Text

Combined 2002 Annual Radioactive Effluent Release Report, Section 3.0 Through Table 2.1-2
	ML031630807
Person / Time
Site:	Crane
Issue date:	04/30/2003
From:	George Gellrich; AmerGen Energy Co
To:	; Document Control Desk, NRC/FSME
References
	-RFPFR, 5928-03-20051 6610-PLN-4200.01, Rev 23
	Download: ML031630807 (128)
	v • d • e

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN-4200.01_

Tile evision No Offsite Dose Calculation Manual (ODCM) 23 3.0 SURVEILLANCES 3.0.1 Surveillance Requirements shall be applicable during the conditions specified for individual Controls unless otherwise stated in an individual Surveillance Requirement.

The Surveillance Requirements shall be performed to demonstrate compliance with the OPERABILITY requirements of the Control.

3.0 2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

3.0.3 Failure to perform a Surveillance Requirement within the time interval specified in Section 3.0.2 shall constitute non-compliance with OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation Surveillance Requirements Radioactive Liquid Effluent Instrumentation is common between TMI-1 and TMI-2.

Surveillances for this instrumentation are specified in ODCM Part I, Surveillance 3.1.1.

3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation SURVEILLANCE REQUIREMENTS 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2.

78

66' Re Table 3.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENT

1.

Containment Purge Monitoring System

a.

Noble Gas Activity Monitor (2HP-R-225)

b.

Particulate Sampler (2HP-R-225)

2.

Station Ventilation Monitoring System

a.

Noble Gas Activity Monitor (2HP-R-219) and (2HP-R-219A)

b.

Particulate Sampler (2HP-R-219) and (2HP-R-219A)

CHECK CALIBRATION ILSI D

w D

w E

N/A E

N/A M

N/A 1 0-P LN-4200.01 visIon 23 APPLICABILITY NOTE 1 NOTE 1 NOTE 1 NOTE 1 NOTES:

I.

During operation of the monitored system.

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Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 3.2 Radioactive Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration 3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with Table 3.2-1. The results of analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.1.2 Analysis of samples composited from batch releases shall be performed in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2 1.1.

3.2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2 1.2 Dose Calculations 3 2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month.

3.2.1.3 Dose Projections 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM.

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Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 3.2-1 Radioactive Liquid Waste Sampling and Analysis (4, 5)

A.

Liquid Releases Sampling Frequency Type of l

Detectable Il Activity Analysis j

Concentration (3) l Individual Gamma 5E-7 IlCiml (2)

Each Batch H-3 IE-5 ItCi/ml l

Gross Alpha 1E-7 iCi/ml Quarterly Composite (1)

Sr-90 5E-8 plCi/mI NOTES:

(1)

A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant.

(2)

For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near this sensitivity limit 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 radionuclides using measured ratios with those radionuclides which are routinely identified and measured.

(3)

The detectability limits for radioactivity analysis are based on the technical feasibility and on the potential significance in the environment of the quantities 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 performed, the average of the two adjacent data points spanning this period should be used. Such estimates should be included in the effluent records and reports; however, they should be clearly identified as estimates, and the method used to obtain these data should be described.

(5)

Deviations from the sampling/analysis regime will be noted in the report specified in ODCM Part IV.

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Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 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 accordance with the methods and procedures of the ODCM.

3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 3.2-2.

3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.3 Dose, Tritium and Radionuclides In Particulate Form 3.2.2.3.1 Cumulative dose contributions from Tritium and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3 2.2.4 Ventilation Exhaust Treatment 3 2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM.

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Number 661 0-PLN4200.01 TMI - Unit 1 Radiological Controls Procedure Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 3.2-2 Radioactive Gaseous Waste Sampling and Analysis (3) 1 DETECTABLE SAMPLE SAMPLING TYPE OF CONCENTRATION(1)(

SAMPLE POINT

--TYPE FREQUENCY ACTIVITY ANALYSIS a)

Reactor Building Purge Releases P

H-3 I E-6 gCVcc Gas Each Purge Gamma Emitters 1 E-4 pCicc (2)

Unit Exhaust Vent Release Points M

H-3 1 E-6 zIC icc Gas MnhyIndividual 1E4pic 2 Gas Monthly Gamma Emitters IE jilcc (2)

W Individual (b)

E10lCVc(2 Weekly Gamma Emitters 1E-10 jiCicc (2)

M Particulates Monthly Sr-90 1 E-11 I iCi/cc M

Monthly Gross Alpha Emitters 1 E-1 1 pCi/cc Composite Reactor Building Breather Indv. Gamma 1 E-10 pC1cc (2)

Patclts SA Emitters (b)

IE10pic 2 ParticulatesSemi-Annually Sr-90 1 E-1 1 gCi/cc l

I Gross Alpha Emitters 1 E-1 1 aC i/cc (1)

The above detectability limits are based on technical feasibility and on the potential significance in the environment of the quantities 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.

(2)

For certain mixtures of gamma emitters, it may be possible to measure radionuclides at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios in the gaseous component in the reactor coolant for those radionuclides which are measurable.

(3)

Deviations from the sampling and analysis regime will be noted in the report specified in ODCM Part IV.

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Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 3.2-2 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):

LLD =

4.66 sp E x V x 2.22 X 106 X Y x exp (-XAt)

Where LLD is the lower limit of detection as defined above (as picocurie per unit mass or volume).

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).

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

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

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

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples),

The value of Sb used 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 normally present in the samples. Typical values of E, V.

Y, and At shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be with +/- one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma-ray peak used for the quantitative analysis for that radionuclide.

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Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Tide Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 3.2-2

b.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.

85

Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN4200.01_

Title Revision No Offsite Dose Calculation Manual (ODCM) 23 3 2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM.

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Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Ttle Revision No Offsite Dose Calculation Manual (ODCM) 23 4 0 PART II REFERENCES 4.1 NUREG-0683, 'Final Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28, 1979, accident Three Mile Island Nuclear Station, Unit 2," March 1981, and its supplements.

4 2 TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-73 4.3 Title 10, Code of Federal Regulations, 'Energy" 4.4 "Statement of Policy Relative to the NRC Programmatic Environmental Impact Statement on the Cleanup of Three Mile Island Unit 2," dated April 27, 1981 4.5 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 4.6 DOEITIC-27601, Atmospheric Science and Power Reduction 4.7 TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50 4.8 PDMS-SAR 87

Number TMI - Unit 1 I

Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 PART IIl EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES 88

Number TMI - Unit 1 I

Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 1.0 LIQUID EFFLUENT MONITORS 1.1 TMI-1 and TMI-2 Liquid Radiation Monitor Set Points The liquid effluent off-line monitors are set such that the concentration(s) of radionuclides in the liquid effluents will not exceed ten times the concentrations specified in 10 CFR 20, Appendix B Table 2, Col 2. Table 1.1 lists the Liquid Effluent Release Points and their parameters; Figure 1.1 provides a Liquid Release Pathway Diagram.

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

TC (eq 1.1)

F +f where:

C= ten times the effluent concentration of 10 CFR 20 for the site, in pCifml.

c = the set point, in pCi/ml, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to dilution and release. The set point is inversely proportional to the maximum volumetric flow of the effluent line and proportional to the minimal volumetric flow of the dilution stream plus the effluent stream. The alert set point value is set to ensure that advance warning occurs prior to exceeding any limits. The high alarm set point value is such that if it were exceeded, it would result in concentrations exceeding ten times the 10 CFR 20 concentrations for the unrestricted area.

f =

flow set point as measured at the radiation monitor location, in volume per unit time, but in the same units as F below.

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

The set point concentration is reduced such that concentration contributions from multiple release points would not combine to exceed ten times 10 CFR 20 concentrations The set point concentration is converted to set point scale units using appropriate radiation monitor calibration factors.

This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and, for batch releases, the Releasing Radioactive Liquid Waste procedure.

89

Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.0 I Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 1.2 TMI Liauid Effluent Release Points and Liauid Radiation Monitor Data TMI-1 has two required liquid radiation monitors. These are RM-L6 and RM-L12. These liquid release point radiation monitors and sample points are shown in Table 1.1. (The TMI outfall radiation monitor, RM-L7, is also listed for information only.)

TMI-2 does not have any required liquid radiation monitors, but does utilize RM-L12, and RM-L7 for release of liquid waste.

1.2.1 RM-L6 RM-L6 is an off-line system, monitoring radioactive batch discharges from 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 times the 10 CFR 20 concentrations [20% for H-3] to radionuclide concentrations in the unrestricted area, including conservative default values for Sr-89, Sr-90, and Fe-55.

The release flow rate used is the most restrictive of two flow rates calculated for each liquid batch release, per the approved plant procedure.

Two Dilution Factors (DF) are calculated to ultimately calculate the batch release flow rate. These two DF's are calculated to insure each radionuclide released to the unrestricted area is less than 10 percent of ten times the 10CFR20 radionuclide concentrations, (20% for H-3), and to ensure each liquid batch release boron concentration to the river will not exceed 0.7 ppm.

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

DF into 90 percent of the current dilution flow rate of the Mechanical Draft Cooling Tower (MDCT). This conservative flow rate is then multiplied by 0.9 for the allowable flow rate.

Calculation of the 10CFR20 concentration DF:

DF = II (SA) + (10% [20% for H-3] of ten times the 1 OCFR20 concentration)

SA =

Specific Activity of each identified radionuclide Calculation of Boron DF:

DF2 = Actual Tank Boron Concentration + 0.7.

Maximum release flow rate calculation:

Max Flow = [(MDCT flow gpm

0.9) + (Most Restrictive DF)]

0.9 The dilution 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 will meet the following equation.

I(C1IXI) + (CH.3I2XH-3) < 0-1, (eq 1.2) 90

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 where:

Ci = diluted concentration of the ith radionuclide, other than H-3 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 pCi/ml for dissolved and entrained noble gases shall be used.

CH- =diluted concentration of H-3 XH-3 =Ten times the concentration for H-3 in the restricted area (10 CFR 20, App. B, Table 2, Col. 2)

The set points for RM-L6 are based on the maximum release rate (30 gpm), a minimum dilution flow (5000 gpm), and 25% of ten times the 10CFR20 concentration for Cs-137, which is the most limiting radionuclide at a concentration of 1.OE-5 uCi/mI. These inputs are used in Equation 1.1 to determine the RM-L-6 High Alarm setpoint for all radionuclides being released. A high alarm on RM-L-6 will close valve WDL-V-257 and terminate any WECST releases to the environment.

1.2.2 RM-L12 RM-L12 is an off-line system, monitoring periodic combined releases from the Industrial Waste Treatment System/Industrial Waste Filtration System (IWTSIIWFS). The input to IWTS/IWFS originates in TMI-2 sumps, (see Figures 1.1 and 1.2) and the TMI-1 Turbine Building sump (see Figure 1.1). The set points are based on the maximum release rate from both IWTS and IWFS simultaneously, (see Figure 1.1) a minimum 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-5 jCilml. 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 will close IWTS and IWFS release valves and trip release pumps to stop the release.

1.2.3 RM-L1 0 RM-L10 was a Nal detector submerged in the TMI-1 Turbine Building Sump. This detector has been removed from service.

1 2 4 RM-L7 RM-L7 is not an ODCM required liquid radiation monitor. RM-L7 is an off-line system, monitoring the TMI outfall to the Susquehanna River (see Figures 1.1 and 1.2). This monitor is the final radiation monitor for TMI-1 and TMI-2 normal liquid effluent releases.

1.3 Control of Linuid Releases TMI liquid effluent releases are controlled to less than ten times the 10CFR20 concentrations by limiting the percentage of this limit allowable from the two TMI liquid release points. RM-L6 and effluent sampling limit batch releases to less than or equal to 25% for all radionuclides, and RM-L12 and effluent sampling limit releases from TMI-1 and TMI-2 to less than or equal to 50% for Cs-1 37.

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

91

Number TMI-Unit I I

Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 The radioactivity 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 or ODCM Part II, Table 3.2-1.

The results of analyses are used with the calculational methods in Section 1.1, to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part !! Control 2.2.1.1.

Post-release analysis of samples composited from batch releases are performed in accordance with ODCM Part I Table 3.2-1 or ODCM Part !! Table 3.2-1..The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part !!

Control 2.2.1.1.

The radioactivity concentration of liquids discharged from continuous release points are determined by collection and analysis of samples in accordance with ODCM Part I Table 3.2-1, or ODCM Part I!

Table 3.2-1. The results of the analysis are used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part !! Control 2.2.1.1.

92

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revsion No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 1.1 TMI Liquid Release Point and Liquid Radiation Monitor Data RELEASE LIQUID RADIATION LIQUID RELEASE TERMINATION MONITOR l POINT (Maximum DISCHARGE FLOW INTERLOCK (DETECTOR)

LOCATION Volume)

RECORDER (YES/NO) VALVES RM-L6 281' Elevation WECST Batch FT-84 YES (Nal)

TMI-1 Auxiliary Bldg Releases (8000 gal.)

WDL-V257 R(NM-1-)7 South end of TMI-1 Station Discharge YES (Nal)

MDTTMI-1 and FT-146 WDL-V257 TMI-2,

WDL-R-1311 YES IWTS/IWFS IW-V73, RM-L12 IWFS Building NW Continuous Releases FT-342/

IW-P16,17,18 (Nal)

Corner (300,000!

FT-373 80,000 gal.)

IW-V279, l_

IW-P29,30 WDL-R-1311 has been flanged off as a TMI-2 liquid outfall.

- RM-L7 is not an ODCM required liquid radiation monitor.

93

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 1.2 TMI-2 Sump Capacities l

Total l

Capacity Gallons Sump Gallons per Inch Turbine Building Sump 1346 22.43 Circulating Water Pump House Sump 572 10.59 Control Building Area Sump 718 9.96 Tendon Access Galley Sump 538 9.96 Control to Service Building Sump 1346 22.43 Contaminated Drain Tank Room Sump 135 3.80 Chlorinator House Sump Water Treatment Sump**

1615 22.43 Air Intake Tunnel Normal Sump 700 Air Intake Tunnel Emergency Sump 100000 766.00 Condensate Polisher Sump 2617 62.31 Sludge Collection Sump**

1106 26.33 Heater Drain Sump Solid Waste Staging Facility Sump 1476 24.00 Auxiliary Building Sump 10102 202.00 Decay Heat Vault Sump 479 10.00 Building Spray Vault Sump 479 10.00 Condensate Polisher Sump is deactivated and in PDMS condition.

- The Water Treatment and Sludge Collection Sumps will be deactivated for PDMS 94

661 0-PLN-4200.01 Revision 23 Figure 1.1 TMI-1 Liquid Effluent Pathways Composite Radiation Sampler W~~

Radwaste I

Grab Disposal Es-Sample Pre-Operation Chemical Cleaning Basins 2 Component Cooling Water TMI-1 a

X to RIVER 95

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN_200.01__

Title Revision No Offsite Dose Calculation Manual (ODCM) 23 FIGURE 1.2 TMI-2 Liquid Effluent Pathways CONTROL BUILDING SUMP I

CONTROL &

SERVICE AREA SUMP TURBINE BUILDING SUMP TENDON ACCESS GALLERY SUMP I I n

IWTS SUMP l

INDUSTRIAL WASTE TREATMENT SYSTEM 4

P rI RML1

-- COMPOSITE SAMPLER 0-96

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 2 0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liouid Effluents - 10 CFR 50 Appendix I The dose from liquid effluents results from the consumption of fish and drinking water. The location of the nearest potable water intake is PP&L Brunner Island Steam Electric Station located downstream of TMI. The use of the flow of the Susquehanna River as the dilution flow is justified based on the complete mixing in the river prior to the first potable water supply, adequately demonstrated by flume tracer die studies and additional liquid effluent release studies conducted using actual TMI-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=

(At)X (Cl) X AW ijX

+ (AFij X f X

(eq 2.1) where:

Dose j =

the cumulative dose commitment to the total body or any organ, j, from the liquid effluents for the total time period, in mrem.

At =

the length of the time period of actual releases, over which C, and f are averaged for all liquid releases, in hours.

C1 =

the average concentration of radionuclide, i, in undiluted liquid effluent during time period At from any liquid release, in pCi/ml.

NOTE For Fe-55, Sr-89, Sr-90, prior to batch releases conservative concentration values will be used in the initial dose calculation based on similar past plant conditions. LLD values are not used in dose calculations.

f =

undiluted liquid waste flow, in gpm.

FD =

plant dilution water flowrate during the period of release, in gpm FR =

actual river flowrate during the period of release or average river flowrate for the month the release is occurring, in gpm.

DF =

dilution factor as a result of mixing effects in the near field of the discharge structure of 0.2 (NUREG 0133) or taken to be 5 based on the inverse of 0.2.

AWij and AFij =

the site-related ingestion dose commitment factor to the total body or any organ, j, for each identified principle gamma and beta emitter, in mrem/hr per pCi/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway.

97

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Reision No Offsite Dose Calculation Manual (ODCM) 23 Values for AWij are determined by the following equation:

AWj = (1.14E5) x (U,) x (DFi1)

(eq 2.2) where:

1.14E5 =

(1.OE6 pCilCi)x (1.OE3 mllkg)+(8760 hrlyr)

Uw=

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

DFij =

ingestion dose conversion factor for radionuclide, i, for adults total body and for "worst case" organ, j, in mrem/pCi, from Table 2.1 (Reg. Guide 1.109)

Values for AF1j are determined by the following equation:

AFij =

(1.14E5) x (Uf) x (DFij) x (BFi)

(eq 2.2.2) where:

1.14E5 =

defined above Uf =

adult fish consumption, assumed to be 21 kg/yr (Reg. Guide 1.109, Rev. 1).

DFij =

ingestion dose conversion factor for radionuclide, i, for adult total body and for "worst case" organ, j, in mrem/pCi, from Table 2.1 (Reg. Guide 1.109, Rev. 1).

BFi =

Bioaccumulation factor for radionuclide, i, in fish, in pCi/kg per pCi/L from Table 2.2 (Reg.

Guide 1.109, Rev. 1).

2.2 TMI Liquid Radwaste System Dose Calcs Once/Month ODCM Part I Control 2.2.1.3 and TMI-2 PDMS Tech Spec Section 6.7A.a.6 requires that appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the monthly projected doses due to the liquid effluent releases from each unit to unrestricted areas would exceed 0 06 mrem to the total body or 0.2 mrem to any organ in any calendar month. The following calculational method is provided for performing this dose projection.

At least once per month, the total dose from all liquid releases for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual releases during the period for which the projection is made. If this projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, appropriate portions of the Liquid Radwaste Treatment System, as defined in Section 3.1, shall be used to reduce radioactivity levels prior to release.

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

98

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 2.3 Alternative Liquid Dose Calculational MethodoloqV As an alternative, models in, or based upon, those presented in Regulatory Guide 1.109 (Rev. 1) may be used to make a comprehensive dose assessment. Default parameter values from Reg.

Guide 1.109 (Rev. 1) and/or actual site specific data are used where applicable.

As an alternative dose calculational methodology TMI calculates doses using SEEDS (simplified environmental effluent dosimetry system).

The onsite and SEEDS calculational models use actual liquid release data with actual monthly Susquehanna River flow data to assess the dispersion of effluents in the river.

99

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFIJ Page 1 of 3 Ingestion Dose Factors for Adults*

(MREM Per PCI Ingested)

NUCLIDE BONE LIVER H

3 NO DATA 1.05E-07 C

14 2.84E-06 5.68E-07 NA 24 1.70E-06 1.70E-06 T. BODY THYROID KIDNEY LUNG 1.05E-07 1.05E-07 1.05E-07 1.05E-07 5.68E-07 5 68E-07 5.68E-07 5.68E-07 1.70E-06 1.70E-06 1.70E-06 1.70E-06 GI-LLI I1.05E-07 5.68E-07 I1.70E-06 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3 53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01 E-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-06 CU 64 NO DATA 8.33E-08 3.91 E-08 NO DATA 2.10E-07 NO DATA 7.1OE-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 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-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01 E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y

90 9 62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 100

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 2 of 3 Ingestion Dose Factors for Adults*

(MREM Per PCI Ingested)

BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NUCLIDE Y

91M Y

91 Y

92 9.09 E-11 1.41 E-07 8.45E-10 NO DATA NO DATA NO DATA 3.52E-12 3.77E-09 2.47E-1 1 NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA NO DATA 2.67E-1 0 7.76E-05 1.48E-05 Y

93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5 12E-10 NO DATA 1.05E-04 NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31 E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 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 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 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31 E-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 6.04E-05 SB 125 1.79E-06 2.OOE-08 4.26E-07 1.82E-09 0.0 1.38E-06 1.97E-05 TE 125M 2.68E-06 9.71E-07 3 59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05 1

130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 1

131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 I

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 3.63E-04 4.31E-06 NO DATA 2.22E-06 1

134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 101

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Tdle Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFIJ Page 3 of 3 Ingestion Dose Factors for Adults*

(MREM Per PCI Ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 1

135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS 134 6 22E-05 1.48E-04 1.21 E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS 136 6.51 E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS 137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA 139 9.70E-08 6.91 E-11 2.84E-09 NO DATA 6 46E-11 3 92E-11 1.72E-07 BA 140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA 141 4.71 E-08 3 56E-11 1.59E-09 NO DATA 3 31E-11 2 02E-11 2.22E-17 BA 142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA 140 2.50E-09 LA 142 1.28E-10 CE 141 9.36E-09 1.26E-09 5.82E-1 1 6.33E-09 3.33E-10 1.45E-11 7.18E-10 NO DATA NO DATA NO DATA NO DATA NO DATA 2.94E-09 NO DATA NO DATA NO DATA 9.25E-05 4.25E-07 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 3.01E-11 ND 147 6.29E-09 W

187 1.03E-07 1.25E-11 7.27E-09 8.61 E-08 1.53E-12 4.35E-10 3 01E-08 NO DATA NO DATA NO DATA 7.05E-12 4.25E-09 NO DATA NO DATA NO DATA NO DATA 4.33E-1 8 3.49E-05 2.82E-05 NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3 65E-10 NO DATA 2.40E-05 Dose factors of internal exposure are for continuous intake over a one-year period and include the dose commitment over a 50-year period; from Reg. Guide 1.109 (Rev. 1). Additional dose factors for nuclides not included in this table may be obtained from NUREG-0172.

102

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN-4200.01 Tite ReeMsion No Offsite Dose Calculation Manual (ODCM) 23 TABLE 2.2 Bioaccumulation Factors, BF, Bioaccumulation Factors to be Used in the Absence of Site-Specific Data*

(pCi/kg per pCi/liter)

ELEMENT l

FRESHWATER

_FISH INVERTEBRATE H

9.OE-01 9 OE-01 C

4.6E+03 9.1 E+03 NA 1.OE+02 2.OE+02 CR 2.OE+02 2.OE+03 MN 4.OE+02 9.OE+04 FE 1.OE+02 3.2E+03 CO 5.OE+01 2.OE+02 N I 1.OE+02 1.OE+02 CU 5 OE+01 4 OE+02 ZN 2.OE+03 1.OE+04 BR 4.2E+02 3 3E+02 RB 2.0E+03 1.OE+03 SR 3.OE+01 1.OE+02 Y

2.5E+01 1.OE+03 ZR 3.3E+00 6.7E+O0 NB 3 OE+04 1.OE+02 MO 1.OE+01 1.OE+01 TC 1.5E+01 5.OE+OO RU 1.OE+O1 3.OE+02 RH 1.OE+01 3.OE+02

- - AG-1 IOm 2.30E+1 7.70E+2

- SB 1.OE+00 1.OE+OO TE 4.OE+02 6.1 E+03 I

1.5E+01 5.OE+OO CS 2.OE+03 1.OE+03 BA 4.OE+00 2.OE+02 LA 2.5E+01 1.OE+03 CE 1.OE+00 1.OE+03 PR 2.5E+01 1.OE+03 ND 2.5E+01 1.OE+03 W

1.2E+03 1.OE+01 NP 1.OE+01 4.OE+02 Bioaccumulation factor values are taken from Reg. Guide 1.109 (Rev. 1), Table A-1j.

t*

Sb bioaccumulation factor value is taken from EPRI NP-3840.

