ML20084N354
| ML20084N354 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 03/24/1995 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20084N349 | List: |
| References | |
| 6610-PLN-4200.0, NUDOCS 9506080005 | |
| Download: ML20084N354 (192) | |
Text
9503088974
. Numbw M SOE TMI RadiologicaTControis Departmental Procedure 6610-PLN-4200.01 Tatie Revision No.
Offsite Dose Calculation Manual (ODCM) 11 Calculate offsite doses due to radioactive Assponsable Office Effective Date Applicabmty/ Scope effluents for demonstrating compliance with Site Technical Specifications 10 CFR 20 & 10 CFR 50 Appendix l 6610' 03/24/95 This document is within OA plan scope X Yes No Safety Reviews Required X Yes No List of Effective Pages ,
Revision Pace Revision a f_aSe- Revision Paae Revision Pa2e 1.0 11 21.0 11 41.0 11 61.0 11 ,
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Radiological Engineer, TMi ""i-7.I_ %
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Manager, Rad. Eng., TMI r , R E- h g .5[2: / 95 Manager, TMI Licensing .
T-2 Z~ 9I Rad Con / Safety Director', TMI -
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COPY 9506080005 950601 PDR ADOCK 050002B9 P PDR )
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Number TMI Radiological Controls ME Departmental Procedure 6610-PW200.01 1m. n.vt on No.
Offsite Dose Calculation Manual (ODCM) 11
- Ust of Effective Pages (Cont'd)
Page Revision Paae Revision Page Revision Pace Revision 81.0 11 121.0 11 161.0 11 82.0 11 122.0 11 162.0 11 83.0 11 123.0 11 163.0 11 84.0 11 124.0 11 164.0 11 85.0 11 125.0 11 166.0
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DOCUMENT CONTROL CONTROLLED COPE N '
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TMI Radiologicer Contrds
' gaadUI Departmental Procedure 6610-PLN-4200.01 l Rmmon No.
Te , l 11 l Offsite Dose Calculation Manual (ODCM) 1 i
- INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the GPUNC Three Mie Island Nuclear Station (TMINS) Unit 1 and Ut" 2 PDMS Technical Specifications and implements TMI radiological emuent contrds. The ODCNI contains the corFris, bases, and surveillance requirements for liquid and gaseous radiological effluents. In addition, the ODCM describes the methodology'and parameters to be used in t'he calculation of off-site doses due to radioactive liquid and gaseous emuents. This document also describes the methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm / trip set points. Liquid and Gaseous Radwaste Treatment System configurations are also included.
The ODCM also is used to define the requirements for the TMINS radiological environmental monitoring program (REMP) and contains a list and graphical description of the specific sample locations used in the REMP.
The ODCM is maintained at the Three Mile Island (TMI) site for use as a reference guide and training document of accepted methoddogies and calculations. Changes in the calculation methods or parameters wil be incorporated into the ODCM to ensure the ODCM represents the present methodology in all applicable areas. GPUNC initiated changes to the ODCM will be implemented in accordance with the TMl-1 and TMI-2 PDMS Technical Specifications.
The ODCM fdiows the methodology and models suggested by NUREG4)133, and' Regulatory Guide 1.109, Revision 1 for calculation of off-site doses due to plant effluent releases. Simplifying assumptions have been applied in this manual where applicable to provide a more workable document for implementation of the Radioiogical Effluent Controls requirements.
GPUN implements the TMI Radidogical Effluent Centrols Program and Regulatory Guide 1.21, Revision 1 (Annual Radioactive Emuent Release Report) requirements by use of a computerized system used to determine TMI effluent releases and to update cumulative effluent doses.
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Offsite Dose Calculation Manual (ODCM) 11 TABLE OF CONTENTS i
l Section Page PARTI TL11-1 RADIOLOGICAL EFFLUENT CONTROLS 1.0 DEFINITIONS '15.0 Table 1-1, Frequency Notations 18.0 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 20.0 l
2.1 Radioactive Effluent instrumentation 20.0 l 2.1.1 Radioactive Liquid Emuent instrumentation 20.0 2.1.2 Radioactive Gaseous Process and Emuent Monitoring Instrumentation 23.0 Table 2.1-1, Radioactive Liquid Effluent Instrumentation 21.0 Table 2.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 24.0 2.2 Radiological Effluent Controls 29.0 1
2.2.1 Liquid Effluent Controls 29.0 l
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32.0 l 2.2.2 Gaseous Effluent Controls 2.2.3 Total Radioactive Effluent Controls 37.0 1
3.0 SURVEILLANCES 38.0 j 3.1 Radioactive Effluent Instrumentation 38.0 3.1.1 Radioactive Uquid Effluent instrumentation 38.0 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 41.0 Table 3.1-1, Radioactive Uguid Effluent Monitoring Instrumentation Surveillance Requirements 39.0 Table 3.1-2, Radioa_ctive Gaseous Process and Effluent Monitoring Instrumentation 42.0 Survellance Requirements 3.2 Radiological Effluents 46.0 3.2.1 Liquid Effluents 46.0 3.2.2 Gaseous Effluents 52.0 4.0 wu
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Offsite Dose Calculation Manual (ODCM) 11 TABLE OF CONTENTS Section Page PARTI TMI-1 RADIOLOGICAL EFFLUENT CONTROLS l
Table 3.2-1, Radioactive Uquid Waste Sampling and Analysis Program 48.0 j i
Tab'e 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 54.0 3.2.3 Total Radioactive Effluents 58.0-4.0 PART I REFERENCES 59.0 l
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Offsite Dose Calculation Manual (ODCM) 11 TABLE OF CONTENTS (Cont'd)
PARTll TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Page 1.0 DEFINITIONS 61.0 Table 1.1, Frequency Notation 63.0 2.0 RADIOLOGICAL EFFLUENT REQUIREMENTS 66.0 2.1 Radioactive Discharges 66.0 2.1.1 Uquid Erfluents 66.0 2.1.2 Gateous Effluents 68.0 2.2 Radbact!ve Gaseous Effluent Monitoring instrumentation 70.0 Table 2.2-1, Radioactive Gaseous Emuent-Monitoring Instrumentation 71.0 3.0 MONITORING REQUIREMENTS 72.0 3.1 Radioactive Discharges 72.0 3.1.1 Liquid Effluents 72.0 3.1.2 Gaseous Effluents 72.0 3.2 Radioactive Gaseous Effluent Monitoring instrumentation 74.0 Table 3.1 1, RadioactNe Uguid Waste Sampling and Analysis 75.0 Table 3.1-2, Radioactive Gaseous Waste Sampling and A.'alysis 76.0 O
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PART11 TMI-2 RADIOLdGICAL EFFLUENT CONTROLS Section Page 4.0 DESIGN FEATURES 79.0 4.1 SITE 79.0 4.1.1 Exclusion Area 79.0 4.1.2 Low Population Zone 79.0 4.1.3 Site Boundary for Gaseous Effluents 79.0 4.1.4 Site Boundary for Uquid Emuents 79.0 PART 11 REFERENCES 80.0
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TABLE OF CONTENTS j Page Section PARTlli EFFLUENT DATA A.ND CALCULATIONAL METHODOLOGIES !
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1.0 UQUID EFFLUENT MONITORS 82.0 1.1 TMI-1 and TMI-2 Uquki Radiation Monitor Set Points 82.0 1.2 TMl Uquki Release Points and Uquid Radiation Monitor Data 83.0 1.3 Control of Uguid Releases 85.0 1
I 2.0 UQUID EFFLUENT DOSE ASSESSMENT 90.0 i
2.1 Uquid Effluents - 10 CFR 50 Appendix 1 90.0 2.2 TMI-1 Uquid Radwaste System Dose Cales Once per Month 92.0 2.3 Altemative Dose Caledational Methodology 93.0 3.0 UQUID EFFLUENT W/JTE TREATMENT SYSTEM 98.0 3.1 TMI-1 Uquid Emuent Waste Treatment System 98.0 3.2 Operabity of TMI-1 Uquid Effluent Waste Treatment System 99.0 3.3 TMI-2 Uguid Emuent Waste Treatment System 99.0 4.0~ GASEOUS EFFLUENT MONITORS 102.0 4.1 TMI-1 Noble G'as Monitor Set Points 102.0 4.2 TMI-1 Particulate and Radioiodine Monitor Set Points 104.0 4.3 TMI-2 Gaseous Radiation Monitor Set Points 105.0 4.4 TMI-1 Gaseous Emuent Release Points and Gaseous Radiation Monitor Data 106.0 4.5 TMi-2 Gaseous Emuent Release Points and Gaseous Radiation Monitor Data 108.0 4.6 Control of Gaseous Emuent Releases ~ 109.0 O
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TABLE OF CONTENTS Section Page PARTlli EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 122.0 5.1 Gaseous Effluents - Dose Rate Limits 122.0 5.1.1 Noble Gases 122.0 5.1.1.1 Total Body 122.0 5.1.1.2 Skin 123.0 1
5.1.2 lodines and Particulates 124.0 5.2 Gaseous Effluents,- 10 CFR 50 Appendix 1 125.0 5.2.1 Noble Gases -- 125.0 5.2.2 lodines and Particulates 126.0 5.3 Ga'seous Radioactive System Dose Calculations Once per Month 128.0 5.4 Altemative Dose Calculational Methodologies 129.0 6.0 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM 151.0 6* Description of the TMI 1 Gaseous Radwaste Treatment System 151.0 6.2 Operabilty of the TMI-1 Gaseous Radwaste Treatment System 151.0 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 153.0 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 154.0 8.1 Monitoring Program Requirements 154.0 8.2 latnd Use Census 156.0 8.3 Interiaboratory Comparison Program- 158.0 9.0 PART 111 REFERENCES 175.0 9.0 nm.
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- TABLE OF CONTENTS (Cont'd)
PARTlli EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Page Section TABLES TMI-1 Uquid Release Point and Uguid Radiation Monitor Data 86.0 Table 1.1 TMI-2 Sump Capacities 87.0 Table 1.2 Uquid Dose Conversion Factors (DCF): DFij 94.0 Table 2.1 Bloaccumulation Factors. BFi 97.0 Table 2.2 TMI-1 Gaseous Re%se Point & Gaseous Radiation Monitor Data 110.0 Table 4.1 112.0 Table 4.2 TMI-2 Gaseous Release Point & Gaseous Radiation Monitor Data Dose Factors for Noble Gases and. Daughters 113.0 Table 4.3 Atmospheric Dispersion Factors for Three MBe Island - Station Vent 114.0 Table 4.4 Atmospheric Dispersion Factors for Three Mie Island - Ground Release 115.0 l Table 4.5 l
Table 4.6 Dose Parameters for Radiolodines and RadioactNe Particulate, Gaseous, Effluents 116.0 Pathway Dose Factors, Ri -Infant, inhalation 130.0 Table 5.2.1 Pathway Dose Factors, Ri - Child, inhalation 131.0 Table 5.2.2 Pathway Dose Factors, Ri - Teen, inhalation 132.0 Table 5.2.3 Table 5.2.4 Pathway Dose Factors, Ri - Adult, Inhalation 133.0 Pathway Dose Factors, Ri - All Age Groups, Ground Plane 134.0 Table 5.3.1 l
Table 5 1 Pathway Dose Factors, Ri - Infant, Grass-Cow-Mik 135.0 l Table 5.4.2 Pathway Dose Factors, Ri - ChBd, Grass-Cow-Milk 136.0 Table 5.4.3 Pathway Dose Factors, Ri - Teen, Grass-Cow-Mik 137.0 Table 5.4.4 Pathway Dose Factors, Ri Adult, Grass-Cow-Milk 138.0 Tab'e 5.5.1 Pathway Dose Factors, Ri - Infant, Grass-Goat-Mik 139.0 10.0 rme
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Offsite Dose Calculation Manual (ODCM) 11 TABLE OF CONTENTS (Cont'd)
PART 111 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES Table 5.5.2 Pathway Dose Factors, Ri - Chld, Grass-Goat-MRk 140.0 Table 5.5.3 Pathway Dose Factors, Ri - Teen, Grass-Goat.MHk 141.0 Table 5.5.4 Pathway Dose Factors, R, - Adutt, Grass-Goat-Mik 142.0 Table 5.6.1 Pathway Dose Factors, Ri -Infant, Grass-Cow-Meat 143.0 Table 5.6.2 Pathway Dose Factors, Ri - Chid, Grass-Cow-Meat 144.0 Table 5.6.3 Pathway Dose Factors, Ri - Teen, Grass-Cow-Meat 145.0 Table 5.6.4 Pathway Dose Factors, Ri - Adult-Grass-Cow-Meat 146.0 Table 5.7.1 Pathway Dose Factors, Ri - Infant, Vegetation 147.0 Table 5.7.2 Pathway Dose Factors, Ri - Chid, Vegetation 148.0 Table 5.7.3 Pathway Dose Factors, Ri - Teen, Vegetation 149.0 Table 5.7.4 Pathway Dose Factors, Ri - Adult, Vegetation 150.0 Table 8.1 Sample Collection and Analysis Requirements 159.0 Table 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples '164.0 Table 8.3 Detection Capabiltles for Environmental Sample Analysis 165.0 Table 8.4 TMINS REMP Station Locations - Air Particulate and Air lodine 167.0 Table 8.5 TMINS REMP Station Locations - Direct Radiation (TLD) 167.0 Table 8.6 TMINS REMP Station Loations - Surface Water 169.0 Table 8.7 TMINS REMP Station Locations - Aquatic Sediment 169.0 Table 8.8 TMINS REMP Station Locations - Mik 170.0 j Table 8.9 TMINS REMP Station Locations.- Fish 170.0 1
Table 8.10 TMINS REMP Station Locations - Food Products 171.0 I 11.0 nm, l
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a Offsite Dose Calculation Manual (ODCM) 11 TABLE OF CONTENTS (Cont'd)
PART 111 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES MAP 8.1 Three MHe Island Nuclear Station Locations of Radiological Environmental 172.0 Monitoring Program Stations within 1 Mie of the Site MAP 8.2 Three Mile Island Nuclear Station Locations of Radiological Ermronmental 173.0
, Monitoring Program Stations within 5 mies of the Site MAP 8.3 Three Mile Island Nuclear Station Locations of Radiological Environmental 174.0 Monitoring Program Stations Greater than 5 mRes from the Site FIGURES i
kigure 1.1 TMI-1 Uquid Emuent Pathways 88.0 Figure 1.2 TMI-2 Uguid Emuent Pathways 89.0 Figure 3.1 TMI-1 Uquid Radwaste 100.0 Figure 3.2 TMI-1 Uquid Waste Evaporators 101.0 Figure 4.1 TMI-1 Gaseous Effluent Pathways 117.0 !
Figure 4.2 TMI-1 Auxiliary & Fuel Hand!!ng Buildings Emuent Pathways 118.0 Figure 4.3 TMI-1 Reactor Building Emuent Pathway 119.0 Figure 4.4 TMI-1 Condenser Offgas Emuent Pathway 120.0 Figure 4.5 TMI-2 Gaseous Emuent Futration System / Pathways 121.0 Figure 6.1 Waste Gas System 152.0 M
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TABLE OF CONTENTS (Cont'd)
PART IV REPORTING REQUIREMENTS Section Page 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 178.0 2.0 TMl ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 179.0 3.0 PART IV REFERENCES 181.0 APPENDICES A. Pathway Dose Rate Parameter (P) E1-1 3
B. Inhrdation. Pathway Dose Factor (R,) E2-1 C. Ground Plane Pathway Dose Factor (R;) E3-i
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D. Grass-Cow-Mik Pathway Dose Factor (R,) E4-1 E. Cow-Meat Pathway Dose Factor (R;) E5-1 F. Vegetation Pathway Dose Factor (R;) E6-1 APPENDIX A - F REFERENCES E7-1 m..
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l Number Nuclear TMI Radiologic # Controls o e,oo dure 6610-PLN-4200.01 Title b'sson No.
Offsite Dose Calculation Manual (ODCM) 11 I
PARTI i TMI-1 RADIOLOGICAL EFFLUENT CONTROLS l
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Offsite Dose Calculation Manual (ODCM) 11 l
l 1.0 DEFINITIONS The following terms are defined for uniform interpretation of these controls and survellances.
1.1 Reactor Operating Conditions 1.1.1 Cold Shutdown The reactor is in the cold shutdown condition when it is subcritical by at least one percent.
delta k/k and Tavg is no more than 200* F. Pressure is defined by Technical ,
Specification 3.1.2.
1.1.2 Hot Shutdown The reactor is in the hot shutdown condition when it is suberttical by at least one percent delta k/k and Tavg is at or greater than 525* F.
1.1.3 Reactor Critical The reactor is critical when the neutron chain reaction is self. sustaining and Keff = 1.0.
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1.1.4 Hot Standby The reactor is in the hot standby condition when all of the following conditions exist: ,
- a. Tavg is greater than 525' F
- b. The reactor is critical
- c. Indicated neutron power on the power range channels is less than two percent of rated power. Rated power is defined in Technical Specification Definition 1.1.
1.1.5 Power Operation The reactor is in a power operating condition when the indicated neutron power is above two percent of rated power as indicated on the power range channels. Rated power is dafined in Technical Specification Definition 1.1.
1.1.6 Refueling Shutdown The reactor is in the refueling shutdown condition when, even with all rods re' moved, the reactor would be subcritical by at least one percent delta k/k and the coolant temperature at the decay heat removal pump suction is no more than 140' F. Pressure is defined by Technical Specification 3.1.2. A refueling shutdown refers to a shutdown to replace or rearrange all or a portion of the fuel assemblies and/or control rods.
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- 1.1.7 . Refueling Operation l An' operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.
1.1.8 Refueling Interval Time between normal refuelings of the reactor. This is defined as once per 24 months.
1.1.9 Startup The reactor shall be considered in the startup mode when the shutdown margin is reduced ,
with the intent of going critical. T l
1.1.10 Tave )
Tave is defined as the arithmetic average of the coolant temperatures in the hot and cdd I legs of the loop with the greater number of reactor codant pumps operating, if such a l distinction of loops can be made.
l 1.1.11 Heatup .Cooldown Mode _
1 The heatup cooldown mode is the range of jreactor coolant temperature greater than 200' F and less than 525" F.
1.2 Operable A system, subsystem, train, component or device shall be OPERABLE or have OPERAIllLITY 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 auxiliary 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).
1.3 instrument Channel An instrument channel is the combination of sensor, wires, am'pilfiers, and output devices which are connected for the purpose of measuring the value of a process variable for the purpose of observation, control, and/or protection. An instrument channel may be either analog or dig!tal.
1.4 Instrumentation Surveillance 1.4.1 Channel Test A CHANNEL TEST shall be tim injection of a simulated signal into the channel as dose to the sensor as practical to verify OPERABilflY, induding alarm and/or trip functions.
1.4.2 Channel Check A CHANNEL CHECK shall be the qualltative assessment of channel behavior during operation by observation. This determination shall include, where possible, ~ comparison of 16.0 nm.
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Offsite Dose Calculation Manual (ODCM) 11 the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter. j 1.4.3 Source Check A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. -
1.4.4 Channel Calibration An instrument CHANNEL CAUBRATION is a test, and adjustment (if necessary), to establish that the'channsi output responds with acceptable range and accuracy to known values of the parameter which the channel measures or an accurate simulation of these values.
- Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include the channel test.
1.5 Dose Equivalent 1-131 The DOSE EQUIVALENT l-131 shall be that concentration of l-131 (microcurie / gram) which alone
- would produce the same thyroid dose as the quantity and isotopic' mixture of I-131,1-132,1-133, 1-134, and 1-135 actually present._The thyroid dose conversion factors used for this calculation shall be those listed in Table lli of TID 14844, " Calculation of Distance Factors for Power and Test Reactor Sites". (Or in Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.]
1.6 Offsite Dose Calculation Manual (ODCM)
The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the methodology and parameters '
used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the calculatiori of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains (1) the Radiological Effluent Controis, (2) the Radiological Environmental Monitoring Program and (3) descriptions of the -
information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Efiluent Release Reports.
1.7 Gaseous Radwaste Treatment The GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactNe gaseous effluent by collecting primary cociant system off gases from the pnmary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
1.8 Ventilation Exhaust Treatment System
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A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce ,
gaseous radiolodine or radioactive material in particulate form in effluent by passing ventiation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodine or particulates from the gaseous exhaust system prior to the release to the environment.
Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEMS.
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Offsite Dose Calculation Manual (ODCM) 11 1.9 Purge - Purging PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is required to purify the confinement.
1.10 Venting VENTING is the controlled process of discharging air as gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is not provided. Vent used in system name does not imply a VENTING process.
1.11 Member (s) of the Public MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the GPU System, GPU contractors or vendors. Also exduded from this category are persons who enter the site to service equipment or to rnake deliveries.
1.12 Site Boundary _
The SITE BOUNDARY is the boundary line forming the base for the limits on the release of gaseous effluents as defined in Sect!on 2.1.2.2 of the TMl-1 FSAR and shown on Figure 2.1-3 of the TMI-1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three MBe Island and between Three Mie Island and Shelley lsland.
1.13 Frequency Notation The FREQUENCY NOTATION specified for the performance of Survellance Requirements shall correspond to the intervals defined in Table 1-1. All SurveHlance Requirements shall be pedciiived within the specified time interval with a maximum aNowable extension not to exceed 25% of the surveillance interval. The 25% extension applies to all frequency intervals with the exception of *F.*
No extension is allowed for intervals designated "F.'
Table 1-1 Frequency Notation Notation Frequency S .. Shiftly (once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) l l
D Daily (once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) l W Weekly (once per 7 days)
M MontNy (once per 31 days) ,
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Notation Frequency Q Quarterly (once per 92 days)
Semi-Annually (once per 184 days)
S/A R Refueling Interval (once per 24 months)
Prior to each reactor startup, if not done during the P S/U previous 7 days P Completed prior to each release N/A (NA) Not applicable E Once per 18 months F Not to exceed 24 months
' Bases Section 1.13 establishes the limt for which_the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal survellance interval to faclitate survellance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g.; transient conditions or other ongoing surveBlance or mairmenance activities. It also provides flexibilty to accommodate the length of a fuel cycle for survellances that are specified to be
. performed at least once each REFUEUNG INTERVAL lt is not intended that this provision be used~
repeatedly as a convenience to extend survellance intervals beyond that specified for survellances that are not performed once each REFUEUNG INTERVAL Ukewise, it is not the intent that REFUEUNG INTERVAL survealances be performed during power operation unless R is consistent wth safe plant operation. The limitation of Section 1.13 is based on engineering judgement and the recogntion that the most probable result of any particular survellance being performed is the verification of conformance with the SurveRance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveBlance interval.
0 19.0 mm.
Numte
, j EE TMI Radiologicil ~C ontrols
' Departmental Procedure 6610-PLN-4200.01 a.m.on No.
Offsite Dose Calculation Manual (ODCM) 11 2.0 CONTROLS AND BASES 2.1 Radioactive Emuent instrumentation 2.1.1 Radioactive Uquid Effluent Instrumentation CONTROL-The radioactive liquid eNuent monitoring instrumentation channels shown in Table 2.1-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 2.2.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY: At all times
- 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 eMuent montored by the affected channel or declare the charviel inoperable.
- b. With less than the minimum number of radioactive liquid emuent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-1. Exert best efforts to retum the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.
- For FT-84, and RM-L6, operability is not required when discharges are positively controlled through the closure of WDL-V257.
- For RM-L12 and associated IWTS/lWFS flow interiocks, operabity is not required when discharges are positively controlled through the closure of IW-V72,75 and IW-V280,281.
- For FT-146, operablity is not required when discharges are positively controlled through the closure of WDL-V257, IW-V72,75 and IW-V280,281.
BASES ,
The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluent during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm / trip WRI occur prior to exceeding ten times the emuent concentrations of 10 CFR Part 20.
20.0 mm.
s
Number TMI Radiological' Controls g!lgp Departmental Procedure 6610-PLN-4200.01 Tit 6s Revision No.
Offsite Dose Calculation Manual (ODCM) 11 Table 2.1-1 Radioactive Uquid Effluent Instrumentation Minimum Channels Instrument Operable ACTION
- 1. Gross Radioactivity Monitors Providing AutomaticTermination of Release i a. Unit 1 Liquid Radwaste. Effluent 1 18 Une (RM-LE)
- b. lWTS/lWFS Discharge Une (RM-L12) 1 20
- 2. Flow Rate Measurement Devices
- a. Unit 1 Uquid Radwaste Effluent __ 1 21 Une (FT-84)
- b. Station Effluent Discharge 1 21 (FT-146)
Table Notation ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE l requirement, effluent releases may continue, provided that prior to initiating a release:
At least two independent samples are analyzed in accordance with Surveillances 3.2.1.1.1 l 1.
and 3.2.1.1.2 and;
- 2. At least two technically qualified members of the Unit staff independently verify the release i rate calculations and verify the discharge valve lineup. l l
- 3. Director Operations and Maintenance TMI shall approve each release. !
l Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may commence or continue provided that grab samples are collected and analyzed for gross radioactMty (beta or gamma) at a limit of detection of at least 1x10~7 microcuries/ml, prior to initiating a release 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 release.
O 21.0 sm.
Number ggp TMI Radiologicif Controls Departmental Procedure 6610-PLN-4200.01 me am.on No.
Offsite Dose Calculation Manual (ODCM) 11 Table 2.1-1 (Cont'd)
ACTION 21 Wth the numbar of channels OPERABLE less than required by the Minimum Channels OFERABLE requirement, radioactive effluent releases via this pathway may continue, l provided the flow rate is estirnated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow. ,
O e
l e
1 22.0 ruw
Number TMI Radiologicial' Controls I I Departmental Procedure 6610-PLN-4200.01 1 Trn. ammon No.
Offsite Dose Calculation Manual (ODCM) 11 2.1.2 Radioactive Gaseous Process and Effluent Monitoring instrumentation CONTROL:
The radicar:tive' gaseous process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alarm / trip setpoirts of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPUCABILITY: As shown in Table 2.1-2.
ACTION: ,
- a. With a radioactive gaseous process or effluent monitoring instrumentation channel
. alarm / trip setpoint less conservative tien required by the above control, immediately suspend the release of radioactive efiluent monitored by the affected channel or declare the channel inoperable.
- b. With less than the minimum number of radioactive gaseous process or ef!Iuent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-2. Exert bee _t efforts to retum the instrumentation to OPERABLE status within 30 days and, if ur=m-'ul, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.
BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases. The alarm / trip setpoints for these instruments shal be calculated in accordance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301.
The low range condenser offgas noble gas actMty monitors also provide data for determination of steam generator primary to secondary leakage rate. Channel operability requiremerrts are based on an ASLB Order No. LBP.84-47 dated October 31,1984, and as cited in 20 NRC 1405 (1964).
e f
9 23.0 mi,
Table 2.1-2 881tNU4-4200.01 -
Radioactive Gaseous Process and Efiluent Monitoring instrumentation MINIMUM CHANNELS INSTRUMENT OPERABL_E APPUCABluTY ACTION -
- 1. Waste Gas Holdup System
- 25
- a. Noble Gas Activity Monitor (RM-A7) 1-
- 26
- b. Efiluent System Flow Rate Measuring Device (FT-123) 1
- 2. Weste Gas Holdup System Exploshw Gas Monitoring System
- 30
- a. Hydrogen Monitor .2 t
- b. Oxygen Monitor 2 30
- 3. Containment Purge Monitoring System
- a. Noble Gas Activity Monitor (RM-A9) 1 # 27
. b. todine Sampler (RM-A9) 1 # 31
- c. Particulate Sampler (RM-A9) 1 # 31
- d. Effluent System Flow Rate Measuring Device (FR-148) 1 # 26
- e. Sampler Flow Rate Monitor 1 # 26 t
m 0
24.0 mu
. _ _ ..~m. _ _ . _ _ . . . .. _ _ , . . . - - _ _ . ~ - , - . ~ , . _ - - - . - . . . _ _ _ _ _ _ - _ _ _ _ ___.___._____m____ _ _ _ _ _ _ - _ . . . _ _ _ _ _ _ _ _ _ .
i l
Table 2.1-2 (Cont'd) 8610-PLN-4200.01, !
Revision 11
- Radioactive G'aseous Process and Efiluent Monitoring Instruetion j i
l j MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABlUTY ACTION
- 4. Condenser Vent System
- a. Low Range Noble Gas Activity Monitor (RM-ASLo and 2M ## 32 Suitable Equivalent)
NOTE (1): For one of the channels, an operable channel may be defined for purposes of this control and 3.1.2.1 only as a suitable equivalent monitoring system capable of being placed in service within one hour. A suitable equivalent system shall include instrumentation with comparable sensitMty and response time to the RM-A5Lo monitoring channel When the equivalent monitoring system is in service, -
Indication wil be continuously avaRable to the operator, either through indication and alarm in the Control Room or through communication with a ddeignated indMdual continuously observing local Indication.
l 25.0 mm
Table 2.1-2 (Cont'd) 0610-PLN-4200.01 ,,
. Radioactive Gaseous Process and Efiluent Monitoring Instrumentation MINIMUM CHANNELS INSTRUMENT OPERABLE APPUCABluTY ACTION
- 5. Auxtlary and Fuel Handling BuBding Ventilation System
- a. Noble Gas Activity Monitor (RM-A8) or (RMM and RM-A6) 1 27
- b. lodine Samples (RM-AB) or (RM-A4 and RM-A6)
- 1 31
- c. Particulate Sampler (RM-AB) or (RM-A4 and RM-A6) 1 31
- d.
- Efiluent System Flow Rate Measuring Devices (FR-149 i1 26 and FR-150) F r
Sampler Flow Rate Monitor *
- e. 1 26 i
- 6. Fuel Handling Building ESF Air Treatment System
- a. Noble Gas ActMty Monitor (RM-A14 or Sultable j j Equivalent) 1
- 27,33 N/AM
- b. lodine Cartridge **** 31,33
- c. Particulate FRter N/AW 31,33
- d. Efiluent System Flow (UR-1,104A/E) ~1
- 26,33 *
- e. Sampler Flow Rate Monitor 1
- " 26,33 NOTE 2: No Instrumentation channel is provided However, for determining operabilty, the' equipment named must be installed and functional or the ACTION appiles.
26.0 nn.
E mv--, w- ~ >w.- -, .-,w- e- ,-- s-- vne , - e - v s- - - ~ v~--- -~r- - - - - -- -- - - - - - - - - - - - - - - - - - - -
l Nurnber ggy mi Radiologicial Controls Departmental Procedure 6610-PLN-4200.01 1
l Me Rasen No.
Offsite Dose Calculation Manual (ODCM) 11 Table 2.1-2 (Cont'd)
Table Notation At all times.
- During waste gas holdup system operation.
"* Operability is not required when discharges are positively controlled through the closure of WDG-V47 and where RM-A8 (or RM-A4 and RM-A6), FT-149, and FT-150 are operable.
- " During Fuel Handling Building ESF Air Treatment System Operation.
- At all times during containment purging.
- At all tirnos when condenser vacuum is established.
ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels
- a. OPERABE requirement, the contents of the tank may be released to the environment provided that prior to initiating the release:
- 1. At least two indep.ndent samples of the tank's contents are analyzed in accordance with Table 3.2-2, ftem A, and a 2. At least two technically qualified members of the Unit staff independently yerify the release rate calc _ulations and verify the discharge valve lineup. -
- 3. The Director Operations & Maintenance TMI, shall approve each release.
Otherwise, suspend release of radioactive effluent via this pathway.
ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABE requirement, effluent releases via this pathway rnay continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the initial samples are analyzed for gross
~
actMty (gamma scan) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the channel has been declare t inoperable. If RM-A9 is declared inoperable, see also Technical Specification 3.5.1, Table 3-5.1, item C.3.f.
ACTION 30 1. With the number of channels OPERAEE less than required by the Minimum Channels OPERABLE requirement, a grab sample shall be collected and analyzed .
for the inoperable gas channel (s) at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With both cha,nnels inoperable, a grab sample shall be collected and analyzed for the inoperable gas channel (s):
(a) at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations.
~
(b) at least orice per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other opera'Jons (e.g. Feed and Bleed).
27.0 rm.
Number TMI Radiologicif Controls ggUI Departmental Procedure 6610-PLN-4200.01 Tree Revision No.
Offsite Dose Calculation Manual (ODCM) ' 11 Table 2.1-2 (Cont'd)
- 2. . If th'e inoperable gas channel (s) is not restored to service within 14 days, a special report shall be submtted to the Regional Administrator of the NRC Region i Office and a copy to the Director, Office of Inspection and Enforcement within 30 days of declaring the channel (s) inoperable. The report shall describe (a) the cause of the monitor inoperability, (b) action being taken to restore the instrument to service, j
and (c) action to be taken to prevent recurrence.
ACTION 31 With the number of channels Ci'ERABW less than required by the Minimum Channels'OPERABW requirement, effluent releases via this pathway may continue l provided that within four hours after the channel has been declared inoperable, samples are continuously collected with auxtlary sampling equipment.
ACTION 32 .With the number of channels OPERABT less than required by the Minimum Channels OPERABW requirement, effluent releases via this pathway may continue for up to 28 days, provided that one OPERABW channel remains in service or is (
placed in service within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. After 28 days, or if one OPERABLE channel l does not remain in service or is not placed in service within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the 1 provisions of Technical SpectScotion 3.0.1 apply, as if this Control were a Tech Spec Limiting C_ondition for Operation.
ACTION 33 With the number of channels OPERABW less than required by the Minimum Channels OPERABE requirement, either restore the inoperable channel to OPERABW status within 7 days, or prepare and submt a special report within 30 days outlining the action (s) taken, the cause of the inoperability, and plans and schedule for restoring the system to OPERABW status.
e Oa 1
l 28.0 nm, I
1 Number j TMI Radiologgid ' Controls l g Departmental Procedure 6610-PLN-4200.01 T no Revieson No.
Offsite Dose Calculation Manual (ODCM) 11 2.2 Radioactive Emuent Controls 2.2.1 Uguid Effluent Controls 2.2.1.1 Uquid Emuent Concentration CONTROL:
The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limted to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or For dissolved or entrained noble gases, the concentration shall be entrained limted to 3 xnoble 10 u yCl/cc total actMty.
APPUCABluTY: dt all times i
ACTION: )
With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within the above limits.
BASES l
This control is provided to ensure that the concentration of radioactive materials released in ,
liquid waste effluent from the unit to unrestricted areas will be less than ten times the I concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures with (1) the Section ll.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBUC and (2) the limts of 10 CFR Part 20.1301 to the ,rvvyhn. The concentration limit for noble gases is based upon the assumption the Xe-135 is the con; rolling radioisotope and ts MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in Intemational Commission on Radiological Protection (ICRP) Publication 2.
2.2.1.2 Uguid Effluent Dose CONTROL The dose or dose commitment to a MEMBER OF THE PUBUC from radioactive materials in liquid effluents released from the unt to the SITE BOUNDARY shall be limked:
l
- a. During any calendar quarter to less than or equal to 1.5 mrem to the ' total body and )
to less than or equal to 5 mrem to any organ.
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
APPUCABluTY: At all times l
l 29.0 _
sms
- . - . . = . . . - .- - ..
. Number -
TMl Radiologic'al' Controls I Departmental Procedure 6610 PUM200.01 4- ns. Rev6een No.
Offsite Dose Calculation Manual (ODCM) 11 I -
ACTION:
j -. a. With the calculated dose from the release of radioactive materials in liquid emuents i exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for ,
exceeding the limit (s) and defines the corrective actions to be taken to reduce the ;
- ralamaan of radioactive materials in liquid,alliuents during the remainder of the j cummt calender quarter and during the =haarPant 3 calender queners so that the l i cumuistive dose or dose commitment to any individual from such releases during 4 these four calendar quarters is within 3 mrom to the total body and 10 mrom to any - ;
organ. This Special Report shal also include (1) the result of radiological analyses [
- of the drinidng water source, and (2) the radiological impact on finished drinidng ;
water supplies with regard to the requrements of 40 CFR 141, Safe Drinking Wateir I
Act.
i
- BASES j This control and associated action is provided to implement the requirements of Sections j 4 II.A, Ill.A and IV.A of Appendk I,10 CFR Part 50.' The Control implements the guides set forth in Section ll.A of Appendk 1. The ACTION statements provide the required operating s
- ilevihaky and at the game, time implement the guides set forth in Semion N.A of Appendk 1 i to assure that the releases of tariinar% material in liquid silluonts wr be kept 'as low as is l reasonably achievable". Also, for fresh water sites with drinidng watri supplies which can be ,
potentially allected by plant operations, there is reasonable assu an:e that the operation of i ,
the facElty will not result in radionuclide concentrations in the finished $1nidng water that are I
in excess of the requirements of 10 CFR 20. The does calcLAstions in tha ODCM implement The requirements in Section Ill.A. of Appendk i that coniormance with the gd6 of Appendk I is to be shown by calculational procedures based on models and data such that ,
the actual avpamante of a MEMBER OF THE PUBUC through appropriate pathways is unilkely !
to be substantially underestimated. The equations specNied in the ODCM for r miadating the 1 doses due to the actual release rates of radioactive materials in liquid elliuents are ;
consistant with the methodology provided in Reguladry Guide 1.109, " Calculation of Annual ;
Doses to Man from Routine Releases of Reactor EfRuonts for the Purpose of Evaluating -
- i Compliance with 10 CFR Part 50, Appendk I," Revleion 1. October,1977, and Regulatory (
Guide 1.113, " Estimating Aquatic Diepersion of Efiluents from Accidental and Routine (*
Reador Releases for the Purpose of implementing Appendk I.* Aprt,1977. NUREG 0133
. provides methods for does calculations consistent with Regulatory Guidos 1.109 and 1.113. . i i
2.2.1.3 Liquid Radwaste Treatment System :
CONTROL-l i The appropriate podions of the liquid radweste treatment system shall be used to 'I reduce the radioacdve materials in liquid wastes prior to their discharge when the i
[ projected doses due to the liquid emuent from the unit to unrestricted areas would ,
1 exceed 0.06 mrom to the total body or 0.2 mrom to any organ in any calendar
' month. :
1 APPUCABILITY: At aN times e
30.0 nm. !
l g ..q.- "--
t "e'- T ' - -*' W-' t -- ---
t v =* -- -' - - - --- -- - - - . - -
Number ggy TMI Radiologicil Controls Departmental Procedure 6610-PLN4200.01 True , ,
Fevieson No.
Offsite Dose Calculation Manual (ODCM) 11 ACTION:
- a. With radioactive liquid waste being disch.iged without treatment and in excess of the above limits, prepare and subrnit to the NRC Region 1 Administrator within 30 days, a Special Report which includes the following infortpation:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperability, l
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and,
- 3. A summary desuipiivn of action (s) taken to prevent a recurrence.
BASES l The Auirement that the appropdate portions of this system be used, when I spot %d, provides assurance that the releases of radioactive materials in liquid i effluents wil be kept as low as is reasonably achievable This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A l to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix 1 to 10 l CFR Part 50. The intent of Section ll.D. is to reduce emuents to as low as is l reasonably achievable in a cost effective manner ~. This control satisfum this intent by establishing a dose limit which is a small fraction (25%) of Section ll.A of Appendix 1,10 CFR Part 50 dose requirements This margin, a factor of 4, const!tutes a reasonable reduction.
2.2.1.4 Liquid Holdup Tanks ]
CONTROL The quantity of radioactive material contained in each of the following tanks shall be 1 limited, to less than or equal to 10 curies, excluding tritium and dissolved or i entrained noble gases.
. a. Outside temporary tank APPLICABILITY: At all times.
ACTION:
~
- a. With the quantity of radioactive material in any of the above listed tanks i exceeding the above lirnit, immediately suspend all additions of radioactive' material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within l
the limit.
l :
i 31.0 ame j i
Number
, gggy .
TMI Radiological Controls Departmental Procedure 6610-PLN 4200.01 Tine Revision No.
Offsite Dose Calculation Manual (ODCM) 11 BASES Restricting the quantity of radioactive material contained in the specified tanks )
provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20.1001-20-20.2401, Appendix B Table 2. Column 2, at the nearest potable water supply and the nearest surface water supply.in an unrestricted area.
2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL:
The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following:
- a. For noble gases: less than or equal to 500 mrom/yr to the total body and less than or equal to 3000 mrom/yr to the skin, and 6
- b. For 1-131,1-133, _ tritium and all radionuclides ic particulate form with half lives greater than 8< days: less than or equal to 1500 mrem /yr to any organ.
APPUCABluTY: At all times.
ACTION:
With the release rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above limit (s),
BASES The control provides ressorwbie assurance that the annual dose at the SITE BOUNDARY from gaseous effluent from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas while providing sufficient op=&ticr=1 flexibility in establishing efRuent monitor setpoints. These gaseous release rates provide reasonable assurance that radioactive material discharged in gaseous effluent wll not result in the exposure of a MEMBER OF THE PUBUC in an unrestricted area, either within or outside the SITE BOUNDARY, to annual avorage concentrations exceeding the values specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBUC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBUC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamme and beta dose rates above background to a MEMBER OF THE PUBUC at or beyond the SITE BOUNDARY to less than or equal to 500 mrom/ year to the -
total body or to less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year (NUREG 0133).
32.0 mi.
. Number TMI Radiological' Controls
- E Departmental Procedure 6610-PLN-4200.01 -
RmWon No.
Te Offsite Dose Calculation Manual (ODCM) 11 2.2.2.2 Gaseous Effluents Dose-Noble Gases CONTROL:
The air dose due to noble gases released in gaseous affluents from the unit to areas at and beyond the SITE BOUNDARY shal be limited to the following
- a. During any calendar quarter; less than or equel to 5 mrad for gamma radiation and -
less than or equel to 10 mrad for beta radiation and,
- b. During any calendar year: less than or aquel to 10 mrad for gamma radiation and '
less than or equal to 20 mrad for beta radiation.
APPUCABluTY: At all times.
ACTION: ,
- a. With the calculated air dose from radioactive noble gases in gaseous effluents .
meaarung any of the above limits, prepare and submit to the NRC Region i Administrator within 30 days, a Special Report which identilles 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 wil be in compliance with the above limits.
