ML20137B537

Rev 11 to 6610-PLN-4200.01, Odcm

ML20137B537
Person / Time
Site:	Three Mile Island
Issue date:	03/22/1995
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20137B534	List: ML20137B529 ML20137B537
References
6610-PLN-4200.0, NUDOCS 9703210358
Download: ML20137B537 (192)

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9503088174 03-12-97 07:47:08

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Departmental Procedure 6610-PLN 4200.01

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Offsite Dose Calculation Manual (ODCM) 11 Appucabletty/Soope Calculate offske doses due to radioactive Revonsible Ornos Effective Date effluents for demonstrating compilance with Site Technical Specifications to CFR 20 & 10 CFR 50 - Appendix I 6610 03/24/95

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This document is within QA plan scope X Yes No ,

Safety Reviews Required X Yes No Ust of Effective Pages a

f_agg Revision faQ2 Revision Eggg. Revision fagg. Revision 1.0 11 21.0 11 41.0 11 61.0 11 2.0 11 22.0 11 42.0 11 62.0 11 3.0 11 23.0 11 43.0 11 63.0 11 4.0 11 24.0 11 44.0 11 64.0 11 5.0 11 ~ 25.0 11 45.0 11 65.0 11 6.0 11 26.0 11 48.0 11 66.0 ' 11 7.0 11 27.0 11 47.0 11 67.0 11 8.0 11 28.0 11 48.0 11 68.0 11 9.0 11 29.0 11 49.0 11 69.0 11 10.0 '11 30.0 11 50.0 11 70.0 11 11.0 - 11 31.0 11 51.0 11 71.0 11 12.0 11 32.0 11 52.0 11 72.0 11 13.0 11 33.0 11 53.0 11 73.0 11 14.0 11 .34.0 11- 54.0 11 74.0 11 15.0 11 .35.0 11 55.0- 11 75.0 11 18.0 11 38.0 11 58.0 11 78.0 11 17.0 11 37.0 11 57.0 11 77.0 11 18.0 11 38.0 11 58.0 11 78.0 11 19.0 . 11 39.0 11 .59.0 11 79 40.0 11 60.0 11 .0 20.0 11 p q1 DOCUMENTCONTROL ,

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Offsite Dose Calculation Manual (ODCM) ' 11 4

. Ust of Effective Pages (Cont'd)

! Eggg RevIslon Eggg. Revision Pggg Revision fggg Revision i 81.0 11 121.0 11 161.0 11 82.0 11 122.0 11 162.0 11 83.0 11 123.0 11 163.0 11 84.0 11 124.0 11 164.0 11 85.0 11 125.0 11 165.0 11 86.0 11 128.0 11 166.0 11

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03-12-97 07:47:08' Number gggp TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 m* RMaon No.

Offsite Dose Calculation Manual (ODCM) 11 1

, INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the GPUNC Three Mlle Island Nuclear Station (TMINS) Unt 1 and Unit 2 PDMS Technical Specifications and implements TMI radiological effluent controls. The ODCM contains the controls, tem, and surveRance requirements for liquid and gaseous radiological effluents. In addition, the ODCM describes the methodology 1md paiameters to be used in the-calculation of off-site doces due to radioactive liquid and gaseous effluents. This document also describes the methodology usert for calculation'of the liquid and gaseous effluent monitoring instrumentation alarm / trip set points. Liquid a V Gaseous Radwaste Treatment System configurations are also included.

! The ODCM also is used to define the requirements for the TMINS radiological environmental monitoring program (REMP) and contains a IIst and graphical description of the spectfc sample locations used in the REMP.-

The ODCM is maintained at the Three MIe Island (l'MI) site for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated

~ Into the ODCM to ensure the ODCM represents'the present methodology in all applicable areas. GPUNC inillated changes to the ODCM wil be implemented in accordance with the TMI 1 and TMI-2 PDMS Technical Specifications.

'The ODCM follows the methodology and models suggested by NUREG0133, and Regulatory Guide 1.109, Revision 1 for calculation of off4lte doses due to plant efRuent releases. Simpilfying assumptions have been j . applied in this rnanual where applicable to provide a more workable document for implementation of the Radiological Effluent Controls requirements.

GPUN implements the TMI Radiological Effluent Controls Program and Regulatory Guide 1.21, Revision 1 (Annual Radioactive Efluent Release Report) requirements by use of a computertzed system used to determine TMI effluent releases and to update cumulative effluent doses.

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Offsite Dose Calculation Manual (ODCM) 11 TABLE OF CONTENTS Section Page PARTI TMI-1 RADIOLOGICAL EFFLUENT CONTROLS 1.0 DEFINITIONS '15.0

Table 1-1, Frequency Notations 18.0 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES '

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j 2.1 RadioactNo Effluent Instrumentation 20.0 2.1.1 Radioacttve Uquid Emuent instrumentation 20.0 2.1.2 Radioactive Gaseous Process and Effluent Monitoring instrumentation 23.0 >

Table 2.1 1, Radioactive Liquid Emuent Instrumentation 21.0 l ,

Table 2.1-2, RadioactNo Gaseous Process and Effluent Monitoring instrumentation 24.0 2.2 Radiological ENuent Controls 29.0 2.2.1 Liquid Emuent Controls , 29.0 2.2.2 Gaseous Emuent Controls 32.0 2.2.3 Total Radioactive Effluerd Controls 37.0 3.0 SUHVEIL1.ANCES 38.0 3.1 Radioactive Effluent instrumentation 38.0 3.1.1 RadioactNe Liquid Effluent Instrumentation 38.0 3.1.2 Radioactive Gaseous Process and Effluent Monitorirg Instrumentation 41.0 Table 3.1 1, RadioactNe Liquid Effluent Monitoring instrumentation SurveH!ance Requirements 39.0 Table 3.1-2, Radica_ctNe Gaseous Process and Effluent Monitoring instrumentation 42.0 Surveillance Requirements 3.2 Radiological Effluents 46.0 3.2.1 Uquid Effluents 46.0 3.2.2 Gaseous Effluents 52.0 4.0 wu I

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Offsite Dose Calculation Manual (ODCM) 11 TABLE OF CONTENTS Section Page PARTI TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Table 3.2-1, RadioactNe Liquid Waste Sampling and Analysis Program 48.0 Table 3.2-2, RadioactNo Gaseous Waste Sampling and Analysis Program 54.0 3.2.3 Total RadioactNe Effluents 58.0 4.0 PART I REFEREN'CES .

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Offsite Dose Calculation Manual (ODCM) 11 1

TABLE OF CONTENTS (Cont'd) 3 PART11 TMl-2 RADIOLOGICAL EFFLUENT CONTROLS j Section Page l 1

1.0 DEFINITIONS 61.0 Table 1.1, Frequency Notation 63.0 2.0 RADIOLOGICAL EFFLUENT REQUIREMENTS 66.0 2.1 Radioactive Discharges 68.0 2.1.1 Liquid Emuents 68.0 2.1.2 Gaseous Emuents 68.0 2.2 Radioactive Gaseous Est, -ant Monitoring instrumentation 70.0 l Table 2.2-1, Radioactive Gaseous Emuent Monitoring instrumentation 71.0 i .

3.0 - MONITORING REQUIREMENTS 72.0 3.1 Radioactive Discharges 72.0 3.1.1 Liquid Emuents 72.0 3.1.2 Gaseous Emuents 72.0 3.2 Radioactive Gaseous Emuent Monitoring Instrumentation 74.0 l Table 3.1 1, Radioactive Liquid Waste Sampling and Analysis 75.0 Table 3.1-2, Radioactive Gaseous Waste Sampling and Analysis 78.0 i .

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TABLE OF CONTENTS (Cont'd)

PART 11 TMI 2 RADIOLOGICAL EFFLUENT CONTROLS ,

1

, Section Page f

4.0 DESIGN FEA11JRES 79.0 i 4.1 SITE -

79.0 4.1.1 Exclusion Area 79.0 4.L2 Low Population Zone 79.0

4.1.3 Site Boundary for Gaseous Emuents 79.0

l. , 4.1.4 Site Boundary for Uquid Emuents ,

79.0 5.0 PART11 REFERENCES 80.0 i

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Offsite Dose Calculation Manual (ODCM) 11

] TABLE OF CONTENTd j Section Page FART 111 EFFLUENT DATA AND CALCULATI NAL METHODOLOGIES 1.0 UCulD EFFLUENT MONITORS 82.0 1.1 TMl-1 and TMI-2 Uquid Radiation Monitor Set Points 82.0 1.2 TMI Uquid Release Points and Uquid Radiation Monitor Data 83.0 l 1.3 Control of Liquid Releases 85.0 2.0 UQUID EFFLUENT DOSE ASSESSMENT 90.0 i .

2.1 ' Uquid Emuents - 10 CFR 50 Appendix 1 90.0 1

2.2 TMi-1 Liquid Radwaste System Dose Calcs Once per Month 92.0 2.3 Alternative Dose Calculational Methodology 93.0' 3.0 UQUID EFFLUENT WASTE TREATMENT SYSTEM 98.0 3.1 TM1-1 Uquid Effluent Waste Treatment System 98.0 4

3.2 Operability of TMI-1 Uquid Efiluent Waste Treatment System 99.0 3.3 TMI-2 Uquid Emuent Waste Treatment System 99.0 4.0 GASEOUS EFFLUENT MONITORS 102.0 4.1 102.0 T.MI-1 Noble G'as Monitor Set Points 4.2 TMI-1 Particulate and Radiolodine. Monitor Set Pcints . 104.0 4.3 TMI-2 Gaseous Radiation Monitor Set Points 105.0 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 106.0 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 108.0 4.8 Control of Gaseous Effluent Releases 109.0 J

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Offsite Dose Calculation Manual (ODCM) 11 TABLE OF CONTENTS Section Page PARTlli EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES -

5.0 - GASEOUS EFFLUENT DOSE ASSESSMENT 122.0

! 5.1 Gaseous Effluents - Dose Rate Limits 122.0 5.1.1 Noble Gases 122.0 5.1.1.1 Total Body 122.0 5.1.1.2 Skin 123.0 5.1.2 lodines and Particulates 124.0 i

5.2 Gaseous Effluents .10 CFR 50 Appendix 1 125.0 i . 1 1 5.2.1 Noble Gases 125.0 ,

5.2.21 lodines and Particulates ' 126.0 J

5.3 Gaseous Radioactive System Dose Calculations Once per Month 128.0 1

5.4 Alternative Dose Calculational Methodologies 129.0 l, 6.0 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM 151.0 t

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6.1 Description of the TMI-1 Gaseous Radwaste Treatment System 151.0 l 6.2 Operability of the TM1-1 Gaseous Radwaste Treatment System 151.0 J

i 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 153.0 l 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 154.0 8.1 Monitoring Program Requirements 154.0 1

,8.2 Land Use Census 156.0

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s 8.3 Intertaboratory Comparison Program 158.0 i

9.0 PART 111 REFERENCES '175.0 4

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TABE OF CONTENTS (Cont'd)

PART lli EFFLUENT DATA ANQ CALCULATIONAL' METHODOLOGIES Section ,

Page ,

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TABLES .

j Table 1.1 TM1-1 Liquid Release Point and Uquid Radiation Monitor Data. 86.0 1 Table 1.'2 TMI-2 Sump Capacities 87.0.

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Table 2.1 Uquid Dose Conversion Factors (DCF)

DF6- 94.0 Table 2.2 Bloaccumulation Factdrs, BFi 97.0 1 .

Table 4.1 TMI-1 Gaseous Release Point & Gaseous Radiation Monitor Data 110.0 i Table 4.2 TMl-2 Gaseous Release Point & Gaseous Radiation Monitor Data 112.0 ,

1 i Table 4.3 Dose Factors for Noble Gases and Daughters- 113.0 2

Table 4.4 Atmospheric Dispersion Factors for Three M8e Island - Station Vent ,

114.0 Table 4.5. Atmospheric Dispersion Factors for Three MIe Island - Ground Release 115.0

. Table 4.6 Dose Parameters for Radiolodines and Radioactive Particulate, Gaseous, Effluents 116.0 i

i Table 5.2.1 Pathway Dose Factors, Ri - Infant, Inhalation 130.0 l Table 5.2.2 Pathway Dose Factors, R g'- ChBd, Inhalation 131.0 Table 5.2.3 Pathway Dose Factors, Rs - Teen, Inhalation 132.0 ,

! Table 5.2.4 Pathway Dose Factors, Ri - Adult, inhalation 133.0 Table 5.3.1 Pathway Dose Factors, Ri - All ADe Groups, Ground Plane 134.0 Table 5 1 Pathway Dose Factors, Ri -Infant,' Grass-Cow-Milk 135.0 l

Table 5.4.2 Pathway Dose. Factors, Ri - Chud, Grass-Cow-Milk 136.0

. l Table 5.4.3 Pathway Dose Factors, Ri - Teen, Grass-Cow-Milk 137.0 Table 5.4.4 Pathway Dose Factors, Ri - Adult, Grass-Cow-Mik 138.0 Table 5.5.1 Pathway Dose Factors, R ia Infant, Grass. Goat-Milk 139.0 l

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Title Revleion ref Offsite Dose Calculation Manual (O'DCM) 11 l

l TABLE OF CONTENTS (Cont'd)

PART111 EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section , Page TABLES Table 5.5.2 Pathway Dose Factors, R, ChRd, Grass-Goat-Milk 140.0 l Table 5.5.3 _ Pathway Dose Factors, R i - Teen, Grass-Goat-Mik 141.0 ,

Table 5.5.4 Pathway Dose Factors, Ri . Adult, Grass-Goat-Mik 142.0 Table 5.6.1 . Pathway Dose Factors, R, - Infant, Grass-Cow-Meat 143.0 Table 5.6.2 Pathway Dose Factors, % - Chid, Grass-Cow-Meat 144.0 Table 5.6.3 Pathway Dose Factors, Ri - Teen; Grass-Cow-Meat 145.0 i

. Table 5.6.4 Pathway Dose Factors, Ri - Adult, Grass. Cow-Meat 146.0 l

Table 5.7.1 Pathway Dose Factors, Ri -Infant, Vegetation ,

147.0 Table 5.7.2 Pathway Dose Factors, Ri - Child, Vegetation ,

148.0 Table 5.7.3 ' Pathway Dose Factors, Ri - Teen, Vegetation -

149.0 Table 5.7.4 Pathway Dose Factors, Ri - Adult, Vegetation 150.0 Table 8.1 Sample Collection and Analysis Requirements 159.0 Table 8.2 Reporting Levels for RadioactMty Concentrations in Environmental Samples 164.0 Table 8.3 Detection Capabiltles for Environmental Sample Analysis 165.0 Table 8.4 TMINS REMP Station Locations - Air Particulate and Air lodine 167.0 Tabie 8.5 TMINS REMP Station Locations - Direct Radiation (TLb) 167.0 Table 8.8 . TMINS REMP Station Locations - Surface Water 169.0 Table 8.7 , TM!NS REMP Station Locations.- Aquatic Sediment 169.0 Table 8.8 *n41NS REMP Station Locations - Milk 170.0 Table 8.9 TMINS REMP Station LocatJons - Fish 170.0 Table 8.10 TMINS REMP Station !.ocations - Food Products 171.0 11.0 nm.

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Offsite Dose Calculation Manual (ODCM) 11

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, TABLE OF CONTENTS (Cont'd)

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P A R T 111 EFFLUENT DATA AND CALCUl.ATIONAL METHODOLOGIES Section Page TABLES .

MAP 8.1 Three Mile Island Nuclear Station Locations of Radiological Environmental 172.0 Monitoring Program Stations within 1 MRe of the Site MAP 8.2 Three MNe Island Nuclear Station Locations of Radiological Environrnental 173.0 Monitoring Program Stations within 5 mies of the Sta i . .

j MAP 8.3 Three MRe Island Nuclear Station Locations of Radiological Environmental 174.0 Monitoring Program Stations Greater than 5 mies from the Site

FIGURES 4

i Figure 1.1 TMI 1 Liquid Effluent Pafhways 88.0 Figure 1.2 TMI-2 Uquid Effluent Pathways 89.0 i Figure 3.1 TM11 Liquid Radwaste 100.0 Figure 3.2 TMl-1 Liquid Waste Evaporators 101.0 Figure 4.1 TMI 1 Gaseous EfHuent Pathways 111.0 Figure 4.2 TMI-1 Auxiliary & Fuel Handling Buildings EfRuent' Pathways '.118.0 Figure 4.3 TMI-1 Roactor B'ulding EfRuont Pathway 119.0 Figure 4.4 TMI-1 Condenser Offgas Effluent Pathway 120.0 Figure 4.5 TMI-2 Gaseous Effluent Futration System / Pathways 121.0 Figure 6.1 Wasta Gas System . 152.0 4

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i Offsite Dose Calculation Manual (ODCM) 11 I

TABLE OF CONTENTS -(Cont'd) ,

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PART IV REPORTING REQUIREMENTS i Section - Page 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 178.0 l

2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 179'.0

! 3.0 PART IV REFERENCES -

181.0 l i

AP'PENDICES A. ' Pathway Dose Rate Parameter (P) E1-1 l 1

i B. Inhalation Pathway Dose Factor (R) E2-1 -

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'C' Ground Plane Pathway Dose Factor (R)i E3-1 l 1

l D. Grass-Cow-Muk Pathway Dose Factor (R) E4.-1

! E. Cow-Meat Pathway Dose Factor (R) E5-1 F. Vegetation Pathway Dose Factor (R) E6-1

. APPEND!X A - F REFERENCES E7-1 i

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Nmber gggp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 noe nwwon wo.

Offsite Dose Calculation Manual (ODCM) 11 1.0 , DEFINITIONS The following terms are defined for uniform interpretation of these controls and surveillances.

1.1 Reactor Operating Coi 0tions 1.1.1 Cold Shutdown The reactor is trt the' cold shutdown condition when it is subcritical by at least one percent, i detta k/k and Tavg la no more than 200* F. Pressure is defined by Technical Specification 3.1.2.

4 1.1.2 Hot Shutdown ,

The reactor is in the hot shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is at or greater than 525* F.

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

1.1.4 Hot Standby s The reactor is in the hot standby condition when all of the following conditions exist:

a. Tavg is greater than 525* F

b. - The reactor is critical -

c. Indicated neutron power on the power range channels is less than two

. percent of rated power. . Rated power is defined in Technical Specification Definition 1.1.

1.1.5 ' Power Operation

l .

The reactor is in a power Op.aiing 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 i

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 kgk and the coolant temperature at j the decay heat removal pump suction is no more than 140 F. Pressure is defined by Technical Spectication 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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03-12-97 07:47:08 Numbw gggy TMI Radiological Contrds Departmental Procedure 6610-PLN-4200.01

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. 1.1.7' Refueling Operation ~

An operation invoMng a change'in' core geometry by manipulation of fuel or contrd rods when the reactor vessel head is removed.

i 1.1.8 Refueling Interval Time between normal refuelings of the reactor.. This is defined as once per 24 months. l 1.1.9 Startup i

The reactor shal be considered in the startup mode when the shutdown margin is reduced wm h WW d @g MW.

l 1.1.10 Tave -

1

. Tave is defined as the arthmetic 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 1.1.11 Heatup .'Cooldown Mode The heatup-cooldown mode is the range of reactor coolant temperature greater than 200* F and less than 525* F.

1.2 Operable -

A system, subsystem, train, component or oevice shal be OPERABLE or have OPERABILi1Y when it is capable of performing its specified function (s) and when al necessary attendant instrumentation, controis, electrical power, cooling or seal water, lubrication or other auxEiary equipment.that are required for the system, subsystem, train, component. or device to perform its function (s) are also capable of performing their related support function (s).

1.3 Instrument Channel An instrument channel is the combination of sensor, wires, arriplifiers, 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 Survellance 1.4.1 Channel Test A CHANNEL TEST s' hall be the injection of a simulated signal into the channel as close to the sensor as practical to verify OPERABluTY, including alarm and/or trip functions.

1.4.2 Channel Check t

A CHANNEL CHECK'shall be the qualitative assessment of channel behavior during operation by obeervation. This determination shau include, where possible, comparison of 16.0 nm.

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03-13-97 07:47:08 .

Number Ng"UI TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 nae , FWWWoq No.

Offsite. Dose Calculation Manual (ODCM) 11 the channel indication and/or status with other indications and/or status dertved from.

Independent instrumentation channels measuring the same parameter.

. 1.4.3 Source Check A SOURCE CHECK shall be the quaikative assessment of channel response when the

, channel sensor is exposed to a radioactive source.

1.4.4 Channel Calibration An instrument CHANNEL CAUBRATION is a test, and adjustment (If necessary), to establish that the' channel output responds wth acceptable range and accuracy to known values of

, the parameter which the channel measures or an accurate simulation of these values.

Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip

~

1 and shall be deemed to include the channel test.

1.5 Dose Equivalent 1-131 2

The DOSE EQUIVALENT l-131 shall be that concentration of I 131 (microcurle/ gram) which alone would produce the same thyroid does as the quantity and isotopic mixture of I-131,1-132, l-133, 1-134, and 1-135 actuaBy 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 Regulttory Guide 1.109, Revision 1, October 1977.]

1.6 Offsite Dose Calculation Manual (ODCM) i The OFFSITE DOSE CALCUl.ATION MANUAL (ODCM) c6ntains the methodology and parameters i used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the '

calculation of gaseous and liquid ofRuent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Erwironmental Monitoring Program. The ODCM also contains (1) the Radiological Effluen't Controls, (2) the Radiological Erwihiw& ; Monitoring Program and (3) deceriptions of the information that should be included in the Annual Radiological Erwironmental Operating and Annual

. Radioactive Effluent Release Reporta .

1.7 Gaseous Radweste Treatment .

The GASEOUS RADWASTE TREATMENT SYSTEM la the system designed and installed to reduce radioactive gaseous ofHuent 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 environrnent.

1.8 VentRation Exhaust Treatment System A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiolodine or radioactive rnaterial in particulate form in effluent by passing ventilation or verit exhaust gases through charcoal absorbers and/or HEPA ftters for the purpose of removing lodine or particulates from the gaseous exhaust system prior to the release to the environment.

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

t 17.0 nm.

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03-12,97 07:47:08

, Number luOlG8r i Radid gi ai contros Departmental Procedure .

6610-PLN-4200.01

- noe n.vwon so.

Offsite Dose Calculation Manual (ODCM) 11 1.9 Purge - Purging PURGE or PURGING la the controlled process of discharging air or gas from a confinement to

', maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that replaceme'n t air or gas is required to purify the confinement.

( l j 1.10 Venting -

! VENTING is the controlled process of discharging air as gas'from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in s'uch a manner that )

4 i replacement air or gas is not provided. Vent used in system name does not imply a VENTING l process. ,

1 l

1.11 Member (s) of the Public l

\

MEMBER (S) OF THE PUBUC shall include aR persons who are net -MnaRy as sociated with I

- the plant. This category does not include employees of the GPU System, GPU cont. actors or

~

vendors. Also excluded from this category are persons who eMer the site to servic a equipment or to make delivertes.

1.12 Site Boundary ,

! The SITE BOUNDARY 14 the boundary line forming the base for the limits on the release of gaseous effluents as defined in Section 2.1.22 of the TMI-1 FSAR and shown on Figure 2.1-3 of the TMi-1  ;

l FSAR. This boundary line includes portions of the Susquehanna River surface between the east  !

! bank of the river and Three MIe Island and between Three MIe Island and Shelley.lsland.

1.13 Frequency Notation I

' The FREQUENCY' NOTATION specified for the performance of Survellance Requirements shall I correspond to the intervals defined in Table 1-1. A!I Surveillance Requirements shal be performed 1 within the specified time interval with a maximum allowable extension not to exceed 25% of the surveRiance interval. The 25% extension applies to aC frequency intervals with the exception of "F.*

No extension is allowed for intervals designated "F."

, Table 1-1 Frequency Notation Notation Frequency S ,, Shiftty (once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

D Daly (once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

.W Weekly (once per 7 days)

M MontNy (once per 31 days) 18.0 ma

03-12-97 07:47:08 '

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. Number i Radid gi e contres GUCl88r Departmental Procedure 6610-PLN-4200.01

' noe w on No.

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

S/A Seml.AnnuaBy (once per 184 days)

R Refueling Interval (once per 24 months)

P S/U Prior to each reactor startup, if not done durin'g the previous 7 days I P Completed prior to each~ release N/A (NA) Not applicable l t

E Once per 18 months F Not to exceed 24 rnontha Bases I Section 1.13 establishes the limt for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal survellance interval to faelltate surveillance

, scheduling and consideration of- plant operating condttons that may not be sukable for conducting the survellance; e.g., transient condtlons or other ongoing surveillance or maintenance actMties, it also provides flexibitty to accommodate the length of a fuel cycle for surveEances that are specified to be performed at least once each REFUEUNG INTERVAL lt is not intended that this provision be used repeatedly as a convenience to extend survellance irtervals beyond that specified for staveBlances that are not performed once each REFUEUNG .lNTERVAL Ukewise, R is not the intent that REFUEUNG INTERVAL surveiBances be performed during power operation unless R is consistent wth safe plant operation. The Ilmtation of Section 1.13 is based on engineering judgement and the recognition that the moet probable result of any particular survoltance being pedormed is the verification of conformance with the Surveniance Requirements. This provision is sufficient to ensure that the reliablity ensured through surve81ance actMtles is not significantly degraded beyond that obtained from the specified surveulance Irterval.

i l

1 19.0 mm.

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'EI Departmental Procedure 6610-PLN-4200.01 l nWo IWmon No.

• j

~

11  ;

Offsite Dose Calculation Manual (ODCM)

, l 2.0 CONTROLS AND BASES 2.1 Radioactive EfAuent instrumentation . .

2.1.1 Radioactive Liquid EfRuent instrumentation CONTROL: l The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.1 1 shall l be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Control 2.2.1.1 are not exceeded The alarm / trip setpoints of these channels shall be determined in acco.-d ce with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times

• ACTION:

a. With a radioactive liquid of6uent monitoring instmmentation channel alarm / trip .

setpoint less conservative than required by the above control, immediately suspend l the release of radioactive liquid affluent monitored by the affected channel or .

declare the channel inoperable. . .

1 l

b. With less than the minimum number of radioactive liquid effluent monitoring Instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-1. Exert i best efforts to retum the instrumentation to OPERABLE status within 30 days and, if l unsuccessful, explain in the next Annual Effluent Release Report why the inoperabilty was not corrected in a timely manner.

• For FT-84, ar.d RM-L8, operabuity is not required when discharges are positively controlled through the closure of WDL-V257.

• For RM-L12 and associated IWTS/lWFS flow interfocics, operabilty is not required when discharges are positively controlled through the closure of .

IW-V72,75 and IW-V280,281.

• For FT-146, operablity is not required when discharges are positively contro5ed through the closure of WDL V257. IW-V72. 75 and IW-V280, 281.

. BASES

. The radioactive liquid efRuent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluent during actual or potential releases. The alarm / trip setpoints for these Instruments shall be calculated in accordance with NRC approved rnethods~ in the ODCM to ensure that the alarm / trip will occur prior to exceeding ten times the effluent concentrations of 10 CFR Part 20.

20.0 mw

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Numter gggp TMI Radiological Controis Departmental Procedure 6610-PLN-4200.01 nu. PWmm No.

Offsite Dose Calculation Manual (ODCM) 11 Table 2.1-1 l Radioactive Uquid Effluent instrumentation Minimum Channels Instrument Operable ACTION

]

1. Gross.RadioactMty Monitors

, Providing Automatic Termination of Release

a. Unit 1 Uquid Radweste Effluent 1 18 Une (RM-L6) l b. IWTS/lWFS Discharge Une (RM-L12) 1 20

2. Flow Rate Measurement Devices .

a. Unit 1 Liquid Radweste' Emu'ont 1 21

, Uno (FT-84) b, Station Effluent Discharge' 1 21 j (FT-146)

Table Notation ACTION 18 With the number of channels OPERABW less than required by the Minimum Channels OPERABLE

+

. requirement, effluent releases may continue, provided that prior to initiating a release:

,1. At least two independent samples are analyzed in.accordance with Surveillances 3.2.1.1.1 and 3.2.1.1.2 and;

2. dt least two technically qualified members of the Unit staff independently verify the release rate calculations and vertfy the discharge valve lineup.

3. Director Operations and Maintenance TMl shall approve' each release.

5 Otherwise, suspend release of radlogetive effluents via this pathway.

ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABE requirement, effluent releases via this pathway rnay commence or continue provided that grab' samples are collected and analyzed for gross radioactMty (beta or gamma) at a limit of detection of at least 1x10-7 microcuries/ml, prior to initiating a release and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during release.

h 21.0 mu

/

03-12-97 07:47:08 Number i TMl Radiological Controls EE Departmental Procedure 6610-PLN-4200.01

1. .  ;

4 Offsite Dose Calculation Manual (ODCM) 11 Table 2.11 (Cont'd) i 1

j ACTION 21 Wrth the number of channels OPERABLE less than required by the Minimurn Channels i OPERABLE requirement, radioactive ofRuent releases via this pathway may continue, provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump ,

curves may be used to estimate Sow.

.i

! 1 1

)

i e

. t 4

F i

22.0 nrw

03-12-97 07:47:08 ,

Number i

Nuolear '" * * * '*

Departmental Procedure - 6610-PLN-4200.01 rm. a won te,.

Offsite Dose Calculation Manual (ODCM) 11 j

l 2.1.2 RadioactNo Gaseous Process and Effluent Monitoring Instrumentation l CONTROL:

I The radloactNe' gaseous process and effluent monitoring instrumentation channels shown in

Table 2.12 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 setpohts of these channels shall be

determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPUCABluTY: As shown in Table 2.1-2. ,

' ~

ACTION:

1 a. With a radioactNo gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservatNe than required by the above control, irnmediately suspend the release of radioactive affluent monitored by the affected i channel or declare the channel inoperable.

b.' Wittk less than the minimum number'of radioactNo gaseous process or effluent

. irreiteiir.g instrumentation channels OPERABLE, take the ACTION shown in Table 2.12. Exert best efforts to retum the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why ~

, the inoperability was not corrected in a time 8y manner.

BASES The radioactNo gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactNe materials in gaseous effluent during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved rnethods in the ODCM to provide reasonable essurance that the annual

. releases are wthin the limits specified in 10 CFR 20.1301.

The low range condenser offgas noble gas actMty monitors also provide data for determination of steam generator primary to secondary leakage rate. Channel operabatty requirements are based on an ASLB Order No. LBP-84-47 dated October 31,1984, and as cited in 20 NRC 1405 (1964).

l

'O 6

23.0 nm.

' o taa Table 2.1-2 8610-PLN-420041 Revision 11 h

Radioactive Gaseous Process and Efluent Monitoring Instrumentation j

o MINIMUM " ' '

CHANNELS

OPERABLE APPdCABluTY ACTION INSTRUMENT < >

1. Wese Gas Holdup System

• 25 rn. Noble Gas Activity Monitor (RM-A7) - 1-

~

EHiuent System Flow Rate Measwing Devce (FT-123) 1

• ' 26 b.

2. Waste Gas Holdup System Explosive Gas Monitoring System

• • 30

a. Hydrogen Monitor 2

• • 30

b. Oxygen Monitor 2

3. Cudair cmis Purge, Monitoring System

a. Noble Gas ActMty Montor (RM-A9) 1 # 27.

b. lodine Sampler (RM-A9) 1 # 31

c. PartictJate Sampler (RM-A9) 1 # 31

d. Efiluent System Flow Rate Measuring Device (FR-148) 1 '# -

26 Sampler Flow Rate Monitor - 1 # 26

e. .

i 1

6 24.0 un. i 7

e l

OI Table 2.1 (Cont'd) 8610-PLN-4200.01 y Revision 11

,Radioact}ve Gaseous Process and Emuent Monitoring Instrumentation j o

- MINIMUM

CHANNELS

OPERABLE APPUCABlUTY . ACTION INSTRUMENT < >

6 , ()

4. Condenser Vent System 20I ## 32

a. tow Range Noble Gas ActMty Monitor (RM-A5lo and ,'

Sultable. Equivalent)

For one of the channels, an operable channel may be defined for purposes of this control and 3.1.2.1 only as a sutable equivalent NOTE (1):

monRoring system capable of being placed in service within one hour. A sumable equivalent system shen include instrumentation wth comparable sensitMty and response time to the RM-A5im mon'toring channel. When the equivalent monitoring system is in service,

' indication wil be conhnuously avalable to the operator, either through indication and alarm in the Control Room or through communication

• wth a designated individual conunuously observing local ind' cation.

O e

e

+

25.0 mm

$ t Table 2.1-2 (Cortd) e610-PUM200l]1 [

Revleion 11 0

Radioactue Gaseous Process and Emuent Monitoring instrumentation l MINIMUM CHANNELS '

INSTRUMENT OPERABLE APPUCASluTY ACTION a )

' 4 0

5. Ausdliary and Fuel Handling Bu5 ding Ventiation System

a. Noble Gas Activity Monitor (RM-AB) or (RM-A4 and

• 1 27 RM-AS) ,

• 31

b. - lodine Samples (RM-AB) or (RM-A4 and RM-AS) 1

• 31

c. Particu' late Sampler (RM-A8) or (RM-A4 arid RM-A6) 1

• 26

d. Emuent System flow Rate Measuring Dences (FR-149 1 and FR-150)

• 26 1

e. Sam'pler Flow Rate Monitor , .

6. Fuel Handling Buildog ESF Air Treatment System _

a. Noble Gas Activity Monitor (RM-A14 or Sultable 1

• • • • 27,33 Equivalent) i M **** 31,33 i

b. lodine Cartridge N/A 31,33

~

c. Particulate Filter N/AM .

Ef8uent System Flow (UR-1104A/B) 1

• • • • 26,33 -

d.

• • • • 26,33

e. Sampler Flow Rate Montor 1 .

NOTE 2- No instrumentation channel is provided. However, for detemining operabilf, the'equ!pment immed must be Installed and functional or the ACTION applies.

'26 0 vn.

._._._______m_m . _ . . _ - . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

- _ ._. - - - . _ _ _ - . .=. .~ - _

l 03-12-97 07:47:08 i Number l ggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01

, l no. a.vwon so.

Offsite Dose Calculation Manual (ODCM) 11' f

Table 2.1-2 (Cont'd)

Table Notation At all times.

During waste gas holdup system operation.

Operability is not required when discharges are positively controlled through the closure of

WDG-V47 and where RM-A8 (or RM-A4 and RM-A6), FF-149, and FT 150 are operable.

• • • • During Fuel Handling Building ESF Air Treatment System Operation.

1. At all times during containment purging.

1. 1. At all times when condenser vacuum is established.

4 ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels 4 OPERABLE requirement, the contents of the tank may be released to the environment i provided that prior to initiating the release: i

.> 1. 'At least two independent samples of the tank's coittents are analyzed in accordance ,

with Table 3.2-2, item A, and I

l

2. At least two technically qualified members of the Unit staff Independently verify the release rate calculations and verify the discharge valve lineup. N

3. The Director Opetutions & Maintenance TM1, shall approve each release.

Otherwise, suspend release of radloactive effluent.via this pathway.

ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels ,

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

ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels ,

OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the initial samples are analyzed for gross activity (gamma scan) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the channel has been declared inoperable. If l RM-A9 is declared inoperable, see also Technical Specification 3.5.1, Table 3-5.1, Itera 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 collected and analyzed for the inoperable gas ,

channel (s): i (a) at least 'once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations.-

(b) at least orice per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations (e.g. Feed and Bleed). j 27,0 u n,

d i

03-12-97 07:47:08 Number gggy TMI Radiological Controls Departmental Procedurc 6610-PLN-4200.01 l Tsue Rowwon No. 1 l

i OffsMe Dese Calculation Manual (ODCM) 11

' Table 2.12 (Cont'd) 4

2. . If the inoperable gas channel (s) is not restored to service within 14 days, a special report shall be submitted to the Regional Administrator of the NRC Reglon 1 Office l and a copy to the Director, Office of Inspection and Enforcement within 30 days of  !

declaring the channel (s) Inoperable.~ The report shall describe'(a) the cause of the ,

monitor inoperablitty (b)' action being taken to restore the instrument to service, j

, and (c) adlon to be taken to prevent recurrence. i ACTION 31 With the number of channels OPERABLE les s than requirad by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue

provided that within four hours after the channel has been declared inoperable, samples are continuoudy collected with auxiliary sampling equipment.

ACTION 32 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days, provided that one OPERABLE channel remains in service or is placed in service within.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. After 24 days, or if one OPERABE channel does not' remain in service or is not placed In service within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the oroviolons of Technical Specification 3.0.1 apply, as if this Control were a Tech Spec Umsting Condition for Operation.

1 ACTION 33 With the number of channels OPERABLE less then required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel to OPERABLE status within 7 days, or. prepare and submit a special report within 30 days oedining the action (s) taken, the cause of the inoperability, and plans and schedule for restoring the system to OPERABLE status.

4 0

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4 1 03-12-97 07:47:08 Number gggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tine Revlelon No.

Offsite Dose Calculation Manual (ODCM) 11 2.2 Radioactive Effluent Controls

! 2.2.1 Uquid Effluent Controls

'; 2.2.1.1 Uguld Effluent Concentration i

CONTROL:

l .  !

The concentration of radioactNo material released at anytime from the unit to unrestricted areas shall be lirnited to ten tim'es the concentrations specified in 10 CFR Part .

20.1001-20.2401, Appendix B Table 2 Column 2 for radionuclides other than dissolved or For dissolved or entrained noble gases, the' concentration shall be entrained limited to 3 xnoble to .uCly/cc total actMty.

APPUCABluTY: At all times ACTION: ,

I With the concentration of radioactive material released from the unit to unrestricted areas exceeding the abovs limits, immediately restore concentrations wkhin the above limits.

BASES l

This cortrol la provided to ensure that the concentration of radioactive materials released in liquid waste e ' ffluent from the unit to unrestricted areas wll be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B. Table 2. This limp.ation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures with (1) the Sectiori ll.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBUC and */) the limits of 10 CFR Part 20.1301 to the population. The concentration limit for noble er,ses is based upen the assumption the Xe-135 is the controlling radioisotope and its MPC in alt (submersion) was converted to an equivalent enneentration in water using the methods dcscribed in intomational Commission on Radiological Protection (ICRP)' Publication 2.

2.2.1.2 Uquid Effluent Dose CONTROL The dose or dose commitment to a MEMBER OF THE PUBUC from radioactive materials in liquid effluents released from the unt to the SITE BOUNDARY shaB be limp.ed:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.

1

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 mrem to any organ.

APPUCABlu1Y: At all times 29.0 ,

mu

03-12-97 07:47:08 Number m Radid gi ai Contras 4

$UClear Departmental Procedure 6610-PLN-4200.01 i nse armo, No. l l

l Offsite Dose Calculation Manual (OQCM) 11 l ACTION:

)

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region i .I I

4 Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the lim!t(s) and defines the corrective actions to be taken to reduce the j i releases of radioactfve materials in liquid effluents during the remainder of the

- current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during l these four calendar quarters is within 3 mrem to the total body and 10 mrem to any ,

, organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking I water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act. - ,

BASES -

This control and associated action is provided to implement the requirements of Sections ll.A Ill.A, and IV.A of Appendk I,10 CFR Part 50.' The Control implements the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents wE be kept "as low as is

{ reasonably achievable". Also, for fresh water sites with drinidng water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of

. the facility wW not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 10 CFR 20. The dose calculations in the ODCM implement j The requirements in Section Ill.A. of Appendix l that conformance with the guides of

Appendk I is to 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 subetantially undersetimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.100, " Calculation of Annual Dosee to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating ,

Compliance with 10 CFR Part 50, Appendix 1," Revision 1. October.1977, and Regulatory l Guide 1.113,

• Estimating Aquatici Dispersion'of Effluents from Accidental and Routine l Reactor Releases for the Purpose of implementing Appendk I," April,1977. NUREG-0133 l' j . provides methods for dese calculations consistent with Regulatory Guides 1.109 and 1.113.

2.2.1.3 Uquid Radwaste Treatment System - -

CONTROL.i The appropdate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid erfluent 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 4

month.

APPUCABIUTY: At all times i

30.0 nm.

l 03-13-97 07:47:08 l Numtw I TMI Radiological Controls -

EMI Departmental Procedure 6610-PLN-4200.01 nue, mn no.

l Offsite Dose Calculation Manual (ODCM) 11 ACTION: .

a. With rad!oactive liquid waste being discharged without treatment and in excess of the above litpits, prepare and submit to the NRC Region i Administrator within' 30 days, a Special Report which includes the following InforrDation:

1. Explanation of why liquid radweste 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 of radioactive materials in liquid .

eff'.uents wW be kept as low as is reasonably achievable. This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendlx A to 10 CFR Part 50 and the design objective given in Section ll.D of Appendix ! te ?.3

• C.5R Part 50. The intent of Section II.D. is to reduce effluents to at le.1,.7, is reasonably achievable in a cost effective manner'. This control satisfies this intent by establishing a dose limit which is a small fractbn (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 quantty of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrairied nobio gases.

a. Outside temporary tank APPUCABluTY: At all tirnes.

ACTION: -

a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

31.0 mw

03-12-97 07:47:08 Number d TM1 Radiological Controls 1 EE Departmental Procedure 6610-PLN-4200.01 Title Revision No.

