Text

Rev 16 to Procedure 6610-PLN-4200.01, Odcm
	ML20217M725
Person / Time
Site:	Three Mile Island
Issue date:	06/22/1997
From:	; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20217M698	List: ML20217M694; ML20217M719; ML20217M725;
References
	6610-PLN-4200.0, NUDOCS 9805050098
	Download: ML20217M725 (204)
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04 17-98 11:13:03 Number Nder 7"' aadia'oa'ca' c atro'=

Departniental Procedure 6610 PLN-4200.01 me mvi. ion No.

Offsite Dose Calculation Manual (ODCM) 16 Appitcabaty/m+;+ Calculate offsite doses due to radioactive Naponsibb Omco Effeedve Dem effluents for demonstrating compliance with Site Technical Specifications 10 CFR 20 & 10 CFR 50 - Appendix ! 6610 06/30/97 This document is within OA plan scope X Yes No Safety Reviews Required X Yes No List of Effective Pages Eggg Revision Pace Revision Paae Revision a P,agg Revision 1,0 18 21.0 15 41.0 15 61.0 15 2.0 16 22.0 15 42.0 15 62.0 15 3.0 11 23.0 15 43.0 15 63.0 15 4.0 15 24.0 15 44.0 15 64.0 15 5.0 15 25.0 15 , 45 0 15 65.0 15 6.0 '15 26.0 '15 46.0 15 66.0 15 7.0 15 27.0 15 47.0 15 67.0 15 8.0 15 28.0 15 4e,0 15 68.0 15 9.0 15 29.0 15 49.0 15 69.0 15 10.0 15 30.0 t5 50.0 15 70.0 15 11.0 15 31.0 15 51.0 15 71.0 15 .

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Offsite Dose Calculation Manual (ODCM) 16 Ust of Effecthe Pages (Cont'd) fagg a Revision fggg Revision fage Revision fg[g Revision !

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Title Asvision No, i Offsite Dose Calculation Manual (ODCM) 11 INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the GPUNC Three Mile faland Nuclear Station (TMINS) Unit 1 and Unit 2 PDMS Technical Specifications and implements TMl radiological effluent controls. The ODCM contains the controls, bases, and surveillance regilrements for liquid and gaseous radiological effluents. In addition, the ODCM describes the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents. This document also describes the methoddogy used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm / trip set points. Liquid and Gaseous Radweste Treatment System configurations are also induded.

The ODCM also is used to define the requirements for the TMINS radidogical environmental monitoring prog am (REMP) and contains a list and graphical description of the specific sample locations used in the REMP.

The ODCM is maintained at the Three Mie Island (IMI) site for use as a reference guide and training document of !

accepted methoddogies and calculations. Changes in the calculation methods or parameters will be incorporated l

Into the ODCM to ensure the ODCM represents the present methoddogy in all appilcable areas. GPUNC Iniflated changes to the ODCM will be implemented in accordance with the TMI-1 and TMl-2 PDMS Technical Specifications.

The ODCM follows the methodology and models suggested by NUREG-0133, and Regulatory Guide 1.109 Revisbn 1 for calculation of off-site doses due to plant emuent releases. Simplifying assumptions have been applied in this manual where applicable to provide a more workable document for implementation of the Radiological Effluent Controls requirements.

GPUN implements the TMi Radidogical Effluent Contrds Program and Regulatory Guide 1.21. Revision 1 (Annual Radioactive Effluent Release Report) requirements by use of a computerized system used to determine TMI effluent releases and to update cumulative affluent doses.

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Offsite Dose Calculation Manual (ODCM) 15 TABLE OF CONTENTS PARTI TMI-1 RADIOLOGICAL EFFLUENT CONTROLS I Section Page 1.0 DEFINITIONS 15.b Table 1 1, Fregrancy Notations 18.0 2.0 RADIOLOG'dAL EFFLUENT CONTROLA AND BASES f 21.0 2.1 Eadioactive Efiluent instrumentation 21.0 2.1.1 Radioactive Uquid Emuent instrumentation 21.0 2.1.2 Radioactive Gaseous Process and Emuent Monitoring instrumentation 24.0 !

Table 2.1 1, Radiondive Liquid Emuent instrumentation 22.0 Table 2.1-2, Radicacttve Gaceous Process and Efiluent Monitoring instrumentation 25.0 2.2 Radiologica' Emuent Controls 31.0 2.2.1 Uquid Emuent Controls 31.0 2.2.2 Gaseous Emuent Controls 34.0 2.2.3 Total Radioactive Emuont Controls 39.0 3.0 SURVEILLANCES 40.0 3.1 Radioactive Effluent instrumentation 40.0 3.1.1 Radioactive Uquid Emuent instrumentation 40.0 3.1.2 RadioactNo Gaseous Process and Emuent Montoring instrumentation 43.0 Table 3.1 1, Radioactive Uquid Emuent Monitoring instrumentation Survetance Requirements 41.0 Table 3.1-2, Radioactive Gaseous Process and Emuent Monitoring instrumentation 44.0 SurveRance Requirements 3.2 Radiological Emuents 49.0

.3.2.1 Uquid Emuents 49.0 3.2.2 Gaseous Emuents 55.0

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TA8t.E OF CONTENTS PARTI TMl-1 RADIOLOGICAL EFFLUENT CONTROLS Section Page i Tabif. J.2-1, hadioactive Uquid Weste Sampling and Analysis Program 51.0 Tab e 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 57.0 3.2.3 Total Radioecsa EMuents 62.0 4.0 PART I REFERENCES 63.0 9

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TABLE OF CONTENTS '(Cont'd)

PART!! TM8-2 RADIOLOGEAL EFFLUENT CONTROLS ,

l Seelon Page 1.0 DEFINITIONS 65.b i Table 1.1, Frequency Notation 67.0 -

2.0 RADIOLOGICALEFFLUENT CONTROLS AND BASES 68.0 2.1 Radioactive Emuent instrumentation 68.0 2.1.1 Radioactive Uquid Emuent instrumentation 21.0 2.1.2 Radioactive Gaseous Process and Emuent Monitoring instrumentation 68.0 Table 2.1,2, Radioactive Gaseous Process and Emuent Monitoring instrumentation 70.0 l 2.2 Radioactive Emuent Controls 71.0 I O,

g 2.2.1 Uquid Emuent Controls 71.0 2.2.2 Gaseous Emuent Controls 73.0 2.2.3 Total Radbhotive Emuent Controls 77.0 3.0 SURVEILLANCES 79.0 3.1 Radioactive Emuent Instrumentation 79.0 3.1.1 Radioactive Uquid Emuent instrumentation 79.0 3.1.2 Radioactive Gaseous Process and Emuents Monitoring 'nstrumentation 79.0 Table 3.1-2, Radioactive Gaseous Process and Emuent Monitoring instrumentation 80.0 Survemance Requirements 3.2 Radiological Emuents 81.0 3.2.1 Uquid Emuents 81.0 3.2.2 Gaseous Emuents 83.0 Table 3.2-1, Radioactive Uquid Waste Sampling and Analysis Program 82.0 C Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 84.0

\b 3.2.3 Total Radioactive Emuents 87.0 6.0 sm.

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TABLE OF CONTENTS '(Cont'd)

PARTIf TMI-2 RADIOLOGICAL EFFLUENT CONTROLS I Page 4.0 PART11 REFERENCES M.0 a

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Offsita Dose Calculation Manual (ODCM) 15 TABLE OF CONTENTS PARTlli EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES.

Section Page 1.0 UQUID EFFLUENT MONITORS 90.b s i

1.1 TMI 1 and TMI-2 Uquid Radiation Monitor Set Points 90.0 f.2 TMl Uquid Release Points and Uquid Radiation Monitor Data 91.0 1.3 Control of Liquid Releases 93.0 2.0 l UQUID EFFLUENT DOSE ASSESSMENT 98.0 2.1 Uquid Ef9uents - 10 CFR 60 Appendbc l 98.0 2.2 TMI Uguld Radwaste System Dose Calcs Once per Month 100.0

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2.3 Altemative Dose Calculational Methodology 101.0 O3.0 UQUID EFFLUENT WASTE TREATMENT SYSTEM 106.0 3.1 TMI 1 Uquid Emuent Waste Treatment System 106.0 3.2 Operabaty of TMI-1 Uquid Effluent Waste Treatment System 107.0 3.3 TMI-2 Uquid ENuent Waste Treatment System 107.0 4.0 GASEOUS EFFLUENT MONITORS 110.0 4.1 TMI-1 Noble Gas Monitor Set Points 110.0 4.2 TMI-1 Particulate and Radionodire Monitor Set Points 112.0 .

4.3 TMI-2 Gaseous Radiation Moriltor Set Points 113.0 4.4 TMI 1 Gaseous EMuent Release Points and Gaseous Radiation Monitor Data 114.0 l 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 116.0 4.6 Control of Gaseous Emuent Releases 117.0 l

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Offsite Dose Calculation Manual (ODCM) 15 TABLE OF CONTENTS PART lli EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 129.0 5.1 Gaseous Effluents - Dose Rate Umits 129.0 5.1.1 Noble Gases 129.0 5.1.1.1 Total Body 129.0 5.1.1.2 Skin 130.0 5.1.'2 lodines and Particulates 131.0 5.2 Gaseous Ef8uents - 10 CFR 50 Appendix i 132.0 5.2.1 Noble Gases 132.0 5.2.2 lodines and Particulates 133.0 5.3 Gaseous Radioactive System Dose Calculations Once per Month 135.0 SA Altemative Dose Calculational Methodologies 136.0 6.0 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM 158.0 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System 158.0 6.2 Operabaty of the TMl-1 Gaseous Radwaste Treatment System 158.0 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 160.0 8.0 T1 WINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 161.0 8.1 Monitoring Program Requirements 161.0 8.2 Land Use Census 163.0 8.3 Interleboratory Comparison Program 165.0 a

9.0 PART lli REFERENCES 182.0 l 9.0 ana

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Two Revlekm k onsite Dose Calculation Manual (oDCM) 1s TABLE OF CONTENTS (Cont'd)

PART lli EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES l section Page

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TABl.ES Table 1.1 TMI 1 Liquid Rolesso Point and Liquid Radiation Monitor Data 94.0 Tabie 'f.2 TMI-2 Sump f N =h 95.0 Table 2.1 Liquid Dose Conversion Factors (DCF): DF, 102.0 Table 2.2 Bloeccumulation Factors BF, 105.0 Table 4.1 TMI 1 Gaseous Release Point & Gaseous Radiation Monitor Data 118.0 l Table 4.2 TMI-2 Gaseous Release Point & Gaseous Radiation Monitor Data 119.0 Table 4.3 Dose Factors for Noble Gases and Daughters 120.0 Table 4.4 Atmospheric Dispersion Factors for Three M5e letand - Station Vent 121.0 Table 4.5 Atmospheric Dispersion Factors for Three Mie Island - Ground Release 122.0 l

Table 4.6 Dose Parameters for Radiciodines and Radiondive Particulate, Gaseous, Effluents 123.0 Table 5.2.1 Pathway Dose Factors, S Infant, inhalation 137.0 Table 5.2 2 Pathway Dose Factors, R - ChDd, Inhaintion 138.0 Table 5.2.3 Pathway Dose Factors, R, . Teen, inhalation 130.0 Table 5.2.4 Pathway Does Factors, R, Adult, inhalation 140.0 Table 5.3.1 Pathway Dose Factors, R All Age Groups, Ground Plane - 141.0 1

Table 5.4.1 Pathway Dose Factors, R, Infant, Grase. Cow-Muk 142.0 Table 5.4.2 Pathway Dose Factors, R5 - Chud, Grass-Cow-Mik 143.0 Table 5.4.3 Pathway Dose Factors, R, Teen, GrassCm-Mak 144.0 Table 5.4.4 Pathway Dose Factors, R,- Adult, Grass-Cow-Milk 145.0 Table 5.5.1 Pathway Dose Factors, R, Infant, Grass-Goet-Milk 146.0 f

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Offsite Dose Calculation Manusi (ODCM) 15 l TALK.E OF CONTENT 5'(Cont'd) t 4

l PARTlli EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES l Section Page TABLES Table 5.5.2 Pathway Dose Factors, R, - Chld, Grass-Goat-Milk 147.0 Table 5.5.3 Pathway Dose Factors, R, - Teen, Grass Goet-M8k 148.0 Table 5.5.4 Pathway Dose Factors, R,- Adult, Grass-Goat-Mik 149.0 TaNe 5.E1 Pathway Dose Factors, R, Infant, Grass <ow-Meet 150.0 Table 6.6.2 Pathway Dose Factors, S Chad, Grass-Cow-Meet 151.0 Table 5.6.3 Pathway Dose Factors, R, - Teen, Grass-Cow-Meat 152.0 Table 5.6.4 Pathway Dose Factors, R,- Adult, Grass-Cow Meet 153.0 0 Table 6.7.1 Pathway Dose Factors, R, Infant Vegetation 154.0 l Table 5.7.2 Pathway Dose factors, R, - Chid, Vegetation 155.0 Table 5.7.3 Pathway Dose Factors, R, - Teen. Vegetation 158.0 Table 5.7.4 Pathway Dose Factors, R, Adult, Vegetation 157.0 l

Table 8.1 Sample Cogection and Analysis Requirements 166.0 Table 8.2 Reporting Levels for RadioactMty Concentrations in Environmental Samples 171.0 1

l Table 8.3 Detection Capab81 ties for Environmental Sample Analysis 172.0 j

i Table 8.4 TMINS REMP Station Locations - Air Particulate and Air lodine 174.0 l

Table 8.5 TMINS REMP Station Locations - Direct Radiation (TLD) ' 174.0 l-Table 8.6 TMINS REMP Station Locations - Surface Water 176.0 Table 8.7 TMINS REMP Station Locations Aquatic Sediment 176.0 Table 8.8 TMINS REMP Station Locations Muk 177.0 Table 8.9 TMINS REMP Station Locations - Fish 177.0 Table 8.10 T' MINS REMP Station Locations - Food Products 178.0 11.0 titu l

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Offsite Dose Calculation Manuel (ODCM) 15 TABLE OF CONTENTS '(Cont'd)

PART111 EFFLUEM DATA AND CALCULATIONAL METHODOLOGIES.

secuen Page TABLES MAP 8.1 Three MEe island Nuclear Station Locations of Radiological Environmental 179.0 Monitoring Program Stations within 1 MEe of the She l

MAP 8.2 Three Mae leland Nuclear Stat'on Locations of Radiological Erwironmentel 180.0 Monitoring Program Stations within 5 mies of the Site j

MAP 8.3 Three M5e Island Nuclear Station Lexations of Radiological Environmental 181.0 ]

Monitodng Program Stations Greater than 5 muse from the Site l FIGURES Figure 1.1 . TMi-1 Liquid EfRuant Pathways 96.0 Figure 1.2 TMI 2 Liquid Eleuent Pathways 97.0 Figure 3.1 TMI 1 Liquid Radwaste 109.0 Figure 3.2 TMi 1 Liquid Waste Evaporators 109.0 Figure 4.1 TMl-1 Gaseous Effluent Pathways 124.0 Figure 4.2 TMI 1 Auxiiery & Fuel Handling BuOdings Efiluent Pathways '125.0 ;

Figure 4.3 TMI-1 Reactor Buuding Efouent Pathway 126.0 !

Figure 4.4 TMI-1 Condenser Oflges EfRuont Pathway 127.0 Figure 4.5 TMI-2 Geseous Efnuent Futration System / Pathways 128.0 Figure 6.1 Waste Gas System 159.0 i l

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, TA8LE OF CONTENTS (Cont'd)

PART IV REPORTING REQUIREMENTS Section Page 1.0 TMl ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 185.0 2.0 TMi ANNUAL RADIOACTIVE EFPLUENT RELEASE REPORT 185.0 3.0 PART IV REFERENCES 188.0 APPENDICES A. Pathway Dose Rate ParameLa (P) E1 1 B. Inhalation Pathway Dose Factor (R) E21 C. Ground Plane Pathway Dosa Factor (R) E3-1 D. Grass-Cow-MRk Pathway Dose Factor (R) E4-1 E. Cow-Meat Pathway Dose Factor (R) ES-1 F. Vegetation Pathway Dose Fr,4or (R) E6-1 APPENDIX A F REFERENCES E7-1 e

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PARTI TMI-1 RADIOLOGICAL EFFLUENT CONTROLS 14.0 mw

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Offsite Dose Calculation Manual (ODCM) 11 1.0 DEFINITIONS 4

The following terms are defined for uniform interpretation of these controls and surveillances.

1.1 Reactor Operating Conditions 1.1.1 Cold Shutdown The reactor is in the cold shutdown condition when it is suberft! cal by at least one porcent 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 subcritical by at least one percent detta k/k and Tavg is at or greater than 625' F.

1.1.3 Reactor Critical The reactor is critical when the neutron chain reaction is self. sustaining and Keff = 1.0.

1.1.4 Hot Standby The reactor is in the hot standby condition whan 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 b less than two percent of rated power. Rated power is defined in Technical Specif'cation Definition 1.1.

I 1.1.5 Power Operation i 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 defined in Technical Specification Definition 1.1.

1.1.6 Refueling Shutdown The reactor is in the refueling shutdown condition when, even with all rods removed, 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 1.1.7 Refueling Operation 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 ,

i 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 tho startup mode when the shutdown margin is reduced with the intent of going critical.

1.1.10 Tave Tave is defined as the arithmetic average of the coolant temperatures in the hot and cold legs of the loop with the greater number of reactor coolant pumps operating, if such a distinction of loops can be made.

1.1.11. Heatup - Cooldown Mode The heatup-cooldown mode is tha range of reactor coolant temperature greater than 200* F j and less than 525' F. l 1.2 Operable A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, coollrig or r,eal water, lubrication or other auxiliary equipment that are '

i 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, amplifiers, 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 digital.

1.4 Instrumentation Surveillance 1.4.1 Channel Test A CHANNEL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practical to verify OPERABILITY, including alarm and/or trip functions.

1.4.2 Channel Check A CHANNEL CHECK shall be the qualitath/e 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.

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 CAllBRATION is a test, and adjustment (if necessary), to estab!Ish that the channel 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, induding 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 I-131 (microcurie / gram) which alone would produce the same thyrold dose as the quantity and isotopic mixture of l 131,1-132,1133, 1134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table ill 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 CALCUl.ATION MANUAL (ODCM) contains the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiologicel Environmental Monitoring Program. The ODCM also contains (1) the Radiological Effluent Controls, (2) the Radidogical Environmental Monitoring Program and (3) dea riptions of the Information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

1.7 Gaseous Radwaste Treatment The GASEOUS RADWASTE TREATMENT SYSTEM la the system designed and Installed to reduce radioactive gaseous effluent by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

1.8 Ventiation Exhaust Treatment System A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and Irmtalled to reduce gaseous radiolodine or radioactive material in particulate form in affluent by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing lodine or particulates from the gaseous exhaust system prior to the release to the environment.

Engineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEMS.

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15 1.9 Purge Purging PURGE or PURGING is the controsed process of discharging air or gas from a conAnement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that repiscement air or gas is required to purify the confinement

.1.10 Venting '

VENTING la the controlled process of discharging air as gas from a conEnement to mainteln temperature, pressure, humidty, concentration or other operating conditions in such a menner 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 MEM8ER(8) OF THE PUBUC shall induda au persons who are not occupationally associated with the plant. This category does not include employees of the GPU System. GPU contractors or vendors. Also excluded from this category are persons who enter the alte to service equipment or to make deliveries.

1.12 Site Boundary The SITE BOUNDARY used as the basis for the limhs on the release of gaseous effluents is as defined in Section 2.1.2.2 and shown on Figure 2.13 of the TMI 1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three Mile Island and between Three Mue leiend and Shelley leiend.

The SITE BOUNDARY used as the basis for the limits on the release of liquid affluents is as shown in Figure 1.1 in Part I of this ODCM i

1,13 Frequency Notation The FREQUENCY NOTATION specified for the performance of Survellance Requirements shall curi pund to the intenels defined in Table 1 1. AR SurveElance Requirements shall be performed within the speciRed time interval with a maximum alloweble extension not to exceed 25% of the l eurvemance interval. The 25% extension applies to all frequency intervals with the exception of T."

No extension is allowed for intervals designated T.'

Table 11 Frequency Notation Notation Frequency S Shiftly (once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months )

D Daay (once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )

W Weeldy (once per 7 days)

M Monthly (once per 31 days) 18.0 rm.

04-17-98 11:13:03 Number Nuclear ' a*d'd**'

Departmental Procedure

"d * -

6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 11 Notation Frequency Q Quarterly (once per 92 days)

S/A SemLAnnually (once per 184 days)

R Refueling interval (once per 24 months)

P S/U Prior to each reactor startup, if not done during the 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 limit for which the specified time interval for SurvelDance Requirements may be extended. It permits an allowable extension of the normal survellance interval to facultate surveillance scheduling and consideration of plant operating conditions that may not be suitable for cond'ucting the surveillance; e.g., transient conditions or other ongoing surveDianco or maintenance activities. It also provides flexibilty to accommodate the length of a fuel cycle for surveulances that are specified to be performed at least once each REFUEUNG INTERVAL lt is not intended that this provision be used repeated!y as a convenience to extend survellance intervals beyond that specified for surveillances that are not performed once each REFUEUNG INTERVAL Ukewise, it is not the intent that REFUEUNG INTERVAL surveillances be performed during power operation unless it is consistent with safe plant operation. The limitation of Section 1.13 is based on engineer!ng judgement and the recognition that the most probable retAt of any particular surveitance being performed is the verification of conformance with the Survellance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified survellance interval.

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14 17-98 11:13:03

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04-17-98 11:13:03 Number Nuclear ' "**doa**' c '*"* [- } _(/ Tive Departmental Procedure 6610-PLN-4200.01 Revision No. Offsite Dose Calculation Manual (ODCM) 15 Table 2.12 (Cont'd) Table Notation
At all times. *
** During waste gas holdup system operation. *** Operabity is not required when discharges are positively controlled through the closure of j WDG-V47 and where RMM (or RM.A4 and RM-AS). FT 149, and FT-150 are operable. ** During Fuel Handling BuHding ESF Air Treatment System Operation. # At all times during containment purging. ,
1
## At aR times when condenser vacuum is estabilshed. ### During operation of the ventilation system.
ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment provided that prior to initiating the release:
1. At least two independent samples of the tank's conterts are analyzed in accordance f with Table 3.2-2, item A, and ,
j
2. At least two technically qualified members of the Unit staff independently verify the release rate calculations and verify the discharge valve lineup.

3. The Director Operations & Maintenance TMI, shan approve each release. J Otherwise, suspend release of radioactive efnuent via tth pathway.
ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, efRuent releases via this pathway may cordinue provided the flow rate is estimated at least once per 4 hours. ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and the initial samples are analyzed for gross activity (gamma scan) within 24 hours after the channel has been declared 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 OPERABLE 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 hours. With both channels inoperable, a grab sample shall be conected and analyzed for the Inoperable gas chanteel(s): (a) at least once per 4 hours during degassing operations. (b) at least once per 24 hours during other operations (e.g. Feed and Bleed). 29.0 mm
)4-17-98 11:13:03 Nwntw g
p TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
m. m No.
Offsite Dose Calculation Manual (ODCM) 15 1 Table 2.12 (Cont'd)
2. If the inoperable gas channel (s) is not restored to service within 14 days, a special report shall be submined to the Regional Administrator of the NRC Region 1 Omco and a copy to the Director, Omce of Inspection and Enforcement within 30 days of dedering the channel (s) Inoperable. The report shal describe (a) the cause of the monitor inoperabIty, (b) action being taken to restore the instrument to service, and (c) action to be taken to prevent recurrence.
ACTION 31 With the number of channels OPERABLE less than required by the Minimum Channels OPERABW requirement, effluent releases via this pathway rney continue j provided that within four hours after the channel has been declared inoperable, samples are continuously colected with aux 8lary sampling equipment ACTION 32 With the number of channels OPERABE less than required by the Minimum Channels OPERABE requirement, emuent releases via this pathway may continue for up to 28 days, provided that one OPERABLE channel remains in service or is pieced in service within 1 hour. Ahor 28 days, or N one OPERABLE channel does not remain in servloe or la not pissed in servloe within 1 hour, the
, 2 of Technical Spoollication 3.0.1 apply, as if this Control were a Tech Spec Liralling Condition for Operation.
ACTION 33 With the number of channels OPERABLE less than required by the Minimum l Channels OPERAB2 mquirement, other restore the Inoperable channel to OPERABLE status within 7 days, or prepare and submit a special report within 30 days oudining the adion(s) taken, the cause of the Inoperabity, and plans and schedule for restoring the system to OPERABLE status. r 30.0 nm, e
04-17-981 t13 03 kmber e Ng I TMI Radiological Controls Departmental Procedure f 8610-PLN-4200.01 im. n vwon m. Offsite Dose Calculation Manual (ODCM) 15 2.2 Radioactive Emuent Controis 2.2.1 Liquid Emuent Controls 1 2.2.1.1 Uguld EMuent Concentration I CON 17tOL-1 The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limked to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appendtx B. Table 2, Column 2 for radionuclides other than dissotved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limked to 3 x 10* uCl/cc total activity. APPUCABluTY: At all times 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 This control is provided to ensure that the concentration of radioactive materia.; released in liquid waste emuent from the unit to unrestricted areas will be less than ten times the 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 I,10 CFR Part 50, to a MEMBER OF THE PUBUC and (2) the limits of 10 CFR Part 20.1301 to the population. The concentrdion limit for noble gases is based upon the assumption the Xe-135 le the controlling radioisotope and its 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 Uquid Efiluent Dose CONTROL The dose or dose commtment to a MEMBER OF THE PUBUC from radioactive materials in liquid effluents released frorn the unit to the SITE BOUNDARY shall be Ilmited: a. During any calendar quarter to less than or equal to 1.5 mrom to the total body and to less than or equal to 5 mrom to any organ. b. During any calendar year to less than or equal to 3 mrom to the total body and to less than or equal to 10 mrom to any organ. N APPUCABluTY: At all times 31.0 nm.
04-17-98 11:13:03 kmber [ ggy TMl Radiological Controis Departmental Procedure 6610-PLN-4200.01 ; ( . noe anwon m. Offsite Dose Calculation Manual (ODCM) 15 ACTION:
a. With the calculated does from the release of rm,unareeve materials in liquid afilueres exceeding any of the atxwe limits, p.gere anrf submit to the NRC Region i Administrator within 30 days, a Special Report which Ideralflee the cause(s) for ;
exceeding the limit (s) and defines the corrective actions to be taken to reduce the i releases of radioactive malerleis in liguid elliuents durin0 the remainder of the current calender quarter and during thisubesquent 3 calsndar quarters so that the cumuledvs does or does commitment to any individuel from such releases during these four calender quarters is within 3 mrom to the total body and 10 mrom to any organ. This Special Report sheH also include (1) the result of radiological analyses of the drinidng water source, and (2) the radiologimi Impact on finlohed drinidng water supplies with regard to the requirements of 40 CFR 141, Safe Drinidng Water Act. BASES i This control and associated action is provided to implement the requirements of Sections ll.A lil.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 flextilty and at the same time implement the guides set forth in Section N.A of Appendix 1 to assure that the releases of radioactive meterial in liquid elEuents wE be kept "as low as is reasonably achievableP. Also, for fresh water sites with drinidng water supplies which can be potentially affected by plant operations, thwe is reasonable assurance that the operation of the fac8ty wW not result in radionuclide concentrations in the finished drinidng water that are in excess of the requirements of 10 CFR 20. The does ceiculations in the ODCM implement The requirements in Section lil.A. of Appendk I that conformance with the guides of - Appendk I is to be shown by calculational procedures based on models and data such that the arvual exposure of a MEM8ER OF THE PUBUC through appropriate pathways is unlikely to be substantiaBy underestimated. The equations specined in the ODCM for calculating the doses due to the actual reisese rates of radioactive materials in Ilquid elevents are-consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Reiseses of Reactor Eilluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendk I,' Revision 1, October,1977, and Regulatory Guida 1.113, " Estimating Aquatic Dispersion of EIMuents from Accidental and Routine Reactor Releases for the Purpeee of implementing Appendk I," Aptt 1977. NUREG0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113. 2.2.1.3 Uquid Radweste Treatment System CONTROL:
~
The appropriate portions of the liquid redweste treatment system shall be used to reduce the radioactive materials in liquid westes prior to their discharge when the projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrom to any orgen in any calendar month. APPUCABluTY: At all times 32.0 m
04-17-98 11:13:03 Numbu l f NuciEI " "*d'd ** ""d' Departmental Procedure 6610-PLN4200.01
% Due Rwe No. l Offsite Dose Ca:culation Manual (ODCM) 15 ,
ACTION: 1
a. With radioactive liquid waste being dircharged without treatment and in i excess of the above limits, prepare and submit to the NRC Region l l Adtrinistrator within 30 days, a Special Report which includes the fdiowing information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperabilty,

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 requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases d radioactive materials in liquid O ofituents wHI 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 to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix 1 to 10 CFR Part 50. The intent of Section ll.D. Is to reduce effluents to as low as is r wably achievable in a cost effective manner. This contrd satisfies this intent by establishing a dose limit which is a anali fraction (25%) of Section ll.A of Appendix 1,10 CFR Part 50 dose requirements This margin, a factor of 4, constitutes a reasonable reduction. 2.2.1.4 Uquid Holdup Tanks CONTROL The quantity of radioactive material contained in each d the fdlowing tards shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.
a. Outside temporary tank APPLICABILITY: At all times.
ACTION:
a. With the quantity of radioactive materla! In any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit.
V 33.0 m
04 17-98 11:13:03 Netw ! gy WI Radiological Controls Departmental Procedure . 8810-PLN 4200.01 l 9 rue n w.n n onsite cosa calculason manual (oocu) 1s
. 1 BASES Restricting the quantty of radbedilve meterial contained in the specified tanks , provides assurance that in the event of en uncontrolled release of the tanks' l contents, the resulting cancentrations would be less than the limits of 10 CFR Part i 20.1001-20-20.2401. Appendtw B, Table 2, Column 2, at tbo r,mreet potable water supply and the nearest surface water supply in an unrestricted area.
2.2.2 Gaseous Elliuent Controls 2.2.2.1 Gaseous Eftuent Does Rate CONTROL: The does rate due to radioecove meterials released in gessous smuent from the site shall be limited to the following
a. For noble gases: less than or aquel to 500 mrom/yr to the total body and less than -
or aquel to 3000 mrom/yr to the sidn, and
b. For 1-131,1-133, trklum and all radionudidos in particulate form with half lives O greater then 8 days: less then or equel to 1500 mrom/yr to any organ.
APPUCA81UTY: At all times. ACTION: With the telease rate (s) exceeding the above limts, immediately decrease the release rate to comply with the above limit (s). BASES The control provides reasonable assurance that the annual does at the SITE BOUNDARY from gaseous elliuent from all unts on the she wll be within the annual does limts of 10 CFR Part 20 for unrestricted stees whRe providing sufficient operational flextAlly in establishing affluent montor setpoints. These gaseous release rates provide reasonable assurance that radioactive meterial discharged in gaseous eMuent wE not result in the exposure of a MEMBER OF THE PUBUC in an unrestricted area, other within or outside the SITE BOUNDARY, to annual average concentrations exceeding the values specmod 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 'ho atrnospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at at times, the comeponding gamma and beta does rates above background to a MEMBER OF THE PUBUC at or beyond the SITE BOUNDARY to less then or equel to 500 mrom/ year to the total body or to less then or equal to 3000 mrom/ year to the eldn. These rolesse rate limits also restrict, at au times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equel to 1500 mrom/ year (NUREG 0133). 34.0 m
'04-17-98 11:13 03 mmen y TMI Radiological Controls Departmental Procedure 8610-Pt.N-4200.01 nn. wwon m. Offsite Dose Calculation Manual (ODCM) , 15 9999 namaana EMuents Dose-Noble Gases CONTROL: The air does due to noble gases released in gaseous alliuents from the unit to areas at and beyond the SITE BOUNDARY ahall be limited to the following '
a. During any calendar quarter: less than or equal to 6 mrad for gamma radiation and less than or equal to 10 mrad for bets radiation and, i

b. During any calendar year: less than or equal to 10 mrad for gammq radiation and l less than or equal to 20 mrad for beta radiation.
APPLICABILITY: At all times. l ACTION:
a. With the calculated air dose from radioactive noble gases in gaseous elliuents
Ming any of the above limits, prepare ard submit to the NRC Region I l Administrator within 30 days, a Special Report which identilles the cause(s) for 1 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 assyre that enhaary=nt releases wg be in ec.r.p; .co with the above limits.
BASES TNs control apphes to the release of radioactive materials in gaseous emuents frorn TMI-1. TNs control and maded action is provided to implement the requirements of Section ll.B. Ill.A and IV.A of Appendk I,10 CFR Part 50. The Control implements the guides not forth in Section ll.B of Appendk I. The ACTION statements provide the required operating flexibuity and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in gaseous ofiluents wt be kept "as low as is reasonably achievable." The Survellance Requirements implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBlJC through the appropriate pathways is unlikely to be substantially underestimated The dose calculation methodology and parameters established ir; the ODCM for calculating the doses due to the actual reL*ase rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Release of Reactor Emuents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Emuents in Routine Releases from Light Water Cooled Reactors."
Revision 1, Jtdy 1977. The ODCM equations provided for determining the air doses at and beyond the Sf ff BOUNDARY are based upon the historical average atmospheric conditions. NUREG4133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. 35.0 mi,
04-17-98 11:13:03 Nurnber O gg I TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 nw an No. V . m. Offsite Dose Calculation Manual (ODCM) 15 2.2.2.3 Dose lodine-131, lodine 133, Tritium, and Radionuclides in Particulate Form CONTROi.: The dose to a MEMBER OF THE PUBUC from lodine-131, lodine-133 Trttlum, and all radionucildes in particulate form wth half INes greater than 8 days, in gaseous effluents released from the imit to areas at and beyorxi the SITE BOUNDARY shall be limited to the following-
a. During any calendar quarter: less than or equal to 7.5 mrom to any organ, and

b. During any calendar year: less than or equal to 15 mrom to any organ.
APPUCABluTY: At all times. ACTION: Wah the calculated dose from the release of lodine-131, lodine-133, Trtium, and radionuclides in particulate form with half lives greater than 8 days. In gaseous effluents exceeding any of the above limits, prepare and submt to the NRC Region i Administrator , within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and O 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 radioactfue rnatorials in gaseous effluents from TMI-1. This control and associated action is provided to implement the requirements of Section ll.C. lil.A and IV.A of Appendix 1,10 CFR Part 50. The Controls are the guides set forth in Section ll.C of Appendix 1. The ACTION 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 survealance requirements implement the requirements in Section lit.A of Appendix I that conformance with the guides of Appendix 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 unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent wth the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Efiluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October, 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Ught-Water Cooled Reactors,"
Revision 1 July,1977, These equations also provide for dotarmining the actual doses based upon the historical average atmospheric conditions. The release rate controls for ledine-131, G lodine-133, tritium and radionuclides la particulate form with half lives greater than B days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the CITE BOUNDARY. The pathways that were examined in the development of these 36.0 m '.
04-17-98 11:13.03 Number NUCIMr TMl Rad.Jogical Controls Departmental Procedure 6610 PLN-4200.01 Title Rehon No. Offstte Dose Calculation Manual (ODCM) 15 calculations were: 1) indMdual inhalation of alrhome radionuc' ides,2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man,3) i depoettion onto grassy areas where muk animals and meet producing animals Draze with l consumption of the mik and meat by man, and 4) depealtion ora the ground wth subsequent exposure of man. l
. 1 2.2.2.4 Gaseous Redweste Treatment System 1
1 CONTROL The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM sher be OPERABLE. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in the gaseous waste prior to their discharge when the montNy projected gasoous effluent air
doses due to untreated gaseous effluent releases from the unt would exceed 0.2 mrad for l
gamma radiation and 0.4 mrad for beta redletion. The a@upiste portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the mortNy p*ojected doses due to gaseous effluent releanes from the site would exceed 0.3 mrom to any organ. j APPUCABluTY: 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 wth gaseous l waste being discharged wthout treatment and in excess of the above !!mits, prepare l and submit to the NRC Region l Administrator wthin 30 days, a Special Report which includes the following information:

