05 No Data 8.47E-06Zn-69 1.47E-08 2.80E-08 1.96E-09 No Data 1.83E-08 No Data 5.16E-08Br-83 No Data No Data 5.74E-08 No Data No Data No Data No DataBr-84 No Data No Data 7.22E-08 No Data No Data No Data No DataBr-85 No Data No Data 3.05E-09 No Data No Data No Data No DataRb-86 No Data 2.98E-05 1.40E-05 No Data No Data No Data 4.41 E-06Rb-88 No Data 8.52E-08 4.54E-08 No Data No Data No Data 7.30E-15Rb-89 No Data 5.50E-08 3.89E-08 No Data No Data No Data 8.43E-17Sr-89 4.40E-04 No Data 1.26E-05 No Data No Data No Data 5.24E-05Sr-90 8.30E-03 No Data 2.05E-03 No Data No Data No Data 2.33E-04Sr-91 8.07E-06 No Data 3.21 E-07 No Data No Data No Data 3.66E-05All 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-1 05,Sb-1 24, or Sb-1 25.9-37VER 29 VEGP ODCMTable 9-13 (contd).
Ingestion Dose Factors for the Teenager Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLISr-92 3.05E-06 No Data 1.30E-07 No Data No Data No Data 7.77E-05Y-90 1.37E-08 No Data 3.69E-10 No Data No Data No Data 1.13E-04Y-91m 1.29E-10 No Data 4.93E-12 No Data No Data No Data 6.09E-09Y-91 2.01E-07 No Data 5.39E-09 No Data No Data No Data 8.24E-05Y-92 1.21E-09 No Data 3.50E-11 No Data No Data No Data 3.32E-05Y-93 3.83E-09 No Data 1.05E-10 No Data No Data No Data 1.17E-04Zr-95 4.12E-08 1.30E-08 8.94E-09 No Data 1.91 E-08 No Data 3.OOE-05Zr-97 2.37E-09 4.69E-10 2.16E-10 No Data 7.11E-10 No Data 1.27E-04Nb-95 8.22E-09 4.56E-09 2.51E-09 No Data 4.42E-09 No Data 1.95E-05Mo-99 No Data 6.03E-06 1.15E-06 No Data 1.38E-05 No Data 1.08E-05Tc-99m 3.32E-10 9.26E-10 1.20E-08 No Data 1.38E-08 5.14E-10 6.08E-07Tc-101 3.60E-10 5.12E-10 5.03E-09 No Data 9.26E-09 3.12E-10 8.75E-17Ru-103 2.55E-07 No Data 1.09E-07 No Data 8.99E-07 No Data 2.13E-05Ru-105 2.18E-08 No Data 8.46E-09 No Data 2.75E-07 No Data 1.76E-05Ru-106 3.92E-06 No Data 4.94E-07 No Data 7.56E-06 No Data 1.88E-04Rh-1 05 No Data No Data No Data No Data No Data No Data No DataAg-110m 2.05E-07 1.94E-07 1.18E-07 No Data 3.70E-07 No Data 5.45E-05Sb-124 No Data No Data No Data No Data No Data No Data No DataSb-1 25 No Data No Data No Data No Data No Data No Data No DataTe-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 No Data No Data 1.13E-05Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 No Data 2.41E-05Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 No Data 1.22E-05Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 No Data 6.12E-05Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 No Data 2.45E-07Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 No Data 9.39E-05Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 No Data 2.29E-099-38VER 29 VEGP ODCMTable 9-13 (contd).
