ML20206D272
| ML20206D272 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/28/1998 |
| From: | Lash J, Stevens H CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20206D246 | List: |
| References | |
| PROC-980828, NUDOCS 9905040038 | |
| Download: ML20206D272 (200) | |
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DAVIS-BESSE j l
OFFSITE DOSE CALCULATION MANUAL Revision 11.0 Change 1 l l
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Approval:
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SRB Chairman /" Date 1
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skwhr Daie 9905040038 990428 7 PDR ADOCK 05000346' G6 R PDR.,_
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TABLE OF CONTENTS I
1.0 INTRO D U CTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . I t
l 2.0 LIQUID E FFLUENTS ... .. .. . . .. ... . . . . . . .. . .. .. .. . .. ... . . . .. . ... . . .. . . . . .. . . . . .. . ... . . .. . 2 1
l 1 2.1 Radiation Monitoring Instrumentation and Controls .. . . . . . . . . . . . 2 l l 2.1.1 Required Monitors... . . . . . . . . . . . . . .. . . . . . . . . . 3 2.1.2 Non-Required Monitors . . .. . . . . . . . . . . .. . . . . . . 4 2.2 Sampling and Analysis of Liquid Effluents.. . . . . .. . .. 4 l 2.2.1 Ba tch Releases .... ... . . . .. . .... . . .. .... . . .... . ... ... .. . . . . . . . . . .. . 5 l 2.2.2 Continuous Releases... . . .. . .. . ... .... ....... ... ... ... . . . .. 5 l
2.2.3 ' Condensate Demineralizer Backwash........ .. .... ... . . .. . . . 6 j 2.2.4 Borated Water Storage Tank and Primary Water Storage Tank.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 I 2.3 Liquid Effluent Monitor Setpoints . . ..... . . . ... . . . . . . . . . . . . . . . . . . . 8 2.3.1 Concentration Limits.... ........ . . . . . . . . . . . . . . . . . . . . . . . 8 2.3.2 Basic Setpoint Equation ...... . . . . . . . . . . . . . . . . .. . . . . . 8 j
l 2.3.3 Liquid Radwaste Effluent Line Monitor Setpoint l Calculations (RE-1770A & B, RE-1878A & B) . .. . . . . . . . 8 2.3.4 Storm Sewer Drain Monitor (RE-4686).. . ........ .. ..... ... . . 11 2.3.5 Alarm Setpoints for the Non-Required Radiation l M o n i to r s . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 2.3.6 Alarm Response - Evaluating Actual Release Conditions. . 12 2.4 Liquid Effluent Dose Calculation - 10 CFR 50 .. .. .. . ... . . .. 13 ,
2.4.1 Dose Limits to MEMBERS OF THE PUBLIC.. ... .. ... ... .. 13 l 2.4.2 MEMBER OF THE PUBLIC DOSE - Liquid Effluents....... 14 j 2.4.3 Simplified Liquid Effluent Dose Calculation . . . . . . . . . . . . . 15 j 2.4.4 Contaminated TBS /SSD System - Dose Calcuba an. . . . . . 16 2.5 Liquid Effluent Dose Projections. . . . . . . . . . . . . . . . . . . . . . . ... . 17 j l l 3.0 G AS EOUS EFFLUENTS . .. . . . .. ...... ..... . . . ... ... ..... .... . . ... . 32 j f
3.1 Radiation Monitoring Instrumentation and Controls ... ..... . . . . . 32 ;
l 3.1.1 Alarm and Automatic Release Termination.. ....... .. . . . .. 33 3.1.2 Alarm Only . ...... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... .... 34 35 l 3.2 Sampling and Analysis of Gaseous Effluents .. .... . . . . . .. ..
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- 3.2.1 Batch Releases........... ... .. .... . . . . . . . . . . . . . . . . 35 3.2.2 - Continuous Release. .. .. . ...... . .. .. . . . . . . . . . . . . . . . 35 l 3.2.3 Releases Resulting from Primary-to-Secondary System Leakage.... .. ... . . . . . . . . . . . . . .. 36 l
l DBP 6027A v Revision i1.0 ODCM
TABLE OF CONTENTS (Continued) l (3.0 GASEOUS EFFLUENTS - continued) .
I 3.3 Gaseous Eilluent Monitor Setpoint Determination.................... ......... 37 )
3.3.1 Total EfTective Dose Equivalent Limits ..... .. . .... ........ .. . 37 3.3.2 Release Rate Limits ............. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37
'3.3.3 Individual Release Radiation Monitor Setpoints. ..... . . ......... 38 3.3.4 ' Conservative, Generic Radiation Monitor Setpoints............... 39 3.3.5 Release Flow Rate Evaluation for Batch Releases........ ......... 39 3.4 Unrestricted Area Boundary Dose Rate Calculation - Noble Gas .. . . 41 3.5 Unrestricted Area Boundary Dose Rate Calculation - Radioiodine, Tritium, and Particulates ...... . .......... ...... . ...... . ...................... ... 42 3.5.1 Dose Rate Calculation .. .... .... .................. .... ... .. ........... .. 42 3.5.2 Simplified Dose Rate Evaluation for Radioiodine, Tritium and Particulates. ........ ... ...................... . .. . ............. 42 3.6 Quantifying Activity Released ............ .... .................. . ..... ... .... .. ... 43 3.6.1 Quantifying Noble Gas Activity Released Using a -
Grab Sam ple or RE-4 59 8 ............. ... . .... ......... ........... ... ... 43 3.6.2 Quantifying Noble Gas Activity Released While RE-4598 AA and BA, Channel 1, Are Inoperable ........ ..... .. 44 3.6.3 Quantifying Radioiodine, Tritium, and Particulate -
Activ ity Rele ased .. . .. .... . ... .. .. . .. ... .. . . . ... ... ............ ......... ........ . .. 44 3.6.4 Quantifying Ground Level Releases Activity. .... ........ .... .... 45 l
3.7 Noble Gas Dose Calculations - 10 CFR 50........ .. ...... ....................... 47 l 3.7.I UNRESTRICTED AREA Dose - Limits .. ............................ 47 3.7.*i Oose Calculations - Noble Gases ... .. ............. ....... ........... .. 47 3.'s a simplihM Dose Calculation for Noble Gases ........ ...... .... . 48 3.8 Radioiodine, Tritium and Particulate Dose Calculations - .
I 10CFR50........................................................................................ 49 3.8.1 UNRESTRICTED AREA Dose Limits ............... .................. 49
-3.8.2 C ritical Pathway .... .. .. . . .. . .. . . .. . .. . . .. . . . . . . . . . .. . ... . . .. .. . . . . . ... .. .. . 50 l 3.8.3 Dose Calculations - Radiciodir e, Tritium and Particulates .... 50 3.8.4 Simplified Dose Calculation for Radioiodine, Tritium and P a rti c u l ate s .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 3.9 Gaseous Effluent Dose Projection .. .. .. ........ ... ..... ........................ 52 1
4.0 S PECI AL DO S E AN A LY S ES .... .. .. . . ... . ... . . . . .. . . . .. . . . . . . .. . .. . . . . .. . . . . . . . .. .. . .. 102 4.1 Doses To The Public Due To Activities Inside the
. UNRESTRICTED AREA BOUNDARY . ... ...... ...... .. .. . . . .... . 102 l DBP 6027A . vi Revision 11.0 ODCM '
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TABLE OF CONTENTS (Continued)
(4.0 SPECIAL DOSE ANALYSES - continued) 4.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190... .. .............. 103 4.2.1 Effluent Dose Calculations. .. ... .. .................... .. . . ... ...... . 104 4.2.2 Direct Exposure Dose Detennination - Onsite Sources.. . .. 105 4.2.3 Dose Assessment Based on Radiological Environmental M onitoring Data . . .... .. .. . . .. ... ... . . .. . .. .. . .. .... . . . ... . ..... ... . .. . ... 106 4.2.4 Use of Environmental TLD for Assessing Doses Due to Noble G as Releases .. .... . . . . . .. .. .. ... ... ... ......... . . . ...... . .. . . . .. .. . . .. 108 5.0 ASSESSMENT OF LAND USE CENSUS DATA...... ....... . . ... ... .... ...... . I10 5.1 Land Use Census Requirements. .............. ....... ...... ... .............. .... .... I10 5.1.1 Data Compilation........ . . .. . . . . .. .. ... .. .. . ..... . .. . .. . . . .. . . .. . .. . . .. . I11 5.1.2 Relative Dose Significance....... ... .. ............. . ........ ........... I11 5.1.3 Data Eval uation ..... . . .. . . .... . . . ........ ..... ... ...... . ........ .. .... .... .... I11 j 5.2 Land Use Census to Support Realistic Dose Assessment.... ..... ......... I12 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .... .. . 113 6.1 Program De scription . . .. . . .. ... . .... ... .. . ... . . .. . . . . . . . . ..... . .. ... . . . . . . . ... ... ... . . . I13 ;
6.1.1 General........................................................................... I13 6.1.2 Program Deviations .. ... ..... .. . .... .. . ... ..... ... .. . . . . .. . ........ . ... .... . . . .. . . I13 q 6.1.3 Unavailability of Milk or Broad Leaf Vegetation Samples .... I13 4 6.1.4 Seasonal Unavailability, Equipment Malfunctions, Sa fety Concerns . . . . . . . . . . . . .... . ...... . ... .. .. .. .......... .. . . . .. . .. . .. . . . . . . . I14 6.1.5 S a mple Analysis . . . .. .. . . . . ... . .. . . . . . ... . . . .... . . .. . .. . .. .. .. ... . . .. . . . . 114 6.2 Reporting Levels. . . . . .. ..... . . .. . . .. . .. .. . . .. .. . . . . .. . .. . . . . . . ... .. . .. . . . . . . . . . . . . . . . .. . I14 6.2.1 General.......................................................................... I14 6.2.2 Exceedance of Reporting Levels .. .................. ...... .......... ... I14 6.3 Interlaboratory Comparison Program ................................. ........... . I15 7.0 ADMINISTRATIVE CONTROLS .......... .... ..... .... .. .... ............. ...... ..... . .. 128 7.1 Annual Radiological Environmental Operating Report........ .......... ... 128 7.2 Radioactive Effluent R elease Report.. . ......... .... ............... ......... . 128 7.3 Special Reports . .. .. . . . ... . .. . . . . . . . .. . . .. . . . . . . .. . ... . .... .. . . . . ... . . . .. . . . . . . . . . . . 130 7.4 Major Changes to Radioactive Liquid and Gaseous Waste Treatment Systems . . . .......... .......... . . . . . . . . . . . . . . . . . . . . . . . . . . . 130 t
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TABLE OF CONTENTS (Continued) i (7.0 ADMINISTRATIVE CONTROLS - continued) 7.5 De fin it i on s . . . . . . .. . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .131 7.5.1 B atch Re lease . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .131 .....
7.5.2 Channel Calibration . . .. . . .. .. .. . ... . .. . ... . .. . . . . .. . . . . .. . .. . . . . .. . . . ... . .. . . 131 7.5.3 C h an n e l C h ec k . . . . . . . . . . . . .. . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 131 .....
7.5.4 Channel Functional Test ....... ...................... ... ..... ...... ... .. ... 131 7.5.5 Com pos ite S ample. .. . ..... ... ..... . . ...... . . . . .... .. . . . .. . . ... .... . . . . ... . ...... 131 l 7.5.6 Gaseous Radwaste Treatment System ................................ . . 131 I 7.5.7 Lower Limit of Detection (LLD). .............. ......... .............. ... 132 i 7.5.8 Mem ber of the P u blic. ... .. . ....... ... . ... ....... ... . . . . .... . .. .. . . .. .... . .. . . 132 7.5.9 Operable - Operability ....... ...... ....... . .. . . . . . .. . . ... . ..... .. . ... . . . . . . . . . . . . . . 132 7.5.10 Purge-Pu rging . ..... ...... .. ... . .. . .. .. .. .. . .. . ... . .. . . .... . ... ... ...... . . . . . ...... 133 j
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7.5.1 i Unrestricted Area Boundary ... ....... ......... . .. . ...... ............ 133
- 7. 5.11 So urce Check . .... . ... . . . ... .. . ... . . .. .. . ... ... . .. .. . ... . .. . ..... . ... . .. . . .. . .. .. 133
- 7. 5 .13 Unrestricted Area.. . .. ..... . . . . .. .. .. . .. ... .. ... . . . . . . . . .. . . . . . .. . . . . . . . . . . . .. . 133 7.5.14 Ventilation Exhaust Treatment System. ........................ ......... 133 7.5 .1 5 Ve n tin g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. . . . . . .. . . . . . . . . . . . . . . .133 APPENDICES APPENDIX A - Technical Basis for Simplified Dose Calculations, Liquid E ffluent Releases. .. .. .. . . ... ... .. . . ......... . ........ .... ... . . . . . .. .. ... . . ...... . .. . . .. . . .... . . A-1 )
APPENDIX B - Technical Basis for Effective Dose Factors Gaseous Effluent Releases......................................................................................... B-1
- APPENDIX C - Radiological Environmental Monitoring . ........... Program, Sample Loc at i o n M a p s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . C-1 .........
LIST OF TABLES Table 2 Radioactive Liquid Effluent Monitoring Instrumentation................ 19 Table 2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ......................................... ...... ......... .... . 21 l
l Table 2 Radioactive Liquid Waste Sampling and Analysis Program........ ... 23 !
Table 2 Limiting Radionuclide Concentrations in Secondary Side l Clean-up Resins for Allowable Discharges to Onsite Settling l Basin....................................................................................... 26 {
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- Table 2 Radionuclide Activity Limits for the BWST and PWST....... ... . .... 27 Table 2 Liquid Ingestion Dose Commitment Factors . . .... . ... ...... ............ 28 l
Table 2 Bioaccumulation Factors ......... ..... .... .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30 1
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l Table 3 Radioactive Gaseous Effluent Monitoring Instrumentation .. .... . . 54 )
l Table 3 Radioactive Gaseous Effluent Monitoring Instrumentation j Surveillance Requirements.. .... ... ... . . .. ..... .. . . . ... . .. . . ...... 56 l
Table 3 Radioactive Gaseous Waste Sampling and Analysis Program. . . 58 i Table 3 Land Use Census Summary ............ ... . .... ... ....... . . .. . . . 61 i
Table 3 Dose Factors for Noble Gases .... ....... ..................... ........ .. ........ 62 Table 3 Exposure Pathways, Controlling Parameters, and Atmospheric l Dispersion for Dose Calculations.. ... . . .... . ..... .................... .. . .. 63 1
l Table 3 Inhalation Pathway Dose Factors'......... .... ... .. . . .. . .... . . .. 64 i
fable 3 Grass - Cow - Milk Pathway Dose Factors.. ... . ...... .. ... .. .... .... 72 Table 3 Grass - Goat - Milk Pathway Dose Factors.. ........ .. ..... . .. . .. . ... 80 Table 310 - Grass - Cow - Meat Pathway Dose Factors...... . ....... ........ ..... .... 88 Table 311 Vegetation Pathway Dose Factors .. . .. ...... ..... ... ..... .. .. .. ..... . 94 Table 3 Ground Plane Pathway Dose Factors .... ... ..... .. ............ . .... . . .... 100 Table 4 Recommended Exposure Rates in Lieu of Site Specific Data....... .. 109 Table 6 Radiological Environmental Monitoring Program ........ .. . .. . .... . . I16 l Table 6 Required Sampling Locations .... . ............. . . . . . . . .. . . . . . 121 Table 6 Lower Limits of Detection . .... . .. .. . ... ....... .... ... .. . ..... . . . 124 Table 6 Reporting Levels for Radioactivity Concentrations in Environmental Samples...... . ........... . . . . . . . . . . . . . . . . . .. .... 127 1
!' Table B Default Noble Gas Radionuclide Distribution of Gaseous Effluents ... . .. ... . . . . . . . . .. . . . . . . . . . . . . .. B-5 Table B 2 - Effective Dose Factors - Noble Gas Effluents . . . . .. .. B-6 1
DBP 6027A ix Revision 11.0 ODCM
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1 LIST OF FIGURES l 1
Figure 2 Liquid Radioactive Effluent Monitoring and Processing Diagram .. 31 Figure 3 Gaseous Radioactive Effluent Monitoring and Ventilation System s Diagram . .. ... ..... . . . ... . . ...... .. ... . . . . . . .. .. . .. .. . .. ... .. . .... . . . .. .. .. . .. . . 101 f
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1.0 INTRODUCTION
l The Davis Besse Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in:
- 1) determining the radioactive material release rates and cumulative releases;
- 2) calculating the radioactive liquid and gaseous effluent monitoring inctrumentation alarm / trip setpoints; and
- 3) calculating the corresponding dose rates and cumulative quarterly and yearly doses.
The ODCM also describes and provides requirements for the Radiological Environmental I Monitoring Program. Sampling locations, media and collection frequencies, and analytical requirements are specified. The methodology provided in this manual is acceptable for use in demonstrating compliance with concentration limits of 10 CFR 20.1302; the cumulative dose criteria of 10 CFR 50, Appendix I; 40 CFR 190; and the Davis Besse Tecimical Specifications (TS) 6.8.4.d and 6.8.4.e.
He exposure pathway and dose modeling presented provides estimates (e.g., calculational results) that are conservative (i.e., higher than actual exposures in the environment). This ,
conservatism does not invalidate the modeling since the main purpose of these calculations I is for demonstrating "As Low As is Reasonably Achievable" (ALARA) for radioactive effluents. In using these models for evaluation and controlling actual effluents, further simplification and conservatism may be applied. For purposes of demonstrating compliance with the EPA environmental dose standard for the Uranium Fuel Cycle (40 CFR 190), more realistic dose assessment modeling may be used. Other approved methodologies (LADTAP, GASPAR, XOQDOQ) also may be used to assess dose from radioactive effluents.
The ODCM will be maintained for use as a reference guide and training document of I accepted methodologies and calculations. Changes to the ODCM calculational methodologies and parameters will be made as necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50, Appendix I, Section III and IV. Questions about the ODCM should be directed to the Manager - Radiation Protection.
NOTE: Throughout this document, words appearing all capitalized denote definitions specified in Section 7.5 of this manual, or common acronyms.
Section 2.0 describes equipment for monitoring and controlling liquid effluents, sampling requirements, and dose evaluation methods. Section 3.0 provides similar information on gaseous effluent controls, sampling, and dose evaluation. Section 4.0 describes special dose analyses required for Regulatory Guide 1.21, Annual Effluent Reporting and EPA Environmental Dose Standard of 40 CFR 190. Section 5.0 describes the role of the annual land use census in identifying the controlling pathways and locations of exposure for assessing the potential offsite doses. Section 6.0 describes the Radiological Environmental Monitoring Program. Section 7.0 describes the environmental, effluent and special reporting requirements, procedural requirements for major changes to liquid and gaseous radwaste systems, and definitions.
DBP 6027A - 1 Revision 11.0 ODCM
2.0 LIOUID EFFLUENTS )
l 2.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS !
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This section summarizes information on the liquid effluent radiation monitormg 1
- instrumentation and controls. More detailed information is provided in the Davis-Besse ;
USAR, Section 11.2, Liquid Waste Systems, and associated design drawings from which this l summary was derived. Location and control function of the monitors are displayed in Figure ]
2-1. !
The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, releases of radioactivity in liquid effluents during actual or potential releases. q The radioactive liquid effluent monitoring instrumentation channels listed in Table 2-1 shall j be OPERABLE with their alarm / trip setpoints set to ensure the limits specified in i Section 2.3.1 are not exceeded. I
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Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CIIECK, SOURCE CIIECK, CHANNEL CALIBRATION, and CIIANNEL FUNCTIONAL TEST operations at the ;
frequencies shown in Table 2-2. Each of these operations shall be performed within the specified time interval with a maximum allowable extension not to exceed 25 percent of the specified interval.
NOTE: The monitors indicated in 2.1.1 a), b), and c) are inoperable if surveillances are not performed or setpoints are less conservative than required.
With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required, without delay suspend the release of radioactive liquid effluents
' monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative. 1 l
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the actions described in Table 2-1. Exert best i
. efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, l explain in the next Radioactive Effluent Release Report, (Section 7.2), why the inoperability was not corrected in a timely manner.
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2.1.1 Reauired Monitors This section describes the monitoring required during liquid releases and the backup sampling required when monitors are inoperable, a) ' Alarm and Automatic Release Terminatiau
. i. Clean Radwaste Effluent Monitors (RE-1770 A & B)
Discharges from the Clean Radwaste Monitor Tanks (2) are monitored by redundant radiation monitoring systems (RE-1770 A & B). These monitors detect gross gamma activity in the effluent prior to mixing in the Collection Box. Measurements from each detector read out on the Victoreen panel in the Control Room. Each monitoring system is capable ofinitiating an alarm and an automatic termination of the release by closing valve WC-1771. The method for determining setpoints for the alarms is discussed in Section 2.3.
ii. Miscellaneous Radwaste Effluent Monitors (RE-1878 A & B) Discharges from the Miscellaneous Liquid Waste Monitor Tank and the Detergent Waste Drain Tank are monitored by redundant radiation monitoring systems (RE-1878 A & B). These monitors detect gross gamma activity in the effluent line prior to mixing in the Collection Box. Measurements from each detector read out on the Victoreen panel in the Control Room. Each monitor is separately capable ofinitiating an alarm and automatic termination of the release by closing valve WM-1876. Setpoint determination for the alarms is discussed in Section 2.3.
b) . Alarm (ontv)
- i. Storm Sewer Drain Line (RE-4686)
The monitor on the Storm Sewer Drain effluent line detects abnormal radionuclide concentrations in the storm sewer effluent. This monitor is located near the end of the storm sewer drain pipe, upstream of the final discharge point into the Training Center Pond. The most probable source of any non-naturally occurring radioactive material in the storm sewer would be from the secondary system.
To eliminate this potential source of radioac.ivity, the Turbine Building Sump effluent is normally directed to the onsite Settling Basins. In this configuration, the source of radioactivity in the Storm Sewer Drain line is from Turbine Building drains that are not routed to the Turbine Building Sump, or from Storm Sewer drains. Evaluation of the alarm setpoint for RE-4686 is discussed in Section 2.3.4.
c) 4 Flow Rate Measuring Devices j
- i. Clean Radwaste Effluent Line Flow Indicator (FI) 1700 A & B
. Flow Totalizer (FQI) 1700 A & B I
Revision 11.0 I DBP 6027A 3 ODCM l l
ii. Miscellaneous Radwaste Effluent Line FlowIndicator(FI) 1887 A & B Flow Totalizer (FQI) 1887 A & B iii. Dilution Flow to th'e Collection Box Computer Point F201 consists of four points:
- F147 Cooling Tower Blowdown e F890 Service Water Outflow e F200 Collection Box Dilution Flow e F886 Unit Dilution Pump Flow 2.1.2 Non-Reauired Monitors Additional monitors, although not required by the ODCM, have been installed to monitor radioactive material in liquid. The monitors are:
Collection Box Outlet to the Lake (RE-8433) - monitors the final station effluent to the lake,
- Component Cooling Water System (CCWS) (RE-1412 & 1413)-monitors the CCWS return lines. Ifigh alarm closes the atmospheric vent valves on the CCWS surge tank, and redirects the vent path to the Miscellaneous Waste Drain Tank,
- Service Water System (SWS) (RE-8432)- off-line detector monitors the SWS outlet prior to discharge to the Collection Box, and 5 - Intake Forebay (RE-8434) - monitors the station intake water from intake forebay.
2.2 SAMPLING AND ANALYSIS OF LIQUID EFFLUENTS As a minimum, radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 2-3. Table 2-3 identifies three potential sources of liquid radioactive effluents. A fourth potential release point from the Turbine Building Sump it discussed in Section 2.2.2. ,
The results of the radioactivity analyses shall be used in accordance with the methodology and parameters of this section to ensure that the concentrations at the point of release are maintained within the limits of 10 CFR 20.1302.
DBP 6027A 4 Revision 11.0 ODCM I .
2.2.1 Batch Releases BATCH .9ELEASE is defined as the discharge ofliquid waste of a discrete volume. The releases from the Clean Waste Monitor Tanks 1-1 and 1-2, the Miscellaneous Liquid Waste Monitor Tank, and the Detergent Waste Drain Tank are classified as BATCH RELEASES.
The following sampling and analysis requirements shall be met for all releases from these
. tanks.
- Prior to each release, analysis of a representative grab sample for principal gamma j emitters. j
- ~ Once per month, as a minimum, analysis of one sample from a BATCH RELEASE l for dissolved and entrained gases (see note below). -l
- Once per month, analysis of a COMPOSITE SAMPLE of all releases that month for tritium and gross alpha activity. Samples' contributed to the composite are to be -
proportional to the quantity ofliquid discharged.
- Once per quarter, analysis of a COMPOSITE SAMPLE of all releases that quarter i for Strontium (Sr)-89, Sr-90, and Iron (Fe)-55.
NOTE: Identification of noble gases that are principal gamma-emitting radionuclides are included as a part of the gamma spectral analysis performed on all liquid radwaste effluents. Therefore, the Table 2-3 requirement for sampling and analysis of one batch per month for noble gases need not be performed as a separate program.
2.2.2 Continuous Releases Releases from the Turbine Building Sump (TBS) and Storm Sewer Drains (SSD) are c .fied as continuous releases.
Because the Turbine Building Sump discharges may contain minute concentrations of radionuclides due to primary-to-secondary system leakage, the Turbine Building Sump discharges are routed to the onsite Settling Basins instead of the SSD line. Overflow from the Settling Basins is pumped to the Collection Box where it is mixed with dilution flow and released to Lake Erie. Releases via this pathway are monitored by weekly analysis for principal gamma-emitting radionuclides and tritium, and by quarterly analysis of composite
. samples for Fe-55, Sr-89 and St-90.
- Discharges to the Storm Sewer Drains are from Turbine Building drains that are not routed to the TBS and from storm drains. The Storm Sewer discharges to the Training Center Pond with the overflow discharging to the Toussaint River. For conservatism, it is assumed that radioactive material released to the Training Center Pond is ultimately discharged to Lake Eric (unless actions are taken to prevent this occurrence).
l i
I DBP 6027A - 5 Revision 11.0 ODCM
l Grab samples are collected weekly from the Settling Btsins and analyzed by gamma spectroscopy. If activity is identified, additional controls are enacted to ensure that the f release concentrations are maintained below Effluent Concentration Limits and that the L
cumulative releases are a small fraction of the dose limits of Section 2.4.1. The following actions will be considered for controlling any radioactive material releases via the TBS and SSD:
- Increase the sampling frequency of the TBS and SSD until the source of the contamination is identified.
- Perform gamma spectral analysis on each sample for principal gamma emitters.
-' Compare the measured radionuclide concentrations in the sample with EC (equation 2-2) to ensure releases are within the limits.
Based on the measured concentrations, a re-evaluation of the alarm setpoint for the SSD monitor (RE-4686) may be performed as specified in Section 2.3.4.
- Consider each sample representative of the releases that have occurred since the previous sample. Determine the volume ofliquid released from the Turbine Building Sump based on the Turbine Building Sump pump run times and flow rates.
- Determine the total radioactive material released from the sample analysis and the calculated volume released. Determine cumulative doses in accordance with Section 2.4.
2.2.3 Condensate Demineralizer Backwash
~ Discharges from the Condensate Demineralizer Backwash Receiving Tank (BRT) to the South Settling Basin are sampled in accordance with Table 2-3.- Samples are collected prior to each release of the resin / water slurry and separated into the liquid phase (transfer water) and solid phase (resin). These samples are separately analyzed for principal gamma emitters. Toledo Edison has imposed guidelines on concentrations of radionuclides that may be discharged to the onsite settling basin. These guidelines are presented in Table 2-4.
The radioactive material contamination in the condensate demineralizer backwash will be I contained on the powdered resin; soluble or suspended radioactive material associated with the water phase is not expected. The resin and the water are analyzed separately thus allowing for a determination of the amounts retained onsite in the Settling Basin (the resin) and the amounts released to Lake Erie as an effluent (the decant).
The BRT receives the spent resin from the Condensate Polishing System. Low-level l radioactive material contamination of the spent resin is periodically expected due to minor i leaks in the steam generators and the leaching of residual activity in the secondary system.
l During primary-to-secondary leakage, activity levels will be elevated and typically above the limits imposed for acceptable discharge to the basin. Under these coriditions, the powdered resins are retained within the plant and processed as solid radwaste for offsite transport and disposal at a licensed radioactive waste disposal site. If within the criteria of Table 2-4, the BRT may be discharged to the onsite settling basin with the approval of the Manager -
Radiation Protection.
DBP 6027A 6 Revision 11.0 ODCM
2.2.4 Borated Water Storage Tank and Primarv Water Storage Tank The quantity of radioactive material stored in the Borated Water Storage Tank (BWST) and j Primary Water Storage Tank (PWST) shall be limited to ensure the followmg: )
f
- 1) Protected Area boundary dose rates remain less than 0.25 mR/hr, and j
- 2) - Tank rupture would result in ALARA isotopic concentrations at the nearest offsite !
potable water intake.
The concentration of radionuclides in the BWST and PWST shall be determined to be within the applicable limits by analyzing a representative sample of the tank contents at least once per 7 days when radioactive materials are being added to the tank. Although the PWST is not currently used to support plant operation, the following limits still would apply should it be in use.
The method for limiting the BWST and PWST radionuclide concentration to meet the criteria above is described below and represented in equation (2-1).
- 1) Determine the limiting fraction of each radionuclide present in a liquid sample from the tank. This is the sample concentration times the volume ofliquid in the tank divided by the limiting activity from Table 2-5.
- 2) Sum the limiting fractions of each radionuclide in the sample. This sum should be less than one (1) to meet the limiting criteria for area dose rates and offsite dose rates via the liquid pathway, a
LF,um = .I C.
- VOL
- 3785 (21) i=i A iimi Where:
LF,um = sum of the limiting fraction of each radionuclide "i" in the sample, C,i = concentration of radionuclide "i" in the liquid sample ( Ci/ml),
VOL = volume ofliquid in the tank (gal),
3785 = ml per gal, Aumi = limiting activity of radionuclide "i" from Table 2-5 ( Ci/ml) n- = number of radionuclides found in the liquid sample.
If the sum of the limiting fractions of radionuclides in the BWST or PWST exceeds one (1),
then suspend all additions of radioactive material to the tank, reduce tank contents to within the limits, and describe the events leading to this condition in the next Radioactive Effluent Release Report. t I
The values in Table 2-5 were calculated specifically for the BWST. They are conservative f for the PWST due to its smaller volume.
DBP 6027A 7 Revision i1.0 ODCM j
R l
l l 2.3 LIQUID EFFLUENT MONITOR SETPOINTS 2.3.1 Concentration Limits The concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Part 20.1302 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 Ci/ml. If the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeds these limits, then without delay restore the concentrations to within these limits.
This limitation provides additional assurance that the levels of radioactive material in bodies of water outside the site should not result in exposures exceeding the Section II.A design objective of Appendix I,10 CFR Part 50, to an individual, and the limits of 10 CFR Part 20.1302 to the population.
The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its EC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
2.3.2 Basic Setnoint Eauntion j During the release ofliquid rai aactive effluents, radiation monitor setpoints shall be )
established to alarm and trip p<or to exceeding the limits specified above. To meet this requirements, the alarm / trip setpoint for liquid effluent monitors measuring the radioactivity concentration prior to dilution is derived in Section 2.3.3. ,
2.3.3 Liould Radwaste Effluent Line Monitor Setnoint Calculations (RE-1770A & B. RE-1878A A.B3 The Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of releases prior to exceeding the Effluent Concentrations (EC) of 10 CFR 20.1302 at the UNRESTRICTED AREA. As required by Table 2-3 and as discussed in Section 2.2.1, a sample of the liquid radwaste to be discharged is collected and analyzed by gamma spectroscopy to identify principal gamma-emitting radionuclides. A maximum release rate from the tank is determined for the release based on the radionuclide concentrations and the available dilution flow rate.
The maximum release rate is inversely proportional to the ratio of the radionuclide
. concentrations to their EC values. This ratio of measured concentration to EC values is referred to as the EC fraction (ECF) and is calculated by the equation:
C '.
ECF=I (2-2) i EC i DBP 6027A 8 Revision 11.0 ODCM l
I k
. where:
ECF = sum of the fractions of the unrestricted area EC for a mixture of radionuclides, C-i = concentration of each radionuclide i measured in tank prior to release (pCi/ml), and
-ECi =' . unrestricted area EC ( Ci/ml) for each radionuclide i from 10 CFR Part 20.1302. For dissolved and entrained noble gases an EC value of l 2.0E-04 pCi/ml shall be used. j Based on the ECF, the minimum dilution factor (MDF) for the conduct of the release is established at 3.33 times larger than actually required. This safety factor (SF) provides conservatism, accounting for variations in monitor response and flow rates and also for the .
presence of radionuclides that may not be detected by the monitors (i.e., non-gamma l emitters). The following equation is used for calculating the required minimum dilution factor:
MDF = ECF/SF (2-3) where:
MDF = minimum required dilution factor, SF = 0.3 administrative safety factor.
The maximum release rate from the tank is then calculated by dividing the available dilution
' flow rate (ADF) at the Collection Box by the MDF as calculated by equation (2-4).
MAX RR = 0.9 (ADF/MDF) (2-4) where:
MAX RR = maximum allowable release rate (gal / min),
0.9 = administrative conservatism factor, and ADF = available dilution flow rate at the Collection Box as measured by Computer Point F201 (gal / min).
NOTE: Equations (2-3) and (2-4) are valid only for ECF >1. For ECF $1, the waste tank concentration is below the limits of 10 CFR Part 20.1302 without dilution, and MAX RR may take on any value within discharge pump capacity.
If MAX RR is greater than the maximum discharge pump capacity, then the pump capacity should be used in establishing the actual release rate (RR) for the radwaste discharge. For releases from the Miscellaneous Waste Monitor Tank and Detergent Waste Drain Tank, the discharge pump capacity is 100 gpm; for the Clean Waste Monitor Tank, this value is 140 gpm. ,
- DBP 6027A 9 Revision 11.0 ODCM. f L
0 I
Since the actual release rate from the tank is derived such that 10 CFR 20.1302 limits will not be exceeded given the radionuclide concentration in the tank and the available dilution j l flow, setpoints must be established to ensure:
- 1) radionuclide concentration released from the tank does not increase above the concentration detected in the sample,
- 2) available dilution flow does not decrease, and i.
' 3) actual release rate from the tank does not increase above the calculated value.
l l l The setpoints for the predilution radiation monitor (RE-1770 A & B, or RE-1878 A & B) are l- determined as follows:
Alert Alarm SP = [2
- R
- E (Ci
- SEN)] i + Bkg (2-5)
High Alarm SP = [3
- R
- I(Ci
- SEN)] i + Bkg (2-6) l where:
SP = setpoint of the radiation monitor (cpm), j Ci = concentration of radionuclide i as measured by gamma spectroscopy (pCi/ml),
SENi
= monitor sensitivity for radionuclide i based on calibration curve (epm per pCi/ml),
i Bkg ' =- background reading of the radiation monitor (cpm), and R = MAX RR / actual release rate -
The Cs 137 sensitivity may be used in lieu of the . sensitivity values for individual radionuclides. The Cs 137 sensitivity provides a reasonably conservative monitor response l.
correlation for radionuclides ofinterest in reactor effluents. Coupled with the safety factor l
SF in equation (2-3), this assumption simplifies the evaluation without invalidating the overall conservatism of the setpoint determination.
The high flow setpoint should be set equal to the MAX RR calculated in equation (2-4) or discharge pump capacity (whichever is smaller). The low flow setpoint for dilution flow rate should be set at 0.9 times the available dilution flow rate.
DBP 6027A 10 Revision 11.0 ODCM l
[.
2.3.4 Storm Sewer Drain Monitor (RE-46861
' The setpoint for the SSD radiation monitor, RE-4686, shall be established to ensure the concentration in the effluent does not exceed the limits of 10 CFR 20.1302. The SSD is not normally radioactively cantaminated by other than naturally-occurring radionuclides.
Therefore, the setpoint for this monitor has been established at a practical level to provide an early indication of any abnormal conditions without causing spurious alarm due to fluctuations in background.-
. Since discharge is to the Training Center Pond, exceeding the RE-4686 setpoint does not necessarily mean Section 2.3.1 concentration limits have been exceeded at UNRESTRICTED AREAS. The verification of compliance with the limits on concentration
- should be based on actual samples of the effluent from the pond to the Toussaint River and Lake Erie. (Refer to Section 2.3.6).
2.3.5 Alarm Setnoints for the Non-Required Radiation Monitors a) . Collection Box Outlet to the Enke (RE-8433)
The radiation monitor on the Collection Box outlet utilizes a single off-line detector to continuously monitor all station liquid effluent discharges to the lake. Although this is the final effluent monitor, it does not serve any control function. Control functions have been placed on the upstream undiluted effluent line that will ,
terminate the release prior to exceeding the effluent concentration for UNRESTRICTED AREAS in 10 CFR 20.1392. RE-8433 provides a final check of the total diluted effluent stream. Since this monitor views the diluted radwaste discharges, its response during routine operations will be minimal (i.e., typical of background levels). Therefore, the alarm setpoint for this monitor should be established as close to background as possible without incurring a spurious alarm due to background fluctuations. The setpoint is controlled in accordance with the Radiation Monitor Setpoint Manual, b) Comnonent Cooling Water System (CCWSHRE-1412 & 1413)
The monitors RE-1412 and 1413 provide indication of a breach in the CCWS integrity that would allow reactor coolant water to enter and contaminate the system.
