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Text

Offsite Dose Calculation Manual Rev 7
	ML20082V407
Person / Time
Site:	Davis Besse
Issue date:	02/03/1995
From:	; CENTERIOR ENERGY
To:	;
Shared Package
ML20082V402	List: ML20082V398; ML20082V405; ML20082V407;
References
	PROC-950203, NUDOCS 9505090236
	Download: ML20082V407 (200)
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TABLE OF CONTENTS

1.0 INTRODUCTION

. . . . . . . . . . . . . . . . . . . . . . . . . . 1 i

2.0 LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . 2 i

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. . . . . . . . . . . . . . . . . . . . 9 2.3.4 Storm Sewer Drain Monitor . . . . . . . . . . . . . 12 2.3.5 Alarm Setpoints for the Non-Required l Radiation Monitors . . . . . . . . . . . . . . . . 12 .

2.3.6 Alarm Response - Evaluating Actual Release Conditions. . . . . . . . . . . . . . . . . . . . . 13 2.4 Liquid Effluent Dose Calculations - 10 CFR 50 . . . . . . . . 15 ,

2.4.1 Dose Limits to MEMBERS OF THE PUBLIC. . . . . . . . 15 1 2.4.2 MEMBER OF THE PUBLIC DOSE - Liquid Effluents. . . . 16 ;

2.4.3 Simplified Liquid Effluent Dose Calculation . . . . 18 i 2.4.4 Contaminated TBS /SSD System - Dose Calculation. . . 19 ;

2.5 Liquid Effluent Dose Projections. . . . . . . . . . . . . . . 20 3.0 GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . 35 i

3.1 Radiation Monitoring 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 fi 3.2.1 Batch Releases. . . . . . . . . . . . . . . . . . . 38 3.2.2 Continuous Release. . . . . . . . . . . . . . . . . 38 ;

3.2.3 Releases Resulting from Primary-to-Secondary l System Leakage. . . . . . . . . . . . . . . . . . . 39 !

3.3 Gaseous Effluent Monitor Setpoint Determination . . . . . . . 40 .

3.3.1 Total Effective Dose Equivalent Limits . . . . . . 40 3.3.2 Release Rate Limits . . . . . . . . . . . . . . . . 40 3.3.3 Individual Release Radiation Monitor Setpoints. . . 41 <

3.3.4 Conservative Generic Radiation Monitor Setpoints . 42 l

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s 3.3.5 Release Flow Rate Evaluation for Batch Releases . . 42 l

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TABLE OF CONTENTS (Continued)

(3.0 GASEOUS EFFLUENTS - continued) 3.4 Site Boundary Dose Rate Calculation - Noble Gas . . . . . . . 45 3.5 . Site Boundary Dose Rate Calculation - Radioiodine, Tritium, ,

and Particulates. . . . . . . . . . . . . . . . . . . . . . . 46 3.5.1 Dose Rate Calculation . . . . . . . . . . . . . . . 46 3.5.2 Simplified Dose Rate Evaluation for Radiciodine.

Tritium and Particulates. . . . . . . . . . . . . . 46 ,

3.6 Quantifying. Activity Released . . . . . . . . . . . . . . . . 47 3.6.1 Quantifying Noble Gas Activity Released Using Station Vent Monitor. . . . . . . . . . . . . . . . 47 [

3.6.2 Quantifying Noble Gas Activity Released Using [

48 A Grab Sample . . . . . . . . . . . . . . . . . . .

3.6.3 Quantifying Radioiodine Tritium, and Particulate ,

Activity Released . . . . . . . . . . . . . . . . . 49 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 Radiolodine and Particulate Dose Calculations - ;

10 CFR 50 . . . . . . . . . . . . . . . . . . . . . . . . . . 53 ;

3.8.1 UNRESTRICTED AREA Dose Limits . . . . . . . . . . . 53

3.8.2 Critical Pathway. . . . . . . . . . . . . . . . .. 54 l 3.8.3 Dose Calculations - Radiciodine Tritium and l Particulates. . . . . . . . . . . . . . . . . . . . 55 3.8.4 Simplified Dose Calculation for Radiciodines 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 Inside the SITE BOUNDARY . . . . . . . . . . . . . . . . . . 100 4.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 . . . . . . . . . 101 4.2.1 Effluent Dose Calculations. . . . . . . . . . . . . 102 ;

4.2.2 Direct Exposure Dose Determination -

Onsite Sources. . . . . . . . . . . . . . . . . . . 103 4.2.3 Dose Assessment Based on Radiological Environmental Monitoring Data . . . . . . . . . . . 104 4.2.4 Use of Environmental TLD for Assessing Doses Due to Noble Gas Releases . . . . . . . . . . . . . 106 l I

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TABLE OF CONTENTS (Continued) 5.0 ASSESSMENT OF LAND USE CENSUS DATA . . . . . . . . . . . . . . . . 108 5.1 Land Use Census Requirements. . . . . . . . . . . . . . . . . 108 5.1.1 Data Compilation. . . . . . . . . . . . . . . . . . 109 5.1.2 Relative Dose Significance. . . . . . . . . . . . . 109 5.1.3 Data Evaluation . . . . . . . . . . . . . . . . . . 109 5.2 Land Use Census to Support Realistic Dose Assessment . . . . 110 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . . . . . . . . . . 111 6.1 Program Description . . . . . . . . . . . . . . . . . . . . . 111 6.1.1 General . . . . . . . . . . . . . . . . . . . . . . 111 6.1.2 Program Deviations. . . . . . . . . . . . . . . . . 111 6.1.3 Unavailability of Milk or Broad Leaf Vegetation Samples . . . . . . . . . . . . . . . . . . . . . . 112 6.1.4 Seasonal Unavailability, Equipment Malfunctions, Safety Concerns . . . . . . . . . . . . . . . . . . 112 6.1.5 Sample Analysis . . . . . . . . . . . . . . . . . . 112 ~

6.2 Reporting Levels . . . . . . . . . . . . . . . . . . . . . . 112 6.2.1 General . . . . . . . . . . . . . . . . . . . . . . 112 6.2.2 Exceedance of Reporting Levels. . . . . . . . . . . 113 6.3 Interlaboratory Comparison Program . . . . . . . . . . . . . 113 7.0 ADMINISTRA71VE CONTROLS . . . . . . . . . . . . . . . . . . . . . 126 7.1 Annual Radiological Environmental Operating Report . . . . . 126 7.2 Radioactive Effluent Release Report . . . . . . . . . . . . . 126 7.3 Special Reports . . . . . . . . . . . . . . . . . . . . . . . 128 7.4 Major Changes to Radioactive Liquid and Gaseous Waste Treatment Systems . . . . . . . . . . . . . . . . . . . 128 7.5 Definitions . . . . . . . . . . . . . . . . . . . . . . . . . 129 7.5.1 Batch Release . . . . . . . . . . . . . . . . . . . 129 7.5.2 Channel Calibration . . . . . . . . . . . . . . . . 129 7.5.3 Channel Check . . . . . . . . . . . . . . . . . . . 129 7.5.4 Channel Functional Test . . . . . . . . . . . . . . 129 7.5.5 Composite Sample. . . . . . . . . . . . . . . . . . 130 7.5.6 Gaseous Radwaste Treatment System . . . . . . . . . 130 7.5.7 Lower Limit of Detection (LLD). . . . . . . . . . . 130 7.5.8 Member of the Public. . . . . . . . . . . . . . . . 131 7.5.9 Operable - Operability. . . . . . . . . . . . . . . 131 7.5.10 Purge-Purging . . . . . . . . . . . . . . . . . . . 131 7.5.11 Site Boundary . . . . . . . . . . . . . . . . . . . 131 7.5.12 Source Check . . . . . . . . . . . . . . . . . . . 131 Unrestricted Area .

7.5.13 . . . . . . . . . . . . . . . 131 !

7.5.14 Ventilation Exhaust Treatment System. . . . . . . . 131 7.5.15 Venting . . . . . . . . . . . . . . . . . . . . 132

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, APPENDICES i l

APPENDIX A - Technical Basis for Simplified Dose Calculations, I Liquid Effluent Releases. . ... .. . . . . .. . . . . A-1 )

APPENDIX B - Technical Basis for Effective Dose Factors .l Gaseous Effluent Releases ... .. . . . . . .. . . . . B-1 APPENDIX C - Radiological Environmental Monitoring ,

Program, Sample Location Maps . .... ... . . . . . . C-1 LIST OF TABLES Table 2 Radioactive Liquid Effluent Monitoring Instrumentation . 22 ,

Table 2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements .. . . . . . .. . . . . . . . 24 Table 2 Radioactive Liquid Waste Sampling and Analysis Program. . 26 Table 2 Limiting Radionuclide Concentrations in Secondary Side )

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 Bloaccumulation Factors . ... . . . ... . .. . . . . 33 O\,, Radioactive Gaseous Effluent Monitoring Instrumentation . 59 Table 3 Table 3 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements . .. . . . . . . . . .. . . . 62 Table 3 Radioactive Gaseous Waste Sampling and Analysis Program . 64 ;

Table 3 Land Use Census Summary . . . . ... . . . . . . . . . . 67 i,

Dose Factors for Noble Gases .

Table 3 . .. . . . . . . . . . . 68 i

Table 3 Exposure Pathways, Controlling Parameters, and i Atmospheric Dispersion for Mose Calculations. . .. . . . 69 Table 3 Inhalation Pathway Dose Factor. . .. . . .. . .. . . . 70 Table 3 Grass - Cow - Milk Pathway Dose Factors . . . . . . . . . 78 i i

Table 3 Grass - Cow - Heat Pathway Dose Factors . .. .. . . . . 86 r

Table 3-10 Vegetation Pathway Dose Factors . . . .. . . . . . . . . 92 Table 3 Ground Plane Pathway Dose Factors . . . . . . . . . . . . 98 Table 4 Recommended Exposure Rates in Lieu of Site Specific Data. . . . . .. . . . . . . . . . . . . . 107 DBP 6027A vili Revision 7.0 3 ODCM ;

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(List of Tables - Cont.)

Table 6 Radiological Environmental Monitoring Program . . . . . . 114 Table 6 Required Sampling Locations . . . . . . . . . . . . . . . 119 Table 6 Lower Limits of Detection . . . . . . . . . . . . . . . . 122 Table 6 Reporting levels for Radioactivity Concentrations in Environmental Sampler. . . . . . . . . . 125 Table B Default Noble Gas Radionuclide Distribution of Gaseous Effluents . . . . . . . . . . . . . . . . . . B-4 Table B Effective Dose Factors - Noble Gas Effluents . . . . . . B-5 LIST OF FIGURES Figure 2-1 -

Liquid Radioactive Effluent Monitoring and Processing Diagram . . . . . . . . . . . . . . . . . . . 34 Figure 3-1 -

Gaseous Radioactive Effluent Monitoring and Ventilation Systet.s Dir. cam . . . . . . . . . . . . . . . 99 0

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1.0 INTRODUCTION

Tte Davis-Besse Offsite Dose Calculation Manual (CDCM) describes the methodology and parameters used in:

1) determining the radioactive material release rates and cumulative releases;

2) calculating the radioactive liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints; and

3) calculating the corresponding doce rates and cumulative quarterly and yearly doses.

The ODCM also describes and provides requirements for the Radiological Environmental Monitoring Program. Sampling locations, media and collection frequencies, and analytical requirements are specified. The methodology provided in this manual is acceptable for use in demonstrating compliance with concentration ILmits of 10 CFR 20.1302; the cumulative dose criteria of 10 CFR 50, Appendix I; 40 CFR 190; and the Davis-Besse Technical Specifications (TS) 6.8.4.d and 6.8.4.e.

The exposure pathway and dose modeling presented provides estimates (e.g.,

calculational results) that ar conservative (i.e., higher than actual exposures in the environment). This conservatism does net invalidate the 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 purposen of demor.strating 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 training document of accepted methodologies and calculations. Changes to the ODCM calculational methodologies and parameters will be made as necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR ?? Appendix I,Section III and IV. Questions about the ODCM should U e vected to the Manager - Radiation Protection.

NOTE: Throughout this document, words appearing all capitalized denote definitions specified in Section 7.5 of this manual, or common acronyms.

Section 2.0 describes equipment for monitoring and controlling liquid effluents, sampling requirements, and dose evaluation methods. Section 3.0 provides similar information on gaseous effluent controls, sampling, and dose evaluation. Section 4.0 describes special dose analyses required for Regulatory Guide 1.21, Semiannual Effluent Reporting and EPA Environmental Dose Standard of 40 CFR 190. Section 5.0 describes the role of the annual land use. census in identifying the controlling pathways and locations of exposure for assessing the potential offsite doses. Section 6.0 describes the Radiological Environmental Monitoring Program. Section 7.0 describes the environmental, ef fluent and special rept . ting requirements, procedural requirements for major changes to liquid and gaseous radwaste systems, and definitions.

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2.0 LIQUID EFFLUENTS 2.1 RADIATION HONITORING INSTRUMENTATION AND CONTROLS 9, This section summarizes information on the liquid effluent radiation monitoring instrumentation and controls. More detailed information is provided in the Davis-Besse USAR, Section 11.2, Liquid Waste Systems and associated design drawings from which this summary was derived. location and control function of the monitors are displayed in Figure 2-1.

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, releases of radioactivity in liquid effluents during actual or potential releases. 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.

Earh 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 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 Required Monitors '

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\s_,r This section describes the monitoring required during 11guld releases and the backup sampling required when monitors are inoperable.

a) Alarm and Automatic Release Termination ,

1. Clean Radweste Effluent Monitors (RE-1770 A & B)

Discharges from the Clean Radwaste Monitor Tanks (2) are monitored by redundant radiation monitoring systems .

(RE-1770 A & B). These monitors detect gross gamma t activity in the effluent prior to mixing in the Collection i

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Box. Measurements from each detector read out on the Victoreen panel in the Control Room. Each monitoring system 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. t i

11. Miscellaneous Radwaste Effluent Monitors (RE-1878 A E B)

Discharges from the Miscellaneous Liquid Waste Monitor Tank and the Detergent Waste Drain Tank are monitored by ,

redundant radiation monitoring systems (RE-1878 A & B). !

These monitors detect gross gamma activity in the effluent line prior to mixing in the Collection Box. Measurements from each detector read out on the Victoreen panel in the control Room. Each' monitor is separately capable of l t

\ initiating an alarm and automatic termination of the release by closing valve WM-1876. Setpoint determination ,

f or the alarms is discussed in Section 2.3. ;

i b) Alarm (only) >

1. 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 i point into the Training Center Pond. The most probable ,

source of any radioactive material in the storm sewer would be from the secondary system. ,

When radioactivity is present in the secondary system, the Turbine Building Sump effluent shall be directed to the onsite Settling Basins. In this configuration, the source of radioactivity in the Storm Sewer Drain line is from Turbine Building drains that are not routed to the Turbine Building Sump, or from Storm Sewer drains. Evaluation of the alsrm setpoint for RE-4686 is discussed in Section 2.3.4.

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F c) Flow Rate Measuring Devices

1. Clean Radvaste Effluent Line Flow Indicator (FI) 1700 A & B Flow Totalizer (FQI) 1700 A & B

11. Miscellaneous Radwaste Effluent Line Flow Indicator (FI) 1887 A & B Flow Totalizer (FQI) 1887 A & B 111. Dilution Flow to the Collection Box Computer Point F201 2.1.2 Non-Required Monitors Additional monitors, although not required by the ODCH, have been installed to monitor radioactive material in liquid. The monitors are Collection Box outlet to the Lake (RE-8433) - monitors the final station effluent to the lake.

Component Cooling Water System (CCVS) (RE-1412 & 1413)-monitors the CCWS return lines. High alarm closes the atmospheric vent valves on the CCWS surge tank.

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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2.2 SAMPLING AND ANALYSIS OF LIQUID EFFLUENTS n-k ,) As a minimum, radioactive liquid wastes shall be sampled and analyzed

.nccording to the sampling and analysis program of Table 2-3. Table 2-3 Identifies three potential sources of liquid radioactive effluents. A fourth potential release point from the Turbine Building Sump is discussion 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 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 Faste Monitor Tank, and the Detergent Waste Drain Tank are classified as BATCH RELEASES. The following sampling and analysis requirements must 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).

- 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 liquid discharged.

- 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 gamma spectral analysis performed on all liquid raduaste effluents. Therefore. the Tab!.e 2-3 requirement for rampling and analysis of one batch per month for noble gases need not be performed as a separate program.

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2.2.2 continuous Releases Releases from the Turbine Building Sump (TBS) and Storm Sewer Drains (SSD) are classified as continuous releases.

Because the Turbine Building Sump discharges may contain minute concentrations of radionuclides due to primary-to-secondary system leakage, the Turbine Building Sump discharges are routed to the onsite Settling Basins instead of the SSD line. Overflow from the Settling Basins is pumped to the Collection Box where it is mixed with dilution flow and released to Lake Erie. Releases via this pathway are monitored by weekly analysis for principal gamma-emitting radionuclides and tritium, and by quarterly analysis of composite samples for Fe-55, Sr-89 and Sr-90.

Discharges to the Storm Sewer Drains are from Turbine Building drains that are not routed to the TBS and from storm drains when the 7BS effluent is routed to the Settlitg Basins. The Storm Sewer discharges to the Training Center Pond with the overflow discharging to the Toussaint River. For conservatism, it is assumed that radioactive material released to the Trainir.g Center Pond is ultimately discharged to Lake Erie (unless actions are taken to prevent this occurrence).

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 con =fdered for controlling any radioactive material releases via the TBS and SSD:

Increase the sampling frequency of the TBS and SSD until the source of the contamination is identified.

Perform gamma spectral analysis on each sample for principal gamma emitters.

Compare the measured radionuclide concentrations in the sample with EC (equation 2-2) to ensure releases are within the limits.

Based on the measured concentrations, a re-evaluation of the alarm setpoint for the SSD monitor (RE-4686) may be performed as specified in Section 2.3.4.

Consider each sample representative of the releases that have occurred since the previous sample. Determine the volume of liquid released from the Turbine Building Sump based on the Turbine Building Sump pump runtimes 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.

O DBP 6027A 6 Revision 7.0 i ODCM

{

1 l

i

F- ;

2.2.3 Condensate Demineralizer Backwash )

t rx, !

\,,) Discharges from the Condensate Demineralizer Backwash Receiving Tank j (BRT) to the South Settling Basin are sampled in accordance with l Table 2-3. Samples are collected prior to each release of the l resin / water slurry and separated into the liquid phase (transfer l water) and solid phase (resin). These samples are separately l analyzed for principal hamma emitters. Toledo Edison has imposed 1 guidelines on concentrations of radionuclides that may be discharged to the onsite Settling Basin. These guidelines are presented in Table 2-4.

The radioactive material contamination in the condensate demineralizer backwash will be contained on the powdered resin; soluble or suspended radioactive material associated with the water phase is not expected. The resin and the water are analyzed separately thus allowing for a determination of the amounts retained onsite in the Settling Basin (the resin) and the amounts released to Lake Erie as an effluent (the decant).

The BRT receives the spent resin from the Condensate Polishing System. Low-level radioactive material contamination of the spent resin is per.odically 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

/h 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 vaste disposal site.

If within the criteria of Table 2-4, the BRT may be discharged to the onsite settling basin with the approval of the Manager - Radiation Protection.

2.2.4 Borated Water Storage Tank and Primary Water Storage Tank The quantity of radioactive material stored in in the Borated Water Storage Tank (BWST) and Primary Water Storage Tank (PWST) shall bc limited to ensure the following:

1) Protected Area boundary dose rates remain less than 0.25 mR/hr, and

2) Tank rupture would resilt in ALAP.A isotopic concentrations at the nearest offsite potable water intake.

The concentration of radionuclides in the BWST and PWST shall be determined to be within the applicable limits by analyzing a representative sample of the tank contents at least once per 7 days when radioactive materials are being added to the tank. Although the PWST is not currently used to support plant operation, the following limits still would apply should it be in use.

(O _/ -

DBP 6027A 7 Revision 7.0 ODCM

j!

H ll J

The method for limiting the BWST and PWST radionuclide concentration to meet the criteria above is described below and represented in equation (2-1).

1) Determine the limiting fraction of esca 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.

n Cg

VOL

3785 LF = E (2-1)

I"I A lim i Where LF = sum of the limiting fraction of each radionuclide "i" in the sample, c = c ncentration of radionuclide "i* in the liquid sample d

(pC1/ml),

VOL = volume of liquid in the tank (gal),

3785 = ml per gal, O A = limiting activity of radionuclide "i" from Table 2-5 gg (pC1/ml), and n = number of radionuclides found in the liquid sample.

If the sum of the limiting fractions of radionuclides in the BWST or FWST exceeds one (1), then suspend all additions of radioactive material to the tank, reduce tank contents to within the limits, and describe the events leading to this condition in the next Radioactive Effluent Release Report.

The values in Table 2-5 were calculated specifically for the BWST.

They are conservative for the PWST due to its smaller volume.

O DBP 6027A 8 Revision 7.0 ODCH

q -

s i o , 1

.c .l 2.3 LIQUID EFFLUENT MONITOR SETPOINTC l 2'.3.1 Concentration Limits The concentrations of radioactive material released in liquid .i effluents to UNRESTRICTED AREAS shall be limited to the 'l 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 11guld effluents to UNRESTRICTED AREAS exceeds these limits,'then.

without delay restore the concentrations to within these limits.

This limitation provides additional assurance thet the. levels of l 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 on individual, and the limits.of 10 CFR Part 20.1302 to the population. _r

.l 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 ".ossaission on .i Radiological Protection (ICRP) Publication 2.

2.3.2 Basic Setpoir.t Equation l O 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 i

alarm / trip setpoint for liquid effluent monitors measuring the ,

radioactivity concentration prior to dilution is derived in .

Section 2.3.3.

i 2.3.3 Liquid Radwaste Effluent Line Monitor Setpoint Calculations (RE-1770A & B, RE-1878A & B) ;

The Liquid Radwaste Effluent Line Monitors provide alarm and {'

automatic terminktion 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 ,

L the liquid radwaste to be discharged is collected and analyzed by gamma spectroscopy to identify principal gansna-emitting ;

radionuclides. A maximum release rate from the tank is determined 3 for the release based on the radionuclide concentrations and the available dilution flow rate. !

O !

DBP 6027A 9 Rest ision 7.0 Of4M ,

The maximum release rate is inversely proportional to the ratio of the radionuclide concentrations to their EC values. This ratio of measured concentration to EC values is referred to as the EC fraction (ECF) and is calculated by the equation:

ECF = E (2-2) i EC g where ECF =

sum of the fractions of the unrestricted area EC for a mixture of radionuclides, Cg =

concentration of each radionuclide i measured in tank prior to release (pC1/ml), and EC'

=

unrestricted area EC for each radionuclide i from 10 CFR Part 20.1302. For dissolved and entrained noble gases an EC value of 2.0E-04 pC1/ml shall be used (pC1/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 for variations in monitor response and flow rates and also for the presence of radionuclides that may not be detected by the monitors (i.e., non-gamma emitters). The following equation is used for calculating the required minimum dilution tactor:

MDF = ECF/SF (2-3) where MDF = minimum required dilution f actor, SF = 0.3 administrative safety factor.

The maximum release rate from the tank is then calculated by dividing the available dilution flow rate (ADF) at the Collectien Box by the MDF as calculated by equation (2-4).

MAX RR =

0.9 (ADF/MDF) (2-4) where:

MAX RR =

maximum allowable release rate (gal / min),

0.9 =

adm2 41strative conservatism factor, and ADF =

available dilution flow rate at the Collection Box as measured by Computer Point F201 (gal / min).

O DBP 6027A 10 Revision 7.0 ODCM f --.

n

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i o b .. t NOTE: Equations (2-3) and (2-4) are valid only'for ECF >1. For '

[l- ECF <1, the waste tank concentration is below the limits of i s_s/- 10 CFR Part 20.1302 without dilution, and MAX RR rsy take [

on any value within discharge pump capacity, t If MAX RR is greater than the maximum discharge pump capacity, then I the pump capacity should bw used in establishing the actual. release rate (RR) for the radwaste discharge. For releases from the i Hiscellaneous Waste Monitor Tank and Detergent Waste Drain Tank, the [

discharge pump capacity is 100 gpm; for the Clean Waste Monitor Tank, this value is 140 gpm.

&ince the actual release rate from the tank is derived such that 10 ,

c

'FR 20.1302 limits will not be exceeded given the radionuclide concentration in the tank and the available dilution flow, setpoints '

must be established to ensure:

1) radionuclide concentration released from the tank does not increase above the concentration detected in the sample,

2) available dilution flow does not decrease, and ,

3) actual release rate from the tank does not increase above the calculated value. ,

i The setpoints for the predilution radiation monitor (RE-1770 A & B, or RE-1878 A & B) are determined as follows:

\ Alert Alarm SP = [2

R

E (C g

SENg )] + Bkg (2-5)

High Alarm SP = [3

R

E (Cf.* SENg )) + Bkg (2-6) where

'SP = setpoint of the radiation monitor (cpm),

l I

Cg = concentration of radionuclide i as measured by gamma spectroscopy (pCi/ml),

SEN. =

monitor sensitivity for radionuclide i based on calibration curve (cpm per pCi/ml), and -)

i Bkg = background reading of the radiation monitor (cpm).

R = MAX RR / actual release rate The Cs-137 sensitivity may be used in lieu of the sensitivity values for individual radionuclides. The Cs-137 sensitivity provides e reasonably conservative monitor response correlation for radionuclides of interest in reactor effluents. Coupled with the l safety factor SF in equation (2-3), this assumption simplifies the l evaluation without invalidating the overall conservatism of the setpoint determination.

/~') )

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I DBP 6027A 11 Rev!sion 7.0 ODCM ,

1

]

The high flow setpoint should be set equal to the MAX RR calculated in equation (2-4). The low flow setpoint for dilution flow rate should be set at 0.9 times the available dilution flow rate.

2.3.4 , Storm Sewer Drain Monitor (RE-4686)

The setpoint for the SSD radiation monitor, RE-4686, shall be established to ensure the concentration in the effluent does not exceed the limits of 10 CFR 20.1302. The SSD is not normally radioactively contaminated by other than naturally-occurring radionuclides. Therefore, the setpoint for this monitor has been established at a practical level to provide an early indication of any abnormal conditions without causing spurious alarm due to fluctuations in background.

Since discharge is to the Training Center Pond, exceeding the RE-4686 setpoint does not necessarily mean Section 2.3.1 concentration limits have been exceeded at UNRESTRICTED AREAS. The verification of compliance with the limits on concentration should be based on actual samples of the effluent from the pond to the Toussaint River and Lake Eric. (Refer to Sectior: 2.3.6).

2.3.5 Alarm Setpoints for the Non-Required Radiation Monitors a) Collection Box Outlet to the Lake (RE-8433)

The radiation monitor on the Collection Box outlet utilizes a single off-line detector to continuously monitor all station liquid effluent discharges to the lake. Although this is the final effluent monitor, it does not serve any control function.

Control functions have been placed on the upstream undiluted effluent line that will terminate the release prior to exceeding the effluent concentration for UNRESTRICTED AREAS in 10 CFR 20.1302. 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 backgrounj fluctuations. The setpoint is controlled in accordance with the Radiation Monitor Setpoint Manual.

b) Component Cooling 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.