1. Identification of the Inoperable equipment or subsysterns and the reason for inoperabilty,

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 Tha 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 assu ance that the releases of radioactive materials in gaseous effluents wHl be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Crkerlon 60 of Appendix A to 10 CFR Part 50, and the design objectives grven in Section ll.D of Appendix 1 to 10 CFR Part 50. The specified limits O goveming the use of appropriate portions of the systems were specifimi as a.sultable l Q fraction of the Guida set forth in Sections ll.B and 11.C of Appendix 1,'10 CFR Part 50, for gaseous effluents. 37.0 un. 1 1
04-17-98 11:13:03 Number Nuclear ' "'d'*S*aa* Departmental Procedure 6610-PLN-4200.01 9Tm nwen m. Offsite Dose Calculation Manual (ODCM) 15 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 equel to 4% by volume. AVAILAB(UTY: 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 htgin to reduce the oxygen concentration to within its limit.
b. The cancentration of oxygen in the Waste Gas Holdup System is greater than or eQ'J ?o 2% by volume, immediately suspend additions of waste gas to the Waste Gas hddup System and without delay begin to reduce the oxygen concentration to within its limt.
BASES: Based on experimental data (Reference 1), lower limits of flammabilty for hydrogen is 5% and for oxygen is 5% by volume. Therefore, if the concentration of shher gas is kept below it lower limit, the other gas may be present in higher amounts without the danger of an exploalve mixture. Malntaining the concentrations of hydrogen and oxygen such that an explosive mixture does not occur in the waste gas holdup system provides assurance that the release of radioactive materials will be controlled in cuiviiience wth the requirements of General Design Criterion 60 of Appendix A to 10 CFR 50. REFERENCES (1) Bulletin 503, Bureau of Mines; Limits of Flammabity of Gases and Vapors. 2.2.2.6 Waste Gas Decay Tanks - CONTROL:
~
The quantity of radioactivity contained in each waste gas decay tank shall be limited to less than or equal to 8800 curies noble gases (considered as Xe.133). APPUCABluTY: At all times. O 38.0 m
04-17-98 11:13:03 Numter l h Nuclear M Radid@MontrW Departmental Procedure 6610-PLN-4200.01 Q Tm Revnen No. l Offsite Dose Calculation Manual (ODCM) 15 ACTION:
a. With the quantty of radioactive material in any waste gas decay tank exceeding the above limt, immediately suspend all additions of radioactNe material to the tank and within 48 hours reduce the tank contents to wthin the limit.
1 BASES Restricting the quantky of radioactMty contained in each waste gas decay tank provides i assurance that in the event of an uncontrcGed release of the tanks contents, the resulting total body exposure to a MEMBER OF THE PUBUC at the nearest exclusion area boundary wtl not exceed 0.5 rem. This is consistert wth Standard Review Plan 15.7.1, ' Waste Gas System Fabure.' 2.2.3 Total Recticactive EfRuant Controls 2.2.3.1 Total Dose i CONTROU [ i The annual (calerxiar year) dose or dose commitment to any MEMBER OF THE PUBUC, due to releases of radioactMty and to radiation from uranium fuel cycle sources shaR be limited to less than or equal to 25 mrem *.o the total body or any organ except the thyroid, which shau be limited to less than or equal to 75 mrem. APPUCABluTY: At all times. ACTION: Wth 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 cortributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submit to the NRC Region i Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevert recurrence of exceeding the abovo limits and indudes the schedde for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b), shall include an analysis which settmates the radladon exposure (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 radicactive material involved, and the cause of the exposure levcis or concentrations. If the estimated dose (s) exceed the above limks, and if the release condition resulting in vloiation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted unti g staff action on the request is complete. k 39.0 m
04-17-98 11:13:03 menber ggggg TMI Radiological Controls Departmental Procedure 6610-PLN-4200,01 9me , neuen m. _ Offsite Dose Calculation Manual (ODCM) 16 BASES This control is provided to meet the dose Omitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). TNs control requires the preparation and sutxwttal of a Special Report whenevu the calculated doses from plant generated radioactive effluents and direct racRation exceed 25 mrom to the total body or any organ, ; except the thyroid, which shall be limited to lees than or equal to 75 mrom. For sites j containing up to 4 reactors, k is hl ONy unlikely that the resultant does to a MEMBER OF l THE PUBUC wtX exceed the does limas of 40 CFR Part 190 if the individual reactors remain i within twice the dose design objectNes of Appendix 1, and if direct radiation doses from the { reactor units and outside storage tanks are kept smal. The Special Report will describe a l course of action that should result in the limitation of the annual dose to a MEMBER OF j THE PUBUC to within the 40 CFR Part 190 limts. For the purposes of the Special Report, R j may be assumed that the dose commitment to the member cf the public from other uranium ! fuel cycle sources is negligible, with the exception that dose contributions from other nuclear i fuel cycle fac8kles at the same she or within a radius of 8 km must be considered. If the ! dose to any member of the public la estimated to exceed the requirements of 40 CFR Part ! 190, the Special Report with a request for a variance (provided the release condtions ! roeutting 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 10.2203(b), is considered to be a j timely request and fulfils the requirements of 40 CFR Part 190 until NRC staff action is 9 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 individual is not consklared a MEMBER OF THE PUBUC 4 during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 3.0 SURVEILIANCES I 3.1 Radioactive Effluent instrumentation 3.1.1 Radioactive Uquid n' fluent instrumentation Surveillance Requirements 1 3.1.1.1 Each radioactive Ilquid effluent monitoring instrumentation cir% shall be ! demonstrated OPERABLE by performance of the CHANh.el.CMCK, SOURCE CHECK, CHANNEL CAUBRATION, AND CHANNEL TEST operations during the ! MODES and at the frequencies shown in Table 3.1-1. I O . l l 40.0 m
2 k m^ $ g , n u L E 5 NI ) ) _ 1 N G 1 ( 1 ( O O n A E Q Q o H J i s C . i t v se eR -- J L Y E K T NA NR
)
(2
)
(2 t R R AB R R HU CA s t n C e m ~ e r . u i q e R
- e E K c C C .
m R E P P A
/ /
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r EK NC NE
) ) _
t s AH D D (3 (3 0 _ e n D D HC 1 d I _ t g 4 a n C T i r o . it n o M tr e u c ) 6 lt f E d it a m L-- M
)
4 8 - iu t o R ( T q u ) F ( U A e 2 n 1 e e d n U L-- n ) 6 8v 4 a s U 4 t n M t 1 m R n
- r a
e u ( e u T-F - id T i e l ( a M l l n i e f R N g E U E g E e e r M in t s e g t s a d h - U i v e r a a c _ R o w h w is T r d c d D a a S P N R is R t s D n . I r o d i e t iu S s k u u n q F r o iq m E o U W it L M l/ n n y 1 S o 1 o it it T M it it a v n W e n t it cn U l t U S ao a R ioi t dl a [/ ao Ri s a b F w lo a b 1 2 .
04 17-98 11:13:03 t Numb.t T Nuclear ' "*d'd a=* Departmental Procedure 6610-PLN-4200.01 { [V no. m wo. l Offsits Dose Calculation Manual (ODCM) 15 Table 3.1-1 (Cont'd) Table Notation (1)- The CrMNNEL TEST shen also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the falowing condition exfsts: 1
1. Instrument indicates measured levels above the high alarm / trip setpoint. (includes - circuit failure)

2. Instrument indicates a down scale faaure. (Alarm function only.) (includes - circuit failure)

3. Instrument controls moved from the operate rnode (Alarm function only).
(2) The intial CHANNEL CAUBRATION for radioactMty measurement instrumentation shou be performed using one or more of the refcnence standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participated in measurement assurance actMtles with NBS. These standards should permit calibratin0 the system over to intended range of energy and rnesourement range. For subsequent CHANNEL CAUBRATION, sources that have been related to the initial calibrellon should be used. (Operating plants may subettute previously established calibration procedures for this requirement) f (3) CHANNEL CHECK shall consist of vertfying Indication of flow during periods of release. CHANNEL CHECK shal be made at least once daily on any day on which continuous, periodic, or batch releases are made. O 42.0 2%
04-17-98 11:13:03 l Nwnbw NgEI TMI Radidogk:al Controls Departrnental Procedure 6610 PLN-4200.01 Q},1./~~in . m ne Offsite Dose Calculation Manual (ODCM) 15 3.1.2 Radioactive Gaseous Process and Ef8uent Monitoring instrumentat! A SURVElLLANCE REQUIREMENTS l 3.1.2.1 Each radioactwe Oaseous process or of8uent monitoring instrumentation channel shall be ' demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, ' CHANNEL CAllBRATION, and CHANNEL TEST operations at the frequencies shown in . Table 3.1-2. l l I o O f e 43.0 nm.
J $ , e,C) ow j m Y m m T I L I 5 S
1 A

n C

o U l
o P l P 1 v 8e A 8R L E NT ) ) A A A ) NS ( 1 Q M M ( 1
/ / NQ (2 s A TE Q M N N /
O t n H e C . m e r iuq N e LO EI T R NA ) ) ) e NR (3 E (4 5
)
(3 A A ) c AB E O ( / / E E (3 n Hl Q E N N E la t t e CA
v C r
u S n E K io C C t R A A A A A A A a UH E P / / / P / / / / M t n OC N N N N N N N e S m u r t s In L EK Du (e i g n r o NC N E AH P P D D DW W D D D 0 l e t in HC 4 b a o C 4 T M t n e lu f
)
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, M o
y MMe M R ( r R lo w M o e n oe Mba yT l R e t F e o t R lp F t a N t v it r t n i v ( t ve I sy i t c m t sy n o e i t r m m R m ie S A e S o it n V c e a e w e dS p t s M o e A lp S t s o t s A - s y p g s m e y l y s u a S u n e M r a a t S F S a a. d G t d g n u G S a r t l H o le n e u l H o o r e g P le e n luc t n e l e p n e Gi le s b o dy y t n b i i t u m V b t. a lf f a s x e o d r a l ff a r oq t N E H O m N lo P E S e NE G G n s n e e ia e F( t t s s t n d a a o n . . W a W o a b b C a b c t. r e C a
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/ N/ O / (2 QQ s AE O N N O t
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)
B M t a ( ( e v E i d t o o A- t e i m e r r o e r u it a T t s n i i. c M R u
)
8 M R i t n a a a U o R u r o R e o R B M A ( w M iA M id a T S in g t y M R l r e l o5)0 t e F S M y l o w e R p F1 a t N l d v ( - E it v F a r n R R i t I n t c e m g i t n R a A i p a eF w n t c e H S ud o A u w mn i s m e d m c l e a e t Ea R 4t s e E R u G)6 S a 9 r e B G r F e l u m4 m e d le A n c ef lp g e e lp n b - oM i d it r t s yR m n l b t s m a NR a a i Ac o y a y lo P S( F S n N S S j r ia l x H a f( / _ A u a b c d e l F e u a b c 5 . 6
1yb
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m Y ar T u l 5 B # # # # # A # # # # # , 1 C # # n U # # # i o .P _ e P t W A _ se eR E NT ) A A NE S (2 / / W W O N N t n s MT C e m e r iu q N e R EIO e N AT ) A A A A c n NR (3 / / S S a E N N t MBU e CA vr u C S n E o i t a CK A A RC U E M / / W W t n N N e OH m S C ) u r d t s i n g n EK NC i r o NE D W W D D 0 H 6 _ 1 3 i t n o MC C 4 . e M l b a t n e _ T lu f f E d m e n m a t s y e s S t s _ s y e n c o
)
8 1 io t S n r P m 4 a i o i s e M t n t a u t sy R ) e tt o 8 V ) n _ e s S C 1
- f 1 e )
1 a n L ) 4 T- V - _ A G o ( 8 M Rc IR-e M T it r 1 R c R-e N i a o 1 F a P n a N E t n t M C H n M n i L g L M e o R A W e R _ U V ( in ( t n ( R g M C r g r a r R- T n y L e a e e _ a S i t i A( lp k c lp M l p R N d l i v r m a m y m I u t c e a P a d r a
, B A lp S d S n S g s m e n e u e n a a t a a t a t a
i n G S g la L l a e lu n c u d u __ ic le le n ic i n _ a l b t d it t id r _ r C o r a n a r a l N o P a P o P a l H t ic a . m t e ir p __ e s s h a e W a C a b c. R a _ 7 8 9
04 17-98 11:13:03 mme., TM: Radiological controis r Departmental Procedure 6610-PLN-4200.01 s Asvteson No. Offsite Dose Calculation Manual (ODCM) 15 Table 3.12 (Cont'd) Table Notation At all times. During waste gas holdup system operation Operablity is not required when discharges are positwely controHed through the closure of WDG-V47, and where RM A8 (or RM-A4 and RM-A8), FT-149, innd FT-150 are operable.
**** . During Fuel Harding Bulding ESF Air Treatment System Operation. # At all times during containment purging. ## At all times when condoneer vacuum is established. ### During operation of the ventiation system.
(1) The CHANNEL TEST shad also demonstrate that automatic isolation of this pathway for the AuxRiary and Fuel Hand!!ng Bunding Ventiation System, the supply ventBation is isolated and control room alarm annunciation occurs ll the following condtlon exists: 1. Inshument Indicates measured levels above the high alarm / trip setpoint (Includes circuit falure). 3 2. Instrument Indicates a down scale falure (Alarm function only) (includes circuit fagure). 3. Instrument controis moved from the operate mode (Alarm function only). (2) The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm setpoint. (includes circut falure) 2. Instrument indicates a down scale fature (includes circut falure).
3. Instrument controls moved from the operate mode.
(3) The initi) CHANNEL CAUBRATION for radioactivty measurement instrumentation shall be performed 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 participate in measurement assurance activities wth NBS These standards should permit calibrating the system over its irtended 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 previously estabilshed calibration procedures for this requirement.) (4) The CHANNEL CAUBRATION shallinclude the use of sindard gas samples containing a nominal: 1. One volume percent hydrogen, balance nitrogen, and n 2. Four volume percent hydrogen, balance nitrogen. 47.0 v n,
04-17-98 11:13:03 Numbw Nuclear ' "ade oa'* Departmental Procedure -6610-PLN 4200.01 G Tlue Rev6eion No. Offsite Dose Calculation Manual (ODCM) 15 Table 3.1-2 (Cont'd) (5) The CHANNEL CAUBRATION shallinclude the use of standard gas samples containing a nominal:
1. One volume percent oxygen, balance nitrogen, and

2. Four volume percent oxygen, balance nitrogen.
O i e-O 48.0 n t=
04-17-98 11:13:03 Nuin a ggy TMl Radiclogical Controls Departmental Procedure j __ Tree 6610-PLN-4200.01 RevWon No. Offsite Does Calculation Manual (ODCM) 15 3.2 Radioactive Efiluents 3.2.1 Uquid EfRuonts SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration 3.2.1.1.1 The radioactivty 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 shau be used wth the calculational methods in the ODCM to assure that the conoontration 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 rolesses shal be performed in accordance with Table 3.2-1. The results of the previous post release analysis shall be used with the calculational 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. O 3.2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points sheit be determined by collection and analysis of samples in accordance with Table 3.21. The results of the analysis shall be used with the calculatlanal methods 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 Calet.dations 3.2.1.2.1 Cumulative does contributions from liquid affluents shal be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month. 3.2.1.3 Liquid Waste Treatment 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the 00CM. 49.0 un.
04-17-98 11:13:03 m bw gggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 O m. W No. Offsite Dose Calculation Manual (CDCM) 15 3.2.1.4 1.iquid Holdup Tanks 3.2.1.4.1 The quantky of radioactive material contained in each of the tanks specified in Control 2.2.1.4 shau be determined to be within the limt by analyzing a i+: _:G;m sample of the tanl(s content weeldy when radioactive matedals are being added to the tank. O O S0.0 n n.
04-17-98 11:13:03 l I t { 3 v. f bb
;=;
b b b b b a j1 - - -*- ' 1 l c t I ! *lj'l]5Y3 1!g- ! E a b ce
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e @ 98Oay>< m m
) )a f
oDL e t it L o t5 m(N '0 '0
0 4
0 '0
0 '0 "L n 1
un( riqo 1 x 1 x 1 x 1 x 1 x 1 x 1 x o e t cn pi e we/ 5 1 1 1 1 5 1 oteC l i t w so eR L D (p lle ! 'l ,!ll 8!l! y a) ss) t mfe dero n st a 0 M: s mt a o a ab hp 9 ci Ay s G(N 1 d Gm 3 l a S r- 5 3 ed E - 4e _ fo la n la rs 1
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eA ipet 1 oim sa o 4r p y ct ni m itsr m Dna G r S _ pre i T EG(
!leIl! . l lil!' l!
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) lli .ll ' lll!Ill!
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g s s s n gcy u) u) u) oc i l p n in oc u oc u e u e m lpu e int e nt nt 0 2- a mq t o io t io t 2 5 S aer nN o( nN o( nN o( _ s e sF C C C l e t s b a a W !ll il! T ,l l _ ll d iu q _ U e _ kt c - a o id a R e p y T 4 e s a ) e e le e t R o . d N( iu q s e U s a l e e R s u o u i n t G-n o C 2 A
l 04-17-98 11:13.03 l l Number g'g I TMI Radiological Controls Departmental Procedure 8610-PLN-4200.01 1
\, T ro, W No.
Offsite Dose Calculation Manual (ODCM) 15 f Table 3.21 (Cont'd) , Table Notation
a. The LLD is defined, for purposes of this surveillance, as the smauest concentration of radioactive j material in a sample that will yloid a not count above system background.that wil be detected wth !
96% probabilty with 5% probabDity of falsely conduding that a blank observation represents a "real* signal. For a particular measurement system (which may include radiochemical separaton): LLD - 4.66 s< i E x V x 2.22 x 10' x Y x exp ( J At) i Wnere: LLD is the "a priort* lower limit of detection as defined above (as rnicrocurie per unit mass or ; volume), ' i s, is the standard deviation of the background counting rate or of the counting rate of a blank p sample as appropriate (as counts per minute), i E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), j 2.22 x 10'is the number of disintegrations per minute per microcurie, ! Y is the fractional radiochemical yield (when applicable). I A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample dection and time of counting. Typical values of E, V, Y and At shan be used in the calculation. It should be recognized that the LLD is defined as an "a priorr (before the fact) limit representing the capablity of a measurement system and not as an 'a posterior!" (after the fact) limit for a particular measurement.
b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. >

c. To be representative of the quantitles 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 I to analyses, all samples taken for the composite shall be thoroughly mixed in order for the b) compos!!e sample to be representative of the effluent release.
l 53.0 nn, I
04-17-98 11:13:03 Nanta gdgy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 9rm
.s, n vi n so, Offsite Dose Calculation Manual (ODCM) 15 Table 3.2-1 (Cont'd)
d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for se,w each batch shall be isolated, and be thoroughly mixed, by a method described in the 00CM, to assure representative sampling.

e. A continuous release is the discharge of Ilquid wastes of a non- discrete volume; e.g., from a volume or system that has an input flow during the continuous release,

f. The principal gamma emitters for whid the LLD spelfication applies exclusively are the following radionuclides: Mn-54, Fe 59, Co-58 Co40, Zn45, Mo 99, Co-134, Cs-137 Co-141, and Co.144.
This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identinable, 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. O O 54.0 wu
04 17-98 11:13:03 Numter TMI Radiological Controls A I Departmental Procedure 6610-PLN-4200.01
m. m ua.
Offsite Dose Calculation Manual (ODCM) 15 3.2.2 Gaseous Efiluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates 3.2.2.1.1 The does rate due to noble gases in gaseous affluents shall be determined to be within the limits of Control 2.2.2.1.a in accordance with the rnethods and procedures of the ODCM. 3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in
. gaseous effluents shall be determined to ba within the lirnits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative sangles and performing analyses in accordance with the sampling and analysis program, specified in Table 3.2 2.
3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly. 3.2.2.3 Dose, lodine-131. lodine-133, Tritium, and Radionuclides in Particulate Form 3.2.2.3.1 Cumulative dose contributions 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 j be determined in accordance with the OFFSITE DOSE CALCULATION I MANUAL (ODCM) monthly. l 3.2.2.4 Gaseous Waste Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM. 3.2.2.5 Explosive Gas Mtxture 3.2.2.5.1 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the limits of Control 2.2.2.5 by monitoring the waste gases in the Waste Gas Holdup System with the hydrogen and oxygen monitors cwered in Table 2.1-2 of Control 2.1.2. O
$5.0 mw
04-17-98 11:13:03 Numbw p Nuclear ' "*d* c"** Departmental Procedure 6610 PLN-4200.01 h Tm W No. Offalte Dose Calculation Manual (ODCM) 15 3.2.2.6 Waste Gas Decay Tank 3.2.2.8.1 The concentration of radioec:Mty 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 Das decay tank being added to, to determine N the tank (s) is less than or equal to 8800 Cl/ tank. O t w O 56.0 2"w
h $ U6* - n i s
)
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1 v cr r

4

i 4
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t DpeC l 0 1 1 x 1 1 xx 1 1 00 1 1 xx 1 1 1 1 xx 1 1 o0 t1 xx 1 1 Il . 3Ilil;1ll y _ t a) a) a )' a) a) mg mg mg i i t v s mg e mg ci s Ay mt ao e mte ao mte ao mt ao mt a o e la G(N G(N
.dn eA GN(
las l as G (N las G (N l p pr pr s pr as r e iper ie Mi icte y t ie t t T ct ct t ct t ni ni nit ni im r PE aim HPE r 4 tim HFE 4im HPE r 4im HPE r m a r ilg l !' lll; " :l! g o r y P n sc e ) s oinus ye k n )b rg g
)
n h is y mdq Pa eP u M n o Mteo n e u mi i la T t r t n uAr F h oh er a N ( A c a Nca ( (d s t e y p d n E PE MSO a ilgell l!! a i!lj! ! W g i n l p gcy e e )e e e e m a n en hpu k lp ) elp ep,l
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g gy TMt Radiological Controls Departmental Procedure 6610 PLN-4200.01 Tree 52n No. Offalte Dose Calculation Manual (7DCM) 15 Table 3.2-2 (Cont'd) Table Notation
a. The LLD is defined, for purposes of this survedlance, as the smallest concentration of radioactive material in a sample that wIl yield a not count above system background.that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a 'real" signal.
For a particular measurement system (which may include radiochemical separation): LLD = 4.66 sm E x V x 2.22 x 10' x Y x exp (-A At) Where: LLD is the "a priort" lower limit of detection as defined above (as nucrocurie per unt mass or volume), s,is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E la the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22 x 10' is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yloid (when applicsbe), 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 shall be used in the calculation. It should be recognized that the LLD is defined as an "a priorf' (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after tha fact) limit for a particular measurement
b. Sampling and analysis shal also be perforrned following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within 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 monitor shows that effluent activity has not increased by more than a factor of 3.

c. Tritium' grab samples from the spent fuel pool area shall be taken at least once per 24 hours when the refueling canalis flooded.
60.0 mu
04-17-98 11:13:03 Number Nuclear ' "a**"aa"* Departmental Procedure 6610-PLN-4200.01 nos Armen No. 15 Offalte Dose Calculation Manual (ODCM) Table 3.2 2 (Cont'd) Table Notation
a. The LLD is defined, for purposes of this survedlance, as the smallest concentration of radioactive material in a sample that wil yield a not count above system background that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation): LLD = 4.66 L E x V x 2.22 x 10' x Y x exp (-A At) Where: LLD is the "a priort" lower lirnit of detection as defined above (as microcurie por unit mass or volume), s,is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E la the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22 x 108 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and 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 priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular l measurement.
b. Sampling and analysis shal also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the prirnary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activty has not increased by more than a factor of 3.
c . Tritium' grab samples from the spent fuel pool area shall be taken at least once par 24 hours when O the refueling canal is flooded. 60.0 mw
04-17-98 11:13 03 Number C gg E TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 t, re. RwWon No. OffsNe Dose Calculation Manual (ODCM) 15 Table 3.22 (Cont'd) ,
d. Charcoal cartridges and particulate fBters shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after removal from sampler).

e. Trttlum grab samples shau be taken weekly from the spent fuel pool area whenever spent fuel is Iri the spent fuel pool.

f. The ratio of the sample ilow rate to the sampled stream flow rate shall be known for the time period i I
cwored by each does or dose rate calculation made in accordance with Controls 2.2.2.1,2.2.2.2 and 2.2.2.3.
g. The principal gamma emitters for which the L1D specification applies exclusively are the following radionuclides: Kr 87, Kr.as, Xe-133, Xe-133m, Xe-136 and Xe-138 for gaseous emissions and Mn 54, Fe-69, Co-68, Co 60,2n 86, Mo40, Cs-137, Co-141 and Co 144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identillable, 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 performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUlVALENT l-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas actMty monitor shows that effluent actMty has not increased by more than a factor of 3.

1. Gross Alpha, Sr40, 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 wW be placed in service within 48 hours or a report WE be prepared and submitted within 30 days from the time the sampler is found or made Inoperable which identifies (a) the cause of the l Inoperabtity, (b) the action taken to restore representative sampilng capabity, (c) the action taken to prevent recurrence, and (d) quantification of the release via the pathway during the period and comparison to the limbs prescribed by Control 2.2.2.1.b.
k. Applicable only when condenser vacuum is established.

1. Appilcable when liquid radweste is moved or processed within the facility,

m. todine samples only required in the Chemical Cleaning Building when TMI-1 liquid radweste is stored or processed in the faclity.
O 61.0 nm,
04 17-98 11:13:03 Nwnber gggy WI Radiologimi Controls Departmental Procedure 6810-PLN-4200.01 te m No. Offsite Dose Calculation Manual (ODCM)' 15 3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous affluerts shah be determined in accordance wth Survellances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, includin0 direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM i
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62.0 8" = iI
04-17-98 11:13:03 mmbu Nuclear "*d'*a'a' coa"d' Departmental Procedure 6610-PLN-4200,01
)
in. a.uon m. 1 Offette Dose Calculation Manual (ODCM) 15 I 4.0 PART1 REFERENCES 4.1 Tide 10, Code of Federal Regulations, " Energy" 4.2 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routing Releases of Reactor ' Emuents for the Purpose of Evaluating Compilance with 10 CFR Part 50, Appendk I, " Revision 1, October 1977 4.3 TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50 t 4.4 TMi-1 FSAR , O 63.0 un,
04-17 98 11:13:03
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6610-PLN-4200.01 me m na.
Offsite Dose Calculation Manual (ODCM) 15 O PART11 l l TMI 2 RADIOLOGICAL EFFLUENT CONTROLS 4 O 64.0 m
04-17-9811:13 03 Number l O Nuclear " " d ***' o "* Departmental Procedure 661pLN-4200.01 Q Du m m. Offsite Dose Calculation Manual (ODCM) 15 PART 11 Definitions 1.0 DEFINITIONS " DEFINED TERMS
)
1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part 11 of the ODCM. PDMS 1.2 Post-Defueling Monitored Storage (PDMS) is that condulon where TMI-2 defueling has been completed, the core debris removed from the reactor during the clearHJp period has been shioped off-ske and the feelity has been placed in a stable, safe and secure condition. ACTION 1.3 ACTION shall be those addhional requirements specified as corotary statements to each control and i shall be part of the controls. o -OPERABLE OPERABluTY 1.4 A system, subsystem, train, component or device shall be OPERABLE or have OPERABluTY when R is capable of performing its specified function (s). Implicit in tNs definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubncation or other auxiliary equipment, that are required for the system, subsystem, train, component or device to perform its function (s), are also capable or performing their related support function (s). CHANNEL CAUBRATION 1.5 A CHANNEL CAUBRATION shaR be the adjustment, as necessary, of the channel output such that it responds wth necessary range and accuracy to known values of the parameter which the channel monkors. 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 CAU8 RATION may be performed by any series of sequential, overiapping or total channel steps such that the entire channel is callbrated. CHANNEL CHECK 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by ebservation. This determination shall include, where possibie, comparison of the channel indication and/or status with other indicatiors and/or status derived from independent instrument channels measuring the same parameter. v . . I l 1 65.0 nm.
04 17-98 11:13:03 Nw2w TMl Radiological Cordrols NI Departmental Procedure 6610 PLN-4200.01 noe m No. Offsite Dose Calculation Manual (ODCM) 15 CHANPE!L FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shal be:
a. Analog channels - the injection of a simulated signal into the channe,t as close to the primary sensor as prar*aNe to verify OPERA 81UTY including alarm and/or trip functions.

b. Blatable channels - the injection of a simulated signal into the channel sensor to verify OPERA 81UTY Including alarm and/or trip functions SOURCE CHECK 1.8 A SOURCE CHECK shal be the quaillative assessmert of ctensi resoonse when the channel sensor is exposed to a radioactive source COMPOSITE SAMPLE 1.9 A COMPOSITE SAMPLE is a combination of individual samples obtained at regular Iraervals over a time period. Elther the volume of each Individual sample is proportional to the flow rate discharge at the time of sampilng or the number of equal volume samples is proportional to the time period used to produce the cow-i-::': ,
GRAB SAMPLE 1.10 A GRAB SA MPLE is an Individual sample collected in less than fifteen minutes. BATCH RELEASE 1.11 A BATCH RELEASE is the discharge of fluid waste of a discrete volume. CON'11NUOUS RELEASE 1.12 A CONTINUOUS RELEASE is the discharge of fluid waste of a non<llscrete volume, e.g., from a l volume or system that has an input flow during the CONTINUOUS RELEASE. { SITE BOUNDARY 1.13 The SITE BOUNDARY used as the basis for the limits on the release of gaseous efAuents is as denned in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI 1 FSAR. This boundary line includes portions of the Susquehanna River surlace between the east bank of the river and Three Mile Island and between Three M8e Island and Shelley Island. The SITE BOUNDARY used as the basis for the limits on the release of liquid effluents is as shown in Figure 1.1 in Part i of this ODCM. FREQOENCY NOTATION - 9 1.14 The FREQUENCY NOTATION specified for the performance of Surveniance Requirements shall correspond to the intervals defined in Table 1.1. All Surveillance Requirements shall be performed within the specified time Interval with a maximum allowable extension not to exceed 25% of the survetlance interval i l 66.0 m= I i J
04-17-98 11:13.03 i Number p TMI Radiolortti Controls Departmental Procedure 6610-PLN-4200.01
m. AeMon No.
Offsita Dose Calculation Manual (ODCM) 15 TABLE 1.1 Frequency Notation _ NOTATION FREQUENCY S (SNftly) M least once per 12 hours. D (Daily) At least once per 24 hours. W (Weeldy) At least once per 7 days. M (MontNy) At least once per 31 days. Q (Quarterty) At leest once per 92 days. SA (SemMnnually) At least once per 184 days. A (Annually) At least once per 12 months. E At least once per 18 months. N.A. Not applicable. , P Completed prior to each release l l l l b
\
67.0 ann
04-17-98 11:13:03 Number gp TMl Radiological Controls Departmental Procedure 6610 PLN-4200.01 9noe Remon m. Offalte Dose Calculation Manual (ODCM) 15 2.0 CONTROLS AND BASES 2.0.1 Contrds and ACTION requirements shall be appilcable during the conditions specified for each control 2.0.2 Adherence to the requirements of the Control and/or associated ACTION withiri the specified time Interval shall constitute 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. 2.0.3 in the event the Control and associated ACTION requirements cannot be satisfied because of circumstances in excess of those addressed in the Control, intiste appropriate actions to . rectify the problem to the extent possible under the circumstances, and submit a special l report to the Commission pursuant to TMI-2 PDMS Technical Specification (Tech. Spec.) Section 6.8.2 wkhin 30 days unless otherwise specified 2.1 Radioactive Emuent instrumentation 2.1.1 Radioactive Uquid Effluent Instrumentation l J Radioactive Uquid Emuent Instrumentation is common between TMl 1 and TMI-2. Contrels, 9 2.1.2 applicabHity, and a*ms are specified in ODCM Part 1, Control 2.1.1 Radioactive Gaseous Process and Effluent Monitoring Instrumentation j i CONTROL: ) i The radioactive gaseous process and emuent montoring 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 setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). ; APPUCABluTY: As shown in Table 2.1-2. ACTION:
a. With a radioactive gaseous process or emuent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control, immediately suspend the releaae of radioactive effluent montored by the affected channel or declare the channel inoperable.

b. Wlth less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-2. 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 Inoperabatty was not corrected in a timely manner.
O 68.0 mu
04-17-98 11:13:03 mmb.c gp TMI Radiological Controls Departmental Procedure .6610-PLN-4200.01 T** m m. Offsite Dose Calculation Manual (ODCM)' 15 BASES The radioactive gnecous oftluent instrumentation le provided to monitor and control, as applicable, the rolesses of radioactive materials in gaseous afluent 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 provide reasonable assurance that the annual rolesses are within the limits specified in 10 CFR 20.1301. i 9 O 69.0 mu
04-17-98 11:13:03
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m _ ggE TMl Radiological Controls Departmental Procedure 6610-PLN-4200.0'; se fWWon No. Offsite Dose Calculation Marmel (ODCM) 16 2.2 Radioactive ENiuent Controls 2.2.1 Liquid EfRuont Controls 2.2.1.1 Liquid EfRuont Concentration CONTROL: The concentration of radioactive material relemoed at anytime from the unit to unrestricted areas shall be lirnited to ten times the concentrations speculed in 10 CFR Part 20.1001-20.2401, Appendh B. Table 2, Column 2. APPUCA81UTY: At aN times ACTION: With the concentration of radioactive material released from the unit to unrestricted areas maariing the above limits, immediately restore concentrations within the above limts. BASES x This control is provided to ensure that the concentration of radioactive materials roleesed in liquid weste elliuent from the unit to unrestricted areas wil be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendk B. Table 2. These Controis permt flodbity under unusual conditions, which may temporarty result in higher than normal releases, but st31 wthin ten times the concentrations, specined in 10 CFR 20. It is expected that by using this Sodbilty under unusual conditions, and exerting overy ellort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases wNI not exceed a smaH fraction of the annual average concentrations specined in 10 CFR 20. As a result, this Control provides reasonable assurance that the resulting annual exposure to an Individual in olf ste areas wil not exceed the design objectives of Section ll.A of Appendix 1 to 10 CFR Prt 50, which were established as requirements for the cleanup of . TMI 2 in the NRC's Statement of Policy of Apff 27,1981. 2.2.1.2 Liquid EfRuont Dose CONTROL The dose or dose commitment to a MEMBER OF THE PUBUC from radioactive materials in liquid etAusnts released from the unit to the SITE BOUNDARY shall be Rmted:
a. During any calender quarter to less than or equel to 1.5 mrom to the total body and to less than or equal to 5 mrom to any organ. l l

b. During any calendar year to less than or equal to 3 mrom to the total body and to less than or equal to 10 mrom to any organ.
APPUCABluTY: At all times 71.0 nm.
04 17-98 11:13:03 Numter ggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 9 noe amoa Offsite Dose Calculatlost Manual (ODCM) 15 ACTION:
a. With the calculated does from the release of radioactive meterials in liquid afluents exceeding any of the above limits, prepare and othmit to the NRC Region 1 Administrator within 30 days, a Special Report which identilles the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of rad % materials in liquid elliuents during the remainder of the current calendar quarter and during the subsequent 3 calender quarters so that the cumulative does or cioso commitment to any individual from such releases during these four calender quarters.is within 3 mrom to the total body and 10 mrom to any orgen. This Special Report shall 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 requirements of 40 CFR 141 Selo Drinidng Water Act.
BASES This Cortrol requires that the does to offsite personnel be limited to the design objectives of Appendk l of 10 CFR Part 50. This wGl assure the does received by the pubile during PDMS is equivalent to or lees then that from a normal operating reactor. The limits also assure that the environmental impacts are consistent with those assessed in NUREG4683, the TMI-2 9 Prcy.r..r. aic EnvironmentalImpact Statement (PEIS). The ACTION statements provide the required flexbity under unusual condtions and at the same time implement the guides set forth in Section IV.A of Appendh I to assure that the releases of radioactive material in liquid offluents wil be kept 'as low me le i:1.-W echievable'. The does calculations in the ODCM implement the requirements in Section Ill.A. of Appendk i that conformance with the guides of Appendk i is to be shown by calculational procedures based on models and data such that the octual exposure of a MEM8ER OF THE PU8UC through appropriate pathways is unikely to be substantially underestimated. The equations specilled in the ODCM for calculating the doses due to the actual release rates of radioactive meterials in liquid effluents are consletant with the methodology provided in Regtdatory Guide 1.100,
'Celculation of Annual Doses to Man from Routine Releases of Reactor EfRuonts for the Purpose of Evolusting Compliance with 10 CFR Part 50, Appendk I,' Revleion 1, October, 1977, and Regulatory Guide 1.113,
Estimating Aquatic Dispersion of Elfluents from Accklental and Routine Reactor Releases for the Purpose of implementing Appendk I,' April, 1977. NUREG 0133 provides methods for dose calculations consistent wth Regulatory Guides 1.100 and t.113.
2.2.1.3 Liquid Radweste Treatment System CONTROL: The appropriate portions of the liquid radwee4 treatment system shall be used to reduce the radioactive meterials in liquid westos prior to their discharge when the , projected doses due to the liquH ofiluent from the unit to unrestricted areas would ! exceed 0.06 mrom to the total body or 0.2 mrom to any organ in any calendar month. APPUCABluTY: At en times 72.0 nt=
04-17-98 11:13:03-Nwnber TM1 Radiological Controls F Departmental Procedure 8610 PLN-4200.01 OTme Revision No. Offsite Dose Calculation Manual (ODCM) 15 ACTION:
a. With radioactive liquid waste being discharged 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' informatiotr

1. Explanation of why liquid radweste was being discharged without treatment, idertification of any inoperable equipment or subsystems, and the reason for inoperabElty,

2. Actie :(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 requirement that the appropriate portions of this system (shared with TMI-1) be used, when specilled, provides assurance that the releases of radioactive rnatorials p in liquid affluents 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
\
Appendk A to 10 CFR Part 50 and the design objeceve given in Section ll.D of Appendk I to 10 CFR Part 50. The intent of Section ll.D. le to reduce effluents to as low as is reasonably achievable in a cost effecove menner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section ll.A of Appendk 1,10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction. 2.2.2 Gaseous E1Ruont Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL: The doso rate due to radioacdve meterials released in geseaus ofnuent from the site shall be limited to the fogowing
a. For noble gases: less than or equal to 500 mrom/yr to the total body and less than or equal to 3000 rnrem/yr to the skin, and

b. For tritium and al radionuclides in particulate form with half lives greater than 8 days: less than or equel to 1500 mrom/yr to any organ.
APPUCABluTY: At all times. ACTION: , With the release rste(s) exceeding the sbove limits, immediately decrease the release rate to comply with the above limit (s). l 73.0 nm. 1 l _ - - - - l
04-97-98 11:13:03 mesu gggy TMI Radiological Controle Departmental Procedure 6610 PLN-4200.01 9 noe newesen m. Offsite Does Calculation Manual (ODCM) 15 BASES The control provides reasonable aneurance that the annual dose et the SITE BOUNDARY from gessous el8uent frorn aH units on the alte wtl be within the annual does limits of 10 C,FR Part 20 for unrestricted areas. At the same time, these Controls permt Sedbilty under unusual conditions, which may 1;+ / result in higher then the design objective levels, but stil within the dose limits aparmed in 10 CFR 20 and within the design objectives d Appendk i to 10 CFR 50, it is expected that usin0 this Sexibulty under unusual conditions, and by exerting overy ellert to keep levels of radioactive meterial in gessous wastes as low
.as practicable, the annusf rolesses wBl not exceed a emeft fraction of the annual does limits specified in 10 CFR 20 and wEl not result in donos which exceed the design objectives of Appendk i to 10 CFR 50, which were endorsed as limits for the cleanup of TMI-2 by the NRC's Statement of Policy of Apr0 27,1981. These gaseous release rates provide reasonable assurance that radioactive material discharged in gessous emuent wiu not result in the awpamme of a MEMBER OF THE PUBUC in an unrtetricted ares, other within or outside the SITE BOUNDARY, to annual average concentrations aveandhg the values speclRed in Appendk 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 wil be susciently low to componente for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The speclRed release rate limits restrict, .
at all times, the cc.,s, pvicing gamma and beta dose rates above background to a O 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 then or equal to 3000 mrom/ year to the skin. The absence of iodine ensures that the corresponding thyroid does rule above background to an infant via the inhalation pathway is less than or equel to 1500 mrom/yr (NUREG 0133), thus there is no need to specify dose rate limits for these nuclides. 2.2.2.2 naaar= Emuonts Dose-Noble Gases CONTROL: The air dose due to noble gases released in gaseous effluents 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 equal to 5 mrad for gamma radiation and less then or equal to 10 mrad for beta radletion and,

b. During any calendar year: less than or equel to 10 mrad for gamma radiation and less then or equal to 20 mrad for beta tartistinn.
APPUCABluTY: At aN times. ACTION: )
a. Wth the ceiculeled air does from radioactive noble gases in gaseous affluents exceeding 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 G 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 reiseses will be in compliance with the above limits.
74.0 nm.
04-17-98 11:13 03 Number TMI Radiological Controls F Departmental Procedure 8610-PLN-4200.01 O m. Remon No. Offsite Dose Calculation Manuel (ODCM) 15 BASES This control applies to the release of radioactive materials in gessous celuents from TMI-2. This control and aaaar4=8ad action is provided to implement the requirements of Section 11.5, Ill.A and IV.A of Appendk I,10 CFR Part 50. The Control implements the guides set forth in Section ILB of Appendk 1. The ACTION statemente provide flodbtity under unusual conditions and at the emme time implement the guides set forth in Section IV.A of Appendk I to assure that the releases of radioactive meterial in gessous egluents wig be kept 'as low as is reasonably achievable.' The Survellence Requirements implement the requrements in Section lil.A of Appendk I that conformance with the guides of Appendk i be shown by calculational procedures beoed on models and data auch that the actual awpamme of a ' MEMBER OF THE PUBUC through the appropriek 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 egluents are consistent with the methodology provided in Reguietory Guide 1.109,
" Calculation of Annual Domes to Man from Routine Release of Reactor EfRuonts for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendk 1.* Revision 1. October 1977 and Regulatory Guide 1.111, ' Methods for Estimating Atmospheric Transport and Disperelon of Gaseous EfRuonts in Routine Releases from Ught-Water Cooled Reactors "
Revision 1, July 1977. The ODCM equations provided for datermining the air doses at and beyond the SITE BOUNDARY are based upon the historical avwage atmospheric conditions. NUREG4133 provides methods for dose calculations consistent with Regulatory Guides 1.100 and 1.111, 2.2.2.3 Dose lodine-131, lodine 133, Tritium, and Radeonuclides In Particulate Form CONTROL: The dose to a MEMBER OF THE PUBUC from Trtium and all radionucedes h particulats form with half lives greater then 8 days, in gessous ellb.ients released from the unit to areas et and beyond the SITE BOUNDARY shall be Emited to the foNowing'
a. During any calendar quarter; less then or aquel to 7.5 mrom to any orgen, and

b. During any calendar year. less then or aquel to 15 mrom to arry organ.
APPUCABluTY: At eN th ACTION: With the ceiculated dose from the release of Trttlum and radionuclidos in particulate form with half lives greater then 8 days. In gessous elliuents avanading 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 awrearling 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 wil be in compliance with the above limits. 75.0 8""
04 17-98 11:13:03 Number gggg TMI Radiological Controls Departmental Procedure 6610 PLN-4200.01 9 Ties nowan no. Offsite Dose Calculation Manual (ODCM) 15 BASES This control applies to the release of rarea=r+1ve meterials in gaseous of8uents frorn TMI-2. This control and ===aal=*ad action is provided to implement the requirements of Section 11.C, lit.A and IV.A d Appendk I,10 CFR Part 50. The Controls are the guides set forth in Section ll.C of Appendix 1. The ACTION statement provides flexabIlly during unusual conditions and at the same time implements the guides set forth in Saction IV.A of Appendk I to assure that the releases of radioactive materials in gaseous ofRunnts wm be kept "as low as is reasonably achievabia* The ODCM calculational hwehods ep canari in the survellence requirements implement the requirements in Section Ill.A of Appendix l that conformance with the guides of Appendk i be shown by calculational procedures beoed on models and data such that the actual exposure of a MEMBER OF THE PU8UC through appropriate pathueys is unlikely to be subetontially underestimated ~ The ODCM calcadmelanel methodology and parameters for calculating the doses due to the actual release rates of the subject meserials are consistent with the methodology provided in Reguissory Guide 1.109, "Calculmeinn of Annual Doses to Man from Routine Releases of Reactor Efiluents for the Purpose of Evaluating Compilence 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 Efiluents in Routine Releases from Ught-Water Cooled Reactors,' Revision 1, July,1977. These equations also provide for determining the actual doses based O upon the historical average atmospheric conditions. The release rate controis for iodine-131, iodine-133, tritium and radionuclides in particulate form with half lives greater than 8 days are dependem upon the existing radionudido pathways to men, in areas et and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) Individual inhalation of airbome radionuclides,2) deposition of radionuclides onto green leafy vegetation with enhaary=it consumption by man,3) I deposition otto grassy areas where mik animals and meet producing animals graze with consumption of the milk and meet by man, and 4) depaahiari on the ground with subsequent exposure of men. The absence of iodines at the site eliminates the need to specify does limbs for these nuclides. 2.2.2.4 Ventuation Exhaust Treatment System CONTROL The VENTil.ATION EXHAUST TREATMENT SYSTEM shall be OPERABLE The appropriate portions of the VENTil.ATION EXHAUST TREATMENT SYSTEM shes be tised to reduce rareinar*lve matarleis in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site would avemari 0.3 mrom to any organ. APPUCABluT(: At au times. O 76.0 nm.
04-17-98 11:13:03 PkJmber O N r TMI Radiological Controls Departmental Procedure 8610-PL.N-4200.01 nu. m No. Offsite Dose Calculation Manual (ODCM) 15 ACTION:
a. With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being discharged wthout treatment and in excess of the above limits, prepare and submt to the NRC Region i Administrator within 30 days, a Special Report which includes the following Information.

