ML20140D948
| ML20140D948 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/09/1997 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20140D936 | List: |
| References | |
| PROC-970409, NUDOCS 9704250005 | |
| Download: ML20140D948 (194) | |
Text
.
e' DAVIS-BESSE OFFSITE DOSE CALCULATION MANUAL Revision 10.0 Approval:
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TABLE OF CONTENTS
1.0 INTRODUCTION
1 2.0 LIQUID EFFLUENTS.
2 2.1 Radiation Monitoring Instrumentation and Controls.
2 2.1.1 Required Monitors.
3 2.1.2 Non-Required Monitors.
4 2.2 Sampling and Analysis of Liquid Effluents.
5 2.2.1 Batch Releases 5
2.2.2 Continuous Releases.
6 2.2.3 Condensate Demineralizer Backwash.
7 2.2.4 Borated Water Storage Tank and Primary Water Storage Tank.
7 2.3 Liquid Effluent Monitor Setpoints.
9 2.3.1 Concentration Limits.
9 2.3.2 Basic Setpoint Equation.
9 2.3.3 Liquid Radwaste Effluent Line Monitor Setpoint Calculations (RE-1770A & B, RE-1878A & B) 9 2.3.4 Storm Sewer Drain Monitor (RE-4686) 12 2.3.5 Alarm Setpoints for the Non-Required Radiation Monitors 12 2.2.6 Alarm Response - Evaluating Actual Release Conditions.
13 2.4 Liquid Effluent Dose Calculation - 10 CFR 50 15 2.4.1 Dose Limits to MEMBERS OF THE PUBLIC.
15 2.4.2 MEMBER OF THE PUBLIC DOSE - Liquid Effluents.
16 2.4.3 Simplified Liquid Effluent Dose Calculation 18 1
2.4.4 Contaminated TBS /SSD System - Dose Calculation.
19 2.5 Liquid Effluent Dose Projections.
20 3.0 GASEOUS EFFLUENTS 35 3.1 Radiation Moritering Instrumentation and Controls 35 3.1.1 Alarm and Automatic Release Termination.
36 3.1.2 Alarm Only 37 3.2 Sampling and Analysis of Gaseous Effluents 38 3.2.1 Batch Releases 38 3.2.2 Continuous Felease.
38 3.2.3 Releases Result ing f rom Primary-to-Secondary System Leakage 39 3.3 Gaseous Effluent M niter Setpoint Determination.
40 3.3.1 Total Effectave Dose Equivalent Limits 40 3.3.2 Release Rate Limits 40 3.3.3 Individual Release Radiation Monitor Setpoints.
41 3.3.4 Conservative. Generie Radiation Monitor Setpoints 42 3.3.5 Release Flow Rate Evaluation for Batch Releases.
42 DBP 6027A v
Revision 10.0 ODCM
e TABLE OF CONTENTS (Continued)
(3.0 GASW.US EFFLUENTS - continued) 3.4 Ur. restricted Area Boundary Dose Rate Calculation -
Noble Gas.
45 3.5 Unrescricted Area Boundary Dose Rate Calculation -
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Radiciodine, Tritium, and Particulates 46 3.5.1 Dose Rate Calculation.
46 4
3.5.2 Simplified Dose Rate Evaluation for Radioiodine, Tritium and Particulates.
46 3.6 Quantifying Activity Released.
47 3.6.1 Quantifying Noble Gas Activity Releabed Using Station Vent Monitor (RE-4598).
47 3.6.2 Quantifying Noble Gas Activity Released Using A Grab Sample.
48 3.6.3 Quantifying Radiciodine, Tritium, and Particulate Activity Released.
49 i
3.7 Noble Gas Dose Calculations - 10 CFR 50 50 3.7.1 UNRESTRICTED AREA Dose - Limits.
50 3.7.2 Dose Calculations - Noble Gases.
51 3.7.3 Simplified Dose Calculation for Noble Gases.
52 3.8 Radiciodine, Tritium and Particulate Dose Calculations -
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10 CFR 50 53 3.8.1 UNRESTRICTED AREA Dose Limits 53 3.8.2 Critical Pathway.
54 3.8.3 Dose calculations - Radioiodine, Tritium and Particulates.
55 0
3.8.4 Simplified Dose Calculation for Radiciodine, Tritium and Particulates 56 3.9 Gaseous Effluent Dose Projection 57 4.0 SPECIAL DOSE ANALYSES.
100 4.1 Doses To The Public Due To Activities l
Inside the UNRESTRICTED AREA BOUNDARY,
100 4.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 101 4.2.1 Effluent Dose ' Ca'fculations.
102 4.2.2 Direct Exposure Dose Determination -
Onsite Sources.
104 4.2.3 Dose Assessment Based on Radiological j
Environmental Monitoring Data 104 4.2.4 Use of Environmental TLD for Assessing Doses Due to Noble Gas Releases 106 i
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l DBP 6027A vi Revision 10.0 ODCM
s TABLE OF COMTEIrfS (Continued) 5.0 ASSESSMB3rr OF IJulD USE CENSUS DATA.
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5.1 Land Use Census Requirements.
109 i
5.1.1 Data Compilation.
110
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5.1.2 Relative Dose Significance.
110 5.1.3 Data Evaluation.....
110 5.2 Land Use Census to Support Realistic Dose Assessment 111 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 112 6.1 Program Description.
112 6.1.1 General.
112 6.1.2 Program Deviations.
112 6.1.3 Unavailability of Milk or Broad Leaf Vegetation Samples.
113 6.1.4 Seasonal Unavailability, Equipme.nt Malfunctions, 113 Safety Concerns 6.1.5 Sample Analysis.
113 6.2 Reporting Levels 113 6.2.1 General.
113 6.2.2 Exceedance of Reporting Levels.
114 6.3 Interlaboratory Comparison Program 114 7.0 ADMINISTRATIVE CONTROLS 127 7.1 Annual Radiological Environmental Operating Report 127 a
7.2 Radioactive Effluent Release Report 127 7.3 Special Reports 129 7.4 Major Changes to Radioactive Liquid and Gaseous 129 Waste Treatment Systems.
7.5 Definitions 130 7.5.1 Batch Release 130 1
7.5.2 Channel Calibration.
130 7.5.3 Channel Check 130 7.5.4 Channel Functional' Test 130 7.5.5 Composite Sample.
131
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7.5.6 Gaseous Radwaste Treatment System.
131 7.5.7 Lower Limit of Detection (LLD).
131 7.5.8 Member of the Public.
132 7.5.9 Operable - Operability.
132 7.5.10 Purge-Purging.
132 7.5.11 Unrestricted Area Ecundary 132 7.5.12 Source Check 132 7.5.13 Unrestricted Area.
132 7.5.14 Ventilation Exhaust Treatment System.
132 7.5.15 Venting.
133 DBP 6027A vii Revision 10.0 ODCM I
s APPENDICES APPENDIK A -
Technical Basis for Simplified Dose Calculations, A-1 i
Liquid Effinant Releases.
APPENDIX B -
Technical Bat:is for Effective Dose Factors Gaseous Effluent Releases.
B-1 APPENDIX' C -
Radiological Enviran=antal Monitoring Program, Sample Location Maps.
C-1 LIST OF TABLES Table 2 Radioactive' Liquid Effluent Monitoring Instrumentation 22 Table 2 Radicactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.
24 Table 2 Radioactjve Liquid Waste Sampling and Analysis Program.
26 Limiting Radionuclide Concentrations in Secondary Side Table 2-4 Clean-up Resins for Allowable Discharges to Onsite Settling Basin.
29 Table 2 Radionuclide Activity Limits for the BWST and PWST.
30 Table 2 Liquid Ingestion Dose Committment Factors.
31 Table 2 Bioaccumulation Factors.
33 Table 3 Radioactive Gaseous Effluent Monitoring Instrumentation.
59 Table 3 2 -
Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 62 0
Table 3 Radioactive Gaseous Waste Sampling and Analysis Program.
64 Table 3 Land Use Census Summary.
67 Table 3 Dose Factors for Noble Gases 68 Table 3 Exposure Pathways. Controlling Parameters, and Atmospheric Dispersion for Dose Calculations.
69 70 Table 3 Inhalation Pathway Dos _e Factors.
Table 3 Grass -. Cow - Milk Pathway Dose Factors.
78 Table 3 Grass - Cow - Meat Pathway Dose Factors 86 92 Table 3 Vegetation Pathway Dose Factors Table 3 Ground Plane Pathway Dose Factors.
98 Table 4 Recommended Exposure Rates in Lieu of 108 Site Specific Data.
DBP 6027A viii Revision 10.0 CDCM
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(List of Tables - Cont.)
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Table 6 Radiological Envi m atal Monitoring Program.
115 Table 6 Required Sampling Locations.
120 Table 6 Lower Limits of Detection...
123 Table 6 Reporting Levels for Radioactivity concentrations in Environmental samples.
126 Table B Default Noble Gas Radionuclide Distribution of Gaseous Effluents B-5 Table B gffective Dose Factors - Noble Gas Effluents B-6 LIST OF FIGURES Liquid Radioactive Effluent Monitoring and Figure 2-1 Processing Diagram 34 Figure 3 1 Gaseous Radioactive Effluent Monitoring and Ventilation Systems Diagram.
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i DBP 6027A ix Revision 10.0 l
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1.0 INTRODUCTION
The Davis-Besse Offsite Dose Calculation Manual (ODCH) describes the methodology and parameters used, ins, 1) determining the radioactive material rel' esse rates and i
cumulative _ releases:
2) calculating the radioat tive liquid and gaseous effluent monitoring instrumentation alarm / trip setpointss_and 3) calculating the corresponding dose rates and cumulative 1
quarterly and yearly ~ doses.
The ODCM also describes and providge requirements for the Radiological Environmental Monitoring Program. Sampling locations, media and collection frequencies, and analytical requirements are specified, The i
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 e
Technical Specifications (TS) 6.8.4.d and 6.8.4.e.
l The exposure pathway and dose modeling prescated provides estimates (e.g.,
calculational results) that are conservative (i.e., higher than actual exposures in the environment). This conservatism does not invalidate the j
modeling since the main purpose of these calculations 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 I
demonstrating compliance with the EPA environmental dose standard for the Uranium Fuel Cycle (40 CFR 190), more realistic dose assessment modeling may be used.
The ODCM will be maintained for use as a reference guide and iraining 0I document of accepted methodologies and calculations. Changes to the ODCM i
calculational methodologies and parameters will be made as necessary to ensure reasonable conservatism in keeping with the principles of j
10 CFR 50. Appendix 1.Section III and IV.
Questions about the ODCM 3
should be directed to the Manager - Radiation Protection.
NOTE:
Throughout this document, words appearing all capitalized denote definitions specsf2ed in Section 7.5 of this manual, or common acronyms.
Section 2.0 describes equipment for monitoring and controlling liquid effluents. sampling requirementti and dose evaluation methods. Section 3.0 provides similar informatsen on gaseous effluent controls, sampling, and dose evaluation.
Secticn
.0 describes special dose analyses required for Regulatory Guide 1.21. Annual Effluent Reporting and EPA Environmental Dose Standard of 40 CFR lot.
Section 5.0 describes the role of the annual land use census in identifvang the controlling pathways and locations of exposure for assessing the petential offsite doses. Section 6.0 describes the Padtological Environmental Monitoring Program. Section 7.0 describes 4
the environmental, effluent and special reporting requirements, procedural I
requirements for major changes to liquid and gaseous radwaste systems, and definitions.
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l 2.0 LIQUID EFFLUENTS 2.1 RADIATION MONI'IDRING INSTRUMDITATION AND CONTROLS This section sunenarizes iaformation on the liquid offluent radiation monitoring instrumentatien and controls. More det' ailed infonnation is provided in the Davis-Besse USAR, Section 11.2, Liquid Waste Systems, and associated design drawings from which this summary was derived. Location and control function of tks 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. The radioactive liquid effluent monitoring instrumentation channels listed in Table 2-1 shall be OPERABLE with their alarm / trip setpoints set to ensure the limits specified in Section 2.3.1 are not exceeded.
Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL 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 0
is acceptably conservative.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the actions described in Table 2-1.
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.
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2.1.1 Reauired Monitors
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This section describes the monitoring required during iquid releases and the backup sampling required when monitors are inoperable.
A)
Alarm and Automatic Release Term 4 nation' i.
Clean Radwaste Effluent Monitors (RE-1770 A & B)
Discharges from the Clean Radwaste Monitor Tanks (2) are acnitored 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 systen is capable of initiating 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 Radweste 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 grost 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 of initiating an alarm and automatic termination of the release by closing valve WM-1876.
Setpoint determination for the alarms is discussed in Section 2.3.
O b)
Alarm (on1v) 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 radioactivity, 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 f rom Storm Sewer drains. Evaluation of the alarm setpoint for RE-4686 is discussed in Section 2.3.4.
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c)
Flow Rate Measurine Devices 1.
Clean Radwaste Effluent Line Flow Indicator (FI) 1700 A & B Flow Totaliser (FQI) 1700 A & B ii. Miscellaneous.Radwaste Effluent Line Flow Indicator (FI) 1887 A & B Flow Totalizer (FQI) 1887 A & B s
iii. Dilution Flow to the Collection Box l
Computer Point F201 consists of four points:
o F147 Cooling Tower Blowdown o
A890 Service Water Outflow o
F250 Collection Bay Dilution Flow I
o F886 Unit Dilution Pump Flow 2.1.2 Non-Recuired 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
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j station effluent to the lake, Component Cooling Water System (CCWS) (RE-1412 & 1413)-monitors the CCWS return lines. High alarm closes the atmospheric vent valves on the CCWS surge tank, 1
Service Water System (SWS) (RE-8432) - off-line detector-monitors the SWS outlet prior to discharge to the Collection Box, and Intake Forebay.(RE-8434) - monitors the station intake water from Lake Erie.
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I 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 l
identifies three potential sources of liquid radioactive effluents. A fourth pctential release point from the Turbine Bdilding Sump is j
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.
2.2.1 Batch Releases l
BATCH RELEASE is defined as the discharge of liquid 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 emitters.
Once per month, as a minimum, analysis of one sample from a BATCH RELEASE 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 of 11guid discharged.
l Once per quarter, analysis of a COMPOSITE SAMPLE of all releases that quarter 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 garra spectral analysis performed on all liquid radwaste effluents. Therefore, the Table 2-3 re qui r ement for sampling and analysis of one batch per month for noble gases need not be performed as a separate prdgram.
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2.2.2 Continuous Emleases l~
Releases from the Turbine Building susp (Tas) and storm sewer Drains (asD) are classified as continuous releases.
Because the Turbine Building susp discharges'may contain minute l
concentrations of radionuclides due to primary-to-secondary system 1eakage, the Turbine Building sump disclarges are routed to the onsite settling Basins instead of the 880 line. Overflow from the settling Basins is pusped to the collection Box where it is mixed with dilution flow and released to Lake Erie. Releases via this l
pathway are monitored by weekly analysis for principal gamma-emitting
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radionuclides and tritium, and by quarterly analysis of composite samples for Fe-55, Sr-89 and ar-90.
1 Discharges to the Storm Sewer Drains are from Turbine Building drains
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that are not routed to the TBS and from storm drains. The Storm j
Sawer discharges to the Training Center Pond with the overflow i
discharging to the Toussaint River. For conservatism, it is assumed I
that radioactive material released to the Training Center Pond is ultimately discharged to Lake Erie (unless actions are taken to i
prevent this occurrence).
j Grab samples are collected weekly from the settling Basins and analyzed by gamma spectroscopy. If activity is identified, additional controls are enacted to ensure that the release concentrations are maintained below Effluent Concentration Limits and that the 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:
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1 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.
1 Compare the measured radionuclide concentrations in the sample with EC (equation 2 2) to ensure releases are within the limits.
Btsed on the measured concentrations, a re-evaluation of the alarm setpoint for the SSD monitor (RE-4686) may be performed as epecified in Section 2.3.4.
Consider each sample representative of the releases that have occurred since the previous sample. Determine the volume of liquid released from the Turbine Building Sump based on the Turbine Building Surp 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.
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W 2.2.3
"-==te w a=rm11 mar
==d-==h Discharges from the condensate Domineraliser Backwash Receiving Tank (RAT) to the south settling Basin are sampled in accordance with Table 2-3.
samples are collected prior to each release of the l
resin / water slurry and separated into the liciuid phase (transfer water) and solid phase (resin). These samples are separately analyzed for principal gamma emitters. Toledo Edison luts 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 domineralizer backwash will be 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).
r j-The BRT receives the spent resin from the condensate Polishing System. Low level radioactive material contamination of the spent resin is periodically expected due to minor weeps in the steam generators and the leaching of residual activity in the secondary system.
During primary-to-secondary leakage, activity levels will be elevated and typically above the limits imposed for acceptable discharge to the basin. Under these conditions, 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 1~.
onsite settling basin with the approval of the Manager - Radiation Protection.
2.2.4 Borated Water Storace Tank and Primary Water Storace Tank The quantity of radioactive material stored in in the Borated Water Storage Tank (BWST) and Primary Water Storage Tank (PWST) shall,be limited to ensure the following:
1)
Protected Area boundary dose rates remain less than 0.25 mR/hr, and 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
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representative sample of the tank contents at least once per 7 days when radioactive materials are being added to the tank. Although the l
PWST is not currently used to support plant operation, the following limits still would apply should it ha in use.
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The method for limiting the BWST and PNST 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 of liquid 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.
C,
- VOL
- 3785 n
LF,
= E (2-1) lim i Where:
LF
= sum of the limiting fraction of each radionuclide "i" in the sample, C,
= concentration of radionuclide "i" in the liquid sample 3
(pCi/ml),
VOL
= volume of liquid in the tank (gal),
3785
= ml per gal, A
= limiting activity of radionuclide "i" from Table 2-5 (gC1/ml), and 0
n
= number of radienuclides 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 descr:be the events leading to this condition in the next Radioactive Effluent Release Report.
The values in Table 2-5 were calculated specifically for the BWST.
They are conservative for the PWST due to its smal Aer volume.
DBP 6027A 8
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J 2.3 LIQUID EFFLUENT MONITOR SETPOINTS 1
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 pCi/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 Setooint Ecuation During the release of liquid radioactive effluents, radiation monitor setpoints shall be established to alarm and trip prior 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 Licuid Radwaste Effluent Line Monitor Setooint Calculations (RF-1770A & B, RE-1978A & B) i-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'ielease rate from the tank is determined for the release based on the radionuclide concentrations and the available dilution flow rate.
l DBP 6027A 9
Revision 10.0 ODCM l
The maximum release rate is inversely proportional to the ratio of i
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:
ECF = E (2-2) i ECg where:
ECF sum of the fractions of the unrestricted area EC for a
=
mixture of radionuclides, j
g concentration of each radionuclide i measured in tank prior C
=
to release (gCi/ml), and EC unrestricted area EC for each radionuclide i from 10 CFR
=
g Part 20.1302.
For dissolved and entrained noble gases an EC value of 2.0E-04 pCi/ml shall be used (gCi/ml).
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 i
for variations in monitor response and flow rates and also for the i
1 presence of radionuclides that may not be detected by the monitors (i.e., non-ganna emitters). The following equation is used for calculating the required minimum dilution factor MDF = ECF/SF (2-3) where:
minimum required dilution factor, MDF
=
0.3 administrative safety factor.
SF
=
The maximum release rate from the tank is then calculated by dividing the available dilutloa flow rate (ADF) at the Collection Box by the MDF as calculated by equation (2-4).
0.9 (ADF/MDF)
(2-4)
KAX RR
=
where:
maximum allowable release rate (gal / min),
HAX RR
=
administrative conservatism f actor, and 0.9 available dilution flow rate at the Collection Box as ADF
=
measured by Computer Point F201 (gal / min).
DBP 6027A 10 Revision 10.0 ODCM
~
(
(
NOTES
- Equations (2-3) and (2-4) are valid only for ECF >1.
For ECF S1, the waste tank concantration is below the limits of 10 CFR Part 20.1302 without dilution, and MAX RR may take i
on any value within discharge-pung capacity.
If MAX RR is greater than the maximum discharget pung capacity, then the pump capacity should be used in establishing the actual release I
rate (RR) for the radwaste discharge. For releases from the Miscellaneous Waste Monitor Tank and D2tergent waste Drain Tank, the discharge pump capacity is 100 gpas for the clean Waste Monitor Tank, this value is 140 gym.
I Since the actual release rate from the tank is derived such enat 10 l
CFR 20.1302 limits will not be exceeded given the radionuclide concentration in the tank and the available dilution flow, sotpoints i
must be established to ensures 1) radionuclide concentration released from the tank does not increase above the couantration 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 The setpoints for the predilution radiation monitor (RE-1770 A & B, j
or RE-1878 A & B) are determined as follows:
Alert Alam SP = (2 R*E (C
- SEN )] + Bkg (2-5) g High Alarm SP = [3 +R*E (C
- SEN )) + Bkg (2-6) where:
j setpoint of the radiation monitor (cpm),
=
concentration of radionuclide i as measured by gamma C,
=
spectroscopy t>01/ml),
monitor senst:1vity for radionuclide i based on calibration SEN
=
curve (cpm per SC1/ml), and background readig of the radiation monitor (cpm).
Ekg
=
MAX RR / actua* release rate R
=
The Ca 137 sensitivity may be used in lieu of the sensitivity values fer individual radionu:11 des.
The Cs-137 sensitivity provides a reasonably conservative monitor response correlation for radionuclides of interes in reactor effluents. Coupled with the safety factor SF in equation (2-3), this assumption simplifies the evaluation without invalidating the overall conservatism of the setpoint determination.
DBP 6027A 11 Revision 10.0 ODCM
.u ~
The high flow setpoint should be set equal to the MAE RR calculated in equation (2-4) or discharge pump capacity (whichever is smaller).
The 2ow flow setpoint for dilution flow rate should be sat at 0.9 times the available dilution flow rate.
I 2.3.4 Storm Sewer Drain panitor (RE-45AS)
The setpoint for the SSD radiation monitor, RE-4686, shall be established to ensure the concentration in the affluent does not exceed the limits of 10 CFR 20.1302.
The SSD is not normally radioactively contaminated by other than naturally-occurring j
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 alarin 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 Setooints for the Non-Recuired Radiation Monitors a) Collection Box Outlet to the Lake (RE-8433)
The radiation monitor on the Collection Box outlet utilizes a i
single off-line detector to continuously monitor all station liquid ef fluent 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 0
effluent line that will terminate the release prior to exceeding the effluent concentration for UNRESTRICTED AREAS in 10 CFR 20.1302.
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)
Component Coolina Water System (CCWS) (RE-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.
DBP 6027A 12 Revision 10.0 ODCM
+
4
?
^
c) service water system (swal-fan-s432)
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 i
fluctuations. The setpoint is controlled in'accordance with the l
a Radiation Monitor Setpoint Manual.
I d)
Intake Forabav Monitor (RE-8434) l I
The high alarm setpcint is established to prevent incurring a spurious alarm due to background fluctuations. Although highly j
9 unlikely, a verified alarm from this system would indicate a possible contamination of the station intake water. The setpoint is controlled in accordance with the Radiation Monitor Setpoint Manual.
l 2.3.6 Alarm ResDonne - Evaluatina Actual Release Conditions i
Liquid release rates are controlled and alarm setpoints are J
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 i
A & B, or RE-4686) alarm during a liquid release, it becomes necessary to re-evaluate the release 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 releaset l
4 i
re-sample and re-analyze the source of the release 0l 1
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:
i C
RR l
11 (2-7)
(
C g measured concentr,ation of radionuclide i in the effluent
=
stream prior to dilution (pCi/ml),
the Effluent Concentration for radionuclide i from EC
=
Appendix B, Table II, Column 2 of 10 CFR 20 or 2.0E-04 pCi/ml for dissolved or entrained noble gases
]
(pCi/ml),
1 b
DBP 6027A 13 Revision 10.0 ODCM i
m.-
actual release rate of the liquid offluent at the time of i
Rat the alarm (gal / min), and 1
actual dilution water flow at the time of the release alarm DF
=
(gal / min).