BASES This control applies to the release of radioactive tratorialsin gessous effluents from TMI-1. l l
l This control and associated action is provided to implement the requirements of Section ll.B.
lil.A and IV.A of Appendk I,'10 CFR Part 50. The Control implements the guides set forth in Section 11.B of Appendix 1. The ACTION statements provide the required operating fledblity
- i and at the same time implement the guides set forth in Section IV.A of Appendk I to assure that the releases of radioactive material in gaseous ofRuonts wil be kept 'as low as is -
reasonably achievable." The SurveElence Requirements implement the requirements in Section 111.A of Appendk I that corWormance with the guides of Appendk i be shown by l calcuistional procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBUC through the appropriate pathways is unlikely to be substantially underestimated. The does calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "CalcWation of Annual Doses to Man from Routine Release of Reactor Efiluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendk I," Revision 1, October 1977 and Regulatory Guide 1.111,
- Methods for Estimating Atmospheric Transport and Dispersion of Gaseous EfRuents in Routine Releases from Ught-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.
NUREG4133 provides methods for does calculations consistert with Regulatory Guides-1.109 and 1.111.
O 33.0 m.
Nurnber l
I MgUE R
TMI RadiologicWControls Departmental Procedure 6610-PLN-4200.01 Tine novision No.
Offste Dose Calculation Manual (ODCM) 11 I
- 2.2.2.3 Dose - lodine-131, lodine-133, Tritium, and Radionuclides in Particulate Form CONTROL:
The dose to a MEMBER OF THE PUBUC from lodine-131, lodine-133, Tritium, and all radionuclides in particulate form Mth half Hves greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:
- a. During any calendar quarter: less t'han or equal to 7.5 mrem to any organ, and
- b. During any calendar yea : less than or equal to 15 mrem to any organ.
APPUCABluTY: At all times.
ACTION:
With the calculated dose from the release of lodine-131, lodine-133, Tritium, and I
radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents '
exceeding any of the above limits, preparo and submit to the NRC Region 1 Administrator within 30 days, a SpecialJieport which 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. I 1
BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-1, ,
1 This control and associated action is provided to implement the requirements of Section !!.C, Ill.A and IV.A of Appendix 1,10 CFR Part 50. The Controls are the guides set forth in Sedion ll.C of Appendix 1. The ACTION statement provides the required operating flexibilty and at the same time implements the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable
- The ODCM calculational methods specified in the survellance requirements implement the requirements in Section Ill.A of Appendix i that conformance with the guides of Appendtx 1 be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBUC through appropriate -
pathways is unikely 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 j 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 Ught-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, lodine-133, tritium and radionuclides in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these 34 0 nm,
I Number
~
Ng I TMl Radiologicil Controls Departmental Procedure 6610-PLN4200.01 {
H* vision No.
Tme Offsite Dose Calculation Manual (ODCM) 11
- calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionudides Onto green leafy vegetation with subsequent consumption by man,3) deposition onto grassy areas where milk animals and meat producing animals graze with s
consumption of the m8k and meat by man, and 4) deposition on the ground wth' subsequent exposure of man.
2.2.2.4 Gaseous Radwaste Treatment System CONTRCt.
The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM she i be OPERABLE. The appropriate portions of the GASEOUS RADWASTE TREATMENT OYSTEM shall be used to reduce radioactive materials in the gaseous waste prior to thdr discharge when the monthly prQected gaseous effluent air doses due to untreated gaseous effluent releases from the unit would exceed 0.2 mrad for csmma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site wotJd exceed 0.3 mrom to any organ.
APPUCABILITY: At all times.
ACTION:
- a. With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being diid-ig d without treatment and in excess of the above limits, prepare and submit to the NRC Region 1 Administrator within 30 days, a Special Report which includes the following infufw=1;un.
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperabBity,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. A summary description of action (s) taken to prevent a recurrence.
BASES The use of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment. The appropriate portions of this system provide 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 10 CFR Part 50.36a, General Design Criterion 60 of Appendtx A to 10 CFR Part 50, and the design objectives given in Section ll.D of Appendix I to 10 CFR Part 50. The specified limits goveming the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections ll.B and ll.C of Appendix 1,10 CFR Part 50, for .
gaseous offluents.
35.0 nm.
kmber TMl Radiologicid Controls
^
I Departmental Procedure 6610-PLN-4200.01
- a. a.wmon m.
Offsite Dose Calculation Manual (ODCM) 11 2.2.2.5 Explosive Gas Mixture CONTROL The concentration of oxygen in the Waste Gas Holdup System shall be limited to less than or equal to 2% by volume whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume.
AVAILABlUTY: At all times. -
ACTION:
Whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume, and:
- a. The concentration of oxygen in the Waste Gas Holdup System is greater than 2%
by volume, but less than 4% by volume, without delay begin to reduce the oxygen concentration to wthin its limit,
- b. The concentration of oxygen in the Waste Gas Holdup System is greater than or equal to 2% by volume, immediately suspend additions of waste gas to the Waste -
Gas Holdup System and without delay begin to reduce the oxygen concentration to within its limit.
BASEST Based on expddi.= Jai data (Reference 1), lower limits of flammabity for hydrogen is 5%
and for oxygen is 5% by volume. Therefore, if the concentration of either gas is kept below R lower limit, the other gas may be present in higher amounts without the danger of an explosive mixture. Maintaining the concentrations of hydrogen and oxygen such that an ,
exploeWve mixture does not occur in the waste gag holdup system provides assurance that the release of radioactive materials will be controlled in conformance with the requirements of General Design Crfterion 60 of Appendix A to 10 CFR 50.
REFERENCES I
(1) Bulletin 503, Bureau of Miries: Umits of Flammabity of Gases and Vapors.
2.2.2.6 W:ste Gas Decay Tanks ;
l CONTROL: <
. l The quantity of radioactMty contained in each waste gas decay tank shall be limited to less than or equal to 8800 curies noble gases (considered as Xe-133). l l
APPUCABluTY: At all times.
36.0 mm.
1 Number b CleGr * "** ' S'# "*'*
Departmental Procedure 6610-PLN-4200.01 True Revmon No.
Offsite Dose Calculation Manual (ODCM) 11 j ACTION:
- a. With the quantty of radioactive material in any waste gas decay tank e'xceeding the -
above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
BASES Restricting the quantty of radioactMty contained in each waste gas decay tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to a MEMBER OF THE PUBUC at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, ' Waste Gas l System Falure.'
e 2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose 1
CONTROL-4 The annual (calendar yea _r)_ dose or dose commitment to any MEMBER OF THE PUBUC, due to releases of radioactMty and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limtad to less than or equal to 75 mrem.
APPUCABluTY: At all times.
ACTION:
With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a. 2.2.1.2.b, 2.2.2.2.a. 2.2.2.2.b, 2.2.2.3.a. or,2.2.2.3.b calculations should be made including direct radiation contributions from the unit and from ouhide storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submt to the NRC Region 1 Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limts and includes the schedule for achieving conformance with the above limts. This Special Report, as defined in 10 CFR Part 20.2203(b), shall include an analysis which estimates the radiation se:posure (dose) to a MEMBER OF THE PUBUC 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 materbi involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceed the above limits, and if the release condtion resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provtsions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
37.0 m
Number m Radid gi a Contres GUClear Departmental Procedure . 6610-PLN-4200.01 Tm . Ammon No.
Offsite Dose Calculation Manual (ODCM) 11 1
BASES This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). This control requires the preparation and submktal of a Special Report whenever the calculated doses from p! ant Generated ;
radioactive effluents and direct radiation exceed 25 mrom to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For stes containing up to 4 reactors, it is highly urdikely that the resultant dose to a MEMBER OF THE PUBUC wil exceed the dose limts of 40 CFR Part 190 if the individual reactors remain wthin twice the dose desi t,n objectives of Appendix 1, and if direct radiation doses from the reactor units and outside storage tanks are kept smaR. The Special Report will describe a 1 course of action that should result in the limitation of the annual dose to a MEMBER OF l THd PUBUC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium .
fuel cyde sources is negligible, wth the exception that dose contributions from otfer nuclear fuel cyde facIlties 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 wth the provisions of 40 CFR Part 190.11 and 10 CFR Part'20.2203(b), is considered to be a timely request and fulfWsyte requirements of 40 CFR Part 190 unta 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 2.2.1.1 and 2.2.2.1. An indMdual is not considered a MEMBER OF THE PUBUC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
3.0 SURVEILLANCES .
3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent instrumentation Surveillance Requirements 3.1.1.1 Each radioactive liquid effluent monitoring instruiiodadcri channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE i 1
CHECK, CHANNEL CAUBRATION, AND CHANNEL TEST operations during the I
MODES and at the frequencies shown in Table 3.1-1.
E O
38.D nm,
TatWe 3.1-1 8610-PLN-4200.01 ,
Revision 11 '.
Radioactive Liquid Effluent Monitoring Instrumentation Survegiance Requirements INSTRUMENT CHANNEL SOURCE CHANNEL CHANNEL CHECK CHECK CAUBRATION TEST
- 1. RadioactMty Monitors Providing Alami and Automatic
. Isolation
- a. Ualt 1 Uquid Radweste Effluents Line (RM-1.6) D P R(2) Q(1)
- b. IWTS/lWFS Discharge Line (RM-1.12) D P R(2) O(1)'
- 2. Flow Rate Monitors ,
- a. Unit 1 Liquid Radwaste Effluent Line (FT-84) . D(3) l N/A R Q '
- b. Station Effluent Discharge (FT-146) D(3) N/A R Q i
1 e
e 9
39.0 mu
.. -- _ _-. _ . - . _ . . , ~. _ _ - . . . . . _ _ .m. ~ _.+ - , _ _ . ,,__._m__,__-,-,_.--y,., . ...._ , , , _ , . ,.,.,,m._ . %,. ,, _ , , -. . , . . . . . , , y
Number
, ggp TMI Radlologichl' Controls Departmental Procedure 6610-PLN-4200.01 iro. w on No.
Offsite Dose Calculation Manual (ODCM) 11
- Table 3.1-1 (Cont'd)
Table Notation (1) The CHANNELTEST shaR also demonstrate that automatic isolation of this pathway and control. room alarm annunciation occurs if the following condition exists:
- 1. Instrument indicates measured levels above the high alarm / trip setpoint. (includes - circuit falure)
- 2. Instrument indicates a down scale talure. (Alarm function only.) (includes circuit falure) ,
- 3. Instrument controls moved from the operate mode (Alarm function only).
(2) The initial CHANNEL CAUBRATION for radioactivity measurement instrumentation shaR be'pinkannid using one or more of the reference standards certified.by the National Bureau of Standards or using standards that have been obtained from suppliers that participated in measurement assurance actMties with NBS. These standards should permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute prwiously established calibration procedures for this requirement)
(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.
m
$a i
l 40.0 mw 1
Numtw TMl RadiologicaI Controls Nuclear Ce ,,,1m e ,,e, r ,ocado,e io.ptu_42oo.o, Reveon No.
rio.
11 Offsite Dose Calculation Manual (ODCM) 3.1.2 Radioactive Gaseous Process and Emuent Monitoring Instrumentation SURVEILLANCE REQUIREMENTS 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAUBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2.
aus e b
6
. l 41.0 nm.
)
i
..,...,q Tatde 3.1-2 (Cont'd) es1HU6-4200.et e
, nyveesen i1 Radioactive Gaseous Process and Emuent Monitoring Instrumentation Survellance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTfRNENT CHECK CHECK CAUBRATION -TEST APPUCABluTY - ,
- 1. Weste Gas Holdup System l
- i P ***
- a. Noble Gas ActMty Monitor (RM-A7) P E(3) Q(1)
Emuent System Flow Rate Measuring Device (FT-123) Q ***
- b. P 'N/A E -
- 2. ' Waste Gas Holdup System Explosive Gas Monitoring System
- a. Hydrogen Monitor D N/A Q(4) M
- b. Oxygen Monitor D' 'N/A Q(5) M **
- 3. Containment Purge Vent System
- a. Noble Gas ActMty Monitor (RM-A9) D P- E(3) M(1) #
- b. lodine Sampler (RM-A9) W N/A N/A N/A
- c. PartictAate Sampler (RM-A9) W N/A N/A N/A #
- d. Emuent System Flow Rate Measuring Device (FR-148) 'D N/A E O #
- e. Sampler Flow Rate Monitor D N/A E. N/A #
- 4. Condenser Vent System
- a. Noble Gas ActMty Monitor (RM-A5 and Sultable D M E(3) Q(2) ##
Equivalent - See Table 2.1-2, item 4.a) 42.0 nn.
t TaWe 3.1-2 (Cont'd) es10 PLN-4200.01, Rpvleton 11 Radioactive Gauxas Process and Efiluent Monitorin0 nstrumentation i SurvelRance Requirements
^
CHANNEL SOURCE CHANNEL CHANNEL-INSTRUIENT CHECK CHECK CAUBRATION TEST APPUCAB1UTY
- 5. AuxBlary and Fuel HandNng Bulding Vent 8ation System
- a. Noble Gas ActMiy Monitor (RM-A8) or (RMM and D M E(3) Q(1)
RM-A6)
- b. lodine Sampler (RM-A8) or (RM-A4 and RM-AS) W N/A , N/A - N/A *
- c. Particulste Sampler (RM-AB) or (RMM and RM-AS) W N/A N/A. N/A
- d. System EfRuert Flow Rate Measurement Devices D i N/A E Q i
(FR-149 % FR-150)
- e. Sampler Flow Rate Monitor D N/A E N/A
- 6. Fuel Handling Building ESF Air Trestrmmt System D M ""'
- a. Noble Gas ActMty Monitor (RM-A14) R(3) O(2)
D R -
O ""
- b. System EfRuont Flow Rate (UR-1104 A/B) N/A Q **"
i c. Sampler Flciw Rate Measurement Device _
D N/A R e
s u
?
43.0 mw
Number
^ j
- EE TMl Radidogicil Contrds Departmental Procedure 6610 PLN-4200.01 no. am on No.
Offsite Dose Calculation Manual (ODCM) 11 Table 3.1-2 (Cont'd)
Table Notation
- At aR times.
- During waste gas holdup system operation.
- Operabilty is not required when discharges are positively contrdled through the dosure of WDG-V47, and where RM-A8 (or RM-A4 and RM-A6), FT-149, and FT-150 are operable.
- During Fuel Handling Buiding ESF Air Treatment* System Operation.
- At aR times during containment purging.
- At aR times when condenser vacuum is established.
(1)
The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway for the Auxiiary and Fuel Handling Bulding Ventiation System, the supply ventilation is isolated and contrd room alarm annunciation occurs if the following condition exists:
- 1. Instrument indicates measured levels above the high alarm / trip setpoint (indudes circu!!
falure).
- 2. Instrument indicates a do_wp scale faRure (Alarm function ordy) (Indudes circuit faHure).
- 3. Instrument contr'ds moved from the operate mode (Alarm function only).
(2) The CHANNEL TEST shall also demonstrate that contrd room alarm annunciation occurs if any of the foRowing conditions exist '
- 1. Instrument indicates measured levels above the alarm setpoint. (indudes circuit falure)
- 2. Instrument indicates a down scale faBure (includes circuit faBure).
- 3. Instrument controls mwed from the operate mode.
(3) The initial CHANNEL CALIBRATION for radioactMty measurement instrumentation shall be performed using one or more of the reference starmiards certified by the National Bureau of Standards or using standards that have been obtained from suppi'ers that participate in
, measurement assurance activties with NBS. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute previously established calibration procedures for this requirement.)
(4) The CHANNEL CAL!BRATION shall indude the use of standard gas samples containing a nominal:
- 1. One volume percent hydroghn, balance nitrogen, and
Numbw TMI Radiologicsl Controls
~
I Departmental Procedure 6610 PLN-4200.01 we, Revision No.
Offsite Dose Calculation Manual (ODCM) 11 Table 3.1-2 (Cont'd)
(5)
The CHANNEL CAUBRATION shall include the use of standard gas samples containing a nominal:
e 9
45.0 nm.
Number
. ggy- TMl RadiologicifControls Departmental Procedure 6610-PLN-4200.01 FWeson No.
Me 11 Offstte Dose Calculation Manual (ODCM) 3.2 Radioactive Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Corsa.haiion .
3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 3.2-1. The results of pre-release analyses shall be used wth the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1,1.
3.2.1.1.2 Post. release analysis of samples composited from batch releases shall be performed in acccidarce with Table 3.2-1. The results of the ,
previous post <elease analysis shall be used with the calculational l methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1.
~~
3.2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational method's of the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.
3.2.1.2 Dose Calculations 3.2.1.2.1 CumtAative dose contributions from liquid effluents shall be l
determined in accordance with the Offsne Dose Calculation Manual (ODCM) at least once a month.
3.2.1.3 Uquid Waste Treatment 1 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM.
3.2.1.3.2 The liquid radwaste treatment. system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 60 minutes quarterly unless the liquid radwaste system has been utilized to process radioactive liquid ef!Iuents during the previous 92 days.
1 1
l 46.0 mm.
Number ggp TMI Radiologicil Controis Departrnental Procedure 6610-PLN-4200.01 Tm Arvmeon No.
Offsite Dose Calculation Manual (ODCM) 11 3.2.1.4 Uquid Holdup Tanks 3.2.1.4.1 The quantity of radioactive material' contained in each of~the tanks specified in Control 2.2.1.4 shall be determined to be within the limit by analyzing a representative sample of the tank's content weekly when radioactive materials are being added to the tank.
G O
e P
e G
9 47.0 un,
Table 3.2-1 6610PLN-4200.01, Rph " r Radioactive Uquid Waste Sampilng and Analysis Program ,
i i l l Lower Limit of Sampling Minimum Analysis ! Type of Activity ! Detection (LLD) l ! I _ (pCl/ml) (Note a)
L61uld Release Type Frequency , Frequency Analysis A.1 Batch Waste Release Tanks (Note d) P P H4 1 x 10-8 Each Batch g Each Batch Principal Gamma i 5 x 10-7 Emitters (Note f) l
! I-131 1 x 104 I i 4
P l M ! Dissolved and l 1 x 10 l One Bttch/N l l Entrained Gases i j i I (Gamma
! I l Emitters) l 1 !
P Q l Gross alpha 1 x 10-7 Each Batch Composite (Note b) l g Sr-89, Sr-90 5 x 10-8
-l ,
- l l
1 x 10 4 Fe-55 l, ,
. j O
e S
48.0 mm
- - r . --. .__--v - , .-,
Table 3.2-1 (Cont'd) 0610-PLN-4200.01 ,
p 11 Radioactive Liquid Waste Sampling and Analysis Program l l t-r una or Sampling Minimum Analysis l Type of ActMty Detection (LLD)
Liquid Release Type Frequency e Frequency j Analysis l; (pCl/mi) (Note a)
A.2 Continuous Releases (Note e) l Continuous l W PrincipalGamma l 5 x 10-7
! (Note c) l Composite l Emitters (Note f) i j j (Note c) l l l l l l-131 ; 1 x 10 l M l M ~l Dissolved and l 1 x 10-5 l Grab Sample j i Entrained Gases '
l , j (Gamma Emitters)
R I Continuous M H4 1 x 10'5 (Note c) g Composite j-
,e : (Note c) Gross alpha 1 x IJ 7 I I l Continuous
- O Sr-89, Sr-90 5 x 104 .
l Composite !
(Note c) !
4 l (Note c) Fe-55 l 1 x 10 4
O ab 49.0 ma
Number
, g I TMl Radiologic a~l Controls Departmental Procedure 6610-PLN-4200.01 True Revisson No.
Offsite Dose Calculation Manual (ODCM) 11
. I Table 3.2-1 (Cont'd)
Table Notation
- a. The LLD is defined, for purposes of this survellance, as the smallest concentration of radioactive material in a sample that wil yield a net count above system background that wil be detected with i 95% probability with 5% probablity of falsely concluding that a blank observation represents a "real" signal For a particular measurement system (which may include radiochemical separation):
LLD = 4 66 s, E x V x 2.22 x 10' x Y x exp (-A At) l Where:
i i LLD is the 'a priori" lower limit of detection as defined above (as microcurie per unk mass or volurne),
sbis the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per disintegration),
i I
V is the sample size (in units of mass or volume),
2.22 x 10e is the number of disirtegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting.
Typical values of E, V, Y and At shah be used in the calculation.
It should be recognized that the LLD is defined as an 'a priorl* (before the fact) limt representing the.
capabity of a measurement system and not as an "a postericri" (after the fact) limit for a particular measurement.
- b. A composse sample is one in which the quantity of liquid sampled is proportional to t,he quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representatNe of the liquids released.
- c. To be representative of the quantiles and concentrations of radioactive materials in liquid effluent, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, au samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
I 50.0 mm.
l i
i Number )
TMI Radiologicsf Controls l EI Departmental Procedure 6610 PLN-4200.01 Tme Revision No.
I Offsite Dose Calculation Manual (ODCM) 11 l l
l Table 3.2-1 (Cont'd)
- d. A batch release is the discharge of liquid wastes of a discrete vdume. Prior to sampling for analyses, each batch shall be isdated, and be thoroughly mixed, by a method described in the CDCM, to assure representathm sampling.
A continuous release is the discharge of liquid wastes of a non- discrete volume; e.g., from a volume I e.
or system that has an input flow during the continuous release.
- f. The principal gamma' emitters for which the LLD specifiestion applies exclusively are the following radionudides: Mn-54, Fe-59, Co-58, Co-60,2n45, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.
This list does not mean that only these nudides are to be considered. Other gamma peaks that are identifiable, together with those of the above nudides, shall also be analyzed and reported in the '
Annual Radioactive Effluent Release Report pursuant to TS 6.9.4.
t om e 9
4 4
e.
9 51.0 mm.
1 1
Numb.r )
TMI Radiologicil' Controls l UI Departmental Procedure 6610-PLN-4200.01 m.. mvimon No.
Offsite Dose Calculation Manual (ODCM) 11 3.2.2 Gaseous Effluents SURVEILI.ANCE REOUIREMENTS 3.2.2.1 ' Dose Rates 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be -
determined to be within the limits of Control 2.2.2.1.a in accordance with the methods and procedures of the ODCM.
3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseus effluents shall be determined to be within the limits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM
- by obtaining representative samples and performing anelyses in accordance with the sampling and analysis program, specified in Table 3.2-2.
3.2.2.2 Dose, Noble Gas
- Cumulative dose contributions from noble gas effluents for the current 3.2.2.2.1 cal _endar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) montNy.
3.2.2.3 Dose, lodine-131, lodine-133, Trttlum, and Radionuclides in Particulate Form 3.2.2.3.1 Cumulative dose contnbutions from lodine-131, lodine-133 Tritium, and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) mentNy.
3.2.2.4 Gaseous Waste Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected montNy in accordance with the ODCM.
3.2.2.5 Explosive Gas Mixture !
3.2.2.5.1 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the limts of Control 2.2.2.5 by monitoring the waste gases in the Waste Gas Holdup System with the ,
hydrogen and oxygen montors covered in Table 2.1-2 of Control 2.1.2. ,
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Offsite Dose Calculation Manual (ODCM) 11 l
3.2.2.6 Waste Gas Decay Tank 3.2.2.6.1 The concentration of radioactMty contained in the vent header shall be determined weeldy. If the concentration of the vent header exceeds 10.7 Cl/cc, daily samples shall be taken of each waste gas decay tank being added to, to determine if the tank (s) is less than or equal to 8000 Cl/ tank.
l
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O 53.0 mm,
x Table 3.2-2 . este.-PU6-4ase.01, Rpvleton 11 L Rad 6oactive Uquid Weste Sampling and Analysis Program l Minimum l l Lower Umit of I sampling l Analysis i Type of ActMiy 1 - Detection (LLD) .
Gassous Reisese Type l Frequency Frequency Analysis l pCl/nd) (Note a) -
I !
4 -
l P P l t 1 A. Waste Gas .
I Each Tank i Each Tank Principal Gemme i 1 x 104 Decay Tank ' Grab Sample ! Emitters (Note g) I B. Containment l P (Note b) P (Note b)' I H-3 1 x 10-s ,
4 Purge ! Each Purge Each Purgo Principal Gamma l 1 x 10 i' e Grab Sample Emitters (Note g)
, M (Notes c, e) H4 4-C. Auxtlery arul , , M l 1 x 10 d Fuel Handling Bugding l Grab Sample ! Principal Gamma l 1 x 10 i Air Treatment System l l Emitters (Note g) I.
i D. Fuel Handling Building l M (during l' M (during , H4 l l Principal Gamma 4 ESF Air Treatment System l System l System i 1 x 10 .
j Operation) l Operation) l Emitters (Note g) ! 1 x 104 ,
I I I E. Condenser Vacuum ! ! M ! H -3 I Pumgis Exhaust ! Grab M (Note Sample h) ! (Note h) ! Principal Gamma ! 1 x 10-s 4 '
(Note h) l I Emitters (Note g) 1 x 10 l
+ t 54.0 . mi, l
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Table 3.2-2 (Coned) estptN-4200.01, Rpviolon 11 r-Radioactive Uquid Waste Sampling and Analysis Program l Sampling Minimum Analysis ! ! Lower Umit of Detection (LLD)-
Gaseous Release Type l Frequency l Frequency l Type of ActMty Analysis l (pCl/mi) (Note a)
F. All Release Types as Usted Above l , Continuous ! W (Note d) l l-131 l 1 x 10 42 in A B, C and D (During System O l (Note f) l Charcoal Sample l l Operation ! ! !
Continuous W (Note d) Principal Gamma Emitters l 1 x 10-"
(Note f) Particulate j (Note g) !
l (1-131, Others) l I ! 1 x 10-"
l Continuous O ! ,
l (Note f) Composite 5 l Gross Alpha j
, Particulate SarO i
- Continuous ! o ! I l' (Note f) ! Composite ' St-89, Sr-90 l 1 x 10'"
' Particulate Sample I i G. Condenser vent Stack Continuous j j ! ,
lodine l Continuous l W (Note d) 'g 1-131 l 1 x 10a2 Sampler (Note j) I Charcoal Sample 3 -
l l (Note k) ,
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O a
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55.0 mm
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i Number NUd '"' "*d'o'oo'ca' o "tro
Dopretri dal Procedure 6610 PLN-4200.01 m Hovmon No.
Offsite Dose Calculation Manual (ODCM) 11 Table 3.2-2 (Cont'd) .
Table Notation
- a. The Lt.D is deilned, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that wil be detected with 95% probabilty with 5% probabity of falsely concluding that a blank observation represents a "real*
signal l For a particular measurement system (which may include radiochemical separation): !
LLD = 4.66 s,.
E x V x 2.22 x 10' x Y x exp (-A At)
)
Where: )
I LLD is the "a priori" lower limit of detection as defined atme (as microcurie per unt mass or volume),
sbis the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counttper minute),
E is the counting efficiency (as counts per disintegration),
i V is the sample size (in units of mass or volume), l
\
2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
l A is the radioactive decay constant for the particular radionuclide, and 1
- l At is the elapsed time between midpoint of sample collection and time of counting.
Typical values of E, V, Y and At shall be used in the calculation.
It should be recognized that the LLD is defined as an *a priorf (before the fact) limt representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular j measuremert
- b. Sampling and analysis shall also be par'vinied following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER wthin one hour unless (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 activity montor shows that effluent actMty has wt increased by more than a factor of 3.
- c. Tritium grab samples from the spent fuel pool area shaB be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded. '
56.0 mm.
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' ggEI Departmental Procedure 6610-PLN-4200.01 rm. aevmon No.
4 Offsite Dose Calculation. Manual (ODCM) 11 Table 3.2-2 (Cont'd)
- d. Charcoal cartridges and particulate ftters shall be changed at least once per 7 days and analyses shall be completed wthin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).
- e. Tritium grab samples shall be taken weekly from the spent fuel pod area whenever spent fuel is in the spent fuel pool.
- f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each done or dose rate calculation made in accordance wth Controls 2.2.2.1,2.22.2, and 2.2.2.3.
- g. The principal gamma emitters for which the LLD specification applies exclusively are the following
- radionuclides: Kr47, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-69, Co-58, Co-60,2n45, Mo 99, Cs-137, Ce-141 and Ce-144 for particulate omissions. 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 TS 6.9.4.
- h. Applicable only when condenser vacuum is established. Sampling and analysis shall also be ,
imifciTred following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER wthin one hour unless (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 activity rnonitor shows that aflluent activity has not increased by more than a factor of 3.
- 1. Gross Alpha, Sr-89, and Sr-90 analyses do not apply to the Fuel Handling Building ESF Air Treatment System.
J.
If the Condenser Vent Stack Continuous lodine Sampler is unavalable, then attemate sampling equipment will be placed in service within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or a report wRI be prepared and submitted within 30 days from the time the sampler is found or made inoperable which identifies (a) the cause of the inoperabGity, (b) the action taken to restore representative sampling capabity, (c) the action taken to prevent recurrence, and (d) quantification of the release via the pathway during the penod and comparison to the limits prescribed by Cordrol 22.2.1.b.
- k. Applicable only when condenser vacuum is established.
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Number TMI Radiologicil Controls EI Departmental Procedure 6610-PLN-4200.01
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Offsite Dose Calculation Manual (ODCM) 1.1 3.2.3 Total Radioactive EfMuents 3.2.3.1 Dose Calculation 3.2.3.1.1 - Cumulative annual dose contributions from liquid and gaseous efRuents shall be determined in accordance with SurveWances 3.2.1.2.1,3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM.
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- gggy TMI Radiologicil Controls Departmental Procedure 6610-PLN-4200.01 Tree , Revisson No.
Offsite Dose. Calculation Manual (ODCM) 11 4
4.0 PART I REFERENCES 4.1 Title 10, Code of Federal Regulations, " Energy
- l 4.2 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routing Releases of Reactor I
Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, " Revision 1, October 1977 I l
4.3 TMI-1 Technical Specifications, attached to Fac8ty Operating License No. DPR40 4.4 TMI-1 FSAR l
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Number Nuclear " "* Sd ""d*
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Offsite Dose Calculation Manual (ODCM) < 11 9 O f
ame+
PART11 l
TMI-2 RADIOLOGICAL EFFLUENT CONTROLS l
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Number ggp TMI Radiologicil Controls Departmental Procedure 6610-PLN-4200.01 Tree Asvision No.
Offsite Dose Calculation Manual (ODCM) 11 4
PART il Definitions 1.0 DEFINITIONS DEFINED TERMS ,
1.1 The DEFINED TERMS of this section appear in captalized type and are applicable throughout Part ll of the ODCM.
FA'CIUTY MODE 3 1.2 Post-Defueling Monitored Storage (PDMS) is that condition where TMI-2 defueling has been completed, the core debris removed from the reactor during the dean-up period hEs been shipped off-ste and the facility has been placed in a stable,' safe and secure condtion.
ACTION 1.3 ACTION shall be those additional requirements specified as corollary statements to each control and shall be part of the controls.
OPERABLE - OPERABluTY 1.4 A system, subsystem, train, component or device shall be OPERABLE or have OPERABluTY when it is capable of performing its specified function (s), implict in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency skn,L-kid power sources, cooling or seal water, lubik.&iv6 or other auxilary equipment, that are required for the system, subsystem, train, component or device to perform ts function (s), are also capable of performing their related support func'jon(s).
CHANNEL CAllBRATION 1.5 A CHANNEL CAUBRATION shall be the adjustment, as necessary, of the ciennel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CAUBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CAUBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shalt include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
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Offsite Dose Calculation Manual (ODCM) 11 NOTE l For radioactive effluent monitors, except for those in Table 2.2-1, this shall indude a verification which provides a qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog channels - the injection of a simulated signal into the channel as close to the primary
, sensor as practicable to verify OPERABILITY induding alami and/or trip functions.
- b. Bistable channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY induding alarm and/or trip functions.
i FREQUENCY NOTATnUN .
1.8 The FREQUENCY NOTATION specified for the performance of Survellance Requirements shall correspond to the intervals defined-in Table 1.1.
COMPOSITE SAMPLE j 1.9 A COMPOSITE SAMPLE is a combination of individual samples obtained at regular intervals over a I time period. Elther the volume of each individual sample is proportional to the low rate discharge at the time of sampling or the number of equal vdume samples is proportional to the time period used to produce the composite.
GRAB SAMPLE 1.10 A GRAB SAMPLE is an indMdual sample collected in less than fifteen minutes.
BATCH RELEASE 1.11 , A BATCH RELEASE is the discharge of fluid waste of a discrete volume.
CONTINUOUS RELEASE 1.12 A CONTINUOUS RELEASE is the discharge of fluid waste of a non-discrete volume, e.g., from a volume or system that has an input flow during the CONTINUOUS RELEASE.
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NgEI Departrnental Procedure 6610-PLN-4200.01 Revmon No.
Tatie 11 Offsite Dose Calculation Manual (ODCM)
- TABl.E 1.1 Frequency Notation NOTATION FREQUENCY S (Shiftly) 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 (Daly) 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 (Weeldy) At least once pcr 7 days.
M (Monthly) At least once per 31 days.
Q (Quarterly) ' , At least once per 92 days.
SA (Semi-Annually) At least once per 184 days.
A (Annually). At least once per 12 months.
E _ . .
At least once per is rnonths.
N.A. Not applicable.
- 1 63.0 mm. 1 l
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Numtsw TMI Radidogical ~ Controls y Departmental Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 11
- ' SECTIONS 2.0,3.0 AND 4.0 Controls and Surveillance Requirements 2/3.0 APPLICABILITY CONTROLS 2/3.0.1 Controls and ACTION requirements shall be applicable during the conditions specified for each control.
2/3.0.2 Adherence to the requiremerits of the Control and/or associated ACTION within the specified time interval shal consttute compliance with the control. In the event the Control is restored prior to expiration to the specified time interval, completion of the ACTION statement is not required.
2/3.0.3 in the event the Control and/or associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the Control, initiate appurimie actions to rectify the problem to the extent possible under the circumstances, and submit a special report to the Commission pursuant to TMI-2 PDMS Technical Specification (Tech. Spec.) Section 6.8.2 within ,
30 days unless otherwise specified
~
SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the conditions specified for individual Controls urdess otherwise stated in an individual Surveillance Requirement. The Survellance Requirements shall be performed to demonstrato compliance wth the OPERABILITY requirements of the Control.
4.0.2 Each Survellance Requirement shall be performed wthin the specified time interval with:
- a. A maximum allowable extension not to exceed 25% of the surveiHance interval, and
- b. A total maximum combined interval time for any 4 consecutive tests not to exceed 3.25 times the specified surveulance interval.
, 4.0.3 Performance of a Survellance Requiremert within the specif'ed time interval shau consttute compliance with 4 OPERABluTY requirements for a Control and associated ACTION statements unless otherwise required by the Control.
64.0 mi.
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Nuclear Departmental Procedure 6610-PLN-4200.01 Tme Revisxm No.
Offsite Dose Calculation Manual (ODCM) 11 BASES The Controls of this section provide the general requirements applicable to each of the Control and Surveillance Requirements.
2/3.0.1 This Control defines the applicability of each Control in terms of the specified conditions and is provided to delineate specifically when each Control is applicable.
2/3.0.2 This Control defines those conditions necessary to constitute compliance wth the terms of an individual Control and associated ACTION requirement. I 2/3.0.3 This Contrd delineates the ACTION to be taken for circumstances not directly provided for in the ACTION statements or when the provisions of the stated ACTION statement are not or cannot be '
complied with. The intent of this Control is to require that inoperable equipment be restored to an OPERABLE status in a prompt manner, that the unt be maintained in stable conditions, and that the Commission be promptly notified of such conditions.
4.0.1 This Control provides that survellance activities necessary to ensure the Contrds are met and will be performed during the FACluTY MODE or other condtions for which the Contrds are applicable.
'4.0.2 The provisions of this Contrd provide allowable tolerances for performing survellance activities beyond those specified in the normal survellance interval. These tderances are necessary to provide operational flexibilty because of scheduling and performance considerations. The phrase "at least* associated with a surveillance frequency does no negate this allowable tolerance value and permits the performance of more frequent survellance activities.
The tolerance values, taken either individually or consecutively over 3 test intervals, are sufficiently restrictive to ensure that the reliability associated with the survellance actMty is not degraded beyond that obtained from the nominal specified interval.
4.0.3 The provisions of this Contrd set forth the criteria for determination of compliance with the OPERABlUTY requirements of the Contrd. Under this crteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance actMties have been satisfactorty performed wthin the specified time interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABlf., when such items are found or known to be inoperable although stil meeting the Survellance Requiremeits.
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Offsite Dose Calculation Manual (ODCM) 11 2.0 RADIOLOGICAL EFFLUENT REQUIREMENTS 2.1 Radioactive Discharges 2.1.1 Uquid Effluents 2.1.1.' OBJECTIVES To define the limits and conditions for the contrdied release of liquid radioactive effluents to the environs to ensure that these releases are as low as practicable. These releases should not result in radiation exposures to offsite areas greater than a few percent of background exposures. The instantaneous release rate for all effluent discharges should be within ten times the concentrations -
specified in to CFR Part 20.
To assure that the releases of radioactive liquids to offsde areas meet the "as low as practicable" j concept, the following objectives apply:
I A. The annual total quantity of radioactive materials in liquid waste, excluding tritium and dissolved gases, should not exceed 5 curies per radioactive wasterproducing reactor, and the annual dose to the whde body or any organ of an individual should not exceed 3 mrem to the total body and shall_be less than or equal to 10 mrem to any organ.
B. The annual average concentration of radioactive materials in the effluent from the Mechanical Draft Cooling Towers prior to dilution in the Susquehanna River, excluding tritium and dissdved gases, should not exceed 2E-8 pCi/ml.
C. The annual average concentration of tritium in liquid waste prior to dilution in the environment should not exceed SE-6 pCl/ml.
2.1.1.2 APPLICABILITY Applies to the contrdled release of radioactive liquids from TMI-2.
2.1.1.3 CONTROLS A. The radioactMty release concentration in liquid effluents from TMI-2 to the environment shall not exceed ten times the values specified in 10 CFR 20, Appendix B, for unrestricted areas.
B. The total release of radioactive liquid effluent from TMI-2, excluding tritium and noble gases, shall not exceed 10 curies during any calendar quarter.
C. The equipment inctalled in the liquid radioactive wasta system shall be maintained and shall be operated to process all radioactive liquid wastes prior to this discharge when the actMty release rate wil exceed 1.25 curies, excluding tritium and dissolved gases, during any calendar quarter.
D. The maximum radioactMty to be contained in one liquid radwaste tank, excluding tritium and dissdved gases, that can be discharged directly, to the environs, shall not exceed 10 curies.
66.0 nm.
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Namber J TMI Radiologicil ~Contrals
-W ME Departmental Procedure 6610-PLN 4200.01 True Revtsson No.
L Offsite Dose Calculation Manual (ODCM) 11 l E. When the average release rate of radioactive effluents, excluding tritium and dissolved gases, exceeds 2.5 curies per radioactive waste-producing reactor during any calendar quarter, the licensee shan notify the NRC within 30 days, identifying the causes and describing the proposed program of action to reduce such release rates.
F. The dose or dose commitment from liquid effluents shall be less than or equal to 3 mrom total body and less than or equal to 10 mrem to any organ for the calendar year.
2.1.1.4 BASES ,
Uquid radioactive waste release levels to unrestricted areas should be kept 'as low as practicable" and are not to exceed ten times the concentrations specified in to CFR 20. The Controls provide reasonable assurance that the resulting annual exposure to an individual in off-site areas wHl not exceed the design objectives of Appendix I to 10 CFR Part 50, which were established as requirements for the cleanup of TMI-2 in the NRC's Statement of Policy of AprI 27,1981. This assurance is based on the fact that the Susquehanna River WHI dilute the liquid effluents upon their release from the site. The effluents wul be diluted by a factor of about 250 in the region where finfish can exist (within a onequarter rnie radius of the discharge point). At the same time these Controls ,
permit flexibility under unusual conditions, which may temporarly result in higher than normal releases, but stBI within ten times the concentrations, specified in 10 CFR 20. It is avpaM that by using this flexitAlly under unusual, condtions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases wil not exceed a small fraction of
. the annual average concentrations specified in 10 CFR 20.
Control 2.1.1.3 A. above requires the licensee to limit the concentration of radioactive materials in liquid effluents from TMI-2 to ten times the levels specified in 10 CFR 20, Appendix B, for ,
unrestricted areas. This Control provides assurance that no member of the general public can be !
exposed to liquids containing radioactive rnaterials in excess of limits considered permissible under ;
the Commission's rules and regulations. 7 Control 2.1.1.3 B. above establishes an upper limit for the release of radioactive liquid effluents, excluding tritium and disadved gases, of 10 cunes during any calendar quarter. The intent of this Control is to permt the licensee flexibity under unusual conditions, which may temporarly result in !
releases higher than the levels normeNy achievable when the unit and the liquid radwaste equipment are functioning as designed. Releases of up to 10 curies during any calendar quarter will result in concentrations of radioactive materials in liquid effluents at small percentages of the concentrations specified in 10 CFR 20.
Control 2.1.1.3 C. requires the licensee to maintain and operate the equipment installed in the liquid radioactive waste system to reduce the release of radioactive materials in liquid effluents to as low as practicable, 'onsistent with the requirements of 10 CFR 50.36a. Normal use and maintenance of instaNed equir : ent in the liquid radioactive system is expected to result in releases of not more than about five curies per year, excluding _ tritium and dissolved gases during normal operations. In order to keep releases of radioactive materials as low as practicable, the Control requires, as a minimum, operation of equipment whenever the rate of release exceeds 1.25 curies per quarter, excluding ;
tritium and dissolved gases -
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l Number gggp TMl Radiologicsl Controls Departmental Procedure 6610-PLN-4200.01 Tm. Revmon No.