1. Identification of the inoperable equipmert or subsystems and the reason for inoperabuity,

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 VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous ofHuonts are treated as appropriate prior to release to the erwironment. The appropriate portions of this system provide reasonable assurance that the releases of radioactive l matenals in gaseous ofBuents wlE be kept 'as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Crterion 60 of
\
Appendix A to 10 CFR Part 50, and the design objectives given in Section ILD of Appendix 1 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 effluents. 2.2.3 Total Radioactive Efiluent Controls 2.2.3.1 Total Dose' i. CONTROL: The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBUC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limkod to less than or equal to 25 mrom to the total body or any organ except the thyroid, ' which shal be limited to less than or equal to 75 mrom. APPUCABlu1Y: At at times. ACTION: With the csiculated dose from the release of radioactive materials in liquid or gaseous infiluerts exceeding twice the litnits of Controls 2.2.1.2.a. 2.2.1.2.b 2.2.2.2.a. 2.2.2.2.b, i I 2.22.3.a. or, 2.2.2.3.b, calculations should be made including direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submit to the NRC Region l Administrator within 30 days, a Special Report which defines tM corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above T1.0 wu l 1 I
04-17-98 11:13:03 Nwnber gE TMI Radiological Controls Departmental Procedure 6610 PLN-4200.01 G me RwWon No. Offsite Dose Calculation Manual (ODCM) 15 limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b), shou include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUSUC from uranium fuel cycle sources, including all efRuent pathways and direct radiation, for the calendar year that includes the reisese(s) covered by this report. It shall also describe levels of radiation and concentrations of rar#ancHve materialinvolved, and the cause of the exposure levels or concentrations. If the estimated dose (s) avraart the above limits, and if the reitase condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report sher include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely rarpiaar and a variance is granted untn staff action on the request is complete. BASES This control is provided to meet the does limitations of 40 CFR Part 190 that have been
'ix.eipu,e.d into 10 CFR Part 20.1301(d). This control requires the preparation and .
submittel of a Special Report whenever the enleda*=d doses from plant generated radioactive ofRuonts and direct radiation exceed 25 mrom to the total body or any orgen, except the thyroid, which shall be limited to less than or equal to 75 mrom. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF G THE PUSUC wE exceed the does limits of 40 CFR Part 190 ll the individual reactors remain within twice the dose design objectfves of Appendix 1, and if direct radiation doses from the reactor units and outside storage tanks are kept emeR. The Special Report wil describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBUC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it i may be assumed that the does commitment to the member of the public from other uranium ; fuel cycle sources is negligible, with the exception that does contributions from other nuclear ' fuel cycle facElties at the sarne site or within a radius of 8 km must be considered. If the does to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and to CFR Part 20.2203(b), is considered to be a j timely request and fulfBis the requirements of 40 CFR Part 190 untN 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 individual 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 l the nucieer fuel cycle. , V O 78.0 m
04-17-98 11:13:03 Number TMi Radiological Controls
- E Departmental Procedure 6610-PLN-4200.01
( Tme h No.
. Offsite ' Dose Calculation Manual (ODCM) 15 3.0 SURVEILIANCES 3.0.1 Survealence Requirements shall be apphcable during the conditions speelned.for individual Controle unless otherwise stated in an indMdual SurvelBance Requirement. The Survemence Requiremeras shall be performed to demonstrate compilence with the OPERABILITY requirements d the Control 3.0.2 Each Survellence Requirement shall be performed within the speellied time interval with a maximum agowable axlension not to exceed 26% d the survallance interval 3.0.3 Failure to perform a Survellence Requirement within the time interval specined in Section 3.0.2 sher constkuto non. compliance with OPERABiUTY requirements for a Control. The time limits d the ACTION requirements are applicable at the time it is identilled that a SurveWance Requiremert has not been performed The ACTION requirements may be delayed for.up to 24 hours to permit cv.v-f f':-, d the survellence when the alloweble outage time limits of the ACTION requirements are less than 24 hours. SurveiBance Requirements do not have to be performed on inoperable equipment.
3.1 Radioactive Emuent instrumentation 3.1.1 Radioactive Liquid Efiluent Instrumentation Survallance Requirements l Radioacth Liquid Elliuent Instrumentation is common betwoon TMI.1 and TMI 2. Survellances for this instrumentation are specMed in OOCM Part I, Survellance 3.1.1. 3.1.2 Radioactive Aa- Process and EfRuont Monitoring Instrumentation SURVEILLANCE REQUIREMENTS 3.1.2.1 Each radioactive gessous process or emuent 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 3.12. 9 l l 79.0 giri.
04-17-98 11:13:03 n
-j 8
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o !
'l,I og , .il 3 ] m i g 1le e g
i
. - 2.
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04-17-98 11:13:03 Number gg I TMI Radiological Cortrols Departmental Procedure 661pLN-4200.01 fltie h No. Offsite Dose Calculation Manual (ODCM) 15 3.2 Radioactive Effluents 3.2.1 Uquid Effluents SURVElu.ANCE REQUIREMENTS 3.2.1.1 Concentration 3.2.1.1.1 The radioactMty content of each batch of radioactive liquid waste shall be du ormined by sampling and analysis in accordance with Table 3.2-1. The reedts of analyses shall be used with 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 Analysis of samples composited from batch releases shall be performed in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods in the ODCM to assure that the conoentrations 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 disdwged from continuous release points shall be determined by collection and analysis of samples in accordance wth Table 3.21. The results of the analysis shall be used with the calculational methods 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 Curnuletive dose contributions from liquid effluents shall be deterrruned in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a mortit 3.2.1.3 Dose Projections 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month. In accordance with the ODCM. ( l l 81.0 mu 1
04-17-98 11:13:03 I m )
~gggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
o. -
Offsite Dose Calculation Manual (ODCM) 15 '
. TABLE 3.21 ]
Radioactive Liquid Waste Sampling and Analysis (4,5) A. ,Wgyld. Releases I Type of Detectable Sampling Freqtancy ActMty Analysis Concentration (3) P IndMdual Gamma SE-7 pCl/mi (2) Each Batch H-3 1E-6 pC1/mi Q Gross Alpha 1E-7 pCi/mi Quarterly Composte (1) Sr-90 SE-8 pCl/mi j NOTES: (1) A COMPOSITE SAMPLE la one in which the quantty of liquid sampled is proportional to the quantty of i
!! quid waste diederv.d frorn the plant. l 9(2) For certain mbdures of gamma emtters, It may not be possible to measure radionuclides in concertrations near this sensitMty limit when other nudides are present in the sample in much greater concentrations.
Under these circumstances, it will be more appropres to calculate the concentrations of such radionudides using measured ratios with those radionuclides which are routinely identified and measured. (3) The detectabity limits for radioactMty analysis are based on the technical feasibility and nn the potential significance in the environment of the quantities released For some nuclides, lower detection limts may be readily 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 quantities of radioactive material released in liquid effluents during the sampling period. In estimating releases for a i 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 clearly 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. O 82.0 mi.
04-17-98 11:13 03 Number g gy TMI Radiological Controls f Tm. Departmental Procedure 6610 PLN-4200.01 am.en No. Offsite Dose Calculation Manuel (ODCM) 15 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates , l 3.2.2.1.1 The dose rate due to noble gases in gaseous offluents 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 gaseous elRuents shall be determined to be within the limits of Control , 2.2.2.1.b in accordance with methods and procedures of the ODCM i by obtaining refs:::i:2 samples and perfoaming analyses in j accordance with the sampling and analysis program, specified in ! Table 3.2 2. 3.2.2.2 Dose, Noble Gas 3.2.2.z.1 Cumulathe dose contributions from noble gas of8uents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL 1 (ODCM) montNy. j 3.2.2.3 Dose, Tritium and Radionuclides in Particulats Form 32.2.3.1 Cumulatke dose contributions from Trtitum and radionuclides in particulate form with half lives greater than 8 dys for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly. 3.2.2.4 Ventilation Exhaust Treatment 3.2.2.4.1 Doses dut to gaseous releases from the unit shaX be projected montNy in socordarme with the ODCM. l l l i 83.0 mu
04-17-98 11:13:03 j mmb. Nuclear i Radl&gW Contre Departmental Procedure 6610 PLN-4200.01 9 noe m m. Offsite Dose Calculation Manual (ODCM) 15 TABE 3.2-2 Radioactive Gaseous Weste Sampling and Analysis (3) SAMP2 SAMPUNG TYPE OF DETECTABE SAMPM POIMI' TYPE FREQUENCY ACTIVITY ANALYSIS CONCENTRATION (1)(a) Reactor Buiding Purge Releases Gas P H-3 1E4 pCl/cc Each Purge IndMdual i Gamma Emitters 1E-4 pCl/cc (2) ) Unit Exhaust Vent Release Points. Gas M H-3 1E 6 pCl/cc MontNy IndMdual , Gamma Emit %r. (HW pCl/cc (2) l
- n~m - -
Particulates Weeldy Gamma Emitters 1E-10 pCl/cc (2) M MontNy Sr-90 1E-11 pCl/cc Composite 9 M MontNy CompoeRe Gross Alpha Emitters 1E-11 pCl/cc j j Reactor Building Breather Particulates SA Indv. Gamma 1E-10 pCl/cc (2) Semi-Annually Emitters (b) Sr-90 1E-11 pC1/cc Gross Alpha IE-11 pCl/cc ) Emitters (1) The above detectabHRy limits are based on techriical feasibility and on the potertial significance in the { environment of the quantitles released. For some nuclides, lower detection limits nwy be readly achievable l and when nuclides are measured below the stated limits, they should also be reported. l l (2) For certain mixtures of gamma emitters, it may be possible to measure radionucIldes at levels near their sensitMty limits when other nuclides are present in the sample at much higher levels. Under these circe.nstances, R wE be more appropriate to calculate the levels of such radionuclides using observed ratios I in the gaseous component in the reactor coolant for those radionuclides which are measurable. (3) ' Deviations from the sampling and analysis regime wil be noted in the report specified in ODCM Part IV. O 84.0 mi. l
04 17-98 11:13:03 Number O gggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 l Q rm. a.uon % Offsite Dose Celculation Manual (ODCM) 15
. I TABLE 3.2-2 (Cont'd)
Radioactive Gaseous Weste Sampling and Analysis Program Table Notation
a. The LLD is the smallest concentration of radioactive material in a sample that wBI be detected with 95% ;
probabity with 5% probabity of falsely conduding that a blank observation represents a 'real* signal. ! l For a particular measurement system (which rnay include radiochemical separation): I g, 4.66 S3 E V 2.22 Y exp (-AAC) ! Where LLD is the lower limit of detection as defined above (as picoeurie per unit mass or volume). , p S, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute). E la the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), 2.22 la the number of transformations per minute per picoeur'e , 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 environmental samples), The value of S, used in the calculation of the LLD for a detection system shall be based on the l actual observed variance of the background counting rate or of the counting rate of the blank l samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma 4ay spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and At shall be used in the calculation. The background count rate is calculated from the background counts that are de'.orminsd to be with t one FWHM (Full-Wdth-at-Half-Maximum) energy band about the energy of the gamma-ray peak used for the quantitative analysis for that radionuclide. t 85.0 nm.
04-17-98 11:13:03 mmna ggy TMI Radiological Controis f ( no. Departmental Procedure 6610 PLN-4200.01
n. Mon No.
15 Offsite Dose Calculation Manual (ODCM) TABLE 3.2-2 (Cont'd)
b. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: MrW54, Fe49, Co48, Co-80,2n46, Mo419, Co-134, Cs-137, Co-141 and Co 144 for partictdate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identlflable, together with the above nuclides, shal also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as 'less than' the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The 'less than" values shall not be used in the required dose calculations.
G l _ ....
)
I 04-17-98 11:13:03 l l 1 mmtw i [* gggp TMI Radiological Controis Departmental Procedure 6610-PLN-4200,01 TIO* lhWon No. -' Offsite Dose Calculation Manual (ODCM) 15 3.2.3 Total Radioactive EfRuonts 3.2.3.1 Dose Calculation ! 3.2.3.1.1 Cumulative annual does contributions from liquid and gaseous ' efRuonts shall be determined in ash with SurvelRances 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 stora0e tanks, and in accordance with the methodology contained in the ODCM. 4 I I i i l 1 i I l 1 I l j 87.0 nn. j i
04-17-98 11:13:03 mne.r g gy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tme Revtalon No. Offsite Dose Calculation Manual (ODCM) - 15 4.0 PARTll REFERENCES 4.1 NUREG4683, " Final Programmatic Environmental Impact Statement related to decontamination ar d ! disposal of radioactive wastes resulting from March 28,1979, accidert Three M8e Island Nuedear Station, Unit 2,* Mard 1981, and its supplements. l 4.2 TMI-2 PDMS Technical Specifications, attached to Fac81ty License No. DPR-73 4.3 . Title 10, Code of Federal Regulations, " Energy' l 4.4 " Statement of Policy Relative to the NRC Programmatic Erwironmental impact Statement on the I Cleanup of Three Mlle Island Unit 2,* dated AprI 27,1981 1 4.5 Regulatory Guide 1.109,
Calculation of Annual Doses to Man from Routine Releases of Reactor ,
Effluents for the Purpose of Evaluating Compliance with to CFR Part 60, Appendix 1,* Revision 1, l October 1977 4.6 DOE / TIC-27601, ALi,0.p;.efic Science and Power Reduction 4.7 TMI 1 Technical Specifications, attached to Facility Operating Ucense No. OPR40 I N 4.8 PDMS SAR l 9 ' 88.0 w'.
04-17-98 11:13:03
. 1 Numbet !
Nuolear TMI Radiological Controls on amat% m 6610-PLN-4200.01 rm 8"*a Na-Offsite Dose Calculation Manual (ODCM) 1.2 1 1 4 4 0 0 0 PARTlli EFFLUENT-DATA AND CALCUI.ATIONAL METHODOLOGIES O O
, 89.0 me
04-17-98 11:13:03
. Number Nuclear i RadblogicContr*
Departmental Procedure 8810 PLN-4200.01 Title , Revision No. Offsite Dose Calculation Manual (ODCM) 12 1.0 LIQUID EFFLUENT MONITORS 1.1 TMI-1 and TMI-2 Liould Radiation Monitor Set Points The liquid ofRuent off-line monitors are set such that the concentration (s) of radionuclides in the liquid effluents will 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 Uquid Release Pathway Diagram. To meet the above limit, the alarm / trip set points for liquid effluent monitors and flow measuring devices are set in accordance with the following equation: j c
f .1 C (eq 1.1)
F+f wiiere:
, C= ten times the effluent concentration of 10 CFR 20 for the site, in pCl/ml.
e= the set point, in pCl/ml, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to diution and release. The set point is inversely proportional to the maximum volumetric flow of the effluent line and proportional to the minimal volumetric flow of the diution stream plus the effluent stream. The alert set point value is set to ensure that advance warning 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 below. F= flow rate of dilution water measured prior to the release point, in volume per un!! 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 concentration 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. G 90.0 mm
04-17-98 11:13:03 Number Nuclear ' "*d'*a'* "* Departmental Procedure 6610 PLN-4200.01 nu.
a. Mon No.
1 Offsite Dose Calculation Manual (ODCM) 12 ! 1.2 TMI Llauld Efiluent Release Points and Liould Radiation Monitor Data TMI 1 has two required liquid radiation monitors. These are RM-L8 and RM-L12. These liquid release point radiation monitors and sample points are shown in Table 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 utlize RM-L12, and RM-L7 for release of liquid waste. 1.2.1 RM-L6 RM-L6 is an off-line system, monitoring radioactive batch discharges from tne 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%, o; l~ ten times the 10 CFR 20 concentrations to radionuclide concentrations in the unrestricter area, including conservative default values for Sr-89, St-90, and Fe-66. The release flow rate used la the most restrictive of three flow rates calculated for each liquid batch release, per the approved plant procedure. Three Diution Factors (DF) are calculated to ultimately calculate the batch release flow rate. These three DFs 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), l ensure ten tirnes the 10CFR20 concentration for Cestem-137 (IE-6 pCl/ml) will 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 maxirwJm release flow rate is then calculated by dMding the most restrictive (largest) l DF Into 90 percent of the current dilution flow rate of the Mechanical Draft Cooling Tower I (MDCT). This conservative flow rate is then multiplied by 0.9 for the allowable flow rate.
Calculation of 10 percent 10% of ten times the 10CFR20 concentration DF:
DF, = K (SA,) + (10% of ten times the 10CFR20 concentration) SA = Specific Activity of each identified radionuclide ! e Calculation of Boron DF:
.. DF, = Actual Tank Boron Concentration + 0.7.
Calculation of Cs 137 Limit:
l DF, = High Alarm Set Point + (IE-5 pCl/mi
1.06Es opm per pCl/ml) e Maximum release flow rate calculation:
Max Flow = [(MDCT flow gpm
0.9) + (Most Restrictive DF)]

0.9 91.0 me l
l l l
04-17-98 11:13 03 Number Nuclear " "*d'd S'o*' "d ' Departmental Procedure 6610-PLN-4200.01 i Title Revision No. 1 Offsite Dose Calculation Manual (ODCM) 12 The dBution flow rate used is the current flow rate at the site. The minimum dilution flow rate is 5000 gpm per the TMI-1 FSAR. This ensures this batch release wHI meet the following equation. E(C/X,) ,1 0.10, (eq 1.2) where: Cl = dButed concentration of the l* radionuclide, X, - Ten times the concentration for that radionudide in the unrestricted area l (10 CFR 20, App. B, Table 2, Col 2). A value of 3E-3 pCl/rni for dissolved
,and entrained noble gases shall be used.
The set points for RM-L6 are set for each release based on the monitor response to each radionudide identified in the gamma scan sample results as follows: (1.5)* [Il (pCl/cc),*(CPM /pCl/cc)J + (CFM.) = ALERT CPM (2.0)* [Il (pCl/cc), (CPM /pCl/cc)J + (CPM.) = HIGH ALARM CPM where: ( Cl/ce), - positively identified radionudides (CPM /pCl/cc), = RM-L6 sensitivity to radionuclide L (CPM.) - RM-LS background prior to batch release A high alarm on RM-L6 wil dose valve WDL-V-257 and terminate any WECST releases to the environment. 1.2.2 RM-L12 RM-L12 is an off-line system, monitoring periodic ccseir,6d releases from the Industrial Waste Treatment System / industrial Waste FItration System (IWTS/lWFS). The input to IWTS/lWFS onw. nates in TMI-2 sumps, (see Figures 1.1 and 1.2) and the TMI-1 Turbine Building 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 minimum dIution flow rate, and 50% of ten times the 10CFR20 concentration for Cs-137, which is the most limiting radionuclide at a concentration of 1E-6 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 wHi dose IWTS and IWFS release valves and trip release pumps to stop the release. 1.2.3 RM-L10 RM-L10 was a Na! detector submerged in the TMI-1 Turbine BuRding 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 off4ine system, monitoring the TMINS outfall 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. 92.0 me.
04-17-98 11:13:03 Hamsst TMI Radiological Controls
-(UCIOSF Departmental Procedure 6610-PLN-4200.01 Title Revision No.
Offsite Dose Calculation Manual (ODCM) 12 1.3 Control of Llauld Releases TMI liquid effluent releases are controlled to less than ten times the 10CFR20 concentrations by limiting the percentage of this limit allowable from the two TMl liquid release points. RM-l.S, and effluent sampling, limits batch releases to less than or equal to 10% for all radionuclides, and RM-L12, and effluent sampling, limits releases from TM1-1 and TMI-2 to less than or equal to 50% for , Cs 137. These radiation monitor set points also include buit in meter error factors to further ensure that TMl liquid effluent releases are less than ten times the 10CFR20 concentrations to the environment. i The radioactivity content of each batch of radioactive liquid waste is determined prior to release by j sampilng and analysis in accordance with ODCM Part i Table 3.2-1 or ODCM Part 11, Table 3.21. The results of analyses are used with the calculational methods in Section 1.1, to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part 11 Control 2.2.1.1. j j Post release analysis of samples composited from batch releases are performed in accordance with ODCM Part i Table 3.2-1 or ODCM'Part 11 Table 3.2-1. The restAts of the previous post-release , analysis shall be used with the calculational methods in the ODCM to assure that the concentrations ! at the point of release were maintained within the ODCM Part i Control 2.2.1.t, and ODCM Part 11 Control 2.2.1.1. i The radioactivity concentration of liquids discharged from continuous release points are determined , by collection and analysis of samples in accordance with ODCM Part i Table 3.21, or ODCM Part 11 Table 3.21. 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 I Control i 2.2.1.1, and ODCM Part 11 Contrei 2.2.1.1. j l i
) ]
93.0 ma
04-17-98 11:13:03 l 1 Number Nuclear ' aad* co'** Departmental Procedure 6610-PLN-4200.01 ; rme wilon No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 1.1 TMl Liquid Release Point and Liquid Radiation Monitor Data UQUID RELEASE UQUID RELEASE TERMINATION j RADIATION POINT DISCHARGE INTERLOCK ! MONITOR (Maximum FLOW (YES/NO) ! (DETECTOR) LOCATION Volume) ' RECORDER VALVES j i YES i WDbV257 l 281' Devation WECST Batch RM4.6 TMk1 Auxiliary Releases (Na0 Bldo (8000 gal.) FT44
Station YES RM-L7 Diecharge WDLV267 (Nal) South end of TMI.1 and *WDLR.1311
** TMk2, TMI.1 MDCT FT.146 YES-(WTS/lWFS IW.V73, Continuous WP16,17,18 ,
Releases ' RM-L12 IWFS Building (300,000/ FT 342/ (W-V279, (Nal) NW Comer 80,000 gal.) FT473 WP29,30
WDL.R.1311 has been flanG*d off as a TMk2 requ:d outfall.
**RM-L7 is not an 00CM required liquid radiation rnonitor.
94.0 me.
04-17-98-11:13:03 l j i Number l Nuclear ' aad" a**' "* Departmental Procedure 6610-PLN-4200.01 T& ~ Revision No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 1.2 TMI-2 Sump Capacities Total Capacity. Gallons Sump l Gallons perinch i Turbine Building Sump 1346 22.43 Circulating Water Pump House Sump 572 10.59 Control Buliding Area Sump 718 9.96 Tendon Access Galley Sump 538 9.96 Control to Service BuBding Sump 1346 ~22.43 Contaminated Drain Tank Room Sump 135 3.80 Chlorinator House Sump - - Water Treatment 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 -- -
i Solid Waste Staging Faclity Sump 1476 24.00 AuxHlary Bulding Sump 10102 202.00 Decay Heat Vault Sump 479 10.00 k Bulding Spray Vault Sump 479 10.00 ' Condensate P.olisher Sump is deactivated and in PDMS condition. The Water Treatment and Sludge Collection Sumps will be deactivated for PDMS. i
'1 l
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04-17-98 19:93 03 , l
~
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+
0610-PLN-4200.01 ! FIGURE 1.2 Revision 12 O TMI-2 Uguld Etsuent Pathways l j CONTRdL CONTROL & ; BUILDING l4 SERVICE
, SUMP AREA SUMP -
9 4 TURSINE , TENDON SulLDING l; ACCESS sump GALLERY SUMP 5I O '"'S S""" INDUSTRIAL WASTE TREAT' MENT SYSTEM lI g r RML-12 C RML-7 C -- COMPOSITE SAMPLER 97.0 me. mu mmi mu i gem , g
04 17-98 11:13:03 l Nummer E TMI Radiological Controls g m, . Offsite Does Calculagon Manual (ODCM) ' Departmental Procedure 6610 PLN-4200.01
%n .
14 2.0 IJGUID EFFlJJENT DOBE ASSERRIAENT 2.1 Unilld Eftuente - 10 CFR 50 AnnensSK I The dose fram ilquid saluente residie from the consumpson of Seh and drinidng water. The location of the nearest potable water intake le PP&L Brmner island Steam Bectric 8 tenon located downstroom of TMI. The use of the Sow cf the Susquehanna River as the dIution tow is jusdfied bened on the complete mbdne in the river prior to the first potable water supply, arlarr =8aly
. demonstruesd by Rume tracer die studies and addidones liquid eAluent rolesse studies conducted using actualTMI-1 tralum rolesses. Other pathwgye conermute negligtdy at Three Mile leiend. The done coraribudon from en radionuceden in uguld sauerne released to the unrestricted area is ra uningthefosowingsupression: . -Dose .) = (h t) X ( Cg) X M ,3 X + l M gj X-X 1 (eg2.1) where-Doesl= . the cumulative does commitment to the totes body or any orgen, j, from the liquid aniuents for the toni time pasad, in mrom.
At = . . the length of the time period of actual releases, over which Ci and f are averaged for all - liquid releases,in hours. C= i the average concentration of radionudido, I, in undIuted liquid emuent during tkne period At from any liquid release, in pCi/ml. NOTE , For Fe 66, Sr 80, St 00, prior to batch releases conservative concentration wdues wW be used in the inities does calculation bened on elmtar past plant conditions. LLD values are not used in does calculations. f= undluted liquid weste Sow, in gpm. FD = piant dIudon water Sowrote during the portod of release, in gpm FR = actual river flowrote during the period of release or average rlwer Sowrate for the rnonth the release is occurring, in gpm. DF = dIution factor as a reeldt of mbdng eSocts in the near11 eld of the discharge structure of 0.2 (NUREG 0133) or taken to be 6 bened on the inverse of 0.2. AW6 and AFq = the eno reisted ingestion dose commitment factor to the total body or any organ, l. for O each identNied principle gamme and beta emitter, in mrom/hr per pCl/ml. AW le the factor for the water pathway and AF is the factor for the fish pathway. 98.0 mee h
04 17-98 11:13:03 Number NUgEI TMl Radiological Controls Departmental Procedure 6610 PLN-4200.01 me bision No. Offsite Dose Calculation Manual (ODCM) 12 Values for AW, are determined by the following equation: AW, = (1.14E5) x (U,) x (DF) (eq 2.2) where: 1.14E6 = (1.0E6 pCl/pCl) x (1.0E3 ml/kg) + (8760 hr/yr) i U, - Water consumption rate for adult is 730 kg/yr (Reg. Guide 1.109, Rev.1). DF,= Ingestion dose conversion factor for radionuclide, I, for adults total body and for " worst case" organ, j, in mrem /pCI, from Tabic 2.1 (Reg. Guide 1.109) Values for AF, are determined by the following equation: AF, = (1.14E5) x (U,) x (DF ) x (BF) (eq 2.2.2) I where: 1.14E5 = defined above U, = adult fish consumption, assumed to be 21 kg/yr (Reg. Guide 1.109, Rev.1). DF, = ingestion dose conversion factor for radionuclide, I, for adult total body and for " worst case' organ, j, in mrem /pCl, from Table 2.1 (Reg. Guide 1.109, Rev.1). BF,- Bloaccumulation factor for radionuclide, I, in fish, in pCl/kg per pCl/L from Table 2.2 (Reg. Guide 1.109, Rev.1). 99.0 mm
L l 04-17-98 11:13:03 Nurnber l gggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 l l Dse _ ne u on no. 1 Offsite Dose Calculation Manual (ODCM) 12 2'.2 TMI Liould Radwaste System Dose Cales Once/ Month ODCM Part i Control 2.2.1.3 and TMl-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 affluent releases from each unit to unrestricted areas would exceed 0.06 mrom to the total body or 0.2 mrem' I to any organ in any calendar month. The following calculational method is provided for performing this dose projection. At least once per month, the total dose from all 1lquid releases for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, thls dose projection shall include - , the estimated dose due to any anticipated unusual releases during the period for which the l projection is made. If this projected dose exceeds 0.06 mrom total body or 0.2 mrem any organ, l appropriate portions of the Liquid Radwaste Treatment System, as defined in Section 3.1, shall be l used to reduce radioactMty levels prior to release. At the discretion of Radiological Engineering, time periods other than the current quarter-tcxfate 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 l l l l l ., l l l l l l 100.0 mai 1
04-97-98 11:13:03 Number GUCle8r mi nadia ow Contros - Departmental Procedure 6610-PLN-4200.01 nu. a.vwon No. Offsite Dose Calculation Manual (ODCM) 12 2.3 Altemative Uauld Dose Calculational Methodoloav i As an alternative, models in, or based upon, thcee 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 an attematNe dose calculational methodology GPU Nuclear calculates doses using SEEDS (simpilfied environmental effluent dosimetry system). The onsite and SEEDS calculational models use actual liquid release data with actual monthly Susquehanna River flow data to assess the dispersion of effluents in the river. 101.0 me,
04-17-98 11:13:03 Number NUCIh"I TM1 Radiological Controls Departmental Procedure 6610-PLN-4200.01 me FWWon No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DF, Page 1 of 3 Ingestion Dose Factors for Adults * (MREM Per PCI Ingested) NUCUDE BONE LIVER T. BODY THYROID K!DNEY LUNG GI-LL1 H 3 NO DATA 1.05E-07 1.05E-07 1.05E 07 1.05E 07 1.05E-07 1.05E47 C 14 . 2.84E<06 5.68E 07 5.68E 07 5.68E-07 5.68E-07 5.68E47 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E 06 1.70E 06 1.70E-06 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 1.40E-05 MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E46 1.90E-06 4.43E47 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.86E-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 2.14 E-06 4.72E46 NO DATA NO DATA NO DATA 4.02E-05 ! NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E 06 NI 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 7.10E46 ZN 65 4.84E-06 1.54E-05 6.96E.06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN' 69 1.03E 08 1.97E 08 1.37E-09 NO DATA 1.28E 08 NO DATA 2.96E-09 l BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E 08 ) BR 84 NO DATA NO DATA 5.21 E-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 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E 04 NO DATA 8.84E 06 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 , 1 SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA ' 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E 08 NO DATA NO DATA NO DATA 4.26E45 - i Y 90 9.62E-09 NO DATA 2.58E-10 . NO DATA NO DATA - NO DATA 1.02E-04 I . l l
. 102.0 mm J
I
04-17-98 11:13:03 Number NEIMF TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tme Revision No. Offsite Dose Calculation Manual (ODCM) 12
' TABLE 2.1 (Cont'd)
Uquid Dose Conversion Factors (DCF): DF, Page 2.of 3 Ingestion Dose Factors for Adults * (MREM Per PCI Ingested) NUCUDE BONE UVER T. BODY THYROlD K1DNEY LUNG Gl-LU Y 91M 9.09E-11 NO DATA 332E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41 E-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 830E-05 ZR 95 3.04E-08 9.75E 09 6.60E-09 NO DATA 1.53E 08 NO DATA 3.09E05 ZR 97 ' 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NB 95 6.22E49 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.90E-10 8.89E-09 NO DATA 1.06E 08 3.42E-10 4.13E-07 TC 101 2.54E 10 3.66E 10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E 21 l' RU 103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU 105 134E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG 110M 1.60E47 1.48E-07 8.79E 08 NO DATA 2.91 E-07 NO DATA 6.04E-05 SB 125 1.79E 06 2.00E-08 4.26E-07 1.82E-09 0.0 1.38E-06 1.97E45 TE 125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E45 NO DATA 1.07E-05 TE 127M 6.77E 06 2.42E-06 8.25E-07 1.73E 06 2.75E-05 NO DATA 2.27E-05 TE 127 1.10E 07 3.95E48 2.38E-08. 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE 129M 1.15E-05 4.29E 06 1.82E-06 3.95E-06 4.80E45 NO DATA 5.79E-05 TE 129 3.14E-08 1.18E 08 7.65E49 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E 07 7.05E-07 1.34E 06 8.57E46 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E48 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 i 130 7.56E-07 2.23E-06 8.80E 07 1.89E 04 3.48E-06 NO DATA 1.92E-06 1 131 4.18E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E 05 NO DATA 1.57E-06 i -. ! I 132 2.03E-07 5.A3E-07 1.90E-07 1.90E-05 8.65E 07 NO DATA 1.02E-07 1 133 1.42E-06 2.47E-06 733E 07 3.63E 04 4.31E 06 NO DATA 2.22E-06 1 134 1.06E-07 ?.sdE 07 1.03E-07 4.99E-06 438E-07 NO DATA 2.51 E-10 . i 103.0 me
04 17-9811:13:03-Nurober i Nuclear * "ad'doa**' coatr* Departmental Procedure 6610 PLN-4200.01 Title Revision M. 1 Offsite Dose Calculation Manual (ODCM) 12 TABLE 2.1 (Cont'd) Liquid Dose Conversion Factors (DCF): DF, Page 3 of 3 1 Ingestion Dose Factors for Adults * (MREM Per PCI Ingested) NUCUDE BONE LIVER T. BODY THYROID KlDNEY LUNG GI-LLI j i 135 4.43E 07 1.16E-06 4.28E-07 7.65E 05 1.86E46 NO DATA 1.31E-06 CS 134 6.22E 05 1.48E 04 1.21 E-04 NO DATA 4.iDE45 1.59E-05 2.59E-06 CS 136 6.51E46 2.57E45 185E-05 NO DATA 1.43E 05 1.96E-06 2.92E-06 CS 137 7.97E-05 1:09E-04 7.14E 05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS 138 5.52E 08 1.09E-07 5.40E-08 NO DATA 8.01E 08 7.91E 09 4.65E-13 BA 139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E 11 3.92E.11 1.72E-07 BA 140 2.03E-05 2.55E-08 1.33E-06 NO DATA . 8.67E-09 1.46E 08 4.18E-05 BA 141 4.71 E-08 3.56E-11 1.59E 09 NO DATA 3.31 E-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 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E 05 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 1.22E46 1.35E 10 NO DATA 5.37E 10 NO DATA 4.56E45 CE 144 4.88E 07 2.04E(17 2.62E-08 NO DATA 1.21E 07 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E 09 4.56E-10 NO DATA 2.13E 09 NO DATA 4.03E-05 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 2.40E-05 i
Dose factors of internal exposure are for continuous intake over a one-year period and include the dose o commitment over a 50-year period; from Reg. Guide 1.109 (Rev.1). Additional dose factors for nuclides not included in this table may be obtained from NUREG-0172.
i 104.0 mm
.W
04-17-98 11:13-03 Number Nuolear " " " * "d
Departmental Procedure 6610-PLN-4200.01 TWe RwWon No.
Offsite Dose Calculation Manual (ODCM) 16 TABLE 2.2 Bioaccumulation Factors, BF, Bioaccumulation Factors to be Used in the Absence of SbSpecific Data * (pCl/kg per pCl/ liter)
. FRESHWATER ELEMENT FISH INVERTEBRATE H 9.0E-01 9.0E41 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 FE 1.0E + 02 3.2E + 03 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 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 l MO 1.0E + 01 1.0E + 01 i TC 1.5E + 01 5.0E +00 ! RU 1.0E + 01 3.0E + 02 ; RH 1.0E + 01 3.0E + 02 .
***AG-110m 2.30Ev1 7.70E + 2 **SB 1.0E + 00 1.0E + 00 l TE 4.0E +02 6.1E + 03.
l l 1.5E + 01 5.0E +00 ' CS 2.0E + 03 1.0E + 03 , BA 4.0E + 00 2.0E + 02 i LA 2.5E + 01 1.0E + 03 CE 1.0E + 00 1.0E + 03 - ' { PR 2.5E+ 01 1.0E +03 i ND 2.5E + 01 1.0E+ 03 W 1.2E+03 1.0E + 01 i NP 1.0E + 01 4.0E + 02 1 i Bloaccumulation factor values are taken from Reg. Guide 1.109 (Rev.1), Table A-1). l jl q l I ** ' Sb bloaccumdation factor value is taken from EPRI NP-3840. Ag bioaccumulation factor value is taken from Reg. Guide 1.109 (Rev. 0), Table A-8. I 105.0 me. 4 i
04-17-98 11:13:03 Nurnber Nuclear- " "'d'*a'ca' coair* Departmental Procedure 6610-PLN-4200.01 TH6e - Revision No. Offsite Dose Calculation Manual (ODCM) 12 3.0 ' TMI UQUID EFFLUENT WASTE TREATMENT SYSTEMS 3.1 TMI-1 Uould Effluent Waste Treatment System 3.1.1 Description of the Uquid Radioactive 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. Uquid Processing Reactor Coolant Waste Evaporator (see Figure 3.2)
Demlneralizers prior to release
c. Uquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks (WECST)