]

Offsite Dose Calculation Manual (ODCM). 11 ,

BASES

$ Restricting the quantity of radioactive material contained in the specified tanks i

provides assurance that in the~ event of an uncontrolled release of the tanks' contents, the resulting concentratiorn would be %ss 6an the limits of 10 CFR Part i 20.1001-20-20.2401, Appendix B, Table 2, Column 2, at the nearest potable water )

supply and the nearest surface water supply in an unrestricted area.

2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL:

The dose rate due to radioactive materials released in gaseous affluent 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 mrom/yr to the skin, and

b. 'For 1-131,1-133, tritium and a5 radionuclides in particdate form with half lives greater than 8 days: less than or equal to 1500 mrem /yr_ to any organ.

APPUCABluTY: At au times.

i ACTION:

With the release rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above limit (s).

, BASES i

The control provides reasonable assurance that the annual dose at the SITE BOUNDARY. l from gaseous affluent from all units on the site wiu be within the annual dose limits of 10 '

CFR Part 20 for unrestricted areas whfe providing sufficient operational flexibility in

, establishing effluent monitor setpoints, These gaseous release rates provide reasonable

assurance that radioactive material discharged in gaseous o!!Iuent wil not result in the exposure of a MEMBER OF THE PUBUC in an unrestricted area, either within or outskie the SITE BOUNDARY, to annual average concentrations exceeding the values specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBUC who may at times be within the SITE BOUNDARY, the occupancy of tim MEMBER OF THE PUBUp wil be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at au times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBUC at or beyond the SITE BOUNDARY to less than or equal to 500 mrom/ year to the total body or to less than or equal to 3000 mrom/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem / year (NUREG 0133).

32.0 nm,

. ~_

03-12-97 07:47:08 l mew Rad d gi at Conads

-(UCIO8r Departmental Procedure 6610-PLN-4200.01

m. - a,uonm.

Offsite Dose Calculation Manual (ODCM) 11 l

2.2.2.2 Gaseous Effluents 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 shall be limited to the following:

al During any calendar quarter: less than or equal to 5 mrad for gamma radiation ar(

less than or equal to 10 mrad for beta radiation and, 4

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

APPLICABluTY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents .

. exc.eeding any of the above limts, prepare and submit to the NRC Region l Administrator within 30 days, a Special Report which Identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases wBl be in compliance with the above limits.

BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-1.

This control and associated action la provided to implement the requirements of Section li.B.

Ill.A and IV.A of Appendk 1,10 CFR Part 50. The Control implements the guldes' set forth in

. Section ll.B of Appendix 1. The ACTION statements provide the required operating flexiblity 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 effluents wSI be kept 'as low as is reasonably achievable." The Survellance Requirements implement the requirements in Section Ill.A of Appendix i that conformance with the guides of Appendix i be shown by

, calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the cppropriate pathways is unlikely to be substantla!!y underestimated. The dose calcubnon methodology and parameters established in the ODCM for calculating the dosas due to the actual release rates of radioactive noble gases in gaseous effluents are consistent wth the methodology provided in Regulatory Guide 1.109,

' Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendt< 1,* Revision 1 October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmo spheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cocied Reactors,"

Revision 1. July 1977. The ODCM equations prtwided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average aimospheric conditions.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides-

.1.109 and 1.111.

33.0 mi.

d >-

s ll 03-12-97 07:47:00 Number

, g g y~ . TMI Radiological Controls Departmental Procedure -

6610-PLN-4200.01 True Asvis4on No.

Offsite Dose Calcuiation Mariual (ODCM) 11 2.2.2.3 Dose - lodine-131, lodine-133, Tritium, and Radionuclides in Particulate Form CONTROL: ,

The dose to a MEMBER OF THE PUBUC from lodine-131, lodine-133. Tritium, and all radionucildes in particulate form with half lives greater than 8 days, in gaseous effluents i released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: less than or equal to 7.5 mrem to any organ, and

b. During any calendar year. less than or equal to 15 mrem to any organ.

APPUCABluTY: At all times.

ACTION:

With the calculated dose from the release of lodine-131, lodine 133, Tritium, and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any'of the above limits, prepare and sutimit to the NRC Region i Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce.the releases and the proposed corrective actions to be taken to assure that subsequent releases wil be in compilance with the above liroits. j BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-1.

This control and associated action is provided to implement the requirements of Section ll.C, Ill.A and IV.A of Appendk I,10 CFR Part 50. The Controls are the guides set forth in Section ILC of Appendix 1. The ACTION statement provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendk I 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 survallance l requirements implement the requirements in Section Ill.A of Appendtg 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 caletdating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109,

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October, 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Efiluents in Routine Releases from Ught-Water-Cooled Reactors,"

Revision 1, July,1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for lodine-131, lodine-133, tritium and radionucildes in particulate form with half lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these 34.0 nn.

03-12-97 07:47:08 Number Nuclear ' "ad*' 9'a' coat'o

Departmental Procedure 6610-PLN-4200.01  !

Tme RoWon No. l I

Offsite Dose Calculation'Martual (ODCM) 11 calculations were: 1) indMdual inhalation of airbome radionuclides, 2) deposition of

radionuclides onto green leafy vegetation with subsequent consumption by< nan,3) deposition onto grassy areas where mik animals and meat producing animals graze with consumption of the muk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

2.2.2.4 Gaseous Radwaste Treatment System CONTROL The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTit.ATION EXHAUST TREATMENT SYSTEM shall 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 monthly projected gaseous effluent air doses due to untreated gaseous effluent releases from the unit would exceed 0.2 mrad for

~

gamma radiation and 0.4 mrad for beta radiation. The appropriate ;fortions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected d.oses due to gaseous effluent releases from the site would exceed 0.3 mrom to any organ.

APPLICABluTY: At all times.

ACTION:

a. With the' GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION j EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous i waste being discharged w!thout treatment and in excess of the above limits, prepare and submit to the NRC Region I Adin;niiuser within 30 daysc h Special Report which includes the following information: l 1'. Identification of the Inoperable equipment or subsystems and the reason for inoperabilty, .

2. Action (s) taken to restore the inoperhble equipment to OPERABLE status, and l ,

3. ' A summary description of action (s) taken to prevent a recurrence.

I BASES i The use of the GASEOUS RADWASTE TREATMEfff 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 syctem provide reasonable assurance that the releases of radioactive materials in gaseous effluents wlil be kept 'as low as is reasonably achievable." This' control implements the requirements of 10 CFR Part 50.38a, General Design Criterion 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 Appendt* 1,10.CFR Part 50, for gaseous effluents.

I 35.0 nm.

03-12-97 07:47:08 Numtm ggy TMI Radlological Controls

' Departmental Procedure 6610-PLN-4200.01 rm ,

n.uon no.

l _

Offsite Dose Calculation Manual (ODCM) 11 1

2.2.2.5 Explosive Gas Mixture CONTROL >

4 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 hydroge' n in the Waste Gas Holdup System is greater than or equal to 4% by volume. 1 AVAILABluTY: At all times.

2 ACTION:

Whenever the concentration of hydrogen in the Wasta Gas Holdup System is greater than or equal to 4% by volume, and:

a. The concentration of oxygen in the Waste Gas Holdup System la greater than 2% )

by volume, but less than 4% by volume, without delay begin to reduce the oxygen concentration to within its limit. j

b. The concentration of oxygen in the Wasto Gas Holdup System is greater than or equal to 2% by volume, immediately suspend additions of waste gas to the Waste Gas Holdup System and without delay begin to reduce the oxygen concentration to ,

within its limit. 1 BASES:

Based on experimental data (Reference 1), lower limits of flammability for hydrogen is 5% ,

and for oxygen is 5% by volume. Therefore, if the concentration of either Das is kept below I It lower limit, the other gas may be present in higher amounts without the danger of an explostco mixture. Maintaining the coiwnsaiions'of hydrogen and oxygen such that an explosive mtxture does not occur in the waste gag holdup system provides assurance that the release of radioactive materials will be controlled in conforrnance with the requirements of_ General Design Criterlon 60 of Appendix A to 10 CFR 50.

REFERENCES (1) Bulletin 503, Bureau of Mines; Limity of FlammabDity of Gases and Vapors.

2.2.2.6 Waste Gas Decay Tanks

. CONTROL:

The quantity of radioactMty contained in each waste gas decay tank shall be llrnited to less than or equal to 8000 curies noble gases (considered as Xo-133).

APPUCABILITY: At all times.

36.0 nm.

i

03-12'-97 07:47:08 _

Number d

S"UI M TMl Radiological Controls '

Departmental Procedure 6610-PLN-4200.01 hp, FWWcn No.

Offsite Dose Calculation Manual (ODCM). 11 ACflON:

a. With the quantity of radioactive material in any waste gas decay tank exceeding, the -

)

above limit, immediately suspend all additions of radioactive material to the tank j and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

BASES Restricting the quantity of radioactivity contained in each waste gas decay tank provides ,

assurance that in the went of an uncontrolled release of the tanks contents, the resulting l total body exposure to a MEMBER OF THE PUBUC at the nearest exclusion area boundary I wW not exceed 0.5 rem; This is consistent with Standard Review Plan 15.7.1, ' Waste Gas System Failure."

2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Tctal Dose CONTROL: j The annual (calendar year) dose or dose commitment to any MEMBER OF'THE PUBUC, due to releases of radioactMty and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrom to the total body or any organ except the thyroid, i which shall be limited to less than or equal to 75 mrem. I i

l d

APPUCABluTY: At all times. l ACTION:

1 With the calculated dose from the release of radioactive materials in liquid or gaseous i

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, l

2.2.2.3.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.llmits 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 correctNe action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above l limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b), shap include an analysis whbh estimates the radiation exposure (dose) to a MEMBER 67 VHE PUBUC from uranium fuel l cycle sources, including all effluent pathways and dired radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the caues of the exposure levels or concentrations. If the estimated dose (s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a varience in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

37.0 am.

03-12-97 07:47:08 '

, Numtw

! ggp TM1 Radiological Controls Departmental Procedure. 6610-PLN-4200.01 noe n. vicon no.

j Offsite Dose Calculation Manual (ODCM) 11 BASES This control is provided to meet the dose limitations of 40 CFR Part 190,that have been i incorporated into 10 CFR Part 20.1301(d). This control requires the prosparation and .

submittal of a Special Report whenever the calculated doses from plant generated I radioactive effluents and direct radiation exceed 25 mrom to the total body or any organ,

< except the thyroid, which shall .be limked to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBUC wiu exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of AppendtK 1, and if direct radiation doses from the l reactor units and outside storage tanks are kept small. The Special Report wHl describe a '

course of action that should resiult in the limitation of the annual dose to e MEMBER OF THE PUBUC to wthin the 40 CFR Part 1901.imits. For the purposes of the Special Report, it l may be assumed that the dose committnent to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facBities at the same site or within a radius of 8 km must be considered. If the dose to any member of the public ispotimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a I timely request and fulfils the requirements of 40 CFR Part 190 untE NRC staff action is ,

completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in j 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 l during any period in which he/she is engaged in carrying out any opemtion that is part of j the nuclear fuel cycle. i 3.0 SURVEILLANCES ,

i 3.1. Radioactive Effluert Instrumentation .

3.1.1 Radioactive Uquid Effluent Instrumentation Survellance Requiremeras 3.1.1.1 Each r~adioactive liquid effluent monitoring instrumentation channel shau be demonstrated OPERABLE by performance of the CHAN!sEL CHECK, SOURCE i CHECK, CHANNEL CAUBRATION, AND CHANNEL TEST operations during the MODES and at the frequencies shown in Table 3.1-1.

r s

e 38.0 mu

t o

. w Table 3.1-1 6610-PLN-4200.01 l 3

• Revision 11 .

. sa Radioactive Liquid Efiluent Monitoring instrumentation SurveBance Requirements

-J INSTRUMENT CHANNEL SOURCE CHANNEL CHANNEL j

' CHECK CHECK CAllBRATION .

TEST o

(3

1. Radioactuty Montors Providing Alarm and Automatic isolation

'a. Unit 1 Liquid Radwaste EfEuents Line'(RM-1.6) D P R(2) O(1)

b. IWTS/lWFS Discharge une (RM-1.12) D P 'R(2) Q(1)

2. Flow Rate Montors

a. Unit 1 Liquid Radwaste Effluent Line (FT-84) . D(3) N/A R Q

b. Station Effluent Discharge (FT-146) D(3) N/A R -

Q s d

p b

o 9

5 39.0 mu

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l 03-12-97 07:47:08 '

l

. Number gggy TM1 Radiological Controls' Departmental Procedure 6610-PLN-4200.01 Title Revision No.

Offsite' Dose Calculation Manual (ODCM) 11 Table 3.1-1 (Cont'd)

Table Notation (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the following condition exists:

1. Iristrument indicates measured levels above the high alarm / trip setpoint.. (includes - circuit failure)

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

3. Instrument controls moved from the operate mode (Alarm function only).

(2) The Inillal CHANNEL CAUBRATION for radioactMty measurement instrumentation shall biperformed using one or more of the reference standards certified,by the f sational Bureau of Standards or using standards that have been obtained from suppliers that participated in rieasurement assurance activities with NBS. These standards should permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANNEL CAUBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute previously established calibration procedures for this requirement)

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daBy on any day on which continuous, periodic, or . batch releases are made.-

40.0 w.

- _ ._.-_ -- .- -- - - - . .. . .. . - - _ - - - - - - - = = - - - -- -

d 1

1 1 03-12-97 07:47:08 Number Nuclear ' "ad'o'os" co"*

Departmental Procedure 8610-PLN-4200.01

~

l l

rice a.vi on so.

Offsite Dose Calculation Manual (ODCM) 11 j 3.1.2 Radioactive Gaseous Process and EfRuent Monitoring Instrumentation SURVElu.ANCE REQUIREMENTS 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be I

demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, l CHANNEL CAUBRATION, and CHANNEL TEST operations at the frequencies sixmn in Table 3.1-2.

4 l

l 4

i s

9 4

4

/

e e

41.0 inw

. . . ~ . . - . . . . - . . . - . . - . . . - . ._. . . _. -

t

[

B Table 3.1-2 (Cont'd) .

6610-PLN-4200.01 [j Revision 11 i m

Radioactive Gaseous Process and Effluent Monitoring Instrumentation Suiveillance Requirements ,

J CHANNEL SOURCE CHANNEL CHANNEL j INSTRUMENT . CHECK CHECK CAUBRATION - TEST APPUCABlUTY l$

1. Waste Gas Holdup System .

a. Noble Gas ActMty Monitor (RM-A7) P P E(3) O(1)

b. Ef6uent System Flow Rate Measuring Device (FT-123) P N/A E Q

2. Waste Gas Holdup System Explosive Gas Monitoring System -

D N/A Q(4) M

a. Hydrogen Monitor M **

b. Oxygen Montor D 'N/A Q(5)

3. . Containment Purge Vent System

a. Noble Gas Activity Monitor (RM-A9) D P E(3) M(1) #

lodine Sampler (RM-A9) W N/A N/A N/A b.

c. Particulate Sampler (RM-A9) W N/A N/A N/A #

Eftluent System Row Rate Measuring Device (FR-148) D N/A E Q #

d.

Sampler Flow Rate Monitor D N/A E, N/A #

e.

4. Condenser Vent System

a. Noble Gas ActMty Monitor (RM-A5 and SultaMe D M E(3) Q(2) ##

Equwalent - See Table 2.1-2, item 4.a) s

- 42.0 mu

S ll Table 3.1-2 (Cont'd)~ 6610-PLN-4203.21 Revision 11 ,

Radioactive Gaseous Process and EfEuent Monitoring Instrumentation Surveillance Requirements

. p CHANNEL SOURCE CHANNEL' CHANNEL Q INSTRUMENT CHECK CHECK CAUBRATION TEST APPUCABluTY

~

S. Auxilary and Fuel Handing Buldog Ventiation System -

a. Noble Gas Activty Monitor (RM-A8) or (RMA4 and D M E(3) O(1).

RM-A6) .

W . N/A - N/A

b. lodine Sampler (RM-A8) or (RM-A4 and RM-AS) N/A

c. Particulate Sampler (RM-A8) or (RM-A4 and RMAS) W- N/A N/A N/A

d. System Effluent Flow Rate Measurement Devices D N/A E O (FR-149 and FR-150) ,

i D E N/A

e. Sampler Row Rate Monitor N/A

6. Fuel Handling Buldhg ESF Air Treatment System

"" l

- a. Noble Gas Actrvity Monitor (RM-A14) D M R(3) Q(2)

b. System Emuent Flow Rate (UR-1104 A/B) D N/A R Q

c. ' Sampler Floiw Rate Measurement Device D N/A R O 4

b e

43.0 mm

03-12-97 07:47:08 Number Nuclear i Radid@al Contrds Departmental Procedure 6610-PLN-4200.01 Tw. ame on No.

l Offsite Dose Calculation Manual (ODCM) 11 1

i Table 3.1-2 (^rnt'd) l Table Notation 1 At all times.

l During waste gas holdup system operation.

Operabity is not required when discharges are poskively contrdled through the closure of WDG-V47, and where RM-A8 (or RMM and RM-A6), FT-149, and FT 150 are operable.

During Fuel Handling BuRding ESF Air Treatment System Operation.

1. At all times during containment purging.

1. 1. - At all times when condenser vacuum is established.

i (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway for the Auxiliary and Fuel Handling Building Ventiation System, the supply ventRation is isolated and control room 1

alarm annunciation occurs ll the following condt!on exists: -

1. Instrument Indicatee measured levels above the high alarm / trip setpoint (includes circut 4

fature).

l 2. Instrument Indicates a down scale failure (Alarm. function only) (includes circuit faRu e).

3. Instrument controls 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 condklons exist:

1. Instrument indicates measured levels above the alarm setpoint. (includes circuit failure)

2. Instrument indicates a down scale faRure.(includes circuit fature).

3. Instrument controls moved from the operate mode.

(3) The Initial CHANNEL CALIBRATION for radioactMty 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 with NBS. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAUBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substtute previously established calibration procedures for this requirement.)

l (4) The CHANNEL CAllBRATION shau include the use of standard gas samples containing'a nominal:

1. One volume percent hydrogen, balance nitroger% and

2. Four volume percent hydrogen, balance nitrogen. l l

44.0 ms

)

03-12-97 07:47:08 Number

-( g g y TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 N Revision No.

a Offsite Dose Calculation Manual (ODCM) 11 Table 3.1-2 (Cont'd)

(5) The CHANNEL CAUBRATION shall include the use of standard gas samples containing a nominal

1

1. One volume percent oxygen, balance nitro 0en, and l 2. Four volume percent oxygen, balance nitrogen. -

l

)

O i

i i

i l

1 i ,

1 .

I 1

1 a

1 45.0 wu i

q 03-12-97 07:47:08 Number Nuclear-

' "ad*oaica' coa'r* '

I Departmental Procedure 6610-PLN-4200.01 me twen uo, Offsite Dose Calculation Manual (ODCM) 11 1 3.2 Radioactive Effluents 3.2.1 Uquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration.

3 2 1.1.1 The radioactMty content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 3.21. The results of pre-release 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 Post-release analysis of samples cciripcened from batch releases shall be performed in accordance with Table 3.2-1. The results of the previous post 4elease analysis shaE be used with the calculational methods in the OOCM to assure that the concentrations at the point of rel. ease were maintained within the limits of Control 2.2.1.1.

3.2.1.1.3 The radioactMty R,rn,ecu.i;cn of liquids discharged from continuous release points shaE be determined'by collection and analysis of samples in accordance.with Table 3.2-1. The results of the analysis shot be used with the calculational n* Mis of the ODCM to assure that the concentration at the point of release is maintained within the limits cf Control 2.2.1.1.

3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative does contrt>utions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month.

3.2.1.3 Uquid Ydaste Treatment i

~

3.2.1.3.1- Dooes due to liquid releases shall be projected at least once a month,

'In accordance with the ODCM. '

3.2.1.3.2 The liquid radwaste treatment, system shall be demonstrated ,

OP.ERABLE by. operating the liquid radwaste treatment system i equipment for at least 60 minutes quarterly unless the liquid radwaste system has been'utfilzed to process radioactive liquid effluents during the prWlous 92 days. i 48.0 am.

1 i ,

I 03-12-97 07:47:08 l

ggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Rev6elon No. i j Offsite Dose Calculation Manual (ODCM) 11 0 1 1 3.2.1.4 Uquid Holdup Tanks ,

, 3.2.1.4.1 The quantity of radioactive material contained in each of the tanks specified in Control 2.2.1.4 shall,be determined to be within the limit by analyzing a representative sample of the tar #s content weeldy i 1

when radioactive materials are being ad'd ed to the tank. j

! i 1

j

< i j i i

l l

l l

l 1

9 47.0 mu

o w

661ptN-4200.01 S Table 3.2-1 Revision 11 /

' o 4

Radioactive Uquid Waste Sampling and Analysis Program 3 4

s e i ' Lower Umit d S j ~

4 Minimum Analysis ,

• I Sampling Frequency Frequency l

• TypeAnalysis d ActMty (pCl/ml) (Note ll Detection a) ' 3(LLD Uquid Release Type ,

~

P , P' 't H4 1 x 10-8 A.1 Batch Waste Release Tanks (Note d) Principal Gamma 5 x 10~7 Each Batch ' Each Batch Emitters (Note f) i I' .

' 4

'~

1-131 1 x 10 j d

j M  ! Dissolved and l. 1 x 10

i ' P.

l Entrained Gases l l' One Batch /N l l (Gamma l l Emitters) 1 '

i l l l 1 1 x 10'7 P . l Q l Grossalpha Each Batch L ,' I Composite (Note l

Sr-89,b)Sr-90 l! ,

S X 1'04 Fe65 1 x 10-s

. g

'k

)

t 4

e-g>

L i

l mm 48.0

O e

M 6610-PLfM200lD1

~

Table 3.2-1 (Cont'd) #

Revienon'11 ,

Radioactive Uquid Waste Samphng and Analysis Program 3 4

i Lower Umit of

• 4 Samphng l ' Minimum Analysis, Type of Activity Detection (LLD)

Frequency l

e. Frequency Analysis (pCl/ml) (Note a) ;j

. Uguld Release Type Continuous W I PrincipalGamma l 5 x 10'7 A.2 Conunuous Releases (Note e) l l I (Note c) i Composite  ! Emitters (Note f) l l  !  !

l (Note c) 4 l-131 .l 1 x 10

-l' l

?

M M Dissolved and ! 1 x'104 1 Grab Sample Entmined Gases I (Gamma Emitters) l l.

M 14 3 1 x 104 s - l Continuous '

Composita (Note c)

Gross alpha l- 1 x 10'T (Note c)

Continuous I Q ,

Sr-89, Sr-90 '

5 x 10-8

- l' (Note c)  ! Composte  !  !

-l Fe-55 l 1 x 101 l (Note c) l I f f 0

4 o

mi, 49.0

_ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ _

03-12-97 08:06:17 Numtwf TMI Radiological Controls I Departmental Procedure 6610-PLN-4200.01 noe neWon No.

Offsite Dose Calculation Manual'(ODCM) 11 Table 3.241 (Cont'd)

Table Notation

a. The LLD is defined, for purposes of this surveillance, as the smallest concentration of radioactive material in a sample that wWl yloid a not count above system background that will be detected with 95% probability with 5% probabilty of falsely concluding that a blank observation represents a " rear

@M. *

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

LLD = 4.86 s,.

1 E x V x 2.22 x 10' x Y x exp (-A At) '

Where: ,

' LLD is the "a priorf lower limit of detection as defined above (as microcurie per unit mass or volume),

se,is the standard dev!ation of the background counting rate or of the counting rate of a blank sarnple as appropriate (as counts per minute),

f E is the counting efficiency (as counts per disintegration),

~

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

2.22 x.10sis the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yleid (when sp' plicable),

A is the radioactfve 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 priorr (before the fact) limit representing the

, capability of a measurement system and not as an *a posteriorr (after the fact) limit for a particular measurement.

b. A composite sample is one in which the quantty of liquid sampled is proportional to the quantity of .

Ilquid waste discic=w.d 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 quantities and concentrations of radioactive materials in liquid effluent, samples shall be collected continuously in, proportion to the rate of flow of the effluent stream. Prior to analyses, all sarnples taken for the composite shall be thoroughly mtxed in order for the composite sample to be representative'of the effluent release.

50.0 sm.

03-12-97 08:06:17 ,

Number gggy TMI Radiological Contrds Departmental Procedure - 6610-PLN-4200.01

Ude Mon No.

• l j Offsite Dose Calculation Manual (ODCM) 11 Table 3.2-1 (Cont'd) j

d. A batch release is the discharge of I! quid wastes of a discrete volume. Prior to sampling for -

analyses, each batch shall be isolated, and be thorougNy mixed, by a method described in the ODCM, to assure representative sampling.

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

. f. The principal gamma emitters for which the LLD spec 5;c.i;on applies exclusively are the following radionudides: Mn-54, Fe-69, Co48, Co40, Zn45, Mo-99. Cs-134, Co-137, Co-141, and Ce-144.

This list does not rnean that only these nuclides are to be co'nsidered. Other gamma peaks that are l

, I identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release lieport pursuant to TS 6.9.4.

i

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e s a

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03-13-97 08:06:17 Numb.r -

Nuder '"' "*d'o' S'oa' o a -

Departmerdal Procedure 6610-PLN-4200.01 l

no. AwWon No. '

Offsite Dose Calculation Manual (ODCM) 11 3.2.2 Gaseous , Effluents -

SURVEILLANCE REQUIREMENTS 3.2.2.1 ' Dose Rates 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be

determined to be within the limits of Control 2.2.2.1.a In accordaince, '

, with the methods and procedures of the ODCM.

I 3.2.'2.1.2 The dose rate of radioactive mats 4 other than noble gases,'in  :

l gaseous effluents shall be determined toLbe within the limts of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM

by obtaining representative samples 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 4

- (ODCM) monthly.

j 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, I and radionuclides in particulate form with half lives greater than 8 '

days for the current calendar quarter and current calendar year shall '

' be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

i 3.2.2.4 Gaseous Waste Treatmer:t

) 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected

! montNy in accordance wth the ODCM.

3.2.2.5 Explosive Gas Mixture

! 3.2.2.5.1 The concws Uons of hydrogen arid oxygen in the wa'ste gas holdup i I

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 i hydrogen and oxygen monitors covered in Table 2.1-2 of Control

! 2.1.2.

l l

52.0 row

. 03-12-97 08:06:17 Number gUggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 nu. MWon No.

. Offsite Dose Calculation Manual (ODCM) 11 j 3.2.2.6 Waste Gas Decay Tank 3.2.2.6.1 The concentration of radioactMty contained in the vent header shall be determined weeldy. If the concontration of the vent header exceeds 10.7 Cl/ce, daly samples shal be taken of each waste gas

. decay tank being added.to, to determine if the tank (s) is less than or

- equal to 8800 Cl/ tank.

1 i

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8

+

4 s

s 6

53.0 nm.

- 0 661MLN-4200.01 ib Tat $e 3.2-2 Revision 11 7 o

Radioactive Uquid Waste Sampling and Analysis Program

- n 1

3 Minirnum  !~ Lower Umit of

• Sampling ' Analysis . Type of Activty Detection (LLD) 7 l Frequency Analysis pCi/ml) (Note a) j Gaseous Release Type Frequency l P R  !

-Each Tank ' Each Tank Pix:Ipal Gamma  ! .1 x idd A Waste Gas  !

Decay Tank Grab Sample l Emitters (Note g) l.  !

4 B. Containment P (Note b) ' l 'P (Note b)~ l H4 l 1 x 10 4 1 x 10 Purge . g Each Purge- l Each Purge l Princ% mil Gamma

Grab Sample , , Emitters (Note g)

'l M (Notes c, e) l M l H'4 1 x 104 -

C. AuxIlary and 4 i j PrincipalGamma 1 x 10 Fuel Handling Building j Grab Sample AirTreatment System j l l Emitters (Note,g) l M (during l M (during D. Fuel Handling Building lH4 i Principal Gamma i 1 x 10-s ESF Air Treatment System j System ~ j System 4 Operation) l Emitters (Note g) I 1 x 10

. l Operation) l Grab Sample l l l

! I I  !

i i i i j M (Note h) M  !

E. Condenser Vacuum l Grab Sample lH4

. Prirripal Gamma  ! 1 x 10 4

Pumps Exhaust (Note h) 4 -

l -l Emtters (Note g) l 1 x 10 (Note h)  ! I t.

ri, 54.0 6

o W

e l .

6610fLN-4200.01 P Tatne 3.2-2 (Cont'd) ,,

t>

Radioactive Liquid Waste Sampling and Analysis Program -

(3 l . Sampling l Minimum Analys:s l . -

l Lower und of Detection (LLD)- h Frequency Frequency l Type of ActMty Analyss  ! (pCl/mi) (Note a)

Gaseous Release Type l l

!  ! U

!  ! 42 l 1 x 10 F.' AI Release Types as Listed Above l , Continuous l W (Note-d)-  ! l-131 .

in A, B, C and D W System j (Note 0 - . l Charcoal Sample  !

-!~ '

operation  !  !

Cortinuous . W (Note d) Principal Gamma Emitters . t x 10'"

1 (Note f) Particulate (Note 9) .

l '

(I-131. Others)

~O .! ~ 1 x 10'"

! Cortinuous Gross Alpha I l (Note f) Composite -

Paribulate Sample ls l l-  !

- I Continuous l Q  ! l l

' i Composite i Sr49, Sr-90  ! 1 x 10'"

(Note f) l Particulate Sample I -

g' I  ! .

G. Condenser Vent Stack Continuous l

! l 'l 1 x 10 42 lodme Continuous , l W (Note d)  ! l-131 Sampler (Note j) . . (Nde k)' l Cbsrcoal Samp6 ,

O e

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03-12-97 08:06:17 J Numbw RUmgEI EE TMI Radiological Controls M Departmental Procedure 6610-PLN-4200.01 Tee -

MWon No.

Offsite Dose Calculation Mariual (OOCM) 11

. Table 3.2-2 (Cont'd) "

Table Notation

a. The 11D is defined, forpurposes of this surveillance, as the smallest concentration of radioactive material in a sample that will yleeJ u net count above system background (fat wil be detected with 95% probab8ttywith 5% probability of faicely conduding that a blank observation represents a " rear signal.

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

1 LLD = 4.66 sm E x V x 2.22 x 10' x Y x exp (-A At)

Where:

llD is the "a priorr lower limit of detection as defined above (as microcurie per unit mass or volume),

1 s is the standard deviation of the background counting rate or of the counting rate of a blank 3

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 x 108la 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 i

. At is the elapsed time between midpoint of sarnple collection and time of counting.

Typical values'of E, V, Y and At shall be used in the calculation.

l It should be recognized that the 11D is defined as an "a priorr (before the fact) limit representing the '

l capabilty of a measurement system and not as an *a posteriorf (after the fact) limit for a particular measurement.

b. 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 i shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant has not increased more tien a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not l

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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded. .

56.0 **

l 03-12-97 08:06:17 Number l

gI TMI Radiological Controls i Departmental Procedure 6610-PLN 4200.01 Dse Asvision No.

4 Offsite Dose Calculation. Manual (ODCM) 11 -- -

i Table 3 2-2 (Cont'd) 1

d. Charcoal cartridges and particulate filters shall be changed at least once per 7 days and analyses shall be completed within ~48 hours after changing (or after removal from sampler).

1 e, Tritium grab samples shall be taken weekly from the spent fuel pool area whenever spent fuel is in

> the spent fuel pool.

f. The ratio of the. sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculatfortmade 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 LLD specification applies exclusively are the following

radionuclides

Kr-87, Kr-88, Xe-133, Xo-133rn, Xe-135 and Xe 138 for gaseous emissions and Mn-54, l Fe49, Co-58, Co40, Zn-66, Mo-99,' Co-137, Co 14t and Co-144 for particulate emissions. This list

' j does not mean that only these nuclides are to be oorwidered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall'also be analyzed and reported in the l Annual Radioact!ve Effluent Release Report pursuant to TS 6.9.4.

I i h. Applicable only when condenser vacuum is established. Samgiling and analysis shall also be .

performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of l l RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT I 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 of8uent activity has not increased by more than a factor of 3.  ;

i

' I

1. Gross Alpha, Sr 89, and Sr-00 analyses do not apply to the Fuel Handling Building ESF Air Treatment System.

j. If the Condenser Vent Stack Continuous lodine Sampler is unavailable, then altamate sampling equipment wlR be placed in service within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or a report wE be prepared and submitted withia ,

30 days frorn the time the sampler is found or rnade Inoperable which identifies (a) the cause of the inoperabuity, (b) the action taken to restore representative . sampling capability, (c) the action taken to prevent recurrence, and (d) quantification.of the release via the pathway during the period and comparison to the limits prescribed by Control 2.2.2.1.b.

k. Applicable only when condenser vacuum is established.

57.0 sm,

d 03-12-97 08:06:17

. Number j

Nuclear ' adidoa'e=' o ""d*

Departmental Procedure . 6610-PLN-4200.01 noe neaan ua.

Offsite Dose Calculation Manual (ODCM) 1.1 3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation

i 3i3.1.1 Cumulative annual dose contributions from liquid and gaseous

, effluents shall be determined in accordance with Surveillances 4

' 3.2.1.2.1,3.2.2.2.1, and 3.2.2.3.1, including direct radiation  ;

e contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM.

! l I

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4 f

y *s t

.g #

I 58.0 . mi.

s

1 l

t 03-12-97 08:06:17 Number j

gggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01

rio.  % on No.

Offsite Dose Calculation Manual (ODCM) 11

4.0 PART I REFERENCES 4.1 Title 10, Code of Federal Regulations, " Energy' f

, 4.2 Regulatory Guide 1.109, " Calculation of Annual Dosed.to Man from Routing Releases of Reactor l Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50. Appendix 1. "Revislon 1,

~

October 1977 4.3 TMI-1 Technical Specifications, attached to Faclity Operating License No. DPR-50 4

4.4 TMI 1 FSAR ,

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0 e

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O

l l D3-12-97 08:06:17 i Numbw jggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 l Tm m no.

Offsite Dose Calculation Manual (ODCM) 11 i

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i i.

k 4

l 2

4 l .

t

~ PART 11 '

9 TMI-2 RADIOLOGICAL EFFLUENT CONTROLS 1

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Numtm i gggy TMI Radiciogical Controls Departmental Procedure 6610-PLN-4200.01

)

noe RevWon No.

l

! Offsite Dose Calculation Manual (ODCM) . 11 l l

l l PART11

\

Definitions 1.0 DEFINITIONS

. DEFINED TERMS

*I l 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part il I of the.ODCM. . l FACILITY MODE 3 1.2 Post-Defueling Monitored Storage (PDMS) is that condklon-where TMI-2 defueling has been completed, the core debrio removed from the reactor during the clean-up period h'as been shipped l off-site and the facElty has been placed in a stable, safe and secure condition.

1 ACTION 1.3 ACTION shall be those additional requirements specified as corollary stabments to each control and shall be part of the controls.

l OPERABLE - OPERABillTY l 1.4 A system, subsystem, train, component or device shal be OPERABLE or have OPERABIUTY when it

< la capable of performing ks specified function (s). Implict in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxulary equipment, that are required for the system, subsystem, train, component or device to perform its function (s), are also t'apable of performing their related support function (s). l

, . . l CHANNEL CALIBRATION 1.5 A CHANNEL CAUBRATION shall be the adjustment, as necessary, of the channel output such that it  !

responds with necessary range and accuracy to,known values of the parameter which the channel monitors. The CHANNEL CAUBRATION shall encorr. pass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CAUBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by

observation. This determination shal include, where possible, comparison of the channel Indication and/or status with other Indications and/or status derived from independent instrument channels measuring the same parameter.

61.0 mi.

1 03-12-97 08:06:17 Number Nuclear "ad'o'oS'ca' ooatm'* -

Departmental Procedure 6610 PLN-4200.01 Tine Revision No.

Offsite Dose Calculation Manual (ODCM) 11 NOTE l For radioactive ' effluent monitors, except for those in Table 2.2-1, this

! shall include a verification which provides a qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

I CHANNEL FUNCTIONAL TEST l 1.7 A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the ' injection of a simulated signal into the channel ti close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

1 .

b. Bistable channels - the injection of a simulated sl0nal into the channel sensor to verify 1 OPERABILITY including alarm and/or trip functions.

FREQUENCY NOTATION ' ,

1.8 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1, l COMPOSITE SAMPLE i

1.9 A COMPOSITE SAMPLE is a combination of Individual samples obtained at regular intervals over a j time period. Elther the volume of each Individual sample is proportional to the low rate discharge at i the time of sampling or the number of equal volume samples is proportional to the time period used '

to produce the composite.

GRAB SAMPl_E 1.10 A GRAB SAMPLE is an indh/idual sample collected in less than fifteen minutes.

BATCH RELEASE 1.11 . A BATCH RELEASE is the discharge of fluid waste of a discrete volume.

CONTINUOUS RELEASE 1.12 A CONTINUOUS RELEASE is the d!scharge of flu'Id waste of a non-discrete volume, e.g., from a volume or system that has an input flow during the CONTINUOUS RELEASE. s 62.0 nm.

i 03'-12-97 08:06:17 Number I

Nuclear ' a*d***' coa"*

Departrnental Procedure 6610-PLN-4200.01

. no. rwwon so. ,

j Offsite Dose Calculation Manual (ODCM) 11 i

TABl E 1.1 i Frequency Notation -

NOTATION FREQUENCY l l

i S (Shifdy) At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D (Daily) At least orme per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I W (Weeldy) At least once per 7 days.

M (Monthly) At least once per 31 days.

Q (Quarterly)

• At least once per 92 days. ,

SA (SemhAnnually) At least once per 184 days.

A (Annually). At least once por 12 months.

E At least once per 18 months.

N.A. ' Not applicable. .

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3 03-12-97 08:06:17 Number Nuclear ' "*d'S**' coad' Departmental Procedure 6610-PLN-4200.01

, Title Redslon No.

Offsite Dose Calculation Manual (ODCM) 11

. ' SECTIONS 2.0,3.0 AND 4.0 Controls and Surveillance Requirements 2/3.0 APPLICABluTY CONTROLS , .

2/3.0.1 Controls and ACTION requirements shall be applicable during the conditions specified for each control.

' 2/3.0.2 Adherence to the requirements of the Control and/or associated ACTION within the specified time interval sher constitute compliance with the ~ control. in the event the Contml is restored prior to expiration to the specified time interval, completion of the ACTION statement is not regulred.

2/3.0.3 in the event the Control and/or associated ACTION requirements cannot be satisfied because of

' circumstances in excess of those addressed in the Control, initiate appe r iste actions to rectity the problem to the extent possible under the circumstances, and submit a special report to the Commission pursuant.to TMI-2 PDMS Technical Specification (Tech. Spec.) Section 6.8.2 within 30 days unless otherwise specified.

SURVEILLANCE REQUIREMENTS 4.0.1 Survallance Requirements shau be applicable during the conditions specified for individual Controls unless otherwise stated in an Individual Survellance Requirement. The Survealance Requirements shall be performed to demonstrate compilance with the OPERABILITY requirements of the Control 4.0.2 Each Surveillance Requirement shah be performed within the specified time interval with:

a. A maximum allowable extension not to exceed 25% of the surveillance interval, and

b. A total maximum combined interval time for any 4 consecutive tests not to exceed 3.25_ times the specified surveulance interval.

4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compilance with OPERABILITY requirements for a Control and associated ACTION statements unless otherwise required by the Contrd.

m e 64.0 nm.

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03-12-97 08

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Number gggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01

Th FWelon No.

I 1'1 Offsite Dose Calculation Manual (ODCM)

)

M8E8  ;

The Controls of this section provide the general requirements applicable to each of the C9ntrol and Survemance

Requirsments.

. l 2/3.0.1 This Contrd defines the applicabity of each Control in terms of the specified conditions and is  ;

j provided to delineate specifically when each Control is applicable.

2/3.0.2 This Control defines those conditions necessary to constitute compil'ance with the terms of an 3

4 IndMdual Control and associated ACTION requirement.

I 2/3.0.3 This Control delineates the ACTION to be taken for circumstances not directly prtMded for in the )

ACTION. statements or when the provisions of the stated ACTION statement are not or cannot be j l

. complied with. The sitent of this Control is to require that inoperable equipment be restored to an OPERABLE status in a' prompt manner, that the unit be maintained In'statde conditions, and that the ,

Commission be promptly notified of such conditions.

! 4.0.1 This Control provides that survallance actMties necessary to ensure the Controls'are' met and wl!! be performed during the FACIUTY MODE or other condtions for which the Controls are applicable.

4.0.2 The provisions of this Control provide allowable tolerances for performing survellance actMiles beyond I those specified in the normal survealance interval. These tolerances are necessary to provide operational  !

i ilexib8ty because of scheduling and performance considerations. The phrase 'at least" associated with'a

surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent surveillance actMtles.

The tolerance values, taken either indMdually or consecutively over 3 test Intervals, are sufficiently restrictive to ensure that the reliabity associated wth the surveillance actMty is not degraded beyond that obtained from the nominal specified interval.

. 4.0.3 The provisions of this Control' set forth the criteria for determination of compilance with the OPERABluTY requirements of the Control. Under this criteria, equipment, systems or components are assumed to be

OPERABl.E ll the associated surveRance actMtles have been satisfactorly performed within the specified

< time interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such iterns are found or known to be Inoperable although stm meeting the SurveEapce Requiremortts.

