Revision as of 16:07, 6 November 2019

Text

Offsite Dose Calculation Manual.
	ML18130A392
Person / Time
Site:	Surry
Issue date:	05/04/1983
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18130A393	List: ML18130A392; ML18139C330; ML18139C331;
References
	HP-ODCM-01, HP-ODCM-1, NUDOCS 8307140264
	Download: ML18130A392 (167)
	v • d • e

HP-ODCM Page 1 of 3

VIRGINIA ELECTRIC AND POWER COMPANY I

SURRY POWER STATION I

!

. I OFFSITE DOSE CALCULATION MANUAL UNITS 1 AND 2

Recommend Approval:

Approved By:

Date:

HP-ODCM Page 2 of 3 SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL

REFERENCES:

1. Surry Power Station Technical Specifications.

2. 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," Rev. 1, U.S. Nuclear Regulatory Commission, October 1977.

3. Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water -

Cooled Reactors," Rev. 1, U.S. Nuclear Regulatory Commission, July 1977.

4. U.S. Nuclear Regul~tory Commission, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133, October 1978.

5.

U.S. Nuclear Regulatory Commission, "XOQDOQ, Program for the Meteorologi-cal Evaluation of Routine Effluent Releases at Nuclear Power Stations,"

NUREG-0324, September 1977.

6. U.S. Nuclear Regulatory Commission, "User's Guide to GASPAR Code,"

NUREG-0597, June 1980.

7. Surry Power Station Radioactive Release Reports for 1976, 1977, 1978, 1979, 1980, and 1981.

8. Virginia Electric and Power Company, Surry Power Station, Units 1 and 2, Updated Final Safety Analysis Report.

IMPLEMENTATION:

The provisions in the Surry Offsite Dose Calculation Manual will be implemented upon approval of the Surry Power Station Radiological Effluent Technical Specifications by the NRC.

I'

HP-ODCM Page 3 of 3

SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL INDEX Section No. Date

1. Introduction

2. Liquid Effluent Radiation Monitor Setpoints

3. Liquid Effluent Concentration Limit

4. Liquid Effluent Dose Limits

5. Liquid Effluent Dose Projection

6. Gaseous Effluent Radiation Monitor Setpoints

7. Gaseous Effluent Release Rates

- 8.

9.

10.

Noble Gas Effluent Air Dose Limits Iodine - 131, Tritium, and Radionuclid.es in Particulate Form Gaseous Effluent Dose*iimits Gaseous Effluent Dose Projection

11. Total Dose

12. Semiannual Radioactive Effluent Release Report

13. Radiological Environmental }ionitoring Locations Appendix *A Appendix B

HP-ODCM-1 Page 1 of 3

SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 1 Introduction Part Subject 1 Purpose 2 2 Scope 2

HP-ODCM-1 Page 2 of 3

1. PURPOSE The Offsite Dose Calculation Manual (ODCM) provides the methodology and

.~parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents to assure compliance with the dose limitations of the Radiological Effluent Technical Specifications.

These dose limitations assure that:

1) the concentration of radioactive liquid effluents to the unrestricted area will be limited to the concentration levels of 10CFR20, Appendix B, Table II;

2) the exposure to the maximum exposed member of the public in the unrestricted area from radioactive liquid effluents will not result in doses greater than the liquid dose limits of 10CFRSO, Appendix I;

3) the dose rate at and beyond the site boundary from radioactive gaseous effluents wi 11 be limited to the annual dose limits of 10CFR20;

4) the exposure to the maximum exposed member of the public in the unrestricted area from radioactive gaseous effluents will not result in doses greater than the gaseous dose limits of 10CFRSO, Appendix I; and

5) the exposure to the maximum exposed member of the public will not exceed 40CFR190 dose limits.

The Manual provides the methodology and parameters to be used in the assessment of the radiation doses due to. the radioactive liquid and gaseous effluents released from the station. Examples are provided to demonstrate methodology, and do not necessarily reflect procedure calculations.

The Manual provides the methodology and parameters to be used in the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints to ensure compliance with the concentration and dose rate limitations of the Radiological Effluent Technical Specifications. The Manual provides simplified drawings of the radioactive liquid and gaseous effluent waste streams.

The Manual gives the specific locations for collecting radiological environmental monitoring samples.

2. SCOPE The methodology used to assure compliance with the dose, dose rate, and concentration limitations described above shall be used tq, prepare the radioactive liquid and gaseous effluent procedures and reports required by the Technical Specifications. This .manual does not include the procedures and forms required to document compliance with the surveillance requirements in the Technical Specifications.

,.

HP-ODCM-1 Page 3 of 3 Changes to this manual shall be reviewed and approved by the Station Nuclear Safety and Operating Committee prior to implementation. Changes to this manual shall be submitted to the Nuclear Regulatory Commission by

. ,inclusion in the Semi-Annual Radioactive Release Report for the period during which the change was made effective *

,

HP-ODCM-2 Page 1 of 5

.. SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 2 Liquid Effluent Radiation Monitor Setpoints Part Subject 1 Technical Specification Requirement 2 2 Applicable Monitors 2 3 Setpoint Calculation 2

4 Example 3

HP-ODCM-'2 Page 2 of 5

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3. 7. E requires that: "The radioactive liquid

_.and *gaseous effluent monitoring instrumentation channels shown i~ Table

3. 7-5 (a) and Table 3. 7-5 (b) shall be operable with their alarm/trip setpoints set to ensure that the limits of Specifications 3.11.A.1 and 3 .11. B. l are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the Offsite Dose Calculation Manual".

2. APPLICABLE MONITORS Radioactive liquid effluent monitors for which alarm/trip setpoints are determined in accordance with this Manual are:

Radiation Monitor Plant Release Point Instrument Number*

Liquid Radwaste Effluent Line LW-108 Component Cooling Service Water System Effluent Line SW-107 Circulating Water Discharge Line SW-120, SW-220 Monitor locations on the liquid effluent waste stream are shown in Figure 2.0.

3. SETPOINT CALCULATION 3.1 Maximum setpoint values shall be calculated using the following equation:

CF C =-

f where:

c = the setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution; C= the effluent concentration limit for this monitor used in implementing 10CFR20 for the site, in uCi/ml; ...

f = the flow setpoint as measured at the radiation monitor location, GPM; F = the dilution water flow calculated as:

'

F = f + (200,000 GPM x No. of Circ. Pumps in Service).

HP-ODCM-2 Page 3 of 5 3.2 Each of the condenser circulating water channels (SW-120, SW-220) monitors the effluent (service water including component cooling service water, circulating water, and liquid radwaste) in the circulating water discharge tunnel beyond the last point of possible radioactive material addition. No dilution is assumed for this pathway. Therefore, the equation in 3 .1 above becomes:

C = C The setpoint becomes the effluent concentration limit for these monitors used in implementing 10CFR20 for the site.

3.3 In addition, for added conservatism, setpoints are calculated for the liquid radwaste effluent line (LW-108) and the component cooling service water system effluent line (SW-107).

For the liquid radwaste effluent line (LW-108), the equation in 3.1 be*comes:

C = c~w f

where; The fraction of the effluent concentration limit used in implementing 10CFR20 for the site attributable to liquid radwaste effluent line pathway.

For the component cooling service water system effluent line (SW-107), the equation in 3.1 becomes:

CFK C = CC f

where; K = The fraction of the effluent concentration limit used in cc implementing 10CFR20 for the site attributable to the component cooling service water effluent line pathway.

<

The sum ~W +Kee= 1.0.

4. EXAMPLE 4.1 The following information is obtained from an isotopic analysis of the effluent from the liquid radwaste effluent:

Radionuclide Average Undiluted Concentration Released Released (uCi/m1)

Co-60 3.09E-06 Cs-137 4.0SE-06 Cs-134 2.65E-06 Co-58 3.19E-06 Fe-59 1.78E-06

HP-ODCM-2 Page 4 of 5

4. 2 The following information is obtained from an isotopic analysis of the effluent from the component cooling service water system:

- 4 Radionuclide Average Undiluted Concentration Released Released (uCi/ml)

Co-60 5.67E-08 Cs-137 6.73E-08 Co-58 5.30E-08 4.3 Calculate, 1), and K , the fraction of the effluent limit for the liquid radwasfe and c~'inponent cooling service water pathways.

Liquid Waste:

Radionuclide uCi/mli Released MPC MPCi Co-60 3E-05 1.03E-01 Cs-137 2E-05 2.04E-01 Cs-134 9E-06 2.94E-01 Co-58 9E-05 3.54E-02 Fe-59 SE-05 3.56E-02 r uCi/mli = 6.72E-01 i MPC.1 Component Cooling Service Water:

Radionuclide uCi/mli Released MPC MPCi.

Co-60 3E-05 1.89E-03 Cs-137 2E-05 3.37E-03 Co-58 9E-05 5. 89E.-04 l: uCi/mli

= 5.85E-03

-i MPC i

Calculate the fraction of maximum. allowable concentration (FMAC) using the following equation: .

f E uCi/mli.

FMAC c: - X i MPC

F i

The flow rate for the liquid radwaste pathway is 50 GPM and 18,000 GPM for the component cooling service water pat~way. Three circulating water pumps are available.

FMAC for liquid waste:

50

'.FMAC s [ 50 + (200,000 x 3) ] x 6

72 E-Ol FMAC = 5.60E-05

HP-ODCM-2 Page 5 of 5

FMAC for component cooling service water:

18,000 FMAC = [ 18,000 + (200,000 x 3) ]

FMAC = 1.7E-04 X S.BSE-0 3 K._W = 5.6E-05

-L 5.6E-05 + 1.7E-04 = 0

25 K

cc = 0.75 4.4 The liquid radwaste monitor (LW-108) is calibrated for Cs-137, therefore:

C (uCi/ml) = r uCi/mli x MPCCs-l 37 i MPC.

1 C = 6.72E-01 x 2E-05 C = 1.34E-05 4 .5 The liquid radwaste monitor (LW-108) setpoint would be calculated

as:

c = 1.34E-05 X [

c = 4.02E-02 uCi/ml 50 + (200,000 50 X 3) ] X 0.25 4.6 The component cooling service water monitor (SW-107) is calibrated for Cs-137, therefore:

C (uCi/ml) = t uCi/mli x MPCC _ 137 i MPCi s C = 5.85E-03 x 2E-05 = l.17E-07 4.7

The component cooling service water monitor (SW-107) setpoint would be calculated as:

c = 1.17E-07 X [ 18,000 + (200,000 X 3) ] X 0. 75 18,000 c = 3.0lE-06 uCi/ml 4.8 The setpdints may be multiplied by the appropriate monitor conversion factor to determine the setpoints in CPM.. (counts per minute).

i S,ys t e11 Vent an d Dran Laboratory Draine High Level L

Ion Exchange Variou1 Fluih Line* . Waste Tanks Low Level . Filtration - Te1t -

.

Waste Tanks Tank1 System Spent Resin Flueh Drains .

.

'

tawdry Waste I

-- I Contaminated . -

Peroonnel Decontamination Area I 1Drain Tanks

',.

I I

I i

,,

Boron Recoftry System I ouron I !Boron Recovery I

. ,. 1 Evaporator I

~

1 Test Tanke I

.

'

LV-108 f)

..

.

Condensate Polishing Chemical Waste Service Water -

0

. ~

SV-107 SV-120,

~ Radiation Monitor '~ !20 "j

Dhcharge I Tunnel SURRY LIQUID EFFLUENT SYSTEM

HP-ODCM-3 Pagel of 3 SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 3 Liquid Effluent Concentration Limit Part Subject Page l Technical Specification Requirement 2 2 Calculation 2 3 Example 2

HP-ODCM-3 Page 2 of 3

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.A.l.a. requires that: "The concentration of

_.radioactive materials released in liquid waste effluents to unrestricted areas (see Figure 5.1-1) shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolv1;_9+ or entrained noble gases, the concentration shall be limited to 2 x 10 microcuries/ml".

2. CALCULATION 2.1 The daily concentrations of radioactive materials in liquid waste to unrestricted areas must meet the following:

Volume of Waste Discharged+ Volume of Dilution Water>

1 Volume of Waste Discharged x I uCi/mli -

i MPCi where:

uCi/mli = the concentration of nuclide i in the liquid effluent discharge;

= the maximum permissible concentration in unrestricted areas of nuclide, i, expressed as uCi/ml from 10CFR Part 20, Appendix B, Table II, for *radionuclides other than noble gases and 2E-04 uCi/ml for dissolved or entrained noble gases.

3. EXAMPLE 3.1 Compilation of data from liquid effluent release records for a day indicated the following radionuclides and concentrations were released from the liquid radwaste effluent line.

Radionuclide Concentration (uCi/ml) MPC uCi/ml/MPC Co-60 4.00E-06 3E-05 1.33E-01 Cs-137 3.00E-06 2E-05 1.SOE-01 Cs-134 1.00E-06 9E-06 1.llE-01 Co-58 4.50E-06 9E-05 5.00E-02 I-131 5.00E-08 3E-07 1.67E-01 I uCi/ml i *MPC 1

..

6. llE-01 i

Volume of Dilution Water for day= 1.71E+07 gal.

Volume of Waste Discharged for day= 2.88E+05 gal.

HP-ODCM-3 Page 3 of 3 3.2 The daily concentration must meet the following:

Volume of Waste Discharged+ Volume of Dilution Water>

Volume of Waste Discharged x E uCi/ml 1 1

i MPCi 2.88E+05 + 1.71E+07 > l 2.88E+05 x 6.llE-01 98.8 > 1

,

HP-ODCM-4 Page 1 of 6 SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 4 Liquid Effluent Dose Limit Part Subject 1 Technical Specification Requirement 2 2 Calculation 2 3 Example 3 4 Quarterly Composite Analyses 4

HP-ODCM-4 Page 2 of 6

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3 .11.A. 2. a requires that: "The dose or dose

.,commitment to the maximum exposed member of the public from radioactive materials in liquid effluents released, from each reactor unit, to unrestricted areas shall be limited:

(i) During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to critical organ, and, (ii) During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to critical organ.

2. CALCULATIONS 2.1 Dose contribution shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas based on the following expressions:

D = t FM r C. Ai i 1 where:

D = the cumulative dose commitment to the total body or critical organ, from the liquid effluents for the time period t, in mrem;

t = the length of the time period over which C. and F are averaged l.

for all liquid releases, hours; M = the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless, 0.2 from Appendix llA, Surry UFSAR; F*= the near field average dilution factor for Ci during any liquid effluent release. Defined as the ratio of the average undiluted liquid waste flow during release to the average flow from the site discharge structure to unrestricted areas; Ci= the average concentration of radionuclide, i, in undiluted liquid effluent during time period, t, from any liquid releases, in uCi/ml;.

Ai= the site related ingestion dose commitment factor to the total body. or critical organ of an adult for each identified principal gamma and beta emmitter listed in Table 4 .O, in mrem-ml per hr-uCi; **

where:

,

1.14E+OS ~ 1E+06 pCi/uCi x 1E+03 ml/kg~ 8760 hr/yr, units con-version factor;

HP-ODCM-4 Page 3 of 6

21 = adult fish consumption, Kg/yr, from NUREG-0133; 5 = adult invertebrate consumption, Kg/yr, from NUREG-0133; Bli = the bioaccumulat:ion factor for nuclide, i, in inverte-brates, pCi/kg per pCi/1, from Table A-1 of Regulatory Guide 1.109, Rev. 1;

= the bioaccumulation factor for nuclide, i, in fish, pCi/kg perr pCi/1, from Table A-1 of Regulatory Guide 1.109, Rev.

1.

= the critical organ dose conversion factor for nuclide, i, for adults, in mrem/pCi, from Table E-11 of Regulatory Guide 1.109, Rev. 1.

Thyroid and GI-LLI organ doses must be calculated to determine which i~ the critical organ for the period being considered. The pathway analysis used to determine the critical organ is presented in HP-0DCM-A2.

3. EXAMPLE 3.1 Compilation of data from release records for a 31 day period provides the following information:

Total Volume of Undiluted Liquid Effluent R~leased = 4.86E+10 ml Total Volume of Dilution Water Used During Period = 2.26E+14 ml Average Concentration of Radionuclides in Undiluted Liquid Effluent Cs-134 5.64E-06 uCi/ml Co-58 2.22E-06 uCi/ml Cs-137 8.35E-06 uCi/ml Co-60 1. 65E-06 uCi/ml I-131 5.66E-06 uCi/ml H-3 8.07E-04 uCi/ml 3.2 31 Day Total Body Calculation:

D = t FM I: C. Ai i l.

Obtain total body Ai values from Table. 4 .0 t = 744 hours0.00861 days 0.207 hours 0.00123 weeks 2.83092e-4 months .

Ci (uCi/ml) A (mrem-ml) (mrem)

Nuclide X i uCi-hr = hr Cs..-134 5.46E-06 X 1.33E+04 = 7.26E-02 Cs-137 8.35E-06 X 7.85E+03 = 6.SSE-02 1-131 5.66E-06 X 1.79E+02 = l .01E-'D3 Co-58 2.22E-06 X 1.35E+03 = 3.00E-03 Co-60 1.65E-06 X 3.82E+03 = 6.30E-03 H-3 8.07E-04 X 2.82E-01 11: 2.28E-04

, I: Ci Ai = l.49E-Ol i

HP-ODCM-4 Page 4 of 6 F = 4.86E+l0 (ml)

2. 26E+ 14 (ml)

Therefore, D - 744(h) 4.86E+10 (ml) 0 2 x l.49E-01 (mhrerm)

- r x 2.26E+14 (ml) x

D = 4.77E-03 mrem to Total Body.

3.3 31 Day Thyroid Calculation:

D = t FM IC. Ai i l.

Obtain Thyroid A. values from Table 4.0.

l.

t = 744 hours0.00861 days 0.207 hours 0.00123 weeks 2.83092e-4 months .

Ci (uCi/ml) A (mrem-ml) (~)

Nuclide X i uCi-hr = hr Cs-134 5.46E-06 X 0 = 0

Cs-137 8.35E-06 X 0 = 0 I-131 5.66E-06 X 1.02E+05 = 5.77E-01 Co-58 2.22E-06 X 0 = 0 Co-60 1.65E-06 X 0 - 0 H-3 8.07E-04 X 2.82E-01 = 2.28E-04 r Ci Ai = 5. 77E-01 i

F = 4.86E+l0 (ml) 2.26E+l4 (ml)

Therefore, 4.86E+10 (ml) E (mrem)

D = 744 (h)

~ x 2.26E+14 (ml) x 0 "2 x 5 " 77 - 01 hr D = 1.SSE-02 mrem to thyroid.

3.4 31 Day Gl-LLI Calculation:

Obtain Gl-LLI Ai values from Table 4.0.

t = 744 hours0.00861 days 0.207 hours 0.00123 weeks 2.83092e-4 months

HP-ODCM-4 Page 5 of 6 Ci (uCi/ml) A (mrem-ml) (mrem)

Nuclide X i uCi-hr = hr

..

Cs-134 Cs-137 5.46E-06 8.35E-06*

X X

2.85E+02 2.32E+02

=

l.56E-03 l.93E-03 I-131 5.66E-06 X 8.23E+Ol = 4.66E-04 Co-58 2.22E-06 X 1.22E+04 = 2. 71E-02 Co-60 1.65E-06 X 3.25E+04 = 5.36E-02 H-3 8.07E-04 X 2.82E-01 = 2.28E-04 r Ci Ai = 8.49E-02 i

4.86E+l0 (ml)

F =

2.26E+l4 (ml)

Therefore, D = 744(hr) x ~:~:::~~ ~:i~ x 0.2 x 8.49E-02 (m~;m)

D = 2.72E-03 mrem to GI-LLI.

3.5 For this case, the critical organ would be the thyroid.

4. QUARTERLY COMPOSITE ANALYSES For radionuclides not determined in each batch or weekly composite, the dose contribution to the current monthly or ca~endar quarter cumulative summation may be approximated by assuming an average monthly concentra-tion based on the previous monthly or quarterly composite analyses.

However, for reporting purposes, the calculated dose contribution shall be based on the actual composite analyses.

HP-ODCM-4 Page 6 of 6 TABLE 4.0

. ~

LIQUID INGESTION PATHWAY DOSE FACTOR FOR SURRY POWER STATION UNIT NOS. 1 AND 2 Total Body Ai Thyroid Ai GI-LLI Ai RadionucUde mrem/hr . mrem/hr mrem/hr uCi/ml uCi/ml uCi/ml H-3 2.82E-01 2.82E-Ol 2.82E-01 Na-24 4.57E-01 4.57E-01 4.57E-01 Cr-51 5.SBE+OO 3.34E-01 1.40E+03 Mn-54 1.35E+03 2.16E+04 Fe-55 8.23E+03 2.03E+04 Fe-59 7.27E+04 6.32E+05 Co-58 1.35E+03 1.22E+04 Co-60 3.82E+03 3.25E+04 Zn-65 2.32E+05 3.23E+OS Rb-86 2.91E+02 1.23E+02 Sr-87 1.43E+02 8.00E+02 Sr-90 3. 01E+04 3.55E+03 Y-91 2.37E+OO 4.89E+04 Zr-95 3.46E+OO l.62E+04 Zr-97 8.13E-02 5.51E+04 Nb-95 1.34E+02 1.51E+06 Mo-99 2.43E+Ol 2. 96E+02 Ru-103 4.60E+Ol 1.25E+04 Ru-106 2.01E+02 1.03E+OS A~-llOm 8.60E+02 5.97E+05 Sb-124 1.09E+02 6.70E-01 7.84E+03 Sb-125 4.20E+Ol 1. 79E-01 1.94E+03 Te-125m 2.91E+Ol 6.52E+Ol 8.66E+02 Te-127m 6.68E+Ol 1.40E+02 1.84E+03 Te-129m 1.47E+02 3.20E+02 4.69E+03 Te-131m 5.71E+Ol 1.08E+02 6.80E+03 Te-132 1.24E+02 1.46E+02 6.24E+03 I-131 1.79E+02 1.02E+05 8.23E+Ol I-132 9.96E+OO 9.96E+02 5.35E+OO I-133 3.95E+Ol 1.90E+04 1.16E+02 I-134 5.40E+OO 2.62E+02 1.32E-02 I-135 2.24E+Ol 4.01E+03 6.87E+Ol Cs-134 1.33E+04 2.85E+02 Cs-136 2.04E+03 3.21E+02 Cs-137 7.85E+03 2.32E+02 Cs-138 5.94E+OO 5.12E-05 Ba-140 1.08E+02 '3 .38E+03 La-140 2.lOE-01 5.83E+04 Ce-141 2.63E-01 8.86E+03 Ce-143 4.94E-02 1.67E+04 Ce-144 9.59E+OO 6.04E+04 Np-239 1.91E-03 7 .1 l-E+02

HP-ODCM-5 Page 1 of 3

SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 5 Liquid Effluent Dose Projections Part Subject Page 1 Technical Specification Requirement 2 2 Projected Total Body Dose 2 3 Projected Critical Organ Dose 2

4 Example 2

HP-ODCM-5 Page 2 of 3

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.A.3.a requires that: "The Liquid Radwaste

_,Treatment System shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to liquid effluent releases to unrestricted areas (see Figure 5.1-1) when averaged over 31. days would exceed 0.06 mrem to the total body or 0.2 mrem to the critical organ."

2. PROJECTED TOTAL BODY DOSE 2.1 Determine DB= total body dose from liquid effluents in the previous 31 aay period, calculated according to H.P.-ODCM-4.

2. 2 Estimate R = ratio of the estimated volume of liquid effluent 1

releases in the present 31 day period to the volume released in the previous 31 day period.

2. 3 Estimate F = ratio of the estimated liquid effluent radioactivity 1

in the present 31 day period to the liquid effluent activity in the previous 31 day period.

2.4 Determine PDTB = projected total body dose in a 31 day period.

3. PROJECTED CRITICAL ORGAN DOSE 3 .1 Determine D = critical organ dose from liquid effluents in the previous 31 ~ay period, cal cu lated according to H.P. -ODCM-4.

3.2 Estimate R as in Step 2.2.

1 3.3 Estimate F as in Step 2.3.

1 3.4 Determine PD = projected critical organ dose in a 31 day period.

0

- PD = D (R Fl)

O O 1 Historical data pertaining to the* volumes and radioactivity of liquid effluents released in connection to specific station functions, as maintenance or refueling outages, shall be used in the above projections as appropriate.

4. EXAMPLE 4 .1 A critical organ dose in a 31 day period due to liquid effluent releases was calculated in H.P.-ODCM-4.3.3 using the data in H.P.-ODCM-4.3.1. Therefore, D c l.SSE-02 mrem to the thyroid.

HP-ODCM-5 Page 3 of 3

4.2 According to H.P.-ODCM-4.3.1, the total volume of undiluted liquid effluent released was 4.86E+l0 ml. It is estimated that the liquid effluent release may double to 9. 72E+ 10 ml in the present 31 day

period. Therefore, R = 9.72E+l0 = 2.0.

1 4.86E+l0 4.3 From H.P.-ODCM-4.3.1, the total concentration of radionuclides in undiluted liquid effluents is 8. 33E-04 uCi/ml. The total concentration of radionuclides in undiluted liquid effluents in the present 31 day period is estimated to be 1.00E-03 uCi/ml.

Therefore, F = 1.00E-03 = 1.2.

1 8.33E-04 4.4 The projected total body dose in a 31 day period is:

PDTB = DTB (Rl Fl)

PDTB - 1.85E-02 (mrem) x 2.0 x 1.2 PDTB = 4.44E-02 mrem.

4.5 The projected critical organ dose, PD, in a 31 day period would be 0

similarly obtained *

HP-ODCM-6 Page 1 of 9

SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 6 Gaseous Effluent Radiation Monitor Setpoints Part Subject 1 Technical Specification Requirement 2 2 Applicable Monitors 2 3 Setpoint Calculation 2

4 Example 3

HP-ODCM-6 Page 2 of 9

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.7.E requires that: "The radioactive liquid and

. 4gaseous effluent monitoring instrumentation channels shown in Table 3.7-S(a) and Table 3.7-S(b) shall be operable with their alarm/trip setpoints set to ensure that the limits of Specifications 3 .11.A. l and 3 .11. B .1 are not exceeded. The alarm/ trip setpoints of these channels shall be determined and adjusted in accordance with the Offsite Dose Calculation Manual (ODCM)".

2. APPLICABLE MONITORS Radioactive gaseous effluent monitors for which alarm/trip setpoints are determined in accordance with this Manual are:

Radiation Monitor Plant Release Point Instrument Number Process Vent GW-102 Condenser Air Ejector SV-111, 211 Ventilation Vent VG-110 Monitor locations on the gaseous effluent waste streams are shown in Figure 6.0.

3. SETPOINT CALCULATIONS 3 .1 The setpoint calculations for each monitor listed above shall be determined such that the following relationship is maintained:

D + D + D + D <.D pv. cael cae2

vv -

where:

D = The Technical Specification 3 .11.B .1 dose limits implementing 10CFR20 for the site, mrem/yr;

. D = The noble gas site boundary dose rate from* process vent pv gaseous effluent relea~es, mrem/yr; D = The noble gas site boundary dose rate from Unit 1 condenser cael air ejector gaseous effluent releases, mrem/yr; D = The noble gas site boundary dose rate from Unit 2 condenser cae2 ai*r ejector gaseous effluent releases, mrem/yr; D = The noble gas.site boundary dose rate from ven~ilation vent vv gaseous effluent releases, mrem/yr *

3.2 Setpoint values shall be determined using the following equation:

C m

= (Rni) 2.12E-03 Fm

HP-ODCM-6 Page 3 of 9

where:

m = The release pathway, process vent (pv), Unit 1 condenser air ejector (cael), Unit ventilation vent (vv);

2 condenser C == The effluent concentration limit air ejector implementing (cae2), or Technical m Specification 3.11.B.1 for the site, uCi/ml; R = The release rate limit for pathway m determined from the m

methodology in HP-ODCM-7, using Xe-133 as the nuclide to be.

released~ uCi/s,c; 2.12E-03 = CFM per ml/sec; and F = The maximum flow rate for pathway m, CFM.

m 3.3 According to NUREG-0133, the radioactive effluent radiation monitor alarm/trip setpoints should be based on the radioactive noble gases.

It is not considered to be practicable to apply instantaneous alarm/

trip setpoints to integrating moni.tors sensitive to radio iodines, radioactive materials in particulate form, and radionuclides other than noble gases.

4* EXAMPLE

4 .1 Assume Unit 1 is operating and Unit 2 is _shut down. To calculate the limiting release rate, the following .i.nformation is obtained from process vent release records:

Radionuclide Release Rate (Curies/sec)

Xe-133 4.43E-06 Xe-135 3.04E-07 Kr-88 2.84E-10 Xe-131m l.38E-07 and ventilation vent release records:

Radionuclide Release Rate (Curies/sec)

Xe-133 1. 77E-05 Xe-135 1.21E-06 Kr-88 l.14E-09 Xe-131m 5.52E-07 and Unit 1- condenser air ejector release records:

Radionuclide Release Rate (Curies/sec):

Xe-133. 2. llE-08 Xe-135 l.22E-09

HP-ODCM-6

Page 4 of 9 4.2 Determine the fraction of the total noble gas total body dose that is attributable to each pathway using the methodology and Tables 7.0 and 7.1 in HP-ODCM-7 *

. .

Process Vent:

K Radionuclide ~ X Qipv =

Xe-133 2.94E+02 X 4.43E-06 = l.30E-03 Xe-135 1.81E+03 X 3.04E-07 a: 5.SOE-04 Kr-88 1.47E+04 X 2.84E-10 = 4. l 7E-06 Xe-13lm 9.15E+Ol X 1.38E-07 = lo26E-05 I Ki pv i

x Qipv = l.87E-03 Ventilation Vent:

Radionuclide K.1VV Qivv =

X Xe-133 l.76E+04 X l.77E-05 = 3.12E-01 Xe-135 l.09E+05 X l.21E-06 = 1.32E-01 Kr-88 8.82E+05 X l.14E-09 = 1.0lE-03 Xe-131m 5.49E+03 X 5.52E-07 = 3.03E-03 4.48E-01

.*.-=

Unit 1 Condenser Air Ejector:

Radionuclide Kivv X Qicael =

Xe-133 l.76E+04 X 2. llE-08 = 3.71E-04 Xe-135 l.09E+05 X l.22E-09 a:: l.33E-04 I K i ivv x Q icael = 5.04E-04 The total body noble gas dose for = 1.87E-03 + 4.48E-01 + S.04E-04 process vent, ventilation vent, and Unit 1 condenser air ejector, mrem/yr.

The total body noble gas dose for a:: 4.SOE-01 process vent, ventilation vent, and Unit 1 condenser air ejector, ...

mrem/yr.

Process vent fractional dose a:: l.87E-03. 4

16 E_03

4.SOE-01 Ventilation vent fractional dose

4.4SE-Ol. 9 96 E-Ol 4.SOE-01 °

HP-ODCM-6 Page 5 of 9 Unit 1 condenser air ejector fractional dose= 5.04E-04 4.SOE-01 = l.12E-03

.*4.3 - Determine the fraction of the total noble gas skin dose that is attributable to each pathway using the methodology and Tables 7 .0 and 7.1 in HP-ODCM-7.