O DE 6027A 12 Revision 7.0 ODCM

.o c) Service Water System (SWS) (RE-8432) ,

fM

'd . '~

No radioactive material is expected to be contained within the SWS during normal operations. Therefore, the high alarm setpoint is established to prevent incurring a spurious alarm due to background fluctuations. The setpoint is controlled in accordance with the Radiation Monitor Setpoint Manual.

d)- Intake Forebay Monitor (RE-8434)

The high alarm setpoint is established to prevent incurring a spurious alarm due to background fluctuations. The setpoint is controlled in accordance with the Radiation Monitor Setpoint Manual.

Although highly 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 Rsdiation Monitor Setpoint Manual.

~2.3.6 Alarm Response - Evaluating Actual Release Conditions Liquid release rates are controlled and alarm setpoints are established to ensure that releases do not exceed the concentration limits of Section 2.3.1 (i.e., 10 CFR 20 ECs at the discharge to Lake Erie). However, if any of the monitors (RE-1770 A & B, RE-1878 A & B, or RE-4686) alarm during a liquid release, it becomes necessary to re-evaluate the release conditions to deterraine 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 releases

- re-sample and re-analyze the source of the release'

- re-determine the release rate and the dilution water flow.

Based on available data, the following equation may be used for evaluating the actual release conditions: ;

(2-7)

E 51 EC g DF + RR Cg = measured concentration of radionuclide i in the effluent i

stream prior to dilution (pcilml),

EC f

= the Effluent Concentration for radionuclide i from Appendix B. Table II, Column 2 of 10 CFR 20.1001 - 20.2401 or 2.0E-04 pCi/mi for disse!ved or entrained noble gases (pCi/ml).

DBP 6027A 13 Revision 7.0 ODCM

RR =

actual release rate of the liquid effluent at the time of the alarm (gal / min), and DF =

actual dilution water flow at the time of the release alarm (gal / min).

If the value calculated by equation 2-7 is less than or equal to 1, then the release did not exceed the limits of 10CFR 20.1302.

O O

DBP 6027A 14 Revision 7.0 ODCM

,-. 2.4' LIQUID EFFLUENT DOSE CALCULATION - 10 CFR 50 +

km 2.4.1 Dose Limits'to MEMBERS'0F THE PUBLIC The limits for dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from Davis-Besse. The .!

ILuits ares :

- during any calendar quarter

$ 1.5 mrem to total dody 5 5.0 mrem to any organ

- during any calendar year 5 3.0 mrem to total body ;

5 10.0 mrem to any organ With the calculated dose from the release of radioactive materials in !

liquid effluents exceeding any of the above limits, in lieu of a ,

Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, a Special Report that identifies j the cause(s) for exceeding the limit (s) and defines the corrective 1 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 ef fluents 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-O- once per 31 days. l This requirement is provided to implement the requirements of Sections II.A. III.A and IV.A of Appendix I, 10 CFR Part 50.

This action provides the required operating flexibility and at the ,

same time implements the guides set forth in Section IV.A of Appendix 1, 10 CFR Part 50 to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." 1 i

N I

'[d !

DBP 6027A 15 Revision 7.0 ODCM

NOTE: For fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements of Section III.A of Appendix I, 10 CFR Part 50. Conformance with the guides of Appendix I is to be shown by calculational procedures based on 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 effluents are consistent with the methodology provided in Regulatory Cuide 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.

2.4.2 MEMBER OF THE PUBLIC DOSE - Liquid Effluents The calculation of the potential doses to MEMBERS OF THE PUBLIC is a function of the radioactive material releases to the lake, the subsequent transport and dilution in the exposure pathways, and the resultant individual uptake. At Davis-Besse, the combined fish consumption and drinking water pathway has been modeled to provide a conservative dose assessment for exposures to MEMBERS OF THE PUBLIC.

For the fish pathway, it has been conservatively assumed that the maximum exposed individual consumes 21 kg per year of fish taken in the immediate vicinity of the Davis-Besse discharge to the lake. For the drinking water pathway, the conservative mcdeling is based on an 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 water from these beach wells is not suitable for consumption; however, for conservatism this pathway has been included in the dose modeling for the maximum exposed individual.)

The equation for assessing the maximum potential dose to MEMBEPS OF THE PUBLIC from liquid raddaste releases from Davis-Besse 18: -

1.67E-02

VOL Dg =

E (C g *A gg) (2-8) where:

Dg =

dose or dose commitment to organ "o" including total body (wrem).

A yg =

site-specific ingestion dose commitment factor to the total body or any organ "o" for radionuclide "1" given in Table 2-6 (mrem /hr per pCi/ml),

DBP 6027A 16 Revision 7.0 ODCM

1 e.- .

l l

C

= ' average concentration of radionuclide i in undiluted liquid effluent representative of the the volume VOL (pci/ml),

j[j\;-

-N VOL = total volume of undiluted liquid effluent released (gal),

DF = average dilution water flow rate during release period (gal / min) (typically 20,000 gpm),

2 = 10 (near field dilution factor)*

b 1.67E-02 = 1 hr/60 min.

The site-specific ingestion dose / dose commitment factors (Ago) 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 gg are presented in -7 Table 2-6. These values were derived in accordance with the guidance of NUREG-0133 using the following equation: }

A g9 = 1.14E+05 (Ug/Dy+UF

BFg) DF g (2-9) where: J U

F-

= 21 kglyr adult fish consumption, Up = 730 liters /yr adult water consumption, g Dg = 5.7 additional dilution from the near field to the beach

' wells (net dilution of 57),

BF g = bioaccumulation factor for radionuclide "i" in fish from Table 2-7 (pC1/kg per pCill), l DF g = dose conversion factor for nuclide "1" for adults in organ "o" from Table E-11 of Regulatory Guide 1.109 ,

(mrem /pci), and -

1.14E+05 = 10 6 (pC1/pCi)

10 3 (ml/kg) / 8760 (hrifr).

i t

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 I 1980.

(

DBP 6027A 17 Revision 7.0 DDCH ,

The radionuclides included in the periodic dose assessment required by Section 2.4.1 are those identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of Table 2-3. In keeping with the NUREG-0133 guidance, the adult age group represents the maximum exposed individual age group.

Evaluation of doses for other age groups is not required for demonstrating compliance with the dose criteria of Section 2.4.1.

The dose analysis for radionuclides requiring radiochemical analysis will be performed after 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 Simplified Liquid 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 dosa limits required by Section 2.4.1. Radionuclides included in this dote calculation should be those measured in the grab sample of the r21 ease (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 D ., = *EC g (2-10)

Maximun, organ 1.19E+03

VOL D,,, = *E C f (2-11) where:

C 1

=

average concentration of radionuclide i excluding H-3 in undiluted liquid effluent representative of the release volume (pC1/ml).

VOL = volume of liquid effluent released (gal),

DF =

average dilution water flow rate during release period (gal / min),

D b

=

c neervatively evaluated total body dose (mrem),

D,,, =

conservatively evaluated maximum organ dose (mrem),

9.70E+02 =

0.0167 (hr/ min)

5.81E+05 (mrem /hr per pCifml, Cs-134 total body dose factor from Table 2-6) / 10 (near field dilution), and O

DBP 6027A 18 Revision 7.0 ODCM

fl.

1.19E+03 =

~

0.0167 (hr/ min).* 7 11E+05'(mrem /hr per pCi/ml Cs-134

"'~')

I liver dose factor from Table 2-6) / 10 (near field k,/ ' dilution).

2.4.4' Contaminated TBS /SSD System - Dose Calculation

.All non-naturally occurring radioactivity released from the SSD must be included in the evaluation of the cumulative dose to a MEMBER OF THE PUBLIC. Although the discharges are via the Training Center Pond to Pool 3. and then to the Toussaint River (instead of directly to Lake Erie), the modeling of equation (2-8) remains reasonably conservative for determining a hypothetical maximum individual dose.

The following assumptions should be applied for the dose assessment of any radioactive material releases from the SSD into the Training Center Pond and subsequently to the Toussaint Rivers

- If no additional controls are taken, then it should be assumed that any radioactive material released to the Training Center Fond 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 J

- The dilution flow should consider additional dilution of the SSD discharge from other sources into the Training Center Pond prior to release to the rives l

H i

l DBP 6027A 19 Revision 7.0 ODCH I

2.5 LIQUID EFFLUEhT DOSE PROJECTIONS 10 CFR 50.36s requires licensees to maintain and operate the radwaste system to ensure releases are maintained ALARA. This Section impuments O

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 radvaste, the specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as the dose design objectives as set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents. This requirement is implemented through this ODCH.

The liquid radioactive waste processing system shall be used to reduce the radioactive material levels in the 11guld 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 qaarter of the '

design objective rate (i.e., 1/4 of 3 mrem /yr total body and 10 mrem /yr any organ over a 31-day projection).

With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, a Special Report that includes the following information explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability; action (s) taken to restore the inoperable eqeiprent to OPERABLE status: and summary description of action (s) taken to prevent r recurrence.

In any month in which radioactive liquid effluent is being discharged without treatment, doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCH.

The following equations may be used for the dose projection calculation:

D tbp =Dg (31 / d) (2-12)

D =D (31 / d) (2-13) where:

O tbp

=

the 31-day total body dose projection (mrem),

O DBP 6027A 20 Revision 7.0 ODCM

_r.

D = the cumulative total body dose for current calendar quarter tb including release under consideration as determined by equation.

/

-( (2-8) or (2-10) (mrem),

D = the 31-day maximum organ dose projection (mrem).

p D = the maximum organ dose for current calendar quarter including

""* release under consideration as determined by equation (2-8) or (2-11) (mrem),

d = the number of days accounted for by the calendar quarter dose, and 31 = the number of days in projection.

i O

i

(

I l0 Revision 7.0 DBP 6027A 21 l

fE ODCM

-~

HIMIMUH g CHANNELS *

'o INSTRUMENT OPERABLE APPLICABILITY ACTION o

N 1. Gross Radioactivity Monitors

> Providing Alarms and Automatic Termination of Release

a. Liquid Radwaste Effluent Line 1 (1) A (either Hiscellaneous or Clean. O but not hath simultaneously) $

0

2. Flow Rate Measurement Devices t$

t-

a. Liquid Radwaste Effluent Line 1 (t) B 5 3

h. pilution Flow to Collection Box 1 (1) B tw n

6. Gross Beta ut Gamma Radioactivity E Honituts Providing Alarm But Not MY N

Providing Automatic Termination of Release E8*

" x ON

a. Storm Sewer Drain 1 (1) B,C O

3

=

o i z I

5 m

z 4

>4 O *A O O tt Z o<

E X

v o -

i tn l y .in e setease trather HVHT or CWHT) at a t iiiie cast be iii inaugtess, l .

, p.

Table 2-1 (continued) ,

O I

TABLE NOTATION i

(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 releases i

1. At least two independent samples are analyzed in accordance with Table 2-3 for analyses performed with each batch:

2. At least two independent verification of the release rate ;

calculations are performed:

3. At least.two independent verifications of the. discharge ;

valving are performed <

Otherwise, suspend release of radioactive effluents via this pathway, t ACTION B With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases via ,

this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 '

hours, during effluent releases, grab samples are collected and '

analyzed for gross radioactivity (beta or gamma) at a lower

limit of detection no greater than 1.0E-07 pC1/ml.

r O

DBP 6027A 23 Revision 7.0 ODCM a

! E l

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Gross Beta or Gamma Radioactivity w Honitors Providing Alarm and $ $

Automatic Isolation, if applicable. $3o I I I I I2I

a. Liquid Radweste Effluents Lines D P R Q z 5EM

b. Storm Sewer Discharge Line D(4)

H R(3) Q(2) d o e z w

2. Flow Rate Monitors m @g N UE w a. 1.iquid Radwaste Effluent Lines D N.A. R Q $ m7 E lm 13 . Dilution Flow to Collection Box D( I N.A. R Q

{ di a5 A 5 8~ 5 e

h 3

. s 8a' a<

e X

a

?

o O O O. .

4 Table 2-2 (continued)

_ jm ms TABLE NOTATION (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 activities with NIST. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, scarces 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 radioective 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.

f V} (D) At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(M) At least once per 31 days.

(P) Prior to each release. ]

l. (R) At least once per 18 month (550 days) .

l !

i (Q) At least ence per 92 days.

1 l

l I

I l

}() DBP 6027A 25 Revision 7.0 ODCM Y

m i

.i Table 2-3 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Type of Lower Limit Liquid Release Type Sampling Analysis Activity of Detection Frequency Frequency Analysis (LLD) (pC1/ml),

P P Principal A. Batch Waste Each Batch Each Batch Gamma 5.0E-07 d g Release Tanks Emitters I

I-131 1.0E-06 P Dissolved One Batch /M M and Entrained 1.0E-05 Gases P M Each Batch Composite" H-3 1.0E-05 Gross Alpha 1.0E-07 P Q c Each Batch Composite Sr-89, Sr-90 5.0E-08 Fe-55 1.0E-06 B. Storm Sewer Principal Drain Continuously S' Gamma 5.0E-07 monitored Emitters 1-131 1.0E-06 P P Principal C. Condensate Each Batch Each Batch Gamma b 5.0E-07 Demineralizer when when Emitters Backwash discharged discharged to the to the settling settling I-131 1.0E-06 basin basin i

O DBP 6027A 26 Revision 7.0 ODCM

Table 2-3 (continued)

TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95Z probability with 5Z probability of falsely concluding that a blank observation represents a 'real' signal.

For a particular measurement system (which may include radiochemical separation):

LLD =

E

V

2.22

Y

exp (-Aat) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);

S is the standard deviation of the background counting rate or of h

the counting rate of a blank sample as appropriate (as counts per minute);

E is the counting efficiency (as counts per transformation);

V is the sample size (in units of mass or volume);

2.22 is the number of transformations per minute per picocurle; Y is the fractional radiochemical yield (when applicable);

A is the radioactive decay constant for the particular radionuclide; At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

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 an a posteriori (after the fact) limit for a particular measurement.

DBP 6027A 27 Revision 7.0 ODCM

I l

l Table 2-3 (continued)

TABLE NOTATION

b. The principal gamma emitters for which the LLD specification will apply are exclusively the following radio..aclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134. Cs-137, and Ce-141. For Ce-144, the LLD is 2.0E-06 pC1/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 emf l oyed results is a specimen which is representative of the liquids released.

d. A BATCH RELEASE ~is the discharge of liquid v ntes of a discrete volume,

e. When the monitor is out of service, a grab sample shall be taken and analyzed once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if there is flow from the Storm Sewer line.

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/mi and a COMPOSITE SAMPLE is analyzed for principal gamma emitters when instrumentation is available,

g. Frequency notation:

P - Prior to each release.

M - At least once per 31 days.

Q - At least once per 92 days.

S - At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (when the monitor is inoperable).

O DBP 6027A 28 Revision 7.0 ODCM

I h

Table 2-4 j Limiting Radionuclide Concentrations

In Secondary-Side Clean-Up Resins for Dischargos to Onsite Settling Basin j Radionuclide LimitingConcengration**

(pci/cm )

Cr-51 3.3E-02 Hn-54 6.2E-05 Fe-59 5.1E-04 Co-58 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 3.5E-02 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 1.1E-02 Te-132 7.4E-03 I-131 1.1E-04 I-133 3.8E-04 I-135 1.5"-03 Cs-134 1.1E-05 Cs-136 2.6E-03 Cs-137 1.0E-05 Ba-140 1.1E-02 La-140 7.4E-03 Ce-141 5.8E-03 Ce.144 4.1E-05 Pr-143 1.9E-02 -

Concentration limits based on the study, Disposal of Low-Level Radioactively Contaminated Secondary-Side Clean-up Resins in the On-site Settling Basins at the Davis-Besse Nuclear Power Station, J. Stewart Bland, May 1983. The limits represent a hypothetical maximum 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 report have been reduced by a factor of 10 for added conservatism -

representing a hypothetical dose of less than 0.1 mrem.

- With more than one radionuclide identified in a resin batch, the evaluation for acceptable discharge to the onsite settling basin shall be based on the

' sum of the fractions" rule as follows: Determine for each identified radionuclide the ratio between the measured concentration and the limiting concentration; the sum of these ratios for all radionuclides should be less than one (1) for discharge to the basin.

O DBP 6027A 29 Revision 7.0 ODCM i

Table 2-5 Radionuclide Activity Limits for the BWST and PWST Radionuclide Total Activity (C1)

H-3 2.12E+03 Cr-51 2.88E+02 Mn-54 1.41E+01 Fe-59 1.07E+01 i Co-57 1.26E+02 I Co-58 1.18E+01 l Co-60 5.14E+00 Zn-65 2.16E+01 Rb-88 1.04E+02 3r-89 2.12E+00 i Sr-90 2.12E-01 1 Sr-91 1.73E+01 Sr-92 9.72E+00 Y-91 2.12E+01 Y-93 2.12E+03 Z r- 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 I 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 1-132 5.00E+00 1-133 7.05E-01 I-134 4.53E+00 1-135 2.82E+00 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 5.3BE+00 Ce-141 6.35E+01 Ce-144 7.05E+00 DBP 6027A 30 Revision 7.0 ODCM

Table 2-6 Davis-Besse Site-Specific Liquid Ingestion Dose Commitment Factors A gg (mrem /hr per pCi/ml)

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+0 1.76E+0 1.76E+0 1.76E+0 1.76E+0 1.76E+0 1.76E+0 C-14 3.13E+4 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 hia-24 4.32E+2 4.32E+2 4.32E+2 4.32E+2 4.32E+2 4.32E+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 Hn-54 0.00E+0 4.44E+3 8.48E+2 0.00E+0 1.32E+3 0.00E+0 1.36E+4 Hn-56 0.00E+0 1.12E+2 1.98E+1 0.00E+0 1.42E+2 0.00E+0 3.57E+3 Fe-55 6.99E+2 4.83E+2 1.13E+2 0.00E+0 0.00E+0 2.69E+2 2.77E+2 Fe-59 1.10E+3 2.59E+3 9.93E+2 0.00E+0 0.00E+0 7.24E+2 8.64E+3 Co-57 0.00E+0 2.35E+1 3.91E+1 0.00E+0 0.00E+0 0.00E+0 5.96E+2 Co-58 0.00E+0 1.00E+2 2.24E+2 0.00E+0 0.00E+0 0.00E+0 2.03E+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.J0E+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 0.00P&O 0.00E+0 5.91E+1 Br-84 0.00E+0 0.00E+0 5.31E+1 0.00E+0 0.00t+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 0.00E+0 7.59E+3 Y-91m 6.77E-3 0.00E+0 2.62E-4 0.00E+0 0.00E+0 0.00E+0 1.99E-2 Y-91 1.05E+1 0.00E+0 2.81E-1 0.00E+0 0.00E+0 0.00E+0 5.78E+3 Y-92 6.29E-2 0.00E+0 1.84E-3 0.00E+0 0.00E+0 0.00E+0 1.10E+3 Y-93 2.00E-1 0.00E+0 5.51E 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+2 1.34E+2 0.00E+0 2.46E+2 0.00E+0 1.51E+6 Nb-97 3.75E+0 9.48E-1 1.46E-1 0.00E+0 1.11E+0 0.00E+0 3.50E+3 Ho-99 0.00E+0 1.66E+? 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 0.00E40 3.33E-1 9.45E-3 5.56E-14 Ru-103 7.13E+0 0.00E+0 3.07E40 0.00E+0 2.72E+1 0.00E+0 8.32E+2 l Ru-105 5.94E-1 0.00E+0 2.34E-1 0.00E+0 7.67E+0 0.00E+0 3.63E+2 l Ru-106 1.06E+2 0.00E+0 1.34E+1 0.00E+0 2.05E+2 0.00E+0 6.86E+3 I Rh-103m 0.00E+0 0.00E+0 0.00E40 0.00E+0 0.00E40 0.00E+0 0.00E+0 l

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 3.22E+0 2.98E40 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 7.0 l

ODCH l

__..y

i l

Table 2-6 (continued) !

Davis-Besse Site-Specific Liquid Ingestion Dose Commitment Factors. Agg I fN(_,) (mrem /hr per pCi/ml)

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sb-125 3.04E+1 3.40E-1 7.24E+0 3.09E-2 0.00E+0 2.35E+1 3.35E+2 Te-125m 2.61E+3 9.44E+2 3.49E+2 7.84E+2 1.06E+4 0.00E+0 1.04E+4 Te-127m 6.58E+3 2.35E+3 8.02E+2 1.68E+3 2.67E+4 0.00E+0 2.21E+4 Te-127 1.07E+2 3.84E+1 2.31E+1 7.92E+1 4.36E+2 0.00E+0 8.44E+3 Te-129m 1.12E+4 4.17E+3 1.77E+3 3.84E+3 4.67E+4 0.00E+0 5.63E+4 Te-129 3.05E+1 1.15E+1 7.44E+0 2.34E+1 1.28E+2 0.00E+0 2.30E+1 Te-131m 1.68E+3 8.22E+2 6.85E+2 1.30E+3 8.33E+3 0.00E+0 8.17E+4 Te-131 1.92E+1 8.00E+0 6.05E+0 1.57E+1 8.39E+1 0.00E+0 2.71E+0 Te-132 2.45E+3 1.58E+3 1.49E+3 1. 7 5E .-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 1-131 2.10E+2 3.01E+2 1.72E+2 9.85E+4 5.15E+2 0.00E+0 7.93E+1 1-132 1.03E+1 2.74E+1 9.60E+0 9.60E+2 4.37E+1 0.00E+0 5.15E+0 I-133 7.17E+1 1.25E+2 3.80E+1 1.83E+4 2.18E+2 0.00E+0 1.12E+2 1-134 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 Cs-137 3.83E+5 5.23E+5 3.43E+5 0.00E+0 1.78E+5 5.91E+4 1.01E+4 Cs-138 2.65E+2 5.'IE+2 2.59E+2 0.00E+0 3.85E+2 3.30E+1 2.23E-3 Ba-139 2.35E+0 1.UiE-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

[/h

\s,. Ba-141 Ba-142 1.14E+0 5.15E-1 8.61E-4 5.29E-4 3.84E-2 3.24E-2 0.00E+0 0.00E+0 8.00E-4 4.47E-4 4.88E-4 3.00E-4 5.37E-10 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 Ce-141 1.59E-1 1.08E-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 l

l l

l O

DBP 6027A 32 Revision 7.0 l ODCM l

Table 2-6 (continued)

Davis-Besse Site-Specific Liquid Ingestion Dose Commitment Factors, Agg (mrem /hr per pCi/ml)

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sb-125 3.04E+1 3.40E-1 7.24E+0 3.09E-2 0.00E+0 2.35E+1 3.35E+2 Te-125m 2.61E+3 9.44E+2 3.49E+2 7.84E+2 1.06E+4 0.00E+0 1.04E+4 Te-127m 6.58E+3 2.35E+3 8.02E+2 1.68E+3 2.67E+4 0.00E+0 2.21E+4 Te-127 1.07E&2 3.84E+1 2.31E+1 7.92E+1 4.36E+2 0.00E+0 8.44E+3 Te-129m 1.12E+4 4.17E+3 1.77E+3 3.84E+3 4.67E+4 0.00E+0 5.63E+4 Te-129 3.05E+1 1.15E+1 7.44E+0 2.34E+1 1.28E+2 0.00E+0 2.30E+1 Te-131m 1.68E+3 8.22E+2 6.85E+2 1.30E+3 8.33E+3 0.00E+0 8.17E+4 Te-131 1.92E+1 8.00E+0 6.05E+0 1.57E+1 8.39E+1 0.00E+0 2.71E+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 1-132 1.03E+1 2.74E+1 9.60E+0 9.60E+2 4.37E+1 0.00E+0 5.15E+0 I-133 7.17E+1 1.25E+2 3.80E+1 1.83E+4 2.18E+2 0.00E+0 1.12E+2 I-134 5.35E+0 1.45E+1 5.20E+0 2.52E+2 2.31E+1 0.00E+0 1.27E-2 I-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 Cs-137 3.83E+5 5.23E+5 3.43E+5 0.00E+0 1.78E+5 5.91E+4 1.01E+4 ,

Cs-138 2.65E+2 5.23E+2 2.59E+2 0.00E+0 3.85E+2 3.80E+1 2.23E-3 i 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 3.1-Z-2 0.00E+0 8.00E-4 4.88E-4 5.37E-10 Ba-142 5.15E-1 5.29E-4 3.. E-2 0.00E+0 4.47E-4 3.00E-4 7.25E-19 f La-140 1.86E-1 9.38E-2 2.48E-2 0.00E+0 0.00E+0 0.00E+0 6.89E+3 l La-142 9.53E-3 4.33E-3 1.08E-3 0.00E+0 0.00E+0 0.00E+0 3.16E+1 ,

Ce-141 1.59E-1 1 08E-1 1.22E-2 0.00E+0 5.00E-2 0.00E+0 4.11E+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 3.397.-2 0.00E+0 1.59E-1 0.00E+0 3.00E+3 '

Pr-144 2.24E-3 9.31E-4 1. J t2-4 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 'J . 6 9 E + 1 0.00E+0 0.00E+0 0.00E+0 8.14E+4 Np-239 4.59E-2 4.51E-3 2.49E-3 0.00E40 1.41E-2 0.00E+0 9.25E+2 l

DBP 6027A 32 Revision 7.0 ODCM

1 Table 2-7 Bioaccumulation Factors (BF1)

(pC1/kg per pCi/11ter)*

Element Freshwater Fish H 9.0E-01 C 4.6E+03 Na 1.0E+02 P 3.0E+03 Cr 2.0E+02 Mn 4.0E+02 Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 Br 4.2E+02 Rb 2.0E+03 Sr 3.0E+01 Y 2.5E+01 Zr 3.3E+00 Nb 3.0E+04 Mo 1.0E+01 Tc 1.5E+01 Ru 1. 0E F01 Rh 1.0E+01 Ag 2.3E+00 Sb 1.0E+00 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

Values in this Table are taken from Regulatory Guide 1.109 except for phosphorus which is adapted from NUREG/CR-1336 and silver and antimony which ,

are taken from UCRL 50564. Rev. 1. October 1972. ,

DBP 6027A 33 Revision 7.0 f

ODCM

i l

l I

l

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Figure 2-1 '

Liquid Radioactive Effluent Monitoring and Processing Diagram O. i 1

{

I 1

i LEGEMD e ::n n:-

DAVIS-BESSE NPS 3**

LIQUID RAD 10 ACTIVE

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RELEASE PATHWAYS g.3.

contarm rur BUILDING "i'.*tt*"

f

= %= '

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O l DBP 6027A 34 Revision 7.0 ODCH i

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~

l 3.0 CASEOUS EFFLUENTS 3.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS This Section specifies the gaseous effluent monitoring instrumentation required at Davis-Besse for controlling and monitoring radioactive effluents. Location and control function of these monitors are displayed in Figure 3-1. More information is provided in the Davis-Besse USAR, Section 11.3, Gaseous Waste System.

The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Section 3.3 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section 3.3.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the actions shown in Table 3-1. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report (Section 7.2) why the inoperability was not corrected in a timely manner.

Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 3-2. Each of these operations shall be performed within the specified time interval with a maximum allowable extension not to exceed 25 percent of the specified interval.

NOTE: The monitors specified in Table 3-2 are inoperable if surveillances are not performed or setpoints are less conservative than required.

The radioactive gaseous effluent instrumentation is provided to monitor -

and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with methods in Section 3.3 to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

l 1

I tilli DBP 6027A 35 Revision 7.0 ;

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3.1.1 Alanm and Automatic Release Termination

\

/( / _, a) Waste Gas Decry System Monitor (RE-1822 A&B)

The radioactive vaste gas discharge line is continuously monitored by tw) off-line detectors, each measuring gross activity. The aonitors' control function will terminata the waste discharge pcio: to exceeding the release rate limits of 4 Section 3.3.2. Table 3-1 requires that the Waste Gas Decay System contain as a minimum the following instrumentation:

- noble gas activity monitor (RE-1822 A or B), and

- effluent system flow rate measuring device (FT-1821 or 1821 A).

If both noble gas monitors are declared inoperable, then the contents of the tank may be released provided that prior to the releases

- at least two independent gas samples are collected and analyzed by gamma spectroscopy for principal gamma emitters (noble gases).

- at least two independent verifications of the release rate calculations are performed, and

- at least two independent verifications of the discharge

[)\

\s, valve line-up are performed.

If ,he 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Flow rates may be estimated based on fan curves '

or discharge valve header positioning.

b) Containment Purge Exhaust Filter Monitor (RE-5052 A,B&C)

This detector monitors the containment atmosphere for radioactivity during Containment VENT or PURGE. The noble gas activity monitor (Channel C) is required by Table 3-1. It provides an automatic termination of the release prior to 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.

O DBP 6027A 36 Revision 7.0 ODCM

3.1.2 Alarm 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, sampler flow rate measuring device, and unit vent flow rate measuring device (computer points F883 or F885).

The hydrogen purge line serves as a Containment pressure relief route to the Station Vent. A separate radiation monitor on this line is not required. Any release through the hydrogen purge line will be monitored by the Station Vent monitor, RE-4598.

b) Waste Gas System Oxygen Monitors (AE 5984 and 6570)

The Waste Gas System is provided with two oxygen monitors (with an alarm function) as required by Table 3-1 to alert operators in the unlikely event of oxygen leakage into the waste gas header. The concentration of oxygen is limited to less than or equal to 22 by volume whenever the hydrogen concentration exceeds 42 by volume. An oxygen concentration above the specified limit will actuate a local and control room alarm.

O DBP 6027A 37 Revision 7.0 ODCM

1

-. 3.2 SAMPLING AND ANALYSIS OF GASEOUS EFFLUENTS ,

(\ss) . Radioactive gaseous wastes shall be sampled and analyzed in accordance with Table 3-3. This sampling and analysis ensures that the dose rates i and doses from gaseous effluents remain below the release rate limits of ;

S6: tion 3.3.2, and the dose limits of Sections 3.7.1 and 3.8.1. !

3.2.1 Batch Releases {

Table 3-3 requires that a grab gas sample be collected and analyzed prior to each BATCH RELEASE from the Waste Gas Decay Tanks (WGDT) or a Containment PURGE. The analysis shall include the identification of all principal gamma emitters (noble gas) and tritium. Although t 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. ,

t 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 i All releases from the Station Vent are required to be continuously sampled for radioactivity. As specified in Table 3-3, the following ;

minimum samples and analyses are required

- once per week, analysis of an absorption media (e.g., charcoal l cartridge) for I-131. j

- once per week, analysis of a filter sample for all prircipal ;

gamma emitters (particulate radioactive material), j

- once per month, analysis of a grab gas sample for all principal gamma emitters (noble gas) and tritium,

- once per month, analysis of a composite of the particulate samples of all releases for that month for gross alpha activity,

- once per quarter, analysis of a composite of the particulate samples for all releases for that quarter for Sr-89 and 90, and

- continuous monitoring for noble gases (gross beta and gamma activity). !

t I

l i

r

() ,

DBP 6027A 38 Revision 7.0 l ODCM i

L 1 l

3.2.3 Releases Resulting from Primary-to-Secondary System Leakage Should the secondary coolant system become contaminated, then there are several additional gaseous release points to consider:

The Atmospheric Vent Valves (AVVs),

Main Steam System Relief Valves (MSSVs).

Auxiliary Feed Pump Turbines (AFPTs), and Auxiliary Steam System Relief Valves.

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 '

to overpressurization of the Auxiliary Steam System via the relief valves on the various steam headers.

For secondary coolant system release pathways, the following minimum samples and analyses are required:

once per week, analysis of a secondary system off-gas sample for principal gamma emitters (noble gases) and tritium; once per week, analysis of a ;,econdary system liquid sample for principal gamma emitters (iodic.es 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 l its return to the steam generator as feedwater. However, these i processes do not remove tritium.

l l

DBP 6027A 39 Revision 7.0 '

ODCM

e p.

3.3 GASEOUS EFFLUENT HONITOR SETPOINT DETERMINATION

/ \

(m,/ 3.3.1 Tota 1 5ffective Dose Equivalent Limits 10 CFR 20.1301 limits the total effective dose equivalent, (TEDE), to individual members of the public from all licensed operations to l 100 mrem 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 Vent alarm setpoints shall be established to initiate Control Room isolation when the activity level exceeds the Derived AIR Concentration limits of 10 CFR 20 and to ensure release rate of noble gas, radiciodine 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:

l N !

1

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 l Iodine 131, Tritium and all radionuclides in particulate form l with half-lives greater than 8 days: to less than or equal to 1500 mrem / year averaged over one hour to any - Sn.

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 SITE BOUNDARY from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 for individual members of the public. l For INDIVIDUAL MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will be

[~ h sufficiently low to compensate for any increase in the atmospheric N diffusion factor above that for the SITE BOUNDARY.

DBP 6027A 40 Revision 7.0 ODCM

E 3.3.3 Individual Kelease Radiation Monitor Setpoints 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:

ECg

500 SP (3-1) 472

y/Q NG i

'l EC g

3000 SP g -

(3-2) 472

y/Q ggVF

E(Cf * (Lg + 1.1 Mg) where:

SP = m nitor setpoint corresponding to the release rate TB limit for the total body dose rate of 500 mrem per year (pCi/ml),

SP g = monitor setpoint corresponding to the release rate limit for the skin dose rate of 3000 mrem per year (pcilml),

500 =

total body dose rate limit (mrem /yr),

3000 = skin dose rate limit (mremlyr),

y/Q

8tm 8P h eric y/Q value for direct exposure to ngble gas NG at the SITE BOUNDARY given in Table 3-6 (sec/m ),

VF

. =

ventilationsystemflowrate{ortheapplicable release point and monitor (ft / minute),

Cg =

concentration of noble gas radionuclide 'i' as determined by gamma spectral analysis of grab sample (pCi/ml),

Kg =

total body dose cogversion factor for radionuclide 'i' (mrem /yr per pCi/m ) from Table 3-5, Lg =

beta skin dose conyersion factor for radionuclide 'i' !

(mrem /yr per pCi/m ) from Table 3-5, Mg -

gamma air dose conyersion factor for radionuclide "i" (mradlyr per pCi/m ) from Table 3-5, 1.1 =

mrem skin dose per mrad gamma air dose (mrem / mrad),

and 472 = 28,317 (ml/ft )

1/60 (min /sec).

DBP 6027A 41 Revision 7.0 ODCM ct *$

- ~

J l

, l The lesser value of 8P TB r SPg is used to establish the monitor l

,) setpoint.

(V The Station Vent monitor (RE-4598) efficiencies and read outs are in f pC1/mli 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 i pC1/mi must be corrected to an equivalent monitor counts per minute. ,

The monitor calibration curves are used for determining specific i radionuclide efficiencies (cpm per pCi/ml).

Normally, the monitor efficiency for Xe-133 is used in lieu of the ,

efficiency values for the individual radionuclides. Because its '

lower gamma energy causes a higher monitor response, the Xe-133 ef ficiency provides a conservative value for alarm setpoint ,

determination. i 3.3.4 Conservative, Generic Radiation Monitor Setpoints t Normally, generic alarm setpoints are established instead of those determined by individual radionuclide analysis. This approach- ;

eliminates the need to adjust the setpoint periodically to reflect j minor changes in radionuclide distribution or release flow rate. The ;

alarm setpoint may be conservatively determined by assuming all '

activity released is Kr-89. The Kr-89 total body dose conversion factor is the most limiting. Therefore, the more restrictive setpoint is based on the total body dose rate limit and may be calculated using equation (3-1). Again, the Xe-133 monitor

[ efficiency is used for conservatism. The alarm setpoints are controlled for RE-4598 RE-5052, and RE-1822 in accordance with the !

Radiation Monitor Setpoint Manual.

l 3.3.5 Release Flow Rate Evaluation For Batch Releases r

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 radiciodine, 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 i RR, or RRINH is use as e max mum allowable release value of RR b flow rate. ,

i h

6 DBP 6027A 42 Revision 7.0 l ODCM 1 I

s r~T

e To determine RR INH exacdy, a separate RRyg must be calculated for everyorganineveryagegroup(28valuesoYRRINH). The smallest of which is compared to RR and RR

to determine these 28 is the RR IN tb

l. maximumallowablere$easerate. A conservative shortet t is to calculate RR from Table 3!h for any organ of any age group for each nuclideonce by using th released. The largest dose factors in the inhalation pathway are usually for the teen lung.

500 472

y/Q NG

1* l' 3000 RR =

(3-4) 472

y/Q NG * ( i+ *

"i} " l' 1500 INH "

472

y/Q INH * (R gg

CINHg )

DF 7p where:

RR =

exceed a tb all wable total bodyrelease dose rateflow rate mrem of 500 so as /yr not(fttg/ minute),

RR =

as not to exceed a skin 8

allowable dose release rate of flow rate 3000 mrem /yr (ftsg/ minute),

RR INH

= a wa er ease flow rate so as not to exced an inhalation dose rate of 1500 mrem /yr (ft 3/ min),

500 = total body dose rate limit at the SITE BOUNDARY (mrem /yr).

3000 =

skin dose rate limit at the SITE BOUNDARY (mrem /yr),

1500 =

inhalation dose rate limit at the SITE BOUNDARY (mrem /yr),

472 = 28317 (ml/ft )

1/60 (min /sec),

y/Q NG =

atmospheric y/Q value for direct exposure to ngble gas at the SITE BOUNDARY given in Table 3-6 (sec/m ),

y/Q 1NH =

atmospheric y/Q value for inhalatign at the SITE BOUNDARY given in Table 3-6 (sec/m ),

Kg =

total body dose cogversion factor for radionuclide 'i' (mrem /yr per pCi/m ) from Table 3-5, O

DBP 6027A 43 Revision 7.0 ODCM

m D

L =. beta skin dose conyersion factor for radionuclide "i" h-(mremlyr per pC1/m ) from Table.3-5,-

Mg -

~ gamma air dose conyersion factor for radionuclide "i" (mradlyr per pC1/m ) from Table 3-5, R,g

= dose factor for radionuclide g toorgan"o"ogage group, given in Table 3-7 (mrem /yr per pCi/m ),

CNG g = concentration of noble gas radionuclide "i" analyzed in grab samples, CINH g = concentration of tritium, radiciodine, or particulate radionuclide "i" analyzed in grab samples, and DF = removal factor of 100 to be used for radioiodines and particulates when the effluent is processed through an absolute filter (do not use for tritium).

The actual release rate may be set lower than the maximum allowable release rate to provide an additional assurance that the release rate limits of Section 3.3.2 are not exceeded.

DBP 6027A 44 Revision 7.0' ODCH

)

l

.l 3.4 SITE BOUNDARY DOSE RATE CALCULATION - NOBLE GAS If an effluent noble gas monitor exceeds the alarm setpoint, then an evaluation of compliance with the release rate limits of Section 3.3.2 l

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:

Dtb = 4 2

y/QNG * * (

i l' ( ~

D, = 472

y/Q NG

VF

E((Lg + 1.1 H g ) *C)g (3-7) where D

b

=

total body dose rate (mrem /yr),

D, = skin dose rate (mremlyr),

y/Q NG =

atmospheric y/Q for given the SITE BOUNDARY directinexposure to noblg) gases at Table 3-6 (sec/m ,

VF = ventilation system flow rate (ft / min),

Cg =

concentration of radionuclide "1" as measured in the sample (pcilml),

Kg =

total body dose conversion factor fgr noble gas radionuclide "i" (mrem /yr per pCi/m ) from Table 3-5, Lg =

beta skin dose conversion factgr for noble gas radio-nuclide "i" (mrem /yr per pC1/m ) from Table 3-5, Mg =

gamma air dose radionuclide conversion "i" (mradlyr factor fog) per pCi/m noble from Tablegas 3-5 1.1 =

mrem skin dose per mrad gamma air dose (mrem / mrad),

and 472 = 28,317 (ml/ft )

1/60 (min /sec).

O DBP 6027A 45 Revision 7.0 CDCM

3.5 SITE BOUNDARY DOSE RATE CALCULATION - RADIOIODINE, TRITIUM, AND

[^T)

\

PARTICULATES

~

3.5.1 Dose Rate Calculation Section 3.3.2 limits the dose rate to $1500 mrem /yr to any organ for gaseous releases of I-131, tritium and all particulates with half-lives greater than 8 days. To demonstrate compliance with this 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 evaluationt D

o

= y/Q 1NH * (

10 i

( ~

}

where:

D, = dose rate to organ 'o' over the sampling time period (mrem /yr) y/Q INH = atmospheric y/Q value for inhalation 3

at the SITE BOUNDARY given in Table 3-6 (sec/m ),

= dose factor to organ from radionuclide "i" for the R'

ontrolligg age group via the inhalation pathway (mremlyr per pCi/m ) from Table 3-7, and

( Qg = average release rate over the appropriate sampling period and analysis frequency for radionuclide 'i' (pci/sec).

3.5.2 Simplified Dose Rate Evaluation for Radiciodine, Tritium and Particulates It is conservative to evaluate dose rates by applying the I-131 dose factor to the collective releases for all measured radionuclides. By substituting 1500 mremlyr for the dose rate to organ 'o" in Equation (3-8) and solving for Q ,gan allowable release rate can be determined. Based on the annual average meteorological dispersion (see Table 3-6) and the I-131 dose factor for the most limiting potential pathway, age group and organ (inhalation, child, thyroid --

R = 1.62E+07 mrem /yr per pCi/m3 ), the allowable release rate is 4h?1pCi/sec. An added conservatism factor of 0.8 has been included in this calculation to account for any potential dose contribution from other radioactive particulate material.

For a 7-day period, which is the nominal sampling and analysis frequency, the cumulative release would be 26.7 Ci. Therefore, as long as the total radiciodine, tritium, and particulate releases in any 7-day period do not exceed 26.7 C1, no additional analyses are needed to verify compliance with the Section 3.3.2 limits on allowable release rate.

A m-DDP 6027A 46 Revision 7.0 ODCM

3.6 QUANTIFYING ACTIVITY RELEASED NRC Regulatory Guide 1.21 requires reporting the quantities of individual radionuclides released in gaseous effluents. Therefore, these quantities shall be determined.

3.6.1 Quantifying Noble Gas Activity Released Using 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 nave 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:

A

=

i Q 28.317 *

C

VF

T (3-9) 1 EA g where Qg =

total activity released of radionuclide 'i" (pci), j 3

28,337 = milliliters per ft ,

Ag = activity concentration of radionuclide "1" from the gamma spectral analysis of the grab sample from the release point (pCi/ml),

C =

average gross activity concentration over the release period as measured by the noble gas monitor excluding -l any BATCH RELEASES (pci/ml),

l VF =

ventilation system flow rate (ft / min), and T =

rele9se duration (min).

O DBP 6027A 47 Revision 7.0 ODCM

. 3.6.2_ : Quantifying Noble Gas Activity Released Using A Grab Sample

.i j'-

A_/ With both Station Vent radiation monitors inoperable (i.e., RE-4598 AA and BA,' Channel 1), the once-per-8 hours grab samples provide for. -

continued quantification of releases in accordance with Table 3.1 requirements. ~ Analysis of grab samplas provides the radionuclide concentrations in the effluent. 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 determined.

The following equation may be used for determining the release quantities from any release point based on the grab sample analysis (

Qg

= 28,317

VF

T

Cg

1E-06 (3-10) i where !

Q =

total activity released of radionuclideg (Cl),

3

28,317 = milliliters per ft ,

3 VF = ventilation system flow rate (ft / min),

T = release duration (min),

1E-06 = Ci per pC1, and Cg = concentration of radionuclide 'i' as measured in the grab sample (pC1/ml). l l

i i

o 48 Revision 7.0 DBP 6027A ODCM i

)

[.

1 3.6.3 Quantifying Radiolodine Tritium, and Particulate Activity Released For radiciodine and particulates:

i Qg- Ag *A g

t

v

1E-06 )

I3-11)

(1-e-X1 t)

s

0.72 l where Qg =

total activity released of radionuclideg (C1),

Ag = activity of radionuclide measured g

on filter media (pCi).

Ag -

decay constant of radionuclideg (hr ~1),

t = release duration (hr),

y =

total vent system flow for sampling period (cc),

IE Ci per pC1, s =

total flow through sampler (cc), and 0.72 =

isokinetic flow correction factor for normal range station vent skid RE 4598 AA or BA filter media.

For Tritium:

Q = L* W

V

IE-06 0.9

S (3-12) where:

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),

1E-06 = Ci per pCi, 0.9 -

efficiency for collection of tritium, and S =

total sample volume through gas washing bottle (cc).

O DBP 6027A 49 Revision 7.0 ODCM

,y 3.7 NOBLE GAS DOSE CALCULATIONS - 10 CFR 50 r i s

\~ ' 3.7.1- UNRESTRICTED AREA Dose - Limits Cumulative dose contributions for the current calendar quarter and ,

current calendar year for noble gases shall be determined in accordance with the methodology and parameters in this Section at least once per 31 days. This periodic assessment of releases of noble gases is to evaluate compliance with the quarterly dose limits and calendar year limits.

The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE 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 t o 10 mrad for beta radiation, and

- during any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days.

pursuant to Section 7.3, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective

[- '}

\~ - actions that have been taken to reduce the releases and the proposed corrective actior s to be taken to assure that subsequent releases will be in comp 3=.ance with the above limits.

This specificaolon 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 is reasonably achievable.'

This Section implements the requirements of Section III.A of Appendix I that conformance with the guider of Appendix i to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1. October 1977 and Regulatory Guide 1.111, " Methods for ,

Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1. l July 1977.

V DBP 6027A 50 Revision 7.0 I ODCM l

3.7.2 Dose Calculations - Noble Cases The following equations may be used to calculate the gamma-air and beta-air doses:

D7

=

3.17E-08

y/Q pg *EWy

Qg ) (3-13)

Dp =

3.17E-08

y/Q NG * .i *91' (~

where:

D7 =

alt dose due to garrma entissions for noble gas radionuclides (mrad),

Dp =

air dose due to beta emissions for noble gas radionuclides (mrad),

i y/Q NG =

atmospheric y/Q value for direct exposure to

) noble gas at the SITE BOUNDARY given in lable 3-6 j (sec/m ), '

Qg =

cumulative release of noble gas radionuclide "1" over the period of interest (pci),

My =

airdosefactorduetogammaemissions{romnoble gas radionuclide #1" (mradlyr per pC1/m ) from Table 3-5, Ng =

air dose factor due to beta etnissions fgom noble gas radionuclide "i" (mradlyr per pC1/m ) from j Table 3-5, and t

3.17E-08 = 1/3.15E+07 (yr/sec).

I I

l l

9l DBP 6027A 51 Revision 7.0 ODCM I

1 L_.___ _ . _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ .

.- 1 i

3.7.3 Simplified Dose calculation for Noble Gases ,

i (N,~/) In lieu of the individual noble gas radionuclide dose assessment presented above, the following simplified equations may be used for !

verifying compliance with the dose limits of Section 3.7.1. (Refer j to Appendix B for the derivation and justification of this simplified ,

method.) -

D7 2.0

3.17E-08

y/Q,g

H,gg

E Qg (3-15) and ,

Dp = 2.0

3.17E-08

y/Q NG eff i

( ~

~

where:

H,ff = 5.7E+02,effectivegamma-airgosefactorfrom Appendix B (mradlyr per pCi/m ), ,

t N,gg = 1.1E+03, effective beta-air dgse factor from Appendix B (mrad /yr per pC1/m ), and ,

2.0 = conservatism factor to account for potential l variability in the radionuclide distribution. j I

j f

)

i i

i P

l I

t

\ i i

l DBP 6027A 52 Revision 7.0 ;

ODCM

3.8 RADI0 IODINE, 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 quatierly 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 teleased to areas at and beyond the SITE BOUNDARY shall be limited to the following:

During any calendar quarters less than or equal to 7.5 mrem to any organ, and During any calendar years 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 8 days in gaseous effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, a Special report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

This requirement is provided to implement the requirements of Section II.C. III.A. and IV.A of Appendix I, 10 CFR Part 50. The l limits are the guides set forth in Section II.C of Appendix I. The '

actions specified provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in ;

gaseous effluents will be kept 'as low as is reasonably achievable." l The ODCM calculational methods specified in this Section implement 'l the requirements in Section III.A of Appendix I that conformance with l

the guides of Appendix I be shown by calculational procedure based on j models and data such that the actual exposure of an individual !

through appropriate pathways is unlikely to be substantially underestimated. The ODCM methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " 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.

DBP 6027A 53 Revision 7.0 ODCM

m

?

~

i

-. 'I The release rate specifications for radiciodines and radioactive !

/) material in particulate form are dependent on the existing :

k _s/ ' radionuclide pathways to man in the UNRESTRICTED AREA. The pathways l which are examined in the development of these calculations ares !

i

- individual inhalation of airborne radionuclides, ,

f

- deposition of radionuclides into green leafy vegetttfon with l subsequent consumption by man,

- deposition onto grassy areas where milk animals and !

meat-producing animals graze with consumption of the m' N.and i meat by man, and j deposition on the ground with subsequent exposure of man, f

3.8.2 Oritical Pathuay The critical pathway is that exposure pathway, age group, organ, and receptor location for which 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 sector and is listed in Table 3-6.

D ks _s 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.

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 7.0 ODCM

3.8.3 Dose calculations - Radiciodine, Tritium and Particulates ,

The following equation may be used to evaluate the maximum organ dose 1 due to releasee of iodine-131, tritium and particulates with half-lives greater than 8 days:

D,gp = 3.17E-08

W

ICF

SF

E (Ryg

Qg) (3-17)

Where:

D,gp = dose or dose commitment to organ 'o' via controlling pathway 'p' and age group 'a' as identified in Table 3-6 (mrem).

W =

atmospheric dispersion factor to the controlling I location as identified in Table 3-6 W =

y/Q, dispersion factor for inhalation pathway 3and H-3 dose contribution via all pathways (sec/m )

W =

D/Q, deposition factor for vegetation m and grc.4nd plane exposure pathways (mg) ilk, l R'

=

dose factor for radionuclide "i" to organ 'o* of i age group"a" via pathway "p' as identified in Table 3-7, 3-8, 3-9, 3-10,or3-11depengingon thg pathway specified (mrem /yr per pCi/m ) or l (m - mrem /yr per pCi/sec), i Qg =

cumulative release over the period of interest i for radionuclide 'i' (pCi), 1 ICF =

elemental lodine correction factor which may be i used in calculating doses from radiolodines via l the vegetation, milk, and ground plane exposure l pathways = 0.5, I SF =

seasonal correction factor which may be used for l

milk and vegetation pathways = 0.5, and 3.17E-08 = 1/3.15E+07 (yr/sec).

The dose factors in Tables 3-7 through 3-11 are derived in accordance with NUREG-0133. The elemental iodine correction factor in equation (3-17) is referenced in Regulatory Guide 1.109.

l i

1 O

l DBP 6027A 55 Revision 7.0 ODCM 1

l

m .

F

,_ 3.8.4 Simplified Dose Calculation for Radiciodines and Particulates I )

\ _/ In lieu of the individual radionuclide dose assessment presented in equation (3-17) the following simplified dose calculation may be used for verifying compliance with the dose limits of Section 3.8.1:

D,, =

3.17E-08

W

ICF

SF

R g,131

EQg (3-18) where D,,, = maximum organ dose (mrem),

R = - dose factor for the thyroid for the controlling I-131 pathway identified in Table 3-6, and EQ g = sum of the activities of all radiolodines, tritium and particulates (pci).

The ground plane exposure and inhalation pathways need not he 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.

t

'v/

DBP 6027A 56 Revision 7.0 ODCM

~~,

3.9 GASEOUS EFFLUENT DOSE PROJECTION As with liquid effluents, gaseous effluents require processing if the projected dose exceeds specified limits. This requirement implements the requirements of 10 CFR 50.36a on maintaining and using the appropriate radwaste processing equipment to keep releases ALARA.

The GASEOUS RADWASTE TREATMENT SYSTEM (i.e., Waste Gas Decay Tank) shall be used to reduce noble gas levels prior to discharge when the projected air dose due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation in a 31 day patiod (i.e., one quarter of the design objective rate).

The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radiolodine and particulate effluents, prior to their discharge, when the projected dose due to gaseous effluents releases to areas at or beyond the SITE 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 GASEOUS RADWASTE and VENTILATION EXHAUST TREATMENT SYSTEMS applicable for reducing effluents prior to release. '

With the gaseous waste being discharged without treatment and in excess of the limits, in lieu of a Licensee Event Report prepare and submit to the commission within 30 days, pursuant to Section 7.3 a Special Report that includes the following information:

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

Actions taken to restore the inoperable equipment to OPERABLE status, and Summaty description of action (s) taken to prevent a recurrence.

The requirements that the appropriate portions of these systems be used, when specified. provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This requirement implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.

O DBp 6027A 57 Revision 7.0 ODCM

f]:'

If the GASEOUS'RADWASTE and VENTILATION EXHAUST TREATMENT SYSTEMS are not

((Ad-}. being used, dose projections shall be performed at least once per 31 days using the following equations:

D7 p

=

D7 * (31/d)

(3-19)

Dp = Dp * (31/d) (3-20) ;

P ;

t i

i

'Dmaxp = D max

(31/d) (3-21) !

where: l

~

l' D7

= projected 31-day gamma-air dose (mrad),

P g D7

- gamma-air dose for current calendar quarter (mrad), l l

Dp p

= projected 31-day beta-air dose (mrad),

Dp = beta-air dose for current calendar quarter (mrad), l D,,,p = projected 31-day maximum organ dose (mrem),

D = maximum organ dose for current calendar quarter as determined by equation (3-17) or (3-18) (mrem), ;

d = number of days accounted for by current calendar quarter f dose, and j "A 31 = number of days in projection. f 1

I l

l i

i i

t 5

i i

I 3

s ,

l DBP 6027A- 58 Revision 7.0- i ODCM ,

t

m e

% MINIMUM

, CHANNELS 8 IrssTRUMENT OPERABLE APPLICABILITY PARAMETER

" ACTION

1. Waste Gas Decay System (provides automatic isolation) @

o

a. Noble Gas Activity Monitor >

1 (1) Radioactivity Measurement A Q

b. Etfluent System Flow Rate 1 (1) System Flow Rate Measurement ps B

Measuring Device o

2. Waste Gas System N o

(provides alarm function) e

a. Oxygen Monitor 1 (2) 2 Oxygen D p g 3 Containment Purge Monitoring 5 2

Er

v. System (provides automatic n a isolation) 2 w o

w

a. Noble Gas Activity Monitor s 1 (1) Radioactivity measurement C g 5

O N

O

=

a 5

U 21 8

.~

O e- - -- --

e - - - -

O.

o' O

n/--

\

e '

en

" HINIMUM

$ CHANNELS PARAMETER ACTION INSTRt24ENT OPERABLE APPLICABILITY ,

h

4. Station Vent Stack (provides alarm function)

Noble Gas Activity Monitor 1 (1) Radioactivity Measurement C $

a. $

Iodine Sampier Cartridge 1 (1) Verify Presence of E d l

b.