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03'12-97 08:06:17 Number Nuclear ' "ad'doa~da Departmental Procedure 6610-PLN-4200.01 Title m No.

Offsite Dose Calculation Manual (ODCM) 11 l

2.0 RADIOLOGICA1. EFFLUENT REQUIREMENTS i

~

2.1 RadioactNe Discharges 2.1.1 Liquid Effluents l

2.1.1.1 OBJECTIVES ,

s To define the limits and conditions for the controlled release of liquid radioactive emuents'to the  !

l environs to ensure that these releases are as low as practicable. These releases should not result in radiation exposures to offsite areas greater than a few percent of background exposures. The instantaneous release rate for all' effluent discharges should be within ten times the concentrations specified in 10 CFR Part 20.

~

4 To assure that the releases of radioactive liquids to offsite areas meet the 'as low as practicable" concept, the following objectNas apply:

A. The annual total quantity of radioactive material in liquid waste, excluding tritium and .

disadved gases, should not exceed 5 curies per radioactive waste-producing reactor, and the annual dose' to the whole body or any organ of an Individual should not exceed 3 mrem to the total body and shall be less than or equal to 10 mrom to any organ.

B. The annual average concentration of radioactive materials in the effluent from the Mechanical Draft Coding Towers prior to diulion in the Susquehanna River, excluding tritium and disadved gases, should not. exceed 2E-8 pCl/mi.

C. The annual average concentration of tritium in liquid waste prior to diution in the

' environment should not exceed SE-6 pCl/ml.

2.1.1.2 APPLICABILITY Applies to the controlled release of radioactive liquids from TMI-2.

2.1.1.3 CONTROLS A. The radioactNity release concentration in liquid emuents from TMi-2 to the environment shall not exceed ten times the values specified in 10 CFR 20, Appendix B,for unrestricted areas.

B. The total release of radioactive liquid effluent from TMI-2, excluding tritium and noble gases, shall not exceed 10 curies during any calendar quarter.

C. The equipment instaDed in the liquid radioactNe waste system shaN be maintained and shall be operated to process all radioactive liquid wastes prior to this discharge when the actMty release rate will exceed 1.25 curies, excluding tritium and dissolved gases, during any calendar quarter.

D. The maximum radioactMty to be contained in one liquid radwaste tank, excluding tritium and dissoNed gases, that can be discharged directly, to the environs, shall not exceed 10 curies.

66.0 a am,

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Offsite Dose Calculation Manual (ODCM) 11 l

E. When the average release rate of radioactive effluents, excluding trtium and dissolved gases, exceeds 2.5 curies per radioactive waste-producing reactor during any calendar quarter, the licensee shall notify the NRC wkhin 30 days, identifying the causes and describing the proposed program of action to reduce such release rates.

F. The dose or dose commitment from liquid effluerds shall be less than or equal to,3 mrem total body and less than or' equal to 10 mrom to any organ for the calendar year.

2.1.1.4 BASES Liquid radioactive waste release levels to unrestricted areas should be kept 'as low as practicable" i and are not to exceed ten times the concentrations specified in 10 CFR 20. The Controls provide l reasonable assurance that the resulting annual exposure to an Individual in off-site areas will not I exceed the design objectives of Appendix I to 10 CFR Part 50, which were established as l requirements for the cleanup of TMI 2 in the NRC's Statement of Policy of AprI 27,1981. This I assurance is based on the fact that the Susquehanna River wBl dIute the liquid effluents upon their l release from the site. The effluents wlR be dIuted by a factor of about 250 in the region where finfish can exist (within a one<1uarter mie radius of the discharge point). At the same time these Controls permit flexibility under unusual conditions, which may temporarly result in higher than normal releases, but stHI w! thin ten times the :,oncentrations, specified in 10 CFR 20. It is expected that.by using this flexibRy undar unusue! conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the annual average concentrations specified in 10 CFR 20.

Control 2.1.1.3 A. above requires the licensee to limit the concentration of radioactive materials in liquid effluents from TMI-2 to ten times the levels specified in 10 CFR 20, Appendix B, for unrestricted areas. This Control provides assurance that no member,of the general public can be exposed to liquids containing radioactive materialp in s< cess of limits considered permissible under the Commission's rules and regulations.

Control 2.1.1.3 B. above establishes an upper limit for the release of radioactive liquid effluents, excluding trklum and dissolved gases, of 10 curies during any calendar quarter. The intent of this Control is to permit the licensee flexibalty under unusual conditions, which may temporarily result in releases higher than the levels normally achievable when the unit and the liquid radwaste equipment are functioning as designed. Releases of up to 10 curies during any calendar quarter will result in concentrations of radioactive materials in liquid effluents at small percentages of the concentrations

~

specified in 10 CFR 20. .

Control 2.1.1.3 C. requires the licensee to maintain and operate tho equipment installed in the liquid radioactive waste system to reduce the release of radioactive materials In liquid effluents to as low as practicable, consistent with the requirements of 10 CFR 50.36a. Normal use and maintenance of

, installed equipment in the liquid radioactive system is expected to result in releases of not more than about five curies per year, excluding tritlum and dissolved gases during normal operations. In order to keep releases of radioactive materials as low as practicable, the Control requires, as a minimum, operation of equipment whenever the rate of release exceeds 1.25 curies per quarter, excluding tritium and dissolved gases. -

67.0 mw m

. . = _

03-12-97 08:06:17 Numt>er gggy .

TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 nn. -

n.vmon no.

Offsite Dose Calculation Manual (ODCM) 11 In addition'to Control 2.1.1.3 B., the reporting requirements of Control 2.1.1.3 E. and Section 6.6 of the TMI.2 PDMS Tech. Specs., delineate that the licensee shall identify the cause whenever the rate of radioactive affluents, excluding tritium and noble gases, exceeds 2.5 curies during any calendar quarter and describe the proposed program of action to reduce such release rates. This report must be filed within 30 days following the calendar quarter in which the 2.5 curie release occurred.

l 1

, Control 2.1.1.3 F. requires that the dose to offsite personnel be Ilmited to the design ob[ectives of Appendix 1 of 10 CFR Part 50. This will assure the dose received by the public during the cleanup is equivalent to or less than that from a normal operating reactor. The limits also assure that the environmental Impacts'are consistent with those assessed in NUREG 0683, the TMi-2 Programmatic .

Environmental Impact Statement (PElS). I l

2.1.2 Gaseous. Effluents 2.1.2.1 OBJECTIVES

. I 4 To define the limits and conditions for the controlled release of radioactive gaseous effluents to the a environs to ensure that these releases are as low as practicable. These releases should not result in radiation exposuras in offsite areas greater than a few percent of background exposures.

1 To assure that the release of radioactive gases to offsite arms meet the as low as practicable concept, the release rate of gaseous effluents shall not result in doses to the public exceeding the

, design objectives of Appendix 1 to 10 CFR Part 50. l 2.1.2.2 APPUCABluTY Applies to the controlled release of radioactive gases from TMI-2.

2.1.2.3 CONTROLS A. Th's instantaneous dose rate from release of gross gaseous activity except for halogens and j particulates with half-lives longer than eight days shall not exceed 500 mrern/ year to the I total body and 3000 mrom/ year to the skin. i B. The instantaneous dose rate from release of particulates with half-lives greater than eight days, to the environs as part of the airbome effluents, shall not exceed 1500 mrom/ year to -

any urgan. ,

C. Radioactive gases and particulates purged from th's Reactor Building shall be filtered through the high efficiency particulate air filters. .

D. The air dose due to noble gases in gaseous effluents shall be less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation for the calendar year, and less than or equal to 5 mrad for gamma radiation and 10 mrad for beta radiation for any calendar quarter.

E. The dose for radioactive (other than noble gaseous effluents) shall be less than or equal to 15 mrem to any organ for the calendar year, and 7.5 mrem to any organ for any calendar quarter.

4 60.0 sm.

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l me ,

F W alon No.

Offsite Dose Calculation Manual (ODCM) 11 l l

. \

F. When the release of radioactive materials in gaseous wastes exceeds the values in Controls A, B, D or E, the licensee shal notity the NRC within 30 days, identifying the causes and describing the proposed program of action to reduce such releases.

2.1.2.4 BASES l

The specified levels provide reasonable assurance that the resulting annual exposure rate from noble l gases at any location at the site boundary wil not exceed 10 millirems por year. At the same time, l these Controls permit flextlity under unusual conditions,.which may temporarty result in higher I

~

than the design objective levels, but stHI within the dose limits specified in 10 CFR 20 and within the design objectives of Appendix 1 to to CFR 50. It is expected that using this flexibilty under unusual conditions, and by exerting every effort to keep levels of radioactive rnatorial in gaseous wastes as low as practicable. the annual releases wil not exceed a small fraction of the annual dose limits '

specified in 10 CFR 20 and wil not result in doses which. exceed the design objectives of Appendix 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 efforts should include consideration of meteorological conditions during releases.

Control 2.1.2.3 A., requires the licensee to limit the concentration of noble gases from TMI-2 to unrestricted areas to levels such that no indMdual will receive dose at a rate greater than 500 mrem /yr to the total body or 3000 mrom/yr to the skin.

Control 2.1.2.3 B., requires the licensee to limit the concentration of particulates with half-lives greater than eight days, released from TMI-2 to unrestricted areas to levels such that no individual wil receive dose at a rate greater than 1500 mrem /yr to any organ. The absence of iodine ensures that the corresponding thyroid ' dose rate above background to an infant via the cow-mDk-infant pathway is less than or equal to,1500 mrem /yr. A grazing period of 6 months has been applied to

. all radionuclides in particulate form with half-lives greater than 8 days, to allow for the mik exposure-pathway. ,

Control 2.1.2.3 C., limits the radioactivity that may be released to the ersvironment to "as low as practicable." -

In addition to the requirements of Controls 2.1.2.3 B., D. and E., the ' reporting requirements of Control 2.1.2.3 F. delineate that the licensee shaR identify the cause whenever the radioactive gaseous releases exceed Control 2.1.2.3 D. or Control 2.1.2.3 E., and describe the proposed l program of action to reduce such releases. The report must be fDed within 30 days following the calendar quarter in which the release occurred.

9 69.0- mi.

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Num W ,

Nuclear ' "*d*' **' o"**

Departmental Procedure 6610-PLN-4200.01 htm < Revmon No.

$ Offsite Dose Calculation Manual (ODCM) 11 4

2.2 Radioactive Gaseous Effluent Monitoring instrumentation 2.2.1 OBJECTIVE ,

The radioactfve Caseous effluent monitoring instrumentation channels shown in Tabla 2.2-1 shas be OPERABLE.

2.2,2 APPUCABluTY ,

As shown in Table 2.2-1.

2.2.3 CONTROL

. With less than the minimum number of radioactive Oaseous effluent monitoring 1, instrumentation channels OPERABLE, take the ACTION shown in Table 2.2-1, i

2.2.4 BASES 4

The radioactive gaseous sinuent instrumentation is provided to monitor and contrel, as applicable, the releases of radioactive materiais in gaseous effluents during actual or potential releases of gaseous effluents. ' The OPERABluTY and use of this instrumentation is'

- consistent with the requirements of General Design Criterlon 64 of Appendix A to 10 CFR J Part 50.

i ,

s 0

70.0 mm

s- _ _ . . -

l 03-12-97 08:06:17 Numbw gggy TMl Radiological Controls Departmental Procedure -

6610-PLN-4200.01 l Title Revision No.

, Offsite Dose Calculation Manual (ODCM) 11 i

TABLE 2.2-1 Radioactive Geseous Effluent Monitoring instrumentation 5

CHANNEL MINIMUM CHANNEL CHANNEL FUNCTIONAL CHANNELS

INSTRUMENT CHECK CAUBRATION TEST OPERABLE APPLICABlu1Y ACTION HP-R219 Gee D E' M 1 Note 1 Note 2 HP-R 219 Particulate ~D E M 1 Note 1 Note 2 HP-R219A Gas D-' E M 1 Note 1 ' Note 3

} HP-R219A Perttoulate D E M 1 Note 1 Note 3 -

l HP-4225 Gas o E M 1 Note 1 Note 4 4

l HP.R226 Particulate D E M 1 Note 1 Note 4 NOTES: s

1. During operation of the monitor'ed system.

2. If the same channel on HP-R-219A is. inoperable, secure Reactor Buiding Purge if in progress.

3. If the sarne channel on HP-R-219 is inoperable, secure Reactor Buiding Purge if in progress.

4. If channel is inoperable, secure Reactor Bulding Purge if in progrees.

\

e 0

71.0 mw

. ~ - . __ . - _ .- - . . .

l 03-12-97 08:06:17 l Number  !

gggy

, TMI Radiological Controls l Departmental Procedure 6610-PLN-4200.01 I me awtelon No.

Offsite Dose Calculation Manual (ODCM) 11  !

L i 3.0 MONITORING REQUIREMENTS  ;

I l 3.1 Radioactive Discharges  !

l l

3.1.1 Liquid Effluents )

3.1.1.1 OBJECTIVE To ensure that radlloactive liquid releasen from the factilty are within the limits of Controls 2.1.1.3 A.

l through F.

3.1.1.2 CONTROLS During refease of liquid radioactive wastes from Radioactke Waste-Miscellaneous Liquids System, the following conditions shad be met:

A. Facliity records'shau be maintained of the radioactive concentrations and volume before dRution of each batch of liquid effluent released, and the average diution flow and length of time over which each discharge occurred. Estimates of the error associated with each reported value should be included in facility records.

B. Radioactive liquki waste sampling and activity analysis shall be performed in accordance with Table 3.1 1. Prior to the release of each batch of liquid affluent, a sample shall be taken from that batch and analyzed for the concentration of each significant gamma emitter to demonstrate cornpliance with Control 2.1.1.3 A. using the flow into which the effluent is dischargad.

3.1.1.3 BASES These monitoring requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive liquid wastes released to the environment. Reports on .

the quantities of radioactive materials released in liquid effluents shall be fumished to the ,

Commission on the basis of ODCM Part IV Requirements. On the basis of such reports and any l additional irk,w-iksi obtained from the licensee or others, the Commission may require the licensee to take appOpfuite action.

3.1.2 Gaseous Effluents -

3.1.2.1 OBJECTIVE To enstre that radioactive gaseous releases from the faciity are within the limits of Controls 2.1.2.3 A. through F.

3.1.2.2 CONTROLS During release of radioactive gaseoQs wastes, the following conditions shall be met-

~

l 72.0 m,.

I 03-12-97 08:06:17 l gg y TMl Radiological. Controls Departmental Procedure 6610-PLN-4200.01 l Tm awwon No.

Offsite Dose Calculation Manual (ODCM) 11 l l

l A. During purge of the Reactor Bulding, the following conditions shall be met:

1. The Reactor Bulding Purge Exhaust Monitors (HP-R-225 and HP-R-21g or similar device) shau be OPERABLE. j l

B. The flow rate for radioactive effluent streams and the Auxtlary and Fuel Handling Buildings j

' and the Reactor BuBding, shall be monitored and recorded. Gaseous of60ents fiorn the

, Reactor Building Purge Exhaust shall be continuously monitored and recorded.

1 1 NOTE With flow rate monitoring instrumentation out of service, flow rates from the Auxsiary and Fuel Handling Buldings may be estimated using the - l

. maximum design flow for the exhaust fans in operation. j

- i C. Radioactive gaseous waste sampling and actMty analysis shad be performed in accordance l with Table 3.1-2. l l

D. FacDity records shall be maintained of radioactive concentration, release ratio and volume of_ i each batch ci gaseous efiluents released and the length of time over which release occurred. Estimates of the. error associated intth each reported value should be included in facIlty records. l i

E. The release of radioactive materials, other than noble gases, in gaseous effluents shall be 1 determined to be within the.lirnits calculated in accordance with this Control by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 3.1-2.

~

3.1.2.3 BASES Controls 3.1.2.2 A. through D. require that suitable equipment to monitor the radioactive gaseous releases are operating during any period these releases are taldng place.

Cor, trol 3.1.2.2 E. is provided to ensure that the dose to a member of the public from gaseous effluents from TMI-2 wil be within the limits of Control 2.1.2.3 D and Control 2.1.2.3 E.

1 These nanitoring regulromonts provide assurance that radioactive gaseous affluents from the station l are propedy controlled and monitored over the life of the station. These monitoring requirements provide the data for the licensee and the Commission to evaluate the station's' perfortnance relative l

' to radioacthe gaseous wastes released to the errvironrnent.

Repo% on the quantitles of radioactive materials released in gaseous effluents shall be fumished to the Commission on the basis of ODCM Part IV requirementa. On the basis of such report and any l adraltional Information the Commiss!on may obtain from the licensee or others, the Commission may

. from time to time require the licensee to take such action as the Commission deems appropriate.

73.0 e n.

I 03-12-97 08:06:17 .

Number ggggp TMI Radiological Controls' Departmental Procedure 6610-PLN-4200.01 l

Time weion No. )

Offsite Dose Calculation Manual (ODCM) ~ 11 3.2 Radioactive Gaseous Effluent Montoring instrumentation Each radicactive gaseous emuent monitoring instrumentation channel shall be demonstmted l OPERABLE by performan.co of the CHANNEL CHECK, CHANNEL CAUBRATION and CHANNEL l RJNCTIONAL TEST operations at the frequencies shown in Table 2.2-1 (per occupational exposure )

l considerations and detector sensitMty in ambient radiation areas). ,

l  !

l 1 i l l l

I 1

I l

A 1

1 74.0 nm.

03-12-97 08:06:17 Number y

i ggy TMl Radiological Controls Depinin- tel Procedure 6614PLN-4200.01 -

I l

D8e RwWon No. l Offsite Dose Calculation Manual (ODCM) 11 1

1 TABLE 3.11 )

l Radioactive Liquid Waste Sampling and Analysis (4,5)

A. Uauld Releases l

Type of Detectable Sampling Frequency ActMty Analysis Concentration (3)

Each Batch Individual Gamma SE-7 pCl/mi (2) j H4 1E-5 pCl/mi Quarterty Composte (1) Gross Alpha 1E-7 pCl/mi

! Sr-89 SE-8 pCl/ml Sr-90 SE-8 pCl/rni ,

,- J NOTES:

(1) A COMPOSITE SAMPLE Is one in which the quantty of liquid sampled is proportional to the quantity of liquid waste disc.hiiW from the plant. .

(2) For certain mboures of gamma emitters, it may not tse possible to measure radionuclidas in concentrations ,

near this sensitivity limt when other nuclides are present in the sample in much greater concentrations.  !

Under these circumstances, it will be more appropriate to calculate the concentrations of such radionucl! des using measured ratios with those radionuclides which are routinely identified-and measured.

(3) The d'etectability limits for radioactMty analysis are based on the technical feasiblity and on the potential significance in the environment of the quantitles released For some nuclides, lower detection limits 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 ,

period when analyses were not periviin6d, the average of the two ad}acent 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.egtimates, and the method used to.obtain these data should be described.

(5) Deviations from the sampling / analysis regime wHl be noted in the report specified In'ODCM Part IV.

4 75.0 nm.

4 e

j 03-12-97 08:06:17

- Number g

~ g gy TM1 Radiological Controls Departmental Procedure 6610 PLN-4200.01

m. w on No.

Offsite Dose Calculation Manual (ODCM) 11.

TABLE 3.1-2 Radioactive Gaseous Waste Sampling and Analysis (3) j SAMPLE SAMPLING T PE OF DETECTABLE i SAMPLE POINT TYPE FREQUENCY ACT'VITY ANALYSIS CONCENTRATION (1)(a) i Reactor Buiding Purge Releases Gas Each Purge H-3 1E-6 pCl/cc Individual l' Gamma Emitters 1E-4 pCl/cc (2)

Una Exhaust Vent Release Points Gas MontNy. i+3 1E-6 pCl/cc

) Individual

Gamma Emitters 1E-4'pC1/cc (2)

IndMdual (b) i Particulates Weeldy Gamma Emitters 1E-10 pCl/cc (2)

MontNy

. Composto St-90 1E-11 pCi/cc l 8

MontNy Gross Alpha .

Composite Emitters IE-11 pCl/cc Reactor Building Breather Particulates Semi-Annually Indy. Gamma 1E-10 pCl/cc (2)

Emitters (b) 1E 11 pCl/cc St-90 I Gross Alpha IE-11 pCl/cc Emitters (1) The above detectabBty limits are based on technical feasibuty and on the potential significance in the.

- environment of the quantitles released For some nuclides, lower detection limits may be readily achievable i and when nuclides are measured below the stated limits, they should also be reported. l (2) For certain mixtures of gamma emitters, it may be possible to measure radionticlides at levels near their

. sensitMty limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it wSI be more appropriate to calculate the levels of such radlonuclides using obseived ratios in the gaseous component in the reactor. coolant for those radionuclides which are measurable.

(3) Deviations from the sampling and anatysis regime will be noted in the report specified in ODCM Part IV.  !

76.0 nm.

em

i 03-12-97 08:06:17 Number Nuclear ' "*d*' a**' "*

Departmental Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 11 TABLE 3.1-2 (Cont'd) .

Radioactive Gaseous Waste Sampling and Analysis Program

Table Notation

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95%

probability with 5% probability of falsely concluding that a blank observation represents a "real* signal.

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

4.66 S3 -

E V 2. 22 . Y

• exp (-A4 t:)

1 Where I

. 1 LLD is the lower limit of detection as defined'above (as picoeurie per unit mass or volume). 1 Sbis the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).

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

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

2.22 la the number of transformations per minute per picocurie,'

Y la the fractional radiochemical yield (when app!! cable).

A is the radioactive' decay constant for the particular radionu'clide, and At is the elapsed time between rnkipoint of sample collection and time of counting (for plant effluents, not enviisiurmidal samples),.

The value of Sbused in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an. unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normaty present In the samples. Typical values of E, V,

'(, and At shall be used in the calculation. The background count rate la calculated from the background counts that are determined to be with one FWHM (Full-Widthst-Half-Maximum) energy band about the energy of the gamma-ray peak used for the quantitat!ve analysis for that radionuclide.

77.0 sm.

03-12-97 08:06:17 Numtw i nadid gi ai Contrss

! GUCIO8r Departmental Procedure. 6610-PLN-4200.01 is. m so. ]

Offsite Dose Calculation Manual (ODCM) 11 TABLE 3.1-2 (Cont'd)

Radioactive Gaseous Waste Sampling and Analysis Program Table Notation

b. The principal gamma ernitters for which the LLD specification' applies exdusively are the following radionuclides: Mn-54, Fe-59, 00-58, Co40, Zn-65, Mo-99, Cs-134, Cs-137, Co-141'aixl Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identifed and reported. Nudides which are below the LLD for the analyses shall be reported as "less than' the nuclide's LLD and shaN not be reported as being present at the LLD level for that nimilde. The 'less than* Values shall J not be used in the required dose calculations. '

l l

l l

. l I

e 4

e 78.0 nm.

1 03-12-97 08:06:17

Numbw gggy- TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tine RevWort No.

l.

Offsite Dose Calculation Manual (ODCM) 11 l SECTION 4.0 Design Features '

l 4.0 DESIGN FEATURES i

i 4.1 SITE EXCLUSION AREA 5 . .

4.1.1. The exclusion area is shown in Figure 5-1, TMI 1 Tech. Specs.

LOW POPULATION ZONE i

4.1.2 The low population zone is shown in Figure 5-2, TMI 1 Tech'. Specs.

l SITE BOUNDARY FOR GASEOUS EFFLUENTS ,

i

! 4.1.3 The site boundary for gaseous affluents shau be as defined in Section 2.1.2.2 of the TMI-1 FSAR and j as shown in Figure 2'13, TMI-1 FSAR.

5 SITE BOUNDARY FOR LlOUID EFFLUENTS 4.1.4 The site boundary for liquid effluents shaR be as shown in Figure 5-3, TMI 1 Tech. Specs.

i e

j .

i I

I 1

d

. 79.0 mu

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03.-12-97-08:06:17

' Number Nuclear ' "ad'Soa**' o"'**

Departmental Procedure .6610-PLN-4200.01

. me w.m No.

' 11 Offsite Dose Calcula' tion Manual (ODCM) 5.0 PART11 REFERENCES 5.1 NUREG-0683, " Final Frogrammatic Environmental impact Statement related to decontamiriation and ,

disposal of radioactive wastes resulting from March 28,1979, accident Three Mie Island Nuclear Station, Unit 2," March 1981, and its supplements.

]

5.2 TMI-2 PDMS Technical Specifications, attached to FacIlty Ucense No. DPN-73 5.3 Title 10 Code of Federal Regulations,' Energy" 5.4

• Statement of Policy Relative to the NRC Programmatic Environmental Impact Statement on the i Oeanup of Three Mile Island Unit 2," dated Apri 27,1981 5.5 Regulatory Guide 1.109, ' Calculation of Annual Doses .to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,* Revision 1, i

October 1977 i .

5.6 DOE / TIC-27601, Atmospheric Science and Power Reduction

]

5.7 TMi-1 Technical Specifications, attached to FacElty Operati.g License No. DPR40 I

5.8 PDMS-SAR l l

e d

9 9

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y TMl Radiological Controls Departmental Procedure 6610-PLNJ.200.01 i N' Rove No.

Offsite Dose Calculation Manual (ODCM) 11 f

i W

i 1

. 1

1 l

1  ;

1 l 3

i -

}

! PART lli EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES.

G 4

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Departmental Procedure 6610-PLN-4200.01 l j nue -

Wn No.

1

^

Offsite Dose Calculation Manual (ODCM) 11 l A

1.0 UQUID EFFLUENT MONITORS 1.1 TMI-1 and TMI-2 Liould Radiation Monitor Set Points l l

The liquid effluent off-line monitors are set such that the concentration (s) of radionuclides in the liquid ofRuonts will not exceed ten times the concentrations specified in 10 CFR 20, Appendix B Table 2, Col 2. Table 1.1 lists the Liquid EfRuent Release Points and their parameters; Figure 1.1 provides a Liquid Release Pathway Diagram.

d

, To meet the above limit, the alarm / trip set points for liquid efRuent monitors and flow measuring devices are set in accordance with the following' equation:

, c

• f _t C (eq 1.1)

F+f .

i g

4 C= ten times the ofRuent concentration of 10 CFR 20 for the site, in pCl/ml.

1 c= the set point, in pCl/mi, of the liquid effluent monitor measuring the radioactivity concentration in the sinuent line prior to dilution e.nd release. The set point _ is inversely 4

proportional to the maximum volumetric flow of the effluent line and proportional to the minimal volumetric flow of the dilution stream plus the effluent stream. The alert set point value is set to ensure that advance waming occurs prior to exceeding any limits. .The high alarm set point value is such that if it were exceeded, t 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 J

F- flow rate of dBution water measured prior to the release point, in volume per unit time.

l'

. The set point concentration is reduced such that concentration contributions from multiple release points would not c6mbine 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.

?

eThis section of the ODCM la irnplemented by the Radiation Monitor System Set Points procedure and, for batch releases, the Releasing Radioactive Liquid Waste procedure.

~

6 1

82.0 mm

03-12-97 08:0'5:17 Number l

E Nuclear ren.

TMI Radiological Controls Depa.e,g procedure 6610-PLN-4200.01 w ion No.

Offstte. Dose Calculation Manual (ODCM) 11 1.2 . TMI Llauld Effluent Release Points and Llauld Radiation Monitor Data -

i TMI-1 has two required liquid radiation monitors. These are RM-tE and RM4.12. 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 utilze RM-L12 and RM-L7 for release ofliquid waste I

1.2.1 .RM-LS

' 1 RM-!.S is an off41rke system, monitoring radioactive batch discharges fro'm the TMI 1 liquid

radwaste system (see Figure 1.1). These batch releases are sampled and analyzed per site procedures prior to release. The release rate is based on releasing one of two Waste Evaporator Condensate Storage Tanks (WECST) at a flow which will add less than 10%, of ten tlmes the 10 CFR 20 concentrations to radionuclide concentrations In the unrestricted i area, including conservative default values for St-89, Sr-90, and Fe-66.

The release Sow 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 DF's are calculated to: 1) insure each radionuclide released to the unrestricted area is less than 10 percent of ten times the 10CFR20 radionuclide concentrations,2). ensure each liquid batch release boron concentration to the river wHI not exceed 0.7 ppm, and 3),

ensure ten tirnes the 10CFR20 concentration for Cesium-137 (1E-S pCl/ml) wil not be exceeded based on the calculated high alarm set point and the expected response of RM-L8 to this concentration of Cs-137.

The maximum release flow rate is then calculated by' dividing the most restrictive (largest)

DF into 90 percent of the current dIution flow rate of the Mechanical Draft Coollng Tower

~

(MDCT). This conservative flow rate is then multipiled by 0.9 for the allowable flow rate.

e Calculation of 10 percent 10% of ten times the 10CFR20 concentration DF:

DF, si K (SA)3 + (10% of ten times the 10CFR20 concentration)

SA = Specific Activity of each identifled radionuclide-

• Calculation of Boron DF:

DFg = Actual Tank Boron' Concentration + 0.7.

e Calculation of Cs-137 IJmit:

DF, = High Alarm Set Point + (1E-6 pCl/ml

• 1.05E8 cpm per pCI/ml) e Maximum release flow rate calculation:

i Max Flow = [(MDCT flow gpm

• 0.9) + (Most Restrictive DF)]

• 0.9 83.0 mm

03-12-97 08:06:17 Number TM1 Radiological Controls gI I Departmental Procedure 6610-PLN-4200.01 huon No.

m.

Offsite Dose Calculation Manual (ODCM) 11 The diution 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 WH1 meet the following equation.

E(C/X,) < 0.10, (eq 1.2) w'here: Cl - duuted concentration of the i* radionudide, .

X, = Ten times the concentration for that radionuclide in the unrestricted area (10 CFR 20, App. B, Table 2. Col 2). A value of 3E-3 pCl/mi for dissolved and entrained noble gases shan be used.

The set points for RM-LS are set for esclk release based on the monitor response to each radionudide identified in the gamma scan sample results as follows:

(1.5)* [IS (pCi/cc),*(CPM /pCl/cc)) + (CPMaus) = ALERT CPM (2.0)* [I! (pCl/cc), (CPM /pCl/cc)) + (CPM,,,) = HIGH, ALARM CPM where; (pCl/cc), - positively identified radionuclides (CPM /pCl/cc), = RM-l.6 Sensitivity to radionuclide L (CPMago) - RM-LS background prior to batch rplease A high alarm on RM-L6 wfil close valve WDL-V 257 and terminate any WECST releases to the environment.

4 1.2.2 RM-L12 RM-L12 is an off-line system, montoring periodic combined releases from the industrial Waste Treatment System / Industrial Waste Fitration System (IMS/lWFS). The input to IWTS/lWFS originates in TMI-2 sumps, (see Figures 1.1 and 1.2) and the TML-1 Turbine Bulding sump (aee Figure 1.1). The set points are based on the maximum release rate from both IMS and IWFS simultaneously, (see Figure 1.1) a minimum dilution 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/rni. These inputs are used in equation 1.1 to determine the RM-L12 High Alarm set point for all radionuclides being released. A high alarm on RM-L12 wiu close IWTS and IWFS release valvesind trip release pumps to stop the release.

1.2.3 RM-L10 RM-L10 was a Nel detector submer'ged in the TMl-1 Turbine Dullding Sump. This detector has been removed from service.

1.2.4 RM-L7 4

RM-L7 la not an ODCM required liquid radiation monitor. RM-L7 is an off-line system,

~

monitoring the TMINS outfaB to the Susquehanna River (see Figures 1.1 and 1.2). This monitor is the final radiation monitor for TMI 1 and TMI-2 normal, liquid effluent releases.

84.0 mm i

i

. l

f 03-12-97 08:06:17 tunbn ggy TMi Radiological Controls Departmental Procedure 6610-PLN-4200.01

w. . m nte.

Offsite Dose Calculation Manual (ODCM) 11 1.3 Control of Liould Releases I TMl 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-L6, and effluent sampling, limits batch releases to less than or equal to 10% for ah radionuclides, and l FIM-L12, and effluent sampling limits releases from TMI-1 and TM1-2 to less than or equal to 50% for Cs-137.

These radiation monitor set points also include butt in meter er' ror factors to further ensure that TMI liquid effluent releases are less than ten times the 10CFR20 concentrations to the environment.  ;

. l l

The radioadivity content of each batch of radioactive liquid waste is determined prior to release by

< sampling and analysis in accordance with ODCM Part I Table 3.2-1. The results of pre-release analyses are used with the calculational m . ethods 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. .

Post-release analysis of samples composited from batch releases are performed in accordance with I

ODCM Part i 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 corice.e.e;urie at the point of release were

. maintained within the ODCM Part i Control 2.2.1.1.

, The radioactMty concentration of liquids discharged from continuous release points are determl'ned by .ollection and analysis of samples in accordance with ODCM Part i Table 3.2-1. The results of the analysis are used with the calculational methods of the ODCM to assure that the concentration i at the point of release is maintained within the ODCM Part I Control 2.2.1.1.

~

1 l

}

• r

, l 1

4 85.0 me.

I

.. - - _ ~ .. .-. - - _ . . . . _ ._. _ _ _ _ _ .. . . .

l 03-12-97 08:06:17 - , Number

- ggggy TMl Radiological Controls Departmental Procedure 6610-PLN4200.01

+

Tme Revidm No.

Offsite Dose Calculation Manual (ODCM) '11 TABLE 1.1 TMl Liquid Release Point and Liquid Radiation Monitor Data

! L10UID RELEASE LIQUC RELEASE TERMINATION

- RADIATION POINT DISCHARGE INTERLOCK l MONITOR (Maximum FLOW ,(YES/NO)

(DETECTOR) LOCATON Volume) RECOFCER VALVES YE8

WDLv257 281' Elevation WECST Batch

RM-L8 TMI-1 Aux 81ery Rollmanes (Na0 Bid 0

9000 gat) FT-84 l

Station YES

' F94L7 Discharge WDLrV257

, (Na0 South end of TMk1 and *WDL41311

" TML1MDCT TML2. FT-146 l

YES iwTs/iWFS rW-vrs, Continuous IW-P16.17,18 Releases IW-V2F9, li RNLL12 IWFS Building (300,000/ FT442/

Np29,30 (Na0 NW Comer 80,000 gal) FT-373

)

• WDLA41311 has been San 0ed off as,a TML2 liquid outfag.

" RIM.7 le not an ODCM required liquid radiation monitor.

1 1 i 4

)

i Y

l e

d 86.0 mm

1 r

(

03-12-97 08:06:17 Number s ggy .

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tm FWWon No.

Offsite Dose Calculation Manual (ODCM) 11 TABLE 1.2 TMI-2 Sump, Capacities i

Total Capacity Gallons Sump

• Gallons porinch Turbine Building Sump 1346 22.43 Circulating Water Pump House Sump 572 10.59 Control Bulding Area Sump

• 718 9.96 Tendon Access GaBey Sump 538 9.96 Control to Service Building Sump ' 1346 22.43 i 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 I

4 Sludge Collection Sump ** -

1106 26.33 Floater Drain Sump - -

Solid Wa's te Staging Facility Sump 1476 24.00 1

AuxElary Bulding Sump 10102 202.00 Decay Heat Vault Sump' 479 10.00 Bull ding Spray Vault Sump ,

479 10.00

-*- Corxlensate Polisher Sump Is deactNated and in PDMS condtion.:

4'

' " The Water Treatment and Sludge Collection Sumps wil be deactNated for PDMS.

87.0 me.

e l

F igure 1.1 g 'j,,mP, ' g nadiation uonitor I".

TMI-1 Liquid Effluent Pathways ~~ naowast.

oran Disposal 1 Sample Pre-Operatbn Auxiliary Powdex Solids Graver ,

" s -

ChemicalCleaning Boiler Vessels System -

Bains(a Blow down 4 t

i i SB0Dieul S80 Diesel 116 2

'

• SuspA SuspB Suses

- _._ _ _ _ _ , np int .

r I .

img ,,

S Intermediate -

• 1 cooin. ,

Building Sump -

Turbine ,, ,, . Collection ( .

i East ' '

Build.ing '

4 Sump .

l Sump industrial  !

Intermediate ' W*

• t.

Building Sump

i s Treatment iWI West i Sanitary System 8 Cabon Preetnant l 6 m2 . t' t

WasteTMI-1 m W Condensou andTMl-2 Tels

,r i 9_ _

co.m i ,,

s canuent SII "'

Collection -

Tank i

M aste Waste Se @ -

" " i Plant '

Evaporator Evaporator SeWageIIeahnt Neutralizer w' .. " d "".* ,, ,

Condensatt Condensatt plgg{ Filtration s. -

stwage storage g.%  !

Tank sv. tern Tank A Ta'nk B sE3, t mG , Solids -  ;

- , n

,, Filter  ! l Cake l

Component Mechanical Draft Cooling Cooling Tower S!

RIVER.

Water TMI-1 TMl-1

4 03-12-97 08:06:17 - -

6610-PLN-4200.01

< FIGURE 1.2 Revision 11 TMI-2 Uquid EfAusnt Pathways l

} .

l CONTROL CONTROL &

BUILDING ><

, SERVICE SUMP AREA SUMP i

TURBINE TENDON 4

sulLDING >< ACCESS

SUMP ~ GALLERY SUMP i

4 i

1r I

IWTS SUMP 1r INDUSTRIAL WASTE TREATMENT SYSTEM i

l l I RML .12 Y

a C RML7 l

i C -- COMPOSITE SAMPLER l.

NI 89.0 mm .

b 03-12-97 08:06:17 -

Numtiet jggy' TMI Radiological Controls.

Departmental Procedure 6610-PLN-4200.01 i m. mwon No.

3 Offsite Dose Calculailon Manual (ODCM) 11 2.0 UQUID EFFLUENT DOSE ASSESSMENT 2.1 Uauld Eff!uents - 10 CFR 50 Aooendix 1 The dose from liquid ofMuents results from the consumption d fish and drinking water. The location of the nearest potable water intake is PP&L Brunner Island Steam Electric Station located downstream of TML' The use of the flow of the Susquehanna River as the dilution flow is justified based on the complete mixing in the river prior to the first potable water supply, adequately

• demonstrated by fiume tracer die studies and additional liquid effluent release studies conducted using actual TML-1 tritium releases. Other pathways contribute negligibly at Three Mile Island. The dose contribution from all radionuclides in liquid effluents released to the unrestricted area is calculated using the following expression:

Dosej = (b c) X (Cg) X AW39X -- + AFggX-X {eq 2.1}

l where:

Dose j = the cumulative dose commitment to tho' total body or any organ, j,.from the liquid '

i efRuents for the total time period, in mrom. ]

l 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 radionuclide, I, in undButed liquid effluent during time period At from any liquid release, in pCl/ml.

NOTE For Fe 65, St-89, Sr-90, prior to batch releases conservative concentration values wlE be used in the initial dose calculation based on simiar past plant conditions. LLD values are not used in dose calculations.

f= undiluted liquid waste flow lIn gpm.

FD = plant dilution water.flowrate during the period of release, in opm FR = actual river flowrate during the period of release or average river flowrate for the month the release is occurring, in gpm. .

DF = dIution factor as a result of mixing effects in the near field of the discharge structure of

.0.2 (Reg. Guide 1.109, Rev.1, Table A-2) or taken to be 5 based on the inverse of 0.2.

AWg and AFg = the alte-related ingestion dose commitment factor to the total body or any organ, J, for each identified principle gamma and beta emitter, in mrom/hr per pCl/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway...

90.0 mm

t 03-12-97 08:D6:17

• Number g gy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Rwision No.

Offsite Dose Calculation Manual (ODCM) 11 4

Values for AWg are determined by the following equation:

l AWg = (1.14ES) x (U) x (DF g) (eq 2.2) where: .

l 1.14E5 = (1.0E6 pCl/pCl) x (1.0E3 ml/kg) + (8780 hr/yr)

U, = Water consumption rate for adult is 730 kg/yr (Reg. Guide 1.109, Rev.1).

DFg = ingestion dose conversion factor for radionuclide, I, for adults total body and for

• worst case" organ, j, in mrom/pCl, from Table 2.1 (Reg. Guide 1.109) l 1

Values for AFg are determined by the following equation:

AFg= (1.14E5) x (U,) x (DFg ) x (SF) (eq 2.2.2)

'where:

/

1.14E5 = defined above U, = adult fish consumption, ' assumed to be 21 kg/yr (Reg. Guide 1.109, Rev'.1).

DFg = ingestion dose conversion factor for radionuclide, I, for adult total body and for " worst case" organ, j, in mrom/pCl, from Table 2.1 (Reg. Guide 1.109, Rev.1).

BF,= Bioaccumulation factor for radionuclide, I, in fish, in pCl/kg per pCl/L ' from Table 2.2 (Reg. Guide 1.109 Rev.1).

. i t

91.0 mm

i 03-12-97 08:06:17 Numbw l Nuder - '" "*d'o' a'o=' contro'*

Departmental Procedure 6610-PLN-4200.01 I Title Revis6on te.

i Offsite Dose Calculation Manual (ODCM) 11 .

I 2.2 TMI-1 Uauld Radwaste System Dose Cales Once/ Month

! ODCM Part i Control 2.2.1.3 and TMI-2 PDMS Tech Spec Section 6.7.4.a.6 ' requires that appropriate ,

portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in j liquid wastes prior to their discharge when the monthly projected doses due to the liquid effluent releases from each unit to unrestricted areas would exceed 0.06 mrom to the total body or 0.2 mrem to any organ in any calendar month. The following calculational method is provided for performing this dose projection.