Offsite Dose Calculation Manual (ODCM) 11 i
- In addition to Control 2.1.1.3 B., the reporting requirements of Control 2.1.1.3 E. and Section 6.6 of the TMI-2 PDMS Tech. Specs., delineate that the licensee shall identify the cause whenever the rate of radioactive effluents, excluding tritium and noble gases, exceeds 2.5 curies during any calendar quarter and describe the proposed program of action to reduce such release lates. This report must be fled within 30 days following the calendar quarter in which the 2.5 curie release occurred.
Control 2.1.1.3 F. requires that the dose to offsite personnel be limited to the design objectives of
- Appendix 1 of 10 CFR Part 50. This will assure the dose received by the public during the cleanup is equivalent to or less than that from a normal operating reactor. The limits also assure that the environmental irnpacts are consistent with those assessed in NUREG-0683, the TMI-2 Programmatic, EnvironmentalImpact Stateme.1(PElS).
2.1.2 Gaseous Effluents 2.1.2.1 OBJECTIVES To define the limits and conditions for the controlled release of radioactive gaseous effluents to the environs to ensure that these releases are as low as practicable. These releases should not result in I
radiation exposures in offsite areas Dreater than a few percent of background exposures.
To assure that the release of radioactive gases to offsite areas meet the as low as practicable l
concept, the release rate of gaseous effluents shall not result in doses to the public exceeding the
, design objectives of Appendtx I to 10 CFR Part 50.
2.1.2.2 APPUCABluTY Applies to the controlled release of radioactive gases from TMI-2.
2.1.2.3 CONTROLS l A. The insuntaneous dose rate from release of gross gaseous activity except for halogens and i particul2tes with half-lives longer than eight days shall not exceed 500 mrem / year to the ;
total fxxfy and 3000 mrem / year to the skin.
B. The instantaneous dose rate from release of particulates with half-lives greater than eight i days, to the environs as part of the airbome effluents, shall not exceed 1500 mrem / year to l any organ.
C. Radioactive gases and particulates purDed from the Reactor Bulding shall be filtered through the high efficiency particulate air filters. :
i D. The air dose due to noble gases in gaseous effluents shall be less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation for the calendar year, and less than or equal to 5 mrad for gamma radiation and 10 mrad for beta radiation for any calendar quarter.
E. The dose for radioactive (other than noble gaseous effluents) shall be less than or equal to 15 mrem to any organ f6r the calendar year, and 7.5 mrem to any organ for any caterxiar quarter.
68.0 rm.
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' hgI Departmental Procedure 6610-PLN-4200.01 FWvupon No.
Tme a
l Offsite Dose Calculation Manual (ODCM) 11 F. When the release of radioactive materials in gaseous wastes exceeds the values in Controls A, B, D or E, the licensee shaX notify the NRC within 30 days, identifying the causes and describing the proposed program of action to reduce such releases.
2.1.2.4 BASES 1
The specified levels provide reasonable assurance that the resulting annual exposure rate from noble gases at any location at the site boundary wil not exceed 10 m5irems per year. At the same time, these Controls permit flexibility under unusual conditions, which may temporarly result in higher than the design objective levels, but stil wthin the dose limits specified in 10 CFR 20 and within the design objectives of Appendix i to 10 CFR 50. It is expected that using this flexibilty under unusual I conditions, and by exerting every effort to keep levels of radioactive material in gaseous wastes as low as practicable, the annual releases wHI not exceed a small fraction of the annual dose limits
- specified in 10 CFR 20 and wRI not result in doses which exceed the design objectives of Appendix 1 to 10 CFH 50, which were endorsed as limits for the cleanup of TMI-2 by the NRC's Statement of Policy of April 27,1981.
These efforts should include consideration of meteorological conditions during releases.
- Control 2.1.2.3 A., requires the licensee to limit the concentration of noble gar,es from TMI.-2 to unrestricted areas to levels such that no individual wRI receive dose at a rate greater than 500 .
mrem /yr to the total body or 3000 mrom/yr to the skin.
Control 2.1.2.3 B., requires the licensee to limit the concentration of partict6es with half-lives greater than eight days, released from TMI-2 to unrestricted areas to levds such that no individual wHI receive dose at a rate greater than 1500 rnrem/yr to any organ. T he absence of iodine ensures that the corresponding thyroid dose rate above background to ar'snfant via the cow-milk-infant pathway is less than or equal to 1500 mrem /yr. A grazing pe&f of 6 months has been applied to au radionuclides in particulate form with half-lives greater than 8 days, to aHow for the mik exposure pathway Control 2.1.2.3 C., limits the radioactivity that may be released to the environment to "as low as l practicable."
In addition to the requirements of Controls 2.1.2.3 B., D. and E., the reporting requirements of Control 2.1.2.3 F. delineate that the licensee shaB identify the cause whenever the radioactive gaseous releases exceed Control 2.1.2.3 D. or Control 2.1.2.3 E., and describe the proposed prograrn of action to reduce such releases. The report must be fled within 30 days following the .
calendar quarter in which the release occurred.
o 69.0 wu ,
Number, TMI RadiologiciG' Controls
. 'g p Departmental Procedure 6610-PLN-4200.01 Tr5e Rwisaort No.
Offstle Dose Calculation Manual (ODCM) 11 2.2 Radioactive Gaseous Effluent Monitoring Instrumentation 2.2.1 OBJECTIVN The radioactive gaseous effluent monitoring instrumentation channels shown in Table 2.2-1 i shall be OPERABLE.
2.2.2 APPUCABILITY As shown in Table 2.2-1.
2.2.3 CONTROL With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.2-1, 2.2.4 BASES The radioactive gaseous affluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The OPERABIUTY and use of this instrumentation is consistent with the requirements of General Design Criterion 64 of Appendix A to 10 CFR Part 50.
O o.
4 9
O 70.0 ms.
)
i l
J
l Number TMI Radiological Cortrols lEI
" Departmental Procedure 6610-PLN-4200.01 Tme Revision No.
Offsite Dose Calculation Manual (ODCM) 11 1
TABLE 2.2-1 i Radioactive Gaseous Effluent Monitoring instrumentation CHANNEL MINIMUM ,
CHANNEL CHANNEL FUNCTONAL CHANNELS INSTRJMENT CHriCK CAUBRATON TEST OPERABLE APPUCABRJTY ACTON HPA219 Gas D E M 1 Note 1 Note 2 HP4219 Particulate D E M 1 Note 1 Hote 2 HPA219A Gas D E M 1 Note 1 Note 3 HPA219A Partculate D E M 1 Note i Note 3 HPA225 Gas D E M 1 Note 1 Note 4 HPA225 Partculate D E M 1 Note 1 Note 4 l
NOTES:
- 1. During operation of the monitored systern.,.
- 2. If the same channel on HP-R-219A is inoperable, secure Reactor Building Purge N in progress.
- 3. If the same channel on HP-R-219 is inoperable, secure Reactor Building Purgo N in progress.
- 4. If channel is inoperable, secure Reactor Building Purge N in progress.
e 4
71.0 mm,
l l
Number ggy TMl Radiological' Controls Departmental Procedure 6610-PLN-4200.01 !
Title Revieson No.
1 Offsite Dose Calculation Manual (ODCM) 11 l l
3.0 MONITORING REQUIREMENTS 3.1 RadioactNe Discharges 3.1.1 Uquid Elfluents 3.1.1.1 OBJECTIVE To ensure that radioactNe liquid releases from the factity are within the limts of Controls 2.1.1.3 A.
through F.
3.1.1.2 CONTROLS ,
During release of liquid radioactive wastes from Radioactke Waste-Miscellaneous Uquids System, the following condtions shall be met:
A. Faclity records shall be maintained of the radioactke concentrations and volume before diution of each batch of liquid effluent released, and the average diution flow and length of time over which each discharge occurred. Estimates of the error associated with each reported value should be included in faclity records.
B. Radioactive liquid waste Empling and activity analysis shall be performed in accordance with Table 3.1-1 Prior to the release of each batch of liquid effluent, a sample shall be taken from that batch and analyzed for the concentration of each significant gamma emitter to demonstrate compliance with Control 2.1.1.3 A. using the flow into which the effluent is discharged.
3.1.1.3 BASES These monitoring requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive liquid wastes released to the environment. Reports on the quantitles of radioactive materials released in liquid effluents shah be fumished to the Commission on the basis of ODCM Part IV Requirements. On the basis of such reports and any addtional information obtained from the licensee or others, the Commission may require the licensee to take appropriate action.
3.1.2 Gaseous Effluents 3.1.2.1 OBJECTIVE To ensure that radioactive gaseous releases from the facllty are wthin the limits of Controls 2.1.2.3 A. through F.
3.1.2.2 CONTROLS During release of radioactive gaseous wastes, the following condtions shall be met:
i i
l 72.0 wu i l
l l
Number gggE TMI Radiological' Controls Departmental Procedure 6610-PLN 4200.01 m.. FWw)n No.
Offsite Dose Calculation Manual (ODCM) 11 A. During purge of the Reactor Building, the following conditions shall be met:
- 1. The Reactor Buuding Purge Exhaust Monitors (HP-R-225 and HP-R-219 or simRar device) shall be OPERABLE.
B. The flow rate for radioactive effluent streams and the Auxillary and Fuel Handling BuBdings
_.k and the Reactor Buiding, shall be rnonitored and recorded. Gaseous effluents from the - j Reactor Bulding PurDe Exhaust shaR be continuously monitored and recorded.
q l
NOTE With flow rate monitoring instrumentation out of service, flow rates from the Auxiliary and Fuel Hand!!ng Buldings may be estimated using the -
maximum design flow for the exhaust fans in operation.
C. Radioactive gaseous waste sampling and activity analysis shall be performed in accordance '
with Table 3.1-2.
D. Facility records shall be maintained of radioactive concentration, release ratio and volume of each batch of gaseous effluents released and the length of time over which release occurred. Estimates of the error associated with each reported value should be included in faculty records.
E. The release of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits calculated in accordance with this Control by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 3.1-2.
3.1.2.3 BASES Controls 3.1.2.2 A. through D. require that suitable equipment to monitor the radioactive gaseous releases are operating during any period these releases are taking place.
Control 3.1.2.2 E. is provided to ensure that the dose to a member of the public from gaseous effluents from TMI-2 wil be within the limits of Control 2.1.2.3 D and Control 2.1.2.3 E.
These monitoring requirements provide assurarre that radioactive gaseous effluents from the station are properly contro5ed and monitored over the life of the station. These monitoring requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive gaseous wastes released to the environment.
Reports on the quantities of radioactive materials released in gaseous effluents shaR be fumished to the Commission on the basis of ODCM Part IV requirements. On the basis of such report and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.
73.0 nm. l l
i j
Number Nuclear " "ad*oad~o ""d'~
Departmental Procedure 6610-PLN-4200.01 Title Revis#on fe.
Offsite Dose Calculation Manual (ODCM) 11 3.2 Radioactive Gaseous Effluent Monitoring Instrumentation Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CAUBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2.2-1 (per occupational exposure considerations and detector sensitivity in ambient radiation areas).
o 9
m O
74.0 nm.
l
1 1
Nurvib.r TMI Radiologic'al'Controis EI Depudw ntal Procedure 6610-PLN-4200.01
- m. a.n on No. )
Offsite Dose Calculation Manual (ODCM) 11 i
TABLE 3.1-1 Radioactive Liquid Waste Sampling and Analysis (4,5) i A. Liauid Releases ,
Type of Detectable Sampling Frequency ActMty Analysis Concentration (3)
Each Batch IndMdual Gamma SE-7 pct /ml (2)
H-3 1E-5 pCl/ml Quarterly Composite (1) Gross Alpha 1E 7 pCl/ml Sr-89 SE-8 pCl/mi Sr-90 SE 8 pCl/rni NOTES:
(1) A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.
(2) For cortain mbdures of gamma emitters, it may not be possible to measure radionuclides in concin&ations near this sensitMty limit when other nuclides are present in the sample in much greater concentrations.
Under these circumstances, k wil be more appropriate to calculate the concentrations of such radionudides using measured ratios wth those radionuclides which are routinely identified ard measured.
(3) The detectabaty limits for radioactMty analysis are based on the technical feasibity and on the potential significance in the erwiivnii.ent of the quantities released For some nuclides, lower detection limits may be readly achievable and when nuclides are measured below the stated limits, they should also be reported.
(4) The results of these analyses should be used as the basis for recording and reporting the quantitles of radioactive material released in liquid effluents during the sampling period in estimating releases for a period when analyses were not performed, the average of the two adjacent data points spanning this period should be used. Such estimates should be included in the effluent records and reports; however, they should be dearty identified as. estimates, and the method used to obtain these data should be described.
(5) Deviations from the sampling / analysis regime wil be noted in the report specified in'ODCM Part IV.
9 75.0 mi.
Number TMI RadidogicifContrds ggI Departmental Procedure 6610-PLN-4200.01 ns. Reseon No.
Offsite Dose Calculation Manual (ODCM) 11 TABl.E 3.1-2 Radioactive Gaseous Weste Sampling and Analysis (3)
SAMPLE SAMPLING TYPE OF DETECTABLE SAMPLE POINT TYPE FREQUENCY ACTIVITY ANALYSIS CONCENTRATION (1)(a)
Reactor Building Purge Releases Ges Each Purge H4 1E4 pCl/cc Individual Gamma Emkters IE-4 pCl/cc (2)
Unk Exhaust Vent Release Points Gas MontNy H4 IE-6 pCl/cc Individual Gamma Emitters 1E-4'pCl/cc (2)
Individual (b) ,
Particulates Weeldy Gamma Emitters 1E-10 pCl/cc (2)
MontNy Composite Sr-90 1E-11 pCl/cc MontNy Gross Alpha Compoelte Emkters 1E-11 pCl/cc Reactor Bulding Breather Particulates Semi-Annually Indv. Gamma 1E-10 pCl/cc (2)
Emitters (b)
Sr-90 1E-11 pCl/cc Gross Alpha 1E-11 pCl/cc Emitters (1) The above detectab8ty limits are based on technical feasiblity and on the potential significance in the.
environment of the quantiles released. For some nuclides, lower detection limits may be reedly achievable .
and when nudides are measured below the stated limts, they should also be reported.
(2) For certain mixtures of gamma emitters, k may be possible to rneasure radionuclides at levels near their I sensitivity limts when other nudides are present in the sample at much higher levels. Under these circumstances, it wil be more appropriate to. calculate the levels of such rad'onuclides using observed ratios in the gaseous component in the reactor coolant for those radionudidos which are measurable.
(3) Deviations from the sampling and analysis regime will be noted in the report specified in ODCM Part IV.
76.0 mw
Number d TMI Radiological Controls
- EE Departmental Procedure 6610-PLN-4200.01
- m. Ammon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 3.12 (Cont'd)
Radioac'tive Gaseous Waste Sampling and Analysis Program ,
Table Notation !
- a. The LLD is the smallest concentration of radioacthre material in a sample that Mi be detected with 95%
probability with 5% probabaty 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
- V 2.22
- Y exp (-A A C)
Where LLD is the lower limit of detection as defined above (as picoeurie per unit mass or volume).
Sbis the standard deviation of the backgrouno counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).
~
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume),
2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not erwiivniaa&J samples).
The value of Seused in the calculation of the LLD for a detection system shall be based on the !
adual observed variance of the background counting rate or of the counting rate of the blank :
samples (as appropriate) rather than on an urwerified theoreticaly predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spevhvinstry, the background shaR include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and At shal be used in the calculation. The background count rate is calculated from the background counts that are determined to be with i one FWHM (Full-Wdth-at-Half-Maximum) energy band about the energy of the gamma-ray peak used for the quanttative analysis for that radionuclide.
j l
77.0 2m.
I
Numtw TMI Radio logicid Controls glgp Departmental Procedure 6610-PLN-4200.01 Tme Asvmon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 3.1-2 (Cont'd)
Radioactive Gaseous Weste Sampling and Analysis Program Table Notation
- b. The principal gamma emitters for which the LLD specification applies exdusively are the following radionudides: Mn-54, Fe-59, CW, Co-60, Zns, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nudides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nudides which are below the LLD for the analyses shall be reported as "less than" the nudide's LLD and shall not be reported as being present at the LLD level for that nudide. The "less than" values shall not be used in the required dose calculations.
ee e
9 0
o-9 78.0 nm.
Numtw TMI Radiologicid Controls
, MgE R - Departmental Procedure 6610-PLN-4200.01 Foovision No.
True 11 Offsite Dose Calculation Manual (ODCM) i
- SECTION 4.0 Design Features 4.0 DESIGN FEATURES 4.1 SITE EXCLUSION AREA .
4.1.1 The exclusion area is shown in Figure 5-1, TMI-1 Tech. Specs.
LOW POPULATION ZONE e
4.1.2 The low population zone is shown in Figure 5-2 TMI-1 Tech. Specs.
SITE BOUNDARY FOR GASEOUS EFFLUENTS 4.1.3 The site boundary for gaseous of!Iuents shall be as defined in Section 2.1.2.2 of the TMi-1 FSAR and
- as shown in Figure 2.1-3, TMI-1 FSAR.
SITE BOUNDARY FOR UQUID EFFLUENTS 4.1.4 The she boundary for liquid effluents shall be as shown in Figure 54, TMI-1 Tech. Specs.
l 1
l l
l 79.0 nm
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" i TMt Radiologicid Controis MF Departmental Procedure 6610-PLN-4200.01 Due . hamn No.
Offsite Dose Calculation Manual (ODCM) 11 5.0 PART 11 REFERENCES 5.1 NUREG4683, ' Final Programmatic Environmental impact Statement related to decontamination and disposal of radioactive wastes restiting from March 28,1979, accident Three Mie Island Nuclear Station, Unit 2,* March 1981, and its supplements.
5.2 TMI-2 PDMS Technical Specifications, attached to Facility Ucense No. DPN-73 -
5.3 Title 10, Code of Federal Regulations, ' Energy" 5.4 " Statement of Policy Relative to the NRC Programmatic Environmental Impact Statemert on the Cleanup of Three Mae Island Unit 2," dated Apri 27,1981 5.5 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 5.6 DOE / TIC-27601, Atmospheric Science and Power Reduction
~
5.7 TMI-1 Technical Specifications, attached to Facilty Operating License No. DPR-50
- ~
5.8 PDMS-SAR O
80.0 sm.
I
l Nuclear =Departmental wweProcedure 6610 PLN-4200.01 -
- r. bh No.
,9y Offsite Dose Calculation Manual (ODCM)
-e O 9 PARTll1 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES eu.e w- g 4
e t
81.0 ,,
Number TMl Railolegicid Controls g EI Departmenta' Proedure 6610-PLN-4200.01 FWymon No.
me 11 Offsite Dose Calculation Manual (ODCM) 1.0 LIQUID EFFLUENT MONITORS 1.1 TMi-1 and TMI-2 Llauid Radiation Monitor Set Points The liquid effluent off 4ine montors are set such that the concentration (s) of radionuclides in the liquid eMuents wWI not exceed ten times the concentrations specified in 10 CFR 20 Appendix B Table 2 Col 2. Table 1.1 lists the Liquid Effluent Release Points and their parameters; Figure 1.1 provides a Liquid Release Pathway Diagram.
To meet the above limt, the alarm / trip set points for liquid effluent monitors and flow measuring ,
devices are set in accordance with the following equation:
(eq 1.1) c
- f .1 C F+f where:
C= ten times the emuent concentration of 10 CFR 20 for the site, in pCl/ml.
c= the set point, in pCl/ml, of the liquid eMuent monitor measuring the radioactivity concentration in the effluent line prior to dBution and release. The set point is inversely proportional to the maximum volumetric flow of the effluent line and propodiuria to the minimal volumetric flow of the diution stream plus the effluent stream. The alert set point value is set to ensure that advance waming occurs prior to exceeding any limits. The high alarm set point value is such that if it were exceeded, it would result in concentrations exceeding ten times the 10 CFR 20 concentrations for the unrestricted area.
f= flow set point as measured at the radiation monitor location, in volume per unit time, but in the same units as F belcrw.
F= flow rate of diution water measured prior to the release point, in volume per unit time.
The set point concentration is reduced such that concentration contributions from multiple release points would not combine to exceed ten times 10 CFR 20 concentrations. The set point corssauc6 is converted to set point scale units using appropriate radiation monitor calibration factors.
This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and, for batch releases, the Releasing Radioactive Uquid Waste procedure.
m.
k 82.0 mm
I l
1 Number -- l ggp TMI Radiologicid ~ Controls Departmental Procedure 6610-PLN-4200.01 l
Tia n vmon No.
Offsite Dose Calculation Manual (ODCM) 11 1.2 TMi Liouid Effluent Release Points and Uould Radiation Monito'r Data TMI-1 has two required liquid radiation monitors. These are RM-LS and RM-L12. These liquid release point radiation monitors and sample points are shown in Tabl.e 1.1. (The TMI outfall radiation monitor, RM-L7, is also listed for information,only.)
TMI-2 does not have any required liquid radiation monitors, but does utilize RM-L12, and RM-L7 for release of liquid waste.
1.2.1 RM-LB RM-L6 is an off-line system, monitoring radioactive batch discharges from the TMI-1 liquid radwaste system (see Figure 1.1). These batch releases are sampled and analyzed per site procedures prior to release. The release rate is based'on releasing one of two Waste Evaporator Condensate Storage Tanks (WECST) at a flow which wil add less than 10%, of ten times the 10 CFR 20 concentrations to radionudide concentrations in the unrestricted area, including conservative default values for Sr-89, Sr-90, and Fe-55.
The release flow rate used is the most restrictive of three flow rates'calctdated for each liquid batch release, per the approved plant procedure.
~
Three DBution Factors (DF)'are calculated to ultimately calculate the batch release flow rate.
These three DF's are calculated to: 1) insure each radionuclide released to the unrestricted area is less than 10 percent of ten times the 10CFR20 radionuclide concentrations, 2) ensure each liquid batch release boron concentration to the river wil not exceed 0.7 ppm, and 3),
ensure ten times the 10CFR20 concentration for Cesium-137 (1E-5 pCl/mi) wil not be exceeded based on the calculated high alarm set point and the expected response of RM-L6 to this concentration of Cs-137.
The maximum release flow rate is then calculated by dividing the most restrictive (largest)
DF Into 90 percent of the current diution flow rate of the Mechanical Draft Cooling Tower (MDCT). This conservative fkw rate is then multiplied by 0.9 for the allowable flow rate.
]
J e Calculation of 10 percent 10% of ten times the 10CFR20 concentration DF: i l
DF, = Ii (SA) + (10% of ten times the 10CFR20 concentration)
SA = Specific Activity of each identified radionuclide -
- Calculation of Boron DF:
DF, = Actual Tank Boron' Concentration + 0.7.
e Calculation of Cs-137 Limit:
DF, = High Alann Set Point + (IE-5 pCI/mi
- 1.05E8 cpm per pCl/ml) e Maximum release flow rate calculation:
Max Flow = [(MDCT flow gpm
- 0.9) + (Most Restrictive DF)]
- 0.9 83.0 m l
I
i Number TMl Radiological' Controls ggE Departmental Procedure 6610-PLN-4200.01 l
hymon No.
ne. l Offsite Dose Calculation Manual (ODCM) 11 The dilution fiow rate used is the current flow rate at the site. The minimum dilution flow rate is 5000 gprrt per the TMI-1 FSAR. This ensures this batch release wRI meet the following equation.
E(CpoQ .1 0.10, (eq1.2) ;
~
where: Cl - dEuted concentration of the i* radionuclide, X, - Ten times the concentration for that radionuclide in the unrestricted area (10 CFR 20, App. B Table 2, Col. 2). A value of 3E-3 pCl/mi for dissolved '
'and entrained noble gases shall be used.
The set points for RM-LS are set for each release based on the monitor response to each .
- radionuclide identried in the gamma scan sMe results as follows:
(1.5)* [s (pCl/cc)f(CPM /pCl/cc)) + (CPM,,,) = ALERT CPM (2.0)* [s (pCl/cc), (CPM /pCi/cc)) + (CPM,,,) = HIGH ALARM CPM
~
- where: (pCl/cc), - positively identified radionuclides (CPM /pCI/cc), -~~ RM-L6 sensitMty to radionudide 1.
. (CPMW = RM-L6 background prior to batch rplease A high alarm on RM-L6 wBl close valve WDL-V-257 and terminate any WECST releases to the environrnent.
1.2.2 RM-L12 RM-L12 is an off-line system, monitoring periodic combined releases from the industrial Waste Treatment, System / industrial Waste Fitration System (IWTS/lWFS). The input to r#TS/lWFS originates in TMI-2 sumps, (see Figures 1.1 and 1.2) and the TMI-1 Turbine Bulding sump (see Figure 1.1). The set points are based on the maximum release rate from both IWTS and IWFS simultaneously, (see Figure 1.1) a nunimum diution flow rate, and 50%
of ten times the 10CFR20 concentration for Cs-137, which is the most limiting radionudide at a concentration of 1E-5 pCl/ml. These inputs are used in equation 1.1 to determine the RM-L12 High Alarm set point for all radionudides being released. A high alarm on RM-L12 wil dose IWTS and IWFS release valves and trip release pumps to stop the release.
1.2.3 RM-L10 RM-L10 was a Nal detector submerged in the TMI-1 Turbine Bulding Sump. This detector has been removed from service.
1.2.4 RM-L7 RM-L7 is not an ODCM required liquid radiation monitor. RM-L7 is an off-line system, monitoring the TMINS outfaB to the Susquehanna River (see Figures 1.1 and 1.2). This monitor is the final radiation monitor for TMI-1 and TMI-2 normal liquid effluent releases.
84.0 mm
Number gI TMI Radiological Controls
~
Departmental Procedure 6610-PLN-4200.01 Tree 1%msson No.
Offsite Dose Calculation Manual (ODCM) 11
\
1.3 Control of Liould Releases i i
TMI liquid effluent releases are controlled to less than ten times the 10CFR20 concentrations by limiting the percentage of this limk allowable from the two TMI liquid release pointa RMM and ;
effluent sampling, limits batch releases to less than or equal to 10% for all radionuclides, and i RM-L12, and effluent sampling, limits releases from TMI-1 and TMI-2 to less than or equal to 50% for Cs-137.
These radiation rnonitor set points also include built in meter error factors to further ensure that TMI liquid effluent releases are less than ten times the 10CFR20 concentrations to the erwironment. l l
The radioactMty content of each batch of radioactive liquid waste is determined prior to release by sampling and analysis in accordance with ODCM Part i Table 3.2-1. The results of pre-release analyses are used with the calculational methods in Section 1.1, to assure that the concentration at the point of release is maintained wthin the ODCM Part I Control 2.2.1.1. I' Post-release analysis of samples composted from batch releases are i-Linied in accordanco with ODCM Part i Table 3.z-1. The results of the previous post-release analysis shal be used wth the calculational methods in the ODCM to assure that _the concentrations at the point of release were maintained wthin the ODCM Part I Control 2.2.1.1.
The radioactMty concentration of' liquids discharged from continuous release points are determined by collection and analysis of samples in accordance wth ODCM Part i Table 3.2-1. The results of the analysis are used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the ODCM Part 1 Control 2.2.1.1.
l
. l l
l i
O e
85.0 mm
Nurnber
, g I TMI Radiologicia Controls Departmental Procedure 6610-PLN-4200.01 Tree Revmon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 1.1 TMI Uquid Release Point and L) quid Radiation Monitor Data UQUID RELEASE UCKJID ' FEEASE TERMINATION RADIATION POINT DISCHARGE INTERLOCK MONITOR (Maxwnum FLO W (YES/NO)
(DETECTOR) LOCATION Volume) - RECORDER VALVES YES ,
WDLV257 281' Elevation WECST Batch RM4B TMI1 Auxiliary nelinases (Nal) Bldg (8000 gal.) FT 84 Station YES RM-L7 Decharge WDbV257 (Na!) South end of TMI-1 and M-R 1311
- TMI-1 MDCT T E 2. FT-146 YES IWTS/fWFS . !W-V73. . .
Continuous IW#16,17.18 ,
Releases RM-L12 fWFS Building ~ ~ (300,000/ FT-342/ IV/-V279, (Naf) NW Comer 80,000 gel) FT 373 IW-P29,30
- WDL-R-1311 has been flanged off as a TMI-2 liquid outfall. , i
- RMr.7 is not an ODCM required liquid radiation monitor. l b
O 86.0 mm
I Number 5
, gg E TMI Radiologicid Controis Departmental Procedure 6610-PLN4200.01 '
rs. aramon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 1.2 TMI-2 Sump Capacities l
, Total l Capacity Gallons Sump Gallons perinch )
Turbine Bulding Sump 1346 22.43 Circulating Water Purr.p House Sump 572 10.59 Contrd Building Area Sump 718 9.96 Tendon Access Galley Sump 538 9.96 Control to Service Building Sump 1346 22.43 Contaminated Drain Tank Room Sump 135 3.80 CNorinator House Sump - -
Water Trestrnent Sump ** 1615 22.43 Air intake Tunnel Normal Sump 700 -
Air intake Tunnel Emergency Sump 100000 766.00 Condensate Polisher Sump * '2617 62.31 Sludge Collection Sump ** 1106 26.33 ,
Heater Drain Sump - -
Solid Waste Staging Facity Sump 1476 24.00 Auxiliary Building Sump 10102 202.00 Decay Heat Vault Sump' 479 10.00 Building Spray Vatit Sump 479 10.00 Condensate Polisher Sump is deactivated and in PDMS condtion.
- The Water Treatment and Sludge Collection Sumps wil be deactivated for PDMS.
J 87.0 mm
\
l
__--_________________________.__--___________.______________________._____j
Figure 1.1 O Composite Radiation Monitor Sampler 1MI-1 Liquid Effluent Pathways n a ,asto erab E o ,i ne i S * - a '-
Pre. operation Amilian Powdex Solids, Graver chemicalcleaning 80' vessels -
system Bag e 4
S800 met S80 Diesel M2
- ' Powdex
__._---- , int.nn.diate gg9A SepB Suns Sump
' sundino Industrial Intermediate i ,.
g cooias Building Sump -
Turbine
,, S East ,, . Collection <
Building '
' 4 sump Sump '
Intermediate g
Building Sump West
9 i Sanita4 g
W h industrial waste Treatment 6 i Presenent """***
Tw2 WasteTMl1 Fler condensiti i andTMI-2 System 4-- Tanks ~
storage p .
~~
Tank A co-T1B S 'r Emuent Main Pumping S ;
gj 8800ndafY Stations
-+ Col ection sump /
aste Waste 4 S-Plant Evaporator Evaporator "*'
Condensatt Condensatt Neutralizer SewageTreatment '20t.
storage storage Tank Plant eiitration system Ia g%
- 2 Solids #g'
- ilter Cake Component Mechanical Drah _
Cooling ._,, Cooling Tower ,r
,, 8 Water TMI-1 TMI-1 : RIVER
881MLN-4200.01 FIGURE 1.2 Revision 11 TMi-2 Liquid Emuent Pathways CONTROL CONTROL &
BUILDING >< SERVICE SUMP. AREA SUMP TURBINE TENDON BUILDING >< ACCESS SUMP GALLERY SUMP e
v JWTS SUMP INDUSTRIAL WASTE TREATMENT SYSTEM
> RML-12 v
C RML-7 C - COMPOSITE SAMPLER 9
89.0 mm 4
i I
Number gp TMI RadiologicalControls Departmental Procedure 6610-PLN-4200.01 l
)
M8 Anson No. I i
Offshe Dose Calculation Manual (ODCM) 11 2.0 UQUID EFFLUENT DOSE ASSESSMENT 2.1 Uauid Effluents - 10 CFR 50 Apoendix 1 The dose from liquid effluents results from the consumption of fish and drinking water. The location of the nearest potable water intake is PP&L Brunner Island, Steam Electric Station located downstream of TMI. The use of the flow of the Susquehanna River as the dilution flow is justified based on the complete mixing in the river prior to the first potable water supply, adequately l demer Lded by flume tracer die studies and additional liquid effluent release studies conducted (
using actual TMI-1 tritium releases. Other pathways contribute negligibly at Three MBe Island. The .
dose contribution from all radionuclides in liquid effluents released to the unrestricted area is calculated using the following expression:
Dose j = % t) X (C) 3 X AW33X + AF,3 X -- X (eq 2.1) l I
where: .
Dose j = the cumiAative dose _ commitment to the total body or any organ, j, from the liquid effluents for the total time period, in mrem.
At = the length 'of the time period of actual releases, over which Ci and f are averaged for all 1 liquid releases, in hours. )
1 C=
i the average concentration of radionuclide, I, in undButed liquid effluent during time l period At from any liquid release, in pCl/ml.
1 NOTE For Fe-55, Sr-89, Sr-90, prior to batch releases conservative concentration values wil be used in the initial dose calculation based on similar past plant cond!tions. LLD values are not used in dose calculations.
f= undiluted liquid waste flow lin gpm. ;
FD = plant dRution water flowrate during the period of release, in opm FR = actual rfver flowrate during the period of release o,r average river flowrate for the month the release is occurring, in gpm.
DF = dilution facto' as a result of mbdng effects in the near field of the discharge structure of 0.2 (Reg. Guide 1.109, Rev.1 Table A-2,1 t# taken to be 5 based on the inverse of 0.2.
AWg and AFg = the site-re'ated ingestion dose commitment factor to the 1o19 body or any organ, j, for j each identified principle gamma and beta emitter, in mrem /hr per pCl/ml. AW is the j factor for the water pathway and AF is the factor for the fish pathway. j 90.0 mm l
uwnte TMI Radidogicil Controls
~-
gNI Departmental Procedure 6610-PLN-4200.01 Tree Rmneson No.
Offsite Dose Calculation Manual (ODCM) 11
-- Values for AWij are determined by the following equation: .
AWg = (1.14E5) x (U,,) x (DFg) (eq 2.2) where:
1.14E5 = (1.0E6 pCi/pCl) x (1.0E3 ml/kg) + (8760 hr/yr)
U, = Water consumption rate for adult is 730 kg/,yr (Reg. Guide 1.109, Rev.1).
DFg = ingestion dose conversion factor for radionudide, I, for adults total body and for " worst case
- organ, j, in mrem /pCl, from Table 2.1 (Reg. Guide 1.109)
Values for AF are determined by the following equation:
6 AFg = (1.14ES) x (U,) x (DFg ) x (BF) (eq 2.2.2) where:
1.14E5 = defined above
~
U, = adult fish consumptiok assumed to be 21 kg/yr (Reg. Guide 1.109, Rev.1).
DFg - ingestion dose converskon factor for radionudide, I, for adult total body and for " worst case" organ, j, in mrem /pCl, from Table 2.1 (Reg. Guide 1.109, Rev.1).
BFi - Bioaccumulation factor for radionuclide, I, in fish, in pCl/kg per pCl/L from Table 2.2 (Reg. Guide 1.109, Rev.1).
l l
4 91.0 mm
l Numbw TMi Radiologicil Cortrols gEI Departmental Procedure 6610 PLN-4200.01 i
Tme , Rovmon No.
Offsite Dose Calculation Manual (ODCM) 11 2.2 TMI-1 Liould Radwaste System Dose Cales Once/ Month ODCM Part I Control 2.2.1.3 and TMI-2 PDMS Tech Spec Section 6.7.4.a.6 requires that appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the monthly projected doses due to the liquid effluent releases from each unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month. The following calculational method is provded for performing this dose projection.
At least once per month, the total dose from all liquid releases for the quarter-todate wil be divided by the number of days irco the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual releases during the period for which the i projection is made. If this projected dose exceeds 0.06 mrom total body or 0.2 mrem any organ, appropriate po".lons of the Liquid Radwaste Treatment System, as defined in Section 3.1, shall be used to reduce radioactMty levels prior to release.
At the discretion of Radiological Engineering, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the_ current quarter-to-date is not believed to be representative of the dose per day projected for the next month.
em 9
92.0 mm
I Number
~-
NU"EI d 7"' "*d' ' S' ii' ~ "t'
Departmental Procedure 6610 PLN-4200.01 Tro, Revisson No.
Offsite Dose Calculation Manual (ODCM) 11 2.3 Alternative Uauld Dose Calculational Methodoloav As an attemative, models in, or based upon, those presented in Regulatory Guide 1.109 (Rev.1) may be used to make a comprehensive dose assessment. Default parameter values from Reg.
Guide 1.109 (Rev.1) and/or actual site specific data are used where applicable.
As en attemative dose calculational methodology GPU Nuclear calculates doses using SEEDS (simplified enviiviur-iual effluent dosimetry system).
The onsite and SEEDS calculational models use actualliquid release data with actual monthly Susquehanna River flow data to assess the dispersion of effluents in the river.
l l
OO m+
1 93.0 me,
Number l
TMI Radiologicid'Controis NgEI D,ui muu Procedure 6610-PLN-4200.01
- Trree Asvision No.
Offsite dom Calculation Manual (ODCM) 11 TABLE 2.1 Uquid Dose Conversion Factors .(DCF): DFg Page 1 of 3
. Ingestion Dose Factors for Adults
- l (MREM Per PCI Ingested)
~
NUCUDE BONE UVER T. BODY THYROID KIDNEY LUNG GI-LLI H' 3 NO DATA 1.55E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 9 14 2.84E-06 5.68E-07 5.68E 5.68E-07 5.68E-07 5.68E 07 5.68E-07 NA 24 1.70E46 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E 06 1.70E-06 l CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E 06 NO DATA 1.40E45 MN 56 ' NO DATA 1.15E-07 2.04E-08 NUDATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E46 1.90E46 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E45 3.91E-06 NO DATA NO DATA 2.85E 06 3.40E-05 CO 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51 E-05 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E44 9.01E 06 4.36E-06 NO DATA NO DATA NO DATA 1.88E46 N1 65 5.28E-07 6.86E-08 3.13E-08 NO DATA- NO DATA NO DATA 1.74E46 CU 64 NO DATA 8 33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E45 6.96E-06 NO DATA 1.03E45 NO DATA 9.70E 06 ZN 69 1.03E48 1.97E 08 1.37E-09 NO DATA 1.28E48 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E48 . NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E46 RB 88 NO DATA 6.05E 08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01E48 2.82E48 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E44 NO DATA 8.84E46 NO DATA NO DATA NO DATA 4.94E 05
-SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04
- SR 91 5.67E 06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 l SR 92 2.15E46 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E 05 I Y 90 9.62E49 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 94.0 me.
Number TMI Radiologicaf Controls ME Departmental Procedure 6610-PLN-4200.01 Trtle Hwisson No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 2.1 (Cont'd)
Liquid Dose Conversion Factors (DCF): DF, Page 2 of 3 Ingestion Dose Factors for Adults * -
(MREM Per PCI Ingested) ;
NUCUDE BONE LIVER T. BODY THYROlD KIDNEY LUNG GI-LLI Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E 07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y. '92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.00E49 NO DATA 1.53E-08 NO DATA 3.09E45 ZR 97 1.68E 09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E44 NB 95 6.22E-09 3.46E-09 1.86E49 N6 DATA 3.42E-09 NO DATA 2.10E45 MO 99 NO DATA 4.31 E-06 8.29E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC'99M 2.47E-10 6.98E-10 8.89E49 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC 101 2.54E-10 3.86E-10 3.59E-09 NO DATA 6.59E-09 1.87E 10 1.10E-21 RU 103 1.85E 07 NO DATA 7.97E48 NO DATA 7.06E-07 NO DATA 2.16E-05 RU 105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E 06 RU 106 2.75E46 NO DATA 3.48E47 NO DATA 5.31E 06 NO DATA 1.78E44 AG 110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 SB 125 1.79E46 2.00E-08 4.26E-07 1.82E49 0.0 1.38E-06 1.97E-05 TE- 125M 2.68E 06 9.71 E-07 3.59E-07 8.06E 07 1.09E-05 NO DATA 1.07E45 TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E45 TE 127 1.10E-07 3.95E48 2.38E-08 8.15E48 4.48E-07 NO DATA 8.68E 06 TE 129M 1.15E 05 4.29E46 1.82E-06 3.95E-06 4.80E45 NO DATA 5.79E 05 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E 07 NO DATA 2.37E 08 l TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 .
TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E48 NO DATA 2.79E-09 TE 132 2.52E-06 1.63E 06 1.53E 06 1.80E-06 1.57E45 NO DATA 7.71 E-05 l 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E 06 l
1 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E 05 NO DATA 1.57E-06 1 132 2.03E 07 5.43E-07 1.90E-07 1.90E45 8.65E 07 NO DATA 1.02E-07 1 133 1.42E-06 2.47E-06 7.53E-07 3.63E44 4.31E46 NO DATA 2.22E-06 1 134 1.06E-07 2.88E-07 1.03E-07 4.99E 06 4.58E-07 NO DATA 2.51E-10 95.0 mm ;
l
Numtm TMI Radiologicid ' Controls J MSSF Departmental Procedure 6610-PLN-4200.01 rm. n-on te.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 2.1 (Cont'd) bquid Dose Conversion Factors (DCF): DF g Page 3 of 3 Ingestion Dose Factors for Adults *
(MREM Per PCI ingested)
NUCUDE BONE UVER T. BODY THYROID KIDNEY LUNG GI-LU
- l. 135 4.43E-07 1.16E46 4.28E-07 7.65E 05 1.86E46 NO DATA 1.31 E-06 CS 134 6.22E45 1.48E-04 1.21E44 NO DATA 4.79E45 1.59E45 2.59E46 l CS 136 6.51E46 2.57E 05 1.85E-05 NO DATA 1.43E45 1.96E46 2.92E46 CS 137 7.97E45 1.09E 04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11 E-06 CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8,01E-08 7.91 E-09 4.65E-13 BA 139 9.7DE48 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1,72E-07 BA 140 2.03E45 2.55E48 1.33E-06 NUDATA 8.67E-09 1.46E48 4.18E-05 BA 141 4.71E48 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA 142 2.13E 08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA 140 2.50E-09 1.26E49 3.33E-10 NO DATA NO DATA - NO DATA 9.25E45 LA 142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E49 NO DATA 2.42E 05 CE 143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E47 2.04E 07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR 143 9.20E49 3.69E 09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E45 PR 144 3.01 E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA - 3.49E-05 W 187 1.03E-07 8.61 E-08 3.01E 08 NO DATA NO DATA NO DATA 2.82E-05 ,
NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E45 i
Dose factors of internal exposure are for continuous intake over a one-year period and include the dose commitment over a 50-year period; from Reg. Guide 1.109 (Rev.1). Additional dose factors for nuclides j not included in tNs table rney be obtained from NUREG-0172.
