ML20247A651
| ML20247A651 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/08/1997 |
| From: | DETROIT EDISON CO. |
| To: | |
| Shared Package | |
| ML20247A621 | List: |
| References | |
| PROC-971208, NUDOCS 9805060195 | |
| Download: ML20247A651 (197) | |
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Nuclear Production - Fermi 2 ODCM-0.0 L
Offsite Dose Calculation Manual Revision 11 Page 0.0-1 J
DETROIT EDISON - FERMI 2 OFFSITE DOSE CALCULATION MANUAL l
i implementation Plan
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These revisions go into effect upon approval.
l Current Revision Status by Section Section Number Revision Number Approval Date 1
0.0 11 11/25/97 1.0 6
12/12/95 2.0 6
12/12/95 3.0 10 12/12/95 4.0 7
12/12/95 5.0 7
11/25/97 6.0 7
12/12/95 7.0 8
12/12/95 l
8.0 6
12/12/95 l
9.0 6
12/12/95 10.0 7
12/12/95 Appendix A 5
12/12/95 Appendix B 5
12/12/95 l
Information and Procedures DSN Revision Change #
DTC File #
TRM VOL ll 11 97-145-ODM TMTRM 1754 IP Code Date Approved Released By Date Recipient I
11/25/97 A/A
/2-$-97 dA g5060195980430 R
ADOCK 05000341 PDR L ________ -
ODCM-O'.0 Revision 11 Page 0.0-2 TABLE OF CONTENTS
__ Pace Section 1.0-1
1.0 INTRODUCTION
1 PART I - RADIOLOGICAL EFFLUENT CONTROLS 2.0-2 2.0 DEFINITIONS 3.0-1 3.0 CONTROLS AND SURVEILLANCE REQUIREMENTS 3.0-2 3/4.0 Controls and Surveillance Requirements Applicability 3.0-4 3/4.3.7.11 Radioactive Liquid Effluent Monitoring instrumentation 3.0-10 3/4.3.7.12 RrCoactive Gaseous Effluent Monitoring instrumentation l
3.0-17 3/4.11.1.1 Liquid Effluents Concentration
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3.0-21 3/4.11.1.2 Liquid Effluents Dose l
3.0-22 3/4.11.1.3 Liquid Waste Treatment 3.0-23 3/4.11.2.1 Gaseous Effluents Dose Rate l
3.0-27 3/4.11.2.2 Gaseous Effluents Dose - Noble Gases 3.0-28 3/4.11.2.3 Gaseous Effluents Dose - lodine-131, lodine-133, i
Tritium, and Radionuclides in Particulate Form l
3.0-29 3/4.11.2.4 Offgas Treatment System 3.0-30 3/4.11.2.5 Ventilation Exhaust Treatment System 3.0-31 3/4.11.2.8 Venting or Purging 3.0-32 3/4.11.4 Radioactive Effluents Total Dose 3.0-33 3/4.12.1 Radiological Environmental Monitoring Program 3.0-44 3/4.12.2 Land Use Census 3.0-45 3/4.12.3 Interlaboratory Comparison Program 4.0-1 4.0 BASES 5.0-1 5.0 ADMINISTRATIVE CONTROLS 5.0-2 5.9.1.7 Annual Radiological Environmental Operating Report l
5.0-2 5.9.1.8 Annual Radioactive Effluent Release Report i
5.0-4 5.15 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems o
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ODCM-0.0 Revision 11 Page 0.0-3 l
TABLE OF CONTENTS (continued) l l
Pace Section l
PART 11-CALCULATIONAL METHODS 6.0-2 6.0 LIQUID EFFLUENTS 6.0-2 6.1 Radiation Monitoring instrumentation and Controls 6.0-2 6.1.1 Offsite Dose Calculation Manual (ODCM) 3.3.7.11 Requirement 6.0-3 6.1.2 Non-ODCM Required Monitor 6.0-4 6.2 Sampling and Analysis of Liquid Effluents 1
6.0-4 6.2.1
' BATCH Releases I
6.0-5 6.2.2 CONTINUOUS Releases 6.0-5 6.3 Liquid Effluent Monitor Setpoints 6.0-6 6.3.1 Tank Effluent Line Monitors 6.0-9 6.3.2 Circulating Water Reservoir Decant Line Radiation Monitor (D11-N402)
L 6.0-10 6.3.3 Generic, Conservative Alarm Setpoint for D11-N402 6.0-11 6.3.4 Alarm Setpoint for GSW and RHR System Radiation Monitors 6.0-11 6.3.5 Alarm Response - Evaluating Actual Release Conditions l
6.0-12 6.3.6 Liquid Radwaste Setpoint Determination With Contaminated Circulating Water Reservoir 6.0-13 6.4 Contaminated GSW or RHR System - Quantifying and Controlling Releases I
6.0-14 6.5 Liquid Effluent Dose Calculation - 10 CFR 50 6.0-14 6.5.1 MEMBER OF THE PUBLIC Dose - Liquid Effluents i
l 6.0-16 6.5.2 Simplified Liquid Effluent Dose Calculation 6.0-17 6.5.3 Contaminated CWR System - Dose Calculation 6.0-18 6.6 Liquid Effluent Dose Projections l
l 7.0-1 7.0 GASEOUS EFFLUENTS l
7.0-1 7.1 Radiation Monitoring instrumentation and Controls 7.0-1 7.1.1 Effluent Monitoring - Ventilation System Releases 7.0-1 7.1.2 Main Condenser Offgas Monitoring 7.0-2 7.1.3 Reactor Building Ventilation Monitors (Gulf Atomic)
ODCM-0.0 Revision 11 Page 0.0-4 TABLE OF CONTENTS (continued)
Pace Section 7.0-2 7.2 Sampling and Analysis of Gaseous Effluents 7.0 2 7.2.1 Containment PURGE 7.0-3 7.2.2 Ven*jiation System Releases 7.0-4 7.3 Gaseous Effluent Monitor Setpoint Determination i
I 7.0-4 7.3.1 Ventilation System Monitors 7.0-6 7.3.2 Setpoint Determination with No Nuclides Detected 7.0-6 7.3.3 Gaseous Effluent Alarm Response - Evaluating Actual Release Conditions 7.0-7 7.4 Primary Containment VENTING and PURGING 7.0-7 7.4.1 Release Rate Evaluation 7.0-8 7.4.2 Alarm Setpoint Evaluation 7.0 9 7.5 Quantifying Releases - Noble Gases 7.0-9 7.5.1 Sampling Protocol 7.0-10 7.5.2 Release Concentration Determination for Reactor Building Exhaust Plenum 7.010 7.5.3 Calculation of Activity Released 7.0-11 7.6 Site Boundary Dose Rate - Radiolodine and Particulate 7.0-12 7.7 Noble Gas Effluent Dose Calculations - 10 CFR 50 7.0-12 7.7.1 UNRESTRICTED AREA Dose - Noble Gases 7.0-13 7.7.2 Simplified Dose Calculation for Noble Gases 7.0-13 7.8 Radiolodine and Particulate Dose Calculations - 10 CFR 50 7.0-13 7.8.1 UNRESTRICTED AREA Dose - Radiolodine, Particulate, and Tritium 7.0-15 7.8.2 Simplified Dose Calculation for Radiolodines and Particulate 7.0-16 7.9 Gaseous Effluent Dose Projection
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7.0-17 7.10 Waste Oil incineration b.
3 8.0 SPECIAL DOSE ANALYSES 8.0-1 8.1 Doses Due to Activities inside the SITE BOUNDARY 8.0-1 8.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 t
8.0-2 8.2.1 Effluent Dose Calculations 8.0-3 8.2.2 Direct Exposure Dose Determination 8.0-4 8.2.3 Dose Assessment Based on Radiological Environmental Monitoring Data
ODCM-0.0 Revision 11 Page 0.0-5 TABLE OF CONTENTS (continued)
Pace Section l
9.0-1
9.0 ASSESSMENT
OF LAND USE CENSUS DATA l
9.0-1 9.1 Land Use Census as Required by ODCM 3.12.2 I
9.0-3 9.2 Land Use Census to Support Realistic Dose Assessment I
10.0-1 10.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 10.0-1 10.1 Sampling Locations 10.0-1 10.2 Reporting Levels
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10.0-2 10.3 Interlaboratory Comparison Program I
APPENDICES i
A-1 A
Technical Basis for Effective Dose Factors Liquid Effluent Releases B-1 B
Technical Basis for Effective Dose Factors Gaseous Radwaste Effluents TABLES 2.0-7 2.1 Surveillance Frequency Notation 2.0-8 2.2 Operational Conditions 3.0-5 3.3.7.11-1 Radioactive Liquid Effluent Monitoring Instrumentation 3.0-8 4.3.7.11-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements
..3.0-11 3.3.7.12-1 Radioactive Gaseous Effluent Monitoring instrumentation 3.0-14 4.3.7.12-1 Radioactive Gaseous Effluent Monitoring i
instrumentation Surveillance Requirements 3.0-18 4.11.1.1.1-1 Radioactive Liquid Waste Sampling and Analysis Program 3.G-24 4.11.2.1.2-1 Radioactive Gaseous Waste Sampling and analysis Program l
3.0-35 3.12.1-1 Radiological Environmental Monitoring Program 3.0-40 3.12.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3.0-41 4.12.1-1 Detection Capabilities for Environmental Sample Analysis
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l ODCM-0.0 Revision 11 l
Page 0.0-6 l
I TABLE OF CONTENTS (continued)
Pace Section
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6.0-20 6.0-1 Fermi 2 Site Specific Liquid Ingestion Dose Commitment Factors, Alo l
6.0-22 6.0-2 Bioaccumulation Factors (BFi) l 7.0-18 7.0-1 Values for Evaluating Gaseous Release Rates and Alarm Setpoints 7.0-19 7.0-2 Dose Factors for Noble Gases 7.0-20 7.0-3 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations 7.0-21 7.0-4 Gaseous Effluent Pathway Dose Commitment Factors 8.0-7 8.0-1 Assumptions for Assessing Doses Due to Activities inside SITE BOUNDARY 8.0-8 8.0 2 Recommended Exposure Rates la Lieu of Site Specific Data 10.0-3 10.0-1 Radiological Environmenbi Monitoring Program, Fermi 2 Gample Locs%ns and Associated Media 10.0-15 10.0-2 Radiological Environmental Monitoring Program, Fermi 1 Sample Locations and Associated Media A-4 A-1 Relative Dose Significance of Radionuclides in Liquid Effluents l
B-4 B-1 Effective Dose Factors - Noble Gas Effluents FIGURES 1
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3.0-46 3.0-1 Map Defining Unrestricted Areas and Site Boundary l
for Radioactive Gaseous and Liquid Effluents 6.0-23 6.0-1 Liquid Radioactive Effluent Monitoring and Processing Diagram 7.0-51 7.0-1 Gaseous Radioactive Effluent Monitoring and Ventilation Systems Diagram 10.0-17 10.0-1 Radiological Environmental Monitoring Program Sampling Locations - Site Area 10.0-18 10.0-2 Radiological Environmental Monitoring Program Sampling Locations - Greater than 10 Miles 10.0-19 10.0-3 Radiological Environmental Monitoring Program Sampling Locations - within 10 Miles 10.0-20 10.0-4 Radiological Environmental Monitoring Program Sampling Locations - Site Area (Lake Erie side) 10.0-21 10.0-5 Fermi 1 Sampling Locations END OF SECTION 0.0 l
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FERMI 2 - TECHNICAL REQUIREMENTS MANUAL l
VOLUME 11 LIST OF EFFECTIVE PAGES I
l OFFSITE DO' E CALCULATION MANUAL S
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l Nuclear Production - Ferm'l 2 ODCM-1.0 Offsite Dose Calculation Manual Revision 6 Page 1.01 l
INTRODUCTION l
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1.0 INTRODUCTION
Part I of the Fermi 2 Offsite Dose Calculation Manual (ODCM), which includes Sections 2.0 through 5.0, contains the controls and surveillance requirements for radioactive effluents and radiological environmental monitoring. It also contains requirements for the Annual Radiological Environmental l
Operating Report and the Annual Radioactive Effluent Release Report.
Part il of the ODCU describes the methodology and parameters used in a) determining radioactive material release rates and cumulative releases, b) calculating radioactive liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints, and c) calculating the
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corresponding dose rates and cumulative quarterly and yearly doses. Calculational methods different from those provided in the ODCM may be used only if they lead to more conservative results than would be obtained using ODCM methods. ODCM data for dispersion factors, receptor locations, exposure pathways, ventilation flow rates, etc. are intended to lead to conservative results. However, it is permissible to use plant procedures which implement the ODCM and which contain different data due to changes in environmental and plant conditions.
The methodology provided in Part 11 of this manualis acceptable for use in demonstrating compliance with the dose limits for members of the public of 10 CFR 20, the cumulative dose criteria of 10 CFR 50, Appendix I and 40 CFR 190, and the controls in Part I of this manual.
Part 11, Section 6.0 of the ODCM describes equipment for monitoring and controlling liquid effluents, sampling requirements, and dose evaluation methods. Section 7.0 provides similar information on gaseous effluent controls, sampling, and dose evaluation. Section 8.0 describes special dose analyses required for compliance with Fermi 2 Offsite Dose Calculation Manual and 40 CFR 190.
Section 9.0 describes the role of the annualland use census in identifying the controlling pathways and locations of exposure for assessing potential off-site doses. Section 10.0 describes the Radiological Environmental Monitoring Program.
The ODCM will be maintained at Fermi 2 for use as a listing of radiological effluent controls and surveillance requirements, as well as a reference guide and training document for accepted methodologies and calculations. Changes to the ODCM calculational methodologies and pmameters will be made as necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50.36a and Appendix l for demonstrating that radioactive effluents are "As Low As Reasonably Achievable."
NOTE: Throughout this document words appearing all capitalized denote either definitions specified in the Fermi 2 Controls or common acronyms.
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END OF SECTION 1.0 l
Nuclear Production - Fermi 2 ODCM-2.0 Offsite Dose Calculation Manual Page 2.0-1 PARTI RADIOLOGICAL EFFLUENT CONTROLO I
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Nuclear Production - Fermi 2 ODCM-2.0 Offsite Dose Calculation Manual Revision 6 Page 2.0-2 t
t SECTION 2.0 DEFINITIONS l
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1 ODCM 2.0 Revision 6 Page 2.0-3 2.0 ' DEFINITIONS j
ACTION 2.1 ACTION shall be that part of a specification which prescribes remedial measures required i
under designated conditions.
CHANNEL CALIBRATION 2.4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the 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 fEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channet steps such that the entire channel is calibrated. Calibration of instrument channels with resistance temperature detectors (RTD) or thermocouple sensors shall consist of verification of operability of the sensing element and adjustment, as necessary, of the remaining adjustable devices in the channel.
CH ANNEL CHECK 2.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shallinclude, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measunng the same parameter.
CHANNEL FUNCTIONAL TEST 2.6 A CHANNEL FUNCTIONAL TEST shall be:
a.
Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions j
and channel failure trips.
j b.
Bistable channels - the injection of a simulated signalinto the sensor to verify OPERABILITY including alarm and/or inp functions.
Tha CHANNEL FUNCTIONAL TEST may be performed by any sequential, overlapping, or total channel steps such that the entire channelis tested.
DOSE EQUIVALENT l-131 2.9 DOSE EQUIVALENT l-131 shall be that concentration of I-131, microcuries per gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1132,1133,1-134, and 1135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table ll1 of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites.'
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l ODCM-2.0 Revision 6 Page 2.0-4 l
2.0 DEFINITIONS 1
FREQUENCY NOTATION 2.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 2.1.
MEMBER (S) OF THE PUBLIC 2.21 MEMBER (S) OF THE PUBLIC means any individual except when that individual is receiving an occupational dose.
OCCUPATIONAL DOSE l
2.22 Occupational Dose means the dose receitad by an individualin the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licer'see or other person. Occupational dose does not include dose received from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the general public.
I OFF-G AS TRE ATMENT SYSTEM 2.23 An OFF-GAS TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system offgases from the reactor coolant and providing for delay or holdup for the purpose of reducing the total radioactiv'ty prior to release to the environment.
OFFSITE DOSE CALCULATIONAL MANUAL 2.24 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the radiological environmental monitoring program. The ODCM shall Aso contain (1) the Radiological Effluent Controls and Radiological Environmental Monitonng Program Controls required by Technical Specification 6.8.5, and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Reports required by Controls 5.9.1.7 and 5.9.1.8.
OPER ABLE - OPER ABILITY 2.25 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation. controls, electrical power, cooling or seal water, lubrication or other auxilliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
OPER ATION AL CONDITION - CONDITION 2.26 An OPERATIONAL CONDITION, i.e. CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 2.2.
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ODCM 2.0 Revision 6 Page 2.0 5 2.0 DEFINITIONS PUBLIC DOSE 2.27 Public Dose means the dose received by a member of the public from exposure to radiation and/or radioactive material released by a licensee, or.to any other source of radiation under the control of a licensee. It does not include occupational dose or doses received from background radiation, as a patient from medical practices,~or from voluntary participation in medical research programs.
PURGE - PURGING 2.31 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humi6ty, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
RATED THERMAL POWER 2.32 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant equivalent to that stated in the Technical Specification definition of RATED THERMAL POWER.
REPORTABLE EVENT 2.34 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
SITE BOUNDARY 2.38 The SITE BOUNDARY shall be that litie beyond which the land is neither owned, nor l
leased, nor otherwise controlled. by the licensee.
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SOURCE CHECK 2.40 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
THERM AL POWER l
l 2.42 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor l
coolant.
UNRESTRICTED AREA 2.45 The Fermi 2 Energy Center UNRESTRICTED AREA includes all areas outside the site boundary.
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i ODCM-2.0 Revision 6
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Page 2.0-6 2.0 DEFINITIONS VENTILATION EXHAUST TREATMENT SYSTEM i
2.46 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and i
installed to reduce gaseous radioiodine or radioactive material in particulate form in l
effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulate from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atiaospheric cleanup systeme are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM l
I compor.ents.
VENTING 2.47 VENTING shall be 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.
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Nuclear Production - Fermi 2 ODCM 2.0 Offsite Dose Calculation Manual Revision 6 Page 2.0-7 TABLE 2.1 SURVEILLANCE FREQUENCY NOTATION l
l NOTATION FREQUENCY S
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
O At least once per 92 days.
SA At least once per 184 days.
A At least once per 366 days.
R At least once per 18 months (550 days).
S/U Prior to each reactor stariup.
P Prior to each radioactive release.
N.A.
Not applicable.
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Neelear Production - Fermi 2 ODCM-2.0 Orfsite Dose Calculation Manual Revision 6 l
Page 2.0-8 l
2.0 DEFINITIONS l
TABLE 2.2 OPERATIONAL CONDITIOlad MODE SWITCH AVERAGE REACTOR CONDITION POSITION COOLANT TEMPERATURE 1.
POWER OPERATION Run Any temperature 2.
STARTUP Startup/ Hot Standby Any ternperature 3.
HOT SHUTDOWN Shutdown #, ""
> 200 degrees F 4.
COLD SHUTDOWN Shutdown #. ##, *"
s 200 degrees F 5.
REFUELING-Shutdown or ref uel",#
s 140 degrees F The reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Refuel position to test the switch interlock functions and related instrumentation provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.
The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Technical Specification 3.9.10.1.
Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
See Special Test Exceptions 3.10.1 and 3.10.3 of Technical Specifications.
The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled or withdrawn provided that the one-rod-out interlock is OPERABLE.
END OF SECTION 2.0 i
Nuclear Production - Fermi 2 ODCM-3.0 Offsite Dose Calculation Manual Revision 10 Page 3.0-1 l
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l SECTION 3.0 CONTROLS AND SURVEILLANCE REQUIREMENTS l
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ODCM 3.0 l
Revision 10 i
Page 3.0-2 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS i
3/4.0 APPLICABILITY.
CONTROLS 3.0.1 Compliance with the succeeding Controls is required during the OPERATIONAL.
CONDITIONS or other conditions specified therein; except that upon failure to meet the control, the associated ACTION requirements shall be met.
3.0.2 Noncompliance with a Control shall exist when the requirements of the control and associated ACTION requirements are not met within the specified time intervals. If the Controlis restored prior to expiration of the specified time intervals, completion of the Action requirements is riot required.
3.0.3 When a Control is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an i
OPERATIONAL CONDITION in which the control does not apply by placing it, as applicable, in:
1.
At least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, i
2.
At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.
At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Control. Exceptions to these requirements are stated in the individual Controls.
This Control is not applicable in OPERATIONAL CONDITIONS 4 or 5.
3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made when the conditions for the Controls are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with the ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Controls.
t 1
i
ODCM 3.0 Revision 10 Page 3.0 3 APPLICABILITY SURVEILLANCE REQUIREMENTS I-4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS
)
j or other conditions specified for individual Controls unless otherwise stated in an l.
individual Surveillance Requirement.
{
l l?
.4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance i
interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
i.
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4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Surveillance 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Control. The time limits of the ACTION
- requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed l-for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to be performed on inoperable equipment.
'4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition j
shall not be made unless the Surveillance Requirement (s) associated with the Control have been periormed within the applicable surveillance interval or as otherwise specified. This provision shall not prevent pcssage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.
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ODCM 3.0 Revision 10 l.
Page 3.0-4 l
l INSTRUMENTATION 1
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.
1 CONTROLS 3.3.7.11 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of l
Control 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATIONAL MANUAL (ODCM).
APPLICABILITY:
At all times, except as noted for Condensate Storage Tank Discharge Monitor and Flow Rate Measurement Device.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control, immediately 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.
b.
With less than the minimum number of radioactive liquid effl'uent monitorir 1
)
instrumentation channels OPERABLE, take the ACTION shown in Table 3.17.11-1.
I Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in I
the next Annual Radioactive Effluent Release Report.
c.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive liquid 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 4.3.7.11 1.
4
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l-ODCM-3.0 Revision 10 Page 3.0-5 TABLE 3.3.7.11-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
- "I""* #""*I*
instrument Action Operable 1.
GROSS RADIOACTIVliY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Eifluent Line D11-N007 1
110 2.
GROSS RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF l
RELEASE a.
Circulating Water Reservoir Decant Line D11 N402 1
111 b.
Condensate Storage Tank Discharge Path (1) (2) 1 113 3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line G11 R703 1
112 b.
Circulating Water Reservoir Decant Line N71 R802 1
112 c.
Condensate Storage Tank Discharge Path (2) 1 112 l
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ODCM-3.0 Revision 10 Page 3.0-6 i
TABLE 3.3.7.11-1 (Continued)
TABLE NOTATIONS ACTION 110 -
With the number of channels OPERABLE lest Man required by the Minimum Channels OPERABLE requirement, effluent releases from this pathway may continue provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Surveillance Requirement 4.11.1.1.1, and b.
At least two technically qualified individuals independently verify the release rate calculatio.ns and discharge line valving (one technically qualified individual can be the preparer of the calculation, the other independently reviews the release rate calculations to verify accuracy);
Otherwise, suspend release of radioactive effluents via this pathway.
With the number of channels OPERABLE less than the Minimum Channels ACTION 111 OPERABLE requirement, radioactive effluent releases via this pathway may continue provided that grab samples are collected and analyzed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for gross radioactivity (beta or, gamma) at a lower limit of detection of at least 10-7 microcurielml, for Cs-137. Otherwise, suspend release of radioactive effluents via this pathway, if radioactive effluent releases are not in progress, i.e., if no Waste Sample Tank (or other tank containing radioactive liquid) is being released and the circulating water is not contaminated as shown by the most recent circulating water sample (s), this sampling requirement does not apply.
1 ACTION 112 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, radioactive effluent releases i
via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> dunng actual releases. Pump performance curves 1
generated in place may be used to estimate flow. Otherwise, suspend I
release of radioactive effluents via this pathway. If radioactive effluent releases are not in progress, i.e., if no Waste Sample Tank (or other tank l
containing radioactive liquid) is being released and the circulating water is not contaminated as shown by the most recent circulating water sample (s),
this requirement does not apply.
E-_-__
a
CDCM-3.0 Revision 10 Page 3.0-7 ACTION 113 -
Suspend release of radioactive effluents via this pathway Prior to initiating a release, a) at least two independent samples are (1) analyzed in accordance with Surveillance Requirement 4.11.1.1.1, b) the release rate calculations are reviewed by two technically qualified individuals, and c) the discharge line valving is independently verified by a technically qualified individual.
In addition, the Condensate Storage Tank Discharge Monitor will be contir Jally monitoreci to ensure that the tank is isolated promptly if the monitor alarms.
(2)
The Conderisate Storage Tank Discharge Path Monitor and Flow Rate Measurement Device need be OPERABLE only when the Condensate Storage Tank discharge path is in use
l ODCM-3.0 l
Revision 10 Page 3.0-8 TABLE 4.3.7.11-1 l
RADIOACTIVE LlOUlD EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE.
REQUIREMENTS Channel Channel Source Channel f " *"*I I"*'"""*"'
Check Check Calibration; Test 1.
GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE l
a.
Liquid Radwaste Effluent Line P
P R(3)
O(1) (2) 2.
GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE 1
s Circulating Water Reservoir Decant Line D
M R(3)
O(5)
D11 N402 b.
Condensate Storage Tank Discharge P
P R(3)
O(6)
Path (7) 3.
FLOW RATE MEASUREMENT DEVICES (4) 1 a.
Liquid Radwaste Effluent Line D(4)
N.A.
R O
b.
Circulating Water Reservoir Decant Line D(4)
N.A.
r-o l
c.
Condensate Storage Tank Discharge D(4)
N.A.
R O
Path (7) i I
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ODCM-3.0 Revision 10 i
l Page 3.0 9 l
TABLE 4.3.7.11-1 (Continued)
TABLE NOTATIONS (1)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
(2)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(3)
The initial CHANNEL CALIBRATION shall be performed using National Institute of Standards and Technology traceable sources. These standards shall permit calibrating the system over the range of energy and measurement expected during normal operation and anticipated operational occurrences. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration or are National Institute of Standards and Technology traceable shall be used.
(4).
CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
(5)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
l 3.
Instrument indicates a downscale failure.
.(6)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that local alarm occurs if any of the following conditions exists: 1) instrument indicates measured levels above the alarm setpoint,2) circuit failure, or 3) instrument indicates a downscale failure.
i (7)
Surveillance requirements for the Condensate Storage Tank Discharge Path Monitor and the Condensate Storage Tank Discharge Path Flow Rate Measurement Device shall be met when the Condensate Storage Ta 1k discharge path is in use.
1
ODCM-3.0 Revision 10 Page 3.0-10 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLU9 T MONITORING INSTP'JMENTATION CONTROLS 3.3.7.12 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.12-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels, with the exception of the offgas monitoring system, shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
APPLICABILITY; As shown in Table 3.3.7.121 ACTION:
a.
With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Control, immediately suspend
{
l.
the release of radioactive gaseous effluents monitored by the affected channel, or i
declare the channel inoperable, or change the setpoint so it is acceptably l
conservative.
1 b.
With less than the minimum number of radioactive gaseous. effluent monitoring l
instrumentatic n channels OPERABLE, take the ACTION shown in Table 3.3.7.12-1.
Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report, j
l c.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
I SURVEILL ANCE REQUIREMENTS 4.3.7.12 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 4.3.7.12-1.
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i ODCM-3.0 Revision 10 Page 3.0-11
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TABLE 3.3.7.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l
1 Minimum Instrument Channels Appilcability Action l
l Operable
]
1.
REACTOR BUILDING EXHAUST PLENUM EFFLUENT I
MONITORING SYSTEM
' oviding 1
121 a,
Low Range Noble Gas Activity Monitor b.
lodine Sampler 1
122
]
c.
Particulate Sampler 1
122 d.
Sampler Flow Rate Monitor 1
123 2.
OFFGAS MONITORING SYSTEM (At the 2.2 minute delay piping) a.
Noble Gas Activity Monitor Providing Alarm 1
126 3.
STANDBY GAS TREATMENT SYSTEM a.
Low Range Noble Gas Activity Monitor #s Providing 1
125 b.
lodine Sampler 1
122 c.
Particulate Sampler 1
122 d.
Sampler Flow Rate Monitor 1
123 4.
TURBINE BLDG. VENTILATION MONITORING SYSTEM a.
Low Range Noble Gas Activity Monitor. Providing 1
121 b.
lodine Sampler 1
122 c.
Particulate Sampler 1
122 d.
Sampier Flow Rate Monitor 1
123 l
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l ODCM-3.0 Revision 10 i
Page 3.012 TABLE 3.3.7.121 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l
Minimum Instrument Channels AppIIcebility Action Operable 5.
SERVICE BUILDING VENTILATION MONITORING l
SYSTEM a.
Low Range Noble Gas Activity Monitor Providing 1
121 b.
todine Sampler 1
122 c.
Particulate Sampler 1
122 d.
Sampler Flow Rate Monitor 1
123 6.
RADWASTE BUILDING VENTILATION MONITORING SYSTEM a.
Low Range Noble Gas Activity Monitor Providing 1
121 b.
lodine Sampler 1
122 c.
Particulate Sampler 1
122 d.
Sampler Flow Rate Monitor 1
123 7.
ONSITE STORAGE BUILDING VENTILATION EXHAUST RADIATION MONITOR a.
Low Range Noble Gas Activit/ Monitor Providing 1
121 b.
lodine Sampler 1
122 c.
Particulate Sampler 1
122 d.
Sampler Flow Rate Monitor 1
123 l
l
ODCM-3.0 Revision 10 Page 3.013 TABLE 3.3.7.12-1 (Continued) l TABLE NOTATIONS At all times.
Not used.
I During operation of the main condenser air ejector.
During operation of the standby gas treatment system.
l Also included in Technical Specifications Table 3.3.7.5.1 Item 13.a.
ACTION STATEMENTS ACTION 121 -
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 pe. 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 122 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> samples are continuously collected with auxiliary sampling equipment as required in Table 4.11.2.1.21.
ACTION 123 -
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 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. Otherwise, suspend release of radioactive effluents via thic pathway.
ACTION 124 -
Not used.
l ACTION 125 -
With the number of channels OPERABLE less Clan required by the l
Minimum Channels OPERABLE requirement, effluent releases via this l
pathway may continue provided grab samples are taken at least once per 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
]
Otherwise. suspend release of radioactive effluents via this pathway.
ACTION 126 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, releases via this pathway to the environment may continue for up to 7 days provided that:
a.
The offgas system is not bypassed, and b.
The reactor building exhaust plenum noble gas effluent (downstream) monitor is OPERABLE; l
Otherwise, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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ODCM-3.0 Revision 10 Page 3.0-14 TABLE 4.3.7.12-1
)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE
{
REQUIREMENTS Modes in Channel Instrument Channel Source Channel.
Which my,y Suwelliance Check Check Calim
- y 3,,q Required w ~. ~ :
t
~
1.
REACTOR BUILDING EXHAUST PLENUM a.
Low Range Noble Gas Activity Monitor -
D M
R(2)
O(1)
, Providing Alarm b.
lodine Sampler W
N.A.
N.A.
N.A.
c.
Particulate Sampler
'N N.A.
N.A.
N.A.
d.
Sampler Flow Rate Monitor D
N.A.
R O
j 2.
OFFGAS MONITORING SYSTEM (At the 2.2 minute delay piping) a.
Noble Gas Activity Monitor D
M R(2)
O(1) 3.
STANDBY GAS TREATMENT MONITORING SYSTEM a Low Range Noble Gas Activity Monitor D
M R(2)
O(1) b.
lodine Sampler W
N.A.
N.A.
N.A.
c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Sampler Flow Rate Monitor D
N.A.
R O
4.
TURBINE BLDG. VENTILATION l
MONITORING SYSTEM a.
Low Range Noble Gas Activity Monitor D
M R(2)
O(4) b.
lodine Sampler W
N.A.
N.A.
N.A.
c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Sampler Flow Rate Monitor D
N.A.
R O
ODCM-3.0 Revision 10 l
Page 3.0-15 TABLE 4.3.7.12-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Modes in Instrument Channel Source Channel Which onal Survelliance Check Check Calibention
.;. Test Required i
5.
SERVICE BUILDING VENTILATION MONITORING SYSTEM j
a.
Low Range Noble Gas Activity Monitor D
M R(2)
O(4) b lodine Sampler W
N.A.
N.A.
N.A.
c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Sampler Flow Rate Monitor D
N.A.
R O
6.
RADWASTE BUILDING VENTILATION MONITORING SYSTEM a.
Low Range Noble Gas Activity Monitor D
M R(2)
O(4) b.
lodine Sampler W
N.A N.A.
N.A.
c.
Paniculate Sampler W
N.A.
N.A.
N.A.
I d.
Sampler Flow Rate Monitor D
N.A.
P.
O 7.
ONSITE STORAGE BUILDING VENTILATION c.XHAUST RADIATION MONITOR a.
Low Range Noble Gas Activity Monitor D
M R(2)
O(1) b.
lodine Sampler W
N.A.
N.A.
N.A.
c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Sampler Flow Rate Monitor D
N.A.
R O
1
ODCM-3.0 Revision 10 Page 3.016 TABLE 4.3.7.12-1 (Continued)
TABLE NOTATIONS l
l At all times.
Not used.
During' operation of the main condenser air ejector.
During operation of the standby gas treatment system.
(1)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode (alarm or type).
(2)
The initial CHANNEL CALIBRATION shall be performed using National Institute of Standards and Technology traceable sources. These standards shall permit calibrating the system over the range of energy and measurement expected during normal operation and anticipated operational occurrences. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration or are National Institute of Standards and Technology traceable shall be used.
(3)
Not used.
(4)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation occurs on high level and that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoints.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in the operate mode (alarm or type).
i
ODCM-3.0 Revision 10 Page 3.017 3/4.11' RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 The concentration of radioactive materialisbased in liquid effluents to UNRESTRICTED AREAS (see Figure 3.0-1) shall be limited to ten times the concentration values specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microcuries/mi total activity.
APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.
I SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11.1.1.1-1.
i 4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.
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ODCM-3.0 Revision 10 l
Page 3.0-18 l
TABLE 4.11.1.1.1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM
- "I*""
Luer Limit of Liquid Release Sampling Type of Activity Analysis Analysis Detection (LLD)*
Type Frequency Frequency luCVml)
P P
Principal Gamma S x 3 o-7 Each Batch Each Batch Emitterse A.