If the value calculated by equation 2-7 is less than or equal to 1, j
then the release did not exceed the limits of 10 CFR 20.1302.
i l
1 l
I
)
I l
J a
DBP 6027A 14 Revision 10.0 ODCM
\\
I 2.4 LIQUID EFFLUErf DOSE CALCOLATICII - 10 CFR 50
)
2.4.1 Dose Limits to MEMBERS OF THE PUBLIC The limits for dose or dose commitment to MEMBERS OF THE PUBLIC from j
radioactive materials in liquid effluents from Davis-Besse are:
during any calendar quarter s 1.5 mrem to total body s 5.0 mrem to any organ during any calendar years s 3.0 mrem to total body i 10.0 mrom 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.
This requirement is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50.
C 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."
P i
DBP 6027A 15 Revision 10.0 ODCM
=
1 o
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 ODO4 implement the requirements of Section III.A of Appendix I, 10 CFR Part 50.
Conferinance with the guides of Appendix I is to be shown by calculational procedures based on modes and data such that the actual exposure of an individual 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 affluents 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.
4 2.4.2 MEMBER OF THE PUBLIC DOSE - Licuid Effluents The calculation of the potential doses to MEMBERS OF THE PUBLIC is a function of the radioactive material releases to the lake, the I
subsequent transport and dilution in the exposure pathways, and the resultant individual uptake. At Davis-Besse, the combined fish j
consumption and drinking water pathway has been modeled to ovide a conservative dose assessment for exposures to MEMBERS OF "!L, PUBLIC.
For the fish pathway, it has been conservatively assumed that the maximum exposed individual consumes 21 kg per year of fish taken in the immediate vicinity of the Davis-Besse discharge to the lake. For the drinking water pathway, the conservative modeling is based on an C.
individual drinking 730 liters per year of water from the beach wells located 966 m to the NW of the site discharge.
(It is important to note that because of the high sulfur content, the watet 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 and:v: dual.)
The equation for assess;ng tre maximum potential dose to MEMBERS OF THE PUBLIC f rom liquid radwaste releases from Davis-Besse is:
J 1.67E-c; " VOL D
~
- I (C
- A g
g)
(2-8) 0F* 2 where:
dose or dose commitment to organ "o" including total body D
=
(mrem).
i site-specsfac ingestion dose commitment factor to the total A
=
body or any organ "o" for radionuclide "i" given in Table 2-6 (mrem /hr per pCi/ml),
DBP 6027A 16 Revision 10.0 ODCM
+ y:, ; a.
i average concentration of radionuclide i in undiluted liquid C
=
affluent representative of the the volume VOL (pci/ml),
total volume of undiluted liquid effluent released (gal),
VOL
=
average dilution water flow rate dUring release period DF
=
(gal / min) (typically 20,000 gpm),
10 (near field dilution factor)*
2
=
1 hr/60 min.
1.67E-02
=
The site-specific ingestion dose / dose commitment factors (A )
represent a composite dose factor 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 are presented in g
Table 2-6.
These values were derived in accordance,with the guidance of NUREG-0133 using the following equation:
A
= 1.14E+05 (Up / D, + U BF ) DF (2-9)
F g
wheres.
21 kg/yr adult fish consumption, U
=
F 730 liters /yr adult water consumption, U
=
g 5.7 additional dilution from the near field to the beach D
=
g wells (net dilution of 57),
bioaccumulation factor for radionuclide "i" in fish from BF
=
Table 2-7 (pCi/kg per pCi/1),
O dose conversion factor for nuclide "i" for adults in DF
=
organ "o" from Table E-11 of Regulatory Guide 1.109 (mrem /pCi), and 10 (pC1/ucil
- 10 (ml/kg) / 8760 (hr/yr).
1.14E+05
=
'* Near field dilution 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 Unit 1 Nuclear Power Plant", June 1980., _.
DBP 6027A 17 Revision 10.0 ODCM
The radionuclides included in the periodic dose assessment required by section 2.4.1 are those identified by gasuna spectral analysis of the liquid waste sasples collected and analyzed per the requirements of Table 2-3.
In keeping with the NUREG-0133 guidance, the adult age group represents the maxianna exposed individual age group.
Evaluation of doses for other age groups is n'ot required for demonstrating compliance with the dose criteria of section 2.4.1.
The dose analysis for radionuclides requiring radiochemical analysis will be perforned af ter receipt of results of the analysis of the composite samples. In keeping with the required analytical frequencies of Table 2-3, tritium dose analyses will be performed at least monthly Sr-89, Sr-90 and Fe-55 dose analyses will be performed at least quarterly.
2.4.3 Simolified Licuid 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 spectroscopy).
H-3 should not be included in this analysis. Refer to Appendix A for the derivation of this simplified method.
Total Body 9.70E+02
- VOL EC (2-10)
D b" DF Maximum Oroan 1.19E+03
- VOL
~
- E C.
(2-11)
D
=
max 1
where:
average concentration of radionuclide i excluding H-3 in C
undiluted 11guld effluent representative of the release volume (utt/ml),
volume of liquid effluent released (gal),
VOL
~~
average dilution water flow rate during release period DF
=
(gal / min),
c neervatively evaluated total body dose (mrem),
D
=
b D,,
conservatively evaluated maximum organ dose (mrem),
5.81E+05 (mrem /hr per pCi/ml, Cs-134 0.0167 (hr/ min) 9.70E 02
=
total body dose factor from Table 2-6) / 10 (near field dilution), and DBP 6027A 18 Revision 10.0 ODCM
v 0.0167 (hr/ min)
- 7.11E+05 (area /hr per pCi/ml, Cs-134 1.19E+03
=
liver dose factor from Table 2-6) / 10 (near field dilution).
Cont==4nated TBS /SSD System - Dose Calculation 2.4.4 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 Rivert 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 lake environment; 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 other sources into the Training Center Pond prior to release to the river.
~ ~,
1 i
l I
DBP 6027A 19 Revision 10.0 ODCM
2.5 LIQUID EFFLUENT DOSE PROJECTIONS 10 CFk 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 offluents. This requirement is implemented through this ODot.
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 j
any organ over a 31-day projection).
1 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 equipment 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 LMRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the CDCM.
The following equationc may be used for the dose projection calculation:
(31 / d)
(2-12) bp " D D
tb D
=D (31 / d)
(2-13) maxp max where:
the 31-day total body dose projection (mrem),
D
=
DBP 6027A 20 Revision 10.0 ODCM
.~.
-. ~.
o O
the cumulative total body dose for current calendar quarter D
=
including release under consideration as determined by equation (2-8) or (2-10) (arem),
the 31-day maximum organ dose projection (mrom),
D
=
the maximum organ dose for current calendar quarter including D
=
release under consideration as determined by equation (2-8) or (2-11) (mrem),
the number of days s'ecounted for by the calendar quarter dose, d
=
and the number of days in projection.
31 1
e DBP 6027A 21 Revision 10.0 ODCM
~ _ _ _.
4 2
MINIMUM o
CHANNELS c
N INSTRUMENT OPERABLE APPLICABILITY ACTIOtt k
- n -
0 1.
Gross Radioactivity Monitors y-N Providing Alarms and Automatic Y
Termination of Release l
e a.
Liquid Radwaste Ef fluent Li ne 1
(1)
A j
d (either Miscellaneous or Clean.
but not both simultaneously) 2.
Flow Rate Measurement Devices d
a.
Liquid Radwaste Effluent Line 1
(1)
B 3
b.
Dilution Flow to Collection Box 1
(1)
B e
c.
FE 4607 Storm Sewer 1
(1)
B,C 3.
Gross Beta or Opmma Radioactivity be*
Monitors Providing Alarm But Not u
Providing Automatic Termination Y
of Release a.
Storm sewer Drain 1
(1)
B,C aa M
1
+
4.a o :o 2
a oe9d aron
>a O
- Only one release (either MWMT or CNMT) at a time'can be in progress.
t n.-.
-- ---w- --- -
Table 2-1 (continued) i TABLE NOTATION (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 iridependent 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 I
i 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 estimate flow.
ACTION C With the number of channels OPERABLE less than required by the minimum channels CPERABLE requirement, effluent releases via l
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 0,
analyzed for gross radioactivity (beta or gamma) at a lower limit of detection no greater than 1.0E-07 pCi/ml.
J i
e i
l i
.~
DBP 6027A 23 Revision 10.0 ODCM
e CHANNEL g
CHANNEL SOURCE CHANNEL FUNCTIONAL
'o INSTRUMENT CHECK CHECK CALIBRATION TEST m
h 1.
Gross Beta or Gamma Radioactivity Monitors Providing Alarm and Automatic Isolation, if applicable.
+
a.
Liquid Radwaste Effluents Lines D
P' R
Q b.
Storm Sewer Discharge Line D
M R
Q 2.
Flow Rate Monitors a.
Liquid Radwaste Effluent Lines D
N.A.
R Q
b.
Dilution Flow to Collection Box D
N.A.
R Q
c.
Storm Sewer N.A.
Br
.1 u
a 8F 9 ;1 E
8 b
\\\\
Table 2-2 (continued)
TABLE NOTATIO2 (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.
(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 participate in measurement assurance activitias 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.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, 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 />.
(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.
9 e
DBP 6027A 25 Revision 10.0 ODCM
Table 2-3 J
RADIQACTIVE LIOUID WASTE SAMPLING AMD ANALYSIS PR W Ant Ministum Type of Lower Limit Liquid Release Type Sangling Analysis Activity of Detection Frecuenev Freesency Analysis (T in) (uci/ml)"
I P
P Principal A.
Batch Waste Each Batch Each Batch Gamma 5.0E-07 d
g Release Tanks EmitteIs I-131 1.0E-06 P
Dissolved One Batch /M M
and Entrained 1.0E-05 Gases a
P M
Each Batch Composite #
H-3 1.0E-05 i
Gross Aloha 1.0E-07 P
Q Each Batch Composite Sr-89, Sr-90 5.0E-08 j
Fe-55 1.0E-06 B.
Storm Sewer Principal b
Drain Continuously S
Gamma 5.0E-07 f
monitored Emitters I-131 1.0E-06 P
P Principal C.
Condensate Each Batch Each Batch Gamma 5.0E-07' I
f Demineralizer when when Emitters Backwash discharged discharged to the to the l
f settling settling I-131 1.0E-06 basin basin DBP 6027A 26 Revision 10.0 CDCM
V'd Table 2-3 (continued) 4 TABLE NOTATION The LLD is the smallest concentrati6n of radioactive material in a sample s.
that will be detected with 95Z probability with 5Z' probability of falsely concluding that a blank observation represents a 'real" signal.
For s'particular measurement system (which may include radiochemical separation):
b LLD =
3 E
- V
- 2.22
- Y
- exp (-Aat) i where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);
1 S is the standard deviation of the background counting rate or of j
the counting rate of a blank sample as appropriate (as counts per
~
4 b
minute):
1 1
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):
1 1 is the radioactive decay constant for the particular radionuclide:
At for plant effluents is the elapsed time between the midpoint of senple collection and time of counting.
4 It should be recognized that the LLD is defined as an a priori (before the i
fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
l i
.~
U P
DBP 6027A 27 Revision 10.0 ODCM
l l
~
Table 2-3 (continued)
TABLE NOTATION b.
The principal gamma emitters for which the LLD specification will apply 1
are exclusively the following radionuclides:
Mn-54, Fe-59, Co-58, Co-60, En-65', Mo-99, Cs-134, Cs-137, and Ce-141.
For Co-144, the LLD is 2.0E-06 Ci/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.
d.
A BATCH RELEASE is the discharge of liquid wastes of & 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.
1 i
l f.
If an isotopic analysis is unavailable, gross beta or gamma measurement of BATCH 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.
1 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 inoptrable).
DBP 6027A 28 Revision 10.0 ODCM
P r
Table 2-4 Limiting Radionuclide Concentrations
- In Secondary-Side clean-Up Resins for Allowable Discharges to Onsite Settling Basin Radionuclide LimitingConcengration**
(pci/cm )
Cr-51 3.3E-02 Mn-54 6.2E-05 Fa 59 5.1E-04 Co-C*
3.0E-04 Co-60 5.4E-06 Y-91 2.1E-03 Zr-95 4.1E-04 Nb-95 1.0E-03 Mo-99 7.8E-03***
Ru-103 1.0E-03 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 3.1E-03***
Te-132 3.5E-03***
I-131 1.1E-04 I-133 3.8E-04 I-135 1.5E-03 I
Cs-134 1.1E-05 Cs-136 2.3E-03***
l Cs-137 1.0E-05 Ba-140 3.1E-03***
La-140-3.5E-03***
l Ce-141 5.8E-03 Ce-144 4.1E-05 l
Pr-143 1.9E-02 Concentration limits based on the study, Disposal of Low-Level Radioactivelv Contaminated Secondarv-Side Clean-up Resins in the On-site Settline Basins at the Davis-Besse Nuclear Power Station, J. Stewart Bland, May 1983.
The limits represent a hypothetical maximum individual dose of less 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 j
report have been reduced by a factor of 10 for added conservatism -
representing a hypothetical dose of less than 0.1 mrem.
L
- With more than one radionuclide 2dentified in a resin batch, the evaluation j
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 l
concentration: 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 II, Column 2 value,s.
4 DBP 6027A 29 Revision 10.0 ODCM l
-~. - _
_ ~-
Table 2-5 Radionuclide Activity Limits for the BNST and PNST Radionuclide Total Activity (ci)
H-3 2.12E+03 Cr-51 2.888+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 1.73E+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-110m 4.31E+00 Sn-113 5.64E+01 Sb-125 2.47E+01 1-131 2.12E-01 I-132 5.00E+00 I-133 7.05E-01 4,53E+00 I-134
~
2.82E+00 I-135 Cs-134 6.35E+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 6.35E+01 Ce 144 7.05E+00 DBP 6027A 30 Revision 10.0 ODCM l
~,
~
.l 2
l
\\
5 1
i Table 2-6 Davis-Smse site-specific Liquid Ingestion Dose Comunitment Factors, A i
g*
(ares /hr per pCi/ml)
Nuclide uma Liver T. Body Thyroid Kidney Luna ar-LLI i
l
. H-3 0.00E+0 1.76E+0 1.76E+0 1.76E+0 1.76E+0 1.76E+0 1.76E+0 j
C-14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 Na-24 4.32E+2 4.32E+2 4.32E+2 4.32E+2 4.32E+2 4.32R+2 4.32E+2 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 1.31E+0 7.85E-1 2.89E-1 1.74E+0 3.30E+2 l
Mn-54 0.00E+0 4.44E+3 8.48E+2 0.00E+0-1.32E+3 0.00E+0 1.36E+4 f
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 4.93E+2 1.13E+2 0.00E+0 0.00E+0 2.69E+2 2.77E+2 Fe-59 1.10E+3 2.592+3 9.93E+2 0.00E+0 0.00E+0 7.24E+2 8.64E+3 Co-57 0.00E+0 2.35E+1 3.91E+1 0.00E+0 0.00E+0 0.00E+0 5.96E+2 1
Co-50 0.00E+0 1.00E+2 2.24E+2 0.00E+0 0.00E+0 0.00E+0 2.03E+3 Co-60 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 1.11E+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 4.01E-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+*.
0.00E+C 7.59E+3 Y-91m 6.77E-3 0.00E+0 2.6:E-4 0.00E+0 0.00E+0' O.00E+0 1.99E-2 Y-91 1.05E+1 0.00E+0
- .81E 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
- .00E-1 0.00E-0 5 51E 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 :
1 34E :-
0.00E+0 2.46E+2 0.00E+0 1.51E+6 Nb-97 3.75E+0 9.48E-1 3 46El1~
0.00E+0 1.11E+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 3.53E-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 0*E 0 0.00E+0 2.72E+1 0.00E+0 8.32E+2 Ru.105 5.94E-1 0.00E+0
- 34E 1 0.00E+0 7.67E+0 0.00E+0 3.63E+2 Ru 106
.06E+2 0.00E+0 1 34E.1 0.00E+0 2.05E+2 0.00E+0 6.86E+3 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 l#
Ag 110m 3.2:E+0 2.9BE+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 DBP 6027A 31 Revision 10.0 ODCM
=
_m Table 2-6 (continued)
Davis-Besse site-specific Liquid Ingestion Dose Commitment Factors, A I*
(area /hr per pCi/ml) maam Liver T. Body Thyroid Kidney f-GI-t.f,7 8b-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 2.21E+4 f
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 i
Te-131 1.92E+1 8.00E+0 6.05E+0 1.57E+1 8.39E+1 0.00E+0 2.71E+0 Te-132 2.45E+3 1.58E+3 1.49E+3 1.75E+3 1.53E+4 0.00E+0 7.50E+4 I-130 3.82E+1 1.13E+2 4.44E+1 9.55E+3 1.76E+2 0.00E+0 9.70E+1 I-131 2.10E+2 3.01E+2 1.72E+2 9.85E+4 5.15E+2 0.00E+0 7.93E+1 I-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 1-135 2.24E+1 5.86E+1 2.16E+1 3.86E+3 9.39E+1 0.00E+0 6.62E+1 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 Co-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 2.23E-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 8.61E-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-3 1.08E-3 0.00E+0 0.00E+0 0.00E+0 3.16E+1 0
Ce-141 1.59E-1 1.00E-1 1.22E-2 0.00E+0 5.00E-2 0.00E+0 4.11E+2 Ce-143 2.80E-2 2.07E+1 2.29E-3 0.00E+0 9.13E-3 0.00E+0 7.75E+2 Ce-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 9.31E-4 1.14E-4 0.00E+0 5.25E-4 0.00E+0 3.22E-10 Nd-147 4.68E-1 5.41E-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 9.25E+2 I
i i
DBP 6027A 32 Revision 10.0 ODCM
.d Table 2-7 Bioaccumulation Factors (BFi)
(pci/kg per pCi/ liter)*
Element Framhunter Fish H
9.0E-01 C
4.6E+03 Na 1.0E+02 P
3.0E+03 Cr 2.0E+02
'l Mn 4.OE+02 Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 Br 4.2E+02 l
i Rb 2.0E+03 l
Sr 3.0E+01 j
Y 2.5E+01 J
J Zr 3.3E+00 IQ) 3.0E+04 Mo 1.0E+01 Tc 1.5E+01 i
Ru 1.0E+01 Rh 1.0E+01 Ag 2.3E+00 Sb 1.0E+00 r
Te 4.0E+02 I
1.5E+01 Cs 2.0E+03 Ba 4.0E+00 La 2.5E+01 Ce 1.0E+00 Pr 2.5E+01 Nd 2.5E+01 W
1.2E+03 Np 1.0E+01 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 ta, ken from UCRL 50564, Rev.
1, October 1972.
DBP 6027A 33 Revision 10.0 l
~
i*
4 l
Figure 2-1 Liquid Radioactive Effluent Monitoring and Processing Diagram L(CE o
-U.........
. DAVIS BESSE NPS o **
- Ll0Ul0 RnalonClivi f
l RELEASE Pa!HVAys 4
cour
..c.,
w aa u.....
4....
e....
f vuas:=c oustor.c
{
Aux.
surto we l
l ql
=
stAOwASTE AAC4 c--
g q. _....
99 9
g>
r
.= m 1............c.'....
a 1
e.....
9........
i I......
o........
I Y
.o.
M.....
v se.....
6...
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'DBP'6027A 34 Revisior.10. 0 ODCM t
t
j
't 3.0 GhSEOUS 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.
i 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 i
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.
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.
r 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.
DBP 6027A 35 Revision 10.0 ODCM
_.. _ ~. _
1 3.1.1 Mars and Automatic Release Terminatioq a)
Waste n== Decav System Manitor (RE-1822 A&B)
The radioactive waste gas discharge line,is continuously monitored by two off-line detectors, each measuring gross i
setivity. 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 (PT-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 i
release:
)
at least two independent gas samples are collected and analyzed by gamma spectroscopy for principal gamma emitters (noble gases),
j at least two independent verifications of the release rate calculations are performed, and I
at least two independent verifications of the discharge valve line-up are performed.
If the flow 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.
b)
Containment Purce Exhaust Filter Monitor (RE-5052 A,B&C)
This detector monitors the containment atmosphere for radioactivity during containment VENT or PURGE.
The noble gas i
activity monitor (Channel Cl is required by Table 3-1.
It provides an automatie termination of the release prior to 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 36 Revision 10.0 ODCM
3.1.2 Alarn Only 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 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 by Table 3.1.
The Channel 2 and channel 3 detectors provide information on potential particulate and radiciodine 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 radiciodines 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.
The following sampling and/or monitoring instrumentation on the Station Vent is required by Table 3-1:
noble gas activity monitor (Channel 1),
particulate sampler filter, iodine sampler cartridge, C
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 Oxvoen Monitors (AE 5984 and 657C)
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 volume. An oxygen concentration above the specified limit will actuate a local and control room alarm.
DBP 6027A 37 Revision 10.0 ODCM
I l
3.2 SAMPLING AND ANALYSIS OF GhSEOUS EFFLUENTS Radioactive gaseous wastes shall be sasqpled and analyzed in accordance l
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 3.1.1 and 3.8.1.
l 3.2.1 Batch Releasta Table 3-3 requires that a grab gas sample be collected and an.tlyzed 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 1
All releases from the Station Vent are required to be coptinuously 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, ence per week, analysis of a filter sample for all principal 1
gamra emitters (partzculate radioactive material),
ence per month, analysis of a grab gas sample for all principal gamma emitters (noble gas) and tritium, ence per month, analysis of a composite of the particulate samples of all releases for that month for gross alpha activity, ence per quarter, analysis of a composite of the particulate saeples for all releases for that quarter for Sr-89 and 90, and continuous monitoring for noble gases (gross beta and gamma activity).
DBP 6027A 38 Revision 10.0 ODCM
p a
3.2.3 Rel===es Resultinct from Pr4 =arv-to-Ba-Am*v Bystem t==1rmae Should the secondary coolant system become contaminated, then there are several additional gaseous release points to consider:
The Atmospheric Vent Valves (AVVs),
l 4
Main Steam System Relief Valves (M20Vs),
Auxiliary Feed Pump Turbines (AFPTs),
I i
l 235#, 50# Relief Valves, 1
Auxiliary Steam System Relief Valves and Auxiliary Boiler Relief Valve.
l Since these releases of radioactivity are not controlled on a batch basis, they should be considered continuous releases unless they are unplanned and uncontrolled in which case they are abnormal releases.
Steam may be released via any of these points due to improper valve seating. Steam may be released via the MSSVs and AVVs if the plant trips, or via the AVVs during a condenser outage. Steam is released through the AFPTs during their operation. Steam may be released due l
to overpressurization of the Auxiliary Steam System via the relief j
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 1
principal gamma emitters (noble gases) and tritium; once per week, analysis of a 1econdary system liquid sample for principal gamma emitters (iodines and particulates);
once per quarter, analysis of a composite of secondary system liquid samples for strontium-89 and strontium-90.
Liquid samples are analyzed from Main Steam during normal operations, and from the Auxiliary Boiler during Modes 5 and 6.
For Auxiliary Steam System Relief lifts that occur when the Auxiliary Boiler is the source of Auxiliary Steam,' analyze liquid samples from the Auxiliary Boiler for gamma emitters and tritium.
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.
DBP 6027A 39 Revision 10,0 ODCM
.I 3.2 GASEOUS EFFLUENT MC,NITOR SITPOINT DETERMINATION 3.3.1 Total Effective Dome Eaulvalent Limits 10 CFR 20.1301 limits the total effective dose equivalent, (TEDE), to individual members of the public from all licensed operations to 100 mrom in a year. At Davis-Besse, the total effective dose equivalent due to radioactive materials released in gaseous effluents at the 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 vant 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 particulates effluent does not exceed the following limits:
This may be demonstrated by ensuring thats 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 batch 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, 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.
DBP 6027A 40 Revision 10.0 ODCM
i For INDIVIDUAL MEMBERS OF THE PUBLIC who may at times be within the, l
12iRESTRICTED AREA BOUNDARY, the occupancy of that MEMBER OF THE 8
PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the UNRESTRICTED AREA BOUNDARY.
3.3.3 7"divid"m1 Release Radiation Monitor Setroints 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:
EC
- 500 g
~
TB 472
- x/Q
- E(C
- K)
NG g
g I C.