d. Dilution - Mechanical Draft Cooling Tower (0-38k gpm)
- River Flow (2E7 gpm average)
Miscellaneous Waste Train
~
a. Water sources: - Auxiliary Building Sump
- Reactor Building Sump Miscellaneous Waste Storage Tank - Laundry Waste Storage Tank Neutralizer Mixing Tank - Neutralizer Feed Tank - Used Precoat Tank - Borated Water Tank Tunnel Sump '
Heat Exchanger Vault Sump y - 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. Uquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks (WECST)

d. DIution - Mechanical Draft Cooling Tower (0-38k gpm)
- River Flow (2E7 gpm average) 106.0 me.
04-1W-9811f13 03 Number gggy TMI R diologicil Controls Departmental Procedure 6610-PLN-4200.01 Tine Revision No. Offsite Dose Calculation Manual (ODCM) 12 3.2 Ooerobilty of the TMl-1 Uould Effluent Waste Treatment System 3.2.1 The TMI-1 Uquid Waste Treatment System as described in Section 11 of the TM; 1 Final Safety Analysis Report Is considered to be operable when one of each of the fo!!owing pieces of equipment is available to perform its intended funde a) Miscellaneous Waste Evaporator (WDL-Z1B) or Reactor Coolant Evaporator (WDL-21A) 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 All liquid releases from the TMI 1 Uquid Waste Treatment System are made through the Waste Evaporator Condensate Storage Tanks. To provide thorough mbdng and a representative sample, the contents of the tank are recirculated using one of the Waste Evaporator Condensate Transfer Pumps. 3.3 TMI-2 Uauld 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 Liquid 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. i l i i 107.0 mm
04-17 98 11:13:03 y Number M RadWogical Coritrois p Departmental Procedure 6610-PLN-4200.01 11ee Tr.Zn No. f Offsite Dose Calculation Manual (ODCM) 12 . I l
. I 1
FIGURE 3.1, - l wi.1 uguid Rede
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-+ FILTER -
DEMIN r TO MU V9 (1 OF 2) (1 OF 2)
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108.0
04 17-98 11:13:03 f mma.1 S m ME
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Tui Radiological controis Departmental Procedure 661Mt.N-4200.01 w w. Offsite Dose Calculation Manual (ODCM) 12 FIGURE 3.2 , TMI-1 @uid Waste Evaporators
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34 17-98 11:13:03 Number N Mr TMl R:diological Controls Departmental Procedure 6610-PLN-4200.01 Tm. MWon No. Offsite Dose Calculation Manual (ODCM) 12 ,, 4.0 QASEOUS EFFLUENT MONITORS 4.1 TMI-1 Noble Gas Monitor Set Points The gaseous affluent 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 Pathway Diagram. The set points are established to satisfy the more restrictive set point concentration in the following two equations: 500 > I(c)(F)(Kj(Dv) (eq 4.1.1) I and 3000 > I(c)(L, + 1.1 Mj(Dv)(F) (eq 4.1.2) I where: c, = set point concentration based on Xe-133 oquivalent, in pCl/cc F= gaseous effluent flowrate at the monitor, in cc/sec K, - total body dose factor, in mrem /yr per pCl/m' from Table 4.3 Dv = highest sector annual average gaseous atmospheric dispersion factor (X/Q) at or
. beyond the unrestricted area boundary, in sec/m' 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/m' at sector NNE for station vent, and 1.16E-6 sec/m' at sectors N and WNW for all other releases.
(= skin dose factor due to beta emissions from radionuclide I, in mrom/yr per pCl/m2 from Table 4.3. M, = air dose factor due to gamma emissions from radionuclide I, in mrad /yr per pCi/m' from Table 4.3. 1.1 - mrem skin dose per mrad air dose. 500 - annual whole body dose rate limit for unrestricted areas, in mrem /yr. 3000 = annual skin dose rate limit for unrestricted areas, in mrom/yr. 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 radidon monitor using appropriate calibration factors. 110.0 me, , j '
i l 04-17-98 11:13:03 l l Number Nuclear =Departmental a***' car
Procedure 6610-PLN-4200.01 28 boon No.
l Offsite Dose Calculation Manual (ODCM) 12 l 1 This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste.
. t I
e l 1 b l l 111.0 mm 4
14-17-98 11:13 03 Number. NUWEI ,J TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
w. ,
won no. Offsite Dose Calculation Manual (ODCM) 12 4.2 TMI-1 Par *.teulate and Radiolodine Monitor Set Points Set points for monitors which detect radionuclides other than noble gases are also established to assure that concentrations of these radionucildes in gaseous effluents do not exceed the limits of ODCM Part I Control 2.2.2.1. Set points are established so as to satisfy the fo!!owing equations: 1500 > E(c)(F)(P)(Dv) (eq 4.2) I where: ci = sot point concentration based on 1131 equivalent, in pCl/cc F= Gaseous effluent flow rate at the monitor, in cc/seo P, - pathway dose parameter, in mrem /yr per pCl/m' for the inhalation pathway from Table 4.6. The dose factors are based on the actual indMdual organ and most restrictive age group (chud) (NUREG4133). NOTE Appendix A contains P, calculational methodology. 1500 = annual dose rate limit to any organ from particulates and radiolodines 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/O or D/Q) at or beyond the unrestricted area boundary from Table 4.4 for releases from the statlon vent and i Table 4.5 for all other releases. X/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 7.17E-7 sec/m' for station vent, at sector SE, and j 1.16E-5 sec/m' for all other releases, at sectors N and WNW. The set point concentration is further reduced such that 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 callbration factors. This section of the ODCM la implemented by the Radiation Monitor Systems Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste. 112.0 mm l
04 17-98 11:13:03 Number Nuclear '"a*'S *
Departrnental Procedure 6610-PLN-4200.01 Title Revtsson No.
Offsite Dose Calculation Manual (ODCM) 12 i
)
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 provides a Gaseous effluent release pathway diagrarn. Table 4.2 provides TMI-2 Radiation Monitor Data. These set points are set in accordance with the Controls delineated in Part 11 of this ODCM. 113.0 mm
04-17-98 11:13:03 Number M Nuclear im. i Raddo@al Coe6 Departmental Procedum 6610-PLN-4200.01
a. w on No.
Offsite Dose Calculation Manual (ODCM) 12 4.4 TMi-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMl-1 has eleven (11) required effluent gaseous radiation monitors. These are RM-A4, RM-AS, j RM-A15, RM-AS, 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. 4.4.1 RM-A4/RM-A6 Fuel Handlina and Auxiliary Buildina Exhaust RM-A4 is the particulate, radiolodine and gaseous radiation monitor for the TMl-1 Fuel Handling BuAding Ventuation (see Figures 4.1 and 4.2). RM A6 la the particulate, radiolodine, and gaseous radiation monitor for the TM1-1 AuxBlary Building Ventilation (see Figures 4.1 and 4.2). High alarms on RM-A4 or RM-A6 noble gas channels wil Initiate shutdown of the related buiding ventiation air supply system. These two radiation monitors concurrently will satisfy requirements for the Station Vent release point in place of RM-A8. 4.4.2 RM-A8 Station Ventilation Exhaust RM-A8 is the particulate, radiolodine and gaseous radiation monitor for the TMl-1 Station Ventilation (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with samp!!ng lines located before the sample filters. High alarm on RM-A8 noble gas low channel wil initiate shutdown of the Station Ventiation air supply systerns. (The Fuel Handling and Auxiliary Building Ventilation). This radiation monitor satisfies requirements for the Station Vent release point in place of RM-A4 and P.M-A6. 4.4.3 RM-A5/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 TMl-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 will Initiate the MAP-5 Radiolodine 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 wil 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 Buildino Puroe Exhaust RM-A9 Is the particulate, radiolodine and gaseous radiation monitor for the TMI 1 Reactor Building Purge system (see l'igures 4.1 and 4.3). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters. High alarm on RM-A9 noble gas low channel will Initiate shutdown of the Reactor Building Purge System. This radiation monitor satisfies requirements for the Reactor Building Purge System release point. 114.0 mm
=04-1F-9811:13.03 Number N I TMI Radiologeal Controls Departmental Procedure 6610-PLN-4200.01 Tate Rev6sion No. Offsite Dose Calculation Manual (ODCM) 12 4.4.6 RM-A14 ESF FHB Ventilation System RM-A14 is the gaseous radiation monitor for the TMI-1 Emergency Safeguards Features (ESF) Fuel Handling Bunding Exhaust system (m Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associate; _ampling panel with sampling lines located before the sampiri filters. High alarm on RM-A14 noble gas channel wfil Initiate shutdown of the ESF Fuel Handling Bulding Exhaust System. This radiation monitor satisfies requirements for the ESF Fuel Handling BuBding Exhaust System release point. 4.4.7 ALC-RMI-18 Chemical Cleanina Facility (CCF) Ventuation Exhaust ALC-RMI 18 is an Victoreen particulate, radiolodine, and gaseous radiation monitor for the Chemical Cleaning buBding exht._ This monitor is located in the Chemical Cleaning 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-RIT-1 Waste Handlina and Packaaina FacIlty (WHPF) Exhaust WHP RIT 1 is an Eberline AMS-3 particulate radiation monitor for the TMI WHPF. The monitor is located in the Mechanical Equipment Room in the'WHPF, Samp!!ng for particulate activity is performed off of the monitor. A high alarm will initiate shutdown of the ventilation air exhaust system. 4.4.9 RLM-RM-1 Resolrator Cleanina and laundry Maintenance (RLM) Facility RLM-RM-1 is an Eberline AMS4 particulate radiation monitor for the TMt RLM Facility. The monitor is located in the Mechtnical Equipment Room in the RLM. Sampling for particulate activhy is performed off of the monitor. 115.0 mm
04-17-98 11:13:03 Number l Nuclear- '"ad**a'a' coad' Departmental Procedure 6610-PLN-4200.01 Titl* Revision No. l Offsite Dose Calculation Manual (ODCM) 12 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMl-2 has three (3) regulatory required gaseous effluent radiatbn monitors. These are HP-R 219. HP-R-219A and HP-R-225. These gaseous release points, radiation monkors, and sample points are shown in Table'4.2, and various gaseous effluent pathways are depicted in Figure 4.5. 4.5.1 HP-R-219 Station VentGation Exhaust HP-R 219 Is a Victoreen particulate and gaseous radiation monkor for the TMI-2 ventliation exhaust. This in-plant effluent radiation monkor is located in the TMI-2 Auxillary Building 328 foot elevation and has an associated sample panel. 4.5.2 HP-R-219A Station Ventilation Exhaust HP-R-219A is a Victoreen particulate and ~ gaseous radiation monitor for the TMI-2 ventiation exhaust. This in-plant effluent radiation monitor is located in the TMI 2 Auxilary Building 328 foot elevation. 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 BuRding Purge Air Exhaust System. This in-plant effluent radiation monitor is located in the TMI-2 Auxillary BuRding 328' elevation area. i 1 116.0 mm meur.
04-17-98 11:13 03 Number . NUWEI ,J TMl Radiological Controls Departmental Procedure 6610 PLN-4200.01 Tme Rowlefon No. Offsite Dose Calculation Manual (ODCM) 12 1 4.6 Control of Gaseous Effluent Releases TMl gaseous effluertt combined relear,es are controlled (per ODCM Part I for TMil t and ODCM Part j 11 for TMl 2) by effluent sampling and radiation monitor set points. These measures assure that i releases from the various vents do not combine to produce dose rates at the site boundary exceeding the most restrictive of 500 mrem per year to the total body or 3000 mrem 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 , l 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 actua! set points are then listed in TMl-1 Operations Procedure 1101-2.1. The radioactive content of each batch of gaseous waste is detstmined prior to release by sampling and analyses in accordance with ODCM Part i for TMI 1 and ODCM Part 11 for TMI-2. The results of pre-release 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 ll for TMI-2. Post-release analyses of samples composited from batch and continuous releases are performed in accordance with ODCM Part I for TMI-1 and ODCM Part ll 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 ll for TMI-2. 117.0 mm
04-17-98 11:13:03 Number , Nuclear ' "adid*a' ca'd* Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 12 s TABLE 4.1 TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data RELEASE GASEOUS TERMINATION RADIATION GASEOUS (F) INTERLOCK MONITOR RELEASE FLOW (YES/NO) (DETECTOR) LOCATION POINT RECORDER VALVES YES AH E-10 FuelHand. AH.O 120 306' Bevatton Building AH-D 171 RM-A4 Auxiliary Bidg. Exhaust F4140 AH-D 122 Auxiliary 306' Elevation Building YES RM-A8 Auxiliary Bldg. Exhaust FR150 AH-E-11 YES WDG-V47
, AH-E 10 AH-E-11 RMA4/9 Bldg. Starts MAP 4 Near BWST Station FR 149 Radiolodine RM-A8 Exhaust Vent & FR-150 Sampler YES 322' Bevation Condenser Starts MAP 4 Second Floor Off Gas Radiolodine RM-A5 Turbine Bldg. Exhaust FR 1113 Sampler YES 322' Bevation Condenser Starte MAP 4 Second Roor Off Gas Radioiodine RM Ats Turbine Bldg. Exhaust FR 1113 Sampler , Waste Gas 306' Elevation Decay Tanke YES i FW7 Auxiliary Bldg. (A.B.C) F4123 WDG V47 f YES AH-V 1A/B/C/D Reactor WDG 534/535 Building Starts MAP S RMA4/9 Bldg. Purge F4900/ Radiolodine RM A9 Near BWST Exhaust FR 148 Sampler 331' Bevatibn ESF FHB ESF Fuel Outside Handling NO Chem. Building Manual RM-A;4 Addition Bldg. Exhaust FR1104A/B Actions 118.0 ma
04-17-98 11:13:03 Number TMl Radiological Controls W' U "MEI Departmental Procedure 6610-PLN-4200.01 Title Rev6sion No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 4.1 (Cont'd) TMI-1 wooous Release Point and Gaseous Radiation Monitor Data GA8EOUS RELEASE RADIATION GASEOUS TERMINATION MONITOR RELEASE INTERLOCK (DETECTOR) LOCATION PO(NT (YES/NO) VALVES Chemical Cleaning CCB Exhaust ALC-RhE18 Bldg. 304' Eleva6on System NONE YES WHPF Mechanical WHPF Exhaust WHPF Ventiation WHP-RiT.1 Equipment Room System Tripe RLM Me$ankel RLM Exhaust RLM-RM-1 Equipment Room System NONE TABLE 4.2 J TMI-2 Gaseous Release Point and Gaseous Radiation Monitor Data i Mm GASEOUS TERMINATION RADIATION ! GASEOUS INTERLOCK MONITOR RELEASE (YES/NO) . (DETECTOR) LOCATION POINT VALVES 328' Eleve6on Station - Auxinary Vent ! HP421g Building Exhaust NONE l 328' Elevation ! Auxiliary Station Vent HPA219A Building Exhaust NONE Reactor Bldg 328'E!evation Auxiuary Purge Exhaust HP4226 Buildng Duct 'A' NONE i j 1 l 1 119.0 ma
1 ll 04-17-98 11:13:03 1 Number Nuclear T"' a*d'o'oa'oa' contro'* Departmental Procedure 6610-PLN-4200.01 1 Title bWn No. Offsite Dose Calculation Manual (ODCM) 12 I i TABLE 4.3 Dose Factors for Noble Gases and Daughters
l Gamma Beta Total Body Skin Dose Gamma Air Beta Air ]
Dose Factor (a) Factor (b) Dose Factor Dose Factor i K b M N Radio- (mram/y* ;er (mrem /yr per (mrad /yr per (mrad /yr per nucikle pCl/m') pCl/rn') pCl/m') pCl/m') Kr 83m 7.56E-02** -- 1.93E + 01 2.88E + 02 Kr-85m 1.17E + 03 1.46E + 03 1.23E + 03 1.97E + 03 Kr-85 1.61 E + 01' 1.34E + 03 1.72E + 01 1.95E + 03 j Kr-87 5.92E + 03 9.73E + 03 6.17E + 03 1.03E + 04 Kr-88 1.47E + 04 2.37E + 03 1.52E + 04 2.93E + 03 l Kr-89 1.66E + 04 1.01 E + 04 1.73E + 04 1.06E + 04 Kr 90 1.56E + 04 7.29E + 03 1.63E + 04 7.83E + 03 l Xe 131m 9.15E +01 4.76E + 02 1.56E +02 1.11 E + 03 1 Xe-133m 2.51E + 02 9.94E + 02 3.27E + 02 1.48E + 03 j 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 1.81E + 03 1.86E +03 1.92E + 03 2.46E + 03 [ Xe-137 1.42E + 03 1.22E + 04 1.51 E + 03 1.27E + 04 Xe-138 8.83E + 03 4.13E + 03 9.21E +03 4.75E + 03 Ar-41 8.84E + 03 2.69E + 03 9.30E + 03 3.28E + 03
)
Dose factors are for immersion exposure in uniform semi-Infinite cloud of noble Das radionuclides that may be detected Ingaseous effluents. Dose factor values are taken from Regulatory Guide 1.109 (Rev.1), Table B-1.
1
**7.56E-02 = 7.56 x 10-2, l (a) Total body dose factor for gamma penetration depth of 5 cm into the body.
(b) Skin dose factor at a tissue depth or tissue density thickness of 7 mg/cm'. 120.0 ::a l
M 99.92@3 Number
-gggp TMI Radiolo0 lcal Controls Departmental Procedure 6610-PLN-4200.01 Tide Revision No.
Offsite Dose Calculation Manual (ODCM) 12 TABE 4.4 Atmospheric Dispersion Factors for Three Mile Island e STATION VENT DISTANCE o SECTOR AVERAGE X/O (IN 8EC/MS) ON METERS) SEASON. ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24136 40226 86315 72405 N 1.18E47 5.32E47 2.96E47 1.93E 07 1.30507 5.52E46 1.91E48 5.02600 1.88E40 1.00E40 NNE 1.70607 7.17E47 3.45E47 2.00E 07 1.30E 07 5.58508 1.70Ee 4.77E40 't.90E 00 9.00610 NE 1.12607 1.75607 3.26607 1.88607 1.21E-07 5.00E 08 1.67508 4.67000 1.85000 9.93E-10 ENE 1.00E47 2.13E47 2.67607 1.63007 1.05E-07 4.31E48 1.42E46 4.42E40 1.50E 00 8.64610 E 2.31E47 1.71E47 1.52E-07 1.40E47 1.06E-07 4.63Ee 1.52Ee 5.19500 2.48E40 1.50E00 ESE 3.50E-07 2.12E 07
2.50EW 1.48E 07 9.48EM SA8608 1.50Ee 6.92500 2.92E-00 1.93E SE 4.10E-07 3.70007 2.53EW 1.55507 1.11E 07 4.82508 1.81508 6.84G00 3.30E00 2.22E40 SSE 2.90E47 3.62E47 2.56507 1.40E07 1.11E& 5.02Ee 1.98EM 6.97E40 2.94600 1.70E00 S 1.87507 6.47Em 2.16E47 1.30E47 8.86508 4.00E-08 1.40E 08 4.96500 1.90E40 1.04E40 SSW 6.13E-08 4.16Em 1.56E47 1.03E.07 6.81E48 2.72E48 9.74E40 3.01 E-00 1.50E 00 8.23510 SW 6.76008 1.14E-07 1.70E.07 1.06E-07 6.93Ee 2.51606 9.34600 2.72500 1.33E 00 8.33E-10 WSW 8.52608 3.75EW 2.14E& 1.26507 7.74Ee 3.08Ee 1.02608 3.28600 1.30E-00 0.00E-10 W 1.15E47 5.80E-07 2.88E47 1.63E& 1.18E47 5.23E48 1.72E 08 5.06E40 1.98E 00 1.25E40 WNW 1.41E 07 6.28E47 3.30E& 2.19E-07 1.48E47 5.68508 1.96608 6.32E40 2.16E.00 1.34500 NW 1.42E47 5.67E47 3.17E47 1.03EW 1.30E47 5.67Em 2.06EG 6.90600 2.70600 1.45E 00 NNW 1.00607 5.77507 3.18E47 1.80607 1.27E 07 5.2r*e 1.77Em 4.82500 2.01500 1.22EW e STATION VENT DISTANCE o SECTOR AVERAGE D/O CN M-2) ON METERS) SEASON . ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 2.51E40 8.72510 4.84E-10 2.98E-10 2.50E 10 8.57E-11 2.51E-11 4.98E-12 1.57E 12 7.84E-13 NNE 3.80E4C 1.98E40 0.54610 4.90E-10 3.38510 1.10E-10 2.80E-11 6.06512 2.10E 12 8.80E-13 NE 2.58E40 6.70610 9.13E.10 4.91510 2.97510 1.04E 10 2.87511 6.01612 1.90E 12 9.23613 ENE 2.15E-00 5.85E-10 6.54510 3.06E 10 2.08E 10 8.30E-11 2.32E 11 5.41E 12 1.03E-12 7.64E 13 E 5.54E 00 1.23500 6.17510 4.50E 10 3.63E-10 1.34E-10 3.86511 9.44E-12 3.77E-12 1.97E-12 ESE 9.17000 2.06500 1.51500 8.86610 5.11 E-10 1.82E 10 5.77511 1.72E 11 7 "7512 4.07512 SE 1.22000 2.88E40 1.84000 1.02000 6.85E-10 2.80610 8.30E-11 2.34511 G $2E-12 5.51 E-12 SSE 7.50E40 1.62E40 1.08E40 5.80610 4.49E-10 1.87610 6.16E-11 1.61E 11 5.67E 12 2.83512 S 3.86G00 0.53E 10 6.27610 3.50E 10 2.32E-10 1.06E-10 3.05611 8.10E 12 2.73612 1.23512 SSW 1.13600 2.94510 4.19E 10 2.53610 1.56610 5.38E-11 1.88E 11 3.91E 12 1.84E.12 7.84513 SW 1.19000 3.84610 4.96010 2.80E 10 1.70E 10 5.24E 11 1.05511 3.62E-12 1.40E 12 8.12513 WSW 1.77E 00 8.31E-10 8.40E 10 3.50E 10 1.90510 6.73E 11 1.80611 4.58512 1.63E-12 9.90513 W 2.41500 1.20600 6.81E 10 3.65E-10 2.96510 1.12E-10 3.11511 6.90512 2.20E 12 1.25E 12 WNW 3.20500 1.30E-00 7.73E-10 5.91510 3.06610 1.19610 3.43E 11 8.36E-12 2.30612 1.20612 NW 3.25000 1.23600 7.30510 4.22E 10 2.77510 1.14E-10 7.28611 7.61E-12 2.02E 12 1.36612 NNW 1.98E40 9.88610 5.71 E-10 3.05E-10 2.23E 10 8.21E 11 2.41E 11 4.93E 12 1.72612 9.03E 13 DATA FROM 1/1/78 THROUGH 12/31/86 USED IN CALCULATIONS 121.0 m.
N l-AA.
04-17-98 11:13:03 Number
- 4U0l987 mot aceu contw8 s
Departmental Procedure 6610-PLN-4200.01 i Tih Rmmon No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 4 5 Atmospheric Dispersion Factors for Three Mile Island e OROUNO RELEASE DtSTANCE i e SECTOR AVERAGE X/O (IN SEC/M3 ) ON METERS) SEASON - ANNUAL q SECTOR 610 2413 4022 5631 7240 12067 24136 40225 56315 72405 N 1.16EG 1.13E-06 5.94E-07 3.80E.07 2.38E47 9.74608 3.46E48 9.28EG 3.52E40 2.05609 ; NNE 1.0$EM 1.10E 06 5.66E47 3.41E47 2.38E47 0.55608 3.11EM 8.94E-00 3.74E 00 1.84E40 l NE 7.02608 9.81E47 5.42E.07 3.17E47 2.10E47 9.01E48 110600 8.87E40 3.54600 1.91 E49 ENE 7.14606 9.64E47 4.92607 2.85E47 1.97607 7.82Ee 2.64608 8.38E 00 3.04E40 1.66600 l E 8.40E-06 1.00E46 5.48E47 2.91E47 1.87E-07 8.40EM 2.82EM 985600 4.75E 00 2.87EG l ESE 6.91E 06 9.02607 4.49E 07 2.57507 1.67507 7.20E4 2.77Em 1.12608 5.54E-00 3.68E40 l SE 6.70E.06 9.06E47 4.53E.07 2.81E47 2.03607 8.94E48 3.33608 1.28E48 6.19600 4.18600 SSE 7.26Em 9,26E47 4.91E47 2.87607 2.08507 9.18608 3.72Em 1.32Ea 5.62600 3.26E 00 S 8.70E46 0.08E47 3.90E 07 2.41 E-07 1.61547 7.31600 2.57E48 9.23E 00 3.74E40 1.95609 SSW 6.05E46 7.01E-07 2.75E47 1.86E47 1.24607 5.06Em 1.82E4 5.71E 00 2.87EG 1.58E40 SW 5.94EG 6.71E& 2.86E47 1.81E47 1.22E-07 4.50E48 1.72608 5.12E40 2.53E-00 1.50600 WSW 8.00E46 7.02607 3.60E47 ~ 2.15E47 1.34607 5.50008 1.87E-08 6.12E-00 2.62E 00 1.83600 W 1.02E-05 1.07E46 5.30607 3.02EW 2.05E& 9.31E-06 3.15E 08 9.48E40 3.74EG 2.38E49 WNW 1.16EM 1.13Ee 5.98E-07 0.67E 07 2.53E47 1.00E47 3.56E48 1.18608 4.07E40 2.54E-09 j NW t.13606 1.06E46 5.70E47 3.53E-07 2.40E47 1.02E.07 3.82E.06 1.11608 5.14000 2.78E-09 NNW 1.08E45 1.0 G 06 5.72E& 3.27007 2.22607 9.06608 3.20608 8.89600 3.75E 00 2.29609 eGROUND RELEASE DISTANCE e SECTOR AVERAGE D/O (IN M-2) (IN METERS) WSON ANNUAL SECTOR 610 2413 4022 6631 7240 12067 24135 40225 d.d 72406 N 2.30E48 1.88500 8.93E 10 4.82610 2.70510 8.96611 2.53E 11 4.98612 1.57512 7.84E13 l NNE 2.66E48 2.25600 1.06E40 5.42E-10 3.38E-10 1.10E 10 2.80E 11 8.06612 2.10E 12 8.89E.13 NE 1.75E 08 2.00600 1.01E 00 5.04510 2.98610 1.04E-10 2.88611 6.01E-12 1.90E-12 9.23E 13
! ENE 1.68608 1.85600 8.86610 4.28E-10 2.65010 8J57E-11 2.33E-11 5.41E 12 1.63E 12 7.64E.13
,l E 2.88608 2.90E40 1.30E49 6.34510 3.67610 1.36510 3.68611 0.42E-12 3.77E-12 1.97E 12 ESE 3.50E.08 3.80E 00 1.77600 8.79510 6.15610 1.83610 5.78E-11 1.71E-11 7.06612 4.06E-12 l SE 4.12E 08 4.56E 00 2.13500 1.15E.00 7.50610 2.72610 8.31E 11 2.34E-11 9.42612 5.50612 SSE 3.12E-08 3.23E40 1.50E40 8.00E 10 6J20E 10 1.88510 e.18E-11 1.61 E-11 5.68612 2.83 E.* 2 S- 2.65608 2.21E40 9.07610 4.75E 10 2.86E 10 1.07610 3.06E 11 8.10512 2.73E 12 1.23612 SSW 1.45E-08 1.30600 4.80610 2.82E 10 1.70610 5.71E 11 1.00611 3.91E 12 1.64E-12 7.84613 SW 1.42606 1.10E40 5.15610 2.82610 1.71E 10 5.24E-11 1.65E-11 3.62612 1.49E 12 8.12613 WSW 2.01E48 1.41E40 6.82E 10 3.54610 2.00E-10 6.76E-11 1.80611 4.58612 1.63612 9 90E.13
. W 2.55E48 2.16E 00 1.00E40 4.91510 3.01610 1.12610 3.11611 6.90612 2.27E 12 125012 WNW 2.88600 2.30E-00 1.13600 5.93E-10 3.67610 1.19610 3.43E 11 8.36612 2.30612 129612 g NW 2.78E-08 2.15E 00 1.06500 5.58E-10 3.41E-10 1.19610 3.57E-11 7.61E 12 2.92612 1.36E 12 NNW 2.17 E-08 1.75E40 875610 4.24E-10 2.57510 8.55611 2.42E-11 4.93E-12 1.72612 9 03E.13 E
DATA FROM 1/1/78 THROUOH 12/31/86 USED IN CALCULATIONS 122.0 mm
~04-17-981 t13:03 Nurnber Nuclear * "ad*a'cd ooa"d* Departroental Procedure 6610 PLN-4200.01 1 Tio. n.vWon No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 4.6 Dose Parameters for Radiolodines and Radioactive Partloulste in Gaseous Effluents
CRITICAL ORGAN CRITICAL ORGAN NUCUDE ORGAN FACTOR Pl* *