Batch Release ;
l131 1 x 10-6 b
Waste Sample Tanks (3) or P
M Dissolved and 3 x 30 5 Condensate One Batch /M Entrained Gases Storage Tank (Gamma Emitters)
P M
H3 3 x 30-5 d
Gross Alpha 1 x 10-7 Each Batch Composite P
O Sr 89, Sr-90 5 x 10 8 d
Fe 55 1 x 10-6 Each Batch Composite M
Prir cipal Gamma 5 x 10-7 l
l d
Emitterse NA Composite B.
Continuous 1-131 1 x 10-6 Releasese Circulating W
M Dissolved and 1 x 10-5 Water System (if Grab Sample Entrained Gases contaminated)
(Gamma Emitters)
M H3 1 x 10-5 l
NA l
d Gross Alpha 1 x 10 7 Composite O
Sr 89, Sr-90 5 x 10-8 Composited Fe 55 1 x 10 6
ODCM-3.0 Revision 10 Page 3.019 TABLE 4.11.1.1.1-1 (Continued)
TABLE NOTATION aThe LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a ".eal" signal.
For a particular measurement system, which may include radiochemical separation:
LLD = E V.2.22 x 106. Y.exp (-At)
Where:
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sb s the standard deviation of the background counting rate or of the counting rate of a i
blank sample as appropriate, as counts por minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume.
6 l
2.22 x 10 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, h is the radioactive decay constant for the particular radionuclides, and l
1 t for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.
i Typical values of E, V, Y, and t should be used in the calculation, it should be recognized that the LLD is defined as an g oriori (before the fact) limit representing
. the capability of a measurement system and not as an a costeriori (after the fact) limit for a particular measurement.
bA batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a l
method described in the ODCM to assure representative sampling. Batch liquid discharge may l-be made from only one tank at a time.
1 I
ODCM-3.0 l
Revision 10 Page 3.0 20 TABLE 4,11.1.1.1 1 (Continued)
TABLE NOTATION cThe principal gamma emitters for which the LLD specification applies exclusively are:
Mn-54, Fe-59, Co 58, Co 60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144, This does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together -
with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 5.9.1.8.
dA composite sample is one in which the quantity of liquid samples is proportional to the quantity i
of liquid waste discharged and in which the method of sampling employed results in a specimen L
that is representative of the liquids released. This may be accomplished through composites of grab samples obtained prior to discharge after the tanks have been recirculated.
eA contin'uous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of a system that has an input flow during the continuous release.
I 1
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ODCM-3.0 Revision 10 Page 3.0-21 RADIOACTIVE EFFLUENTS l
LIQUID EFFLUENTS DOSE l
CONTROLS 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 3.0-1) shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and b.
During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
APPLICABILITY: At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Par 1141, Safe Drinking Water Act.*
b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
- Applicable only if drinking water supply is taken from the receiving water body within 3 miles of the plant discharge.
ODCM-3.0 Revision 10 Page 3.0-22 RADIOACTIVE EFFLUENTS i
LIQUID WASTE TREATMENT CONTROLS I
3.11.1.3 The liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each reactor unit, to j
UNRESTRICTED AREAS (see Figure 3.0-1) woulo exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any 31-day period.
APPLICABILITY: At all times.
'l ACTION:
a.
With radioactive liquid waste being discharged and in excess of the above limits and any portion of the liquid radwaste treatment system not in operation, prepare and l
submit to the Commission within 30 days pursuant to Technical Specification 6.9.2 a j
Special Report that includes the following information:
i 1.
Explanation of why liquid radwaste was being discharged without complete treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.
i 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRIC,FJ AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstrated OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2.
1 l
1 1
b
ODCM 3.0 Revision 10 Page 3.0 23 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE CONTROLS 3.11.2.1 The ciose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.0-1) shall be limited to the following:
For noble gases: Less than or equal to 500 mrems/yr to the total body and less a.
than or equal to 3000 mrems/yr to the skin, end b.
For iodine-131, iodine 133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
APPLICABILITY: At all times.
ACTION:
With the dose rate (s) exceeding the above limits,immediately restore the release rate to within the above limit (s).
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.
4.11.2.1.2 The dose rate due to iodine 131, iodine 133, tritium, and all other radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be i
within the above limits in accordance with the methodology and parameters in the ODCM by I
obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11.2.1.2-1.
ODCM 3.0 Revision 10 Page 3.0-24 TABLE 4.11.2.1.2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l
1 Sampling Minimum Type of Acuvity Lower Limit of Gaseous Release Frequency Analysis Analysis Detection (LLD)*
Type Frequency c
(UCVm!)
A.
Containment pi,gj pi, gj Principal Gamma 1 x 10-4
- PURGE (Pre Each PURGE Each PURGE Emittersb Treatment)
Grab Sample Pi H-3 1 x 10-6 B.
Reactor Building Exhaust Plenum ye,e Mc Principal Gamma 1 x 10-4 Standby Gas Emittersb h
Treatment System Grab Sample uc H-3 3 x j o-6 C.
Radwaste Building Principal Gamma Turbine Building M
M Emittersb 1 x 10-4 Service Building Grab Sample M
H-3 1 x 10-6 On Site Storage Facility D.
All Release Types wg 1-131 1 x 10-12 as listed in B and C ContinuousI Absorbent Sample 1-133 1 x 10-10 above.
Wg Principal Gamma-ContinuousI Particulate Sample Emittersb 1 x 1011 (1 131, others)
M Continuousf Composite Gross Alpha 1 x 10-11 Particulate Sample f
O f
Composite Sr 89, Sr-90 1 x 1011 Continuous Particulate Sample Continuousf Noble Gas Monitor Noble Gas Gross 1 x 10-6 Beta or Gamma E.
Waste Oil P
Principal Gamma incineration by P
Each Batch Waste Emittersb 5 x 10 7 Injection into Each Batch Oil Liquid Sample I-131 1 x 10-6 Auxiliary Boiler Fuel l
Stream i
i l
l u__________
ODCM 3.0 Revision 10 Page 3.0-25 TABLE 4.11.2.1.21 (Continued) l TABLE NOTATION aThe LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a real" signal.
For a particular measurement system, which may include radiochemical separation:
4.66 s e E V 2.22 x 10' Y exp(-At)
Where:
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sb s the standard deviation of the background counting rate or of the counting rate of a i
blank sample as appropriate, as counts per minute, i
E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 6
2.22 x 10 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclides, and t for plant effluents is the elapsed time between the midpoint of sample collection and time
.l of counting.
Typical values of E, V, Y, and t should be used in the calculation.
It should be recognized that the LLD is defined as an g oriori (before the fact) limit representing the capability of a measurement system and not as an g posteriori (after the fact) limit for a particular measurement.
bThe principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr 87, Kr 88, Xe 133, Xe 133m, Xe 135, and Xe 138 in noble gas releases and Mn 54, Fe-59, Co 58. Co 60. Zn 65, Mo-99,1-131, Cs-134, Cs-137, Ce 141, and Ce 144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to Control 5.9.1.8.
ODCM-3.0 Revision 10 Page 3.0 26 TABLE 4.11.2.1.2-1 (Continued)
TABLE NOTATION cSampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
dNot used.
eTritium grab samples shall be taken at least once per 7 days from the ventilation exhausror" the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
IThe ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3.
9 Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 3 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in 1 heur and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing, under the following conditions: (1) If any release point noble gas monitor shows that effluent activity has increased more than a factor of 3, sampling shall be performed at that release point. (2) If analysis shows that the DOSE EQUIVALENT l 131 concentration in the primary coolant has increased more than a factor of 3, sampling shall be performed at the reactor building, radwaste building, turbine building, and if standby gas treatment is running, the standby gas treatment system release points. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. When samples collected for periods between 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and 7 days are analyzed, the corresponding LLDs may be increased by a factor equal to the normal weekly sample volume divided by the volume of the sample in question.
hRequired when the SGTS is in operation.
I n OPERATIONAL CONDITIONS 1,2,3, and 4, the applicable portion of primary containment l
shall be sampled and analyzed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the start of any PURGING.
Iln OPERATIONAL CONDITIONS 1,2,3, and 4, when the primary containment atmosphere radiation monitoring system is declared INOPERABLE or is in alarm condition, the applicable portion of primary containment shall be sampled and analyzed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the start of any VENTING or PURGING and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING through other than SGTS.
ODCM-3.0 Revision 10 Page 3.0-27 RADIOACTIVE EFFLUENTS GASEOUS EFFLUENTS DOSE - NOBLE GASES CONTROLS 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 3.0-1) shall be limited to the following:
a.
During e.ny calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and, b.
During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times.
ACTION:
a.
With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
ODCM-3.0 Revision 10 Page 3.0-28 l
RADIOACTIVE EFFLUENTS l
l GASEOUS EFFLUENTS DOSE -LODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM CONTPOLS 3.11.2.3 The dose to a MEMBEP OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 3.0-1) shall be limited to the following:
a.
During any calendar quarter: Less than or equal to 7.5 mrems to any organ and, b.
During any calendar year: Less than or equal to 15 mrems to any organ.
APPLICABILITY: At all times.
ACTION:
a.
With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than.8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Ccmmission within 30 days, pursuant to Technical Specification 6.9.2, 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.
b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133. tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
l
ODCM 3.0 Revision 10 Page 3.0-29 l
RADIOACTIVE EFFLUENTS OFF-GAS TREATMENT SYSTEM CONTROLS 3.11.2.4 The OFF-GAS TREATMENT SYSTEM shall be OPERABLE and shall be in operation.
APPLICABILITY: Whenever the main condenser steam jet air ejectors are in operation.
ACTION:
a.
With the OFF GAS TREATMENT SYSTEM inoperable for more than 7 days, prepare and submit to the commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:
1, Identification of the inoperable equipment or subsystems and the reason j
for the inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and I
3.
Summary description of action (s) taken to prevent a recurrence, b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
c.
The provisions of Control 4.0.4 are not applicable.
I SURVEILLANCE REQUIREMENTS 4.11.2.4 The OFF-GAS TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting j
Cmtrols 3.11.2.1, 3.11.2.2. and 3.11.2.3.
j i
i i
i I
l I
I ODCM 3.0 Revision 10 Page 3.0-30 RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM CONTROLS 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM as described in the ODCM shall be OPERABLE and appropriate portions of the system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site to UNRESTRICTED AREAS (see Figure 3.0-1) would exceed 0.3 mrom to any organ in any 31-day period.
APPLICABILITY: At all times.
ACTION:
a.
With radioactive gaseous waste being discharged in excess of the above limits and l
any portion of the VENTILATION EXHAUST TREATMENT SYSTEM not in operation, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2 a Specia! Report that includes the following I
information:
1.
Identification of any inoperable equipment or subsystems, and the reason for the inoperability.
2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, I
and 1
l 3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM, when any portion of the VENTILATION EXHAUST TREATMENT SYSTEM is not in use.
4.11.2.5.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting Controls 3.11.2.1, 3.11.2.2, and 3.11.2.3.
t b __. _. _ _ _
ODCM-3.0 Revision 10 Page 3.0-31 RADIOACTIVE EFFLUENTS VENTING OR PURGING l
CONTROLS 3.11.2.8 VENTING or PURGING of the primary containment shall be through the standby gas treatment system or the reactor building ventilation system.
APPLICABILl1Y: OPERATIONAL CONDITIONS 1,2,3, and 4 ACTION:
a.
With the requirements of the above control not satisfied, suspend all VENTING or PURGING of the primary containment.
b.
The provision of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.8.1 The applicable portion of primary containment shall be sampled and analyzed per Table 4.11.2.1.2-1 of Control 3.11.2.1 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the start of any PURGING.
4.11.2.8.2 If the primary containment radiation monitoring system is INOPERABLE or is in alarm condition, the applicable portion of primary containment shall be sampled and analyzed per Table 4.11.2.1.2-1 of Control 3.11.2.1 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING of primary containment through other than the standby gas treatment system.
4.11.2.8.3 The primary containment shall be determined to be aligned for VENTING or PURGING through the standby gas treatment system or the reactor building ventilation system within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING of the containment.
4.11.2.8.4 Pnor to use of the vent / purge system through the standby gas treatment system assure that:
a.
Both standby gas treatment system trains are OPERABLE whenever the vent / purge system is in use, and b.
Whenever the vent / purge system is in use during OPERATIONAL CONDITION 1 or 2 or 3, only one of the standby gas trE3tment system trains may be used.
4.11.2.8.5 Prior to VENTING or PURGING, assure that at least one of the following monitors is OPERABLE: the primary containment atmosphere radiation monitor, the reactor building ventilation exhaust radiation monitor (at least one division), or the SPING monitor corresponding to the release path (the reactor building exhaust plenum radiation monitor or the standby gas treatment system radiation monitor, Division 1 or 2).
E i
\\
ODCM-3.0 l
l Revision 10 Page 5.0-32
)
1 RADIOACTIVE EFFLUENTS I
l 3/4.11.4 TOTAL DOSE l
l CONTROLS l
l I
3.11.4 The annual (calendar year) dose or dose commitment to any member of the public (as defined in 40 CFR Part 190) due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, l
except the thyroid, which shall be limited to less than or equal to 75 mrems.
j APPLICABILITY: At all times.
ACTION-a.
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 3.11.1.2a.,3.11.1.2b.,
3.11.2.2a.,3.11.2.2b.,3.11.2.3a., or 3.11.2.3b., calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, 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, a's defined in 10 CFR 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 hmits, 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 vanance 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.
b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2,4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.
l l
4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and from outside storage tanks shall be determined in accordance with the methodology and parameters in
- the ODCM. This requirement is apphcable only under conditions set forth in Control 3.11.4, ACTION a.
ODCM 3.0 Rsvision 10 Page 3.0-33 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1 1.
APPLICABILITY: At all times.
ACTION:
a.
With the rau;ological environmental monitoring program not being conducted as specified in Table 3.12.1 1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Control 5.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
b.
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 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, 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 A MEMBER l
OF THE PUBLIC is less than the calendar year limits of Controls 3.11.1.2,3.11.2.2, and
)
3.11.2.3. When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:
l concentration (1) + concentration (2) +..2 1.0 reporting level (1) reporting level (2)
When radionuclides other than those in Table 3.12.1-2 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 from all radionuclides is equal to or greater than the calendar year limits of Controls 3.11.1.2,3.11.2.2, and 3.11.2.3. This 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 pursuant to Control 5.9.1.7.
c.
With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12.1-1, identify specific locations for obtaining replacement samples and add them to the radiological environmental monitoring
[
program within 30 days. The specific locations from which samples t
'The methodology used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
ODCM-3.0 i
Revision 10 l
Page 3.0-34 RADIOLOGICAL ENVIRONMENTAL MONITORING I
CONTROLS (Continued) were unavailable may then be deleted from the monitoring program. Pursuant to Control 5.9.1.8, identify the cause of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Annual Radioactive j
Effluent Release Report pursuant to Control 5.9.1.8 and also include in the report a j
revised figure (s) and table for the ODCM reflecting the new location (s).
d.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to
(
Table 3.12.1 1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.
l 1
i
ODCM 3.0 Revision 10 Page 3.0-35 TABLE 3.12.1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Represenentive Sampling and Exposure Pathway Samples and Sample Collection Type and Frequency ofAnalysis and/or Sample Locationsa '
Frequency e
1.
DIRECT RADIATIONb 67 routine monitoring statior 8 Quarterly Gamma dose quarterly.
with two or more dosimeters placed as follows: 1) an inner nng of stations in the general area of the SITE BOUf JDARY and additional rings at approximately 2, 5, and 10 miles, with a station in at least every other meteorological sector for each ring with the exception of those sectors over Lake Ene.
The balance of the stations,8, should be placed in special' interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations, i
l 2.
AIRBORNr.
Samples from 5 locations.
C'ontinuous sampler Radiciodine Canister:
l Radioiodine and operation with sample 1-131 analysis weekly.
Particulate a.
3 samples f rom clore to the collection weekly, or 3 SITE BOUNDARY more frequently if Particulate Samoler:
locations. in different sators, required by dust Gross beta radioactivity of the highest calculaied loading.
analysis following filter annual average ground level change:d l
Dio.
i Gamma isotopic b.
1 sample from the vicinity of e
analysis of composite' (by location) quarterly, hi s cal una e a al average ground level D/O.
c.
1 sample from a control location as for example 15 30 km distant and in the least prevalent wind C
direction.
ODCM-3.0 Revision 10 Page 3.0-36 TABLE ' 3.12.1-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM tl umber of Represenistive Sampling and Exposure Pathway Samples and Sample Collection Type and Frequency and/or Sample Locationsa Frequency otAnalysis 3.
WATERBORNE f
a.
1 sample upstream.
Composite sample Gamma isotopic a.
Surface b.
1 sample downstream.
over 1 month period 9 analysis monthly.
e Composite for tritium analysis quarterly.
b.
Ground e
Samples from 1 or 2 sources only Quarterly Gammaisotopic and if likely to be affected.
tritium analysis h
quarterly.
1131 analysis on each c.
Drinking a.
1 sample of each of 1 to 3 of i
Compos.te sample composite when the i
the nearest water supplies that could be affected by its over 2 week period 9 due calculated for the i
discharge.
when 1131 analysis is consumption of the j
performed, monthly water is greater than 1 b.
1 sample from a control composite otherwise, mrem per year.I location.
Composite for gross beta and gamma e
isotopic anaiyses monthly Composite for tritium analysis quu.erty.
I a.
Sediment from 1 sample from cownstream area Sem; annually Gamma isotopic shoreline with existing or potential analysis' semiannually.
l recreational value.
I t
ODCM 3.0 Revision 10 Page 3.0-37 TABLE 3.12.1-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MOiJITORING PROGRAM Number of Representative Sampling and Exposure Pathway Samples und Sample Collection Type and Frequency andfor Sample Locationsa Frequency otAnalysis 4.
INGESTION a.
Milk a.
Samples from milking Semimonthly when Gammaisotopic and 8
animals in 3 locations within animals are on i.131 analysis 5 km distance having the pasture, monthly at semimonthly when highest dose potential. If other times, animals are on pasture; there are none, then 1 monthly at other times.
sample from milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated to be greater I
than 1 mrem per yr.
b.
1 sample from milking animals at a controllocation 15 30 km distant and in the least prevalent wind direction.
a.
1 sample of each 8"*p e in seas n. f Gamma isotopic s mia a
ey b.
Fish and commercially and e
analysis on edible Invertebrates recreatienally important
- portions, species in vicinity of plant discharge area b.
1 sample of same species in areas not influenced by plant discharge a 1 sample f each principal At time of harvestl-Gamma isotopic f
c.
Food Products class of food products from analyses on edible e
any area that is artigated by portions.
water in which liquid plant wastes have been l
discharged e
b Samples of 3 ditterent kinds Monthly when Gammaisotopic and of broad leaf vegetation available.
1131 analysis, grown nearest each of two different ottsite locations of highest predicted annual average level D'O if milk sampling is not performed c.
1 sample of eacn of the Monthly when Gamma isotopic and e
similar broad leaf vegetation available.
1-131 analysis.
grown 15-30 km distant in the least prevaient wind direction it milk sampling is not performed i
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ODCM-3.0 Revision 10 Page 3.0-38 TABLE 3.12.1-1 (Continued)
TABLE NOTATIONS aspecific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12.1-1 in a table and figure (s) in the ODCM. 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. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next samoling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Contol 5.9.1.7. 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 specific 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. Pursuant to Control 5.9.1.8, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s),
b ne or more instruments, such as a pressurized ion charnber, for measuring and recording O
dose rate continuously rnay be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimete. (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 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.
cThe purpose of this sample is to obtain background information. If it is not practical to establish controllocations in accordance with the distance and wind direction critena, other sites that have valid background data may be substituted.
dAirborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after st mpling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples, eGamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attnbutable to the effluents from the facility.
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1 l
ODCM 3.0 Revision 10 Page 3.0-39 TABLE 3.12.1-1 (Continued)
TABLE NOTATION IThe " upstream sample" shall be taken at a distance beyond significant influence of thE discharge. The " downstream" sample shall be taken in an area beyond but near the mixing zone.
" Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence.
- 9 Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly).
h roundwater samples shall be taken when this source is tapped for drinking or irrigation G
purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
iThe dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.
Ilf harvest occurs more than once a year, sampling shall be performed during each discrete d
harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.
l
ODCM-3.0 Revision 10 Page 3,0-40 TABLE 3.12.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Water Airborne Fish Milk Food Analysis (pCV1)
Particulate or (pCVkg, wet)
(pCW1)
Products Gases (pCVm )
(PCVkg, wet) 3 H3 20,000*
Mn 54 1,000 30,000 Fe 59 400 10,000 Co 58 1,000 30,000 Co 60 300 10,000 Zn-65 300 20,000 Zr Nb 95 400 1131 2
0.9 3
100 Cs 134 30 to 1,000 60
-1,000 Cs 137 50 20 2,000 70 2,000 Ba La 140 200 300
- For dnnking water samples. This is 40 CFR Part 141 value.
1 l
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ODCM-3.0 Revision 10 Page 3.0-41 TABLE 4.12.1-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS a LOWER LIMIT OF DETECTION (LLD)b,c Water Airborne Fish htilk Food Sediment Analysis (pCV1)
Particulate or (pCVkg, wet)
(pCV1)
Products (pCVkg, dry)
Gsses (pCVm3)
(pCVkg, wet) gross beta 4
0.01 H-3 2000 Mn-54 15 130 Fe 59 30 260 Co-58.60 15 130 2n-65 30 260 Zr-Nb-95 15 l131 jd 0 07 1
60 Cs 134 15 0.05 130 15 60 150 Cs 137 18 0.06 150 18 80 180 Ba La 140 15 15 i
l
I OdCM 3.0 R: vision 10
)
Page 3.0-42 TABLE 4,12.1-1 (Continued)
TABLE NOTATIONS 1
aThis list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the j
Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.
b equired detection c' capabilities for thermoluminescent dosimeters used for environmental R
measurements are given in Regulatory Guide 4.13.
cThe LLD is defined, for purposes of these Controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% 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 x 10* Y exp(-At)
Where:
LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume, sb s the standard deviation of the background counting rate or of the counting rate of a i
blank sample as appropriate, as counts per minute, j
E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picoeurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclides, and t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical values of E, V, Y, and t should be used in the calculation.
ODCM-3.0 Revision 10 Page 3.0-43 TABLE 4.12.1 1 (Continued)
TABLE NOTATIONS It should be recognized that the LLD is defined as an a p_rigri(before the fact) limit representing r
the capability of a measurement system and not as an a costeriori (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 other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.
dLLD for drinking water samples.
i l
L____-______________--__--___-
ODCM-3.0 Revision 10 i
Page 3.0-44 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS i
i CONTROLS 3.12.2 A land use census shall be conducted and shallidentify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal. the j
nearest residence and the nearest garden
- of greater than 50 m2 (500 ft ) producing broad leaf 2
"egetation.
APPLICABILITY: At all times.
ACTION:
a.
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 Surveillance Requirement 4.11.2.3, identify the new location (s)in the next Annual Radioactive Effluent Release Report, pursuant to Control 5.9.1.8.
b.
With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samoles are currently being obtained in accordance with Control 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to Control 5.9.1.8, identify the new 1
location (s)in the next Annual Radioactive Effluent Release Report and also include j
in the report a revised figure (s) and table for the ODCM reflecting the new i
location (s).
I c.
The provisions of Control 3.0.3 and 3.0.4 are not applicable.
j SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results. such as by a door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.
I
{
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Os 1
in lieu of the garden census. Controls for broad leaf vegetation sampling in Table 3.12.1-1, i
Part 4.c, shall be followed. including analysis of control samples.
j i
)
i ODCM-3.0 Revision 10 Page 3.0-45 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.
I APPLICABILITY: At all times.
]
ACTION:
I a.
With analyses not being performed as required above, report the corrective actions j
taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.
b.
The provisions of Controls 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS l
1 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of j
the results obtained as part of the above required interlaboratory Comparison Program shall be j
included in the Annual Radiological Environmental Operating Report pursuant to Control 5.9.1.7.
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Nuclear Production - Fermi 2 ODCM-4.0 Offatte Dose Ct.lculation Manual Revision 7 Page 4.0-1 u
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3 e'
SECTION 4.0 BASES d
f
--_m_
i ODCM-4.0 t
i Revision 7 Page 4.0-2 l INSTRUMENTATION l
1 BASES 3/4.3.7.11 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION l
The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential l
releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the lim.is 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.
3/4.3.7.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or j
potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM utilizing the system design flow rates as specified in the ODCM. This conservative method is
)
used because the Fermi 2 design does not include flow rate measurement devices. This will l
ensure 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.
3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR Part 20.100120.2401, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section ll.A design objectives of Appendix I,10 CFR Part 50. to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1301 to a MEMBER OF THE PUBLIC. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in Internationsi Commission on Radiological Protection (ICRP)
Publication 2.
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedure Manual, HASL-300 (revised annually),
Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40,586 93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
l l
ODCM-4.0 Revision 7 Page 4.0-3 RADIOACTIVE EFFLUENTS BASES 3/4.11.1.2 DO!f This control is provided to implement the requirements of Sections ll.A, lii.A, and IV.A of Appendix 1,10 CFR Part 50. The controlimplements the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AF.EAS will be kept "as low as is reasonably achievable." Also. for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclides concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section Ill.A of Appendix i that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.113 " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix 1," April 1977.
3/4.11.1.3 LIOUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to their release to the environment. The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable" This specification implements the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix i to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section ll.A of Appendix 1,10 CFR Part 50, for liquid effluents.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This controlis provided to ensure that the dose to individual MEMBERS OF THE PUBLIC from
- gaseous effluents from all units on the site will be within the limits of 10 CFR Part 20.1301.
______-_A
ODCM-4.0 Revision 7 Page 4.0-4 RADIOACTIVE EFFLUENTS BASES 3/4.11.2.1 DOSE RATE (Continued)
Although this control applies to the SITE BOUNDARY, the occupancy and exposure pathways applicable to a MEMBER OF THE PUBLIC who may at times be within the SITE BOUNDARY will usually be such that such an individual will not receive significantly greater dose due to gaseous effluents tnan a MEMBER OF THE PUBLIC who remains outside the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUJLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified dose rate limits l
restrict, at all times, the dose rates above background to a MEMBER OF THE PUBLIC at or i
beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total body or to
)
less ttjan or equal to 3000 mrems/ year to the skin. These dose rate limits also restrict,.at all l
times, the thyroid dose rates above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year.
The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Dett.iled discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually),
Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report j
ARH-SA 215 (June 1975).
l 3/4.11.2.2 DOSE - NOBLE GASES j
l This control is provided to implement the requirements of Sections 11.B, Ill.A, and IV.A of l
Appendix 1,10 CFR Part 50. The control implements the guides set forth in Section ll.B of j
Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section Ill. A of Appendix 1 that conformance with the guides of Appendix l be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropnate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous l
effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
ODCM-4.0 Revision 7 Page 4.0-5 RADIOACTIVE EFFLUENTS BASES 3/4.11.2.3 DOSE - IODINE-131. IODINE-133. TRITIUM. AND RADIONUCLIDES IN PARTICULATE FORM This control is provided to implement the requirements of Sections ll.C, Ill.A, and IV.A of Appendix 1,10 CFR Part 50. The controls are the guides set forth in Section ll.C of Appendix 1.
The ACTION statemerits provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix l to assure that the releasts of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix l that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters 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, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 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.
These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine 131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclides pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
3/4.11.2.4 OFF-GAS TREATMENT SYSTEM The OPERABILITY of the OFF-GAS TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement 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 control implements the requirements of General Design Criteria 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section ll.D of Appendix 1 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 11.8 and ll.C of Appendix 1,10 CFR Part 50, for gaseous effluents.
ODCM-4.0 Revision 7 Page 4.0-6 RADIOACTIVE EFFLUENTS BASES 3/4.11.2.5 VENTILATION' EXHAUST TREATMENT SYSTEM The requirement that the appropriate portions of this system 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." 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 ll.B and ll.C of Appendix 1,10 CFR Part 50, for gaseous effluents.
3/4.11.2.8 VENTING OR PURGING This control provides reasonable assurance that releases from primary containment purging operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED ARE4S.
.3/4.11.4 TOTAL DOSE This controlis 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 control 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 mrems. - For sites containing up to 4 reactors,.
it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the reactor units 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 purpose of the Special Report, it may be assumed that the dose commitment to the member of the public from other than uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a 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 20.2203, 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 requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 3.11.1.1 and 3.11.2.1. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any t
operation that is part of the nuclear fuel cycle.
ODCM-4.0 Revision 7 Page 4.0-7 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological environmental monitoring program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix l to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measureable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12.1-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a oriori (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.
Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedure Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40,586-93(1968),
and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic I
Richfield Hanford Company Report ARH SA-215 (June 1975).
l l
3/4.12.2 LAND USE CENSUS This controlis provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey, from visual survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix l to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 -
kglyear) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.
To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2, I
ODCM 4.0 Revision 7 Page 4.0-8 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARfSON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materialin environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
END OF SECTION 4.0 l
4 l
Nuclear Production - Fermi 2 ODCM-5.0 Offsite Dose Calculation Manual Revision 7 Page 5.0-1 SECTION 5.0 ADMINISTRATIVE CONTROLS 1
l 1
- /
ODCM-5.0 Revision 7 Page 5.0-2 ADMINISTRATIVE CONTROLS I
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 5.9.1.7 Routine Annual 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 shal1 be submitted prior to May 1 of the year following initial criticality.
The Annual Radiological Environmental Operating Reports shallinclude summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison as appropriate, with preoperational studies, with operational controls, 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 reiuired by Control 3.12.2. The Annual Radiological Environmental Operating Reports shall inc:ade the results of analysis of all radiological environmental samples and of all environmentrJ radiation measurements taken during the period pursuant to the locations specio d in the Table and Figures in the ODCM, as e
well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. 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. If possible, the missing data shall be submitted as soon as possible in a supplementary report.
e 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 Companson Program, required by Control 3.12.3; discussion of all deviations from the sampling schedule of Table 3.12.1-1; and discussion of all analyses in which the LLD required by Table 4.12.1 1 was not achievable.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT" 5.9.1.8 Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous year of operation shall be submitted prior to May 1 of each year. The l ///97 period of the first report shall begin with the date of initial criticality.
- One map shall cover stations near the SITE BOUNDARY; a second shallinclude the more distant stations.
"A single submittal may be made for a mutiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall cpecify the releases of radioactive material from each unit.
ODCM-5.0 Revision 7 Page 5.0 3 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)
The Annual Radioactive Effluent Release Report shallinclude a summary of the quantities of 1
radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes
- and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The Annual Radioactive Effluent Release Report shallinclude an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing 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 statior, 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 SITE BOUNDARY (Figure 3.0-1) during the report 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 th.e methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby 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 assessment of radiation doses shall be performed in accordance with methodology and parameters in the ODCM.
The Annual Radioactive Efluent Release Reports 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),
"*in lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
ODCM 5.0 Revision 7 Page 5.0-4 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued) c.
Principal radionuclides (specify whether determined by measurement or estimate),
d.
Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),
e.
Type of container (e.g., LSA, Type A, Type B, Large Quantity), and f.
Solidification agent or absorbent (e.g., cement, urea formaldehyde).
The Annual Radioactive Effluent Release Reports shallinclude a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Annual Radioactive Effluent Release Reports shallinclude any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM) as described in Technical Specification 6.14.2.c, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Control 3.12.2.
The Annual Radioactive Effluent Release Reports shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Control 3.3.7.11 or 3.3.7.12, respectively; and description of the events leading to liquid holdup tanks exceeding the limits of Technical Specification 3.11.1.4.
5.15 MAJOR CHANGES TO RADIOACTIVE LIOUlD. GASEOUS. AND SOLID WASTE TREATMENT SYSTEMS
- 5.15.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid):
a.
Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the OSRO. The discussion of each change shall contain:
A summary of the evaluation that led to the determination that the change 1
could be made in accordance with 10 CFR 50.59.
2.
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplementalinformation;
- Licensees may choose to submit the information called for in this Control as part of the UFSAR revision in accordance with 10 CFR 50.71(e).
ODCM-5.0 Revision 7 Page 5.0-5 ADMINISTRATIVE CONTROLS l
3.
A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems; 4.
An evaluation of the change, which shows the pr,edicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; 5.
An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto; 6.
A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents ard in solid waste, to the actual releases for the period prior to when the changes are to be made; 7.
An estimate of the exposure to plant operating personr el as a result of the change; and 8.
Documentation of the fact that the change was reviewed and found acceptable by the OSRO.
b.
Shall become effective upon review and acceptance by the OSRO.
END OF SECTION 5.0
Nuclear Production - Fermi 2 ODCM-6.0 Offsite Dose Calculation Manual Page 6.0-1 PARTil CALCULATIONAL METHODS
ODCM-6.0 Revision 7 Page 6.0-2 LIQUID EFFLUENTS 6.0 LIQUID EFFLUENTS This section summarizes information on the liquid effluent radiation monitoring instrumentation and controls. More detailed information is provided in the Fermi 2 UFSAR and Fermi 2 design drawings from which this summary was derived. This section also describes the sampling and l
analysis required by the Offsite Dose Calculation Manual. Methods for calculating alarm setpoints fr the liquid effluent monitors are presented. Also, methods for evaluating doses from liquid effluents are provided.
6.1 Radiation Monitoring Instrumentation and Controls This section summarizes the instrumentation and controls monitoring liquid effluents. This discussion focuses on the rok of this equipment in assuring compliance with the Offsite Dose Calculation Manual.
6.1.1 Offsite Dose Calculation Manual (ODCM) 3.3.7.11 Requirement Fermi 2 ODCM 3.3.7.11 prescribes the monitoring required during liquid releases and the backup sampling required when monitors are inoperable.
The liquid effluent monitoring instrumentation for controlling and monitoring radioactive effluents in accordance with the Fermi 2 ODCM 3.3.7.11 is summarized below:
1.
Radiation Alarm - Automatic Release Termination a.
Liquid Radwaste Effluent Line - The D11-N007 Radiation Monitor on the liquid radwaste effluent line provides the alarm and automatic termination of liquid radioactive material releases prior to exceeding 1 Maximum Permissible Concentration (MPC) at the discharge to Lake Erie (ten times 10 CFR 20. Appendix B, Table 2, Column 2 values) required by ODCM 3.3.7.11. The monitor is located upstream of the isolation Valve (G11-F733) on the liquid radwaste discharge line and monitors the concentration of liquid effluent before dilution by the circulating water reservoir (CWR) decant flow.
2.
Radiation Alarm (only) a.