Ag bioaccumulation factor value is taken from Reg. Guide 1.109 (Rev. 0), Table A-8.

103

Number 6610-PLN-42nnfn1 TMI - Unit 1 Radiolooical Controls Prcerdiire F._ Ad.

_v Title Revision No Offsite Dose Calculation Manual (ODCM) 23 3.0 TMI LIQUID EFFLUENT WASTE TREATMENT SYSTEMS 3.1 TMI-1 Liguid Effluent Waste Treatment System 3 1.1 Description of the Liquid Radioactive Waste Treatment System (see Figure 3.1)

Reactor Coolant Train

a.

Water Sources - (3) Reactor Coolant Bleed Tanks (RCBT)

- (1) Reactor Coolant Drain Tank (RCDT)

b.

Liquid Processing - Reactor Coolant Waste Evaporator (see Figure 3.2)

- Demineralizers prior to release

c.

Liquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks

- (WECST)

d.

Dilution - Mechanical Draft Cooling Tower (0-38k gpm)

- River Flow (2E7 gpm average)

Miscellaneous Waste Train a

Water sources: - Auxiliary Building Sump

- Reactor Building Sump

- Miscellaneous Waste Storage Tank

- Laundry Waste Storage Tank

- Neutralizer Mixing Tank

- Neutralizer Feed Tank

- Used Precoat Tank

- Borated Water Tank Tunnel Sump

- Heat Exchanger Vault Sump

- Tendon Access Galley Sump

- Spent Fuel Pool Room Sump

- TMI-2 Miscellaneous Waste Holdup Tank

b.

Liquid Processing - Miscellaneous Waste Evaporator, MWE (see Figure 3.2)

- Demineralizers prior to release c

Liquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks

- (WECST)

d.

Dilution - Mechanical Draft Cooling Tower (0-38k gpm)

- River Flow (2E7 gpm average) 104

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 3 2 Operabilitv of the TMI-1 Linuid Effluent Waste Treatment System 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 pieces of equipment is available to perform its intended function:

a)

Miscellaneous Waste Evaporator (WDL-Z1 B) or Reactor Coolant Evaporator (WDL-ZlA) b)

Waste Evaporator Condensate Demineralizer (WDL-K3 A or B) c)

Waste Evaporator Condensate Storage Tank (WDL-T 11 A or B) d)

Evaporator Condensate Pumps (WDL-P 14 A or B) 3.2.2 TMI-1 Representative Sampling Prior to Discharge All liquid releases from the TMI-1 Liquid Waste Treatment System are made through the Waste Evaporator Condensate Storage Tanks. To provide thorough mixing and a representative sample, the contents of the tank are recirculated using one of the Waste Evaporator Condensate Transfer Pumps.

3 3 TMI-2 Liquid Effluent Waste Treatment System 3.3 1 Description of the TMI-2 Liquid Radioactive Waste Treatment System The TMI-2 Liquid Radioactive Waste Treatment System has been out of service since the TMI-2 Accident in 1979. TMI-2 Liquid Radioactive Waste is processed by the TMI-1 system described in Section 3.1 prior to release. In addition, TMI-2 releases water from various sumps and tanks to the river (see Figures 1.1 and 1.2). These processes are governed by plant procedures that encompass proper sampling, sample analysis, and radiation monitoring techniques.

105

Number 661 0-PLN-4200.01 TMI - Unit 1 Radioloqical Controls Procedure Title Revision No Offsite Dose Calculation Manual (ODCM) 23 FIGURE 3.1 TMI-1 Liquid Radwaste B. A MU-VB MIX TANK I

DEMIN WATER WATER STOR TANK RECLAIMED WATER SYSTEM 106

6610-PLN-4200.01 Revision 23 FIGURE 3.2 TMI-1 Liquid Waste Evaporators 107

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 4.0 GASEOUS EFFLUENT MONITORS 4.1 TMI-1 Noble Gas Monitor Set Points The gaseous effluent monitor set points are established for each gaseous effluent radiation monitor to assure concentrations of radionuclides in gaseous effluents do not exceed the limits set forth in ODCM Part I Control 2.2.2.1. Table 4.1 lists Gaseous Effluent Release Points and their associated parameters; Figure 4.1 provides a Gaseous Effluent Release Pathway Diagram.

The set points are established to satisfy the more restrictive set point concentration in the following two equations:

500 >

(ci)(F)(Ki)(Dv)

(eq 4.1.1) and 3000 >

(ci)(L1 + 1.1 M)(Dv)(F)

(eq 4.1.2) where:

c= set point concentration based on Xe-1 33 equivalent, in IiCi/cc F = gaseous effluent flowrate at the monitor, in ccfsec

= total body dose factor, in mrem/yr per RCi/m 3 from Table 4.3 Dv = highest sector annual average gaseous atmospheric dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m 3, from Table 4.4 for station vent releases and Table 4.5 for all other releases, (Condenser off gas, ESF FHB, and ground releases).

Maximum values presently used are 7.17E-7 sec/M 3 at sector NNE for station vent, and 1.16E-5 sec/M 3 at sectors N and WNW for all other releases.

Li = skin dose factor due to beta emissions from radionuclide i, in mrem/yr per RCilM3 from Table 4.3.

M= air dose factor due to gamma emissions from radionuclide i, in mrad/yr per,ICi/m3 from Table 4.3.

1.1 =

mrem skin dose per mrad air dose.

500 = annual whole body dose rate limit for unrestricted areas, in mrem/yr.

3000 = annual skin dose rate limit for unrestricted areas, in mrem/yr.

The set point concentration is further reduced such that the concentration contributions from multiple release points would not combine to exceed ODCM Control limits.

The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors.

108

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste.

109

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 4.2 TMI-1 Particulate and Radioiodine Monitor Set Points Set points for monitors which detect radionuclides other than noble gases are also established to assure that concentrations of these radionuclides in gaseous effluents do not exceed the limits of ODCM Part I Control 2.2.2.1.

Set points are established so as to satisfy the following equations:

1500>

(c1)(F)(Pj)(Dv)

(eq 4.2) where:

cl = set point concentration based on 1-131 equivalent, in ItCi/cc F = gaseous effluent flow rate at the monitor, in cc/sec P. = pathway dose parameter, in mrem/yr per jiCi/m3 for the inhalation pathway from Table 4.6. The dose factors are based on the actual individual organ and most restrictive age group (child) (NUREG-0133).

NOTE Appendix A contains PI calculational methodology.

1500 = annual dose rate limit to any organ from particulates and radioiodines and radionuclides (other than noble gases) with half lives greater than eight days in mremlyr.

Dv = highest sector annual average gaseous dispersion factor (X/Q or D/Q) at or beyond the unrestricted area boundary from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. X/Q is used for the inhalation pathway. Maximum values of XIQ presently used are 7.17E-7 sec/m3 for station vent, at sector SE, and 1.16E-5 secIm3 for all other releases, at sectors N and WNW.

The set point concentration is further reduced such that concentration contributions from multiple release points would not combine to exceed ODCM Control limits.

The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors.

This section of the ODCM is implemented by the Radiation Monitor Systems Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste.

110

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 4.3 TMI-2 Gaseous Radiation Monitor Set Points TMI-2 Gaseous Radiation Monitors have their set points described in TMI Plant Procedure 1101-2.1.

Figure 4.5 provides a gaseous effluent release pathway diagram. Table 4.2 provides TMI-2 Radiation Monitor Data.

These set points are set in accordance with the Controls delineated in Part II of this ODCM 111

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMI-1 has eleven (11) required effluent gaseous radiation monitors. These are RM-A4, RM-A5, RM-A15, RM-A6, RM-A7, RM-A8, RM-A9, RM-A14, ALC-RMI-18, WHP-RIT-1, and RLM-RM-1.

These gaseous release points, radiation monitors, and sample points are shown in Table 4.1.

4.4.1 RM-A4/RM-A6 Fuel Handling and Auxiliary Building Exhaust RM-A4 is the particulate, radioiodine and gaseous radiation monitor for the TMI-1 Fuel Handling Building Ventilation (see Figures 4.1 and 4.2). RM-A6 is the particulate, radioiodine, and gaseous radiation monitor for the TMI-1 Auxiliary Building Ventilation (see Figures 4.1 and 4.2). High alarms on RM-A4 or RM-A6 noble gas channels will initiate shutdown of the related building ventilation air supply system. These two radiation monitors concurrently will satisfy requirements for the Station Vent release point in place of RM-A8.

4.4.2 RM-A8 Station Ventilation Exhaust RM-A8 is the particulate, radioiodine and gaseous radiation monitor for the TMI-1 Station Ventilation (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters. High alarm on RM-A8 noble gas low channel will initiate shutdown of the Station Ventilation air supply systems. (The Fuel Handling and Auxiliary Building Ventilation). This radiation monitor satisfies requirements for the Station Vent release point in place of RM-A4 and RM-A6.

4.4.3 RM-A5IRM-A15 Condenser Off Gas Exhaust RM-A5 is the gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). RM-A15 is the back up gaseous radiation monitorfor the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). High alarms on RM-A5 low channel or RM-A15 noble gas channels will initiate the MAP-5 Radioiodine Processor Station. These two radiation monitors together satisfy requirements for the Condenser Off Gas release point.

4A.4 RM-A7 Waste Gas Decay Tank Exhaust RM-A7 is the gaseous radiation monitor for the TM I-1 Waste Gas Decay tanks (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel. High alarm on RM-A7 noble gas channel will initiate shutdown of the Waste Gas Decay Tank release in progress. This radiation monitor satisfies requirements for batch gaseous releases to the Station Vent release point.

4.4.5 RM-A9 Reactor Building Purge Exhaust RM-A9 is the particulate, radioiodine and gaseous radiation monitor for the TMI-1 Reactor Building Purge system (see Figures 4.1 and 4.3). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters. High alarm on RM-A9 noble gas low channel will initiate shutdown of the Reactor Building Purge System. This radiation monitor satisfies requirements for the Reactor Building Purge System release point.

112

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 4.4.6 RM-A14 ESF FHB Ventilation System RM-A14 is the gaseous radiation monitor for the TMI-1 Emergency Safeguards Features (ESF) Fuel Handling Building Exhaust system (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sampler filters. High alarm on RM-A14 noble gas channel will 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 Cleaning Facility (CCF) Ventilation Exhaust ALC-RMI-18 is an Victoreen particulate, radioiodine, and gaseous radiation monitor for the Chemical Cleaning building exhaust. This monitor is located in the Chemical Cleaning building on the ground floor, and has an associated sample panel. Sampling for particulate activity is performed off of the monitor.

4.4.8 WHP-RIT-1 Waste Handling and Packaging Facility (WHPF) Exhaust WHP-RIT-1 is an Eberline AMS-3 particulate radiation monitor for the TMI WHPF. The monitor is located in the Mechanical Equipment Room in the WHPF. Sampling for particulate activity is performed off of the monitor. A high alarm will initiate shutdown of the ventilation air exhaust system.

4.4.9 RLM-RM-1 ResDirator Cleaning and Laundry Maintenance (RLM) Facility RLM-RM-1 is an Eberline AMS-3 particulate radiation monitor for the TMI RLM Facility.

The monitor is located in the Mechanical Equipment Room in the RLM. Sampling for particulate activity is performed off of the monitor.

113

Number TMI - Unit 1 I

Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 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 Ventilation Exhaust HP-R-219 is a Victoreen particulate and gaseous radiation monitorfor the TMI-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the TMI-2 Auxiliary Building 328 foot elevation and has an associated sample panel.

4.5.2 HP-R-219A Station Ventilation Exhaust HP-R-219A is a Victoreen particulate and gaseous radiation monitor for the TMI-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the TMI-2 Auxiliary Building 328 foot elevation.

4.5.3 HP-R-225 Reactor Building Purae Air Exhaust Duct 'A" HP-R-225 is a Victoreen particulate and gaseous radiation monitor for the TMI-2 Reactor Building Purge Air Exhaust System. This in-plant effluent radiation monitor is located in the TMI-2 Auxiliary Building 328' elevation area 114

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 4.6 Control of Gaseous Effluent Releases TMI gaseous effluent combined releases are controlled (per ODCM Part I for TMI-1 and ODCM Part II for TMI-2) by effluent sampling and radiation monitor set points. These measures assure that releases from the various vents do not combine to produce dose rates at the site boundary exceeding the most restrictive of 500 mrem per year to the total body or 3000 mrem per year to the skin, and 1500 mrem per year to the thyroid. This is done by restricting simultaneous releases and by limiting the dose rates that may be contributed by the various vents at any time. The various vent radiation monitor set points are each based on fractions of the above limits and do not exceed the above limits when summed together. These effluent radiation monitor set points are calculated using the methodology described in equations 4.1.1, or 4.1.2 and 4.2. The actual set points are then listed in TMI-1 Operations Procedure 1101-2.1.

The radioactive content of each batch of gaseous waste is determined prior to release by sampling and analyses in accordance with ODCM Part I for TMI-1 and ODCM Part II for TMI-2. The results of pre-release analyses are used with the calculational methods in Sections 4.1 and 4.2 to assure that the dose rates at the site boundary are maintained below the limits in ODCM Part I for TMI-1 and ODCM Part II 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 II 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 II for TMI-2.

115

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 4.1 TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data GASEOUS RELEASE RADIATION GASEOUS (F)

TERMI NATI ONl MONITOR RELEASE FLOW INTERLOCK (DETECTOR)

LOCATION POINT RECORDER (YES/NO) VALVES YES MA4 306' Elevation Fuell-Hand.AHE1 Auxiliary Bldg.

Bullding FR-149 AH-D-120 l_

_AH-D-122 M-6 306' Elevation AuxilirYE RM-A6 Auxilaryo Bldg.Building FR-50 AH-E-11 S

Auxliay Bdg.Exhaust A--

YES WDG-V47 RMA-8/9 Bldg. Station FR 149 AH-E-11 0 RM-A8 Near BWST Vent FR-150 AH-E-1 1 Exhaust Vet&F-0 Starts MAP-5 Radioiodine l_

Sampler 322' Elevation Condenser YES RM-A5 Second Floor Off Gas FR-1113 Radioiodine Turbine Bldg.

Exhaust Sampler 322' Elevation Condenser YES RM-A15 Second Floor Off Gas FR-1113 Radiriodi ne Turbine Bldg Exhaust Sampler Waste Gas RM-A7 306' Elevation Decay FR-123 YES Auxiliary Bldg.

Tanks WDG-V47 YES Reactor AH-V-I AIB/C/D RM-A9 RMA-8/9 Bldg. Building FR-909/

WDG-534/535 Near BWST Purge FR-148 Starts MAP-5 Exhaust Radioiodine I_

Sampler 331' Elevation ESF Fuel NO RM-A14 ESF FHB Handling FR-II04A/B Manual Outside Chem. Building Actions l____

Addition Bldg.

Exhaust Actions 116

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Tite Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 4.1 TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data GASEOUSRELEASE GAS EOUS TERMINATION RADIATION INTERLOCK MONITOR GASEOUS (YES/NO) l (DETECTOR)

LOCATION RELEASE POINT VALVES Chemical CCB Exhaust ALC-RMI-18 Cleaning Bldg.

sytmN E

304' Elevation (Typical flow rate is 10,000 Cfm )

WHPF WHPF Exhaust YES WHP-RIT-1 Mechanical System WP etlto Equipment Room Typical flow rate trips is 7,500 dfm )Tr p

RLM Exhaust RLM-RM-1 RLM-Mechanical System NONE Equipment Room (Typical flow rate l_

is 900 cfm)

TABLE 4.2 TMI-2 Gaseous Release Point and Gaseous Radiation Monitor Data RELEASE GASEOUS TERMINATION RADIATION GASEOUS INTERLOCK MONITOR RELEASE (YES/NO)

(DETECTOR)

LOCATION POINT VALVES 328' Elevation Station HP-R-219 Auxiliary Vent NONE Building Exhaust 328' Elevation Station Vent HP-R-219A Auxiliary Exhaust NONE y

Building

____a_

328' Elevation Reactor Bldg HP-R-225 Auxiliary Building Purge Exhaust NONE D uct 'A 117

Number 6610-PLN-4200.01 TMI - Unit 1 Radioloaical Controls Procedure Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 4.3 Dose Factors for Noble Gases and Daughters*

Gamma Beta Total Body Skin Dose Gamma Air Dose Factor(a)

Factor(b)

Dose Factor Beta Air K,

LI M,

Dose Factor (mrem/yr per (mrem/yr per (mrad/yr per N.

Radionuclide iCVUM 3) pAUr 3) iCVm3)

(mrad/yr per piCi/m3)

Kr-83m 7.56E-02**

1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131 m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-1 33m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02 Xe-135 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51 E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 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 penetration depth of 5 cm into the body.

2 (b)

Skin dose factor at a tissue depth or tissue density thickness of 7 mg/cm 118

Number 661 0-PLN-4200.01 TMI - Unit 1 Radioloaical Controls Procedure Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 4.4 Atmospheric Dispersion Factors for Three Mile Island

STATION VENT DISTANCE

SECTOR AVERAGE XIQ (IN SEC/M3)

IN METERS)

SEASON - ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N

1.18E-07 5.32E-07 2.95E-07 1.93E-07 1.39E-07 5.52E-08 1.91E-08 5.02E-09 1.88E-09 1.09E-09 NNE 1.70E-07 7.17E-07 3.45E-07 2.OOE-07 1.39E-07 5.58E-08 1.70E-08 4.77E-09 1.98E-09 9.69E-10 NE 1.12E-07 1.75E-07 3.26E-07 1.86E-07 1.21 E-07 5.OOE-08 1.67E-08 4.67E-09 1.85E-09 9.93E-10 ENE 1.09E-07 2.13E-07 2.67E-07 1.53E-07 1.05E-07 4.31 E-08 1.42E-08 4.42E-09 1.59E-09 8.64E-10 E

2.31 E-07 1.71 E-07 1.52E-07 1.49E-07 1.06E-07 4.63E-08 1.52E-08 5.19E-09 2.48E-09 1.50E-09 ESE 3.50E-07 2.12E-07 2.50E-07 1.48E-07 9.48E-08 3.98E-08 1.50E-08 5.92E-09 2.92E-09 1.93E-09 SE 4.19E-07 3.79E-07 2.53E-07 1.55E-07 1.11 E-07 4.82E-08 1.81 E-08 6.84E-09 3.30E-09 2.22E-09.

SSE 2.90E-07 3.62E-07 2.55E-07 1.49E-07 1.11 E-07 5.02E-08 1.98E-08 6.97E-09 2.94E-09 1.70E-09 S

1.87E-07 6.47E-08 2.16E-07 1.30E-07 8.65E-08 4.09E-08 1.40E-08 4.96E-09 1.99E-09 1.04E-09 SSW 6.13E-08 4.16E-08 1.56E-07 1.03E-07 6.81 E-08 2.72E-08 9.74E-09 3.01 E-09 1.50E-09 8.23E-10 SW 5.76E-08 1.14E-07 1.70E-07 1.05E-07 6.93E-08 2.51 E-08 9.34E-09 2.72E-09 1.33E-09 8.33 E-10 WSW 8.52E-08 3.75E-07 2.14E-07 1.26E-07 7.74E-08 3.08E-08 1.02E-08 3.28E-09 1.39E-09 9.69E-10 W

1.15E-07 5.80E-07 2.88E-07 1.63E-07 1.18E-07 5.23E-08 1.72E-08 5.06E-09 1.98E-09 1.25E-09 WNW 1.41 E-07 6.28E-07 3.30E-07 2.19E-07 1.A8E-07 5.68E-08 1.95E-08 6.32E-09 2.16E-09 1.34E-09 NW 1 A2E-07 5.67E-07 3.17E-07 1.93E-07 1.30E-07 5.67E-08 2.06E-08 5.90E-09 2.70E-09 1.45E-09 NNW 1.OOE-07 5.77E-07 3.18E-07 1.80E-07 1.27E-07 5.20E-08 1.77E-08 4.82E-09 2.01E-09 1.22E-09

STATION VENT DISTANCE

SECTOR AVERAGE D/Q (IN M2)

(IN METERS)

SEASON - ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N

2.51 E-09 8.72E-10 4.84E-10 2.98E-10 2.50E-10 8.57E-11 2.51 E-11 4.98E-12 1.57E-12 7.84E-13 NNE 3.89E-09 1.98E-09 9.54E-10 4.99E-10 3.38E-10 1.1OE-10 2.89E-11 6.06E-12 2.1OE-12 8.89E-13 NE 2.58E-09 6.70E-10 9.13E-10 4.91E-10 2.97E-10 1.04E-10 2.87E-11 6.01E-12 1.99E-12 9.23E-13 ENE 2.15E-09 5.85E-10 5.54E-10 3.06E-10 2.08E-10 8.30E-11 2.32E-11 5.41 E-12 1.63E-12 7.64E-13 E

5.54E-09 1.23E-09 6.17E-10 4.59E-10 3.63E-10 1.34E-10 3.66E-11 9.44E-12 3.77E-12 1.97E-12 ESE 9.17E-09 2.05E-09 1.51 E-09 8.66E-10 5.11 E-10 1.82E-10 5.77E-11 1.72E-11 7.07E-12 4.07E-12 SE 1.22E-08 2.88E-09 1.84E-09 1.02E-09 6.85E-10 2.60E-10 8.30E-11 2.34E-11 9.42E-12 5.51E-12 SSE 7.50E-09 1.62E-09 1.08E-09 5.89E-10 4.49E-10 1.87E-10 6.16E-11 1.61E-11 5.67E-12 2.83E-12 S

3.86E-09 6.53E-10 6.27E-10 3.59E-10 2.32E-10 1.06E-10 3.05E-11 8.10E-12 2.73E-12 1.23E-12 SSW 1.13E-09 2.94E-10 4.19E-10 2.53E-10 1.56E-10 5.38E-11 1.68E-11 3.91E-12 1.64E-12 7.84E-13 SW 1.19E-09 3.84E-10 4.96E-10 2.80E-10 1.70E-10 5.24E-11 1.65E-11 3.62E-12 1.49E-12 8.12E-13 WSW 1.77E-09 8.31E-10 6.49E-10 3.50E-10 1.99E-10 6.73E-11 1.89E-11 4.58E-12 1.63E-12 9.90E-13 W

2.41E-09 1.29E-09 6.81E-10 3.65E-10 2.96E-10 1.12E-10 3.11E-11 6.90E-12 2.26E-12 1.25E-12 WNW 3.20E-09 1.39E-09 7.73E-10 5.91E-10 3.66E-10 1.19E-10 3.43E-11 8.36E-12 2.39E-12 1.29E-12 NW 3.25E-09 1.23E-09 7.39E-10 4.22E-10 2.77E-10 1.14E-10 7.28E-11 7.61 E-12 2.92E-12 1.36E-12 NNW 1.98E-09 9.88E-10 5.71E-10 3.05E-10 2.23E-10 8.21E-11 2.41E-11 4.93E-12 1.72E-12 9.03E-13 DATA FROM 1/1/78 THROUGH 12131/86 USED IN CALCULATIONS 119

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 4.5 Atmospheric Dispersion Factors for Three Mile Island