Process Vent:

Radio- +

nuclide (Lipv 1.1 X Mip) X Qipv

, Xe-133 (3.06E+02 + 1.1 X* 3.53E+02) X 4.43E-06 = 3.0BE-03 Xe-135 (1.86E+03 + 1.1 X 1. 92E+03) X 3.04E-07 = 1. 21E-03 Kr-88 (2 .37E+03 + 1.1 X l .52E+04) X 2.84E-10 = 5.42E-06 Xe-13lm (4.76E+02 + 1.1 X l.56E+02) X l.38E-07 = 8.94E-05 l: (Li i pv

+ 1.1 Mip) Qipv = 4.38E-03 Ventilation Vent:

Radio- +

(Livv 1.1 X Mivv) X Qivv =

nuclide Xe-133 (1.84E+04 + 1.1 X 2.12E+04) x 1. 77E-05 = 7.38E-Ol Xe-135 (l.12E+05 + 1.1 x l.15E+05) x 1. 21E = 2.89E-Ol Kr-88 (l .42E+05 + 1.1 x 9.12E+05) x l.14E-09 = l.31E-03 Xe-13lm (2.86E+04 + 1.1 x 9.36E+03) X ,1 5. 52E-07 = 2.14E-02 Unit 1 Condenser Air Ejector:

Radio- +

(Livv 1.1 X Mivv) X Qicael nuclide Xe-133 (1.84E+04 + 1.1 X 2.12E+04) X 2. llE-08 C: 8.BOE-04 Xe-135 (1.12E+05 + 1.1 X l.15E+05) X l.22E-09 C: 2.91E-04

.

r <;ivv + 1.1 Mivv) Qicael C: l. l 7E-03 i

The skin noble gas dose for

4.38E-03 + l.OSE+OO + l.17E-03 process vent, ventilation vent, and Unit 1 condenser air ejector, mrem/yr.

The skin noble gas dose for

l.06E+OO process vent, ventilation vent, and Unit l condenser air ejector, mrem/yr.

Process'Vent fractional dose

4.38E-03 l.06E+OO

4.13E-03

HP-ODCM-6 Page 6 of 9 Ventilation vent fractional dose a:: l.05E+OO l.06E+OO a:: 9.91E-01 Unit 1 condenser air ejector = l.17E-03 l.06E+OO = l.lOE-03 4.4 Determine the release rate limit for total body dose, R , from the methodology in HP-ODCM-7, using Xe-133 as the nuc~!de to be released.

The part of Technical Specification 3.11.B.1.a(i) total body dose limit that is attributable to the process vent = 500 mrem/yr x 4.16E-03 = 2.08 mrem/yr.

From the methodology in HP-ODCM-7.2.1, K.ipv Qi pv -< 2.08 mrem/yr.

Calculating Qi pv for Xe-133, QXe- 133 = 2.08 mrem/yr

~e-133 QXe- 133 = 2.08 mrem/yr 2.94E+02 mrem/yr ' .

Curie/sec.

QXe-lJJ = 7.07E-03 Curie/sec.= 7.07E+03 uCi/sec.

4.5 Determine the release rate limit for total body dose, R , from the methodology in HP-ODCM-7, using Xe-133 as the nuc"fide to be released.

The part of Technical Specification 3.11.B.1.a(i) total body dose limit that is attributable to the ventilation vent= 500 mrem/yr x 9.96E-01 = 498 mrem/yr.

'From the methodology in HP-ODCM-7.2.1, Kivv Qivv ~ 2.08 mrem/yr.

Calculating Qivv for Xe-133, QXe-lJJ

498 mrem/yr Kxe-133 QXe-lJJ

_........,,...4_9....,8,...,.-m_r_em~/'-y:..;;r.---

, l. 76E+04 mrem/yr Curie/sec.

HP-ODCM-6 Page 7 of 9 QXe-lJJ a 2.83E-02 Curie/sec. a 2.83E+04 uCi/sec *

. *4.6

Determine the release rate limit for total body dose, R , from the methodology in HP-ODCM-7, using Xe-133 as the nucl'i~1 to be released.

The part of Technical Specification 3.11.B.l.a(i) total body dose limit that is attributable to the Unit 1 condenser air ejector= 500 mrem x l.12E-03

0.56 mrem.

yr yr From the methodology in HP-ODCM-7.2.1, Kivv Qicael < 0.56 mrem/yr.

Calculating Q for Xe-133, icael

.

QXe- 133 = 0.56 mrem/yr JSce-133 Qxe-133 = ..,.......,.-.,-o_.;...,5,....,6_m_r_em.....;/_.y,...r__

l.76E+04 mrem/yr Curie/sec.

QXe- 133 = 3.lBE-05 Curie/sec.= 3.lBE+Ol .

.. . uCi/sec *

4. 7 Determine the release rate limit for skin dose, R , from the methodology in HP-ODCM-7, using Xe-133 as the nJ'c"lide to be released.

The part of Technical Specification 3.11.B.1.a(i) skin dose limit that is attributable to thefprocess vent= 3000 mrem/yr x 4.13E-03 =

l.24E+Ol mrem/yr.

From the methodology in HP-ODCM-7.2.1, (Li pv +, 1.1 Mi pv ) Qipv -< l.24E+Ol

mre~/yr.

QXe- 133

l.24E+Ol mrem/yr (LXe-133 + 1

1 ~e-133) mrem/yr Curie/sec.

QXe- 133

l.24E+Ol mrem/yr .

(3.06E+02 + 1.1 x 3.53E+02) mrem/yr

Curie/sec *

QX;_

133

l.79E-02 Curie/sec.= l.79E+04 uCi/sec.

HP-ODCM-6 Page 8 of 9

4 .8 Determine the release rate limit for skin dose, R , from the methodology in HP-ODCM-7, using Xe-133 as the nu"c:'l.ide to be released.

The part of Technical Specification 3.11.B.1.a(i) skin dose limit that is attributable to the ventilation vent

3000 mrem/yr x 9.91E-01 = 2.973E+03 mrem/yr.

From the methodology in HP-ODCM-7.2.1, (Livv + 1.1 Mivv) Qivv ~ 2.973E+03 mrem/yr.

QXe- 133 = 2.973E+03 mrem/yr (LXe-133 + l.l ~e-133) mrem/yr Curie/sec.

QXe- 133 = "'":"'!""-=-".,.--...,,....,.~-2~.9~7~3-E_+~0~3~m~r~e~m~/~y~r~~----~-

(1.84E+04 + 1.1 x 2.12E+04) mrem/yr Curie/sec.

QXe- 133 = 7.13E-02 Curie/sec.= 7.13E+04 uCi/sec.

4.9 Determine the release rate limit for skin dose, R , from the

methodology in HP-ODCM-7, using Xe-133 as the released.

The part of Technical Specification 3.11.B.1.a(i) skin dose limit that is attributable to the Unit 1 condenser air ejector = 3000 mrem/yr x l.lOE-03 = 3.303E+OO mrem/yr.

,*

fiflElide to be From the methodology in HP-ODCM-7.2.1, (Li cae 1 + 1.1 Mi cae 1 ) Qi cae 1 -< 3.30E+OO mrem/yr.

QXe- 133 = 3.30E+OO mrem/yr (LXe-133 + l.l ~e-133) mrem/yr Curie/sec.

QXe- 133 c 3.30E+OO mrem/yr (l.84E+04 + 1.1 x 2.12E+04) mrem/yr Curie/sec.

QXe- 133 = 7.91E-05 Curie/sec.~ 7.91E+Ol uCi/sec *

..

4.10 The calculations indicate that the total body dose limits result in the most restrictive release rate limits. Therefore.

C

m (Rpv) 2.12E-03 pv Fpv

HP-ODCM-6 Page 9 of 9 C s (7.07E+03) x 2.12E-03 pv 300 Cpv c 5.0E-02 uCi/ml and C = (Rvv) 2.12E-03 vv F

vv C

vv = (2.83E+04) x 2.12E-03 172,000 C

vv = 3.49E-04 uCi/ml and C

cael

= (Rcael) 2.12E-03 Fcael Ccael = (3.18E+Ol) 2.12E-03 5

Ccael = l.35E-02 uCi/ml

4.11 Setpoints in CPM (counts per minute) can be determined by multi plying the above effluent concen;ration limits by the appropriate monitor conversion factors.

..

Boron ltecove Boron Page 2 Gas Stripper ..._....,.__-r.,ompreasor Recovery Overhead Surge Tank

...

Waste Caa urge Drum

,.

Compressor Waete Gas Decay Tank

...... - ...... _ Proce**

Containment Vacuum S stem I - -- -

-- - --- -- - ..... ------ Vent Vent and Drain S stem -- ....... ....

Relief Valve Dischar e '

ii

\ \*

1\

.*'

6 Radiation Monitor

--- Automatic Ac.tuation SURRY GASEOUS EFFLUENT SYSTEM

.

.*'

f

~ r e 6.0 (cont'd) of 2 Puel Buildin1 Safeguard* Areal Safeguard, Area 2

'. ,

I Auxili1E1 Central lvftdto*

. I I

Ventilation Vent

"""-~_..--~~~r-1..--1 HEPA Radioiodine VG-.110, Decoatawinatlon Bulldi h

Contai1111e11t Pur

,.

Conden*er Air Ejector (Unit l)

AtmospherE SV-111

..

Conden*er Air I ector (Unit 2 SV-211

.*'

SURRY GASEOUS EFFLUENT SYSTEM

HP-ODCM-7 Page 1 of 6

SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 7

Gaseous Effluent Release Rate Part

Subject 1 Technical Specification Requirement 2 2 Calculations 2 3 Example 3

HP-ODCM-7 Page 2 of 6

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.B.l.a requires that: "The dose rate due to

. ,radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary (see Figure 5.1-1) shall be limited to the following:

(i) for noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and (ii) for iodine - 131, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to the critical organ".

2. CALCULATION

1. The dose rate limit for noble gases shall be determined to be within the Technical Specification limit by limiting the release rate to the lessor of:

L [Kivv Qivv + Kipv Qipv] < 500 mrem/yr to total body, i

or

. .

E i

f (Livv + 1. lMivv ) Qivv + (Li pv + 1

lMi pv ) :qi pv ] < 3000 mrem/yr to the skin where:

Subscripts= vv, refers to vent releases from the building ventilation vent; pv, refers to the vent releases from the process vent; i, refers ~o individual radionuclide; Kivv' Kipv -= The total body dose factor for ventilation vent or process vent release due to galTU!la emissions for each identified noble gas radionuclide, i, in mrem/yr per Curie/sec. Factors are listed in Table 7.0 and Table 7.1; Livv' Lipv -= The skin dose factor for ventilation vent or process vent release due to beta emissions for each identified noble gas radionuclide i, in mrem/yr per Curie/sec. Factors are listed in Table 7.0 and Table 7.1;

'

HP-ODCM-7 Page 3 of 6

M M C The air dose factor for ventilation vent or ivv' ipv process vent release due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per Curie/sec. Factors are listed in Table 7.0 and Table 7.1; The release rate for ventilation vent or process vent of noble gas radionuclide, i, in gaseous effluents in Curie/sec (per site);

1.1 = The unit conversion factor that converts air dose to skin dose, in mrem/mrad.

2. The dose rate limit for iodine - 131, for tritium, and for all radionuclides in particulate form with half-live greater than 8 days shall be determined to be within the Technical Specification limit by limiting the release rate to:

r [Pivv Qivv + P.ipv Qipv ] < 1500 mrem/yr to critical organ i

where:

The critical organ dose factor for ventilation vent or process vent .for I-131, H-3, and all radionuclides in pa1tticulate half-lives greater than 8 days form for inhalation pathway, in mrem/yr per Curie/sec.

Factors are listed in Table 7.2; with the The release rate for ventilation vent or process vent of I-131, H-3, and all radionuclides, i, in particulate form with half-lives greater than 8 days in gaseous effluents in Curie/sec (per site).

3. All gaseous releases, not through the process vent, are considered

ground level and shall be included in the determination of Qivv"

3. EXAMPLE 3.1 For demonstration of methodology, see. HP-ODCM-6.4.

HP-ODCM-7 Page 4 of 6 TABLE 7.0 GAMMA AND BETA DOSE FACTORS FOR SURRY POWER STATION UNIT NOS. 1 AND 2 X/Q = 6.0E-05 sec/m3 at 499 meters N Direction Dose Factors for Ventilation Vent K L Mivv N.

Noble Gas Totaf~ody sirn Gamma Air Bet§'Air Radionuclide mrem/ r mrem/ r mrad/vr mrad/xr Curie Sec Curie Sec Curie7sec Curie7sec Kr-83m 4.54E+OO l .16E+03 1. 73E+04 Kr-85m 7.02E+04 8.76E+04 7.38E+04 l.18E+05 Kr-85 9.66E+02 8.04E+04 l.03E+03 l.17E+05 Kr-87 3.55E+05 5.84E+05 3.70E+05 6.18E+05 Kr-88 8.82E+05 l.42E+05 9.12E+05 l.76E+05 Kr-89 9.96E+05 6.06E+05 l.04E+06 6.36E+05 Kr-90 9.36E+05 4.37E+05 .9.78E+05 4.70E+05 Xe-13lm 5.49E+03 2.86E+04 ~.36E+03 6.66E+04 Xe-133m l.51E+04 5.96E+04 l.96E+04 8.88E+04 Xe-133 1. 76E+04 l.84E+04 2 .12E+04 6.30E+04 Xe-135m l.87E+05 4.27E+04 2.02E+05 4.43E+04 Xe-135 l.09E+05 l.12E+05. l.15E+05 l.48E+05 Xe-137 8.52E+04 7.32E+05 9.06E+04 7.62E+05 Xe-138 5.30E+05 2.48E+05 5.53E+05 2.85E+05 Ar-41 5.30E+05 l.61E+05 5.58E+05 l.97E+05

.,

HP-ODCM-7 Page 5 of 6

. TABLE 7 .1 GAMMA AND BETA DOSE FACTORS FOR SURRY POWER STATION UNIT NOS. 1 AND 2 X/g = l.OE-06 sec/m3 at 644 meters S Direction Dose Factors for Process Vent K L M Ni Noble Gas TotafP!ody si~X GanJiivAir BetaPXir Radionuclide mrem/y_r mrem/"i.r mrad/vr mrad/"i.r Curie/Sec Curie/Sec Curie/sec Curie/sec Kr-83m 7.56E-02 1. 93E+Ol 2.BBE+02 Kr-85m l.17E+03 l.46E+03 l.23E+03 l.97E+03 Kr-85 l.61E+Ol l.34E+03 1. 72E+Ol 1. 95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+02 Kr-88 l.47E+04 2.37E+03 l.52E+04 2.93E+03 Kr-89 l.66E+04 l.01E+04 l.73E+04 l.06E+04 Kr-90 l.56E+04 7.29E+03 l.63E+04 7.83E+03 Xe-13lm 9.15E+Ol 4.76E+02 )..56E+02 l .11E+03 Xe-133m 2.5IE+02 9.94E+02 3.27E+02 l.4BE+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 l.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 l.81E+03 l.86E+03 1. 92E+03 2.46E+03 Xe-137 l.42E+03 l.22E+04 l.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.2IE+03 4.75E+03 Ar-41 B.84E+03 2.69E+03 9.30E+03 3.28E+03

HP-ODCM-7 Page 6 of 6 TABLE 7.2

.. INHALATION PATHWAY DOSE FACTORS FOR SURRY POWER STATION UNIT NOS. 1 AND 2 Ventilati_on Vent. XIQ = 6.0E-05 sec/,3 at 499 Meters N Direction Process Vent X/Q = 1.0E-06 sec/m at 644 Meters S Direction pi pi Radionuclide mre-rt-y_r mreR.Yvr Curie/sec Curie/sec H-3 6.75E+04 1.12E+03 Cr-51 5.13E+03 8.SSE+Ol Mn-54 ND :ND Fe-59 ND ND Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-89 ND ND

...,

Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-llOm ND ND Te-127m 3.64E+OS 6.07E+03 Te-129m 3.80E+OS 6.33E+03 Cs-134 ND ND Cs-136 ND ND

-cs-137 ND ND Ba-140 ND ND Ce-141 ND ND Ce-144 ND ND 1-131 9.75E+08 1.62E+07

,.

ND - No data for dose factor according to R.G. 1.109, Rev. 1.

HP-ODCM-8 Page 1 of 4

SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 8 Noble Gas Effluent Air Dose Limits Part Subject 1 Technical Specification Requirement 2 2 Calculation 2 3 Example . 3

,

HP-ODCM-8 Page 2 of 4

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.B.2.a requires that: "The air dose due to

. .noble gases released in gaseous effluents, from each reactor unit, from the site to areas at and beyond site boundary (see Figure 5.1-1) shall be limited to the following:

(i) During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and, (ii) During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

2. CALCULATIONS 2.1 The air dose to areas at or beyond the site boundary due to noble gases shall be determined by the following:

For gamma radiation:

For beta radiation:

.~-

Db= 3.17E-08 L [N Q ivv ivv

+ N Q ]

ipv ipv i

where:

Subscripts= vv, refers to vent releases from the building ventilation vent; pv, refers to the vent releases from the process vent; i, refers to individual radionuclide; Dg .. the air dose for gamma radiation, in mrad; Db - the air dose for beta radiation. in mrad; M M

the air dose* factors for ventilation vent or ivv' ip~ process vent release due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per Curie/sec. Factors ICre listed in Tables 7.0 and 7.1; N the air dose factor . for ventilation vent or ivv' Nipv

process vent release due to beta emissions for

, each identified noble gas radionuclide, i, in mrad/yr per Curie/sec. Factors are listed in Tables 7.0 and 7.1;

HP-ODCM-8 Page 3 of 4 the release for ventilation vent or process vent of noble gas radionuclide, i, in gaseous efflu-ents for 31 days, quarter, or year as appropri-ate in Curies (per site);

3.17E-08 "" the inverse of the number of seconds in a year.

2.2 All gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Q. .

l.VV

3. EXAMPLE 3.1 Compilation of data from release records for the process vent for a quarter provides the following information:

Noble Gas Radionuclide Activity Released (Curies)

Xe-133 6.25E+Ol Xe-135 2.24E-01 Xe-131m 6.71E-02 Xe-133m 3.BlE-02 3.2 Compilation of data from release records for the ventilation vents

for a quarter provides the following information:

Noble Gas Radionuclide Activity*~eleased (Curies)

Xe-133 5.62E+02 Xe-135 2.02E+OO Xe-131m 6.04E-01 Xe-133m 3.43E-01 3.3 The air dose for gamma radiation is calculated from:

The appropriate values of Mivv and M shall be obtained from Tables 7 .O and 7. l. ipv (mrad-sec)

Noble Gas Radionucli*de Mi (mrad/yr pe¥"Curie/sec) X Qin (Cure)

- yr Xe-133 2.12E+04 l.15E+05 X 5.62E+02 2.02E+OO -- l.19E+07 2.32E+05 Xe-135

-

X

Xe-13lm 9.36E+03 X 6.04E-Ol 5.65E+03 Xe-133m l.96E+04 X 3.43E-Ol "" 6. 72E+03 l: Mi i vv Qivv - l.21E+07

HP-ODCM-8 Page 4 of 4 Noble Gas M (mrad-sec)

Radionuclide (mrad/yr Ei¥vcurie/sec) X Qi (cuFYe) - yr Xe-133 Xe-135 3.53E+02 1.92E+03 X 6.25E+Ol 2.24E-Ol

-- 2.21E+04 4.30E+02

--

X Xe-131m 1.56E+02 X 6.71E-02 1.0SE+Ol Xe-133m 3.27E+02 X 3.81E-02 l.25E+Ol t M Q = 2.26E+04 i ipv ipv Dg = 3.17E-08 (~) [ l.ZlE+0 7 (mrad-sec) + 2

26 E+0 4 (mrad-sec) sec yr yr Dg = 3.84E-01 mrad 3.4 A similar approach could be taken to calculate Db.

*.

HP-ODCM-9 Page I of 6 SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 9 Iodine - 131, Tritium, and Radionuclides in Particulate Form Gaseous Effluent Dose Limits Part Subject Page I Technical Specification Requirement 2

2 Calculation 2

3 Example 3

.."'*

HP-ODCM-9 Page 2 of 6

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.B.3.a requires that: "The dose to the

-*maximum exposed member of the public from all I-131. from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit. from the site to areas at and beyond the site boundary (see Figure 5.1-1) shall be limited to the following:

(i) During any calendar quarter: Less than or equal to 7.5 mrems to the critical organ, and (ii) During any_ calendar year: Less than or equal to 15 mrems to the critical organ".

2. CALCULATION 2.1 The dose to the maximum exposed member of the public from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents from the site to areas at and beyond the site boundary shall* be determined as follows:

where:

Subscripts = vv, refers to vent releases from the building ventilation vent; pv, refers to the vent releases from the process vent; Dr = the dose to the critical organ of the maximum exposed member of the public in mrem;

. RMivv' RMipv = the milk pathway dose factor for ventilation vent or process vent release due to iodine-131, tritium, .. and from all radionuclides in particulate form with half-lives greater than 8 days, in mrem/yr per Curie/sec. Factors are listed in Table 9.0; Rli vv , Rli pv .. the inhalation pathway dose factor for ventilation vent or process vent release due to iodine-131, tritium, and from all radionuclides in particulate form with half-live; greater than 8 days, in mrem/yr per Curie/sec. Factors are listed in Table 9.1; the release for ventilation vent or process vent of iodine-131, tritium, and from all radionu-clides in particulate form with half-lives greater than 8 days *in Curies (per site);

HP-ODCM-9 Page 3 of 6 3.17E-08 the inverse of the number of seconds in a year.

2.2 All gaseous releases, not through process vent, are CScnsidered ground level and shall be included in the determination of Q. .

l.VV

3. EXAMPLE 3.1 Compilation of data from release records for the process vent for a quarter provides the following information:

Radionuclide Activity Released (Curies)

I-131 7.20E-04 H-3 2.45E-01 Co-58 l. IOE-06

3. 2 Compilation of data from release records for the ventilation vent for a quarter provides the following information:

Radionuclide Activity Released (Curies)

I-131 6.48E-03 H-3 2.21E+OO Co-58 9.90E-05 3.3 The dose to the critical organ of the maximum exposed member of the public is calculated from:

Dr= 3.17E-08 1:i [(RM.1vv Qivv + RMi pv Qi pv ) + (Rrivv Qivv + RI_ipv Qip)J The appropriate values of RM. , RMi , Riivv and Riipv shall be obtained from Tables 9. 0 and f.'r. pv

'\.,

RMi Qivv (mrem-sec)

Radionuclide (mrem/yr per~urie/sec) X (Curies) = yr I-131 6.21E+08 X 6.48E-03 = 4.02E+06 H-3 7.20E+02 X 2.21E+OO == l.59E+03 Co-58 X 9.90E-05 =

4.02E+06 i1: RMi vv ~i vv ""

Due to lack of information, according to Regulatory Guide 1. 109, Rev. 1, Co-58 is not included in these calculations.

RMi ~mrem-sec)

Radionuclide (mrem/yr perp~urie/sec) Qi~ves)

(Cur yr X *':

I-131 H-3 2.97E+OB 3.12E+02 X 7.20E-04 2.45E-01 - 2 .14E+05 7.64E+Ol

-

X ""

Co-58 X l.lOE-06

,

f RMipv ~ipv a: 2.14E+05

HP-ODCM-9 Page 4 of 6 Rii ~i . (mrem-sec)

Radionuclide (mrem/yr perv~urie/sec) x (Cur!Xs)

yr I-131 4.45E+06 x 6.48E-03

2.88E+04 H-3 1. 94E+02 x 2.21E+OO

4.29E+02 Co-58 x 9.90E-05

r i

RI 1 vv Q~LVV = 2.92E+04 Due to lack of information, according to Regulatory Guide 1.109, Rev. 1, Co-58 is not included in these calculations.

'\,

Rii (mrem-sec)

(mrem/yr perp~urie/sec) Qi~v Radionuclide X (Cur es) = yr I-131 1. 93E+06 X 7.20E-04 = l.39E+03 H-3 8.41E+Ol X 2.45E-01 I: 2.06E+Ol Co-58 X l. lOE-06 = .,..

I: RI i ipv

~ipv = 1. 41E+03 Dr= 3.17E-08 [(4.02E+06 + 2.14E+05) + (2.92E+04 + l.41E+03)]

Dr= l.35E-Ol (mrem)

,

HP-ODC:M-9 Page 5 of 6 TABLE 9.0 CRITICAL PATHWAY DOSE FACTORS FOR SURRY POWER STATION UNIT NOS. 1 AND 2 Ventilation Vent D/Q = 9.0E-10 m-2 at 5150 Meters S Direction 2

Process Vent D/Q = 4.3E-10 m- at 5150 Meters S Direction

,----------------------------------- RMi RMi Radionuclide mremryr mremf~r Curie/sec Curie/sec H-3 7.20E+02 3.12E+02 Mn-54 ND ND Fe-59 ND ND Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND

Sr-89 ND ND Sr:-90 ND ND

I Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-llOm ND ND Te-127m 8.06E+04 3*.asE+04 Te-129m 1.25E+05

5.98E+04 I-131 6.21E+08 2.97E+08 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Ce-141 Ce-144 ND ND

.. ND ND

ND - No data for dose factor according to R.G. 1.109, Rev. 1.

HP-ODCM-9 Page 6 of 6*

TABLE 9.1 INHALATION PATHWAY DOSE FACTORS FOR SURRY POWER STATION

.. UNIT NOS. 1 AND 2 Ventilation Vent X/Q = 3.0E-07 sec/m3 at 5150 Meters S Direction 3

Process Vent X/Q = l.3E-07 sec/m at 5150 Meters S Direction RI RI.

mrem1fV 1

Radionuclide mremYyr ir Curie/sec Curie/sec H-3 1.94E+02 8.41E+Ol Cr-51 1.73E+Ol 7.48E+OO Mn-54 ND ND Fe-59 ND ND Co-58 ND ND Co-60 ND 't-,,"I)

Zn-65 ND 't-,,"I)

Rb-86 ND ND Sr-89 ND ND Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-llOm ND ND Te-127m l.46E+03 6.33E+02 Te-129ni 1.64E+03 7.12E+02 I-131 4.45E+06 1.93E+06 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND Ce-141 ND ND

.. ND Ce-144 ND ND ND - No data for dose factor according to R.G. 1.109, Rev. 1.

HP-ODCM-10 Page 1 of 5 SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 10 Gaseous Effluent Dose Projections Part Subject Page 1 Technical Specification Requirement 2

2 Projected Gamma Dose 2

3 Projected Beta Dose 2

- 4 5

Projected Maximum Exposed Member of the Public Dose Example .. 3 2

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HP-ODCM-10 Page 2 of 5

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.B.4.a requires that: "The Gaseous Radwaste

.*Treatment System, and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous eff*luent air doses due to gaseous effluent releases, from each reactor unit, from the site to areas at or beyond the site boundary (see Figure 5.1-1) would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation over 31 days. The Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, from the site to areas at and beyond the site boundary (see Figure 5.1-1) would exceed 0.3 mrem to the critical organ over 31 days".

2. PROJECTED GAMMA DOSE 2 .1 Determine Dg = the 31 day gamma air dose in the previous 31 day period calculated according to H.P.-ODCM-8.

2.2 Estimate Rg = ratio of the volume of gaseous effluent in the present 31 day period to the volume released during the previous 31 day period.

2.3 Estimate Fg = ratio of the estimated noble gas effluent activity in

the present 31 day period to the noble gas effluent activity during the previous 31 day period.

2.4 Determine PD = projected 31 day gamma air dose g

PD = D (R F )

g g g g

3. PROJECTED BETA DOSE 3.1 Determine Db = the 31 day beta air dose in the previous 31 day period, calculated according to H.P.-ODCM-8.

3.2 Estimate R and F as in Steps 2.2 and 2.3 above.

g g 3.3 Determine PDb"' projected 31 d~y period beta air dose PDb "'Db (Rg Fg)

4. PROJECTED MAXIMUM EXPOSED MEMBER OF THE PUBLIC DOSE 4 .1 Determine D "' the 31 day maximum exposed member of the pub lie dose in tne max previous 31 day period, calculated :accor di ng to H.P.-ODCM-9 *

- 4.2 Estimate Fi s ratio of the estimated activity from I-131, radio-active materials in particulate form with half-lives greater than 8 days, and tritium in the present 31 day period to the activity of 1-131 1 radioactive materials in particulate form with half-lives greater than 8 days, and tritium in the previous 31 day period.

,-

HP-ODCM-10 Page 3 of 5 4.3 Determine PD -= projected 31 day maximum exposed member of the

max public dose.

Historical data pertaining to the volumes and radioactive concentrations of gaseous effluents released in connection to specific station functions, such as containment purges, shall be used in the above estimates as appropriate.

5. EXAMPLE 5.1 Compilation of data from release records for the process vent in a 31 day period provides the following information:

Noble Gas Radionuclide Activity Released (Curie)

Xe-133 2.08E+Ol Xe-135 7.47E-02 Xe-13lm 2.24E-02 Xe-133m l.27E-02 5.2 Compilation of data from release records for the ventilation vents in a 31 day period provides the following information:

Noble Gas Radionuclide Xe-133 Xe-135 Xe-13lm Activit7 Released (Curie) l.87E+02 6.73E-01 2.0lE-01 Xe-133m l.14E-01 5.3 The air dose for gamma radiation is calculated according to H.P.-ODCM-8 from:

The appropriate values of Mivv and Mipv are obtained from Tables 7.0 and 7 .1..

M - (mrad-sec)

- ..

Noble Gas Qivv Radionuclide (mrad/yr ~i¥Vcurie/sec) X (Curie) yr Xe-133 Xe-135 Xe-13lm 2.12E+04 l .15E+05 9.36E+03

~

X l.87E+02 6.73E-01 2.0lE-01

-..- 3.96E+06 7.74E+04 l.88E+03

-..

X Xe-133m, l.96E+04 X l.14E-Ol 2.23E+03 t Mi 4.04E+06 i vv Qivv

HP-ODCM-10 Page 4 of 5 Noble Gas M. (mrad-sec)

Radionuclide (mrad/yr p~Fvcurie/sec) X Qi (cuFYe) - yr Xe-133 Xe-135 3.53E+02

1. 92E+03 X 2.0SE+Ol 7.47E-02 -- 7.34E+03 l.43E+02

--

X Xe-13lm 1.56E+02 X 2.24E-02 3.49E+OO Xe-133m 3.27E+02 X 1.27E-02 4.15E+OO I: M Q = 7.49E+03 i ipv ipv Dg = 3.17E-08 (.!!....) [ 4.04E+06 (mrad-sec) + 7.49E+03 (mrad-sec) ]

sec yr yr Dg = 1.28E-01 mrad 5.4 Total volume of gaseous effluent released in 31 day period is:

31 day average flow 31 day average flow rate . min

[ . rate (CFM) for + (CFM) for ventilation ] X 4.46E+04 31 day process vent vent*

Total Volume (ft 3 ) = (295 CFM + 120,000 CFM.) x 4.46E+04 Total Volume (ft 3 ) = 5.37E+09 Estimated total volume in 31 day period= 4.46E+09 (ft 3 )

Therefore, Rg "'4.46E+09

0.83 5.37E+09 5.5 The total activity released in 31 day period is:

31 day process vent + 31 day ventilation.vent A+ B total activity (Curies) total activity (Curies)

Total activity released* (2.09E+Ol Curies+ 1.BBE+02 Curies)

Total activity released"' 2.09E+02 Curies Estimated ,total activity released"' 2.50E+02 Curies Therefore, Fg

2.50E+02 "' 1.20 2.09E+02

5.6 The projected 31 day gamma air dose is:

PD' ... D g g (Rg Fg)

HP-ODCM-10 Page 5 of 5 PD g ~ l.28E-01 mrad x 0.83 x 1.20 PD g ~ l.27E-01 mrad

. .

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HP-ODCM-11 Page 1 of 2 SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 11 Total Dose Part Subject 1 Technical Specification Requirement 2 2 Calculation 2

- - ""

'

HP-ODCM-11 Page 2 of 2

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.C.l requires that: "The annual (calendar year) dose or dose commitment to the maximum exposed member of the

'public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or critical organ (except the thyroid, which shall be limited to less than or equal to 75 mrems)".

2. CALCULATION Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with the methodology presented in H.P.-ODCM Sections 4, 8, 9, or Regulatory Guide 1.109, Rev. 1 (see Appendix B).

If the dose to the maximum exposed member of the public exceeds twice the limits of Specifications 3.11.A.2, 3.11.B.2, or 3.11.B.3, the dose commitment shall include the contribution from direct radiation. Direct radiation shall be determined from an evaluation of environmental TLD's or calculated using_ the simple methodology presented in Lamarsh, Introduction to Nuclear Engineering, June 1977, or point kernal computer codes such as QAD .