Circulating Water Reservoir (CWR) Decar.t Line - The CWR Decant Line Radiation Monitor (D11-N402) provides indication of the concentration of radioactive materialin the diluted radioactive liquid releases just before discharge to Lake Erie. As required by ODCM 3.3.7.11. the alarm setpoint is established to alarm (only) prior to exceeding one MPC.
ODCM-6.0 R;, vision 7 I
Page 6.0-3 b.
Condensate Storage Tank (CST) Discharge Path - The CST l
l Discharge Monitor provides indication of the concentration of radioactive material in the CST Discharge Path prior to dilution by the circulating water decant flow. As required by ODCM 3.3.7.11, the alarm setpoint is established to alarm (only) prior to exceeding one MPC at the discharge to Lake Erie.
3.
Flow Rate Measuring Devices a.
Liquid Radwaste Effluent Line -In E Ocordance with ODCM 3.3.7.11, the release rate of liquid radwaste discharges is monitored by G11-R703.
This flow rate instrumentation is located on the radwaste discharge line prior to the junction with tne CWR decant line.
b.
Circulating Water Reservoir Decant Line - In accordance with ODCM 3.3.7.11, the flow rate of the CWR decant line is monitored by y
N71 R802. The flow rate instrumentation is located on the decant line j
downstream of the junction with the liquid radwaste effluent line. This i
instrumentation measures the total discharge flow rate from Fermi 2 I
to Lake Erie, i
c.
Condensate Storage Tank Discharge Path - In accordance with j
ODCM 3.3.7.11, the flow rate of this line is monitored.
6.1.2 Non-ODCM Required Monitor An additional monitor not required by Fermi 2 ODCM is provided by Detroit Edison to reduce the likelihood of an unmonitored release of radioactive liquids.
1.
General Service Water - The General Service Water (GSW) Radiation Monitor (D11 N008) provides additional control of potential radioactive i
effluents. D11-N008 monitors the GSW System prior to discharge into the i
Main Condenser circulating water discharge line to the Circulating Water Reservoir. Although not an ODCM required monitor, D11-N008 monitors a primary liquid stream in the plant that also discharges to the environment (Lake Ene via the Circulating Water Reservoir). Indication of radioactive material contamination in the GSW System would also indicate potential CWR contamination and the need to control all escharges from the CWR as radioactive effluents.
-____-._____..__________w
ODCM-6.0 Revision 7 Page 6.0-4 6.2 Sampling and Analysis of Liquid Effluents The program for sampling and analysis of liquid waste is prescribed in the Fermi 2 Offsite Dose Calculation Manual Table 4.11.1.1.1 1. This table distinguishes two types of liquid releases: a) BATCH releases, defined as discrete volumes, from the Waste Sample Tanks (normally after processing through the radwaste system) or from the Condensate Storage Tank, and b) CONTINUOUS releases, from the Circulating Water Reservoir (CWR) System, if it becomes contaminated Continuous releases from the CWR System are via the CWR decar'. line to Lake Erie.
The CWR System is not expected to become contaminated. Therefore, continuous radioactive material releases are not expected. However, the General Service Water (GSW) and the CWR systems interface with radioactive systems in the plant. Also, the GSW intake is within a few hundred feet of the CWR decant lire discharge to Lake Erie.
For these reasons, it is prudent to consider the GSW and the CWR a potential source of radioactive effluents and to sample them regularly.
6.2.1 BATCH Releases Fermi 2 ODCM Table 4.11.1.1.1-1 requires that a sample representative of the tank contents be obtained before it is released. The table specifies the following program:
Prior to sampling, the tank is isolated. The tank level is determined and this value is cor,verted to tank volume. A pump with a known recirculation flow rate is then activated to recirculate tank contents. The pump is allowed to run for at least the time required to recirculate the tank volume twice.
Prior to each batch releese, analysis for principal gamma emitters (including all peaks identified by gamma spectroscopy)
Once per month, analysis of one batch sample for dissolved and entrained gases (gamma emitters). (See note in Section 6.2.2 below.)
Once per month, analysis of a composite sample of all releases that month for tritium (H-3) and gross alpha activity. (The composite sample is required to be representative of the liquids released and sample quantities of the composite are to be proportional to the quantities 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.
l ODCM-6.0 R:: vision 7 Page 6.0-5 6.2.2 CONTINUOUS Releases i
Fermi 2 ODCM Table 4.11.1.1.1-1 requires that composite samples be collected
)
from the CWR System, if contaminated. The table specifies the following
~
l sample analysis:
Once per month, analysis of a composite sample for principal gamma
)
emitters and for 1131.
Once per month, analysis of a composite sample for H-3 and gro.s alpha.
Once per month, analysis of weekly grab samples (composited) for dissolved and entrained gases (gamma emitters). (See note below.)
Once per quarter, analysis for Sr-89, -90 and Fe-55.
J NOTE: Identification of noble gases that are principal gamma emitting radionuclides are included in the gamma spectral analysis performed on all liquid radwaste effluents. Thveafore, the ODCM Table 4.11.1.1.1-1 sampling and analysis for noble gases in batch releases (one batch per month) and continuous releases.
(monthly analysis of weekly grab samples) need not be performed as a separate program. The gamma spectral analysis on each batch release and on the CWR monthly composite meets the intent of this ODCM requirement.
6.3 Liquid Effluent Monitor Setpoints Offsite Dose Calculation Manual 3.11.1.1 requires that the concentration of liquid radioactive effluents not exceed the unrestricted area MPC at the discharge point to i
Lake Erie. Dissolved or entrained noble gases in liquid effluents are limited to a concentration of 2 E-04 pCi/ml, total noble gas activity. ODCM 3.3.7.11 requires that radiation monitor setpoints be established to alarm prior to exceeding the limits of ODCM 3.11.1.1.
To meet this specification. the alarm setpoints for liquid effluent monitors are determined 1
in accordance with the following equation:
RR (6-1) where:
the setpoint,in pCi/ml, of the monitor measuring the radioactivity
-SP
=
concentration in the effluent line prior to dilution. The setpoint represents a value which, if exceeded, would result in concentrations exceeding the MPC in the unrestncted area C L.
=.
the effluent concentration limit (ODCM 3.11.1.1) corresponding to ten times the 0mits of 10 CFR Part 20.1302.b.2.i at the discharge point in pCi/ml, defined in Equation (6-4) 1
~
ODCM-6.0 Revi.sion 7 I
Page 6.0-6 l
l the liquid effluent release rate as measured at the radiation monitor RR
=
location, in volume per unit time, but in the same units as DF, below DF the dilution water flow as measured prior to the release point (Lake Erie)
=
in volume per unit time l
At Fermi 2 the available Dilution Water Flow (DF) is constant for a given release, and the I
waste tank Release Rate (RR) and monitor Setpoint (SP) are set to meet the condition of Equation (6-1) for a given effluent Concentration Limit, CL.
l l
NOTE: If no dilution is provided, SP s CL. Also, when DF is large compared to RR, then l
(DF + RR)-DF, and DF may be used instead of (DF + RR) as a simplification, as l
in Equation (6-5).
1 6.3.1 Tank Effluent Line Monitors The Liquid Radwaste Effluent Line Monitor D11-N007 provides alarm and i
1 automatic termination of releases prior to exceeding MPC. The Condansate l
Storage Tank Discharge Monitor provides alarm only prior to exceeding MPC.
As required by ODCM Table 4.11.1.1.1-1 and as discussed in ODCM Section 6.2.1, a sample of the liquid radwaste to be discharged is collected and l
analyzed by gamma spectroscopy to identify principal gamma emitting radionuclides. From the measured individual radionuclides concentrations, the allowable release rate is determined.
The allowable release rate is inversely proportional to the ratio of the radionuclides concentrations to the MPC values. The ratio of the measured concentration to MPC values is referred to as the "MPC fraction' and is calculated by the equation:
MPCF = [ MPC, (6-2) where:
MPCF =
fraction of the unrestricted area MPC for a mixture of gamma l
emitting radionuclides concentration of each gamma emitting radionuclides i measured in Ci
=
l each tank pnor to release (pCi/ml) l i
1 l
l
I l
ODCM 6.0.
Rsvision 7 Page 6.0 7-MPCi - =
unrestricted area most restrictive MPC for each radionuclides 1: ten times the value from 10 CFR Part 20, Appendix B, Table 2, Column 2. For dissolved and entrained noble gases an MPC value of 2E 04 pCi/mi may be used, but noble gases need not be included in this calculation.
including noble gases in Equation (6-2) eliminates the need for a separate evaluation of compliance with the noble gas concentration limit of ODCM 3.11.1.1.
l Based on the MPCF, the maximum allowable release rate can be calculated by
{
the following equation:
- SF MAX RR S {MPCF *(1 + BF))+ H3MPCF (6-3)
{
I where:
)
maximum acceptable waste tank discharge rate (gai. min)
MAX RR
=
(Monitor #G11-R703) dilution flow rate from the CWR as observed from the -
=
Control Room readout (gal / min) (Monitor CN71-R802) administrative safety factor to account for variations in monitor SF-
=
response and flow rates. A SF,value of 0.5 is suggested because it provides for 100% variation caused by statistical fluctuation and/or errors in measurements.
conservative estimate of the ratio of the MPC fraction of pure
.BF
=.
beta emitters other than tritium to the gamma MPC fraction (MPCF) (The value 0.10 may be used for BF.)
As previously defined by equation (6-2)
MPCF
=
H3MPCF =
conservative estimate of MPC fraction due to tritium (The value 0.13 may be used for H3MPCF.)
NOTE: Equation (6-3) is valid only for MPCF >1; if the MPCF $1, the waste tank concentration meets the limits of 10 CFR Part 20 without dilution, and the tank may be discharged at the maximum rate.
If MAX RR as calculated above is greater than the maximum discharge pump capacity, the pump capacity should be used in establishing the actual Release -
Rate RR for the radwaste discharge. For a Waste Sample Tank, the maximum discharge rate is 50 gallons per minute. This Release Rate RR is monitored in -
the Radwaste Control Room by G11-R703.
i ODCM-6.0 Revision 7 Page 6.0-8 The Concentration Limit (CL) of a liquid radwaste discharge is the same as the effective MPC for the radionuclides mixture of the discharge. Simply, the CL (or effective MPC) represents the equivalent MPC value for a mixture of radionuclides evaluated collectively. The equation for determining CL is:
a __ [ C, MPCF (6-4)
Based on the Release Rate RR and Dilution Flow DF and by substituting Equation (6-4) foi CL in Equation (61) and introducing sensitivity factors and factors to account for the presence of pure beta emitters, the alarm setpoint is calculated by the equation:
1(C,
- SEN,)* DF
- H3F
- SF SP s
+ Bkg MPCF* (1 + BF)* RR (65) where:
setpoint of the radiation monitor counts per se'cond (cps) or SP
=
counts per minute (cpm) concentration of radionuclides i as measured by gamma Ci
=
spectroscopy (pCi/ml) monitor sensitivity for radionuclides i based on calibration SENj
=
curve (cps /(pCi/ml) or cpm /(pCi/ml)) or single conservative value for all radionuclides (see below) actual release rate of the liquid radwaste discharge (gal / min)
=
pure beta f actor as defined for Equation (6-3)
BF
=
MPC fraction as determined by Equation (6-2)
MPCF
=
correction factor to account for estimated tritium concentration at H3F
=
the discharge point (The value 0.99 may be used.)
background reading of monitor (eps)
Bkg
=
dilution flow rate of Circulating Water Decant Line as observed DF
=
from Control Room readout (gal / min) monitor #N71-R802. See 3
note preceding Section 6.3.1.
1.0 when a single conservative sensitivity value is used; 0.5 when SF
=
individual nuclide sensitivity factors are used
\\
1 I
ODCM-6.0 Rsvision 7 Page 6.0-9 The sensitivity of Cr 51 determined from the primary calibration sensitivity curves may be used as a single conservative value for SENj above. The Cr-51 sensitivity has been determined to be conservative based on the nuclide mixes which have been seen in actualliquid discharges from Fermi 2. For the D11-N007 monitor, a monitor sensitivity value of 1.0 E6 cps /(pCi/ml) may be used as the single conservative value of SENi, and for the CST Discharge monitor, a 1
single value of 1.6 E7 cpm /(pCi/ml) r ay be used.
1 if no radionuclides are measured by g. nma spectroscopy, the alarm setpoint
)
can be established at one half the setpunt of the most recent discharge for I
which radionuclides were detected by gamma spectroscopy.
l Prior to conducting any batch liquid radwaste release, Equation (6 3) is used to c<termine the allowable release rate in accordance with ODCM 3.11.1.1.
Equation (6-5) is used to determine the alarm setpoint in accordance with ODCM 3.3.7.11.
6.3.2 Circulating Water Reservoir Decant Line Radiation Monitor (D11 N402) l ODCM 3.3.7.11 requires that the setpoint for the CWR Decant Line Radiation Monitor D11 N402 be established to ensure the radioactive material concentration in the decant line prior to discharge to Lake Erie does not exceed MPC, unrestricted area (ten times 10 CFR 20, Appendix B, Table 2, Column 2
]
values). The approach for determining the alarm setpoint for the CWR Decant l
Line Radiation Monitor is the same as presented in Section 6.3.1. However, the
{
CWR Decant Line Radiation Monitor setpoint need not be changed prior to each release. Equation (6-1) remains valid, except that, for the CWR Decant Line j
Monitor, the dilution flow previously assumed for diluting the BATCH liquid i'
radwaste effluents is now the release rate. There is no additional dilution prior to discharge to Lake Erie. Thus, Equation (6-1) simplifies to:
SP 5 CL (6-6) l Substituting Equation (6-4) for CL and introducing a safety factor, sensitivity factors, and monitor background the D11 N402 alarm setpoint can be calculated by the equation:
l T
+ Bkg SP s -(C
- SEN,)* SF MPCF (6-7) l
ODCM 6.0 R: vision 7 Page 6.0-10 j
where:
setpoint in counts per minute (cpm)
=
concentration of each radionuclides iin the CWR decant line Ci
=
effluent (pCi/ml) monitor sensitivity for nuclide i based on calibration curve SENi
=
(cpm /(pCi/ml))
MPC fraction as determined by Equation (6 2) with Ci defined as MPCF
=
for Equation (6-7) 0.5, administrative safety factor SF
=
l background reading of monitor (cpm)
Bkg
=
Normally, only during periods of batch liquid radwaste discharges will there exist 4
any plant-related radioactive materialin the CWR decant line.
6.3.3 Generic, Conservative Alarm Setpoint for D11-N402 The D11 N402 setpoint could be adjusted for each BATCH release as is done for the liquid radwaste effluent line monitor. Based on the measured levels of radioactive material in a BATCH liquid release, the alarm setpoint for D11-N402
)
could be calculated using Equation (6-7). However, during these planned l
releases, the concentrations will almost always be so low (due to dilution) that i
the D11-N402 Monitor will not indicate measurable levels. The CWR decant line i
design flow is 10,000 gpm; and the maximum liquid radwaste release rate is 50 gpm, providing a 200:1 dilution. The radioactive material concentration of B TCH liquid releases is typically in the range of 10-7 to 10-4 pCi/ml. With a nominal 200:1 dilution (actual dilution has been greater since in actual releases the decant line flow rate has been about 18,000 gpm), the CWR decant line monitor would monitor diluted activity in the range of 5 x 1010 to 5 x 10'7 pCi/ml. D11-N402 Monitor response at these levels would be 0.1 to 100 cpm, depending on the particular radionuclides mixture and corresponding instrument response. These response levels are less than the monitor background levels.
In lieu of routinely adjusting the D11-N402 setpoints, generic, conservative setpoints have been established based on an analysis of nuclides seen in actual liquid discharges and on the primary calibration sensitivity curve.
i 1
ODCM 6.0 Rsvision 7 Page 6.0-11 i
6.3.4 Alarm Setpoint for GSW and RHR System Radiation Monitors Levels of radioactive material detectable above background at Radiation Monitor D11-N008 would be one of the first indicators of contamination of the General Service Water (GSW) System and the CWR. Likewise, for the Residual
~
Heat Removal (RHR) System, the D11-N401 A and B Monitors would be one of the first indicators of contamination and subsequent contamination of the CWR.
Therefore,' to provide early indication and assure prompt attention, the alarm setpoints for these monitors should be established as close to background as possible without incurring a spurious alarm due to background fluctuations. This level is typically around three times background, if the GSW System or RHR System becomes contaminated,it may become necessary to raise the radiation monitor setpoints. The alarm setpoints should be re-evaluated to provide the CR operator a timely indication of further increasing activity levels in the GSW or RHR System without spurious alarms.
The method for this re-evaluation is the same as described above - the alarm setpoint established at three times its current reading. No regulatory limits apply for establishing a maximum value for these alarm setpoints since these monitors are located on plant systems and ~do not monitor final release points to the environment. However, as a practical matter, upper limits on the alarm setpoints can be evaluated using the methods of ODCM Section 6.3.1 based on the actual system flows, dilution and release paths in effect at the time.
6.3.5 Alarm Response - Evaluating Actual Release Conditions Normally, liquid release rates are controlled and alarm setpoints are established to ensure that the release does not exceed the concentration limits of ODCM 3.11.1.1 at the discharge to Lake Erie. However,if either Monitor D11-N007 or D11-N402 or the CST Discharge Monitor alarms during a liquid release, it becomes necessary to re-evaluate the release conditions to determine compliance with ODCM 3.11.1.1. Following an alarm, the actual release conditions should be determined. Radioactive material concentrations should be evaluated by sampling the effluent stream or resampling the waste tank.
Discharge flow and dilution water flow should be redetermined.
To perform this evaluation, the following equation may be used for all nuclides, or dissolved and entrained noble gases may be evaluated separately from other nuclides using this equation:
~
~
C, RR
, (l + BF) g,
< MPC,,
ODCM-6.0 Rsvision 7 Page 6.012 where:
measured concentration of radionuclides iin the effluent Ci
=
i-stream (pCi/ml) the MPC value for radionuclides i: ten times the 10 CFR 20, MPCi
=
Appendix B, Table 2, Column 2 value (pCi/ml); 2 E-04 pCi/mi for dissolved or entrained noble gases actual release rate of the liquid effluerst at the time of the alarm, RR
=
gpm actual dilution circulating water flow at the time of the release DF
=
alarm, gpm H3F,BF =
as previously defined l
NOTE: For alarm on D11-N402 (CWR decant line), the Release Rate RR is the l
Dilution Water Flow DF and the DF term drops out of the equation.
6.3.6 Liquid Radwaste Monitor Setpoint Determination with Contaminated l
Circulating Water Heservoir 1
in the event the CWR is determined to contain radioactive material, the effective dilution capacity of the CWR is reduced as a function of the MPCF, To determine the available dilution flow capacity the MPCF for the CWR is determined using equation (6-2). The MPCF of the CWR is used to determine l
the available dilution flow as follows:
l l
CWR Dilution Flow = CWR Decant Flow Rate (GPM) * (1-CWR MPCF) l-j (6-9) l
, The resulting dilution flow rate is substituted in equation (6 3) to determine the maximum allowable release rate for discharges from the reawaste system.
Substituting the available CWR dilution flow from equation (6-9), the Liquid Radwaste Monitor maximum release rate can be determined using equation (6 3).
Once the available dilution flow and maximum allowable release rate have been determined the radwaste monitor setpoint can be determined using l
equation (6-5).
i
ODCM-6.0 Rsvision 7 Page 6.0-13 6.4 Contaminated GSW or RHR System - Quantifying anel Controlling Releases The GSW Radiation Monitor (D11-N008) provides an indication of contamination of this system. The Monitors D11-N401 A and B perform this function for the RHR System.
i Also, the CWR Decant Line Radiation Monitor monitors all liquid release.s from the plant and would record any release to Lake Erie from either of these systems if contaminated.
As discussed in ODCM Section 6.2.2, sampling and analysis of the CWR System is required only if this system is contaminated, as would be indicated by D11-N402 or D11-N008. Nonetheless, periodic samples are collected from the CWR System to verify absence of contamination. Although not required by the ODCM, periodic sampling and analysis of the RHR System is also performed since it also is a potential source of contamination of the CWR and subsequent releases to Lake Erie. If contamination is found, further releases from the applicable system (GSW or RHR) via the CWR decant l
line must be evaluated and controlled to ensure that releases are maintained ALARA.
The following actions will be considered for controlling releases.
Sampling frequency of the applicable source (GSW or RHR System) and the CWR will be increased until the source of the contamination is found and controlled. This frequency may be relaxed after the source of contamination has been identified and isolated.
Gamma spectral analysis will be performed on each sample.
i The measured radionuclides concentrations from the gamma spectral analysis y 11 1
be compared with MPC (Equation 6-2) to ensure releases are within the limits of l
ODCM 3.11.1.1.
Based on the measured concentrations, the setpoint for the CWR Decant Line Radiation Monitor (D11 N402) will be determined as specified in Section 6.3.2. If the calculated setpoint based on tne measured distribution is greater than the i
current setpoint (see ODCM Section 6.3.3) no adjustment to the setpoint is required.
l Samples will be composited in accordance with ODCM Table 4.11.1.1.1-1 for monthly analysis for H 3 and gross alpha and for quarterly analysis for Sr-89,90 and Fe 55.
Each sample will be considered representative of the releases that have occurred since the previous sample. For each sample (and corresponding release period), the volume of liquid released to the lake will be determined based on the measured CWR decant line cumulative flow.
From the sample analysis and the calculated volume released, the total l
radioactive material released will be determined and considered representative of the release penod. Cumulative doses will be determined in accordance with ODCM Section 6.5.
l
I 1
ODCM 6.0
)
R vision 7 i
Page 6.0-14
)
6.5 Liquid Effluent Dose Calculation - 10 CFR GO The parameters of the liquid release (or estimated parameters, for a pre-release calculation) may be used to calculate the potential dose to the public from the release (o'r planned release). The dose calculation provides a conservative method for estimating the impact of radioactive effluents released by Fermi 2 and for comparing that impact against
]
limits set by the NRC in the Fermi 2 ODCM. The limits in the Fermi 2 ODCM are specified 1
as quarterly and calendar year limits. This assures that the average over the year is kept l
as low as reasonably achievable.
6.5.1 MEMBER OF THE PUBLIC Dose - Liquid Effluents l
ODCM 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from Fermi 2 to:
during any calendar quarter; j
s 1.5 mrem to total body s 5.0 mrem to any organ during any calendar year;
)
s 3.0 mrera to total body l
s 10.0 mren,'o any organ j
L ODCM 4.11.1.2 requires that quarterly and annual cumulative dose due to liquid effluents be determined at least once per 31 days. The calculation of the i
potential doses to MEMBERS OF THE PUBLIC is a function of the radioactive i
material releases to the lake, the subsequent transport and dilution in the exposure pathways, and the resultant individual uptake. At Fermi 2, pre-operational evaluation of radiation exposure pathways indicated that doses from I
consumption of fish from Lake Eric provided the most conservative estimate of' i
doses from releases of radioactive liquids. However, with the proximity of the water intake for the City of Monroe,it must be assumed that individuals will consume drinking water as well as fish that might contain radioactivity from discharges into Lake Erie.
Study of the currents in Lake Erie indicates that the current in the Lagoona Beach embayment carries liquid effluents from Fermi 2 north along the coast part of the time and south along the coast part of the time. When the current flows north, liquid effluents are carried away from the Monroe Water intake, so only the fish consumption exposure pathway must be considered.
When the current flows south, toward the Monroe Water intake, both fish consumption and drinking water consumption exposure pathways must be considered. To ensure conservatism in the dose modeling, the combined fish and drinking water pathway is used for evaluating the maximum hypothetical dose to a MEMBER OF THE PUBLIC from liquid radioactive effluents. The following calculational methods may be used for determining the dose or dose commitment due to the liquid radioactive effluents from Fermi 2:
i
i i
I ODCM-6.0 Revision 7 Page 6.0-15 D, = 1.67 E - 02
- VOL * [(q
- 4)
(6 10) where:
Do
= dose or dose commitment to organ o or total body (mrem) due to release of a single tank site-specific ingest.on dose commitment factor to the total body or Aio
=
any organ o for radionuclides I (mrem /hr per pCi/ml) concentration of radionuclides iin undiluted liquid effluent Ci
=
representative of the volume VOL (pCi/ml) l total volume of liquid effluent released (gal)
VOL
=
average dilution water flow (CWR decant line) during tank DF
=
release (gal / min) 5, near field dilution factor Z
=
(Derived from Regulatory Guide 1.109, Rev 0) 1.67 E-02 = 1 hr/60 min l
The site specific ingestion dose / dose commitment factors (Ajo) represents 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 l
rates. Values of Aio are presented in Table 61. They were derived in accordance with guidance of NUREG-0133 from the following equation:
l 4, = 1.14 E + 05 ((U, / D, )+ (U,
- BE)] DE (6 11) j.
l where:
21 kglyr adult fish consumption UF
=
730 liters /yr adult water consumption UW
=
l 15.4. additional dilution from the near field to the water intake DW
=
for the City of Monroe (Net dilution factor of 77 from discharge point to drinking water intake, Fermi 2 UFSAR, Chapter 11, Table 11.211)
Bioaccumulation factor for radionuclides i in fish from Table 6 2 BFi
=
(pCi/kg per pCi/ liter)
ODCM-6.0 R: vision 7 Page 6.0-16 dose conversion factor for nuclide i for adults in orgen o from DFi
=
Table E-11 of Regulatory Guide 1.109 (mrem /pCl) 1.14 E + 05 = 10 (pCi/ uCi)
- 10'(ml/ kg) 6 8760 (hr / yr)
The radionuclides included in the periodic dose assessment required by ODCM 3.11.1.2 are those identified by gamma spectral analysis of the liquid -
)
waste samples collected and analyzed per the requirements of ODCM l
Table 4.11.1.1.1-1. 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 ODCM 3.11.1.2. The dose analysis for radionuclides requiring j
radiochemical analysis will be performed after receipt of results of the analysis of j
the composite samples. In keeping with the required analytical frequencies of ODCM Table 4.11.1.1.1-1, tritium dose analyses will be performed at least monthly; Sr 89, Sr-90 and Fe-55 dose analyses will be performed at least quarterly.
6.5.2 Simplified Liquid Effluent Dose Calculation In lieu of the individual radionuclides dose assessment presented in Section 6.5.1, L
the following simplified dose calculavon may be used for demonstrating l
compliar.ce with the dose limits of ODCM 3.11.1.2. (Refer to Appendix A for the l
derivation of this simplified method ) Equations (6-12) and (613) are to be applied to the release of a single tank.
f Total Body D* = 9.69 E + 03
- VOL, [C' DF'Z (6-12)
Maximum Organ D" = 1.18 E + 04
- VOL
- t G L
DF'Z (6-13)
ODCM 6.0 Revision 7 Page 6.0-17 l
where:
Ci concentration of radionuclides iin undiluted liquid effluent
=
representative of the volume VOL (pCi/ml)
VOL volume of undiluted liquid effluent released (gal)
=
DF average dilution water flow (CWR decant line) during tank
=
release (gal / min)
Z 5, near field dilution factor (derived from Regulatory Guide
=
1.109, Rev 0) conservatively evaluated total body dose (mrem)
Db t
=
Dmax conservatively evaluated maximum organ dose (mrem)
=
9.69 E + 03 =
0.0167 (hr/ min)
- 5.80 E + 05 (mrem /hr per pCi/ml, Cs 134 total body dose factor from Table 6.0-1)
)
1.18 E + 04 =
0.0167 (hr/ min)
- 7.09 E + 05 (mrem /hr per pCi/mi, Cs 134 liver dose factor from Table 6.0-1) l 6.5.3 Contaminated CWR System - Dose Calculation if the CWR System becomes contaminated, releases via the CWR System to Lake Erie must be included in the evaluation of the cumulative dose to a MEMBER OF THE PUBLIC as required by ODCM 3.11.1.2. ODCM Section 6.4 described the methods for quantifying and controlling releases from the CWR System.
For calculating the dose to a MEMBER OF THE PUBLIC, Equation (610) remains applicable for releases from the GSW System with the following assumptions:
DF, Dilution Flow, is set equal to the average CWR decant line flow rate over the release penod.
Ci, Radionuclides Concentration. is determined as specified in ODCM Section 6.4.
VOL, Volume Released, is set equal to the total volume of the discharges to Lake Erie via the CWR decant line as specified in Section 6.4.
t I
L___________
ODCM-6.0 R: vision 7 Page 6.0-18 6.6 Liquid Effluent Dose Projections 10 CFR 50.36a requires licensees to maintain and operate the Radwaste System to ensure releases are maintained ALARA. This requirement is implemented through ODCM 3.11,1.3. This section requires that the Liquid Radioactive Waste Processing System be used to reduce the radioactive material levels in the liquid waste prior to release when the projected dose in any 31 day period would exceed:
0.06 mram to the total body, or 0.2 mrem to any organ When the projected doses exceed either of the above limits, the waste must be processed by the Liquid Radwaste System nrior to release. This dose criteria for processing is established at one forty eighth of the design objective rate (3 mistn/yr, total body or 10 mrem /yr any organ) in any 31 day period.
l I
The applicable Liquid Waste Processing System for maintaining radioactive material releases ALARA is the Mixed Bed Demineralizers as delineated in Figure 61. Alternately, the Waste Evaporator (presented in the Fermi 2 UFSAR, Section 11.2) can be used to meet the NRC ALARA design requirements. It may be used in conjunction with or in lieu of the Mixed Bed Demineralizers to meet the waste processing requirements of ODCM 3.11.1.3.
Each BATCH release of liquid radwaste is evaluated to ensure that cumulative doses are maintained ALARA. In keeping witn the requirements of ODCM 3.11.1.3, dose projections are made at least once per 31 days to evaluate the need for additional radwaste processing to ensure future releases are maintained ALARA.
The following equations may be used for the dose projection calculation:
D, = D,(31/ d)
(6-14)
D
= D,m(31/ d) am r (6-15) where.
the total body dose projection for the next 31 day period (mrem)
D bp t
=
NOTE: The reference calendar quarter is normally the current calendar quarter. If there have been liquid releases in the previous quarter but not in the current quarter, the previous quarter should be used as the reference calendar quarter.
the cumulative total body dose for all releases to date in the reference Dtb
=
calendar quarter (normally the current quarter) as determined by equation (6-10) or (612) (mrem)
ODCM 6.0 Revision 7 Page 6.0-19 the maximum organ dose projection for the next 31 day period (mrem)
Dmaxp
=
the cumulative maximum organ dose for all releases to date in the Dmax
=
reference calendar quarter as determined by Equation (6-10) or l
(6-13) (mrem) the number of days from the beginning of the reference calendar quarter d
=
to the date of the dose projection evaluation.
the number of days in projection 31
=
in the case of Condensate Storage Tank releases only, it may be possible to make an accurate dose projection without relying entirely on releases during the reference calendar quarter. If the above equations are not used for the portion of the dose projection pertaining to CST releases, the method used shall be in accordance with the dose projection procedure.
l 1
ODCM-6.0 Revision 7 Page 6.0-20 TABLE 6.0-1 Fermi 2 Site Specific Liquid Ingestion Dose Commitment Factors Aio (mrem /hr per uCi/ml)
Nuclide Bone Liver T Body Thyroid kidney Lung GI LLI H-3 7.94E 1 7.94 E-1 7.94E-1 7.94E-1 7.94E 1 7.94E 1 C-14 3.13E+4 6.26E+ 3 6.26 E+3 6.26E+3 6.26E+3 6.26E+3 6.26E+3 Na 24 4.16E+2 4.16E+2 4.16E+2 4.16E+2 4.16E+2 4.16E+ 2 4.16E+2 1.56E+5 P-32 1.39E+6 8.62 E+4 5.36 E+4 1.29E+0 7.70E-1 2.84E 1 1.71 E+0 3.24E+2 Cr 51 4.40E+3 8.40E+2 1.31 E+3 1.35E+4 Mn-54 3.53E+3 1.11 E+2 1.96E+ 1 1.41 E+2 Mn 56 2.59E+2 2.67E+2 Fe 55 6.73E+2 4.65E+2 1.08E+2 6.98E+2 8.32 E+3 Fe-59 1.06E+3 2.50E+3 9.57E+ 2 Co-57 2.19E+ 1 3.64 E+ 1 5.55E+2 1.89E+3 Co 58 9.32E+ 1 2.09E+2 5.03E+3 2.68E+2 5.90E+2 Co-60 Ni-63 3.18E+4 2.21 E+3 1.07 E+3 4.60E+2 4.26 E +2 Ni-65 1.23E+2 1.68E+1 7.66E+0 8.88E+ 2 Cu-64 1.04 E+ 1 4.89E+0 2.63E+1 4.65E+4 Zn-65 2.32 E+4 7.38 E+4 3.34 E +4 4.94E+4 6.14E+1 1.42E+1 Zn 69 4.94 E+1 9.44 E+1 6.57E+0 2.62E+3 Br 82 2.28E +3 4 06E+1 5.85E+ 1 Br-83 5.27E+1 4.13E 4 Br 84 Br 85 2.16E + 0 1.01E 15 1.99E+4 1.01 E+ 5 4.71 E +4 Rb 86 Rb-88 2.90E+ 2 1.54 E + 2 4.01 E 9 Rb 89 1.92E +2 1.35 E + 2 1.12E 11 Sr-89 2.38E +4 6.83E+2 3.81 E+ 3 144 E+ 5 Sr90 5.85E+5 1.69E+4 Sr 91 4.38E+2 1.77E.1 2.09E+ 3 Sr-92 1.66E+ 2 7.18E +0 3.29E+3 Y-90 6.28E-1 1.68E 2 6.66E+ 3 Y-91m 5.93E 3 2.30E 4 1.74 E-2 Y 91 9.20E+0 2.46E 1 5.06E+3 Y 92 5.51 E 2 1.61 E 3 9.66E+2 Y 93 1.75E 1 4.83E 3 5.55E+3 2.04E-1 4.11 E+ 2 Zr.95 4.04E 1 1.30E 1 8.78E 2
' Zr 97 2.24E 2 4.51E 3 2.06E 3 6.81 E-3 1.40E+3 Nb-95 4.47E+2 2.49E + 2 1.34E.2 2.46E+2 1.51 E+6 Nb 97 3.75E+0 9.48 E-1 3 46E 1 1.11 E+0 3.50E+3 Mo-99 1.26E +2 2 41E.1 2.86E+2 2.93 E+2 Tc 99m 1.02E 2 2.88E 2 3 67E 1 4.38E 1 1.41E 2 1.71 E+ 1 Tc 101 1.05E 2 1.51 E-2 1.48E 1 2.72E 1 7.73E 3 4.54E 14
ODCM-6.0 Revision 7 Page 6.0-21 TABLE 6.01 Fermi 2 Site Specific Liquid Ingestion Dose Commitment Factors Ago (mrem /hr per uCi/ml)
Nuclide Bone
. Liver T Body Thyroid Kidney Lung GI-LLI 6.34E+2 2.07E+1 2.34 E+0 Ru-103.