Therefore, the alarm setpoint is established to prevent incurring a spurious alarm due to background fluctuations. The setpoint is controlled in accordance with the Radiation Monitor Setpoint Manual.
c) Service Water System (SWS) (RE-8432)
'No radioactive material is expected to be contained within the SWS during normal operations. Therefore, the high alarm setpoint is established to prevent incurring a spurious alarm due to background fluctuations. The setpoint is controlled in accordance with the Radiation Monitor Setpoint Manual.
i.
L L
DBP 6027A 11 Revision i1.0 ODCM w _ ._. ._
F l d) Intake Forebay Monitor (RE 8434)
The high alarm setpoint is established to prevent incurring a spurious alarm due to l background fluctuations. Although highly unlikely, a verified alarm from this system would indicate a possible contamination of the station intake water. The l setpoing is controlled in accordance with the Radiation Monitor Setpoint Manual.
2.3.6 - Alarm Resnonse - Evaluating Actual Release Conditions -
. Liquid release rates are controlled and alarm setpoints are established to ensure that releases do not exceed the concentration limits of Section 2.3.1 (i.e.,10 CFR 20 ECs at the discharge to Lake Erie). However, if any of the monitors (RE-1770 A & B, RE-1878 A & B, or l RE-4686) alarm during a liquid release, it becomes necessary to re-evaluate the release I conditions to determine compliance with the limits. After an alarm, the following actual release conditions should be determined:
- verify radiation monitor alarm setpoint to ensure consistency with the setpoint evaluation for the release;
- re-sample and re-analyze the source of the release
- re-determine the release rate and the dilution water flow.
Based on available data, the following equation may be used for evaluating the actual release conditions:
C'.
- RR s;1 E (2-7)
! Ci
= - measured concentration of radionuclide i in the effluent stream prior to l dilution (pCi/ml),
'= the Effluent Concentration for radionuclide i from Appendix B, Table II,
.ECi ;
Column 2 of 10 CFR 20 or 2.0E-04 pCi/ml for dissolved or entrained noble I gases ( Ci/ml), - l RR = actual release rate of the liquid effluent at the time of the alarm (gal / min),
and DF = actual dilution water flow at the time of the release alarm (gal / min).
]
If the value calculated by equation 2-7 is less than or equal to 1, then the release did not i exceed the limits of 10 CFR 20.1302; l-l-
DBP 6027A' 12 Revision 11.0 ODCM I-
n 2.4 LIQUID EFFLUENT DOSE CALCULATION - 10 CFR 50 i
2.4.1 Dose Limits to MEMBERS OF THE PUBLIC The limits for dose or dose commitment to MEMBERS OF TIIE PUBLIC from radioactive materials in liquid effluents from Davis Besse are:
- during any calendar quarter:
$ 1.5 mrem to total body 5 5.0 mrem to any organ
- during any calendar year:
$ 3.0 mrem to total body
$ 10.0 mrem to any organ With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to ;
the Commission within 30 days, pursuant to Section 7.3, 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.
Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
l This requirement is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I,10 CFR Part 50.
This action provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I,10 CFR Part 50 to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable."
NOTE: 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 CFR 141. The dose calculations in the ODCM implement the requirements of Section III.A of Appendix I,10 CFR Part 50.
Conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an indisidual l through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109," Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977.
DBP 6027A 13 Revision 11.0 ODCM
_a
r3
!' 2.4.2 MEMBER OF THE PUBLIC DOSE - Liouid Effluents i
i The calculation of the potential doses to MEMBERS OF Tile PUBLIC is a function of the radioactive material releases to the lake, the subsequent transport and dilution in the exposure pathways, and the resultant individual uptake. At Davis-Besse, the combined fish consumption and drinking water pathway has been modeled to provide a conservative dose assessment for exposures to MEMBERS OF THE PUBLIC. For the fish pathway, it has been conservatively assumed that the maximum exposed individual consumes 21 kg per year 4 of fish taken in the immediate vicinity of the Davis-Besse discharge to the lake. For the f drinking water pathway, the conservative modeling is based on an individual drinking 730 i liters per year of water from the beach wells located 966 m to the NW of the site discharge.
(It is important to note tnat because of the high sulfur content, the water from these beach wells is not suitable for consumption; however, for conservatism this pathway has been included in the dose modeling for the maximum exposed individual.) ,
l The equation for assessing the maximum potential dose to MEMBERS OF THE PUBLIC from liquid radwaste releases from Davis-Besse is:
Do = 1.67E - 02
- VOL *i I(Cio* A )
DF*Z (2-8) where:
Do = dose or dose commitment to organ "o" including total body (mrem),
Aoi = site-specific ingestion dose commitment factor to the total body or any organ "o" for radionuclide "i" given in Table 2-6 (mrem /hr per pCi/ml),
Ci
= average concentration of radionuclide i in undiluted liquid effluent representative of the volume VOL (pCi/ml),
VOL = total volume of undiluted liquid effluent released (gal),
DF = average dilution water flow rate during release period (gal / min) (typically 20,000 gpm),
Z =
10 (near field dilution factor)*
1.67E-02 = 1 hr/60 min.
- Near field ditction factor and dilution to beach wells are based on a study performed by Stone &
Webster for Toledo Edison entitled " Aquatic Dilution Factors within 50 Miles of the Davis-Besse f Unit 1 Nuclear Power Plant", June 1980.
- DBP 6027A 14 Revision 11.0 ODCM
1 The site-specific ingestion dose / dose commitment factors (A o) i rcpresent a composite dose factec for the fish and drinking water pathway. The site-specific dose factor is based on the NRC's generic maximum individual consumption rates. Values of A oi are presented in Table 2-6. These values were derived in accordance with the guidance of NUREG-0133 using the following equation:
Ao i
= 1.14E+05 (Uw / D, + Up
- BF)i DFi (2-9) where:
Up = 21 kg/yr adult fish consumption, Uw- = 730 liters /yr adult water consumption, Dw = 5.7 additional dilution from the near field to the beach wells (net dilution of 57),
BF i = bioaccumulation factor for radionuclide "i" in fish from Table 2-7 (pCi/kg per pCi/1),
DF; = dose conversion factor for nuclide "i" for adults in organ "o" from Table E-11 of Regulatory Guide 1.109 (mrem /pCi), and 1.14E+05 = 106 (pCi/ Ci)
- 10' (ml/kg) / 8760 (hr/yr).
The radionuclides included in the periodic dose assessment required by Section 2.4.1 are those identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of Table 2-3. In keeping with the NUREG-0133 guidance, the aduh age group represents the maximum exposed individual age group. Evaluation of doses for other age groups is not required for demonstrating compliance with the dose criteria of I Section 2.4.1. The dose analysis for radionuclides requiring radiochemical analysis will be l performed after receipt of results of the analysis of the composite samples. In keeping with l
the required analytical frequencies of Table 2-3, tritium dose analyses will be performed at i
least monthly; Sr-89, Sr-90 and Fe-55 dose analyses will be performed at least quarterly.
2.4.3 Simplified Liauid Effluent Dose Calculation In lieu of the individual radionuclide dose assessment presented in Section 2.4.2, the following simplified dose calculation may be used for demonstrating compliance with the dose limits required by Section 2.4.1. Radionuclides included in this dose calculation should be those measured in the grab sample of the release (principal gamma emitters measured by gamma. .p ctroscopy). II-3 should not be included in this analysis. Refer to Appendix A for the derivation of this simplified method.
DBP 6027A 15 Revision 11.0 ODCM
p l Total Bodv i
Do, = 9.70E + 02
- VOL
- I Ci (2-10) l DF 1.19E + 03
- VOL *i I C l
D mo =
(211)
DF where: j Ci
= average concentration of radionuclide i excluding H-3 in undiluted liquid '
effluent representative of the release volume (pCi/ml),
- VOL = volume ofliquid effluent released (gal),-
DF = average dilution water flow rate during release period (gal / min),
Dib = conservatively evaluated total body dose (mrem),
Dmo. = conservatively evaluated maximum organ dose (mrem), ]
9.70E+02 = 0.0167 (hr/ min)
- 5.81E+05 (mrem /hr per pCi/ml, Cs-134 total body ]
dose factor from Table 2-6) /10 (near field dilution), and )
i 1.19E+03 = 0.0167 (hr/ min)
- 7.11E+05 (mrem /hr per pCi/ml, Cs-134 liver dose i factor from Table 2-6) /10 (near field dilution).
2.4.4 Contaminated TBS /SSD System - Dose Calculation All non-naturally occurring radioactivity released from the SSD must be included in the evaluation of the cumulative dose to a MEMBER OF THE PUBLIC. Although the discharges are via the Training Center Pond to Pool 3, and then to the Toussaint River
,. (instead of directly to Lake Erie), the modeling of equation (2-8) remains reasonably conservative for determining a hypothetical maximum individual dose. The following assumptions should be applied for the dose assessment of any radioactive material releases from the SSD into the Training Center Pond and subsequently to the Toussaint River:
- If no additional controls are taken, then it should be assumed that any radioactive material released to the Training Center Pond will ultimately be discharged to the take environment; l
- If actions are taken to limit any release, then the assessment of dose should be made based on an evaluation of actual releases; and
- The dilution flow should consider additional dilution of the SSD discharge from l; other sources into the Training Center Pond prior to release to the river.
DBP 6027A 16 Revision 11.0 i ODCM I-L
p 25 LIQUID EFFLUENT DOSE PROJECTIONS '
10 CFR 50.36a requires licensees to maintain and operate the radwaste system to ensure . )
releases are maintained ALARA. This Section implements the requirements of 10 CFR Part
'50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective
'Section II.D of Appendix I to 10 CFR Part 50.' Based on a cost analysis of treating liquid radwaste, the specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as the dose design objectives as set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents. This requirement is
. implemented through this ODCM.
The liquid radioactive waste processing system shall be used to reduce the radioactive material levels in the liquid waste prior to release when the projected doses in any 31-day period would exceed:
- 0.06 mrem to the total body, or
- 0.20 mrem to any organ.
This dose criteria for processing is established at one quarter of the design objective rate (i.e.,1/4 of 3 mrem /yr total body and 10 mrem /yr any organ over a 31-day projection).
With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, a Special Report that includes the following information:
- explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability;
- action (s) taken to restore the inoperable :quipment to OPERABLE status; and
- summary description of action (s) taken to prevent a recurrence.
In any month in which radioactive liquid effluent is being discharged without treatment,-
doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
The following equations may be used for the dose projection calculation:
Dibp = Di s (31/ d) (2-12)
- Dm,xp = Dm , (31/ d) (2-13)
- DBP 6027A 17 Revision i1.0 ODCM
where:
Didy = the 31-day total body dose projection (mrem),
D,3 = the cumulative total body dose for current calendar quarter including release under consideration as determined by equation (2-8) or (2-10) (mrem), l
+-
Dmax, = the 31-day maximum organ dose projection (mrem), ;
1 Dm., = the maximum organ dose for current calendar quarter including release
- under consideration as determined by equation (2-8) or (2-11) (mrem), 1 1
d = . the number of days accounted for by the calendar quarter dose, and l 31 =. the number of days in projection.
l l
l l
l DBP 6027A 18 Revision 11.0 ODCM
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)
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r nl e u s
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c e W P um c u e r t
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t n e o D e S e
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n t s t m t D Ma e s at wo a w r a u r W yle d n m
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i Table 2-1 (continued) i TABLE NOTATION l
-(1) During radioactive releases via this pathway ACTION A With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases may be resumed, provided that prior to initiating a release:
1.~ At least two independent samples are analyzed in accordance with Table 2-3 for analyses performed with each batch;
- 2. At least two independent verification of the release rate calculations are performed;
- 3. At least two independent verifications of the discharge valving are performed; 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 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 may be used to estinate flow.
ACTION C With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, during effluent releases, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection no greater than 1.0E-07 Ci/ml.
I i
DBP 6027A 20 Revision 11.0 ODCM
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Table 2-2 (continued) I j
TABLE NOTATION l
.(1) . During releases via this pathway.
(2) If applicable, the CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the alarm / trip setpoint.
l(3). The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that I participate in measurement assurance activities with NIST. These standards should permit )
calibrating the system over its intended range of energy and rate capabilities. For subsequent
-l CHANNEL CALIBRATION, sources that have been related to the initial calibration should j be used, at intervals of at least once per eighteen months. For high range monitoring -
instrumentation, where calibration with a radioactive source is impractical, an electronic . 1 calibration may be substituted for the radiation source calibration. l 1
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. j CHANNEL CHECK shall be made at least once daily on any day on which continuous, J periodic, or BATCH RELEASES are made.
(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 />. 1 (M) At least once per 31 days.
(P) Prior to each release.
(R) At least once per 18 month (550 days).
(Q) ( At least once per 92 days.
l l
I l
I l
l l
l
- DBP 6027A 22 Revision 11.0 ODCM
V:
Table 2-3 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM ;
Minimum Type of Lower Limit of Liquid Release Type - Sampling Analysis Activity Detection (LLD)
Frequency Frequency Analysis (pCi/ml)'
A. Batch Waste P P Principal d 6 Release Tanks Each Batch Each Batch Gamma 5.0E-07 r
Emitters I-131' l.0E-06 P M Dissolved and One Batch /M Entrained 1.0E-05 Gases P M Each Batch Composite c H-3 1.0E-05 Gross Alpha 1.0E-07 P Q Each Batch Compositec Sr-89, Sr-90 5.0E-08 Fe-55 1.0E-06 B. Storm Sewer Drain Principal 6
Continuously S* Gamma 5.0E-07 monitored Emitters' I-131' l .0E-06 C. Condensate P P Principal b
Demineralizer Each Batch Each Batch Gamma 5.0E-07 Backwash when when Emitters #
discharged to discharged to ;
the settling the settling 1.0E-06 I-131' basm basm, DBP 6027A 23 Revision 11.0 ODCM
1 Table 2 3 (continued)
TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank
. observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66s3 LLD =
E
- V
- 2.22
- Y
- exp (-AAt) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);
S3is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute);
E is the counting efficiency (as counts per transformation);
V is the sample size (in units of mass or volume); .
2.22 is the number of transformations per minute per picoeurie; Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radionuclide; At for plant effluents is the elapsed time between the midpoint of sample collection and time ofcounting.
It should be recognized that the LLD is defined as an a pnori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
- b. The principal gamma emitters for which the LLD specification will apply are exclusively the
- following radionuclides: Mn-54, Fe-59, Co-58, Co-60,2n-65, Mo-99, Cs-134, Cs-137, and Cc-141. For Ce-144, the LLD is 2.0E-06 pCi/ml. Other peaks which are measured and identified shall also be reported.
Nuclides which are below the LLD for the analysis should not be reported as being present at the LLD level. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Radioactive Effluent Release Report.
- c. A COMPOSITE SAMPLE is one in which the method of sampling employed results is a specimen which is representative of the liquids released.
)
i DBP 6027A' 24 Revision 11.0 ODCM
r-Table 2-3 (continued) l TABLE NOTATION
- d. A BATCII RELEASE is the discharge ofliquid wastes of a discrete volume,
- e. ' When the monitor is out of service, a grab sample shall be taken and analyzed once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if there is flow from the Storm Sewer line.
l If an isotopic analysis is unavailable, gross beta or gamma measurement of BATCH I f.
RELEASE may be substituted provided the concentration released to the UNRESTRICTED AREA does not exceed 1.0E-07 pCi/ml and a COMPOSITE SAMPLE is analyzed for principal gamma emitters when instrumentation is available.
- g. Frequency notation:
P - Prior to each release.
M - At least once per 31 days.
Q - At least once per 92 days.
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 /> (when the monitor is inoperable).
I 1
i DBP 6027A 25 Revision i1.0 l ODCM
Table 2-4 Limiting Radionuclide Concentrations
- In Secondary-Side Clean-Up Resins for Allowable Discharges to Onsite Settling Basin Radionuclide Limiting Concentration ** l 3
(pCi/cm )
Cr51- 3.3E-02 Mn-54 6.2E-05 4
Fe-59 5.lE-04 Co-58 3.0E-04 Co-60 5.4E-06 Y-91 2.1 E-03 Zr-95 4.1E-04 Nb-95 1.0E-03 Mo-99 7.8E-03 * *
- Ru-103 1.0E Ru-106 1.6E-05 Ag-110m 1.6E-05 Te-125m 5.4E-05 Te-127m 1.5E-05 Te-129m 6.2E-05 Te-131m 3.lE-03***
Te-132 3.5 E-03"*
I-131 1.1E-04 -,
I133 ~3.8E-04 I I-135 1.5E-03 Cs-134 1.lE-05 I Cs-136 2.3 E-03 *"
Cs-137 1.0E-05 Ba-140 3.lE-03***
La 140 3.5 E-03 * "
Ce-141 5.8E-03 Ce-144 4.1E-05 Pr-143 1.9E-02
- Concentration limits based on the study, Disnosal of Low-Level Radioactivelv Contaminated
! Secondarv-Side Clean-up Resins in the On-site Settling Basins at the Davis-Besse Nuclear Power Station, J. Stewart Bland, May 1983. The limits represent a hypothetical maximum individuai l_
!- dose ofless than 1 mrem per year due to an inadvertent release to the offsite environment. The allowable release limits as presented in Table 2 of the above reference report have been reduced by a factor of 10 for added conservatism - representing a hypothetical dose ofless than 0.1 mrem.
j - " With more than one radionuclide identified in a resin batch, the evaluation for acceptable discharge to the onsite settling basin shall be based on the " sum of the fractions" rule as follows:
Determine for each identified radionuclide the ratio between the measured concentration and the limiting concentrationi the sum of these ratios for all radionuclides should be less than one (1) for
. discharge to the basin.
- " Limits updated due to changes in 10CFR20, Appendix B, Table 11, Column 2 values.
l L DBP 6027A 26 Revision 11.0 ODCM L.
r.
Table 2-5 Radionuclide Activity Limits for the BWST and PWST Radionuclide Total Activity (Ci)
H-3 2.12E+03 Cr-51 2.88E+02 Mn-54 1.41E+01 Fe-59 1.07E+01 Co-57 1.26E+02 Co-58 1.18E+01 Co-60 5.14E+00 Zn-65 2.16E+01 Rb-88 1.04E+02 Sr-89 2.12E+00 Sr-90 2.12E-01 Sr-91 ' l.73E+01 Sr-92 9.72E+00 Y-91 2.12E+01 Y-93 2.12E+01 Zr 95 4.23E+01 Zr-97 1.41E+01 Nb-95 4.31E+00 Nb-97 1.63E+01 Mo-99 2.82E+01 Tc-99m 1.01E+02 Ru-103 2.16E+01 Ru-106 7.06E+00 Ag-11Om 4.31 E+00 Sn113 5.64E+01 Sb-125 2.47E+01 I-131 2.12E-01 1-132 5.00E+00 1-133 7.05E-01 I-134 4.53E+00 I-135 2.82E+00 Cs-134 6.35 E+00 Cs-136 5.44E+00 Cs-137 1.41E+01 Cs-138 2.73E+01 Ba-139 1.43E+03 Ba-140 1.41E+01 La-140 - 5.38E+00 Ce-141 6.35E401 Ce-144 7.05 E+00 DBP 6027A 27 Revision 11.0 ODCM i i
r I
Table 2-6 Davis-Besse Site-Specific Liquid Ingestion Dose Commitment Factors, A io (mrem /hr per pCi/ml)
Nuchde Bons Lly.cr T. Body Thyroid Kidney Lung GI-LLI 11-3 0.00E+0 1.76E+0 1.76E+0 1.76E+0 1.76E+0 1.76E+0 1.76E+0 C 3.13 E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 i Na-24 4.32E+2 4.32E+2 4.32E+2 4.32E+2 4.32E+2 4.32E+2 4.32E+2 l P-32 1.39E+6 8.64E+4 5.37E+4 0.00E+0 0.00E+0 0.00E+0 1.56E+5 Cr-51 0.00E+0 0.00E+0 1.31 E+0 7.85 E-1. 2.89E-1 1.74E+0 3.30E+2 Mn-54 0.00E+0 4.44E+3 8.48E+2 0.00E+0 1.32E+3 0.00E+0 1.36E+4 Mn-56 0.00E+0 1.12E+2 1.98E+1 0.00E+0 1.42E+2 0.00E+0 3.57E+3 Fe-55 6.99E+2 4.83E+2 1.13 E+2 0.00E+0 0.00E+0 2.69E+2 2.77E+2 Fe-59 1.10E+3 2.59E+3 9.93E+2 0.00E+0 0.00E+0 7.24E+2 8.64E+3 Co-57 0.00E+0 2.35E+1 3.91 E+1 0.00E+0 0.00E+0 0.00E+0 5.96E+2 Co-58 0.00E+0 1.00E+2 2.24E+2 0.00E+0 0.00E+0 0.00E+0 2.03 E+3 Co 0.00E+0 2.87E+2 6.34E+2 0.00E+0 0.00E+0 0.00E+0 5.40E+3 Ni-63 3.30E+4 2.29E+3 1.11 E+3 0.00E+0 0.00E+0 0.00E+0 4.78E+2 Ni 65 1.34E+2 1.74E+1 7.95E+0 0.00E+0 0.00E+0 0.00E+0 4.42E+2 Cu-64 0.00E+0 1.12E+1 5.25E+0 0.00E+0 2.82E+1 0.00E+0 9.54E+2 )
Zn-65 2.32E+4 7.40E+4 3.34E+4 0.00E+0 4.95E+4 0.00E+0 4.66E+4 Zn-69 4.95E+1 9.46E+1 6.58E+0 0.00E+0 6.15E+1 0.00E+0 1.42E+1 Br-82 0.00E+0 0.00E+0 2.60E+2 0.00E+0 0.00E+0 0.00E+0 2.98E+2 Br-83 0.00E+0 0.00E+0 4.10E+1 0.00E+0 0.00E+0 0.00E+0 5.91E+1 Br-84 0.00E+0 0.00E+0 5.31E+1 0.00E+0 0.00E+0 0.00E+0 4.17E-4 Br-85 0.00E+0 0.00E+0 2.18E+0 0.00E+0 0.00E+0 0.00E+0 0.00E+0 Rb-86 0.00E+0 1.01E+5 4.72E+4 0.00E+0 0.00E+0 0.00E+0 2.00E+4 Rb-88 0.00E+0 2.91E+2 1.54E+2 0.00E+0 0.00E+0 0.00E+0 4.01 E-9 Rb-89 0.00E+0 1.93E+2 1.35E+2 0.00E+0 0.00E+0 0.00E+0 1.12E-11 Sr-89 2.66E+4 0.00E+0 7.64E+2 0.00E+0 0.00E+0 0.00E+0 4.27E+3 Sr-90 6.55E+5 0.00E+0 1.61E+5 0.00E+0 0.00E+0 0.00E+0 1.89E+4 Sr-91 4.90E+2 0.00E+0 1.98E+1 0.00E+0 0.00E+0 0.00E+0 2.33E+3 Sr-92 1.86E+2 0.00E+0 8.04E+0 0.00E+0 0.00E+0 0.00E+0 3.68E+3 Y-90 7.16E-1 0.00E+0 1.92E-2 0.00E+0 0.00E+0 0.00E+0 7.59E+3 Y-91m 6.77E-3 0.00E+0 2.62E-4 0.00E+0 0.00E+0 0.00E+0 1.99E-2 Y-91 1.05E+1 0.00E+0 2.81 E-1 0.00E+0 0.00E+0 0.00E+0 5.78E+3 Y-92 6.29E 0.00E+0 1.84E-3 0.00E+0 0.00E+0 0.00E+0 1.10E+3 Y-93 2.00E-1 0.00E+0 5.51 E-3 0.00E+0 0.00E+0 0.00E+0 6.33E+3 Zr-95 6.84E-1 2.19E-1 1.49E-1 0.00E+0 3.44E-1 0.00E+0 6.95E+2 Zr-97 3.78E-2 7.63E-3 3.49E-3 0.00E+0 1.15E 2 0.00E+0 2.36E+3 Nb-95 4.47E+2 2.49E+2 - 1.34E+2 0.00E+0 2.46E+2 0.00E+0 1.51E+6 Nb-97 3.75E+0 9.48E-1 3.46E-1 0.00E+0 1.llE+0 0.00E+0 3.50E+3 Mo-99 0.00E+0 1.66E+2 3.16E+1 - 0.00E+0 3.76E+2 0.00E+0 3.85E+2 Tc-99m 1.25E-2 3.53 E-2 4.49E-1 0.00E+0 5.35E-1 1.73E-2 2.09E+1 Tc-101 1.28E-2 1.85E-2 1.81E-1 0.00E+0 3.33E-1 9.45E-3 5.56E-14 Ru-103 7.13E+0 0.00E+0 3.07E+0 0.00E+0 2.72E+1 0.00E+0 8.32E+2 Ru-105 5.94E-1 0.00E+0 2.34E-1 0.00E+0 7.67E+0 0.00E+0 3.63 E+2 Ru-106 1.06E+2 0.00E+0 1.34E+1 0.00E+0 2.05 E+2 0.00E+0 6.86E+3 DBP 6027A 28 Revision 11.0 ODCM
o I
Table 2-6 (Continued)
Davis-Besse Site-Specific Liquid Ingestion Dose Commitment Factors, A io l (mrem /hr per pCi/ml)
Nuchde Bsac LiYtt T. Body Thyroid Kidney Lung GI-LLI Rh-103m 0.00E+0 0.00E+0 0.00E+0 0.00E+0 0.00E+0 0.00E+0 0.00E+0 Rh-106 0.00E+0 0.00E+0 0.00E+0 0.00E+0 0.00E+0 0.00E+0 0.00E+0 Ag-110m - 3.22E+0 2.98E+0 1.77E+0 0.00E+0 5.85E+0 0.00E+0 1.21E+3 Sb-124 4.76E+1 8.99E-1 1.89E+1 1.15E-1 0.00E+0 3.70E+1 1.35E+3 Sb-125 3.04E+1 3.40E-1 7.24E+0 3.09E-2 0.00E+0 2.35E+1 3.35E+2 Te-125m ' 2.61E+3 9.44E+2 3.49E+2 7.84E+2 1.06E+4 0.00E+0 1.04E+4 Te-127m 6.58E+3 2.35E+3 8.02E+2 1.68E+3 2.67E+4 0.00E+0 2.21 E+4 Te-127 1.07E+2 3.84E+1 2.31E+1 7.92E+1 4.36E+2 0.00E+0 8.44E+3 Te-129m 1.12E+4 4.17E+3 1.77E+3 3.84E+3 4.67E+4 0.00E+0 5.63E+4 Te-129 3.05E+1 1.15E+1 7.44E+0 2.34E+1 1.28E+2 0.00E+0 2.30E+1 Te-131m 1.68E+3 8.22E+2 6.85E+2 - 1.30E+3 8.33E+3 0.00E+0 8.17E+4 Te-131 1.92E+1 8.00E+0 6.05E+0 1.57E+1 8.39E+1 0.00E+0 2.71 E+0 Te-132 2.45E+3 1.58E+3 1.49E+3 1.75E+3 1.53E+4 0.00E+0 7.50E+4 1-130 3.82E+1 1.13E+2 4.44E+1 9.55E+3 1.76E+2 0.00E+0 9.70E+1 1-131 2.10E+2 3.01 E+2 1.72E+2 9.85E+4 5.15E+2 0.00E+0 7.93 E+1 1-132 1.03E+1 2.74E+1 9.60E+0 9.60E+2 4.37E+1 0.00E+0 5.15E+0 I-133 7.17E+1 1.25E+2 3.80E+1 1.83E+4 2.18E+2 0.00E+0 1.12E+2 I-134- 5.35E+0 1.45E+1 5.20E+0 2.52E+2 2.31E+1 0.00E+0 1.27E-2 6.62E+1 I I-135 2.24E+1 5.86E+1 2.16E+1 3.86E+3 9.39E+1 0.00E+0 Cs-134 2.99E+5 7.11E+5 5.81E+5 0.00E+0 2.30E+5 7.64E+4 1.24E+4 Cs-136 3.13E+4 1.23E+5 8.88E+4 0.00E+0 6.87E+4 9.41E+3 1.40E+4 Cs-137 3.83E+5 5.23E+5 3.43E+5 0.00E+0 1.78E+5 5.91E+4 1.01E+4 Cs-138 2.65E+2 5.23E+2 2.59E+2 0.00E+0 3.85E+2 3.80E+1 2.23 E-3 .
Ba-139 2.35E+0 1.67E-3 6.87E-2 0.00E+0 1.56E-3 9.48E-4 4.16E+0 Ba-140 4.91E+2 6.16E-1 3.22E+1 0.00E+0 2.10E-1 3.53E-1 1.01E+3 Ba-141 1.14E+0 8.61 E-4 3.84E-2 0.00E+0 8.00E-4 4.88E-4 5.37E-10 ;
Ba-142 5.15E-1 5.29E-4 3.24E-2 0.00E+0 4.47E-4 3.00E-4 7.25E-19 !
La-140 1.86E-1 9.38E-2 2.48E-2 0.00E+0 0.00E+0 0.00E+0 6.89E+3 ;
La-142 9.53E-3 4.33E 1.08E 0.00E+0 0.00E+0 0.00E+0 3.16E+1 ;
Ce-141 1.59E-1 1.08E-1 1.22E-2 0.00E+0 5.00E-2 0.00E+0 4.l l E+2 i Ce 143 2.80E-2 2.07E+1 2.29E-3 0.00E+0 9.13E-3 0.00E+0 7.75 E+2 Cc-144 8.29E+0 3.47E+0 4.45E-1 0.00E+0 2.06E+0 0.00E+0 2.80E+3 Pr-143 - 6.85E-1 2.75E-1 3.39E-2 0.00E+0 1.59E-1 0.00E+0 3.00E+3 ,
Pr-144 2.24E-3 9.31 E-4 1.14E-4 0.00E+0 5.25E-4 0.00E+0 3.221i-10 Nd-147 4.68E-1 5.41 E-1 3.24E-2 0.00E+0 3.16E-1 0.00E+0 2.60E+3 W-187 2.97E+2 2.49E+2 8.69E+1 0.00E+0 0.00E+0 0.00E+0 8.14E+4 Np-239 4.59E-2 4.51E-3 2.49E-3 0.00E+0 1.41E-2 0.00E+0 9.25 E+2 DBP 6027A 29 Revision 11.0 ODCM
Table 2-7 Bioaccumulation Factors (BFi)
(pCi/kg per pCi/ liter)*
Element Freshwater Fish 11 9.0E-01 C 4.6E+03 Na 1.0E+02 P 3.0E+03 Cr 2.0E+02 Mn 4.0E+02 Fe 1.0E+02 Co 5.0E+01 l Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 Br 4.2E+02 ,
Rb 2.0E+03 I Sr 3.0E+01 Y 2.5E+01 Zr 3.3E+00 ,
Nb 3.0E+04 Mo 1.0E+01 Tc 1.5E+01 Ru 1.0E+01 f Rh 1.0E+01 Ag 2.3E+00 4 Sb 1.0E+00 ,
Te 4.0E+02 l 1 1.5E+01 l Cs 2.0E+03 i Ba 4.0E+00 i La 2.5E+01 Ce 1.0E+00 l Pr 2.5E+01 ;
Nd 2.5E+01 l W 1.2E+03 l Np 1.0E+01 l l
l l
I
- Values in this Table are taken from Regulatory Guide 1.109 except for phosphorus which is adapted !
from NUREG/CR-1336 and silver and antimony which are taken from UCRL 50564, Rev.1, 1 October 1972. !
DBP 6027A 30 Revision 11.0 4 I
ODCM 4
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1 3.0 GASEOUS EFFLUENTS 3.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS This Section specifies the gaseous effluent monitoring instrumentation required at Davis-Besse for controlling and monitoring radioactive effluents. Location and control
' function of these monitors are displayed in Figure 3-1. More information is provided in the Davis Besse USAR, Section 11.3, Gaseous Waste System.
The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Section 3.3 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section 3.3.
With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint
. less conservative than required, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the actions shown in Table 3-1. Exert best
. efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report (Section 7.2) why the inoperability ;
was not corrected in a timely manner.
l Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 3 2. Each of these operations shall be performed within the specified time interval with a maximum allowable extension not to exceed 25 percent of the specified interval.
NOTE: The monitors specified in Table 3-2 are inoperable if surveillances are not performed or setpoints are less conservative than required.
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with methods in Section 3.3 to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 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 Part 50.
1 j DBP 6027A - 32 Revision 11.0 l ODCM
}
(
3.1.1 Alarm and Automatic Rele==a Termination a)' Waste Gas Decav System Monitor (RE-1R22 AaB)
The radioactive waste gas discharge line is continuously monitored by two off-line j i
detectors, each measuring gross activity. The monitors' control function will terminate the waste discharge prior to exceeding the release rate limits of Section 3.3.2. Table 3-1 requires that the Waste Gas Decay System contain as a minimum the
' following instrumentation:
. noble gas activity monitor (RE-1822 A or B), and
- effluent system flow rate measuring device (FT-1821 or 1821 A).
If both noble gas monitors are declared inoperable, then the contents of the tank may be released provided that prior to the release:
- at least two independent gas samples are collected and analyzed by gamma spectroscopy for principal gamma emitters (noble gases),
i
- at least two independent verifications of the release rate calculations are performed, and least two independent verifications of the discharge valve line up are
,erformed.
If the i aw rate device is inoperable,' effluent releases may continue provided that the flow rate is estimated at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Flow rates may be estimated based on fan curves or discharge valve header positioning. j b) Containment Purge Exhaust Filter Monitor (RE-5052 A.B&C) )
This detector monitors the containment atmosphere for radioactivity during Containment VENT or PURGE. The noble gas activity monitor (Channel C) is required by Table 3 1. It provides an automatic termination of the release prior to j' exceeding the release rate limits of Section 3.3.2. Although not required in order to comply with Table 3.1, Channels A and B provide indications of increasing levels of
, particulate and radiciodine releases and terminate the release if their high alarm
- setpoint is exceeded.
DBP 6027A L 33 Revision 11.0 ODCM
3.1.2 Alarm Only I
a) Station Vent Monitor (RE-4598 AA. BA)
The Station Vent is designed as the final release point for all gaseous radioactive effluents. Three separate channels (1,2, and 3) are provided for each monitoring system. Channel 1 is a beta scintillation detector viewing a fixed air volume measuring for noble gases. Channel 2 is a beta scintillation detector viewing a fixed i particulate filter sampler. Channel 3 is a gamma scintillation detector viewing a fixed cartridge sampler (e.g., charcoal). Only the Channel I radiation detector is required l
by Table 3.1.
The Channel 2 and Channel 3 detectors provide information on potential particulate and radioiodine releases. However, those monitors experience wide variations in ;
response due, in part, to the much more abundant noble gases in the effluent stream {
relative to the particulate or radioiodines being sampled. Therefore, while Channels 2 and 3 provide useful information for identifying particulate and radioiodine releases, they are not required by Table 3.1 for quantifying the release rate. Refer to Section 3.5.
I The following sampling and/or monitoring instrumentation on the Station Vent is i required by Table 3-1: j i
- noble gas activity monitor (Channel 1), !
f
- particulate sampler filter,
- iodine sampler cartridge,
)
- sampler flow rate measuring device, and
- unit vent flow rate measuring device (computer points F883 or F885).
The hydrogen purge line serves as a Containment pressure relief route to the Station Vent. A separate radiation monitor on this line is not required. Any release through the hydrogen purge line will be monitored by the Station Vent monitor, RE-4598.
b) Waste Gas System Oxygen Monitors (AE 5984 and 6570)
The Waste Gas System is provided with two oxygen monitors (with an alarm function) as required by Table 3-1 to alert operators in the unlikely event of oxygen leakage into the waste gas header. The concentration of oxygen is limited to less than
' or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by l' volume. An oxygen concentration above the specified limit will actuate a local and control room alarm.
i j
DBP 6027A 34 Revision 11.0 ODCM l'
3.2 SAMPLING AND ANALYSIS OF GASEOUS EFFLUENTS l - Radioactive gaseous wastes shall be sampled and analyzed in accordance with Table 3-3.
This sampling and analysis ensures that the dose rates and doses from gaseous effluents ,
remain below the release rate limits of Section 3.3.2, and the dose limits of Sections 3.7.1 and 3.8.1.
3.2.1 Batch Releases Table 3-3 requires that a grab gas sample be collected and analyzed prior to each BATCH RELEASE from the Waste Gas Decay Tanks (WGDT) or a Containment PURGE. The analysis shall include the identification of all principal gamma emitters (noble gas) and tritium. Although not required by Table 3-3, Containment Pressure releases, Integrated Leak Rate Tests of Containment, and other tank venting operations are batch releases and shall be sampled similarly.
The results of the sample analysis are used to establish the acceptable release rate in accordance with Section 3.3.5. This evaluation is necessary to ensure compliance with the limits of Section 3.3.2.