Ingestion Dose Factors for the Teenager Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLITe-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 No Data 7.OOE-051-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 No Data 2.29E-061-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 No Data 1.62E-061-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 No Data 3.18E-071-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 No Data 2.58E-061-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.1OE-07 No Data 5.1OE-091-135 6.1OE-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 No Data 1.74E-06Cs-134 8.37E-05 1.97E-04 9.14E-05 No Data 6.26E-05 2.39E-05 2.45E-06Cs-136 8.59E-06 3.38E-05 2.27E-05 No Data 1.84E-05 2.90E-06 2.72E-06Cs-137 1.12E-04 1.49E-04 5.19E-05 No Data 5.07E-05 1.97E-05 2.12E-06Cs-138 7.76E-08 1.49E-07 7.45E-08 No Data 1.1OE-07 1.28E-08 6.76E-11Ba-139 1.39E-07 9.78E-11 4.05E-09 No Data 9.22E-11 6.74E-11 1.24E-06Ba-140 2.84E-05 3.48E-08 1.83E-06 No Data 1.18E-08 2.34E-08 4.38E-05Ba-141 6.71E-08 5.01E-11 2.24E-09 No Data 4.65E-11 3.43E-11 1.43E-13Ba-142 2.99E-08 2.99E-11 1.84E-09 No Data 2.53E-11 1.99E-11 9.18E-20La-140 3.48E-09 1.71E-09 4.55E-10 No Data No Data No Data 9.82E-05La-142 1.79E-10 7.95E-11 1.98E-11 No Data No Data No Data 2.42E-06Ce-141 1.33E-08 8.88E-09 1.02E-09 No Data 4.18E-09 No Data 2.54E-05Ce-143 2.35E-09 1.71E-06 1.91E-10 No Data 7.67E-10 No Data 5.14E-05Ce-144 6.96E-07 2.88E-07 3.74E-08 No Data 1.72E-07 No Data 1.75E-04Pr-143 1.31E-08 5.23E-09 6.52E-10 No Data 3.04E-09 No Data 4.31E-05Pr-144 4.30E-11 1.76E-11 2.18E-12 No Data 1.01 E-11 No Data 4.74E-14Nd-147 9.38E-09 1.02E-08 6.11E-10 No Data 5.99E-09 No Data 3.68E-05W-187 1.46E-07 1.19E-07 4.17E-08 No Data No Data No Data 3.22E-05Np-239 1.76E-09 1.66E-10 9.22E-11 No Data 5.21E-10 No Data 2.67E-059-39VER 29 VEGP ODCMTable 9-14. Ingestion Dose Factors for the Adult Age GroupNuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLIH-3 No Data 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06Fe-55 2.75E-06 1.90E-06 4.43E-07 No Data No Data 1.06E-06 1.09E-06Fe-59 4.34E-06 1.02E-05 3.91 E-06 No Data No Data 2.85E-06 3.40E-05Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51 E-05Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88E-06Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.1OE-07 No Data 7.1OE-06Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08Br-84 No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13Br-85 No Data No Data 2.14E-09 No Data No Data No Data No DataRb-86 No Data 2.11 E-05 9.83E-06 No Data No Data No Data 4.16E-06Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05All values are in (mrem/pCi ingested).
They are obtained from Reference 3(Table E-1 1), except as follows:
Reference 2 (Table A-3) for Rh-1 05, Sb-1 24,and Sb-125.9-40VER 29 VEGP ODCMTable 9-14 (contd).
Ingestion Dose Factors for the Adult Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLISr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04Y-91m 9.09E-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05Y-92 8.45E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05Y-93 2.68E-09 No Data 7.40E-11 No Data No Data No Data 8.50E-05Zr-95 3.04E-08 9.75E-09 6.60E-09 No Data 1.53E-08 No Data 3.09E-05Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04Nb-95 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.1OE-05Mo-99 No Data 4.31E-06 8.20E-07 No Data 9.76E-06 No Data 9.99E-06Tc-99m 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.1OE-21Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04Rh-105 1.22E-07 8.86E-08 5.83E-08 No Data 3.76E-07 No Data 1.41 E-05Ag-110m 1.60E-07 1.48E-07 8.79E-08 No Data 2.91E-07 No Data 6.04E-05Sb-124 2.81E-06 5.30E-08 1.11E-06 6.79E-09 No Data 2.18E-06 7.95E-05Sb-125 2.23E-06 2.40E-08 4.48E-07 1.98E-09 No Data 2.33E-04 1.97E-05Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05Te-127 1.1OE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5.79E-05Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-099-41VER 29 VEGP ODCMTable 9-14 (contd).