GROUND RELEASE DISTANCE

SECTOR AVERAGE X/Q (IN SECo M

(IN METERS SEASON - ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N

1.16E-05 1.13E-06 5.94E-07 3.80E-07 2.38E-07 9.74E-08 3.45E-08 9.28E-09 3.52E-09 2.05E-09 NNE 1.08E-05 1.1OE-06 5.66E-07 3.41 E-07 2.38E-07 9.55E-08 3.11 E-08 8.94E-09 3.74E-09 1.84E-09 NE 7.02E-06 9.81 E-07 5.42E-07 3.17E-07 2.10E-07 9.01 E-08 3.1OE-08 8.87E-09 3.54E-09 1.91 E-09 ENE 7.14E-06 9.64E-07 4.92E-07 2.85E-07 1.97E-07 7.82E-08 2.64E-08 8.38E-09 3.04E-09 1.66E-09 E

8.49E-06 1.09E-06 5.48E-07 2.91 E-07 1.87E-07 8.40E-08 2.82E-08 9.85E-09 4.75E-09 2.87E-09 ESE 6.91E-06 9.02E-07 4.49E-07 2.57E-07 1.67E-07 7.20E-08 2.77E-08 1.12E-08 5.54E-09 3.68E-09 SE 6.70E-06 9.06E-07 4.53E-07 2.81 E-07 2.03E-07 8.94E-08 3.33E-08 1.28E-08 6.19E-09 4.18E-09 SSE 7.26E-06 9.25E-07 4.91 E-07 2.87E-07 2.08E-07 9.18E-08 3.72E-08 1.32E-08 5.62E-09 3.26E-09 S

8.70E-06 9.08E-07 3.99E-07 2.41 E-07 1.61 E-07 7.31 E-08 2.57E-08 9.23E-09 3.74E-09 1.95E-09 SSW 6.05E-06 7.01 E-07 2.75E-07 1.86E-07 1.24E-07 5.06E-08 1.82E-08 5.71 E-09 2.87E-09 1.58E-09 SW 5.94E-06 5.71 E-07 2.86E-07 1.81 E-07 1.22E-07 4.50E-08 1.72E-08 5.12E-09 2.53E-09 1.59E-09 WSW 8.OOE-06 7.02E-07 3.60E-07 2.15E-07 1.34E-07 5.50E-08 1.87E-08 6.12E-09 2.62E-09 1.83E-09 W

1.02E-05 1.07E-06 5.30E-07 3.02E-07 2.05E-07 9.31 E-08 3.15E-08 9.48E-09 3.74E-09 2.38E-09 WNW 1.16E-05 1.13E-06 5.98E-07 3.67E-07 2.53E-07 1.00E-07 3.56E-08 1.18E-08 4.07E-09 2.54E-09 NW 1.13E-05 1.06E-06 5.70E-07 3.53E-07 2.40E-07 1.02E-07 3.82E-08 1.11 E-08 5.14E-09 2.78E-09 NNW 1.08E-05 1.04E-06 5.72E-07 3.27E-07 2.22E-07 9.06E-08 3.20E-08 8.89E-09 3.75E-09 2.29E-09

GROUND RELEASE DISTANCE

SECTOR AVERAGE D/Q (IN M2 (IN METERS)

SEASON - ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N

2.30E-08 1.88E-09 8.93E-10 4.82E-10 2.70E-10 8.96E-11 2.53E-11 4.98E-12 1.57E-12 7.84E-13 NNE 2.66E-08 2.25E-09 1.06E-09 5.42E-10 3.38E-10 1.10E-10 2.89E-11 6.06E-12 2.10E-12 8.89E-13 NE 1.75E-08 2.OOE-09 1.01 E-09 5 04E-10 2.98E-10 1.04E-10 2.88E-11 6.01E-12 1.99E-12 9.23E-13 ENE 1.68E-08 1.85E-09 8.65E-10 4.28E-10 2.65E-10 8.57E-11 2.33E-11 5.41E-12 1.63E-12 7.64E-13 E

2.88E-08 2.99E-09 1.39E-09 6.34E-10 3.67E-10 1.35E-10 3.68E-11 9A2E-12 3.77E-12 1.97E-12 ESE 3.59E-08 3.80E-09 1.77E-09 8.79E-10 5.15E-10 1.83E-10 5.78E-1 1 1.71 E-11 7.06E-12 4.06E-12 SE 4.12E-08 4.55E-09 2.13E-09 1.15E-09 7.50E-10 2.72E-10 8.31E-11 2.34E-11 9.42E-12 5.50E-12 SSE 3.12E-08 3.23E-09 1.59E-09 8.OOE-10 5.20E-10 1.88E-10 6.18E-11 1.61E-11 5.66E-12 2.83E-12 S

2.65E-08 2.21 E-09 9.07E-10 4.75 E-10 2.86E-10 1.07E-10 3.06E-11 8.10E-12 2.73E-12 1.23E-12 SSW 1.45E-08 1.30E-09 4.80E-10 2.82E-10 1.70E-10 5.71 E-11 1.69E-11 3.91 E-12 1.64E-12 7.84E-13 SW 1.42E-08 1.10E-09 5.15E-10 2.82E-10 1.71 E-10 5.24E-11 1.65E-11 3.62E-12 1.49E-12 8.12E-13 WSW 2.01 E-08 1.41 E-09 6.82E-10 3.54E-10 2.00E-10 6.76E-11 1.89E-11 4.58E-12 1.63E-12 9.90E-13 W

2.55E-08 2.16E-09 1.00E-09 4.91 E-10 3.01 E-10 1.12E-10 3.11 E-11 6.90E-12 2.27E-12 1.25E-12 WNW 2.88E-08 2.30E-09 1.13E-09 5.93E-10 3.67E-10 1.19E-10 3 43E-11 8.36E-12 2.39E-12 1.29E-12 NW 2.78E-08 2.15E-09 1.06E-09 5.58E-10 3.41E-10 1.19E-10 3.57E-11 7.61E-12 2.92E-12 1.36E-12 NNW 2.17E-08 1.75E-09 8.75E-10 4.24E-10 2.57E-10 8.55E-11 2.42E-11 4.93E-12 1.72E-12 9.03E-13 DATA FROM 1/1178 THROUGH 12/31/86 USED IN CALCULATIONS 120

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 4.6 Dose Parameters for Radiolodines and Radioactive Particulate in Gaseous Effluents*

l CRITICAL l

ORGAN l

1 1 CRITICAL l

ORGAN NUCLIDE ORGAN FACTOR pj***

NUCLIDE l ORGAN l

FACTOR l

Pi**

H-3**

TOTAL BODY 3.04E-07 1.12E+03 RU-1 03 LUNG 1.79E-04 6.62E+05 C-14 BONE 9.70E-06 3.59E+04 RU-1 05 GI-LLI 2.69E-05 9.95E+04 NA-24 TOTAL BODY 4.35E-06 1.61 E+04 RU-1 06 LUNG 3.87E-03 1.43E+07 P-32 BONE 7.04E-04 2.60E+06 AG-11OM LUNG 1.48E-03 5 48E+06 CR-51 LUNG 4.59E-06 1.70E+04 TE-125M LUNG 1.29E-04 4.77E+05 MN-54 LUNG 4.26E-04 1.58E+06 SB-125 LUNG 6.27E-04 2.32E+06 MN-56 GI-LLI 3.33E-05 1.23E+05 TE-127M LUNG 4.OOE-04 1.48E+06 FE-55 LUNG 3.OOE-05 1.11E+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 GI-LLI 6.89E-06 2.55E+04 CO-60 LUNG 1.91 E-03 7.07E+06 TE-131M GI-LLI 8.32E-05 3.08E+05 NI-63 BONE 2.22E-04 8.21 E+05 TE-131 LUNG 5.55E-07 2.05E+03 NI-65 GI-LLI 2.27E-05 8.40E+04 TE-132 LUNG 1.02E-04 3.77E+05 CU-64 GI-LLI 9.92E-06 3.67E+04 1-130 TYHROID 4.99E-04 1.85E+06 ZN-65 LUNG 2.69E-04 9.95E+05 1-131 THYROID 4.39E-03 1.62E+07 ZN-69 GI-LLI 2.75E-06 1.02E+04 1-132 THYROID 5.23E-05 1.94E+05 BR-83 TOTAL BODY 1.28E-07 4.74E+02 1-133 THYROID 1.04E-03 3.85E+06 BR-84 TOTAL BODY 1.48E-07 5.48E+02 1-134 THYROID 1.37E-05 5.07E+04 BR-85 TOTAL BODY 6.84E-09 2.53E+01 1-135 THYROID 2.14E-04 7.92E+05 RB-86 LIVER 5.36E-05 1.98E+05 CS-134 LIVER 2.74E-04 1.01E+06 RB-88 LIVER 1.52E-07 5.62E+02 CS-136 LIVER 4.62E-05 1.71 E+05 RB-89 LIVER 9.33E-08 3.45E+02 CS-137 BONE 2.45E-04 9.07E+05 SR-89 LUNG 5.89E-04 2.16E+06 CS-138 LIVER 2.27E-07 8.40E+02 SR-90 BONE 2.73E-02 1.01 E+08 BA-139 GI-LLI 1.56E-05 5.77E+04 SR-91 GI-LLI 4.70E-05 1.74E+05 BA-140 LUNG 4.71 E-04 1.74E+06 SR-92 GIl-LLI 6.55E-05 2.42E+05 BA-141 LUNG 7.89E-07 2.92E+03 Y-90 GI-LLI 7.24E-05 2.68E+05 BA-142 LUNG 4.44E-07 I 64E+03 Y-91 M LUNG 7.60E-07 2.81 E+03 LA-140 GI-LLI 6.1 OE-05 2.26E+05 Y-91 LUNG 7.1OE-04 2.63E+06 LA-142 GI-LLI 2.05E-05 7.59E+04 Y-92 GI-LLI 6.46E-05 2.39E+05 CE-141 LUNG 1.47E-04 5.44E+05 Y-93 GI-LLI 1.05E-04 3.89E+05 CE-143 GI-LLI 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-LLI 9.49E-05 3.51 E+05 PR-143 LUNG 1.17E-04 4.33E+05 NB-95 LUNG 1.66E-04 6.14E+05 PR-144 LUNG 4.23E-07 1.57E+03 MO-99 LUNG 3.66E-05 1.35E+05 ND-147 LUNG 8.87E-05 3.28E+05 TC-99M GI-LLI 1.30E-06 4.81E+03 W-187 GI-LLI 2.46E-05 9.1OE+04 TC-101 LUNG 1.58E-07 5 85E+02 NP-239 GI-LLI 1.73E-05 6.40E+04 The listed dose parameters are for radionuclides, other than noble gases that may be detected in gaseous effluents. Pi factors include all nonatmospheric pathway transport parameters, the receptors usage of pathway media, and are based on the most restrictive age group (child) critical organ. Additional dose parameters for nuclides not included in this Table may be calculated using the methodology described in NUREG-01 33.

Tritium dose factors include an increase of 50% to account for the additional amount of this nuclide absorbed through the skin.

mrem/year per jIC/m 3.

121

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 FIGURE 4.1 TMI-1 Gaseous Effluent Pathways I FIGURE 4.1 lTAlrO N

OCSfl FLW Ou~

PLOW CONDUNaSR OFF OAS STACK 0430 CFM 140,000 CFM P-PRE FILTER A-ABSOLUTE HEPA C-CHARCOAL FILTER VACUUM PUMPS 122

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 FIGURE 4.2 TMI-1 Auxiliary and Fuel Handling Buildings Effluent Pathways I

123

Number TMI - Unit I I

Radiological Controls Procedure 661Ro-PLN-4200.N Title Revision No Offsite Dose Calculation Manual (ODCM) 23 FIGURE 4.3 TMI-1 Reactor Building Effluent Pathway 170 FEET REACTOR BUILDING PURGE EXHAUST RADIATION MONITORS AND SAMPLING STATIONS REACTO BUILDING SC-1

&Go-0 2"12 11J 54 FILTERS CFN KrM ruO SAMIN SYST1DS PARTKUTUATRIftRi HODNEMIJE GAS IA: ABSOIEI c :[

124

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Tile Revision No.

Offsite Dose Calculation Manual (ODCM) 23 FIGURE 4.4 TMI-1 Condenser Offgas Effluent Pathway CONDENSER OFF GAS STACK CONDENSER OFF GAS EXHAUST RADIATION MONITORS AND SAMPLING STATIONS 125

661 OPLN-4200.01 Revision 23 FIGURE 4.5 TMI-2 Gaseous Effluent Filtration System/Pathways STATION VENT a.- 141,oB cPU RB BREATHER I

UNIT 2 EXHAUST AIR FLOW AND RMS SCHEMATIC 126

Number TMI - Unit I I

Radiological Controls Procedure l 6610-PLN4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 5 0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents - Instantaneous Release Limits 5.1.1 Noble Gases For noble gases, the following equations apply for total body and skin dose rate at the unrestricted area boundary:

5.1.1.1 Total Body Dose Rate,

=

(Ki) x (Dv) x (Q.)

(eq 5.1.1.1) where:

Dose Ratet b instantaneous total body dose rate limit, at the site boundary, in mrem/yr.

total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem/yr per [tCi/M3 from Table 4.3.

Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/iM3, from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases) Maximum values presently in use are 7.17E-7 sec/M3 at sector NNE for station vent, and 1.16E-5 sec/m 3 for all other releases, at sectors N and WNW.

Q0 = Release rate of radionuclide, i, in ItCi/sec as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, in gCicc, times the release pathway flow rate, in cc/second 127

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 rT-e Revision No.

Offite Dose Calculation Manual (ODCM) 23 5.1.1.2 Skin Dose RateSk = z (Li + 1.1 M,) X (Dv) X (Q.)

where:

(eq 5.1.1.2)

Dose RateSk = instantaneous mremlyear skin dose rate limit, at the site boundary, in mremlyr.

L, = skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem/yr per jCiUm3 from Table 4.3.

M, = air dose factor due to gamma emissions for each identified noble gas radionuclide, in mradlyr per,ICi/m3 from Table 4.3.

1.1 = mrem skin dose per mrad air dose. Converts air dose to skin dose.

Q. = release rate of radionuclide, i, in ItCi/sec, as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, in ACi/cc, times the release pathway flow rate, in cc/second.

Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3, from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values presently in use are 7.17E-7 sec/iM3 at sector NNE for station vent, and 1.16E-5 sec/iM3 for all other releases, at sectors N and WNW.

128

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 5.1.2 Iodine-131. Iodine-133. Tritium and Radionuclides in Particulate Form. with Half-Lives Greater than 8 Days For 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, the following equation applies:

Dose Ratelp =

(Pi) (Dv) (Qi)

(eq 5.1.2) where:

Dose Ratelp = mrem/year organ dose rate.

Pi = dose parameter for 1-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, for the inhalation pathway, in mrem/yr per tIC/m 3, from Table 4.6. The dose factors are based on the cntical individual organ and most restrictive age group (child).

Dv highest sector annual average gaseous dispersion factor (X/Q or D/Q) at or beyond the unrestricted area boundary, in sec/iM3, from Table 4.4 for the station vent releases and Table 4.5 for all other releases. X/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 7.1 7E-7 sec/iM3 for station vent, at sector NNE, and 1.1 6E-5 sec/M 3 for all other releases, at sectors N and WNW.

Q= release rate of each radionuclide, i, in liCi/sec. Calculated using the concentration of each radionuclide, i, in jtCi/cc, times the release pathway flow rate, in cc/second.

129

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 5.2 Gaseous Effluents - 10 CFR 50 Appendix i 5 2.1 Noble Gases The air dose in an unrestricted area due to noble gases released in gaseous effluents from the site is determined using the following expressions:

Dose r = (3.17E-8) x (MI) x (Dv) x (Qi)

(eq 5.2.1) and Dose P = (3.17E-8) x f (N.) x (Dv) x (Qi)

(eq 5.2.2) where:

Dose r = mrad gamma air dose due to gamma emissions from noble gas radionuclides.

Dose p mrad beta air dose due to beta emissions from noble gas radionuclides.

M, = air dose factor due to gamma emissions for each identified noble gas radionuclide, in mradlyr per plCi/M 3, from Table 4.3.

N, = air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per p1Ci/M 3, from Table 4.3.

Dv = highest sector annual average gaseous dispersion factor, X/Q, at or beyond the unrestricted area boundary, in seclm3. Values may be read or interpolated from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. Maximum values of X/Q presently used are 7.17E-7 sec/iM3 for station vent at sector NNE, and 1.16E-5 sec/iM3 for all other releases at sectors N or WNW.

Q. = release of noble gas radionuclide, i, in pCi, over the specified time period, (pCi/second

seconds).

3.17E-8 = inverse of the number of seconds in a year.

NOTE If the methodology in this section is used in determining dose to an individual, rather than air dose due to noble gases, substitute Ki, from Table 4 3, for Mi, and (Li + 1.1 Mi) for Ni 130

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN-4200.01 litle Revision No Offsite Dose Calculation Manual (ODCM) 23 5.2.2 Iodine-131. Iodine-133. Tritium and Radionuclides in Particulate Form. with Half-Lives Greater than 8 Days The dose to an individual from 1-131,1-133, Tritium and Radionuclides in Particulate Form with half-lives greater than 8 days in gaseous effluents released from the site to an unrestricted area is determined by solving the following expression:

Dose, = Z (3.17E.8) x Z (RI) (Dv) (Q,)

(eq 5.2.2) where:

Dose, = dose to all real pathways, p, to organ, o, of an individual in age group, a, from 1-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, in mrem, during any desired time period.

Since there is i condenser off-all pathways, e when performii off-gas air ejec for condenser i R. = the dose factor for each identified radionuclide, i, pathway, p, age group, a, and organ, o, in mrem/yr per gCi/m 3 for the inhalation pathway and m2 mrem/yr per tiCVsec for other pathways, from Tables 5.2 to 5.7.

NOTE minimal or no elemental iodine released from the gas air ejector (see NUREG-0017) all Iodine R. values for xcept the inhalation pathway, are considered to be zero ng dose calculations for releases from the condenser tor. Only calculate the dose due to the inhalation pathway off-gas air eiector iodines.

NOTE 3, dose factor is mrem/year per iiCi/m3 for all pathways.

Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in seclm3, for the inhalation pathway, and D/Q, in M2, for other pathways. Table 4.4 is used to derive the values for station vent releases and Table 4.5 is used to derive the values for all other releases. The values used to calculate site boundary and critical receptor doses are as follows:

Tritium, H-Station Vent Releases - Boundary Inhalation X/Q 7.17 E-7 Meat D/Q 1.22 E-8 Cow/Milk/Infant D/Q 1.22 E-8 Station Vent Releases - Critical Receptor Inhalation X/Q 7.2 E-7 Meat D/Q 4.6 E-9 Cow/Milk/infant D/Q 3 1 E-9 Ground DIQ Vegetation DlQ Ground DJQ Vegetation D/Q 1.22 E-8 1.22 E-8 7.8 E-9 8.9 E-9 131

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 Ground or Other Rleases - Boundary Inhalation X/Q 1.16 E-5 Meat DIQ 4.12 E-8 Ground DIQ 4.12 E-8 Cow/Milk/lnfant D/Q 4.12 E-8 Vegetation DIQ 4.12 E-8 Ground or Other Rleases - Critical Receptor Inhalation X/Q 1.2 E-5 Meat DIQ 9.2 E-9 Ground DIQ 3.0 E-8 Cow/Milk/lnfant D/Q 6.3 E-9 Vegetation D/Q 2.6 E-8 Dv(H-3) = In the case of H-3 only the X/Q's above are used for all pathways.

Q, = release of 1-131, 1-133, Tritium and Radionuclides, i, in Particulate Form with half-lives greater than 8 days, in pCi, cumulative over the specified time period (gCisecond

seconds).

3.17E-8 = inverse of the number of seconds in a year.

132

Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 5.3 Gaseous Radioactive System Dose Calculations Once per Month ODCM Part I Control 2.2.2.4 and TMI-2 PDMS Tech Spec Section 6.7.4.a 6 requires that appropriate subsystem of the Gaseous Radwaste Treatment System shall be used to reduce the radioactive materials in gaseous waste prior to their discharge. When the monthly projected doses due to the gaseous effluent releases from the site would exceed:

0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ.

The following calculational method is provided for performing this dose projection.

At least once per month the gamma air dose, beta air dose and the maximum organ dose for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual release during the period for which the projection is made. If these projected doses exceed any of the values listed above, appropriate portions of the TMI-1 Gaseous Waste Treatment System, as defined in Section 6.0, or appropriate portions of the TMI-2 Gaseous Effluent Filtration System as shown on Figure 4.5, shall be used to reduce radioactivity levels prior to release At the discretion of Radiological Engineering, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the current quarter-to-date is not believed to be representative of the dose per day projected for the next month.

133

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01.

Title Revision No Offsite Dose Calculation Manual (ODCM) 23 5 4 Alternative Dose Calculational Methodologies for Gaseous Effluents 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 parametervalues from Regulatory Guide 1.109 (Rev. 1)and/oractual site specific data can be used where applicable.

The onsite, on-line computerized system for tracking gaseous effluent dose uses annual average gaseous dispersion factors. As an alternative dose calculational methodology. TMI calculates doses using an advanced class WA" dispersion model called SEEDS (simplified environmental effluent dosimetry system).

This model incorporates the guidelines and methodology set forth in USNRC Regulatory Guide 1.109, and uses actual hourly meteorological information matched to the time of releases to more accurately assess the dispersion of effluents in the atmosphere. Combining this assessment of dispersion with TMI effluent data for each unit, postulated maximum hypothetical doses to the public are calculated.