NUCUDE ORGAN FACTOR Pl***
H -3 " 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 P-32 BONE 7.04E-04 2.60E + 06 AG 110M LUNG 1.48E-03 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 4.00E-04 1.48E + 06 FE55 LUNG 3.00E 05 1.11E + 05 TE-127 GI-LU 1.52E 05 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 1.11E+ 06 TE 129 Gl-LU 6.89E-06 2.55E +04 C0-60 LUNG 1.91E-03 7.07E+06 TE-131M GI-LLI 8.32E 05 3.08E +05 NI-63 BONE 2.22E 04 8.21 E + 05 TE 131 LUNG 5.55E 07 2.05E + 03 N1-65 GI-LU 2.27E-05 8.40E + 04 TE-132 LUNG 1.02E-04 3.77E+ 05 CU-64 Gl LU 9.92E-06 3.67E + 04 l-130 TYHROID 4.99E-04 1.85E + 06 ZN45 LUNG 2.69E-04 9.95E + 05 l131 THYROID 4.39E-03 1.62E + 07 ZN-69 GI-LU 2.75E46 1.02E + 04 l132 THYROID 5.23E-05 1.94E + 05 BR43 TOTAL BODY 1.28E 07 4,74E + 02 1133 THYROID 1.04E-03 3.85E + 06 BR-84 TOTAL BODY 1.48E-07 5.48E+02 1-134 THYRO!D 1.37E-05 5.07E+ 04 BR45 TOTAL BODY 6.84E 09 2.53E + 01 1-135 THYROID 2.14E-04 7.92E + 05 RB-86 UVER 5.36E-05 1.98E + 05 CS-134 UVER 2.74E 04 1.01 E + 06 RB-68 UVER 1.52E-07 5.62E + 02 CS 136 UVER 4.62E-05 1.71E+ 05 RB 89 UVER 9.33E 08 3.45E+02 CS-137 BONE 2.45E44 9.07E+ 05 SR 89 LUNG 5.89E-04 2.18E + 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 Gl-LU 4.70E-05 1.74E + 05 BA-140 LUNG 4.71 E-04 1.74E + 06 SR 92 Gl LU 6.55E-05 2.42E + 05 BA-141 LUNG 7.89E47 2.92E+ 03 Y-90 GILLI 7.24E-05 2.68E + 05 BA 142 LUNG 4.44E-07 1.64E+ 03 Y-91M LUNG 7.60E 07 2.81E +03 LA 140 GILLI 6.10E-05 2.26E + 05 Y 91 LUNG 7.10E-04 2.63E + 06 LA-142 GI-LU 2.05E 05 7.59E + 04 Y-92 Gl-LU 6.46E 05 2.39E + 05 CE 141 LUNG 1.47E-04 5.44E + 05 Y 93 GI-LU 1.05E-04 3.89E+ 05 CE 143 GI-LU 3.44E-05 1.27E + 05 ZR 95 LUNG 6.03E-04 2.23E &O6 CE 144 LUNG 3.23E-03 1.20E + 07 ZR-97 Gl-LLI 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 GILLI 1.GOE 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-LU 1.73E-05 6.40E + 04 The listed dose parame;ers are for radionuclides, other trunn 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 include an increase of 50% to account for the additional amount of this nuclide absorbed through the skin.
~**
mrem / year per pCl/m'. 123.0 sm,
04-17-98 11:13:03 i Number Mggr [ 6610-PLN-4200.01 g ,
% e.
Omh Dose Calculation Manual (ODCM) , 12 FIGURE 4.1 TMl.1 Gaseous EtSuest Pathways .
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{ 124.0 **
04-17-98 11:13 03 l w,nd r Nuclear "Depamnental
" *' "a O im Procedure 6610-PLN-42DO.01 m No.
Offsite Dose Calculation Manual (ODCM) 12 FIGUFIE 4.2 TMI-1 Amdliary and Fuel Handling Buildings Ef8uent Pattmeys f
. j l
q g ==. un - som aus a a "E == E* 1
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BUILDING RH-A7 ? lulLDM mnata . j
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v - l AUX 1UARY W flEl. HNUE BUILDMiS EXHAUST RADIAlim l.gr SliRS AND SARING STATIDNS t.onta i
. 1 1
t.v - 125.0 mm A
04-17-98 11:13:03 Number 9 m N MF TM1 Radiological Controls Departmanal Procedw. 6610-PLN-4200.01 m no. Offsite Dose Calculation Manual (ODCM). . 12 FIGURE 4.3 TM-1 Reactor Building Efnuent Pathway nas 170 M-FEET REACTOR BUILDING PURGE EXPAIST
RADIAllDN HONITORS AND
" '8 SAMPLING STATIDNS O
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04-17-98 11:13 03
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DepsM Procedwo . 6610 PLN-4200.01 m men m. Ottsite Dose Calc'ulation Manual (ODCM) 12 FIGURE 4.4
1 TMI 1 Condenser OMges Emuent Pathway '
CONDENSER OFF GAS STACK 3 CONDENSER OFF GAS 115 EXHAUST FEET (m RADIATION HONITDRS AND SAMPLING STATIONS
j m mW
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/ / = g MAIN t CONDENSER j D . D eneonte
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17-98 11:13:03 Number Nuclear " ":d'd o' "a* Departmental Procedure 6610-PLN-4200.01 rio. a.vwon uo. Ottsite Dose Calculation Manual (ODCM) 12 6.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents -Instantaneous Release Umits
)
5.1.1 Noble Gases 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 Dose Rate. = I(K,) x (Dv) x (Q,) (eq 5.1.1.1) I where: l Dose Rate,, = instantaneous total body dose rate limit, at the site boundary, in mrem /yr. I K, = total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr per pCl/m' from Table 4.3. Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m', from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off l Gas, ESF FHB, and ground releases). Maximum values presently in use l are 7.17E-7 sec/m' at sector NNE for station vent, and 1.16E-6 spc/m' for all other releases, at sectors' N and WNW 0, = Release rate of radionuclide,1, in pCl/sec as detennined 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. 129.0 mm
04 17-98 11:13:03 nunber Nuolear ' "*doo'd ooat* Departmental Procedure 6610-PLN-4200.01
u. m no.
Offsite Dose Calculation Manual (ODCM) 12 5.1.1.2 Skin . Dose Rate = I(i., + 1.1 M) X (Dv) X (Q) (eq 5.1.1.2), I where: Dose Rate = instantaneous mrem / year skin dose rate limit, at the site boundary, in mrem /yr. (= skin dose factor due to beta emissions for each klentified noble gas radionuclide, in mrem /yr per pC1/m' from Table 4.3. M, - alt dose factor due to gamma emissions for each ident! fled noble gas radionuclide, In mrad /yr per pCl/m' from Table 4.3. 1.1 = mrem skin dose per mrad air dose. Converts air dose to skin dose. t Q, - release rate of radionuclida, 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. Dv = highest sector annual average gaseous dispersion factor (X/0) at or beyond the unrestricted area boundary, in sec/m', 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/m' at sector NNE for station vent, and 1.16E-5 sec/m' for all other releases, at sectors N and WNW. 130.0 mm I
04-17-98 11:13:03 l Number Nuclear "ad'd S**' "*d Departmental Procedure 6610-PLN-4200.01 , Tm. w ion no. l l Offsite Dose Calculation Manual (ODCM) 12 ! 1 ! 5.1.2 lodine-131. lodine-133. Tritium and Radionuclides in Particulate Form. with Half-Uves Greater than 8 Days l For 1131, !-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 . days, the following equation applies: Dose Rate, = Z (P) (Dv) (Q) (eq 5.1'.2) I i ' where:
, Dose Rate, = mrem / year organ dose rate.
P, = dose parameter for 1-131, l.133, Tritium and Radionuclides in Particulate Form, with half 4fves greater than 8 days, for the inhalation pathway, in mrom/yr per pCl/m', from Table 4.6. The dose factors are based on the critical individual organ and most restrictive age group (child). 1 Dv = highest sector annual average gaseous dispersion factor (X/O or D/Q) at or beyond the unrestricted area boundary, in sec/m', from Table 4.4 for the station vent releases and Table 4.5 for all other releases. X/Q is used l for the inhalation pathway. Maximum values of X/Q presently used are 7.17E-7 sec/m' 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. s 131.0 me,
04-17-98 11:13:03 Numbw Nuclear ' "ad'doa**' co""* Departmental Procedure 6610-PLN-4200.01. me n.vWon No. l
' Offsite Dose Calculation Manual (ODCM) 12 5.2 Gaseous Effluents - 10 CFR 50 Appendix 1 5.2.1 Noble Gases The air dose in an unrestricted area due to noble gases released in gaseous effluents from the site is determined using the following expressions:
Dose r = (3.17E-4) x Z (M) x (Dv) x (01) (eq 5.2.1) I and Dose p = (3.17E-8) x Z (N) x (Dv) x (Qi) (eq 5.2.2) I where: Dose r - mrad gamma air dose due to gamma emissions from noble gas radionuclides. Dose # = mrad beta air dose due to beta emissions from noble gas radionuclides. M, = air dose factor due to gamma emissions for each identified noble gas radionucilde, in mrad /yr per pCl/m', from Table 4.3. N, = air dose factor due to beta emissions for each identified noble gas radlonuclide, in mrad /yr per pCl/m', from Table 4.3. Dv = highest sector annual average gaseous dispersion factor, X/Q, at or beyond the unrestricted area boundary, in sec/m*. Values may be read or
; interpolated from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. Maximum values of X/O presently used are 7.17E-7 sec/m 8for station vent at sector NNE, and 1.16E-5 sec/m' for all other releases at sectors N or WNW.
Q, = release of noble gas radionuclide, I, in pCl, over the specified time period, (pCl/second
seconds).
3.17E4 = irwerse of the number of seconds in a year. NOTE I If the methodology in this section is used in de' termining dose to an individual, rather than air dose due to noble gases, substitute K1, from Table 4.3, for MI, and (LI + 1.1 Mi) for N1. 132.0 mm
04-17-98 11:13:03 Nurnber ggy TMi Radiological Controls Departmental Procedure 6610-PLN-4200.01 j
m. n. Won No.
Offsite Dose Calculation Manual (ODCM) 12 5.2.2 lodine-131, lodine-133. ' Tritium and Radionuclides in Particulate Form. with Half-Lives Greater than 8 Davs The dose to an individual from I 131,1-133, Tritium and Radlonuclides 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 expression: Does, = Z(3.17E-s) 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 group, a, from 1-131,1133, Tritium and Radlonuclides 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 mram/yr per pCl/m' for the inhalation pathway and m' - mrom/yr perpCl/sec for other pathways, from Tables 5.2 to 5.7. NOTE Since there is minimal or no elemental lodine released from the condenser off-gas air ejector (see NUREG-0017) all lodine f\ values for all pathways, gx.gggt the inhalation pathway, are considered to be zero when performing dose calculations for releases from the condenser off-gas air ejector. Only calculate the dose due to the inhalation pathway for condenser off-gas air ejector lodines. i NOTE Tritium, H-3, dose factor is mrem / year per pCl/m' for all pathways.
Dv = highest sector annual average gaseous dispersion factor (X/Q) at or i
beyond the unrestricted area boundary, in sec/m', for the Inhalation pathway, and D/Q, in m, for other pathways. Table 4.4 is used for station vent releases and Table 4.5 for all other releases. Maximum values of X/Q presently used are 7.17E 7 sec/m' for station vent at sector NNE and . 8 1.16E-5 sec/m for all other releases et sectors N and WNW. Maximum values of D/O in m 8for station vent is 1.22E-8/m' at sector SE, and for ground releases, 4.12E4/m' for sector SE. Dv(H-3) = In the cete of H4 only the X/Q's are used for all pathways from Table 4.4 for station vent releases and Table 4.5 for all otler releases. 133.0 22,
04-17-98 11:13:03 Number (UClear i Radiological Conkols Departmental Procedure 6610-PLN-4200.01 me Wn No. Offsite Dose Calculation Manual (ODCM) 12 O, = release of I-131,1-133, Tritium and Radionuclides, l. In Particulate Form with ' 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. l. l I I i i 1 1 1 i l I ' 134.0 mm 1 1
04-17-98 11:13.03 , Number gg TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 l im. FWWon No. l Offsite Dose Calculation Manual (ODCM) 12 5.3 Gaseous Radioactive System Dose Calculations Once oer 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 projeMed doses due to the gaseous effluent releases from the site would exceed: 0.2 mrad to alt 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 to-date 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 TMl-1 Gaseous Waste Treatment System, as defined in Section 6.0, or appropriate portions of the TMI-2 Gaseous Effluent Filtration System as shown on Figure 4.5, shall be used to reduce radioactMty levala p&r to re' ease. At the discretion of Radiological Engineering, time periods other than the current quarter-todte 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. 135.0 m.,
04 17-98 11:13:03 Number Nuclear ' "aao9d coa* Departmental Procedure 6610-PLN-4200.01 me RevWon No. Offsite Dose Calculation Manual (ODCM) 12 5.4 Alternative Dose Calculational Methodoloales for Gaseous EfMuentr, As an alternative to the methods described above, the models infor based upon, those presented in . Regulatory Guide 1.109 (Rev.1) may be used to make a comprehensive dose assessment. Default j 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 gaseous dispersion factors. As an altemative dose calculational methodclogy. GPU Nuclear 3 calculates doses using an advanced class 'A' dispersion model called SEEDS (simplified environmental effluent dosimetry system). This model incorporates the guidelines and methodology set forth in USNRC Regulatory Guide 1.109, and uses actual hourly meteorological Information matched to the time of releases to more ! accurately assiess the dispersion of effluents in the atmosphere. Combining this assessment of j dispersion with TMINS effluent data for each unit, postulated maximum hypothetical doses to the i public are calculated.
]
1 i l l l l a l
)
1 1 138.0 mm
(C 97Afle9f:98 M l l Numbw lE4CIS8r
~
TMI Radiological Controla Departmental Procedure 6610-PLN-4200.01 Title Main No.
OffsNe Dose Calculation Manual (ODCM) 12 TABLE 5.2.1 Pathway Dose Factors, RI AGE GROUP: INFANT PATHWAY: INHALATION ORGAN DOSE FACTORS: mrem / year per pCl/m' NUCUDE ------------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
BONE UVER T. BODY THYROID KIDNEY
.............. ...._. _._ ... ...._.... ......._. _ . . _... LUNG =. ....GI.-l...U 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 '5.31E+ 03 5.31E+ 03 5.31 E + 03 5.31E + 03 5.31 E + 03 5.31 E + 03 CR-51 0.00E +00 0.00E + 00 8.95E + 01 5.75E + 01 1.32E4 01 1.28E + 04 3.57E + 02 MN-54 0.00E + 00 2.53E + 04 4.98E + 03 0.00E + 00 4.98E + 03 1.00E + 06 7.06E + 03 FE-55 1.97E+ 04 1.17E + 04 3.33E+03 0.00E+ 00 0.00E + 00 8.69E+ 04 1.09E + 03 FE-59 1.36E + 04 2.35E + 04 9.48E + 03 0.00E + 00 0.00E + 00 1.02E + 06 2.48E + 04 CO-58 0.00E + 00 1.22E + 03 1.82E + 03 0.00E + 00 0.00E + 00 7.77E + 05 1.11 E + 04 C0-60 0.00E + 00 8.02E + 03 1.18E+ 04 0.00E + 00 0.00E + 00 4.51 E + 06 3.19E + 04 N1-63 3.39E +05 2.04E + 04 1.16E + 04 0.00E + 00 0.00E + 00 2.09E + 05 2.42E + 03 ZN-65 1.93E + 04 6.26E + 04 3.11 E+ 04 0.00E + 00 3.25E+ 04 6.47E+ 05 5.14E + 04 RB-P6 0.00E+ 00 1.90E+ 05 8.82E+ 04 0.00E+00 0.00E + 00 0.00E + 00 3.04E + 03 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 1.31E+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 7.03E + 04 0.00E + 00 3.11E + 04 1.75E + 06 2.17E + 04 NB-95 1.57E + 04 6.43E + 03 3.78E+ 03 0.00E + 00 4.72E + 03 4.79E+05 1.27E + 04 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_ __. 1.67...E ... + 04_ ..
6.90E...
+ _03__
2.07E... + 03 4.87
.....E+03_____ 1.3 J. 75E + 04.... ..... ._ .. 73E ..1E+06 2. + 04 TE 129M 1.41E +04 6.09E + 03 2.23E + 03 5.47E+ 03 3.18E + 04 1.68E + 06 6.90E + 04 l-131 3.79E + 04 4.44E + 04 1.96E+ 04 1.48E+ 07 5.18E+04 0.00E+00 1.06E+ 03 1-133 1.32E+ 04 1.92E + 04 5.60E + 03 3.59E + 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 CS-136 4.C3E + 04 1.35E + 05 5.29E + 04 0.00E+ 00 5.64E+ 04 1.18E+ 04 1.43E+ 03 CS 137 5.49E + 05 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 CE_. .144 3.19E + 06 1.21 E + 06 1.76E + 05 0.00E + 00 6.38E + 05 ' 9.84 E + 06 1.48E + 05 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
___ _.. .... ..__... . .. _ _.._ _... . . . ..._ _ 3.15 E +...____. 03 3.22E+ ......_05 3.12E .___ + 04 137.0 em. I
1 04-17-98 11:13:03 Number M Radiological Comrols GEJOlear Departmental Procedure 6610 PLN.4200.01
m. %.on No.
Offsite Dose Calculation Manual (ODCM) , 12 TABLE 5.2.2 Pathway Dose Factors, RI AGE GROUP: CHILD PATHWAY: INHALATION NUCLIDE
-------------- ORGAN DOSE FACTORS; mrem / year per pCl/m' BONE LIVER T. BODY THYROID KIDNEY LUNG GlLLI H3 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
0. 0.00E + 00 1.54E + 02 8.56E+01 2.43E+ 01 1.70E+ 04 1.0 CR 61______. __ _00E
__....+ 00..___.... __.. .. _____...__.... ..__..__...___ . 8E+03-- MN64 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 1.11 E + 05 2.87E + 03 FE-59
.___.07E + 04 3.34E + 04 1.67E +
2.
...... .__..... - ... .04 0.00 0.00E + 00.. _ _ _ . ..___... E + 00 1.27E.+.06 7.0 ._. 7E + 04 ...
CO-58 0.00E + 00 1.77E + 03 3.16E + 03 0.00E + 00 0.00E + 00 1.11 E + 06 3.44E + 04 C040 0.00E + 00 1.31 E + 04 2.26E + 04 0.00E + 00 0.00E+ 00 7.07E + 06 9.62E + 04 Ni-63 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 1.01 E + 08 0.00E + 00 6.44E + 06 0.00E + 00 65E+00 1.48bO7 3 E+~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 ,0.14E + 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 + 04 . ._ -._. - .._-..._. _-..._ - ..__...._ - ... _ . - .. . _=- _-.
TE 129M 1.92E +04 6.85E+03 3.04E+ 03 6.33E+ 03 5.03E+ 04 1.76E + 06 1.82E + 05 l131 4.81 E + 04 4.81 E + 04 2.73E + 04 1.62E + 07 7.88E + 04 0.00E +00 2.84E + 03 1133 1.66E + 04 2.03E + 04 7.70E + 03 3.85E + 06 3.38E + 04 0.00E + 00 5.485 + 03 CS-134 6.51 E + 05 1.01E + 06 2.2SE + 05 0.00E + 00 3.30E+05 1.21E+05 3.85E+0[ 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 8.25E + 05 1.28E + 05 0.00E + 00 2.82E + 05 1.04E + 05 3.62E + 03 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 CE...144 ..... 6.77E +.......-- ......... 06 2.12E + 06 3.61E.__+__._..05_0.00E + 00 1.17E + 061.20E+
07 3.89E + 05 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 6.81E + 02 0.00E+ 00 4.81 E+ 03 3.28E + 05 8.21 E + 04 138.0 mm
04 17-98 11:13:03 l Number jgggp TMI Radiological Controts Departmental Procedure 6610-PLN-4200.01 , rm awwon m. Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.2.3 l l Pathway Dose Factors, RI AGE GROUP: TEEN PATHWAY: INHALATION
.. . .. l ...... . _ .. . ._. ... - ........ ......... _ __......_..._-.... \
NUCLlDE
'------------ ORGAN- DOSE FACTORS: mrem / year per pCl/m' l
BONE
....._......._....____....__.....___............_.........___-LLI H-3 0.00E +00 LIVER T. BODY THYROID KIDNEY LUNG GI 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 l CR41 0.00E + 00 0.00E + 00 1.35E + 02 7.50E + 01 3.07E + 01 2.10E + 04 3.00E +03 '
MN44 0.00E + 00 5.11 E + 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 0 0-58 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 N143
....... __5.80E + 05 4.34E + 04_____1.98E .._......_.......04.._ + . 0.00E + 00 0.00E + 00 . .. ._..__.... 3.07E ..+ _______......__.
05 1.42E + 04 ZN45 3.86E + 04 1.34E + 05 0.24E + 04 0.00E + 00 8.64E + 04 1.24E + 06 4.66E + 04 RB-86 0.005 + 00 1.90E + 05 8.40E + 04 0.00E + 00 0.00E + 00 0.00E + 00 1.77E + 04 SR 4.34E + 05 0.00E + 00 1.25E + 04 0.00E + 00 0.00E + 00 2.42E + 06 3.71E + 05
. _-89 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 6.61E+ 05 0.00E + 00 1.77E+ 04 0.00E+ 00 0.00E+ 00 2.94E+ 06 4.09E + 05 ZR 1.46E + 05 4.58E + 04 3.15E + 04 0.00E + 00 6.74E +04 2.69E + 06 1.49E + 05
_ .-95 ...... ....__... ...__.... . ..___ ..___..._..._ ..... .... .__... _ .. NB-95 1.86E + 04 1.03E + 04 5.66E + 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 1.61E + 07 9.60E + 05 AG-110M 1.38E + 04 1.31E + 04 7.99E+ 03 0.00E+ 00 2.50E + 04 6.75E + C6 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 TE 1.80E + 04 ........ 8.16E +...._______.... 03 2.18E + 03 4.38E +03 6.54E+04 1.66E+06 1.59E+ 05 __ _ -127M .- . ..... __.. ____...__ .._ . _ .. __.... TE-129M 1.39E + 04 6.5BE+03 2.25E + 03 4.58E + 03 5.19E+04 1.98E + 06 4.05E'+05 l131 3.54E + 04 4.91E + 04 2.64E + 04 1.46E + 07 8.40E + 04 0.00E+ 00 6.49E + 03 1133 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 5.49E + 05 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 3.11E + 05 0.0 3.04E+ 0
.. ....___.. ... ..____ . ..0E+00 ...... . 5 .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 + 0 2.02E +06 2.62E + 05 0.00E + 00 1.21E+ 06 1.34E + 07 8.64E + 05 .._.....____6 _ ........ ........ ...... . _ ..___.. . . .____.__
PR 143 1.34E + 04 5.31F + 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 + 05 139.0 mm
04 17 98 11:13:03 Number i Radidogical Contrds GUOledhr Departmental Procedure 6610-PLN-4200.01 Tme RevWon No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.2.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: INHALATION ORGAN DOSE FACTORS; mrom/ year per pCl/m' NUCUDE --- = = = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - BONE LIVER T. BODY THYROID KIDNEY LUNG Gl-LLI H4 0.00E +00 1.26E + 03 1.26E +03 1.26E+ 03 1.26E+ 03 1.26E+ 03 1.26E +03 C-14 1.82E + 04 3.41 E +03 3.41 E + 03 3.41 E + 03 3.41 E + 03 3.41 E + 03 3.41 E + 03 CR41 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 + 05 CO-58 0.00E + 00 1.58E + 03 2.07E + 03 0.00E + 00 0.00E+ 00 9.i8E + 05 1.06E + 05 C040 0.00E + 00 1.15E + 04 1.48E + 04 0.00E+00 ' O.00E+00 5.97E + 06 2.85E +05 N!-63 4.32E + 05 3.14E +04 1.45E + 04 0.00E + 00 0.00E+00 1.78E + 05 1.34E +04 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 1.25E+ 05 5.90E + 04 0.00E + 00 0.00E +00 0.00E + 00 1.66E + 04 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. 3.44E + 04 2.33E + 04 0.00E + 00 5.42E+04 1.77E + 06 1.5 .....
.__..07E+05 .__ . ...._... ....___. ....__... ..._______........__ ..0.E+05 NB-95 1.41 E + 04 7.82E + 03 4.21 E + 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 6.91 E + 04 0.00E + 00 8.72E + 03 0.00E + 00 1.34E + 05 9.36E + 09 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 1.26E + 04 5.77E +03 1.57E + 03 3.29E+ 03 4.58E + 04 9.60E+ 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 l-131 2.52E + 04 3.58E + 04 2.05E + 04 1.19E + 07 6.13E+04 0.00E +00 6.28E + 03 1133 8.64E +03 1.48E + 04 4.52E + 03 2.15E + 06 2.58E + 04 0.00E + 00 8.88E + 03 CS 134 3.73E + 05 8.43E + 05 7.20E + 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 1.20E + 05 CE-144 3.43E + 06 1.43E + 06 1.84E + 05 0.00E+00 8.48E + 05 7.78E+06 8.16E + 05 PP 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 2.21E+ 05 1.73E+05 140.0 mm
'04-17-98 11:13:03 ) Number EIEI TMI Radiological Corgrois Departmental Procedure 6610-OLN-4200.01 l 1
w. ~~'
a.vwen No. ! Offsite Dose Calculation Mailual (ODCM) 12 TABLE 6.3.1 ' Pathway Dose Factors, Rl AGE GROUP: ALL PATHWAY: GROUND PLANE
........._.r -____. .
8 ORGAN DOSE FACTORS
i i NUCLlDE -----------4 l T. BODY SKIN s '
.._____..q H4 0.00E + 00 0.00E + 00 C-14 0.00E + 00 0.00E+ 00 CR-51 4.65E + 06 5.50E + 06 MN-54 1.39E + 09 1.62E + 09 FE-55 0.00E + 00 0.00E+ 00 FE-69 2.73E + 08 3.21E + 08 CO-68 3.79E + 08 4.44E + 08 CO-60 2.15E + 10 2.53E+ 10 l 0.00E + 00 0.00E + 00 NI..-63 .... ........... l 4
ZN45 7.47E+ 08 8.59E + 08 RB-86 8.97E + 06 1.03E + 07 SR-89 2.16E + 04 2.51 E + 04 4 f SR -90 0.00E + 00 0.00E + 00 l 1 Y-91 1.07E + 06 1.21 E + 06 ZR-95 NB-95 2.45E + 08 1.37E+08 2.84E+08]l 1.81E+ 08 RU 103 1.08E + 08 1.26E + 08 R 4.22E + 08 5.06E + 08
...U-106 . . . . . . . .
l AG-110M 3.44E + 09 4.01 E + 09 TE-125M 1.55E + 06 2.13E + 06 TE-127M 9.17E4 04 1.08E+ 05 TE-129M 1.98E + 07 2.31 E + 07 l-131 1.72E + 07 2.09E + 07 - I133 2.45E + 06 2.98E+06j
; CS-134 6.86E + 09 8.00E + 09 i CS-136 1.51 E + 08 1.71 E + 08 ' CS,137 1.03E + 10 1.20E + 10 .
4 BA 140 2.06E+ 07 2.36E+07 l CE-141 1.37E + 07 1.54E + 07 CE
p. -144 6.96E + 07 8.05E + 07 l-4 0.00E + 00 l ND PR-143 0.00E + 00 l L -147 8.39E+ 06 1.01E+07) a m'- mrem / year per pCI/sec.
141.0 nm
04-17-98 11:13:03 Numbw l E NucleaI ya
' "*d'd**' o"d*
Departmental Procedure 6610-PLN-4200.01 Wn No. l i Offsite Dose Calculation Manual (ODCM) 12 l l l
~ TABLE 5.4.1 Pathway Dose Factors, Ri 4
AGE GROUP: INFANT PATHWAY: GRASS-COW-MILK i
.- _.. .... 1 ORGAN DOSE FACTORS; m' - mrem / year per pCl/sec 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 , CR51 0.00E + 00 0.00E + 00 1.61 E + 05 1.05E + 05 2.30E +04 2.05E + 05 4.70E E06 l M-54 0.00E + 00 3.91 E +07 8.85E + 06 0.00E +00 8.65E + 06 0.00E + 00 1.43E +07 FE-55 1.35E + 08 8.74E + 07 2.34E + 07 0.00E+ 00 0.00E + 00 4.27E + 07 1.11 E + 07 I FE-59 2.25E + 08 3.93E + 08 1.55E + 08 0.00E + 00 0.00E + 00 1.16E + 08 1.88E +08 ;
~ ~ ~ ~
i CO-58 0.00E + 00 2.43E + 07 6.06E +07 b.00E+iO~~b2IOE'+00. 0.00E+00 6.05E+bi CO-60 0.00E + 00 8.83E +07 2.08E + 08 0.00E + 00 0.00E + 00 0.00E + 00 2.10E + 08 N143 3.50E + 10 2.16E +09 1.21 E + 09 0.00E + 00 0.00E +00 0.00E + 00 1.08E + 08 ZN45 5.56E + 09. f.91E + 10 8.79E + 09 0.00E + 00 9.24E + 09 0.00E +00 1.61 E + 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 3.62E + 08 0.00E + 00 0.00E + 00 0.00E + 00 2.59E + 08 SR-90 1.22E + 11 0.00E + 00 3.10E + 10 0.00E + 00 0.00E + 00 0.00E + 00 1.52E + 09 Y-91 7.34E + 04 0.00E + 00 1.95E + 03 0.00E +00 0.00E + 00 0.00E + 00 5.26E + 06 ZR 1.66E + 03 1.18E + 03 __..-95 .__... 6.81 E + 03
. __ . . . . ._.. . _.. . . ._ _ _ .000.E.____. + 00 1.79E + 03 0.00E + 00 8.27E +05 NB-95 5.94E + 05 2.45E + 05 1.41 E + 05 0.00E + 00 1.75E + 05 0.00E+ 00 2.07E + 08 RU-103 8.68E + 03 0.00E + 00 2.90E t 03 0.00E + 00 1.81E+ 04 0.00E + 00 1.06E + 05 RU-106 1.91E + 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 1.46EME TE-125M 1.51E +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 l131 2.72E + 09 3.21 E + 09 1.41 E + 09 1.05E + 12 3.75E + 09 0.00E + 00 1.15E + 08 l133 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 6.81 E + 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 6.65E + 09 1.89E + 08
~~ ~ ~ ~~~~
BA IM~~~E.42E + b8 E.EE+05 1.25E + 07 ~52ICIE+bb~5.75E +b4 1.49E + 05 5.94E+b[ CE-141 4.34E + 04 2.65E + 04 3.12E + 03 0.00E + 00 8.17E +03 0.00E + 00 1.37E + 07
.CE-144 2.33E + 06 9.53E + 05 1.30E + 05 0.00E + 00 3.85E + 05 0.00E + 00 1.34E + 08 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 + 05 142.0 me. ,
04-17 98 11:13:03 i Number
$tIOl88r m Raw oic i Comrois Departmental Procedure 6610-PLN-4200.01 Title AeWoion No.
Offsite Dose Calculation Manual (ODCM) 12 1 1 1 TABLE 5.4.2 l Pathway Dose Factors, RI ' AGE GROUP: CHILD PATHWAY: GRASS
..._.._g_g g.g. 7.__. . -COW-MILK . . . _ . _ . .
NUCLIDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - BONE LIVER T. BODY TH KIDNEY ___............_......._.._______....YROID .__ _...... LUN _........G._..._GI-LLI H4 0.00E + 00 1.57E + 03 1.57E + 03 1.57E + 03 1.57E + 03 157E+03 1.57E + 03 0 14 1.20E + 09 2.39E+ 08 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 l 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 6.89E + 06 0.00E +00 1.76E + 07 FE 65 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 + 00 0.00E + 00 0.00E+ 00 7.08E + 07 C040 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 1.07E+ 08 i
.. ... ..._......___.1.01 E.. + ...09 0.00E .+ ... 00 0.00E .... ... + ...
00 0.00E
... ...... + 00 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 1.89E +08 0.00E + 00 0.00E+ 00 0.00E+ 00 2.57E+ 08 SR-90 1.12E + 11 0.00E + 00 2.84E + 10 0.00E+ 00 0.00E + 00 0.00E + 00 1.51 E + 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 3.84E + 03 8.43E + 02 7.51 E + 02 0.0 1.21 E + 03 0.00E + 00 8.80E + 05
_.._......-.......___........._..___..._..0E+00 _ZR-95 ... ...... . ....___.... .... 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-100 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 1.41 E + 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 0.00E + 00 0.00E+ 00 7.13E + 07 TE-127M 2.08E + 08 5.61E + 07 2.47E + 07 4.9BE + 07 5.94E + 08 0.00E + 00 1.69E + 08 1 TE-129M 2.72E+ 08 7.59E + 07 4.22E + 07 8.76E + 07 7.98E+ 08 0.00E + 00 3.31E + 08 l-131 1.31 E + 09 1.31 E + 09 7.46E + 08 4.34Ti+ 11 2.18E + 09 0.00E + 00 1.17E + 08 1-133 l 1.72E + 07 2.13E + 07 8.05E +06 3 3.55E+ 07 0.00E+ 00 8.
-__..___......._.._________......__E..E+09 .... ....... ..... .. 58E 4 06 .......
l' CS-134 2.27E + 10 3.72E + 10 7.85E+ 09 0.00E+ 00 1.15E+ 10 4.14E + 09 2.01 E + 08 CS-136 1.01E + 0c 2.79E + 09 1.80E + 09 0.00E + 00 1.49E + 09 2.21 E + 08 9.80E + 07 CS-137 3.23E + 10 3.09E + 10 4.56E + 09 0.00E + 00 1.01E + 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 6.96E+07 I I 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 , 143.0 na
l 04-17-98 11:13:03 ' 1 1 Humber ggggggy M RaMogkal Controla Departmental Procedure 6610-PLN.4200.01 htte Revistori No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 6.4.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-COW-MILK 8 NUCUDE ------------ ORGAN DOSE FACTORS; m mrem
/ year per pCl/sec BONE UVER T. BODY THYROID KIDNEY LUNG GI-U.I H3 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 4.9 . . . .._ ......_ _ .. 9E + 04..... 2.77E + 04 1.09E + 04 7.13E+ 04 8.39 ...._____.E + 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 2.01 E + 07 1.37E + 07 FE 5.19E+07 1.21E + ..-59
___ .... ... ..___.08 4.68E
+ 07......___
0.00E+ 00 0.00E + 00 3.82E + 07 2.86E + 08 CO-68 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 NI43 1.18E + 10 8.36E+ 08 4.01E+ 08 0.00E+00 0.00E+ 00 0.00E + 00 1.33E + 08
. ZN-65 2.11E + 09 7.32E + 09 3.42E+ 09 0.00E+00 4.69E+ 09 0.00E + 00 3.10E + 09 RB-86 0.00E 4 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 7.67E + 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 ZR-05 1.65E + 03 5.21 E + 02 3.58E + 02 0.00E+00 7.65E + 02 0.00E + 00 1.20E + 0S 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 0.00E + 00 0.00E + 00 8.87E + 07 TE 8.45E + 07 1.00E + 07 2.01 E + 07 3.42E + 08 ..__-127M
_..... ........ .. 003.E ._+ _07 .. .... . . . _ __...._ _ .....
0. 00 E + 00 2.11E + 08 TE-129M 1.10E+ 08 4.09E + 07 1.74E + 07 3.56E + 07 4.61E+08 0.00E+ 00 4.14E + 08 l131 5.30E + 08 7.53E +08 4.05E +08 2.20E + 11 1.30E + 09 0.00E + 00 1.49E + 08 l133 7. 3.66E + 06 1.68E +
._______.. 08E + 06.._1.20E. +..07....__... .......09 2.11E + 07 .. . _..___ 9.09 0.00E + 00 ..E +...__
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 CS-137 1.34E + 10 1.78E + 10 . 6.21E + 09 0.00E+00 6.06E + 09 2.36E+09 2.54E + 08 BA 140 4.87E + 07 5.97E + 04 3.14E +06 0.00E+00 2.02E + 04 4.01 E + 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 CE 144 6.59E+05 2.73E.... + 05 3.54E + 04 0.00E + 00 1.63E +05 0.00E + 00 1.66E + 08 PR-143 2.90E + 02 1.16E + 02 1.44E + 01 0.00E+ 00 6.73E + 01 0.00E + 00 9.55E + 05 i ND-147 1.81E + 02 1.97E+02 1.18E + 01 0.00E + 00 1.16E + 02 0.00E + 00 7.12E + 05 i 1 144.0 ma
04 17 98 11:13:03 . 1 Number I jug TM) Radiological Cordrois Departmernal Procedure 6610-PLN-4200.01
m. Revision No.
Offstte Dose Calculation Manual (ODCM) 12 TABLE 5.4.4 Pathtmy Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MILK NUCt.lDE
------------- ORGAN DOSE FACTORS; m' mrom/ year per pCl/sec l ~ ~
BONE LIVER T. BODY THYROID KlDNEY LUNG GI-LLt
~~ ~ 'IIT~~~~
C 14
~0 d~EI~0b~~f.EIE2~~f.~62 IE2~~f.~h~EIE2~f.EIE2~f.EI0E~f.EIOE 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 2.51E+ 07 1.73E4 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 4.71E + 06 1.05E + 07 0.00E+ 00 0.00E+ 00 0.00E + 00 9.54E+07 CO-60 0.00E + 00 1.64E + 07 3.61E + 07 0.00E + 00 0.00E + 00 0.00E + 00 3.08E+ 08 NI-63 6.72E + 09 4.65E + 08 2.25E + 08 0.00E +00 0.00E+00 0.00E+00 9.71E+ 07 ZN-65 1.37E + 09 4.36E + 09 1.97E + 09 0.00E + 00 2.91E + 09 0.00E +00 2.74E +09 RB-80 0.00E + 00 2.59E + 09 1.21E + 09 0.00E+ 00 0.00E + d 0.00E+ 00 5.10E + 08 SR-89
.. . . ...1.45E + .. _ _09. 0.00E + 00 4.16E + 07 .. 0.00E + 00.. ... 0.00E 00 0.00.E.. + 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 2 8-95 9.41E + 02 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 2.04E + 04 0.00E + 00 2.58E + 03 0.00E+ 00
_106 _.. . . _ _ . ..._ _... _ _. _ _.._.. . . .. .. 3.93 E + 044...___...
..... 0.00E + 00 1.32E + 06 AG 110M 5.81E + 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-127M 4.57E + 07 1.63E+ 07 5.57E+06 1.17E + 07 1.86E + 08 0.00E+00 1.53E + 08 TE 129M 6.01E + 07 2.24E + 07 9.51E+06 2.06E + 07 2.51E+ 08 0.00E + 00 3.02E + 08 l131 2.96E + 08 4.23E+ 08 2.42E + 08 1.39E + 11 7.25E+ 08 000E+ 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 + 03 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 1.01E + 10 6.60E+ 09 0.00E+ 00 3.42E+09 1.14E+09 1.95E+ 08 BA-140 2.69E + 07 3.38E + 04 1.76E+ 06 0.00E + 00 1.15E + 04 1.94E + 04 5.54E + 07 CE-141 4.84E + 03 3.27E + 03 3.71 E + 02 0.00E+ 00 1.52E + 03 0.00E+ 00 13tSE+07 CE 144 3.57E + 05 1.49E + 05 1.92E + 04 0.00E + 00 8.85E + 04 0.00E+00 1.21E + 08 PR 143 1.57E +02 6.32E + 01 7.81 E + 00 0.00E + 00 3.65E + 01 0.00E + 00 6.90E + 05 ND 147 9.40E + 01 1.09E >02 8.50E+00 0.00E + 00 6.35E +01 0.00E +00 5.22E + 05 145.0 me.
'04 17 98 11:13:03 Number gggy- TM) Radiological Controls Departmental Procedure 6610-PLN.4200.01 ltte Revision No. Offsite Dose Calculation Mant.al (ODCM) 12 TABLE 5.6.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK ORGAN DOSE FACTORS; m8 . mrem / year per pCl/sec NUCLIDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
---- BONE UVE .. _ . ..._.. __ ...R. ...T.B ODY ...... THYROID .____.. . ..KIDNEY ._____L_U.NG. _ . ...GI-LU H-3 0.00E + 00 4.86E + 03 4.86E + 03 4.86E + 03 4.86E + 03 4.86E + 03 4.86E + 03 0-14 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 j ~"
5 ~54~~~~~bE+~b~4E+ 06 I E +06~bE+5 1.U U~6~b.E+M~iI72El5" l FE-65 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 2.01E+ 06 0.00E +00 0.00E + 00 1.51 E + 06 2.44E+06
. .-59 CO-58 0.00E + 00 2.91E +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 !
NI-63 4.19E + 09 2.59E + 08 1.48E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.29E + 07 i ZN-65 6.67E +08 2.29E + 09 1.05E + 09 0.00E+ 00 1.11 E + 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 7.59E + 08 0.00E + 00 0.00E + 00 0.00E + 00 5.44E + 08 1 1 SR-90 2.55E+ 11 0.00E + 00 6.50E+10 0.00E+ 00 0.00E + 00 0.00E+ 00 3.19E + 09 j Y-91 8.80E + 03 0.00E +00 2.34E + 02 0.00E + 00 0.00E+00 0.00E +00 6.31E + 05 ZR-95 8.17E +02 1.99E +02 1.41E +02 0.00E + 00 2.15E+ 02 0.00E+ 00 9.91 E + 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.... + 0._...7 .1.24E . 0.00E + 08+' 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 l131 3.27E +09 3.85E + 09 1.69E + 09 1.27E + 12 4.50E + 09 0.00E +00 1.37E + 08 l133 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-130 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 181E+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 144 2.79E + 05 1.14E + 05 1.56E + 04 0.00E + 00 4.62E + 04 0.00E + 00 1.60E + 07 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 + 04 146.0 n2=
04 17 98 11 13 03 Number . gg y TMl Radiological Co'ntrols Departmental Procedure 6610.PLN-4200.01 Title FWvWon No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.5.2 Pathway Dose Factors, RI AGE GROUP: CHILD PATHWAY: GRASS GOAT. MILK ORGAN DOSE FACTORS; m' . mrem / year per pCl/sec NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - BONE UVER.B O T D Y THYROID KlDNEY LUNG Gl-LU 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 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 _......._....._........--_......_..._..............__....._6.48E+05 CR51 0.00E+00 0.00E + 00 1.22E + 04 6.78E + 03 1.85E+ 03 1.24E + 04 _._ .... i
\
MN-54 0.00E+ 00 2.62E + 06 6.71E +05 0.00E + 00 7.06E + 05 0.00E + 00 2.11 E + 06 ) FE 55 1.45E + 06 7.71E+ 05 2.39E + 05 0.00E +00 0.00E+ 00 4.36E + 05 1.43E + 05 i FE59 1.56E + 06 2.53E + 06 1.26E + 06 0.00E + 00 0.00E + 00 7.34E+ 05 2.64E +06 l
. .... ......_.. .... ..._...._... _ .. ...._.......- _._._.... .... .... I CO58 0.00E + 00 1.4EE + 06 4.46E + 06 0.00E + 00 0.00E + 00 0.00E + 00 8.49E + 06 C040 0.00E + 00 5.18E + 06 1.53E + 07 0.00E + 00 0.00E + 00 0.00E + 00 2.87E + 07 NI-63 3.56E + 09 1.91E + 08 1.21 E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.28E+ 07 ZN45 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 0.97E + 08 0.00E + 00 0.00E + 00 0.00E + 00 5.39E + 08 SR-90 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 t00 6.24E + 05 2R-95 4.60E + 02 1.01 E + 02 9.00E + 01 0.00E + 00 1.45E +02 0.00E + 00 1.05E+ 05 NB-95 3.82E + 04 1.49E + 04 1.06E + 04 0.00E + 01 1.40E + 04 0.00E + 00 2.75E + 07 RU 103 5.14E + 02 0.00E+ 00 1.96E +02 0.00E + 00 1.29E +03 0.00E + 00 1.33E + 04 RU 106 1.11E + 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 1.69E + 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 '
T 2.50E + 07 6.72E +
...E.127M ......_......... .......06 2.9.6E+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 l131 1.57E + 09 1.57E + 09 8.95E + 08 5.21E + 11 2.58E + 09 0.00E + 00 1.40E + 08 l 13.3 .....
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 + 08 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 1.41E + 07 1.24E + 04 8.23E + 05 0.00E + 00 4.02E + 03 7.37E+ 03 7.15E + 06 CE 141 2.63E + 03 1.31E +03 1.95E+ 02 0.00E+ 00 5.74E + 02 0.00E + 00 1.63E + 06 CE-144 1.95E + 05 6.11E + 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 ND 147 5.34E + 01 4.33E + 01 3.35E + 00 0.00E + 00 2.37E + 01 0.00E + 00 6.85E + 04 147.0 mu
1 04-17-98 11:13:03 1 Number gggy TMi Radiolo91cal Controls Departmental Procedure 6610-PLN-4200.01 i l
% w.on no.
Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.5.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK ORGAN DOSE FACTORS: 8m mrom/ year per pCl/sec NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = - - --------- BONE UVER T. BODY THYROID KIDNEY LUNG Gl-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 2.61 E + 05 1.78E+05 ' FE-59 . 6.74E +05 1.57E + 06 6.08E + 050.00E + 00 0.00E +00 4.96E + 05 3.72E + 06 CO-68 0.00E + 00 9.53E+ 05 2.20E+ 06 0.00E + 00 0.00E + 00 0.00E+ 00 1.31E+ 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 4.81 E + 07 0.00E + 00 0.00E+00 0.00E + 00 1.60E + 07 ZN-65 2.53E + 08 8.78E + 08 4.10E + 08 0.00E +00 5.62E+ 08 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 1.61E + 08 0.00E + 00 0.00E + 00 0.00E + 00 6.69E + 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 7.7BE+ 05 ' ZR 1.98E + 02 6.25E + 01 4.30E + 01 0.00E + 00 9.18E + 01 0.00E +...00 1.44E + 05 __..-95...... .__...... ....___ . ..________......__.. ..____.. .......__. ND-95 1.69E + 04 9.38E + 03 5.16E +03 0.00E + 00 9.09E+ 03 0.00E + 00 4.01E +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 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 TE 1.01E + 07 3.59E +06 1.2
..127M . . . . . _ _ . . . . _ _ . - ... ____0.E .... + 06 2.41 ........ E + 06_4.11 E + 07 ..._.. 0.00E + 00 2.52E ......-- ====.__ + 07 TE-129M 1.32E + 07 4.90E + 06 2.09E +06 4.26E + 06 5.53E +07 0.00E+00 4.96E + 07 l131 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 + 0 . . - . _ ..._._.. - ._. . _ ...__.._ ..__....9 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 8.41E + 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 CS-137 4.02E + 10 5.34E + 10 1.86E + 10 0.00E +00 1.8V + 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 9.01E + 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 ME+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 + 04 148.0 m=
~04 17 98 11:13:03 Number ggEI TMI Radiological Controls Departmental Procedure 6610.PLN-4200.01 me Rewon No. j Offsite Dose Calculation Manual (ODCM) 12 I 1 i TABLE 5.6.4 i Pathway Dpse Factors, RI AGE GROUP: ADULT
...._ ___. . .. . . . ... ...__.. .. ...._PATHWAY:
__._.. GOAT GRASS _M..I _LK. ___ ..___..... { i ORGAN DOSE FACTORS; m8. mrom/ year per pCl NUCUDE --------------------------------------------------/sec - - - - - - - - - - - - - - - - - j BONE UVER T KIDNEY L GI i
.. ._ _ ... .. .___... ...T. BODY. .... ...H.YROID ..... .. .. . _ _ ......U.NG_..__ .._ _.....-LLI i H-3 0.00E + 00 1.56E + 03 1.56E+ 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 2.05E + 03 7. ___ .... 0.00E + 00 0.0_0E + 00........ ___ .. . ..___ _ _.... 3 43 E_.+ ..0356E + 02.__4.55E + 03 _ ....... 8.63E + 05 _ _........ { l MN 54 0.00E + 00 1.01E + 06 1.93E + 05 0.00E + 00 3.01E + 05 0.00E + 00 3.10E + 06 ; FE-55 3.27E +05 2.26E + 05 5.26E+04 0.00E + 00 0.00E +00 1.26E + 05 1.30E + 05 i FE-59 3.87E + 05 9.09E + 05 3.48E + 05 0.00E + 00 0.00E + 00 2.54E + 05 3.03E + 06 j 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
)
NI63
. ....... 8.08E ___..... + 08 5.60E+07 ....__ . 2.71 E +. 07 0.00E +. 00
___.... 0.00E + 00 0.00E + 00 1.17E
+ 07 .__ ..__ l ZN-65 1.65E + 08 5.24E + 08 2.37E + 08 0.00E +00 3.51E + 08 0.00E + 00 3.30E +08 3 RB-86 0.00E+00 3.12E + 08 1.45E + 08 0.00E + 00 0.00E + 00 0.00E + 00 6.14E + 07 SR-89 3.05E + 09 0.00E+ 00 8.76E + 07 0.00E + 00 0.00E + 00 0.00E + 00 4.89E + 08 SR-90 9.84E + 10 0.00E+ 00 2.41 E + 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 l ZR-95 1.13E + 02 3.63E + 01 2.46E + 01 0.00E + 00 5.70E + 01 0.00E + 00 1.15E + 05 ;
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 l 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 AG-110M 6.99E + 06 6.47E + 06 3.84E + 06 0.00E+ 00 1.27E +07 0.00E + 00 2.64E + 09 TE-125M 1.96E + 06 7.09E + 05 2.62E+ 05 5.89E+05 7.96E + 06 0.00E+00 7.81E + 06 !
TE 6.70E + 05 1.41E + 06 2.23E + 07 0.00E + 00 1.84E + 07 _ .127M.__.5.50E+06___..... 1.97E + 06__...... TE-129M 7.23E + 06 2.70E + 06 1.14E + 06 2.48E + 06 3.02E+07 0.00E+00 3.64E + 07 i 1131 3.56E+08 5.09E + 08 2.92E +08 1.67E + 11 8.73E+ 08 0.00E + 00 1.34E + 08 l133 4.65E + 06 8.10E + 06 2.47E + 06 1.
... ... __...__. ... ... ..19E+09 1.41 E + 07 0.00E + 00 7.28E + 06 CS 134 1.70E + 10 4.04E + 10 3.30E +10 0.00E + 00 1.31E + 10 4.34E + 09 7.07E + 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 1.51 E + 06 CE 144 4.30E + 04 1.80E + 04 2.31E + 03 0.00E + 00 .... .... .._ .. .... ... .. . ..._...._ _.. .1.0 7E + 04 0.00E__==.... .. ... + 00....._-...
1.45E + 07 PR-143 1.90E + 01 7.60E + 00 9.40e41 0.00E + 00 4.39E + 00 0.00E + 00 8.30E + 04 ND-147 1.13E + 01 1.31 E + 01 7.82e 01 0.00E + 00 7.65E + 00 0.00E + 00 6.28E + 04 I i 149.0 me.
l 04-17 98 11:13:03 l
- )
GMClO8r m nam Ow Control. I Departmental Procedure 6610-PLN-4200.01 ;
m. Mon No.
Offsite Dose Calculation Manual (ODCM) 12 i
)
TABLE 5.8.1 Pathway Dose Factors, RI i i AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT j 2 ORGAN DOSE FACTORS; m - mrem / year per pCl/sec NUCUDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H4 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 l C-14 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 j CR-51 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 j MN-54 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 j FE-55 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 j FE..-59 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 0.00E + 00 0.00E + 00 a C048 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 4 00 0.00E +00 0.00E + 00 0.00E + 00 ! NI63 0.00E + 00 0.00E + 00 0.00E +00 0.00E +00 0.00E +00 0.00E + 00 0.00E +00 , 6 ZN.66 0.00E + 00 0.00E + 00 0.00E +00 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E +00 i 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 l 1 SR-90 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 i Y-91 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 0.00E + 00 0.00E + 00 0.00E + 00 i ZR 0.00E + 00 0.00E + 00 0.00E +00 0.00E+00 0.00 !
..-95 _ _ _ __ _ _ _ = . ... .... ..... ....... .. ........ ... ..E.+. 00 0.00E . .......+....
00.... 0.00E + 00 > 4 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+bb 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 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 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 j CS-137 0.00E + 00' O.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
~
3R-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
. . . - . . . . . . . - - - - - - - .____ ... ........ ......... ... ... ... =
150.0 me.
0417-98 99$3:03 Number
$UCIBar TMI Radiological Controls o,ponment,, proc.go,, ee3o.ptN.4200.01 Dh Revision No.
Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.6.2 Pathway Dose Factors, RI AGE GROUP: CHILD PATHWAY: GRASS COW-MEAT NUCUDE
------------ ORGAN DOSE FACTORS; m' . mram/ year per pCl/sec BONE UVER T. BODY THYROID KIDNEY LUNG GI-LLI H4 0.00E + 00 2.34E + 02 2.34E + 02 2.34E + 02 2.34E + 02 2.34E + 02 2.34E + 02 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 4.66E + 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 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 CO-58 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 + 00 0.00E + 00 0.00E + 00 0.00E + 00 3.84E + 08 N16 2.91 E + 10 1.56 -__. 3. ...__.___ ..E + 00 _. 9. .___ 91......
E + 08_0.00E + 00 0.00E + 00 0.00E + ._..__.._
... .____........_...__..__ 00 1.05E + 08 ZN.65 3.76E + 08 1.00E + 09 6.22E + 08 0.00E + 00 6.31 E + 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 3.71 E + 07 SR-89 4.82E + 08 0.00E +00 1.38E + 07 0.00E+00 0.00E +00 0.00E + 00 1.87E+ 07 SR-90 1.04E + 10 0.00E + 00 2.64E + 09 0.00E + 00 0.00E + 00 0.00E + 00 1.40E + 08 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 6.11 E + 08 NB-95 3.10E + 06 1.21E + 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 4.01 E + 09 RU-106 4.44E + 09 0.00E +
....__...______ ... .......00. .......__
5.54E + 08 0.00E + 00 6.00E+ 09 0.00E + 00 6.91E + 10 AG 110M 8.39E+ 06 5.67E+06 4.53E+ 06 0.00E+ 00 1.06E+ 07 0.00E+ 00 6.74E +08 TE 125M 5.69E + 08 1.54E + 08 ' 7.59E + 07 1.60E+ 08 0.00E+00 0.00E+ 00 5.49E + 08 TE-127M 1.78E + 09 4.78E + 08 2.11E+ 08 4.2SE + 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 l131 1.66E + 07 1.67E + 07 9.48E + 06 5.52E+ 09 2.74E+ 07 0.00E + 00 1.48E+ 06 l133 5.72e 01
..... .._ _. . ......_ _ _ _ _ . 7.08e ___01 2.68e41 1.3
_ .__ _..... .__.1..... 1.18 E + 02 .....E.+._00 _ 0.00
.....E + 2.85e 01 00........._
CS-134 9.23E+ 08 1.51E + 09 3.19E +08 0.00E+ 00 4.69E + 08 1.68E+ 08 8.16E+06 CS-136 1.63E + 07 4.48E + 07 2.90E + 07 0.00E+ 00 2.39E+ 07 3.56E + 06 1.57E +06
.CS. .137 ..==
1.33E + 09 1.28E +09 1.89E + 08 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 2.31E + 04 2.24E + 07 CE 141 2.22E + 04 1.11 E + 04 1.65E + 03 0.00E +00 4.86E + 03 0.00E+00 1.38E + 07 CE 2.32E + 06 7.26E + 05 1.24 0.00E + 00 4.02E + 05 0.00E+ 00
....-144 . ....._____..__..... .___E+05___ . .._ _ _ _.__ _ _ _ ...._ __._ _ _ _. .__. ......
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 + 07 151.0 mm
04 17-98 11:13:03 Numbw Nuclear * "ad* o ""* Departmental Procedure 6610-PLN-4200.01 Title Rev6eion No. Offsite Dose Calculation Manual (ODCM) 12
' TABLE 5.6.3 Pathway Dose Factors, R1 AGE GROUP: TEEN PATHWAY: GRASS COW MEAT 2
NUCLIDE
----------- ORGAN DOSE FACTORS; m mrom/ year per pCl/sec BONE UVER T. BODY THYROID KlDNEY LUNG GI-til H-3 0.00E + 00 1.93E + 02 1.93E+ 02 1.93E + 02 1.93E+02 1.93E+ 02 1.93E +02 C-14 2.04E + 08 4.08E + 07 4.08E + 07 4.08E + 07 4.08E + 07 4.08E + 07 4.08E + 07 '
CR-51 0.00E + 00 0.00E + 00 5.63E+ 03 3.13E +03 1.23E + 03 8.03E + 03 9.46E + 05 MN-54 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-59 2.12E + 08 4.95E + 08 - 1.91 E + 08 0.00E + 00 0.00E + 00 1.56E + 08 1.17E + 09 CO-58 0.00E + 00 1.40E + 07 3.24E + 07 0.00E +00 0.00E+00 . 0.00E+00 1.94E +08 CO-80 0.00E + 00 5.83E + 07 1.31E+ 08 0.00E + 00 0.00E + 00 0.00E+ 00 7.60E+08 N143 1.52E + 10 1.07E + 09 5.15E +08 0.00E + 00 0.00E + 00 0.00E + 00 1.71 E+ 08 ZN-65 2.50E +06 8.68E + 08 4.05E+ 08 0.00E+00 5.56E +06 0.00E +00 3.68E +08 RB-86 0.00E +00 4.06E +08 1.91E +08 0.00E+00 0.00E +00 0.00E+00' 6.00E+07 SR-89 2.55E + 08 0.00E + 00 7.29E + 06 0.00E + 00 0.00E + 00 0.00E +00 3.03E + 07 SR-90 8.04E + 09 0.00E + 00 1.PE +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 3.2SE + 05 0.00E + 00 6.95E + 05 0.00E + 00 1.09E + 09 NS-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 3.66E + 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 5.06E429 4.78E + 06 2.91 E + 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 12eM 9.49E + 0S 3.52E + 08 1.50E + 08 3.06E+ 08 3.97E+ 09 0.00E + 00 3.56E + 09 l131 8.93E + 06 1.25E + 07 6.72E + 06 3.65E+09 2.15E +07 0.00E+ 00 2.47E + 06 l-133 3.088-01 5.22e 01 1.59e41 7.29E + 01 9.16e-01 0.00E + 00 3.95e-01 CS 134 5.23E+08 1.23E + 09 5.71 E + 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 3.18E406 2.99E + 06 CS-137 7.24E + 08 9.63E+ 08 3.35E + 08 0 *0E + 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 3.71 E + 03 0.00E + 00 2.2SE + 07
.CE-144 1.23E + 06 5.08E + 05 6.60E + 04 0.00E+ 00 3.03E + 05 0.00E + 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 + 07 152.0 nm.
04 17 98 11:13:03 Number ggUI TM) Radiological Controls Departrnental Procedure 6810-PLN-4200.01
m. nemon No.
Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.6.4 Pathway Dose Factors, RI AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT - NUCUDE - - - - - ~ ~ ~ - - ~ ~ - - - - - - ~ ~ - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- BONE UVER T. BODY THYROID KIDNEY LUNG GI-LU H3 0.00E + 00 3.24E + 02 3.24E + 02 3.24E4 02 3.24E + 02 3.24E + 02 3.24E + 02 0-14 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 4.21 E + 03 1.55E + 03 9.35E + 03 1.77E + 06 MN-64 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 2.6 6.25E + 08 2.39E +08 0.00E + 00 1.75E + 0
.___-59
_... _...6E+08 .... . . ... .........__......__. 0.00E + 00. ______....8
.. 2.08E + 09 CO-68 0.00E + 00 1.82E + 07 4.09E + 07 0.00E + 00 0.00E + 00 0.00E +00 3.70E+ 08 CO60 0.00E + 00 7.52E + 07 1.66E +08 0.00E + 00 0.00E+ 00 0.00E + 00 1.41E+ 09 Ni-63 1.89E +10 1.31E + 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 RB-86 0.00E + 00 4.87E +08 2.27E+ 08 0.00E+ 00 0.00E +00 0.00E+ 00 9.59E + 07 SR-89 3.02E+08 0.00E+ 00 8.66E + 06 0.00E+ 00 0.00E + 00 0.00E +00 4.84E + 07 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-95 1.87E + 06 6.01E+ 05 4.07E+05 0.00E + 00 9.43E + 05 0.00E + 00 1.90E + 09 NS-05 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 5.41E + 09 0.00E + 00 1.81 E + 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 + 00 0.00E + 00 1.43E + 09 TE-127M 1.12E + 09 3.99E + 08 1.36E + 08 2.85E + 08 4.53E + 09 0.00E + 00 3.74E + 09 TE 129M 1.13E + 09 4.23E + 08 1.79E + 08 3.89E + 08 4.73E + 09 0.00E + 00 5.71 E + 09 l131 1.08E + 07 1.54E + 07 8.82E + 06 5.04E + 09 2.64E + 07 0.00E + 00 4.06E+ 06 l-133 3.68e-01 6.41e 01 1.95e-01 9.42E + 01 1.12E + 00 0.00E + 00 5.76e-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 1.21E4 07 4.78E + 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 1.41E + 04 9.51E + 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 4.93E + 08 PR 143 2.09E + 04 8.40E + 03 1.04E+ 03 0.00E + 00 4.85E + 03 0.00E+ 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 + 07 153.0 me.
04 17 98 11:13:03 Number Nuclea* = a***' c ** Departmental Procedure 6610-PLN-4200.01 me n.vimon No. Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.7.1 Pathway Dose Factors, RI AGE GROUP: INFANT PATHWAY: VEGETATION NUCUDE ----------------------------------------- - - - - - - - - - - - - - - - - BONE LIVER TH H4
.... . .. _ __ _ _. ._ _ _ _ .. .. ... ...T. B OD Y...... ....____.................-LLI . .YR.OID KIDNEY LUNG GI 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +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 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 MN-64 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 l CO-60 0.00E +00 0.00E + 00 0.00E+00 0.00E + 00 0.00E + 00 0.00E+00 0.00E+00 NI63 ......__. . ._ _ 0.00E . . .. . +. ._
00 0.00E + 00 0.00E + 00 _ _ . . . . .. . ..._.-_ .0.00...__... E + 00 0.00E +00 0.00E___
.... ..___.... + 00 0.00E + 00 ZN-66 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 l
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 l SR-90 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 l I 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 TE-129M 0.00E + 00 0.00E+ 00 0.00E+00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 1131 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 1133 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 0.00E700 0dd+~0b~bIdd+bb~b.~dd+~0b~bIddIOb~ 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 0.00d+ 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+0b 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 =... .... . . .... ._- .........-
154.0 me
04 17 98 11:13.03 Number UIEI TMI Radkdog6 cal Oontrols Departmental Procedure 6610-PLN-4200.01 f Titfe Revision No. l Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.7.2 Pathway Dose Factors, RI AGE PATHWAY: VEGETATION _ __ __ __ ......._...G R..____ OUP: CHILD ORGAN DOSE FACTORS; rri-
--------------------------------------- mrem per pCl/sec / year NUCL1DE - - - - - - - - - - - - - - - - - - - - - - - - - - -
B LIVER H4
............____.........._........_........__-tu .. .....O N E T. BODY THYROID KIDNEY LUNG Gt 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 1.78E+08 CR 51 6.4 ....- - 0.00E + 00...... .__... +1.17E
_0. 00E ... +...05 9E 00 +.. ... 1.77 04 .....E +
....04 ._
1.18E.... +____05 6.20E
.__. + 06 MN-54 0.00E + 00 6.65E+08 1.77E + 08 0.00E + 00 1.86E + 08 0.00E + 00 5.58E + 08 FE-55 8.01E + 08 4.25E + 08 1.32E+ 08 0.00E+ 00 0.00E+00 2.40E+ 08 7.87E + 07 FE -..-59 CO-58 .__........._........_..._______........._.....0 3.98E + 08 6.44E + 08 3.21 E + 08 0.00E + 00 0.00E + 0 1.87E + 08 6.71E+ 08 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 + 08 1.12E+ 09 0.00E+ 00 0.00E + 00 0.00E+ 00 2.10E+ 09 NI-63 3.95E + 10 2.11 E + 09 1.34E + 09 0.00E + 00 0.00E+ 00 0.00E + 00 1.42E+ 08 ZN 65 8.12E + 08 2.16E + 09 1.35E + 09 0.00E + 00 1.36E + 09 0.00E +00 3.80E + 08 RB-86 0.00E + 00 l.51E + 08 2.77E+ 08 0.00E + 00 0.00E +00 0.00E C 2.90E + 07 SR-89 3.60E + 10 J.00E + 00 1.03E + 09 0.00E + 00 0.00E + 00 0.00E+ 00 1/d + 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 4.99E + 05 0.00E + 00 0.00E + 00 0.00E + 00 2.49E +09 ZR-95 3.86E+n s 8.48E +05 7.55E + 05 0.00E + 00 1.21 E + 06 0.00E + 00 8.85E + 08 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 1.53h + 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 1.01E + 09 0.00E + 00 1.16E + 10 AG-110M 3.21 E + 07 2.17E + 07 1.73E + 07 0.00E + 00 4.04E + 07 0.00E+00 2.58E + 09 TE-125M 3.51E+ 08 . 9.50E+07 4.67E + 07 9.84E + 07 0.00E +00 0.00E +00 3.38E + 08 TE-127M 1
_. 32E + 09....
.. ... 3.56E . + 08 1.57E+ ......__.08 3.16E+ 08 .....___ 3.77E + 09 0.00E ..__... - __...... +00...1.07E+ ......
09 TE-129M 8.40E+ 08 2.35E+ 08 1.30E + 08 2.71E +08 2.47E + 09 0.00E+ 00 1.02E + 09 l131 1.43E + 08 1.44E + 08 8.18E + 07 4.76E + 10 2.36E +08 0.00E+00 1.28E + 07 l133 3.53E
.. .. ... ....__... ....+ __..
06 4.37E + 06 1.65E
...__.... _ _ _2E + 06 +8.108 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+0? 1.42E + 08 CS 136 8.28E + 07 2.28E +08 1.47E + 08 0.00E + 00 1.21E+ 08 1.81E+ 07 8.00E + 06 CS 2.39E + 1 3.3 .-137 . ...__.0 ._2.29E + 10_..._8E _ _. ...+.___
090.00E + 00........7.46
. ..E+09... 2.68E + 09__...__
1.4
..3E+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 8.57E + 05 3.28E + 05 4.86E + 04 0.00E + 00 1.44E + 05 0.00E + 00 4.09E +08 CE-144 1.27E + 08 3.99E + 07 6.79E + 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-147 7.15E + 04 5.79E + 04 4.49E + 03 0.00E + 00 3.18E + 04 0.00E+00 9.18E + 07 155.0 me.
04 17 98 11:13:03 Number l l Nuclear- ' "*d'**=' contr* Departmental Procedure 6610-PLN-4200.01 1 rm. n m.on No. l Offsite Dose Calculation Manual (ODCM) 12 TABLE 5.7.3 Pathway Dose Factors, RI AGE GROUP: TEEN PATHWAY: VEGETATION 8 NUCLIDE
------------- ORGAN DOSE FACTORS; m - mrem / year per pCl/sec H-3 ...._.......--........._.......................-...---.-LLI BONE LIVER T. BODY THYROtD 0.00E + 00 2.59E + 03 2.59E +03 2.59E +03 K]DNEY LUNG GI 2.59E + 03 2.59E + 03 2.59E + 03 C 14 3.69E + 08 7.38E+ 07 7.38E+07 7.38E+07 7.38E+ 07 7.38E+ 07 7.38E+07 , C3 61 ,,
0.00E + 00 0.00E + 00 6.16E + 04 3.42E + 04 1.35E + 04 8.79E + 04 1.03E + 07 MN-54 0.00E + 00 4.54E + 08 9.01 E + 07 0.00E + 00 1.36E +08 0.00E + 00 9.32E + 08 l 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 9.91 E + 08 CO-58 0.00E + 00 4.36E + 07 1.01 E + 08 0.00E + 00 0.00E + 00 0.00E + 00 6.01 E + 08 C040 0.00E + 00 2.49E + 08 5.60E + 08 0.00E+ 00 0.00E + 00 0.00E + 00 3.24E + 09 N143 1.61E + 10 1.13E + 09 5.45E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.81 E + 08 ZN45 4.24E + 08 1.47E + 09 6.86E + 08 0.00E + 00 9.42E + 08 0.00E + 00 8.23E + 08 i RB-86 0.00E + 00 2.73E + 08 1.28E + 08 0.00E +00 0.00E + 00 0.00E +00 4.04E + 07 l 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 7.51 E + 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 ZR-95 1.72E+ 06 5.43E + 05 3.73E +05 0.00E+ 00 7.98E+ 06 0.00E +00 1.25E + 09 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 1.98E + 07 4.14E+07 0.00E+00 0.00E + 00 4.37E + 08 TE-127M 5.52E + 08 1.96E + 08 6.56E + 07 1.31 E+ 08 2.24E + 09 .0.00E + 00 1.37E + 09 , 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 7.69E + 07 1.08E + 08 5.78E + 07 3.14E + 10 1.85E + 08 0.00E + 00 2.13E + 07 l133 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 5.31 E + 09 2.03E + 09 2.08E + 08 CS-138 4.39E + 07 1.73E + 08 1.16E + 08 0.00E + 00 9.41 E + 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 1.71 E + 05 8.97E + 06 0.00E + 00 5.78E + 04 1.15E + 05 2.15E + 08 CE-141 2.83E + 05 1.89E+ 05 2.17E + 04 0.00E + 00 8.90E+ 04 0.00E +00 5.41E + 08
. CE 144 5.28E + 07 2.18E + 07 2.83E + 06 0.00E + 00 1.30E + 07 0.00E + 00. 1.33E + 10 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 + 08 156.0 me.
04 17 98 11 13 03 Numtw TMI R diologicd Controls E I Departmental Procedure 6610 PLN-4200.01 True Fievision No. OffsMe Dose Calculation Manual (ODCM) 12 TABLE 5.7.4 Pathway Dose Factors, Ri ___..... .. ... _AGE .. GROUP: ADULT __.__'......... PATHWAY: VEGETATION ORGAN DOSE FACTORS; rd . mrem / year per pCl/seo NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - BONE UVER T. BODY THYROID KIDNEY GI
.___... .. ... _ _.. ....____...... ........_ _ ... ... _ . LUNG.. ____. -LU--
H-3 0.00E+ 00 2.26E + 03 226E+03 2.26E+ 03 2.26E +03 2.26E + 03 2.26E + 03 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 8.31E + 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 + 08 3.69E + 08 0.00E + 00 0.00E + 00 0.00E + 00 3.14E + 09 NI-63 1.04E + 10 7.21E + 08 3.40E + 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 9.98E + 09 0.00E+00 2.86E +08 0.00E + 00 0.00E + 00 0.00E + 00 1.60E + 09
....-89.. . ..__.- =
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 0.00E+ 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 1.93E4 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 ..TE127M 3.49E + 08 1.25E + 08 4.26E + 07 8.93E + 07 1.42E + 09 0.00E + 00 1.17E + 09 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 1.98E + 08 0.00E + 00 3.05E + 07 l-133 2.09E + 06 3.63E +06 1.11E+ 06 5.34E + 08 6.33E + 06 0.0 - . .. ....___.....__ ..___...___.__... ...___..__.... 0 E + 00 3.26E-== + 06 - = -_..
CS 134 4.67E + 09 1.11E + 10 9.08E+ 09 0.00E+ 00 3.59E+09 1.19E + 09 1.94E + 08 CS-136 4.28E + 07 1.69E + 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 + 09 9.81 E + 08 1.68E + 08 BA-140 1.29d + 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 1.77E + 06 0.00E + 00 8.16E + 06 0.00E + 00 1.11 E + 10 PR 143 6.25E + 04 2.5' C +04 3.10E + 03 0.00E + 00 1.45E + 04 0.00E + 00 2.74E+ 08 ND-147 3.34E + 04 3.UE +04 2.31E+03 - 0.00E+00 2.25E + 04 0.00E + 00 1.85E + 08 157.0 mm
04-17-98 11:13:03 Number E Nuclear rio.
'"'De"",d W.
I roc s 6610-PLN-4200.01 aavwon No. _ Offsite Dose Calculation Manual (ODCM) 12 i 6.0 TMI 1 GASEOUS WASTE TREATMENT SYSTEM 6.1 Descriotion of the TM1-1 Gaseous Radwaste Treatment System (see Flaure 6.1) 6.1.1 Waste Gas System
a. Reactor Bulding:
- Reactor Coolant Drain Tank (RCDT) header
b. AuxXiary 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) Wasta Gas Decay Tanks (WGDT)
c. Filtration and dIution provided by the Station Ventiation System.
6.2 _ Operability - Operability of the Gaseous Waste Treatment System is defined as the abilty 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 sample 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 automatically, removing gases from the vent header system as required, to maintain the pressure in the system at a maximum of about 16.4 psia. g i 158.0 me.
04-17-98 11:13:03 kmber Nuoleer ""* .
Depanmental Procedure 6610 PLN-4200.01 T* nmien m.
ONsite Dose Calculation Manual (ODCM) 12 FIGURE s.1 , waste Gas system
-. =
gasm j iL j'IE Ri R -
. .a. i wic - ,, < , o o
u-asemas I
a ir a6 d b
)
b db
**" 8 i ,,,,,,,,, e.s man.s e.s man.s e.s. man.s I a ,
u._______s a f .aa. m
*. =': , e \ < , o 43 e. %T >
?:
Oda 01:= ol [a d' d' eaut and eastases cepelta 5, [ ensm sans e seene.seen eense.es.s W s """' ' I f k a nD '. n no n ' n]lsl(. . ==='+qf 9001 + 0 --)-= 1> l_ 4 [ 159.0 me
04 17-98 11:13:03 Number Nuclear ' Radd a**' coa'r* Departmenel Procedure 6610-PLN-4200.01 Te n.wi. ion so. Offsite Dose Calculation Manual (ODCM) 12 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 7.1 Total Dose Calculation The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivtty 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 thyrold, which shall be limited to less than or equal to 75 mrom. This control la provided in order to meet the dose limitations of 40 CFR 190. The total dose from TMl 1 and TMf 2 (uranium fuel cycle facilities within 8 klometers) is calculated by summing the calcula:ad annual doses to critical organs of a real indMdual for liquid effluent using Section 2.1 mathodology, 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. t 160.0 me.
i 04-17-96 11:13:03 Numtw Nuolear '"' "*d* ""S' Departmental Procedure 6610-PLN-4200.01 Title Revssion No. l Offsite Dose Calculation Manual (ODCM) 16 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) i 8.1 Monitorino Prooram Reauirements j 8.1.1 Controls l In accordance with the TMl-1 Tech. Specs. and TMI 2 PDMS Tech. Spoca., the radiological l environmental monitoring program shall be conducted as speelfled in Table 8.1. 1 i 8.1.2 ADolicability j l At all times. ! i 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 Commission 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 radioactivity 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 radioactke affluents so that the potential annual dose
to a member of the public is less than the calendar year limits of ODCM Part I Controls 2.2.1.2,2.2.2.2 and 2.2.2.3 and ODCM Part 11 Controls 2.2.1.2,2.2.2.2 and 2.2.2.3.
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: concentration (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 limits of ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part il, Controls 2.2.1.2,2.2.2.2 and 2.2.2.3. This report is not required if the measured level of radioactMty was not the result of plant effluents; however, i
in such an event, the condition shall be reported and described in the Annual Radiological knvironmental Operating Report. l I l The methodology and parameters used to estimate the potential annual dose to a member of the pubile sha!! be indicated in this report. 161.0 me. l
04 17-98 11:13:03 Numtw Nuclear- ' "*d'*a'ca' co"tr* Departmental Procedure 6610-PLN-4200.01 noe n.vt.w no. l Offsite Dose Calculation Manual (ODCM) 12
c. Witn milk or fresh leafy vegetation samples unavah ble from one or more of the sample locations required by Table 8.1, identify specific 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 unavailabllity of samples and justifying the selection of the new location (s) for obtaining i samples. ]
8.1.4 Bases The radiological monitoring program required by this control provides representattve measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation expoe' ires of members of the general public resulting from the station operation. This monitoring program implements Section IV B.2 of Appendix 1 to 10CFR50 and thereby supplements the radiological offluent monitoring program by verifying that the ! l measurable concentrations of radioactive materials and levels of radiation are not higher than l expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring (Revision 1, November 1979). Program changes may be initiated based on operational experience. 8.1.5 Surveillance Reouirements 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 capabilities required by Table 8.3. 162.0 mm
04-17-98 11:13:03
. 1 Number .
C __ Nuclear =Departmental
=.* Procedurt co=*
6610 PLN-4200.01 -
** n no.
Offsite Dose Calculation Manual (ODCM) 12 FIGURE s.1 , Weste Gas s'ystem paseemasse esasseneena.s senses aa. , etAWB l Rli I' 8- l I eis'es geeses- 3p 4i o <> . L ---- n i r u u l
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04 17-98 1013.03 l Number i Nuclear ' "*d'd**' co** Departmental Procedure 6610-PLN-4200.01 , T,tle .
%sion No. l Offsite Dose Calculation Manual (ODCM) 12 l
7.0 EFFLUENT TOTAL DOSE ASSESSMENT 7.1 Total Dose Calculation l The annual (calendar year) dose or dose commitment to any member of the public, due to releases l of radloactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrom. This control is provided in order to meet the dose limitations of 40 CFR 190. The total dose from TMl-1 and TMI 2 (uranium fuel cycle facilities within 8 klometers) is calculated by summing the calculated annual doses to critical organs of a real Individual for liquid effluent using l 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. 6 160.0 me, i l . . . - . . . . . . . . . .
mmm., N E TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
3. HwWon No.
Offsite Dose Calculation Manual (ODCM) 16 , 8.0 TMINS RADIOLOGICAL ENVIRONa8MTAL MONITORING PROGRAM (REMP) 8.1 Monitorina Proaram Reauirements B.1.1 Controls 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.t.2 ADDilcabNiry At all times. 8.1.3 Aglig0
a. With the radiological environmental monitoring program not being conducted as speellied in Table 8.1, prepare and submit to the Commission in the Annual Radiological Erwironmental
. 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 radioactivity 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 affluents so that the potential annual dose
to a member of the public is less than the calendar year limits of ODCM Part i Controls 2.2.1.2,2.2.2.2 and 2.2.2.3 and ODCM Part 11 Controls 2.2.1.2,2.2.2.2 and 2.2.2.3.
When more than one of the radionuclides in Table 8.2 are detected as the result of plant affluents in the sampling medium, this report shall be submitted N: concentration (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 limits of ODCM Part i Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part II, Controls 2.2.1.2,2.2.2.2 and 2.2.2.3. This report is not required N the treasured level of radioactMty was not the result of plant effluents however, in auch an event, the condition shall be reported and described in the Annual Radiological knvironmental Operating Report.
I The me.hodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report. 161.0 me,
04-17-98 11:13:03 Number i Radidogical Contrds GUClear- Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 12
' c. With mik or fresh leafy vegetation samples unavalable from one or more of the sample locations required by Table 8.1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program gh/en 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 Efnuent 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.
J.1.4 Bases The radidogical monitoring program required by this contrd 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 operation. This monitoring program implements Section IV B.2 of Appendbc I to 10CFR50 and thereby supplements the radiological ofRuont monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the bals of the effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring (Revision 1 November 1979) Program changes may be initiated based on operational experience. 8.1.5 Surveillance Rsouirements 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 capabilities required by Table 8.3. 4 162.0 ma l l
04-17-98 11:13:03 Numbw NEIEI TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tree RMaion No. Offsite Dose Calculation Manual (ODCM) 12
' 8.2 land Use Census 8.2.1 Contrds in accordance with the TMl-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., a Land U,se Census shall be conducted and shall identify within a distance of 8 km (5 mRes) the location in each of the 16 meteordogical sectors of the nearest milk an!rnal, the nearest residence, and toe nearest garden * '
of greater than 50 m' (500 ft') producing broad leaf vegetation. 8.2.2 ADDlicablity At all times. 8.2.3 Action
a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in ODCM Part i Surveillance 3.2.2.3.1, pursuant to ODCM, Part IV, Section 2.0, identify the new location (s) in the next Annual Radioactive Effluent Release Report.