I O
96.0 m=
l l
l
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t _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _
_ jl
l l
Nurnbw i TMI RadiologicM bois 2
EI Departmental Procedure 6610-PLN-4200.01 True Rwoon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 2.2 Bioaccumulation Factors, BF, Bioaccumulation Factors to be Used in the Absence of Site-Specific Data *
(pCl/kg per pCl/Ilter)
FRESHWATER ELEMENT FISH INVERTEBRATE H 9.0E41 9.0E41 i
l C 4.6E + 03 9.1 E + 03 NA 1.0E + 02 2.0E + 02 CR 2.0E + 02 2.0E+ 03 MN 4.0E + 02 9.0E + 04 3.2E + 03 FE 1.0E + 02 -
CO 5.0E + 01 2.0E + 02 )
- NI 1.0E + 02 1.0E + 02 CU 5.0E + 01 -- 4.0E + 02 ZN 2.0E + 03 1.0E + 04 BR -- 4.2E + 02 3.3E + 02 I RB 2.0E + 03 1.0E + 03 SR . 3.0E + 01 1.0E + 02 Y 2.5E + 01 1.0E + 03 ZR 3.3E + 00 6.7E + 00 NB 3.0E + 04 1.0E+ 02 I
MO 1.0E + 01 1.0E + 01 TC 1.5E + 01 5.0E + 00 RU 1.0E + 01 3.0E + 02 RH 1.0E + 01 3.0E + 02
- SB 1.0E + 00 1.0E + 00 l TE 4.0E + 02 6.1 E + 03 I 1.5E + 01 5.0E + 00 I
l CS 2.0E + 03 1.0E + 03 BA 4.0E + 00 2.0E + 02 LA 2.5E + 01 1.0E + 03 ,
CE 1.0E + 00 1.0E + 03 PR 2.5E + 01 1.0E + 03 ND 2.5E + 01 1.0E + 03 W 1.2E + 03 1.0E + 01 NP 1.0E + 01 4.0E +02
- Bioaccumulation factor values are taken frorn Reg. Guide 1.109 (Rev.1), Table A-1].
" Sb bioaccumulation factor value is taken from EPRI NP.3840.
97.0 me. -
l i
________ __ _______________________ _ _______.__ ______________________ _______ __________ _____ ____________j
Number M Nuclear Tise TMI RadiologicifControls De,a,tmental R,ocedure 6610-PLN-4200.01 Rowston No.
Offsite Dose Calculation Manual (ODCM) 11 3.0 TMl UQUID EFFLUENT WASTE TREATMENT SYSTEMS 3.1 TMI-1 Uould Effluent Waste Treatment System 3.1.1 DescriM of the Uquid RadioactNe Waste Treatment System (see Figure 3.1).
Reactor Coolant Train
- a. Water Sources - (3) Reactor Coolant Bleed Tanks (RCBT)
- (1) Reactor Coolant Drain Tank (RCDT)
- b. Uguid Processing - Reactor Coolant Waste Evaporator (see Figure 3.2) ,
- Demineralizers prior to release
- c. Uquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks (WECST)
- d. DBution - Mechanical Draft Cooling Tower (0-38k gpm)
- Rker Flow (2E7 gpm average)
Miscellaneous Waste Train
- a. Water sources: - Auxilary BuHding Sump
- Reactor Bulding Sump
- Miscellaneous Waste Storage Tank
- Laundry Waste Storage Tank
- Neutralizer Mbdng Tank
- Neutraltzer Feed Tank
- Used Precoat Tank
- Borated Water Tank Tunnel Sump
- Heat Exchanger Vault Sump
- Tendon Access Galley Sump
- Spent Fuel Pool Room Sump
- TMi-2 Miscellaneous Waste Holdup Tank
- b. Uquid Processing - Miscellaneous Waste Evaporator, MWE (see Figure 3.2)
. - Domineralizers prior to release
- c. Uguid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks (WECST)
- d. DHution - Mechanical Draft Cooling Tower (0-38k gpm)
- River Flow (2E7 gpm average) e 98.0 mm l
Number TMl Radiological' Controls EI Departmental Procedure 6610 PLN-4200.01
. rm . % on No.
Offsite Dose Calculation Manual (ODCM) 11 3.2 Ooerability of the TMI-1 Uould Effluent Waste Treatment System 3.2.1 The TMI-1 Uguld Waste Treatment System as described in Section 11 of the TMI-1 Final Safety Analysis Report is considered to be operable when one of each of the following pieces of equipment is avalable to perform its intended function a) Miscetaneous Waste Evaporator (WDL-Z1B) or Reactor Coolant Evaporator (WDL-Z1A) b) Waste Evaporator Condensate Demineralizer (WDL-K3 A or B) c). Waste Evaporator Condensate Storage Tank (WDL-T 11 A or B)
- d) Evaporator Condensate Pumps (WDL-P 14 A or B) 3.2.2 TMI-1 Representative Sampling Prior to Discharge AN liquid releases from the TMI-1 Uquid Waste Treatment System are made through the Waste Evaporator Condensate Storage Taris. To provide thorough mbdng and a
- representative sample, the contents of the tank are recirculated using one of the Waste Evaporator Condensate TJransfer Pumps.
3.3 TMI-2 Uould Effluent Waste Treatment System 3.3.1 Description of the TMI-2 Uquid Radioactive Waste Treatment System .
The TMI-2 Uquid Radioactive Waste Treatment System has been out of service since the TMI-2 Accident in 1979. TMI-2 Uguld Radioactive Waste is processed by the TMI-1 system described in Sectin 3.1 prior to release. In addition, TMI-2 releases water from various sumps and tanks to the river (see Figures 1.1 and 1.2). These processes are govemed by plant procedures that encompass proper sampling, sample analysis, and radiation monitoring techniques.
4 4
99.0 :==
l I
wmna TMI Radiologicil ~ Controls EE Departmental Procedure 6610-PLN-4200.01 Tme w No.
l Offsite Dose. Calculation Manual (ODCM) 11 l FIGURE 3.1 TMI-1 Uquid Radweste ac i B. A. M U-V8 MIX h - MAKE up TANK ;
RC DRAIN <
BWST SUMP TANK !
RB S.F. SUMP SUMP TEND. GAL. [ y _ pony SAMPLE 4
SUMP -" I @ wm TANK AUX Bl.DG MISC. DRAIN valves SUMP - & REUEF
,r ,r,, .
ir1r + ^
9r 4 4 4 TMl-2 NI RCBT A .RCST B RCBT C ST MWHT i I I I 33 --
,6 ,$ 6 3r 3r 1r 1r 1r T W ,
CATION p PRECOAT4 DEMIN FILTER PRECOAT CATION & MAKE UP 4 FILTER -
DEMIN r TO MU-V9
( 1 OF 2) (1 OF 2) ir ir h wr I MISC WASTE RC WASTE
-DISTILLATE
. gyAp, - EVAR OtSTILLATE 9F 1r N
+ +
CWST
(-- AUX ----) ( OF 2)
(1 O F 2) STEAM
<b h MDCT EoEAte <b b HlTTMAN 2 1r ? EFFLUENT 4 3yr i
BUILDING }'
A _ WECST ,
' )
RECLAIM (1 O F 2) COND. !
DEMIN _g WATER ' DEMIN '
WATER 4_
STOR TANK (1 OF 2) 9 1r RECLAIMED WATER SYSTEM 9
100.0 m= j
Number pqqlqqy MI RadidogicB Contrdu Departmental Procedure 6610-PLN-4200.01 im. a.v on re.
Offsite Dose Calculation Manual (ODCM) 11 FIGURE 3.2 TMl-1 Liquid Weste Evaporators
_ ^;
UQo.JW E r f4 WEWE J2M M
K }: k b hs &:
i i _ l 3 e
gi ;; (^55 M , E e , ,
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[' ; ' '
,. : l'i '!: m o- .a h w
,, v
- g =9 =
%, ,7 N < >
x n I a a; , i g . . .,
k E
- uu t a gy g, e qf;3 101.0 mm
Number NWUI '"' "*di ' a' "'*
Departmental Procedure 6610-PLN-4200.01 rme Rem km No.
Offsite Dose Calculation Manual (ODCM) 11 4.0 GASEOUS EFFLUENT MONITORS 4.1 TMI-1 Noble Gas Monitor Set Points The gaseous effluent monitor set points are established for each gaseous effluent radiation monitor to assure concentrations of radionuclides in gaseous effluents do not exceed the limits set forth in ODCM Part I Control 2.2.2.1. Table 4.1 lists Gaseous Effluent Release Points and their associated parameters; Figure 4.1 provides a Gaseous Effluent Release Pattway Diagram.
l The set points are established to satisfy the more restrictive set point concentration in the following l two equations:
(eq 4.1.1) 500 > I(c)(F)(K)(Dv)
I and (eq 4.1.2) 3000 > I(c)(h + 1.1 M)(Dv)(F)
I -
where: , , ,
c=
3 set point concentration based on Xe-133 equivalent, in pCi/cc F= gaseous effluent flowrate at the monitor, in cc/sec K=
i total body dose factor, in mrem /yr per pCl/m3from Table 4.3 Dv = highest sector annual average gaseous atmospheric dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/ma. from Table 4.4 for station vent releases and Table 4.5 for all other releases, (Condenser off gas, ESF FHB, and ground releases). Maximum values presently used are 7.17E-7 sec/m3 at sector NNE for station vent, and 1.16E-6 sec/m3 at sectors N and WNW for all other releases.
Q= skin dose factor due to beta emissions from radionuclide I, in mrem /yr per pC1/m8 from Table 4.3.
3 M=
i air dose factor due to gamrna emissions from radionuclide i, in mrad /yr per pCl/m .
from Table 4.3.
1.1 = mrem skin dose per mrad air dose.
500 = annual whole body dose rate limit for unrestrk:ted areas, in mrem /yr.
, 3000 = annual skin dose rate limit for unrestricted areas, in mrem /yr.
f f The set point concentration is further reduced such that the concentration contributions from
( multiple release points would not combine to exceed ODCM Control limits.
The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors.
102.0 mm
Numtm TMI Radidogicsf Contrds (ggdgy Departmental Procedure 6610-PLN-4200.01 D Revision No.
Offsite Dose Calculation Manual (ODCM) 11 This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste.
e*
l l
I
_ i 103.0 m
Number ggp TMt Radiological Controls Departmental Procedure 6610-PLN-4200.01 rm aemon No.
Offsite Dose Calculation Manual (ODCM) 11 4.2 TMI-1 Particulate and Radiciodine Monitor Set Points Set points for monitors which detect radionuclides other than noble gases are also established to assure that concentrations of these radionuclides in gaseous efRuents do not exceed the limts of OOCM Part I Control 2.2.2.1.
Set points are established so as to satisfy the following eq'uations:
1500 > E(c)(F)(P)(Dv) (eg 4.2)
I where:
- c=3 set point concentration based cn 1-131 equivalent, in pCl/cc F= gaseous effluent flow rate at the monitor, in cc/sec P, = pathway dose parameter, in mrem /yr per pCl/m3 for the inhalation pathway from Table 4.6. The dose factors are based on the actual indMdual organ and most
- restrictive age group (child) (NUREG-0133).
NOTE Appendbc A contains Pi calculational methodology.
1500 = annual dose rate limt to any organ from particulates and radioiodines and radionuclides (other than noble gases) with half lives greater than eight days in mrem /yr.
Dv = highest sector annual average gaseous dispersion factor (X/Q or D/Q) at or beyond the unrestricted area boundary from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. X/O is used for the inhalation pathway. Maximum 8
values of X/O pently used are 7.17E-7 sec/m for station vent, at sector SE, and 1.16E-5 sec/m for all other releases, at sectors N and WNW.
The set pchu concentration is further reduced such that concentration contributions from multiple release p)ints would not combine to exceed ODCM Controllimits.
The set p sint concentration is converted to set poirt scale units on each radiation monitor using approprtste calibration factors.
This selon of the ODCM is implemented by the Radiation Mcinitor Systems Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste.
9 104.0 mm
Number TMl Radiological' Controls ggEI Departmental Procedure 6610 PLN-4200.01 Tmo Revenson No.
Offsite Dose Calculation Manual (ODCM) 11 4.3 TMI-2 Gaseous Radiation Monitor Set Points TMI-2 Gaseous Radiation Monitors have their set points described in TMi Plant Procedure 1101-2.1.
Figure 4.5 provdes a gaseous effluent release pathway diagram. Table 4.2 provides TMI-2 Radiation Montor Data.
These set points are set in accordance with the Controls delineated in Part 11 of this ODCM.
9
- e e 4>
t
. l O
e.
l 1
O 105.0 mu
Number TMI Radiological Controls
~ gUgEI Depaimieiital Procedure 6610-PLN-4200.01 rine . am.on No.
Offsite Dose Calculation Manual (ODCM) 11 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation MonRor Data TMI-1 has eleven (11) required effluent gaseous radiation monitors. These are RM-A4, RM-A5, RM-A15, RM-A6, RM-A7, RM-A8, RM-A9, RM-A14, ALC-RMI-18, WHP-RIT 1, and RLM-RM-1. These gaseous release points, radiation monitors, and sample points are shown in Table 4.1. Survellance frequencies for TMI-1 out of plant monitors are specified in Table 4.1 A. SurveHlance frequencies for TMI-1 frvplant monitors are specified in Part I of the ODCM. -
4.4.1 RM44/RM-A6 Fuel Handlho and Auxpiary Buldina Exhaust RM-A4 is the particulate, radioiodine ard gaseous radiation montor for the TMI-1 Fuel Handling Bu8 ding Vent 5ation (see Figures 4.1 and 4.2). RM-A6 is the particulate,
. radioiodine, and gaseous radiation monitor for the TMI-1 Auxilary BuHding VerfJlation (see Figures 4.1 and 4.2). High alarms on RM-A4 or RM-A6 noble gas channels wil initiate shutdown of the related buBding ventiation air supply system These two radiation monitors concurrently wil satisfy requirements for the Station Vent release point in place of RM-AB.
4.4.2 RM-A8 Station Ventuation Exhaust RM-A8 is the particulate, radiciodine and gaseous radiatiori montor for the TMI-1 Station Ventilation (see Figures 4.1_and 4.2). This in plant efRuent radiation monitor also has an associated sampling panel with sampling lines located before the sample fIters. High alarm on RM-A8 noble gas low channel wil initiate shutdown of the Station Ventilation air supply systems. '(The Fuel Handling and Auxilary Bu8 ding Ventiation). This radiation monitor I satisfies requirements for the Station Vent release point in place of RM-A4 ard RM-A6.
4.4.3 RM-AS/RM-A15 Condenser Off Gas Exhaust RM-A5 is the gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). RM-A15 is the back up gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). High alarms on RM-A5 low channel or RM-A15 noble gas channels wil intiate the MAP-5 Radioiodine Processor Station. These two radiation monitors together satisfy requirements for the Condenser Off Gas release point.
4.4.4 RM-A7 Waste Gas Decay Tank Exhaust RM-A7 is the gaseous radiation monitor for the TMI-1 Waste Gas Decay tanks (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel. High alarm on RM-A7 noble gas channel wHl initiate shutdown of the Waste Gas Decay Tank release in progress. This radiation monitor satisfies requirements for batch gaseous releases to the Station Vent release point.
4.4.5 RM-A9 Reactor Buldino Purce Exhaust RM-A9 is the particulate, radiolodine and gaseous radiation monitor for the TMI-1 Reactor Bulding Purge system (see Figures 4.1 and 4.3). This in plant effluent radiation mo,nitor also has an associated sampling panel with sampling lines located before the sample fBters.
High alarm on RM-A9 noble gas low channel wil initiate shutdown of the Reactor Building Purge System. This radiation monitor satisfies requirements for the Reactor Building Purge 106.0 m
1 Nmber e
ggy TMI Radiologicil Controls Departmental Procedure 6610-PLN-4200.01 ime am on re. l Offsite Dose Calculation Manual (ODCM) 11 )
i
. System release poilt 4.4.6 RM-A14 ESF FHB VentBation System RM-A14 is the gaseous radiation monitor for the TMI-1 Emergency Safeguards Features (ESF) Fuel Handling BuBding Exhaust system (see Figures 4.1 and 4.2). This in plant efnuent radiation monitor also has an associated sampling panel with sampling lines located before the sampler fRters. High alarm on RM-A14 noble gas channel wH1 initiate shutdown of the ESF Fuel Handling Bulding Exhaust System. This radiation monitor satisfies requirements for the ESF Fuel Handling Bulding Exhaust System release point.
4.4.7 ALC-RMI-18 Chemical Oeanino Faculty (CCF) Ventiation Exhaust ALC-RMI-18 is an Victoreen particulate, radiolodine, and gaseous radiation monitor for the Chemical Cleaning bu8 ding exhaust. Presently, the radiciodine channel is not in use. This monitor is located in the Chemical Oeaning bulding on the ground floor, and has an associated sample panel. Sampling for particulate actMty is performed off of the monitor.
4.4.8 WHP-RfT-1 Waste Handlino and Packaoino FacRtv (WHPF) Exhaust ,
WHP-RIT-1 is an EberlineAMS-3 particulate radiatien monitor for the TMI WHPF. The monitor is located in the Mechanical Equipment Room in the WHPF. Sampling for particulate actMty is F Anined off of the monitor. A high alami wRI inklate shutdown of the '
ventilation air exhaust system, 4.4.9 RLM-RM-1 Respirator C' leanino and Laundry Maintenance (RLM) FacHity RLM-RM-1 is an Eberline AMS4 particulate radiation monitor for the TMl Rt.M Facity. The monitor is located in the Mechanical Equipment Room in the RLM. Sampling for particulate actMty is pwiciriied off of the montor.
J 9
107.0 m
Number ggp TMl Radiologicsl Controls Departmental Procedure 6610-PLN-4200.01 Tsue ,
Revision No.
Offsite Dose Calculation Manual (ODCM) 11 4.5 TMI-2 Gaseous Efnuent Release Points and Gaseous Radiation Monitor Data TMI-2 has three (3) regtdatory required gaseous efnuent radiation monitors. These are HP-R-219, HP-R-210A and HP-R-225. These gaseous release points, radiation monitors, and sample points are shown in Table 4.2, and various gaseous efnuent pathways are depicted in Figure 4.5.
4.5.1 HP-R-219 Station Ventiation Exhaust HP-R-219 is a Victoreen particulate and gaseous radiation monitor for the TMI-2 ventilation exhaust. This in-plant efRuent radiation montor is located.in the TMI-2 Auxilary BuBding 328 foot elevation and has an associated sample panel.
4.5.2 HP-R-219A Station Ventiation Exhaust HP-R-219A is a Victoreen particulate and gaseous radiation monitor for the TMI-2 ventBation exhaust. This in-plant efRuent radiation monitor is located in the TMI-2 Auxilary BuRding 328 foot elevabon 4.5.3 HP R-225 Reactor Buldino Purae Air Exhaust Duct 'A' HP-R-225 is a Victoreen particulate and gaseous radiation monitor for the TMI-2 Reactor Building Purge Air Exhaust System. This irmlant etnuent radiation monitor is located in the TMI-2 Auxliary Bulding 328' elevation area.
m.
O 108.0 mm
1 l
Numtw TMI Radiological'Controls SSF oepartmentai erocedure 6610 PLN-4200.01 Tme Aovmon No.
Offsite Dose Calculation Manual (ODCM) 11 4.6 Control of Gaseous Effluent Releases TMI gaseous effluent combined releases are controlled (per ODCM Part i for TMI-1 and'ODCM Part il for TMI-2) by effluent sampling and radiation monitor set points. These measures assure that releases from the various vents do not combine to produce dose rates at the site boundary excdeding the most restrictive of 500 mrem per year to the total body or 3000 mrom per year to the skin, and 1500 mrom per year to the thyroid. This is done by restricting simultaneous releases and by limiting the dose rates that may be contributed by the various vents at any time. The various vent radiation monitor set points are each based on fractions of the above limits and do not exceed the above limits when summed together. These effluent radiation monitor set points are calculated using the methodology described in equations 4.1.1, or 4.1.2 and 4.2. The actual set points are then listed in TMI-1 Operations Procedure 1101-2.1.
- . The radioe'ctive content of each batch of gaseous waste is determined prior to release by sampling and analyses in accordance with ODCM Part I for TMI-1 and ODCM Part ll for TMI-2. The results of pre <elease analyses are used with the calculational methods in Sections 4.1 and 4.2 to assure that the dose rates at the site boundary are maintained below the limits in ODCM Part I for TMI-1 and ODCM Part 11 for TMI-2.
- Post-release analyses of samples composited frord batch and continuous releases are performed in accordance with ODCM Part i fotT)41-1 and ODCM Part 11 for TMI-2. The results of the analyses are used to assure that the dose rates at the site boundary are maintained within the limits of ODCM Part I for TMI-1 and ODCM Part il for TMi-2. '
I 1
l 1
1 l
109.0 mm j l
4 l
Number j TMl Radiological Controls !
- EI ' Departmental Procedure 6610-PLN-4200.01 Tme Revie on No. i Offsite Dose Calculation Manual (ODCM) 11 )
l TABE 4.1 1 TMI-1 Gese'ous Release Point and Gaseous Rtdistion Monitor Data RELEASE GASEOUS TERMINATION RADtATION GASEOUS (F) INTERLOCK MONITOR FIELEASE FLOW (YES/NO)
(DETECTOR) LOCATION POINT RECORDER VALVES YES
- 4 E 10 Fuel Hand. AH-D 120 306' Osvason Building AH D 121 FN.A4 Auxiliary B6dg. Exhaust FR-149 AH-D 122 Auxiliary 306' Eevation Building YES FWM6 Auxiliary Bidg. Exhaust FR-150 #+E-11 YES WDG V47
- +E10 M+E-11 RMAr8/9 Bldg.- .
Starts MAP 4 Near BWST Station FR 149 Radeoiodine FIMJe Exhaust Vent & FR150 . Sampler ,
YES 322' Beveson Condenser Starts MAP-5 Somnd Roar Off Gee Radioiodine RWM5 Turt>ine Bldo. Exhaust FR1113 Sampier YES 322' Oevanon Condeneer Starts MAP 4 Second Roor Off Gas Radioiodine RMA15 Turbine Bidg. Exhaust FR1113 Sampw Weste Gas i 306' Beve6on Decay Tanks YES l FWLA7 Auxiliary B6dg. (A,B.C) FR123 WDG-V47 i YES Mi-V-1A/B/C/D Reactor WDG434/535 Build 6ng Starti MAP 4 RhW8/9 Bldg. PurDe FR909/ Radioiodine l RNMG Near BWST Exhaust FB-148 Samp6er l
331' Bevason ESF FHB ESF Fuel Outesde Handling NO Chem. _ Building Manual FIM414 Addliion Bldg. Exhaust FR 1104A/B Actone
\
l 110.D mm
Number TMI RadiologicifControls ggNy Departmental Procedure 6610-PLN-4200.01 Treo Revisson No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 4.1 (Cort'd)
TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data GASEOUS RELEASE RADIATION GASEOUS TERMINATKIN MONrTOR RELEASE NTIEROCK (DETECTOR) LOCATON PONT (YES/NO) VALVES Chemical Oeaning CCB Exhaust ALC-FEIL 18 Bldg. 304' Elevabon System NONE YES .
WHPF Mechanical WHPF Exhaust WHPF
- Ventilate WHP-RIT-1 Equipment Room System Trips RLM-Mechanical RLM Exhaust RLM-RM-1 Equipment Room System NONE TABLE 4.1A TMl-1 Out of Plant Radioactive Gaseous Monitoring instrumentatk. 'Jurveillence Frequencies CHANNEL CHANNEL CHANNEL NSTRUMErn CHECK CAUBRATON FUNCTIONAL TEST ALC-RML18 G D E O .
ALC-RML18 P W E Q WHP4UT-1 0 SA W RLM-Rui D SA W See Page 63.0 Table 1.1 for frequency notation explanation.
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111.0 m. l 1
i Number
-gp TMi Radiologicil Controls Departmental Procedure 6610-PLN-4200.01 Titie Ravinson No.
Offsite Dose Calculation Manua! (ODCM) 11 TABLE 4.2 TMI-2 Gaseous Release Point and Gaseous Radiation MonMor Data RElf.ASE GASEOUS TERMINATION RADIATION GASEOUS INTERLOCK MONITOR RELEASE (YES/NO)
(DETECTOR) LOCATION POINT VALVES 328' Elevaton Sts6on Axiliary Vent HP-R-219 Building Exhaust NONE ,
328' Elevation Axiliary Stabon Vent HP-R-219A - Building Exhaust NONE Rmeor Bldg 328'Elevabon Auxinary Purge Exhaust HP-R 225 Building Duct "A* NONE 112.0 mm l
1 1
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Number a
glgp TMI Radiologiciil' Controls Departmental Procedure 6610-PLN-4200.01 Title , Asynon No.
Offsite Dose Calculation Manual (ODCM) 11 TABt.E 4.3 Dose Factors for Noble Cases and Daughters
- Gamma Beta -
Total Body Skin Dose Gamma Air Beta Air Dose Factor (a) Factor (b) Dose Factor Dose Factor Ki y M, N, Radio- (mrem /yr per (mrem /yr per (mrad /yr per (mrad /yr per nuclide pCi/m3) pCi/m3) pCl/m3) pCl/m3)
Kr-83m 7.56E-02" - 1.93E+ 01 2.88E + 02 Kr45m 1.17E + 03 1.46E +03 1.23E + 03 1.97E +03 .
Kr-85 1.61E + 01 1.34E + 03 1.72E + 01 1.95E + 03 Kr 87 5.92E + 03 9.73E + 03 6.17E+03 1.03E + 04 Kr-88 1.47E + 04 1.37E + 03 1.52E + 04 2.93E + 03 Kr-89 1.66E + 04 ~1 701E+04 1.73E + 04 1.06E + 04 Kr-90 1.56E + 04 7.29E +03 1.63E + 04 7.83E + 03 Xe-131m 9.15E+ 01 4.76E + 02 1.56E + 02 1.11E + 03 '
Xe-133m 2.51 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 2.46E + 03 ;
Xe-137 1.42E + 03 1.22E + 04 1.51E +03 1.27E + 04 l Xe-138 8.83E + 03 4.13E + 03 9.21E+ 03 4.75E + 03 Ar-41 8.84E+ 03 2.69E + 03 9.30E + 03 3.28E + 03 ;
- Dose factors are for immersion exposure in uniform semi-infinite cloud of noble gas radionuclides that may be detected ingaseous effluents. Dose factor values are taken from Regtdatory Guide 1.109 (Rev.1), Table B-1.
- 7.56E-02 = 7.56 x 10-2, -
(a) Total body dose factor for gamma penetration depth of 5 cm into the body.
'(b) Skin dose factor at a tis' sue depth or tissue density thickness of 7 mg/cm2 ,
113.0 mm
Number gggp TMI Radiological Controls .
Departmental Procedure 6610-PLN-4200.01 Tree Revimori No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 4.4 Atmospheric Dispersion Factors for Three Mile Island e STATION VENT DISTANCE 3 ON METERS) SEASON. ANNUAL e SECTOR AVERAGE X/O ON SEC/M )
SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 1.18607 5.32E47 2.95E47 1.93E47 1.30E-07 5.52E 08 1.91E 08 5.02500 1.88E 09 1.00E 09 NNE 1.70E 07 7.17E47 3.45E 07 2.00E47 1.39EW 5.58608 1.70E-08 4.77E-09 1.98E09 9.69E 10 NE 1.12E-07 1.75E47 3.26E 07 1.86607 1.21507 5.00508 1NE48 4.67E49 1.85E09 9.93E-10 ENE 1.09E& 2.13E47 2.67507 1.53E47 1.05E& 4.31508 1.42Ea 4.42E49 1.59E-09 8.64E-10 E 2.31E 07 1.71E47 1.52E47 1.49E47 1.06507 4.63508 1.52508 5.19E49 2.48E 09 1.50E49 ESE 3.50607 2.12E47 2.50E 07 1.48E47 9.48E 08 3.98508 1.50EM 5.92500 2.92500 1.93E49
' SE 4.19E47 3.79E47 2.53E 07 1.56507 1.11507 442E.08 1.81E4 6.84E-09 3.30E-00 2.22500 SSE 2.90007 3.62E47 2.55607 1.49E47 1.11E& 5.02608 1.98E-08 6.97500 2.94E-00 1.70E49 S 1.87E07 6.47Em 2.16E47 1.30E 07 8.65E-08 4.00508 1.40E48 4.96E 09 1.99500 1.04E49 SSW 6.13EG 4.16E4B 1.56EW 1.03E-07 6AIE48 2.72608 9.74500 3.01500 1.50E00 8.23510 SW 5.76E48 1.14EW 1.70E-07 1.05EW 693508 2.51508 9.34E 00 2.72E-09 ,1.33600 8.33510 WSW 8.52E48 3.75E47 2.14EW 126E-07 7.74508 3.08E48 1.02E-08 3.28E-00 1.39600 9.60E-10 W 1.15E4;7 5.80E47 2.88E47 1.63E trf 1.18E47 523E-08 1.72E-08 5.06E49 1.98509 1.25509 WNW 1.41E47 6.28E47 3.30E47 2.19E47 1.48E 07 568508 1.95E48 6.32E 00 2.16E49 1.34E 09 NW 1.42E47 5.67E47 3.17E & 1.93607 1.30E 07 5.67508 2.06608 5.90E 00 2.7DE-09 1.45500 l
NNW 1.00EW 5.77E47 3.18507 1.80E47 127E-07 5.20508 1.77E08 4.82500 2.01E-00 1.22E-00
- STATION VENT DISTANCE e SECTOR AVERAGE D/O ON M-2) ON METERS) SEASON. ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 2.51E 09 8.72610 4.84510 2.98510 2.50E 10 BRE11 2.51E 11 4.98E-12 1.57512 7.84513 )
NNE 3.89509 1.98500 9.54610 4.99610 3.38E10 1.10510 2.89E-11 6.06E-12 2.10E-12 8.89613 NE 2.58E40 6.70E-10 9.13610 4.91E-10 2.97E-10 1.04510 2.87E-11 6.01512 1.90E-12 9.23613 ENE 2.15E.0G 5.85510 5.54510 3.06E10 2.085-10 8.30611 2.32E-11 5.41E-12 143E-12 7.64E 13 E 5.54E49 1.23609 6.17510 4.50510 3.63510 1.34510 3.66E-11 9.44E-12 3.77E-12 1.97E-12 ESE 9.17E00 2.05E 00 1.51509 8.66E-10 5.11E-10 1.82E-10 5.77511 1.72E-11 7.07612 4.07E-12 SE 122E48 228509 1A4E-09 1.02E-09 6.85E-10 2.60E-10 8.30E-11 2.34E-11 9.42612 5.51E-12 SSE . 7.50E 09 1.62600 1.08509 5.89E-10 4.49E10 1NE10 6.16E-11 1.61E11 5.67512 2.83E-12 S 3A6500 8.53610 6 27E-10 3.59E-10 2.32E-10 1.06E-10 3.05511 8.10612 2.73512 1.23E-12 SSW 1.13E49 2.94E-10 4.19E-10 2.53E10 1.56610 5.38E 11 1.68E-11 3.91E-12 1.64512 7.84513 SW 1.19E49 3.84610 4.98E-10 2.80E-10 1.70E-10 5.24E-11 1.65E-11 3.62E-12 1.40E-12 8.12E-13 WSW 1.77E00 8.31510 6.49610 3.50510 1.99610 6.73C-11 1.89611 4.58E-12 1.63E-12 9.90E 13 W 2.41E.00 129E49 6A1E-10 3.65E-10 2.96E-10 1.12E-10 3.11E-11 6.90612 2.26512 1.25E-12 WNW 3 20E-09 1.30E 09 7.73E-10 5.91E-10 3.66E-10 1.19E-10 3.43E11 8.36E-12 2.39E-12 1.29E12 NW 325E00 1.23E-09 7.39E-10 422E-10 2.77E-10 1.14E-10 7.28E 11 7.61512 2.92E-12 1.36E-12 NNW 1.98509 9.88510 5.71E-10 3.05510 2.23E-10 8.21E-11 2.41511 4.93512 1.72512 9.03513 DATA FROM 1/1/78 THROUGH 12/31/86 USED IN CALCUt.ATIONS 114.0 mer
Number gggp TMI Radiologicaf Controls Departmental Procedure 6610 PLN-4200.01 Title Revision No.
Offsne Dose Calculation Manual (ODCM) 11 TABLE 4.5 Atmospheric Dispersion Factors for Three Mile Island e GROUND RELEASE DISTANCE e SECTOR AVERAGE X/Q CN SEC/M3) ON METERS) SEASON- ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 1.16E-05 1.13606 5.94E47 3.80E47 2.38E-07 9.74EM 3.45E48 9.28E40 3.52E-00 2.05E@ ;
1 NNE 1.08Er05 1.10E-06 5.86E47 3.41E-07 2.38E47 9.55EG 3.11E48 8.94E.00 3.74E 00 134E-09 j NE 7.02E 06 9.81E-07 5.42607 3.17E-07 2.10E47 9.01E-08 3.10008 8.87E 09 3.54E 09 1.91E49 l 1.97507 7.82E48 2.64E 08 8.38E40 3.04500 1.66E-09 !
ENE 7.14E 06 9.64607 4.92E-07 2.85507 E 8.40E46 1.09606 5.48E-07 2.91E-07 1.87E47 8.40E48 2.82E48 9.85600 4.75E 00 2.67E49 ESE 6.91506 9.02607 4.40E-07 2.57E47 1.87E47 7.20E48 2.77E 08 1.12E-08 5.54E-00 3.68E-09 SE 6.70E-06 9.06E-07 4.53E 07 2.81E 07 2.03507 8.94608 3.33E48 1.28508 6.19E-00 4.18E49 SSE 7.26E 06 9.25507 4.91E47 2.87E-07 2.08E 07 9.18E48 3.72Ea 1.32E 08 5.62500 326E40 S 8.70E46 9.08E 07 3.90E47 2.41E 07 1.61E47 7.31E 08 2.57500 9.23500 3.74E49 1.95600 SSW 6.05E-06 7.01E-07 2.75E47 1 A6E 07 1.24E47 5.06Em 1A2E48 5.71E-00 2A7E-00 1.58500-SW 5.94606 5.71E47 2.86E-07 1 A1E47 ' 122E 07 4.50E-08 1.72E 08 5.12E-00 2.53500 1.59600 WSW 8.00E 08 7.02E-07 3.60507 2.15E 07 1.34E-07 5.50E-08 1A7E48 6.12E40 2.62E-09 1.83E 00 ;
W 122E 05 1.07E46 5.30E-07 3.02E-DT 2.05E47 9.31508 3.15E-06 OA8500 3.74E49 2.38600 WNW 1.16E-05 1.13606 5.98E 07 3ETE47 2.53E47 1.00E47 3.56E-08 1.18608 4.07600 2.54G00 NW 1.13E@ 1.06606 5.70E47 3.53E-07 2.40507 1.02E-07 3A2E48 1.11E-08 5.14E-09 2.78E 00 .
NNW 1.08E 05 1.04E 06 5.72E47 327E47 2.22E47 9.06E 08 320008 8 AGE-09 3.75609 2.29000 eGROUND RELEASE DISTANCF.
- SECTOR AVERAGE D/Q CN M-2) ON METERS) SEASON- ANNUAL 72405 I SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 N 2.30008 1.88E 00 8.93E-to 4.82E-10 2.70610 8.98E-11 2.53611 4.98E-12 1.57E-12 7.84513 1 NNE 2.06E-08 2.25000 1.06E 00 5.42E-10 3.38E-10 1.10E-10 2A0611 6.06E-12 2.10E-12 8.80613 l NE 1.75E-08 2.00000 1.01600 5.04E-10 2.98E-10 1.04E-10 2.88611 6.01612 1.99E-12 9.23E-13 l 8.57E11 2.33611 5 41E-12 1.63512 7.64E-13 ENE 1.68E48 1.85E40 8.85610 4 28E-10 2.85E-10 )
E 2.88E48 2.99509 1.30E-00 6.34510 3.67 S 10 1.35E 10 3.88E-11 9 42E-12 3.77512 1.97E-12
]
ESE 3.59E 08 3.80600 1.77500 8.79610 5.15E-10 1.83E 10 5.78E-11 1.71511 7.06E-12 4.06E-12 1 SE 4.12E-08 4.55E40 2.13E49 1.15E 09 7.50610 2.72E-10 8.31E-11 2.34E 11 9.42512 5.50E-12 1.61511 5 66E-12 2.83E-12 l SSE 3.12E-08 3.23E49 1.50609 8.00E-10 5.20E-10 1.88E-10 6.18E-11 S 2.65E48 2.21E49 9.07E10 4.75510 2ASE-10 1.07610 3.00E-11 8.10512 2.73E-12 1.23612 SSW 1.45E08 1.30E49 4.80610 2.82E-10 1.70610 5.71E-11 1.00E-11 3.91E-12 1.64E-12 7.84E-13 SW 1.42E48 1.10E 09 5.15610 2.82E-10 1.71610 5.24E-11 1.65E-11 3.62E-12 1.49E-12 8.12E-13 WSW 2.01E46 1.41E00 6.82E-10 3.54E-10 2.00E-10 6.76E-11 149611 4.58512 1.63E-12 9.90E-13 W 2.55E48 2.16E 09 1J00E49 4.91E-10 3.01E-10 1.12E-10 3.11E-11 6.90E-12 2.27E-12 1.25E-12 WNW 2.88E-06 2.30E 00 1.13E@ 5.93E-10 3.67E10 1.19E-10 3.43E-11 8.36E-12 2.39512 1.29E-12 NW 2.78E4B 2.15E49 1.06600 5.58E-10 3.41510 1.19E-10 3.57E11 7.61512 2.92E-12 1.36E-12 NNW 2.17E46 1.75E49 8.75510 4.24E-10 2.57510 8.55E-11 2.42611 4.93E-12 1.72E-12 9.03E-13 l l
i QATA FROM 1/1/78 THROUGH 12/31/86 USED IN CALCULATIONS 115.0 mm j i
Number Nuclear " "ad'd S' "*d' Departmental Procedure 6610-PLN-4200.01 l noe Reymon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 4.6 Dose Parameters for Radioiodines and Radioactive Particuiste in Gaseous Effluents
- CRITICAL ORGAN CRITICAL ORGAN !
NUCUDE ORGAN FACTOR Pl*" NUCUDE ORGAN FACTOR Pl* * * !
H-G" TOTAL BODY 3.04E-07 1.12E + 03 RU-103 LUNG 1.79E-04 6.62E + 05 C-14 BONE 9.70E 06 3.59E + 04 RU-105 GI-LU 2.69E45 9.95E + 04 NA-24 TOTAL BODY 4.35E-06 1.61E+ 04 RU-106 LUNG 3.87E 03 1.43E + 07 ,
l P 32 BONE 7.04E 04 2.60E + 06 AG-110M LUNG 1.48E43 5.48E + 06 CR-51 LUNG 4.59E 06 1.70E + 04 TE-125M LUNG 1.29E-04 4.77E + 05 MN-54 LUNG 4.26E 04 1.58E + 06 SB-125 LUNG 6.27E-04 2.32E + 06 MN-56 GI-LU 3.33E 05 1.23E+05 TE-127M LUNG 4.00E44 1.48E + 06 FE-55 LUNG 3.00E 05 1.11 E + 05 TE-127 GI-LU 1.52E45 5.62E + 04 FE-59 LUNG 3.43E 04 1.27E + 06 TE-129M LUNG 4.76E-04 1.76E + 06 CO-58 LUNG 2.99E-04 1.11 E + 06 TE-129 GI-LU 6.89E46 2.55E + 04 CO-60 LUNG 1.91E 03 7.07E + 06 TE-131M Gl-LU 8.32E45 3.08E + 05 NI-63 BONE 222E44 8.21 E + 05 TE-131 LUNG 5.55E 07 2.05E + 03 .
NI-65 GI-LU 2.27E-05 8.40E + 04 TE-132 LUNG 1.02E-04 3.77E + 05 CU-64 GI-LU 9.92E-06 3.67E + 04 l136 TYHROID 4.99E44 1.85E + 06 ZN-65 LUNG 2.69E-04 9.95E+ 05 l-131 THYROID 4.39E43 1.62E + 07 ZN-69 GI-LU 2.75E46 i'.02E + 04 l-132 THYROID 5.23E 05 1.94E + 05 -
BR43 TOTAL BODY' 1.28E 07 4.74E + 02 1-133 THYROID 1.04E-03 3.85E +06 BR-84 TOTAL BODY 1.48E 07 5.48E + 02 1-134 THYROID 1.37E45 5.07E + 04 BR45 TOTAL BODY 6.84E-09 2 53E+01 1-135 THYHOID 2.14E44 7.92E + 05 RB-86 UVER 5.36E-05 1.98E + 05 CS-134 UVER 2.74E-04 1.01 E + 06 RB48 UVER 1.52E-07 5.62E+ 02 CS-136 UVER . 4.62E-05 1.71 E + 05 RB-89 UVER 9.33E-08 3.45E + 02 CS-137 BONE 2.45E 04 9.07E405 SR-89 LUNG 5.89E 04 2.16E + 06 CS-138 UVER 2.27E-07 8.40E + 02 SR-90 BONE. 2.73E 02 1.01 E+ 08 BA-139 GI-LU 1.56E 05 5.77E + 04 SR-91 GI-LU 4.70E-05 1.74E + 05 BA-140 LUNG 4.71E 04 1.74E + 06 SR-92 GI-LU 6.55E 05 2.42E + 05 BA-141 LUNG 7.89E-07 2.92E + 03 Y-90 GI-LU 7.24E45 2.68E+05 BA-142 LUNG 4.44E 07 1.64E + 03 Y-91M LUNG 7.60E-07 2.81 E + 03 LA-140 GI-LU 6.10E 05 226E+05 Y-91 LUNG 7.10E-04 2.63E + 06 LA-142 GI-LU 2.05E-05 7.59E + 04 Y-92 GI-LU 6.46E45 2.39E + 05 CE-141 LUNG 1.47E44 5.44E + 05 Y-93 GI-LLI 1.05E44 3.89E + 05 CE-143 GI-LU 3.44E-05 1.27E +05 ZR-95 LUNG 6.03E 04 2.23E + 06 CE-144 LUNG 323E43 120E+07 ZR.97 GI-LU 9.49E-05 3.51 E + 05 PR 143 LUNG 1.17E-04 4.33E + 05 NB-95 LUNG 1.66E 04 6.14E + 05 PR-144 LUNG 4.23E-07 1.57E + 03 MO-99 LUNG 3.66E-05 1.35E + 05 ND-147 LUNG 8.87E 05 3.28E + 05 TC-99M GI-LU 1.30E-06 4.81 E + 03 W-187 GI-LU 2.46E-05 9.10E +04 TC-101 LUNG 1.58E-07 5.85E + 02 NP-239 GI-UJ 1.73E 05 6.40E + 04 The hsted dose parame:ers are for radionuc! ides, other than noble gases that may be detected in gaseous effluents. PI factors include all nonatmospheric pathway transport parameters, the receptor's usage of pathway media, and are based on the most restrictive age group (child) critical organ. Additional dose parameters for nuclides not included in this Table may be calculated using the methodology described in NUREG-0133.