- 3000 (3-2)
=
472
- x/Q NG i
i i
where:
SPTB limit for the total body dose rate of 500 mrem per year (uC1/ml),
monitor setpoint corresponding to the release rate SP
=
g limit for the skin dose rate of 3000 mrem per year (uca/ml),
3 total body dose rate limit (mrem /yr),
500
=
skin dose rate limit (mrem /yr),
3000 x/Q _ =
atmospherac x/Q value for direct exposure to noble gas at the 1'NTESTRICTED AREA BOUNDARY given in Table 3-6 3
(sec/r >,
ventalationsystemflowrate{ortheapplicable VF release point and monitor (ft / minute),
concentra: ton of noble gas radionuclide "i" as C
=
deterraned by gamma spectral analysis of grab sample (ucare;..
total body dose cogversion factor for radionuclide "i" K
=
(mrem'yr per uCi/m ) from Table 3-5, j
skin dose conyersion factor for radionuclide "i" beta L
=
(mrem /yr per uCi/m ) from Table 3-5, DBP 6027A 41 Revision 10.0 ODCM
. =__..
.o 6
g gammaairdosecogersionfactorforradionuclide"i" M
=
(arad/yr per pci/m ) from Table 3-5, mrem skin dose per mrad gansna air dose (arem/arad),
1.1
=
and 28,317 (ml/ft )
- 1/60 (min /sec).
472
=
setpoint.
The Station Vent monitor (RE-4598) efficiencies and read outs are 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/ml must be corrected to an equivalent monitor counts per minute.
The monitor calibration curves are used for determining specific radionuclide efficiencies (cpm per yci/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 ef ficiency provides a conservative value for alarm setpoint determination.
3.3.4 ggnservative, Generie Padiation Monitor Setooints Normally, generic alarm setpoints are established instead of those j
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 i
alarm setpoint may be conservatively determined by assuming all 0
l 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).
.' gain, 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 Pate Evaluation For Batch Releases 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 is used as the maximum allowable release b, RR, or RR H flow rate.
DBP 6027A 42 Revision 10.0 ODCM
- 1 q
1 To determine RR azactly, a separate RR unast be calculated for every organ in every age group (28 valuesE RR
).
The smallest of 1
these 28 is the RR which is compared to RR SdRR to determine maximum allowable M ease rate. A conservatiN shorteEt is to calculate RR @ once by using the largest inhalation dose factor (R I from Table 3 for any organ of any age gro6p for each nuclide released. The largest dose factors in the inhalation pathway are usually for the teen lung.
500 472
- x/Q,g* IM
- N) g g
3000 (3-4)
=
1 472
- x/Q,g* r ( a + 1.1 M ) *m) f g
g 1500 (3-5)
=
7 472
- x/Q
- I (R
- CINH )
- DF 4
g 7p where:
exceed a allowable release flow rate so as not g/ minute),
=
g total body dose rate of 500 mrem /yr (ft as not to exceed a skin allowable release flow rate sg/ minute),
=
8 dose rate of 3000 mrem /yr (f t j
allowable release flow rate so as not to exceed an C
=
3 inhalation dose rate of 1500 mrem /yr (ft / min),
500
= total body dose rate limit at the UNRESTRICTED AREA BOUNDARY (mrem /yr),
skin dose rate limit at the UNRESTRICTED AREA l
3000
=
BOUNDARY (mrem /yr),
inhalation dose rate limit at the UNRESTRICTED AREA 1500
=
BOUNDARY (mrem /yr),
1/60 (min /sec),
28317 (ml/ft )
472
=
atmospheric x/Q value for direct exposure to noble gas x/Q
=
NG (sec/m)MSTRME N BMW ghen in Tame M at the
),
atmospheric x/Q value for inhalation at the x/Q
=
UNRESTg.ICTEDAREABOUNDARYgiveninTable3-6 l
(sec/m ),
I DBP 6027A 43 Revision 10.0 ODCM
g total body dose co9 version factor for radionuclide "i" K
=
(arem/yr per pci/m ) from Table 3-5, g
beta skin dose couyersion factor for radionuclide "i" L
=
i (arem/yr per pCi/m ) from Table 3-5, gamma air dose conyet=1on factor for radionuclide "i" M
=
(mrad /yr per pCi/m ) from Table 3-5, dose factor for radionuclide toorgan"o"ofage R,
g group, given in Table 3-7 (arem/yr per pCi/m ),
concentration of noble gas radionuclide "i" analyzed CNG
=
g in grab samples,
)
concentration of tritium, radiciodine, or particulate CINH
=
g radionuclide "i" analyzed in grab samples, and removal factor of 100 to be used for radiciodines and DF
=
7p particulates when the effluent is processed through an absolute filter (do n21 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.
g l
1 I
DBP 6027A 44 Revision 10.0 ODCM
UNRESTRICTED ARIA BOUNDARY DOSE RATE CALCUIATICIf - NOBLE GAS 3.4 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:
- W*
EW
- C) g = 472
- x/Q D
yg 3
D,
= 472
- x/O
- W*
E(%$ + 1.1 M ) *C) 0-D gg 3
where:
D tb skin dose rate (mrem /yr).
D;
=
x/0,g =
atmospheric x/Q for direct exposure to noble gases at STRICTED AREA BOUNDARY given in Table 3-6 l
the y/m )
(sec ventilation system flow rate (ft / min),
=
concentration of radionuclide "i" as ceasured in C
=
the sample (pci/ml),
total body dose conversion factor fgr noble gas K
=
radionuclide "i" (mrem /yr per pCi/m ) from Table 3-5, beta skin dose conversion factgr for noble gas radio-L.
=
nuclide "i" (mrem /yr per pCi/m ) from Table 3-5, gamma air dose conversion factor fog) noble gas M
=
radienuclide "i" (mrad /yr per pCi/m from Table 3-5, mrem skin dose per mrad gamma air dose (mrem / mrad),
1.1
=
and 28,317 (ml/ft )
- 1/60 (min /sec).
472
=
l DBP 6027A 45 Revision 10.0
(
l 3.5 tRERESTRICTED ARIA BOUNDARY DOSE RATE CALCULATION - RADIOIODINE. TRITIUM, AND PARTICUIATES 3.5.1 Dose Rate Calculation Section 3.3.2 limits the dose rate to $1500 area /yr to any organ for gaseous releases of I-131, tritium and all particulates with half-lives greater than s_ days. To demonstrate conqpliance with this l
limit, an evaluation is performed in accordance with Table 3-3 (nominally once per 7 days). The following equation may be used for the dose rate evaluation:
x/Q Do INH io i
" I
=
where:
4 dose rate to organ "o" over the sampling time period D
=
j (mrem /yr) i x/Q atmospheric x/Q value for inhalation at the UNRESTRICTED
=
INH 3
AREA BOUNDARY given in Table 3-6 (sec/m ),
i dose factor to organ R
=
g from radionuclide "i" for the controlligg age group via the inhalation pathway (mrem /yr
{
par pCi/m ) from Table 3-7, and
}
average release rate over the appropriate sampling period Q
=
g and analysis f requency for radionuclide "i" (pci/sec).
4, l
3.5.2 Simolified Dose Rate Evaluation for Radiciodine. Tritium and Particulates E
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 organ "o" in j
Equation (3-8) and solving for Q, an allowable release rate can be j
i determined. Based on the annual average meteorological dispersion j
(see Table 3-6) and the : 131 dose factor for the most limiting l
potential pathway. age group and organ (inhalation, child, thyroid --
3 R
= 1.62E+07 mrem /yr per act/m ),
the allowable release rate is 4kilpCi/sec. An added'censervatism factor of 0.8 has been included 3
in this calculation to aerount for any potential dose contribution from other radioactive parta'culate material.
For a 7-day period.'wh1ch as the nominal sampling and analysis frequency, the cumulatave release would be 26.7.Ci.
Therefore, as long as the total radiotodane, tritium, and particulate releases in j
any 7-day period do not exceed 26.7 Ci, no additional analyses are l
needed to verify compliance with the Section 3.3.2 limits on l
i allowable release rate.
l
'O
}
i l
1 1
i i
n DBP 6027A 46 Revision 10.0 j
I I
ODCM k
l
~
b 3.6 QUANTIFYING ACTIVITY RELEASED NRC Regulatory Guide 1.21 requires reporting the quantities of individual radionuclides released in gaseous affluents. Therefore, these quantities shall be determined.
3.6.1 on=ntifvina Noble Gas Activity Released Usino Station Vent Monitor (RE-4598)
The quantification of continuous noble gas effluents is based on sampling and analysis of'the station vent effluent. The monitor provides a measurement of gross radioactive 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 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 released. 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 average noble gas monitor reading and a gas analysis for the release period, the individual noble gas radionuclides released are quantified by the equation:
^i 28,317 *
- C
- T (3-9)
Q
=
EA g where:
total activity released of radionuclide "i" (pCi),
1 Q
=
milliliters per ft 28,317
=
activity concentration of radionuclide "ia from the A.
=
gamma spectral analysis of the grab sample from the release point (gCi/ml),
average gross activity concentration over the release C
=
period as measured by the noble gas monitor excluding any BATCH RELEASES (pCi/ml),
l ventilat'on system flow rate (ft / min), and i ~
=
release duration (min).
T
=
w~
DBP 6027A 47 Revision 10.0 ODCM 1
-~
m.
.t L
3.6.2 Quantifyiner Moble Gas Activity Released Usinst A Grab Samole With both station vent radiation monitors inoperable (i.e., RE-4598 AA and BA, N nnel 1), the once-per-B hours grab samples provide for continued quantification of releases in accordance with Table 3.1 i
I requireinants. Analysis of grab samples provides the radionuclide concentrations in the affluent. The flow measurement device (or flow rate estimate) and the release duration provide the total volume released. With these, the total amount of radioactive material
]
released can be deterinined.
l i
l The following equation may be used for determining the release quantities from any release point based on the grab sample analysis:
28,317
- T
- C
- 1E-06 (3-10)
- i Q
=
g where total activity released of radionuclidag (C1),
O
=
g 28,317 = milliliters per ft,
ventilation system flow rate (ft / min),
=
release duration (min),
j T
=
Ci per yCi, and 1E-06
=
concentration of radionuclide "i" as measured in the C.
=
grab sample (yci/ml).
I I
I l
DBP 6027A 48 Revision 10.0 ODCM i
- - ~
._._.._.___.___-.______._...-m
.._._.-..m.__
3,6.3 Quantifying Radiciodine, Tritium, and Particulate Activity Released For radiolodine and particulates:
1If A
- A
- t
- v
- IE-06 Q
=
g (3-11)
(1-e,yi g)
- s
- 0.72 where total activity released of radionuclideg (C1),
Q
=
g activity of radionuclide measured on filter media A
=
g g
l-(pci),
decay constant of radionuclideg (hr ~I),
X
=
g
(..
t release duration (hr),
=
i total vent system flow for sampling period (cc),
i v
=
l lE-06 =
Ci per pC1,
[
total flow through sampler (cc), and s
=
isokinetic. flow correction factor for normal range 0.72
=
station vent skid RE 4598 AA or BA filter media.
l-For Tritium:
Q = C
- W
- V
- 1E-06 0.9 *S (3 12) l where:
I Q
total activity of tritium released (Ci),
=
C tritium concentration in gas washing bottle (pcilml),
=
W
=
volume of Water added to gas washing bottle (ml),
'V total vent system flow for release period (cc),
=
IE-06 =
Ci per pC1, u
0.9 l~
efficiency for collection of tritium, and
=
S total sample volume.through gas washing bottle (cc).
=
. ~
{
DBP 6027A 49 Revision 10.0 1
=.
w.
[ -;
I 3.7 NOBLE GAS DOSE CALCUIATICOIS - 10 CFR 50 3.7.1 TygtESTRICTED AREA Dose - Limits cuan11stive dose contributions for the cur 7 ent cal =^ quarter and current calendar year for noble gases shall be detarta:'.ned in accordance with the methodology and parameters in Mhia Section at least once per 31 days. This periodic sesessment of releases of noble gases is to evaluate compliance with the qu.arterly 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 radicactive 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 33 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 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 in reasonably achievable."
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 vases in gaseous effluents are consistont 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.
DBP 6027A 50 Revision 10.0 ODCM l
I
~
l 3.7.2 Dose calculations - Noble Gases The following equations may be used to calculate the gamma-air and
' beta-air doses 3.17E-os
- y/q,g* E (Mg*gg)
(3-13)
DX
=
- Qg)
(3-14) 3.17E-08
- y/Q,g* E (Ng Dp
=
where:
DA sir dose due to gamma emissions for noble gas
=
radionuclides (mrad),
Dp air dose due to beta emissions for noble gas
=
radionuclides (mrad),
y/Q atmospheric y/Q value for direct exposure to pg noble gas at theUNgESTRICTEDAREABOUNDARYgiven
)
in Table 3-6 (sec/m ),
)
Qg cumulative release of noble gas radionuclide "i"
=
over the period of interest (pC1),
i g
airdosefactorduetogammaemissionsjromnoble M
=
gas radionuclide "i" (mradlyr per pCi/m ) from i
Table 3-5
)
i g
air dose factor due to beta emissions fgom noble N
=
gas radionuclide "i" (mradlyr per pCi/m ) from Table 3-5, and 0
3.17E-08 =
Il3.15E+07 (yr/sec).
DBP 6027A 51 Revision 10.0 CDCM
ec, a
,y' L.
3.7.3 Simplified Dose Calculation for Noble Gases j
1 i
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 ILuits of Section 3.7.1.
(Refer to Appendix B for the derivation and justific'ation of this simplified method.)
i DA 2.0
- 3.172-08
- y/Q,g
- H,gg
- EQ 3-15)
(
=
g I
and l
D/
2.0
- 3.17E-08
- y/Q S
( - 6)
=
NG eff i
where:
H,gg =
5.7E+02,effectivegamma-airgosefactorfrom Appendix B (mradlyr per pCi/m ).
N,gg =
1.1E+03, effective beta-air dgse factor from Appendix B (mrad /yr per pCi/m ), and conservatism factor to account for potential 2.0 4
=
variability in the radionuclide distribution.
j 1
+
4 d
6 1
i 1
t
)
DBP 6027A 52 Revision 10.0 ODCM i
3.8 RADIOIODINE, TRITIUM AND PARTICULATE DOSE CALCULATIONS - 10 CFR 50 3.8.1 UNRESTRICTED AREA Dose Limits 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 current 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 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 l
AREA BOUNDARY shall be limited to the following:
During any calendar quarter: lest 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 of iodine-131, tritium and radionuclides in particulate form with half-lives greater than B 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.
0 This requirement is provided to implement the requirements of j
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 specifiei provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of I
Appendix I to assure that the releases of radioactive materials in j
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 00CM 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, " 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 DSP 6027A 53 Revision 10.0 ODCM 4
l
(
The release rate specifications for radiciodines and radioactive material in particulate form are dependant on the existing l
radionuclide pathways to man in the IMRESTRICTED ARIA. The pathways l
which are examined in the development of these calculations are:
individual inhalation of airborne radiotiuclides, deposition of radionuclides into green leafy vegetation with subsequent consumption by man, deposition onto gras'sy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and deposition en 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 wnich the maximum dose is calculated due to a given gaseous release of radionuclides. Determination of the critical pathway is made as part of the Annual Land Use census. As 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 listed in Table 3-4.
The critical pathway is chosen from among the maximum pathways for each secter and is listed in Table 3-6.
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 group to determine the maximum organ dose.
1 The dose factors for organs of the various age groups are listed by exposure pathway in Tables 3-7 through 3-11.
DBP 6027A 54 Revision 10.0 ODCM
3.8.3 nose calculatiaa=
nadiciodine. 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 a days:
D
= 3.17E-08
- W
- ICF
- SF
- E (R
- Q)
(3-17) aop io i
Where:
dose'or dose commitment to organ "o" via D
=
aop controlling pathway "p" and age group "a" as identified in Table 3-6 (mrem),
atmospheric dispersion factor to the controlling W
=
location as identified in Table 3-6 x/0,' dispersion factor for inhalation pathway and W
=
3 H-3 dose contribution via all pathways (sec/m )
D/Q, deposition f actor for vegetation,2) ilk m
W
=
and ground plane exposure pathways (m dose factor for radionuclide "i" to organ "o" of R'
=
age group"a" via pathway "p" as identified in Table 3-7, 3-8, 3-9, 3-10, or3-11depengingon thq pathway specified (mrem /yr per pCi/m )
or (m' - mrem /yr per pCi/sec),
cumulative release over the period of interest Q
=
for radionuclide "i" (gCi),
1 elemental iodine correction factor which may be ICF
=
used in calculating doses from radioiodines via the vegetation, milk, and ground plane exposure pathways = 0.5, seasonal correction factor which may be used for SF
=
milk and vegetation pathways = 0.5, and 1/3.15E+07 (yr/sec),
3.17E-08
=
The dose factors in Tables 3-7 through 3-l'1 are derived in accordance with NUREG-0133.
The elemental iodine correction factor in equation (3-17) is referenced in Regulatory Guide 1.109.
DBP 6027A 55 Revision 10.0 ODCM
3.8.4 si-nlified Dome Emiculation for mad 4eind4na. 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.s.1:
4 3.17E-08
- W
- ICF
- SF
- R
- EQ (3-18)
D
=
max I-131 i
where 4
maximum organ dose (mrem),
D
=
R,131 I-131 dose factor for the thyroid for the controlling
=
1 pathway identified in Table 3-6, and sum of the activities of all radiciodines, tritium and EQ g
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. However, use of the I-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 I-131 for the thyroid via the vegetable or milk pathway.
l l
DBP 6027A 56 Revision 10.0
)
ODCM i
i 3.9 GASEOUS EFFLUENT DOSE PROJECTION I
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 TREAMENT SYSTEM (i.e., Waste Gas Decay Tank) shall be used to reduce noble gas levels prior to discharge when the projected I
air dose due to gaseous effluent releases to areas at and beyond the i
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 TREAMENT SYSTEM shall be used to reduce radiciodine 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 would exceed 0.3 mrem to any organ in a 31-day period. Figure 3-1 presents the gaseous effluent release points and the 7
GASEOUS RADWASTE and VENTILATION EXHAUST TREATMENT SYSTEMS applicable for reducing effluents prior to release.
j 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 l
includes the following information:
i Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reasons for the inoperability, Actions taken to restore the inoperable equipment to OPERABLE I
status, and Summary description of action (s) taken to prevent a recurrence.
I The requirements that the appropriate portiens of these systems be used, when specified, provides reasonable assurance that the releases of 2
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.1.imits governing the use of appropriate portions of the systems were specified a,s_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 a
1 DBP 6027A 57 Revision 10.0 ODCM
I l
IftheGASEOUSRADWASTEandVENTILATIONEkHAUSTTREATMENTSYSTEMSarenot being used, dose projections shall be performed at least once per 31 days using the following equations:
DA * (31/d)
(3-19) 1A
=
l P
Df Dp * (31/d)
(3-20)
=
p t
D,,p =
D,, * (31/d)
(3-21) where:
DA projected 31-day gamma-air dose (mrad),
=
p DA gamma-air dose for. current calendar quarter (mrad).
=
Df projected 31-day beta-air dose (mrad),
=
p Dp beta-air dose for current calendar quarter (mrad),
=
D,,xp =
projected 31-day maximum organ dose (mrem).
maximum organ dose for current calendar quarter as D
=
determined by equation (3-17) or (3-18) (mrem),
d number of days accounted for by current calendar quarter
=
dose. and number of days in projection.
31
=
4 i
l i
1 DBP 6027A 58 Revision 10.0 ODCM
MINIMUM g
CHANNELS g
INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTI(N mo 1.
Waste Gas Decay System y
(provides automatic
]
isolation) 4 a.
Noble Gas Activity Monitor 1
(1)
Radioactivity Measurement A
M b.
Effluent System Flow Rate 1
(1)
System Flow Rate Measurement B
]
Measuring Device 2.
Waste Gas System j
(provides alarm function) 2 a.
Oxygen Monitor 1
(2)
% Oxygen D
3.
Containment Purge Monitoring g
System (provideq automatic g
isolation) y en R
w a.
Noble Gas Activity Monitor 1
(1)
Radioactivity measurement C
p
,a k
3 o=
o.
91 8
o
~
i.
=
MINIMUM t3 CHANilELS E
INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTIN u
4.
Station Vent Stack (provides alarm function)
I a.
Noble Gas Activity Monitor 1
(1)
Radioactivity Measurement C*
b.
Iodine Sampler Cartridge 1
(1)
Verify Presence of E*
Cartridge y
c.
Patticulate Sampler Filter 1
(3)
Verify Presence of Filter E*
d.
Effluent System Flow 1
(1)
System Flow Rate B*
Rate Measuring Device Measurement gg ut e.
Sampler Flow Rate l
7 Measuring Device 1
(1)
Sampler Flow Rate B*
7, w
Measurement 4
i s
I 1i s-E; 5
I!
w M
8 if 8
91 O
D i
H l
- This requirement is not applicable for routine replacement of sampling media or routine test.
-s.
4
,d Table 3-1 (Continued) i l
TABLE NOTATION f
l (1) During radioactive waste gas releases via this pathway.
(2) During additions to the waste gas surge tank 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.
At 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.
0 ACTICN O With the number of channels OPERABLE less than' required by the minimum channels OPERABLE requirement, additions to the waste gas surge tank may continue provided another method for ascertaining oxygen concentrations, such as grab sample analysis. is implemented to provide measurements at least once per f our(4) hours during degassing and daily during other operations.
ACTION E With the number of channels OPERABLE less than required by the minimum channels CFERABLE requirement, effluent releases via this pathway may centYnue provided samples are continuously collected with auxelaary sampling equipment, as required in Table 3-3 (this requirement is not applicable for routine replacement of sampling media or routine testing).
DBP 6027A 61 Revision 10.0 CDCM
k i
CHANNEL SOURCE CHANNEL FUNCTIONAL jf,j.
g
- o INSTRUMENT CHECK CHECK CALIBRATIOtt TEST
.- !?G 05-
'[h; s
m O
1.
Waste Gas Decay System y
- d7 '
[,,k '
a.
Noble Gas Activity Monitor P
P R
Q I
P(1)
N/A R
Q 3
b.
Effluent System Flow Rate 3
2.
Containment Purge Vent System
]
a.
Noble Gas Activity Monitor D
P
- M R
Q a
3.
Station Vent Stack A
a.
Noble Gas Activity Monitor D
M R
Q m
b.
Iodine Sampler W
N/A N/A N/A hg ParticulatejSampler W(1)
N/A N/A N/A y
c.
0 W
d.
System Effluent Flow Rate g
Measurement Device D
N/A R
N/A 5
e.
Sampler Flov Rate Measurement Device W
N/A R
N/A j,
Y J
l
-4 oy a
E ;i l
0 b
s; s.
Table 3-2 (continued)
TABLE NOTATIORf (1) During radioactive waste gas releases via this pathway.
(2) During additions to the waste gas surge tank.
(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 CHANNEL 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 CHANNEL CALIBRATION for radios;tivity measurement instrumentation shall be performed using one or more of they 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 releated 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 a nominal:
1.
One volume percent oxygen, balance nitrogen; and 2.
Four volume percent oxygen, balance nitrogen.
(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).
t 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 63 Revision 10.0 ODCM
r
[*f g
Minimum Lower Limit of-w Gaseous Release Type Sampling Analysis Type of Detection ( f ).
"p i
m Frecuency Frecuency Activity Analysis faci /ml)
O N
P P
Each Each Principal Gamma Emitters 1.0E-04
- waste Gas Decay Release Release j
~
Grab Sample H-3 1.0E-06
]
P P
g Containment Purge Each Purge Each Purge Principal Gamma Emitters 1.0E-04
}
H-3 1.0E-06 m
h C
Station Vent Stack Grab Sample Principal Gamma Smitters 1.0E-04 mf H-3 1.0E-06 w
B b
Continuous Charcoal I-131, I-133 1.0E-12 Sample b
Continuous Particulate Principag Ganuna 1.0E-11 m
y-
+
m Sample Emitters M
b u
continuous composite Particulate Gross Alpha 1.0E-11 Sample b
s Continuous Composite g
Particulate Sr-89, Sr-90 1.0E-11
-4 Sample m
b Continuous Noble Gas Noble Gases g
Monitor Gross Beta or Ganuna 1.0E-06 3
Q 8
i 91 8
0 b
si
Table 3-3 (Continued)
TABLE NOTATION The LLD is the smallest concentrati6n of radioactive material in a sample a.
that will be detected with 95Z probability with 5Z' probability of falsely concluding that a blank observation represents a "real' signal.