b. With a Land Use Census identifying a location (s) that yleids 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 contrd station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to TMl-1 Tech. Spec. 6.14 arxf TMI-2 PDMS Tech. Spec. 6.12, submit in the next hulual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODOM reflecting the new location (s) with information supporting the change in sampling locations. 8.2.4 Base 9 This Contrd is provided to ensure that changes in the use of unrrstricted 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 consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix 1 to 10 CFR 50. Restricting the census to gardens of greater than 500 square feet (50 m') provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegstables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., almiar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter. 3 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 samp!!ng in Table 8.1 shall be followed, including analysis of control samples. ;# 163.0 mw
04-17-98 11:13:03
. mmb.c Nuclear " " d'*a'oa' coa'r*
Departmental Procedure 6610-PLN-4200.01 Tide Reven No. Offsite Dose Calculation Manual (ODCM) 12 8.2.5 Surveillance Reautrements
. The Land Use Census shall be conducted during the Growing season at least once per 12 months, using that information that will provide the best results, such as by a door-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. l 1 164.0 222h
04-17-98 11:13.03 Number i NUg TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
)
I
. Trtle Revtalon No.
Offsite Dose Calculation Manual (ODCM) 12 8.3 Interlaboratory Comparison Proaram 8.3.1 Controls l In accordance with the TMI 1 Tech. Specs. and TMI-2 PDMS Tech. Specs., analyses shall be performed on radioactive materials supplied as part of an Interiaboratory Comparison Program which has been approved by the Commission (NRC). Only those samples and analyses which are, required by Table 8.1 shall be performed. 8.3.2 Apolicabbtv l At all times. l 8.3.3 Action With analysis 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 The requirement for participation in an approved interlaboratory Comparison Program is provided to ensure that independent checks on precision and accuracy of the m ms'urements of radioactive material in environmental sample matrices are performed 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 Appendix ! to 10 CFR 50. 8.3.5 Surveillance Reautrements A summary of the Interlaboratory Comparison Program results shall be included in the Annual Radiological Environmental Operating Report. J i l 165.0 me. E
04-17-98 11:13:03 Numbw Nuclear ' aa*'oa'ca' contr* Departmental Procedure 6610-PLN-4200.01 Tme FWolon No. Offsite Dose Calculation Manual (ODCM) 12 l TABLE 8.1 Sample Collection and Analysis Requirements 1 Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations
Collection Frequency

of Analysish l
1. Airbome Radiolodine and Samples from 5 locations Continuous sampler Radiolodine Canister:
Particulates from Table 8.4.~ operation with sample Analyze weeldy for 1131. t collection weeldy, or more Particulate Filter: frequently if required by dust Analyze for gross beta loading. radioactMty following filter change'. Perform gamma isotopic analysis
on composite (by location) sample quarterly.
l
2. Direct Samples from 40 Sample Quartsrty 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). 166.0 me.
04-17-98 11:13 03 Number NUWEIM TMI Radiological Control) Departmental Procedure 6610-PLN-4200.01 Title RrAskm No. Offsite Dose Calculation Manual (ODCM) 16 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 Frequency' of Analysis'
3. Waterbome -

a. Surface' Samples from 2 locations Composite
sample over 1 Perform gamma isotopic from Table 8.6. montNy period. analysis' montNy.
Composite for tritium e 1 sample from analysis quarterly, downstream (indicator) location
1 sample from upstream (contrcl) location (or location not influenced by the station discharge)
b. Drinking Samples from 2 locations Composite' sample over 1 Perform gross beta and from Table 8.6. montNy period. gamma isotopic analysis' montNy. 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 ana'ysis discharge. quarterly.
1 sample from a control location.
c. Sediment from Samples from 2 locations Shoreline (1 Control and 1 Indicator) Sample twice per year Perform gamma Isotopic from Table 8.7. (Spring and Fall) analysis' on each sample.
i 167.0 m.
04-17-98 11:13:03 l Number Nuclear ' "*d' ' **m a'a* Departmental Procedure 6610-PLN-4200.01 Th Revision No. Offsite Dose Calculation Manual (ODCM) 16 TABLE s.1 (Cont'd) Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling at.d Type and Frequency and/or Sample Sample Locations
Collection Frequenc/ of Analysis'
4. Ingestion

a. Milk Samples from 4 locations Sample semimonthly when Perform gamma isotopic from Table 8.8. animals are on pasture; analysis' and 1-131 l monthly at other times. analysis on each sample.
Composite for Sr-90 analysis quarterly.
b. Fish Samples from 2 locations Sample twice per year Perform gamma isotopic' from Table 8.9. (Spring and Fall). and Sr 00 analysis on edible portions.
e 1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators in the vicinity of the station discharge. e 1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators from an area not influenced by the station discharas. 168.0 mm
04-17-98 11:13:03 Number NumE"EI TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 re. Mon No. Offsite Dose Calculation Manual (ODCM) 16 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
Colle:: tion Frequency

of Analysis'
c. Food Samples from 2 locations Sample at time of harvest. Perform gamma isotopic',
Pr'oducts from Table 8.10 (when 1131, and Sr-90 analysis l avalable) on edible portions. i
1 sample of green leafy vegetables or leafy vegetation at a location in the-mmediate vicinity of ti,; :tation. (indicator) e 1 sample of same species or group from a location not influenood by the station discharos.
169.0 me
04-17-98 11:13:03 Number Nuclear ' "*di*S'ca' coatr* Departmental Procedure 6610-F d-4200.01
m. w n No.
Offsite Dose Calculation Manual (ODCM) 12 TABLE s.1 (Cont'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 conditions, seasonal unavalabilty, malfunction of automatic sampling equipment and other legitimate reasons. All deviations from the sapling schedule shall be explained in the Annual Radiological Environmental Operating Report.
b. Frequency notation; weekly (7 days), semimonthly (15 days), monthly (31 days), ami quarterly (92 days).
All surveillance requirements shall be performed within the specified time Interval with a maximum allowable extension not to exceed 25% of the survellance 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 lon chamber for measuring and recording dose rate continuously, may be used in place of, or in addition to, Integrating 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 dos! meters. Film badges shall not be used as doelmeters for measuring direct radiation.
d. Airbome particulate sample filters shall be analyzed for gross beta radioactMty 24 hours 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 shall be performed on the Individual sample (s).
e. Gamma isotopic analysis means the identification and quantification of gamma-er@rg radionuclides that may be attributable to the effluents from the facility.

