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These methodologies and parameters were developed using the guidance in NUREG-01.33 (Reference 3);Regulatory Guide 1:.109 (Reference 4); Regulatory Guide 1.111, (Reference 5); Regulatory Guide 1.113 (Reference 6); ,Regulatory Guide 1.21 (Reference 7); and Radiologicail AssessmentBranch Technical Position onEnvironmental Monitoring (Reference 8). Where any methodology or parameter.
These methodologies and parameters were developed using the guidance in NUREG-01.33 (Reference 3);Regulatory Guide 1:.109 (Reference 4); Regulatory Guide 1.111, (Reference 5); Regulatory Guide 1.113 (Reference 6); ,Regulatory Guide 1.21 (Reference 7); and Radiologicail AssessmentBranch Technical Position onEnvironmental Monitoring (Reference 8). Where any methodology or parameter.
differs from the guidance provided,1i the, above documents, it has been documented in the .text and references given for the source of the information.
differs from the guidance provided,1i the, above documents, it has been documented in the .text and references given for the source of the information.
E1-67 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 6 of 195 1.0/2.0 -CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.0 APPLICABILITY CONTROLS 1.0.1 Controls shall be met during the MODES or other specified conditions in the Applicability,,'except as provided in Control 1.0.2.1.0.2 Upon discovery of a failure to meet a Control, the Action(s) of the associated Conditions shall be met.If the Control is metor is no longer applicable prior to expiration;of theAction(s), completion of the Action(s) is not required unless otherwise stated.SURVEILLANCE REQUIREMENTS 2.0.1 Surveillance Requirements(SR) shall be met during MODES or other conditions in theApplicability for individual Controls, unless otherwise stated in the SR. Failure to meet the Control occurs when a surveillance isfailed or when conditions occur between surveillances--that~would result.in affailed surveillance if testing was performed.
E1-67 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 6 of 195 1.0/2.0 -CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.0 APPLICABILITY CONTROLS 1.0.1 Controls shall be met during the MODES or other specified conditions in the Applicability,,'except as provided in Control 1.0.2.1.0.2 Upon discovery of a failure to meet a Control, the Action(s) of the associated Conditions shall be met.If the Control is metor is no longer applicable prior to expiration;of theAction(s), completion of the Action(s) is not required unless otherwise stated.SURVEILLANCE REQUIREMENTS
 
====2.0.1 Surveillance====
 
Requirements(SR) shall be met during MODES or other conditions in theApplicability for individual Controls, unless otherwise stated in the SR. Failure to meet the Control occurs when a surveillance isfailed or when conditions occur between surveillances--that~would result.in affailed surveillance if testing was performed.
Failure to perform a surveillance within the specified frequency shall befailureto meet theControl except as provided in SR 2.0.3. Surveillancesdo, not have to- be performed on inoperable equipment or variables outside specified limits.2.0.2 The specified frequency foreach SR is met if the surveillance is performed within.1.25 times.the interval specified in the frequency, as measured from the previous performance or. asmeasured from a time a specified condition of the frequency is met.For frequencies specified'as "once," the above interval extension does not apply.If an Action requires periodic performance on a "once per..." basis, the above frequency extension applies to each performance after the initial performance.
Failure to perform a surveillance within the specified frequency shall befailureto meet theControl except as provided in SR 2.0.3. Surveillancesdo, not have to- be performed on inoperable equipment or variables outside specified limits.2.0.2 The specified frequency foreach SR is met if the surveillance is performed within.1.25 times.the interval specified in the frequency, as measured from the previous performance or. asmeasured from a time a specified condition of the frequency is met.For frequencies specified'as "once," the above interval extension does not apply.If an Action requires periodic performance on a "once per..." basis, the above frequency extension applies to each performance after the initial performance.
Exceptions to this SR control section are stated in the individualSRs.
Exceptions to this SR control section are stated in the individualSRs.
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Detailed description of the LLD,.and other detection limits can be found in HASL Procedures:Manual, HASL-300, Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination -Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J: K.,",Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).112.3.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of areas at and beyond the UNRESTRICTED AREA BOUNDARY are identified and that modificationsto the monitoring program are made, if required by the results of that census. The best information from the door-to-door survey, mailsurvey, telephone survey, aerial survey, or by consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10-CFR 50. Restricting Ithe census-to gardens of greater than 50 m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to provide the quantity (26 kg/y) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption:by a child.To determine this minimum garden size, the following assumptions were. used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m 2.E1-114 WBN OFFSITE DOSE CALCULATION MANUAL RevisiOn 22 0 (ODCM) Page 53 of 195 1/2.3.3 INTERLABORATORY COMPARISON The Control for participation in an approved Interlaboratory Comparison Program is provided to ensure.that independent checks on the. precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix Ito 10 .CFR 50.E1-115 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22.
Detailed description of the LLD,.and other detection limits can be found in HASL Procedures:Manual, HASL-300, Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination -Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J: K.,",Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).112.3.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of areas at and beyond the UNRESTRICTED AREA BOUNDARY are identified and that modificationsto the monitoring program are made, if required by the results of that census. The best information from the door-to-door survey, mailsurvey, telephone survey, aerial survey, or by consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10-CFR 50. Restricting Ithe census-to gardens of greater than 50 m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to provide the quantity (26 kg/y) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption:by a child.To determine this minimum garden size, the following assumptions were. used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m 2.E1-114 WBN OFFSITE DOSE CALCULATION MANUAL RevisiOn 22 0 (ODCM) Page 53 of 195 1/2.3.3 INTERLABORATORY COMPARISON The Control for participation in an approved Interlaboratory Comparison Program is provided to ensure.that independent checks on the. precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix Ito 10 .CFR 50.E1-115 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22.
0 (ODCM) Page 54 of '195 3.0 DEFINITIONS The defined terms in this section appear in capitalized type in the text and are applicable throughout these Controls and Bases.3.1 ACTION ACTION shall be that part of a Control that prescribes remedial measures required under designated conditions.
0 (ODCM) Page 54 of '195 3.0 DEFINITIONS The defined terms in this section appear in capitalized type in the text and are applicable throughout these Controls and Bases.3.1 ACTION ACTION shall be that part of a Control that prescribes remedial measures required under designated conditions.
3.2 CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the necessary range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm, interlock, display, and/or trip functions.
 
===3.2 CHANNEL===
CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the necessary range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm, interlock, display, and/or trip functions.
Calibration of instrument channels with resistance temperature detector or thermocouple sensors shall consist of an in place cross calibration of the remaining adjustable devices in the channel. Whenever a sensing element is replaced, the, next'required in.place cross calibration consists of comparing the other sensing elementswith the recently rinstalled sensing element. The CHANNEL CALIBRATION may be performed by anyseries of sequential, overlapping channel calibrations or total channel steps such that the entire channel is calibrated.
Calibration of instrument channels with resistance temperature detector or thermocouple sensors shall consist of an in place cross calibration of the remaining adjustable devices in the channel. Whenever a sensing element is replaced, the, next'required in.place cross calibration consists of comparing the other sensing elementswith the recently rinstalled sensing element. The CHANNEL CALIBRATION may be performed by anyseries of sequential, overlapping channel calibrations or total channel steps such that the entire channel is calibrated.
3.3 CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channelbehavior during operation.
 
===3.3 CHANNEL===
CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channelbehavior during operation.
Thisdetermination shall include, where possible, comparison of the channel.indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
Thisdetermination shall include, where possible, comparison of the channel.indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
3.4 CHANNEL OPERATIONAL TEST A CHANNEL OPERATIONAL TEST shall be the injection of a.simulated signal or actual signal into the channel asclose to the sensor as practicable to verify OPERABILITY of alarm, interlock, and/or trip functions.
 
The CHANNEL OPERATIONAL TEST shall include adjustments, as, necessary, of the required alarm, interlock, and/or trip setpoints such that the setpoints are within the required range and accuracy.3.5 CONTROLLED AREA A CONTROLLED AREA, as defined in 10 CFR 20, is the area outside the RESTRICTED AREA but inside the 10 CFR 20defined UNRESTRICTED AREA BOUNDARY, access towhich can'be' limited by the licenseefor any reason (see Figure 3.1).3.6 DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 alone would~produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132,1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.E1-116 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 55 of 195 3.0 DEFINITIONS 3.7 FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of SurveillanceRequirements shall correspond to the intervals defined in Table 3.1.3.8 MEMBER(S)
===3.4 CHANNEL===
OPERATIONAL TEST A CHANNEL OPERATIONAL TEST shall be the injection of a.simulated signal or actual signal into the channel asclose to the sensor as practicable to verify OPERABILITY of alarm, interlock, and/or trip functions.
The CHANNEL OPERATIONAL TEST shall include adjustments, as, necessary, of the required alarm, interlock, and/or trip setpoints such that the setpoints are within the required range and accuracy.3.5 CONTROLLED AREA A CONTROLLED AREA, as defined in 10 CFR 20, is the area outside the RESTRICTED AREA but inside the 10 CFR 20defined UNRESTRICTED AREA BOUNDARY, access towhich can'be' limited by the licenseefor any reason (see Figure 3.1).3.6 DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 alone would~produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132,1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.E1-116 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 55 of 195 3.0 DEFINITIONS
 
===3.7 FREQUENCY===
 
NOTATION The FREQUENCY NOTATION specified for the performance of SurveillanceRequirements shall correspond to the intervals defined in Table 3.1.3.8 MEMBER(S)
OF THE PUBLIC MEMBER(S)
OF THE PUBLIC MEMBER(S)
OF THE PUBLIC, as defined in 10 CFR 20, is any individual except when that individual is receiving an occupational dose.3.9 MODE A MODE shall- correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 3.2 with fuel in the reactor vessel -and reactor vessel head.closure bolt tensioning.
OF THE PUBLIC, as defined in 10 CFR 20, is any individual except when that individual is receiving an occupational dose.3.9 MODE A MODE shall- correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 3.2 with fuel in the reactor vessel -and reactor vessel head.closure bolt tensioning.
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a summary description of the radiological environmental monitoring program;.at least two legible maps (one map shall cover stations near.the:UNRESTRICTED AREA BOUNDARY, a second shall include the more distant stations):covering..all:
a summary description of the radiological environmental monitoring program;.at least two legible maps (one map shall cover stations near.the:UNRESTRICTED AREA BOUNDARY, a second shall include the more distant stations):covering..all:
samplingldobations keyed to a table giving distances and directions from the centerline of one reactor; and the results of licensee participation in the Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not-being performed as required by ODCM Control 1.3.1; discussion of all deviations from the sampling schedule of Table 2.3-1;, reasons for not conducting the radiological environmental monitoring program as required by ODCM Control 1.3.1 and discussions of environmental sample measurements that exceed the reporting levels of Table 2.3-2 but are not the result0of plant effluents, pursuant to action b. of ODCM Control 1.3.1; and discussion ofiall analyses:in which the LLD required by Table 2.3-3 was not achievable.
samplingldobations keyed to a table giving distances and directions from the centerline of one reactor; and the results of licensee participation in the Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not-being performed as required by ODCM Control 1.3.1; discussion of all deviations from the sampling schedule of Table 2.3-1;, reasons for not conducting the radiological environmental monitoring program as required by ODCM Control 1.3.1 and discussions of environmental sample measurements that exceed the reporting levels of Table 2.3-2 but are not the result0of plant effluents, pursuant to action b. of ODCM Control 1.3.1; and discussion ofiall analyses:in which the LLD required by Table 2.3-3 was not achievable.
5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT As required by WBN TS 5.9.3, a Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year. The period ,f the first report shall begin with the date-of initial criticality.
 
===5.2 ANNUAL===
RADIOACTIVE EFFLUENT RELEASE REPORT As required by WBN TS 5.9.3, a Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year. The period ,f the first report shall begin with the date-of initial criticality.
The Annual Radioactive Effluent Release Report shall include a summary of the quantities-of radioactive liquid and gaseous effluents and solid waste released from the-units as outlined in. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releasesof Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled:Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof, as applicable.
The Annual Radioactive Effluent Release Report shall include a summary of the quantities-of radioactive liquid and gaseous effluents and solid waste released from the-units as outlined in. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releasesof Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled:Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof, as applicable.
Additional requirements for reporting solid waste are specified in theProcess Control Program.The radioactive effluent release reports-shall include a list and description of unplanned releases from:the site to UNRESTRICTED AREAS of radioactive materials in gaseousand liquid effluents made'during the reporting period.E1-122 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page 61 of 195 The radioactive effluent release reports shall include any changes made during the reporting period to the Process Control Program,, and to the ODCM pursuant to ODCM Administrative Control 5.3, as well.as any major changes to Liquid, Gaseous, or Solid Radwaste Treatment.Systems, pursuant to WBN Technical Specifications.
Additional requirements for reporting solid waste are specified in theProcess Control Program.The radioactive effluent release reports-shall include a list and description of unplanned releases from:the site to UNRESTRICTED AREAS of radioactive materials in gaseousand liquid effluents made'during the reporting period.E1-122 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page 61 of 195 The radioactive effluent release reports shall include any changes made during the reporting period to the Process Control Program,, and to the ODCM pursuant to ODCM Administrative Control 5.3, as well.as any major changes to Liquid, Gaseous, or Solid Radwaste Treatment.Systems, pursuant to WBN Technical Specifications.
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For WBN, a portion of thetotal-dilution flow-is- allocated-to each release point using an-allocation factor (AF). To determine the maximum calculated monitor;setpoint, Smax, in cpm for a release point, the following equation is used: Smax { OSF(f + (AF x F)) }(ER- BKG) + BKG (6.5)where: AF = fraction of dilution flow allocated to this release point. For the TBS, AF= 0. The-fractions:
For WBN, a portion of thetotal-dilution flow-is- allocated-to each release point using an-allocation factor (AF). To determine the maximum calculated monitor;setpoint, Smax, in cpm for a release point, the following equation is used: Smax { OSF(f + (AF x F)) }(ER- BKG) + BKG (6.5)where: AF = fraction of dilution flow allocated to this release point. For the TBS, AF= 0. The-fractions:
for, the remaining 4 release points are normally defined as the ratio of the allocated CTBD flow .for that release point to the total CTBD flow. The CTBD flow allocation fractions for these release points are routinely:
for, the remaining 4 release points are normally defined as the ratio of the allocated CTBD flow .for that release point to the total CTBD flow. The CTBD flow allocation fractions for these release points are routinely:
Radwaste 0.6 Condensate demineralizer 0.2 Steam Generator Blowdown (U1) 0.1 Steam Generator Blowdown (U2) 0.1 These allocation factors may beadjusted for a~particular release if it is known that.there are no releases being made through other release points into the CTBD. For example, if there are no releases being made through the-Condensate Demineralizer or either SGBD, the AF for the Radwaste-System may be set equal to one.ER = expected monitor response, cpm, as calculated in Equation.
Radwaste 0.6 Condensate demineralizer  
 
===0.2 Steam===
Generator Blowdown (U1) 0.1 Steam Generator Blowdown (U2) 0.1 These allocation factors may beadjusted for a~particular release if it is known that.there are no releases being made through other release points into the CTBD. For example, if there are no releases being made through the-Condensate Demineralizer or either SGBD, the AF for the Radwaste-System may be set equal to one.ER = expected monitor response, cpm, as calculated in Equation.
6.3.BKG = background, cpm.El-132 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 71 of 195 6.3 CUMULATIVE LIQUIDEFFLUENT DOSE CALCULATIONS Doses due to liquid effluents are calculated for each release for thefollowing;age.
6.3.BKG = background, cpm.El-132 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 71 of 195 6.3 CUMULATIVE LIQUIDEFFLUENT DOSE CALCULATIONS Doses due to liquid effluents are calculated for each release for thefollowing;age.
groups: adult.(17 years and older),.teen(11-17 years), child (1-11 years), infant (0-1 years) (Reference'4);
groups: adult.(17 years and older),.teen(11-17 years), child (1-11 years), infant (0-1 years) (Reference'4);
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all organ doses for all age.groups.
all organ doses for all age.groups.
The agegroup with the highest single organ dose: isselected as the critical age group. The total body and maximum organ doses for the critical age group are used~in the icalculation of the cumulative doses described in Section 6.3.1.El-133 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 72.of 195 6.3.1 Cumulative Doses Cumulative quarterly and annual sums of all doses are determined for. eachý release to compare to the limits given in ODCM Control 1.2.1.2. These quarterly and annual sums~will bethe sum of the doses for each releasewhich occurred in that quarter or year. These doses will be. used inthe comparison to the limits.6.3.2 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to the limits in ODCM Control 1.2.1.2 at least once per 31 days to determine compliance.
The agegroup with the highest single organ dose: isselected as the critical age group. The total body and maximum organ doses for the critical age group are used~in the icalculation of the cumulative doses described in Section 6.3.1.El-133 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 72.of 195 6.3.1 Cumulative Doses Cumulative quarterly and annual sums of all doses are determined for. eachý release to compare to the limits given in ODCM Control 1.2.1.2. These quarterly and annual sums~will bethe sum of the doses for each releasewhich occurred in that quarter or year. These doses will be. used inthe comparison to the limits.6.3.2 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to the limits in ODCM Control 1.2.1.2 at least once per 31 days to determine compliance.
6.4 LIQUID WASTE TREATMENT SYSTEM The LRTS described in the WBN FSAR shall be maintained and operated toý keep releases ALARA.A flow diagram for the LRTS is given in Figure 6.2.6.5 DOSE PROJECTIONS In accordance with ODCM Surveillance Requirements 2.2.1.3.1 and 2.2'1.3.2, doseprojections!will be performed at least once per 31 days using the equation below: D (a b) x31} +c (6.8)where: D = the 31-day dose projection, mrem.a = the cumulative dose for the quarter, mrem.b = the projected dose for this release, mrem.c = any anticipated additional dose in the next month from other sources, mrem.d = current number of days into the quarter up to the time of the release under consideration.
 
===6.4 LIQUID===
WASTE TREATMENT SYSTEM The LRTS described in the WBN FSAR shall be maintained and operated toý keep releases ALARA.A flow diagram for the LRTS is given in Figure 6.2.6.5 DOSE PROJECTIONS In accordance with ODCM Surveillance Requirements 2.2.1.3.1 and 2.2'1.3.2, doseprojections!will be performed at least once per 31 days using the equation below: D (a b) x31} +c (6.8)where: D = the 31-day dose projection, mrem.a = the cumulative dose for the quarter, mrem.b = the projected dose for this release, mrem.c = any anticipated additional dose in the next month from other sources, mrem.d = current number of days into the quarter up to the time of the release under consideration.
El-134 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 73'of 195 6.6 DOSE CALCULATIONS FOR REPORTING A complete dose analysis utilizing the total estimated liquid releases for each calendar-quarter will.be performed and reported as required in ODCMAdministrative Control 5.2. Methodology-for this analysis is based:on the methodology presented in Regulatory-Guide 1.109 and is described in this.section.
El-134 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 73'of 195 6.6 DOSE CALCULATIONS FOR REPORTING A complete dose analysis utilizing the total estimated liquid releases for each calendar-quarter will.be performed and reported as required in ODCMAdministrative Control 5.2. Methodology-for this analysis is based:on the methodology presented in Regulatory-Guide 1.109 and is described in this.section.
The releases are assumed, for this calculation, to be continuous over the 90 day. peridd.The near-field dilution factor, DNF, used for the quarterly calculations is: DNF =-0.10 RF (for receptors upstream of Tennessee-River Mile 510.0)(6.9)and DNF =-RF (for receptors downstream of Tennessee River Mile 510.0)(6.10)where: RF = the average actual riverflow for the location at which the dose is being determined,..cfs.
The releases are assumed, for this calculation, to be continuous over the 90 day. peridd.The near-field dilution factor, DNF, used for the quarterly calculations is: DNF =-0.10 RF (for receptors upstream of Tennessee-River Mile 510.0)(6.9)and DNF =-RF (for receptors downstream of Tennessee River Mile 510.0)(6.10)where: RF = the average actual riverflow for the location at which the dose is being determined,..cfs.
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, lw (iodines) 7.71 E-07 s"1 Reference 21 (Table 3.10).(15A4 d half-life) lw (particulates) 5.21 E-07 s-1 Reference 21 (Table3.10)
, lw (iodines) 7.71 E-07 s"1 Reference 21 (Table 3.10).(15A4 d half-life) lw (particulates) 5.21 E-07 s-1 Reference 21 (Table3.10)
(10.4 d half-life), E1-148 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page87W.of 195 Table 6.4 -INGESTION DOSE FACTORS -DF.a.(mrem/pCi ingested) (Page 1 of 8)ADULT Nuclide H-3 C,14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91 m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-1O1 Ru-1 03 Ru-105 Ru-106 bone 1.05E-07 2.84E-06 1.70E-,06 1.93E-04 O.OOE+00 0.OOE+00 0.OOE+00 2.75E-06 4.34E-06 O.00E+00 0.00E+00 0.OOE+00 1.30Er014 5.28E&07 0.00E+00 4.'84E-06 1..03E-08 1.70E-07 0.00E+00 0.00E+00.00OE+00 0.00E+00 O.OOE+00 0.00E+00 O.00E+00 3.08E-04 7.58E-03 5.67E-06 21'5E-06 9.62E-09 9.09E-1 1 1.41E-07 8.45E-1 0 2.68E&09 3.04E-08 1'.68E-09 6.22E&09 5.22E-1 1 0.OOE+00 2.47E-1 0 2*54E-10 1.85E-07 1.54E-08 2.75E-06 liver 1.05E-07 5.68E-07 1.70E-06 1 .20E-05 0:00E+00 4.57E-06 1.15E-07 1 .90E-06 1.02E-05 1.75E-07.7.45E-07 2.14E-06 9.01 E-06 6.86E-08 8 33E-08 1 .54E-05 1.97E'08 4.08E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+ý00 2A1&E-05 6.05E-08 4.01 E-08 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 9.75E-09 3.39E-10 3.46E-09 1.32E-11 4.31 E-06 6.98E-1 0 3*66E-10 0.OOE+00 0.00E+00 0.00E+00 total body 1.05E-07 5.68E-07 1.70E-06 7.46E-06 2.66E-09 8.72E-07 2.04E-08 4.43E-07 3.91 E-06 2.91E-07 1.67E-06 4.72E-06 4.36E-06 3.13E-08 3*91 E-08 6.96E'06 1 *37E-09 3.73E-08 2.26E-06 4.02E-08 5.21 E-08 2.14E-09 9.83E-06 3.21 E-08 2.82E-08 8.84E-06 1.86E-03 2.29E-07 9.30E-08 2.58E-1 0 152E-1 2 3.77E-09 2.47E- 1 7.40E-1 1 6.60E-09 1.55E-10 1.86E-09 4.82E-1 2 8.20E-07 8.89E-09 3.59E-09 7.97E-08 6.08E-09 3.48E-07 thyroid 1 .05E1-07 5.68E-07 1 .70E-06 0.00E+00 1 .59E-09 0.00E+00 0.OOE+00.0.OOE+ý00 0.OOE+00 0.O0Ei-00 0.OOE+00, 0.00E-t00 0.OOE+00 0.OOE+00: 0.OOE+00 0.00E+00 0.OOEl-00 0.00E+00 0.00OE4-00, 0.00E+00 0.OOE+00, 0.0OE+00 0.00E+00 0.OOE-'00 0.OOE+00, 0.OOE+00 0.00E+00 0.00E+00 0.OOE+/-00 0.00E+00 0.OOE+00 O.OOE4W.0.OOE+00 0 *OOE-i-00 0.OOE+00 0.OOE+00.0 *0OE-'00: 0.OOE+00 0.00E+00 0.OOE+00.OOE-'010 0.OOE+00 0.OOE+00 0.OOE+00 kidney 1.05E707 5&68E-07 1.70E-06 0.OOE+00 5.86E-1 0 1.36E-06 1.46E-07 0.OOE+00 0.00E+00 O.OOE+00 0.00E*00 0*00E+00" 0.00E+00 0.00E+00 2.1tE-07 1.03E&05 1.28E-08 2.47E-07 o*OOE+00 O.OOE+00 0ý00E-00 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0;00E+00 O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.53E-08 3142E-09 1.54E-11 9.76E&06 1.06E-08 6.59E-09 7.06EL-07 1.99E&07 5.31,E-06 lung 1 .OSE-07 S.68E-07 1 .70&-06, 0.OOE+00o 3.53E-09 1.06 0E-ý06 2.85&-06 0.00E-'-0 0.OOE+00;0.OOE+00 0.OE00E+G 0.OOE+ý00-0.OOE+00 0.00E+00, 0.OE00L+p 0.OOE+-00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+-00 0.OOEt00.OOE+Q100.0.OQE+00 0.1001E+,00 0.OOE+00: 0.00E+00, 0OOE+ý00: 0.00E+00 0ODOE+00, 0.OOE-'-00 0.00E+00 0O.OOE+00ýO.'OOE 1+00'3.42E-,1 0~1.87E-1:0 0.00E,+00 0.OOE+0O 0OME+ý00: GI-LLI 1.05EL07 5.68E-:07 1 .70E-06 2.1 7E-05 6.69E-07 1 40E-05 3.367E-06 1":09E-06 3.40E&05 4.44E-06 1;.51E-05.4.02E-05 1.88E-06 7.10Et 06 9,70E-06 2.96E-09 2.49E-05 2.59E-606:
(10.4 d half-life), E1-148 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page87W.of 195 Table 6.4 -INGESTION DOSE FACTORS -DF.a.(mrem/pCi ingested) (Page 1 of 8)ADULT Nuclide H-3 C,14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91 m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-1O1 Ru-1 03 Ru-105 Ru-106 bone 1.05E-07 2.84E-06 1.70E-,06 1.93E-04 O.OOE+00 0.OOE+00 0.OOE+00 2.75E-06 4.34E-06 O.00E+00 0.00E+00 0.OOE+00 1.30Er014 5.28E&07 0.00E+00 4.'84E-06 1..03E-08 1.70E-07 0.00E+00 0.00E+00.00OE+00 0.00E+00 O.OOE+00 0.00E+00 O.00E+00 3.08E-04 7.58E-03 5.67E-06 21'5E-06 9.62E-09 9.09E-1 1 1.41E-07 8.45E-1 0 2.68E&09 3.04E-08 1'.68E-09 6.22E&09 5.22E-1 1 0.OOE+00 2.47E-1 0 2*54E-10 1.85E-07 1.54E-08 2.75E-06 liver 1.05E-07 5.68E-07 1.70E-06 1 .20E-05 0:00E+00 4.57E-06 1.15E-07 1 .90E-06 1.02E-05 1.75E-07.7.45E-07 2.14E-06 9.01 E-06 6.86E-08 8 33E-08 1 .54E-05 1.97E'08 4.08E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+ý00 2A1&E-05 6.05E-08 4.01 E-08 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 9.75E-09 3.39E-10 3.46E-09 1.32E-11 4.31 E-06 6.98E-1 0 3*66E-10 0.OOE+00 0.00E+00 0.00E+00 total body 1.05E-07 5.68E-07 1.70E-06 7.46E-06 2.66E-09 8.72E-07 2.04E-08 4.43E-07 3.91 E-06 2.91E-07 1.67E-06 4.72E-06 4.36E-06 3.13E-08 3*91 E-08 6.96E'06 1 *37E-09 3.73E-08 2.26E-06 4.02E-08 5.21 E-08 2.14E-09 9.83E-06 3.21 E-08 2.82E-08 8.84E-06 1.86E-03 2.29E-07 9.30E-08 2.58E-1 0 152E-1 2 3.77E-09 2.47E- 1 7.40E-1 1 6.60E-09 1.55E-10 1.86E-09 4.82E-1 2 8.20E-07 8.89E-09 3.59E-09 7.97E-08 6.08E-09 3.48E-07 thyroid 1 .05E1-07 5.68E-07 1 .70E-06 0.00E+00 1 .59E-09 0.00E+00 0.OOE+00.0.OOE+ý00 0.OOE+00 0.O0Ei-00 0.OOE+00, 0.00E-t00 0.OOE+00 0.OOE+00: 0.OOE+00 0.00E+00 0.OOEl-00 0.00E+00 0.00OE4-00, 0.00E+00 0.OOE+00, 0.0OE+00 0.00E+00 0.OOE-'00 0.OOE+00, 0.OOE+00 0.00E+00 0.00E+00 0.OOE+/-00 0.00E+00 0.OOE+00 O.OOE4W.0.OOE+00 0 *OOE-i-00 0.OOE+00 0.OOE+00.0 *0OE-'00: 0.OOE+00 0.00E+00 0.OOE+00.OOE-'010 0.OOE+00 0.OOE+00 0.OOE+00 kidney 1.05E707 5&68E-07 1.70E-06 0.OOE+00 5.86E-1 0 1.36E-06 1.46E-07 0.OOE+00 0.00E+00 O.OOE+00 0.00E*00 0*00E+00" 0.00E+00 0.00E+00 2.1tE-07 1.03E&05 1.28E-08 2.47E-07 o*OOE+00 O.OOE+00 0ý00E-00 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0;00E+00 O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.53E-08 3142E-09 1.54E-11 9.76E&06 1.06E-08 6.59E-09 7.06EL-07 1.99E&07 5.31,E-06 lung 1 .OSE-07 S.68E-07 1 .70&-06, 0.OOE+00o 3.53E-09 1.06 0E-ý06 2.85&-06 0.00E-'-0 0.OOE+00;0.OOE+00 0.OE00E+G 0.OOE+ý00-0.OOE+00 0.00E+00, 0.OE00L+p 0.OOE+-00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+-00 0.OOEt00.OOE+Q100.0.OQE+00 0.1001E+,00 0.OOE+00: 0.00E+00, 0OOE+ý00: 0.00E+00 0ODOE+00, 0.OOE-'-00 0.00E+00 0O.OOE+00ýO.'OOE 1+00'3.42E-,1 0~1.87E-1:0 0.00E,+00 0.OOE+0O 0OME+ý00: GI-LLI 1.05EL07 5.68E-:07 1 .70E-06 2.1 7E-05 6.69E-07 1 40E-05 3.367E-06 1":09E-06 3.40E&05 4.44E-06 1;.51E-05.4.02E-05 1.88E-06 7.10Et 06 9,70E-06 2.96E-09 2.49E-05 2.59E-606:
5.79E-08 4.09E-1 3 6.'00Et6-0 4.1 6E'06 8.36E-l 9, 2.33E-21 4.94E'05 2.19E'04 2:70E-105 4:26EI-05 1.02E-04, 2.67E-10 7.76E-05 1.48E-,05 3.09E-'05 1A.05E-04 2.1 QE-05 4. 87E-08*9.99E-06 4.1 3E107 1. 1OE-2.1 2.,16E-05 9.42E-06ý1.78E-04 E1-149 WBN OFFSITE DOSE CALCULATIONMANUAL Revision 22 0 (ODCM) Page 88of 195 Table 6.4 -INGESTION DOSE FACTORS -DF.ai (mrem/pCi ingested) (Page 2 of 8)ADULT Nuclide Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-1 29m Te-129 Te-131m Te-131 Te-132 1-130 1-131 1-132 1-133 1-134 1-135 Cs-1 34 Cs-136 Cs-137 Cs- 138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 1.60E-07 2.80E-06 1.79E-06 2.68E-06 6;77E-06 1.10E-07 1 .15E-05 3.14E-08 1.73E-06 1.97E-08 2.52E&06 7.56E-07 4.16E-06 2.03E-07 1.42E-06 1 '06E&07 4.43E-07 6.22E-05 6.51 E-06 7.97E-05 5.52E-08 9.70E-08 2.03E-05 4.71 E-08 2.1 3E-08 2.50E-09 1.28E-10 9:36E-09 1.65E-09 4.88E-07 9.20E-09 3.01E-1I 6.29E-09 1.03E-07 1.19E-09 liver 1,48E&07 5.29E-08 2,00E-08 9.71 E-07 2.42E-06 3.95E-08 4.29E-06 1 18E-08 8.46E-07 8:23E-09 1.63E-06 2.23E-06 5.95E-06 5.43E-07 2.-47E-06 2.88E-07.1 6E-06 1.48E-04 2.57E-05 1.09E-04 1:09E-07 6.91 E-1 1 2'55E&08 3.56E- 1 2.19E-11 1.26E-09 5.82E-1 1 633E-09 1.22E-06 2.04E-07 3169E-09 1.25E-11 7.27E-09 8.61 E-08 1.17E-10 total body 8.79E-08 1.11E-06 4.26E-07 3.59E-07 8.25E-07 2.38E-08 1.82E-06 7.65E-09 7.05E-07 6.22E-09 1.53E-06 8.80E-07 3.41 E-06 1.90E-07 7.53E-07 1.03E-07 4.28E-07 1.21 E-04 1.85E-05 7.14E-05 5.40E-08 2.84E-09 1.33E-06 1.59E-09 1.34E-09 3.33E-10 1.45E-1 1 7.18E-10 1.35E-10 2;62E&08 4.56E-1 0 1.53E-1 2 4.35E-10 3.01 E-08 6.45E-1 1 thyroid 0.00E+00 6.79E-09 1.82E-09 8.06E-07 1.73E-06 8.15E-08 3.95E-06 2.41 E-08 1.34E-06 1.62E-08 1.80E-06 1.89E-04 1.95E-03 1.90E-05 3.63E-04 4.99E-06 7.65E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00, 0.OOE+00 kidney 2.91 E-07 0.00E-7'00 0.00E-00 1.09E-05 2.75E-05, 4.48E-07 4.80E-05 1.32E-07 8.57E-06 8.63E-08 1.57E-05 3.48E-06 1.02E-05 8.65E-07 4.31 E-06 4.58E-07 1.86E-06 4.79E-05 1.43E-05 3.70E&05 8.01 E-08 6.46E-1I 8.67E-09 3.31 E-1i1 1.85E- 1I 0.OOE+00 0.00E+00 2.94E-09 5.37E-10 1.21 E-07 2.1-3E09 7.05E-12 4.25E-09 0.OOE+00 3.65E-1 0 lung 0.00E00 2:.18E-06 1.38E-06 0.00E+00 0.00E+00 0.0OE+00 0.00E+00 0.OOE+00 0.00Et00;0.00E+/-00 0OOE+00 0.00E-+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 1'.59E-05 1.96E-06 1.23E-05 7.91E-09 3;92E-'i1 1.46E-08 2.02E-I 1 1.24E-11 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 000E+.00 0.00E+00 GI-LLI 6.04E-05 7'.95E&05 1 97E-05 1.07E-05 2.27E-05 8.68E-06 5.79E-05 2.37E-08 8.40E-05 2.79E-09 7.71E&05 1.92E-06 1 .57E-06 1.02E407 2.22E-06 2.51 E-1 0 1.31 E-06 2.59E-06 2.92E-06 2.11E-06 4.65E-13 1 .72E-07 4.1 8E&05 2.22E-1:7 300E,-26 9.25E-05 4.25E-07 2.42E-05 4.56E-05 1i.65E-04 4M03E-05 4*33E-18 3.49E-05 2.82E&05 2.40E-05  
5.79E-08 4.09E-1 3 6.'00Et6-0
 
===4.1 6E'06===
8.36E-l 9, 2.33E-21 4.94E'05 2.19E'04 2:70E-105 4:26EI-05 1.02E-04, 2.67E-10 7.76E-05 1.48E-,05 3.09E-'05 1A.05E-04 2.1 QE-05 4. 87E-08*9.99E-06 4.1 3E107 1. 1OE-2.1 2.,16E-05 9.42E-06ý1.78E-04 E1-149 WBN OFFSITE DOSE CALCULATIONMANUAL Revision 22 0 (ODCM) Page 88of 195 Table 6.4 -INGESTION DOSE FACTORS -DF.ai (mrem/pCi ingested) (Page 2 of 8)ADULT Nuclide Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-1 29m Te-129 Te-131m Te-131 Te-132 1-130 1-131 1-132 1-133 1-134 1-135 Cs-1 34 Cs-136 Cs-137 Cs- 138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 1.60E-07 2.80E-06 1.79E-06 2.68E-06 6;77E-06 1.10E-07 1 .15E-05 3.14E-08 1.73E-06 1.97E-08 2.52E&06 7.56E-07 4.16E-06 2.03E-07 1.42E-06 1 '06E&07 4.43E-07 6.22E-05 6.51 E-06 7.97E-05 5.52E-08 9.70E-08 2.03E-05 4.71 E-08 2.1 3E-08 2.50E-09 1.28E-10 9:36E-09 1.65E-09 4.88E-07 9.20E-09 3.01E-1I 6.29E-09 1.03E-07 1.19E-09 liver 1,48E&07 5.29E-08 2,00E-08 9.71 E-07 2.42E-06 3.95E-08 4.29E-06 1 18E-08 8.46E-07 8:23E-09 1.63E-06 2.23E-06 5.95E-06 5.43E-07 2.-47E-06 2.88E-07.1 6E-06 1.48E-04 2.57E-05 1.09E-04 1:09E-07 6.91 E-1 1 2'55E&08 3.56E- 1 2.19E-11 1.26E-09 5.82E-1 1 633E-09 1.22E-06 2.04E-07 3169E-09 1.25E-11 7.27E-09 8.61 E-08 1.17E-10 total body 8.79E-08 1.11E-06 4.26E-07 3.59E-07 8.25E-07 2.38E-08 1.82E-06 7.65E-09 7.05E-07 6.22E-09 1.53E-06 8.80E-07 3.41 E-06 1.90E-07 7.53E-07 1.03E-07 4.28E-07 1.21 E-04 1.85E-05 7.14E-05 5.40E-08 2.84E-09 1.33E-06 1.59E-09 1.34E-09 3.33E-10 1.45E-1 1 7.18E-10 1.35E-10 2;62E&08 4.56E-1 0 1.53E-1 2 4.35E-10 3.01 E-08 6.45E-1 1 thyroid 0.00E+00 6.79E-09 1.82E-09 8.06E-07 1.73E-06 8.15E-08 3.95E-06 2.41 E-08 1.34E-06 1.62E-08 1.80E-06 1.89E-04 1.95E-03 1.90E-05 3.63E-04 4.99E-06 7.65E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00, 0.OOE+00 kidney 2.91 E-07 0.00E-7'00 0.00E-00 1.09E-05 2.75E-05, 4.48E-07 4.80E-05 1.32E-07 8.57E-06 8.63E-08 1.57E-05 3.48E-06 1.02E-05 8.65E-07 4.31 E-06 4.58E-07 1.86E-06 4.79E-05 1.43E-05 3.70E&05 8.01 E-08 6.46E-1I 8.67E-09 3.31 E-1i1 1.85E- 1I 0.OOE+00 0.00E+00 2.94E-09 5.37E-10 1.21 E-07 2.1-3E09 7.05E-12 4.25E-09 0.OOE+00 3.65E-1 0 lung 0.00E00 2:.18E-06 1.38E-06 0.00E+00 0.00E+00 0.0OE+00 0.00E+00 0.OOE+00 0.00Et00;0.00E+/-00 0OOE+00 0.00E-+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 1'.59E-05 1.96E-06 1.23E-05 7.91E-09 3;92E-'i1 1.46E-08 2.02E-I 1 1.24E-11 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 000E+.00 0.00E+00 GI-LLI 6.04E-05 7'.95E&05 1 97E-05 1.07E-05 2.27E-05 8.68E-06 5.79E-05 2.37E-08 8.40E-05 2.79E-09 7.71E&05 1.92E-06 1 .57E-06 1.02E407 2.22E-06 2.51 E-1 0 1.31 E-06 2.59E-06 2.92E-06 2.11E-06 4.65E-13 1 .72E-07 4.1 8E&05 2.22E-1:7 300E,-26 9.25E-05 4.25E-07 2.42E-05 4.56E-05 1i.65E-04 4M03E-05 4*33E-18 3.49E-05 2.82E&05 2.40E-05  


==References:==
==References:==
Line 863: Line 887:
This will be done for the gamma dose, the beta dose and the maximum organ dose.D={(ad) x3} +c (7.10)where: D = the 31-day dose projection, mrem.a = the cumulative dose for the quarter, mrem.b = the projected dose for this release (as calculated in Sections 7.4.1, 7.4.2 and 7.4.3), mrem.c = any anticipated.additional dose in the next month from other sources, mrem.d = current number of days into the quarter up to the time of the release under consideration.
This will be done for the gamma dose, the beta dose and the maximum organ dose.D={(ad) x3} +c (7.10)where: D = the 31-day dose projection, mrem.a = the cumulative dose for the quarter, mrem.b = the projected dose for this release (as calculated in Sections 7.4.1, 7.4.2 and 7.4.3), mrem.c = any anticipated.additional dose in the next month from other sources, mrem.d = current number of days into the quarter up to the time of the release under consideration.
The 31-day projected dose-will be compared to the limits given in ODCM Control 1.2.2.4 in accordance with Surveillance Requirement 2.2.2.4.1 to determine compliance.
The 31-day projected dose-will be compared to the limits given in ODCM Control 1.2.2.4 in accordance with Surveillance Requirement 2.2.2.4.1 to determine compliance.
7.6 GASEOUS RADWASTE TREATMENT SYSTEM DESCRIPTION The GASEOUS RADWASTE TREATMENT SYSTEM (GRTS) described in the WBN FSAR shall be maintained and operated to keep releases ALARA. A simplified flow diagram for the GRTS is given in Figure 7.3.El-175 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 114!of 195 7.7 DOSE CALCULATIONSFOR REPORTING A complete dose: analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control15.2.
 
===7.6 GASEOUS===
RADWASTE TREATMENT SYSTEM DESCRIPTION The GASEOUS RADWASTE TREATMENT SYSTEM (GRTS) described in the WBN FSAR shall be maintained and operated to keep releases ALARA. A simplified flow diagram for the GRTS is given in Figure 7.3.El-175 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 114!of 195 7.7 DOSE CALCULATIONSFOR REPORTING A complete dose: analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control15.2.
All 'real pathways and receptor locations identified by the most recent land use survey are considered., In.addition, actual meteOrological data representative of a ground level release for each corresponding  
All 'real pathways and receptor locations identified by the most recent land use survey are considered., In.addition, actual meteOrological data representative of a ground level release for each corresponding  
!calendar quaiter will be used. For iodine, releasesitf is assumed thathalf the iodine released is in organicpform.
!calendar quaiter will be used. For iodine, releasesitf is assumed thathalf the iodine released is in organicpform.
Organic iodine6causes a dose only by inhalation.
Organic iodine6causes a dose only by inhalation.
For cow-milk and beef ingestion doses, thefradction of0the time the animals are on stored feed (identified in the survey) is used in the calculation.'
For cow-milk and beef ingestion doses, thefradction of0the time the animals are on stored feed (identified in the survey) is used in the calculation.'
7.7.1 Noble Gas- Gamma and Beta Air Dose Regulatory Guide 11.109 Equation B-5 provides the following equation for the calculation of.gamma and beta airdoses from noble gas releases: D = , (DFý or 1) (7.11)where: cim = concentration of nuclide i at location m, gCi/m 3.. Air concentrations are calculated as described by Equation 7:33.DFgi = dose conversion factor for external gamma for nuclide i, .mrad/y per jI/Cim 3 (Table 7.4).DFbi = doseconversion factor for external beta for nuclide i, mrad/y per gCi/m 3.(Table7.4).
 
7.7.2 Noble Gat- Air Submersion Dose Regulatory Guide 1.109 Equation B-8 provides the following equation for the calculation of the total body submersion dose from noble gas releases: D = SF Y_ Xim DFBI (7.12)i where: SF = shielding factor. This factor is conservatively set equal to,1.0.cim = concentr'ation of nuclide] at location m, jiCi/m 3.Air concentrations are calculated as described by Equation 7.33.DFBi = total body dose conversion factor due to submersion in a semi-infinite cloud of noble gases for nuclide i, mrem/y per.jCi/m 3 (Table 7.4).Regulatory Guide 1.109 Equation B-9 provides the following equation'for the calculation of the skin submersion dose from noble gas releases: D= {1.11 1SF y_ Xim DF +Y Xim DFSj (7.13)where: 1.11 =the average ratio of tissue to air energy absorption coefficients, mrem/mrad.
====7.7.1 Noble====
Gas- Gamma and Beta Air Dose Regulatory Guide 11.109 Equation B-5 provides the following equation for the calculation of.gamma and beta airdoses from noble gas releases: D = , (DFý or 1) (7.11)where: cim = concentration of nuclide i at location m, gCi/m 3.. Air concentrations are calculated as described by Equation 7:33.DFgi = dose conversion factor for external gamma for nuclide i, .mrad/y per jI/Cim 3 (Table 7.4).DFbi = doseconversion factor for external beta for nuclide i, mrad/y per gCi/m 3.(Table7.4).
 
====7.7.2 Noble====
Gat- Air Submersion Dose Regulatory Guide 1.109 Equation B-8 provides the following equation for the calculation of the total body submersion dose from noble gas releases: D = SF Y_ Xim DFBI (7.12)i where: SF = shielding factor. This factor is conservatively set equal to,1.0.cim = concentr'ation of nuclide] at location m, jiCi/m 3.Air concentrations are calculated as described by Equation 7.33.DFBi = total body dose conversion factor due to submersion in a semi-infinite cloud of noble gases for nuclide i, mrem/y per.jCi/m 3 (Table 7.4).Regulatory Guide 1.109 Equation B-9 provides the following equation'for the calculation of the skin submersion dose from noble gas releases: D= {1.11 1SF y_ Xim DF +Y Xim DFSj (7.13)where: 1.11 =the average ratio of tissue to air energy absorption coefficients, mrem/mrad.
SF = shielding:
SF = shielding:
factor. This factor is conservatively set equal to 1.0.cim = concentration of nuclide i at location M, gCi/m 3.Air concentrations are calculated as described by:Equation 7.33.DF = dose conversion factor for external gamma for nuclide i, mrad/y per jCi/rj 3 (Table 7.4),.DFi = skin dose conversion factordue to submersion in a semi-irnfinite dclud of nbble gases-for nuclide i, .mrem/y per ýtCi/m 3 (Table 7.4).El-176 WBN OFFSITE DOSE CALCULATION MANUAL Revision22 0 (ODCM) Page 115 of 195 7.7.3 Radioiodine, Particulate, and Tritium -Maximum Organ Dose Regulatory Guide. 1.109 Equations C-12, -13, and -14 provides the following equation'for the-calculation of doses from the release of iodine and particulate radionuclides:
factor. This factor is conservatively set equal to 1.0.cim = concentration of nuclide i at location M, gCi/m 3.Air concentrations are calculated as described by:Equation 7.33.DF = dose conversion factor for external gamma for nuclide i, mrad/y per jCi/rj 3 (Table 7.4),.DFi = skin dose conversion factordue to submersion in a semi-irnfinite dclud of nbble gases-for nuclide i, .mrem/y per ýtCi/m 3 (Table 7.4).El-176 WBN OFFSITE DOSE CALCULATION MANUAL Revision22 0 (ODCM) Page 115 of 195 7.7.3 Radioiodine, Particulate, and Tritium -Maximum Organ Dose Regulatory Guide. 1.109 Equations C-12, -13, and -14 provides the following equation'for the-calculation of doses from the release of iodine and particulate radionuclides:
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-RVF (see Section 7.8.5).stored vegetable ingestion  
-RVF (see Section 7.8.5).stored vegetable ingestion  
-Rvs (see Section 7.8.6).RGi = Dose factor for standing on contaminated ground, m 2-mrem/y per ICi/s. The equation for calculating theground plane dose factor is given in Section 7.8.14.X/Q = Relative concentration for location under consideration, s/m 3.Relativeconcentrations are-calculated as described by Equation 7.34.Rli = Inhalation dose factor, mrem/y per gCi/m 3.The equation for calculating the inhalation dose factor is given in Section 7.8.13.Qi = adjusted release rate for nuclide i for location under consideration, gCi/s. Calculated in the same manner as QT above.The highest organ dose for a real receptor is determined by summing thedose contributionfrorm all identified pathways for each receptor including ground contamination, inhalation,, vegetable ingestion: (for identified garden locations), cow and/or goat milk ingestion (if a cow or goat is identifiedifor the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all receptors).
-Rvs (see Section 7.8.6).RGi = Dose factor for standing on contaminated ground, m 2-mrem/y per ICi/s. The equation for calculating theground plane dose factor is given in Section 7.8.14.X/Q = Relative concentration for location under consideration, s/m 3.Relativeconcentrations are-calculated as described by Equation 7.34.Rli = Inhalation dose factor, mrem/y per gCi/m 3.The equation for calculating the inhalation dose factor is given in Section 7.8.13.Qi = adjusted release rate for nuclide i for location under consideration, gCi/s. Calculated in the same manner as QT above.The highest organ dose for a real receptor is determined by summing thedose contributionfrorm all identified pathways for each receptor including ground contamination, inhalation,, vegetable ingestion: (for identified garden locations), cow and/or goat milk ingestion (if a cow or goat is identifiedifor the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all receptors).
7.7.4 Population Doses The population dose is determined using Equation D-1 from Regulatory Guide 1.109: D = k Y POPm Y. Daij FPma m For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements.
 
====7.7.4 Population====
 
Doses The population dose is determined using Equation D-1 from Regulatory Guide 1.109: D = k Y POPm Y. Daij FPma m For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements.
These elements are defined in Table 7T5. Dispersion factors;are calculated for the midpoint of each sector element (see Table 7.5). For each of these sector elements, an iaverage dose is calculated, and'then multiplied by the population in that sector element. The average dose is determined by multiplying the maximum individual dose for the sector by the ratio of the: average tothe maximum usage rates. For population doses resulting from~ingestion,.itis conservatively assumed that all foodeaten by the average individual is grown within the sector element. The-general equation used for calculating the population dose in a given sector element is: Dosepop = 0.001 ERATIOp POPm FPa DOSEp P where: 0.001 = conversion from mrem to rem.RATIOp = ratio of average to maximum dose for pathway P. Maximum ingestion rates are given in Table 6.3. (Average ingestion rates are obtained from Reference 4, Table E-4.)= 0.5 for submersion and ground exposure pathways, a shielding/occupancy factor..= 1.0 for.the inhalation pathway.= 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult,: respectively. (Itis assumed that the-ratio of average to maximum infant milk ingestion rates is:the same as that for child.)= 1.0, 0.90, 0.91, 0.86for beef ingestion, for infant, child, teen and adult, respectively.
These elements are defined in Table 7T5. Dispersion factors;are calculated for the midpoint of each sector element (see Table 7.5). For each of these sector elements, an iaverage dose is calculated, and'then multiplied by the population in that sector element. The average dose is determined by multiplying the maximum individual dose for the sector by the ratio of the: average tothe maximum usage rates. For population doses resulting from~ingestion,.itis conservatively assumed that all foodeaten by the average individual is grown within the sector element. The-general equation used for calculating the population dose in a given sector element is: Dosepop = 0.001 ERATIOp POPm FPa DOSEp P where: 0.001 = conversion from mrem to rem.RATIOp = ratio of average to maximum dose for pathway P. Maximum ingestion rates are given in Table 6.3. (Average ingestion rates are obtained from Reference 4, Table E-4.)= 0.5 for submersion and ground exposure pathways, a shielding/occupancy factor..= 1.0 for.the inhalation pathway.= 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult,: respectively. (Itis assumed that the-ratio of average to maximum infant milk ingestion rates is:the same as that for child.)= 1.0, 0.90, 0.91, 0.86for beef ingestion, for infant, child, teen and adult, respectively.
= 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, teen and'adult, respectively. (It is assumed that the average individual eats no fresh leafy vegetables, only stored vegetables.)
= 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, teen and'adult, respectively. (It is assumed that the average individual eats no fresh leafy vegetables, only stored vegetables.)
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Xitcb (7.18)1- exp(-XitCb) where: i= decay constant for nuclide i, s1.td = distribution time for food product under consideration (values from Reference 4, Table D-1).= 1 -21 E+06 s (14 d) for vegetables.
Xitcb (7.18)1- exp(-XitCb) where: i= decay constant for nuclide i, s1.td = distribution time for food product under consideration (values from Reference 4, Table D-1).= 1 -21 E+06 s (14 d) for vegetables.
= 3.46E+05 s (4 d) for milk.= 7d for beef tcb = time to consume a whole beef, as described in Section 7.8.3.For beef ingestion, the additional .factors in the calculation of ADC negate the integration of the dose term over the period during Which a whole beef is consumed, for the calculationof population dose. Inother words, this assumes that the maximum individual freezes and eats a whole beef, while the-average individual buys smaller portions.at.a time.Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.
= 3.46E+05 s (4 d) for milk.= 7d for beef tcb = time to consume a whole beef, as described in Section 7.8.3.For beef ingestion, the additional .factors in the calculation of ADC negate the integration of the dose term over the period during Which a whole beef is consumed, for the calculationof population dose. Inother words, this assumes that the maximum individual freezes and eats a whole beef, while the-average individual buys smaller portions.at.a time.Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.
7.7.5 Reporting of Doses The calculated quarterly doses and calculated population doses described inSection,7.7 are reported in the Annual Radioactive Effluent Release Report as required by ODCM Administrative Control 5.2.El-179 WBN OFFSITE DOSE CALCULATION"MANUAL Revision 22 10 (ODCM) Page 118 of!195 7.7.6 Dose to a MEMBEROF THE PUBLIC Inside the CONTROLLED or RESTRICTED AREA The Basis for ODCM Control 1.2.2.1 states that for MEMBERS OF THEPUBLIC who may at times be within the CONTROLLED or RESTRICTED AREA, the occupancy factor of thatMEMBER OF THE PUBLIC will usually be sufficiently low to compensate for anyincrease in the atmospheric dispersion factor above that for the unrestricted area boundary.
 
====7.7.5 Reporting====
 
of Doses The calculated quarterly doses and calculated population doses described inSection,7.7 are reported in the Annual Radioactive Effluent Release Report as required by ODCM Administrative Control 5.2.El-179 WBN OFFSITE DOSE CALCULATION"MANUAL Revision 22 10 (ODCM) Page 118 of!195 7.7.6 Dose to a MEMBEROF THE PUBLIC Inside the CONTROLLED or RESTRICTED AREA The Basis for ODCM Control 1.2.2.1 states that for MEMBERS OF THEPUBLIC who may at times be within the CONTROLLED or RESTRICTED AREA, the occupancy factor of thatMEMBER OF THE PUBLIC will usually be sufficiently low to compensate for anyincrease in the atmospheric dispersion factor above that for the unrestricted area boundary.
This basis also states that examples:of calculations for such MEMBERS'OF THE PUBLIC will be given in the ODCM.Calculations are presented in Section 12.4 of the WBN UFSAR which estimate the annual doses-at the boundary of the restricted area (WBN UFSAR Table 12.4-2)ý The total dose rate is'thesufriof the adult whole body inhalation dose~rate, the gamma dose ratefrom the plume and:ground contamination, and the gamma dose rate from outdoor storage tanks. As indicated in the UFSAR, the highest total dose, rate at the boundary of the restricted area is 105 mremly, based on a continuous 2000.h/y Occupancy.
This basis also states that examples:of calculations for such MEMBERS'OF THE PUBLIC will be given in the ODCM.Calculations are presented in Section 12.4 of the WBN UFSAR which estimate the annual doses-at the boundary of the restricted area (WBN UFSAR Table 12.4-2)ý The total dose rate is'thesufriof the adult whole body inhalation dose~rate, the gamma dose ratefrom the plume and:ground contamination, and the gamma dose rate from outdoor storage tanks. As indicated in the UFSAR, the highest total dose, rate at the boundary of the restricted area is 105 mremly, based on a continuous 2000.h/y Occupancy.
Use of a more realistic occupancy, reflective of the transient traffic expected for this location, would result in a much lower dose estimate.
Use of a more realistic occupancy, reflective of the transient traffic expected for this location, would result in a much lower dose estimate.
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This is due to the revision to 10 CFR 20 implemented by TVA on 1/1194. The definitions are consistent with that regulation.
This is due to the revision to 10 CFR 20 implemented by TVA on 1/1194. The definitions are consistent with that regulation.
Similar changes are made to theBASES sections to clarify the wording where these definitions are used. Figure 3.1 shows.the locations of these boundaries and areas. A calculation is given in Section 7.7.6*for a member of;the public inside the.Site Boundary demonstrating that the location of the unrestricted area. boundary on the opposite side of the Tennessee River.meets the intent of the regulation.
Similar changes are made to theBASES sections to clarify the wording where these definitions are used. Figure 3.1 shows.the locations of these boundaries and areas. A calculation is given in Section 7.7.6*for a member of;the public inside the.Site Boundary demonstrating that the location of the unrestricted area. boundary on the opposite side of the Tennessee River.meets the intent of the regulation.
: 16. The Source Check definition' is changed to reflect changes made in the definition, for SQN (revision 27). The new definition will allow the use of internal test circuits' in:lieu of a radioactive source (some monitors use anLED light source to provide the check signal to the photomultiplier tube).17. The Operational ModesTable (Table 3.2) is consistent with the WBN TS.E1-250 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 189 of 1 95 APPENDIX C -WBN ODCM REVISION PROCESS (Page 1 of 7)This Appendix establishes the minimum requirements for preparation; review, and approval of the Watts Bar Nuclear Plant Offsite Dose Calculation Manual. This Appendix also- implements the requirements of ODCM Section 5.3 and WBN TS 5.7.2.3.1.0 Reviewer Responsibilities 1.1 Affected Organization Review (AOR)The identification of affected organizations is the responsibility of the Sponsor and applies to all revisions of the ODCM.The affected organizations shall ensure that their reviewers have adequate u'nderstanding of the requirements-and intent of the ODCM and access to pertinent background information.
: 16. The Source Check definition' is changed to reflect changes made in the definition, for SQN (revision 27). The new definition will allow the use of internal test circuits' in:lieu of a radioactive source (some monitors use anLED light source to provide the check signal to the photomultiplier tube).17. The Operational ModesTable (Table 3.2) is consistent with the WBN TS.E1-250 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 189 of 1 95 APPENDIX C -WBN ODCM REVISION PROCESS (Page 1 of 7)This Appendix establishes the minimum requirements for preparation; review, and approval of the Watts Bar Nuclear Plant Offsite Dose Calculation Manual. This Appendix also- implements the requirements of ODCM Section 5.3 and WBN TS 5.7.2.3.1.0 Reviewer Responsibilities
 
===1.1 Affected===
Organization Review (AOR)The identification of affected organizations is the responsibility of the Sponsor and applies to all revisions of the ODCM.The affected organizations shall ensure that their reviewers have adequate u'nderstanding of the requirements-and intent of the ODCM and access to pertinent background information.
The AO reviews the draft for impact on the organization and adequate interface  
The AO reviews the draft for impact on the organization and adequate interface  
-not technical content.1.2 Independent Qualified Review (IQR)An independent qualified review is the process of independent technical review by Qualified Reviewers of activities potentially affecting nuclear safety.The IQR shall NOT be the person who prepared the ODCM revision.An IQR is performed by an individual designated by responsible department Ievel managers to perform an independent technical review of activities potentially affecting nuclear safety.The IQR must be qualified to perform the 10 CFR 50.59 review.1.3 Cross Disciplinary Review (CDR)The need for a CDR is determined by the IQR.CDRis a technical review by disciplines other than those responsible for the document reparation.
-not technical content.1.2 Independent Qualified Review (IQR)An independent qualified review is the process of independent technical review by Qualified Reviewers of activities potentially affecting nuclear safety.The IQR shall NOT be the person who prepared the ODCM revision.An IQR is performed by an individual designated by responsible department Ievel managers to perform an independent technical review of activities potentially affecting nuclear safety.The IQR must be qualified to perform the 10 CFR 50.59 review.1.3 Cross Disciplinary Review (CDR)The need for a CDR is determined by the IQR.CDRis a technical review by disciplines other than those responsible for the document reparation.
The CDR is responsible for only the technical aspects of the areas specified by the IQR and any portions of the document that support or justify those areas.Persons performing CDR do not have to be IQR qualified.
The CDR is responsible for only the technical aspects of the areas specified by the IQR and any portions of the document that support or justify those areas.Persons performing CDR do not have to be IQR qualified.
1.4 Plant Operations Review Committee (PORC) Review The PORC reviews and recommends final approval of the ODCM.1.5 Approval Authority The Plant Manager will approve all revisions to the ODCM as required by Technical Specifications.
 
===1.4 Plant===
Operations Review Committee (PORC) Review The PORC reviews and recommends final approval of the ODCM.1.5 Approval Authority The Plant Manager will approve all revisions to the ODCM as required by Technical Specifications.
Signature authority shall not be delegated to a lower level manager.E1-251 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 190 of 195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 2 of 7)2.0 Processing ODCM Revisions 2.1 Requestor (If other than the Sponsor)Identify the need for an ODCM improvement.
Signature authority shall not be delegated to a lower level manager.E1-251 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 190 of 195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 2 of 7)2.0 Processing ODCM Revisions 2.1 Requestor (If other than the Sponsor)Identify the need for an ODCM improvement.
Prepare a justification for the ODCM revision.Attach a marked-up copy of the existing ODCM.Forward the requested.ODCM revision to the sponsoring organization.
Prepare a justification for the ODCM revision.Attach a marked-up copy of the existing ODCM.Forward the requested.ODCM revision to the sponsoring organization.
Line 1,144: Line 1,185:
Ensure ODCM has been reviewed by sponsor and IQR in accordance with Attachment B.Ensure all Affected Organizations have reviewed the ODCM change and have identified the affected procedures on Attachment A.Ensure all IQR, and CDR review requirements have been met.Assign an Effective Date typically 60 calendar days forward UNLESS there is reasonable justification for making it effective earlier, such as plant operating conditions, test schedules, commitment-or corrective action deadlines, or implementation of upper-tier requirements, or lack of affected procedures identified on Attachment A.2.5 PORC Review changes and Attachment B. Document recommendation for approval in BSL.2.6 Plant Manager Approve the ODCM revision in BSL.3.7 ODCM Sponsor Record the ODCM approval date and implementation date on each completed Attachment Aý provided by the affected organizations.
Ensure ODCM has been reviewed by sponsor and IQR in accordance with Attachment B.Ensure all Affected Organizations have reviewed the ODCM change and have identified the affected procedures on Attachment A.Ensure all IQR, and CDR review requirements have been met.Assign an Effective Date typically 60 calendar days forward UNLESS there is reasonable justification for making it effective earlier, such as plant operating conditions, test schedules, commitment-or corrective action deadlines, or implementation of upper-tier requirements, or lack of affected procedures identified on Attachment A.2.5 PORC Review changes and Attachment B. Document recommendation for approval in BSL.2.6 Plant Manager Approve the ODCM revision in BSL.3.7 ODCM Sponsor Record the ODCM approval date and implementation date on each completed Attachment Aý provided by the affected organizations.
Return the Attachment A to each affected organization.
Return the Attachment A to each affected organization.
3.8 Affected Organization Revise procedures identified on the Attachment A and assign an effective date which matches that of the ODCM revision.Complete the Attachment A and return to the ODCM Sponsor.El-253 WBN OFFSITE DOSE CALCULATIONWMANUAL Revision22 0 (ODCM) Page '192 of 195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 4 of 7)3.9 ODCMSponsor Ensure all Affected Organizations have completed and returned Attachment A prior to the effective date of the ODCM.Forward the approved ODCM change to Management Services at least three working days before the implementation date.The completed Attachments A and B are QA records, and are handled in accordance with the Document Control and Records Management Program.Forward a completedocopy of each revision to Licensing to be filed and forwardedto theNRC in the Annual Radiological Effluent Release Report.3.10 Management Services Issue the ODCM and implementing procedures onthe effective date-of the ODCM revision.El -254 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 193 of 195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 5 of 7)Attachment A ODCM Affected Organization Review/Implementation Proposed ODCM Revision No.Expected PORC Review Date: Expected Effective Date: Affected Organization:  
 
===3.8 Affected===
Organization Revise procedures identified on the Attachment A and assign an effective date which matches that of the ODCM revision.Complete the Attachment A and return to the ODCM Sponsor.El-253 WBN OFFSITE DOSE CALCULATIONWMANUAL Revision22 0 (ODCM) Page '192 of 195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 4 of 7)3.9 ODCMSponsor Ensure all Affected Organizations have completed and returned Attachment A prior to the effective date of the ODCM.Forward the approved ODCM change to Management Services at least three working days before the implementation date.The completed Attachments A and B are QA records, and are handled in accordance with the Document Control and Records Management Program.Forward a completedocopy of each revision to Licensing to be filed and forwardedto theNRC in the Annual Radiological Effluent Release Report.3.10 Management Services Issue the ODCM and implementing procedures onthe effective date-of the ODCM revision.El -254 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 193 of 195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 5 of 7)Attachment A ODCM Affected Organization Review/Implementation Proposed ODCM Revision No.Expected PORC Review Date: Expected Effective Date: Affected Organization:  
[ ] Operations  
[ ] Operations  
[ I RADCON[ Chemistry  
[ I RADCON[ Chemistry  
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==1.0 INTRODUCTION==
==1.0 INTRODUCTION==


1.1 PURPOSE The purpose of the Watts Bar Nuclear Plant (WBN):Process ControlIProgram (PCP)is to establish a program which provides reasonable assurance that all radioactive wastes processed at WBN for disposal at a land disposal facility are processed and packaged such that applicable Federal and State regulations and disposal site criteria are satisfied.
===1.1 PURPOSE===
The purpose of the Watts Bar Nuclear Plant (WBN):Process ControlIProgram (PCP)is to establish a program which provides reasonable assurance that all radioactive wastes processed at WBN for disposal at a land disposal facility are processed and packaged such that applicable Federal and State regulations and disposal site criteria are satisfied.
The PCP contains a general description of the methods for controlling the processing and packaging of radioactive wastes, specific parameters for each method, and the administrative controls and quality assurance required to ensure compliance with applicable regulations and requirements.
The PCP contains a general description of the methods for controlling the processing and packaging of radioactive wastes, specific parameters for each method, and the administrative controls and quality assurance required to ensure compliance with applicable regulations and requirements.
This PCP is not applicable to wastes transported to an off-site vendor for processing.
This PCP is not applicable to wastes transported to an off-site vendor for processing.
1.2 SCOPE This PCP applies to the processing of wet solid radioactive wastes generated as a result of plant operation and maintenance.
 