.' l At least once per month, the total dose from all liquid releases for the quarter-to-date will be dMded 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 releases _during the period.for which the projection is made if this projected dose exceeds 0.06 mrom total body or 0.2 mrem any organ, appropriate portions of the Liquid Radwaste Treatment Syste,m, as defined in Section 3.1, shall be used to reduce radioactMty levels prior to release.

At the discretion of Radiological Engineering, time periods other then the current quarter-to-date may be used to project doses,1f the dose per day in the current quarter-to-date is not believed to, be representative of the does per day projected for the next month.

e e

9 1

92.0 me.

l J

03-12-97 08:06:17 s Nurnber gglgy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01' rm. awwon wo.

Offsite Dose Calculation Manual (ODCM) 11 2.3 Aftemative Uauld Dose Chulatlanal Methodoloav .

As an alternative, models in, or based upon, those presented in Regulatory Guide f.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 altemative dose calculational methodology GPU Nuclear calculates dosee using SEEDS (simpilflod environmental effluent doelmetry system).

The onsite and SEEDS calcula'lonal t models use actual liquid release data with actual monthly Susquehanna River flow data to assess the dispersion of emuents in the river.

0 l

4 93.0 mm

03-12-97 08:06:17 ,

. Nurnber ggy TMl Radiological Controls -

Departrnental Procedure 6610-PLN-4200.01

. m. a.vwon No.

Offsite Dose Calculation Manual (ODCM) 11

. TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFg 4

Page 1 of 3 -

4

Ingestion Dose Factors for AdtAts*

(MREM Per PCI Ingested)

NVOUDE BONE LIVER T. BODY iHYROID KIDNEY LUNG GI-LLI H. 3 NO DATA 1.05E-07 1.05E-07 ,1.05E-07 1.05E 07 1.05E47 1.05E-07

. C 14 2.84E-06 ' 5.68E-07 5.68E 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 2.66E49 1.59E-09 5.86E-10 3.53E49 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E 07 ' NO DATA 1.36E46 ' 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 2.75E 06 1.90E-06 4.43E 07 NO DATA NO DATA 1.06E46 1.09E46

.FE 59 4.34E46 1.02E-05 3.91 E-06 NO DATA NO DATA 2.85E.06 3.405-05 CO 58 NO DATA 7.45E 07 1.67E 06 NO DATA NO DATA NO DATA 1.51E45 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E44 ' 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E-08

• 3.13E-08 NO DATA- NO DATA NO DATA- 1.74E l CU 64 NO DATA 8.33E-08 3.91E48 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6.96E NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E48 1.97E48 1.37E 09 NO DATA 1.28E 08 NO DATA 2.96E49 BR 83 NO DATA NO DATA 4.02E 08. NO DATA NO DATA NO DATA' 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA' 2.14E OS NO DAT5 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 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA ' 4.01E48 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 7.58E43 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E47 NO DATA NO DATA NO DATA 2.70E45 SR 92 2.15E 06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 l

Y 90. 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 94.0 mm

4 03-12-97 08:06:17 Numtw Nuclear ' "*d* co""*

Departmental Procedure 6610-PLN-4200.01 we n.vWon No.

l 1

Offsite Dose Calculation Manual (ODCM) 11 TABLE 2.1 (Cont'd) l 1

Liquid Dose Conversion Factors (DCF): DFg

. Page 2 of 3 Ingestion Itose Factors for Adults * -

(MREM Per PCI Ingested)

NUCUDE BONE LIVER T. BODY THYROfD KIDNL/ t.UNG GI-LLI Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA ' NO DATA NO DATA 2.67E-10 Y 91 1.41 E-07 NO DATA ' 3.77E49 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 1.48E45 Y 93 2.68E-09 NO DATA' 7.40E-11 NO DATA NO DATA NO DATA 8.50E 05 ZR 95' 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E48. NO DATA 3.09E 05 ZR 97 1.68E49 3.39E-10 1.55E-10 NO DATA 5.12E 10 NO DATA 1.05E44 NB 95 6.22E49. 3.48E49 1.86E 09 NO DATA 3.42E-09 NO 7ATA ~ 2.10E-05 l MO 99 NO DATA ' 4.31E46 8.20E-07 NO DATA 9.76E46 NO JATA 9.99E-06

'TC' 99M 2.47E'-10 6.98E-10 8.89E-09 NO DATA 1.06E 08 3.42E-10 4.13E-07 I

TC 101 2.54E 10 3.66E 10 3.59E-09 NO DATA 6.59E 09 1.87E-10 1.10E-21

. RU 103 1.85E-07 NO DATA 7.97E-08 ' NO DATA- 7.06E 07 NO DATA 2.16E-05 RU .105 1.54E48 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 1.60E-07 1.48E 07 8.79E-08 NO DATA 2.91 E-07 NO DATA 6.04E45 SB 125 1.79E-06 2.00E-08 4.26E-07 1.82E49 0.0 1.38E-06 1.97E-05 TE 125M 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 . NO DATA 1.07E45 TE 127M 6.77E46 2.42E-06 8.25E-07 1.73E46 - 2.75E-05 NO DATA 2.27E 05 TE 127 1.10E-07 3.95E-06 2.38E 08 8.15E48 4.48E-07 NO DATA 8.68E-06 TE 129M 1.15E-05 4.29E-06 1.82E46 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE 129 3.14E48 1.18E-08 7.65E49 2.41E-08 1.32E47 NO DATA 2.37E 08 TE 131M 1.73E-06 8.46E-07 7.05E 07 1.34E-06 8.57E 06 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.22E49 '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 1 130 7.56E-07 2.23E 06 8.80E 07 1.89E-04 3.48E-06 NO DATA 1.92E 06

-l 131 4.16E 06 5.95E-06 3.41E46 1.95E-03 1.02E45 NO DATA 1.57E46 1 132 2.03E 07 5.43E-07 . 1.90E 07 ' 1.90E-05 - 8.65E 07 NO DATA 1.02E-07 1 133 1.42E-06 ' 2.47E-06 7.53E 07 3.63E44 4.31E 06 NO DATA 2.22E-06 i 134 1.06E 07 2.88507. 1.03E47 4.99E-06 4.58E-07 NO DATA 2.51 E-10 95.0 m.

4 5 .

07-12-97 08:06:17 Number -

J NMar '"' "*d'o'oa'c=' coat'o

Departmental Procedure 6610-PLN-4200.01 -

Title Asvte6on No.

Offsite Dose Calculation Manual (ODCM) . 11 TABl.E 2.1 (Cont'd) j Liquid Dose Conversion Factors (DCF): DFg Page 3 of 3 Ingestion Dose Factors for Adults

• 4 (MREM Per PCI Ingested)

NUCUDE BONE , LIVER T. BODY THYROID KIDNEY LUNG GI-LU l 135 4.43E47 ' 1.16E46 4.28E-07 7.65E-05 1.86E46 NO DATA 1.31E46

.CS 134 6.22E 06 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E 05 2.59E46 CS 136 6.51E-06 2.57E45 - 1.85E-05 NO DATA .1.43E-05 ' 1.96E-C6 2.92E46 CS 137 7.97E-06 1.00E O4 7.14E 05 NO DATA 3.70E45 1.23E45 2.11E 06 CS 138 5.52E-08 1.09E 07 5.40E NO DATA 8.01 E-08 7.91 E-09 4.65E 13 BA 139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E 11 1.72E47 BA 140 2.03E-06 2.56E 08 1.33E46 NO DATA 8.67E-09 1.46E48 4.18E-05

< BA 141 4.71 E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E 17 l BA 1'2 4 2.13E 08 2.19E-11 1.34E-09 NO DATA -

1.86E-11 1.24E-11 3.00E-26 l l.A 140 -

2.50E49 1.26E49 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 142 1.28E-10 5.82E-11 1.46E-11 NO DATA NO DATA NO DATA 4.25E-07

CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E 09 NO DATA 2.42E-05

' CE 143 1.65E-09 . 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21 E-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 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18  !

, ND 147 6.29E.00 7.27E-09 4.35E-10 NO DATA 4.25E 09 NO DATA - 3.49E-05 I

-W 187 1.03E-07 8.61E-06 3.01E-06 NO DATA NO DATA NO DATA 2.82E45 l NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E45

• Dose factors of latemal exposure are for continuous intake over a one-year period and include the dose commitment over a 50-year period; from Reg. Guide 1.109 (Rev.1). Additional dose factors for nuclides not included in this table may be ottained from NUREG 0172.

1 -

e 96.0 mm

I . .

03-12-97 08:06:17 Numbw g gy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 me . memon No.

Offsite Dose Calculation Manual (ODCM). 11 a

! TABLE 2.2 Bloaccumulation Factors, BF, -

1 s

, Blosecumulation Factors to be Used in the Absence of Site-Specific Data *

• l (pCl/kg per pCI/ liter) i, FRESHWATER ELEMENT FISH INVERTEBRATE.

, H 9.0E-01 9.0E-01 A C 4.6E + 03 9.1 E + 03 4

NA 1.0E+ 02 2.0E + 02 CR- 2.0E +02 . 2.0E + 03 I

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 MO 1.0E + 01 1.0E + 01 TC , 1.5E +01 5.0E+00 RU 1.0E +01 3.0E + 02 RH 1.0E + 01 3.0E + 02

• SB 1.0E + 00 1.0E + 00 TE ' 4.0E +02 6.1E + 03 1 1.5E + 01 5.0E +00 CS 2.0E + 03 1.0E+ 03 l 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'(Rev.1), Table' A-1).

" Sb bioaccumulation factor value is taken from EPRI NF-0840.

?

97.0 me,

03.-12-97 08:06:17 4

Numtw Nuclear ' "ad'*ad caat'*

Departmental Procedure 6610-PLN-4200.01 l TWe RevWon No.

i Offsite Dose Calculation Manuai (O.DCM) 11 2

3.0 TMI UQUID EFFLUENT WASTE TREATMF.NT SYSTEMS -

3.1 TMI-1 Uould Effluent Waste Treatment System 3.1.1 DescriNion of the 1: quid Radioactive Waste Treatment System (see Figure 3.1).

j Reactor Coolant Train .,

a. Water Sources - (3) Reactor Coolant Bleed Tanks (RCBT) i

- (1) Reactor Coolant Drain Tank (RCDT)

b. Uquid Processing - Reactor Coolant Waste Evaporator (see Figure 3.2)

- Domineralizers prior to release 4

c. Lkiuld Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks -

(WECST) ,

d. DIution - Mechanical Draft. Cooling Tower (048k gpm)

. - River Flow (2E7 gpm average)

Miscellaneous Weste Train ,

, a. Watcr sources: - Auxiliary Building Sump -

- Reactor Building Sump l

- Miscellaneous Waste Sturage Tank l j - Laundry Waste Stora0s Tank

- Neutralizer Mbdng. Tank l - Neutralizer Feed Tank

- Used Precoat Tank

- Borated Water Tank Tunnel Sump

- Heat Exchanger Vault Sump

-Tendon Access Galley Sump i

. , Spent Fuel Pool Room Sump

- TMI-2 Miscellaneous Wasta Holdup Tank l b. ~ Uquid Processing - Miscellaneous Waste Evaporator, MWE (see Figure 3.2)

. - Domineralizers orior to release I

c. Uquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks l (WECST) j i  !

d. Dilution - Mechanical Draft Cooling Tower (048k gpm)

] - River Flow (2E7 gpm average) 1 l

. 1 I

! 98.0 ms

1 . l 03-12-97 08106:17 '

bumber g g TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01

. me a.uon no. i Offsite Dose Calculation Manual (ODCM) 11  ;

3.2 ODerabilltV of the TMl-1 Llauld Efiluent Waste Treatment System i 3.2.1 The TMI-1 Liquid Waste Treatment System as described in Section 11 of the TMI-1 Final Safety Analysis Report is considered to be operable when one of each of the following places of equipment is avalable to perform its intended ' function:

I a) Miscellaneous Waste Evapordtor (WDL-Z18) or Reactor Coolant Evaporator l (WDL-Z1A)  !

) b) Waste Evaporator Condensate Domineralizer (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) j 3.2.2 TMI-1 Representative Sampilng Prlor to Discharge All liquid releases from the TMl-1 Liquid Waste Treatment System are med6 through the l . 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 Condensato Transfer Pumps.

3.3 TMl-2 Llould Effluent Weste Treatment Syste_m j .

3.3.1 Descdption of the TMI-2 Liquid Radioactive Waste Treatment System ,

The TMI-2 Liquid Radioactive Waste Treatment System has been out of service since the

~

t TMI-2 Accident in 1979. TMI-2 Liquid Radioective Waste is processed by the TMI-1 system

described in Sectin 3.1 prior to release. In addition, TMl-2 releases water from various sumps and tanks to the river (see Figures 1.1 and 1.2). These processes are governed by

' plant procedures that encompass proper sampling, sample analysis, and ~ radiation monitoring techniques.

I 99.0 me.  !

s I

03-12-97;08:09:56 I

Nurnber

' Nuclear " "*d* a'" "

• Departmental Procedure 6610-PLN 4200.01

. Title Fieviam No.

Offsite Dose. Calculation Manual (ODCM) 11

~

FIGURE 3.1 i

TIG 1 Liquid Radweste 8

RC B. A. M U-V8 d

MIX 4 _ ung ur I TANK RC DRAIN BWST SUMP d TANK R8 8.F. SUMP .

SUMP TEND. GAL. - -- pony 1

SAMPLE SUMP T 3 l f TANK 4 -

sam

~i AUX BLDG MISC. DRAIN -

vAcvse MSUMP - &. RELIEF

,r ir9r. Mr 1r 1r3r + A 4 4 4 TMI-2 ' NH RCBT A RCBTB RCBT C MWHT r MW8T i i l I

. bb 'b <b b

. 3r 3r 1r 1r ir

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CATION p PRECOATp i DEMIN . FILTER

• J PRECOAT CATION . t MAKE UP 4 FILTER -

DEMIN r TO MU'-V9

( 1 OF 2) (1 O F,2) 1r h

$r ir MISC. WASTE RC WASTE ' p.!8TILLATE EVAR - EVAP.

~

DISTILLATE

• 1r ir . U 4

RBAT CWST AUX M 4-.--- (1 O F 2)

(1 O F 2) STEAM i EMER.

BORATE HITTMAN e 1r + EFFLUENT + ,

BUILDING '

3 WECST v

RECLAIM (1 O F 2) COND.

DEMIN y WATER p i DEMIN WATER STOR TANK '(1 OF 2)

RECLAIMED WATER. SYSTEM 100.0' me.

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03-12-97 08:09:56 l mmber l

Nuclear " "adwoo'd contro

Departmental Procedure 6610 PLN-4200.01 noe m m.

i Offsite Dose Calculation Manual (ODCM)' 11 l

l FIGURE 3.2 l TMl-1 Liquid Weste Evaporators i

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i 7{ $

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03-12-97 08:09':56 ,

Number TMI Raidiological Controls I I Departmental Procedure 6610-PLN-4200.01  !

m FWeion No.

' Offsite' Dose Calculation Manual (ODCM) 11 4.0 GASEOUS EFFLUENT MONITOR (

] ,

- 4.1 TMI-1 Noble Gas Monitor SM Points

. I

The gaseous effluent monitor i;< points are established for each gaseous effluem radiation monitor' I to assure concentrations of radionuclides in Qaseous effluents do not exceed the limits set forth in  !

ODCM Part I Control 2.2.2.1. Table 4.1 lists Gaseous Efiluent 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 restrictNe set point concentration in the following two equations:

500 > E(c)(F)(K)(Dv) (eq 4.1.1) l

I i and

, 3000 > I(c)(I, + 1.1 M)(Dv)(F) (eq 4.1.2) i I

where:

c, - set point concent' ration based on Xe-133' equivalent, in pCl/cc F= gaseous effluent flowrate at the monitor, in cc/sec l

K, - total body' dose factor, in mrem /yr per pCl/m3 from Table 4.3 Dv - highest sector annual average gaseous atmospheric dispersiori factor (X/Q) at or j

, beyond the unrestricted area boundary, in sec/m8, from Table 4.4 for station vent i releases and Table 4.5 for all other releases, (Condenser off gas, ESF FHB, and ground 8

I releases). Maximum values presently used are 7.17E-7 sec/m at sector NNE for j 3 '

station vent, and 1.16E-5 sec/m at sectors N and WNW for all other releases.

i

13- ' skin dose factor due to beta emissions from radionuclide I, in mrem /yr per pCl/m8 from Table 4.3.

3 M, - air dose factor due to gamma emissions from radionuclide 1, in mrad /yr per pCl/m from Table 4.3.

l 4

1.1 = mrem skin dose per mrad air dose.

500 = annual whole body dose rate limit for unrestricted areas, in mrom/yr.

l 3000 = annual sidn dose rate limit for unrestricted areas, in mrem /yr.

i The set point concentration is further reduced sucti that the concentration contributions from j multiple release points would not combine to exceed ODCM Control limits.

The set point concentration'is converted to set point scale units on each radiation monitor using appropriate calibration factors.

]

102.0 -

mm

i

! 03-12-97 08:09:56 4

Nwntw i

ggggp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01

Title Rev6elon No.

J Offsite Dose Calculation Manual (ODCM) 11-This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure j

j and the procedure for Releasing Radioactive Gaseous Waste. 1 I

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. Number Nuclear ' "*d *' a'* o "*

Departmental Procedure - 6610-PLN-4200.01

m. am.on so.

Offsite Dose Calculation Manual (ODCM) 11 4

4 4.2 ' TMl-1 Particulate and Radiolodine Monitor Set Points Set points for monitors which. detect radionuclides other than noble gases are also estabilshed to assure that concentrations of these radionuclides in gaseous effluents do 'not exceed the limits of ODCM Part I Control 2.2.2.1.

i Set points are established so as to satisfy the following equations:

l 1500 > E(c)(F)(P)(Dv) (eq 4.2) t i . ,

where:

c=

i set point concentration based on 1-131 equivalent, in pCl/cc F-. gaseous ' effluent flow rate at the monitor, in cc/sec P-i pathway dose parameter, in mrom/yr per pCl/m 3for the inhalation pathway from ~ j Table 4.6. The dose factors are based on the actual Individual organ and most' '

restricdve age group (child) (NUREG-0133).

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) vith half lives greater than'alght days in mrom/yr. ,

Dv = higheel sector annual average gaseous dispersion factor (X/O or D/0) at or beyond the unrestricted area boundary from Table 4.4 for releases frorn the station vent and Table 4.5 for aR other releases. X/O is used for the inhalation pathway. Maximum 8

values of X/O gresently used are 7.17E-7 sec/m for station vent, at sector SE, and l

1.16E-5 sec/m for all other releases, at sectors N and WNW.

I The set point concentration is further reduced such that concer.tration contributions from multiple release points would not combine to exceed ODCM Control limits. .

i The set point concentration is converted to set point scale units on'each radiation monitor using

appropriate calibration factors. -

l l

This section of the ODCM is implemented by the Radiation Monitor Systems Set Points procedure l and the procedure for Releasing Radioactive Gaseous Waste. <

l l

• s 104.0 mm i

i l

i 03-12-97 08:09:56 i Numbw gggy TMI Radiological Controls ,

Departmental Procedure 6610-PLN-4200.01 4 no. n. con te.

t l Offsite Dose Calculation Manual (ODCM) 11 4.3 TMI-2 Gaseous Radiation Monitor Set Points 1

TMi-2 Gaseous Radiation Monitors have their set points described in TMI Plant Procedure 1101-2.1. l l Figure 4.5 provides a gaseous emuent release pathway diagram. 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. j d

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6 105.0' mm O

03-12-97 08

09:56 ..

l Number l 1 gggy TMI Radiological Controls Departrnental Procedure 6610-PLN-4200.01 me nevwon No.

Offsite Dose Calculation Manual (ODCM) 11 l

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-A5, RM-AIS, RM-AS, RM-A7, RM-A8, RM-A9, RM-A14. ALC-RMi-18, WHP-RIT-1, and RLM-RM-1. These I gaseous release points, radiation monitors, and sample points are shown in Table 4.1. Survellance l frequencies for TMI-1 out of plant monitors are specified in Table 4.1A. Surveillance frequencies for I TMI-1 in-plant monkors are epmf.ed Iri Part I of,the ODCM.

4.4.1 - RM-A4/RM-A6 Fuel Hpdin 2 and Auxiliary BuBdina Exhaust RM-A4 is the particulate, radiolodine and gaseous radiation monitor for the TMI-1 Fuel I

. Handling Building Ventiation (see Figures 4.1 and 4.2). RM-A6 is the particulate, I radiolodine, and gaseous radiation monitor for the TMI-1 Auxiliary Buiding Ventiation (see l Figures 4.1 and 4.2). High alarms on RM-A4 or RM-A8 noble gas channels wil initiate

)

I shutdown of the related buiding ventiation air supply system. These two radiation monitors' ,

' concurrently wil satisfy requirements for the Stattorf Vent release point in place of RM-A8. l 4.4.2 'RM-A8 Station Ventuation Exhaust -

1 RM-A8 is the particulate, radiolodine and gaseous radiation taonitor for the TMI-1 Station i Ventiation (see Figures 4.1 and 4.2).- This in plant affluent radiation monkor also has an I associated sampling panel with sampling lines located before the~ sample fBters. High alarm I on RM-A8 noble gas low channel wIl intiate shutdown of the Station VentBation air supply 4

systems.1The Fuel Handling and Auxillary Building VentBation).' This mdiation monitor satisfies requirements for.the Station Vent release point in place of RM-A4 and RM-A6.

4.4.3 'RM-A5/RM-A15 Condenser Off Gas Exhaust RM-A5 is the gaseous radiation rnonitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). RM-A15 is the back up gaseous radiation montor 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 wil Initiate the MAP-5 Radioiodine Processor Station. These two radiation monitors together satisfy requirements forthe Condenser Off Gas release point.

4.4.4 RM-A7 Waste Gas Decay Tank Exhaust t

~

RM-A7 la 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 I sampling panel. High alarm on RM-A7 noble gas channel wil Initiate shutdown of the Waste i 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 BuBdina Purae Exhaust l

- RM-A9 la the particulate, radiolodine and' gaseous radiation monitor for the TMI 1 Reactor Bulding Purge system (see Figures 4.1 and 4.3). This in plant offluent radiation monitor also has an associated sampilng 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

?

106.0 me,

6 i 03-12-97 08:09:56 Number ggp TMl Radiological Controls Departrnental Procedure 6610-PLN-4200.01 no. fwWon No.

l ,

Offsite Dose Calculation Manual (ODCM) 11.

. System release point.

4.4.6 RM-A14 ESF FHB Ventilation System RM.A14 is the gaseous radiation rnontor for the TMI-1 Ernergency Safeguards Features I (ESF) Fuel Handling Bulding Exhaust system (see Figures 4.1 and 4.2). This in plant l I effluent radiation monitor also has an associated sampilng panel with sampilng lines located I before the sampler fliers. High alarm on RM-A14 noble gas channel wHi Initiate shutdown of

' the ESF Fuel Handling Building Exhaust System. This radiation monitor satisfies requirements for the ESF Fuel Handling Building Exhaust System release point..

~

$ 4.4.7 ALC-RMI-18 Chemical Cleanina Faculty (CCF) Ventilation Exh_ gag l

4 ALC-RMI 18 is an Victoreen particulate, radiolodine, and gaseous radiation monitor for the  ;

Chemical Cleaning building exhaust.' ' Presently, the radiolodine channel is not in use. This I I

monitor is located in the Chemical Cleaning bulding on the Ground floor, and has an associated sample panel. Samplin0 for particulate actMty is performed off of the monitor.

4.4.8 WHP-RIT-1 Waste Handeiro and Packaolno FacNRy (WHPF) Exhaust

! WHP-RIT-1 is an Ebertine AMS4 particulate radiation monitor for the TMl WHPF. The monitor is located in the Mechanical Equipment Room in the WHPF. Sampling for .

particulate actMty is performed off of the monitor. A high alarm wil initiate shutdown of the '

ventBation air exhaust system-1 4.4.9 RLM-RM-1 Respirator Cleanino and Laundry Maintenance (RLM) Fac5tv l RLM-RM 1 is an Ebertine AMS-3 particulate radiation monitor for the TMI RLM Facity. The monitor is located in the Mechanical Equipment Room in the RLM. Sampling for particulate activity is performed off of the monitor.

,1 l

s 107.0 me.

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. . Number j TMI Radiol'ogical Controls ggE Departmental Procedure 6610-PLN-4200.01 noe h m No.

J Offsite ' Dose Calculation Manual (ODCM) 11 4

4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data

~

TMI-2,has three (3) regulatory required gaseous effluent radiation monitors. These are HP-R-219, HP-R 219A and HP-R-225. These gaseous release points, radiation monitors; 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 Ventiation Exhaust HP-R-219 is.a Victoreen particulate and gaseous radiation monitor for the TMI-2 ventilation exhaust. This in-plant effluent radiation monitor is located .In the TMI-2 AuxElary Bulding 328 foot elevation and has an associated sample panel. ,

, 4.5.2 'HP-R-219A Station Ventiation Exhaust HP-R-219A is a Victoreen particulate and gaseous radiation monitor for the TMI-2 ventilation exhaust. This in-plant ofnuent radiation monitor is located in the TMI-2 Aux 111ary Building 328 foot eleva6on.

4.5.3 HP-R-225 Reactor Buldina Purae Air Exhaust Duct 'A' HP-R-225 is a Victoreen particulate and gaseous radiation monitor for the TMI-2 Reactor

- Bulding Purge Air Exhaust System' This In-plant effluent radiation monitor is located in the TMI-2 Auxliary Building 328' elevation area. -

i 1

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i 108.0 me

m I

03-12-97 08:09:56 -

Number -

4 glgy TMI Radiological Contrcis Departmental Procedure 6610-PLN-4200.01 l

noe twmon No.

I Off's ite Dose Calculation Manual (ODCM) 11 4.6 Control of Gaseous Effluent Releasee j TMl gaceous efiluent combined releases are controlled (per ODCM Part I for TMI-1 and ODCM Part 11 for TMl-2) by effluent sampling and radiation monitor set points. These measures assure that

. releases from the various vents do not ec.T.b.we pioduce dose rates at the' site boundary l l exceeding the most restrictive of 500 mrom per year to the total body or 3000 mrem per year to the l 1

skin, and 1500 m' rem per year to the thyroid.' This is done by restricting simultaneous releases and d

by limiting the dose rates that may be contributed by the various vents at any time. .The various vent radiation monitor set points are each based on fractions of the above limits and do not exceed the above limits when summed together. These effluent radiation monitor set points are calculated using the methodology described in equations 4.1.1, or 4.1.2 and 4.2. The actual set points are then

listed in TMI-1 Operations Procedure 1101-2.1.

i The radioactive content of each batch of gaseous waste is determined prior'to release by sampling and analyses in acccidiciO6 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 Secdons 4.1 and 4.2 to assure that the dose rates at the site boundary are maintained below the limits in ODCM Part I for TMI 1 and. ,

ODCM Part 11 for TMI-2.

Post-release analyses of samples'composited from batch and continuous releases are performed in accordance with ODCM Part i for TMI-1 and ODCM Part 11 for TMI-2. The results of the analyses are used to assure that the dose rates at the site boundary are maintained within the limits of ODCM Part I for TMI-1 and ODCM Part 11 for TMI 2.

t 4

109.0 mm o

3 -

J

. 03-12-97 08:09:56 Number Nuclear * "ad

• oom'*

Departmental Procedure 6610-PLN-4200.01 Tide Revision No.

Offsite Dose Calculation Manual (ODCM) -

11 t

, TABLE 4.1 1

TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data l

1 RELEASE GASEOUS TERMNATION RADIATION GASECUS (F) , INTERLOCK MONITOR RELEASE FLOW (YES/NO)

(DETECTOR) LOCATION POINT RECORDER VALVES

'YES AR E10 AHO120 Fuel Hand.

2 306* Bevaton Building AH D-121 l RM-A4 AuxlRary Bldg. Exhaust FR140 AH-D 122 Auxuiary 308' Elevation' Building YES

RM-A8 AuxHiery Bldg. Exhaust FR150 AH E 11 YES

, WDG-V47 i AH E-10 AH-E 11 RMA8/9 Bldg. , . Starts MAP 4 Near BWST Station FA149 Hadiolodine i

RMM Exhaust Vent & FR1F0 Sampler i

• YES 322' Elevation Condenser Starts MAP 4 ,

Sacorid Floor Off Gao Radiolodino j i RMM Turbine 8tdg. Exhaust FRt113 Sampler j YES 322' Sevation Condenser Starts MAP 4

) Second Floor - Off Gas Radiolodine i RMA15 Turbine Bldg. Exhauet FR 1113 Sampler I

Wasie Gas e 300' Elevation Decay Tanks YES

' RM-A7 Aux 51ery Ridg. (A,B,C) - FR 123 WDG V47 YES AH V 1A/B/C/D

, Reactor WDG434/536 Duilding Starts MAP 4 RMA4/9 Bido. Purge FR 900/ Radioiodine RIAA9 Near BWST Exhaust FR 148 Sampler 331' Eevation ESF FHB . ESF Fuel Outelde Handling NO 4

Chem. Suuding Manual RM A14 Addition Bldg. Exhaust FR 1104A/B Actions j

9 E

'110.0 me.

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i 03-12-97 08:09:56 -

Number jgp TMl Radiological Controis Departmental Procedure 6610-PLN-4200.01 Te .

. sw. ion No.

l Offsite Dose Calculation Manual (6DCM) 11 r

TABLE 4.1 (Cont'd)

TMI-1 Gaseous Release Point and Gaseous Rediation Monitor Data-GASEOUS RELEASE RADIATION GASEOUS TE7MNATION

• MONITOR FELEASE INTER.OCK

(DETECTOR) LOCATION POINT ((ES/NO) VALVES Chemical Oeening CC8 Exhaust j 'ALC AMI.18 Bldg. 304' Elevapon System NONE ,

YES .

WHPF Mechanical WHPF Exhaust WHPF Vendlauon WHP-RIT 1 Equipment Room System Tripe l RLM.Mechanteel F4.M Exhauet j IU4RM1 Equipment Room System NONE

! ' TABLE 4.1 A l

TMI-1 Out of Plant Radioactive Gaseous Monitoring instrumentation Surveillance Frequencies i .

1

CHANNEL QiANNEL CHANNEL INSTRUMENT CHECK. CAL!BRATION FUNCTIONAL TEST ALC.RMi-1s G D E Q l ALC RMI-1s P W E Q

! WHP.RfT-1 D SA W a

RLM.RM D SA W See Page 63.0 Table 1.1 for frequency notation explanation.

4 4

4 i

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111.0 me.

1 03-12-97 08:09:56 Number gggy. TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 1 Tese Revmon No.  ;

i Offsite Dose Calculation Manual (ODCM)' '-*

11 )

l

l 3 TABLE 4.2 i TMl-it Geseous Release Point and Gaseous Redistion Monitor Data i

RELEASE GASEOUS TERMINATION 1 RADIATION GASEOUS INTERLOCX l

MONITOR RELEASE (YES/NO)

(DETECTOM LOCATION POINT VALVES i

32s' Bevenon Station ,

Auxisery Vent j HP-R 219 Buildin0 Exhaust NONE

. 32s'sevation

, Auxiliary Stamon Vent

, HP-R 219A Bulksng Exhaust NONE i Ruotor sido 32s* Beve6cn Auxiliary Purge Exhaust i HP-R-225 Bt. Ming Duct "A* NONE i .

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03-12-97 08:09:56 Number i Nuclear '"*d'*a -

Departmental Procedure 6610-PLN-4200.01 I

I ime Mon No.

i Offsite Dose Calculation Manual (ODCM) 11 i

TABLE 4.3 Dose Factors for Noble Geses and Daughters

• Gamma ' Beta .

Total Body Skin Dose Garnma Air. Beta Air j Dose Factor (a) Factor (b) Dose Factor- Dose Factor t3 Mi N, Radio. (mrom per (mrem /yr per (mrad /yr per (mrad /yr nuclide pCl/ ) pCl/m3) pCl/ms) pCl/m l 1

Kr-83m 7.56E-02** - 1.93E + 01 2.88E + 02 l

, Kr-85m 1.17E + 03 1.46E + 03 1.23E +03 1.97E + 03 i

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 -

4 Kr-88 1.47E + 04 2.37E + 03 ' 1.52E+ 04 2,93E + 03 l

i Kr-89 1.8eE +04 1.01 E + 0'4 1.73E + 04 1.06E + 04 Kr-90 1.56E +04 7.29E +03 1.63E + 04 7.83E + 03 I Xe-131m 9.15E+01 4.76E + 02 1.56E + 02 1.11 E+ 03 -

Xe-133m 2.51E + 02 9.94E + 02 3.27E +02 1.48E +03 4 Xe-133 2.94E + 02 3.06E + 02 3.53E+02 .1.05E + 03 l Xe-135m 3.12E + 03 7.11E + 02 3.36E +03 '7.39E + 02 2.46E + 03

)

Xe-135

~

1.81E + 03 1.86E + 03 1.92E + 03 Xe-137 1.42E +03 1.22E + 04 1.51E+ 03 1.27E+ 04 Xe-138 8.83E + 03 4.13E + 03 9.21 E + 03 4.75E + 03 Ar-41 8.84E + 03 2.69E + 03 9.30E + 03 3.28E + 03

• Dose factors are for immersion exposure in uniform semi-infinite cloud of noble gas radionuclides that may be detected Ingaseous effluents. . Dose factor values are taken from Regulatory Guide 1,109 (Rev.1), Table B-1.

• • 7.56E-02 = 7.56 x 10-2, (a) Total body dose factor for gamma persuation depth of 5 cm into the body.

'(b) Skin dose factor at a tissue depth or tissue density thickness of 7 mg/cm2 ,

113.0- me

)

03-13-97 08:09:56 Number TMl Rad 10 logical Controls

! GMCiSar ~ o,p itmental Procedure 6610-PLN-4200.01 l rm. a m on16.

J-Offsite Dose Calculation Manual (ODCM) 11 TABl.E 4.4

- Atmospheric DI8persion Factors for Three Mlle Island

)

• STATION VENT . OfSTANCE 4

, o SECTOR AVERAGE X/O ON SEC/M .3) ON METERS) SEASON - ANNUAL l SECTOR 610 2413 - 402L 6631 7240 12067 24135' 40225 50315 72405 l j N 1.18607 5.32E-07 2.96607 193607 1.30E47 5.52E48 1.91Em 5.02E-00 1.88E40 1J00E40 NNE 1.70E47 7.17E & 3.45E 07 2.00E47 1.30E47 5.58E M 1.70E48 4.77500 1.98E 00 960510 i NE 1.12507 1.75E47 3.2eE47 1.88E-07 1.21E 07 500E 6 1.67E 08 4.67E40 1.85E@ 0.93510 I

ENE 1.00E47 2.13EW 2.67507 1.53E47 1.05E& 4.31E-08 1.42E48 4.42500 1.50500 8.64E-10 )

E 2.31E-07 1.71E& 1.52507 1.40E47 1.08E47 4.63E-08 1.52508 5.19E40 2.48E 00 1.50500 )

ESE 3.50E 07 2.12E 07 2.50E47 1.48E47 9.48Ee 3.98EM ' 1.80Ee 5.92E40 2.02000 1.93600

SE 4.10007 3.79E47 2.53EW 1.55E W 1.11E-07 ' 4.82E48 1.81E@ 6.84600 3.30E-00 2.22600 l SSE 2.90EW 3.82E 07 2.55E-07 1.40E47 1.11E47 5.02608 1.98E-08 6.97500 2.94E 00 1.70500 S 1.87E47 6.47508 2.16EW 1.30E47 8.85EG 4.00E-08 1.40608 4.96E40 1.90600 1.04E40 1 SSW 6.13E 08 4.18EG 1.56EW 1.0SE47 6A1508 2.72Ee 9.74500 3.01E 00 1.50500 8.23E-10 .

SW 5.78E-08 1.14E47 1.70E47 1.05607 6.93608 2.51008 9.34E 00 ' 2.72E 00 1.33E49 8.33E-10 WSW 8.52E-08 3.75E-07 ' 2.14E47 1.26E-07 7.74500 3.08608 1.02508 3.28E40 1.30E-00 9.60510 W 1.15E47 5.80507 2.88E47 1.63E47 1.18E47 5.23508 1.72E48 5.08600 1.98500 1.25E-00 WNW 1.41547 6.28E-07 3.30E47 2.10E47 1.48E 07 5.08E.08 1.95608 6.32500 2.18E40 1.34600 i

NW 1.42607 5.67507 3.17E-07 1.93E47 1.30E47 5.67E-08 2.06608 5.90500 2.70E@ 1.45E40 NNW 1.00E47 5.77E47 3.18E47 1.00507 1.27E47 5.20E M 1.77EM 4.82E 00 2.01600 1.22500 i

1

• STATION VENT DISTANCE e SECTOR AVERAGE D/O ON M-2) ON METERS) SEASON ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135

• 402't5 56315 72405 N 2.51E40 8.72E-10 4.84510 2.98610 2.50E-10 8.57E 11 2.51E-11 4.98612 1.57512 7.84E13 NNE 3.80600 1.98E-00 9.54610 4.90610 '3.38610 1.10E 10 2.80E-11 6.06612 2.10612 8.00E 13 I. NE 2.58E-00 6.70E-10 0.13610 4.91510 2.97E-10 1.04510 2.87611 8.01512 1.90E-12 9.23513 ENE 2.15E40 5.85610 5.54610 3.00E 10 2.08610 8.30E 11 2.32 & 11 5.41512 1.63612 7.64513 l E 5.54E-00 1.23500 6.17610 4.50610 3.63510 1.34E-10 3.88611 9.44E-12 3.77512 1.97E12 ESE 9.17E40 2.05500 1.51E-00 8.00610 5.11E-10 1.82610 5.77E11 1.72E11 7.07E-12 4.07612 SE 1.22E-06 2.88500 1.84500 1.02E-00 6.85E-10 2.00E-10 8.30E-11 2.34E-11 9.42512 551512 SSE . 7.50600 1.62E40 1.08500 5.80E 10 4.40E 10 1.87510 6.16511 1.61611 5.67E-12 2.83E-12 l

. S 3.86E40 8.53610 6.27510 3.50610 2.32610 1.08610 3.05511 8.10612 2.73612 1.23512 SSW 1.13E-00 2.94610 4.19510 2.53510 1.56510 5.38611 1.88E-11 3.91E-12 1.64512 7.84G13 q

SW 1.19500 3.84E10 4.98610 2.80E-10 1.70610 5.24G11 1.65E-11 3.62E 12 1.40E-12 8.12E-13 WSW 1.77E40 8.31510 6.40E-10 3.50E-10 1.90E 10 6.73611 1.80511 4.58G12 1.63E-12 9.90E 13 W 2.41E-00 1.20600 6.81E-10 3.05610 2.96610 1.12E-10 3.11E-11 6.90E 12 2.26612 1.25E-12 WNW 3.20E-00 1.30G00 '7.73610 5.01510 3.66610 1.19610 3.43611 6.30E-12 2.30512 1.29E 12 1

NW 3.25E.00 1,23E40 7.30E-10 4.22510 2.77E-10 1.14510 7.28611 7.61612 2.92E-12 1.36E-12 NNW 1.98600 9.88610 5.71E-10 3.05E-10 2.23610 8.21E-11 2.41E-11 4.03512 1.72612 9.03513 i

' DATA FROM 1/1/78 THROUGH 12/31/06 USED Pf CALCUtATIONS 114.0 me

l

- 1 1

03-13-97.08;09:56  !

Number d EI TMt Radiological Control 8 Departmental Procedure 6610-PLN-4200.01 d

Tine Revtalon No.

i Offsite Dose Calculation Manual (ODCM) 11 TABLE 4.5 Atmospheric Dispersion Factors for Three Mile Island

e GROUND RELEASE DISTANCE e SECTOR AVERAGE X/O ON SEC/M3) .,

(IN METERS) SEASON ANNUAL j SECTOR 610 2413 4022 5631 7240 12067 24135 40225 58315 72406 N 1.16Em 1.13E-06 5.94E47 3.80E@ 2.38507 9.74E48 3.45E48 9.28600 3.52EG 2.05E40 NNE 1.08E45 1.10506 568E47 '3.41507 2.38E47 9.56E 08 3.11E-08 8.04E40 3.74500 1.84E40 NE 7.02E46 9A1E-07 5.42E47 3.17E47 2.10E47 9.01E-08 3.10EG 8.87500 3.54EG 1.91E-00

, ENE 7.14E46 0.64507 4.02607 2.85E47 1.97E47 7.82E 08 2.64E-08 8.38E 00 3.04E40 1.66E40 j E 8.40E46 1.00E46 5.48507 2.91507 1.87E-07 8.40EM 2.82508 9.85500 4.75E40 2.87E00

' 5.54500 ESE 6.91E48 9.02E47 4.40E47 2.57E47 1.67507 7.20508 2.77E48 1.12E-08 3.68E 00 l SE 6.70506 9.08E47 4.83E47 - 2.81E47 2.0SE47 8.94508 3.33Ee 1.28E4 6.19600 4.18E40 SSE 7.28508 9.25E 07 4.91E 07 2.87E 07 2.08E47 0.18E-08 3.72Ee 1.32508 5.82E40 3.26E40

& 8.70E-06 9.08E-07 3.00E47 2.41E47 1.61507 7.31E46 2.57E48 923E 00 3.74E40 1.95E00

SSW 6.05508 7.01E47 2.75E47 1.86507 1.24E47 5.08608 1.82Em 571E40 2.87E40 1.58E40 SW 5.91506 5.71E47 2A6E-07 1.81E47 1.22507 4.50E48 1.72E48 5.12600 2.53E40 1.5GE40 WSW 840E46 7.02E47 3.80E47 2.15E47 1.34E47 5.50E48 1.87E48 6.12E.00 ' 2.82E 00 1.83E 00 W 1.02E 05 1.07EG 5.30E 07 3.02E47 205607 9.31508 3.15Em 9.48E-00 3.74E 00 2.38500 l WNW 1.16606 1.13E46 5.98E47 3.67E47 2A3E-07 1.00607 3.56E46 1.18E48 4.07500 2.54E 00 l

NW 1.13006 1.00E 06 5.70E47 353607 2'40E47 1.02E47 3.82508 1.11E48 5.1450s 2.78500 .