134

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Tige Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.2.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: INHALATION D

ORGAN DOSE FACTORS; mrem/year per IICi/m3 NUCLIDE BONE LV T--OD-THYROID KIDNEY LUNG

.BONE LIVER T.BODY THYROID KIDNEY LUNG Gl-LLI H-3 C-14 CR-51 MN-54 FE-55 FE-59 0.OOE+00 6 47E+02 2.65E+04 5.31 E+03 0.OOE+00 0.00E+00 0.OOE+00 2.53E+04 1.97E+04 1.17E+04 1.36E+04 2.35E+04 6.47E+02 5.31 E+03 8 95E+01 4.98E+03 3.33E+03 9.48E+03 6A7E+02 5.31 E+03 5.75E+01 0.OOE+00 0.OOE+00 0.OOE+00 6.47E+02 5.31 E+03 1.32E+01 4.98E+03 0.OOE+00 0.OOE+00 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-1 34 CS-136 CS-137 BA-140 CE-141 CE-144 0.OOE+00 0.00E+00 3.39E+05 1.93E+04 0,OOE+00 3.98E+05 4.09E+07 5.88E+05 1.15E+05 1.57E+04 2.02E+03 8.68E+04 9.98E+03 4.76E+03 1.67E+04 1A41E+04 3.79E+04 I1.32E+04 3.96E+05 4.83E+04 5A49E+05 5.60E+04 2.77E+04 3.1 9E+06 1.22E+03 8 02E+03 2.04E+04 6.26E+04 1.90E+05 O.OOE+00 0.OOE+00 2.79E+04 6.43E+03 0.OOE+00 0.OOE+00 7.22E+03 1.99E+03 6.90E+03 1.82E+03 1.18E+04 1.16E+04 3.11E+04 8.82E+04 1.14E+04 2.59E+06 1.57E+04 2.03E+04 3.78E+03 6.79E+02 1.09E+04 5.OOE+03 6.58E+02 2.07E+03 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0 OOE+00 I1.62E+03 4.87E+03 0.00E+00 0.OOE+00 0.OOE+00 3.25E+04 0.OOE+00 0.OOE+00 0.O O E + 0- 0 0.OOE+00 3.1I1E+04 4.72E+03 4.24E+03 I1.07E+05 1.09E+04 0.00E+00 3.75E+04 6.47E+02 6A7E+02 5.31E+03 5.31E+03 1.28E+04 3.57E+02 1.OOE+06 7.06E+03 8.69E+04 1.09E+03 1.02E+06 2.48E+04 7.77E+05 1.11E+04 4.51E+06 3.19E+04 2.09E+05 2A2E+03 6.47E+05 5.14E+04 0.OOE+00 3.04E+03 2.03E+06 6.40E+04 1.12E+07 1.31E+05 2.45E+06 7.03E+04 1.75E+06 2.17E+04 4.79E+05 1.27E+04 5.52E+05 1.61E+04 1.16E+07 1.64E+05 3 67E+06 3.30E+04 4.47E+05 1.29E+04 1.31E+06 2.73E+04 1.68E+06 6.90E+04 0.OOE+00 1.06E+03 0.00E+00 2.16E+03 7.97E+04 1.33E+03 1.18E+04 1.43E+03 7.13E+04 1.33E+03 1.60E+06 3 84E+04 5.17E+05 2.16E+04 9.84E+06 1.48E+05 6.09E+03 4A4E+04 1.92E+04 7.03E+05 1.35E+05 6.12E+05 5.60E+01 1.67E+04 1.21 E+06 2.23E+03 1.96E+04 5.60E+03 7A5E+04 5.29E+04 4.55E+04 5.47E+03 1.48E+07 3.56E+06 0.OOE+00 0.OOE+00 0.OOE+00 3.18E+04 5.18E+04 2.24E+04 1.90E+05 5.64E+04 1.72E+05 E 0

_0_

_0 E+_

2.90E+03 0.OOE+00 1.99E+03 0.OOE+00 1.76E+05 0.00E+00 1.34E+01 5.25E+03 5.38E+05 PR-143 1.40E+04 5.24E+03 ND-147 7.94E+03 8.13E+03 6.99E+02 0.00E+00 1.97E+03 5.OOE+02 0.OOE+00 3.15E+03 4.33E+05 3.72E+04 3.22E+05 3.12E+04 135

Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.2.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: INHALATION ORGAN DOSE FACTORS; mrem/year per jiCi/m3 NUCLIDE J

BONE LIVER T.BODY H-3 0.OOE+00 1.12E+03 C-14 3 59E+04 6 73E+03 CR-51 0.OOE+00 0.OOE+00 MN-54 0.OOE+00 4.29E+04 FE-55 4.74E+04 2.52E+04 FE-59 2.07E+04 3.34E+04 CO-58 0.OOE+00 1.77E+03 CO-60 0.OOE+00 1.31E+04 NI-63 8.21 E+05 4.63E+04 ZN-65 4.26E+04 1.13E+05 RB-86 0.OOE+00 1.98E+05 SR-89 5.99E+05 0.OOE+00 SR-90 1.01E+08 0.OOE+00 Y-91 9.14E+05 0 OOE+00 ZR-95 1.90E+05 4.18E+04 NB-95 2.35E+04 9.18E+03 RU-1 03 2.79E+03 0 OOE+00 RU-106 1.36E+05 O.OOE+00 AG-110M 1.69E+04 1.14E+04 TE-125M 6.73E+03 2.33E+03 TE-127M 2.49E+04 8.55E+03 TE-129M 1.92E+04 6.85E+03 1-131 4.81 E+04 4.81 E+04 1-133 1.66E+04 2.03E+04 1.12E+03 6.73E+03 1.54E+02 9.51 E+03 7.77E+03 1.67E+04 3.16E+03 2.26E+04 2.80E+04 7.03E+04 1.14E+05 1.72E+04 6.44E+06 2.44E+04 3.70E+04 6.55E+03 1.07E+03 1.69E+04 9.14E+03 9.14E+02 3.02E+03 3.04E+03 2.73E+04 7.70E+03 THYROID KIDNEY LUNG Gl-LLI 1.12E+03 1.12E+03 1.12E+03 1.12E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 8.55E+01 2.43E+01 1.70E+04 1.08E+03 0.OOE+00 1.OOE+04 1.58E+06 2.29E+04 0.OOE+00 0.00E+00 1.11E+05 2.87E+03 0.OOE+00 0.OOE+00 1.27E+06 7.07E+04 0.OOE+00 0 00E+00 1.11E+06 3.44E+04 0.OOE+00 0.00E+00 7.07E+06 9.62E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 O.OOE+00 7.14E+04 9.95E+05 1.63E+04 O.OOE+00 0.OOE+00 0.00E+00 7.99E+03 O.OOE+00 0.OOE+00 2.16E+06 1.67E+05 0.00E+00 0.00E+00 1.48E+07 3.43E+05 0.OOE+00 O.OOE+00 2.63E+06 1.84E+05 0.OOE+00 5.96E+04 2.23E+06 6.11E+04 0.OOE+00 8.62E+03 6.14E+05 3.70E+04 O.OOE+00 7.03E+03 6.62E+05 4.48E+04 0.OOE+00 1.84E+05 1.43E+07 4.29E+05 0.OOE+00 2.12E+04 5.48E+06 1.00E+05 1.92E+03 O.OOE+00 4.77E+05 3.38E+04 6.07E+03 6.36E+04 1.48E+06 7.14E+04 6.33E+03 5.03E+04 1.76E+06 1.82E+05 1.62E+07 7.88E+04 0.00E+00 2.84E+03 3.85E+06 3.38E+04 0.OOE+00 5.48E+03 0 00E+00 3.30E+05 1.21E+05 3.85E+03 0.OOE+00 9.55E+04 1.45E+04 4.18E+03 0.00E+00 2.82E+05 1.04E+05 3.62E+03 0.OOE+00 2.11E+01 1.74E+06 1.02E+05 0.00E+00 8.55E+03 5.44E+05 5.66E+04 0.00E+00 1.17E+06 1.20E+07 3.89E+05 CS-134 CS-136 CS-1 37 BA-140 CE-141 CE-144 6.51 E+05 6.51 E+04 9.07E+05 7.40E+04 3.92E+04 6.77E+06 1.01E+06 1.71 E+05 8.25E+05 6.48E+01 1.95E+04 2.12E+06 2.25E+05 1.16E+05 1.28E+05 4.33E+03 2.90E+03 3.61 E+05 PR-143 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.OOE+03 4.33E+05 ND-147 1.08E+04 8.73E+03 6.81E+02 0.00E+00 4.81E+03 3.28E+05 9.73E+04 8.21 E+04 136

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN-4200.01I Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.2.3 Pathway Dose Factors, RI AGE GROUP: TEEN PATHWAY: INHALATION ORGAN DOSE FACTORS; mrem/year per PCi/m3 NUCLIDE BN LE TOY TRD KN LUNG

_----L---

BONE LIVER T.BODY THYROID KIDNEY LUNG Gl-LLI H-3 0.00E+00 C-14 2.60E+04 CR-51 0.00E+00 MN-54 0.00E+00 FE-55 3.34E+04 FE-59 1.59E+04 CO-58 O.OOE+00 CO-60 0.00E+00 Nl-63 5.80E+05 ZN-65 3.86E+04 RB-86 0.OOE+00 SR-89 4.34E+05 SR-90 1.08E+08 Y-91 6.61 E+05 ZR-95 1.46E+05 NB-95 1.86E+04 RU-103 2.1OE+03 RU-1 06 9.84E+04 1.27E+03 4.87E+03 0.00E+00 5.11 E+04 2.38E+04 3.70E+04 2.07E+03 1.51 E+04 4.34E+04 1.34E+05 1.90E+05 0.OOE+00 0.OOE+00 0.OOE+00 4.58E+04 1.03E+04 0.00E+00 0.OOE+00 1.27E+03 4.87E+03 1.35E+02 1.27E+03 1.27E+03 4.87E+03 4.87E+03 7.50E+01 3.07E+01 8.40E+03 O.OOE+00 5.54E+03 0.OOE+00 1.43E+04 0.OOE+00 1.27E+04 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0 00E+00 2.78E+03 1.98E+04 1.98E+04 0.OOE+00 0.OOE+00 0.OOE+00 1.27E+03 4.87E+03 2.1 OE+04 1.98E+06 1.24E+05 1.53E+06 1.34E+06 8.72E+06 3.07E+05 1.24E+06 0.OOE+00 2.42E+06 1.65E+07 2.94E+06 2.69E+06 1.27E+03 4.87E+03 3.OOE+03 6.68E+04 6.39E+03 1.78E+05 9.52E+04 2.59E+05 1.42E+04 6.24E+04 8.40E+04 1.25E+04 6.68E+06 1.77E+04 3.15E+04 5.66E+03 8.96E+02 1.24E+04 7.99E+03 6.67E+02 2.18E+03 2.25E+03 2.64E+04 6.22E+03 5.49E+05 1.37E+05 3.11 E+05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 8.64E+04 0.OOE+00 0.OOE+00

E+--

0.OOE+00 6.74E+04 4.66E+04 1.77E+04 3.71 E+05 7.65E+05 4.09E+05 1.49E+05 AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-134 CS-1 36 CS-137 BA-140 CE-141 CE-144 1.38E+04 4.88E+03 1.80E+04 1.39E+04 3.54E+04 1.22E+04 5.02E+05 5.15E+04 6.70E+05 5.47E+04 2.84E+04 4.89E+06 1.31 E+04 2.24E+03 8.16E+03 6.58E+03 4.91 E+04 2.05E+04 1.13E+06 1.94E+05 8.48E+05 6.70E+01 1.90E+04 2.02E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.40E+03 4.38E+03 4.58E+03 I1.46E+07 2.92E+06 0.OOE+00 0.OOE+00 0.OOE+00 1.OOE+04 7.43E+03 1.90E+05 2.50E+04 0.OOE+00 6.54E+04 5.19E+04 8.40E+04 3.59E+04 3.75E+05 1.1OE+05 3 04E+05 2.28E+01 8.88E+03 1.21 E+06 7.51 E+05 9.68E+04 7.83E+05 1.09E+05 1.61E+07 9.60E+05 6.75E+06 2.73E+05 5.36E+05 7.50E+04 1.66E+06 1.59E+05 1.98E+06 4.05E+05 0.00E+00 6.49E+03 0.OOE+00 1.03E+04 1.46E+05 9.76E+03 1.78E+04 1.09E+04 1.21E+05 8A8E+03 2.03E+06 2.29E+05 6.14E+05 1.26E+05 1.34E+07 8.64E+05 3.52E+03 2.17E+03 2.62E+05 0.00E+00 0.OOE+00 0.OOE+00 PR-143 1.34E+04 5.31E+03 ND-147 7.86E+03 8.56E+03 6.62E+02 0.OOE+00 3.09E+03 5.13E+02 0.OOE+00 5.02E+03 4.83E+05 2.14E+05 3.72E+05 1.82E+05 137

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.2.4 Pathway Dose Factors, RI AGE GROUP. ADULT PATHWAY: INHALATION ORGAN DOSE FACTORS; mrem/year per pCi/M3 NUCLIDE -

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 C-14 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 0.OOE+O0 1.82E+04 0.OOE+O0 0.OOE+O0 2.46E+04 1.18E4-04

--- 0-E+--

0.OOE+00 4.32E+05 1.26E+03 3.41 E+03 0.OOE+00 3.96E+04 1.70E+04 2.78E+04 1.58E+03 1.15E+04 3 14E+04 1.26E+03 3.41 E+03 1.OOE+02 6.30E+03 3.94E+03 1.06E+04 2.07E+03 1.48E+04 1.45E+04 1.26E+03 1.26E+03 1.26E+03 1.26E+03 3.41E+03 341E+03 3.41E+03 341E+03 5.95E+01 2.28E+01 1.44E+04 3.32E+03 O.OOE+00 9.84E+03 1.40E+06 7.74E+04 O.OOE+00 0.00E+00 7.21 E+04 6.03E+03 O.OOE+00 O.00E+00 1.02E+06 1.88E+05 O.OOE+00 0.00E+00 9.28E+05 1.06E+05 O.00E+00 0.OOE+00 5.97E+06 2.85E+05 O.OOE+00 0.00E+00 1.78E+05 1.34E+04 ZN-65 3.24E+04 1.03E+05 RB-86 0.00E+00 1.35E+05 SR-89 3.04E+05 0.OOE+00 SR-90 9.92E+07 0.OOE+00 Y-91 4.62E+05 0.OOE+00 ZR-95 1.07E+05 3 44E+04 4.66E+04 5.90E+04 8.72E+03 6.1 OE+06 1.24E+04 2.33E+04 NB-95 1.41 E+04 7.82E+03 RU-103 1.53E+03 0.OOE+00 RU-1 06 6.91E+04 0 OOE+00 AG-11OM 1.08E+04 1.OOE+04 TE-125M 3.42E+03 1.58E+03 TE-127M 1.26E+04 5.77E+03 TE-129M 9.76E+03 4.67E+03 1-131 2.52E+04 3.58E+04 1-133 8.64E+03 1.48E+04 CS-134 3.73E+05 8.48E+05 CS-136 3.90E+04 1.46E+05 CS-137 4.78E+05 6.21E+05 BA-140 3.90E+04 4.90E+01 CE-141 1.99E+04 1.35E+04 CE-144 3.43E+06 1.43E+06 4.21 E+03 6.58E+02 8.72E+03 5.94E+03 4.67E+02 1.57E+03 1.58E+03 2.05E+04 4.52E+03 7.28E+05 1.1OE+05 4.28E+05 2.57E+03 1.53E+03 1.84E+05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 I1.05E+03 3.29E+03 3A44E+03 1.19E+07 2.1 5E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0 OOE+O0 6.90E+04 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 5 42E+04 7.74E+03 5.83E+03 1.34E+05 1.97E+04 1.24E+04 4.58E+04 8.64E+05 0.00E+00 1.40E+06 9.60E+06 1.70E+06 1.77E+06

_E _0 _

5.05E+05 5.05E+05 9.36E+06 4.63E+06 3.14E+05 9.60E+05 5.34E+04 1.66E+04 3.50E+05 7.22E+05 3 85E+05 1.50E+05 1.04E+05 1.10E+05 9.12E+05 3.02E+05 7.06E+04 1.50E+05 3.66E+04 6.13E+04 2.58E+04 2.87E+05 8.56E+04 2.22E+05 1.67E+01 6.26E+03 8.48E+05 1.16E+06 0.OOE+00 0.OOE+00 9.76E+04 I1.20E+04 7.52E+04 1.27E+06 3.62E+05 7.78E+06 3.83E+05 6.28E+03 8.88E+03 1.04E+04 1.17E+04 8.40E+03 2.18E+05 1.20E+05 8.16E+05 PR-143 9.36E+03 3.75E+03 ND-147 5.27E+03 6 1OE+03 4.64E+02 0.OOE+00 2.16E+03 2.81E+05 3.65E+02 0.OOE+00 3.56E+03 2.21E+05 2.OOE+05 I1.73E+05 138

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.3.1 Pathway Dose Factors, Ri AGE GROUP: ALL PATHWAY: GROUND PLANE ORGAN DOSE FACTORS*

NUCLIDE _- __-- -- - - - ------------

T.BODY SKIN r------

H-3 O.OOE+00 0.OOE+00 C-14 0.OOE+00 0.OOE+00 CR-51 4.65E+06 5.50E+06 MN-54 1.39E+09 1.62E+09 FE-55 0.OOE+00 0.OOE+00 FE-59 2.73E+08 3.21E+08 I---

CO-58 3.79E+08 4.44E+08 CO-60 2.15E+10 2.53E+10 NI-63 0.OOE+00 0.OOE+00 rZN-65 7.47E+0B 8.59E+08 RB-86 8.97E+06 1.03E+07 SR-89 2.16E+04 2.51E+04 SR-90 0.00E+00 0.OOE+00 Y-91 1.07E+06 1.21 E+06 ZR-95 2.45E+08 2.84E+08 NB-95 1.37E+08 1.61E+08 RU-103 1.08E+08 1.26E+08 RU-1 06 4.22E+08 5.06E+08 AG-11OM 3.44E+09 4.01 E+09 TE-125M 1.55E+06 2.13E+06 TE-127M 9.17E+04 1.08E+05

TE-129M 1.98E+07 2.31E+07 11-131 1.72E+07 2.09E+07

1-133 2.45E+06 2.98E+06 r- -----

CS-134 6.86E+09 8.OOE+09 CS-136 1.51E+08 1.71E+08 CS-137 1.03E+10 1.20E+10 BA-140 2.06E+07 2.36E+07 CE-141 1.37E+07 1.54E+07 CE-144 6.96E+07 8.05E+07 PR-143 0.00E+00 0.OOE+00 ND-147 8.39E+06 1.01E+07

-2 mremlyear per iCi/sec.

139

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.4.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MILK 1

ORGAN DOSE FACTORS; m2

- mrem/year per plCi/sec NUCLIDE --------------------

j BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+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.OOE+08 5.OOE+08 5.00E+08 5.00E+08 5.OOE+08 CR-51 O.OOE+00 O.OOE+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 MN-54 O.OOE+00 3.91E+07 8.85E+06 O.OOE+00 8.65E+06 O.OOE+00 1.43E+07 FE-55 1.35E+08 8.74E+07 2.34E+07 O.OOE+00 O.OOE+00 4.27E+07 1.11 E+07 FE-59 2.25E+08 3.93E+08 1.55E+08 O.OOE+00 O.OOE+00 1.16E+08 1.88E+08 CO-58 O.OOE+00 2.43E+07 6.06E+07 O.OOE+00 O.OOE+00 0.00E+00 6.05E+07 CO-60 O.OOE+00 8.83E+07 2.08E+08 O.OOE+00 O.OOE+00 O.OOE+00 2.10E+08 NI-63 3.50E+10 2.16E+09 1.21E+09 O.OOE+00 O.OOE+00 O.OE+00 1.08E+08 ZN-65 5.56E+09 1.91E+10 8.79E+09 O.OOE+00 9.24E+09 O.OOE+00 1.61E+10 RB-86 O.OOE+00 2.23E+10 1.10E+10 O.OOE+00 O.OOE+00 O.OOE+00 5.70E+08 SR-89 1.26E+10 O.OOE+00 3.62E+08 O.OOE+00 O.OOE+00 O.OE+00 2.59E+08 SR-90 1.22E+11 O.OOE+00 3.10E+10 O.OOE+00 O.OOE+00 O.OOE+00 1.52E+09 Y-91 7.34E+04 O.OOE+00 1.95E+03 O.OOE+00 O.OOE+00 O.OOE+00 5.26E+06 ZR-95 6.81E+03 1.66E+03 1.18E+03 O.OOE+00 1.79E+03 O.OOE+00 8.27E+05 NB-95 5.94E+05 2.45E+05 1.A1 E+05 O.OOE+00 1.75E+05 O.OOE+00 2.07E+08 RU-103 8.68E+03 O.OOE+00 2.90E+03 O.OOE+00 1.81E+04 O.OOE+00 1.06E+05 RU-106 1.91E+05 O.OOE+00 2.38E+04 O.OOE+00 2.25E+05 O.OOE+00 1.45E+06 AG-11 OM 3.86E+08 2.82E+08 1.87E+08 O.OOE+00 4.03E+08 O.OOE+00 1.46E+10 TE-125M 1.51E+08 5.05E+07 2.04E+07 5.08E+07 O.OOE+00 O.OOE+00 7.19E+07 TE-127M 4.22E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 O.OOE+00 1.70E+08 TE-129M 5.58E+08 1.91 E+08 8.59E+07 2.14E+08 1.39E+09 0 OOE+00 3.33E+08 1-131 2.72E+09 3.21E+09 1.41E+09 1.05E+12 3.75E+09 O.OOE+00 1.15E+08 1-133 3 63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 0.OOE+00 8.96E+06 CS-134 3.65E+10 6.81E+10 6.88E+09 O.OOE+00 1.75E+10 7.19E+09 1.85E+08 CS-136 1.98E+09 5.83E+09 2.18E+09 O.OOE+00 2.32E+09 4.75E+08 8.85E+07 CS-137 5.15E+10 6.03E+10 4.27E+09 O.OOE+00 1.62E+10 6.55E+09 1.89E+08 BA-140 2.42E+08 2.42E+05 1.25E+07 O.OOE+00 5.75E+04 1.49E+05 5.94E+07 CE-141 4.34E+04 2.65E+04 3.12E+03 O.00E+00 8.17E+03 O.OOE+00 1.37E+07 CE-144 2.33E+06 9.53E+05 1.30E+05 O.OOE+00 3.85E+05 O.00E+00 1.34E+08 PR-143 1.49E+03 5.56E+02 7.37E+01 O.OOE+00 2.07E+02 O.OOE+00 7.84E+05 ND-147 8.83E+02 9.07E+02 5.55E+01 O.OOE+00 3.50E+02 O.OOE+00 5.75E+05 140

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.4.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-COW-MILK NUCLIDE H-3 C-14 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 ORGAN DOSE FACTORS; m2

-mrem/year per giCi/sec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI 0.00E+00 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 0.00E+00 0.OOE+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5 40E+06 O.00E+00 2.10E+07 5.59E+06 0.OOE+00 5.89E+06 O.OOE+00 1.76E+07 1.12E+08 5.94E+07 1.84E+07 O.OOE+00 0.OOE+00 3.36E+07 1.10E+07 1.20E+08 1.95E+08 9.70E+07 0.OOE+00 0.00E+00 5.65E+07 2.03E+08 0.OOE+00 1.21E+07 3.72E+07 0.00E+00 O.OOE+00 O.00E+00 7.08E+07 0.00E+00 4.32E+07 1.27E+08 0.OOE+00 0.00E+00 0.OOE+00 2.39E+08 2.97E+10 1.59E+09 1.01E+09 0.OOE+00 0.OOE+00 0.OOE+00 1.07E+08 4.14E+09 O.OOE+00 6.63E+09 1.12E+ll 3.91 E+04 3.84E+03 1.10E+10 8.78E+09 O.OOE+00 O.OOE+00 O.OOE+00 8.43E+02 NB-95 RU-103 RU-1 06 AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 3.18E+05 4.29E+03 9.25E+04 2.09E+08 7.39E+07 2 08E+08 1.24E+05 O.OOE+00 O.OOE+00 1.41 E+08 2.OOE+07 5 61 E+07 6.86E+09 O.OOE+00 5.40E+09 O.OOE+00 1.89E+08 0.00E+00 2.84E+10 0.OOE+00 1.05E+03 0.00E+00 7.51E+02 0.00E+00 8.86E+04 0.00E+00 1.65E+03 0.00E+00 1.15E+04 0.00E+00 1.13E+08 0.OOE+00 9.85E+06 2.07E+07 2.47E+07 4.98E+07 4.22E+07 8.76E+07 7.46E+08 4.34E+11 8.05E+06 3.95E+09 7.85E+09 0.00E+00 1.80E+09 0.00E+00 4.56E+09 0.OOE+00 6.86E+06 0.OOE+00 1.62E+03 0.OOE+00 8.67E+04 0.OOE+00 2.72E+08 7.59E+07 1.31E+09 1.31E+09 1.72E+07 2.13E+07 6.95E+09 O.00E+00 O.OOE+00 O.OOE+00 1.94E+09 0.OOE+00 5.65E+08 0.OOE+00 2.57E+08 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 1.21 E+03 0.O0E+00 1.16E+05 0 00E+00 1.08E+04 0.OOE+00 1.25E+05 0.00E+00 2 63E+08 0 OOE+00 0.OOE+00 0.OOE+00 5.94E+08 0.OOE+00 7.98E+08 0.OOE+00 2.16E+09 0.OOE+00 3.55E+07 0.OOE+00 1.15E+10 4.14E+09 1.49E+09 2.21E+08 1.01E+10 3.62E+09 3.35E+04 6.14E+04 4.79E+03 0.OOE+00 2.82E+05 0.00E+00 1.51 E+09 5.21 E+06 8.80E+05 2.29E+08 1.11E+05 1.44E+06 1.68E+10 7.13E+07 1.69E+08 3.31 E+08 1.17E+08 8.58E+06 2.01 E+08 9.80E+07 1.93E+08 5.96E+07 1.36E+07 1.33E+08 2.27E+10 1.01 E+09 3.23E+1 0 1.18E+08 2.19E+04 1.63E+06 3.72E+l 0 2.79E+09 3.09E+10 1.03E+05 1.09E+04 5.09E+05 PR-143 7.18E+02 2.16E+02 3.56E+01 O.OOE+00 1.17E+02 O.OOE+00 7.75E+05 ND-147 4A5E+02 3.61E+02 2.79E+01 O.OOE+00 1.98E+02 O.OOE+00 5.71E+05 141