===1.2 SCOPE===
This PCP applies to the processing of wet solid radioactive wastes generated as a result of plant operation and maintenance.
This PCP does not apply to the treatment of mixed radioactive and hazardous wastes.E2-5 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 5of 14 2.0 DETAILS 2.1 WASTE CHARACTERISTICS A. Waste Streams 1. There are six waste streams that have been identified at WBN. These are primary resins, secondary resins, mobile demineralizer resin, filter elements, oil, and dry active waste.(DAW).
This PCP does not apply to the treatment of mixed radioactive and hazardous wastes.E2-5 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 5of 14 2.0 DETAILS 2.1 WASTE CHARACTERISTICS A. Waste Streams 1. There are six waste streams that have been identified at WBN. These are primary resins, secondary resins, mobile demineralizer resin, filter elements, oil, and dry active waste.(DAW).
This POP is not normally applicable to DAW. Other waste streams may be identified based upon plant operating characteristics.
This POP is not normally applicable to DAW. Other waste streams may be identified based upon plant operating characteristics.
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: 3. Calculational methods for determining the total activity in each container shall be developed which utilizes the results from the annual analysis.4. The classification program shall establish criteria and include provisions for an increased frequency for sampling and analysis-required by paragraph 1 above, if the waste stream isotopic content may have :changed by a factor of 10.2.2 PROCESSING OF WET RADIOACTIVE WASTE A. Processing Methods Wet radioactive waste processed at WBN shall be processed into a form acceptable for disposal at a licensed facility.
: 3. Calculational methods for determining the total activity in each container shall be developed which utilizes the results from the annual analysis.4. The classification program shall establish criteria and include provisions for an increased frequency for sampling and analysis-required by paragraph 1 above, if the waste stream isotopic content may have :changed by a factor of 10.2.2 PROCESSING OF WET RADIOACTIVE WASTE A. Processing Methods Wet radioactive waste processed at WBN shall be processed into a form acceptable for disposal at a licensed facility.
Processing shall be performed utilizing vendor supplied equipment operated in accordance with the vendor's PCP and procedures.
Processing shall be performed utilizing vendor supplied equipment operated in accordance with the vendor's PCP and procedures.
Any vendor selected to provide services or products used for compliance with 10 CFR 61 stability requirements shall have a topical report addressing 10 CFR 61 requirements under review or approved by the NRC. The topical reports and PCP's of other vendors may be referenced in this PCP even if all vendors are not actively providing service or products at WBN.However, if any vendor is selected whose documents are not referenced, this document shall be revised to reference them.B. System Qualification Tests 1. Prior to the initial solidification of a given waste stream using a specified process, a test shall be conducted to demonstrate the ability of the process to produce an acceptable waste form over the range of critical parameters identified during the prequalification testing. Bounds for critical parameters and specific operating limits shall be specified in the vendor's PCP.2. These tests shall be performed on laboratory scale or full scale specimens and shall ensure that the acceptance criteria specified in Section 2.2.E are achieved.3. The-dewatering process shall specify an endpoint for each dewatering evolution so as to assure that the acceptance criteria specified in Section 2.2.E are achieved.E2-8 2.2 PROCESSING OF WET RADIOACTIVE WASTE (continued)
Any vendor selected to provide services or products used for compliance with 10 CFR 61 stability requirements shall have a topical report addressing 10 CFR 61 requirements under review or approved by the NRC. The topical reports and PCP's of other vendors may be referenced in this PCP even if all vendors are not actively providing service or products at WBN.However, if any vendor is selected whose documents are not referenced, this document shall be revised to reference them.B. System Qualification Tests 1. Prior to the initial solidification of a given waste stream using a specified process, a test shall be conducted to demonstrate the ability of the process to produce an acceptable waste form over the range of critical parameters identified during the prequalification testing. Bounds for critical parameters and specific operating limits shall be specified in the vendor's PCP.2. These tests shall be performed on laboratory scale or full scale specimens and shall ensure that the acceptance criteria specified in Section 2.2.E are achieved.3. The-dewatering process shall specify an endpoint for each dewatering evolution so as to assure that the acceptance criteria specified in Section 2.2.E are achieved.E2-8  
 
===2.2 PROCESSING===
 
OF WET RADIOACTIVE WASTE (continued)
C. Batch Processing Each batch of waste offered for processing shall be sampled and analyzed, as appropriate, in accordance with site procedures, the vendor's PCP and the topical report that addresses the 10 CFR 61 stability requirements.
C. Batch Processing Each batch of waste offered for processing shall be sampled and analyzed, as appropriate, in accordance with site procedures, the vendor's PCP and the topical report that addresses the 10 CFR 61 stability requirements.
This sampling shall: 1. Provide the necessary data to estimate curie content and to perform the waste classification analysis.2. When solidification is involved, sampling shall provide data necessary to: a. Ensure that waste stream parameters are within the bounds for. critical parameters established in the vendor's PCP and topical report.b. Verify the application of preestablished mix ratios.D. Testing/Inspections
This sampling shall: 1. Provide the necessary data to estimate curie content and to perform the waste classification analysis.2. When solidification is involved, sampling shall provide data necessary to: a. Ensure that waste stream parameters are within the bounds for. critical parameters established in the vendor's PCP and topical report.b. Verify the application of preestablished mix ratios.D. Testing/Inspections

Revision as of 03:04, 14 October 2018

Watts Bar, Unit 1, 2009 Annual Radioactive Effluent Release Report
ML102080384
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 12/31/2009
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
References
Download: ML102080384 (272)
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Text

Enclosure I Watts Bar Nuclear Plant 2009 Annual Radioactive Effluent Release Report El-1 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTEý DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION-

1. Regulatory Limits A. Gaseous Effluents 1. Dose rates due~to radioactivity released in gaseous effluents from the site to areas at and beyond the unrestricted area boundary shall be limited to the following:
a. Noble gases: -Less than or equal to 500 mrem/year to the total body.-Less than or equal to 3000 mrem/year to the skin.b. Iodine-i 31, iodine-133, tritium, and all radionuclides in: particulate form.with half-lives greater than 8 days:-Less than or equal to 1500 mrem/year to any organ.2. Air dose due to noble gases released in gaseous effluents~toareas at and beyond the unrestricted area, boundary shall be limited to the following:
a. Less than or equal to, 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation during any calendar quarter.b. Less than or equal to, 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation during any calendar year.3. Dose to a member of the public from iodine-131, iodine-i;33, tritium, and.all radionuclides in particulate form with half-lives greater than eight days in gaseouseffluentsý.released to areas at and beyond the unrestricted area boundary shall be limited to the following:
a. Less than or equal to 7.5 mrem to any organ during any calendar quarter..b. Less than or equal to 15 mrem to any organ during any calendar year.B. Liquid Effluents 1. The concentration of radioactivity released in liquid effluents.to unrestricted areas shall be limited to 10times the concentrations specified in Title 10.of of Federal Regulations, Part 20 (Standards for Protection Against Radiation), Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 9Ci/ml total activity.2. The dose or dose commitment to a member of the public from radioactivity in.:liquid effluents released to unrestricted areas shall be limited to: a. Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ during any calendar quarter.b. Less than or equal to 3 .mrem to the total body and less than or equal to 10. mrem to any organ during any calendar year.E1-2 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION
2. EffluentConcentration Limits A. Liquids The Effluent Concentration Limits (ECL) for liquids are those listed in 10 CFR 20, Appendix B, Table 2, Column 2. For dissolved and entrained gases the ECL of 2.0E-04 jiCi/ml is-applied.

This ECL is based on :the Xe-1 35 concentration in air (submersion dose) converted to an equivalent.

concentration in water as discussed in the International Commission on Radiological Protection (ICRP), Publication 2.B. Gaseous Concentration limits forgaseous releases are met through compliance with the maximum permissible~dose -rates for gaseous releases as defined in plant;OffsiteDose Calculation Manual (ODCM) and presented in Section 1 .A.1 of this report.3. Average Energy WattsBar's ODCM limits the dose equivalent rates due to the release of-noble gases to-, less than or equal to 500 mrem/year to the total body and less than or equalkto 3000 mrem/ye~arto the skin.Therefore, the average beta and gamma energies (E) for gaseous effluents as described, in Regulatory Guide 1.21, "Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-booled Nuclear Power Plants," -are not applicable.

4. Measurements and Approximations of Total Radioactivity Radioactivity measurements performed in support of the WBN Offsite Dose Calculation Manual (ODCM) meet the Lower Limit of Detection requirements given in ODCM Tables 2.2-1 and 2.2-2.A. Liquid:Effluents Batch (Radwaste and Condensate Demineralizer tanks)Total gamma isotopic activity concentrations are determined on each Radwaste and Condensate Demineralizer batch tank prior to release. The total activity of-a batch release is-obtained by determining the concentration of each nuclide and then multiplying--by-the volume discharged to arrive at~the curieactivity for each nuclide. The curies of each nuclide are then summed.Composite samples are maintained and analyzed monthly for tritium and gross alpha, and quarterly for Iron-55, Strontium,89, and Strontium-90.

Duringperiods of'no-significant identified primary to secondary leakage, composite samples are not maintained'for Condensate Demineralizer Tank releases and the feedwater tritium concentration lis used to determine the curies of.tritium released from Condensate DemineralizerTank.

El-3 2009 WATTS BAR NUCLEAR PLANT EFFLUENTAND WASTE DISPOSAL ANNUALREPORT SUPPLEMENTAL INFORMATION Continuous Releases (Turbine Building Sump, Steam Generator Blowdown, and-Groundwater Sump)During periods of no significant identified primary to secondary leakage,-thevolume released from, the TBS and SGB is obtained.

The TBS tritium concentration is determined via weekly grab, samples. The feedwatertritium concentration is usedito determine the curies of tritium released from SGB. The Groundwater Sump is sampled monthly and analyzed for gross gammaand tritium on a monthly basis and Sr-89, and Sr-90 quarterly.

The total activity released, is obtained by determining the concentration of each nuclide and then, multiplyingý bythevolume discharged to arrive at the curie activity for each nuclide.Monitoring Wells WBN started conducting an investigation of tritium releases to the groundwater' in 2003 due to identification of tritium in three of the four newly installed n-.site monitoring wells.associated with theDOE tritium production program site preparation activity.in December,2002.

This study involved pressuretesting of the radwaste discharge:

line,. evaporation calculations of the SFP and RWST, installationand sampling of.groundwater wells, inspection of, drainm lines boroscopic investigation of the.SFP, and FTC leak collection system.channels and drains.., In addition to the Six.(6) Radiologocial Environmental Montioring Program (REMP) on-site groundwater monitoring wells, Watts Bar Nuclear Plant also has.37 non-REMP monitoring wells tosupport monitoring the onsite groundwater plume for the presence.

or increase of radioactivity.

Watts Bar contracted ARCADIS in 2004 to perform .an investigation of the impact tritium, had on, groundwater and perform a site characterization, area of impact,.and preliminary human. health and ecological risk screening.

ARCADIS has been contacted to update these same evaluations this year.The non-REMP on-site monitoring wells are sampled semi-annually;for gamma and tritium. These wells continue to exhibit a downward trend. The tritium. concentrations obtained in 2009 from these non-REMP monitoring wells are listed below. Wells K, L, R, and S samples were- analyzed for Sr-89, Sr-90, Fe-55, and Ni-63 which the results were all nondetectable.

04/30/2009 10/27/2009 Activity Activity Well ID pCi/L pCi/L B 3,843 2,573 C 720 171 D 2;912 1,583 F 2,579 2,906 I 403 358 J 376 <266 K 19,165 3,947 L 14,200 8,377 R 1,737 1,724 S 628 <266 Onsite Radioactive Spills or Leaks There were no onsite radioactive spills or leaks.E1-4 2009 WATTS BAR NUCLEAR PLANT EFFLUENT.

AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION Doses from 1-131 Water Ingestion Pathway The radiological environmental monitoring program (REMP),requirements:as specified in Table 3.12-1 from NUREG 1301, "Offsite Does Calculation Manual Guidance:

Staandard lRadiological Effluent Controls for Pressurized Water Reactors" April ,1991, requires an 1-131 specific analysis for drinking water pathway samples if the annual dose fr0m 1-.131 is greater than 1 mrem. In order to.evaluate the need for implementation of this additional analysis, the drinking water pathway dose from 1-131 to the maximum organ and age group4was calculated.

'The results reportedhere confirm that the drinking water pathway dose from 1-131 was onlya small fraction of the 1 mrem limit and that the performance of the 1-131 specific analysis is not required for WBN REMP drinking water samples.Quarter 1 2 3 4 Totals 1-131 Ci 1.67E-06 0,00E+00 0010E+00 0.QO E00E 167E-06 Child/Thyroid (mrerm) 1.1E-06 0.OOE+00 0.00E+00 r, 0.OOE+00 1.1%E-06 Population/Thyroid (torer) 6.8E-06 0.OOE+00 0.00E+00 0.OOE+0Q 6.8E-06 I El-5 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION B.. Fission and Activation Gases Airborne effluent gaseous activity is continuously monitored and recorded.

Weekly igrab samples from the auxiliary building andimonthly grab samples from the service building'aire-,taken and analyzed to determine the quantity of noble gas activity released based on the -total flows for the sample period. Also, noble gas samples arecollected and evaluated following startup, shutdown, or rated thermal, power change exceeding 15 percent within one. hour (sampling only required if dose equivalent 1-1i31 concentration in the primary coolant or thenoble gas activity monitor shows that the containment activity has increased more'than a factor- of 3).The concentration of noble gases released through the shield building exhaust d ue to purging of containment.is determined by using the purge monitor response in .combination:

with containment air samples obtained prior to purge. The quantityofactivity released during the purge. is determined using .the duration, flowrate, and concentration of noble gases determined for each purge. Also, noble gas samples are collected and evaluated for ongoing,.containment, purges following startup, shutdown, or rated thermal power change exceeding 15 percent within one hour (sampling only required if DErconcentration in the primary coolantor the noble gas activity monitor shows that the containment activity has increased more thanha-factor-of 3).The quantity of noble gases released through the shield building-exhaust due to the batch release of waste gas decay tanks is determined by sampling each tank priorito release: The totalcaCtivity released is determined from the total pressure change recordedfor tlhetank during the release.C. lodines and Particulates in Gaseous Releases Iodine and particulate activity is continuously sampled. Weekly charcoal and particulate samples aretaken from the shield building exhaust and auxiliary building exhausts and fromýcondenser vacuum exhaust during periods of primary to secondary leak. These samples, are analyzed at least weekly to determine the total activity released from the plant based on the'total vent flows recorded for the sampling period. Also, particulateand charcoal sam"ples are taken from the shield building exhausts, auxiliary building exhaust, and condenser vacuum exhaustwhen a primary to secondary leak exist once per'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following" startufp, shutdown, or a rated thermal power change exceeding 15 percent within one hour (if doseequivalent 1-131 concentration in the-primary coolant or the noble gas activity monitor shows that the containment activity has increased more than a factor of 3).El-6

5. B 2009 WATTS BAR NUCLEARPLANT' EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION atch Releases Value 1st Half 2nd Half A. Liquid (Radwaste only)1. Number of releases 40 64 2. Total time period of releases 5955 1,0002 3. Maximum time period of release 304 381 4. Average time period of releases 80 2 5. Minimum time period for release 80 2 6. Average dilution stream flow during 24,535 38;P98 release. periods B. Gaseous (Batches only -containment purges, and waste gas decay tanks)1. Number of releases 24 21 2. Total-time period of releases 5203 36317 3. Maximum time period for release 17 1729 4. Average time.period for releases 3 6 5. Minimum time period for release Units Each Minutes Minutes Minutes Minutes CFS Each Minutesi, Minutes Minutesl Minutest Units 6. Abnormal Releases A. Liquid Number of Releases Total Activity Released Value 1st Half 2nd Half 0 0 0.OOE+00 0.OOE+00 Ci B. Gaseous Number of Releases Total Activity Released 0 0 0.OOE+00 0.OOE+00 Ci E1-7 t 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTEIDISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 1-A Liquid Effluents

-Summation of All Releases During the.period Starting:

1-Jan-2009 Ending: 30-Jun-2009,'Est.Tot Type Of Effluent Units QuarterI, Quarter 2 Error %A. Fission & Activation:ProdUcts

1. Total Release (Not Including Tritium, Ci 1.91E-03 5.23E-03 25%Gases,. Alpha)2. Average Diluted:Concentration During pCi/mI 2.96E-10 3.19E-10 Period 3. Percent Of Applicable Limit %* *B. Tritium 1. Total Release Ci 4.OE+01 8.84E+02 1:8%2. Average Diluted Concentration During pCi/mI 6.19E-06 5'40E-05: Period 3. Percent Of Applicable Limit %* *C. DissIlved And Entrained Gases 1. Total Release Ci 8.88E-04' 8.27E-03 39%2. Average Diluted Concentration During pCi/mI 1.37E-10 5.05E-10 Period 3. Percent Of Applicable Limit % 6,87E-05 2.52E-04 D. Gross, Alpha RadioactiVity.
1. Total Release Curies O.OOOE+00**

O.OOOE+00*

N/A***E. Total Waste Volume Released Liters 2.68E+08 1,,82E+08 2%(Pre-Dilution)

F. Volume Of Dilution Water Used Liters 6:46E+09 1.64E+10 12%G. Radwaste Volume Released Liters 5.13E+05 1.1i2E+06 12%* AppJicable limits are expressed in-terms of dose. See Table 7A of this report..** Zeroes in this table indicate that no radioactivity was present at detectable levels.N/A -Errors in measurements are not reported for these-values:

since none were identified during the reporting period.E1-8 2009 WATTS BAR NUCLEAR PLANT,'EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 1-B Liquid Effluents

-,Summation of All Releases During the period Starting:

1-Jul-2009 Ending: 31-Dec-2009.Est. Tot Type Of Effluent Units Quarter*3 Quarter 4- Error %A. Fission & Activation Products.1. Total Release (Not Including Ci 3.54E-02 4M63E-02 25%Tritium, Gases, Alpha)2. Average Diluted Concentration.

pCi/ml 2.25E-09 8.49E-09 During Period 3. Percent Of Applicable Limit %* *B. Tritium 1. Total Release Ci 8.90E+02 2.53E+02 18%2. Average Diluted Concentration pCi/ml 5.66E-05 4.64E-05 During Period 3. Percent Of Applicable Limit %C. Dissolved And Entrained Gases 1. Total Release Ci 5.39E-03 7.37E&04 39%2. Average Diluted Concentration pCi/ml 3.43E-10 1.35E-10 During Period 3. Percent Of Applicable Limit % 1.71 E-04 6.76E-05 D. Gross Alpha Radioactivity

1. Total Release Ci O.OOE+00**

0.00E+0 , E. Total Waste Volume Released Liters 2.68E+08 ,1.82E+08 2%(Pre-Dilution)

F. Volume Of Dilution Water Used Liters 1.57E+10 5.45E+09 12%, G. Radwaste Volume Released Liters 1.58E+06 1.03E+06 12%*k"**Applicable limits are expressed in terms of dose. See Table.7B of this report.Zeroes in this table indicate that no. radioactivity was presentr.at detectable levels.N/A -Errors in measurements are not reported for these values since none were identified during the reporting period.E1-9 2009 WATTS BAR NUCLEAR PLANT EFFLUENT:AND WASTE'DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 2-A Curies Released in Liquid Effluents During the period ,Starting:

1-Jan-2009 Ending: 31-Mar-2009.CONTINUOUS BATCH TOTAL, H-3 4.77E-01 3.95E+01 4.OOE+01 FISSION & ACTIVATION PRODUCTS CO-57 O.OOE+00 3.52E-06*

3.52E-06 CO-58 O.OOE+00 2.25E-04 2.25E-04 CO-60 0.00E+00 1 .87E-04j 1.87E-04 CS-137 'O.00E+00 1.85E-06 1.85E-06 FE-55 0.00E+00 9.34E-04 9.34E-04 1-131 O.OOE+00 1.67E-06 1.67E-06 1-133 O.OOE+00 1.40E-06 1.40E-06 MN-54 O.OOE+00 2.80E-06 2.80E-06 SB-1 22 O.OOE+00 1.82E-06 1.82E-06 SB-1 25 0.OOE+00 5.06E-04 5.06E-04 SN-117M O.OOE+00 9.54E-06 9.54E-06 SR-89 O.OOE+00 1.54E-05 1.54E-05 SR-90 O.OOE+00 1.52E-05 1.52E-05 TOTALS O.OOE+00 1.91 E-03 1.91 E-03 DISSOLVED AND ENTRAINED GASES XE-133 0.00E,00 8.03E-04 8.03E-04 XE-135 O.OEtOO 8&51E-05 8,51E-05 TOTALS obO0E+00 8.88E-04 8.88E-04* Zeroes in this table indicate that no radioactivity was present at detectable levels.El-10 2009 WATTS. BARNUCLEAR PLANT , EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 2-B Curies Released in Liquid EfflUents During the period Starting:

1-Apr-2009 Ending: 30-Jun-2009 CONTINUOUS BATCH TOTAL H-3 4.75E-01 >8.83E+02 8.84E4-02 FISSION & ACTIVATION PRODUCTS CO-57 0.OOE+00 1.84E-06 1.84E&06 CO-58 0.00E+00 1.15E-03 1:15E-03 CO-60 O00E+00 3.13E-04 3.13E&04 CS-1 37 M0OE+00 6.24E-06 6.24E-06 FE-55 0.00E+00 3.47E-03 3"47E-03 MN-54 0.00E+00 3.66E-06 3.66E-06 SB-125 0.OOE÷00 1;58E-04 1.58E-04 SR-89 0.OOE+00 1.25E-04 1.25E-04 TOTALS 0.OOE+00 5.23E-03 5.23E-03 DISSOLVED AND ENTRAINED GASES KR-85M 0.00E+00 2.75E-06 2.75E&06 XE-133 0.00E+00 7.80E-03 7.80E&03 XE-133M O0OOE+00 7.87E-05 7,87E-05 XE-135 0.OOE+00 3.87E-04 3.87E-04 TOTALS 0.OOE+00 8.27E-03 8.27E-03*Zeroes in this table indicate that no radioactivity was present at detectable levels.El-11 2009 WATTS BAR NUCLEAR PLANT EFFLUENT ANDWASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 2-C Curies Released in Liquid Effluents During the period Starting:

1-Jul-2009 Ending: 30-Sep-2009 CONTINUOUS BATCH TOTAL H-3 4.97E701, 8.89E+02 8.90E+.02 FISSION & ACTIVATION PRODUCTS CO-58 0.OOE+00 1.39E-03 1.39E-03 CO-60 O.OOE+00 5.26E-04 5.26E-04 CS-137 0.OOE+00 8.32E-06.

8.32E-06 FE-55 O.OOE+oo 3.30E-02 3.30E-02 FE-59 O.OOE+00 4.32E-06 4.32E-06 1-132 O.OOE+00 4.61E-06 4.61&E06 MN-54 O.OOE+00 2.24E-06 2.24&E06 SB-122 O.OOE+00 7.37E-06 7.37E-06: SB-124 O.OOE-OO 2.12E-05 2.12E-05 SB-125 O.OOE+00 1.06E-04 1.06E-04 SN-117M O.OOE+00 4.1.1E-06 4.11E-06 SR-89 0.00E+00 3.50E-04 3.50E-04 TOTALS O.OOE+00 3.54E-02 3.54E-02 DISSOLVED AND ENTRAINED GASES KR-85M 0OOE+÷00 1.79E-05 1.79E-05 XE-131M O.OE+O00 5.61E-05 5.61E-05 XE-133 OOOE+00 5.01 E-02 5.01E-02 XE-133M O.OOE+00 8.38E-04 8.38E-04 XE-135 0.00E+00 2.97E-03 2.97E--03.TOTALS O.OOE+00 5.39E-02 5.39E-02*Zeroes in this table indicate that no radioactivity was, present at detectable levels.El-12 2009 WATTS BAR.NUCLEAR PLANT EFFLUENT ANDWASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 2-D Curies Released in Liquid Effluents During the period Starting:

1-Oct-2009 Ending: 31-Dec-2009 CONTINUOUS -BATCH TOTAL H-3 3.75E-01 2.53Et02 2,.53E+02 FISSION & ACTIVATION, PRODUCTS CO-58 1.05E-02 4.25E703 1.48E-02 CO-60 7.98E-04 1.65E-04 9.63E&04 CR-51 5.30E-03 1.51E-04 5.45E-03 CS-134 O.OOE+00 1.58E,06 1.58E-06 CS-137 O.OOE+00 4.18E-06 4.18E-06 FE-55 1.96E-02 2.48E-03 2.21E-02, FE-59 3.79E-04 O.OOE+00 3.79E-04 MN-54 5.54E-04 2.31E-06 5.56E-04 NB-95 9.03E-04 1.20E-06 9.04E:04 SB-124 O.OOE+00 7.03E-06 7.03E&06 SB-125 O.OOE+00 1.84E-04 1.84E&04 SN-1 17M O.OOE+00 5.89E-05 5.89E-05 ZR_95 9.63E-04 O.OOE+00 9.63Er04 TOTALS 3.90E-02 7.31 E-03 4.63E-02 DISSOLVED AND ENTRAINED GASES XE-133 O.OOE+00 7.37E-04 7.37E-04 TOTALS O.OOE+00 7.37E-04 7.37E-04* Zeroes in this table indicate that no radioactivity was present at detectable levels.E1-13 2009 WATTS BAR NUCLEARPL.ANT EFFLUENT AND WASTE DISPOSALANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 3-A Gaseous Effluents

-Summation of All Releases During the period Starting:

1-Jan-2009 Ending: 30-Jun-2009 Est. Tot Type Of Effluent Units Quarter I Quarter. 2 Error %A. Fission & Activation Products 1. Total Release Ci 8.84E-02 3.42E+00 22 2. Average Release Rate For Period pCi/sec 1.14E-02 4.34E-01 3. PercentOf Applicable Limit %* *B. Radioiodines

1. Total Iodine-131 Ci 1.03E-06 1.51E-06 12 2. Average Release Rate, For: Period pCi/sec 1.32E-07 1.92E-07 3. Percent Of Applicable Limit %* *C. Particulates
1. Particulates

.(Half-Lives>8 Days) Ci 0.000E+00 0000E+00 N/A***2. Average Release Rate For Period pCi/sec O.00OE+00 O.OOE+00 3. Percent Of Applicable Limit %* *4. Gross Alpha Radioactivity Ci O.OOOE+00 0:O.0E+00 D. Tritium 1. Total Release 2. Average Release Rate For Period 3. Percent Of Applicable Limit Ci pCi/sec 3-04E+01 3.91 E+00 6.31 E+00 8.02E-01 11**Applicable limits are expressed in terms of dose. See Table 6A of this report.Zeroes in this table indicate that no radioactivity was present at detectable, levels.N/A -Errors in measurements are not reported for these values since none were identified'during the reporting period.E1-14 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL, REPORT SUPPLEMENTAL INFORMATION TABLE 3-B Gaseous Effluents

-Summation.

of All:'Releases During.the period Starting:

1-Jul-200g Ending: 31-D ec-2009 Est. Tot Type Of Effluent Units Quarter 3 Quarter.4 Errror%A. Fission. &-'Activation Products 1. Total Release Ci 7.48E-01, 1.188E+60 22 2. Average Release Rate: For Period pCi/sec 9.41 E-02 1 49L-01 3. Percent Of Applicable Limit %* *B. Radioiodines

1. Total iodine-131 Ci 2.59E-07 1.85E-04 12 2. Average Release, Rate For Period pCi/sec 3.26E-08 2.33E-05 3. Percent'OfApplicable Limit %* *C. Particulates:
1. Particulates (Half-Lives>8&Days)

Ci 8&98E-05 O.000E+O ***N/AO 2. Average Release Rate:For Period pCi/sec 1.13E-05 0.000E+00 3. Percent Of Applicable Limit %* *4. Gross AlphawRadioactivity Ci O.0OOE+00

.0.000E+00, D. Tritium 1. Total Release 2. Average Release Rate For Period 3. Percent Of Applicable Limit Ci pCi/sec 9.92E+00 1.25E+00 6.93E+00 8.71 E-01 11"**k" Applicable limits are expressed in terms of dose. See Table, 6.-B.of this report.Zeroes in this table indicate thatno radioactivity was present at, detectableb, levels.N/A -Errors in measurements are not reported for these values since none Were identified during the reporting period.E1-15 2009 WATTS BAR NUCLEARPLAINT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 4-A Curies released in Gaseous Ground Level Releases During the period Starting:

1-Jan-2009 Ending: 31-Mar-2009 CONTINUOUS BATCH TOTAL FISSION GASES Xe-w 33m O.00E÷00 4.92E-05 4.92E-05 Xe-1 31 m O.0OE+00 4.37E-04 4.37E-04 Kr-85 O.OOE+00 1.67E-03 I67E-03 Xe-135 O.OOE+00 1.43E-03 1.43E-0.3 Ar-41 O.OOE+00 3.18E-02 3.18E&02 Xe-133 O.00E+00 5.30E-02 5.30E'02 TOTALS O.OOE+00 8.84E-02 8.84E-02 IODINES 1-131 1.03E-06 O.OOE+00 1.03E-06 1-133 8.48E-06 O.OOE+00 8.48E-06 TOTALS 9.51E-06 O.OOE÷00 9.51 E-06 PARTICULATES TOTALS O.OOE+00 O.OOE+00 O.00E+00 H-3 3.04E+01 O.OOE+00 3.04E+01* Zeroes in this table indicate that no radioactivity was present at detectable levels.E1-16 2009 WATTS BAR NUCLEARPLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 4-B Curies released in Gaseous Ground LevelIReleases During theperiod Starting:

1-Apr-2009 Ending: 30-Jun-2009 CONTINUOUS FISSION GASES Xe-1 35 Ar-41 Kr-85 Xe-1 33 TOTALS IODINES 1-131 1-133 TOTALS PARTICU LATES TOTALS Br-82 H-3 7.15E-01 O.OOE+00 O.OOE+00 1.97E+00 2.69E+00 1.51 E-06 1.16E&05 1.31 E-05 1.07E-07 6.31 E+00 BATCH 1.60E-02 2.24E-01 9.64E-04 4.86E-01 7.27E-01 O.OOE+00O O.OOE+-00 O.OOE+O0 O.OOE+00 O.OOE+00 TOTAL 7.31 E01 2;24E-01 9.64E-04 2.46E+00 3.42E+00 1.51 E-06 1.16E-05 1.31 E705 1-.07E-07 6.31 E+00* Zeroes in this table indicate that no radioactivity was present at'detectable levels.EI-17 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION.

TABLE 4-C Curies released in Gaseous Ground Level[Releases During the period Starting:

1-Jul-2009 Ending: 30-Sep-2009 CONTINUOUS BATCH TOTAL FISSION GASES Kr-88 O.OOE+00 1.79E-04 1.79E-04 Kr-85m O.OOE+00 2.11E-04.

2. 11 E-04 Xe-133m O.OOE+00 1.21E-03 1.21 E-03 Kr-85 O.OOE+00 2.29E-03 2.29E-03 Xe-131m O.OOE+00 5.17E-03 5.17E-03 Xe-135 O.OOE+00 1.47E-02 1.47E-02 Ar-41 O.OOE+00 1.64E-01 1 .64E-01 Xe-133 1.09E-01 4.51E-01 5.60E-01 TOTALS 1.09E-01 6.39E-O1 7.48E-01 IODINES 1-133 1.26E&1 1 O.OOE+00 1.26E-& 1 1-131 2.59E-07 O.OOE+00 2.59E-07 1-132 4.44E-05 O.OOE+00 4.44E-05 TOTALS 4.46E-05 O.OOE+OO 4.46E&05 PARTICULATES Co-58 8.41 E-06 O.OOE+00 8.41 &06 Mn-54 1.20E-05 0.OOE0oO 1.20E-05 Co-60 6.94E-05 O.OOE+00 6.94E-05 TOTALS 8.98E-05 O.OOE'+00 8'98E-05 H-3 9.92E+00 O.OOE+00 9.92EO00 Zeroes in this table indicate that no radioactivity was present at detectable levels.E1-18 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL.ANNUALL REPORT SUPPLEMENTAL INFORMATION TABLE 4-D Curies released in Gaseous Ground Level Releases During the period Starting:

1-Oct-2009 Ending: 31-Dec-2009 CONTINUOUS BATCH TOTAL FISSION GASES Kr-85 O.OOE+00 5.86E-07 5.86E-07 Xe-131m 0,00E+00 8.00E-04 8.00E-04 Xe-135 3.69E-01 9.69E&03 3.79E-01 Ar-41 O0OOE+00 2.51 E-01 2.51 E-01 Xe-133 2.02E-01 3.51E-01 .5.53E-01 TOTALS 5.71E-01 6.12E-01 1.18E+00 IODINES 1-131 1.85E-04 O.OOE+00 1.85E-04 1-132 2.18E-04 O.OOE+00 2.18E-04 TOTALS 4.04E-.04 O.OOE+O0 4.04E&04 PARTICULATES TOTALS O.OOE+00 O.OOE+00 O.OOE+00 H-3 6.93E+00 O.OOE+00 6.93E+00O* Zeroes in this table indicate that no radioactivity was present at detectable levels.E1-19 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 5-A SOLID WASTE (RADIOACTIVE SHIPMENTS)

A. Solid Waste Shipped Offsite for Burial or Disposal (not Irradiated Fuel)12 Month Est. (Ci)1. Type of Waste Unit Period Error%m~3 a. Spent resins, filter sludges, evaporator 48.5 N/A bottoms, etc. Ci 160.0 +/-25%b. Dry Active Waste, Compressible Waste m 3 397.0 N/A Contaminated Equipment, etc. Ci 1.41 +/-25%c. Irradiated Components, Control m 3 None N/A Rods, etc. Ci None N/A 2. Estimate of Maior Nuclide Composition (by tvne of waste)Percent Ci a. Spent resins, filter sludges, evlaporator bottoms, etc.(nuclides determined by measurement)(Percent Cutoff = 1%)Fe-55 8.792 1.41 E+01 Co-58 1.330 2.13E+00 Co-60 9.522 1.52E+01 Ni-63 53.507 8.55E+01 Cs-134 7.074 1.13E+01 Cs-137 17.334 277E+01 E1-20 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND-WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 5-A SOLID WASTE (RADIOACTIVE SHIPMENTS)

b. Dry active waste, compressible waste, contaminated equipment, etc. (nuclides determined by estimate)(Percent Cutoff = 1.0 percent)H-3 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Sb-125 Cs-1 34 Cs-1 37 Percent 1.322 1.439 7.608 4.970 7.525 31.771 1.043 19.303 22.683 NIA C['I Z86E-02 2.02E.02 1.07E-01 6.99E-102 I.06E-01 4.47E-01 1.47E-02 2;71 E-01 3.19E-01 N/A c. Irradiated Components None E1-21 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 5-B SOLID WASTE (RADIOACTIVE SHIPMENTS)
3. Solid Waste Disposition Number of Shipments 7 8 3 Mode of Transportation Motor Freight Motor Freight Motor Freight Destination Duratek Inc.Duratek Radwaste Processing.lnc.

Sequoyah Nuclear Facility 4. Irradiated Fuel Shipments (Disposition)

Number of Shipments Type Quantity Mode of Transportation.

None N/A N/A 5. Solidification of Waste Was solidification performed?

No If yes, solidification media: N/A Destination N/A E1-22 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION Radiological Impact Introduction Potential doses to maximum individuals and the population around Wattsý Bar are calculated for each quarter as required in Section 5.2 of the Offsite Dose Calculation Manual (ODCM). Measured plant releases for the reporting period are used to estimate these doses. Dispersion of radioactive effluents in the environment is estimated using meteorological data and riverflow data measured during -the period. In this report, the doses resulting from releases are described and compared to limits established for Watts Bar.Dose Limits The ODCM specifies limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of radioactive effluents.

These limits are set well-below the Technical Specification limits which govern the concentrations of radioactivity and doses permissible in unrestricted areas. This ensures that radioactive effluent releases are As Low As Reasonably Achievable.

Dose Calculations Estimated doses to the public are determined using computer.

models (the Gaseous Effluent Licensing Code, GELC, and the Quarterly Water Dose Assessment Code, QWATA). These models are based on guidance provided by the NRC (in Regulatory Guides 1.109, 1.111 and 1.113) for determining'the potential dose to individuals and populations living in the vicinity of the plant. The area around the plant is analyzed to determine the pathways through which the public may receive. a dose. The doses calculated are a representation of the dose to a "maximum exposed individual." Some of the factors used in these calculations (such as ingestion rates) are maximum values. Many of these factors are obtained from NUREG/CR-1004.

The values chosen will tend to overestimate the dose to this "maximum" person. The expected dose to actual individuals is lower. The calculated doses are presented in Tables 6A, 6B, 7A and 7B.Doses. From Airborne Effluents For airborne effluents, the public can be exposed to radiation from several sources: direct radiation from the radioactivity in the air, direct radiation from radioactivity deposited on .the ground, inhalation of airborne radioactivity, ingestion of vegetation which contains radioactivity deposited from the atmosphere, and ingestion of milk and beef which contains radioactivity deposited from the atmosphere onto vegetation and subsequently eaten by milk and beef animals.Airborne Discharge Points All releases from Watts Bar are considered ground-level releases.

The ground-level Joint Frequency Distribution (JFD) is derived from wind speeds and directions measured 10 meters above ground and from the vertical temperature difference between 10 and 46 meters, and are presentedfor each quarter on pages E1-32 through E1-59.E1-23 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION Radiological Impact Meteorological Data Meteorological variables at Watts Bar are measured continuously.

Measurements collected include wind speed, wind direction, and temperature at heights of 10, 46, and 91 meters above the ground. Quarterly joint frequency, distributions (JFDs) are calculated for each release point using the appropriate levels. of meteorological data. A joint frequency distribution gives the percentage of the time in a quarter that the wind is blowing out of a particular upwind compass sector in a particular range of wind speeds for a. given stability class A through G. The wind speeds are divided into nine wind speed ranges. Calms are distributed by direction in proportion to the distribution of non-calm wind directions less than 0,7 m/s (1.5 mph). Stability classes are determined from the vertical temperature difference between.two measurement levels.External Exposure Dose Dose estimates for maximum external air dose (gamma-air and beta-air doses) are made for points at and beyond the unrestricted area boundary as described in the Watts Bar ODCM. The highest of these doses is then selected.Submersion Dose External doses to the skin and total body, due to submersion in a cloud of-noble gases, are estimated for the nearest residence in each sector. The residence with the highest dose is then selected-from all sectors.Organ Dose Doses to organs due to releases of airborne effluents are estimatedfor the inhalation, ground contamination, and ingestion pathways.

The ingestion pathway is further divided into four possible contributing pathways:

ingestion of cow/goat milk, ingestion of beef, and ingestion of yegetables.

Doses from applicable -pathways are calculated for each real receptor location identified -in the most recent land use survey. To determine the maximum organ dose, the doses.from.the pathways are summed for each receptor.

For the ingestion dose, however, only those pathways that exist for each. receptor are considered in the sum, i.e., milk ingestion doses are included only for locations where milk is consumed without commercial preparation and vegetable ingestion is included only for those locations where a garden is identified.

To conservatively account for beef ingestion, a beef ingestion dose equal to that for the highest unrestricted area boundary location is added to each identified receptor.

For ground contamination, the.dose added to the organ dose being calculated is, the total body dose calculated for that location, i.e., it is assumed that the dose to an individual organ is equallto the total body dose.Doses from airborne effluents are presented in Tables 6A and 6B.Doses From Liquid Effluents For liquid effluents, the public can be exposed to radiation from three sources: the ingestion of water from the Tennessee River, the ingestion of fish caught in the Tennessee River, and direct exposure from radioactive material deposited on the river shoreline sediment:(recreation).

El-24 2009 WATTS BAR NUCLEAR' PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION Radiological Impact The concentrations of radioactivity in the Tennessee River are, estimated by a computer model which uses measured.

hydraulic data downstream of Watts Bar. Parameters used to determine thetdoses are based on guidance given by the NRC (in Regulatory Guide 1.109) for maximum ,ingestion.

rates,, exposure times, etc.Wherever possible, parameters used in the dose calculation are site specific use factors determined by TVA. The models.that are-used to estimate doses, as well as the parameters input to the models, are described in detail in the WattsBar ODCM.Liquid Release. Points and River Data Radioactivity concentrations in the Tennessee River are calculated assuming that releases in liquid effluents are continuous.

All routine liquid releases from Watts Bar, located at Tennessee River Mile 528.5, are made through diffusers which extend into the Tennessee River. It.is assumed that releases to the river through these diffusers will initially be entrained in one-tenth of the water which flows past the plant. The QWATA code makes the assumption that this mixing condition holds true until the water is completely mixed at Tennessee River Mile 510.0.Doses are calculated for locations within a 50 mile radius downstream of the plant site. The maximum potential recreation dose is calculated for a location immediately downstream from the plant outfall. The maximum individual dose from ingestion of fish is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the first downstream dam (Chickamauga Dam). The maximum individual dose from drinking water is assumed to be that calculated -at the nearest downstream.public water supply (Dayton, TN). This could be interpreted as indicating that the maximum individual, as assumed for liquid releases from Watts Bar, is an individual who obtains all of his. drinking water at Dayton, TN, consumes fish caught from the Tennessee River between Watts Bar and Chickamauga'Dam, and spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year on the shoreline just below the outfall from Watts:Bar.

Dose estimates for the maximum individual due to liquid effluents for each quarter in the period are presented in TablesIA 'and 7B, along with the average river flows past the plant site for the periods.Population Doses Population doses for highest exposed organ due to airborne effluents are. calculated for an estimated 1,066,600 persons living within a 50-mile radius of the plant site. Doses from external:

pathways and inhalation are based on the 50-mile human population distribution.

Ingestion population doses are calculated assuming that each individual consumes milk, vegetables, -and meat produced within the sector annulus in which he resides. Doses from external pathways and inhalation are based on the 50-mile human population distribution.

Population doses for total body and the maximum exposed organ due to liquid effluents are calculated for the entire downstream Tennessee River Population.

Water ingestion population doses are calculated, using actual population figures for downstream public water supplies.

Fish ingestion population doses are calculated assuming that all sport fish caught in the Tennessee River are consumed by the Tennessee River population.

Recreation population doses are calculated-using actual recreational data on the number of shoreline visits at downstream locations.

Population dose estimates for airborne and liquid effluents are presented in Tables 6A, 6B, 7A and 7B.E1-25 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUALCREPORT SUPPLEMENTAL INFORMATION Radiological Impact Direct Radiation External gamma radiation levels were measured by thermoluminescent dosimeters (TLDs).deployed around WBN as part of the offsite Environmental Radiological Monitoring Program. The quarterlygamma radiation levels determined from these TLDs during this reporting period averaged 12:'0 mR/quarter.

at onsite (at or near the site boundary) stations and 11.0 mR/quarter at offsite stations or 1.00 mR/quarter higher onsite than at offsite stations.

This difference is consistent with levels. measured for preoperation and construction phases of the WBN plant site where the average radiation levels onsite were generally 2-6 mR/quarter higher than the levels offsite. This may be attributable to natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the: construdtibn of the plants, or other undetermined influences.

Fluctuations in natural background dose rates and in TLD :readings tend to mask any small increments which may be due to plant operations.

Thus, therewas no identifiable increase in dose rate levels attributable to direct radiation from plant equipment and/or gaseous, effluents.

Dose To A.Member OfThe Public Inside.The Unrestricted Area Boundary As stated in the Watts Bar Offsite Dose Calculation Manual, an evaluation of the dose to a member of the public inside the unrestricted area boundary is performed for a hypothetical TVA employee who works just outside the restricted area boundary for an entire work year (2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />). Results from-onsite quarterly TLD measurements indicated that the highest annual TLD reading outside, Radiological Control Areas was 92 mrem. Using this value, subtracting an annual background value of approximately.

48 mrem/year (see previous section), and multiplying by the ratio of the occupancy times (2000/8760), the -highest external dose to a member of the public inside the unrestricted area boundary would be 10 mrem. The doses due to radioactive effluents released to the atmosphere calculated in this report would not add a significant amount to this measured dose. This dose is below the 10 CFR 20 annual limit of 1:00 mrem.Total Dose To determine compliance with 40 CFR 190, annual total dose contributions to the maximum individual from Watts Bar radioactive effluents and all other nearby uranium fuel cycle sources are considered.

The annual dose to any organ other than thyroid for the maximum individual is conservatively estimated by summing the following doses: the total body air submersion dose for each quarter, the critical organ dose (for any organ other than the thyroid) from airborne effluents for each quarter from ground contamination, inhalation and ingestion, the total body dose from liquid effluents for each quarter, the-maximum organ dose (for any organ other than the thyroid) from liquid effluents for eachý quarter, and any identifiable increase in direct radiation dose levels as measured by the environmental monitoring program. This~dose is. compared to the 40 CFR 190 limit for total body or any organ dose (other than. thyroid) to determine compliance.

The annual thyroid dose to the maximum individual is conservatively estimated byý summing.the following doses: the total body air submersion.

dose for each quarter, the thyroid dose from airborne effluents for each quarter, the total body dose from liquid effluents for each quarter, the thyroid dose from liquid effluents for each quarter, and any identifiable increase in direct radiation dose levels as measured...by, the environmental monitoring program. This dose is compared to the 40 CFR 190 limit for thyroid dose to determine compliance.

Cumulative annual total doses are presented in Table 8.El-26 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION

.TABLE 6-A Doses from Airborne Effluents First Quarter Individual Doses Pathway Dose Quarterly Percent of Location Limit Limit External Gamma Air 9.28E-05 mrad 5 mrad <1% ENE/11370 meters Beta Air 5.40E-05 mrad 10 mrad <1% ENE/11370 meters Submersion Total Body 3.7J1E-05 mrem N/A N/A SE/I 372 meters Skin 5.75E-05 mrem N/A N/A SE/137r2 meters.Organ Doses Child Thyroid 3.26E-02 mrem 7.5 mrem <1% SE/! 1372 meters Child/Total Body 3.25E-02 mrem 75. mrem < 1.%

  • SE/i 372 meters Population Doses Total Body Dose 9.01'E-02 man-rem Maximum Organ Dose (organ) 9.02E-02 man-rem (thyroid)Second Quarter Individual Doses Pathway Dose Quarterly Percent of Location Limit Limit External _ _ _Gamma Air 1.87E-03mrad 5 mrad <'1% E/1 280 meters Beta Air; 2.39E-03mrad 10 mrad < 1% E/1280 meters Submersion Total Body 6&42E-04 mrem N/A N/A SE/1372meters, Skin 1.23E-03 .mrem N/A N/A SE/1372 meters Organ Doses Child/Thyroid 8.74E-03 mrem 7.5 mrem <1% 16 SE/372 meters Child/Total Body 8.71 E-03 mrem 7.5 mrem < 1% SE/i 372 meters Population Doses Total Body Dose Maximum Organ Dose (organ)2.35E-02 man-rem 2.36E-02 man-rem (thyroid)Population doses can be compared to the natural background dose for the entire, 50-mile population of about 150,000 man-rem/year (based on 140 mrem/yr for natural background).

'EI-27 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSALANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 6-B Doses from Airborne Effluents Third Quarter Individual Doses Pathway Dose Quarterly Percent of Location'Limit Limit External Gamma Air 7.13E-04 mrad 5 mrad < 1% ESE/ 250 meters.BetaAir 5.33E-04 mrad 10 mrad < 1% EESE/.1250,meters Submersion.

Total Body 1.03E-03 mrem N/A N/A SE[/ 372 meters Skin 1.36E-03 mrem N/A N/A SE/1372 meters-Organ Doses __, Child/Thyroid 1.87E-02 mrem 7.5 mrem <1% SE/I 372meters Child/Total'Body 1.91 E-02 mrem 7.5 mrem < 1% 1 SE/i 372 mbters Population Doses Total Body Dose 2.99E-02 man-rem Maximum Organ Dose (organ) 3.02E-02 man-rem (G.I. Tract.)Fourth Quarter Individual Doses Pathway Dose Quarterly Percent of Location Limit Limit, External ....Gamma Air 1.44E-03 mrad 5 mrad <1% ESE/1 250meters Beta Air 1.12E-03 mrad 10 mrad < 1%. ESE/1i250 meters Submersion

__*Total Body 1.01 E-03 mrem N/A N/A SE/1 372 meters Skin 1.74E'03 mrem N/A N/A SE/1i372 meters Organ Doses Child/Thyroid 2.36E-02 mrem 7.5 mrem < 1% SE/1i372 meters Child/Total Body 1.95E-02 mrem 7.5 mrem <1% SE/1372:meters Population Doses Total Body Dose Maximum Organ Dose (organ)2.19E-02 man-rem 2.66E-02 man-rem (thyroid)Population doses can be compared to the natural background dose for the entire 50-mile population of about 150,000 man-rem/year (based on 140 mrem/yr for natural background).

El-28 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 7-A Doses from Liquid Effluents First Quarter Individual Doses (mrem)Age Group Organ Dose " Quarterly Limit Percent of Limit Child Total Body 2.4E-04 1.5 mrem < 1%Child Bone 2.8E-04 5 mrem < 1 %Child Thyroid 2.3E&04 5 mrem < 1 %Average Riverflow past WBN (cubic feet per second): 26,886 Population Doses Total Body Dose 1.2E-02 man-rem Maximum Organ Dose (organ) 1.3E-02 man-rem (Bone)Second Quarter Individual Doses (mrem)Age Group Organ Dose Quarterly Limit Percentof Limit Child Total Body 5.OE-03 1.5 mrem <1 %Child Bone 5.1E-03 5 mrem < 1 %Child Thyroid 5.OE-03 5 mrem < 1 %Average Riverflow past WBN (cubic feet per second): 22,183 Population Doses Total Body'Dose 3.1E-01 man-rem Maximum Organ Dose (organ) 3.1E-01 man-rem (Bone)Population doses can be compared to the natural background dose for the entire 50-mile population of about 150,000 man-rem/year (based on 140 mrem/yr for natural background).

E1-29 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 7-B Doses from Liquid Effluents Third Quarter Individual Doses (mrem)Age Group Organ Dose Quarterly Limit Percent of:Limit Child Total Body 5.4E-03 1.5 mrem < 1 %Child Bone 5.6E-03 5 mrem < 1 %Child Thyroid 5.3E-03 5 mrem < 1 %Average Riverflow past WBN (cubic feet per second): 21,977 Population Doses Total Body Dose 3.4E-01 man-rem Maximum Organ Dose (organ) 3.4E-01 man-rem (Bone)Fourth Quarter Individual Doses (mrem)Age Group Organ Dose Quarterly Limit Percent oftLimit.Child Total Body 6.8E-04 1.5 mrem < 1%Adult GIT 3.OE-03 5 mrem < 1%Child Thyroid 6.7E-04 5 mrem < 1 %Average Riverflow past WBN (cubic feet per second): 55,419 Population Doses Total Body Dose 3.9E-02 man-rem Maximum Organ Dose (organ) 4.1E-02 man-rem (GIT)Population.

doses can be compared to the natural background dose for the entire 50-mile population of about 150,000 man-rem/year.(based on 140 mrem/yr for natural background).

E1-30 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 8 Total Dose from Fuel Cycle First Second Third Fourth Dose Quarter Quarter Quarter Quarter Total Body or any Organ (except thyroid)Total body air 3.71,E-05 6.42E-04 1.03E-03 1.01 E-03 (submersion)

Criticalorgan dose 3.25E-02 8.71 E-03 1.91 E&02 1.95E-02 (airborne)

Total body dose 2.40E-04 5.OOE-03 5.40E-03 6.80E-04 (liquid)Maximum organ dose 2.80E-04 5.1OE-03 5.60E-03 3.OOOE-03 (liquid)Direct Radiation Dose 0.00E+00 O.OOE+00 0.OOE+00 0.00E+00 Total 3.31E-02 1.95E-02 3.11E-02 2.42E-02., Cumulative Total Dose (mrem) 1 .08E-01 Annual Dose Limit (mrem)' 25 Percent of Limit 0.43%Thyroid Total body air 3.71 E-05 6.42E-04 1.03E-03 1.01 E-03 (submersion)

Thyroid dose 3.26E-02 8.74E-03 1.87E-02 2.36E-02 (airborne)

Total body dose 2.40E-04 5.OOE-03 5.40E-03 6.80E-04 (liquid)Thyroid dose 2.30E-04 5.OOE-03 5.30E-03 6.70E-04 (liquid)Total 3.31 E-02 1.94E-02 3.04E702 2.60E-02 Cumulative Total Dose.(mrem) 1.09E-01 Annual Dose Limit.(mrem) 75 Percentlof Limit 0.15%El-31 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT -PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS A (DELTA T<=-1.9 C/100 M)Watts Bar Nuclear Plant JAN 1, 2009 -MAR 31, 2009 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL WIND SPEED (MPH)3.5-5.4 5.5-7.4 CALM 0.6-1.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1.5-3.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0,000 0,000 0.000 0.046 0.000 0.000 0.000 0.000 0.046 0.000 0.093 0.093 0.139 0.046 0.000 0.000 0.000 0.000 0.000 0.139 0.510 0.371 0.000 0.000 0.000 0.000 0.046 1.344 7.5-12.4 0.139 0.185 0.093 0.000 0.000 0.000 0.000 0.000 0.093 1.297 0.093 0.000 0.000 0.000 0.000 0.093 1.993 12.5-18.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.046 18.5-24.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000>-24 .5 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0'.,000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.232 0.324 0.139 0.000 0.000 0.000 0.000 0.000 0.232 1.900 0.463 0.000 0.000 0.046 0.046 0.139 0.000 3.522 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS A TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS A TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 7.98 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS 2158 76 76 2158 0 DATE-PRINTED:

2009/05/19 E1-32 2009 WATTS BAR NUCLEARPLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS B (-1.9< DELTA T<=LI.7 C/100 M), Watts Bar Nuclear'Plant JAN 1, 2009 -MAR 31, 2009 WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 12.5-18.4 18.5-24.4>=24.5 TOTAL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0 000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.046 0.046 0.046 0.000 0.000 0.046 0.278 0.185 0.278 0.046 0.000 0.000 0.000 0.000 0.185 0.185 0.139 0.000 0.000 0.000 0.000 0.000 0.139 0.417 0.139 0.000 0.000 0.046 0.000 0.139 0.139 0.417 0.046 0.000 0.000 0.000 0.000 0.000 0.185 0.463 0.046 0.000 0.046 0.417 0.139 0.046 0.000 0.000 06 000 0.000'0.000 0.000 0 ;'ooo 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000'0.000 0.000 0.000 0.000 0.000 0.000 0.000 0:000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000.0.000 0.000 0.000 0.000 0.000 0 000 0.000 0.324 0.649 0.232 0.046 0.046 0.000 0.000 0.093 0.602 1.112 0.463 0.046 0.046 0.510 0.139 0.185 SUBT TOTAL 0.000 0.000 0.093 1.019 1.390 1 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS B TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS B TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 7.26 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS.946 0.046 0.000 0.000 4.495 2158 97 97 2158 DATE PRINTED: 2009/05/19 El-33 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS C (-1.7< DELTA T<=-1.5 C/100 M)Watts Bar Nuclear Plant JAN 1, 2009 -MAR 31, 2009 WIND DIRECTION WIND SPEED (MPH)3.5-5.4 5.5-7.4 CALM 0.6-1.4 1.5-3.4 7.5-12.4 12.5-18.4 18.5-24.4>=24.5 TOTAL N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL TOTAL HOURS TOTAL HOURS TOTAL HOURS TOTAL HOURS TOTAL HOURS 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.046 0.046 0.046 0.046 0.046 0.000 0.046 0.000 0.000 0.046 0.000 0.000 0.000 0.093 0.324 0.139 0.139 0.000 0.000 0.000 0.000 0.417 0.324 0.556 0.046 0.000 0.000 0.000 0.000 0.093 0.093 0.093 0.000 0.000 0.000 0.000 0.000 0.093 0.371 0.093 0.000 0.046 0.139 0.000 0.000 0.046 0.278 0.046 0.000 0.000 0.000 0.000 0M046 0,139 0,232 0.000 0,000 0.046 0.046 0.185 0,232 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.232 0.788 0.278 0.185 0.046 0.046 0.046 0.093 0.649 0.973 0.649 0.046 0.139 0.232 0.185 0.232 0.000 0.000 0.371 2.039 1.019 1,297 0.093 0.000 0.000 4.819 OF VALID STABILITY OBSERVATIONS OF STABILITY CLASS C OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS C OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS CALM 2158 104 104 2158 0 METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 6.22 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS DATE PRINTED: 2009/05/19 El-34 2009 WATTS BAR NUCLEARPLANT EFFLUENT AND*WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS D (-1.5< DELTA T<=-0.5 C/100 M)Watts Bar Nuclear Plant JAN 1, 2009 -MAR 31, 2009 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4

>=24.5 TOTAL N 0.000 0.093 1.158 1.576 1.483 1.807 0.463 0.000 0000 6.580 NNE 0.000 0.000 0.680 1.854 1.205 1.483 0.139 0.000 0.000 5.561 NE 0.000 0.000 0.695 0.973 0.695 0.046 0.000 0.000 0.000 2.410 ENE 0.000 0.000 0.834 0.139 -0.000 0.000 0.000 0.000 0.000 0.973 E 0.000 0.046 0.232 0.046 0.000 0.000 0.000 0.000 0.000 0.324 ESE 0.000 0.046 0.139 0.000 0.000 0.000 0.000 0.000 0.000 0.185 SE 0.000 0.093 0.139 0.046 0.000 0.000 0.000 0.000 0.000 0.278 SSE 0.000 0.046 0.185 0.139 0.093 0.093 0.000 0.000 0.000 0.556 S 0.000 0.046 0.834 0.463 0.602 0.973 0.278 0.093 0.000 3.290 SSW 0.000 0.093 1.761 1.529 1.529 1.576 0.093 0.046 0.000 6.627 SW 0.000 0.185 0.973 0.834 0.000 0.093 0.000 0.000 0.000 2.085 WSW 0.000 0.139 0.602 0.278 0.093 0.649 0.000 0.000 0.000 1.761 W 0.000 0.046 0.278 0.324 0.139 0.371 0.000 0.000 0.000 1.158 WNW 0.000 0.139 0.185 0.510 0.695 0.417 0.139 0.000 0.000 2.085 NW 0.000 0.046 0.324 0.602 0.927 1.344 0.139 0.000 0.000 3.383 NNW 0.000 0.046 0.324 0.278 1.483 2.410 0.139 0.000 0.000 4.680 SUBTOTAL 0.000 1.066 9.546 9.592 8.943 11.260 1.390 0.139 0.000 41.937 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2158 TOTAL HOURS OF STABILITY CLASS D 905 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS D 905 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2158 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL DATE PRINTED: 2009/05/19 MEAN WIND SPEED = 5.97 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-35 2009 WATTS BAR NUCLEARPLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS E (-0.5< DELTA I<= 1.5 C/100 M)Watts Bar Nuclear Plant JAN 1, 2009 -MAR 31, 2009 WIND SPEED(MPH) 3.5-5.4 5.5-7.4 7.5-12.4 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL CALM 0.6-1.4 1.5-3.4 12.5-18.4 18.5-24.4>=24.5 TOTAL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.139 0.139 0.185 0.000 0.232 0.000 0.185 0.185 0.185 0.510 0.093 0.695 0.510 0.371 0.324 0.139 0.371 0.000 0.139 0.556 0.139 0.232 0.093 0.093 0.788 1.205 1.019 0.741 0.788 0.880 0.973 0.556 0.510 0.232 0.046 0.093 0.000 0.046 0.046 0.046 0.788 1.529 0.278 0.139 0.232 0.324 0.510 0.417 0.139 0.000 0.000 0.000 0.000 0.000 0.046 0.093 0.602 1.205 0.139 0.139 0.046 0.093 0.046 0.463 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.139 0.510 0.556 0.324 0.185 0.093 0.046 0.139 0.093 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.,000 0.000 0.000 0.000 0.000 0:000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000, 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0:000 0.000 0.000 0.000 O..000 0.000 0:000 0.000 0.000 0.000 0.000 1.205 0.371 0.371 0.649 0.371 0.278 0.371 0.556 2.873 5.051 1.854 1.900 1.668 1.715 1.993 1.668 0.000 3.892 8.573 5.236 3.012 2.132 0.046 0.000 0.000 22.892 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS E TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E TOTAL HOURS OF VALID WIND DIRECTION-WIND' SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 3.74 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-36 2158 494 494 2158 0 DATE PRINTED: 2009/05/19 2009 WATTS BAR, NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUALREPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS F ( 1.5< DELTA T<= 4.0 C/100 M)Watts Bar Nuclear Plant JAN 1, 2009 -MAR 31, 2009 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL WIND SPEED (MPH)CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24ý4>_=24.5 TOTAL 0.000 0.000 0.000 0.001 0.000 0.000 0.001 0.001 0.002 0.006 0.004 0.008 0.008 0.007 0.004 0.001 0.046 0.000 0.000 0.093 0.000 0.046 0.093 0.046 0.185 0.324 0.185 0.834 1.205 0.788 0.510 0.139 0.046 0.046 0.093 0.185 0.046 0.046 0.093 0.185 0.232 0.927 0.602 0.880 0.510 0.556 0.371 0,046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.324 0.000 0.000 0.046 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0 .000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.0o00 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0: 000 0.000 0.000 0.000 0.000, 0.000 0.000 0.000 0~.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.006 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.093 0.047 0.093 0.279 0.047 0.093 0.186 0.233 0.419 1.582 0.792 1.723 1.769 1.350 0.885 0.279 0.046 4.495 4.866 0.417 0.046 0.000 0.000 0.000 0.000 9.870 y,, TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS F TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 1.80 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS El-37 2158 213 213 2158 1 DATE PRINTED: 2009/05/19 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS G (DELTA T > 4.0 C/100 M)Watts Bar Nuclear Plant JAN 1, 2009 -MAR 31, 2009 WIND DIRECTION N NNE.NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL TOTAL HOURS TOTAL HOURS TOTAL HOURS TOTAL HOURS TOTAL HOURS WIND SPEED (MPH)3.5-5.4 5.5-7.4 CALM 0.004 0.003 0.006 0.014 0.009 0.006 0.014 0.007 0.009 0.023 0.032 0.054 0.044 0.028 0.015 0.010 0.6-1.4 0.139 0.046 0.232 0.324 0.185 0.278 0.602 0.232 0.324 0. 602 1.066 1.761 1.390 0. 973 0.417 0.232 1.5-3.4 0.046 0.093 0.046 0.278 0.185 0.000 0.000 0.093 0.046 0.417 0.324 0.602 0.510 0.232 0.232 0.185 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.093 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 7.5-12.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 12.5-18.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 18.5-24.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000>=24.5 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.190 0.142 0.284 0.616 0.379 0.284 0.616 0.332 0.379 1.136 1'.422 2.418 1.944 1.233 0.664 0.427 0.278 8.804 3.290 0.093 0.000 0.000 0.000 0.000 0.000 12.465 OF VALID STABILITY OBSERVATIONS OF STABILITY CLASS G OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS G OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS CALM 2158 269 269 2158 6 METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 1.20 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS EI-38 DATE PRINTED: 2009/05/19 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS A (DELTA T<=-1.9 C/100 M)WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data APR 1, 2009 -JUN 30, 2009 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL WIND SPEED (MPH)CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4>=24.5 TOTAL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.092 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.046 0.000 0.000 0.046 0.000 0.046 0.046 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.092 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.046 0.092 0.046 0.000 0.000 0.000 0.000 0.000 0.092 0.000 0.092 0.092 0.000 0.000 0.000 0.000 0.000 0.369.0.046 0.046 0.092 0.046 0.000 0.092 0.000 0.000 0.1000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0 000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.185 0.000 0.185 0.092 0.046 0.046 0.000 0.092 0.046 0.508 0.092 0.092 0.139 0.046 0.000 0.139 0.000 0.000 0.185 0.185 0.323 0.970 0.046 0.000 0.000 1.708 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS A TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS A TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM 2170 37 37 2166 METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 7.51 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS DATE PRINTED: 2009/08/06 E1-39 2009 WATTS BAR: NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS B (-1.9< DELTA T<=-1.7 C/100 M)WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data APR 1, 2009 -JUN 30, 2009 WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL>=24.5 TOTAL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.092 0.092 0.000 0.092 0.000 0.046 0.000 0.000 0.046 0.000 0.000 0.000 0.046 0.000 0.000 0.046 0.000 0.046 0.000 0.139 0.000 0.000 0.000 0.000 0.092 0.369 0.185 0.000 0.000 0.092 0.000 0.046 0.000 0.277 0.046 0.092.0.000 0.000 0.000 0.000 0.000 0.416 0.000 0.000 0.277 0.046 0.139 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0,000 0.000 0.000 0.000 0.000 0.000 0.000 0.0.00 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0;000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.092 0.416 0.046 0.323 0.000 0.046 0.000 0.046 0.139 0.785 0.185 0.000 0.323 0.139 0.139 0.092 0.000 0.000 0.046 0.462 0.970 1.293 0.000 0.000 0.000 2.770 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS B TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS B TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM 2170 60 60 2166 0 METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 7.33 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS DATE PRINTED: 2009/08/06 E1-40 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS C (-1.7< DELTA T<=-1.5 C/100 M)WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data APR 1, 2009 -JUN 30, 2009 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL CALM 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.6-1.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1.5-3.4 0.046 0.000 0.000 0.046 0.046 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.185 WIND SPEED (MPH)3.5-5.4 5.5-7.4 0.277 0.231 0.185 0.185 0.139 0.139 0.046 0.046 0.323 0.739 0.092 0.000 0.000 0.000 0.000 0.000 2.401 0.139 0.416 0.185 0.046 0.000 0.000 0.000 0.000 0.416 0.508 0.231 0.000 0.092 0.323 0.092 0.277 2.724 7.5-12.4 0.185 0.462 0.000 0.046 0.000 0.000 0.000 0.000 0.139 0.139 0.000 0.139 0.139 0.416 0.092 0.000 12.5-18.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 18.5-24.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000>=24.5 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.646 1.108 0.369 0.323 0.185 0.139 0.046 0:092 0.877 1.385 0.323 0.139 0.277 0.739 0.185 0.277 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS C TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS C TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIO]

TOTAL HOURS CALM 1.754 0.046 0.000 0.000 7.110 2170 154 154 9S 2166 0 METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 6.39 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS DATE PRINTED: 2009/08/06 El-41 2009 WATTS BAR NUCLEARPLANT EFFLUENT AND WASTE DISPOSAL ANNUALREPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS D (-1.5< DELTA T<=-0.5 C/100 M)WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data APR 1, 2009 -JUN 30, 2009 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL CALM 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.6-1.4 1.5-3.4 0.000 0.000 0.046 0.046 0.092 0.000 0.139 0.000 0.092 0.231 0.092 0.046 0.046 0.000 0.000 0.000 0.462 0.323 0.693 0.277 0.508 0.508 0.462 1.108 2.124 1.847 0.831 0.508 0.277 0.231 0.277 0.462 WIND SPEED (MPH)3.5-5.4 5.5-7.4 7.5-12.4 0.693 1.108 0.416 0.693 0.646 0.462 0.508 0.139 0.046 0.600 0.277 0.046 0.231 0.000 0.000 0.139 0.000 0.000 0.185 0.046 0.000 0.323 0.092 0.092 1.754 0.508 0.600 3.186 1.339 0.554 0.970 0.139 0.092 0.508 0.139 0.092 0.693 0.462 0.646 0.970 1.062 0.785 0.416 1.016 0.646 0.646 0.462 0.185 12.5-18.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0 000 18.5-24.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000>=24.5 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 2.678 2.124 1.431 1.247 0.831 0.646 0.831 1.662 5.078 7.156 2.124 1.293 2.124 3.047 2.355 1.754 0.000 0.831 10.896 12.512 7.433 4.663 0.046 0.000 0.000 36.380 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS D TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS D TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM 2170 790 788 2166 METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTIONMEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 4.79 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS DATE PRINTED: 2009/08/06 El-42 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS E (-0.5< DELTA T<= 1.5 C/100 M)WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data APR 1, 2009 -JUN 30, 2009 WIND DIRECTION WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4>=24.5 TOTAL N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 0.001 0.001 0.002 0.002 0.002 0.001 0.001 0.004 0.005 0.008 0.007 0.005 0.003 0.002 0.002 0.001 0.046 0.046 0.092 0.092 0.185 0.092 0.277 0.739 0.462 0.600 0.600 0.554 0.462 0.046 0.139 0.046 0.231 0.369 0.508 0.554 0.369 0.139 0.185 0.739 1.385 2.401 1.754 1.154 0.785 0.739 0.508 0.323 0.185 0.185 0.046 0.139 0.046 0.000 0.000 0.139 0.508 1.385 0.092 0.092 0.139 0.323 0.092 0.277 0.046 0.231 0.000 0.046 0.046 0.000 0.000 0.046 0.139 0.693 0.092 0.139 0.046 0.046 0.092 0.092 0.139 0.000 0.000 0.000 0.046 0.000 0.000 0.046 0.092 0.185 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0M000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.647 0.832 0.648 0.833 0.694 0.231 0.463 1.758 2.591 5.271 2.546 1.944 1.435 1.156 0.833 0.740 SUBTOTAL 0.046 4.478 12.142 3.647 1.754 0.508 0.046 0.000 0.000 22.622 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2170 TOTAL HOURS OF STABILITY CLASS E 492 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E 490 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2166 TOTAL HOURS CALM 1 METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 2.85 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-43 DATE PRINTED: 2009/08/06 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS F ( 1.5< DELTA T<= 4.0 C/100 M)WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data APR 1, 2009 -JUN 30, 2009 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4>=24.5 TOTAL 0.001 0.002 0.002 0.002 0.002 0.001 0.002 0.002 0.005 0:010 0.015 0.018 0.014 0.009 0.006 0.002 0.046 0.139 0.046 0.139 0.185 0.092 0.139 0.231 0.369 0.600 1.062 1.754 1.431 1.016 0.554 0.231 0.139 0.231 0.231 0.185 0.046 0.046 0.139 0.092 0.369 0.877 1.293 0.923 0.646 0.323 0.369 0.139 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.092 0.000 0.000 0.000 0.000 0.092 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0'.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0; 000 0.000 0.000 0.000 0.000 0.000 0:000 0.000 0.000 0.186 0.372 0.279 0.325 0.232 0.139 0.279 0.325 0.790 1.579 2.370 2.695 2.091 1.348 1.022 0.372 0.092 8.033 6.048 0.231 0.000 0.000 0.000 0.000 0;000 14.404 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS F TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM 2170 312 312 2166 2 METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED -1.55 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS El-44 DATE PRINTED: 2009/08/06 2009 WATTS BAR'NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS.G (DELTA T > 4.0 C/100 M)WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data APR 1, 2009 -JUN 30, 2009 WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.:5-24.4 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL>=24.5 TOTAL 0.003 0.002 0.002 0.003 0.003 0.002 0.003 0.005 0.007 0.012 0.023 0.033 0.038 0.023 0.017 0.009 0.139 0.139 0.092 0.231 0.139 0.139 0.231 0.369 0.554 0.831 1.385 1.98S 2.493 1.200 0.923 0.462 0.092 0.000 0.046 0.046 0.092 0.000 0.000 0.000 0.046 0.139 0.462 0.646 0.554 0.646 0.462 0.277 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.00 0.000 0 000 0 000 0.000 0.000 0.000 0.000.0.000 0.000 0.000 0.000 0.000 0.000 0'.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000, 0,000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000.0.000 0.000 0.000 0.000 o.1ooo 0,000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.1000 0 .000 0. 000 0.000 0.000 0.234 0.140 0.140 0.280 0.234 0.140 0.234 0.374 0.608 0.982 1.870 2.664 3.085 1.870 1.402 0.748 0.185 11.311 3.509 0.000 0.000 0.000 0.000 0.000 0.000 15.005 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS G TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS G TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM 2170 325, 325 2166 4 METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STA 58 B -Validated Edited Data STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 1.20 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS DATE PRINTED: 2009/08/06 E1-45 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUALREPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS A (DELTA T<=-1.9 C/00 M)WATTS BAR NUCLEAR PLANT JUL 1, 2009 -SEP 30, 2009 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4