NNW 1.08E-05 1.04506 5.72E-07 3.2TE47 2.22607 9.06E 08 3.20508 8 AGE 40 3.75E40 2.29E40 4

eGROUND RELEASE DISTANCE e SECTOR AVERAGE D/O (IN M 2) (IN METERS) SEASON ANNUAL SECTOR 610 2413 4022 5631 7240 12087 ~ 24135 40225 56315 72405 N 2.30E-08 1.88E40 8.93610 4.82E10 2.70610 8.98E 11 243511 4.98612 157E12 7.84E 13 NNE 2.86508 2.25E40 1.08E40 5.42E10 3.38610 1.10E-10 2.80E-11 6.08E-12 2.10E-12 8.89513 NE 175E m 2.00E-00 1D1E40 5.04610 2.98510 1.04510 2.88611 6.01E-f2 1.90E-12 9.23E-13 l l

ENE 1.68E48 1.85E-00 8.86E-10 4.2tE-10 2.06510 8.57E11 2.33611 5.41E-12 1.63612 7.64E-13 E 2.88608 2.90E40 1.30600 6.34 E-10 3.67510 1.35510 3.88511 9.42512 3.77512 1.97612 ESE 3.50E48 3.80600 1.77500 8.79E-10 5.15510 1.83510 5.78511 1.71E11 7.06612 4.06E '12 SE 4.12608 4.55500 2.13E40 1.15E-00 7.50610 2.72E-10 ' 8.31511 2.34511 9.42E-12 5.50E-12 SSE 3.12E-08 3.23E40 1.50E40 8.00510 5.20510 1.88610 6.18E-11 1.81E 11 5.86E12 2.83D12 S 2.65508 2.21E 00 9.0TE-10 4.75E 10 2.86610 1.0TE-10 3.00E-11 8.10612 2.73612 1.23E-12 SSW 1.45608 1.30600 4.80E-10 2A2510 1.70610 5.71511 1.00E-11 3.91512 1.64E-12 7.84E-13 SW 1.42E 06 1.10500 5.15510 2.82E-10 1.71510 .524511 1.65E-11 3.62512 1.40612 8.12E 13 WSW.. 2.01E 08 1.41E40 6.82E 10 3.54510 2.00E-10 6.76611 1.80511 4.58612 1.63E-12 9.90613 i W 2.55E48 2.16E-00 1.00E40 4.91510 3.01E-10 1.12510 3.11511 6.90612 2.27E-12 1.25512 i WNW 2.88E48 2.30500 1.13E40 5.93E-10 3.67E 10 1.19610 3.43611 8J6E-12 2.30512 1.29E-12

' NW 2.78E48 2.15E40 148E40 - 5.5aE-10 3.41510 1.19610 3.57511 7.61512 2.92E-12 1.3eE 12 NNW 2.17E-08 1.75500 8.75510 4.24610 2.57E-10 8.55511 2.42611 4.93512 1.72512 9.03E13 DATA PROM 1/1/78 THROUGH 12/31/88 USED IN CALOLA.ATIONS 115.0 me

03-12'-97 08:09:56 Numbw NMar '"i aad' ' S'o*' contro

Departmental Procedure 6610-PLN-4200.01 Lo* Revleion No.

Offsite Dose Calculation Manual (ODCM) 11 I

1 TABLE 4.6 Dose Parameters for Radiolodines and Radioactive '

Particulate in Gaseous EfRuonts* I CRITICAL ORGAN CRITICAL ORGAN  !

NUCUDE ORGAN FACTOR Pl* ** NUCUDE ORGAN FACTOR ' Pl"*

l H-3" TOTAL BODY LUNG 1.79E-04 6.62E +05 3.04E-07 1.12E + 03 RU-103 C 14 BONE 9.70E 06 3.59E +04 RU-105 GI-LLI 2.69E-05 9.95E + 04 NA-24 TOTAL BODY 4.35E46 1.61E + 04 RU-106 LUNG 3.87E43 1.43E + 07 P-32 BONE- 7.04E-04 2.60E + 06 AG-110M LUNG 1.48E43 5.48E+06 CR-51 LUNG 4.59E-06 1.70E + 04 TE-125M -

LUNG 1.29E-04 4.77E + 05 MN-54 LUNG 4.26E44 1.58E + 06 SB-125 LUNG 6.27E-04 2.32E + 06 MN46 GI-LU 3.33E-05 1.23E + 05 TE-127M LUNG 4.00E-04 1.48E + 06 l I

FE-55 LUNG 3.00E-05 1.11 E + 05 TE-127 GI-LLI 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 GlG 6.89E-06 2.55E + 04 C040 LUNG 1.91E 03 7.07E + 06 TE-131M GI-U.I 8.32E 05 3.08E+05 NI 83 BONE 2.22E 04 8.21 E +05 TE-131 LUNG 5.55E 07 2 05E+03 -

NI-66 GI-LLI 2.27E45 8.40E + 04 TE 132 LUNG 1.02E 04 3.77E+05 CU-64 Gl-LU ' 9.92E-06 3.67E + 04 l-130 TYHRotD 4.90E-04 1.85E + 06 .

ZN45 LUNG 2.69E-04 9.95E + 05 l-131 THYROID 4.39E 03 1.62E + 07 ZN-69 GI-LU 2.75E-06 1.02E + 04 l-132 THYROID 5.23E-05 1.94E+05

, BR43 TOTAL BODY" 1.28E 07 4.74E + 02 1-133 THYROID 1.04E-03 7 3.85E + 06.

BR-84 TOTAL BODY 1.48E-07 5.48E + 02 1-134 THYROID 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 1.01E + 06 - .

RB48 UVER 1.52E-07 5.62E +02 CS-136 UVER - 4.62E-05 1.71 E+ 05 RB49 UVER 9.33E-08 3.45E + 02 CS-137 BONE 2.45E-04 9.07E + 05 i SR-89 LUNG 5.89E 04 2.16E + 06 CS-138 UVER. 2.27E47 8.40E4 02 1 i

SR-90' BONE. l 2.73E 02 1.01 E +08 - BA-139 Gl-LU 1.56E-05 5.77E + 04 SR-91 GI-LU 4.70E-05 1.74E + 05 BA-140 LUNG 4.71E 04 - 1. 74E + 06 SR-92 GI G 6.55E 05 2.42E + 05 BA-141 LUNG 7.89E47 2.92E+03 Y-90 GI G 7.24E-05 2.68E + 05 BA-142 LUNG 4.44E 07 1.64E + 03 l Y-91M LUNG 7.60E 07 2.81 E + 03 LA-140 GI-LU 6.10E45 2.26E + 05 Y-91 LUNG 7.10E44 ' 2.63E +06 LA 142 GI-LU 2.05E 05 7.59E + 04 Y-92 GI-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 +06 CE-144 LUNG 3.23E-03 1.20E+ 07 ZR-97 GI-LU 9.49E-05 3.51E + 05 PR-143 LUNG 1.17E-04 4.33E + 05 NS-95 LUNG 1.66E 04 6.14E + 05 PR-144- LUNG 4.23E-07 1.57E + 03 MO-99 LUNG 3.66E-05 ~ 1.35E +05 ND-147 LUNG 8.87E-05 3.28E + 05 TC-99M GI G 1.30E 06 4.81E + 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

-" Ine usted dose parame;ers are for radonucudos, other than noDie gases that may oe datarw in gaseous effluents. Pi factors include all nonstmospheric pathway transport parameters, the receptor's usage of pathway media, and are based on the most restrictive age group (chid) critical organ. Additional dose parameters for nudides not included in this Table may be calculated using the methodology described in NUREG-0133.'

• • Tritium dose factors include an increa'se of 50% to account for the additional amount of this nuc!Ide absorbed throu0h the skin.

"* mrom/ year per pCl/m8.

~

116.0 m

= .

03-12-97 08:09:56 Number E NucIear-Trtle TMI Radiological Controls o,% r,oc ou,, 3 ptu.42co.oi Revleion No.

11  !

Offsite Dose Calculation Manual (ODCM) .

FIGURE 4.1 TMI-1 Gaseous Effluent Pathways e

n FIGURE 4.1 0307'"* EM*2 Lt.'.=.m "th

e.' =*am

.E ._

AUXILLARY BUILDING eases m .  % 4 P A C C A P l m.ay F. _ _

woors0 0 0- ,Imal . auum 4

, IBGE I lRMA14, f $

3 H' y IIna"~ 7 -M W FUEL espo an v HANDUNG E="=

BUILDING g. wu

~

N P-PRE FILTER im '"* 4 A-ABSOLUTE HEPA C-CHARCOAL FILTER um M $

C-IvT l 117.0 nm

I 03-12-97 08:09:56

, Number TML Radiological Controls NgEI .

Departmental Procedure 6610-PLN-4200.01

m. a. u on No.

Offsite Dose Calculation Manual (ODCM) ,

11 RGURE A2 TMI-1 Auxiliary and Fuel Handling Buildings Effluent Pathways l

g --- i un j

" ,j, see m l WA8 mm aus a e gPAC i

g era:t b

ws RM-A6 enn sw RM-A14

. RN-A4 mm em n f ESF REL g P A AOL My $ wiu - C -

1 3

/

BUILMNG

$ A n A REL HANDLING-

/ at at at BUILDING i

% a.v v 3 t v

~

AUXlLIARY AND flEl HANKING BUILDMS EXHAUST RADIAll31 lE t ' 0*R SlT[RSANDSARINGSTATENS l

i i

i 118.0 me

03-12-97 08:09:56

~

Number Nuclear "Departmental oa -Procedure

• 8610-PLN-4200.01 Tine . Asvtekm No.

Offsite Do'se Calculation Manual (ODCM) ~11 l

FIGURE 4.3 TMl-1 Reactor Building Effluent Pathway ,

l l

i 4

nur 170 m_

FEET  !

REACTOR BUILDING PURGE EXHAUST RADIAil0N MONITORS AND .

SAMPLING STATIONS m

m O. -

r A .

sata

. PMU REACTR BUILDING ) -

s' aire ese A

- g , amn 200131M.

EER llLBE SAWOE MIDE MW r:pastAE A AREUE C = OWEDL 4

0 0

119.0 mm s

- . . . . . - . . ~ . . - - - . . . - ._ ..

i 03-12-97 08:09:56 i Number i

E Nuclear TWe TMi Radiological Controls op prwure 6610-PLN-4200.01 Rwison No, j Offsite Dose Calculation Manual (ODCM) 11 j FIGURE 4.4

', TMI-1 Condenser Offgas Effluent Pathway -

CONDENSER OFF GAS STACK 3 CDNDENSER OFF GAS 115 -cas EXHAUST-FEET RADIATION MONITORS AND SAMPLING STATIONS.

N

55t" i

/

m w p MAIN.

m C0NDEN.SER V ,

. a. .

l l

ca.nonse '

%5T'm< l

(

I i

120.0 me.

• *  :  ! ,r' li  ; j :;;:! ,. .' Ihl, e ,

Om,Hm ea O8 . "

F ,

yr;tN = pI.

0m o1t 5 3 eiE4,8h ,

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g K8 ,D5k g =x,all_. jOu- -

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s ,. ge" g(pa54%s1 o=

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s. i g'

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=

1 03-12-97 08:09:56 Number i Radid gu Contmis 1

- GUCIO8r Departmental Procedure 6610-PLN-4200.01 Two  %.on No.

Offsite Dose Calculation Manual (ODCM) 11 5.0 GASEOUS EFFLUENY DOSE ASSESSMENT ,

5.1 Gas'eous Effluents -Instantaneous Release Limits ,

! 5.1.1 Noble Gases For noble gases, the following equations apply for tot'al. body and skin dose rate at the unrestricted area boundary-5.1.1.1 Total Body

' (eq 5.1.1.1)

Dose Rate = I(Ig) x,(Dv) x (Q)

I ,

~where:

Dose Ratet b = instantaneous total body dose rate limit, at the site boundary, in mrem /yr.

i . .

K=

i total body dose factor due to gamma emissions for each identified noble i gas radionuclide, in mrom/yr per pCl/m3from Table 4.3.

l Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m8, frorn Table 4.4 for I i station vent releases; and Table 4.5 for all other releases (Condenser Off I Gas, ESF FHB, and ground releases). Maximum values presently in use 3

are 7.17E-7 sec/m3 at sector NNE for station vent, and 1.16E-5 sec/m for all other releases, at sectors N and WNW. -

Q= 3 Release' rate of radionuclide, I, in pCl/sec as determined by sampling and

, analysis. Calculated using the concentration of noble gas radionuclide, I, l In pCl/ce, times the release pathway flow rate, in cc/second j l

1 E

O 4

4 i

i 122.0 me,

o - l l

' l 03-12-97 08:09:56 l l

Nurnber 1 4 gggy , TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 l

l

, Title Revision No.

Offsite Dose Calculation Manual (ODCM) 11 i

l 5.1.1.2 Skin j l

i 4

Dose Ratog = Z (y + 1.1 M) X (Dv) X (Q) (eq 5.1.1.2) l l

, where: l l Dose Rate, = Instantaneous mrem / year skin dose rate limit, at the site boundary, in mrom/yr.

4= skin dose factor due to bem emissions for each identified noble gas

radionuclide, in mrem /yr per W/m 8from Table 4.3.

l M-i air dose factor due to gamma emissions for each identified noble gas i radionuclide, in mrad /yr per pCl/m8from Table 4.3.

1

1.1 = mrom skin dose per mrad air dose. Convert's air dose to skin dose.

l Q, = release rate of radionuclide,1, in pCl/sec, as determined b'y sampling and 3 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/Q) at or

s beyond the unrestricted area boundary, in sec/m , from Table 4.4 for .

station vent releasps; and Table 4.5 for all other releases (Condenser Off i Gas, ESF FHB, and ground releases). Maximum values presortly in use 3

e are 7.17E-7 sec/m8 at sector NNE for station vent, and 1.16E-5 sec/m for

all other releases, at sectors N and WNW.

. I i

9 .

4 4

123.0 mm d

4

= .

03-12-97 08:09:56 J Number Nuclear " "*d'o'oa'ca' coa"d*

Departmental Procedure 6610-PLN-4200.01 rm.- a.v,= no.

1 Offsite Dose Calculation Manual (ODCM) 11 5.1.2 lodine-131. Iodine-133. Trtium and Radionuclides in Particulate Form. with Half-Lives Greater than 8 Days

! For.1-131,1-133, Tritium and Radionudidos in Particulate Form, with half 4fves greater than 8

days, the following equation app,Iles

i .

Doce Rate, = E (P) (Dv) (Q) (eq 5.1.2) i I

where:

Dose Rateip - mrom/ year organ dose rate.

P-i dose parameter for 1131,1-133, Trtium and Radlonuclides in Particulate j Form, with half 4h'esproater than 8 days, for the inhalation pathway, in mrem /yr per pCl/m , from Table 4.6. The dose factors are based on ,the critical indMdual organ and .ost restrictive age group (child).

I Dv = highest sector annual' average gaseous dispersion factor (X/Q or D/Q) at j or beyond the unrestricted area boundary, in sec/m 8, fro'm Table 4.4 for

, the station vent releases and Table 4.5 for all other releases. X/Q is used for the ir,halation pathway. Maximum values of X/O presently used are j 7.17E-7 sec/ms for station vent, at sector NNE, and 1.18E-6 sec/m3 for all

other releases, at sectors N and WNW.

1 .

] Q=i release' rate of each radionuclide, I, in pCl/sec. Calculated using the i concentration of each radionucilde, I, in pCl/ce, times the release pathway flow rate, in oc/second.

l ,

t 4

j 124.0 m=

. -- - . . - . - . . . + . - - .n- w. -- .~-_x-+s.-. .

03-12-97 08:09:56 Number Nuclear ' Radido**' coad8 Departmental Procedure 6610 PLN-4200.01 me twmon No. )

Offsite Dose Calculation Manual (ODCM) 11 5.2 Gaseous Effluents - 10 CFR 50 ADoendix I Noble Gases 5.2.1-s The air dose in an unrestricted area due to noble gases released in gaseous offluents from the site is determined using the following expressions: l Dose r = (3.17E-8) x I(M) x (Dv) x (Qi) . (eq 5.2.1)

I and Does p = (3.17E-8) x Z (N,) x (Dv) x (Q1) . (eq 5.2.2) i I where:

l Dose r = mrad garnma air dose due to gamma emissions from noble gas'.

radionuclides.

4 Dose # = mrad beta air dose due to beta emissions from noble gas radionuclides.

M= i air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCl/m 3, from Table 4.3.

. N, = air dose factor due to beta emissions for each identified noble gas j radionuclide, in mrad /yr per pCi/m 8, from Table 4.3.

l Dv = highest sector annual average gaseous dispersion factor, X/Q, at or beyond the unrestricted area boundary, in sec/m8 . Values may be read or Interpolded from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. Maximum values of X/Q presendy used are 7.17E-7 sec/m 3for station vent at sector NNE, and 1.16E-5 sec/m3 for all other .

releases at sectors N or WNW.

l Q, = release of nnhfe gas radionuclide, I, in pCl, over the specified time period, j (yCl/sece "conds). l 3.17E-8 = inverse of the number of seconds in a year.

NOTE l 1

If the motliodology in this section is used in determining dose to an- -

Individual, rather than air dose due to noble gases, substitute Ki, from Table 4.3, for Mi, and (Li + 1.1 MI) for Nl.

l 1

l 125.0 mai

03-12-97 08:09:56 I Number ggy TMI Radiologicai Controls Departmental Procedure 6610-PLN-4200.01.

]

i nu. n on te.

Offsite Dose Calculation Manual'(ODCM) 4 11 5.2.2 lodine-131. Iodine-133. Tritium and Radionuclides in Partledata Form. with Half-l lves Greater than 8 Days

, The dose to an indMdual from I-131. I-133, Tritium and Radionudides in Particulate Form wfth half-lives greater than 8 days in gaseous effluents released from the site to an unrestricted area is determined by soMng the following expression.

1 Dose, = Z(3.17E-8) x Z (R,) (Dv) (Q) (eq 5.2.2) i i ,

where:

Dose = dose to all real pathways, p, to organ, o, of an indMdualin a0e group, a.

from 1-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, in mrom, during any desired time period.

R=i the dose factor for each identified radionucilde, I, pathway, p, age groug, a, and organ, o, in mrom/yr per pC1/m8 for the inhalation pattmay and m -

mrom/yr per pCl/sec for other pathways, from Tables 5.2 to 5.7.

NOTE Since there is minimal or no elemental iodine released from the condenser off gas air ejector (see NUREG-0017) all. lodine R, values for all pathways, _aggggt the Inhalation pathway, are considered .to be ze.ro when performing dose calculations for releases from the condenser off-Des alt ejector. Only calculate the dose due to the inhalation pathway for condenser off-gas air ejector lodines.

NOTE Tritium, H-3, dose factor is mrem / year per pCl/m8 for all pathways.

Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/ms, for the inhalation pathway, and D/Q, in tria, for other pathways. Table 4.4 is used for station vent releases and Table 4.5 for aH other releases. Maximum values of X/O s

' presently used are 7.17E-7 sec/m for station vent at sector NNE and 3

1.16E-5 sec/m for a!! other releases at sectors N and Wf4V. Maximum values of D/O in m.a for station vent is 1.22E-8/m2 at sector SE, and for Ground releases,4,12E 8/m for sector SE.

Dv(H4) = In'the case of H4 only the X/Q's are used for all pathways from Table 4.4 for station vent releases and Tablef4.5 for all other releases.

126.0 me.

J 03-12-97 08:09:56 .

, Nurnber

'"' "ad' ' S'c"' " '

1 NNIEI' -

Departmental Procedure 6610-PLN-4200.01 Tide Revision No. ,

i l Offsite Dose Calculation Manual (ODCM) ' 11 1

0=

3 release of I-131, l.-133, Tritluth and Radionuclides, I, in Particulate Form with half-lives greater than 8 days, in pCl, cumulative over the specified time 1 period (pCi/second

• seconds).

1 l l

3.17E-8 = inverse of the number of seconds in a year.  !

l . .

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1 e

f

~

4

?

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f a

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03-12-97 08:09:56 2 .

Numbw ,

Jg g g y TMI Radiological Controls .

Departmental Procedure 6610-PLN-4200.01

m. n.vm No.

1 Offsite Dose Calculation Manual (ODCM) 11 4

j .

5.3' Gaseous Radioactive System Dose Calculations On'ce per Month ODCM Part 1 Control 2.2.2.4 and TMI-2 PDMS Tech Spec Section 6.'(.4.a.6 requires that appropriate subsystem of the Gaseous Radwaste Treatment System shall be used to reduce the radioactive materials in gaseous waste prior to their discharge. When the monthly projected doses due to the

} gaseous effluent releases from the site would exceed 0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 mrom to any organ.

i The following calculational method is provried for performing this dose projection.

4 l At least once per month the gamma air dose, beta air dose and the maximum organ dose for the j quarter-to<iate wil be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual release during the period for which the projection is made. If these projected doses exceed any of the values listed above, appropriate portions of the TMI-1 Gaseous Waste Treatment System, as defined in Section 6.0, or spyrupi'.te portions of the TMI-2 Gaseous Effluent FRtration System as shown on Figure 4.5, shall be used to reduce radioactivity levels prior to release.

At the dis'cretion of Radiological Engineering, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the current quarter-to date is not believed to be representative of the dose per day projected for the next month.

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03-12-97 08:09:56 Number 1 Radidogical Conuds bCleer Departmental Procedure 6610-PLN-4200.01 Tiue n vision No.

{ onsite pose calculation Manual (oocu) 11 1 .

5.4 Alternative Dose Calculational Methoddoales for Gaseous Effluents I .

As an alternative to the methods described above, the models in/or based upon, those presented in Regulatory Guide 1.109 (Rev.1) may be used to make a comprehensive' dose assessment. Default parameter values from Regulatory Guide 1.109 (Rw.1) and/or actual site specific data can be used

' where applicable. ,

! The onsite, on-line computerized system for tracking gaseous affluent dose uses annual average i

gaseous dispersion factors. As an alternative dose calculational methodology. GPU Nuclear 4' calculates doses usfrvj an advanced dass 'A" dispersion model caBed SEEDS (simpitfied environmental effluent dosimetry system).

I This model incorporates the guidelines and methodology set forth in USNRC Regulatory Guide

1.109, and uses actual hourly meteorological information matched to tre time of releases to more accurately assess the dispersion of effluents in the atmosphere Combining this assessment of

. dispersion with TMINS emuent data for each unit, postulated maximum hypothetical doses to the public are calculated.

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03-12-97 08:09:56 Number -

i g I TMl Radiological Controis Departmental Prooedure 6610-PLN-4200.01 Tme FWoon No.

J Offsite Dose Calculation MaNal (ODCM) 11 TABLE 5.2.1 Pathway Dose Factors, RI AGE GROUP: INFAN1' PATHWAY: INHALATION

~ ~ ~ ~ ~ ~ ~ ~~ ~ ~ ~~~

ERGMEdESE [ACEOlUi~rn~ rem [y~e~ahdrrf~

' NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

.UVER T. BODY THYROID KIDNEY LUNG GI

__ . ...~ ...

BONE _____ ... .___. ...______ . . .. ___. .._ ._ _ _.-LU H-3 0.00E + 00 6.47E+ 02 6.47E + 02 6.47E + 02 6.47E + 02 6.47E +02' 6.47E + 02 i C 14 2.65E + 04 5.31E+03 5.31E + 03 5.31E + 03 5.31 E + 03 5.31E +03 5.31 E + 03 CR-51 0.00E + 00 0.00E + 00 8.95E +01 5.75E + 01 1.

. . . _ _ _ _ _ _ _ _ . . _ . _ . . . . . 1.32_E

. _____'28E

+01 _ + 04.... 3.57E +.__02 MN-54 0.00E + 00 2.53E+04. 4.98E+03 0.00E +00 4.90E +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 1.11E + 04 C040 0.00E + 00 8.02E + 03 1.18E + 04 0.00E + 00 0.00E + 00 4.51E +06 3.19E + 04 NI 63

_ _ . 3.39E + 05 2.04E + 04 1.16E + 04---.'

. _ _ _ _ _ . . . . . . . . _ _ . . . . . . . . . . . O.00E

..._____ . + 00 . 0.00E .__ ... + 00 2.09E +05 2.42E + 03 ZN-65 1.93E+ 04 6.26E + 04. 3.11E+ 04 0.00E+00 3.25E + 04 8.47E + 05 5.14E + 04 RB-86 0.00E + 00 1.90E + 05 8.82E + 04 0.00E +00 0.00E +00 0.00E+ 00 ' 3.04E +03 SR-89 1.14E + 0.00E +0 3.98E +05. .._0.00_E __ _ _+ 0_0

..._..04__ .. . 0 0.00E+00 ~ 2.03E+06. _ _ _ _ _ _ _6.40E+04 SR-90 4.09E + 07 0.00E + 00 2.59E+ 06 0.00E +00 0.00E +00 1.12E + 07 1.31 E +05 Y-91 5.88E+ 05 0.00E +00 1.57E + 04 0.00E+00 0.00E + 00 2.45E+06 7.03E+04 1.15E + 06 2.79E+04 3.

ZR.-95

. . .. ...... __2 03E + 04 0.00E+00

.__... ...__.11 E + 04 1.75E+06

. 2.17E+04 NS-95 1.57E + 04 6.43E + 03 3.78E + 03 0.00E+ 00 4.72E + 03 4.79E+ 05 1.27E + 04 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 + C3 1.09E ..+ __....

04 0.00E .. ..

+ 00 1.07E+05 ... ....

1.16E+07 1.64E _.

+ 05 AG-110M 9.98E + 03 7.22E+ 03 5.00E + 03 0.00E + 00 1.09E'+ 04 3.67E +06 3.30E + 04 TE-125M 4.76E + 03 1.99E + 03 6.58E+02 1.62E + 03 0.00E +00 4.47E +05 . 1.29E + 04 TE-127M 1.67E + 04 6.90E+03 2.07E +03 4.87E +03 3.75E +04 1.31E + 06 . 2.73E + 04 TE-129M 1.41E +04 6.09E +03 2.23E+03. 5.47E+03 3.18E+04 1.68E_+ 06 6.90E +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 . 3.56E+06 2.24E + 04 0.00E+ 00 2.16E + 03 CS-134 3.96E + 05 7.03E + 05 7.45E+ 04 0.00E + 00 1.90E + 05 7.97E + 04 1.33E + 03 CS-136 4.83E + 04 1.35E + 05 5.29E + 04 0.00E + 00 5.04E'+ 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 + 1.76E + 05 0.00E + 00 5.38E+05 9.84E+06 1.48E + 05

. __.. . 06 1.21 E +.._ .._0_6 ..____ _ ___ _ ..____ __ .. _.. _ .......__

PR-143 1.40E+ 04 5.24E+03 6.99E+02 0.00E + 00 1.97E+03 4.33E + 05 3.72E+ 04

_ . . _ _ . .7.94E ND _147 . . _ _ _+_ 03

. 8.13E.+03 5.00E +.02 . _ _0.00E

. . . _ _ .+. 00

. . . 3.15E+03 . 3.22E + 05__3.12E

... ... .. __ + 04

, 130.0 mm J

i

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< 03.-12-97 08:09:56 I M Nuclear TMI Radiological Controls o,partmental procedure 6610-PLN-4200.01

m. m.

1 Offsite Dose Calculation Manual (ODCM) 11  !

1 1

TABLE 5.2.2 .

i Pathway Dose Factors, Rt AGE GROUP: CHILD PATHWAY: INHALATION

~ ~~~

---

ORGAN DOSE FACTORS; mrom/ year per pCl/rE~- - - - - - - - - -

NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - -

, BONE l.NER T. BODY THYROID KIDNEY LUNG GI-LLI H.3 ~ 0.00E + 00 1.12E + 03 1.12E + 03 1.12E + 03 ' 1.12E + 03 1.12E +03 1.12E + 03 j C-14 3.59E + 04 6.73E + 03 6.73E + 03 6.73E + 03 6.73E + 03 6.73E + 03 6.73E + 03 i CR-51

~~

0.00E +00 0.00E+00 1.54E+02 8.55E +01 2.43E +01 1.70E + 04 1.08E + 03 i MN-54 0.00E + 00 4.29E+04 ' 9.51E+03 ' O.00E+00 1.00E +04 1.58E+ 06 2.29E + 04 l FE-55 4.7,4E + 04 2.52E +04 7.77E +03 0.00E + 00 0.00E +90 1.11 E + 05. 2.87E + 03 l FE-59 2.07E+ 04 3.34E +04 1.67E + 04 0.00E + 00 0.00E + 00 1.27E< ~~

06 7.07E + 04

~ ~~ ~~~ ~

~kEE C h.~0CE+00~i.[E+[i3 3.16E+05~5EE+~U'0~5EE+~00 5.~11E+5 3.44d+~04 CO-60 0.00E+00 1.31E + 04 2.26E + 04 0.00E + 00 0.00E +00 7.07E+ 06 9.62E+ 04 N143 8.21E + 05 4.63E + 04 2.80E+ 04 0:00E+00 0.00E + 00 2.75E+

05 6.33E + 03 ZN-65 ' 4.26E + 04 1.13E +05 7.03E + 04 0.00E + 00 7.14E + 04 9.95E + 05 1.63E + 04 RB-86 0.00E+00 1.96E + 05 1.14E + 05 0.00E+ 00 0.00E +00 0.00E+ 00 7.90E + 03 SR 5.99E+05 . 0.00E+00 1.72E+ 04 0.00E + 00 0.00E + 00 2.18E + 06 1.67E + 05 .

_..-89 _ . _ ._ _ _...__.. _ _.. _ _ ... . _ ___ ._ _ _.

SR-90 1.01E + 06 0.00E + 00 6.44E + 06 0.00E + 00 0.00E +00 1.48E+07 3.43E+05 Y-91 9.14E + Ti 0.00E+00 2.44E + 04 0.00E + 00 0.00E +00 2.63E + 06 1.84E + 05 1.90E+05 ' 4.18E+04_ ..._... 3.70E+04 +04 2.23E + 06 6.11E+ 04 ZR-95 0.00E + 0

.._.3 5 96E NB-95 2.35E r04 9.18E + 03 6.55E+03 ' O.00E+00 8.62E + 03 6.14E + 05 3.70E + 04 RU 103 2.79E+03 ' O.00E+00 1.07E + 03 0.00E + 00 7.03E + 03 6.62E + 05 4.48E+ 04 RU._-106 1.3_6E + 05 0.00E + 00 1.69E + 04 0.00E

+ 00 1.84E + 05 1.43E +

.. 4.29E +05

..07 ......__.

AG-110M 1.69E + 04 1.14E+ 04 9.14E + 03 0.00E + 00 2.12E + 04 5.48E + 06 1.00E + 05 TE-125M 6.73E + 03 2.33E + 03 9.14E + 02 1.92E + 03 0.00E + 00 4.77E+ 05 3.38E + 04 2.49E+ 04 8.55E + 03 3. ____

TE..-127M _______... ...._... __.0_2E + 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 l-131 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 + 0

. ._. ._..__..... ...__. .. ... .. .... .. ._.. 0 5.48E ...__..+ 03 CS-134 6.51 E + 05 1.01 E + 06 2.25E+05 0.00E + 00 3.30E +05 1.21 E + 05 3.85E + 03 CS-136 6.51E+04 1.71E+ 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 2.11E + 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 +. 06 1.20E ..-

+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 1.08E + 04 8.73E + 03 6.81 E + 02 0.00E+00 ' 4.81E+03 3.28E + 05 8.21E + 04 ND._-147 ... .___. .. ...__.. .__ ... .... ... .._____. ___..___..

131.0 mm

O -

l 03-12-97 08:09:56 l Number l gggy '

TML Radiological Controls Departmental Procedure 6610-PLN-4200.01

)

nue am.on m. l Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.2.3 Pathway Dose Factors, R1 '

AGE GROUP: TEEN PATHWAY: INHALATION )

1 NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------

l i BONE UVER T. BODY THYROID KIDNEY LUNG Gl.LLI ,

1 H-3 0.00E + 00 1.27E + 03 1.27E +03 1.27E+ 03 1.27E +03 1.27E + 03 1.27E + 03 4 C-14 2.60E + 04 4.87E+ 03 4.87E + 03 4.87E + 03 4.87E + 03 4.87E + 03 4.87E + 03 CR-51 0.00E+ 00 ' O.00E+00 1.35E + 02 7.50E + 01 3.07E+01 2.10E + 04 3.00E+ 03 l MN-54 0.00E + 00 5.11E + 04 8.40E + 03 0.00E + 00 1.27E+ 04 1.98E +06 6.68E + 04 FE-55 3.34E + 04 2.38E + 04 5.54E + 03 0.00E + 00 0.00E + 00 1.24E+05 6.39E + 03 FE

_. -59 _ 1.59E +

......04 3.70E+ 04 1.43E+ 04 0.00E + 0

. .--. .__.__...__.0 0.00E + 00 1.53E + 06 1.78E + 05 l

1 CO-58 0.00E + 00 2.07E+03 2.78E+03 0.00E +00 0.00E + 00 1.34E + 06 9.52E + 04 CO-60 0.00E+ 00 1.51E +04 1.98E +04 0.00E +00 0.00E + 00 8.72E + 06 2.59E + 05 NI-83 5.80E + 05 4.34E + 04 1.98E +04 0.00E+00 '0.00E+00 3.07E + 05 1.42E + 04 -

ZN 65 3.86E+04 1.34E+ 05 6.24E+ 04 0.00E + 00 8.64E +04 1.24E+ 06 4.66E+04 RB-86 0.00E + 00 1.90E+05 - 8.40E+04 0.00E +00 0.00E +00 D.00E + 00 1.77E + 04

- SR-89 4.34E + 05 0.00E+00 1.25E + 04. 0.00E +00 0.00E+00 2.42E + 06' 3.71E + 05 SR-90 1.08E + 08' O.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 95 1.46E + 05 4.58E + 04 3.15E + 04 0.00E +.00 6.74E + 04 2.69E +...06_ _1.49E +__.. 05 NB-95 1.86E + 04 1. 03E + 04 5.66E + 03 0.00E + 00 . 1.00E + 04 7.51E+ 05 9.68E + 04 RU-103 ' 2.10E + 03 0.00E + 00 8.96E + 02 0.00E +00 7.43E + 03 7.83E + 05 1.00E + 05 l RU-106 9. 0.00 1.90E + 05 1.61 E.+ 07 l

..._ _'84E __. + 04 0.00E + 0_0. __.. 1.24E + 04

. ... .E_+_.._ 00

_ ___..._ __.. 9.60E + 05 ..

AG-110M 1.38E + 04 1.31E +04 7.99E+03 0.00E + 00 2.50E +04 6.75E+06 2.73E+ 05 TE-125M 4.88E+03 2.24E +03 6.67E+02 1.40E+03 .0.00E +00 5.36E + 05 7.50E + 04 1.80E + 04 8.18E +03 2.18E + 03 4.38E + 03 6.54E +04 1.66E + 06 1.5 TE.127M

.. . . . . _ _ _ .. . _ . _... ..__ .._ . __. .____.9E+05 .

TE-129M 1.39E + 04 6.58E + 03 2.25E + 03 4.58E+ 03 5.19E + 04 1.98E + 06 4.05E +05 .

1-131 3.54E + 04 4.91 E + 04 2.64E + 04 1.46E+ 07 8.40E +04 0.00E + 00 6.49E + 03 1-133 1.22E + 04 2.05E + 04 6.22E + 03 2.92E+ 06 3.59E + 04 0.00E + 00 1.03E + 04 CS-134 5.02E + 05 1.13E + 06 5.49E + 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 0.00E + 00 3.04E + 05 1.21E + 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 +06 2.02E + 06 2.62E + 05 0.00E + 00 1.21E + 0 _. 1.34E+ 07 8.64E + 05

._. ___ _ . .__....__......__..__.6 PR-143 1.34E +04 5.31E + 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

)

132.0 nn.

O'3-12-97 08:09:56 Number M Radologd Contmis

_GUCIO8r Departmental Procedure 6610-PLN-4200.01 me Revision No.

Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.2.4 Pathway Dose Factors, RI 1

AGE GROUP: ADULT PATHWAY: INHALATION ORGAN DOSE FACTORS: mrom/ year per pCl/m8 NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

---

ONEB UVER T. BODY THYROID KIDNEY LUNG GI-LU H-3 0.00E + 00 1.26E+ 03 1.26E + 03 1.26E + 03 1.26E + 03 1.26E + 03 1.26E + 03 i C-14 1.82E + 04 3.41 E + 03 3.41 E +03 ' 3.41 E + 03 . 3.41E + 03 3.41 E + 03 3.41 E + 03 i CR 0.00E +00 0.00E+00 1.00E +02 2.28E + 1.44E + 04 3.32E + 03

____-51 _ _..... _____..__ _ __.. 5.95E+ 01. _____... ._. 0_1 .. .___

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 7.21 E +04 6.03E+03 i

.FE. -59 .............._____..._.0_0 1.18E + 04 2.78E + 04 1.06E+ 04 0.00E + 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 9.28E+05 1.06E + 05 CO-60 0.00E + 00 1.15E + 04 1.48E +04 0.00E + 00 0.00E+ 00 5.97E +06 2.85E+05 NI-63 4.32E +05 3.14E + 04 1.45E + 04 0.00E + 00 0.00E+00 1.78E + 05 1.34E + 04 l ZN 65 3.24E + 04 1.03E +05 4.66E + 04 0.00E + 00 6.90E + 04 8.64E + 05 5.34E + 04 RB-86 0.00E + 00 1.35E + 05 5.90E + 04 0.00E + 00 0.00E + 00 0.00E + 00 1.66E + 04 SR-89 3.04E + 05 0.00E + 00 0.00E +00 s . _ __ _____._____._' 8.72E + 03_________0_.0_0E _ __ .. _ ___ ... _-1.40E + 00 +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 i ZR-95 1.07E + 05 . 3.44E + 04 2.33E + 04 0.00E+ 00 5.42E + 04 1.77E + 06 1.50E + 05 l 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 80-103 1.53E + 03 0.00E+ 00 6.58E + 02 0.00E + 00 5.83E + 03 5.05E + 05 1.10E +05 RU 106 6.91E + 04

_ .. ._. 0.00E.+__00

. ._8.72E + 03 s_ ......._

0.00E +

__.___.00 .... .._.. 9.36E 1.34E + 05

_.. +9.12E+05 06 AG-110M 1.085 + 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 1.24E + 04 3.14E + 05 7.06E + 04 TE-127M 1.26E + 04 5.77E + 03 1.

.... .__. ..._...__. . .. 5_7E + 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 1.18E + 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.

--___ ____. ._... ... .. ___ _ _ . 2 15 E + 06__ ..._. 58E + 04._0..__00E _. _ +00 8.86E + 03 CS-134 3.73E +05 8.48E + 05 7.28E + 05 0.00E+00 2.87E + 05 ' 9.76E + 04 1.04E +04 CS-136 3.90E + 04 1.46E + 05 1.10E + 05 0.00E +00 8.56E +04 1.20E + 04 1.17E + 04 CS 137

.... 4.78E + 05____6.21

_. E + 05 4.28E +.._

.._ _ .....___ 05__0.00E + 00

_ _.. ... _ ...2.22E + 05 7.52E + 04 8.40E +03 BA-140 3.90E +04 4.90E + 01 2.57E + 03 0.00E +00 1.67E +01 1.27E + 06 2.18E + 05 CE-141 1.99E+04 1.35E+ 04 1.53E + 03 0.00E+00 6.26E +03 3.62E+05 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 PR-143 9.36E + 03 3.75E+03 ' 4.64E+02 0.00E + 00 2.16E + 03 2.81 E + 05 2.00E + 05 5.27E + 03 6.10E + 03 3.65E + 02 0.00E + 00 3.56E + 03 2.21 E + 05 1.73E+ 05 ND. 147 -- _ _ _ _ _ _ _ _ _ _ . _ _ . . . . _ _ . . . . . . . . . . . _ _ _ . . _ _ . . _ _ . . . .

9 133.0- mm

l 03-12-97 08:09:5.6 Number

-- gggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 rm. w.on so.

Offsite Dose Calculation Manual (ODCM) 11

,. TABLE 5.3.1 Pathway Dose Factors, RI

~ ~ ~

AGE GROUP: ALL PATHWAY: . GROUND PLANE

~ ~ ~

i ORGAN DOSE FACTORS

• i lNUCUDE 4

- s T. BODY SKIN s H-3 0.00E + 00 0.00E +00 C-14 0.00E + 00 0.00E + 00

! 4.65E + 06 4

CR.51 .