3.2.2 Continuous Release All releases from the Station Vent are required to be continuously sampled for radioactivity.
As specified in Table 3-3, the following minimum samples and analyses are required:
- once per week, analysis of an absorption media (e.g., charcoal cartridge) for I-131,
- once per week, analysis of a filter sample for all principal gamma emitters (particulate radioactive material),
- once per month, analysis of a grab gas sample for all principal gamma emitters (noble gas) and tritium,
- once per month, analysis of a composite of the particulate samples of all releases for that month for gross alpha activity,
- once per quarter, analysis of a composite of the particulate samples for all releases for that quarter for St-89 and 90, and
- continuous monitoring for noble gases (gross beta and gamma activity).
l DBP 6027A- 35 Revision 11.0 ODCM
i l.
3.2.3 Releases Resultine from Primarv-to-Secondary Svatem Lenknoe i
l Due to secondary coolant system contamination, there are several additional gaseous release points to consider:
- 'Ihe Atmospheric Vent Valves (AVVs) weepage - continuous ground level release
-- The Atmospheric Vent Valves (AVVs) testing - batch ground level release
- Main Steam System Relief Valves (MSSVs) - batch ground level release I - Auxiliary Feed Pump Turbines (AFPTs) - batch ground level release ,
l
- 235#,15#, 50#,5# Relief Valves - batch ground level release
- Auxiliary Steam System Relief Valves - batch ground level release
- ' Auxiliary Boiler Relief Valve - batch ground level release Steam may be released via any of these points due to improper valve seating. Steam may be j released via the MSSVs and AVVs if the plant trips, or via tne AVVs during a condenser q i
_ outage. Steam is released through the AFPTs during their operation. Steam may be released l l due to overpressurization of the Auxiliary Steam System via the relief valves on the various steam headers.
For secondary coolant system release pathways, the following minimum samples and analyses are required:
! - once per week, analysis of a secondary system off-gas sample for principal gamma emitters (nobic gases) and tritium;
- once per week, analysis of condensate sample for principal gamma emitters (iodines and particulates) and tritium;
- once per quarter, analysis of a composite of condensate samples for strontium-89 and strontium-90. l l
To supplement the above requirements, the moisture separator drain tank liquid may be analyzed for principal gamma emitters (iodines and particulants) ,
I l
Liquid samples are analyzed from Condensate during normal operations, and from the !
l Auxiliary Boiler during Modes 5 and 6. For Auxiliary Steam System Relieflifts that occur l j when the Auxiliary Boiler is the source of Auxiliary Steam, liquid samples from the j
!. Auxiliary Boiler are analyzed for principal gamma emitters (iodines and particulates) and {
i tritium. )
i If only one steam generator has a primary-to-secondary leak, then radionuclides other than !
tritium are released through the valves on the leaking steam generator's main steam line.
Demineralizing and gas stripping remove some radionuclides from the condensate prior to its return to the steam generator as feedwater. However, these processes do not remove tritium, t.
! DBP 6027A 36 Revision 11.0 i ODCM L
3.3 GASEOUS EFFLUENT MONITOR SETPOINT DETERMINATION 3.3.1 Total Effective Dose Eauivalent Limits 10 CFR 20.1301 limits the total effective dose equivalent, (TEDE), to individual members of the public from all licensed operations to 100 mrem in a year. At Davis-Besse, the total j effective dose equivalent due to radioactive materials released in gaseous effluents at the l boundary of the unrestricted area shall be limited to 50 mrem in a year.
3.3.2 Release Rate Limits All releases of gaseous radioactive effluents are designed to occur via the Station Vent.
Station Vent alarm setpoints shall be established to initiate Control Room isolation when the activity level exceeds the Derived Air Concentration limits of 10 CFR 20 and to ensure release rate of noble gas, radioiodine and p articulates effluent does not exceed any 10 CFR limit.
This may be demonstrated by ensuring that:
- a. The annual average gaseous effluent concentrations at the boundary of the unrestricted area do not exceed the values specified in Table 2 of Appendix B of 10 CFR 20.
For butch and intermittent releases (e.g. containment purges, etc.), compliance may be demonstrated by ensuring that:
- b. Airborne effluent concentrations at the boundary of the unrestricted area do not exceed ten times the values specified in Table 2 of Appendix B of 10 CFR 20 averaged over one hour.
or Noble gas: to less than or equal to 500 mrem / year, averaged over one hour, to the total body, (Deep Dose Equivalent, DDE) and to less than or equal to 3000 mrem / year averaged over one hour to the skin, (Skin Dose Equivalent, SDE), and Iodine 131, Tritium and all radionuclides in particulate form with half lives greater than 8 days: to less than or equal to 1500 mrem / year averaged over one hour to any organ.
Should dose rate (s) exceed the above limits of a. or b., without delay restore the release rate to within the above limit (s).
These requirements ensure that the total effective dose equivalent at the UNRESTRICTED AREA BOUNDARY from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 for individual members of the public.
For INDIVIDUAL MEMBERS OF THE PUBLIC who may at times be within the UNRESTRICTED AREA BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC {
will be sufficiently low to compensate for any increase in the atmospheric diffusion factor {
above that for the UNRESTRICTED AREA BOUNDARY. j DBP 6027A 37 Revision 11.0 ODCM
3.3.3 Individual Release Radiation Monitor Setooints Although generic radiation monitor setpoints are normally used at Davis-Besse (see Section 3.3.4), setpoints may be established from a sample analysis of the applicable source (i.e.,
Station Vent, Waste Gas Decay Tanks, or Containment atmosphere), and the following equations:
E Ci *500 SP" = (3-1) 472
- x/Qno
- I(Ci
- K i )
I C i* 3000 SPs = (3-2) 472
- x / QNa
- I(C * (L + 1.1 M ))
i i i where: i SPro = monitor setpoint corresponding to the release rate limit for the total body dose rate of 500 mrem per year (pCi/ml),
= monitor setpoint corresponding to the release rate limit far the skin dose rate of 3000 mrem per year ( Ci/ml),
500 = total bc dy dose rate limit (mrem /yr), I l
3000 = skin dose rate limit (mrem /yr),
x/Qso = atmospheric x/Q value for direct exposure to noble gas at the 3
UNRESTRICTED AREA BOUNDARY given in Table 3-6 (sec/m ),
VF = ventilation system flow rate for the applicable release point and 3
monitor (ft / minute),
Ci = concentration of noble gas radionuclide "i" as determined by gamma spectral analysis of grab sample (pCi/ml),
Ki = total body dose conversion factor for radionuclide "i" (mrem /yr per 3
pCi/m ) from Table 3-5, Li = beta skin dose conversion factor for radionuclide "i" (mren/yr per 3
pCi/m ) from Table 3-5, Mi = gamma air dose conversion factor for radionuclide "i" (mrad /yr per 3
pCi/m ) from Table 3-5, 1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad), and i
3 472 = 28,317 (ml/ft )
- 1/60 (min /sec).
The lesser value of SPTa or SPs is used to establish the monitor setpoint.
DBP 6027A 38 Revision 11.0
( ODCM
The Station V nt monitor (RE-4598) efficirncies and read outs tre in pCi/ml; however, the Containment Purge Exhaust Monitor (RE-5052) and the WGDT monitor (RE-1822) efficiencies and read outs are in counts per minute. Therefore, for RE-5052 and RE-1822, the setpoints in pCi/mi must be corrected to an equivalent monitor counts per minute. The monitor calibration curves are used for determining specific radionuclide efficiencies (cpm per pCi/ml).
Normally, the monitor efficiency for Xe-133 is used in lieu of the efficiency values for the individual radionuclides. Because its lower gamma energy causes a higher monitor response, the Xe 133 efficiency provides a conservative value for alarm setpoint determination.
3.3.4 Conservative. Genede Radiation Monitor Setnoints Normally, generic alarm setpoints are established instead of those determined by individual radionuclide analysis. This approach eliminates the need to adjust the setpoint periodically to reflect minor changes in radionuclide distribution or release flow rate. The alarm setpoint .
may be conservatively determined by assuming all activity released is Kr-89. The Kr-89 total body dose conversion factor is the most limiting. Therefore, the more restrictive setpoint is based on the total body dose rate limit and may be calculated using equation (3-1). Again, the Xe-133 monitor efficiency is used for conservatism. The alarm setpoints are controlled for RE-4598, RE-5052, and RE-1822 in accordance with the Radiation Monitor Setpoint Manual.
3.3.5 Release Flow Rate Evaluation For Batch Releases l To comply with the release rate limits of Section 3.3.2, each batch release shall be evaluated for maximum release flow rate prior to being released. Based on noble gas concentration, and the radioiodine, particulate, and tritium concentration in the sample as collected in accordance with Table 3-3, the allowable release rate is determined based on equations (3-3), !
(3-4) and (3-5). The smallest value of RR th, RRs or RRmn is used as the maximum allowable release flow rate.
To determine RRmn exactly, a separate RRmn must be calculated for every organ in every age group (28 values of RRmu). The smallest of these 28 is the RRmn which is compared to RRtb and RRs to determine maximum allowable release rate. A conservative shortcut is to calculate RRmn once by using the largest inhalation dose factor (Rs from Table 3-7) for any organ of any age group for each nuclide released. The largest dose factors in the inhalation pathway are usually for the teen lung.
500 (3-3)
RRai = 472
- x/Qsoi
- I(K i
- CNG )
3000 RR3 = (3-4) 472
- x / Gm
- I(( L, + 1.1 M,)
- CNG,)
1500 RRmn (3-5) 472
- x/Qmn
- I(Rg
- CINH )i
= 1 l
where:
RRid ' = allowable release flow rate so as not to exceed a total body dose rate 3
of 500 mrem /yr (ft / minute), )
1 RR, ' = allowable release flow rate so as not to exceed a skin dose rate of 3
3000 mrem /yr (ft / minute),
RRnn = allowable release flow rate so as not to exceed an inhalation dose rate 3
)
of 1500 mrem /yr (ft / min),
500 = total body dose rate limit at the UNRESTRICTED AREA BOUNDARY (mrem /yr),
3000 = skin dose rate limit at the UNRESTRICTED AREA BOUNDARY (mrem /yr), ,
l 1500 = inhalation dose rate limit at the UNRESTRICTED AREA BOUNDARY (mrem /yr),
472 = 28317 (ml/1t')
- 1/60 (min /sec),
x/ Quo = atmospheric x/Q value for direct exposure to noble gas at the 3
UNRESTRICTED AREA BOUNDARY given in Tabic 3-6 (sec/m ),
x/Qwn = atmospheric x/Q value for inhalation at the UNRESTRICTED AREA 3
BOUNDARY given in Table 3-6 (sec/m ),
Kg '= total body dose conversion factor for radionuclide "i" (mrem /yr per 3
pCi/m ) from Table 3-5, Li = beta skin dose conversion factor for radionuclide "i" (mrem /yr per 3
pCi/m ) from Table 3-5, Mi = gamma air dose conversion factor for radionuclide "i" (mrad /yr per 3
Ci/m ) from Table 3-5, Roi
= dose factor for radionuclidei to organ "o" of age group, given in 3
Table 3-7 (mrem /yr per pCi/m ),
CNG 4
= concentration of noble gas radionuclide "i" analyzed in grab samples, CINHi = concentration of tritium, radioiodine, or particulate radionuclide "i" analyzed in grab samples, and DFw = removal factor of 100 to be used for radioiodines and particulates when the effluent is processed through an absolute filter (do not use for tritium).
The actual release rate may be set lower than the maximum allowable release rate to provide an additional assurance that the release rate limits of Section 3.3.2 are not exceeded.
. DBP 6027A 40 Revision 11.0 ODCM I.-
3.4 - UNRESTRICTED AREA BOUNDARY DOSE RATE CALCULATION - NOBLE GAS If an effluent noble gas monitor exceeds the alarm setpoint, then an evaluation of compliance with the release rate limits of Section 3.3.2 must be performed using actual release conditions. This evaluation requires collecting a sample of the effluent to establish actual radionuclide concentrations and monitor response.
The following equations may be used for evaluating compliance with the release rate limit of Section 3.3.2 for noble gases:
D,3 = 472
- x/ Quo
- I(K;
- C i ) (36) {
. D, = 472
- x / Qso
- I((L i+ 1.1 Mi )
- Ci ) (3-7)
.where:
Dib
= total body dose rate (mrem /yr),
D, = skin dose rate (mrem /yr),
x/ Quo = atmospheric x/Q for direct exposure to noble gases at the 3
UNRESTRICTED AREA BOUNDARY given in Table 3-6 (sec/m ),
3 VF = ventilation system flow rate (ft / min),
Ci
= concentration of radionuclide "i" as measured in sample ( Ci/ml),
Ki = total body dose conversion factor for noble gas radionuclide "i" 3
(mrem /yr per pCi/m ) from Table 3-5, L, = beta skin dose conversion factor for noble gas radionuclide "i" 3
(mrem /yr per pCi/m ) from Table 3-5, M, = gamma air dose conversion factor for noble gas radionuclide "i" 3
(mrad /yr per pCi/m ) from Table 3-5, 1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad), and 3
472 = 28,317 (ml/ft )
- 1/60 (min /sec).
DBP 6027A 41 Revision 11.0 ODCM
i 3.5 . UNRESTRICTED AREA BOUNDARY DOSE RATE CALCULATION - RADIOIODINE,
- TRITIUM, AND PARTICULATES I
3.5.1 Dose Rate Calculation Section 3.3.2 limits the dose rate to $1500 mrem /yr to any organ for gaseous releases of I-131, tritium and all particulates with half-lives greater than 8 days. To demonstrate L ~ compliance with this limit, an evaluation is performed in accordance with Table 3-3 L (nominally onc'e per 7 days). The following equation may be used for the dose rate evaluation:
L Do= x/Qma
- I(R;o
- Q;) (3-8) where:
H Do
= dose rate to organ "o" over the sampling time period (mrem /yr)
X/ Qmu = atmospheric x/Q value for inhalation at the UNRESTRICTED AREA 3
BOUNDARY given in Table 3-6 (sec/m ),
Rio = dose factor to organo from radionuclide "i" for the controlling age group via 3
the inhalation pathway (mrem /yr per Ci/m ) from Table 3-7, and Qi = average release rate over the appropriate sampling period and analysis frequency for radionuclide "i" (pCi/sec).
3.5.2 Simnlified Dose Rate Evaluation for Radiciodine. Tritium and Particulates It is conservative to evaluate dose rates by applying the I-131 dose factor to the collective releases for all measured radionuclides. By substituting 1500 mrem /yr for the dose rate to j organ "o" in Equation (3-8) and solving for Qi, an allowable release rate can be determined.
Based on the annual average meteorological dispersion (see Table 3-6) and the I-131 dose i
factor for the most limiting potential pathway, age group and organ (inhalation, child, thyroid 3
-- R io = 1.62E+07 mrem /yr per pCi/m ), the allowr.ble release rate is 44.1 Ci/sec. An added -
l conservatism factor of 0.8 has been included in this calculation to account for any potential dose contribution from other radioactive particulate material.
For a 7-day period, which is the nominal sampling and analysis frequency, the cumulative release would be 26.7 Ci. Therefore, as long as the total radioiodine, tritium, and ~ particulate releases in eny 7-day period do not exceed 26.7 Ci, no additional analyses are needed to .
verify comphance with the Section 3.3.2 limits cri allowable release rate.
.~ ,
i i
tL DBP 6027A- 42 Revision 11.0 ODCM L ._. m.
g
'3,61 ! QUANTIFYING ACTIVITY RELEASED NRC Regulatory Guide 1.21 requires reporting the quantities ofindividual radionuclides released in gaseous effluents. Therefore, ther: quantities shall be determined.
3.6.1 - Onantifying Noble Gas Activity Released Using a Grab Samnle or RE-4598 The quantification of continuous noble gas effluents is based on sampling and analysis of the Station Vent effluent. The monitor, RE-4598, provides a measurement of gross radioactive l material concentration in the effluent. As required by Table 3-3, a gas sample is collected at least monthly from the Station Vent. And, as discussed in Section 3.2.2, this sample is 1 analyzed by gamma spectroscopy to identify principal gamma emitting radionuclides (noble gases). The results of the analysis are used to determine the quantities of radionuclides (
ieleased.- This simplified approach reasonably quantifies the continuous release provided that }
no atypical levels have been observed (e.g., alert setpoint being exceeded). )
Based on the actual grab sample analysis, the release quantities are determined by using the following equation:
- Qi
= 28,317
- T
- Ci
- 1E-06 (3-9) where:
Q, = total activity released of radionuclidei (Ci),
3 28,317 = milliliters per fl ,
3 VF- = ventilation system flow rate (ft /mb),
T = release duration (min),
IE-06 = Ci per pCi, and
%- = concentration of radionuclide "i" as measured in the grab sample
- (pCi/ml).
As an attemative method, the average noble gas reading for the release period can be used to quantity individual noble gas radionuclides released provided a normal isotopic mixture of gases is present by using the following equation:
Qi = 28,317
- A i *C*VF*T (3-10)
IA i where:
Qi = total activity released of radionuclide "i" (pCi),
28,317 = milliliters per ft',
DBP 6027A 43 . Revision 11.0 ODCM
F A; = activity concentration of radionuclide "i" from the gamma spectral j analysis of a grab sample from the release point ( Ci/ml),
C = average gross activity concentration over the release period as measured by the noble gas monitor excluding any BATCH RELEASES (pCi/ml),
VF = ventilation system flow rate (ff/ min), and T =
release duration (min).
3.6.2 Ouantifying Noble Gas Activity Released While RE-4598AA and BA. Channel 1. Are Inonerable With both Station Vent radiation monitors inoperable (i.e., RE-4598 AA and BA, Channel 1),-
the alarm functions are also inoperable. The once-per-8 hours grab samples provide for continued quantification of releases in accordance with Table 3-1 requirements. Analysis of grab samples provides the radionuclide concentrations in the effluent. The flow measurement
- d:vice (or flow rate estimate) and the release duration provide the total volume released.
With these, the total amount of radioactive material released can be determined by using equation 3-9.
3.6.3 Ouantifying Radiciodine. Tritium. and Particulate Activity Released For radioiodine and particulates:
Q, = A,
- k'
- t
- v
- 1E - 06 (3-11) {
. *s
- 0.72 !
(l- e-i l
where:
Qi = total activity released of radionuclidei (Ci),
A; = activity of radionuclide; measured on filter media (pCi), !
l d
Ai = decay constant of radionuclidei (hr ), -
l t = release duration (hr), !
y =- . total vent system flow for sampling period (cc),
1E-06 = Ci per pCi, s = total flow through sampler (ce), and L 0.72 = isokinetic flow correction factor for normal range station vent skid I- RE 4598 AA or BA filter media.
I DBP 6027A~ 44 Revision 11.0 ODCM
. For Tritium:
Q = C
- 0.9*S W
- V
- 1E - 06 (3-12) where:
Q. = total activity of tritium released (Ci),
C = tritium concentration in gas washing bottle (pCi/ml), )
W- = volume of water added to gas washing bottle (ml),
V = total vent system flow for release period (cc),
l 1E 06 = Ci per pCi, 0.9 = efficiency for collection af tritium, and total sample volume through gas washing bottle (cc).
S- =
' 3.6.4 Otinntifying Groimd Level Releases Activity I
The ground level releases listed in Section 3.2.3 do not exhaust through Station Vent nor are directly sampled for activity. The condensate sample is used to calculate the postulated iodine and particulates activities and a portion of the tritium and noble gas activity. The off gas sample supplement the tritium and noble gas activities released (due to partitioning factors, over 99.9% ofiodines and particulates are in the condensate and moisture separator drain tank liquid). The results of the sampling program are used to indirectly quantify the l activity released as follows:
Qi = T'(M
- 7.564)(Cu + 0.065
- P
- Cw) + (F
- 28317
- Ci ,
- M / M,)
where:
Qi = total activity released of radionuclide ( Ci),
T = duration of release (min),
M = mass flow rate of release (lbs/hr),
M. = mass flow rate of condensate (lbs/hr),
1 7.564 = - hr/ min * (3785 cc/8.34 lbs),
60 Cei = concentration of radionuclide in condensate (pCi/cc),
DBP 6027A 45 Revision 11.0 ODCM
p; l
0.065 = m2ss flow rate ratin of moisture separator drain to condensate, P = fraction of moisture separator drain flow routed to feedwater, C.i = concentration of radionuclide in moisture separator drain (pCi/cc),
3 flowrate of off gas system (ft / min),
F =
28317 = cc per ft' C,i = concentration of radionuclides in off-gas sample ( Ci/cc) i i
i i
DBP 6027A- 46 Revision 11.0 l ODCM l
n
'3.7 NOBLE GAS DOSE CALCULATIONS - 10 CFR 50 3.7.1 UNRFRTRICTED AREA Dose Iimits Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in this
' Section or the methodology used in GASPAR II (NUREG/CR-4653) at least once per 31 (i days. This periodic assessment of releases of noble gases is to evaluate compliance with the
' quarterly dose limits and calendar year limits.
The air dose due to noble gases released in gaseous effluents to areas at and beyond the UNRESTRICTED AREA BOUNDARY shall be limited to the following:
- during any calendar quarter: less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and
- during any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, 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.
This specification is provided to implement the requirements of Section II.B, III.A and IV.A 1 of Appendix I,10 CFR Part 50. The limits specified above provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievab:
- This Section implements the requirements of Section III.A of Appendix I that conformance with the guides of Appendix I to be shown by calculational
. procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established for calculating the doses due to the 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 Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.
3.7.2 Dose Calculations - Noble Gases The following equations may be used to calculate the gamma-air and beta-air doses:
DA = 3.17E - 08
- x/ Qso
- I (Mi
- Qi) (3-13)
Dp = 3.17E-08
- x/ Qso
- I(Ni
- Qi) (3-14)
DBP 6027A- 47 Revision 11.0 ODCM
y j where:
i DA = air dose due to gamma emissions for noble gas radionuclides (mrad),
l Dp = air dose due to beta emissions for noble gas radionuclides (mrad),
i x/QNo = atmospheric X/Q value for direct exposure to noble gas at the 3
UNRESTRICTED AREA BOUNDARY given in Table 3-6 (sec/m ),
Q, ' = cumulative release of noble gas radionuclide "i" over the period of interest ( Ci),
! M; =. air dose factor due to gamma emissions from noble gas radionuclide 3
"i" (mradlyr per pCi/m ) from Table 3 5, I
Ni = air dose factor due to beta emissions from noble gas radionuclide "i" 3
(mrad /yr per pCi/m ) from Table 3 5, and s
1 3.17E-08 = 1/3.15E+07 (yr/sec). )
3.7.3 Simolified Dose Calculation for Noble Gases In lieu of the individual noble gas radionuclide dose assessment presented above, the following simplified equations may be used for verifying compliance with the dose limits of Section 3.7.1. (Refer to Appendix B for the derivation andjustification of this simplified method.)
i DA = 2.0
- 3.17E - 08
- x / Qso
- M err
- E Qi (3-15) and Dp = 2.0
- 3.17E - 08
- x / Q uo
- Ne rr
- I Qi (3-16) where:
Merr
= 5.7E+02, effective gamma-air dose factor from Appendix B (mrad /yr 3
per pCi/m ),
Nerr
= ' 1.lE+03, effective beta-air dose factor from Appendix B (mrad /yr 3
per pCi/m ), and 2.0 = conservatism factor to account for potential variability in the radionuclide distribution.
i DBP 6027A 48 Revision 11.0 ODCM L
3.8' RADIOIODINE, TRITIUM AND PARTICULATE DOSE CALCULATIONS - 10 CFR 50 3.8.l' UNRFSTRICTED AREA Dose I imits
. A periodic assessment is required to evaluate compliance with the quarterly dose limit and the calendar year limit to any organ. Cumulative dose contributions for the cunent calendar quarter and current calendar year for I-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in this Section or the methodology used in GASPAR II (NREG/CR-4653) at least once per 31 days.
The dose to a MEMBER OF THE PUBLIC from I-131, tritium and all radionuclides in - ]
particulate form with half-lives greater than 8 days in gaseous effluents released to areas at !
and beyond the UNRESTRICTED AREA BOUNDARY shall be limited to the following: l
- . During any calendar quarter: less than or equal to 7.5 mrem to any organ, and
- During any calendar year: less than or equal to 15 mrem to any organ.
With the calculated dose from the release ofiodine-131, tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, a Special report that identifies the cause(s) for exceeding the limit 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.
This requirement is provided to implement the requirements of Section II.C, III.A, and IV.A of Appendix I,10 CFR Part 50. The limits are the guides set forth in Section II.C of Appendix I. The actions specified provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." !
The ODCM calculational methods specified in this Section implement the requirements in Section III.A of Appendix I that'conformance with the guides of Appendix I be shown by calculational procedure based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, l
" Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the !
Purpose of Evaluating Compliance with 10 CFR 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111," Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.
)
l DBP 6027A 49 Revision 11.0 ;
l l
He release rate specific _tions for radiciodines and radioactive mat: rial in particulate form l are dependent on the existing radionuclide pathways to man in the UNRESTRICTED AREA.
The pathways which are examined in the development of these calculations are:
{
l
- individual inhalation of airborne radionuclides, !
I deposition of radionuclides into green leafy vegetation with sub.;equent consumption by man, deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and
~ deposition on the ground with subsequent exposure of man.
3.8.2 Critical Pathway The critical pathway is that exposure pathway, age group, organ, and receptor location for I which the maximum dose is calculated due to a given gaseous release of radionuclides, l Determination of the critical pathway is made as part of the Annual Land Use Census. As l part of this process, the maximum exposure pathway is determined for each directional sector !
in the area surrounding Davis-Besse. The maximum exposure pathways for each sector are I listed in Table 3-4. The critical pathway is chosen from among the maximum pathways for each sector and is listed in Table 3-6.
1 Only the dose via the critical pathway identified in Table 3-6 need be evaluated for compliance with the dose limits of Section 3.8.1. Dose shall be calculated to the organ with the highest dose factor for the controlling age gwup to determine the maximum organ dose.
The dose factors for organs of the various age groups are listed by exposure pathway in Tables 3-7 through 3-12. The meteorological dispersion values used (Table 3-6) may be those derived from current Land Use Census or those created by XOQDOQ.
3.8.3 Dose Calculations - Radiciodine. Tritium and Particulates The following equation may be used to evaluate the maximum organ dose due to releases of iodine-131, tritium and particulates with half lives greater than 8 days:
D., = 3.17E - 08
- W
- ICF ^ SF
- I(Rg
- Qi) (3 17)
Where:
Dop = dose or dose commitment to organ "o" via controlling pathway "p" and age group "a" as identified in Table 3-6 (mrem),
W = atmospheric dispersion factor to the controlling location as identified in Table 3-6
-W =
x/Q, dispersion contribution factor via all pathways for inhalation p)athway and H-3 dose (sec/m W = D/Q, deposition factor for vegetation, milk and ground plane exposure pathways (m-2),
DBP 6027A 50 Revision i1.0 ODCM L
W = D/Q, deposition factor for vegetation, milk and ground plane exposure pathways (m-2),
Rio
= dose factor for radionuclide "i" to organ "o" of age group "a"_ via pathway "p" as identified in Table 3-7,3 8,3-9,3-10,3-11, or 3-12 depending on the pathway specified (mrem /yr per pCi/m') or (m* -
mrem /yrper Ci/sec),
Qi
= cumulative release over the period ofinterest for radionuclide "i"
'(pCi),
ICF = elemental iodine correction factor which may be used in calculating doses from radioiodines via the vegetation, milk, and ground plane exposure pathways = 0.5, SF = seasonal correction factor which may be used for milk and vegetation pathways = 0.5, and 3.17E-08 = 1/3.15E+07 (yr/sec).
. The dose factors in Tables 3-7 through 3-12 are derived in accordance with NUREG-0133.
The elemental iodine correction factor in equation (3 17) is referenced in Regulatory Guide 1.109, 3.8.4 Simolified Dose Calculation for Radiciodine. Tritium and Particulates In lieu of the individual radionuclide dose assessment presented in equation (3-17) the following simplified dose calculation may be used for verifying compliance with the dose limits of Section 3.8.1:
D,, = 3.17E - 08
- W
- ICF
- SF
- Ri .i3, *IQi (3-18) where:
Dom-
= maximum organ dose (mrem),
R.m i
= I-131 dose factor for the thyroid for the controlling pathway identified in Table 3-6, and IQi = sum of the activities of all radioiodines, tritium and particulates (pCi).
The ground plane exposure and inhalation pathways need not be considered when the simplified method is used because of the negligible contribution of these pathways to the total thyroid dose. It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway, liowever, use of the 1-131 thyroid dose factor for all radionuclides will maximize the organ dose calculation, especially considering that no other radionuclide has a higher dose factor for any organ via any pathway than 1-131 for the thyroid via the vegetable or milk pathway.
DBP 6027A 51 Revision 11.0 ODCM E
p
,- 3.9 GASEOUS EFFLUENT DOSE PROJECTION t
l As with liquid effluents, gaseous effluents require processing if the projected dose exceeds specified limits. This requirement implements the requirements of 10 CFR 50.36a on maintaining and using the appropriate radwaste processing equipment to keep releases ALARA.
The GASEOUS RADWASTE TREATMENT SYSTEM (i.e., Waste Gas Decay Tank) shall be used to reduce noble gas levels prior to discharge when the projected air dose due to gaseous effluent releases to areas at and beyond the UNRESTRICTED AREA BOUNDARY would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation in a 31 day period (i.e., one quarter of the design objective rate).
The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioiodine and particulate effluents, prior to their discharge, when the projected dose due to
. gaseous effluents releases to areas at or beyond the UNRESTRICTED AREA BOUNDARY q would exceed 0.3 mrem to any organ in a 31-day period. Figure 3-1 presents the gaseous ;
effluent release points and the GASEOUS RADWASTE and VENTILATION EXHAUST TREATMENT SYSTEMS applicable for reducing effluents prior to release.
I With the gaseous waste being discharged without treatment and in excess of the limits, in lieu {
of a Licensee Event Report, prepare and submit to the commission within 30 days, pursuant to Section 7.3 a Special Report that includes the following information:
- Explanation of why gaseous radwaste was being discharged without treatment, l identification of any inoperable equipment or subsystems, and the reasons for the !
inoperability, I j
- Actions taken to restore the inoperable equipment to OPERABLE status, and
- Summary description of action (s) taken to prevent a recurrence.
l The requirements that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This requirement implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents. I If the GASEOUS RADWASTE and VENTILATION EXHAUST TREATMENT SYSTEMS are not being used, dose projections shall be performed at least once per 31 days using the
- following equations:
lA p= DA *(31/ d) (3-19) !
- Dpp = Dp * (31/ d) (3-20) 1 l
=D ox * (31/ d)
D ox , (3-21) l DBP 6027A 52 Revision i1.0 ODCM l
-where:
L DAp = projected 31-day gamma-air dose (mrad),
DA = gamma-air dose for current calendar quarter (mrad),
Dpp = projected 31-day beta-air dose (mrad), j Dp = beta-air dose for current calendar quarter (mrad), .
D.xp = projected 31-day maximum organ dose (mrem),
Dm., = maximum organ dose for current calendar quarter as determined by equation (3-17) or (3-18) (mrem),
d = number of days accounted for by current calendar quarter dose, and 31 = number of days in projection.
i 1
i DBP 6027A 53 Revision 11.0 ODCM
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Table 31 (Continued) l TABLE NOTATION l
i
-(l) 'During radioactive waste gas releases via this pathway.
(2) ' During additions to the waste gas surge tani j ACTION A With the number of channels OPERABLE less than required by the minimum
. channels OPERABLE requirement, the contents of the tank may be released to the environment provided that prior to initiating the release:
1.' 5t least two independent samples are analyzed in accordance with Table 3-3 for analyses performed with each batch;
- 2. At least two independent verifications of the release rate calculations are performed;
- 3. At least two independent verifications of the discharge valving are performed.
ACTION B 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 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION C With the number of channels OPERABLE less than required by the minimum -
channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed in accordance -
with applicable procedures.
. ACTION D With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, additions to the waste gas surge tani: may continue provided another method for ascertaining oxygen concentrations, such as grab sample analysis, is implemented to provide measurements at least once per four(4) hours during degassing and daily during other operations.
. ACTION E With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment, as required in Table 3-3 (this requirement is not applicable for routine replacement of sampling media or routine testing).
DBP 6027A 55 Revision a '. 0 ODCM
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Table 3-2 (Continued)
TABLE NOTATION (1) During radioactive waste gas releases via this pathway.
(2) During additions to the waste gas surge tank. 1 (3) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this -
. pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the alarm / trip setpoint.
(4) The CIIANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if the instrument indicates measured levels above the alarm / trip setpoint.
- (5) The initial CIIANNEL CALIBRATION for radioactivity measurement instrumentation shall
. be performed using one or more reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that
. participate in measurement assurance activities with NIST. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per eighteen months. For high range monitoring instrumentation, where calibration with a radioactive source is impractical, an electronic calibration may be substituted for the radiation source calibration.
(6) The CHANNEL CALIBRATION shall include the use of standard gas samples containing e nominal:
(7) - During containment purges.
(8) When used in a continuous mode.
P Prior to each release.
R At least once per 18 months (550 days).
. .Q At least once per 92 days.
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 />.
M At least once per 31 days.
W At least once per 7 days.
- DBP 6027A' 57 Revision i1.0 ODCM i rr - - -
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TABI.E NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank {
observation represents a "real" signal.
For a particular measurement system (which may include radio-chemical separation):
4.66s3 LLD = l E
- V
- 2.22
- Y
- exp(-AAt) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);
sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute);
E is the counting efficiency (as counts per transformation);
V is the sample size (in units of mass or volume);
2.22 is the number of transformations per minute per picoeurie; Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radionuclide; At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.
l it should be recognized that the LLD is defined as an a pnori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
- b. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Sections 3.3.1 and 3.8.
DBP 6027A 59 Revision 11.0 ODCM L
Table 3-3 (Continued)
TABLE NOTATION c.. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr 88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Cc-144 for particulate emissions. This list does not mean that only these nuclides are to be
. detected and reported. Other peaks which are measured and identified, together with the above nuclides,.shall also be identified and reported. Nuclides which are below the LLD for the analyses should be reported as "less than" the nuclide's LLD and should not be reported as being present at the LLD level for the nuclide. The "less than" values shall not be used in the required dose calculations. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Radioactive Effluent Release Report.
Frequency notation:
P - Prior to each release.
M - At least once per 31 days.
W - At least once per 7 days, f
Q - At least once per 92 days.
. DBP 6027A 60 Revision 11.0 ODCM l: -_____ - _ _ _
r Table 3-4 Land Use Census Summary Exposure Pathway Locations and Atmospheric Dispersion Parameters l l
Distance Exposure Controlling /
XQ D/Q !
Pathway 3 S Sector (meters) Age Group (sec/m ) (m )
N' 880 inhalation child 9.15E-07 8.40E-09 NNE 870 inhalation child 1.27E-06 1.47E-08 NE 900 inhalation child 1.26E-06 1.58E-08 ENE* - - - - -
E* - - - - -
ESE* - - - - -
SE* - - - - -
SSE 2,820 vegetation child 7.02E-08 8.36E-10 S 3,440 vegetation child 4.39E-08 4.55E-10 SSW*
- 3,450 vegetation child 3.98E-08 5.llE-10 l SW" 5,140 vegetation child 3.88E-08 3.45E-10 l WSW 7,010 vegetation child 3.60E-08 2.03E-10 l W 1,640 vegetation child 2.69E-07 4.21E-09 WNW" 3,650 vegetation child 5.67E-08 4.28E-10 l NW 2,320 vegetation child 6.91E-08 5.70E 10 NNW 1,210 inhalation child 2.70E-07 1.92E-09
- Since these sectors are located over marsh areas and Lake Erie, no ingestion or inhalation pathways are present.
" These values are a change to this table as a result of the 1997 Land Use Census.
Note: The meteorological dispersion factors are taken from the Stone and Webster report, Handbook for ODCM y/O and D/O Calculations, October 1983.
DBP 6027A 61 Revision 11.0 ODCM
Table 3-5 Dose Factors for Noble Gases
- Total Body - Skin Gamma Air Beta Air Gamma Dose Beta Dose Dose Factor Dose Factor Factor Ki Factor Li Mi Ni (mrem /yr per (mrem /yr per (mrad /yr per (mrad /yr per Nuclide uCi/m3 L., uCi/m L I
uCi/m3 L uCi/ml )_
' Kr-83m 7.56E-02 -- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+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 7.83 E+03 Xe-131m 9.15E+01 4.76E+02 1.56E402 1.llE+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E402 3.06E+02 3.53E+02 1.05E+03 I
Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 f Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 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 i
l l
l l
I 1
i I
i
- Dose factors taken from NRC Regulatory Guide 1.109 !
l DBP 6027A 62 Revision 11.0 ODCM j
\
Table 3-6 Exposure Pathways, Controlling Parameters, and Atmospheric Dispersion i for Dose Calculations Atmospheric Dispersion Exposure Receptor Controlling x/g D/Q I
Pathway Location Age Group (sec/m ) (m.2) Use noble gases UNRESTRICTED (Ul .83E-06 N/A (a) direct AREA BOUNDARY
. exposure NNE inhalation UNRESTRICTED child (0 1.68E-06 N/A (a)
AREA BOUNDARY NNE 1640 meters W- child U)2.69E-07 (u4.21E-09 (b),(c)
(critical pathway) garden Variable (2) Variable (2) Variable (c),(d)
Dispersion Factors i
'(a) To calculate allowable release rates (b) To reflect results of Land Use Census (c) To screen individual releases for dose and/or calculate 31 day dose (d) To calculate annual dose and/or calculate 31 day dose NOTES:
- 1. Meteorological dispersion values have been taken from the Stone and Webster report, Handbook for ODCM xLQ and DZQ Calculations. October 1983.