>=24.5 TOTAL N 0.000 0.046 0.000 0.000 0.046 0.046 0.000 0.000 0.000 0.137 NNE 0.000 0.000 0.000 0.137 0.000 0.046. 0.000 0.000 0.000 0.182 NE 0.000 0.000 0.182 0.182 0.046 0.000 0.000 0.000 0.000 0.411 ENE 0.000 0.000 0.046 0.000. 0.000 0.000 0.000 0.000 0.000 E 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.046 ESE 0.000 0.000 0.046 0.046 0.000 0.000 0.000 0.000' 0.000 0.091 SE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0,000 SSE 0.000 0.000 0.000 0.091 0.046 0.000 0.000 0.000 0.000 0.137 S 0.000 0.000 0.091 0.046 0.046 0.000 0.000 0.000 0.000 0.182 SSW 0.000 0.000 0.046 0.137 0.046 0.000 0.000 0*000 0.000 0.228 SW 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.046 WSW 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.046 W 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 WNW 0.000 0.000 0.000 0.000 0.046 0.046 0.000 0.000 0.000 0.091 NW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 NNW 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 SUBTOTAL 0.000 0.046 0.502 0.684 0.274 0.137 0.000 0.000 0.000 1.642 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 2193 TOTAL HOURS OF STABILITY CLASS A 37 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS A .36 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2192 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL DATE PRINTED: 2009/11/10 MEAN WIND SPEED = 4.30 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-46 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUALREPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS B (-1.9< DELTA T<=-1.7 C/100 M)WATTS BAR NUCLEAR PLANT JUL 1, 2009 -SEP 30, 2009 WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL 12.5-18.4 18.5-24.4>=24.5 TOTAL 0,000 0.000 0,000 0.000 0.000, 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.091 0.046 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.046 0.000 0.091 0.046 0.046 0.000 0.000 0.046 0.000 0.091 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.091 0.274 0.137 0.091 0.000 0.000 0.000 0.000 0.046 0.046 0.000 0.000 0.000 0.000 0.000, 0.182 0.046'0.000 0.046 0.000 0.046 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000, 0.137 0.046 0.091 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.274 0.319 0.319 0.137 0.046 0.091 0.000 0.091 0.091 0.091 0.000 0.000 0.046 0.137 0.091 0.274 0.000 0.000 0.319 0.365 0.867 0.456 ' 0000 0.000 0.000 2.007 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS B TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS B TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 5.89 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS 2193 44 44 2192 0 DATE PRINTED: 2009/11/10 El -47 2009 WATTS BAR NUCLEAR-PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS C (-1.7< DELTA T<=-1.5 C/100 M)WATTS BAR NUCLEAR PLANT JUL 1, 2009 -SEP 30, 2009 WIND SPEED (MPH)CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4

>=24.5 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000'0 000 0.000 0.000 0.000 0.000 0.000 0.046 0.046 0.091 0.046 0.046 0.046 0.091 0.091 0.046 0.090 0.000 0.000 0.000 0.000 0.046 0.182 0.091 0.137 0.046 0.091 0.046 0.046 0.000 0.182 0.456 0.137 0.000 0.000 0.046 0.046 0.046 0.365 0.319 0.000 0.000 0.046 0.000 0.000 0.000 0.091 0.411 0.046 0.046 0.137 0.137 0.091 0.091 0.091 0.274 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.228 0.091 0.182 0.000 0.000 0.000 0.000 0.000 0.000 0..000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000*0.'000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 TOTAL 0.639 0.730 0.182 0.137 0.182 0.091 0.091 0.091 0.365 0.912 0.182 0.046 0.137 0.411 0.228 0.365 0.000 0.000 0.593 1.551 1.779 0.867 0.000 0.000 0.000 4.790 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS C TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS C TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 5.76 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS 2193 105 105 2192 0 DATE PRINTED: 2009/11/10 E1-48 2009 WATTS. BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS D (-1.5< DELTA T<=-0.5 C/100 M)WATTS BAR NUCLEAR PLANT JUL 1, 2009 -SEP 30, 2009 WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL 12.5-18.4 18.5-24.4>=24.5 'TOTAL 0.000 0.000 0.000 0.000 0..000 0.000 0.000 0.000 0.000'0,;000 0.'000 0.000 0.000 0.000 0000 0.000 0.182 0.046 0.000 0.091 0.046 0.046 0.137 0.091 0 365 0.274 0.228 0. 046 0.046 0.137 0.091 0.000'0.639 1.323 1.095 1.095 1.323 0.:730 1.049 1.141 1.825 2.:555 1.597 0.593 0.593 0.319 0.456 0.730 1.323 1.369 0.684 0.456 0.228 0.137 0.228 0.228 1.460 3.102 1.004 0.228 0.274 0.228 0.411 0.912 1.277 0.730 0.137 0.046 0.000 0.000 0.000 0.000 0.274 0.867 0.046 0.137 0.182 0.274 0.639 0.547 0.137 0.182 0.046 0.000 0.000 0.000 0.046 0.000 0. 137 0.137 0.000 0.000 0.046 0.365 0.411 0.182 0,000 0,000 0.000 0,000 0.000 0.000 0.000 0.000 0.000-0;'000 0.000 0.;000 0.000.0.. 000 o0.000: 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0 :000 0.000 0.000 0.00.0 0.000.0.000 0.000 0.000 0.000 0:,000 0:000 0.000 0.000 0.000 0.000 0:000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 3.558 3.650 1.962 1.688 1.597 0.912 1.460 1.460 4.060 6.934 2.874 1.004 1. 141 1.323 2.007 2.372 0.000 1.825 17.062 12.272 5.155 1.688 e0.000 0.000 0.000 38.002 TOTAL HOURS'OF-VALID STABILITY OBSERVATIONS TOTALHOURS OF STABILITY CLASS Di'TOTAL HOURS, OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS D TOTAL HOURS OF VALID.WIND-DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL.HOURS CALM METEOROLOGICAL FACILITY:

WATTS BAR:NUCLEAR PLANT STABILITY'BASED

'ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 3.85 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-49 2193 833 833-2192 DATE PRINTED: 2009/11/10 2009 WATTS BAR NUCLEAR PLANT EFFLUENT ANDWASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION' FOR STABILITY CLASS E (-0.5< DELTA T<= 1.5 C/100 M)WATTS BAR NUCLEAR PLANT JUL 1, 2009 -SEP 30, 2009 WIND DIRECTION WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4>=24.5 TOTAL N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL TOTAL HOURS TOTAL HOURS TOTAL HOURS TOTAL HOURS TOTAL HOURS 0.002 0.002 0.005 0.005 0.002 0.003 0.002 0.003 0.008 0.012 0.009 0.011 0.010 0.008 ,0.005 0.003 0.137 0.046 0.365 0.411 0.274 0.411 0.228 0.365 0.776 0.593 1.049 1.551 1.779 1.505 0.730 0.182 0.411 0.593 0.867 1.004 0.319 0.411 0.411 0.365 1.369 2.737 1.460 1.323 0.821 0.730 0.684 0.639 0.684 0.274 0.182 0.137 0.046 0.000 0.046 0.091 0.502 1.049 0.228 0.000 0.182 0.365 0.182 1.004 0.091 0.091 0.000 0.000 0.000 0.000 0.000 0.000 0.274 0.137 0.000 0.000 0.000 0.137 0.046 0.365 0.000 0.000 0.000 0.000 0..000 0.000 0.000 0.000 0.000 0.000.0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0 000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0; 000 0.000 0.000 0.000 0.000 0.000 0.000 1.325 1.006 1'.419 1.556 0.641 0.824 0 687 0.824 2.928 4.529 2.747 2.885 2.793 2.746 1.693 2.193 0.091 10.401 14.142 4.973 1.141 0.046 0.000 0.000 0.000 30.794 OF VALID STABILITY OBSERVATIONS OF STABILITYCLASS'E OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS CALM 2193 675 675 2192 2 METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON.DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 2.34 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS El-50 DATE PRINTED: 2009/11/10 2009 WATTS BAR-NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS F ( 1.5< DELTA T<= 4.0 C/100 M)WATTS BAR NUCLEAR PLANT JUL 1, 2009 -SEP 30, 2009 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL CALM 0.001 0.001 0.001 0.001 0.000 0.000 0.000 0.001 0.001 0.003 0.004 0.006 0.010 0.009 0.006 0.002 ,0.6-1.4 0.182 0.182 0.182 0.000 0.137 0.000 0.046 0.319 0.182 0.547 0.684 1. 551 2.737 2.372 1.460 0.365 1.5-3.4 0.046 0.091 0.091 0.365 0.000 0.091 0.091 0.091 0.137 0.456 0.639 0.730 0.912 0.821 0.730 0.228 WIND SPEED(MPH) 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 0.046 0.000 0.000 0:000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.091 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 18.5-24.4 0.000 0.000 0.000.0.000 0.000 0.000.0.000 0.000 0.000 0.000.0.000 0 000 0.000 0.000 0.000 0.000>=24 .5 0.000 0.000 0.000 0.000 01000 0.000 0.000 0.000 0.000 0.000 0:000 0ý.000-0.000 0:000 0.000 0:000 TOTAL 0.274 0.274 0.274 0.366 0.137 0.091 0.137 0.412 0.320 1.006 1.327 2.287 3.660 3.294 2.196 0.595 0.046 10.949 5.520 0.046 0.091 0.000 0.000 0.000 0.000 16.651 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS F TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 1.40 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-51 2193 365 365 2192 DATE PRINTED: 2009/11/10 2009 WATTS BAR NUCLEAR, PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS G (DELTA T > 4.0 C/100 M)WATTS BAR NUCLEAR PLANT JUL 1, 2009 -SEP 30, 2009 WIND SPEED (MPH)CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL 12.5-18.4 18.5-24.4>=24.5 TOTAL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0..000 0.000 0.000 0.000 0.046 0.046 0.046 0, 000 0.091 0.046 0.091 0.046 0.046 0.091 0.091 1.004 0.958 0.776 0.684 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.091 0.365 0.547 0.411 0.502 0.091 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0..000 0,000 0.000 0.000 0:000 0.000 0.000 0.000 0.000 0-.000 0.000 0.000 0.000 0.000 0.;000 0.0.00 0.000 0.000 0.0o00 0.000 0.000 0.000 0.000"0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.:000 0.:000 0,046 0.046 0.046 0.000 0.091 0.046 0.091 0 *046 0.046 0.091 0.182 1.369 1.505 1.186 1.186 0.137 0.000 4.106 2.007 0.000 0.000 0.000 0.000 0.000 0.000 6.113 TOTAL.HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF- STABILITY CLASS G TOTAL HOURS OF VALID.WIND DIRECTION-WIND SPEED-STABILITY CLASS G TOTAL;HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 1.37 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-52 2193 134 134 2192 0 DATE PRINTED: 2009/11/10 2009 WATTS BAR, NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS A (DELTA T<=-1.9 C/100 M)WATTS BAR NUCLEAR PLANT OCT 1, 2009 -DEC 31, 2009 WIND DIRECTION N NNE NE ENE E ESE SE_SSE S SSW SW WSW W WNW NW NNW SUBTOTAL WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.092.0.092 0.092 0.230 0.000 0.000 0.092 0.000 0.092 0.000 0.092 0.000 0.046 0.046 0.092 0.092 1.058 0.046 0.138 0.184 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.092 0.046 0.000 0.092 0.644 0.046 0.092 0.184 0.046 0.000 0.000 0.000 0.000 0.000 0.276 0.000 0.000 0.046 0.046 0.046 0.046 0.828 7.5-12.4.

12.5-18.4 0.138 0.000 0.644 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.'000 0.000 0.000 0.092 0o.'000 0.046 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.046 0.000 0.000 0.000 1.058 0.000 18.5-24.'4 0.000, 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0o000 0.,000*0.000 0.000 0. '000 0.000 0.000 0.000>=24.5 0.000 0.000 0.000 0.000 0.000 0.000 0..000 0.000 0.000 0.000 0.000 0*.000.0.000 0 .000 0.000 0.000 0.000 TOTAL 0.322 0:966 0 506 0.322 0.000 0 000 0.092 0.000 0.184 0.322 0.092 0.000 0.230 0.138 0.184 0.230 3.590 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS A TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS A TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 6.02 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS 2173 78 78 2173 0 DATE PRINTED: 2010/02/10 EI-53 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUALREPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS B (-1.9< DELTA T<=-1.7 C/100 M)WATTS BAR NUCLEAR PLANT OCT 1, 2009 -DEC 31, 2009 WIND SPEED (MPH)CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL 12.5-18.4 18.5-24.4>=24.5 TOTAL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0,000 0.138 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.138 0.000 0.092 0.000 0.000 0.092 0.138 0.368 0.000 0.000 0.092 0.046 0.000 0.000 01.000 0.092 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.276 0.092 0.000 0.000 0.000 0.092 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.184 0.184 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.230 0.598 0.276 0.092 0.000 0.046 0.000 0.000 0.046 0.368 0.138 0.046 0.046 0.368 0.000 0.046 0.000 0.000 0.184 0.460 0.874 0.736 0.046 0.000 0.000 2.301 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS B TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS B TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEFDAND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 6.77 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS 2173 50 50 2173 0 DATE PRINTED: 2010/02/10 E1-54 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS C (-1.7< DELTA T<=-1.5 C/100 M)WATTS BAR NUCLEAR PLANT OCT 1, 2009 -DEC 31, 2009 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4

>=24.5 TOTAL N 0.000 0.000 0.000 0.322 0.230 0.138 0.000 0.000 0.000 0.690 NNE 0.000 0.000 0.092 0.460 0.138 0.184 0.000 0.000 0.000 0.874 NE 0.000 0.000 0.000 0.276 0.138 0.046 0.000 0.000 0.000 0.460 ENE 0.000 0.000 0.138 0.046 0.000 0.000 0.000 0.000 0.000 0.184 E 0.000 0.046 0.138 0.046 0.000 0.000 0.000 0.000 0.000 0.230 ESE 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 SE 0.000 0.046 0.000 0.046 0.000 0.046 0.000 0.000 0.000 0.138 SSE 0.000 0.000 0.092 0.000 0.000 0,000 0.000 0.-000 0.000 0.092 S 0.000 0.046 0.046 0.092 0.000 0.000 0.000 0.000 0.000 0.184 SSW 0.000 0.000 0.000 0.230 0.230 0.046 0.000 0.000 0.000 0.506 SW 0.000 0.000 0.046 0.138 0.138 0.000 0.000 0.000 0.000 0.322 WSW 0.000 0.000 0.000 0.046 0.000 0.000 0.092 0.000 0.000 0.138 W 0.000 0.000 0.000 0.000 0.184 0,.000 0.000 0.000 0.000 0.184 WNW 0.000 0.000 0.000 0.092 0.138 0.000 01.000 0.000 0.000 0.230 NW 0.000 0.000 0.046 0.000 0.000 0.138 0.000 0.000 0:000 0.184 NNW 0.000 0.000 0.000 0.000 0.184 0.000 0.000 0.o000 0.000 0.184 SUBTOTAL 0.000 0.138 0.598 1.795 1.381 0.598 0.092 0.000 0.000 4.602 TOTALHOURS OF VALID STABILITY OBSERVATIONS 2173 TOTAL HOURS OF STABILITY CLASS C 100 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS C 100 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 2173 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL DATE PRINTED: 2010/02/10 MEAN WIND SPEED = 5.57 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-55 2009 WATTS BAR NUCLEAR PLANT EFFLUENT ANDf WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS D (-1.5< DELTA T<=-0.5 C/100 M)WATTS BAR NUCLEAR PLANT OCT 1, 2009 -DEC 31, 2009 WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL>=24.5 TOTAL 0.000 0.000 0.000 0.1000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.092 0.046.0.184 0.000 0.046 0.27,6 0.046 0.046 0.230 0.046 0.184 0.276 0.230 0.230 0.000 0.138 0.644 1.058 1.289 0.966 0.598 0.184.0.368 0.598 1.335 1.979 1.473 0.690 0.920 0.736 0.322 0.736 1.657 0.920 1.243 0.506 0.138 0.000 0.000 0.092 0.598 2.531 0.920 0.230 0.506 1.289 0.644 0.920 1.289 1.381 0.138 0.000 0.000 0.000 0.000 0.000 0.184 0.920 0.092 0.184 0.322 0.874 0.506 1.335 1.150 0.690 0.000 0.000 0.000 0.000 0.092 0.046 0.322 0.920 0.092 0.184 0.276 0.552 0.276 1.058 0.000 0.138 0.046 0..000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0:000 0.000 0.000 0.,000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0'.000 0:000 0.000 0.000 0.000 0.000 4.832 4.. 234 2.899 1.473 0.782 0.460 0.506 0.782 2.669 6.397 2.807 1.565 2.255 3.682 1.749 4.188 0.000 2.071 13.898 12.195 7.225 5.660 0.230 0.000 0.000 41.279 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS D TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS D TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 4.61 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-56 2173 897 897 2173 0 DATE PRINTED: 2010/02/10 2009 WATTS BAR, NUCLEAR- PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS E (-0.5< DELTA T<= 1.5 C/100 M)WATTS BAR NUCLEAR PLANT OCT 1, 2009 -DEC 31, 2009 WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL>=24.5 TOTAL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.184 0.000 0.184 0.184 0.138 0.092 0.092 0.230 0.506 0.644 0.552 0.920 0.828 0.598 0.690 0.552 0.276 0.414 0.230 0.506 0.322 0.184 0.046 0.046 0.782 1.565 1.841 1.289 0.690 0.552 0.552 0.644 0.782 0.000 0.230 0.046 0.000 0.000 0.046 0.000 0.414 1.012 0.138 0.092 0.230 0.230 0.368 0.506 0.230 0.138 0.000 0.000 0.000 0.092 0.092 0.092 0.138 0.184 0.046 0.046 0.000 0.000 0.184 0.460 0.000 0.046 0.000 0.000 0.000 0.046 0.046 0.046 0.000 0.230 0.046 0.000 0.000 0M046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.'000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1.473 0.598 0.644 0.736 0.460 0.414 0.322 0.414 1.841 3.636 2.623 2.347 1.749 1.427 1.795 2.163 0.000 6.397 9.940 4.096 1.703 0.506 0.000 0.000 0.000 22.642 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS E TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T.BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 2.76 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS El-57 2173 492 492 2173 0 DATE PRINTED: 2010/02/10 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS F ( 1.5< DELTA T<= 4.0 C/100 M)WATTS BAR NUCLEAR PLANT OCT 1, 2009 -DEC 31, 2009 WIND SPEED (MPH)CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 WIND DIRECTION 12.5-18.4 18.5-24:4>=24.5 TOTAL N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.322 0.414 0.092 0.138 0.138 0.092 0.092 0.092 0.322 0.138 0.276 1.012 1.611 1.887 1.657 0.322 0.230 0.322 0.184 0.506 0.138 0.000 0.000 0.138 0.092 0.184 0.368 0.506 0.598 1.104 0.966 0.276 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.046 0.138 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.092 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0:000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0:000 0,.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000.0'.000 0.000 ,0.000 0.000 0.000 0.000 0:000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.552 0.736 0.2.6 0.690 0.276 0.092 0.092 0.230 0.460 0.460 0.690 1.519.2.209 2.991 2.715 0.598 SUB~0.000 8.606 5.614 0.230 0.138 0.000 0.000 0.000 0.000 14.588 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL. HOURS OF STABILITY CLASS F TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS TOTAL HOURS CALM METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND.SPEED

= 1.50 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS 2173 317 317 2173 0 DATE PRINTED: 2010/02/10 E1-58 2009 WATTS BAR NUCLEAR PLANT EFFLUENT AND.WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION JOINT PERCENTAGE FREQUENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS G (DELTA T > 4.0 C/100 M)WATTS BAR NUCLEAR PLANT OCT 1, 2009 -DEC 31, 2009 WIND SPEED(MPH)

CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW SUBTOTAL>=24.5 TOTAL 0.005 0.004 0.002 0.004 0.000 0.001 0.000 0.001 0.005 0.002 0.009 0.014 0.020 0.026 0.037 0.009 0.276 0.276 0.184 0.276 0.000 0.046 0.000 0.092 0.322 0.138 0.414 0.828 1.335 1.427 1.795 0.414 0.138 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.046 0.046 0.276 0.230 0.230 0.598 1.104 0.276 0.000 0.000 0.000 0.000 0.000 0.000 0.,000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.046 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.60oo 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000.0.000 0.000 0.419 0.280 0.186 0.326 0.000 0.047 0.000 0.093 0.373 0.186 0.699 1.072 1.585 2.051 2.982 0.699 0.138 7.823 2.991 0.046 0.000 0.000 0.000 0.000 0.000 10.999 TOTAL HOURS TOTAL HOURS TOTAL HOURS TOTAL HOURS TOTAL HOURS OF VALID STABILITY OBSERVATIONS OF STABILITY CLASS G OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS G OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS CALM 2173 239 239 2173 3 METEOROLOGICAL FACILITY:

WATTS BAR NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 1.25 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS DATE PRINTED: 2010/02/10 E1-59 2009 WATTS BAR'NUCLEAR PLANT.EFFLUENT AND WASTE DISPOSAL ANNUAL -REPORT ATTACHMENT 1 Deviations.from ODCM Controls/Surveillance Requirements None E1-60 2009 WATTS BAR NUCLEAR-PLANT EFFLUENTAND WASTE DISPOSAL ANNUAL REPORT ATTACHMENT 2 Radioactive Effluent Monitoring Instrumentation Inoperable fr, Greater than 30-days 1/2.1.1 10/29/2009 Control 1.1.1 Action B Table 1.1-2 Item 2 b.Turbine Building Station. Sump Radiation Monitorý0-RE-90-1.12 was inoperable for more than 30 days due a higher than normal background reading. During this period compensatory samples were obtained every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.El-61 2009 WATTS BAR NUCLEARPLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT ATTACHMENT 3 Offsite Dose Calculation Manual El-62 WATTS BAR NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)Revision 22 Prepared by: Submitted By: Approved By: Eddie Woods Chemistry.Darrin Hutchison Date: 04/15/2009 Date: .04/16/2009 Date: 04/28/2009 Doug Helms.PORC Chairman PORC Meeting No. 4257 Plant Manager: Greg Boerschig Effective Date: 05/11/2009 E1-63 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 2of 195 REVISION LOG Page 1 of 1 REVISION%, EFFECTIVE AFFECTED.NUMBER DATE PAGES DESCRIPTION.OF REVISION Rev 15 03/08/05 1, 2,15' :Revised Action G on Table 1. 1i-2 to allow plannedo ' ngoing releases to continue via the Shield'Building Exhaust during periods when the isokinetic flow control equipment:or heat trace is declared I_ inoperable provided they are returned -operable.within 4-hours.Rev 16 08/19/05 1,2, 64, 65, Revised description of liquid .effluent release paths".in'Section 6.0 98 and Figure 6.1 to implementEDC-51879.

The EDC:allows for releases to be made from the Condensate Demineralizer or Steam Generator Blowdown without a minimum.CTBD flow of 20,000 gpm provided the sum of the ratios of the ECLs for all release points is 5 1 _10.Rev 17 05/08/2006 1, 2,J10, 95, Corrected typo's and discrepancies identified in the':WBN/SQN 105, ODCM difference matrix project. Added a note to clarify the 114,115, calibration ofl-FIT-15-42.

117, 121,122, 150, 152, 154,169 Rev18 08/18/2006 1, 2, 38, 1'67, Revised sample location wording in Table.3-13 for the fish 169,172 exposure pathway. Added'additional sample location for fish in Table 9.1 and Table,9.2.

Added-point 37 to sample.map in Table 9.2 to reflect additional fish location..

Rev 19 02/01/2007 1,-, 2, 4, 21, 39, Added the Groundwater Sump (GWS) as a liquidrelease path,.and 65,118, 164, associated analyses and sampling frequency.

Replaced all 170,183 references to Thermoluminescent Dosimeters(ITLD's)..with dosimeter since Western Area Radiological Laboratory vendor uses laser etched dosimeters versus:TLD's.

Rev 20 09/07/2007 1, 2, 41, 107- Removed the non-drinkiingwater limit of30,000 p.Ci/Ltritium found 109, 112, in groundwater to be. consistent with the NEI Groundwater 132,135-143 Protection Initiative Program. .Updated.X/Q, D/Q,-and the joint frequency distribution tables.for the period from-Januar'y 1986 to December 2005.Rev 21 01/22/2008.

1, 2, 15, 67, Clarified Action L on page. 15. Revised gaseous setpoint table to be 68, 103, 104, consistent with liquid setpoint table. Added wording to allow O-RE-169, 170,90-122 setpoint to be set at a:default value. Corrected reference in 172,173 gaseous setpoint table andclarifiedw6rding for 0,-RE90-118 setpoint.

Removed dairy farm that is nolonger in operation from Table 9.2. Removed an extra control location.

for ýenvironmental dosimeters from Table g3. Update Figures'9.2.and:9.3-3to reflect the changes in Table 9.2 and 9.3.Rev 22 05/11/2009 1, 2, 61, 169, Added statement toinclude results-from non-REMPwell samples;171 any onsitespill or leaks and their assigned doses that occurred during the reporting period in the radioactive effluent.release report.Replaced Well D in the REMP with WelI..F. Updated Figure 9.1 to reflect location of Well F (map location #85).E1-64 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 3 of 195 TABLE OF CONTENTS (Page 1 of 2)TABLE OF CONTENTS .................................................................................................................................................

3 LIST OF TABLES/FIGURES

..........................................................................................................................................

4

1.0 INTRODUCTION

..............................................................................................................................................

5 1.0/2.0 -CONTROLS AND SURVEILLANCE REQUIREMENTS

..............................................................................

6 1/2 .0 A P P L IC A B IL IT Y ....................................................................................................................................................

6 1/2.1 INSTRUMENTATION

............................................................................................................................................

7 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

..................................................

7 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

...........................

12 1/2.1.3 METEOROLOGICAL INSTRUMENTATION/DATA

.....................................................................................

18 1/2.2 RADIOACTIVE EFFLUENTS

.............................................................................................................................

20 1/2.2.1 LIQUID EFFLUENTS

.......................................................................................................................................

20 1/2.2.1.1 CONCENTRATION

......................................................................................................................................

20 1/2 .2 .1 .2 D O S E ............................................................................................................................................................

2 4 1/2.2.1.3 LIQUID RADW ASTE TREATMENT SYSTEM ........................................................................................

25 1/2.2.2 GASEOUS EFFLUENTS

..................................................................................................................................

26 1/2.2.2.1 DOSE RATE .................................................................................................................................................

26 1/2.2.2 22 DOSE -NOBLE GASES ...............................................................................................................................

30 1/2.2.2.3 DOSE 131, 1-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM WITH HALF--LIVES GREATER.THAN EIGHT DAYS ...................................................................................................

31 1/2.2.2.4 GASEOUS RADWASTE TREATMENT

.................................................

32 1/2.2.3 TOTAL DOSE ..................................................................................................................................................

33 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING

....................................................................................

34 1/2.3.1 MONITORING PROGRAM ..............................................................................................................................

34 1/2.3.2 LA ND USE CENSUS .......................................................................................................................................

44 1/2.3.3 INTERLABORATORY COMPARISON PROGRAM ....................................................................................

45 B A S E S ...........................................................................................................................................

B..............................

4 7 3 .0 D E F IN IT IO N S .. ......................................................................................................................................................

54 4 .0 -(N O T U S E D .) ........................................................................................................................................................

6 0 5.0 ADMINISTRATIVE CONTROLS ............................................................................................................................

60 6.0 -LIQUID EFFLUENTS

..........................................................................................................................................

64 7.0 -GASEOUS, EFFLUENTS

..................................................................................................................................

101 8.0 -TOTAL DOSE ...................................................................................................................................................

161 9.0 -RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRA M (REMP) ......................................................

162

10.0 REFERENCES

..................................................................................................................................................

174 11.0 SOURCE NOTES ........................................................................................................................

175 APPENDIX A -NOTATION CONVENTIONS.............................................................................................................

178 LIST OF ACRONYMS ........................................................................

.....................

........ ....... 183 LIST OF UNITS ............................................................................

......................

I ....................

184 APPENDIX B -DEVIATIONS, IN THE WBNODCM CONTROLS/SURVEILLANCE REQUIREMENTS FROM THOSE GIVEN IN NUREG-1301

.........................................................................................

185 APPENDIX C -W BN ODCM REVISION PROCESS .............................................................................

187-E1-65 WBN OFFSITE DOSE CALCULATION MANUAL Revision'22 0 (ODCM) Page,4 0f4195 TABLE OF CONTENTS (Page 2 of 2)LIST OF TABLESIFIGURES TABLES 1.1-1 -RADIOACTIVE LIQUID.EFFLUENT MONITORING INSTRUMENTATION, ......................................

8 2.1-1 -RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

-SURVEILLANCE R E Q U IR E M E N TS .... ................................................................

.........

10 1.1-2 -RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

..............

... 13 2.1-2 -RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

-SURVEILLANCE REQUIREMENTS

....................................................

.................

16 1.1-3 -METEOROLOGICAL MONITORING INSTRUMENTATION

..........................................................

19 2.2-1 -'RADIOACTIVE LIQUIDIWASTE SAMPLING AND ANALYSIS PROGRAM ........................

21 2.2-2 -RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM. .... 27 2.3-1 -,MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM....., ..........

36 2.3-2 -REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 41 2.3-3 -DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS -LLD.............................

42 3.1 -FREQUENCY NOTATION .............................................................

57 3.2 -OPERATIONAL MODES .................

58...................

." 58 6.1 -RECEPTORS FOR LIQUID DOSE CALCULATIONS

..........................................

81 6.2 -RADIONUCLIDE DECAY:AND STABLE ELEMENT TRANSFER DATA ............................

82 6.3 -DOSE CALCULATION FACTORS.......................................................

85 6.4 -INGESTION DOSE FACTORS .........................................................................................

87 6.5 -BIOACCUMULATION'FACTORS FOR FRESHWATER FISH ...........................................................

95 6.6 -EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND ................................

96 7.1 -WBN -OFFSITE RECEPTOR LOCATION DATA ...................................

........ 135 7.2 -JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT, STABILITY CLASSES ........................................................

.... ..............

136 7.3 -ADJUSTED 'DISPERSION FACTORS .........................................................................................

143 7.4 -DOSE FACTORS FOR SUBMERSION IN NOBLE GASES ...........................................................

144 7.5 -SECTOR ELEMENTSCONSIDERED!FOR POPULATION DOSES.................................................

145 7.6 -POPULATION W ITHIN EACH SECTOR ELEMENT ......................................................................

146 7.7 -INHALATION DOSE FACTORS ......................................................

.....................

147 9.1 -REMP -MONITORING; SAMPLING, AND ANALYSIS ....................................................................

164 9.2 -REM P -SAM PLING 'LO CATIO NS ...............................................................................................

168 9.3 -REMP -DOSIMETRY LOCATIONS

.......................................................

169 FIGURES 3.1 -W BN S ITE A R EA M A P .............................

..............................................................................

59 6.1 -LIQUID EFFLUENT RELEASE-POINTS

......................................................................................

98 6.2 -LIQ UID RADW ASTE SYSTEM ... ..............................

..........................................................

99 6.3 -STEAM GENERATOR BLOWDOWN/CONDENSATE DEMINERALIZER

............................................

100 7.1 -GASEOUS EFFLUENT RELEASE/DISCHARGE POINTS. .............................

155 7.2 -DETAIL OF GASEOUS RELEASE!DISCHARGE POINTS .....................................

156 7.3 -GASEOUS RADWASTE TREATMENT SYSTEM ..........................................................................

157 7.4 -PLUME DEPLETION EFFECT FOR GROUND LEVEL RELEASES.

.....................

158 7.5 -VERTICAL STANDARDDEVIATION OF MATERIAL IN A PLUME ...................................................

.159 7.6.- RELATIVE DEPOSITION FOR GROUND LEVEL.RELEASES

......................................................

160 9.1 -REMP LOCATIONSW ITHIN ONE MILEOF THE PLANT ................................................................

170 9.2 -REMP LOCATIONS'FROM ONE TO FIVE MILES FROM THE PLANT ...........................................

171 9.3 -REMP LOCATIONS GREATER THAN FIVE MILES FROM THE PLANT ...........................................

172 El-66 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 I 0 (ODCM) Page 5 of 195

1.0 INTRODUCTION

The Watts Bar Nuclear Plant (WBN) Offsite Dose Calculation Manual (ODCM)"is a supporting documentof the WBN Technical Specifications (TS) required by WBN TS 5.7.2.3; The ODCM isdividedinto two major parts:,Controls (Sections 1 through 5) and program descript!on(Sections'

6. through 9). References are given in each section ýas applicable and are further described in Section 10.0.The first part of the ODCM (Sections 1 through 5) contains: 1) Radioactive-Effluent'Controls required by Section 5.7.2.7 of the.WBN TS;2). Radiological Environmental Monitoring Controls required by 10 CFR Part 50, Appendix.I,Section IV.B;3) Controls for Meteorological Monitoring Instrumentation;
4) Descriptions of the information that should be included in the Annual RadiologicalEnvironmental Operating and Radioactive Effluent Release Reports required by WBNl- echnicaF'Specifications 5.9.2 and 5.9.3;and 5) Administrative Controls for the ODCM requirements.

These sections of the'document have been prepared using the guidance provided in NUREG-1301 (Reference

1) and draft Nuclear Regulatory Commission Generic Letter (Reference 2). Exceptions to this guidance have been documented in Appendix B to the ODCM.The second part of the ODCM (Sections 6 through 9) contains the methodologies and-parameters used to: 1) Calculate offsite doses resulting from radioactive gaseous and'liquid effluents;
2) Calculate gaseousand liquid effluent monitor Alarm/Trip setpoints;,and, 3) Conduct.the Radiological Environmental Monitoring Program,(REMP).

These methodologies and parameters were developed using the guidance in NUREG-01.33 (Reference 3);Regulatory Guide 1:.109 (Reference 4); Regulatory Guide 1.111, (Reference 5); Regulatory Guide 1.113 (Reference 6); ,Regulatory Guide 1.21 (Reference 7); and Radiologicail AssessmentBranch Technical Position onEnvironmental Monitoring (Reference 8). Where any methodology or parameter.

differs from the guidance provided,1i the, above documents, it has been documented in the .text and references given for the source of the information.

E1-67 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 6 of 195 1.0/2.0 -CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.0 APPLICABILITY CONTROLS 1.0.1 Controls shall be met during the MODES or other specified conditions in the Applicability,,'except as provided in Control 1.0.2.1.0.2 Upon discovery of a failure to meet a Control, the Action(s) of the associated Conditions shall be met.If the Control is metor is no longer applicable prior to expiration;of theAction(s), completion of the Action(s) is not required unless otherwise stated.SURVEILLANCE REQUIREMENTS

2.0.1 Surveillance

Requirements(SR) shall be met during MODES or other conditions in theApplicability for individual Controls, unless otherwise stated in the SR. Failure to meet the Control occurs when a surveillance isfailed or when conditions occur between surveillances--that~would result.in affailed surveillance if testing was performed.

Failure to perform a surveillance within the specified frequency shall befailureto meet theControl except as provided in SR 2.0.3. Surveillancesdo, not have to- be performed on inoperable equipment or variables outside specified limits.2.0.2 The specified frequency foreach SR is met if the surveillance is performed within.1.25 times.the interval specified in the frequency, as measured from the previous performance or. asmeasured from a time a specified condition of the frequency is met.For frequencies specified'as "once," the above interval extension does not apply.If an Action requires periodic performance on a "once per..." basis, the above frequency extension applies to each performance after the initial performance.

Exceptions to this SR control section are stated in the individualSRs.

2.0.3 If it is discovered that a surveillance was not performed within its specifiedfrequency, then compliance with therequirement to declare the Control not metrmay be delayed, from the time of discovery, up to 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sor up to the limit of the specified frequency, whichever is less. This delay period is permitted to allow performance of the surveillance.

If the surveillance is not performed within the delay period, the Control must'irmmediately be declared not met, and the applicable Action(s) must be entered. The Action(s) begin 'immediately upon expiration of the delay period.When the surveillance"is performed within the delay period and the surveillance isnot met,. the Control must immediately be entered. The Action(s) begin immediately upon failureto meet the surveillance.

2.0.4 Entry:-into a MODE or other specified condition in the Applicability of a Control shall not be made unless the Control's surveillances have been met within .their specified frequency.

This provision shall not prevent passage through to MODES or other specified conditions incompliance with Action(s).

El-68 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page.7 6f,.1 95 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1I2.11 INSTRUMENTATION 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.1 As.required by WBN TS 5.7.2.7.a, the radioactive liquid effluent monitoringinstrumentation channels shown inTable 1.1-1 shall be OPERABLEwith their alarm/trip setpoints set~fo ensure that the limits of ODCM Control 1.2.1.1 are not exceeded.

The alarm/trip setpoints,of these channels shall be determined in accordance with the methodology and parameters in.ODCM Section 6.2.APPLICABILITY:

This requirement is applicable as shown in Table 1.1-1.ACTION: a. With a radioactive liquid effluent monitoring instrumentation, channel alarrm/tripsetpoint less conservative than required by the above control, immediately suspend the release ofrradioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so that it is acceptably conservative.

b. With less than .the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the action shown in Table 1.1-1. Restore the inoperable instruments to OPERABLE statusrwithin 30 days and, if unsuccessful,.explain in the next Annual.Radioactive Effluent Release, Report, pursuant to ODCM Administrative Control!52,.

why the inoperabil ty was not corrected within 30 days.c. The provisions of SR 2.0.4 are not applicable.

Report all deviations' in the Annual 2 Radioactive Effluent Release Report.SURVEILLANCE REQUIREMENTS 2.1.1 Each radioactive liquid effluent monitoring instrumentation

ýchannel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST operations.

at the frequencies shown in, Table 2.1-1.El-69 WBN OFFSITE DOSE CALCULATIONMANUAL Revision 22 0 (ODCM) Page, 8 of 195 Table 1.1-1 -RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Page 1 of 2)MINIMUM CHANNELS ACTION APPLICABILITY INSTRUMENT OPERABLE.1. RADIOACTIVITY MONITORS:PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a. Liquid. Radwaste Effluent Line (RE-90-122) 1 A (2)b. Steam'Generator Blowdown EffluentLine.

1 B (3)(RE-90-120A and -121)c. Condensate, Demineralizer Regenerant 1 A (2)Effluent Line (RE-90-225).

2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATIONOF RELEASE a. Essential Raw Cooling:WaterEffluent 1/Discharge C (1)Header .(RE790-1 33,-134,-140,-1
41) Header b. TurbineBuildingSump Effluent Line 1 C (1)(RE-90-212)
3. FLOW RATE MEASUREMENT DEVICES a. Liquid Radwaste Effluent Line 1 D (2)(0-FIT-77-5042)
b. SteamGenerator Blowdown Effluent Line 1 D (3)(1-FIT-15-42)
c. Condensate Demineralizer Effluent Line 1 D (2)(Fl-14i456)
d. Diffuser Discharge Effluent Line 1 D (2)(0-LPF-27-98)

Applicability Notation: (1) At all times.(2) During releases via this pathway.(3) During releases in MODES 1, 2, 3, and 4.El-70 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 90 of 195 Table 1.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Page 2 of 2)TABLE NOTATION ACTION A -With the number of channels OPERABLE less than required by the Minimum Channels-OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release: a. At least two independent samples of the tank's contents obtained by two technically qualified members of the facilitystaffare analyzed, and b. Atleast two technically qualified members of the facility staff independently verify therelease rate calculations, c. At least two technically qualified members of the facility staff independently verify the discharge valve lineup;Otherwise, suspend release of radioactive effluents via this pathway.ACTION B -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases viathis pathway may continue provided grab samples are analyzed for principal gamma emitters in accordance, with ODCM SR2.2.1.1.1 and 2.2.1.1.2.

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is.equal~to or greater than 0.01lCi/g DOSE EQUIVALENT 1-131, or b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than 0.01gCi/g DOSE EQUIVALENT 1-131.ACTION C -ACTION D -With the number of channels OPERABLE less than required by'the, Minimum Channels OPERABLE requirement, effluent releases viathis pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for principalgamma emitters in accordance with ODCM SR 2.2.1.1.1 and 2.2.1.1.2.

With the number of channels OPERABLE less than required by theMinimum:

Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases..

Pump curves or the change in tank level indication, if applicable, may be~used to estimate flow.El-71 WBN OFFSITE DOSE CALCULATION MANUAL Revisibn'22 0 (ODCM) Page 10 of 195 Table 2.1-1 -RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

-SURVEILLANCE REQUIREMENTS*(Page 1 of 2)I CHANNEL CHANNEL SOURCE CHANNEL 'OPERATIONAL INSTRUMENT I CHECK I CHECK :CALIBRATION, TEST 1. RADIOACTIVITY MONITORS PROVIDING ALARM ANDAUTOMATIC TERMINATION' OF RELEASE a. Liquid Radwaste Effluent D P R(3) 30Q(1,6)Line (RE-90-122)

b. Steam GeneratorBiowdown D M R(3) 3Q(5)Effluent Line (RE-90-120A and -121)c. Condensate Demineralizer D P/M** R(3) 3Q(5)Regenerant Effluent Line (RE-90-225)
2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OIFRELEASE
a. Essential Raw Cooling D M R(3) 3Q(2)Water Effluent Line (RE,-90-133,-134,-140,-141)
b. Turbine' Building Sump D M R(3) 3Q(2,)Effluent Line (RE-90-212)

.3. FLOWORATEMEASUREMENT DEVICES a. Liquid Radwaste Effluent D(4) N/A R N/A Line (0-FIT-77-5042)

b. Steam Generator Blowdown D(4) N/A R*** N/A EffluenttLine,(1-FIT-15-42)
c. Condensate Demineralizer D(4) N/A R N/A Effluent Line(FI-14-456)
d. Diffuser Discharge Effluent D(4) N/A Y Q Line:(LPF-27-98)
  • See Table 31 (FREQUENCY NOTATION) for the surveillance frequency definitions.
    • The source check on.the condensate demineralizer radiation monitor will be performed monthly during periodsofno release, and prior toeeach batch release during release periods:(when secondary coolant activity determination (principal gamma emitters) is greater than lxi 0'6 gCi/g).1-FIT-1 5-42 is a programmabledevice.

that has no calibration features.

Therefore, a calibration verification satisfies the channel calibration requirement.

El-72 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 11 of 195 Table 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORINGIINSTRUMENTATION SURVEILLANCE REQUIREMENTS (Page 2 of 2)TABLE NOTATION (1) The CHANNEL OPERATIONAL TEST shall demonstrate that automatic isolation of this-pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint.

The CHANNEL OPERATIONAL TEST also demonstrates control room annunciation occurs if any of the following conditions exist: 1, Instrument indicates measured levels above the alarm setpoint, or 2, Indication of downscale failure, or 3, Instrumentation controls not set in operate mode, or 4, Loss of sample flow.(2) The CHANNEL OPERATIONAL TEST shall demonstrate that control room alarm annunciation occurs if any of the following conditions exists: 1, Instrument indicatesmeasured levels above the alarm setpoint, or 2, Indication of downscale failure, or 3, Instrumentation controls not set in operate mode.(3) The initial CHANNEL CALIBRATION shall be performed usingone or more of the reference:

standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that are traceable via measurement assurancer activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION,, NIST traceable standards or sources that have been related to the initial calibration (transfer calibration sources) shall'be used.(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be.made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic:or batch releases, are made.(5) The CHANNEL OPERATIONAL TEST, shall demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm/trip setpoint.(6) The CHANNEL OPERATIONAL TEST that demonstrates control room annunciation upon a' loss of sample flow shall be performed at least once per 92 days.E1-73 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 12 of 195 1/2 CONTROLS AND'SURVEILLANCE REQUIREMENTS 1/2! INSTRUMENTATION 1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 1.1.2 rlnracco.rdance with WBN TS 5.7.2.7.a, the radioactive gaseous*effluent monitoring, instrumentation channels shown in Table 1.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure'that the limits of ODCM Control 1.2.2.1 and Technical Specification 3.3:6. are, not exceededý.

The alarm/trip setpoints of these channels shall be determined and adjusted in .accordancewith the methodology and parameters in ODCM Section 7.1.APPLICABILITY:

As shown in Table 1.1-2.ACTION: a. With a, radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive gaseouseffluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels:OPERABLE, take the ACTIONshown in Table 1.1-2. Restore the inoperabie instruments to OPERABLE status within 30:days and, if unsuccessful, explain in.the next Annual Radioactive Effluent Release Report, per ODCM Administrative Control'5.2, whythe inoperabilityiwas not corrected within 30 days.c. The provisions of SR 2.0.4 are not applicable.

Report all deviations-in the Annual Radioactive Effluent Release Report.SURVEILLANCE REQUIREMENTS 2.1.2. Each radioactive gaseous effluent monitoring instrumentation channelshall be demonstrated OPERABLE by performancemof the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST at the frequencies shown in Table.2.1-2.

El-74 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 13 of 195 Table 1.1-2 -RADIOACTIVE GASEOUS EFFLUENTMONITORING INSTRUMENTATION (Page 1 of 3)MINIMUM-INSTRUMENT

[CHANNELS INSTRUMENT_

OPERABLE APPLICABILITY

'ACTION, 1. WASTE GAS DISPOSALSYSTEM

a. Noble Gas Activity Monitor,(RE-90-118) 1 A b. Pressure Measuring Device 1 (9)(8) J WGDT A 0-PIS-77-115 WGDT B O-PIS-77-114 WGDT C 0-PIS-77-113 WGDT D O-PIS-77-100 WGDT E 0-PIS-77-101 WGDT. F 0-PIS-77-102 WGDT G 0-PIS-77-145 WGDT H 0-PIS-77-146 WGDT J O-PIS-77-147
2. CONDENSER VACUUM EXHAUST SYSTEM a. Noble-Gas Activity Monitors (RE-90-119) 1 _ (_3) C b. DeletedinRevision.5 I c. Flow Rate Monitor (FE-2-256) 1 (3) B d. Iodine/Particulate Sample Line Heat Trace P (3) K[SOURCE NOTE, 1.3]3. SHIELD BUILDING :EXHAUST SYSTEM a. Nobl Gas Low-Range Activity Monitor (RE-90-400A) 1 (2) E b. Iodine/Particulate Sampler and'Sampler Flow Rate 1 (2)(5) D Measuring Device (RE-90-400

-Monitor Item 028)c. Effluent.Flow Rate Measuring Device (FI-90-400) 1 (2) B, E d. IsokineticFIwContr61Equipment G (2)(6) G[SOURCE'NOTE 11]__e. Iodine/Particulate Sample Line Heat Trace I (2) G ,[SOURCE NOTE 13]f. Tritium'flowrate measuring device 1 (11) M (FIQ-90-801,)

4. AUXILiARYýBUILDINGMVENTILATION SYSTEM AND FUEL HANDLING'AREA VENTILATION SYSTEM a. Noble Gas Activity Monitor (RE-90-101B) 1 (ic) C b. Iod ine/Particulate Sampler and Sampler Flow Rate 1 (1)(5)(7)

D Measuring.Device (FIS-90-101,C)

c. EffluentFlow Rate Measuring Device (FI-90-300/1B) 1 (1) B, L d. Isokinetic Flow:Control Equipment 1 (1.0), H[SOURCE.NOTE 11]e. Tritium flowrate measuring device 1 (.11) M (FIQ-90-800)
5. SERVICE BUILDING:VENTILATION SYSTEM a. Noble Gas Activity"Monitor (RE-90-132B) 1 /1) I C.b: Effluent Flow.Rate Measuring System FI-90-320/1B 1 1 B 6. CONTAINMENT PURGE AND EXHAUST SYSTEM a. Noble, Gas Activity Monitors (RE-90-130, RE-90-131) 1 (4) F E1-75 WBN OFFSITE DOSE CALCULATION MANUAL Revision'22 0 (ODCM) Page 14iof 195 Table 1.1-2 -RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Page 2 of 3)Applicability Notation: (1) At altimes.(2) At all times. Both Unit 1 and 2 Shield Building Exhaust System equipment must meet the minimum channel OPERABLE requirement, even for Unit 1 operation only, Operability of shield building noble gas activity monitor requires both flow rate and radiation inputs since the high radiation alarm is only on the effluent channel, which reads in RCi/s.(3) In MODES 1 through 6 when Condenser Vacuum Exhaust System is in operation.

(4) At all times in MODES 1, 2i 3, 4; during core alterations; during movement of irradiated fuel assemblies within containment.

(5) Applies to charcoal and particulate'filters, does not apply to detection channels.(6) Shield Building isokinetic flow control equipment may be considered 6operable'if one primary sample pump 1,2-PMP-90-452A or -452B and the flow control valve 1,2-FCV-90-452 are operable.

If.automatic flow control, 1,2-FM-090L0400A, is unavailable, isokinetic~flow control must be established manually (using.1 ,12-FC-90-452), based on flow rates determined during most recent flow rate-measurement device calibration.

(7) Auxiliary Building Exhaust iodine/particulate samplermay be considered operable with the. isokinetic flow control equipment inoperable.

(8) The pressure indicator for the WGDT being released must be operable for the tank to be released.(9) At all 'timesduring periods of release.(10) Isokinetic sampling on the Auxiliary Building Exhaust is required when flow rate exceeds 160:000 SCFM.(11) At all times during periods of release when irradiated TPBARs are in the Reactor or.in the Spent Fuel Pool.Compensatory Actions ACTION A -ACTION B -ACTION C -ACTION D -With the number of channels OPERABLE less than requiredby the Minimum Channels OPERABLE requirement, the contents of the tank(s) 'may be released, to the environment providedthat prior to initiating'the release: a. At least two independent samples of the tank's contents obtained by twotechnically qualified members of the facility staff are analyzed,.

and b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations, and c. At least two technically qualified members of the Facility Staff independently-verify the discharge~valve lineup;Otherwise, suspend release of radioactive effluents via this:pathway.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during releasesvia this pathway.With the number of channels OPERABLE less than required~by the MinimumChannels OPERABLE :reqluirement, effluent releases via this pathway, may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and thesesamples are analyzed f6r noble gases (gamma emitters) in accordance with plant procedures.

Grab samples -are required only during those. periods when releases are being made.With the number of channels OPERABLE less than required by theWMinimum Channels OPERABLE requirement, effluent releases via the affected pathway may,!continue provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment as required in Table 2.2-2.Continuous sampling is required only during those periods when releases arebbeing made.El-76 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 15,of 195, Table 1.1-2 -RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Page 3 of 3)Compensatory Actions (Continued)

ACTION E -ACTION F -ACTION G -ACTION H -ACTION J -ACTION K-Flow. Rate Channel Inoperable.-

With an inoperable flow element on a discharge pathway where afan is~operating (Purge A, Purge B, ABGTS, or EGTS), effluent release rmay continue provided: (a) "Low Rng" on RE-90-400 is selectedinstead'of 7'Eff";.and (b) at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated instrument malfunction is verified not annunciated;'and (c) a reading from "Low Rng" on RE-90-400 is obtained at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the release.Radiation Monitor Inoperable-With the "EFF" and "LOW RNG" channels, inoperable, effluent releases may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for noble.gases (gamma emitters) in accordance with plant procedures.

Grab samples are required only during those periods when releases are being made.With the .number of channels OPERABLE less than required by theMinimum Channel OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE-requirement,.

planned ongoing effluent releases via the affected.pathway may continue provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the channel has:been declared inoperable, the equipment is restored to OPERABLE.With the required equipment inoperable, effluent releases may continue via this.pathway provided the sampler's transmission factor(s) are corrected for the loss of this equipment.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from that WGDT must bediscontinued until the channel is:OPERABLE.

With the heattrace inoperable and auxiliary sampling equipment.required for iodine and particulate collection, effluent releases via the affected pathwaymay continue provided that steam generator activity is evaluated weekly to determine if a path exists for release. of iodine or particulate activity, and any such activity being released is:quantified:in accordance with plant procedures.

ACTION L- With the required equipment INOPERABLE due to the flowrate being greater than 0 and less than 100,000 scfm, manually adjust sample loop O0LPF-90&300 flowrate.to 20 scfm +/-1 scfm within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to return the channel to operable status.Inaddition, if the flow rate is greater than 0 and less than 40,000 scfm, then. verify, at least one Auxiliary Building or Fuel Handling exhaust fan is running.ACTION M-With the required equipment inoperable, effluent releases, may continue .via the pathway provided that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the channel has been declared inoperable, samplers are replaced or tritium grab samples are taken once .per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Continuous sampling is required only. during those periods when applicability note (1 1) is met.E1-77 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 16 of 195 Table 2.1-2 -RADIOACTIVE GASEOUS EFFLUENT MONITORING]INSTRUMENTATION

-SURVEILLANCE REQUIREMENTS*(Page 1 of 2)CHANNEL'CHANNEL SOURCE CHANNEL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1. WASTE GAS DISPOSAL SYSTEM a. Noble Gas Activity.

Monitor (RE-90-118)

P P R(3) M(1)b. Pressure Measuring Device P N/A R N/A WGDT A 0-PIS-77-115 WGDT B 0-PIS-77-114 WGDT C 0-PIS-77-113 WGDT D 0-PIS-77-100.

WGDT E 0-PIS-77-101 WGDTF 0-PIS-77-102 ,WGDT G 0-PIS-77-145 WGDT H 0-PIS-77-146 W.GDT J 0'-PIS-77-147

2. CONDENSERVACUUM EXHAUST SYSTEM a. Noble Gas Activity Monitor (RE-90-119)

D M R(3)- 3Q(2)b Deletedin Revision 5 c. Effluent Flow Rate Measuring, Device (FE&2-256)

D N/A R N/A d. Deleted in Revision.5, e. Iodine/Particulate Sample Line, Heat Trace N/A N/A N/A Q[SOURCE NOTE 131.3. SHIELD BUILDING EXHAUST SYSTEM a. Noble Gas Activity Monitor (RE-90-400A)

D M R(3) 3Q(2)b. Iodine and Particulate.

Sampler (RE-90:402)

N/A N/A N/A N/A c. Effluent Flow Rate Measuring Device (FI-90-400)

D N/A R ,Q d. SamplerFlow Rate Measuring Device D N/A R Q (RE-90-400

-Monitor Item 028)e. Iodine/Particulate Sample'Line Heat Trace N/A N/A N/A Q[SOURCE NOTE 131 f. Tritium Flow Rate Measuring Device FIQ-90-801)

D N/A V N/A 4. AUXILIARY BUILDINGVENTILATION AND FUEL HANDLING-AREA VENTILATIONSYSTEM

a. Noble Gas Activity MonitOr (RE790-101 B) D M R(3) 3Q(2)b. Iodine~and Particulate Sampler (RE-90-101)

N/A N/A N/A N/A c. Effluent Flow Rate Measuring Device D N/A R Q (FI-90-300/1 B)d. Sampler Flow Rate Measuring Device D N/A R Q (FIS-90-101C)

e. Tritium Flow Rate Measuring Device ,(FIQ-90-800)

D N/A Y N/A 5. SERVICE BUILDING VENTILATION SYSTEM a. Noble Gas ActivityMonitor (RE790-1 32) D M R(3) '3Q(2)b. Effluent Flow Rate Measuring D N/A R Q System (FI-90-320/1 B), 6. CONTAINMENT PURGE AND EXHAUST SYSTEM Noble Gas Activity Monitors P '"(3)(RE-90-1 30, RE-90-1 31_* See Table 3.1 (FREQUENCYNOTATION) for the surveillance frequency definitions.

See WBN TS 3.3.6.1, 3.316.7, and 3.3.6.4 for these requirements.

E1-78 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 17 of 195 Table 2.1-2 -RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS*(Page 2 of 2)TABLE NOTATION (1) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists: 1. Instrument indicates' measured levels above the alarm/trip setpoint, or 2.lndication of downscale failure, or 3. Instrumentation controls not set in operate mode.(2) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: 1.Instrument indicates measured levels above the alarm setpoint, or 2.1ndication of dbwnscale failure, or 3. Instrumentation controls not set in operate mode.(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference.

standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that are traceable via measurementlassurance activities with NIST. These standards shall permit calibrating the system over its intended rangeof:.energy and measurement range. For subsequent CHANNEL CALIBRATION;, NIST traceable~standards or sources that have been related to the initial calibration (transfer calibration sources) shall be used.El-79 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 18 of 195 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.3. METEOROLOGICAL INSTRUMENTATIONIDATA CONTROLS 1.1.3 The meteorological monitoring instrumentation channels shown in Table 1.1-3 shall: be OPERABLE.APPLICABILITY:

At all times.ACTION: Withone or more required meteorological monitoring channels inoperable for more than 7;days,. prepare and submit a SpecialReport to the NRC, pursuant to ODCM Administrative'Control 5.4, within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status.The provisions of SR 2.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 2.1.3. Each of the above meteorological instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the CHANNEL CALIBRATION at least once per 184 days.El-80 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 19.of 195 Table 1.1-3 -METEOROLOGICAL MONITORING INSTRUMENTATION

'Minimum Instrument Location OPERABLE 1. WIND SPEED Channel 1 Nominal Height-10 m Channel 2 NominalHeight 46 m 2 of 3 Channel 3 Nominal Height 91 m 2. WIND DIRECTION Channel 1 Nominal Height 10 m ChannelF2 Nominal Height 46:m 2 of 3 Channel 3 Nominl Height 91 m 3. AIRTEMPERATURE

-DELTA T Channel 1 Nominal Height 10 to.46 m Channel2.

Nominal'HeightA10.to,91 m 1 of 3 Channel 3 Nominal Height 46 to 91,m _. *El-81 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 20 of 195 112 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.1 CONCENTRATION CONTROLS 1.2.1.1 In accordance with WBN TS 5.7.2.7.b and c, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure-3.1) shall belimited to .10 timesthe.concentration values specified in Appendix B, Table 2, Column 2 to 1OCFR 20.1001-20.2401 for radionuclides other than dissolved or entrained noble gases. For dissolved or~entrained noble gases, the concentration shall be limited to 2xl 0-4 pCi/mI total activity.APPLICABILITY:

At all times.ACTION: With the concentration of radioactive material released in liquid effluents exceeding theabove, limits, immediately restore the concentration to within the above limits.The provisions of SR 2.0.4 are not applicable.

Report all-deviations in the Annual Radioactive Effluent Release Report.SURVEILLANCE REQUIREMENTS 2.2.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling.

and analysis program of Table 2.2-1.2.2.1.1.2 The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in ODCM Section 6.1 to assure that the concentrations at-the point of'release are maintained within the limits of Control 1.2.1.1.El-82 WBN OFFSITE DOSE CALCULATION MANUAL Revision, 22 , 0 (ODCM) Page 21 of 195 Table 2.2-1 -RADIOACTIVE LIQUID WASTE SAMPLING-AND ANALYSIS PROGRAM (Page 1 of 3)Minimum Minimum ýLower Limit of.Sampling Analysis Type of Activity Detection Liquid Release Type Frequency Frequency Analysis .I (LLD),(+/-Ci/ml)

Batch ,Release Tanks 2 P P Principal, Gamma A. Radwaste System Tanks Each Each Batch Emitters 3 5x10-7 Waste Condensate A, B, & C Batch Cask Decontamination*

1-131 1x10, Chemical Drain P M Dissolved/

Monitor One Entrained Noble lx10" 5 Laundry and Hot Shower A&B Batch/M Gases (Gamma Emitters)B. Condensate Demineralizer P M H-3 lx10 5 System Tanks 6 Each Lab Waste Neutralization Batch Composite 4 Gross Alpha lx1.0i7 Non-Reclaimable Waste P Q Sr-89 .Sr-90 5x10'8-High Crud A&B Each Lab Batch Composite 4 Fe-55 lx110-6 Continuous Releases 5 D D Principal Gamma 5x10" 7 C. Steam Generator Grab Each Grab Emitters 3 Blowdown 6 Sample Sample 1-131 lX101-D. Turbine Building Sump 6 M M Dissolved/

Grab Entrained' Noble lx10 5 Sample Gases (Gamma Emitters)D M H-3 1x10-5 Grab Lab Sample Composite 4 Gross Alpha 1x10"1 D Q Sr-89, Sr-90 5x10-8 Grab Lab I Sample Composite 4 Fe-55 lx 1,07" E. Groundwater Sump M M PrincipalGamma 5x10-7 Grab Each Grab Emitters 3 Sample Sample 1-131 1x10-6 Dissolved/

Entrained Noble lx1i0" Gases (Gamma Emitters)H-3 lxl 0-5 Q Q Grab Grab Sr-89, Sr-90 5x10-8 Sample Sample*See Table 3.1 (FREQUENCY NOTATION) for the surveillance frequency definitions.

E1-83 WBN OFFSITE DOSE CALCULATION MANUAL Revision'22 0 (ODCM) Page 22 of195 Table 2.2-1 -RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 2 of 3)TABLE NOTATION The LLD is defined for the purpose of these Controls as the smallest concentration of radioactive material in a sample that will yield a net count, above system, background, thatwilLbei detected with 95% probability with-only a 5% probability of falsely concluding that a blank observation represents a"real" signal. (Reference 8)For a particular measurement system (which may include radiochemical separation):

LLD = 4.6 6 Sb E V 2.22E6 Y exp(-XAt)where: LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume).Sb = the standard deviation of the background counting rate or of the countingrate of a blank sample as appropriate (counts per minute).E =.the counting efficiency. (counts per disintegration).

V = the sample size (units of mass or volume).2.22x10 6 = the number of disintegrations per minute per microcurie.

Y = the fractional radiochemical yield, when applicable.

I = the radioactive decay constant for the particular radionuclide (s-1), and Dt = the elapsed time between midpoint of sample collection and time of counting (s). The definition of Dt applies only to the calculation of the LLD. A more rigorous treatment of the buildup and decay during the sample collection and/or counting interval(s) may be applied to actual sample analysis if desired.It should be recognized that the LLD is defined as an a priori (before the fact).limit representing;the capability of a measurement system and not an a posteriori (after the fact)ý limit for a particular, measurement.

Typical values of E, V, Y, and At should be used in the calculation.

2 A batch release is the discharge of liquid wastes of a discrete volume. Prior to samplingrfor analyses, each batch shall be isolated and then thoroughly mixed by the method described in appropriate plant procedures to assure representative sampling.3 The principal gamma emitters for which the LLD Control applies exclusively arethe following' radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, MO-99, Cs-134, Cs-137, Ce-141. Ce&144 shall also be measured, but with -an LLD of 5x10-6 gtCi/ml. This list does not mean that only.these, nuclides are to be considered.

Othergamma peaks which are identifiable, together with~thoseo0f the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release.Report pursuant to ODCM Administrative Control 5.2, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.4 A laboratory composite sample is one prepared by combining representative samples from each release into one well-mixed, homogeneous sample. The volume of sample added to thecomposite from each release shall be proportional to the release volume. The composite

ýsample shall' be preserved according to plant procedures as appropriate.

El-84 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Paget23 of 195 Table 2.2A1 -RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Page 3 of 3)TABLE NOTATION 5 A continuous release is.the discharge of liquid wastes of a nondiscrete volume; eg., from a system that has an input filow during the continuoUs release.6 Not applicable whenmost recent Secondary Coolant System activity determination (principal gamma emitters).is less:than or equal to lx10i 6 gCi/g and either of the followin g conditiohs exist: (1) !he discharge'radiation, monitor setppint is less than or equal to 2 times background or (2)compensatory requirements associated with applicable inoperable monitors are met.E1-85 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page-24 of 195 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 112.2.1.2 DOSE CONTROLS 1.2.1.2 In accordancewith WBN TS 5.7.2.7.d and e, the dose or dose, commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents discharged fromeach unit;.to UNRESTRICTED AREAS (see Figure 3.1) shall be limited: a.During any.calendarquarter to less than or equal to 1.5 mrem to the total.body and to less .than or equal to 5rmrem to any organ, and b.During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.APPLICABILITY:

At all times.ACTION: With the calculated dose from the.release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and::submit to the NRC within 30 days, pursuant to ODCM Administrative Control 5.4; a Special Report that. identifies the cause(s)'for exceeding the limit(s) and defines the corrective actions that havebeen taken to reduce the releases and the proposed correctiveactions to be taken to assure that subsequent releases will be in compliance with the above limits. This Spedial' Report shall also include: (1) the results of radiological analyses .of drinking water sources and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40CFR 141, Safe Drinking Water Act, (applicable only if drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge).

The provisions of SR 2.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 2.2.1.2' Cumulative dose contributions from liquid effluents for the current calendar quarter and current calendar year-.shall be~determined in accordance with the methodology and parameters in ODCM Section 6.3 at. least once per 31 days.[SOURCE NOTE 5]El-86 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22.0 (ODCM) Page 25 of 195 1/2 CONTROLS AND SURVEILLANCEREQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM CONTROLS 1.2.1.3 In accordance with WBN TS 5.7.2.7.f, the Liquid Radwaste Treatment System (LRTS) shall. be OPERABLE and appropriate portions of the system shall be used to reduce..the radioactive.

materials in liquidwastes prior to their discharge when the projected doses due to the liquid effluent from'each unit to UNRESTRICTED AREAS (see Figure 3.1) would exceed 0.06 mremto the totalbody or 0.2 mrem to any organ in a 31-day period.APPLICABILITY:

At all times.ACTION: With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the LRTS not in-operation, prepare and submit to the NRC within 30,days, pursuant to ODCMAdministrative Contr0l15.4, a Special Report which:includes the following information:

1. Explanation of why liquid waste was being discharged without treatment, identification of the inoperable equipment or subsystems, and the reason for the inoperability, 2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and 3. Summary description of action(s) taken to prevent a recurrence.

The provisions of SR 2.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 2.2.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with the methodology and parameters.

in ODCM Section 6.5 when the LRTS are not being fully utilized.[SOURCE NOTE 91 2.2.1.3.2 The installed LRTS shall be considered OPERABLE by meeting ODCM Controls 1.2.1.1 and 1.2.1.2.EI-87 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 26 of 195 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2,2.2 GASEOUS EFFLUENTS 1/212.2.1 DOSE RATE CONTROLS 1.2.2.1 In accordance with WBN TS 5.7.2.7.g, the dose rate due to radioactive materials released in gaseous effluents from.the site to areas at and beyond the UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following:

a.For noble gases: Less than or equal to a dose rate of 500 mrem/y to. the total body and less than or equal to a dose rate of 3000 mrem/y to the skin, and b. For Iodine-131, Iodine-133, tritium, and for all radionuclides inparticulate -form with':half-lives ,greater than 8 days: Less than or equal to a dose rate of 1500 mrem/y to any organ.APPLICABILITY:

At all times.ACTION: With dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).The provisions of.SR 2.0.4 are not applicable.

Report all deviations in the Annual Radioactive.Effluent Release Report.SURVEILLANCE REQUIREMENTS 2.2.2.1.1 The dose rate due.to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in ODCM. Section 7.2.2 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 2.2-2.[SOURCE NOTE 7]2.2.2.1.2 The dose rate due to lodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in ODCM Section 7 2.3 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 2.2-2.[SOURCE NOTE 7,1]El-88 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 27 of 195 Table 2.2-2-RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSISPROGRAM*(Page 1 of 3)Gaseous Release Type Minimum Analysis Type of Activity Lower Limit of Sampling, Frequency Analysis Detection Frequency (LLD) (l+/-Cilml)1 A. Waste Gas P P Ndble.Gases 2 lx10-4 Decay Tank Each Tank Each (Gamma, Emitters)Grab Sample Tank H-3. (oxide) J1xlO-6 B. Containment P8 P Noble:GasesZ PURGE 3 Each Each (GammaErmitters):.

lx10-4 PURGE Purge Grab Sample C. Incore Instrument Each Each Noble Gases 1x10-4 Room PURGE 3 PURGE 9 Purge (Gamma Emitters)Grab Sample D. Requirement Deleted .I E. Auxiliary Building Exh.olU M M Noble Gasesz 1xj 0-4 F. Condenser.