Cartridge $

1' o Particulate Sampler Filter 1 (1) Verify Presence of Filter E $

c. 5 (1) System Flow Rate 8 @ y

d. Etfluent System Flow 1 e., $

Rate Measuring Device Measurement

7

e. Sampler Flow Rate B z Heasuring Device 1 (1) Sampler Flow Rate "

, Measurernent W o ~ $ 8 5 ;

3 E

~

E 0

m n

?,

OM e 83 z-E 8

O 4 ,

Table 3-1 (Continued)

TABLE NOTATION (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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and analyzed in accordance with applicable procedures.

ACTION D With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, additions to the waste gas surge tank may continue provided another method for ascertaining oxygen concentrations, such as grab sample analysis, .s implemented to provide measurements at least once per four(4) hours during degassing and daily during other operations.

ACTION E With the number of channels OPERABLE less than required by the i

minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment, as required in Table 3-3 (this requirement is not applicable for routine replacement of sampling media or routine testing).

l l

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DBP 6027A 61 Revision 7.0 ODCM

e,

% CHANNEL CHANNEL SOURCE CHANNEL e INSTRUMENT FUNCTIONAL CHECK CHECK CALIBRATION TEST 0

3' 1. Weste Gas Decay System II R II

a. Noble Gas Activity Honitor P P I3I Q g

b. Effluent System Flow Rate P II N/A R q h

2. Containment Purge Vent System O "N

a. Noble Gas Activity Monitor D II P II ;M I8I R

I II Q $

3. Station Vent Stack m N j< g m

a. Noble Gas Activity Monitor D( I H R( I Q Q

b. Iodine Sampler W(1) N/A N/A h N/A o N $"-

e c. Particulate Sampler W(1) N/A N/A N/A Qx w

d. System Effluent Flow Rate OO b Heasurement Device D yy N/A R N/A $

e. Sampler Flow Rate = G Heasurement Device g O W N/A R N/A y U

w

=

n 2,2 8

O e e .

e.. _ _ - _ _ _ _ _ _ _ _ .

1 I

1 Table 3-2 (Continued) m TABLE NOTATION I

(1) During radioactive waste gas releases via this pathway. !

l (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 radioactivity 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 CHA'ANEL CALIBRATION, sources that have been releated to the initial calibrat. ion should be used, at intervals of at .

least once per eighteen months. For high range monitoring instrumentation, where c3libration 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 ,,ercent oxygen, balance nitrogen and

2. Four volume pe rcent 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). ,

Q At least once per 92 days. I D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

H At least once per 31 days.

V At least once per 7 days.

DBP 6027A 63 Revision 7.0 ODCM

E

'o Minimum

$ Gaseous Release Type Sampling Analysis Lower Lin:it of Type of O Frequency Frequency Detection (LLD)

> Activity Analysis (pCl/ml)* _

P P Each Each Principal Gamma Emitters Waste Gas Decay Release 1.0E-04 h Release Grab Sample H-3 g

P 1.0E-06 $

P Containment Purge Each Purge Each Purge Principal Gaasna Emitters-C Grab Sample 1.0E-04 %

H-3 O H H 1.0E-06 g Station Vent Stack Grab Sample C Principal Gaauna Emitters- 5 H-3 1.0E-04 _

g 1.0E-06 W

Continuous b Charcoal I-131 Sample 1.0E-12 y" g W m $

i Continuous Particulate g

Sample PrincipafGasmaa Emitters-1.0E-11 p y M y **

o Continuous Composite Particulate g Gross Alpha 1.0E-11 O Sample S

g b b Continuous Composite Particulate Sr-89 Sr-90 g

Sample 1.0E-11 g b N Continuous Noble Gas Noble Gases o o

o 33 s:

Monitor Gross Beta or Gammaa 1.0E-06 f

o a

O O O O. .

l Table 3-3-(Continued)

. (3

\s_s/ TABLE NOTATION ]

1

a. The LLD is the smallest concentration of radioactive material in a sample ]

that will be detected with 95Z probability with SZ probability of falsely-concluding that a blank observation represents s "real" signal.

l For a particular measurement system (which may include radio-chemical separation):- l 1

4.66 s

'b LLD = :

E

V

2.22

Y

exp(-Aat) !

l where LLD is the lower limit of detection as defined above (as pCi per unit ,

mass or volume); t ss is the standard deviation of the background counting rate or of '

the counting rate of a blank sample as appropriate (as counts per minute):

E is the counting efficiency (as counts per transformation);

t 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 radionuclides -

At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting. l It should be recognized that the LLD is defined as an a 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. l 1

b. The ratio of the sample flow rate to the sampled stream flow rate shall be l known for the time period covered by each dose or dose rate calculation !

made in accordance with Sections 3.3.1 and 3.8. [

i t

s i

DBP 6027A 65 Revision 7.0 ,

ODCM

..._..m __ , ,-

Table 3-3 (Continued)

TABLE NOTATION

c. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87. Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Co-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 level for the nuclide. The "less than" values shall. not be used in the required dose calculations. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Radioactive Effluent Release Report.

Frequency notation:

P - Prior to each release.

M - At least once per 31 days.

W - At least once per 7 days.

Q - At least once per 92 days.

O l

l l

I l;

I 1

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DBP 6027A 66 Revision 7.0 ODCM

i Table 3-4 ,

Land-Use Census Summary Exposure Pathway Locations and Atmospheric Dispersion Parameters Distance Exposure Controlling y/Q 3 D[g Sector (meters) Pathway Age Group (sec/m 1 im 1 N 880 inhalation child 9.15E-07 8.39E-09 NNE 870 inhalation child 1.27E-06 1.47E-08 NE 900 inhalation child 1.26E-06 1.58E-08 ENE* -- -- -- -- --

E* -- -- -- -- --

ESE* -- -- -- -- --

SE* -- -- -- -- --

SSE 2,880 vegetation child 6.85E-08 8.02E-10 S** 3,280 vegetation child 4.57E-08 4.98E-10 SSW 1,560 vegetation child 1.03E-07 2.28E-09 ,

SW** 4,150 vegetation child 4.88E-08 5.13E-10 WSW** 4,270 vegetation child 5.71E-08 5.31E-10 W** 1,660 vegetation child 2.63E-07 4.11E-09 WNW 1,750 vegetation child 1.46E-07 1.72E-09 KW** 2,340 vegetation child 6.84E-08 5.61E-10 NNW** 1,370 vegetation child 2.01E-07 1.48E-09

Since these sectors are located over marsh areas and Lake Erie, no ingestion or inhalation pathways are present.

- These values are a change to this table as a result of the 1994 Land Use Census.

Note: The meteorological dispersion factors are taken from the Stone and Webster report, Handbook for ODCM y/Q and D/Q Calculations, October 1983.

O DBP 6027A 67 Revision 7.0 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 g Factor L g My Ng (mrad /yr per (mradlyr 3E' (mrem pC1/m /yg)per (mrem pC1/m /yg)per pCi/m ) pCi/m )

Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+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 1.05E+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 A r- 41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 '

Dose factors taken from NRC Regulatory Guide 1.109 O

DBP 6027A 68 Revision 7.0 ODCM

Table 3-6 >

Exposure Pathways, Controlling Parameters, and Atmospheric Dispersion for Dose Calculations Atmospheric Dispersion Exposure Receptor Controlling y/Q 3 Pathway Location Age Group (sec/m ) (m'3) noble gases SITE BOUNDARY N/A 1.83E-06 N/A direct NNE exposure inhalation SITE BOUNDARY child 1.68E-06 N/A NNE (critical pathway) vegetation 1660 meters child 2.63E-07 4.11E-09 W

P O

NOTES:

1. All meteorological dispersion values have been taken from the Stone and Webster report, Handbook for ODCM y[Q and Dig Calculations, October 1983.

2. The noble gas, direct exposure y/Qs are based on the decayed, undepleted values.

3. The inhalation pathway y/Qs are based on the decayed, depleted values.

DBP 6027A 69 Revision 7.0 ODCM

Table 3-7 R yg, Inhalation Pathway Dose Fgetors - ADULT (mrem /yr per pCi/m )

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 -

1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+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 P-32 1.32E+6 7.71E+4 - - -

8.64E+4 5.01E+4 Cr-51 - -

5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.00E+2 Hn-54 -

3.96E+4 -

9.84E+3 1.40E+6 7.74E+4 6.30E+3 Mn-56 - 1.24E+0 -

1.30E+0 9.44E+3 2.02E+4 1.83E-1 Fe-55 2.46E+4 1.70E+4 - -

7.21E+4 6.03E+3 3.94E+3 Fe-59 1.18E+4 2.78E+4 - -

1.02E+6 1.88E+5 1.06E+4 Co-57 -

6.92E+2 - -

3.70E+5 3.14E+4 6.71E+2 Co-58 -

1.58E+3 - -

9.28E+5 1.06E+5 2.07E+3 Co-60 - 1.15E+4 - - 5.97E+6 2.85E+5 1.48E+4 Ni-63 4.32E+5 3.14E+4 - -

1.78E+5 1.34E+4 1.45E+4 Ni-65 1.54E+0 2.10E-1 - -

5.60E+3 1.23E+4 9.12E-2 Cu-64 -

1.46E+0 -

4.62E+0 6.78E+3 4.90E+4 6.15E-1 Zn-65 3.24E+4 1.03E+5 -

6.90E+4 8.64E+5 5.34E+4 4.66E+4 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 Br-83 - - - - -

2.32E+2 2.41E+2 Br-84 - - - - -

1.64E-3 3.13Ee2 Br-85 - - - - - -

1.28E+1 Rb-86 -

1.35E+5 - - -

1.66E+4 5.90E+4 Rb-88 -

3.87E+2 - - -

3.34E-9 1.93E+2

.Rb-89 -

2.56E+2 - - - -

1.70E+2 Sr-89 3.04E+5 - - -

1.40E+6 3.50E+5 8.72E+3 I

l Sr-90 9.92E+7 - - -

9.60E+6 7.22E+5 6.10E+6 ;

Sr-91 6.19E+1 - - -

3.65E+4 1.91E+5 2.50E+0 )

Sr-92 6.74E+0 - - -

1.65E+4 4.30E+4 2.91E-1 I Y-90 2.09E+3 - - -

1.70E+5 5.06E+5 5.61E+1 i Y-91m 2.61E-1 - - -

1.92E+3 1.33E+0 1.02E-2 l Y-91 4.62E+5 - - - 1.70E+6 3.85E+5 1.24E+4 Y-92 1.03E+1 - - -

1.57E+4 7.35E+4 3.02E-1 Y-93 9.44E+1 - - -

4.85E+4 4.22E+5 2.61E+0

{

j Zr-95 1.07E+5 3.44E+4 -

5.42E+4 1.77E+6 1.50E+5 2.33E+4 !

2r-97 9.68E+1 1.96E+1 -

2.97E+1 7.87E+4 5.23E+5 9.04E+0 Nb-95 1.41E+4 7.82E+3 -

7.74E+3 5.05E+5 1.04E+5 4.21E+3 Nb-97 2.22E-1 5.62E-2 -

6.54E-2 2.40E+3 2.42E+2 2.05E-2 l Mo-99 -

1.21E+2 -

2.91E+2 9.12E+4 2.48E+5 2.30E+1 Tc-99m 1.03E-3 2.91E-3 -

4.42E-2 7.64E+2 4.16E+3 3.70E-2 l Tc-101 4.18E-5 6.02E-5 -

1.08E-3 3.99E+2 - 5.90E-4 tilll DBP 6027A 70 Revision 7.0 ODCM

t Table 3-7 (continued)

'/N Rf ,, Inhalation Pathway Dose Factors3 ~ ^ (# " ""'

( ,) (mrem /yr per pCi/m )

-Nuclide Bone Liver Thyroid Kidney Lung CI-LLI T. Body Ru-103 1.53E+3 - - 5.83E+3 5.05E+5 1.10E+5 6.58E+2 Ru-105 7.90E-1 - - 1.02E+0 1.10E+4 4.82E44 3.11E-1 Ru-106 6.91E+4 - - 1.34E+5 9.36E+6 9.12E+5 8.72E+3 Rh-103m - - - - - - -

Rh-106 - - - - - - -

Ag-110m 1.08E+4 1.00E+4 - 1.97E+4 4.63E+6 3.02E+5 5.94E+3 Sb-124 3.12E+4 5.89E+2 7.55E+1 - 2.48E+6 4.06E+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 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3 l

Te-127 1.40E+0 6.42E-1 1.06E+0 3.10E+0 6.51E+3 5.74E+4 3.10E-1 i 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 l Te-132 2.60E+2 2.15E+2 1.90E+2 1.46E+3 2.88E+5 5.10E+5 1.62E+2 I-130 4.58E+3 1.34E+4 1.14E+6 2.09E+4 - 7.69E+3 5.28E+3 6.28E+3 2.05E+4 5 1-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 -

, 1-132 1.16E+3 3.26E+3 1.14E+5 5.18E+3 - 4.06E+2 1.16E+3 !

k I-133 8.64E+3 1.48E+4 2.15E+6 2.58E+4 - 8.88E+3 4.52E+3 I I-134 6.44E+2 1.73E+3 2.98E+4 2.75E+3 - 1.01E+0 6.15E+2 I-135 2.68E+3 6.98E+3 4.48E+5 1.11E+4 - 5.25E+3 2.57E+3 .

Cs-134 3.73E+5 8.4BE+5 - 2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 - 8.56E+4 1.20E+4 1.17E+4 1.10E+5 Cs-137 4.78E+5 6.21E+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 1.00E-1 7.53E-5 - 7.00E-5 1.94E+3 1.16E-7 3.36E-3 Ba-142 2.63E-2 2.70E-5 - 2.29E-5 1.19E+3 - 1.66E-3 ;

La-140 3.44E+2 1.74E+2 - - 1.36E+5 4.58E+5 4.58E+1 La-142 6.83E-1 3.10E-1 - - 6.33E+3 2.11E+3 7.72E-2 Ce-141 1.99E+4 1.35E+4 - 6.26E+3 3.62E+5 1.20E+5 1.53E+3 :

Ce-143 1.86E+2 1.38E+2 - 6.08E+1 7.98E+4 2.26E+5 1.53E+1 :

Ce-144 3.43E+6 1.43E+6 - 8.48E+5 7.78E+6 8.16E+5 1.84E+5 :

i Pr-143 9.36E+3 3.75E+3 - 2.16E+3 2.81E+5 2.00E+5 4.64E+2 !'

Pr-144 3.01E-2 1.25E-2 - 7.05E-3 1.02E+3 2.15E-8 1.53E-3 Nd-147 5.27E+3 6.10E+3 - 3.56E+3 2.21E+5 1.73E+5 3.65E+2 W-187 8.48E+0 7.08E+0 - - 2.90E+4 1.55E+5 2.48E+0 Np-239 2.30E+2 2.26E+1 - 7.00E+1 3.76E+4 1.19E+5 1.24E+1 l

-) i DBP 6027A 71 Revision 7.0 ODCH l

I

Table 3-7 (continued)

R yg, Inhalation Pathway Dose Fagtors - TEENAGER (mrem /yr per pC1/m )

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 - 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 Na-24 1.38E+4 1.38E+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 C r-51 - -

7.50E+1 3.07E+1 2.10E+4 3.00E+3 1.35E+2 Mn-54 -

5.11E+4 -

1.27E+4 1.98E+6 6.68E+4 8.40E+3 Mn-56 -

1.70E+0 -

1.79E+0 1.52E44 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 1.98Et4 Hi-65 2.18E+0 2.93E-1 - -

9.36E+3 3.67E+4 1.27E-1 Cu-64 -

2.03E+0 -

6.41E+0 1.11E+4 6.14E+4 8.48E-1 Zn-65 3.86E+4 1.34E+5 -

8.64E+4 1.24E+6 4.66E+4 6.24E+4 Zn-69 4.83E-2 9.20E-2 -

6.02E-2 1.58E+3 2.85E+2 6.46E-3 Br-82 - - - - - -

1.82E+4 Br-83 - - - - - -

3.44E+2 Br-84 - - - - - -

4.33E+2 Br-85 - - - - - -

1.83E+1 Rb-86 -

1.90E+5 - - -

1.77E+4 8.40E+4 Rb-88 -

5.46E+2 - - -

2.92E-5 2.72E+2 Rb-89 -

3.52E+2 - - -

3.38E-7 2.33E+2

, Sr-89 4.34E+5 - - -

2.42E+6 3.71E+5 1.25E+4 Sr-90 1.08E+8 - - -

1.65E+7 7.65E+5 6.68E+6 Sr-91 8.80E+1 - - -

6.07E+4 2.59E+5 3.51E+0 Sr-92 9.52E+0 - - -

2.74E+4 1.19E+5 4.06E-1 Y-90 2.98E+3 - - -

2.93E+5 5.59E+5 8.00E+1 Y-91m 3.70E-1 - - -

3.20E+3 3.02E+1 1.42E-2 -

Y-91 6.61Et5 - - -

2.94E+6 4.09E+5 1.77E+4 Y-92 1.47E+1 - - -

2.68E+4 1.65E+5 4.29E-1 Y-93 1.35E+2 - - -

8.32E+4 5.79E+5 3.72E+0 Zr-95 1.46E+5 4.58E+4 -

6.74E+4 2.69E+6 1.49E+5 3.15E+4 2r-97 1.38E+2 2.72E+1 -

4.12E+1 1.30E+5 6.30E+5 1.26E+1 Nb-95 1.86E+4 1.03E+4 -

1.00E+4 7.51E+5 9.68E+4 5.66E+3 Hb-97 3.14E-1 7.78E-2 -

9.12E-2 3.93E+3 2.17E+3 2.84E-2 Mo-99 -

1.69E+2 -

4.11E+2 1.54E+5 2.69E+5 3.22E+1 Tc-99m 1.38E-3 3.86E-3 -

5.76E-2 1.15E43 6.13E+3 4.99E-2 Tc-101 5.92E-5 8.40E-5 -

1.52E-3 6.67E+2 8.72E-7 8.24E-4 O

DBP 6027A 72 Revision 7.0 ODCM

, 1 t

N

,.. Table 3-7 (continued)

(/) R yg, i

s__

Inhalation Pathway Doseper (mremlyr Factors pCi/m 3) TEENAGER (continued)-

i Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body 4 :

Ru-103 2.10E+3. - - 7.43E+3 7.83E+5 1.09E+5 8.96E+2 l Ru-105 1.12E+0 - - 1.41E+0 1.82E+4 9.04E+4 4.34E-1 j Ru-106 9.84E+4 - - 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Rh-103m - - - - - - -

l Rh-106 - - - - - - -

Ag-110m 1.38E+4 1.31E+4 - 2.50E+4 6.75E+6 2.73E+5- 7.99E+3 i Sb-124 4.30E+4 7.94E+2 9.76E+1 - 3.85E+6 3.98E+5 1.68E+4 i Sb-125 7.38E+4 8.08E+2 7.04E+1 - 2.74E+6 9.92E+4 1.72E+4- {

Te-125m 4.88E+3 2.24E+3 1.40E+3 - 5.36E+5 7.50E+4 6.67E+2 :

Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3 'f Te-127- 2.01E+0 9.12E-1 1.42E+0 7.28E+0 1.12E+4 8.08E+4 4.42E-1 Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4.05E+5 2.25E+3 'l Te'-129 7.10E-2 3.38E-2 5.18E-2 2.66E-1 3.30E+3 1.62E+3 1.76E-2 ;

Te-131m 9.84E+1 6.01E+1 7.25E+1 4.39E+2 2.38E+5 6.21E+5 4.02E+1 i 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 - 6.49E+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 I-135 3.70E+3 9.44E+3 6.21E+5 1.49E+4 - 6.95E+3 3.49E+3 i Cs-134 5.02E+5 1.13E+6 - 3.75E+5 1.46E+5 9.76E+3 5.49E+5 Cs-136 5.15E+4 1.94E+5 - 1.10E+5 1.78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 8.48E+5 - 3.04E+5 1.21E+5 8.48E+3 3.11E+5 _l l

Cs-138 4.66E+2 8.56E+2 - 6.62E+2 7.87E+1 2.70E-1 4.46E+2' i Ba-139 1.34E+0 9.44E-4 - 8.88E-4 6.46E+3 6.45E+3 3.90E-2 Ba-140 5.47E+4 6.70E+1 - 2.28E+1 2.03E+6 2.29E+5 3.52E+3 Ba-141 1.42E-1 1.06E-4 - 9.84E-5 3.29E+3 7.46E-4 4.74E-3 -'

Ba-142 3.70E-2 3.70E-5 - 3.14E-5 1.91E+3 - 2.27E-3 .j i

La-140 4.79E+2 2.36E+2 - - 2.14E+5 4.87E+5 6.26E+1 ;

I La-142. 9.60E-1 4.25E-1 - - 1.02E+4 1.20E+4 1.06E-1 Ce-141 2.84E+4 1.90E+4 - 8.88E+3 6.14E+5 1.26E+5 2.17E+3 l Ce-143 2.66E+2 1.94E+2 - 8.64E+1 1.30E+5 2.55E+5- 2.16E+1 l 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 i

Nd-147 7.86E+3 e.56E+3 - 5.02E+3 3.72E+5 1.82E+5 5.13E+2 W-187 1.20E+1 9.76E+0 - - 4.74E+4 1.77E+5 3.43E+0- ;

Np-239 3.38E+2 3.19E+1 - 1.00E&2 6.49E+4 1.32E+5 1.77E+1 !

DBP 6027A 73 Revision 7.0 ODCM i

)

Table 3-7 (continued)

R g9, Inhalation Pathway Dose Fgetors - CHILD (mrem /yr per pC1/m )

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 -

1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+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 Cr-51 - -

8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Hn-54 -

4.29E+4 -

1.00E+4 1.58E+6 2.29E+4 9.51E+3 Mn-56 -

1.66E+0 -

1.67E+0 1.31E+4 1.23E+5 3.12E-1 Fe-55 4.74E+4 2.52E+4 - -

1.11E+5 2.87E+3 7.77E+3 Fe-59 2.07E+4 3.34E+4 - -

1.27E+6 7.07E+4 1.67E+4 Co-57 -

9.03E+2 - -

5607E+5 1.32E+4 1.07E+3 Co-58 -

1.77E+3 - -

1.11E+6 3.44E+4 3.16E+3 Co-60 -

1.31E+4 - -

7.07E+6 9.62E+4 2.26E+4 Ni-63 8.21E+5 4.63E+4 - -

2.75E+5 6.33E+3 2.80E+4 Ni-65 2.99E+0 2.96E-1 - -

8.18E+3 8.40E+4 1.64E-1 Cu-64 -

1.99E+0 -

6.03E+0 9.58E+3 3.67E+4 1.07t+0 Zn-65 4.26E+4 1.13E+5 -

7.14E+4 9.95E+5 1.63E+4 7.03E+4 2n-69 6.70E-2 9.66E-2 -

5.85E-2 1.42E+3 1.01E+4 8.92E-3 Br-82 - - - - - -

2.09E+4 Br-83 - - - - - -

4.74E+2 Br-84 - - - - - -

5.48E+2 Br-85 - - - - - -

2.53E+1 Rb-86 -

1.98E+5 - - -

7.99E+3 1.14E+5 Rb-88 -

5.62E+2 - - -

1.72E+1 3.66E+2 Rb-89 -

3.45E+2 - - -

1.89E+0 2.90E+2 Sr-89 5.99E+5 - - -

2.16E+6 1.67E+5 1.72E+4 Sr-90 1.01E+8 - - -

1.48E+7 3.43E+5 6.44E+6 Sr-91 1.21E+2 - - -

5.33E+4 1.74E+5 4.59E+0 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 Y-91 9.14E+5 - - -

2.63E+6 1.84E+5 2.44E+4 Y-92 2.04E+1 - - -

2.39E+4 2.39E+5 5.81E-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 -

S.62E+3 6.14E+5 3.70E+4 6.55E+3 Nb-97 4.29E-1 7.70E-2 8.55E-2 3.42E+3 2.78E+4 3.60E-2 Mo-99 -

1.72E+2 -

3.92E+2 1.35E+5 1.27E+5 4.26E+1 Tc-99m 1.78E-3 3.48E-3 -

5.07E-2 9.51E+2 4.81E+3 5.77E-2 Tc-101 8.10E-5 8.51E-5 -

1.45E-3 5.85E+2 1.63E+1 1.08E-3 O

DBP 6027A 74 Revision 7.0 ODCH

i Table 3-7 (continued)

R gg. Inhalation Pathway Dose Factors3- CHILD (continued) l'(_,/I (mremfyr per pC1/m )

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body i'

Ru-103 2.79E+3 - - 7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-105 1.53E+0 - - 1.34E+0 1.59E+4 9.95E+4 5.55E-1 Ru-106 1.36E+5 - - 1.84E+5 1.43E+7 4.29E+5 1.69E+4 Rh-103m - - - - - - -

Rh-106 - - - - - - -

Ag-110m 1.69E+4 1.14E+4 - 2.12E+4 5.48E+6 1.00E+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 - 3.24E+6 1.64E+5- 2.00E+4 Sb-125 9.84E+4 7.59E+2 9.10E+1 - 2.32E+6 4.03E+4 2.07E+4 Te-125m 6.73E+3 2.33E+3 1.92E+3 - 4.77E+5 3.38E+4 9.14E+2 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+0 9.51E-1 1.96E+0 7.07E+0 1.00E+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 f 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 0.77E+1 4.00E+2 2.06E+5 3.08E+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 I

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 1.88E+3

[~'\ I-133 1.66E+4 2.03E+4 3.85E+6 3.38E+4 - 5.48E+3 7.70E+3 i I-134 1.17E+3 2.16E+3 5.07E+4 3.30E+3 - 9.55E+2 9.95E+2 I-135 4.92E+3 8.73E+3 7.92E+5 1.34E+4 - 4.44E+3 4.14E+3 Cs-134 6.51E+5 1.01E+6 - 3.30E+5 1.21E+5 3.85E+3 2.25E+5 Cs-136 6.51E+4 1.71E+5 - 9.55E+4 1.45E+4 4.18E+3 1.16E+5 i Cs-137 9.07E+5 8.25E+5 - 2.82E+5 1.04E+5 3.62E+3 1.28E+5 Cs-138 6.33E+2 8.40E+2 - 6.22E+2 6.81E+1 2.70E+2 5.55E+2 ,

Ba-139 1.84E+0 9.84E-4 - 8.62E-4 5.77E+3 5.77E+4 5.37E-2 Ba-140 7.40E+4 6.48E+1 - 2.11E+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 5.00E-2 3.60E-5 - 2.91E-5 1.64E+3 2.74E+0 2.79E-3 La-140 6.44E+2 2.25E+2 - - 1.83E+5 2.26E+5 7.55E+1 La-142 1.30E+0 4.11E-1 - - 8.70E+3 7.59E+4 1.29E-1 Ce-141 3.92E+4 1.95E+4 - 8.55E+3 5.44E+5 5.66E+4 2.90E+3 .