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HP-ODCM-12 Page 1 of 2 SUR.RY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 12 Semiannual Radioactive Effluent Release Report Dose Assessment Part Subject 1 Technical Specification Requirement 2 2 Dose Assessment 2

.*

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HP-ODCM-12 Page 2 of 2 1 0 TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 6.9.1.12 requires that the Semiannual Radioactive

. 4Release Report submitted within 60 days after January 1 of each year include, in part, an assessment of the radiation doses to individuals due to the radioactive liquid and gaseous effluents from the station during the previous calendar year, and an assessment of the radiation doses to the maximum exposed member of the public from reactor releases and radiation.

2. DOSE ASSESSMENT

1. The radiation doses to individuals due to the radioactive liquid and gaseous effluents from the station during the previous calendar year shall be calculated using the methodology _presented in this Manual or in Regulatory Guide 1.109 (Revision 1), October 1977, "Calcula-tion of Annual Doses to Man from Routine Releases of Reactor Efflu-ents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I" (see Appendix B). Population doses are not to be included in the dose assessment.

2. The dose to the maximum exposed member of the public due to the radioactive liquid and gaseous effluents from the station shall be incorporated with the dose assessment performed above. If the dose to the maximum exposed member of the public exceeds twice the limits

of Specifications 3.11.A.2, 3.11.B.2 or 3.11.B.3, the dose assessment shall include the contribution from direct radiation.

U.S. Nuclear Regulatory Commission NUR.EG-0543, February 1980, "Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40CFR Part 190)", states "There is reasonable*

assurance that sit:es with up to four operating reactors that have releases within Appendix I design objective values are also in conformance with the EPA Uranium Fuel Cycle Standard, 40CFR Part

. 190".

3. The meteorological conditions during the previous calendar year or historical annual average atmospheric dispersion conditions shall be used for determining the gaseous pathway doses *

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HP-ODCM-13 Page 1 of 8 SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 13 Radiological Environmental Monitoring Locations Part Subject 1 Land Based Samples 2 2 River Based Samples 11 3 Figures

HP-ODCM-13 Page 2 of 8 1.0 LAND BASED SAMPLES Particulate and Charcoal Air Samples Hog Island Reserve (HIR) - Route 650 to Hog Island Reserve, end of dirt road of reserve. On Vepco pole on right side of road.

Bacon's Castle (BC) - 50 yards back on Rt. 617 from intersection of Rt. 617 and Rt. 10 on Vepco pole near Addison's Grocery #2.

Alliance (ALL) - Route 10 to Route 634 north; 1.4 miles on Vepco pole on right side of road.

Colonial Parkway (CP) - Take Route 31 from James River Ferry, Jamestown, to Route 359. Take Colonial Parkway for approx. 2. 9 miles; sampler on right side of road on Vepco pole.

Dow Chemical - Route 60 east to Dow Chemical Road at Badische Corp. sign. Follow road parallel to railroad tracks. At first curve in road, turn left at substation. Air sampler inside substation.

Fort Eustis (FE) - Route 60 east to Fort Eustis entrance road.

Straight to circle, first right out of circle onto Lee JHvd. Left on Harrison Road to stop sign; continue on Harrison Road to small railroad house on left.

Vepco pole by this house on left.

Newport News (N. N. ) - Route 60 east (Warwick Blvd.) to 34th Street. Left. on 34th Street, one block to Jefferson Avenue, left on Jefferson Avenue.

Sampler inside Vepco substation.

Surry Station (SS) - On roof inside station gate on top of storeroom area Unit #1 side.

Environmental TLD's Control - (00) Control TLD located in shield in count room.

Surry Station - (01) See air sample location - Surry Power Station West North West - (02) Located on the center, rear fence of the sewage treatment plant.

Station Discharge - (03) End of discharge structure.

HP-ODCM-13 Page 3 of 8

Environmental TLD's (cont'd)

North North West - (04) Take dirt road on left, on the north side of discharge canal. At the end of the road, walk through the gate and TLD will be located on a pine tree.

North - (05) Prior to entrance to Hog Island Game Reserve, located on Vepco property sign, on left side of Route 650.

North North East - (06) Take the second dirt road to the construc-tion site, prior to the intersection of the other construction site roadway, TLD is located on a tree, North East - (07) Located on the northern property line, approx. 1250 feet from Route 650. TLD is attached to a Vepco property sign.

East North East - (08) Located on the northern property line, approx. 2500 feet from Route 650. TLD is located on Vepco property sign.

East (exclusion) - (09) Located on a telephone pole on the back corner of the Vepco construction project

parking lot.

West - (10) Located on y~pco property sign approx. 1600 feet from Route 650.

West South West - (11) Located on telephone pole approx. 800 feet from Route 650.

South West - (12) Located on a telephone pole, on Route 650, at the curve in road.

South South West - (13) Located on a telephone pole on Route 650.

South - (14) Take road to warehouse off of Route 650.

TLD located on first telephone pole on the right.

South South East - (15) Drive to the primary meteorological tower.

Walk toward Vepco property line and turn right. TLD is located on a telephone pole, approx, 600 feet.

South East - (16) Drive to the primary meteorological tower.

Walk toward Vepco property line and turn left. TLD located on telephone pole, approx. 1000 feet *

East - (17) TLD located behind the low level radwaste storage facility. Contact the environmen-talists to obtain sample.

HP-ODCM-.13 Page 4 of 8 Environmental TLD's (cont'd)

Station Intake - (18) Located at loading pier. TLD on loading dock boom.

Hog Island Reserve - (19) See Air Sampler Location (HIR).

Bacon's Castle - (20) See Air Sampler Location (BC).

Route 633 - (21) Route 10 west to Route 633 north, approx.

2. 0 miles on Vepco pole on right side of road.

Alliance - (22) See Air Sampler Location (ALL).

Surry - (23) On Route 10 west one block prior to reaching caution light at intersection of Route 10 and Route 31 in town of Surry. On Vepco pole on left side of road.

Route 636 & 637 - (24) Route 10 to Route 634 north, approx. 1. 5 miles take left on Route 636, approx. 2 miles to Route 637. On Vepco pole on left side of road approx. 50 yards past Cobham Wharf Road (Rt. 636) and Route 637 junction .

Scotland Wharf - (25)

Jamestown - (26)

Route 10 to Route 31 north toward toll ferry. On Vepco pole on left side of road, left of the ferry ~all collection booth.

Take ferry from Scotland Wharf Jamestown. On Vepco pole on left side of to road, left of the toll collection booth.

Colonial Parkway - (27) See Air Sampler Location (CP).

Route 617 & 618 - (28) Route 31 from ferry on Jamestown side to Route 359 to Colonial Parkway. Parkway toward Williamsburg approx. 3.0 miles turn left into Smith dairy, turn left past house. Take road between out-buildings, (dirt road) to hard surface road. Take right on hard surface road, approx. 1. 3 miles to intersection of Routes 617 and 618. On Vepco pole on right side of road, at intersection.

Kingsmill - (29). Route 31 from ferry on Jamestown side to Route 359 to Colonial Parkway. Approx.

O. 40 miles on Colonial Parkway after crossing College Creek Bridge and before crossing Halfway Creek Bridge. On large pine tree on right side of road.

HP-ODCM-13 Page 5 of 8 Environmental TLD's (cont'd)

Williamsburg - (30) On Colonial Parkway follow signs to Williamsburg information center. Turn into entrance road to information center.

Approx, 30 yards from entrance on Vepco pole on right side of road.

Kingsmill North - (31) Route 199 to Mounts Bay Road (entrance to Kingsmill on the James), past guard house on Southall Road to first left on Peyton Road, take left again on Peyton Road to house #109. In backyard on pine tree.

Budweiser - (32) Route 199 to Route 60 east to stoplight at Busch Brewery. Take left at light into plant. TLD on tree directly in front of the plant.

Water Plant - (33) Route 60 east past Busch Gardens to Ron Springs Drive take right on Ron Springs Drive to gate of water treatment plant. On Vepco pole on right side of road at gate of water treatment plant.

DOW - (34) See Air Sampler Location (DOW) .

Lee Hall - (35)

Goose Island - (36)

Route 60 east to Lee Hall Village.

Vepco pole on right side of road across from Lee Hall train station.

Route 60 east to Fort *Eustis entrance road.

Right into Fort Eustis then straight past On guard building to circle. First right out of circle on Lee Blvd. until dead end in a parking lot at harbor. On Vepco pole on right side of parking lot.

Fort Eustis - (37) See Air Sampler Locati6n (FE).

Newport News - (38) See Air Sampler Location (NN).

Control, James River Bridge - (39) Route 17 across bridge to Isle of Wight side. Turn right behind state building after exiting bridge. On Vepco pole behind state building.

Control, Benn's Church - (40) At Benn's Church on Vepco pole toward rear of church on exit road near Route 258.

Smithfield - (41) Route 10 and Route 258 intersection on west side of town. A stoplight near Little's Supermarket. On Vepco pole at intersec-tion.

HP-ODCM-13 Page 6 of 8 Environmental TLD's (cont'd)

Rushmere - (42) Route 676 to Route 686 (bear right). First road to left into Rushmere Shores, take left on dirt road prior to reaching waterfront homes. Go to first intersection, on Vepco pole at corner of intersection on dirt road.

Route 628 - (43) Route 10 to Route 676 to left on Route 628.

On Vepco pole under first power line crossing on right side of road.

Milk Samples Judkins Dairy - Approx. 2.0 miles from intersection of Route 10 and Route 617. First dairy on left side of road.

Colonial Parkway (Smith) Dairy - Route 31 from James River Ferry, Jamestown, to Route 359 to Colonial Parkway. Approx.

3. 0 miles on Colonial Parkway first dairy on left side of road .

William's Dairy - Eleven miles from light at Benn's Church take right on Route 634 (Kings Fork Road),

approx. 2.0 mile~ to Route 460, across Route 460, approx. 1.5 miles on right side of road.

Epps Dairy - State Split

- State Collects - Route 617 to Route 10, left on Route 10 approx. 400 yards on left side of road.

Lee Hall (Ross) Dairy

- State Split - State Collects - Route 60 east to Lee Hall Village. On left side of road prior to reaching Lee 'Hall train station.

Well Water WW Hog Island Reserve - See air sampler location (HIR). Sample from faucet at nearest out-building by air sampler.

Bacon's Castle - See air sampler location (BC). Sample from faucet at Addison's Grocery #2 at intersection of Route 10 and Route 617 .

Jamestown - See Jamestown TLD location.

pump in picnic area, Sample from

HP-ODCM-13 Page 7 of 8 Well Water (cont'd)

Surry Station - Surry Power Station on Route 650. Sample from faucet in Environmental Science Building behind south annex.

Surface Water SW Chippokes Creek - Route 10 to Route 633 to Route 634 left to first bridge. Take sample at bridge.

Williamsburg, Waller Mill Reservoir - Colonial Parkway past visitors information center. Follow signs to I-64 (Route 132 to Route 143 north). On Route 143 north turn left under sign that reads "Richmond".

Follow road that runs parallel to 1-64 past school exit road, past school entrance road, left at next road, past Waller Mill Park entrance to reservoir on right next to road. Sample from reservoir.

Newport News Reservoir - Route 60 to Fort Eustis Blvd. (exit road from Fort Eustis). Past Fort Eustis approx. 0.5 mile to bridge crossing reservoir. Sample from reservoir.

Smithfield Reservoir - Route 10 to Route.258 west, right on Route 709 approx. 2.0 miles to reservoir on left side of road. Take sample from reservoir.

Crop Samples In Bacon's Castle area, usually from Slade's farm on Route 650 approx.

2.0 miles from intersection of Route 650 and Route 617 toward Surry Power Station and/ or from Brock's farm near intersection for Route 650 and Route 617.

2.0 RIVER BASED SAMPLES River Water Samples W Chicahominy River - obain sample from the mouth of Chicahominy River.

Surry Station Discharge Hog Island Point Surry Station Intake Newport News - sample obtained downstream of the mouth of Warwick River.

HP-ODCM-13 Page 8 of 8

Silt Samples D Chicahominy River - mouth of the Chicahominy River.

Surry Station Discharge Hog Island Point Point of Shoals Newport News Clam C Chicahominy River Jamestown Surry Station Discharge Hog Island Point Lawnes Creek

HP-ODCM-14 Page 1 of 2 SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 14 Interlaboratory Comparison Program Part Subject 1 Technical Specification Requirement 2 2 Program 2

3 Results

2

HP-ODCM-14 Page 2 of 2 I. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.D.3.a requires. that: "Analyses shall be

. *performed on radioactive materials (which contain nuclides produced at nuclear power stations) supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission. The Interlaboratory Comparison Program is described in the ODCM".

2. PROGRAM In order to comply with the above Technical Specification, analyses are performed as part of the EPA' s Environmental Radioactivity Laboratory Intercomparison Studies (Cross-Check) Program.

Participation includes the following analyses:

program Cross-Check Of

Milk I-131, Cs-137, Ba-140, K, Sr-89, -90 Water Gross Beta Gamma: Co-60, Ru-106, Cs-134, I-131, Cs-137, Cr-51, Zn-65 I-131 H-3 (Tritium)

Sr-89, 90 Blind - any combination of above

..

radionuclides

Air Filter Gross Beta Cs-137, Sr-90

3. RESULTS Results will be reported in the Radiological Environmental Monitoring Report.

HP-ODCM-A Page 1 of 1 SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL Appendix A.

Section Date Al. Meteorological Analysis A2. Liquid Pathway Analysis A3. Gaseous Pathway Analysis

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HP-OD CM-Al Page 1 of 3

SUR.RY POWER STATION OFFSITE DOSE CALCULATION MANUAL Section Al Meteorological Analysis Part Subject Page 1 Purpose 2 2 Meteorological Data, Parameters, and Methodology 2 3 Results 3

HP-OD CM-Al Page 2 of 3

1. PURPOSE The purpose of the meteorological analysis was to determine the annual

.* average X/Q and D/Q values at critical locations around the station for ventilation vent (ground level) and process vent (mixed mode) releases.

The annual average X/Q and D/Q values were used in performing a dose pathway analysis to determine both the maximum exposed individual at site boundary and member of the public. The X/Q and D/Q values resulting in the maximum exposures were incorporated into the dose factors in Tables 7.0, 7.1, 7.2, and 9.0.

2. METEOROLOGICAL DATA, PARAMETERS, AND METHODOLOGY Onsite meteorological data for the period January 1, 1979, through December 31, 1981, was used in calculations. This data included windspeed, wind direction, and differential temperature for the purpose of determining joint frequency distributions for those releases characterized as ground level (i.e. ventilation vent), and those characterized as mixed mode (i.e. process vent). The portions of release

characterized as ground level were based on .6T 158 gft- 28 2 ft and 28.2 foot wind data, and the portions characterized as m1xeo moae were based on .6T 158 _9ft- 28 _2ft and 158.9ft wind data.

X/Q' s and D/Q' s were calculated using the NRC computer code "XOQDOQ -

Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations", September, 197 7. The code is based upon a straight line airflow model implementing the . assumptions outlined in Section C (excluding Cla and Clb) of Regulatory*~uide I.Ill, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors".

The open terrain adjustment factors were applied to the X/Q values as recommended in Regulatory Guide I.Ill. The site region is characterized flat terrain such that open terrain correction factors are considered appropriate. The ground level ventilation vent elease calculations included a building wake correction based on a 1516m1 containment minimum cross-sectional area. The effective release height used in mixed mode release calculations was based on a process vent release height of 131 ft, and plume rise due to momentum for a vent diameter of 3 in. with plume exit velocity of 100 ft/sec. Ventilation vent, and vent releases other than from the process vent, are considered ground level as specified in Regulatory Guide 1. i'll for release points less than the height of adjacent solid structures. Terrain elevations were obtaine.d from Surry 'Power Station Units. 1 and 2 Virginia Electric and Power Company Updated Final Safety Analysis Report Table llA-11.

X/Q and D/Q values were calculated for the nearest site boundary, resident, milk cow, and vegetable garden by sector for process vent and ventilation vent releases at distances specified from North Anna Power Station Annual Environmental Survey Data for 1981. X/Q values were also calculated for the nearest discharge canal bank for process and

ventilation vent releases.

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HP-OD CM-Al Page 3 of 3

According to the definition for short term in NUREG-0133, "Preparation of Radiological Effluent ,Technical Specifications for Nuclear Power Stations", October, 1978, some gaseous releases may fit this category,

.*primarily waste gas decay tank releases and containment purges. However, these releases are considered long term for dose calculations as past releases were both random in time of day and duration as evidenced by reviewing past* release reports. Therefore, the use of annual average concentrations is appropriate according to NUREG-0133.

The X/Q and D/Q values calculated from 1979, 1980, 1981 meteorological data are comparable to the values presented in the North Anna Power Station UFSAR.

3. RESULTS The X/Q value that resulted in the maximum total body, ski~ and inhalation exposure for ventilation vent releases was 6.0E-05 sec/m at a site boundary location 499 meters N sector. For process vent releases, the site boundary X/Q value was l.OE-06 sec/m3 at a location 644 meters S sector. The discharge canal bank X/Q value that resulted in the m ximum inhalation exposure for ventilation vent releases was 7.SE-05 sec/m3 at a location 290 meters NW sector The discharge canal bank X/Q value for 3

process vent was 1.6E-06 sec/m at a location 290 meters NW sector.

Pathway analysis indicated that the maximum exposure from iodine-131, and from all radionuclides in particulate form with half-lives greater than 8 days was through the grass-cow-milk pat~ay. The D/Q value from venti;ation vent releases resulting in the maximum exposure was 9.0E-10 perm at a location 5150 metE:fs S sector. For process vent releases, the D/Q value was 4.3E-10 perm at a location 5150 meters S sector. For tritium, the X/Q value from ventilation vent releases rejulting in the maxim~m exposure for the milk pathway was 3 .OE-07 sec/m , and 1. 3E-07 sec/m for process vent releases at a location 5150 meters S sector. The inhalation pathway is the only other pathway existing at this location.

Therefore, the X/Q values given for tritium also apply for the inhalation pathway *

HP-ODCM-A2 Page 1 of 2 SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION A2 Liquid Pathway Analysis Part Subject 1 Purpose 2 2 Data, Parameters, and Methodology 2 3 Results 2

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RP-ODCM-A2 Page 2 of 2

1. PURPOSE The purpose of the liquid pathway analysis was to determine the maximum

. ~exposed member of the public in unrestricted areas as a result of radioactive liquid effluent releases. The analysis includes a determination of the most restrictive liquid pathway, most restrictive age group, and the critical organ. This analysis is required for Technical Specification 3.11.A.

2. DATA, PARAMETERS, AND METHODOLOGY Radioactive liquid effluent release data for the years 1976, 1977, 1978, 1979, 1980, and 1981 was compiled from the Surry Power Station effluent release reports. The data for each year, along with appropriate site specific parameters and default selected parameters, was entered into the NRC computer code LADTAP as described in NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978.

Liquid radioactive effluents from both units are released to the James River via the discharge canal. Possible pathways of exposure for release from the station include ingestion of fish and invertebrates and shoreline activities. The irragated food pathway and potable water pathway do not exist at this location. Access to the discharge canal by

the general public is gained two ways: access for bank fishing is controlled by the station and is limited to Vepco employees or guests of Vepco employees, and boating access is open to tbe public as far upstream as the inshore end of the discharge canal groin. It has been estimated that boat sport fishing would be performed a maximum of 800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months per year, and that bank fishing would be performed a maximum of 160 hours0.00185 days 0.0444 hours 2.645503e-4 weeks 6.088e-5 months per year.

For an individual fishing in the discharge canal, no river dilution was assumed for the fish pathway. For an individual located beyond the discharge canal groins, a river dilution factor of 5 was assumed as appropriate according to Regulatory Guide 1.109, Rev. 1, and the fish, invertebrate, and shoreline pathways were

considered to exist. Dose factors, bioaccumulation factors, and shorewidth factors given in Regulatory Guide 1.109, Rev. 1, and in LADTAP were used, as were usage terms for shoreline activities and ingestion of fish and invertebrates.

The dose to an individual fishing on the discharge bank was.determined by multiplying the annual dose calculated with GASPAR by the fractional year the individual spent fishing in the canal.

3. RESULTS For the years 1976, 1977, 1979, 1980, and 1981, the invertei,rate pathway resulted in the largest dose. In 1978 the fish pathway resulted in the largest dose. The maximum exposed member of the public was determined to utilize the James River. The critical age group was the adult and the critical organ was either the thyroid or GI-LLI. The ingestion dose factor, Ai, in HP-ODCM-4 includes the fish and iQvertebrate pathways. Af dose factors' were calculated for the total body, thyroid, and GI-LL organs.

HP-ODCM-A3 Page 1 of 5 SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL Section A3 Gaseous Pathway Analysis Part Subject 1 Purpose 2 2 Data, Parameters, and Methodology 2

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HP-ODCM-A3 Page 2 of 5

1. PURPOSE A gaseous effluent pathway analysis was performed to determine the

-*location that would result in the maximum doses due to noble gases for use in demonstrating compliance with Technical Specifications 3.11. B. l. a and 3.11.B.2.a. The analysis also included a determination of the location, pathway, and critical organ, of the maximum exposed member of the public, as a result of the release of iodine-131, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for use in demonstrating compliance with Technical Specifications 3.11.B.3.a. In addition, the analysis includes the determination of the critical organ, maximum age group, and sector location of an exposed individual through the inhalation pathway from iodine-131, tritium, and particulates for use in demonstrating compliance with Technical Specification 3.11.B.l.a.

2. DATA, PARAMETERS, AND METHODOLOGY Annual average X/Q values were calculated, as described in ODCM-Al, for the nearest site boundary in each directional sector and at other critical locations accessible to the public inside site boundary. The largest X/Q value was determined to be 6.0E-05 sec/ms at site boundary for ventilation vent releases at a location 499 meters N direction, and l.OE-06 sec/ms at site boundary for process vent releases at a location

644 meters S direction. The maximum doses to total body and skin, and air doses for gamma and beta radiation due to noble gases would be at these site boundary locations. The doses fro~:both release points are summed in ODCM calculations to calculate total maximum dose.

Technical Specification 3.11.B.l.a(ii) dose limits apply specifically to the inhalation pathway. Therefore, the locations and X/Q values determined for maximum noble gas doses can be used to determine the maximum dose from iodine-131, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for the inhalation pathway.

The NRC computer code GASPAR, "Evaluation of Atmospheric Releases",

Revised 8/19/77, was run using 1976, 1977, 1978, 1979, 1980, and 1981 Surry Power Station gaseous effluent release report data. Doses from iodine-131, tritium, and particulates for the inhalation pathway were calculated using the 6.0E-05 sec/m3 site boundary X/Q. Except for the source term data and the X/Q value, computer code default parameters were used. The results for each year indicated that the critical age group was the child and the critical organ was the thyroid for the inhalation pathway. In 1979, the teen was the critical age group. However, the dose calculated for the teen was only slightly greater than for the child and the doses could be considered equivalent.

The gamma and beta dose factors K , Li

Mi , and Ni in HP-ODCM-Table 7.0 were obtained by per?6rining l"unitsVXonversion i¥ the appropriate dose factors from Table B-1, Regulatory Guide 1.109, Rev. 1, to mrem/yr per Ci/m 3 or mrad/yr per Ci/m 3 , and multiplying by the ventilation vent site boundary X/Q value of 6.0E-05 sec/ms. The same approach was' used in calculating the gamma and beta dose factors K. ,

Li , M. / and Ni in HP-ODCM-T\ble 7 .1 using the process vent H'fe boBNdar?~ Q value BY 1. OE-06 sec/m *.

HP-ODCM-A3 Page 3 of 5 The inhalation pathway dose factors Pi and Pi in HP-ODCM-Table 7. 2 were calculated using the following equ:lion: pv

-~ *Pi* K' (BR) DFAi (X/Q) (mrem/yr per Curie/sec)

.where, K' .., a constant of unit conversion, 1E+l2 pCi/Ci; BR -= the breathing rate of the child age group, 3700 m3 /yr, from Table E-5, Regulatory Guide 1.109, Rev. l; DFA = the thyroid organ inhalation dose factor for child age group i

for the ith radionuclide, in mrem/pCi, from Table E-9, Regulatory Guide l'.109, Rev. l;

. 3 X/Q = the ventilation vent site boundary X/Q, 6.0E 05 sec/m, or the process vent site boundary X/Q, l.OE-06 sec/m3 as appropriate.

Technical. Specification 3.11.B.3.a requires that the dose to the maximum exposed member of the public from iodine-131, tritium, and from all radionuclides in particulate form with half-lives greater 8 days be less than or equal to the specified limits. Dose calculations were performed for an exposed member of the public within site boundary unrestricted areas, discharge canal bank, and to an exposed member of the public beyond site boundary at real residences with the largest X/Q values using the NRC computer code GASPAR. Doses to members of the public were also calculated for the vegetable garden, meat animal, and milk-cow pathways with the largest D/Q values using the NRC computer code GASPAR.

It was determined that the member of the public within site boundary would be using the discharge canal bank for fishing a maximum of 160 hours0.00185 days 0.0444 hours 2.645503e-4 weeks 6.088e-5 months per year. The j18Ximum annual X/Q at this location was determined to be 7 .8E-05 sec/m at 290 meters NW direction. After applying a correction for the fractional part of year an individual would be fishing at this location, the dose was calculated to be less than an individual would receive at site boundary.

The member of the public receiving the largest dose beyond site boundary was determined to be located 5150 meters S sector. The critical pathway was

the grass-cow-milk, the maximum age group was the inf ant, and the critical organ the thyroid. For e$ch year 1976, 1977, 1978, 1979, 1980 and 1981 the dose to the infant from the grass-cow-milk pathway was greater than the dose to the member of the public within site boundary, nearest

residence, vegetable or meat pathways. Therefore, the maximum exposed member of the public was determined to be the infant, exposed through the grass-cow-milk pathway, critical organ thyroid, at a location 5150 meters S sector. The only other pathway existing at this location for the infant is the inhalation.

The RMi and RM dose factors, except for tritium, in HP-ODCM-Table

9. 0 wer-r' calculaffX by multiplying the appropriate D/Q value with the following equation:

HP-ODCM-A3 Page 4 of 5 where, K' = a constant of unit conversion, 1E+l2 pCi/Ci;

..

QF = the cow's consumption rate, 50, in Kg/day (wet weight);

uap = the infant milk consumption rate, 330, liters/yr; y

p = . the agricultura~ productivity by unit area of pasture feed grass, 0.7, Kg/m; y = the agr~cultural productivity by unit area of stored feed, 2.0, s

in Kg/m; F = the stable element transfer coefficients, from Table E-1, m

Regulatory Guide 1.109, Rev. l; r = fraction of deposited activity retained on cow's feed grass, 1.0 for radioiodine, and 0.2 for particulates; DFL. = the thyroid ingestion dose factor for the ith radionuclide for l.

the infant, in mrem/pCi, from Table E-14, Regulatory Guide

1. 10 9 , Rev

1 ;

-1

= the d~tay constant for the ith radionuclide, in sec ;

= the decay constant for removal of a£ ivity on leaf and plant 1

surfaces by weathering, 5.73E-07 sec - (corresponding to a 14 day half-life);

tf = the transport time from pasture to cow, to milk, to receptor, l.73E+05, in sec; th = the transport time from pasture, to harvest, to cow, to milk, to receptor, 7.78E+06, in sec; f = fraction of the year that the cow is on pasture, 0.67 p

(dimensionless), 8 months per year from NUREG-0597; f = fraction of the cow feed that is pasture grass while the cow is s

on pasture, 1.0 (dimensionless).

Parameters used in* the above equation were obtained from NUREG-0133 and Regulatory Guide 1.109, Rev. 1.

Since the concentration of tritium in milk is based on the airborne concentration rather than the deposition, the following equation is used:

~- 3 = K' K Fm QF Uap (DFLH_ 3 ) [0.75(0.5/H)] x X/Q where, K"' = a constant of unit conversion, 1E+03 gm/kg; H absolute humidity of the atmosphere, 8.0, gm/m3 ;

HP-ODCM-A3 Page 5 of 5 0.75 = the fraction of total feed that is water;

0.5 X/Q

=

the ratio of the specific activity of the feed grass to the atmospheric water; the annual average co°:fentration at a location 5150 meters S sector, 3.0E 07 sec/m for ventilation vent releases, and 3

l.JE-07 sec/m for the process vent releases.

Other parameters have been previously defined.

The inhalation pathway dose factors Rii and Rii in HP-ODCM-Table 9.1 were calculated using the following equa"?7ion: pv Rii = K' (BR) DFAi (X/Q) (mrem/yr per Curie/sec) where, K' = a constant of unit conversion, 1E+l2 pCi/Ci; BR = the breathing rate of the infant age group, 1400 m3 /yr, from Table E-5, Regulatory Guide 1.109, Rev. l; DFA.

1

= the thyroid organ inhalation dose factor for infant age group for the ith radionuclide, in mrem/pCi, from Table E-10, Regulatory Guide 1.109, Rev. l; X/Q = the ventilation vent X/Q, 3.0E-07 sec/m3 , or the process vent site boundary X/Q, l.3E-07 sec/m3 , at a location 5150 meters S sector.

The GASPAR computer runs using 1976, 1977, 1978, 1979, 1980 and 1981 Surry effluent release data were reviewed to determine the percent of total dose from the cow milk and inhalation pathways for I-133. I-133 contributed less than 1% of the total dose to an infant's thyroid except for the year 1977 when the percent I-133 was 1. 77. The calculations indicate that I-133 is a negligible dose contributer and it's inclusion in a sampling and analysis program, and dose*calculations is unnecessary.*

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HP-ODCM-B Page 1 of

SURRY POWER STATION OFFSITE DOSE CALCULATION MANUAL APPENDIX B

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.;**k Revision 1

£ ~~ U.S. NUCLEAII IIEGULATOIIY COMMISSION . October 1977

\~) ~~~~!.~!2M~YGU1DE 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

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1907lOO'i0(

TABLE OF CGNT£1fTS A. INTRODtJCTICli. * * * * * * * * *.* * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

1. ?09-1 DISCUSSION ***************************************** ~ ****************************** 1.109-1

c. IE&ULATORY POSITIDN ****** ~ ******************** e*********************************** 1.109-2

1. Doses froa Ltqutd Effluent Pati..,s ********************************* ~ ******** 1.109-2

1. Potable Miter ****************************** ~ **************************** 1.109-2

b. Aquattc FDOds *********************************************************** 1:109-2

e. Shore11ne Deposits ******************************************************* 1.109-2 cl. lrrf91ted Foods ****************.***************************************** 1.109-3

2. .._. and leta Doses frm Noble lases Dtschl1"9ed to the Ataosphere * ********** 1.109-4 1.. Annua1 61191111 Afr Dose frOII Noble Sas Reluses frCIII Free-Standing Stacks Nore Than 80 Meters High ************************************************ 1.109-4

b. Annual &Inna Atr Dose fra11 All Other &as Releases; Annual leta Air Dose fran All Noble Sas lteleases ***************************** o*************** 1.109-5

c. Annual Total Body Dose frCIII Noble Sas RelHses ff'GII Free-Standing Stacks Nore Thin 80 ;:;eters H1gh ************************************************ 1.109e5

d. Annuel Skfn Dose from Noble &as RelHses from F~*Standfng Stacks Nore Than 80 Meters High **************************************************** 1.109-6.

e. Annual Total Body Dose frCIII All Other Noble &as RelHses **************** 1.109-6

f. Annua1 Skfn Dose frCIII All Other Noble Gas Releases ********************** 1.109-6

( 3. Doses frcm Rldfotodfnes and Other Rldionuclfdes Relused to the Ataosphere *** 1.109-6

4.

1. Annual Organ Dose fn111 E1temal lrr1dfatfon fram Radfonuc11des Deposited onto the &round Surface ************************************************* 1.109-7

b. Annua1 Organ Dose frCIII lnhalitfon of Radfonucltdes tn Afr *************** l.109-7

c.