_.5 50E + 06 -._____.4 i MN44' 1.39E + 09 1.62E + 09

' FE55 0.00E + 00 0.00E +00

, FE-59 2.73E + 08 3.21 E + 08 ' ,

CO-58 3.79E + 08 4.44E + 08 C0-60 2.15E + 10 2.53E + 10

N143 0.00E+ 00 0.00E + 00 ZN46' 7.47E + 08 8.59E + 08 RB-86 8.97E +06 1.03E+ 07 I SR 89 2.16E + 04 2.51 E +04 SR-90 0.00E+00 0.00E+ 00 Y-91 1.07E + 06 1.21 E + 06 ZN-95 2.45E+08 2.84E+ 08 NB-95 .1.37E + 08 1.61 E + 08 l RU-103 1.08E+ 08 1.26E + 08 I RU.106 4.22E +06 5.06E+08 AG-110M 3.44E + 00 4.01 E + 09 TE 125M 1.55E +06 2.13E + 06

' TE 127M 9.17E + 04 1.08E + 05

~ ~

TE i~29M 1.98E + 07' ~~2.31E ~~~~~bi+

, 1-131 1.72E+ 07 2.09E + 07 l-133 2.45E + 06 2.98E+ 06 CS-134 6.86E + 09 8.00E + 09 i CS-136 1.51E + 08 1.71 E + 08 CS-137 1.03E + 10 1.20E+ 10

~~ ~

. BA 140 2.06E + 07 2.36E+6i 4

CE-141 1.37E + 07 1.54E +07 CE-144 ' 6.96E + 07 8.05E + 07 ,

PR-143 0.00E+ 00 0.00E + 00 y ND-147 8.39E + 06 a

1.01E+07f 2

• m - mrem / year per pCi/sec. .

1 134.0 mm i >

1

M .

03-12-97 08:09:56 Numbw TMI Radiological Controls

$ ME Departrnental Procedure 6610-PLN-4200.01 i Tlue Revision No.

2 Offsite Dose Calculation Manual (ODCM) .

11 TABLE 5.4.1

. Pathway Dose Factors, R1

< . AGE GROUP: INFANT PATHWAY: GRASS-COW-MilX NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

BONE LIVER - T. BODY THYROID KIDNEY LUNG GI-LLI H4 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 1.61E + 05 1.05E + 05 2.30E + 04 2.05E+ 05 4.70E + 06

, MN-54 0.00E +00 3.91E+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 1.11E+07 -

2 FE-59 2.25E + 08 3.93E + 08 1.55E+ 08 0.00E + 00 0.00E +00 - 1.16E + 08 1.88E + 08 .

CO-58 0.00E + 00 2.43E + 07 6.06E + 07 0.00E + 00 0.00E + 00 . 0.00E + 00 6.05E+ 07 CO.60 0.00E + 00 8.83E + 07 2.08E + 08 0.00E + 60 0.00E +00 0.00E+00 2.10E + 08 NI-63 3.50F + 10 2.16E + 09 1.21 E + 09 0.00E + 00 . 0.00E + 00 0.00E + 00 1.08E + 08 ZN-66 5.50E+09 1.91E + 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-95 6.81E + 03 1.66E + 03 1.18E + 03 0.00E + 00 1.79E +03 0.00E + 00 8.27E +05 NB-95 5.94E + 05 2.45E+ 05 1.41 E + 05 0.00E + 00 1.75E + 05 0.00E + 00 2.07E + 08 RU-103 8.68E + 03 0.00E+ 00 2.90E + 03 0.00E+00 1.81E+04 0.00E+00 1.06E+05 RU-106 0.00E + 00 2.25E + 05 0.00E +00 1.45E +

1.91E + 05 0.00E + 00_2.38E + 04 ..._.... _ .

..____- ... __.. ...__ ._._____.06 ._

AG-110M 3.86E + 08 2.82E + 08 1.87E + 08 . 0.00E + 00 4.03E +08 0.00E +00 1.40E + 10 TE-125M 1.51E+08 5.05E+07 2.04E+07 5.08.E +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 1.91 E + 08 8.59E + 07 2.14E + 08 1.39E + 09 0.00E + 00 - 3.33E +08 l-131 2.72E + 09 3.21 E+ 09 1.41 E + 09 1.05E + 12 3.75E + 09 0.00E + 00 1.15E + 08 l 3.63E + 07 5.29E + 07 _____E+07 9.62E + 09 6.22E + 07 0.00E + 0 1.55 ..___ _____..

.-133 . ......._______. ... . ______ ___ .... .. 0_. 8.96 E + 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 6.55E + 09 1.89E +08 BA-140 2.42E +08 2.42E + 05 1.25E + 07 0.00E + 00' 5.75E +04 1.49E+ 05 .5.94E +07 CE-141 4.34E + 04 2.65E+ 04 3.12E + 03 0.00E + 00 8.17E + 03 0.00E + 00 1.37E + 07 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 9.07E+ 02 5.55E + _01 0.00E + 00 3.50E+ 02 0.00E+00 5.75E+05 ND-147 ____8.83E+02 135.0 me.

3 4 03-12-97 08:09:56 '

. Numtw gggy .TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01

m. Reviam wo.

Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.4.2 .

] Pathway Dose Factors, RI AGE GROUP: CHILD PATHWAY: GRASS-COW-MILX

. ORGAN DOSE FACTORS; m2 - mrem / year per pCl/sec NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - . _ . - -

BONE LIVER T KIDNE LUNG l .._ _ ....... _ .... _ T. BODY _ _ ... ...H.Y.ROID_ _ ___

.Y ....GI-LLI H3 0.00E + 00 1.57E + 03 1.57E+ 03 1.57E +03 1.57E +03 1.57E+ 03 1.57E+03

( C-14 1.20E + 09 2.39E + 08 2.39E+08, 2.39E+08 2.39E + 08 2.39E + 08' 2.39E + 08 CR41 0.00E + 00 ' O.00E+ 00 1.02E + 05 5.65E + 04 1.54E + 04 1.03E + 05 5.40E +06

~~ ~~~~~ ~~'~

I M -54 OE+~5 2.10E+h 5E+~5~5E+~5~5E+~5~5E+~5~1.76E+0E FE-55 1.12E +08 5.94E + 07 1.84E + 07 0.00E + 00 0.00E + 00 3.36E +07 1.10E + 07  ;

FE49 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 1.21 E + 07 3.72E + 07 0.00E + 00 0.00E + 00 0.00E + 00 - 7.08E + 07 1 CO40 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 1.01E+09 0.00E+00 ' O.00E+00 0.00E + 00 ' 1.07E+08 1 ZN-66 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 i 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 1.51E+09 i Y-91 3.91E+ 04 0.00E +00 1.05E + 03 0.00E + 00 0.00E + 00 0.00E +'00 5.21E +06 l ZR 3.84E + 03 8.43E + 02 7.51 E + 02 I

_.-95 ... . . 0.'00E+ 00 1.21E +03..._'O 00E + 00 8.80E + 05 I

NB-95 3.18E+05 1.24E + 05. 8.86E+04 - 0.00E+00 1.16E+05 0.00E + 00. 2.29E + 08 l RU-103 4.29E + 03 0.00E +00 1.65E + 03 0.00E +00 1.08E +04 0.00E + 00 1.11E + 05 l 9.25E+ 04 RU 106.. '. .. 0.00E+00 1.15E+04. .._0.00E

... ____. + 00 1.25E .. + 05 0.00E + 00 1.44E + 06-AG-110M 2.09E + 08 1.41E +'08 1.13E +08 0.00E + 00 . 2.63E +08 0.00E + 00 1.68E+ 10 TE-125M 7.39E+07 ' 2.00E+07 9.85E+06 2.07E + 07 0.00E+00. 0.00E+00 7.13E+ 07 i 2.08E + 08 5.61E +07 2.47E + 07 4.98E+07 TE..-127M

._ . . ._. _...__ _.__ ________ _ _ __. 5.94E _ . .+_ .08_ _ 0.00E+

_ . . . _ . . 00

. . _1.69E

_ _ _ +08 TE-129M 2.72E + 08 7.59E + 07 4.22E + 07 8.76E + 07. 7.90E + 08 . 0.00E + 00 3.31 E + 08  ;

l-131 1.31 E + 09 1.31E + 09 7.46E + 08 4.34E+ 11 2.16E +09 0.00E+00 ~ 1.17E+08 l 1

i

_-133.. 1.72E+07 2.13E+07 8.05E+06 3.95E

____.... _ . . _ _ _ .... _ _+_ .09_3.55E +07

... ... _ __...... 0.00E+

_... .._. 00 8.58E +06 CS-134 2.27E + 10 3.72E +10 7.85E409 0.00E +00 1.15E + 10 4.14E + 09 2.01 E + 08 CS-136 1.01E +09 2.79E +09 1.80E +09 0.00E + 00 1.49E + 09 2.21E + 08 9.80E + 07 3.23E + 10 3.00E + 10 4.56E +09 0.00E4. 00 1.01E + 10 ...

CS-13_7 . _____... .. .. _.. __. . _ ... ... _'3.62E + 09 1.93E +08 . ._..__

BA-140 1.18E + 08 1.03E +05 6.86E + 06 0.00E + 00 3.35E + 04 6.14E +04 5.96E +07 CE-141 2.19E +04 1.09E + 04 1.62E + 03 0.00E+ 00 4.79E + 03 0.00E+00 1.36E + 07 CE-144 1.83E + 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 4.45E + 02 ND_-147. ....... 3.61E+ 02___. __ .2 79E.+. .01 _ . 0.00E .+ 00 1.98E+02 .. _ ._0.00E +00 5.71 E + 05 4

i 136.0 m

03-12-97 08:09:56 Numtsr j gdgp TMl Radiological Controls Departmental Procedure 6610 PLN-4200.01 l

l I

Title RevWon No.

Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.4.3 l Pathway Dose Factors, Ri -

AGGROUP: PATHWAY: GRASS COW

_.- ..-.. _E _ ..... TEEN .._...___ ___ ____ .-MILK .. __. .....

ORGAN DOSE FACTORS: 2m mrom/ year per pCl/sec NUCLlDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ - - - - - . - _ . . . . - - . . . i T. BODY THYROID . KIDNEY _' LUNG......._.-LU GI i

. - ... ... BONE ._ _._.UVER __ _ .. ... _ ._.___._ _ . .._ 1 l

H4 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 4

CR-51 0.00E+ 00 0.00E +00 4.99E+04 2.77E+04 ' 1.09E+04 7.13E + 04 8.39E + 06 1 MN.64 0.00E + 00 1.40E + 07 2.78E+ 06 0.00E + 00 4.19E + 06 0.00E + 00 2.88E + 07 l FE-65 4.46E +07 3.16E + 07 7.37E +06 0.00E+00 0.00E+00 2.01E +07 1.37E + 07 l FE-69 5.19E+07 1.21Et08 4.68E +07 0.00E + 00 0.00E +00 3.82E + 07 2.86E + 08

CO-58 0.00E + 00 7.94E + 06 1.83E + 07 0.00E+00 0.00E+00 0.00E + 00 1.10E + 08 CO-60 0.00E+00 2.7BE + 07 6.27E + 07 0.00E + 00 0.00E+00 0.00E+ 00 3.62E+ 08 l

N1-63 1.18E + 10 8.36E + 08 4.01 E + 08 ______.00 0.00E + 0.00E+00 0.00E + 00 f.33E + 08.

l ZN.65 2.11E +09 7.32E+ 09 3.42E +09 0.00E+00 4.89E + 09 0.00E +00 3.10E + 09 RB-86 0.00E + 00 4.73E + 09 2.22E + 09 0.00E + 00 0.00E + 00 0.00E +00 7.00E + 08

SR-89 2.68E + 09 0.00E+00 ' 7.67E+07 0.00E +00 0.00E +00 0.00E+ 00 3.19E+08

~

~SR-~hb S E UO. 000E+(b ~ i E +10 d.0bE+00~~5.~00E +ib~6E+~00~iE+0h l Y-91 1.58E + 04 0.00E+ 00 4.24E + 02 0.00E + 00 0.00E+ 00 0.00E + 00 6.48E + 06

, ZR-95 1.65E + 03 5.21 E + 02 3.58E + 02 0.00E+ 00 7.65E+ 02 0.00E +00 1.20E + 06 ,

i NS-96 1.41E+05 7.82E+04 4.30E+04 0.00E+00 7.58E+04 0.00E + 00 3.34E + 08 i 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 l i

TE-127M 8.45E + 07 3.00E+ 07 1.00E +07 2.01 E + 07 3.42E + 08 0.00E + 00 2.11E + 08 TE-129M 1.10E + 08 4.00E +07 1.74E + 07 3.56E + 07 4.61 E + 08 0.00E +00 4.14E4 08 l131 5.38E+08 7.53E + 08 4.05E + 08 2.20E +11 1.30E+09 . 0.00E+00 1.49E + 08 l133 7.08E + 06 1.20E +07 3.66E + 06 1.68E + 09 2.11E +07 0.00E +00 9.09E + 06 .

CS-134 9.83E+ 09 2.31 E + 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 2.

CS.-137 1.34E

. _ _ _ . _+. 10

. _ .1.78E + 10 6.21 E_+_.-_...

...._.. ...__ .. .. 36E 09 . _0.00E + 00.__6.06E + 09 +-..09_2.54E + 0_8 BA-140 4.87E + 07 5.97E + 04 3.14E+ 06 0.00E + 00 2.02E + 04 4.01E + 04 7.51 E+ 07 CE-141 8.89E+03 5.94E+03 6.82E+ 02 0.00E+00 ' 2.80E+03 0.00E +00 1.70E + 07 CE 144 3.54E.+ 04 0.00E + 00 1.63E +05 1.66E + 0

..._0_.00E + 00_.-..__._--..8

.__ .. 8.59E

...____ + 05_2.73E_.. ... __ +05 .._ ___ _...._.._

PR 143 2.90E + 02 1.16E +02 1.44E + 01 0.00E + 00 6.73E + 01 0.00E + 00 9.55E + 05 ND,147 1.81 E + 02 1.97E + 02 1.18E + 01 0. ......____...---.....___....-

__. ..-.. .. ._ . ...... _. 'COE + 00 1.16E + 02 0.00E + 00 7.12E +05 t

137.0 mm

D '

i l

l

\

l 03-12-97 08:09:56 .

l Number.

(UClear mi Ram 9, ai i Departmental Procedure Corcoi.

6610-PLN-4200.01

Tme Meion No.

1 Offsite Dose Calculation Manual (ODCM) 11 l

< 1 TABLE 5.4.4 Pathway Dose Factors, RI 1

l

..... AGE GROUP: ADULT

......__ _ ..__. __ .. PATH.W_AY:

__. GRASS-COW. MILK ORGAN DOSE FACTORS; r2___m_ rem __/ year per pCl/sec NUCtJDE - - - - - - - - - - - - - - - - - - - - - - - - - - ------ - - - - - - - - - - - - - - - -

l

---

BONE LIVER T. BODY THYROID KIDNEY LUNG Gl.LLI

.. ...__ _.._. 1 H-3 0.00E + 00 7.62E + 02 7.62E + 02 -7.62E + 02 7.62E + 02 7.62E + 02 7.62E+ 02

. C-14 2.63E + 08 5.26E + 07 5.26E + 07 5.26E + 07 5.26E + 07 5.26E + 07 5.26E + 07 l CR 51 0.00E +00 0.00E +00 2.85E +. 04 1.70E +04 6.28E + 03 3.78E+

04 7.17E .. ....

+06 l 1

! MN-64 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 1.73E + 07 4.04E + 06- 0.00E + 00 0.00E + 00 9.66E + 06 9.93E + 06 i

, FE-59 2.97E + 07 6.97E+ 07 2.67E + 07- 0.00E + 00 0.00E + 00 ' 1.95E + 07 2.32E + 08 i-CO-58 0.00E +00 4.71E +06 1.05E +07 0.00E + 00 0.00E + 00 0.00E +00 9.54E +07 CO-00 0.00E +00 '1.64E + 07 3.61E + 07 0.00E + 00 0.00E + 00 0.00E +00 3.08E + 08 l

, NI 63 6.72E+09 4.65E+08 2.25E + 06 0.00E+00 0.00E+00 0.00E + 00

9. 71 _ _ E

_ _+

. 07 .

ZN-65 1.37E + 09 4.36E+ 09 1.97E+09

• 0.00E+00 2.91E + 09- 0.00E + 00 2.74E + 09 RB-86 ' O.00E +00 2.59E + 09 1.2'1 E + 09 ' O.00E + 00 0.00E+00. 0.00E+00 5.10E + 08 SR-89 1.45E+ 09 0.

. __..__..________. 00.E + 00. . .._4.16E

__ ._.... .. + 07' O.00E + 00 '....

. . ....__ .O.00E+ 00 0.00E+00 2.32E + 08 SR-90 4.67E + 10 0.00E +00 1.15E + 10 0.00E+ 00 0.00E + 00 0.00E+00 1.35E+ 09 l Y-91 8.57E + 03 0.00E + 00 2.29E + 02 0.00E+00 0.00E + 00 .0.00E +00 4.72E + 06 i ZR 9.41E+02 3.02E+02 2.04E + 02 0.00E. ___ + 00 ' 4.74E +.._02 0.00E..__ + 00 9.57E +05

__..-95. . . _ _ _ _ _ . _ .. _....__.. _ ..._____ ,

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 0.0GE >00 4.38E + 02 0.00E + 00 3.88E + 03 0.00E + 00 1.19E+ 05 RU-106 2.58E + 03 0.00E + 00 3.93E + 04 0. 1.32E + 06 2.04E+04

.. ..._ ' _O.00U.+00

.____.________... ... ___ .__. .0_0E+00 AG-110M 5.81 E+ 07 5.38E+.07 3.19E +07 0.00E+ 00 1.06E + 08 0.00E + 00 2.19E + 10 TE-125M 1.63E + 07 5.89E +06 2.18E +06 4.89Et06 6.61E4 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-125II'~5EIIf7 2EIIi7 5IS1EI'06 25fEIE7 2.51EIidi 6E+00 3.02EI~0ii 1-131 2.96E+08 4.23E+CS 2.42E + 08 1.39E + 11 7.25E+ 08 0.00E + 00 1.12E+ 08 l133 ___.______._..___________..._._____........6.04E+06 3.87E + 06 6.73E + 06 2.05E + 06 9.88E + 08 1.17E + 07 0.00E + 00 .

1.10E + 10 0.00E +00 4.34E + 09 1.44E + 09 2.35E +08

~

CS-134 5.64E + 09 1.34E +10 CS-136 2.63E +08 1.04E +09 7.48E + 08 ' O.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 4

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 3.71E+ 02 0.00E+ 00 1.52E+ 03 0.00E+00 1.25E+07

,,_,g_E

_CE ,;144 g_,119etg_1.92E+04_ gE 0 + g_ 8.85E + 04_ gE 0 +g_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 6.50E+00 0.00E+00 6.35E +01 0.00E + 00 5.22E +05 4

138.0 mm

O 03-12-97 08:09:56 Nurnber Nuclear ' "a****' co**

Departmental Procedure 6610-PLN-4200.01  !

Tm. -

woon No.

Offsite Dose Calculation Manual (ODCM) 11 i

TABLE 5.5.1 l Pathway Dose Factors, RI 1

AGE GROUP: INFANT PATHWAY: GRASS-GOAT-Mil.K 2

ORGAN DOSE FACTORS: m - mrem /iear per pCl/sec NUCLlDE - - - - - - - - - - - - - - - - - - - - - - - - - - - ------ - - - - - - - - - - - - - - - - -

BONE UVER T. BODY THYROlD KIDNEY

_ ... .. _ ... _ ________ _ _ _ _ _ _ _ _ _ _ _ . . ... ... LUNG

. __ ' 1.1JGl ...

H-3 0.00E + 00 4.86E +03 4.86E + 03 4.86E+03 4.86E +03 4.86E + 03 4.86E + 03 C-14 2.34E + 09 5.00E + 08 5.00E+08 5.00E +08 5.00E+08 5.00E +08 5.00E + 08 CR-51 0.00E + 00 0.00E + 00 1.94E + 04 1.26E + 04 2.76E + 03 2.46E + 04 5.64E +05 MN-54 0.00E + 00 4.68E +06 1.06E + 06 0.00E +00 1.04E + 06 0.00E + 00 1.72E +06 FE-55 1.76E + 06 1.14E + 06 3.63E+ 05 0.00E +00 0.00E +00 5.55E + 05 .1.44E + 05 FE-59

- 2.92E + .06

_ . . _ _ . _ 5.10E . +06

_ _ ...2.01

_... E + 06 0.00E +. 00 _ _ _. __0.00E

_ . . + 00 .__..

1.51 E+ 06 2.44E...+ 06 CO-58 0.00E + 00 2.91 E + 06 7.26E + 06 0.00E + 03 0.00E+06 0.00E + 00 7.2SE + 06 CO 60 0.00E + 00 1.08E+07 ~ 2.50E+07 ' O.00E+00 0.00E + 00 0.00E + 00 2.52E + 07 NI 83 ~.19E+09 4 2.59E + 08 1.46E + 08 0.00E + 00 0.00E + 00 0.00E + ..__......____00 1.29E + 07 ZN-65 6.67E + 08 2.29E + 09 1.05E + 09 0.00E + 00 1.11E + 09 0.00E + 00 .1.93E + 09

' RB-86 0.00E+ 00 2.67E + 09 1.32E + 09 0.00E + 00 0.00E + 00 0.00E + 00 6.83E + 07 SR-89 5.44E + 0 2.65E + 10 0.00E ._+ 00 7.59.E

.... . + _____

.. 08 ....0.00E.+00 0.00E+00 .O.00E+00.__'.__________..8 .

SR-90 2.55E + 11 0.00E + 00 6.50E + 10 0.00E + 00 0.00E + 00 0.00E + 00 3.19E + 09 Y-91 8.80E + 03 0.00E+00 2.34E + 02 0.00E+ 00 0.00E+00 0.00E + 00 6.31E + 05 ZR 95 8.17E +02 1.99E4 02 1.41E + 02 0.00E + 00 2.15E+ 02 0.00E+00 ~

9.91 E +04

~ ~~ ~

NBE 7713E+04 5.EE +hl.~70E+ 04 UE0E[00~5~10E+~0 d.~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 -l TE-125M 1.81E+07 6.05E+06. 2.45E + 06 '6.09E +06 0.00E + 00 0.00E + 00 8.62E +06 5.06E+07 '1.68E+07 6.12E+06 1.46E+07 1.24E + 08 0.00E +. 00 2.04E +07

_.._127MTE ___ _ _ _ _ _ . . . _ _ _ _ _ _ _ . . _ . . _ - - - . _ _ _ . _ . . .

TE-129M 6.69E + 07. 2.29E +07 1.03E + 07 2.57E+07 1.67E+08. 0.00E+00 3.99E+07 l-131 3.27E + 09 3.85E +09 1.69E + 09 ' 1.27E + 12 4.50E+09 0.00E+00 1.37E +08 l 103 4.36E +__ _07 6.35E + 07 1.86E + 07 1.15E + 10 7.46E +07 0.00E + 00 1.07E

+07..

CS.134 1.09E + 11 2.04E + 11 2.06E + 10 0.00E + 00 5:26E+10 2.15E + 10. 5.55E+08 CS-136 5.94E + 09 1.75E + 10 6.52E + 09 0.00E + 00 6.96E +09 1.42E + 09 2.65E + 08 CS 137 1.54E + 11 1.81 E + 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.

. 00.E +..._00 1.60E

_ ___ .... + 07 i

PR-143 - 1.78E + 02 . 6.66E + 01 8.83E+ 00 0.00E + 00 2.48E + 01 0.00E + 00 9.40E + 04 ND-147 1.06E +02 1.09E + 02 6.66E + 00 0.00E + 00 4.19E +01 0.00E + 00 6.89E + 04 139.0 mm I

O .

l 03-12-97 08:09':56 Numbw

,J TMt Radiological Controls

@EMEE Departmental Procedure 6610 PLN-4200.01

, Ties Revision No.

I

Offsite Dose Calculation Manual (ODCM) 11 -

TtALE 5.5.it Pathway Dooo Factors, Ri 1

} AGE GROUP: CHILD PATHWAY: GRASS-GOAT-MILK ORGAN DOSE FACTORS: ma . mrem / year per pCl/sec

' NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = - - - - - - - - - - - - - - - - ---

---

BONE . . . .UVER T. BODY THYROID KIDNEY LUN

._.G._.. .GI-LLI .

H-3 0.00E+00 3.20E+03 3.20E + 03 3.20E + 03 3.20E+ 03 3.20E + 03 3.20E +03 C 14 1.20E+09 2.30E + 06 2.39E+CS 2.39E +08 2.39E + 08 2.39E +08 2.39E+ 08

__.____.__3 CR41 0.00E + 1.22E + 04 6.78E + 0 1.85E +03 1.24E + 04 6.48E +0

. 0.00E +00.__.. .. . _.00 _ ... . _ ....__ ____. ..5. ,

. MN-54 0.00E+00 2.52E + 06 6.71E +05 0.00E+00 ' 7.03E+05 0.00E+00 2.11E+ 06 1 FE-55 1.45'E + 06 7s 71E +05 2.39E+ 05 0.00E + 00 0.00E +00 4.36E+05 .1.43E+05 FE-59 0.00E + 00 1.. 56.E __. + 06 2.53E+06 . 1.26E+06

. -- 0.00E.+

00 . ___ 7.34E. _+_ 05 2.64E _ . + __.06

CO-58 0.00E+00 1.46E+ 06 4.46E+ 06 0.00E+00. 0.00E+00 0.00E+00 8.49E + 06

C040 0.00E + 00 5.18E+08 1.53E +07 0.00E +00 0.00E+ 00 0.00E+00 . 2.87E+07 1

N143 3.562+ 09 1.91E + 08 1.21E+08 0.00E+00 0.00E + 00 0.00E + 00 1.28E +07 s

ZN45 4.96E + 08 ~ 1.32E + 00 8.22E + 08 0.00E + 00 8.33E+08. 0.00E+00 2.32E+ 08 RB-86 0.00E+00 1.05E+00

• 6.47E+08 0.00E+ 00 0.00E+00 0.00E +00. 6.77E + 07 1.39E+ 10_0.00E _._ +00 3.97E+08 0.00E+00 0.0

.. .. 0.E+00 0.00E +00 5.

- __....._ _ _.39E+08 SR_.-89 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+00 6.24E+05 j ZR-95 4.60E +02 1.01E + 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+ 00 1.40E + 04 0.00E + 00 2.75E+ 07

, RU-103 5.14E+02 0.00E+00. 1.98E +02 0.00E+ 00 1.29E +03 0.00E + 00 1.33E + 04 RU-106 0.00E + 00 1.50E +. _..._... 04 0.00E+00 1.72 E + 05

. 1.11E +04 0.00.E .. .... + 00_1.38E _ _____ __+ __

03_ ._ _ _. . ....

. AG-110M. 2.51E + 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 2.50E + 07 6.72E+06 2.96E + 06 5.97E + 06 7.1

, TE.-127M . ._.. .. ..____..._______ ..__.. _ .. 2.E+07 0.00E+ 00 2.02E + 07 .. __...... . ____..

l TE-129M 3.26E + 07 9.10E + 06 5.06E + 06 1.05E+ 07 9.56E+07 0.00E+ 00 3.97E + 07 1 1131 1.57E +09 1.57E + 09 8.95E + 08 . 5.21 E + 11 2.58E + 09 0.00E+00 , 1.40E + 08 l 2.06E + 07 2.55E+07 4.25E +

.07_ 0.00E+00 1.03E + 07

.-133 _ . . ...__._ _9 66E + 06 4.74E + 09 _ _ . . . _....__.__

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 6.645+ 08 2.94E +08 CS-137 9.68E + 10 9.26E + 10 1.37E + 10 0.00E +60 3.02E + 10 1.09E +10 5.80E + 08 BA-140 1.41E + 07 1.24E + 04 8.23E + 05 0.00R + 00 4.02E + 03 7.37E + 03 7.15E + 06 .

CE-141 2.63E + 03 1.31E+ 0J 1.95E + 02 0.00E + 00 5.74E+ 02 0.00E + 00 1.63E + 06 i CE 144 1.95E + 05 6.11 E + 04 ' 1.04E + 04 0.00E+ 00 3.38E +04 0.00E + 00 1.59E + 07 PR 143 8.61 E + 01 2.59E + 01 4.27E + 00 0.00E + 00 1.40E + 01 0.00E+00 9.29E+ 04 ND-147 5.34E+01 - 4.33E+01 3.35E + 00 0.00E+00 2.37E+01 0.00E + 00 6.85E + 04 140.0 mas

o l l

03-12-97 08:09:56

$UCle8r " 8'd ' S"

Departmental Procedure 6610-PLN-4200.01 m nwwon wo.

~

Offsite Dose Calculation Manual (ODCM) 11

, TABLE 5.5.3 '

Pathway Dose Factors, Ri

~ ~

AGE GROUP: TEEN PATHWAY: GRASS-GOAT-Mit.X

~ ~~

~~~~~~~~

---

dRGA ~~~ D~dE7E[iT75iS"; n7.~m~r~em/yEperphE~~

' NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

BONE UVER T. BODY THYROID' IGDNEY 1.UNG GI-LU I H3 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 1.31E.. + 03 8.55E + 03 1.01E + 06 MN44 0.00E+ 00 1.68E + 06 3.34E + 05 0.00E+ 00 5.02E+05 0.00E+ 00 3.45E+ 06 i FE45 5.79E+ 05 4.11 E + 05 9.58E + 04 0.00E+00 0.00E+ 00 2.61E +05 1.78E + 05 FE-50 6.74E+ 05 1.57E+06 . 6.08E+05 0.00E + 00 0.00E + 00 4.96E+05 3.72E+06 i

CO-58 0.00E + 00 9.53E +05 2.20E+ 06 0.00E + 00 0.00E + 00 0.00E + 00 1.31 E + 07 1 CO-60 .0.00E + 00 3.34E + 06 7.52E +06 0.00E + 00 0.00E+00 . 0.00E+00 4.35E + 07 NI63 1.42E

._.. + 09_1.00E+

. . . _ _ .08_4.81E

. ___ +..07 0.00E+00 0.00.E +00... ...._0.. 00E

_ ....__. _ 60E+07+1. 00___ _  !

i ZN-65 2.53E + 08_ 8.78E +08 4.10E +08 0.00E +00 5.62E + 08 0.00E + 00 3.72E + 08 i RB-86 0.00E+ 00 5.67E 408 2.67E+ 08 0.00E + 00 0.00E+00' O.00E+00 8.40E + 07 SR-89 5.62E

._. + 09 ~ .0.0_0_E + 1.61E

__. ._____00. .. + 08 0.00E+00 ___ 0.00E +..._ 00 . E0.00

+ 00 .6.89E + ..08 ,

SR-90 1.39E + 11 0.00E+00 3.43E+10 0.00E +00 0.00E +00 0.00E +00 3.90E + 09 i Y-91 1.90E + 03 0.00E + 00 5.00E +01 0.00E+00 0.'0 0E+00 0.00E +00 7.78E + 05 ZR 95 1.98E + 0

... .. ..2 6.25E ... ... _+._. 01 4.30E +01 'O.00E + 00 9.18E + 01 -. 0 00E+00 1.44E + 05 NS-95 1.69E + 04 9.38E+03 5.16E + 03 0.00E + 00 9.09E + 03 0.00E +00 4.01 E+ 07 RU 103 2.17E + 02 0.00E+ 00 9.29E +01 0.00E + 00 7.66E + 02. 0.00E +00 1.82E + 04 RU 106 4.50E + 03 - 0.00E + 00 5.68E +02

.. .________. .____. . 0.00E . _ .+_ 00

_ _ _8.89E

. . . + 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 3.61 E + 06 1.30E +06 4.82E +05 1.01 E + 06 0.00E + 00 0.00E +00 1.06E + 07 TE

._ 127M __.._ _.... 1.01 B +07 3.59E + 06 1.20E + 06

._ < ....... _2.41 E..+...06 4.11 E + 07 0.00E

.. ....____. .__ _ ...+ 00 2.52E + 07 TE 129M 1.32E + 07 4.90E + 06 t19E+ 06 4.26E + 06 5.53E+ 07 0.00E +00 4.96E+ 07 1-131 6.45E+ 08 9.0aE+06 4sE + 08- 2.64E + 11 1.56E + 09 0.00E+ 00 1.79E+ 08 1133 06 .2.01 E ..+ 09 2.53E+07 8.49E + 06 1.44E+ 07 4.40E + 0.

. ...__. _...__. . .. _ ..._. 00E + 00 1.09E + 07 OS-134 2.95E +10 6.93E + 10 3.22E + 10 0.00E + 00 2.20E + 10 8.41E + 09 8.62E + 08 CSM6 1.35E + 09 5.30E + 09 3.5eE + 09 0.00E + 00 2.89E + 09 4.55E + 08 4.27E + 08 CS-131 4.02E + 10 5.34E+ 10 1.86E + 10 0.00E + 00 1.82E+ 10 7.07E + 09 7.60E + 08 E-Ido 5.84E + 06 7.16E+ 03 3.76E + 05 0.00E + 00 2.43E+ 03 4.81E + 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

_. 27E + 04 - 4.25E + 03 0.00E + 00 1.95E +04 0.00E+ 00 1.90E + 07 CE 144 7.90E + 04 3.

PR-143 3.48E+ 01 1.39E + 01 1.73E + 00 0.00E +00 8.08E + 00 0.00E +00 1.15E + 05 NO-147 2.18E + 01 2.37E + 01 1.42E +00 0.00E +00 1.39E + 01 0.00E +00 8.54E + 04 141.0 me.

3 4

03-12-97 08':09:56

. Number g g g y- TM) Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tro. nevi on No.

I Offsite Dose Calculation Manaal (ODCM) 11 1

TABLE 5.5.4 Pathway Dose Factors, Ri AGE GROUP

ADULT PATHWAY: GRASS. GOAT-MILK

' ~~~ ~~~ ~ ~~~ ~~~ ~

~~~5c'EN3dS$ FACTERS; 5~mIe~r~n~/hhr pCl/sec NUCLIDE . - ------- ---- - - - - - - - - - - - - - - - - - - - - - - - - -

LIVER IGDNEY LUNG -

GI-LLI s

_. BONE __... _ . .. _' T. _. BODY THYROID ...... . ___. ..

H.3 0.00E + 00 1.56E + 03 1.56E + 03 1.56E + 03 1.56E+ 03 1.56E + 03 1.56E+ 03 I C-14 2.64E + 08 5'.27E+07 52.7E+07 5.27E + 07 5.27E+07 5.27E+07 5.27E+07 CR 2.0

, __ -51 .___ 0.00E...+ _00 _. 0.00E + 00' .3.43E+03...._. _. 5_E+03 __ 7.56E

__ _+..02 4.55E .__ _ + 03 8.63E ..____ + 05 i MN.64 0.00E +00 1.01 E + 06 1.9E 03 0.00E + 00 3.01 E + 05 0.00E + 00 3.10E + 06 FE-55 3.27E +05 2.26E +05 5.20E+04 0.00E+00 0.00E + 00' 1.26E +05 1.30E + 05 05_9.00E+05 . 3.485+05__..__....._.0 0 00E+00 2.54E+ 05 3.03E +06 i FE-59 3.87E + 0.00E +0 CO-58 ' O.00E + 00 5.66E+05 1.27E+06. 0.00E+00 ' O.00E+00 0.00E + 00 1.15E + 07 CO.60 0.00E+00 1.97E +06 4.35E+06 0.00E +00' O.00E + 00 0.00E +00 3.70E + 07 s

NI.63 8.00E + 08 5.60E+07. 2.71E+07

.._ _ .. _ ...._. ..___.. 0.00.E +00.... _..._0.00E . +.. 00 0.00E+

. 00 1.17E + 07

!- ZN-65 , 1.65E+06 5.24E+ 08 2.37E+ 08 0.00E + 00 3.51E + 08 0.00E+ 00 3.30E + 08 RB46 0.00E+00 3.12E+08 1.45E+06 0.00E+ 00 0.00E + 00 0.00E+00 6.14E+07 i SR49 3.05E+ 09 0.00E+ 00 8.76E4 07'....__... O.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-01 1.03E + 03 0.00E+ 00 2.76E +<01 - 0.00E + 00 0.00E + 00 0.00E+00. 5.88E+05 l ZR-96 1.13E +02 3.63E + 01 2.46E + 0.00E+ 00 5.70E+ 01_ .0.00E+00 1.15E + 05 i .._.._....._...._0.1 . . . . . . . . . . . _ .......

NS-95 9.92E + 03 5.52E +03 2.97E + 03 0.00E + 00 5.45E+03 0.00E +00 3.35E+ 07 RU-103 1.22E + 02 0.00E+00 ' 5.27E+01 0.00E + 00 4.67E + 02 0.00E+00 1.43E +04 RU-106 2.45E + 03 0.00E+00 3.10E+02 0.00E +00 4.73E + 03 0.00E +00 1.59E + 05 AG-110M .6.99E +06 6.47E +06 3.84E + 0S 0.00E +00 1.27E +07 0.00E + 00 2.64E + 09

, TE-125M 1.96E + 06 7.00E + 05 2.62E+ 05 5.89E+05 7.96E +06 0.00E + 00 7.81E +06 TE 127M 5.50E + 06 ' 1.97E + 06 6.70E +05 1.41E +06 2.23E + 07 0.00E+00 ' 1.84E+07 TE-129M 7.23E +06 2.70E +06 1.14E + 06 2.48E + 06 3.02E + 07 0.00E + 00 3.64E + 07 l-131 3.56E + 08 5.09E +08 2.92E + 08 1.67E +11 8.73E + 08 0.00E +00 1.34E +08 l 4.65E + 06 8.10E + 06 2.47E + 00 1.19E + 09

_-133 ...._ _ _ _.. ..._ _ ___. _ _ _. . ___.._ _ _1.41 E + 07 0.00E + 00 7.28E + 06 CS-134 1.70E + 10 4.04E +10 3.30E + 10 0.00E + 00 . 1.31 E + 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 2.22 l

..._.E.+.10 . ....3.03E + 10.1.99E + 10 0.00E ..__...+_ 00 _ . 1.03E

. _____. +10 3.42E + 0_9 _ ..5.87E+ 08 <

BA-140 3.24E + 06 4.07E + 03 2.12E + 05 0.00lj!+00 1.38E + 03 2.33E + 03 6.67E + 06 CE 141 5.82E + 02 3.94E + 02 4.47E +01 0.00E + 00 1'.83E + 02 0.00E + 00 1.51E + 06 .

CE-144 4.30E + 04 1.80E+ 04 . 2.31E +03 0.00E + 00 1.07E + 04 0.00E +00 1.45E + 07 4

PR-143 1.90E +01 7.60E+00 9.40e 01 0.00E + 00 4.39E + 00 0.00E + 00 8.30E + 04 ND-147 . 1.13E + 01 1.31 E + 01 7.82001 ' O.00E+00 7.65E + 00 0.00E + 00 6.28E + 04 d

0 142.0 me.