- 2. ' . Meterological dispersion values generated using XOQDOQ (NUREG/CR-2919) for input into GASPAR. Meterological data may be historic or real time.
- 3. The noble gas, direct exposure x/Qs are based on the decayed, undepleted values.
- 4. The inhalation pathway x/Qs are based on the decayed, depleted values.
1 1
DBP 6027A 63 Revision 11.0 l ODCM N- w-._
l Table 3-7 l
Rjo inhalation Pathway Dose Factors ADULT i
l (mrem /yr per pCi/m')
Huslids llong Liver 'nivroid Kidacy . Lung GI-LLI LBady H-3 -
1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 C-14' l.82E+4 3.41E+3 3.41 E+3 3.41 E+3 3.41 E+3 3.41 E+3 3.41 E+3 Na-24 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 i P-32 1.32E+6 7.71E+4 - - -
8.64E+4 5.01E+4 Cr-51 - -
5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.00E+2 Mn-54 - 3.96E+4 - 9.84E+3 1.40E+6 7.74E+4 6.30E+3 Mn 56 - 1.24E+0 - 1.30E+0 9.44E+3 2.02E+4 1.83E 1 1 Fe-55 2.46E+4 1.70E+4 - - 7.21E+4 6.03E+3 3.94E+3 Fe-59 1.18E+4 2.78E+4 - - 1.02E+6 1.88E+5 1.06E+4 Co-57 - 6.92E+2 - - 3.70E+5 3.14E+4 6.71E+2 Co-58 - 1.58E+3 - - 9.28E+5 1.06E+5 2.07E+3 Co 60 - 1.15E+4 - - 5.97E+6 2.85E+5 1.48E+4 l
Ni-63 4.32E+5 3,14E+4 - - 1.78E+5 1.34E+4 1.45E+4 Ni-65 1.54E+0 2.10E-1 - -
5.60E+3 1.23E+4 9.12E-2 Cu 64 - 1.46E+0 - 4.62E+0 6.78E+3 4.90E+4 6.15E-1 4
Zn-65 3.24E+4 1.03 E+5 - 6.90E+4 8.64E+5 5.34E+4 4.66E+4 Zn-69 3.38E-2 6.51 E-2 - 4.22E.2 9.20E+2 1.63E+1 4.52E-3 Br-82 - - - - - 1.04E+4 1.35E+4 Br-83 - - - - - 2.32E+2 2.41 E+2 Br-84 - - - - - 1.64E-3 3.13E+2 Br 85 - - - - - - 1.28E+1 Rb-86 - 1.35E+5 - - - 1.66E+4 5.90E+4 Rb-88 - 3.87E+2 - - - 3.34E-9 1.93E+2 Rb-89 - 2.56E+2 - - - - 1.70E+2 Sr-89 3.04E+5 - - - 1.40E+6 3.50E+5 8.72E+3 Sr-90 9.92E+7 - - - 9.60E+6 7.22E+5 6.10E+6 Sr91 6.19E+1 - - - 3.65E+4 1.91E+5 2.50E+0 Sr-92 6.74E+0 - - - 1.65 E+4 4.30E+4 2.91 E-1 Y-90 2.09E+3 - - - 1.70E+5 5.06E+5 5.61E+1 Y-91m 2.61E 1 - - - 1.92E+3 1.33E+0 1.02E-2 Y-91 4.62E+6 - - - 1.70E+6 - 3.85E+5 1.24E+4 Y-92 1.03 E+1 - - - 1.57E+4 7.35 E+4 3.02E-1 Y-93 9.44E+1 - - - 4.85E+4 4.22E+5 2.61 E+0
! Zr-95 1.07E+5 3.44E+4 - 5.42E+4 1.77E+6 1.50E+5 2.33 E+4 Zr 97 9.68E+1 - 1.96E+1 - 2.97E+1 7.87E+4 5.23E+5 9.04E+0 Nb 95 1.41 E+4 7.82E+3 -
7.74E+3 5.05E+5 1.04E+5 4.21 E+3 Nb-97 2.22E-1 5.62E-2 - 6.54E 2 2.40E+3 2.42E+2 2.05 E-2 Mo 99 - - 1.21E+2 - 2.91 E+2 9.12E+4 2.48E+5 2.30E+1
' Tc-99m 1.03 E-3 2.91E 3 - 4.42E-2 7.64E+2 4.16E+3 3.70E-2 Tc-101 4.18E 5 6.02E-5 - 1.08E 3 3.99E+2 - 5.90E-4 DBP 6027A' 64 Revision 11.0 ODCM i-
Table 3-7 Ri o Inhalation Pathway Dose Factors - ADULT (Continued)
(mrem /yr per pCi/m')
, Nuchde Liver Thyroid Kidney Lung GI-LLI T. Body Bone Ru 103 1.53 E+3 - - 5.83E+3 5.05 E+5 1.10E+5 6.58E+2 Ru 105 7.90E-1 - - 1.02E+0 1.10E+4 4.82E+4 3.llE-1 l Ru-106 6.91 E+4 - - 1.34E+5 9.36E+6 9.12E+5 8.72E+3 Rh 103m - - - - - -
Rh-106 - - - - -
Ag-110m 1.08E+4 1.00E+4 -
1.97E+4 4.63E+6 3.02E+5 5.94E+3 Sb 124 3.12E+4 5.89E+2 7.55E+1 - 2.48E+6 4.06E F5 1.24E+4
' Sb 125 5.34E+4 5.95E+2 5.40E+1 -
1.74E+6 1.01 E+5 1.26E+4 Te 125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3 Te-127 1.40E+0 6.42E-1 1.06E+0 5.10E+0 6.51 E+3 5.74E+4 3.10E-1 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83 E+5 1.58E+3 Te-129 4.98E-2 2.39E-2 3.90E-2 1.87E-1 1.94E+3 1.57E+2 1.24E-2 Te-131m 6.99E+1 4.36E+1 5.50E+1 3.09E+2 1.46E+5 5.56E+5 2.90E+1 Te 131 1. ! ! E-2 5.95E-3 9.36E-3 4.37E-2 1.39E+3 1.84E+1 3.59E-3 Te 132 2.60E+2 2.15E+2 1.90E+2 1.46E+3 2.88E+5 5.10E+5 1.62E+2
- I 130 4.58E+3 1.34E+4 1.14E+6 2.09E+4 - 7.69E+3 5.28E+3 1131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 - 6.28E+3 2.05 E+4 I132 1.16E+3 3.26E+3 1.14E+5 5.18E+3 - 4.06E+2 1.16E+3 I-133 8.64E+3 1.48E+4 2.15 E+6 2.5 8E+4 - 8.88E+3 4.52E+3 I134 6.44E+2 1.73E+3 2.98E+4 2.75E+3 - 1.01E+0 6.15E+2 I135 2.68E+3 6.98E+3 4.48E+5 1.llE+4 - 5.25E+3 2.57E+3 Cs 134 3.73E+5 8.48E+5 - 2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 -
8.56E+4 1.20E+4 1.17E+4 1.10E+5 Cs-137 4.78E+5 6.21 E+5 - 2.22E+5 7.52E+4 8.40E+3 4.28E+5 Cs-138 3.31E+2 6.21 E+2 - 4.80E+2 4.86E+1 1.86E-3 3.24E+2 Ba-139 - 9.36E-1 6.66E-4 -
6.22E-4 3.76E+3 8.96E+2 2.74E-2 Ba-140 3.90E+4 4.90E+1 - 1.67E+1 1.27E+6 2.18E+5 2.57E+3 Ba-141 1.00E-l 7.53 E-5 - 7.00E 1.94E+3 1.16E-7 3.36E 3 Ba-142 2.63E 2 2.70E 5 - 2.29E-5 1.19E+3 -
1.66E-3 La-140 3.44E+2 1.74E+2 - -
1.36E+5 4.58E+5 4.58E+1 La-142 6.83E-1 3.10E-1 - - 6.33E+3 2.l l E+3 7.72E-2 Ce 141 1.99E+4 1.35E+4 - 6.26E+3 3.62E+5 1.20E+5 1.53E+3 Ce-143 1.86E+2 1.38E+2 - 6.08E+1 7.98E+4 2.26E+5 1.53 E+1 Ce-144 3.43E+6 1.43E+6 -
8.48E+5 7.78E+6 8.16E+5 1.84E+5 I
Pr-143 9.36E+3 3.75 E+3 -
2.16E+3 2.81E+5 2.00E+5 4.64E+2 Pr-144 3.01 E-2 1.25E-2 -
7.05E 3 1.02E+3 2.15E-8 1.53 E-3 Nd-147 5.27E+3 6.10E+3 -
3.56E+3 2.21 E+5 1.73E+5 3.65E+2 W-187 8.48E+0 7.08E+0 - - 2.90E+4 1.55E+5 2.48E+0 Np-239 2.30E+2 2.26E+1 -
7.00E+1 3.76E+4 1.19E+5 1.24E+1 DBP 6027A 65 Revision i1.0 ODCM
l Table 3-7 Rjo Inhalation Pathway Dose Factors - TEENAGER L (mrem /yr per pCi/m')
Nuclide Ilong Liver Thyroid Kidney Lung GI LLI T. Body i H-3 - 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3
'C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 Na-24 1.38E+4 1.38 E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 1.38E+4 P-32 1.89E+6 1.10E+5 - - - 9.28E+4 7.16E+4 Cr-51 - -
7.50E+1 3.07E+1 2.10E+4 3.00E+3 1.35E+2 j l
Mn-54 -
5.llE+4 -
1.27E+4 1.98E+6 6.68E+4 8.40E+3 l Mn-56 - 1.70E+0 -
1.79E+0 1.52E+4 5.74E+4 2.52E-1 Fe 55 3.34E+4 2.38E+4 - -
1.24E+5 6.39E+3 5.54E+3 j Fe-59 1.59E+4 3.70E+4 - - 1.53E+6 1.78E+5 1.43E+4 j Co-57 - 6.92E+2 - - 5.86E+5 3.14E+4 9.20E+2 l
Co 58 - 2.07E+3 - - 1.34E+6 9.52E+4 2.78E+3 Co-60 - 1.51E+4 - - 8.72E+6 2.59E+5 1.98E+4 Ni-63 5.80E+5 4.34E+4 - -
3.07E+5 1.42E+4 1.98E+4 Ni-65 2.18E+0 2.93E-1 - - 9.36E+3 3.67E+4 1.27E-1 i Cu-64 - 2.03E+0 - 6.41E+0 1.11 E+4 6.14E+4 8.48E-1 Zn-65 3.86E+4 1.34E+5 - 8.64E+4 1.24E+6 4.66E+4 6.24E+4 Zn-69 4.83E-2 9.20E-2 - 6.02E-2 1.58E+3 2.85E+2 6.46E-3 Br-82 - - - - - - 1.82E+4 i Br-83 - - - - - -
3.44E+2 i Br 84 - - - - - -
4.33E+2 Br-85 - - - - - -
1.83 E+1 Rb 86 - 1.90E+5 - - -
1.77E+4 8.40E+4 Rb-88 - 5.46E+2 - - - 2.92E-5 2.72E+2 Rb-89 - 3.52E+2 - - -
3.38E-7 2.33E+2 l Sr 89 4.34E+5 - - - 2.42E+6 3.71E+5 1.25E+4 Sr-90 1.08E+8 - - - 1.65 E+7 7.65E+5 6.68E+6 Sr-91 8.80E+1 - - -
6.07E+4 2.59E+5 3.51E+0 l Sr-92 9.52E+0 - - -
2.74E+4 1.19E+5 4.06E-1 Y-90 2.98E+3 - - - 2.93E+5 5.59E+5 8.00E+1 Y 91m 3.70E-1 - - - 3.20E+3 3.02E+1 1.42E-2 Y-91 6.61 E+5 - - -
2.94E+6 4.09E+5 1.77E+4 Y-92 1.47E+1 - - - 2.68E+4 1.65 E+5 4.29E-1 Y-93 1.35E+2 - - - 8.32E+4 5.79E+5 3.72E+0 Zr-95 1.46E+5 4.58E+4 - 6.74E+4 2.69E+6 1.49E+5 3.15E+4 L Zr-97 1.38E+2 2.72E+1 - 4.12E+1 1.30E+5 6.30E+5 1.26E+ 1 Nb 1.86E+4 1.03E+4 - 1.00E+4 7.51 E+5 9.68E+4 5.66E+3 Nb-97 3.14E-1 7.78E-2 - 9.12E-2 3.93E+3 2.17E+3 2.84E-2 Mo-99 - 1.69E+2 - 4.l l E+2 1.54E+5 2.69E+5 3.22 E+1 Tc-99m 1.38E-3 3.86E-3 -
5.76E-2 1.15E+3 6.13E+3 4.99E-2 Tc-101 5.92E-5 8.40E-5 - 1.52E 3 6.67E+2 8.72E-7 8.24E-4
' DBP 6027A 66 Revision 11.0 ODCM u
r Table 3 7 '
Rjo. Inhalation Pathway Dose Factors TEENAGER (Continued)
(mrem /yr per pCi/m') l T. Body I
Nuchde Bonc .. Liver Thyroid Kidney Lung GI-LLI i'
Ru-103 2.10E+3 - - 7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru 105 1.12E+0 - - 1.41E+0 1.82E+4 9.04E+4 4.34E-1 Ru-106 9.84E+4 - -
1.90E+5 1.61E+7 9.60E+5 1.24E+4 -
Rh-103m - - - -
Rh-106 - - - -
Ag-110m 1.38E+4 1.31E+4 - 2.50E+4 6.75 E+6 2.73 E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 - 3.85E+6 3.98E+5 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 - 2.74E+6 9.92E+4 1.72E+4 Te 125m 4.88E+3 2.24E+3 1.40E+3 - 5.36E+5 7.50E+4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54 E+4 1.66E+6 1.59E+5 2.18E+3 Te-127 2.01 E+0 9.12E-1 1.42E+0 7.28E+0 1.12E+4 8.08E+4 4.42E-1 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.25E+3 Te-129 7.10E 2 3.38E-2 5.18E-2 2.66E-1 3.30E+3 1.62E+3 1.76E-2 Te 131m 9.84E+1 6.01E+1 7.25E+1 4.39E+2 2.38E+5 6.21E+5 4.02E+1 Te-131 1.58E-2 8.32E-3 1.24E-2 6.18E 2 2.34E+3 1.51E+1 5.04E-3 ,
Te 132 3.60E+2 2.90E+2 2.46E+2 ' l.95E+3 4.49E+5 4.63E+5 2.19E+2 I.130 6.24E+3 1.79E+4 1.49E+6 2.75 E+4 - 9.12E+3 7.17E+3 I-131 3.54E+4 4.91 E+4 1.46E+7 8.40E+4 - 6.49E+3 2.64E+4 I132 1.59E+3 4.38E+3 1.51E+5 6.92E+3 -
1.27E+3 1.58E+3 I133 1.22E+4 2.05E+4 2.92E+6 3.59E+4 -
1.03E+4 6.22E+3 I134 8.88E+2 2.32E+3 3.95E+4 3.66E+3 - 2.04E+1 8.40E+2 .
1135 3.70E+3 9.44E+3 6.21E+5 1.49E+4 - 6.95E+3 3.49E+3 ;
Cs-134 5.02E+5 1.13E+6 - 3.75 E+5 1.46E+5 9.76E+3 549E+5 Cs-136 5.15E+4 1.94E+5 - 1.10E+5 1.78E+4 1.09E+4 1.37E+5 Cs 137 6.70E+5 8.48E+5 - 3.04E+5 1.21 E+5 8.48E+3 3.l lE+5
- Cs 138 4.66E+2 8.56E+2 -
6.62E+2 7.87E+1 2.70E-1 4.46E+2 Ba-139 1.34E+0 9.44E-4 - 8.88E-4 6.46E+3 6.45E+3 3.90E-2 Ba-140 5.47E+4 6.70E+1 - 2.28E+1 2.03E+6 2.29E+5 3.52E+3 Ba-141 1.42E-1 1.06E-4 - 9.84E-5 3.29E+3 7.46E-4 4.74E-3 Ba-142 3.70E-2 3.70E-5 - 3.14E-5 1.91E+3 - 2.27E-3 .
l La 140 4.79E+2 2.36E+2 - - 2.14E+5 4.87E+5 6.26E+1 La 142 9.60E-1 4.25 E-1 - - 1.02E+4 1.20E+4 1.06E-1 Ce-141 2.84E+4 1.90E+4 - 8.88E+3 6.14E+5 1.26E+5 2.17E+3 Ce 143 2.66E+2 1.94E+2 - 8.64E+1 1.30E+5 2.55E+5 2.16E+1 Cc-144 4.89E+6 2.02E+6 -
1.21E+6 1.34E+7 8.64E+5 2.62E+5 Pr 143 1.34E+4 5.31 E+3 - 3.09E+3 4.83 E+5 2.14E+5 6.62E+2 Pr-144 4.30E-2 1.76E-2 -
1.01E 2 1.75 E+3 2.35 E-4 2.18E-3
- Nd 147 7.86E+3 8.56E+3 - 5.02E+3 3.72E+5 1.82E+5 5.13 E+2 W-187 1.20E+1 9.76E+0 - -
4.74E+4 1.77E+5 3.43E+0 Np-239 3.38E+2 3.19E+1 - 1.00E+2 6.49E+4 1.32E+5 1.77E+1 DBP 6027A 67 Revision 11.0 ODCM j i
]
- _ __-_ _ _ __ _ _ a
Table 3 7 Ri o inhalation Pathway Dose Factors - CIIILD 3
(mrem /yr per pCi/m )
Nuclide Bang. Liver Thyroid Kidney Lung GI-LLI T. Body II3 - 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73 E+3 Na-24 1.61E+4 1.61E+4 1.61 E+4 ' l.61E+4 1.61E+4 1.61E+4 1.61 E+4 P-32 2.60E+6 1.14E+5 - - - 4.22E+4 9.88E+4 Cr-51 - - 8.55 E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Mn-54 - 4.29E+4 - 1.00E+4 1.58E+6 2.29E+4 9.51 E+3 Mn-56 -
1.66E+0 - 1.67E+0 1.31 E+4 1.23E+5 3.12E-1 Fe-55 4.74E+4 2.52E+4 - -
1.11E+5 2.87E+3 7.77E+3 Fe-59 2.07E+4 3.34E+4 - -
1.27E+6 7.07E+4 1.67E+4 Co 57 -
9.03E+2 - -
5.07E+5 1.32E+4 1.07E+3 Co-58 - 1.77E+3 - -
1.llE+6 3.44E+4 3.16E+3 Co-60 -
1.31E+4 - - 7.07E+6 9.62E+4 2.26E+4 Ni-63 8.21 E+5 4.63E+4 - - 2.75E+5 6.33E+3 2.80E+4 Ni-65 2.99E+0 2.96E-1 - -
8.18E+3 8.40E+4 1.64E-1 Cu-64 -
1.99E+0 - 6.03E+0 9.58E+3 3.67E+4 1.07E+0 Zn-65 4.26E+4 1.13E+5 -
7.14E+4 9.95E+5 1.63E+4 7.03E44 Zn-69 6.70E-2 9.66E-2 - 5.85E-2 1.42E+3 1.01E+4 8.92E-3 Br-82 - - - - - - 2.09E+4 Br 83 - - - - - - 4.74E+2 Br-84 - - - - - -
5.48E+2
- Br-85 - - - - - -
2.53E+1 Rb-86 -
1.98E+5 - - -
7.99E+3 1.14E+5 Rb-88 - 5.62E+2 - - - 1.72E+1 3.66E+2 Rb-89 -
3.45E+2 - - -
1.89E+0 2.90E+2 Sr-89 5.99E+5 - - - 2.16E+6 1.67E+5 1.72E+4 St-90 1,01E+8 - - -
1.48E+7 3.43E+5 6.44E+6 Sr-91 1.21 E+2 - - -
5.33E+4 1.74E+5 4.59E+0 Sr-92 1.31 E+1 - - - 2.40E+4 2.42E+5 5.2S E-1 Y-90 4.11E+3 - - - 2.62E+5 2.68E+5 1.11 E+2 Y-91m 5.07E-1 - - - 2.81 E+3 1.72E+3 1.84E-2 Y-91 9.14E+5 - - - 2.63E+6 1.84E+5 2.44E+4 Y-92 2.04E+ 1 - - - 2.39E+4 2.39E+5 5.81 E-1 Y-93 1.86E+2 - - -
7.44E+4 3.89E+5 5.11E+0 Zr-95 1.90E+5 4.18E+4 - 5.96E+4 2.23E+6 6.l l E+4 3.70E+4 Zr-97 1.88E+2 2.72E+1 - 3.89E+1 1.13E+5 3.51 E+5 1.60E+1 Nb-95 2.35E+4 9.18E+3 - 8.62E+3 6.14E+5 3.70E+4 6.55E+3 Nb-97 4.29E-1 7.70E-2 -
8.55E-2 3.42E+3 2.78E+4 3.60E-2 Mo 99 -
1.72E+2 -
3.92E+2 1.35E+5 1.27E+5 4.26E+1 Tc-99m - 1.78E-3 3.48E-3 - 5.07E-2 9.51 E+2 4.81E+3 5.77E-2 Tc-101 ' 8.10E 5 8.51E-5 - 1,45E-3 5.85E+2 1.63E+1 1.08E-3 DBP 6027A 68 Revision 11.0 ODCM
[-
L L - -
_ __ _ _ ]
i l
Table 3-7 RjoiInhalation Pathway Dose Factors CIIILD (continued) l (mrem /yr per pCi/m')
Nuchde Liver Ihymid Kidacy Lung GI-LLI T. Body Bonc Ru 103 2.79E+3 - - 7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-105 1.53E+0 - -
1.34E+0 1.59E+4 9.95E+4 5.55E-1 Ru-106 1.36E+5 - - 1.84E+5 1.43E+7 4.29E+5 1.69E+4 Rh-103m - - - -
Rh-106 - - - -
Ag 110m 1.69E+4 1.14E+4 -
2.12E+4 5.48E+6 1.00E+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 -
3.24E+6 1.64E+5 2.00E+4 Sb 125 9.84E+4 7.59E+2 9.10E+1 -
2.32E+6 4.03E+4 2.07E+4 Te 125m 6.73E+3 2.33E+3 1.92E+3 - 4.77E+5 3.38E+4 9.14E+2 j Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.48E+6 7.14E+4 3.02E+3 j Te-127 2.77EM 9.51E-1 1.96E+0 7.07E+0 1.00E+4 5.62E+4 6.llE-1 Te-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1.76E+6 1.82E+5 3.04E+3 .
Te-129 9.77E-2 3.50E-2 7.14E-2 2.57E-1 2.93E+3 2.55E+4 2.38E-2 !
l Te-131m 1.34E+2 5.92E+1 9.77E+1 4.00E+2 2.06E+5 3.08E+5 5.07E+1 I
Te 131 2.17E-2 8.44E-3 1.70E-2 5.88E-2 2.05E+3 1.33E+3 6.59E-3 Te-132 4.81E+2 2.72E+2 3.17E+2 1.77E+3 3.77E+5 1.38E+5 2.63E+2 I-130 8.18E+3 1.64E+4 1.85E+6 2.45E+4 -
5.l lE+3 8.44E+3 I131 4.81 E+4 4.81 E+4 1.62E+7 7.88E+4 - 2.84E+3 2.73 E+4 1-132 2.12E+3 4.07E+3 1.94E+5 6.25 E+3 -
3.20E+3 1.88E+3 I-133 1.66E+4 2.03 E+4 3.85E+6 3.38 E+4 -
5.48E+3 7.70E+3 I
I-134 - 1.17E+3 2.16E+3 5.07E+4 3.30E+3 - 9.55E+2 9.95E+2 l l 135 4.92E+3 8.73E+3 7.92E+5 1.34E+4 - 4.44E+3 4.14E+3 j Cs-134 6.51E+5 1.01E+6 - 3.30E+5 1.21E+5 3.85E+3 2.25E+5 Cs-136 6.51E+4 1.71E+5 - 9.55E+4 1.45 E+4 4.18E+3 1.16E+5 Cs-137 9.07E+5 8.25E+5 - 2.82E+5 1.04E+5 3.62E+3 1.28E+5 Cs-138 6.33 E+2 8.40E+2 - 6.22E+2 6.81 E+1 2.70E+2 5.55E+2 Ba-139 1.84E+0 9.84E-4 - 8.62E-4 5.77E+3 5.77E+4 5.37E-2 )
Ba 140 7.40E+4 6.48E+1 -
- 2. l l E+1 1.74E+6 1.02E+5 4.33 E+3 i Ba 141 1.96E-1 1.09E-4 - 9.47E-5 2.92E+3 2.75E+2 6.36E-3 Ba 142 5.00E-2 3.60E-5 - 2.91 E-5 1.64E+3 2.74E+0 2.79E-3 La 140 6.44E+2 2.25E+2 - - 1.83E+5 2.26E+5 7.55E+1 La 142 1.30E+0 4.llE-1 - - 8.70E+3 7.59E+4 1.29E-1 Ce 141 3.92E+4 1.95E+4 - 8.55E+3 5.44E+5 5.66E+4 2.90E+3 d
Cc 143 3.66E+2 1.99E+2 - 8.36E+1 1.15 E+5 1.27E+5 2.87E+1 Ce-144 6.77E+6 2.12E+6 -
1.17E+6 1.20E+7 3.89E+5 3.61 E+5 Pr-143 1.85E+4 5.55E+3 - 3.00E+3 4.33 E+5 9.73E+4 9.14E+2 Pr-144 5.96E-2 1.85E 2 - 9.77E-3 1.57E+3 1.97E+2 3.00E-3 Nd-147 1.08E+4 8.73 E+3 - 4.81 E+3 3.28E+5 8.21 E+4 6.81 E+2 W-187 1.63E+1 9.66E+0 - - 4.l l E+4 9.10E+4 4.33 E+0 Np-239 4.66E+2 3.34E+1 - 9.73E+ 1 5.81E+4 6.40E+4 2.35 E+ 1 l
DBP 6027A 69 Revision 11.0 l ODCM 1
Table 3-7 (continued)
R io Inhalation Pathway Dose Factors -INFANT 3
- (mrem /yr per pCi/m )
- Nuclide Bong Liver Thyroid Kidney Lung GI-LLI T. Body H-3 -
6.47E+2 6.47E+2 6.47E+2 - 6.47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 .i.31E+0 l Na-24 1.06E+4 - 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 P-32 2.03E+6 1.12E+5 - - -
1.61E+4 7.74E+4 Cr-51 - -
5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1 Mn-54 -
2.53E+4 - 4.98E+3 1.00E+6 7.06E+3 4.98E+3 Mn-56 -
1.54E+0 -
1.10E+0 1.25E+4 7.17E+4 2.21E-1 Fe-55 'l.97E+4 1.17E+4 - - 8.69E+4 1.09E+3 3.33E+3 Fe-59 1.36E+4 2.3 G+4 - -
1.02E+6 2.48E+4 9.48E+3 '
Co-57 . . 6.5!3+2 - -
3.79E+5 4.86E+3 6.41E+2 Co-58 - 1.22E+3 - - 7.77E+5 1.l lE+4 1.82E+3 Co-60 - 8.02E+3 - - 4.51E+6 3.19E+4 1.18E+4 -
Ni-63 3.39E+5 2.0/.E+4 - - 2.09E+5 2.42E+3 1.16E+4 Ni-65 2.39E+0 2.84E-1 - - 8.12E+3 5.01E+4 1.23E-1 Cu-64 -
1.88E+0 -
3.9SE40 9.30E+3 1.50E+4 7.74E-1 Zn-65 1.93E+4 6.26E+4 -
3.25E+4 6.47E+5 5.14E+4 3.ll E+4 f Zn-69 ' 5.39E-2 9.67E-2 - 4.02E-2 1.47E+3 1.32E+4 7.18E-3 Br-82 - - - - - -
1.33E+4 Br-83 -- - - - - - 3.81E+2 Br-84 - - - . - - 4.00E+2 Br-85 - - - - - -
2.04E+1
, Rb-86 - 1.90E+5 - - -
3.04E+3 8.82E+4 TRb - 5.57E+2 - - -
3.39E+2 2.87E+2 Rb-89 -
3.21E+2 - - - 6.82E+1 2.06E+2 Sr-89 3.98E+5 - - -
2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 - - -
1.12E+7 1.31E+5 2.59i1+6 Sr-91 9.56E+1 - - - S.26E+4 7.34E+4 3.46E+0 Sr-92 1.05E+1 - - - 2.38E+4 1.40E+5 3.91 E-1 Y-90 3.29E+3 - - - 2.69E+5 1.04E+5 8.82E+1 Y-91m 4.07E-1 - - -
2.79E+3 2.35E+3 1.39E-2 Y-91 5.88E+5 - - -
2.45E+6 7.03E+4 1.57E+4 Y-92 1.64E+11 - - - 2.45E+4 1.27E+5 4.61 E-1 Y-93 = 1.50E+2 - - -
7.64E+4 1.67E+5 4.07E+0 Zr-95 1.15E+5 2.79E+4 -
3.l l E+4 1.75E+6 2.17E+4 2.03E+4
' Zr-97 1.50E+2 2.56E+1 -
2.59E+1 1.10E+5 1.40F+5 1.17E+1
'Nb-95 ~ 1.57E+4 6.43E+3 - 4.72E+3 4.79E+5 1.27E+4 3.78E+3 Nb-971 3.42E 1- 7.29E-2 - 5.70E 3.32E+3 2.69E+4 2.63E-2 Mo-99 - 'l.65E+2 -
2.65E+2 1.35E+5 4.87E+4 3 23E+1 Tc-99m 1.40E-3 2.88E-3 -
3.11E 2 8.11 E+2 2.03E+3 3.72E-2 Tc-101 ' 6.51E-5 8.23E-5 -
9.79E-4 5.84E+2 8.44E+2 8.12E-4 DBP 6027A 70 Revision i1.0 ODCM
i Table 3-7 (continued) f Ri o Inhalation Pathway Dose Factors - INFANT (continued) 3 (mrem /yr per Ci/m )
Nuchde B.ong Liver Ihymid Kidney Lung GI-LLI T. Body Ru-103 2.02E+3 - - 4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-105 . 1.22E+0 - - 8.998-1 1.57E+4 4.84E+4 4.10E-1 Ru 106 . 8.68E+4 - -
1.07E+5 1.16E+7 1.64E+5 1.09E+4 Rh-103m - - - - -
Rh-106 - - - - -
Ag-110m 9.98E+3 7.22E+3 - 1.09E+4 3.67E+6 3.30E+4 5.00E+3 Sb-124 - 3.79E+4 ~ 5.56E+2 1.01 E+2 -
2.65E+6 5.91E+4 - 1.20E+4 Sb-125 5.17E+4 4.77E+2 6.23E+1 - 1.64E+6 1.47E+4 1.09E+4 4 Te-125m 4.76E+3 1.99E+3 1.62E+3 - 4.47E+5 1.29E+4 6.58E+2 Te-127m' l .67E+4 ' 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 Te-127 2.23E+0 9.53 E-1 1.85E+0 4.86E+0 1.03E+4 2.44E+4 4.89E-1 Te-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3 Te-129 7.88E-2 3.47E 2 6.75E-2 1.75E-1 3.00E+3 2.63 E+4 1.88E-2 Te-131m 1.07E+2 5.50E+1 8.93E+1 2.65E+2 1.99E+5 1.19E+5 3.63E+1 Te-131 1.74E-2 8.22E-3 1.58E-2 3.99E-2 2.06E+3 8.22E+3 5.00E-3 Te-132 3.72E '2 2.37E+2 2.79E+2 1.03E+3 3.40E+5 4.41 E+d 1.76E+2 I-130 6.36Et3 - 1.39E+4 1.60E+6 1.53E+4 - 1.99E+3 5.57E+3 I-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 - 1.06E+3 1.96E+4 l I-132 1.69E+3 3.54E+3 1.69E+5 3.95 E+3 - 1.90E+3 1.26E+3 l I-133 1.32E+4 1.92E+4 3.56E+6 2.24E+4 - 2.16E+3 5.60E+3 I-134 9.21E+2 1.88E+3 4.45 E+4 2.09E+3 -
1.29E+3 6.65E+2 1-135 3.86E+3 7.60E+3 6.96E+5 8.47E+3 -
1.83E+3 2.77E+3 Cs-134 3.96E+5 7.03E+5 - 1.90E+5 7.97E+4 1.33E+3 7.45E+4 Cs-136 4.83E+4 1.35E+5 -
5.64E+4 - 1.18E+4 1.43E+3 5.29E+4
- Cs-137 5.49E+5 6.12E+5 - 1.72E+5 7.13E+4 1.33E+3 4.55E+4 Cs-138 5.05E+2 7.81E+2 -
4.10E+2 6.54E+1 8.76E+2 3.98E+2
~ Ba-139 1.48E+0 9.84E-4 - 5.92E-4 5.95E+3 5.10E+4 4.30E-2 Ba-140 5.60E+4 5.60ht! -
1.34E+1 1.60E+6 3.84E+4 230E+3 Ba-141 1.57E-1 1.08E-4 -
6.50E-5 2.97E+3 4.75E+3 4.97E-3 Ba-142 3.98E-2 3.30E-5 - 1.90E-5 1.55E+3 6.93E+2 1.96E-3 La-140 5.05E+2 2.00E+2 - - 1.68E+5 8.48E+4 5.15E+1 La-142 1.03E+0 3.77E-1 - 8.22E+3 5.95E+4 9.04E-2 Ce-141 2.77E+4 1.67E+4 -
5.25E+3 5.17E+5 2.16E+4 1. M +3 Cc-143- 2.93E+2 1.93 E+2 -
5.64E+1 1.16E+5 4.97E+4 2.21 E+1 Ce-144 3.19E+6 1.21 E+6 -
5.38E+5 9.84E+6 1.48E+5 1.76E+5 ;
1 Pr-143 1.40E+4 5.24E+3 -
1.97E+3 4.33 E+5 3.72E+4 6.99E+2 Pr-144 ~ 4.79E-2 1.85E-2 - 6.72E-3 1.61E+3 4.28E+3 2.41 E-3 Nd-147 7.94E+3 8.13E+3 -
3.15E+3 3.22E+5 3.12E+4 5.00E+2 ;
W-187 1.30E+ 1 9.02E+0 - -
3.96E+4 3.56E+4 3.12E+0 Np-239 3.71E+2 3.32E+1 -
6.62E+1 5.95E+4 2.49E+4 1.88E+1 DBP 6027A 71 Revision 11.0 ODCM
Table 3-8 Ri o. Grass - Cow - Milk Pathway Dose Factors - ADULT 3
(mrem /yr per pCi/m ) for H-3 and C-14 2
(m
- mrem /yr per pCi/sec) for others Nuclide Banc Liver Thyroid Kidney Lung GI-LLI T. Body H -
7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 Na-24 2.54E+6 2.54E+6 2.54E+6 2.54E4 5 2.54E+6 2.54E+6 2.54E+6 P-32 1.71E+10 1.06E+9 - - -
1.92E+9 6.60E+8 Cr-51 - - 1.71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Mn-54 - 8.40E+6 - 2.50E+6 -
2.57E+7 1.60E+6 Mn-56 - 4.23E-3 -
5.38E-3 -
1.35E-1 7.51E-4 Fe-55 2.51E+7 1.73E+7 - - 9.67E+6 9.95 E+6 4.04E+6 Fe-59 2.98E+7 7.00E+7 - -
1.95E+7 2.33E+8 2.68E+7 Co-57 - 1.28E+6 - - - 3.25E+7 2.13 E+6 Co-58 -
4.72E+6 - - - 9.57E+7 1.06E+7 Co-60 - 1.64E+7 - - - 3.08E+8 3.62E+7 Ni-63 6.73E+9 4.66T' ' - - - 9.73E+7 2.26E+8 Ni-65 3.70E-1 4.81' - - - 1.22E+0 2.19E-2 Cu-64 -
2.41 e4 - 6.08E+4 -
2.05 E+6 1.13E+4 Zn-65 1.37E+9 4.36E4 9 - 2.92E+9 -
2.75E+9 1.97E+9 Zn-69 - - - - - - -
Br-82 - - - - - 3.72E+7 3.25E+7 Br-83 - - - - - 1.49E-1 1.03E-1 Br-84 - - - - - - -
Br-85 - - - - - - -
Rb-86 -
2.59E+9 - - - 5.I 1E+8 1.21E+9 Rb-88 - - - - - - -
Rb-89 - - - - - - -
Sr-89 1.45E+9 - - - - 2.33E+8 4.16E+7 Sr-90 4.68Ed ' 0
- - - - 1.35E+9 1.15E+10 Sr-91 3.13E+4 - - - - L49E+5 1.27E+3 Sr-92 4.89E-1 - - - - 9.68E+0 2.11 E-2 Y-90 7.07E+1 - - - - 7.50E+5 1.90E+0 Y-91m - - - - - - -
Y-91 8.60E+3 - - - - 4.73 E+6 2.30E+2 Y-92 S.42E-5 - - - -
9.49E-1 1.58E-6 Y-93 2.33E-1 - - - - 7.39E+3 6.43 E-3 Zr-95 9.46E+2 3.03E+2 - 4.76E+2 - 9.62E+5 2.05E+2 Zr-97 4.26E-1 8.59E-2 -
1.30E-1 - 2.66E+4 3.93E-2 Nb-95 8.25E+4 4.59E+4 - 4.54Et4 - 2.79E+8 2.47E+4 Nb07 - - - - - 5.47E-9 -
Mo-> > - 2.52E+7 - 5.72E+7 - 5.85E+7 4.80E+5 Tc-99m 3.25E+0 9.19E+0 - 1.40F. & ? 4.50E+0 5.44E+3 1.17E+2 Tc-101 - - - - -
DBP 6027A 72 Revision i1.0 ODCM e
l Table 3-8 Ri o' Grass - Cow - Milk Pathway Dose Factors - ADULT (continued)
(mrem /yr per pCi/m') for H-3 and C-14 (m2* mrem /yr per pCi/sec) for others Nuclide Banc L1Yg Thyroid Kidney Lung GI-LLI . T. Body l
Ru '03 1.02E+3 - -
3.89E+3 - 1.19E+5 4.39E+2 Re-105 8.57E-4 - - 1.l lE-2 - 5.24E-1 3.38E-4 Ru-106 2.04E+4 - - 3.94E+4 - 1.32E+6 2.58E+3 Rh-103m ' - - - -
Rh-106 - -- - - -
Ag-110m - 5.83E+7 5.39E+7 .. 1.06E+8 - 2.20E+ 10 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 - -
2.00E+7 7.31 E+8 1.02E+7 Sb-125 2.04E+7 2.28E+5 2.08E+4 - 1.58E+7 2.25E+8 4.86E+6 Te-125m ' l.63E+7 5.90E+6 4.90E+6 6.63E+7 - 6.50E+7 2.18E+6 Te-127m 4.58E+7 ' l.64E+7 1.17E+7 1.86E+8 - 1.54E+8 5.58E+6 Te-127 6.72E+2 2.41 E+2 4.98E+2 2.74E+3 - 5.30E+4 1.45E+2 Te-129m 6.04E+7 - 2.25E+7 2.08E+7 2.52E+8 3.04E+8 9.57E+6 Te-129' - - - - - -
Te-131m 3.61E+5 1.77E+5 2.80E+5 1.79E+6 -
1.75E+7 1.47E+5 Te-131 - - - -
Te-132 2.39E+6 1.55E+6 1.71E+6 1.49E+7 -
7.32E+7 1.45E+6 I-130 4.26E+5 1.26E+6 1.07E+8 1.96E+6 - 1.08E+6 4.96E+5 I-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 - 1.12E+8 2.43E+8 I-132 1.64E-1 4.37E-1 1.53E+1 6.97E-1 -
8.22E-2 1.53E-1 1-133 3.97E+6 6.90E+6 1.01E+9 1.20E+7 - 6.20E+6 2.10E+6 I-134 -- - - - -
-I-135 1.39E+4 3.63E+4 2.40E+6 5.83E+4 - 4.10E+4 1.34E+4 Cs-134 5.65E+9 1.34E+10 - 4.35E+9 1.44E+9 2.35E+8 1.10E+10 Cs-136 2.61E+8 1.03E+9 - 5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-137 7.38E+9 1.01 E+10 - 3.43E+9 1.14E+9 1.95E+8 6.61E+9 Cs-138 - - - -
Ba-139 4.70E-8 - - - - 8.34E-8 1.38E-9 Ba-140 2.69E+7 3.38E+4 -
1.15E+4 1.93E+4 5.54E+7 1.76E+6 Ba-141 - - - - -
Ba-142 - - - - - -
La-140 4.49E+0 2.26E+0 - - - 1.66E+5 5.97E-1 La-142 - - - - - 3.03E-8 -
Ce-141 4.84E+3 3.27E+3 -
1.52E+3 -
1.25E+7 3.71 E+2 Ce-143 4.19E+1 3.09E+4 - 1.36E+1 - 1.16E+6 3.42E+0 Cc-144 3.58E+5 1.50E+5 -
8.87E+4 - 1.21E+8 1.92E+4 I
Pr-143 1.59E+2 6.37E+1 - 3.68E+1 -
6.96E+5 7.88E+0 Pr-144 - - - - -
Nd-147 9.42E+1 1.09E+2 - 6.37E+1 - 5.23E+5 6.52E+0 )
W-187 6.56E+3 5.48E+3 - - e i10E+6 1.92E +3 Np-239 3.66E+0 3.60E-1 - 1.12E+0 - 7..N F+ 4 1.98E-1 DBP 6027A 73 Revision ) 1.0 ODCM
Table 3-8 (continued)
Ri o, Grass - Cow - Milk Pathway Dose Factors - TEENAGER 3
(mrem /yr per pCi/m ) for H-3 and C-14 2
(m
- mrem /yr per pCi/sec) for others Nuchde Bone Liver Thyroid Kidney Lung GI-LLI T. Body H3 -
9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6liOE+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 -
Na-24 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 P-32 3.15E+10 1.95E+9 - - - 2.65E+9 1.22E+9 Cr-51 - -
2.78E+4 1.10E+4 7.13E+4 8.40E+6 5.00E+4 Mn-54 - 1.40E+7 - - 4.17E+6 -
2.87E+7 2.78E+6 Mn-56 -
7.51 E-3 - 9.50E-3 -
4.94E-1 1.33E-3 Fe-55 4.45E+7 3.16E+7 - - 2.00E+7 1.37E+7 7.36E+6 l Fe-59 5.20E+7 1.21E+8 - - 3.82E+7 2.87E+8 4.68E+7 l Co-57 -
2.25E+6 - - - 4.19E+7 3.76E+6 l Co-58 - 7.95E+6 - - - 1,10E+8 1.83E+7
- Co-60 - 2.78E+7 - - -
3.62E+8 6.26E+7 Ni-63 1.18E+10 8.35E+8 - - -
1.33E+8 4.01E+8 Ni-65 6.78E-1 8.66E-2 - - - 4.70E+0 3.94E-2 Cu-64 -
4.29E+4 - 1.09E+5 -
3.33E+6 2.02E+4 Zr o5 2.11E+9 7.31 E+9 - 4.68E+9 -
3.10E+9 3.41E+9 Zn - - - - - - -
Br-82 - - - - - -
5.64E+7 :
Br-83 -- - - - - - 1.91E-1 Br-84 - - - - - - -
l 1 - Br-85 - - - - - - -
- l. Rb-86 - 4.73E+9 - - -
7.00E+8 2.22E+9 :
Rb-88 - - - - - - -
l l Rb-89 - - - - - - -
l Sr-89 2.67E+9 - - - -
3.18E+8 7.66E+7 l l Sr-90 6.61E+10 - - - - 1.86E+9 1.63E+10 Sr-91 5.75E+4 - - - -
2.61 E+5 2.29E+3 Sr-92 8.95E-1 - - - - 2.28E+1 3.81E-2 Y-90 1.30E+2 - - - - 1.07E+6 3.50E+0 j Y-91m - - - - - - -
l i
I Y-91 1.58E44 - - - -
6.48E+6 '.24E+2 Y-92 1.00E+ - - - -
2.75 E+0 _ .90E-6 j Y-93 4.30E-: - - - - 1.31E+4 1.18E-2 i Zr-95 1.65E+3 5.22E+2 - 7.67E+2 -
1.20E+6 3.59E+2 ;
Zr-97 7.75E-1 1.53 E-1 - 2.32E-1 -
4.15E+4 7.06E-2 Nb-95 ; 1.41E+5 7.80E+4 - 7.57E+4 -
3.34E+8 4.30E+4 Nb-97 - - - - - 6.34E-8 -
Mo-99 - 4.56E+7 -
1.04E+8 - 8.16E+7 8.69E+6 Tc-99m 5.64E+0 1.57E+1 - 2.34E+2 8.73E+0 1.03 E+4 2.04E+2 Tc-101' - . - - - - -
DBP 6027A - 74 Revision 11.0 OI.'>CM I
r
r-q
\ q i
Table 3-8 (continued)
Rio, Grass - Cow - Milk Pathway Dose Factors - TEENAGER (continued) 3 (mrem /yr per pCi/m ) for H-3 and C-14 2
(m
- mrem /yr per pCi/sec) for others Nuclide- Bonc laygt ' Thyroid Kidney Lung GI-LLI T.Bodv Ru-103 1.81E+3 -- - 6.40E+3 - 1.52E+5 7.75E+2 Ru-105 ' l.57E-3 - - 1.97E-2 - 1.26E+0 6.08E-4 .