Annua1 Organ Dose from Ingestion of Ataospherfcally Re1eased lld1onuc11des tn Food *************************************************** 1.109-7 Integrated Doses to the Popul1tfon ******************************************* 1.109-8

5. Suallry of Staff flosttton **************************************************** 1.109-S D. INPLEJIIENTATIC>N ***************************************************** -**** ~********** 1.109-8 APPENDIX A1 METHODS FOR CALCULATING DOSES TO MN FROM LIQUID EFFLUENT PATIIIAYS ......... 1.109-11

1. leneraltztd Equation for Cl1cu1attng ladtation Dost wta Ltqutd Pat,..ys ****** 1.109-11

1. Radfonuc11de Concentration tn Env1roraenta1 Nldta (C 1P) *******.********** 1.109-11

- Us191 (U1 p>************************************************************* 1.109-11

c. DD11 Factor (D1 tpJ>**~************************~********~******~********* 1.109-11 I. Eq111tton1 for Ltqutd Patta.ays *********************************************** ."1.109-12

- Potlb11 llater.o*********************************************************

Aquattc Foods *********************************************************** 1.109-12 1.109-12

c. Dost frOII Sho"911ne Deposits ******************************************** 1.109-12

- Dost fraa Foods '"*" on Lind with Contaatnited Matar ******************* 1.10,.:15 IEFERENCES FOR APPENDIX ************************************************************* ;. 1.109-11

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ttt

TABLE Of CONTENTS (Continued) fllDELS FOR CALCULATING DOSES FROM NOBLE 6ASES DISCHARGED TO TH£ 1.109-19

'

1. Annual 611111111 Air Dose fran Noble las Reletses fran Free-Standing Stacks More Thin 80 Ne~ers High ..*************************************************** 1.109-19

2. Annual &llffllll Air Dose from All Other Noble &as Releases and Annual leta A1r Dose from All Noble Sis Releases .**************************************** 1.109-20

3. Annual Total Body and Skin Doses frGIII Nobl_e Sas Effluents ******************** 1.109-20

1. Releeses from Free-Standing Stacks Nore Thin 80 Meters Htgh ************* 1.109-20

b. All Other Releases* .***************************************************** 1.109-22 REFERENCES FOR APPENDIX B ************************************************************* 1.109-23 APPENDIX C tllDELS FOR CAl.CULATJNG DOSES YJA ADDITIONAL PATHWAYS FROM RADIOJODINES*

AND OTHER tAotONUCLIDES DISCHARGED To THE X'tk)SPHERE .********************************** 1.109-24

1. Annual External Dose from Direct Exposure to Activity Deposited on the Cround Plane .**************************************************************** 1.109-24

2. Annual Dose from Inhalation of Radionuclides tn Air ************************** 1.109-25

3. Concentrations of Airborne Radionuclides tn Foods **************************** 1.109-25

- Parameters for Cllculatfng Nuclide Concentrations tn Forage, Produce, Ind Leafy Vegetables ***.************************** e * * * * * * * * * * * * * * * * * * * *

1.109-25

b. Parameters for Cllculating Nuclide Concentrations tn Milt **************. 1.109-27

c. Parameters for Cllculeting Nucli~ Concentration fn ~t **************** 1.109-28

4. Annual Dose from Atlllosphericelly Released Radionuc11des tn Foods .************ 1.109-28 REFERENCES FOR APPENDIX C**************************************************** ~ ********* 1. 109-29 1.109-30

1. Seneral Expressions for Population Dose ************************************** 1.109-30

2. Use of the Nod1l1 ************************************************************ 1.109-33

1. Popul1tion-Intt9rated Doses fra11 Ltqu1d Effluents *********************** 1.109-33

b. Populatfon-Intt9rated Doses from Airborne Effluents ********************* 1.109-34 IEFERENCE FOR APPENDIX D*************************************************************** 1.109-35

\.109-36

1. Envfronlllfttll Dita ******** : ************************************************** 1.109-36

z. Mulln Dita****************************************************************** 1.109-36

3. Dose F1ctors ******************* ~************************************~~******* 1.109-36

-*

4. Other P1r1111ters **************************** G******************************** 1.109-*3 I

~FERENCES FOR APPENDIX£************************************************************** 1.109-70

T*E OF CG1i1EN1S (Conttllllld)

!!i!.

APPENDIX F. IIETHODS FOR EYAL.UATill6 THE I FUIICTJON *************************************** 1.109-72

1. Drertv1tton of tile I Functton *************************************** : ********** 1.109-72 Z. Ewa1uatton of the I Functton **************************** ~********************* 1.109-75 l£FERt1CES FOR APPENDIX'*************************************************************** 1.109*80

(

LIST OF TAIL.[S 1 Slanary of Staff Position - Methods of EYalY1t1ng Ccapl11nce wftll Appendix l.o******o************************************************e******** 1.109-9 A-1 li01ttU111Ulat1on Factors To le Used in the Absence of S1te-Spec1f1c Data .****** 1.109-13 A-2 Shore-Width Factors for Use in Equations (A-5). (A-6), 1nd (A-7) ************** 1.109-15.

8-1 Dose Factors for Exposure to I Setnf-lnfinite Cloud of Noble Gases **** ~ ******** 1.109-21.

D-1 RecClllllended Values for the Transport Tfaes in the Food Distribution System .*** 1.109-32 E-1 Stable Element Transfer Dl~***********o************************************** ,.109-37 E-2 Nuclide Transfer. Paraaeters for Goat's Milk *********************************** 1.109-38 E-3 An1ma1 Cons1111ptfon Rltes .******** 8 ********************************* 8 ********** 1.109-38 E-4 RecOlllll!nded Values for Uap To Be Used for the Average Indfvfdual fn lieu of S1te-Spec1f1c D1t1 ******************************************* o * * * * * * * * * * * * * * *

1.109-39 E-5 Recoamended Values for Uap To Be Used for the MaxilllUIII Exposed Individual fn lieu of S1te-Spec1fic Data ..................................................... 1~.109-40 E-6 External Dose Factors for Standing on Contaminated Ground *************** : ***** 1.109-41 E-7 Inhalation* Dose Factors for Adults ******************************************** 1.109-,44

. .

E-8 Inhalation Dose Factors for Teenagers ********************* : ******************* 1.109-47 E-9 lnhalatfon Dose.Factors for Children ****************************************** 1.109-50 E-10 Inhalation Dose Factors for Infants ******************************************* 1.109-53 E-11 Ingestion Dose Factors for Adults .............................................. 1.109-56 E-12 Ingestion Dose Factors for Teenagers ****************************************** 1.109-59 E-13 Ingestion Dose Factors for Children ******************************************* 1.109-62 E-14 Ingestion Dose Factors for l"f1nts ******************************************** 1.109-65

£-15 Recomnended Values for pther Par111eters *************************************** 1.109-68 UST OF FIGURES Ff pure £!.9.!.

F*l Staff..Wrttten Colnputer l1sttng ********************************** o********** 1.109~76.

F-2 f11111w1-Written Cc.iputer Ltsttng ****************** *************************** 1.109.;78 wt

A. lfflOIUTION Appendix I, -...rtca1 Cut des for Design Objecthn 1nd Ltaittng Conditions for' Operation to Meet the Criterion 'As Low As Is Reasonablf Achievable' for Rad1oatt1ve Nateri11 tn Light-llater-Cooled Nuclear Power Rt1ctor Effluents, to 10 CFR Part 50 provides ru11rfe1l guidance for radfo,ct1ve effluent design objtcthes Ind technfcal specfficatton 1"9quiraents for 11aitfng conditions of ope~at1on for 11ght-.. ter-coo1~ nuclear poii,ar plan~. *

To fapleaent Appendht I, the lltC staff Ills developed I series of guides that provide *thods 1ccept1ble to the staff for the taltulatfon of preoperattonal estf111tes of effluent releases, dispersion of the effluent in the 1t.osphere and different water bodies, 1nd est1111tfon of the associated r1diatfon doses* to aan. This guide describes. &llsft features of these taltulattonal

~els end s~gests ~r!l!!!ters for the esti~tfnn of r~dfAtfnn doses to !l!!ln frt!II efflyent releases.

The aethods used herein are general approaches that the lltC staff Ills developed for 1ppl1t1tion fn lfeu of specfffc par1111eters for fndivfdual sites. The use of site-specific values by the applicant 1s encouraged. However, the ISSllll?tfons and aethods used to obtain these parueters should be fully described and doc1111nted.

Portions of tll1s guide supersede Regulatory fiufde 1.42, Revision 1, *1nterf11 Lfcensfng Polfcy on as Low as Practftable for Gaseous Radiofodine Releases fro11 Light-Water-Cooled Nuclear Power Reactors,* .tifch has been withdrawn.

lo OlSCUSSIDN Appendix I to 10 CfR Part 50 provides guidance on the doses to aembers of the general public resulting from effluent releases that aay be considered to be as low as ts reasonably achievable. This guide.describes baste features of the calculational IIOdels and 1SS1111Ptions tn use by the NRC staff for the estf .. tton of closes.

Appendht A of thfs guide describes Slfigested aodels and ISS1111Ptfons for calculatfng the

1stf11111ted doses to 111n from discharges to.the tt,drosphere. Appendix I of thfs gufde describes suggested aodels and 1ss1111ptfons for calculating doses fram noble gases dfsch!rged to the atmos-phere, and Appendix C gfves IIOdels and 1ss1111ptfons for estt11111tfng doses from radiofodfnes and other radionuclides released to the atmosphere. Appendix D describes the 1110dels and assumptions for calculating population doses (111an-N111 and 111an-thyroid-ran) from radfonuclfde releases to the atmosphere and hydrosphere. Appendix£ presents tabular data pertaining to two or 110re of the other appendices. Appendix F provides a dfscussfon of, and derfvatfon for, the I function used tn cmaputfng 91111111 doses fro11 elevated noble gas rel11ses.

In provfdtng guidance for tmpleinenttng Section II of Appendix I, the NRC staff his *de use of the aaxf1111111 exposed fndivfduel approach. In thfs approach the nuinerfcal design objectives of Section II are COllplred to the calculated r1df1t1on exposures to auilMIII fndivfduals in Heh of four age groups.

The population ts considered to be .. de up of infants (0 to 1 ye1r), children (1 to 11 years),

teenagers (11 to 17 years), and adults (17 years and older). For the purpose of e~luatfng dose comnftinent, the ..xfllUII infant fs asslllled to be newborn, the .. xflUTI child 1s taken to be 4 years old. the 11ut111.111 teenager 15 taken to be 14111rs old. and the ..xtain adult ts taken to be 17 ,ears old.

Naxhu1 individuals are characterized as -..x1a111* wfth regard to food cons~tton. occupancy, and other usage of the region in the v1cfnfty of the plant site and as such represent tndtvfdu1ls with habits representing reasonable dev1at1ons fran the average for the population tn general.

In all physiological and aetabolfc respects the maxi1111111 exposed 1ntf1w1duals are assiaied to have thosi chir=cter1st1cs that ropresent th! evtreges for ttletr corresponding ege group 1n the general In this gufde, the ter11 *dose,* when app11ed to tndivfduals, ts used tnstead of the aore precise tel'WI *dose equivalent.* as defined by the Jnternattonal C011111fssfon on Radio1ogfca1 Units and Neasur1111ents (ICRU). lnlen applttd to the evaluation of internal deposition of ndtoactfvfty, the tenn *c1ose,* as used here. includes the prospective dose to11POnent arfsfng froi_retentfon

- tn the body beyond the period of tnvfronnental exposure, t.,.!. the dose ccaaftatnt. The dose COllll1taent ts evaluated over I period of 50 111rs, -

1.109-1

popul1tfon. Althouvh.specfffc fndivfdu&ls w1111laost certlfnly display dietary, '9Crettion1l, and other lfvfng habits considerably different fl'GII those suggested here, and actual phystologtcal and aetaboltc par111etel"S 1111 vary consfderlbly, the laC staff consfdel"S the

x i - uposed tndhidual to be I w11-deffned reference for fapl-ntatfon of Section II of Appendb J. The wracterfzatfon of *xflUII exposed tndfvfduals ts subJect to contfnuf119 revfew _, the laC staff, and the 1pp1fc1nt ts encouraged to use 1nforwtfon 1nd data applicable to I specfffc region or 1tte when possfble. Mhere sfte-spectftc tnfor91tton and data fs IISed, fts justfftc:atfon should M *atnted for the *c staff's Nvtaw.

Sha the radfatfon don caaftaent per unft fntate of a 1fwtt1 f'ldfonuclfdt usually wartes as I function of 1ge., *four sets of fnternal dose converston factors hive been calculated. These dose factors are 1pproprf1te for the four dffferent age groups defined above. Specfftc1lly, these dose factors are based on contfnuous fntate over I OM-year enviroraental axposUT"e period and an 1ssocf1ted dose CG1111itaent utendfng over

S0-1*r ,.rfod fram fnftf1tfon of fntate.

The IIOdels and usiaptions described tn Appendfces A, I, C, and D of tllfs gufde are Keept-able to the IIRC staff for calcul1tfng doses to tndfvfduals and populatfons. If other IIOdels are selected, they should include the s111e exposure pat,-ys consfdel"ed fn the models described fn thfs gufde. The 1ssi,11pt1ons and aethods used should be fully descrfbed and dociaented.

As discussed fn Sectfon 111.A.2 of Appendix I to 10 CFR P1rt 50, tlle ~1fc1nt *1 take fnto account any rHl phenomna or 1ctual exposure conditfons. Such condittons could include actual values for agricultural productfvf~. dfetary habits, residence tiaes, dose attenuation by structures, aeesured envirornental transport factol"S (such 11 bfoaccwnulltion factors), or sfmflar values actually determined for I specfffc sfte. The 1pplfcant should provide enough fnfonr.atfon on the 11easurements or other aethods used to dlrfv1 these substftute values to en1ble the NRC staff_ to ev~l-~te thti~ _w~114J!f..* .*;_, ., .,_, . -:¥-i'. . ~ -* . .. .

<'U"** * ,,:.;Jj, .~;;ft .,-;,iiJis~l~idli .,Jiji:*;Jji*~f~*jJ ~-

[quatiOnS are provided below by lfflfch the IIRC staff wf11 estf*te radfatfon exs,osure for

xill\lll fndfvfduals and the population within SO afles. These equetfons are 1ppr"Opr'i1te for the

exposure pathways that the staff routinely considers fn tts evaluations. In 1ddft1on, other exposure pathways that 1111y arise due to unique condftfons at I specific stte should be considered tf they ire lftely to pr"Ovide 1 1ignfffc1nt contribution to the total dose. A pathway ts con-sidered significant ff I conservatfve evaluatfon yields an 1ddfttonal dose tncl"lllltnt equal to or aore thin 10 percent of the total from 111 pat'*',ys consfderecl tn thfs gufda.

1. Doses from Liquid Effluent P*thi!n The NRC staff will ca1cu11te radiation doses fran potable wter, equatfc food. shoreline deposits, and frrfg1ted food pathways by usfng the following equatfons, whfch ire described *fn detefl fn Appendix A of this gufde.

- . Potlble Mater R1 pj

1100 u*p"e .{

.

Q1D1 fp.,.xp(*l1t,> (1)

. a,. Aquatic Foods u " .

apj

1100 ~ i QtltpD1tp.,.xp(*l1tp)

/" (2)

c. Shoreltne 11,osfts U NII

apJ

110,000 ¥ f 1T1Datpj [up(-11t,)][1. - up{-11~)]

Q (3)

d.. lrrtgated Foods For 111 radionucltdes ucept trtt11111:

~

~nt*l

+ ap

.

1pj

Uap { d1exp(*ltth)D1tpj

.*

f 111v[l f

[r[l

exp(-1Eit1 )] f 111v[1

exp(-1 1tb)]]

{ FtA0atpj Q,:d1*xp(*l1th)

- exp(-1 1ta,)l]

'*lEt *

[r[l - exp(-1E 1t 1 )]

}

f 1 V £1 Plt

+ Pl I

ct,,_Q,,_ (4)

For trttt1a1:

1pj

u::9cvD1pj

U:~1..1Dapj ~A(tvQF + c,_~,.> (5) where

tp ts the equ111br1UIII bfoacc1111Ulatfon factor for nuclide 1 1n l)lthway p, expressed 1s the ratio of the concentration fn biota (1n pCf/kg) to the radionuclide concentration tn water (tn pt1/11ter), tn 11ters/kgi

1v ts the concentration factor for uptake of r1d~onuc11de i fran 1011 by edible parts of crops. tn pCi/kg (.et .eight) per pti/kg dry 1011; CtAw ts the concentration of r1dfonuc11de f tn ..ter cons&llled by 1ni*ls, fn pti/11ter; ctv ts the concentration of radfonuclfde 1 tn ~tatfon, tn ptf/kgi D11pj ts the dose factor, specff1c to a g1ven age group 1, radionuclide f, P1thway p, and orvan j, which can be used to calculate the radiation dose fran an intake of I r1dionuc11de, tn arem/pC1, or from exposure to I given concentra-

tion of a radfonuclf~e fn sedfinent, expressed as a ratio of th~,dose rate *

.(1n arem/hr) 1nd the areal red1onuc11de conc:entret1on (1n ptf/-,.)i d1 ts the deposftfon rate of nuclide 1, tn pC1/r.2 l:"r hr; F ts the flow nte of the 11qutd effluent, 1n tt3/sec; fl ts the fraction of the yar crops are trrtgated, di*ns1onless; FtA ts the stable 1l1111ent transfer coefffc1ent that relates the daily intake nte

,Yan anfaal to the concentration tn 1n edible portion of anf111l product, tn pC1/11ter (aflk) per pC1/dly or pti/kg (anf*l product) per pC1/dlYi.

", ts the atxtng ratio (rectprocal of the d11ut1on factor) 1t the potnt of exposure (or the potnt of w1thdr...1 of drtnktng .. ter or point of harvest of aquatic food), diaens1onless,

, h the 1ff1et1vt *surface dens tty* for son 9 tn kg(dry son )/112 ,

a,. h the conslllll)tfon nte of contulinated ..ter by 1n ani*l, 1n 11ters/dly; QF ts the con11111Ption rite of contul1natld fHCI or forage by. an 1nt*l, tn lg/clay (..t .. tght),

Qt h the r;1a11 ,-;tt of =ic1tcb t. tn Ct/yr; r h the fraction of deposited 1ct1vtQ ntatned on crops, ftaeniionless.

h the total 1nnual dose to ort1n j of tncltwiduals of *tt ll"OUP 111

apj of tM ftUC:1 tdes i tn patt..11 p, tn --,yr-, * :I fNII

(..

1.109-3

ts the pertod of tt* for Witch Ndt*nt or soil ts exposed to the contaminated

ter, tn flours, *

ts the tt* period that crops are exposed to contamfnatton durtng the growing suson, tn hours;,

ts I taoldup ti111t that represents the ttae tnterval bebleen harvest and cons&111ption of the food, tn taours, ts the radioactive taalf 11fe of nucltde 1, tn days, ts the average transit tf111t required for nuclides to reach the point of exposure. For internal do*se, tp ts the total tfae elapsed between release of the nuc11des and ingestion of food or *ter, fn taours, ts I usage factor that specifies the exposure ti111e or tntake rate for an 1ndfvfdual of age group I associated with pathway p, tn hr/yr, 1/yr, or lg/yr, ts the staorelfne width factor, dtaensfonless;

" ts the agricultural productivity (yield), fn kg(.-et .-eight)/m2 ,

- fs the effectfve ""90Va1 rate constant for*iscfiOl'l~t11de 1 from crops, tn hr-l, where 1E1

11 + \.* 11 1s the radioactive decay constant, and lw 1s the

. f,!'.fl*. ;, 'fl=~*,,.,,

.

~,.-...,.remov.~l rate constant for physical Tabte*t-15);

loss bi weathering (see Appendix E, 1

1 ts ihe radfoactfve decay constant of nuclide 1, fn hr-1.

1100 1s the factor to convert fn1111 (Ct/yr)/(ft3/sec) to pCt/11ter, and 110,000 ts the factor to convert from (Ci/yr}/(ft3/sec) to pCi/liter and to account for the proportionality constant used tn the sediaent radioactivity aodel.

These equations yteld the dose rates to various organs.of individuals from the exposure pathways mentfoned above. Appendix r of 10 CFR Part 50 requires that the annual doses or dose C0111T1itments to the total body or any organ of any tndfvfdual from the s1111 of the exposure path-ways from lfqufd effluents assoctated with Heh reactor should not exceed 3 arsn and 10 .,..,

respectively.

2. 111111111 and Beta Doses from No&le Gases Dfschlraed to the Atllosphere

. The NRC staff will calculate radiation doses from noble gases using the following equations from Appendix B of thts gufde. Atmospheric disperston IIOdels are found tn Regulatory Guide 1.111,

Methods for Estf1111ting Atlnospherfc Transport and Dispersion for Gaseous Effluents on Routine Releases from Lfght-W.ter-Cooled Reactors.* *

1. Annua1 Ga1111111 Air Dose fram Noble Gu Re1eases fran Free-Standing Stacks Nore Thin 10 Meters Miah (6) 11 the ptaoton yf1ld for 9111111-ray ptaotons tn 1n1rgy group t fna the decay of ndionucUdt f, tn photons/dbtntegratfon, h the annual . . - atr dost at I dtstanct r (*ters) tn the sector at angle e, 1n .,.,d/yr, ts the energy of the ktta ptaoton energy group, tn NeY/photon, 1.109-4

ts the ,tofnt fr1q"uency of occurrence of 1tab1lfty class I and wind speed class n for MCtor ** dfaen1fonl111; ts the tlfaenstonltH llllltf'1cal tnttgratfon constant 1ecountfng for the

~tstrtbutfon of radfoacttvtt., 1CCordfr19 to ..ttorologfc:al condftfons of wfnd speed (u) and 1taosphtrtc stabflft., (sJ .tlfch tn part detel'Wlfne the effective atact hefght (H) and tilt werttc:al pl..e standard clevt1tton (o2 ). In 1ddftfon, I ts I function of the photon anergy E11 Ind ts T

T1 + tT2 11 fDf'llllllted fn S11~e (Appendix I, Reference 1).

ts the release rate of ndtonucltcle f, corrected for decay during transit to the distance r under wind speed un* tn Cf/yr;

. .

fi the *an wfnd speed of wfnd speed class n, tn II/sec; h the sector width over witch 1t11ospherfc condfttons are averaged, tn radians; h tM efr eergy absorption coefftcfent for the kth photon energy group, tn

.- 1* Ind .

160 ts the conversion factor to obtlfn D"(r,e), tn arad/yr, and his the unfts of ar1d-r1df1ns-ml-dfsfntegr1tfon/sec-NeV-Cf.

b. nnua1 61111111 Afr Dose from A11 Other Nob1e &Is Releases; Annua1 Beta Afr Dose from All oble &as Releases (7) where are the 91111111 and beta *fr.dose factors for I unffonn 111111-fnffnfte cloud of radfonuclfde f, tn ar1d-a3/pCf-yr;

D'(r.e) o.r D8(r,e)

Qt

\

are the annual 911111111 and beta 1fr doses at the ct1stanct r tn the sector 1t 1ng1e e from the discharge pofnt, fn arad/yr; ts the release rate of the radfonuclfde f, tn Cf/y~;

[x/Q]D(r,e) .ts the annual average gaseous dfspersfon factor (corrected for radfo1cthe decay) at the distance r fn sector e fn sec/rn3 (see Regulato"Y &ufde 1.111,

ttethods for Estf111tfng Atllospherfc Transport and Dfspersfon of Caseous Effluents fn Routfne Releases fr'OII Lfght-Water-Cooled Reactors,* for *thods to estf*te x/Q); and J.17a104 ts the IU!ber of pCf per Cf dfvfded by the IUllber of seconds per year.

c. Annual Total Body Dose fn1111 Noble las Releases from Free-Standing Stacks More Thin IQ Meters Hfah 1

D (r,e)

1.11 S, I D~(r,e)expt-~!<Et)td] (8) ta the annual total lloQ dose at till dfltance r tn nctor ,. tn .,.Jyr;

ts the annual , . _ atr doH associated with the kth photon . .rgy group at the distance r tn sector ** tn arad/yr;

.(

1.109-5

11 Ute 1ttet1u1tton factor that accounts for the dose reduction due to shftldfng provided by restdtntt1l structures. dtaenstonltss.

ts tM product of tfssue denstty and depth used to dtterw1ne

total body ese. tn 1/m2*

ts Ute tfssue energy 1bsorptfon coefftcfent. fn m2/g; and ts the 1ver1ge r1tto of tt1sue to 1tr energy lbsorptton coefftctents.

d. Annual Skin Dose fNIII Noble &Is Releases fNIII Frte-Stlndfna Stacks Nore Thin 80 Meters High (9) ts the beta slcfn dose factor for I s1111f-fnftntte cloud of radionuclide f, lllhfcn tncl~es the attenuation by the OMter *dead* layer of the sltin, 1n wem-t113/pCt~yr. and fs the annuil sttn dose at the distance r tn sector e, tn .,..,.,r.

All other paraeters are IS defined in preceding paragraphs.

,. Annual Total Body Dose from All Other Noble 6as Releases (10) ts the total body dose factor for 11t111i-fnftnfte cloud of the r1dfonuclfde 1,

.tlich includes the attenuation of 5 g/an2 of tissue, fn arein-113/pCi-yr; ts the annual total body dose due to tanersfon fn 11e111f-tnfinfte cloud at the distance r tn sector e, tn ..,../yri 1nd x1(r,e) fs the annual 1ver1ge ground-level conc:entr1tfon of r1dfonuclfcle f 1t the distance r tn sector e, tn pCi/113

All other par. . ters are IS dtftned above.

f. Annual Slcfn Dose from All Other Noble Cas Releases (11) where ts the annual attn dose due to t-rston tn 1 . .1.tnffnfte cloud at the distance r fn sector e, tn .-./yr.

All other p1r1111eters lrt II defined above.

J. poses from Radiofodfnes and Other Rldfonucltdes 0 Rm1eased to ttie Atmosphere The NRC stiff wtll calculate r1df1tf0fl doses frea radfoiodfnes and other r1dtonuc1tdes nlused to the 1t;ac,sphere using thit following equations fra11 Appendix C of ttits 1ufde,

Not tnc1udfng noble 1111s.

1.109-6

. .......... - ...... .,. - . .. -* . ,,_ ... .

- tnual ~n Dose fraa Extem11 Irradiation fNIIII bdionuclides Deposited onto the round ur ace .

(12) ti tM ground plane concentration of rad1onuc1tde 1 at distance r 1n sector 1, tn pC1/*'i ts the open field tround plane close conversion factor for org1n j ff'CIII radio-llUC11de 1, 1n .....2/pCi*hr,

ts the amual ese to tM °""" j at location (r,e), tn wa/yr; ts I shielding factor that accounts for the dose reduction clue to shielding provided by residential structures d"r1ng occupancy, dtaensionlessi and 1760 1s the ftlllber of hours 1n 1 ,ur.

b. Annual Oraan Dose from Inhalatton of ltadionuc11des tn Air (13) ts the annual dose to organ j @f i~ 1nd1w1dual tn the ege group~ ~t location (r,e) due to tnhllation, 1n artlll/yri ts the 1nha1atton dose factor for radtonuc11de 1, organ J, and age group .1 1 1n IINIII/ pC i i ts the annual 11r intake for tndtviduals in the age group 1, tn a 3/yr; and f! the annual average concentration of radtonuclide t tn atr at locatton (r,e), tn pCt/m. 3

c. Annual Organ Dose from Inaestion of Atmospherically Releesed"Radionucltdes tn Food where C~(r,e), ~(r,e),

~(r,e), C~(r,e) are the concentrations of radtonucltde 1 1n produce (non-leafy-vevetables, frutts, and grains), atlk, leafy Y19etables, and 111at, respectively, at

location (r, e), 1n pCi/tg or pCi/&i is the annual close to the Drttn J of 1n tncltvtdual tn age yroup I froin tngestton of produce, a11k, leafy vegetables, and aeat at ocation (r,e), in Sf'flll/yri \__

1s the ingestion close factor for radionuclide t, organ j, and age group**

tn --.,pet, fg,f& are the respective fractions of the 1f19est1on rates of produce 1nd 1Mfy vegetables that are produced tn the garden of tnteresti and u:. '-* .,.. ~ are the amual tntake (usage) of produce, a11k, 111at, and 1Nfy "9ftables, nspecttwely, for tndtvtduals tn the age group 1, tn kg/yr or 1./7" (equivalent to u1 p>*

,.,...,

4. Integrated Doses to the Population The NRC staff wtll calculate integrated doses to the local populltfon fl"CIII 111 pathways discussed in Sections C.1, 2, Ind 3. lec1use of the various cond1t1ons under lllfltch the equa-tions 1n Appendix D ire ustd, they are not pre5ented tn this section. It 1s recam!nded that Appendix D be read for I detailed d1scuss1on of tt. staff's IIINlels.

S. S1a11111ry of Stiff Positfon A brief s""'111ry of the staff position on aethods of ev1luat1ng ~Hance with the nainericel tu1des for design objectives of Appendix I 1s presented 1n Table 1. Methods of evaluating compliance with the cost-benefit provisions of Appendix I ire addressed in Rt9ul1tory 6uide 1.110,

cost-Benefit Analysts for Rldlilllste Syste11S for Ltght-W1ter-Cooled Nucleer Power Reactors.*

D. INPLEMEKT'ATION The purpose of thts section is to provide 1nforsat1on to applicants 1nd licensees regarding the NRC staff's plans for ut111zing this resiulatory guide.

This guide ref~cts current Nuclear Regulatory CDlllllissfon practice. Therefore, except fn those cases fn which the license applicant or licensee pl"Oposes an acceptable alternative method, the 11ethod described herein for complying with specified portions of the CC111111issfon's regulations is being ind will continue to be used in the evaluation of submittals for operating license or construction permit applications until the guide is revised as I result of suggestions from the public or additional staff review.

i.

1.109-1

TABt.E 1 SIMRY OF STAF'F POSITION*

METll>DS OF EVALUATING COMPLIANCE WITH APPEWOJX I nPE OF DOSE APPOeJX t*

DESIGN OIJECTIYES 111-50-2 DESIGN OBJECTJffl*

. POINT OF DOSE EVALUATION (QMTI-TO BE usm Lt!l!td r,n11111ts DDH te total 1-, J .,.,,,. ,... ant t S ..,,_,,,. per stte locatton of tlte 1, f, J. 4, IS.

fna 111 patlMlys htghlst dose offstte ...

. . 111 fraa to "" °""'"

p1thwllys 10 . .,,,. per untt S .,.,.,Jf' per sfte S1111 IS 11Mtft

1, 2, J, 4, I 5

--

. IIDtt-trftt* N1NMI

.._ r,n11111tsi...

. --- 5 Cf/Jf' Pl" unft. . - -- . ---

I I

Gala . , . 111 11tr 10 .,..d/yr per unft 10 flff'ad/,r per stte Locatfon of tM I or 7, 11 highest dose offsfte.* 1pproprt1te leta dos* tn 11, 20 and/yr per unf t 20 ,,,,.,d/Jf' per stte S.. IS lboft. 7 Dos* to total IM>dJ 5 .,..,,,. per untt 5 8"11/Jf' per stte Loc1tton of the I or 10, 11 of 1n tftdtyt.,.._1 highest dose 1pproprt1te f

offstte.**

Duse to 1Hn of 111 15 .,.,,,. per untt 15 llf'f!M/Jf' per stte S... II above.' , or 11, 11 tndfyfdUll 1ppro,rt1te See footnotes 1t end of tibie, on followtng pa*ge *

.'

TABI.E 1 (Contfnued)

SIJIMRT Of' STAFF POSITION -

M.IHOOS OF EVALUATING COMPLIANCE WITH APPENDIX t APP£11Dll fit RM-50-Z POIIIT OF DOSE ~IONS DESIGN OBJECTMS DESIGN OBJECTIVES* EVALUATION TO BE USED ltldfotDdlnn 11111 Partle11l1testt Re1Nsecl to the Atllospflere DMe to 11,, or,an 15 --,.,.,. per unft 15 Jfll'f!.fl/yr per site Locatton of the 12, n,

14 fra 111 pathNlys highest dose offslte.*++

-. . .

--

1 Cf/yr per unft

.

....E,aluated for 1 *

f - fnd1Yfdul1, H clescrll,ed fn Section B of thfs guide.

'

...