Vacuum Exh.1 I Grab Sample (Gamma Emitters)G, ServiceBuilding Exh.H. Deleted in Revision 11.I. Deleted in Revision 11.J. Deleted in Revision 11.K. Auxiliary Building Exh. Continuous 6 W H-3 (oxide) lx10-6 L. Shield Building Exh. Tritium M. Condenser Vacuum Exh.1 1 , 1 2 Sample Continuous 6 W7 1-131 lx10-1 2.Charcoal 1-133 1x10-1 0 Sample Continuous 6 W7 Principal Gamma 1 xi 0.11 Particulate Emitters 2 Sample Continuous 6 M Gross Alpha 1x10":11 Composite Particulate Sample Q Sr-89, Sr-90 1x10 1 1 See Table 3.1 (FREQUENCY NOTATION) for the surveillance frequencydefinitions.

El-89 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 28,of'195 Table 2.2-2-RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS`PROGRAM (Page 2 of 3)TABLE NOTATION The LLD is defined in Note 1 of Table 2.2-1.2 The principal gamma emitters for which the LLD Control applies include the following radionuclides:

K(-87, Kr-88, Xe-133, Xe-133m, Xe-1l35, and Xe-138 in noblegas releases andMn-54, Fe-59, 1-131, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144.in Iodine and particulate releases.This list does not mean that only these nuclides are to be considered.

Other gamma peaks-that are identifiable, together with the above nuclides, shall also be analyzed and reported in;the.Annual Radioactive Effluent ReleaseReport pursuant to ODOM Administrative Control 5.2, in, the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.3 Sampling and analysis for containment purges, incore instrument room purges, and the Auxiliary BuildingExhaust shall alsobe performed following shutdown, startup,, or a thermal power change exceeding 15% of RATED THERMAL POWER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period unless (a) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased'more than a factor of 3 and (b) the containment noble gas activity monitor.(RE-90-106 or RE-90-112)ior latest grab sample obtained as compensatory requirement associated with applicable inoperable monitorshows that the radioactivity-.has not increased by more than a factor of 3.4 Deleted in Revision 11 5 Deleted in Revision 11 6 The ratio of the sample flow rate to the sampled stream flow rate shall be known for the timeperiod covered by each doseor dose rate calculation made in accordance with ODCM Controls 1.2.2.1, 1.2.2.2, and 1.2.2.3.7 Samples shall be changed at least once per 7days. Analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler for those release points that had a discharge during the sampling period. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least,7 days following each shutdown, startup, or THERMAL POWER change exceeding 15%-of RATED THERMAL POWER within.a one hour period for those release points that had a discharge during the sampling period. Analyses of samples shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.

When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> areanalyzed, the corresponding LLDs may be increased by.a factor of 10. This daily sampling and analysis requirement does not apply if: (1) analysis showsmthat the DOSE EQUIVALENT 1-131 concentration in the reactor coolant has not increased by more than a factor of 3;.,and:,(2) the containment noble gas monitor aligned to lower containment (RE-90-106 orRE'90-112) or latest grab sample obtained as compensatory requirement associated with applicable inoperable monitor shows that the'radioactivity has not increased by more than a factor of 3.8 In all MODES, the compartment(s) of the containment to be purged shall be sampled for noble gas prior to PURGING.9 The incore instrument room PURGE sample shall be obtained at the shield'building monitor between 5 and 20 minutes following initiation of the incore instrument room PURGE.El-90 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 29 of 195 Table 2.2-2-RADIOACTIVE GASEOUS WASTE'MONITORING SAMPLING AND.ANALYSIS PROGRAM (Page 3 of 3)TABLE NOTATION 10 Applicable in-MODES 1, 2, 3, and 4, the containment will be VENTED to the containment annulus and then to the auxiliary building via containment annulus fans. The lower containment noble, gas monitor (RE 106.or -112) response will be recorded daily when VENTING is occurring to monitorthe radioactivity being discharged.

The Auxiliary Building Exhaust will beire-sampled when the~reading on the lower containment radiation monitor (RE-90-106 or -112) increases by 50% from the~initial value. If the lower containment noble gas monitor (RE-90-106 or -112) is inoperable, noble gasgrab samples may be used to perform this comparison.

1 Not applicable when the most recent Secondary Coolant System radioactivity determination (principal gamma emitters) is less than or equal to lx10-6 glCi/g and either ofthe-following conditions exist: (1) the discharge~radiation monitor setpoint is less than or equal to 2 times background or (2) compensatory requirements associated with applicable inoperable monitors are met.12 Continuous tritium samplecollection not applicable.

El-91 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 30 of'195 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVEEFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 112.2.2.2 DOSE -NOBLEGASES CONTROLS 1.2,.2.2 In accordance-with WBN TS,5.7.2.7.h, the air dose due to noble gases released in gaseous effluents from each unit to areas at and beyond the UNRESTRICTED-AR EABOUNDARY (see Figure 3.1) shall be limited to the following:

a. During any calendarquarter:, Less than or equal to 5 mrad for gamma radiation and lessthan or equal to 10mradfor.

beta radiation, and b. During any calendaryear:

Less than or equal to 10 mrad for gammas radiation and less than or equalito 20 mrad for beta radiation.

APPLICABILITY:

At all times.ACTION: With the calculated air dose from radioactive noble gases in gaseous effluents exceeding .any of the above limits, prepare and submit tothe NRC within 30 days, pursuant to ODCM Administrative Contro 5.4, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have~been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.The provisions of SR 2.0.4 are not applicable.

SURVEILLANCE ,REQUIREMENTS 2.2.2.2 Cumulative dose contributions for the current calendar quarter and current calendar,.year for noble gases shall~be determined in accordance with the methodology and parameters inODCM Section 7.3 at least once per 31 days.[SOURCE NOTE 5]El-92 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 31 of 195 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.3 DOSE 131, 1-133, TRITIUM, AND RADIONUCLIDES'IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS CONTROLS 1.2.2.3 In accordancewith WBN TS 5.7.2.7.i, the dose to a MEMBER OF THE PUBLIC from 1-131,1-133, tritium,.and alI radionuclides in particulate form with half-lives greater than,8 days.,in gaseous effluents released, from each unit to areas at and beyond the UNRESTRICTED AREA BOUNDARY (see Figure 3.1) shall be limited to the following:

a.During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, b. During any calendaryear:

Less than or equal to 15 mrem to any organ.APPLICABILITY:

At all times.ACTION: With the calculated dose from the release of 1-131, 1-133, tritium, andallradionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceedingany ofthe abovejlimits,prepare and submit to the NRC within 30 days, pursuant to ODCM Administrative Control 5.4,aSpecial'.Report which identifies the cause(s) for exceeding the limit(s) and defines the correctiveactions thathavebeentaken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.The provisions of SR 2.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 2.2.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for 1-131, 1-133, tritium, and all radionuclides in particulate form with half4ives greater than 8 days shall be determined in accordance with the methodology and parameters inODCM Section 7.4 at least once, per 31 days.[SOURCE NOTE 51 E1-93 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 32 of 195 1/2 CONTROLSAND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.2 GASEOUS EFFLUENTS 1/2,2.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 1.2.2.4 In accordance with WBN TS 5.7.2.7.f, the VENTILATION EXHAUST TREATMENTSYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases from each unit to areas at and beyondthe-UNRESTRICTED AREA BOUNDARY (See Figure 3.1) would exceed: a. 0.2 mrad to air from gamma radiation, or b. 0.4 mrad to air from beta radiation, or c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.APPLICABILITY:

At all times.ACTION: With the radioactive gaseous waste being discharged without. treatment and in excess of the abovelimits, prepare and submit to the NRC within 30 days, pursuant to ODCM Administrative Control.:5.4, a Special Report that includes thefollowing information:

1. Identification of the inoperable equipment or subsystems andthe reason for inoperability
2. Action(s) taken to restore the inoperable equipment to OPERABLE status,. and 3. Summary description of action(s) taken to prevent a recurrence.

The provisions of SR 2.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 2.2.2.4.1 Doses due to gaseous releases from eachunit to areas at and beyond.the UNRESTRICTED AREA BOUNDARY shall be projected at least once per 31 days, iin accordance ,with the methodology and parameters in ODCM Section 7.5 when.the VENTILATION EXHAUST TREATMENT SYSTEMS and WASTE GAS HOLDUP SYSTEMS are not being fully utilized.[SOURCE NOTE 9]2.2:2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEMS and WASTE GAS HOLDUP SYSTEM' shall be considered OPERABLE by meeting the requirements in ODCM Controls 1.2.2.1, 1.2.2.2, and 1.2.2.3.El-94 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 33 of 195 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.3 TOTAL DOSE CONTROLS 1.2.3 In accordance with WBN TS 5.7.2.7.j, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radibactivity and to direct radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25:mrem to the total body or,any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.APPLICABILITY:

At all times.ACTION: a.With the calculated doses from the release of radioactive materials.in liquid orgaseouseffluents.

exceeding twice the limits of ODCM Control 1.2.1.2, 1.2.2.2, or 1.2.2.3; calculations shall be made in accordance withODCM Section 8.1 including direct radiation contributions from thereactor units and from outside storage tanks to determine whether the above limits have.been exceeded.

If such. is the case, prepare and submit to the NRC within 30 days, pursuant to ODCM Administrative Control[5.4, a Special Report that defines the corrective action to be taken to reduce subsequentreleases toýprevent recurrence of. exceeding:the.above:

limits and includes the schedule for achievihg conformnarnce with the above limits. This Special Report, as defined in 10 CFR 20.2203(a)(4), shall include an analysis that estimates the radiationexposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all.effluent, pathways and direct radiation, for the calendar.year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive materials involved, and the cause of the exposure levels or concentrations.

If-the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance&in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until the staff action on the request is complete.b.With the estimated doses exceeding the 40 CFR 190 dose limits, aseparate determination must be made, in ,accordance with the requirements of 40 CFR 302.5, regarding the reportable quantities for radionuclide releases given in 40 CFR 302.4. Any required notifications will .be made in accordance with ODCM Administrative Control 5.5.c. The provisions of SR 2.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 2.2.3.1 Cumulative dose contributions from liquid and gaseous effluents shall.be determined in accordance with ODCM Surveillance Requirements 2.2.1.2,2.2.2.2, and 2.2.2.3 andin accordance with the methodology and parameters in ODCM Sections.

6.3, 7.3, and:7.4.2.2.3.2 Cumulative dose contributions from direct radiation from the units-and from radwaste storage tanks shall be obtained from the REMP described in ODCM Section 9.1. This requirement is applicable only under conditions set forth in the action above.E1-95 WBN OFFSITE DOSE CALCULATION MANUAL RevisiOnf 22 0 (ODCM) Page,34 Of 195 112 CONTROLS AND SURVEILLANCE REQUIREMENTS 112.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM CONTROLS 1.3.1, As required by 10 CFRPart 50, Appendix I, Section IV.B,.the Radiological Environmental Monitoring Program (REMP) shallbe conducted as specified in Table.2.3-1.

APPLICABILITY:

At all times.ACTION: a. With the REMP not being conductedas specified in Table 2.3-1, prepare and-submit to the NRC, in the Annual. Radiological Environmental Operating Report described inrODCM Administrative Control 5.1,-a description of the reasons for not~conducting the program as required anidtherplan for preventing a recurrence.

b. With the level of radioactivity as,aresult of plant effluents in an environmenta[sampling medium at a specified location exceeding the reporting levels of Table 2.3-2, when averaged over any calendar quarter, prepare and submit:to the NRC within 30 days from the end of the affected quarter,'

pursuant to ODCM Administrative Control 5.4, a Special Report that identifies the cause(s) for. exceeding the limit(s) and define.s'the corrective actions to be taken to reduce: radioactive effluents, so that the potential annual dose* to a MEMBER OF THE PUBLIC is less thani:thecailendar year limits ofODCM Controls 1.2.1.2, 1.2.2.2 and 1.22.3. When more than one of the radionuclid6s in Table 2.3-2.are detected in the sampling medium, this report shall be submitted if: concentrationfi)

+ concentration(i

+ 1).>lirn it level (i) lim it level (i + 1)When radionuclides other than those in Table 2.3-2 are detected and ate the result of planteffluents, this report shall be submitted if the potential annual dose* to a MEMBER OFTHE PUBLIC from all radionuclides is equal to or greater~than the calendar year limits of ODCM Controls 1.21.2,14.2.2.2, and 1:22.3. This report is not requited if the measured, level of radioacti ity was not the result: of plant effluents; however, in such an event, the condition shall be reported andAdescribed in the Annual Radiological Environmental Operating Report described in ODCM Administrative Control 5.1.* The methodology.and parameters used to determine the potential annualdoseJto a MEMBER OF THE PUBLIC shall be indicated Iin this report.E1-96 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 35 of 195 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1. MONITORING PROGRAM ACTION (CONTINUED):

c. With milk or fresh leafy vegetation samples unavailable from one or more of the sample:locations required by Table .2.3-1, identify specific locations:for obtaining replacement Samples and'add them within 30 daysto the REMP described in ODCM Section 9.0 (excluding short termwor temporary unavailability).

The specified locations from which samples were unavailable may then'be deleted from the monitoring program.Pursuant to ODCM Administrative Controls 5.2 and 5.3, submit in the next Effluent Release Report documentation for a change in the ODCM, with supporting information identifying the causeof the unavailability of samples and justifying the selection of the new location(s) for obtainingsamples.

The provisions of SR 2.0.4-are not applicable.

SURVEILLANCE REQUIREMENTS 2.3.1' The radiological environmental monitoring samples shall be collected pursuant to Table,2.3-1 from the specific locations given in the tables and figures in ODCM Section 9.0 and shall be analyzed pursuant to the requirements of Table 2.3-1 and the detection capabilities required, by Table-2.3-3.

[SOURCE NOTE 6]El -97 WBN OFFSITE DOSE CALCULATION'MANUAL Revision 22Z 0 (ODCM) Page 36 Of 195 Table 2.3-1 -MINIMUMREQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 1 of 5)Exposure Pathway andlor

  • Number of Samples.and Sampling and j Type and Frequency of Sample .SampleLocations 1 Collection.Frequency , Analyses*1. DIRECT RADIATION 2__Forty'routine monitoring Quarterly Gamma dose stations either with two or quarterly more dosimeters or with one instrument 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 UNRESTRICTED AREA BOUNDARY; and An outer ring of stations, one in each meteorological sector in the 6- to 8-km range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.2. AIRBORNE Radioiodine

ýSamples from five locations:

Continuous sampler Radioiodine,.canister:

and. Three samples from.close to operation with. 1-131 analysis weekly Particulates the three unrestricted area sample collection boundary locations in weekly, or more Particulate sampler: different sectors of the frequently if required Gross beta highest calculated annual by dust loading. radioactivity.

analysis average ground-level D/Q; followiIng, fiIter change 4 One sample from the vicinity and gammaisotopic of a community having the analysis 5 of composite highest calculated annual (by locationquafterly) average ground level D/Q;and One sample from a control location, as for example 15-30 km distant and in the least_ _ prevalent wind direction 3 El-98 WBN OFFSITE DOSE CALCULATION

ýMANUAL Revision 22 0 (ODCM) Page 37,of 195 Table 2.3-1 -MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 2 of 5)Exposure Pathway and/or Number of Samples and Sampling and Type and Frequency of Sample Sample Locations 1 Collection Frequency[

Analys6s: 3. WATERBORNE Surface 6 One sample upstream.

Composite sample Gamma' isotopic One sample downstream.

over a 1-month analysis 5 monthly;period.7 composite for tritium.analysis quarterly.

Ground Samples from one or two At least once per 92 Gamma isotopic 5 and sources only if likely to be days tritium analysis affected 8 quarterly.

Drinking One sample of each of one to Composite sample Gross betawand three ofthe nearest water over a one month gamma isotopic supplies that could be period.7 analyses0'monthly.

affected by the discharge 9 Composite.foi*'tritium analysis quarterly.

Shoreline One Sample from Semiannually Garmma isotopic Sediment downstream area with analysis semiannually existing or potential recreational value Holding Samples from at least three Annually Gamma'isotopic Pond locations in the Yard Holding analysis 5 annually Sediment Pond 4. INGESTION Milk Samples from milking Semimonthly when Gamma isotopiC5 and animals in three locations animals~are on 1-13.1 analysis semi-within 5 km distance having pasture; monthly at monthly when animals the. highest dose potential.

If other times. are on. pasture;there are none, then one monthly at other times.additional sample from milking animals in each of one to three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem/yr 1°One sample from milking animals at a control location 15-30 km distant and in the least prevalent wind direction.3 I E1-99 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 38 of 195 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 3 of 5)Exposure Pathway and/or Number of Samples and Sampling and Type and"Frequency of Sample SampleLocations 1' Collection Frequency.

Analyses INGESTION (continued)

Fish One sample ofocommercially Sample in season, Gamma isotopic'important species and one or semiannually if analysis 5 on edible sample of recreationally they are not portions.important species in vicinity seasonal.of plant discharge area and the Chickamagua Reservoir.

One sample of same species in.areas not influenced by_ plant discharge.

Food Onesample of each principal At time of harvest 1 1 Gamma isotopic Products class of food products from analysis 5 on edible any area within 10 miles of portion.the plant that is irrigated by water in which liquid plant ,wastes have been discharged..Samples of three different kinds of available broad leaf vegetation grown nearest each of two different offsite locations of highest predicted annual average ground-level D/Q if milk sampling is not performed as outlined in 4.a.above.One sample of eachof the similar broad leaf vegetation grown 15-30 km distant in the least prevalent wind direction if milk sampling is not performed as outlined in 4.a.above.3 El-100 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page.39 of 195 Table 2.3-1 -MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 4 of 5)TABLE NOTATION 1 Specific parameters of distance and direction sector from the centerline of one-reactor, and, additional description where pertinent, shall-be provided for each and every samplelocation in Table 2.3-1in a table(s) and figure(s) in ODCM Section 9,0. Refer to.NUREG-1301', "Offsite DoseCalculation Manual Guidance:

Standard Effluent Controls for.Pressurized Water Reactors, Generic:Letter 89-01, Supplement 1 ," April 1991. Deviations are permitted from the required samplingschedule if specimens are, unobtainable due.to hazardous conditions, seasonal unavailability,, malfunction of automatic sampling:.equipment and other legitimate reasons. If specimensare unobtainable due to.sampling equipment malfunction, every effort shall be made to complete corrective~action priorto the end of the nextsampling period. All deviations from the sampling sclheduleshallbe documented in the Annual Radiological, Environmental Operating Report pursuant to ODCM Administrative Control05.1.

Itis recognized that; at~times, it may~not be possible or practicable to continue~toobtain samples.'of the media of choice atthe'mostidesired location or time. In these instances suitable specifictalternative media and locations mayý be chosen..for the particular pathwayin question'and appropriate

substitutions madewithin 30 'days in'the Radiological EnvironmentalMonitoring Program given in:!ODCM Section 9.0. Pursuant to ODCMAdministrative Controls 5.2 and53Asubmit in the next-Annual Radioactive Effluent Release!Report documentation for a change in :ODM Section.9.0, including a revised, figu re(s), and..table reflecting the new location(s) with supporting information identifying the cause. of the unavailability of samples for thatpathway and justifYing'the selection of the newlocation(s) for obtaining samples.2 Removed in Revision 19.3 The purpose of this sample is to obtain backgroundinformation.

If it is not practical to~establish control locations in accordancewith the distance and wind direction criteria, other sites that provide: Valid background data may be substituted.

4 Airborne particulatesample filters shall be analyzed for gross beta radioactivity.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in airparticulate samples is greater than 10 times, that of control samples, gamma isotopic analysis shall:be performedon the individual samples.5 Gamma isotopic analysis means the identification and quantification of gamma-emittingiradionuclides that maybe attributable to the effluents from the WBN plant.6 The "upstream sample" shall be taken at a distance beyond significant influence of the discharge.

The"downstream sample" shall be taken in an area beyond but near the mixing zone.EI-101 WBN OFFSITE DOSE CALCULATION MANUAL (Revision22 0 (ODCM) Page 40Wo 195 Table 2.3-1 -MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 5 of 5)TABLE NOTATION 7 A composite.sample is one.in which the quantity (aliquot) ofliquid sampled is proportional'to the-quantity Of flowing liquid and in which the method of sampling employedresultsih a specimen that is representative-of the liquid flow. In this program composite sample aliquots shall be at time intervals that are very short (e6g., hourly) relative to the compositing period (e.g, monthly) in order to assure obtaining a representative sample. The composite sample shall.be preserved according to plant procedures as appropriate.

8 Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge propertiesare suitable for contamifiation.

Groundwater flow in the area of WBN has been shown~to be toward Chickamauga Reservoir (Reference'9)',.

There are no sourcestapped for drinking or irrigation purposes between the plant and the reservoir.

Therefore, sampling of the medium is not required.9 The surface water control shall be considered a control for the drinkingiwatersamples.

10 The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in ODCMSection 7.4.11 If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to includingsýamples of tuberous and root food products.El-102 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 41of 195 Table 2.3-2 -REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS:IN ENVIRONMENTAL SAMPLES Airborne Food Water Particulate or Fish Products Analysis (pCiIL)3 gases (pCi/Kg, wet)4 Milk (pCi/L)3 (pCi/Kg, wet)4 (pCi/m 3)5 H-3 20,0001 N/A N/A N/A N/A Mn-54 1,000 N/A 30,000 N/A N/A Fe-59 400 N/A 10,000 N/A N/A Co-58 1,000 N/A 30,000 N/A N/A Co-60 300 N/A 10,000 N/A N/A Zn-65 300 N/A 20,000 N/A N/A Zr-Nb-95 400 N/A N/A N/A N/A 1-131 22 0.9 N/A 3 100 Cs-134 30 10 1,000 60 1,000 Cs-1 37 50 20 2,000 70 2,000 Ba-La-i 40 200 N/A N/A 300 N/A 1 Footnote I deleted in Revision.20.

2 For drinking water samples. If no drinking water pathway exists, value of 20 pCi/L may be used.3 Multiply the values in this column by 10-9 to convert to units of ACi/ml.4 Multiply the values in this column by 10-9 to convert to units of g.Ci/g (wet).5 Multiply the values in this column by 10-12 to convert to units of pCi/cc.El-103 WBN OFFSITE DOSE CALCULATIONMANUAL Revision 22 0 (ODCM) Page 42 of 195 Table 2.3-3 -DETECTION CAPABILITIES FOR ENVIRONMENTAL:SAMPLE ANALYSIS 1 , 2-LOWER LIMITS OF DETECTION (LLD)3 (Page 1 of 2)Airborne Particulate Food Water" or Ga;ses Fish (IpCi/K~g, Milk Products Se , Sdimnent Analysis (pCiIL)6', (pCi/m)8 wet)7 (pCi/L)6 (pCiiKg, wet)7 (pCilKg, dry)7 gross beta 4 '0.01 N/A N/A N/A N/A H-3 20004 N/A N/A N/A N/A N/A Mn-54 15 N/A 130 N/A N/A N/A Fe-59 30 N/A 260 N/A N/A N/A Co-58;. 60 15 N/A 130 N/A N/A " N/A Zn-65 30 N/A 260 N/A N/A N/A Zr-95 30 N/A N/A N/A N/A , NA Nb-:95 15 N/A N/A N/A N/A N/A 1-131 15 0.07 N/A 1 60 N/A Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-i40 60 N/A N/A 60 N/A N/A La-l40 15 N/A N/A 15 N/A: N/A TABLE NOTATION 1 This list does not mean that only these nuclides are to be considered.

Other nuclides that are identifiable, together with those of the above nuclides, shall also be analyzed and reported, in the Annual Radiological Environmental Operating Report pursuant to Administrative Control 5.1.2 Required detection capabilities for DOSIMETERsusedfor environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.3 The LLDis defined, forthe purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, abovesystem background, thatwill be detected with 95%:probability with only a '5% probability of falsely concluding that a blank observation represents a"real" signal. (Reference 8)For a particular measurement system (which may include radiochemical separation):

LLD = 4.66-sb E V 2.22 Y exp(-XAt)Where: LLD = the "a priori" lower limit of detection (pCi per unit mass or volume)Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute)E = the counting efficiency (counts per disintegration)

V = the sample size (units of mass or volume)2.22 = the number of disintegrations per minute per picocurie El-104 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 43'of 195 Table 2.3-3 -DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 1;2-LOWER LIMITS OF DETECTION (LLD)3 (Page 2 of 2)Y = the fractional,radiochemical yield, when applicable I = the radioactive decay constant for the particular radionuclide (s-1)Dt = the elapsed time between midpoint of environmental sample collection and time of counting (s).Typical values of E, V, Y, and Dt should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representingthe capability of a measurement system and not an a posteriori (after the fact) limit for a particular' measurement.

Analysis will be performed in such a manner that the stated.LLDs will be-achieved under routine conditions.

Occasionally background fluctuations, unavoidable small'sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may renderthese LLDs unachievable.

In such cases, the contributing factors shallbe identified and described in the Annual Radiological Environmental Operating Report pursuant to ODCM AdministratiVe Control 5.2.4 If no drinkingwater pathway exists, a value of 3,000 pCi/L may be used.5 If no drinkingwater pathway exists, a value of 15 pCi/L may be used.6 Multiply the values in this column by 10-9 to convert to units of R.Ci/ml.7 Multiply the values in this column by 10-9 to convert to units of pICi/g(wet).

8 Multiply the values in this column by 10-12 to convert to units of !iCi/cc.El-105 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 44 of 195 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.2 LAND USE CENSUS CONTROLS 1.3.2 A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal; the nearest residence, andthe nearest garden* of greater than 50 m 2 (500 ft 2) producing fresh leafy vegetation.

  • Broad leaf vegetation:

sampling of at least three different kinds of vegetation may be,performed at the UNRESTRICTED AREA BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Controls for broad leaf vegetation sampling in Table 2.3-1 Part 4:c., shall be followed, including analysis .of control samples.APPLICABILITY:

At all times.ACTION: a. With a Land Use Survey identifying a location(s) that yields a calculated dose or dose commitment greaterthan the values currently being calculated in Control 2.2.2.3, pursuant toODCM Administrative Controls 5.1 and 5.2, identify the new location(s) in the next Annual Radioactive EffluentRelease Report.b. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance With the requirements of ODCM Control 1.3.1, add the new location(s) within 30'daysto the radiological environmental monitoring program given in ODCM Section 9.0, if samples are available.

The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deletedfrom this monitoring program after October 31 of the year in which this Land Use Census was conducted.

Pursuant:to ODCM Administrative Controls 5.2 and 5.3, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM reflecting the new location(s) with-the information supporting the change in sampling locations.

c. The provisions of SR 2.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 2.3.2 The Land Use Census shall be conducted during the growing season at least once per 12 months usingthat information that will provide the best results, such as by a door-to-door survey, mail survey, telephone survey, aerial survey, or by consulting local agricultural authorities.

The~results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant toODCM Administrative Control 5.1.El-106 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 45 of 195 112 CONTROLS AND.SURVEILLANCE REQUIREMENTS 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 112.3.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 1.3.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program which has been approved by the NRC, that correspond to samples required by Table 2.3-1.APPLICABILITY:

At all times.ACTION: With analyses not being.performed as required above, report the correctiveactions being taken to prevent a recurrence to the NRC in the Annual Radiological Environmental Operating Report pursuant to ODCM Administrative Control 5.1.The provisions of SR 2.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 2.3.3 The Interlaboratory Comparison Program shall be described in ODCM Section 9.0. A summary of the results obtained as a part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuantto ODCM Administrative Control 5.1.El-107 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 46 of 195 BASES, FOR SECTIONS 1.0 AND 2.0 'CONTROLS AND, SURVEILLANCE REQUIREMENTS NOTE The BASES contained in succeeding pages summarize the reasons for the Controls in Sections 1.0 and 2.0, but are not part of these Controls.E1-108 WBN OFFSITE DOSE CALCULATION MANUAL Revision.22 0 (ODCM) Page 47 of',195 BASES FOR SECTIONS 1.0 AND 2.0 -CONTROLS AND SURVEILLANCE REQUIREMENTS 1/2.1 INSTRUMENTATION 1/2.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Theradioactive liquid effluent instrumentation sis providedto monitor and'control, as applicable, the releases of radioactive materials in liquid effluents during actual and potential releases of 'liquid effluents.

The alarm/trip setpoints forfthese instruments shall be calculated andadjusted ini, accordance with the methodology and parameters in ODCM Section 6.2 to ensure that the alarm/trip will occur prior to exceeding

ten times the concentration limits of 10 CFR 20. The OPERABILITY and'use of this instrumentation is.consistent with the requirements of General Design Criteria 60,63, and'64 of Appendix A to 10 CFR'50.1/2.1.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous ;effluent instrumentation is provided to monitor and control, as- applicable,, the releases of radioactive materials in.gaseous effluents during actual and potential releases of gaseous effluents.

The radiation monitor alarm/trip setpoints for each release point are based on the radioactive noble gases in gaseous effluents.

It is not considered practical to apply the instantaneous alarm/trip setpoints to. integrating radiation monitors sensitive to radioiodines, 'radioactive materials' in particulate form, and radionuclides other than noble gases. The alarm/trip setpoints for these instruments shall be calculated and adjusted in~accordance with the methodology and parameters in ODCM Section'7.1 to ensure'that'the alarm/trip will occur prior to exceeding the. dose rate limits of ODCM Control 1.2.2.1.The OPERABILITYand use of this instrumentation isconsistent with the requirements of General:Design Criteria 60, 63,. and 64 of Appendix A to 10 CFR 50.1/2.1.3,METEOROLOGICAL INSTRUMENTATIONIDATA The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating.

potential radiation doses to the public as a result of routine or accidental, release of radioactive materials to the atmosphere.

This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and.is consistentwith the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972, ANSI/ANS-3.11-2000, "Standard for Determining Meteorological Information at- Nuclear Power Sites," 2000, Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants:to Assess Plant and Environs Conditions During and Following an Accident," May 1983, and. Supplement Ito NUREG-0737, "Requirements for Emergency Response Capability (Generic Letter 82-33)," December 1982.The interval for the sensor calibration portion of the CHANNEL CALIBRATION is based onlthe length of time asensor has been-in service (i.e., non-service or "shelf" time, not to exceed -six months, is not included).

NUREG-0452, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors," contained" meteorological monitoring instrumentation requirements.

As part.of the Technical Specification Improvement Program, these requirements have been. split out of the Standard Technical.

Specifications.

Therefore, the meteorological monitoring Control has been included in the ODCM.El-109 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 48 of 195 1/2.2 RADIOACTIVE EFFLUENTS 1/2.2.1 LIQUID EFFLUENTS 1/2.2.1.1 CONCENTRATION This Control is provided to ensure that the concentration of radioactive materials released inliquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the concentration values specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402.

It provides operational flexibility~for releasing liquid effluents in concentrations to follow the Section IL;A and Il.C design objectives of Appendix I to 10 CFR 50. This limitation provides reasonable assurance that the.levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures Within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC, and.(2)restrictions authorized by 10 CFR 20:.1 301(e). The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-1 35 is the controlling radioisotope and its concentration in air (submersion) was converted to an equivalent concentration in water. This specification does'not affect the requirement to comply with the annual limitations of 10 CFR 20.1301 (a).This Control applies to the release of radioactive materials in liquid effluents from all reactors.

at the site.The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed description of the LLD, and other detection limits can be found in HASLProcedures Manual, HASL-300, Currie, L. A., "Limits for QualitativeDetection and Quantitative, Determination

-Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, JI K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).1/2.2.1.2 DOSE This Control is provided to implement the requirements of Sections ll.A; Ill.A, and IV A of Appendix I, 10 CFR 50. The Control implementsthe guides set forth in Section ll.A of Appendixl.

Compliance with this Control will be considered to demonstrate compliance with the 0.1 rem limit Of 1OCFR20.1301(a)(1) per 56 FR 23374. The ACTION statements provide the required operating flexibility and at the-same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in liquid effluents to UNRESTRICTED AREAS will be kept "as low as reasonable achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not~result in radionuclide concentrations in the finished drinking water that are in excess of the requirements, of 40 CFR141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section I II.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such.that the actual exposure of a MEMBER OF THE&PUBLIC through appropriate

'pathways is unlikely to be substantially underestimated.

The equations specified

'in the ODCM section for calculating the doses due to the actual release rates of radioactive.materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.1 09 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50 Appendix I," Revision 1, October 1977 and Regulatory Guide 1:113, "Estimating.Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.This Control applies to the release of radioactive materials in liquid effluents from each unit at the'site.When shared Radwaste Treatment Systems are used by more than one unit on a site, .the wastes from:all units are mixed for shared treatment; by such mixing, the effluent releasescannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unitbased~on input conditions, e.g., flow to each of the radioactive producing units sharing the Radwaste Treatment System.El-110 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 49 of 195 For determining conformance to controls, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unitto obtain-the totalrelease per site.For those nuclides whose activities are determined from compositesamples(as noted in Table 2.2-1), the concentrations for the previous composite period will be assumed as the concentration for the next period to perform the calculations in ODCM Sections 6.1 and 6.3.1/2.2.1.3 LIQUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the LRTS ensures that this systemwill be available for use Whenever liquid effluents require treatment prior to release to the environment.

The Control that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept-"as low as reasonably achievable." This requirement implements the requirements of 1'0 CFR 50.36a, General Design Criteria 60 of Appendix A to 10 CER 50 and the design objective given in Section II.D of'Appendix I to 10 CFR 50. The specified'limits governing the use of appropriate portions of.the liquid radwaste system were specified as a suitable'fraction of the dose design objectives set forth inSection I L.A of Appendix 1, 10 CFR 50, for liquid' effluents.

This Control, applies to the release of'radioactive materials in liquid effluents from each unit~at the' site.When shared, LRTS are used'by more than one unit on a site, the wastes;from~all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately-be ascribed.toa specific unit.An estimate should be made of the contributions from each unit based-on input.cond'itions,ý e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent'releases be allocated' equally to each of the'radioactiveproducing units sharing the LRTS. For determining conformance:ýto.controls', these allocations from shared LRTS are to be added to the releases specifically attributed to each unit to obtain the total release per site.1/2.2.2 GASEOUS EFFLUENTS 1/2.2.2.1 DOSE RATE This Control provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA in excess of the design objectives-of Appendix I to 10 CFR 50. This Control is 'provided to ensure that gaseous effluents from all units on the site will be appropriately controlled.

It provides operational flexibility for releasing gaseous effluents to satisfy the.Section I.A and II.C design objectives'of Appendix Ito 10 CFR 50.. For MEMBERS OF THE PUBLIC who may at times be within the CONTROLLEDor RESTRICTED AREAS, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for the reduced atmospheric dispersion relative to that for the UNRESTRICTED AREA BOUNDARY.

Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond.the UNRESTRICTED AREA BOUNDARY to <500 mrem/y to the total body or to 3000 mrem/y to the skin. These limits also restrict, at all times, the corresponding thyroid dose rate above background'to a child via the inhalation pathway to 1500 mrem/y. This Control does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301 (a).This requirement applies to'the release of radioactive material in gaseous effluents from all -reactors at the site.The required detection capabilities for radioactive materials in gaseous waste samples aretabulated in terms of the lower limits of detection (LLDs). Detailed description of the LLD, and other detection

ýlimits canbe found in HASL Procedures Manual, HASL-300,'Currie, L. A., "Limitsfor Qualitative.

Detectionand Quantitative Determination

-Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968),; and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).For those nuclides whose activities are determined from composite samples (as noted in Table i.2-1), the concentrations for the previous composite period will be assumed as the concentration for the next period to perform the calculations'in ODCM Sections 7.2.El-111 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 50 of 195 1/2.2.2.2 DOSE -NOBLE GASES This Control is provided to implement the requirements of Sections II.B, III.A and IV.A.of Appendix I, 10 CFR 50. The requirement implements the guides set forth in Section 1.B of Appendix I. Compliance with this control will be considered to demonstrate compliance with the 0.1 remi limit of 10.CFR-20.1301(a)(1) per 56 FR 23374. The ACTIONs to be taken provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure thatthe releases of.radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable." The surveillance implements therequirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures:

based on models and data such that the actual exposure of aMEMBER OF THE PUBLIC through appropriate.pathways is unlikely to: be substantially underestimated.

The dose calculation methodology and. parameters.

established in ODCM Section.7.3 for calculating the doses due tothe .aCtual'release.rates.

of radioactive noble gases in gaseous effluents are consistent with the methodology, provided, in'Regulatory.Guide 1.109,".Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the:Purposes of Evaluating Compliance .with 1.0 CFR Part 50, Appendix I," Revision l, October 1977 and Regulatory Guide 1'11.1, "Methods for Estimating Atmospheric Transportand Dispersion.of.Gaseous-EfflUe'nts in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The equations provided for determining the air doses at and beyond the UNRESTRICTED AREA BOUNDARY are based uponthe historical average atmospheric conditions.

This Control applies to the release of gaseous effluents from each reactorat the site. Whenshared Radwaste Treatment Systems are used by more than one unit on a site, the wastesfrom all Units are mixed for sharedý treatment; by, such mixing, the effluent releases cannot accurately berascribed to~a specificunit.

An estimate should be made of the contributions from~each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent-releasesbe allocated equally to each ofthe radioactive producing units sharing the Radwaste'Treatment System. For determining conformance to requirements, these allocations from shared Radwaste Treatment Systems are to be added to the releases specifically attributed to each unit to obtain the total release per site.1/2.2.2.3 DOSE -IODINE-131, IODINE-133, TRITIUM, ANDRADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN EIGHT DAYS This -Control is provided to-implement the requirements of Sections II.C,. IILA and :IV.A of Appendix I, 10 CFR 50. The Control'implements the guides set forth in Section IL.C.ofAppendix I. Compliance with this control will be considered to demonstrate compliance with the.& Orem lin'it.of:lo CFR 20.1301 (a)(1)per 56 FR23374. The ACTION to be taken provides the requiredoperatingrflexibility and at.the same time implements the guides set forth in Section IV.A of Appendix Ito assure that'the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." ODCM Section .7.4 calculational methods specified in the Surveillance Requirement implement the: requirements in Section III.A of Appendix I that.conformance with the guides of Appendix I be shownby calculational procedures based on models and: data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately modeled pathways is unlikely to be substantially underestimated.

ODCM Section 7A calculational methodology and parameters for calculating the doses due to~the actual release rates of.the subject materials are consistent with the methodologies provided in NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food&Chain Transport and InternalDose of Radionuclides,".October 1979 and Regulatory Guide 1.109, "Calculation,of Annual Doses to Man from Routine Releases of Reactor Effluentsfor the Purposes ofEvaluating Compliance with -10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111* "Methods for:EEstimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from:Light-Water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon. the historical average atmospheric conditions.

The release rate controls for 1-131, 1-1.33, tritium and particulate radionuclideswith half-lives greater than eight days are dependent;upon the existing radionuclide pathways to, man in the areas at and beyond the UNRESTRICTED AREA BOUNDARY.The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne radionuclides, (2),deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animalsand beef: producing.^animals graze with consumption of the milk and beef by man, and (4) deposition'on the ground, with subsequent exposure of man.E1-112 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page. 51 of 195 For those nuclides whose activities are determined from composite samples, the concentrations for the.previous composite period will be assumed as the concentrationfor the next period to perform~the, calculations in ODCM Section 7.4.112.2.2:4 GASEOUS RADWASTE TREATMENT SYSTEM The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for.use whenever, gaseous effluents require treatment prior to release to the environment.

The Control thatthe appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will'be kept "as low as is reasonably achievable." Thisrequirement implements the requirements of 10 CFR 50.36a, General Design Criteria.60 of Appendix A-to 10 CFR 50, and thedesign objectives given in Section IL.D of Appendix I to 10 CFR 50. The :specified limits governing the use of appropriate portionsof the systems were specified as'a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix 1, 10 CFR 50, for gaseous effluents.

This Controlapplies tothe release of radioactive materials in gaseous effluents from each'unit~at the site.When shared Radwaste Treatment Systems are used by more than one unit on asite,-the wastes from all units are mixedfor shared treatment; by such mixing, the effluent releases cannot.accurately be.ascribed to a specific unit. An estimate should be made of the contributions from each unit[basedion.

input conditions, e.g., flowrates and radioactivity concentrations, or, if notpracticable, the~treated effluent releases be allocated-equally to each of the radioactive producing units sharing the;Radwaste Treatment System. For determining conformance to Controls, these allocations from sharedRadwasteTreatment Systems are to be added to the releases specifically attributed to each unit to obtainwthe total release per site.1/2.2.3 TOTAL DOSE This Control is provided to meet the dose limitations of 40 CFR 190 .that have been incorporated into 10 CFR 20.1301(d).

The Control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrem to-the total body or any other organ, except the thyroid, which shall be limited to, less than or. equal:to 75 mrem. For sites containing up to 4 reactors, it is. highlyunlikely.that the~resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 1950if.the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of annual dose to a MEMBER OF THE.PUBLIC to within the40 CFR.190 limits. For the purposes of the Special Report, it may be assumed thatfthe dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible,with'the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius Of..8 km must be considered.

If the dose to any MEMBER OF THE PUBLICisestimatedto exceed therequirements of 40 CFR.Part 190, the Special Report.with a request for a variance (provided the release.conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with.the provisions of 40.CFR 190.11 and 1.0 CFR 20.2203(a)(4), is considered to be a timely request and fulfills1the requirements of 40 CFR 190 until NRC staff action is completed.

The.variance only, relates to the:limits of 40 CFR 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR 20, as addressed-in ODCM Controls 1.2.1.1 and 1.2.2.1. An individual is not considered THE PUBLIC during any period in which he/she is engaged in carrying out any operation that-is part of the nuclear fuel cycle. Demonstration of compliance with the limits of 40 CFR 190 or with the design objectives of Appendix I.to 10 CFR 50 will be considered to demonstrate compliance with.the 0.1 rem limit of 10 CFR 20.1301.The requirements for evaluating compliance with 40 CFR 302 are added to ensure compliance with these limits. The regulation states that federally permitted releases do not have to determine compliance with the reportable quantities unless the permitted release allowance is exceeded.E1-113 WBN OFFSITE DOSE CALCULATION MANUAL Revision.,22 0 (ODCM) Page 52 of 195 1/2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1/2.3.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this.Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the plant operation.

This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR 50 and thereby supplements the Radiological Effluent Monitoring;Program by verifying that the measurable concentration of-radioactive materials and levels of radiation arenot higher-than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.Guidance for this'monitoring program is provided by the Radiological Assessment BranchTechnical Position on Environmental Monitoring, Revision 1, November 1979. The initiallyspecifiedl monitoring program will be effective for at least the first three years of commercial operation.

Following this period, program' changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in, terms of the lower limits of detection (LLDS). The LLDs required'by Table'2.3-3 are consideredoptimum for routine'environmental measurements in industrial laboratories.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system.and not as a posteriori (after the fact) limit for a particular measurement.

Detailed description of the LLD,.and other detection limits can be found in HASL Procedures:Manual, HASL-300, Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination -Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J: K.,",Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).112.3.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of areas at and beyond the UNRESTRICTED AREA BOUNDARY are identified and that modificationsto the monitoring program are made, if required by the results of that census. The best information from the door-to-door survey, mailsurvey, telephone survey, aerial survey, or by consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10-CFR 50. Restricting Ithe census-to gardens of greater than 50 m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to provide the quantity (26 kg/y) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption:by a child.To determine this minimum garden size, the following assumptions were. used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m 2.E1-114 WBN OFFSITE DOSE CALCULATION MANUAL RevisiOn 22 0 (ODCM) Page 53 of 195 1/2.3.3 INTERLABORATORY COMPARISON The Control for participation in an approved Interlaboratory Comparison Program is provided to ensure.that independent checks on the. precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix Ito 10 .CFR 50.E1-115 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22.

0 (ODCM) Page 54 of '195 3.0 DEFINITIONS The defined terms in this section appear in capitalized type in the text and are applicable throughout these Controls and Bases.3.1 ACTION ACTION shall be that part of a Control that prescribes remedial measures required under designated conditions.

3.2 CHANNEL

CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the necessary range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm, interlock, display, and/or trip functions.

Calibration of instrument channels with resistance temperature detector or thermocouple sensors shall consist of an in place cross calibration of the remaining adjustable devices in the channel. Whenever a sensing element is replaced, the, next'required in.place cross calibration consists of comparing the other sensing elementswith the recently rinstalled sensing element. The CHANNEL CALIBRATION may be performed by anyseries of sequential, overlapping channel calibrations or total channel steps such that the entire channel is calibrated.

3.3 CHANNEL

CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channelbehavior during operation.

Thisdetermination shall include, where possible, comparison of the channel.indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

3.4 CHANNEL

OPERATIONAL TEST A CHANNEL OPERATIONAL TEST shall be the injection of a.simulated signal or actual signal into the channel asclose to the sensor as practicable to verify OPERABILITY of alarm, interlock, and/or trip functions.

The CHANNEL OPERATIONAL TEST shall include adjustments, as, necessary, of the required alarm, interlock, and/or trip setpoints such that the setpoints are within the required range and accuracy.3.5 CONTROLLED AREA A CONTROLLED AREA, as defined in 10 CFR 20, is the area outside the RESTRICTED AREA but inside the 10 CFR 20defined UNRESTRICTED AREA BOUNDARY, access towhich can'be' limited by the licenseefor any reason (see Figure 3.1).3.6 DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 alone would~produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132,1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.E1-116 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 55 of 195 3.0 DEFINITIONS

3.7 FREQUENCY

NOTATION The FREQUENCY NOTATION specified for the performance of SurveillanceRequirements shall correspond to the intervals defined in Table 3.1.3.8 MEMBER(S)

OF THE PUBLIC MEMBER(S)

OF THE PUBLIC, as defined in 10 CFR 20, is any individual except when that individual is receiving an occupational dose.3.9 MODE A MODE shall- correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 3.2 with fuel in the reactor vessel -and reactor vessel head.closure bolt tensioning.

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

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

3.12 RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3459 MWt.3.13 REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR 50.3.14 RESTRICTED AREA The RESTRICTED AREA, as defined in 10 CFR 20, is that area, access to which is limitedby the licensee for the purposes of protecting individuals against undue risks from exposure to radiation and radioactive materials.

RESTRICTED AREA does not include areas.usedas residential quarters, but separate rooms in a residential building may be set apart as a RESTRICTED AREA (see Figure 3.1).El-117 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 56 of 195 3.0 DEFINITIONS 3.15'SITE BOUNDARY The site, boundary is defined in 10 CFR 20 as that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee (see Figure 3.1).3.16 SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to.a radioactive source orother channel sensor internal test circuits.3.17 UNRESTRICTED AREAIUNRESTRICTED AREA BOUNDARY An UNRESTRICTED:

AREA, as defined in 10 CFR 20, shall be anyarea, access to which is.not controlled by the licensee for the purposes of protection ofindividualsfromexposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes 3.18 VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed rand installed%,to reduce gaseous radioiodine or radioactive material in particulate form in effluents.by.

passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose-of removing iodines or.particulates from the gaseous exhaust stream: prior to the release to the environment (such a system.is not considered to have any effect on noble gas effluents).

'Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered-to be VENTILATION EXHAUST TREATMENT SYSTEM. components.

3.19 VENTING VENTING is the controlled process of discharging air or gas from-a confinement'to maintain temperature, pressure, humidity, concentration, or other operating -condition, in such a manner-that replacement air or gas is.not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.3.20 WASTE GAS HOLDUP SYSTEM A WASTE GAS HOLDUP SYSTEM is any system designed and-installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from'the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to-release to the environment.

E1-118 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 57 of 195 Table 3.1 -FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.W At least once per 7,days.M At least once per 31 days.Q At least once per92 days.SA At least once per 184 days.3Q At least once per 276 days.Y At least once per 365 days.R At least once per 18 months.N/A Not applicable.

P Completed prior to each release.E1-119 WBN OFFSITE DOSE CALCULATION MANUAL RevisiOn 22 0 (ODCM) Page 58 of 195 Table 3.2 -OPERATIONAL MODES REACTIVITY CONDITION, % RATED THERMAL AVERAGE: COOLANT, MODE Keff POWER* TEMPERATURE-1

1. Power Operation 0.99 > 5% N/A 2. Startup _>0.99 < 5% N/A 3. Hot Standby <0.99 N/A > 350°F 4. Hot Shutdown**

<0.99 N/A 350 0 FF> Tý,ý > 200 0 F 5. Cold Shutdown**

< 0.99 N/A _<200 0 F 6. Refueling***

N/A N/A N/A* Excludingdecay heat.** All reactor vessel head closure bolts fully tensioned.

      • One or more reactor vessel head closure bolts less than fully tensioned.

E1-120 I WBN 01 0 FFSITE DOSE CALCULATIONWMANUAL (ODCM)Revision 22 Page 59 of 195 Figure 3.1 -WBN SITE AREA MAP UNRESTRICTED AREA A BOUNDARYA E1-121 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 60 of 195 4.0 -(NOT USED)5.0 ADMINISTRATIVE" CONTROLS 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT As required by WBN TS 5.9.2, Routine Annual RadiologicalEnvironmental Operating-Reports.covering the operation of the unit during theprevious calendar year shall be submhitted, pridr to May 15 of each year.The annual radiological environmental operating reports shall include summaries,.

interpretations,, and an analysis of trends:of the.results .of.the radiological environmental surveillance activities for the report period, including a comparison with. preoperational studies, with operational'controls,:

andwith previous environmental surveillancereports andan assessment of the observed impactsoftheiplant operation on the environment.

The reports shall also~include the results of land use censuses required by ODCM Control 1.3.2.The annual radiological environmental~operating reports shall include summarized and tabulated results of these analyses and measurements in the format of the table in.the RadiologicalAssessment.Branch Technical Position, Revision 1, November.1979.

In the event that some results are not available for inclusion with the report, the report shall be submitted.

noting and explaining, the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.The reports shall also include the following:

a summary description of the radiological environmental monitoring program;.at least two legible maps (one map shall cover stations near.the:UNRESTRICTED AREA BOUNDARY, a second shall include the more distant stations):covering..all:

samplingldobations keyed to a table giving distances and directions from the centerline of one reactor; and the results of licensee participation in the Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not-being performed as required by ODCM Control 1.3.1; discussion of all deviations from the sampling schedule of Table 2.3-1;, reasons for not conducting the radiological environmental monitoring program as required by ODCM Control 1.3.1 and discussions of environmental sample measurements that exceed the reporting levels of Table 2.3-2 but are not the result0of plant effluents, pursuant to action b. of ODCM Control 1.3.1; and discussion ofiall analyses:in which the LLD required by Table 2.3-3 was not achievable.

5.2 ANNUAL

RADIOACTIVE EFFLUENT RELEASE REPORT As required by WBN TS 5.9.3, a Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year. The period ,f the first report shall begin with the date-of initial criticality.

The Annual Radioactive Effluent Release Report shall include a summary of the quantities-of radioactive liquid and gaseous effluents and solid waste released from the-units as outlined in. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releasesof Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled:Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof, as applicable.

Additional requirements for reporting solid waste are specified in theProcess Control Program.The radioactive effluent release reports-shall include a list and description of unplanned releases from:the site to UNRESTRICTED AREAS of radioactive materials in gaseousand liquid effluents made'during the reporting period.E1-122 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page 61 of 195 The radioactive effluent release reports shall include any changes made during the reporting period to the Process Control Program,, and to the ODCM pursuant to ODCM Administrative Control 5.3, as well.as any major changes to Liquid, Gaseous, or Solid Radwaste Treatment.Systems, pursuant to WBN Technical Specifications.

It shall also include a listing of new locationfor dose calculations and/or environmental monitoring identified by the Land Use Census pursuantto ODCMControl1.3.2.

The radioactive effluent release reports shall also include the following:

an explanation as towhy the inoperability of liquidor gaseous effluentmonitoring.instrumentation was not-correctedwithin the time specifiedin ODCM Controls 1.1.1 or 1.1.2, respectively.

The. radioactive effluent release report shall include an annual summary of hourly'meteorological data collected over the previous year. This annual summary may be either.inhthe formof anhbur-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation:(if measured), or in the form of joint frequency distributions of windspeed, wind directin, n:and :atmospheric stability.

In lieu of submission with the radioactive effluent release report, this summary of,'required, meteorologicaldata maybe retained on site in afilethat shallbe provided :toNRCupon..request.

'This same report shall:include an assessment of the radiation doses due to radioactiVieliquid and-gaseous effluents released-from the unit~orstation during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to"MEMBERS OF THE PUBLIC. due to theiractivities inside the UNRESTRICTEDrAREAkBOUNDARY during the report period. All assumptions used. in making these assessments (i.e., specific activity,,exposure'tirne,.

and lo.cation),shall be included'in.these reports. The meteorological conditions concurrent with'the~time of release of radioactive materials in gaseous effluents, as determined by sampling.frequency and: measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with Sections 6.6 and 7.7. [SOURCE NOTE8]The radioactive effluent release report shall also include an assessment of radiation-doses to the. likely most exposed MEMBER-OF THE PUBLIC from reactor releases and~other nearby uraniumfuel cycle sources,.including doses from primary effluents and direct radiation; for the previous calendar year to show conformance with 40 CFR 190, in accordance with ODCM Section 8.1.The radioactive effluent release report shall include results from any groundwater samples~obtained during the reporting period that are not described in the ODCM.The radioactive effluent release report shall include any onsite radioactive spills or leaks, and their assigned doses that occurred during the reporting period.El-123 WBN OFFSITE, DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 620of:195 5.3 OFFSITE DOSE CALCULATION MANUAL CHANGES As required by WBN TS 5.7.2.3, changes to the ODCM: 1. Shall be documented and records of reviews performed shall be retained.

This documentation shall contain: a. Sufficient information to support the change together with the appropriate analyses or evaluations justifyingrthe change(s) and b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a,,and Appendix Ito 10 CFR,50 and notadversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

2. Shall become effective.after review and acceptance by the PORC and the approval ofthe Plant Manager.3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCMas~a part of or concurrent with the Annual Radioactive Effluent Release Report forithe periodoffthe report in which any change:to the ODCM was made. Each change shall be identified by markings:in the margin of the affected pages, clearly indicating the area of the page that was'changed;-

and shall indicate the date (i.e., month/year) the change was implemented.

Changes to the ODCM shall be performed in accordance with the requirements of Appendix C.5.4 SPECIAL REPORTS Special Reports shall be submitted in accordance with 10 CFR Part 50.44[SOURCE NOTE 16]5.5 40 CFR 302 REPORTING Any releases of radioactivity exceeding both the 40 CFR 190 dose limits and40 CFR 302.4 reportable quantities, shall be reported'immediatelyto the National Response Center in accordance with the requirements given in 40 CFR'302.6.

El-124 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 63 of 195 5.6 CHANGES TO RADWASTE TREATMENT SYSTEM Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous) shall be reported to the Commission in the Annual Radioactive Effluent ReleaselReportfor the period in which the evaluation was reviewed by the Plant Operations Review Committee (PORC). The discussion of-each change shall contain: 1. A summary of the evaluation that led to the determination that the change could be mader in accordance with 10 CFR 50.59;2. Sufficient detailed .information to totally support the reason for the change without benefit of additional or supplemental information;

3. A detailed description of the equipment, components, and processes involvedand~the interfaces with other plant systems;4. An evaluation of the-change, which shows the predicted releases.of.

radioactive materials,in liquid and .gaseous effluents that differ from those previously evaluated in the FinaiSafety Analysis Report;5. An evaluation of the change, which shows that the expected maximum.exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general:population that differ from those previously estimated.

in the Final Safety Analysis Report;6. A comparison ofthe predicted releases of radioactive materials, in.liquid and gaseous effluents, to the actual releases for the period prior to when the changes areto'be made;7. An estimate of the exposure to plant operating personnel as a result of the change;8. Documentation of the fact that the change was reviewed and found acceptable by the PORC.El-125 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 641of 195 6.0 -;LIQUID EFFLUENTS INTRODUCTION Radioactive liquideffluents from WBN enter the UNRESTRICTED AREA through'the diffusers into the Tennessee<River.

There arefourplant systems from which'radioactive effluentsare released.

These are the Liquid Radwaste Treatment'System (LRTS), the Condensate Derriineralizer Systemý,the:Turbine Building Sump (TBS); and'the Units 1 and 2 Steam Generator BlowdownJ(SGBD).

Figure 6.1 provides an outline of these liquid release paths with associated radiation monitors.The LRTS, the Condensate Demineralizer System and the SGBDs flow into the .Cooling:Tower'Blowdown (CTBD) for dilution.

Each of these release paths is also monitored by a radiation monitor. These monitors perform two mainfunctions:

to identify any unexpectedradioactivity releases, and to ensure. that the concentration.limits of ODCM Control 1.2.1.1 are not exceeded.

Each monitor haýsan alarm/trip:setpoint which will alarm if the monitor's setpoint is exceeded.

Alarm and trip functions are not provided Iby separate devices, therefore the alarm/trip setpoint is a single calcuiated value. The monitors onthe Radwaste, Condensate Demineralizer,.-and SGBDsystemswill alarm and isolate: any release which exceeds thealarm/trip:setpoint.

The TBS radiation monitor will alarm if the setpoint is exceeded, but this monitor does not have an ,isolation function.Releasesare made as either a batch or continuous release. Releases from Radwaste Tanks, (see Figure 6.2) and the Condensate Demineralizer tanks (see Figure 6.3),are made. as batch, releases.

The TBS and SGBD are continuous releases when flow exists.For batch releases, any~tank to be released is sampled for radioactivity, as.described in ODCM Section 6..1,1. .The tank contents are analyzed to determine the maximumallowable:release flow rates to ensure compliance with the,'concentration limits of ODCM Control 1.2,1.1 as described'in ODOM Section 6.1.2. The sampling results'are also used to determine a setpoint for the associated radiation monitor for the release in accordance with ODCM Section 6.2.3.For continuous releases, the pathways are sampled for radioactivity periodically,.as described in ODCM Section 6.1.1. The samples are analyzed to ensure compliance with the concentration limitsof 0f.DCM Control 1.2.1.1,,.as described in ODCM Section 6.1.2. The sampling resultsare also0used to determine a setpoint for the associated*

radiation monitor for the release in accordance with oDCM Section 6. 2.3.Dose, calculations are performed for each sampling period, or release, as-applicable,, to determine compliance with ODCMControl 1.2.1.2 as detailed in ODCM Sections 6.3 and 6.4. Ornce permonth, the projected

  • dose is calculated, as outlined in. Section 6.5, to determine compliance:

With 0OCM Control 1.2:1.3..

The calculational methodologies are based on the guidance provided in NUREG 0133 and Regulatory'Guide

1. 109.The quantities of each radionuclide identified and released are input into a more rigorous calculation methodology,, described in :ODCM Section 6.6, to determine the individual .and'population doses to be reportedto.the NRC in theAnnual Radioactive Effluent Release Report. These dose methodologies are based on.the guidance provided in Regulatory Guide 1.109.El-126 WBN OFFSITE DOSE CALCULATIONMANUAL Revision.22 0 (ODCM) Page 65 of 195 RELEASE POINTS Liquid Radwaste Treatment System The LRTSprocesses liquid from the Reactor Building and Auxiliary Building.Floor Drains, the"CVCS Holdup Tanksthe Laundry/Hot-Showeri the Waste Condensate Tanks and Chemical :Drain Tanks.Figure 6.2 provides a schematic of the Liquid Radwaste System, showing the:flow pathways and flow rates. The LRTS has indivillual~release points for each of the tanks. The routine release points for liquid radwaste are the Monitor-Tank and the Cask Decontamination CollectorTank (CDCT). The:Monitor Tank has a.capacity of 20,000gal and can be released at a maximum design flowl rate sof1150 gpm.-'The CDCT has a capacity of 15;000 gal and can be released at a maximum design flow rate.of 100 gpm. The Monitor Tank and CDCT discharge to the Cooling Tower Blowdown line asa batch release-and are monitored by radiation monitor 0-RE-90-122.

There is a flow interlock-on the CTBD'which suspends the release if the flow is less than,20,000 gpm.Condensate Demineralizer System The Condensate Demineralizer System liquid wastes are released-from the High Crud-Tanks (HCT-A and -B), the Neutralization:Tank,-

and the Non-Reclaimable Waste Tank (NRWT)." Figure-6.3 provides a schematic of.the Condensate'Demineralizer System, showing'the flow pathways and-flow rates. The HCTs have a capacity of 20,000 gal and.a maximum design *discharge flow rate ofl 50 gpm. The Neutralization Tank has a capacity of 20,000 gal and a maximum design discharge flow rate of 100 gpm.The NRWT-has a capacity of 1-1,000 gal and a maximum'design discharge flow rate of.30 gpm: .Each of these tanks. is defined as a release point for the system. When tank contents are-,required to be permitted for radioactivity, the Condensate Demineralizer System waste is releasedto..the-CTBD line and is monitored by radiation monitor 0-RE-90-225.

There is a flow interlock on the CTBD which suspends the release* if the flow-is less than 20,000 gpm. The low flow interlock may be bypassed,'and releases made from the Condensate Demineralizer System with less than 20,000 gpm CTBD flow provided the sum of the ratios of the ECLs for all release points is < 10.Turbine Building Sump The TBS normally releases to the Low Volume Waste Treatment Pond, but can.be released to either the Metal Waste Cleaning Ponds or the 35 acre Yard Holding Pond. The.TBS'has.a.

capacity of 57,783 gal and a design discharge release rate of 2,000 gpm per pump. The TBS is monitored by-radiation monitor 0-RE-90-212.

Steam Generator Blowdown The SGBD is processed in theSteam Generator Blowdown Flash Tanks or SGBD Heat Exchangers.

Figure 6.3 provides-a schematic of the SGBD System, showing the-flow-pathways andflow rates. The SGBD discharge-has a maximum~design flow rate of 65.5 gpm per steam generatbr when-discharging to the Cooling Tower Blowdownm SGBD is recycled or is released to the CTBD line andmonitored by.radiation monitors 1,2-RE&90-120A and 1,2ýRE-90-121.

There is a flow interlock on the CTBD which suspends the release if the-flow-is less than 20,000 gpm. The low flow interlock may-be bypassed and releasesrmade from the Steam Generator Blowdown System with less~than 20,00b gpm CTBD ,flow provided the sum of the ratios of the ECLs for all release points is < 10.Groundwater Sump The Groundwater Sump (GWS) normally releases to the 35 acre Yard-Holding Pond via the stormdrains.

The GWS has a design discharge release rate of 300 gpm per pump. The GWS is:not monitored by a radiation monitor.El-127 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page! 66 of 195 6.1 LIQUID RELEASES 6.1.1 Pre-Release Analysis Radwaste and Condensate Demineralizer tanks will be mixed fora period of time (specified in plant procedures) prior to sampling to ensure that a representative sample is obtained.

Recirculation times to ensure adequate mixing will be established by testing. Periodically, checks will be made; to.ensure a representative mixing of tank contents.

Prior to any batch release, a grab samplewill be takenand analyzed in accordance with Table 2.2-1.Releases from the steam generator blowdown and turbine building sump are considered continuous.

For continuous releases, daily grab or composite samples will be taken on days when releasesare being made and analyzed in accordance with Table 2.2-1.Composite samples are maintained during periods of radioactive discharge fromall pathways (as required by Table 2.2-1) to determine the concentration of certain nuclides (H-3, Fe-55, Sr-89, Sr-90, and gross alpha). For those nuclides whose activities are determined from composite samples, the.concentrations for the previous.

composite, period can be assumed as the concentration for the.next period to perform the calculations in Sections 6.3 and 6.5. The actualmeasured concentrations will be used for the dose calculations described in Section 6.6.A maximum allowable waste flow rate, which will ensure compliance with ODCM Control 1.2.1.1, will be determined using Equations 6.1 and 6.2. Setpoints for the release are determined as described in Section 6.2. Dose;calculations are performed in accordance with Section 6.3 6.1.2 Effluent Concentration Limits (ECL)-Sum of the Ratios To determine release parameters toensure compliance with ODCM Control: 1.2.1..,a sum of the .ratios calculation is performed.

The sum of the ratios (R) for each release point~will be calculated by the following relationship.

R=X Cj (6.1)i ECL 1 where: R = the sum of the ratios for the release point.ECLi = the ECL of radionuclide i, pCi/ml, from 10 CFR 20, Appendix B, Table 2,Column 2.Ci = concentration of radionuclide i, gCi/ml.The sum of the ECL ratios must.be < 10 following dilution due to the releases from anyor all of,the release points described above. The ECL ratios for releases from the Turbine Building Sump will be < 10 at the sump.El-128 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page:67 of1195 The following relationship is used to ensure that this criterion is met: RTBS + f 1 R 1 + f 2 R 2 + f 3 R 3 + f 4 R 4 < 0.0 F (6.2)where: RTBS = sum of the ECL ratios of the turbine building sump as determined by equation 6.1.fl,2,3, 4 = effluent flow rate for radwaste, condensate demineralizer system andthe steam-generator blowdowns, respectively, gpm.R1,2,3 = sum of ECL ratios for radwaste, condensate demineralizer system and the steam generator blowdowns, respectively, as determined by equation 6.1.F = dilution flow rateforCTBD.

The minimum assumed flow of 20,000 gpmwiltbe usedfor radwaste pre-release calculations.

6.1.3 Post-Release Analysis A post-release evaluation will be done using actual release data to ensure that the limits specified in ODCM Control 1.2.1.1 were not exceeded.A composite list of concentrations (Ci), by nuclide, will be used with the actual waste flow (f) and dilution (F)flow rates (or volumes) during the release. The data will be evaluated to demonstrate compliance with-the limits in ODCM Control 1.2.1.1. [SOURCE NOTE 10]6.2 INSTRUMENT SETPOINTS Liquid effluent monitor setpoints are determined to ensure that the concentration of.radioactiVe material released at any time from the site to UNRESTRICTED AREAS does not exceed ten times the ECL limits referenced in ODCM Control 1.2.1.1 and to identify any unplanned releases.The liquid effluent radiation monitors.

and their setpoint information are outlined below: Pathway Monitor Default Setpoint Setpoint ODCM I I I Limit Section ERCW 0-RE-90-133 Section 6.2.1 N/A 6.2.1 0-RE-90-134 0-RE-90-140

_0-RE-90-141 Radwaste 0-RE-90-1 22 Section 6.2.2 Smny 6.2.2 Condensate 0-RE-90-225 Section 6.2.2 Smax 6.2.2 Demineralizer TBS 0-RE-90-212 Section 6.2.2 Smnx 6.2.2 SGBD 1-RE-90-120A Section 6.2.2 Smax 6.2.2 2-RE-90-120A 1 -RE-90-121 2-RE-90-121 El-129 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 68;of 195 6.2.1 Process Discharge Point Monitor Setpoints (0-RE-90-133,-134,-140,-141)

The setpoints for the ERCW monitors (RE-90-133,-134,-140,-141) must ensure that the concentration of radioactive materials released at any time from the site do not exceed the limits given in ODCM Control 1.2.1.1. Since thiseffluent stream will not routinely contain, radioactivity, the setpointsfor-these monitors will be set at two times background to ensure thatany radioactivity is identified.

Site procedures will document and control this value.6.2.2 Release Point Monitor Setpoints (0-RE-90-122; O-RE,90-225; 0-RE-90-212; 1,2-RE&90-120A,-121)

The radiation monitor for batch release points, the Liquid Radwaste System and the Condensate Demineralizer System, monitors the undiluted waste streamas it comes out of a tank. The purpose of the monitor setpoints for these batch releases is to identify any, gamma-emitting release thats' ls arger than expected and would have the potential to exceed the limits after dilution.

Setpoints are calculated as described by equations 6.3, 6.4, and 6.5 and may be set at a default value. Site procedures will document and control this value.The continuous release points, the Steam Generator Blowdowns, and.the Turbine Building Sump, will notýbe releasing gamma-emitting radioactivity unless there is or has beena primary to secondary leak. If this is the case, the continuous release points are monitored to identify~any gamma-emitting reiease that is larger than expected and would have the potential to exceed the ODCM Control 1.21.1. concentration limits after dilution.

The monitor setpoints are calculated using Equations 6.3, 6.4, and 6.5 whenthis is the case. When these release points are being treated in this manner, a single release is defined'as all effluent released through this point on a continuous bases for a period of time (usually one week): During periods when there is no identified primary to secondary leak, these monitors are'set to _ 2 times background.

Site procedures will document and control these setpoint-values.