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 - 3.00E+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 3.00E-3 Nd-147 1.08E+4 8.73E43 - 4.81E+3 3.28E+5 8.21E+4 6.81E+2 ,

W-187 1.63E+1 9.66E+0 - - 4.11E+4 9.10E+4 4.33E+0 ;

Np-239 4.66E+2 3.34E+1 - 9.73E+1 5.81E+4 6.40E+4 2.35E+1 DBP 6027A 75 Revision 7.0 ODCM

Table 3-7 (continued)

R g9, Inhalation Pathway Dose Fgetors - INFANT (mrem /yr per pCi/m )

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 -

6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 3.31E+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 1.06E44 1.06E+4 P-32 2.03E+6 1.12E+5 - - -

1.61E+4 7.74E+4 Cr-51 - -

5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1 Hn-54 -

2.53E+4 4.98E+3 1.00E+6 7.06E+3 4.98E+3 Mn-56 -

1.54E+0 1.10E+0 1.25E+4 7.17E+4 2.21E-1 Fe-55 1.97E+4 1.17E+4 8.69E+4 1.09E+3 3.33E+3 Fe-59 1.36E+4 2.35E+4 -

1.02E+6 2.48E+4 Co-57 9.48E+3 6.51E+2 - -

3.79E+5 4.86E+3 6.41E+2 Co-58 -

1.22E+3 7.77E+5 1.11E+4 1.82E+3 Co-60 -

8.02E+3 4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 -

2.09E+5 2.42E+3 1.16E+4 '

Ni-65 2.39E+0 2.84E-1 -

8.12E+3 5.01E+4 Cu-64 1.23E-1 1.88E+0 -

3.98E+0 9. 30E >3 1.50E+4 7.74E-1 Zn-65 1.93E+4 6.26E+4 3.25E+4 6.47E+5 5.14E+4 3.11E+4 Zn-69 5.39E-2 9.67E-2 4.02E-2 1.47E+3 1.32E+4 7.18E-3 Br-82 - - -

Br-83 - -

1.33E+4 Br-84 -

3.81E+2 4.00E+2 Br-85 - - -

Rb-86 2.04E+1 1.90E+5 - - -

3.04E+3 8.82E+4 Rb-88 -

5.57E+2 - - -

3.39E42 2.87E+2 Rb-89 -

3.21E+2 - - -

6.82E+1 2.06E+2 Sr-89 3.98E+5 - - -

2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 - -

1.12E+7 1.31E+5 2.59E+6 Sr-91 9.56E+1 - -

5.26E+4 7.34E+4 3.46E+0 St-92 1.05E+1 -

2.38E+4 1.40E+5 Y-90 3.91E-1 3.29E+3 - -

2.69E+5 1.04E+5 Y-91m 8.82E+1 4.07E-1 -

2.79E+3 2.35E+3 1.39E-2 Y-91 5.8BE+5 -

2.45E+6 7.03E+4 1.57E+4 Y-92 1.64E+1 -

2.45E+4 1.27E45 4.61E-1 Y-93 1.50E+2 -

7.64E+4 1.67E+5 4.07E+0 Zr-95 1.15E+5 2.79E+4 -

3.11E+4 1.75E+6 2.17E+4 2.03E+4 Zr-97 1.50E+2 2.56E+1 -

2.59E+1 1.10E+5 1.40E+5 1.17E+1 Nb-95 1.57E+4 6.43E+3 4.72E+3 4.79E+5 1.27E+4 3.78E+3 Hb-97 3.42E-1 7.29E-2 5.70E-2 3.32E+3 2.69E+4 2.63E-2 Mo-99 -

1.65E+2 2.65E+2 1.35E+5 4.87E+4 3.23E+1 Tc-99m 1.40E-3 2.88E-3 3.11E-2 8.11E+2 2.03E+3 3.72E-2 Tc-101 6.51E-5 8.23E-5 9.79E-4 5.84E+2 8.44E+2 8.12E-4 O

DBP 6027A 76 Revision 7.0 ODCM

r 7

Table 3-7 (continued)

[ }

R yg, Inhalation Pathway Dose Factors 3- INFANT (continued)

\_ / (mrem /yr per pCi/m )

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body nu-103 2.02E+3 - - 4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-105 1.22E+0 - - 8.99E-1 1.57E+4 4.84E+4 4.10E-1 Ru-106 8.68E+4 - - 1.07E+5 1.16E+7 1.64E+5 1.09E+4 Rh-103m - - - - - - -

Rh-106 - - - - - - -

Ag-110m 9.98E+3 7.22E+3 - 1.09E+4 3.67E+6 3.30E+4 5.00E+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 - 2.65E+6 5.91E+4 1.20E+4 Sb-125 5.17E+4 4.77E+2 6.23E+1 - 1.64E+6 1.47E+4 1.09E+4 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+0 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 3.00E+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 5.00E-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 1.60E46 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

[ ,.'v; I-134 9.21E+2 1.88E+3 4.45E+4 2.09E+3 -

1.29E+3 6.65E+2 I-135 3.86E+3 7.60E+3 6.96E+5 8.47E+3 - 1.83E+3 2.77E+3 Cs-134 3.96E+5 7.03E+5 - 1.90E+5 7.97E+4 1.33E+3 7.45E+4 Cs-136 4.83E+4 1.35E+5 - 5.64E+4 1.18E+4 1.43E+3 5.29E+4 Cs-137 5.49E+5 6.12E+5 - 1.72E+5 7.13E+4 1.33E+3 4.55E+4 Cs-138 5.05E+2 7.81E+2 - 4.10E+2 6.54E+1 8.76E+2 3.98E+2 Ba-139 1.48E+0 9.84E-4 - 5.92E-4 5.95E+3 5.10E+4 4.30E-2 Ba-140 5.60E+4 5.60E+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 2.00E+2 - - 1.68E+5 8.48E+4 5.15E+1 La-142 1.03E+0 3.77E-1 - - 8.22E+3 5.95E+4 9.04E-2 Ce-141 2.77E+4 1.67E+4 - 5.25E+3 5.17E+5 2.16E+4 1.99E+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 5.00E+2 W-187 1.30E+1 9.02E+0 - - 3.96E+4 3.56E+4 3.12E+0 Np-239 3.71E+2 3.32E+1 - 6.62E+1 5.95E+4 2.49E+4 1.88E+1 7

(s DBP 6027A 77 Revision 7.0 l ODCM ,

Table 3-8 R gg, Grass - Cow - Milk Paghway Dose Factors - ADULT (grem/yr per pCi/m ) for H-3 and C-14 (m

mrem /yr per pC1/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 - 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 Na-24 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 2.54E+6 P-32 1.71E+10 1.06E+9 - - -

1.92E+9 6.60E+8 Cr-51 - -

1.71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 Mn-54 -

8.40E+6 2.50E+6 2.57E+7 1.60Es6 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 4.04E46 Fe-59 2.98E+7 7.00E+7 - -

1.95E+7 2.33E+8 2.68E+7 Co-57 -

1.28E+6 - - -

3.25E+7 2.13E+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 - - -

1.22E40 2.19E-2 Cu-64 -

2.41E+4 6.08E+4 2.05E+6 1.13E+4 2n-65 1.37E+9 4.36E+9 -

2.92E+9 -

2.75E+9 1.97E+9 2n-69 - - - - - - -

Br-82 - - - - -

3.72E+7 3.25E+7 Br-83 - - - - -

1.49E-1 1.03E-1 Br-84 - - - - - - -

Br-85 - - - - - - -

Rb-86 -

2.59E+9 5.11E+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 i Y-90 7.07E+1 - - - -

7.50E+5 1.90E+0 .l Y-91m - - - - - - -

Y-91 8.60E+3 -

4.73E+6 2.30E+2 Y-92 5.42E-5 -

9.49E-1 1.5BE-6 Y-93 2.33E-1 -

7.39E+3 l

6.43E-3 '

2r-95 9.46E+2 3.03E+2 -

4.76E+2 -

9.62E+5 2.05E+2 Zr-97 4.26E-1 8.59E-2 -

1.30E-1 -

2.66E+4 3.93E-2 Nb-95 8.25E+4 4.59E+4 4.54E+4 2.79E+8 2.47E+4 Nb-97 5.47E-9 Mo-99 -

2.52E+7 5.72E+7 5.85E+7 4.80E+6 !

Tc-99m 3.25E+0 9.19E+0 1.40E+2 4.50E+0 5.44E+3 1.17E+2 Tc-101 - - - - - - -

DBP 6027A 78 Revision 7.0 ODCM

Table 3 ' [ 'h 'R , Grass-Cow-MilkPathwaygoea Factors - ADULT (continued)

J\_,/ (mgemlyr per pCi/m ) for H-3 and C-14 (m

mrem /yr per pC1/sec) for others Nuclide- Bone Liver Thyroid Kidney Lung GI-LLI T. Body Ru-103' 1.02E+3 - - 3.89E+3 - 1.19E+5 4.39E+2-Ru-105. 8.57E-4 - - 1.11E-2 - 5.24E-1 3.38E-4 Ru-106 2.04E+4 - - 3.94E+4 - 1.32E+6 2.58E+3 Rh-103m - - - - -

Rh-106 - - - - -

Ag-110m 5.83E+7 5.39E+7 - 1.06E+8 - 2.20E+10 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 - 2.00E+7 7.31E+8 1.02E+7' Sb-125 2.04E+7 2.28E+5 2.08E+4 - 1.58E+7 2.25E+8 4.86E+6 Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 - 6.50E+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 - 1.54E+8 5.58E+6 Te-127 6.72E+2 2.41E+2 4.98E+2 2.74E+3 - 5.30E+4 1.45E+2 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 - 3.04E+8 9.57E+6 Te-129 - - - - - - -

Te-131m 3.61E+5 1.77E+5 2.80E+5 1.79E+6 - 1.75E+7 1.47E+5 Te-131 .- - - - - - -

Te-132 2.39E+6 1.55E+6 1.71E+6 1.49E+7 - 7.32E+7 1.45E+6 I-130 4.26E+5 1.26E+6 1.07E+8 1.96E+6 - 1.08E+6 4.96E+5 I-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 - 1.12E+8 2.43E+8 I-132 1.64E-1 4.37E-1 1.53E+1 6.97E-1 - 8.22E-2 1.53E-1 I-133 3.97E+6 6.90E+6 1.01E+9 1.20E+7 - 6.20E+6 2.10E+6 I-134 - - - -

I-135 1.39E+4 3.63E*4 2.40E+6 5.83E+4 - 4.10E+4 1.34E+4 Cs-134 5.65E+9 1.34E+10 - 4.35E+9 1.44E+9 2.35E+8 1.10E+10 Cs-136 2.61E+8 1.03E+9 - 5.74E+8 7.87E+7 1.17E+9 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 - - - - - - -

Ba-139 4.70E-8 - - - - 8.34E-8 1.38E-9 Ba-140 2.69E+7 3.38E+4 - 1.15E+4 1.93E+4 5.54E+7 1.76E+6 Ba-141 - - - - - - -

Ba-142 - - - - - - -

La-140 4.49E+0 2.26E+0 - - - 1.66E+5 5.97E-1 La-142 - -

- - - '3.03E-8 -

Ce-141 4.84E+3 3.27E+3 - 1.52E+3 - 1.25E+7 3.71E+2 Ce-143 4.19E+1 3.09E+4 - 1.36E+1 - 1.16E+6 3.42E+0 Ce-144 3.58E+5 1.50E+5 - 8.87E+4 - 1.21E+8 1.92E+4 Pr-143 1.59E+2 6.37E+1 - 3.68E+1 - 6.96E+5 7.88E+0 Pr-144 - - - - - - -

Nd-147 9.42E+1 1.09E+2 - 6.37E+1 - 5.23E+5 6.52E+0 W-187 6.56E+3 5.48E+3 - - - 1.80E+6 1.92E+3 Np-239 3.66E+0 3.60E-1 - 1.12E+0 - 7.39E+4 1.98E-1 DBP 6027A 79 Revision 7.0 CDCH

Table 3-8 (continued)

R yg. Grass - Cow - Milk Pathyay Dose Factors - TEENAGER (mgem/yr per pCi/m ) for H-3 cnd C-14 (m

mrem /yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 -

9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 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 P-32 3.15E+10 1.95E+9 2.65E+9 1.22E+9 Cr-51 - -

2.78E+4 1.10E+4 7.13E+4 8.40E+6 5.00E+4 Mn-54 -

1.40E+7 4.17E+6 2.87E+7 2.78E+6 Mn-56 -

7.51E-3 9.50E-3 4.94E-1 1.33E-3 Fe-55 4.45E+7 3.16E+7 2.00E+7 1.37E+7 7.36E+6 Fe-59 5.20E+7 1.21E+8 3.82E+7 2.87E+8 4.68E+7 Co-57 -

2.25E+6 4.19E+7 3.76E+6 Co-58 -

7.95E+6 1.10E+8 1.83E+7 Co-60 -

2.78E+7 3.62E+8 6.26E+7 Ni-63 1.18E+10 8.35E+8 1.33E+8 4.01E+8 N1-65 6.78S-1 8.66E-2 4.70E+0 3.94E-2 Cu-64 -

4.29E+4 1.09E+5 3.33E+6 2.02E+4 2n-65 2.11E+9 7.31E+9 4.68E+9 3.10E+9 3.41E+9 Zn-69 - - - - - - -

Br-82 - - - - - -

5.64E+7 Br-83 - - - - - -

1.91E.1 Br-84 - - - - - - -

Br-85 - - - - - - -

Rb-86 -

4.73E+9 - - -

7.00E+8 2.22E+9 Rb-88 - - - - - - -

Rb-89 - - - - - - -

Sr-89 2.67E+9 -

3. lee +8 7.66E+7 Sr-90 6.61E+10 - - - -

1.86E+9 1.63E+10 Sr-91 5.75E+4 - - - -

2. 61F.+ 5 2.29E+3 Sr-92 8.95E-1 -

2.28E+1 3.81E-2 Y-90 1.30E+2 -

1.07E+6 3.50E+0 Y-91m - - - - - - -

Y-91 1.58E+4 -

6.48E+6 4.24E+2 Y-92 1.00E-4 -

2.75E+0 2.90E-6 Y-93 4.30E-1 - - - -

1.31E+4 1.18E-2 Zr-95 1.65E+3 5.22E+2 -

7.67E+2 1.20E+6 Zr-97 3.59E+2 7.75E-1 1.53E-1 -

2.32E-1 -

4.15E+4 7.06E-2 Nb-95 1.41E+5 7.80E+4 7.57E+4 3.34E'8 4.30E+4 Nb-97 - - - - -

6.34E-8 -

Mo-99 -

4.56E+7 1.04E+8 8.16E+7 8.69E+6 Tc-99m 5.64E+0 1.57E+1 2.34E+2 8.73E+0 1.03E+4 2.04E+2 Tc-101 - - - - - - -

DBP 6027A 80 Revision 7.0 ODCM

Table 3-8 (continued)

I[~'\) R gg, Grass - Cow - Milk Pathway Dgse Factors - TEENAGER (continued)

\s,,/ (mgemlyr per pC1/m ) for H-3 and C-14 (m

mrem /yr per pCi/sec) for others Thyroid Kidney Lung GI-LLI T. Body-Nuclide Bone Liver Ru-103 1.81E+3 - - 6.40E+3 - 1.52E+5 7.75E+2 Ru-105 1.57E-3 - - 1.97E-2 - 1.26E+0 6.08E-4 Ru-106 3.75E+4 - - 7.23E+4 - 1.80E+6 4.73E+3 L

Rh-103m - - -

Rh-106 - - - -

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 3.00E+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 1.00E+7 Te-127 1.24E+3 4.41E+2 8.59E+2 5.04E+3 - 9.61E+4 2.68E+2 Te-129m 1.11E+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-1?lm 6.57E+5 3.15E+5 4.74E+5 3.29E+6 - 2.53E+7 2.63E+5 Te-131 - - - - - -

Te-132 4.28E+6 2.71E+6 2.86E+6 2.60E+7 - 8.58E+7 2.55E+6 I-130 7.49E+5 2.17E+6 1.77E+8 3.34E+6 - 1.67E+6 8.66E+5 I-131 5.38E+8 7.53E+8 2.20E+11 1.30E+9 - 1.49E+8 4.04E+8 I-132 2.90E-1 7.59E-1 2.56E+1 1.20E+0 - 3.31E-1 2.72E-1 I-133 7.24E+6 1.23E+7 1.72E+9 2.15E+7 - 9.30E+6 3.75E+6 I-134 - - - - - - -

I-135 2.47E+4 6.35E+4 4.08E+6 1.00E+5 - 7.03E+4 2.35E+4 Cs-134 9.81E+9 2.31E+10 - 7.34E+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+E 2.53E+8 6.20E+9 Cs-138 - - - - -

Ba-139 8.69E-8 - - - - 7.75E-7 2.53E-9 Ba-140 4.85E+7 5.95E+4 - 2.02E+4 4.00E+4 7.49E+7 3.13E+6 Ba-141 - - - - -

Ba-142 - - - - - -

La-140 8.06E+0 3.96E+0 - - - 2.27E+5 1.05E+0 La-142 - - -

- 2.23E-7 -

Ce-141 8.87E+3 5.92E+3 - 2.79E+3 - 1.69E+7 6.81E+2 Ce-143 7.69E+1 5.60E+4 - 2.51E+1 - 1.68E+6 6.25E+0 Ce-144 6.58E+5 2.72E+5 - 1.63E+5 - 1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 - 6.77E+1 - 9.61E+5 1.45E+1 Pr-144 - - - - - - -

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 DBP 6027A 81 Revision 7.0 ODCH

Table 3-8 (cor.tinued)

R gg. Grass-Cow-MilkPaghwayDoseFactors-CHILD (mgemlyrperpCi/m) for H-3 and C-14 (m

mrem /yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 - 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 Na-24 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 9.23E+6 P-32 7.77E+10 3.64E+9 - - -

2.15E+9 3.00E+9 Cr-51 - -

5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 Ma-54 -

2.09E+7 5.87E+6 1.76E+7 5.58E+6 Mn-56 -

1.31E-2 1.58E-2 1.90E+0 2.95E-3 Fe-55 1.12E+8 5.93E+7 - -

3.35E+7 1.10E+7 1.84E+7 Fe-59 1.20E+8 1.95E+8 5.65E+7 2.03E+8 9.71E+7 Co-57 -

3.84E+6 3.14E+7 7.77E+6 Co-58 -

1.21E+7 7.08E+7 3.72E+7 Co-60 -

4.32E+7 2.39E+8 1.27E+8 Ni-63 2.96E+10 1.59E+9 - - -

1.07E+8 1.01E+9 N1-65 1.66E+0 1.56E-1 1.91E+1 9.11E-2 Cu-64 -

7.55E+4 1.82E+5 3.54E+6 4.56E+4 Zn-65 4.13E+9 1.10E+10 -

6.94E+9 -

1.93E+9 6.85E+9 Zn-69 - - - - -

2.14E-9 -

Br-82 - - - - - -

1.15E+8 Br-83 - - - - - -

4.69E-1 Br-84 - - - - - - -

Br-85 - - - - - - -

Rb-86 -

8.77E+9 5.64E+8 5.39E+9 Rb-88 - - - - - - -

Rb-89 - - - - - - -

Sr-89 6.62E+9 - - - -

2.56E+8 1.89E+8 St-90 1.12E+11 - - - -

1.51E+9 2.83E+10 Sr-91 1.41E+5 - - - -

3.12E+5 5.33E+3 Sr-92 2.19E+0 - - - -

4.14E+1 8.76E-2 Y-90 3.22E+2 -

9.15E+5 8.61E+0 Y-91m - - - - - - -

Y-91 3.91E+4 -

5.21E+6 1.04E+3 Y-92 2.46E-4 -

7.10E+0 7.03E-6 Y-93 1.06E+0 1.57E+4 2.90E-2 Zr-95 3.84E+3 8.45E+2 -

1.21E+3 -

8.81E+5 7.52E+2 Zr-97 1.89E+0 2.72E-1 3.91E-1 4.13E+4 1.61E-1 Nb-95 3.15E+5 1.24E+5 -

1.16E+5 -

2.29E+8 8.84E+4 l

Hb-97 - - - - -

1.45E-6 -

i Mo-99 -

8.29E+7 1.77E+8 6.86E+7 2.05E+7 j Tc 99m 1.29E+1 2.54E+1 3.68E+2 1.29E+1 1.44E+4 4.20E+2 l Tc-101 - - - - - - -

1 DBP 6027A 82 Revision 7.0 ODCM l

l 1

- - . . . = . -. . .. . -. .- . .

l Table 3-8 (continued)

R yg, Grass-Cow-MilkPathwaygoseFactors-CHILD (continued)

(mgem/yr per pCi/m ) for H-3 and C-14 (m

mremlyr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-Li,I T. Body ;

Ru-103 ~4.29E+3 - -- 1.08E+4 -- 1.11E+5 1.65E+3 l Ru-105 3.82E-3 - - 3.36E-2 - 2.49E+0 1.39E-3 {

Ru-106 9.24E+4 - - 1.25E+5 - 1.44E+6 1.15E+4 ,

Rh-103m - - - - - -

l Rh-106 - - - -. - -

Ag-110m 2.09E+8 1.41E+8 - 2.63E+8 - 1.68E+10 1.13E+8 !

Sb-124 1.09E+8 1.41E+8 2.40E+5 - 6.03E+7 6.79E+8 3.81E+7 l I

Sb-125 8.70E+7 1.41E+6 8.06E+4 - 4.85E+7 2.08E+8 1.82E+7 Te-125m 7.38E+7 2.00E+7 2.07E+7 - - 7.12E+7 9.84E+6 l Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 - 1.68E+8 2.47E+7 l

Te-127 3.06E+3 8.25E+2 2.12E+3 8.71E+3 - 1.20E+5 6.56E+2 i Te-129m 2.72E+8 7.61E+7 8.78E+7 8.00E+8 - 3.32E+8 4.23E+7 l Te-129 - - - 2.87E-9 - 6.12E-8 -

l Te-131m 1.60E+6 5.53E+5 1.14E46 5.35E+6 - 2.24E+7 5.89E+5 :

Te-131 - - - - - - -

Te-132 1.02E+7 4.52E+6 6.58E+6 4.20E+7 - 4.55E+7 5.46E46 l I-130 1.75E+6 3.54E+6 3.90E+8 5.29E+6 - 1.66E+6 1.82E+6 i 1 131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 - 1.17E+8 7.46E+8 f I-132 6.86E-1 1.26E+0 5.85E+1 1.93E+0 - 1.48E+0 5.80E-1 j I-133 1.76E+7 2.18E+7 4.04E+9 3.63E+7 - 8.77E+6 8.23E+6 ;

i 1-134 - - - - - - - E I-135 5.84E+4 1.05E+5 9.30E+6 1.61E+5 - 8.00E+4 4.97E+4 I Cs-134- 2.26E+10 3.71E410 - 1.15E+10 4.13E+9 2.00E+8 7.83E+9 i Cs-136 1.00E+9 2.76E+9 - 1.47E+9 2.19E+8 9.70E+7 1.79E+9 I Cs-137 3.22E+10 3.09E+10 - 1.01E+10 3.62E+9 1.93E+8 4.55E+9 i

Cs-138 - - - - - - -

Ba-139 2.14E-7 - - - - 1.23E-5 6.19E-9 [

Ba-140 1.17E+8 1.03E+5 - 3.34E+4 6.12E+4 5.94E+7 6.84E46 i Ba-141 - - - - - - -

[

Ba-142 - - - - - - -

i La-140 1.93E+1 6.74E+0 - - - 1.88E+5 2.27E+0 ,

La-142 - - - - - 2.51E-6 -

l Ce-141 2.19E+4 1.09E+4 - 4.78E+3 - 1.36E+7 1.62E+3 l Ce-143 1.89E+2 1.02E45 - 4.29E+1 - 1.50E+6 1.48E+1 i Ce-144 1.62E+6 5.09E+5 - 2.82E+5 - 1.33E+8 8.66E+4 i I

Pr-143 7.23E+2 2.17E+2 - 1.17E+2 - 7.80E+5 3.59E+1 j Pr-144 - - - - - - -

Nd-147 4.45E+2 3.60E+2 - 1.98E+2 - 5.71E+5 2.79E+1 l W-187 2.91E+4 1.72E+4 - - - 2.42E46 7.73E+3 {

Np-239 1.72E41 1.23E+0 - 3.57E+0 - 9.14E+4 8.68E-1 l

l DBP 6027A 83 Revision 7.0 ODCM l

i l

1 l

l

~

Table 3-8 (continued) I R yg, Grass-Cow-MilkPaghwayDoseFactors-INFANT (mgem/yr per pCi/m ) for H-3 and C-14 (m

mrem /yr per pC1/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 - 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23E+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 Cr-51 - - 1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 Mn-54 - 3.89E+7 -

8.63E+6 - 1.43E+7 8.83E+6 Hn-56 - 3.21E-2 -

2.76E-2 - 2.91E+0 5.53E-3 Fe-55 1.35E+8 8.72E47 - -

4.27E+7 1.11E+7 2.33E+7 '

Fe-59 2.25E48 3.93E+8 - - 1.16E+8 1.88E+8 1.55E+8 Co-57 -

8.95E+6 - - -

3.05E+7 1.46E+7 l

Co 58 -

2.43E+7 - - -

6.05E+7 6.06E+7 Co-60 - 8.81E+7 - - - 2.10E+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 - - -

1.07E+8 1.21E49 Ni-65 3.51E+0 3.97E-1 - - -

3.02E+1 1.81E-1 Cu-64 -

1.88E+5 -

3.17E+5 -

3.85E+6 8.69E+4 I Zn-65 5.55E49 1.90E+10 - 9.23E+9 -

1.61E+10 8.78E+9 Zn-69 - - - - -

7.36E-9 -

Br-82 - - - - - - 1.94E+8 Br-83 - - - - - -

9.95E-1 Br-84 - - - - - - -

Br-85 - - - - - - -

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 7.33E44 - - - - 5.26E46 1.95E+3 Y-92 5.22E-4 - - - -

9.97E+0 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 1.41E45 Nb-97 - - - - -

3.70E-6 -

Mo-99 -

2.12E+8 -

3.17E+8 -

6.98E+7 4.13E+7 Tc-99m 2.69E+1 5.55E+1 -

5.97E42 2.90E+1 1.61E+4 7.15E+2 Tc-101 - - - - - - -

DBP 6027A 84 Revision 7.0 ODCM

7 D

7_

Table 3-8 (continued)