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.4.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-COW-MILK ORGAN DOSE FACTORS; m2-mrem/year per,+/-Ci/sec NUCLIDE ----------------------------------------------------------

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 C-14 4.86E+08 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 CR-51 0.OOE+00 0.OOE+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 MN-54 0.00E+00 1.40E+07 FE-55 4.46E+07 3.16E+07 FE-59 5.19E+07 1.21E+08 CO-58 0.OOE+00 7.94E+06 CO-60 0.OOE+00 2.78E+07 NI-63 1.18E+10 8.36E+08 ZN-65 2.11 E+09 7.32E+09 RB-86 0.OOE+00 4.73E+09 SR-89 2.68E+09 0.OOE+00 SR-90 6.62E+10 0.OOE+00 Y-91 1.58E+04 0.OOE+00 ZR-95 1.65E+03 5.21 E+02 NB-95 1.41 E+05 7.82E+04 RU-103 1.81E+03 0.00E+00 RU-1 06 3.76E+04 0.OOE+00 2.78E+06 7.37E+06 4.68E+07 1.83E+07 6.27E+07 4.01 E+08 3.42E+09 2.22E+09 7.67E+07 1.63E+10 4.24E+02 3.58E+02 4.30E+04 7.75E+02 4.73E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E1+00 4.19E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.69E+09 0.OOE+00 0 00E+00 0.OOE+00 0 OOE+00 7.65E+02 7.58E+04 6.39E+03 7.24E+04 1.74E+08 0.OOE+00 3A2E+08 4.61 E+08 1.30E+09 2.11 E+07 7.35E+09 9.63E+08 6.06E+09 2.02E+04 2.80E+03 1.63E+05 0.OOE+00 2.01 E+07 3.82E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.81 E+09 0.52E+08 2.36E+09 4.01 E+04 0.OOE+00 0.00E-+00 2.88E+07 1.37E+07 2.86E+08 1.1OE+08 3.62E+08 1.33E+08 3.1 OE+09 7.00E+08 3.19E+08 1.86E+09 6.48E+06 1.20E+06 3.34E+08 1.51 E+05 1.80E+06 2.56E+10 8.87E+07 2.11E+08 4.14E+08 1.49E+08 9.09E+06 2.88E+08 1.42E+08 2.54E+08 7.51 E+07 1.70E+07 1.66E+08 AG-11OM 9.64E+07 9.12E+07 5.55E+07 0.00E+00 TE-125M 3.01E+07 1.08E+07 4.02E+06 8.40E+06 TE-127M 8 45E+07 3 00E+07 11.OOE+07 2.01 E+07 TE-129M 1.1OE+08 4.09E+07 1.74E+07 3.56E+07 1-131 5.38E+08 7.53E+08 4.05E+08 2.20E+11 1-133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 CS-134 9.83E+09 2.31E+10 1.07E+10 0.OOE+00 CS-136 4.49E+08 1.77E+09 1.19E+09 0.OOE+00 CS-137 1.34E+10 1.78E+10 6.21E+09 0.OOE+00 BA-140 4.87E+07 5.97E+04 3.14E+06 0.OOE+00 CE-141 8.89E+03 5.94E+03 6.82E+02 0.OOE+00 CE-144 6.59E+05 2.73E+05 3.54E+04 0.OOE+00 PR-143 2.90E+02 1.16E+02 1.44E+01 0.OOE+00 6.73E+01 0.OOE+00 ND-147 1.81E+02 1.97E+02 1.18E+01 0.OOE+00 1.16E+02 0.OOE+00 9.55E+05 7.12E4-05 142

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.4.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MILK 1

ORGAN DOSE FACTORS; m2 rmremlyear per,iCi/sec NUCLIDE ----------------------------------------------------------

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 C-14 2.63E+08 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 CR-51 0.OOE+00 0.OOE+00 2.85E+04 1.70E+04 6.28E+03 3.78E+04 7.17E+06 MN-54 0 OOE+00 8.40E+06 1.60E+06 0.OOE+00 2.50E+06 O.OOE+00 2.57E+07 FE-55 2.51 E+07 1.73E+07 4.04E+06 0.OOE+00 0.00E-+00 9.66E+06 9.93E+06 FE-59 2.97E+07 6.97E+07 2.67E+07 0.OOE+00 0.OOE+00 1.95E+07 2.32E+08 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-110 TE-125 TE-127 TE-129 1-131 1-133 0.00E+00 4.71 E+06 0.OOE+00 1.64E+07 6.72E+09 4.65E+08 1.37E+09 4.36E+09 0.OOE+00 2.59E+09 1.45E+09 0.OOE+00 4.67E+10 0 00E+00 8.57E+03 0.OOE+00 9.41E+02 3 02E+02 8.24E+04 4.58E+04 3

1.02E+03 0 OOE+00 2 04E+04 0.O0E+00

)M 5 81E+07 5.38E+07 iM 1.63E+07 5.89E+06 M

4.57E+07 1.63E+07 1.05E+07 3.61 E+07 2.25E+08 1.97E+09 1.21 E+09 4.16E+07 1.15E+10 2.29E+02 2.04E+02 2.46E+04 4.38E+02 2.58E+03 3.19E+07 2.18E+06 5.57E+06 9.51 E+06 2.42E+08 2.05E+06 1.10E+10 7.48E+08 6.60E+09 1.76E+06 3.71 E+02 1.92E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 9.54E+07 0.OOE+00 3.08E+08 0.OOE+00 9.71 E+07 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE1+00 O OOE+00 0.00E+00 4.89E+06 1.17E+07 2.06E+07 1.39E+1 1 9.88E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE1+00 0.00E+00 2.91 E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.74E+02 4.53E+04 3.88E+03 3.93E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00-0.OOE+00 0.OOE+00 0.OOE+00

---OOE+0-0.OOE+00 2.74E+09 5.1 OE+08 2.32E+08 1.35E+09 4.72E+06 9.57E+05 2.78E+08 1.1 9E+05 1.32E+06 M

6.01 E+07 2.96E+08 3.87E+06 2.24E+07 4.23E+08 6.73E+06 CS-134 CS-136 CS-1 37 BA-140 CE-141 CE-144 5.64E+09 1.34E+10 2.63E+08 1.04E+09 7.37E+09 1.01E+10 2.69E+07 3 38E+04 4.84E+03 3.27E+03 3.57E+05 I 49E+05 1.06E+08 6.61 E+07 1.86E+08 2.51 E+08 7.25E+08 1.17E+07 4.34E+09 5.78E+08 3.42E+09 1.15E+04 1.52E+03 8.85E+04 0.OOE+00 0.OOE+00 0.OOE+00

--- OO-+00 0.OOE+00 0.OOE+00 1 44E+09 7.92E+07 I1.14E+09 1.94E+04 0.OOE+00 0.OOE+00 2.1 9E+10 6.49E+07 1.53E+08 3.02E+08 1.12E+08 6.04E+06 2.35E+08 1.18E+08 1.95E+08 5 54E+07 1.25E+07 1.21 E+08 PR-143 1.57E+02 6.32E+01 7.81E+00 ND-147 9.40E+01 1 09E+02 6.50E+00 0.OOE+00 3.65E+01 0.00E+00 6.90E+05 0.OOE+00 6.35E+01 0 OOE+00 5 22E+05 143

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.5.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK 1 --

ORGAN DOSE FACTORS; rn2 - mrem/year per gCi/sec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+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.OOE+08 5.OOE+08 5 00E+08 5.OOE+08 5.00E+08 5.OOE+08 CR-51 0.00E+00 0.OOE+00 1.94E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05 MN-54 0.OOE+00 FE-55 1.76E+06 FE-59 2.92E+06 CO-58 0.OOE+00 CO-60 0.OOE+00 NI-63 4.19E+09 ZN-65 6.67E+08 RB-86 0.OOE+00 SR-89 2.65E+10 SR-90 2.55E+l1 Y-91 8.80E+03 ZR-95 8.17E+02 NB-95 7.13E+04 RU-1 03 1.04E+03 RU-1 06 2.28E+04 4.68E+06 1.06E+06 1.14E+06 3.03E+05 5.10E+06 2.01E+06 2.91E+06 7.26E+06 1.06E+07 2.50E+07 2.59E+08 1.46E+08 2.29E+09 1.05E+09 2.67E+09 1.32E+09 0.OOE+00 7.59E+08 0.OOE+00 6.50E+10 0.OOE+00 2.34E+02 1.99E+02 1.41E+02 2.93E+04 1.70E+04 0.OOE+00 3.48E+02 0.OOE+00 2.85E+03 0.OOE+00 1.04E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.00E+00 0.00E+00 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.l11E+09 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.15E+02 0.OOE+00 2.1OE+04 0.OOE+00 2.17E+03 0.OOE+00 2.70E+04 0.OOE+00 1.72E+06 5.55E+05 1.44E+05 1.51E+06 2.44E+06 0.OOE+00 7.25E+06 0.OOE+00 2.52E+07 0.OOE+00 1.29E+07 0.OOE+00 1.93E+09 0.OOE+00 6.83E+07 0.00E+00 5.44E+08 0.O0E+00 3.19E+09 0.O0E+00 6.31 E+05 0 OOE+00 9.91 E+04 0.OOE+00 2.48E+07 0.OOE+00 1.27E+04 0.OOE+00 1.73E+05 AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-134 CS-1 36 CS-1 37 4.63E+07 I.81 E+07 5.06E+07 6.69E+07 3.27E+09 4.36E+07 1.09E+l11 5.94E+09 1.54E+l I 3.38E+07 2.24E+07 0.OOE+00 4.84E+07 0.OOE+00 1.75E+09 6.05E+06 2.45E+06 6.09E+06 0.OOE+00 0.OOE+00 8.62E+06 1.68E+07 6.12E+06 1.46E+07 1.24E+08 0 OOE+00 2.04E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.OOE+00 3.99E+07 3.85E+09 1.69E+09 1.27E+12 4.50E+09 0.OOE+00 1.37E+08 6.35E+07 1.86E+07 1.15E+10 7.46E+07 0.OOE+00 1.07E+07 2.04E+11 2.06E+10 0.OOE+00 5.26E+10 2.15E+10 5.55E+08 1.75E+10 6.52E+09 0.OOE+00 6.96E+09 1.42E+09 2.65E+08 1.81E+11 1.28E+10 0.OOE+00 4.85E+10 1.96E+10 5.65E+08 2.90E+04 1.50E+06 0.OOE+00 6.89E+03 1.78E+04 7.13E+06 3.18E+03 3.74E+02 0.OOE+00 9.79E+02 0.OOE+00 1.64E+06 1.14E+05 1.56E+04 0.OOE+00 4.62E+04 0.OOE+00 1.60E+07 BA-140 CE-141 CE-144 2.90E+07 5.21 E+03 2.79E+05 PR-143 1.78E+02 6.66E+01 8.83E+00 0.OOE+00 2.48E+01 0.OOE+00 9.40E+04 ND-147 1.06E+02 1.09E+02 6.66E+00 0.OOE+00 4.19E+01 0.OOE+00 6.89E+04 144

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Tile Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.5.2 Pathway Dose Factors, RI AGE GROUP. CHILD PATHWAY: GRASS-GOAT-MILK ORGAN DOSE FACTORS; m2 - mrem/year per IuCi/sec NUCLIDE ----------

LUN

-Gl-LL jBONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 C-14 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 0.00E+00 3.20E+03 1.20E+09 2.39E+08 0.OOE+00 0 00E+00 0.00E+00 2.52E+06 1.45E+06 7.71E+05 1.56E+06 2.53E+06 0.00E+00 1.46E+06 0 00E+00 5.18E+06 3.56E+09 1.91E+08 3.20E+03 2.39E+08 1.22E+04 6 71E+05 2.39E+05 1.26E+06 4.46E+06 1.53E+07 1.21 E+08 3.20E+03 2.39E+08 6.78E+03 0.OOE+00 I

0.OOE+00 I

0.00E+00 I

0 OOE+00 I

0.00E+00 I

3.20E+03 2.39E+08 1.85E+03 7.06E+05

).OOE+00

).OOE+00 3.20E+03 2.39E+08 1.24E+04 0.OOE+00 4.36E+05 7.34E+05

_0.00E+0 0.00E+00 0.00E+00 0.00E+00 3.20E+03 2.39E+08 6.48E+05 2.11 E+06 1.43E+05 2.64E+06 8.49E+06 2.87E+07 1.28E+07 ZN-65 4.96E+08 RB-86 0.00E+00 SR-89 1.39E+10 SR-90 2.35E+11 Y-91 4.69E+03 ZR-95 4.60E+02 NB-95 3.82E+04 RU-1 03 5.14E+02 RU-1 06 1.11 E+04 1.32E+09 1.05E+09 0 OOE+00 0.OOE+00 0.OOE+00 1.01E+02 1.49E+04 0.OOE+00 0.OOE+00 AG-11OM 2.51E+07 TE-125M 8 86E+06 TE-127M 2.50E+07 TE-129M 3 26E+07 1-131 1.57E+09 1-133 2.06E+07 CS-134 6.80E+10 CS-1 36 3.04E+09 CS-137 9.68E+10 BA-140 1.41 E+07 CE-141 2.63E+03 CE-144 1.95E+05 1.69E+07 2.40E+06 6.72E+06 9.1 OE+06 1.57E+09 2.55E+07 1.1 2E+11 8.36E+09 9.26E+10 1.24E+04 1.31 E+03

6. 1 E+04 8.22E+08 6.47E+08 3.97E+08 5 95E+10 1.25E+02 9.OOE+01 1.06E+04 1.98E+02 1.38E+03 1.35E+07 1.18E+06 2.96E+06 5.06E+06 8.95E+08 9.66E+06 2.35E+10 5.41 E+09 1.37E+10 8.23E+05 1.95E+02 1.04E+04 0.00E+00 8.33E+08 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O OOE+00 0.00E+00 0.00E4-00 0.OOE+00 I A45E+02 0.00E+00 1.40E+04 0.00E+00 1.29E+03 0.00E+00 1.50E+04 0.OOE+00 3.15E+07 2.49E+06 0.00E+00 5.97E+06 7.12E+07 1.05E+07 9.56E+07 5.21E+11 2.58E+09 4.74E+09 4.25E+07 0.00E+00 3.46E+10 0.OOE+00 4.45E+09 0.OOE+00 3.02E+10 0.OOE+00 4.02E+03 0.OOE+00 5.74E+02 0.OOE+00 3.38E+04 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00-O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00-O.OOE+00 1.24E+l10 6.64E+08 1.09E+l10 7.37E+03 0 OOE+00 0.OOE+00 2.75E+07 1.33E+04 1.73E+05 2.01 E+09 8.55E+06 2.02E+07 3.97E+07 1.40E+08 1.03E+07 6.01 E+08 2.94E+08 5.80E+08 7.15E+06 1.63E+06 1.59E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00-0.OOE+00 0.OOE+00 2.32E+08 6.77E+07 5.39E+08 3.16E+09 6.24E+05 1.05E+05 PR-143 8.61E+01 2.59E+01 4.27E+00 0.OOE+00 1.40E+01 0.OOE+00 9.29E+04 ND-147 5.34E+01 4.33E+01 3.35E+00 0.OOE+00 2.37E+01 0.OOE+00 6.85E+04 145

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.5.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK I

ORGAN DOSE FACTORS; m2 rmrem/year per pCi/sec NUCLIDE ----------------------------------------

j BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 C-14 CR-51 MN-54 FE-55 FE-59 0.00E+00 4.86E+08 0.00E+00 0.OOE+00 5.79E+05 6.74E+05 2.04E+03 9.72E+07 0.00E+00 1.68E+06 4.11 E+05 1.57E+06 2.04E+03 9.72E+07 5.99E+03 3.34E+05 9.58E+04 6.08E+05 2.04E+03 9.72E+07 3.33E+03 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

.00E+00 2.04E+03 9.72E+07 1.31 E+03 5.02E+05 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.04E+03 2.04E+03 9.72E+07 9.72E+07 8.55E+03 1.01E+06 0.OOE+00 3.45E+06 2.61 E+05 1.78E+05 4.96E+05 3.72E+06

_-O-0 1_3_1E+_0_

0.OOE+00 1.31 E+07 0.OOE+00 4.35E+07 0.00E+00 1.60E+07 CO-58 0.OOE+00 9.53E+05 CO-60 0.OOE+00 3.34E+06 NI-63 1.42E+09 1.OOE+08 2.20E+06 7.52E+06 4.81 E+07 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-110M TE-125M TE-127M TE-129M 1-131 1-133 2.53E+08 0.OOE+00 5.62E+09 1.39E+11 1.90E+03 1.98E+02 1.69E+04 2.17E+02 4.50E+03 1.16E+07 3 61E+06 1.01 E+07 1.32E+07 6.45E+08 8.49E+06 8.78E+08 5.67E+08 0.OOE+00 0.OOE+00 0.OOE+00 6.25E+01 9.38E+03 0.OOE+00 0.OOE+00 1.09E+07 1.30E+06 3.59E+06 4.90E+06 9.03E+08 1.44E+07 4.1 OE+08 2.67E+08 1.61 E+08 3.43E+10 5.09E+01 4.30E+01 5.16E+03 9.29E+01 5.68E+02 6.65E+06 4.82E+05 1.20E+06 2.09E+06 4.85E+08 4.40E+06 3.22E+1 0 3.56E+09 1.86E+10 3.76E+05 8.18E+01 4.25E+03 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+O0 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.00E+06 2.41 E+06 4.26E+06 2.64E+1 1 2.01 E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 5.62E+08 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 9.18E+01 9.09E+03 7.66E+02 8.69E+03 2.09E+07 0.OOE+00 4.11 E+07 5.53E+07 1.56E+09 2.53E+07 2.20E+10 2.89E+09 1.82E+10 2.43E+03 3.35E+02 1.95E+04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.72E+08 8 40E+07 6.69E+08 3 90E+09 7.78E+05 1.44E+05 0.OOE+00 4.01E+07 0.OOE+00 1.82E+04 0.OOE+00 2.16E+05 0 OOE+00 3 07E+09 0.OOE+00 1.06E+07 0.OOE+00 2.52E+07 0.OOE+00 4.96E+07 0.OOE+00 1.79E+08 0.OOE+00 1.09E+07 8.41 E+09 8.62E+08 4.55E+08 4.27E+08 7.07E+09 7.60E+08 4.81E+03 9.01E+06 0.OOE+00 2.04E+06 0.OOE+00 1.99E+07 CS-1 34 2.95E+10 6.93E+10 CS-1 36 1.35E+09 5.30E+09 CS-137 4.02E+10 5.34E+10 BA-140 5.84E+06 7.16E+03 CE-141 1.07E+03 7.12E+02 CE-144 7.90E+04 3.27E+04 PR-143 3.48E+01 1.39E+01 1.73E+00 0.OOE+00 8.08E+00 0.OOE+00 1.15E+05 ND-147 2.18E+01 2.37E+01 1.42E+00 0.OOE+00 1.39E+01 0.OOE+00 8.54E+04 146

Number TMI - Unit 1 I

Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.5.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-GOAT-MILK I

ORGAN DOSE FACTORS; m2 rnremlyear per jICi/sec NUCLIDE ----------

I BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 C-14 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 Nl-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 0.OOE+00 2.64E+08 o 00E+00 0.00E+00 3.27E+05 3.87E+05 0.OOE+00 0.OOE+00 8.08E+08 1.65E+08 0.OOE+00 3.05E+09 9.84E+10 1.03E+03 1.13E+02 1.56E+03 5.27E+07 0.OOE+00 1.01E+06 2.26E+05 9.09E+05 5.66E+05 1.97E+06 5.60E+07 5.24E+08 3.12E+08 0.OOE+00 0.00E+00 0.OOE+00 3.63E+01 1.56E+03 1.56E+03 1.56E+03 5.27E+07 5.27E+07 5.27E+07 3.43E+03 2.05E+03 7.56E+02 1.93E+05 0.OOE+00 3.01E+05 5.26E+04 0.OOE+00 O.OOE+00 3.48E+05 0.OOE+00 O.OOE+00 1.27E+06 0.OOE+00 O.OOE+00 4.35E+06 0.OOE+00 O.OOE+00 2.71E+07 0.OOE+00 0.OOE+00 2.37E+08 0.OOE+00 3.51E+08 1.45E+08 0.OOE+00 0.OOE+00 8.76E+07 0.OOE+00 0.OOE+00 2.41E+10 0.OOE+00 0.OOE+00 2.76E+01 0.OOE+00 0.00E+00 2.46E+01 0.OOE+00 5.70E+01 2.97E+03 0.OOE+00 5.45E+03 5.27E+01 0.OOE+00 4.67E+02 3.1 OE+02 0.OOE+00 4.73E+03 3.84E+06 0.OOE+00 1.27E+07 2.62E+05 5.89E+05 7.96E+06 6.70E+05 1.41 E+06 2.23E+07 1.56E+03 1.56E+03 5.27E+07 5 27E+07 4.55E+03 8 63E+05 0.OOE+00 3.1OE+06 1.26E+05 1.30E+05 2.54E+05 3.03E+06 O.OOE+00 1.15E+07 0.OOE+00 3.70E+07 0.OOE+00 1.17E+07 0.OOE+00 3 30E+08 O.OOE+00 6.14E+07 0.OOE+00 4.89E+08 0.00E+00 2.84E+09 0.00E+00 5.68E+05 O.OOE+00 1.15E+05 O.OOE+00 3.35E+07 O.OOE+00 1.43E+04 0.OOE+00 1.59E+05 0 OOE+00 2.64E+09 0.OOE+00 7.81E+06 O.OOE+00 1.84E+07 NB-95 RU-1 03 RU-1 06 AG-110M TE-125M TE-127M TE-129M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 9.9211+03 1.22E+02 2A45E+03 6.99E+06 1.96E+06 5.50E+06 7.23E+06 3.56E-I08 4.65E+06 1.70E+1 0 7.92E+08 2.22E+1 0 3.24E-'06 5.82E+02 4.30E+04 5.52E+03 0.OOE+00 0.OOE+00 6.47E+06 7.09E+05 1.97E+06 2.70E+06 5.09E+08 8.1 OE+06 4.04E+10 3.13E+09 3.03E+10 4.07E+03 3.94E+02 1.80E+04 1.14E+06 2.92E+08 2.47E+06 3.30E+10 2.25E+09 1.99E+10 2.12E+05 4.47E+01 2.31 E+03 2.48E+06 1.67E+1 1 1.19E+09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.02E+07 8.73E+08 1.41 E+07 1.31E+10 I1.74E+09 1.03E+10 1.38E+03 1.83E+02 1.07E+04 0.OOE+00 3.64E+07 0 OOE+00 1.34E+08 0.OOE+00 7.28E+06 4.34E+09 7.07E+08 2.38E+08 3.55E+08 3.42E+09 5.87E+08 2.33E+03 6.67E+06 0.OOE+00 1.51 E+06 0 OOE+00 1.45E+07 PR-143 1.90E+01 7.60E+00 9.40e-01 0.OOE+00 4.39E+00 ND-147 1.13E+01 1.31E+01 7.82e-01 0.00E+00 7.65E+00 0.OOE+00 8.30E+04 0.OOE+00 6.28E+04 147