For each release from a release point, two setpoints are calculated:

one based on the monitor response to the contents of the effluent stream (as described below in Equation 6.4); and another based-onthe predicted response of the monitor to the activity in the release stream ifit were large enough to exceed ten times the 10 CFR 20 limits after dilution (as described below in Equation 6.5). .A comparison is made between these two calculated setpoints and the lower of the two is used'for the release. If default setpoints are used then a comparison is made between the two calculated setpoints and the default setpoint as described below to choose the appropriate setpoint for the monitor during the release (after the release, the monitor is normally returned to the defaultsetpoint).

1. If SER < Sdefault < Smax Reported = Sdefault 2. If SER < Smax < Sdefault Reported = SER 3. If SER > Smax Reported = Smax 6.2.2,1 Expected Response An expected response (ER) is calculated for the monitor for each release: ER = BKG + Y,(Ei Ci) (6.3)where: BKG = monitor background, cpm. The monitor's background is controlled .at an appropriate limit to ensure adequate sensitivity in accordance with site procedures.

Ei = monitor efficiency for nuclide i, cpm per IaCi/ml. This term may also be referred to as a response or calibration factor.Ci, = tank concentration of nuclide i, pCi/ml.El-130 WBN OFFSITEDOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 69 of 195 6.2.2.2 Expected Response Setpoint An expected response setpoint SER is calculated for the monitor for each release: SER =X EiCI+ X BKG (6.4)where: X = administrative factors designed to account for expected variations in. monitor response and background (as defined in plant procedures).

The ranges of values are: 0< X _ 2.0.6.2.2.3 Calculated Maximum Monitor Setpoint A second setpoint is calculated for the release based on the predicted response of the monitor to the gamma-emitting activity in the release stream if it were large enough to exceed ODCM Control .1.2.1.1 limitsafter dilution.

This setpoint ensures-that the release willbe stopped if it exceeds-thisjlimit.

The maximum calculated setpoint calculation must satisfy the following relationship -from NUREG-0133:

sf (F +f) -where: C = the effluent concentration limit from 10 CFR 20 Appendix B, Table 2, Column 2, in gCi/ml, represented by a value of 1.s = the setpoint, in pCi/ml, of the monitor measuring the radioactivity concentration inlthe effluent line prior to dilution and subsequent release. The setpoint, which is proportional to the -volumetric flow of the effluent line and inversely proportional to the volumetric flow ofthedilution stream, represents-a value which, if exceeded, would result in release concentrations exceeding the limits of ODCM Control 1.2.1.1 when the-effluent enters the Tennessee River.f = the flow rate of the waste stream, gpm.F = the dilution flow rate, gpm.To determine the setpoint in cpm, If no dilution is available, then s < C.Since C in the above equation represents the concentration equal to the limit, the setpoint s can be replaced by: s = c. Dreq where c. = the actual effluent concentration, pCi/ml.Oreq = the required dilution factor.E1-131 WBN OFFSITE DOSE CALCULATION MANUAL Revision, 22 0 (ODCM) Page 70 of 195 The required dilution can be defined as: R Dreq " 10 SF where: R = the sum of the ratios for gamma-emitting radionuclides, as~determined by equation 6.1.10 = a value which implements the concentration limits of ODCMControl 1.2.1.1.SF = a safety factor. The range of values for SF is: 0 < SF < 1.Substituting ca Dreq into the above equation.for s, substituting 1 for C, and solving for ca: 10 SF (F+f)f R This value represents the amount that theexpected.

response setpoint would be adjusted upward to account for the downstream dilution.

For WBN, a portion of thetotal-dilution flow-is- allocated-to each release point using an-allocation factor (AF). To determine the maximum calculated monitor;setpoint, Smax, in cpm for a release point, the following equation is used: Smax { OSF(f + (AF x F)) }(ER- BKG) + BKG (6.5)where: AF = fraction of dilution flow allocated to this release point. For the TBS, AF= 0. The-fractions:

for, the remaining 4 release points are normally defined as the ratio of the allocated CTBD flow .for that release point to the total CTBD flow. The CTBD flow allocation fractions for these release points are routinely:

Radwaste 0.6 Condensate demineralizer

0.2 Steam

Generator Blowdown (U1) 0.1 Steam Generator Blowdown (U2) 0.1 These allocation factors may beadjusted for a~particular release if it is known that.there are no releases being made through other release points into the CTBD. For example, if there are no releases being made through the-Condensate Demineralizer or either SGBD, the AF for the Radwaste-System may be set equal to one.ER = expected monitor response, cpm, as calculated in Equation.

6.3.BKG = background, cpm.El-132 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 71 of 195 6.3 CUMULATIVE LIQUIDEFFLUENT DOSE CALCULATIONS Doses due to liquid effluents are calculated for each release for thefollowing;age.

groups: adult.(17 years and older),.teen(11-17 years), child (1-11 years), infant (0-1 years) (Reference'4);

and thefoIllowing organs: bone, liver, total body, thyroid, skin, kidney, lung, and Gltract.Using the methodology presented in NUREG-0133, Section4.3, doses due to liquid effluents .are calculated for the ingestion of drinking water and freshwater fish consumption.

Duelto the amount of recreation:along the TennesseeRiver, a dose for shoreline recreation is also calculated.

This:, recreation dose is calculated by deriving a dose factor for use in the dose equation for the recreatioh path way using equations A-4 and A-6 in Regulatory Guide 1.109. Dose factors for these.three pathways are calculated as described in Section 6.7. For pathways with no age or organ specific dose factors (i.e.,, shoreline recreation), the total body dose will be added to the internal organ doses for all age groups. The consumption of freshwater invertebrates and consumption of food, crops irrigated with Tennessee River water are not considered significant pathways for the area surrounding WBN(References 9 and 10), s0 they are not considered in the dose calculations.

The maximum individual dose from drinking water is assumed to be that calculated at the' location immediately downstream from the diffuser.

The maximum individualtdose from fish ingestion.is assumed to be that.calculated for the consumption of fish caught anywhere, between the plant and the'100% mixing point downstream(Table 6.1). The maximum potential recreation dose is calculated for a location immediately downstream of the plant outfall.The general equation for the dose to an organ j is: Dj ATCi D (6.6)where: Aij =the total dose factor to the total body or any organ j for nuclide i,mrem/h per jgCi/ml. The total dose factor is the sum of the dose factors for water ingestion; fish ingestion, and shoreline recreation, as defined in Section 6.7.T = the length. of time period over which the concentrations and the flows are averaged, h.Ci = the average concentration of radionuclide i, in undiluted liquid effluent during the'time periodT from any liquid release, giCi/ml.D = the near field averagedilution factorfor Ci during any effluent release. D is calculated bythe following equation:-F (6.7)0.10 fx RF(67 where: f = maximum undiluted liquid waste flow during the release,.cfs.

For TBS releases, this term is the waste flowinto the pond.0.10 = mixing fraction of effluent in river, defined as the fraction of.the~riverflow which isavailable for dilution of the release (Reference 11).RF = default riverfiow,.cfS:

For each release, this value is setto 25,657 cfs (the~average quarterly riverflow recorded from the period 1985-94).From the four age groups considered, the maximum organ dose is determined by comparing:

all organ doses for all age.groups.

The agegroup with the highest single organ dose: isselected as the critical age group. The total body and maximum organ doses for the critical age group are used~in the icalculation of the cumulative doses described in Section 6.3.1.El-133 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 72.of 195 6.3.1 Cumulative Doses Cumulative quarterly and annual sums of all doses are determined for. eachý release to compare to the limits given in ODCM Control 1.2.1.2. These quarterly and annual sums~will bethe sum of the doses for each releasewhich occurred in that quarter or year. These doses will be. used inthe comparison to the limits.6.3.2 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to the limits in ODCM Control 1.2.1.2 at least once per 31 days to determine compliance.

6.4 LIQUID

WASTE TREATMENT SYSTEM The LRTS described in the WBN FSAR shall be maintained and operated toý keep releases ALARA.A flow diagram for the LRTS is given in Figure 6.2.6.5 DOSE PROJECTIONS In accordance with ODCM Surveillance Requirements 2.2.1.3.1 and 2.2'1.3.2, doseprojections!will be performed at least once per 31 days using the equation below: D (a b) x31} +c (6.8)where: D = the 31-day dose projection, mrem.a = the cumulative dose for the quarter, mrem.b = the projected dose for this release, mrem.c = any anticipated additional dose in the next month from other sources, mrem.d = current number of days into the quarter up to the time of the release under consideration.

El-134 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 73'of 195 6.6 DOSE CALCULATIONS FOR REPORTING A complete dose analysis utilizing the total estimated liquid releases for each calendar-quarter will.be performed and reported as required in ODCMAdministrative Control 5.2. Methodology-for this analysis is based:on the methodology presented in Regulatory-Guide 1.109 and is described in this.section.

The releases are assumed, for this calculation, to be continuous over the 90 day. peridd.The near-field dilution factor, DNF, used for the quarterly calculations is: DNF =-0.10 RF (for receptors upstream of Tennessee-River Mile 510.0)(6.9)and DNF =-RF (for receptors downstream of Tennessee River Mile 510.0)(6.10)where: RF = the average actual riverflow for the location at which the dose is being determined,..cfs.

0.10 = the fraction of the riverflow available for dilution in the near field, dimensionless (Reference 11).Note: TRM 510.0 is the point at which the effluent is considered to be fully mixed with the riverflow (Reference 11).E1-135 WBN OFFSITEDOSE CALCULATION MANUAL Revision-22 0 (ODCM) Page 74 of 195 6.6.1 Water Ingestion Water. ingestion doses are calculated for each water supply identified within a 50 mile radius downstream of WBN (Table 6.1). The water ingestion dose equation is based on RegulatoryGuide 1V.109, Equation 1: D = k ( _UaPMP)y.

Awal exp(-Xitd)

For WBN, the dilution~factor(MP/F) is replaced by the near field dilution factor.(DNF) described by Equations 6.9 and 6.10, and theusage factor (Uap) and dose conversion factors (Awai) are incorporated into the dose factor (as described in Section 6.7.1). The resulting equation for the water ingestion dose, Dj, in mrem, to organ jis: Di = 106 (9.80 E- 09) 0.25 Y Awai.qi DNF exp(-8.64E04 kitd) (6.11)where: 106 = conversion factor, gCi/Ci.9.80E-09 = conversion factor, cfs per ml/h.0.25 = fraction of the yearly water consumption in one quarter, dimensionless.

Awai = dose factor for water ingestion for age group a, nuclide i, mrem/h per faCi/ml, as calculated in Section 6.7.1.qj = quantity of nuclide i released during the quarter, Ci.DNF = dilution factor, as described above; cfs-1.li = radiological decay constant of nuclide i, s-1 (Table 6.2).td = decay time for water ingestion, equal to the travel time from the plant to.the watersupply plus one -day to account for the time of processing at the water supply (per Regulatory Guide 1.109), d.8.64E+04 = conversion factor, s/d.6.6.2 Fish Ingestion Fish ingestion doses are calculated for each identified reach within a 50 mile, radius downstream of WBN (Table 6,1). The fish ingestion doseequation is based on'Regulatory Guide 1.109, Equation 2;D=k ~UaPM P- ~qi Bi AFaij exp(-Xitd)

For WBN, the dilution factor (M /F) is replaced by the near field dilution factor (D4F) described by Equations 6.9 and 6.10, andthe usage factor (Uap), bioaccumulation factor (B1), and dose conversion factors (AFaij) are incorporated into the dose factor (as described in Section 6.7.2). The resulting equation for the fish ingestion dose Dj, in mrem, to organ j is: Dj = 106 (9.80E- 09) 0.25 1AFoij qi DNF exp(-8.64E04 kitd) (6.12)i where: 106 = conversion factor, gCi/Ci.9.80E-09 = conversion factor, cfs per ml/h.0.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless.

AFaii = dose factor for fish ingestion for nuclide i, age group a, organ j, mrem/h per gCi/ml, as calculated in Section 6.7.2.qi = quantity of nuclide i released during the quarter, Ci.DNF. = dilution factor, as described above, cfs-1.= radiological decay constant of nuclide i, s-1 (Table 6.2).El-136 WBN OFFSITE DOSE CALCULATION MANUAL ReviSibn 22 0 (ODCM) Page 75 of 195 td = decay time for fish. ingestion, equal to the travel time from the plant to., the'center ofthe reach plus one day to account for transit through the food chain and food preparation time (per Regulatory Guide 1.109), d.8.64E+04 = conversion factor, s/d.6.6.3 Shoreline Recreation Recreation doses are calculated for each identified reach within a 50 mile radius downstream of-WBN (Table 6.!). It is assumed;that the maximum exposed individual spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />.per year on: the shore!ine at.a location immediately downstream from the diffusers.

This is'a more factor than that provided in Regulatory Guide 1.109. It assumes that an individual visits the shoreline for an averageof 1Ohours per week for'50 weeks per year. The shoreline recreation dose equation is based on Regulatory-Guide 1.109, Equation 3: For WBN, the dilution~factor.

Mp/F is replaced by the near field dilution factor (DNF),described by Equations 6.9 and 6.10, and the usage factor (Uap), shoreline width factor (SWF), radioactive half-life (Ti), dose conversion factor (ARaij) and the second exponential term are incorporated into the dose factor (as described:in Section 6.7.3). The resulting equation for. the shoreline recreation dose Dj, in mrem, to organ j is: (6.13)where: 106 = conversion factor, IaCi/Ci.9.80E-09 = conversion factor, cfs per ml/h.rf = recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter (Reference.25).

Recreation factors used are: 1st quarter -0.1 2nd quarter -0.3 3rd quarter -0.4 4th quarter -0.2.ARaij = dose factor for shoreline recreation for nuclide i, age group a, organ j, mrem/h per pgCi/ml, as calculatedin Section 6.7.3.qj = quantity of nuclide i released during the quarter, Ci.DNF = dilution factor, as described above, cfs-1 li = radiological decay-constant of nuclide i, s-1 (Table 6.2).td = decay time for recreation, equal to the travel time from the plant to the center of the reach, d.8.64E+04 = conversion factor, s/d.E1-137 WBN OFFSITE DOSE CALCULATION MANUAL Revision.22 0 (ODCM) Page 76 of 195 6.6.4 Total Maximum Individual Dose The total maximum individual quarterly total body dose for each age group a, D(tb)a, is obtained using the following equation: D(tb)a = DW + DF + DR (6.14)where: Dw -the highest total body water ingestion dose for age group a from-among allthe. public water supplies DF = the highest total body fish ingestion dose for age group a from among all the.reaches DR= the total body maximum shoreline recreation dose.The total maximum individual quarterly organ dose for each age group a.and each organj, D(org)aj, is obtained using the following equation: D(org)aj = Dw + DF + DR (6.15)where: Dw = the highest water ingestion dose for age group a and organ j from among all the public'water supplies DF = the highest fish ingestion dose for age group a and organ j from among all the reaches DR = the maximum shoreline recreation dose for organ j. The total body dose is used for allorgans exceptskin.

The doses reported are the highest total body dose (selected from all age groups) and the highest maximum organ dose (selected from all remaining organs and all agegroups).

El-138 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 77'of 195 6.6.5 Population Doses For determining population doses to the 50-mile population around the plant, an average-dose, is calculated for each age group and each pathway and then multiplied by the population and the fraction of the population in each age group. The population dose is determined using equation D-1 from Regulatory Guide 1.109: For WBN, the average individual doses (Djma) are determined by obtaihing the ratio~of the, average consumption rate to the maximum consumption rateand multiplying this bythe maximum individual dose.For wateringestion, the general equation used for calculating the population doses; POPWTR, in person-rem for a given Public Water Supply (PWS) is: (6.16)where: POPWTRj = water ingestion population dose to organ j, person-rem.

fPa = fraction of population in each age group a (from NUREG:CR-1004, table 3.39).Adult = 0.665 Child = 0.168 Infant= 0.015 Teen = 0.153 POPm = population at. PWS m. The 3 PWSs and theirpopulations are listed in Table 6.1.ATMWa = ratio of average to maximum water ingestion rates for each age group a. The values for maximum water ingestion rates are given as Uwa in Table 6.3. Average water ingestion rates, in L/y, (from Reference 4, Table E-4) are: Adult = 370 Child = 260 Infant = 260 Teen = 260 TWDOSanj = total individual water ingestion dose to organ j at PWS m, to the age group a (calculated as described in Section 6.6.1), mrem.10-3 = conversion factor for rem/mrem.For population doses resulting from fish ingestion the calculation assumes that allfish caught within a 50-mile radius downstream of WBN are consumed by local population.

The total fish harvest is calculated by multiplying the average fish harvest for the Tennessee River (HVST) by the size of the river reach under consideration (APR). These terms replace POPm. The general equation for calculating population doses, POPF, in person-rem from fish ingestion of all fish caught within a 50-mile radius downstream is: (6.17)where: POPFj = total fish ingestion population dose to organ j, person-rem.

HVST = fish harvest for the Tennessee River, 3.04 lbs/acre/y edible weight (Reference 12).APR = size of reach, acres (Table,6.1).

TFDOSari = total fish ingestion dose to organ j for reach r, for the age group a, (calculated as described in Section 6.6.2), mrem.fPa = fraction of population in each age group a, as given above.FISHa = amount of-fish ingested by each age group a, kg/y. Average fish ingestion rates, kg/y (Reference 4, Table E-4) are: Adult = 6.9 Child = 2.2 Teen = 5.2 Infant = 0.0 E1-139 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 78 of 195 453.6 = conversion factor, g/lb.10-3 =: conversion factor, rem/mrem.10-3 = conversion factor, kg/g.For shoreline recreation, the total recreation dose is determined by multiplying the-average dose rate (TSHDOS) to an individual by the number of visits to that.river reach (SHVIS) and~the'length ofthe average visit (HRSVIS).

The general equation used for calculating the population doses, POPR, in person-rem is: rf 4 POPRj = 1 8 TSHDOSrj SHVISr HRSVISr (6.18)10 3 8760 r=1 where: POPRj = total recreation population dose for all reaches to organ j, person-rem., rf = fraction of,;yearly recreation which occurs in that quarter, as given-in Section, 6.63.TSHDOSrj = total shoreline dose rate for organ j, in reach r, mrem/h.SHVISr = shoreline visits per year at each reach r, (Table 6.1-).HRSVISr = length ofaverageshoreline recreation visit at reach r, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.103 = conversion factor, mrem/rem.8760 = conversion factor, h/y.E1-140 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 79 of 195 6.7 LIQUID DOSE FACTOR EQUATIONS The general form of the liquid dose factor equation from NUREG-0133 is: A 1 1 = +ow UFB +UFBFIjJ )DFi where: k 0 = conversion factors.Uw = water consumption rate, L/y.Dw = dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for water. consumption, dimensionless.

UF = fish consumption rate, kg/y.BFi = bioaccumulation factor for nuclide i in freshwater fish, pCi/kg per pCi/L.U, = invertebrate consumption rate, kg/y.DFi = ingestiondose conversion factor, mrem/pCi.Since the value of the: term. Ui. is negligible, WBN will not be considering the.dose from invertebrate ingestion and thatportion ofthe equation isdropped.

In addition, a term is addedjto account for recreation.

The near-field dilution factor is assigned a value of 1 in the water ingestion portion of the equation and is not used for WBN due to the use of riverflow as the dilution factor in the dose calculation.

The resulting general dosefactor equation is: Aij = ko (Uw +UF BFi)DFi +kl UR Cs DFGi where: k 0 , 1 = conversion factors.UR = recreation usage factor, h/y.Cs = accumulation factor for buildup of activity in sediment, pCi/in 2 per, pCi/L.DFGi = dose factor for standing on contaminated ground, mrem/h per pCi/m 2.The equations for each of the individual pathway dose factors are presented in the following sections.6.7.1 Water Ingestion Dose Factor -Awaij (mrem/h per pCi/ml)106103. DFaii Uwa.Awaij 8760 (6.19)where: DFaij = ingestion dose conversion factor for nuclide i, age a, organ j, mrem/pCi,: (Table 64).Uwa = water consumption rate for age group a, L/y, (Table 6.3).106 = conversion factor, pCi/4Ci.10 3 = conversion factor, mil/L.8760 .= conversion factor, h/y.E1-141 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 80 of 195 6.7.2 Fish Ingestion Dose Factor -AFaij (mrem/h per [tCi/ml)106103 DFaij Ufa B 1 AFaij 8760 (6.20)where: DFaij = ingestion dose:conversion factor for nuclide i,.age a, organ j, mrem/pCi, (Table 6.4).Ufa = fish consumption rate for age group .a, kg/y, (Table 6.3).Bi = bioaccumulation factor for nuclide i, pCi/kg per pCi/L, (Table 6.5).106 = conversion factor, pCi/pCi.103 = conversion factor, ml/L.8760 = conversion factor, h/y.6.7.3 Shoreline Recreation Dose Factor -ARaiJ (mrem/h per IiCi/ml).Equation A-6 in Regulatory.

Guide 1.109 provides a methodology for calculating the .dose due to. shoreline recreation along a water body: Dose = k Kc U SWF y.Ciw Ti DFG 1 j [1-exp(- 1itb) b Since the terms Ciw and T are part of the dose equation (Equation 6.6), the equation forthe dose factor becomes: ARai = "(1031 6 -DFG 0 K M SW [1-exp(-'itb)

] (6.21)18760.3600 F )}[ -eP-Jb)J(.1 where: DFGij = dose conversion factor for standing on contaminated.ground for nuclide i and organ-j (total body and skin), mrem/h per pCi/im 2 , (Table 6.6).Kc = transfer coefficient from water to shoreline sediment; L/kg-h, (Table 6:3).M = mass density of sediment, kg/m 2 , (Table 6.3).SWF = shoreline width factor, dimensionless, (Table 6.3).103 = conversion factor, ml/L.106 = conversion factor, pCi/gCi.3600 = conversion factor, s/h.Ii = decay constant for nuclide i, s-1, (Table 6.2).tb = time shoreline is exposed to the concentration of the water, s, (Table 6.3).UR = recreation usage factor, 500 h/y.8760 = conversion factor, h/y.El-142 WBN OFFSITE DOSE CALCULATION-MANUAL Revision 22 0 (ODCM) Page 81 of'195 Table 6.1 -RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream .of WBN, Beginning Ending Size 1 Recreation 2 Name I TRM [ TRM, (acres) visits/y ChickamaugaLake (from WBN to 528 5103 4799 85,200 100% mixing point)Chickarnauga Lake (from 100% mixing 5103 484 22101 914,000 point .to. Sequoyah Nuclear Plant)Chickarnauga Lake (from Sequoyah 484 471 9889 5,226,700 Nuclear Plant to Chickamauga Dam)Nickajack Lake (from Chickamauga 471 460 1799 200,000 Dam to.WBN 50-mile radius)TRM..- Tennessee River Mile.1 Reference 13.2 Reference 14.3 100% Mixing Point (Reference 11).Public Water Supplies Within 50 Mile Radius Downstream of WBN.Name TRM 11990 Population Dayton, TN 504 13,500 Soddy-Daisy/Falling 487 10,000 Water Utility District East Side Utility, TN 473 35,000 Chattanooga, TN 465 167,500 NOTE: Tennessee river mile locations are rounded to the nearest mile for dose calculation purposes.E1-143 WBN OFFSITE DOSE CALCULATION MANUAL Revision.22 0 (ODCM) Page 82 of 195 Table 6.2 -RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 1 of 3)Half-Life I Biv Fmi Fmi Ffi Nuclide (minutes) (s.) (cow) (goat) (beef)H-3 6.46E+06 1.79E-09 4.80E+00 1.OOE-02 1.70E-01 1.20E&02 C-14 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.01E0&1 3.1OE-02 Na-24 9OOE+02 1.28E-05 5.20E-02 4.OOE-02 4.00E-02 3.00E.02 P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2.20E-03 2.20E-03 2.40E-03 Mn-54 4.50E+05 2.57E-08 2.90E-02 2.50E-04 2.50E-04 8.0OE-04, Mn-56 1'55E+02 .7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00&E04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E&02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03' 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00&E03 1.OOE-03 1.30E&02 Co-58 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E'02'Co-60 2.77E+06 4.17E-09 9.40E-03 1.OOE-03 1.00E-03 ;1.30E-02 Ni-63 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9:70E-04 Zn-65 3.52E+05 3.28E-08 4.OOE-01 3.90E-02 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.40E-05 4.OOE-01 3.90E-02 3190E-02 3*OOE-02 Zn-69 5.56E+O1 2.08E-04 4.OOE-01 3.90E&02 3.90E"02 -3.OOE-02 Br-82 2.12E+03 5.45E-06 7.60E-01 5.OOE-02 5.OOE-02 2.60E-02 Br-83 1.43E+02 8.08E-05 7.60E-01 5.00;E02 5.OOE-02 2.60E-02 Br-84 3.18E+O1 3.63E704 7.60E-01 5.OOE-02 5.OE-02 2.60E&02 Br-85 2.87E+00 4.02E-03 7.60E-01 5.OOE-02 5.O0E-02 2.60E-02 Rb-86 2. 69E+04 4.29E-07 1.30E-01 3.OOE-02 3.00E-02 3;1OE-02 Rb-88 1.78E+Q1 6.49E-04 1.30E-01 3.OOE-02 3.OOE-02 3.1OE-02 Rb-89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.OOE-02 3.1OE-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.OOE-04 Sr-91 5.70Et02 2.03E-05 1.70E-02 1.40E,03 1.40E-02 6.OOE-04 Sr-92 1.63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3,85E+03 3.OOE-06 2.60E-03 1.OOE-05 1.OOE-05 4.60E-03 Y-91 m 4:97E+01 2.32E-04 2.60E-03 1.OOE-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.37E-07 2;60E-03 1.00E-05 1:.OOE-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-03 1.0OE-05 1.00&E05 4;60E-03 Y-93 6.06E+02 1.91E-05 2.60E-03 1.00E-05 1.00&E05 4.60E-03 Zr-95 9.22E+04 1.25E-07 1.70E-04 5.OOE-06 5.OOE-06 3.40E-02 Zr-97 1.01E+03 1.14E-05 1.70E-04 5.00E-(06

ý500E06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E-03 2.50E-03 2.50E-03 2280E-01 Nb-97 7.21 E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.1.OE-03 Tc-99m 3.61 E+02 3.20E-05 2.50E-01 2.50E-02 2.50E&02 4.O0E-01 Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.OOE-01 Ru-103 5.67E+04 2.04E-07 5.OOE-02 1.OOE-06 1.OOE-06 4.OOE-01 El-144 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 83,of 195 Table 6.2 -RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 2 of 3)Half-Life I Biv Fmi Fm Ffi,.Nuclide (minutes) (s-1) (cow) (goat) (beef)Ru-105 2.66E+02 4.34E-05 5.OOE-02 1.OOE-06 1.OOE-06 4.OOE'-01 Ru-106 5.30E+05 2.18E-08 5.OOE-02 1.OOE-06 1.OOE-06 4.0E&-01 Ag-110m 3.60E+05 3.21E-08 1.50E-01 5.OOE-02 5.OOE-02 1.70E-02, Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A Sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A Te-125m 8.35E+04 1.38E-07 1.30E+00 1.00E-03 1.OOE-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.30E+00 1.OOE-03 1.OOE-03 7!70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.OOE-03 1.OOE-03 7;70E-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.OOE-03 1.OOE-03 7.70E-02 Te-129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1.OOE-03 7.70E-02 Te-131m 1.80E+03 6.42E-06 1.30E÷00 1.OOE-03 1.OOE-03 7.70E-02 Te-131 2.50E+01 4.62E-04 1.30E+00 1.00E-03 1.OOE-03 7.70E-02 Te-132 4.69E+03 2;46E-06 1.30E+00 1.00E-03 1.00&E03 7.70E-02 1-130 7.42E+02 1.56E-05 2.OOE-02 1.20E-02 4.30E-01 2;90E-03 1-131 1.1'6E+04 9.96E-07 2.OOE-02 1.20E&02 4.30E-01 2.90E-03 1-132 1.38E+02 8.37E-05 2.OOE-02 1.20E-02 4.30E-01 2.90E-03 1-133 1.25E+03 9.24E-06 2.OOE-02 1.20E-02 4.30E-01 2.90E-03 1-134 5.26E+01 2.20E-04 2.OOE-02 1.20E-02 4,30E-01 2.90E-03 1-135 3.97E+02 2.91E-05 2.OOE-02 1.20E-02 4.30E-01 2.90E-03 Cs-134 1.08E+06 1.06E-08 1.OOE-02 8.OOE-03 3.00E-01 1.50E;02 Cs-136 1.90E+04 6.08E-07 1.00E-02 8.OOE-03 3.00&E01 1.50E-02 Cs-137 1.59E+07 7.26E-10 1.00E-02 8.OOE-03 3.OOE-01 1.50E-02 Cs-138 3.22E+01 3.59E-04 1.OOE-02 8.OOE-03 3.OOE-01 1.50E-02 Ba-139 8.31E+01 1.39E-04 5.OOE-03 4.OOE-04 4.OOE-04 3.20E-03 Ba-140 1.84E+04 6.28E-07 5.OOE-03 4.OOE-04 4.OOE-04 3120E-03 Ba-141 1.83E+01-6.31 E-04 5.OOE-03 4.OOE-04 4.OOE-04 320E-03 Ba-142 1.07E+01 1.08E-03 5.OOE-03 4.OOE-04 4.OOE-04 3.20E-03 La-140 2.41 E+03 4.79E-06 2.50E-03 5.OOE-06 5.OOE-06 2.00&E04.La-142 9.54E+01 1.21E-04 2.50E-03 5.00&E06 5.OOE-06 2.OOE-04 Ce-141 4.68E+04 2.47E-07 2.50E-03 1.00E-04 1.OOE-04 1,20E-03 Ce-143 1.98E+03 5.83E-06 2.50E-03 1.0&E-04 1.OOE-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.OOE-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.OOE-06 5.OOE-06 4.70E-03 Pr-144 1.73E+01 6.68E-04 2.50E-03 5.OOE-06 5.OOE-06 4.70E-03 Nd-147 1.58E+04 7.31E-07 2.40E-03 5.OOE-06 5OOE-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5.OOE-04 5OOE-04 1.30E-03 Np-239 3.39E+03 3.41 E-06 2.50E-03 5.OOE-06 5.OOE-06 2.00E-04 Ar-41 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A N/A Kr-87 7.63E+01 1.51 E-04 N/A N/A N/A N/A El-145 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 84 of. 195 Table 6.2 -RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 3 of 3)Half-Life I Biv Fmi Fmi Ffi Nuclide (minutes) (s-1) (cow) (goat) (beef)Kr-88 1.70E+02 6.79E-05 N/A N/A N/A N/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-131 m 1.70E+04 6.79E-07 N/A N/A N/A N/A Xe-1 33m 3.15E+03 3.67E-06 N/A N/A N/A N/A Xe-133 7.55E+03 1.53E-06 N/A N/A N/A N/A Xe-1 35m 1.54E+01 7.50E-04 N/A N/A N/A N/A Xe-1 35 5.47E+02 2.11E-05 N/A N/A N/A N/A Xe-1 37 3.83E+00 3.02E-03 N/A N/A N/A N/A Xer138 1.41 E+01 8.19E-04 N/A N/A N/A N/A

References:

All nuclides half-lives from: Reference 15.Transfer factors for Sb- isotopes:

Reference 16 Table 2-7.Cow-milk transfer factors forl, Sr, and Cs nuclides are from Reference 21, Table 3.17.Goat-milk transfer factors for Inuclides are from Reference 21, Table 3.17.Beef transfer factors for Fe,?Cu, Mo, and Cs nuclides are from Reference 21, Table 3,18.All other nuclides transfer factors are from Reference 4, Tables E-1 and E-2.E1-146 WBN OFFSITE DOSE CALCULATION MANUAL ReviSion 22, 0 (ODCM) Page 85 of 195 Table 6.3 -DOSE CALCULATION FACTORS (Page 1 of 2)SFactor. Value Units I Reference1

BRa (infant):

1400 m 3/y Reference 20 -BR,.(child) 5500 m 3/y Reference.20 BRa.(teen) 8000 m 3/y Reference

20 BRa.(adult) 8100 m 3/y Reference 20 f 9 1 Conservatively assumes all stored vegetables are grown locally.fL I Reference4(Table E-1 5)fp 1 see ýNote fS 0 see Note H 9 g/m 3 TVA Value K, 0.072 L/kg-h Reference 4 (Secti6on2.C.)

M 40 kg/m 2 Reference 4 (Section 2.C.)P 240 kg/m 2 Reference 4(T'able E415)Qf (cow) 64 kg/day Reference.

21 (Sect.- 3 4).Qf (goat) 08 kg/day Reference 21 (Sect. ,4)r 0.47 Reference,.21 (Sect.3.2)-

tb 4.73E+08 (15 y) s Reference 4 (Table E-15i tcb 7;78E4-06 (90 d) s Reference 10, Section 14.3.9:1 6cf 1.56E+ 07 (180 d) s Reference 10, Section 11.3.9.1.te 5.18E+06 (60 d) s Reference'4, (Table Ei15)'ten :2;59E÷06 (30 d) s Reference 4 ;(Table.E-15).

tesf 7 78E+06'(90 d) s Reference 4 (Table E- 5)tfm &64E+04 (1 d) s Reference 10,',Section 11.3.9.1 the 8.64E+04 (1 d) s Refebrence 21, Table 3.40 t 1 12E÷06(13 d) s Reference 21, Table!3.40 tsy 2.38E+07(275 d), s " Reference 10; Section 11.3.9.1 Uam.(infant) 0 kg/y Reference 4 (Table E-5)Uam (child) 41 kg/y Reference 4: (Table E75)Uam.(teen) 65 kg/y 'Reference4 4(Table E-5)Uam (adult) 110 kg/y Reference 4 (Table E-5)Note: Calculations for release permits use the conservative valuegivenmin the table for these:parameters.

The calculations performed for reporting purposes (as .described in Section 7.7) use actual grazing percentages identified in the land use census.El-147 WBN OFFSITE DOSE CALCULATIONMANUAL Revision 22 0 (ODCM) "Page 86 of 195 Table 6.3 -DOSE CALCULATION FACTORS (Page 2 of 2)Factor Value Units. [Reference.

Ua 0 (infant) 330 L/y Reference 4 (Table-E&5)

Ua,: (child) 330 L/y Reference 4 (Table E-5).U,, (teen) 400, L/y Reference 4 (Table E-5)UaD 0 (adult) 310- L/y Reference 4 (Table E-5).Uf 2 (ihfant) 0 kg/y Referencef,4(Table E-5)Uf(child) 6.9 kg/y Reference

4. (Table E-5)'Ufa(teen) 16 kg/y Reference

ýUfp(adult)ý

.21 kg/y Reference

4. (Table E-5)UFLa (infant) 0 kgly Reference 4 (Table E-5)UFLa (child). 26 kgly Reference 4 (Table E-5)UFLa (teen) 42 kg/y Reference 4 (Table E-5)UFLa (adult) 64 kg/y `Reference 4 (Table E-5)Usa (infant) 0 kg/y Reference 4 (Table E75)Usa.(child) 520 kg/y Refeerien4 4(Table E-5)Usa (teen) 630 kg/y

Reference:

4,(Table E-5)Us ,(adult):

520 kg/y Reference.4 (Table E'-5)Uwp(infant) 330 L/y Refereince.4 (Table E-5)Uwa(child) 510 _Y ,Table E-5)Uwd(teen) 510 L/y Reference 4 (Table E-5)Uwa(adult) 730 L/y ReferenCe.4ý(Table E-5).SWF 0.2 none Reference4 (T6able, A-2)Yf 1.85 kg/m2 21 (Table,3.4)

Y 1 1.18 kg/m 2 Reference 21 (Table 3.3)Ysf 0.64 kg/m 2 Reference 21 :(Table3.3)

Ysv 0.57 kg/m 2 Reference 21 (Table 3.4)(value selected is for non-leafy vegetables).

, lw (iodines) 7.71 E-07 s"1 Reference 21 (Table 3.10).(15A4 d half-life) lw (particulates) 5.21 E-07 s-1 Reference 21 (Table3.10)

(10.4 d half-life), E1-148 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page87W.of 195 Table 6.4 -INGESTION DOSE FACTORS -DF.a.(mrem/pCi ingested) (Page 1 of 8)ADULT Nuclide H-3 C,14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91 m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-1O1 Ru-1 03 Ru-105 Ru-106 bone 1.05E-07 2.84E-06 1.70E-,06 1.93E-04 O.OOE+00 0.OOE+00 0.OOE+00 2.75E-06 4.34E-06 O.00E+00 0.00E+00 0.OOE+00 1.30Er014 5.28E&07 0.00E+00 4.'84E-06 1..03E-08 1.70E-07 0.00E+00 0.00E+00.00OE+00 0.00E+00 O.OOE+00 0.00E+00 O.00E+00 3.08E-04 7.58E-03 5.67E-06 21'5E-06 9.62E-09 9.09E-1 1 1.41E-07 8.45E-1 0 2.68E&09 3.04E-08 1'.68E-09 6.22E&09 5.22E-1 1 0.OOE+00 2.47E-1 0 2*54E-10 1.85E-07 1.54E-08 2.75E-06 liver 1.05E-07 5.68E-07 1.70E-06 1 .20E-05 0:00E+00 4.57E-06 1.15E-07 1 .90E-06 1.02E-05 1.75E-07.7.45E-07 2.14E-06 9.01 E-06 6.86E-08 8 33E-08 1 .54E-05 1.97E'08 4.08E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+ý00 2A1&E-05 6.05E-08 4.01 E-08 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 9.75E-09 3.39E-10 3.46E-09 1.32E-11 4.31 E-06 6.98E-1 0 3*66E-10 0.OOE+00 0.00E+00 0.00E+00 total body 1.05E-07 5.68E-07 1.70E-06 7.46E-06 2.66E-09 8.72E-07 2.04E-08 4.43E-07 3.91 E-06 2.91E-07 1.67E-06 4.72E-06 4.36E-06 3.13E-08 3*91 E-08 6.96E'06 1 *37E-09 3.73E-08 2.26E-06 4.02E-08 5.21 E-08 2.14E-09 9.83E-06 3.21 E-08 2.82E-08 8.84E-06 1.86E-03 2.29E-07 9.30E-08 2.58E-1 0 152E-1 2 3.77E-09 2.47E- 1 7.40E-1 1 6.60E-09 1.55E-10 1.86E-09 4.82E-1 2 8.20E-07 8.89E-09 3.59E-09 7.97E-08 6.08E-09 3.48E-07 thyroid 1 .05E1-07 5.68E-07 1 .70E-06 0.00E+00 1 .59E-09 0.00E+00 0.OOE+00.0.OOE+ý00 0.OOE+00 0.O0Ei-00 0.OOE+00, 0.00E-t00 0.OOE+00 0.OOE+00: 0.OOE+00 0.00E+00 0.OOEl-00 0.00E+00 0.00OE4-00, 0.00E+00 0.OOE+00, 0.0OE+00 0.00E+00 0.OOE-'00 0.OOE+00, 0.OOE+00 0.00E+00 0.00E+00 0.OOE+/-00 0.00E+00 0.OOE+00 O.OOE4W.0.OOE+00 0 *OOE-i-00 0.OOE+00 0.OOE+00.0 *0OE-'00: 0.OOE+00 0.00E+00 0.OOE+00.OOE-'010 0.OOE+00 0.OOE+00 0.OOE+00 kidney 1.05E707 5&68E-07 1.70E-06 0.OOE+00 5.86E-1 0 1.36E-06 1.46E-07 0.OOE+00 0.00E+00 O.OOE+00 0.00E*00 0*00E+00" 0.00E+00 0.00E+00 2.1tE-07 1.03E&05 1.28E-08 2.47E-07 o*OOE+00 O.OOE+00 0ý00E-00 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0;00E+00 O.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.53E-08 3142E-09 1.54E-11 9.76E&06 1.06E-08 6.59E-09 7.06EL-07 1.99E&07 5.31,E-06 lung 1 .OSE-07 S.68E-07 1 .70&-06, 0.OOE+00o 3.53E-09 1.06 0E-ý06 2.85&-06 0.00E-'-0 0.OOE+00;0.OOE+00 0.OE00E+G 0.OOE+ý00-0.OOE+00 0.00E+00, 0.OE00L+p 0.OOE+-00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+-00 0.OOEt00.OOE+Q100.0.OQE+00 0.1001E+,00 0.OOE+00: 0.00E+00, 0OOE+ý00: 0.00E+00 0ODOE+00, 0.OOE-'-00 0.00E+00 0O.OOE+00ýO.'OOE 1+00'3.42E-,1 0~1.87E-1:0 0.00E,+00 0.OOE+0O 0OME+ý00: GI-LLI 1.05EL07 5.68E-:07 1 .70E-06 2.1 7E-05 6.69E-07 1 40E-05 3.367E-06 1":09E-06 3.40E&05 4.44E-06 1;.51E-05.4.02E-05 1.88E-06 7.10Et 06 9,70E-06 2.96E-09 2.49E-05 2.59E-606:

5.79E-08 4.09E-1 3 6.'00Et6-0

4.1 6E'06

8.36E-l 9, 2.33E-21 4.94E'05 2.19E'04 2:70E-105 4:26EI-05 1.02E-04, 2.67E-10 7.76E-05 1.48E-,05 3.09E-'05 1A.05E-04 2.1 QE-05 4. 87E-08*9.99E-06 4.1 3E107 1. 1OE-2.1 2.,16E-05 9.42E-06ý1.78E-04 E1-149 WBN OFFSITE DOSE CALCULATIONMANUAL Revision 22 0 (ODCM) Page 88of 195 Table 6.4 -INGESTION DOSE FACTORS -DF.ai (mrem/pCi ingested) (Page 2 of 8)ADULT Nuclide Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-1 29m Te-129 Te-131m Te-131 Te-132 1-130 1-131 1-132 1-133 1-134 1-135 Cs-1 34 Cs-136 Cs-137 Cs- 138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 1.60E-07 2.80E-06 1.79E-06 2.68E-06 6;77E-06 1.10E-07 1 .15E-05 3.14E-08 1.73E-06 1.97E-08 2.52E&06 7.56E-07 4.16E-06 2.03E-07 1.42E-06 1 '06E&07 4.43E-07 6.22E-05 6.51 E-06 7.97E-05 5.52E-08 9.70E-08 2.03E-05 4.71 E-08 2.1 3E-08 2.50E-09 1.28E-10 9:36E-09 1.65E-09 4.88E-07 9.20E-09 3.01E-1I 6.29E-09 1.03E-07 1.19E-09 liver 1,48E&07 5.29E-08 2,00E-08 9.71 E-07 2.42E-06 3.95E-08 4.29E-06 1 18E-08 8.46E-07 8:23E-09 1.63E-06 2.23E-06 5.95E-06 5.43E-07 2.-47E-06 2.88E-07.1 6E-06 1.48E-04 2.57E-05 1.09E-04 1:09E-07 6.91 E-1 1 2'55E&08 3.56E- 1 2.19E-11 1.26E-09 5.82E-1 1 633E-09 1.22E-06 2.04E-07 3169E-09 1.25E-11 7.27E-09 8.61 E-08 1.17E-10 total body 8.79E-08 1.11E-06 4.26E-07 3.59E-07 8.25E-07 2.38E-08 1.82E-06 7.65E-09 7.05E-07 6.22E-09 1.53E-06 8.80E-07 3.41 E-06 1.90E-07 7.53E-07 1.03E-07 4.28E-07 1.21 E-04 1.85E-05 7.14E-05 5.40E-08 2.84E-09 1.33E-06 1.59E-09 1.34E-09 3.33E-10 1.45E-1 1 7.18E-10 1.35E-10 2;62E&08 4.56E-1 0 1.53E-1 2 4.35E-10 3.01 E-08 6.45E-1 1 thyroid 0.00E+00 6.79E-09 1.82E-09 8.06E-07 1.73E-06 8.15E-08 3.95E-06 2.41 E-08 1.34E-06 1.62E-08 1.80E-06 1.89E-04 1.95E-03 1.90E-05 3.63E-04 4.99E-06 7.65E-05 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00, 0.OOE+00 kidney 2.91 E-07 0.00E-7'00 0.00E-00 1.09E-05 2.75E-05, 4.48E-07 4.80E-05 1.32E-07 8.57E-06 8.63E-08 1.57E-05 3.48E-06 1.02E-05 8.65E-07 4.31 E-06 4.58E-07 1.86E-06 4.79E-05 1.43E-05 3.70E&05 8.01 E-08 6.46E-1I 8.67E-09 3.31 E-1i1 1.85E- 1I 0.OOE+00 0.00E+00 2.94E-09 5.37E-10 1.21 E-07 2.1-3E09 7.05E-12 4.25E-09 0.OOE+00 3.65E-1 0 lung 0.00E00 2:.18E-06 1.38E-06 0.00E+00 0.00E+00 0.0OE+00 0.00E+00 0.OOE+00 0.00Et00;0.00E+/-00 0OOE+00 0.00E-+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 1'.59E-05 1.96E-06 1.23E-05 7.91E-09 3;92E-'i1 1.46E-08 2.02E-I 1 1.24E-11 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 000E+.00 0.00E+00 GI-LLI 6.04E-05 7'.95E&05 1 97E-05 1.07E-05 2.27E-05 8.68E-06 5.79E-05 2.37E-08 8.40E-05 2.79E-09 7.71E&05 1.92E-06 1 .57E-06 1.02E407 2.22E-06 2.51 E-1 0 1.31 E-06 2.59E-06 2.92E-06 2.11E-06 4.65E-13 1 .72E-07 4.1 8E&05 2.22E-1:7 300E,-26 9.25E-05 4.25E-07 2.42E-05 4.56E-05 1i.65E-04 4M03E-05 4*33E-18 3.49E-05 2.82E&05 2.40E-05

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, All others are from Reference 4, Table E-1 1.Sb-124, Sb-125 are from

Reference:

17, Table 4.NOTE: The tritium dosefactor for bone is assumed to be equal tothetotal body dose factor. This assumes that tritium will act similarly in all organs (Reference 24).El-150 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 89 of 195 Table 6.4 -INGESTION DOSE FACTORS -DFaij (mrem/pCi ingested) (Page 3 of 8)TEEN Nuclide H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91 m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 TC-99m Tc-101 Ru-1 03 Ru-105 Ru-1 06 bone 1.06E-07 4.06E-06 2.30E&06 2.76E-04 0.OOE+00 0.OOE+00 0.OOE+00 3.78E-06 5.87E-06 0.OOE+00 O.OOE+00 0.OOE+00 1.77E-04 7.49E-07 0.OOE+00 5.76E-06 1.47E-08 2.40E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.40E-04 8.30E-03 8.07E-06 3.05E-06 1.37E-08'1.29E-10 2.01 E-07 1.21E-09 3.83E-09 4.12E-08 2.37E-09 8.22E-09 7.37E-1 1 0.OOE+00 3.32E-10 3160E-10 2.55E-07 2.18E-08 3.92E-06 liver 1.06E-07 8.12E-07 2.30E-06 1.71 E-05 0.OOE+00 5.90E-06 1.58E-07 2.68E-06 1.37E-05 2.38E-07 9.72E-07 2.81 E-06 1.25E-05 9.57E-08 1.15E-07 2.OOE-05 2.80E-08 5.66E-07 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 2.98E-05 8.52E-08 5.50E-08 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.'OOEE+00 0.OOE+00 0.OOE+00 1.30E-08 4.69E-10 4.56E-09 1.83E-1 1 6.03E-06 9*26E-1 0.5.12E1 0 0.OOE+00 0.OOE+00 0.OOE+00 total body 1.06E-07 8.12E-07 2.30E-06 1.07E-05 3.60E-09 1.17E-06 2.81 E-08 6.25E-07 5.29E-06 3.99E-07 2.24E-06 6.33E-06 6.OOE-06 4.36E-08 5.41 E-08 9.33E-06 1.96E-09 5.19E-08 3.04E-06 5.74E-08 7.22E-08 3.05E-09 1.40E-05 4.54E-08 3.89E-08 1.26E-05 2.05E-03 3.21 E-07 1.30E-07 3.69E-1 0 4.93E-12 5.39E-09 3.50E-1 1 1.05E-10 8.94E-09 2.16E-10 2.51 E-09 6.68E-12 1.15E-06 1.20E-08 5.03E-09 1.09E-07 8.46E-09 4.94E-07 thyroid 1.06E-07 8.12E-07 2.30E-06 0.OOE+00 2.OOE-09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney 1.06E-07 8.12E-07 2.30E-06 0.OOE+00 7.89E-1 0 1.76E-06 2.OOE-07 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 2.91 E-07 1.28E-05 1.83E-08 3.44E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.91E-08 7.11E-10 4.42E-09 2.14E-11 1.38E-05 1.38E-08 9.26E-09 8.99E-07 2.75E'-07 7.56E-06 lung, 1.06E-07 8.12E-07 2.30E-06 0.OOE+00 5.14E-09 0.00E+00 0.OOE+00 1.70E-06 4.32E-06 0.OOE+00 0.OOE+00 O.OOE+O0 O.OOE+O0 0.OOE+00 0,0OE+00 0.O0E+00 0.O0E+00 0.OOE+00 0.OOE+00 O.OOE+00 0i00E.÷00 0.00E+00 0*OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00, 0.OOE+00 0.00E400 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+/-00 5.14E-,10 3.12E&10 0.OOE+00 0.OOE+00 0.OOE+00 GImLLI 1.06E&-07 8.12E-07 2.30E-06 2.32E-05 6.05ED07 1.21 E-05 1.04E-05 1A16E-06 3.24E-05 4.44E-06 1'.34E;05 3.66E'-05 11.99E&06 5.19E-:06 8.92E-06 8.47E-06 5.1 6E-08 3.1IE-05 0.OOE+00 0.OOE+60 0'.00E+00 0o0.E+00 4.41 E-06 7.30E-15*8.'43E-17 5.24E-05 2.33 E-04 3.66E-05 7.77E-05 1.13E-04 6,09E-0g 8.24E-05 3.32E-05 1.17E&04 3.00E-05 1.27E-%04 1.95E o5 4.37E-07 1.08E-05 6.08E-07 8.75E-17 2.13E-05 1.76E-05 1.88E-04 El-151 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page.90 of 195 Table 6.4 -INGESTION DOSE FACTORS -DFaij (mrem/pCi ingested) (Page 4 of 8)TEEN Nuclide Ag-110m Sb-1 24 Sb-125 Te-125m Te-127m Te-127 Te- 129m Te-129 Te-131m Te-131 Te-132 I-130 1-131 1-132 1-133 1-134 1-135 Cs-134 Cs 136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 2.05E-07 3.87E-06 2.48E-06 3.83E-06 9.67E-06 1.58E-07 1.63E-05 4.48E-08 2.44E-06 2179E-08 3.49E&06'1.03E-06 5.85E-06 2.79E-07 2.01E-06 1.46E-07 6.1OE-07 8.37E-05 8.59E-06 1.12E-04 7.76E-08 1.39E-07 2.84E-05 6.71E-08 2.99E-08 3.48E-09 1.79E&10 1.33E-08 2.35E-09 6.96E-07 1.31E-08 4.30E-i 1 9.38E-09 1.46E-07 1.76E-09 liver 1.94E-07 7.13E-08 2.71E-08 1.38E-06 3.43E-06 5.60E-08 6.05E-06 1.67E-08 1.17E-06 1.15E-08 2.21 E-06 2.98E-06 8.19E-06 7.30E-07 3.41 E-06 3.87E-07 1.57E-06 1 :97E-04 3.38E-05 1.49E-04 1.49E-07 9.78E-11 3:48E-08 5.01 E-1i1 2.99E-1i1 7.95E-i 1 8.88E-09 1.71E&06 2.88E-07 5.23E-09 1.76E-11 1.02E-08 1.19E-07 1.66E-1 0 total body 1.18E-07 1.51 E-06 5.80E-07 5.12E-07 1.15E-06 3.40E-08 2.58E-06 1.09E-08 9.76E-07 8.72E-09 2.08E-06 1.19E-06 4.40E-06 2.62E-07 1.04E-06 1.39E-07 5.82E-07 9.14E-05 2.27E-05 5.19E-05 7.45E-08 4.05E-09 1.83E-06 2.24E-09 1.84E-09 4.55E-10 1.98E-11 1.02E-09 1.91E-10 3.74E-08 6.52E-1 0 2.18E-12 6.11E-10 4.17E-08 9.22E-1i1 thyroid O.OOE+00 8.78E-09 2.37E-09 1.07E-06 2.30E-06 1.09E-07 5.26E-06 3.20E-08 1.76E-06 2.15E-08 2.33E-06 2.43E-04 2.39E-03 2.46E&05 4.76E-04 6.45E-06 1.01E-04 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney 3.70E-07 0.00E-00 0.00E+00 0.OOE+00 3.92E,-05 6.40E-07 6.82E-.05 1.88E&07 1.22E-05 1.22E-07 2.12E-05 4.59E-06 1.41 E-05 1.15E-06 5.98E-06 6.10E-07 2.48E-06 6.26E-05 1.84E-05 5.07E-05 1.10E-07 9.22E-1i1 1.18E-08 4.65E-1i1 2.53E-11 0.00E+00 0.OOE+00 4.18E-09 7.67E-10 1.72E-07 3.04E-09 1.01E-11 5.99E-09 0.00E+00 5.21E-10 lung 0.OOE*00 3.38E-06 2.1 8E-06 O.OOEtOO 0.OOE+00 0.00E+00 OOOE+O0.O.OOE+O0 O.OOE+00 0.OOE+00 O.OOE+00 OOOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.39E-05, 2.90E-06 1 .97E-05 i1.28E-08 6.74E-1 1.2.34E&08 3.43E-1-1 1.99E-ýil 0.00 E-'00 0-.00Et0,61 0.OOE+00 0.00E+00 O.OOE+O0 0:00E+00 OOOE+00 0,.OOE+00 0.00E+00 GI-LLI 5A45E-05 7.80E-05 1.93E-05 1.13E-05&2.41 E-05 1'.22E-05 6.12E-05 2.45E-07 9.39E-05 2.29E-09 7.OOE-05 2.29E&06 1.62E-06 3,18E&07 2.58E706 5.1 0E-09 1.74E-06 2:45E1706 2.72E-06 2.12E&06 6076E-.1 1 .24E-06 4.38E&05 1.413E-13 9.i 8E-20-9.82E-05 ,2;42E-06:2.54E-05 5.14E'05 1 .75E-04 4.31 Er05 4.74E-14 3168E&-05 3.22E-05 2.67E-05

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, All others are from Reference 4, Table E-12.Sb-124, Sb-1 25 are from Reference 9, Table 4.NOTE: The tritium dose factor for bone is assumed to be equal to the total. body dose factor. This assumes that tritium will act similarly in all organs (Reference 24).El-152 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 9i of 195 Table 6.4 -INGESTION DOSE FACTORS'-

DF (mrem/pCi ingested) (Page 5 of 8)CHILD Nuclide H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 Ru-1 05 Ru-1 06 bone 2.03E-07 1.21 E-05 5.80E-06 8.25E-04 0.00E+00 0.00E+00 0 "OOE+00 1.15E-05 1.65E-05 0.OOE+00 0.OOE+00 0.OOE+00 5.38E-04 2122E-06 0.OOE+00 1.37E-05 4.38E-08 7.1OE-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.32E-03 1.70E-02 2.40E-05 9.03E-06 4.11E-08 3.82E-1 0 6.02E-07 3.60E-09 1.14E-08 1.16E-07 6.99E-09 2.25E-08 2.17E-1 0 0.00E+00 9.23E-10 1.07E-09 7.31 E-07 6.45E-08 1.17E-05 liver 2.03E-07 2.42E-06 5.80E-06 3.86E-05 0.00E+00 1.07E-05 3.34E-07 6.1OE-06 2.67E-05 4.93E-07 1 .80E-06 5.29E-706 2.88E-05 2.09E-07 2.45E-07 3.65E-05 6.33E-08 1.21 E-06 0,OOE+00 0.OOE+00 0.OOE+00 0OOE+00 6.70E-05 1.90E-07 1.17E-07 0.OOE+00 0:OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0OOE+00 0.OOE+00 0.OOE+00 2.55E-08 1.01E-09 8.76E-09 3.92E-1,1 1.33E-05 1.81E-09 1.12E-09 0.OOE+00 0.OOE+00 0.00E+00 total body 2.03E-07 2.42E-06 5.80E-06 3.18E-05 8.90E-09 2.85E-06 7.54E-08 1.89E-;06 1.33E-05 9.98E-07 5.51 E706 1.56E-05 1.83E-05 1.22E-07 1.48E-07 2.27E-05 5.85E-09 1.43E-07 7.55E-06 1.71 E-07 1.98E-07 9.12E-09 4,12E-05 1.32E-07 1.04E-07 3.77E-05 4.31 E-03 9.06E-07 3.62E-07 1.10E-09 1.39E-11 1.61E-08 1.03E-10 3.13E-10 2.27E-08 5.96E-1 0 6.26E-09 1.83E-1-1 3.29E-06 3.OOE-08 1.42E-08 2.81 E-07 2.34E-08 1.46E-06 thyroid 2.03E-07 2.42E-06 5.80E-06 0.OOE+00 4.94E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0 OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 kidney 2.03E-07 2.42E-ý06 5.80E-06 0.OOE+00 1.35E-09 3.OOE-06 4.04E-07 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.92E-07 2.30E-05 3.84E-08 7.03E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.OOE÷00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.65E-08 1.45E-ý09 8.23E-09 4.35E-1 1 2.84E-05 2.63E-08 1.91 E-08 1.84E-06.5.67E-07 1.58E-05 lung 203E-,07 242E-06 5,80E-06 0.OOE+00 9.02E-09 0.OOE+00 0.OOE+00 3.45E-06 7.74E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0:OOE+00 0'.00E+00 0.00E00 O.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOEO00 9.19E-10 5;92E-1 0 0.OOE+00 0.OOE+00 0.OOE+00 GI-LLI 2.03E:07 2.42E-06 5!80E06.2.28E-05 4.72E-07 8.98E-06 4.84E&05 1.13E-06 2.78E-05 4.04E-06 1.05E-05 2.93E-05'1 .94E-06 2.56E-05-1.15E-05 6.41 .E-06 3199E"06 3.94E-;05 0.00E+00 O.OOE+O0 0.00E+00 0.OOE+00 0*00E÷00 4. 31 E-06 9.32E-09 1 .02E-09 5.1 E-,05 2.29E-04 5.30E-05 1.71 E-04 1:.17E-04 7.48E707 8'02E-05 1.04E-04 1.70E704 2.66E-05 1.53E-04 1.62E-05 1.21.E-05 1.1OE-05 1.03E-06 3.56E-09 1 .89E-05 4.21E-05 1.82E-04 El-153 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 92 of 195 Table 6.4 -INGESTION DOSE FACTORS -DFa-(mrem/pCi ingested) (Page 6 of 8) aj CHILD Nuclide Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-1 29 Te-131m Te-131 Te-132 1-130 1-131'1-132 1-133 1-134 1-135 Cs- 134 Cs- 136 Cs- 137 Cs-1 38 Ba-i 39 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-1 87 Np-239 bone 5.39E-07 1.11E-05 7.16E-06 1 .14E-05 2.89E-05 4.71E-07 4.87E-05 1.34E-07 7.20E-06 8.30E-08 1.01E-05 2.92E-06 1.72E-05 8.00E-07 5.92E-06 4.19E-07 1.75E-06 2.34E-04 2.35E-05 3.27E-04 2.28E-07 4.14E-07 8.31E-05 2.00E-07 8.74E-08 1.01E-08 5.24E-10 3.97E-08 6.99E-09 2.08E-06 3.93E-08 1.29E-10 2.79E-08 4.29E-07 5.25E-09 liver 3.64E-07 1.44E-07 5.52E-08 3.09E-06 7.78E-06 1.27E-07 1,36E-05 3.74E-08 2;49E-06 2.53E-08 4.47E-06 5.90E-06 1-,73E-05 1.47E-06 7.32E-06 7.78E-07 3.15E-06 3.84E-04 6.46E-05 313E-04 3.17E&07 2.21E-10 7.28E-08 1.12E-10 6.29E-1 1 3.53E-09 1.67E-1 0 1.98E-08 3.79E-06 6.52E-07 1.18E-08 3.99E-11 2.26E-08 2.54E-07 3.77E-1 0 total body 2.91E-07 3.89E-06 1.50E-06 1.52E-06 3.43E-06 1.01 E-07 7.56E-06 3.18E-08 2.65E-06 2.47E-08 5.40E-06 3.04E-06 9.83E-06 6.76E-07 2.77E-06 3.58E-07 1.49E-06 8.10E-05 4.18E-05 4.62E-05 2.01 E-07 1.20E-08 4.85E-06 6.51 E-09 4.88E-09 1.19E-09 5.23E- 1I 2.94E-09 5.49E&10 1.11E-07 1.95E-09 6.49E-12 1.75E-09 1.14E-07 2.65E-10 thyroid 0OOE+00 2.45E-08 6.63E-09 3.20E-06 6.91E-06 3.26E-07 1.57E-05 9.56E-08 5.12E-06 6.35E-08 6.51E-06 6.50E-04 5.72E-03 6.82E-05 1.36E-03 1.79E-05 2.79E-04 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 kidney 6.78E-07 0.OOE+00 0.00E+00 0.OOE+00 8.24E-05 1.34E&06 1.43E-04.3.92E-07 2.41 E-05 2.51E-07 4.15E-05 8.82E-06 2.84E-05 2.25E-06 1:.22E-05 1.19E-06 4.83E-06 1.119E-04 3.44E-05 1.02E-04 2.23E-07 1.93E-10 2.37E-08 9.69E-&1 5.09E-11 0.00E+00 0.00E+00 8;68E-09 1.59E-09 3.61E-07 6.39E-09 2.11E-1I 1.24E-08 0.OOE+00 1.09E-09 lung O.OOE+00 6.16E-06 3.99E-06 O.OOE+O0 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+-00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 D'00E+00 0.00E+00 4.27E-05 5.13E-06 3.67E-05 2.40E-08 1.30E-10 4.34E-08 6.58E-10 3.70E-i1 0.OOE+00 O.OOE-00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0:00E+00&GI-LLI 4.33E-05 6.94E&05 1.71E&05 1;.1OE405 2.34E-05 1' 84E-05 5.94E-05 8.34E-06 1.01 E-04 4.36E-07 4.50E3-05 2.76E-06 1'.54E-06 1.73E-06 2.95E-06 5.16E-07 2.40E-06 2.07E-06 2.27E&06 1.96E,-06 1.46E-07 2.39E&05 4.21 E-05 1.14E-07 1.14E-09 9,84E-05 3.31 E-05 2.47E-05 5.55E-05 1.70E-04 4.24E-05 8.59E-08 3;58E-05.3.57E-05 2.79E-05

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, All others are from Reference 4, Table E-13.Sb-124, Sb-125 are from Reference 17, Table 4.NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium will act similarly in all organs (Reference 24);El-154 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page.93 of 195 Table 6.4 -INGESTION DOSE FACTORS -DFa..(mrem/pCi ingested) (Page 7 6f 8)INFANT Nuclide H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97'Mo-99 Tc-99m Tc-101 Ru-1 03 Ru-105 Ru-106 bone 3.08E-07 2.37E-05 1.0V E-05 1 .70E-03 0.OOE+00 0.OOE+00 0.OOE+00 1.39E-05 3.08E-05 0.00E÷00 0.00E400 0.OOE+00 6.34E&-04 4.70E&06 0.00E+00 1;84E-05 9.33E-08 1.50E-06 O.OOE+O0, 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 2.51 E-03 1.85E-02 5.00E-05.1.92E-05 8.69E-08 8.10E7-1:0 1.13E-06 7.65E-09 2.43E-08 2.06E-07 1.48E-08 4.2QE-08 4.59E-10 0.00E+00 2.27E-09 1 48E-06.1'.36E-07 2.41 E-05 liver 3.08E-07 5.06E-06 1.01 E-05 1.OOE-04 0.OOE+00 1.99E-05 8.18E807 8.98E-06.5.38E-05 1 .15E-06 3.60E-06 1.08E-05 3.92E-05 5.32E-07 6.09E-07 6.31E-05 1.68E-07 3.06E-06 0.00E+00 0.00E+00 0.0pE+00 0.00E+00 1.70E-04 4.98E-07 2.86E-07 0.00E400 O.OOE+00 0*OOE+00 O.OOE+O0 0.010E+,00 0.00E+00 0.00E+00 0.0O0E+00 O.OOE+00 5.02E&08 2.54E-09 1.73E-08 9.79E-1 1 3.40E-05 3196E-09, 2.86E-09-0.OOE+00 O0OOE+00 0.00E+00 total body 3.08E-07 5.06E-06 1.01 E-05 6.59E-05 1.41 E-08 4.51 E-06 1.41 E-07 2.40E-'06 2.12E-05 1.87E-06 8.98E1-06 2.55E-05 2.20E-05 2.42E-07 2.82E-07 2.91 E05 1.25E-08 2.79E-07 1 .27E-05 3.63E-07 3.82E-07 1.94E-08 8.40E-05 2.73E-07 1.97E-07 7.20E-05 4.71 E-03 1.81 E-06 7.13E-07 2.33E-09 2.76E-1 1 3.01 E-08 2.15E-10 6.62E-1 0 3.56E-08 1.16E-09 1.00E-08 3.53E-1 1 6.63E-06 5.1OE-08 2.83E-08 4.95E-07 4.58E&08 3.01 E-06 thyroid 3.08E-07 5.06E-06 1.01 E-05 0.OOE+00 9.20E-09 0.OOE+00 0.OOE+/-00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOEt00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00r 0.OOE+00 0.OOE+00 0.OOE+00 U0.E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+,00 0.00E+00ý0.OOE+00 0.OOE+00, 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 6.0EOOEi0 0.OOE+00 o.OoE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 kidney 3.08E-07 5.06E-06 1.01 E-05.;0.00E+00 2.01:E709 4.4.1 E-06 7.03E-07 0.OOE+'00 0.00E÷00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 1 .03E-06 3.06E-05 6.98E-08 1.24E-06 0.00E+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOEO0 0.00E+O0 O.OOE+00 0.00E+00 0.OOE+00 000ooE+00 0.OOE+00 0.OOE+00 5.41 E-08 2.56E-09 1.24E-08 7.65E-1 1 5.08E-05 4.26E&08 3.40E-08 3.08E-06 1.00E-706 2.85E-05 lung 3.08E-07 5.06E-06 1.01 E-05;0.OOE+00 1.79E-08 O.OOE+00 0.OO.E+Q0 4.39E-06 1 .59E-:05 O.OOE+O00 0.00E+00 0.00E+00 0,.OOE+-00' O.OOE+00 0.00E+00 O.OOE+/-ýO0 0.00E+00:;

0.00E+00: O.OOE+0 0.00E+00: 0.00E++/-00 O.OOE+0 0,00E+00 0.OE00EýG 0.00E400, 0.00E+00 0.00E+001 O.OOE+00 0.00E+00 0.00E+00 0.O0E+00 O.OOE+00 0.00E÷00-O.OOEO00 0.00E÷tO0 2;07E-09 1 .56E-'09 0.00E+-00 0.OOE+00 GI-LLI 3. .5.06E-06 1.011E-05:2.30E,05 4.11rE-07 7.31 E,-06 7.43E-05 1,14E-06 2.57E-05 3.92E-06 ,8.97E-06 2.57E;-05 1-95E-06 4.05E-05 1 .25E-05 5;33E-,05 ,1.37E-05 4.24E-05 O.OOE+O0-.OOdE+/-00 O.OOE+00 O.OOE-00 4.35E706.4.85E-07 9J74E-08 5.16E-05 2.31 E-04 5.92E-05 2.07E-04 1 2.70 E-06 8:.10OE-05:

1 A46E-04 1 ,92E-04 2.50 E-05 1:.62E-04 1.46E7-05 3.09E-05 1.12E-05 1' 15E-06 4.86E-07 1,.80E-05 5.41 E-051 1.83E-04 El-155 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 94 of 195 Table 6.4 -INGESTION DOSE FACTORS -DFa-.(mrem/pCi ingested) (Page 8 of 8)INFANT Nuclide Ag-110n Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 1-130 1-131 1-132 1-133 1-134 1-135 Cs- 134 Cs-136 Cs-137 Cs-138 Ba-1 39 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 9.96E-07 2.14E-05 1.23E-05 2.33E-05 5.85E-05 1.OOE-06 1.OOE-04 2.84E-07 1.52E-05 1.76E-07 2.08E-05 6.OOE-06 3:59E-05 1.66E-06 1.25E-05 8.69E-07 3.64E-06 3.77E-04 4.59E-05 5.22E-04 4.81 E-07 8.81 E-07 1.71E-04 4.25E-07 1.84E-07 2.11E-08 1.1OE-09 7.87E-08 1.48E-08 2.98E-06 8.13E-08 2.74E-10 5.53E-08 9.03E-07 1.11E-08 liver 7.27E-07 3.15E-07 1.19E-07 7.79E-06 1.94E-05 3.35E-07 143E-05 9.79E-08 6.,12E-06.