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 allquots shall be collected 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.
i I 170.0 rua
04-17-98 11:13:03 Number NUgEI TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
7. n vien No.
Offsite Dose Calculation Manual (ODCM) .12 TABLE 8.2 Reponing Levels for Radioactivity Concentrations in Environmental Samples Airbome Particulate Water or gas Fish Mik Food Products Analysis (pCl/L) (pCl/m') (pCi/kg, wet) (pCl/L) (pCl/kg, wet) H-3 20,000" Mn44 1000 30,000 Fe49 400 10,000 Co-58 1000 30,000 Co40 300 10,000 Zn45 300 20,000 Sr-90 8 0.1 100 8 100 . Zr-Nb-95 4C0
]
1131 2 0.9 3 100 Cs-134 30
10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300 "For drinking water samples This is 40 CFR Part 141 value.
9 i i e a 4 171.0 mm
04-17-98 11:13:03 Nurnber Nuclear ' "*d*oa'a' coa'r* Departmental Procedure 6610 PLN-4200.01 Title lh6elor No. Offsite Dose Calculation Manual (ODCM) 16 TABLE 8.3 Detection Capabilities for Environmental Sample Analysis
Lower Umit of Detection (LLD)u Airbome Particulate Fish Food Sediment Water or Gas (pCl/kg, Mik Products (pCl/kg.
Analysis (pCl/L) (pCl/m') wet) (pCl/L) (pCl/kg, wet) dry) Gross Beta 4 0.01 H-3 2000 Mn-64 15 130 Fe-60 30 200 Co-58, 60 15 130 Zn45 30 260 Zr-95 30 Sr-90 2 0.01 10 2 10 Nb-95 15 l131 1 8 0.07 1 60 l Cs-134 15 0.05 130 15 60 150 i Cs 137 18 0.06 150 18 80 180 Ba-140 60 00 ; La 140 15 15 1 172.0 me.
04-17-98 11:13:03 Number 3
EI TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01
m. Rmion No.
Offsite Dose Calculation Manual (ODCM) 12 TABLE 8.3 - (Cont'd) l 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 nuclides, shall also be analyzed .
and reported in the Annual Radiological Environmental Operating Report.
b. Required detection capahilities for thermoluminescent dosimeters used for environmental measurements are given in Reguietory 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 yleid a not count, above system background, that wil be detected with 95% probabilty with only 5% probablity of falsely concluding that a blank cbservation represents a 'real' signal.
For a particular measurement system (which may include radiochemical separation):
, 4.66 S3 E
V 2. 2 2 Y ' exp (- A A C)
( Where: LLD is the 'a prior!" lower limit of detection as defined above, as picocuries per unit mass or volume. s, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 la the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable), l A la the radioactive decay constant for the particular radionuclide and At for environmental samples is the elapsed time between sample collection, or end of the sample coll 6ction l 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 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 will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small samples sizes, the presence of Interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental - Operating Report.
d. LLD for drinking water.
173.0 me
04-17-98 11:13:03 Number k45 dn
- 9 Nuclear " "ad* S*"*
Departmental Procedure 6610-PLN-4200.01 Title Rev%n No. Offsite Dose Calculation Manual (ODCM) 16 TABLE 8.4 l TMINS REMP Station Locations Air Particulate and Air Iodine Station Code Distance (miles) Azimuth M MaoNo. l B1-4 0.8 28 60 E1-2 0.4 95 2 l F13 0.6 105 70 G21 1.4 125 74 M2-1 1.3 253 3 A3-1 2.6 358 4 H3-1 2.3 159 5 Q4-1 3.5 325 61 Q15-1 13.5 305 8 TABLE 8.5 , TMINS REMP Station Locations-Direct Radiation (TLD) Station Code Distance (miteel Azimuth {'l Mao No. A1-4 0.3 5 9 l B1-1 0.6 25 10 B1-2 0.4 26 11 l C12 0.3 54 13 I D11 0.2 74 14 E1-2 0.4 95 2 E1-4 0.2 98 16 l F1-2 0.2 109 17 G13 0.3 129 18 H11 0.5 167 19 J1 1 0.8 184 21 J13 0.3 180 22 i Ki-4 0.2 208 24 l L1-1 0.1 235 26 M11 0.1 249 27 N1-3 0.1 270 28 P11 0.4 293 29 P1-2 0.2 290 30 6 174.0 mm
04 17-98 11:13:03 Number NUgUI TMI Radiological Controls Departmortal Procedure 6610-PLN-4200.01 Tatie Revieson No. Offsite Dose Calculation Manual (ODCM) 16 TABLE s.5 (Cont'd) TMINS REMP Station Locations-Direct Radiation (TLD) Station Code Distance (mies) Azimuth M MaoNo. Q12 0.2 318 31 R11 0.2 335 32 C21 1.6 48 33 K2-1 1.1 200 34 M2-1 1.3 253 3 A31 2.6 358 4 H3-1 2.3 159 5 R31 2.6 338 35 B51' 4.8 18 30 C5-1 4.5 42 37 ES-1 4.6 81 38 F51 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 LS-1 4.1 228 44 MS-1 4.3 249 45 NS-1 4.9 268 46 PS-1 4.9 285 47 QS 1 5.0 318 48 RS 1 4.9 339 49 D6-1 S.0 65 50 E7-1 0.8 86 51 Q9-1 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 I 175.0 nm
04-17-98 11:13:03 l
, Numbet Nuclear i ' """d*d coa"d' I Departmental Procedure 6610-PLN-4200.01 1 h Awision No.
Offsite Dose Calculation Manual (ODCM) 16 l TABLE 8.8 1 TMINS REMP Station Locations-Surface Water l Station Code Distance (miles) Azimuth P) MaoNo. I J1-2 (R) 0.5 188 57 A3 2 (R) 2.5 355 59 091(F) 8.5 308 52 09-1 (R) 8.5 308 52 l G15-2 (F) 13.6 128 62 l G15-3 (F) 14.8 124 63 l F15-1 (R) 12.6 122 65 I (R) = Raw Water ! (F) = Finished Wate'r TABLE 8.7 TMINS REMP Station Locations Aquatic Sediment Station Code Distance (mies) Azimuth P) MaoNo. A1-3 0.5 0 67 G11 0.3 137 68 K1-3 0.3 l 202 69 J21 1.5 182 58 J12 0.5 188 57 l 176.0 me
04-17-98 11:13 03 Number NUCI88r TMl Rsdiological Controls Deparimental Procedure 6610-PLN-4200.01 ) Tw. hion No. Offatte Dose Calculation Manual (ODCM) 16 i TABLE 8.8
)
TMINS REMP Station Locations-Mllk _ Station Code Distance (milos) Azimuth M MaoNo. D2-1 1.1 65 72 E2-2 1.1 93 73 G2-1 1.4 125 74 i P71 6.7 293 77 K15-2 12.8 208 78 I TABLE 8.9 ; l TMINS REMP Station Locations-Fish Station Cods Station Location IND Downstream of Station Discterge BKG Upstream of Station Dischargo 177.0 mm
04 17-98 11:13:03 Number Nuclear WI RadW Contrds Departmental Procedure 6610-PLN-4200.01 nu. Rewon No. Offsite Dose Calculation Manual (ODCM) 16 TABLE 8.10 TMINS REMP Station Locations-Food Products Station Code Distance (miles) Azimuth M Mao No. D13 0.5 65 79 EI-2 0.4 95 2 F1-1 0.5 117 80 A151 10.5 10 85 B10 2 10.1 28 55 170.0 me.
04-17 98 11:13:03 E m. Nuolear o'"g?TC"f3 sum oo.oi m no. Offsite Dose Calculation Manual (ODCM) 16 MAP 8.1 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE O
,- O s ;"- /
h ,=o,,,',.'x y! .
/ ,/
4'
's s ,s' O 1
p
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's / , /%\
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g ss s 1 2 .75* I g
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f
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179.0 ank
04 17-98 11:13:03 Number mgNI TMi Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title N' Offsite Dose Calculation Manual (ODCM) 16 MAP s.2 THREE M:!E ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGIC 4!. ENVIRONMENTAL MONITORING PROGRAM STATIONS WITh'N 5 MILES OF THE SITE I o ygyg. 13 g 11,.25'
\' ! ' sus
B a, \ *u 33 "
\ I LL: y ' , j c 3.y._ _ . - \ \ i i .**
N i, i ' 1 see r-s g / / ss.26'
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, 180.0 "
t 4
04-17 98 11.13 03 Number - : Nuclear ""Wa' o*'* Departmental Procedure 6610-PLN-4200.01 True l un No. l Offstte Dose Calculation Manual (ODCM) 16 l MAP 8.3 ' THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS GREATER THAN 5 MILES FROM THE SITE l O , Ms.76* A 1
. 11,.m+ :J n a mem- \i l , n.w l \
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sn.W K f \ H tet.F J 188.W 181.0 me.
04-17-98 11:13:03 Numbw Nder '"' "ad'o'oa ca co"d' Departmental Procedure 6610-PLN-4200.01 Tiue Revision No. Offsite Dose Calculation Manual (ODCM) 12 9.0 - PART lli REFERENCES
1. EPRI NP-3840, RP 15604 Final Report, " Environmental Radiation Doses From Difficult To-Measure Nuclides," January 1985

2. 'Evaluarlon 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. TMI-2 Final Safety Analysis Report (FSAR)

5. Meteorological Information and Dose Assessment System (MIDAS) ,

6. NUREG4017, " 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

8. NUREG-0172, " Age-Specific Radiation Dose Commitment Factors For A Ono-Year Chronlo intake,'
November 1977
9. 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

10. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compilance with 10 CFR 50, Appendk I,' Revision 1 October 1977

11. Simplified Environmental Effluent Dosimetry System (SEEDS)

12. TMl Recirculation Factor Memos, Apri 12,1988 and March i7,1988

13. TMI 1 Operations Procedure, 1101-2.1, " Radiation Monitor Set Points"

14. Title 10, Code of Federal Regulations, ' Energy"

15. TMI 1 Technical Specifications, attached to Faclity Operating License No. DPR-50

18. 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

17. TMI 2 PDMS Technical Specifications, attached to FacElty Ucense No. DPR 73

18. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979

19. Title 40, Code of Federal Regulations, " Protection of Environment" 182.0 m=
N Number NUOIMF TMl Radidogical Controls Departmental Procedure 6610-PLN-4200.01 T ,= a.vt. ion No. Offsite Dose Calculation Manual (ODCM) 12
20. Regulatory Guide 4.13, " Performance, Testing, and Procedural SpecHications for Thermoluminescence Doelmetry: ErrAronmerstal Applications," Revision 1. July 1977

21. Post Defueling Monitored Storage Safety Analysis Report (PDMS SAR)
\
183.0 mm
04 17-9811:13:03 Number Nuclear ' ""d'*a'* co** Departmental Procedure 6610-PLN-4200.01 Tme Romeon No. Offsite Dose Calculation Manual (ODCM) 12 l l
)
l PART IV. l l REPORTING REQUIREMENTS l l l l 0 184.0 rne
04-17-98 11:13:03 Number NgUI TMI Radiological Controls Departmental Procedure 6610-PLN 4200.01 Tine Revnelon No. Offatte Dose Calculation Manual (ODCM)- 12 PARTIV s Reporting Requirements 1.0 TMl ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ** 1.1 Routine Radiological Erwironmental Ope:1 sting Reports covering the operation of the unit during the t previous calendar year shall be submitted to the Commission prior to May 1 of each year. l 1.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, I and an analysis of trends of the results of the radiological environmeatal monitoring activities for the j report period, including a comparison with pre-operational studies, with operational controls as j appropriate, and with previous environmental monkoring reports, and an assessment of the 1 observed impacts of the plant operation on the environment. The reports shall also include the results of Land Use Censuses required by Part til, Section 8.2. t.3 The Annual Radiological Environmental Operating Reports shall include the summarized tabulated results of analysis of all radiological environmental samples and environmental radiation measurements required by Part til Table 8.1 taken during the period pursuant to the locu? ras specified in the tables and figures in this ODCM, as well as summarized and tabulated resdts of these analyses and measurements in a format almilar to the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some Individual results are not available for inclusion with the report, the report shall be submitted explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. 1.4 The reports shall also include the following: a summary description of the radiological environments monitoring program; a rnap(s) of all sampling locations keyed to a table giving distances and directions from a point that is midway between the Reactor Buildings of TMI-1 and TMl-2; the results of licensee participation in the interlaboratory Comparison Program, required by Part 111. Section 8.3; discussion of all deviations from the sampling schedule of Part III, Table 8.1; discussion of all.the required analyses in which the LLD required by Part Ill, Table 8.3 was not achievable. i
**A single submittal may be made for the station.
185.0 me a
04-17-98 11:13:03 Number Nuclear " " d'd o'ca' "d ' . Departmental Procedure 6610-PLN-4200.01 l Tite HovWon No. Offsite Dose Calculation Manual (ODCM) 12 a 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE RF.PCM NOTE ; 1 A single submittal may be made for '.ne station. The submittal should j combine those sections that are common to both units at the station i however, for units with separate mdwaste 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 submRted prior to May 1 for TMI-1 and TMI-2. 2.2 The following information shall be included in both Radioactive Effluent Release Reports to be submitted each year: The Radioactive Effluent Release Reports shall include 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 Appendtx B thereof. 2.3 The Radioactive Effluent Release Reports shall include the following information for each type of solid waste shipped offsite during the report period: .
a. container volume, b, total curie quantity (specify whether detennined by measurement or estimate),

c. principal radionuclides (specify whether determined by measurement or estimate),
1
d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms), l

e. typo of shipment (e g., LSA, Type A Type B) and

f. solidification agent (e.g., cement).
2.4 The Radioactive Effluent Release Reports shall include a summary of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and ilquid 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 CALCUt.ATION 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 111 Section 8.2. 2.0 The Radioactive Effluent Release Reports shall include the instrumentation not returned to OPERABLE status within 30 days per ODCM Part I Controls 2.1.1b and 2.2.1b, and ODCM Part 11 Control 2.2.1.b. 186.0 mm
04-17-98 11:13:03 1 I l Number M Radidogical Contrds luCIOSF Departmental Procedure 6610-PLN-4200.01 j is. n.vWon No. l
)
Offsite Dose Calculation Manual (ODCM) 12 2.7 The Radioactive EfRuent Release Report to be submitted shall indude an annual summary of hourly meteorological data cdlocted 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 stabElty, and precipitation j (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind f direction, and atmospheric stabilty.
2.8 The Radioactive Effluent Release Report shall include an assessment of the radiation doses to - MEMBERS OF THE PUBUC due to the radioactive liquid and gaseous effluents released from the , unit or station during the previous calendar year. The meteorological conditions concurrent with the i time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with this ODCM. 2.9 The Radioactive Effluent Release Report shall indude an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their actMtles inside the SITE BOUNDARY during the report period, to verify compliance with the limits of i 10CFR20.1301(a)(1).. All assumptions used in making these assessments (i.e., specific activity, i exposure time and location) shall be included in these ' reports. I 2.10 The Radioactive Effluent Release Report shall also indude an assessment of radietion doses to the likely most exposed real individual from reactor releases and other nearby uranium fuel cycle sources including doses from primary effluent pathways and direct radiation for the previous 12 consecutive months to show conformance with 40 CFR 190
Environmental Radiation Protection Standards for Nudear Power Operation." Acceptable methods for calculating the dose contributions from liquid and gaseous effluents are given in Regulatory Guide 1.109 Rev.1.
1 G 187.0 mm
04-17-98 11:13:03 l Numtwr Nuclear " "*d * *' "* Departmental Procedure 6610-PLN 4200.01 me Meion No. Offalte Dose Calculation Manual (ODCM) 12 3.0 PART 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 ancj Gaseous Effluents from Ught-Water-Cooled Nuclear Power Plants,' Revision 1, June 1974 3.3 TMI.1 Technical Specifications, attached to Fac81ty Operating License No. DPR40 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 Eftluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," 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 Liquid Effluents from Light-Water-Cooled Power Reactors," Revision 0-R, AprH 1976 3.9 Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Ef!Iuents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendbc I," Revision 1, Apr81977 i
i l I
\
1 i l j i 188.0 me,
04-17-98 11:13.03 Number NEIEE TMI Radiolo06cal Controls Departmental Procedure 6610-PLN-4200.01
m. n. vision No.
Offsite Dose Calculation Manual (ODCM) 11 APPENDIX A P,- Pathway Dose Rate Parameter P, (inhalation) a 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 microcurle/m'. The dose factors are based on the critical IndMdual organ for the chid age group. k' - conversion factor,1E6 pCl/ microcurie BR - 3700 m'/yr, breathing rate for chHd (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 yleids: (ODCM Part lli Table 4.6) P,(Inhalation) = 3.7E9 DFA,(mrom/yr perpCl/m') (Eq A-2) 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 child. 4 h C s E1 1 rum
04-17-98 11:13:03 Number Nuclear ' "ad'*a'a' coatr* Departmental Procedure 6610-PLN-4200.01 Title Revieson No. Offsite Dose Calculation Manual (ODCM) 11 APPENDIX 8 RI-Inhalation Pathway Dose Factor Ri = k' (BR) (DFAJ (mrom/yr per microcurlo/m') (Eq B-1) ' Where: k'- conversion factor,1E6 pCl/ microcurie BR - breathing rate, 1400,3700,8000,8000 m'/yr for infant, chid, teenager, and adult age groups, respectively. (Reg. Guide 1.109, Rev.1. Table E-5) DFAw= the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the Ith radionuclide, in mrom/pCl. The total body is considered as an organ in the selection of DFL Values are taken from Tables E 7 through E 10, Reg. Guide 1.109 (Rev.1). Resolutions of the units yleids: RI - (1.4E9) (DFM infant (ODCM Part lli Table 5.2.1) RI = (3.7E9) (DFQ chid (ODCM Part lll Table 5.2.2) Ri = (8.0E9) (DFV teen and adult (ODCM Part til Tables 5.2.3 and 5.2.4) a s F c o
. E2-1 me, I
\ _ _ _ - - --
04-17-98 11:13 03 Nurnber Nuclear " "*d " 9' "' "d
Departmental Procedure 6010-PLN-4200.01
m. , n.vi. ion no.
Ottsite Dose Calculation Manual (ODCM) 11 APPENDlX C RI- Ground Plane Pathway Dose Factor R, = k' k' (SF) (DFG) [(1-e T)/A,] (Eq C-1) Where: k' = conversion factor,1E6 pCl/ microcurie k' = conversion factor,8760 hr/yr A, = decay constant for the i* radionuclide, sec ' t= the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 10'sec. (15 yrs), Reg. Guide 1.109 (Rev.1), Appendix C DFG,= the ground plane dose conversion factor for the l* radionuclide (mrem /hr per pCl/m'). Values are taken from Table E-6, Reg. Guide 1.109 (Rev.1). These values apply to eit aoe oroups. 1 SF = 0.7, shleiding factor, from Table E-15 Reg. Guide 1.109 (Rev.1) l Reference ODCM Part ll1 Toble 5.3.1 j 9 0 8 E3-1 m 1
04-17-98 11:13:03 Nume., Nuclear '"*d*ad "d ' Departmental Procedure 6610-PLN-4200.01
m. Maion No.
Offsite Dose Calculaiion Manual (ODCM) 3 APPENDIX D RI - Grass Cow-Milk Pathway Dose Factor R, a k' [(Q, x U,) / (A, + A.)] x (F,,) x (r) x (DFV x [((f, x f.)/Y,) + ((1-f, x f,) ed i'h)/Y,] odrf (Eq D-1) Where: k' = conversion factor,1E6 picoeurle/ microcurie (pCl/pci) l Q, = 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, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev.1) 8 Y, = agricultural productivity by unit area of pasture feed grass,0.7 kg/m (NUREG 0133) Y, = agricultural productMty by unit area of stored feed,2.0 kg/m', (NUREGo133) F, - stable element transfer coefficient (Table E-1, Reg. Guide 1.109, Rev.1) r- fraction of deposited activity retained in cow's feed grass,0.2 for particulates,1.0 for radiolodine Fable E 15, Reg. Guide 1.109, Rev.1) DF6 = the ingestion dose factor for organ, o, and the Ith radionudide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109. Rev.1) A, = decay constant for the Ith radionuclide, see d A,, = decay constant for weathering,5.73 x 10 4sec (NUREG4133); 4 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 whle the cow is on pasture E4-1 m=
04-17-98 11:13:03 l l Number i j g g y. TM1 Radiological Controls Departrnental Procedure 6610-PLN-4200.01 Tlee RevWon No. Offsite Dose Calculation Manual (ODCM) 11 APPENDIX D (Cont'd) The concentration of tritium In mHR is based on the alrborne concentration rather than the deposition. Therefore, R, is based on (X/Q): R*a, = k'k'" F, 0, U,DFlw (.75 [.5/H]) (Eq D-2) Where: k'" = 1E3 grams /kg l l H- 8 grams /m*, absolute humidity of the atmosptwre '
.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)
DF6 - the ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E 11 to E-14, j Reg. Guide 1.109, Rev.1) l All other parameters and values are as given above. NOTE Goat-mik pathway factor, R, will be computed using the cow-mHk pathway factor equation. F, factor for goat-milk wil be from Table E-2 Reg. Guide 1.109, Rev.1.
Reference:
ODCM Part 111 Tables 5.4.1 to 5.4.4 i O E4-2 me.
04-17-98 11:13:03 Number Nuclear " Rad *'oa** coatr* Departmental Procedure 6610-PLN-4200.01 me nom.cn No. Offsite Dose Calculation Manual (ODCM) 11 APPENDIX E RI - Cow-Meet Pathway Dose Factor R, = k' [(Q, x U,) / (A, + A,,)] x (F,) x (r) x (DFl%)x (((f, x f,)/Y,) + ((1-f,f,) e 'I'h)/Y,] x ed i'f (Eq E 1) Where: k'= conversion factor,1E6 picocurie / microcurie (pct /;,ci) Q, = cow consumption rate,50 kg/ day, (Reg. Guide 1.109, Rev.1) U, = Receptor's meat 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 actMty retained in cow's feed grass,0.2 for particulates,1.0 for radiolodine (Table E 15, Reg. Guide 1'109, Rev.1) DFlw= the ingestion dose factor for organ, o, and the ith radionucIlde for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev.1) A,= decay constant for the radionuclide I, secl 4 4 A, = decay constant for weathering,5.73 x 10 sec (NUREG-0133), based on a 14 day half life t, = 1.73 x 10'sec, the transport tims from pasture to receptor (NUREG 0133) t, = 7.79 x 10'sec, the transport time from crop to receptor (NUREG4133) Y, = agricultural productivity by unit area of pasture feed grass,0.7 kg/m 2(NUREG-0133) 2 Y, = agricultural productMty by unit 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 The concentration of tritium in meat is based on the airbome concentration rather than the deposition. Therefore, R, is based on (X/Q):
! R = k'k'" F, Q, Uj (DFly x 0.75 x (0.5/H]) (Eq E-2)
Where: . All terms are as oefined above and in Append!x D. 4
Reference:
ODCM Part lii, Tables 5.6.1 to 5.6.4 ES-1 me.
[ 04-17-98 11:13.03 Number g0g E TMi Radiological Controls Departmental Procedure 6610-PLN-4200.01 l
'5 a.vwonte.
Offsite Dose Calculation Manual (ODCM) 11 APPENDIX F RI Vegetation Pathway Dose Factor f R, = k' x [r/ (Y, (A, + A,,))] x (DFV x [(U',) f, edfL + 0', f, e'fh] (Eq F-1) ! Where: k' = 1E6 picocurle/ microcurie (pCl/ pol) U', = the consumption rate of fresh levy vegetation,0,26,42,64 kg/yr for Infant, child, teenager, or adult age groups, respectively (Reg. Guide 1.109, Rev.1) l U', - the consumption rate of stored vegetation,0,520,630,520 kg/yr for Infant, child, teenager, or adult age l t groups respectively (Reg. Guide 1.109, Rev.1) l i f, - the fraction of the annual intake of fresh leafy vegetation Crown locally. - 1.0 (NUREG-0133) f, = the fraction of the stored vegetation grown locally = 0.76 (NUREG-0133) t, = the average time between harvest of leafy vegetatio 1 and its consumption,8.6 x 104 seconds [ Table E-15, Reg. Guide 1.100, Rev.1 (24 hrs)] t, - the average time br v harvest of stored leafy vegetation and its consumption,5.18 x 10' seconds, [ Table E-15 Reg. O .ae 1,109, Rev.1 (60 days)] y, - the vegetation area density,2.0 kg/m' (Table E-15, Reg. Guide 1.109, Rev.1) ; 1 All other parameters are as previously defin'ed. l 1 The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. j Therefore, R, is based on (X/Q) ' R = k'k"' [U', f, + U', f,] (DFly (.75 [.5/H]) (Eq F-2) { Where:
All terms are as defined above and in Appendix D.
Reference:
ODCM Part lil, Tables 5.7.1 to 5.7.4 l l l i E6-1 me.
04-17-98 11:13:03 - Nurnber j Nuclear " "*d'doa'a' coa"d* Departmental Procedure 6610-PLN-4200.01 i re ws.n no. ; Offsite Dose Calculation Manual (ODCM) 3 I APPENDIX A F REFERENCES l (Page 1 of 4) l Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site. Parametor Value R.G.1.109 NUREG4133 Specific l
*" For P, *"
DFA Each radionuclide E-9 Note 1 BR -3700 m*/yr (chid) E-5
"*For Ri (Vegetation)***
r Each element type E-1 l Y, 2.0 kg/m2 E 15 l Aw 5.73 E 7 sec' 5.3.1.3 l DFl., Each age group and radionuclide E 11 thru E-14 Note 1 U,5 Each age roup E5 - ft 1.0 5.3.1.5 , tt 8.6 E + 4 seconds E 15 U,' Each age group E-5 l 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 R1 (Inhalation)*** !
BR Each age group E-5 DFA Each age group and E-7 thru E-10 Note 1 nuclide ! E7-1 mm
~ 04-M/-9811:13 03 Number NUg I TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tme Revision No. Offsite Dose Calculation Manual (ODCM) 3 APPENDlX A-F REFERENCES (Page 2 of 4) Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Siti Parameter Value R.G.1.109 NUREG-0133 ' Specific
*" For R, (Ground Plane) ***
SF 0.7 E 15 DFG, Each radionuclide E-6 1 4.73 E + 8 sec 5.3.1.2
"* For R1 (Grass / Animal / Meat) ***
O,(Cow) 50 kg/ day E3 Q, (Goat) 6 kg/ day E-3 Ref. Only U,, Each age Group E-5 Aw 5.73 E 7 sec' 5.3.1.3 F, (Both) Each element E1 r Each element type E 15 DFly 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/m' 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 me,
n 04-17-98 11:13:03 Number Nuclear M RaMogical Contre Departmental Procedure 6610 PLN-4200.01 Titje Revision No. Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES (Page 3 of 4) Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site- ! Parameter . Value R.G.1.109 NUREG4133 Specific
*** For R, (Grass / Cow / Milk) *** . O, 50 kg/ day E-3 j
U,, Each age group E-5 I Aw 5.73 E-7 sec' 5.3.1.3 F, Each element E1 ' r Each element type E-15 I DFL, Each age group and nuclide E-11 thru E-14 Note 1 l 1 Y, 0.7 kg/m' E 15 ; t, 7.78 E + 8 sec E-15 Y, 2.0 kg/m' E-15 I t, 1.73 E + 5 sec E-15 j f, 1.0 5.3.1.3 f, 1.0 5.3.1.3 i H 8.0 grams /kg 5.2.1.3 i 9
, E7-3 me
04-17-98 11:13:03 Number NgEI TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 rm. Revison No. l 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, far each nudide, the organ dose factor used was the highest dose factor for that nuclide and age group in the
, 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 miles typleally are used for grass control and not food or milk.
Nevertheless, the goats can be treated as full meat sources where present, despite the fact that their numbem cannot sustain the meat consumption rates of Table E-5, NUREG4133. REFERENCES
1. Regulatory Guido 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compilance with 10 CFR Part 50, Appendix 1." Revision 1, October 1977.

2. TMI.1 Technical Specifications, attached to Fac91ty Operating Ucense No. DPR-50.

3. NUREG-0133, " Preparation of Radiolo0l eal Effluent Technical Specifications for Nuclear Power Plants,"
October 1978. t t e E7-4 222
Enclosure 2 .e 1997 Annual Radioactive Effluent Releases Report for TMI'
,1920-98-20209 't t i
Procedure Change Request (PCR) 1-RC-96-0070 to the ODCM,6610-PLN-4200.01 l
'l i 'i l l.
L
1 04-20-98 10:16:02 * - ' -
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i 1 04-20-98 10:16:02- ' l 1001A Revision 30 4 FIGURE 4 i 1 THREE Mll.E isl.AND UNIT ONE ; I SAFETY DETERMINATION i This determene6en le required for aN documents within 1001A appucebility/seope. 1 New Premdwe,_,,,,, . _ . . _ C TCN . _ ,,,_,. _ _ _ _ _ ]
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' Lfs L O-PLM - 4200.01 O' t
1. is this a eutetentive change? Indiesee 'YsS* for new procedures and STP's - Yes u Ne
, N som 1 is "Ne*, sign and does this form. The remainder of the form need not be sempleted.
2. Does this change inweeve any norwadielegieel enwonmentes impeet? poser to Denninene esemen of this procedwe.) Yu .No e w 'Yes'. esmotese Pleure e and enewe the enance le submined to t'nvironmenesi controle and environmened useneing ser review. ,
e composes the remainder of this tonn. ,
3. . Does this ehenge have the pesennel to adveremy eneet nuelser eefety or esse piant operadene? Yes, . ,, No u Feier to Perseraph 4.2.2 -

4. Osw this mehe ehenges in me teeWIy no deserted in the safety analysis report? 4 Yu No d

s. Dess this mehe changes in the procedwee as deserted in the esfety analysie repen?, Yes- 'No #

e. Are teens er aperimenes eendueese which are not deserted in me enemy eneereis repert? Yes Ne #