For a particular smasurement system (which may include radio-chemical separation):
4.66 sb 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);
s is the standard deviation of the background counting rate or of uthe counting rate of a blank sample as appropriate (as counts per minute);
E is the counting ef ficiency (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);
1 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.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
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.
l DBP 6027A 65 Revision 10.0 ODCM l
e... g, 4
Table 3-3 (Continued)
TABLE NOTATIQRt 1
The principal gasuna mitters for which the LLD specification will apply c.
are excliwively the following radionuclides:
Kr-87, Kr-88, Xe-133, 1
Xe-13'3m, It-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.- This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measured and identified, together with the above nuclides, shall also be identifed 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 Jevel 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 reesons 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.
I Q - At least once per 92 days.
0 DBP 6027A 66 Revision 10.0 ODCM
_ _ _. = _ -_-
b Table 3-4 t
I Land Use census suunnary w
i 4:
Exposure Pathway Locations and Atmospheric Dispersion Parameters
- l i
r 9
^
Distance Exposure controlling x/Q D[g 3
Sector (meters)
Pathway Ace Group (sec/m 1 la 1 N
880 inhalation child 9.15E-07 8.40E-09 i
NNE**
870 inhalation child 1.27E-06 1.47E-08 i
NE 900 inhalation child 1.26E-06 1.58E-08 ENE*
e E*
i i
f ESE*
SE*
1 SSE
'2,820 vegetation child 7.02E-08 8.36E-10 l
S**
3,440 vegetation child 4.38E-08 4.55E-10 SSW 1,220 vegetation child 1.57E-07 3.46E-09 t
1 SW**
4,130 vegetation child 4.79E-08 5.17E-10 WSW 7,010 goat milk infant 3.60E-08 2.03E-10 W**
1,640 vegetation child 2.69E-07 4.21E-09 4
l l
WNW**
2,900 vegetation child 7.19E-08 6.50E-10 NW**
2,320 vegetation child 6.91E-08 5.70E-10 NNW 1,210 vegetation child 2.70E-07 1.92E-09
- Since these sectors are located over marsh areas and Lake Erie, no ingestian j
I or inhalation pathways are present.
- These values are a change to this table as a result of the 1996 Land Use Census.
Note: The meteorological dispersion factors are taken from the Stone and Webster report, Handbook fer ODCM x/O and D/O Calculations, October j
1983.
J DBP 6027A 67 Revision 10.0 ODCM
_ =.
Table 3-5 Dose Factors for Noble Gases
- Total Body Skin Gamma Air Beta Air Gamma Dose Beta Dose Dose Factor Dose Factor Nuclide Factor K Factor L M
N l
(mrem /yg)peh(mrom/yy)per (arad/hper W a h per 3
3 FCi/m pCi/m pCi/m )
- Ci/m )
1 Kr-83m 7.56E-02 1.93E+01 2.88E+02 4
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 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.052+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 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 3.2BE+03
- Dose factors taken from NRC Regulatory Guide 1.109 1
DBP 6027A 68 Revision 10.0 ODCM
1
/
Table 3 5 i
Exposure Pathways, Controlling Parameters, and Atmospheric Dispersion for Dose calculations Atmospheric, Dispersion Exposure Receptor Controlling x/Q D/g) 3 Pathway Location Ace Group (sec/m )
J noble gases UNRESTRICTED AREA BOUNDARY 1.83E-06 N/A direct NNE exposure j
inhalation UNRESTRICTED
)
AREA BOUNDARY child 1.68E-06 N/A NNE (critical pathway) goat 7010 meters infant 3.60'E-08 2.03E-10 WSW NOTES:
1.
All meteorological dispersion values have been taken from the Stone and Webster report, Handbook f.,gI QP2 2c,/_Q apus Q/_Q Calculations, October 1983.
,2.
The noble gas, direct exposure x/Qs are based on the decayed, undepleted values.
3.
The. inhalation pathway x/Os are based on the decayed, depleted values.
DBP 6027A 69 Revision 10.'0 ODCM
Table 3-7 g, Inhalation Pathway Dose Fgetors - ADULT R
(arem/yr per pCi/m )
Nuclide Bone Liver Thyroid Kidney Luna GI-LLI T. Body 1.26E+3 1.26E+3 1.26E+3 1.268+3 1.26E+3 1.26E+3 H-3 C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 Na-24 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 1.02E+4 8.64E+4 5.01E+4 P-32 1.32E+6 7.71E+4 5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.OOE+2 Cr-51 9.84E+3 1.40E+6 7.74E+4 6.30E+3 3.96E+4 Hn-54 1.24E+O 1.30E+0 9.44E+3 2.02E+4 1.83E-1 Ma-56 7.21E+4 6.03E+3 3.94E+3 Fe 55 2.46E+4 1.70E+4 l
1.02E+6 1.8BE+5 1.06E+4 Fe-59 1.18E+4 2.7BE+4 3.70E+5 3.14E+4 6.71E+2 Co-57 6.92E+2 Co-58 1.58E+3 9.2BE+5 1.06E+5 2.07E+3 5.97E+6 2.85E+5 1.48E+4 1.15E+4 Co-60 1.78E+5 1.34E+4 1.45E+4 Ni-63 4.32E+5 3.14E+4 Ni-65 1.54E+O 2.10E-1 5.60E+3 1.23E+4 9.12E-2 4.62E+O 6.7BE+3 4.90E+4 6.15E-1 1.46E+0 Cu-64 6.90E+4 8.64E+5 5.34E+4 4.66E+4 Zn-65 3.24E+4 1.03E+5 Zn-69 3.38E-2 6.51E-2 4.22E-2 9.20E+2 1.63E+1 4.52E-3 Br-82 1.04E+4 1.35E+4 2.32E+2 2.41E+2 Br-83 1.64E-3 3.13E+2 Br-84 1.2BE+1 Br-85
~
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 1.40E+6 3.50E+5 8.72E+3 Sr-89 3.04E+5 9.60E+6 7.22E+5 6.10E+6 Sr-90 9.92E+7 Sr-91 6.19E+1 3.65E+4 1.91E+5 2.50E+O Sr-92 6.74E+0 1.65E+4 4.30E+4 2.91E-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 1.70E+6 3.85E+5 1.24E+4 Y-91 4.62E+6
~
1.57E+4 7.35E+4 3.02E-1 Y-92 1.03E+1 Y-93 9.44E+1 4.85E+4 4.22E+5 2.61E+0 5.42E+4 1.77E+6 1.50E+5 2.33E+4 Zr-95 1.07E+5 3.44E+4 2.97E+1 7.87E+4 5.23E+5 9.04E+0 Zr-97 9.6BE+1 1.96E+1 Nb-95 1.41E+4 7.82E+3 7.74E+3 5.05E+5 1.04E+5 4.21E+3 6.54E-2 2.40E+3 2.42E+2 2.05E-2 Nb-97 2.22E-1 5.62E-2 2.91E+2 9.12E+4 2.48E+5 2.30E+1 Mo-99 1.21E+2 Tc-99m 1.03E-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 70 Revision 10.0 ODCM
Table 3-7 (continued)
I Inhalation Pathway Dose Factors - ADULT (continued)
R 3
(mres/yr per pci/m )
Nuclide Bone Liver Thyroid Kidney Luna GI TIT T. Body 5.83E+3 5.05E+5 1.10E+5 6.58E+2 Ru-103 1.53E+3 1.02E+0 1.10E+4 4.82E+4 3.11E-1 Ru-105 7.90E-1 1.34E+5 9.36E+6 9.12E+5 8.72E+3 Ru-106 6.91E+4 Rh-103m Rh-106 Ag-110m 1.08E+4 1.OOE+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+5 1.24E+4 Sb-125 5.34E+4 5.95E+2 5.40E+1 1.74E+6 1.01E+5 1.26E+4 Te-125m 3.42E+3 1.5BE+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 4.53E+4 9.60E+5 1.50E+5 1.57E+3 Te-127 1.40E+O 6.42E-1 1.06E+0 5.10E+0 6.51E+3 5.74E+4 3.10E-1 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+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 1.11E-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 5.282+3 I-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 6.283+3 2.05E+4 4.06E+2 1.16E+3 I-132 1.16E+3 3.26E+3 1.14E+5 5.18E+3 8.88E+3 4.52E+3 I-133 8.64E+3 1.48E+4 0.15E+6 2.58E+4 I-134 6.44E+2 1.73E+3
.98E+4 2.75E+3 1.01E+0 6.15E+2 5.25E+3 2.57E+3 I
I-135 2.68E+3 6.98E+3 4.48E.5 1.11E+4 0.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-134 3.73E+5 8.48E*5 8.56E+4 1.20E+4 1.17E+4 1.10E+5 Cs-136 3.90E+4 1.46E+5 Cs-137 4.78E+5 6.21E+5 2.22E+5 7.52E+4 8.40E+3 4.28E+5 Cs-138 3.31E+2 6.21E+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 l
Ba-140 3.90E+4 4.90E.1 1.67E+1 1.27E+6 2.18E+5 2.57E+3 Ba-141 1.OOE-1 7.53E 5 7.OOE-5 1.94E+3 1.16E-7 3.36E-3 j
Ba-142
- 63E-2 2.70E-5 2.29E-5 1.19E+3 1.J6E-3 l
La-140 3.44E+2 1.74E :
1.36E+5 4.58E+5 4.58E+1 La-142 6.83E-1 3.10E-1
'~
6.33E+3 2.11E+3 7.72E-2 Ce-141 1.99E*4 1.35E+4 b.26E+3 3.62E+5 1.20E+5 1.53E+3 l
Ce-143 1.86E+2 1.38E+:
6.08E+1 7.98E+4 2.26E+5 1.53E+1 4
Ce-144 3.43E+6 1.43E+6 8.48E+5 7.78E+6 8.16E+5 1.84E+5 l
l Pr 143 9.36E+3 3.75E+3 2.16E+3 2.81E+5 2.OOE+5 4.64E+2
(
Pr-144 3.01E-2 1.25E-:
7.05E-3 1.02E+3 2.15E-8 1.53E-3 l
Nd-147 5.27E+3 6.10E+3 3.56E+3 2.21E+5 1.73E+5 3.65E+2 W-187 8.48E+O 7.08E+0 2.90E+4 1.55E+5 2.4BE+0 Np-239 2.30E+2 2.26E+1 7.OOE+1 3.76E+4 1.19E+5 1.24E+1 1
1 DBP 6027A 71 Revision 10.0 ODCM
7 1
Table 3-7 (continued) g,InhalationPathwayDoseFagtors-TEENN3ER R
(arem/yr per pC1/m )
Nuclide none Liver Thyroid Kidney Luna GI-11T T. Body 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 H-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 1.38E+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 7.50E+1 3.07E+1 2.10E+4 3.OOR+3 1.35E+2 Cr-51 1
5.11E+4 1.27E+4 1.98E+6 6.68E+4 8.40E+3 Mn-54 Hn-56 1.70E+O 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 Fe-59 1.59E+4 3.70E+4 1.53E+6 1.78E+5 1.43E+4 Co-57 6.92E+2 5.86E+5 3.14E+4 9.20E+2 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 Cu-64 2.03E+O 6.41E+0 1.11E+4 6.14E44 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 Br-83 3.44E+2 4.33E+2 Br-84 Br-85 1.83E+1 1.77E+4 8.40E+4
~
Rb-86 1.90E+5 Rb-88 5.46E+2 2.92E-5 2.72E+2 Rb-89 3.52E+2 3.38E-7 2.33E+2 2.42E+6 3.71E+5 1.25E+4 Sr-89 4.34E+5 1.65E+7 7.65E+5 6.68E+6 Sr-90 1.08E+8 Sr-91 8.80E+1 6.07E+4 2.59E+5 3.51E+O 2.74E+4 1.19E+5 4.06E-1 Sr-92 9.52E+0 2.9?E+5 5.59E+5 8.OOE+1 Y-90 2.90E+3 3.20E+3 3.02E+1 1.42E-2 Y-91m 3.70E-1 2.94E+6 4.09E+5 1.77E+4 Y-91 6.61E+5
~~
2.6BE+4 1.65E+5 4.29E-1 Y-92 1.47E+1 8.32E+4 5.79E+5 3.72E+0 Y-93 1.35E+2 6.74E+4 2.69E+6 1.49E+5 3.15E+4 Zr-95 1.46E+5 4.58E+4 4.12E+1 1.30E+5 6.30E+5 1.26E+1 Zr-97 1.38E+2 2.72E+1 Nb-95 1.86E+4 1.03E+4 1.OOE+4 7.51E+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 1.69E+2 4.11E+2 1.54E+5 2.69E+5 3.22E+1 Mo-99 5.76E-2 1.15E+3 6.13E+3 4.99E-2 Tc-99m 1.38E-3 3.86E-3 Tc-101 5.92E-5 8.40E-5 1.52E-3 6.67E+2 8.72E-7 8.24E-4 DBP 6027A 72 Revision 10.0 ODCM
-.- -.=
~.. - -
l
?
A
~
Table 3-7 (continued) g,' Inhalation Pathway Dose Factors 3)Temrarme(continued)
R (area /yr per pCi/m
=
Liver Thyroid Kidney T-ggglida SI-Md.
T. Body Ru-103 ' 2.10E+3 7.43E+3 7.83E+5 1.09E+5 8.965+2 r
l Ru-105 1.12E+O 1.41E+0 1.82E+4 9.04E+4 4.345-1 l'
Ru-106 9.84E+4 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Rh-103m Rh-106 l
2.50E+4 6.75E+6 2.73E+5 7.99E+3 Ag-110m 1.38E+4 1.31E+4 3.85E+6 3.98E+5 1.68E+4 Sb-124 4.30E+4 7.94E+2 9.76E+1 2.74E+6 9.92E+4 1.72E+4 Sb-125 7.38E+4 0.08E+2 7.04E+1 5.36E+5 7.50E+4 6.67E+2 Te-125m' 4.88E+3 2.24E+3 1.40E+3 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3
-Te-127 2.01E+O 9.12E-1 1.42E+O 7.28E+O 1.12E+4 8.08E+4 4.42E-1 Te-129m 1.39E+4 6.5BE+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.25E+3 Te-129 7.10E-2 3.3BE-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 1.95E+3 4.49E+5 4.63E+5 2.19E+2 I-130 6.24E+3 1.79E+4 1.49E+6 2.75E+4 9.12E+3 7.17E+3 I-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 6.49H+3 2.64E+4 I-132 1.59E+3 4.38E+3 1.51E+5 6.92E+3 1.27E+3 1.58E+3 I-133
.1.22E+4 2.05E+4 2.92E+6 3.59E+4 1.03E+4 6.22E+3 I-134 8.88E+2 2.32E+3 3.95E+4 3.66E+3 2.04E+1 8.40E+2 I-135 3.70E+3 9.44E+3 6.21E+5 1.49E+4 6.95E+3 3.49E+3 3.75E+5 1.46E+5 9.76E+3 5.49E+5 0
Cs-134 5.02E+5 1.13E+6 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 1.21E+5 8.48E+3 3.11E+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-7 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 La-140 4.79E+2 2.36E+2 2.14E+5 4.87E+5 6.26E+1 La-142 9.60E 1 4.25E-1 1.02E+4 1.20E+4 1.06E-1 Ce-141 2.94E+4 1.90E+4
~
B.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 Ce-144 4.89E+6 2.02E+6 1.21E+6 1.34E+7 8.64E+5 2.62E+5 Pr-143 1.34E+4 5.31E+3 3.09E+3 4.83E+5 2.14E+5 6.62E+2 Pr-144 4.30E-2 1.76E-2 1.01E-2 1.75E+3 2.35E-4 2.18E-3 Nd-147 7.86E+3 8.56E+3 5.02E+3 3.72E+5 1.82E+5 5.13E+2 W-187 1.20E+1 9.76E+O 4.74E+4 1.77E+5 3.43E+0 Np-239 3.38E+2 3.19E+1 1.OOE+2 6.49E+4 1.32E+5 1.77E+1 DBP 6027A 73 Revision 10.0 ODCM
~~
1 Table 3-7 (continued) g, Inhalation Pathway Dose Fgetors - CEILD R
(arem/yr per pCi/m )
Nuclide none Liver Thyroid Kidney Luna GI-1.t 7 T. Body 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 H-3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 Na-24 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 1.61E+4 P-32 2.60E+6 1.14E+5 4.22E+4 9.88E&4 B.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Cr-51 4.29E+4 1.OOE+4 1.58E+6 2.29E+4 9.51E+3 Mn-54 1.67E+O 1.31E+4 1.23E+5 3.12E-1 1.66E+O Mn-56 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 5.075+5 1.32E+4 1.07E+3 9.03E+2 Co-57 Co-58 1.77E+3 1.11E+6 3.44E+4 3.16E+3 7.07E+6 9.62E+4 2.26E+4 1.31E+4 Co-60 Ni-63 8.21E+5 4.63E+4 2.75E+5 6.33E+3 2.80E+4 Ni-65 2.99E+O 2.96E-1 8.18E+3 8.40E+4 1.64E-1 6.03E+O 9.58E+3 3.67E+4 1.07E+0 1.99E+O Cu-64 Zn-65 4.26E+4 1.13E+5 7.14E+4 9.95E+5 1.63E+4 7.03E+4 5.85E-2 1.42E+3 1.01E+4 8.92E-3 Zn-69 6.70E-2 9.66E-2 Br-82 2.09E+4 Br-83 4.74E+2 Br-84 5.48E+2 j
Br-85 2.53E+1 1.98E+5 7.99E+3 1.14E+5 0
Rb-86 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 Sr-90 1.01E+8 1.48E+7 3.43E+5 6.44E+6 5.33E+4 1.74E+5 4.59E+0 Sr-91 1.21E+2 Sr-92 1.31E+1 2.40E+4 2.42E+5 5.25E-1 Y-90 4.11E+3 2.62E+5 2.68E+5 1.11E+2 Y-91m 5.07E-1 2.81E+3 1.72E+3 1.84E-2 2.63E+6 1.84E+5 2.44E+4 l
Y-91 9.14E+5 Y-92 2.04E+1 2.39E+4 2.39E+5 5.81E-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 6.11E+4 3.70E+4 Zr-97 1.88E+2 2.72E+1 3.89E+1 1.13E+5 3.51E+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 5.07E-2 9.51E+2 4.81E+3 5.77E-2 j
Tc-99m 1.78E-3 3.48E-3 Tc-101 8.10E-5 8.51E-5 1.45E-3 5.85E+2 1.63E+1 1.08E-3 DBP 6027A 74 Revision 10.0 ODCM
^
Table 3-7 (continued) g, Inhalation Pathway Dose Factors - GM hthueO R
3 (arem/yr per pci/m )
4 Nuclide B931 Liver Thyroid Kidney Luna GI-LLI T. Body 7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-103 2.79E+3 1.34E+0 1.59E+4 9.95E+4 5.555-1 Ru-105 1.53E+O 1.84E+5 1.43E+7 4.29E+5 1.69E+4 Ru-106 1.36E+5 Rb-103m Rh-106 2.12E+4 5.48E+6 1.OOE+5 9.14E+3 Ag-110m 1.69E+4 1.14E+4 i
Sb-124 5.74E+4 7.40E+2 1.26E+2 3.24E+6 1.64E+5 2.OOE+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 Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.48E+6 7.14E+4 3.02E+3 Te-127 2.77E+O 9.51E-1 1.96E+0 7.07E+O 1.OOE+4 5.62E+4 6.11E-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 Te-131m 1.34E+2 5.92E+1 9.77E+1 4.OOE+2 2.06E+5 3.OBE+5 5.07E+1 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 5.11E+3 8.44E+3 j
I-131 4.81E+4 4.81E+4 1.62E+7 7.88E+4 2.84E+3 2.73E+4 I-132 2.12E+3 4.07E+3 1.94E+5 6.25E+3 3.20E+3 1.8BE+3 I-133 1.66E+4 2.03E+4 3.85E+6 3.38E+4 5.48E+3 7.70E+3 J
I-134 1.17E+3 2.16E+3 5.07E+4 3.30E+3 9.55E+2 9.95E+2 I-135 4.92E+3 8.73E+3 7.92E+5 1.34E+4 4.442+3 4.14E+3 3.30E+5 1.21E+5 3.85E+3 2.25E+5 0
Cs-134 6.51E+5 1.01E+6 Cs-136 6.51E+4 1.71E+5 9.55E+4 1.45E+4 4.18E+3 1.16E+5 2.82E+5 1.04E+5 3.62E+3 1.28E+5 Cs-137 9.07E+5 8.25E+5 6.22E+2 6.81E+1 2.70E+2 5.55E+2 Cs-138 6.33E+2 8.40E+2 8.62E-4 5.77E+3 5.77E+4 5.37E-2 Ba-139 1.84E+0 9.84E-4 Ba-140 7.40E+4 6.48E+1 2.11E+1 1.74E+6 1.02E+5 4.33E+3 Ba-141 1.96E-1 1.09E-4 9.47E-5 2.92E+3 2.75E+2 6.36E-3 Ba-142 5.OOE-2 3.60E-5 2.91E-5 1.64E+3 2.74E+O 2.79E-3 l
1.83E+5 2.26E+5 7.55E+1 La-140 6.44E+2 2.25E+2 8.70E+3 7.59E+4 1.29E-1 La-142 1.30E+0 4.11E-1
~
8.55E+3 5.44E+5 5.66E+4 2.90E+3 Ce-141 3.92E+4 1.95E+4
~
Ce-143 3.66E+2 1.99E+2 8.36E+1 1.15E+5 1.27E+5 2.87E+1 Ce-144 6.77E+6 2.12E+6 1.17E+6 1.20E+7 3.89E+5 3.61E+5
{
Pr-143 1.85E+4 5.55E+3
- 3. DOE +3 4.33E+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.OOE-3 Nd-147 1.08E+4 8.73E+3 4.81E+3 3.28E+5 8.21E+4 6.81E+2 l
W-187 1.63E+1 9.66E+0 4.11E+4 9.10E+4 4.33E+O Np-239 4.66E+2 3.34E+1 9.73E+1 5.81E+4 6.40E+4 2.35E+1
-DBP 6027A 75 Revision 10.0 j
CDCM
,..- g.