6:50E-08 1.03E-05 1 .32E-05 4.23E-05 3*37E-06 1.82E-05 1:.78E-06 7.24E-06 7.03E-04 1.35E-04 6.11 E-04 7.82E-07 5.84E-1 0 1.71 E-07 2.91 E-10 1.53E-10 8.32E-09 4.04E-1 0 4.80E-08 9.82E-06 1.22E-06 3.04E-08 1.06E-10 5.68E-08 6.28E-07 9.93E-1 0 total body 4.81 E-07 6.63E-06 2.53E-06 3.15E-06 7.08E-06 2.15E-07 1.54E-05 6.63E-08 5.05E-06 4.94E-08 9.61 E-06 5.30E-06 1.86E-05 1.20E-06 5.33E-06 6.33E-07 2.64E-06 7.1OE-05 5.04E-05 4.33E-05 3.79E-07 2.55E-08 8.81 E-06 1.34E-08 9.06E-09 2.14E-09 9.67E-1 1 5.65E-09 1 .12E-09 1.67E-07 4.03E-09 1.38E-1 1 3.48E-09 2.17E-07 5.61 E-1 0 thyroid 0.OOE+00 5.68E-08 1.54E-08 7.84E-06 1.69E-05 8.14E-07 3.84E-05 2.38E-07 1.24E-05 1.57E-07 1.52E-05 1.48E-03 1.39E-02 1.58E-04 3.31 E-03 4.15E-05 6.49E-04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0:00E+00 0.OOE+00 0.OOE+00 kidney 1.04E-06 0.OOE+00 0.00E+00 0.OOE+00 1.44E-04 2.44E-06 2.50E-04 7.07E-07 4.21,E-05 4.50E-07 6.44E'05 1.45E-05 4.94E-05 3.76E-06 2.14E-05 1.99E-06 8.07E-06 1.81E.04 5.38E-05 1.64E-04 3.90E-07 3.51 E-10 4.06E-08 1.75E-1 0 8.81 E-1 1 0.OOE+00 0'OOE+00 1.48E-08 2.86E-09 4.93E-07 1.13E-08 3.84E-1 1 2.19E-08 0.OOE+00 1.98E-09 lung 0.OOE+00 1.34E-05 7.72E-06 0.OOE+00 0:OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE-00 0OOE+-00 0.00E+60 0.OOE+00 O.OOE+00 OOOE00 0.OOE+00 0.OOE+00 0.OOE+00 7.42E-05 1.10E-05 6.64E705 6.09E-08'3.54E-10'1.05E-07 1.77E-10 9.26E-1 1-0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 O.OOE+00 O.OOE+O0 O.OOE+00 0.00E-t00 0,OOE+00 0.OOE+00 GI-LLI ,3.77E-05 6.60E-05 1.64E-05 1. 11E-05 2.36E-05 2.1OE-05-5.97E-05 2.27E-.05 1 .03E-04 7:11E-06 3.81 E-05 2983E-06 1.51 E-06 2;73E-06 3.08E-06 1.'84E-06 2.62E-06 1:91 E-06 2.05E-06 1.91'E-06 1 .25E&06 5.58E&05 4.20E-05 5.19E-06 7.59E-07 9.77E-05 6.86E-05 2.48E-05 5.73E-05 1.71 E-04 4.29E-05 4.93E&06 3.60E-05 3.69E;05 2.87E-05

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125 are from Reference 17, Table4.All others are from Reference 4, Table E-14.NOTE: The tritium dose factor for bone is assumed to be equal to theitotal body dosefactor.

This assumes that tritium will act similarly in all organs (Reference 24).El-156 WBN OFFSITE'DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 95 of 195 Table 6.5 -BIOACCUMULATION FACTORS (B1) FOR FRESHWATER FISH Nuclide H-3 C-1 4 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Bi 9.OE-01 4.6E+03 1.OE+02 1.OE+05 2.0E+02 4.OE+02 4.OE+02 1.0E+02 1.OE+02 5.0E+01 5.OE+01 5.0E+01 1.OE+02 1,OE+02 5:0E'01 2.OE+03 2.OE+03 2.OE+03 4.2E+02 4.2E+02 4.2E+02 4.2E+02 2.OE+03 2.0E+03 2.OE+03 5.6E+01 5.6E+01 5.6E+01 5.6E+01 2.5E+01 2.5E+01 2.5E+01 2.5E+01 2.5E+01 3.3E+00 3.3E+00 3.0E+04 3.OE+04 1.0E+01 Nuclide Tc-99m Tc-101 Ru-1 03 Ru-i 05 Ru-1 06 Ag-110m Sb-124 Sb-125 Sn-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 1-130 1-131 1-132 1-133 1-134 1-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 B.1 .5E+01 1 ýKE+01 1 .OE+'01 1.0E401 1 .OE+01 2.3E+00 1.OE-'00 1.OE+00 3.OE+03 4.OE+02 4.OE-'02 4.OE+02 4.OE+02 4 .OE-'02 4;OE+02 4.OE+02 4.OE+02 4.OE+01 4.OE+01 4.OE-i01 4.OE+01 4.OE+0i 4.0E+01 1 .9E+03 1 .9E+03 1 .9Ei-03 1.9E+03 4.OE+00 4.OE+00 4.OE+00 4.OE+00 2.5E+01 2,5Ei-01 1.OE-'00 1,OE+00 I .OEi-00 2.5Ei-01 2 '5Ei-01 2,5E+'01 1,.2Ei-03 I .OE+01

References:

Bioaccumulation factors for Ag, Sb, and Sn -nuclides are from Reference 16.Bioaccumulation factors for k, Cs-, and Sr- nuclides are from Reference 21, Table 3.2.4.All other nuclides' bioaccumulation factors are from Reference 4, Table A-1.El-157 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 96 of 195 Table,6.6 -EXTERNAL DOSE FACTORS FOR STANDING ONjCONTAMINATED GROUND -DFij (mrem/h per pCi/m 2) (Page 1 of 2)Nuclide H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-91 Sr-92 Y-90 Y-91 m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-i01 Ru-103 Ru-1 05 Total Body 0.0 0.0 2.50E-08 0.0 2.20E-1 0 5.80E-09 1.1OE-08 0.0 8.OOE-09 1.77E-09 7.OOE-09 1.70E-08 0.0 3.70E-09 1.50E-09 4.OOE-09 0.0 5.50E-09 3.18E-08 6.40E-1 1 1.20E-08 0.0 6.30E-10 3.50E-09 1.50E-08 5.60E-1 3 7,IOE-09 9.OOE-09 2.20E-12 3.80E-09 2.40E-1 1 1.60E-09 5.70E-10 5.OOE-09 5.50E-09 5.1 OE-09 8.11 E-09 1.90E-09 9.60E-1 0 2.70E-09 3.60E-09 4.50E-09 Skin 0.0 0.0 2.90E-08 0.0 2.60E-10 6.80E-09 1.30E-08 0.0 9.40E-09 2.21 E-09 8.20E-09 2.OOE-08 0.0 4.30E-09 1.70E-09 4.60E-09 0.0 6.59E-09 3.90E-08 9.30E-11, 1.40E-08 0.0 7.20E-10 4.00E-09 1.80E-08 6.50E-13 8.30E-09 1.OOE-08 2.60E-12 4.40E-09 2.70E-1 1 1.90E-09 7.80E-10 5.80E-09 6.40E-09 6.OOE-09 1.OOE'08 2.20E-09 1.1 IE-09 3.00&E09 4.20E-09 5.1OE-09 E1-158 WBN OFFSITE DOSE CALCULATIONMANUAL Revision 22 0 (ODCM) Page 97 of 195.Table 6.6 -EXTERNAL DOSE FACTORS FOR STANDING ONCONTAMINATED GROUND -DFij (mrem/h per pCi/m 2) (Page 2 of 2)Nuclide Ru-106 Ag-11im Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 1-130 1-131 1-132 1-133 1-134 I-135 Cs7134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 Total Body 1.50E-09 1.80E-08 2.17E-08 5.48E-09 3.50E- 1I 1.10E-12 1.O0E-11 7.70E-1 0 7.10E-10 8.40E-09 2.20E-09 1.70E-09 1.40E&08 2.80E-09 1.70E-08 3.70E&09 1.60E-08 1.20E-08 1.20E-08 1.50E-08 4.20E-09 2.1OE-08 2.40E&09 2.10E-09 4.30E-09 7.90E-09 1.50E-08 1.50E-08 5.50E-10 2.20E-09 3.20E-10 0.0 2.OOE-10 1.OOE-09 3.1 OE-09 9.50E-10 Skin 1.80E-09 2.10E-08 2.57E-08 6.80E-09 4.80E-1 1 1.30E-12 1.10E-11 9.OOE-1 0 8.40E-10 9.90E-09 2.60E-06 2.OOE-09 1.70E-08 3.40E-09 2.OOE-08 4.50E-09 1.90E-08 1.40E-08 1.40E-08 1.70E-08 4.90E-09 2.40E-08 2.70E-09 2,40E-09 4.90E-09 9.OOE-09 1.70E-08 1.80E-08 6.20E-1 0 2.50E-09 3.70E-1 0 0.0 2.30E-1 0 1.20E-09 3.60E-09 1.10E-09

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-1 24 and Sb-1 25 are from Reference 18.All others are from Reference 4, Table E-6.E1-159 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 98 of 195 Figure 6.1 -LIQUID EFFLUENT RELEASE POINTS-r~e~~X~eS$e El-160 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 99 of 195 Figure 6.2 -LIQUID RADWASTE SYSTEM Reactor Building and Auxiliary Building Floor Drains, CVCS Holdup Tanks Tank x3 Zu gpm 1500 gal 07-RE-90-122'11 I Cooling Tower Blowdown E1-161 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 100 of 195 Figure 6.3 -STEAM GENERATOR BLOWDOWNICONDENSATE DEMINERALIZER I I I I I I I I I I I--- mmmmm-----------

M----- M-Steam Generator BwoimS Unit 1 or 2 Tank ACgm L CNdeub matio Dn m lzrS te MY~y: S/G Steam Generator H/X Heat Exchangers SGBD Stm Generator bhdoam I1 Coo~ng Tower 8kbwdowv El-162 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page, 101 of 195, 7.0 -GASEOUS EFFLUENTS INTRODUCTION There are six discharge points for gaseous radioactive effluents from WBN. These dischargepoints are: Unit 1 Condenser Vacuum Exhaust (CVE), Unit 2 CVE, Service Building Exhaust., Auxiliary Building Exhaust, Unit 1 Shield Building Exhaust,-

and Unit 2 Shield Building Exhaust. Detailed descriptions are provided below, and Figure 7.1 provides an outline of these airborne dischargepoints with associated radiation monitors.

None of these discharge points meets the criteria of Regulatory Guide 1.111 for elevated releases; therefore, all releases are considered to be ground-level.

Various plant systems contribute activity to the CVE, the Service Building Exhaust and the Auxiliary Building Exhaust, but these sources are not treated as individual release points. There are two gas systems associated with each Shield Building Exhaust: the Waste Gas Decay Tank (WGDT) System and the System which includes the Incore Instrument Room Purge.The discharge points and the two associated gas systems are each monitored by noble gas radiation monitors.

These monitors perform two main functions:

to identify any unexpected radioactivity releases, and to ensure that the dose rate limits of ODCM Control 1.2.2.1 are met. Each monitor has an alarm/trip setpoint which causes the monitor to alarm if the monitor's setpoint is exceeded.

The;monitors do not have separate alarm and trip setpoints; they have one setpoint which performs.

both functions.

The noble gas radiation monitors for Containment Purge and the WGDT release points initiate an isolation function if the alarm/trip setpointis exceeded.

The radiation monitor alarm/trip setpoints foreach release point and discharge point are based on the radioactive noble gases in the gaseous effluent.

It is not~considered practical to apply instantaneous alarm/trip setpoints for integrating radiation monitors sensitive to radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases.Releases are continuous, except for releases from the WGDT or Containment Purge Systems which are made as batch releases.For batch releases, the WGDT or Containment to be released is grab sampled for radioactivity in accordance with Table 2.2-2. The samples are analyzed to determine the maximum allowable release flow rate to ensure compliance with the dose rate limits of ODCM Control 1.2.2.1 as described in ODCM Section 7.2. The sampling results are also used to determine a setpoint for the associated noble gas radiation monitor for the release. The setpoints are determined in accordance with ODCM Section 7.1.Dose calculations are performed for each release, as outlined in ODCM Sections 7:3 and 7.4, to determine compliance with ODCM Controls 1.2.2.2 and 1.2.2.3.For continuous releases, the pathways are sampled for radioactivity periodically, as required by Table 2.2-2. The samples are analyzed to ensure compliance with the dose and dose rate limits of ODCM Control 1.2.2.1, 1.2.2.2, and 1.2.2.3, as described in ODCM Sections 7.1 and 7.2. The sampling results are also used to determine a setpoint for the associated noble gas radiation ,monitor for the release. The setpoints are determined in accordance with ODCM Section 7.1. Dose calculations are performed for each sampling period, as outlined in ODCM Sections 7.3 and 7.4, to determine compliance with ODCM Controls 1.2.2.2 and 1.2.2.3.Once per month, the projected dose is calculated, as outlined in ODCM Section 7.5,. to determine compliance with ODCM Control 1.2.2.4.El-163 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 102 of 195 All dose calculations performed to determine compliance with ODCM Controls 1.2.2.2 1.2.2,3 and 1.2.2.4 are detailed in ODCM Sections 7.3 and 7.4. The calculational methodologies are based on the guidance provided in NUREG-0133 andRegulatory Guide 1.109. Because all releases aregroundrlevel, semiý-infinite cloud models are used.in the dose calculations.

The quantities of each radionuclide identified and released are input into a more rigorous calculation methodology, described inODCM Section 7.7, to determine the individual and population doses'to be reported to the NRC in the Annual Radioactive Effluent Release Report. These dose. calculation methodologies are based on the guidance provided in Regulatory Guide 1.109.RELEASE/DISCHARGE POINTS DESCRIPTION There are six discharge points at WBN that are monitored for airborne, radioactive effluents.

These are: a CVE for reach unit, ýa Service Building Exhaust, an Auxiliary Building Exhaust and a Shield Building Exhaust for each unit. Each of these discharge points may have oneor more release points associated with it as described below. Figure 7.1 provides a simplified outline of the airborne effluent release and dischargepoints with associated radiation monitor identifications.

Figure 7.2. provides a more detailed description of the release and discharge points, with flow rates, radiation monitors, and associated inputs.Condenser Vacuum Exhaust The CVEs are located in the turbine building.

They exhaust at a maximum design flow rate of 45 cfm per pump. These discharge points are monitored by radiation monitors 1,2-RE-90-119 for normal operation.

Service Buildina Exhaust Areas in .the Service Building in which work is conducted which may produce radioactive effluents all exhaust to.the Service Building Exhaust. This discharge point exhausts at a. maximum design flow rate of approximately 10,000 cfm and is monitored by radiation monitor 0-RE-90-132B.

Auxiliary Buildinaq Exhaust The Auxiliary Building exhausts at a maximum total design flow of.228,000-cfm (2 of 4 ventilation fans and 1 fuel handling fan). This discharge point exhaust is monitored by radiation monitor,0-RE-90-I01B.

The annulus vacuum priming fans (2 fans at 1000 cfm each) exhaust to the auxiliary building fuel handling exhaust header.Shield Building Exhaust There is one Shield Building Exhaust for each unit. These discharge points are monitored by- radiation monitors 1,2-RE-90-400A.

There are nine Waste Gas.Decay Tanks (WGDTs) that discharge into the waste gas header which is released into the Unit 1 Shield Building Vent (see Figure 7.3). The Train A Auxiliary Building Gas TreatmentSystem (ABGTS) is operated during a WGDT release. EachWGDT hasa design capacity of 600 ft 3 and a maximum design release rate of 100 cfm [SOURCE NOTE 17]. The WGDT release point is monitored by radiation monitor 0-RE-90-118.

El-164 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page .1103of 195 The Auxiliary Building Gas Treatment System (ABGTS) draws from theAuxiliar BuidingSecondary Containment Enclosure andexhausts to the Shield Building Exhaust. Any activity-releasedifrom the Auxiliary Building through theABGTS is accounted for as a. part of the Auxiliary.Building Exhaust releases, and will not be tracked separately.

An Auxiliary Building Isolation signal starts'.the ABGTS.The Emergency GasTreatment System:is used to draw a vacuum in the annulus and exhaust to the Shield Building Exhaust under emergency conditions, and coulddo so during normal operation.

Both the Containment Purge and the. Incore Instrument Room-Purge from each unit tie into the Shield Building Exhaust..

The Containment Purge release pointexhausts at a maximum of 28;000 cfrm and is monitored by radiation monitors 1,2-RE&90-130 and 1,27,RE-90-131.

If the Incore Instrument Room Purge is operating exclusively, it~exhausts at 800 cfm, and is monitored by the Containment PurgeMonitors given above. The common header exhausts to the Shield Building Exhaust.7.1 GASEOUS EFFLUENT.MONITOR INSTRUMENT SETPOINTS Airborne effluent noble gas monitor setpoints are determined toensure that the d6se rate at the UNRESTRICTED AREA BOUNDARY does not exceed the dose rate limits given.,in.ODCM Control 1.2.2.1 and to0identify unexpected releases.

ODCM Control 1'.1.2 establishes operabilityi requirements for these .monitors.

Allocation factors (AF) are used in. the setpoint calculation to allocatea fraction of the total body, dose rate limit to, each discharge point. These allocationlfactors may be changed,,as required to support plant operational needs, but shall not exceed asum of one.' Therefore, a particularfmonitor reaching the calculated maximum setpoint as described below-does not necessarily mean thatI thedose rate limit at-the UNRESTRICTED AREA BOUNDARY is being.exceeded; the alarm indicates that:the specific release/discharge point is contributing a greater fraction of the dose rate limit thanwas allocated to the associated monitor and will require further evaluation.

The gaseous effluent radiation monitors and their setpoint information are outlined-below:

Pathway Monitor Default Setpoint Setpoint, Release I__Limit .Setpoint.Containment 1 -RE-90-130 Purge 2-RE-90-130 Section 7.1.1.3 (1) Section 7.1.2 1-RE-90-131 2-RE-90-131 WGDT O-RE-90-1.18 Section 7.1.1.2 Sma Section 7.1 -2 Shield 1 -RE-90-400A Building 2-RE-90-400A Section 7.1.1.3 Smax Section 7.1.2 Exhaust Auxiliary Building 0-RE-90-101B Section 7.1.1.3 Smax Section 7.1.2 Exhaust Service Building 0-RE-90-132B Section 7.1.1.3 Smax Section 7.1.2 Exhaust 1-RE-90-119 CVE 2-RE-90-119 Section 7.1.1.4 Smax Section 7.1.2 (1) Smax orTech Spec value from setpoint and scaling document, whichever is smaller.El-165 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page .104 of'195 7.1.1 Default Monitor Setpoints 7.1.1.1 Section Deleted 7.1.1.2 Waste Gas Decay Tank Effluent Monitor (0-RE-90-118)

During periods of release, the methodology in Section 7.1.2 will be usedto determine-the monitor setpoint and may be set at a default value. Site procedures will document and control this value.7.1.1.3 Shield Building Exhaust (1,2-RE-90-400A), AuxiliaryBuildingExhaust(0-RE-90-101 B), Containment Purge Effluent Monitors (1 ,2RE-90-130:,-131), and Service Building Exhaust (0-RE-90-132B)

These discharge point effluent monitors are set to ensure compliance with ODCM Control 1.2.2.1.The default setpoints aredetermined by calculating the maximum calculated setpoint described by Equation 7.3 using Xe-1 33 monitor efficiencies, design flow rates, and setting the ýratio DRuim/DR equal to 1.0. The default setppints.for the shield building monitors are calculated in units of gCi/s. The default setpoints will be defined in plant procedures.

7.1.1.4 Condenser Vacuum Exhaust Vent (1,2-RE-90-119)

This discharge point effluent monitor is set to ensure compliance with ODCM Control 1.2.2.1 and to identify the presence of primary to secondary leakage of radioactivity.

The default setpoint is determined in one of two ways: by calculating the maximum calculated Setpoiht as described in Section 7.1 .1.3, and then taking a percentage of this value as the setpoint; or by defining the setpointas two times thenormal background.

The default setpoint will be defined in plant instructions.

Once a primary to'secondary leak is identified, the setpoint on this monitor may be incrementally adjusted upward as defined in plant procedures to enable it to be used to identify any further increases in the leak rate.7.1.2 Release Permit Monitor Setpoint Determination For each release, two setpoints are calculated for the monitor: one based on the expected response of the monitor to the radioactivity in the effluent stream (described in Sections.71

2.1and 7
1.22) Which allows for the identification of any release of radioactivity above the expected amount; and a calculated maximum setpoint which corresponds to the most restrictive dose rate limit given in ODCM Control 1.2.2.1 (described in Section 7.1.2.3) which ensures that the release will be stopped if it exceeds the dose rate limits after dilution.

A comparison is then made (as described in Section 7.1:2.4) between these two calculated setpoints and the default setpoints (described in Section 7.1.1) to determine which is used for the release.E1-166 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 105, of 195 7.1.2.1Expected Monitor Response The expected monitor response, ER, is determined using the following-equation:

ER = BKG + EE C 1 (7.1)where: BKG = monitor background, cpm.Ei =efficiency factor for the monitor for nuclide i, cpm per gCi/cc. This term may also be referred to as a response or calibration

  • factor.Ci = measured concentration of nuclide i, gCi/cc.7.1.2.2 Expected Response Setpoint An expected response setpoint'SER is calculated for the monitor for each release: SER = XXZEiCi+X BKG (7.2)i where: X = administrative factors designed to account for expected variations, in monitor response and background.(as defined in plant procedures).

The ranges of values are:1 < X 2.0.[SOURCE'NOTE 15]7.1.2.3 Calculated Maximum Setpoint The calculated maximum setpoint, Smax in cpm, corresponding to thel dose rate limit is determined using the following equation: Smax = AF VCF SF[-D-LmER-BKG)

+BKG (7.3)LLDR (EjJBG]ý+K where: AF = dose rate allocation factor for the release point, dimensionless.

The sum of all dose rate allocation factors must be < 1. The dose rate~allocation factors for release points are'defined in approved plant procedures.

VCF = Vacuum correctionfactor applied'to noble gas monitors whose detector operates at a negative pressure.

This factor willbe defined in plant procedures for applicable monitors-and will Ihave a range of: 0 <VCF_ 1.0. [SOURCE NOTE 2]SF = safety factor for-the monitor, dimensionless.

Safety factors willbe <1. Safety factors-for each monitor are defined in approved plant procedures-.

DRLim= the dose~ratelimit, mrem/y.= 500 mrem/y to the total body for noble gases,= 3000 mrem/y to the skin for:noble gases, and DR = the calculated dose rate for the release, mrem/y.= DRTB for total body:(as described in Section 7.2.1),= DRs for skin (as described in Section 7.2.2), and ER = expected monitor response (as calculated in Equation 7.1),. cpm.BKG = the monitor background, cpm.EI-167 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22'0 (ODCM) Page 106o,0f195 7.1.2.4 Setpoint Determination When release permits are generated, the expected response and maximuncalculated setpoints:

are determined as described, in Equations 7.2 and 7.3. A comparison is-made between these:two calculated setpo ints and the default setpoint as described below to choosethe appropriate setpoint for the monitor during the release (after the release, the monitor is normally returned tothe default setpoint).

1.IF SER < Sa< Smax 2. IF SER < Smax < Sdefault 3. IF Sdefault < SER < S'Sa 4. IF SER -> Smax Reported = Sd,%ujt Reported = SER Reported = SER= (for Containment Purge-monitors)

Reported = Smax E1-168 WBN OFFSITE DOSE CALCULATIONMANUAL Revision-22 0 (ODCM) Page 107 of 195 7.2 GASEOUS EFFLUENTS

-DOSE RATES Dose rates are calculated for total body and skin due to submersion within a cloud of noblegases using a semi-infinite cloud model as described in NUREG-0133.

The dose rates are compared to their. respective limits and are used in the determination of setpoints for noble gas radiation monitors.7.2.1 Total Body Dose Rate The calculated total body dose rate must meet the condition (from NUREG-0133 Section 5.2.1): f( +DFB ] 500 mrem/y Since there are no elevated release points at WBN, the elevated release terms in the equation (Vi and Qis) are not used. Substituting the flow (f) multiplied by the concentration, (C) for therelease rate (Q) in the above equation, the dose rate to the total body, DRTB in mrem/y, is calculated using the following equation: DRTB = -f Y_ Ci DFBi (7.4)where: x/Q= terrain adjusted relative concentration, s/m 3.Relative air concentrations are calculated for the unrestricted area boundary in each of the 16 sectors as described in Section 7:9.2 using the historical meteorological data for the period 1986-2005 given in Table 7.2. For dose rate calculations, the highest value from the 16 unrestricted area boundary locations, is'used. The values for each of the sixteen sectors are given in Table 7.3 (maximum values are highlighted on the table).f = flowrate of effluent stream, cc/s.Ci = concentration of noble gas nuclide i in effluent stream, gCi/cc.DFBi = total body dose factor due to gamma radiation for noble gas nuclide i, mrem/y per gCi/m 3 (Table 7.4).The totalbody dose rate is calculated for each release. It is compared to the limit of 500 mrem/y and is also used in the determination of the radiation monitor setpoint as described in Section 7.1.2.El-169 WBN OFFSITE DOSE CALCUILATION MANUAL Revision 22 0 (ODCM) Page08 ofl195 7.2.2 Skin Dose Rate The calculated skin dose rate must meet the condition (from NUREG-0133Section 5.2.1): x {[[FSi/s( +1]1 BiiQ sl+/-[DFSi +1.1 DFý] [L, QivJ} < 3000 mrem/Y Since there are no elevated release points at WBN, the stack terms in the equation; DFSi; (x/Q)s, Bi, and Qis, are not used. Substituting:the flow (f) multiplied by the concentration'(C)for the release rate, (Q) in the above equation, the dose rate to the skin, DRs in mrem/y, is calculated using the following equation: DR = f YCi (Ol~i +l1.11 DFý) (7.5)where: X/Q = terrain adjusted relative.

concentration, s/m 3.Relative air-concentrations are calculated for the unrestricted area boundary in. each of the 16 sectors as'descdbed in Section 7.9.2fusing the historical meteorological data for the period 1986-2005 given in Table'7.2.

For dosestrate calculations,:the highest valuefrom the 16 unrestricted.area boundary locations is used. The values for:each of the:sixteen sectors are given inTable 7.3 (maximum values are highlighted on the table).f = flowrate.

of effluent-stream, cc/s.Ci = concentration of noble ýgas nuclide i in effluent stream, ttCi/cc.DFsi = skin dose factor. due to-beta: radiation for noble gas nuclide i, mrem/y per gCi/m 3 (Table ý7.4).1.11 = the average.ratio of tissue to air energy absorption coefficients, mrem/mrad.

DFgi = dose conversion factor for external gamma for noble gas nuclide i, mrad/y per iiCi/m 3 (Table 7.4).The skin dose rate is calculated for each release. It is compared to the limit of 3000 mrem/y and is also used in the determination of the radiation monitor setpoint as described in Section 7.1.2.El-170 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page4 109 of 195 7.2.3 1-131, 1-133, Tritium and All Radionuclides in Particulate Formwith Half-Lives of Greater Than 8 Days -Organ Dose Rate Organ-dose rates due to 1-131, 1-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days; DRj in. mrem/y, are calculated for all age groups (adlIt, teen,: Child, and I nfant) and all organs,(bone, liver, total body, thyroid, kidney, lung, and GI Tract). The calculated organ'dose rate must meet the conditiOn (from NUREG-01 33 Section 5.2. 1): Pi(WQ, + WvQj,) <1500 mrem /.y Since there are no elevatedrelease points at WBN, the elevated release terms (Wsand Qs) are not used.Substituting.the flow (f) multiplied by the concentration (C) for the release rate (Q) in the aboveequation, and inserting the appropriate dispersion factor (X/Q or D/Q) for each pathway considered, the organ dose rate, DRj in mrem/y, is calculated, using the following equation: DR 1 = f{CT -X.(RIT +RCTP) +YC -C[.R 1 i +2-(RCp 1 +RG1)]} (7.6)where: f = flowrate of effluent stream, cc/s.CT = concentration of tritium in effluent stream, gCi/cc.X/Q = terrain adjusted relative concentration, s/m 3.Relative air concentrations are calculated for the unrestricted area boundary in each of the 16 sectors as described in Section 7.9.2 uSing the historical meteorological data for the period 1986-2005 given:in Table_7.2.

For dose rate calculations, the highest valuefrom the 16 unrestricted, area boundary locations is used. The values for each ofthe sixteen sectors are given in Table 7.3 (maximum values are highlighted on the table).= (X/Q) for the inhalation and. tritium ingestion pathways, RIT = inhalation dose factor for tritium, mrem/y per gCi/m 3.Dose factor is calculated as described in Section 7.8.13.RCTP = Grass-cow-milk dose factor for tritium, mrem/y per gCi/m 3.Dose factor is calculated as described ih Section 7.8.7.Ci = concentration of nuclide i in effluent stream, gCi/cc.Rli = inhalation dosefactor for each identified nuclide i, mrem/y per gCi/m 3.Dose factorsare calculatedas described in Section 7.8.13.D/Q = terrain adjusted relative deposition, 1/m 2.Relative deposition is calculatedfor the unrestricted area boundaryin-each of the 16'sectors as described%

in Section 7.9.30 using the historical meteorological data for the period 1986-2005 given in Table 7.2. For dose rate calculaiions, the highest-value from the 16 unrestricted area boundarylocations is used. The of the sixteen sectors are given in Table 7.3 (maximum values are highlighted on the table).Rcpi = Grass-cow-milk dose~factor for each identified nuclide i, m 2-mrem/y per pCi/s. Dose factors are calculated as described in Section 7.8.1.a~i = ground plane dose factor for each identified nuclide i, m 2-mrem/y per Ici/s. Dose factors are calculated as described in Section 7.8.14.The maximum organ. doserate is selected from among the doserates calculated for all the organs and all age groups. It is comparedto the limit of 1500 mrem/y.El-171 WBN OFFSITE DOSE CALCULATION MANUAL Revision:'22 0 (ODCM) Page 110 of 195 7.3 DOSE -NOBLE GASES Doses are calculated for gamma and beta air doses due to exposure to a semi-infinite cloud of noble gases. These doses will be calculated at the unrestricted area boundary locationwith the highest terrain adjusted annual-averagepX/Q based on 1974-1993 meteorological data (Table 7.2-). This location is chosen from the UNRESTRICTED AREA BOUNDARY locations listed in Table 7.1. Dispersion factors are calculated using the methodology described in Section 7.9.2.No credit is taken for radioactive decay.7.3.1 Gamma'Dose to Air NUREG-0133 Section 5.3.1 provides the following equation for the calculation of the gamma air dose from noble gases: k ~[M~~.Q 1 , + (qjv+ BQS ý~Because there are no elevated release points, the terms subscripted s inthe equation are not used.Since all releasesare considered to be long-term, the terms using lower case variables

ýare not used.,Since WBN will be calculating a dose for each release made, the total release (Q) in the above equation is replaced by the release rate (Q) multiplied by the length of the release (T). The gamma air dose, Dg in mrad, is calculated for each release using the following equation: D 7 = 1.9E-06 DF 1 T (7.7)where: 1.9E-06= conversion factor, y/min.X/Q = highest terrain adjusted unrestricted area boundary annual-average relative concentration, s/m 3 (from Table 7.3).Qi -- release rate for nuclide i, RCi/s.DFgi = dose conversion factor for external gamma for nuclide i (Table 7.4), mrad/y per gCi/m 3.T = duration of release, min.The gamma air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 7.3.3.El-172 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) PageA 111,o'f 195 7.3.2 Beta Dose to Air NUREG-0133 Section 5.3.1 provides the following equation for the calculation of'the ýbeta air dose from noble gases: D = k Y{Ni[(.ýX Qi 1,ci] (Eý j + (*J 1-]}Because there are no elevated release points, the terms subscripted s in,.the equation are: notused.Since all releases are considered to be long-term, the terms using lower. case va iables are not used.Since WBN will be calculating a:dose for each release made, the-totai release (Q) in, the above equation is replaced, byvthe release rate (Q) multiplied by the.length of the release (T).' The beta air dose, Db in mrad, is calculated for each release using the following equation: Do =1.9E

-_ Qj DFIi T (7.8)where: 1.9E-06= conversion factor ,y/Tin.X/Q = highest terrrain adjusted unrestricted area boundary annual-average relative concentration, s/i 3.(from Table 7.3).Qi = release rate for nuclide i, gCi/s.DFbi = dose conversion factor for external beta for nuclide i, mrad/y per iCi/m 3 t(from, Table 7.4).T = duration of releasej mrin, The beta air dose calculated

by this method will be used in the cumulative dose calculations discussed in Section 7.3.3.7.3.3 Cumulative Dose -Noble Gas Quarterlyand annual sums of all doses are calculated for each release as described:

below to.compare to the limits listed in ODCM Control 1.2.2.2.For noble gases, cumulative doses are calculated for gamma and beta air doses. Doses due to each release are summed with the doses for all previous releases in the current quarter or year to obtain cumulative quarterly and annual doses.7.3.4 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits in accordance with Surveillance Requirement 2.2.2.2. to determine compliance.

El-173 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 112 of:195 7.4 DOSE DUE TO 1-131, 1-133, TRITIUM AND ALL RADIONUCLIDESIN PARTICULATE FORM WITH HALF-LIVES OF GREATER THAN 8 DAYS 7.4.1 Organ Dose Calculation Organ dosesdue to 1-131, 1-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days are calculated for each release for the critical receptor.

Thecritical.receptor is. defined as the unrestricted area boundary in thesector with the highest annual average terrain adjustedXIQ., The annual average.X/Q and D/Q are calculated using the methodOlogy in'Sections 7.9.2 and 7.9.3 using the historical.

1986-2005 meteorological data (Table 7.2). A conservativeassumption is usedto select the dispersion factorstfor the critical receptor.

The highest calculated X/Qand D/Q valuesare chosen from Table 7.1 values after being.multiplied by the applicable terrain adjustment.factors (from and may not be for the same compass sector. Pathways considered to exist at this locatio. are1 inhalation, ground plane exposure,;grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafyr-and stored vegetable ingestion.

All agegroups are considered (adult, teen, child andinfant).

Dose factors4for these age groups andpathways:are; calculated as described in Section 7.8. For the groundexposure'.

pathway, which has no-age or organ specific dose factors, the total body dose will.be added to~theinternalorgan doses for all age groups. No.creditis taken for radioactive decay.NUREG-0133 Section 5.3.1 provides the following equation for the calculation of-the:organ dose~from radioiodines, radioactivematerials in particulate form with half-lives greater than 8 days: D = k Y Ri(WsQis +wsqis + WvQiý + wvq 1 v)i Because there are no elevated release points, the terms subscripted s:inFthe equation are not used.Since all~releases are considered to be long-term, the terms using, lwer 16ase variables are not used.Since WBNwill becalculating a dosefor each release made, the total ,release (Q) in the aboveequation is replaced by the.release rate (Q) times the length of the release (T). 'The general equation for the calculation of organ dose is: D= 3.17E-08 T _. R_.(WQi) (7.9)i P where: 3.17E-08 = conversion factor, y/s T = duration of release, s.Rpi = dose factor for pathway P for each identified nuclide i, m 2-mrem/y-per laCi/s for ground plane, grass-milk animal-milk, grass-cow-beef, and vegetationrpathways, and mrem/y per gCi/m 3 for inhalation and'tritium ingestion pathways.

Equations for calculating these dose'factors are given in Section 7.8.Wp = dispersion factor for the location and pathway P (from Table 7.3),= terrain adjusted x/Q for the inhalation and tritium ingestion pathways,= terrain adjusted D/Q for the food and ground plane pathways, Qi = release rate for radionuclide i, plCi/s.El-174 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 113 of 195 From the four age groups considered, the maximum is determined by comparing all organ doses for all agegroups.

The age groupwith the highest single organ dose is selectedasthecritical age group. The organ doses for the critical age group will be used in the cumulative doses discussed in Section 7.4.2.7.4.2 Cumulative Organ Doses Quarterly and annual sums of all doses are calculated for each release as described below to compare to the limits listed in ODCM Control 1.2.2.3.For maximum organ dose, cumulative quarterly and annual doses are maintained for each of the:eight organs considered.

The cumulative dose is obtained by summing the doses for each organ of the critical age group.(as calculated in Section 7.4.1) as determined for each release with the organ dosesfor all previous releases in the quarter or year to obtain the cumulative quarterly and annual doses. Thus, the cumulative organ doses will be conservative values, consisting of d0ses.belonging to vadous age groups depending on the mix of radionuclides.

The highest of these cumulative organ doses is usedfor rthe comparison to the limits described in ODCM Control 1.2.2.3.7.4.3 Comparison to Limits The cumulative calendar quarter and calendar year doses are compared to their respective limits in accordance with ODCM Surveillance Requirement 2.2.2.3 to determine compliance.

7.5 DOSE PROJECTIONS In accordance with ODCM Surveillance.

Requirement 2.2.2.4.1, dose projections will be performed.

This will be done for the gamma dose, the beta dose and the maximum organ dose.D={(ad) x3} +c (7.10)where: D = the 31-day dose projection, mrem.a = the cumulative dose for the quarter, mrem.b = the projected dose for this release (as calculated in Sections 7.4.1, 7.4.2 and 7.4.3), mrem.c = any anticipated.additional dose in the next month from other sources, mrem.d = current number of days into the quarter up to the time of the release under consideration.

The 31-day projected dose-will be compared to the limits given in ODCM Control 1.2.2.4 in accordance with Surveillance Requirement 2.2.2.4.1 to determine compliance.

7.6 GASEOUS

RADWASTE TREATMENT SYSTEM DESCRIPTION The GASEOUS RADWASTE TREATMENT SYSTEM (GRTS) described in the WBN FSAR shall be maintained and operated to keep releases ALARA. A simplified flow diagram for the GRTS is given in Figure 7.3.El-175 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 114!of 195 7.7 DOSE CALCULATIONSFOR REPORTING A complete dose: analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in ODCM Administrative Control15.2.

All 'real pathways and receptor locations identified by the most recent land use survey are considered., In.addition, actual meteOrological data representative of a ground level release for each corresponding

!calendar quaiter will be used. For iodine, releasesitf is assumed thathalf the iodine released is in organicpform.

Organic iodine6causes a dose only by inhalation.

For cow-milk and beef ingestion doses, thefradction of0the time the animals are on stored feed (identified in the survey) is used in the calculation.'

7.7.1 Noble

Gas- Gamma and Beta Air Dose Regulatory Guide 11.109 Equation B-5 provides the following equation for the calculation of.gamma and beta airdoses from noble gas releases: D = , (DFý or 1) (7.11)where: cim = concentration of nuclide i at location m, gCi/m 3.. Air concentrations are calculated as described by Equation 7:33.DFgi = dose conversion factor for external gamma for nuclide i, .mrad/y per jI/Cim 3 (Table 7.4).DFbi = doseconversion factor for external beta for nuclide i, mrad/y per gCi/m 3.(Table7.4).

7.7.2 Noble

Gat- Air Submersion Dose Regulatory Guide 1.109 Equation B-8 provides the following equation for the calculation of the total body submersion dose from noble gas releases: D = SF Y_ Xim DFBI (7.12)i where: SF = shielding factor. This factor is conservatively set equal to,1.0.cim = concentr'ation of nuclide] at location m, jiCi/m 3.Air concentrations are calculated as described by Equation 7.33.DFBi = total body dose conversion factor due to submersion in a semi-infinite cloud of noble gases for nuclide i, mrem/y per.jCi/m 3 (Table 7.4).Regulatory Guide 1.109 Equation B-9 provides the following equation'for the calculation of the skin submersion dose from noble gas releases: D= {1.11 1SF y_ Xim DF +Y Xim DFSj (7.13)where: 1.11 =the average ratio of tissue to air energy absorption coefficients, mrem/mrad.

SF = shielding:

factor. This factor is conservatively set equal to 1.0.cim = concentration of nuclide i at location M, gCi/m 3.Air concentrations are calculated as described by:Equation 7.33.DF = dose conversion factor for external gamma for nuclide i, mrad/y per jCi/rj 3 (Table 7.4),.DFi = skin dose conversion factordue to submersion in a semi-irnfinite dclud of nbble gases-for nuclide i, .mrem/y per ýtCi/m 3 (Table 7.4).El-176 WBN OFFSITE DOSE CALCULATION MANUAL Revision22 0 (ODCM) Page 115 of 195 7.7.3 Radioiodine, Particulate, and Tritium -Maximum Organ Dose Regulatory Guide. 1.109 Equations C-12, -13, and -14 provides the following equation'for the-calculation of doses from the release of iodine and particulate radionuclides:

D = SF CCGiRGi (for ground contamination)

D = BR 0 X ;Rpi (for inhalation)

DR= PJRUvafgCjv

+Uma Cim +UFa CFi +ULaFL CL ) (for ingestion) i These three equations are combined into one equation for this presentation by dropping the subscripts on the dose factors, and substitutingthe appropriate dispersion factor.(D/Q or X/Q) multiplied by the total release (Q) for the concentration terms (C) as follows:_oQ.p+S Q,R% DZ Q i +o~vo+BRa -QiRp + QRGi +/-R 1 Q (Ufg +Uma +UFa +ULa f i i i The shielding factor:(SF) is conservatively set equal to 1.0, .therefore, that, term drops out of the equation.The vegetable fractions

.(f),. ingestion rates (U) and breathing rate (BR) are includ6dJin the ;calculation of the dose factors,.

given in ODCM Sections 7.8.1 through 7.8.14, therefore,.they mayalso be dropped from this equation.

The equation then becomes: D = JAQi R 1 i +.LQi RGi Rp 1 i i P Since the calculation of tritium concentration in vegetation is based on air concentration rather than ground' deposition (Equation C-9 in Regulatory Guide 1.109), a separate term is added to~the equation to account'for the tritium ingestion dose pathways.

In addition, a terrain adjustmentfactor (TAF) is added.Therefore the equation for calculating the organ dose, Dj in mrem, is: D= 3.17 E-O8{( XTAF). RPTQT + [(0)(TAF)z R, + (L,)(TAF )RG, +( )(TAF )RQ , } (7.14)where: 3.17E-08 = conversion factor, .y/s.D/Q = Relative deposition for location under consideration, m-2.Relative deposition .is calculated as described in Equation 7.35.RPT = ingestion dose factor for pathway P for tritium, m 2-mrem/yper gCi/s. Ingestiont.pathways available for consideration are the same as those listed abovefor Rpi. Equations for calculating ingestion dose factors for tritium are given in :Sections 7.8;7 through 7.8:12.QT = adjusted release rate for tritium for location under consideration, IaCi/s. The. initial release rate:is adjusted to account for. decay between the release pointand the location, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted.

release rate is equal-to the actual release rate decayed for an average travel time during the period.9 QT =-: QT1, _ fk exp(-X , -k (7.15)k=l where: QT, = initial average release rate for tritium over the period, tCi/s.fk = joint relative frequency of occurrence of winds in windspeed class k blowing toward this exposure point, expressed as a fraction.Ii = radiologicaldecay constant for nuclide i, s-1.x = downwind-distance,.m.

Uk = midpoint value of wind speed class interval k, m/s.El-177 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 116 of 195 Rpi = ingestion dose factor for pathway P for each identified nuclidei (except tritium), m 2-mrem/y per pCi/s. Ingestion.pathways available for consideration include: pasture grass-milk animal-milk ingestion

-Rcp (see Section 7.8.1).stored feed-milk animal-milk ingestion

-Rcs (see Section 7.8:2).pasture grass-beef ingestion

-RMp (see Section 7.8.3).stored feed-beef ingestion

-RMS (see Section 7.8.4).fresh leafy vegetable ingestion

-RVF (see Section 7.8.5).stored vegetable ingestion

-Rvs (see Section 7.8.6).RGi = Dose factor for standing on contaminated ground, m 2-mrem/y per ICi/s. The equation for calculating theground plane dose factor is given in Section 7.8.14.X/Q = Relative concentration for location under consideration, s/m 3.Relativeconcentrations are-calculated as described by Equation 7.34.Rli = Inhalation dose factor, mrem/y per gCi/m 3.The equation for calculating the inhalation dose factor is given in Section 7.8.13.Qi = adjusted release rate for nuclide i for location under consideration, gCi/s. Calculated in the same manner as QT above.The highest organ dose for a real receptor is determined by summing thedose contributionfrorm all identified pathways for each receptor including ground contamination, inhalation,, vegetable ingestion: (for identified garden locations), cow and/or goat milk ingestion (if a cow or goat is identifiedifor the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all receptors).

7.7.4 Population

Doses The population dose is determined using Equation D-1 from Regulatory Guide 1.109: D = k Y POPm Y. Daij FPma m For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements.

These elements are defined in Table 7T5. Dispersion factors;are calculated for the midpoint of each sector element (see Table 7.5). For each of these sector elements, an iaverage dose is calculated, and'then multiplied by the population in that sector element. The average dose is determined by multiplying the maximum individual dose for the sector by the ratio of the: average tothe maximum usage rates. For population doses resulting from~ingestion,.itis conservatively assumed that all foodeaten by the average individual is grown within the sector element. The-general equation used for calculating the population dose in a given sector element is: Dosepop = 0.001 ERATIOp POPm FPa DOSEp P where: 0.001 = conversion from mrem to rem.RATIOp = ratio of average to maximum dose for pathway P. Maximum ingestion rates are given in Table 6.3. (Average ingestion rates are obtained from Reference 4, Table E-4.)= 0.5 for submersion and ground exposure pathways, a shielding/occupancy factor..= 1.0 for.the inhalation pathway.= 0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult,: respectively. (Itis assumed that the-ratio of average to maximum infant milk ingestion rates is:the same as that for child.)= 1.0, 0.90, 0.91, 0.86for beef ingestion, for infant, child, teen and adult, respectively.

= 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, child, teen and'adult, respectively. (It is assumed that the average individual eats no fresh leafy vegetables, only stored vegetables.)

POPm = the population of the sector element m, persons (Table 7.6).FPa = fraction of the population belonging to each age group.El-178 WBN OFFS!TE DOSE CALCULATIONMANUAL Revision22 0 (ODCM) Page 117 of 195= 0.015, 0.168, 0.153, 0.665 for infant, child, teen and adult, respectively (fractions taken from Reference 21, Table,3.39).

DOSEp = the dose for.pathway P to.the maximum individual at the location underconsideration,tmrem (as described in:Sections 7.7.1, 7.7.2, and 7*7.3). For ingestion pathways, this dose is-multiplied, by an average decay correction to account for decay as thefood is moved through the food distribution cycle. This average decay correction; ADC, is defined as follows: For milk and vegetables:

ADC = exp(-,itd)

(7.17)For beef: ADC = exp(-Xitd)

Xitcb (7.18)1- exp(-XitCb) where: i= decay constant for nuclide i, s1.td = distribution time for food product under consideration (values from Reference 4, Table D-1).= 1 -21 E+06 s (14 d) for vegetables.

= 3.46E+05 s (4 d) for milk.= 7d for beef tcb = time to consume a whole beef, as described in Section 7.8.3.For beef ingestion, the additional .factors in the calculation of ADC negate the integration of the dose term over the period during Which a whole beef is consumed, for the calculationof population dose. Inother words, this assumes that the maximum individual freezes and eats a whole beef, while the-average individual buys smaller portions.at.a time.Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.

7.7.5 Reporting

of Doses The calculated quarterly doses and calculated population doses described inSection,7.7 are reported in the Annual Radioactive Effluent Release Report as required by ODCM Administrative Control 5.2.El-179 WBN OFFSITE DOSE CALCULATION"MANUAL Revision 22 10 (ODCM) Page 118 of!195 7.7.6 Dose to a MEMBEROF THE PUBLIC Inside the CONTROLLED or RESTRICTED AREA The Basis for ODCM Control 1.2.2.1 states that for MEMBERS OF THEPUBLIC who may at times be within the CONTROLLED or RESTRICTED AREA, the occupancy factor of thatMEMBER OF THE PUBLIC will usually be sufficiently low to compensate for anyincrease in the atmospheric dispersion factor above that for the unrestricted area boundary.

This basis also states that examples:of calculations for such MEMBERS'OF THE PUBLIC will be given in the ODCM.Calculations are presented in Section 12.4 of the WBN UFSAR which estimate the annual doses-at the boundary of the restricted area (WBN UFSAR Table 12.4-2)ý The total dose rate is'thesufriof the adult whole body inhalation dose~rate, the gamma dose ratefrom the plume and:ground contamination, and the gamma dose rate from outdoor storage tanks. As indicated in the UFSAR, the highest total dose, rate at the boundary of the restricted area is 105 mremly, based on a continuous 2000.h/y Occupancy.

Use of a more realistic occupancy, reflective of the transient traffic expected for this location, would result in a much lower dose estimate.

It is, therefore, considered highly unlikelythat a member of the public would receive greater than 100'mrem/y at Orbeyond the restricted:area boundary.In addition to this calculation, .the dose to these MEMBERS OF THE PUBLIC (obtained'from dosimeters deployed at the Restricted:

Area Boundaryand from estimates of the dose from gaseous effluents) will' be reviewed on' an annual basis to ensure that the actual exposure to any indi viduals is less'.than-i00 mrem/y for these locations.

The results of this review will be included 'in'the Annual' Radiological Effluent Report pursuant to ODCM Administrative Control 5.2.El-180 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 119 of 195 7.8 GASEOUS RELEASES -DOSE FACTORS 7.8.1 Pasture Grass-Cow/Goat-Milk Ingestion Dose Factors -Rcpi (m 2-mrem/y per !iCi/s)The general dose equation stated in Regulatory Guide 1.109 for calculating the~annual dose from consuming foods containing atmospherically released radionuclides (Equation CA13) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C)For the milk pathway, Regulatory Guide 1.109 Equations C-5 and C-10 are inserted into the above equation to yield the following:

jr[1- exp(-?LEte)j Bj,[ -exp(-Xtb)]

D= DFL Uap Fmi Qf exp(-ktfm) di exp(-Xth)r 1 YVXE exp(-Eteh)

Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.14) containmthe yariableý di (equal to the product of the release rate (Q) and the deposition factor (D/Q)); the factors.remaining inI.the above equation are defined as the dose factor. For pasture grass, the variable this defined as zero in Regulatory Guide 1.109, therefore that exponential term drops out of the equation.

The resulting dose factor equation is: RCpj = 106 DFLiaj Uap Fmi Qf exp(-XitfM) fp {[i -x(-ep)] + vi,[I -ePb)]} (7.19)YPkE 4- PLi J(.9 where: 106 = conversion factor, pCi/gCi.DFLiaj = ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table 6.4).Uap = milk ingestion rate.for age group a, L/y.Fmi = transfer factor for nuclide i from animal's feed to milk, d/L(Table6.2).

Qf = animal's consumptionmrate, kg/d.li = decay constant for nuclide i, s-1 (Table 6.2).tfm = transport time from milking to receptor, s.fp = fraction of time animal spends on pasture, dimensionless.

r = fraction of activity retained on pasture grass, dimensionless.

IE = the effective decay constant, due to radioactive decay and weathering, s-1.= li + 1w.Iw = weathering decay-constant for leaf and plant surfaces, s-1 top = time pasture is exposed to deposition, s.Yp = agricultural productivity by unit area of pasture grass, kg/m 2.Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wetweight of vegetation) per pCi/kg (dry soil). (Table 6.2)tb = time period over which accumulation on the ground is evaluated, s.P = effective surface density of soil, kg/m 2.NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.E1-181 WBN OFFSITE DOSE CALCULATION MANUAL Revision.22 0 (ODCM) Page 120of 195 7.8.2 Stored Feed-Cow/Goat-Milk Ingestion Dose Factors -Rcsi (m 2-mrem/y per gCi/s)The general dose equation stated in Regulatory Guide 1.109 for calculatingthe annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration in: Media(C)For the milk pathway, Regulatory Guide 1.109 Equations C-5 and C-10 are inserted into.the above equation to yield the following:

Dr [1 -exp(-XEte)]

Biv [1 -exp(-Xtb)]

1 D = DFL Uap Fm QF exp(-'tfm) di YVXE + p exp(-Xth)Sincethe dose equation inSections 7.4 and 7.7.3 (Equations 7.9 and 7.14) contain the variable di:(equal to the product.of the release rate.(Q) and the deposition factor (D/Q)), the factors remaining in the above equation aredefined as the dose factor. For stored feed, it is assumed that the milk animalsmwill, be eating the feed continuously fromthe time of harvest, therefore the decay term forthe consumption of stored. feed used is not that given in Reg..Guide 1.109 for the end of the periodbetween harvest.:and consumption, but is instead an integrated decay over the period (Reference 10). The resulting~dose factor is: Rcsi =106 DFLia` Uap Fmi Qf exp(-Xitfm) f{ 1exp(-it.s')j r []-exp(-Xjt6)t

+Bv[1-exp(--Itb)r+

(7.20)where: 106 = conversion factor, pCi/ýtCi.DFLiaj = ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table 6.4).Uap = milk ingestion rate for age group a, L/y.Fmi = transfer factor for nuclide i from animal's feed to milk, d/L (Table 6.2).Qf = animal's consumption rate, kg/d.fs = fraction of time animal spends on stored feed, dimensionless.

li = decay constantfor nuclide i, s-1 (Table 6.2).tfm = transport time from milking to receptor, s.tcsf = time between harvest of stored feed and consumption by animal, s.r = fraction of activity retained on pasture grass, dimensionless.

IE = the effective decay constant, due to radioactive decay and weathering, s-1= li + 1w.Iw = weathering decay constant for leaf and plant surfaces, s-1.te = time stored feed is exposed to deposition, s.Ysf = agricultural productivity by unit area of stored feed, kg/m2.Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation)1per pCi/kg (dry soil). (Table 6.2)tb = time period over Which accumulation on the ground is evaluated, s.P = effective surface density of soil, kg/m2.NOTE: Factors defined above which do not reference a table for.their numerical values are given in Table 6.3.El-182 WBN OFFSITE DOSE CALCULATION MANUAL Revision22 0 (ODCM) Page 121.of 195 7.8.3 Pasture Grass-Beef Ingestion Dose Factors -RMpi (m 2-mrem/y per gCi/s)The general dose equation stated in Regulatory Guide 1. 109 for calculating the, annual dose from, consuming foods containing atmospherically released radionuclides (Equation:

C-13) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide.Concentration in Media(C)For the beef pathway, Regulatory Guide 1.109 Equations C-5 and C-12 are inserted into theiabove equation to yield the following:

DDFL Uap F, QF exp(-X) dr [1 -exp(-XEte)]

Biv[+ -exp(- exp(-)D= DFLU t dA- FfQ x(XYXEP x(X Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and'7.14) contain the variabledi (equal to the product of the release rate (Q). and the deposition factor (D/Q)), the factors remaining in the above equation are defined. as thedose factor. In addition, a factor is added to account for the decay during. the time the. beef is being consumed.

This term assumes that the individual slaughters andý eats.the animal over a period, of time (tcb) (Reference 10). Forpasture grass, the variable th is defined as zero in Regulatory Guide 1.109, therefore thatexponential term drops out of the equation.

The resultingdose factor is: RM~i =O6 DFL iaj U -F,. Q { }CXP.it. e Y-Xt)f r [exp(-kXtj)+

Bi[1-exp(-Xi]}

(721)where: 106 = conversion factor, pCi/!Ci.DFLiaj = ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table6.4).

Uam = beeflingestion rate for age groupa, kg/y.Ffi = transfer factor for nuclide i from cow's feed to beef, d/kg (Table 6.2).Qf = cow's consumption rate, kg/d.li = decay constant.for nuclide i, s-1 (Table 6.2).tcb = time for receptor to consume a whole beef, s.ts = transport time from. slaughter to consumer, s.fp = fraction of timecow spends on pasture, dimensionless.

r = fraction of activity retained on pasture grass, dimensionless.

IE = the effective decay-constant, due to radioactive decay and weathering, s-1, equal to litlw Iw = weathering decay constant for leaf and plant surfaces, S-1.tep = time pasture is exposed to deposition, s.Yp = agricultural.

productivity by unit area of pasture grass, kg/m2.Biv = transferfactor for.nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation).

per pCi/kg (dry soil). (Table 6.2)tb = time over which accumulation on the ground is evaluated, s.P = effective surface' density of soil, kg/m 2" NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.El-183 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 122 of 195 7.8.4 Stored Feed-Beef Ingestion Dose Factors -RMsi (m 2-mrem/y per gCils)The general dose equation stated, in Regulatory Guide 1.109 for calculating the,annual.dosefrom consuming:foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration'inMedia(C)

For the beef pathway, Regulatory Guide 1.109 Equations C-5 and C-;1 2 are inserted into the above equation to yield the following:

D = DFL Up Ff QF exp(-At,)

d, {r [1 -exp(-2Ete)]

+ B"[1 -exp(-At)]

exp(-Ath)Since the doseequation in, Sections 7.4 and 7.7.3 (Equations 7.9 and 7.14) contain the variable di: (equal to the product of the release rate (Q) and the deposition factor (DIQ)), the factors: remaining in the'above equation are defined as the dose factor. In addition, factors are added to account for the decay during the time the animals are consuming the stored feed.(tcsf) and during thetime period of over which the beef is being consumed (tcb) (Reference 10). The resulting dosefactor is: RMSi = 1O 6 DFljUamFflQf~

[-ex1(-k'tctD]}x ( `t f{[1 -[exý-XitC)]}{r[i-exr jtj)]+ B j[l-exp(Xtb (7.22)where: 106 = conversion factor, pCi/gCi.DFLiaj = ingestiondose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table 6.4).Uam = beef ingestion rate for age group a, kg/y.Ffi = transfer factor for nuclide i from cow's feed to beef, d/kg (Table 6.2).Qf = cow'sconsumption rate, kgld.Ii = decay constant for nuclide i, s-1 (Table 6.2).tcb = time for receptor to consume a whole beef, s.ts = transport time from slaughter to consumer, s.fs = fraction of time cow spends on stored feed, dimensionless.

tcsf = time between harvest of stored feed and consumption by cow, s.r =fraction of activity retained on pasture grass, dimensionless.

te = time stored feed is exposed to deposition, s.Ysf = agricultural productivity by unit area of stored feed, kg/m 2.IE =,the effective decay constant, due to radioactive decay and weathering; s7 1 ,= li+lw.Iw = weathering decay constant for leaf and plant surfaces, s-1.Biv = transfer factor for nuclide i from soil to vegetation, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil). (Table 6.2)tb = time over which~accumulation on the ground is evaluated, s.P = effective surfacedensity of soil, kg/m 2.NOTE: Factors defined above which do not reference a table for their numericalvalues are given in Table 6.3.El-184 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page'1231of 195 7.8.5 Fresh Leafy VegetableIngestion Dose Factors -RVFi (m 2-mrem/y per gCi/s)The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods. containing atmospherically released radionuclides'(Equation, CA 3) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide!Concentration.,in Media(C)For the vegetable pathway, Regulatory Guide 1.109 Equation C-5 is inserted into the above equation to yield, the-following:

Fi r[I-exp(-XEte)]

Bv1-exp(-tb)]

hc D FLU~ad~{ YVE + x(-XC Sincethe dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and :7.14) contain fthe varidable d (equal to the product of the :release rate.(Q) and the deposition factor (DiQ)),the

  • factorsrem a ining" in. the above equation.are defined as the dose factor. Thus, the dose factor is: RVFI = 106DFLiajexp(-Xithc)

UFLa FL { [ p(Ee)] + Bvll-exp(itb)]}

(7.23)where: 106 = conversion factor, pCi/gCi.DFLiaj = ingestion doseconversion factor for nuclide i, age group a, organ j, mrem/pCij(Table 6.4).li = decay constant for nuclide i, S-1 (Table 6.2).thc = average time'between harvest of vegetables.and their consumption and/or storage,.s.

UFLa = consurnption rate of fresh leafy vegetables.by the receptor:

in age group a,-kg/y..fL = fraction of fresh leafy vegetables grown locally, dimensionless.

r = fraction of deposited'activity retainedon vegetables, dimensionless.

IE = the effective decay constant, due to radioactive decay andweathering, s-1.= li + IW Iw = decay. constant for removal of activity on leaf and plant surfaces by weathering, .s"i.te =exposuretime in garden for fresh leafy and/or stored vegetables, s.Yf = agricultural yield. for fresh leafy vegetables, kgmn 2.Biv = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil). (Table 6.2)tb = time period over which accumulation on the ground is evaluated, s.P = effective surface density of soil, kg/m 2.NOTE: Factors definedabovewhich do not reference a table for their numerical values are given in Table 6.3.El-185 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 124 of 195 7.8.6 Stored Vegetable Ingestion Dose Factors -Rvsi m 2-mrem/y per pCi/s)The general dose equation stated in Regulatory Guide 1.109 for calculating theannual dosefrom consuming foods containing atmospherically released radionuclides (Equation C-i 3) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C)For the vegetable pathway, Regulatory Guide 1.109 Equation C-5 is inserted into the above equation to yield the following:

r [1-exp(-2Et)]

Bv [1- exp(- b)] A D == DFL UFLa d Y {r PA exp(- At h.Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and 7.14) contain thevariable di.(equal to the product of the release rate (Q) and the deposition factor (D/Q)), the factorsremaining in the above equationare defined as the dose factor. One additional decay termis added to account for the decay during the period of time after harvest during which the food is consumed(tsv);

thisterm assumes that the stored vegetables are eaten throughout the storage period (Reference 10). Thus, the dose factor is:[1-___exp__-

__, ifs ][ [1- exp(-XEte)]

Biv [1 -exp(-,itb,)]]l RVSj = 106 DFLaj exp(-?,Ithc)

Usa fg [xp(its [1 YsvXE + p f (7.24)where: 106 = conversion factor, pCi/gCi.DFLiaj = ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table.6.4).

li = decay constant for nuclide i, s-1 (Table 6.2).thc = average.time between harvest of vegetables and their consumption and/or storage, s.Usa = consumption rate of stored vegetables by the receptor in age group a, kg/y.fg = fraction of stored vegetables grown locally, dimensionless.

tsv = time between storage of Vegetables and their consumption,, s.r = fraction of deposited activity retained on vegetables, dimensionlessi IE = the effective decay constant, due to radioactive decay and weathering, s-1.= Ij + 1w Iw = decay constant for removal of activity on leaf and plant surfaces by weathering, s-1.te = exposure time in garden for fresh leafy and/or stored vegetables, s.Ysv = agricultural yield for stored vegetables, kg/m 2.giv = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of'vegetatibn) per pCi/kg (dry soil). (Table 6.2)tb =time period over which accumulation on the ground is evaluated, s.P = effective surface. density of soilI kg/m 2.NOTE: Factors defined above which do not reference a table for their numerical values aregiven in Table 6.3.E1-186 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 125,of 195 7.8.7 Tritium-Pasture Grass-Cow/Goat-Milk Dose Factor -RcPT (mrem/y per gCi/m 3)The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C)For the milk pathway, Regulatory Guide 1.109 Equations C-9 and C-10 are inserted into the above equation to yield the following:

D = DFL Uap Fm Qf exp(-2tfm)QT 1 Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and 7.14) contain thevariablesforthe release rate (Q) and the dispersion factor (X/Q), the factors remaining in the above equation are defined as the dose factor. The resulting dose factor equation is: RCTp -=1 0 106 DFLTaj FmT Q1 Uap [o0.750".5

]fp At t) (7.25)Q L KH~jPPTtJ where: 10 3 = conversion factor, g/kg.106 = conversion factor, pCi/tCi.DFLTaj = ingestion dose conversion factor for tritium for age group a, organ j, mrem/pCi (Table 6.4).FmT = transfer factor fortritium from animal's feed to milk, d/L (Table 6.2).Qf = animal's consumption rate, kg/d.Uap = milk ingestion rate forage group a, L/y.0.75 = the fraction of total feed that is water.0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.H = absolute humidity of the atmosphere, g/m 3.fp = fraction of time animal spends on pasture, dimensionless.

IT = decay constant for tritium, s-1 (Table 6.2).tfm = transport time from milking to receptor, s.El-187 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 126,of:195 7.8.8 Tritium-Stored Feed-CowlGoat-Milk Dose Factor -RCST (mrem/y per vCi/m 3)The general dose equation stated in Regulatory Guide 1.109 for calculating~the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-1 3).is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C)For the milk pathway, Regulatory Guide 1.109 Equations C-9 and C-10 are inserted into the above equation to yield the following:

D=DFLUp Fm Qf exp(-,tft)QT x-0.75 0.5)] (7.26)Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and 7.14) contain thevariables for the release rate (Q) and the dispersion factor (X/Q), the factors remaining in theabove equationare defined as the dose factor. In addition, a factor is added to account for the decay during the time theýanimals are consuming the stored feed (Reference 10). The resulting dosefactor is: RCST =O: 10'6 DFLrTaj Fr QF Uam 0.75 0-5]f, exp(- ATt,){[ -exp(-/kt,,f where: 103 = conversion factor, g/kg.106 = conversion factor, pCi/gCi.DFLTaj = ingestion dose conversion factor for H-3 for age~group a, organ j, mrem/pCi (Table 6.4).FfT = transfer factor for H-3 from cow's feed to beef, d/kg (Table 6.2).Qf = cow'sconsumption rate, kg/d.Uam = beef ingestion rate for age group a, kg/y.0.75 = the fraction of total feed .that is water.0.5 = theratio of the specific activity of the feed grass water to the atmospheric water.H = absolute humidity of the atmosphere, g/m 3.fs = fraction of time cow spends on stored feed, dimensionless.

IT = decayconstant for tritium, s-1 (Table 6.2).ts = transport time from slaughter to consumer, s.tcsf = time to consume stored feed, s.NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.E1-188 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page,127 of 195 7.8.9 Tritium-Pasture Grass-Beef Dose Factor -RMPT (mrem/y per gCi/m 3)The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides Equation C-13) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C)For the beef pathway, Regulatory Guide 1.109 Equations C-9 and C-10 are inserted intothe above equation to yield the following:

D=DFL Uap Ff.Qf exp(-At,))QT X 0.7 5 g0.5)]Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and 7.14) contain theovariables.for the release rate (Q) and the dispersion factor (y/Q), the factors remaining in the% above, equation are defined as the dose factor. Two decay terms are added to the equation to account for:the decay during the time the pasture is exposedto the activity in the air, and the decay during the time the, beef is being:consumed (Reference 10). The resulting dose factor is: RAIT =i1o1 106 DFL T~j F, % U_, [.75(o0.5]

f, -) Ixp(- , )fl [I exp(-tt..i h) (7.27)-where: 103 = conversion factor, g/kg.106 = conversion factor, pCi/pCi.DFLTaj = ingestion dose conversion factor for H-3 for age group a, organ j, mrem/pCi (Table 6.4).FfT = transfer factor for H'3 from cow's feed to beef, d/kg (Table 6.2).Qf = cow's consumption rate, kg/d.Uam = beef ingestion rate for age group a, kg/y.0.75 = the fraction of total feed that iswater.0.5 = the ratio ofthe specific activity of the feed grass water to the atmospheric water.H = absolute humidity of the atmosphere, g/m 3.fp = fraction of time cow spends on pasture, dimensionless.

IT = decay constant for tritium, s-1 (Table 6.2).ts = transport time from slaughter to consumer, s.tep = time pasture.is exposed to deposition, s.tcb = time for receptor to consume a whole beef, s.E1-189 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 128 of 195 7.8.10 Tritium-Stored Feed-Beef Dose Factor -RMST (mrem/y per p.Ci/m 3)The general dose equation stated in Regulatory Guide 1.109 for calculating the:annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C)For the beef pathway, Regulatory Guide 1.109 Equations C-9 and C-10 are insertedintotheabove equation to yieldthe following:

D = DFL Uam Ff Q f exp(- 2t ) QT 2. [ .5j]Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and 7.14) contain the variables for the release rate (Q), and the dispersion factor (X/Q), the factors remaining in the aboveequation aredefined as the dose factor. Two decay terms are added to the'equation to account for the decay during the time the, pasture is exposed to the activity in the air, and the decay during the time the beef isbeingconsumed (Reference 10). The resulting dose factor is:.10'10'DFLF

)ýI-ep.(t~jj f[-ex(-4,)](7.28)

R_ _ MT 1 LTaj IT Q U. .75(0 ]f, ex(7.28)where: 103 = conversion factor, g/kg.106 = conversion factor, pCi/RCi.DFLTaj = ingestion-dose conversion factor for H-3 for age group a, organ j, mrem/pCi (Tabled6:4).