Tritium dose factors indude an increase of 50% to account for the additional amount of this nuclide absorbed through the sidn.
- " mrem / year per pCl/m3.
116.0 mm
1 Number TMI Radiologk$idontrols Niaclear D.,,mo.m g,oc ao,. 6610-PLN-4200.01 g, Revision No.
Offetts Dose Calculation Manual (ODCM) 11 FIGURE 4.1 TMI-1 Gaseous Emueni Pathways J W L FIGURE 4.1 "
- M*
- jW llLT.% ***"3%.
= ==.
AUXIUARY BUILDING 'Uncm P 4 e Q
% C A P
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HANDUNG EL"=i BUILDING g m cru M P-PRE FILTER Im **"I A-ABSOLUTE HEPA C-CHARCOAL FILTER net O
vg 117.0 mm
Number TMI RadiologicaIControls EI Departrnental Procedure 6610-PLN-4200.01 Tme Revisson No.
Offsite Dose Calculation Manual (ODCM) 11 RGURE 42 TMI-1 Auxiliary and Fuel Handling Buildings Effluent Pathways
-_.u.
4
"& B-A8 ma mm a m gPAC mm 3
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118.0 me
Number TMl Radiologic 5iControls "EI Departmental Procedure 6610-PLN-4200.01 T** me.onte.
Offsite Dose Calculation Manual (ODCM) 11
~
FIGURE 4.3 TMI-1 Reactor Building Effluent Pathway
~
pug- .
- 170 m FEET REACTE Bull. DING PljRGE EXRIST me
- e e i RADIAilm MONITCRS AND
~
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A AIRE C s OlG.
119.0 ,,,
s
! l TMI Radiologdd Controls F Departmental Procedure 6610-PLN-4200.01 Title . Aewmon No.
Offsite Dose Calculation Manual (ODCM) 11 FIGURE 4.4 TMl-1 Condenser Offges Effluent Pathway CONDENSER OFF GAS STACK 3 CONDENSER OFF GAS 115 m EXHAUST FEET RADIATION MONITORS AND SAMPLING STATIONS t
e.-a W l
W w I g MAIN CONDENSER ftp l
l
( -
l O
120.0 mm l
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Number
, TMI Radiological Controls Departmental Procedure 6610 PLN-4200.01 Trtie Revisen No.
Offsite Dose Calculation Manual (ODCM) 11 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT l
5.1 Gaseous Effluents - Instantaneous Release Limits l i
5.1.1 Noble Gases l l
For noble gases, the following equations apply for total body and skin dose rate at the unrestricted area boundary:
5.1.1.1 Total Body l Dose Rate = I(K,) x (Dv) x (Q) (eg 5.1.1.1)
I where:
Dose Rateh - instantaneous total body dose rate limit, at the site boundary, in mrem /yr.
K, - total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrgm/yr per pCl/m3from Table 4.3.
Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values presently in use are 7.17E-7 sec/m3 at sector NNE for station vent, and 1.16E4 sec/m3 for all other releases, at sectors N and WNW Q; - Release rate of radionuclide, I, in pCl/sec as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, I, in pCl/cc, times the release pathway flow rate, in cc/second 4
~
l O
122.0 me i
l Number gggp TMl Radiologicsi Controls Departmental Procedure 6610-PLN-4200.01. j Tine FWvmon No. 1 Offsite Dose Calculation Manual (ODCM) 11 5.1.1.2 Skin Dose Rate, = I(y + 1.1 M) X (Dv) X (Q) (eq 5.1.1.2) i !
where:
Dose Rateg = instantaneous mrem / year skin dose rate limit, at the site boundary, in mrem /yr.
y= skin dose factor due to beta emissions for each identified noble gas 8
radionuclide, in mrem /yr per pCl/m from Table 4.3.
M, = air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCl/m8 fromTable 4.3.
1.1 = mrem skin dose per mrad air dose. Converts air dose to skin dose.
~Q=i release rate of radionuclicje, I, in pCl/sec, as determined by sampling and analysis Calculated using the concentration of noble gas radionuclide, I, in pCl/cc utimes the release pathway flow rate, in cc/second. -
Dv = highest sector annual average gaseous dispersion factor (X/Q) at or 8
beyond the unrestricted area boundary, in sec/m , from Table 4.4 for station vent releases; and Table 4.5 for al other releases (Condenser Off Gas, ESF FHB, and ground releases). Maxirnum values presently in use 3
are 7.17E-7 sec/m8 at sector NNE for station vent, and 1.15E-5 sec/m for all other releases, at sectors N and WNW.
\
123.0 mm
l Number WI Radiological Controis ggI Departrnental Procedure 6610-PLN4200.01 Tm heen No.
Offsite Dose Calculation Manual (ODCM) 11 5.1.2 lodine-131. lodine-133. Tritium and Radionuclides in Particulate Form. with Half-Uves Greater than 8 DAVE, For 1-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, the following equation applies:
Dose Rate, = I(P) (Dv) (Q) ,(eq 5.1.2)
I where:
Dose Ratep = mrem / year organ dose rate.
- P, = dose parameter for I 131,1-133 Tritium and Radionuclides in Particulate Form, with naiNia:: greatar than 8 days, for the inhalation pathway, in mrom/yr per pCl/m 8, from Table 4.6. The dese factors are based on the critical indMdual organ and most restrictive age group (chilo).
Dv = highest sector annual average gaseous dispersion factor (X/Q or D/Q) at
- a or beyond the unrestricted area boundary, in sec/m , from Table 4.4 for the statipo vent releases and Table 4.5 for all other releases. X/Q is used for the inhalation pathway. Maximum values of X/O pcasently used are 3
7.17E-7 sec/m3 for station vent, at sector NNE, and 1.16E-5 sec/m for all other releases, at sectors N and WNW.
O, = release rate of each radionuclide, I, in pCl/sec. Calculated using the concentration of each radionuclide, I, in pCl/cc, times the release pathway flow rate, in cc/second.
t l
l l
124.0 me,
l Number !
TMl RadiologicaTControls ggI Departmental Procedure 6610-PLN-4200.01 ren. Moon No.
)
Offsite Dose Calculation Manual (ODCM) 11 5.2 Gaseous Effluents - 10 CFR 50 Appendix I I
5.2.1 Noble Gases l The air dose in an unrestricted area due to noble gases released in gaseous effluents from the site is determined using the following expressiorm:
(eg 5.2.1)
Dose r = (3.17E-8) x I (M) x (Dv) x (Qi)
I and Dose p = (3.17E-8) x I (N;) x (Dv) x (Qi) (eg 5.2.2)
I where:
Dose r = mrad ge mma air dose due to gamma emissions from noble gas
- radionurJides._ .
Dose # = rr1td beta air dose due to beta emissions from noble gas radionuclides.
~
M, = air dose fa'ctor due to gamma emissions for each iderrJfied noble gas radionuclide, in mrad /yr per pCl/m ,3fr.Sm Table 4.3.
N; = air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad /yr per pCl/m a, from Table 4.3.
Dv = highest sector annual average gaseous dispersion factor, X/Q, at or 8
beyond the unrestricted area boundary, in sec/m . Values rnay be read or interpolated from Table 4.4 for releases from the station vent and Table 4.5 for all other releasas. Maximum values of X/O presently used are 7.17E-7 8
sec/m 3for station vent at sector NNE, and 1.16E-5 sec/m for all other releases at sectors N or WNW.
O, = release of noble gas radionuclide, I, in pCI, over the specified time period.
(pCl/second
- seconds).
3.17E-8 = inverse of the number of seconds in a year.
NOTE .
If the methodology in this section is used in determining dose to an individual, rather than air dose due to noble gases, substitute Ki, from Table 4.3, for MI, and (U + 1.1 Ml) for Nl.
i i
i
. i 125.0 mm
Number TMI Radiological Controis gp Departmental Procedure 6610-PLN-4200.01 rm m No.
Offsite Dose Calculation Manual (ODCM) 11 5.2.2 lodine-131. lodine-133. Tritium and Radionuclides in Particulate Form, with Half-Uves Greater than 8 Days The dose to an indMdual from l-131.1-133, Tritium and Radionuclides in Particulate Form with half-lives greater than 8 days in gaseous effluents released from the site to an unrestricted area is determined by solving the following exposiAgi.
Dose, = E(3.17E-8) x I (R) (Dv) (Q) (eq 5.2.2) i i ,
where Dose = dose to all real pathways, p, to organ, o, of an individual in age gro.up, a, '
from I-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, in mrem, during any desired time period.
R, = the dose factor for each identified radionuclide, I, pathway, p, age group, a, and organ, o, in mrem /yr per pCi/m3 for the inhalation pathway and m' -
mrom/yr per pCl/sec for.other pathways, fmm Tables 5.2 to 5.7. '
NOTE Since there is minimal or no elemental iodine released from the condenser off-gas air ejector (see NUREG4017) all lodine R values for all pathways,'exceot the inhalation pathway, are considertd to be zero when performing dose calculations for releases from the condenser offgas alt ejector. Only calculate the dose due to the inhalation pathway for condenser off-gas air ejector lodines.
NOTE Trtium, H-3, dose factor is m!am/ year per pCl/m3 for all pathways.
Dv = highest '.ccoor emual average gaseous dispersion factor (X/Q) at or beyorv'. the unrestricted area boundary, in sec/m8 , for the inhalation pathwef, and D/O, in m-2, for other pathways. Table 4.4 is used for station vent rebases and Table 4.5 for all other releases. Maximum values of X/O presently used are 7.17E-7 sec/m3 for station vent at sector NNE and 1.18E-5 se,c/ra8 for all other releases at sectors N and WNW. Maximum values of D/O in m4for station vent is 1.22E-8/m2at sector SE, and for ground releases,4.12E-8/m2 for sector SE.
Dv(H3)= In the case of H-3 only the X/Q's are used for all pathways from Table 4.4 for station vent releases and Table'4.5 for all other releases.
126.0 me,
i Number Nuclear = "aa'*8 ==
Departmental Procedure 6610-PLN 4200.01
- Revision No.
11 j Offsite Dose Calculation Manual (ODCM) l 0= release of I-131,1-133, Tritium and Rad lonuclides, I, in Particulate Form with 3
half-lives greater than 8 days, in pCl, cumulative over the specified time period (pCl/second
- seconds).
3.17E-8 = inverse of the number of seconds in a year.
- e W@
_. j O
O 127.0 mm l
l Number ,
TMI Radiological Controls N SSF Departmental Procedure 6610-PLN-4200.01 True Revision No.
Offsite Dose Calculation Manual (ODCM) 11 5.3 Gaseous Radioactive System Dose Calculations Once per Month ODCM Part I Control 2.2.2.4 and TMI-2 PDMS Tech Spec Section 6.7.4.a.6 requires that appropriate subsystem of the Gaseous Radwaste Treatment System shall be used to reduce the radioactive materials in gaseous waste prior to their discharge. When the monthly projected doses due to the gaseous effluent releases from the site would exceed:
0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ.
The following calculational method is provided for performing this dose projection.
At least once per month the gamma air dose, beta air dose and the maximum organ dose for the quarter-to4 ate will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual release during the period for which the projection is made. If these projected doses exceed any of the values listed above, appropriate portions of the TMI-1 Gaseous Waste Treatment System, as defined in Section 6.0, or appropriate portions of the TMI-2 Gaseous Effluent FRtration System as shown on Figure 4.5, shall be used to reduce radioactivity levels prior to release.
At the disicretion of Radiological 5tgineering, time periods other than the current quarter-to date may be used to project doses if the dose per day in the current quarter-to date is not believed to be representative of the dose per day projected for the next month.
l 1
l 128.0 me.
l Numbw TMl Radiologichi Controls gEI Departmental Procedure 6610-PLN-4200.01 1,s. Mn No.
Offsite Dose Calculation Manual (ODCM) 11 5.4 Altemative Dose Calculational Methodolooies for Gaseous Effluents As an alternative to the rnethods described above, the models in/or based upon, those p.Wed in Regulatory Guide 1.109 (Rev.1) may be used to make a comprehensive dose assessment. Default parameter values from Regulatory Guide 1.109 (Rev.1) and/or actual site specific data can be used where applicable. -
The onsite, on-line computerized system for tracking gaseous effluent dose uses annual average g6seous dispersion factors. As an attemative dose calculational methodology. GPU Nuclear calculates doses using an advanced class 'A' dispersion model called SEEDS (simplified
- environmental effluent dosimetry system).
This model Irccipuisies the guidelines and methodology set forth in USNRC Regulatory Guide
- 1.109, and uses actual hourfy meteorological information matched to the tirne of releases to more accurately assess the dispersion of effluents in the atmosphere. Combining this assessment of dispersion wth TMINS effluent data for each unit, postulated maximum hypothetical doses to the public are calculated.
I O
129.0 mu
Number
, g
' I TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tree Revieson No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.2.1 Pathway Does Factors, RI 1
l AGE GROUP: INFANT PATHWAY: INHALATION l
i
~~
ORGAN DOSE FACTORS; mrom/ year per pCl/m3 NUCLIDE - - - - - - - - - - - - - - - - - - - - - - - -
1
BONE T. BODY THYROlD
......_......___.._.___..__...___-_--.._._..___..-LLI LIVER KlDNEY LUNG GI l H-3 0.00E + 00 6.47E + 02 6.47E + 02 6.47E + 02 6.47E+ 02 6.47E+ 02 6.47E + 02 C-14 2.65E + 04 5.31 E + 03 5.31E + 03 5.31E + 03 5.31E+03 5.31E + 03 5.31E + 03 0.00E + 00 0.00E + 00 8.95E + 01 5.75E + 01 1.32E + 01 1.28E + 04 3.57E + 02 CR .51 ._ . .. . _ _.___ _ ___ .. ._______ _ _______ .___._______
MN-54 0.00E + 00 2.53E + 04. 4.98E + 03 0.00E+ 00 4.98E + 03 1.00E + 06 7.06E + 03 i FE-55 1.97E +04 1.17E + 04 3.33E + 03 0.00E+ 00 0.00E+ 00 8.69E + 04 1.09E + 03 I FE-59 1.36E + 04 2.35E + 04 9.48E + 03 E0.00E+00 0.00E + 00 1.02E + .06 2.48E + 04
..____. . .. . .__ _ __. ... _ ....____ _ _ _ _ _ . - - ... I CO-58 0.00E+ 00 1.22E + 03 1.82E + 03- 0.00E+00 0.00E +00 7.77E + 05 1.11E + 04 CO40 0.00E + 00 8.02E + 03 1.18E + 04 0.00E + 00 0.00E+ 00 4.51E + 06 3.19E + 04 NI63 3.39E+ 05 2.04E + 04 1.16E + 04 0.00E+ 00 0.00E + 00 2.09E +. 05 2.42E + 03
_. ____.._.__...___.m________._. . . _ _ _ _ _ _ <
ZN-65 1.93E + 04 6.26E + 04 3.11E + 04 0.00E + 00 3.2SE + 04 6.47E +05 5.14E + 04
- RB-86 0.00E + 00 1.90E + 05 8.82E + 04 0.00E+ 00 0.00E+ 00 0.00E+00 3.04E + 03 l SR-89 3 98E+ 05 0.00E+00 1.14E + ..04..___. 0.00E + 00 0.00E . .
+ 00 2.03E+ .
06 6.40E ____
+ 04 SR-90 4.09E + 07 0.00E + 00 2.59E+ 06 0.00E+ 00 0.00E+00 1.12E + 07 1.31 E + 05 Y-91 5.88E + 05 0.00E + 00 1.57E + 04 0.00E + 00 0.00E + 00 2.45E + 06 7.03E + 04 ZR-95 1.15E + 05 2.79E + 04 2.03E +04 0.00E+...00 3.11E+ 04 1.75E +...06_ ________.
2.17E + 04 NS-95 1.57E + 04 6.43E + 03 3.78E+03 0.00E + 00 4.72E + 03 4.79E + 05 1.27E + 04 l RU-103 2.02E + 03 0.00E + 00 6.79E + 02 0.00E +00 4.24E+ 03 5.52E + 05 1.61E + 04 )
RU-106 8.68E + 04 0.00E + 00 1.09E + 04 0.00E+ 00 1.07E +05 1.16E + 07 1.64E + 05 AG-110M 9.98E + 03 7.22E + 03 5.00E + 03 0.00E + 00 1.09E + 04 3.67E + 06 3.30E + 04 TE-125M 4.76E + 03 1.99E + 03 6.58E + 02 1.62E+ 03 0.00E + 00 4.47E + 05 1.29E + 04 TE-127M 1.67E + 04 6.90E +03 2.07E .
+. _03 4.87E+ 03 3.75E+04 __. .
1.31 E + 06 .
2.73E
+ 04 TE-129M 1.41E + 04 6.09E + 03 2.23E + 03 5.47E+03 3.18E + 04 1.68E + 06 6.90Et04 l-131 3.79E & O4 4.44E + 04 1.96E + 04 1.48E + 07 5.18E +04 0.00E + 00 1.06E + 03 1133 1.32E + 04 1.92E + 04 5.00E + 03 3.56E + 06 2.24E + 04 _____
0.00E + 00 2.16E + 03 CS-134 3.96E + 05 7.03E + 05 7.45E + 04 0.00E + 00 1.90E +05 7.97E + 04 1.33E + 03 J 4.83E + 04 1.35E+ 05 5.29E + 04 0.00E + 00 5.64E +04 1.18E + 04 1.43E + 03 CS-136 CS-137 5.49Et05 6.12E+ 05 4.55E + 04 0.00E + 00 1.72E +05 7.13E + 04 1.33E + 03 BA-140 5.60E + 04 5.60E + 01 2.90E + 03 0.00E + 00 1.34E + 01 1.60E + 06 3.84E + 04 CE-141 2.77E + 04 1.67E + 04 1.99E + 03 0.00E + 00 5.25E + 03 5.17E + 05 2.16E + 04 3.19E + 06 1.21 E + 06 1.76E + 05 0.00E + 00 .5.38E + 05 9.84E + 06 1.48E + 05 j CE..-144 _ ..__..._ _ _.__.._ _ ._____...____ ____ __..... .... ... . ____.
PR-143 1.40E + 04 5.24E + 03 6.99E + 02 0.00E +00 1.97E + 03 4.33E + 05 3.72E + 04 ND-147 7.94E + 03 8.13E + 03 5.00E + 02 0.00E + 00 3.15E+ 03 3.22E + 05 3.12E + 04.
l 130.0 mm ,
l i
t
Number gg I TMI Radiological' Controls Departmental Procedure 6610-PLN-4200.01 Tee Revision No.
Offstte Dose Calculation Manual (ODCM) 11 1
TABLE 5.2.2 Pathway Dose Factors, RI AGE GROUP: CHil.D PATHWAY: INHALATION NUCUDE ----- - - - - - - - - - - - - - - - - - - - - - - - - -
LUNG - GI-LLI BONE IJVER T. BODY THYR KIDNEY
_ .. .. . ....__. ....______ ... _ ___OID H-3 0.00E + 00 1.12E + 03 1.12E + 03 1.12E + 03 1.12E + 03 1.12E + 03 1.12E+ 03 C-14 3.59E + 04 6.73E + 03 6.73E + 03 6.73E + 03 6.73E + 03 6.73E + 03 6.73E + 03
+04 1.08E+ 03 l CR 51 0.00E + 00 0.00E .
+ 00 1.54E + 02 8.55E
+ 01 2.43E +01 1.70E MN-54 0.00E + 00 4.29E + 04 9.51E + 03 0.00E + 00 1.00E + 04 1.58E + 06 2.29E + 04 FE-55 4.74E +04 2.52E + 04 7.77E + 03 0.00E + 00 0.00E + 00 1.11E + 05 2.87E + 03 FE -59 2.07E + 04 3.34E + 04 1.67E _.._ .
+ 04 0.00E .. ..
+ 00 0.00E
+ 00 1.27E+ 06 7.07E+ _..____.
04 l 1
I CO-58 0.00E + 00 1.77E + 03 3.16E + 03 0.00E + 00 0.00E + 00 1.11E +06 3.44E + 04 CO-60 0.00E+00 1.31E + 04 2.26E + 04 0.00E + 00 0.00E + 00 7.07E+ 06 9.62E + 04 N143 8.21E + 05 4.63E +04 2.80E +04 0.00E +00 0.00E + 00 2.75E + 05 6.33E +03 ZN-65 4.26E + 04 1.13E + 05 7.03E + 04 0.00E + 00 7.14E + 04 9.95E+ 05 1.63E+ 04 RB-86 0.00E + 00 1.98E + 05 1.14E + 05 0.00E + 00 0.00E + 00 0.00E + 00 7.99E+ 03 SR-89 5.99E + 05 0.00E + 00 1.72E + 04 0.00E +_00 0.00E + 00 2.16E + ._....__
06 1.67E+05 ._
SR-90 1.01E + 08 0.00E + 00 6.44E+06 0.00E + 00 0.00E + 00 1.48E+07 3.43E+05 Y 91 9.14E + 05 0.00E + 00 2.44E + 04 0.00E + 00 0.00E + 00 2.63E + 06 1.84E + 05 ZR-95 1.90E + 05 ~ 4.18E + 04 3.70E+ 04 0.00E+ .00 5.96E +04 2.23E
+ 06 6.11 E + 04 NB-95 2.35E+04 ' 9.18E+03 6.55E +03 0.00E+ 00 8.62E + 03 6.14E + 05 3.70E + 04 RU 103 2.79E + 03 0.00E + 00 1.07E + 03 0.00E+ 00 7.03E + 03 6.62E+ 05 4.48E + 04 RU-106 1.36E + 05 0.00E + 00 1.69E + 04 0.00E + 00 1.84E + 05 1.43E + 07 4.29E +05 AG-110M 1.69E + 04 1.14E + 04 9.14E + 03 0.00E + 00 2.12E + 04 5.48E+06 1.00E + 05 TE-125M 6.73E + 03 2.33E + 03 9.14E + 02 1.92E + 03 0.00E + 00 4.77E-05 3.38E + 04 TE-127M 2.49E + 04 8.55E
_. . . . . _ _ _ _ _ _ . +. 03 3.02E+ . . . . .03 . .6.07E
. _ _ . +. .03. _6.36E
_ _ _ +. 04 1.48E
_ _ _ . . + 06. 7.14E ... ..+_ 0_4 TE-129M 1.92E + 04 6.85E + 03 3.04E + 03 6.33E + 03 5.03E + 04 1.76E + 06 1.82E + 05 l131 4.81E + 04 4.81 E + 04 2.73E + 04 1.62E + 07 7.88E + 04 0.00E+ 00 2.84E + 03 1 1.66E + 04 2.03E + 04 7.70E + 03 3' .85E + 06 3.38E + 04 0.00E + 00 5.48E +.... 03
_-133 .. . . . . . . . . . . _ _ _ . . . . . . ....____... . .... ..___..
CS-134 6.51E+ 05 1.01E+06 2.25E+ 05 0.00E + 00 3.30E +05 1.21E + 05 3.85E + 03 CS-136 6.51 E + 04 1.71 E + 05 1.16E + 05 0.00E + 00 9.55E+ 04 1.45E + 04 4.18E + 03 CS-137 9.07E + 05 8.2SE + 05 1.28E + 05 0.00E + 00 2.82E + 05 1.04E + 05 , 3.62E + 03
. ._._.... . . .. .. ....... __ ...._.. .... .. _.._..._ .. I l
BA-140 7.40E + 04 6.48E + 01 4.33E + 03 0.00E + 00 2.11 E + 01 1.74E + 06 1.02E + 05 CE-141 3.92E + 04 1.95E + 04 2.90E + 03 0.00E + 00 8.55E+03 5.44E + 05 5.66E+04 l l
6.77E + 06 2.12E + 06 3.61E + 05 0.00E + 00 1.17E + 06 1.20E + 07 3.89E +05 CE__-144 . . _ ____.... ..____.. . ... .... .____....__. ..___. ...__ .
PR-143 1.85E + 04 5.55E +03 9.14E + 02 0.00E + 00 3.00E + 03 4.33E+ 05 9.73E+ 04 ND-147 1.08E + 04 8.73E + 03 6.81 E + 02 0.00E + 00 4.81E + 03 3.28E + 05 8.21 E + 04
.... .. _ .. ...____...__.... ... _ ... {
I
\
131.0 222m l
l
_ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ . . _ . _ _ _ _ _ _ . _ _ . . _ _ . _ _ . _ . _ _3
Number
< ggy TMl RadiologicaTControls Departmental Procedure 6610-PLN-4200.01 Tme Asvision No.
Offsite Dose Calculation Manual (ODCM) 11 i
I TABLE 5.2.3 Pathway Dose Factors, Ri l
AGE GROUP: TEEN PATHWAY: INHALATION
__ _ ..__.. ._ _.. ._. _ _ _..... __ _ _s__.__. _ _____... __.____
ORGAN DOSE FACTORS; mrem / year per pCi/m 3 NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
LUNG Gl-LU BONE UVER T. BODY THYROID IGDNEY H-3 0.00E + 00 1.27E + 03 1.27E + 03 1.27E + 03 1.27E+ 03 1.27E + 03 1.27E + 03 C-14 2.60E + 04 4.87E + 03 4.87E + 03 4.87E + 03 4.87E + 03 4.87E + 03 4.87E + 03 CR 0.00E+00 0.00E+00 1.35E + 02 7.50E + 01 3.07E+ 01 2.10E + 04 3.00E + 03.
__ -51__. .____.....______.... _ _______ _ _____.... _ ..___________ _ _ _.
MN-54 0.00E + 00 5.11E + 04 8.40E + 03 0.00E + 00 1.27E + 04 1.98E + 06 6.68E + 04 FE-55 3.34E +04 2.38E + 04 5.54E + 03 0.00E + 00 0.00E + 00 1.24E + 05 6.39E + 03 FE-59 1.59E + 04 3.70E + 04 1.43E + 04 0.00E
+ 00 0.00E + 00 1.53E+
06 1.78E..
+ 05.
CO-58 0.00E + 00 2.07E + 03 2.78E + 03 0.00E + 00 0.00E + 00 1.34E+ 06 9.52E + 04 CO-60 0.00E + 00 1.51 E + 04 1.98E + 04 0.00E + 00 0.00E + 00 8.72E+ 06 2.59E + 05 NI-63 5.80E + 05 4.34E + 04 1.98E + 04 0.00E+ ___m..__
00 0.00E +. 00 3.07E . . _
+ 05. _1.42E
+ 04 __.
1 ZN-65 3.86E + 04 1.34E + 05 6.24E + 04 0.00E+00 8.64E + 04 1.24E + 06 4.66E+ 04 RB-86 0.00E + 00 1.90E + 05 8.40E + 04 0.00E+00 0.00E + 00 0.00E + 00 1.77E + 04 SR-89 4.34E + 05 0.00E + 00 1.2SE + 04 0.00E +00 0.00E + 00 2.42E + 06 3.71E + 05 SR-90 1.08E + 08 0.00E + 00 6.68E +06 0.00E + 00 0.00E + 00 1.65E + 07 7.65E + 05 Y-91 6.61 E + 05 0.00E + 00 1.77E + 04 0.00E + 00 0.00E + 00 2.94E+ 06 4.09E + 05 ZR-95 1.46E + 05 4.58E + 04 3.15E + 04 0.00E___.. + 00 6.74E + 04 2.69E + 06 1.49E + 05..
NS-95 1.86E + 04 1.03E + 04 5.66E4 03 0.00E + 00 1.00E + 04 7.51 E + 05 9.68E + 04 RU-103 2.10E + 03 0.00E + 00 8.96E + 02 0.00E + 00 7.43E + 03 7.83E + 05 1.09E + 05 RU-106 9.'84E + 04 0.00E +00 1.24E + 04 0.00E+ ..00 1.90E + 05 1.61 E + 07 9.60E +..05 AG-110M 1.38E + 04 1.31E + 04 7.99E + 03 0.00E+00 - 2.50E+04 6.75E +06 2.73E + 05
- TE-125M 4.88E +03 2.24E + 03 6.67E + 02 1.40E + 03 0.00E + 00 5.36E +05 7.50E+04 l TE 1.80E + 04 8.16E + 03 2.18E + 03 4.38E + 03 6.54E + ..04__.1.66E + 06 1.59E + 05 i ___-127M TE-129M 1.39E + 04 6.58E+ 03 2.25E + 03 4.58E + 03 5.19E + 04 1.9BE + 06 4.05E + 05 I-131 3.54E + 04 4.91 E + 04 2.64E + 04 1.46E + 07 8.40E + 04 0.00E + 00 6.49E + 03 1-133 1.22E + 04 2.05E + 04 6.22E + 03 2.92E + 06 3.59E +04 0.00E + 00 1.03E + 04 CS-134 5.02E + 05 1.13E + 06 5.49E405 0.00E + 00 3.75E+ 05 1.46E + 05 9.76E+ 03 CS-136 5.15E + 04 1.94E + 05 1.37E + 05 0.00E+ 00 1.10E + 05 1.78E + 04 1.09E + 04 CS 137 6.70E + 05 8.48E + 05 3.11 E +----
05.___
Of0E +00 3.04E.__
+ 05 1.21 E + 05 8.48E + 03 BA-140 5.47E + 04 6.70E+ 01 3.52E + 03 0.00E + 00 2.28E + 01 2.03E + 06 2.29E + 05 CE-141 2.84E + 04 1.90E + 04 2.17E + 03 0.00E + 00 8.88E + 03 6.14E + 05 1.26E + 05 CE
_. 144 4.89E+0fr 2.02E+06 2.62E + 05 0.00E + 00 1.21E+ 06 1.34E
+ 07 8.64E
+ ___
05 PR-143 1.34E + 04 5.31 E + 03 6.62E + 02 0.00E + 00 3.09E + 03 4.83E + 05 2.14E + 05 ND-147 7.86E+ 03 8.56E + 03 5.13E + 02 0.00E + 00 5.02E +03 3.72E + 05 1.82E + 05 l 5 l
132.0 mm
Numtw TMI RadiologicaTControls g Departmental Procedure 6610-PLN-4200.01
- m. a m on No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.2.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: INHALATION
~~~ ~~
ORGAN DOSE FACTORS; mrem / year per pCl/m3 NUCUDE - - - - - - - - - -----
LUNG GI-LLI BONE UVER 10DNEY
._____... . .-- T. BODY _-THYROID H-3 0.00E + 00 126E +03 126E+ 03 1.26E + 03 1.26E + 03 126E+03 1.26E + 03 C-14 1.82E + 04 3.41E + 03 3.41E + 03 3.41E + 03 '3.41E + 03 3.41E + 03 3.41 E+ 03 CR-51 0.00E + 00 0.00E.+. 00 1.00E + 02 5.95E + 01 2.28E
+ 01 1.44E + 04 3.32E+
03 MN-54 0.00E + 00 3.96E + 04 6.30E + 03 0.00E + 00 9.84E + 03 1.40E + 06 7.74E + 04 .
FE-55 2.46E + 04 1.70E + 04 3.94E + 03 0.00E + 00 0.00E + 00 7.21E + 04 6.03E + 03 FE-59 1.18E + 04 2.78E. + 04 1.06E + 04 0.00E .+ 00 .0.00E
+ 00 1.02E_____+ 06 1.88E + 06
}
CO-58 0.00E + 00 1.58E + 03 2.07E + 03 0.00E + 00 0.00E + 00 9.28E + 05 1.06E + 05 CO 60 0.00E + 00 1.15E + 04 1.48E +04- 0.00E + 00 0.00E + 00 5.97E + 06 2.85E+ 05 NI-63 4.32E + 05 3.14E + 04 1.45E + 04 0.00E + 00 0.00E + 00 1.78E+ 05 1.34E + 04 l
ZN-65 3.24E + 04 1.03E + 05 4.66E + 04 0.00E + 00 6.90E + 04 8.64E + 05 5.34E+04 RB-86 0.00E + 00 1.35E + 05 5.90E + 04 0.00E + 00 0.00E + 00 0.00E + 00 1.06E + 04 I SR-89 3.04E + 05 0.00E+00 ' 8.72E+03 . . - -
0.00E . . .
+ 00 0.00E .____ _ _____..
+ 00 1.40E + 06 3.50E+05 ___ ..__
. SR-90 9.92E + 07 0.00E + 00 6.10E + 06 0.00E + 00 0.00E + 00 9.60E + 06 7.22E+ 05 Y-91 4.62E + 05 0.00E + 00 1.24E + 04 0.00E + 00 0.00E + 00 1.70E + 06 3.85E + 05 ZR-95 1.07E + 053.44E + 04 2.33E + 04 ...__...___..
0.00E + 00 5.42E + 04 ._.
1.77E + 06 1.50E +05 NB-95 1.41E + 04 7.82E + 03 421E+ 03 0.00E + 00 7.74E + 03 5.05E+ 05 1.04E + 05 RU-103 1.53E + 03 0.00E + 00 6.58E + 02 0.00E + 00 5.83E + 03 5.05E+ 05 1.10E + 05 RU-106 6.91E + 04 0.00E+ 00 8.72E + 03 0.00E + 00 1.34E + 05 9.36E+ 06 9.12E + 05 AG-110M 1.08E + 04 1.00E + 04 5.94E + 03 0.00E + 00 1.97E + 04 4.63E+ 06 3.02E+05 TE-125M 3.42E + 03 1.58E + 03 4.67E + 02 1.05E+ 03 1.24E + 04 3.14E + 05 7.06E + 04 TE-127M 126E+ 04 5.77E + 03 1.57E + 03 3.29E + 03 4.58E + 04 9.00E+05 .1.50E+05 TE-129M 9.76E + 03 4.67E + 03 1.58E + 03 3.44E + 03 3.66E + 04 1.16E + 06 3.83E + 05 l131 2.52E + 04 3.58E + 04 2.05E + 04 1.19E + 07 6.13E + 04 0.00E + 00 6.28E + 03 1-133 8.64E + 03 1.48E+ 04 4.52E+
03 2.15E+06 2.58E + 04 0.00E+00 8.88E + 03 l
CS-134 3.73E + 05 8.48E + 05 7.28E + 05 0.00E + 00 2.87E +05 9.76E + 04 1.04E + 04 !
. CS-136 3.90E + 04 1.46E + 05 1.10E + 05 0.00E + 00 8.56E +04 1.20E +04 1.17E +04 CS 137 4.78E + 05 ..6.21 E. + 05 4.28E +.. 05 0.00E ....
+ 00 2.22E..+ 05 7.52E ..
+ 04 8.40E + 03 BA-140 3.90E + 04 4.90E + 01 2.57E + 03 0.00E + 00 1.67E + 01 1.27E + 06 2.18E + 05 CE-141 1.99E+ 04 1.35E + 04 1.53E + 03 0.00E + 00 6.26E + 03 3.62E + 05 120E+05 CE 3.43E + 06 1.43E + 06 1.84E + 05 0.00E + 00__8.48E + 05 7.78E + 06 8.16E + 05
__. -144 ...___.. .___...__ _ ..._... ..... .. ... _ ___ ... _ __. ___.
PR-143 9.36E + 03 3.75E+ 03 4.64E + 02 0.00E+00 2.16E + 03 2.81E + 05 2.00E +05 ND-147 5.27E + 03 6.10E + 03 3.65E + 02 0.00E + 00 3.56E + 03 2.21 E + 05 1.73E + 05 133.0' 22n
l Number TMl RadiologicifControls EE Departmental Procedure 6610-PLN-4200.01 Tage . Revissori No.
Offsite Dose Calculation Manual (ODCM) 11-TABLE 5.3.1 Pathway Dose Factors, Ri AGE GROUP: ALL PATHWAY: GROUND PLANE
...r. . . .
ORGAN DOSE FACTORS * *
- NUCUDE ----
4 T. BODY SKIN e p ...
.l l H-3 0.00E + 00 0.00E +00 l l C-14 0.00E + 00 0.00E+001 CR-51 4.65E + 06 5.50E +06 I MN-54 1.39E + 09 1.62E + 09 8
, FE45 0.00E + 00 0.00E +00 !.
FE-59 2.73E + 08 3.21E+08 l g ...
4 l CO-58 3.79E + 08 4.44E +08 l l CO-60 2.iSE +10 2.53E +10 l
' N143 3.00E + 00 0.00E +00 ;I ZN46' 7.47E + 08 -- 8.59E + 08 l RB-B6 8.97E + 06 1.03E+07 !
! SR-89 --
2.16E + 04 2.51E +04 !
l-- -l
- SR-90 0.00E + 00 0.00E+00 !
Y-91 1.07E + 06 1.21E+06 l ZR-95 2.45E + 08 2.84E +081
. ___.. l j NS-95 1.37E + 08 1.61 E +08 ' !
RU-103 1.08E + 08 1.26E+08 ! I 4.22E + 08 5.06E+08 i pRU -106 . ____.....l l
l AG-110M 3.44E + 09 4.01E+09 l l TE-125M 1.55E + 06 2.13E + 06 ! '
TE-127M 9.17E + 04 1.08E + 05 p_ .. ......]'
TE-129M 1.98E + 07 2.31 E + 07 '
l-131 1.72E + 07 2.09E + 07 l 2.45E + 06 2.98E + 06
_-133
._. ....a CS-134 6.86E + 09 8.00E +09 l CS-136 1.51 E + 08 1.71 E + 08 ' '
i CS-137 1.03E + 10 1.20E +10 ;l
- BA-140 2.06E + 07 2.36E + 07 i CE-141 1.37E + 07 1.54E + 07 l CE-144 6.96E + 07 8.05E + 07
....__.l PR-143 _ 0.00E + 00 0.00E + 00 '
8.39E W_,,,3,+,g1.0
- l. .
- m 2- mrem / year per pCi/sec. 134.0 mm l
Number TMI RadiologicaIControls I Departmental Procedure 6610-PLN-4200.01 Tme Revision No.
Offsite Dose Calculation Manual (ODCM) 11
- ' TABLE 5.4.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MILK ~ ~ ~ ~ ~ ~ ~
ORGAN DOSE FACTORS; 2 m - mrem /yearkhih NUCLIDE - - - - - - -------
BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E +00 2.38E + 03 2.38E + 03 2.38E + 03 2.38E + 03 2.38E + 03 2.38E + 03 C-14 2.34E + 09 5.00E + 08 5.00E+08 5.00E + 08 5.00E + 08 5.00E+08 5.00E + 08 CR 51 0.00E + 00 0.00E + 00 1.61 .__..
E + 05 1.05E + 05 2.30E + 04 2.05E + 05 4.70E4 06 MN-54 0.00E + 00 3.91E + 07 8.85E + 06 0.00E + 00 8.66E + 06 0.00E+ 00 1.43E + 07 e FE-55 1.35E + 08 8.74E + 07 2.34E + 07 0.00E + 00 0.00E + 00 4.27E + 07 1.11E + 07 FE-59 2.25E + 08 3.93E + 08 1.55E+08 . 0.00E+00 0.00E.__.. + 00 1.16E .___.
+ 08 1.88E + 08 CO-58 0.00E + 00 2.43E + 07 6.06E + 07 0.00E + 00 0.00E + 00 . 0.00E + 00 6.05E + 07 CO-60 0.00E + 00 8.83E + 07 2.08E + 08 0.00E + 00 0.00E + 00 0.00E + 00 2.10E +08 NI-63 3.50E + 10 2.16E + 09 1.21E + 09 0.00E + 00 0.00E + 00 0.00E + 00 1.08E + 08
, ZN-65 5.56E + 09 1.91E + 10 8.79E +09 0.00E+ 00 9.24E + 09 0.00E+ 00 1.61E + 10 RB-86 0.00E + 00 2.23E + 10 1.10E + 10 0.00E + 00 0.00E + 00 0.00E + 00 5.70E + 08 SR-89 1.26E +10 0.00E + 00 3E2E+08 ~~ ~
0.00E +00 0.00E+ 00 0.00E + 00 2.59E+ 08~
~ ~1.52E ~ T9
~ ~
SR-9b 122E +ii~b.~00E+00 3.10E+l0 OE+~b~0 bE+~00 b.00E+ 00 +
Y-91 7.34E + G4 0.00E + 00 1.95E + 03 0.00E + 00 0.00E+00 . 0.00E+00 5.26E + 06 i ZR-95 6.81 E + 03 1.66E + 03 1.18E .__.
+ 03_ ...