5.43E+0 2.76E+2 5.84E+0 1.78E 1 Ru 105 4.52E-1 5.22 E+ 3 1.56E+2 1.02E+1 Ru 106 8.07E+1 Rh-103m Rh 106 1
6.59E+2 3.17E+0 Ag-110m '
1.75E+0 1.61 E+0 9.59E 1 1.70E+1 6.20E+ 2 Sb-124 2.18E+1 4.13E 1 8.66E+0 5.29E-2 1.08E+1 1.54 E+2 Sb 125 1.40E+1 1.56E 1 3.32 E+0 1.42E 2 Te-125m 2.58E+3 9.35E+2 3.46E+2 7.76E+2 1.05E+4 1.03E+4 2.19E+4 Ts-127m 6.52E+3 2.33E+3 7.94E+2 1.67E+3 2.65E+4 8.36E+3 Ts 127 1.06E+2 3.80E+1 2.29E+ 1 7.85E+1 4.31 E+2 5.58E+4 Ts 129m 1.11 E+4 4.13 E+3 1.75E+3 3.80E+3 4.62E+4 2.28E+1 To-129 3.02E+1 1.14 E+ 1 7.37E+0 2.32 E+1 1.27E+2 Ts 13tm 1.67E+3 8.15E+2 6.79E+2 1.29E+3 8.25E+3 o.00E+4 Te-131 1.90E+1 7.93E+ 0 5.99E+0 1.56E+1 8.31 E +1 2.69E+0 7.42 E+4 Te-132 2.43E+3 1.57E+ 3 1.47E+3 1.73E+3 1.51 E+4 7.93E+ 1 l130 3.12 E+1 9.21 E+ 1 3.64 E+ 1 7.81 E+3 1.44E+2 6.49E+1 131 1.72 E+2 2.46E+2 1.41 E+ 2 8.06E+4 4.21 E+2 4.21 E+ 0 1-132 8.39E+0 2.24E+1 7.85E+0 7.85E+2 3.57E+1 9.17E+ 1 1133 5.87E+1 1.02E+2 3.11 E +1 1.50E+4 1.78E+2 1.04E 2 1-134 4.38E+0 1.19E+ 1 4.26E+0 2.06E+2 1.89E+1 1135 1.83E+1 4.79E+1 1.77E+ 1 3.16E+3 7.68E+1 5.41 E+ 1 2.30E+ 5 7.625+4 1.24 E+4 Cs 134 2.98 E+ 5 7.09E4 5 5.80E+5 Cs 136
- 3.12E+4 1.23E45 8.87E+4 6.85E+4 9.40E+3 1.40E+4 1.77E+ 5 5.90E+4 1.01 E+4 Cs 137 3.82E+ 5 5.22E+5 3 42E+5 Cs 138 2.65E+ 2
~5.22E+2 2.59E+2 3.84 E+2 3.79E+ 1 2.23E 3 Ba 139 1.45E 0 1.04E 3 4.25E-2 9.68E 4 5.87E 4 2.58 E+0 1.30E-1 2.19E 1 6.26E+2 -
Ba-140
' 3.04E+2 3.82E 1 1.99E+ 1 Ba 141 7.06E 1 5.33E 4 2.38E 2 4.96E 4 3.03E 4 3.33E 10 Ba 142
- 3.19E 1 3.28E 4 2 01E 2 2.77E 4 1.86E-4 4.49E 19 6.04E+3 La 140 1.63E 1 8.22E 2 2.17E 2 2.77E+1 La 142
' 8.35E 3 3.80E 3 9 46E-4 1.89E+2 2.29E 2 Ce-141 7.30E 2 4.94E 2 5 60E 3 4.19E 3 3.56E+2 Ce 143 1.29E 2 9.51 E+0 1.05E 3 1.29E+3 9.44E 1 Ce-144 3.81 E+0 1.59E +0 2.04E 1 1.39E 1 2.63E+3 Pr143 6.00E 1 2.41E 1 2.98E 2 2.83E-10 4.60E 4 Pr 144 1.96E 3 8.16E 4 9 98E 5 2.28E+ 3 Nd 147 4.10E 1 4.74E 1 2.84E 2 2.77E-1 8.12E+4 W 187 2.96E+2 2.48E+2 8.66E + 1 7.04 E+ 2 1.07E 2 Np 239 3.49F 2 3.43E 3 1.89E 3 l
l l
ODCM-6.0 Revision 7 Page 6.0 22 TABLE 6.0-2 Bioaccumulation Factors (BFi)
(pCl/kg per pCl/ liter)*
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+01 Rh 1.0E+01 Ag 2.3 E+00 Sb 1.0E+00 Te 4.0E+02 1
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 f rom 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.
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Production - Fermi 2 ODCM-7.0 Offsite Dose Calculation Manual Revision 8 Page 7.0-1 l
GASEOUS EFFLUENTS l
7.0 GASEOUS EFFLUENTS 7.1 Radiation Monitoring Instrumentation and Controls 7.1.1 Effluent Monitoring - Ventilation System Releases The gaseous effluent monitoring instrumentation required at Fermi 2 for controlling and monitoring radioactive effluents are specified in ODCM 3.3.7.12.
The monitoring of each identified gaseous effluent release point must include the following:
Noble Gas Activity Monitor lodine Sampler (sample cartridge containing charcoal or silver zeolite)
Particulate Sampler (filter paper)
Sampler Flow Rate Monitor Meeting these requirements, a total of seven Eberline SPING Monitoring Systems are installed on the six gaseous release points (Onsite Storage Facility, Service Building, Radwaste Building, Turbine Building, Reactor Building Exhaust Plenum, and Standby Gas Treatment System Division 1 and Division 2). The SPING Monitor outputs are reco-ded electronically in the CT-28 Controi Terminal in the Main Control Room.
In general, a reading exceedingi the High alarm setpoint of the SPING Monitors causes an alarm in the Control Room. Fermi 2 ODCM Table 3.3.7.12-1 identifies these alarm functions.
7.1.2 Main Condenser Offgas Monitoring ODCM Table 3.3.7.12-1 and Technical Specification Table 3.3.7.12-1 specify monitoring requirements for the Offgas System at the 2.2 minute delay line. The following monitors are requeed:
ODCM 7.0 Revision 8 Page 7.0-2 l
Hydrogen Monitor - used to ensure the hydrogen concentration in the Offgas Treatment System is maintained less than 4% by volume as required by Technical Specification 3.11.2.6.
l l
Noble Gas Activity Monitor - used to ensure the gross activity release rate l
is maintained within 340 millicuries per second after 30 minute decay as l
required by Technical Specification 3.11.2.7.
These two monitors perform safety functions. The Hydrogen Monitor monitors the potertial explosive mixtures in the Offgas System. The Noble Gas Monitor monitors the release rate from the main condenser ensuring doses at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR 100 in the event this effluent is inadvertently discharged 5
directly to the environment bypassing the Offgas Treatment System.
7.1.3 Reactor Building Ventilation Monitors (Gulf Atomic)
The Gulf Atomic Monitors (D11-N408 and 410) on the Reactor Building Ventilation System provide on high radiation levels (above alarm setpoint) initiation of SGTS, isolation of drywell vent / purge, isolation of the RB and Contro!
Center Ventilation Systems and initiation of Control Center recirculation mode ventilation. These monitors and functions are not required by Fermi 2 ODCM but are important in controlling containment venting / purging.
7.2 Sampling and Analysis of Gaseous Effluents The program for sampling and analysis of gaseous waste is proscribed in Fermi 2 ODCM Table 4.11.2.1.2-1. This table distinguishes two types of gaseous releases:
(1) containment PURGE, treated as BATCH releases, and (2) discharges from the Reactor Building Exhaust Plenum (including Standby Gas Treatment System (SGTS) when operating), and otner building ventilation exhausts, treated as CONTINUOUS releases.
7.2.1 Containment PURGE ODCM Table 4.11.2.1.2-1 requires that samples be collected and analyzed before each primary containment PURGE. Sampling and analysis is required within eight hours before starting a PURGE. ODCM Table 4.11.2.1.2-1 Footnote j and ODCM 4.11.2.8.2 also require that if the purging or venting is through the Reactor Building ventilt. tion, rather than through SGTS, and if the primary containment radiation monitoring system is INOPERABLE or in alarm condition, sampling and analysis is required within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during venting or purging of the primary containment. The required analyses must include principal gamma emitters and, if a pre vent or pre-purge sample, tritium.
ODCM-7.0 i
Revision 8 Page 7.0-3 i
For a planned containment PURGE, the results of the samples and analyses may be used to establish the acceptable release rate and radiation monitor alarm l
setpoint in accordance with ODCM Section 7.3. This evaluation may be necessary to ensure compliance with the dose rate limits of ODCM 3.11.2.1. In j
practice, release flow rates are fairly constant and these calculations are necessary only if a threshold value of nuclide concentration in the primary containment atmosphere is reached. The alarm setpoints of the primary containment atmosphere monitor, the Reactor Building ventilation exhaust monitors, and the Reactor Building and SGTS SPING monitors are set to ensure that release routes are continuously monitored and controlled in accordance with 10 CFR PO or limits specified in the ODCM.
l 7.2.2 Ventilation System Releases.
l ODCM Table 4.11.2.1.2-1 requires continuous samples of releases from the RB Exhaust Plenum, Standby Gas Treatment System, Radwaste Building, Turbine Building, Service Building, and Onsite Storage Facility. The table specifies the following program:
Once per week, analysis of an adsorbent sample of I-131 and 1133, plus
. analysis of a particulate sample for principal gamma emitters.
Once per month, analysis of a composite particulate sample of all releases (by release point) that month for gross alpha activity.
Once per quarter, analysis of a composite particulate sample of all releases that quarter for Sr 89 and Sr 90.
i 1
Once per month, analysis of a grab sample for principal gamma emitters (noble gases and tntium).
t ODOM Table 4.11.2.1.21 also requires continuous monitoring for noble gases.
l This requirement is met by the SPING Monitors on each of the plant gaseous release points.
The ODCM requires more frequent sampling and analysis following reactor startup, shutdown, or change in thermal power exceeding 15% within one hour, i
The ODCM allows exceptions to this increased sampling schedule provided that neither one of the following conditions exist:
Primary coolant dose equivalent 1131 has increased more than a factor of three.
Reactor Building SPING noble gas monitor has increased more than a factor of three.
ODCM 7.0 Revision 8 Page 7.0-4 Grab samples of the Fuel Pool Ventilation Exhaust are required tritium analysis once per seven days wnenever spent fuel is in the Spent Fuel Pool. Also, grab samples for tritium are required when either the reactor well or the dryer separator poolis filled. These samples are taken at the Reactor Building
~
Exhaust Plenum and Standby Gas Treatment System (SGTS) when operating.
7.3 Gaseous Effluent Monitor Setpoint Determination 7 3.1 Ventilation System Monitors Per the requirements of ODCM 3.3.7.12, alarm setpoints shall be established for
}
the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of ODCM 3.11.2.1. This section limits releases to a dose rate at the SITE BOUNDARY of 500 mrem / year to the total body or 3000 mrem / year to the skin. From a grab sample analysis of the applicable release (i.e., grab sample of the primary containment or Ventilation System release), the radiation monitoring alarm setpoints may be
)
established by the following calculational method. The measured radionuclides J
concentrations and release rate are used to calculate the fraction of the allowable release rate, limited by ODCM 3.11.2.1, by the equation:
1.67E + 01
- x / G
- VF * [(C,
- K,)
500 (7-1) 1.67E + 01
- x / O
- VF * [(C, * [L, + 1.lM,])
3000 (7-2)
Where:
fraction of the allowable release rate based on the identified FRAC
=
radionuclides concentrations and the release flow rate
% /0 annual average meteorological dispersion to the controlling
=
site boundary location from Table 7.0-3 (sec/m3) or plant procedures VF
=
Ventilation System flow rate for the applicable release point and monitor (liters / minute)
Ci cer, centration of noble gas radionuclides i at release point as
=
determined by gamma spectral analysis of grab sample (pCi/cc) (If a noble gas is not detected at the reactor building release point, its concentration at this release point may be calculated by applying a dilution factor to its concentration in an Offgas Vent Pipe sample.)
ODCM 7.0 Rsvision 8 Page 7.0-5 total body dose conversion factor for noble gas Ki
=
radionuclides i (mrem /yr per pCi/m3, from Table 7.0-2)'
beta skin dose conversion factor for noble gas radionuclides i Li
=
(mrem /yr per pCi/m3, from Table 7.0-2).
gamma air dose conversion factor for noble gas Mi
=
radionuclides i (mrad /yr pei pCi/m3, from Table 7.0-2) mrem skin d( se per mrad gamma air dose (mrem / mrad) 1.1
=
total body dose rate limit (mrem /yr) 500
=
l skin dose rate limit (mrem /yr) 3000
=
1 E + 03 (cc/ liter) * (1/60) (min /sec) 1.67 E + 01
=
Based on the more limiting (i.e., higher) value of FRAC as determined above, the alarm setpoints for the applicable monitors may be calculated by the equation:
' SP S (AF * [C,) + Bkg FRAC (7-3)
Where:
alarm setpoint corresponding to the maximum allowable release SP
=
rate (pCi/cc) background of the monitor (pCi/cc)
Bkg
=
administrative allocation factor (Table 7.0-1) for the specific AF
=
monitor and type release, which corresponds to the fraction of the total allowable release rate that is administratively allocated to the individual release points.
concentration of Noble Gas Radionuclides i as determined by Ci
=
l gamma spectral analysis of grab sample (pCi/cc)(If a noble gas I
is not detected at the reactor building release point, its concentration at this release point may be calculated by applying a dilution factor to its concentration in an Offgas Vent Pipe l
sample.) Note: If the monitor channel in question was showing a response to the effluent at the time of the grab sample, this response minus background may be used in lieu of the summed l
grab sample concentrations.
l l
r
1 l
ODCM-7.0 Revision 8 Page 7.0-6 The Allocation Factor (AF) is an administrative control imposed to ensure that combined releases from all release points at Fermi 2 will not exceed the regulatory limits on release rate from the site (i.e., the release rate limits of ODCM 3.11.2.1). From the Fermi 2 design evaluation of gaseous effluents l
presented in the UFSAR Section 11.3, representative values have been determined for AF. These values are presented in Table 7.0-1. These values may be changed in the future as warranted by operational experience, provided the site releases comply with ODCM 3.11.2.1. In addition to the allocation factor, safety factors which have the effect of lowering the calculated setpoints may be applied. When determining the Noble Gas M nitor calibration constant, the l
monitor sensitivity for Xe-133 may be used in lieu of the sensitivity values for the I
Individual radionuclides. Because of its lower gamma energy and corresponding monitor response, the Xe-133 sensitivity provides a conservative value for alarm setpoint determination. Alternatively,if the monitor channelin question frequently shows a response to a mix of isotopes whose concentrations can be determined, the calibration constant may be determined from this type of data without reference to primary calibration data.
7.3.2 Setpoint Determination with No Nuclides Detected When noble gas concentrations for a release point cannot be determined from grab samples, there are two options for setpoint determination. First, the setpoint may be set slightly above monitor background (e.g. 2 to 3 times background). This approach may be used when releases are not expected from a particular release point. Second, the equations of Section 7.3.1 may be used I
with noble gas concentration values based either on UFSAR tables or on values from a release point for which concentrations have been determined (e.g. reactor building exhaust plenum). When this method is used, a safety factor should be used in the setpoint calculation.
7.3.3 -
Gaseous Effluent Alarm Response - Evaluating Actual Release Conditions The monitor alarm setpoint is used as the primary method for ensuring and demonstrating compliance with the release rate limits of ODCM 3.11.2.1. Not exceeding alarm setpoints constitutes a demonstration that release rates have been maintained within the ODCM limits. When an effluent Noble Gas Monitor exceeds the alarm setpoint, an evaluation of compliance with the release rate
.]
limits must be performed using actual release conditions. This evaluation q
requires collecting a sample of the effluent to establish actual radionuclides
]
l concentrations and permit evaluating the monitor response. The following i
equations may be used for evaluating compliance with the release rate limit of ODCM 3.11.2.1a:
D,,, = 1.67E + 01
- x / O
- VF * [(K,
- C,)
(7-4)
D, = 1.67E + 0!
- x / O
- VF * [([L, + 1.lM,]* C,)
(75)
]
l
____a
I ODCM-7.0 -
Revision 8 Page 7.0-7 1
l Where:
total body dose rate (mrem /yr)
Db l
t
=
. skin dose rate (mrem /yr)
Ds
=
%IO atmospheric dispersion to the controlling SITE BOUNDARY
=
i.
location (sec/m3) i Ventilation System release rate (liters /n in) l VF
=
concentration of radionuclios i as measured in the grab Ci
=
sample or as correlated from the SPING Noble Gas Monitor reading (pCi/cc) total body dose conversion factor for noble gas radionuclides I Ki
=
(mrem /yr per pCi/m3, from Table 7.0-2) beta skin dose conversion factor for noble gas radionuclides i Li
=
3 (mrem /yr per pCi/m, from Table 7.0-2) i gamma air dose conversion factor for noble gas radionuclides i Mi
=
I (mrad /yr per pCi/m3, from Table 7.0-2)
I mrem skin dose per mrad gamma air dose (mrem / mrad) 1.1
=
1.67 E + 01 =
1 E + 03 (cc/ liter) - (1/60) (min /sec)
The above equations may also be used to verify compliance with ODCM 3.11.2.1.a when noble gases are detected in penodic (e.g. monthly) effluent i
noble gas samples.
l l
7.4 Primary Containment VENTING and PURGING 7.4.1 Release Rate Evaluation L
l For primary containment VENTING or PURGING, an evaluation of acceptable release rate may be performed prior to the release. Based on the measured noble gas concentration in the grab sample collected per the requirements of ODCM Table 4.11.2.1.2-1, the allowable release rate from primary containment l
can be calculated by the following equation:
ODCM-7.0 Revision 8 Page 7.0-8 500
1.67 + 01
- x / Q * {(K,
- C,)
(7-6) or 3000
- AF RR*= 1.67E + 0l
- x / G * [ ( [L, + 1.lM,]* C,)
(7-7)
Where:
allowable releau rate so as not to exceed a dose rate of RRtb
=
500 mrem /yr, total body (liters / minute) allowable release rate so as not to exceed a dose rate of RRs i
=
3000 mrem /yr, skin (liters / minute) 1 allocation factor for the applicable release point from Table 7.0-1 AF
=
(default value is 0.5 for Reactor Building Exhaust Plenum) 4 total body dose rate lirnit (mrem /yr) 500
=
I skin oc rate limit (mrem /yr)
I 3000
=
The lesser value (RRtb or RRs) as calculated above may be used for establishing the allowable release rate for primary containment PURGING or VENTING, taking into account the fraction of the allocated release limit already accounted for by continuous releases from the proposed release point. As discussed in section 7.2.1, this evaluation is rarely necessary.
7.4.2 Alarm Setpoint Evaluation For a primary containment VENTING or PURGING, a re-evaluation of the alarm setpoint may be needed to ensure compliance with the requirements of ODCM 3.3.7.12. For the identified release path (RB Exhaust Plenum or SGTS) and associated effluent Radiation Monitor, the alarm setpoint should be calculated using Equations (71), (7-2) and (7-3). In Equations (7-1) and (7-2),
the value of the Ventilation Flow VF should be established at the total release flow rate, including the contribution from the PURGE or VENT. If the calculated alarm setpoint is greater than the current setpoint, no adjustments are necessary. As discussed in section 7.2.1, this setpoint evaluation is rarely necessary.
___..__-_____.___________-._m._a
l l
i ODCM-7.0
)
Revis. ion 8
)
Page 7.0-9 7.5 Quantifying Releases - Noble Gases The determination of doses in the environment from releases is dependent on the mixture l
of the radioactive material. Also, NRC Regulatory Guide 1.21 requires reporting of individual radionuclides released in gaseous effluents. Therefore, Detroit Edison must determine the quantities of the individual radionuclides released. For noble gases, these 4
l l
quantities must be based on actual noble gas grab samples.
l 7.5.1 Sampling Protocol i
As required by ODCM 3.11.2.1, a gas sample is collected at least monthly from each of the six gaseous release points (Reactor Building Exhaust Plenum, Standby Gas Treatment System, Radwaste Building, Turbine Building, Onsite Storage Facility, and Service Building). As discussed in ODCM Section 7.2.2, this gas sample is analyzed by gamma spectroscopy to identify individual radionuclides (noble gases). To date (May 1992) noble gases have been detected only in the reactor building effluent.
I in addition to these monthly samples from each release point, noble gas grab 1
samples from the Offgas Vent Pipe may be collected using the sample lines of the abandoned Offgas Vent Pipe Monitor (D11-N105 and D11-N106). Since noble gases are more concentrated at this point than at the Reactor Building Exhaust Plenum, a greater number of noble gases are detected at this point.
Sampling should be performed monthly at the Offgas Vent Pipe unless the reactor is shut down or noble gas concentrations increase sufficiently to allow l
I detection of all significant noble gas nuclides at the Reactor Building Exhaust l
Plenum.
1 For Containment PURGE / VENT, samples are collected prior to the initiation of j
the release and periodically throughout the release (see ODCM Section 7.2.1).
These samples are evaluated using Equations (7-4) and (7-5) to ensure that the site boundary dose rate limits of ODCM 3.11.2.1 are not exceeded. For an l
extended PURGE / VENT period (e.g., longer than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />), drywell airborne l
activity levels will equilibrate. After equilibrium is reached, the quantification of the PURGE / VENT can be adequately addressed by the periodic (typically weekly) sample and analysis of the Reactor Building Exhaust Plenum or Standby Gas Treatment System.
As required by ODCM Table 4.11.2.1.2-1, special samples are required of the RB Exhaust Plenum and SGTS following shutdown, startup or a THERMAL POWER change exceeding 15% within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. Exceptions to this special sampling are allowed as nded previously in ODCM Section 7.2.2.
l l
ODCM-7.0 Rsvision 8 Page 7.0-10 7.5.2 Release Concentration Determination for Reactor Building Exhaust Plenum l
in cases where both a RB Exhaust Plenum noble gas sample and an Offgas Vent Pipe (OGVP) sample have been taken, the RB Exhaust Plenum noble gas concentrations are determined as follows: First, the RB SPING channel 15 l
readings (above background) at the times the two samples were taken are
~
)
compared, and the noble gas concentrations for the sample taken at the lower RB SPING channel 15 reading are normalized to the higher RB SPING channel-1-5 reading. Second, a dilution factor relating OGVP concentrations to RB Exhaust Plenum concentrations is calculated by dividing'the RB Exhaust Plenum l
flow rate (nominally 9.43 E4 cfm) by the OGVP flow rate as indicated in the i
control room (N62 R808, blue pen). Third, the OGVP noble gas concentrations l
l are divided by this dilution factor. Fourth, the diluted OGVP noble gas i
concentrations are compared to the RB Exhaust Plenum noble gas concentrations. and the higher of the two concentration values for each nuclide is taken to be the RB Exhaust Plenum concentration for that nuclide. (For purposes of calculation, the concentrations of nuclides which are not detected are taken to be zero.) Fifth, the resulting RB Exhaust Plenum concentrations are corrected for variations during the release period by multiplying each concentration value by the average RB SPING channel 1-5 readir.g (above background) for the period divided by the higher of the two RB SPING channel i
1-5 sample readings (above background) at time the samples were taken.
1 These corrected values are then used as Ci in Equation (7-8) to determine the l
quantity of noble gases released.
1 7.5.3 Calculation of Activity Released The foliowing equation may be used for determining the release quantities from l
any release point based on the grab sample analysis l
Q, = 1.0E + 03
- VF T
- C; (7-8)
Where:
total activity released of radionuclides i(pCi)
Oi
=
Ventilation System release rate (liters / min)
=
total time of release period (min)
T
=
l 1.0 E + 03 =
milliliters per liter concentration of radionuclides i as determined by gamma spectral Ci
=
analysis of grab sample (pCi/cc) corrected for variations during release penod as described in Section 7.5.2 i
ODCM-7.0 Revision 8
^
4 Page 7.0-11 7.6 Site Boundary Dose Rate - Radiolodine and Particulate ODCM 3.11.2.1.b limits the dose rate to s1500 mrem /yr to any organ for 1-131,1133, tritium and particulate with half lives greater than 8 days. To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than'that corresponding to the sampling and analysis time period (nominally once per 7 days). The following equation may be used in the dose rate evaluation for 1131,1-133, and particulate with half lives greater than 8 days:
/
3 DR = h x / Q
- R,_m
- VFi
- 16.7.* [q r \\
i
.)
(7-9)
WherM total maximum organ dose rate for all release points (mrem /yr)
DR
=
%Q=
atmospheric dispersion factor for release point r to the controlling SITE
/
3 BOUNDARY location (sec/m ) from Table 7-3 or plant procedures R, _,.s i l 131 child thyroid inhalation pathway dose factor (mrem /yr per pCi/m3)
=
from Table 7-4 Average ventilation flow for release point r during release period (liters / min)
VFr
=
I Concentration of radionuclides I (I 131,1-133, or particulate with half life Cir
=
greater than 8 days) released from release point r during the appropriate release period (pCi/cc)- usually determined by gamma spectral analysis of effluent sample 1000 cc/ liter
- 0.0167 min /sec 16.7
=
. Release periods used in Equation (7 9) are the most recent periods evaluated for the different release points, and these periods may not be identical.
Alternatively, the site boundary dose rate may be evaluated using the highest individual isotopic dose factors for all age groups to calculate inhalation and ground plane exposure at the highest dispersion factor location at or beyond the site boundary,' as well as vegetation, milk, and meat exposure a' the garden, milk, and meat locations with the highest deposition factors. Dose rate due to tntium is currently evaluated by this method, and when tritium has been detected in gaseous effluents during the most recent release penod, the tritium dose rate must be added to the result from Equation (7-9) to evaluate l
compliance with ODCM 3.11.2.1.b.
I l
l
ODCM-7.0 Revision 8 Page 7.0-12 The dose rate evaluation described above may have to be performed more frequ'ently than once per week in order to meet the requirements of ODCM Table 4.11.2.1.2-1, footnote g: Daily sampling is required following startup, shutdown, or thermal power changes exceeding 15% in one hour if DEI has increased by a factor of 3 or if the applicable noble gas effluent monitor reading has increased by a factor,of 3.
7.7 Noble Gas Effluent Dose Calculations - 10 CFR 50 7.7.1 UNRESTRICTED AREA Dose - Noble Gases ODCM 4.11.2.2 requires that an assessment of releases of noble gases be performed at least once per 31 days to evaluate compliance with the quarterly dose limits of 5 mrad, gamma-air and 10 mrad, beta air and the calendar year limits 10 mrad, gamma-air and 20 mrad, beta-air. The following equations may be used to calculate the gamma-air and beta air doses. If noble gases are detected at multiple release points, these equations must be performed for each such release point, and the calculated air doses must be summed.
Dy = 3.17 E - 08 * % / Q * [(ht
- Q )
(7-10) and D, = 3.17E - 08
- x / Q * [(N,
- Q )
(7-11)
Where:
07 air dose due to gamma emissions for noble gas
=
radionuc! ides (mrad)
D air dose due to beta emissions for noble gas radionuclides (mrad)
=
%O atmospheric dispersion to the controlling SITE BOUNDARY
/
=
location (sec/m3) cumulative release of noble gas radionuclides i over the period of Qi
=
interest (pCi) air dose factor due to gamma emissions from noble gas Mi
=
radionuclides i (mradlyr per pCi/m3, from Table 7.0-2) air dose factor due to beta emissions from noble gas Ni
=
radionuclides i (mradlyr per pCi/m3, Table 7.0-2) 3.17 E - 08 =
1/3.15 E + 07 (year /sec)
ODCM-7.0 Revision 8 Page 7.013 1
j 7.7.2 Simplified Dose Calculation for Noble Gases In lieu of the individual noble gas radionuclides dose assessment presented above, the following simplified dose calculational equations may be qsed for verifying compliance with the dose limits of ODCM 3.11.2.2. If nobio gases are detected at multiple release points, these equations must be performed for each such release point, and the calculated air doses must be summed. (Refer to Appendix B for the derivation and justification of this simplified method.)
Dy = 2.0
- 3.17E - 08
- X / Q
- M,
- 1Q (7-12) and Dh = 2.0
- 3.17 E - 08
- x / Q
- N, * [Q, (7-13)
Where:
}
2.7 E + 03, effective gamma-air dose factor (mrad /yr per pCi/m3)
J Meff
=
l 2.3 E + 03, effective beta-air dose factor (mrad /yr per pCi/m3)
Neff
=
i conservatism factor to account for potential variability in the 2.0
=
radionuclides distribution 7.8 Radiolodine and Particulate Dose Calculations - 10 CFR 50 7.8.1 UNRESTRICTED AREA Dose - Radiolodine, Particulate.s, and Tritium i
in accordance with requirements of ODCM 4.11.2.3, a periodic assessment (at least once per 31 days)is required to evaluate compliance with the quarterly dose limit of 7.5 mrem and the calendar year limit of 15 mrem to any organ. The following equation may be used to evaluate the maximum organ dose due to l
releases of I-131,1-133, tritium, and particulate with half lives greater than 8 days:
D, =
(W,
- SF,
- 3.17E - 8
- R,,,
- QJ (7-14)
Where:
dose or dose commitment to Organ o of age group a (identified in Dao
=
Table 7.0-3 or plant procedures) l l
l
I ODCM 7.0 R: vision 8 i'
Page 7.0-14
)
atmospheric dispersion parameter for release point r and the Wr
=
residence location identified in Table 7.0-3 or plant procedures.
Either:
a)
% /O, atmospheric dispersion for inhalation pathway and I
H-3 and C-14 dose contribution via other pathways (sec/m3), or b)
D/O, atmospheric deposition for vegetation, milk and ground plane exposure pathways (m-2) 2 dose factor (mrem /yr per pCi/m3) or (m - mrem /yr per pCi/sec)
Raipo
=
from Table 7.0-4 for radionuclides i, age group a, pathway p, and organ o as identified in Table 7.0-3 or plant procedures. Values for Raipo were derived in accordance with the methods described in NUREG 0133. As noted in NUREG-0133 section 5.3.1.3,in the case that the milk animal is a goat, parameter values from Reg Guide 1.109 should be used. For 1-131, for example, use of the goat feed / forage consumption rate given in Table E-3 and the i
stable element transfer factor given in Table E-2 of Reg Guide 1.109 results in grass-goat-milk dose factors which are equivaient to the grass-cow milk dose factors in Table 7.0-4 multiplied by 1.2.
l cumulative release from release point r over the period of interest l
Oir
=
(normally one month) for radionuclides i -- l-131,1 133, tritium or j
radioactive material in particulate form with half life greater than j
8 days (pCi).
annual seasonal correction factor to account for the fraction of the SFp
=
year that the applicable exposure pathway does not exist:
i 1)
For milk and vegetation exposure pathways:
l 0.5 (derived from Reg Guide 1.109 Rev 1. A six.
I
=
month fresh vegetation and grazing season (May l
through October) limits exposure through this pathway I
to half the year.
2)
For inhalation and ground plane exposure pathways:
l 1.0 (derived from Reg Guide 1.109, Rev 1)
=
3.17 E-8 =
1/ 3.15 E7 (year /sec)
ODCM 7.0 Revision 8 Page 7.0-15 This equation should be used to evaluate organ doses for the individual with the highest potential offsite dose. This calculation is performed monthly and is added to previous results for the quarter and year. The highest quarterly and annual cumulative organ dose totals for this individual should be compared with the limits of ODCM 3.11.2.3.
The residence, age group, and relevant exposure pathways for this individual are listed in Table 7.0-3 and in plant procedures. Plant procedures may provide updated information which differs from Table 7.0-3. This individual is identified from data obtained in the annual Land Use Census (ODCM 3.12.2).
7.8.2 Simplified Dose Calculation for Radiolodines and Particulate in lieu of the individual radionuclides (1-131 anc particulate) dose assessment presented above, the following simplified dose calculation may be used for verifying compliance with the dose limits of ODCM 3.11.2.3. However, the result of this calculation should not be used as the reported offsite dose.
D, = 3.17E - 08
- W * % _33, *M (7-15)
Where:
maximum orga-dose (mrem)
Dmax
=
I3' 4.76 E + 10, child thyroid 1131 dose factor for the vegetable
=
pathway (m2. mrem /yr per pCl/sec) highest D/O for residence listed in Table 7.0-3 (m-2)
W
=
cumulative quarterly or annual release of radionuclides i from all O
=
i release points-- l-131.1-133, H-3, and particulate with half lives greater than 8 days (pCi)
The ground plane exposure and inhalation pathways need not be considered when the above simplified calculational method is used because of the overall 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 patnway may represent a higher dose contribution than either the vegetation or milk pathway. However, use of the 1-131 thyroid dose parameter for all radionuclides will maximize the organ dose calculation, especially considering that no other radionuclides has a higher dose parameter for l
l any organ via any pathway than 1-131 for the thyroid via the vegetable or milk l
pathway.
1 ODCM-7.0 Revision 8 Page 7.0-16 7.9 Gaseous Effluent Dose Projection As with liquid effluents, the Fermi 2 ODCM controls on gaseous effluents require
" processing" of gaseous effluents if the projected dose exceeds specified limits. These controls implement the requirements of 10 CFR 50.36a on maintaining and using the appropriate radwaste processing equipment to keep releases ALARA.
ODCM 3.11.2.5 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be i
used to reduce radioactive material levels prior to discharge when the projected dose I
exceeds 0.3 mrem to any organ in any 31 day period (i.e., one-quarter ( f the design objective rate). Figure 7.0-1 presents the gaseous effluent release points and the VENTILATION EXHAUST TREATMENT SYSTEMS applicable for reducing effluents prior to release.
Dose projection is performed at least once per 31 days using the following equation:
)
I D= r = D,,, * (31/ d) j (7-16) l l
Where:
1 maximum organ dose projection for the next 31 day period (mrem)
Dmaxp
=
NOTE:
The reference calandar quarter is normally the current calendar quarter. If the dose projection is done in the first month of the quarter and is to be based on dose calculated for the previous quarter, the reference calendar quarter is the previous quarter.
the cumulative maximum organ dose from the beginning of the reference Dmax
=
calendar quarter (normally the curient quarter) to the end of the most recently evaluated release period as determined by Equation (7-14) or (7-
- 15) (mrem) number of days from the beginning of the reference calendar quarter to d
=
the end of the most recently evaluated release period.
number of days in projection 31
=
ODCM 7.0 Revision 8 Page 7.0-17 7.10 Waste Oilincineration As indicated in Table 4.11.2.1.21, waste oil containing radioactive material may be
. incinerated by injection into the Auxiliary Boiler fuel stream, but this shall only be done according to approved plant procedures. Prior to incineration of such oil, a sample of the oil must be analyzed by gamma spectroscopy to determine radionuclides concentration.