~
s Table 3-7 (continued) g, Inhalation Pathway Dose Py) tors - INFANT R
(ares /yr per pCi/m Nuclide mana Liver Thyroid Kidney maa GI-LLI T. Body 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 E -
C-14 2.65E+4 5.31E+3
-5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 Na-24 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.06E+4 1.61E+4 7.74E+4 P-32 2.03E+6 1.12E+5 5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1 Cr-51 4.98E+3 1.00E+6 7.06E+3 4.98E+3 2.53E+4 Mn-54 1.54E+0 1.10E+0 1.25E+4 7.175+4 2.21E-1 Mn-56 8.69E+4 1.09E+3 3.33E+3 Fe-55 1.97E+4 1.17E+4 1.02E+6 2.48E+4 9.48E+3 Fe-59 1.36E+4 2.35E+4 3.798+5 4.86E+3 6.41E+2 Co-57 6.51E+2 7.77E+5 1.11E+4 1.82E+3 1.22E+3 Co-58 4.51E+6 3.19E+4 1.18E+4 8.02E+3 Co-60 2.09E+5 2.42E+3 1.16E+4 Ni-63 3.39E+5 2.04E+4 Ni-65 2.39E+O 2.84E-1 8.12E+3 5.01E+4 1.235-1 1.88E+O 3.982+O 9.3OE+3 1.50E+4 7.74E-1 Cu-64 3.25E+4 6.47E+5 5.14E+4 3.11E+4 Zn-65 1.93E+4 6.26E+4 Zn-69 5.39E-2 9.67E-2 4.02E-2 1.47E+3 1.32E+4 7.18E-3 1.33E+4 Br-82 Br-83 3.81E+2 4.OOE+2 Br-84 2.04E+1 Br-85 3.04E+3 8.82E+4 1
Rb-86 1.90E+5 Rb-88 3.39E+2 2.87E+2 5.57E+2 6.82E+1 2.06E+2 Rb-89 3.21E+2 2.03E+6 6.40E+4 1.14E+4 Sr-89 3.98E+5 1.12E+7 1.31E+5 2.59E+6 Sr-90 4.09E+7 5.26E+4 7.34E+4 3.46E+O Sr-91 9.56E+1 2.38E+4 1.40E+5 3.91E-1 Sr-92 1.05E+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-92 1.64E+1
'~
2.45E+6 7.03E+4 1.57E+4 Y-91 5.88E+5 2.45E+4 1.27E+5 4.61E-1 7.64E+4 1.67E+5 4.07E+O Y-93 1.50E+2 3.11E+4 1.75E+6 2.17E+4 2.03E+4 Zr 1.15E+5 2.79E+4 2.59E+1 1.10E+5 1.40E+5 1.17E+1 Zr-97 1.50E+2 2.56E+1 4.72E+3 4.79E+5 1.27E+4 3.78E+3 Nb-95 1.57E+4 6.43E+3 5.70E-2 3.32E+3 2.69E+4 2.63E-2 Nb-97 3.42E-1 7.29E-2 2.65E+2 1.35E+5 4.87E+4 3.23E+1 Mo-99 1.65E+2 Tc-99m 1.40E-3 2.8BE-3 3.11E-2 8.11E+2 2.03E+3 3.72E-2 9.79E-4 5.84E+2 8.44E+2 8.12E-4 Tc-101 6.51E-5 8.23E-5 DBP 6027A 76 Revision 10.0 ODCM
e
[N Table 3-7 (continued) io' Inhalation Pathway Dose Factors - INFANT (continued)
R (arem/yr per pCi/m )
Nuclide
- =*
Liver Thyroid Kidney Luna GI-LLI T. Body 4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-103 2.02E+3 8.99E-1 1.57E+4 4.84E+4 4.10E-1 Ru-105 1.22E+0 1.07E+5 1.16E+7 1.64E+5 1.09E+4 Ru-106 8.68E+4 Rh-103m-Rh-106 1.09E+4 3.67E+6 3.30E+4 5.OOE+3 Ag-110m 9.98E+3 7.22E+3 2.65E+6 5.91E+4 1.20E+4 Sb-124 3.79E+4 5.56E+2 1.C1E+2 1.64E+6 1.47E+4 1.09E+4 Sb-125 5.17E+4 4.77E+2 6.23E+1 Te-125m 4.76E+3 1.99E+3 1.62E+3 4.47E+5 1.29E+4 6.58E+2 Te-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 Te-127 2.23E+O 9.53E-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.OOE+3 2.63E+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.OOE-3 Te-132 3.72E+2 2.37E+2 2.79E+2 1.03E+3 3.40E+5 4.41E+4 1.76E+2 I-130 6.36E+3 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 I-132 1.69E+3 3.54E+3 1.69E+5 3.95E+3 1.90E+3 1.26E+3 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 4.45E+4 2.09E+3 1.29E+3 6.65E+2 1.83E+3 2.77E+3 I-135 3.86E+3 7.60E+3 6.96E+5 8.47E+3 1.90E+5 7.97E+4 1.33E+3 7.45E+4 C
Cs-134 3.96E+5 7.03E+5 Cs-136 4.83E+4 1.35E+5 5.64E+4 1.IBE+4 1.43E+3 5.29E+4 1.72E+5 7.13E+4 1.33E+3 4.55E+4 Cs-137 5.49E+5 6.12E+5 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 5.60E+1 1.34E+1 1.60E+6 3.84E+4 2.90E+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.OOE+2 1.68E+5 8.48E+4 5.15E+1 La-142 1.03E+O 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 1.99E+3 Ce-143 2.93E+2 1.93E+2 5.64E+1 1.16E+5 4.97E+4 2.21E+1 Ce-144 3.19E+6 1.21E+6 5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 1.40E+4 5.24E+3 1.97E+3 4.33E+5 3.72E+4 6.99E+2 Pr-144 4.79E-2 1.85E-2 6.72E-3 1.61E+3 4.28E+3 2.41E-3 Nd-147 7.94E+3 8.13E+3 3.15E+3 3.22E+5 3.12E+4 5.OOE+2 W-187 1.30E+1 9.02E+0 3.96E+4 3.56E+4 3.12E+O Np-239 3.71E+2 3.32E+1 6.62E+1 5.95E+4 2.49E+4 1.88E+1 DBP 6027A 77 Revision 10.0 ODCM
i 4
Table 3-8 Rg, Grass - Cow - Milk Pgthway Dose Factors - ADULT (mfem/yr per pCi/m ) for E-3 and C-14 i
(m
- mrem /yr per pci/sec) for others Nuclide Bone Liver Thyroid Kidney Lunir GI-LLI gg 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 H-3 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 2.54E+6 2.54E+6 2.54E+6 2.54E+6 P-32 1.71E+10 1.06E+9 1.S2E69 6.60E+8 Cr-51 1.71E+4 6.30E+3 3.80E+4 7.2OE+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 9.95E+6 4.04E+6 Fe-59 2.98E+7 7.OOE+7 1.95E+7 1.332+8 2.68E+7 Co-57 1.28E+6 3.25E+7 2.13E+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 4.66E+8 9.73E+7 2.26E+8 Ni-65 3.70E-1 4.81E-2 1.22E+O 2.19E-2 Cu-64 2.41E+4 6.08E+4 2.05E+6 1.13E+4 Zn-65 1.37E+9 4.36E+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 1
Rb-86 2.59E+9 5.11E+8 1.21E+9 Rb-88 Rb-89 Sr-89 1.45E+9 2.33E+8 4.16E+7 Sr-90 4.68E.10 1.35E+9 1.15E+10 Sr-91 3.13E 4 1.49E+5 1.27E+3 Sr-92 4.89E-1 9.68E+0 2.11E-2
/
Y-90 7,07E+1 7.50E+5 1.90E+O i
Y-91m
\\
Y-91 8.60E+3 4.73E+6 2.30E+2 Y-92 5.42E 5 9.49E-1 1.58E-6 Y-93 2.33E 1 7.39E+3 6.43E-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+1 4.54E+4 2.79E+8 2.47E+4 Nb-97 5.47E-9 Mo-99 2.52E+7 5.72E+7 5.35E+7 4.80E+6 Tc-99m 3.25E+0 9.19E+0 1.40E+2 4.5CE+0 5.44E+3 1.17E+2 Tc-101 DBP 6027A 78 Revision 10.0 ODCM
Table 3-8 g, Grass - Cow - Milk Pathway p) se Factors - ADULT (continued)
R (agem/yr per pCi/m for R-3 and C-14 (m
- mrem /yr per pCi/sec) for others Nuclide ha Liver Thyroid Kidney Lund GI-LLI T. Body l
3.89E+3 1.19E+5 4.39E+2 Ru-103 1.02E+3 5.24E-1 3.38E-4 1.11E-2 Ru-105 8.57E-4 1.32E+6 2.58E+3 3.94E+4 Ru-106 2.04E+4 Rh-103m Rh-106 2.20E+10 3.20E+7 1.06E+8 Ag-110m 5.83E+7 5.39E+7 2.00E+7 7.31E+8 1.02E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 1.58E+7 2.25E+8 4.86E+6 Sb-125 2.04E+7 2.28E+5.
2.08E+4 Te-125m 1.f3E+7 5.90E+6 4.90E+6 6.63E+7 6.50E+7 2.185+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 1.54E+8 5.58E+6 i
Te-127 6.72E+2 2.41E+2 4.98E+2 2.74E+3 5.30E+4 1.45E+2 3.04E+8 9.57E+6 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 Te-129 Te-131m 3.61E+5 1.77E+5 2.80E+3 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 1.12B+8 2.43E+9 I-132 1.64E-1 4.37E-1 1.53E+1 6.97E-1 8.22E-2 1.53E-1 6.20E+6 2.10E+6 I-133 3.97E+6 6.90E+6 1.01E+9 1.20E+7 I-134 I-135 1.39E+4 3.63E+4 2.40E+6 5.83E+4 4.10E+4 1.34E+4 0
4.35E+9 1.44E+9 2.35E+8 1.10E+10 Cs-134 5.65E+9 1.34E+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 1.01E+10 3.43E+9 1.14E+9 1.95E+8 6.61E+9 Cs-138 8.34E-8 1.38E-9 Ba-139 4.70E-8 Ea-140-2.69E+7-3.3BE+4 1.15E+4 1.93E+4 5.54E+7 1.76E+6 l
Ba-141 Ba-142 1.66E+5 E.??E-1 La-140 4.49E+O 2.26E+0
~~
3.03E-8 La-142 1.25E+7 3.71E+2 Ce-141 4.84E+3 3.27E+3 1.52E+3 Ce-143 4.19E+1 3.09E+4 1.36E+1 1.16E+6 3.42E+O Ce-144 3.58E+5 1.50E+5 8.87E+4 1.21E+8 1.92E+4 6.96E+5 7.88E+O Pr-143 1.59E+2 6.37E+1 3.68E+1 Pr-144 Nd-147 9.42E+1 1.09E+2 6.37E+1 5.23E+5 6.52E+0 1.80E+6 1.92E+3 W-187 6.56E+3 5.48E+3 Np-239 3.66E+0 3.60E-1 1.12E+0 7.39E+4 1.98E-1
.~
DBP 6027A 79 Revision 10.0 ODCM
~.
l l
Table 3-8 (continued)
R,, Grass - Cow - Milk Patp) y Dose Factors - TIENAGER g
(agem/yrperpCi/m for E-3 and C-14 (m
- mrom/yr per pCi/sec) for others Nuclide ha Liver Thyroid Kidney Lund GI T.f T T.aody i
l 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 H-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 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 4.44E+6 2.65E+9 1.22E+9 P-32 3.15E+10 1.95E+9 2.785+4 1.10E+4 7.13E+4 8.40E+6 5.OOE+4 Cr-51 2.87E+7 2.78E+6 4.17E+6 1.40E+7 l
Mn-54 4.94E-1 1.33E-3 7.51E-3 9.50E-3 Mn-56 2.OOE+7 1.37E+7 7.36E+6 Fe-55 4.45E+7 3.16E+7 3.82E+7 2.87E+8 4.68E+7 l
Fe-59 5.2OE+7 1.21E+8 4.19E+7 3.76E+6 2.25E+6 Co-57 1.10E+8 1.83E+7 Co-58 7.95E+6 3.62E+8 6.26E+7 2.78E+7 Co-60 1.33E+8 4.01E+8 Ni-63 1.18E+10 8.35E+8 4.70E+O 3.94E-2 Ni-65 6.78E-1 8.66E-2 3.33E+6 2.02E+4 1.09E+5 Cu-64 4.29E+4 4.68E+9 3.10E+9 3.41E+9 Zn-65 2.11E+9 7.31E+9 Zn-69
-5.64E+7 Br-82 1.91E-1 Br-83 Br-84 I
Br-85 7.OOE+8 2.22E+9 4.73E+9 Rb-86 Rb-88 Rb-89 3.18E+8 7.66E+7 Sr-89 2.67E+9 1.86E+9 1.63E+10 Sr-90 6.61E+10 2.61E+5 2.29E+3 Sr-91 5.75E+4 2.28E+1 3.81E-2 Sr-92 8.95E-1 1.07E+6 3.50E+O Y-90 1.3OE+2 Y-91m
~
6.48E+6 4.24E+2 Y-91 1.58E+4 2.75E+O 2.90E-6 Y 92 1.OOE-4 1.31E+4 1.18E-2 Y-93 4.30E-1 1.20E+6 3.59E+2 7.67E+2 Zr-95 1.65E+3 5.22E+2 4.15E+4 7.06E-2 2.32E-1 Zr-97 7.75E-1 1.53E-1 3.34E+8 4.3OE+4 7.57E+4 Nb-95 1.41E+5 7.80E+4 6.34E-8 Nb-97 8.16E+7 8.69E+6 1.04E+8 4.56E+7 Mo-99 Tc-99m 5.64E+0 1.57E+1 2.34E+2 8.73E+O 1.03E+4 2.04E+2 Tc-101
(
DBP 6027A 80 Revision 10.0 ODCM
Table 3-8 (continued)
I g, Grass - Cow - Milk Pathway Dp)e ' actors - TERIDGER (continued)
R (agen/yrperpci/m for E-3 and C-14 (m
- mres/yr per pci/sec) for others l
Nuclide Bone Liver Thyroid Kidney Lund GI-tmi T T. Body 6.40E+3 Ru-103 1.81E+3 1.52E+5 7.75E+2 1.97E-2 Ru-105 1.57E-3 1.26E+0 6.08E-4 7.23E+4 Ru-106 3.75E+4 1.80E+6 4.73E+3 Rh-103m Rh-106 j
Ag-110m 9.63E+7 9.11E+7 1.74E+8 2.56E+10 5.54E+7 Sb-124 4.59E+7 8.46E+5 1.04E+5 4.01E+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.OOE+7 1.08E+7 8.39E+6 8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 2.10E+8 1.OOE+7 Te-127 1.24E+3 4.41E+2 8.59E+2 5.04E+3 9.61E+4 2.68E+2 Te-129m 1.11E+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 l
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.OOE+5 7.03E+4 2.35E+4 1,
Cs-134 9.81E+9 2.31E+10 7.34E+9 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.OOE+4 7.49E+7 3.13E+6 Ba-141 Ba-142 La 140 8.06E+0 3.96E+0 2.27E+5 1.05E+O
~~
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 2.51E+1 1.68E+6 6.25E+O I
Ce-144 6.58E+5 2.72E+5 1.63E+5 1.66E+8 3.54E+4 4
1 Pr 143 2.92E+2 1.17E+2 6.77E+1 9.61E+5 1.45E+1 4
Pr-144 l
Nd-147 1.81E+2 1.97E+2 1.16E+2 7.11E+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 1
DBP 6027A 81 Revision 10.0 ODCM i
m.
___.___m
^
' aY
- 4:;
Table 3-8 (continued)
Grass - Cow - Milk Pp) y Dose Factors - CEILD Rg (ages /yrperpCi/m for E-3 and C-14 (m
- mrom/yr per pCi/sec) for others guelida ha Liver Thyroid Kidney Ltmd G I t T.T T. Body i
1.57E+3 1.57E+3 1.57E+3 1.575+3 1.57E+3 1.57E+3 H-3
'l C-14 1.65E+6 3.29E+5 3.298+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 9.23E+6 9.23E+6 9.23E+6 I
2.15E+9 3.00E+9 P-32 7.77E+10 3.64E+9 Cr-51 5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 2.09E+7 5.87E+6 1.76E+7 5.58E+6 Mn-54 1.90E+0 2.95E-3 1.58E-2 1.31E-2 Mn-56 Fe-55 1.12E+8 5.93E+7 3.35E+7 1.10E+7 1.84E+7 5.65E+7 2.03E+8 9.71E+7 Fe-59 1.2OE+8 1.95E+8 3.14E+7 7.77E+6 3.84E+6 Co-57 7.08E+7 3.72E+7 1.21E+7 3
Co-58 j
Co-60 2.39E+8 1.27E+8 4.32E+7 j.
Ni-63 2.96E+10 1.59E+9 1.07E+8 1.01E+9 Ni-65 1.66E+0 1.56E-1 1.91E+1 9.11E-2 3.54E+6 4.56E+4 1.82E+5 7.55E+4 4
Cu-64 6.94E+9 1.93E+9 6.85E+9 i'
Zn-65 4.13E+9 1.10E+10 l
Zn-69 2.1dE-9 1.15E+8 Br-82 i
Br-83 4.69E-1 i
Br-84
'~
Br-85 Rb-86 8.77E+9 5.64E+8 5.39E+9 Rb-88 Rb-89 2.56E+8 1.89E+8
)
Sr-89 6.62E,9 1.51E+9 2.83E+10 Sr-90 1.12E+11 3.12E+5 5.33E+3 Sr-91 1.41E+5 4.14E+1 8.76E-2 Sr-92 2.19E+O 9.15E+5 8.61E+O Y-90 3.22E+2 Y-91m
' ~
5.21E+6 1.04E+3 Y-91 3.91E+4 7.10E+O 7.03E-6 Y-92 2.46E-4 1.57E+4 2.90E-2 Y-93 1.06E+0 8.81E+5 7.52E+2 1.21E+3 Zr-95 3.84E+3 8.45E+2 3.91E-1 4.13E+4 1.61E-1 Zr-97 1.89E+0 2.72E-1 2.29E+8 8.84E+4 1.16E+5 Nb-95 3.18E+5 1.24E+5 Nb-97 1.45E-6 6.86E+7 2.05E+7 I
8.29E+7 1.77E+8 Mo-99 Tc-99m 1.29E+1 2.54E+1 3.68E+2 1.29E+1 1.44E+4 4.20E+2 Tc-101 DBP 6027A 82 Revision 10.0 ODCM
6 Table 3-8 (continued) g, Grass - Cow - Milk Pathway p) se Factors - CHILD (continued)
R (m{en/yrperpCi/m for R-3 and C-14 (m
- mrem /yr per pCi/sec) for others Nuclide Bone Liver Thsroid Kidney Lund GI-LLI T. Body 1.11E+5 1.65E+3 1.08E+4 Ru-103 4.29E+3 2.49E+O 1.39E-3 3.36E-2 Ru-105 3.82E-3 1.44E+6 1.15E+4 1.25E+5 Ru-106 9.24E+4 Rh-103m Rh 106 1.68E+10 1.13E+8 2.63E+8 Ag-110m 2.09E+8 1.41E+8 6.03E+7 6.79E+8 3.81E+7 Sb-124 1.09E+8 1.41E+8 2.40E+5 Sb-125 8.70E+7 1.41E+6 8.06E+4 4.85E+7 2.08E+8 1.82E+7 7.12E+7 9.84E+6 Te-125m 7.38E+7 2.OOE+7 2.07E+7
. 68E+6 2.47E+7 Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 1.20E+5 6.56E+2 Te-127 3.06Ec3 8.25E+2 2.12E+3 8.71E+3 3.32E+8 4.23E+7 Te-129m 2.7.g+8 7.61E+7 8.78E+7 8.OOE+8 6.12E-8 2.87E-9 Te-129 2.24E+7 5.89E+5 Te-131m 1.60E+6 5.53E+5 1.14E+6 5.35E+6 Te-131 4.55E+7 5.46E+6 Te-132 1.02E+7 4.52E+6 6.58E+6 4.20E+7 1.66E+6 1.82E+6 I-130 1.75E+6 3.54E+6 3.90E+8 5.29E+6 1.17E+8 7.46E+8 I-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 1.48E+0 5.80E-1 I-132 6.86E-1 1.26E+0 5.85E+1 1.93E+O 8.77E+6 8.23E+6 I-133 1.76E+7 2.18E+7 4.04E+9 3.63E+7 I-134 8.OOE+4 4.97E+4 3
I-135 5.84E+4 1.05E+5 9.30E+6 1.61E+5 Cs-134 2.26E+10 3.71E+10 1.15E+10 4.13E+9 2.OOE+8 7.83E+9 1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs-136 1.OOE+9 2.76E+9 Cs-137 3.22E+10 3.09E+10 1.01E+10 3.62E+9 1.93E+8 4.55E+9 l
Cs-138 i
1.23E-5 6.19E-9
'l Ba-139 2.14E-7 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+O 1.88E+5 2.27E+O
~
2.51E-6 La-142 1.36E+7 1.62E+3 Ce-141 2.19E+4 1.09E+4 4.78E+3 Ce-143 1.89E+2 1.02E+5 4.29E+1 1.50E+6 1.48E+1 Ce-144 1.62E+6 5.09E+5 2.82E+5 1.33E+8 8.t6E+4 Pr-143 7.23E+2 2.17E+2 1.17E+2 7.80E+5 3.59E+1 Pr-144 5.71E+5 2.79E+1 Nd-147 4.45E+2 3.60E+2 1.98E+2 i
2.42E+6 7.73E+3 W-187 2.91E+4 1.72E+4 Np-239 1.72E+1 1.23E+0 3.57E+O 9.14E+4 8.68E-1 DBP 6027A 83 Revision 10.0 ODCM
-Table 3-8 (continued) g, Grass - Cow - Milk Pa p) for E-3 and C-14 R
y Dose Factors - INFANT (ages /yrperpCi/m (m
- mrom/yr per pCi/sec) for others l
Nuclide ha Liver Thyroid Kidnav Lund G I-T.T.T T.nody 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 H-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 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 1.61E+7 P-32 1.60E+11 9.42E+9 2.17E+9 6.21E+9 1.05E+5 2.3OE+4 2.05E+5 4.71E+6 1.61E+5 Cr-51 i
3.89E+7 8.63E+6 1.43E+7 8.83E+6 Mn-54 3.21E-2 Mn-56 2.76E-2 2.91E+0 5.53E-3 Fe-55 1.35E+8 8.72E+7 4.27E+7 1.11E+7 2.33E+7 Fe-59 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+u Ni-63 3.49E+10 2.16E+9 1.07E+8 1.21E+9 Ni-65 3.51E+O 3.97E-1 3.02E+1 1.81E-1 Cu-64 1.88E+5 3.17E+5 3.85E+6 8.69E+4 Zn-65 5.55E+9 1.90E+10 9.23E+9 1.61E+10 B.78E+9 Zn-69 7.36E-9 Br-82 1.94E+8 Br-83 9.95E-1 Br-84 Br-85 Rb-86 2.22E+10 5.69E+8 1.10E+10 Rb-88 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 1.82E+1 Y-91m
~~
Y-91 7.33E+4 5.26E+6 1.95E+3 Y-92 5.22E-4 9.97E+O 1.47E-5 Y-93 2.25E+0 1.78E+4 6.13E-2 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 6.98E+7 4.13E47 Mo-99 2.12E+8 3.17E+8 Tc-99m 2.69E+1 5.55E+1 5.97E+2 2.90E+1 1.61E+4 7.15E+2 Tc-101
(
DBP 6027A 84 Revision 10.0 ODCM i
t
... ~ -. - - -
. =,
't
's b
Table 3-8 (continued)
R Orass - Cow - Milk Pathway p)se Factors - INFANT (continued) gg, (ages /yrperpCi/m for E-3 and C-14
)
(m
- mrom/yr per pCi/sec) for others Nuclide mana Liver Thyroid Eidney inaS
'GI-f17 h
Ru-103 8.69E+3 t
1.81E+4 1.065+5 2.91E+3 Ru-105 8.06E-3 5.92E-2
- 3. 21E+O 2.71E-3 Ru-IO6 1.90E+5' 2.25E+5 1.44E+6 2.38E+4 Rh-103m Rh-106 Ag-110m 3.86E+8 2.82E+8 4.03E+8 1.465+10 1.86E+8 Sb-124 2.09E+8 3.0SE+C 5.56E+5 1.31E+8 6.46E+8 6.49E+7 l
Eb-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 t
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 3.34E+8 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 I
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 1
I-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 1.15E+8
-1.41E+9 i
I-132 1.42E+0 2.89E+0 1.35E+2 3.22E+0 2.34E+0 1.03E+O I-133 3.72E+7 5.41E+7 9.84E+9 6.36E+7 9.16E+6 1.58E+7 1
j 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 1
Cs-134 3.65E+10 6.80E+10 1.75E+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 j
Cs-138 Ba-139 4 ~. 5 5E-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 Ba-141 Ba-142
[
La-140 4.03E+1 1.59E+1 La-142
'~
1.87E+5 4.09E+O 5.21E-6 Ce-141 4.33E+4 2.64E+4.