4

1 03-12-97 08:09:56 -

i

, n.nen ggy

• TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 1

Tme neweion No. l Offsite Dose Calculation Manual (ODCM) 11 l

l TABLE 5.6.1

Pathway Dose Factors, RI -1 1

. AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT I

~~~

2 ORGAN DOSE FACTORS; m - mrom/ year per pCI/sec NUCUDE BONE .UVER T. BODY THYROlD KlDNEY LUNG GI-LU H-3 , 0.00E + 00 0.00E + 00 0.00E+00 0.00E+ 00 0.00E + 00 0.00E +00 0.00E + 00

C-14 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CR 51 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 MN-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 1 CO-68 0.00E + 00 0.00E +00 0.00E+00 ' O.00E+00 . 0.00E+00 0.00E+00 0.00E + 00  !

CO-80 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E+00 .0.00E+00 N143 0.00E + 00 0.00E +00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 .

ZN 66 0.00E + 03 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00. 0.00E+00 0.00E +00 RB-86 0.00E+ 03 - 0.00E +00 0.00E +00 0.00E +00 0.00E +00 0.00E + 00 0.00E +00 SR-89 0.00E +03 0.00E + 00 0.00E.+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 SR-90 0.00E+ 03 0.00E + 00 0.00E + 00 - 0.00E +00 0.00E +00 0.00E + 00 0.00E+ 00 Y 91 0.00E + 03 0.00E+ 00 0.00E + 00 0.00E + 00 0.00F + 00 0.00E + 00' O.00E + 00 ZR-96 0.00E + 03 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 0.00EW 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

- 00.E+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' O.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 ' O.00E +00 0.00E+ 00 0.00E+00 0.00E + 00 0.00E+00 0.00E+00 0.00E + 00 CS-137 . 0.00E + 00 0.00E + 00 0.00E +00 0.00E +00 0.00E +00 0.00E + 00 0.00E + 00 BA-140 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 0.00E + 00 0 00E+00 0.00E +00

' CE-141 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 CE-144 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 0.00E + 00 0.00E + 00 0.00E + 00 PR-143 0.00E+00 . 0.00E+00 0.00E+00 ' O.00E+00 0.00E + 00 0.00E + 00 0.00E+ 00 ND-147 0.00E + 00 0.00E + 00 0.00E +00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 143.0 me.

O .,

03-12-97'08:09:56 Nwnbw Nuclear TMI Radiciogical Controls o , - Proc oore 6610-PLN-4200.01 i

m. n e on wa.

Offsite Dose Calculation Manual >(ODCM) 11 .

TABLE 5.6.2 Pathway Dose Factors, RI

AGE GROUP: CHil.D PATHWAY: GRASS-COW-MEAT 2

ORGAN DOSE FACTORS; m - mrom/ year por pCl/sec

, NUCUDE - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - -

---

UVER BONE T. BODY THYROID KIDNEY LUNG Gl-LU

-H 0.00E + 00 2.34E + 02 '2.34E + 02 2.34E + 02 2.34E + 02 2.34E + 02 2.34E +02 l C 14 3.84E + 08 . 7.67E + 07 7.67E + 07 ' 7.67E + 07 . 7.67E +07 7.67E + 07 7.67E + 07 CR - 0.00E+00 0.00E + 00 8.78E + 03 4.88E +03 1

_..51 . __ _ ___ _ ___ - ..___ ..___.33E + 03 8.90E + 03 4.88E

___.... ____ ___ + 05 MN-54 0.00E +00 8.01E +06 2.13E +06 0.00E +00 2.25E +06 0.00E + 00 6.73E+06 FE55 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 6.1 3.04 1.77E+08

... . ___.0.E + __ 08 _ _.._E+06 _ 0.00.E

. + 00_'O.00E+00

_.. _ ... ... 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 +08 0.00E + 00 ~0.00E+00 0.00E + 00 3.84E + 08 NI-63 2. 0. 0.00E + 00 0.00 __ _.

i ._ 91 10 1.56E + 09 E_..+ ._. . 9.91 E +... 08.. 00E_+ . 00

.________ ...._E + 00_1.05E + ... 08 ZN.65 3.76E + 08 1.00E +09 6.22E +08 0.00E + 00 6.31E+08 . 0.00E+00 1.76E + 08 RB-86 0.00E+00 5.76E + 08 3.54E+08 0.00E+ 00 0.00E+ 00 0.00E + 00 3.71E + 07 SR.80 4.82E +08 1.3 0.00E + 00 0.00E +0_0_0_.00.E

. 0.00E + 00_.._ ..__. 8E + 07.

_____... ... + 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-01 1.80E+06 0.00E+ 00 4.82E+ 04 0.00E +00 0.00E +00 0.00E+00 2.40E + 08 ZR-96 2.66E+06

. 5.86E+05 5.21 E + 05 0.00E + 00 '8.38E + ._.

05 0.00E+00 ..

6.11E

+ 08 4

NB-95 3.10E+ 06 1.21 E + 06 8.63E+ 05 0.00E+00 1.13E + 06 0.00E+ 00 2.23E +09 RU-103 1.55E + 08 0.00E+00 5.96E+07 0.00E+00 3.90E + 08 0.00E+ 00 4.01E + 09 RU-106 4.44E._+ 09 0.00E +. 00 5.54E + 08 0.00E

+ 00 6 00E+09 0.00E+

00 6.91E ...__._.

+10 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

__2.11E + 08 4.25E+08 5.06E+ 09 1.78E + 09_....._" .__ 4.78E +08 _ _..__ _ __..___.. _._. 0.00 E + 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 1

1-131 1.66E + 07 - 1.67E + 07 9.48E + 06 5.52E + 09 2.74E + 07 0.00E +00 1.48E + 06 l-133 5.726 01 7.08e 01 2.68e-01 1.31E ~~~

+ 02 1.18E ~

+ 00 0.00E+00~

2.85e-01

~~

' ~~~ ~ ~

CSU~34 9h3E+5~1.51E+00 3.19E + 08 5.~CIOE + 00 4.E+~~08 1.E5[+0E 8.16)i+~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 1.80E + 08 0.00E .__.--

+00 4.16E +.._.........

08 1.50E+08 8.00E +06 x _ .. ...__... ._._. .. _

4.42E + 07 3.87E + 04 2.58E + 06 0.00E + 00 1.26E + 04 2.31 E + 04 . 2.24E + 07 BA-140 ,

i 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.144 2.32E + 06 7.26E + 05 1.24E + 05 0.00E + 00 4.02E + 05 0.00E + 00 1.89E + 08 PR-143 3.33E + 04 1.00E+04 .1.65E+03 0.00E +00 5.42E+03 0.00E+ 00 3.60E+ 07 ND-147 1.17E + 04 9.48E + 03 7.34E + 02 0.00E + 00 5.20E+ 03 0.00E + 00 1.50E + 07 k

t 4

1 144.0 mm i

I 03-12-97'08:09:56 .

Numbw gggp TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Ties Revis6on No.

Offsite Dose Calculation Manual (ODCM) 11

, TABLE 5.8.3

Pathway Dose Factors, R1 AGE GROUP

TEEN PATHWAY: GRASS 40W. MEAT .

~~~~

' ~~~~~~~ ~ ~

Ok:~A Y)~OSU Ub~RS3~~m3r~~~Ipe5~ / yea p k~,lh' NUCUDE -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

BONE LIVER T. BODY THYROID KIDNEY LUNG Gl-LLI -

H-3 0.00E + 00 1.93E + 02 1.93E + 02 1.93E + 02 1.93E+ 02 1.93E+ 02 1.93E +02 i

C-14 2.04E + 08 4.08E + 07 4.08E + 07 4.08E + 07 4.08E + 07 4.08E + 07 4.08E +07 0.00E + 00 0.00E + 00 5.63E + 03 3.13E + 03 1.23E+ 0 . .___

CR.51

. ._.... _ . _... ..._.._____....__. 3 8.03E_+___ _ 03 9.46E .... + 05 MN-64 0.00E+00 7.00E +06 1.30E+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 '7.31 E + 01

FE 69 2.12E + 08 4.95E + 08 1. 1.17E + 09 1 __ . _ . . __ 91 E __ +.. 08

.....0.00E + 00 0.00E + _. 00

.._ 1.56E

_ __. +08 CO-58 0.00E + 00 1.40E + 07 3.24E + 07 0.00E + 00 0.00E + 00 0.00E +00 1.94E +08 CO 60 0.00E + 00 5.83E + 07 1.31 E +08 0.00E+00 0.00E+00 . 0.00E+00 7.60E + 08 NI63 1.52E + 10 1.07E _...____ _ +09

_____5.15E +08 0.00E+00 ...____ _ 0.00E +G0_0.00E ... ...__ . + 00 1.71..____ E + 08

'ZN65 2.50E +08 8.68E +08 4.05E + 08 0.00E + 00 5.56E + 08 0.00E+ 00 . 3.68E+08 -

RB-86 0.00E+ 00 4.08E + 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 1.90E+09 0.00E+00 0.00E+ 00 0.00E + 00 2.26E + 08

. Y-91 9.54E + 05 0.00E+00 2.56E + 04 0.00E + 00 0.00E +00 0.00E + 00 3.91E+08 ZR-95 1.50E + 06_4.73E+ . _ 05 3.25.E+05

. ..___..________ 0.00E+00 6.95E+05 0.0_0E+0_0_I_.09E+09 NB-95 1.79E + 06 9.95E+ 05 5.48E + 05 0.00E+00 9.64E+05 0.00E+00 ' 4.25E+ 09 .

RU-103 8.56E+ 07 0.00E + 00 3.66E + 07 0.00E + 00 3.02E + 08 0.00E + 00 7.15E + 09 RU-106 2.36E +09 0 00E+00_. 2.97E+08_0.00.E+00 _.. .. 4.54E.+.09_.0.._...

.. .. 00E+00 1.13.E .. ..... + 11 AG-110M 5.06E +06 4.78E +06' 2.91E +06 0.00E+00 9.13E+06 0.00E + 00 1.34E + 09 -

TE-125M 3.03E + 08 1.09E + 08 4.05E+ 07 8.46E + 07 0.00E + 00 0.0CE + 00 8.94E + 08 9.4 0.00E+

TE.-127M _ _.1_E+08 .___ . 3.34E+_.. 08 1.12E+08 -_. 2.24E+08

.... '.3.81.E.+.09

.. .-.......00_2.35.E ... ... +. 09 TE-129M 9.49E + 08 3.52E + 08 1.50E + 08 3.06E+08 3.97E + 09 0.00E +00 3.56E + 09 l-131 8.93E + 06 1.25E+07 6.72E + 06 3.65E+09 2.15E + 07 0.00E+ 00 2.47E + 06 l-133 1.59041 7.29E+01 9.16e41 0.00E

.______0_.+0 3.95e .01.

.. . 3.08e .01_.5.22041 CS-134 5.23E +08 1.23E + 09 5.71G+ 08 0.00E+00 3.91E + 08 1.49E + 08 1.53E + 07 CS-138 9.43E+06 3.71 E + 07 2.49E + 07 0.00E+ 00 2.02E + 07 3.18E+ 06 2.99E + 06 CS-137 7.24E + 08 9.83E+08 3.35E + 08 0.00E+ 00 3.28E + 08 1.27E + 08 1.37E + 07 -

BA 140 2.39E + 07 2.93E + 04 1.54E + 06 0.00E + 00 9.94E + 03 1.97E +04 3.69E + 07 CE-141 1.18E +04 7.87E +03 9.05E +02 0.00E + 00 3.71 E + 03 0.00E + 00 2.25E + 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 4

145.0 um

o .,

03-12-97 08:09:56 4 -

. mmn.,

ggy TMI Radiological Controls Departmental Procedure. 6610 PLN-4200.01 ns. n.vwon m.

Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.6.4 ,

Pathway Dose Factors, RI s

AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT

---

ORGAN E FACTORS;7- mrom/ year for pCl/sec DOS NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - --- ----

,r BONE UVER T. BODY THYROID GI

... . . _ _.. ____. ______ .._ _ __. KIDNEY ._ LUNG _____..__-LU H-3

' O.00E+00 3.24E + 02 3.24E +02 3.24E +02 3.24E+02 3.24E +02 3.24E + 02 C-14 2.42E+08 4.83E +07 4.83E + 07 ' 4.83E + 07 4.83E+07 4.83E+ 07 4.83E + 07 1

CR 61 0.00E+00 0.00E+00 7.04E+03 ' 4.21E+03 1.55E + 03 9.35E + 03 1.77E + 06 MN-54 0.00E+00 9.18E+ 06 1.75E+ 06 0.00E+ 00 2.73E+ 06 0.00E+ 00 2.81E + 07 FE-55 2.93E + 08 2.03E + 08 4.73E+ 07 0.00E+00 0.00E+00 1.13E+ 08 1.16E + 08 ,

FE-59 2.66E+ 08 6.25E + 08 2.30E + 08 0.00E+00 0.00E+00 1.75E + 08 2.08E + 09 CO-58 0.00E+ 00 1.82E+07 4.00E+07 0.00E+00 0.00E+00 0.00E +00 3.70E + 08 CO-80 0.00E+00 7.52E + 07 1.66E +08 0.00E + 00 0.00E+00 0.00E +00 1.41E +09 4

N!.83 . ~.1.89E+10 1.31E+09 . 6.33E+08 --

0.00E+ 00 0.00E+ 00 0.00E+ 00 2.73E +08 ZN45 ~ 3.56E+08 1.13E+09 5.12E+08 0.03E + 00 7.57E + 08 0.00E+00 7.13E+08 i RB-88 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 8.86e +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 ' O.00E+00 'O.00E+00 0.00E + 00 6.24E + 08 2

ZR-95 1.87E+06 6 01 .. E +_05_4.07E. ._ . + 05 '0 .__...

00E+00 9.43_E + 05.. __. _____0.00E..+ 00 1.90E + 09 i NBW 2.30E+06 1.28E+06 ' 6.87E+0S 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 1'81E +11 .

AG-110M- 6.68E + 06 6.18E +06 3.67E+06 0.00E+00 1.22E+07. 0.00E+00 2.52E + 09 TE-125M 3.59E+08 1.30E+08 4.81E+07 .1.08E+08 1.46E+ 09 0.00E +00 . 1.43E + 09 TE-127M 1.12E+09 3.90E + 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

1'131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 0.00E +00 4.06E + 06 I l-133 3.680 6.41e 1.95e41' 1.12E + 00 5.76e 01

. _. _-01_. _-01 . ... 9.42E

___ ____ t_01 ___0 00E+ 00 . ____

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 1.21E+ 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_....__.00

__ _ .. ~ . __ _ _.

0.00E +

..4.0_5E

_ _ + 08 1.35E+ _.. _ . 08 2.31E _ . _+07 i BA-140 2.90E + 07 . 3.64E + 04 1.90E + 06 0.00E + 00 1.24E + 04 2.08E + 04 5.96E + 07 i CE-141 1.41 E + 04 9.51E + 03 1.08E + 03 d.00E+00 4.42E + 03 0.00E + 00 3.64E+07 -

CE 7.8 0.00E + 00 s __..-144 1.46.E+06

. ._. 6.10E+05._ .. - _.... _.3E+04

.... .'.._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 +07 146.0 m

l j 03-12-97-08:09:56 Number .

TML Radiological Controls i

gp Departmental Procedure 6610-PLN-4200.01 ,

1

m. a.ven so.

1 "

. Offsite Dose Calculation Manual (ODCM) 11 3

j TABLE 5.7.1 i .

.i Pathway Dose Factors, RI '

..____ AGE. . .GROUP:

_ .. _ ___ INFANT

. .____. PATHWAY:- __ VE.GETATION 2

ORGAN DOSE FACTORS; m - mrom/ year per pCl/sec NUCUDE --------------- . BODY T THYROLD 10DNEY LUNG Gl-LU

' BONE UVER H-3 0.00E + 00 0.00E+00. 0.00E+00'. 0.00E+00 0.00E + 00 0.00E + 00 0.00E +00 C-14 ' O.00E+00 0.00E+ 0C 0.00E + 00 0.00E + 00 0.00E+00 0.00E+00 0.00E + 00

. CR-61 0.00E+00 0.00E+00 0.00E + 00 0.00E + 00 0.00E+00 0.00E + 00 0.00E + 00 MN-54 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00' FE-65 0.00E +00 0.00E+00 0.00E + 00 0.00E'+00 0.00E + 00 0.00E+00 'O.00E+00 FE-69 0.00E + 00 0.00E+ 00 0.00E +00 0.00E + 00 0.00E + 00 0.00E+00 0.00E +00 CO-58 0.00E+00 - 0.00E+00 0.00E+00 0.00E +00 0.00E+00 0.00E+00 0.00E +00 CO-60 . 0.00E+00 0.00E + 00 0.00E +00 0.00E+00 0.00E+ 00 0.00E+ 00 0.00E+00 NI 63 0.00E+00 0.00E + 00 0.00E + 00 0.00E+00. 0.00E+00 0.00E+ 00 0.00E+ 00

, ZN45 0.00E+ 00 0.00E+ 00 0.00E +00 0.00E + 00 0.00E+00 0.00E +00 0.00E +00

! RB-86 0.00E + 00 0.00E+00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 -

l

. __ 0.00.E+0_0 0.00E 4 00. .. 0.00E +00 0.00E+00. _.0_.00E + 00 0.00E + 00 '

! SR. 89 0.00E.+00 SR-90 0.00E+ 00 0.00E+00 0.00E +00 0.00E+00 0.00E+ 00 0.00E + 00 0.00E + 00 Y-91 0.00E+00 0.00E +00 0.00E+00 0.00E+00 0.00E +00 0.00E+00 ' O.00E+00 ZR-96 0.00E+00 0.00E +00 0.00E+00 ,0.00E+00 ' O.00E+00 0.00E + 00 0.00E+ 00 i NS-95 0.00E +00 0.00E + 00 0.00E+00 ' O.00E+00 0.00E +00 0.00E + 00 0.00E + 00 a 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 ' O.00E + 00 'O.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 ' O.00E+00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E+ 00

< l-131 0.00E+ 00 0.00E +00 0.00E+00 0.00E +00 0.00E +00 0.00E+00 0.00E + 00

, 1-133 0.00E + 00 0.00E + 00 ' 0.00E+ 00 0.00E + 00 0.00E +00 0.00E + 00 0.00E+ 00 1

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 ' O.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 ' O.00E+00 0.00E + 00 0.00E + 00 0.00E + 00

' BA-140 0.00E + 00 0.00E+00 ' O.00E+00 0.00E + 00 0.00E +00 0.00E + 00 0.00E + 00

.0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 CE-141 0.00E + 00 0.00E + 00 0.00E + 00 i CE-144 0.00E + 00 0.00E +00 0.00E + 00 0.00E +00 0.00E + 00 0.00E + 00 0.00E + 00 PR-143. 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 ND-147 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E +00 0.00E + 00 147.0 me.

m =

03-12-97 08:09:56 ,

Number ,

Nuclear. TMI Radiological Controls o,p r ntal procedure 6610 PLN-4200.01 w w.on no.

Offsite Dose Calculation Manual (ODCM) 11 TABLE 5.7.2 Pathway Dose Factors, RI AGE GROUP: . CHILD PATHWAY: VEGETATION . . _

a ORGAN DOSE FACTORS; m - mram/ year per pCl/seo_- - _____

l l

NUCUDE. -- - ----------------- --

BONE LIVER T. BODY THYROID KIDNEY . LUNG GI-LLI 1

~ ~ ~ ~~~ ~ ~

~

~IH 05E+E4502EI~03~~I.~02EIO3~d.~02E + 03. 4.02E+ 03 4 02Ed~4IO2EI~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 61 0.00E+00. 0.0_0E+00 1.17E+ 05 .-. 6.

__ ... 40E + 04 1.77E+04

______ ..____1.18E+ 05 .. ..6.20E

. + 0_6 MN 54 0.00E +00 6.65E+08 / 1.77E+08 0.00E+00 1.86E+08 0.00E +00 5.58E+08 ~

FE 8.01E+ 08 4.25E + 08 1.32E+08 0.00E+00 0.00E +00 2.40E + 08 7.87E + 07 FE-59 3.98E+ 08 6.44E+ 08 3.21E+08 _.- - . _0.00_E+00

_ 0.00E +00 1.87

.~.________.._E + 08_._ _.8.71 E_____ + 08 CO 68 0.00E +00 6.44E +07 1.97E +08 0.00E +00 0.00E +00 0.00E + 00 3.76E+08 C040 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 2.11E+ 09 1.34E + 09 0.00E+00 0.00E + 00 0.00E +00 1.42E +08 l ZN45 8.12E+08 2.16E +09 1.35E+09 0.00E+00 1.30E+09 0.00E+00 3.80E +08 RB46 0.00E +00 '4.51E + 08 2.77E+08 0.00E+00 0.00E+00' O.00E+00 2.90E+ 07 3.60E+ 10 0.0_0E+ 00 1.03E + 1.

SR49 _ _. _ _ ..__09 0.00_E

._ _. + 00 0.00E

. .._. + 00 . 0.00E+ 00. . .. . ~ 39.E + 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 4.90E + 05 -0.00E+00 ' O.00E+00 0.00E+00 _2.49E +09 7.55 1.

ZR-95 _ 3.86E

.. + _06_8.48_E

___ + 05 + 05 0.00E + _.

._..._E . . - - 0_0 _ 21 E

. _+ . 06 0.00E.+.00_8.8_5E

_ _ _. _... . + 08 N8-95 4.11E+05 1.60E +05 1.14E+05. 0.00E+00 1.50E+05 0.00E + 00 2 96E+08 RU-103 1.53E+ 07 0.00E+00 5.90E + 06 0.00E+00 3.86E+07 0.00E+00 3.97E+08 RU-106 7.45E+08 0.00E+00 9.30E+ 07 0.00E+ 00 1.01E+ 09 0.00E+00 1.16E + 10 AG-110M 3.21E+07 2.17Et07 1.73E + 07 0.00E + 00 4.04E +07 0.00E+ 00 2.58E + 09 TE 125M ' 3.51 E + 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+0_8

. _. _ _ . 1.57E+08_3_.16E+0_8

. . . _ . _____. . . ' 3.77E+09 0.00E+00_1.0_7E+09 TE-129M 8.40E + 08 2.35E + 08 1.30E + 08 2.71E+ 08 2.47E +09 0.00E + 00 1.02E+09 l-131 1.43E + 08 1.44E+ 08 8.18E+07 4.76E+10 2.36E + 08 0.00E + 00 .28E+07 l

l133 3.53E + 06 4.37E +06 1.65E+ 06 8.12E +08 7.28E + 06 0.00E+00 ' 1.78E+06 CS-134 1.60E +10 2.63E+10 5.55E+09 0.00E +00 8.15E+09 2.93E+09 1.42E + 08 CS-136 a.28E + 07 2.28E+08 1.47E + 08 0.00E+ 00 1.21Et08 1.81E+ 07 8.00E+ 06 CS.1M 2.30E + 10 2.29E + 10 3.38E + 09 0.00E +00 7.46E+09 2.68E+09 1.43E+ 08 .

BA-140 2.79E+ 08 2.44E + 05 1.83E+07. 0.00E+00 7.96E + 04 '1.48E + 05 1.41 E+ 08 CE-141 6.57E+ 05 3.28E+05 ' 4.86E+04 . 0.00E+00 1.44E + 05 0.00E + 00 4.09E + 08 CE-144 1.27E + 08 3.99E +07 '6.79E +06 0.00E+00 ' 2.21E+07 0.00E+00 1.04E +10 PR-143 1.45Et05 4.36E + 047.21E + 03 0.00E + 00 2.36E + 04 0.00E + 00 .1.57E + 08 7.15E+ 04 5.79E+04 3.18E+04 0.00E +00 _._ 9.18E_._ + 07 ND _147-...

.. .._ _._4.49E + 03 0.00.E

___ . . . + 00. _

_ . . . ~ .

148.0 ,

9

03-12-97 08:09:56 Numbw -

gggp TMI Radiological Contrais Departmental Procedure 6610-PLN-4200.01 l

no. , Weaon No.

l Offsite Dose Calculation Manual (ODCM) 11 i TABLE 5.7.3 Pathway Dose Factors, RI l

i AGE GROUPi. TEEN. PATHWAY:

..._ ._ _ ..VE_GETATIO..N i . . __-

2 ORGAN DOSE FACTORS: - - - - - - - .

m - mrom/ ..

year per -- pCl/_sec - - - - - - ---.

NUCUDE -----. - - - - - - - - - - - -

Gl.LU BONE UVER T. BODY; THYROID KlDNEY ~ -_ LUNG l

___. ... . . _ . _ _ _ _ _ _ _ _ _ _ .. .. .__. _ ___._ ... i H-3 0.00E+00 2.59E +03 2.59E + 03 2.59E +03 2.59E +03 2.59E+03 2.59E+03 l 4 C-14 3.69E + 08 7.38E + 07 7.38E + 07 7.38E+ 07 7.38E+07 7.38E+07 7.38E +07 1

CR-51 0.00E + 00 0.00E+00 '6.16E+04 3.42E + 04 1.35E+04 . 8.79E+04 1.03E + 07 MN.64 0.00E+ 00 4.54E + 08 9.01 E+ 07 0.00E + 00 1.36E +08 0.00E + 00 9.32E+ 08 4

FE-55 3.26E+ 08 2.31E + 08 5.39E +07 0.00E + 00 0.00E+00 1.47E + 08 1.00E+08 FE-59 .1.80E + 08 4.19E +08 0.00E +00 0.00E+00

... __ _ _____ _'1.62E. + 08 .____. ..____. _- 1.32E + 08____

_ _ 9.91E + 08

- CO-58 0.00E + 00 4.36E + 07 1.01E+08 0.00E+00 0.00E+ 00 0.00E+ 00- 6.01E+08  ;

CO-60 0.00E+00 - 2.40E+08 5.60E+08 0.00E+00 0.00E+00. , 0.00E+00 3.24E +09 NI-83 1.1 5.45E + 08 0. i

- 1.61.E+ 10. .____ . __ _________... 00E...+ _00

..3.E+09 ___ 0.00E +00 0.00E . .. ....+.._.

00 1.81E +08  !

ZN.65 4.24E+08 .1.47E+09 6.86E+ 08 0.00E + 00 9.42E + 08 0.00E+00 6.23E + 08 -

RB-86 0.00E +00 2.73E + 08. 1.28E + 08 0.00E + 00 0.00E + 00 0.00E+00 4.04E + 07 I SR-89 1.52E + 1 0 4.34E +

_ ._ . 0.00E + 00.. ___.. 08 0.00E+00_0 00E

....-_.... . _ _ _+0_0_

_ .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 2.11E+10

, Y 7.84E +06 0,00E +00 2.10E +05 0.00E +00 0.00E + 00 ' .0.00F +00 3.22E + 09

, - ZR-95 1.72E+ 06 5.43E+05 . 3.73E+05

~

0.00E+00

~

7.98E+05 0.00E+00 1.25E + 09 I

~

NB95

~

752E+~05- 1.0E+~057.8EE704'5IO0E+00 53EI$'550E+00 ~ ~ 1 ~ ~ ~456E UO8

- 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 1 1.31 E + 08. 2.24E + 1.37E + 09 TE.-127M 5.52E

. + 08

..__. __ .'_1.96_E

_ +...._______.

08_6.56E + 07 .._____ .09_0.00E + 0_0 TE 129M 3.61E+08 .1.34E+08 5.72E + 07 1.17E+08 1.51E+09 0.00E + 00 1.36E + 09 3

1131 7.69E + 07 1.00E +08 5.78E + 07 3.14E + 10 1.85E + 08 0.00E + 00 2.13E + 07 d

11 1.94E + 06 3.29E +06 1

.33

. . ... .. ._. 00E + 06~ .4.59E _ . . .+_ 08 _ - 5.77E+06

- - - .0.00E+00

. . 2.49E + 06 CS-134 7.10E + 09 1.67E + 10 7.NE+09 0.00E + 00 5.31E + 09 2.03E + 09 2.08E + 08 CS-136 4.39E + 07 1.73E+08 1.16h + 08 ~ 0.00E + 00 9.41E+07 1.48E + 07 1.39E+07 CS 1.01E + 10 1.35E+ 10 4.69E + 09 ' O.

__ -137 _ .... ._____. ...~.. 0_0E____. + 00 4.59E + 09 1.78E

.. .... _ _ _ _+ _ _0_9

. _ _.1.92E

. . + 08

< , BA-140 1.39E+08 ,1.71E+05 8.97E +06 0.00E + 00 - 5.78E+04 1.15E + 05 2.15E + 08

' CE 141 2.83E +05 1.89E+ 05 2.17E + 04 0.00E +00 8.90E+04 0.00E + 00 5.41 E+ 08 5.28E + 07 2.18E + 07 . 2. 0.00E + 0 CE-144 + 07.._..__.0 1.33.E . . . . _ +. 10.'

d

.... . ..... 83E_ _+. 06 . . ~0 00E + 00 1.30E PR-143 6.99E+ 04 2.79E + 04 3.48E + 03 0.00E + 00 1.62E +04 0.00E + 00 2.30E t08 ND-147 3.62E +04 3.94E+04 0.00E + 00 2.31E + 04 _ .....--__.______

._' 2.36E + 03 __...._____ ___ .._0.00E + 00 1.42E + 08 4

1 4

Y  %

149.0 me, s

4

03-12-97 08:16:22 Number .

, gggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Me RWon No.

Offsite Dose Calculation Manual (ODCM) 11

TABLE 5.7.4 Pathway Dose Factors, RI AGE GROUP

ADULT PATHWAY: VEGETATION 2

. - ORGAN DOSE FACTORS; m - mrem / year per pCl/sec

{

NUCUDE --------------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

B T. BODY THYROID ' KIDNEY LUNG GI-LLI

_.. --- ONE ......UVE.R -

H-3 0.00E + 00 2.26E + 03 2.26E + 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 ..

l 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 1.26E+ 08 2.97E + 08 1.14E.+.08' O.00E+00

.. _ .. 0.00E+00 8.29E+07

_ _ ..._.. 9.89E+08

__-59 . . _. . .. _.. ._ _ ..___

- CO.58 0.00E + 00 3.07E + 07 6.89E+07 0.00E + 00 0.00E + 00 0.00E+ 00 6.23E+08 a 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 3.49E +08 0.00E+00 0.00E +00 0.00E+00 1.50E + 08 3.17E + 08 1.01 E+ 09 4.56E + 08 0.00E +00 6.75E+08 . 0.00E+00 6.36E + 08 ZN-65

RB-86 0,00E + 00 , 2.19E + 06 1.02E+08 0.00E +00 0.00E +00 0.00E +00 4.32E +07 SR.89 9.98E + 09 0.00E _...+ 2.86E 00 .. + 08_0.00E __ _ _ . . + _ 00

_ _ _ 0.00E+

_ . . _ _00 . .0.00E+00

_ _ _ _ _ _ _ 1.60E _ _ _ _+. 09. .

SR-90 6.05E + 11 -0.00E + 00 1.48E + 11 0.00E +00 0.00E + 00 0.00E + 00 1.75E + 10 Y-91 5.12E + 06 0.00E + 00 1.37E + 05 0.00E + 00 0.00E+00 ' O.00E+00 2.82E + 09 ZR-95 1.17E+ 06 2.55E +05 0.00E +00 5.91E+ 05 0.00E +0 . __ . ___

... .___3.77E ._. . + 05 ________. .._____. . ________ 0_1.195 + 09 NS-95 1.42E + 05 7.92E+04 4.26E + 04 0.00E +00 7.83E+04 'O.00E+00 4.81 E + 08 RU-103 4.77E + 06 0.00E +00 2.06E + 06 0.00E + 00 1.82E +07 0.00E+00 5.57E + 08

_.RU-106 .

1.93E+ 08

.__.___ 0.00E + 00.._2.44E + 07 .. _ .______..-..__.0 0.00E + 00 3.72E + 08 0.00E +0 1.25E + 10 AG 110M 1.05E + 07 9.75E + 06- 5.79E+06 0.00E+00 ~ 1.92E+07 0.00E + 00 .3.98E + 09 TE-125M ' 9.66E + 07 3.50E +07 1.29E +07 2.90E + 07 3.93E + 08 0.00E + 00 3.86E + 08 TE-127M ~ 3.49E + 08 1.25E + .- 08___...__-

4.26E +... 07 8.93E+ 07 ..... 1.42E + 09 0.00E+00 1.17E+ 09 TE-129M 2.51E + 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 3.63E +06 1.11E + 06 2.0 9E+06

. ._. . . ..._5.34E ___ _+

. 08 6.33E +06 0.00E

.__.. ... +00 3.26E _ __.+06 CS-134 4.67E.+ 09 1.11 E + 10 9.08E + 09 0.00E + 00 3.59E + 09 1.19E+09 1.94E+08 CS-136 4.28E +07 1.69E + 08 1.22E + 08 0.00E + 00 9.41 E + 07 1.29E + 07 1.92E + 07 CS .137

.. 6.36E.. + 09 ..__ 8.70E+09 -.5.70E+09..0.00E+00

.___. ____ ... ' 2.95E.+.0_9_9.81

____. ..._ _E + 08 1.68E + 08 BA-140 1.29E + 08 1.62E + 05 8.47E + 06 0.00E +00 5.52E + 04 9.29E + 04 2.66E + 08

. CE-141 1.97E + 05 1.33E + 05 1.51 E + 04 'O.00E + 00 6.20E+04 ' O.00E+00 5.10E+08 3.29E + 07 1.38E +..07 1.77E + 06 0.00E +__0_0_. ..a .8.16E . . ._ + 06 '_.. O.0_0E

_ _ . - _+ 00_1.'11 E + 10 CE .144 PR 143 6.25E + 04 2.51E +04 ' 3.10E+03 0.00E + 00 1.45E +04 0.00E + 00 2.74E + 08 ND-147 3.34E+04 3.85E+04 2.31 E + 03 0.00E + 00 2.25E + 04 0.00E + 00 1.85E + 08 150.0 me-

i 03-12-97.08:16:22 Number Nuclear "ad

• oa " co"ta*

Departmental Procedure 6610-PLN-4200.01

m.  % ion no.

Offsite Dose Calculation Manual (ODCM) 11 6.0 TMI-1 GASEOUS WAS1E TREATMENT SYSTEM 6.1 Descriotion of the TMI-1 Gaseous Radwaste Treatment System (see Floure 6.1) 6.1.1 Waste Gas System l

1

a. Reactor Building:

- Reactor Coolant Drain Tank (RCOT) header ,

. b. Auxiliary BuBding:

. - Vent Header from

1. Miscellaneous Waste Storage Tank (MWST) -

i 2. Three (3) Reactor Coolant Bleed Tanks (RCBT) -

l Weste Gas Delay Tank

-Two (2) Waste Gas Compressors

- Three (3) Waste Gas Decay Tanks (WGDT) ,

. c. FBtra5on and diution provided by the Station Ventiation System.

j -

, 6.2 Ooerability ,

l Operabuity 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 6r disposal of compressed waste gases stored in the waste gas decay tanks, the operation of the waste gas

. system is entiretV automatic. One waste gas compressor comes on automatically, removing gases j from the vent header system as required, to maintain the pressure in the system at a maximum of about 16.4 pala. l i

l l f

I i

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i ,

l 151.0 mm i

e

3 .

i .

1 03-12-97 08:16:22, , l 1, Number i

-ggy TM'l Radiological Controls Departmental Procedure 6610-PLN.4200.01

Dee Mn No.

4 i onsite Dose calculation Manual (ODCM) 11 -

i .

i 1 1 1 FIGURE 8.1

• i 1 j Waste Gas System a

i i -

j mammessa

===.e.e amma u 4

i senes j gs l q l -

mI 5 merames o "

r . .r.- ni .s o

i r< r4 6- a 6 g r 3

, 5 ,

d b d b d b

! ,,,u, 4 t i r4 6 i uma i asmans masse assuse z l ,amas sess,, sense rasse sesas l . ,

l u------ J '

i l A

l .s's.se wmemanass # e"ssa*s"sE N 4 . seassessans a sses l d 4

% =,s ame j am

, as a

.- asses p-4 seSott g ens . -

i sammeses r m is',,e W

i

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$ l88 eas E-i 46 d6 magsg gas sagess'as WASN ess

% aNl' Mg i engas sans e

seset sans e

.essas goes e

W 1.

,,tn

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! 03-12-97 08:16:22 Nurnber mi nad I gi al Contmt.

I GMCISSF Departmenta! Procedure 6610-PLN-4200.01

. nn. n.vh No.

! Offsite Dose Calculation Manual (ODCM) 11 4

7.0 EFFLUENT TOTAL DOSE ASSESSMENT 1

4 7.1 Total Dose Calculation

~

l The annual (calendar year) dose or dose committment to any member of the' pub le, due to releases of radioactMty and to radiation from uranium fuel cycle sources shall be limted to less than or equal l

,j to 25 mrom 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 mset the dose limitations of 40 CFR 190.

4 The total dose from TMl-1 and TM1-2 (uranium fuel cycle facilities within 8 klorneters) is calculated i by summing the calculated annual doses to critical organs of a real indMdual for liquid effluent using 4

Section 2.1 methodology, for gaseous effluent using Section 5.2.1 and 5.2.2 methodology, and the i direct radiation from the site from the environmental monitoring program's direct radiation (TLD) monitors.

) '

d i

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4 . 1 l  !

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)

1'53.0 mm i

03-12-97 08:16:22

- Numtier

^

Nhr '"' "adio' ato*' co"tro'*

Departmental Procedure 6610-PLN-4200.01 Tdle - Reymon No.

Offsite Dose Calculation Manual (ODCM) 11 1

8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitorino Proaram Reouirements 4 8.1.1 Controls .

in accordance with the TMl-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., the radiciogical environmental monkoring program shall be conducted'as specified in Table 8.1.

8.1.2 Applicability i

At eli times. -

8.1.3 Action

a. Wth the radiological erwlronmental 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. j

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 calendar quarter, prepars and submit to the Commission wthin 30 days from the end of the affected calendar quarter, a special report that identifies the cause(s) for exceeding the ilmR(s) and l defines the conective actions to be taken to reduce radioactive effluents so that the potential annual dose

• to a member of the pubile is less than the calendar year limts of ODCM Part I Controls 2.2.1.2, 2.2.2.2, 2.2.2.3 and ODCM Part 11, Sections 2.1.1'.3F, 2.1.2.30, and ' ,

2.1.2.3E. When more than one of the radionuclides in Table 8.2 are detected as the result of plant effluents in the sampling rnedium, this report shad 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 shal 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.

9 9 9 9, 2.2.2.3 and ODCM Part II, Sections 2.1.1.3F,2.1.2.3D, and 2.1.2.3E. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condtion shall be reported and described in the Annual Radiological Environmental Operating' Report.

• The methodology and parameters used to estimate the potential annual dose to a member of the public shall

.be Indicated in this report..

154.0 ma,

~>

i 03-12-97 08:16:22

. Number

• • "*d' ' 8' "''

MUCle8F Departmental Procedure 6610-PLN-4200.01 Tree novision No.

Offsite Dose Calculation Manual (ODCM) 11

~

c. With milk or fresh leafy vegetation samples unavailable 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 unavalable may then be j 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 Efliuent Release Report documentation for a change in the ODCM including a revised figure (s) and table for the -

ODCM rollecting the new location (s) with supporting information identifying the cause of the I unavalabRity 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 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 i from the station operation. This monitoring program implementsSection IV B.2 of Appendt< 1 to

' 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable conce eeluns of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements end modeling of the environmental exposure pathways. Guidance for this monitoring is provided by the Radiological Aaaaamment Branch Technical Position on Environmental Monitoring (Revision 1, November 1979). Program changes may be initiated based on operational experience.'

8.1.5 Survellance Reauirements The radiological env'conmental

. 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 capablities required by Table 8.3.

II I

g i*

155.0 mm 1

03-12-97 08:16:22 -

Number 1

ggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 THis Revleton No.

Offsite' Dose Calculation Manual (ODCM) 11 )

8.2 Land Use Census

{

8.2.1 Controls In accordance with the TMI-1 Tech. Specs, and TMI-2 PDMS Tech. Specs., a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 mies) the location in each of the 16 ,

meteorologica! sectors of the nearest milk animal, the nearest residence, and the nearest garden

• of greater than 50 ma(500 ft a) producing broad feaf vegetation.

8.2.2- Apolicablity s

j At all times.

I i 8.2.3 Action

, a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose I

commitment greater than the values currently being calculated in ODCM Part i Survellance 3.2.2.3.1, pursuant to ODCM, Part IV, Section 2.0, identify the new location (s) in the next l Annual Radioactive Effluent Release Report.

l' .

l

b. With a Land Use Census identifying a location (s) that yleids a calculated dose or dose I commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Table 8.1, add the new location (s) .

within 30 days to the Radiological Environmental, Monitoring Program given in the ODCM.

The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to TMI 1 Tech. Spec. 6.14 and TMl-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 (s) for the ODCM reflecting the new location (s) with iiJuiivist;on supporting the change in sampling locations.

8.2.4 Bases t

This Control is provided to ensure that changes in the use of unrestricted areas are identified and modifications to the monitoring program are inade 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 Appendbc I to

10 CFR 50. Restricting the census to gardens of greater than 500 square feet (50 m2 ) provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables 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 (l.a., similar to lettuce and cabbage)land 2) a vegetation yield.of 2 kg/ square meter.

• Broad leaf vegetation sampling of at least three different kinds of vegstation may be performed at the site boundary in each of two different sectors with the highest predicted D/Os in hu of the garden census.

- Requirements for broad leaf sampilng in Table 8.1 shall be followed, including analy31s of control samples.

156.0 me, e

I J

03-12-97 08:16:22 Number ggggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 j nuo n vision wo. i i Offsite Dose Calculation Manual (ODCM) 11' l I

l 8.2.5 Survetance Reauirements i The Land Use Census shall be conducted during the growing season at least once per 12 months, l ' using that Information that wlit provide the best results, such as by a door-to-door survey, aerial i 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. i l l l

l l

l i

j 1

157.0 m=

05-12-97 08:15:22 Number l

y' TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 noe , a.v.on te>.

, Offsite Dose Calculation Manual (ODCM) 11 8.3 Interiaboratory Comoarison Procram 8.3.1 Controls in accordance with the TMI-1 Tech. Specs. and TMl-2 PD'MS Tech. Specs., analyses shan be performed on radioactive materials supplied as part of an intertaboratory Comparison Program which has been approved by the Commission (NRC). Only those samples and analyses which are required by Table 8.1 shall be performed l 8.3.2 , Apolicability a' i

- At all times.

1 8.3.3 Ag.182!1 l l With analysis not being performed as required above, report the corrective action taken to prevent a i i

recurrence to the Comrnission in the Annual Radiological Environmental Operating Report.  !

I j 8.3.4 Basee The requirement for participation in an approved Intertaboratory Compjarison Program is provided to ensure that independent checks on precision and accuracy of the measurements of radioactive -

material in environmental sample matrices are performed as part of a quality assurance program for i environmental monitoring in order to d.emonstrate that the results are reasonably valid for'the purpose of Section IV, B.2 of Appendtx i to 10 CFR 50. '

8.3.5 Surveillance Reautrements A summary of the frytertaboratory Comparison Program results shall be included in the Annual l

Radiological Environmental Operating Report. .  !

l 1 ,

s I

o 1

Y l

158.0 me a

03-12-97 08:16:22 Number gggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01

m. w n No.

Offsite Dose Calculation Manual (ODCM) 11 3 TABLE 8.1 Sample Collection and Analysis Requirements 1

Number of Samples .