Based on the analysis results and proposed incineration rate, the proposed release must be determined to be within site boundary dose rate limits (when combined with dose rates.
from other release points) prior to incineratic" After incineration, the activity released i
must be determined and recorded. The eqt e os of this ODCM section (section 7.^-)
should be used in these calculations, and the d.ghest dispersion factors in Table 7.0 3 may be used, unless data specific to the Auxiliary Boiler stack is available. (Since this
{
stack is f arther from most land receptors than other plant stacks, Table 7.0-3 dispersion j
factors should be conservative for this release point.)
ODCM-7.0 Revision 8 Page 7.0-18 TABLE 7.0-1 Values for Evaluating Gaseous Release Rates and Alarm Setpoints Al:ocation Allocated Dose Release Point Flow Rate
- Factor Rate Limit (liter / min)
(AF)
(mrem / year)
Reactor Building 2.67E6 0.50 T Body = 250 Exhaust Pierum Skin = 1500 D11 P280 Organ = 750 Standby Gas 1.07ES 0.10 T Body = 50 Treatment System Skin = 300 Div i D,11 P275 Organ = 150 Standby Gas 1.12E5 0.10 T Body = 50 Treatment System Skin = 300 Div 11 D11-P276 Organ = 150 Turbine Building 8.67E6 0.20 T Body = 100 Ventilation Skin = 600 D11-P279 Organ = 300 Service Building 9.06E5 0.01 T Body = 5 Ventilation Skin = 30 D11 P282 Organ = 15 Radwaste Building 1.13E6 0.02 T Body = 10 Ventilation Skin = 60 D11 P2B1 Organ = 30 Onsite Storage 3 06E5 0.02 T Body = 10 Building Skin = 60 Ventilation Organ = 30 D11-P281 Reactor Building 2.57E6 0.50 T Body = 125 Ventilation" Skin = 750 Gulf Atomic Monitors D11 N408, N410 Ventilation flow rate values are subject to change due to plant modifications and changing plant conditions; therefore updated values in plant procedures may be used.
D11-N408 and N410 will star 1 the SGTS, close the Drywell Purge / Vent Valves, isolate Rx Building Ventilation System, isolate Control Center, and initiate emergency recirculation mode.
ODCM 7.0 Revision 8 Page 7.0-19 TABLE 7.0-2 Dose Factors for Noble Gases *
- Total Body Skin Gamma Air Beta Air Gamma Dose Beta Dose Dose Factor Dose Factor Nuclide Factor Ki Factor Li Mi Ni (mrem /yr per (mremlyr per (mradlyr per (mrad /yr per pCl/m )
pCi/m )
pCi/m )
pCl/m3) 3 3
3 1.93E+01 2.88E+02 Kr-83m 7.56E-02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61 E+01 1.34 E+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 1.01 E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131 m 9.15E+01 4.76E+02 1.56E+02 1.11 E+03 Xe 133m 2.51 E+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 7.11 E+02 3.36E+03 7.39E+02 Xe-135 1.81 E+03 1.86E+03 1.92E+03 2.4GE+03 Xe-137 1.42E+03 1.22 E +04 1.51 E+03 1.27E+04 Xe 138 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 NOTE:
l Dose f actors taken from NRC Regulatory Guide 1.109 l
l i
OUCM-7.0 Revision 8 Page 7.0-20 i
TABLE 7.0-3 Controlling Locations, Pathways, and Atmospheric Dispersion for Dose Calculations
- Controlling y,/Q D/O ODCM Control Location Pathway (s) 3 2
Age Group (sec/m )
(1/m )
3.11.2.1 a site boundary noble gases N/A RB: 1.25E-6 N/A (0.57 mi, NW) direct exposure TB: 5.71 E-6 RW: 2.66E-6 3.11.2.1 b site boundary inhalation child RB: 1.25E-6 N/A (0.57 mi, NW)
TB: 5.71E 6 RW: 2.66E-6 3.11.2.2 site boundary gamma-air N/A RB: 1.25E-6 N/A (0.57 mi, NW) beta air TB: 5.71 E-6 RW: 2.66E-6 11.2.3 resistance vegetation child RB: 1.10E-6 1.59E 8 (0.67 mi, inhalation. and TB: 4.02E-6 3.06E-8 WNW) ground plane RW: 1.53E-6 1.76E 8 NOTE: *The identified controlling locations and pathways are derived from land use census data and dispersion and deposition f actor data tables. The dispersion and deposition factor values listed are conservative values; they represent the highest annual average values seen between 1984 and 1994. When performing dose and dose rate evaluations for plant surveillance, the dispersion and deposition factor values and location and pathway information found in plant procedures should be used. These data in plant procedures should be the same as the above data unless recent information has shown the above data to be non-conservative or inaccurate.
When performing dose evaluation for the Annual Effluent Release Report, the annual average dispersion and deposition f actors for the year being evaluated should be i
used.
i i
m i
l i
l j
i 4
ODCM-7.0 1
Revision 8 Page 7.0-21 j
Table 7.0-4 Gaseous Effluent Pathway Dose Commitment Factors Raipo, Inhalation Pathway Dose Factors - ADULT j
3 (mrem /yr per yCi/m )
1
{
puclide Some Liver Thyroit Eldeey Lees G1-113 T.Sedy 1.26E+3 1.26E+3 1.24E+3 1.26Ee3 1.268*3 1.26E+3 M-3 C+14
.1.42E*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 1.03E+4 1.02E*4 j
a 8.64E+4 5.01E+4
{
P,12 1.32E*6 7.71E*4 5.95E+1 2.24t*1 1.44E+4 3.32E*3 1.001+2 Cr-51 3.961+4 9.84t*3 1.40E+6 7.74E+4 6.30E*3 Mn-54 1.30E+0 9.44E*3 2.02E+4 1.83E 1 Mn-56 1.24E*0 7.21E+4 6.03E+3 3.94E+3 te-55 2.46E+4 1.70E+4 Te-59 1.18E*4 2.78E+4 1.02E+6 1.8BE+5 1.04E*4 3.70E*5 3.14E+4 6.71E+2 Co-57 6,92E*2 9.24E*5 1.06E+5 2.07E*3 co-58 1.58E*3 5.97E*6 2.85E*5 1.44E+4 Co-60 1.15E+4 1.78t+5 1.34E+4 1.45E+4 Nn-63 4.12E*5 3.14E+4 5.60E*3 1.23E+4 9.12E-2 pi-65 1.54E+0 2.10E-1 4.62E*0 6.78E*3 4.90E+4 6.15E-1 1.46teo Cu-64
- 6. 90E+ 4 8.64E+5
- 5. 34E+4 4.66E*4 2n-65 3.24E+4 1.03E+5 En-69 3.30E-2 6.51E 2 4.22E-2 9.20Ee2 1.63E+1 4.52E-3
- 1. 04 E+ 4 1.35E+4 tr-82 2.32E*2 2.41E+2 Br-83 1.64E-3 3.13E*2 Sr-84 1.28E+1 Br-85 1.66E.4 5.90E+4 kb-86 1.35E+5 3.34E-9 1.93E*2 Rb-88 3.87E+2 1.70E*2 tb-89 2.56t+2 1.40E+6
- 3. 50E+ 5 4.72E+3 sr-89 3.04E+5 s r -90 9.92E.7 9.60E*6 7.22E+5 6.10E+6 3.65t+4 1.91E+5
- 2. 50E+0
$r-91 6.19E+1 1.65t*4 4.30E+4 2.91E 1 3r-92 6.741+0 1.70E*5 5.06E*5 5.61E+1 Y-90 2.09E*3 1.92E*3 1.33E+0 1.02E 2 Y 91e 2.61E-1 1.70E*6 3.45E+5 1.24F+4 Y-91 4.62E+5 1.57E*4 7.35E+4 3.02E-1 Y 92 1.03E*1 4.85E+4 4.22E*5 2.61E+0 Y-93 9.44E+1 5.42E*4 1.77E*6
- 1. 50E* 5 2.33E+4 2r-95 1.07E*5 3.44E*4 2.97t+1 7.87E+4 5.23E*5
- 9. 04 E+0 Er-97 9.68E+1 1.96E*1 7.74E.3 5.051*5 1.041*5 4.21E+1
- D-95 1.41E*4 7.82E*3 6.54E-2 2.40E+3 2.42E+2 2.05E-2 kb-97 2.22E 1 5.62E 2 2.91E*2 9.12E+4 2.48E.5 2.30E*1 Mo-99 1.21E*2 4.42E.2 7.64E+2 4.16t+3 3.70E-2 Tc-99e 1.03E 3 2.91E 3 5.90E-4 1.08E-3 3.99E*2 Tc-101 4.18E 5 6.02E 5 5.83E*3 5.05E 5 1.101 5 6.58E+2 Ru-103 1.53E+3 1.02E+0 1.10E*4 4.82E+4 3.11E 1 Ru-105 7.90E 1 1.34E+5 9.36t+6 9.121 5 8.72E+3 Ru-106 6.91E+4 Rh-103e th-106 1.9?E*4 4.63E*6 3.021e5 5.94E*3 As-110e 1.00E+4 1.00f*4 SD-124 3.12E+4 5.89E*2 7.55E.1 2.48E*6 4.06E*5 1.241+4 Sb-125 5.34E 6 5.95E*2 5.40E+1 1.74E+6 1.01E*5 1.26E+4 Te-125m 3.42E+3 1.584 3 1,05E+3 1.24E+4 3.14E+5 7.04E+4 4.671+2 Te-127e 1.26E+4 5.77E.1 3.291 3 4.58E+4 9.60E+5 1.50E+5 1.57E 3 Te-127 1.40E*0 6.42E 1 1.04E+0 5.10E+0 6.51E*3 5.74E*4 3.10E-1 Te-129s 9.76t+3 4.67E.3 3.44E*3 3.66E+4 1.16t*6 3.83E*5 1.54E*3 Te-129 4.98E-2 2.39E 2 3.901-2 1.871-1 1.94E*3 1.57E*2 1.24E-2 Te-131e 6.99E.1 4.34E*1 5.50E+1 3.09E*2 1.4CE.% 5.56E+5 2.90E+1 Te-131 1.11E 2 5.951 3 9.36E 3 4.37E-2 1.39E*3 1.84E+1 3.59E-3 te-132 2.60E*2 2.15E*2 1.90E*2 1.46t+3 2.88E+5 5.10E+5 1.62E*2 1 130 4.58E+3 1.34E+4 1.14E*6 2.09E*4 7.69E+3 5.28E+3 2 131 2.52E.4 3.58E.4 1.19E*1 6.13E*4 6.28E*3 2.05E*4 3 132 1.161*3 3.264*J 1.14E*5 5.18E*3 4.06E+2 1.16t*3 1-133 8.64E*3 1.481++
2.15t*6 2.54E 4 8.48E+3 4.52E*3 s
J
)
}
ODCM-7.0 Revision S Page 7.0-22 Table 7.0-4 Gaseous Effluent Pathway Dose Commitment Factors Raipo, Inhalation Pathway Dose Factors - ADULT (cont.)
3 (mrem /yr per Ci/m )
leuclide tone 1.iver ThFre18 Eidney 1 mas SI-LL2 T.Sedy 1.01E+0 6.15E+2 I 134 6.44E+2 1.73E.3 2.98E+4 2.75E+3 5.25E*3 2.571+3 2-135 2.68E*3 6.98E+1 4.48E+5 1.11E+6 2.87E+5 9.76E+4 1.04E*4 7.28E*5 Cs-134 3.73E+5 8.48E*5
-8.56E*4 1.20E*4 1.171+4 1.10E+5 Co-136 3.90E+4 1.46E+5 2.22E+5 7.52t+4 8.40E*3 4.28Ee5 Cs 137 4.781+5 6.21E+5 l
Co 138 3.31E+2 6.21E+2 4.80E+2 4.861+1 1.46E-3 3.24E+2 6.221-4 3.76t+3 8.96t+2 2.74E-2 84-139 9.36E-1 6.661-6 as 140 3.90E+4 4.90E+1 1.67E+1 1.27E*6 2.18t+5 2.57E+ 3 -
Sa-141 1.00E-1 7.53E 5 7.00E-5 1.94E+3 1.16E 7 3.36E-3 1.66E-3 8a-142 2.63E 2 2.70E-5 2.29E-5 1.19E*3 1.36E+5 4.581+5 4.58E* 1 i
1.n-140 3.44E+2 1.74t+2 6.331+1 2.11E*3 7.721-2 La 142 6.831-1 3.101-1 Ce-141 1.99E+4 1.35E.4 6.261+3 3.62E+5 1.20E+5 1.53E*3 6.08E+1 7.98E*4 2.26E+5 1.53t+1 Ce 143 1.46E+2 1.38E+2 Ce-144 3.43E*6 1.43E*6 8.48E+5 7.78t+6 8.16E+5 1.84E+5 3
)
Pr-143 9.36E+3 3.75E*3 2.16E+3 2.81E+5 2.00E+5 4.64t+2 1
J 7.0$E-3 1.02E+3 2.15E-8 1.53E-3 Pr-144 3.011-2 1.25E 2 3.56E+3 2.21E*5 1.73t+5 3.65E*2 NS-147 5.27E+3 6.10E*3 2.90t+4 1.55t+5 2.48E*0 W-187 8.48E+0 7.081+0 NP 239 2.30E+2 2.261+1 7.00E+1 3.761+4 1.19E+5 1.24t+1 l
L----_~__m______________
ODCM-7.0 Revision 8 Page 7.0l-23 liable 7.0-4 Raipo, Inhalation Pathway Dose Factors - TEENAGER 3
(mremlyr per yCi/m )
huctile bone Liver Thyro!4 Eleney Lung Cl*LL2 T.bo4y 1.271,3 1.27E+3 1.27E+3 1.27E*3 1.27t+3 1.27t+3 N-3 C-14
~2.60t*4 4.87E.3 4.87E*3 4.87E*3 4.87E*3 4.87E+3 4.87E*3 ha-24 1.381+4 1.381 4 1.38E+4 1.38E+4 1.38E+4 1.38t*4 1.38t+4 9.28E+4 7.16E+4 P-32 1.89E*6 1.10E*5
- 7. 50E* 1 3.07E*1 2.10E+4 3.00E*3 1.35E*2 Cr-51 1.27E+4 1.985+6 6.68E*4 8.40Ee3 5.115 4 Mn-54 1.19E+0 1.52E*4 5.74E+4
- 2. lie-1 1.701+0 M1-56 1.24E*5 6.39:+3
- 5. 54 E* 3 Fe-55 3.34E+4 2.381 4 1.53E+6 1.78E*5 1.43t+4 Te-55 1.591+4 3,70t+4 5.86E+5 3.14E+4 9.20Ee2 6.92E+2
+
Co-57 1.34E+6 9.52E+4 2.38E*3 2.07t+3 co-58 8.72E*6 2.591+5 1.98E+4 1.511 4 Co-60 3.07E*5 1.42E+4 1.98E*4 Mi-63 5.80t+5, 4.34t+4 9.36t*3 3.67E*4 1.27E-1 Ni-65 2.18t+0 2.93E 1 2.03t+0 6.41t+0 1.11E*4 6.14E+4 8.48E-1 Cu-64 8.64E+4 1.24E+6 4.66E*4 6.24E*4 2n-65 3.86E+4 1.34E+5 6.02E-2
- 1. 58E+ 3 2.85E+2 6.46E-3 Zn-69 4.831-2 9.20E-2 1.821+4
=
Br-82 3.44E*2 Br-83 4.33E*2 tr-84 Br-85 1.83E*1 1.77E+4 8.40E+4 Rb-86 1.90E+5 2.92E-5 2.72E*2 5.46E+2 Ab-88 3.38E-7 2.33E*2 Rb-89 3.52t+2 2.421+6 3.7tt+5 1.25E+4 sr-89 4.34E.5 1.45E+7 7.65E+5 6.68E*6 S r-90 1.04t*8 6.07E*4 2.59E 5 3.51E+0 Er-91 8.80t+1 2.74E+4 1.19E*5 4.06E-1 3r 92 9.52E+0
+
2.93E* 5 5.59E*5 8.00E*1 Y-90 2.981 3 3.20E*3 3.02E*1 1.421 2 T 9tm 3.701-1 2.94E+6 4.09E+5 1.775+4 Y-91 6.61Ee5 2.64t+4 1.65te5 4.291-1 Y 92 1.47t+1 8.32E+4 5.79t+5 3.72E+0 Y-93 1.35t+2 6.74E+4 2.69E*6 1.49E+5 3.15E*4 2r-95 1.46E+5 4.58t+4 2r 97 1.38t+2 2.72t*1 4.12t+1 1.30E*5 6.30E*5 1.261+t 1.00t+4 7.51E+5 9.68t+4 5.66E*3 Nb-95 1.861 4 1.03E*4 9.121 2 3.93t+3 2.17E*3 2.84E 2 Nb-97 3.14E 1 7.781-2 4.11E*2
- 1. 54 E+ 5
- 2. 69E+ 5 3.22E+1 1.691 2 Mo*99 5.76E-2 1.15t*3 6.13E*3 4.99E-2 Te-99s t.38t 3 3.841 3 Tc-101 5.921 5 8.401 5 1.521-3 6.67E*2 8.72E-7 8.24E-4 7.43t+3 7.83E*5 1.09E*5 8.96E*2 Ru-103 2.101 3 1.41E*0 1.821*4 9.04E+4 4.34E 1 Re 105 1.12t*0 1.90t+5 1.61E+7 9.601 5 1.24E+4 Ru-106 9.84t+4 ph-103e Rh 106 2.501 4 6.75E*6 2.73E+5 7.99E*3 Aa-110s 1.341 4 1.3tE*4 3.85t+6 3.98E+5 1.68E+4
$b 124 4.301 4 7.94E+2 9.761+1 Sb 125 7.381 4 8.081 2 7.04t+1 2.74E+6 9.92E+4 1.72E*4 5.36E+5 7.50E*4 6.67E*2 Te-125e 4.88t+3 2.241*3 1.40t*3 Te 127e 1.80t+4 8.16t+3 4.38E+3 6.54E*4 1.66E*6 1.59E+5 2.18E*3 Te-127 2.01E+0 9.12E-1 1.421 0 7.281+0 1.12E*4 8.08E+4 4.42E-l Te-129s 1.391 4 6.581+1 4.581 3 5.19t+4 1.94E*6 4.0$E+5 2.25E+3 Te-129 7.10E-2 3.381 2 5.181 2 2.661 1 3.30E*3 1.62E+3 1.76E-2 Te-131m 9.84E*1 6.01t+1 7.251+1 4.391+2 2.38E 5 6.2tE*5 4.02E+1 Te-Ill 1.58F-2 8.321-3 1.24E 2 6.18E-2 2.34E*3 1.511+1 5.04 E-3 1
)
3.401 2 2.90!+2 2.46E*2 1.951 3 4.49E*5 4.63E+5 2.19E+2 l
Te-132 9.121+3 7.17E+3 l
I-130 4.241 3 1.791 4 1.49t+6 2.75E+4 6.49E*3 2.64E+4 t
1 131 3.541 4 4.911+4 1.461 7 8.40t+4 1.27E+3 1.587+3 2-132 1.591 3 4.38t+3 1.51t+5 6.92t+3 1.031+4 6.22E+3 j
3-933 1.221*4 2.05t+4 2.921 6 3.59t*4
[
i
ODCM-7.0 Revision 8 Page 7.0-24 Table 7.0-4 Raipo, Inhalation Pathway Dose Factors TEENAGER (Cont.)
3 (mremlyr per y Ci/m )
Nuclide Sees Liver Thyre &8 Elesey Lune Gl-LLI T.8edy 2.04E*1 8.40E 2 2-134 8.88E.2 2.32E+3 3.95E*4 3.66Ee3 6.95E*3 3.49E*3 3-135 3.70E*3 9.44E+1 6.21E*5 1.49E+4 Cs-134 5.02E*5 1.13E 6 3.75E+5 1.46t*5 9.76t*3 5.49E*5 1.101 5 1.78E*4 1.09E+4 1.37E*5 Co-136 5.15E*4 1.94E+5 Co-137 6.70E+5 8.48E+5 3.04E+5 1.21E*5 8.48t*3 3.11E*5 6.62E+2 7.87E*1 2.70E-1 4.46t*2 Ca-138 4.661+2 8.56Ee2 8,88E-6 6.46E+3 6.45E*3 3.90E-2 Ba=139 1.34E+0 9.44L-4 2.28t+1 2.03E*6 2.29E*5 3.52E*3 5a-140 5.47E+4 6.70E+1 9.84E-5 3.29E+3 7.66E-4 4.74E 3 Sa-141 1.42E-1 1.04E-6 2.27E-3 3.14E-5 1.91E*3 Ba-142 3.70E 2 3.70E-5 2.14E*5 4.87E*5 6.26E+1 La-140 4.79E+2 2.36E+2 1.02E*4 1.20E*4 1.06E-1 La-142 9.60E-1 4.25E-1 8.84E+1 6.14E*5 1.265+5 2.17E*3 Ce-141 2.84E+4 1.90E+4 8.64E+1 1.10E*5 2.55E+5 2.16E*1 Ce-143 2.66t+2 1.94E*2 1.21E+6 1.34E*7 4.64E+5 2.62E+5 Ce-144 4.89E*6 2.02E+e 3.09E+3 4.83E*5 2.14E,5 6.62E+2 Pr-143 1.34E+4 5.31E+3 1.01E-2 1.75E+3 2.35E-4 2.18E-3 Pr-144 4.30E-2 1.76E 2 5.02E*3 3.72E+5 1.82E+5 5.13E+2 Md-147 7.861 3 8.561 3 4.74E+4 1.77E+5 3.43E+0 W-187 1.20E*1 9.76t+0 pp-239 3.38t+2 3.19E*1 1.00E+2 6.49E*4 1.32E*5 1.77E*1 l
)
1
)
l l
l 1
l l
l
ODCM-7.0 Flevision 8 Page 7.0-25 Table 7.0-4 Raipo, inhalation Pathway Dose Factors - CHILD 3
(mremlyr per y Ci/m )
hochee tone Liver Thyro 18 Eisney 14:a8 Cl-12.3 f.8o8y 1.12E+3, 1.12E*3 1.12E+3 1.12E*3 1.12E*3 1.12E+3 N3 C-14 3.59E*4 6.73E+3 6.73E*3 6.73t*3 6.73E+3 6.73E+3 6.73E+3 ba-24 1.61E+4 1.61E*4 1.61E*4 1.61E*4 1.61E+4 1.61E*4 1.61E+4 4.22E+4
- 9. 8 8 E.4.
P-32 2.60E*6 1.14E+5 8.55E+1 2.43E+1 1.70t+4 1.08t+3 1.54E*2 Cr-51 1.00E+4 1.54E+6 2.29E+4 9.51E*3 Mn 54 4.29t+4 1.67t+0 1.31E+4 1.23E*5 3.12E-1 1.66E*0 Mn-56 fe-55 4.74E+4 2.52E+4 1.11E*5 2.87E+3 7.771+3 Fe-59 2.07t+4 3.34t*4 1.27E+6 7.07t+4 1.67E*4 Co-57 9.03E*2 5.07E+5 1.32E+4 1.07E+3 1.11E+6 3.44t+4 3.16E+1 Co-58 1.77t+3 7.07t+6 9.62t+4 2.26E+4 1.31E*4 Co-60 Ni-63 8.21E+5 4.631 4 2.75t*5 6.33t+3 2.80!+4 8.18E+3 8.40E*4 1.640-1 Ni-65 2.99E*0 2.96t-1 6.03E+0 9.58E*3 3.47E+4 1.07t+0 Cu-64 1.99E,0 7.14E+4 9.95E*5 1.63E*4 7.03E+4 2 n-65 4.26t*4 1.13E+5 5.851-2 1.42t+3 6.02E+4 8.92E-3 2n-69 6.70E-2 9.66E-2 2.09t+4 Or-82 4.74E*2 Br-83 5.48t*2 Br-84 2.53t*1 ar-85 7.99E*3 1.14E+5 1.98E+5 Rb-86 1.72E+1 3.66E+2 5.62E*2 Rb-88 1.89E+0 2,90E+2 3 45E*2 Rb-89 2.16E*6 1.47t+5 1.72t+4 8s-89 5 99E*5 1.48t+7 3.43E+5 6.44E+6 st-90 1.01E+8 5.33E+4 1.74E+5 4.59E+0 St-91 1.21t+2 2.40E+4 2.42E+5 5.25E-1 St-92 1.31E*1 2.62E+5 2.64E+5 1.11t+2 Y 90 4.11E+3 2.81t+3 1.721*3 1.841-2 7-91e 5.071-1 2.63E+6 1.84E+5 2.44E+4 Y-91 9.14E*5 2.39t+4 2.39t+5 5.01E-1 Y-92 2.04E+1 7.44t+4 3.09t+5 5.11E*0 Y-93 1.86E+2 5.96E+4 2.23E+6 6.11t*4 3.70E*4 Zr-95
- 1. 90E+ 5 4.18t+4 3.89E+1 1.13E*5 3.51E*5 1.60E+1 2r-97 1.88t+2 2.72E*1 8.62E+3 6.14E+5 3.70E+4 6.55E+3 Nb-95 2.35t+4 9.t8t*3 8.55E 2 3.42E*3 2.78t+4 3.bOE-2 Mb-97 4.291 1 7.701-2 3.92E*2 1.35I+5 1.271*5 4.26E*1 1.72E+2 Mo-99 5.071-2 9.51E*2 4.811+3 5.77E-2 Te-99e 1.781 3 3.481 3 1.45E-3 5.85t+2 1.43E+t 1.041-3 Te-101 8.10E-5 8.511 5 7.03E+3 6.62E+5 4.48E+4 1.07E*3 Ru-103 2.79t+3 1.14E+0 1.591+4 9.95E*4 1.551-1 Ru-105 1.53t+0 1.84t+5 1.43E+7 4.291+5 1.69t+4 Ru-106 1.36E+5 Rh-103e Rb-106 As-11De 1.69t+4 1.let*4 2.12E+4 5.48E 6 1.00E*5 9.14E+3 Sb-124 5.74E*4 7.40t+2 1.26t+.
3.24E+6 1.64E+5 2.00E+4 Sb-125 9.84E+4 7.591+2 9.10E*1 2.32E+6 4.03E*4 2.071+4 Te 125e 6.73E*3 2.33E+3 1.92t+3 4.77E+5 3.38E+4 9.14E+2 Te-127e 2.49t+4 4.55t+3 6.071 3 6.36t+4 1.48E*6 7.14E+4 3.02E*3 Te-127 2.77t*0 9.511 1 1.96E*0 7.07E*0 1.00E+4 5.62E*4 6.11E-1 Te-129s 1.92E*4 6.85E*3 6.331*) 5.03E*4 1.76t+6 1.82E+5 3.04E+1 Te-129 9.77E-2 3.50E-2 7.14t 2 2.571-1 2.93E+3 2.55E+4 2.38E-2 Te-131e 1.14t+2 5.92t+1 9.77E*1 4.00E+2 2.06t+5 3.08E*5 5.07E*1 Te-131 2.17E-2 8.46E 3 1.701-2 5.48E-2 2.05E+3 1.33E*3 6.591-3 Te-132 4.81E*2 2.72t+2 3.17E 2 1.77E+3. 3.77E+5 1.38E+5 2.61E*2 1-130 8.18E*3 1.6+1*4 1.85E*6 2 45E+6 5.111+3 8.44E*3 1-131 a.81E+4 4.81E*4 1.62E+7 7.88E*4 2.84E+3 2.73E*4 1-132 2.12t+3 4.07E+3 1.94t+5 6.25E*3 3.20!+3 1.88t*3 1-133 1.66t+4 2.03t*4 3.85t+6 3.38E*4 5.48t+3 7.70E+3
{
1 r
1 l
ODCM 7.0 l
l Revision 8 Page 7.0-26 i
Table 7.0-4 Raipo, Inhalatior Pathway Dose Factors CHILD (Cont.)
l 3
(mrem /yr per yCi/m )
sectide some Liver Thyteld Eidney Lens 01 EL3 f.tedy
.~.
1-134 1.17E*3 2.16E*3 5.07E+4 3.30E*3 9.55E*2 9.95E*2 1-135 4.92E*3 8.732 3 7.92E*5 1.34E*4 4.44E*3 4.14E*3 3.30E*5 1.21E*5 3.85E*3 2.251*5 Co 134 6.51E+5 1.01E*6 9.55E*4 1.45E+6 4.18E*3 1.16E+5 Cs 136 6.51E*4 1.71E*5 2.82E*5 1.04E*5 3.62E*3 1.24E+5 Co-137 9.07E+5 8.25E*5 6.22E*2 6.811+1 2.70E*2 5.55E*2 Co-138 6.33E*2 8.40E*7 8.62E-4 5.77E*3 5.77E*4 5.37E-2 B.i-13 9 1.84E*0
- 9. e4 E-4 2.11E*1 1.74E*6 1.02E*5 4.33E*3 54-140 7.40E*4 6.48E*1 9.47E*5 2.92E*3 2.75E*2 6.36E-3 to-141 1.96E-1 1.09E-4 2.91E-5 1.64E*3 2.74E+0 2.79E 3 Be-142 5.00E-2 3.60E-5 1.83E*$ 2.26E*5 7.55E*1 Le-140 6.44E*2 2.25E*2 3.70E+3 7.598*4 1.29E-1 La-142 1.30E*0 8.11t-1 5.55E*3 5.44E*5 5.66E+4 2.90E*3 j
Ce-141 3.92E+4 1.95E+4 Ce-143 3.66E*2 1.99E*2 8.361+1 1.15E*5 1.271 5 2.87E*1 1.17E*6 1.20E*7 3.89E*5 3.61E*5 Ce-144 6.77E*6 2.12E*6 Pr-163 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 4.81E*3 3.20E*5 8.21E+4 6.81E*2 f
Nd-147 1.0aE+4 8.73E*3 4.11E*4 9.10E*4 4.33E*0 W-187 1.63E*1 9.66E*0 9.73E*1 5.81E*4 6.40E*4 2.35E*1 hp-239 4.6H+7 3.3'I'l I
i
ODCM-7.0 l.
Revision 8 Page 7.0-27 Table 7.0-4 Raipo, Inhalation Pathway Dose Factors - INFANT 3
(mremlyr per Ci/m )
Nec!!se Bone Liver Thyroid Eldney taas GI-1.LI T.5edy l
6.47t+2 6.47E+2 6.47t+2 6.47E+2 6.47t+2 6.47E*2 N-3 l
l C-14
- 2.65t+4 5.31t+3 5.31t+3 5.31E*3 5.31E*3 5.31E*3 5.3tt+3 i
Wa*24 1.061+4 1.06t+4 1.061+4 1.06t+4 1.06t+4 1.06E+4 1.06E+4 1.61E+4 7.74E+4 P-32 2.03t+6 1.12E+1 5.75t+1 1.32t+1 1.28t+4 3.57t+2 8.95E*1 Cr 51 2.531 4 4.98t+3 1.00t*6 7.06t*3 4.981*3 Ma.54 1.10t+0 1.25E+4 7.17t+4 2.211 1
- 1. 54 t + 0 Ma 56 8.69t+4 1.091+3 3.331*3 Fe-55 1.97E*4 1.171+4 1.02t+6 2.48t+4 9.48E*3 te-59 1.36t+4 2.35t+4 3.79E+5 4.46t+3 6.41t+2 6.51E+2 Co 57 7.771+5 1.11t+4 1.82t+3 1.22t*3 Co-58 4.51t+6 3.19t+4 1.181 4 8.02t+3 Co 60 2.09t+5 2.42t+3 1.16E+4 NA 63 3.39E*5 2.041 4 8.12E*3 5.01E*4 1.23E-1 Mi-65 2.39E+0 2.84t 1 1.841*0 3.981+0. 9.30t+3 1.50Ee4 7.74E-1 Co-64 2n 65 1.93E+4 6.26t+4 3.251+4 6.47E*5 5.14E*4 3.11E+4 4.02E-2 1.47t+3 1.32t+4 7.18E-3 l
En 69 5.391-2 9.671-2 1.33E+4 Or-82 3.81t+2 3r-83 4.00E+2 Or-84 2.04E+1 Or-85 3.04E*3 8.42t+4 1.90E*5 Rb-86 3.39E*2 2.87E*2 5.571 2 Rb-88 6.82t+1 2.06Ek2 3.21t*2 Rb-89 2.03t+6 6.40t*4 1.14E+4 Sr-89 3.94E+5 1.12t+7 1.31E*5 2.591+6 l
Sr-90 4.091+7 5.26E*4 7.34t+4 3.46t+0 St 91 9.56t+1 2.38t+4 1.40t*5 3.91E-1 Er-92 1.05E+l 2.69t*5 1.04t+5 8.828 1 Y-90 3.29E+3 2.79t+3 2.35E*3 1.191-2 Y-91a 4.07E 1 2.45t+6 7.031 4 1.571 4 T-91 5.88t+5 2.45t+4 1.27E*5 4.61E-1 7-92 1.64t+1 7.64E*4 1.67t+5 4.07t*0 T 9) 1.50t+2 2r-95 1.151+5 2.791*4 3.11t+4 1.75E*6 2.17t+4 2.03t*4 2.59t+1 1.10E+5 1.40t+5 1.17t*1 i
Er-97 1.501 2 2.56t+1 l
1 4.721 3 4.79E*5 1.27t*4 3.181+3 Nb-95 1.57t*4 6.431 3 5.701-2 3.32t*3 2.69E+4 2.65E-2 kb-97 3.421 1 7.291-2 2.45t+2 1.35E+5 4.871+4 3.2:t*1 1.65t+2 Mo-99 3.11E-2 0.11E*2 2.03t+1 3.721 2 j
Te-99s 1.401 3 2.481 3 9.791-4 5.44t+2 8.44E 2 8.121-4 l
Tc-101 6.311 5 8.231-5 4.24E 3 5.52t+5 1.61E*4 6.79t+2 1
Ru 103 2.02t+3 8.991-1 1.57t+4 4.44t+4 4.10E-1 j
Rv 105 1.22t+0 s
1.071+5 1.16t+7 1.641*5 1.D9t+4 R9 106 8.681 4
.,.-io3.