8.15E+3 1.37E+7 3.11E+3 j
Ce-143 4.OOE+2 2.65E+5 7.72E+1 1.55E+6 3.02E+1 Ce-144 2.33E+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 7.41E+1 Pr-144 Nd-147 8.82E+2 9.06E+2 3.49E+2 5.74E+5 5.55E+1 W-187 6.12E+4 4.26E+4 2.50E+6 1.47E+4 4
Np-239 3.64E+1 3.25E+O 6.49E+0 9.40E+4 1.84E+O l
i DBP 6027A 85 Revision 10.0 ODCM l
J
s s..
t
- 1-5
\\
T s
Table 3-9 g, Grass - Cow - Meat Pp) for E-3 and C-14 y Dose Factors - ADULT R
(ages /yrperpCi/m (m
- mrom/yr per pCi/sec) for others Nuclide ha=
Liver Thyroid Kidney Tnan GI f.f,T T. Body 3.25E+2 3.25E+2 3.25E+2 3.25E+2 3.25F+2 3.25E+2 E-3 I
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 5.23E+8 1.80E+8 P-32 4.65E+9 2.89E+8 4.22E+3 1.56E+3 9.38E+3 1.785+6 7.07E+3 Cr-51 2.80E+7 1.75E+6
)
2.72E+6 9.15E+6 Mn-54 Mn-56 1.13E+8 1.16E+8 4.72E+7 Fe-55 2.93E+8 2.02E+8 1.75E+8 2.09E+9 2.40E+8 Fe-59 2.67E+8 6.27E+8 1.43E+8 9.37E+6 5.64E+6 Co-57 3.70E+8 4.10E+7 Co-58 1.83E+7 1.41E+9 1.66E+8 7.52E+7 Co-60 2.73E+8 6.33E+8 Ni-63 1.89E+10 1.31E+9 Ni-65 2.52E-5 1.39E-7 7.45E-7 Cu-64 2.95E-7 7.13E+8 5.12E+8 7.57E+8 Zn-65 3.56E+8 1.13E+9 Zn-69 1.44E+3 1.26E+3 Br-82 Br-83 Br-84
'~
Br-85 9.60E+7 2.27E+8 Rb-86 4.87E+8 Rb-88 Rb-89 4.84E+7 8.65E+6 Sr.89 3.01E+8 3.59E+8 3.05E+9 S.
90 1.24E+10 Sr-91 1.38E-9 Sr-92 Y-90 1.07E+2 1.13E+6 2.86E+0 Y-91m Y-91 1.13E+6 6.24E+8 3.03E+4 Y-92 2.08E-7 Y-93 9.48E+5 1.91E+9 4.09E+5 Zr-95 1.88E+6 6.04E+5 1.14E+O 1.693-6 5.58E-6 Zr-97 1.83E-5 3.69E-6
~
Nb-95 2.29E+6 1.28E+6 1.26E+6 7.75E+9 6.86E+5 Nb-97 2.52E+5 2.07E+4 Mo-99 1.09E+5 2.46E+5 Tc-99m Tc-101 DBP 6027A 86 Revision 10.0 i
(.
Table 3-9 R,, Grass - Cow - Meat Pathway p) se Factors - ADULT (continued) g (agem/yrperpCi/m for E-3 and C-14 (m
- mram/yr per pCi/sec) for others Nuclide Baa.
Liver Thyroid Kidney Lund GI-LLY T.aody 1
l 1.23E+10 4.55E+7 l
4.03E+8 Ru-103 1.06E+8 Ru-105 1.81E+11 3.54E+8 5.40E+9 Ru-106 2.80E+9 Rh-103m Rh-106 1.22E+7 2.52E+9 3.67E+6 Ag-110m 6.69E+6 6.19E+6 1.54E+7 5.62E+8 7.85E+6 Sb-124 1.9BE+7 3.74E+5 4.80E+4 1.47E+7 2.10E+8 4.54E+6 Sb-125 1.91E+7 2.13E+5 1.94E+4 1.43E+9 4.81E+7 Te-125m 3.59E+8 1.30E+8 1.08E+8 1.46E+9 3.74E+9 1.36E+8 Te-127m 1.12E+9 3.99E+8 2.85E+8 4.53E+9 2.10E-8 1.09E-9 Te-127 Te-129m 1.14E+9 4.27E+8 3.93E+8 4.77E+9 5.76E+9 1.81E+8 Te-129 2.19E+4 1.84E+2 Te-131m 4.51E+2 2.21E+2 3.50E+2 2.24E+3 Te-131 Te-132 1.40E+6 9.07E+5 1.OOE+6 8.73E+6 4.29E+7 8.51E+5 5.98E-6 2.74E-6 I-130 2.35E-6 6.94E-6 5.8BE-4 1.08E-5 I-131 1.08E+7 1.54E+7 5.05E+9 2.64E+7 4.07E+6 8.83E+6 I-132 I-133 4.30E-1 7.47E-1 1.10E+2 1.3OE+O 6.72E-1 2.28E-1 I-134 I
I-135 Cs-134 6.57E+8 1.56E+9 5.06E+8 1.68E+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 7.81E+8 Cs-138 Ba-139 Ba-140 2.88E+7 3.61E+4 1.23E+4 2.07E+4 5.92E+7 1.89E+6 Ba-141i Ba-142 1.33E+3 4.79E-3 La-140 3.60E-2 1.81E-2
~~
La-142 4.40E+3 3.62E+7 1.08E+3 Ce-141 1.40E+4 9.4BE+3 6.80E-3 5.78E+2 1.71E-3
)
Ce-143 2.09E-2 1.55E+1 i
l Ce-144 1.46E+6 6.09E+5 3.61E+5 4.93E+8 7.83E+4 i
9.33E+7 1.06E+3 Pr-143 2.13E+4 8.54E+3 4.93E+3 Pr 144 Nd-147 7.08E+3 8.18E+3 4.78E+3 3.93E+7 4.90E+2 W-187 2.16E-2 1.81E-2 5.92E+0 6.32E-3 7.84E-2 5.15E+3 1.39E-2 Np-239 2.56E-1 2.51E-2 DBP 6027A 87 Revision 10.0 ODCM
Table 3-9 (continued) g, Grass-Cow-MeatPatgw)ayDoseFactors-TEENAGER R
(ages /yrperpCi/m for E-3 and C-14 (m
- mrem /yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidnav Lund GI-ilf T. Body 1.94E+2 1.94E+2 1.94E+2 1.94E+2 1.94E+2 1.94E+2 H-3 C-14 2.81E+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 3.93E+9 2.44E+8 3.3OE+8 1.52E+8 3.14E+3 1.24E+3 8.07E+3 9.50E+5 5.65E+3 Cr-51 2.08E+6 1.43E+7 1.3BE+6 6.98E+6 Mn-54 Mn-56 1.07E+8 7.30E+7 3.93E+7 Fe-55 2.38E+8 1.69E+8 1.57E+8 1.18E+9 1.92E+8 Fe-59 2.13E+8 4.SBE+8 8.45E+7 7.59E+6 Co-57 4.53E+6 1.94E+8 3.25E+7 1.41E+7 Co-58 5.83E+7 7.60E+8 1.31E+8 Co-60 Ni-63 1.52E+10 1.07E+9 1.71E+8 5.15E+8 Ni-65 2.41E-7 6.10E-7 1.87E-5 1.13E-7 Cu-64 3.6BE+8 4.05E+8 Zn-65 2.50E+8 8.69E+8 5.56E+8 Zn-69 Br-82 9.98E+2 Br-83 Br-84 C
Br-85 Rb-86 4.06E+8 6.01E+7 1.91E+8 Rb-88 Rb-89 3.03E+7 7.29E+6 Sr-89 2.54E+8 2.26E+8 1.99E+9 Sr-90 8.05E+9 1.10E-9 Sr-91 Sr-92 Y-90 8.98E+1 7.40E+5 2.42E+O y.91m
~~
3.92E+8 2.56E+4 Y-91 9.56E+5 y.92 1.69E-7 Y-93 6.99E+5 1.10E+9 3.27E+5 Zr-95 1.51E+6 4.76E+5 8.18E-1 1.39E-6 4.58E-6 Zr-97 1.53E 5 3.02E-6 4.25E+9 5.47E+5 tTb-95 1.19E*6 9.94E+5 9.64E+5 Nb-97 8.98E+4 2.06E+5 1.61E+5 1.71E+4 Mo-99 Tc-99m Tc-101 DBP 6027A 88 Revision 10.0 ODCM
~
-- - -. - - ~.
n 1
a Table 3-9 (continued) g, Grass - Cow - Meat Pathway Dp)e Factors - Tenranza (continued)
]
R (agen/yrperpCi/m for H-3 and C-14 (m
- mram/yr per pCi/sec) for others J
Muclida mene Liver Tnvroid Kidnav Lund aI-i.t T T.nody 3.03E+8 Ru-103 8.60E+7 7.18E+9 3.688+7 Ru-105 Ru-106 2.36E+9 4.55E+9 1.13E+11 2.97E+8 I
Rh-103m Rh-106 1.35E+9 2.91E+6 Ag-110m 5.06E+6 4.79E+6 9.14E+6 2
Sb-124 1.62E+7 2.98E+5 3.67E+4 1.41E+7 3.26E+8 6.31E+6 1.37E+7 1.22E+8 3.66E+6
- Sb-125 1.565+7 1.71E+5 1.49E+4 8.94E+8 4.05E+7 I
Te-125m 3.03E+8 1.09E+8 8.47E+7 3
Te-127m 9.41E+8 3.34E+8 2.24E+8 3.82Ee9 2.35E+9 1.12E+8 1.75E-8 Te-127 Te-129m 9.58E+8 3.56E+8 3.09E+8 4.01E+9 3.60E+9 1.52E+8 Te-129 i
Te-131m 3.76E+2 1.80E+2 2.71E+2 1.88E+3 1.45E+4 1.50E+2 l
Te-131 Te-132 1.15E+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 I-131 8.95E+6 1.25E+7 3.66E+9 2.16E+7 2.48E+6 6.73E+6' 4
I-132 i
I-133 3.59E-1 6.10E-1 8.51E+1 1.07E+0 4.61E-1 1.86E-1 I-134 I-135
- ~-
Cs-134 5.23E+8 1.23E+9 3.91E+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 9.63E+8 3.28E+8 1.27E+8 1.37E+7 3.36E+8 Cs-138 Ba-139 Ba-140 2.38E+7 2.91E+4 9.88E+3 1.96E+4 3.67E+7 1.53E+6 Ba-141 Ba-142 La-140 2.96E-2 1.45E-2 8.35E+2 3.87E-3
~
La-142 Ce-141 1.18E+4 7.86E+3 3.70E+3 2.25E+7 9.03E+2 Ce-143 1.76E-2 1.28E+1 5.74E-3 3.85E+2 1.43E-3 Ce-144 1.23E+6 5.08E+5 3.04E+5 3.09E+8 6.60E+4 Pr-143 1.79E+4 7.15E+3 4.16E+3 5.90E+7 8.92E+2
- Pr-144 Nd-147 6.24E+3 6.79E+3 3.98E+3 2.45E+7 4.06E+2 W-187 1.81E-2 1.48E-2 3.99E+0 5.17E-3 Np-239 2.23E-1 2.11E-2 6.61E-2 3.39E+3 1.17E-2 DBP 6027A 89 Revision 10.0 ODCM l
l i
n t
Table 3-9 (continued) g,~ Grass - Cow - Meat Pgthway Dose Factors - CHILD R
(ages /yr per pCi/m ) for H-3 and C-14 (m
- tarem/yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lunir GI-LLI
'r. Body 2.34E+2 2.34E+2 2.34E+2 2.34E+2 2.34E+2 2.34E+2 H-3 C-14 5.29E+5 1.06E+5 1.06E+5 1.06E+5 1.06E+5 1.06E+5 1.06E+5 i
Na-24 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.345-3 2.05E+8 2.86E+8 P-32 7.41E+9 3.47E+8 4.89E+3 1.34E+3 8.93E+3 4.67E+5 8.81E+3 Cr-51 6.70E+6 2.13E+6 2.24E+6 Ma-54 7.99E+6 Mn-55 1.37E+8 4.49E+7 7.51E+7 Fe-55 4.57E+8 2.42E+8 i
1.77E+8 6.37E+8 3.05E+8 Fe-59 3.78E+8 6.12E+8 4.85E+7 1.20E+7 5.92E+6 Co-57 j
9.60E+7 5.04E+7 1.65E+7 Co-58 3.84E+8 2.04E+8 6.93E+7 Co-60 1.OSE+8 9.91E+8 Ni-63 2.91E+10 1.56E+9 Ni-65 1.52E 5 1.9/L-7 Cu-64 3.24E-7 7.82E-7 Zn-65 3.75E+8 1.OOE+9 6.30E+8 1.75E+8 6.22E+8 Zn-69 Br-82 1.56E+3 Br-83 Br-84 Br-85
',~.
I 3.71E+7 3.54E+8 Rb-86 5.76E+8 Rb-88 Rb-89 Sr-69 4.82E+8 1.86E+7 1.38E+7 Sr-90 1.04E+10 1.40E+8 2.64E+9 Sr-91 1.01E-9 Sr-92 4.84E+5 4.55E+O Y-90 1.70E+2 Y-91m
~
Y-91 1.81E+6 2.41E+8 4.83E+4 Y-92 1.55E-7 Y-93 6.14E+8 5.24E+5 8.43E+5 Zr-95 2.68E+6 5.89E+5 6.21E-1 2.42E-6 5.89E-6 Zr-97 2.84E-5 4.10E-6 2.23E+9 8.61E+5 Nb-95 3.09E+6 1.20E+6 1.13E+6 Nb-97 Mo-99 1.25E+5 2.67E+5 1.03E+5 3.09E+4 Tc-99m Tc-101 DBP 6027A 90 Revision 10.0 ODCM
- i Table 3-9 (continued) g, Grass - Cow - Meet Pathway p) se Factors - CEILD (continued)
R (agen/yrperpCi/m for H-3 and C-14 (m
- mrem /yr per pci/sec) for others Nuclide Bone Liver Thyroid Kidney Lund GI-T. Body 4.02E+9 5.98E+7 3.92E+8 Ru-103 1.56E+8 Ru-105 6.90E+10 5.54E+8 5.99E+9 Ru-106 4.44E+9 Rh-103m Rh-106 6.75E+8 4.53E+6 1.06E+7 Ag-110m B.40E+6 5.67E+6 Sb-124 2.93E+7 3.80E+5 6.46E+4 1.62E+7 1.83E+8 1.03E+7 1.59E+7 6.80E+7 5.96E+6 Sb-125 2.85E+7 2.19E+5 2.64E+4 5.49E+8 7.59E+7 Te-125m 5.69E+8 1.54E+8 1.60E+8 1.44E+9 2.11E+8 Te-127m 1.77E+9 4.78E+8 4.24E+8 5.06E+9 1.66E-8 1.21E-9 Te-127 2.20E+9 2.80E+8 Te-129m 1.81E+9 5.04E+8 5.82E+8 5.30E+9 Te-129 9.82E+3 2.58E+2 Te-131m 7.OOE+2 2.42E+2 4.98E+2 2.34E+3 Te-131 Te-132 2.09E+6 9.27E+5 1.35E+6 8.60E+6 9.33E+6 1.12E+6 3.2OE-6 3.53E-6 I-130 3.39E-6 6.85E-6 7.54E-4 1.02E-5 I-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+O 3.33E-1 3.12E-1 I-134 I-135 I
Cs-134 9.22E+8 1.51E+9 4.69E+8 1.68E+8 8.15E+6 3.19E+8 Cs-136
- .59E+7 4.37E+7 2.33E+7 3.47E+6 1.54E+6 2.83E+7 4.16E+8 1.50E+8 7.99E+6 1.8BE+8 Cs-137 1.33E+9 1.28E+9 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 1=1 Ba-142 5.27E+2 6.38E-3 La-140 5.41E 2 1.89E-2
^~
La 142 Ce 141 2.22E+4 1.11E+4 4.84E+3 1.38E+7 1.64E+3 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 3.66E+7 1.68E+3 Pr 143 3.39E+4 1.02E+4 5.51E+3 Pr-144 Nd 147
- .17E+4 9.48E+3 5.20E+3 1.50E+7 7.34E+2 W-187 3.36E-2 1.99E-2 2.79E+O 8.92E-3 2.23E+3 2.12E-2 Np 239 4.20E-1 3.02E-2 8.73E-2 g
DBP 6027A 91 Revision 10.0 ODCM
-.. - - ~ _ _.
e Table 3-10 Vegetation Path Dose Factors - ADULT R
g,(agem/yr per pCi/y) m for E-3 and C-14 (m
- mrom/yr per pC1/sec) for others Nuclide Bona Liver Thyroid Kidney Ltm$
GI-I.t T T.Rody 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 H-3 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 Na-24 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 2.76E+5 1.583+8 5.42E+7 P-32 1.40E+9 8.73E+7 2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 Cr-51 9.27E+7 9.54E+8 5.94E+7 3.11E+C Mn-54 Mn-56 1.61E+1 2.04E+1 5.13E+2 2.85E+0 8.06E+7 8.29E+7 3.37E+7 Fe-55 2.09E+8 1.45E+8 8.35E+7 9.96E+8 1.14E+8 l
Fe-59 1.27E+0 2.99E+8 2.97E+8 1.95E+7 1.17E+7 Co-57 l
6.26E+8 6.92E+7 3.09E+7 Co-58 3.14E+9 3.69E+8 1.67E+8 Co-60 Ni-63 1.04E+10 7.21E+8 1.50E+8 3.49E+8 Ni 6.15E+1 7.99E+0 2.03E+2 3.65E+O Cu-64 9.27E+3 2.34E+4 7.90E+5 4.35E+3 Zn-65 3.17E+8 1.01E+9 6.75F 8 6.36E+8 4.56E+8 Zn-69 8.75E-6 1.67E-5 1.09E-5 2.51E-6 1.16E-6 1.73E+6 1.51E+6 Br-82 4.63E+0 3.21E+0 Br-83 Br-84 1
C 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 4
1.41E+8 3.56E+2 Y-90 1.33E+4 Y-91m 5.83E-9 1.71E-8
'~
Y-91 5.13E+6 2.82E+9 1.37E+5 1.58E+4 2.63E-2 Y-92 9.01E-1 5.52E+6 4.80E+0 Y-93 1.74E+2 1.21E+9 2.58E+5 Zr-95 1.19E+6 3.81E+5 5.97E+5 1.02E+2 2.08E+7 3.08E+1 Zr-97 3.33E+2 6.73E+1 4.80E+8 4.2SE+4 Nb-95 1.42E+5 7.91E+4 7.81E+4 B.56E-7 2.71E-3 2.68E-7 Nb-97 2.90E-6 7.34E-7 1.45E+7 1.19E+6 Mo-99 6.25E+6 1.41E+7 1.32E+2 4.24E+O 5.12E+3 1.10E+2 Tc-99m 3.06E+O 8.66E+O Tc-101
. ~~
DBP 6027A 92 Revision 10.0 ODCM
q l
m.
i Table 3-10 (continued)
Vegetation Pathway Dosg) Factors - ADULT (continued)
Rg (m{em/yrperpCi/m for E-3 and C-14 (m
- mram/yr per pC1/sec) for others Nuclide Bone Liver Thyroid Ki h v Lund GI-LLY T. Body 1.83E+7 5.61E+8 2.07E+6 Ru-103 4.80E+6 6.96E+2 3.30E+4 2.13E+1 Ru-105 5.39E+1 3.72E+8 1.25E+10 2.44E+7 Ru-106 1.93E+8 Rh-103m r
Rh-106 1.92E+7 3.98E+9 5.80E+6 Ag-110m 1.06E+7 9.76E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 8.08E+7 2.95E+9 4.11E+7 1.03E+8 1.50E+9 3.25E+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 3.86E+8 1.29E+7 1.17E+9 4.26E+7 Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 4.54E+5 1.25E+3 Te-127 5.76E+3 2.07E+3 4.27E+3 2.35E+4 Te-129m 2.55E+B 9.50E+7 8.75E+7 1.06E+9 1.28E+9 4.03E+7 5.02E-4 1.62E-4 Te-129 6.65E-4 2.50E-4 5.10E-4 2.79E-3 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 1.01E+6 4.61E+5 I-130 3.96E+5 1.17E+6 9.90E+7 1.82E+6 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 3.31E+6 1.12E+6 I-133 2.12E+6 3.69E+6 5.42E+8 6.44E+6 I-134 1.06E-4 2.88E-4 5.OOE-3 4.59E-4 2.51E-7 1.03E-4 1.21E+5 3.94E+4 I
I-135 4.08E+4 1.07E+5 7.04E+6 1.71E+5 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 2.95E+9 9.81E+8 1.68E+8 5.70E+9 Cs-137 6.36E+9 8.70E+9 Cs-138 1.96E-5 1.19E-5 5.23E-2 8.64E-4 Ba-139 2.95E-2 2.10E-5 Ba-140 1.29E+8 1.62E+5 5.49E+4 9.25E+4 2.65E+8 8.43E+6 Ba-141 Ba-142 7.28E+7 2.62E+2 La-140 1.97E+3 9.92E+2 4.64E-1 1.58E-5 La-142 1.40E-4 6.35E-5 5.08E+8 1.51E+4 Ce-141 1.96E+5 1.33E+5 6.17E+4 2.77E+7 8.21E+1 Ce-143 1.OOE+3 7.42E+5 3.26E+2 8.16E+6 1.11E+10 1.77E+6 Ce-144 3.29E+7 1.38E+7 Pr-143 6.34E+4 2.54E+4 1.47E+4 2.78E+8 3.14E+3 Pr-144 2.2SE+4 1.85E+8 2.31E+3 Nd-147 3.34E+4 3.86E+4 1.05E+7 1.12E+4 W-187 3.82E+4 3.19E+4 Np-2;9 1.42E+3 1.40E+2 4.37E+2 2.87E+7 7.72E+1 DBP 6027A 93 Revision 10.0 ODCM
Table 3-10 (continued) g, Vegetation Pathway Mee Factors - m n R
3 (gem /yr per pCi/m ) for E-3 and C-14 (m
- mrom/yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lund GI-LLI T. Body 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 H-3 C-14 1.45E+6 2.51E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 1.91E+5 Na-24 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 1.35E+8 6.23E+7 P-32 1.61E+9 9.96E+7 3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Cr-51 9.27E+8 8.97E+7 1.35E+8 4.52E+8 Mn-54 Mn-56 1.45E+1 1.83E+1 9.54E+2 2.58E+0 1.46E+8 9.98E+7 5.38E+7 Fe-55 3.25E+8 2.31E+8 1.33E+8 9.98E+8 1.63E+8 Fe-59 1.81E+8 4.22E+8 1.79E+7 3.34E+8 3.OOE+7 Co-57 6.04E+8 1.01E+8 Co-58 4.38E+7 3.24E+9 5.60E+8 Co-60 2.49E+8 Ni-63 1.61E+10 1.13E+9 1.81E+8 5.45E+8 3.97E+2 3.33E+O Ni-65 5.73E+1 7.32E+0 6.51E+5 3.95E+3 Cu-64 8.40E+3 2.12E+4 Zn-65 4.24E+8 1.47E+9 9.41E+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-84
~
Br-85 Rb-86 2.73E+8 4.05E+7 1.28E+8 Rb-88 Rb-89 1.80E+9 4.33E+8 Sr-89 1.51E+10 2.11E+10 1.85E+11 Sr-90 7.51E+11 Sr-91 2.99E+5 1.36E+6 1.19E+4 1.01E+4 1.69E+1 Sr-92 3.97E+2 Y-90 1.24E+4 1.02E+8 3.34E+2 2.56E-7 Y-91m 5.43E-9
~~
3.23E+9 2.11E+5 Y-91 7.87E+6 Y-92 8.47E-1 2.32E+4 2.45E-2 4.98E+6 4.47E+O Y-93 1.63E+2 8.07E+5 1.27E+9 3.78E+5 Zr-95 1.74E+6 5.49E+5 Zr-97 3.09E+2 6.11E+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 l
Nb-97 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 1.12E+2 4.19E+O 4.95E+3 9.77E+1 Tc-99m 2.70E+0 7.54E+0 Tc-101 DBP 6027A 94 Revision 10.0 ODCM l
~-.