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.6.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT ORGAN DOSE FACTORS; m2 - mrem/year per giCi/sec NUCLIDE ----------

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 C-14 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.00E+00 0.OOE+00 CR-51 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 MN-54 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 FE-55 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 FE-59 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CO-58 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 CO-60 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 NI-63 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 ZN-65 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 RB-86 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 SR-89 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.00E+00 0.00E+00 SR-90 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-91 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 ZR-95 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 NB-95 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 RU-1 03 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 RU-1 06 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 AG-110M 0 00E+00 0.OOE+00 0.00E+00 0 OE+00 0.OOE+00 0 OOE+00 0.00E+00 TE-125M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 TE-127M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 TE-129M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-131 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-133 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 C-i_ 34

_____________E________E________E________E________E_____.O-E CS-134 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CS-136 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CS-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+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.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CE-144 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 PR-143 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 ND-147 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 148

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01I Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.6.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-COW-MEAT 1

ORGAN DOSE FACTORS; m2 rmrem/year per p.Ci/sec NUCLIDE -

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 C-14 3.84E+08 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 CR-51 0.00E+00 0.00E+00 8.78E+03 4.88E+03 1.33E+03 8.90E+03 4.66E+05 MN-54 0.OOE+00 8.01E+06 2.13E+06 0.00E+00 2.25E+06 0.00E+00 6.73E+06 FE-55 4.57E+08 2.43E+08 7.52E+07 0.00E+00 O.OOE+00 1.37E+08 4.49E+07 FE-59 3 77E+08 6.10E+08 3.04E+08 0.00E+00 O.OOE+00 1.77E+08 6.35E+08 CO-58 0.OOE+00 1.64E+07 5 03E+07 0.OOE+00 0.OOE+00 0.OOE+00 9.58E+07 CO-60 0.00E+00 6.93E+07 2.04E+08 0.00E+00 0.00E+00 0.00E+00 3.84E+08 NI-63 2.91E+10 1.56E+09 9.91E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.05E+08 ZN-65 3.76E+08 1.OOE+09 6.22E+08 0.OOE+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.OOE+00 0.OOE+00 3.71 E+07 SR-89 4.82E+08 0.OOE+00 1.38E+07 0.00E+00 0.00E+00 0.00E+00 1.87E+07 SR-90 1.04E+10 0.00E+00 Y-91 1.80E+06 0.00E+00 ZR-95 2.66E+06 5.86E+05 NB-95 3.10E+06 1.21E+06 RU-103 1.55E+08 0.00E+00 RU-1 06 4.44E+09 0.OOE+00 AG-110M 8.39E+06 567E+06 TE-125M 5.69E+08 1.54E+08 TE-127M 1.78E+09 4.78E+08 TE-129M 1.79E+09 5.00E+08 1-131 1.66E+07 1.67E+07 1-133 5.72e-01 7.08e-01 CS-134 9.23E+08 1.51E+09 CS-136 1.63E+07 4.48E+07 CS-137 1.33E+09 1.28E+09 BA-140 4.42E+07 3.87E+04 CE-141 2.22E+04 1.11E+04 CE-144 2.32E+06 7.26E+05 2.64E+09 4.82E+04 5.21 E+05 8.63E+05 5.96E+07 5.54E+08 4.53E+06 7.59E+07 2.11 E+08 2.78E+08 9.48E+06 2.68e-01 3.19E+08 2.90E+07 1.89E+08 2.58E+06 1.65E+03 1.24E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.38E+05 0.OOE+00 1.13E+06 0.00E+00 3.90E+08 0.00E+00 6.00E+09 0.00E+00 1.06E+07 1.60E+08 0.00E+00 4.25E+08 5.06E+09 5.77E+08 5.26E+09 5 52E+09 2.74E+07 1.31E+02 1.18E+00 0.00E+00 4.69E+08 0.00E+00 2.39E+07 0.00E+00 4.16E+08 0_002+00 1_40__08 0.00E+00 1.40E+08 0.00E+00 2.40E+08 0.00E+00 6.11 E+08 0 00E+00 2.23E+09 0.00E+00 4.01 E+09 0.00E+00 6.91 E+10 0.00E+00 6 74E+08 0.00E+00 5.49E+08 0.00E+00 1.44E+09 0.00E+00 2.18E+09 0.00E+00 1.48E+06 0.00E+00 2.85e-01 1.68E+08 8.16E+06 3.56E+06 1.57E+06 1.50E+08 8.00E+06 0.00E+00 0.00E+00 0.00E+00 1.26E+04 4.86E+03 4.02E+05 2.31 E+04 0.00E+00 0.00E+00 2.24E+07 1.38E+07 1.89E+08 PR-143 3.33E+04 1.00E+04 1.65E+03 0.00E+00 5.42E+03 0.00E+00 ND-147 1.17E+04 9.48E+03 7.34E+02 0.00E+00 5.20E+03 0.00E+00 3.60E+07 1.50E+07 149

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.6.3 Pathway Dose Factors, RI AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT NUCLIDE ORGAN DOSE FACTORS; m2

- mrem/year per IaCi/sec j

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.00E+00 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 C-14 2.04E+08 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 CR-51 O.00E+00 O.OOE+00 5.63E+03 3.13E+03 1.23E+03 8.03E+03 9.46E+05 MN-54 FE-55 FE-59 C0-58 C0-60 Nl-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-1 06 AG-110M TE-125M TE-127M O.OOE+00 2.38E+08 2.12E+08 O.OOE+00 O.OOE+00 1.52E+10 2.50E+08 O.OOE+00 2.55E+08 8.04E+09 9.54E+05 1.50E+06 1.79E+06 8.56E+07 2.36E+09 5.06E+06 3.03E+08 9.41 E+08 7.OOE+06 1.69E+08 4.95E+08 1.39E+06 3.94E+07 1.91 E+08 0.OOE+00 0.OOE+00 0.OOE+00 2.09E+06 0.00E+00 0.00E+00 0.OOE+00 1.07E+08 1.56E+08 1.44E+07 7.31 E+07 1.17E+09 1.40E+07 5.83E+07 1.07E+09 8.68E+08 4.06E+08 O.OOE+00 O.OOE+00 O.OOE+00 4.73E+05 3.24E+07 C

1.31 E+08 C

5.15E+08 C

4.05E+08 C

1.91E+08 C

7.29E+06 C

1.99E+09 C

2.56E+04 C

3.25E+05 C

).OOE+00

).OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 1.94E+08 7.60E+08 1.71 E+08

).OOE+00

E+-

).OOE+00

).OOE+00 5.56E+08 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 6.95E+05 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.OOE+00 3.68E+08 6.00E+07 3.03E+07 2.26E+08 3.91 E+08 1.09E+09 9.95E+05 O.OOE+O0 O.OOE+O0 4.78E+06 1.09E+08 3.34E+08 5.48E+05 3.66E+07 2.97E+08 2.91 E+06 4.05E+07 1.12E+08 0.OOE+00 0.OOE+00 0.OOE+00 0 00E+00 8.46E+07 2.24E+08 3.06E+08 3.65E+09 7.29E+01 9.64E+05 3.02E+08 4.54E+09 9.13E+06 0.OOE+00 3 81E+09 3.97E+09 2.15E+07 9.16e-01 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00-0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00-0.OOE+00 4.25E+09 7.15E+09 1.13E+11 1.34E+09 8.94E+08 2.35E+09 3.56E+09 2.47E+06 3.95e-01 TE-129M 1-131 1-133 CS-1 34 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 9.49E+08 8.93E+06 3.08e-01 5.23E+08 9.43E+06 7.24E+08 2.39E+07 1.18E+04 1.23E+06 3.52E+08 1.25E+07 5.22e-01 1.23E+09 3.71 E+07 9.63E+08 1.50E+(

6.72E+(

1.59e-0 5.71 E+I 2.49E+(

3.35E+(

38 36 1

38 0.OOE+00 37 0.OOE+00 38 0.OOE+00 06 0.OOE+00 02 0.OOE+00 04 O.OOE+00 3.91 E+08 2.02E+07 3.28E+08 9.94E+03 3.71 E+03 3.03E+05 1.49E+08 3.18E+06 1.27E+08 1.97E+04 0.OOE+00 O.OOE+00 1.53E+07 2.99E+06 1.37E+07 3.69E+07 2.25E+07 3.09E+08 2.93E+04 7.87E+03 5.08E+05 1.54E+(

9.05E+(

6.60E+(

PR-143 1.76E+04 7.03E+03 ND-147 6.23E+03 6.78E+03 8.76E+02 O.OOE+00 4.08E+03 4.06E+02 O.OOE+00 3.98E+03 O.OOE+00 5.79E+07 O.OOE+00 2.44E+07 150

Number TMI -Unit I I

Radiological Controls Procedure 6610-PLN-4200.01 Tile Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.6.4 Pathway Dose Factors, RI AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT ORGAN DOSE FACTORS; m2-mrem/year per iiCi/sec NUCLIDE BONE ---

LIVER ---

T.BODY-THYROID-KIDNEY --

LUNG -

Gl-LLI H-3 C-14 CR-51 MN-54 FE-55 FE-59 0.00E+00 2A42E+08 o OOE+00 0.00E+00 2.93E+08 2.66E+08 3.24E+02 4.83E+07 0.00E+00 9.18E+06 2.03E+08 6.25E+08 3.24E+02 4.83E+07 7.04E+03 3.24E+02 4.83E+07 4.21 E+03 CO-58 0.00E+00 CO-60 0.00E+00 NI-63 1.89E+10 ZN-65 3.56E+08 RB-86 0.00E+00 SR-89 3.02E+08 SR-90 1.24E+10 Y-91 1.13E+06 ZR-95 1.87E+06 NB-95 2.30E+06 RU-103 1.05E+08 RU-1 06 2.80E+09 AG-110M 6.68E+06 TE-125M 3 59E+08 TE-127M 1.12E+09 TE-129M 1.13E+09 1-131 1.08E+07 1-133 3.68e-01 CS-134 6.58E+08 CS-1 36 1.21 E+07 CS-1 37 8.72E+08 BA-140 2.90E+07 CE-141 1.41 E+04 CE-144 1.46E+06 1.82E+07 7.52E+07 1.31 E+09 I1.13E+09 4.87E+08 0.OOE+00 O.OOE+00-O.OOE+00 6.01 E+05 I1.28E+06 0 OOE+00 O.OOE+00 6.1 8E+06 1.30E+08 3.99E+08 1.75E+06 4.73E+07 2.39E+08 4.09E+07 1.66E+08 6.33E+08 5.12E+08 2.27E+08 8.66E+06 3.05E+09 3.03E+04 4.07E+05 6.87E+05 4.53E+07 3.54E+08 3.67E+06 4.81 E+07 1.36E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 000OE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 00OOE+00 0.OOE+00 0.OOE+00 I1.08E+08 2.85E+08 3.24E+02 4.83E+07 1.55E+03 2.73E+06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.57E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 9.43E+05 1.26E+06 4.02E+08 5.41 E+09 1.22E+07 1.46E+09 4.53E+09 4.73E+09 2.64E+07 1.12E+00 5.07E+08 2.66E+07 4.05E+08 1.24E+04 4.42E+03 3.62E+05 3.24E+02 3.24E+02 4.83E+07 4.83E+07 9.35E+03 1.77E+06 0.OOE+00 2.81E+07 1.13E+08 1.16E+08 1.75E+08 2.08E+09 0.OOE+00 3.70E+08 0.OOE+00 1.41E+09 0.OOE+00 2.73E+08 0.OOE+00 7.13E+08 0.OOE+00 9.59E+07 0.OOE+00 4.84E+07 0.OOE+00 3.60E+08 0.OOE+00 6.24E+08 0.OOE+00 1.90E+09 0.OOE+00 7.76E+09 0.OOE+00 1.23E+10 0.OOE+00 1.81E+11 0.OOE+00 2.52E+09 0.00E+00 1.43E+09 0.OOE+00 3.74E+09 0.OOE+00 5.71 E+09 0.OOE+00 4.06E+06 0.OOE+00 5.76e-01 1.68E+08 2.74E+07 3.65E+06 5.43E+06 1.35E+08 2.31E+07 2.08E+04 5.96E+07 0.OOE+00 3.64E+07 0.OOE+00 4.93E+08 4.23E+08 1.54E+07 6.41e-01 1.57E+09 4.78E+07 1.19E+09 3.64E+04 9.51 E+03 6.1OE+05 1.79E+08 8.82E+06 1.95e-01 1.28E+09 3.44E+07 7.82E+08 1.90E+06 1.08E+03 7.83E+04 3.89E+08 5.04E+09 9A42E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 PR-143 2.09E+04 8AOE+03 ND-147 7.08E+03 8.18E+03 1.04E+03 0.OOE+00 4.85E+03 4.90E+02 0.OOE+00 4.78E+03 0 OOE+00 9.17E+07 0.OOE+00 3.93E+07 151

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01I Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.7.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: VEGETATION ORGAN DOSE FACTORS; m2

- mremlyear per giCi/sec NUCLIDE _---------- __ _ __

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 C-14 0.OOE+00 O.00E+00 O.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 CR-51 0.00E+00 0.00E+00 O.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 MN-54 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 FE-55 0.00E+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-59 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-58 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 CO-60 0.00E+00 0.00E+00 0.00E+00 0 00E+00 0.OOE+00 0.OOE+00 0.00E+00 NI-63 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.OOE+00 0.00E+00 0 00E+00 ZN-65 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 RB-86 0.00E+00 0.00E+00 O.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 SR-89 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-90 0.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0 00E+00 Y-91 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 O.OOE+00 O.00E+00 0.OOE+00 ZR-95 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 O.OOE+00 O.00E+00 NB-95 0.OOE+00 O.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 RU-1 03 0 00E+00 O.00E+00 0.00E+00 0.00E+00 0.OOE+00 O.OOE+00 O.OOE+00 RU-1 06 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 AG-110M 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0 00E+00 TE-125M 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 TE-127M 0.OOE+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 TE-129M 0.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.OOE+00 0 00E+00 1-131 O.OOE+00 0.00E+00 O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-133 0.00E+00 0.00E+00 O.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 CS-I 34

_______0-----E+----.00E+00-

.00E+00--

.O-E+00-0.00 CS-1 34 O.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-I137 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-136 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 CE-140 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 CE-144 O.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 PR-143 O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0 OOE+00 ND-147 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0 OOE+00 0.OOE+00 152

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Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.7.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: VEGETATION I

ORGAN DOSE FACTORS; m2 rnremlyear per iLCi/sec NUCLIDE -

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 C-14 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 SR-90 Y-91 ZR-95 0.OOE+00 4.02E+03 8 89E+08 1.78E+08 0.00E+00 0.00E+00 0.00E+00 6.65E+08 8.01E+08 4.25E+08 3.98E+08 6.44E+08 0.00E+00 6.44E+07 0.00E+00 3.78E+08 3.95E+10 2.11E+09 8.12E+08 2.16E+09 0.00E+00 4.51E+08 3.60E+10 0 00E+00 1.24E+12 0.00E+00 1.87E+07 0 00E+00 3.86E+06 8.48E+05 4.02E+03 1.78E+08 1.17E+05 1.77E+08 1.32E+08 3.21 E+08 1.97E+08 1.12E+09 1.34E+09 1.35E+09 2.77E+08 1.03E+09 3.15E+11 4.99E+05 7.55E+05 1.14E+05 5.90E+06 9.30E+07 1.73E+07 4.67E+07 1.57E+08 1.30E+08 8.18E+07 1.65E+06 5.55E+09 1.47E+08 3.38E+09 1.63E+07 4.86E+04 6.79E+06 4.02E+03 1.78E+08 6.49E+04 0.002+00 0.002+00 0.002+00 0.002+00 0.002+00 0.002+00 0.002+00 0.002+00 0.002+00 0.002+00 0002E+00 0.002+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.84E+07 3 16E+08 4.02E+03 1.78E+08 1.77E+04 1.86E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.02E+03 4.02E+03 1.78E+08 1.78E+08 1.18E+05 6.20E+06 0.OOE+00 5.58E+08 2.40E+08 7.87E+07 1.87E+08 6.71E+08 0.OOE+00 3.76E+08 0.00E+00 2.10E+09 0.OOE+00 1.42E+08 1.36E+09 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 1.21 E+06 1.50E+05 3.86E+07 1.01 E+09 4.04E+07 0.00E+00 3.77E+09 0.00E+00 3 80E+08 0.00E+00 2.90E+07 0.00E+00 1.39E+09 0.00E+00 1.67E+10 0.00E+00 2.49E+09 0.00E+00 8.85E+08 0.00E+00 2.96E+08 0.00E+00 3.97E+08 0.00E+00 1.16E+10 0 00E+00 2.58E+09 0.00E+00 3.38E+08 0.00E+00 1.07E+09 NB-95 4.11E+05 1.60E+05 RU-1 03 1.53E+07 0.00E+00 RU-106 7.45E+08 0.00E+00 AG-110M 3 21E+07 2.17E+07 TE-125M 3.51 E+08 9.50E+07 TE-127M 1.32E+09 3.56E+08 TE-129M 8.40E+08 2.35E+08 1-131 1.43E+08 1.44E+08 1-133 3.53E+06 4.37E+06 CS-134 1.60E+10 2.63E+10 CS-136 8.28E+07 2.28E+08 CS-137 2.39E+10 2.29E+10 BA-140 2.79E+08 2.44E+05 CE-141 6.57E+05 3 28E+05 CE-144 1.27E+08 3.99E+07 2.71 E+08 4.76E+10 8.12E+08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.47E+09 2.36E+08 7.28E+06 8.15E+09 1.21 E+08 7.46E+09 7.96E+04 1.44E+05 2.21 E+07 0.00E+00 0.00E+00 0.00E+00 2.93E+09 1.81 E+07 2.68E+09 1.46E+05 0.00E+00 0.00E+00 1.02E+09 1.28E+07 1.76E+06 1.42E+08 8 00E+06 1.43E+08 1.41 E+08 4.09E+08 1.04E+10 PR-143 1.45E+05 4.36E+04 ND-147 7.15E+04 5.79E+04 7.21 E+03 0.00E+00 2.36E+04 0.00E+00 4.49E+03 0.00E+00 3.18E+04 0.00E+00 1.57E+08 9.18E+07 153

Number 661 O-PLN-4200.01 TMI - Unit 1 Radioloqical Controls Procedure Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.7.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: VEGETATION ORGAN DOSE FACTORS; m2 rmrem/year per pCi/sec NUCLIDE -

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.O0E+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 C-14 3.69E+08 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 CR-51 0.OOE+00 0.OOE+00 6.16E+04 3 42E+04 1.35E+04 8 79E+04 1.03E+07 MN-54 0.OOE+00 4.54E+08 9.01E+07 0.OOE+00 1.36E+08 0 00E+00 9.32E+08 FE-55 3.26E+08 2.31E+08 5.39E+07 0.OOE+00 0.00E+00 1.47E+08 1.OOE+08 FE-59 1.80E+08 4.19E+08 1.62E+08 0.OOE+00 0.OOE+00 1.32E+08 9.91E+08 CO-58 0.OOE+00 4.36E+07 1.01E+08 0.OOE+00 0.OOE+00 O.OOE+00 6.01E+08 CO-60 0.OOE+00 2.49E+08 5.60E+08 0.OOE+00 0.OOE+00 0.OOE+00 3.24E+09 NI-63 1.61E+10 1.13E+09 5.45E+08 0.OOE+00 0.00E+00 0.00E+00 1.81E+08 ZN-65 4.24E+08 1.47E+09 6.86E+08 0.OOE+00 9.42E+08 O.OOE+00 6.23E+08 RB-86 0.OOE+00 2.73E+08 1.28E+08 0.OOE+00 0.OOE+00 0.OOE+00 4.04E+07 SR-89 1.52E+10 O.OOE+00 4.34E+08 0 00E+00 0.00E+00 O.OOE+00 1.80E+09 SR-90 7.51E+11 0.OOE+00 1.85E+11 0.OOE+00 OOOE+00 OOOE+00 2.11E+10 Y-91 7.84E+06 0.OOE+00 2.10E+05 0.OOE+00 0.OOE+00 O.OOE+00 3.22E+09 ZR-95 1.72E+06 5.43E+05 3.73E+05 0.OOE+00 7.98E+05 0.OOE+00 1.25E+09 NB-95 1.92E+05 1.07E+05 5.87E+04 0.OOE+00 1.03E+05 0.OOE+00 4.56E+08 RU-103 6.82E+06 O.OOE+00 2.92E+06 0.OOE+00 2.41E+07 O.OOE+00 5.70E+08 RU-106 3.09E+08 0.OOE+00 3.90E+07 0.OOE+00 5.97E+08 O.OOE+00 1.48E+10 AG-11 OM 1.52E+07 1.43E+07 8.72E+06 0.OOE+00 2.74E+07 O.OOE+00 4.03E+09 TE-125M 1.48E+08 5.34E+07 1.98E+07 4.14E+07 O.OOE+00 0.OOE+00 4.37E+08 TE-127M 5.52E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 0.00E+00 1.37E+09 TE-129 1-131 1-133 CS-1 34 CS-1 36 CS-137 BA-140 CE-141 CE-144 M

3.61E+08 1.34E+08 7.69E+07 1.08E+08 1.94E+06 3.29E+06 7.1OE+09 1.67E+10 4.39E+07 1.73E+08 1.01E+10 1.35E+10 1.39E+08 1.71E+05 2.83E+05 1.89E+05 5.28E+07 2.1 BE+07 5.72E+07 5.78E+07 1.OOE+06 7.75E+09 1.16E+08 4.69E+09 8 97E+06 2.17E+04 2.83E+06 1.1 7E+08 3.14E+10 4.59E+08

-.0-E+--

0.OOE+00 0.OOE+00 o OOE+00 0.OOE+00 0.OOE+00 1.51 E+09 1.85E+08 5.77E+06 5.31 E+09 9.41 E+07 4.59E+09 5.78E+04 8.9OE+04 1.30E+07 0.OOE+O0 0.OOE+00 O.OOE1+00 2.03E+09 i A48E+07 1.78E+09 1.1 5E+05 0.OOE1+00 O.OOE+00 1.36E+09 2.13E+07 2.49E+06 2.08E+08 1.39E+07 1.92E+08 2.15E+08 5.41 E+08 1.33E+10 PR-143 6 99E+04 2.79E+04 ND-147 3.62E+04 3.94E+04 3.48E+03 O.OOE+00 1.62E+04 0.OOE+00 2.36E+03 0.OOE+00 2.31 E+04 0.OOE+00 2.30E+08 1.42E+08 154

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Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 5.7.4 Pathway Dose Factors, Ri AGE GROUP. ADULT PATHWAY: VEGETATION I

ORGAN DOSE FACTORS; m2

- mremlyear per IiCi/sec NUCLIDE ----------

BONE LIVER T.BODY.