Ingestion Dose Factors for the Adult Age GroupNuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLITe-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71 E-051-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-061-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-061-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 No Data 1.02E-071-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 No Data 2.22E-061-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51 E-101-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31E-06Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13Ba-139 9.70E-08 6.91E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.OOE-26La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05La-142 1.28E-10 5.82E-11 1.45E-11 No Data No Data No Data 4.25E-07Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05Pr-144 3.01 E-11 1.25E-11 1.53E-12 No Data 7.05E-12 No Data 4.33E-18Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05Np-239 1.19E-09 1.17E-10 6.45E-11 No Data 3.65E-10 No Data 2.40E-059-42 VER 299-42VER 29 VEGP ODCMTable 9-15.External Dose Factors for Standing on Contaminated GroundNuclide T. Body SkinH-3 0.00 0.00C-14 0.00 0.00Na-24 2.50E-08 2.90E-08P-32 0.00 0.00Cr-51 2.20E-10 2.60E-10Mn-54 5.80E-09 6.80E-09Mn-56 1.10E-08 1.30E-08Fe-55 0.00 0.00Fe-59 8.OOE-09 9.40E-09Co-58 7.OOE-09 8.20E-09Co-60 1.70E-08 2.OOE-08Ni-63 0.00 0.00Ni-65 3.70E-09 4.30E-09Cu-64 1.50E-09 1.70E-09Zn-65 4.OOE-09 4.60E-09Zn-69 0.00 0.00Br-83 6.40E-1 1 9.30E-1 1Br-84 1.20E-08 1.40E-08Br-85 0.00 0.00Rb-86 6.30E-10 7.20E-10Rb-88 3.50E-09 4.OOE-09Rb-89 1.50E-08 1.80E-08Sr-89 5.60E-13 6.50E-13Sr-90 0.00 0.00Nuclide T. Body SkinSr-91 7.1OE-09 8.30E-09Sr-92 9.OOE-09 1.OOE-08Y-90 2.20E-12 2.60E-12Y-91 m 3.80E-09 4.40E-09Y-91 2.40E-11 2.70E- 11Y-92 1.60E-09 1.90E-09Y-93 5.70E-10 7.80E-10Zr-95 5.OOE-09 5.80E-09Zr-97 5.50E-09 6.40E-09Nb-95 5.1OE-09 6.OOE-09Mo-99 1.90E-09 2.20E-09Tc-99m 9.60E-10 1.1OE-09Tc-101 2.70E-09 3.OOE-09Ru-103 3.60E-09 4.20E-09Ru-105 4.50E-09 5.1OE-09Ru-106 1.50E-09 1.80E-09Rh-105 6.60E-10 7.70E-10Ag-11im 1.80E-08 2.1OE-08Sb-124 1.30E-08 1.50E-08Sb-125 3.1OE-09 3.50E-09Te-125m 3.50E-11 4.80E-11Te-127m 1.10E-12 1.30E-12Te-127 1.O0E-11 1.10E-11Te-129m 7.70E-10 9.OOE-10All values are in (mrem/h) per (pCi/m2). They are obtained from Reference 3(Table E-6), except as follows:
Reference 2 (Table A-7) for Rh-105, Sb-124,and Sb-125.9-43VER 29 VEGP ODCMTable 9-15 (contd).External Dose Factors for Standing on Contaminated GroundNuclide T.Body SkinTe-129 7.10E-10 8.40E-10Te-131m 8.40E-09 9.90E-09Te-131 2.20E-09 2.60E-06Te-132 1.70E-09 2.OOE-091-130 1.40E-08 1.70E-081-131 2.80E-09 3.40E-091-132 1.70E-08 2.OOE-081-133 3.70E-09 4.50E-091-134 1.60E-08 1.90E-081-135 1.20E-08 1.40E-08Cs-134 1.20E-08 1.40E-08Cs-136 1.50E-08 1.70E-08Cs-137 4.20E-09 4.90E-09Cs-138 2.1OE-08 2.40E-08Ba-139 2.40E-09 2.70E-09Ba-140 2.1OE-09 2.40E-09Ba-141 4.30E-09 4.90E-09Ba-142 7.90E-09 9.OOE-09La-140 1.50E-08 1.70E-08La-142 1.50E-08 1.80E-08Ce-141 5.50E-10 6.20E-10Ce-143 2.20E-09 2.50E-09Ce-144 3.20E-10 3.70E-10Pr-143 0.00 0.00Pr-144 2.OOE-10 2.30E-10Nd-147 1.00E-09 1.20E-09W-187 3.1OE-09 3.60E-09Np-239 9.50E-10 1.1OE-099-44VER 29 VEGP ODCMCHAPTER 10DEFINITIONS OF EFFLUENT CONTROL TERMSThe 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 ODCMThe 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 measuresrequired under designated conditions.