FfT = transfer factor for H-3 from cow's feed to beef, d/kg (Table 6.2).Qf = cow's consumption rate, kg/d.Uam = beef ingestion rate for age group a, kg/y.0.75 = the fraction of total feed that is water.0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.H = absolute humidity of the atmosphere, g/m 3.fs = fraction of time cow spends on stored feed, dimensionless.

IT = decay constant;for~titium, s-1 (Table 6.2).ts = transport time from slaughter to consumer, s.tcsf = time to consume~stored feed, s.tcb = time for receptor to'consume awhole beef, s.NOTE: Factors defined above which do not reference a table for their numerical values are given in Table El-190 WBN OFFSITE DOSE CALCULATIONMANUAL Revision 22 0 (ODCM) Page :129 of 195 7.8.11 Tritium-Fresh Leafy Vegetable Dose Factor -RVFT (mrem/y per jiCi/m 3)The general dose equation-stated inRegulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-i 3) is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C)For the vegetable pathway, Regulatory Guide 1.109 Equation C-9 is inserted into the ýabove equation to yield the following:

D=DFLUap exp(- .,thc)QT 0.75(0]Since thedose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and 7.14) contain the variables for the release rate (Q) andý the dispersion factor (X/Q), the factors remaining in the aboveequationare defined as the dose factor. The resulting dose factor is: R VF = 10 106 DFLTaj[ 0.750.5)U]

U FL. fL exp(- T thc) (7.29)where: 103 = conversion factor, g/kg.106 = conversion factor, pCi/ltCi.DFLTaj = ingestion dose conversion factor for tritium for age group a, organ j, mrem/pCi (Table 6.4).0.75 = the fraction of total vegetation that is water.0.5 = the ratio of the specific activity of the vegetables water to the atmospheric water.H = absolute humidity of the atmosphere, g/m 3.UFLa ='consumption rate of fresh leafy vegetables by the receptorin age group a, kg/y.fL = fraction of freshr leafy vegetables grown locally, dimensionless.

IT = decay constant for tritium, s-1 (Table 6.2).thc = time between harvest of vegetables and their consumption and/or storage, s.NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.E1-191 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 130 of.195 7.8.12 Tritium-Stored Vegetable Dose Factor -RvsT (mrem/y per pLCi/mr 3)The general dose equation stated in Regulatory Guide 1.109 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation C-13)'is: Dose(D) = Dose Conversion Factor(DFL)*Usage Rate(U)*Radionuclide Concentration in Media(C)For the vegetable pathway, Regulatory Guide 1.109 Equation C-9 is inserted into the above equation to yield the following:

V=DFL Uap exp(- 2th.)QT [ 0.75( 0".5]Since the dose equation.in Sections 7.4 and 7.7.3 (Equations 7.9 and 7.14) contain thevariables for the release rate (Q) and the dispersion factor (X/Q), the factors remaining in the above equation are defined as the dose factor. An additional decay term is added to account for the decay during theltime the " vegetables are stored (this term assumes that the vegetables are being- eaten during the storage period)(Reference 10). The resulting dose factor is: RVST =10 106 DFLTaj [.75(IJjUsa fg {[1-exp(-'art

)]} exp(-.rt 1 ) (7.30)where: 103 = conversion factor, g/kg.106 = conversion factor, pCi/gCi.DFLTai = ingestion dose conversion factor for tritium for age group a, organ j, mrem/pCi (Table 6.4).0.75 = the fraction of total vegetation that is water.0.5 = the ratio of the specific activity of the vegetation water to the atmosphericwater.

H = absolute humidity of the atmosphere, g/m 3.Usa = consumption rate of stored vegetables by the receptor in age group a, kg/y.fg = fraction of.stored vegetables grown locally, dimensionless.

IT = decay constant for tritium, s-1 (Table 6.2). , tsv = time between harvest of stored vegetables and their consumption and/br storage, s.thc = time between harvest of vegetables and their storage, s.EI-192 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 131 of- 195 7.8.13 Inhalation Dose Factors -Rli (mrem/y per gCi/m 3)The inhalation dose factors are calculated using the equation provided in NUREG-0133, Section 5.3.1.1.Rp = 106 DFAiaj BR, (7.31)where: 106 = conversion factor, pCi/[Ci.DFAiaj = inhalation dose conversion factor for nuclide i, age group a and-organ j, mrem/pCi (Table 7.7).BRa = breathing rate for age group a, m 3/y (Table 6.3).7.8.14 Ground Plane Dose Factors -RGi (m 2-mrem/y per gCi/s)The ground plane dose factors are calculated using the equation provided in NUREG-0133, Section 5.3.1.2. The shielding factor in that equation is conservatively assumed to be 1.0.RG, = 10 6 8760 DFGii -- [1- exp(-2,tb

)] (7.32)where: 106 = conversion factor, pCi/gCi.8760 = conversion factor, h/y.DFGij = dose conversion factor for standing on contaminated ground for nuclide i and organ j (total body and skin), mrem/h per pCi/m 2 (Table 6.6).li = decay constant of nuclide i, s-1 (Table 6.2).tb = time period over which the ground accumulation is evaluated, s (Table 6.3).E1-193 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 132 of 195 7.9 DISPERSION METHODOLOGY Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data consisting of wind speed and direction measurements at 1Om and temperature measurements at 1Om and 46m.A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considers plume depletion (using information from Figure 7.4), and building wake effects. Terrain effects on dispersion are considered as described in Section 7.9.4.Hourly average meteorological'data are expressed as a joint-frequency distributionof wind speed, wind direction, and atmospheric stability.

The joint-frequency distribution which represents thethistorical meteorological data for the period January 1986 to December 2005 is given in Table 7.2.The wind speed classes that are used are as follows: Number Range,(m/s)1 Midpoint,(m/s) 1 <0.3 0.13 2 0.3-0.6 0.45 3, 0.7-1.5 1.10 4 1.6-2.4 1.99 5 2.5-3.3 2.88 6 3.4-5.5 4.45 7 5.6-8.2 6.91 8 8.3-10.9 9.59 9 >10.9 10.95 The stability classes that will be used are the standard Pasquill A through G classifications.

The stability classes 1-7 will correspond to A=1, B=2 ..., G=7.7.9.1 Air Concentration

-X Air concentrations of nuclides at downwind locations are calculated using the following equation: 9 f72/ Qi P TAF (--)(.3 X i =i i I. X exp -(7 33 k= , 1=1 TE ,zz .Uk ( -U)where: fk1 = joint relative frequency of occurrence of winds in windspeed-class k; stability class I, blowing toward this exposure point, expressed as a fraction.Qi = average annual release rate of radionuclide i, pCi/s.p = fraction of radionuclide remaining in plume (Figure 7.4).TAF = site specific terrain adjustment factor (from Table 7.3). Calculated as described in Section 7.9.4.Szl = vertical dispersion coefficient for stability class I which includesa building wake adjustment,---- + SO or = a , whichever is smaller.where: Szl is the vertical dispersion coefficient for stability class I (m) (Figure 7.5), c is a building shape factor (c=0.5) (Reference 5), a is~the minimum building cross-sectional area (1630 m 2) (Reference 23).uk = midpoint value of wind speed class interval k, m/s.El-194 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 133 of 195 x = downwind distance, m.n = number of sectors, 16.= radioactive decay coefficient of radionuclide i, s-1 2px/n = sector width at point of interest, m.7.9.2 Relative Concentration

-XIQ Relative concentrations of nuclides at downwind locations are calculated using~the following equation: X 7 fk, TAF-=Y Y, -(7.34)Q 7E1 E' ( -)where: fk1 = joint relative frequency of occurrence of winds in windspeed class k, stability class I, blowing toward this exposure point, expressed as a fraction.TAF = site specific terrain adjustment factor (from Table 7.3). Calculated as described in Section 7.9.4.Sz1 = verticaldispersion coefficient for stability class I which includes-a building wake adjustment, F, J2 +CEO or = V 5 az, whicheveris smaller.where: s,1 is the vertical dispersion coefficient for stability class I (m) (Figure 7.5), c is a building shape factor (c=0.5) (Reference 5), a is the minimum building cross-sectional area (1630 m 2) (Reference 23).Uk = midpoint value of. wind speed class interval k, m/s.x = downwind distance, m.n = number of sectors, 16.2px/n = sector width at-point of interest, m.7.9.3 Relative Deposition

-D/Q Relative deposition of nuclides at downwind locations is calculated using the following equation: D 9 7 fkl dr TAF-= Y Y (7.35)Q k=1 1=1 , 2x where: fkl = joint relativefrequency of occurrence of winds in windspeed class k and stability class I, blowing toward this exposure point, expressed as a fraction.dr = relative deposition rate, m7 1 (from Figure 7.6).TAF = site specific terrain adjustment factor (from Table 7.3). Calculated as described in Section 7.9.4.x = downwind distance, m.n = number of sectors, 16.2px/n = sector width at point of interest, m.E1-195 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 134o6f 195 7.9.4 Terrain Adjustment Factor -TAF As discussed in Reference,5, the straight-line dispersion model does not account for spatial andtemporal variations in the airflow expected from the southwest-northeast aligned'river valley. Such variations are considered by application of site-specific terrain adjustment factors, TAF. These factors were developed through the comparison of variable trajectory model results with straight-line model results for onIsite meteorological data for 1978 (Reference 19). The ratio of the variable trajectory model[dispersion factors to the straight-line model dispersion factors is defined as the TAF.The dispersion factors used in the dose rate and dose calculations described in Sections 7.2.2, 7.2.3, 7.3.1, 7.3.2, and. 7.4.1 are calculated using the meteorological data from the 1 986 to 2005 period (in Table 7.2)..XIQ and D/Q values are calculated for each of the 16 UNRESTRICTED.AREABOUNDARY sector locations (Table 7.1). Theseare multiplied by the TAF associated with each of these sectors (see Table 7.3). The highest of these dispersion values are chosen for the dose or dose ratecalculations.

The dispersion factors used in the dose calculations described in Section 7.7 are calculated using the: actual meteorological data for the :period. X/Q or D/Q values are calculated using Equations 7.34 and 7.35 for the unrestricted areaboundary:locations identified in Table 7.1, for the 16 nearest resident locations, and all garden and milk animal locations identified in the annual land use censu's described in Section 9.3. The TAF values associated with these dispersion factors is the ratio of the dispersion factor calculatedbythe variable trajectory model to that calculated by the straight-line model for each of these locations using the 1978 meteorological data. These values will be calculated for all locations identified by the land, usecensus and then used to modify the -IQ and D/Q values determined with the actual meteorologicaldata:

Any TAF values of less than 1.0 will be defined as 1.0.E1-196 WBN OFFSITE DOSE CALCULATIONMANULAL Revision22 0 (ODCM) Pageý ,135 of :195 Table 7.1 -WBN -OFFSITE RECEPTOR LOCATIONDATA Receptor Sector DISTANCE -7Q* D/Q*from plant (in) (s/m 3) (llm 2)Unrestricted Area Boundary N 1550 3.01 E706 4.78E-09 Unrestricted Area Boundary NNE 1980 3.53E-06 6.83E-09 Unrestricted Area Boundary NE 1580 5.OOE-06 5'24E-09 Unrestricted Area Boundary ENE 1370 7.24E-06 5.16E-09 Unrestricted Area' Boundary E 1280 8.56E-06 6.04E-09 Unrestricted Area Boundary ESE 1250 7.94E-06 6:44E-09 Unrestricted Area Boundary SE 1250 7.40E-06 6.33E-09 Unrestricted Area Boundary SSE 1250 4.03E-06 5.47E-09 Unrestricted Area Boundary S 1340 2.81 E-06 6.16E-09 Unrestricted Area Boundary SSW 1550 2.07E-06 5.25E-09 Unrestricted Area Boundary SW 1670 2.12E-06 3.50E-09 Unrestricted Area Boundary WSW 1430 3104E-06 3.54E-09 Unrestricted Area Boundary W 1460 1.76E-06 1 .73E-09 Unrestricted Area Boundary WNW 1400 9.96E-08 9.52E-10 Unrestricted Area Boundary NW 1400 1.21 E-06 1.25E-09 Unrestricted Area.Boundary NNW 1460 1 .68E-06 1.93E-09 Liquid Discharge N/A N/A NOTE: For quarterly airborne dose calculations, doses will also be calculated for all locations identified in the most recdnt land use census, and for any additional points deemed necessary.

  • These x/Q andl D/Q values must be multiplied by the sector specific Terrain Adjustment Factor (from Table 7.3) prior to selecting.the critical UNRESTRICTED AREA BOUNDARY location to be used in dose calculations.

E1-197 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 136 of 195 Table 7.2 -JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT:STABILITY CLASSES (Page 1 of 7)STABILITY CLASS A (DELTA T<=-1.9 C/100 M)Watts Bar Nuclear Plant JAN 1, 1986 -DEC 31. 2005 WIND WIND SPEED(MPH)

DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4

.=24.5 TOTAL N 0.000 0.001 0.011 0.052 0.079 0.095 0.005 0.000 0.000 0.244 NNE 0.000 0.001 0.021 0.084 0.124 0.181 0.007 0.000 0.000 0.418 NE 0.000 0.000 0.034 0.100 0.080 0.094 0.000 0.000 0.000 0.308 ENE 0.000 0.000 0.039 0.076 0.045 0.017 0.000 0.000 0.000 0.175 E 0.000 0.000 0.037 0.040 0.010 0.004 0.000 0.000 0.000 0.092 ESE 0.000 0.000 0.017 0.023 0.002 0.001 0.000 0.000 0.000 0.042 SE 0.000 0.001 0.026 0.027 0.005 0.004 0.000 0;000 0 000 0.064 SSE 0.000 0.000 0.049 0.063 0.015 0.011 0.001 0.000 0.000 0.140 S 0.000 0.002 0.070 0.180 0.142 0.121 0.020 0.001 0.000 0.535 SSW 0.000 0.000 0.063 0.371 0.594 0.700 0.049 0.001 0.000 1.778 SW 0.000 0.000 0.029 0.146 0.148 0.065 0.002 0. 000 0.000 0.390 WSW 0.000 0.000 0.007 0.020 0. 018 0.040 0.006 0.000 0.000 0.091 W 0.000 0.000 0.006 0.007 0.029 0.059 0.007 0.000 0.000 0.108 WNW 0.000 0.000 0.004 0.010 0.011 0.064 0.005 0.000 0.000 0.093 NW 0.000 0.000 0.004 0.007 0. 0 19 0.052 0.005 0.000 0.000 0.087 NNW 0.000 0.000 0.009 0.021 0. 038 0.081 0.012 0.000 0.000 0.161 SUBTOTAL 0.001 0.005 0.426 1.226 1.359 1.589 0.119 0.001 0.000 4.725 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 170639 TOTAL HOURS OF STABILITY CLASS A 8030 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS A 7945 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 168144 TOTAL HOURS CALM 1 METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 6.72 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS El-198 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page 137 of,195 Table 7.2 -JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTIONAND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 2 of 7)STABILITY CLASS B (-1.9< DELTA T<=-1.7 C/100 M)Watts Bar Nuclear Plant JAN 1, 1986 -DEC 31, 2005 WIND WIND SPEED (MPH)DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4

-=24.5 TOTAL N 0.000 0.000 0.027 0.092 0.084 0.109 0.005 0.000 0.000 0.318 NNE 0.000 0.001 0.039 0.155 0.147 0.212 0.009 0:000 0.000 N0.563 NE 0.000 0.000 0.081 0.147 0.090 0.077 0.001 0.000 0.000 0.396 ENE 0.000 0.001 0.058 0.096 0.043 0.010 0.000 0.000 0.000 0.208 B 0.000 0.001 0.046 0.052 0.004 0.002 0.000 0.000 0.000 0.106 ESE 0.000 0.002 0.026 0.022 0.000 0.000 0.000 0.000 0.000 0.051 SE 0.000 0.000 0.039 0.032 0.005 0.002 0.001 0.000 0.000 0.078 SSE 0.000 0.000 0.057 0.035 0.008 0.004 0.000 0.000 0.000 0.104 S 0.000 0.001 0.077 0.148 0.075 0.039 0.014 0.001 0.000 0.354 SSW 0.000 0.001 0.052 0.322 0.266 0.199 0.020. 0.000 0.000 0.890 SW 0.000 0.000 0.036 0.169 0.054 0.014 0.001 0.000 0.000 0.275 WSW 0.000 0.000 0.007 0.037 0.015 0.021 0.001 0.000 0.000 0.081 W 0.000 0.000 0.006 0.011 0.025 0.040 0.009 0.000 0.000 0.091 WNW 0.000 0.001 0.005 0.014 0.031 0.079 0.007 0.000 0.000 0.137 NW 0.000 0.000 0.007 0.015 0.033 0.071 0-.008 0.000 0.000 0.135 NNW 0.000 0.000 0.011 0.034 0.040 0.079 0.008 0.000 0.000 0.173 SUBTOTAL 0.000 0.007 0.606 1.383 0.923 0.955 0.083 0.001 0.000 3.960 TOTAL HOURS OF VALID STABILITY OSERVATIONS 170639 TOTAL HOURS OF STABILITYCLASS B 6722 TOTAL'HOURS OF VALID WIND.DIRECTION-WIND SPEED-STABILITY CLASS B 6659 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 168144 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 5.98 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS El-199 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page138iof 195 Table 7.2 -JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION ANDWIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 3 of 7)STABILITY CLASS C (-1.7< DELTA T<=-1.5 C/100 W)Watts Bar Nuclear Plant JAN 1, 1986 -DEC31, 2005 WIND WIND SPEED (MPH)DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4

-=24.5 TOTAL N 0.000 0.001 NNE 0.000 0.001 ME 0.000 0.003 ENE 0.000 0.001 E 0.000 0.005 ESE 0.000 0.003 SE 0.000 .0.002 SSE 0.000 0.002 S 0.000 0.001 SSW 0.000 0.001 SW 0.000 0.001 WSW 0.000 0.001 W 0.000 0.001 WNW 0.000 .0.000 NW 0.000 0.000 NNW 0.000 0.000 SUBTOTAL 0.000 0.023 0.060 0.141 0.125 0.151 0.007 0.000 0.111 0.224 0.209 0.260 0.013 0ý000 0.139 0.221 0.117 0.070 0.001 0.000 0.113 0.127 0.030 0.005 0.001 0.000 0.080 0.049 0.005 0.002 0.000 0.000 0.054 0:028 0.002 0.001 0.000 0.000 0.071 0.033 0.002 0.001 0.000 0.000 0.080 0.064 0.009 0.004 0.002 0.000 0.128 0.230 0.085 0.048 0.008 0.001 0.152 0.423 0.256 0.177 0.019 0.000 0.080 0.225 0.070 0.011 0:001 0.000 0.023 0.049 0.026 0.015 0:001 0.000 0.016 0.027 0.039 0.042 0.004 0.000 0.013 0.030 0.049 0.111 0.010 0.000 0.020 0.036 0.043 0.096 0.011 0.000 0.032 , 0.059 0.064 0.098 0.011 0.000 1.171 1.968 1.130 1.093 0.089 0.001 0.000 0.485 0.000 0.817 0.000 0.552 0.000 0.277 0.000 0.140 0.000 0.088 0.000 0.109 0.000. 0.161 0.000 0.503 0.00 0 1.028 0.000" 0.387 0.000 0.117 0.000 0.130 0.000 0,214 0.000 0.206 0.000 0.264 0.000 5.476 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 170639 TOTAL HOURS) OF STABILITY CLASS C 9309 TOTAL, HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS C 9207 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 168144 TOTAL HOURS CALM 0 METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED.ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 5.57 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS EI-200 WBN OFFSITE DOSE CALCULATION MANUAL Revision-22 0 (ODCM) Page 139 of 195 Table 7.2 -JOINT PERCENTAGE FREQUENCIES OF WIND:DIRECTION ANDWIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 4of 7)STABILITY CLASS D (-1.5< DELTA T<=-0.5 C/100 M)Watts Bar Nuclear Plant JAN 1, 1986 -DEC 31, 2005 WIND WIND SPEED (MPH)DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4

-=2 4.5 TOTAL N 0.006 0.050 0.656 0.996 1.063 1.203 0.034 0.000 0.000 4.007 NNE 0.006 0.052 0.697 1.241 1.206 1.182 0.072 0.002 0.000 4.458 NE 0.007 0.064 0.796 1.060 0.477 0.203 0.005 0.000 0.000 2.612 ENE 0.008 0.095 0.840 0.479 0.115 0.038 0.002 0.000 0.000 1.577 E 0.005 0.126 0.478 0.137 0.022 0.005 0.000 0.000 0.000 0.774 ESE 0.003 0.081 0.275 0.057 0.006 0.004 0.000 0.000 0.000 0.426 SE 0.004 0.090 0.369 0.076 0.022 0.014 0.001 0.001 0.000 0.575 SSE 0.006 0.133 0.566 0.160 0.035 0.034 0.014 0.000 0.000 0.949 S 0.011 0.174 1.104 0.699 0.296 0.251 0.076 0.004 0.000 2.615 SSW 0.015 0.145 1.610 1.796 0.927 0.815 0.076 0.002 0.000 5.386 SW 0.010 0.167 1.060 0.790 0.202 0.097 0.004 0.000 0.000 2.329 WSW 0.006 0.109 0.558 0.289 0.123 0.088 0.004 0;000 0.000 1.177 W 0.005 0.121 0.406 0.293 0.258 0.256 0.008 0.000 0.000 1.347 WNW 0.004 0.095 0.353 0.394 0.491 0.520 0.021 0.000 0.000 1.879 NW 0.004 0.071 0.353 0.403 0. 532 0.608 0.046 0.001 0.000 2.017 NNW 0.004 0.042 0.445 0.566 0.631 0.795 0.0 34 0.000 0.000 2.517 SUBTOTAL 0.104 1.615 10.566 9.436 6.405 6.113 0.395 0.010 0.000 34.645 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 170639 TOTAL HOURS OF STABILITY CLASS D 58946 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS D 58253 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 168144 TOTAL HOURS CALM 175 METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 4.96 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NDMBERS E1-201 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 140ýof 195 Table 7.2 -JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 5 of 7)STABILITY CLASS E (-0.5< DELTA T-= 1.5 C/100 M)Watts Bar Nuclear Plant JAN 1, 1986 -DEC 31, 2005 WIND WIND SPEED (MPH)DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4

-=24.5 TOTAL N 0.032 0.156 0.484 0.623 0.300 0.062 0.002 0.000 0.000 1.659 NNE 0.029 0.142 0.431 0.322 0.171 0.047 0.003 0.000 0.000 1.144 NE 0.039 0.169 0.606 0.366 0.068 0.012 0.003 0.000 0.000 1.264 ENE 0.053 0.240 0.813 0.196 0.015 0.004 0.001 0.000 0.000 1.321 E 0.029 0.277 0.310 0.040 0.011 0.003 0.000 0.000 0.000 0.671 ESE 0.014 0.167 0.118 0.024 0.006 0.004 0.001 0.000 0.000 0.333 SE 0.018 0.203 0.149 0.048 0.025 0.017 0.002 0.000 0.000 0.462 SSE 0.032 0.324 0.321 0.083 0.051 0.039 0.007 0.000 0.000 0,856 S 0.077 0.519 1.012 0.415 0.197 0.193 0.041 0.001 0.000 2.454 SSW 0.123 0.604 1.864 1.178 0.645 0.516 0.051 0.000 01.000 4.961 SW 0.101 0.731 1.291 0.307 0.121 0.062 0.002 0:000 0.000 2.616 WSW 0.072 0.736 0.711 0.147 0.087 0.037 0.001 0.000 0.000 1.792 W 0.064 o;698 0.591 0.194 0.083 0.034 0.000 0.000 0.000 1.664 WNW 0.059 0.645 0.537 0.263 0.099 0.037 .0.001 0.000 0.000 1.642 NW 0.048 0.461 0.507 0.279 0.108 0.047 0.002 0.001 0.000 11453 NNW 0.036 0.255 0.457 0.375 0.247 0.092 0.005 0.000 0.000 1.465 SUBTOTAL 0.827 6.326 10.201 4.862 2.234 1.206 0.121 0.002 0.000 25.777 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 170639 TOTAL HOURS OF STABILITY CLASS E 44130 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS E 43343 TOTAL' HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 168144 TOTAL HOURS CALM 1390 METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 3.03 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-202 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page'.141 of 195 Table! 7.2 -JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 6 of 7)STABILITY CLASS F ( 1.5< DELTA T1= 4.0 C/100 M)Watts Bar Nuclear Plant JAN 1, 1986 -DEC 31, 2005 WIND WIND SPEED (MPH)DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4

-=24.5 TOTAL N 0.046 0.268 0.181 0.018 0.001 0.001 0.000 0.000 0.000 0.515 NNE 0.038 0.199 0.172 0.016 0.002 0.001 0 000 0.000 0.000 0.429 NE 0.050 0.218 0.266 0.029 0.002 0.000 0.000 0.000 0.000 0.565 ENE 0.064 0.275 0.348 0.032 0.002 0.001 0.000 0.000 0.000: 0.721 E 0.033 0.197 0,123 0.005 0.001 0.000 0.000 0.000 0.000 0.358 ESE 0.015 0.121 0.027 0.000 0.000 0.000 0.000 0.000 0.000 0.163 SE 0.016 0.119 0.036 0.004 0.001 0.001 0.000 0.000 0.000 0.176 SSE 0.025 0: .177 0.066 0.010 0.001 0.002 0.001 0.000 0.000 0.282 S 0.056 0.313 0.236 0.032 0.004 0.002 0.000 0.000 0.000 0.643 SSW 0.103 0.459 0.547 0.156 0.020 0.004 0.000 0.000 0.000 1.290 SW 0.136 0.698 0.627 0.040 0.006 0.001 0.000 0.000 0.000 1.507 WSW 0.167 0.994 0.639 0.023 0.002 0.001 0.000 0.000 0.000 1.827 W 0.183 1.268 0.522 0.021 0.003 0.001 0.000 0.000 0.000 1.999 WNW 0.177 1.279 0.447 0.029 0.001 0.001 0.000 0.000 0.000 1.933 NW 0.171 1.198 0.472 0.034 0.002 0.001 0.000 0.000 0.000 1.878 NNW 0.080 0.525 0.254 0.036 0.002 0.001 0.000 0.000 0.000 0.897 SUBTOTAL 1.360 8.307 4.963 0.486 0.049 0.016 0.001 0.000 0.000 15.181 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 170639 TOTAL HOURS OF STABILITY CLASS F 26048 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS F 25526 TOTAL HOURS, OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 168144 TOTAL HOURS CALM 2286 METEOROLOGICAL FACILITY:

Watts .Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 1.42 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-203 WBN OFFSITE DOSE CALCULATION MANUAL Revision 221 0 (ODCM) Page 142-6f 195 Table 7.2 -JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 7 of 7)STABILITY CLASS G (DELTA T .4.0 C/100 M)Watts Bar Nuclear Plant JAN 1, 1986 -DEC 31, 2005 WIND WIND SPEED (MPH)DIRECTION CALM 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4.

18.5-24.4

-24.5 TOTAL N 0.035 0.221 0.066 0.001 0.000 0.000 0.000 0.000 0.000 0.323 NNE 0.034 0.199 0.077 0.001 0.000 0. 000 0.000 0.000 0.000 0.310 NE 0.048 0.271 0.123 0.002 0.000 0.000 0.000 0.000 0.000 0.444 ENE 0.059 0,300 0.188 0.004 0.001 0.000 0.000 0.000 0.000 0 551 E 0.032 0.202 0.0058 0.002 0.000 0.000 0.000 0.000 0.000 0.294 ESE 0.016 0.116 0.018 0.000 0.000 0.000 0.000 0.000 0.000 0:i151 SE 0.021 0.145 0.023 0.000 0.000 0.000 0.000 0.000 0.000 0.189 SSE 0.025 0.173 0.032 0.001 0.000 0.000 0.000 0.000 0.000 0.231 S 0.036 0.246 0.051 0.002 0.000 0.000 0.000 0.000 0.000 0.335 SSW 0.060 0.367 0.123 0.005 0.001 0.000 0.000 0.000 0.000 0.556 SW 0.096 0.569 0.222 0.002 0.000 0.000 0.000 0.000 0.000 0.889 WSW 0.162 0.916 0.410 0.007 0.000 0.000 0.000 0.000 0.000 1.495 W 0.169 1.036 0.351 0.002 0.000 0.000 0.000 0.000 0.000 1.559 WNW 0.130 0.825 0.240 0.004 0.000 0.000 0.000 0.000 0.1000 1.200 NW 0.127 0.751 0.292 0.002 0.000 0.000 0.000 0.000 0.000 1.173 NNW 0.058 0.356 0.120 0.002 0.000 0.000 0.000 0.000. 0.000 0.536 SUBTOTAL 1.109 6.695 2.394 0.037 0.001 0.000 0.000 0.000 0.000 10.236 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 170639 TOTAL HOURS OF STABILITY CLASS G 17454 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY CLASS G 17211 TOTAL HOURS OF VALID WIND DIRECTION-WIND SPEED-STABILITY OBSERVATIONS 168144 TOTAL HOURS CALM 1864 METEOROLOGICAL FACILITY:

Watts Bar Nuclear Plant STABILITY BASED ON DELTA-T BETWEEN 9.51 AND 45.63 METERS WIND SPEED AND DIRECTION MEASURED AT 9.72 METER LEVEL MEAN WIND SPEED = 1.14 NOTE: TOTALS AND SUBTOTALS ARE OBTAINED FROM UNROUNDED NUMBERS E1-204 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page143 of 195 Table 7.3 -ADJUSTED DISPERSION FACTORS Sector TAF* f/Q(TAF) DIQ(TAF)(s/m3) (1/m2.)N 1.7 5.12E-06 8.13E&09 NNE 1.8 6.35E-06 1.23E-08 NE 2.1 1.05E-05 1.1OE-08 ENE 1.7 1.23E-05 8.77E-09 E 1.6 1.37E-05 9:66E-09 ESE 1.8 1.43E-05, 1. 16E-08 SE 1.5 1.11E-05 9.49E-09 SSE 1.5 6.04E-06 8.21 E-09 S 1.9 5.33E-06 1-,17E-08 SSW 2.0 4.14E-06 1.05E-08 SW 2.1 4.46E-06 7.34E-09 WSW 1.8 5.47E-06 6.37E-09 W 1.2 2.11E-06 2.07E-09 WNW 2.5 2.49E-06 2.38E-09 NW 1.7 2.05E-06 2.13E-09 NNW 1.6 2.68E-06 3.08E-09*The Site Specific Terrain Adjustment Factor (TAF) is equal to the ratio of the variable trajectory X/Qto the straight-line XIQ. See ODCM Section 7.9.4 for a full explanation.

E1-205 WBN OFFSITE DOSE CALCULATION MANUAL Revision-22 0 (ODCM) Page,144 of 195 Table 7.4 -DOSE FACTORS. FOR SUBMERSION IN! NOBLE.GASES Submersion dose Air dose mremly per. I.,Ci/m 3 mradiy-perFgilm3 IDFi" DFSi .DFai ,DibiL Kr-83m 7.56E-02 --- 1.93E+O1 2.88E+02 Kr-85m 1,17E+03 1.46E+03 1.23E+03 1%97E+03 Kr-85 1.61 E+01 1..34E+03 1.72E+01 1,.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1 .03E÷04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-1 31 m 9.15EtO- 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 153E+02 1;05E+03 Xe-I135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81 E+03 1.86E+03 1.92Et03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 i.27E+04 Xe-1 38 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 .3.28E+03

Reference:

.

Regulatory Guide 1.109, Table B-1.El-206 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 145&of 195 Table 7.5 -SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES Range of Sector Element Midpoint of Sector Element.(mi) J (mi)Unrestricted Area Boundary -1 0.8 1-2 1.5 2-3 2.5 3-4 3.5 4- 5 4.5 5-10 7.5 10-20 15 20-30 25 30-40 35 40-50 45 E1-207 WBN OFFSITE DOSE CALCULATION MANUAL RevisiOn22 0 (ODCM) Page 146 of 195 Table 7.6 -POPULATION WITHIN EACH SECTOR ELEMENT Distance from Site (miles)0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 N 0 111 32 47 135 893 2071 21'66 3453, 4040 NNE 0 25 25 76 43 796 8591 19187 9342 1194 NE 0 0 130 208 130 861 3381 19210 30623 54111 ENE 0 2 55 53 78 252 2445 9497 38457 136395 E 0 2 7 53 38 482 9716 8837 10649 17404 ESE 0 2 4 47 58 591 4514 12085 3420 300 SE 0 0 16 35 29 505 17835 10818 3969 3756 SSE 12 23 3 27 24 714 4018 8056 3899 6362 S 0 54 14 24 257 1368 1141 34699 40812 11522 SSW 0 34 7 .19 32 739 5653 17523 25829 117868 SW 0 0 5 2 0 519 6490' 9411 68565 125338 WSW 0 10 40 38 30 1281 10369 2091 7134 6571 W 2 5 19 59 65 837 965 5337 2839 2035 WNW 5 30 10 140 121 244 1461 2925 3440 17598 NW 0 10 111 113 387 2279 314 7266 7004 9802 NNW 0 0 62 87 98 2081 874 18279 4784 2983 Total 19 308 540 1028 1525 14442 79838 187387 264219 517279.Total 1066585 1990 Population data from Reference 10 E1-208 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 147 of 195 Table 7.7 -INHALATION DOSE FACTORS -DFiao (mrem/pCi inhaled)(Page 1 of 8)ADULT Nuclide bone liver total body thyroid kidney lung, GI-LLI H-3 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E&07 Na-24 1.28E-06 1 28E-06 1.28E"06 1.28E-06 1.28E-06 1.28E-'06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 O.OOE+00 O.OOE+00 0.00E+00 1-.68E-05 Cr-51 O.00E+00 O.OOE+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 O.OQE+00 4.95E-06 7.87E-07 O.OOE÷00 1.23E-06 1.75E-04 9.67E-06 Mn-56 O.OOE+00 1.55E-10 2.29E-11 O.OOE+00 1.63E-10 1.18E-06 2.53E-06 Fe-55 3:07E-06 2.12E-06 4.93E-07 O.OOE+00 O.OOE+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3;47E-06 1.32E-06 O.OOE+00 0.00E00 1.27E-04 2.35E-05 Co-57 0.OOE+00 8.65E-08 8.39E-08 O.OOE+00 O.OE+00 4.62E-05 3.93E-06 Co-58 0.OOE+00 1.98E-07 2.59E-07 0.OOE+00 0.00E+00 1.16E-04 1.33E&05 Co-60 O.OOE+00 1.44E-06 1.85E-06 O.OOE+00 O.OOE+00 7.46E&04 3:56E-05 Ni-63 5.40E-05 3.93E-06 1.81E&06 O.OOE+00 O.OOE+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 O.OOE+00 O.OOE+00 7.00E-07 1.54E-06 Cu-64 O.OOE+00 1.83E-10 7.69E-11 O.OOE+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 O.OE+00 8.62E&06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 O.OOE+00 5.27E-12 1.15E-07 2.04E-09 Zn-69m 1.02E-09 2.45E-09 2.24E-10 O.OOE+00 1.48E-09 2.38E-06 1-.71 E05 Br-82 O.OOE+00 O.OOE+00 1.69E-06 O.OOE+00 0.00E+00 O.OOE+00 1.30E-06 Br-83 O.OOE+00 O.OOE+00 3.01E-08 O.OOE+00 O.OOE÷00 O OEOO 2.90E-08 Br-84 O.OOE+00 O.OOE÷00 3.91E-08 O.OOE+00 O.OOE+00 O.OOE+00 2.05E-13 Br-85 O.OOE+00 O.OOE+00 1;60E-09 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Rb-86 O.OOE+00 1.69E-05 7.37E-06 O.OOE00 O.OOE+Q00 0.00E÷E00 2.08E-06 Rb-88 0OOE+00 4.84E-08 2.41E-08 O.00E+00 0.00E00 0.00E+00 4.18E-19 Rb-89 O.OOE+00 3.20E-08 2.12E-08 O.OOE+00 O.OOE+00 O.OOEQ00 1.16E-21 Sr-89 3.80E-05 O.OOE+00 1.09E-06 O.OOE+00 O.00EO+00 1:75E-r04 4.37E-05 Sr-90 1.24E-02 O.OOE+00 7.62E-04 O.OOE+00 0.00E+00 1.20E-03 9.02E-05 Sr-91 7.74E-09 0OOE+÷00 3.13E-10 O.OOE+00 O.OOE-00 4.56E706 2.39E-05 Sr-92 8.43E-10 O.OOE+00 3.64E-11 O.OOE+00 O.OOE00 2.06E-06 5.38E-06 Y-90 2.61E-07 O.OE+00 7.01E-09 O.OOE+00 O.OOE+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 O.OOE+00 1.27E-12 O.OOE+00 O.OE+÷00 2.40E-07 1.66E-10 Y-91 5.78E-05 O.OOE+00 1.55E-06 O.OOE+00 O.00E+00 2.13E-04 4.81E-05 Y-92 1.29E-09 O.OOE+00 3.77E-11 O.OOE+00 O.OQE+00 1.96E706 9.19E'06 Y-93 1.18E-08 O.OOE+00 3.26E-10 O.OOE+00 0.OOE+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 O.OOE+00 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 O.OOEOO 3.71E-09 .9.84E-06 6.54E-05 Nb-95 1.76E&06 9.77E-07 5.26E-07 O.OOE+00 9.67E-07 6.31&E05 1.30E405 Nb-97 2.78E-11 7.03E-12 2.56E-12 O.OOE+00 8.18E-12 3.OOE-07 3.02E-08 Mo-99 O.OOE+00 1.51E-08 2.87E-09 O.OOE+00 3.64E-08 1.14E-05" 3.1OE-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 O.OOE+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 O.OOE+00 1.35E-13 4.99E'08, 1.36E-21 Ru-103 1.91E-07 0.0OE+00 8.23E-08 O.OOE+00 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 O.OOE+00 3.89E-11 O.OOE+00 1.27E-10 1.37E-06 6:02E&06 Ru-106 8.64E-06 O.OOE+00 1.09E-06 O.OOE+00 1.67E-05 1.17E-03 1.14E-04 E1-209 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page 148 of 195 Table 7.7 -INHALATION DOSE FACTORS -DFiao (mrem/pCi inhaled)(Page 2 of 8)ADULT Nuclide bone liver total body thyroid kidney lung GI-LLI Ag-1I0m 1.35E-06 1.25E-06 7.43E-07 0.OOE+00 2.46E-06 5.79E-04 3'78E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.OrE+00 3.lOE-04 5.08E-05 Sb-125 6*67E-06 7.44E-08 1.58E-06 6.75E-09 0.OOE-+00 2.18E'04 1.26E-;05 Sn-125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0.OOE+00 7.37E-05 6.81E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E'04 1.87E-05 Te-127 1.75E-10 8.03E-1I 3.87E-11 1.32E-10 6.37E-10 8.14E&07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1;.45E-04 4.79E&05 Te-129 6.22E-12 2.99E-12 1:55E-12 4.87E-12 2.34E-1i 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1'.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-i3 4.49E-13 1.17E-12 5.46E-1'2 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05, 6.37E-05 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E.06 O.OOE+O0 9.61E-07 1-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E&06 rO.OOE+00

.7.85E-07 1-132 1.45E-07 4.07E&07 1.45E-07 1.43E-05 6.48E-07 O.OOE+O0 58;08&08 1-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 O.OOE+O0 1i11E-06 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0;00E+00, 1.26E'10 1-135 3;35E-07 8.73E-07 3.21E-07 5*60E-05 1.39E-06 O.OOE+00 6.56E-07 Cs-i 34 4.66E-05 1.06E-04 9.10E.05 O.OOE+00 3.59E-05 1.22E-05 1.30E-706 Cs-1 36 4.88E-06 1.83E-05 1.38E-05 O.OOE+O0 1.07E-05 1.50E-06 1..46E,-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 O.OOE+00 2.78E-05 9.40E-,06 1.05E-'06 Cs-138 4.14E-08 7.76E-08 4;05E-08 O.OOE+O0 6.OOE-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 O.OOE+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21 E-07 O.OOE+O0 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 O.OOE+00 8.75E-15 2.42E-07 1.45E-1,7 Ba-142 3.29E&12 3.38E-15 2.07E-13 O.OOE+00 2.86E-15 1.49E-.07 1.96E-26 La-140 4,30&E08 2.17E-08 5.73E-09 O.OOE+00 0.OOE+00 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 O.OOE+00 0.00E+00 7.91E.07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 O.OOE+00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 0.OOE+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 0.OOE+00 2.70E-07 3.51 E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 0.OOE+00 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 0.OOE+00 4.45E-07 2,76E-05 2.16E-05 W-187 1.06E-09 8:85E-10 3.10E-10 0.OOE+00 3163E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 O.00E+00 8.75E-09 4.70E-06 1.49E-05

Reference:

Dose.Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125, Sm-125 are fromnReference 17, Table 8.All others from: Regulatory, Guide 1.109, Table E-7.NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium willactsimilarly in all organs (Reference 24).El-210 WBN OFFSITE DOSE CALCULATION MANUAL Revision, 22 0 (ODCM) Page 149 of 195 Table 7.7 -INHALATION DOSE FACTORS -DFiao (mrem/pCi inhaled)Nuclide H-3 C-14 Na-24 P-32 Cr-51 MW54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-1 01 Ru-1 03 Ru-1 05 Ru-1 06 bone 1.59E-07 3.25E-06 1.72E-06 2.36E-04 O.OOE+00 0.00E+00 O.OOE+00 4.18E-06 1.99E-06 0.OOE+00 0.00E+00 0.OOE+00 7.25E-05 2.73E-1 0 0.OOE+00 4.82E-06 6.04E-12 1.44E-09 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 5.43E-05 1.35E&-02 1.10E-08 1.19E-09 3.73E-07 4.63E-1 1 8.26E-05 1.84E-09 1.69E-08 1.82E-05 1.72E-08 2.32E-06 3.92E-1 1 0.00E+00 1.73E-13 7.40E-1 5 2.63E-07 1.40E-10 1.23E-05 liver 1.59E-07 6.09E-07 1.72E-06 1.37E-05 0.OOE+00 6.39E-06 2.12E-10 2.98E-06 4.62E-06 1.18E707 2.59&E07 1.89E-06 5.43E-06 3.66E-1 I 2.54E-1 0 1.67E-05 1.15E-11 3.39E-09 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 2.38E-05&82E-08 4.40E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 O.OOE+00 0.OOE+00 0.OOE+00 5.73E-06 3.40E-09 1.29E-06 9.72E-1 2 2.11 E-08 4.83E-13 1.05E-14 0.00E+00 0.OOE+00 0.OOE+00 total body 1.59E-07 6.09E-07 1.72E-06 8.95E-06 1.69E-08 1.05E-06 3.15E-11 6.93E-07 1.79E-06 1 .15E-07 3.47E-07 2.48E-06 2.47E-06 1.59E-11 1.06E-10 7.80E-06 8.07E-1 3 3.11E-10 2.28E-06 4.30E-08 5.41 E-08 2.29E-09 1.05E-05 3.40E-08 2.91 E-08 1.56E-06 8.35E-04 4.39E-1 0 5.08E-1 1 1.00E-08 1.77E-12 2.21 E-06 5.36E-1 1 4.65E-10 3.94E-06 1.57E-09 7.08E-07 3.55E-12 4.03E-09 6.24E-12 1.03E-13 1.12E-07 5.42E-1 1 1.55E-06'age 3of 8)TEEN thyroid 1 .59E-07 6.09E-07 1 .72E-06 0.OOE+00 9.37E-09 0.00E+00 0.OOE+00 0.OOE400 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00O 0.O0E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.O0E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE--00 0.OOE+00 0 .00E+00 0.00E+00 0.OOE+00 0.00E+00 O.OOE+00 kidney 1.59E-07 6.09E-07 1.72E-06, 0.OOE+00 3.84E-09 1.59E-06 2.24E-10 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E,-00 8.01 E-1 0 1.08E-05 7.53E-12 2.06E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0,00E+00 O.OOE+00 0.OOE+00 0.OOE+00 8.42E-06 5.15E-09 1.25E-06 1.14E-11 5.14E-08 7.20E-1 2 1.90E-13 9;29E-07 1.76E-10 2.38E-05 lung, 1 ,59E-07 6.09E-07 1.72E-06 0,OOE+00 2,62E-06 2.48E-04 1.90E-06 1.55E-05 1.91 E-04 7.33E-05 1.68E-04 1.09E-03 3.84E-05 1.17E-06 1.39E-06 1 '55E-04 1.98E-07 3:92E-06 0.00E+00 0.OOE+00 0.00E-+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 3.02E-04 2.06E-03.7.59E-06 3.43E-06 3.66E-05 4.00E-07 3.67E-04 3.35E-06 1.04E"-05 3.36E-04 1.62E-05 9.39E-05 4.91 E-07 1.92E-05 1.44E-07 8:34E-08 9.79E-05 2.27E-06 2.01 E-03 GI-.LI 1.59E-07 6.09E-'07 1 .72E-06 1-.16E-05 3.75E-07 8.35E&06 7.18E-06 7.99E-07 2.23E-05 3.93E-06 1.19E-05 3.24E-05 1.77E-06 4.59E-06 7.68E-06 5.83E-06 3.56E&08 2.14E-05 0.00E+00 0.OOE+00 0.00E+00 0.0OE+00 2.21 E-06 3.65E-15 4.22E-1 7 4.64E'05 9.56E-05 3.24E-05 1.49E-05 6.99E-05 3.77E-09 5.11E-05 2.06E-05 7.24E-05 1.86E-05 7.88E-05 1.21 E-05 2.71 E-07 3.36E-05 7.66E-07 1.09E-1 6 1.36E-05 1 .13E-05 1.20E-04 r-El-211 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 150 of 195 Table 7.7 -INHALATION DOSE FACTORS -DFiao (mrem/pCi.

inhaled)(Page 4 of 8)TEEN Nuclide bone liver total body thyroid kidney 'lung GI-LLI Ag-110m 1.73E-06 1,.64E-06 9.99E-07 0.OOE+00 3.13E-06, 8.44E&04 3.41'E-05 Sb-124 5.38E-06 9.92E-08 2.1OE-06 1.22E-08 0.00E+00 4.81E-04 4.98E&05 Sb-125 9.23E-06 1.01 E-07 2.15E-06 8.80E-09 O.OOE+00 3.42E-04 .1.24E-05 Sn-125 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0.O0E+00 1.26E704 7.29E-05 Te-125m 6.1OE-07 2.80E-07 8.34E-08 1.75E-07 0.OOE+00 6.70E-05 9*38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2107E-04 1499E-05 Te-127 2.51E-10 1'.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E&06, 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E705 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E&07 21.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E&09 5.49E-08 2.,97E-05 7.76E-05 Te-131 1.97E&12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.,89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05 1-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.O0E+00 1.14E&06 1-131 4.43E'06 6.r14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.1 -iE07 1-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.OOE+00 1.59E-07 1-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.OOE+00 1.29E&06 1-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0.OOE+400 2.55E-09 1-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E706 0:OOE+00 8&69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 0.OOE+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E&06 2.42E-05 1.71E-05 0.OOE+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 0.OOE+00 3.80E-05 1.51 E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E&08 0.OOE+00 8.28E-08 9.84E-09 3.38E-1'1 Ba-139 1.67E-10 1.18E-13 4.87E-12 0.OOE+00 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.OOE+00 2.85E-09 2.54E&04 2.86E&05 Ba-141 1.78E-11 1.32E-14 5.93E-13 0.OOE+00 1.23E-14 4:11E-07 9.33E,14 Ba-142 4.62E-12 4.63E-15 2.84E-13 0.OOE+00 3192E-15 2.39E-07 5.99E&20 La-140 5.99E-08 2.95E-08 7.82E-09 0.OOE+00 0.OOE+00 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 0.OOE+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 0.OOE+00 1.11E-06 7 67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 0.OOE+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11 E-04 2.53E-04 3.28E-05 0.OOE+00 1.51 E-04 1 67E&03 1-.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 O.00E+00 3.86E-07 6.04E-05 2.V67E05 Pr-144 5.37E-12 2.20E-12 2.72E-13 0.OOE+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41 E-08 0.00E+00 6;28E&07 4.65E-05 2.28E-05 W-187 1.50E-09 1.-22E-09 4.29E-1 0 0.00E+00 0.00E+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 0.OOE+00 1.25E-08 8.11E-06 1.65E-05

References:

/Dose Factorsfor Co-57, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125, Sn-125 are from. Reference.17, Table 8.All others from: Regulatory Guide 1.109, Table E-8.NOTE: The tritium dose factor for bone is assumed to be equal ,to the total body dose factor. This assumes that:tritium will act similarly in all organs (Reference 24).El-212 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page 151 of .195 Table 7.7 -INHALATION DOSE FACTORS -DFiao (mrem/pCi inhaled)(Page 5 of 8)CHILD Nuclide bone liver total body thyroid kidney lung GI-LLI H-3 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E&07 3.04E-07 3.04E-07 C-14 9.70E-06 1 .82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 435E&06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E&06 P-32 7T04E-04 3.09E-05 2.67E-05 O.OOE+00 O.OOE+00 O'.OOE+00 1.14E-05 Cr-51 0.OOE+00 O.00E+00 4.17E-08 2.31E-08 6.57E-09 4.59EL06 2.93E&07 Mn-54 0.OOE+00 1.16E-05 2.57E-06 O.OOE+00 2.71E-06 4.26E,-04 6.19E'06 Mn-56 0.00E+OO 4.48E-10 8.43E-11 O.OOE+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 O.OOE+00 0.00E+00 3.00&E05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 O.OOE+00 O.OOE+00 3:43E04. 1.91;E-05 Co-57 O.OOE+00 2*44E-07 2.88E-07 O.OOE+00 O.OOE+00-1.37E-04 3-58E-06 Co-58 O.OOE÷00 4.79E-07 8.55E-07 O.OOE+00 O.OOE00 2.99E-04 9.29E-06 Co-60 O.OOE+00 3155E706 6.12E-06 O.00E+00 O.OOE+00 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 O.OOE+00 Or.OOE+00 7.43E-05 1.71 E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 O.OOE+00 O.QOE+00 2.21E-06 2.27E-05 Cu-64 O.OOE+00 5.39E-10 2.90E-10 O.OOE+00 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 O.OOE+00 1.93E-05 ' 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 O.OOE+00 1*58E-11 3.84E-07 2.75E-06 Zn-69m 4.26E-09 7.28E-09 8.59E-10 O.OOE+00 4;22E-09 7.36E-ý06 2.71iE-05 Br-82 0.00E+00 0.00E+00 5.66E-06 0.OOE+00 O.OOE+00 0OOE-OO Br-83 0.OOE+00 O.OOE+00 1.28E-07 O.OOE E+00 0;00E+0O O.OOE+00 O.OOE+00 Br-84 O.OOE00 O.OOE+00 1.48E-07 O.OOE+÷00 OOOE+OQ 0.00E-O.00:

OE:OE00 Br-85 0.00E+00 O.OOE+00 6.84E-09 O.OOE+00 O.0OE+00 0.OOE+00 0.O0E-00 Rb-86 O.OOE+00 5.36E-05 3.09E-05 O.OOE+00 O.OOE+00 O.Q0E+.00 2.16E-06 Rb-88 O.OOE+00 1.52E-07 9.90E-08 O.OOE+00 O.OOE+00 0,00E+00 4*66E-09 Rb-89 O.OOE+00 9.33E-08 7.83E-08 O.OOE+00 O.OOE+00 0:OOE+00 5.11E-10 Sr-89 1 .62E-04 O.OOE+00 4.66E-06 O.OOE+00 0.00Ei-00 5:83E704 4.52E-05.Sr-90 2.73E-02 O.OOE+00 1.74E-03 O.OOE+00 O.OOE+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 O.OOE+00 1.24E-09 O.OOE+00 O.00EO00 1.44E-05 4.70E-05 Sr-92 3.54E-09 O.OOE+00 1.42E-10 O.OOE+00 O.OE+OO 6.49E-06 6*55E-05 Y-90 1.11E-06 0.OOE÷00 2.99E-08 O.OOE+00 0OOE+00 7 07E-05 7.24E-05 Y-91rm 1.37E-10 O.OOE+00 4.98E-12 O.OOE+00 0.00E+00 7.60E-07 4,64E-07 Y-91 2.47E-04 O.OOE00 6.59E-06 O.OOE+00 O.OOE-0i0 7.10E"04 4.97E&05 Y-92 5.50E-'09 0.00E+00-1.57E-10 O.OOE+00 O.OOE+00 6.46E406 6.46E-05 Y-93 5.04E-08 O.00EO00 1.38E-09 O.OOE+00 0.00E+00 201:&E05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.OOE-05 O.OOE+00 1.61E-705 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 O.OOE+00 1.05E-08 3.06E-05:

9.49EQ05 Nb-95 6.35E-06 2.48E-06 1.77E-06 0.00E+00 2.33E-06 1T.66E-04 100E-05 Nb-97 1.16E-10 2.08E-11 9.74E-12 O.OOE+00 2.31E-1l 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 O.OOE+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 O.OOE+00 1.37E-11 2,57E&07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 O.OOE+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 0.00E4-00 2.90E-07 O.OOE+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 O.OE+00 1.50E-10 O.OOE+OO 3.63E-10 4.30E-06 2.69E&05 Ru-106 3.68E-05 O.OOE+00 4.57E-06 O.OOE+00 4.97E-05 3.87E-03 1.16E-04 El-213 WBN OFFSITE DOSE CALCULATION MANUAL Revision.22 0 (ODCM) Page 1520of 1955 Table 7.7 -INHALATION DOSE FACTORS:-

DFiao (mrem/pCi inhaled)(Page 6 of 8)CHILD Nuclide bone liver total body thyroid kidney lung, GI-LLI Ag-1I0m 4.56E-06 3.08E-06 2.47E-06 O.OOE+00 5.74E-06 1.48E103 2.71E-05 Sb-124 1.55E-05 2.OOE-07 5.41E-06 3.41E-08 0100E+00 8.76E-04 4.43E-05 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.OOE+00 6.27E-04 1.09E-05 Sn-125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 O.OOE÷00 2.43E704 7.17E705 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.OOE+00 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E704 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94Eý11 7.93E,07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E:-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 1-130 2.21.E-06 4.43E-06 2.28E-06 4.99E-04 6.61 Er06 0.00E+00 1.38E'06 1-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00Ei-00 7.68E-07 1-132 5.72E-07 1.1OE-06 5.07E-07 5.23E-05 1.69E&06 0.OOE+00 8.65E-07 1-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.OOE+00 1.48E-06 1-134 3.17E-07 5.84E&07 2.69E-07 1.37E-05 8.92E-07 O:0OE+00 21.58E-07 1-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0.OOE+00 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 0.OOE+00 8.93E&05 3.27E-05 1 .04E-06 Cs-136 1V76E-05 4.62E-05 3.14E-05 O.OOE+00 2.58E-05 3:93E-06 1.13E706 Cs-137 2.45E-04 2.23E-04 3.47E-05 O.0OE+00 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 0.OOE+00 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 O.OOE+00 2.33E-13 1.56E-06 1.56E&05 Ba-140 2.OOE-05 1.75E-08 1.17E-06 0.OOE+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 0.OOE+00 2.56E-14 7.89E 07 7.44E-08 Ba-142 1.35E-11 9173E-15 7.54E-13 0.OOE+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.OOE+00 0.OOE+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 0.00E+00 0.00E+00' 2.35E-06 2:05E&05 Ce-141 1.06E-05 5*28E-06 7.83E-07 O.OOE+00 2.31E-06 1:.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 0.OOE+00 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 O.OOE+00 3.17E'04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 0.OOE+00 8.11E-07 1.17E-04 2.63E705 Pr-144 1.61E-11 4.99E-12 8.10E-13 0.OOE+00 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 0.OOE+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.611E-09 1.17E-09 0.OOE+00 0.OOE+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 O.OOE+00 2.63E-08 1.57E-05 1.73E705

Reference:

Dose Factors for Co-57,.Zn-,69m, Br-82, Nb-97, Sb-124, Sb-125, Sn-125 are from Reference 17,'Table 8.All others from: Regulatory Guide 1.109, Table E-9.NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium will act similarly in all organs (Reference 24).E1 -214 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 153 of 195 Table 7.7 -INHALATION DOSE FACTORS- Dfiao (mrem/pCi inhaled)Nuclide H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-1 06 bone 4.62E-07 1.89E-05 7.54E-06 1.45E-03 0.OOE+00 0.00E+00 O.00E+00 1.41 E-05 9.69E-06 0.OOE+00 0.OOE+00 0.00E+00 2.42E-04 1.71 E-09 0.00E+00 1.38E-05 3.85E-1 1 8.98E-09 O.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 2.84E-04 2.92E-02 6.83E-08 7.50E-09 2.35E-06 2.91 EA10 4.20E-04 1.17E-08 1.07E-07 8.24E-05 1.07E-07 1.12E-05 2.44E-10 0.00E+00 9.98E-13 4.65E-14 1.44E-06 8.74E-10 6.20E-05 liver 4.62E-07 3.79E-06*7'54E-06 8;03E+05 O.OOE+00 1.81 E-05 1.1OE-09 8.39E-06 1.68E-05 4.65E-07 8.71 E-07 5.73E-06 1.46E-05 2.03E-10 1 34E-09 4.47E-05 6.91E-11 1.84E-08 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 1.36E-04 3.98E-07 2.29E-07 0.00E+00 0OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 1.99E-05 1.83E-08 4.59E-06 5.21 E-11 1.18E-07 2:06E41 2 5.88E-14 0.OOE+00 0.00E+00 0.OOE+00 (Page 7 of 8)INFANT total body thyroid 4.62E-07 4.62E-07 3.79E-06 3.79E-06 7.54E-06 7.54E-06 5.53E-05 0.OOE+00 6.39E-08 4.11E-08 3.56E-06 0;00E+00 1.58E-10 0 OOE+00 2.38E-06 0.OOE+00 6.77E-06 0.OOE+00 4 58E-07 0.00E+00 1 .30E-06 0.00E+00 8.41 E-06 0.00E+00 8.29E-06 0.OOE+00 8.79E-1 1 0.OOE+00 5.53E-10 0.OOE+00 2.22E-05 0.00E+00 5.13E-12 0.O0E+00 1.67E-09 0.OOE+00 9.49E-06 0.OOE+00 2.72E-07 0.00E+00 2.86E-07 0.OOE+00 1.46E-08 0.OOE+00 6.30E-05 0.00E+00 2.05E-07 0.00E+00 1.47E-07 0.00E+00 8.15E-06 0.OOE+00 1.85E-03 0.OOE+00 2.47E-09 0;OOE+00 2.79E-10 0.OOE+00 6.30E-08 0.00E+00 9.90E-12 0.OOE+00 1.12E-05 0.OOE+00 3.29E-10 0,00E+00 2.91 E-09 0.00E+00 1.45E-05 0.00E+00 8.36E-09 0.00E+00 2.70E-06 0.OOE+00 1.88E-1 1 0.00E+00 2.31 E-08 0.OOE+00 2.66E-11 0.OOE+00 5.80E-13 0.00E+00 4.85E-07 0.00E+00 2.93E-10 0.00E+00 7.77E-06 0.OOE+00 kidney 4.62E-07 3.79E-06 7.54E-06 0.00E+00 9.45E-09 3.56E-+06 7.86E-10 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE÷00 2.84E-09 2.32E-05 2.87E-1 1 7.45E-09 0.OOE+00 0.00E+00 0.OOE+00 0OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00.OOE+,00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.22E-05 1.85E-08 3.37E-06 4.07E-11 1.89E-07 2.22E- 1I 6.99E-1 3 3.03E&06 6.42E-10 7.61 E-05*lung 4.62E'-07 3.79E&06, 7.54E406 0.00E*00 9.17E-06 7.14E-04 8.95E-06 6.21E-05 7.25E-04 2,71E'04 5.55E-04 3.22E-03 1.49E-,04 5.80E&06 6.64E-06 4.62E-04 1.05E-06 1.91E-05 0.00E+00 0.OOE+00, 0.OOEt-00 0.OOE+00 0.OOE+00 0OOE(00 0.OOE+00 1.45E-03 8.03E-03 3.76E-705 1.70E-05 1.92E-04 1.99E-06 1.75E703 1.75E-05 5.46E-05 1.25E-03 7.88E&05.3.42E-04 2.37E-06 9.63E-05 5.79E-07 4.17E-07 3'94E-04 1.12E-05 8.26E-03 GILLI 4.62E-07 3.79E-06 7. 54E-06 1.15E-05 2,55E&07 5.04E-06 5,12E-05 7.82E-07 1.77E-05 3;47E-06 7.95E-06 2.28E&05 1.73E-06 3.58E-'05 1.07E'-05 3.67&E05 9.44E-06 2.92E-05 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 2.17E-06&2.42E707 4.87E-08 4.57E705 9.36E-05 5;24E-05 1.00E-04 7.43E'05 1;68E-06 5.02E-05'9*04E-05 1.19E-04 1.5:5E-05 1.OOE-04 9.05E-06 1.92E-05 3:48E&05 1 45E-06 6.03E-07 1. 15E-05 3.46E705 E1-215 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 154 of 195 Table 7.7 -INHALATION DOSE FACTORS -Dfiao (mrem/pCi inhaled)Nuclide Ag-110m Sb-124 Sb-125 Sn-125 Te-125m Te-127m Te-127 Te-t29m Te-129 Te-131m Te-1 31 Te-132 1-130 1-131 1-132 1-133 1-134 1-135 Cs-134 Cs-1 36 Cs-1 37 Cs-1 38 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 7.13E-06 2.71E-05 3.69E-05 1.011E.-05 3.40E-06 1.19E-05 1.59E-09 1i'01E-05 5.63E-1 1 7.62E-08 1.24E-1I 2.66E-07 4.54E-06 2.71 E-05 1.21E-06 9.46E-06 6.58E-07 2.76E-06 2.83E-04 3.45E-05 3.92E-04 3.61 &07 1.06E-09 4.OOE-05 1.12E-10 2.84E-11 3.61E-07 7.36E-10 1.98E-05 2.09E-07 2.28E-03 1.OOE-05 3.42E-i 1 5.67E-06 9.26E-09 2.65E-07 liver 5.16E-06 3.97E-07 3.41 E-07 2.51 E-07 4.93E-06 6.81 E-10 4.35E-06 2.48E- 1 3.93E-08 5.87E-12 1.69E-07 9.91 E-06 3.17E-05 2.53E-06 1.37E-05 1.34E-06 5.43E-06 5*02E-04 9.61 E-05 4.37E-04 5.58E-07 7.03E-13 4.OOE-08 7.70E-14 2.36E-14 1,.43E-07 2.69E-1 0 1.19E-05 1.38E-07 8.65E-04 3.74E-06 1.32E-11 5.81 E-06 6.44E-09 2.37E-08 (page 8 of 8)INFANT total body thyroid 3.57E-06 0.OOE+00 8.56E-06 7.18E-08 7.78E-06 4.45E&08 6.OOE-07 2.47E-07 4.70E-07 1.16E-06 1.48E-06 3.48E-06 3.49E-10 1.32E-09 1.59E-06 3.91E-06 1.34E-11 4.82E-11 2.59E-08 6.38E-08 3.57E-12 1.13E-11 1.26E-07 1.99E-07 3.98E-06 1.14E-03 1.40E-05 1.06E-02 8.99E-07 1.21 E-04 4.OOE-06 2.54E-03 4.75E-07 3*18E-05 1.98E-06 4.97E-04 5.32E-05 0.OOE+00 3.78E-05 0.OOE+00 3.25E-05 0.OOE+00 284E-07 0.OOE+00 3.07E-1 1 0.OOE+00 2.07E-06 0.OOE+00 3.55E-12 0.OOE+00 1.40E-12 0.OOE+00 3.68E-08 0.OOE+00 6.46E-1 1 0.OOE+00 1.42E-06 0.OOE+00 1.58E-08 0.OOE+00 1.26E-04 0.OOE+00 4.99E-07 0.OOE+00 1.72E-12 0.00E+00-3.57E-07 0.OOE+00 2.23E-09 0.OOE+00 1.34E-08 0.OOE+00 kidney 7.80E-06 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 2.68E-05t 3.47E-09'2.27 E-05 1.25E-10 1.89E-07 2;85E-t 1 7.39E&07 1.09E-05 3.70E-05 2.82E-06 1 .60E-05 1.49E-06 6.05E-06 1.36E-04 4,03E-05 1.23E-04 2.93E-07 4.23E-13 9.59E-09 4.64E-14 1.36E-14 O.OQE+O0, 0.OOE+00 3.75E-06 4.03E-08 3.84E-04 1.41 E-06 4.80E-12 2.25E-06 O.OOE+00 4.73E-08 lung 2.62E-03 1.89E-03 1.17E-03 6.43E- 04 3.19E-04 9.37E-'04 7:39E-06 1.20E-03 2.14E-06 1.42E-04 1.47E-06 2.43E-04 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 5.69E905 8.40E-06 5;09E-05 4.67E-08 4.25E-06 1 .14E-03 2.12E-06 1.11E-06 1;.20E-04 5.87E496 3.69E&04 8.30E&65 7.03E-03 3.09E-04 1 .15E-06 2.30E-04 2.83E-05 4.25E-05 GI-LLI 2.36E-05 4.22E-05 1,05E-05 7.26E-05 9.22E-06 1.95E-05 1.74E-05 4.93E"05 1.88E-05 8.51 E-05 5.87E-06 3.15E-05 1.42E-06 7.56E-07 1 .36E-06 1-.54E&06"9.21 E-07 1.31 E&06 9.53E-07 1.02E-06 9.53E-07 6.26E&07 3.64E-05 2.74E-05 3.39E-06 4.95E-07 6&06E-05 4.25E-05 1.54E705 3.55E-:05 1.06E-04 2.66E-05 3.06E-06 2.23E-05 2.54E705 1.78E-05

Reference:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-1 All others from: Regulatory, Guide 1.109, Table E-10.24, Sb-125, Sn-125 arefrom Reference 17, Table 8.NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor. This assumes that tritium willact similarly in all organs (Reference 24).El-216 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 155 of 195 Figure 7.1 -GASEOUS EFFLUENT RELEASEI/ISCHARGE POINTS Condenser Service Vacuum Building Exhaust Vent (one per (common)unit)Waste Gas Decay Tanks (9)Containment Purge System (one per unit)Shield Building Vent (one per unit)El-217 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 156 of,195 Figure 7.2 -DETAIL OF GASEOUS RELEASE/DISCHARGE POINTS.c.C,4'E c CI >x >*EM>0 X(D";c -LU C 0 0)0 <(LC LL Z M )'E 0 0 0 aU)El-218 WBN OFFSITE DOSE CALCULATIONMANUAL Revision 22 0 (ODCM) Page 157 of 195 Figure 7.3 -GASEOUS RADWASTE TREATMENT SYSTEM J!El-219 WBN OFFSITE DOSE CALCULATION MANUAL Revision.22 0 (ODCM) Page 158 of 195 Figure 7.4 -PLUME DEPLETION EFFECT FOR GROUND LEVEL.RELEASES (All Stability Classes)0D E 2 CL E 0)0 r-C 0 Q.0.1 1.0 10.0 PLUME TRAVEL DISTANCE (KILOMETERS) 100.0 200:0 Source: Reference 5, Figure 2 E1-220 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Pagel59of 195 Figure 7.5 -VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 1000___E2EF1EFFEHE1EfEV~Ti I .I 1,II J U)Lu z 0 w z U)100 10 1 .4 "1 1 7-77 F A.1oo Llorll, 1A .0--, -lei I x-.00 Jol 10, A- G ZD tal) 111 L)1 0.1 1.0 1,0 100 PLUME TRAVEL DISTANCE:.(KILOMETERS)

Source: Reference.5, Figure 1 E1-221 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 160 of 195 Figure 7.6 -RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES (All Stability Classes)1E-03 LU Ir LU CL 0~LU x.IE-.04 1IE-05 1IE-06 1 E-07 0.1 1.0 10.0 100;0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS.)

Source: Reference 5, Figure 6 E1-222 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 161 of 195 8.0 -TOTAL DOSE 8.1 TOTAL MAXIMUM INDIVIDUAL DOSES To determine compliance with 40.CFR 190 as required in ODCM Surveillance Requirement and 2.2.3.2, the dose contributions to themaximum individual from WBN radioactive effluents and .all other nearby uranium fuel cycle sources will be considered.