1' r
Table 3-10 (continued) g Vegetation Pathway Dose { actors - TEENAGER (continued)
R (mges/yr per pCi/m ) for H-3 and C-14 (m
- mrem /yr per pCi/sec) for others 3
Nuclide Bone Liver Thyroid Kidnav Lundr GI-LLI T. Body Ru-103 6.87E+6 2.42E+7 5.74E+8 2.94E+6 Ru-105 5.OOE+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 4.04E+9 8.74E+6 I
Ag-110m 1.52E+7 1.44E+7 2.74E+7 1.35E+8 3.11E+9 6.03E+7 Sb-124 1.55E+8 2.85E+6 3.51E+5 Sb-125 2.14E+8 2.34E+6 2.04E+5 1.88E+8 1.66E+9 5.OOE+7 4.37E+8 1.98E+7 Te-125m 1.48E+8 5.34E+7 4.14E+7 Te-127m 5.51E+8 1.9EE+8 1.31E+8 2.24E+9 1.37E+9 6.56E+7 4.19E+5 1.17E+3 Te-127 5.43E+3 1.92E+3 3.74E+3 2.20E+4 1.38E+9 5.81E+7
)
Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 Te-129 6.22E-4 2.32E-4 4.45E-4 2.61E-3 3.40E-3 1.51E-4 3.25E+7 3.38E+5 Te-131m 8.44E+5 4.05E+5 6.09E+5 4.22E+6 Te-131 Te-132 3.90E+6 2.47E+6 2.60E+6 2.37E+7 7.82E+7 2.32E+6 7.87E+5 4.09E+5 I-130 3.54E+5 1.02E+6 8.35E+7 1.58E+6 2.13E+7 5.79E+7 I-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 I-132 5.18E+1 1.36E+2 4.57E+3 2.14E+2 5.91E+1 4.87E+1 2.53E+6 1.02E+6 I-133 1.97E+6 3.34E+6 4.66E+8 5.86E+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 3i Cs-134.
7.09E+9 1.67E+10 5.30E+9 2.02E+9 2.00E+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 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 Ce-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
?.55E+3 Pr-144 1.42E+8 2.36E+3 Nd-147 3.63E+4 3.94E+4 2.32E+4 W-187 3.55E+4 2.90E+4 7.84E+6 1.02E+4 2.10E+7 7.24E+1 4.09E+2 Np-239 1.38E+3 1.30E+2 DBP 6027A 95 Revision 10.0 ODCM
Table 3-10 (continued)
R Vegetation Pathwy Does Factors - CHILD
'(ges/yrperpCi/m) for E-3 and C-14 (m
- mrea/yr per pCi/sec) for others Nuclide naam Liver Thyroid Kidney f=A GI-t.tT T.aody 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 H-3 C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 Na-24 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 3.83E+5 9.30E+7 1.3OE+8 P-32 3.37E+9 1.58E+8 6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 Cr-51 5.55E+8 1.76E+8 1.85E+8 Mn-54 6.61E+8 2.75E+3 4.28E+O 2.29E+1 1.90E+1 Mn-56 2.40E+8 7.86E+7 1.31E+8 Fe-55 8.OOE+8 4.24E+8 1.88E+8 6.76E+8 3.23E+8 Fe-59 4.01E+8 6.49E+8 2.45E+8 6.04E+7 2.99E+7 Co-57 3.77E+8 1.98E+8 6.47E+7 Co-58 2.10E+9 1.12E+9 3.78E+8 Co-60 1.42E+8 1.34E+9 Ni-63 3.95E+10 2.11E+9 1.21E+3 5.77E+0 Ni-65 1.05E+2 9.89E+O 2.68E+4 5.20E+5 6.69E+3 Cu-64 1.11E+4 3.80E+8 1.35E+9 Zn-65 8.12E+8 2.16E+9 1.36E+9 1.38E-3 2.02E-6 Zn-69 1.51E-5 2.18E-5 1.32E-5 2.04E+6 Br-82 Br-83 5.55E+0
)
Br-84 1
Br-85 2.91E+7 2.78E+8 Rb-86 4.52E+8 Rb-88 Rb-89 1.39E+9 1.03E+9 Sr-89 3.59.E+10 Sr-90 1.24E+12 1.67E+10 3.15E+11 1.21E+6 2.08E+4 Sr-91 5.50E+5 Sr-92 7.28E+2 1.38E+4 2.92E+1 6.56E+7 6.17E+2 Y-90 2.30E+4 1.95E-5 Y-91m 9.94E-9
~~
2.49E+9 5.01E+5 Y-91 1.87E+7 Y-92 1.56E+0 4.51E+4 4.46E-2 4.48E+6 8.25E+O Y-93 3.01E+2 8.95E+8 7.64E+5 Zr-95 3.90E+6 8.58E+5 1.23E+6 1.17E+2 1.23E+7 4.81E+1 Zr-97 5.64E+2 8.15E+1 2.95E+8 1.14E+5
~
Nb-95 4.10E+5 1.59E+5 1.50E+5 2.73E-1 4.13E-7 Nb-97 4.90E-6 8.85E-7 9.82E-7 Mo-99 7.83E+6 1.67E+7 6.48E+6 1.94E+6 Tc-99m 4.65E+O 9.12E+0 1.33E+2 4.63E+0 5.19E+3 1.51E+2 Tc-101 DBP 6027A 96 Revision 10.0 ODCM m
I*
~ ~ -_ -
m.
~l Table 3-10 (continued)
Vegetation Pathway Dosg) Factors - CHILD (continued)
Rgg' (ages /yrperpCi/m for E-3 and C-14 (m
- mrom/yr per pei/sec) for others Nuclide Bone Liver Thyroid Kidnav Lund GI t t.T T.mody Ru-103 1.55E+7 3.89E+7 3.99E+8 5.94E+6 j
5.98E+4 3.33E+1 Ru-105 9.17E+1 8.06E+2 Ru-106 7.45E+8 1.01E+9 1.16E+10 9.30E+7 Rh-103m 2
Rh-106 l
9 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 i
i Sb-125 4.99E+8 3.85E+6 4.62E+5 2.782+8 1.19E+9 1.05E+8 i
i
~
Te-125m 3.51E+8 9.50E+7 9.84E+7 3.38E+8 4.67E+7 Te-127 1.32E+9 3.56E+8 3.16E+8 3.77E+9 1.07E+9 1.57E+8 Te-127 1.OOE+4 2.70E+3 6.93E+3 2.85E+4 3.91E+5 2.15E+3 4
1.04E+9 1.33E+8 Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 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 1.100+6 5.16E+6 2.16E+7 5.68E+5 Te-131 Te-132 6.98E+6 3.09E+6
'.50E+6 2.87E+7 3.11E+7 3.73E+6 I-130 6.21E+5 1.26E+6
.38E+8 1.88E+6 5.873+5 6.47E+5 I-131 1.43E+8 1.44E+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 I-133 3.59E+6 4.44E+6 8.25E+8 7.40E+6 1.79E+6 1.68E+6 2.10E-4 1.46E-4 I
I-134 1.70E-4 3.16E-4 7.28E 3 4.84E-4 I-135 6.54E+4 1.18E+5 1.04E+7 1.81E+5 8.98E+4 5.57E+4 Cs-134 1.60E+10 2.63F+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 i
Cs-138 Ba-139 5.11E-2 2.73E-5 2.38E 5 1.61E-5 2.95E+O 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 3.23E+3 1.13E+3 3.15E+7 3.81E+2 La-142.
2.32E-4 7.40E-5 1.47E+1 2.32E-5 Ce-141 1.23E+5 6.14E+4 2.69E+4 7.66E+7 9.12E+3 Ce-143 1.73E+3 9.36E+5 3.93E+2 1.37E+7 1.36E+2 Ce-144 1.27E+8 3.98E+7 2.21E+7 1.04E+10 6.78E+6 Pr-143 1.48E+5 4.46E+4 2 41E+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 1.83E+2 5.30E+2 1.36E+7 1.29E+2 DBP 6027A 97 Revision 10.0 ODCM me
^ ~
1
+
l Table 3-11 Plane Pathway Dose Factors g'Grop*mrom/yrperpci/sec)
R (m
l Nuclide Any Ornan B&Tlida Any Orcan Rh-103m Rh-106 C-14 tia-24 1.21E+7 Ag-110m 3.47E+9 i
Te-125m 1.55E+6 P-32 Cr-51 4.68E+6 Te-127m 9.17E+4 Mn-54 1.34E+9 Te-127 3.OOE+3 Mn-56 9.05E+5 Te-129m 2.OOE+7 Te-129 2.60E+4 Fe-55 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 i
Cu-64 6.09E+5 I-132 1.24E+6 Zn-65 7.45E+8 I-133 2.47E+6 I-13+
4.49E+5 Zn-69
- -135 2.56E+6 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 0
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 Pr-144 1.83E+3 Y-93 1.85E+5 Nd-147 8.40E+6 Zr-95 2.48E+8 Zr-97 2.94E+6 W-187 2.36E+6 Nb-95 1.36E+8 Np-239 1.71E+6 Mo-99 4.05E+6 I
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 1
DBP 6027A 98 Revision 10.0
. ODCM
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DAvi5 DESSE tiUCLE AR POWER ST ATI0ll LECitt0 y
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y 4.0 SPECIAL DOSE AMALYSES 4.1 DOSES TO TER PUBLIC DUE '20 ACTIVITIES INSIDE THE IDERESTRICTED 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 offluents 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 atandards).
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 l
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.
l 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 I
of 2SO hours (1 h/ day. 5 day /wk. 50 wk/yr). *
.For noble gas direct exposure, default use of the maximum UNRESTRICTED AREA' BOUNDARY dispersion from table 3-6.
l For Inhalation Pathway, default use of the maximum UNRESTRICTED AREA BOUNDARY dispersion from Table 3-6.
For Direct " Shine
- froe the ISFSI, default use of the maximum dose rate for a completed (1u119 ISFSI, and a distance of 950 feet.
The equations in Section 4.I may tie used for calculating the potential l
dose to a MEMBER OF THE PUB *10 for activities inside the UNRESTRICTED AREA I
BOUNDARY. Based on these assumptions, this dose would be at least a l
factor of 35 less than the maximum UNRESTRICTED AREA BOUNDARY air dose as g
j calculated in Section 3.1.
I j
l Based on a maximum conservative estimate.
DBP 6027A 100 Revision 10.0 j
1 There are no areas onsite accessible to the public where exposures to liquid effluents could occur. Therefore, the modeling of section 2.4 conservatively estimates the maximum potential dose to MEMBERS OF THE PUBLIC.
l l
4.2 DOSES TO MEMBERS OF THE PUBLIC 40 CFR 190 I
As required by and ODCM Section 7.2, the Radioactive Effluent Release j'
Report shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other
'I nearby uranium fuel cycle sources (including dose contributions from effluents and direct radiation from onsite sources). For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of the Davis-Besse site, the sources of exposure need consider only the radioactive effluents and direct exposure contribution from Davis-Besse. No other fuel cycle facilities contribute significantly to the cumulative dose to a MEMBER OF i-THE PUBLIC in the immediate vicinity of the site. Fermi-2 is the closest j
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.
l The correlation of measured plant effluents with pathway modeling of this l
ODCM provide the primary method for demonstrating / evaluating compliance 4
with the limits specified below (40 CFR 190).
However, as appropriate, the results of the environmental monitoring program may be used to provide 4
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 ar.nual (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 j
less than or equal to 75 mrem.
With the calculated doses from the releases of radioactive materials in liquid or gaseous ef fluents exceeding twice the limits of Sections 2.4.1,
-347.1.
and 3.8.1, evaluations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determane whether the above limits of this Section have been exceeded. If such as the case, in lieu of a Ilcensee 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 conf ormance with the above limits. This Special Report. as defined in 10 CFR Part 20.2203, shall include an analysts that estimates the radiation exposure (dose) to a MEMBER OF THE FUBt:0 from uranium fuel cycle sources, including all effluent pathways and d: rect radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and con.centrations of radioactive material involved, and the cause of the DBP 6027A 101 Revision 10.0 ODCM
_. ~ _.. -. _ _ _ _
(.
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4+
~:
exposure levels or ocacentrations. 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 couplete.
1 This requirement is provided to meet the dose limitations of 40 CFR Part 190 that have been 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 j
and direct radiation exceed 25 mrom to the total body or any organ, except i
the thyroid, which shall be limited to less than or equal to 75 mrom.
2t is highly unlikely that the resultant dose'to a MEMBER OF THE PUBLIC will oxceed the 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 l
THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the special Report with a request for variance (provided the release j
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 and 10 j
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 1
in any way to.the other dose requirements for dose limitation of 10 CFR l
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 j
engaged in carrying out any operation that is a part of the nuclear fuel j
cycle.
1 4.2.1 Effluent Dose Calculations For purposes of implementing 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, dese calculations Tor Davis-Besse may be performed using the calculational 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 radiciodines, tritium and particulates are calculated based on equations in Section 3.8.
DBP 6027A 102 Revision 10.0 ODCM
- a
.r i
The following equations may be used for calculating the dose to l
M1MBERS OF THE PUBLIC from releases of noble gases:
I D
= 3.17E-08
- _E__
- x/Q
- E (K
- Qg)
(4-1) b g
8760 l
and D,
= 3.17E-08
- U
- x/Q
- E ((Lg + 1.1 M )
- Q)
(4-2) g g
where:
total body dose due to gamma' emissions for noble gas D
=
radionuclides (mrem) skin dose due to gamma and beta emissions for noble gas D
=
radionuclides (mrem) duration of exposure (hr/yr, default values in Table 4-1)
U
=
atmospheric dispersion to the offsite location (sec/m )
x/Q
=
cumulative release of noble gas radionuclide i over the period O
=
g of interest (gCi) g total body dose factor due to gamma emissions frgm noble gas K
=
radionuclide i from Table 3-5 (mrem /yr per pCi/m )
skin dose factor due to beta emissions from noblg) gas L
=
radionuclide i from Table 3-5 (mrem /yr per pCi/m g
gammaairdosefactorgernoblegasradionuclideifromTable 1
M
=
3-5 (mrad /yr per pCi/m )
8760 =
hours per year mrem skin dose per mrad gamma air dose (mrem / mrad) 1.1
=
1/3.15E+07 yr/see 3.17E-08
=
Average annual meteorological dispersion parameters or meteorological l
conditions concurrent with the release period under evaluation may be used (e.g., quarterly averages or year-spe,cific annual averages).
l
.~
DBP 6027A 103 Revision 10.0 ODCM y
. ~_
4.2.2 nirect :-== m m--
nater-4==tian n==ite 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 i:alculational 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.
1 The following sitplified method may be used for evaluating the direct dose based on ons.te et site boundary measurements:
D,0
= D 'e (X B
_ _ B_ _,__
(X 9)
I where:
D,'o =
direct radiation dose measured at 1ocation. consite or site boundary) in sector O D
0=
extrapolated dose at location L in same sector G X
G=
distance to the location L from the radiation source j
B,0 =
distance to location B from the radiation source
~
X 4.2.3 Dose Assessment Based on Radiolocical Environmental Monitorine Data Normally, the assessment of potential doses to MEMBERS OF THE PUBLIC must be calculated based on the neasured radioactive effluents at the plant. The resultant levels of radioactive material in the offsite environment are so minute as to be undetectable. The calculational l
methods as presented in this ODCM are used for modeling the transport in the environment and the resultant exposure to offsite individuals.
The results of the radiological environmental. monitoring program can provide input into the overall assessment of impact 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, a confirmatory the data provides a qualitative assessment
' demonstration of the negligible impact.
DBP 6027A 104 Revision 10.0 ODCM
..__ _ ~ _
4 Dose modeling can be sieplified into three basic parameters that can be applied in using enviran=antal monitoring data for dose
- assessment.
D = C
- U
- DF (4-4)
{
where:
)
dose or dose commitment D'
=
concentration in the exposure media, such as air concentration C
=
for the inhalation pathway, or fish, vegetation or. milk concentration for the ingestion pathway individual exposure to the pathway, such as hr/yr for direct U
=
exposure, kg/yr for ingestion pathway j
1 dose conversion factor to convert from an exposure or uptake i
=
to an individual dose or dose commitment The applicability of each of these basic modeling parameters to the use of environmental monitcring data for dose assessment is addressed below:
Concentration - C The main value of using environmental sampling data to assess potential doses to individuals is that the data represents actual measured levels of radioactive material in the exposure pathways. This eliminates one main uncertainty in the modeling - the release from the plant and the transport to the environmental exposure medium.
j Environmental samples are collected on a routine frequency (e.g., weekly C
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.
E(C.
- t)/365 (4-5)
C.
=
where:
average concentration in the sampling medium for the year C
=
~
concentration of each radionuclide + measured in the C
=
g individual sampling medium period of time that the measured concentration is t
=
considered representative of the sampling medium (typically equal to the sampling frequency; 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 Jero should be used for C (C = 0).
DBP 6027A 105 Revision 10.0 ODCM
4; Mg. 4 p
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~
7 4
Exnosure - U Default exposure valbes (U) as remndad. in Regulatory Guide 1.109 are presented in Table 4-1.
These values should be used only when specific
~
data applicable to be environmental pathway being evaluated is unavailable.
Also, the routine radiological environmental monitoring program is designed to sample / monitor the environa, ental 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 naasured 1evels of radioactivity in samples that are not directly applicable to exposure to real individuals, the approach reco==anded is to correlate the i
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.
2 The other alternative is to conservatively assume a hypothetical j
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 i
presented in NRC Regulatory Guide 1.109.
The use of the Regulatory Guide 1
1.109 values applicable to the exposure pathway and maximum exposed individual is referenced in Table 4-1.
j 4.2.4 Use of Environmental TLD for Assessino Doses Due to Noble Gas
]
Releases q
i
[
Thermoluminescent dosameters (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 j
low.
A study
- performed for the NRC concluded that it is possible to
]
determine a plant contribution to the natural background radiation i
levels (direct exposure) of arouni 'O mrem per year-(by optimum 2
niethods and high precision data).
.hereiere, for routine releases from nuclear power plants the use of TLD is mainly confirwat at'y -
ensuring actual exposures are within the expected natural background variation.
4 NUREG/CR-0711, Evaluation of Methods for the Determination of x-and Gamma: Ray Expostre Attributable to a Nuclear Facility Using Environmental TLD Measurements, Gail dePlanque, June 1979, USNRC.
DBP 6027A 106 Revision 10.0 ODCM
~ -
i
}-
For releases of noble gases, environmental modeling using plant measured releases and atmospheric transport models as presented in this ODCN represents the best method of assessing potential i
environmental doses. However, any observed variations in TLD measurements outside the norm should be evaluated.
4 i
d l
4 I
i I
i 1
1 l
i l
1 1
CBP 6027A 107 Revision 10.0 ODCM
~
i Table 4-1 Recommended Exposure Rates in Lieu of Site Specific Data
- Table Reference Exposure Pathway Maximum Exposed Exposure Rates for Dose Factors Age Group from RG 1.109
+
Lj.auid Releases Fish Adult 21 kg/y E-11 Drinking Water Adult 730 1/y E-11 Pottom Sediment Teen 67 h/y E-6 Atmoseherie Releases 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 7.
Milk Infant 330 1/y E-14 i
Adapted froS 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 1.109.
DBP 6027A 108 Revision 10.0 j
4 6
5.0 ASSESSMENT
OF LMID 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.a (as required by 10 CFR 50, Appendix I, Section IV.B.3) for identifying controlling location / pathway for dose assessment of'ODOI 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 s distance of 8 km (5 miles) the location, in each of the 16 meteorologicalsectors,ofthenearestmilkanimal,ghenearestresidence 2
and the nearest 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.
Thiscensus.satisfiestherequirementsofSectionIV.B.3ofAppendixIgo s
10CFRgart50. Restricting the census to gardens of greater than 50 m (500 ft ) provides 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) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made:
(1) 20% of the garden was used for growing broad leaf vegetation (i.e),
similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/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 l
shall be included in the Annual Radiological Fnvironmental 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 Repcrt, identify the new locations (s) in the next Radioactive Effluent Release Rep 7rt, pursuant to l
Section 7.2. With a land use census identif ying a locations (s) that yields a calculated dose or dose commit, ment (via the same exposure pathway) 20 percent greater than that at a' location from which sarples are currently being obtained in accordance with Section 6.1, add the new locations (s) if practical (and readily obtainable) to the Radiological 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 aa.d pursuant to Section 7.2, identify the new location (s) in the next Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
DBP 602'A 109 Revision 10.0 ODCM t
\\.l
..g The following guidelines shall be used for assessing the results from the land use census to ensure compliance with this section.
5.1.1 Data Commilation 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, annual 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 1
data set.
5.1.2 Relative Dose Sienificance 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 I-131 source term dose may be used for assessment 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 lo:atten used in the ODCM Table 3-4 will be verified.
- f any le:atton/ pathway (s) is identified with a higher relative dese, this location / pathway (s) should replace the previously : dent:!aed controlling location / pathway in Table 3-4.
- ! the previously identified controlling pathway is no longer present. tne current controlling location / pathway should be determaned B.
Any changes an e:tner the controlling location / pathway (s) of the ODCM dose calculata:ns (Section 3.7 and Table 3-4) or the Radiological Envaren-ental Monitoring Program (ODCM Section 6.0 and Table 6 'l sha;; be reported to NRC in accordance with ODCM Section 5.1 and
- DBP 6027A 110 Revision 10.0 ODCM
j1 l.
[.
$.2 LMID USE CENSUS TO SUPPORT REALISTIC DOSE ASSESSMENT The Land Use Census (LUC) provides data needed to support the special dose j'
analyses of Section 4.0.. Activities inside the UNRESTRICTED ARIA BOUNDARY l
should be periodically reviewed for dose assessment as required by Section 4.1.
Assessment of realistic doses to MSMBERS OF THE PUBLIC is required j
by Section 4.0 for d==an=trating compliance with the EPA Environmental Dose Standard, 40 CFR 190 (Section 4.2).
4
)
To support these dose assessments, the LUC shall include (a) areas within
)
}
the UNRESTRICTED AREA BOUNDARY that are accessible to the public; and (b)
I use of Lake Erie water on and near the site. The scope of the LUC shall 1
)
include the following:
1 Assessment of areas onsite that are accessible to MEMBERS OF THE PUBLIC. Particular attention ghould 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.
1 r
I DBP 6027A 111 Revision 10.0 ODCI
e s.o 3)DIOLOGICAL ENVIRQtBEENTAL MOBII1DRING PROGRAD{
The Radiological Environmental Monitoring Program (REMP) provides measurements of radiation and of radioactive materials in those exposure pathways r.nd for those radionuclides which lead to the higher potential radiation exposures of individuals 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. This monitoring program implements Sections IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent controls by verifying that the measurable concentrations cf 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 locetions, 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 i
7.2, respectively.
If the changes are to be permanent, Table 6-2 and Appendix C shall be updated.
4 Note: For the purpose of implementing Section 5.1, sampling locations will be modified, to reflect the findings of the land use census as described in ODCM Section 5.1.
l 6.1.2 Procram Deviations I
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 preventing a recurrence.
l
\\
l l
DBP 6027A 112 Revision 10.0 ODCM a
e
1 U
a g,1,3 mavailability of Mille or Broad haf Venetation _n==les 1
With milk or fresh leafy vegetable samples unavailable from one or 1
more of the sample locations required by Table 6-1, identify j
locations for obtaining replacement sangles and if practical add them J
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).
6.1.4 Seasonal Unavailabilitv> Eeuipment 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 3
from the sampling schedule will be documented in the Annual Radiological Environmental Operating report pursuant to Section 7.1.
6.1.5 Sa_ mole Analysis REMP samples shall be analyzed pursuant to the requirenents 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 s
6.2.1 General The 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).
These potential doses are modeled on the maximum exposure or consumption rates of NRC Regulatory Gut,de 1 109.
The evaluation of potential doses should be based solely on radioactive material resulting from plant operation.
DBP 6027A 113 Revision 10.0 CDCM
,.., ~
.y e
6.2.2 EEsmedance of menortincr Levels j
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 defines ths corrective actions to be taken to reduce radioactive affluents 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 s l
concentration (1) +
concentration (2) +.. 1 1.0.
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 l
potential annual dose to a MZMSER 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.
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 j
~
Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission. The requirement for participating in an approved j
Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive j
material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to i
demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix 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.