0 Enl*ted 1t I loc1tfon tfllt ts 1ntfcfpated to be occupied dul"fng plant ltfetf* or e,11uated wftlt respect to such potential land and 111ter usage and food pathNlllys H could actually exist during tfle ter111 of plant oreretion

C.le11l1hd on1, for dle gases.

tvaluatad 1t I loc1tfon tfllt could be occupied du"ring the ter'III of plant operation.

"'Dnn due to cartion-14 Ind trlttmi tntalte frm terrestrial food chafns ere fncluded In this category.

tttEv11uated It I loc1tton llfleN 1n exposure pat'*'Y ind dose recei,tor actually e*tst 1t the tiae of lfcenstng. Nallleffl', ff the 1pp1fe1nt deten11fnes desfgn of,Jectfves wtth respect *to*radioactive fodine on the blsts of existing conditions and ff potentf11 changes In land and wter usage and food patfMys could result fn exposures fn excess of the guideline values ghen above, the 1peltc1nt should provide reasonar>>le assurance that a IIIIHlftoring and su"e111ance progr* will be perfoniecl to detenrtne:

(1) the quantftfes of radtoactf.e todfne actually released to the atlllosphere and deposited re11ttve to those estf*ted In the dttffat111tiOt1 of desfgn of>Jecttves; (2J llflether cfllnges fn land 1fld water usage and food pathways Nhtch wuld result in tndhtdull e-,osures greater tflln orfgfnally estf11111ted have occurred; and* (3) the content of radtoacttve tDdfnt tn foods tmolnd tn the changes, ff and .tten they occur.

_I

(

APPENDIX A ll£11l)DS FOR r.ALCULATJIC DOSES TO MN FION LIQUID EFFWENT MTIIIAYS The equattons for estt.. ttny r1df1tton exposure to .. n fran four prfnctpal exposure path-ways tn the *quatfc envfrol'alent potable .. ter, aquatfc foods, shoreline deposits, Ind frrfgated foods) *re listed tn S.ctfon C, *1egul1tory Posftton,* of ttlfs gufde.

1.

. &cneralfzed Equation for Ca]culatfnq Radfatton Dose *1* Lfqufd Pathwa,YS

£quatfon (A-1) ts the generalized equatfon for calculatfng the r1df1tfon dose to .. n vfa 1tqufd effluent pathways.

(A-1) 11 the concentratfon of nuclide t tn the lledia of path1iay p, tn pCf/1, pCt/tg, or r,t.tta2i 1s the dose f*ctor, specific to age group a, radfonuclfde t, pathway p.

and organ J. Jt represents the dose due to the tntllce of a radionuclide, 1n artffl/pCf, or from exposure to a given concentratfon of a r*dfonuclfde fn sedf1111nt, 1n *rain per hr/pCt per a 2i fs the I nnua 1 dose to orva n J of' an tndtvf dua 1 of age group a frmi nuc 1f de 1 wta pathway p, 1n arr,n/yri and fs the exposure tf11e or tntlte rate (usage) assocflted wtth pathlilly p. for age group a, tn hr/¥", &/yr or tg/yr (as appropriate). *

( The three factors .. ttnsi 1p Equation (A-1) are discussed tn the *following sectfons, 1110st of

which were taken dfrectly from the WASH-1258 report (Ref. 1). (An updated versfon of the portfon of itie WASH-12S8 report descr1bf119 IIOdels and CCll!puter progrcms ts cont1fned 1n the BNWL 1754 0 report (Ref. 2).) -

a. ladfonucltde Concentratfon tn Envfro1111ent1l Nedta (C 1p)

The concentratfons fn envfroranentll lledfa of interest can be estf1111ted from the mfxfng ratio",* the discharge flow F, the radfonuclfde release rate Q1, and other teMIIS presented 1n the pathway- equations thlt appear later tn this dfscusston.

,. Jl!!ll. cu1 ,>

The second tenn of Equatfon (A-1) ts the usage tena u ,. Usage 1s expressed as a 1

cons1111ption rate tn tg/yr or liters/yr or as an exposure ti* tn hr/yr, as appropriate for the pathway and age group under constderatfon.

Tht llRt stiff encourages the use of stte-ss,tc1ftc dltl, wntver posstblt. Such dAtl should be doc1111ented. Jn the absence of s1te-spectffc dltl, however, the usage values (cons~tton rates and exposure tf*s) pruenttd tn Appendix E, Tule E-5, are r"Kllllltllded.

c. Dose Factor (Dafpj) .

Dost factors for tnternal exposure vta tngestton are provtded tn Appendix E, Tables E* 11, U, U, and

std.

1,. AppendiJl E .a1£0 pn,vfdes fwtli.r dfscuHton of the dlt!, l!!IIOdel!, end IHl.!lll!)tions

.

Mltertal deposited froa Hdfl1entAtfon tn an equatfc 1,sta represents a fafrly large, Marly untfor11 thtn sheet of contuinatton. Thi factors for converting surface mntaatnatton then tn ~t/rl to the dose rate at one *ter abovt

untfora1y mntutnated plane dHcrtbtd by So1dlt Aftd others (lefs. J and 4). Dose fa~~" for exposure to 1011 lldiaent haft

.,..we been ntts of .,./hr per r,t.tta2 and are prisentld tn Appendta £. Table E-1. .

( . 1.109-11

-.

2. Egua tions for Li gut d Pa thwYS This section develops the equations required for the liquid patllllly IIOdels. The principal difference between pathways fl the llilnner tn which the radfonuc11de concentrations ire calculated.

The doses fl"OIII the four patt.ys 1flould be added to dttennine the total dose,

a. PDtlblt Miter The annual dose' fn111 ingestion of *tar ts calculated fraa Equation (A-2) below:

R,pj

1100 *-{ Q1D11~jexp(-i1tp) (A-2)

Sywt,ols for this equation .ere defined earlier. tn Section C.1 of thts gutde.

The s1111111tion process adds the dose contribution fNIII each nuclide to yield the total dose for the pathway-organ clllllbinetfon selected. The expression (1100 QiMp/F)exp(-~itp) yields the concentration of nuclide t It the time the *ter ts cons111ed, tn pC1/&. This concentration ts the tel"'III c1P tn Equation (A-1). As I atni11111111, the transit time tp lllly be set equal to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to allow for r1dfonuclide transport through the water purification plant and the water distribution system (Ref. 5). The transit tfae should be increased as appropriate to allow for travel frora the point of effluent release to the water purfffc1tion plant intake. Credit 1111y be taken for radionuclide removal by water purification processes using techniques such 1s those outlined tn Reference 3.

Jt should be noted that, depending on the hydrological dfsperston IIOdel employed, the

ixing ratio, Np* or dflutfon factor aay no~ be explicitly defined. Jn those instances (e.g .*

buildup of activity in I coolfng pond), the relative concentration in the ~txed stream (compared to the effluent concentration) 1111y f>e supplied as* function of the r1dfologicel decay constant.

wfth any potential effluent recycling taken into account. Suggested hydrological dispersion.

aodels are presented tn Regulatory Guide 1.113 1 *Estt1111tfng Aquatic Dfspersfon of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix 1.*

b. Aquatic Foods The concentrations of radionuclides in aquatic foods ire a,slllled tc be directly related to the concentrations of the nuclfdes fn .ater. Equilfbria,n ratios between the two concentrations.

called bioacc&a111Jlatton factors in thfs gutde, can be found in the literature (Ref. 6). The inclusion of the bfoacc""'latfon factor s1P in Equation (A-2) yields Equation (A-3), which ts suitable for calculating the internal dose fr'OII consumption of 1quatfc foods.

~

R1 pj

1100----,---- i_Q1B1pDafpJexp(-1 1tp) (A-3)

Values of lip ire gfven tn Table A-1i the other -,arueters hive been previously defined. The aethodology presented 1n Reference 7 for the development of stte-specfffc frestwater bfoacc111111la-tion factors ts considered to be acceptable l>>y the NRC stiff.

The transit t1111e tp *Y le set equa1 to 2C hours* to allow for radionucltde decay during transit through the food cllafn, as *11 as during food preparation.

c. Dose from Shoreline Deposits The ca1cu1at1on of tnd1vtdua1 dose f,- 1hore1fnt cltpostts ts coapltx stnce tt involves estt*tfon of Mdi11ent load, transport, and concentratfons of radionuc11des assoctated wtth 6

11tre, and tn I IIUllbtr of other f111tlncu 11 tilt 11H: staff Ills found tt ..cessary to Mt forth 1utdlnce II to I paraMter Y&lue tn the 1henct of l!llp1rtca1 data. Jn such tnstances judgnlents have been *de 1fter eonstdertng values assUBed l>y others and IIOdel sensftfvtty to.the p1ra111eter

value tn q111st1on. In thh particular tnstlnct, t~" total_llody dose fn111 ftsh tngestton. for

typical 1ftuatfon 1 *s found to vary ., 1ns tlliln I factor of blo for I range of *vtromental I transit tt*s of frm one to NVtn days.

1.1D9-12

TMLE A-1 IIOACCINILATION FACTORS TO 1£ USED IN THE ABSENCE OF SITE-SPECIFIC l!TA (pC1/kg per pC1/l1ter)*

I FRESHWATER SAl.1'1Mmt ELEMENT FISH IIIYERTEBltATE fil!i INVERTEBRATE H t.DE-01 t.DE-01 t.OE-01 1.3£-01 C 4~6£ 03 ,.u 03 1.IE 03 1.4£ 03

,

11A 1.DE 02 1.DE 05 Z.DE 02 2.DE 04 l.7E-02 2.tE 04 1.tE-01 3.0E 04 CR 2,(£ 02 2.GE 03

e.OE 02 2cOE 03

FE 4,DE 02 1.DE 02 I.DE 04 3.2£ 03 S.SE 02 3.0E 03 4.0E 02 2.0E 04 co s.ot 01 Z.DE D2 1.0£ 02 1.0E 03 NI 1.0E 02* 1.DE 02 1.0E 02 2.SE 02 cu 5.DE 01 4.DE 02 l.7E 02 1.7E 03 ZN 2.0E 03 1.DE 04 2.0£ 03 5.0E 04 IR 4.2£ 02 3.3[ D2 1.SE-02 3.1£ 00 RB Z,DE 03 1,DE 03 l.3E 00 1.7E 01 SR 3.0E 01 1.0E D2 2.0£ 00 . 2.0E 01 2.SE 01 1.DE 03 2.5£ 01 1.0E 03

'

ZR 3,3£ 00 *1.n oo 2.0E 02 I.OE 01

NB 3,0[ 04 1.0E 02 3.0E 04 1.0E 02 1.DE 01 1.0E 01 1.0E 01 1.0E 01

"'TC 1. 5£ 01 5.0E 00 1.or 01 5.0E 01 RU 1.0E 01 3.0E 02 3.0E 00 1.0E 03 1H 1,0E 01 3.0E D2 1.0E 01 2.0E 03 TE.. 4,DE 02 l.1E 03 1.DE 01 1.0f: 02 I 1.SE 01 S.DE 00 1.0E 01 5.0E 01 cs 2.DE 03 1.DE 03*" 4.0£ 01 2.SE 01 IA 4,DE 00 2.0E 02 1.0E 01 1.0E 02 LA I.SE 01 1.DE 03 2.SE 01 1.0£ 03 CE 1.0E 00 1.CIE 03 1.0E 01 I.OE 02

, PR z.SE en 1.CI[ 03 Z.SE D1 1.0E 03 ND I.SE 01 1.CIE 03 2.S£ 01 1.0E 03 If 1.Zt 03 1.CIE 01 J.OE 01 J.OE 01 IP 1.CIE* 01 4.CIE 02 1.DE 01 1,DE 01

Values. 1n *

...** T1bl1 A-1 IN taken fran bf1renc1 i unless Dita taken fraa bf1ranc1 I

Dita taken froa bfll'BCI 7.

othirviH tiidtcatcd .

{

-

1.109-13

suspended 1nd depostted *terf1ls. One *thod of 1pproechtng thts pT'Oblan .as presented tn the Y11r 2000 Study (Ref. 3). llsed on tflfs IIOdel, 1n estfaate of the r1dtonucl1de concentr1tfon fn shoreline sed1aents can be obtltned fna tM followfng upresston:

. ct.n - eap(-1 1;>1 ct,. 'c it (A-C) ts the concentration of eucltde t tn sed1aent, tn pCf/kgi h the concentr1t1on of nucltde t tn .. ter 1dJ1cent to the Hdfaent, fn pCf/11teri is 1n asswaed -transfer constlnt.fran Wlter to sedfaent, tn liters/kg per hri ts the length of ttine the stdfaent ts uposed to the contat11fn1ted *ter, n1111fn1111y 15 years (1pprox1*te a1dpo1nt of f1cf11ty oper1tfng lffe), 1n lloursi and ts the decay constant* of nuclide t, tn bours*1* In the original ev1lu1tion of the equ1tton, 11 .. s chosen to be the ndfologtc1l det1y constant. The true value should include 1n as yet unknown *envtronaient11* f'IIIIOval const1nt.

The value of Kc .. s derived for several ndionuclfdes by ustng dlta from water 1nd sedi111ent semples collected over I period of several years fn the Columbia River between Richland, Wlshington, 1nd the rfver 110uth 1nd in Tillamook Bay, Oregon, 75 bn south of the river aouth (Refs. 9 1nd 10). Since the pri111Ary use of the equation ts to facilitate estf1111tes of the exposure rate from 911111\1. emitters one meter above the sediment, 1n effective surface contemfna-tfon was*estfaated. This surface contamfnatfon was assumed to be contlfned within the top 2.5 c:m (1 tn.) of sedi111ent (with 11111ss of 40 tgtm2 of surface). The dose contrfbutfon from the r1dfonuclfdes 1t depths below 2.5 an was ignored. The resulting equation ts (A-5) ts the *effective* surface contlll1nat1on, tn pCf/m2, that ts used 1n subsequent c1lcul1tionsi ts the r1dfological hllf-lffe of nuclfde f, fn diySi h I shore-wfdth factor thlt descrfbes the geometry of the exposure, 1nd ts equal to [Kc(1/tg-hr)~40(tg/m2)* 24(hr/da.y)/0.693], tn &/m2-d&y.

Shore-wfdth factors were derived froa experfNntll clltl (Ref. 11) and ire s1a1111rized in Table A-2. They represent the friction of the dose fr'GIII an tnf1nfte plane source thlt ts estt.. ted for these shoreline s1tu1tfons.

The cOlllbinatfon of Equ1ttons (A-4) and (A-5) tnto the gener1l Equ1tion (A-1) leads to Equation (A-6) below for c1lcul1tton of radf1t1on dose fl'OII exposure to shoreline sedfaents.

l a_PJ

u*P s1D1 tpJ

100 I u.Pw c1.T1Datp,1Cl - eap(-1 1i.>>>l (A-6)

As tn the dtvelopaent of Equ1t1cn (A-2), the eapresstOft (1100 Q1 '\,IF)eap(-11t,> *1 be substituted for Ctw* Tb1s results tn ttlt following reJ1ttonshtp:

(A-7)

If the presence of I r1dfonuclfde tn *ter 1nd sediment ts controlled pr1*rf1y by r1dioective equ1ltbrt1111 with fts parent nuclfde. the *ter concentr1t1on and decay constant of the parent should be used tn Equations (A-4) and (A-5).

1.1Dt-14

TABLE A-2 SHORE-WIDTH FACTORS FOR USE IN EQUATIONS (A-5) 1 (A-6) 1 AND (A-7)

EXPOSURE SITUATION D1schlrge canal blnlt River shoreltne Laite shore SHORE-WIDTH FACTOR. W 0.1 0.2 0.3 llomin11 oce1n sfte 0.5 Tidal basin 1.0

d. liose from Foods Grown on Land with Conta11inated Water The equations 1n the following paragraphs can be used to calcul1te doses from rad;o-nuclides released in liquid effluents but appearing in crops or animal products. Separate expressions are presented for tritf1111 because of 1ts unfque envirol'llllental behlvior.

(1) Vegetation The concentration of radioactive .. terial 1n vegetation results from depos;tion onto the plant foliage and from uptake from the soil of 1ctivity deposited on the ground. The 110del used for esti1111t;ng the transfer of radionuclides from irrigation water to crops through water deposited on leaves and uptake from soil was derived for o Gtudy of the potential doses to people from a nuclear power complex in the year 2000 (Ref. 3).

The equat;on for the 110del (for r1dionuclides except tritium) is presented below in slightly 110d;fied form. The first term in brackets rel1tes to the concentrat;on derived from direct foli1r deposition during the growing season. The second term relates to uptake from soil and reflects the long-term deposition during oper1tion of the nuclear facility. Thus, for a uniform release rite, the concentr1tion Civ of radionuclide i in the edible portion of crop species v, in units of pCf/ltg, "Is given by:

(A-8) where the terms are defined in Section C, *Regulatory Position.* A1,pendix E, T1ble E-15, presents suggested values for the par1111eters r, Yv* t 1 , P, and th. Values for Biv are i~ Table E-1.

The deposition rate, di' fn111 irrigated water 1s defined by the relation d1

c1wl (water deposition) (A-9) where c1w 1s the concentration of radionuclide t tn 1Mter used for irrigation, in pti/lfter, and

. 2 J ts tht 1v1r1ge trrfgatfon rate, tn liters/11 /hr, during the growing season.

For a*cow gr1zfng on fresh for1ge, t 1 1n EqoJetfon (A-B) ts set equal to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months (30 days), the typical ttae for a cow to return to I particular portion of the grazing site (Refs. l and 12). .

For trittia, the equation for estt.. ttng c1v fl (lee Ref. 13):

(A-10)

(_

1.109-15

(2) Anfaal Products The radfonuclfde concentration fn an ant111l product such as ... tor atlk is dependent on the an:>unt of contaminated feed or forage Hten b1 the ani*l and fts intake of contallinated water. The radionuclide concentration in ani*l products c1A tn tenas of pCi/liter or pC1/k9 1s proportional to the ani111l 's tntake of the radionucltde tn feed or forage (sub-script F) and in water*(subscript w):

(A-11)

The second set of tenns fn the brackets in Equation (A-11) can be omitted ff the anf111l does not drink contaminated water. Values for QF and QAw are presented in Appendix E, Table E-3. Values for Bfv and F1A are given in Appendix E. Table E-1.*

(3) Total Dose from Food Grown on Land The total dose Rapj from trrtgated fouds and aniNl products (uclllding tritf1111) f I given b1:

(A-12)

If values for c1v fran Equation (A-B) and c1A fran Equation (A-11) are substituted tn Equation (A-12): *

(A-13) where the tenns are deftned tn Section c. *Regulatory Position.*

It should be noted that the two cD111ponents of Equation (A-12) f111pl1 that contribu-tions from the individual vegetable and antmel products hive already been s1111111ed. In actual use, it wtll be necessary to compute separately the ailk and aeat portions of the dose due to 1ni111l products (also applicable to Equation (A-16)).

For tritf1111 1 the concentration tn aniael products (*flt or aeat) fs given b1 the following equation: *

(A-14) where the term are defined tn Section c. *1tgulatory Position.*

Stnce by Equation (A-10) Cw* c** and sfnce for all practical purposes Cllw

Cw*

Equation (A-14) can be restated I I follows:

I*

(A-15)

Values for FfA appear as F* and Ff fn Table E-1.

1.109-16

S1af11r1y. tM above equatfans for trtth* concentr1Uon can be CGllbtned with the ttner1l Equatton (A-1):

apJ

veg *.ant*l u.p CwD1pJ. "ap CAD1pJ (A-16)

.: ~* .: . *-::.

( .

1.1Dt-17

ltEFERENCES FOR APPENDIX A

1. *Final Enviroraentel Statement Concerning Proposed Rule Miking Actfon: 11\inerical Guides for Design Objectives 1nd Limiting Conditions for Operation to Meet the Criterion 'As Low As Pr1ctic1ble' for Radioactive Material 1n Light-Water-Cooled Power Reactor Effluents,N USAEC Report WASH-1258, Wlshington. D.c ** July 1973.

2. J. K. Soldet et 11 ** *Models and CCl!lputer Codes for Evaluating Environmental Radiation Doses.* USA£C Report BNWL-1754. Pacific Northwest Laboratories, February 1974.

3. J. F. Fletcher 1nd W. L. Dotson (compilers), *HERMES - A Digital Computer Code for Estimating Regional Radiological Effects from the Nu~lear Power Industry,* USAEC Report HEDL-TME-71-168, Hanford Engineering Developnent Laboratory. 1971.

4. J, K. Soldet, *conversion of Survey Meter Readings to Concentration h,Citm2).* Item 04.3.4 1n *Emergency Radiological Plans and Procedures.* K. R. Heid (ed.). USAEC Report HW-7og35, Hanford L1bor1tortes, 1962.

5. D. H. Denham ind J. _K. Soldet. *A Study of Selected Parameters Affecting the Radiation Dose from Radionuclides 1n Drinking Weter Downstream of the Hanford Project.* Health Physics.

Vol. 28. pp. 139-144, February 1975.

6. S. E. Thompson et al., *eoncentretion Factors of Chemical Elements 1n Edible Aquatic Organisms,* USAEC Report UCRL-50564, Rev. 1. Lawrence Radiation Laboratory. October 1972.

7. H. A. Vanderploeg et 11 ** *Bioecci,nulat1on Factors for Radionuclides tn Freshwater Biota.*

ORNL-5002, Oak Ridge, Tenn ** November 1975.

8. G. G. Kil1ugh and L, R. McKay, *A Methodology for Calculating Rld1ation Doses from Radio-activity Released to the Environment.* ORNL-4992. Oak Ridge National Laboratory, Oak Ridge, Tenn .* March 1976.

9. J. L. Nelson. *Distribution of Sediments and Associated Rldionuclides 1n the Columbia River below Hanford.* p. 3.80 in *Hanford Radiological Sciences Research and Development Annual Report for 1964,* D. W.'Peerce and J. K. 5reen (eds.), USAEC Report BNWL-36.

Pacific Northlilest Laboratories. 1965.

10. G. L. Toombs and P. B. Cutler (compilers). *Comprehensive Final Report for the Lower Columbia River Environmental Survey in Oregon Junes. 1961 - July 31, 1967,* Oregon State Board of Health, Div. of Sanitation and Engineering. 1968.

11. *Handbook of Radiological Protection. Part I: Dita,* prepared by I panel of the Radioactivity Advisory Comfttee (H. J. Dunster. Chaira11n), Department of Elllployment, Deparbnent of Health and Social Security, Ministry of Health and Social Services, Northern Ireland. Nianber SNS 11-360079-8. Her Majesty's Stationery Office. London. England. 1971.

12. J. J. Kor1nd1. *Agricultural Factors Affecting the Dafly Intake of Fresh Fallout by Dairy tows.* USAEC Report UCRL-12479, 1965. .

13. L. R. Anspaugh et 11., *The Dose to Nin v1a Food-Chain Transfer Resulting fra11 Exposure to Trftiated Water Vapor,* in Tritium (A. A, Moghiss1 and M. W. Clrter, Ids.),

CONF-710809 1 1973.

I 1.109-11

APP£11DIII ll>OELS FOR CALCULATING DOSES FlOM IDILE MSES DISCHARGED TO TH£ l111>SPHER£ The fo11ow1fti analytical IIDdels are used for calcul1ti"i doses fro., exposure to noble gases discharged to the 1t1110sphere. Stp1rate IIOdels are gfven for a1r 1nd tissue doses due to ganrna 1nd bet* r1ys. Except for the case of noble gas doses resultfng fl'OII elevated releases, 111 aodels assuae t1111ersfon 1n a 11111-tnfintte clOU;d,

1. Annual 61111111 A1r Dose* from Noble Gas Releases fr'CIIII Free-St1ndin9 Sticks Nore Thin 80 Meters

Righ . *

Slede (Ref. 1) describes I der1vat1on of equations for est1.. ting annual 1fr doses from photon mitters dispersed 1n the 1t11osphere. The following expreu1on c.n ~ usH for celcyl11ting 1nnua 1 doses :

(B-1)

S,Y111bo1s for th1s equation were defined t1r11er, tn Regulatory Position c.2.1 of this guide.

A discussion of, and derivation for, the I function are presented in Appendix F of this guide .

.:;: =.** The photons are cCllllbined 1nto energy groups, and each photon intensity within; group is weighted by its energy and energy 1bsorption coefficient. Thus, the effective fraction of disintegrations of the nuclide i yfelding photons corresponding to the photon energy group k, llti, is detennined to be ,, *

(B-2)

(

where fs the fraction of the dbfntegratfons of nuc11,de t yielding photons of energy ~i ts the energy of the *th photon within the tth energy group-,. tn NeV, and ts the energy absorpi1on coefficient tn 11r associated wtth the photon energy Ea* tn .-,

All other p,r1111eters are as previously cleffned. The i11111111tton ts carried out over 111 photons within energy group t. DIU for the photon energies and abundances for aost of the noble gas nuclides were Uken fr1111 Reference 2. For r1dionucltdes not contlined tn Reference 2, dlta were obtained fl'OII Reference 3.

Decay cturfng trnel fra11 the point of rel*se to the receptor ts (1-3)

The tenn *91111111 air dose* refers to the COllpOnents of the air dose associated wtth photons

.. itted during nucle1r and atoinfc transfor111tions, 1.1., 1&111111 and*x-rays. Ann1h111tion 1nd

rtasstrahlung photon radtatfons are possfble contributors to this coaponent of the a1r dose.

( 1.109-11

ts the tnttt11 n1nse rate of nuclfde 1, tn Cf/yr.

fl the dfltlnct fna tM source to the l"ICeptor, tn ** nd

"

ts . ~ decly constant of nuclfde

. t, tn sec*

1 A11 otller paraaeters ' " as pnvtous1y dlftned.

z. Annua1 C.111111 Air Dose from All Other Noble Gas Re1eases and Annual Beta Air Dose* from A11 loble &is Releases .

Pl1111es of gaseous effluents are considered semi-infinite tn the case of ground-level noble

11s releases. The annual average ground-level concentration of radionuclide fat location (r,e) 1s deterwf ned fra11 x1(r,e)** 3.17 x 104o1[x/QJ0 (r,e) (B-4) where ts the annual average ground-level concentration of nuclide i 1t the distance r tn the sector 1t angle e from the release point, tn pCi/11 3, and ts the annual 1ver1ge gaseous dispersion factor (corrected for r1dfoactive decay) tn the sector at angle eat the distance r fro11 the release point, tn sec/113 * (See Regulatory Qufde 1.111 for 1t111ospheric dispersion IE!dels.)

0 All other par1111eters are 1s previously defined.

The associated annual 91111111 or beta air dose ts then oY(r,e) or D8 (r,e) * { x1(r,e)(DF1 or DF:) (B-5) where the tenns are IS defined fn Regulatory Pos.1tfon C.2.b.

Table 1-1 presents a tlbulatfon of the dose factors for the noble gases of interest.

3. Annual Total Body and Skin Doses from Noble Gas Effluents It ts also necessary to d1ter11ine annual doses. to Nil tndivfduals tn unrestricted areas.

The staff coniputes the total body dose frolli 1xteM11l r1di1tfon at I depth of 5 CII tnto the body and the 1tin dose at I depth of 7 ag/cm2 of tfssue (Ref. 4).-

- .. lnses from Frae-Stlnding Stacks Nore Thin 80 Meters Hfah The annual total body dose ts cClllpUted IS follows:

DT(r,1)

1.11 a _S, I D?(r,t)exp[*~!<Ek)td] (1-6)

.. The terw *beta 1tr dose* Nfers to the caponent of the 1tr dose 1ssoct1tecf wtth particle

hsfcns durfng n1.1C1Hr and 1t011ic transforwttons, t.1., 9+, t*, and conwersfon electrons.

.

SH dtscusston tn Appendix E, Stctton J, I

1.1Dt*ZO

-~

TAILE 1-1

.

DOSE FACTORS FOR EXPOSURE TO A SENI-INFJNITE CLOUD OF NOBLE IASES

lucltde 1-11r*(DF~) l*Sk1n ** (DFS 1 ) *

rAtr (DFl> x-lodi** (DFB1>

lr-13* Z.IBE-04 ***_ 1.t3E*OS 7.56E-08 lr .. 15* 1.17£-03 1.0E-03 1.23E-03 1.17E-03 ltr-15 1.tsE-03 1.34£-03 1.72E-05 1.61E-05 ltr-87 1.03E-02 t.7U-C3 !.17£-03 5.t2E-03 lr-88 2.93E-03 2.37£-03 1.52[-02 1.47[-02 lr-89 1.06[-02 1.01[-02 1.73[-02 1.HE-02 lr-90 7.13£-03 7.HE-03 1.UE-02 1.56E-02 le-13111 1.11£-03 4.76£-04 1. 56£-04 t.lSE-05 le-13311 1.4:SE-03 t.94£-04 3.27E-04 2. 51£-04

.

le-133 1.0SE-03 3.06£-04 3.53£-04 2.94£-04 le-13511 7.HE-04 7.11£-04 3.36£-03 3.12£-03 le-135 2.46£-03 1.16E-03 1. 12E-03 1.BlE-03 lec137 1.27E-02 1.22[-02 1. SlE-03 1.42[-03 le"-138 4.75[-03 4.13£-03 ,. 21E-03 8.83[-03 Ar-41 3.28[-03 2.HE-03 1.30[...03 8. 84~-03 1

11r1d-11J pti-yr

- are11-11 3 pC1-yr

- - 2.IBE-04

2.18 x 10* 4

(. .

1.10I-Z1

Symbols for this equation are defined in Regulatory Position C.2.c of this guide. The factor SF account_s for the dose reduction provided by the shielding effect of typical residential structures (He Appendix £, Section c and Table £*15) *

. The sltfn close Ills t.o CCllllpOftents, the .-a and beta contributions. TIit skin dose rate 1s caaputed by D1 (r,e)

1.11*a S,O'(r,e) + 3.17 x 10* { Qi[x/QJ 0(r,e)DF5i. (1-7)

Symbols for this equation are defined tn Regulatory Position C.2.d of this guide.

The skin bete dose factors DFS were detennined using the decay scheme source docU111ents ctted above and the methods used in References 5, 6, and 7. They are presented in Table B-1.

b. All Other Releases The annual total body dose ts COlllputecl as follows:

(B-8)

I I

Symbols for this equation are defined tn Regulatory Position C.2.e of this guide. I The annual skin dose is computed as follows:

(B-9)

Symbols for this equation are defined in Regulatory Position C.2.f of this guide .

1.109-22

1£FERENCES FOR APPENDIX 8

1. *Meteorology and Atomic ENrgy 1168,* D. H."Slacle (ed.), USAEC leport TID-24190, 1968.

2. N. J. Nart1n, *1tacl1oact1n AtGIIS, Supplaent I,* USAEC Report ORNL-4923, NDvaber 1973.

3. N. E. Neek and R. S. 511bert, *s...ry of 5111111 and Beta Energy and lntenstty Data,* NED0-12037, 1170. .

4.

.

.J. I, Soldat et al., -Yhe Dost*try of the Radfoacttve Noble lilses,* The Noble Gases (A. A. Noghisst and R. E. Stanley, Ids.), ERDA-CONF 730 915, U.S. Energy Research and Development Administration, 1975.

5. R. Loevtnger et 11., 1n Radtatton Dost111etry (G. S. Htne and G. L. lrownell, eds.), Academic Press, New York, 1956.

6. M. J. Berger, *111proved Point ICernels for Electron and Beta-Ray Dos1111etry,* NBS Report NBSIR 73-107, 1973.

7. M. J. Berger, *1eta-Ray Dose 1n Tissue - Equivalent Nater11l l11111ersed 1n a Radioactive Cloud," Health Ph,Ys1cs, Vol. 26, pp. 1-12, January 1974 *

...

r*

1.109-23

'

APP£NDI1. C 11>D£LS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES AND OTHER RADI0NUCLID£S*

DISCHARGED TO THE ATil>SPHER£

1. Annual External Dose from Direct Exposure to Activity Deposited on the Gl"Ound Plane The ground plane concentration of radfonuclfde 1 at the location (r.e) with respect to the reluse point Ny be detennfned by 6 [1.0 x 1012] [ai(r.e) Q1] '

C1(r,e)

A (1 * -~p(-Aitb)] (C-1) f where ts the gl"Ound plane concentration of the radionuclide 1 fn the sector at angle eat the distance r fl'CIII the release point. fn pCitm2, ts the annual release rate of nuclide i to the atmosphere, tn Ci/yri ts the timt period over which the 1cc1111Ul1t1on 1s evaluated, which is 15 years (~id-point of plant OpeT'lting life). This is I simplified 111ethod of approximating the average deposition over the operating lifetime of the facility,

ts the annual average relative deposition of effluent species 1 at location (r,e), considering depletion of the plume duri~g transport, 1n m* 2 ,

Ai ts the r1diologic1l decay constant for nuclide 1, 1n yr*1 , and 1.0 a 1012 ts the ftlalber of pCi per Cf.