[ j R yg, Grass-Cow-MilkPathwaygoseFactors-INFANT (continued)

'n. / (mgem/yrperpCi/m) for H-3 and C-14 (m

mrem /yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body Ru-103 8.69E+3 - - 1.81E+4 - 1.06E+5 2.91E+3 Ru-105 8.06E-3 - - 5.92E-2 - 3.21E+0 2.71E-3 Ru-106 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 - 1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 - 1.31E+8 6.46E+8 6.49E+7 Sb-125 1.49E+8 1.45E+6 1.87E+5 - 9.38E+7 1.99E+8 3.07E+7 Te-125m 1.51E+8 5.04E+7 5.07E+7 - - 7.18E+7 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 - 1.70E+8 5.10E+7 Te-127 6.50E+3 2.18E+3 5.29E+3 1.59E+4 - 1.36E+5 1.40E+3 ,

Te-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 - 3.34E+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 1.12E46 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 p- I-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 - 1.15E+8 1.41E+9

{

> I-132 1.42E+0 2.89E+0 1.35E+2 3.22E+0 - 2.34E+0 1.03E+0

\I I-133 3.72E+7 5.41E+7 9.84E+9 6.36E+7 - 9.16E+6 1.58E+7 I-134 - - 1.01E-9 - - - -

I-135 1.21E+5 2.41E+5 2.16E+7 2.69E+5 - 8.74E+4 8.80E+4 Cs-134 3.65E+10 6.80E+10 - 1.75E+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 Cc-138 - - - - - - -

Ba-139 4.55E-7 - - - - 2.88E-5 1.32E-8 Ba-140 2.41E+8 2.41E+5 - 5.73E+4 1.48E+5 5.92E+7 1.24E+7 Ba-141 - - - - - - -

Ba-142 - - - - - - -

La-140 4.03E+1 1.59E+1 - - - 1.87E+5 4.09E+0 i La-142 - - - - - 5.21E-6 - l Ce-141 4.33E+4 2.64E+4 - 8.15E+3 -

1.37E+7 3.11E+3 l Ce-143 4.00E+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 l

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 I Np-239 3.64E+1 3.25E+0 - 6.49E+0 - 9.40E+4 1.84E+0

/~'T

(_ ,/ l DBP 6027A 85 Revision 7.0 ODCM

1 i

1 l

Table 3-9 '

R gg, Grass-Cow-MeatPaghwayDoseFactors-ADULT ,

(mgem/yr per pCi/m ) for H-3 and C-14 (m

mrem /yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 - 3.25E+2 3.25E+2 3.25E+2 3.25E+2 3.25E+2 3.25E+2 C-14 3.33E+5 6.66E+4 6.66E+4 6.66E+4 6.66E+4 6.66E+4 6.66E+4 Na-24 1.84E-3 1.84E-3 1.84E-3 1.84E-3 1.84E-3 1.84E-3 1.84E-3 P-32 4.65E+9 2.89E+8 - - - 5.23E+8 1.80E+8 Cr-51 - -

4.22E+3 1.56E+3 9.38E+3 1.78E+6 7.07E+3 Mn-54 -

9.15E+6 - 2.72E+6 - 2.80E+7 1.75E+6 Mn-56 - - - - - - -

Fe-55 2.93E+8 2.02E48 - -

1.13E+8 1.16E+8 4.72E+7 Fe-59 2.67E+8 6.27E+8 - -

1.75E+8 2.09E+9 2.40E+8 Co-57 -

5.64E+6 - - -

1.43E+8 9.37E+6 Co-58 - 1.83E+7 - - - 3.70E+8 4.10E+7 Co-60 -

7.52E+7 - - -

1.41E+9 1.66E+8 Hi-63 1.89E+10 1.31E+9 - - -

2.73E+8 6.33E+8 Ni-65 - - - - - - -

Cu-64 -

2.95E-7 - 7.45E-7 -

2.52E-5 1.39E-7 Zn-65 3.56E+8 1.13E+9 -

7.57E+8 - 7.13E+8 5.12E+8 Z,-69 - - - - - - -

Br-82 - - - - -

1.44E+3 1.26E+3 Br-83 - - - - - - -

Br-84 - - - - - - -

Br-85 - - - - - - -

Rb-86 - 4.87E+8 - - - 9.60E+7 2.27E+8 Rb-88 - - - - - - -

Rb-89 - - - - - - -

Sr-89 3.01E48 - - - - 4.84E+7 8.65E+6 Sr-90 1.24E+10 - - - - 3.59E+8 3.05E+9 Sr-91 - - - - -

1.38E-9 -

Sr-92 - - - - - - -

Y-90 1.07E+2 - - - -

1.13E+6 2.86E+0 Y-92m - - - - - - -

Y-91 1.13E+ - - - - 6.24E+8 3.03E+4 Y-92 - - - - - - -

Y-93 - - - - -

2.08E-7 -

Zr-95 1.88E+6 6.04E+5 -

9.48E+5 - 1.91E+9 4.09E+5 Zr-97 1.83E-5 3.69E-6 -

5.58E-6 -

1.14E+0 1.69E-6 Nb-95 2.29E+6 1.28E+6 -

1.26E+6 -

7.75E+9 6.8bE+5 Nb-97 - - - - - - -

Mo-99 -

1.09E+5 -

2.46E+5 -

2.52E+5 2.07E+4 Tc-99m - - - - - - -

Tc-101 - - - - - - -

DBP 6027A 86 Revision 7.0 ODCM

o i*

y ,'

Table 3-9 ,

[~') R yg, Grass-Cow-MeatPathwaygoseFactors-ADULT (continued) 1

\m) (mjem/yr per pCi/m ) for H-3 and C-14 (m

mrem /yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI- T. Body Ru-103 1.06E+8 - - 4.03E+8 - 1.23E+10 4.55E+7 Ru-105 - - - - - -

Ru-106 2.80E+9 - - 5.40E+9 - 1.81E+11 3.54E+8 '[

Rh-103m - - - - - -

Rh-106 - - - - -

1 Ag-110m 6.69E+6 6.19E+6 - 1.22E+7 - 2.52E+9 3.67E+6 :

Sb-124 1.98E+7 3.74E+5 4.80E+4 - 1.54E+7 5.62E+8 7.85E+6 !

Sb-125 1.91E+7 2.13E+5 1.94E+4 - 1.47E+7 2.10E+8 4.54E+6 Te-125m 3.59E+8 1.30E+8 1.08E+8 1.46E+9 - 1.43E+9 4.81E+7 Te-127m 1.12E+9 3.99E+8 2.85E+8 4.53E+9 - 3.74E+9 1.36E+8 {

Te-127 - - - 1.09E-9 - 2.10E-8 -

Te-129m 1.14E+9 4.27E+8 3.93E+8 4.77E+9 - 5.76E+9 1.81E+8 I Te-129 - - - - - - -

Te-131m 4.51E+2 2.21E+2 3.50E+2 2.24E+3 - 2.19E+4 1.84E+2 ;

Te-131 - - - - - - -

Te-132 1.40E+6 9.07E+5 1.00E+6 8.73E+6 - 4.29E+7 8.51E+5 ;

2.74E-6 1-130 2.35E-6 6.94E-6 5.88E-4 1.08E-5 - 5.98E-6 I-131 1.08E+7 1.54E+7 5.05E+9 2.64E+7 - 4.07E+6 8.83E+6 i

[~')

\m,/

I-132 1-133 4.30E-1 7.47E-1 1.10E+2 1.30E+0 6.72E-1 2.28E-1 j

t i

I-134 - - - - - - -

1-135 - - - - - - - ,

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 i

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-141 - - - - - - -

Ba-142 - - - - - - -

i La-140 3.60E-2 1.81E-2 - - - 1.33E+3 4.79E-3 l La-142 - - - - - - -

Ce-141 1.40E+4 9.4BE+3 - 4.40E+3 - 3.62E+7 1.08E+3 Ce-143 2.09E-2 1.55E+1 - 6.BOE-3 - 5.78E+2 1.71E-3 Ce-144 1.46E+6 6.09E+5 - 3.61E+5 - 4.93E+8 7.83E+4 i l

Pr-143 2.13E+4 8.54E+3 - 4.93E+3 - 9.33E+7 1.06E+3 I 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 {

Np-239 2.56E-1 2.51E-2 - 7.845-2 - 5.15E+3 1.39E-2 l

\ '

I 87 Revision 7.0 l DBP 6027A ODCM

e Table 3-9 (continued)

R gg, Grass-Cow-HeatPatgw)ayDoseFactors-TEENAGER (mgem/yrperpCi/m for H-3 and C-14 (m

mrem /yr per pC1/sec) for others Nuclide Bone _ Liver Thyroid Kidney LunR GI-LLI T. Body H-3 -

1.94E+2 1.94E+2 1.94E+2 1.94E+2 1.94E+2 1.94E+2 C-14 2.81E+5 5.62E+4 5.62E+4 5.62E+4 5.62E+4 5.62E+4 5.62E+4 Ha-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 -

3.30E+8 1.52E+8 Cr-51 - -

3.14E+3 1.24E+3 8.07E+3 9.50E+5 5.65E+3 Mn-54 -

6.98E+6 -

2.08E+6 1.43E+7 1.38E+6 Mn-56 - - - - - - -

Fe-55 2.38E+8 1.69E+8 1.07E+8 7.30E+7 3.93E+7 Fe-59 2.13E+8 4.98E+8 -

1.57E+8 1.18E+9 1.92E+8 Co-57 -

4.53E+6 -

8.45E+7 7.59E+6 Co-58 -

1.41E+7 1.94E+8 3.25E+7 Co-60 -

5.83E+7 -

7.60E+8 1.31E+8 Ni-63 1.52E+10 1.07E+9 - - -

1.71E+8 5.15E+8 Ni-65 - - - - - - -

Cu-64 -

2.41E-7 6.10E-7 1.87E-5 1.13E-7 2n-65 2.50E+8 8.69E+8 -

5.56E+8 3.68E+8 4.05E+8 2n-69 - - - - - - -

Br-82 - - - - - -

9.98E+2 Br-83 - - - - - - -

Br-84 - - - - - - -

Br-85 - - - - - - -

Rb-86 -

4.06E+8 6.01E+7 1.91E+8 Rb-88 - - - - - - -

Rb-89 - - - - - - -

Sr-89 2.54E+8 - - - -

3.03E+7 7.29E+6 Sr-90 8.05E+9 - .

2.26E+8 1.99E+9 Sr-91 - - - - -

1.10E-9 -

Sr-92 - - - - - - -

Y-90 8.98E+1 - - - -

7.40E+5 2.42E+0 Y-91m - - - - - - -

Y-91 9.56E+5 - - - -

3.92E+8 2.56E+4 Y-92 - - - - - - -

Y-93 - - - - -

1.69E-7 -

2r-95 1.51E+6 4.76E+5 -

6.99E+5 -

1.10E+9 3.27E+5 Zr-97 1.53E-5 3.02E-6 4.58E-6 8.18E-1 1.39E-6 Nb-95 1.79E46 9.94E+5 9.64E+5 4.25E49 5.47E+5 Hb-97 - - - - - - -

Mo-99 -

8.98E+4 2.06E+5 1.61E+5 1.71E+4 fc-99m - - - - - - -

Tc-101 - - - - - - -

DBP 6027A 88 Revision 7.0 ODCM B

v

.i F:.

i

~'

Table 3-9 (continued) l l R yg, Grass - Cow - Meat Pat.hway Dgse Factors - TEENAGER'(continued).

l (mgemlyr per pCi/m ) for H-3 and C-14 (m

mrem /yr per pC1/sec) for others ll Nuclide Bone Liver Thyroid Kidney Lung GI-LLI 'T. Body i

Ru-103 8.60E+7 - - 3.03E+8 - 7.18E+9 3.68E+7 !

Ra-105 - - - - - - -

[

Ru-106- ,2.36E+9 - - 4.55E+9- - 1.13E+11 . 2.97E+8 i Rh-103m - - - - - -

l Rh-106 - - , - .- - -

i 2.91E+6 Ag-110m 5.06E+6 4.79E+6 - 9.14E+6 - 1.35E+9 Sb-124 1.62E+7 2.98E+5 3.67E+4 - 1.41E+7 3.26E+8 6.31E+6 Sb-125 1.56E+7 1.71E+5 1.49E+4 - 1.37E+7 1.22E+8 3.66E+6 ,

Te-125m 3.03E+8 1.09E+8 8.47E+7 . - 8.94E+8 4.0$E+7. :

Te-127m 9.41E+8 3.**E+8 2.24E+8 3.8?.E+9 - 2.35E+9 1.12E+8 Te-127 - - - - - 1.75E-8 -

Te-129m 9.58E+8 3.56E+8 3.09E+8 4.01E+9 - 3.60E+9 1.52E+8 Te-129 - - - - - - -

'f 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 6.843+'

I-130 1.89E-6 5.48E-6 4.47E-4 8.44E-6 - 4.21E-6 2.191-6 I-131 8.95E+6 1.25E+7 3.66E+9 2.16E+7 - 2.48E+6 6. 7 3", r6 O

I-132 - - - t I-133 3.59E-1 6.10E-1 8.51E+1 1.07E+0 - 4.61E-1 1. 3f E-J l l

5 I-134 - - - - - - -

I-135 - - - - - - .

Cs-134 5.23E+8 1.23E+9 - 3.91E+8 1.49E+8 1.53E+7 5.71E+o- !

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 .

i Cs-138 - - - - - - -

j Ba-139 - - - - - - - i Ba-140 2.38E+7 2.91E+4 - 9.88E+3 1.96E+4 3.67E+7 1.53E+6 Ba-141 - - - - - - - jl 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 l l

Pr-143 1.79E+4 7.15E+3 - 4.16E+3 - 5.90E+7 8.92E+2 i t

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 . - 6.61E-2 - 3.39E+3 1.17E-2 i

l I

DBP 6027A 89 Revision 7.0 !

ODCM

Table 3-9 (continued)

R g9, Crass-Cow-HeatPaghwayDoseFactors-CHILD (mgem/yr per pCi/m ) for H-3 and C-14 (m

mrem /yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 -

2.34E+2 2.34E+2 2.34E+2 2.34E+2 2.34E+2 2.34E+2 C-14 5.29E+5 1.06E+5 1.06E+5 1.06E+5 1.06E+5 1.06E+5 1.06E+5 Na-24 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.34E-3 2.34E-3 P-32 7.41E+9 3.47E+8 - - -

2.05E+8 2.86E+8 Cr-51 - -

4.89E+3 1.34E+3 8.93E+3 4.67E+5 8.81E+3 Mn-54 -

7.99E+6 -

2.24E+6 -

6.70E+6 2.13E+6 Mn-56 - - - - - - -

Fe-55 4.57E+8 2.42E+8 - -

1.37E+P 4.49E+7 7.51E+7 Fe-59 3.78E+8 6.12E+8 - -

1.77E+L 6.37E+8 3.05E+8 Co-57 -

5.92E+6 - - -

4.85E+7 1.20E+7 Co-58 -

1.65E+7 - - -

9.60E+7 5.04E+7 Co-60 -

6.93E+7 - - -

3.84E+8 2.04E+8 Ni-63 2.91E+10 1.56E+9 - - -

1.05E+8 9.91E+8 Ni-65 - - - - - - -

Cu-64 -

3.24E-7 -

7.82E-7 -

1.52E-5 1.96E-7 Zn-65 3.75E+8 1.00E+9 -

6.30E+8 -

1.76E+8 6.22E+8 Zn-69 - - - - - - -

Br-82 - - - - - -

1.56E+3 Br-83 - - - - - - -

Br-84 - - - - - - -

Br-85 - - - - - - -

Rb-86 -

5.76E+8 3.71E+7 3.54E+8 Rb-88 - - - - - - -

, Rb-89 - - - - - - -

Sr-89 4.82E+8 - - - -

1.86E+7 1.38E+7 Sr-90 1.04E+10 - - - -

1.40E+8 2.64E+9 Sr-91 - - - - -

1.01E-9 -

Sr-92 - - - - - - -

Y-90 1.70E+2 -

4.84E+5 4.55E+0 .

Y-91m - - - - - - -

Y 91 1.81E+6 - -

2.41E+8 4.83E+4 Y-92 - - - - - - .

Y-93 - - - - -

1.55E-7 -

Zr-95 2.68E+6 5.89E+5 -

8.43E+5 -

6.14E+8 5.24E+5 Zr-97 2.84E-5 4.10E-6 -

5.89E-6 -

6.21E-1 2.42E-6 Nb-95 3.09E+6 1.20E+6 1.13E+6 2.23E+9 8.61E+5 Nb-97 - - - - - - -

Mo-99 -

1.2SE+5 2.67E45 1.03E+5 3.09E+4 Tc-99m - - - - - - -

Tc-101 - - - - - - -

DBP 6027A 90 Revision 7.0 ODCM

i

.a Table 3-9 (continued)

L/h-/ R yg, Grass - Cow . Heat Pathway gose Factors - CHILD (continued)

\s / (mgem/yrperpC1/m) for H-3 and C-14 f (m

mremlyr per pCi/sec) for others Nuclide Bone- Liver Thyroid Kidney LunR GI-LLI T. Body Ru-103 1.56E+8 - - 3.92E+8 - 4.02E+9 5.98E+7 Ru-105 - - - - - -

Ru-106 4.44E+9 - - 5.99E+9 - 6.90E+10 5.54E+8 Rh-103m- - - - - - - -

Rh-106 - - - - - - -

Ag-110m 8.40E+6 5.67E+6 - 1.06E+7 - 6.75E+8 4.53E+6 l Sb-124 2.93E+7 3.80E+5 6.46E+4 - 1.62E+7 1.83E+8 1.03E+7 l Sb-125 2.85E+7 2.19E+5 2.64E+4 - 1.59E+7 6.80E+7 5.96E+6 !

Te-125m 5.69E+8 1.54E+8 1.60E+8 - - 5.49E+8 7.59E+7 Te-127m 1.77E+9 4.78E+8 4.24E48 5.06E+9 - 1.44E+9 2.11E+8-Te-127 - - - 1.21E-9 - 1.66E-8 -

Te-129m 1.81E+9 5.04E+8 5.82E+8 5.30E+9 - 2.20E+9 2.80E+8 Te-129 - - - - - - - $

Te-131m 7.00E+2 2.42E+2 4.98E+2 2.34E+3 . 9.82E+3 2.58E+2 !

Te-131 - - - - - - -

Te-132 2.09E+6 9.27E+5 1.35E+6 8.60E+6 - 9.33E+6 1.12E+6 1-130 3.39E-6 6.85E-6 7.54E-4 1.02E-5 - 3.20E-6 3.53E-6 i I

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+0 - 3.33E-1 3.12E-1 I-134 - - - -

I-135 - - - - - - -

[

Cs-134 9.22E+8 1.51E+9 - 4.69E+8 1.68E+8 8.15E+6 3.19E+8 i Cs-136 1.59E+7 4.37E+7 - 2.33E+7 3.47E+6 1.54E+6 2.83E+7 [

Cs-137 1.33E+9 1.28E+9 - 4.16E+8 1.50E+8 7.99E+6 1.88E+8 f

Cs-138 - - - - - - -

Ba-139 - - - - - - -

t Ba 140 4.39E+7 3.85E+4 - 1.25E+4 2.29E+4 2.22E+7 2.56E+6 .

Ba-141 - - - - - - -

Ba-142 - - - - - - -

j La-140 5.41E-2 1.89E-2 - - - 5.27E+2 6.38E-3 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 i Pr-143 3.39E+4 1.02E+4 - 5.51E+3 - 3.66E+7 1.68E+3 ,

Pr-144 - - - - - - -

Nd-147 1.17E+4 9.48E+3 - 5.20E+3 - 1.50r+7 7.34E42 W-187 3.36E-2 1.99E-2 - - - 2.79E+0 8.92E-3 '

Np *19 4.20E-1 3.02E-2 - 8.73E-2 - 2.23E+3 2.12E-2 DBP 602"A 91 Revision 7.0 ;

ODCH

Table 3-10 R

Vegetation Pathwag Dose Factors - ADULT g ,(mgem/yr per pCi/m ) for H-3 and C-14 (m

mrem /yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 -

2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+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 P-32 1.40E+9 8.73E+7 1.58E+8 5.42E+7 Cr-51 - -

2.79E+4 1.03E+4 6.19E+4 1.17E+7 4.66E+4 M1-54 -

3.11E+8 -

9.27E+7 9.54E+8 5.94E+7 Mr. 56 -

1.61E+1 -

2.04E+1 5.13E+2 2.85E+0 Fe-55 2.09E+8 1.43Z15 -

8.06E+7 8.29E+7 3.37E+7 Fe-59 1.27E+8 2.99E+8 -

8.35E+7 9.96E+8 1.14E+8 Co-57 -

1.17E+7 -

2.97E+8 1.95E+7 Co-58 -

3.09E+7 6.26E+8 6.92E+7 Co-60 -

1.67E+8 3.14E+9 3.69E+8 Ni-63 1.04E+10 7.21E+8 - - -

1.50E+8 3.49E+8 Ni-65 6.15E+1 7.99E+0 - - -

2.03E+2 3.65E+0 Cu-64 -

9.27E+3 -

2.34E+4 7.90E+5 4.35E+3 Zn-65 3.17E+8 1.01E49 6.75E+8 6.36E+8 4.56E+8 Zn-69 8.75E-6 1.67E-5 1.09E-5 2.51E-6 1.16E-6 Br-82 - - - - - 1.73E+6 1.51E+6 Br-83 - - - - -

4.63E+0 3.21E+0 Br-84 - - - - - - -

Br-85 - - - - - - -

Rb-86 -

2.19E+8 4.32E+7 1.02E+8 Rb-88 - - - - - - -

Rb-89 - - - - - - -

Sr-89 9.96E+9 - - - -

1.60E+9 2.86E+8 Sr-90 6.05E+11 - - - -

1.75E+10 1.48E+11 Sr-91 3.20E+5 - - - -

1.52E+6 1.29E+4 Sr-92 4.27E+2 - - - -

8.46E+3 1.85E+1 Y-90 1.33E+4 - -

1.41E+8 3.56E+2 Y-91m 5.83E-9 - - - -

1.71E-8 -

Y-91 5.13E+6 - -

2.82E+9 1.37E+5 Y-92 9.01E-1 -

1.58E+4 2.63E-2 Y-93 1.74E+2 -

5.52E+6 4.80E+0 Zr-95 1.19E+6 3.81E+5 5.97E+5 1.21E+9 2.58E+5 Zr-97 3.33E+2 6.73E+1 -

1.02E+2 -

2.08E+7 3.08E+1 Hb-95 1.42E+5 7.91E+4 7.81E+4 4.80E+8 4.25E+4 Nb-97 2.90E-6 7.34E-7 -

8.56E-7 -

2.71E-3 2.68E-7

{

Mo-99 -

6.25E+6 1.41E+7 1.45E+7 1.19E+6 I Tc-99m 3.06E+0 8.66E40 1.32E+2 4.24E+0 5.12E+3 1.10E+2 Tc-101 - - - - - - -

DBP 6027A 92 Revision 7.0 l

ODCM

[

Table 3-10 (continued)

r R gg, Vegetation Pathway Dose Factors - ADULT (continued) 3 (s-)s (mgemlyrperpCi/m) for H-3 and C-14 (m

mrem /yr per pCi/sec) for others

'l l

't Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body [

,Ru-103 4.80E+6 - - 1.83E+7 - 5.61E+8- 2.07E+6 Ru-105 5.39E+1 - .- 6.96E+2 - 3.30E+4 2.13E+1 Ru-106 1.93E+8 - - 3.72E+8 - 1.25E+10 2.44E+7 Rh-103m - - - - - - -

l Rh-106 - - - - - - - >

Ag-110m 1.06E+7 9.76E+6 - 1.92E+7 - 3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 - 8.08E+7 2.95E+9 4.11E+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 - 1.05E+8 1.50E+9 3.25E+7 Te-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 - 3.86E+8 1.29E+7 r Te-127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 - 1.17E+9 4.26E+7 -[

Te-127 5.76E+3 2.07E+3 4.27E+3 2.35E+4 - 4.54E+5 1.25E+3 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 - 1.28E+9 4.03E+7 Te-129 6.65E-4 2.50E-4 5.10E-4 2.79E-3 - 5.02E-4 1.62E-4 [

Te-131m 9.12E+5 4.46E+5 7.06E+5 4.52E+6 - 4.43E+7 3.72E+5 Te-131 - - - - - - -

Te-132 4.29E+6 2.77E+6 3.06E+6 2.67E+7 - 1.31E+8 2.60E+6 I-130 3.96E+5. 1.17E+6 9.90E+7 1.82E+6 - 1.01E+6 4.61E+5 1-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 - 3.05E+7 6.63E+7 !

1-132 5.74E+1 1.54E+2 5.38E+3 2.45E+2 - 2.8DE+1 5.38E+1 .

1-133 2.12E+6 3.69E+6 5.42E+8 6.44E+6 - 3.31E+6 1.12E+6 I-134 1.06E-4 2.88E-4 5.00E-3 4.59E-4 - 2.51E-7 1.03E-4 '

I-135 4.08E+4 1.07E+5 7.04E+6 1.71E+5 - 1.21E+5 3.94E+4 Cs-134 4.66E+9 1.11E+10 - 3.59E+9 1.19E+9 1.94E+8 9.07E+9 f Cs-136 4.20E+7 1.66E+8 - 9.24E+7 1.27E+7 1.89E+7 1.19E+8 i Cs-137 6.36E+9' 8.70E+9 - 2.95E+9 9.81E+8 1.68E+8 5.70E+9 I Cs-138 - - - - - - -

Ba-139 2.95E-2 2.10E-5 - 1.96E-5 1.19E-5 5.23E-2 8.64E-4 Ba-140 1.29E+8 1.62E+5 - 5.49E+4 9.25E+4 2.65E+8 8.43E+6-Ba-141 - - - - - - -

Ba-142 - - - - - - -

l l

La-140 1.97E+3 9.92E+2 - - - 7.28E+7 2.62E+2 La-142 1.40E-4 6.35E-5 - - - 4.64E-1 1.58E-5 ,

Ce-141 1.96E+5 1.33E+5 - 6.17E+4 - 5.08E+8 1.51E+4 Ce-143 1.00E+3 7.42E+5 - 3.26E+2 - 2.77E+7 8.21E+1 t Ce-144 3.29E+7 1.3BE+7 - 8.16E+6 - 1.11E+10 1.77E+6 l Pr-143 6.34E+4 2.54E+4 - 1.47E+4 - 2.78E+8 3.14E+3 Pr-144 - - - - - - -

Nd-147 3.34E+4 3.86E+4 - 2.25E+4 - 1.85E48 2.31E43 ,

V-187 3.82E+4 3.19E+4 - - - 1.0$E+7 1.12E+4 Np-239 1.42E+3 1.40E+2 - 4.37E+2 - 2.87E+7 7.72E+1 ,

1 DBP 6027A 93 Revision 7.0 !

ODCM l l

Table 3-10 (continued)

R gg, Vegetation Pathway Dose 3

Factors - TEENAGER (mgem/yr per pCi/m ) for H-3 and C-14 (m

mrem /yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 - 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 Na-24 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 2.45E+5 P-32 1.61E+9 9.96E+7 - - - 1.35E+8 6.23E+7 Cr-51 - -

3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 Mn-54 - 4.52E+8 -

1.35E+8 - 9.27E+8 8.97E+7 Mn-56 - 1.45E+1 -

1.83E+1 -

9.54E+2 2.58E+0 Fe-55 3.25E+8 2.31E+8 - -

1.46E+8 9.98E+7 5.38E+7 Fe-59 1.81E+8 4.22E+8 - -

1.33E+8 9.98E+8 1.63E+8 Co-57 - 1.79E+7 - - -

3.34E+8 3.00E+7 Co-58 - 4.38E+7 - - -

6.04E+8 1.01E+8 Co-60 -

2.49E+8 - - -

3.24E+9 5.60E+8

~

Ni-63 1.61E+10 1.13E+9 - - -

1.81E+8 5.45E+8 Ni-65 5.73E+1 7.32E+0 - - -

3.97E+2 3.33E40 Cu-64 -

8.40E+3 -

2.12E+4 -

6.51E+5 3.95E+3 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 B r-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 - - - - - - -

Sr-89 1.51E+10 - - - -

1.80E+9 4.33E+8 Sr-90 7.51E+11 - - - -

2.11E+10 1.85E+11 Sr-91 2.99E+5 - - - -

1.36E+6 1.19E+4 Sr-92 3.97E+2 - - - -

1.01E+4 1.69E+1 Y-90 1.24E+4 - - - -

1.02E+8 3.34E+2 Y-91m 5.43E-9 - - - -

2.56E-7 -

Y-91 7.87E+6 - - - -

3.23E+9 2.11E+5 Y-92 8.47E-1 - . - -

2.32E+4 2.45E-2 Y-93 1.63E+2 - - - -

4.98E+6 4.47E+0 Zr-95 1.74E+6 5.49E+5 -

8.07E+5 -

1.27E+9 3.78E+5 Zr-97 3.09E+2 6.11E+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 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 Tc-99m 2.70E+0 7.54E+0 -

1.12E+2 4.19E+0 4.95E+3 9.77E+1 Tc-101 - - - - - - -

DBP 6027A 94 Revision 7.0 ODCM

r e

Table 3-10 (continued) !