0.00E
+ 00 1.79E+. 03 0.00E + 00-..___.____ 8.27E+ 05 NB-95 5.94E + 05 2.45E + 05 1.41E + 05 0.00E + 00 1.75E+ 05 0.00E + 00 2.07E + 08 RU-103 8.68E +03 0.00E + 00 2.90E + 03 0.00E + 00 1.81E + 04 0.00E + 00 1.06E + 05 RU-106 1.91 E + 05 0.00E + 00 2.38E + 04 0.00E+ 00 2.25E + 05 0.00E+ 00 1.45E
+ 06 AG-110M 3.86E + 08 2.82E + 08 1.87E + 08 0.00E+00 4.03E + 08 0.00E + 00 1.46E + 10 TE-125M 1.51 E + 08 5.05E + 07 2.04E + 07 5.08E + 07 0.00E + 00 0.00E + 00 7.19E + 07 TE-127M 4.22E + 08 1.40E + 08 5.10E .._ + 07 1.22E + 08 1.04E + 09 0.00E +- .00 1.70E ...._
+ 08 TE-129M 5.58E + 08 1.91E + 08 8.59E + 07 2.14E + 08 1.39E + 09 0.00E + 00 3.33E + 08 l-131 2.72E + 09 3.21E + 09 1.41E + 09 1.05E + 12 3.75E + 09 0.00E + 00 1.15E + 08 l-133
. _ _ _ . _ _3.63E
_ _ . .+. 07 . _ 5.29E
_ . . . .+ _07 _ _1.55E
. + .07 9.62E+
_ ... 09..._.____.
... _ __. 6.22E + 07 0.00E + 00_8.96E __.___...+ 06 CS-134 3.65E + 10 6.81E + 10 6.88E + 09 0.00E + 00 1.75E + 10 7.19E + 09 1.85E +08 CS-136 1.98E + 09 5.83E + 09 2.18E + 09 0.00E + 00 2.32E + 09 4.75E + 08 8.85E + 07 CS-137 5.15E + 10 6.03E+ 10 4.27E + 09 0.00E + 00 1.62E + 10 6.55E + 09 1.89E + 08 BA-140 2.42E + 08 2.42E + 05 1.25E + 07 0.00E + 00 5.75E + 04 1.49E+ 05 5.94E + 07 CE-141 4.34E + 04 2.65E + 04 3.12E + 03 0.00E+ 00 8.17E + 03 0.00E +00 1.37E + 07 2.33E + 06 9.53E +_ 05 1.30E + 05 0.00E + 00 3.85E +...__..
05 0.00E + 00 1.34E + 08 CE .144 . _ . . ...- . . _ . . . _ _ . . . . . . _ _ . . . . ..... .. ....
PR-143 1.49E + 03 5.56E + 02 7.37E + 01 0.00E + 00 2.07E + 02 0.00E + 00 7.84E + 05 ND-147 8.83E + 02 9.07E + 02 5.55E ._
+ 01 .0.00E + 00 3.50E + 02 0.00E....
+ 00 5.75E + ...
05 135.0 mm
Number g I TMl RadiologicN Controls Departmental Procedure 6610-PLN-4200.01 me % mon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.4.2 Potimey Dose Factors, Ri AGE GROUP: CHILD l'ATHWAY: GRASS COW-MILK ~
~~ ~ '
ORGAA~D'~5E F 5R'S;7.~~mN/ yea"r;Mk~
~~
O ------ -- ------ - - - - - - - - - - - - - - - - - - -
NUCUDE - - - - - - - - - - -
.....n...__..
ONE B
==
UVER T. BODY THYROID KIDNEY LUNG
.. .. ... GI-LLI H-3 0.00E + 00 1.57E + 03 1.57E + 03 1.57E + 03 1.57E+03 1.57E + 03 1.57E + 03 C-14 1.20E +09 2.39E + 08 2.39E+08, 2.39E+08 2.39E+ 08 2.39E+ 08 2.39E + 08 .
CR-51 0.00E + 00 0.00E +___ 00 ......_
1.02E + 05 5.65E + 04 1.54E + 04 1.03E + 05 5.40E + 06 MN-54 0.00E + 00 2.10E + 07 5.59E + 06 0.00E + 00 5.89E+06 0.00E + 00 1.76E + 07 FE-55 1.12E + 08 5.94E + 07 1.84E + 07 0.00E + 00 0.00E + 00 3.36E + 07 1.10E + 07 FE-59 1.20E + 08 1.95E + 08 9.70E + 07 0.00E + 00 0.00E + 00 5.65E + 07 2.03E + 08 CO-58 0.00E + 00 1.21E + 07 3.72E + 07 0.00E 4 00 0.00E + 00 0.00E+ 00 7.08E + 07 CO-60 0.00E + 00 4.32E + 07 1.27E + 08 0.00E + 00 0.00E + 00 0.00E + 00 2.39E + 08 NI63 2.97E + 10 1.59E +. 09 1.01_ E + 09 0.00E + _00 0.00E + 00 0.00E+
00 1.07E +..._08 ZN-65 4.14E + 09 1.10E + 10 6.86E + 09 0.00E+ 00 6.95E+ 09 0.00E+ 00 1.94E+ 09 RB-86 0.00E + 00 8.78E + 09 5.40E + 09 0.00E + 00 0.00E + 00 0.00E + 00 5.65E + 08 SR-89 '6.63E .____
+ 09....
0.00E + 00 h89E +08 0.00E + 00 0.00E+ 00 0.00E+00 2.57E + ._.
08 SR-90 1.12E + 11 0.00E 4 00 2.84E + 10 0.00E + 00 0.00E+ 00 0.00E + 00 1.51E + 09 Y-91 3.91 E + 04 0.00E + 00 1.05E +03 0.00E + 00 0.00E + 00 0.00E +00 5.21 E + 06 .
ZR-95 3.84E + 03 8.43E +02 7.51E + 02 0.00E + 00 1.21 E + 03 0.00E
+ 00 8.80E ...__+ 05 NB-95 3.18E + 05 1.24E + 05 8.86E + 04 0.00E + 00 1.16E + 05 0.00E+00 2.29E + 08 RU-103 4.29E + 03 0.00E + 00 1.65E + 03 0.00E + 00 1.08E + 04 0.00E +00 1.11E + 05' RU-106 9.25E + 04 0.00E+ 00 1.15E+ 04 0.00E+ 00 1.25E+05 0.00E+00 1.44E + 06 AG-110M 2.09E + 08 1.41E + 08 1.13E + 08 0.00E + 00 2.63E + 08 0.00E + 00 1.68E + 10 TE-125M 7.39E + 07 2.00E + 07 9.85E + 06 2.07E + 07 0.bOE + 00 0.00E + 00 7.13E + 07 TE-127M 2.08E +. 08 5.61E + 07 2.47E + 07 4.90E+ 07 5.94E.. + 08 0.00E+00 1.69E+ 08 TE-129M 2.72E + 08 7.59E + 07 4.22E + 07 8.78E + 07 7.98E + 08 0.00E + 00 3.31E + 08 l-131 1.31E + 09 1.31E + 09 7.46E + 08 4.34E + 11 2.16E + 09 0.00E + 00 1.17E + 08 l-133 1.72E + 07 2.13E + 07 8.05E + 06 3.95E + 09 3.55E+ 07 0.00E + 00 8.58E + 06 CS-134 2.27E + 10 3.72E + 10 7.85E409 0.00E+ 00 1.15E + 10 4.14E + 09 2.01E+ 08 CS-136 1.01E+ 09 2.79E + 03 1.80E + 09 0.00E + 00 1.49E+09 2.21E + 08 9.80E + 07 CS-137 3.23E + 10 3.09E + 10 4.56E + 09 0.00E+ 00 1.01 E + 10 3.62E + 09 1.93E + 08 BA 140 1.18E + 08 1.03E + 05 6.86E + 06 0.00E + 00 3.35E + 04 6.14E + 04 5.96E +07 CE-141 2.19E + 04 1.09E + 04 1.62E + 03 0.00E + 00 4.79E + 03 0.00E + 00 1.36E + 07 CE-144 1.63E + 06 5.09E + 05 8.67E + 04 0.00E + 00
~ 2.82E+ 05 0.00E + 00 1.33E + 08 PR 143 7.18E + 02 2.16E + 02 3.56E + 01 0.00E + 00 1.17E + 02 0.00E + 00 7.75E + 05 ND-147 4.45E + 02 3.61E + 02 2.79E + 01 0.00E + 00 1.98E + 02 0.00E .... ..
+ 00 5.71E
+ 05 9
136.0 mw
Numbier gggp TMI RadiologicdCortrois Departrnental Procedure 6610-PLN-4200.01 Tm Asmon No.
(
Offstte Dose Calculation Manual (ODCM) 11 TABLE 5.4.3 l Pathway Dose Factors, Ri l
AGE GROUP: TEEN PATHWAY: GRASS-COW-Mii.K
gg-- g g-gg, j , ------- --- - - - - - - - - - -
NUCUDE - - - - - - - - - - - - - - - - - - - ---
80NE UVER T. BODY THYROID KIDNEY LUNG GILLI H.3 0.00E + 00 9.93E + 02 9.93E + 02 9.93E + 02 9.93E + 02 9.93E + 02 9.93E + 02 C.14 4.86E + 08 9.73E + 07 9.73E + 07 9.73E + 07 - 9.73E + 07 9.73E + 07 9.73E + 07 CR 51 0.00E + 00 0.00E + 00 4.99E + 04 2.77E + 04 1.09E . ...
+ 04 7.13E + 04 8.39E + 06 MN-54 0.00E + 00 1.40E +07 2.78E + 06 0.00E + 00 4.19E + 06 0.00E + 00 2.88E +07 FE-55 4.46E + 07 3.16E + 07 7.37E + 06 0.00E + 00 0.00E + 00 2.01E + 07 1.37E+ 07 FE-59 5.19E + 07 1.21 E +08 4.68E + 07 0.00E + 00 0.00E + 00 3.82E + 07 2.86E+ 08 CO-58 0.00E + 00 7.94E + 06 1.83E + 07 0.00E + 00 0.00E + 00 0.00E + 00 1.10E + 08 CO-60 0.00E + 00 2.78E +07 6.27E + 07 0.00E + 00 0.00E +00 0.00E + 00 3.62E + 08 N143 1.18E + 10 8.36E + 08 4.01 E + 08 0.00E + .00 0.00E +00 0.00E + 00 1.33E +.. 08 ZN-65 2.11 E + 09 7.32E + 09 3.42E + 09 0.00E400 4.69E+ 09 0.00E + 00 3.10E + 09 RB-86 0.00E + 00 4.73E + 09 2.22E + 09 0.00E + 00 0.00E+ 00 0.00E + 00 7.00E + 08 ~
SR-89 2.68E + 09 0.00E + 00 747E+07 0.00E + 00 0.00E+00 0.00E+ 00 3.19E+ 08 SR-90 6.62E + 10 0.00E + 00 1.63E+10 0.00E + 00 0.00E+ 00 0.00E+ 00 1.86E+ 09 Y-91 1.58E + 04 0.00E + 00 4.24E + 02 0.00E+ 00 0.00E+ 00 0.00E + 00 6.48E+ 06 1.65E + 03 5.21.... E + 02 3.58E + 02 0.00E + .00 7.65E + 02 0.00E+ 00 1.20E+ 06 ZR__-95 _. _____.. .._. _ ....____ _ __._ __ _ _______
NB-95 1.41 E + 05 7.82E + 04 4.30E + 04 0.00E +00 7.58E +04 0.00E+00 3.34E+ 08 RU-103 1.81 E + 03 0.00E+00 7.75E+02 0.00E + 00 6.39E + 03 0.00E + 00 1.51 E+ 05 RU-106 3.76E + 04 0.00E + 00 4.73E + 03 0.00E+00 7.24E+ 04 0.00E+00 1.80E+ 06 AG-110M 9.64E + 07 9.12E + 07 5.55E + 07 0.00E +00 1.74E + 08 0.00E+ 00 2.56E + 10 TE-125M 3.01 E + 07 1.08E + 07 4.02E + 06 8.40E + 06 0.00E4 00 0.00E+ 00 8.87E+ 07 TE-127M 8.45E + 07 3.00E + .07 1.00E + 07 2.01E .+_ .07 3.42E+ 08_ ... 0.00E+
00 2.11 E + 08 TE-129M 1.10E + 08 4.09E + 07 1.74E + 07 3.56E + 07 4.61E + 08 0.00E+ 00 4.14E + 08 l-131 5.38E + 0B 7.53E + 08 4.05E + 08 2.20E + 11 1.30E+09 0.00E + 00 1.49E.+ 08 l-133 7.08E + 06 1.20E + 07 3.66E + 06 1.68E + 09 2.11E+07. 0.00E+00 9.09E +06 CS-134 9.83E + 09 2.31E + 10 1.07E + 10 0.00E + 00 7.35E+ 09 2.81E + 09 2.88E+ 08 CS-136 4.49E + 08 1.77E + 09 1.19E + 09 0.00E + 00 9.63E + 08 1.52E + 08 1.42E + 08 1.34E + 10 1.78E + 10 6.21 E + 09 0.00E + 00 6.06E+ 09 2.36E+ 09 2.54E +..._ 08 -
CS .137 ... ... .._ _ __ _ ______. _ _... ... ..
BA-140 4.87E + 07 5.97E + 04 3.14E + 06 0.00E + 00 2.02E + 04 4.01E + 04 7.51 E + 07 CE-141 8.89E + 03 5.94E + 03 6.82E+ 02 0.00E+00 2.80E+03 0.00E+ 00 1.70E+07 6.59E + 05 2.73E+05 3.54E + 04 0.00E + 00 1.63E + 05 0.00E+00 1.66E + 08 CE .144 . . . . . . . ._______.. _ ..._.__ _ ... ..- _ ... ._-_.______.
PR-143 2.90E + O2 1.16E + 02 1.44E+ 01 0.00E+00 6.73E + 01 0.00E + 00 9.55E + 05 ND,147 1.81 E + 02 1.97E + 02 1.18E + 01 0.00E+ 00 1.16E + 02 0.00E + 00 7.12E + 05 I
I I
137.0 m I
- _ - _ - _ _ _ _ _ _ - _ _ _ . ___ i
Number ggy TMl Radiologic 8 Controls Departmental Procedure 6610-PLN-4200.01 Trtie Asvision No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.4.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS
.__ _ __. . ..____ _ __ . _ _ . _____...-COW-MILK __ .. _ __. ..._
NUCUDE - -- ---
BONE UVER T. BODY THYROID KlDNEY LUNG Gl
....-LLI H-3 0.00E + 00 7.62E + 02 7.62E + 02 7.62E + 02 7.62E +02 7.62E +02 7.62E + 02 C-14 2.63E + 08 5.26E + 07 5.26E + 07 5.26E + 07 5.26E + 07 5.26E+ 07 5.26E + 07 CR 51 0.00E + 00 0.00E + 00 2.85E ..+ 04 1.70E ...
+ 04 6.28E + 03 . . .
3.78E + .04 7.17E ... .__.
+ 06 MN-54 0.00E+ 00 8.40E + 06 1.60E + 06 0.00E + 00 2.50E + 06 0.00E + 00 2.57E + 07 FE-55 2.51 E + 07 1.73E + 07 4.04E + 06 0.00E + 00 0.00E + 00 9.66E + 06 9.93E + 06 FE-59 2.97E + 07 6.97E + 07 2.67E +07 0.00E + 00 0.00E + 00 1.95E + 07 2.32E + 08 CO-58 0.00E + 00 4.71 E + 06 1.05E + 07 0.00E + 00 0.00E + 00 0.00E + 00 9.54E + 07 CO-60 0.00E + 00 1.64E +07 3.61 E + 07 ' O.00E + 00 0.00E + 00 0.00E + 00 3.08E + 08 NI43 6.72E + 09 4.65E +08 2.2SE + 08 0.00E .....
+ 00 0.00E. _ _
+ 00 0.00E+00 9.71 E + 07.
ZN-65 1.37E+ 09 4.36E + 09 1.97E+09 0.00E+00 2.91 E + 09 0.00E + 00 2.74E + 09
~
RB-86 0.00E+ 00 2.59E + 09 1.21 E + 09 0.00E + 00 0.00E + 00. ' O.00E + 00 5.10E+ 08 SR-89 1.45E+ 09 0.00E + 00 4-16E + 07 0.00E + 00 0.00E + 00 0.00E+00 2.32E+08 SR-90 4.67E + 10 0.00E + 00 1.15E + 10 0.00E + 00 0.00E + 00 0.00E+00 1.35E + 09 Y-91 8.57E + 03 0.00E + 00 2.29E + 02 0.00E + 00 0.00E + 00 .0.00E + 00 4.72E + 06 ZR-95 9.41 E + O2 3.02E + 02 2.04E + 02 0.00E + 00 4.74E + 02 0.00E + 00 9.57E + 05 NB-95 8.24E + 04 4.58E + 04 2.46E + 04 0.00E + 00 4.53E + 04 0.00E + 00 2.78E + 08 RU-103 1.02E + 03 0.00E + 00 4.38E +02 0.00E + 00 3.88E + 03 0.00E + 00 1.19E + 05 RU-106 2.04E+04 ~ 0.00E+00 _..___..__.
2.58E + 03 0.00E + 00 3.93E + 04 0.00E + 00 1.32E + 06 AG-110M 5.81 E + 07 5.38E + 07 3.19E + 07 0.00E + 00 1.06E + 08 0.00E + 00 2.19E + 10 TE-125M 1.63E + 07 5.89E + 06 2.18E + 06 4.89E + 06 6.61E + 07 0.00E + 00 6.49E + 07 TE 4.57E + 07 1.63E + 07 5.57E+06 1.17E + 07 1.86E + 08 0.00E+00 .1.53E+08
.___-127M TE-129M 6.01E + 07 2.24E'+ 07 9.51E + 06 2.06E + 07 2.51 E + 08 0.00E + 00 3.02E + 08 l-131 7.96E + 08 4.23E + 08 2.42E + 08 1.39E + 11 7.25E + 08 0.00E + 00 1.12E + 08 l133 3.87E___+ __..._____...
06 6.73E. + 06 2.05E + 06 9.88E + 08 1.17E + 07 0.00E
+ 00 6.04E + 06 CS-134 5.64E+ 09 1.34E + 10 1.10E + 10 0.00E+ 00 4.34E + 09 1.44E + 09 2.35E+ 08 CS-136 2.63E + 08 1.04E + 09 7.48E + 08 0.00E+00 5.78E+08 7.92E +07 1.18E + 08 CS 137 7.37E + 09 1.01 E + 10 6.60E + 09 0.00E +.__00 3.42E + 09 1.14E + 09 1.95E +....
08 BA-140 2.89E + 07 3.38E + 04 1.76E + 06 0.00E + 00 1.15E + 04 1.94E + 04 5.54E + 07 CE 141 4.86,E + 03 3.27E + 03 3.71 E + 02 0.00E + 00 1.52E + 03 0.00E+ 00 1.25E + 07 CE-144 3.57E + 05 1.49E + 05 1.92E + 04 0.00E +00 8.85E + 04 0.00E + 00 1.21 E + 08 PR-143 1.57E + O2 6.32E + 01 7.81E + 00 0.00E + 00 3.65E+ 01 0.00E+ 00 6.90E + 05 ND 147 9.40E + 01 1.09E + 02 6.50E + 00 0.00E +__00 6.35E + 01 0.00E + 00 5.22E + 05 9
138.0 mm
Number gggy
~
TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 nu. Fwmon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.5.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK
~~~~ ~~
~~~~~ICOA IEE F EORS; m - mrem 2 / year per pCl/sec NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI J
H-3 0.00E + 00 4.86E + 03 4.86E + 03 4.86E + 03 4.86E + 03 4.86E + 03 4.86E+ 03 i C 14 2.34E + 09 5.00E + 08 5.00E + 08 5.00E + 08 5.00E+08 5.00E+08 5.00E + 08 CR-51 0.00E+ 00 0.00E + 00 1.94E ..
+ 04___... 1.26E + 04 2.76E +...03_ _. 2.46E + 04 5.64E +.__.
05 MN44 0.00E + 00 4.68E + 06 1.06E + 06 0.00E + 00 1.04E + 06 0.00E + 00 1.72E + 06 FE-55 1.76E + 06 1.14E + 06 3.03E + 05 0.00E + 00 0.00E + 00 5.55E + 05 1.44E + 05 FE 2.92E + 06 5.10E + 06 2.01 E +.._... 06 0.00E ... + 00 0.00E + 00 1.51E + .06 2.44E + 06
____-59_______. . _ ___ ... _ - . - -
CO-58 0.00E + 00 2.91 E + 06 7.26E +06 0.00E + 00 0.00E +00 0.00E + 00 7.25E + 06 CO-60 0.00E + 00 1.06E + 07 2.50E + 07 0.00E + 00 0.00E + 00 0.00E + 00 2.52E + 07 NI63 4.19E + 09 2.59E.. + 08 1.46E ______.
+ 08 0.00E ___._.
+00 0.00E + 00 0.00E+ 00_ _____..__
1.29E4 07 ZN-65 6.67E + 08 2.29E + 09 1.05E + 09 0.00E+ 00 1.11E + 09 0.00E + 00 1.93E+ 09 RB-86 0.00E + 00 2.67E + 09 1.32E + 09 0.00E + 00 0.00E+00 0.00E + 00 6.83E +07 SR49 2.65E + 10 0.00E + 00 749E+08 0.00E....+00 0.00E+00 0.00E____+ _00 5.44E+08 SR-90 2.55E + 11 0.00E + 00 6.50E + 10 0.00E + 00 0.00E + 00 0.00E + 00 3.19E + 09 Y-91 8.80E + 03 0.00E + 00 2.34E + 02 0.00E + 00 0.00E + 00 0.00E+ 00 6.31 E + 05 -
ZR-95 8.17E + 02 1.99E + 02 1.41E + 02 0.00E + 00 2.15E + 02 0.00E + 00 9.91E + 04 NB-95 7.13E + 04 2.93E + 04 1.70E + 04 0.00E + 00 2.10E + 04 0.00E + 00 2.48E+ 07 RU-103 1.04E + 03 0.00E + 00 3.48E + 02 0.00E+ 00 2.17E + 03 0.00E + 00 1.27E+ 04 RU-106 2.28E + 04 0.00E + 00 2.85E+ 03 0.00E + 00 2.70E + 04 0.00E+ 00 1.73E+ 05 AG-110M 4.63E + 07 3.38E + 07 2.24E + 07 0.00E + 00 4.84E + 07 0.00E + 00 1.75E + 09 TE-125M 1.81 E + 07 6.05E + 06 2.45E + 06 6.09E + 06 0.00E+ 00 0.00E + 00 8.62E + 06 TE-127M 5.06E + 07 1.68E+07 . _ _ . _ _ . . . _ _ .
6.12E+06 1.46E+07 1.24E + 08 0.00E + 00 2.04E + .__
07 TE-129M 6.69E + 07 2.29E + 07 1.03E + 07 2.57E + 07 1.67E + 08 0.00E + 00 3.99E + 07 l-131 3.27E + 09 3.85E+09 1.69E + 09 1.27E + 12 4.50E + 09 0.00E+ 00 1.37E + 08 l-133 4.36E + 07 6.35E + .07 1.86E + 07 1.15E + 10 7.46E +.._......___
07 0.00E_ +_____....
00 1.07E + 07 CS-134 1.09E + 11 2.04E + 11 2.06E + 10 0.00E+ 00 5.26E+ 10 2.15E + 10 5.55E + 08 ,
CS-136 5 94E + 09 1.75E + 10 6.52E + 09 0.00E+ 00 6.96E + 09 1.42E + 09 2.65E + 08 CS-137 1.54E + 11 1.81E + 11 1.28E .
+ 10 - . . .
0.00E + 00 4.85E + 10 1.96E + 10 5.65E +____
08 BA-140 2.90E + 07 2.90E + 04 1.50E + 06 0.00E+ 00 6.89E + 03 1.78E + 04 7.13E + 06 CE-141 5.21 E + 03 3.18E + 03 3.74E + 02 0.00E + 00 9.79E + 02 0.00E + 00 1.64E + 06 CE 2.79E + 05 1.14E + 05 ..1.56E +.._.. 04 0.00E. + 00 4.62E + 04 0.00E + 00 1.60E + 07
__ -144 ....___.._ . ..a _- -.__.___.._._..____
PR-143 ' 1.78E + 02 6.66E + 01 8.83E + 00 0.00E + 00 2.48E + 01 0.00E + 00 9.40E + 04 ND-147 1.06E + 02 1.09E + 02 6.66E + 00 0.00E + 00 4.19E + 01 0.00E + 00 6.89E + 04 139.0 mm
- - _ _ - - . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ .___ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ]
Number j gg I TMI RadiologicaiControls Departmental Procodure 6610-PLN-4200.01 l
l
. me Romson No. j Offsite Dose Calculation Manual (ODCM) 11 ;
l TABLE 5.5.2 Pathway Dose Factors, Ri l AGE GROUP: CHILD PATHWAY: GRASS
_ _ _ . _ _ _ _ _ _ _ _ . . . ___ ...__ _-GOAT _ _ _ . . _
. MILK ______. __
NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --
BONE UVER T. BODY THYROID IGDNEY LUNG GI-LLI H-3 0.00E+ 00 3.20E + 03 3.20E + 03 3.20E + 03 3.20E + 03 3.20E+ 03 3.20E + 03 C-14 1.20E + 09 2.39E + 08 2.30E + 08 2.39E + 08 2.39E + 08 2.39E+ 08 2.39E + 08 CR 51 0.00E + 00 0.00E + 00 1.22E + 04 6.78E + 03 1.85E + 03 1.24E +...04 6.48E+ 05 MN-54 0.00E + 00 2.52E + 06 6.71 E + 05 0.00E + 00 7.06E + 05 0.00E+00 2.11E+06 -
e FE-55 1.45E + 06 7 71E+05 2.39E + 05 0.00E + 00 0.00E+ 00 4.36E+05 .1.43E+05 FE-59 1.56E + 06 2.53E..+ 06 1.26E ...
+ 06 0.00E + 00 0.00E +00 7.34E +05 2.64E + 06 CO-58 0.00E + 00 1.46E + 06 4.46E + 06 0.00E + 00 0.00E + 00 0.00E + 00 8.49E + 06 CO40 0.00E + 00 5.18E + 06 1.53E + 07 0.00E + 00 0.00E + 00 0.00E + 00 2.87E+ 07 N163 3.56E+ _______.09 1.91 .
E+ 08 1.21 ..
E + .08 0.00E + 00 0.00E+
00 0.00E + 00 1.28E + 07 ZN-65 4.96E+ 08 1.32E + 09 8.22E + 08 0.00E+ 00 8.33E + 08 0.00E + 00 2.32E + 08 RB-86 0.00E + 00 1.05E + 09 6.47E + 08 0.00E + 00 0.00E + 00 0.00E + 00 6.77E + 07 SR-89 1.39E + 10 0.00E + 00 347E+08 0.00E+00 0.00E + 00 0.00E + 00 5.39E + 08
-SR40 2.35E + 11 0.00E'+ 00 5.95E + 10 0.00E + 00 0.00E + 00 0.00E + 00 3.16E + 09 Y-91 4.69E + 03 0.00E + 00 1.25E + 02 0.00E + 00 0.00E + 00 0.00E + 00 6.24E + 05 ZR-95 4.60E + 02 1.01 E + 02 9.00E + 01 0.00E 4...__.. 00 1.45E ..___.._____..
+ 02 0.00E + 00 1.05E ___ + 05 NB-95 3.82E+ 04 1.49E + 04 1.06E + 04 0.00E + 00 1.40E+ 04 0.00E + 00 2.75E + 07 RU-103 5.14E + 02 0.00E + 00. 1.98E + 02 0.00E + 00 1.29E+ 03 0.00E + 00 1.33E + 04 RU 106 1.11 E + 04 0.00E + 00 ... 1.38E
+ 03 ... 0.00E + 00 1.50E + 04 0.00E+00 1.73E .+. 05 AG-110M 2.51 E + 07 1.00E + 07 1.35E + 07 0.00E+ 00 3.15E + 07 0.00E + 00 2.01E + 09 TE-125M 8.86E + 06 2.40E + 06 1.18E + 06 2.49E + 06 0.00E+00 0.00E + 00 8.55E+06 TE-127M 2.50E + 07 6.72E + 06 2.96E . .
+ 06 5.97E .-+ 06 7.12E +07 0.00E + 00 2.02E + 07 TE-129M 3.26E + 07 9.10E + 06 5.06E + 06 1.05E + 07 9.56E + 07 0.00E + 00 3.97E + 07 l-131 1.57E + 09 1.57E + 09 8.95E + 08 5.21 E + 11 2.58E + 09 0.00E + 00 - 1.40E + 08 l-133 2.06E + 07 2.55E + 07 9.66E + 06 4.74E +. 09 4.25E + 07 0.00E + 00 1.03E +.... 07 CS-134 6.80E + 10 1.12E + 11 2.35E + 10 0.00E + 00 3.46E + 10 1.24E + 10 6.01E + 08 CS-136 3.04E + 09 8.36E + 09 5.41E + 09 0.00E + 00 4.45E + 09 6.64E + 0B 2.94E + 08 CS-137 9.68E + 10 9.26E + 10 1.37E + 10 0.00E+ 00 3.02E + 10 1.09E + 10 5.80E + 08 BA 140 1.41 E + 07 1.24E + 04 8.23E + 05 0.00E + 00 4.02E + 03 7.37E + 03 7.15E + 06 CE-141 2.63E + 03 1.31 E + 03 1.95E + 02 0.00E + 00 5.74E + 02 0.00E + 00 1.63E + 06 CE-144 1.95E + 05 6.11 E + 04 1.04E + 04 0.00E + 00 3.38E + 04 0.00E + 00 1.59E + 07 PR-143 8.61 E + 01 2.59E + 01 4.27E + 00 0.00E + 00 1.40E + 01 0.00E + 00 9.29E + 04 i ND-147 5.34E + 01 4.33E + 01 3.35E + 00 0.00E + 00 2.37E + 01 0.00E + 00 6.85E +.._.04 i
._______ ...__..__ _ __. ._ _ . .__ _ . . l 140.0 mm I
l i
l i
l Number jggp TMI RadiologicalControls Departmental Procedure 6610-PLN-4200.01 Title . Anteen No.
Offsite Dose Calculation Manual (ODCM) 11 l
TABLE 5.5.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILX
~ ~ ~ ~ ~~~ ~~"~
~~~~~~~ d~AE~DOSEE[ o ORS; r7- mrem / year [pCl/seI~~~ ~ ~"
- NUCUDE --- - ------ - - - - - - - - - - - - - - - - - - - - - - -
BON E UVER T. BODY THYROID. KIDNEY LUNG GI-LU H-3 0.00E + 00 2.04E + 03 2.04E + 03 2.04E + 03 2.04E + 03 2.04E + 03 2.04E+ 03 C-14 4.86E + 08 9.72E + 07 9.72E + 07 9.72E + 07 9.72E + 07 9.72E + 07 9.72E + 07 CR-51 0.00E + 00 0.00E + 00 5.99E + 03 3.33E + 03 1.31 E +. .03 8.55E + 03 1.01 E + 06 MN-54 0.00E + 00 1.68E + 06 3.34E + 05 0.00E + 00 5.02E+05 0.00E + 00 3.45E + 06 FE-55 5.79E + 05 4.11E + 05 9.58E+ 04 0.00E + 00 0.00E + 00 2.61E + 05 1.78E + 05 74 *05 1.57E + 06 &O8E+05 0.00Et,00 0.00E 00,3, ,,,4.96E1,05 3.72E + 06 9'.- . _ . , _ , , , , , , , , , , , , ,,,, ,,,,, ,, , ,,,,,, ,
CO-58 0.00E + 00 9.53E + 05 2.20E+ 06 0.00E + 00 0.00E + 00 0.00E+ 00 1.31 E + 07 CO-60 0.00E + 00 3.34E + 06 7.52E + 06 0.00E + 00 0.00E + 00 0.00E + 00 4.35E + 07 NI-63 1.42E + 09 1.00E + 08 4.81E + 07 0.00E + 00 0.00E +-00 0.00E + 00 1.60E + 07 ZN45 2.53E + 08 8.78E + 08 4.10E + 08 0.00E+ 00 5.62E + 06 0.00E + 00 3.72E +08 RB-86 0.00E+00 5.67E+08 2.67E + 08 0.00E+00 0.00E + 00 0.00E+00 8.40E + 07 SR-89 5.62E + 09 0.00E+ 00 t61E+08 0.00E + 00 0.00E + 00 0.00E+00 6.09E
+ 08 SR-90 1.39E + 11 0.00E + 00 3.43E + 10 0.00E + 00 0.00E + 00 0.00E + 00 3.90E + 09 Y-91 1.90E + 03 0.00E + 00 5.09E + 01 0.00E + 00 0.00E + 00 0.00E +00 7.78E + 05 ZR-95 1.98E + 02 6.25E + 01 4.30E + 01 0.00E + 00 9.18E + 01 0.00E +00 1.44E + 05 NB-95 ' 1.69E + 04 9.38E + 03 5.16E + 03 0.00E + 00 9.09E + 03 0.00E+00 4.01 E + 07 )
RU-103 2.17E + 02 0.00E+ 00 9.29E + 01 0.00E + 00 7.66E + 02 0.00E + 00 1.82E + 04 ;
RU 106 4.50E + 03 0.00E + 00 5.68E + 02 0.00E + 00 8.69E
+ 03 0.00E...
+ .00 2.16E + 05 I
AG-110M 1.16E + 07 1.09E + 07 6.65E+06 0.00E + 00 2.09E + 07 0.00E + 00 3.07E + 09 !
TE-125M 3.61E + 06 1.30E + 06 4.82E + 05 1.01 E + 06 0.00E + 00 0.00E + 00 1.06E + 07 l TE 1.01 E + 07 3.59E + 06 1.20E + 06 2.41 E + 06 4.11 E....____......
+ 07 0.00E+ 00 2.52E + 07 l
_ -127M . . -
TE-129M 1.32E + 07 4.90E + 06 2.09E + 06 4.26E + 06 5.53E + 07 0.00E + 00 4.96E + 07 l-131 6.45E + 08 9.03E+08 4.85E + 08 2.64E + 11 1.56E + 09 0.00E + 00 1.79E + 08 l133 8.49E+ 06 1.44E + 07 4.40E + 06 2.01 E + 09 2.53E + 07 ,0.00E + 00 1.09E + 07 CS-134 2.95E + 10 6.93E + 10 3.22E + 10 0.00E + 00 2.20E + 10 8.41 E + 09 8.62E + 08 ;
CS-136 1.35E + 09 5.30E+09 3.56E + 09 0.00E + 00 2.89E + 09 4.55E + 08 4.27E + 08 i CS-137 4.02E + 10 5.34E + 10 1.86E + 10 0.00E + 00 1.82E + 10 7.07E + 09 7.60E + 08 BA-140 5.84E + 06 7.16E + 03 3.76E + 05 0.00E+00 2.43E + 03 4.81 E + 03 9.01 E + 06 CE-141 1.07E + 03 7.12E + 02 8.18E + 01 0.00E + 00 3.35E + 02 0.00E + 00 2.04E + 06 CE 144 7.90E+ 04 3.27E + 04 - 4.25E + 03 0.00E + 00 1.95E + 04 0.00E + 00 1.99E + 07 PR-143 3.48E + 01 1.39E + 01 1.73E + 00 0.00E + 00 8.08E + 00 0.00E + 00 1.15E + 05 ND-147 2.18E + 01 2.37E + 01 1.42E + 00 0.00E + 00 1.39E + 01 0.00E + 00 8.54E + 04 141.0 m
Number TMI Radiological Controls gUgEI Departmental Procedure 6610-PLN-4200.01 no. Fwmeon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.5.4 Pathway Dose Factors, RI l AGE GROUP: ADULT PATHWAY: GRASS-GOAT-MILX ORGAN DOSE FAC70RS; m2 . mrem / year per pCl/sec NUCUDE - - - - - - ------ ---
BONE T. BODY THYROID KIDNEY LUNG GI
. . . ....'___. UVER _ _ _ . _ ..._____..________________..__...-LLI .._
H-3 0.00E + 00 1.56E + 03 1.5GE + 03 1.56E + 03 1.56E + 03 1.56E+ 03 1.56E + 03 C-14 2.64E + 08 5.27E + 07 5.27E + 07 5.27E + 07 5.27E+07 5.27E + 07 5.27E + 07 CR-51 0.00E + 00 0.00E + 00 3.43E 4 03 2.05E + 03 7.56E + 02 4.55E + 03 8.63E + 05 MN-54 0.00E + 00 1.01E + 06 1.93E + 05 0.00E + 00 3.01 E+ 05 0.00E + 00 3.10E.+ 06 FE55 3.27E + 05 2.26E + 05 5.26E + 04 0.00E + 00 0.00E + 00 1.26E + 05 1.30E + 05 FE-59 3.87E + 05 9.09E + 05 3.48E + 05 0.00E + 00 0.00E+ ..__ _ ..
00 2.54E + 05 3.03E + 06 CO-58 0.00E + 00 5.66E + 05 1.27E + 06 0.00E + 00 0.00E + 00 0.00E + 00 1.15E + 07 CO-60 0.00E + 00 1.97E + 06 4.35E + 06 0.00E + 00 0.00E + 00 0.00E + 00 3.70E + 07 N143 8.08E + 08 .5.60E +. 07 12.71E .
+ 07 0.00E + 00 0.00E + 00 0.00E
+ 00 1.17E + 07 ZN.65 , 1.65E + 08 5.24E+08 2.37E + 0B 0.00E+ 00 3.51 E + 08 0.00E+00 3.30E+08 RB-85 0.00E + 00 3.12E + 08 1.45E + 08 0.00E + 00 0.00E+00 0.00E + 00 6.14E + 07 SR 3.05E+ 09 0.00E+00_ .__ 876E+ 07
__ -89 _ _____... _ __. _' O.00E + 00 0.00E + 00 0.00E + 00 4.89E
. .. .... ___. + 08 SR-90 9.84E + 10 0.00E + 00 2.41E + 10 0.00E+ 00 0.00E +00 0.00E + 00 2.84E + 09 Y-91 1.03E + 03 0.00E + 00 2.76E + 01 0.00E + 00 0.00E + 00 0.00E + 00 5.68E + 05 ZR-95 1.13E + 02 3.63E + 01 2.46E + 01 ' O.00E ..
+ 00 5.70E + 01 0.00E +
00 1.15E + 05.
i
_ .__ _ .._.... _ ..__._._ _ ... . 1 NB-95 9.92E + 03 5.52E+03 2.97E + 03 0.00E+ 00 5.45E+ 03 0.00E +00 3.35E +07 RU-103 1.22E + 02 0.00E + 00 5.27E + 01 0.00E+ 00 4.67E + 02 0.00E + 00 1.43E + 04 RU-106 2.45E +.. 03 0.00E + 00 3.10E + 02 0.00E + 00 4.73E....
+ 03 0.00E +00 1.59E + 05 1
AG-110M 6.99E + 06 6.47E + 06 3.84E + 06 0.00E+ 00 1.27E + 07 0.00E + 00 2.64E + 09 l TE-125M 1.96E + 06 7.09E + 05 2.62E + 05 5.89E+ 05 7.96E + 06 0.00E + 00 7.81 E+ 06 TE 5.50E + 06 1.97E + 06 6.70E + 05 1.41E+ 06 2.23E + 07 0.00E + 00 1.84E + 07
.___-127M TE-129M 7.23E + 06 2.70E + 06 1.14E + 06 2.48E + 06 3.02E + 07 0.00E + 00 3.64E + 07 l-131 3.56E + 08 5.09E + 08 2.92E + 08 1.67E+ 11 8.73E + 08 0.00E + 00 1.34E + 08 l-133
~
4.65E + 06 8.10E+06 ~~ ~ ~ ~ ~
2.47E+06 1.19E+ 09 1.41 ~~
E + 07 0.00E + 00 7.28E + 06
~
~E[34 C 1.70E + 15~IEE+5~0 3 30E + 10 bE+~0b~1.3E+~5b 4.34E+09 7.0E+~~08 CS-136 7.92E + 08 3.13E + 09 2.25E + 09 0.00E + 00 1.74E + 09 2.38E + 08 3.55E + 08 CS-137 2.22E
+. 10 3.03E + 10 1.99E + 10 0.00E+
00 ..__
1.03E ...
+ 10 3.42E + 09 5.87E+ ._.
08 BA-140 3.24E + 06 4.07E + 03 2.12E + 05 0.00E+ 00 1.38E + 03 2.33E + 03 6.67E + 06 CE-141 5.82E + 02 3.94E + 02 4.47E + 01 0.00E+ 00 1.83E + 02 0.00E+ 00 1.51E+06 CE 144 4.30E + 04 1.80E + 04 2.31E +.__..
03___.0.00E + 00 1.07E ..
+ 04 0.00E .
+ 00 1.45E
+ 07
)
s PR-143 1.90E + 01 7.60E + 00 9.40s.01 0.00E + 00 4.39E + 00 0.00E + 00 8.30E+ 04 ND-147 1.13E + 01 1.31 E + 01 7.82e41 0.00E + 00 7.65E + 00 0.00E + 00 6.28E .
+ 04 9
142.0 m l
_ _ _ _ _ _ _ __ )
Number
' TMI Radiologica!' Controls
~ gEI Departmental Procedure 661&PLN-4200.01 Tme Revissori No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.6.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT 2
ORGAN DOSE FACTORS; m - mrom/ year per pCl/sec NUCUDE -------------------------------------------------------------
BONE UVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E+00 ' O.00E+00 C-14 0.00E + 00 0.00E + 00 0.00E+00 0.00E+00 0.00E +00 0.00E +00 0.00E+00 .