The annual dose resulting froin direct exposure to the contaminated gl"Dund plane, from 111 radfonuclides, ts then (C-2) where the tenns are defined 1n Regulatory Posftton C.3.1 of Uiis guide.

Values for the open field gt'ound plane dost cOf\verston factors for the skin and total body are given tn Appendix E, Table E-6. The annual dose to 1\1 other organs fs taken to be equivalent to the total body dose. The factor SF 1s asslllled to hive I value of D.7, diaensionless.

1*

Does not include noble 91111.

1.109-24

2. Annual Dose ff'OII l11hll1tfon of lldfonucHdes in Afr

(_ The annual average airborne concentration of radionuclide 1 at ttte location (r,e) wfth res-pect to the "least pofnt *Y be deterafned 11

1s the release rate of nuclide 1 to the ataosphere, tn Cf/yr.

(C-3) ts the annual average ground-level concentration of nuclide 1 fn air fn sector* at distance r, tn pCi/*3*

ts the annual average ataosphere dispersion factor, fn sec/~ 3 (see Regulatory Ciu1d~ 1.111), This includes depletion (for radfofodines and particulates) and radioactive detay of tht pliae, and 3.17 a 104 h the nlllber of pCi/Cf divided by the IIUllber of sec/yr.

The annual dose associated with tnhllatfon of 111 radtonucltdes, to organ j of an tndfvidual

.fn age group 1, 1s then (C-4)

Values for DFAfja are given fn Appendix E, Tables E-7 through E-10, values for R1 are given tn Appendix £,,Table E-5. All other symbols are as defined earlier fn Regulatory Position C.3.b.

(_ 3. Concentrations of Airborne Radionuc11des fn Foods

The eoncentrat1on of radfoactfve 111terf11 tn vegetation results fro111 deposftfon onto the plant folf1ge and from uptake of 1ctivfty fniti111y deposited on the ground. The 110del used for estimating the transfer of radfonuclfdes from the atlllosphere to food products fs sfmflar to the aodel developed for estf111ting the transfer of radfonuclfdes from irrigation ..ater given 1n Appendix A of this gufde. * *

a. Par1111eters for Calculating Nuclide Concentr1tions 1n Forage, Produce, and Leafy Vegetables For 111 radiofodines and particulate radfonuc11des, except trit11111 and carbon-14, the concentration of nuclide i tn and on vegetation at the location (r,e) fs estimated using cv1(r,t)

d1(r,t)

{r[l

exp(*1£itell liv[l

exp(-1 1tb)]1 y1 + Pl exp(-1 1th)

(C-S) w£1 t Ste Regulatory Posftton C.1 of this guide for definitions of tenns. Values for the paraaeters ,. te* 'v* P, and th are provided 1n Appendix E, Table E-15. for the paruieters te*

'v* and~* different values*are given (tn Appendix E) to allow the use of Equation (C-5) for different purposes: esti111tfng concentrations tn produce cons11111d by ..n, tn leafy vegetables consUllltd by Nn, fn forage consU111ed directly as pasture grass by dairy cows, beef cattle, or goats, and h\' forage cons!Md II stored feed b1 dairy cows, beef cattle, or goats.

( -

I. 109-ZS

. . .. ... *- *- - . -:* . . - '***:- .

The deposftfon rite fr1111 the pl111e ts deftntd by d 1(r,e)

1.1 a 1a8a 1(r,t)Q1 fs .the deposttfon rate of r1dfonuclfde f onto ground 1t locatton (r,e), fn

,Cf/a2-tir; fs the rel1tfve deposftton of redionuc11de t, consfderfng depletion 1nd dec1y tn tr1nstt to 1oc1tfon (r,e), tn a* 2 (see Regulatory lillide 1.111); 1nd 1.1 x 108 ts the n1111ber of ,Ci per Cf (10 12

) divided by the number of hours per year (8760).

For r1dioiodines, the IIOdel considers only the eleinental friction of the ~fluent. The deposition should be ca11puted only for that friction rf the effluent thlt fs estimated to be elemental iodine. Neasurenents It oper1tfng f1cflftfes indicate that 1bout half the r1dioiodine etRissions 1111y be considered none1911ental (Ref. 1). With thfs consfderatfon included,

.Equation (C-6) for r1diofodine becaaes (C-7) where Qi is the total (elemental 1nd nonelemental) r1dfoiodfne ..issfon rate. The retention factor r for elemental radioiodine on vegetation should be taken as unity, since the experiNenta1 measun!fh!nts (Refs. 1, 2, and 3) used to evaluate this transfer aechlnism consisted of direct comparison of the gross r1diotodine concentration on vegetation 1nd the concentration tn air (Refs. 4 and 5).

For radioiodines, the deposition aodel is based only on the dry deposftfon process. Wet deposition, including *washout" of the organic and non-organic iodine fractions, should be con-sidered at same sftes depending on the meteorological conditions (see Regulatory Guide 1.111).

For particulates, the deposition IIOdel considers both wet ind.dry deposftfon. There ts also a retention factor (r of Equation (C-5)) that accounts for the interception and capture of the deposited activity by the vegetative cover. A value of 0.2 is taken for this factor (Refs. 6 and 7). All nuclides except noble gases, triti1111, carbon-14, and the iodines are treated as particulates.

Carbon-14 ts asslllled to be released fn aatde fona (CO or CO2). The concentration of carbon-14 fn vegetation ts calculated by ass1111ing that fts ratfo to the natural carbon in wegetatfon fs the same as the ratio of carbon-14 to natural carbon tn the ataosphere surrounding the vegetation (see Refs. 8 and 9). Also, tn the case of intel"lliitent releases, such as fran gaseous waste decay tanks, the parameter p ts eaployed to account for the fractional equi11briUIII ratio achieved. The parameter pis defined as the ratio of the total annual release ttae (for C-14 atllospheric releases) to the total annual ttme during which photosynthesis occurs (taken to be 4400 hrs), under the condition that the value of p should never eaceed unity. For continuous C-14 releases, \p fs taken to be unity. These consider1tions yield the following relationship:

c;4(r,e)

J.17 a 1o1P014[1/Q](r,1) 0.11/0.16 7

2.Z a 10 P0 14[1/Q](r,1) * (C-8) ts the concentration of carbon-14 fn vegetation grown at location (r,e), tn pCi/tg; ts the annual release rite of carbon-14, fn Cf/yr,

. p ts the fractional equflfbr1111 ratto, diaensionless. .' 1 0.11 ts the fraction of total plint *ss that ts natural carbon, dfaensfonless; 1.109-26

0.16 ts equal to the concentration of 111tur1l car*bon 1n the ataosphere, 1n g/m3i and

3.17 x 107 ts equal to (1.0 x 1012pet/C1)(1,0 x 103 g/kg)/(3,15 x 1071ec:/yr).

The concentration of trftf1111 tn*vegetat1on ts calculated fro111 fts concentration 1n the air surrounding the vegetation. Using the *thod described 1n Reference 10, the NRC staff derived the following equation:

t;<r,t)

3:17 x 1070y[x/Q](r,t)(0.75)(0.5/H)

1.2 x 1070y[x/Q](r,e)/H (C-9) t;<r,e) 1s the concentration of tr1t11111 fn vegetation grown at 1ocat1on*(r,e), fn pCi/kQi H ts the absolute hllllidity of the atmosphere at location (r,e), 1n g/m 3 i Oy 1s the annual release rate of tr1t11111, 1n Cf/yr; 0.5 ts the ratio of tr1t11111 concentration 1n plant ... ter to tritf1111 concentration 1n atmospheric water, dfinensionlessi and 0.75 ts the fraction of total plant aass thlt ts water, dimensionless.

b. Parameters for Calculating Nuclide Concentr1t1ons in Milk The radionuclide concentration 1n *11k 1s dependent on the IIIIOunt and contamination level of the feed consum.d by the ani1111l. The radionuclide concentration in ailk fs estimated IS (C-10) where

~(r,t) ts the concentration 1n ailk of nuclide f, in pCi/11teri

. .

crcr,e)_ ts the conctntratfon of radionuclide i 1n the ani1111l's feed. tn pCf/kg; Fin ts the average fraction of the an1aal's daily intake of radionuclide i which appears in each liter of Milk. tn days/liter (see Appendix E. Tables E-1 and E-2 for cow and goat data. respectively; for nutlides not listed in Table E-2, use the values tn Table E-1);

ts the 1110unt of feed consumed by the aniNl per day, tn kg/day.

ts the average transport tf111e of the activity from the f~ into the *ilk and to the receptor (a value of 2 clays ts assumed). and ts the rad1o1og1ca1 decay constant of nuclide f, tn clays*1*

The concentration of ndionucltde t tn the 1ni*l 1 s fNd 1s estt*ted as c;(r,1)

fpf1C~(r,t) ~ (1 e fp)t~(ril) + fp(l

f 1)C~(r,t) (C-11) ts the concentration of radionuclide ton pasture grass (calculated ustng Equation (t-5) wtth t,,-0), tn pCt/kg; ts the concentration of radionucltcle t fn stored feeds (calculated using

( Equation (C-5) wtth te.-tO days), tn pC1/1tti

1.109-27

ts the fr1ctton of the JNr that antaals gr1ze on pasture;. and ts the fnctton of *ny feed that ts pasture grass when the 1n1*1 grazes on pasture.

The values of _the parPtters th. te* 'v* al'ld tf that w111 be aployed fn evaluating the ant pat-.y. unless site-specific data ts supplied, *re provided tn Appendix E, T1ble E-15.

c. Parllll!ters for talculatina Nuclide Concentration in Neat As fn the *ilk pathway, the radionuclide concentration in aeat ts dependent on the IIIIOunt ind contamination level of the feed consU111ed by the 1niaal. The radionuclide concentra-tJon fn aeat fs esti*ted as (C-12) where fs the concentr1tfon of nuclide 1 fn 1n1..1 flesh, fn pCi/kgi ts the fraction of the anfaal's daily intake of nuclide i which appears in

..ch kilogr1111 of flesh, tn clays/kg (see Appendix E, Table E-1 for values)i and is the 1verage time from ~l1ughter to consumption (see Appendix E, Table E-15).

All the other symbols *re as previously defined.

Beef cattle will be ass1111ed to be on open pasture for the grazing periods outlined for ailk cattle.

4. Annual Dose from Atmospherically Released Radionuclides in Foods The annual dose to organ j of an individual tn age group a res~lting from ingestion of 111 radionuclides tn produce, milk, aeat, and leafy vegetables ts given by (C-13) where ts the annual dose to organ j *of an individual tn age group a from dietary intake of a~spheric:.lly released r1dionucltdes, 1n art!l!l/yr;.

1s the dose conversion factor for the tngestton of nuclide t, organ j, and ege group 1 1 tn 11'1111/pCt (frGII Tables E-11 through E-14 of Appendix E of thts guide);. end are the tngestton ntes of produce (non-leafy vegetables, fruit, and grains),

ailk, aeat, and leafy vegetables, respectively, for tnclivtclulls tn age group a (froa Table E-5 of Appendix E of this gutde).

All the other syaboll are as previously deftned. Values of f and f 1 to be assiaed tn the absence 1

of 1tte-spectftc tnfol"llltton are gtven tn Table E-15 of Appendix E as 0.76 end 1.0, respectively.

. f 1.109-28

IEFERDICES FOR APPENDIX C

1. I, H. lllhs tit 11., *aa.u11ed Nusura1nt of 1-131 1n Afr. Vegeut1on and "11k Around Three Oper1tfng ..,ctor Sttes.

IUlEG-75/021, U.S. luclnr legulatory Ccalfssfon.

Mashtngton. D.C., Narch 1975,

z. D. F, lunch (ed. r. *eontrolled Envfro,aenul ladfofod1ne Test. Progress Report ll.llber Tw.

USAEC leport ID0-12063. January 1168, .

3. J. D, Zfllbrfclt and P. &. ¥of11eque. *eontrolled Envfromenul ladfotodine Tests at the National Re1ctor Testing Stltfon. Progress Report Nlllber Four,* USAEC Report ID0-12065 1

~~r 1968.

*

4. F. D. lloffllan. *[nvfromentll Varfablts Involved with the Estf*tfon of the Allount of 131 1 1n "flit and the Subsequent Dose to the Tl\1rofd.* Institute flJr Relktorsfcherheft. Cologne, llest &eraany. IRS-W-&. June 1973:

5. F. D. Hoffllan, *A Reusessaent of the Parueters Used To Predict the Environaentll Transport of 131 1 from Afr to Mf1t 1

Institute fur Relktors1cherhtit, IRS-11-13, April 1975.

,. C. A. Pelletier and P. G. Vofllaque 1 9The Behavior of 137cs and Other Fallout lldfonucltdes on I Mfchfgan Dairy Fi!ii,* Health PhYS,g Ygl. 21e p. 777, 1971.

7. P. G. Voflleque and C, A. Pelletfer, *tOIIIJ)lrfson of External lrradfatfon and ConsllllJ)tfon of Cow's Mflk as Critical PattMys for 137cs, ~ and 144c~ 144Pr Released to the Ataosphere,* Health Phys .* Vol. 27, p. 189, 1974.

8. Y. C. "9 et 11. 1 *Precffctfon of the NufllUII Dosage to Nan from the Fallout of Nuclear Devfces. IV Handbook for Estf111tfng the Naxf1U11 Internal Dose fMIIII Radtonucltdes Released to the Biosphere.* USAEC Report UCRL-501631 Part IV, 1968.

9, R. C. Meast (ed.), *Handbook of Chelllfstry and Pfu,sfcs.* CRC Press. Cleveland. Ohfo, 1970.

10. L. R. Anspaugh et 11., *The Dose to Nan vf1 the Food-Chlfn Trinsfer Resulting from Exposure to Trftfated Water V1por,* USAEC Report UCRl-73195. Rev. 1, 1972 *

-

1.109-ZI

APPENDIX D IIK>£LS FOR CALCULATING POPULATION DOSES FD IIJCLEAR POWER PLANT EFFLUENTS Calculation of the annual population-integrated total body and thyroid doses* should be performed for the three effluent types identified fn this guide. These doses should be evaluated for the population within I S0-111le radius of the site, as specified 1n paragraph D, Section n of*Appendix I to 10 CFR Part 50.

For the purpose of calculating the annual population-integrated dose, the 50-tnile region should be divided into I n1111ber of subregions consistent wfth the nature of the region. These subregions ..Y represent, for example, the reaches of I rfwer or land areas ower which the appro-priate dispersion factor fs IYtraged. Dispersion factors, population dlta, and other tnfonnation

. describing existing or planned uses of the subregfons should be deweloped.

1. General Expressions for Population Dose For pathways in which the pen11nent and transfent population of the subregion can be con-sidered to be exposed to the average radionuclide concentrations estf111ted for the subregion, the annual population-integrated dose is calculated as follows:

(D-1) where 1s the annual dose to organ j (total body or thyroid) of an 1wer1ge individual of age group a in subregion d, fn arf!lfl/yr, fs the annual popul1tion-fntegr1ted dose to organ j (total body or thyroid),

fn *n-rens or thyroid *n-rems, fs the fraction of the population in subregion d that is in age group Ii is the population 1ssocf1ted with subregion di and is the conwersion factor fro11 *rem to rt111.

The annual dose to the total body or thyroid of an average indfvfdual should be evaluated with the usage factors of Table E-4 of Appendix E. Models and equations for the detailed dose calculations are presented fn Appendices A, B, and C of this guide. The annual population-integrated doses from fngestfon of potable ..ater, inhalation of airborne effluents, and external exposure to airborne or deposited radfonuclfdes should be evaluated. In addition to the pethways for which equations are presented fn Appendices A, B, and C, other exposure pathways should be evaluated ff conditions at I specific site indicate that they 11ight provide I significant contri-bution to the total population dose fl"OII 111 pathways. In this context, a significant contribu-tion is defined as 10 percent or aore.

For pathways that inwohe food products produced in the subregion; th\ food product$ NY be distributed to other areas for consUIIIJ)tfon. For 111 the food that is produced within the 50-aile radius, the radioactivity concentr1ti0fts are aweraged over the entire area by weighting the concentratfons in etch subregion by the IIIOUnt produced fn each subregion. This average concentra-tion ts used tn calculating the population doses. The S0-a11e average concentration of nuclide t tn food p 1s coaputed as (D-2)

The populatfon-tntegrated dose ts the 1111a1tfon of the dose recetwed by 111 tndivtduals and has unfts of *n-rm when applied to the total body dose and unfts of *n-thyrofd-ra when applied to the 1111111t ion of thyrofd dose.

_

1 109 30

......

Cc11p ts the average concentritfon onr subregion d of the nuclfde 1 fn pethway p, fn pC1/kg or pCi/liter (see Appendices A and C of tti1s 9utde for IIOdels 1nd ..-uons for calculatfon of pat,-, concentratfons).

'ftp ts the ~a11e 1¥1r1ge concentration of nuc:ltde t tn patllwly p, fn pCi/kg or pC1/liter. .

tp ts the transport ttae of the food lled1um p ttirough the d1strtbutfon system, tn clays (Table D*l presents est1*tes of the transport t1aes thlt *Y be used fn 1teu of sfte-speciftc dltl).

'dp ts the IMual *ss or vol1111e of food aedi1111 p produced tn subregion d, 1n ltg or liters, VP ts the aass or vol11111e of the food lledfum p produced 1nnuilly with th~ SO-mile radius about the stte, 1n kg or 11~rs, and 11 ts the radiological decay constant for nuclide 1, tn days* 1 The population served by 111 the food produced within SO miles of the stte ts estimated as (D-3) where f, ts the fraction of the population within the age group a.

, ..

pp 1s the 1sti1111ted population that can be served by the quantity of food p

likely to be produced within SO miles of the stte, u,p ts the use or cons1111Pt1on f1ctor of food inedium p for the aver1ge 1ndiv16ual tn age group 1, tn kg/yr or liters/yr (taken (n,m T1b1e E-4), and VP ts the annual .. ss or vola,ne of food aedium p likely to be produced within 1 50-mfle radius about the site, tn kg or liters.

The annual popul1tton-tntegr1ted dose ts then calcul1ted as

.... .

(D-4)

pp ff pp*

I C plO p * .

P 'so

tf pp~ P50 Ind ts the tngestfon dose factor for age group* and nuclide t, fn llrlll/pCi (taken frc111 Appendix E, Tables E-11 to E-14). .

(

,.u,t-31

.

.,;,;._.,,...~'91': -~

.. ......,v~.*.

~ ~ 1 1 [ * ,,.--.~~

- .::*..c * : :: ...:t,-:.~ .,;,_ : *.,. *~ - .

-*tML.E D-1 IECOfllENDED VALUES FOR THE TRANSPORT TINES IN THE FOOD DISTRIBUTION SYSTEM*

FOOD MEDIUM OISTRIBUTION TRANSPORT TIME (1n days)

Fruits, vrains, and w19etables 14 Nfllt 4 Neat and poultry 20 Sport ftsh 7 C011111ercfa 1 ffsh 10 Drinking water 1 To be used 1n lieu of sfte-spec1f1c data on food dfstrfbutfon.

1.109-32

.._

-,- ..... -

-,-c.~

... ...... .....

. ,.... :.

,: *

- ~

..**. !~ ..*. ** , ~*-

ts the 1mual populatton-h1tegrtted dose to 9"11n .1 (total body or thyroid),

1n *n-ra/yr or ~ t d *n-ra/,r. *

. *-~- -.* *- ......,~... s. -

, 11 tM popu11tton consiatng food adt* p; and

, 50 11 tlll total ,opu11tton w1thtn so atles.

All other factors ' " 11 deftned above.

lote that the above *forwulatton ltaits the evaluation of the exposed population evaluation to the population "siding within SO atles IS specifted tn paragraph D,Section II of Appendix I to 10 CFR Part 50; In calculating the anntM1 population-integrated total body ind thyroid doses, the age distribution of the population within SO ailes *Y be assll!led to be the same as the age distribution of the U.S. population (Ref. 1). Reference 1 tndicates the fractional bre9kd0Wn to b: es follows: children, 0.18. teenagers, 0.11, 1nd adults, 0.71. Jnfants (0-1 year tn age) are not projected to exceed 21 of the population (Ref. 1), and their population fraction has been included tn that given above for children.

z. Use of the NDdels

- Population-Inttgrated Doses fNIII Ltguid Effluents The annual total body and thyroid population-integrated doses due to exposure to liq-uid effluents should be evaluated for the following principal pathways: potable water, aquatic

_food products, =xter~l trrad1ation from shoreline deposits, and terrestrial food products irri-gated with .. ter that has received the liquid efflwnt.

(1) Doses from Potable water The annual population-integrated total body and thyroid doses fl"OIII water consump-tion are evaluated for all subregions that hive water intakes existing or designated at the time of the license application. The products of the individual doses and the population exposed in

(* each such subregion within 50 111les from the site are slllllled to obtain the total dose. The

fonnulation expressed in Equ~tion (D-1) *Y be used.

The total body and thyroid dose of the individuals should be evaluated using Equation (A-2) in Appendix Aof this guide, together with the age-dependent usage factors uap obtained from Table D-1. The d11ut1on from the discharge point to'the us.ge point should be evaluated using appropriate hydrol~ical aodels for the various subregions.

If the population served by I particular .. ter supply systein ts not known, 1t can be 1stt*ted by the following:

,.,** Y/C (D-5) c 1s the average daily usage of individuals on the systsn, tn gal/day per person. * *

'* ts the 11ttated population 11ntd by the *tir 1yst111, and w ts the 1v1r1ge dl11y tntake of the .. ter supply 1y1t111, tn gal/day.

If the industrial u11ge fN191 the W1ter supply system ts ~ . tt can be sub-tracted fr"OII the average datly intake of the system before thil value h entered tnto Equation (D-5).

The population 11rvtd by 1 *ttr IU1'P1Y 1ysta lllhost intake ts within the 50-11111

. nd1us *Y tnclude ind1v1dua1s who reside outside the ctrcle. This population *Y be pro-rated to include only the population within tilt S0-.1le radius. Conver11ly, 1 . . ter supply system with 1n 1nt&ke beyond the 50-11111 radius *Y 11rve the population within the S0-11111:W-adius, wose

( *.

expesu~ v11 drink.ing *ter should bt included in the 50-a11e population 'dose evaluation.

1.109-33

(2) Doses fran Aquatic Food Products The 1nnual~popul1tfon-fntegrated total body 1nd thyroid closes,,,,...- consumption of aquatic food products are -.valuated using the production of sport and cC111111ercf1l harvests fn the various subregions. The afxfng ratio (or dilution) should be evaluated for each subregion using an appropriate hydrological IIIOdel. For sport harvests, the entire edible harvest is 1ssU111ed to be ingested by the popul1tfon wfthfn 50 afles. The fon1111l1tfon expressed by Equation

-

(D-4) should be used w_ith the population Pp given b1 the results of Equation (D-3). The 1ge-1pec:ffic 1ngestfon rates of Table E-4 .., be us~ 1n 11eu of sfte-specffic data.

For coa....ercfal harvests, the production wfthfn 50 ailes frc111 the site fs con-sidered as part of ihe total U.S. harvest. Equation (D-2) should be used to compute the average concentration, with VP as the total estf*ted U.S. ccnnercial harvest of the aquatic food

di1111 p. The annual populatfon-fntegrated dose fs then cOllputed using Equation (D-4) with PP* P50

The_age-specffic factors of Table E-4 .., be used fn lfeu of site-specific data.

(3) Doses from Shoreline Deposits The annual population-integrated total l>Ody and thyroid doses from recreational activities on the shoreline of the receiving water body are evaluated by s111111ing the product of the individual doses in each subregion and the population exposed therein. All subregions within the SO-mile radius should be considered where existing or designated recreational facili~

ties exist. If available, actual recreational usage in the vicinity of each facility should be used. The fol"IIUlation of Equation (D-1) fs appropriate.

(4) Doses from Consumption of Terrestrial Food Products Irrigated by Waters Receiving the Liquid Effluent .

The annual populatfon-fntegrated total body and thyroid doses from consumption of food irrigated with 11111ter from the body receiving the liquid effluent are evaluated following the procedures outlined fn the development of Equation (D-4). Note that the term VP of Equations (D-2) and (D-3) denotes the total production of food medium p within SO miles, not just the total production of irrigated food aedium p. The consumption rite data of Table D-1 may be used in lieu of site-specific data in the evaluation of Equation (D-4).

b. Population-Integrated Doses from Airborne Effluents The annual total body and thyroid population-integrated doses should be evaluated for the following principal exposure pathlllllys: noble gas submersion. inhalation of airborne efflu-ents. ingestion of contaminated terrestrial foods (milk, 11eat. and produce), and external irradiation from activity deposited on the ground. Available state or county agricultural pro-duction data aay be used for estimating the popul1tion-1ntegr1ted doses from food consumption.

For the evaluation of exposures frc111t111ospheric releases. the SO-mile region should be divided 1nto 160 subregions formed by sectors centered on the 16 compass points (N, NNE, NE, etc.) and annuli 1t distances of 1, 2. 31 4 1 5 1 10 1 20 1 30. 40, and 50 miles from the center of the facility. The atmospheric dispersion factors (x/Q) or si~iler factors should be evaluated at the r1dial ~fdpoint for each of the subregions using appropriate 1t1nospheric dispersion

aodels such as those described 1n Regul1tor1 &ufde 1.111. .

(1) Doses due to Exposure to Noble &lses

The annual population-integrated total body dose due to noble gas effluents should be evaluated by SU11111ing the products of the individual doses in each subregion and the population 1n each subregion. Equation (D-1) .., be used. For external exposure. the 110del does not differentiate between age groups. A structural shielding factor of 0.5 should be applied 1n conjunction with the dose factor data of Table B-1.

(2) poses due to lnhllat1on of lldfofodines and Particulates The annual popul1t1on-fntegr1ted total body 1nd thyroid doses fra111nhll1tion of airborne tfflu.nts should be evaluated by 11111111119 the products of the 1ndivfdua1 closes received tn each subregion and the population fn Nth subregion. Equ1t1on (D-1) ..Y be ,sed. The age-1pec:ific 1nhl11tton rates of Table E-4 .., ba used with the data of Tables E-7 to E-10

1.109-34 *

(J) .Doses~ to l!!9!stion of Terrestrial Food Products

~?*:. . .., -fi.!'*f~~:..:~-..--.-;..:~.-:*~:

.

._

TIie annual ,opulation-integrated total body end thyroid doses f,.. ingestion of terrestrial food products should be evaluated using the production data for *ch subregion. For aillt, Nit, end coanercial vegetables, tlle fol'lll.llation of Equation (D-2) should be used to calculate the average concentrations 1n the foods. These concentrations ere then used in Equation (D-4), along with the data of Tables D-1, E-4, 1~ E-11 to E-14, to calculate population doses. *

(4) Doses due to External Irradiation from Activity Deposited on the Ground The annual population-integrated total body and thyroid doses fro11 external exposure to surface deposition of the effluent should be evaluated using Equation (D-1). A household shielding and occupancy factor of 0.5 should be applied in conjunction with the dose factors of T&bli E=5.

IEFERENCE FOR APPefDIX D

1. *current Population Reports,* Bureau of the Census, Series P-25, No. 541, U.S. Dept. of Comnerce, 1975.

(

1.109-35

...au>Ut E

llli'ERICAL ~TA FOR THE CALCULATION OF ANNUAL DOSES TO NAN FROM ROUTINE RELEASES OF REACTOR EFFLUENTS This appendix contains data for use 1n the equations presented tn the Regulatory Position and in Appendices A, 8, C, and D of this guide. The n1111ertcal values presented in this appendix are those routinely used by the NRC staff. In instances where aore appropriate infonnation of.a site-specific nature his been developed and cloc1111ented, thlt tnforwt1on should be used.

Jn

nll!lber of instances the staff his found 1t necessary to provide guidance as to the value of* particular parameter 1n the absence of subJtantial 111piric1l data. Jn such instances the staff his exercised judgment.and his considered values used by others and the sensitivity of the results to the value 1sslllled.

Jnfonnation fs provided below under four broad categories: envirol'lllefltal data, tunan data, dose factors, and other parameters.

1. Environmental Data Table E-1 provides values for the following stable element transfer coefficients:

1. B1v for the esti1111tion of produce, leafy vegetable, or pasture grass radioactivity from that 1n soil (pCi/kg 1n vegetation per ptt/kg 1n soil)i

b. F* for the esti111tion of cow ailk activity from that 1n feed (pCi/1 tn *ilk per pCi/

day ingested by the anf1111l)i and

c. Ff for the esti1111tion of aeat activity from that 1n f~ (pCi/kg in 11e1t per pCf/day ingested by the ani1111l).

The data are largely derived from Reference 1: The value of the cow 11flk transfer coefficient for radioiodine ts based on the staff's review of the literature (Refs. 2-9).

Values of transfer coefficients for goat ailk are presented tn Table E-2 for a lt11ited number of nuclides. For nucltdes not listed tn Table E-2, the ailk transfer coeffic~ent from Table E-1 should be used.

Various 1ni1111l par1111eter values are presented 1n Table E-3 for use tn esti11111ting ani1111l product activity levels as functions of the corresponding levels 1n feed and water supplies.

2. Human Data Tables E-4 and £-5 present usage rates of various environmental lltdia by average individuals and .. xt11U111 tndfviduals, respectively, according to age group. *5tafoodN ts used to indicate intake of aquatic invertebrates such as lobster, crab, clams, and oysters. Ingestion of aquatic plant .. teria1 ts not nol'Wll11y asslllled.

J. Dose Factors i

'. Dose factors for 1atemal irradiation fNIII a uniforaly contusinated ground plane are presented in Table E-6 (Refs. 10 and 11), 111 units of llfflll/hr per pCi/112

These factors are i:i; applicable for surface contamination via deposition of liquid effluents on shoreline sedf111tnts or 11rbome effluents on fl"OUnd surfaces. Dose f1cton are provided for the total bod.Y and skin I:. only. Dose, to other orpns art 11sllleC! ..-.1 to tile total body dose. -:-* .

I: Dose factors provfded tn Table E-6 are derived f,,;;-;- consfderat1on of the dose rate to air

I 1 *ter above the ground plane and the penetration of the r1di1tfon tnto the body. Thi! total body dor.e ts C011Puted at I penetration depth of 5 an, the skfn dose ts coaputed at I depth of 1 *

!*

7 WiJ/m2

These tfssue depths art tndfcatld by leference 12, where tt 1s suggested that, for I.