THYROID KIDNEY LUNG GI-LLI H-3 C-14 CR-51 MN-54 FE-55 FE-59 CO-58 CO-60 NI-63 ZN-65 RB-86 SR-89 0.00E+00 2.26E+03 2.28E+08 4.55E+07 O.OOE+00 0.OOE+00 0.OOE+00 3.13E+08 2.1OE+08 1.45E+08 1.26E+08 2.97E+08 0.OOE+00 3.07E+07 0.OOE+00 1.67E+08 1.04E+10 7.21E+08 3.17E+08 1.01E+09 0.OOE+00 2.19E+08 9 98E+09 0.OOE+00 2.26E+03 4.55E+07 4.64E+04 5.97E+07 3.38E+07 1.14E+08 6.89E+07 3.69E+08 3 49E+08 4.56E+08 1.02E+08 2.86E+08 2.26E+03 2.26E+03 4.55E+07 4.55E+07 2.77E+04 1.02E+04 0.00E+00 9.31E+07 0.OOE+00 0.00E+00 0.OOE+00 O.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0 OOE+00 0.OOE+00 0.OOE+00 6.75E+08 0.OOE+00 0.0OE+00 0 OOE+00 0.OOE+00 0 OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.91 E+05 0.OOE+00 7.83E+04 0.OOE+00 1.82E+07 0.OOE+00 3.72E+08 0.OOE+00 1.92E+07 2.90E+07 3.93E+08 8.93E+07 1.42E+09 2.26E+03 2.26E+03 4.55E+07 4.55E+07 6.15E+04 1.17E+07 0.OOE+00 9.58E+08 8.08E+07 8.31E+07 8.29E+07 9.89E+08 0.00E+00 6.23E+08 0.00E+00 3.14E+09 0 00E+00 1.50E+08

_____________E___

0.00E+00 6.36E+08 0.00E+00 4.32E+07 0.OOE+00 1.60E+09 0.OOE+00 1.75E+10 0.OOE+00 2.82E+09 0.OOE+00 1.19E+09 0.OOE+00 4.81 E+08 0 OOE+00 5.57E+08 0.OOE+00 1.25E+10 0 OOE+00 3.98E+09 O.OOE+00 3.86E+08 O.OOE+00 1.17E+09 SR-90 Y-91 ZR-95 NB-95 RU-1 03 RU-106 AG-11OM TE-125M TE-127M TE-129M 1-131 1-133 CS-134 CS-1 36 CS-1 37 BA-140 CE-141 CE-144 6 05E+11 0.OOE+00 1.48E+11 5.12E+06 0.OOE+00 1.37E+05 1.17E+06 3.77E+05 2.55E+05 1.42E+05 7.92E+04 4.26E+04 4.77E+06 0.OOE+00 2.06E+06 1.93E+08 0.OOE+00 2A4E+07 1.05E+07 9.75E+06 5.79E+06 9.66E+07 3.50E+07 1.29E+07 3.49E+08 1.25E+08 4.26E+07 2.51 E+08 9.37E+07 3.97E+07 8.08E+07 1.16E+08 6.62E+07 2.09E+06 3.63E+06 1.11E+06 4.67E+09 1.11E+10 9.08E+09 4.28E+07 1.69E+08 1.22E+08 6.36E+09 8.70E+09 5.70E+09 1.29E+08 1.62E+05 8.47E+06 1.97E+05 1.33E+05 1.51E+04 3.29E+07 1.38E+07 1.77E+06 8.63E+07 1.05E+09 3.79E+10 1.98E+08 5.34E+08 6.33E+06 O.OOE+00 3.59E+09 0.OOE+00 9.41E+07 0.OOE+00 2.95E+09 0.OOE+00 5.52E+04 0.00E+00 6.20E+04 0.OOE+00 8.16E+06 0.OOE+00 0.OOE+00 o OOE+O0 1.19E+09 I1.29E+07 9.81 E+08 9.29E+04 O.OOE+O0 O.OOE+O0 1.26E+09 3.05E+07 3.26E+06 1.94E+08 1.92E+07 1.68E+08 2.66E+08 5.1 OE+08 1.IIE+10 PR-143 6.25E+04 2.51E+04 3.10E+03 0.OOE+00 1.45E+04 0.OOE+00 2.74E+08 ND-147 3.34E+04 3.85E+04 2.31E+03 0.OOE+00 2.25E+04 0.OOE+00 1.85E+08 155

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 6.0 TMI-1 GASEOUS WASTE TREATMENT SYSTEM 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System (see Figure 6 1) 6.1.1 Waste Gas System

a.

Reactor Building:

- Reactor Coolant Drain Tank (RCDT) header

b.

Auxiliary Building:

- Vent Header from

1.

Miscellaneous Waste Storage Tank (MWST)

2.

Three (3) Reactor Coolant Bleed Tanks (RCBT)

- Waste Gas Delay Tank

- Two (2) Waste Gas Compressors

- Three (3) Waste Gas Decay Tanks (WGDT)

c.

Filtration and dilution provided by the Station Ventilation System.

6.2 Operability Operability of the Gaseous Waste Treatment System is defined as the ability to remove gas from the vent header/tank gas spaces and store it under a higher pressure in the Waste Gas Decay Tanks for subsequent release.

Except for initiating the make up tank sample and waste gas venting and the recycle or disposal of compressed waste gases stored in the waste gas decay tanks, the operation of the waste gas system is entirely automatic. One waste gas compressor comes on automatically, removing gases from the vent header system as required, to maintain the pressure in the system at a maximum of about 16.4 psia.

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Offsite Dose Calculation Manual (ODCM) 23 FIGURE 6.1 Waste Gas System 81"Se..to U.-

A $W"m Sec viol ad 157

Number 661 0-PLN-4200.01 TMI - Unit 1 Radiological Controls Procedure ritle Revision No Offsite Dose Calculation Manual (ODCM) 23 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 7.1 Total Dose Calculation The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem. This control is provided in order to meet the dose limitations of 40 CFR 190.

The total dose from TMI-1 and TMI-2 (uranium fuel cycle facilities within 8 kilometers) is calculated by summing the calculated annual doses to critical organs of a real individual for liquid effluent using Section 2.1 methodology, for gaseous effluent using Section 5.2.1 and 5.2.2 methodology, and the direct radiation from the site from the environmental monitoring program's direct radiation (TLD) monitors.

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Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitoring Program Requirements 8.1.1 Controls In accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech Specs., the radiological environmental monitoring program shall be conducted as specified in Table 8.1.

8 1.2 Aopicabilitv At all times.

8.1.3 Action

a.

With the radiological environmental monitoring program not being conducted as specified in Table 8.1, prepare and submit to the Commission in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Table 8.2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a special report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of ODCM Part I Controls 2.2.1.2, 2.2.2 2 and 2.2.2.3 and ODCM Part II Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3. When more than one of the radionuclides in Table 8 2 are detected as the result of plant effluents in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2) + > 1.0 reportinglevel (1) reporting level (2)

When radionuclides other than those in Table 8.2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a member of the public is equal to or greater than the calendar year limits of ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part II, Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.

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Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23

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 unavailable may then be deleted from the monitoring program Pursuant to TMI-1 Tech. Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

8 1.4 Bases The radiological 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 from the station operation. This monitoring program implementsSection IV B.2 of Appendix I to IOCFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Guidance for this monitoring is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring (Revision 1, November 1979). Program changes may be initiated based on operational experience.

8.1.5 Surveillance Reguirements The radiological environmental monitoring samples shall be collected pursuant to Table 8.1, from the specific locations given in Tables 8.4 through 8.10 and Maps 8.1 through 8.3, and shall be analyzed pursuant to the requirements of Table 8.1 and the detection capabilities required by Table 8.3.

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Radiological Controls Procedure 6610-PLN-4200.01I Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 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 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden of greater than 50 m2 (500 ft2) producing broad leaf vegetation.

8.2.2 Applicabilitv At all times.

8.2.3 Action a

With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in ODCM Part I Surveillance 3.2.2.3.1, pursuant to ODCM, Part IV, Section 2.0, identify the new location(s) in the next Annual Radioactive Effluent Release Report.

b.

With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Table 8.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to TMI-1 Tech. Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12, submit 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 information supporting the change in sampling locations.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different sectors with the highest predicted DlQs in lieu of the garden census.

Requirements for broad leaf sampling in Table 8.1 shall be followed, including analysis of control samples.

161

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Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 8 2.4 Bases This Control is provided to ensure that changes in the use of unrestricted areas are identified and modifications to the monitoring program are made if required by the results of this census. The best information from the door-to-door survey, aerial surveys, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix 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 (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.

8.2.5 Surveillance Requirements The Land Use Census shall be conducted during the growing season at least once per 12 months, using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agricultural authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Part IV, Section 1.0.

162

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLNo 4200.01 M

teDRevision No.

Offsite Dose Calculation Manual (ODCM) 23 8.3 Interlaboratorv Comparison Proaram 8.3.1 Controls In accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission (NRC). Only those samples and analyses which are required by Table 8.1 shall be performed.

8.3.2 Applicabilitv At all times.

8.3.3 Action With analysis not being performed as required above, report the corrective action taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

8.3.4 Bases The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV, B.2 of Appendix I to 10 CFR 50.

8 3.5 Surveillance Requirements A summary of the Interlaboratory Comparison Program results shall be included in the Annual Radiological Environmental Operating Report.

163

Number TMI - Unit 1 Radioloilcal Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.1 Sample Collection and Analysis Requirements l

Number of Samples l

Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations8 Collection Frequencyb of Analysisb

1. Airborne Radioiodine and Samples from 5 locations Continuous sampler operation Radioiodine Canister:

Particulates from Table 8.4.

with sample collection weekly, Analyze weekly for 1-131.

or more frequently if required Particulate Filter:

by dust loading Analyze for gross beta radioactivity following filter changed. Perform gamma isotopic analysise on composite (by location) sample quarterly.

2. Direct Radiationc Samples from 40 locations Sample Quarterly Analyze for gamma dose from Table 8.5 (using either quarterly.

2 dosimeters or at least 1 instrument for continuously measuring and recording dose rate at each location).

164

Number 661 0-PLN-4200.01 TMI - Unit 1 Radiological Controls Procedure Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.1 Sample Collection and Analysis Requirements Number of Samples l

1 Exposure Pathway and Sampling and Type and Frequency andlor Sample Sample Locationsa Collection Frequencyb of Analysisb

3. Waterbome

a. Surface' Samples from 2 locations Composite9 sample over Perform gamma isotopic from Table 8.6.

1 monthly period.

analysis' monthly.

Composite for tritium

1 sample from analysis quarterly.

downstream (indicator) location

1 sample from upstream (control) location (or location not influenced by the station discharge)

b. Drinking Samples from 2 locations Composites sample over Perform gross beta and from Table 8.6 1 monthly period gamma isotopic analysis' monthly. Perform Sr-90

1 sample at the location analysis if gross beta of of the nearest water monthly composite >10 supply that could be times control. Composite for affected by the station tritium analysis quarterly.

discharge.

1 sample from a control location.

c. Sediment from Samples from 2 locations Sample twice per year Perform gamma isotopic Shoreline (1 Control and 1 Indicator)

(Spring and Fall) analysise on each sample.

from Table 8.7.

165

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.1 Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locationsa Collection Frequencyb of Analysisb

4. Ingestion

a. Milk

b. Fish c Food Products Samples from 4 locations from Table 8.8.

Samples from 2 locations from Table 8 9

1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators in the vicinity of the station discharge.

1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators from an area not influenced by the station discharge.

Samples from 2 locations from Table 8.10 (when available)

1 sample of green leafy vegetables or leafy vegetation at a location in the immediate vicinity of the station. (indicator)

1 sample of same species or group from a location not influenced by the station discharge.

Sample semimonthly when animals are on pasture; monthly at other times.

Sample twice per year (Spring and Fall).

Sample at time of harvest.

Perform gamma isotopic analysise and 1-131 analysis on each sample.

Composite for Sr-90 analysis quarterly.

Perform gamma isotopic6 and Sr-90 analysis on edible portions.

Perform gamma isotopice, 1-131, and Sr-90 analysis on edible portions.

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Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.1 Sample Collection and Analysis Requirements Table Notation

a.

Sampling locations are provided in Tables 8.4 through 8.10. They are depicted in Maps 8.1 through 8.3.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. All deviations from the sampling schedule shall be explained in the Annual Radiological Environmental Operating Report.

b.

Frequency notation: weekly (7 days), semimonthly (15 days), monthly (31 days), and quarterly (92 days).

All surveillance requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. A total maximum combined interval time for any 4 consecutive tests shall not exceed 3.25 times the specified collection or analysis interval.

c.

One or more instruments, such as a pressurized ion chamber for measuring and recording dose rate continuously, may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor, two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

d.

Airbome particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in an air particulate sample(s) is greater than ten times the calendar year mean of control samples, Sr-90 and gamma isotopic analysis shall be performed on the individual sample(s).

e.

Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

f.

The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream sample" shall be taken in an area beyond but near the mixing zone.

9.

Composite sample aliquots shall be collected at time intervals that are short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

167

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN_4200.01 Tide Rala anon2No Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Particulate Water or gas Fish Milk Food Products Analysis (pCUL)

(pCi/m3)

(pClkgwet)

(2CVL (pCi/kg, wet)

H-3 20,000(a)

Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Sr-90 8

0.1 100 8

100 Zr-Nb-95 400 1-131 2

0.9 3

100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300 (a) For drinking water samples. This is 40 CFR Part 141 value.

168

Number 661 O-PLN-4200.01 TMI - Unit I Radioloaical Controls Procedure Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.3 Detection Capabilities for Environmental Sample Analysis" Lower Limit of Detection (LLD)bc Airborne Particulate Fish Food Sediment Water or Gas (pCi/kg, Milk Products (pCi/kg, Analysis (pCVL)

(pCi/M3) wet)

(pCVL)

(pClkg,wet) dry)

Gross Beta 4

0.01 H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Sr-90 2

0.01 10 2

10 Nb-95 15 1-131 id 0.07 1

60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 169

Number TMI - Unit I I

Radiological Controls Procedure 6610-PLN-4200.01 fitle DReilsion No Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.3 Detection Capabilities for Environmental Sample Analysiso Table Notation

a.

This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, which may be related to plant operations, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

b.

Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13 (Rev. 1).

c.

The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD =4.66 Sb E a V

2.22. Y

exp (-XAt)

Where:

LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume.

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting.

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

It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small samples sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

d.

LLD for drinking water.

170

Number TMI - Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No

Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.4 TMINS REMP Station Locations-Air Particulate and Air Iodine Station Code B1-4 El-2 Fl-3 G2-1 M2-1 A3-1 H3-1 Q4-1 Q15-1 Distance (miles) 0.8 0.4 0.6 1.4 1.3 2.6 2.3 35 13.5 Azimuth (0)

Mar No 28 95 105 125 253 358 159 325 305 60 2

70 74 3

4 5

61 8

TABLE 8.5 TMINS REMP Station Locations-Direct Radiation (TLD)

Station Code Al -4 B1I-1 B13-2 C1-2 D1-1 El-2 E1-4 Fl -2 G1-3 HI-1 J1-1 J,1-3 K1-4 Ll-l Mi-1 Ni-3 P1-1 P1-2 Distance (miles) 0.3 0.6 0.4 0.3 0.2 0.4 0.2 0.2 0.3 05 0.8 0.3 0.2 0.1 0.1 0.1 04 0.2 Azimuth (0)

Map No 5

25 26 54 74 95 98 109 129 167 184 189 208 235 249 270 293 290 9

10 11 13 14 2

16 17 18 19 21 22 24 26 27 28 29 30 171

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.5 TMINS REMP Station Locations-Direct Radiation (TLD)

Station Code Q1-2 Ri-I C2-1 K2-1 M2-1 A3-1 H3-1 R3-1 B5-1 C5-1 E5-1 F5-1 G5-1 H5-1 J5-1 K5-1 L5-1 M5-1 N5-1 P5-1 Q5-1 R5-1 D6-1 E7-1 Q9-1 B10-1 G10-1 G15-1 J15-1 Q15-1 Distance (miles) 0.2 0.2 1.6 1.1 1.3 2.6 2.3 2.6 4.8 4.5 4.6 4.7 4.8 4.1 4.9 5.0 4.1 4.3 4.9 4.9 5.0 4.9 5.2 6.8 85 9.4 9.8 14.4 12.6 13.5 Azimuth (0)

MaD No 318 335 48 200 253 358 159 338 18 42 81 107 131 157 182 200 228 249 268 285 318 339 65 86 308 21 127 124 180 305 31 32 33 34 3

4 5

35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 6

54 7

8 172

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.6 TMINS REMP Station Locations-Surface Water Station Code J1-2 (R)

A3-2 (R)

Q9-1 (F)

Q9-1 (R)

G15-2 (F)

G15-3 (F)

F15-1 (R)

Distance (miles) 0.5 2.5 8.5 8.5 13.6 14.8 12.6 Azimuth (0) 188 355 308 308 128 124 122 Man No.

57 59 52 52 62 63 65 (R) = Raw Water (F) = Finished Water TABLE 8.7 TMINS REMP Station Locations-Aquatic Sediment Station Code Al -3 G1-1 Kl -3 J2-1 J,1-2 Distance (miles) 0.5 0.3 0.3 1.5 0.5 Azimuth (0)

Map No.

0 137 202 182 188 67 68 69 58 57 173

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.8 TMINS REMP Station Locations-Milk Station Code D2-1 E2-2 G2-1 P7-1 K1 5-3 Distance (miles) 1.1 1.1 1.4 6.7 14.5 Azimuth (0)

Mai No 65 93 125 293 205 72 73 74 77 78 TABLE 8.9 TMINS REMP Station Locations-Fish Station Code IND BKG Station Location Downstream of Station Discharge Upstream of Station Discharge 174

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 TABLE 8.10 TMINS REMP Station Locations-Food Products Station Code D1-3 El-2 Fl-I Al 5-1 B10-2 Distance (miles) 0.5 0.4 0.5 10.5 10.1 Azimuth (0)

Mar No 65 95 117 10 28 79 2

80 85 55 175

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Ttle Revision No.

Offsite Dose Calculation Manual (ODCM) 23 MAP 8.1 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN I MILE OF THE SITE 10125' 176

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 MAP 8.2 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 5 MILES OF THE SITE 75.

E

I25, 177

Number TMI - Unit I I

Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 MAP 8.3 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS GREATER THAN 5 MILES FROM THE SITE 4

348 75' A

115*

I t

H e-.

178

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 9.0 PART lIl REFERENCES

1.

EPRI NP-3840, RP 1560-3 Final Report, "Environmental Radiation Doses From Difficult-To-Measure Nuclides," January 1985

2.

"Evaluation of the Three Mile Island Nuclear Station Unit 1 to Demonstrate Conformance to the Design Objectives of 10 CFR 50, Appendix I,' Nuclear Safety Associates, May 1976

3.

TMI-1 Final Safety Analysis Report (FSAR)

4.

TMI-2 Final Safety Analysis Report (FSAR)

5.

Meteorological Information and Dose Assessment System (MIDAS)

6.

NUREG-0017, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWR," Revision 1, 1985

7.

NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for Nuclear 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 Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," Revision 1, June 1974

10.

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 50, Appendix I," Revision 1, October 1977

11.

Simplified Environmental Effluent Dosimetry System (SEEDS)

12.

TMI Recirculation Factor Memos, April 12,1988 and March 17, 1988

13.

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

14.

Title 10, Code of Federal Regulations, "Energy"

15.

TMI-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 Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977

17.

TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-73

18.

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

19.

Title 40, Code of Federal Regulations, "Protection of Environment" 179

Number 661 0-PLN-4200.01 TMI - Unit 1 Radiological Controls Procedure Title D

C M

Revision No Offsite Dose Calculation Manual (ODCM) 23

20.

Regulatory Guide 4.13, "Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications," Revision 1, July 1977

21.

Post-Defueling Monitored Storage Safety Analysis Report (PDMS SAR) 180

Number 661 0-PLN-4200.01 TMI - Unit 1 Radioloaical Controls Procedure Title Revision No Offsite Dose Calculation Manual (ODCM) 23 PART IV REPORTING REQUIREMENTS 181

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 PART IV Reporting Requirements 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted to the Commission prior to May 1 of each year.

1.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring activities for the 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 ll, Section 8.2.

1.3 The Annual Radiological Environmental Operating Reports shall include the summarized tabulated results of analysis of all radiological environmental samples and environmental radiation measurements required by Part IlIl Table 8.1 taken during the period pursuant to the locations specified in the tables and figures in this ODCM, as well as summarized and tabulated results of these analyses and measurements in a format similar to the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

1.4 The reports shall also include the following. a summary description of the radiological environments monitoring program; a map(s) of all sampling locations keyed to a table giving distances and directions from a point that is midway between the Reactor Buildings of TMI-1 and TMI-2; the results of licensee participation in the Interlaboratory Comparison Program, required by Part IlIl, Section 8.3; discussion of all deviations from the sampling schedule of Part IlIl, Table 8.1; discussion of all the required analyses in which the LLD required by Part IIl, Table 8.3 was not achievable.

A single submittal may be made for the station.

182

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NOTE A single submittal may be made for the station. The submittal should combine those sections that are common to both units at the station however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit.

2.1 Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous 12 months of operation shall be submitted prior to May 1 for TMI-1 and TMI-2.

2.2 The following information shall be included in both Radioactive Effluent Release Reports to be submitted each year:

The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Reg. Guide 1.21, Rev. 1, with data summarized on a quarterly basis following the format of Appendix B thereof.

2.3 The Radioactive Effluent Release Reports shall include the following information for each type of solid waste shipped offsite during the report period:

a container volume,

b.

total curie quantity (specify whether determined by measurement or estimate),

c.

principal radionuclides (specify whether determined by measurement or estimate),

d.

type of waste (e g., spent resin, compacted dry waste, evaporator bottoms),

e.

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

solidification agent (e.g., cement).

2.4 The Radioactive Effluent Release Reports shall include a summary of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.

2.5 The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part IlIl Section 8 2.

2.6 The Radioactive Effluent Release Reports shall include the instrumentation not returned to OPERABLE status within 30 days per ODCM Part I Controls 2.1.1b and 2.1.2b, and ODCM Part II Control 2.1.2b.

183

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Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 2.7 The Radioactive Effluent Release Report to be submitted shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmosphere stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability.

2.8 The Radioactive Effluent Release Report shall include an assessment of the radiation doses to MEMBERS OF THE PUBLIC due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with this ODCM.

2.9 The Radioactive Effluent Release Report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period, to verify compliance with the limits of 10CFR20.1301(a)(1). All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports.

2.10 The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed real individual from reactor releases and other nearby uranium fuel cycle sources including doses from primary effluent pathways and direct radiation for the previous 12 consecutive months to show conformance with 40 CFR 190 "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contributions from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

184

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revsion No Offsite Dose Calculation Manual (ODCM) 23 3.0 PART IV REFERENCES 3.1 Radiological Assessment Branch Technical Position, Revision 1, November 1979 3 2 Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-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 Environment" 3.5 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 3.6 Title 10, Code of Federal Regulations, 'Energy" 3.7

' Regulatory Guide 1.111, "Methods of Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977 3.8 Regulatory Guide 1.112, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors," Revision O-R, April 1976 3.9 Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," Revision 1, April 1977 185

Number TMI - Unit I Radiological Controls Procedure 661 0-PLN-4200.01 Title ReiinNo Offsite Dose Calculation Manual (ODCM) 23 APPENDIX A Page 1 of I Pi - Pathway Dose Rate Parameter PI (inhalation) = k' (BR) DFAi (Eq A-1)

Where:

P. =the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation pathway, in mrem/yr per microcurie/m3. The dose factors are based on the critical individual organ for the child age group.

k'= conversion factor, 1 E6 pCi/microcurie BR = 3700 m3/yr, breathing rate for child (Reg. Guide 1.109, Rev. 1, Table E-5)

DFA, = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide (mRem/pCi).

Values are taken from Table E-10, Reg. Guide 1.109 (Rev. 1), or NUREG-0172.

Resolution of the units yields: (ODCM Part III Table 4.6)

PI (inhalation) = 3.7E9 DFA (mremlyr per jPCiIm3)

(Eq A-2)

NOTE The latest NRC Guidance has deleted the requirement to determine Pi (ground plane) and Pi (food). In addition, the critical age group has been changed from infant to child.