Ru-106' 3.75E+4 - - -
7.23E+4 - 1.80E+6 4.73E+3 Rh-103m - - - - - - -
Rh-106 - - - - - - -
Ag-110m ~ 9.'63 E+7 9.11E+7 -
1.74E+8 - 2.56E+10 5.54E+7 Sb-124 -4.59E+7 8.46E+5 1.04E+5 - 4.01 E+7 9.25E+8 1.79E+7
' Sb-125 3.65E+7 3.99E+5 3.49E+4 - 3.21E+7 2.84E+8 8.54E+6 Te-125m 3.00E+7 1.08E+7 8.39E+6 - -
8.86E+7 4.02E+6 1 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 -
2.10E+8 1.00E+7 Te-127 1.24E+3 4.41E+2 8.59E+2 5.04E+3 - 9.61E+4 2.68E+2 Te-129m 1.l lE+8 . 4.10E+7 3.57E+7 4.62E+8 - 4.15E+8 1.75E+7 Te-129 - -
1.67E-9 - 2.18E-9 -
Te-131m 6.57E+5 3.15E+5 4.74E+5 3.29E+6 - 2.53E+7 2.63E+5 Te-131 -- - - - - - -
Te-132 . 4.28E+6 2.71E+6 2.86E+6 2.60E+7 -
8.58E+7 2.55E+6 I-130 7.49E+5 2.17E+6 1.77E+8 3.34E+6 - 1.67E+6 8.66E+5 I-131 5.38E+8 7.53E+8 2.20E+11 1.30E+9 - 1.49E+8 4.04E+8 I-132 2.90E-1 7.59E-1 2.56E+1 1.20E+0 -
3.31E-1 2.72E-1 1-133. 7.24E+6 1.23E+7 1.72E+9 2.15E+7 -
9.30E+6 3.75E+6 I-134 - - - - - - -
I-135 2.47E+4 6.35E+4 4.08E+6 1.00E+5 - 7.03E+4 2.35E+4 Cs-134 9.81E+9 2.31E+10 -
7.34Er9 2.80E+9 2.87E+8 1.07E+10
- Cs-136 4.45E+8 1.75E+9 -
9.53E+8 1.50E+8 1.41E+8 1.18E+9 Cs-137 1.34E+10 1.78E+10 - 6.06E+9 2.35E+9 2.53E+8 6.20E+9 Cs-138 - - - - - - -
Ba-139 - 8.69E-8 - - - - 7.75E-7 2.53E-9 Ba-140 4.85E+7 5.95E+4 -
2.02E+4 4.00E+4 7.49E+7 3.13E+6 Ba-141 - - - - - - -
Ba-142 - - - - - - -
La-140.. 8.06E+0 3.96E+0 - - -
2.27E+5 1.05E+0 La-142 - - - - -
2.23E-7 -
Ce-141. 8.87E+3 5.92E+3 -
2.79E+3 - 1.69E+7 6.81E+2 Ce-143 7.69E+1 5.60E+4 -
2.51 E+1 -
1.68E+6 6.25E+0 Ce-144 6.58E+5 2.72E+5 -
1.63E+5 -
1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 - 6.77E+ 1 -
9.61 E+5 1.45 E+1 Pr-144 - - - - - -
Nd-147 1.81E+2 1.97E+2 - 1.16E+2 -
7.l l E+5 1.18E+ 1 W-187 1.20E+4 9.78E+3 - - - 2.65E+ 6 3.43E+3 Np-239 6.99E+0 6.59E-1 -
2.07E+0 -
1.06E+5 3.66E-1 DBP 6027A 75 Revision 11.0 ODCM
r~
Table 3-8 (continued)
Rjo, Grass - Cow - Milk Pathway Dose Factors - Cll!LD 1 (mrem /yr per pCi/m') for 11-3 and C-14 l 2
(m
- mrem /yr per pCi/sec) for others !
l Nuchde Bonc LlysI Thyroid Kidney Lung .Gl-LLI T. Body j H 3- -
1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14~ 1.65E+6 - 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 Na-24 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23 E+6 9.23E+6 9.23E+6 P-32 7.77E+10 3.64E+9 - - -
2.15E+9 3.00E+9 Cr-51 - - 5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 l Mn-54 - 2.09E+7 -
5.87E+6 - 1.76E+7 5.58E+6 Mn-56 -
1.31E-2 -
1.58E-2 -
1.90E+0 2.95E-3 Fe-55 1.12E+8 5.93E+7 - - 3.35E+7 1.10E+7 1.84E+7 Fe-59 1.20E+8 1.95E+8 - -
5.65E+7 2.03 E+8 9.71E+7 Co-57 -
3.84E+6 - - -
3.14E+7 7.77E+6 I Co-58 -
1.21E+7 - - -
7.08E+7 3.72E+7 4 i
Co-60 - 4.32E+7 - - - 2.39E+8 1.27E+8 Ni-63 2.96E+10 .1.59E+9 - - -
1.07E+8 1.01 E+9 Ni-65 1.66E+0 1.56E-1 - - -
1.91E+1 9.llE-2 Cu-64 - 7.55E+4 -
1.82E+5 -
3.54E+6 4.56E+4 Zn-65 4.13E+9 1.10E+10 - 6.94E+9 - 1.93E+9 6.85E+9 Zn-69 - - - - -
2.14E-9 -
j Br-82 - - - - - - 1.15E+8 Br-83 - - - - - - 4.69E-1 Br-84 - - - - - - -
l Br-85 - - - - - - -
l Rb-86 - 8.77E+9 - - - 5.64E+8 5.39E+9 l Rb-88 - - - - - - -
Rb-89 - - - - - - -
Sr-89 6.62E+9 ' - - - -
2.56E+8 1.89E+8 1 I Sr-90 1.12E+11 - - - - 1.51E+9 2.83E+10 Sr-91 1.41E+5 - - - -
3.12E+5 5.33E+3 i 4.14E+1 8.76E-2 Sr-92 2.19E+0 - - - -
l Y-90 3.22E+2 - - - - 9.15E+5 8.61E+0 t Y-91m - - - - - - -
i Y-91 3.91E+4 - -- - -
5.21E+6 1.04E+3 !
Y-92 2.46E-4 - - - -
7.10E+0 7.03E-6 Y-93 1.06E+0 - - - - 1.57E+4 2.90E-2
- Zr 3.84E+3 8.45E+2 - 1.21E+3 - 89'E+5 7.52E+2 Zr-97 1.89E+0 2.72E-1 -
3.91E-1 -
4.Dd+4 1.61 E-1 Nb-95 3.18E+5 1.24E+5 - 1.16E+5 - 2.29E+8 8.84E+4 1.45 E-6 Nb-97 - . - - - -
Mo-99 -
8.29E+7 - 1.77E+8 - 6.86E+7 2.05E+7 Tc-99m 1.29E+1 2.54E+1 - 3.68E+2 1.29E+ 1 1.44E+4 4.20E+2 l Tc-101 - - - - - - -
DSP 6027A 76 ' Revision 11.0 ODCM
Table 3 8 (continued) f Rjo, Grass - Cow - Milk Pathway Dose Factors - CHILD (continued) 3
)
(mrem /yr per pCi/m ) for H-3 and C-14 2
(m
- mrem /yr per pCi/sec) for others i Nuclide Thyroid Kidacy Lung- GI LLI T. Body Bonc L1Yet Ru-103 - 4.29E+3 - -
1.08E+4 - 1.11E+5 1.65E+3 Ru-105 3.82E-3 - -
3.36E-2 - 2.49E+0 1.39E-3 Ru-106 9.24E+4 - - 1.25E+5 - 1.44E+6 1.15E+4 Rh-103m - - - - - - -
Rh-106 '- -- - - - - -
Ag-110m 2.09E+8 1.41E+8 - 2.63E+8 - 1.68E+10 1.13E+8 Sb-124 1.09E+8 1.41E+8 2.40E+5 - 6.03E+7 6.79E+8 3.81E+7 Sb-125 8.70E+7 1.41E+6 8.06E+4 - 4.85E+7 2.08E+8 1.82E+7 Te-125m 7.38E+7 2.00E+7 2.07E+7 - - 7.12E+7 9.84E+6 Te-127m - 2.08E+8 5.60E+7 4.97E+7 5.93E+8 -
1.68E+8 2.47E+7 Te-127 3.06E+3 - 8.25E+2 2.12R+3 8.71E+3 - 1.20E+5 6.56E+2 i Te-129m 2.72E+8 7.61E+7 8.7sE+7 8.00E+8 - 3.32E+8 4.23E+7 Te-129 - - - 2.87E-9 - 6.12E-8 --
Te-131m 1.60E+6 5.53E+5 1.14E+6 5.35E+6 - 2.24E+7 5.89E+5 Te-131 - - - - -
Te-132 1.02E+7 4.52E+6 6.58E+6 4.20E+7 - 4.55E+7 5.46E+6 I 130 1.75E+6 3.54E+6 3.90E+8 5.29E+6 -
1.66E+6 1.82E+6 I-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 - 1.17E+8 7.46E+8 1132 6.86E-1 1.26E+0 5.85E+1 1.93E+0 - 1.48E+0 5.80E-1
'I-133 1.76E+7 2.18E+7 4.04E+9 3.63 E+7 - 8.77E+6 8.23 E+6 I-134 - - - - - -
I-135 5.84E+4 1.05 E+5 9.30E+6 1.61E+5 - 8.00E+4 4.97E+4 Cs-134 - 2.26E+10 3.71E+10 - 1.15E+10 4.13E+9 2.00E+8 7.83E+9 Cs-136 1.00E+9 2.76E+9 - 1.47E+9 2.19E+8 9.70E+7 1.79E+9 i Cs-137 3.22E+10 3.09E+10 - 1.01E+10 3.62E+9 1.93E+8 4.55E+9 Cs-138 - - - - - -
Ba-139 2.14E-7 - - - -
1.23E-5 6.19E-9 Ba-140 1.17E+8 1.03E+5 - 3.34E+4 6.12E+4 5.94E+7 6.84E+6 Ba-141 - - - - - -
Ba-142 - - - - - -
La-140 1.93E+1 6.74E+0 - - - 1.88E+5 2.27E+0 La-142 - - - - - 2.51 E-6 -
Ce-141 2.19E+4 1.09E+4 - 4.78E+3 -
1.36E+7 1.62E+3 Ce-143 1.89E+2 1.02E+5 -
4.29E+1 - 1.50E+6 1.48E+1 a Ce-144 1.62E+6 . 5.09E+5 - 2.82E+5 - 1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 - 1.17E+2 - 7.80E+5 3.59E+1 Pr'144 Nd-147 4.45E+2 3.60E+2 - 1.98E+2 -
5.71 E+5 2.79E+1 W-187 2.91 E+4 1.72E+4 - - - 2,42E+6 7.73 E+3 Np-239 1.72E+1 1.23E+0 -
3.57E+0 - 9.14E+4 8.68E-1 DBP 6027A : 77 Revision 11.0 ODCM
b Table 3 8 (continued) q Rio, Grass - Cow - Milk Pathway Dose Factors - INFANT 3
(mrem /yr per pCi/m ) for 11-3 and C-14 2
(m
- mrem /yr per pCi/sec) for others Huchde Bont Llyn Thyroid Kidney Lung GI-LIJ T. Body H-3 -
2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3
'C-14 3.23 E+6 - 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E i-5 6.89E+5 Na-24 1.61E+7 1.61E+7 'l.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7
- P 32 1.60E+11 9.42E+9 - - - -
2.17E+9 6.21 E+9 Cr-51 - - 1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 Mn-54 -
3.89E+7 -
8.63E+6 - 1.43E+7 8.83E+6 Mn-56 ' -
3.21E-2 -
2.76E-2 -
2.91E+0 5.53E-3 Fe-55 1.35E+8 8.72E+7- - -
4.27E+7 1.llE+7 2.33 E+7 Fe 2.25E+8 3.93E+8 - - 1.16E+8 1.88E+8 1.55E+8 Co-57 ^ -
8.95E+6 - - - 3.05E+7 1.46E+7 Co-58 -
2.43E+7 - - -- 6.05E+7 6.06E+7 Co-60 - 8.81E+7 - - - 2.10E+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 - - - 1.07E+8 1.21E+9 Ni-65 3.51E+0 3.97E-1 - - -
3.02E+1 1.81 E-1 Cu-64 -
1.88E+5 -
3.17E+5 -
3.85E+6 8.69E+4 l Zn 65 5.55E+9 1.90E+10 -
9.23E+9 - 1.61E+10 8.78E+9 Zn-69 - - - - - 7.36E-9 -
Br-82 - - - - - - 1.94E+8 Br-83 - - - - - - 9.95E-1 Br-84 - - - - - - -
! Br-85 - - - - - - -
L Rb-86 - 2.22E+10 - - - 5.69E+3 1.10E+10 l- Rb-88 - - - - - - -
l Rb-89 - -- - - - - -
Sr-89 1.26E+10 - - - - 2.59E+8 3.61E+8 Sr-90 1.22E+11 - - - - 1.52E+9 3.10E+10 Sr-91. - 2.94E+5 - -- - - 3.48E+5 1.06E+4 Sr-92 4.65E+0 . - - - - 5.01E+1 1.73E-1 Y-90 6.80E+2 - - - - 9.39E+5 1.82F+1 Y-91m ' - -- - - - - -
Y-91 7.33E+4 - - - - -
5.26E+6 1.95E+3 Y-92 5.22E-4 - - - - 9.97E+0 1.47E-5 Y 2.25E+0 - - - -
1.78E+4 6.13 E Zr-95 6.83E+3 1.66E+3 -- 1.79E+3 - 8.28E+5 1.18E+3
' Zr-97 3.99E+0 6.85E-1 - 6.91E-1 -
4.37E+4 3.13E-1 Nb-95 ~ 5.93E+5 2.44E+5 - 1.75E+5 -
2.06E+8 1.41E+5 Nb-97 -- -- - - - 3.70E-6 -
Mo-99 - 2.12E+8 - 3.17E+ 8 - 6.98E+7 4.13E+7 Tc-99m 2.69E+1 5.55E+1 -
5.97E+2 2.90E+1 1.61 E+4 7.15 E+2 Tc-101 - - - - - .-
DBP 6027A 78 Revision 11.0 OIX'M
=_
Table 3 8 (continued)
Ri o, Grass - Cow - Milk Pathway Dose Factors - INFANT (continued)
(mrem /yr per pCi/m') for H-3 and C-14 (m2* mrem /yr per Ci/sec) for others Nuclide Bonc layn Thyroid Kidney Lung GI-LLI T. Body Ru 103 - 8.69E+3 - - 1.81E+4 - -
1.06E+5 2.91 E+3 Ru-105 8.06E-3 - - 5.92E-2 -
3.21E+0 2.71 E-3 Ru-106 1.90E+5 - - 2.25 E+5 -
1.44E+6 2.38E+4 Rh-103m - - - - - - -
Rh-106 - - - - - - -
Ag-110m 3.86E+8 2.82E+8 -
4.03E+8 - 1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 - 1.31E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 - 9.38E+7 1.99E+8 3.07E+7 Te-125m 1.51E+8 5.04E+7 5.07E+7 - -
7.18E+7 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 -
1.70E+8 5.10E+7 Te-127 6.50E+3 .- 2.18E+3 5.29E+3 1.59E+4 -
1.36E+5 1.40E+3 Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 -
3.34E48 8.62E+7 Te-129 2.08E-9 - 1.75E-9 5.18E-9 - 1.66E-7 -
Te-131m 3.38E+6 1.36E+6 2.76E+6 9.35E+6 - 2.29E+7 1.12E+6 Te-131 - - - - - -
Te-132 2.10E+7 1.04E+7 1.54E+7 6.51E+7 -
3.85E+7 9.72E+6 I-130 3.60E+6 7.92E+6 8.88E+8 8.70E+6 -
1.70E+6 3.18E+6 I-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 - 1.15E+8 1.41E+9 I-132 1.42E+0 2.89E+0 1.35E+2 3.22E+0 -
2.34E+0 1.03 E+0 I-133 3.72E+7 5.41E+7 9.84E+9 6.36E+7 -
9.16E+6 1.58E+7 I-134 - - 1.01E-9 - - - -
I-135 1.21E+5 2.41E+5 2.16E+7 2.69E+5 - 8.74E+4 8.80E+4 Cs-134 3.65E+10 6.80E+10 -
1.75 E+10 7.18E+9 1.85E+8 6.87E+9 Cs-136 1.96E+9 5.77E+9 - 2.30E+9 4.70E+8 8.76E+7 2.15E+9 Cs-137 5.15E+10 6.02E+10 - 1.62E+10 6.55E+9 1.88E+8 4.27E+9 Cs-138 - - - - - -
Ba-139 4.55E-7 - - - - 2.88E-5 1.32E-8 .
Ba-140 2.41E+8 2.41E+5 -
5.73E+4 1.48E+5 5.92E+7 1.24E+7 I
. Ba-141 - - - - - -
Ba-142 - - - - - -
La-140 4.03E+1 1.59E+1 - - -
1.87E+5 4.09E+0 l La-142 - - - - -
5.21E-6 -
I Ce-141 4.33E+4 2.64E+4 -
8.15 E+3 -
1.37E+7 3.11 E+3 i Ce 143 4.00E+2 2.65E+5 -
7.72E+1 -
1.55 E+6 3.02E+1 Cc-144 2.33 E+6 9.52E+5 -
3.85E+5 - 1.33E+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 - 2.08E+2 - 7.89E+5 7.41 E+1 l Pr-144 - - -
Nd-147 8.82E+2 9.06E+2 -
3.49E+2 - 5.74E+5 5.55 E+1 W-187 6.12E+4 4.26E+4 - - - 2.50E+6 1.47E+4 Np-239 3.64E+1 3.25E+0 - 6.49E+ 0 - 9.40E+4 1.84E+0 DBP 6027A 79 Revision 11.0 i ODCM
n 1
i f- Table 3-9
, Rjoi Grass - Goat - Milk Pathway Dose Factors - ADULT 3
I (mrem /yr per pCi/m ) for H-3 and C-14 2
l (m
- mrem /yr per pCi/sec) for others Nuclide Bang Liver Thyroid Kidney Lung GI-LLI T. Body f
! J l - H-3 -
1.56E+3 1.56E+3 1.56E+3 1.56E+3 1.56E+3 1.56E+3 C-14 3.63 E+5 7.26E+4 7.26E44 7.26E+4 7.26E+4 7.26E+4 7.26E+4 Na-24 3.05E+5 ' 3.05E+5 3.05 E+5 3.05E+5 3.05E+5 3.05E+5 3.05E+5 P-32 2.05E+10 1.27E+9 - - - 2.30E+9 7.92E+8
! Cr-51 - - 2.05 E+3 7.56E+2 4.56E+3 8.64E+5 3.43E+3 l-Mn-54 - 1.01E+6 -
3.00E+5 -
3.08E+6 1.92E+5 l Mn-56 - 5.08E-4 - 6.46E-4 - 1.65E-2 9.01 E-5 i Fe-55 3.31 E+5 2.28E+5 - - 1.28E+5 1.31E+5 5.33E+4 l Fe-59 3.93 E+5 9.24E+5 - -
2.57E+5 3.08E+6 3.54E+5 Co-57 -
1.54E+5 - - - 3.90E+6 2.56E+5 Co-58 - 5.66E+5 - - - 1.15E+7 1.27E+6 Co-60 - 1.97E+6 - - -
3.70E+7 3.34E+6 Ni-63 8.08E+8 5.59E+7 - - - 1.17E+7 2.71 E+7 Ni-65 4.44E-2 5.77E-3 - - -
1.46E-1 2.63 E-3 l Cu-64 -
2.69E+3 -
6.79E+3 - 2.79E+5 1.26E+3 Zn-65 1.64E+8 5.23E+8 - 3.50E+8 - 3.30E+8 2.36E+8 l Zn-69 - - - - - - -
Br-82 - - - - - 4.46E+6 3.90E+6 l
l Br-83 - - - - -
1.79E-2 1.24E-2 Br-84 - - - - - - -
Br-85 - - - - - -
Rb 86 - 3.l lE+8 - - - 6.13E+7 1.45E+8 Rb 88 - - - - - - -
Rb-89 - - - - - - -
Sr-89 3.04E+9 - - - -
4.89E+8 8.74E+7 Sr-90 9.83E+10 - - - - 2.84E+9 2.42E+10 Sr 91 6.57E+4 - - - - 3.13E+5 2.67E+3 l Sr-92 1.03E+0 - - - -
2.03E+1 4.43E-2 Y-90 8.48E+0 - - - - 9.00E+4 2.28E-1 Y-91m - - - - - - -
Y-91 1.03E+3 - - - -
5.71E+5 2.76E+1
~Y-92 6.50E-6 - - - - 1.14E-1 1.90E-7 Y-93 2.80E-2 - - - - 8.87E+2 7.72E-4 Zr-95 1.15 E+2 3.64E+1 -
5.71E+1 -
1.15E+5 2.46E+1 Zr-97 5.11 E-2 1.03E-2 - 1.56E-2 - 3.19E+3 4.72E-3 Nb-95 9.90E+3 5.51E+3 - 5.34E+3 -
3.35E+7 2.96E+3 Nb-97 - - - - - 6.56E-10 -
Mo-99 - 3.02E+6 - 6.96E+6 - 7.02E+6 5.76E+5 Tc-99m 3.90-1 1.10E+0 - 1.68E+1 5.40E-1 6.53 E+2 1.40E+1 Tc-101 - - - - - -
DBP 6027A 80 Revision i1.0 l
0 ODCM L
r Table 3 9 Ri o Grass - Goat - Milk Pathway Dose Factors - ADULT (continued) 3
' (mrem /yr per pCi/m ) for 113 and C-14 (m*
- mrem /yr per pCi/sec) for others Nuchde Hont L1Yet Thyroid Kidney Lung GI-LLI T. Body l
)
Ru-103 1.22E+2 - - 4.67E+2 - 1.43E+4 5.27E+1 Ru-105 1.03E-4 - - 1.33E-3 - 6.29E-2 4.06E 5 )
l Ru-106 2.45E+3 - -
4.73E+3 - 1.58E+5 3.10E +2 Rh-103m - - -
Rh-106 - - - -
Ag-110m 6.70E+6 6.47E+6 - 1.27E+7 - 2.64E+9 3.84E+6 Sb-124 3.08E+6 5.83E+4 7.49E+3 - 2.40E+6 8.77E+7 1.22E+6 Sb 125 2.45E+6 2.74E+4 2.50E+3 - 1.90E+6 2.70E+7 5.83E+5 Te-125m 1.96E+6 7.08E+5 5.88E+5 7.96E+6 - 7.80E+6 2.62E+5 -
Te-127m 5.50E+6 1.97E+6 1.40E+6 2.23E+7 -
1.85E+7 6.70E+5 Te-127 8.06E+1 2.89E+1 5.80E+1 3.29E+2 -
6.36E+3 1.74E+1 l l Te-129m 7.25E+6 2.70E+6 2.50E+6 3.02E+7 - 3.65E+7 1.15E+6 l Te-129 - - -
Te-131m 4.33E+4 2.12E+4 3.36E+4 2.15E+5 - 2.10E+6 1.76E+4 Te-131 - - -
Te-132 2.87E+5 1.96E+5 2.05E+5 1.79E+6 - 8.78E+6 1.74E+5 I-130 5.l lE+5 1.51E+6 1.28E+8 2.35E+6 -
1.30E+6 5.95E+5 I-131 3.55E+8 5.01E+8 1.67E+11 8.72E+8 - 1.34E+8 2.92E+8 I-132 1.97E-1 5.24E-1 1.84E+1 8.36E-1 - 9.86E-2 1.84E-1 I-133 4.76E+6 8.28E+6 1.21E+9 1.44E+7 - 7.44E+6 2.52E+6 I-134 - - - -
I-135 1.67E+4 4.36E+4 2.88E+6 6.70E+4 - 4.92E+4 1.61E+4 Cs-134 1.70E+10 4.02E+10 -
1.31E+10 4.32E+9 7.05E+8 3.30E+10 Cs-136 7.83E+8 3.09E+9 -
1.72E+9 2.36E+8 3.31E+8 2.23E+9 Cs-137 2.21E+10 3.03E+10 - 1.03E+10 3.42E+9 5.85E+8 1.98E+10 Cs-138 - - -
Ba-139 5.64E-9 - - - - 1.00E-8 1.66E-10 Ba-140 3.23E+6 4.06E+3 - 1.38E+3 2.32E+3 6.65E+6 2.11E+5 Ba-141 - - -
Ba-142 - - - -
La-140 5.39E-1 2.71E-1 - - - 1.99E+4 7.16E-2 La-142 - - - - - 3.64E-9 -
Ce-141 5.81 E+2 3.92E+2 - 1.82E+2 -
1.50E+6 4.45E+1 Ce-143 5.03E+0 3.71 E+3 - 1.62E+0 -
1.39E+5 4.10E-1 Cc-144 4.30E+4 1.80E+4 - 1.06E+4 - 1.45E+7 2.30E+3 Pr-143 - 1.91E+1 7.64E+0 - 4.42E+0 - 8.35 E+4 9.46E-1 Pr-144 - - -
Nd-147 1.13E+1 1.31E+1 - 7.64E+0 - 6.28E+4 6.74E 1 W-187 7.87E+2 6.58E+2 - - - 2.16E+5 2.30E+2 Np-239 4.39E-l 4.32E-2 - 1.34E-1 - 8.87E+3 2.38 E-2 DBP 6027A 81 Revision i1.0 ODCM
Table 3-9 (continued)
Ri o, Grass - Goat - Milk Pathway Dose Factors - TEENAGER (mrem /yr per pCi/m') for II-3 and C-14 2
(m
- mtem/yr per pCi/sec) for others Nuclids Bonc LLEcr Thyroid Kidney Lung GI-LLI T. Body H3 - 2.03E+3 2.03E+3 2.03 E+3 2.03E+3 2.03E+3 2.03E+3 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 Na-24 5.33E+5 5.33E+5 5.33E+5 5.33E+5 5.33E+5 5.33E+5 5.33F+5 P-32 3.78E+10 2.34E+9 - - - 3.18E+9 1.46E+9 Cr-51 - - 3.34E+3 1.32E+3 8.56E+3 1.01E+6 6.00E+3 Mn-54 -
1.68E+6 -
5.00E+5 -
3.44E+6 3.34E+5 Mn-56 - 9.01E-4 - 1.14E-3 -
5.93E-2 1.60E-4 Fe-55 5.79E+5 4.11 E+5 - - 2.60E+5 1.78E+5 9.57E+4 Fe-59 6.76E+5 1.57E+6 - -
4.97E+5 3.73 E+6 6.08E+5 Co-57 -
2.70E+5 - - -
5.03E+6 4.51 E+5 Co-58 - 9.54E+5 - - -
1.32E+7 2.20E+6 Co-60 -
3.34E+6 - - -
4.34E+7 7.51 E+6 Ni-63 1.42E+9 1.00E+8 - - -
1.60E+7 4.81E+7 Ni-65 8.14E-2 1.04E-2 - - - 5.64E-1 4.73E-3 Cu-64 -
4.78E+3 -
1.21E+4 - 3.71E+5 2.25E+3 Zn-65 2.53E+8 8.77E+8 -
5.62E+8 - 3.72E+8 4.09E+8 Zn-69 - - - - - - -
Br-82 - - - - - -
6.77E+6 Br-83 - - - - - - 2.29E-2 Br-84 - - - - - - -
Br-85 - - - - - - -
Rb-86 - 5.68E+8 - - - 8.40E+7 2.66E+8 Rb-88 ~ - - - - - - -
Rb-89 - - - - - - -
Sr-89 5.61 E+9 - - - -
6.68E+8 1.61E+8 Sr-90 1.39E+11 - - - -
3.91 E+9 3.42E+10 Sr 1.20E+5 - - - -
5.48E+5 4.81 E+3 Sr-92 1.88E+0 - - - -
4.79E+1 8.00E-2 Y-90 1.56E+1 - - - -
1.28E+5 4.20E-1 Y-91m - - - - - - -
! Y-91 1.90E+3 - - - - 7.78E+5 5.09E+1 l Y-92 1.20E-5 - - - -
3.30E-l 3.48E-7 l Y-93 5.16E-2 - - - -
1.57E+3 1.42E-3 Zr-95 1.98E+2 6.26E+1 -
9.20E+1 -
1.44E+5 4.31 E+1 Zr-97 9.30E-2 1.84E-2 -
2.78E-2 -
4.98E+3 8.47E-3 Nb-95 1.69E+4 936E+3 -
9.08E+3 -
4.01 E+7 5.16E+3 Nb-97 - - - - -
7.61 E-9 -
Mo-99 - 5.47E+6 -
1.25E+7 -
9.79E+6 1.04E+6 Tc-99m 6.77E-1 1.88E+0 -
2.81 E+1 1.05 E+0 1.24E+3 2.45E+ 1 Tc-101 - - - - - - -
DBP 6027A 82 Revision 11.0 ODCM
1 Table 3-9 (continued)
Ri o, Grass - Goat - Milk Pathway Dose Factors - TEENAGER (continued)
(mrem /yr per pCi/m') for H-3 and C-14 (m** mrem /yr per pCi/sec) for others Nuchde LlysI Thyroid Kidney Lung GI-LLI T. Body Bsan Ru-103 - 2.17E+2 - -- 7.68E+2. -
1.82E+4 9.30E+1 Ru-105 : 1.88E-4 - - 2.36E-3 -
1.51 E-1 7.30E 5 Ru-106 4.50E+3 .- - 8.68E+3 - 2.16+E5 5.68E+2 Rh-103m - - - - -
Rh 106 - - - - - - -
Ag-110m 1.16E+7. 1.09E+7 - 2.09E+7 - 3.07E+9 6.65E+6 l Sb-124 5.51E+6 1.02E+5 1.25E+4 - 4.81E+6 1.l lE+8 2.15E+6 Sb-125 : 4.38E+6 4.79E+4 4.19E+3 - 3.85E+6 3.41E+7 1.02E+6 '
Te-125m . 3.60E+6 1.30E+6 1.01E+6 - - 1.06E+7 4.82E+5 Te-127m 1.01E+7 3.59E&6 2.41E+6 4.10E+7 - 2.52E+7 1.20E+6 Te-127 - 1.49E+2 5.29E+1 1.03E+2 6.05E+2 - 1.15E+4 3.22E+1 Te-129m 1.33E+7 4.92E+6 4.28E+6 5.54E+7 - 4.98E+7 2.10E+6 Te-129 - - -- 2.00E-10 - 2.62E -
- Tc-131m 7.88E+4 3.78E+4 5.69E+4 3.95E+5 - 3.04E+6 3.16E+4 l Te-131 - - - - -. -
Te-132 5.14E+5 3.25E+5 3.43E+5 3.12E+6 -
1.03E+7 3.06E+5 l I-130 - 8.99E+5 2.60E+6 2.12E+8 4.01E+6 -
2.00E+6 1.04E+6 I-131 6.46E+8 9.04E+8 2.64E+11 1.56E+9 -
1.79E+8 4.85E+8 I-132 3.48E-1 9.11E-1 3.07E+1 1.44E+0 - 3.97E-1 3.26E-1 1-133 8.69E+6 1.48E+7 2.06E+9 2.58E+7 . 1.12E+7 4.50E+6 1
I-134 - - - - - - -
I-135 . 2.96E+4 7.62E+4 4.90E+6 1.20E+5 - 8.44E+4 2.82E+4 ;
Cs-134 2.94E+10 6.93E+10 - ? '^D ' O 8.40E+9 8.61E+8 3.21 E+10 Cs-136 1.34E+9 5.25E+9 - 2.86E+9 4.50E+8 4.23 E+8 3.54E+9 >
Cs-137 4.02E+10 - 5.34E+10 - 1.82E+1) 7.05 E+9 7.59E+8 1.86E+10 Cs-138 - - - - - - -
Ba-139 1.04E-8 - - - -
9.30E-8 3.04E-10 Ba-140 5.82E+6 7.14E+3 - 2 42E+3 4.80E+3 6.99E+6 3.76E+5 j Ba-141 - - - - - - -
l Ba-142 - - - - - - - -
La-140 9.67E-1 4.75E-1 - - -
2.72E+4 1.26E-1 La-142 - - - - - 2.68E-8 -
Cc-141 1.06E+3 7.10E+2 . -
3.35E+2 -
2.03 E+6 8.17E+1 Ce-143 9.23E+0 6.72E+3 - 3.01 E+0 -
2.02E+5 7.50E-1 Ce-144 7.90E+4 3.26E+4 - -
1.96E+4 - 1.99E+', 4.25E+3 Pr-143 3.50E41 1.40E+1 - 8.12E+0 -
1.15E+5 1.74E+0 Pr 144 - - - - . - -
Nd-147 2.17E+1 2.36E+1 -
1.39E+1 -
8.53E+4 1.42E+0 W-187 1.44E+3 1.17E+3 - - - 3.18E+5 4.12E+2 Np-239 8.39E-1 7.91 E-2 -
2.48E-1 - 1.27E+4 4.39E-2 I I
DBP 6027A' 83 Revision 11.0 ODCM i c
r k.