DBP 6027A 114 Revision 10.0 ODCM
m..._.
O' d b
' b' Number of Representative g
Exposure Pathway Samples and Sgmple.
Collection Type and Frequency-m and/or Sample Locations Frecuency of Analysis ao b
u 1.
DIRECT RADIATION 27 routine monitoring Quarterly Gamma dose quarterly stations either with two i
or more dosimeters or with one instrument for measur-ing and recording dose rate continuously, placed as a
follows:
H an i" ring of stations, f
generally one in each c
meteorological sector in g"
the general area of the F
4 U!! RESTRICTED AREA BOUNDARY:
an outer ring of stations, one in each meteorological sector in the 6 to 8 km e.
9 range from the site, excluding the sectors over I'
Lake Erie; the balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.
OM oa k h-O D
9 O
u r
\\b
.m
~s Number of Representative g
Exposure Pathway Samples and Sgmple Collection Type and Frequency
,3 v
and/or Samole Locations Frecuency of Analysis
~ *!
' fG m
O 2.
AIRBORNE a>
Radiciodine and Samples from 5 locations, Continuous Radiciodine i
Particulates placed as follows:
sampler opera-Canister I-131 tion with sample analysis weekly.
3 samples from close to the collection weekly, Particulate Sampler UNRESTRICTED AREA BOUNDARY, or more frequent Gross beta radio-in different sectors, if required by activity analysis H
generally from areas of dust loading.
following filter h
higher calculated annual change; Gamma e
average groundlevel D/Q.
isotopic analysis of g
composite (by P
location) quarterly, gh 1 sample from the vicinity
}w*
of a nearby community, generally in the area of I"
higher calculated annual e
average groundlevel D/Q.
75 8
1 sample from a control location, 15-30 km from the site.
w 3.
WATERBORNE a.
Surface 2 samples Weekly composite Tritium gnd gamma (untreated water) sample (Indicator isotopic analysis location should of composite sample be a composite) monthly.
OE b.
Ground Sample from one source Quarterly Gamma Isotopic and 9d-only if likely to be tritium analysis O.
affected*
quarterly.
o D
o
'o l
l ti i
l i
t
+
e Number of Representative and Sam Collection Type and Frequency Locations ^ ple t1 Exposure Pathway Samples E
and/or Sample Frecuency of Analysis m
O c.
Drinking 1 sample from the nearest Weekly composite Gross beta on monthly N
\\
(Treated water) source.
sample.
composite. Tritium and ganuna isotopic 1 sample from a er. trol analysis on quarterly location.
composite.
I-131 analysis on each com-posite when the dose f
(
calculated for the g
consumption of the water is greater than g
1 mrem per year.
H d.
Sert a ment from t sample from area with Semiannually Ganuna iagtopic g
Shm eline estating or potential analysis semi-p reereattonal value.
annually.
l 1
y h
4.
INGESTION o
i a.
Milk If available, samples from Semimonthly when Gamma isotopic and 0
animals up to 2 locations animals are on I-131 analysis semi-h within 8 km distance having pasture, monthly monthly when animals c
gh the highest dose potential.
at other times are on pasture; monthly at other g
times.
g 1 sample from milking i
animals at a control location 15-30 km distant and generally in a less prevalent wind direction.
9d l
Ea o
o o
r Number of Representative g
Exposure Pathway Samples and Sample collection Type and Frequency e
and/or Sample Locations Frecuency of Analysis 3 -_
m O
b.
Fish 1 sample each of 2 commere-1 sample in Ganana legtopic lally and/or recreationally season.
analysis on edible important species in portions.
vicinity of site.
1 sample of same species in areas not intluenced by plant discharge.
w o
c.
Food Products Samples of up to 3 different Monthly when Gamma isotopic and inroad leaf kinds of broad leaf vegeta-available.
I-131 analysis.
"g vegetationi tion growth in two different P
offaite locations of higher predicted annual average w*
ground-level D/O if milk sarnpling is not per f ormed.
I y
^
e 1 sample of each of the Monthly when Gamma isotopic and similar broad leaf vegeta-available.
I-131 analysis.
tions grown 15-30 km distant in a less prevalent wind direction if milk sampling is not performed.
I 8 if 9&
8 b
si 3
9
j Table 6-1 (continued)
]
TABLE NOTATION 1
1
- 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",
1 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 i
media and locations may be chesen 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 locations (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).
bone or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. 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 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 radioactivi'ty 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.
dGamma 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 cource is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
DBP 6027A 119 Revision 10.0 ODCM
Table 5-2 Required Sampling Isocations app =adiv C Type of t_m tion Pace Reference Location
- Location Descrintion T-1 C-4 I
Uhrestricted area boundary, l
0.6 mile ENE of Station.
t l
T-2 C-5 I
Unrestricted area buundary, f
0.9 mile E of Station.
T-3 C-6 I
Unrestricted area boundary, l
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, T-5 C-8 I
Main entrance to site, 0.5 mile W of Station.
l T-6 C-9 I
Unrestricted area boundary, l
0.5 mile NNE of Station.
T-7A & B C-10 I
Sand Beach, 0.9 mile NW of Station.
T-s C-11 I
Farm, 2.7 miles WSW of Station.
1 T-9 C-12 C
Oak Harbor substation, 6.8 miles SW of Station.
T-10 C-13 Unrestricted area boundary, 0.5 mile SSW of Station.
T-11 C-14 0
Port Clin *cn Water Treatment plant, 9.5 miles SE of Station.
T-12A & B C-15 E
Toledo Water Treatment
' Plant, 23.5 miles WNW of Station. Water samples are collected 11.3 miles NW of site.
T-17 C-16 Unrestricted area boundary, 1.8 mile SSE of Station
- I = Indicator locations; C = Control locations.
DBP 6027A 120 Revision 10.0 ODCM l
i 1
Table 6-2 (Continued)
Required Sampling Locations Appendix C Type of Location Pace Reference Location
- Location Descrintion l
T-19 C-17 I
Farm, 1.0 mile W of Station l
T-25 C-18 I
Farm, 3.7 miles S of Station.
T-27A & B C-19 C
Crane Creek State Park, 5.3 miles WNW of Station.
l T-28 C-20 I
Davis-Besse Water Treatment Plant, onsite.
T-33 C-21 I
Lake Erie within a 5-mile radius from Station.
T-35 C-22 C
Lake Erie, greater than a 10-mile radius from Station.
T-37 C-23 C
Farm, 13 miles SW of Station.
T-40 C-24 I
Unrestricted area boundary, l
0.7 mile SE of Station.
l T-41 C-25 I
UNRESTRICTED AREA BOUNDARY, 0.6 mile SSE of Station.
T-4I C-26 I
Unrestricted area boundary, 0.8 mile SW of Station.
T-44 C-27 I
Unrestricted area boundary, 0.5 mile WSW of Station.
T-46 C-28 I
Unrestricted area boundary, l
0.5 mile NW of Station.
T-47 C-29
_ I Unrestricted area boundary, l
0.5 mile N of Station.
/
T-48 C-30 I
Unrestricted area boundary, 0.5 mile NE of Station.
T 50 C-31 I
Erie Industrial Park Water
~
Treatment Plant, 4.5 mile SE of Station.
Indicator locations; C = Control locations.
I e
DBP 6027A 121 Revision 10.0 ODCM f
~
Table 6-2 (Continued)
Required Sampling Locations Appendix C Type of Location Pace Reference Locatier.*
Location Descriotion T-52 C-32 I
Farm, 3.7 miles S of Station.
T-54 C-33 I
Parm, 4.8 miles SW of Station.
T-55 C-34 I
Farm, 4. 0 milets W.
of Station.
T-67 C-35 I
Unrestricted area boundary, l
0.3 mile NNW of Station.
T-68 C-36 I
UNRESTRICTED AREA BOUNDARY, l
0.5 miles WNW of station T-91 C-37 I
Siren Post No. 1108, 2.5 miles SSE of Station.
T-112 C-38 I
State Route 2 and Thompson Road, 1.5 miles SSW of Station.
T-151 C-39 I
State Route 2 and Humphrey Road, 1.8 miles WNW of Station.
I I = Indicator locations; C = Control locations.
DBP 6027A 122 Revision 10.0 ODCM
s Airborne Particulate O
E Water or Gas Fish Milk Food Products Sediment m
Analysis toCi/1)
(oCi/m )
(DCi/ka. wet)
(DCi/1)
(DCi/ka. wet)
(oCi/ka. drv)
O Gross Beta 4
1.0E-02 i
11 2000 Mn 15 130 Fe 30 260 1
Co 15 130 2n 30 260 r
2r 15 I
1 7.0E-02 1
60 e
Cs 15(10 ),18 6.0E-02 130 15 60 150 U
I O
Ba 15 15 w
R NOTE: This list does not mean that only these nuclides are to be detected and reported. Other a
peaks which are measurable and id %tifiable, together with the above nuclides, shall be identified and reported.
If no drinking water pathway exists, a value of 3000 pCi/L may be used.
8#
9E tr D
o O
\\N
- s
O Table'6-5 (Continued)
TABLE NOTATION The LLD is the smallest concentfst16n of radioactive material in a sample a.
that will be detected with 95I probability (with 5I probability of falsely concluding that a blank observation represents a 'real' signal).
For a particular measurement system (which may include radiochemical separation):
4.66 sb LLD =
E
- V
- 2.22
- Y
- exp(-AAt) where LLD is the lower limit of detection as defined above (pCi per unit mass or volume),
b is the standard deviation of the background counting rate or of s
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 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 is the elapsed time between end of the sample collection period 1
and time of counting.
I 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.
j Analyses shall be performed in such a manner that the stated ILDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering 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 folluving:
j
(')
HASL Procedures Manual, HASL-300 (revised annually).
l DBP 6027A 124 Revision 10.0 ODCM
Table 6-3 (Continued)
TABLE NOTATION j
(2) Currie, L.
A.', ' Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" 1..
Anal. r'h= =. 40, 586-93 (1968).
(3). Hartwell, J.
K., " Detection Limits for Radioisotopic Count.4.ng Techniques", Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).
b.
LLD for drinking water.
c.
If no drinking water pathway exists, a value of 3000 pCi/ liter may be used.
T 4.
d.
LLD only when specific analysis for I-131 required.
1 1,
i 4
i-i
-I 9
DBP 6027A 125 Revision 10.0 ODCM 1
'M.di Reporting Lesels
- Sfij d;D*'h.}
'3p[f v
Airborne Particulate
-(
m Water or Gas Milk vegetables 3
f, %
w Analysis (oci/L)-
(oCi/m 1 (oCi/ka. wet)
(oci/11 (oci/ka. wet)
. i:E 4
4 H-3 2.0E+04*
i jy, Mn-54 1.0E+03 3.0E+04
'f '
Fe-59 4.0E+02 1.0E+04
[
Co-58 1.0E+03 3.0E+04 E
Co-60 3.0E+02 1.0E+04 g
2n-65 3.0E+02 2.0E+04 Zr-Nb-95 4.0E+02 I-131 2.0g+00 9.0E-01 3.0E+00 1.0E+02 en*
s m
Cs-134 3.0E+01 1.OE+01 1.0E+03 6.0E+01 1.0E+03 I
s Cs-137 5.0E+01 2.0E+01 2.0E+03 7.0E+02 2.0E+03 M
Ba-La-140 2.0E+02 3.0E+02 w
For drinking water samples, this is the 40 CFR 141 value.
If no drinking water pathway exists, a value of 30,000 pCi/ liter may be used.
l 8F 9 ;i.
E 8
5 a
o O
l
\\i
I 7.0 ADMINISTRATIVE CONTROLS 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Routine Radiological Environmental Operating reports covering the operation of the unit 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 of land use censuses as required in Section 5.1.
The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all radiation measurements taken during the period pursuant to the locations specified in Sections 6.1 and Appendix C of this ODCM, r' well as summarized and tabulated tesults of these analyses and measurements.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The taissing 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 l
and directions from the centerline of one reactor; the results of licensee
)
participation in the Interlaboratory Comparison Program, required by l
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 FEPORT l
l l
Radioactive Effluent Release Peports covering the operation of the unit i
during the previous 12 menths cf operation shall be submitted no later than 12 months from the submittal of the previous report.
The Radioactive Effluent Delease Reports ()RERR) shall include a summary of
~
i the quantities of radica:::ve stquid and gaseous ef fluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting padt:aetivity in Solid Wastes and Releases of Radioactive Materials in L quad and Gaseous Effluents from Light-Water-Cooled Nuclear Fower Plants,"
Revision 1, June 1974, with I
data summarized on a quarterly basis following the format of Appendix B
~
thereof.
l DBP 6027A 127 Revision 10.0 ODCM 1
The RERR shall include an annual summary of hourly meteorological data collected over the previous year. This annual susumary may be either in tbs forin of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of th's 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.
4 The RERR shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for i
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 l
measurement or estimate),
d.
source of waste and processing employed (e.g., dewatered spent resin, compressed dry waste, evaporator bottoms).
e.
t>Te 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 COh* TROL PROGRAM (PCP) and to the CDCM, as well as a listing of new locations for dose calculations and pursuant to Section 5.1.
DBP 6027A 128 Revision 10.0 ODCM
^ l
. 1 The RERR shall include any radionuclide activity limits for the BWST and PNST which have been exceeded during the reporting period, a description of the event leading to the limit being exceeded and action taken to l
return it to within the limits.
1 7.3 SPECIAL REPORTS special Reports shall be submitted to the U. S. Nuclear Regulatory Commission (NRC) in 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 applicable reference 4 a.
dose or dose commitment exceedences to a MEMBER OF THE PITBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (Sectio,n 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 of iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding the limits of Section 3.8.1, j
l e,
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 c: 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).
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 "e 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; DBP 6027A 129 Revision 10.0 ODCM
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 amaterials in liquid or gaseous effluents and/or quantity of solid waste that differ froes those previously predicted in the license applichMon and amendments thereto; an evaluation of the change which shows the expected maximum j
e.
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 gaseous effluents to the actual releases for.;he i
period prior to when the changes are to be made;
)
i g.
an estimate of the exposure to plant operating personnel as a result of the change; and j
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 t
7.5.1 BATCH RELEASE - The discharge of liquid wastes of a discrete volume.
7.5.2 CHANNEL CALIBRATION - A CHAMEL 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 shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHAMEL FUNCTIONAL TEST.
CHl.NNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entare channel is calibrated.
7.5.3 CHANNEL CHECK - A CHAM E-CHECT hhall be the qualitative assessment of channel behavior during cperation by observation. This determination shall snelude. where possible, comparison of the channel indication and/or status with other indications and/or status
~
derived from independent sne:rument channels monitoring the same parameter.
7.5.4 CHANNEL FUNCTIONAL TEST - A CHANNEL FUNCTIONAL TEST shall bei The injection of a simulated signal irco the a.
Analog Channels channel as close te the primary sensor as practicable tr, verify OPERABILITY including alarm and/or trip f unctions.
DBP 6027A 130 Revision 10.0 DDCM
1 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 P *which the method of sampling employed results in a specimen which is representative of the liquids released.
GASEOUSRADWASTETREATMENTSYhTEM-TheGASEOUSRADWASTETREATMENT 7.5.6 SYSTEM is a system that is designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system-off gases and providing for deca'y for the purpose of reducing the total radioactivity prior to release to the environment.
7.5.7 LOWER LIMIT OF DETECTION (LLD) - 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):
LLD =
4.66 Sb E
- V
- 2.22
- Y
- exp(-Abt) 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 j
- nute!:
E is the counting efficiency (as counts per transformations);
V is the sample size ( in units of mass or volume);
2.:
as the rumber of transformations per minute per picocuries Y ts the fractiona! radiochemical yield (when applicable):
1 15 the radioactive decay Tonstant for the particular radionuclide; j
ani St for plant effluents is tne elapsed time between the midpoint of sample collection and time of ct.cnting.
1* should be recognized that the LLD is defined as an a, priori tt'efore the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
DBP 6027A 131 Revision 10.0 ODCM
3:. ;,
7.5.8 MBtBER OF TER PUBLIC - Member (s) of the public shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreation, o':cupational, or other purposes not associated with the plant.
7.5.9 OPEDBLE - OPERABILITY - A system, subsystem, train, conqponent or device shall be operable or have operability when it is capable of performing its specified 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).
7.5.10 PURGE-PURGING - PURGE OR PURGING 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 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.
]
i 7.5.13 UNRESTRICTED AREA - An unrestricted area shall be any area at or i
beyond the UNRESTRICTED AREA BOUNDARY, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation or radioactive materials, or any area within the UNRESTRICTED AREA BOUNDARY used for residential quarters l
or for industrial, commercial, institutional, and/or recreational purposes. The definition of unrestricted area used in implementing the Radiological Effluent Technical Specifications has been expended 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 efiluents as low as is
]
~
reasonably achievable, pursuant to 10 CFD. CO 36a.
i 7.5.14 VEWILATION 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 i
prior to release to the environment. Engineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be VENTILATION 1
E)CHAUST TREATMEE SYSTEM components.
DBP 6027A 132 Revision 10.0 ODCM
_. -. ~
4 7.5.15 VENTING - VENTING is the controlled process of discharging air or i
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 igly a VENTING process.
I b
9 1
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DBP 6027A 133 Revision 10.0 ODCM i
l
f 3
1 APPENDIX A Technical Basis for simplified Dose Calculations Liquid Effluent Releases l
J DBP 6027A A-1 Revision 10.0 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 of its 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 pCi/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 nu-lear 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 7.11E+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.
I i
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l DBP 6027A A-2 Revision 10.0 1
l ODCM
ee
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simplified Method 1
For evaluating compliance with the dose limits of Section 2.4.1, the following simplified equations may be used:
Total Body 1.67E-02
- VOL 0
tb s
- Z where:
j d se to the total body (mrem)
D
=
tb volume of liquid effluents released (gal)
)
a VOL average Collection Box release flow (gal / min)
DF 1
=
- 10. near field dilution 3
Z
=
=.
5.81E+05 mrem /hr per pCi/ml, the total body ingestion dose A(Cs-134,tb) i factor for Cs-134 4
EC total concentration of all radionuclides (pci/ml)
=
g 1 hr/60 min 1.67E-02
=
Substituting the values for Z and the Cs-134 total body dose conversion factor, the equation simplifies to:
9.70 E+02
- VOL EC (A-2)
D
=
b g
Maximum Organ 1.67E-02
- VOL D,,x
=
- Z where:
D,,,
maximum organ dose (mrem)
=
1 A(Cs-134. liver) 7.11 +05 mrem /hr per pC1/ml the liver ingestion dose
=
factor for Cs 134 DBP 6027A A-3 Revision 10.0 ODCM j
i Substituting the values for z and the Cs-134 liver dose conversion factor, the i
equation simplifies to j
l 1.19 E+03
- VOL
- IC (A.4)
D
=
g Tritium should not be included in the simplified analysis dose assessment for liquid releases, The potential dose resulting from normal reactor releases of H-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.
j l
l DBP 6027A A-4 Revision 10.0 ODCM l
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APPENDIX B
. Technical Basis for Effective Dese Factors Gaseous Radwaste Effluents l
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4 DBP 6027A B-1 Revision 10.0 ODCM i
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APPENDIX B Technical Basis for Effective Dose Factors i
Gaseous Radweste Effluents 4
Overview Dose evaluations for releases of gaseous radioactive effluents may be simplified by the use of an effective dose factor rather than l
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 Factors Effective dose factors are calculated by equations (B-1) through (B-4).
K,gg = I( K
- f
)
(B-1) where:
the effective total body dose factor due to gamma emissions from K
=
3 l
gg all noble gases released (mrem /yr per pCi/m ),
the total body dose factor due to gamma emissions from each K
=
g noble gas radionuclide released, from Table 3-5 (mrem /yr per i
3 1
pCi/m ), and
~
the fractional abundance of noble gas radionuclide relative to f
=
the total noble gas activity.
f)
(B-2) 1.1M )
- ((L +
(L + 1.1 M)
=
g g
where the effective sk:n dose factor due to beta and gamma (L+1.1M)
=
gg emissgensfro-a;; noble gases released (mrem /yr per pCi/m
),
and the skin dose fa::ct due to beta and gamma emissions from (L +1.1M )
=
g g
released, from Table 3-5 each noble gas radgonuclide g (mrem /yr per u0;.e !.
f)
(B-3)
M
. ItM
- e!!
1 1
DBP 6027A B-2 Revision 10.0 ODCM
1 where:
M,gg the effective air dose factor due to ga p emissions from all
=
noble gases released Onradlyr per pCi/m ), and the air dose factor due to gasusa emissions from each noble gas M
=
g 3
radionuclide released, from Table 3-5 (mradlyr per pCi/m.
g N,gg = E(N
- f)
_ B-4
(
g g
where:
N" theeffectiveairdosefactor'duetobegaemissionsfromall
=
noble gases released (mradlyr per pci/m ),
and the air dose factor due to beta emissions from each noble gas N
=
i radionuclide released, f rom Table 3-5 (mradlyr per pCi/m ).
g 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.
Application 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 assurance that the evaluation of doses by the use of a. single effective dose factor will not significantly underestimate any
~.
a:tual doses in the environment.
For evaluatang compliance with the dose limits of Technical Specification 3.11.2.2 the following simplified equations may be used:
Dh =
2.0
- 3.17E-08
- y/Q
- M S
(B-5) eH i
and Dp =
2.0
- 3.17E-08
- y/Q
- N,gg
- EQ (B-6)
DBP 6027A B-3 Revision 10.0 ODCM
.~
I where:
DA air dose due to gamma emissions for the cumulative release of all
=
i noble gases (arad),
air dose due to beta emissions for the cumulative release of all Dp
=
noble gases (mrad),
atmosphericdisgersiontothe'controllingunrestrictedarea y/q
=
boundary (sec/m ),
M,fg =
5.7E+02, effective gamma-air dose factor (mradlyr per pCi/m'),
3 N,gg =
1.1E+03. effective beta-air dose factor (aradlyr per pCi/m ),
Qg cumulative release for all noble gas radionuclides (pci),
=
conversion factor (yr/sec), and
)
3.17E-08
=
i conservatism factor to account for the variability in the effluent 2.0 data.
l combining the constants, the dose calculation equations simplify to:
1 DA = 3.61E-05
- y/Q
- EQ (B-7) g and 1
J Dp = 7.20E-05
- X/Q
- EQ (B-8) g
' The effective dose factors are used for the purpose of fccilitating the timely
~
assessment of radioactive effluent releases, particularly during periods when the computer or ODCH software may be unavailable to perform a detailed dose assessment.
a 3
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i DBP 6027A B-4 Revision 10.0 ODCM
Table B-1 Default Noble Gas Radionuclide Distribution
- of Gaseous Effluents Fraction of Total (A / E A )
g g
containment station Wacte Gas Nrclida Vessel Purae Vent Decav Tank Total
=,
Ar-41 0.0003 0.004 0.004 0.003 Kr-85 0.12 0.012 0.034 0.06 Xe-131m 0.02 0.009 0.008 0.017 Xe-133m 0.005 0.011 0.011 0.008 Xe-133 0.86 0.94 0.92 0.83 0.004 0.0034 0.06 Xe-135m Xe-135 0.002 Ra1 9.J1 Ed21 Total 1.0 1.0 1.0 1.0 L
i F
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 abandance (i.e.,
< 1%).
DBP 6027A B5 Revision 10.0 ODCM l
l
Table B-2 Effective Dose Factors - Noble Gas Effluents Total Body skin Dose na - Air Beta Air Dose Factor Factor Dose Factor Dose Factor Isotope Fractional K,gg (L+1.1M,gg)
M,gg N,gg Abundance (mromfyrper (mromfyrper (mradfyrper (mradjyrper pCi/m )
pCi/m )
pCi/m )
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 1.03E+00 1.17E+02 Xe-131m 0.017 1.55E+00 1.10E+01 2.65E+00 1.88E+01 Ke-133m 0.008 2.00E+00 1.08E+01 2.61E+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 10.0 ODCM i
)
4%
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l I
APPENDIX C
. Radiological Environmental Monitoring Program Sample Location Maps 1
l l
DBP 6027A C-1 Revision 10.0 ODCM
3 i.
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o
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