r. ' ones this ehenge eenniet wish me equiremones er'the plant Technions apodasemenet Yes Ne #
um of the enemere to 3,4, s, e opi r are,tgg you must as eut rigwe sAtgt premie a wemen esseer evasuamen. sien and date mie form. ir me enemere e a,4 s, e AND T engjg thle pregiudge the edseense el an C r ' Z Esfety Gesemen er Technical ; . '- ^' change Prowse me beste ter why me change is sees here. sign and done mes form. g R
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04-20-98 10:16:02
/4 C-96-oo70 l ~
SAFETYDETERMINATION The change does not have the potential.to advenely affect nucicar safety or safe plant operatkms. This change does not afIcet the type or quantity of = L'=h1 etBuents released from the plant. The change will not adversely affect nuclear safety or safe plant a:* *+i- for the following resums: The change iiw g.i Figure 5 3 ofTechnical %- 1' =b into the ODCM since this figure will be deleted from Technkal Saa4hh upon approval of Technical S"Re=h Change Requet (TSCR)# 257.- This change is rw-mary because the ODCM uses this figure to define the site boundary for liquid effluents. Rderence to the new Pigure 1.1 as the site boundary for liquid effluents is made in this change to the definitions secbons ofPart I and Part II of the ODCM. , The change ehnunates Section 4.0 " Design Featurcs" from Part II of the ODCM. NUREG 1301,"ODCM Guidance: Standani Radiological Effluent Controls for ".-61 Water Reactors", does not specify this as a
- section in the ODCM. The site boundary defirutions in Secuon 4.0 ofPart IIof the ODCM will be incorporated into the Part II definitions secuon upon kr.phentation of this change. Mmbea of the definitions for Exclusion Area and Is Population Zone from the ODCM is acceptable as these are terms used for emergency planning purposes, not for routine cf!!uent controls and ofTsite dose calculations. These terms are already defined in the Figure 5 GPUN Emergency Plan and TMI-1 FSAR, Secuans 2.1 and 2.2.
inchange does not make changes to any facihties as described in the safetyanalysis report. This PCR does not mak any changes to facilities. !
'Ihe change does not make clianges in the procedures as described in'the safety analpis report. The changes are consrstent with Secton 2 of the TMI 1 FSAR and the GPUN EmerEency Plan.
No tests or expenments are conducted which are not described in the safety analysis report. The PCR does not conduct any tests or sgh &. The change does not conflict with the i%uhaws ofTechnical Specifications! Figure 1.1 in the change is idenucal to l Figure 5-3 ofTech Specs. Implementation of the change prior to approval of the TSCR will not ennfher with existing ' Technical he4Ae=*ns. Based on the forgoing, the change is' considered safe. B. A.Parfitt i1/25/96 ' We
04-20-98 10:16 02 . Number N EI- TMI Radido0 lcal Controls Departmental Prwure 6610-PLN 4200.01 Tme Revision No. Offsite Dose Calculation Manual (ODCM) . 14
.W3mty/
scope Calculate offsjte doses due to radioactive AeoponmNo ovnoe Effectrve cate effluents for dernonstrating compliance wth Site Technical Specifications 10 CFR 20 & 10 CFR 50 - Appendix i ,6610 05/09/96 Thl4 document is within OA plan scope X Yes No ' Safety Reviews Required X Yes No ' List of $ffective' Pages
,P J g2 Revision fagg g 'qlga fagg Revision fagg Revision 1.0 14 21.0 s1 41.0 12 61.0 12 2.0 14 22.0 11 42.0 12 62.0 12 3.0 11 23.0 11 43.0 12 63.0 12 4.0 12 24.0 11 44.0 12 64.0 12 5.0 12 25.0 11 45.0 12 65.0 12 6.0 - 12 26.0 , 11 46.0 12 86.0 12 7.0 12 27.0- 13 47.0 12 67.0 12 8.0 12 28.0 12 48.0 14 68.0 12 9t0 12 29.0 12 49.0 12- 69.0 12 10.0 12 .30.0 12 50.0 ^
14 70.0 12 l 11.0 12 31.0 12 51.0 14 71.0 12 12.0 12 32.0 12- l 52.0 12 72.0 12 13.0 12 33.0 i 12 ~ 53.0 12 73.0 12 ! 14.0 11 34.0 12 54.0 12 74.0 12 15.0 11 35.0 12 55.0 12 75.0 12 16.0 11- 36.0 12 56.0 12 , 76.0 12 17.0 11 37.0' 12 57.0 12 77.0 12 18.0 A 38.0 12 58.0 . 12 . 78.0 12 19.0/ . 11 39.0 12 59.0 12 79.0 12 20if C P 14 N 40.0 12 60.0 13 80.0 12
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{ C C r'.V/.:i G l Radiological Engineer, TMl NNNNN $$kNN q g Env. Affairs f , u - a.r. Rad m .ru, w gj i;c.s M_,e,.1., Roa,,s wp r., . 24 Rad Con / Safety Director. TMl /
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04-20-98 10:16:02 , hbar gp
~ TMl Radiologic # Controls .-
Departmerdal Procedwo 6$10-PLN 4200.01 Time nww.nre. J Offsite Dose Calculation Manuel (ODCM) . 11 1.9 Purge Purging PURGE or PURGING is the controlled process of discherging air or gas from a confinement to - malrnain torpperature, pressure, humidity, conowntration or other operating conditions in such a ' manner that replacemeht Air or gas is required to purry the confinement. 1.10 . Venting -
. VENTING is the controlled process of discharging air as goe from a conknement to maintain tempennure, pressure, humidity, concentration or other operating conditions in such a manner that .t replacement air or gas is not prtwided Vent used in system name does not imply a VENTING -
process. 1.11 Member (s) of the Public MEMBER (8) OF THE PUBdC shaR induda all persons who are not cocupationally ammaenatart with -
.the plert. This category does not indude employees of the GPU System, GPU contractors or vendors. Also excluded from this category are persons who enter the alte to service equipment or . to mInke deliverlos. ' .
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~
correspond to the intervals defined in Table 1 1. All Survellence Requremente shall be performed withm the specilled time Interval with a rmodmum aloweblo entension not to =tamart 25% of the . survellence interval. The 25% extension appges to an frequency irtervals with the exception of T.* No entension is alowed for intervals designated 7.* Table 11 s Frequency N$tesion Notation . Frequency S Shirdy (once per 12 hours)' *
. O Daly(once per24 hours)
W Weeldy (once por 7 days) . -
. M. Monthly (once per 31 days) 18.0 m d
'04-20-98 10:16:02: ,
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.l Replace existing 1.12 with the following:
1.12. ' Site "My The SITE BOUNDARY used as the basis for the limits on the release of gaseous
effluents is as deAned in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI-1 FSAR.
This boundary line includes portions of the S = ='== River surface between the east
~ bank of the river and'Ihree Mile Island and between Three Mile Island and Shelley - I Island The Si1E BOUNDARY used as the basis for the limits'on the micase ofliqui.d cfBuents is as shown in Figure 1.1 in Part I of this ODCM.
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. mese -
ggp TM) Radiologiciiltontrols Departmental Procedure 6610 PL.N-4200.01
~.
Tces MNelon No. Offsite Dose Calculation Manual (ODCM) 11 Notation Frequency
.O Quartedy'(once per 92 days)
S/A > Semi-Annuely (once per 184 dayo)
)1 R Refueling Interval (once per 24 morths). * ' l P S/U Prior to each reactor startup, if not done during the , i 1 previous 7 days P Completed prior to each release N/A (NA) - Not appumble I 4
E Once per 18 monthe F Not to exceed 24 months Bases Section 1.13 establishes,the limit for which_the specified time' interval for Survellence quirements may be extended. it permits an alloweblo extension of the normal surveBlance interval to f de survedience . i scheddng and consideradon of plant operating condklons that may not be sultath / conducting the i survallance; e.g., transient conditions or other ongoing surveBance or maintenance actMties. It also provides Roxblity to accommodate the length of a fuel cycle for surveBances that are specNied to be performed et least once each REFUELING INTERVAL lt is not intended that this provision be used - repeatedly as a convenience to extend surveRance intervals beyond that specified for survellences that are ' not performed once each REFUEUNG INTERVAL Ukowise, it is not the Intent that REFUEUNG INTERVAL survellences be performed during power operation unless it is consistent with esfo plant operation. The' limitation of Section 1.13 is based on engineering judgement and the recognition that the most probable result of any particular survetlance being performed is the vertncation of conformance with the Survellance. Requirements This provision is sullicient to ensure that the reliabulty ensured through survellence actMtles is not signMcendy degraded beyond trat otdahid from the specMed surveRance intenel 4 l'asce.r- % Fteue.e 1. t ou cex T- %a- , 9
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._ Tim 6610-PLN-4200.01 w oon No.
1 Offsite Dose Calculation Manual (ODCM) 12 l l 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 OPERABluTY Including alarm and/or trip functions. l b. Bistable channels - the injection of a simulated signal into the channel sensor to verify. OPERABluTY including alarm and/or trip functions. SOURCE CHECK ' 1.8 A SOURCE CHECK shall be the qualitalke assessment of channel response when the channel sensor is exposed to a radioactive source. ; COMPOSITE SAMPt.E 1.9 - A COMPOSITE SAMPLE is a combination of individual samples obtained at regular int 6svals over a
' time period. Elther the volume of each IndMdual sample is proponional to the flow rate discharge at the time of sampling or the number of equal volume samples is proportional to the tirne period used to produce the composite.
i
. GRAB SAMPLE , .
1.10 A GRAB SAMPLE is an indMdual sample collected in less th n fifteen minutes. BATCH REl,g6fg 1.11 A BATCH RELEASE is the discharge of fluid waste of a discrete volume. CONTINUOUS RELEASE l 1.12 [ A CONTINUOUS RELEASE is the discharge of fluid waste of a non<liscrete volume, e.g., from a i volume or system that has an input flow during the CONTINUOUS RELEASE. ADD Mdu8 S E.C.Tiod I. IS s fR, EQUENCY NOTATION 1.W The FREQUENCY NOTATION specified for the performance of Survelliance Requirements sha!!'. 14- correspond to the intervals defined in Table 1.1. All Surveillance Requirements shall be perfonned within the speelfied time Interval with a maximum allowable extension not to exceed 25% of the ! survelliance interval, h h 65.0 tim
04-20-98 10:16:02 . e l
' Add following Section 1.13:'
1 SrrE BOUNDARY 1.13. The SITE BOUNDARY used as the basis for the limits on the release of gaseous cfDuents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI-l F$AR. - This boundary line includes portions of the SM.enna River surface between the east 1 bank of the river and Three Mile Island and between Three Mile Island and Shelley - Island . 1 t
- r
I The SITE BOUNDARY used as the basis for the limits on the release ofliquid efHuents
, is as shown in Figure 1.1 in Part I of this ODCM.. .
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04-20-98 10:16:02
. Number Nuclear = a*'doa~da Departmental Procedure 6610-PLN-4200.01 M*
Revision No. Offsite Dose Calculation Manual (ODCM) 12 9 SECDON LO
' Design Features .
4.0 DESIGN FEATUR'ES . 4.1 ,$[IE EXCLUSION AREA i 4.1.1 The exclusion area.is shown in r 1. TMI 1 Tech. Specs. LOW POPULATIONO2' NE ' 4.1.2 The low population zo .ss shown in Figure 6-2, et Tech. Specs. SITE BOUNDARY FOR GASEOU FFLUENTS . 4.1.3 The she bou ary for Osseous effluents shall be as defined Section 2.1.2.2 of'the TMI 1 FSAR and as shown Figure 2.13, TMl-1 FSAR.- - SITE BOUNDARY F UQU!D EFFLUENTS 4.1.4 e site ' boundary for liquid effluents shall be as shown in Figure 5 3, TMI- ech. Specs. I
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04-20-98 10:16:02 Number Nuclear ' "ad'd* coa"d* Departmental Procedure 6610-PLN-4200.01 7rtle Revision No. Offsite Dose Calculation Manual (ODCM) 12
.0 PART ll REFERENCES 1 4g.1 NUREG-0683,
Final Programmatic Envirvis.nt&l Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28,1979, accident Three Mlle Island Nuclear Station, Unit 2." March 1981, and its supplements.
4f.2 TMI-2 PDMS Technical Specifications, attached to Facility Ucense No. DPR-73 4 f.bl Title 10, Code of Federal Regulations, " Energy" i 4 f.4 . ' Statement of Policy Relative to the NRC Programmatic Environmental Impact Statement on the Cleanup of Three Mile Island Unit 2,* dated April 27,1981 4 /.5 Regulatory Guide 1.109, ' Calculation of Annual Doses to Man from Routine Releases of Reactor Emuents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 4 /.6 DOE / TIC-27601, Atmospheric Science and Power Reduction 4 f.7 ' .TMI-1 Technical Specifications, attached to FacIlty Operating Ucense No. DPR-50 i 4-/.8 PDMS . SAR 9 9 9 t l 9 4 4 88.0 nm. 9
{- .t Enclosure 3 - 1997 Annual Radioactive EfBuent Releases Report for TMI 1920-9F 20209 i l l I Procedure Change Request (PCR) 1-RC-97-0023 to the ODCM,6610-PLN-4200.01 l l l l
04-20.98 10:18:03:
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20 98 10:18:03 . . . o' .
. Prona=A REMP Channen to the ODCM nad P==ans for Chances. ,
Change #1. Change the wording in the first and second paragraphs of Part IH Section 8.1.3b '
.(pg 161) . from ODCM Part II, Sections 2.1.1.3F,2.1.2.3D, and 2.1.2.3E' to 'ODCM Part - ~
H Controls 2.2.1.2,.2.2.2.2 and 2.2.2.3'. Reason #1. This change is proposed so that the current Casignation of the applicable O Controls is reflected.
. Change #2. Change the wording in Table 8.1 for sediment sampling and collection frequency (pg 167)* from ' Sample,twice per year (Spring and Fau),the interval not to exceed 184 eys' ,
to ' Sample twice per year (Spring and Fall)'. Reason #2. . This change will enhance personnel safety by providing additional flexibility in the. sampling schedule.' Deleting the absolute sampling' frequency will enhance personnel safety by eliminating the need to collect samples during adverse river ; ,
. conditions. The change will hilow for collections during the safest river conditions j - in mid to late Spring aAer high river flows and in early to mid Fau prior to cold -
I weather. ! This change will not reduce the number of samples collected'and analyzed. Sediment samples will continue to be collected twice per year, once in the Spring- , and once in the Fall, as required by the ODCM. The frequency for sediment sampling also will be consistent with the collection frequency proposed for fish, :1
. sampling (Change #3). This will permit a comparative study of' radionuclides . l dead in both media. Sediments may be a source of radionuclides to fish. -i . Change #3. Change the wordinig in Table 8.1 for fish sampling and coHection frequency from (pg 168) . ' Sample twice per year (Spring and Fall) the interval not to exceed 184 days' to , ' Sample twice per year (Spring and Fall)'.-
Reason #3. This change will provide additional flexibility in the sampling' schedule. The added j flexibility will increase personnel safety and increase the probability of obtaining ; l the ODCM required samples. Deleting the absolute sampling frequency will . ~ 1 enhance personnel safety by eliminating the need 'tol collect samples during adverse river conditions. The change will allow for collections during the safest river - conditions - in mid to late Spring after high river flows and in early to mid Fall .
. prior to cold weather. Also, the probability of obtaining samples will be enhanced ;
because fish are most active biologicaHy during these same Spring and Fall periods.
, l f .
This' change will not reduce the number of samples collected and analyzed. Fish samples will continue to be collected twice per year, once in the Spring and once in the Fall, as required by the ODCM. The frequency for fish sampling also will be consistent with.the collection frequency proposed for aadiment sampling (Change
#2). This will permit a comparative study of radionuclides detected in both media.
Sediments may be a source of radionuclides to fish. O O .
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04 20-98 10;18:03 - - D
'1-Change #4. In Table 8.1, delete the sampling and analysis requirements for fruits and - ,(pg _ 16% vegetables. . The Table 8.1 requirement for sampling and analyzing green leafy '
vegetables will be retained. Reason #4; Both the USNRC Branch Tecnical Position (BTP) and NUREG'1301 recommend 3 collection and analysis of food products (i.e.. fruits and vegetables) from areas aat are' irrigated by water in which liquid plant wastes have been dicharged. This requirement may be deleted because no irrigaGon with water fkom the Susquehanna River is practiced in the area proximal to TMINS. Sampling of green leafy vegetables (af one indicator station and one control station during the harvest season) has been retained even though the BTP and NUREG 1301 recommend sampling only if milk samples are not collected. The TMINS : ' l REMP does include routine sampling of milk. j i On' Table 8.3, change '(lld)* to '(LLD)'. Change #5. , (pg 172) ,
* , Reason #5. This change corrects a gt pographical error. ' ,
Change #6. . Delete Stations J3-2, G10-1,and J15-1 from Table 8.4,"TMINS REMP Station (pg 174) Locations- AirParticulate and AirIodine".- , 4 t Reason #6. Air particulate and air iodine samples are no longer collected from these stations. The ODCM requirements for the TMINS REMP can be 16et (o, r. exceeded) with
* ~
the remaining stations. Change #7'. . Delete Stations Al-1, B1-3, El-1,'H1-9, J14, K1 5 and R15-2 from Table 8.5, ,
-(pgs 174 & "TMINS REMP Station Locations - Direct Radiation (TLD)".-
175). Resea #7. TLDS are no longer collected from these stations. The ODCM requirements for
~ '
the TMINS REMP can be met (or exceeded) with the remaining stations. Change #8. Delete raw water StationscPI-3(R) and J2-1(R) and finished water Sthtions (pg 176) , G15-1(F) and J15-1(F) from Table 8.6, "TMINS REMP Station Locations - Surface Water". ' Also, add raw (unfinished) water Station Q9-1(R) to Table 8.6. c Reason #8. Raw and finished water samples are no longer c' o llected from Stations J2-1(R), G15-1(F) and J15-1(F). The ODCM requirements for the TMINS REMP can be met (or exceeded) with the reinaining stations. , Station Q9-1(R) was' added :a replace Station PI-3(R), a raw water control ,
, location. In the near future, raw Susquehanna River waterwill not be supplied to Station P1-3 (TMI-l Pretreatment Building). ' And since a suitable replacement site - , , was ret available on 'IMI, the control raw water station was located at Station Q9-1(R). -Station Q9-1(R) is located at the Steelton Water Authority in Steelton, PA. Finished water is presently collected at this control site.
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04-20-98 10:18:03 ,,
. l si Change #9. Delete Statioi Al-2 from Table 8.7, "TMINS REldP Station Locations'- Aquatic (pg 176) Sediment". Also, add Station J1-2 to Table 8.7 Reason #9. Sediment samples are no longer collected from Coritrol Station Al-2. The ODCM -
requimments for the TMINS REMP can be met (or exceeded) with the is..elr.irg stations. Indicator Station J1-2 was added to enhance the TMINS REMP.
~ Change #10. Delete Stations A4-1 and F4-1 from Table 8.8, "TMINS REMP Station Locations . (pg 177)' '- Milk";
Reason #10. Milk samples are no longer collected from these locations. The ODCM - requirements for the TMINS REMP can be met (or exceeded) with the remaining stations. d 5 Change #11. Except for Stat. ions Dl-3, El-2, F1-1 and A15 delete all listed stations from 1, (pg 178) - - Table 8.10, " TMINS REMP Sta' tion Locations - Food Products" ~ Also, add . Station B10-2 to Table 8.10. - Reason #11. As explained in Change #4 above, fruits and vegetables.(eiccept green leafy) will no . lon8er be sampled as part of the routine REMP. Only those' stations which will be - sampled for green leafy vegetables will be retained on Table 8.10. The ODCM requirement to sample green leafy vegetables at one indicator and one control . station can be met (or exceeded) with the stations retained on Table 8.10. Station B10-2 was added to replace Station RIS-2, a control food ' product ' location; Station R15-2 is no longer a valid control location. The analysis laboratory at this si,te has expanded its operations and now has the potential to release small amounts of radioactive materials to the local environment. Food products grown proximal to the laboratory could be affected by these releases..
. Station B10-2 is located lat the Milton Hershey School which is approximately 10.1 miles firom TMINS in the NNE sector (azimuth = 28 degrees). . Based on guidance firom the BTP,' Station B10-2 is an acceptable control sampling location.
Change #12. Change Maps 8.1, 8.2 and 8.3. Revised maps are included in this package. (pgs 179,180 - ,
&181)
Reason #12. Revisions t6 the maps are necessary to reflect Changes #6 thru #11. C% is # t s Ano 'BioArc.usut.4rtou F^r-Tom ras Acy lio w To ' TASt.c ' E.2 c*> 'F%r-e to7 '
'8" -13 T Pa m it %uin spra us4Y ME CALCUM*AS -
Foe n4 s isowPs 4 4
\ . , , ., g h;. '.*- , I .: ,. ; ,,, , .g. .g
04-20.-98 10:18:03
~ - 1001A . . negleion 30 Ploups 4 ,
mass uu numa usaraus .
. sansw estunumanow .
nwa seinemmenen is ,eevired ser as Weeumenes wsWn 1001A appeseamy/sesper n~~ __.. - _ . . .
*C3 e . -. - . _ _ _ ,cn L . &._C:. 9 S _._ o_. _o .6 L S . . *""""*
b b/4 -P& %sM/ - /
t. le tNe e outeennsive ehenget instenes "YES* ter new poseewes and STP's Yes d No "
r ada 1 le "Ne'. eign and date e feen. The ,emeinder of me teen,nese not he sempleted.
/
a. coes mis enense invesse any no,meleasessel enversamenees impasst (Refer. Dennesene asemen of.is penedwe.) Yes V No e , r Yes*. esmspeso news e and enews es enense is euensued to Envi,enmeness Canesis and Envi,enmenad useneine s.,oveen,
e - composes me ,emeinder et ein se,m. ,
t ones as enen.,ep e ,s .o .ees,,s. . ed.e.e., .is. e. e.eir - e.e erer,,s.e,,i, v.e ' ue / (meserto pene .423
4. Does mis mehe eneness m me seems, as senses. h me esses, mislysis ,epe,tf Yes No Yes_ me d ones . mene . + = .e - es.see,.e. . e. 4 e, e.epe

s. A,e teses esponmente eenduseos maiah e,e not desemed h me setos, enefyele ,epen? . Yie 1 Me W

r. Does ese enense eenmet wem me ,equeememe et me pense M apenasemanet Yes ,_ ,Ne W
'ima n = e,. sos,s .d. . an r e,s.s - , . e. a.no .am e .w o. a.ser.es.=en. .
m. .es .s
.emi. , . .e e e.e. . - r e,. . .
e . .e es...e, es., . e.e, e e i.e.o. s.e e .o . . e D 0 0 J . 6 f m _ A
,,e.e,s. .,.j % 44' 'KL$W r o.o: /245/f4
[ -i. - . .
. m., e ? * * '.,' h,,'flbf , V . ~. . .y _ fi . h ~. l * ( y.' ' 5C. *f ~ ?~: , .
04-20-98 10:18:03.
, , ~
F Safety Determination j Changes to the TMI ODCM are proposed. They are limited to'.the radiological environmental monitoring program (REMP) which is de6ned in Section 8 of Part III. Ju'stification for each change is provided in this package. The proposed changes update Control designations (Change
#1), add flexibility to the sediment and fish sampling' schedules (Changes #2 ahd #3),' delete the -
collection of fruits and vegetables in accordance with.USNRC Branch Technical Posit' ion (BTP) . i guidance (Change #4), correct a typographical error (Change #5), delete stations froia the tables - l and maps which are no longer sampled (Changes #6 thm #10 and add stations to the tables and
. maps which replace stations that no longer provide valid sampes (Changes #8, #1.1 and #12). .
The revised REMP will continue to meet or exceed the recomn'endations of the BTP for radiological environmental monh oring. As such,'none of the proposed chauges to the TMI ODCM REMP will adversely affect inplant
- nuclear safety or safe plant operations. Consequently, the licalth.and safety of the workers or the , public will not be adversely affected. Additionally, the proposed changes do not 1) make changes to the facili*y (e.g.~ plant components, systems or structures) or procedures as described in the l SAR,2) change levels of effluents released to the environment,3) involve or conduct tests or - l experiments not described in th'e'SAR or 4) conflict with the requirements of the TMI-1 and TMI '
2 Technical Specifications. Based on the above, the proposed cl+snges to TMI ODCM REMP are considered to be safe. t t b 6 e e-
.,: - ; ; .s- 4.g .
04-20-98 10:18:03 SAFETY DETERMINATION
~
The' change does not have the potential to adversely affec.t nuclear , safety or safe plant operations. This; change does not affect the type or quantity-of radiological' effluents released from the plant. .l The change spe.cifies the bicaccumulation factor for silver (Ag) that is used to' calculate offsite dose from liquid effluents. containing Ag-110m. This bioaccumulation factor is specified by
Rev 0 of Reg Guide 1.109 and'is used by both the IAGER and SEEDS dose calculation programs. Specifying this factor in the ODCM improves the document'ation of the basis for offaite dose calculations. -
The change.does not.make changes to any facilitles as' described in the safety analysis report. This PCR does not make any changes'to fac lities. The change does'not make changes in the proce~dures as described in the. safety analysis report. Bioaccumulation factors are not described in the FSAR. No tests or experiments are'c'onducted which.are not described in the safety analysis report. The PCR does not conduct any tests or I experiments. - The change does not conflict.with the requirements of Technical Specifications. Effluent controls.are no longer contained in Technical Specifications. They are now contained in the ODCM. Based on the forgoing, the change is considered safe. B.-A. P'ar tt 12/16/96 , T1d E-THESe. CHAsiced.s to por REcoc6 THE LEVEL oF R re19o# EFFLvauT Co4 TROL. REquiRec sv. secpggo.fe4., so Awd toCFE.CO.hA Aao Aresaomr To toda so Ahow+ ADygg,$tay 'MPAc2* Tde AccultACY of 9#.LIABtLtP[ oF EFFLLIEMT,DoS j 3R SgTPot4T CALCD'ATio48 W <,/4 se ' sp 9 4 e
04-20-98 10:18:03 g gy TMI Radiological Controls ' Departmental Procedure 6610 PLN-4200.01 me, w no.
. Offsite Dose Calculation Manual (ODCM). 15 . 1 % /se.p. Calculate offsite doses due to radk se - ~ s omo. e.een o. , - effluents for demonstrating compilence with Site Technical . Specifications 10 CFR 20 & 10 CFR 50 ' Appendk 1 6810 01/17/97 This document is within QA plan scope X Yes No . Safety Reviews Required X Yes No -
Ust of Effective Pages fagg . Revision PEgg Revision - Pggg Revision Pggg Revision
. 1.0 15- 21.0 15 41.0 15 61.0 ~ ' 15-2.0 15 22.0' 15 42,0 15 62.0 15 . , 3.0 11 23.0 15 . 43.0 15 63.0 15 4.0 15 24.0 15 44,0 15 84.0 15 5.0 15 25.0 15 45.0 15 65.0 15 8.0 15 24.0 15 44.0 15 88.0 -15 7.0 '15 27.0 15 47.0 15 47.0 15 ,
8.0 15 20.0 . )5 48.0 15 68.0 15 9.0 15 29.0 15 49.0 15 , 90.0 15 10.0 15 30.0 15 ,50.0 .15 , 70.0 15 i
. 11.0 15 31.0 15- 51.0 15 71.0 15 12.0 15 32.0 . 15 .
52.0 15 72.0 15 13.0 15 . 33.0 15 53.0 15 - 73.0 ' 15 14 0 11 34.0 15 54.0 15 74.0 15 15.L 11 35.0 15 55.0 15 75.0 15
~ 16.0 11 36.0 15' 54.0 15 -
78.0
15 17.0 11' 37.0 15 57.0 15 77.0 - 15

18.0 - 15 38.0 - 15 , 58.0 15 78.0 15 .
19.0 11 39.0 18 59.0 .15 ' 79.0 15 20.0- 18 40.0 15 -80.0 15' 50.0 15 G P I.I N , q occuencWRot. ' CG4mALED . E I " " " DI
k' D N M9BEhmw=h adM
( eu , ) k SBt 4NWnMh4WMhh Radicion
%.m ' @4 .- jQ@.% . '"*^"* . (ck./p$Q \/\ >)%
uan ger. Rad. Eno.. m gQ i/7/91 , Manager. TMI Reg. Affairs juh /-/ 3 -/7 Mad Con /sa v oirect=. = QQ(t, . i.g-97 a.
~
1.0 nm.
'04-20-98 10:18:03 Number - g g y. TMl Radiological Contmis Depenmental Procedure . , 6610-PLN-4200.01 me Remon No.
- ' Offstte Dose Calculation Manual (ODCM)' ,
12 TABLE 2.2 Bloeccumuletion Factors, BF, Bioaccumulation Factors to be'Used in the Absence'of Site.Spe'cl6c Deta* (pct /kg per pCr/mer). FRESHWATER ELEMENT FISH INVERTEBRATE.' , H 9.OE-01 9.0E-01 C- . 4.6E + 03 9.1E + 03
, NA 1.0E +02 2.0E+02 . CR 2.0E +02 2.0E+ 03 MN 4.0E+02 9.0E + 04 'FE 1.0E+ 02 3.2E+03 CO 5.0E+ 01 2.0E+ 02 N1 '
1.0E + 02 1.0E+ 02 CO . 5.0E+01 4.0E+02
.2N 2.0E+ 03 ~ 1.0E+04. '
BR 4.2E +'02 3.3E+02 , RB . 2.0F :.03 . 1.0E + 03 '
~
SR 3 W+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 MO 1.0E + 01 - 1.0E+ 01
,o yC '
1.5E + 01 '5.0 E + 00 k-Ilom RU ' ' 1.0E+ 01 3.0E + 02
- bRH * #'368#10E+01 3.0E +02 VSB f.0E+ 00 # *T.0E+00 -
TE 4.0E+ 02 6.1E + 03 1 1.5E+ 01 5.0E + 00 CS 2.0E+ 03 ' 1 AE+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 from Reg. Guide 1.109 . Table A 1).
Sb bioaccumulation factor value is taken from EPRI NP.3840. g
.,.y , g beaccumdWim 6c.4..- veli.a. n hk.A.4m y' ' '*' .
A N >
,105.0 ::: =
{
04-20,-98 10:18:03 m.mser
= "ad *
S " c a

Nuclear Departmental Procedure 6610-PLN-4200.01 sem.on No.
rue Offsite Dose Calculation Manual (ODCM) k 8.0 TMINS'RADIOLOn! CAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
, 8.1 ' Monitorina Proaram Reouirements ,
8.1.1 Controls 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 Apolicability , t At all times. 8.1.3 Action
a. With the rhkal environmental monitoring program not being conducted as specified in Table 8,1. prepare and submit to the Commission in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as requred '
and the piare for preventing a recurrence.
b. With the level of radioactMty as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 8.2 when averaged over any calender quarter, prepare and submit to the cme.; ;a6 within 30 days from the end of t!)e affected calendar quarter, a special report that' Identifies the cause(s) for exceeding the limit (s) and defines the corrective act be taken to reduce radioactive affluents so that the potental public is less than,the calendar year limits of ODCM Part L p,b annual dose
to a rne p and ODCM Part i S: ' -^"-4'".at^"". -i-
'7e I Controls 2.2.1.2,
e of the radionuclides n Table 8.2 are detected as the result of pi.aoC.-When moreplant affluents in the sampling medium, this report shall be submi j, ), a concentration Hl. + concentration (2) + . a:1.0 reposting level (1) reporting level (2) .
When radionuclides other than those in Table 8.2 are detected and are the result of plant shall be submitted if the potential annual dose
to a member of the pubt o or greater than the calendar year limits of ODCM Part i Contrais 2.2.1.2 "
ODCM Part _ ~' x 0
t.r.

R00, J ^.RGE. Tnes report m -
^
not the rnessurpd I of radioactMty was not the result of plant offluents; however, in such an event, the condition shall be reported and desc ibed in the Annual 4 i Radiological Erv c....wi:al Operating Report.
, A/s ,
Aurad.b AAAA b) . 1 l
The metnodology and parameters used to estimate the potential annual dose to a member of the public shall '
be Indicated in this report.
~
161.0 . me. 4 .
l 04-20-98 10:18:03 , gEIMr- TMt Radiological Controls Departmental Procedure .6610-PLN-4s00.01 Th Reneson No. 12 Offsite Dose Calculation Manual (ODCM) . TABLE 3.1 '(Cont'd) . Sample Collection and Analysis Haquirements f .: Number of Samples . Type and Frequency. Exposure Pathway - and +
. Sampling and and/or Sample Sample 1.cc.duiw" Collection Frequermy" ~ of Analysis" - . 3. Waterbome
a. Surface' Sampos from 2 locations - Compositessample over 1 Perform gamma isotopic from Table 6.6. montNy period. ,
- analysis' montNy.
Composite for tritium - .
1 sample from analysis quarterly.-
downstream (Indicator) , locaten
1 sam #e from upstream ' *
(control) location (or location not influenced by . the station discharge) l
b. Drinking - Sampos from 2 locations Cv i.pc.;1# sample over 1 Perform gross beta and l from Table 8.6. . monthly period gamma isotopic analysis' I
. montNy. Perform Sr 90. l
1 sample at the loca' m - .
analysis if gross beta of I of the nearest water montNy ceir@ >10 l supply that could be times control. Composite affected by the station '. - for tritium analysis , ~ discharge. -
quarterfy. ,

1 sample from a control location. .
c. Sediment from Samples from 2 locations Sampo twice pgr. year . Perform gamma isotopic-Shoreline . (1 Control and 1 Indicator) (Spring and F#gt 1..J" ^ ^ -
analysis
on each .
j from Table 8.7. " + - - -
; ample. % 9 9
167.0 . mm
. , -i: .- :.. '~ .gik})hfig. .
0+20-9810:18:03 i
- Number TMl Radiological Controls I Departmental Procedure 6610-PLN-4200.01 ameion No. -
nue 12 Offsite Dose Calculation Manuel (ODCM) . 1
.TABl.E s.1 (Cont'd) .
Sample Collection and Analysis Requirements . Number of Samples Sampling and . Type and Frequency Exposure Pathway and Cc8ection Frequencyb of Analysish and/or Sample Sample Le*ws"
4. Ingestion ,
Sample seirdimadGy when Perform gamma isotopio
a. MGir Samples from 4locatioris animals are on pasture; analysis' and 1131 from Table 8.8.
montNy at other times. analysis on each sample, Compostte for Sr40 analysis quarterfy. Sample twice per year Perform gamrna isotopic'
b. Fish Samples from 2 locations and Sc-90 analysis on '
from Table 8.9. _..J 6(Spring and Fash
. edible portions. 'e 1 sample'of - '
recrastionally important ' bottom feeders and 1 ' - sample of recreationally
^
LTpu.wa predators in
the vicinity of the station discharge.
1
. e 1"sempf a of' rscreationally kT@vitent bottom feeders and 1 - , l sample of recreationally l
Lv5 t ra preda+ ors from , l an area not inRuenced l by the ; :'.00 d's.t.eme. , , 1 a , B
. U 4
h
~
j~ .
.ame
168.0
~ , . - + * #4 ,. s.
O I ,,
.$.. t . , o W ,
'04-20-98 10:18:03 ' s . 1
. o ,
Numtier M MM NE TMl Radiological Controls 6610-PLN-4200.01
- Departmental Procedure Rev6ason No.
TWo
12, 4
Offsite Dose Calculation Manual (ODCM) 'l TABLE 3.1 (Cont'd) , Sample Colleoth and Analysis Requirements ,
= .
Egosure Pathway - , and Sampling and Type and Frequency and/or Sample Sample Locadons* Collection Frequency b . of Analysis"
c. Food Samples from 2 locado.is* Sample at time of harvest. Perform gamma lectopic'.
Products
- I-131. and Sr4r) analysis ,
from Table 8.10 (when ' avedeble) on edible portions-
1 sample of green leafy )
l veg=tahlaa or leafy vegetation at a locadon in - - the immediate vicinity of - the stadon. (indicator) e 1 sample'of eame , species or group from a , , l location not influenced by the stadon discharge.
^
W w WW1 N N -- -
--7.._ .W 4 .. ~ __u._ .- . -
m_ .m
u. , . ,.
~ . .
e - t S 4 e
0 e
b . ,
- 1 I
6 A 4 4 9 e
, f 4 I
p e 180.0 . man 6 a
* % 9 4 p , ,
9 4 . ea** , '
= ga ,./ , * .8 e ,
04-20-98 10:18:03 Nwnter - , Nd TMl Radiological Comrois Departmental Procedure 6610-PLN-4200.01 l m numan no. . Offsite Dose Calculation Mariual (ODCM) 12' .
' TABLE 8.3 s. . ..
Detection Capabilities for Eiwiron 8- lysis' _ Lower Limit of Detec on b ' (.(LLb)b . Airbome .
. Particulate Fish Food Sedimert Water or Gas (pC1/kg, Mik . Products ' (pCl/kg, i Analysis ' (pCl/L) '(pCl/m8) wet) (pC!/L) (pCl/kg, wet) dry). ,
fi Gross Beta 4- 0.01 j
'4 H 2000 Mn44 if' 130 , l Fe-59 30- 26d -
Co48, 60 15 , 130 ,. Zn45 30 .i.80 ( Zr-95 30 { 8r-00 .2 . 0.01 10 2 10 Nb-95 15 . 8 0.07 1 60-1131 1 Cs-134 15 0.05 * - 130 .15 80 150 j Co 137 18 0.06 150 18 ' 80 180I. Ba 140 '60 80 , La-140- '15 15 5 e e f 9 6 4 4 4
,4 %
e
'172.0 anse -
4
- - a . 'I :* ' ' . * *1'* * , ,r .- , f. , e ., ,, s , ,' ' ' - ,', ; ', -;_ k.;
j l
1 04-20-98 10:18:03 1 1 l Numew d TMl Radiological Controls
I Departmental Procedure 8810-PLN-4200.01 ;
AsvWon No, j Two Offsite Dose Calculation Manual (ODCM) - 12 _. , f 4 i
- y TA8l.E s.4 .
TMINS REMP Station 8 =t*=- ^'k Particulate and Airl'odine Distance Mes) ArimuttiI') Mao No, Station Code l' 81 4 0.8 ,28 60 E1-2 0.4 95 2 P14 0.6 - 105 . 70
G21 -
1.4 .125' ' 74 M21 1.3 253 3 A3-1 2.6 358 4 H3-1 2.3 159 5 JO a 2.0 19? 04-1 3.5 325 + 61
\, -. .., .
r... ( =: a = :; Q151 13.5 305 8 TABl.E-8.5 . 4 TMINS REMP Station Locatione Direct Radiation (TLD) ' Station Code . Distance (mies) Arimuth (*) MaoNo. . 1 i .
;; 0.4 0' ,
I
, A14 0.3 - 5 9 * . 81 1 0.6 25 10 , f ,26 '11
(. l B1-2 0.4
= . = = ' = '
1 C1-2 0.3 ' 54 ' 13 ) 0.2 74 14 - - (
. D1 1 =- = = = 1 95 2, -
E1-2 E1-4 0.4 0.2 98 16 , j F1-2 0.2 109 17 ., t G1-3 02 129 18 - . H11 0.5 ~ 157 19.
\ a emT- en Q a em -
TE5N n.w w *ww - 0.8 184 21- i
' J1-1 J14 02 *189- 22 l N : 0." 12 ** s^ l
( Ki-4 0-0
' . 0.2 0.0 0.1 208 *aa 235 24 -
28 q L1 1 M11 0.1 , 249 27 N14 0.1 270 - 28' , P11 0.4 - 293c 29 g ' ]' P1-2 i 0.2 . 290 - 30 f.'.-
, .-% ~ ,r u..' ;
174.0. . , g.amm. , . , , ,
" I f.h f) f _
04-20-98 10:18:03 m E TMi Radiological Condole
. UEEE Departmental Procedum 6810-PLN-4200 01 ng. . N No.
Offsite Dose Calculation Manual (ODCM) 12 TABLE 8.5 (Cont'd) l TMINS REMP Station t.costions Direct Radiation (TED)
^ ^
Stadon Code DE (miles) Azimuth M .Magttig, . Q1-2 U.2 318 31 R11 02 . 335 32 ' C21 1.6 . 48 33 H21 1.1 200 34 j
. M21' 1.3 253 3- l A3-1 2.6 358 4 ! , H31 '
2.3 150 5 R3-1 2.6 338, . 35 ,
85-1 4.8 18 36 C51 4.5 42 37 E51' ' 4.6 . 81 38
. F51 4.7 . 107 39 G51 '4.8 131 40 .157 41, .
H5-1 4.1 . 1 Jg 1 4.9 . 182 42 - l H5-1 5.0 200- '43 , . 4.1. . 228 44 ts 1 , M5-1 4.3 249 45 - 4.g 288 , 40
- - N5-1 4.g 285 47 PS-1 5.0 - 318 48 - QS-1. , . RS-1 4.g 338 '49 D6-1 ' ,5.2 85- 50, , ~ E71 8.8 85 , ,51 op.) 8.5' . 308 >
52 9.4 21 53 510 1 G10-1 9.8 127 6 G15-1 14.4 . 124 54-J151 12.8- 180 , 7 015 - 13.5' 305 '8
;;;;; ' ? T "2 -
9 .
. t / .# a. . r.' . ~~
175.0' . nur>
. . r' 4r;ftls ,' .
Y '
04-20-98 10:18:03 m j
.TMI Radiological Controls Jggy Departmental Procedure 6610-PLN-4200.01 nao , Rewhen No. >
j
, Offsite Dose Calculation Manual (ODCM) 12 )
l
. TABLE 8.8 .
TMINS REMP 8tation Locauone-Surts ,
e _
StatiortCode Distance (miles) . Azimuth M MaoNo. i i Ne _. .;. . .. m . E I N gnf w.a -- -- 188 ( J1-2 (R)' J2-;J:) O.5 1,.:: 57,
?? .
( I A3-2.(R) 2.5 355 50 (- Q91 (F) 11 ' , 8.5 10.4 308
* *'4 52 54 ;
G15-2 (F) , 13.6 128 ,82 { G16-3 (F) 14.8 124 63 ) g n
;152 r, 14.- ::
I
~
F15-1 R 12.6 122 - 66 l
-(#H (@)
2f,6 3of 52- . (R) - Raw Water * * (F) = Finished Water
TAB.UE 8.'7 .
TMINS REMP Station Lc ^':-- ?quatic Sedirnent , Station Code Distance {mles) AElmuth M . MaoNo. l
. I \ .
nn ame . l
' '87, . ,0, '
u.a A A13-0.5 vw I
%35"5 1-.
K13 - 0.3 202 69* J21 1.5 182 58 .
&is 0,4 .
O b I 8 . , #
* . i .
W 6 . 9 i4 * .. ,, , , , 17tLO- ,
.i ne. n. ' FT 6'. '
~ 04-20-9810:18:03 . l
. i 1
J J
- 4 Number g~ I-TMl R6 Controls .
i Departmental Procedure . 6610-PLN-4200.01 TNie . Rev6eson No. Offsite Dose Calculation Manual (ODCM) 12 TA B M 4.8 ,
-tmh 4S REMP Station Locations-MHk-Station Code Distance (miles) ' Azlrnuth M. MaoNo.
D2,1 1.1 . 86 , 72 E2-2 1.1 93 - 73 - G2r1 + 1.4 ^125 74 l\ x
.m n .m te .,. 2 5TE yN - - -
P71 3.7 293 77 - K15-2 2.8 208 78 ;
, J TABM 8.9 -
i g 1Mi. ..Mi. .t -.it i
- Cod. an - - ^
INO Downstream of Statfori Discharge , SKG Upstrostn of Station Discharge : . i d j
. 1 . j . 4 4
l
. i g
0
* '..f 6 % s' e - . ~ 177.0 . mar
(=,. "
. ,e a+ l . a * ' ' "/ > , .
h. .
"T
04-20-98 10:18:03 Numtw TMI fladiological Controls d'U,J"EI Departmental Procedure 6610-PLN-4200.01 Time
. . _ _ :. No.
Offske Dose Calculation Manual (ODCM) 12 TABLEi8.10 .
. TNINS RF.MP Station Locationt> Food Products Station Code ? Distance (mies) Azimuth M' Manno. , ~ ' .. on ,e 1 m..
Ek 3 h3 U6 2 117 80
\' ' F1 1 0.5 .. ..a .. ., --- -w \<
g yy
& g .2 % .
9%h.g x , , . 6 ~g 5 e-T
'"W "2
V J2-2 ti **
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ML20217M725

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