I

,. 109-36

TAILE E*l STABLE ELEMENT TUNSFER DlTA*

Element

1v Vt9/Sof1 F11 (Caw)

N11k (d/1)

Ff Neat {d/kg}

H** 4.BE 00 1.0E-02 1.2£-02 C** 5.5E 00 1.2E-02 3.lE-02 3.0E-02

- p i.2E-02 1.1EDO 4.0E-02***

2.SE-02

4.6E-02 Cr 2.SE-04 2.2E-03 2.4E-03 Mn 2.tE-02 2.sr-04 8.0E-04 Fe 6.6E*04 1.2£-03 4.0E-02 Co l.4E-03 1.0E-03 1.3E-02 N1 1.tE-02 6.7E-03 5.3E-02 Cu 1.ZE-01 1.4E-02 8.0E-03 Zn 4.0E-01 3.IE-02 3.0E-02 Rb 1.3£-01 3.0E-02 3.lE-02 Sr 1.7£-02 8,0E-04*** 6.0E-04 y 2.6£-03 1.0E-05 4.6£-03 Zr 1.7£-04 S.OE-06 3.4E-02 Nb 9.4E-03 2.SE-03 2.BE-01 No 1.2£-01 7.SE-03 8.0E-03 Tc 2.SE-01 2.SE-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E 01 1.0E-02 1.SE-03 Ag 1.SE-01 5.0E-02 1.7E-02 Te 1.3E 00 1.0E-03 7.7£-02 I 2.0E-02 6.0E-03t 2.IE-03 Cs 1.0E-02 1.ZE-02*** 4.0E-03 Ba 5.0E-03 4.0E-04*** 3.ZE-03 LI 2.SE-03 5.0E-06 2.0E-04 Ce 2.SE-03 1.0E-04*** 1.ZE-03 Pr 2.SE-03 5.0E-06 4.7E-03

.,

Nd 2.4E-03 1.BE-02 s.oE-06 5.0E-04 3.3E-03 1.3E-03 Np 2.SE-03 . 5.0E-06 2.0E-04tt

.

..... .

Dita prutnted tn thfs table ts frm Reference 1 unless othel"W1se tnd1Clted, Neat 1nd *flk coefficients

.

ire blstd on spectffc 1ctfv1~ consfderatfons.

Fl"DII Reference 15.

t5ee teat.

ttr.,. leference 13.

-*

( :

1.10t-S7

TABLE E-2 IIICLIDE TlANSFER PARAMETERS FOR &OAT'S MILK*

El1111ent F11 (days/liter) ff 0.17 C 0.10 p 0.25 Fe 1.3[-04 Cu 0.013 Sr 0.014-I 0.06-Cs 0.30-

-

Values in thfs table ire from References 1 and 14 unless otherwise fnd1cated.

From Reference 15.

TABlE £-3 ANIIIW. CONSUMPTION RATES QF QAw Feed or Forage lflter

!!!!!l (kgld*~ [wet .efghtJJ h/dayJ Nfllt caw 50 (Ref. 10) '° (Ref. H) leef cattle SO (Ref. 10) 50 (Ref. 16)

Coats I (Ref. 17) I (Ref. 11)

I

I.*;

1.109-*

TABLE £-4 IEC<NECDED VALUES FOR Uap TO IE USED FOR THE AVERAGE IIIDJVIDUAL

. IN LIEU OF SITE-SPECIFIC D\TA PatfMy ~ !!!n. ~

Frufts, vegetables, I grain (ltg/yr)* 200 240 1'0 111111;: (t/yr)* 170 200 110 Neat I poultry (ltg/yr)* 37 59 15 Fish (ltg/yr )* 2.2 *s.2 ,.,

Seafood (ltg/yr)* o*.33 0.75 1.0 Drfnking 1111ter (1/yr)** 260 260 370 S~reline recreation (hr/yr)- 9.5 47 8.3 Jnf11l1t1on (a3/yr) 3700*** 8000*** eooot

.....

Consilnpt1on rate Dbtafned from Reference 19 and age-prorated usfng techniques fn Reference 10

D1t1 obtained directly fram Reference 10

Inh1l1tion rite derfved frQf dlta provided tn Reference 20.

tDltl obtained directly fl'CIII Reference 20.

(

TABLE E-5 1£COfllENDED VALUES FOR Uap TO IE USED FOR THE MXIU EXPOSED INDIVIDUAL IN LIEU OF SITE-SPECIFIC DATA Pathway !!!!!nl ~ l!!n. ~

Fruits, vegetables I grain (ltg/yr)*,**

.

520 630 520 Letfy v~tables (ltg/yr

26. 42

,1111t (1/yr). 330 330 400 310 Neat I poultry (kg/yr)* 41 65 110 Fish (fresh or salt)

(ltg/yr)*** 6.9 16' 21 Other seafood (ltg/yr)* 1.7 3.8 5 Drinltfng water (1/yr)t 330 510 510 730 Shoreline recreation (hr/yr)t 14 57 12 lnhalatton (m3/yr) 1400tt 3700ttt IOOOttt IOOOtt Consumption rate obtained from Reference 19 for average individual and

-...1ge-pror1ted and 111xim1zed usfng techniques contained in Reference 10.

Consists of the following (on 1111ss basis): 221 fruit, 541 vegetables (including leafy vegetables), Ind 241 grain

Consumption rate for 1dult obtained by averaging data from References 10 and 21-24 and age-prorated using techniques contained in Reference 10.

to.ta obtained directly from Reference 10.

ttoata obtained directly from Reference 20.

tttlnhalatfon rate derived frGII data provided 1n Reference 20.

1.109-40

TABLE E-1 Ellf!NAL l!QSE FACI!mS FOR STANDING~ CONTAMINATED CROUND (ara/hr per pC t /a2)

Uwnt Total lody n!!

H-3 o.o o.o C-14 o.o o.o IA-24 2.SOE-08 2.toE-08 o.o o.o E;~1 2.20£-10 2.60£-10

--54 Nn-56 5.80[*09 1.10£-08 I.IOE-09 1.30£-08 Fe-55 o.o 0.0 Fe-59 8.00E-09 1.40£-09 Co-58 7.00E-09 8.20£-09 Co-60 1.70£-08 2.00E-08 Ni-63 o.o o.o Nr-65 3.70[-09 4.30£-09 fu-t4 n- 5 1.50£-09 4.00E-09 1.70£-09 4.60£-09 Zn-69 o.o 0.0 lr-83 I.COE-11 t.30E-11 lr-84 1.20£-08 1.40£-08 lr-85 o.o o.o Rb-86 1.30£-10 7.20E-10

-

ib-88 3.50£-09 4.00E-09 Rb-89 1.50£-08* 1.IOE-08 Sr-89 5.60[-13 1.50£-13 Sr-91 7. lOE-09 la30E-09 Sr-92 Y-90

. t.OOE-09 2.20£-12 1.00E-08 2.60£-12 Y-91M 3.IOE-09 4.40£-09 Y-11 2.COE-11 2.70£-11 Y-92 1,IOE-09 1.IOE-09 Y-93 5.70£-10 7.IOE-10 Zr-15 5.00E-09 5.IOE-09 Zr-97 S.SOE-09 1.40£-09 lb-95 S.10E*09 I.OOE-09

.No-99 1.IOE-09 2.20E-09 Tc-99M t.60£-10 1. lOE-09 Tc-101 2.70E-o9 3.00E-09 lu-103 3.IOE-09 4.20[-09 lu-105 4.50£-09 S. lOE-09 lu-106 1.SOE-09 1.IOE-09 Asl-11111 1.IOE-08 2.10£-08 Te-12SM 3.SOE-11 4.IOE-11 1'1-127M 1.10£-12 1.IOE-12

, Te-127 1.00E-11 1.10E-11 Te-134 7.70£-10 t.OOE-10 Te-129 7.10£-10 1.40£-10 Tt-13UI 8.40E-ot t.toE-09 Te-131 2.20£-09 2.IOE-06 Te-132 1.70E*09 I.OOE-ot 1-130 1.40£-08 1.70[-0I 1-131 f.lOE-09 J.40[-ot -

1-132 1.70E-OB 1.00[-0I.

1-133 J.70£ 4.SOE-ot 1-1sc 1.60[-0B 1.IOE-08 1*135 1.20£-0B C: : 1.40[-0B

1.10M1

TABLE E-6 (Continued)

(l111ent Total lody !t!n Cs-134 1.20E-OB 1.40£-08 Cs-136 1,SOE-08 1.70E-08 Cs-137

C.20E-09 C.IOE-09 Cs-138 2. lOE-08 2,4DE-08

- -139 2,40£-09 2.70£-09 11-140 2.1DE-09 2.40E-09 11-141 C.30E-09 4.90E-09 11-142 7, 90E-09 I.OOE-09 La-140 1.SOE-08 1.70£-08 La-142 1.SOE-08 1.80E-08 Ce-141 5.SOE-10 6.20E-10 Ce-143 2,20E-09 2.SOE-09 Ce-144 3.20E-10 3.70E-10 Pr-143 Pr-144 o.o o.o J,00£-10 2.30£-10 ld-147

1,00E-09 1.20E-09 W-187 3. lOE-09 3.60E-09 Np-239 1,50£-10 1.lOE-09

1.109-42

.. *-**-**-*****- *****-*** **- ...

-*

calculatfonal pur,oses, the average depth of the blood-fora1ng organs *1 be assiaed to be 5 CII *

leference 12 also tdent1f1es the cells of the basal layer of ep1derm1s as the tissue of interest tn the ca11putat1on of skin dose and states an average depth for these cells of 7 atrJ/r:11.2. This 9u1dlnce ts reflected in the dose factors presented in *Table E-6 and also in those presented 1n Appendix I, Table 1-1. for use in calculating extemal doses froin noble gases.

Dose factors for tnternal exposure are provided in Tables E-7 through E-14, in units of 11re111 per pCi intake (Ref. 25). Tables E-7 through E-10 are for inhalation (one table for. each of the four age groups), while Tables E-11 through E-lC are for fngestfon. Dose.factors provided for the inhalation of H-3 tnclude an increase of SO percent to account for the additional amount of this isotope absorbed through the skin (Ref. 25).

As discussed tn Section B, *oiscuss1on,* these dose factors are appropriate for continuous tntale over a*one-yur period and include the dose COlllllii.tnt over a SO-year period. The cal-culat1ona1 scheme by which these dose factors are derived includes elementary consideration of changing p~ys1c11 ;nd ~tabolfc characteristics during the period over which the dose c0111nitment ts evaluated. For exal!ple, envirorwiental exposure of an infant oveF i or.e~~er period is treated as follows: dose during the ffrst year 1s ce111puted based on infant physiological and 11etabolic characteristics considering both the buildup and decay of the appropriate orvan burdeni dose during years 1-10 is computed based on child physiolc,gical and aetabolfc data considering decay of the organ burden from its peak value at age li dose during years 11-16 ts treated in a si~ilar fashion using teenager characterfstfCSi and dose during adulthood 1s COIIIPUted based on the physiological and metabolic characteristics of an adult. Age-dependent par. . ters are changed in steps at the breaks between age groups. * .

4. Other Por=n!ters Table E-15 has been provided as a central location for the recomnended values of aany of the 11iscellaneous parameters appearing fn equations fn this guide. In soine instances, a parameter's value or units ts a function of the equation ft ts used in. Additionally, for some parameters used in calculating activities in vegetation, the value is also a function of the exposure path-way. Table E-15 has been 6rganized to note these coq,1fcat1ons.

Values of the parameter SF' 1 structural shielding and occupancy factor, are given fn Table E-15 as 0.7 (for aaxf1111111 fndfvfduals) and 0.5 (for the general population). Using the oeneral approach given fn Reference 26, the staff esti1111tes an average structural shielding factor of 0.5 for typical reactor effluents. Assi,ning the 111ximi,n tndividual spends about SO percent of the time indoors, the overall shielding and occupancy factor is .then approxi111tely 0.7. The factor of 0.5 is used directly for population dose calculations. These factors are applicable for external 91111111 exposure fran noble gases and for external exposure from contaminated ground surfaces.

1. 109-43

.... _...... **-*** .--**** ..

TAILE E-1 PA:iE I OF J INHAUTI~ DOSE FACfDRS FDR AnuL TS C*REM ~Elt etC I INHALED I

-.UCLICE LIVER THYROID KIDNEY lUIWG Gl-lll

~--------------------

H J ND DATA le51E-07 la51F-07 l.51E-C7 I.SIE-07 1.SIE-07 l.!IE-07 C 14 Za27E-06 4a26E-07 4.26£-07 4.26E-D7 4.26E-07 4.26£-07 4a26E-OT U Z4 1.21e-06 1.zae-0, 1.21e-06 1.zae-06 1.21e-06 1.11e-06 1.zae-0,

~-----------------------

p 12 le65E-04 9a64E-06 6a26E-06 NO DATA NC DATA NO DATA leDIE-05 tR 51 NO DATA NO DATA la25E-OI Ta44~-~* Z.ISE-09 lelOE-06 4.l~E-OT MN S4 ND DATA ** ,sE-06 ,.ere-01 NO DATA

1.zn-0~ a.HE-04 ** 6TE-06 "N 56 NO DATA 1.sse-10 ,.1,e-11 ~D DATA 1.ue-10 1.i1E-D6 z.s,e-o, FE 55 J.OTE-06 2.12c-o, 4.IJlE-07 NO DaTA NO DATA ,.oae-o, ,.sc.e-01 FE St 1.c.,e-0, 1.4TE-06 a.JZE-06 ND DATA ND DATA le2TE-04 Z.J5E-05 CO SI ~D DATA l.91f.-Ol Z.59E-D7 ND CATA NC DATA 1.16£-04 l.JJE-05 co 60 ND DATA l.44E-D6 1.,se-0, ~o DATA NO DATA l.46E-04 1.56£-05 NI 61 5.40f-05 J.IJJE-06 lellE-06 1110 D4TA NO DATA z.ZJE-05 1.67£-06

... 65 1.,2e-10 z.,2~-11 l.14F-ll NO DATA ND 8ATA ,.ooE-OT 1.54£-06 cu 64 NO DATA I.IJE-10 J.69E-ll NO DATA ~.,ae-10 1.1t1e-01 ,.12e-06 lN 6S 4.05E-D6 1.29£-05 ~.12£-06 NO DATA 1.,ze-0, 1.01e-oc, 6.6ae-n6 l~ 69 4.2JE-1Z 1.ac,c-12 *s.65£-13 NO DATA 5.ZTE-12 1.11£-0l Z.04£-09 dR 13 ND DATA ~o DATA J.OlE-01 ND DATA ND DATA ND DATA z.,oe-oe BR 14 ND DATA NO DATA J.91£-01 ND DATA ND D~TA ND DATA Z.05E-13

~-----------------~-----

NO DATA ND DATl 1.60£-09. ND DATA ND DUA NO DATA LT E-24 NU DAU l.69£-05 7.JTE-06 NO DATA NO DAU fllD DAU Z.OIE-06 ND DUA 4.B4E-OI Z.41E-DI NO DATA ND DAU NO DAU 4.IIE-1'

tllB 19 NO DATA J.ZOE-01 2.lZE-01 ND DATA NO DATA ND DATl l.16E-2l SR 19 J.IOE-05 NO DATA 1.09E-06 NO DATA NO DATA 1.JSE-04 4.JTE-05 SR 90 1.zc.e-02 ~o DATA 7.62£-04 NO DATa NO DATA 1.zoe-03 ,.oze-os

~-----

SR 91 7.l4E-09 NO DATA J.IJE-10 ND DATA NO DATA 4.56£-06 Z.J9E*05 SR 92 l.4JE-ln NO OATA 1.64£-ll ND DATA NO DATA Z.06E-06 5.JIE-06 Y 90 Z.61E-Ol ND DATA 7.0lE-09 NO DATl ND DATA 2.12e-os ** ,ze-05

y .... J.26E-ll NO DATA 1.27E-1Z NO DATA ND DATA Z.40E-07 1.66E-10 y 91 t.JaE-05 NO DATA 1.55E-06 NO DATA ND DATA Z.lJE-04 4.llE-05 y ,2 I.Z9E-09 NO DATA l.TTE-11 NO DATA NO DATA la96£-06 9.19E-06

~--------------------------------------------

~

1.109-44

TABLE E*7, tONT*D P~E Z DF J INHALITI°" DOSE FACTORS FDA ADULTS C*REM PE, ~Cl ft,H&LEDJ PeUCL I :)I: IDNE LIVER ,.ao:w THYROID &IDNfY LUNG Gl*LLI

~-------------------------------------------------------------

y t) lellE*OI NO DATA leZ6E*10 NO DITA NC DITA **06E*06 5.27E*05 ZR ts l.J4E-D5 4.JCE*D6 z.,,e-o, NO DITA ** ,1e-o* z.z1E-D4 1.aae-os 1* en 1.21£*01 Z.45~*09 lelJE-09 NO ~ATA J.TlE*D9 ~.14E*06 6e54E*05

~=--------------------------------------------------*-

1.1,e-o, t.7TE-DT .5.Z6E-OT NO DITA -~a61E=DT 6oJlE-05 1.JDE-15

..0 DITA l.Slf*OI Z.ITE-09 ND Dill J.64E*OI lel4E*05 1.IOE-r~

lel9E-1J J.64E-1J 4.6lE*lZ ND ~ATI 5.SZE-12 ,.sse-01 5.ZOE*l r llYlD6 *** u-o, NO DUA a.OJE-06 awn DATA l.6TE-D5 a.nE-03 l.HE-04

&Gllt>,i I.HE-06 i.ZSi:=06 ?o4Jt-OT ND DUA 2.46E*06 5.T9E-D4. 1.TaE-05 TElZ5~ 4.ZTE*DT le91E-DT 5.14E-01 I.JlE*Dl i.55£=06 !~9?E*D5 1.IJE*06 TElZl" l.SIE-06 T.11~-07 1.,,e-01 4.IIE*OT s.TZE-06 l.ZDE-04 l.17E-05 TElZ7 1.TSE-10 1.01~-ll J.l?E-11 1.1ze-10 6.JTE-10 l.14E*07. 7.ITE-06 IE u~.- I.ZZE-06 S.ti4E*D7 le98E-07 4.JOE*OT 4.5TE*06 le45E*04 4.T9E*05

.-----------------------------------------

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~--------------------------------------------------------------

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~----------------------~-----

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1.109-45

l&8LL E-Te tONT*D PAGE J OF 3 l~H&LATIO~ DL1E F&tTo*s FD- ADULTS" l*REM P[l PCI l~H&LEDI NUCL ICE BD~E l lYER T.SLIOY THYROID KID~EY LUNG GI-Lll

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'" 142 J.29E-l2 J.JBE-l~ l.OlE-11 NO DATA Z.96E-l5 l.49E-07 l.96E-26

~------------------------------------------------------------------

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!'f0l47 6.~9E-07 7.62E-07 4.~6E-08 NO DAFA 4.45£-nl 2.76E-05 2.16[-05

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1.109-46

f&DLE E-1 PAGE I OF 1 l~HALATIO~ DOSE FACTORS F°" TEENAGER ClltE~ PE- Ptl INHALEDI

.,UCLI CE . IO~E LIVU T.IOCY THYROI~ KID~EY LUNG GI-LL I

NO DATA I.S9E-07 l.19E-OT le59E-OT l.59F-Ol ** ,,E-07 la59E-07 J.2~E-06 6.C9E-OT 6.09E-DT ** 09E-CT 6.~9E-OT 6.09E-07 6.09E-07 1.TZE-06 l.i2E-06 1.12e-a, 1.TZE-06 l.TZE-06 1.,2E-06 1.,2E-06

~~~---------------

Z.)6E-04 1. ni:-o, l.95E-06 'ID .DATA NC DAT& NO DATA lel6F-05 NO DATA NO DATA l.69F.-OI l.lTE-09 J.94E-~9 Z.6ZE-06 J.TSE-07 NO DUA ,.:nF.-06 1.0,e-o, ~o DATA l.~9E-06 2.49E-04 l.35E-06

~N 16 NO DATA Z.l2c-l0 J.ISE-11 NU DATA 2.2,.~-an l.90E-C6 T.lBE-06 f[ ss ** llE-06 z.,af-D6 *** JE-07 NO DATA -.o DATA 1.55E-05 7.99E-07 FE 151 1.,,e-0, ** ,zE-06 l.79E-06 NO DATA NO DATA l.9lf-04 Z.23E-05 CD SB NO DATA z.,tE-DT ,.~TE-OT NO DATA ND DAU l.HE-04 t.19E-05 tU 60 NO DATA 1.a,e-0, Z.41F.-06 NO D&T& 110 i)Ui 1.D9E-03 J.He-os

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TAILE E-1, CONT'D PAGE 2 OF J INHAL*TIO~ DOSE FACTORS FOR TEF~AGER INllE~ PER Ptl l~HALEDI lfUCL I DE *ONE LIYFlt ,.aoDY THYROID KIDNEY LU~G GI-LL!

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- *.* . --*

Tl~LE E-1, CONT'D PAGE J OF 3 INHlLlTIO~ DOSE FACTORS FCR TEENAGER C"REM PER Ptl I .... ALEDI "IUCLIDE BO~E LIVER T.IDDY THYROID KIDNEY LU~G GI-LLI

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.

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~---------------~----------------------------------------------------

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T41LE E-'J

AGE l OF l INHALATION Dr.SE FACTORS FD- CHILD C*RE~ PE~ *Cl l~HALEDJ

._UCL JUE 10 .. E LIVER T .800Y T~YMDID KIDNEY LUNG GI-LLI

~--------------------------------------

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6. IZE-06 T.56E-06 2.,oc-10 l.90[-05 NO DU-\

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'1.UE-05

~-----------------------------------------------------------------

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1. 71F-06

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tSR R4 NO DATA ~U DAU l.4R£-07 NO IJAU NO DATA NC DAU LT E-24

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1.109-50

f&DL~ 1-,, ca~T*o P~E Z OF 1 l~HALATIU~ D~SE FACTORS FOR CHILD C*RE~ PER ~Cl l~HALEDI

~UCLIDE 8U~E LIVER T.IIODY THYROID SID~EY LU,.G GI-Lll

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

5.0ltE*D8 ~O DAU !e lllt:-D*

NO DAU NO DATA

________ _

z.DlE-05 a.osE-04

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,------------------------

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~~--------------------------------------------------

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~--------

1.109-51

TlBLE E-9, CONT'D PAGE J OF J

INHALATION DOSE FACTo,s FOR CHILD IM~EM PER Ptl l~HALEDJ NUCLIDE IUNE LIVER T.BODY THYROID KIDNEY LUPfG GI-LLI

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~--------------------------------------------------

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1.109-52

T&ILE E*lO PAGE l DF J INHALATI~ DOSE FACTORS FDR INFANT CllllEM PEA Ptl l~HALEDI

..- . '}-.*.. _

...:~~q,f!!.-,_~~;;~..... -IVEA _-.c.ac,cy. JHYllDID KIDNEY LUNG GI-LL I

~-----~--------->----------------------------------------

ti J ND DATA 4.6ZE-07 4.6ZE-07 .... zF-07 .... zE-07 4.61E-D7 4.62E-07 C 14 ie&9E-0S Ja?,E-06 J.79E-06 J.T*E*D6 J.79E-06 J.TtE-06 J.79E-06

'IA Z4 ,.~4E*06 T.54E*06 T.S4[-06 T.54E-Du ,.s~E-06 T.S4E-06 T.54E-06

l.4SE*03 I.OJE*OS t.SJE-0~ NO DATA ND DATA ND DATA t.lSE-05 NO DATA ftO DUA ** ne-01 4.nE-01 t.45E-09 9.lTE-06 z.ssE-07 NO DATA l.llE-05 J.56E-O* NO DATA J.56E-06 J.14E*04 5.04E-06

MN H NO DATA lelOE-09 l.51E-ID ND DATA ,.16£-10 1.,se-0, 1.11e-os FE 55 l.4lE-05 l.59E-06 2.11E-06 ND DITA ND DATA 6.ZlE*DS 7.IZE-07 FE 59 9.69E-06 le6IE-05 6.77£-06 ~D DATA ~D DATA ,.zse-o-. 1.11e-os

~~~--------------------------------------~---------------------

CD 51 NU DATA l.?lE*OT I.JOE-06 NO ~iYA ~O DATA S.55E*04 7.95F.-06 to 60 ND DITA s.?JE-06 l.4lE-06 ND DATA ND DATA J.ZZE-03 2.ZIE-05 NI 63 Ze4ZE-04 l.46E*05 l.29E-06 ~O DITA

ND DUA le49E-04 le.UE-06

~-----------------------------

fill 65 l.TlE-09 2.oJc-10 l.?9E-ll ~D DATA ND DITA S.IOE-06 J.58E-05 tu,,. NO DATA lel4E-09 S.SJE-10 NO DATA Z.14E*09 6.64E*06 l.07E-05 z,. 65 1.,ee-os *.~1e-os 2.zze-os ND D&TA 2.JZE-05 4e62E-04 J.67E-05

ZN 69 J.15E*ll 6.91E*ll 5.lJE-!Z NO DATA z.ne-11 1.ose-0, ***"e-06 IR U NO DATA ND DATA Z.?ZE*OT NO DITA NO OITA NO DATA tT E-24 BR 14 ND DATA NO DATA 2.16E-07 NO DATA NO DATA ND DATA LT E-24

BR I> NO DATA NO DATA le46E-DI NO DATA NO DATA NO DATA LT E-24 U 16 NO DITA I.J6E-04* 6.JOE-05 ND DATA ND *DATA NO DATA z.1qe-06 ltD II NO DAU J.91E-07 2.o~e-0, ND DATA ND DITA NO DAU . Z.42E-t>l

It! 19 llfO DATA z.2,e-01 l.47E-O? NO DITA ND DATA ND DATA 4.llE-D8 Sit 19 2el4E-04 NO DATA I.ISC-06 ND DATA NO DATA l.4SE*OJ 4.STE-05 Sil 90 z.,z~-02 NU DATA 1.ISE-OJ NO DAT& ND DATA 1.01e-01 ** ,,e-os

SR 9l 6.IJE*OI ND DATA Z.47E-09 ND DAT~ ND DATA ,.,,e-os s.z-.e-os SR 92 T.5DE-09 ND DITA Z.T*E-10 11D DATA ND DATA I.TOE-OS t.OOE-04 Y 90 2.,se-0, NO DATA 6.JOE-01 ltO DAT& ND DATA l.t2E*04 T.4JE-05

~----------.-------~------------------------------

Y ti'- z.,1E-IO NO DATA t.tDE*lZ NO DATA ND DATA 1.,,e-0, 1.,ae-0, Y 91 4.ZOE-04 ND DATA 1.1ze-os ND DAT& ND DAU *1.TSE-OJ ,.ozE-D5 Y IZ lel7E*OI NO DATA ,.z,e-10 NO DATA ND DAU lelSE*OS t.04E*D5

~----------------------------------------~-------

( *;

1.109-53

TAILl E-10. tONT*D

PA;E Z OF J INHALATION DCSE F&tTORS FD, l~FA~T

...REM P[R ~er l~ALEDI

'WCL ICE IDNE LIVER f .lODY THY~DIO KIDNEY LUNC GI-LLI

~-----------------------------------------------------

I.07E-D7 ND DATA 2.9lE-09 NO DATA "NO DATA 5.46f-~~ 1. ne-01t 1.24[-D~ a.i,e-os l.4SE-D5 ~D DATA Z.22c-n5 1.zse-01 1.sn~os 1.07E-D7 l.lJE-DI I.J6E-09 ~o DATA 1.ese-01 1.eae-05 1.ooe-01t

~8 9~ l.&2E*D5 4.59E-06 Z.TDE-06 NO DATA J.57E-06 J.42£-04 9.0SE-06 "0 99 NO DATA l.llt-07 2.JlE-01 NO DATA I.R9E-07 9.63E-D5 J.48E-05 TC *9~ 9.91E-11 2.0~E-12 l.66E-II NO DATA. 2.22E-ll 5.79E-D7 l.45E-06

TtlOI 4e65E-14 5.~IE-14 5.IDE-13 NO DATA 6.99E*l3 4.&TE-07 6.03E-07 llUI03 le44E-06 NO DATA 4.ISE-07 NO DATA 1.03E*06 J.94[-04 l.lSE-05

tUl05 ** ,.e-10 NO DITA 2.,ie-10 NO DITA 6.42E-JO l.lZE-05 J.46E-05

llUl06 6.ZOE-05 NO DITA 7.77£-06 ND DATA T.61£-05 1.26£-03 lol7E-Olt

&GllO~ T.13f-06 5.16E-06 1.57E-06 ~O OAT4 7.IOE-06 2.62E-03 Z.36E-05 ffl25M J.40[-06 1.42£-06 4.lOE-01 1.16£-06 NO DATA Jel9E-04 9.ZZE-06

~-------------------~-------------------------------------------------------

TE127,. l.l9E-05 4.93E-06 *t.48c-06 1.41E-06 2.69E-05 9.37E-04 l.9~E-05 TE1Z7 l.59E-09 6.BlE-10 J.4?E-IO &.JZE-09 J.47E-09 T.39E-06 1.74E-05

TE 12'_. l.rlE-05 4.J5C-06 le59f-06 1.91E-06 2.ZTE-05 1.ZOE-03 4.93E-05 TEIZ9 S.6JE-ll Ze41E-11 J.)4£-11 4.IZE-ll 1.z~e-10 z.a*e-06 1.sse-os 1[131M J.6ZE-CI 1.93£-08 2.59£-01 6.31E*O& 1.19E-07 l.4Zf*(\4 e.51E-05 IElJl t.24E-ll 5.17E*IZ J.STE-12 . 1.IJE-11

. z.~)E*ll l.47E-06 ,.87E-06

TEU2 2e66E-07 le69E-D1 J.Z6E*07 le99E-07 7.J9E-07 2.43E-04 1.15£-05 I 130 4.54E-06 9.91E*06 J.98E*06 lel4E-03 l.~9E-05 NO DITA le42E-06 I 131 2.11e-os ,.a,e-os l.40E-05 le06E-DZ J.lOE-05 ~D DATA 7e56E-07 I UZ le71E-06 Z.53£-06 l.99E*07 I.Z&E-04 z.~ZE-06 NO DATA l.J6E-06 I IU t.46E-06 l.J7E-05 4.0DE-06 Z.54£-03 l.60E-05 NO DATl 1.54E-D6 I U4 ** ~,e-01 I.J4E-06 4.TSE-07 1.11E-05 1.49£-06 NO DATA ,.21e-01

-~--------------------------------------------------------------------------

I 135 Ze16C*06 5.4 ..tE-06 le9!1E-06 4e97E-04 6.05E-C\6 NO DATA leJlE-06 cs l )4 z.e3E-04 5.0ZE-04 5.JZE-05 NO DATA l.l6E-04 5.69E-05 9.53E-07 tS1J6 J.45E-05 9.61E-D5 J.71£-05 NO DATA 4.0JE-05 8.40E-~6 1.ozE-06

CSU7 J.92E*04 4.J7F*04 J.Z~E-05 NO DATA l.ZJE-04 5.09E-05 t.53£-07 CSUI Je6lE-D7 t.~IC-07 Zel4E-07 NO DITA 2.93E-D7 4.67E-08 6.Z6F-07 lllH le06E*D9 T.DJE-IJ ).07£*11 ND DITA 4.13E-l3 4.25£-06 J.64f-05

~---------------------------------------------------

--

1.1Dl-54

TABLE E-1?, CONT'D PAGE I OF J

..... &UYION DOSE F&troAS FOil INFANT CMREM PER Ptl l~HALEDI IIIIICL 1Dt BONE LIVER r.MDDY JHYRDID KIDNEY LUNG GI-LL1

~-------------------------------------------------------------

4.00E-05 4.0ot-De 2.0Tf-06 ND DATA ** 59E-09 l.l4E-03 Z.T4E-OS i.tZf~IO TeTOr-14 J.,sE-12 ~D DAT& 4.64~-14 2.lZE-06 l.39F-06 Z.14E-ll leJ6~-l4 1.4CE-ll NO DATA !gJ6E-14 lellE-06 4.95E-OT

~--------------~--------------

l&l40 ,.,ae-o, l.41t:-OT ,.,ee-01 NO DAT& 1110 DUA 1.20E-D1t ,.o6e-os L&l42 T.J6E-10 2.,,e-10 ** 4oE-ll ND .DATA NO DATA 5.17f-06 4.ZSE-05 CEl4l 1.,aE-O) 1.19£-05 l.42£-06 NO DATA I.TSt:-06 J.69F.-D4 l.S4E-D5 CHU 2.:>tE-07 1.,ee-~7 1.s~e-01 NO DAT& 4.0Je-oe 1.1ce-ns J.sse-os CE14't 2.HE-03 1.oSE-04 l.ZbE-04 NO DATA J.94E-04 T.DJE-~J l.~6E-04 l'RlO 1.ooe-os J.T4E-D6 4.91E-07 ~O DAT& le4lE-06 J.09£-04 2e66E-05

~CM:!>--------------------------------~---------------------------

PIU44 J.4Zf-ll l.JZE-11 1.,ze-12 NO DATA ~&~OE-12 l.lSF-06 J.06E-06

~D147 S.6TE-Db 5.llF-06 1.57£-07 NO DATA z.2sE-:>b z.,oe-o~ 2.23e-os If 111 9e26E-09 6e4'tt-09 2.ZIE-09 NO DATA ~o DATA 1.IJE~os Z.54E-05 NPZJ9 z.,sE-OT z.11e-01 1.,~E-08 NO DATA 4.TJl-08 4.ZSE-05 i.TBE-05

(

1.109-55

UILE E-11

PAGE 1* OF J INGEUror* DOSE FACTORS FOR IDULFS l*REM 'Etl ,er INGESTEDI NUCLl&;E IONE LIVER f.llOCY fHYROJD KIDNEY LUNG Gl-lll

~----------------------------------------------------------

II J NO DITA a.05E-D7 1.o~E-07 1.05E-D7 1.0Sf-07 1.ose-01 l.D5E-07 C Ile Z.14E-06 l.61E-07 t.61E-07 5.61E-~7 5.61f-07 5.6lf-D7 5.61E-D7 NI Zte 1.TOE-06 1.,oE-06 1.TDE-06 1.,oE-06 1.,oE-06 1.,oe-0, l.70E-06

.-----------------------------------------

, JZ l.9JE-Olt l.20E-05 lele6E-06 ~O QITA NC DATA NO DITA 2.l?E-05 Cllt 5l NO DUI ~o CATI Z.6~E-09 1.s,e-0, ,.a,t-10 ,.sJE-09 6.69E-07

~O DUI 4.57E-06 ,.,2e-01 ND DITA l.J6E-06 ND DITA 1.teoe-os

"" 51t

MN 56 NO DATA l.lSf-07 Z.04E-OI ND DITA le46E-07 ND DITA J.67E-D6 FE 55 z.nE-06. a.,oF-06 4.teJE-07 NO DAU ND DITA 1.06E-06 1.o,e-06 FE 59 4.JteE-06 I.DZE-05 J.91E-06 ~D DATA NO DATA Z.15E-06 J.40E-05

co 58 NO DITA ?eltSf-07 le6TE-06 ~D DITA ND DATA ND DAU l.51E-D5 CD 60 ND DITA Z.lltf-06 4.Tzt-06 ND DITA ffO DAU ND DAU 4.02E-05 ifl 61

l.JDE-04 9.0lE-Oo 4.J6E-06 ND DATA ND DITA NO DAU 1.ue-06

~-----------------

NI 6!i 5.ZIE-07 6el6E-D8 ).lJE-01 ffO OITA ND DITA ND DITA l.TltE-06 cu 64 NO OITA I.JJE-08 J.91E-OI NO DITA Z.lOE-Dl NO DATA T.IOE-06 ZN 65 4el4E-D6 l.S4E-05 ** 9oE-D6 NO DATA l.DJE-05 NO DATA 9.7DE-D6

ZN 69 1.on-01 1.:ne-01 l.J7E-09 NO DITA l.71E-OI ND DATA 2.HE-09 IR 13 fl!D DATA ND DATA 4.0ZE-01 NO DITA ND DATA NO DITA ,.ne-oe Bit 14 ND DAU ffO DAU -5.ZlE-01 NO DATA NO DATA NO DATA 4.09E-U

IR IS NO DUI NO DAU 2.l4E-09 NO DITA. NO DATA NO DITA LT E-24 RB 16 ND DITA 2.llE-05 9.13E-06 NO DATA NO DATA NO DAU 4.l6E-D6 Al H NO DAU 6.on-oe leZlE-01 NO DATA NO DATA NO DITA I.J6E-19

lt8 19 NO DITA 4.0lE-01 lel2E-OI ND DITA NO DITA HD DAU z.ue-21 SR 19 J.OBE-04 NO DATA lel4E-06 ~D DITA ND DUA ND DAU 4.94E-D5 sa 9D ,.sae-DJ NO DATA 1.,.e-01 fltO DATA NO DITA HD DITA 2.l9E-04

le61E-D6 NO DITA 2.29E-~7 ~D DITA NO DITA NO DAU 2.lOE-05 z.t5E-D6 ~o DITA 9e3DE-OI NO DITA NC DITA ND DITA 4.Z6E-D5 9.6ZE-D9 NO DITA 2.sae-10 ~D DITA NO DIU NO D~U 1.oze-04

Y tlM ,.o,e-11 ND DATA J.52E-IZ NO DITA ND DAU ND DAU z.ne-10 Y tl leltlE-D~ NO DAT* Je?TE-09 ND DITA ND DITA NO DUI T.T6E-05 Y 92 leltSE-10 ND DITA Z.47E-ll ND DITA ND DAU ND DATA 1.ttae-os

..'