/'~'\ Rj ,, Vegetation Pathway Dose gactors - TEENAGER (continued) !

is_,/ (mgem/yr per pCi/m ) for H-3 and C-14 !

(m

mremlyr per pC1/sec) for others i

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI- T. Body Ru-103 6.87E+6 - - 2.42E+7 - 5.74E+8 2.94E+6 ;

Ru-105 5.00E+1 - - 6.31E+2 - 4.04E+4 1.94E+1 {

Ru-106 3.09E+8 - - 5.97E+8 - 1.48E+10 3.90E+7 Rh-103m - - - - - - -

f Rh-106 - - - - - - -

i Ag-110m 1.52E+7 1.44E+7 - 2.74E+7 - 4.04E+9 8.74E+6 !

Sb-124 1.55E+8 2.85E+6 3.51E+5 - 1.35E+8 3.11E+9 6.03E+7 >

Sb-125 2.14E+8 2.34E+6 2.04E+5 - 1.88E+8 1.66E+9 5.00E+7 ,

Te-125m 1.48E+8 5.34E+7 4.14E+7 - - 4.37E+8 1.98E+7 f Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 - 1.37E+9 6.56E+7 i Te-127 5.43E+3 1.92E+3 3.74E+3 2.20E+4 - 4.19E+5 1.17E+3 f Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 - 1.38E+9 5.81E+7 i Te-129 6.22E-4 2.32E-4 4.45E-4 2.61E-3 - 3.40E-3 1.51E-4 Te-131m 8.44E+5 4.05E+5 6.09E+5 4.22E+6 - 3.25E+7 3.38E+5 !

Te-131 - - - - - - -

j Te-132 3.90E+6 2.47E+6 2.60E+6 2.37E+7 - 7.82E+7 2.32E46 :

I-130 3.54E+5 1.02E+6 8.35E+7 1.58E+6 - 7.87E+5 4.09E+5 I-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 - 2.13E+7 5.79E+7 l I-132 5.18E+1 1.36E+2 4.57E+3 2.14E+2 - 5.91E+1 4.87E+1 !

I-133 1.97E+6 3.34E+6 4.66E+8 5.86E+6 - 2.53E+6 1.02E+6 :

[

I-134 9.59E-5 2.54E-4 4.24E-3 4.01E-4 - 3.35E-6 9.13E-5 I-135 3.68E+4 9.48E+4 6.10E+6 1.50E+5 - 1.05E+5 3.52E+4 Cs-134 7.09E+9 1.67E+10 - 5.30E+9 2.02E+9 2.08E+8 7.74E+9 Cs-136 4.29E+7 1.69E48 - 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 >

t 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 - - - - - - -

i La-140 1.80E+5 B.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 - B.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.S3E+6 i

Pr-143 7.12E+4 2.84E+4 - 1.65E+4 - 2.34E+8 3.55E+3 l

Pr-144 - - - - - - -

Nd-147 3.63E+4 3.94E+4 - 2.32E+4 - 1.42E+8 2.36E+3 W-187 3.55E+4 2.90E+4 - - - 7.84E+6 1.02E+4 Np-239 1.38E+3 1.30E+2 - 4.09E+2 - 2.10E+7 7.24E+1 O

DBP 6027A 95 Revision 7.0 ODCM

i l

~

. l Table 3-10 (continued)

R gg*(Vegetation Pathwag) Dose Factors - CHILD mgem/yrperpC1/m for H-3 and C-14 (m

mrem /yr per pCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body H-3 - 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+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 P-32 3.37E+9 1.58E+8 - - - 9.30E+7 1.30E+8 Cr-51 - - 6.54E+4 1 79E+4 1.19E+5 6.25E+6 1.18E+5 Mn-54 -

6.61E+8 -

1. 15 E+ 8 - 5.55E+8 1.76E+8 Mn-56 -

1.90E+1 . 2.29E+1 - 2.75E+3 4.28E+0 Fe-55 8.00E+8 4.24E+8 - -

2.40E+0 7.86E+7 1.31E+8 Fe-59 4.01E+8 6.49E+8 - - 1.88E+8 6.763+8 3.23E+8 Co-57 - 2.99E+7 - - -

2.45E+8 6.04E+7 Co-58 -

6.47E+7 - - - 3.77E+8 1.98E+8 Co-60 -

3.78E+8 - - -

2.10E+9 1.12E+9 Ni-63 3.95E+10 2.11E+9 - - - 1.42E+8 1.34E+9 Ni-65 1.05E+2 9.89E+0 - - -

1.21E+3 5.77E+0 Cu-64 -

1.11E+4 -

2.68E+4 -

5.20E+5 6.69E+3 Zn-65 8.12E+8 2.16E+9 -

1.36E+9 - 3.80E+8 1.35E+9 Zn-69 1.51E-5 2.18E-5 - 1.32E-5 -

1.38E-3 2.02E-6 Br-82 - - - - - - 2.04E+6 Br-83 - - - - - -

5.55E+0 Br-84 - - - - - - -

Br-85 - - - - - - -

Rb-86 - 4.52E48 - - -

2.91E+7 2.78E+8 Rb-88 - - - - - - -

. Rb-89 - - - - - - -

Sr-89 3.59E+10 - - - -

1.39E+9 1.03E+9 Sr-90 1.24E+12 - - - -

1.67E+10 3.15E+11 Sr-91 5.50E+5 - - - -

1.21E+6 2.08E+4 Sr-92 7.28E+2 - - - -

1.38E+4 2.92E+1 Y-90 2.30E+4 - - - -

6.56E+7 6.17E+2 -

Y-91m 9.94E-9 - - - -

1.95E-5 -

Y-91 1.87E+7 - - - -

2.49E+9 5.01E+5 Y-92 1.56E40 - - - - 4.51E44 4.46E-2 Y-93 3.01E+2 - - - - 4.48E+6 8.25E+0 Zr-95 3.90E+6 8.58E+5 -

1.23E+6 -

8.95E+8 7.64E+5 2r-97 5.64E+2 8.15E+1 -

1.17E+2 -

1.23E+7 4.81E+1 Nb-95 4.10E+5 1.59E+5 -

1.50E+5 -

2.95E+8 1.14E+5 Nb-97 4.90E-6 8.85E-7 -

9.82E-7 -

2.73E-1 4.13E-7 Mo-99 -

7.83E+6 -

1.67E+7 -

6.48E+6 1.94E+6 Tc-99m 4.65E+0 9.12E+0 -

1.33E+2 4.63E+0 5.19E+3 1.51E+2 Tc-101 - - - - - - -

DBP 6027A 96 Revision 7.0 ODCM

e

-, Table 3-10 (continued)

Ry ' Vegetation Pathway Dose3 Factors - CHILD (continued)

[k -) (mgem/yr per pCi/m ) for H-3 and C-14 (m

mrem /yr per pC1/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body Ru-103 1.55E+7 - - 3.89E+7 - 3.99E+8 5.94E+6 Ru-105 9.17E+1 - - 8.06E+2 - 5.98E+4 3.33E+1 Ru-106 7.45E+8 - - 1.01E+9 - 1.16E+10 9.30E+7 Rh-103m - - - - - - -

Rh-106 - - - - - - -

Ag-110m 3.22E+7 2.17E+7 - 4.05E+7 - 2.58E+9 1.74E+7 Sb-124 3.52E+8 4.57E+6 7.78E+5 - 1.96E+8 2.20E+9 1.23E+8 Sb-125 4.99E+8 3.85E+6 4.62E+5 - 2.78E+8 1.19E+9 1.05E+8 Te-125m 3.51E+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 1.00E+4 2.70E+3 6.93E+3 2.85E+4 - 3.91E+5 2.15E+3 Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 - 1.04E+9 1.33E+8 Te-129 1.15E-3 3.22E-4 8.22E-4 3.37E-3 - 7.17E-2 2.74E-4 Te-131m 1.54E+6 5.33E+5 1.10E+6 5.16E+6 - 2.16E+7 5.68E+5 Te-131 - - - - - - -

Te-132 6.98E+6 3.09E+6 4.50E+6 2.87E+7 - 3.11E+7 3.73E+6 s 1-130 6.21E+5 1.26E+6 1.38E+8 1.88E+6 - 5.87E+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 I-134 1.70E-4 3.16E-4 7.28E-3 4.84E-4 - 2.10E-4 1.46E-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 2.63E+10 - 8.14E+9 2.92E+9 1.42E+8 5.54E+9 Cs-136 8.06E+7 2.22E+8 - 1.18E+8 1.76E+7 7.79E+6 1.43E+8 Cs-137 2.39E+10 2.29E+10 - 7.46E+9 2.68E+9 1.43E+8 3.38E+9 Cs-138 - - - - - - -

Ba-139 5.11E-2 2.73E-5 - 2.38E-5 1.61E-5 2.75E+0 1.48E-3 Ba-140 2.77E+8 2.43E+5 - 7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ba-141 - - - - - - -

Ba-142 - - - - - - -

La-140 3.23E+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

-s W-187 6.47E+4 3.83E+4 - - - 5.38E+6 1.72E+4

> l Np-239 2.55E+3 1.83E+2 - 5.30E+2 - 1.36E+7 1.29E+2 Q/

DBP 6027A 97 Revision 7.0 ODCM

Table 3-11 Rg ,* Groynd Plane Pathway Dose Factors (m

mremlyr per pCi/sec)

Nuclide Any Organ Nuclide Any Organ Rh-103m -

C-14 -

Rh-106 -

Na-24 1.21E+7 Ag-110m 3.47E+9 P-32 -

Te-125m 1.55E+6 Cr-51 4.68E+6 Te-127m 9.17E+4 Hn-54 1.34E+9 Te-127 3.00E+3 Hn-56 9.05E+5 Te-129m 2.00E+7 Fe-55 -

Te-129 2.60E+4 Fe-59 2.75E+8 Te-131m 8.03E+6 Co-58 3.82E+8 Te-131 2.93E+4 Co-60 2.16E+10 Te-132 4.22E+6 Ni-63 -

I-130 5.53E+6 Ni-65 2.97E+5 I-131 1.72E+7 Cu-64 6.09E+5 I-132 1.24E+6 Zn-65 7.45E+8 I-133 2.47E+6 I-134 4.49E+5 Zn-69 -

I-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 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 . 4 8 E+.' Ce-141 1.36E+7 Y-91m 1.01E+5 Ce-143 2.32E+6 Y-91 1.08E+6 Ce-144 6.95E+7 Y-92 1.80E+5 Pr-143 -

Y-93 1.85E+5 Pr-144 1.83E+3 Zr-95 2.48E+8 Nd-147 8.40E+6 Zr-97 2.94E+6 W-187 2.36E+6 Nb-95 1.36E+8 Np-239 1.71E+6 Mo-99 4.05E+6 Tc-99m 1.83E+5 Tc 101 2.04E+4 Ru-103 1.09E+8 Ru-105 6.36E+5 Ru-106 4.21E+8 O

DBP 6027A 98 Revision 7.0 ODCM

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~ FOR INFORMATION ONIY o

4.0 SPECIAL DOSE ANALYSES 4.1 DOSES TO PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY In accordance with Section 7.2, the Radioactive Effluent Release Report shall include an assessment of radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.

In special instances MEMBERS OF THE PUBLIC are permitted access to the radiologically restricted area within the Davis-Besse station. Tours for the public are conducted with the assurance that no individual will receive an appreciable dose (i.e., small fraction of the 40 CFR 190 dose standards).

The Visitor Center located inside the Davis-Besse Administration Building (DBAB) is also accessible to MEMBERS OF THE PUBLIC. Considering the frequency and duration of the visits, the resultant dose would be a small fraction of the calculated maximum SITE BOUNDARY doses. The dose from gaseous effluents as modeled for the DBAB Visitor Center is considered the controlling factor when evaluating doses to MEMBERS OF THE PUBLIC from activities inside the SITE BOUNDARY.

For purposes of assessing the dose to MEMBERS OF THE PUBLIC in accordance with Technical Specification 6.9.1.11 and ODCH Section 7.2, the following exposure assumptions may be used:

Exposure time for maximum exposed visitor of 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months (4 visits, 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months per visit).*

Annual average meteorological dispersion (conservative, default use of maximum SITE BOUNDARY dispersion) from Table 3-6.

The equations in Section 4.2 may be used for calculating the potential dose to a MEMBER OF THE PUBLIC for activities inside the SITE BOUNDARY.

Based on these assumptions, this dose would be at least a factor of 400 less than the maximum SITE BOUNDARY air dose as calculated in Section 3.7.

There are no areas onsite accessible to the public where exposure to liquid effluents could occur. Therefore, the modeling of Section 2.4 conservatively estimates the maximum potential dose to MEMBERS OF THE PUBLIC.

l 1

l l

Based on a maximum conservative estimate.

till 1 DBP 6027A 100 Revision 7.0 ODCM

i i

I 4.2 DOSES TO MEMBERS OF THE PUBLIC - 40 CFR 190

(' ,,)i As required by and ODCM Section 7.2, the Radioactive Effluent Release 1 Report shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other !

nearby uranium fuel cycle sources (including dose 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 THE PUBLIC in the immediate vicinity of the site. Fermi-2 is the closest fuel cycle facility located about 20 miles to the NNW. Due to environmental dispersion, any routine releases from Fermi-2 would contribute insignificantly to the potential doses in the vicinity of Davis-Besse.

The correlation of measured plant effluents with pathway modeling of this ODCM provide the primary method for demonstrating / evaluating compliance with the limits specified below (40 CFR 190). However, as appropriate, the results of the environmental monitoring program may be used to provide additional data on actual measured levels of radioactive material in the actual pathways of exposure. ODCM Section 4.2.3 discusses the methodology for correlating measured levels of radioactive material in environmental pathway samples with potential doses. Also, results of the land use census may be used to determine actual exposure pathways and locations.

The annual (calendar year) dose or dose commitment to any MEMBER OF THE

(T (s_,/ PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

With the calculated doses fror. the releases of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Sections 2.4.1, 3.7.1, and 3.8.1, evaluations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of this Section have been exceeded. If such is the case, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40

) CFR Part 190. Submittal of the report is considered a timely request, and

('~'/

(,_, a variance is granted until staff action on the request is complete.

DBP 6027A 101 Revision 7.0 ODCM

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 and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

It is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the reactor remains within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor and outside storage tanks are kept small.

The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that the dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If a dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other dose requirements for dose limitation of 10 CFR Part 20, as addressed in Sections 2.2 and 3.3.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is a part of the nuclear fuel cycle.

4.2.1 Effluent Dose Calculations For purposes of implementing the above requirements of determining the cumulative dose contribution from 11guld and gaseous effluents in accordance with Sections 2 and 3 and the reporting requirements of Section 7, dose calculations for Davis-Besse may be performed using the 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.

The following equations may be used for calculating the dose to MEMBERS OF THE PUBLIC from releases of noble gases:

D tb

= 3.17E-08

U

y/Q

E (K g *Q g ) (4-1) 8760 and D, = 3.17E-08

U

y/Q

E ((Lg + 1.1 Mg) *Q)g (4-2)

O DBP 6027A 102 Revision 7.0 ODCM

I where

() Dg = total body dose due to gamma emissions for noble gas radionuclides (mrem)

D = skin dose due to gamma and beta emissions for noble gas radionuclides (mrem)

U = duration of exposure (hr/yr, default values in Table 4-1)

I/Q = atmospheric dispersion to the offsite location (sec/m )3 Qg = cumulative release of noble gas radionuclide i over the period of interest (pci)

Kg =

total body dose factor he to gamma eminions frgm nome gas radionuclide i from Table 3-5 (mremlyr per pCi/m )

Lg =

skin dose factor radionuclide due i from to beta Table 3-5 emissions frompCi/m (mrem /yr per nobig) gas Mg =

gammaairdosefactor{ornoblegasradionuclideifromTable 3-5 (mradlyr per pCi/m )

8760 = hours per year 1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad) b 3.17E-08 = 1/3.15E+07 yr/sec Average annual meteorological dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used (e.g., quarterly averages or year-specific annual averages).

4.2.2 Direct Exposure Dose Determination - Onsite Sources Any potentially significant direct exposure contribution from onsite sources to offsite individual doses may be evaluated based on the results of the environmental measurements (e.g., TLD, ion chamber measurements) or by the use of a radiation transport and shielding calculational method. Only during atypical conditions will there exist any potential for significant onsite sources at Davis-Besse t 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.

(O DBP 6027A 103 Revision 7.0 ODCH

The following simplified method may be used for evaluating the direct dose based on ensite or site boundary measurements:

Dg ,6 =D'B IA B, ('~3)

(X g,6)2 where:

D B'

=

direct radiation dose measured at location B (onsite or site boundary) in sector 6 Dg 6= extrapolated dose at location L in same sector 6 X g,6 = distance to the location L from the radiation source X B,6 = distance to location B from the radiation source 4.2.3 Dose Assessment Based on Radiological Environmental Monitoring Data Normally, the assessment of potential doses to MEMBERS OF THE PUBLIC '

must be calculated based on the measured radioactive effluents at the plant. The resultant levels of radioactive material in the offsite environment are so minute as to be undetectable. The calculational 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, the data provides a qualitative assessment - a confirmatory demonstration of the negli: tble impact.

Dose modeling can be simplified into three basic parameters that can be applied in using environmental monitoring data for dose assessment.

D = C

U

DF (4-4) where D =

dose or dose commitment C =

concentration in the exposure media, such as air concentration for the inhalation pathway, or fish, vegetation or milk l concentration for the ingestion pathway !

U =

individual exposure to the pathway, such as hr/yr for direct I exposure, kg/yr for ingestion pathway DF =

dose conversion factor to convert from an exposure or uptake to an individual dose or dose commitment DBP 6027A 104 Revision 7.0 l ODCM I

y

k. .

a .

The applicability of each of these basic modeling parameters to the use of I' O_ l environmental monitoring data for dose assessment is addressed below:

I Concentration - C The main value of using environmental-sampling data to assess potential- ,

r. 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.

Environmental samples are collected on a routine frequency (e.g., weekly airborne particulate samples, monthly vegetable samples, annual fish samples). To determine the annual average concentration in the environmental medium for use in assessing cumulative dose for the year, an average concentration should be determined based on the sampling frequency and measured levels. ,

Cg = E(Cg

t)/365 ('4 - 5 ) [

where:

Cg = average concentration in the sampling medium for the year Cg = concentration of each radionuclide 4 measured in the individual sampling medium h

(f t = period of time that the measured concentration is 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 i of zero should be used for Cg (Cg = 0).

Exposure - U Default exposure values (U) as recommended in Regulatory Guide 1.109 are presented in Table 4-1. These values should be used only when specific '

data applicable to the environmental pathway being evaluated is unavailable. .

Also, the routine radiological environmental monitoring program is designed to sample / monitor the environmental media that would provide early indications of any measurable levels in the environment but not ;

necessarily levels to which any individual is exposed. For example, j sediment samples are collected in the area of the liquid discharge:

typically, no individuals are directly exposed. To apply the measured

levels of radioactivity in samples that are not directly applicable to exposure to real individuals, the approach recommended is to correlate the location and measured levels to actual locations of exposure. l Hydrological or atmospheric dilution factors can be used to provide '

reasonable correlations of concentrations (and doses) at other locations.

h)

\. The other alternative is to conservatively assume a hypothetical DBP 6027A 105 Revision 7.0 i ODCM

i

. \

Individual at the sampling location. Doses that are calculated in this l manner should be presented as hypothetical and very conservatively ;

determined - actual exposure would be much less. Samples collected from l nearby wells or actual water supply intake (e.g., Port Clinton) should be l used for estimating the potential drinking water doses. Other water samples collected, such as near field dilution area, are not applicable to this pathway.

Dose Factors - DF The dose factors are used to convert the intake of the radioactive material to an individual dose commitment. Values of the dose factors are presented in NRC Regulatory Guide 1.109. The use of the Regulatory Guide 1.109 values applicable to the exposure pathway and maximum exposed individual is referenced in Table 4-1.

4.2.4 Use of Environmental TLD for Assessing Doses Due to Noble Gas Releases Thermoluminescent dosimeters (TLD) are routinely used to assess the direct exposure component of radiation doses in the environment.

However, because routine releases of radioactive material (noble gases) are so low, the resultant direct exposure doses are also very low. A study

performed for the NRC concluded that it is possible to determine a plant contribution to the natural background radiation levels (direct exposure) of around 10 mrem per year (by optimum methods and high precision data). Therefore, for routine releases from nuclear power plants the use of TLD is mainly confinmatory -

ensuring actual exposures are within the expected natural background variation.

For releases of noble gases, environmental modeling using plant measured releases and atmospheric transport models as presented in this ODCM represents the best method of assessing potential environmental doses. However, any observed variations in TLD measurements outside the norm should be evaluated.

NUREG/CR-0711. Evaluation of Methods for the Determination of X- and Gamma-Ray Exposure Attributable to a Nuclear Facility Using Environmental TLD Measurements, Gail dePlanque, June 1979, USNRC.

DBP 6027A 105 Revision 7.0 ODCM

Table 4-1 Recommended Exposure Rates in Lieu of Site Specific Data

O Table Reference Exposure Pathway Maximum Exposed Exposure Rates for Dose Factors Age Group from RG 1.109 Liquid Releases Fish Adult 21 kg/y E-11 Drinking Water Adult 730 1/y E-11 Bottom Sediment Teen 67 h/y E-6 Atmospheric 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 kgly E-13 Fruits. Vegetables & Grain Teen 630 kg/y E-12 Milk Infant 330 1/y E-14 1

l 1

Adapted from Regulatory Guide 1.109 Table E-5 Net exposure of 6.100 h/y is based on the total 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months per year adjusted by a 0.7 shielding factor as recommended in Reguletory Guide ,

1.109. I DBP 6027A 107 Revision 7.0 ODCM

{

5.0 ASSESSMENT OF LAND USE CENSUS DATA A land use census (LUC) is conducted annually in the vicinity of the Davis-Besse site. This census fulfilla two main purposes: 1) meet requirements of TS 6.8.4.e (as required by 10 CFR 50, Appendix I, Section IV.B.3) for identifying controlling location / pathway for dose ascessment of ODCM Section 3.8.1: and (2) provide data on actual exposure pathways for assessing realistic doses to MEMBERS OF THE PUBLIC.

5.1 LAND USE CENSUS REQUIREMENTS A land use census shall be conducted during the growing season at least once per twelve months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricultural authorities. The land use census shall identify within a distance of 8 km (5 miles) the location, in each of the 16 meteorologicalsectors,ofthenearestmilkanimal,ghenearest residence and the nearest garden of greater than 50 m2 (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. ~

ThiscensussatisfiestherequirementsofSectionIV.B.3ofAppendixIgo 10CFR[ art 50. 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) 202 of the garden was used for growing broad leaf vegetation (i.eg ,

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 dore assessment and for updating the Radiological Environmental Monitoring Program. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 7.1.

With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Sections 3.8.1, in lieu of a Licensee Event Report, identify the new locations (s) in the next Radioactive Effluent Release Report, parsuant to Section 7.2. With a land use census identifying a locations (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than that at a location from which samples are currently being obtained in accordance with 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 cf a Licensee Event Report and 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).

O DBP 6027A 108 Revision 7.0 ODCM

The following guidelines shall be used for assessing the.results from the

(, h land use census to ensure compliance with this Section.

)

5.1.1 Data Compilation 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 Environmen'al Monitoring Program (Table 6-2) will ba identified.

C. Historical, annual average meteorological dispersion parameters (y/Q, D/Q) for any new location (i.e., location not previously identified and/or evaluated) will be determined. All locations should be evaluated against the same historical meteorological data set.

5.1.2 Relative Dose Significance A. For all new locations, the relative dose significance will be determined by applicable pathways of expcsure.

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 location used in the ODCM Table 3-4 will be verified. If any location / pathway (s) is identified with a higher relative dose, this location / pathway (s) should replace the previously identified controlling location / pathway in Table 3-4. If the previously identified controlling pathway is no longer present, the current controlling location / pathway should be determined.

B. Any changes in either the controlling location / pathway (s) of the ODCM dose calculations (Section 3.7 and Table 3-4) or the Radiological Environmental Monitoring Program (ODCM Section 6.0 and Table 6-2) shall be reported to NRC in accordance with ODCM Section 5.1 and 7.2.

A v h DBP 6027A 109 Revision 7.0 ODCM

F 5.2 LAND USE CENSUS TO SUPPORT REALISTIC DOSE ASSESSMENT The Land Use Census (LUC) provides data needed to support the special dose analyses of Section 4.0. Activities inside the SITE BOUNDARY should be periodically reviewed for dose assessment as required by Section 4.1.

Assessment of realisti- ioses to MEMBERS OF THE PUBLIC is required by Section 4.0 for demonstrating compliance with the EPA Environmental Dose Standard, 40 CFR 190 (Section 4.2).

To support these dose assessments, the LUC shall include (a) areas within the SITE BOUNDARY that are accessible to the publics and (b) use of Lake Erie water on and near the site. The scope of the LUC shall include the following:

Assessment of areas onsite that are accessible to MEMBERS OF THE PUBLIC. Particular attention should be give to assessing exposure times for visits to the Davis-Besse Administration Building. 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.