Exposure Pathway and- Sampling and Type and Frequency j.

and/or Sample Sample Locations

• Collection Frequencyb of Analysish

. 1. Alrbome J

Radioiodine and Samples from 5 locations Continuous sampler Radiolodine Canister:

Particulates from Table 8.4.. operation with sample Analyze weeldy for 1-131. l 2

collection weeldy, or more' Particulate Filter- l frequently if required by dust Analyze for gross beta I loading. '

radioactMty following d

filter change . Ph 3 gamma isotopic analysis *  ;

on composite (by J

location) sample 1 quarterty. .

)

l

2. Direct Samples from 40 Sample Quarterly Analyze for gamma dose Radiation

• locations from Table 8.5 quarterty.

(using either 2 '

. dosimeters or atleast 1 j instrument for ,

continuously measuring and recording dose rate at each location).

i l

l .

i e

d 4

159.0 me.

1 4

~

._l1 l

03-12-97 08:16:22

, Number p- TMI Radiological Controis Departmersal Procedure 6610-PLN-4200.01 me . Fw on.No. I Offsite Dose Calculation Manual (ODCM) 11 I

TABl.E 8.1 (Cont'd) l . Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample 1.ocations* Collection Frequencyb of Analysish

- .3. Waterbome

a. Surface' ' Samples from 2 locations Composite 8 sample over 1 - Perform gamma isotopic from Table 8.6. montNy pedod. analysis' montNy. 1 Composite for tritium

,e 1 sample from. , analysis quarterly, downstream (Indicator) location

• 1 sample from up*tream s

(control) location (or ,

location not influenced by the station discharge) *

b. Drinking Samples from 2 locations. Composite 8 sample over 1 Perform gross beta and i 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 2 supply that could be times control. Composite affected by the . station for trfttum analysis discharge.

quarterly.

e 1 sample from a control location.

c. Sediment from Samples from 2. locations Sample twice per year Perform gamma Isotopic Shorellne (1 Control and 1 Indicator) (Spring and Fall), the interval ' analysis' on each from Table 8.7. not to exceed 184 days, sample.

e 160.0 me, s

i .

. - - - . -. . . _ - _ - . _ -__ - ~_ - _ _ - . . __ .

I

03-12-97 08

16:22 Number Nuclear ' "ad" a=*

Departmental Procedure 6610 PLN-4200.01 This , Revision No.

I .

Offsite Dose Calculation Manual (ODCM) 11 TABLE 8.1 (Cont'd)

Sample Collection 'and Analysis Requirements ,

i Number d Samples

] Exposure Pathway and Sampling and Type and Frequency and/or Sample Sarnple Locations

• Collection Frequencyb of Analysisb

4. Ingestion i a.Mik Samples from 4 locations Sample semimonthly when Perform gamma isotopic from Table 8.8. animals are on pasture; arealysis* and 1-131 monthly at other times. analysis on each sample.

Composite for Sr-90 analysis quarterly.

j b. Fish Samples from 2 locations Sample twice per year Perform gamma Isotopic' from Table 8.9. . (Spring and Fall), the Interval and Sr-90 analysis on

! not to exceed 184 days. edible portions.

! e 1 sample d recreationally important -

bottom feeders and 1 '

sample d recreationally important predators in the vicinity d the station

, discharge.

l e 1' sample d ,

j recreationally important

+

bottom feeders and 1 sample d recreationally important predators from j an area not influenced by the station discharoe.

i i

1 4

161.0. m I

T

03-12-97 08:16:22 Number ggUI TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01

m. . W No.

j Offsite Dose Calculation Manual (ODCM) 11 1

i TABLE 8.1 (Cont'd) i Sample Collection and Analysie Requirements Numberof Samples Exposurs Pathway and Sampling and Type and Frequency and/or Sample Sample Locations

• Collection Frequencyb of Analysisb

. c. Food Samples from 2 locations . Sample at time of harvest. Perform gamma isotopic',

Products from Table 8.10 (when 1131, and Sr-90 analysis avalable) on edible portions.

! e 1 sample of green leafy vegetables orleafy vegetation at a location in the immediate vicinity of the station. (Indicator) .

e.1 sample of sarne species or group from a .

location not influenced by the station discharge.

Samples from 4 locations Sample frutts and Perform gamma isotopic (3 Indicator and 1 control) vegetables at time of ' analysis' on edible from Table 8.10 (when harvest. portions.

avaBable).

h 162.0 an*

03-12-97 08:16:22 ,

Numtw -

gggp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 na nowon so.

I

Offsite Dose Calculation Manual (ODCM) 11

. TABLE 8.1 (Cont'd)

, Sample Collection and Analysis Requirements Table Notation

a. Sampling locations are prmided 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 unavailablity', malfunction of automatic sampilng equipment and other

legitimate reasons. All deviations from the sampling schedule shall be explained in the Annual Radiological Environmental Operating Report.

j b. Frequency notation. weeldy (7 days), semimontNy (15 days), montNy (31 days), and quarterly (92 days).

All survellance requirements shah be performed within the specified time interval with a maximum allowable sxtension not to exceed 25% of the surveEance interval. A total maximum combined interval time for any 4 l consecutive tests shall not exceed 3.25 times the specified collection or analysis interval.

c. One or more Instruments, such as a pressurized ion charnber for measuring.and recording dose rate -

continuously, may be used in place of, or in addition to, integrating dosimeters. For the purpose of this I table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. FUm badges shall not be used as dosimeters for

- measuring direct radiation.

. d. Altbome particulate sample fBters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after j sampling to allow for radon and thoron daughter decay, if gross beta activity in an air particulate sample (s) is greater than ten times the calendar year mean of control samples, Sr 90 and gamma isotopic analysis shaB be performed on the individual sample (s).

l e. Gamma Isotopic analysis means the identl6 cation and quantification of gamma-emitting radionuclides that j may be attributable to the effluents from the facIlty.

3

f. The " upstream samps" shaN be taken at a distance beyond significent Innuence of the discharge. The j ' downstream sample" shall be taken in an area beyond but near the mtxing zone."

g. Composite sample aliquots shah be collected at time Intervals that are short (e.g., hourly) relative to the

compositing period (e.g., montNy) in order to assure obtaining a representative sample.

163.0 -

um i

l 03-12-97 08:16:22 ,

Number Nuclear TM1 Radiological Controls o ena,t m o u e ,oced u,e 6610-PLN-4200.01 nde Rwision No.

Offsite Dose Calculatidn Manual (ODCM) 11 TABLE 8.2 l Reporting Levels for Radioactivity Concentrations in Environmental Samples Airbome

! Particulate

. Water or gas Fish Milk Food Pr'oducts Analysis (pCl/L) (pCl/m3) (pCl/kg, wet) (pCI/L) * (pCl/kg, wet)

H-3 20,000W

$ Mn-54 1000 30,000- .

Fe49 400 10,000 Co-58 1000 30,000 Co60 300- 10,000 Zn 66 300 20,000 '

! , Sr-90 8' O.1 100 8 100 Zr-Nb-95 400 l-131 2- 0.9 3 100

< Cs-134 30 to 1000 00 1000 i

Cs-137 50 20 2000 70 2000 j Ba-La-140 ' 200 300 N For drinking water samples. This is 40 CFR Part 141 value.

a J

e a

[

e 4

/

164.0 mm

03-12-97 08:16:22 Number Nuolear " "*d* * '*

Departmental Procedure 6610-PLN 4200.01 no. n. mon No.

Offsite Dose Calculation Manual (ODCM) 11 TABLE 8.3

! Detection Capabilities for Environmeistal Sample Analysis' l

Lower Limit of Detection (lld)U 4

I Alhe

' Particulafe Fish Food Sediment i Water or Gas (pCl/kg, Muk Products (pCl/kg, Analysis (pCl/L) (pC1/m8) wet) (pCl/L) (pCl/kg, wet) dry)

Gross Beta _ 4 0.01 ' '

l H-3 2000 '

Mn44 15 130

, Fe-59 30 260 -

i Co48,80 15 130 Zn45 30 260 I

Zr-95 30 Sr-90 -

2 0.01 10 2 10 t ,

Nb-95 15 l-131 19 0.07 1 60 I

Cs-134 15 0.06 130 15 60 150 Cs-137 18 0.06 150 18 80 ' 180 Ba-140 60 60

La-140 15 15 i

7 e

i 165.0 m.

03-12-97 08:16:22 .

l Number glgg TMI Radlological Controls Departmental. Procedure 6610-PLN-4200.01 me , Anson No.

Offsite Dose Calculation Manual (ODCM) 11 TABLE 8.3 (Cont'd) i Detection Capabilities for Environmental Sample Analysis *

Table Notation I a. This list does not mean that only these nuclides are to be considered. Other peaks that are identillable, which may be related to plant operations, together with those of the above nuclides, shall also be analyzed i and reported in the Annual Radiological Environmental Operating Report.

b. Required detection capahalties for thermoluminescent doelmsters used for erwironmental measurements are j

given in Regularory Guide 4.13 (Rev.1).

c. The LLD is defned, for purposes of these controls, as the smalleet concentration of radioactive material in a-sample that w'll yield a not count, above system background, that will be detected with 96% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For's partictllar measurement system (which may include radiochemical separation):

4.66 S3 -

7.g ,

4 E V 2. 22 Y , exp (-A A t) ,

Where

1 LLD is '.he "a priori" lower limit of detection as d'efined above, as picocuries per unit mass or volume.

st , is the standard deviation of the background counting rate or of'the counting rate of a blank sample'as appopriate, as counts per minute, j F. is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume,-

2.22 is the number of disintegrations per minute per picocurie, i

l Y la the fractional radiochemical yield (when applicable),

A la the radioactive decay constant for the particular radionuclide and l At for environmental samples is the elapsed time between sample collection, or end of the sample collection 1

period, and time of counting.

Typical values of E, V, Y and At should be used in the calculatis it should be recognized that the LLD is defined as an "a priori" (befoa the fact) limit representing the capability of a measurement system and not as an "a posteriorf' (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs'w8l be achieved under routine conditions. Occasionally background fluctuations, unavoidable smaH 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. .

166.0 me,

l 03-12-97 08:16:22 -

Numtw

' ~

Nuclear " "ad'o' S'o c '*o

Departmental Pmeedure 6610-PLN-4200.01 im. w on No.

Offsite Dose Calculation Manual.(ODCM) 11 4

e i TABLE 8.4 TMINS REMP Station Locations-Air Particulate and Air lodine Station Code Distance (miles) Azimuth M _ Mao' No.

B1-4 0.8 28 60 E1-2 0.4 95 2 F1-3 0.6 105 70 G2-1 1.4 125 74 M2-1 1.3 253 3

. A3-1

• 2.6 358 4 H3-1 2.3 -

_159 5, 1 J3-2 2.9 . 181 71 )

Q4-1 3.5 325 61 G10-1 ' '

9.8 ' 127 6 -

J15-1 12.6 180 7 I

., Q151 13.5 305 8

~

' TABLE '8.5 TMINS REMP Station Locations-Direct Radiation,(TLD)

Station Code Distance (miles) Azimuth M MaoNo.

A1 1 0.4 0 1 A14 0.3 5 9 ,

B1 1 0.6 -

25. ,10 B12 0.4 26 11 81-3 0.5 15 12 C1-2 0.3 54 13 D1-1 0.2 74 14 El-1 0.2 95 15 E1-2 , 0.4 95 2 E1-4 0.2 98 16

-F1-2 0.2 109 17 G1-3 0.3 129 18 H1-1 0.5 167 19 H1-9 0.3 167 20 J1-1 . 0.8 184 21-J1-3 0.3 189 22 J1-4 0.4 . 188 23 K14 0.2 208 . 24 K1-5 0.2 202 25 L11 0.1 . 235 26 M11 0.1 249 27 N13 - 0.1 270 28 PI 1 0.4 293 29 P1'-2 0.2 290 30 167.0 rue.

h I

! 03-12-97 08:16:22 i Number Nuclear '

' "*d

• c " "

Departmental Procedure 6610-PLN-4200.01 1

m. s.vm no. l 1

Offsite Dose Calculation Manual (ODCM) 11 l 1

! TABLE 8.5 (Cont'd) i TMINS RdMP Station Locations-Direct Radiation (TLD)

Station Code Distance (miles) Azimuth M Mao No. .

Q1-2 0.2 318 , 31 4 R1-1 0.2 335 32

?

C2-1 1.6 48 33 K2-1 1.1 200 - 34 M2-1 1.3 253 3 A3-1

2.6 358 4

, H3-1 2.3 159 5 R3-1 2.6 338 35 B5-1 4.8 18 36 C5-1 4.5 42 37 E5-1 4.6 81 38 F5-1 4.7. 107 39 G5-1 4.8 '

131 40 HS1 4.1 157 41

. J5-1 4.9 182 42 KS-1 5.0 200 43 .

L51 4.1 228 44 M5-1 4.3 249 45 NS-1, 4.9 ' 268 46 PS-1 . 4.9 ' 205 47 05-1 5.0 318 48 R5-1 ,

4.9 339 49 D6-1 5.2 65- 50 E71 C8 86 b1 091 8.5 308 52 B10-1 . 9.4 21 53 G10-1 9.8 127 6 G15-1 14.4 124 54 J15-1 12.6 180 7 Q15-1 13.5 . 305 8 R15-2 12.4 329 56 168.0 me

i

' 1 l

03-12-97 08:16:22 ,

Number

, Nuclear ' "*d'd**' o ***

Departmental Procedure . 6610-PLN 4200.01

, Tlue '

Revisen No.

Offsite Dose Calculation Manual (ODCM) 11

' TABLE 8.6 I t

TMINS REMP Station Locations-Surface Water Station Code Distance (miles) Azimuth M Map No.

l ' P1-3 (R) 0.1 284 56 J1-2 (R) 0.5 188 57

J2-1 (R) 1.5 s 182- 58

! A3-2 (R) 2.5 355 59 l Q91(F) 8.5 308 52 1 G 15-1 (F) 14.4 124 54 G15-2(F). 13.6 .128 62 l G1r-G (F) .14.8 124 63 l J154 (F) 14.7 ,178 64 F15-1 (R) 12.8 122 65 (R) = Raw Water -

(F) - Finlahed Wa'er j TABLE B.7 TMINS REMP Station Locations-Aquatic Sediment Station Code Distance (mies) Azimuth M MaoNo.

A1-2 0.8 6- 66 At-3 0.5 0 67 j G11 0.3 - 137 68 K13 0.3 202 69-J2-1 1.5 182 58 e

k 169.0 me.

i

=

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1

,, 03-12-97'08:16:22 l j Numbw Nuclear " """d o'ca' o ""o*

Departmental Procedure 6610-PLN-4200.01 l me wason no.

Offsite Dose Calculation Manual (ODCM) 11 TABLE 8.8

_ TMINS REMP Station Locations-Milk Station Code ' D! stance (mBes) Azimuth M MapNo.

1 i D2-1 1.1 65 72 I I

E2-2 1.1 93 73 i

G2-1 1.4 125 74

A4-1 3.3 10 75 i F4-1 3.2 104 76 P7-1 8.7 293 77

. K15-2 12.8 , 208 78 4

i

, TABLE 8.9 4

TMINS REMP Station Locations-Fish j

Station Code Station Location

! IND Downstream of Station Discharge i

BKG Upstream of Station Discharge

s i

i.

4 170.0 mm

. 03-12-97 08:16:22 - l J

Number i gggp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 i re. %non No.

J Offsite Dose Calculation Manual (ODCM) 11 l 1

! TABIE 8.10

TMINS REMP Station Locations-Food Products Station Code Distance (mues) Azimuth M MaoNo.

! D1-3 0.5 65 79

E1-2 0.4 95 ~2 4 F11 0.5 117 80 1

H1-2 0.9 150 81 j D2-1, 1.1 65 72 i E2-2 1.1 93 73 i G21 1'.4. '

125 74 I I '

J2-2 1.5 178 ~ 82 l M2-2 1.3 252 83 N2-2 1.3 265 . 84

) A4-1 -

3.3 10 75 F4-1 3.2 104 76 l i

P71 6.7 293 77 4 ' A15-1 10.5 10 ,85 1 K15-2 12.8 208 78 '

I M15-2 13.6 253 86 j R15-2 12.4 329 55 l l I -

1 1

1 i

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l 03-12-97 08:16:22 Number .

I Nuclear ""#L =lf,' ,o.ptu.42oo.oi g base No.

• Offsite Dose' Calculation Manual (ODCM) 11 i l l MAP 3.1 l THREE MILE ISLAND NUCLEAR STATION . f i LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE I

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! 03-12-97 08:16:22

Number j

ggmaI "

TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 i me woon No. l l

l 'Offsite Dose Calculation Manual (ODCM) 11

,i MAP 8.2 1

'1 l THREE MILE ISLAND NUCLEAR STATION '

LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l l STATIONS WITHIN 5 MILES OF THE SITE i

> l

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03-12-97 d8:16:22 Nurnber Nuclear

. " """d* co""* -

Departmental Procedure 6610 PLN-4200.01 l

Tite Revisson No.

1 Offsite Dose Calculation Manual (ODCM) 11 i

1 MAP 8.3 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENYlRONMENTAL MONITORING PROGRAM

(: STATIONS GREATER THAN 5 MILES FROM THE SITE i 1 l

, I

( L l

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174.0 mai j

03-12-97 08:16:22 .

Number - l ggp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 M* -

Rwom No.

1 l

l Offstte Dose Calculation Minnual (ODCM) 11 9.0 PART lit REFERENCES 4

1. EPRI NP-3840, RP 1560-3 Final Report, " Environmental Radiation Doses From Diffk: ult-To-Measure Nudides," January 1985 J

2. " Evaluation of the Three MIe Island Nudear Station Unit 1 to Demonstrate CorWormance to the

Design Objectives of 10 CFR 50, Appendk I,' Nudear Safety Associates, May 1976 3

3. TMI-1 Final Safety Analysis Report (FSAR) ,

4. TMI-2 Final Safety Analysis Report (FSAR)

5. Meteorological Irdormation and Dose Assessment System (MIDAS)

6. NUREG-0017, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWR," Revision 1,1986

7. NUREG-0133, " Preparation of Radiological Efiluent Technical Specifications for Nudear Power

< Plants," October 1978

8. NUREG-0172, " Age-Specific Radiation Dose' Commitment Factors For A One-Year Chronic Intake,"

November 1977 9.' Regulatory Guide 1.21, ' Measuring, Evaluating, and Reporting Radioacdvity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous EfRuents from Light-Water Cooled Nuclear ,

Power Plants," Revision 1 June 1974 l

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. Simpitfled Environmental EfRuent Dosimetry System (SEEDS) s i

12. . TMl Recirculation Factor Memos, AprE 12,1988 and March 17,1988

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

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

16. TM1-1 Technical Specifications, attached to Facility Operating License No. DPR-50

16. Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Rout!ne Releases from Light-Water-Cooled Reactors," Revision 1, July 1977

17. TMI-2 PDMS Technical Specifications, attached to Faclity License No. DPR-73

18. Radiological Assessment Branch Terhnical Position on Environmental Monitoring, Revision 1.

November 1979

'19. Title 40, Code of Federal Regulations, " Protection of Environment" 175.0 me.

.-. . _ . - _. --- _ -- _~ - .. - ._. __- - - . . _ . - . _

4

! 03-12-97,08:16:22 j Number i jgggggy M Raddogical Contrds Departmental Procedure 6610-PLN-4200.01

. rm. a.v.on no. ,

} Offsite Dose Calculation Manual (ODCM) 11 1

20.' Regulatory Guide 4.13, " Performance, Testing, and Procedural SpecNications for l Thermduminescence Doelmstry: Environmental Applications," Revision 1 July 1977 1

21. Post-Defueling Monitorfd Storage Safety Analysis Report (PDMS SAR) I 1

l I

i J

l 4

i j

l

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. 1 i

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1 i

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~

t

! l l 03-12-97 08:16:22 I Number l

j ggy TMI Radiological Cortrola s

Departmental Proceduro $610-PLN-4200.01

• • n.vi. son No. )

i j Offsite Dose Calculation Manual (ODCM) 11 i

1 4

2 e

I

, PART IV

' REPORTING REQUIREMENTS t

0 0

e

/

a 177.0 inn

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

03~-12-97 08:16:22 Nurnber i Nuclear " "a 'd a'ca' ooat=

Departmental Procedure 6610 PLN-4200.01 y no. AmW No.

Offsite Dose Calculation Manual (ODCM). 11 PART IV J

Reporting Requirements 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ** '

l 1.1 Routine Radiological Environrnental Operating Reports covedng the operation of the ' unit during the l previous calender year shall be submitted to the Commission prior to May 1 of each year.

! 1.2 The Annual Racilological Environmental Operating Reports shall include summarfes, interpretations,

and an analysis of trends of the results of the radiological environmental monitoring activities for the l report period, including a comparison with pre-operational studies, with operational controls as-

< appropriate, and with previous environmental monitoring reports, and an assessment of the

~

observed impacts of the plant operation on the environment. The reports shall also include the results of Land Use Censuses required by Part lit, Section 8.2. ,

, 1

)

1.3 The Annual Radiological Environmental Operating Reports shall include the summartzed tabulated results of analysis of all radiological environmental samples and erMww& del radiation measurements required by Part !!! Table 8.1 taken during the period. pursuant to the locations j , specified in the tables and figures in this ODCM, as well as summertzed and tabulated results of l these analyses and measure,ments in a format sim8ar to the table in the Radiological Assessment

. Branch Technical Position, Revision 1, November 1979. In the event that some Individual results are 4

not avaBable for inclusion with the report, the report shall be submitted explaining the reasons for ,

1 the missing results. The missing data shall be submitted as.soon as poesi,ble in a supplementary l report.

l 1.4 The reports shall iniso include the following: a summary description of the radiological envir'onments monitoring progrant, a map (s) of aD sampling locations keyed to a table giving dictances and

. directions from a~ point that is midway between the Reactor BuGdings of TMI-1 and TMI-2; the results of licensee participation in the Interlaboratory Cuiip.i's .m. Program, required by Part til. Section 8.3; discussion of aR deviations from the sampling schedule of Part 111 Table 8.1; discussion of all the required analyses in which the LLD required by,Part 111, Table 8.3 was not achievable.

• • A single submittal may be made for the station.

178.0 me,

i 03-12-97'08:16:22 '

Number l Nuoleer ' a*d'd**' coa"*

Departmental Procedure 6610-PLN-4200.01

Tih Rovemon No.

! Offsite Dose Calculation Manual (ODCM) 11 i 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NOTE A single' submittal may be made for the station. The submittal should i combine those sections that are common to both units at the station however, for units with separate radweste systems, the submittal shaN specify the release of radioactive material from each unit.

2.1 Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous

, , 12 months of operation shall be submitted prior to May 1 for TMI-1 and TMI-2.

2.2

• The fogowing information shall be induded in both Radioactive Effluent Release Reports to be submitted each year:

4 The Radioactive Effluent Release Reports shall include a summary of the quartitles of radioactive liquid and gaseous affluents and solid waste released from the unit as outlined in Reg. Guide 1.21, Rev.1, with data surnmartzed on a quarterly basis following the format of Appendtx B thereof.

2.3 Tina Radioactive Effluent Release Reports shall include the following information for eac'h type of i solid waste shipped offsite during the report period:

. a.- container volume, 1

b. total curie quantity (specify whether determined by measurement or estimate),

c. principal radionucildes (specify whether determined by. measurement or estimate),

d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

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

f. solldtlication agent (e.g., cement).

2.4 The Radioactive Effluent Release Reports shall include a summary of unplanned re! eases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents mada during the reporting period.

2.5 The Radioactive Effluent Release Reports shall include ar$y changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) docurnents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for c'ose calculations and/or environmental monitoring id-ntffled by the land use census pursuant to Part lil Section 8.2.

2.6 The Radioactive Effluent Release Reports shall include the instrumentation not retumed to OPERABW status within 30 days per ODCM Part I Controls 2.1.1b and 2.2.1b.

179.0 ,

me

03-12-97 08:16:22 i

Number ggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 j Tiue Revtalon No.

Offsite Dose Calculation Manual (ODCM) 11 2.7 The Radioactive Effluent Release Report to be submitted shall include an annual summary of hourly i meteorological data collected over the previous year. This annual surnmary may be either in the j form d an hour-by-hour listing of wind speed, wind direction, atmosphere stabilty, and precipitation (If measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind

direction, and atmospheric stabilty.

2.8 The Radioactka Emuent Release R'eport shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous ,

i calendar year. l I

2.9 The Radioactive Emuent Release Report shall include an assessment of the radiation doses from

radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their actMties inside.

! the SITE BOUNDARY during the report period. All assumptions used in making these assessments I i (i.e., specific actMty, exposure tirne and location) shaE be included in these reports. The 1 t

meteorological conditions concurrent with the time of release'of radioactive materials in gaseous emuents (as determined by sampling frequency and measurement) shall be used for determining the

gaseous pathway dosos.. The --ment of radiation doses shall be performed in accordance with this ODCM.

J 2.10 The Radioactfve Emuent Release Report shag also include an assessment of radiation doses to the j likely most exposed real Individual from reactor releases and other nearby uranium fuel cycle

~

sources including doses from primary eMuont pathways and direct radiation for the previous 12 4 consecutive months to show conformance with 40 CFR 190 'Erwirc,nmental Radiation Protection d

Standards for Nuclear Power Operation."~ Acceptable methods for calculating the dose contributions y from liquid and gaseous emuents are given in Regulatory Guide 1.109, Rev.1.

4 4

3 .

3 180.0 me.

\

i l

l

03-12-97 08:1G:22 -

wmt.

glgy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 i j tm n., won m. l

~ '

. Offsite Dose Calculation Manual (ODCM) 11

, 3.0 PART IV REFERENCES 1

3.1 Radiological Assessment Branch Technical Position Revision 1, November 1979

. 3.2 Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting RadioactMty in' Solid Waste 6 and Releases d Radioactive Materials iri Liquid and Gaseous Effluents from Ught-Water-Cooled Nuclear Power Plants," Revision 1 June 1974

~

3.3 TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50 3.4 Title 40, Code of Federal Regulations, " Protection of Environrnent' ,

I 3.5 Regulatory Guide 1.109, ' Calculation of Annual Doses to Man from Routine Releases of Reactor

. Emuents for the Purpose of Evaluating Compilance with 10 CFR Part 50, Appendix 1," Revision 1.-

October 1977 l

3.6 ' Title 10, Code of Federal Regulations, " Energy" 3,7 Regulatory Guide 1.111,' Methods of Estimating Atmospheric Transport and Dispersion of Gaseous l 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 Efiluents from Ught-Water-Cooled Power Reactors," Revision 0-R, AprI 1976 3.9 ' Regulatory Guide i.113," Estimating Aquatic Dispersion of Emuents from Accidental and Routine Reactor Releases for the Purpose of Irnpiementing Appendbc 1," Revision 1. Aprl 1977 9

t 4

• 181.0 me, e

l l

03-12-97 08:16:22 I

Nuclear- TMl Radiological Controls D,.. P,,cedo,e io.ptu.42oo.o1 i Tiue W No.

Offsite Dose Calculation Manual (ODCM) 11 APPENDIX 'A '

P, - Pathway Dose Rate Parameter P, (Inhalation) = k' (BR) DFA, (Eq A-1) i Where:

i

P, = the pathway dose rate parameter for radionuclide, I, (other than noble gases) for the inhalation pathway, in I

mromfyr per microcurle/m 3. The dose factors are based on the citical individual organ for the child age group.

l I

k' - conversion factor,1E6 pCl/ microcurie .

BR = 3700 m /yr,3 breathing rate for chMd (Reg. Guide 1.109; Rev.1, Table E-5)'

l

-DFA, = the maximum organ inhalation dose factor for the Infant age group for the ith nadlonuclide (mrem /pCl).

Values are taken from Table E-10, Reg. Guide 1.109 (Rev.1).

Resolution of the units yields: (ODCM Part til Table 4.6)

P, (inhelstion) = 3.7E9 DFA, (mrom/yr per pCl/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 nge group has .

been changed from infant to child.

9 4

9 I

E1-1 ma

i .

j 03-12-97 08:16:22

. Numtm Nuclear i Radidogical Contr$

Departmental Procedure 6610-PLN-4200.01 I no. un no.

i ,

l Offsite Dose Calculation Manual (ODCM) 11 4

APPENDIX B l

RI-Inhalation Pathway Does Factor ,

i l

8

R, = k' (BR) (DFAg) (mrom/yr per microcurie /m ) (Eq B-1) l Where

k' = corwersion factor,1E6'pCl/ microcurie 3

BR - breathing rate, 1400,3700,8000,8000 m /yr for Infant, chid, teenager, and adult age groups, j respectively. (Reg. Guide 1.109, Rev.1, Table E 5)

DFAg, - 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 DF43,n.

i Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Rev.1).

j Resolutions of the units ybids:

R1 = (1.4E9) (DFAi ,,) Infant (ODCM Part 111 Table 5.2.1)

Ri - (3.7E9) (DFAi ,,) child (ODCM Part it! Table 5.2.2) l

. RI = (8.0E9) (DFAi ,,o) teen and adult (ODCM Part til Tables 5.2.3 and 5.2.4) i a

1 I

1 i

5 o 1

I e

s

~

E2-1 me-

l 03-12'-97 08:16:22 g,,,,,

Nuclear

" "*d 'oa'ca' ooao

Departmental Procedure . 6610-PLN-4200.01

. m. woon No. l

! Offsite Dose Calculation Manual (ODCM) 11 i i

i APPENDIX C d

. RI- Ground Plane Pathway Does Factor i

j R, '= k' k" (SF) (DFG,) [(1-e 4)/M (Eq C-1)

Where:

1 k' = conversion factor, IES pCl/ microcurie  !

i j k' = conversion factor,8760 hr/yr J, - decay constant for the l* radionuclide, secd

t= the exposure time (this calculation assumes that decay is the' only operating removal rnechanism) 4.73 x l 10s sec. (15 yrs), Reg. Guide 1.109 (Rev.1), Appendix C

! DFG,= the ground plane dose conversion factor for the (* radionuclide (mrom/hr por pCI/m2). Values are taken from Table E-8, Reg. Guide 1.109 (Rev.1). These values acolv to all aos aroups.

SF = 0.7, shielding factor, from Table E-15 Reg. Guide 1.109 (Rev.1)

Reference'ODCM Part til Table 5.3.1 4

4 1

]

l 4

i i .

2 F3-1 ,

me, 4

4 4

4

03-12-97 08:16:22 (UCIS8r MI Radidogical Contrds Departmental Procedure 6610-PLN-4200.01 me s.viWon No.

Offsite Dose Calculation Manual (ODCM) 3 APPENDIX D RI- Grass Cow-Milk Pathway Dose Factor R, = k' [(Q, x U,) / (A, + A,,)] x (F,) x (r) x (DFV x

(((f, x f,)/Y,) + ((I-f, x f ) e Th)/YJ eTf (Eq D-1)

Where:

, k' = conversion factor,1E6 picocurle/ microcurie (pCl/pci) -

4 Q, = cow consumption rate. 50 kg/dey, (Reg. Guide 1.109, Rev.1) j l goat consumption rate,6 kg/ day, (Reg. Guide 1.109, Rev.1, Table E-2)

I U, = Receptor's milk consumption rate; 330, 330, 400, 310 liters /yr for infant, chud, teenager, and adult l age groups, respectively (Reg. Guide 1.109, Rev.1) '

Y, = agdcultural productMty by unit area of pasture feed grass,0.7 kg/m' (NUREG-0133)

Y, = agricultural productivity by unit area of stored feed 2.0 kg/m2(NUREG4133) l F, - stable element transfer coefficient (Table E-1, Reg. Guide 1.109, Rev.1) r= fraction of deposited actMiy 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 does factor for organ, o, and the Ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev.1)

A, - decay constant for the Ith radionuclide, sec4 d

J, = decay constant for weathering,5.73 x 1Cr'see (NUREG-0133); based on a 14 day half life t, = 1.73 x 10'sec, the transport time from pasture to cow to milk to receptor (Table E 15, Reg.

Guide 1.109, Rev.1), or 2 days t, - 7.78 x 10'sec, the transport time from pasture to harvest to cow to milk 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 E

E4-1 me,

d 03-12-97 08':16:22 Number d

i gggp TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 1

in. a.vi n wo.

4 Offsite Dose Calculation Manual (ODCM)- 11 l APPENDIX D '(Cont'd) t

, The concentration of tritium in milk is based on the airbome cone'entration rather than the deposition. Therefore, Ri i is based on (X/Q): ,

' Rc, = k'k"' F, .Q, U,DFQ (.75 [.5/H])

.(Eq D-2) i Where:

k"' - 1E3 grams /kg H- 8 grams /m8, abeolute humidity of the atmosphere

.75 = fraction of the total feed grass mass that is water

.5 = ratio of the specific activity of the feed grass water to the atmospheric water (NUREG-0133)

DFQ = the Ingestion does factor for tritium and organ, o, for each respectNe age group, a (Tables E.11 to E-14,

- Reg. Guide 1.109, Rev.1) j .

'All other parameters and values are as given above.

NOTE Goat-mIk pathway factor, Ri , wR be computed using the cow-mik

. pathway factor equation. F m factor for p-mRk will be from Table E-2

! Reg. Guide 1.109, Rev.1. ,

i

Reference:

ODCM Part til Tables 5.4.1 to.S.4.4 4

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9 .

4 e

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4 03-12-97 08:16:22 Number 1

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Offsite Dose Calculation Manual (ODCM) .

11 4

l APPENDIX E l RI- Cow-Meet Pathway Dose Factor J

R, = k' [(Qi x U,) / (4 + 4)] x (F,) x (r) x (DFig)x

(((f, x f,)/Y,) + ((1-f,f,) e- th)/Y,] x e ff .(Eq E-1),

Where: -

! k'= conversion factor,1E6 picocurle/ microcurie (pCl/pci) '

j Q, - cow consumption rate,50 kg/ day, (Reg. Guide 1.109, Rw.1)

U, = Receptor's meat consumption rate 0,41,65,110 kg/yr for infant, chid, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev.1) -

. F, = . the stable element transfer coefficients, days /kg (Table E-1, Reg. Guide 1.109, Rev.1) r= fraction of deposited activity retained in cow's feed grass,0.2 for particulates,1.0 for radiolodine (Table E-15, Reg. Guide 1.109,' Rev.1)

DF(, - tlke ingestion dose factc for organ, o, and the Ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide,1,109 Rev.1) a

A, - decay constant foi the radionuclide I, sec'1 -

4 l 4 = decay constant for weathering, 5.73 x 10T sec-1.(NUREG-0133)', based on a 14 day half life t, = 1.73 x 10s sec, the transport.tirne from pasture to receptor (NUREG 0133) ;

t=

h 7.78 x 10e sec, the transport time from crop to receptor (NUREG-0133) .

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 (NUREG 0133) '

f, = 1.0, the fraction of the year that the cow is on pasture i

j f, = 1.0, the fraction of the cow feed that is pasture grass whle the cow is on pasture The concentration of triflum in meat is based on the altborne concentration rather than the deposition. Therefore,

• R,is based on (X/Q):

R9,, = k*k"' F, Q, U, (DFLu ,,) x 0 75 x (0.5/H]) (Eq E-2)

Where:

All terms are as defined above and in Appendix D..

Reference:

ODCM Part 111. Tables.5.6.1 to 5.6.4

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J

, 03-12-97 08:16:22 gggy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 nn. mw.

Offsite Dose Calculation Manual (ODCM) 11 I APPENDIX F RI-Vegetation Pathway Dose Factor I

R; = k' x [r/ (Y, ([3 + Q)] x (DF() x [(ULag ) f e#L + U.8, f, e4h] (Eq F-1)

Where: i

. l k' = 1E6 picocurle/ microcurie (pCl/pci) l L I U,= the consumption rate of fresh leafy vegetation,0, 26,42,64 kg/yr for infant, child, teenager, or adult age '

groups, respectively (Reg. Guide 1.109, Rev.1) i Usa = the consumption rate of stored vegetation,0,520,630,520' kg/yr for Infant, chid, teenager, or adult age l groups respectively (Reg. Guide 1.109, Rev.1) f=g the fraction of the annual intake of fresh leafy vegetation grown locally, = 1.0 (NUREG-0133) ,.

1 i f, = the fraction of the stored vegetation grown locally = 0.76 (NUREG4133) l t=g the average time between harvest of leafy vegetation and Rs consumption,8.6 x 104 seconds

[ Table E 15, Reg. Guide 1.100, Rev.1 (24 hrs))

t=h the average time between harvest of stored leafy vegetation and Rs consumption,5.18 x los seconds,

[ Table E-15, Reg. Guide 1.109, Rev.1.(60 days))

~

2 y, = the vegetation area density,2.0 kg/m (Table E-15, Reg. Guide ' 1.109, Rev.1)

~

All other parameters ara as previously defined.

l The concentration of trtium in vegetation is based on the, airborne concentration rather than the deposition.

)

Therefore. R, is based on (X/Q)

• i

= k'k"' [U AI t + U'AI g] (DQ (.75 !.5/H])

L R (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 9

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03-12-97 08:16:22 3

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Departmental Procedure i

Tao. 6610-PLN-4200.01 l'

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Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES (Page 1 of 4)

Parameters Used in Dose Factor Calculations t L

] Origin of Value 1 1 Table in Section of Ste-Parameter Value R.G.1.10g NUREG4133 SpecMc i

}

• • • For P, ***

DFA Each radionudide E-9 Note 1 BR 3700 m'/yr (cnid) E4

"-For Al(Vegetation)*

r Each element type E1 Y, 2.0 kg/m' E-15 Aw 5.73 E-7 et.c' 5.3.1.3 DFL, Each age group and redlonuclide E-11 thru E 14 Note 1 U," Each age group E4 fg 1.0 5.3.1.5 16 8.6 E + 4 seconds E 15 U,' Each age group E4 -

f, 0.76 5.3.1.5 t, 6.18 E + 6 seconds E-15 H 8.0 grams /k0 5.2.1.3

"For RI (Inhalation)"

BR Each age Group E-6 DFA Each a0e Group and E-7 thru E-10 nuclide Note 1 O

E,. ,

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Number j Departmortal Procedure 6610-PLN-4200.01 rm i n.vWon No.

Offsite Dose Calculation Manual (ODCM) 3 I

I APPENDIX A F REFERENCES 4

(Psge 2 of 4) j i

Parameters Used in Dose Factor Calculations Origin of Value i Table in Section of Site-Parameter Value - R.G.1.109 NUREG4133 Specific l

• For R, (Ground Plane) *** '

SF 0.7 E-15

. DFG, Each radionudide E6

. t 4.73 E + 8 sec 5.3.1.2

• • • For RI (Groes/Animel/ Meet) ***

Q,(Cow) 50 kg/ day E3 I

Q, (Goat) 6kg/ day E.3 Ref. Only U, Each age group E6 i Aw 5.73 E-7 sec' 5.3.1.3 F (Both) Each element E-1 r Each element type E 15 DFL, Each age group and nuclide E-11 thru E 14 Note 1 f, 1.0 5.3.1.3 Note 2

f, 1.0 5.3.1.3 Note 2 j Y, 0.7 kg/nf E-15 t, 7.78 E + 6 sec E 15 8

Y, 2.0 kg/m E-15 j t, 1.73 E + 6 see E-15 H 8.0 grams /kg 5.2 1 3 9

E7-2 mm 4

4 4

03-12-97 08:16:22 9 Numbw '

(gdgp TMI Radiological Controis Departmental Procedure i me 6610-PLN-4200.01 won so.

Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES j i

lI (Page 3 of 4) j Parameters Used in Dose Factor Calculations Origin of Value 5

Table in Section of Site-

! Parameter Value R.G.1.109 NUREG4133 Specific

• For S (Grase/ Cow /M8k)

• j Q, 50 kg/ day E-3 l

U,, Each age group E4 i

Aw 5.73 E 7 sec' 5.3.1.3 F. Each element E-t r Each element type E-15 DFL, Each age group and nuclide E-11 thru E-14 Note 1 Y, 0.7 kg/m' E-15

t. 7.78 E + 6 sec E 16 9

Y, 2.0 kg/m' E-15 t, 1.73 E + 5 see E 15 1,

i f, 1.0 5.3.1.3

f. 1.0 .

5.3.1.3 H 8.0 Grams /kg 5.2.1.3 b

j

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i jug E TMI Radiological Controls Numtwr Departmental Procedure 6610-PLN-4200,01

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Offsite Dose Calculation Manual (ODCM) 3 i

l APPENDIX A-F REFERENCES (Page 4 of 4) i NOTES i 1.

Inhalation and ingestion dose factors were taken from the indicated source. For each age gro

{ nuclide, the referenced organ does factor used was the highest dose factor for that nuclide and age group in th table.

1 2.

Typically beef cattle ore raised all year on pasture. Annual land surveys have indicated that the sm number of goats raised within 5 rnies typiceNy are used for grass control and not food or milk.

Nevertheless, the goats can be treated as full meet sources where present, despite the fact that their }

numbers cannot sustain the meet consumption rates of Table E4, NUREG-0133. l REFERENCES i

1. I Regulatory Guide 1.100, Talculation of Annual Doses to Man imm Routine Releases of Reactor E the Purpose of Evaluating Compliance with to CFR Part 50, Appendix 1," Revision 1. October 1977.

i 2.

TMI-1 Technical Specifications, attached to FacAlty Operating Ucense No. OPR40.

3.

NUREG4133, " Preparation of Radiciogical EfBuent Technical SpecNications for Nud aar Power P October 1978.

h i

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