Table 3-9 (continued)
Rio, Grass - Goat - Milk Pathway Dose Factors - CHILD 3
! (mrem /yr per pCi/m ) for H-3 and C-14 (m'
- mrem /yr per pCi/sec) for others Nuclide HQDC LLYtr Thyroid Kidney Lung GI-LLI T. Body H-3 ' - 3.20E+3 3.20E+3 3.20E+3 3.20E+3 3.20E+3 3.20E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 '
Na-24 1.11E+6 1.11E+6 1.11E+6 1.I1E+6 1.11E+6 1.11 E+6 1.11E+6 P-32 9.32E+10 4.37E+9 - - -
2.58E+9 3.60E+9 Cr-51 - - 6,79E+3 1.86E+3 1.24E+4 6.49E+5 1.22E+4 Mn-54 -
2.51E+6 - 7.04E+5 -
2.11 E+6 6.70E+5 Mn-56 -
1.57E-3 -
1.90E-3 -
2.28E-1 3.54E-4 Fe-55 1.46E+6 - 7.71E+5 - -
4.36E+5 1.43E+5 2.39E+5 Fe 1.56E+6 2.54E+6 - -
7.34E+5 2.64E+6 1.26E+6 Co-57 -
4.61E+5 - - - 3.77E+6 9.32E+5 Co-58 - 1.45E+6 - - -
8.50E+6 4.46E+6 Co-60 - 5.18E+6 - - - 2.87E+7 1.52E+7 Ni-63 3.55E+9 1.91E+8 - - -
1.28E+7 1.21E+8 Ni-65 1.99E-1 1.82E-2 - - -
2.29E+0 1.09E-2 Cu-64 - 8.41 E+3 -
2.03E+4 -
3.94E+5 5.08E+3 Zn-65 4.96E+8 1.32E+9 - 8.33E+8 -
2.32E+8 8.22E+8 Zn - - - - -
2.57E-10 -
Br-82 - - - - - -
1.38E+7 Br-83 - - - - - -
5.63E-2 Br-84 - - - - - -
Br-85 - - - - - - -
Rb-86 - 1.05E+9 - - - 6.77E+7 6.47E+8 Rb-88 - - - - - - -
Rb-89 - - - - - - -
Sr-89 1.39E+10 - - - -
5.38E+8 3.97E+8 !
~
Sr-90 ' 2.35E+11 - - - - 3.17E+9 5.94E+10 l Sr-91 2.96E+5 - - - - 6 5 C+5 1.12E+4 l l
Sr-92 4.60E+0 - - - -
8.69E+1 1.84E-1 Y-90 3.86E+1 - - - -
1.10E+5 1.03E+0 Y-91m - - - - - - -
l Y-91 4.69E+3 - - - - 6.25E+5 1.25E+2 Y-92 2.95E-5 - . - - -
8.52E-1 8.44E 7 Y-93 1.27E-1 - - - - 1.88E+3 3.48E-3 ;
Zr-95 ' 4.61E+2 - 1.01E+2 -
1.45E+2 -
1.06E+5 9.02E+1 1 i
Zr-97 ' 2.27E-1 3.26E-2 -
4.69E-2 - 4.96E+3 1.93E-2 Nb-95 3.82E+4 1.49E+4 -
1.39E+4 - 2.75E+7 1.06E+4 Nb-97 - - - - - 1.74E-7 -
)
Mo-99 - 9.95E+6 - 2.12E+7 -
8.23 E+6 2.46E+6 !
Tc-99m 1.55E+0 3.05E+0 - 4.42E+1 1.55E+0 1.73 E+3 5.04E+1 1 Tc-101 - - - -- - - -
DBP 6027A 84 Revision 11.0 ;
ODCM I i
l' l
Table 3 9 (continued)
Ri o, Grass - Goat - Milk Pathway Dose Factors - CIIILD (continued)
(mrem /yr per pCi/m') for 11-3 and C-14 2
(m
- mrem /yr per pCi/sec) for others Thyroid Kidney Lung GI-LLI T. Body Nuchde Ilo.nc L1YCI Ru-103 5.15E+2 - - 1.30E+3 -
1.33E+4 1.98E+2 Ru-105 4.58E-4 - - 4.03E-3 - 2.99E-1 1.67E-4 Ru-106 - 1.11E+4 - - 1.50E+4 - 1.73E+5 1.38E+3 Rh-103m - - -
Rh 106 - - -
2.51E+7 1.69E+7 2.76E+7 - 2.02E+9 1.36E+7 Ag-110m -
1.31E+7 : 1.69E+7 2.88E+4 - 7.24E+6 8.15 E+7 4.57E+6 Sb-124 1.04E+7 1.69E+5 9.67E+3 - 5.82E+6 2.50E+7 2.18E+6 Sb-125 8.86E+6 2.40E+6 2.49E+6 - - 8.54E+6 1.18E+6 Te-125m 2.50E+7 6.72E+6 5.96E+6 7.12E+7 - 2.02E+7 2.96E+6 Te-127m 9.90E+1 2.54E+2 1.04E+3 - 1.44E+4 7.87E+1 Te-127 3.67E+2 S.13E+6 1.05E+7 9.60E+7 - 3.98E+7 5.08E+6 Te-129m 3.26E+7
- 3.44E-10 - 7.34E-9 -
Te-129 - -
6.64E+4 1.37E+5 6.42E+5 - 2.69E+6 7.07E+4 Te-131m 1.92E+5 Te-131 - -
7.90E+5 5.04E+6 - 5.46E+6 6.55E+5 Te-132 1.22E+6 5.42E+5 4.68E+8 6.35E+6 - 1.99E+6 2.18E+6 I-130 2.llE+6 4.25E+6 5.21E+11 2.58E+9 - 1.40E+8 8.95E+8 I-131 1.56E+9 1.57E+9 7.02E+1 2.32E+0 - 1.78E+0 6.96E-1 I-132 8.23E-1 1.51E+0 4.85E+9 4.36E+7 - 1.05E+7 9.88E+6 I-133 2.11E+7 2.62E+7 I-134 - -
1.26E+5 1.12E+7 1.93E+5 - 9.60E+4 5.96E+4 I-135 7.01 E+4 3.45E+10 1.24E+10 6.00E+8 2.35E+10 Cs-134 6.78E+10 1.13E+11 -
4.41E+9 6.57E+8 2.91E+8 5.37E+9 Cs-136 3.00E+9 8.28E+9 -
3.03E+10 1.09E+10 5.79E+8 1.36E+10 Cs-137 9.66E+10 9.27E+10 -
Cs-138 - -
- - 1.48E-6 7.45E-10 Ba 139 2.57E-8 - -
4.01E+3 7.34E+3 7.13 E+6 8.21E+5 Ba-140 1.40E F7 1.24E+4 -
- Ba-141 -
Ba-142 - -
- - 2.26E+4 2.72E-1 La-140 2.32E+0 8.09E-1 -
- - - 3.01E-7 -
La-142 - -
5.74E+2 - 1.63E+6 1.84E+2 Ce-141 2.63E+3 1.31E+3 -
5.1SE+0 - 1.80E+5 1.78E+0 Cc-143 2.27E+1 1.22E+4 - -
- 6. l l E+4 - 3.38E+4 -- 1.60E+7 1.04E+4 Col 44 1.94E+5 -
1.40E+1 - 9.36E+4 4.31 E+0 Pr-143 ' 8.68E+1 2.60E+1 -
Pr 144 - -
4.32E+1 - 2.38E+1 - 6.83E+4 3.35E+0 Nd-147 5.34E+1 2.06E+3 - - - 2.96E+5 9.28E+2 :
W-187 3.49E+3 1.10E+4 1.04E-1 I Np-239 2.06E+0 1.48E-1 - 4.28E-1 -
i 85 Revision i1.0 DBP 6027A ODCM f
Table 3-9 (continued)
Ri o, Grass - Goat - Milk Pathway Dose Factors - INFANT 3
(mrem /yr per pCi/m ) for H-3 and C-14 2
(m
- mrem /yr per Ci/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body 113 - 4.86E+3 4.86E+3 4.86E+3 4.86E+3 4.86E+3 4.86E+3 C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 Na-24 1.93E+6 1.93E+6- 1.93E+6 1.93E+6 1.93E+6 1.93E+6 1.93E+6 P 32 1.92E+11 1.13E+10 - - - 2.60E+9 7.45 E+9 Cr-51 - -
1.26E+4 2.76E+3 2.46E+4 5.65E+5 1.93E+4 Mn-54 -
4.67E+6 - 1.04E+6 -
1.72E+6 1.06E+6 Mn-56 6.64E-4 3.85E-3 -
3.31E-3 -
3.49E-1 Fe-55 1.76E+6 1.13E+6 - -
5.55E+5 1.44E+5 3.03E+5 Fe-59 2.93E+6 - 5.11E+6 - -. 1.51E+6 2.44E+6 2.02E+6 Co-57 - 1.07E+6 - - - 3.66E+6 1.75E+6 .
1 Co-58 -
2.92E+6 - - - 7.26E+6 7.27E+6 Co-60 - 1.06E+7 - - -
2.52E+7 2.50E+7 Ni-63 4.19E+9 2.59E+8 - - -
1.28E+7 1.45E+8 Ni-65 4.21E-1 4.76E-2 - - -
3.62E+0 2.17E-2 ;
Cu-64 -
2.09E+4 -
3.53E+4 -
4.29E+5 9.68E+3 l l
Zn-65 6.66E+8 2.28E+9 - 1.I 1 E+9 -
1.93E+9 1.05E+9 i 7.n-69 - - - - -
8.83E-10 -
)
Br-82 - - - - - -
2.33E+7 i Br-83 - - - - - -
1.19E-1 Br-84 - - - - - - -
Br-85 - - - - - - -
Rb-86 - 2.66E+9 - - - 6.83E+7 1.32E+9 l Rb-88 - - - - - - -
Rb-89 - - - - - - -
Sr-89 2.65E+10 - - - -
5.44E+8 7.58E+8 Sr-90 2.56E+11 - - - -
3.19E+9 6.51 E+10 l Sr-91 6.17E+5 - - - - 7.31E+5 2.23E+4 l Sr-92 9.76E+0 - - - -
1.05 E+2 3.63 E-1 Y-90 8.16E+1 - - - - 1.13E+5 2.18E+0 Y-91m . - - - - - - -
Y-91 8.80E+3 - - - -
6.31 E+5 2.34E+2 Y-92 6.26E-5 - - - - 1.20E+0 1.76E 6 Y-93 2.70E-1 - - - -
2.14E+3 7.36E-3 Zr-95 8.20E+2 1.99E+2 - -
2.15E+2 -
9.94E+4 1.42E+2 Zr-97 4.79E-1 8.22E-2 - 8.29E-2 - 5.24E+3 3.76E-2 Nb-95 - 7.12E+4 2.93E+4 -
2.10E44 - 2.47E+7 1.69E+4 Nb-97 - - - - -
4.44E-7 -
Mo-99 - 2.54E+7 - 3.80E+7 - 8.38E+6 4.96E+6 Tc-99m 3.23E+0 6.66E+0 - 7.16E+ 1 - 3.48E+0 1.91E+3 8.5 8E+1 Tc.101 - - - - - - -
DBP 6027A 86 Revision i1.0 ODCM
n l
Table 3-9 (continued) !
l Rjo, Grass - Goat - Milk Pathway Dose Factors - INFANT (continued)
(mrem /yr per pCi/m') for H-3 and C-14 (m 2* mrem /yr per pCi/sec) for others i
Llysr Thyroid Kidney Lung GI-LLI T. Body Nuchde Bonc Ru-103 1.04E+3 - - 2.17E+3 - 1.27E+4 3.49E+2 ,
- Ru-105 9.67E-4 - - 7.10E-3 - 3.85E-1 3.25 E-4 Ru 106 2.28E+4 - - 2.70E+4 -
1.73E+5 2.86E+3 Rh-103m - -
i Rh-106 - - -
4.63E+7 3.38E+7 4.84E+7 - 1.75E+9 2.23 E+7.
Ag-110m -
Sb-124 2.51E+7 3.70E+5 6.67E+4 - 1.57E+7 7.75E+7 7.79E+6 l
Sb-125 1.79E+7 1.74E+5 2.24E+4 - 1.13E+7 2.39E+7 3.68E+6 1.81E+7 6.05E+6 6.08E+6 - - 8.62E+6 2.45E+6 Te-125m 5.05E+7 1.68E+7 1.46E+7 1.25E+8 - - 2.04E+7 6.12E+6 Te-127m 7.80E+2 2.62E+2 6.35E+2 1.91E+3 - 1.63E+4 1.68E+2 Te-127 2.30E+7 2.58E+7 1.68E+8 - 4.01E+7 1.03E+7 Te-129m 6.71E+7 2.50E-10 2.10E-10 6.22E-10 - 1.99E-8 -
l Te-129 -
1.63E+5 3.31E+5 1.12E+6 - 2.75E+6 1.34E+5
! Te-131m 4.06E+5 l Te-131 - -
1.25E+6 1.85E+6 7.81E+6 - 4.62E+6 1.17E+6 l l Te 132 2.52E+6 9.50E+6 1.07E+9 - 1.04E+7 - 2.04E+6 3.82E+6 I-130 4.32E+6 1.26E+12 4.50E+9 - 1.38E+8 1.69E+9 l I-131 3.26E+9 3.85E+9 3.47E+0 1.62E+2 3.86E+0 - 2.81E+0 1.24E+0 l-132 1.70E+0 6.49E+7 1.18E+10 7.63E+7 - 1.10E+7 1.90E+7 1-133 4.46E+7 I-134 - - 1.21E-9 - -
2.89E+5 2.59E+7 3.23E+5 - 1.05E+5 1.06E+5 I I-135 1.45E+5 2.04E+11 - 5.2SE+10 2.15E+10 5.55E+8 2.06+10 Cs-134 1.10E+11 6.90E+9 1.41E+9 2.63E+8 6.45 E+9 l Cs-136 5.88E+9 1.73E+10 -
1.81E+11 4.86E+10 1.96E+10 5.64E+8 1.28E+10 Cs-137 1.54E+11 -
Cs-138 - -
- - 3.46E-6 1.58E-9 Ba-139 5.46E-8 - -
2.89E+4 6.88E+3 1.78E+4 7.10E+6 1.49E+6 I Ba-140 2.89E+7 -
Ba-141 -
Ba-142 - -
1.91E+0 - - 2.24E+4 4.91 E-1 La-140 4.84E+0 -
La-142 - - - - - - 6.25E-7 -
3.17E+3 9.78E+2 - 1.64E+6 3.73 E+2 Ce-141 5.20E+3 -
4.80E+1 3.18E+4 - 9.26E+0 - 1.86E+5 3.62E+0 Ce-143 2.80E+5 1.14E+5 - 4.62E+4 - 1.60E+7 1.56E+4 Ce-144 6.71 E+1 2.50E+1 - 9.47E+4 8.89E+0 Pr-143 1.79E+2 -
Pr-144 - -
1.06E+2 1.09E+2 - 4.19E+1 - 6.89E+4 6.66E+0 Nd-147 7.34E+3 5.11E+3 - - 3.00E+5 1.76E+3
' W-187 -
4.67E+0 3.90E-1 7.79E-1 -
1.13 E+4 2.21 E-1 Np-239 -
DBP 6027A 87 - Revision 11.0 ODCM L .. ,.
Table 3-10 Ri o, Grass - Cow - Meat Pathway Dose Factors - ADUllr (mrem /yr per pCi/m') for 113 and C-14 2
(m
- mrem /yr per pCi/sec) for others Nudide Bone Liver Thyroid Kidney Lung GI-LLI T. Body II-3 - 3.25E+2 3.25E+2 3.25E+2 3.25E+2 3.25E+2 3.25 E+2 C-14 3.33E+5 6.66E+4 6.66E+4 6.66E+4 6.66E+4 6.66E+4 6.66E+4 Na 24 1.84E-3 1.84E-3 1.84E-3 1.84E-3 1.84E-3 1.84E-3 1.84E-3 P-32 4.65E+9 2.89E+8 - - -
5.23E+8 1.80E+8 Cr-51 - - 4.22E+3 1.56E+3 9.38E+3 1.78E+6 7.07E+3 Mn-54 - 9.15E+6 - 2.72E+6 -
2.80E+7 1.75E+6 hin-56 - - - - - - -
Fe-55 2.93E+8 2.02E4 8 - - 1.13E+8 1.16E+8 4.72E+7 Fe-59 2.67E+8 6.27E+8 - -
1.75E+8 2.09E+9 2.40E+8 Co-57 -
5.64E+6 - - -
1.43 E+8 9.37E+6 !
Co-58 - 1.83E+7 - -- - 3.70E+8 4.10E+7 Co-60 -
7.52E+7 - - - 1.41E+9 1.66E+8 Ni-63 1.89E+10 1.31E+9 - - -
2.73E+8 6.33 E+8 Ni-65 - - - - -
Cu-64 - 2.95E-7 - 7.45E-7 - 2.52E-5 1.39E-7 Zn-65 3.56E+8 1.13E+9 -
7.57E+8 -
7.13 E+8 5.12E+8 l Zn-69 - - - - - - -
Br-82 - - - - -
1.44E+3 1.26E+3 i Br 83 - - - - - - -
l Br-04 - - - - - - -
1 Br-85 - - - - - - -
Rb-86 - 4.87E+8 - - - 9.60E+7 2.27E+8 Rb-88 - - - - - - -
i Rb-89 - - - - - - -
Sr-89 3.01E+8 - - - - 4.84E+7 8.65E+6 l l
Sr-90 1.24E+10 - - - - 3.59E+8 3.05E+9 i 1.38E-9 - A Sr 91 - - - - -
Sr-92 - - - - - -
Y-90 1.07E+2 - - - -
1.13E+6 2.86E+0 ?
Y-91m - - - - - - -
Y-91 1.13E+6 - - - - 6.24E+8 3.03 E+4 ;
Y-92 - - - - - - -
i Y 93' - - - - - 2.08E-7 -
{
' Zr-95 1.88E+6 6.04E+5 - 9.48E+5 - 1.91E+9 4.09E+5 Zr-97. 1.83E-5 3.69E-6 -
5.58E-6 - 1.14E+0 1.69E-6
- Nb-95 2.29E+6 1.28E+6 - 1.26E46 - -
7.75 E+9 6.86E+5 Nb-97 - - - - - -
Mo-99 - 1.09E+5 - 2.46E+5 -
2.52E+5 2.07E+4 Tc-99m - - - - - - -
Tc 101 - - - - - - -
j DBP 6027A 88 Revision i1.0 l ODCM l
l Table 3-10 l R i o, Grass - Cow - Meat Pathway Dose Factors - ADULT (continued) l 3
(mrem /yr per pCi/m ) for H 3 and C-14 2
(m
- mrem /yr per pCi/sec) for others Nuclide . Bone Liver Thyroid Kidney I ung GI LLI T. Body Ru-103 1.06E+8 - - 4.03 E+8 - 1.23 E+10 4.55E+7 Ru-105 -- - - - - - -
Ru-106 2.80E+9 - - 5.40E+9 - 1.81E+11 ' 3.54E+8 l Rh-103m - - - - - - -
RL 106 - - - - - - -
1 Ag-110m 6.69E+6 6.19E+6 - 1.22E+7 - 2.52E+9 3.67E+6 1.54E+7 5.62E+8 7.85 E+6 ;
Sb-124 1.98E+7 3.74E+5 - 4.80E+4 -
Sb-125 1.91E+7 2.13E+5 1.94E+4 - 1.47E+7 2.10E+8 4.54E+6 i Te-125m 3.59E+8 1.30E+8 1.08E+8 1.46E+9 - 1.43E+9 4.81E+7 l Te-127m 1.12E+9 3.99E+8 2.85E+8 4.53 E+9 -
3.74E+9 1.36E+8 Te-127 - - - 1.09E-9 - 2.10E-8 -
Te-129m 1.14E+9 4.27E+8 3.93E+8 4.77E+9 - 5.76E+9 1.81E+8
-Te-129 - - - - - - -
Te-131m 4.51 E+2 2.21 E+2 3.50E+2 2.24E+3 - 2.19E+4 1.84E+2 Te 131 - - - - - - -
Te-132 1.40E+6 9.07E+5 1.00E+6 8.73E+6 -
4.29E+7 8.51 E+5 I-130 2.35E-6 6.94E-6 5.88E-4 1.08E-5 - 5.98E-6 2.74E-6 I-131 1.08E+7 1.54E+7 5.05E+9 2.64E+7 - 4.07E+6 8.83E+6 1-132 - - - - -
I-133 4.30E-1 7.47E-1 1.10E+2 1.30Et0 - 6.72E-1 2.28E 1 I134 - - - - - - -
I135 - - - - - - -
l I
Cs-134 6.57E+8 1.56E+9 -
5.06E+8 168E+8 2.74E+7 1.28E+9 Cs-136 1.18E+7 4.67E+7 2.60E+7 3.56E+6 5.30E+6 3.36E+7
{
Cs-137 8.72E+8 1.19E+9 - 4.05E+8 1.35E+8 2.31E+7 7.81 E+8 Cs-138 - - - - - - -
Ba-139 - - - - - - -
Ba-140 2.88E+7 3.61 E+4 - 1.23E+4 2.07E+4 5.92E+7 1.89E+6 Ba-141 - - - - - - -
Ba-142 - - - - - - -
i La-140 3.60E-2 1.81E-2 - - - 1.33E+3 4.79E-3 La-142 - - - - - - - l Cc-141 1.40E+4 9.48E+3 - 4.40E+3 - 3.62E+7 1.08E+3 Ce-143 2.09E-2 1.55E+1 - 6.80E-3 - 5.78E+2 1.71 E.3 Ce-144 1.46E+6 6.09E+5 - 3.61 E+5 - 4.93 E+8 7.83 E+4 Pr-143 2.13 E+4 8.54E+3 -
4.93 E+3 -
9.33 E+7 1.06E+3 Pr-144 - - - - - - -
Nd-147 7.08E+3 8.18E+3 - 4.78E+3 -
3.93 E+7 4.90E+2 W-187 2.16E 2 1.81 E-2 - - -
5.92E+0 6.32E-3 Np-239 2.56E-1 2.51E-2 -
7.84E-2 -
5.15E+3 1.39E-2 DDP 6027A 89 Revision 11.0 ODCM J
Q Table 3-10 (continued) d i
R o, Grass (mrem - Cow
/yr per-Ci/m Meat Pathway) for 113 and C-14Dose Factors - TEENAGER 2
(m
- mrem /yr per pCi/sec) for others i
Nuclide . Bone Liver Thyroid Kidney Lung Gl-LLI T. Body H-3 ' - 1.94E+2 1.94E+2 1.94E+2 1.94E+2 1.94E+2 1.94E+2 C-14 2.81 E+5 5.62E+4 5.62E+4 5.62E+4 5.62E+4 5.62E+4 5.62E+4 Na 24 1.47E-3 1.47E-3 1.47E-3 1.47E-3 1.47E-3 1.47E-3 1.47E-3 P-32 3.93 E+9 2.44E+8 - - -
3.30E+8 1.52E+8 s Cr-51 - - 3.14E+3 1.24E+3 8.07E+3 9.50E+5 5.65 E+3 !
Mn-54 - 6.98E+6 - 2.08E+6 -
1.43 E+7 1.38E+6 Mn 56 - - - - - - -
)
Fe-55 2.38E+8 1.69E+8 - - 1.07E+8 7.30E+7 3.93E+7 Fe-59 2.13E+8 4.98E+8 - - 1.57E+8 1.18E+9 1.92E+8 Co-57 -
4.53E+6 - - -
8.45E+7 7.59E+6 i Co-58 - 1.41E+7 - - -
1.94E+8 3.25E+7 Co-60 - 5.83E+7 - - - 7.60E+8 1.31E+8 Ni 63 1.52 E+10 1.07E+9 - - - 1.71E+8 5.15E+8 Ni-65 - - - - - - -
Cu-64 - 2.41 E-7 -
6.10E-7 -
1.87E-5 1.13 E-7 Zn-65 2.50E+8 8.69E+8 - 5.56E+8 - 3.68E+8 4.05E+8 Zn-69 - - - - - - -
Br-82 - - - - - -
9.98E+2 Br 83 ~ - - - - - - -
Br-84 - - - - - - -
Br-85 - - - - - - -
Rb-86 - 4.06E+8 - - - 6.01E+7 1.91E+8 Rb 88 - - - - - - -
Rb-89 - - - - - - -
Sr-89 2.54E+8 - - - -
3.03E+7 7.29E+6 Sr-90 8.05E+9 - - - - 2.26E+8 1.99E+9 Sr-91 - - - - - 1.10E-9 -
Sr-92 - - - - - - -
Y-90 8.98E+1 - - - -
7.40E+5 2.42E+0 Y-91m - - - - - - -
Y-91 9.56E+5 - - - -
3.92E+8 2.56E+4 Y-92, - - - - - - -
Y-93 - - - - - 1.69E-7 -
Zr 95 1.51 E+6 4.76E+5 - 6;99E+5 - 1.10E+9 3.27E+5 Zr-97. 1.53E-5 3.02E-6 - 4.58E-6 - 8.18E-1 1.39E-6 Nb-95 1.79E+6 9.94E+5 -
9.64E+5 - 4.25E+9 5.47E+5 Nb-97 - - - - - - -
Mo-99 - 8.98E+4 - 2.06E+5 - 1.61E+5 1.71E+4 Tc-99m - - - - - - -
Tc-101 - - - - - - -
DBP 6027A 90 Revision 11.0 ODCM
l Table 3-10 (continued)
Ri o, Grass - Cow - Meat Pathway Dose Factors - TEENAGER (continued) 3 (mrem /yr per pCi/m ) for H-3 and C-14 2
(m
- mrem /yr per pCi/sec) for others Nuchde . Bone Liver Thyroid . Kidney Lung GI-LLI T. Body Ru-103 8.60E+7 - -
3.03E+8 - 7.18E+9 3.68E+7 Ru-105 - - - - - - -
Ru-106 2.36E+9 - -
4.55E+9 -
1.13E+11 2.97E+8 Rh-103m - - - - - - -
Rh-106 - - - - - - -
Ag-110m 5.06E+6 4.79E+6 -
9.14E+6 -
1.35E+9 2.91 E+6 Sb-124 1.62E+7 2.98E+5 3.67E+4 -
1.41E+7 3.26E+8 6.31E+6 Sb-125 1.56E+7 1.71E+5 1.49E+4 -
1.37E+7 1.22E+8 3.66E+6 Te-125m 3.03 E+8 1.09E+8 8.47E+7 - -
8.94E+8 4.05 E+7 Te-127m 9.41E+8 3.34E+8 2.24E+8 3.82E+9 -
2.35E+9 1.12E+8 Te-127 - - - - - 1.75 E-8 -
Te-129m 9.58E+8 3.56E+8 3.09E+8 4.01E+9 - 3.60E+9 1.52E+8 Te-129 - - - - - - -
Te-131m 3.76E+2 1.80E+2 2.71E+2 1.88E+3 -
1.45E+4 1.50E+2 Te-131 - - - - - - -
Te-132 1.15 E+6 7.26E+5 7.66E+5 6.97E+6 -
2.30E+7 6.84E+5 I-130 1.89E-6 5.48E-6 4.47E-4 8.44E-6 -
4.21E-6 2.19E-6 L
I-131 8.95E+6 1.25E+7 3.66E+9 2.16E+7 - 2.48E+6 6.73E+6 I-132 - - - - - - -
I-133 3.59E-1 6.10E-1 8.51 E+1 1.07E+0 -
4.61E-1 1.86E-1 1134 - - - - - - -
I-135 - - - - - - -
Cs-134 5.23E+8 1.23 E+9 - 3.91 E+8 1.49E+8 1.53E+7 5.71E+8
! Cs-136 9.22E+6 3.63E+7 - 1.97E+7 ~ 3.11E+6 2.92E+6 2.44E+7 Cs-137 7.24E+8 9.63 E+8 - 3.28E+8 1.27E+8 1.37E+7 3.36E+8 l
i Cs 138 - - - - - - -
l Ba-139 - - - - - - -
Ba 140 2.38E+7 2.91 E+4 - 9.88E+3 1.96E+4 3.67E+7 1.53 E+6 Ba 141 - - - - - - -
(
Ba-142 - - - - - - -
j La-140 2.96E-2 1.45E-2 - - - 8.35E+2 3.87E-3 La-142 - - - - - - -
I Ce-141 1.18E+4 7.86E+3 - 3.70Et3 -
2.25E+7 9 03E+2 Cc-143 1.76E-2 1.28E+1 - 5.74E-3 -
3.85E+2 1.43E-3 Cc-144 1.23E+6 5.08E+5 -
3.04E+5 -
3.09E+8 6.60E+4 Pr-143 1.79E+4 7.15 E+3 -
4.I6E+3 -
5.90E+7 8.92 E+2 Pr-144 - - - - - - -
Nd-147 6.24E+3 6.79E+3 - 3.98 E+3 -
2.45 E+7 4.06E+2 i W-187 1.81 E-2 1.48E-2 - - -
3.99E+0 5.17E 3 Np-239 2.23E-1 2.11 E-2 - 6.61 E-2 - 3.39E+3 1.17E-2 )
DBP 6027A 91 Revision 11.0 l ODCM l
Table 3-10 (continued)
Ri o, Grass - Cow - Meat Pathway Dose Factors - CHILD 3
(mrem /yr per pCi/m ) for 11-3 and C-14 (m'
- mrem /yr per pCi/sec) for others Nuchde Bone Liv r Thyroid Kidney Lung GI-LLI T. Body H-3 -
2.34E+2 2.34E+2 2.34E+2 2.34E+2 2.34E+2 2.34E+2 C-14 5.29E+5 1.06E+5 1.06E+5 1.06E+5 1.06E+5 1.06E+5 1.06E+5 Na-24 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.34E-3 P-32 7.41E+9 3.47E+8 - - -
2.05E+8 2.86E+8 Cr-51 - - 4.89E+3 1.34E+3 8.93E+3 4.67E+5 8.81E+3 Mn-54 - 7.99E+6 -
2.24E+6 - 6.70E+6 2.13E+6 hin-56 - - - - - - -
Fe-55 4.57E+8 2.42E+8 - - 1.37E+8 4.49E+7 7.51E+7 Fe-59 3.78E+8 6.12E+8 - -
1.77E+8 6.37E+8 3.05E+8 Co-57 -
5.92E+6 - - -
4.85E+7 1.20E+7 Co-58 -
1.65E+7 - - -
9.60E+7 5.04E+7 Co-60 - 6.93E+7 - - -
3.84E+8 2.04E+8 Ni-63 2.91 E+10 1.56E+9 - - - 1.05E+8 9.91 E+8 Ni-65 - - - - - - -
Cu-64 -
3.24E-7 -
7.82E-7 -
1.52E-5 1.96E-7 Zn-65 3.75E+8 1.00E+9 - 6.30E+8 -
1.76E+8 6.22E+8 Zn-69 - - - - - - -
Br-82 - - - - - -
1.56E+3 Br-83 - - - - - - -
Br-84 - - - - - - -
Br-85 - - - - - - -
Rb-86 - 5.76E+8 - - - 3.71E+7 3.54E+8 Rb-88 - - - - - - -
Rb-89 - - - - - - -
Sr-89 4.82E+8 - - - - 1.86E+7 1.38E+7 Sr-90 1.04E+10 - - - -
1.40E+8 2.64E+9 Sr-91 - - - - -
1.01 E-9 -
Sr-92 - - - - - - -
Y-90 1.70E+2 - - - - 4.84E+5 4.55E+0 Y-91m - - - - - - -
Y-91 1.81E+6 - - - -
2.41 E+8 4.83E+4 Y-92 - - - - - - -
'Y-93 - - - - -
1.55E-7 -
Zr-95 2.68E+6 5.89E+5 -
8.43E+5 -
6.14E+8 5.24E+5 Zr-97 2.84E-5 4.10E-6 -
5.89E-6 - 6.21 E-1 2.42E-6 Nb-95 3.09E+6 1.20E+6 -
1.13E+6 - 2.23 E+9 8.61 E+5
, Nb-97 - - - - - - -
Mo-99 - 1.25E+5 - 2.67E+5 - 1.03E+5 3.09E+4 Tc-99m - - - - - - -
Tc-101 - - - - - - -
DBP 6027A 92 Revision 11.0 ODCM
m Table 3-10 (continued)
Ri o, Grass - Cow - Meat Pathway Dose Factors - CIllLD (continued)
(mrem /yr per pCi/m') for 113 and C-14 (m*
- mrem /yr per pCi/sec) for others Nuchde Bone Liver Thyroid Kidney _ Lung GI-LLI T. Body Ru-103 1.56E+8 - -
3.92E+8 - 4.02E+9 5.98E+7 Ru-105 - - - - -
Ru-106 4.44E+9 - -
5.99E+9 - 6.90E+10 5.54E+8
~
Rh 103m - - - - - - -
Rh-106 - - - - - -
Ag-110m 8.40E+6 5.67E+6 - 1.06E+7 - 6.75E+8 4.53 E+6 Sb-124 2.93E+7 3.80E+5 6.46E+4 - 1.62E+7 1.83E+8 1.03E+7 Sb-125 2.85E+7 2.19E+5 2.64E+4 -
1.59E+7 6.80E+7 5.96E+6 Te-125m 5.69E+8 1.54E+8 1.60E+8 - -
5.49E+ 8 7.59E+7 Te-127m 1.77E+9 4.78E+8 4.24E+8 5.06E+9 -
1.44E+9 2.11 E+8 Te-127 - - - 1.21 E-9 - 1.66E-8 -
Te-129m 1.81E+9 5.04E+8 5.82E+8 5.30E+9 - 2.20E+9 2.80E+8 Te-129 - - - - - -
Te-131m 7.00E+2 2.42E+2 4.98E+2 2.34E+3 -
9.82E+3 2.58E+2 Te-131 - - - - -
Te-132 2.09E+6 9.27E+5 1.35E+6 8.60E+6 -
9.33E+6 1.12E+6 I-130 3.39E-6 6.85E-6 7.54E-4 1.02E-5 - 3.20E-6 3.53 E-6 1-131 1.66E+7 1.67E+7 5.52E+9 2.74E+7 -
1.49E+6 9.49E+6 I-132 - - - - - -
I-133 6.68E-1 8.26E-1 1.53E+2 1.38E+0 - 3.33E-1 3.12E-1 I-134 - - - - - - -
I-135 - - - - - -
Cs-134 9.22E+8 ' l.51E+9 - 4.69E+8 1.68E+8 8.15E+6 3.19E+8
, Cs-136 1.59E+7 4.37E+7 - 2.33E+7 3.47E+6 1.54E+6 2.83E+7 Cs-137 1.33E+9 1.28E+9 - 4.16E+8 1.50E+8 7.99E+6 1.88E+8 Cs-138 - - - - - -
Ba-139 - - - - - -
Ba-140 4.39E+7 3.85E+4 - 1.25E+4 2.29E+4 2.22E+7 2.56E+6 Ba-141 - - - - -
Ba-142 - - - - - - -
La-140 5.41E-2 1.89E-2 - - -
5.27E+2 6.38E-3 J
La-142 - - - - - - -
]
Ce-141 2.22E+4 1.11E+4 -
4.84E+3 - 1.38E+7 1.64E+3 l Ce-143 3.30E-2 1.79E+1 -
7.51E-3 - 2.62E+2 2.59E-3 )
Ce-144 2.32E+6 7.26E+5 - 4.02E+5 -
1.89E+8 1.24E+5 Pr-143 3.39E+4 1.02E+4 -
- $.51 E+3 -
3.66E+7 1.68E+3 Pr-144 - - - - - - -
Nd-147 1.17E+4 9.48E+3 -
5.20E+3 - 1.50E+7 7.34E+2 W-187 ~ 3.36E-2 1.99E-2 - - -
2.79E+0 8.92E-3 Np-239 4.20E-1 3.02E-2 ' - 8.73E-2 - 2.23E+3 2.12E-2 DBP 6027A 93 Revision 11.0 ODCM e
o ;
Table 3-11 R i o, Vegetation Pathway' Dose Factors - ADULT (mrem /yr per pCi/m ) for H-3 and C-14 2
(m
- mrem /yr per pCi/sec) for others Nuchde Bone _ Liver' Thyroid Kidney Lung GI-LLI T. Body H-3 -
2.26E+3 2.26E+3 2.26E+3 - 2.26E+3 2.26E+3 2.26E+3
'C 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 l Na-24 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 )
P-32 1.40E+9 8.73E+7 - - -
1.58E+8 5.42E+7 l Cr-51 - - 2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 f 1
Mn-54 -- 3.11E+8 -
9.27E+7 . -
9.54E+8 5.94E+7 Mn .