186

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 APPENDIX B Page 1 of 1 Ri - Inhalation Pathway Dose Factor RI = k' (BR) (DFAI,.ao) (mremlyr per microcurielm3)

(Eq B-1)

Where:

k'= conversion factor, 1E6 pCilmicrocurie BR= breathing rate, 1400, 3700, 8000, 8000 m3/yr for infant, child, teenager, and adult age groups, respectively. (Reg. Guide 1.109, Rev. 1, Table E-5)

DFA,B,O = the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in mrem/pCi. The total body is considered as an organ in the selection of DFAia o.

Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Rev. 1), or NUREG 0172.

Resolutions of the units yields-RI = (1.4E9) (DFA1,,a.) infant (ODCM Part IlIl Table 5.2.1)

Ri = (3.7E9) (DFA1. 0) child (ODCM Part IlIl Table 5.2.2)

RI = (8.0E9) (DFAIao) teen and adult (ODCM Part IlIl Tables 5.2.3 and 5.2.4) 187

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 APPENDIX C Page 1 of 1 Ri - Ground Plane Pathway Dose Factor RI = k k" (SF) (DFG1) [(1-e -it)i)/.]

(Eq C-1)

Where:

k'= conversion factor, 1 E6 pCi/microcurie k" =

conversion factor, 8760 hr/yr X = decay constant for the ith radionuclide, sec 1 t = the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108 sec. (15 yrs), Reg. Guide 1.109 (Rev. 1), Appendix C DFG, = the ground plane dose conversion factor for the ith radionuclide (mrem/hr per pCi/m2). Values are taken from Table E-6, Reg. Guide 1.109 (Rev. 1), or NUREG 0172. These values ailyv to all age groups.

SF =

0.7, shielding factor, from Table E-15 Reg. Guide 1.109 (Rev. 1)

Reference ODCM Part IlIl Table 5.3.1 188

Number TMI - Unit 1 I

Radiological Controls Procedure 661 0-PLN-4200.01 TitMe Revision No.

Offsite Dose Calculation Manual (ODCM) 23 APPENDIX D Page 1 of 2 Ri - Grass Cow-Milk Pathway Dose Factor R=

k' [(QF X UAp) / (Xi + Xw)] X (Fm) x (r) x (DFLAo) x

[((fp x f.)!Yp) + ((I-fp x fQ) e -)ith)/Yy] e-'i tf (Eq D-1)

Where:

k'= conversion factor, I E6 picocurie/microcurie (pCi/lici)

QF = cow consumption rate, 50 kglday, (Reg. Guide 1.109, Rev. 1) goat consumption rate, 6 kgfday, (Reg. Guide 1.109, Rev. 1, Table E-2)

UAp = Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1)

Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kglm2 (NUREG-0133)

Y. = agricultural productivity by unit area of stored feed, 2.0 kglm2 (NUREG-0133)

Fm = stable element transfer coefficient (Table E-1, Reg. Guide 1.109, Rev. 1) r = fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0 for radioiodine (Table E-15, Reg Guide 1.109, Rev. 1)

DFL1,0,0 = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172.

Xi = decay constant for the ith radionuclide, sec-1 AW = decay constant for weathering, 5.73 x 10-7 sect (NUREG-0133); based on a 14 day half life tf = 1.73 x 105 sec, the transport time from pasture to cow to milk to receptor (Table E-1 5, Reg.

Guide 1.109, Rev. 1), or 2 days th = 7.78 x 106 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 fp = 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 while the cow is on pasture 189

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 APPENDIX D Page 2 of 2 The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, R.

is based on (X/Q).

RCtao = k'kW" Fm QF UApDFLta~o (.75 [.51H])

(Eq D-2)

Where:

k.. = 1E3 grams/kg H = 8 grams/M 3, absolute 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-01 33)

DFLio = the ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E-1 1 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172.

All other parameters and values are as given above.

NOTE Goat-milk pathway factor, RI, will be computed using the cow-milk pathway factor equation. Fm factor for goat-milk will be from Table E-2 Reg. Guide 1.109, Rev. 1.

Reference:

ODCM Part IlIl Tables 5.4.1 to 5.4.4 190

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 APPENDIX E RI - Cow-Meat Pathway Dose Factor R=

k' [(QF X UAP) I (Xi + SW)] x (Ff) x (r) x (DFL,,.,0) x

[((fp x fjlVYp) + ((I-fpf5) e -xith)/Yl] x e-i tf (Eq E-1)

Where k'= conversion factor, I E6 picocurie/microcurie (pCilpci)

QF =

cow consumption rate, 50 kg/day, (Reg. Guide 1.109, Rev. 1)

UAp = Receptor's meat consumption rate; 0,41, 65, 110 kg/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1)

Ff = 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 radioiodine (Table E-15, Reg. Guide 1.109, Rev. 1)

DFLIB O = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172.

Xi = decay constant for the radionuclide i, sec-'

X, = decay constant for weathering, 5.73 x 10-7 sec1 (NUREG-01 33), based on a 14 day half life tf =

1.73 x 106 sec, the transport time from pasture to receptor (NUREG-0133) th = 7.78 x 106 sec. the transport time from crop to receptor (NUREG-0133)

Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/rm2 (NUREG-0133)

Y, = agricultural productivity by unit area of stored feed, 2.0 kg /M2 (NUREG-0133) fp = 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 while the cow is on pasture The concentration of tritium in meat is based on the airborne concentration rather than the deposition. Therefore, RI is based on (X/Q):

Rtao = k'k-" Ff QF UAP (DFLt,.,0) x 0.75 x (0.5/H])

(Eq E-2)

Where:

All terms are as defined above and in Appendix D.

Reference. ODCM Part l1l, Tables 5.6.1 to 5.6.4 191

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 APPENDIX F RI -Vegetation Pathway Dose Factor R=

k' x [rI ('4 (Xi + X.))] x (DFLi,., 0) x [(ULA) fL eOitL + USA fg e 1ith]

(Eq F-1)

Where:

k'=

1E6 picocurie/microcurie (pCi/ici)

ULA = 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)

U SA = the consumption rate of stored vegetation, 0, 520, 630, 520 kglyr for infant, child, teenager, or adult age groups respectively (Reg. Guide 1.109, Rev. 1) fL = the fraction of the annual intake of fresh leafy vegetation grown locally, = 1.0 (NUREG-0133) fg = the fraction of the stored vegetation grown locally = 0 76 (NUREG-0133) tL = the average time between harvest of leafy vegetation and its consumption, 8.6 x 104 seconds

[Table E-15, Reg. Guide 1.109, Rev. 1 (24 hrs)]

th = the average time between harvest of stored leafy vegetation and its consumption, 5.18 x 106 seconds, [Table E-15, Reg. Guide 1.109, Rev.1 (60 days)]

y, = the vegetation area density, 2.0 kglm2 (Table E-15, Reg. Guide 1.109, Rev. 1)

All other parameters are as previously defined The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition.

Therefore, RI is based on (X/Q)

Rta,o = k'k"' [ULA fL + USA fg] (DFLt,.,O) (.75 [.5/H])

(Eq F-2)

Where:

All terms are as defined above and in Appendix D.

Reference:

ODCM Part l1l, Tables 5.7.1 to 5.7.4 192

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Tite Revision No.

Offsite Dose Calculation Manual (ODCM) 23 APPENDIX A-F REFERENCES (Page 1 of 4)

Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G. 1.109 NUREG-0133 Specific For Pi DFA1 Each radionuclide E-9 Note 1 BR 3700 m3/yr (child)

E-5

- - For Ri (Vegetation)***

r Each element type E-1 Y'

2.0 kg/m2 E-15 xw 5.73 E-7 sec' 5.3.1.3 DFLI Each age group and radionuclide E-1 1 thru E-14 Note 1 UaL Each age group E-5 fL 1.0 5.3.1.5 t,

8.6 E + 4 seconds E-15 UaS Each age group E-5 f9 0.76 5 3.1.5 tI 5.18 E + 6 seconds E-15 H

8.0 grams/kg 5.2.1.3

'For Ri (inhalation)*

BR Each age group E-5 Each age group and nuclide E-7 thru E-10 Note 1 193

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No Offsite Dose Calculation Manual (ODCM) 23 APPENDIX A-F REFERENCES (Page 2 of 4)

Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G. 1.109 NUREG-0133 Specific For RI (Ground Plane)

SF 0.7 E-1 5 DFG1 Each radionuclide E-6 t

4.73 E + 8 sec 5.3.1.2 l

For Ri (GrasslAnimal/Meat) ***_11 QF(COW) 50 kg/day E-3 QF (Goat) 6 kg/day E-3 Ref. Only U

ap Each age group E-5 l

5.73 E-7 sec1 5.3.1.3 Ff (Both)

Each element E-1 r

Each element type E-15 DFLI Each age group and nuclide E-11 thru E-14 Note 1 fp 1.0 5.3.1.3 Note 2

f.

1.0 5.3.1.3 Note 2 YP 0.7 kg/mr3 E-1 5 th 7.78 E + 6 sec E-15 Y.

2.0 kg/M 2 E-1 5 tf 1.73 E + 6 sec E-1 H

8.0 grams/kg 5.2.1.3 194

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 APPENDIX A-F REFERENCES (Page 3 of 4)

Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G. 1.109 NUREG-0133 Specific For RI (Grass/CowlMilk)

Qf 50 kg/day E-3 Uap Each age group E-5 kw5.73 E-7 sec1 5.3.1.3 Fm Each element E-1 r

Each element type E-15

DFL, Each age group and nuclide E-11 thru E-14 Note I Yp 0.7 kg/m2 E-1 5 th 7.78 E + 6 sec E-15 2.0 kglm2 E-1 5 tf 1.73 E + 5 sec E-15 fp 1.0 5.3.1.3 fs 1.0 5.3.1.3 H

8.0 gramsfkg 5.2.1.3 195

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 23 APPENDIX A-F REFERENCES (Page 4 of 4)

NOTES

1.

Inhalation and ingestion dose factors were taken from the indicated source. For each age group, for each nuclide, the organ dose factor used was the highest dose factor for that nuclide and age group in the referenced table.

2 Typically beef cattle are raised all year on pasture. Annual land surveys have indicated that the small number of goats raised within 5 miles typically are used for grass control and not food or milk. Nevertheless, the goats can be treated as full meat sources where present, despite the fact that their numbers cannot sustain the meat consumption rates of Table E-5, NUREG-0133.

REFERENCES

1.

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

2 TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50

3.

NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978.

196 2002 Annual Radioactive Effluent Releases Report for TMI 5928-03-20051 Procedure Change Request PC-10903 to the ODCM, 6610-PLN-4200.01

i AD-TM-101 Rev 1 Page 26 of 52 ATTACHMENT 3 Document Approval Form Document Number:.

4/-

/LA~ -4' ao o/

C Batch E Cancel El Editorial 0 New EReAWshin 0 Supesede Revision Summary:

4h4 I

Attach addttlonal descriplion If required Z2..

Current Revision:

f

-. r-0 r-I --

UI3IJ lAnue 0 Interim Chanoe Document Tracking #:/Oe -/o o 2 4-t~

a e'i Level of Use:

5 Level EP - Event Procedure Use

[3 Level M - Multiple Use EJ T&RM El Level 1 Continuous Use E Level 2-ReferenceUse USQ

.evel 3 - Information Use 7Arr

,DP-Lq4,, r a ~,

/-25Ot.

Z°oe /wZ-,rO

' Appr. Location: Three Mile Island Supersed Validation Required: 0 No El Yes (EP Level of Use procedures oD)

PrnUSSign Change Management: El Change Cheddist hi Not RequTred ed Document(s):

Rev Training Required: 5No ElYes RTR El NIA L Cross Disciplin b.c. 5 PO9QIN -

.ist Required Reviews/Disciplines: -PtivS J?(1 iary Reviews:

U print 8g~r nIL (Z)tO/h2.Vw5 P - 16 0 ?--

We

z-I -(9'Z Date Disopine Oisdpinbe Date RTR Approval Date I

Print Sgn Procedure is lechnically and functionally accurate.

0 El Exempt, per IOCFR 50.59 Required:,6 No El Yes (or euivaTent Reg. Review) 5.59 Tracking Number PORC Required4 No El Yes

- ~~Oqzc ve-ACUA...-A4 IProofreadlDate WPTIDate:

Prc. Clerk/ DateI

50.59 REVIEW COVERSHEET FORM LS-AA-104-1001 01/1]101 Station: Three Mile Bland ActivitytDocumentNumber: 6610-PLN-4200.01 Page I of 1_

Revision Number: 22

Title:

OfFsite Dose Calculation Manual (ODCM)

Description of Activity Correct the Table of Contents, add specificationto noble gas radionuclides to determine LLD values, convert pen numbers into point numbers and add clarification when 30 day clock applies to Unit 2 ventilationflow rate measurements.

Reason for Activity:

Add detail and correct for minor errors in the ODCM.

Effect of Activity:

Improve understanding when the 30 day clock applies and what LLD values are needed for noble gas in liquids. Correct some minor errors.

Summary of Conclusion for the Activities 50.59 Review:

The changes of the Offsite Dose Calculation Manual are controlled under Technical Specifications. The applicable section of Unit 1 Technical Specificationis section 6.14 and the applicable sectioninUnit 2 Technical Specifications is 6.12. Since this is aprogram controlled by the Technical Specifications then 50.59 screening is not required.

Attachments:

Attach completed Applicability Review if 50.59 Screening is not required Attach completed 50.59 Screening if 50.59 Evaluation is not required Attach completed 50.59 Evaluation if required to be performed.

Attach completed 50.59 Screening and 50.59 Evaluation ifmultiple discrete elements of an activity have been linked together and certain elements required a 5 0.59 Evaluation while other elements did not Forms Attached: (Check all that apply.)

i Applicability Review 50.59 Screening 50.59 Evaluation 50.59 Validation 50.59 Screening No.

50.59 Evaluation No.

50.59 Validation No.

Rev.

AG0516 (01/01)

l 50.59 APPLICABILITY REVIEW FORM LS-AA-104-1002 01ll1101 Page I of _t_

Activity/locument Number:

6610-PLN-4200.0

-Revision Number:

22 Address the questions belowfor all aspects of the Activity. Ifthe answeris yes for anyportion of the Activity, apply the identified process(es) to that portion of the Activity. Note that it is not unusual to have more than one process apply to a given Aclivity.

See Section 4 of the Resource Manual (PM) for additional guidance.

I.

Does the proposed Activity involve a change:

1. Technical Specifications or Operating License (10CPR50.90)?

XNO _ YES SeeSection4.2.1.1 oftheRM

2.

Conditions of License Quality Assurance program (10CFR50.54(a))?

_XNO _ YES Security Plan (10CFR50.54(p))?

X NO _ YES See Section 4.2.1.2 of the PM Emergency Plan (10CFR50.54(q))?

X NO _ YES

3.

Codes and Standards IST Program Plan (IOCFR50.55a(f))?

X_ NO

_ YSSee Section 4.2.1.3 of the RM ISI Program Plan (10CFR50.55a(g))?

_XNO YES

4. ECCS Acceptance Criteria (10CFR50.46)?

_XNO __YES See Section 4.2.1.4 of the RM S. Specific Exemptions (10CFR50.12)?

_X NO

_ YES See Section 4.2.1.5 of the RM

6. RadiationProtection Program (10CFR20)?

XNO __YES See Section 4.2.1.6 ofthe RM

7. Fire Protection Program (applicable IFSAR or operating license X NO YES See Section 4.2.1.7 of the RM condition)?

8. Programs controlled by the OperatingLicense or the Technical NO XYES SeeSection4.2.17oftheRM Specifications (such as the ODCM). Y

9. Environmental Protection Program X NO __YES See Section 4.2.1.7 of the RM

10. Other programs contrnlled by other regulations.

_XNO __YES See Section 4.2.1 of the RM

11. Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting XNO _YES See Section 4.2.2 of the RM maintenance that will be in effect during at-power operations for 90 days or less?

IIL Does the proposed Activity involve a change to the:

1. UFSAR (including documents incorporated by reference) that is excluded from the requirement to perform a 50.59 Reviewby XNO __YES See Section 4.23 ofthe RM NEI 96-07 orNEI 98-037

2. Managerial oradministrative procedures governing the conduct of facility operations (subject to the control of 10CFR50, Appendix B)

NO _X YES See Section 4.2.4 of the M 3

Regulatory comnmitmentnotcoveredbyanotherregulationbased

_XNO

_ YES See Section 4.2.3/4.2.4 of the RM change process (see NEI 99-04)?

IV. Does the proposed Activity involve a change to the Independent Spent XNO YES Se Section 4.2.6 of theRM Fuel Storage Installation (ISFSI) (subject to control by 10 CFR 72.48)

X NO

_ YES See Setion 4.2._of the R Check one of the following:

9I1f all aspects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening is not required and the Activity may be implemented in accordanc with its governingprocedure.

0 If any Portion of the Activity is not controlled by one or more of the above processes, then process a 50.59 Screening for the portion not covered by any of the above processes. The remaining portion of the activity should be implemented in accordance with its governing procedure.

Signoff:

50.59 Screenerl50.59 Evaluator.

Pienf't

&vz_

(Circle One)

(Print nme)

Sign:

/9

)

X;-

Date: /

1 '/IA1 L (Signats)

AG0517 (01/01)

PC-10903 change to 6610-PLN-4200.01 Rev 22, Offsite Dose Calculation Manual (ODCM)

Description of Changes:

Correct Table of Contents In reference to page numbers.

Page 50, added note g to noble gas gamma emitters Page 52, added note g which states that the noble gas gamma emitters include Kr-87, Kr-88, Sx-133, Xe-1 33m, and Xe-1 35.

Page 67 Change Pen 6 to Point #6 and change Pen #1 to Point #1. Added explanation when 30 day clock applies.

Reason for Changes:

Table of Contents did not have the proper page numbers for many of the sections. - Current revision is incorrect - typographical error correction.

Note g added to make clear the LLD needed to meet the need to determine noble gas in the liquid effluent. - Currently no guidance exists to the standard RETS LLD is specified. The current LLDs in the ODCM are based on NuReg 0133 which states,'...the principal radionuclides contributing to the dose must be Identifled." As the noble gasses in liquid effluents are not contributors to dose, (Regulatory Guide 1.109, Revi), the LLD values for noble gasses in liquids gives radionuclides to use for determination of noble gas LLD and thereby ensuring the standard is met.

To make clear when the requirement forthe 30-day clock on ventilation flow rate data Is required.

The Unit 2 effluent ventilation flow rate is out of service, the individual flows that make up that flow rate (Auxiliary, Fuel Handling, and Reactor Building) may be measured and added together to get the Station Ventilation Unit flow rate or Containment purge monitoring system. This meets the requirements for ventilation flow. When any ventilation flow needs to be estimated then the 30-day clock applies.

Pen I and Pen 6 was changed to Point 1 and Point 6 because the recorderwas changed to a digital recorder and pens are not used. Points have been substituted.

Accuracy Statement:

There Is no change In calculation methodology, inputs to calculations, or formulas used in determining off site dose. These changes will not affect dose calculations. There is no change to the control of effluent dose. There is no effect to changing alarm setpoints.

The ODCM maintains the level of radioactive effluent control required by ICOCFR20.1301, 40 CFR Part 190, 1 OCFR50.36a, and Appendix I to 1 OCFR50 and not adversely impact the accuracy or reliability of effluent, dose or setpolnt calculations.

Review requirements:, Document Approval Form documents all approval signatures for this change.

1-3_

Number TMI - Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Wte eIson No.

Oste Dose Calculation Manual (ODCM) 22 TABLE OF CONTENTS (Cont'd)

EFFLUENT DATA AND CALCULAllONAL METHODOLOGIES PART III Section 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents - Instantaneous Release Limits 5.1.1 Noble Gases 5.1.1.1 Total Body f;.1.1.2 Skin 5.1.2 lodinos and Particulates 5.2 Gaseous Effluents -10 CFR.50Appendix I 5.2.1 Noble Gases 5.22 lodines and Partculates 5.3 Gaseous Radioactive System Dose Calculations Once per Month 5.4 Alternative Dose Calculational Methodologies 6.0 GASEOUS EFFLUENTWASTE TREATMENT SYSTEM 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System 6.2 Operability of the TMI-1 Gaseous Radwaste Treatment System 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitoring Program Requirements 8.2 Land Use Census 8.3 Interlaboratory Comparison Program 9.0 PART Ill REFERENCES 1a3 12 c 2' 13rr(, I3 1.58I i82'- I.

9

6610-PLN-4200.01 Revision 22 Table 3.2-1 Radioactive Liquid Waste Sampling and Analysis Program Lower Limit of Sampling Minimum Analysis Type of Activity : Detection (LLD)

Liquid Release Type Frequency Frequency Analysis i(Clml) (Note a)

A.1 Batch Waste Release Tanks (tIote d)

P a

P H-3 a

1XIO4 Each Batch Each Batch Principal Gamma '

6 x lo-"

Emitters (Notef)

-13 X lo, I

I a

a ssoaedand 1xIO Entrained Gases (Gamma Ernmltters I

t P

Q Gross alpha i x 10-7 Esch Bate"

Composite (Note b) a a

Sr-89, Sr-90 5 x104

Fe*

1 x1loa A.2 Continuous Releases (Note e)

Continuous W

Principal Gamma 0 5 x iW (Note c)

Composite

Emitters (Note t1 (Note c) a a

I

' Dissolved and I x10

a *

EntrainedGases I

'(Gamma EmItterst11 &rS4 Continuous TM 1H 3 I

ox1a (Notec)

, Composite

(Notc)

Grossalpha

1x10 Continuous

4 Sr-89,Sr-S0

5x10 (Notec)

Composite j

(Note c) 1 x t 50

Number TMI - Unit 1 I

Radiological Controls Procedure 6610-PLN4200.01 TM Revsion No.

Offsite Dlose Calculation Manual (ODCM) 22 Table 3.2-1

d.

A batch release Is the discharge of liquid wastes of a discrete volume.. Prior to sampling for analyses, each batch shall be Isolated, and be thoroughly mixed, by a mothod described in the ODCM, to assure representative sampling.

e.

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

f.

The principal gamma emitters for which the LlD specification applies exclugiveli are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Gs-137, Ce-141, and Ce-144, This list does not mean thatonly these nucildes are to be considered. Other gamma peaks that are identifiable, togetherwIth those of the above nucl[dps, shall also be analyzed and repiorted In the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4.

g.

tet

^

B e."fS>

,.*.u f.c

i'g J1.oe<p~4

/

x~~8/

At lJ)'t; kr.vwctjt 47 Ar,-Fe., Yc -132 xe'2>

"~

-3 if e-4.I vOcr 4 IF 4 e-ceZ ;6.

1

/

e,,-

t 4 c,co. z,>

Aetcla-7CZJf J

?-4 52

6610-PLN-4.

Revision 22 Table 21-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS INSTRUMENT

1.

Containment Purge Monitoring System

a.

Noble Gas Activity Monitor (2HP-R-225)

b.

Particulate Monitor (2HP-R-225)

c.

Effluent System Flow Rate Measuring Device (2AH-FR-5907Pen 1)

2.

Station Ventilation System

a.

Noble Gas Activity Monitor (2HP.-R-219) or (2HP-R-219A)

b.

Particulate Monitor (2HP-R-219) or (2HP-R-219A)

c.

Effluent System Flow Rate Monitoring Device (2AH-FR-5907 Rea 6)

OPERABLE I

I 1

I

1 12 APPLICABILITY NOTE 1 NOTE I NOTE I NOTE I NOTE 1 NOTE 1 ACTION NOTE 2 NOTE 2 NOTE 3 NOTE 2 NOTE 2 NOTE 3 NOTES:

1.

During operation of the monitored system.

2.

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, secure Reactor Building Purge If In progress.

3.

With flow rate monitoring Instrumentation out of service, flow rates from the Auxiliary, Fuel Handling. and Reactor Buildings may be summed individuallyer-e i 1 e " n i

d i

.ff t h o u

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