The annual doseto the maximum individual will be conservatively estimated by using the following equation: 4 D = S D(airtb) + D(airorg)

+ D(liqtb) + D(liqorg)

+ D(direct)

(8.1)q=1 where: q = calendar quarter D(airtb) = the total body air submersion dose (as calculated in Section 7.7)D(airorg)=

the critical organ dose from gaseous effluents (as calculated in Section 7.7), D(liqtb) = the total body dose from liquid effluents (as calculated-in Section 6.6.4), D(liqorg)

= the critical organdose from liquid effluents(ascalculated in Section. 6;6.4), D(direct)

= the directradiation dose measured by the environmental monitoring program.The dose calculated is compared to the total body/organ limit of 25 mrem. If the dose is greater than 25 mrem, then the dose to each individual organ will be evaluated separately for comparison to the limits.El-223 WBN OFFSITE DOSE CALCULATION:

MANUAL Revision,22 0 (ODCM) Page 162 of 195 9.0 -RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)9.1 MONITORING PROGRAM DESCRIPTION The REMP shall be conducted in accordance with the requirements of ODCM Control 1.3:1. The monitoring program described in Tables 9.1, 9.2, and 9.3, and in Figures 9:1, 9.2 and 9.3 shallbe conducted.

The program consists.of 3 major sections corresponding to the atmospheric pathway, the terrestrial pathway, and thewaterborne.pathway.

In the atmospheric monitoring program, samples of air particulates and atmospheric radioiodines are collected from established stations.

The stations are identifiedas Local Monitor (LM) stations, located at or near the unrestricted area boundary; Perimeter Monitor (PM) stations, located typically3-10 miles from the site; and Remote Monitor (RM) stations, located greater than 10 miles from the site, The remote monitors areconsidered as, background or control stations.The terrestrial monitoring program includes the collection of milk, soil, and food crops. In addition, direct gamma radiation levels will be measured in the vicinity of the plant.The waterborne monitoring program consists of the collection of samples of surface and ground water;drinking water, sediment, and fish. Samples are collectedboth downstream and upstream from .the plant site.The basic description of the.REMP is included in Tables 9.1 and 9.2. Table 9.3 describes the'locations of the direct gamma radiation detectors (dosimeter).

Figures 9.1, 9.2, and 9.3 show'theilocations of the stations within one mile of the site, between one and five miles from the site, and greater than'5 miles from the site, respectively.

Deviations are permitted from the required sampling schedule if specimens are.unobtainabledue~to hazardous conditions, sample unavailability, or malfunction of sampling eqUipment.

If-the latter;, every effort shall be made to complete corrective action prior to the end of the nextsampling period. Deviations from the required program will be reported in the Annual Radiological Environmental Operating Report in accordance with the provisions of ODCM Control 1.3.1.a and AdministratiVe Control 5.1. Changes made in the program resulting from unavailability of samples will be reported in accordance with ODCM Control 1.3.1.c.9.2 DETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 2.3-3 are'achieved.

9.3 LAND USE CENSUS A land use survey shall be conducted in accordance with the requirementsgiven in ODCM Control 1.3.2.The results of the survey shallbe reported -in the Annual Radiological Environmental Operating Report.Changes made in the REMPas a result of the Land Use'Census will be reported in accordance with the provisions of ODCM Control 1.3.2.b.E1-224 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 163 of 195 9.4 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an Inter!aboratory Comparison Program which has been approved by the NRC. A summary of the results obtained ih the intercomparison shall be included in the Annual Radiological Environmental Operating Report '(or the EPA program code designation may be provided).

If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported in the Annual Radiological Environmental Operating Report.9.5 DATA REVIEW AND REPORTING Results of this program shall be reported inaccordance with ODCM Administrative Control. 5ý1,Annual Radiological Environmental'Monitoring Report. Analytical, results exceeding the reporting levels outlined in ODCM'Table 2.3-2 will be reported in accordance with the requirements of ODCM Control. 1"3.1..b.

As noted in WBN FSAR Section 11.6, routine releases from WBN will result in environmental, concentrations well below, the detection limits for environmental media, making correlations between calculated, effluent'release dataand environmental measurements impractical.

Onlyif radioactive releases from the site result in statistically measurable increases in environmental levels candosecorrelations be made.E1-225 WBN OFFSITE DOSE CALCULATION MANUAL Revision.22 0 (ODCM) Page 164of 195 Table 9.1 -REMP -MONITORING, SAMPLING, AND ANALYSIS (Page 1 of 5)Exposure S Sample LocationsI Sampling and Typeaand Frequency of Pathway Collection Frequency Analysis and/or Sample, 1. DIRECTRADIATION 2 or more dosimeters Once per 92 days Gamma dose at least placed at locations (in once per 92 days different sectors) at or near the unrestricted area boundary in each of the 16 sectors.2 or more dosimeters placed at stations located approximately 5 miles from the plant in each of the 16 sectors 2 or more dosimeters in at least 8 additional locations of special interest, including at least 2 control stations.E1-226 WBN OFFSITE DOSE CALCULATION MANUAL Revision.22 0 (ODCM) Page 165:of 195 Table 9.1 -REMP -MONITORING, SAMPLING, AND ANALYSIS (Page 2 of 5)Exposure Sample Locations 1 Sampling and Type and Frequency of Pathway Collection Frequency Analysis and/orSample

2. AIRBORNE Particulates 4 samples from locations Continuous sampler Particulate samples: and (in different sectors)at or operation with Analyze.forlgross beta, Radioiodines near. the unrestricted area sample collection radioactivity

_> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> boundary once per 7 days following filter change.(LM-1,2,3,and

4) (more frequently if Perform gamma required by dust isotopic analysis on 4 samples from loading) each sample if gross communities beta > 1,0 times that of approximately 6-10 miles control sample.distance from the plant.(PM-2,3,4,and
5) Composite at least once per. 31 days, (by 2 samples from control location) for gamma locations greater than 10 scan.miles from the plant (RM-2 and 3)Radioiodine cartridge:

1-131 at least once per 7 days Atmospheric 4 samples from locations Continuous sampler Analyze each-sample Moisture* (in different sectors) at or operation with for H-3 near the site boundary sample collection (LM-1,2i3,and

4) biweekly 2 samples from communities approximately 4-10 miles distance from the plant.(PM-2,5,)1 sample from control location greater than 10 miles from the plant (RM-3)Soil Samples from same Once per year Gamma scan; Sr-89, I :location as air particulates.

I Sr-ý90 once per year E1-227 WBN OFFSITE DOSE CALCULATIONMANUAL Revision 22 0 (ODCM) Page 166 of 195 Table 9.1, -REMP -MONITORING, SAMPLING, AND-ANALYSIS (Page 3 of 5)Exposure Sample LocationsI Sampling and Type and Firequency.

of Pathway Collection Frequency Analysis and/or Sample.3. WATERBORNE Surface TRM 529.3 Collected by Gamma scan and H-3 TRM 523.1 automatic sequential-analysis of each TRM 517.9 type sampler 2 with sample composite samples collected atileast once per 311 days Ground 5 sampling locations from Collected.by Gross beta, gamma ground water monitoring automatic sequential-scan, and H-3 analysis wells adjacent to plant type sampler with of each sample composite samples 1 samplinglocation from collected at'least groundwater source once per 31 days upgradient from the plant Drinking 1 sample at the first Collected by Gross beta, ,gamma potable surface water automatic sequential scan, and H-3 analysis supply downstream from type sampler 2 with of each sample the plant (TRM 503.8) composite sample collected at least 1 sample at the next once per 31 days downstream potable surface water supplier (greater than 10 miles downstream) (TRM 473.0)1 sample at control location 3 (TRM 529.3)Shoreline TRM 513, TRM 530.2 At least once per 184, Gamma'scan of each days sample.Pond One sample-from at least Annually Gamma scan of each Sediment three locations in Yard sample.I Holding Pond.E1-228 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) PageA167 Of 195 Table 9.1 -REMP -MONITORING, SAMPLING, AND ANALYSIS (Page 4 of 5)Exposure Sample LocationsI Sampling and Type and Frequency of Pathway Collection Frequency Analysis and/or Sample 4. INGESTION Milk 1 sample from milk At least once per 15 Gammaisotopicand producing animals in each days 1-131 analysiszof each of 1-3 areas indicated by sample. Sr-89, Sr-90 the cow census where once per quarter doses are calculated to be highest. If samples are not availablefrom a milk animal location, doses to that area may be estimated by projecting the doses from concentrations detected in milk from other sectors or samples of vegetation may be taken monthly where milk is produced but is not available.

At least 1 sample from a control location Fish One sample of At least once per 184 Gamma scan on edible commercially important days. portion.species and one sample of recreationally important species. One sample of each species from downstream of Watts Bar Nuclear Plant, Chickamauga reservoir, and Watts Bar reservoir.

Food 1 sample each of principal At least once per 365 .Gamma scan onedible Products food products grown at days at the time of portion.private gardens and/or harvest. The types of farms in the vicinity of the foods available will plant. vary. Following is a list of typical foods which may be available:

Cabbage and/or Lettuce Corn Green Beans Potatoes Tomatoes E1-229 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) of 195 I Table 9.1 -REMP -MONITORING, SAMPLING, AND ANALYSIS (Page 5 of 5)Exposure Sample Locations 1 Sampling'and Type and&Frequency of Pathway Collection Frequency Analysis and/or Sample .I..Vegetation4 Samples from farms At least once per 31 1-131 aridgamma~scan producing milk but not days at least once per: 31 providing.

a milk sample days.1 Sample locations are listed in Tables 9.2 and 9.3 and shown on Figures 9.1, 9.2 and 9.3.2 Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.3 The surface water sample collected at TRM 529.3 is considered a control for the raw drinking water sample.4 Vegetation sampling is applicable only for farms that meet the criteria for milk sampling and When milk samplingr cannot be performed.

Other Notes: LM = Local Monitor PM = Perimeter Monitor RM = Remote Monitor TRM = Tennessee River Mile E1-230 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 169 of 195 Table 9.2 -REMP -SAMPLING LOCATIONS Map Stationa Sector Approximate Indicator(!)

fSamples Location Distance or Collectedb Number I (mi) Control(C) 2 PM-2 NW 7.0 1 ;AP, CF, S, AM 3 PM-3 NNE 10-4 I :AP, CF, S 4 PM-4 NE/ENEc 7.6 I AIP;'tFý, S 5 PM-5 S 8.0 I AP, CF, S, AM 6 RM-2 SW 15.0 C AP, CF; '7 RM-3 NNW 15.0 C APICF, S,___________________

________AM 8 LM-1 SSW 0.5 1 AP, CF, S, AM 9 LM-2 NNE 0.4 I AP, CF, S, AM 10 LM-3 NNE 1.9 1 AP, CF, S, AM 11 LM-4 SE .0.9 1 AP",CF, S, AM 12 Farm L SSW 1.3 Id M,.W 15 Farm K ENE 11.6 C M 18 Well #1 S 0.6 I W 20 Farm.N ESE 4.1 I M 22 Farm EH SSW 24.0 C M 23 Well#5 N 0.5 .C W 25 TRM 517.9 -9 9 e I SW 26 TRM 523.1 -4.7 e I SW 27 TRM 529.3 -1.5e C SW, PW 31 TRM 473.0 (C.F. Industries)

-5 4.8 e I PW 32 TRM 513.0 -1 4 8 8e I SS 33 TRM 530:2 -2.4 e C SS 35 TRM 503.8. (Dayton) -2 4.0 e I ýPW 37 TRM 522.8-527.8 (Downstream of -I F WBNP)38 TRM 471-530 (Chickamauga Lake) -I F 39 TRM 530-602 (Watts Bar Lake) -C ._E 81 Yard Pond SSE/S/SSW Onsite I PS 82 Well A SSE 0:6 Ir W 83 WellIB SSE 0.5 I W 84 WelI'C ESE 0.3 1 W 85 Well F SE 0.3 I W a See Figures 9.1, 9.2, and 9.3 b Sample codes: AP = Air particulate filter; CF = Charcoal Filter; F = Fish; S = Soil; AM = atmospheric moisture, M = Milk; PW Public Water; SS = ShorelineSediment; SW = Surface Water; W= Well Water, PS= Pond Sediment c Station located on boundary between these sectors d A control for well water e Distance from plant discharge (TRM 527.8)f The surface .water sample from TRM 529.3 is also considered a control for raw Public Water samples.E1-231 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page 110 of 195 Table 9.3 -REMP -DOSIMETRY LOCATIONS Map Station Sector Approx. On/ Map Station Sector Approx. ,On/Location Dist. Offsitea Location Dist. Offsitea Number (mi) Number (mi)2 NW-3 NW 7.0 Off 55 SSE-1A SSE 0.6 On 3 NNE-3 NNE 10.4 Off 56 SSE-2 SSE 5.8 Off 4 ENE-3 ENE 7.6 Off 57 S-1 S 0.7 On 5 S-3 S 7.8 Off 58 S-2 S 4.8 Off 6 SW-3 SW 15.0 Off 59 SSW-1 SSW. 0.8 On 7 NNW-4 NNW 15.0 Off 60 SSW-3 SSW 5.0 Off 10 NNE-1A NNE 1.9 On 62 SW-I SW 0.8 -On 11 SE-1A SE 0.9 On 63 SW-2 SW 5.3 Off 12 , SSW-2 SSW 1.3 On 64 WSW-1 WSW, 0.9 On 14 W-2 W 4.8 Off 65 WSW-2. WSW 3.9 Off 40 N-1 N 1.2 On 66 W-1 W 0.9 On 41 N-2 N 4.7 Off 67 WNW-1 WNW, 0.9 On 42 NNE-1 NNE 1.2 On 68 WNW-2. WNW 4.9 Off 43 NNE-2 NNE 4.1 Off 69 NW-I NW 1.1 On 44 NE-1 NE 0.9 On 70 NW-2 NW 4.7 Off 45 NE-2 NE 2.9 Off 71 NNW-1 NNW 1.0 On 46 NE-3 NE 6.1 Off 72 NNW-2 NNW 4.5 Off 47 ENE-1 ENE 0.7 On 73 NNW-3 NNW 7.0 Off 48 ENE-2 ENE 5.8 Off 74 ENE-2A ýENE 3.5 Off 49 E-1 E 1.3 On 75 SE-2A SE 3.1 Off 50 E-2 E 5.0 Off 76 S-2A S 2.0 Off 51 ESE-1 ESE 1.2 On 77 W-2A W 3.2 Off 52 ESE-2 ESE 4.4 Off 78 NW-2A NW 3.0 Off 54 SE72 SE 5.3 Off 79 SSE-1 SE 0.5 On a Dosimeters designated onsite (On ) are those located two miles or less from the plant. Dosimeters designated'offsite (Off) are those located more than two miles from the plant.El-232 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 171 of 195 Figure 9.1 -REMP LOCATIONS WITHIN ONE MILE OF THE PLANT ENE 78.75 E 101.25 ESE S Scale O Mile E1-233 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22*0 (ODCM) Page 172 of 195 Figure 9.2 -REMP LOCATIONS FROM ONE TO FIVE MILES FROM THE PLANT.5 -~a 1 E1-234 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 173 of 195 Figure 9.3 -REMP LOCATIONS GREATER THAN FIVE MILES FROMTHE PLANT N 2 Sc~0 ~ 10 15 '~5 25 E1-235 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 174 of 195

10.0 REFERENCES

1. NUREG-1 301, "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Pressurized Water Reactors," Generic Letter 89-01, Supplement No. 1. April 1991.2. Draft NRC Generic Letter, "Guidance for Modification of Technical Specifications to Reflect (a)Revisions to 10 CFR Part 20, 'Standards for Protection AgainstRadiation' and 10"CFR 50;36a,'Technical Specifications on Effluents from Nuclear.Power Reactors', (b)ý Related Current Industry Initiatives and (c) Miscellaneous Related Editorial Clarifications." 3. NUREG-0133, "Preparation of Radiological Effluent Technical Specificationsfor Nuclear Power Plants," September 1978.4. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of-Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.5. Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents inRoutine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.6. Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing 10 CFR Part 50 Appendix I," Revision 1, April 1977.7. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light"Water-Cooled Reactors," Revision 1, June 1974.8. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.9. WBN Final Environmental Statement, WBNP Units 1,2,3, Chattanooga, TN, November 9,1972.10. WBN Final Safety Analysis Report.11. TVA Memorandum, E. E. Driver to R. B. Maxwell, "Watts Bar Nuclear PlantDispersion," December 3, 1984.12. TVA Memorandum, Edwin M. Scott to Betsy Eiford-Lee, "Fish Harvest Estimates for the Revision of the QWATA Computer Code," December 15, 1987.13. TVA Memorandum, D. L. Stone to B. Eiford-Lee, "Surface area Computations for the Revision of the QWATA Code," April 26, 1988.14. TVA Memorandum, R. A. Marker, "Revision to QWATA Computer Code," January 6i 1988.15. DOE-TIC-1 1026, "Radioactive Decay Data Tables -A Handbook of Decay Datafor Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher, 1981.El-236 WBN OFFSITE DOSE CALCULATION MANUAL Revision22 0 (ODCM) Page 175 of 195 16. ORNL 4992, "Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976,.17. NUREG-01 72, "Age Specific Radiation Dose Commitment Factors for a One Year Chronic Intake," November 1977.18. Dose-Rate Conversion Factorsfor External Exposure to Photon .and Electron Radiation from Radionuclides Occurrinq in Routine Releases from Nuclear. Fuel CycleFacilities:

D. C. Kocher, Health Physics Volume 38, April 1980.19. TVA Memorandum, John P. Blackwell to M. L. Millinor, "Development of Atmospheric Dispersion Adjustment Factors for Application in the Watts Bar Nuclear Plant Offsite Dose Calculation Manual," November 16,1990.20. International Commission on Radiological Protection Publication 23, "Report~of.the Task Group on Reference Man," 1975.21. NUREG/CR-1004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides," October 1979.22. "Tennessee Valley Authority Effluent Management System (48-8434)

Technical Reference Manual," Canberra Nuclear -Nuclear Data Systems Division, January 1994.23. TVA Memorandum, M. S. Robinson to Radiological Hygiene Branch Files, "Cross-Sectional Areas of Nuclear Reactor Buildings," November 2, 1977.24. Sequoyah Nuclear Plant Offsite Dose Calculation Manual.25. TVA Quarterly Water Dose Assessment Computer Code Documentation, Revision 2.0, November 1989 26. TVA Memorandum, M. C. Brickey to M. E. Greeno, "Watts Bar NuclearýPlant Offsite Dose Calculation Manual -Changes Required -Revised agreements based on meeting between NuclearnEngineering and Chemistry on March 9, 1994," March 17, 1994 27. TVA Memorandum, Ed Steinhauser and Stan Nelson to Mike Greeno, "Offsite Dose Calculation Manual for Systems 14 and 15," February 10, 1994 28. TVA Memorandum, M. C. Brickey to Mike Greeno, "ODCM Change Request," March 3, 1995 29. NDP-00-0344, Revision 1, "Implementation and Utilization of Tritium Producing BurnableAbsorber Rods (TPBARS) in Watts Bar Unit 1." E1-237 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 176 of 195 11.0 SOURCE NOTES SOURCE NOTE Source Document Summary 1 NC0850192001 2 NRC IE Bulletin 82-49 SQN LER 50-327/92019 3 4 NC0920030880 5 NC0920042424 6 NC0920042422 7 NC0920042500 8 NC0920042501 9 NC0920042502 10 NC0920042423 11 WBPER960319 TVA response as described in NRC evaluation SER No. 5, Section 11.7, paragraph 4.Adjust noble gas monitor setpoints based on chamber pressure.Source Note deleted and calibration interval changed to 18 months per NE SSD 1-F-90-400A,BC,D,-452 and 2-F-90-400C,-452.

Specifications will ensure compliance with 10 CFR 50.34a (ALARA) and to ensure that concentrations of radioactive effluents released to unrestricted areas are within the limits specified in 10 CFR 20.106 (20.1301).

The reporting requirements of 50.36a (a)(2) will also be included in these specifications.

To ensure compliance with RadiologicalEffluent Tech Specs, cumulative dose calculations wilkbe performed once per month.ODCM shall contain Radiological Environmental Monitoring Program sampling and analysis frequencies.

Dose Calculations will be performed monthly to ensure that the dose rate in unrestricted areas due to gaseous effluents from the reactor at the site will be limited to the prescribed values.A complete analysis utilizing the total estimated liquid release for each. calendar quarter will be performed and reported as required by Technical Specifications.

Dose projections will be performed in accordance with Technical Specifications.

Post-release analysis will be done using actual release data to ensure that limits were not exceeded.

This data and setpoints will be recorded in auditable records by plant personnel.

Operability requirements for Kurzisokinetic sampling panels will be added to the ODCM.El-238 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 177 of .195 SOURCE NOTE Source Document Summary 13 WBPER970486 NCO970059002 NC0970059004 15 WBPER970492 16 WBPER971422 17 WBPER970332 Added operability requirements for heat trace~on iodine/particulate sample lines forCondenser Vacuum Exhaust and Shield Building Exhausts.Changed allowable monitor tolerance factor to 2.0for gaseous monitor setpoint calculations.

Changed submittal requirements to correspond to CFR requirements.

Changed maximum design release flow rate for WGDT from 55 cfm to 100 cfm to reflect; current'design output.E1-239 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page 178of 195 APPENDIX A -NOTATION CONVENTIONS (Page 1 of 7)Symbol Key This symbol key providesa cross-reference between'the symbols used in the Watts Bar ODCM and those symbols used in the Regulatory Guidance documents~for the ODCM (References 1, 2; 3; 4, and 5).The Watts Bar symbol is given, along with a definition of the term; then the reference document is given for that term, along with the corresponding symbol used in that reference.

Some terms may be subscripted in the WBN ODCM text and in the regulatory document.

For simplification, no subscripts are included in this symbol key. The use of subscripts is~standard'.throughout the WBN ODCM as follows: subscript a: subscript i: subscript j: subscript k: subscript I: subscript m: subscript P: subscript r: age group radionuclide (Tis used to denote tritium)organ windspeed category Pasquill stability class Public Water Supply or population element dose pathway river reach WBN ODCM Source Symbol Definition Source Reference Symbol_a Minimum buildingcross-sectional area R.G. 1.111 (p. 11) DZ2 A Liquid dose factor NUREG-0133,(p.

15) A a Cumulative dose for a quarter N/A ADC Average decay correction N/A AF Allocation Fraction N/A APR Size of river reach N/A AF Dose factor for fish ingestion NUREG-0133;(p.

15)AR Dose factor for shoreline recreation N/A ATMW Ratio of average'to maximum ingestion N/A rates BKG Background N/A B Bioaccumulation factor NUREG-0133 (p. 16) BF b Projected dose for a release N/A Biv Transfer factor for nuclide i from soil to R.G. 1.109 (p. 3) Biv vegetation BR Breathing rate ,NUREG-0133 (p. 25) BR c Air concentration R.G. 1.10 9 (p. 25) c c Any anticipated additional dose in the N/A next monthfrom other sources C Concentration NUREG-0133 (p. 15) C X/Q Relative concentration R.G. 1.109 (p. 5) X,/Q El-240 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 179-of 195 I APPENDIX A -NOTATION CONVENTIONS (Page 2 of 7)Symbol Key WBN ODCM Source.SymbolT Definition Source Reference Symbol., d Number of days in the current quarter prior N/A to the time of a release D Dose NUREG-0133 (p. 15) D DNF Near-field dilution NUREG-0133'(p.

15) F D/Q Relative deposition R.G. 1.109 (p. 24) d DFB Dose Conversion Factor for total body R.G. 1.109 (p.6) DFB submersion DFb Dose Conversion Factor for beta air dose R.G. 1.109 (p. 5) DEb DFG Dose conversion'factor for standing on NUREG-0133 (p. 26) DFG contaminatedground DFg Dose conversion:'factor for gamma air dose R.G. 1.109 (p. 5) DFg DF Ingestion dose conversion factor NUREG-0133 (p. 16, 33) DF, DFL DFA Inhalation DoseConversion Factor NUREG-01:33 (p. 25) DFA DFS Dose conversion factor for skin R.G. 1.109 (p.6) DFS submersion dose DR Dose rate N/A dr Relative deposition rate R.G. 1.111.(p.
12) dr E Efficiency NUREG-1301 (p. 40) E ECL Effluent Concentration Limit N/A ER Expected Monitor Response N/A F Dilution flow NUREG-0133 Addendum A F f Waste flow NUREG-0133 Addendum A f Ff Transfer factor from cow's feed to beef R.G. 1.109 (p. 28) Ff fa Fraction of stored vegetables grown locally R.G. 1.109 (p. 7) fa FISH Average amount of fish ingested N/A fkI Joint relative frequency of occurrence of R.G. 1.111 (p. 9) n/N winds in windspeed class k and stability class I fL Fraction of fresh leafy vegetables grown R.G. 1.109 (p. 7) FI locally Fm Transfer factor from animal's feed to milk R.G. 1.1091(p.
27) Fm fP Fractionof population in an age group R.G. 1.109 (p. 30) f f,) Fraction of time animal spends on pasture R.G. 1.109 (p. 28) fp E1-241 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 180 of 195 APPENDIX A -NOTATION CONVENTIONS (Page 3 of 7)Symbol Key WBN ODCM Source Symbol Definition Source Reference Symbol fs Fractionof time animal spends on R.G. 1.109 (p. 28) fs stored feed H Absolute humidity of theatmosphere R.G. 1.109 (p. 27) H HRSVIS Length of shoreline recreation visit N/A HVST Fish harvesit for the Tennessee River N/A Kc Transfer coefficient from water to R.G. 1.109 (p. 14) Kc shoreline sediment , Radioactive decay constant N/A XE Effective decay constant R.G. 1.109 (p. 4) AE LLD Lower Limit-of detection NUREG-1301 (p. 40) LLD?w Weathering decay constant R.G. 1.109 (p. 4) XW M Mass density of sediment R.G. 1.109 (p. 14) M n Number of compass sectors N/A P Effective surface density of soil R.G. 1.109 (p. 3) P p Fraction of radionuclide remaining in R.G. 1.111 (p. 12) p plume POP Population R.G. 1.109 (p. 30) P POPF Population dose due to fish ingestion R.G. 1.109 (p. 30) DP POPR Total recreation population dose R.G. 1:109 (p. 30) DP POPWTR Population dose due to water ingestion R.G. 1.109 (p. 30) DP Q Release, rate NUREG-0133 (p. 22) Q q Total release in aperiod NUREG-0133 (p. 29) q Qf Milk animal's consumption rate R.G. 1.109 (p. 3) Qf r Fraction of activity retained on pasture R.G. 1.109 (p. 3) r grass.Rp Gaseous Dose Factor for Pathway P NUREG-0133 (p. 26) P RI Inhalation dose factor NUREG-0133(p.
26) P RG Ground plane dose. factor NUREG-0133 (p. 26) P RCp Pasture grass-milk animal-milk NUREG-0133 (p. 26) P ingestion RCS Stored feed-milk animal-milk ingestion NUREG-0133 (p. 26) P RMp Pasture grass-beef ingestion NUREG-0133 (p. 26) P RMS Stored feed-beef ingestion NUREG-0133 (p.:26) P RVF Fresh leafy vegetable ingestion NUREG-0133 (p. 26) P E1-242 WBN OFFSITE DOSE CALCULATION MANUAL, ReviSion122 0 (ODCM) Page181ý<of 195 APPENDIX A -NOTATION CONVENTIONS (Page 4 of 7)Symbol Key WBN ODCM Source.Symbol Definition Source Reference Symbol_RVS Stored vegetable ingestion NUREG-0133,(pO
26) P R Sum ofthe.ratios N/A RATIO Ratio of averageto maximum dose N/A REQFRA Fraction of yearly recreation which N/A occurs in a quarter rf Recreation factor N/A RF River flow N/A sb Standard deviation NUREG-1301 (p. 40) sb SF Safetyrfactor N/A SHVIS Shoreline visitscper year N/A Smax Setpoint corresponding to the ODCM N/A Limit'z Vertical dispersion coefficient R.G. 1.111 (pý 11)Gz Vertical dispersion coefficient R.G. 1.111 (p. 11) sz T Duration of'release NUREG-0133 (p. 15) At At Elapsed time. between midpoint of NUREG-1301 (p. 40) At sample collection and counting time TAF Terrain adjustment factor N/A tb Time period over which accumulation R.G. 1.109 (p. 14, 26) tb, t on the .ground is evaluated tcb Time for receptorto consume a whole N/A beef td Distribution time forwater, fish, milk, R.G. 1.109 (p; 4) tp beef, or vegetables tcsf Timebetween harvest of stored feed R.G. 1.109 (p. 4)' :th and consumption by animal te Exposuretime in gardenfor fresh leafy R.G. 1.109:(p.
4) te and/or stored vegetables tep 'Time pasture is exposed to deposition R.G. 1.109 (p. 4) te tesf Time stored feed is exposed to R.G. 1.109 (p. 4) te deposition TFDOS Individual fish ingestion dose R.G. 1.109 (p.30) D tfm Transport time from milking to receptor N/A tfm thc Average time~between harvest of R.G. 1.109 (p. 4) th vegetables and their consumption and/or storage I E1-243 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 182of,195 APPENDIX A -NOTATION CONVENTIONS (Page 5 of 7)Symbol Key WBN ODCM I Source Symbol Definition Source Reference, Symbol ts Transport time from slaughter to R.G. 1.109:(p.
28) ts consumer TSHDOS Total shoreline dose rate R.G. 1.109 (p. 30) D tsv Time period over which stored N/A vegetables are consumed TWDOS Total individual water dose R.G. 1.109 (p, 30) D, u .Wind speed R.G. 1.111 (p.-9) u Uf Fish consumption rate NUREG-0133 (p. 16) UF UFL Consumption rate of fresh leafy vegetables R.G. 1.109 (p. 7) UL Um Meat ingestion rate R.G. 1.109 (p. 7) UF U Milk ingestion rate R.G. 1.109. (p. 7) Up UR Recreation usage factor R.G. 1.109 (p. 14) U US Consumption rateof stored vegetables R.G. 1.109 (p; 7) UV by the receptor Uw Water consumption rate NUREG-0133 (p. 16) UW V Sample size NUREG-1301 (p: 40) V W Dispersion factor NUREG-0133 (p. 22) W SWF Shorelinewidth factor R.G. 1.109 (p. 14) W x Downwind distance R.G. 1.111 (p. 11) x Y Radiochemical yield NUREG-1301 (p. 40) Y Yf Agricultural yield for fresh leafy R.G. 1.109 (p. 4) Yv vegetables Yp P Agricultural productivity by unit area of R.G. 1.109 (p. 4) Yv pasture grass Ysf Agricultural productivity by unit area of R.G. 1.109 (p., 4) Yv stored feed Ysv Agricultural yield for stored vegetables R.G. 1.109 (p.,4) YV E1 -244 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 183 of 195 APPENDIX A -NOTATION CONVENTIONS (Page 6 of 7)List of Acronyms ABGTS -Auxiliary Building Gas Treatment System ALARA -As Low As Reasonably Achievable CDCT -Cask Decontamination Collector Tank CFR -Code of Federal Regulations CTBD -Cooling Tower Blowdown CVCS -Chemical Volume Control System CVE -Condenser Vacuum Exhaust EPA -Environmental':Protection Agency ERCW -Essential Raw Cooling Water ESF -Engineered Safety Feature FI -Flow Indicator FSAR -Final Safety Analysis Report GRTS -GaseousRadwaste Treatment System GWS- Groundwater Sump HCT -High CrudTanks HEPA -High'Efficiency Particulate Air LLD -Lower Limit of Detection LM -Local Monitor LPF -Loop Flow LRTS -Liquid Radwaste Treatment System NIST -National Institute of Standards and Technology NRC -Nuclear Regulatory Commission NRWT -Non-Reclaimable Waste Tank ODCM -Offsite Dose Calculation Manual PM -Perimeter Monitor PWS -Public Water Supply REMP -Radiological Environmental Monitoring Program RE -Radiation Element RM -Remote Monitor SGBD -Steam Generator Blowdown SQN -Sequoyah Nuclear Plant SR -SurveillanceRequirement SSP -Site Standard Practice TBS -Turbine Building Sump TRM -Tennessee River Mile TS -Technical Specifications WBN -Watts Bar Nuclear Plant WGDT -Waste Gas Decay Tank E1-245 WBN OFFSITE DOSE CALCULATION MANUAL Revision22 0 (ODCM) Page 184 of 195 APPENDIX A -NOTATION CONVENTIONS (Page 7 of 7)List of Units The following units are used consistently throughout the WBN ODCM. The table is included to provide the reader with the unit corresponding to each abbreviation used.cc cubic centimeters cfs cubic feet per second Ci Curie cpm counts per minute d day g gram gpm gallons per minute h hour kg kilogram L liter ib pound m meters 4Ci microcurie mi mile min minute ml milliliter mrad millirad mrem millirem loi picocurie s second y year Other Notes: Equations in the text of the WBN ODCM are numbered by section, i.e., equations in Section 6.0 are numbered as 6.1, 6.2, etc. Only final equations are numbered; any equations which are reproduced from Regulatory Guides or NUREGs and used to derive a WBN specific equation are not numbered.E1-246 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 185 of 195 APPENDIX B -Deviations, in the WBN ODCM Controls/Surveillance Requirements from Those Given in NUREG-13016 (Page 1 of 4)1. Controls 1.0.1 and 1.0.2 and Surveillance Requirements 2.0.1-2.0.4 have been replaced by the, most recent WBN LCOs3.0.1 and3.0.2 and SRs 3.0.1-3.0.4.

This has been done toensure consistency between the WBN TS and the WBN ODCM.2. Control 1/2.1.1 NUREG-1 301 does not list the applicability for liquid monitoring instrumentation.

Applicability for WBN liquid effluent instrumentation is defined in Table 1.1-1to match the requirements provided in the ACTION statements associated with the table.Table 2.1-1 -Channel calibration for the Diffuser Discharge Flow Indicator is, changed to yearly due to requirements in the NPDES permit. This is more conservativethan required by'NUREG&1301.

Table 2.1-1 -The Channel Operational Test Frequency for items 3.a (Radwaste Flow), 3.b (Steam GeneratorBlowdown Flow), and 3.c (Condensate Demineralizer Flow) are N/A. These items do not have an associated alarm, interlock, and/or trip setpoint, therefore a Channel Operational Test cannot be performed'for-these items.Table 2.1-1 -Footnote 1 "is deleted from Items 1 .b (Steam Generator BlowdownRadiation) and: 1 .c (Condensate Demineralizer radiation).

Item 1.b and 1.c generate an automatic isolation on level above the alarm/trip setpoint, not instrument malfunction.

Table 2.1-1 -The circuit failure test associated with the channel operational test (COT) has been deleted. By definition a COT verifies the channel can process an input signal and actuate output devices and that there are no circuit failures that impact the required.functions.

The notes in Tables 2.1-2 which supplement the COT definition require tests to verify operation of specific features that alert the operator of a malfunction.

These include downscale failure (loss of counts), controls not in operate mode (switch mispositioned), and loss of sample flow. Circuit failure could be caused by any number of subcomponent failures.

There is not a specific circuit that, is monitoring for each of those subcomponent failures.3. Control 1/2.1.2 -Table 1.1 -2 limits. operability for WGDT release instrumentation to'periods.of release.Table 1.1-2 -Includes operability requirements for heat trace on iodine/particulate sampleliries for Condenser Vacuum Exhaust and Shield Building Exhaust.Tables 1.1-2 and 2.1-2'require that both Unit 1 and 2 Shield Building Exhaust monitors must meet operability requirements to operate either unit. This is because releases through the ABGTS may exit from either unit's Shield Building Vent.Table 1.1-2 -Wording is added to clarify the Shield Building Vent monitor noble gas channel operability requirements.

This monitor has the capability to read in units of gCi/cc or RCi/s, The usual channel will read in gCi/s, but this wording allows the monitor to be switched to read in gCi/cc if the flow channel becomes inoperable to eliminate the need for compensatory samples.Table 1.1-2 -The Applicability for Items 2.a, c, and d (Condenser Vacuum Exhaust (CVE) radiation monitors and flow instruments) is MODES 1, 2, 3, and 4 and duringMODES 5 and 6 with CVE System in operation.

The radiation monitoring instrumentation does not have to be operable if the Exhaust system is not in operation.

Table 1.1-2 -Items 3.f and 4.e were added as part of the changes associated with operating with a TPBAR core.Table 2.1-2 -Includes surveillance requirements for heat trace on iodine/particulate sample lines for Condenser Vacuum Exhaust and Shield'Building Exhaust.Table 2.1-2 -The channeloperational test frequency for 3.b (Shield Building Exhaust Iodine and Particulate Sampler), and 4.b (Auxiliary Building Exhaust Iodine and'Particulate Sampler)of Table 2.1-2 are N/A. These items have no associated alarm, interlock, and/or trip setpoint, therefore a Channel Operational Test cannot be performed.

E1-247 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 186 of195 APPENDIX B -Deviations in the WBN ODCM Controls/Surveillance Requirements from Those Given in NUREG-1301 (Page 2 of 4)Table 2.1-2 -The channel check requirements for all iodine and particulate samplers are N/A. The channel check requirement is intended to demonstrate that the sampler is operable.

An indication of flow through the sampler verifies its operability.

The daily channel checkfor the sampler flow(s) and the weekly sampler filter changeout required by the sampling and analysis program in"Table 2.2-2 provide this indication of operability, therefore a channel check requirement inthis Table is redundant.

Table 2.1-2 -The circuit failure test associated with the channelroperational test ,(COT) has been deleted. By definition a COT verifies the channel can process an input signal and actuate output devices and that there are no circuitfailures that impact~the required functions.

The notes in Tables 2.1-2 which supplement the COT definition require tests to verify operation of specific features that alert the operator of a malfunction.

These include downscale failure (loss of counts), controls not in operate mode (switch mispositioned), and loss of sampleflow.

Circuit failure could'be caused by any number of subcomponent failures.

There is not a specific circuit that is monitoring for each of'those subcomponent failures.4. Control 1/2.1.3 is added to place the meteorological monitoring requirements in the ODCM.5. Control 1/2.2.1.1

-Table 2.2-1, the requirements for samplingof continuous liquid release pathways (TBS and SGBD) are for daily grab samples rather than a continuous sampler. This is consistent with the requirements for SQN for the same points. The definition of a composite liquid effluent sample is somewhat different than that given in NUREG-1301 (WBN will be creating the composite in the lab from the grab samples, the NUREG is referring to a composite sample from a continuous sampler).The analyses for these daily grab samples are daily, rather than weekly. Each sample will be analyzed, rather than compositing the samples for the week.Table 2.2-1 -Footnote 6 is added to require that the continuous liquid release points be sampled only if primary to secondary leakage is identified, and either the monitor must be set to two times background OR compensatory samples are being collected.

This is consistent with requirements in the SQN effluent controlprogram.

The activity determination is clarified to state-thatprincipal gamma emitters will be used for the determination.

6. Control 1/2.2.2.1:

Table 2.2-2 is reformatted from the NUREG version to place more of the requirements in the table itself, and eliminate some of the footnotes.

This allows easier implementation of the sampling requirements in plant procedures.

a. Table 2.2-2 requires sampling of containment purge and vent following shutdown, startup;, or a thermal power change exceeding 15% of RATED THERMAL POWERwithin a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. This is consistent with the NUREG, but WBN goes further to. state that this does not need to be done if.analysis shows that-the DEl has not increased by a factor of 3 or more, AND if.the lower containment noble gas monitor does not show an increase of a factor of 3 or more. This is Consistent with the requirements in the SQN effluent control program.b. Table 2.2-2, Footnote 8 details applicability and timing requirements for sampling of the containment for purges. This note is consistent with one in the SQN ODCM, except that MODE'requirements and times are different.
c. Table 2.2-2, Footnote 8 details applicability and timing requirements for sampling for incore instrument room purges. This note is consistent with one in the SQN ODCM, except that MODE requirements and times are different.
c. Table 2.2-2, Footnote 10 details applicability requirements for sampling of the containment for venting.This note is consistent with one in the SQN ODCM, butdetails are different.

E1-248 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 187 of 195 APPENDIXZB

-Deviations in the WBN ODCM Controls/Surveillance Requirements ,from Those Given in NUREG-'1 301 (Page 3 of 4)d. Table 2.2-2, the Shield Building Exhaust is excluded from the monthly requirement for grab sampling.

to analyze for noble gas and tritium, since all releases through this point will havebeen quantified previously.

e. Table 2.2-2, Footnote 11 excludes the Condenser Vacuum Exhaust from the requirementsfor sampling until, a primary. to secondary leak is identified.

The activity determination is clarified to state that principal gamma emitters will be used for the determination.

f. Table 2.2-2, the table limits:theprincipal gamma emitters for.grab samples to the noble gas,.nuclides to clarify that particulate releases are quantified from filter analyses.g. Table 2.2-2 -Footnotes 3 and 7 allow compensatory grab samples to be used to determine if activity levels have increased during periods of radiation monitor inoperability..
h. Table 2.2-2 -Requirements for continuous tritium sampling were'added for the Auxiliary Building Exhaust and Shield Building Exhaust to quantify releases during1he irradiation and storage of, TPBARs. Since tritium samples willbe collected continuously footnotes 4-and 5, which required tritium grab samples, were removed.'

The use of continuous tritium samplers provides a more accurate account of the tritium released than grab samples.i. Footnotes 8 and 10 clarifies that only the containment compartment to be released, needs to be sampled. This.will eliminate unnecessary sampling.j. Table 2.22- Priorlto release each Waste Gas Decay Tank will require tritium analysis aspart~as the changes associated with operating with a TPBAR core.7. Control 1/2.3.1: a. Table 2.3-1 -the drinking water control sample location is defined in footnote 9 to: be the Upstream surface-water sample.b. Requirementsfor drinking water sample analysis differ from the NUREG. Due to-the large downstream distance of the first public water supply (> 10 miles) and the volume of dildtion water available, doses due to water ingestion will be Very low under normal circumstances.

This situation applies at both SQN andBFN and is reflected in their Environmental.Monitoring Programs.c. Text is added toTable 2.3-1 footnote 8 to state that the hydraulic gradient of the.groundwater at the WBN site is'such that the groundwater will move from the site toward the ýriver, therefore groundwater sampling is not required.d. Table 2.3-1 footnote 3 is added to clarify identification of control samples for iodine and particulate airborne monitoring.

e. Table 2.3ý1, The invertebrate sampling requirements have been relocated to the waterbome section of theTable to more accurately reflect the purpose of these samples. Thereis negligible ihgestion of invertebrates from the Tennessee River.8. BASES 1/2.1.3 -Bases for the meteorological monitoring instrumentation Control are in the IODCM.9. BASES 1/2.2.1.1

-An additional reference is given for further LLDdiscussion (ARH-SA-215, June 1975). Allocation of activity between the reactor units for dose calculation purposes is discussed in more detail.10. BASES 1/2.2.1.2

-Text is added to explain that the dose for composited nuclideswill be calculated using the values from theprevious compositing period.11. BASES 1/2.2.1.4 Allocation of activity between the reactor units for dose calculation purposes is discussed in more detail.E1-249 WBN OFFSITE DOSE CALCULATION MANUAL Revision,22 0 (ODCM) Page 188 of 195 APPENDIX B -Deviations in the WBN ODCM ControlslSurveillance Requirements from Those Given in NUREG-1301 (Page 4 of 4)12. BASES 1/2.2.2.1 An additional reference is given for further LLD discussion (ARH-SA-215, June 1975). Allocation of activity between the reactor units fordose calculation purposes is discussed in more detail.13. BASES 1/2.2.2.2 and 1/2.2.2,4 Allocation of activity between the reactor units for dose calculation purposes is discussed in more detail.14. BASES 1/2.3.1 An additional reference is given for further LLD discussion (ARH-SA-215, June 1975).15. The definitions of Member of the Public and Restricted area are not consistent with those given in NUREG-1301.

This is due to the revision to 10 CFR 20 implemented by TVA on 1/1194. The definitions are consistent with that regulation.

Similar changes are made to theBASES sections to clarify the wording where these definitions are used. Figure 3.1 shows.the locations of these boundaries and areas. A calculation is given in Section 7.7.6*for a member of;the public inside the.Site Boundary demonstrating that the location of the unrestricted area. boundary on the opposite side of the Tennessee River.meets the intent of the regulation.

16. The Source Check definition' is changed to reflect changes made in the definition, for SQN (revision 27). The new definition will allow the use of internal test circuits' in:lieu of a radioactive source (some monitors use anLED light source to provide the check signal to the photomultiplier tube).17. The Operational ModesTable (Table 3.2) is consistent with the WBN TS.E1-250 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 189 of 1 95 APPENDIX C -WBN ODCM REVISION PROCESS (Page 1 of 7)This Appendix establishes the minimum requirements for preparation; review, and approval of the Watts Bar Nuclear Plant Offsite Dose Calculation Manual. This Appendix also- implements the requirements of ODCM Section 5.3 and WBN TS 5.7.2.3.1.0 Reviewer Responsibilities

1.1 Affected

Organization Review (AOR)The identification of affected organizations is the responsibility of the Sponsor and applies to all revisions of the ODCM.The affected organizations shall ensure that their reviewers have adequate u'nderstanding of the requirements-and intent of the ODCM and access to pertinent background information.

The AO reviews the draft for impact on the organization and adequate interface

-not technical content.1.2 Independent Qualified Review (IQR)An independent qualified review is the process of independent technical review by Qualified Reviewers of activities potentially affecting nuclear safety.The IQR shall NOT be the person who prepared the ODCM revision.An IQR is performed by an individual designated by responsible department Ievel managers to perform an independent technical review of activities potentially affecting nuclear safety.The IQR must be qualified to perform the 10 CFR 50.59 review.1.3 Cross Disciplinary Review (CDR)The need for a CDR is determined by the IQR.CDRis a technical review by disciplines other than those responsible for the document reparation.

The CDR is responsible for only the technical aspects of the areas specified by the IQR and any portions of the document that support or justify those areas.Persons performing CDR do not have to be IQR qualified.

1.4 Plant

Operations Review Committee (PORC) Review The PORC reviews and recommends final approval of the ODCM.1.5 Approval Authority The Plant Manager will approve all revisions to the ODCM as required by Technical Specifications.

Signature authority shall not be delegated to a lower level manager.E1-251 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 190 of 195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 2 of 7)2.0 Processing ODCM Revisions 2.1 Requestor (If other than the Sponsor)Identify the need for an ODCM improvement.

Prepare a justification for the ODCM revision.Attach a marked-up copy of the existing ODCM.Forward the requested.ODCM revision to the sponsoring organization.

2.2 ODCM Sponsor Evaluate requested changes and determine if necessary.

If the requested change is not necessary, return the request to the requestor with explanation why the change is not needed.Incorporate all changes in a draft revision on BSL.Identify the organizations to perform AOR and complete the top portion of Attachment A for each organization.

Distribute Attachment A to each Affected Organization and request completion of the review prior to expected PORC review date.Obtain appropriate reviews of the ODCM revision in BSL.2.3 Reviews 2.3.1 IQR Review the ODCM using all questions on Attachment B as a guideline and forward comments to the Sponsor.Identify discipline or organization to perform CDR, if needed.E1-252 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 191 of 195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 3 of 7)2.3.2 Affected Organization Reviewer Review the proposed changes on BSL and provide comments to the ODCM Sponsor.Review the ODCM for impact on assigned organization, identify procedures/documents which require revision to implement the ODCM revision on the Attachment A, and return the Attachment A to the ODCM Sponsor.2.4 Sponsor Resolve comments and obtain reviewer's concurrence in BSL. Escalate anyunresolved comments to appropriate management.

Ensure ODCM has been reviewed by sponsor and IQR in accordance with Attachment B.Ensure all Affected Organizations have reviewed the ODCM change and have identified the affected procedures on Attachment A.Ensure all IQR, and CDR review requirements have been met.Assign an Effective Date typically 60 calendar days forward UNLESS there is reasonable justification for making it effective earlier, such as plant operating conditions, test schedules, commitment-or corrective action deadlines, or implementation of upper-tier requirements, or lack of affected procedures identified on Attachment A.2.5 PORC Review changes and Attachment B. Document recommendation for approval in BSL.2.6 Plant Manager Approve the ODCM revision in BSL.3.7 ODCM Sponsor Record the ODCM approval date and implementation date on each completed Attachment Aý provided by the affected organizations.

Return the Attachment A to each affected organization.

3.8 Affected

Organization Revise procedures identified on the Attachment A and assign an effective date which matches that of the ODCM revision.Complete the Attachment A and return to the ODCM Sponsor.El-253 WBN OFFSITE DOSE CALCULATIONWMANUAL Revision22 0 (ODCM) Page '192 of 195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 4 of 7)3.9 ODCMSponsor Ensure all Affected Organizations have completed and returned Attachment A prior to the effective date of the ODCM.Forward the approved ODCM change to Management Services at least three working days before the implementation date.The completed Attachments A and B are QA records, and are handled in accordance with the Document Control and Records Management Program.Forward a completedocopy of each revision to Licensing to be filed and forwardedto theNRC in the Annual Radiological Effluent Release Report.3.10 Management Services Issue the ODCM and implementing procedures onthe effective date-of the ODCM revision.El -254 WBN OFFSITE DOSE CALCULATION MANUAL Revision:22 0 (ODCM) Page 193 of 195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 5 of 7)Attachment A ODCM Affected Organization Review/Implementation Proposed ODCM Revision No.Expected PORC Review Date: Expected Effective Date: Affected Organization:

[ ] Operations

[ I RADCON[ Chemistry

[] Maintenance

[ ] Technical Support [] Scheduling Engineering

[ ] Licensing[] Other The following procedures/documents will require revision to implement this ODCM change: PROCEDURE/DOCUMENT PROCEDURE/DOCUMENT ODCM Approval Date: ODCM Effective Date: The required procedure/document revisions to support this ODCM revision have been completed-and have an implementation date which matches that given above for the ODCM revision./Affected Organization Date E1-255 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22 0 (ODCM) Page 194 of 195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 6 of 7)Attachment B ODCM Review Checklist All questions of this checklist are considered by the ODCM preparer and reviewed-by the Independent Qualified Reviewer (IQR). Only the revised portion of the ODCM should be evaluated.

Changes to Section(s) 1.0-5.0 YES NO N/A 1. Does the revision meet the intent of the guidance provided in NUREG-1301 for radiological effluent and environmental monitoring controls/surveillance requirements?

2. Do definitions in Section 3.0 match those provided in the WBN TS, NUREG-1301, or other. NRC guidance?3. Do Administrative Controls in Section 5.0 match those provided in WBN TS, NUREG-1301, or other NRC guidance?4. Does the ODCM fulfill the requirements of TVA, Federal or State Laws, WBN FSAR, and any other referenced requirements documents?
5. Does the numbering of the Control and its accompanying Surveillance Requirement correspond?
6. Are instrument/equipment numbers and units of measure an exact I match with those on the equipment?
7. Does nomenclature accuratelydescribe the equipment and correspond to label identifiers?
8. Are referenced documents applicable, valid, and listed in the reference section?9. Does this change maintain the level of radioactive effluent control required by 10 CFR Part 20.1302, 40 CFR Part 190, 10 CFR Part 50.36a, and Appendix I to 10 CFR Part 50? Provide justification for answer: I Preparer Date I IQR Date E1-256 WBN OFFSITE DOSE CALCULATION MANUAL Revision 22, 0 (ODCM) Page 195 of 1195 APPENDIX C -WBN ODCM REVISION PROCESS (Page 7 of 7)Attachment B ODCM Review Checklist (continued)

Chan es to Section(s)6.0-11.0 YES NO N/A 10. Are there methodologies given in Sections 6.0 through 9;0 which implement the applicable ODCM Controls?11. Are references to ODCM Controls and Surveillance Requirements accurate and correct?12. Are changes to setpoint-calculation methodologies consistent with .the guidance provided in NUREG-0133?

13. Are changes to liquid effluent concentration compliance methodologies consistent with the guidance provided in NUREG-0133 and 10 CFR Part 20?14. Are changes to gaseous effluent dose rate calculation/compliance methodologies consistent with the guidance provided in NUREG-0133 and/or Regulatory Guide. 1. 109?15. Are changes to dose or dose projection calculation/compliance methodologies consistent with the guidance provided in NUREG-01 33 and/or Regulatory Guide 1.109?16. Are instrument/equipment numbers and units of measure an exact match with those on the equipment?

_ ._17. Are referenced'documents applicable, valid, and listed in the references?

18. -'Are ODCM Sections numbered consistently'and consecutively?
19. Are references to other ODCMSections correct?20. Are references to ODCMTablesand Figuresaccurate and'correct?

._1 21. ýAre any new acronyms defined in Appendix A?22. Are equations numbered consecutively?

23. Does dimensiona analys 'yie the correct unitsfor equations?
24. Are terms used in equations defined after the equation (andin Appendix A) and the proper units given for that term? .25: .Do units on equation terms which reference tables match the units used for that term in.the Table?26. Are references given for table and other values correct and accurate?27. 'Do data values given match'those in the reference?
28. Do text descriptions of.release/discharge points in Sections 6.0 and 7.0 correspond.with the Figures referenced in those sections?29. The change does notadversely impact the accuracy or reliability of effluent, dose, or setpoint calculations?

Provide justification,.for answer: J /Preparer Date IQR Date E1-257 Enclosure 2 Watts Bar Nuclear Plant Process Control Program Reporting Requirements Section 2.4.D.2 and Section 2.4.E of the Process Control Program (PCP) address the reporting requirements applicable to the PCP. Section 2.4.D.2 requires that revisions to the PCP, which occurred during the reporting period of the Annual Radioactive Effluent Release Report (ARERR), be forwarded to NRC with the ARERR. The current revision level of the PCP is Revision 2, which became effective on August 4, 2009. Section 2.4.E of the PCP requires that major changes to the radiological waste treatment systems be reported in conjunction with the ARERR. For this reporting period, no major changes to the radiological waste treatment systems were made.E2-1 Watts Bar Nuclear Plant Unit 0 Process Control Program PCP Process Control Program Revision 0002 Quality Related Level of Use: Information Use Effective Date: 08-04-2009 Responsible Organization:

RAD, Radiation Protection Prepared By: Brett Sumners Approved By: Bryan Belvin E2-2 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 2 of 14 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change 0 6-10-02 ALL Initial issue replace PAl-13.01 (PER 01-017150-000).

Intent Change.1 04/14/04 ALL Reworded Section 2.3.B to clarify filters are dewatered and. surveyed prior to placing in the HIC. Added a reference in, to NRC Branch Technical Position on Concentration Averaging and Encapsulation,.

Insert level of use information.

Changed sample frequency in Section 2.1 .C.to be consistent with references 5.1 and 5.4,Corrected minor typographical errors. These are intent changes.Rev 2 08/04/09 All This procedure has been converted from Word 95 to Word 2002 (XP) using Rev 1. Removed last sentence in Section 2.1 ,C1 since only isotopic data from Watts Bar will be used for waste classification.

Changed vendor name from CNSI to EnergySolutions.

E2-3 Table of Contents

1.0 INTRODUCTION

...................................................................................................

4 2.0 DETAILS ......................................................................................................................

5 3.0 RECORDS ..................................................................................................................

12 4.0 DEFINITIONS

.............................................................................................................

12

5.0 REFERENCES

...........................................................................................................

13 Source-Notes

..........................................................................................

14 E2-4 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 4 of 14

1.0 INTRODUCTION

1.1 PURPOSE

The purpose of the Watts Bar Nuclear Plant (WBN):Process ControlIProgram (PCP)is to establish a program which provides reasonable assurance that all radioactive wastes processed at WBN for disposal at a land disposal facility are processed and packaged such that applicable Federal and State regulations and disposal site criteria are satisfied.

The PCP contains a general description of the methods for controlling the processing and packaging of radioactive wastes, specific parameters for each method, and the administrative controls and quality assurance required to ensure compliance with applicable regulations and requirements.

This PCP is not applicable to wastes transported to an off-site vendor for processing.

1.2 SCOPE

This PCP applies to the processing of wet solid radioactive wastes generated as a result of plant operation and maintenance.

This PCP does not apply to the treatment of mixed radioactive and hazardous wastes.E2-5 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 5of 14 2.0 DETAILS 2.1 WASTE CHARACTERISTICS A. Waste Streams 1. There are six waste streams that have been identified at WBN. These are primary resins, secondary resins, mobile demineralizer resin, filter elements, oil, and dry active waste.(DAW).

This POP is not normally applicable to DAW. Other waste streams may be identified based upon plant operating characteristics.

2. Primary resins are collected in the spent resin storage tank forblending, decay, and storage. Primary resin sources are Chemical and ,Volume Control System (CVCS) letdown demineralizers, boron recovery demineralizers, and the fuel pool demineralizers.
3. Secondary resins are generated from the condensate polisher demineralizers.
4. Mobile demineralizer resins are fed by several sources including floor drain wastes, equipment drain wastes, laundry and hot shower wastes, and chemical wastes.5. Filter elements will be accumulated from-one or more plant.;systems.

These are CVCS, seal injection, boron recovery, and spent fuel'pool clean-up.6. Oil is contaminated with radioactivity from various areas within the plant, as a result of normal operation and maintenance.

7. The Condensate Demineralizer Waste Evaporator (CDWE) is not part of the Unit 1 license, but may be incorporated into the Unit 2 license application.

If the CDWE is to be operated as part of the Unit 2 startup, the PCP shall be revised to incorporate the processing of the CDWE bottoms.8. DAW is generated within the plant and is not appropriately attributed to the above mentioned waste streams. DAW normally includes paper, plastic, wood, metal, and other such material generated asa result of the operation and maintenance of the plant.E2-6 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 6 of'14 2.1 WASTE CHARACTERISTICS (continued)

B. Waste Form Wastes are processed as appropriate to ensure that the minimum physical characteristics.

required by 10 CFR 61 and disposal site criteria aremet. All class B and C waste must be stabilized.

This shall be accomplished by placement into a high integrity container (HIC), or by solidification using a process that produces a product which meets the stability requirements of 10 CFR 61, per Section 2.2 of this PCP. The vendors topical report shall: include documentation of testing which verifies that the.HIC or solidified product meets these stability requirements.

Additionally, WBN shall comply with Federal and/or State requirements imposed specifically on an approved HIC.or solidification product which limit the type and/or radioactive concentration of the waste to be placed in the HIC or solidified product.C. Waste Classification Radioactive waste shall be classified as Class A, B, or C in accordance with the requirements of 10 CFR 61, using one or more of the classification methods given in the USNRC's "Low- Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (May 1983)."and "NRC Branch Technical Position on Concentration Averaging and Encapsulation" dated January 17,1995 which replaced section C.3 of.the original 1983 Technical Position.Waste classification shall be in accordance with approved station procedures.

The following specific requirements shall be incorporated in the program for sampling and analysis for waste classification:

1. Analysis frequency shall be determined by the waste classification and the date of the last sample taken. Class A waste shall be sampled at least every two years while class B and C waste shall be sampled at least annually for the nuclides listed in Table 1 andTable 2 of 1.0 CFR 61.55 unless the stream is unavailable for-sampling.

For waste streams that are not processed annually, the annual analysis need not be performed until the waste is processed.

2. The results of analysis shall be used to develop isotopic.abundances and scaling factors for difficult to measure nuclides (i.e., beta.emitters and transuranics) based on correlations between those nuclides and more easily measured gamma emitters.E2-7 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 7 of14 2.1 WASTE CHARACTERISTICS (continued)
3. Calculational methods for determining the total activity in each container shall be developed which utilizes the results from the annual analysis.4. The classification program shall establish criteria and include provisions for an increased frequency for sampling and analysis-required by paragraph 1 above, if the waste stream isotopic content may have :changed by a factor of 10.2.2 PROCESSING OF WET RADIOACTIVE WASTE A. Processing Methods Wet radioactive waste processed at WBN shall be processed into a form acceptable for disposal at a licensed facility.

Processing shall be performed utilizing vendor supplied equipment operated in accordance with the vendor's PCP and procedures.

Any vendor selected to provide services or products used for compliance with 10 CFR 61 stability requirements shall have a topical report addressing 10 CFR 61 requirements under review or approved by the NRC. The topical reports and PCP's of other vendors may be referenced in this PCP even if all vendors are not actively providing service or products at WBN.However, if any vendor is selected whose documents are not referenced, this document shall be revised to reference them.B. System Qualification Tests 1. Prior to the initial solidification of a given waste stream using a specified process, a test shall be conducted to demonstrate the ability of the process to produce an acceptable waste form over the range of critical parameters identified during the prequalification testing. Bounds for critical parameters and specific operating limits shall be specified in the vendor's PCP.2. These tests shall be performed on laboratory scale or full scale specimens and shall ensure that the acceptance criteria specified in Section 2.2.E are achieved.3. The-dewatering process shall specify an endpoint for each dewatering evolution so as to assure that the acceptance criteria specified in Section 2.2.E are achieved.E2-8

2.2 PROCESSING

OF WET RADIOACTIVE WASTE (continued)

C. Batch Processing Each batch of waste offered for processing shall be sampled and analyzed, as appropriate, in accordance with site procedures, the vendor's PCP and the topical report that addresses the 10 CFR 61 stability requirements.

This sampling shall: 1. Provide the necessary data to estimate curie content and to perform the waste classification analysis.2. When solidification is involved, sampling shall provide data necessary to: a. Ensure that waste stream parameters are within the bounds for. critical parameters established in the vendor's PCP and topical report.b. Verify the application of preestablished mix ratios.D. Testing/Inspections

1. Tests are performed on those wastes which are solidified to ensure the adequacy of the solidification agent and/or procedural technique.

The vendor's PCP shall be used to verify the solidification of at least one representative test specimen from at least every tenth batch of each type waste being processed.

2. If any test specimen fails to verify solidification, the solidification of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with the vendor's PCP, and a subsequent test verifies solidification.

Solidification of the batch, may then be resumed using the alternative solidification parameters determined by the vendor's PCP.3. If the initial test specimen from a batch fails to verify solidification, the vendor's PCP shall provide for the collection and testing of representative test specimens from each consecutive batch of waste-until'at least 3 consecutive test specimens demonstrate solidification.

E2-9 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 9 of 14 2.2 PROCESSING OF WET RADIOACTIVE WASTE (continued)

E. Acceptance Criteria 1. All classes of waste shall satisfy the following acceptance criteria: a. Liquid wastes shall be solidified.

b. Solid waste containing liquids shall not contain freestanding, liquid in excess of 1 % of the internal volume of the container.
2. For wastes which require structural stability, the acceptance criteria are as follows: a. The waste shall have structural stability.
b. Not withstanding the provisions of Section 2.2E.1, liquid wastesor wastes containing liquid shall be converted into a form in which the freestanding liquid shall not exceed 1% of the internal volume of the container when contained in a HIC, or 0.5% of the volume of the waste for waste processed to a stable form.F. Corrective Actions With processing not meeting the above acceptance criteria or otherwise not meeting disposal site, shipping and/or transportation requirements, suspend shipment of inadequately processed waste and correct the PCP, procedures, and/or waste processing equipment as necessary to prevent recurrence.

The disposition of inadequately processed wastes will be handledon a case-by-case basis.E2-10 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 10 of 14 2.3 WASTE.STREAM PROCESSING METHODS A. Spent Resins 1. Normally spent resins are processed for disposal by dewatering.

The resin is transferred to the liner or HIC where it is processed utilizing vendor supplied services, per Section 2.2.2. Alternatively, resins may be processed for disposal by solidification.

The resins shall be sampled for isotopic content and PCP parameters as defined in the vendor's PCP. The resins are transferred to the vendor's processing skid where they are solidified per Section 2.2.B. Spent Filter Elements Spent filter elements are surveyed for dose rate prior to placement in a disposal container.

The measured dose rate is used to calculate isotopic content using a dose-to-curie conversion and scaling factors per Section 2.1. Based on the isotopic content and waste classification, the appropriate process and container to be used for disposal are determined.

Normally, filters are dewatered and placed in a liner or HIC; however, filters may be dried and handled, as DAW if conditions allow, or may be encapsulated.

C. Miscellaneous Wastes Sludges and other miscellaneous wastes will be collected and handled on a case-by-case basis, and processed per Section 2.2. Oil and, on a case-by-case basis, other acceptable liquid waste will normally be shipped off-site to a licensed incinerator for disposal.E2-11 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 11 of 14 2.4 ADMINISTRATIVE CONTROLS A. Procedures Activities associated with the implementation of the requirements of this program shall be conducted in accordance with approved procedures or vendor documents that have been reviewed and approved by WBN.B. Quality Assurance/Quality Control Quality assurance assessments are conducted by the Quality Assurance organization, and by the Corporate Radiological Control organization.

Assessment findings are reviewed by WBN management.

Quality control measures include site review of all radwaste vendor procedures before use and verification, by site personnel, of end points oracceptance criteria in- vendor procedures.

Quality control of solidification methods isperformed through controlled testing of a minimum of one sample from each! batch to be solidified.

Proportions of solidification agents are established which meet the standards for waste form and free standing liquid criteria.C. Training Personnel involved in processing radioactive waste for shipment are'trained in site procedures, regulatory requirements, and disposal .site criteria applicable to the individuals responsibilities.

The retraining of personnel shall be at the frequency specified in site procedures.

D. Licensee Initiated Changes to the PCP 1. Licensee initiated changes to the PCP shall be documented:and records of reviews performed shall be retained for the duration of the unit Operating License. This documentation shall contain: a. Sufficiently detailed information to support the change(s) and appropriate analyses or evaluations justifying the change(s);

and b. A determination that the change(s) maintain the overall conformance of the solidified waste product to existing ,requirements of Federal, State, or other applicable regulations.

c. Shall be effective after review and acceptance by the Plant Operations Review Committee (PORC) and the approval of the.Plant:Manager.
2. Licensee initiated changes to the PCP shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period "in which the revision was reviewed by the PORC, in accordance with the WBN Off-site Dose Calculation Manual (ODCM).E2-12 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 12 of 14 2.4 ADMINISTRATIVE CONTROLS (continued)

E. Major Changes To Liquid Gaseous Radwaste Treatment Systems Licensee initiated major changes to the Radwaste Treatment Systems (liquid and gaseous) shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PORC, in accordance with the WBN ODCM.3.0 RECORDS None 4.0 DEFINITIONS Batch -An isolated quantity of waste to be processed having constant'physical and chemical characteristics.

Dewatered

-Wet solid wastes which have had excess water removed.Free liquid -Uncombined liquid not bound by the solid matrix of the solid waste mass; capable of flowing.Homogeneous

-Of uniform composition; the waste is uniformly distributed throughout the container.

Liquid waste -Any aqueous or non-aqueous radioactive liquid which requires processing before disposal.

This may include oils, chemicals, water, or other liquids unsuitable for inplant cleanup or treatment.

Mixed waste -Low level radioactive wastes containing chemical constituents which are hazardous under 40 CFR 261.Solidification agent -Material which, when mixed in prescribed proportions with liquid or wet solid wastes, can form a free standing product with no free liquid.Solidification

-The conversion of wet wastes into a solid form that meets shipping and burial site criteria.Stability

-A property of the waste form such that it is able to maintain its structural integrity under the expected disposal conditions; stabilized waste should maintain its gross physical properties and identity over a 300 year period.E2-13 WBN Process Control Program PCP Unit 0 Rev. 0002 Page 13 of 14

5.0 REFERENCES

5.1 Code of Federal Regulations (CFR) Title 10, Parts. 20, 61, 71; 10 CFR 20, 10 CFR 61, 10 CFR 71.5.2 Code of Federal Regulations (CFR) Title 49.5.3 Watts Bar Nuclear Plant Off-site Dose Calculation Manual 5.4 USNRC Low Level Waste Licensing Branch Technical Position, on Radioactive Waste Classification, May 1983 5.5 USNRC Low Level Waste Licensing Branch Technical

'Position on Radioactive Waste Form, January 1991 5.6 NRC Branch Technical Position on Concentration Averaging and Encapsulation, January 1995 5.7 Topical Report CNSI DW-1 1118-01-P-A for Chem-Nuclear Systems, Inc., Dewatering Control Process Containers 5.8 EnergySolutions, FO-OP-023, Bead Resin/Activated Carbon Dewatering Procedure for CNSI 14-215 or Smaller Liners 5.9 EnergySolutions, FO-OP-19, Polyethylene High Integrity Container Overpack Handling Procedure 5.10 EnergySolutions, FO-AD-002, Operating Guidelines for Use of Polyethylene High Integrity Containers E2-14 WBN Process Control Program PCP Unit 0 Rev. 0002ýPaged14 of 14 Source Notes (Page 1 of 1)Implementing Statement Requirements Statement Source Document None E2-15

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