1.61E+1 -
2.04E+1 -
5.13E+2 2.85E+0 Fe-55 2.09E+8 1.45E+8 - - 8.06E+7 8.29E+7 3.37E+7 Fe-59 1.27E+8 2.99E+8 - - 8.35E+7 9.96E+8 1.14E+8 .
Co-57 -- 1.17E+7 - - - 2.97E+8 1.95E+7 Co-58 -
3.09E+7 - - - 6.26E+8 6.92E+7 Co-60 -
1.67E+8 - - -
3.14E+9 3.69E+8 3.49E+8 l
Ni-63 1.04E+10 7.21E+8 - - -
1.50E+8 )
Ni-65 6.15E+1 7.99E+0 - - -
2.03E+2 3.65E+0 Cu-64 -
9.27E+3 - 2.34E+4 -
7.90E+5 4.35E+3 !
I Zn-65 3.17E+8 1.01E+9 - 6.75E+8 - 6.36E+8 4.56E+8 )
Zn 8.75E-6 1.67E-5 - 1.09E-5 -
2.51E-6 1.16E-6
]
Br-82 - - - - -
1.73E+6 1.51E+6 Br-83 - - - - -
4.63E+0 - 3.21E+0 Br-84 - - - - - - -
Br-85 - - - - - - -
Rb-86 -
2.19E+8 - -- - 4.32E+7 1.02E+8 Rb-88 - - - - - - -
Rb-89 - - -- - - - -
Sr-89 9.96E+9 - - - - 1.60E+9 2.86E+8 Sr-90 6.05E+11 - - - - 1.75E+10 1.48E+11 Sr-91 3.20E+5 - - - -
1.52E+6 1.29E+4 Sr-92 4.27E+2 - - - -
8.46E+3 1.85E+1 Y-90 1.33E+4 - - - -
1.41E+8 3.56E+2 Y-91m 5.83E-9 - - - - 1.71E-8 -
Y-91 5.13E+6 - - - - 2.82E+9 1.37E+5 Y-92 9.01E-1 - - - - 1.58E+4 2.63E-2 Y-93 -1.74E+2 - - - - 5.52E+6 4.80E+0 Zr-95 1.19E+6 3.81E+5 - 5.97E+5 - 1.21E+9 2.58E+5 Zr-97 3.33E+2 6.73E+1 -
1.02E+2 -
2.08E+7 3.08E+1 Nb-95 1.42E+5 -- 7.91 E+4 - 7.81 E+4 - 4.80E+8 4.25E+4 Nb-97 2.90E-6 7.34E-7 - 8.56E-7 -
2.71E-3 2.68E-7 Mo-99 -- 6.25E+6 -
1.41E+7 - 1.45E+7 1.19E+6 Tc-99m -- 3.06E+0 8.66E+0 -
1.32E+2 4.24E+0 5.12E+3 1.10E+2 Tc-101 - - - - - - -
DBP 6027A 94 Revision 11.0 ODCM
rr l
Table 3-11 (continued)
R i o, Vegetation Pathway Dose Factors - ADULT (continued)
(mrem /yr per pCi/m') for H-3 and C-14 (m2* mrem /yr per Ci/sec) for others Nuchde . Bone Liver - Thyroid Kidney Lung GI-LLI T. Body Ru-103 4.80E+6 -- - 1.83E+7 -
5.61E+8 2.07E+6 Ru-105 5.39E+1 - -
6.96E+2 - 3.30E+4 2.13E+1 Ru-106 1.93E+8 - - 3.72E+8 - 1.25E+10 2.44E+7 Rh-103m - - - - - - -
Rh-106 - - - - - - -
. Ag-110m 1.06E+7 9.76E+6 .- 1.92E+7 - 3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 - 8.08E+7 2.95E+9 4.11E+7 Sb-125 - 1.36E+8 1.52E+6 1.39E+5 - 1.05E+8 1.50E+9 3.25E+7 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93 E+8 - 3.86E+8 1.29E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 -- 1.17E+9 4.26E+7 Te-127 5.76E+3 2.07E+3 4.27E+3 2.35E+4 - 4.54E+5 1.25E+3 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 -
1.28E+9 4.03E+7 Te-129 6.65 E-4 2.50E-4 5.10E-4 2.79E-3 - 5.02E-4 1.62E-4 Te-131m 9.12E+5 4.46E+5 7.06E+5 4.52E+6 -
4.43E+7 3.72E+5 Te-131 - - - - - - -
Te-132 4.29E+6 2.77E+6 3.06E+6 2.67E+7 - 1.31E+8 2.60E+6
.I-130 3.96E+5 1.17E+6 9.90E+7 1.82E+6 -
1.01E+6 4.61E+5 I-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8- -
3.05E+7 6.63E+7 I-132 5.74E+1 1.54E+2 5.38E+3 2.45E+2 - 2.89E+1 5.38E+1 I-133 2.12E+6 3.69E+6 5.42E+8 6.44E+6 -
3.31E+6 1.12E+6 I-134 1.06E-4 2.88E-4 ' 5.00E-3 4.59E-4 -
2.51E-7 1.03 E-4 1-135 4.08E+4 1.07E+5 7.04E+6 1.71E+5 - 1.21E+5 3.94E+4 Cs-134 4.66E+9 1.11E+10 -
3.59E+9 - 1.19E+9 - 1.94E+8 9.07E+9 Cs-136 4.20E+7 1.66E+8 - 9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-137 6.36E+9 8.70E+9 -
2.95E+9 9.81E+8 1.68E+8 5.70E+9 Cs-138 - - - - - - -
Ba-139 2.95E-2 2.10E-5 -
1.96E-5 1.19E-5 5.23E-2 8.64E-4 Ba-140 1.29E+8 1.62E+5 - 5.49E+4 9.25E+4 2.65E+8 8.43E+6
' Ba 141 - - - - - - - -
Ba-142 - - - - - - -
La-140 1.97E+3 9.92E+2 - - - 7.28E+7 2.62E+2 La-142 1.40E-4 . 6.35E 5 - - -
4.64E-1 1.58E-5
-Cc-141 1.96E+5 1.33E+5 -
6.17E+4 - 5.08E+8 1.51E+4 Cc-143 1.00E+3 7.42E+5 - 3.26E+2 - 2.77E+7 8.21 E+1 Ce-144 3.29E+7 1.38E+7 - 8.16E+6 -
1.11E+10 1.77E+6 l- Pr-143 6.34E+4 2.54E+4 - 1.47E+4 -
2.78E+8 ' 3.14E+3 Pr-144 - - - - - - -
Nd-147 ' 3.34E+4 - 3.86E+4 - 2.25E+4 - 1.85E+8 2.31E+3 W-187 - 3.82E+4 3.19E+4 - - -
1.05E+7 1.12E+4 Np-239 1.42E+3 .1.40E+2 - 4.37E+2 -
2.87E+7 7.72E+1 DBP 6027A - 95 Revision 11.0-ODCM e
y -
Table 3-11 (continued)
R;o, Vegetation Pathway Dose Factors - TEENAGER 3
(mrem /yr per pCi/m ) for H-3 and C-14 2
(m mrem /yr per pCi/sec) for others Nuchde Bone Liver - Thyroid Kidney Lung GI-LLI T. Body H-3 -
2.59E+3 ~ 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3
~ C-14 ' l.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 Na-24 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 -
P-32 1.61E+9 9.96E+7 - - -
1.35E+8 6.23E+7 Cr-51 - - . 3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4
' Mn-54 - '4.52E+8 - - 1.35E+8 - 9.27E+8 8.97E+7 Mn-56 -
- 1.45E+1 - 1.83E+1 -
9.54E+2 2.58E+0 Fe-55 3.25E+8 - - 2.31E+8 - -
1.46E+8 9.98E+7 5.38E+7
- Fe-59 ' l.81E+8 4.22E+8 -- - 1.33E+8 9.98E+8 1.63E+8 Co-57 ' - 1.79E+7 - - -
3.34E+8 3.00E+7 Co-58 - 4.38E+7 - - - 6.04E+8 1.01E+8 Co-60 - 2.49E+8 -- - -
3.24E+9 5.60E+8 Ni-63 ' 1.61E+10 1.13E+9 - - - 1.81E+8 5.45E+8 Ni-65 5.73E+1 . 7.32E+0 - - - 3.97E+2 3.33E+0 i Cu-64 - 8.40E+3 - 2.12E+4 - 6.51E+5 3.95E+3 Zn-65 4.24E+8 1.47E+9 - 9.41 E+8 - 6.23E+8 6.86E+8 Zn-69 8.19E-6 1.56E-5 - 1.02E-5 -
2.88E-5 1.09E-6 Br'-82 - - - - - -
1.33E+6
' Br-83 - - - - - - 3.01E+0 Br - - - - - - -
Br-85 ' - - - - .
Rb-86 '- -
2.73E+8 - - - 4.05E+7 1.28E+8 Rb-88 - - - - - - -
Rb-89 - - - - - - -
Sr-89 1.51 E+10 - - - - 1.80E+9 4.33E+8
. Sr-90 7.51E+11 - - - - 2.1lE+10 1.85E+11 Sr-91 2.99E+5 - - - -
1.36E+6 1.19E+4 i Sr 3.97E+2 - - - -
1.01E+4 1.69E+1 }
1.02E+8 3.34E+2 l Y-90 1.24E+4 - - - -
Y-91m 5.43E-9 - - - - 2.56E-7 -
.Y 7.87E+6 - - - -
3.23E+9 2.11 E+5 Y-92 8.47E-1 - - - -
2.32E+4 2.45 E -Y-93 1.63E+2 - - - - 4.98E+6 4.47E+0 Zr-95 1.74E+6 5.49E+5 - 8.07E+5 - 1.27E+9 3.78E+5
. Zr-97 3.09E+2 6.11 E+1 - 9.26E+1 -
1.65E+7 2.81E+1 Nb-95 1.92E+5 1.06E+5 -
1.03E+5 - 4.55E+8 5.86E+4 Nb 2.69E-6 6.67E-7 - 7.80E-7 - 1.59E-2 2.44E-7
- Mo-99 -. 5.74E+6- -
1.31E+7 -
1.03E+7 1.09E+6 Tc-99m 2.70E+0 7.54E+0 - 1.12E+2 4.19E+0 4.95E+3 9.77E+1 Tc-101. - - - - - - -
DBP 6027A 96 Revision 11.0 ODCM f
Table 3-11 -(continued)
Ri o, Vegetation Pathway Dose Factors - TEENAGER (continued)
(mrem /yr per pCi/m') for H 3 and C-14 (m'
- mrem /yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body Ru-103 6.87E+6 - -
2.42E+7 -
5.74E+8 2.94E+6 Ru-105 5.00E+1 - - 6.31E+2 - 4.04E+4 1.94E+1 Ru-106 3.09E+8 - - 5.97E+8 - 1.48E+10 3.90E+7 Rh-103m - - - -
. Rh-106 - -- -
Ag-110m ' 1.52E+7 1.44E+7 - 2.74E+7 -
4.04E+9 8.74E+6 Sb-124 1.55E+8 - 2.85E+6 3.51E+5 - 1.35E+8 3.llE+9 6.03E+7 Sb-125 . 2.14E+8 2.34E+6 - 2.04E+5 - 1.88E+8 1.66E+9 5.00E+7 Te-125m 1.48E+8: 5.34E+7 4.14E+7 - - 4.37E+8 1.98E+7 Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 ' - 1.37E+9 6.56E+7 Te-127 5.43E+3 - 1.92E+3 3.74E+3 2.20E+4 - 4.19E+5 1.17E+3 Te-129m 3.67E+8 . 1.36E+8 1.18E+8 1.54E+9 -- 1.38E+9 5.81E+7 Te-129 6.22E 2.32E-4 4.45E-4 2.61E-3 -
3.40E-3 1.51 E-4 Te-131m 8.44E+5 - 4.05E+5 6.09E+5 ' 4.22E+6 - 3.25E+7 3.38E+5 Te-131 - - - -
Te-132 3.90E+6 2.47E46 2.60E+6 2.37E+7 - 7.82E+7 2.32E+6 I-130 3.54E+5' l.02E+6 8.35E+7 1.58E+6 -- 7.87E+5 4.09E F5 I-131- . 7.70E+7 - 1.08E+8- 3.14E+10 1.85E+8 -
2.13E+7 5.79E+7 I-132 5.18E+1 1.36E+2 4.57E+3 2.14E+2 -
5.91E+1 . 4.87E+1 1-133 1.97E+6 3.34E+6 4.66E+8 5.86E+6 - 2.53E+6 1.02E+6
'I-134 9.59E-5 2.54E-4 4.24E-3 ' 4.01E-4 - 3.35E-6 9.13E-5 I-135 3.68E+4 9.48E+4 6.10E+6 1.50E+5 ~- 1.05E+5 3.52E+4 Cs-134 . 7,09E+9 1.67E+10 - 5.30E+9 2.02E+9 2.08E+8 7.74E+9 Cs-136 ~ 4.29E+7 1.69E+8 - 9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-137 1.01E+10 1.35E+10 - 4.59E+9 1.78E+9 1.92E+8 4.69E+9 Cs-138 - - - - -
Ba-139. 2.77E-2 1.95E-5 - 1.84E-5 1.34E-5 2.47E-1 8.08E-4 Ba-140 1.38E+8 ' 1.69E+5 - 5.75E+4 1.14E+5 2.13E+8 8.91E+6 I
Ba-141 - - - - -
, Ba-142 - .
La-140 1.80E+3 8.84E+2 - - -
5.08E+7 2.35E+2
.La-142 1.28E-4 5.69E-5 - - -
1.73E+0 1.42E-5 Ce-141 2.82E+5 1.88E+5 - 8.86E+4 -
5.38E+8 2.16E+4 Ce-143 9.37E+2. 6.82E+5 -
3.06E+2 -
2.05E+7 7.62E+1 Cc-144- 5.27E+7~ 2.18E+7 - 1.30E+7 - 1.33E+10 2.83E+6 Pr-143 - 7.12E+4 2.84E+4 - 1.65E+4 -
2.34E+ 8 3.55E+3 -
Pr-144 - - - - - - -
Nd-147 3.63E+4 ' 3.94E+4 . - 2.32E+4 -
1.42Et8 2.36E+3
.W-187: 3.55E+4 2.90E+4 - - --
7.84E+6 1.02E+4 Np-239 : 1.38E+3_ 1.30E+2 - 4.09E+2 - 2.10E+7 7.24E+1 DBP 6027A .97 Revision 11.0 )
Table 3-11 (continued)
R; '(Vegetation mrem /yr per pCi/m Pathway' Dose
) for H-3 and C-14 Factors - CilILD (m*
- mrem /yr per pCi/sec) for others Nuchde Bone Liver Thyroid Kidnev _ Lung GI-LLI T. Body H-3 - 4.01E+3 4.01E+3 4.01E+3 4.01 E+3 4.01E+3 4.01 E+3 C-14 3.50E+6 7.01 E+5 7.01 E+5 7.01E+5 7.01E+5 7.01E+5 7.01 E+5 Na 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 P-32 3.37E+9 1.58E+8 - - -
9.30E+7 1.30E+8 Cr-51 - - 6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 Mn-54 - 6.61E+8 -
1.85E+8 -
5.55E+8 1.76E+8 Mn-56 -
1.90E+1 -
2.29E+1 -
2.75E+3 4.28E+0 Fe-55 8.00E+8 4.24E+8 - -
2.40E+8 7.86E+7 1.31E+8 Fe-59 4.01E+8 6.49E+8 - -
1.88E+8 6.76E+8 3.23E+8 Co-57 -
2.99E+7 - - -
2.45E+ 8 6.04E+7 Co-58 -
6.47E+7 - - -
3.77E+8 1.98E+8 Co-60 -
3.78E+8 - - -
2.10E+9 1.12E+9 Ni-63 3.95 E+10 2.l l E+9 - - -
1.42E+8 1.34E+9 Ni-65 1.05E+2 9.89E+0 - - -
1.21E+3 5.77E+0 Cu-64 -
1.11E+4 - 2.68E+4 -
5.20E+5 6.69E+3 Zn-65 8.12E+8 2.16E+9 -
1.36E+9 -
3.80E+8 1.35E+9 Zn-69 1.51E-5 2.18E-5 -
1.32E-5 -
1.38E-3 2.02E-6 Br-82 - - - - - -
2.04E+6 Br-83 - - - - - -
5.55E+0 Br-84 - - - - - - -
Br-85 - - - - - - -
Rb-86 - 4.52E+8 - - - 2.91E+7 2.78E+8 Rb-88 - - - - - - -
Rb-89 - - - - - - -
Sr-89 3.59E+10 - - - -
1.39E+9 1.03E+9 Sr-90 1.24E+12 - - - -
1.67E+10 3.15E+11 Sr-91 5.50E+5 - - - -
1.21E+6 2.08E+4 Sr-92 7.28E+2 - - - -
1.38E+4 2.92E+1 Y-90 2.30E+4 - - - -
6.56E+7 6.17E+2 Y-91m 9.94E-9 - - - -
1.95 E-5 -
Y-91 1.87E+7 - - - -
2.49E+9 5.01 E+5 Y-92 1.56E+0 - - - -
4.51E+4 4.46E-2 Y-93 3.01E+2 - - - -
4.48E+6 8.25E+0 Zr-95 3.90E+6 8.58E+5 -
1.23E+6 -
8.95E+8 7.64E+5 Zr-97 5.64E+2 8.15E+1 -
1.17E+2 -
1.23E+7 4.81 E+1 Nb-95 4.10E+5 1.59E+5 - 1.50E+5 -
2.95E+8 1.14E+5 Nb-97 4.90E-6 8.85E-7 -
9.82E-7 -
2.73 E-1 4.13E-7 Mo-99 -
7.83E+6 -
1.67E+7 -
6.48E+6 1.94E+6 Tc-99m 4.65E+0 9.12E+0 - 1.33E+2 4.63 E+0 5.19E+3 1.51 E+2 Tc-101 - - - - - - -
DBP 6027A 98 Revision 11.0 ODCM 9 -
n Table 3-11 (continued)
Rw, Vegetation Pathway Dose Factors - CHILD (continued)
(mrem /yr per pCi/m') for H-3 and C-14 l 2
(m
- mrem /yr per pCi/sec) for others Nyclide Bone Liver Thyroid Kidney Lung GI-LL1 T. Body Ru-103 1.55E+7 - -
3.89E+7 - 3.99E+8 5.94E+6 Ru-105 9.17E+1 - - 8.06E+2 -
5.98E+4 3.33E+1 Ru-106 7,45 E+8 - -
1.01 E+9 -
1.16E+10 9.30E+7 Rh-103m - - - - - - -
Rh-106 - - - - - - -
Ag-110m 3.22E+7 2.17E+7 -
4.05E+7 -
2.58E+9 1.74E+7 Sb-124 3.52E+8 - 4.57E+6 7.78E+5 - 1.96E+8 2.20E+9 1.23E+8 Sb-125 4.99E+8 3.85E+6 4.62E+5 - 2.78E+8 1.19E+9 1.05E+8 Te-125m 3.51 E+8 9.50E+7 9.84E+7 - -
3.38E+8 4.67E+7 Te-127 1.32E+9 1.56E+8 3.16E+8 3.77E+9 - 1.07E+9 1.57E+8 Te-127 - 1.00E+4 2.70E+3 6.93E+3 2.85E+4 -
3.91 E+5 2.15E+3 Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 -
1.04E+9 1.33E+8 Te-129 1.15E-3 3.22E-4 8.22E-4 3.37E-3 - 7.17E-2 2.74E-4 Te-131m 1.54E+6 5.33E+5 1.10E+6 5.16E+6 - 2.16E+7 5.68E+5
' Te-131 ' - - - - - - -
Te-132 6.98E+6 3.09E+6 4.50E+6 2.87E+7 -
3.l lE+7 3.73E+6 I-130 6.21E+5 1.26E+6 1.38E+8 1.88E+6 - 5.87E+5 6.47E+5 I-131 1.43E+8 ' l.44E+8 4.76E+10 2.36E+8 - 1.28E+7 8.18E+7 I 132 9.20E+1 1.69E+2 7.84E+3 2.59E+2 -
1.99E+2 7.77E+1 1-133 3.59E+6 4.44E+6 8.25E+ 8 - 7.40E+6 -
1.79E+6 1.68E+6 I-134 1.70E-4 3.16E-4 7.28E-3 4.84E-4 - 2.10E-4 1.46E-4 1-135 6.54E+4 1.18E+5 1.04E+7 1.81E+5 - 8.98E+4 5.57E+4 Cs-134 1.60E+10 2.63E+10 - 8.14E+9 2.92E+9 1.42E+8 5.54E+9 Cs-136 8.06E+7 2.22E+8 -
1.18E+8 1.76E+7 7.79E+6 1.43E+8 Cs-137 2.39E+10 2.29E+10 -
7.46E+9 2.68E+9 1.43E+8 3.38E+9 Cs-138 - - - - - - -
Ba-139 5.ll E-2 2.73E-5 - 2.38E-5 1.61E-5 2.95E+0 1.48E-3 Ba-140 2.77E+8 2.43E+5 -
7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ba-141 - - - - - - -
Ba-142 - - - - - - -
La-140 3.23 E+3 . 1.13E+3 - - - 3.15E+7 3.81E+2 La-142 2.32E-4 7.40E-5 - - -
1.47E+1 2.32E-5 Cc-141 1.23 E+5 - 6.14E+4 -
2.69E+4 - 7.66E+7 9.12E+3 Cc-143 1.73E+3 9.36E+5 -
3.93E+2 -
1.37E+7 1.36E+2 Ce-144 1.27E+8 - 3.98E+7 -
2.21 E+7 -
1.04E+10 6.78E+6 Pr-143 1.48E+5 4.46E+4 -
2.41 E+4 -
1.60E+8 7.37E+3 Pr-144 - - - - - - -
Nd-147 7.16E+4 5.80E+4 -
3.18E+4 - 9.18E+7 4.49E+3 W-187 6.47E+4 3.83E+4 - - - 5.38E+6 1.72E+4 Np-239_ - 2.55E+3 1.83 E+2 -
-5.30E+2 -
1.36E+7 1.29E+2 DBP 6027A 99 Revision 11.0 ODCM l
Table 3-12 R;o' Ground Plane Pathway Dose Factors 2
(m
- mrem /yr per pCi/sec) ;
Nuclide Any Organ Nuchde Any Organ
- Rh-103m -
C-14 - Rh-106 -
Na-24 1.21E+7 Ag-110m 3.47E+9 P-32 - Te-125m 1.55E+6 Cr 51 4.68E+6 Te-127m 9.17E+4 l
Mn-54 1.34E+9 Te-127 3.00E+3 Mn-56 9.05E+5 Te-129m 2.00E+7 l Fe-55 - Te-129 2.60E+4 Fe-59 2.75E+8 Te-131m 8.03E+6 Co-58 3.82E+8 Te-131 2.93E+4 Co-60 2.16E+10 Te-132 4.22E+6 Ni-63 -
I-130 5.53E+6 Ni-65 2.97E+5 I-131 1.72E+7 '
Cu-64 6.09E+5 I-132 1.24E+6 Zn-65 7.45E+8 1-133 2.47E+6 I-134 4.49E+5 Zn-69 - I-135 2.56E+6 l Br-83 4.89E+3 Cs-134 6.75E+9 Br-84 2.03E+5 Cs-136 1.49E+8 Br-85 - Cs-137 1.04E+10 Rb-86 8.98E+6 Cs-138 3.59E+5
. Rb-88 3.29E+4 Ba-139 1.06E+5
' Rb-89 1.21E+5 Ba-140 2.05E+7 Sr-89 2.16E+4 Ba-141 4.18E+4 Sr-90 -
Ba-142 4.49E+4 Sr-91 2,19E+6 La-140 1.91E+7 Sr-92 7.77E+5 La-142 7.36E+5 Y-90 4.48E+3 Ce-141 1.36E+7 Y-91m 1.01E+5 Ce-143 2.32E+6 Y-91 1.08E+6 Ce-144 6.95E+7 Y-92 1.80E+5 Pr-143 -
Y-93 1.85E+5 Pr-144 1.83E+3 Zr-95 2.48E+8 Nd-147 8.40E+6 Zr 2.94E+6 W-187 2.36E+6 Nb-95 1.36E+8 Np-239 1.71E+6 Mo-99 4.05E+6 Tc-99m 1.83E+5 Tc-101 2.04E+4 Ru-103 1.09E+8 Ru-105 6.36E+5 Ru-106 - 4.21E+8 DBP 6027A- 100 Revision 11.0 ODCM
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4.0 SPECIAL DOSE ANALYSES 1 l
' 4.1 DOSES TO THE PUBLIC DUE TO ACTIVITIES INSIDE THE UNRESTRICTED AREA BOUNDARY In accordance with Section 7.2, the Radioactive Effluent Release Report shall include an assessment of radiation doses from radioactive liquid and gaseous effluents to MEMBERS
' OF THE PUBLIC due to their activities inside the UNRESTRICTED AREA BOUNDARY.
In special instances MEMBERS OF THE PUBLIC are permitted access to the radiologically restricted area within the Davis-Besse station. Tours for the public are conducted with the assurance that no individual will receive an appreciable dose (i.e., small fraction of the 40 CFR 190 dose standards).
The Wellness Center, located inside the DBNPS Controlled Area and therefore within the UNRESTRICTED AREA BOUNDARY,is also accessible to MEMBERS OF THE PUBLIC.
Considering the frequency and duration of visits, the resultant dose would be a fraction of the calculated maximum UNRESTRICTED AREA BOUNDARY unrestricted area dose. The dose from airborne effluents and the direct " shine" from the Independent Spent Fuel Storage Installation (ISFSI) are considered. The direct " shine" from normal Plant operation is negligible. This combination is considered the controlling factor when evaluating doses to MEMBERS OF THE PUBLIC from activities inside the UNRESTRICTED AREA BOUNDARY.
For purposes of assessing the dose to MEMBERS OF THE PUBLIC in accordance with Technical Specification 6.9.1.11 and ODCM Section 7.2, the following exposure assumptions may be used:
- Exposure time for maximum exposed visitor user of the Wellness Center of 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> (I h/ day,5 day /wk,50 wk/yr).
- For noble gas dir:ct exposure, default use of the maximum UNRESTRICTED AREA BOUNDARY dispersion from table 3-6. ,
- For Inhalation Pathway, default use of the maximum UNRESTRICTED AREA BOUNDARY dispersion from Table 3-6.
- For Direct " Shine" from the ISFSI, default use of the maximum dose rate for a completed (full) ISFSI, and a distance of 950 feet.
The equations in Section 4.2 may be used for calculating the potential dose to a MEMBER OF THE PUBLIC for activities inside the UNRESTRICTED AREA BOUNDARY. Based on these assumptions, this dose would be at least a factor of 35 less than the maximum UNRESTRICTED AREA BOUNDARY air dose as calculated in Section 3.7.
There are no areas onsite accessible to the public where exposure to liquid effluents could j occur. Therefore, the modeling of Section 2.4 conservatively estimates the maximum l potential dose to MEMBERS OF THE PUBLIC. j l
a
- Based on a maximum conservative estimate.
DBP 6027A 102 Revision 11.0 ODCM
4.2 DOSES TO MEMBERS OF THE PUBLIC - 40 CFR 190 As required by and ODCM Section 7.2, the Radioactive Effluent Release Report shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources (including dose l contributions from effluents and direct radiation from onsite sources). For the likely most l
exposed MEMBER OF THE PUBLIC in the vicinity of the Davis-Besse site, the sources of l exposure need consider only the radioactive effluents and direct exposure contribution from j Davis-Besse. No other fuel cycle facilities contribute significantly to the cumulative dose to a MEMBER OF THE PUBLIC in the immediate vicinity of the site. Fermi-2 is the closest fuel cycle facility located about 20 miles to the NNW. Due to environmental dispersion, any routine releases from Fermi-2 would contribute insignificantly to the potential doses in the vicinity of Davis-Besse.
The correlation of measured plant effluents with pathway modeling of this ODCM provide the primary method for demonstrating / evaluating compliance with the limits specified below (40 CFR 190). However, as appropriate, the results of the environmental monitoring program may be used to provide additional data on actual measured levels of radioactive material in the actual pathways of exposure. ODCM Section 4.2.3 discusses the methodology for correlating measured levels of radioactive material in environmental pathway samples with potential doses. Also, results of the Land Use Census may be used to determine actual exposure pathways and locations.
The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
With the calculated doses from the releases of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Sections 2.4.1,3.7.1, and 3.8.1, evaluations should be
. made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of this Section have been exceeded, if such is the case, in lieu of a 1,icensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190 Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
1 1
DBP 6027A 103 Revision 11.0 ODCM
'Ihis requirement is provided to meet thi dose limitations of 40 CFR Part 190 that have be:n incorporated into 10 CFR Part 20 by 46 FR 18525. The requirement requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the i dose limits of 40 CFR Part 190 if the reactor remains within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment ' ,
to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with -
the exception that the dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If a dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for variance (provided the release conditions resulting in violation of 40 CFR Part 190 ;
have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 l
'and 10 CFR Part 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other dose requirements for dose limitation of 10 CFR Part 20, as addressed in Sections 2.2 and 3.3.1. An individual is not ,
considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is a part of the nuclear fuel cycle.
4.2.1 F1 fluent Dose Calculations For purposes ofimplementing the above requirements of determining the cumulative dose contribution from liquid and gaseous effluents in accordance with Sections 2 and 3 and the reporting requirements of Section 7, dose calculations for Davis-Besse may be performed using the calculaticnal methods contained within this ODCM; the conservative controlling pathways and locations of Table 3-6 or the actual pathways and locations as identified by the Land Use Census may be used. Liquid pathway doses may be calculated using equations in ODCM Section 2.4. Doses due to releases of radioiodines, tritium and particulates are calculated based on equations in Section 3.8.
The following equations may be used for calculating the dose to MEMBERS OF THE PUBLIC from releases of noble gases:
D,, = 3.17E - 08 *
- x / Q
- I(K,
- Q,) (4-1) 8760 and D, = 3.17E -08
- U
- x / Q
- I( (L, + 1.1 M,)
- Q,) (4-2)
DBP 6027A 104 Revision 11.0 ODCM
whare:
Dei
= total body dose due to gamma emissions for noble gas radionuclides (mrem) j D, skin dose due to gamma and beta emissions for noble gas radionuclides
=
(mrem)
U = . duration of exposure (hr/yr, default values in Table 4-1) !
x/Q =. atmospheric dispersion to the offsite location (sec/m')
Qi = ' cumulative release of noble gas radionuclide i over the period ofinterest (pCi)
Ki = total body dose factor due to gamma emissions from noble gas radionuclide i from Table 3-5 (mrem /yr per pCi/m')
i Li = skin dose factor due to beta emissions from noble gas radionuclide i from Table 3 5 (mrem /yr per pCi/m')
Mi = gamma air dose factor for noble gas radionuclide i from Table 3-5 (mrad /yr per pCi/m')
8760 '= hours per year 1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad) 3.17E-08 = 1/3.15E+07 yr/sec Average annual meteorological dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used (e.g., quarterly averages or year-specific annual averages).
4.2.2 Direct Rvnosure Dew Deterrninntion - Onsite Sources Any potentially significant direct exposure contribution from onsite sources to offsite individual doses may be evaluated based on the results of the environmental measurements (e.g., TLD, ion chamber measurements) or by the use of a radiation transport and shielding calculational method. Only during atypical conditions will there exist any potential for significant onsite sources at Davis-Besse that would yield potentially significant offsite doses to a MEMBER OF THE PUBLIC. However, should a situation exist whereby the direct exposure contribution is potentially significant, onsite measurements, offsite measurements and calculational techniques will be used for determination of dose for assessing 40 CFR 190 compliance.
The following simplified method may be used for evaluating the direct dose based on onsite or site boundary measurements:
Dt,0 = D ,0 (Xo,0)* (4-3)
(X t,0)2 DBP 6027A 105 Revision 11.0 ODCM
where:
Da,0 =
direct radiation dose measured at location B (onsite or site boundary) in sector 0
)
Dt,0 = . extrapolated dose at location L in same sector 0 X t,0 = distance to the location L from the radiation source Xa,0 '= distance to location B from the radiation source 1
4.23 Dose Asseccment Bacad on Radinlogical Environmental Monitoring Data Normally, the assessment of potential doses to MEMBERS OF THE PUBLIC must be calculated based on +he measured radioactive effluents at the plant. The resultant levels of radioactive material in the offsite environment are so minute as to be undetectable. The j
. calculational methods as presented in this ODCM are used for modeling the transport in the environment and the resultant exposure to offsite individuals. ;
1 The results of the radiological environmental monitoring program can provide input into the l overall assessment ofimpact of plant operations and radioactive effluents. With measured levels of plant related radioactive material in principal pathways of exposure, a quantitative assessment of potential exposures can be performed. With the monitoring program not identifying any measurable levels, the data provides a qualitative assessment - a confirmatory demonstration of the negligible impact.
Dose modeling can be simplified into three basic parameters that can be applied in using
- environmental monitoring data for dose assessment.
D = C
- U
- DF (4-4) where: -
.D
= dose or dose commitment C = concentration in the exposure media, such as air concentration for the inhalation pathway, or fish, vegetation or milk concentration for the ingestion pathway U = individual exposure to the pathway, such as hr/yr for direct exposure, kg/yr for ingestion pathway DF = dose conversion factor to convert from an exposure or uptake to an individual dose or dose commitment The applicabilit jof each of these basic modeling parameters to the use of environmental monitoring data for dose assessment is addressed below:
- DBP 6027A- 106 Revision 11.0 ODCM
em l
1 Concentration - C _ l l
The main value of using environmental sampling data to assess potential doses to individuals j is that the data represents actual measured levels of radioactive material in the exnosure pathways. This eliminates one main uncertainty in the modeling - the release from the plant and the transport to the environmental exposure medium.