,-106 1.09t+4 3.6?E*6 1.30t+4 5.00t*3 I
As-110e 9.94t*3 7.221 3 2.65t+6 5.91t+4 1.20E+4 l
$b-124 3.79t*4 5.56t*2 1.01t+2 l
Sb-125 5.17t+4 4.77t+2 4.23t+1 1.64t+6 1.47E+4 1.091+4 Te-125m 4.761*3 1.94E+3 1.62E.1 4.47E*5 1.291+4 6.54t*2 l
Te-127e 1.67t+4 t tote) 6.871*3 3.75t+4 1.31E+6 2.73E+4 2.071+3 Te-127 2.23t+0 9.531 1 1.851 0 4.861+0 1.03t+4 2.44t*4 4.89t-1 Te-129e 1.411+4 6.091+3 5.47t+1 1.181*4 1.68t+6 6.90t+4 2.23E+3 Te-129 7.881-2 3.471-2 6.75E 2 1.15E-1 3.00E*3 2.61E*4 1.88t 2 I
7e*131a 1.071+J 5.50E*1 8.93t+1 2.65t+2 1.99t+5 1.19t+5 3.63t+1 Te 131 1.74E 2 8.221-3 1.58E-2 3.991 2 2.061 3 8.221+3 5.00E-3 l
2 Te 132 3.72t+2 2.37t+2 2.791+2 1.03t+3 3.40E45 4.41E+4 1.76t+2 I
i 1 130 6.36t+3 1.391+6 1.601+6 1.53E*4 1.99t+3 5.571 3 1-131 3.791*6 4.44t+6 1.48t*7 5.18te4 1.061*3 1.96t+4 1.90E+3 1.261+3 1-132 1.691+1 3.54t*3 1.491 5 3.95t+3 2.161+3 5.601 3 I 133 1.32t+6 1.92t+6 3.561 6 2.24E+4 l
ODCM 7.0 Revision 8 Page 7.0-28 Table 7.0-4 Raipo, Inhalation Pathway Dose Factors - INFANT (Cont.)
3 (mrem /yr per Ci/m )
Declide Sees Liver Thyrets Eldeer Laes 81*ELI f.Sedy
=
1.198+3 6.65E+2 1-134 9.21E*2 1.84E*3 4.45E+4 2.09E*3 1.83E*3
- 2. 775+ 3.
1 135 3.86t+3 7.60E*3 6.96E*5 8.47E*3 1.90E+5 7.97t+4
- 1. 37 (+ 3 7.45K+4 Co-134 3.96E*5 7.03E+5 5.64E+4 1.18E+4 1.43E+3 S.29E*4 Cs-136 4.83E.4 1.35E+5 Co-137
- 5. 4 9E* 5 6.121 5 1.72E+5 7.13E+4 1.33E*3 4.55E+4 4.10E+2 6.54E*1 0.76E*2 3.98t+2 Cs-138 5.05E*2 7.81E+2 Sa-139 1.48t+0 9.84E-4 5.92E-4 5.95E*3 5 10E+4 4.30E 2 1.34E*1 1.60E*4 3.84E+4 2.90E*1 Ba-140 5.40E*4 5.60K+1
- 6. 50E-5 2.97E*3 4.75E*3 4.978-3 l
Sa-141 1.57E 1 1.08E 4 1.90E 5 1.55t*3 6.93E+2 1.NE 3 Sa-142 3.98E 2 3.305 5 1.681+5 8.48E+4 5.15E*1 La-140 5.05E*2 2.00E.2
-8.22E*3 5.95Ee4 9,04E 2 La-142 1.03E+0 3.77E-1 5.25E 3 5 ilE+5 2.16E+4 1.99E*3 j
Ce-141 2.778+4 1.67E+4 5.64E*1 1.16t+5 4.971 4 2.21E*1 Ce-143 2.93E*2 1.93E+2 Co 146 3.19E+6 1.21E+6 5.38E.5 9.84E+6 1.48E*5 1.76E+5 1.97E*3 6.33E*5 3.72E*4 6.99E*2 Pr-143 1.40E+4 5.24E+3 6.72E 3 1.61E+3 4.28E*3 2.41E 3 Fr 144 4.79E-2 1.85E 2 i
3.15E+3 3.22E*5 3.12E*4 5.00E*2
)
ud-147 7.94E*3 8.13E*3 3.ME*4 3.56E*4 3.12E+0 W-187 1 lotet 9.02E+0 6.62E+1 5.95E+4 2.49E*4 1.84E+1 up-239 3.7tt+2 3.32E 1 l
l j
1 IL______.__________
ODCM-7.0 Revision 8 Page 7.0-29 Table 7.0 4 Raipo, Grass-Cow Milk Pathway Dose Factors ADULT 3
Ci/m ) for H-3 and C-14 (mrem /yr per (m2 x mrem /yr per yCi/sec) for others b
Nm Sone Liver Thyroie Kidney Emna G3-ILE T.aody H-3 7.63t*2 7.63E+2 7.63t+2
- 7. 63 E+ 2 7.63 2 7.63t+2 C-14 3.63E+5 7.26E*4 7.261+4 7.26E+4 7.26E+4 7.261+4 7.26E+4 No-24 2.54Ee6
- 2. 54 t* 6
- 2. 54 t + 6
- 2. 54 E+ 6 2.54E+6 2.54E+6 2.54t+6 1.92t+9 6.60E*8 P-32 1.71E+10 1.061+9 1.71E,4 6.30!+3 3.80E+4 7.20E+6 2.84E+4 Cr-51 2.571+7 1.60E+6 nn-54 8.401 6 2.50E+6 1.351-1 7.511-4 4.231-3 5.38E-3 Mn-56 9.67t+6 9.95t+6 4.04E+6 re 55 2.51E+7 1.73E+7 1.95t*7 2.33E+8 2.68t*7 Fe-39 2.98E*7 7.00E+7 3.25E+7 2.13E+6 Co-57 1.28t+6 9.57E+7 1.06E+7 4.72E+6 Co-58 3.08t+8 3.62t+7 1.64t+7 Co-60 9.73E*7 2.26t+8 Ni-63 6.73E+9 4.66E+8
=
=
1.22E+0 2.19E-2
.N Mi-65 3.70E-1 4.811-2
=
=
2.051*6 1.131+4 6.08E+4 2.41Ee4 2
Cu-64 2.751*9 1.97E*9 T
2n-65 1.371 9 4.361 9 2.92E.9 j
Zn-69 3.72E*7 3.251 7 Br-82 1.49E-1 1.031-1 gr.g3
~
~
ar*se ar 85 5.11t*4 1.21E*9 2.591+9 Rb-86 Ab-84 gg-gg
=
=
2.331 8 4.161+7 sr 49 1.45E*9 1.35E*9 1.15E+10 St-90 4.68E*10 1.49E+5 1.27E+1
$r-91 3.13E*4 9.68E+0 2.11E-2 3r-92 4.891-1
- 7. 50E* 5 1.901+0 Y-90 7.07E+1 Y-91e 4.73E+6 2.30E*2 Y-91 8.60E+3 9.49E-1 1.581-6 Y-92 5.421-5 7.39E*3 6.43E-3 T-93 2.331-1 9.62E+5 2.05E+2 1r-95 9.46E*2 3.03t+2 4.76E*2 2.661*4 3.93E-2 1.301-1 1r-97 4.261-1 4.591-2 2.798+8 2.47E*4 kb-95 8.25E.4 4.59E+4 4.54E+6 5.4?E-9 Mb-97 5.85t+7 4.801+6 2.52t+7 5.72Ee7 Mo-99 Ts*99e 3.25E*0 9.19E*0 1.40E*2 4.50!+0 5.641*3 1.171*2
=
=
=
=
=
Tc-101 1.19E*5 4.39E*2 3.89 Eel 8v-103 1.021,3 5.241-1 3.38E-4 1.11t*2 au-105 4.57E-4 1.32E*6 2.58E*3 3.94I.4 pu-106 2.04E+4 sh-103e Rh-106 2.201+10 3.20E+7 1.06t+4 Aa-110e 5.831 7 5.39E+7
$b-124 2.57E 7 4.861 5 6.24t+4 2.00t*7 7.31148 1.02E+7 1.581*7 2.25t+8 4.86E+6
$b-125 2.04Ee7 2.281 5 2.081 +
6.50E*7 2.18t+6 Te-125e 1.631 7 5.90E+6 4.901 6 6.6'I+7 1.54t*8 5.54t*6 fe-127e 4.581 7 1.64t*7 1.171 7 1.8,1*4 5.30E+4 1.451+2 Te 127 6.72t+2 2.41E*2 4.981 2 2 '4t*3 3.041*8 9.57E*6 Te-129e 6.04E+7 2.25E+7 2.08t+7 2.52E+8 Te-129 1.75E+7 1.47E*5 Te-131e 3.61E+5 1.77E*5 2.80E*5 1.79E*6 Te-131 7.32E*7 1.45E+6 Te-132 2.39E*6 1.55t*6 1.71E*6 1.49E+7 1 130 4.26t*5 1.261 6 1.071 8 1.96t+6 1.08E+6 4.96E*5 3-131 2.96E*8 4.26E*8 1.39E 11 7.27E 8 1.12E+8 2.43E*8 3 132 1.645 1 4.37E 1 1.53E+1 6.97E-1 8.221 2 1.53E 1 1-133 3.97t+6 6.90E*6 1.01E*9 1.20!+7 6.20E*6 2.10E+6
ODCM-7.0 Revision 8 Page 7.0-30 Table 7.0-4 Raipo, Grass-Cow Milk pathway Dose Factors - ADULT (CONT.)
3 (mrem /yr per Ci/m ) for H-3 and C-14 2
(m x mrem /yr per Ci/sec) for others buclide some Liver Thyroid Kidney Lees
$3-112 f.tedy 3-134 4.10E*4 1.34E*4 I-135 1.39E*4 3.63E+4 2.40!*6 183E*4
+.35E 9 1.64E*9 2.35E+8 1.10E+10 Cs-134 5.65E+9 1.34E+'
$.74E+8 7.87t+7 1.17E+8 7.42Ee8 C6-134 2.61E+8 1.63E+v 3.43E*9 1.14E+9 1.95E*8 6.61E*9 Cs-137 7.38E*9 1.01E+10 Co-138 8.341-8 1.38E-9 ba-139 4.701-8 Sa-140 2.691+7 3.38E*4 1.15E+4 1.931 4 5.54E+7 1.761+6 Sa-141 Ba-142 1.64E*5 $.971-1 14-140 4.491+0 2.26E+0 3.03E 8 La-142 1.251*7 3.71E*2 1.521*3 Ce-141 4.84Ee3 3.27E*3 1.36E*1 1.16E*6 3.42E*0 Co-143 4.19E+1 3.09t+4 1.211 8 1.92E+4 ce-144 3.581+5 1.50!*5 8.871 4 6.961*$ 7.88E*0 3.68E*1 Fr-143 1.59E*2 6.371+1 Fr-146 5.23E*$ 6.52E+0 6.371+1 Nd-147 9.42E+1 1.09E*2 1.80E*6 1.92E*3 W-187 6.561*3 $.481+3 7.39E*4 1.98!*1 pp-239 3.661*0 3.601-1 1.121*0 l
i ODCM-7.0 Revision 8 Page 7.0-31 l
l Table 7.0-4 Raipo, Grass-Cow Milk Pathway Dose Factors - TEENAGER i
3 Ci/m ) for H-3 and C-14 (mremlyr per (m2 x mremlyr per # Ci/Sec) for others.
Nuclide Bone Liver Thyroid Ilidney Ims8 81-111 T.8edy 9.941 2 9.94D2 9.94t+2 9.94t+2 9.94E+2
- 1. 54 t+ 5 No.24 4.44t*6 4.44t+6 4.44t+6 4.44t*6 4.44t+6 4.64t*6 4.44t*6 2.65t*9 1.22E+9 P-32 3.15E+10 1.95t*9 2.78t*4 1.10E*4 7.13t+4 8.60t+6 5.00E*4 Cr-51 2.87t+7 2.78t+6 1.40t+7 4.17t+6 Ma-54 4.948-1 1.33E 3 7.511-3 9.50E-5 Ha-54 I
2.00t+7 1.378 7 7.34E+6 te-55 4.45E+7 3.16t+7 3.82E*7 2.87t*4 4.68t+7 Fe-59 5.20E*7 1.21E*8 4.19E*7 3.76t+6 Co-57 2.25t*6 1.10t+8 1.83t*7 7.951 6 Co-58 3.62E+8 6.26t*7 2.781 7 Co-60 1.33t+8 6.01E+8 Wi-63 1.18t+10 8.35t+8 4.70t+0 3.941 2
)
Ni-65 6.781-1 8.661-2 3.33t*6 2.02t+4 l
1.09t+5 Co-64 4.29t+4 I
1 4.68t+9 3.10t+9 3.41t*9 2n-65 2.11t*9 7.31te9 2n-69 5.645 7 Br-82 1.911-1 Br-83 8,.64 1
Sr.85 7.00t*8 2.22t*9 4.73t+9 86-86 86-88
=
=
Ob-89 3.18t+8 7.66t*7 St-89 2.67t+9 1.86t*9 1.43t*10 St-90 6.61t+10 tr-91 5.751 4 2.61t*5 2.298 3 2.28t*1 3.818-2 Sr-92 8.951 1 1.07t+6 3.50t+0 T 90 1.30E*2 1-91.
6.48t*6 4.24t+2 T-91
- 1. 58 t+ 4 2.755*0 2.90E-6 T-92 1.001-4 1.31t*4 1.18E-2 T-93 4.301-1 1.20t*6 3.59te2 7.67t*3 1r-95 1.65te3 5.22t*2 4.15t*4 7.061-2
' 2.32E-1 3r-97 7.751-1 1.131-1 3.34t*4 4.30t+4 7.57E*6 Mb-95 1.411 5 7.80t+4
- 6. 34 T.-8 Mb-97 8.16t*7 4.69t*6 1.04t*8 4.56t+7
~Mo-99 2.34t*2 8.73t+0 1.03E+4 2.04tet j
Te-99e
- 5. 64 t+0 1.171*1 Te-101 1.528*5 7.75t*2 6.40t+3 Ou-103 1.81te3 1.26t+0 6.088-4 1.971 2 Su-105 1.571 3 1.80E*6 4.73t*3 7.23t+4 Ou-106 3.75t+4 1
I Rh-103e
=
=
an 106 2.56t*10 5.54t*7 1.74t*8 Aa 110e 9.63E+7 9.11te?
4.01t*7 9.25t+8 1.798+7 sh-126 4.59E*7 8.46t*5 1.04E 5 3.21E+7 2.84t*8
- 8. 54 t+ 6 sb-125 3.45te? 3.99tel 3.49E*4 8.86t*7 4.02E+6 Te-125e 3.00E+7 1.08t*7 8.39t*6 i
- 2. Ot+ 8 1.00t+7 l
Te-127s 8.44t+7 2.99t+7 2.01E+7 3.421*8 l
Te-127 1.24t*3 4.41t*2 8.59t+2 5.04t+1 9.61t*4 2.6BE*2 4.15t+8 1.75t*7 j
Te-129s 1.111 8 4.10t*7 3.57t+7 4.621 8 1
2.188-9 1.67t-9 Te-129 Te-131e 6.571 5 3.15t+5 4.74t+5 3.~29t+6 2.53t*7 2.63Ee5 Te-131 0.58t+7 2.55t+6 Te-132 4.28t+6 2.71E*6 2.86t+6 2.60s 7 1 130 7.49t*5 2.17t+6 1.77t 8 3.34t+6 1.67t+6 8.66t*5 1.49t*8
- 4. 04 t
- 8 1-131 5.381 8 1.53t+8 2.20E*11 1.30t+9 3.31E 1 2.721-1 3 132 2.90E-1 7.591-1 2.541 1 1.20E*0 9.30t+6 3.75E+6 3-133 7.241 6 1.23t+7 1.72E+9 2.15t+7 1
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ODCM-7.0 1
Revision 8 l
Page 7.0-32 l
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Table 7.0-4 l
Raipo, Grass-Cow Milk Pathway Dose Factors - TEENAGER (Cont.)
3 (mrem /yr per y Ci/m ) for H-3 and C 14 (m2 x mrem /yr per Ci/sec) for others l
Woclide Bees Liver Thyteld Eidney Imeg
$1-111 T. tedy 1 134 7.01E+4 2.3st+4 2-135 2.471+4 6.35E+4 4.08t+6 1.00E*5 7.34E+9 2.00E+9 2.87E+e 1.07Es10 Cs-134 9.81E*9 2.31E*10 Co-136 4.45E*8 1.75E+9 9.53t*8 1.50E+8 1.41E*8 1.18Ee9 6.06E+9 2.35E*9 2.53E*8 6.20E*5 Ca-137 1.34E*10 1.7st+10 Ca-138 7.75E 7 2.53E-9 Be-139 4.49E-8 Ba-140 4.45E+7 5.95t*4 2 02E*4 4.00E+4 7.49E*7 3.13E*6 Ba-141 Sa 142 2.275+5 1.05E*0 h-140 8.06E 0 3.96E*0 2.23E-7 14-142 2.79E+3 1.69E+7 6.81E+2 Ce-141 8.87E*3 5.92E+3 2.51E+1 1.64E*6 6.25E+0 Co-143 7.69E+1 5.60E+4 1.63E+5 Ce-164 6.58E 5 2.72E+5 1.66E+4
- 3. 54 E+4 6.77E*1 9.61E*5 1.45E*1 Pt-143 2.92E+2 1.17E+2 Pt-144 7.11E+5 1.18E*1 1.16E*2 Nd-147 1.81E*2 1.97E+2 2.65E*6 3.43E+3 W-187 1.20E*4 9.7st+3 2.07E*0 1.06t+5 3.66E-1 br-239 6.99E+0 6.59E-1 I
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ODCM-7.0
(
Revision 8 i
Page 7.0-33 Table 7.0-4.
Raipo. Grass Cow Milk Pathway Dose Factors CHILD l
3 (mrem /yr per #Ci/m ) for H 3 and C 14 i
(m2 x mrem /yr per Ci/sec) for others l
Nuc3ide tone Liver Thyro 18 Klesey taas81-111 T.8edy 1.57t+3 1.57t+3 1.57E*3 1.57t*3 1.57E*3 1.57t*3 I
N-3 C-14 1.65E+4 3.291 5 3.29t+5 3.29t+5 3.29t*5 3.29t+5 3.29te5 Ma 24 9.23E+6 9.25t+6 9.23t+6 9.23t*6 9.23t*6 9.23E+6 9.23E*6 2.15t*9 3.00t*9 P *2 7.77t+10 3.64E*9 5.64t*4 1.55t*4 1.03t*5 5.415+6 1.02t*5 Cr*31 1.76t*7 5.58t+6 5.87t+6 2.09E*7 Mn-54 1.90t*0
- 2. 95E-3 1.58E-2 1.31E-2 Mn-56 3.35t*7 1.10t*7 1.54t+7 Fe 59 1.12E.8 5.93E+7 Fe-54 1.20E+8 1.95t**
5.65E+7 2.03t.8 9.71t*7 l
3.14t*7 7.77t+6 3.86t 6 Co 57 7.00E+7 3.725 7 1.211 7 Co-58 2.39t*8 1.278+8 4.32E+7 Co-60 b
1.07E*8 1.01E*9 l
N4-63 2.96t+10 1.591+9 l
1.91t*1 9.115-2 Ni-65 1.661+0 1.561 1
- 1. 54t* 6 4.56t+4 1.82t*5 7.55t+4 Cu-64 1.93E+9 f.85t+9 6.94E+9 te. nl 4.13t*9 1.10E*10 2.14E-9 2n-69 1.15 Eel Sr-82 4.695 1 tr-43 ar 84 j
Br-85 5.64t*8 5.398+9 8.77t*9 Rb-86
=
=
Ab-88
=
=
36-39 2.56t*4 1.89t*8 l
St-89 6.62t+9 1.51E*9 2.83t+10 Sr-90 1.12E*11 3.12tel 5.338*3 St-91 1.41t*5 4.14t*1 8.76t-2' 3r-92 2.19t+0 l
1.15Ee 5 8.61t*0 Y-90 3.221*2
=
=
y-91.
$.21t+6 1.04t+1 Y 91 3.91t+4 7.10t*0 7.035-6 T-92 2.461-4 1.57t+4 2.908 2 f.93 1.06t*0 8.81t*5 7.52t*2 1.21t*3 tr-95 3.84E+3 8.45Eet 6.13t*4 1.611-1 3.911 1 2r-17 1.89t+0 2.72E-1 2.29t*8 8.84t+4 1.16t*5 Nt-95 3.181*$ 1.24t+5 1.457.-6
=
=
Nb-97 6.86t*7 2.05t*7 1.771*8 8.29t+1 Mo-99 3.68t*2 1.29E*1 1.64t*4 4.20E*2 Te-99e 1.29t*1 2.54t*1 Tc=101 1.11t*5 1.65t*3 1.08t+4 Au-103 4.29te) 2.49E*0 1.39E 3 3.361 2 au-105 3.821 3 1.44t+6 1.15E+4 1.25t+5 au 106 9.24t+6 ab-103s
=
Ab-106 1.68t*10 1.138*8 2.65t*8 As-110s 2.09t+8 1.41t+8 6.03t*7 6.79t*8 3.81t*7 56-124 1.098 8 1.41t*8 2.40tel Te-125e 7.381 7 2.00te? 2.07te?
2.04t*8 1.828 7 4.85t*7 Sb-125 8.70t*7 1.41t*6 8.06t 6 7.12t*7 9.54E*6 Te 127s 2.08t 8
- 5. Ot+ 7 4.971*7 5.93t*8 1.68t*8 2.471 7 1.20E*5 6.56t+2 Te-127 3.06t*3 0.25t*2 2.121 3 8.71E+3 3.32t*8 4.23Ee7 Te-129e 2.721*8 7.61te? 8.781 7 8.00t*8 6.128-8 2.878 9 fe-129 2.24t*7 5.89t*5 Te-131s 1.60E*6 5.531 5 1.168 6 5.351 6 Te 131
=
=
4.55t+7 5.46t*6 Te 132 1.02E+1 4.521 6 6.58t*6 4.20t*7 1.66t+6 1.82t+6
- -130 1.751 6 3.*nt+6 3.90t*8 5.29t+6 1.17t*8 7.46t*8 1-131 1.301 9 1.311*9 4.34t+11 2.15t*9 1.48t+0 5.80E-1 3 132 6.86t-1 1.26t+0 5.85t+1 1.93E+0 8.77t+6 8.25t*6 1 133 1.761 7 2.181 7 4.041 9 3.63E*7
ODCM-7.0 Revision S Page 7.0-34 Table 7.0-4 R.,ipo, Grass-Cow-Milk Pathway Dose Factors - CHILD (CONT.)
3 (mrem /yr per Ci/m ) for H-3 and C 14 (m2 x mrem /yr per Ci/sec) for others uvenide Bees Liver Thyteld Eldney Lees 41 111 T.Sedy 2-134 8.00E*4 4.97t+4 1-135 5.44E+4 1.05t+5 9.30E*6 1.61E*5 1.15E+10 4.13E+9 2.00E+8 7.83E*9 Co-134 3.26E+10 3 71t+10 1.47E*9 3.19E 8 9.70E*7 1.79Ee9 Cs-136 1.001 9 2.76t+9 1.01E*10 3.6tt+9 1.93E*8 4.55E+9 Cs-137 3.22t+10 3.091+10
=
=
Ca-138 1.23E 5 6.19E-9 Be 139 2.141-7 3.34E+4 6.125+4 5.94E+7 6.44E+6 Se-140 1.17E*8 1.03E+5
=
Ba-141 34 143 1.84E+5 3.278+0 La-140 1.93E+1 6.74E+0 2.515-4 La-142 1.36E*7 1.62E*3 4.78t+3 Ce-141 2.19t+4 1.09E+4 1.50E*6 1.64t+1 4.29E*1 Co-143 1.89E+2 1.021 5 1.33E*8 8.66t+4 2.62E*5 Ce-144 1.62E*6 5.091+5 7.80t+5 3.59E*1 1.17E*2 Pr-143 7.23t+2 2.171 2 Pr-144 5.71E+5 2.79E*1 1.98t+2 Nd-147 4.45t+2 3.60t+2 2.411+6 7.73t+3 W 187 2.91t+4 1.72t+6 9.14E*4 8.681-1 3.57t+0 WP-239 1.72E+1 1.23t+0 3
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ODCM-7.0 Revision 8 Page 7.0-35 l
Table 7.0-4 Raj o, Grass-Cow Milk Pathway Dose Factors INFANT p
3 (mrem /yr per y Ci/m ) for H-3 and C-14 (m2 x mrem /yr per #Ci/sec) for others NucElde tone Liver Thyroid Kidney Lea 8 GI-E11 T.Sody 2.381+3 2.3
+3 2.38t+3 h.38E+3 2.38E+3 2.381+1 l
N-3 C-14 1.23E+6 6.89E*5 6.89p 5 6.89E*5 6.89E*5 4.89E+5 6.89E+5 pa-24 1.61E*7 1.61E*7 1.61E*7 1.61E+7 1.61E*7 1.61E*7 1.61E+7 2.171+9 6.21E*9 P-32 1.60E*11 9.42E*9 1.05E*5 2.30E+4 2.05t*5 4.71E*6 1.61E* 5 Cr-51 1.43E+7 8.831*6 3.89E+7 8.f3E*6 Ma-54 2.91E+0 5.53E-3 2.76E-2 3.21E-2 Mn-56 4.27E+7 1.11E 7 2.3*E+7 Fe-55 1.35E*8 8.72E+7 1.16E*8 1.88E+8 1.55E*8 Fe-59 2.25E+4 3.93E+8 3.0$E*7 1.46E+7 8.951 6 Co-57 6.0$E+7 6.06E*7 2.43E+7 Co 58 2.10E*8 2.08t*8 8.81E+7 Co-60 1.07E*8 1.21E+9 Ni-63 3.49E*10 2.16E*9 3.02E+1 1.81E-1 Ni-65 3.51E*0 3.971-1 3.85E+6 3.69E*4 3.17E*5 1.88E*5 Cu-64 1.61E*10 8.78E*9 9.23E*9 2n-65 5.55E*9 1.90E+10 7.36E-9 En-69 1.94E*8 8r-82 9.95E-1 ar-83 8t*84 St-45 5.69E*8 1.10E+10 2.22E*10 8b-86 St-8s nn-g1 2.59E*8 3.61E*8 sr-89 1.26E+10 1.52E+9 3.10E+10 3 r-90 1.22E*11 3.4a1+5 1.061+4 Sr-91 2.941 5 5.01E*1 1.73E-1 l
St-92 4.65E*0 l
9.39E+5 1.82E+1 Y-90 6.80E*2 j
,-,1.
5.26t+6 1.95t*3 T-91 7.331+4 9.97E*0 1.47E-5 T 92 5.22E-4 1.78t+4 6.13E-2 Y-93 2.25E+0 8.28E*$ 1.18E*3 1.791 3 2r-95 6.83E*3 1.66E*3 4.37t+4 3.131-1 6.911-1 2r-97 3.99E*0 6.85E 1 2.06t*8 1.41E*5 1.75E*$
Mb-95 5.93E+5 2.44E.5 3.70E 6 8# 97 6.98E*7 4.13E*7 2.12E+8 3.17E*8 Mo-99 5.97t+2 2.90!*1 1.61E+4 7.15E*2 Tc-99e 2.691+1 5.55E*1 Tc 101 1.06E 5 2.91E+3 1.81E+4 8 -103 8.691+3 3.21E+0 2.71E-3 5.12E 2 8v-105 8.06E 3 1.44E+6 2.34E+4 2.2SE+5 Su-106 1.90E*5 Sh-103e Sh-104 1.46E*10 1.86E*8 4.03E*8 As-110e 3.861+8 2.82E+8 1.31E+8 6.46t*8 6.49E+7
$b-124 2.09E*8 3.08t+6 5.56t+5 sh-125 1.491 8 1.451+6 1.871 5 9.38E+7 1 t9E+8 3.07E*7 7.18E*7 2.04E+7 Te-125e 1.511+8 5.04E+7 5.071+7 Te-127s 4.21E*8 1.40E*8 1.22E*8 1.04E+9 1.70E+8 5.10E+7 1.36E*5 1.40E*3 Te-127 6.50E*3 2.181*) 5.29t+3 1.59E*4 3.34E*8 8.62E+7 7e 129s 5.591+8 1.92E*8 2.15E*8 1.401 9 1.66E-7 1.75L-9 5.181-9 fe 129 2.08E 9 2.29E*7 1.12E+4 Te-131e 3.3BE+e 1.36E*6 2.761+6 9.35E*6 y,-13) 3.85E+7 9.721+6 7e-132 2.10E*7 1.041 7 1.54E*7 6.51E 7 1.70E*6 3.18E+6 3-130 3.60E*6 7.92E*6 8.88E*8 8.70E*6 1.15E+8 1.41E*9 3-131 2.72E*9 3.21E.9 1.05t*12 3.75E+9 3-132 1.42E*0 2.891+0 1.35E+2 3.221*0 2.34E+0 1.03E+0 1-133 3.721+1 5.41E*7 9.861+9 c.36E+1 9.16E+6 1.58E+7
1 1
ODCM-7.0 Revision 8 I
Page 7.0-36 Table 7.0-4 Raipo, Grass-Cow-Milk Pathway Dose Factors - INFANT (CONT.)
3 (mrem /yr per y Ci/m ) for H-3 and L 4 (m2 x mrem /yr per Ci/see) for others pullae Seen Liver Thytela 114esy Laat 81-143
- f. Seer 1.01E-9 3-134
=
=
8.74E*4 8.80E+4 1-135 1.21E*5 2.41E+5 2.16t+7 2.69t+5 i
1.75t*10 7.18E+9 1.85t+8 4 871+9 Co-134 3.65E+10 6.80t+10 2.30E*9 4.70E*8 8.76E+7 2.15E*9 Cs-136 1.96t+9 5.77E+9 1.62E+10 6.55E*9 1.88E+8 4.271+9 Ce-137 5.15E+10 6.0JE+10 Co-134 2.841-5 1.32E-8 Sa-139 4.551-7 5.73E+4 1.44t+5 5.921*7 1.24E*7 2.41t+8 2.41E+5 S.a-140
=
=
141 j
. 142 f
1.87t*5 4.09E+0 Le-140 4.03E*1 1.591+1 5.211-6 La-142
=
=
1.37t+7 3.11E*3 8.15E+1 Ce-141 4.33E+4 2.64E+4 1.55E+6 3.02t+1 l
7.72t+1 Ce-143 4.00E*2 2.65E+5 1.33E+8 1.30E+5 Ce-144 2.33t+6 9.52E+5 3.45E+$
7.89E*5 7.41t+1 l
Fr-143 1.49E+3 5.59t+2 2.00E+2 l
Pr-144 5.74E*5 5.55E+1 54-147 8.82E+2 9.04E*2 3.491+2 2.50!*6 1.471+4 W-187 6.12E*4 4.261*4 9.40E*4 1.84E+0 6.49E*0 bp-239 3.64E+1 3.25E+0 i
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ODCM-7.0 Revision 8 Page 7.0-37 Table 7.0-4 Raipo, Grass-Cow Meat Pathway Dose Factors - ADULT 3
Ci/m ) for H 3 and C 14 (mrem /yr per (m, x mrem /yr per Ci/sec) for others kuclide some Liver Thyroid Kidney Im s.