BATCH RELEASEA BATCH RELEASE is the discharge of wastes of a discrete volume. Prior tosampling for analyses, each liquid batch shall be isolated and then thoroughly mixed by a method described in the ODCM to assure representative sampling.
COMPOSITE SAMPLEA COMPOSITE SAMPLE is one which contains material from multiple wastereleases, in which the quantity of sample is proportional to the quantity of wastedischarged, and in which the method of sampling employed results in a specimenthat is representative of the wastes released.
Prior to analyses, all liquid samplesthat are to be aliquotted for a COMPOSITE SAMPLE shall be mixed thoroughly, inorder 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 theapplicable release pathway may be used.CONTINUOUS RELEASEA 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 becollected in proportion to the rate of flow of the effluent stream or to the quantity ofliquid waste discharged.
FREQUENCY NOTATIONThe FREQUENCY NOTATION specified for the performance of surveillance requirements shall correspond to the intervals defined below, with a maximumallowable extension not to exceed 25% of the surveillance interval.
9-45VER 29 VEGP ODCMNOTATION FREQUENCY S (Once per shift) At least once per 12 hours.D (Daily) At least once per 24 hours.W (Weekly)
At least once per 7 days.M (Monthly)
At least once per 31 days.Q (Quarterly)
At least once per 92 days.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 SYSTEMA GASEOUS WASTE PROCESSING SYSTEM shall be any system designed andinstalled to reduce radioactive gaseous effluents by collecting Reactor CoolantSystem offgases from the Reactor Coolant System and providing for delay orholdup for the purpose of reducing the total radioactivity prior to release to theenvironment.
LIQUID RADWASTE TREATMENT SYSTEMA LIQUID RADWASTE TREATMENT SYSTEM is any system designed andinstalled to reduce radioactive materials in liquid effluents by systematic collection, retention, and processing through filtration, evaporation, separation and/or ionexchange treatment.
This system consists of at least one collection tank, oneevaporator or demineralizer system, one post-treatment tank and associated components providing for treatment flow and functional control.MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMSFor the purposes of the ODCM, MAJOR CHANGES TO RADIOACTIVE WASTETREATMENT SYSTEMS include the following changes to such systems:(1) Major changes in process equipment, components, structures, or effluentmonitoring instrumentation as described in the Final Safety Analysis Report(FSAR) or as evaluated in the Nuclear Regulatory Commission staffsSafety Evaluation Report (SER) (e.g., deletion of evaporators andinstallation of demineralizers);
(2) Changes in the design of radwaste treatment systems that couldsignificantly 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 asdescribed in the SER (e.g., changes in tank capacity that would alter thecuries released);
or9-46VER 29 VEGP ODCM(4) Changes in system design that could potentially result in a significant increase in occupational exposure of operating personnel (e.g., use oftemporary equipment without adequate shielding provisions).
MEMBER(S)
OF THE PUBLIC!A MEMBER OF THE PUBLIC means any individual except when that individual isreceiving an occupational dose2.This category may include persons who useportions 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 thecontrols in this ODCM, as the smallest concentration of radioactive material in a sample thatwill 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 (gCiper unit mass or volume).2.71 + 3.29 Rb t +MDC= tsE V -2.22 x 106  Y .e- AtRb = the background counting rate, or the counting rate of a blanksample, as appropriate (counts per minute).ts = the length of the sample counting period (minutes).
tb = 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 106 = the number of disintegrations per minute per &#xfd;tCi.Y = the fractional radiochemical yield, when applicable.