Environmental samples are collected on a routine frequency (e.g., weekly airborne particulate samples, monthly vegetable samples, annual fish samples). To determine the annual average concentration in the environmental medium for use in assessing cumulative dose for the year, an average concentration should be determined based on the sampling frequency and measured levels.
D =I(C,
- t)/365 (4-5) where:
Ci = average concentration in the sampling medium for the year
, Ci = concentration of each radionuclide i measured in the individual sampling medium t = period of time that the measured concentration is considered representative of the sampling medium (typically equal to the sampling frequen_cy; e.g.,7 days for weekly samples,30 days for monthly samples).
If the concentration in the sampling medium is below the detection capabilities (i.e., less than lower limits of detection -LLD), a value of zero should be used for C (Ci = 0).
Fxnosure - U Default exposure values (U) as recommended in Regulatory Guide 1.109 are presented in Table 4-1. These values should be used only when specific data applicable to the environmental pathway being evaluated is unavailable, i
)
4 DBP 6027A 107 Revision i1.0 ODCM I
o Also, the routins radiologicil environmental monitoring progr:m is designed to sample / monitor the environmental media that would provide early indications of any measurable levels in the environment but not necessarily levels to which any individual is exposed. For example, sediment samples are collected in the area of the liquid discharge:
typically, no individuals are directly exposed. To apply the measured levels of radioactivity in samples that are not directly applicable to exposure to real individuals, the approach recommended is to correlate the location and measured levels to actual locations of exposure.
Hydrological or atmospheric dilution factors can be used to provide reasonable correlations of concentrations (and doses) at other locations. The other alternative is to conservatively assume a hypothetical individual at the sampling location. Doses that are calculated in this manner should be presented as hypothetical and very conservatively determined - actual exposure would be much less. Samples collected from nearby wells or actual water supply intake (e.g., Port Clinton) should be used for estimating the potential drinking water doses.
Other water samples collected, such as near field dilution area, are not applicable to this pathway.
Dose Factors - DF The dose factors are used to convert the intake of the radioactive material to an individual dose commitment. Values of the dose factors are presented in NRC Regulatory Guide 1.109.
The use of the Regulatory Guide 1.109 values applicable to the exposure pathway and maximum exposed individual is referenced in Table 4-1.
4.2.4 Use of Environmental TLD for Assessing Doses Due to Noble Gas Releases Thermoluminescent dosimeters (TLD) are routinely used to assess the direct exposure component of radiation doses in the environment. However, because routine releases of radioactive material (noble gases) are so low, the resultant direct exposure doses are also very low. A study
- performed for the NRC concluded that it is possible to determine a plant .
contribution to the natural background radiation levels (direct exposure) of around 10 mrem per year (by optimum methods and high precision data). Therefore, for routine releases from nuclear power plants the use of TLD is mainly confirmatory - ensuring actual exposures are within the expected natural background variation.
For releases of noble gases, environmental modeling using plant measured releases and atmospheric transport models as presented in this ODCM represents the best method of assessing potential environmental doses. However, any observed variations in TLD measurements outside the norm should be evaluated.
- NUREG/CR-0711, Evaluation of Methods for the Determination of X- and Gamma-Ray Exposure Attributable to a Nuclear Facility Using Environmental TLD Measurements, Gail dePlanque, June 1979, USNRC.
- DBP 6027A 108 Revision 11.0 ODCM
Table 4-1 Recommended Exposure Rates in Lieu of Site Specific Data' Table Reference Maximum Exposed for Dose Factors Fvnosure Pathway Age Groun Fvnosure Rates from RG 1.109 Liquid Releases Fish Adult 21 kg/y E-Il Drinking Water Adult 7301/y E-11 Bottom Sediment Teen 67 h/y E-6 Atmosnheric Releases 3
Inhalation Teen 8,000 m /y E-8 Direct Exposure All 6,100 h/y'* N/A (ODCM Table 3-5)
Leafy Vegetables Child 26 kg/y E-13 Fruits, Vegetables & Grain Teen 630 kg/y E-12 Milk - Infant 3301/y E-14 i
i
- Adapted from Regulatory Guide 1.109, Table E-5
' ** Net exposure of 6,100 h/y is based on the total 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> per year adjusted by a 0.7 shielding factor as recommended in Regulatory Guide' l.109. I DBP 6027A 109 Revision 11.0 ODCM
y 5.0 ASSESSMENT OF LAND USE CENSUS DATA' A Land Use Census (LUC) is conducted annually in the vicinity of the Davis-Besse site. This census fulfills two main purposes: 1) meet requirements of TS 6.8.4.e (as required by 10 CFR 50, Appendix 1,Section IV.B.3) for identifying controlling location / pathway for dose assessment of ODCM Section 3.8.1; and (2) provide data on actual exposure pathways for assessing realistic doses to MEMBERS OF THE PUBLIC.
5.1 LAND USE CENSUS REQUIREMENTS A land use census shall be conducted during the growing season at least once per twelve months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricultural authorities. The Land Use Census shall identify within a distance of 8 km (5 miles) the location, in each of the 16 meteorological sectors, of the nearest milk animal, the nearest residence and the nearest 2
garden of greater than 50 m' (500 ft ) producing broad leaf vegetation. This requirement is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the monitoring program are made if required by the results of this census. This census Part 50. Restricting the censussatisfies to gardens ofthe requirements greater than 50 m (500 ftofprovides 2 Section IV.B.3 of App) nd assurance that significant exposure pathways via leafy vegetables will be identified and monitored. A garden of this size is the minimum required to produce the quantity (26 kg/ year) ofleafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a 2
vegetation yield of 2 kg/m ,
The data from the Land Use Census is used for updating the location / pathway for dose assessment and for updating the Radiological Environmental Monitoring Program. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 7.1.
With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Sections 3.8.1, in lieu of a Licensee Event Report, identify the new locations (s) in the next Radioactive Effluent Release i Report, pursuant to Section 7.2. With a Land Use Census identifying a locations (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than that at a location from which samples are currently being obtained in accordance with i Section 6.1, add the new locations (s) if practical (and readily obtainable) to the Radiological I Environmental Monitoring Program within 30 days. The sampling locations (s), excluding the control station location, having a lower calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program. In lieu of a Licensee Event Report and pursuant to Section 7.2, identify the new location (s) in the next Radioactive l Effluent Release Report and also include in the report a revised figure (s) and table for the 1 ODCM reflecting the new location (s).
4 The following guidelines shall be used for assessing the results from the Land Use Census to ensure compliance with this Section.
DBP 6027A 110 Revision 11.0 ODCM i
l g
7 5.1.1 Data Comnilation -
A. Locations and pathways of exposure as identified by the Land Use Census will be compiled for comparison with the current locations as presented in Table 3-4.
B. Changes from the previous year's census will be identified. Also, any location / pathway not currently included in the Radiological Environmental Monitoring Program (Table 6-2) will be identified.
C. Historical, antiual average meteorological dispersion parameters (x/Q, D/Q) for any new location (i.e., location not previously identified and/or evaluated) will be
' determined. All locations should be evaluated against the same historical meteorological data set.
$.1.2 Relative Dose Significance A. For all new locations, the relative dose significance will be determined by applicable pathways of exposure.
B. Relative dose calculations should be based on a generic radionuclide distribution (e.g., Davis-Besse USAR gaseous effluent source term or past year actual effluents).
An 1-131 source term dose may be used for assessmen'. of the maximum organ ingestion pathway dose because of its overwhelming contribution to the total dose
- relative to the other particulates.
C. The pathway dose equations of the ODCM should be used.
5.1.3 ' Data Evaluation -
A. The controlling location used in the ODCM Table 3-4 will be verified. If any location / pathway (s) is identified with a higher relative dose, this location / pathway (s) should replace the previously identified controlling location / pathway in Table 3-4. If the previously identified controlling pathway is no longer present, the current controlling location / pathway should be determined.
B. Any changes in either the controlling location / pathway (s) of the ODCM dose calculations (Section 3.7 and Table 3-4) or the Radiological Environmental (
Monitoring Program (ODCM Section 6.0 and Table 6-2) shall be reported to NRC in accordance with ODCM Section 5.1 and 7.2.
I DBP 6027A 111 Revision 11.0 l ODCM )
i l
~.
5.2 LAND USE CENSUS TO SUPPORT REALISTIC DOSE ASSESSMENT
- The Land Use Census (LUC) provides data needed to support the special dose analyses of ,
Section 4.0. Activities inside the UNRESTRICTED AREA BOUNDARY should be -
periodically reviewed for dose assessment as required by Section 4.1. Assessment of realistic ;
doses to MEMBERS OF THE PUBLIC is required by Section 4.0 for demonstrating compliance with the. EPA Environmental Dose Standard,40 CFR 190 (Section 4.2).
)
l Even though not a part of the LUC, to support these dose assessments, areas within the UNRESTRICTED AREA BOUNDARY that are accessible to the public; and (b) use of Lake Erie water on and near the site are evaluated. The scope of the evaluation includes the following:
- Assessment of areas onsite that are accessible to MEMBERS OF THE PUBLIC.
Particular attention should be give to assessing exposure times for visits to the Davis-Besse Administration Building and Wellness Center. Data should be used for updating Table 4-1.
Data on Lake Erie use should be obtained from local and state officials. Reasonable efforts shall be made to identify individual irrigation and potable water users, and industrial and commercial water users whose source is Lake Erie. This data is used to verify the pathways of exposure used in Section 2.4.
I
)
I DBP 6027A 112 Revision 11.0 ODCM
6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
~
The Radiological Environmental Monitoring Program (REMP) provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the higher potential radiation exposures ofindividuals resulting from the station operations. The sampling and analysis program described in this Section was developed to provide representative measurements of radiation and radioactive materials resulting from
' station operation in the principal pathways of exposure of MEMBERS OF THE PUBLIC.
'Ihis monitoring program implements Sections IV.B.2 of Appendix 1 to 10 CFR Part 50 and thereby supplements the radiological effluent controls by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for the development of this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.
6.1 PROGRAM DESCRIPTION 6.1.1 - General The REMP shall be conducted as specified in Table 6-1. This table describes the minimum environmental media to be sampled, the sample collection frequencies, the number of representative samples required, the characteristics of the sampling locations, and the type and frequency of sample analysis. Table 6-2 provides a detailed listing of the sample locations for Davis-Besse which satisfy the requirements of Table 6-1. Maps for each site listed in Table 6-2 are contained in Appendix C. The specific locations used to satisfy the requirements of Table 6-1 may be changed as deemed appropriate by the Radiation Protection Manager. The changes shall be reported in the Annual Radiological Environmental Operating Report and the Radiological Effluent Release Report as required by Sections 7.1 and 7.2, respectively. If the changes are to be permanent, Table 6-2 and Appendix C shall be updated.
Note: For the purpose ofimplementing Section 5.1, sampling locations will be modified, to reflect the findings of the Land Use Census as described in ODCM Section 5.1.
6.1.2 Pronram Deviations .
With the REMP not being conducted as specified in Table 6-1, in lieu of a Licensee Event Report, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Section 7.1, a description of the reasons for not conducting the program as required and plans for rnventing a recurrence.
6.1.3 Unavailability of Milk or Broad Leaf Vegetation Samnles With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 6-1, identify locations for obtaining replacement samples and if practical add them to the REMP within 30 days. The locations from which samples were unavailable may then be deleted from the monitoring program. In lieu of a Licensee Event Report and pursuant to Section 7.2, identify the cause of the unavailability of samples and
. identify and the new locations (s) for obtaining replacement samples in the next Radiological Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new locations (s).
- DBP. 6027A ' 113 Revision 11.0 ODCM
m 6.1.4 R==mnal Unavailability. Eayinment Malfunctions. Safety Concerns
.With specimens unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons, every effort will be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule will be documented in the Annual Radiological
- Environmental Operating report pursuant to Section 7.1.
6.1.5 Ramnie Analvsis REMP samples shall be analyzed pursuant to the requirements of Table 6-1 and the detection capabilities required by Table 6-3. Cumulative potential dose contributions for the current calendar year from radionuclides detected in environmental samples shall be determined in accordance with the methodology and parameters in this ODCM.
6.2 REPORTING LEVELS 6.2.1 General ne reporting levels are based on the design objective doses of 10 CFR 50, Appendix I (i.e.,
levels of radioactive material in the sampling media corresponding to potential annual doses of 3 mrem, total body or 10 mrem, maximum organ from liquid pathways; or 5 mrem, total body, or 15 mrem, maximum organ for gaseous effluent pathways - the annual limits of Sections 2.4.1,3.7.1 and 3.8.1). Dese potential doses are modeled on the maximum exposure or consumption rates of NRC Regulatory Guide 1.109.
He evaluation of potential doses should be based solely on radioactive material resulting from plant operation.
1 6.2.2 Frea.Aance of Renortina Levels With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 6-4 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, a Special Report that identifies the cause(s) for exceeding the limit (s) and de'ines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to MEMBER OF THE PUBLIC is less than the calendar year limits of Sections 2.4.1,3.7.1 and 3.8.1. When more than one of the radionuclides in Table 6-3 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) + . . 21.0.
reporting level (1) reporting level (2)
When radionuclides other than those in Table 6-4 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Sections 2.4.1,3.7.1 and 3.8.1.
The method described in Section 4.2.3 may be used for assessing the potential dose and required reporting for radionuclides other than those listed in Table 6-4.
DBP 6027A 114 Revision 11.0 ODCM
A special report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
6.3 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an h:terlaboratory Comparison Program that has been approved by the Commission. The requiremet for participating in an approved Interlaboratory Comparison Program is provided to ensere that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 ofAppendix I to 10 CFR Part 50.
A summary of the results obtained as part of the required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 7.1 With analyses not being performed as required, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Section 7.1.
a DBP 6027A 115 Revision 11.0 l ODCM
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TABLE NOTATION
' Specific parameters of distance and direction sector from the centerline of the reactor, and additional description (where pertinent) are provided for each and every sample location in Table 6-2. Refer to
' NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program. In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.11 and Section 7.2, identify the cause of the unavailability of samples for that pathway and identify the new locaticas(s) for obtaining replacement samples in the next Radioactive Effluent Release Report. Also, include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
b One or more instruments, such as a pressurized ion chamber, for measuring and reccrding dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout l for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.
- Airborne particulate sample 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 air particulate samples is greater than ten times the yearly mean of control samples, then gamma isotopic analysis shall be performed on the individual samples.
d Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the facility.
' Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
DBP 6027A 120 Revision 11.0
- l. ODCM
Table 6-2 Required Sampling Locations Appendix C Type of Location Page Reference Location
- Location Description T-1 C-4 1 UNRESTRICTED AREA BOUNDARY,0.6 mile !
ENE of Station.
T-2 C-5 I UNRESTRICTED AREA BOUNDARY,0.9 mile E of Station.
T-3 C-6 I UNRESTRICTED AREA BOUNDARY,1.4 miles ESE of Station near mouth of Toussaint River.
T-4 C-7 I UNRESTRICTED AREA BOUNDARY,0.8 mile S of Station. l T-5 C-8 I Main entrance to site,0.5 mile W of Station.
T-6. C-9 I UNRESTRICTED AREA BOUNDARY,0.5 mile g NNE of Station. I T-7A & B C-10 I Sand Beach,0.9 mile NW of Station. q T-8 C-11 I Farm,2.7 miles WSW of Station.
T-9 C-12 C Oak Ilarbor substation,6.8 miles SW of Station.
T-10 C-13 I UNRESTRICTED AREA BOUNDARY,0.5 mile SSW of Station.
T-11 C-14 C Port Clinton Water Treatment plant,9.5 miles SE of Stetion.
T-12A & B C-15 C Toledo Water Treatment Plant,23.5 miles WNW of Station. Water samples are collected 11.3 miles NW l of site.
T-17 C-16 I UNRESTRICTED AREA BOUNDARY,1.8 mile SSE of Station T-19 C-17 I Farm,1.0 mile W of S:ation T-27A & B C-18 C Crane Creek State Park,5.3 miles WNW of Station.
- I = Indicator locations; C = Control locations.
DBP 6027A 121 Revision 11.0 ODCM
l Table 6-2 Required Sampling Locations Appendix C Type of ;
Location Page Reference Location
- Location Description T-28 C-19 I Davis Besse Water Treatment Plant, onsite.
T-33 C-20 I Lake Erie within a 5-mile radius from Station.
T-35 C-21 C Lake Erie, greater than a 10-mile radius from Station.
T-37 C-22 C Farm,13 miles SW of Station.
UNRESTRICTED AREA BOUNDARY,0.7 mile SE f T-40 C-23 I ofStation.
T-41 C-24 I UNRESTRICTED AREA BOUNDARY,0.6 mile f SSE of Station.
T-42 C-25 I UNRESTRICTED AREA BOUNDARY,0.8 mile SW l of Station.
T-44 C-26 I UNRESTRICTED AREA BOUNDARY,0.5 mile WSW of Station.
T-46 C-27 I UNRESTRICTED AREA BOUNDARY,0.5 mile l NW of Station.
T-47 C-28 I UNRESTRICTED AREA BOUNDARY,0.5 mile N l t ofStation.
T-48 C-29 I UNRESTRICTED AREA BOUNDARY,0.5 mile NE of Station.
T-50 C-30 I Eric Industrial Park Water Treatment Plant,4.5 mile SE of Station.
T-52 C-31 I Farm,3.7 miles S of Station.
T-54 C-32 I Farm,4.8 miles SW of Station.
T-55 C-33 I Farm,4.0 miles W. of Station.
T-67 C-34 I UNRESTRICTED AREA BOUNDARY,0.3 mile l NNW of Station.
l l
1
- I = Indicator locations; C = Control locations.
DBP 6027A 122 Revision 11.0 ODCM
_Y
c Table 6-2 Required Sampling Locations Appendix C Type of Location Page Reference Location
- Location Description T-68 C-35 I UNRESTRICTED AREA BOUNDARY,0.5 miles l WNW of station 1
)
.T-91 C-36 I Siren Post No. I108,2.5 miles SSE of Station.
l T-112 C-37 I State Route 2 and Thompson Road,1.5 miles SSW of i Station. l T-151 C-38 I State Route 2 and Humphrey Road,1.8 miles WNW ;
of Station. !
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- I = Indicator locations; C = Control locations.
' DBP 6027A 123 Revision 11.0 ODCM u
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TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability (with 5% probability of falsely concluding that a blank observation represents a "real" signal).
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si, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),
E is the counting efficiency (counts per transformation),
V is the sample size (in units of. mass or volume),
2.22 is the r. umber of transformations per minute per picoeurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, At is the elapsed time between end of the sample collection period and time of counting.
Typical values of E, V, Y and At should be used in the calculations.
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.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence ofinterfering nuclides, or uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
For more complete discussion of the LLD and other detection limits, see the following:
(1) HASL Procedures Manual, HASL-300 (revised annually).
(2) Currie, L. A, , " Limits for Qualitative Detection and Quanti %tive Determination -
Application to Radiochemistry" Anal. Chem. 40. 586-93 (1968).
DBP 6027A 125 Revision 11.0 ODCM
Table 6-3 (Continued)
TABLE NOTATION (3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques", Atlantic Richfield Hanford Company Report ARH-2537 (June 22,1972).
- b. LLD for drinking water,
- c. If no drinking water p thway exists, a value of 3000 pCi/ liter may be used.
- d. LLD only when specific analysis for 1 131 required.
1 l
l DBP 6027A 126 Revision 11.0 ODCM
______________o
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o 7.0 ADMINISTRATIVE CONTROLS l l
7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l
Routine Radiological Environmental Operating reports covering the operation of the umt during the previous calendar year shall be submitted prior to May 1 of each year. The initial
. report shall be submitted prior to May 1 of the year following initial criticality.
The Annual Radiological Environmental Operating Report 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 the preoperational studies, with operational controls, as appropriate, and with previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results ofland use censuses as required in Section 5.1.
The Annual Radiological Environmental Operating Reports shall include the summarized and j tabulated results of analysis of radiological environmental samples and of radiation measurements taken during the period pursuant to the locations specified in Sections 6.1 and Appendix C of this ODCM. 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 i l
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 covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results ;
oflicensee participation in the Interlaboratory Comparison Program, required by Section 6.3; and discussions of all analyses in which the LLD required by Table 6-3 was not achievable.
7.2 RADIOACTIVE EFFLUENT RELEASE REPORT Radioactive Effluent Release Reports covering the operation of the unit during the previous 12 months of operation shall be submitted no later than 12 months from the submittal of the previous report.
The Radioactive Effluent Release Reports (RERR) shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
DBP 6027A 128 Revision 11.0 C-1 ODCM
p The RERR shall include an canual summary of hourly meteorological data collected over the previous year. 'Ihis annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the fonn ofjoint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the UNRESTRICTED AREA BOUNDARY during the reporting period.
All assumptions used in making these assessments, i.e., specific activity, exposure time, and location, shall be included in these reports. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in this ODCM.
The RERR shall also include an assessment of radiation doses to the likely most exposed MEMBFR OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation."
The RERR shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:
- a. container volume,
- b. total curie quantity (specify whether determined by measurement or estimate),
- c. principal radionuclides (specify whether determined by measurement or estimate),
- d. source of waste and processing employed (e.g., dewatered spent resin, compressed dry waste, evaporator bottoms),
- e. type of container (e.g., Type A, Type 3, Large Quantity), and
- f. solidification agent or absorbent (e.g., cement, urea formaldehyde).
The RERR shall include a list and description of unplanned releases from the site to .
UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The RERR shall include any changes made during the reporting period to the PROCESS l CONTROL PROGRAM (PCP) and to the ODCM, as well as a listing of new locations for i dose calculations and pursuant to Section 5.1.
I The RERR shall include any radionuclide activity limits for the BWST and PWST which have been exceeded during the reponing period, a description of the event leading to the limit being exceeded and action taken to return it to within the limits.
DBP 6027A 129 Revision i1.0 ODCM
g
. 7.3 SPECIAL REPORTS Special Reports shall be submitted to the U. S. Nuclear Regulatory Commission (NRC) in i accordance with 10 CFR 50.4 within the time period specified for each report. These reports !
shall be submitted covering the activities identified below pursuant to the requirements of the I
applicable reference:
- a. dose or dose commitment exceedences to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS
.(Section 2.4.1),
- b. ~ the discharge of radioactive liquid waste without treatment and in excess of the limits in Section 2,
- c. the calculated air dose from radioactive gases exceeding the limits in Section 3.7.1, d.- the calculated dose from the release ofiodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous efiluents exceeding the limits of Section 3.8.1,
- c. the discharge of radioactive gaseous waste without treatment and in excess of the limits in Section 3.9,
- f. the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding the limits of Section 4.2, and
- g. the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 6-4 (Section 6.2.2). l 7.4 MAJOR CHANGES TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS Licensee initiated major changes to the radioactive waste systems (liquid and gaseous):
- 1. Shall be reported to the Commission in the update to the Safety Analysis Report. The discussion of each change shall contain:
- a. a summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59; b, sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
- c. a detailed description of the equipment, components and processes involved and the interfaces with other plant systems;
- d. an evaluation of the change which shows the predicted releases of radioactive materials in liquid or gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; DBP 6027A 130 Revision 11.0 ODCM
7
- e. an evaluation of the change which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and the general population that differ from those previously estimated in the license application and amendments thereto;
- f. a comparison of the predicted releases of radioactive materials in liquid and l' gaseous effluents to the actual releases for the period prior to when the changes are to be made;
- g. an estimate of the exposure to plant operating personnel as a result of the change; and
- h. documentation of the fact that the change was reviewed and found acceptable by the Station Review Board.
- 2. Shall become effective upon review and acceptance by the Station Review Board.
7.5 DEFINITIONS 7.5.1 BATCH RELEASE - The discharge ofliqvid wastes of a discrete volume.
7.5.2 CHANNEL CALIBRATION - A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shell encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL ,
CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
7.5.3 _ CHANNEL CHECK - A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels monitoring the same parameter.
7.5.4 CHANNEL FUNCTIONAL TEST - A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog Channels - The injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
- b. Bistable Channels - The injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions.
7.5.5' COMPOSITE SAMPLE - A sample in which the method of sampling employed results in a specimen which is representative 4the liquids released.
7.5.6 GASEOUS RADWASTE TP2ATMENT SYSTEM - The GASEOUS RADWASTE
-TREATMENT SYSTEM is a system that is designed and installed to reduce radioactive l gaseous effluents by collecting primary coolant system off gases and providing for decay for j the purpose of reducing the total radioactivity prior to release to the environment. !
I i
DBP 6027A 131 Revision 11.0 ODCM 1
l:'
7.5.7 LOWER LIMIT OF DETECTION (LLD)- He LLD is the sm:llest concentration of radioactive material in a sample that will be detected with 95% probability, with 5%
. probability of falsely concluding that a blank observation represents a "real" signal, il For a particular measurement system (which may include radiochemical separation):
4.66 Sb l LLD =
l E
- V
- 2.22
- Y
- exp(-AAt) l where l
LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);
1 Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute);
E is the counting efficiency (as counts per transformations);
l V is the sample size ( in units of mass or volume);
2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radionuclide; and At for plant effluents is the elapsed time between the midpoint of sample collection and time ofcounting.
It should be recognized that the LLD is defined as an a prioIi(before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
7.5.8 MEMBER OF THE PUBLIC - MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. His category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who l enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreation, occupational, or other purposes not associated with the plant.
7.5.9 OPERABLE - OPERABILITY - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified I function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary devices to perform its function (s), are also capable of performing their related support functions (s).
DBP 6027A 132 Revision 11.0 ODCM l-
7.5.10 PURGE-PURGING - PURGE OR PURGING is the controlled process of discharging eir or gas from a coni'mement 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.
7.5.11 UNRESTRICTED AREA BOUNDARY - The UNRESTRICTED AREA BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
7.5.12 SOURCE CHECK - A SOURCE CHECK shall be the observation of channel upscale response when the channel sensor is exposed to a radioactive or LED source.
7.5.13 UNRESTRICTED AREA - An UNRESTRICTED AREA shall be any area at or beyond the UNRESTRICTED AREA BOUNDARY, access to which is not controlled by the licensee for purposes of protection ofindividuals from exposure to radiation or radioactive materials, or
- any area within the UNRESTRICTED AREA BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. The definition of UNRESTRICTED AREA used in implementing the Radiological Effluent Technical Specifications has been expanded over that in 10 CFR 100.3(a), but the unrestricted area does not include areas over water bodies. The concept of unrestricted areas, established at or beyond the UNRESTRICTED AREA BOUNDARY, is utilized in the Technical Specifications and the ODCM to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable, pursuant to 10 CFR 50.36a.
7.5.14 VENTILATION EXHAUST TREATMENT SYSTEM - A VENTILATION EXHAUST TREATMENT SYSTEM is a system that is designed and installed to reduce radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through HEPA filters for the purpose- of removing particulates from the gaseous exhaust stream prior to release to the environment. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
7.5.15 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.
j DBP 6027A 133 Revision 11.0 ODCM c __- _ - _ _ - _ _ _ _ _ _ _ -
r:
i APPENDIX A Technical Basis for Simplified Dose Calculations Liquid Effluent Releases i
i i
DBP 6027A A-1 Revision 11.0 ODCM
APPENDIX A-Technical Basis for Simplified Dose Calculations Liquid Effluent Releases Overview To simplify the dose calculation process, it is conservative to identify a controlling, dose-significant radionuclide and to use its dose conversion factor in the dose calculations. Using the total release (i.e., the cumulative activity of all radionuclides) and this single dose conversion factor as inputs to a one-step dose assessment yields a dose calculation method which is both simple and conservative.
Cs-134 is the controlling nuclide for the total body dose. It has the highest total body dose conversion factor for all the radionuclides listed in Table 2-6. Therefore, the use ofits dose conversion factor in the simplified dose assessment method for evaluating the total body dose is demonstrably conservative.
The selection of the maximum organ dose conversion factor for use in the simplified calculation requires consideration of the prevalence of the radionuclides in the effluents. An examination of the Table 2-6 factor will show that the Nb-95 dose factor for the GI LLI represents the highest value (1.51E+06 mrem /hr per Ci/ml); and the P-32 bone factor (1.39E+06)is similarly high. However, neither of these two radionuclides are of significance in the Davis-Besse effluents. Nb-95 is not typically measured in the liquid effluents and P-32 analyses are not even performed. (NRC has categorically determined that P-32 is not a significant radionuclide in liquid effluents from nuclear power plants and does not require the special radiochemical analyses needed for identification and quantification.) The next highest dose conversion factor is for Cs-134, liver, with a value of 7.1lE+05 mrem /hr per pCi/ml. Cs-134 is a prevalent radionuclide in the liquid effluents from Davis-Besse. Therefore, it is recommended that the Cs-134 liver dose conversion factor be used for the simplified maximum organ dose assessment.
Simnlified Method For evaluating compliance with the dose limits of Section 2.4.1, the following simplified equationi.
may be used:
Total Body D. = 1.67E - 02 ,
- VOL
- Ac c,-u4.e> *IC, (A-1) i DBP 6027A - A-2 Revision 11.0 ODCM
wher::
-D ib -
dose to the total body (mrem)
.VOL' = volume ofliquid effluents released (gal)
DF. =. average Collection Box release flow (gal / min)
~Z = 10, near field dilution
' A<c..i 34,td>
=-- 5.81E+05 mrem /hr per pCi/ml, the total body ingestion dose factor for Cs-134 -
IC; = total concentration of all radionuclides ( Ci/ml)
"1.67E-02 = 1 hr/60 min Substituting the values for Z and the Cs-134 total body dose conversion factor, the equation simplifies to:
D. = 9.70 E + 02
- VOL
- EC, (A-2)
DF Maximum Organ
~
- D rnax ~~
- A(Cs-134, liver) *IC I (A-3) g7 where:
D ,x = maximum organ dose (mrem)
= 7.1lE+05 mrem /hr per pCi/ml, the liver ingestion dose factor for Cs-134 A tc.-134.tiva)
Substituting the values for Z and the Cs-134 liver dose conversion factor, the equation simplifies to:
- IC' (A-4)
D""' ~ =
DF Tritium should not be included in the simplified analysis dose assessment for liquid releases, The
. potential dose resulting from normal reactor releases of11-3 is relatively negligible. But, its relatively
' higher abundance would yield resulting simplified doses that would be overly conservative and unrealistic. Excluding tritium has essentially no impact on the conservative use of this recommended simplified method. Furthermore, the release of tritium is a function of operating history and is essentially unrelated to radwaste system operations.
A-3 : Revision 11.0 DBP 6027A :
ODCM 7
nr APPENDIX B T:chnical Basis for Effective Dose Factors 1 Gaseous Radwaste Effluents i
l 1
(
l i
l DBP 6027A B-1 Revision 11.0 ODCM
APPENDIX B Technical Basis for Effective Dose Factors Gaseous Radwaste Effluents-l
)
Overview i i
Dose evaluations for releases of gaseous radioactive effluents may be simplified by the use of an i effective dose factor rather than radionuclide-specific dose factors. These effective dose factors are applied to the total radioactive release to approximate the various doses in the environment; i.e., the total body, gamma-air, and beta-air doses. The effective dose factors are based on the typical radionuclide distribution in the gaseous radioactive effluents. The approach provides a reasonable estimate of the actual doses since under normal operating conditions, minor variations are expected in the radionuclide distribution.
, Determination of Effective Dose Fagigts Effective dose factors are calculated by equations (B-1) through (B-4).
K,y = I(Ki
- f,) (B-1) where:
Kerr
= the effective total body dose factor due to gamma emissions from all noble gases released (mrem /yr per pCi/m3 ),
K. i
= the total body dose factor due to gamma emissions from each noble gas radionuclide released, from Table 3-5 (mrem /yr per pCiim3), and f,
i
= the fractional abundance of noble gas radionuclide i relative to the total noble gas activity.
. (L + 1.1 M),, = I((L i, + 1.1Mi ) *f)i (B-2) where:
(L+1.1M) err = the effective skin dose factor due to beta and gamma emissions from all noble gases released (mrem /yr per pCi/m3), and
- (Li +1.1Mj) = _ the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released, from Table 3-5 (mrem /yr per pCi/m3 ),
M,g = I(Mi
- f,) (B-3) w DBP 6027A B-2 Revision 11.0 ODCM f
u where:
- M,g = the effective air dose factor due to gamma emissions from all noble gases released (mradlyr per pCi/m'), and M, = the air dose factor due to gamma emissions from each noble gas radionuclide i released, from Table 3-5 (mrad /yr per pCi/m',
N,y =I(Ni
- f,) (B-4)
- where
N,g = the. effective air dose factor due to beta emissions from all noble gases j released (mrad /yr per pCi/m'), and )
i Ni = the air dose factor due to beta emissions from each noble gas radionuclide i released, from Table 3-5 (mrad /yr per pCi/m'). l
. I Normally, past radioactive effluent data would be used for the determination of the effective dose factors. However, the releases of noble gases from Davis-Besse have been exceedingly insignificant.
Therefore, in order to ensure overall conservatism in the modeling, the USAR estimate of radionuclide concentrations at the UNRESTRICTED AREA BOUNDARY (summarized in Table
' B-1) has been used as the initial typical distribution. The effective dose factors derived from this distribution are presented in Table B-2.
Annlication To provide an additional degree of conservatism, a factor of 2.0 is introduced into the dose calculation when the effective dose factor is used. This conservatism provides additional assurar:ce that the evaluation of doses by the use of a single effective dose factor will not significantly underestimate any actual doses in the environment.
' For evaluating c ampliance with the dose limits of Tedmical Specification 3.11.2.2 the following i simplified equa+ ions may be used:- 4 1
DL = 2.0
- 3.17E - 08
- x / Q
- M,y
- IQ, (B-5) and Dp = 2.0
- 3.17E- 08
- x / Q
- N,y
- IQ, (B-6)
DBP 6027A' . B-3 Revision 11.0 ODCM
where:
DA. = . air dose due to gamma emissions for the cumulative release of all noble gases (mrad),
Dp = air dose due to beta emissions for the cumulative release of all noble gases (mrad),
x/Q = atmospheric dispersion to the controlling unrestricted area boundary (sec/m'),
M,g = 5.7E+02, effective gamma-air dose factor (mrad /yr per pCi/m'),
3
' N,g = 1.lE+03, effective beta-air dose factor (mrad /yr per pCi/m ),
Qi = cumulative release for all noble gas radionuclides ( Ci),
3.17E-08 = conversion factor (yr/sec), and 2.0 = conservatism factor to account for the variability in the effluent data.
Combining the constants, the dose calculation equations simplify to:
DA = 3.61E- 05
- x / Q
- IQ, (B-5)
.and Dp = 7.20E - 05
- x / Q
- IQi (B-6)
The effective dose factors are used for the purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods when the computer or ODCM software may be unavailable to perform a detailed dose assessment.
DBP 6027A . B Revision 11.0 ODCM
m Table B-1 Default Noble Gas Radionuclide Distribution
- of Gaseous Effluents Fraction of Total (A/i E A;)
Containment Station . Waste Gas Nuclide Vessel Purge Vent Decav Tank IQtal Ar 0.0003 0.004 0.004 0.003 Kr-RS 0.12 0.012 0.034 0.06 Xe-131m 0.02 0 009 0.008 0.017 I Xe-133m 0.005 0.011 0.011 0.008 I Xe-133 0.86 0.94 0.92 0.83 j
' Xe-135m -- 0.004 0.0034 0.06 Xe-135 ' QA02 DA2 042 DA21 Total LQ .LQ LQ .LQ i
I I
NOTE:
- Data adapted from Davis-Besse USAR Section 11.3, Table 11.3-13 and Table 11.3-14. Kr-83m, Kr-85m, Kr-87, Kr-88 and Xe-138 have been excluded because of their negligible fractional abundance (i.e., < 1%).
DBP 6027A - B-5 Revision 11.0 ODCM
Table B-2 Effective Dose Factors - Noble Gas Effluents Skin Dose Total Body Factor' Gamma Air Beta Air Isotope Fractional Dose Factor (L+1.1M,g) Dose Factor Dose Factor l Abundance K,g(mrem /yr (nuem/yr per Men (mrad /yr N,g(mrad /yr 3 3 3 3 per pCi/m ) pCi/m ) per pCi/m ) per pCi/m )
Ar-41 0.003 2.65E+01 3.87E+01 2.79E+01 9.84E+00 Kr-85 0.06 9.96E-01 8.15E+01 1.03 E+00 1.17E+02 Xe-131m 0.017 1.55E+00 1.10E+01 2.65E+00 1.88E+01 Xe-133m 0.008 2.00E+00 1.08E+01 2.61 E+00 1.18E+01 Xe-133 0.83 2.44E+02 5.76E+02 2.93E+02 8.72E+02 ,
Xe-135m 0.06 1.87E+02 2.64E+02 2.02E+02 4.43E+01 <
Xe-135 0.02 3.62E+01 ' 7.94E+02 4.03E+01 5.16E+01 TOTAL 1.0 4.98E+02 9.89E+02 5.69E+02 1.12E+03 DBP 6027A ' B-6 Revision i1.0 '
F-APPENDIX C Radiological Environmental Monitoring Program Sample Location Maps l
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DBP 6027A C-1 Revision 11.0 ODCM
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