01-LL1 T.Sody 3.25E*2 3.2SE+2 3.25E+2 3.2SE+2 3.25E*2 3.75E+2 N-3 C-14 3.331 5 6.66E*4 6.66t+4 6.66E.4 6.66E*4 6.66E*4 6.66t+4 Na 24
- 1. 84 E-3 1.84E-3 1.84E-3 1.841-3 1.841-3 1.84E-3 1.841-3 5.23E+8 1.8vs+C P-32 4.65E*9 2.89E+8 Cr-51 4.22E*3 1.56E+3 9.38E+3 1.78E+6 7.07E*3 2.80E+7 1.75E+6 2.72E+6 Ms-54 9.15E+6 nn-56 1.13E+8 1.16E+8 4.72t+7 Fe-55 2.93E+8 2.02t*8 1.751*8 2.09E+9 2.40E*8 Te-59 2.671 8 6.27t+8 1.43E*8 9.371+6 Co-57 5.64E*6 3.70E*8 4.10E*7 1.83E+7 Co-58 1.41E+9 1.66E*8 7.521+7 Co-60 2.73E+8 6.33E*8 Mi-63 1.891+10 1.31t*9 pi-65 2.521-5 1.39E-7 2.951-7 7.451-7 Co-64 7.13I.8 5.12E*8 Zn-65 3.56E+8 1.13E+9 7.57E*8 to-69 1.44E+3 1.26E+3 Br-82 Br-83 sr-84 Br-85 9.60E+7 2.271+8 4.87t+8 Rb-86 Rb-88 Rb-89 4.84t+7 8.65E+6 Sr-89 3.0*t+8 5r-90 1.24E*10 3.59t+8 3.05E+9 1.381-9 St-91 Sr-92 1.13E+6 2.461+0 Y-90 1.07t+2 Y-91m 6.24E*4 3.03E+4 Y 91 1.13E*6 y.92 2.08E-7 Y-93 1.91E+9 4.09E+ 5 9.481+5 Ir-95 1.88t+6 6.04t+5 5.581-6 1.14t*0 1.69E-6 Zr-97 1.831 5 3.69E-6 7.751+9 6.86E*5 1.26t+6 Mb-95 2.29t+6 1.28t+6 Mb-97 2.52E+$ 2.071*4 1.091+5 2.46E+$
Mo-99 Tc-99e Tc-101 1.23t+10 4.55E*7 4.031+8 Ru 103
't.06E*8 3.-105 1.81E+11
- 3. 54 E* 8 5.40t+9 Ru 106 2.80E*9 Rh 103e Rh-106
=
=
2.52E*9 3.671+6 1.22E+7 A8-110e 6.49t*6 6.191 6 1.54E+7 5.62I+8 7.85E+6
$b-124 1.94E+1 3.741 5 4.80t+4
$b-125 1.91E 7 2.13E*5 1.94E+4 1.47t+7 2.10E*8 4.54E+6 1.43E+9 4.81E+7 Te-125e 3.59E*8 1.30E*8 1.08t+8 1.46t*9 3.741 9 1.341+8 Te-127m 1.12t*9 3.99E*8 2.85E+8 4.53E*9 1.09E-9 2.101 8 Te-127 5.76t*9 1.81E+8 Te 129e 1.14t*9 4.271 8 3.13k+8 4.771+9 Te-129 2.193+4 1.84E*2 Te-131m 4.511+2 2.211+2 3.50E*2 2.24t*3 Te-131 Te 132 1.40E.6 9.07E*5 1.00E*6 8.73E+6 4.29E+7 8.51E*5 2-130 2.351-6 6.941-6 5.881-4 1.08E-5 5.981-6 2.74E-6 4.071+6 8.83E+6 3-131 1.08t+7 1.54E*7 5.05E+9 2.64t+7 1-132 1*13) 4.30E-1 7.471-1 1.60E*2 1.30E*0 6.721-1 2.28E-1
ODCM 7.0 Revision 8 Page 7.0-38 Table 7J-4 Raipo, Grass-Cow Meat Pathway Lc se Factors - ADULT (CONT) 3 Ci/m ) for H-3 and C 14 (mremlyr per (m2 x mremlyr per Ci/sec) for others sectide Bees Liver Thyseld Eldaer 1 mas 81 111 T.Sody 3 134 3 135 5.04E*8 1.68E*8 2.74E*7 1.28E*9 Co-134 6.57E*8 1.56E+9 Co-136 1.185*7 4.67E*7 2.W E*7 3.56t*6 5.30E*6 3.36E*7 4.05E*8 1.35E+4 2.31E*7 7.41E*8 Co-837 8.721*8 1.19E*9 Cs-138 j
g..g39 Sa-140 2.88t*7 3.61E*4 1.23E*4 2.07E*4 5.92E*7 1.89E*6 Ba-141 ne-142 1.33E*3 4.79E-3 La '40 3.60E-2 1.81E 2 La-442 3.62E*7 1.08E*3 4.40E*3 Co-141 1.40E*4 9.48E*3 I
5.78t*2 1.71E-3 6.80E-3 Ce-143 2.09E-2 1,55E*1 4.93E*u 7.83E*4 3.61E*5 Ce-144 1.44E*6 6.09E*5 9.33E*7 1.06te)
Fr-143 2.13E*4 8.54E*)
4.931*3 Pr 144 3.93E*7 4.90E*2 4.78E*3 Nd-147 7.08E*3 8.18E*3 5.92E+0 6.32E-3 W-187 2.16E-2 1.81E-2 5.15t*3 1.39E 2 pp-239 2.56E-1 2.51E 2 7.84E-2 l
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ODCM-7.0 Revision 8 Page 7.0-39 Table 7.0 4 Raipo, Grass Cow-Meat Pathway Dose Factors - TEENAGER 3
Ci/m ) for H 3 and C 14 (mrem /yr per (m2 x mrem /yr per Ci/sec) for others Nuclide
. Sone Liver Thyroid Kidney 1.uns G2-LLI T.Sody M-3 1.94E+2 1.94E+2
- 1. 94 E+ 2 1.94E*2 1.94E+2 1.94t+2 C 16 2.81E*5 5.62t+4 5.62E+4 5.62E+4 1.62E+4 S.62t+4 5.621*4 ba-24 1.47E-3 1.471-3 1.47E-3 1.47E-3 1.47E-3 1.47E-3 1.47E-3 P-3.2 3.93E*9 3.44E*8 3.30E+8 1.52E+8 Cr-51 3.14E+3 1.24E*3 8.07E*3
- 9. 50E* 5 5.65E+3 1.631+7 1.38E+6 2.08t+6 nn-54 6.98t+6 nn-56 1.07E*8 7.30E+7 3.93t+7 Ee-55 2.38t*8 1.69t+8 1.57E*4 1.181*9 1.92E*8 Fe-59 2.13E+8 4.98E 8 Co-57 4.53t+6 8.45t+7 7.59E+6 1.94E*8 3.25E+7 1.41t*7 Co-58 7.60E*8 1.31E*8 Co-60 5.83E+7 1.71t*8 5.15E*8 Mi-63 1.52E*10 1.07t*9 gg-65 1.87E 5 1.13E-7 6.10E4 2.411 7 Co-64 3.681+8 4.051*8 5.54t*8 En-65 2.50E*8 8.69t*8 2n-69 9.981+2 8t-82 Sr-83 Sr-84 Br-85 Rb-86 4.06t*8
=
=
6.01E*7 1.91E*8 Rb-88 ab-39 3.03E+7 7.29E*6
$r-89 2.546*C 2.26E*8 1.99tt9
$r-90 4.05t*9
=
1.101-9 Sr-91
$r 92 7.40E+5 2.42E+0 Y 90 8.98t*1 y-gt.
3.92E*8 2.56E*4 Y-91 9.561 5 Y 92 1.691-7 Y-93 1.10E*9 3.27t+5 6.99te$
1r-95 1.51E+6 4.761+5 8.181-1 1.391-6 It-97 1.53E 5 3.021-6 4.581-6 9.64te$
4.251 9 5.47E+5 Mb-95 1.791+6 9.9aE*5 Mb-97 1.61Ee5 1.71E+4 2.06t*5 8.981 6 ho-99 Tc-99m Te-101 7.18t*9 3.68t+7 Ru 103 8.60!*7 3.03t+8 3 105 4.55E+9 1.131*11 2.971+8 Ru 106 2.36t+9 Rh-103m
=
=
=
=
Rh 106 1.35E*9 2.91t+6 Aa 110e 5.061 6 4.791 6 9.14t+6
- 1. 41 E
- 7 3.26t+8 6.31E*6 ab 124 1.621*7 2.981*5 3.671 4 1.37E*7 1.22E*8 3.66t*6
$b-125 1.56t+7 1.71t*5 1.491 4 8.94E*8 4.05E+7 Te 125m 3.03t*4 1.09tes 4.47t*7 Te-127e 9.411*4 3.34E+4 2.241*8 3.82t+9 2.35t*9 1.12E+8 1.75E-8 Te 127 3.60E+9 1.52E*8 Te-129s 9.58t+4 3.56t*8 3.09E*8 4.01t+9 Te-124 Te-131a 3.761 2 1.801 2 2.711 2 1.88t+3 1.45t*4 1.50E*2 Te-131 2.30E*7 6.84E+5 Te*134 1.15E*6 7.26t+5 7.66t+5 6.9 7t+6
- 1-130 1.891 6 5.48t-6 4.471-4 8.441-6 4.211 6 2.191-6 2.48t+6 6.73t*6 1-131 8.95t+6 1.251 7 3.64t*9 2.161*7 3-132 1 133 3.59t-1 6.101-1 8.51tet 1.071*0 4.61E-1 1.86E-1
f ODCM-7.0 Revision 8 Page 7.0-40 Table 7.0-4 4
l l
Raipo, Grass-Cow Meat Pathway Dose Factors - TEENAGER (CONT.)
3 l
(mrem /yr per y Ci/m ) for H-3 and C 14 l
(m2 x mrem /yr per Ci/sec) for others 1
muclide bees Liver Thrteld Eldney Easag 81-LLI 7.8edy 1-134 1 135 3.91E*8 1.49E*8 1.535*7 5.71E*8 Co-134 5.23E+8 1.23E*9 1.97E*7 3.11E*6 2.92E*6 2.44E*7 Co-136 9.22E*6 3.63E+7 3.283*8 1.27E*4 1.37E*7 3.36t*8 Co-137 7.241*8 9.63E*8
=
=
=
Cs-138 3 139 9.88t*3 1.96t*4 3.67E*7 1.53E+6 8.-140 2.38E*7 2.91E*4
=
=
=
=
he=141
=
8.-142 8*3I3*3 3*8IE*I Le 140 2.96E-2 1.451 2 u.142 2.25E*1 9.031 2 3.70E*3 Ce-141 1.18E+4 7.86t*3 5.74E-3 3.85E*2 1.43E-3 Ce-143 1.74E-2 1.28E*1 3.09E*8 6.60E*4 3.041*5 Ce-144 1.23E*6 5.081*5 5.90E*7 4.92E*2 4.161+3 tr 143 1.19E*4 7.15t*3 Fr-144 2.65t*7 4.06E*2 3.98E*3 Nd-147 6.24E*3 6.79E*3 i
3.99E*0 5 17E-3 W-187 1.stE-2 1.48E 2 3.39E*3 1.17E 2 6.61E-2 mp-239 2.231-1 2.11E 2 l
l l
l l
l i
I l
l l
ODCM-7.0 Revision 8 Page 7.0-41 i
Table 7.0-4 Raipo, Grass-Cow-Meat Pathway Dose Factors CHILD 3
Ci/m ) for H-3 and C-14 (mremlyr per (m2 x mrem /yr per Ci/sec) for others l
l Mac31de Sone Liver Thyroid Kidney
- 1. usa C1-LLI T.Sody 2.341 2 2.341 2 2.34E+2 2.34E*2 2.34te2 2.34E*2 N-3 C-14 5.291 5 1.06t+5 1.06t+5 1.06Ee5 1.06t+5 1.06t+5 1.06145 Na-24 2.341-3 2.341 3 2.34E-3 2.34E-3 2.34E 3 2.34E-3 2.34E-3 P-J2 7.41t+9 3.471+8 2.05t*8 2.86E+8 4.891 3 1.34E 3 8.93E+3 4.67t*5 8.811+3 Cr-51 Ma-54 7.99E+6 6.70E*6 2.13E+6 2.24E*6 Hn-56 1.37E*8 6.491 7 7.51E*7 te-55 4.57t+8 2.42t*8 1.771+8 6.371+8 3.05E*4 Fe-59 3.78t+8 6.121 8 5.92t+6 4.85E+7 1.20E+7 Co-57 9.60E+7 5.04t+7 Co-58 1.65t+7 Co-60 6.9?t+7 3.84E+8 2.04E*8 1.05t*8 9.91E*8 Ni-63 2.9tt+10 1.561 9 Ng-65 3.24E-7 7.821-7 1.521-5 1.961-7 Cu-64 1.761+8 6.22t*8 2n-65 3.75t+4 1.00!+ 9,
6.30!+8 En-69 8r-82 1.56E*3 Br-83 St-84 Ir-85 3.718e7 3.54E+8 5.76t*8 Rb-86 Rb-88
=
Rb-89 1.86t+7 1.38E*7
$r-89 4.82E+8
$r-90 1.041 10 1.60t*8 2.64t+9 Sr-91 1.01E 9 sr-92 4.84E+$ 4.55t+0 T 90 1.70!*2 Y-91e Y-91 1.81t+6 2.41E+8 4.831+4 y-92 1.55E 7 Y-93 8.43t+5 fr 95 2.68t+6 5.891 5 6.14t*8 5.24E+5 2t-97 2.841-5 4.101-6 6.211-1 2.42E-6 5.891 6 ND-95 3.091+6 1.20t+6 2.23E*9 8.611 5 1.13E*6 Mb-97 Mo-99 1.251 5 2.67t+5 1.031*5 3.091+4 Te-99m Te-101 4.041+9 5.94t*7 3.921 8 Su 103 1.561+8
- 3. 105 6.90!*10 5.54E+8 5.991+9 Su-106 4.46E*9 Rh-103e Rh-106 1.06t*7 As-tion 8.40E*6 5.67t+6 6.75t+8 4.53t+6 8b-124 2.93t+7 3.804+5 6.+61 4 1.62t*7 1.83t+8 1.03t+7 3D-125 2.85t*7 2.191 5 2.64E+4 1.59E*7 6.80E*7 5.96t+6 Te-125e 5.69E*8 1.54t+8 1.60f*8 5.49E*8 1.59t+7 Te-127a 1.771+9 4.78t+8 4.241 8 5.061 9 1.44t+9 2.111+8 Te-127 1.21t-9 1.661 8 2.20E*9 2.80E+8 Te-129a 1.81E*9 5.04t*8 5.821 8 5.30E+9 Te-129 Te-131e 7.00t+2 2.42E*2 4.98t*2 2.34E*3 9.821*3 2.58te2 Te-13) 9.33E 6 1.12t*6 Te-132 2.09t+6 9.271 5 1.35L*6 8.601 6 3.20E-6 3.531-6 3-130 3.39t-=
6.85t 6 7.544-4 1.02E-5 3-131 1.66t+7 1.67t+7 5.5JE*9 2.74t*7 1.491+6 9.497+6 3-132 3.331 1 3.12E-t 3-133 6.681-1 8.261-1 1.53k+2 1.38t+0
ODCM-7.0 Revision 8 Page 7.0-42 Table 7.0-4 Raipo, Grass-Cow Meat Pathway Dose Factors - CHILD (CONT.)
i 3
(mrem /yr per y Ci/m ) for H-3 and C-14 (m2 x mrem /yr per yCi/sec) for others belide some Liver Thyreld tieney Emme 81 IJ.!
f.8edy a
2-134 2-135 4.69t+8 1.64t+8 4.15t*6 3.19t+8 Co-134 9.22t+8 1.51E+9 2.33E+7 3.47t+6 1.54t*6 2.83t*7 Cs-136 1.59E*7 4.37t+7 4.16t*8 1.50E*8 7.99E*6 1.88t+8 Cs 137 1.33E+9 1.28t+9 l
Co-138 j
as-ist to 140 4.39t*7 3.85E+4 1.25t+4 2.291 4 2.22t+7 2.56t+6 se-141 te 142 5.27t+2 6.381-3 La-140 5.411-2 1.89E-2 1.e-142 1.38t*7 1.64t*3 4.84E+3 Ce-141 2.22t+4 1.11E+4 2.62E*2 2.591-3 7.51E-3 Ce-143 3.30E 2 1.191+1 1.89t*8 1.24 E+ 5 l
4.02t+5 Ce-144 2.32t*6 7.26t+5 l
3.66t+7 1.68t*3 5.51E*3 Pr-143 3.39t+4 1.021*4
,,-144 5.20E*3 1.50E*7 7.34t*7 l
Nd-147 1.17E*4 9.48t*3 v 187 3.361-2 1.991 2 2.79E*0 8.92E-3 J
2.23E*3 2.12E-2 j
8.73E-2 Mp-239 4.20! 1 3.C21-2 l
l i
l l
l l
I
l ODCM-7.0 l
Revision 8 c
Page 7.0-43 Table 7,0 4 Raipo, Vegetata Pathway Dose Factors - ADULT JCi/m ) for H 3 and C 14
{
3 (mrem /yr per (m2 x mrem /yr per Ci/sec) for others Nuc!!de some Liver Thyroid. Kidney Imag 83*ILI T.sody 2.26t*3 2.26i+3 2.16t+3 2.26t+3 2.26t*3 2.26t*3 i
N-3 C 14 3.97t+5 1.79t+5 1.79t+5 1.79E*5 1.79t+5 1.79E*5 1.79t*5 Na-24 2.76te$ 2.76t*5 2.76t+5 2.761+5 2.76t*5 2.76t+5 2.76tel 1.54t+8 5.42t+7 P-32 1.40t+9 8.731 7 2.79E*4 1.032*4 6.19E*4 1.171*7 4.66t+4 Cr-51
- 9. 54 t* 4 5.941*7 9.27t+7
- 3. tit *8 Ma-54 5.131 2 2.85t+0 2.04t+1 Mn-56 1.61t+1 Fe-55 2.09t+8 1.45t+8 8.06t+7 a.29t*7 3.37t*7 8.35E+7
- 9. 96 t+ 8 1.14t*8 Fe-59 1.271+8 2.99t*8 2.97t+4 1.95t+1 1.17t+7 Co-57 6.261*8 6.921*7 3.09t+7 Co-58 3.14t*9 3.69t*8 1.67t*8 Co-60 1.50t*8 3.49t+8 Ni-63 1.04t*10 7.21t*8 3.03t*2 3.45E+0 Ni-65 6.15t+1 7.99t+0 7.90t*5 4.35t+3 9.27t+3 2.34t*4 Cu-64 6.36t*8 4.54t*4 6.75t**
In-65 3.17t+8 1.011 9 2.511-6 1.16t-6 1.091 5 2n 69 8.751-6 1.671-5 1.73t*6 1.51t+6 St-82 4.63E+0 3.21E+0 tr 83 Sr 84 Sr-85 4.321+7 1.02E+8 2.191+8 36-86 an-38 36-89 1.63t*9 2.86t*8 8t-89 9.961+9 1.sSt*10 1.44t*11 t r-90 6.05E+11 1.52t+6 1.29t+4 sr-91 3.20!*$
8.461+3 1.85t*1 St-92 4.271+2 1.41t*4 3.56k+2 Y-90 1.33t+4 1.714-8 Y-91e 5.831-9 l
2.82t*9 1.37te$
i Y 11 5.13t+6 1.54t*4 2.63E-2 Y 92 9.018-1 5.521 6 4.60t+0 Y 13 1.74t*2 1.21E*9
- 2. 54t* 5 2r 95 1.191 6 3.811+5 5.971*5 2.08t*7 3.04t*1 tr-97 3.33t+2 6.73tet 1.021*2
- 4. 60t+ 8 4.25t*4 7.811 4 Nt-95 1.42tel 7.911 4 2.718-3 2.64E-7 4.561 7 Mb-97 2.901-6 7.341-7 1.45t*7 1.19t+6 1.411 7 6.25t*4 Me-99 1.32E*2 4.24t+0 5.12t*3 1.10!*2 Te-99e 3.06t+0 4.66t+0 Te-101 5.61t*8 2.071*6 1.83t+7 Ru 103 4.801+6 3.30E+4 2.13t*1 6.96t*2 Su-105 5.39t*1 1.25E+10 2.44t*7 3.72E*8 Ru-106 1.93t+8 An-103e
=
=
Ah-106 3.941*9 5.80t+6 1.92E+7 As 110e 1.04t*7 9.76t.6 8.08t+7 2.95t*9 4.11E*7 8 b-124 1.04Ee8 1.96t+6 2.52t+5 1.05t*8 1.50t*9 3.251*7 Sb-125 1.36t+8 1.521 6 1.39t*5 3.861*8 1.29t*7 Te-125m 9.66t+7 3.501 7 2.90E*7 3.93te8 1.171*9 4.261+7 Te-127e 3.49t*8 1.25t*8 8.921 7 1.42E+9
- 4. 54 t* 5 1.25t+3 Te 127 5.761 3 2.07t+1 4.271 3 2.35t+4 1.28t*9 4.031*7 Te-129e 2.55E 8 9.501 7 8.75t+7 1.06t*9 5.021-4 1.621-4 Te-129 6.651-4 2.50t-4 5.10t-6 2.791-3 4.43t*7 3 72t+5 Te 131a 9.121*$ 4.46t*5 7.06t*5 4.521*6 Te-131 1.31E+8 2.60t+6 Te-132 4.29t*6 2.77E*6 3.06t+6 2.672 7 1.01t+6 4.61t+5 1 130 3.961+5 1.171 6
- 9. 90t+ 7 1.821*6 3.05t*7 6.63t*7 f
1-131 0.091 7 1.161 8 3.79t+10 1.981 8 2.89t*1 5.381+1 1 132 5.74tet 1.54t+2 5.381 3 2.451 2 i
1-133 2.12t+6 3.691 6 5.42t*8 6.44E+6 3.31E+6 1.12t+6
O D C M 7.0 Revision 8 Page 7.0-44
)
Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - ADULT (CONT.)
3 (mremlyr per g Ci/m ) for H-3 and C 14 (m2 x mrem /yr per C1/sec) for others suclide sees Liver Thyroid Eldney Ease 8 81-111 f.8edy 2.518-7 1.031-4 I-134 1.068-4 2.88t-4 5.00E 3
- 4. 59t-4 1.21E*5
- 3. 94 t +4 1-135 4.04t+4 1.07t+5 7.04E+6 1.71E 5 3.59E 9 1.19t+9 1.Det*8 9.07t+9 I
Co-134 4.66t*9 1.11E*10 9.24E+7 1.27t+7 1.89t+7 1.19t+8 Co 136 4.20E*7 1.66t+8 2.95t*9 9.81E*8 1.64t+4 5.70E+9 Co-137 6.36k+9 8.70t*9 Ca 138 1.94t 5 1.19t 5 5.23t-2 8.641 4 ta-139 2.95E-2 2.10E 5 5.49t+4 9.25t+4 2.65t+8 4.43t+6 ba-140 1.29t+8 1.62t+5 ga.141 Ba-142 i
7.24t+7 2.62t+2 la-140 1.971*3 9.92E+2 6.64t 1 1.541-5 La-142 1.401-4 6.35E 5 5.04t+8 1.51t+4 t.17t*4 Ce-141 1.96t+5 1.33E+5 2.77t+7 4.21E+1 3.24t+2 Ce-143 1.001 3 7.421 5 1.11t+10 1.77t+6 8.16t+6 Ce-144 3.291+7 1.381+7 2.74t+8 3.141 3 1.47t+4 I
tr 143 6.34E 4 2.541 4 1
Pr-144 1.85t+8 2.31t*3
)
2.25t+4 Nd 147 3.34t+4 3.861 4 1.05E 7 1.12E+4 W-147 3.82E*4 3.191 4 2.871 7 7.72E+t 4.371+2 NP-239 1.42E+1 1.40t+2 1
t
{
l
(
ODCM-7.0 j
Revision S Page 7.0-45 Table 7.0 4 l
Raipo, Vegetation Pathway Dose Factors - TEENAGER 3
l (mrem /yr per # Ci/m ) for H-3 and C44 2
l (m x mrem /yr per Ci/sec) for others Nuclide tone Liver Thyroit E18ney Imag 01-LLI T.Sody 2.592 3 2.59t*3 2.59t+3 2.59E*3 2.59E*3 2.59h*3 N3 l
C 14 1.45t+6 2.91t*5 2.91t*5 2.91t*5 2.9tE*5 2.91E*5 2.91E+5 l
Na 24 2.451*5 2.45t+5 2.45t*5 2.45E+5 2.45t+5 2.455 5 2.45t+5 1.35E*4 6.23E+7 F 32 1.61t+9 9.96t+7 3.44E+4 1.36t*4 8.85E+4
- 1. 04t* 7 6.20E*4 Cr-51 9.27t+8 8.971*7 1.35t*8 4.52E+8 Ma-5n 1.45t+1 1.83E+1 9.54E*2
- 2. ;8 t*0 Mn-56 Fe-55 3.25E+8 2.31E*8
' 1.46t*8 9.98t*7 5.38t*7 1.33E+8 9.98t*8 1.63t+8 te-59 1.8tt+4 4.22t*8 3.341 8 3.00E+7 1.79t+7 Co-57 6.04E+8 1.0lE*8 4.38t*7 Co-58 3.24E+9 5.60t*8 2.49E.8 Co-60 1.81E*8 5.45E+8 N1-63 1.61t+10 1.131 9 3.97E*2 3.331*0 bi-65 5.73tet 7.32t*0 8.40!*3 2.12E+4 6.51E*5 3.95t*3 Cu-64 6.23t+8 6.86t*8
- 9. 41 E+ 8 In-65 4.24E.8 1.471 9 2.88E-5 1.09E-6 1.021 5 2n-69 8.19E-6 1.56E-5 1.33E+6 St-82 Sr-43 3.01t*0 Br-84 I
t r.c 5 4.05t+7 1.281 8 2.731 8 RD-86 gg-88 Rb-89 1.801 9 4.331*8 St-89 1.51E.10 2.11t+10 1.85Ee11 Br-90 7.51t+11 1.36t+6 1.19t+4 St-91 2.991 5 1.01t+4 1.69E+1 Sr 92 3.971+2 1.02t*8 3.341*2 T-90 1.24 ten 2.561 7 Y 9te 5.431 9 3.25t*9 2.11E*5 1-91 7.875 6 2.32t+4 2.451-2 Y-92 8.471-1 4.98t*6 4.47E*0 Y-93 1,63E*2 1.27t+9 3.78t*5 8.07t+5 It-95 1.761 6 5.491 5 1.45t*7 2.811+1 9.26t+1 3r 97 3.091+2 6.11t*1 4.55t*8 5.86t+4 1.031 5 ht-95 1.921 5 1.06t 5 1.59E-2 2.441-7 7.80E-7 MD-97 2.691.6 6.671 7 1.03t*7 1.09t+6 1.31t+7 5.74t*6 Mo 99 1.12t*2 4.19t*0 4.95t*3 9.77E*1 l
Tc-99e 2.70t 0 7.541 0 Te-101 2.42t+7 5.74t*8 2.94t+6 8 103 6.87te6 4.04E*4 1.94tet 6.311 2 Ru-105 5.00tet 5.97t+8 1.48t*10 3.90t+7 Ru-106 3.09t*8 Rh-103e Sh-106 2.74t+7 4.04t*9 8.74t+6 As 110s 1.521 7 1.44t+7 1.351 8 3.11t*9 6.031,7 56 124 1.551 8 2.851 6 3.511 5 1.88t*8 1.66Ee9 5.00E*7 St-125 2.141 8 2.34te6 2.041 5 4.37E+8 1.98t+7 Te-125e 1.481 8 5.341 7 4.141 7 1.37E*9 6.56t*7 Te-127e 5.51t*8 1.941 4 1.311+8 2.241 9 4.191 5 1.17E*3 Te 127 5.43t*3 1.921 3 3.74t*3 2.20t*4 1.38t+9 5.81t+7 Te-129e 3.67E*8 1.361 8 1.18tet 1.541 9 3.40E-3
- 1. Sit-4 Te 12*
6.22t-6 2.321-4 4.45t 6 2.611 3 Te-13te 8.441 5 4.051 5 6.09te$ 4.221 6 3.251*7 3.3st+5 Te 131 7.821 7 2.32t+6 Te 132
- 3. 90 L
- 6 2.471 6 2.60t*6 2.37t+7 7.871 5 4.091 5 3-130 3.542*5 1.021 4 8.35t*7 1.58t+6
!=131 7.70t*7 1.081 8 3.14t*10 1.85t+8 2.13t+7 5.79t*7 5.91E*1 4.87t+1 2-132 5.18t*1 1.361 2 4.571**
2.14t+2 2.53t*6 1.02E*6 1-133 1.97t+6 3.341 6 4.66t+8 5.86t+6
ODCM 7.0 Revision 8 I
Page 7.0-46 Table 7.0-4
)
Raipo, Vegetation Pathway Dose Factors - TEEN AGER (CONT.)
(mrem /yr per y Ci/m ) for H 3 and C 14 l
3 (m2 x mremlyr per Ci/sec) for others j
}
Woc!!de seee Liver Thyteld Eldney Lues 81 111 f.8edy 3.35t-6 9.131-5 1 134 9.59E-5 2.545 4 4.261-3 4.01E-6 1.05t+5 3.52t*4 I-135 3.68t+6 9.68t+4 6.10E+6 1.50E+5 5.30t+9 2.02t+9 2.08t+8 7.74t+9 Co 136 7.09E*9 1.67E 10 9.19t+7 1.45E+7 1.36t+7 1.13t+8 Co-136 4.29t+7 1.69t+8 4.59t+9 1.78t+9 1.92E+8 4.69t+9 1
Cs-137 1.01t+10 1.35t+10 Co.138 1.848 5 1.34t-5 2.471-1 8.085-4 l
Sa-139 2.77E-2' 1.95t 5 5.75E+4 1.14E+5 2.13t+8 8.91t*6 Sa-160 1.38t+8 1.691+5
=
=
=
84 141 l
- 8. 142 5.08t*7 2.35t+2 La 160 1.80t+3 8.84t+2 1.73E+0 1.42t-5 i
14 142 1.28E-4 5.691-5 5.38t+8 2.16t+4
(
8.86t+6 co-141 2.82t+5 1.88t+5 2.05t+7 7.62t+1 l
3.06t+2 Ce 143 9.371+2 6.82t+5 1.33t+10 2.83E+6 l
1.30t+7 Ce-144 5.27t+7 2.18t+7 2.34t+8 3.55t*3 1.65t*6 Pr-143 7.12t+6 2.86t+6 Pt-144 1.421*8 2.36t*3 2.32t+4 W4 167 3.63t+4 3.96t+6 7.84t+6 1.02E*4 W-187 3.551 4 2.90t*6 2.108 7 7.241 1 6.091 2 WP-239 1.38te) 1.30t+2
ODCM 7.0 Revision S Page 7.0-47 Table 7.0 4 Raipo, Vegetation Pathway Dose Factors - CHILD 3
Ci/m ) for H-3 and C-14 imremlyr per (m2 x mremlyt per Ci/sec) for others J
uuclide sone Liver Thyroid Elener Luns GI-Lt.*.
T.Sody i
4.01E*3 4.01E+3 4.01E*3 4.01E*3 4.011+1 4.01E*3 l
H3 C-14 3.50E*6 7.01E*5 7.01E*5 7.01E*5 7.01E*5 7.01t*5 7.61E*5 ma-24 3.83E.5 3.83t+5 3.83E*5 3.83t+5 3.83t*5 3.83t+5 3.83E*5 9.30E 7 1.30E+s P-32 3.37t+9 1.58t+8 Cr-51 6.54E+4 1.79E 4 1.19E*5 6.25E+6 1.181+5 l
Mn 54 5.55E*8 1.76E+8 1.85E+8 6.61t*8 2.75Ee3 4.28t+0 2.29E*1
- 1. 90t* 1 Mn-56 2.40E*8 7.86t*7 1.31E+8 Fe-55 8.00E*8 4.24t*8 1.48t*8 6.76E*8 3.23E+8 Fe-59 4.01E*8 6.491+8 2.45E+8 6.04E+7 Co-57 2.99E.7 3.77E+8 1.98E*8 6.471 7 Co 58 2.10E*9 1.12E*9 Co-60 3.78E+8 1.42E*8 1.14t*9 Ni-63 3.95t+10 2.11Ee9 1.2tE*3 5.77E+0 Mi-65 1.05t+2 9.89teo I
5.20E*5 6.69E*3 2.68E+4 1.1tE*4 Cu-64
- 3. 60E+ 8 1.35E*9 1.36E*9 Zn 65 8.12Ee8 2.161+9 1.30E-3 2.02E-6 1.321-5 In-69 1.51E 5 2.18E-5 2.04E*6 er-82 5.55E+0 tr-83 er-84
=
=
8t*85 2.91E*7 2.78E*8 Rb-86 4.521*8 Ap*88 Rb-49
=
=
1.39E*1 1.03E+9 5t-89 3.59t+10 1.671+10 3 tSE*11 S t - 90 1.24E+12 1.21E+6 2.08E*4 er-91 5.50t*5 1.38E*4 2.921*1 St-92 7.28E*2 6.56E+7 6.17E*2 V-90 2.301+6 1.95E-5 Y-9te 9.961-9 2.49E+9 5.011+5 Y 91 1.871+7 4.51E*4 4.46E-2 Y-92 1.561*0 4.48Ee6 8.25t+0 Y-93 3.011 2 8.95E+8 F.64E*5 1.23t*6 l
2r-95 3.901 6 8.581 5 1.17t+2 1.23Ee7 4.8tt+1 Zr-97 5.64E 2 8,15tet 2.95E+8 1.14E+5 1.50s.5 hb 95 4.10tel 1.59tes 2.73E-1 4.13E 7 9.821-7 Mb-97 4.90E-6 5.851 7 1.671+7 6.48E*6 1.94E+6 7.831 6 Mo-99 1.33t+2 4.63E*0 5.19E*3 1.51E+2 Tc-99e
- 4. 6 51= 1 9.121*0 Te-tol 3.99t+8 5.94E*6 3.89te?
au-103 1.55L+7 5.98E*4 3.33t*1 8.06t*2 i
Ru-105 9.171+1 1.16E*90 9.30E+7 Ru-106 7.45t*8 1.011 9 Rh-103e Rh-106 2.58E*9 1.741*7 4.05t*7 as 110e 3.22t*7 2.17t*7 1.96t+8 2.20t+9 1.23E*8 56-124 3.52t*8 4.571+6 7.78tel 2.781 8 1.19t+9 1.0$E*8 5b-125 4.99t 8 3.851 6 4.64t+5 j
3.38E*8 4.67Ee7 l
Te-125e 3.51t*8 9.501 7 9.84t.)
1.07E*9 1.57E*8 Te-127e 1.321*9 3.56t*8 3.16t+8 3.771*9 3.9tt+5 2.15k+3 Te-127 1.001 4 2.70t*3 6.93E.3 2.85t*4 1.04t*9 1.33Ee8 Te 129e 8.54E+s 2.49t*8 2.751 4 2.51E*9 7.171-2 2.74E 4 Te-129 1.15L 3 3.221 4 8.22E 4 3.37E 3 2.16t+7 5.68E 5 Te-131e 1.54t*e 5.33t+5 1.10L*6 5.16E*6 y,.g35 3.11E+7 3.73E*6 Te-132 6.98t*6 3.09E*6 4.50t+6 2.87E*7 5.47tel 6.47t+5 1 130 6.21E*5 1.26t*6 1.381 8 1.88L.6 1-131 1.43Ee8 1.641 8 4.76t*10 2.36t+8 1.24E+7 8.18t+7 1.99t+2 7.771+1 1-132 9.201+1 1.69te2 7.861,3 2.591+2 1.79E+6 1.68E+6 2-133 3.591+6 4.46t*6 8.25t*8 7.401+6
ODCM-7.0 Revision 8 Page 7.0-48 Table 7.0-4 Raipo, Vegetation Pathway Dose Factors - CHILD (CONT.)