O t

O DBP 6027A 120 Revision 7.0 ODCM

6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM !

The Radiological Environmental Monitoring Program (REMP) provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the higher potential radiation exposures of individuals resulting from the station operations.

i The sampling and analysis program described in this Section was developed l to provide epresentative measurements of radiation and radioactive l materials resulting from station operation in the principal pathways of f exposure of MEMBERS OF THE PUBLIC. This monitoring program implements I 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 of radioactive materials and levels of radiation are not I l higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for the i

development of this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring.

6.1 PROGRAM DESCRIPTION l

6.1,1 General l i

The REMP shall be conducted as specified in Table 6-1. This table describes the minimum environmental media to be sampled, the sample collection frequencies, the number of representative samples required, the characteristics of the sampling locations, and the type and frequency of sample analysis. Table 6-2 provides a detailed listing of the sample locations for Davis-Besse which satisfy the requirements of Table 6-1. Maps for each site listed in Table 6-2 are contained in Appendix C. The specific locations used to satisfy the requirements of Table 6-1 may be changed as deemed appropriate by ;

the Radiation Protection Manager. The changes shall be reported in

{

the Annual Radiological Environmental Operating Report and the i Radiological Effluent Release Report as required by Sections 7.1 and f 7.2, respectively. If the changes are to be permanent, Table 6-2 and Appendix C shall be updated.

Note: For the purpose of implementing Section 5.1, sampling locations will be modilled, to reflect the findings of the land use census as described in ODCM Section 5.1.

6.1.2 Program Deviations With the REMP not being conducted as specified in Table 6-1, in lieu of a Licensee Event Report, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Section 7.1, a description of the reasons for not conducting the program as required and plans for preventing a recurrence.

O DBP 6027A 111 Revision 7.0 ODCM

I I

i Unavailability of Milk or Broad Leaf Vegetation Samples !

' 6.1.3

./"'}

kss/ With milk or fresh leafy vegetable samples unavailable from one or ,

more of the sample locations required by Table 6-1, identify i locations for obtaining replacement samples and if practical add them to the REMP within 30 days. The locations from which samples were unavailable may then be deleted from the monitoring program. In lieu' i 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 Unavailability, Equipment 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 samnling period. All deviations !

from the sampling schedule will be documented in the Annual Radiological Environmental Operating report pursuant to Section 7.1. ;

6.1.5 Sample Analysis REMP samples shall be analyzed pursuant to the requirements of Table 6-1 and the detection capabilities required by Table 6-3. Cumulative i potential dose contributions for the current calendar year from radionuclides detected in environmental samples shall be determined in accordance with the methodology and parameters in this ODCM.

6.2 REPORTING LEVELS 6.2.1 General e

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 consumptica rates of NRC Regulatory Guide 1.109. ,

The evaluation of potential doses should be based solely on t radioactive material resulting from plant operation.

i i

)

DBP 6027A 112 Revision 7.0 ODCM I

6.2.2 Exceedance of Reporting Levels With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 6-4 when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Section 7.3, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to MEMBER OF THE PUBLIC is less than the calendar year limits of Sections 2.4.1, 3.7.1 and 3.8.1. When more than one of the radionuclides in Table 6-3 are detected in the sampling medium, this report shall be submitted ift concentration (1) + concentration (2) + ...> 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 potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar yiar limits of Sections 2.4.1, 3.7.1 and '

3.8.1. The method described ie ection 4.2.3 may be used for assessing the potential dost <

. required reporting for radionuclides other than those listed in ..te 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 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 Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices ara performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 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.

O DBP 6027A 113 Revision 7.0 ODCM N

g No&M r of Representative Exposure Pathway Samples and Sam Collection Type and Frequency and/or Sample Locations

ple Frequency of Analysis 5 1. DIRECT RADIATION 27 routine monitoring Quarterly Camma dose quarterly stations either with two or more dosimeters or with one instrument for measur-ing and recording dose rate continuously, placed as follows:

h 5

o an inner ring of stations, generally one in each y meteorological sector in t' the general area of the SITE BOUNDARY; }

s E .4 an outer ring of stations, one in each meteo c;1ogical 4

,p 7 sector in the 6- to a- km y, range from the site, t4 excluding the sectors over g Lake Erie; 3

the balance of the stations 5 to be placed in special 5

interest areas such as ms population centers, nearby @

residences, schools, and in

1 or 2 areas to serve as h control stations.

OE 91 8

O e _ __ -. _ _-- .

e --. . _- -. -- -_ -- __

G.

o o-a E Number of Representative Exposure Pathway Samples and Sample Collection Type and Frequency w

and/or Sample Loca t ion s*- Frequency of Analysis 5 2. AIRBORNE Radiciodine and Samples from 5 locations, Continuous Radiolodine Particulates placed as follows: sampler opera- Canister: I-131 tion with sample analysis weekly. g 3 samples from close to the collection weekly. Particulate Sampler: g SITE BOUNDARY. in different or more frequent cross beta radio- @

eactore generally from if required by activity analysis 8 areas of higher calculated dust loading. followin M annual average groundlevel changes Casuna

g filter @

D/Q. isotopic analysis of mg composite (by 5$

location 4 quarterly. y*

1 sample from the vicinity- O7 of a nearby community, h" generally in the area of 53 higher calculated annual @8 average groundlevel D/Q. g[

OE 1 sample from a control y&

location. 15-30 km from S*

the site. y o

3. WATERBORNE g O

a. Surface 2 samples Weekly composite Tritium gnd ganana g l (untreated water) sample (Indicator isotopic analysis 3 l location should of composite sample o: o 'be a composite) monthly.

! 8I d

E b. Ground Sample f rom one source Quarterly Casuna Isotopie and

! o only if likely to be tritium analysis l # affected* quarterly.

I w O

l

e

. Number of Representative Exposure Pathway Samples and Sample Collection 8 and/or Sample Loc a t ion s *-

Type and Frequency Frequency of Analysis D

> c. Drinking i sample from the nearest Weekly composite Gross beta on monthly (Treated water) source. sample. composite. Tritium 1 sample from a control and gamma isotopic location.

analysis on quarterly composite. I-131 analysis on each com- {

s posite when the dose @

calculated for the 8 consumption of the 5 water is greater than $

1 mres per year. e. ;?

d. Sed iawnt from I sample from area with Semiannually EE Shoreline existing or potential Casuna isgtopic M**

analysis semi-recreational value, annually. %@ "

U

4. INCESTION En to

a. Milk If available, samples from Semimonthly when Gasuna isotopicd and 3

animals up to 2 locations animals are on

@E within 8 km distance having I-131 analysis semi- Q1 pasture, monthly monthly when animals @*

the highest dose potential. at other times are on pasture; E monthly at other O times. @

1 sample from milking o animals at a control g location 15-30 km distant gg and generally in a less o< prevalent wind direction.

2 ,-

o a

O

=

'N .

E Number of Representative Exposure Pathway Samples and S Collection Type and Frequency.

[

o and/or Sample Locations p le Frequenc L of Analysis

b. Fish 1 sample each of 2 commerc- 1 sample in Casma isgtopic ially and/or recreationally season. analysis on edible important species in portions.

vicinity of site.

I sample of same species in areas not influenced by .%

plant discharge. o i

Samples of up to 3 different Monthly when Casana isotopic anil c Food Products (Broad test kinds of broad leaf vegeta- available 1-131 analysis. "e veget a t. ion) tion growth in two dit ferent E Ir of f site locations of higher NE predicted annual average 5m ground-level DlQ if milk sampling is not performed.

lE gg

~

po l 1 sample of each of the Monthly when Gaasna isotopic and S similar broad leaf vegeta- available. 1-131 analysis. 6E 65

+

tions grown 15-30 km distant in a less prevalent wind o3 direction if milk sampling is not performed. o E

8 5~

oM 8*

o

= ;

. .- ,-- -~-~, . -, . ~ - - . . - . -- , , - . - - - - , - , , . ~

n.- n.-.. -- . . . - .~, -----,..--.- ,,,- ~ ,~ - - - - . - - - , - - - - - - - . - - - - - - - - - - - - - .

Table 6-1 (Continued)

TABLE NOTATION

' Specific parameters of distance and direction sector from the centerline of the reactor, and additional description (where pertinent) are provided for each and every sample location in Table 6-2. Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",

October 1978, and to Radiological Assessment Branch Technical Position, Revision 1 November 1979. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program. In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.11 and Section 7.2, identify the cause of the unavailability of samples for that pathway and identify the new locations (s) for obtaining replacement samples in the next Semiannual Effluent and Waste Disposal Report. Also, include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

One 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.

C Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater i

than ten times the yearly mean of control samples, then gamma isotopic analysis l shall be performed on the individual samples, d

Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the facility.

i ' Groundwater samples shall be taken when this source is tapped for drinking or l

' 1rrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

O DBP 6027A 118 Revision 7.0 ODCM

Table 6-2 Required Sampling Locations Appendix C Type of Location Page Reference Location

Location Description T-1 C-4 I Site boundary, 0.6 mile ENE of Station.

T-2 C-5 I Site boundary. 0.9 mile E of Station.

T-3 C-6 I Site boundary, 1.4 miles ESE of Station near mouth of Toussaint River.

T-4 C-7 I Site boundary, 0.8 mile S of Station.

T-5 C-8 I Main entrance to site, 0.5 mile W of Station.

T-6 C-9 I Site boundary 0.5 mile NNE of Station.

T-7A & B C-10 I Sand Beach. 0.9 mile NW of Station.

T-8 C-11 I Farm. 2.7 miles VSW of Station.

T-9 C-12 C Oak Harbor substation, 6.8 miles SW of Station.

T-10 C-13 I Site boundary, 0.5 mile SSW of Station.

T-11 C-14 C Port Clinton Water Treatment plant, 9.5 miles SE of Station.

T-12 C-15 C Toledo Water Treatment Plant, 23.5 miles WNW of Station. Water samples are collected 11.3 miles NW of site.

T-17 C-16 I Site boundary, 0.7 mile SW l of Station I ndicator locations C Control locations DBP 6027A 119 Revision 7.0 ODCM

~ ,

h qs Table 6-2 (Continued) s' Required Sampling Locations ;

i Appendix C Type of Location Page Reference Location

Location Description T.19 C.17 I Farm, 0.6 miles W of Station l T-25 C.18 I Farm, 3.7 miles S of ;

Station. ;

T-27 C.19 C Crane Creek State Park, 5.3 ;

miles WNW of Station.

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. i 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 Site boundary, 0.7 mile SE

\ '

of Station.

T.41 C.25 I Site Beundary, 0.6 mile SSE of Station.

T.42 C.26 I Site boundary. 0.8 mile SW ;

of Station.

T-44 C.27 I Site boundary, 0.5 mile WSW ,

of Station. ,

T.46 C.28 I Site boundary. 0.5 mile NW .

of Station.

T.47 C.29 I Site boundary, 0.5 mile N of !

Station.

1 T.48 C.30 I Site boundary. 0.5 mile NE l of Station. _

T.50 C.31 1 Erie Industrial Park Water i Treatment Plant, 4.5 mile SE of Station.

I = Indicator locations; C = Control locations.

DBP 6027A 120 Revision 7.0 ODCM ,

r 1

1 Table 6-2 (Continued)

Required Sampling Locations e Appendix C Type of Location Page Reference Location

Location Description T-52 C-32 I Farm, 3.7 miles S of Station.

T-54 C-33 I Fa rm, 4.8 miles SW of Station.

T-55 C-34 I Farm, 5.0 miles W. of Station.

g T-67 C-35 I Site boundary, 0.3 mile NNW of Station.

T-68 C-36 I Site Boundary, 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.

f T-151 C-39 I State Route 2 and Humphrey Road,1.8 miles WIN of Station.

ndicator ocations C Contro ocations f

DBP 6027A 121 Revision 7.0 ODCM

~

l.

i The RERR shall include any radionuclide activity limits for the BWST and l PWST which have been exceeded during the reporting period, a description of the event leading to the limit being exceeded and action taken to return it to within the limits. '

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 l specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable

~

reference

a. dose or dose commitment exceedences to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (Section 2.4.1),

b. the discharge of radioactive liquid waste without treatment and in excess of the limits in Section 2, the calculated air dose from radioactive gases exceeding the

~

c.

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 gaaeous effluents exceeding the limits of Section 3.8.1

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 or gaseous effluents exceeding the limits of Section 4.2, and

g. the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 6-4 (Section 6.2.2).

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 contains

a. a summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59:

b. sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; DBP 6027A 128 Revision 7.0 ODCM

R '

-i

e .

l

$L c. a. detailed description of the equipment, components'and. ;

processes involved and the interfaces with other plant systems:- l

w. .

p d. an evaluation of the char.se which shows the predicted releases i- of radioactive materials.in liquid or gaseous effluents and/or i quantity of solid waste that differ from those previously j predicted in the license application and amendments thereto; :

I

e. an evaluation of the change which shows the expected' maximum i exposures to. individuals in the UNRESTRICTED AREA and the -i general population that differ from those previously estimated !

in the license application and amendments thereto; r

f. a comparison'of the predicted releases of radioactive materials in liquid and gaseous effluents to the actual releases for the ;

period prior to when the changes are to be made; a

g. an estimate of the exposure to plant operating personnel as a i result of the changes and [

h. documentation of the fact that the' change was reviewed and found ;

acceptable by the Station Review Board.

2. Shall become effective upon review and acceptance by the Station Review Board. ;

I 7.5 DEFINITIONS !

7.5.1 BATCH RELEASE - The discharge of liquid wastes of a discrete volume.

7.5.2 CHANNEL CALIBRATION - A CHANNEL CALIBRATION shall be the adjustment. l 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 CHANNEL FUNCTIONAL TEST. CHANNEL CALIBRATION.

may be performed by any series of sequential, overlapping or total ,

t channel steps such that the entire channel is calibrated.

7.5.3 CHANNEL CHECK - A CHANNEL CHECK shall be the qualitative assessraent of channel behavior during operation by observation. Thir ;

determination shall include, where possible, comparison of the ;

channel indication and/or status with other indications and/or status ,

derived from independent instrument channels monitoring the same parameter, q 7.5.4 CHANNEL FUNCTIONAL TEST - A CHANNEL FUNCTIONAL TEST shall be ,j I

a. Analog Channels - The injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPEFABILITY including alarm and/or trip functions.

I i

i l

DBP 6027A 129 Revision 7.0 j ODCM

{

o Airborne Particulate E

, Water or Gas Hsh 6 8 Analysis (pCift) 3 Food Producu Sehnt (pC1/m ) (pCifkg. wet) (pCi/1) (pCi f k g. wet) (pCifkg, day 1 Gross Beta 4 1.0E-02 H 2000**

i Hn 15 130 Fe 30 260 t

o Co 15 130 Zn 30 260 C "Z r 3 15 $

' om 1 1 7.0E-02 1 60 b oe Cs 15(10 ),18 6.0E-02 130 15 60' 150

[

l Ba 15 15 l -2:

^

t-NOTE:

l This list does not mean that only these nuclides are to be detected and reported. Other t-

_c peaks which are measurable and identifiable, together with the above nuclides, shall be o identified and reported.

If no drinking water pathway exists, a value of 3000 pCi/L may be used, oE 91 l

O e .

9 9. .

,_ Table 6-3 (Continued)

, TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95Z probability (with 5Z 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),

sh is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E is the counting efficiency (counts per transformation),

V is the sample size (in units of mass or volume),

(

( ,/

_ 2.22 is the number of transfonmations per minute per picoeurie, t Y is the fractional radiochemical yield (when applicable), i A is the radioactive decay constant for the particular radionuclide, 6t is the elapsed time between end of the sample collection period and time of counting.

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

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

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence 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 following:

\~ / (1) HASL Procedures Manual, HASL-300 (revised annually).

DBP 6027A 123 Revision 7.0 ODCM

Table 6-3 (Continued)

TABLE NOTATION (2) Currie, L. A. . " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968).

(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques", Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

b. LLD for drinking water.

c. If no drinking water pathway exists, a value of 3000 pC1/11ter may be used.

d. LLD only when specific analysis for I-131 required.

O O

DBP 6027A 124 Revision 7.0 ,

ODCM l

i

ts en Reporting Levels

$ E Airborne Particulate $

Water or Gas Hsh HM Vegetables Analysis (pCi/L) (pCi/st3) (pCifkg. wet) (pCi/1) (pCifkg, wet) 2 O

11 - 3 2.0E+04* E til Hn-54 1.0E+03 3.0E+04 E m

Fe-59 4.0E+02 1.0E+04 S Co-58 1.0E+03 3.0E+04 h a

Co-bo 3.0E+02 1.0E+04 $

Y Zn-b5 3.0E+02 2.0Et04 Y

< H la.Nh-95 4.0E+02 o E-1-131 Oe h 2.0E+00 9.0E-01 3.0E+00 1.0E+02 O.

3.0E+01 Nd '

Cs-134 1.0E+01 1.0E+03 6.0E+01 1.0E+03 @

Y Cs-137 5.0E+01 2.0E+01 2.0E+03 7.0E+02 2.0E+03 Ba-La-140 2.0E+02 3.0E+02 E E

For drinking water samples, this is the 40 CFR 141 value. If no drinking water pathway y exists, a value of 30,000 pCilliter may be used. O O :s 2 x c-

+ un

.~ 7,,,

o tn

O O f O. .

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, as well as summarized and tabulated results of these analyses ar.d 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 missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following a summary description of the radiological environmental monitoring program; at least two legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program, required by Section 6.3 and discussions of all analyses in which the LLD required

, by Table 6-3 was not achievable.

7.2 RADIOACTIVE EFFLUENT RELEASE REPORT Radioactive Effluent Release Reports covering the operation of the unit during the previous 12 months of operation shall be submitted no later than 12 months from the submittal of the previous report. -

The Radioactive Effluent Release Reports (RERR) shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21 " Measuring.

Evaluating, and Reporting Radioact!vity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1. June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

O DBP 6027A 126 Revision 7.0 ODCM

I The RERR shall include an annual summary of hourly meteorological data

' '\ collected over the previous year. This annual summary may be either in-m, the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This.

same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the CITE BOUNDARY during the reporting period. '

All assumptions used in making these assessments, i.e., specific activity.

exposure time, and location, shall be included in these reports. The ,

assessment of radiation doses shall be performed in accordance with the '

methodology and parameters in this ODCM.

The RERR shall also include an assessment of radiation doses to the likely most exposed 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 '

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 r measurement or estimate), ;

d. source of waste and processing employed (e.g.,'dewatered spent resin, compressed dry waste, evaporator bottoms).

e. type of container (e.g.. Type A, Type 3, Large Quantity), and

+

f. solidification agent or absorbent (e.g. , cement, urea formaldehyde).

The RERR shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and !

11guld effluents made during the reporting period. .

The RERR shall include any changes made during the reporting period to the 7 PROCESS CONTROL PROGRAM (PCP) and to the ODCM, as well as a listing of new l locations for dose calculations and pursuant to Section 5.1.

DBP 6027A 127 Revision 7.0 ODCM ,

l l

b. Bistable Channels - The injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions.

1 7.5.5 COMPOSITE SAMPLE - A sample in which the method of sampling employed '

results in a specimen which is representative of the liquids released.

7.5.6 GASEOUS RADWASTE TREATMENT SYSTEM - The GASEOUS RADWASTE TREATMENT SYSTEM is a system that is designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases and providing for decay 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 52 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(-hat) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume);

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute);

E is the counting efficiency (as counts per transformations);

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; and 6t 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 an a posteriori (after the fact) limit..for a particular measurement.

DBP 6027A 130 Revision 7.0 ODCM

,_, 7.5.0 MEMBER OF THE PUBLIC - Member (s) of the public shall include all

/

) persons who are not occupationally associated with the plant. This K/ 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, occupational, or other purposes not associated with the plant.

7.5.9 OPERABLE - OPERABILITY - A system, subsystem, train, component or device shall be operable or have operability when it is capable of performing its specified 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 SITE BOUNDARY - The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

/m \

7.5.12 SOURCE CHECK - A SOURCE CHECK shall bc the observation of channel k-s upscale response when the channel sensor is exposed to a radioactive or LED source.

7.5.13 UNRESTRICTED AREA - An unrestricted area shall be any area at or beyond the SITE 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 SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. Thn 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 SITE BOUNDARY, is utilized in the Technical Specifications and the ODCM to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable, pursuant to 10 CFR 50.36a.

7.5.14 VENTILATION EXHAUST TREATMENT SYSTEM - A VENTILATION EXHAUST TREATMENT SYSTEM is a system that is designed and installed t reduce radioactive material in particulate form in effluents by pass mr ,

ventilation or vent exhaust gases through HEPA filters for the l purpose of removing particulates from the gaseous exhaust stream prior to release to the environment. Engineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be VENTILATION 7-_

EXHAUST TREATMENT SYSTEM components. 1 (Q

3 DBP 5027A 131 Revision 7.0 ODCM

7.5.15 VENTING - VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

O i O DBP 6027A 132 Revision 7.0 OCOM l

l O

APPENDIX A Technical Basis for Simplified Dose Calculations Liquid Effluent Releases O

, I l

i i

i I

l DBP 6027A A-1 Revision 7.0 ei ODCM

\

k

\

APPENDIX A

/}

-(,,/

Technical Basis for Simplified Dose Calculations Liquid Effluent Releases Overview ,

t 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 r 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 l 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 conse rvative .

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 nuclear i 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 pC1/ml. Cs-134 is a prevalent radionuclide in the liquid effluents from Davis-Besse. Therefore, it 2 is recommended that the Cs-134 liver dose conversion factor be used for the simplified maximum organ dose assessment. !

t

[

O DBP 6027A A-2 Revision 7.0 ODCM

Simplified Method 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 D "

tb '~ '

DF

Z where:

D = dose to the total body (mrem) tb VOL = volume of liquid effluents released (gal) )

DF = average Collection Box release flow (gal / min) 2 = 10, near field dilution A(Cs-134,tb) =

5.81E+05 mrem /hr per pC1/m1, the total body ingestion dose factor for Cs-134 ]

EC g = total concentratio- of all radionuclides (pCi/ml) 1.67E-02 =

1 hr/60 min l

Substituting the values for Z and the Cs-134 total body dose conversien factor, f the equation simplifies to: 1 9.70 E+02

VOL Dg =

EC g (A-2)

Maximum Organ 1.67E-02

VOL max ' '

DF

Z wh*re !

D = maximum organ dose (mrem)

A(Cs-134,11ver) = 7.11E+05 mrem /hr per pCi/ml, the liver ingestion dose factor for Cs-134 DBP 6027A A-3 Revision 7.0 O

ODCM

I l

l

,-- Substituting the values for Z and the Cs-134 liver dose conversion factor, the (b equation simplifies tor

\

1.19 E+03

VOL D,, =

EC g (A-4)

Tritium should not be included in the simplified analysia 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.

A

~-

G V

DBP 6027A A-4 Revision 7.0 ODCH l

.i O

l l

l APPENDIX B

Technical Basis for Effective Dose Factors l Gaseous Radwaste Effluents e

i DBP 6027A B-1 Revision 7.0 O

ODCM

1 i

- l l

t APPENDIX B !

Technical Basis for Effective Dose Factors ;

N- Gaseous Radwaste Effluents ;

9' l l

Overview {

l Dose evaluations for releases of gaseous radioactive effluents may be j 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 l environment; i.e., the total body, gamma-air, and beta-air doses. The i 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 i 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 = E( Kg *fg) (B-1) wheres ;

K df

= the ef fective total body dose f actor due to gama minion f rom ;

all noble gases released (mremlyr per pCi/m3 ), j i

Kg = the total body dose f actor due to gansna emissions f rom each a noble gas raMonclide g released, from Table 3-5 (mremlyr per !

3 '

pCi/m ), and f = the fractional abundance of noble gas radionuclide g relative to !

the total noble gas activity. ;

(L + 1.1 M)df " I(Li + 1'1Hi )

1) (B-2) {

where:

(L+1.1M),ff = the effective skin dose factor due to beta and gamma emissjonsfromallnoblegasesreleased(mrem /yrper i pCi/m ), and !

(Lg+1.1Mg ) = the skin dose factor due to beta and gama emissions from f eachnoblegasradjonuclide g released, from Table 3-5 (mremlyr per pCi/m ).

M ,gg = U Mg *f) g (B-3) {

i l

l l

1 DBP 6027A B-2 Revision 7.0 ODCM

where:

H,ff =

the effective air dose factor due to gap a emissions from all '

noble gases released (mrad /yr per pC1/m ), and Hg =

the air dose factor due to gamma emissions from each noble gas radionuclide g released, from Table 3-5 (mradlyr per pCi/m3 .

N eff = E(N g *f)g (B-O where:

N =

theeffectiveairdosefactorduetobegaemissionsfromall noble gases released (mradlyr per pC1/m ), and Ng =

the air dose factor due to beta emissions from each noble gas radionuclide g released, from Table 3-5 (mradlyr per pCi/m ).

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 site boundary (summarized in Table B-1) has been used as the initial typical distribution.

distribution are presented in Table The B-2.effective dose factors derived from this 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 actual doses in the environment.

/or evaluating compliance with the dose limits of Technical Specification 3.11.2.2 the following simplified equations may be used:

D7 = 2.0

3.17E-08

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3 y/Q = atmospheric dispersion to the controlling site boundary (sec/m ), l M,gg = 5.7E+02, effective gamma-air dose factor (mradlyr per pCi/m ),

i 3

N,gg = 1.lE+03, effective beta-air dose factor (mradlyr per pC1/m ),

Q = Cumulative release for all noble gas radionuclides (pC1),

3.17E-08 -= conversion factor (yr/sec), and l 2.0 = conservatism factor to account for the variability'in the effluent data. ,

E Combining the constants, the dose calculation equations simplify to:

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The effective dose factors are used for the purpose of facilitating the timely !

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i Table B-1 Default Noble Gas Radionuclide Distribution

of Gastous Effluents Fraction of Total (Ag / E Ag )

Containment Station Waste Gas Nuclide Vessel Purge Vent Decay 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 Xe-135m --

0.004 0.0034 0.06 Xe-135 0.002 0.02 0.02 0.021 Total 1.0 1.0 1.0 1.0 0

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 f ractional abundance (i.e. , < 12) .

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b.' Table B-2

/3 Effective Dose Factors - Noble Gas Effluents I U I Total Body Skin Dose Gansna Air Beta Air f Dose Factor Factor Dose Factor Dose Factor i

Isotope Fractional K,ff (L+1.1M,ff) M,ff N,ff Abundance (mremfyrper (mremfyrper (mradfyrper (mradfyrper pCi/m ) pCi/m ) pC1/m ) pCi/m )

Ar 0.003 2.65E+01 3.87E+01 2.79E+01 9.84E+00 l 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 Xe-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 1 Xe-135m 0.06 1.87E+02 2.64E+02 2.02E+02 4.43E+01 l

~

Xe-135 0.02 3.62E+01 7.94E+02 4.03E+01 5.16E+01 ,

f TOTAL 1.0 4.98E+02 9.89E+02 5.69E+02 1.12E+03

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