The italicized terms in this definition, which are not otherwise used in this ODCM, shall have the definitions assigned tothem by 10 CFR 20.1003.2 Except as delineated in other parts of 10 CFR chapter I.9-47VER 29 VEGP ODCMX = the radioactive decay constant for the given radionuclide (h-').Values of X used in effluent calculations should be based ondecay data from a recognized and current source, such asReference 20.At = for effluent
: samples, the elapsed time between the midpoint ofsample 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).Typical values of E, V, Y, and At should be used in the calculation.
It should berecognized 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 EMITTERSThe 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, Co-58, Co-60, Zn-65, Mo-99,Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with anMDC of 5 x 10.-6 LtCi/mL.* 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-99, 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.
Othergamma peaks that are identifiable, together with those of the above nuclides, shallalso be analyzed and reported in the Radioactive Effluent Release Report, theAnnual Radiological Environmental Operating Report, or other applicable report(s).
SITE BOUNDARYFor the purpose of effluent controls defined in the ODCM, the SITE BOUNDARYshall be as shown in Figure 4-1.SOURCE CHECKA SOURCE CHECK shall be the qualitative assessment of channel response whenthe channel sensor is exposed to a source of increased radioactivity.
9-48VER 29 VEGP ODCMUNRESTRICTED AREAThe UNRESTRICTED AREA shall be any area access to which is neither limitednor controlled by the licensee, or any area within the SITE BOUNDARY used forresidential quarters or for industrial, commercial, institutional, and/or recreational purposes.
VENTILATION EXHAUST TREATMENT SYSTEMThe VENTILATION EXHAUST TREATMENT SYSTEM is any system designed andinstalled to reduce gaseous radioiodine or radioactive material in particulate form ineffluents, by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters, for the purpose of removing iodines or particulates from thegaseous exhaust stream prior to the release to the environment.
(Such a system isnot considered to have any effect on any noble gas effluents).
Engineered SafetyFeature (ESF) atmospheric cleanup systems are not considered to beVENTILATION EXHAUST TREATMENT SYSTEM components.
9-49VER 29 VEGP ODCM10.2 TERMS DEFINED IN THE TECHNICAL SPECIFICATIONS The following terms are defined in the Technical Specifications, Section 1.0. Because theyare 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 andthose in the Technical Specifications, the Technical Specification definitions shall takeprecedence.
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 ofinput. The CHANNEL CALIBRATION shall encompass the entire channel including the required sensor, alarm, interlock, and/or trip functions and may be performed byany series of sequential, overlapping, or total channel steps, so that the entirechannel is calibrated.
CHANNEL CHECKA CHANNEL CHECK shall be the qualitative assessment of channel behaviorduring operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/orstatus derived from independent instrument channels measuring the sameparameter.
CHANNEL OPERATIONAL TEST (COT)A CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal intothe channel as close to the sensor as practicable to verify operability of requiredalarm, interlock, and/or trip functions.
The CHANNEL OPERATIONAL TEST shallinclude adjustments, as necessary, of the required alarm, interlock, and/or tripsetpoints, so that the setpoints are within the required range and accuracy.
DOSE EQUIVALENT 1-131DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (&#xfd;tCi/g) which alonewould 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 EPA Federal GuidanceReport No. 11, "Limiting Values of Radionuclide Intake and Air Concentration andDose Conversion Factors for Inhalation, Submersion, and Ingestion,"
EPA-520/1-88-020, September 1988.MODE (or OPERATIONAL MODE)An OPERATIONAL MODE shall correspond to any one inclusive combination ofcore reactivity condition, power level, average reactor coolant temperature, andreactor vessel head closure bolt tensioning specified in Section 1.0 of the Technical Specifications with fuel in the reactor vessel.9-50VER 29 VEGP ODCMOPERABLE (or OPERABILITY)
OPERABILITY exists when a system, subsystem, train, component or device iscapable of performing its specified function(s),
and when all necessary attendant instrumentation,
: controls, electrical power, cooling or seal water, lubrication or otherauxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their relatedsupport function(s).
RATED THERMAL POWERRATED THERMAL POWER shall be a total reactor core heat transfer rate to thereactor coolant of 3565 MWt.THERMAL POWERTHERMAL POWER shall be the total reactor core heat transfer rate to the reactorcoolant.9-51VER 29}}

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