3 (mremlyr per p Ci/m ) for H-3 and C 14 (m2 x mrem /yr per Ci/sec) for others Wuclide emme Liver Thyroid Eldaer Emes 81 Lt.1. T.Sedy 2.101-4 1.461-4 2 134 1.701-4 3.16E-4 7.28E-3 4.84E-4 8.98t*4 5.57E*4 2-135
- 6. 54 E* 4 1.18t*5 1.04t+7 1.01E+5 8.14E*9 2.92E+9 1.42t*8
- 5. 54d+9 Co-134 1.60E+10 2.63E+10 1.18E+8 1.76E*7 7.79E*6 1.43E+8 Co-136 8.06t+7 2.22E*8 7.46E+9 2 68E+9 1.63E+8 3.38t+9 Co-137 2.391+10 2.29t+10 Co-138 2.38E-5 1.61E 5 2.95E+0 1.44E-3 Be-139 5.11E-2 2.731 5 7.90E+4 1.45E 5 1.40E.8 1.62E*7 Se-140 2.771*8 2.43E*5 be-141 Se-142
+
3.11E+7 3.81E*2 14-140 3.23E*3 1.13Ee3 14-142 2.321-4 7.401-5 1.471+1 2.328-5
- 7. 66t+7 9.12E*3 2.69E*4 Ce-141 1.23E+5 6.14E+4 l
1.37E*7 1.36Ee2 3.93t+2 Ce-143 1.731 3 9.36E*5 1.04E*10 6.78E*6
)
2.21t+7 Ce-144 1.271 8 3.98t+7 2.41E*4 1.60t+8 7.37E*3 Pr-143 1.48t+5 4.46t+4 Pr 144 9.18E*7 4.49E*3 3.181e4 Nd 147 7.161 4 5.801 4 5.38E+6 1.72E+4 W-187 6.471+4 3.43t+6 1.36E*7 1.29E*2 5.30E*2 N -339 2.55t*3 1.43E*2 P
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ODCM-7.0 f
Revision 8 Page 7.0-49 f
Table 7.0-4 Raipo, Ground Piane Pathway Dose Factors
-(m2 x mremlyr per Ci/sec) i Nuclide Amy Orean N-3 C-14 No-26 1.21E+7 P 32 Cr-51 4.68t+6 Mn-54 1.34E+9 Ma-56 9.05t+5 Fe-55 Fe-59 2.75E+8 Co-58 3.82t*8 Co-60 2.16E+f0 Mi-63 Ni-65 2.97t+5 Cu-64 6.091+5 ta-6S 7.45t*8 1
Zn 69 St-83 4.898 3 tr-86 2.03t*5 tr-45 Rb-86 8.98t*6 Rb-88 3.29t+4 ab-89 1.21E+5
$r-89 2.16t+4 St-90 St-91 2.19t+6 st*92 1.11E*$
Y-90 e.4tE*3 T-91e
- 1.01E+5 T-91 1.08t+6 Y 92 1.80E+5 Y 93 1.85t+5 1r-95 2.48t+8 Zr-93 2.945 6 Mb-95 1.36t*8 Mo-99 4.05E+6 Te 9ve 1.83E+5 Tr-101
_2.04E+4 Re-103 1.09t+8 t
J Rv 105 6.16t+5 l
Re-106
- 4. 21E* 8.
l mh 103.
Sh*106 As tion 3.47E*9 Te-125e 1.55t+6 Te=123e 9.17E*4 m
Te-127 3.00E*3 Te 129m 2.00t+7 Te-129 2.60E*4 Te 13ne 8.03E+6 Te-131 2.93t+4 Te-132 4.22t+6 2 130 5.531 6 1 131 1.72t+7 3 132 1.24t+6 3 133 2.47t+6 3-116 4.49t+5 1 135 2.56t+6 Co 13e 6.75t*9 Cs 136 1.49t+8 i
Cs 137 1.04t*10 1
l l
ODCM-7.0 Revision 8 Page 7.0-50 Table 7.0-4 I
Raipo, Ground Plane Pathway Dose Factors (CONT.)
(m2 m mremlyr per Ci/sec)
I Sustade any Orgas Co-138 3.$9E*S te-139 1.06E*5 Sa-140 2.0SE* 7 ha-141 6.SSE*4 Sa 142 4.49E*4 La-140 1.91E*7 La-142 7.361*$
Ce-141 1.36E*7 Ce-143 2.325*6 Ce 144 6.95t*7 Pt-14)
Pr-144 1.83E*3 hd 147 8.40E*6 W-187 2.36E*6 Np-239 1.71E*6 l
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Nuclear Production - Fermi 2 ODCM 8.0 Offsite Dose Calculation Manual Revision 6 Page 8.0-1 l
SPECIAL DOSE ANALYSIS l
8.0 SPECIAL DOSE ANALYSES 8.1 Doses Due to Activities inside the SITE BOUNDARY in accordance with ODCM 5.9.1.8, the. Annual Radioactive Effluent Release Report submitted within 90 days after January 1 of each year shallinclude an assessment of radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.
Two locations within the Fermi 2 SITE BOUNDARY are accessible to MEMBERS OF THE PUBLIC for activities unrelated to Detroit Edison operational and support activities. One is the over-water portion of the SITE BOUNDARY due east of the plant. Ice fishermen sometimes fish here during the winter. The other is the Fermi 2 Visitor's Center, outside the protected area (but inside the Owner Controlled Area), approximately 470 meters SSW of the Reactor Building. The Visitor's Center is open to the public and is routinely visited by MEMBERS OF THE PUBLIC, including school tour groups on a
~
frequency of once per year.
Conservative assumptions of locations, exposure times; and exposure pathways for assessing doses from gaseous and liquid effluents due to activities inside the SITE SOUNDARY are presented in Table 8.0-1. The calculational methods presented in ODCM Sections 7.6 and 7.7 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC based on the above assumptions. Alternatively, the effluent concentration values of Appendix B. Table 2. of the revised 10 CFR Part 20 may be used to assess dose since these concentrations, if continuously inhaled or ingested, produce a total effective dose equivalent of 50 mrem per year.
The potential dose from the fish pathway to a MEMBER OF THE PUBLIC engaged in ice fishing within the SITE BOUNDARY is accounted for by the modeling presented in ODCM Section 6.5. Therefore, no additional special dose analyses are required for this exposure pathway for reporting in the Annual Radioactive Effluent Release Report.
8.2 Doses to MEMBERS OF THE PUBLIC - 40 CFR 190 The Annual Radioactive Effluent Release Report shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources (including dose contributions from effluents and direct radiation from onsite sources). For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of the Fermi 2 site, the sources of exposure need consider only the radioactive effluents and direct exposure contribution from Fermi 2.
l ODCM-8.0 i
Revision 6 I
Page 8.0-2 l
No other fuel cycle facilities contribute significantly to the cumulative dose to a MEMBER I
OF THE PUBLIC in the immediate vicinity of the site. Davis-Besse is the closest fuel cycle facility located about 20 miles to the SSE. Due to environmental dispersion, any routine releases from Davis-Besse would contribute insignificantly to the potential doses in the vicinity of Fermi 2.
I As appropriate for demonstrating / evaluating compliance with the limits of ODCM 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used to provide data on actual measured levels of radioactive material in the actual pathways of exposure.
8.2.1 Effluent Dose Calculations For purposes of irnplementinc the surveillance requirements of ODCM 3.11.4 and the reporting requirements of ODCM 5.9.1.-8, dose calculations for Fermi 2 -
may be performed using the calculational methods contained within this ODCM; the conservative controlling pathways and locations of Table 7.0-3 or the actual pathways and locations as identified by the land use census (ODCM 3.12.2 and ODCM 9.0) may be usedL Liquid pathway doses may be calculated using Equation (610). Doses due to releases of radiolodines, tritium and particulate may be calculated based on Equation (7-14).
The following equations may be used for calculating the doses to MEMBERS OF THE PUBLIC from releases'of noble gases. Equation (8-2)is not used for evaluating compliance with 40 CFR Part 190, since this regulation does not address skin dose. If noble gases are being released from more than one point, these equations must be used to evaluate each release point separately, and then the doses must be added to obtain the total noble gas dose.
g = 3.17 E -08
- X / Q
- hK;
- Q;)
D
~
(8-1) and D
= 3.17 E - 08 X / Q -[ (L; + 1.1M;)
- Q; s
I (8-2) where:
total body dose due to gamma emissions for noble gas Db t
=
radionuclides (mrem) skin dose due to gamma and beta emissions for noble, gas Ds
=
l radionuclides (mrad) 1 atmospheric dispersion to the offsite location (sec/m3)
X/O
=
ODCM-8.0 Revision 6 Page 8.0-3 cumulative release of noble gas radionuclides i over the Oi
=
period of interest (pCi)--may be determined according to Equation (7-8) concentration of radionuclides i as determined by gamma Ci
=
spectral analysis of media (pCi/ml)
(1E + 03 ml/ iter) * (1 min /60 sec) 1.67E + 01
=
total body dose factor dLe to gamma emissions from noble Ki
=
gas radionuclides i (mrem /yr per pCi/m3)
(from Table 7.0-2) skin dose factor due to beta emissions from noble gas Li
=
radionuclides i (mrem /yr per pCi/m3) (from Table 7.0-2) gamma air dose factor for noble gas radionuclides i Mi
=
(mrad /yr per pCi/m3) (from Table 7.0-2) mrem skin dose per mrad gamma air dose (mrem / mrad) 1.1
=
1/3.15 E + 07 yr/sec 3.17 E 08
=
Average annual meterological dispersion parameters or meterological conditions concurrent with the release period under evaluation may be used (e.g., quarterly averages or year specific annual averages).
8.2.2 Direct Exposure Dose Determination From evaluations performed in the Fermi 2 Environmental Report, Section 5.3.4, the direct exposure to the highest offsite location from the Turbine Building N-16 skyshine dose has been calculated to be approximately 3 mrem / year. This value may be used as a baseline for actual direct exposure during plant operations.
Direct exposure to offsite or onsite individuals may be evaluated based on the results of environmental measurements (e.g. area TLD and survey meter data) 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 Fermi 2 that would yield potentially significant offsite doses to a MEMBER OF THE PUBLIC. However, should a situation exist whereby the direct exposure contribution is potentially significant, onsite measurements, offsite measurements and calculational techniques will be used for determination of dose for assessing 40 CFR 190 compliance. The calculational technique's will be identified, reviewed, and approved at that time, and will be included in any report on doses due to such atypical conditions.
ODCM 8.0 Revision 6 Page 8.0-4 1
8.2.3 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 materialin the offsite environment are usually
]
so minute as to be undetectable. The calculational methods presented in this ODCM are used for modeling the transport in the environment and the resultant exposure to offsite individuals.
4 The results of the radiological environmental monitoring pr > gram can provide input into the overall assessment of impact of plant operations and radioactive effluents. With measured levels of plant related radioactive materialin principal pathways of exposure, a quantitative assessment of potential exposures can be performed. With the monitoring program not identifyirig any measurable levels, the data provides a qualitative assessment - a confirmatory demonstration of the negligible impact.
Dose modeling can be simplified into three basic parameters that can be applied in using environmental monitoring data for dose assessment:
D = C = U
- DF (8-3) l where:
dose or dose commitment D
=
concentration in the exposure media, such as air concentration for the C
=
inhalation pathway, or fish, vegetation or milk concentration for the ingestion pathway individual exposure to the pathway, such as br/yr for direct exposure, U
=
kglyr for ingestion pathway DF =
dose conversion factot to convert from an exposure or uptake to an individual dose or dose commitment The applicability of each of these basic modeling parameters to the use of environmental monitonng data for dose assessment is addressed below:
Concentration - C The main value of using environmental sampling data to assess potential doses to individuals is that the data represents actual measured levels of radioactive materialin the exposure pathways. This eliminates one main uncertainty and the modeling has been removed the release from the plant and the transport to the environmental exposure medium.
ODCM-8.0 Revi.sion 6 Page 8.0-5 Environmental samples are collected on a routine frequency per the ODCM. 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:
{ = MC;
- t) /365 (8-4) where:
Ci average concentration in the sampling medium for the year
=
concentration of each radionuclides i measured in the individual Ci
=
sampling medium period of time that the measured concentration is considered t
=
representative of the sampling medium (typically equal to the sampling frequency; e.g.,7 days for weekly samples,30 days for monthly samples).
If the concentration in the sampling medium is below the detection capabilities (i.e., less than Lower Limits of Detection (LLD), a value of zero should be used for Ci (Ci = 0).
Exposure - U Default Exposure Values (U) as recommended in Regulatory Guide 1.109 are presented in Table 8.0 2. 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, 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 actuallocations of exposure.
Hydrological or atmospheric dilution f actors can be used to provide reasonable correlations of concentrations (and doses) at other locations. The other alternative is to conservatinly assume a hypothetical individual at the sampling location. Doses that are caMulated in this manner should be presented as hypothetical and very conservatively determined - actual exposure would be much less. Samples collected from the Monroe water supply intake should be used for estimating the potential drinking water doses. Other water samples
' collected. such as near field dilution area, are not applicable to this pathway.
ODCM-8.0 Revision 6 l
Page 8.0 '
l 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 RG 1.109 values applicable to the exposure pathway and maximum exposed individual is referenced in Table 8.0-2.
Assessment of Direct Exposure Doses from Noble Gases 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 was generally impractical to distinguish any plant contribution to the natural background radiation levels (direct exposure) below around 10 mrem per year. Therefore, for routine releases from nuclear power plants the use of TLD is mainly confirmatory - ensuring actual exposures are within the expected natural background variation.
For releases of noble gases, environmental modeling using plant measured releases and atmospheric transport models as presented in ODCM Sections 7.6 and 8.2.1 represents the best method of assessing potential environmental doses. However, under unusual conditions, direct radiation from noble gas concentrations could be sufficient to cause significant increases in TLD readings; any observed vanations 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.
END OF SECTION 8.0
l ODCM-8.0 Revision 6 Page 8.0-7 l
TABLE 8.0-1 Assumptions for Assessing Doses Due to Activitics inside SITE BOUNDARY Ice Fishing Visitor's Center Distance /
470 meters / E 470 meters / SSW Direction:
Estimated 240 hr/yr 4 hr/yr Exposure (20 hr/ week over (4 hr/ visit,1 visit Time:
3 month period) per year)
Exposure direct exposure direct exposure Pathways:
from noble gases from noble gases inhalation of inhalation of tritium, iodines, tritium, lodines particulate particulate Meteorological annual average annual average Dispersion:
(as determined (as determined for year being for year being evaluated) evaluated) 6.48E 6 sec/m '
2.54E-6 sec/m3 3
Annual average X/O values for 1991. These values are llown as examples of '
the range of values to be expected.
~~
1 4
I l
ODCM-8.0 Revision 6 Page 8.0-8 TABLE 6.0-2 Recommended Exposure Rates in Lieu of l
Site Specific Data
- Table Reference Exposure Pathway Maximum Exposed Exposure Rates for Dose Factor Age Group from RG 1.109 Liquid Releases Fish Adult 21 kgly E-11 C: inking Water Adult 7301/y E-11 Bottom Sediment Teen 67 h/y E-6 Atmospheric Releases i
Inhalation Teen 8,000 m3/y E-8
)
Direct Exposure All 6,100 h/y" N/A I
Leafy Vegetables Child 26 kg/y E-13 Fruits, Vegetables Teen 630 kg/y E-12 and Grain Milk Infant 330 t/y E-14 Adapted from Regulatory Guide 1.109, Table E 5. This table is not a complete list of exposure rates; other applicable values may be found in Regulatory Guide 1.109.
Net exposure of 6,100 h/y is based on the total 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> per year adjusted by a 0.7 shielding factor as recommended in Regulatory Guide 1.109.
l l
I END OF SECTION 8.0 l
1 l
i 1
)
Nuclear Production - Fermi 2 ODCM-9.0 Offsite Dose Calculation Manual Revision 6 Page 9.0-1 l
ASSESSMENT OF LAND USE CENSUS DATA l
9.0 ASSESSMENT
OF LAND USE CENSUS DATA A Land Use Census (LUC)is conducted annually in the vicinity of the Fermi 2 site. This census fulfills two main purposes: 1) Meet requirements of ODCM 3.12.2 for identifying controlling location / pathway for dose assessment of ODCM 3.11.2.3; and 2) provide data on actual exposure pathways for assessing realistic doses to MEMBERS OF THE PUBLIC.
9.1 Land Use Census as Required by ODCM 3.12.2 As required by ODCM 3.12.2, a land use census shall be conducted during the growing season at least once per twelve months. The purpose of the census is to identify within a 5 mile distance the location in each of the 16 meterological sectors of all milk producing 2 producing broadleaf animals, all meat producing animals, all gardens larger than 500 ft vegetation, and the closest residence to the plant. The data from the LUC is used for j
updating the location / pathway for dose assessment and for updating the Radiological i
Environmental Monitoring Program.
l If the census identifies a location / pathway (s) yielding a higner potential dose to a MEMBER OF THE PUBLIC than currently being assessed as required by ODCM 3.11.2.3 (and ODCM l
Section 7.7 and Table 7.0-3), this new location pathway (s) shall be used for dose assessment.
Table 7.0-3 and plant procedures shall be updated to include the currently identified controlling location / pathway (s). Also, if the census identifies a location (s) that yields a calculated potential dose (via the same exposure pathway) 20% greater than a location currently included in the Radiological Environmental Monitoring Program, the new location (s) shall be added to the program within 30 days, unless permission to take samples cannot be obtained from the affected landowner. The sampling location (s), excluding control locations, having the lowest calculated dose may be deleted from the program after October 31 following the current census. As required by ODCM 3.12.2 and 5.9.1.8, the new location / pathway (s) shall be identified in the next Annual Radioactive Effluent Release Report. The following guideline shall be used for assessing the r9its from the land use census to ensure compliance with ODCM 3.12.2.
9.1.1 Data Compilation 1.
Compile allocations and pathways of exposure as identified by the land use census.
2.
From this compiled data, identify any changes from the previous year's census. Identify the current controlling location /psthway (critical receptor) used in ODCM Table 7.0-3. Also, identify any location currently included in the REMP (Table 10-1).
l i
)
ODCM-9.0 l
Revision 6 Page 9.0-2 9.1.2 Evaluation of Relative Dose Significance if any identified ch'anges are likely to change the identity of the critical receptor or to result in a potential dose via a particular pathway which is at least 20% greater than the current maximum dose for that pathway, perform the following:
1.
Determine the historical, annual average meterological dispersion and deposition parameters (X /O, D/0) for any location to be evaluated for dose
. significance. All locations should be evaluated against the same historical meterological data set.
2.
Perform relative dose calculations based on actual Fermi 2 gaseous effluent releases for a recent period of reactor operation, using the pathway dose equations of the ODCM. In identifying the critical receptor for Table 7.0-3, all age groups and all pathways relevant to ODCM 3.11.2.3 that may.
be present at each evaluated location are considered. The critical receptor is assumed to be a member of the age grou'p with the highest calculated
. dose to the maximally exposed organ due to 1-131,1-133, tritium, and particulate with half lives greater than 8 days. Other receptors may have higher doses to other organs than the critical receptor has to those organs.
3.
Formulate a listing of locations of high dose significance in desconding order of relative dose significance include the relative dose significance in the listing.
.9.1.3
~ Program Updates 1.
If any receptor is identified with a higher relative dose than the current critical receptor in ODCM Table 7.0-3, this receptor and its associated l
location and pathways should replace the previously identified critical receptor information in Table 7.0-3.
2.
The Land Use Census data should be used to revise the REMP and Section 10.0 of the ODCM in accordance with ODCM 3.12.2, Action item b.
' 3.
Any changes in either the controlling location / pathway (s) (critical receptor) for the ODCM dose calculations (Section 7.7 and Table 7.0-3) or the REMP l
(ODCM Section 10.0 and Table 10-1) shall be reported to NRC in accordance with ODCM 3.12.2. Action items a. and b. and ODCM 5.9.1.8.-
i 1
ODCM-9.0 Revision 6 Page 9.0-3 NOTE: As permitted by footnote to ODCM 3.12.2, broadleaf vegetation sampling may be performed at the SITE BOUNDARY in two locations,in different sectors with highest predicted D/Os,in lieu of the garden cersus.
Also, for conservatism in dose assessment for compliance with ODCM 3.11.2.3 (see also ODCM Section 7.7 and Table 7.0-3), hypothetical exposure location / pathway (s) and conservative dispersion factors may be assumed (e.g., milk cow at 5 mile location or garden at SITE BOUNDARY in highest D/O sector). By this approach, the ODCM is not subject to frequent revision as pathways and locations change from year to year. A verification that the hypothetical pathway remains conse:vative and valid is still required. Also, for NRC reporting, the actual pathways and doses should be reported along with the hypothetical. The reporting of the actual pathway and doses provides a formal documentation of the more realistic dose impact.
9.2 Land Use Census to Support Realistic Dose Assessment The LUC provides data needed to support the special dose analyses of the ODCM Section 8.0. Activities inside the SITE BOUNDARY should be periodically reviewed for
{
dose assessment as required by ODCM 5.9.1.8 (see also ODCM Section 8.1).
Assessment of realistic doses to MEMBERS OF THE PUBLIC is required by ODCM 3.11.4 for demonstrating compliance with the EPA Environmental Dose Standard, 40 CFR 190 (ODCM Section 8.2).
To support these dose assessments, the LUC shailinclude use of Lake Erie water on and near the site. The LUC shallinclude data on Lake Erie use 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 ODCM Section 6.5.
l END OF SECTION 9.0 l
l
~ =
l Nuclear Production - Fermi 2 ODCM-10.0 Offsite Dose Calculation Manual Revision 7 Page 10.0-1 l
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l
10.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l
The Rackalogical Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of ODCM 3.12.1. The sampling and analysis program described herein was developed to provide representative measurements of radiation and radioactive niatericts resulting from station operation in the principal pathways of exposure of MEMBERS OF THE PUBL!C. This monitoring program im 71ementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the I
radiological effluent control program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher thaa expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for the development of this monitoring program is provided by the NRC Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.
10.1 Sampling Locations Sampling locations as required by ODCM 3.12.1 are described in Table 10.0-1 and shown on the maps in Figures 10.0-1,10.0 2,10.0-3, and 10.0-4. Fermi 1 sampling locations are described in Table 10.0-2 and shown on the map in Figure 10.0-5.
NOTE: For purposes of imycmenting ODCM 3.12.2, sampling locations will be modified as required to reflect the findings of the annualland use census as described in OOCM Section 9.1 and as required by other contingencies (e.g. unavailability of milk from a : listed location). Such changes will be documented in plant records and reflected in the next ODCM revision, the riext Annual Effluent Release Report, and the next Annual Radiological Environmental Operating Report. Also, if the circumstances of such changes involve a possible change in the maximal,ly
. e> posed individual evaluated for ODCM Control 3.11.2.3, the identity of this individual will be reevaluated.
10.2 Reporting Levels ODCM 'f12.1, Action b. describes enteria for a Special Repor1 to the NRC if levels of plant-related radioat.tive matenal, when veraged over a calendar quarter, exceed the prescribed levels of ODCM Table 3.12.12. Tne reporting levels are based on the design objective doses of 10 CFR 50, Appendix i (i.e., the annuallimits of ODCM 3.11.1.2,3.11.2.2 and 3.11.2.3). In other words, levels of radioactive materialin the respective sampling medium equal to the prescribed reporting levels are representative of 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 the gaseous effluent pathway. These potential doses are modeled on the maximum individual Exposure or consumption rates of NRC Regulatory Guide 1.109.
t L
ODCM-10.0 Revision 7 Page 10.0-2 The evaluation of potential doses should be based solely on radioactive material resulting from plant operation. As stated in ODCM 3.12.1, Action b, the report shall also be submitted if radionuclides other tnan those in ODCM Table 3.12.1-2 are detected (and are a result of plant effluents) and the potential dose exceeds the above annual design objectives. The method described in ODCM Section 8.2.3 may be used for assessing the potential dose and required reporting for radionuclides other than those in ODCM Table 3.12.12.
10.3 Interlaboratory Comparison Program A major objective of this program is to assist laboratories involved in environmental radiation measurements to develop and maintain both an intralaboratory and an interlaboratory quality control program. This is accomplished through a laboratory intercomparison study (" cross-check") program involving environmental media and a variety of radionuclides with activities at or near environmental levels.
Simulated environmental samples, containing known amounts of one or more radionuclides, are prepared and routinely distributed to Detroit Edison's contract environmentallaboratory, which performs the required analyses. The analysis results are then compared to the known concentrations in the samples. The program thus enables the laboratory to document the precision and accuracy of its radiation data, and identify instrument and procedural problems.
The environmental laboratory is required to participate in an Interlaboratory Comparison Program and to submit OA Program Progress Summary Reports to Detroit Edison on an
.j annual basis. These reports contain performance data summaries on blind spiked
)
analyses, and explanations of deviations from expected results. A summary of the 1
Interfaboratory Companson Program results obtained is required to be inc!uded in the Annual Radiological Environmental Operating Report pursuant to ODCM 5.9.1.7.
Participation in an Interlaboratory Comparison Program ensures that an independent check on the precision and accuracy of the measurements of radioactive materialin environmental sample matrices is performed as part of the OA Program for environmental monitoring in order to demonstrate that the results are valid for the purpose of l
Section IV.B.2 of Append.x 1 to 10 CFR Part 50.
t I
ODCM-10.0 Revision 7 Page 10.0-3 TABLE 10.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FERMI 2 SAMPLE LOCATIONS AND ASSOCIATED MEDIA KEY 1-T TLD Locations (Pg.10.0-4 through 10.0-8) 2-S Sediments Locations (Pg.10.0-9) 3-F Fish Locations (Pg.10.0-9) 4-M Milk Locations (Pg.10.010) 5-DW Drinking Water locations (Pg.10.011) 6-SW Surface Water Locations (Pg.10.011) 7-GW Ground Water Locations (Pg.10.011) 8-API Air Particulate / lodine Locations (Pg.10.0-12) 9-FP Food Products Locations (Pg.10.013) 1
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Nuclear Production - Fermi 2 ODCM-APP-A Offsite Dose Calculation Manual Revision 5 Page A-1 APPENDIX A: TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS LIQUID EFFLUENT RELEASES Overview To simplify the dose calculation process, it is conservative to identify a controlling, dose-significant radionuclides and to use its dose conversion factor in the dose calculations. Using the total release (i.e., the cumulative activity of all radionuclides) and this single dose conversion factor as inputs to a one-step dose assessment yields a dose calculation method which is both simple and conservative.
Fermi 2 does not have a large data base of previous releases of radioactive liquid effluents upon which to base the determination of the controlling, dose-significant isotope. The Fermi 2 UFSAR, Table 11.2-9 presents the estimated annual releases from liquid effluents as calculated using the NRC GALE computer code, (NUREG-0016, Revision 1). Site specific dose conversion factors (A o) i from ODCM Table 6.0-1 were multiplied by the UFSAR estimated annual release quantity to determine a relative dose significance. Table A-1 presents the results of this relative dose evaluation.
Because Cs-134 is the controlling nuclide for the total body dose and has the highest dose conversion factor among the nuclides evaluated for that dose, the use of its dose conversion factor in
~
the simplified dose assessment method for evaluating the total body dose is demonstrably conservative.
Selection of the appropriate dose conversion factor for the maximum organ dose is not so straightforward. Inspection of Table A-1 shows that the thyroid dose iu the controlling organ dose, and it follows that the iodines are the controlling radionuclides. However, this identification is based upon the FSAR estimate of annual releases. To be adequately conservative when using this simplified method, it is appropriate to select the largest dose conversion factor from among all the radionuclides evaluated to assure that offsite doses are not mistakenly underestimated.
For the UFSAR Table 11.2 9 isotopes evaluated, there are a few radionuclides with a higher dose conversion factor than 1-133 for the thyroid dose. Further inspection of Table A 1 shows that P 32 is the major contributor to the dose to the bone, which is the second highest organ dose. P-32 has a high dose conversion factor (1.39 E + 06 mrem /hr per uCi/ml) and would provide additional conservatism if used as the simplifying dose conversion factor. However, analysis for P-32 is not required. P-32 decays by beta emission without any accompanying characteristic gammas.
Use of the P-32 dose conversion factor is therefore inappropriate. The next largest dose conversion factor of the evaluated radionuclides is Cs-134 for the dose to the liver at 7.09 E + 05 mrem /hr per uCi/ml. (The dose to the liver is the third largest organ dose.) As Cs-134 is easily measured with gamma spectroscopy, has a long half-life, and a high organ dose conversion factor, n is used as the controlling radionuclides for the simplified maximum organ dose assessment.
ODCM-APP A Revision 5 Page A 2 Simplified Method For evaluation of compliance with the dose limits ODCM 3.11.1.2, the following simplified equations may be used:
Total Body 1.67E - 02
- VOL
^
Dg=
(Cs - 134.tb)
- I C, (A-1) where:
Dtb
= dose to the total body (mrem)
VOL
= volume of liquid effluents released (gal)
= average circulating water reservoir decant line flow (gal / min)
Z
= 5, near field dilution factor (derived from Regulatory Guide 1.109)
A(Cs-134,tb)
= 5.80 E + 05 mrem /hr per pCi/ml, the total body ingestion dose factor for Cs-134 Ci
= total concentration of all radionuclides (pCi/ml) 1.67 E - 02 1 hr/60 min
=
Substituting the value for the Cs-134 total body dose conversion factor, the equation simplifies to:
9.69E + 03
- VOL Dib "
DF*Z i
(A2)
Maximum Organ D,,, = 1.67 E - 02
- VOL A
(Cs - 134, liver)
- Z C, (A3) where:
Dmax
= maximum organ dose (mrem)
A(Cs-134, liver)
= 7.09 E + 05 mrem /hr per pCi/ml, the liver ingestion dose factor for Cs-134
ODCM APP A Revision 5 Page A-3 Substituting the value for the Cs 134 liver dose conversion factor, the equation simplifies to:
i 1.18E + 04
- VOL Dmax DF*Z 8
I I
.(A4)
Tritium is not included in the limited analysis dose assessment for liquid releases, because the l_
potential dose resulting from normal reactor releases is relatively negligible. Furthermore, the release of tritium is a function of operating history and is essentially unrelated to radwaste system operations.
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Nuclear Production - Fermi 2 ODCM-APP-B Offsite Dose Calculation Manual Revision 5 Page B-1 APPENDIX B: TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS j
GASEOUS RADWASTE EFFLUENTS Orsiew Dose evaluations for releases of gaseous radioactive effluents may be simplified by the use of an effective dose factor rather than radionuclides-specific dose factors. These effective dose factors are applied to,the total radioactive release to approximate the various doses in the environment; i.e., the total body, gamma air, and beta-air doses. The effective dose factors are based on tia typical radionuclides distribution in the gaseous radioactive effluents. This approach reduces the analyses to a single multiplication (Keff, Meff, or Neff) times the quantity of radioactive gases released, rather than individual analyses for each radionuclides and summing the results to determine the dose. Yet the approach provides a reasonable estimate of the actual doses since under normal operating conditions there is relatively little variation in the radionuclides distribution.
Determination of Effective Dose Factors Effective dose transfer factors are calculated by the following equations:
Kc77 = 1 (K; - f;)
(B-1) where:
the effective total body dose f actor due to gamma emissions from all noble Keff
=
gases released (mrem /yr per pCi/m3, effective) the total body dose factor due to gamma emissions from each noble gas Ki
=
radionuclides i released (mrem /yr per pCi/m3, from Table 7.0-2) the fractional abundance of noble gas radionuclides i relative to the total noble fi
=
gas activity (L + 1.1 M leff = 1 (L; + 1.1 M;)
- f; (B-2) i I
l l
d
ODCM-APP-B Revision 5 Page B-2 where:
the effective skin dose factor due to beta and gamma emissions (L + 1.1 M)ett
=
from all noble gases released (mrem /yr per uCi/m3, effective) the skin dose factor due to beta and gamma emissions from each (Li + 1.1 Mj)
=
noble gas radionuclides i released (mrem /yr per uCi/m3, from Table 7.0-2)
- g. = kM
- f;)
M g
(B-3) where:
the effective air dose factor due to gamma emissions.from all noble gases Meff
=
released (mradlyr per uCi/m3, effective)
I the air dose factor due to gamma emissions from each noble gas Mi i
=
radionuclides i released (mrad /yr per uCi/m3, from Table 7.0-2) l clT
- I(N
- I) i I
(B-4) l l
where:
the effective air dose factor due to beta emissions from all noble gases Neff
=
released (mradlyr per uCi/m3, effective) the air dose f actor due to beta emissions from each noble gas radionuclida i Ni
=
released (mradlyr per uCum3, from Table 7.0-2)
Normally, past radioactive effluent data would be used for the determination of the effective dose factors. Fermi 2, however, does not have a sufficient operating history at or near full power to provide a reasonable data base for determination of the typical radionuclides i
distribution in gaseous effluents. Therefore tne UFSAR estimate of radionuclides concentrations at the site boundary is used as the initial typical distribution. The effective dose factors derive ( om this distnbution are presented in Table B-1.
l
ODC' APP-B M
Revision 5 Page B 3 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.
For evaluating compliance with the dose limits of ODCM 3.11.2.2 the following simplified equations may be used:
D = 2.0
- 3.17 E- 08
- x / Q
- M,ff *EQ; (B-5) l and Dp = 2.0
- 3.17 E - 08
- X / Q
- N,ff *1Q; (B-6) where:
D Y
air dose due to gamma emissions for the cumulative release of all noble gases (mrad)
=
D 0
air dose due to beta emissions for the cumulative release of all noble gases (mrad)
=
atmospheric dispersion to the controlling site boundary (sec/m3)
%/O
=
2.7 E + 03, effective gamma-air dose factor (mrad /yr per pCi/m3)
Meff
=
2.3 E + 03 effective beta air dose factor (mrad /yr per pCi/m3)
Neff
=
cumulative release for all noble gas radionuclides (pCi)
Oi
=
3.17 E - 08 = conversion factor (yr/sec) conservatism factor to account for the variability in the effluent data 2.0
=
Combining the constants, the dose calculation equations simplify to:
Dy = 1.71 E - 04
- X / Q * [Q, (B-7) and g = 1.46 E - 04. X / Q = [Q, D
(B-8)
The effective dose factors are used for the purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods when the computer or ODCM software may be unavailable to perform a detailed dose assessment.
-z
ODCM-APP-B Revision 5 Page B-4 TABLE B-1 Effective Dose Factors - Noble Gas Eff!!uents Total Body Skin Dose Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Isotope Fractional
- Keff (l. + 1.1 Mett)
Mett Neff Abundance (mrem /yr (mrem /yr per (mrad /yr per (mrad /yr per uCl/m )
uCl/m )
(uCi/m )
uCi/m )
3 3
3 3
Kr 85m 0.10 1.2E+02 2.8E+02 1.2E+02 2.0E+02 Kr 85 0.01 1.6E-01 1.4 E+01 1.7E-01 2.0E+01 Kr 88 0.04 5.SE+02 7.6E+02 6.1 E+02 1.2E+02 Kr 89 0.06 1.0E+03 1.7E+03 1.0E+03 6.4E+02 Xe-133 0.67 2.0E+02 4.7E+02 2.4 E+02 7.0E+02 Xe-135 0.02 3.6E+01 7.9E+01 3.8E+01 4.9E+01 Xe-137 0.02 2.8 E+ 01 2.8 E+ 02 3.0E+01 2.5E+02 Xe-138 0.07 6 2E+02 1.0E+03 6.4E+02
.Q.3E+0a s --
TOTAL 2.6E+03 4.6E+03 2.7E+03 2.3E+03 Radionuclides distribution denved from Fermi 2 UFSAR, Section 11.3, Table 11.3-6, Kr-90, Kr-91, Xe-139, and Xe-140 have been excluded from the UFSAR distribution because of short half-lives and subsequent decay dunng environmental transport. Kr-87, Xe-131m, and Xe-133m have been excluded because of their negligible fractional abundance.
END OF APPENDIX B
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