CR-51 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 0.00E + 00 0.00E + 00 MN-54 0.00E+ 00 0.00E+ 00 0.00E+00 0.00E +00 0.00E + 00 0.00E + 00 0.00E + 00 FE-55 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 FE-59 0.00E + 00 0.00E +00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 CO-58 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E + 00 0.00E + 00 CO40 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 0.00E+ 00 0.00E + 00 0.00E+ 00 NI-63 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E400 0.00E+ 00 0.00E + 00 ZN-65 0.00E+ 00 0.00E+00 0.00E + 00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 SR-89 'O.00E + 00 0.00E+ 00 000E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 SR-90 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E +00 Y-91 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 . 0.00E+00 0.00E + 00 0.00E + 00 ZR-95 0.00E + 00 0.00E +00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E+ 00 NB-95 0.00E+ 00 0.00E+ 00 0.00E+00 0.00E +00 0.00E+ 00 0.00E+00 0.00E+00 RU-103 0,00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E+ 00' RU-106 0.00E + 00 0.00E +00 0.00E + 00 0.00E+'0 0 0.00E+ 00 0.00E + 00 0.00E+ 00 AG-110M 0.00E +00 0.00E+00. 0.00E+00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 TE-125M 0.00E+00 0.00E + 00 0.00E + 00 0.00E+00 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E
___ + 00
_ ... .__ _ 0.00E + 00 0.00E+00 TE_.-127M ....
TE-129M 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E+00 0.00E+ 00 0.00E +00 1-131 0.00E + 00 0.00E + 00 0.00E + 00 'O.00E + 00 0.00E +00 0.00E+ 00 0.00E+00 1-133 0.00E +00 0.00E+ 00 0.00E+00 0.00E + 00 0.00E + 00 0.00E+ 00- 0.0CE+00 CS-134 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 CS-136 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E+00 0.00E+ 00 0.00E+ 00 0.00E + 00 CS-137 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 0.00E + 00 0.00E + 00 0.00E + 00 BA-140 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E + 00 0.00E + 00 CE-141 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E+00 0.00E+ 00 0.00E + 00 CE-144 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 PR-143 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E +00 0.00E +00 ND-147 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 143.0 m
i l
l Number TMI Radiological Controls
. f ggEI Departmernal Procedure 6610-PLN-4200.01 Tree Rowsiort No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.6.2 l Pathway Dose Factors, Ri l l
l AGE GROUP: CHILD PATHWAY: GRASS-COW-MEAT ~ ~ '~
~ ~ '~~
~~~~~~~TGAN o DO5E'F CETORS; [r[- mrerII/ year per pCik l NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
BONE UVER T. BODY THYROID KIDNEY LUNG GI-LU )
H-3' O.00E + 00 2.34E + 02 2.34E + 02 2.34E+ 02 2.34E + 02 2.34E + 02 2.34E + 02 l C-14 3.84E+ 08 7.67E + 07 7.67E + 07 7.67E+ 07 7.67E + 07 7.67E + 07 7.67E + 07 CR 51 0.00E + 00 0.00E + 00 8.78E + 03 4.88E + 03 1.33E + 03 8.90E+ 03 4.86E + 05 MN-54 0.00E + 00 8.01 E + 06 2.13E + 06 0.00E + 00 2.25E + 06 0.00E + 00 6.73E + 06 1 FE-55 4.57E + 08 2.43E + 08 7.52E + 07 0.00E+00 0.00E+ 00 1.37E + 08 4,49E + 07 , )
FE-59 3.77E + 08 6.10E + 08 3.04E +08 0.00E + 00 0.00E ... + 00 1.77E +-_ 08 6.35E .
+ 08.
)
l CO-68 0.00E + 00 1.64E + 07 5.03E + 07 0.00E+ 00 0.00E+ 00 0.00E + 00 9.58E + 07 CO-60 0.00E + 00 6.93E + 07 2.04E + 08 0.00E+ 00 0.00E + 00 0.00E + 00 3.84E+ 08 NI-63 2.91E +10 1.56E + 09 9.91E + 08 0.00E + 00 0.00E+ 00 0.00E + 00 1.05E + 08 ZN-65 3.76E + 08 1.00E + 09 6.22E + 08 0.00E400 6.31E + 08 0.00E + 00 1.76E + 08 RB-86 0.00E + 00 5.76E + 08 3.54E +08 0.00E + 00 0.00E + 00 0.00E + 00 3.71E + 07 SR-89 4.82E + 08 0.00E
~ ~
+ 00 L38E~
+07 0.00E + 00 0.00E + 00 0.00E+ 00 1.87E + 07-
~5iE90 iE4dI10 0.0 DEI ~06~2 EIO9 6.~d6EI00-~6.EdEIE0 6.00E+06- i.4TEi68 Y-91 1.80E + 06 0.00E+ 00 4.82E + 04 0.00E+00 0.00E + 00 0.00E+ 00 2.40E + 08 ZR-95 2.66E + 06 5.86E + 05 5.21E+05 0.00E + 00 8.38E+05 0.00E + 00 6.11E + 08 NB-95 3.10E + 06 1.21 E +06 8.63E+05 0.00E+ 00 1.13E+06 0.00E+ 00 2.23E + 09 '
RU-103 1.55E + 08 0.00E + 00 5.96E + 07 0.00E + 00 3.90E+ 08 0.00E + 00 4.01E + 09 RU-106 4.44E + 09 0.00E + 00 5.54E + 08 0.00E+ 00 6.00E+09 0.00E + .00 6.91E+ 10 l
AG-110M 8.39E + 06 5.67E + 06 4.53E + 06 0.00E + 00 1.06E + 07 0.00E + 00 6.74E+ 08 j TE-125M 5.69E + 08 1.54E + 08 7.59E + 07 1.00E + 08 0.00E + 00 0.00E + 00 5.49E+08 TE-127M 1.78E + 09 4.78E + 08 2.11E + 08 4.25E + 08 5.06E + 09 0.00E + 00 1.44E+ 09 ;
TE-129M 1.79E + 09 5.00E + 08 2.78E + 08 5.77E+ 08 5.26E+ 09 0.00E + 00 2.18E+ 09 l l-131 1.66E + 07 1.67E + 07 9.48E + 06 5.52E + 09 2.74E+ 07 0.00E + 00 1.48E+ 06 )
1-133 5.72e 01 7.08e 01 2.68e-01 1.31 E + 02 1.18E + 00 0.00E + 00~ 2.85e-01 l CS-134 9I2E+~~08~~IE+~~09 35 I8 OliOE+00 4E+idi~~iE+~ iib 8.16E+E l CS-136 1.63E + 07 4.48E + 07 2.90E+07 0.00E+00 2.39E+07 3.56E +06 1.57E + 06 1 CS-137 1.33E+ 09 1.28E + 09 1.89E + 00 0.00E + 00 4.16E + 08 1.50E + 08 8.00E
+ 06 BA-140 4.42E + 07 3.87E + 04 2.58E + 06 0.00E + 00 1.26E + 04 2.31 E + 04 2.24E + 07 CE-141 2.22E + 04 1.11E + 04 1.65E + 03 0.00E + 00 4.86E + 03 0.00E + 00 1.38E + 07 CE-144 2.32E.__+ _06 __.
7.26E + .05 1.24E + 05 0.00E + 00 4.02E + 05 0.00E
+ 00 1.89E ..
+ 08 -
PR-143 3.33E + 04 1.00E + 04 1.65E + 03 0.00E+ 00 5.42E + 03 0.00E + 00 3.60E + 07 ND-147 1.17E + 04 9.48E + 03 7.34E + 02 0.00E + 00 5.20E + 03 0.00E+ 00 1.50E + 07 i
i i
e 144.0 m 4
Number TMl Radiologicaf Controls g Departmental Procedure 6610 PLN-4200.01
.Tme F4Pv!S40n No.
)
Offsite Dose Calculation Manual (ODCM) 11 1
TABLE 5.6.3 Pathway Dose Factors, Ri AGE GROUP: TEEN
...____. _ _. .___.... _____ .__.PATHWAY: GRASS-COW. .. MEAT ORGAN DOSE FACTORS; m2 - mrem / year per pCi/sec NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------
GI-Lij BONE UVER T. BODY THYROID KIDNEY LUNG H4 0.00E + 00 1.93E+ 02 1.93E+02 1.93E + 02 1.93E + 02 1.93E + 02 1.93E + 02 2.04E + 08 4.08E + 07 4.08E +07 4.08E + 07 4.08E +07 4.08E + 07 4.08E + 07 C-14 CR-51 0.00E + 00 0.00G +00 5.63E + 03 3.13E + 03 1.23E + 03 8.03E
+ 03 9.46E .
+05 MN54 0.00E + 00 7.00E + 06 1.39E + 06 0.00E + 00 2.09E + 06 0.00E + 00 1.44E + 07
, FE-55 2.38E + 08 1.69E + 08 3.94E+ 07 0.00E + 00 0.00E+00 1.07E + 08 7.31E + 07 FE 2.12E + 08 4.95E + 08 1.91 E + 08 0.00E + 00 0.00E + 00 1.56E + 08 1.17E + 09
_._-59. ... _ ... ___ ...__ .. .......__ _ ..___.. . ..
CO-58 0.00E + 00 1.40E + 07 3.24E + 07 0.00E + 00 0.00E + 00 0.00E + 00 1.94E + 08 C040 0.00E + 00 5.83E + 07 1.31E + 08 0.00E +00 0.00E + 00 0.00E + 00 7.60E + 08 Nifi3 1.52E + 10 1.07E + 09 5.15E + 08 0.00E + 00 0.00E +00 0.00E+00 1.71E + 08 ZN45 2.50E+ 08 8.68E + 08 4.05E + 08 0.00E400 5.56E + 08 0.00E+ 00 3.68E+ 08 i RB-86 0.00E+ 00 4.06E + 08 1.91E + 08 0.00E +00 0.00E + 00 0.00E+00 6.00E+ 07 2.55E+ 08 0.00E + 00 . 7,20E + 06 0.00E + 00 0.00E + 00 0.00E + 00 3.03E + 07 SR._-89 SR-90 8.04E + 09 0.00E+00 1.90E+ 09 0.00E + 00 0.00E + 00 0.00E +00 2.26E + 08 Y-91 9.54E + 05 0.00E + 00 2.56E + 04 0.00E+00 0.00E + 00 0.00E + 00 3.91 E + 08 ZR-95 1.50E + 06 4.73E + 05 3.25E + 050.00E + 00 6.95E + 05 0.00E + 00 1.09E + 09 NB-95 1.79E + 06 9.95E + 05 5.48E + 05 0.00E + 00 9.64E + 05 0.00E + 00 4.25E + 09
. RU-103 8.56E +07 0.00E + 00 3.06E+ 07 0.00E + 00 3.02E + 08 0.00E +00 7.15E+ 09 RU-106 2.36E+09 0.00E + 00 2.97E +08 0.00E+00 4.54E + 09 0.00E + 00 1.13E+ 11 AG-110M 5.06E + 06 4.78E + 06 2.91E+06 0.00E + 00 9.13E + 06 0.00E + 00 1.34E + 09 TE-125M 3.03E + 08 1.09E + 08 4.05E + 07 8.46E + 07 0.00E +00 0.00E + 00 8.94E + 08 TE-127M 9.41E+08 3.34E + 08 1.12E + 08 2.24E + 08 3.81E+ 09 0.00E+ 00 2.35E+ 09 TE-129M 9.49E + 08 3.52E + 08 1.50E +08 3.06E + 08 3.97E+09 0.00E +00 3.56E+ 09
. 1-131 8.93E+06 1.25E + 07 6.72E + 06 3.65E + 09 2.15E + 07 0.00E + 00 2.47E+ 06 l133 3.08e-01 5.22e 1.59e 01 7.29E + 01 9.16e41
.. _ ___.._..__ .__ _ ..____01 __ _ . ... __.. _ . . . . . _ _ _ .0.00E+00..
. . 3.95e41 .___
CS-134 5.23E + 08 1.23E + 09 5.71E + 08 0.00E + 00 3.91E + 08 1.49E + 08 1.53E + 07 CS-136 9.43E + 06 3.71E + 07 2.49E + 07 0.00E +00 2.02E + 07 3.18E+ 06 2.99E + 06 CS 7.24E
.. -137 . __.. _+. 08 9.63E+ ... 08 3.35E+
_ _.. .. 08 0.00E
.. ___+ _00 3.28E+ 08 1.27E +. .08. ..1.37E
. .__ . . + 07 .
BA-140 2.39E + 07 2.93E + 04 1.54E + 06 0.00E + 00 9.94E + 03 1.97E + 04 3.69E + 07 CE-141 1.18E + 04 7.87E + 03 9.05E + 02 0.00E + 00 3.71E + 03 0.00E + 00 2.20E + 07 CE 144 1.23E + 06 5.08E+05 6.60E+ ...
04 0.00E + 00 3.03E+ 05 0.0GE+ 00 3.09E + 08 PR-143 1.76E + 04 7.03E + 03 8.76E + 02 0.00E + 00 4.08E + 03 0.00E + 00 5.79E + 07 ND-147 6.23E + 03 6.78E + 03 4.06E + 02
._ .. . ___________.______ _0.00E _ _ _ . . .+ . _00 _ _ 3.98E
_ . _ _ _+ _ _03_ _ 0.00E
_ . . _ .+. 00 2.44E-... + 07 4
5 145.0 mm
Number TMI RadiologicaiControls gggI Departmental Procedure 6610-PLN-4200.01 r,* .
neween No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.6.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PAINWAY: GRASS-COW-MEAT ORGAN DOSE FACTORS; m2 - mrem / year per pCl/sec NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -----
BONE UVER T. BODY THYROID KlDNEY LUNG GI-LU -
H-3 0.00E + 00 3.24E + 02 3.24E + 02 3.24E + 02 3.24E + 02 3.24E + 02 3.24E + 02 C-14 2.42E + 08 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 CR-51 0.00E + 00 0.00E + 00 7.04E+ 03 4.21E +...___.....
03 1.56E +03 9.35E..__ + __..__.
03 1.77E
+ 06 MN-54 0.00E + 00 9.18E + 06 1.75E+ 06 0.00E + 00 2.73E + 06 0.00E + 00 2.81 E + 07 FE-55 2.93E + 08 2.03E+ 08 4.73E + 07 0.00E+ 00 0.00E+00 1.13E + 08 1.16E+ 08 FE-59 2.66E + 08 6.25E + 08 2.39E + 08 0.00E + 00 0.00E + 00 1.75E + 08 2.00
- _. . . . . . _ _ . . _ _ _ . . _ _ _ . _ . . . ..__...__.__ _ _ E + 09 ...__
CO-58 0.00E + 00 1.82E + 07 4.09E + 07 0.00E+00 0.00E+00 0.00E + 00 3.70E + 08 CO-60 0.00E+00 7.52E + 07 1.66E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.41 E+ 09 NI-63 1.89E + 10 1.31 E+ 09 6.33E+ 08 0.00E +00 0.00E +00 0.00E
+ 00 2.73E + 08 ZN 65 3.56E+ 08 1.13E + 09 5.12E+ 08 0.00E+ 00 7.57E + 08 0.00E + 00 7.13E+ 08 j RB-86 0.00E + 00 4.87E +D8 2.27E+ 08 0.00E + 00 0.00E + 00 0.00E + 00 9.59E+ 07 i SR-89 3.02E + 08 0.00E + 00 846E+ 06 0.00E + .00 0.00E + 00 0.00E +00 4.84E + 07 I SR-90 1.24E+ 10 0.00E + 00 3.05E +09 0.00E + 00 0.00E + 00 0.00E + 00 3.60E + 08
)
Y-91 1.13E + 06 0.00E + 00 3.03E + 04 0.00E + 00 0.00E + 00 0.00E + 00 6.24E + 08 ZR 1.87E + 06 6.01E + 05 4.07E + 05 0.00E + 00 9.43E + 05 0.00E + 00 1.90E + 09 - l
_. -95 _ ___ ..._____ __. ...__.. .____________.. ___.._....___.
j NB-95 2.30E + 06 1.28E + 06 6.87E +05 0.00E + 00 1.26E + 06 0.00E + 00 7.76E + 09 RU-103 1.05E + 08 0.00E + 00 4.53E+07 0.00E + 00 4.02E + 08 0.00E+ 00 1.23E + 10 RU-106 2.80E + 09 0.00E + 00 3.54E + 08 0.00E + 00 5.41 E +09 0.00E + 00 1.81E + 11 AG-110M 6.68E + 06 6.18E + 06 3.67E + 06 0.00E + 00 1.22E +07 0.00E + 00 2.52E + 09 TE-125M 3.59E + 08 1.30E + 08 4.81 E + 07 1.08E + 08 1.46E +09 0.00E + 00 1.43E + 09 TE 1.12E + 09 3.99E +08 1.36E + 08 2.85E + 08 4.53E+09 0.00E + 00 3.74E + 09._
.__.127M ... ... .__... ....___.. _ _____. . . .._ _ ______.
TE-129M 1.13E + 09 4.23E + 08 1.79E + 08 3.89E + 08 4.73E + 09 0.00E+00 5.71 E + 09 l-131 1.08E + 07 1.54E + 07 8.82E + 06 5.04E + 09 2.64E + 07 0.00E + 00 4.06E + 06 l-133 6.41e 01 1.96e41 9.42E + 01 1.12E + 00 0.00E + 00 5.76eW1
.___ 3.68e
. . _ _ . -.01 CS-134 6.58E + 08 1.57E +09 1.28E +09 0.00E + 00 5.07E + 08 1.68E + 08 2.74E + 07 CS-136 1.21 E + 07 4.18E + 07 3.44E + 07 0.00E + 00 2.66E+07 3.65E + 06 5.43E + 06 CS-137 8.72E + 08 1.19E + 09 7.82E + 08 0.00E + 00 4.05E+ 08 1.35E+ 08 2.31 E + 07 BA-140 2.90E+07 . 3.64E + 04 1.90E +06 0.00E + 00 1.24E +04 2.08E + 04 5.96E + 07 CE-141 1.41 E + 04 9.51 E + 03 .1.08E + 03 0.00E + 00 4.42E + 03 0.00E + 00 3.64E + 07 CE-144 1.46E + 06 6.10E + 05 7.83E~~ + 04 0.00E + 00 3.62E + 05 0.00E + 00 4.90E + 08 ~
~b -143 25+~b4~k~40E~~~~~EE + 03 1 + 03 O E +~00~IiiSN+~03~ ~5 5 +~00 9.17E + 07 ND 147 7.08E + 03 8.18E + 03 4.90E + 02 0.00E + 00 4.78E + 03 0.00E ... __ _ __
+ 00 3.93E+07 4
9 146.0 mm I
l
4 Number TMl Radiologicif Controls
~
EI Departmental Procedure 6610 PLN-4200.01 ,
1
- m. nm.on te.
Offsite Dose Calculation Manual (ODCM) 11 ,
1 i
TABLE 5.7.1 1
Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: VEGETATION ..______ ..
_____.._____________.g.
NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
GI-U.I
--- BONE UVER T. BODY THYROID KIDNEY LUNG H-3 0.00E + 00 0.00E + 00 0.00E+00 0.00E+ 00 0.00E +00 0.00E + 00 0.00E + 00 C-14 ' O.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 ' O.00E + 00 0.00E + 00 0.00E +00 CR-51 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 MN-54 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00' -
FE-55 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 FE-59 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 0.00E+ 00 0.00E + 00 '
CO-58 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CO-60 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 NI-63 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 2N-65 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E+00 RB-86 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E+00 0.00E + 00 SR-89 0.00E +00 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E + 00 0.00E+ 00 0.00E + 00 SR 90 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 Y-91 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 0.00E+00 0.00E+00 ~0.00E + 00 ZR-95 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E+00 0.00E + 00 0.00E+ 00 NB-95 0.00E + 00 0.00E + 00 0.00E + 00 ~ 0.00E + 00 0.00E+00 0.00E + 00 0.00E + 00 RU-103 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 0.00E+ 00 0.00E+ 00 RU-106 0.00E + 00 0.00E + 00 0.00E+00 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E+00 AG-110M 0.00E + 00 0.00E + 00 0.00E +00 0.00E+ 00 0.00E + 00 0.00E+ 00 0.00E+00 TE-125M 0.00E + 00 0.00E + 00 0.00E+00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 TE-127M 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 0.00E + 00 0.00E + 00
~ ~
I TE 129M b EE b ~ bid I~00 0.5 5 0$ d +~b ~b.~d 5 ~b.~E +~E~~b.~d E l-131 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 1-133 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 0.00E+00 0.00E+ 00 0.00E+ 00 CS-134 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E +00 CS-136 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 l 0.00E + 00 0.00E + 00 0.00E+.. 00 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E + 00 t
CS .137 . . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ ___ - .._ _ _..__ __..__ _ . .
BA 140 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E + 00 CE-141 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 CE-144 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 PR-143. 0.00E+00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 ND-147 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 147.0 m.
l l
l l
Numbw TMI RadiologicaTControls gggE Departmental Procedure 6610-PLN-4200.01 True . Revieson No.
l Offsite Dose Calculation Manual (ODCM) 11 1
TABLE 5.7.2 Pathway Dose Factors, RI AGE GROUP: CHILD PATHWAY: VEGETAT10N ~~~
~ ~ ~ ~ ~ ~ ~ '
ORGdN DESE F C[ TORS; 2' m 7' mrem /yEhlrh~ -
NUCUDE- --- - - - - - - - - - - - - - - - - - - - -
BONE UVER T. BODY THYROID KIDNEY LUNG GI-LU H-3 0.00E + 00 4.02E + 03 4.02E + 03 4.02E + 03 4.02E + 03 4.02E + 03 4.02E + 03 C-14 8.89E + 08 1.78E + 08 1.78E + 08 1.78E+ 08 1.78E + 08 1.78E+ 08 1.76E + 08 CR-51 0.00E + 00 0.00E + 00 1.17E + 05 6.49E +. 04 1.77E
+ 04
__.5 6.20E 1.18E + 0
+ 06 MN-54 0.00E + 00 6.65E + 08 1.77E + 08 0.00E + 00 1.8SE + 08 0.00E + 00 5.58E + 08 FE-55 8.01 E + 08 4.25E + 08 1.32E + 08 0.00E + 00 0.00E + 00 2.40E + 08 7.87E+ 07 FE-59 ' 3.98E + 08 6.44E + 08 3.21 E + 08 0.00E + 00 0.00E + 00 1.87E +. 08 6.71 E + 08 CO-58 0.00E + 00 6.44E + 07 1.97E + 08 0.00E+ 00 0.00E + 00 0.00E + 00 3.76E + 08 CO-60 0.00E + 00 3.78E + 0B 1.12E + 09 0.00E + 00 0.00E + 00 0.00E +00 2.10E + 09 NI63 3.95E + 10 2.11E + 09 1.34E + 09 0.00E + 00 0.00E+ 00 0.00E + 00 1.42E + 08 ZN-65 e 12E+08 2.16E + 09 1.35E + 09 0.00E+ 00 1.36E + 09 0.00E + 00 3.80E +08 RB-86 0.00E + 00 4.51E + 08 2.77E+ 08 0.00E+00 0.00E + 00 0.00E + 00 2.90E + 07 SR-89 3.60E + 10 0.00E + 00 1,03E + 09 0.00E + 00 0.00E + 00 0.00E + 00 1.39E + 09 SR.90 1.24E + 12 0.00E + 00 3.15E + 11 . 0.00E + 00 0.00E + 00 0.00E + 00 1.67E + 10 Y-91 1.87E + 07 0.00E+ 00 4.99E4 05 ' O.00E+00 0.00E+ 00 0.00E +00 2.49E + 09 ZR-95 3.86E + 06 8.48E + 05 7.55E +05 0.00E+ 00 1.21E + 06 0.00E + 00 8.85E + 08 l NB-95 4.11E + 05 1.60E + 05 1.14E + 05 0.00E+00 1.50E + 05 0.00E + 00 2.96E + 08 RU-103 1.53E +07 0.00E + 00 5.90E+06 0.00E + 00 3.86E+ 07 0.00E + 00 3.97E + 08 RU-106 7.45E + 08 0.00E + 00 9.30E+ 07 0.00E+ 00 1.01 E + 09 0.00E + 00 1.16E + 10 AG-110M 3.21E + 07 2.17E + 07 1.736 + 07 0.00E+ 00 4.04E + 07 0.00E +00 2.58E + 09 l TE-125M 3.51E + 08 9.50E+ 07 4.67E + 07 9.84E + 07 0.00E + 00 0.00E + 00 3.38E+ 08 TE 1.32E + 09 3.56E + 08 1.57E+08 3.16E + 08 3.77E + 09 0.00E + .00_ .....___.. 1.07E + 09
_.-127M . . ..__ . _.. . . . ._... ..__.._.
TE-129M 8.40E + 08 2.35E + 08 1.30E+ 08 2.71 E + 08 2.47E + 09 0.00E + 00 1.02E + 09 l-131 1.43E + 08 1.44E + 08 8.18E + 07 4.76E + 10 2.36E + 08 0.00E +00 1.28E + 07 l-133 3.53E + 06 4.37E + 06 1.85E + 06 8.12E+ 08 7.28E + 06 0.00E + 00 1.76E + 06 CS-134 1.60E + 10 2.63E + 10 5.55E + 09 0.00E + 00 8.15E + 09 2.93E + 09 1.42E + 08 CS-136 8.28E + 07 2.2BE + 08 1.47E + 08 0.00E + 00 1.21E + 08 1.81E + 07 8.00E+ 06 CS-137 2.39E + 10 2.29E + 10 3.38E+ .______ .... ...
09 0.00E + 00 7.46E +...09 2.6BE + 09 1.43E + 08 BA-140 2.79E + 08 2.44E + 05 1.63E + 07 0.00E + 00 7.96E + 04 1.46E + 05 1.41 E + 08 CE-141 6.57E + 05 3.28E + 05 4.86E + 04 0.00E + 00 1.44E + 05 0.00E +00 4.09E+ 08 CE 144 1.27E + 08
._. . _. 99E3.+ 07 6.79E l
. _.. _ _ - a _+.. 06_ 0.00E .._ + 00 2.21 E +..._ . 07_.. 0.00E + 00 1.04E + 10 PR-143 1.45E + 05 4.36E + 04 7.21E+ 03 0.00E + 00 2.36E + 04 0.00E + 00 1.57E + 08 ND 7.15E + 04 5.79E+ 04 4.49E + 03 0.00E + 00 3.18E + 04 0.00E + 00 9.18E + 07
_ _-147 _ _ . . _ _ _ . . _ . ... ..__ .______. .._ .__ ._ _ ..._________ ..__ ..
j 9
148.0 m l
- _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _u
Numtw TMi RadiologicalControis EI Departmental Procedure 6610-PLN-4200.01 Tetie Revmon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.7.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: VEGETATION 2
ORGAN DOSE FACTORS; m - mrom/ year per pCl/sec NUCUDE - - - - - - - - - - - - - - - ---- -- -
BONE UVER T. BODY THYRO!D KIDNEY
~
LUNG GI-LLI
~~ ~~
H-3 d.~E+~0b~ 2.5d+~b3 2EE+03 b"E+~05~2 E+03 d.~59E +03~b.~E+03 C-14 3.69E + 08 7.38E + 07 7.38E + 07 7.38E +07 7.38E + 07 7.38E + 07 7.38E +07 CR 0.00E + 00 0.00E + 00 6.16E + 04 3.42E + 04 1.35E +04 8.79E + 04 1.03E..+ 07
.. -51 . . _ . . ...__ .... ...... __...... . .____ _ ..___.
MN-54 0.00E + 00 4.54E + 08 9.01 E + 07 0.00E +00 1.36E + 08 0.00E + 00 9.32E.+ 08 FE-55 3.26E + 08 2.31 E + 08 5.39E + 07 0.00E + 00 0.00E + 00 1.47E + 08 1.00E + 08 FE-59 1.80E + 08 4.19E + 08 1.62E + 08 0.00E + 00 0.00E + 00 1.32E+ 08 9.91E + 08 CO-58 0.00E + 00 4.36E + 07 1.01E + 08 0.00E + 00 0.00E + 00 0.00E+ 00 6.01E + 08 CO-60 0.00E + 00 2.49E + 08 5.60E + 08 0.00E + 00 0.00E + 00 0.00E + 00 3.24E + 09 Ni-63 1.61 E + 10 1.13E + 09 5.45E + 08 0.00E + 00 0.00E+ 00 0.00E+00 1.81E +._..
08 ZN-65 4.24E + 08 1.47E +09 6.86E + 08 0.00E+ 00 9.42E + 08 0.00E+00 6.23E+08 RB.86 0.00E+00 2.73E + 08. 1.28E + 08 0.00E+00 0.00E+00 0.00E+00 4.04E + 07 SR-89 1.52E + 10 0.00E + 00 4,34E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.80E+ 09 SR-90 7.51E + 11 0.00E + 00 1.85E+ 11 0.00E + 00 0.00E +00 0.00E + 00 2.11 E+ 10 Y-91 7.84E + 06 0,00E + 00 2.10E +05 0.00E +00 0.00E + 00 0.00E+00 3.22E+09 1.72E + 06 5.43E + 05 3.73E .._ + 05 0.00E + 00 7.98E + 05_ 0.00E + 00 1.2SE._____
+ 09 ZR__-95 NB-95 1.92E+ 05 1.07E + 05 5.87E + 04 0.00E + 00 1.03E +05 0.00E + 00 4.56E + 08 RU-103 6.82E + 06 0.00E+00 2.92E + 06 0.00E+00 2.41E+ 07 0.00E+ 00 5.70E+08 RU-106 3.09E + 08 0.00E + 00 3.90E + 07 0.00E + 00 5.97E +08 0.00E + 00 1.48E+ 10 AG-110M 1.52E + 07 1.43E + 07 8.72E + 06 0.00E + 00 2.74E +07 0.00E + 00 4.03E + 09 TE-125M 1.48E + 08 5.34E + 07 1.90E + 07 4.14E + 07 0.00E + 00 0.00E + 00 4.37E + 08 TE-127M 5.52E + 08 1.96E +08 6.56E+ 07 1.31E + 08 2.24E + 09 0.00E + 00 1.37E + 09 l
TE-129M 3.61 E + 08 1.34E + 08 5.72E+07 1.17E + 08 1.51E + 09 0.00E + 00 1.36E + 09 l-131 7.89E +07 1.08E + 08 5.78E + 07 3.14E + 10 1.85E+08 0.00E+ 00 2.13E + 07 l-133 1.94E + 06 3.29E + __._
06 1.00E +. 06 . _ .
4.59E + 08 5.77E + 06 0.00E
+ 00 2.49E
+ 06..
CS-134 7.10E + 09 1.67E + 10 7.75E + 09 0.00E + 00 5.31E + 09 2.03E + 09 2.08E+ 08 CS-136 4.39E + 07 1.73E + 08 1.16E + 08 0.00E+00 9.41E+07 1.48E + 07 1.39E+07 CS-137 1.01E + 10 1.35E+ 10 4.69E + 09 0.00E + 00 4.59E + 09 1.78E+ 09 1.92E + 08 BA-140 1.39E + 08 1.71E + 05 8.97E + 06 0.00E + 00 5.78E + 04 1.15E + 05 2.15E+08 l CE-141 2.83E + 05 1.89E + 05 2.17E + 04 0.00E +00 8.90E + 04 0.00E+ 00 5.41 E + 08 CE-144 5.28E + 07 2.18E + 07 2.83E + 06 0.00E+ 00 1.30E + 07 1.33E+ to -
...__.__...._ _ . .. . _... .___..__ .._' O.00E + 00 ._. . _ ...
PR-143 6.99E + 04 2.79E + 04 3.48E + 03 0.00E + 00 1.62E + 04 0.00E+ 00 2.30E + 08 ND-147 3.62E + 04 3.94E + 04 2.36E + 03 0.00E + 00 2.31 E + 04 0.00E+ 00 1.42E + 08 O
149.0 m
I Number .
ggy TMl Radiologicaf Cortrols Departmental Procedure 6610-PLN-4200.01
. Title Rwison No.
OffsNe Dose Calculation Manual (ODCM) 11 TABLE 5.7.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: VEGETATION
~ ~~~~ ~ ~~ ~ ~ ~~~~
dRCd5~ DOSE IETORS; ~I~m ~~ . mrenI/ year per[dik~
NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------- -------- -- --
BONE
~
UVER - T. BODY THYROID KIDNEY LUNG GI-LU
~~ ~ ~ ~ ~~
~'5~
H- ' 55~E+00 2.2d+~ 03 5~26E +55~5~26E+ 03~~5~267E 03~5~26E + 03 ' 2.2d+~05~
C-14 2.28E + 08 4.55E + 07 4.55E+ 07 4.55E + 07 4.55E + 07 4.55E + 07 4.55E + 07 .
CR-51 0.00E + 00 0.00E + 00 4.64E+ 04 2.77E + 04 1.02E + 04 6.15E + 04 1.17E + 07 -
MN-54 0.00E + 00 3.13E + 08 5.97E+ 07 0.00E + 00 9.31E + 07 0.00E + 00 9.58E + 08 FE-55 2.10E + 08 1.45E+ 08 3.38E+ 07 0.00E + 00 0.00E + 00 8.08E + 07 8.31 E + 07
- FE-59 1.26E+ .08 ..
2.97E+..08 ...
1.14E .+ 08 .... 0.00E + 00 0.00E +. ....
00 ..8.29E +07 9.89E+ 08 CO-58 0.00E + 00 3.07E + 07 6.89E + 07 0.00E +00 0.00E + 00 0.00E + 00 6.23E + 08 CO-60 0.00E+00 1.67E + 00 3.89E+08 0.00E+00 0.00E + 00 0.00E+00 3.14E + 09 NI63 1.04E+ 10 7.21 E + 08.... 3.49E + 08 0.00E + 00 0.00E...+ ___. 00 ...
0.00E+00 1.50E + 08 -
ZN-65 3.17E + 08 1.01 E + 09 4.56E + 08 0.00E + 00 6.75E + 08 0.00E + 00 6.36E + 08 RB-86 0.00E+ 00 2.19E+ 08 1.02E + 08 0.00E + 00 0.00E + 00 0.00E+00 4.32E + 07 SR-89 9.98E + 09 0.00E + .00 2.86E+....__...
08 0.00E + 00 0.00E + 00 0.00E + 00 1.60E + 09 SR-90 6.05E + 11 0.00E+ 00 1.48E + 11 0.00E + 00 0.00E + 00 0.00E + 00 1.75E + 10 Y-91 5.12E+ 06 0.00E + 00 1.37E + 05 0.00E +00 0.00E+ 00 0.00E + 00 2.82E + 09 ZR 1.17E + 06 3.77E... + __........
05 2.55E + 05 0.00E + 00 5.91E+ 05 0.00E + 00 1.19E + 09
_-95 NB-95 1.42E + 05 7.92E + 04 4.26E + 04 0.00E + 00 7.83E+04 'O.00E+00 4.81E + 08 RU-103 4.77E + 06 0.00E+ 00 2.06E + 06 0.00E + 00 1.82E + 07 0.00E + 00 5.57E + 08' RU-106 1.93E +.08 0.00E + 00______....2.44E + 07 0.00E + 00 3.72E + 08 0.00E + 00 1.25E + 10 AG-110M 1.05E + 07 9.75E+ 06 - 5.79E + 06 . 0.00E + 00 1.92E + 07 0.00E+ 00 3.98E + 09 TE-125M 9.66E + 07 3.50E+ 07 1.29E +07 2.90E + 07 3.93E+ 08 0.00E + 00 3.86E + 08 TE 3.49E+ 08 ... 1.25E ..+ 08 4.26E + 07 8.93E + 07 1.42E .+. 09 0.00E+00 1.17E + 09
...-127M TE-129M 2.51 E+ 08 9.37E + 07 3.97E + 07 8.63E + 07 1.05E + 09 0.00E + 00 1.26E + 09 l-131 8.08E + 07 1.16E + 08 . 6.62E + 07 3.79E + 10 1.90E + 08 0.00E+00 3.05E+07 l-133 2.09E + 06 3.63E .+. _06 1.11 E + 06 5.34E + 08 6.33E+ 06 0.00E+ 00 3.26E + 06 CS-134 4.67E + 09 1.11 E + 10 9.08E + 09 0.00E + 00 3.59E+ 09 1.19E + 09 1.94E + 08 CS-136 4.28E + 07 1.09E + 08 1.22E + 08 0.00E + 00 9.41E +07 1.29E + 07 1.92E + 07 CS-137 6.36E + 09 8.70E + 09 5.70E+ 09 0.00E + 00 2.95E + 0S_ ____. 9.81E + 08 1.68E + 08 BA-140 1.29E + 08 1.62E + 05 8.47E + 06 0.00E + 00 5.52E+ 04 9.29E + 04 2.66E + 08 ,
CE-141 1.97E + 05 1.33E + 05 1.51 E + 04 0.00E + 00 6.20E + 04 0.00E + 00 5.10E + 08 CE-144 3.29E + 07 1.38E + 07 1.7 0.00E + 00 8.16E + 0.00E + 00 1.i1E + 10
. . .____...__ ___ .7E+06 .___.......__....06 _ _ . . . . . . . . ..__
PR-143 6.2SE + 04 2.51 E + 04 3.10E + 03 0.00E + 00 1.45E + 04 0.00E + 00 2.74E + 08 ND-147 3.34E +. 04 3.85E + 04 2.31 E + 03 0.00E + 00 2.25E + 04 0.00E + 00 1.85E + 08 O
150.0 me.
1 l
1 1
l Number
'g g g p ' TMl Radidogicif Controls Departmental Procedure 6610-PLN-4200.01 !
True Amston No.
I Offsite Dose Calculation Manual (ODCM) 11 6.0 TMI-1 GASEOUS WASTE TREATMENT SYSTEM 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System (see Fioure 6.1) 6.1.1 Waste Gas System
- a. Reactor Buuding:
- Reactor Coolant Drain Tank (RCDT) header
- b. Auxliary Bulding:
- Vent Header from
- 1. Miscellaneous Waste Storage Tank (MWST)
- 2. Three (3) Reactor Coolant Bleed Tanks (RCBT)
- Waste Gas Delay Tank
-Two (2) Waste Gas Compressors
- Three (3) Waste Gas Decay Tanks (WGDT)
- c. Fitration and dBution provided by de Station Ventiation System.
6.2 Operabity Operabity of the Gaseous Waste Treatment System is defined as the abity to remove gas from the vent header / tank gas spaces and store it under a higher pressure in the Waste Gas Decay Tanks for subsequent release.
Except for initiating the make up tank sampie and waste gas venting and the recycle or disposal of compressed waste gases stored in the waste gas decay tanks, the operation of the waste gas system is entirely automatic. One waste gas compressor comes on automaticaNy, removing gases from the vent header system as required, to maintain the pressure in the system at a maximum of about 16.4 psia.
4 151.0 mm
Number e
Mgp TMI RadiologicEControis Departmental Procedure 6610-PLN-4200.01 D Revison No.
Offsite Dose Calculation Manual (ODCM) 11
~~
FIGURE 6.1 Waste Gas System StaStet tees.ug meets u seems j 8 g; gl m t E sess masas iL i udging lM q p a 6 4b i P ' 'd ' P~~~* a b q , q , q ,
l d 6 d L 4 6 s eems 1 t <
- r. 6 l a mass i masse aman
._'*" i sansa l namna seens senaam sans d6 i u _ _ _ _ _ _ _ .,l ,
4 g ..
- * * * * ++e.
issA. . u'"nas sans seasssesenssasens ,
. i r s ,
g an et b
. sis M 'y. =' _ e.
E.~,.s I
$ ss Ollss 0l lss
.m % . '"m. i: ==E =>
c m ...a.
e a w
+
.. +s. +, .
- ago
- ks.
a y: s- -
- +y 4 a o ,] c . .
d 4
i 152.0 m i
h.Ther Nuclear " "ad
- d #" *d' 6610-PLN-4200.01 Departmental Procedure True Flavieson No.
Offsite Dose Calculation Manual (ODCM) 11 7.Or EFFLUENT TOTAL DOSE ASSESSMENT 7.1 Total Dose Calculation The annual (calendar year) dose or dose committment to any member of the public, due to releases of radioactMty and to radiation from uranium fuel cycle soyrces shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrom. This control is provided in order to meet the dose limitations of 40 CFR 190.
The total dose from TMI-1 and TMI-2 (uranium fuel cycle facilities within 8 kilometers) is calculated .
by summing the calculated annual doses to critical organs of a real individual for liquid effluent using Section 2.1 methodology, for gaseous effluent using Section 5.2.1 and 5.2.2 methodology, and the direct radiation from the site from the environmental monitoring program's direct radiation (TLD) monitors.
W@
9 9
e e
9 153.0 mm
1 Number gdgy TMI Radiolog6 cal Controls Departmental Procedure 6610-PLN-4200.01 Trtle Revision No.
Offstte Dose Calculation Manual (ODCM) 11 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitorino Prooram Reouirements 8.1.1 Oontrols in accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., the radiological environmental monitoring program shall be conducted'as specified in Table 8.1.
8.1.2 Applicability At all times. ,
8.1.3 Action
- a. With the radiological environmental monitoring program not being conducted as specified in Table 8.1, prepare and submit to the COnunimidon in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence,.
- b. With the level of radioactlylty as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 8.2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, 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 of the public is less than the calendar year limits of ODCM Part 1 Controls 2.2.1.2, 2.2.2.2, 2.2.2.3 and ODCM Part it. Sections 2.1.1.3F,2.1.2.3D .and 2.1.2.3E. When more than one of the radionuclides in Table 8.2 are detected as the result of plant effluents in the sampling medium, this report shall be submitted if:
concentretion (1) + concentration (2) + . a: 1.0 reporting level (1) reporting level (2)
When radionuclides other than those in Table 8.2 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 is equal to or greater than the calendar year Itmits of ODCM Part I Controls 2.2.1.2,
. 2.2.2.2,2.2.2.3 and ODCM Part 11, Sections 2.1.1.3F,2.1.2.3D, and 2.1.2.3E. This report is not required if the measured level of radioactMty was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual l
Radiological Environmental Operating Report. i The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.
154.0 m l
Number TMI Radiologicaf Controls EI Departmental Procedure 6610-PLN-4200.01
.rm. . Amen No.
Offsite Dose Calculation Manual (ODCM) 11
- c. With milk or fresh leafy vegetation samples unavalable from one or more of the sample locations required by Table 8.1, identWy specfic locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to TMI-1 Tech. Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table for the -
ODCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.
8.1.4 Bases
- The radiological montoring program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of members of the general public resulting from the station operatiort This monitoring program implementsSection IV B.2 of Appendix 1 to ,
10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than
- expected on the basis of the effluent measurements and rnodeling of the environmental exposure pathways. Guidance for this morjltgring is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring (Revision 1, November 1979). Program changes may be inklated based on operational experience.
8.1.5 Survealance Reoutrements i The radiological environmental monitoring samples shall be collected pursuant to Table 8.1, from the specific locations given in Tables 8.4 through 8.10 and Maps 8.1 through 8.3, and shall be analyzed pursuant to the requirements of Table 8.1 and the detection capab81 ties required by Table 8.3.
155.0 mu
Number
--glgy TMl Radiologicaf Controls Departmental Procedure 6610-PLN 4200.01 i Title Revreson No. l l
Offsite Dose Calculation Manual (ODCM) 11 l 8.2 1.and Use Census 8.2.1 Controls in accordance wth the TMI-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., a Land Use Census shall i be conducted and shall identify within a distance of 8 km (5 mies) the location in each of the 16 . {
meteorological sectors of the nearest mik animal, the nearest residence, and the nearest garden
- l of greater than 50 m2 (500 ft 2) producing broad leaf vegetation. J 8.2.2 Applicablity At all times.
l 8.2.3 Action l
- a. With a Land Use Census identfying a location (s) that yields a calcula'ted dose or dose commitment greater than the values currently being calculated in ODCM Part i Survellance 3.2.2.3.1, pursuant to ODCM, Part IV, Section 2.0, identify the new location (s) in the next Annual Radioactive EfRuent Release Report
- b. Wth a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which {
samples are currently being obtained in accordance with Table 8.1, add the new location (s) .
within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.
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 l monitoring program after October 31 of the year in which this Land Use Census was !
conducted. Pursuant to TMi-1 Tech. Spec. 6.14 and TMi-2 PDMS Tech. Spec. 6.12, submit I in the next Annual Radioactive Effluent Release Report documentation for a change in the '
ODCM including a revised figure (s) and table (s) for the ODCM reRecting the new location (s) with information supporting the change in sampling locations.
l 8.2.4 Bases This Control is provided to ensure that changes in the use of unrestricted areas are identified and )
modifications to the monitoring program are made if required by the results of this census. The best ,
information from the door-to door survey, aerial surveys, or constAting with local agricultural j authorties shaR be used. This census satisfies the requirements of Section IV.B.3 of Appendix ! to 2
10 CFR 50. Reetricting the census to gardens of greater than 500 square feet (50 m ) provides l assurance that significant exposure pathways via leafy vegetables wil be identified and monitored 1 since a garden of this size is the minimum required to produce the quantty (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a chBd. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (Le., simlar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.
l 1
Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site !'
boundary in each of two different sectors with the highest predicted D/Os in lieu of the garden census.
Requirements for broad leaf sampling in Table 8.1 shall be foBowed, including analysis of control samples.
156.0 m
Numbw TMI Radiologicsl Controls bCISer Departmental Procedure 661&PLN-4200.01 Tm Revison No.
Offsite Dose Calculation Manual (ODCM) 11 8.2.5 Survellance Reauirements The I.and Use Census shall be conducted during the growing season at least once per 12 months, using that information that wHl provide the best results, such as by a door-to4oor survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Part IV, Section 1.0.
1 l
l 157.0 mm
Number jggy TMI Radiologicil ' Controls Departmental Procedure 6610-PLN-4200.01 True ,
Revision No.
Offsite Dose Calculation Manual (ODCM) 11 I
8.3 Intertaboratory Comparison Prooram I
8.3.1 Controls In accvidance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., analyses shall be performed on radioactive materials supplied as part of an intertaboratory Comparison Program which has been approved by the Commission (NRC). Only those samples and analyses which are required by Table 8.1 shall be p=Ivaried.
8.3.2 ApolicabiAl s
At all times.
8.3.3 Action With ahalysis not being performed as required above, report the corrective action taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
8.3.4 Bases .
l The requirement for participationJrtan approved Interlaboratory Companson Program is provided to l ensure that independent checks on precision and accuracy of the measurements of radioactive l material in environmental sample matrices are p=funr.ed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV, B.2 of Appendbc l to 10 CFR 50.
8.3.5 Surveillance Reouirements A summary of the intertaboratory Comparison Program results shall be included in the Annual Radio'ogical Environmental Operating Report.
1 !
,i 158.0 me 1
Number d TMI Radiological' Controls 1 EI Departmental Procedure 6610-PLN-4200.01 Tme Fisinsson No.
Offsite Dose Calculation Manual (ODCM) 11 i i 1 -
TABLE 8.1
' Sample Collection and Analysis Requirements a..
Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations
- Collection Frequencyb of AnalysisD i
- 1. Airbome i Radioiodine and Samples from 5 locations Continuous sampler Radiolodine Canister-Particulates from Table 8.4. operation with sample Analyze weeldy for 1-131.
collection weeldy, or more Particulate Filter:
frequently ll required by dust Analyze for gross beta loading. radioactMty following filter changed . Perform l gamma isotopic an$is'
~
on composite (by location) sample
-~
quarterly.
- 2. Direct Samples from 40 Sample Ouarterly Analyze for gamma dose Radiation' locations from Table 8.5 quarterly.
(using either 2 dosimeters or at least 1 instrument for continuously measuring and recording dose rate at each location). l l
l f
i .
159.0 mm
Nurnber
~
3=EMI F TMI Radiological' Controls Departmental Procedure 6610-PLN-4200.01
. rm. namon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 8.1 (Cont'd)
Sample Collection and Analysis Requirements l .
I Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations
- Collection Frequencyb of AnalysisD
- 3. Waterbome
- a. Surface' Samples from 2 locations Compostte8 sample over 1 Perform gamma isotopic
, from Table 8.6. montNy period. analysis' monthly.
Composite for tritium e 1 sample trom analysis quarteriy.
downstream (indicator) location
- 1 sample from upistream (control) location (or location not influencedby the station discharge) l
- b. Drinking Samples frotn 2 locations Composite8 sample over 1 Perform gross beta and from Table 8.6. montNy period. gamma isotopic analysis' monthly. Perform Sr-90 e 1 sample at the location analysis if gross beta of of the nearest water montNy composite >10 supply that could be times control. Composite affected by the station for tritium analysis discharge. quarterfy.
c'1 sample from a control locatiorL
- c. Sediment from Samples from 2 locations Sample twice per year Perform gamma isotopic Shoreline (1 Control and 1 Indicator) (Spring and Fall), the interval analysis' on each from Table 8.7. not to exceed 184 days. sample.
O 160.0 mm
Number
' a' "' "
~
NhI '"' "*d' Departmental Procedure 6610 PLN-4200.01
- 1. a.v onre.
Offsite Dose Calculation Manual (ODCM) 11 TABl.E 8.1 (Cont'd) ,
Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations
- Collection Frequency b of Analysis"
- 4. Ingestion a.Mak Samples from 4 locations Sample semimonthly when Perform gamma isotopic from Table 8.8. animals are on pasture; analysis
- and 1-131 monthly at other times. analysis on each sample.
Composite for Sr-90 analysis quarterfy.
- b. Fish Samples from 2 locations Sample twice per year Perform gamma isotopic
- from Table 8.9. (Spring and Fall), the interval and Sr-90 analysis on
-- not to exceed 184 days. edible portions.
- 1 sample of recreationally important bottom feeders and 1 '
sample of recreationally ,
important predators in the vicinity of the station discharge.
1 e 1 sample of recreationaRy important bottom feeders and 1 sample of recreationally important predators from an area not influenced by the station discharoe.
161.0 mm
Number ggI TMI Radiological' Controls Departmental Procedure 6610-PLN-4200.01 Tate . Arvesson No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 8.1 (Cont'd)
Sample Collection and Analysis Requirements Number of Samples -
Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations
- Collection Frequencyh of AnalysisD
- c. Food Samples from 2 locations . Sample at time of harvest. Perform gamma isotopic',
Products from Table 8.10 (when 1-131, and Sr-90 analysis available) on edible portions.
e 1 sample of green leafy vegetables or leafy vegetation at a location in the immediate vicinity of the station. (indicator) .-
e 1 sample of same species or group from a~
location not influenced by the station discharge.
Samples from 4 locations Sample fruits and Perform gamma isotopic (3 indicator and 1 control) vegetables at time of analysis' on edible from Table 8.10 (when harvest. portions, available).
O e
O 162.0 mm
l Number gggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Trtto Revisson No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 8.1 (dont'd)
Sample Collection and Analysis Requirements Table Notation
- a. Sampling locations are provided in Tables 8.4 through 8.10. They are depicted in Maps 8.1 through 8.3.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous condtions, seasonal unavalability', malfunction of automatic sampling equipment and other legitimate reasons. All deviations from'the sampling schedule shall be explained in the Annual Radiological Environmental Operating Report.
- b. Frequency notation: weeldy (7 days), semimonthly (15 days), rnonthly (31 days), and quarterly-(92 days).
All survellance requirements shall be performed wthin the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval A total maximum combined interval time for any 4 consecutive tests shall not exceed 3.25 times the specified collection or analysis interval.
- c. One or more instruments, such as a pressurized ion chamber for measuring and recording dose rate continuously, may be used in place of, or in addtion to, irnograting dosimeters. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor, two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.
- d. Airborne particulate sample fBters shan be analyzed for gross beta radioactMty 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta actMty in an air particulate sample (s) is greater than ten times the calendar year mean of control samples, Sr-90 and gamma isotopic analysis 1 shall be performed on the individual sample (s). l e Gamma isotopic analysis means the dentification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facity.
- f. The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. The
" downstream sample'shall be taken in an area beyond but near the mixing zone.
- g. Composite sample aliquots shall be collecte'd at time intervals that are short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
l O
163.0 mm
I l
Number Nuclear ' " a'd **
Departmental Procedure 6610-PLN-4200.01 Title Asvis4on No.
Offsite Dose Calculation Manual (ODCM) 11 1
TABLE 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne -
Particulate Water or gas Fish MHk Food Pr'oducts Analysis (pCl/L) (pCl/m8) (pCl/kg, wet) (pCl/L) (pCl/kg, wet) ,
H-3 20,000W Mn44 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co40 300 10,000 .
~
Zn45 300 20,000 St-90 8 0.1 ~~ 100 8 100 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1000 60 - 1000 Cs-137 50 20 2000 70 2000 Ba-l.a-140 200 300 WFor drinking water samples. This is 40 CFR Part 141 value.
164.0 me
Number TMI Radiologicial brols EI Departmental Procedure 6610-PLN-4200.01 Trtle Fwmon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 8.3 Detection Capabilities for Environmental Sample Analysis' Lower Limit of Detection (lid)*
l l
c.; r Airbome Particulate Fish Food Sediment Water or Gas (pCi/kg, Mak Products (pCi/kg, Analysis (pCl/L) (pCl/m3) wet) (pCl/L) (pCi/kg, wet) dry) e Gross Beta 4 0.01 H-3 2000 Mr>64 15 130 l
Fe-59 30 260 -
Co-58, 60 15 130 ,
zn. 30 , 2e0 l Zr-95 30 Sr-90 2 0.01 10 2 10 Nb-95 15 8
l-131 0.07 60 1 1 l
Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 S
9 165.0 mm
Number gggy TMI fladiological Cortrols Departmental Procedure 6610-PLN-4200.01 Trno Reviemn No.
Offsite Dose Calculation Manual (ODCM) 11 ,
1 l
TABLE 8.3 (Cont'd)
Detection Capabilities for Environmental Sample Analysis
- Table Notation ;
- a. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, which may be related to plant operations, together with those of the above nudides, shaB also be analyzed and reported in the Annual Radiological Environmental Operating Report.
- b. Required detection capabilties for thermoluminescent dosimeters used for environmental measurements are ghten in Regulatory Guide 4.13 (Rev.1).
- c. The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that wil yield a nd count, above system background, that wiu be detected with 95% probabilty with
' only 5% probability of falsely conduding that a blank observation represents a "real" signal.
For a particular measurement system (which may indude radiochemical separation):
4.66 S3 E V 2. 22
- Y
- exp (-A A C) -
Where: -
LLD is the "a priort' lower limit of detection as defin ad above, as picoeuries per unit mass or volume, sbis the standard deviation of the background counting rate or of the counting rate of a blank sample'as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yleid (when applicable),
A is the radioactive decay constant for the particular radionudide and at 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 at should be used in the calculation.
It should be recognized that the LLD is defined as an 'a. priori" (before the fact) limit representing the l capabilty of a measurement system and not-as an 'a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs wil be achieved under routine conditions. Occasionally background fluctuations, unavoidable small samples stres, the presence of interfering nudides, 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.
- d. LLD for drinking water.
166.0 mie
Number Nuoieer '"**'"*****""*
Departmental Procedure 6610-PLN-4200.01 Tree Reviske No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 8.4 TMINS REMP Station Locations-Air Particulate and Air lodine Station Code Distance (miles) Azimuth P) MapNo.
B1-4 0.8 28 60 El-2 0.4 95 2 F1-3 0.6 105 70 G2-1 1.4 125 74 M2-1 1.3 253 3 A3-1 2.6 358 4 H3-1 2.3 159 5, J3-2 2.9 . 181 71 04-1 3.5 325 61 G10-1 9.8 127 6 J15-1 12.6 180 7 Q15-1 13.5 305 8
_ _ ' TABLE 8.5 TMINS REMP Station Locations-Direct Radiation (TLD)
Station Code Distance (miles) Azimuth P) MapNo.
A1-1 0.4 0 1 A1-4 0.3 5 9 B1 1 0.6 25 10 B1-2 0.4 26 11 B1-3 0.5 15 12 C1-2 0.3 54 13 D1-1 0.2 74 14 El-1 0.2 95 15 E1-2 0.4 95 2 El-4 0.2 98 16 F1-2 0.2 109 17 GI-3 0.3 129 18 H1-1 0.5 167 19 H14 0.3 167 20 J1-1 . 0.8 184 21 J1-3 0.3 189 22 J1-4 0.4 - 188 23 K1-4 0.2 208 24 K1-6 0.2 202 25 L1-1 0.1 235 26 M1-1 0.1 249 27 l
N1-3 0.1 270 28 i P1-1 0.4 293 29 P1-2 0.2 290 30 167.0 m.
l
. I Number
~
Nuclear TMI Radiological'Controis D. ,,mnoni i P,oc au,. 6610 PLN-4200.01
{
Tree Romsson No. l l
Offsite Dose Calculation Manual (ODCM) 11 l i
TABLE 8.5 (Cont'd)
TMINS REMP Station Locations-Direct Radiation (TLD)
Station Code Distance (miles) Azirnuth (*) MaoNo.
Q1-2 0.2 318 31 R1-1 0.2 335 32 C2-1 1.6 48 33 K2-1 1.1 200 34 M2-1 1.3 253 3 A3-1 2.6 358 4 '
H3-1 2.3 159 5 R3-1 2.6 338 35 B5-1 4.8 18 36 C5-1 4.5 42 37 ES-1 4.6 81 38 FS-1 4.7 107 39 GS-1 4.8 .. 131 40 H5-1 4.1 157 41 J5-1 4.9 182 42 KS-1 5.0 200 43 -
L5-1 4.1 228 44 MS-1 4.3 249 45 NS-1 4.9 268 46 PS-1 4.9 285 47 05-1 5.0 318 48 RS-1 4.9 339 49 D6-1 5.2 65 50 E7-1 6.8 86 51 09-1 8.5 308 52 B10-1 9.4 21 53 G10-1 9.8 127 6 G15-1 14.4 124 54 J15-1 12.6 180 7 Q15-1 13.5 305 8 R15-2 12.4 329 55 i
' I II2k l
l l
i
Number
, EE TMI Radiological' Controls EW I Departmental Procedure 6610-PLN-4200.01 nu. % on No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 8.6
'TMINS REMP Station Locations-Surface Water Station Code Distance (mues) Azimuth P) MaoNo.
P1-3 (R) 0.1 284 56 -
J1-2 (R) 0.5 188 57 J2-1 (R) 1.5 182 58 A3-2 (R) 2.5 355 59 09-1(F) 8.5 308 52 G15-1 (F) 14.4 124 54 G15-2 (F) 13.6 128 62 G15-3 (F) 14.8 124' 63 J15-2 (F) 14.7 178 64 F15-1 (R) 12.6 122 65 ,
(R) = Raw Water (F) - Finished Water ._
" TABLE 8.7 TMINS REMP Station Locations-Aquatic Sediment Station Code D'estance (mies) Azimuth P) MAD No.
A1-2 0.8 6 66 A1-3 0.5 0 67 G11 0.3 137 68 K1-3 0.3 202 69 J2-1 1.5 182 58 e.
169.0 mm
Number Em TMI RadiologiciU' Controls N F
, Departmental Procedure 6610-PLN-4200.01 Tm. F# mon No.
Offsite Dose Calculation Manual (ODCM) 11 TABLE 8.8 TMINS REMP Station Locations-Milk Station Code Distance (miles) Azimuth (*) MaoNo.
D2-1 1.1 65 72 i E2-2 1.1 93 73 )
G2-1 1.4 125 74 '
A4-1 3.3 10 75 l F4-1 3.2 104 76 P7-1 6.7 293 77 l K15-2 12.8 208 78'
- )
1
. TABLE 8.9
~
- TMINS REMP Station Locations-Fish ,
Station Code Station Location IND Downstream of Station Discharge BKG Upstream of Station Discharge e+
9 170.0 mm
Number
, g gy TMl Radiologicil Controls Departmental Procedure 6610 PLN-4200.01 buon No.
me ,
11 Offsite Dose Calculation Manual (ODCM)
- TABLE s.10 TMINS REMP Station Locations-Food Products Azimuth M MapNo.
Station Code Distance (mies) 0.5 65 79 014 0.4 95 2 El-2 0.5 117 80 F11 0.9 150 81
- H1-2 1.1 65 72 D2-1 1.1 93 73 E2-2 1.4 - 125 74 G2-1 1.5 178 82 J2-2 1.3 252 83 M2-2 1.3 265 . 84 N2-2 3.3 10 75 A4-1 3.2 104 76 F4-1 6.7 - 293 77 P7-1 ..
10.5 10 85 A15-1 208 78 K15-2 124 13.6 253 86 M15-2 12.4 329 55 R15-2
(
i
\
222=
171.0
\
I Number .
g gp TMl RadiologicalControls Departmental Procedure 6610-PLN-4200.01
)
rm. ween No.
f Offsite Dose Calculation Manual (ODCM) 11 MAP 8.1 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE I
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A 172.0 mm
Number iSer TMI RadiologicsIControls o,p ,tmentai procedur. 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 11 MAP 8 '
THREE MILE ISLAND NUCEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 5 MIES OF THE SITE l
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173.0 mm
Number ggy TMI Radiologic 5iControls Departmental Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 11 i
MAP s.3 ,
I THREE MILE ISLAND NUCLEAR STATION l LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS GREATER THAN 5 MILES FROM THE SITE 34 M*
A 11.25' I
lJ l
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174.0 m.
Number I l Radidogid Contrds, GUClear Departmental Procedure 6610-PLN-4200.01 Tatie Revis4on No.
Offsite Dose Calculation Manual (ODCM) 11 9.0 PART 111 REFERENCES j i
- 1. EPril NP-3840, RP 1560-3 Final Report, " Environmental Radiation Doses From Difficult-To-Measure Nuclides,' January 1985 ;
- 2.
- Evaluation of the Three Mie Island Nuclear Station Unit 1 to Demonstrate Conformance to the Design Objectives of 10 CFR 50, Appendk I," Nuclear Safety Associates, May 1976
- 3. TMI-1 Final Safety Analysis Report (FSAR) .
- 4. TMl-2 Final Safety Analysis Report (FSAR)
- 5. Meteorological information and Dose Assessment System (MIDAS) e
- 6. NUREG-0017, ' Calculation of Releases of Radioactive Materials in Gaseous and Uquid Effluents from PWR," Revision 1,1985
- 7. NUREG4133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,' October 1978 .,
e
- 8. NUREG4172, ' Age-Specific Radiation Dose Commitment Factors For A One-Year Chronic Intake,"
i November 1977
- 9. RegulaW Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materlats in Uguid and Gaseous Effluents from Ught-Water Coded Nuclear Power Plants," Revision 1, June 1974
- 10. Regulatory Guide 1.109, "Calcu',ation of Annual Doses to Man from Routine Releases of' Reactor Emuents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendk I,' Revision 1, October 1977
- 11. Simpitfied Environmental Effluent Dosimetry System (SEEDS)
- 12. TMl Recirculation Factor Memos, April 12,1988 and March'17,1988
- 13. TMI-1 Operations Procedure, 1101-2.1, " Radiation Monitor Set Points"
- 14. Title 10, Ccde of Federal Regulations,
- Energy"
- 15. TMI-1 Technical Specifications, attached to Facility Operating Ucense No. DPR-50
- 16. Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Ught. Water-Cooled Reactors,' Revision 1, July 1977 l
- 17. TMI-2 PDMS Technical Specifications, attached to Facility Ucense No. DPR-73
- 18. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979
- 19. Title 40, Cod'e of Federal Regulations,
- Protection of Environment" 175.0 me
l l
l Number I jggy TMI Radiologics Controls Departmental Procedure 6610-PLN-4200.01 Tree . Revissori No.
Offsite Dose Calculation Manual (ODCM) 11 l I
l
- 20. Regulatory Guide 4.13, " Performance, Testing, and Procedural Specifications for f Thermoluminescence Dosimetry: Environmental Applications," Revision 1, July 1977 l l
- 21. Post-Defueling Monitored Storage Safety Analysis Report (PDMS SAR)
~
4 T
l 1
l j
176.0 mm i
Number Nuclear ' aad*** "d
- Departmental Procedure 6610-PLN-4200.01 Tree Revision No.
Offsite Dose Calculation Manual (ODCM) 11 a
o o
, PART IV REPORTING REQUIREMENTS I
- 8 177.0 m
Number TMI Radidogicil Controls
- ggUI Dop.itn-ntal Procedure 6610-PLN-4200.01 rin. Remion No.
Offsite Dose Calculation Manual (ODCM), 11 PART IV Reporting Requirements 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT **
1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the '
previous calendar year shaR be submitted to the Commission prior to May 1 of each year.
1.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, ,
and an analysis of trends of the results of the radiological environmental monitoring actMties for the report period, induding a comparison with pre-operational studies, with operational controls as appropriate, and with previous environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall als6 include the results of Land Use Censuses required by Part 111, Secuon 8.2.
1.3 The Annual Radiological Environmental Operating Reports shall include the summarized tabulated results of analysis of all radiological environrnental samples and environmental radiation measurements required by Part 111 Table 8.1 taker)#uring the period pursuant to the locations
. specified in the tables and figures in this ODCM, as wet as sumtnarized arxl tabulated results of these analyses and measurementpJn a format similar to the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not avalable for inclusion with the report, the report shall be submitted explaining the reasons for the missing results. The missing data shaR be submitted as soon as possible in a supplementary report.
1.4 The reports shall also include the following a summary descriptior) of the radiological environments monitoring program; a map (s) of all sampling locations keyed to a table giving distances and directions from a point that is midway between the Reactor BuRdings of TMI-1 and TMI-2; the results of licensee participation in the Interlaboratory Companson Program, required by Part 111, Section 8.3; discussion of au deviations from the sampling schedule of Part 111 Table 8.1; discussion of aR the required analyses in which the LLD required by Part 111, Table 8.3 was not achievable.
"A single submittal may be made for the station, 178.0 m
Number
.T TMI Radidogiciil'Contrds EI Departmental Procedure 6610-PLN-4200.01 Tme Reviskm No.
Offsite Dose Calculation Manual (ODCM) 11 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NOTE A single submittal may be made for the station. The submittal should combine those sections that are common to both units at the station however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit.
2.1 Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous 12 months of operation shall be submitted prior to May 1 for TMI-1 and TMI-2.
2.2 The fdiowing information shall be induded in both Radioactive Effluent Releaso Reports to be submtted each year:
The Radioactive Efiluent Release Reports shall indude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Reg. Guide 1.21, Rev.1, with data summarized on a quarterly basis following the format of Appendix B thereof.
2.3 The Radioactive Effluent Release Reports shall indude the following information for each type of solid waste shipped offsite during the report period:
- a. container volume,
- b. total curle quantity (specify whether determined by measurement or estimate),
- c. principal radionuclides (specify whether determined by measurement or estimate),
- d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
- s. type of shipment (e.g., LSA, Type A, Type B) and
- f. solidification agent (e.g., cement).
2.4 The Radioactive Effluent Release Reports shaR indude a summary of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period ,
2.5 The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part Ill Section 8.2.
2.6 The Radioactive Effluent Release Reports shall indude the instrumentation not retumed to OPERABLE status within 30 days per ODCM Part I Controls 2.1.1b and 2.2.1b.
179.0 mm
i Number TMI Radiologichl Controls gp DepvuTwital Procedure 6610-PLN-4200.01 Troe Asvmon No.
Offsite Dose Calculation Manual (ODCM) 11 2.7 The Radioactive Effluent Release Report to be submitted shall include an arnual 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 of wind speed, wind direction, atmosphere stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distnbution of wind speed, wind direction, and atmospheric stabilty.
. l 2.8 The Radioactive EfRuent Release Report shaR Include an assessment of the radiation doses due to ;
the radioactive liquid and gaseous effluents released from the unit or station during the previous l calendar year. l l
I 2.9 The Radioactive EfRuent Release Report shaR include an assessment of the radiation doses from radioactive liquid and gaseous efRuents to MEMBERS OF THE PUBUC due to their actMties inside the SITE BOUNDARY during the report period. All assumptions used in making these assessments
- (i.e., specific actMty, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequercy and measurement) shall be used for determining the gaseous pathway doses. The assessment of i.diation doses shah be pakanied in accordance with this ODCM
+ 2.10 The Radioactive EfRuent Release Report shaR also include an assessment of radletion doses to the likely most exposed real indMdualpom reactor releases and other nearby uranium fuel cycle ps including doses from primary ofRuent pathways and direct radiation for the previous 12
/ consecutive months to show conformance with 40 CFR 190
- Environmental Radiation Protection Standards for Nuclear Power Operation.' Acceptable methods for calcidating the dose contributions from liquid and gaseous effluents are given in Reguiatory Guide 1.109, Rev.1.
.. I l
e 180.0 mm
Number gggy TMl Radiologichl Controls Departmental Procedure 6610-PLN-4200.01 True Asweion No.
Offsite Dose Calculation Manual (ODCM) 11 3.0 PANT IV REFERENCES 3.1 Radiological Assessment Branch Technical Position, Revision 1, November 1979 3.2 Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and
> Releases of Radioactive Materials in Liquid and Gaseous Effluents from Ught-Water-Cooled Nuclear Power Plants," Revision 1, June 1974
)
l 3.3 TMI-1 Technical Specifications, attached to Facilty Operating Ucense No. DPR-60 )
3.4 Title 40, Code of Federal Regulations, " Protection of Environment" 3.5 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, Appendk I," Revision 1, October 1977 3.6 Title 10, Code of Federal Regulations, " Energy
- 3,7 Regulatory Guide 1.111, " Methods of Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Ught-Water-Cooled Reactors," Revision 1, July 1977
~
3.8 Regulatory Guide 1.112, " Calculation of Releases of Radioactive Materials in Gaseous and Uquid Effluents from Ught-Water-Cooled Power Reactors,* Revision 0-R, Apri 1976 .
- Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendk I,' Revision 1, Apr91977 181.0 me, i
Number g I TMl Radiologicil Cortrols Departmental Procedure 6610-PLN-4200.01 Tre. ammon No.
)
Offsite Dose Calculation Manual (ODCM) 11 !
APPENDIX A P,- Pathway Dose Rete Parameter P, (Inhalation) = k' (BR) DFA, (Eq A-1)
Where:
P, = the pathway dose rate parameter for radionuclide, I, (other than noble gases) for the inhalation pathway, in mrem /yr per microcurie /m3 . The dose factors are based on the crtical indMdual organ for the child age group.
k' = conversion factor,1ES pCi/ microcurie 3
BR = 3700 m /yr, breathing rate for chid (Reg. Guide 1.109, Rev.1, Table E-5)
DFA,= the maximum organ inhalation dose factor for the infant age group for the ith radionuclide (mrem /pCl).
Values are taken from Table E-10 Reg. Guide 1.109 (Rev.1).
Resolution of the units yields: (ODCM Part ill Table 4.6)
~8 (Eq A-2)
P, (inhalation) = 3.7E9 DFA, (mrom/yr per pCl/m )
NOTE The latest NRC Guidance has deleted the requirement to determine P, (ground plane) and P, (food). In addition, the critical age group has been changed from infant to chid.
O E1 -1 m.
l l
l Number l gggy TMI RadiologicaT Controls Departmental Procedure 6610-PLN-4200.01 l
l True . Revision No. I i
Offsite Dose Calculation Manual (ODCM) 11 APPENDIX B Ri-Inhalation Pathway Dose Factor 3
R, = k' (BR) (DFAiy) (mrom/yr per microcurie /m ) (Eq B-1)
Where: -
k' = conversion factor,1E6 pCl/ microcurie 8
BR = t,reathing rate, 1400,3700,8000,8000 m /yr for infant, child, teenager, and adult age groups, respectively. (Reg. Guide 1.109, Rev.1, Table E-5)
DFAi ,= the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the Ith radionuclide, in mrem /pCl. -The total body is considered as an organ in the selection of DFAi ,,, .
Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Rev.1).
Resolutions of the units yields: .
Ri = (1.4E9) (DFA ,,,,)
i Infant (ODCM Part 111 Table 5.2.1')~
Ri = (3.7E9) (DFA ,,,,)
i child (ODCM Part'lli Table 5.2.2)'
Ri = (8.0E9) (DFA ,,,,)
i teen and adult (ODCM Part lll Tables 5.2.3 and 5.2.4) l E2-1 m l
i Number
- TMI Radiologich1 Controls gINI Departmental Procedure 6610-PLN-4200.01 Asvision No.
Title 11 Offsite Dose Calculation Manual (ODCM)
- APPENDIX C Ri- Ground Plane Pathway Dose Factor (Eq C-1)
R3 = k' k' (SF) (DFG;) [(1-e M/AJ Where:
k' = conversion factor,1E6 pCl/ microcurie k" = conversion factor,8760 hr/yr A=3 decay constant for the P radionuclide, sec
t= the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108sec. (15 yrs), Reg. Guide 1.109 (Rev.1), Appendix C 2
DFG,= the ground plane dose conversion factor for the P radionuclide (mrem /hr per pCl/m ). Values are taken from Table E-6, Reg. Guide 1.109 (Rev.1). These values acolVto all aos aroups.
SF = 0.7, shielding factor, from Table E 15 Reg. Guide 1.109 (Rev.1)
Reference ODCM Part 111 Table 5.3.1 4
4 w
S E3-1 m.
Number
^
'gggy TMi Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 3 l
APPENDM D Ri - Grass Cow-Milk Pathway Dose Factor j R, = k' [(Q, x U,) / (A, + J.)] x (F,) x (r) x (DFV x l((f. x f)/Y,) + ((bf, x f,) ed fh)/Y,] e'rf (Eq D-1)
Where:
k' = conversion factor,1ES picocurie / microcurie (pCi/pci)
O, - cow consumption rate, 50 kg/ day, (Reg. Guide 1.109, Rev.1) goat consumption rate,6 kg/ day, (Reg. Guide 1.109, Rev.1, Table E-2) ,
- U, = Receptor's mik consumption rate; 330,330,400,310 liters /yr for infant, chBd teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev.1) i 8
Y, - agricultural productivity by unit area of pasture feed grass,0.7 kg/m (NUREG-0133)
Y, = agricultural productivity by unit area of stored feed,2.0 kg/m 8(NUREG4133) e i F= stable element transfer coefficient (Table E-1, Reg. Guide 1.109, Rev.1) r= fraction of deposited acthty retained in cow's feed grass,0.2 for particulates,1.0 for radiciodine 1 (Table E-15, Reg. Guide 1.109, Rev.1) {
DFlw= the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev.1)
J, = decay constant for the ith radionuclide, sec' l
A,, = decay constant for weathering, 5.73 x 10'see' (NUREG 0133); based on a 14 day half life t, = 1.73 x 10' sec, the transport time from pasture to cow to milk to receptor (Table E-15, Reg.
Guide 1.109, Rev.1), or 2 days t, = 7.78 x 10'sec, the transport time from pasture to harvest to cow to mik to receptor (Table E-15, Reg. Guide 1.109, Rev.1), or 90 days f, = 1.0, the fraction of the year that the cow is on pasture f, = 1.0, the fraction of the cow feed that is pasture grass whBe the cow is on pasture l
r 9
E4-1 m=
l l
l
Number g gp TMI Radiologicsl Controls 6610-PLN-4200.01 De@ureTe Procedure Ties Revmon No.
Offsite Dose Calculation Manual (ODCM) 11 APPENDIX D (Cont'd)
The concentration of tritium in mBk is based on the airbome concentration rather than the deposition. Therefore, R; is based on (X/Q):
RC = k'k"' F, Q, U,DFQ (.75 [.5/H]) (Eq D-2)
Where:
k"' = IE3 grams /kg H= 8 grams /m8, absolute humidly of the atmosphere
.75 = fraction of the total feed grass mass that is water
.5 = ratio of the specific actMty of the feed grass water to the atmospheric water (NUREG-0133)
DFlw= the ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev.1) ._
M other parameters and values are as given abgve. -
NOTE Goet-mik pathway factor, R,, wHl be computed using the cow-milk pathway factor equation. F, factor for goatanilk will be from Table E-2 Reg. Guide 1.109 Rev.1.
Reference:
ODCM Part til Tables 5.4.1 to 5.4.4 O
E4-2 me
1 Number ;
Nuclear TMI RadiologicaFControls De,,,tmen e,ocedure 6610-PLN-4200.01 u, Revisen No.
Offsite Dose Calculation Manual (ODCM) 11
- APPENDIX E Ri - Cow-Meat Pathway Dose Factor R=3 k' [(Q, x U ,) / Q + 4)]'x (F,) x (r) x,l f(DF6) x i
(Eq E-1),
[((f, x f.)/Y,) + ((l-f,f,) e ' l h)/Y,] x e Where:
k' = corwersion factor,1E6 picoeurie/ microcurie (pCl/pci) ~
0, - cow consumption rate,50 kg/ day, (Reg. Guide 1.109, Rev.1)
U, = Receptor's meet consumption rate; 0,41,65,110 kg/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev.1)
F, = the stable element transfer coefficients, days /kg (Table E-1, Reg. Guide 1.109, Rev.1) r- fraction of deposited activity retained in cow's feed gratss,0.2 for particulates,1.0 for radioiodine (Table E-15, Reg. Guide 1.109, Rev.1)
DFlw= the ingestion dose factor for organ, o[and the Ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev.1) decay constant for the radionuclide i, sec4 A= 3 4 = decay constant for weathering,5.73 x 10-7 seed (NUREG4133), based on a 14 day half ilfe s
t, = 1.73 x 10 sec, the transport time from pasture to receptor (NUREG4133) >
8 t, = 7.78 x 10 sec, the transport time from crop to receptor (NUREG4133) 2 Y, = agricultural productivty by unit area of pasture feed grass,0.7 kg/m (NUREG-0133) 2 Y, = agricultural prodactivity by unt area of stored feed,2.0 kg/m (NUREG4133)
~
f, = 1.0, the fraction of the year that the cow is on pasture f, = 1.0, the fraction of the cow feed that is pasture grass whle the cow is on pasture i The concentration of tritium in meat is based on the airbome concentration rather than the deposition. Therefore, R4 is based on (X/Q): .
l R = k'k'" F, Q, U, (DFLw) x 0.75 x (0.5/H]) (Eq E-2)
Where:
A!! terms are as defined above and in Appendix D.
Reference:
ODCM Part 111, Tables 5.6.1 to 5.6.4 E5-1 mm I
Numtwr
. jggy TMI RadiologicaTControis Departmental Procedure 6610-PLN-4200.01 Trtie Rwiston No.
o Offsite Dose Calculation Manual (ODCM) 11 APPENDIX F Ri- Vegetation Pathway Dose Factor R, = k' x [r/ (Y, (A + Q)] x (DF() x [(U 3 l
at)I e#L + Us AsI e h)
(Eq F-1)
Where:
k' = 1E6 picocurie / microcurie (pCl/pci) , I ULA= the consumption rate of fresh leafy vegetation. O, 26, 42, 64 kg/yr for irdant, child, teenager, or adult age groups, respectively (Reg. Guide 1.109, Rev.1) j Us a- the consumption rate of stored vegetation,0,520,630,520 kg/yr for infant, child, teenager, or adult age l groups respectively (Reg. Guide 1.109, Rev.1) l f=g the fraction of the annual intake of fresh leafy vegetation grown locally, = 1.0 (NUREG4133) f, = the fraction of the stored veg i.iica grown locally = 0,76 (Is UP.004133) 4 t=g the average time between harvest of leafy vegetation and its consumption,8.6 x 10 seconds ,
[ Table E-15, Reg. Guide 1.109, Rev.1 (24 hrs)] ]
8 1=3 the average time between harvest of stored leafy vegetation and its consumption, 5.18 x 10 seco@s,
[ Table E-15, Reg. Guide 1.109, Rev.1 (60 days)]
2 I l y, = the vegetation ares density,2.0 kg/m (Table E-15, Reg. Guide 1.109, Rev.1) l AA other parameters are as previously defined.
The concentration of tritium in vegetation is based on the airbome concentration rather than the deposition.
Therefore, Ri is based on (X/Q) -
R L
= k'k"' [U a It + U'a fe] (DFQ) (.75 [.5/H]) (Eq F-2)
Where:
l All terms are as defined above and in Appendix D.
l
Reference:
ODCM Part lil, Tables 5.7.1 to 5.7.4 m.
ES-1 mm 1
t _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . ._ _ ]
Number NUgEI TMI Radiological Controis Departmental Procedure
- a. 6610-PLN-4200.01 Awoon No.
Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES (Page 1 of 4)
Parameters Used in Dose Factor Calculations
, Origin of Value Table in Section of Site-Parameter Value R.G.1.109 NUREG4133 Spedric
- For P, ***
DFA Each radionucide E-9 Note 1 BR 3700 m'/yr (child) E-5
" Var Ri (Vegetation)*** ~
r Each element type . E-1 Y, 2.0kg/nf E-15 Aw 5.73 E-7 sec' 5.3.1.3 DF( Each age group and radionuclide E-11 thru E-14 Note 1 U,' Each age group E-5 f, 1.0 5.3.1.5 t, 8.6 E + 4 seconds E-15 U,' Each age group E-5 f, 0.76 5.3.1.5 t, 5.18 E + 6 seconds E-15 H 8.0 grams /kg 5.2.1.3
- For Ri (Inhalation)***
BR Each age group .
E-5 DFA, Each age group and -
E-7 thru E-10 Note 1 nuclide 4
6 E7-1 mm 4
/
Nwnber Nuclear ' "* S"=' ""*
Departmental Procedure 6610-PLN-4200:01 Tee hason No.
Offsite Dose Calculation Manual (ODCM) 3 APPENDDC A-F REFERENCES (Page 2 of 4)
Parameters Used in Dose Factor Calcuistions Origin of Value Table in Section of Site-Parameter Value R.G.1.109 NUREG.0133 Specific
- For R, (Ground Plane)
- 9
'SF 0.7 E-15 ,
DFG, Each radionuclide E4 t 4.73 E + 8 sec 5.3.1.2 e
- For Ri (Grass / Animal / Mast) ***
Q,(Cow) 50 kg/ day E4 Q, (Gost) 6 kg/ day E-3' Ref. Only U, Each age Group E-5 Jw 5.73 E-7 sec' 5.3.1.3 F, (Both) Each element E-1 r Eadi element type E-15 DFL, Each age group and nuclide E-11 thru E 14 Note 1 f, 1.0 5.3.1.3 Note 2 f, 1.0 5.3.1.3 Note 2 Y, 0.7 kg/rn' E-15 t, 7.78 E + 6 see E-15 Y, 2.0 kg/m' E-15 t, 1.73 E + 6 see E-15 H 8.0 grams /kg -
5.2.1.3 E7-2 mm
Number E Nuclear TrJe
' "*d"**' o a'
Departmental Procedure 6610-PLN-4200.01 Rowssen No.
Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES (Pege 3 of 4)
Parameters Used in Does Factor Calculations I
Origin of Value Table in Secnon of Site-Parameter Value R.G.1.109 NUREG4133 Se
- For R, (Grose/ Cow / Milk) ***
0, 50. kg/ day E-3 U, Each age group E-5 Aw 5.73 E-7 sec' 5.3.1.3 F. Each element '-
E-1 r Each element type _. E-15 DFL, Each age group and nuclide E-11 thru E-14 Note 1 ,
Y, 0.7 kg/m' E-15 t, 7.78 E + 6 sec E-15 Y, 2.0 kg/m' E-15 t, 1.73 E + 5 esc E-15 f, 1.0 5.3.1.3 f, 1.0 5.3.1.3 H 8.0 grams /kg 5.2.1.3 e
S D
mmo.r gdgy TMl Radiological Controis Departmental Procedure r.o. 6610-PLN-4200.01
% no.
Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES (Page 4 of 4)
NOTES 1.
Inhalation and ingestion dose factors were taken from the indicated source. For each age group, fo nuclide. the organ does factor used was the highest dose factor for that nuclide and age group in t referenced table.
2.
Typically beef cattle are raised all year on pasture. Annual land surveys have indicated that the small number of goats raised within 5 mise typically are used for grass control and not food or msk. '
Nevertheless, the goats can be treated as full meet sources where present, despite the fact that their numbers cannot sustain the meat consumption rates of Table E-5, NUREG 0133.
REFERENCES 1.
Regulatory Guide 1.100, " Calculation of Annual Doses to Man from Routine Releases of henctor EfR the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1 October 1977.
2.
TMI-1 Technical Specincations, attached to Factity Operating Ucense No. DPR-50.
3.
NUREG4133, Treparation of Radiological Effluent Technical Sp+ ~--*-w for Nudear Power Plants,"
October 1978.
O
+
9 O
NI I-