1.109-11

TABLE I-lie CONT'D PAGE 2 OF J lftGESTIDN DOSE FACTO~S FDf' ADULIS l*REM PER Ptl INGESffDI NUCLIDE IONE LIVEll T.IDDY THYROID KIDti,EY LUNG 11-LLI

Z.6SE~C9 ND DATA 7.40£-ll ND DATA ND DATA ND DAT& I.SOE-05 J.04E-DI t.TSE-09 ***OE=Dt ND DATA leSJE-01 NO DATA J.OctE-05 1.,1e-o, 1.1,e-10 1.,se-10 ND DATA lelZE-iO ~D DATA 1.ou-04

.------------------------------

~8 95 ,.2ze-o, J.46E-09 l.16E-09 ND D~TA J.42E-09 NO DATA Z.lbE-05 ND t9 ND DATA 4.JlE-06 I.ZOE-OT NO DATA ** 76E-06 ND DATA ** t9E-06 TC t9M 2.4TE-IO 6.91E-l0 l.19E-09 ND DATA 1.o,e-01 J.4Zf-lD 4.lJE-07

TClOl z.~E-10 J.66E-l0 J.59E-09 NO DATA 6.59E-D9 1.17£-lO 1.aoe-21 RU103 lel5E-07 ND DATA 7.97E-01 ND DATA 7.o,e-07 NO DATA Z.16E-05 RUIO~ , 1QS4E-OI NU DATA 6.0IE-09 ND DATA le99E-07 ND DATA ** 4ZE-06

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

RU106 Z.TSE-06 ~O DATA J.41E-07 ND DATA 5.31E-06 ~O D!Tl _____

1.ne-01i AG110M la60E-07 la4IE-OT l.79E-OI ND DATA 2.91£-0T NO OATA 6e04E-05 TE1Z5M* Z.69E-06 ** TlE-07 J.59E-07 l.06f-07 1.0,e-os NO DATA I.OTE-D5 fElZT" 6.TTE-06 Z.4ZE-06 I.ZSE-07 a.7JE-06 z.,sE-05 NO DATA z.ne-os TE12T 1.aoe-01 J.95E-OI Z.JBE-01 l.15E-OI 4.41E-07 NO DATA I.HE-06 rE l29M I. UE-05 4 .19E-06 l. IIZE-06 J.95E-06 4.IOE-05 HO DATA s.1,e-os Tel29 J.l4E-OI a.11e-01 7.6>E-09 z.~lE-01 ** ,zE-07 NO DATA 1.ne-01 TC l31M 1.TJE-06 .... ,~-07 7.05E-07 a.J4E-06 e.STE-06 ND DATA l .. 40E-05 TEl31 a.9TE-08 8.23E-D9 6.ZZE-09 1.,ze-01 l.63E-DI NO DATA z.HE-09

~-

TUJZ Z.52E-06 1.6JE-06 1:ue-06 . ,.,oE-06 1.576-05 ~D DAU 7. llE-05 1 130 T.56E-07 z.ZJE-06 I.IDE-07 lel9E-04 J.41E-06 ND DATA la9ZE-06 I 131 4.16E-06 5.9SE-D6 J.41E-06 l.95E-03 1.oze-ns ND DATA 1.STE-06

I 112 2.0:1.E-OT 5.0E-OT ** ,oE-DT 1.,oe-os 1.65£-07 NO DAU 1.oze-01 1 an l.42E-06 Z.41£-06 T.SJE-07 J.63£-04 4.JlE-06 HO DATA z.zze-o, I 134 1.o,e-01 Z.IIE-07 1.o,e-01 ** ,,e-o, 4.SIE-07 ND DATA z.su-10

~---------------------~--------------------~---

I 115 4.4JE-OT lal6E-06 4.ZIE-OT 7.65£-05 lel6E-06 ND DATA l.JlE-06 CS1J4 6.22E~05 l.41E-04 l.ZlE-04 NO DATA 4.T9E-05 le59E-05 2a59E-06 CS1J6 ,.51£-06 z.ne-os I.HE-OS NO DATA 1.oe-05 l.96E-06 z_.9ZE-06

a.cc-------------------*-----------------~--------------------_.

CSIJT J.9TE-05 l.09E-04 i.14E-05 NO DATA ______ _

J.TOE-05 1.2,e-os z.11E-D6 CSIJI 5.5ze-01 1.e,e-01 ,.,.OE~I NO DATA I.OlE-01 T.tlE-D9 4.65E-lJ IUH 9.TOE-01 6.91E-11 Z.14E-09 NO DATA ** 4,E-11 ,.,ze-11 a.TZE-07

( .

1.10,.11

T&ILF E-11, CD~T*D

P~E 1 OF J IN,ESTIDN DOSE FACTORS FOR ADULTS (NREM PfR Ptl INGESTED)

'IUCLIVE IO~E LIVER T .BODY THY1l01D KID~EY LUNC GI-LL I

9&140 z.oJC-05 Z.5SE-08 laJJE-06 NO DATA 1.nt:-0, la46E-DI lt.llE-05 Ulltl 4e7lE-DB 1.~6C-ll 1.s,e-09 ~D DATA J.31£-ll z.ozE-11 Z.22E-17 Hl42 z.tJE-oe z.1,e-11 laJ4t-09 ..0 DAFA 1.ase-11 laZltE-ll 1.0DE-26

Ul40 z.~ol-09 l.26~-09 ,.JJ[-10 NO DATA ND DAfA ND DITA 9.UE-05 LU4Z 1.21E-lD s.12e-11 l.4SE-ll ND ~ATA NC DATA -0 DATA 4.UE-07 CE14l 9.36E-D9 6.JJE-09 ,.1ec-10 ND DAT& Ze91tE-D9 NO DAT& Z.42E-05 CElO le65E-09 l.22F.-06 I.J5E-IO ND DITA 5e17E-IO NO DATA 4e56E-D5 CEl44 4.ABE-07 2.04:-07 l.62E-OI ND DITA le2lE-07 NO DITA l.65E-O" PA143 ,.2oe-o, J.69c-09 4.56E-l0 ND DATA Z.IJE-09 NO DATA 4.03E-0S

Pll14" ,.01e-11 1.2se-11 I.SJE-12 ND DATA 7.05E-12 NO DATA 4.J3E-U ND147 6.29E-09 7.27£-09 4.15E-l0 NO DATA 4.25E-09 ~O DATA J.OE-05

.. 11!7. l.DJE-07 l.61E-08 J.OlE-01 NO DATA NO DATA NO DATA 2.12e-05 NP239 l.l9E-D? l.17C-1D 6.45E~ll ~D DATA J.65E-l0 ND DITA Z.40E-05

i.

1.109-58

TULE E-lZ PAGE l DF J INGESTION DDSE FACTORS FOR TEE"A~ER CNlEM PER Ptl l~GE5TED1 NUCLICE IDNE J.IOl'Y THYROID KIDhEY LUNG GI-Lll

It J ND DATA l.06E-07 l.ObE-07 1.06£-07 ** ~6E-07 le06E-07 le06E-07 t 14 4.06E-06 l.12f.-D7 l.l2E-07 i.llf-07 IQ!lf-07 a.12E-07 l.l2f-07

~A 24 Z.JOE-06 Z.!OE-06 2.JOE-06 z.J0[-~6 z.,ot-06 2.10E-06 1.JOE-06

~-------------------------------------------------------------

z.nE-04 1.,1c-os l.07E-D5 NO*DATA NO DATA NO DATA Z.J2E-05

..U DATA NO DITA J.60E-D9 Z.OOE-09 T.19c-10 5.l4E-09 ** as[-07 ND DATA 5.90E-Db 1.17£-06 Nn DAT& l.76[-06 ND DATA leZlE-05

MN 56 111D DATA l.~IC-07 2.RlE-08 NO DATA 2.ooe-01 NO DATA l.04E-05 fE 5~ J. TU-06 2."8F*-o6 6.ZSE-07 1110 DAU ~O OATA l.T~E-06 lel6E-06 FE S9 5.11E-06 l.,rE-05 5.Z9E-06 ND DATA NO DATA 4.12E-06 J.Z4E-ns

~~-------------------------------

to ~8 ND DAT& ,.1ze-01 2.Z4E-06 NO DATA ~o* UATA ND DAY& 1.,~e-05 to *O NO DATA 2.&lE-06 6.llE-0~ WO DATA - ~ DATA

NO DATA -J.66E-05

~I 61 I.TTE-04 1.25(-05 ** DOE-06 NO DATA NO DATA NO DAJ, l.99E-06 ,,

-,1 65 Te49E-D7 ,.~TE-08 4.J6E-OI ~D DATA ND DATA NO DATA s.ue-06 I* .* -

cu 64 NO DATA 1.1se-01 5.4lE-DI NU DATA 2.~lE-07 NO DATA l.92E-06

,,.. 6~ ,.,,e-o, 1.coe-tS ** 13E-06 NO DATA 1.zee-~5 ND DATA l.47E-06

(

~-------~-------------------------------------------------

lN 69 l.47E-OI 2.,oe-01 l.96E-09 NO DATA a.~1E-D8 ND DATA 5. UE-08 I\!\ u NO DATA ND DATA ~.74E~I NO DATA NO DATA NO DATA L'i' E-24 BR 14 NO DATA NO CATA 7.22£-01 NO DATA NO DATA WO DATA LT E-74

ND DAU NO DATA ).05E-09 NO DATA No-*DnA NO DATA LT E-24 Nn DUA. 2.,ae-05 *** ~E-OS ND DATA NO DAU NO CUA 4.4lE-06 NO DAU 1.sze-01 4.S4E-01 NO DATA hD DI.TA ND DUA 7.JOE-15

Ill 19 NO DATA 5.~0E-01 J.19E-OI NO DATA ND DATA NO DAU l.4Jf~l 7 SR l'1 4e40E-04 NO DATA l.Z6E-05 NO DATA NO DATA ND DAU ,.z .. e-05 s" to ** ,oE-OJ ND DATA z.o~E-OJ NO DATA Nn DATA ND DAU 2.ne-04

Slit tl I.DTE-06 NO DUA J.UE-07 ND DITA ND DATA HO DAU J.66E-05 Slit t2 J.D5E-06 NO DUA 1. )OE-07 NO DATA NO DATA NO DATA 7.l7E-05

\' 90 1.:ne-01 NO DAU J.nE-10 NO DAU ND DAU NO DAU le I JE-D'i

y *1 .. l.29E-10 ND DUA *.HE-12 NO DATA NC DAU 110 DATA 6.09E-n9 y ,1 z.o&e-01 ~O DAU t.HE-09 fllO DATA ND DATA 110 DATA l.2ti.E-05 y '2 lellE-09 ND DAU J. 5C.E-l l NO DAU IND DATA ND DATA J.UE-05

~------...-.----------------------------------------------------------

(

1.lot-59

JAdLF. E*ll, CONT'D PA:.E Z Of J INGESTION onse FACTORS FD~ TEE~AGE*

INREM PFlt Ptl l~GESTEDI NUCLl:>E IDffE LIVU T.IDDY THYROID KIDffEY LU..G Gl*LLI

J.83E*09 ~D DATA 1.ose-10 ND DATA ND DATA NO DATA I. l 7E-O'f 4.12e-01 1.Jot-01 l.9~E-09 NO DATA l.91E*OI NO DATA ,.ooe-os Z.JTE*09 4.69£-10 Z.l6E~l0 ~D DATA T.llE*IO NO DATA le27E-04

~-------..----------------------------

1.22e-o, 4.S~:-D9 Z.51E-09 ND DiTA 4.4ZE*09 NO DATA l.95f-D5 NO DATA 6.03[-~6 lelif-06 NO DATA &.3BE*05 NO DATA leOIE-05 1.ize-10 9.26£-10 1.zoe-01 NO DATA 1.11e-n1 t.1*e-10 ** 01e-01

~----------------------------

TtlOl J.6DE-l0 S.lZE-10 5.0lE-09 ND DATA 9.26£*09 J.lZE-10 le75E-17 RU103 Z.55E-07 NO DAU 1.09£-07 NO DATA l.99E-07 NO DATA 2.13E*05 ltUl05 z.11e-01 NO UATA l.46E-09 ~o DATA 2.75E*07 NO DATA J.76E*05

- - - - -*********T*-..*--**--***~-----*---******--*************--***--

RUl06 J.~2E*06 ~O DATA 4.94£-07 NO DATA 1.,6E*06 ND DATA leHE-04 AGllOM* ,.osE-07 l.94E-07 1.1,e-01 ~o DATA J.?OE-07 NO DATA 5.0E-05 TElZS" J.IJE-06 I.Jlf*06 5el2E-Q7 l.07E*06 ~O DATA NO DATA leUE-05 TE127M 9.67E*06 J.4lE*06 l.l5E-06 Z.JOE-06 !e92E-05 NO DATA Z.41E-05 JE127 1.SIE-07 5.~0E-08 J.40E-OI le09E-Ol. 6.40E*07 ND DAT* 1.zze-os TE129M a.63E-05 ,.ose-06 Z.58E-06 t.z~E-06 ,.~ZE-05 Nn DATA 6.lZE-05

TEl29 4.41£-01 le67F.*08 1.01E*OI J.ZOE-01 1.eee-01 NO DATA 1e45F.*07 TE13l~ Z.44E*06 J.17[*06 9.76E-07 l.76E*06 1.zze-os NO DATA 9.ne-os TElll Z.79E*OI 1.ase-01 1.1ze-01 z.ase-01 l.i2E-07 NO DATA z.nc-o*

tEl32 J.49E*06 z.ZIF.-06 Z.OSE-06 z.JJE-06 Z.l2E-05 NO DATA J.OOE-05 1 no I.D3E*06 Z.98f*06 lel9E-06 2e43E-04 4e59E*06 NO DATA z.29E*06 I Ul s.15E*06 1.19(-06 4.40E-06 z.J9E*03 l.41E-05 ND DATA a.ue-o, 1 nz z.79E*07 ,.JOE-D7 z.,ze-o, Z.46[-05 &.15E*D6 NO DATA J.UE-07 I U3 z.01E*06 1.41~*06 le04E*06 4a76E*04 t.91£-06 NO DATA z.see-o, I Ult &.46E-07 J.IJE-07 a.,,e-o, ** 4SE-06 ,.1oe-01 ND DATA S.IDE-09

~--------

I US 6.IOE-07 le57E*06 5.IZE-07 J.OlE*04 2.41E*06 ND DATA 1.74E*06 tSl34 ** JTE-05 l.97E-04 t.14E-05 ND DATA ,.z,e-os z.J9E-05 Z.45E-06 CSU6 ** 59E*06 J.JIE*O~ z.Z7E-OS ND DATA l.14E~05 z.,oE-06 2.,ze-0,

~-~----------------------------------------------

tSlJ7 1.lZE-04 l.49E*04 1.1,e-os NO DATA I.OTE-05 ** ,,e-os z.12E-06 CSUI 7a76E*OI le4tE*07 7.45E*OI NO DATA 1.1oe-o, 1.21E-OI 6.76E*l1 IAIH *1.HE*Ol ** TIE*ll ~.O~E-09 NO DATA ,.z2E-ll ** ,4E*ll a.Z4E*06

~-

-

I.lot-GO

fABLE E-lZ, tONT*D PA:.E J OF J INGESTION DOSE FACTORS FDR TEF.~AGF.R CNREM PER PCI INGESTfDI

'tUCLll:C IONE L IYl:lt T.IODY THYROID IC1D,.£Y LUNG GI-LLI

11140 Z.14E-D~ J.~RE-01 i.lJE-06 ND DATA J.llE-D8 Z.l4E-D8 4.JIE-05 11141 ** 71E-D8 s.01r-11 z.Z4E-09 ~D DATA ~=6SE-ll J.43E-ll J.43E-13 11142 z.,,E-01 ,.,,e-11 l.14E-09 !WO DATA Z.5Jt-ll 1.*tE-ii ~.llE-ZO

Lll4D J.41E-09 lallE-09 4.55E-10 NO.DATA NC DATA ND DATA 9.12E-l 5 Lll42 1.1,e-10 7.95E-ll 1.,ee-11 NO DATA ND DATA NO DATA Z.42E-C~

tl:141 1.JJE-DI 1.1,e-o, 1.D2E-09 ND DATA 4.llE-09 ND DATA Z.54E-C .i

tElltl Z.JSE-09 1.71E-D6 l.91E-10 ND DATA J.6TE-l0 ND DATA 5.l4E-05 Ul44 6.96£-07 z.eee-07 J.74E-OI ND DATA l.72E-07 ~O DATA l.75F.-D4 PRlO 1.Jlf-D8" ~.23[-09 ** ,2e-10 ~o*DATA J.n4E-09 NO DATA 4 * .UE --------------------------------------------=~------------------------------

PR144 4.)0E-11 l.76E-l1 z.1,e-12 ND DATA 1.01e-11 NO DATA 4.74E-}4

- * * -- ~D147 9.11[-09 1.oze-oe 6.llE-10 NO DAU 5.99£-09 NO DAU J.UE-05

- ~ 187 .J.46E-07 1.l9E-07 ~.trE-01 NO DATA NO DA'A NO DATA 3.Z2E-05

~-I:.';: . ~ _;, -~1/ ... ,'..,:/..;,i *-'*"*~-----~------~-.-- - - - - - - - - - - - - - -----------------------------------------

- . . ~P239 le76E-09 l.66E-l0 9.22E-ll NO DATA 5.21£-10 NO DATA Ze67E-05 1.109-11

UBL~ e-u PAuE I OF J l'-GESTION DOSE FACTORS FDR CHILD C"RE~ PER *ti l~GESTEDI "UCL 1.)E 10-.F. L !VEIi. TeRDUY LUNG GI-Lll

ft J ~o DITA Z.OlE-07 Z.01E-D7 2.0JE*D7 z.~,~-07 Z.DJE-D7 Z.OlE-07 t 14 1.21e-os z.-zE-06 Z.42E-D6 2.42E-06 Z.4ZE*06 Z.42E-n6 2.42E-06 ltitl 14 ~.,oE-D6 S.IOE-06 5.IOE-06 S.IDl-06 s.,o~-~6 5.IOE-06 5.IOE-06

p J2 lo75E-D4 J.16r-os J.lBE-0~ *D DITA ..n DITA NO DATA z.zeE-05 Cit S 1 . NO DATA NO tATA l.90E-09 4.94E*n9 1.JSE-09 ** ozt-09 4.72E-07 MN 54 ~D DITA l.~7E*05 Z.15E-06 ND DATA ,.ooc-n, NO DATA *** eE-06 MN '56 NO DATA J.J4E-01 T.54[-08 .. o OITA 4.C4E-D7 ND DITA 4.14E-05 FESS 1.1se-os 6.lOE-06 l.19E-06 NO DAT4 NC DATA J.45E*06 l.13£-06 FE 59 ,.,~E-05 l.61E-05 a.Jj[-05 .. D DATA NO DITA 7.74E-06. 2.78E-05

CD H ~D DATA 1.IOE-06 S.51E-06 NO DATA NC DAT& NO DAU 1.osE-0~

co 60 ~O DATA 5.29F.-06 l.56E-0S NO DAT4 1110 DATA NO DAU 1.*JE-05

.... 63" s.31E-C4 z.saE-05 l.lJE-1)5 NO DATA NO D&Tl fllO DAT& l.94[:-06

... 65 z.22E-06 1.09F-O? 1.22e-01 HO DATA NO DATA NO DITA 1.56E-05 cu 64 NO oar, 2.45E-07 l~48E-07 NO DAT4 s.*2E-07 NO DATA l.15[:-05 ZN 6S l.37E-05 J.oSE-0~ 2.21[-05 NO. D*TA 2.JOE-05 Nn DITA 6.41£-06

ZN 6fJ 4.JSE-08 6.~3£-08 s.ese-09 HO DATA 1.9'iE*D1 NO DATA J.*9E-06 IR U HD DATA NO DATA l.71E-07 NO DATA ND DATA NO DATA LT E-24 BR l'i NO DITA HD DATA l.9S~-07 NO DATA NO DATA NO DATA LT E-24

~?---------------------------

AR b NO DAU NO DATA 9.lZE-09 NO DATA NO DAU NO DAU LT E-24 MIi 16 NO DAU ,.1oe-os 4.12£-05 NO DATA NO DATA NO DAU 4.JlF-06 RI 18 ND DITA l.9CE-07 l.l2E-07 ND DAT& NO DATA NO DAU ** ,2c-09 It i' 19 NO DAU l. l le-07 l.04E-D7 '.10 DAU ffD DAT& NO DITA 1.oze-09 SR 19 I e3ZE-03 NO CATA 1. 77E-05 i'40 DATA 'fO DAU NO DUA 5. llE-05 SR 90 1.,oe-02 ND UAU 4.llE-03 ND DATA ND DUI ND DAU 2.HE*D'i

SR 91 Z.40E-05 NO DATA 9.06E-DT NO DAU ND DAU NO DITA 5.1DE-05 SR 92 9.0JE-06 ND DITA J.62E-07 rtD on, ~O DUI NO DUI 1.ne-0*

y 90 4.UE-01 ND DITA l. h'>E*D9 ND DAU ND DAU NO DITA l.UE-04 y ti.,. ,.,2e-1c NO DATA 1.ne-11 .tiilD DAU .. o D&U NO DAU J.OE-07 Y 91 6.02E*07 ND DATA le61F*09 ND DATA !WO DAU fWO DITA 1.02e-os y ,2 J.60E*09 ~D DATA leOJE*lD NO DITA ~O DATA ND D&Tl le04E-04

J.109-12

___J

TAILE E-IJ, tONT'D PAGE Z OF J INGESTION DOSE FltTOlllS FOR CHILD c..-e" PE, ~ti l~CEST£D1 NUCLIDE IDNE LIVER T.DDDY THYltDID lllO..EY LUNG GI-LLI

=-~--------------------------------------------------------------------

1.14~-0I NO DATA i.i)[-10 NO DATA NO DATA NO DATA le'TDE-04 l.16E-07 ,.~sE-01 2.z1e-01 NO DATA J.6SE-Oi NO DATA !.,66E-05

- 99£-09 1.01e-o, ,.,,e-10 NO DATA le45E*09 NO DATA l.UE-04 NI 95 z.zse-01 ** ,,E-09 ** Z6E*09 ND DATA I.ZJE-09 ND DATA ....---------

1.,ze-os NO 99 ND DATA leJlE-05 J.Z9E-06 NO DATA Z.14£*05 NO DATA lelDE-05 TC,, * *

ZJE-10 1.11e-o, ,.ooe-oa NO DATA z.,,e-01 ,.1,e-10 1.0,e-o,

rtlOl 1.0,e-o, 1.12E-09 l.42E-OI NO DATA 1.,1E-08 s.,ze-10 ,.s,e-o, iilUiOJ Tu!!E-07 ND DAT& ).llE-07 NO DATA

a.14E-06 NO DATA 1.1,e-os ftU105 6e45E*OI ND DATA 2.14E-OI ND DATA 5.6TE*DT NO DATA 4eZlE*D5

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

RUlD6 l.lTE-05 NO DAT& le46E-06 NO DATA I.SIE-05 NO DATA 1.12e-04 AGUDM 5.HE-07 "J.olt[-07 Z.91E-07 NO DAT& ,.nE-07 ND DAU 4.UE-05 TE125M l.l4E*D5 J.09E-D6 1.52E-06 J.ZDE*D6 ND DATA NO DATA l .. 1DF.*OS

~--------------------------------------------------------

JE1Z1M Z.19E-05 T.TIE-06 J.4JE-D6 6.91E-06 !.Z4E*D5 NO DATA z.,u-os TE127 4.71E-D7 1.21F-07 1.DlE-07 J.16E*07 l.14E*D6 NO DATA l.194E-D5 ffl29M 4.87E-D5 leJ6E-D5 T.SoE-06 1.57E*05 l.4JE*04 NO DATA ~.94E-05 1£129 l.J4E-D7 J.74E*08 1.llE-01 9.56E-OI J.~2E*OT NO D&fA a.J4E*D6

_, _________________________________.._ _______________________ _

TElJlM T.20E-D6

_______________ Z.49f*06 2.65E-06 5.IZE-06 Z.ltlE-05 NO DAT& 1.01E*D4 TE131 I.JDE-08 2.~JE-08 Z.47E-OI 6.JSE-DI Z.SIE-Dl ND DATA 4.HE-07 TE1)2 1.01e-os 4.47E-Oo 5.4DE-D6 6.51E-06 4.15E*D5 NO DATA 4e5DE-05 I UD z.,zE-D6 5.90E-06 J.04E*06 6.SOE-04 1.12e-06 NO DATA _Z.T6E-:D6 I Ul l.72E-05 l.73C*05 9.IJE-06 5.72E*03 Z.14E-05 NO DATA l.54E*06 I UZ e.ooE-07 l.47E-D6 6.T6E-OT 6.82E*05 2.ZSE-06 NO DATA 1.TJE*06 J lU 5.92£-06 T.JZE*06 Z.l7E-06 leJ6E*OJ le12E-D5 ND DATA Z.HE-06 I Ult 4.19E-D'F 1.71E-07 J.SIE-07 1.ne-os 1.1n-o, NO DAU 5.16E*D7

I US I.TSE-D6 , ** ~E-Oo l.49E*06 z.,,E-04 4.IJE-06 ND DATA Z.40E*06 tSlJ4 Z.34£-04 J.84C-04 l.lDE-05 NO DATA 1.1,E-04 ... ZTE-D5 z.o,e-o, CSU6 Z.JSE-05 6.46[*05 4.llE-05 ND oar* J.44E-05 5.IJE-06 z.ZTE-06

Q----------------------------------------

CS117 J.Z7E*D4 J.lJE-04 4.62E-05 ND DATA I.D2t-04 J.67E~D5 le96E*06 tSlH z.zeE-07 J.lTE-07 Z.DlE-07 ND DATA z.z,~-o, z.1tOE*D8 l.46E-D7 IUH 4.14E*07 2.z1c-10 a.ZDE-01 ~D DATA 1.,ie-10 1.,oe-10 2.1,e-os

~-----------------------------------------------~---------------

1.10,.,3

YAdlt E-11, tD'fT'O

P~E J OF J IHG~STIO~ DOSE FACTO-S FDA CHILU CMRE~ PE- Ptl IHGESTEDI lfUCL I ii[ IO~E LIVER THYROID KIDNEY LUIIIG ca-LLI

~--------------------------------------------------

P.&140 I.JlE-05 7.18f-08 4.l~E-06 HO DATA 2.JTt-08 4.J4E-OI 4.21E-05

,u1i1 2.ooe-01 1.12~-10 ** ~lE-09 1110 DAT& 9.69£-11 6.SIE-10 lel4E-07 0Al42 I.T4E-08 ,.2,e-11 4.IIE-09 ~o DATA s.o,e-11 ,.,o~-11 1.11oe-09

Ul40 1.01e-o~ ,.s3e-o, 1.1?e-o, ~o nar, NC DATA 1110 DATA *** 4£-05 Ul42 5.74E-1D l.67F.-l0 ~.ZlE-11 NO DATA Nn DATA NO DATA J.31E-05 tEl4l i.97(-08 a.,at-08 Z.94E-Ot NO DATA 1.68£-09 NO DATA Z.OE-05 CE14J 6.99[-09 J.l9E-06 5.49E-10 NO DATA l.59E-09 NO DATA !t.5S[-05 tEl44 2.oee-06 ,.s2e-01 1.11e-01 ~o DATA J.6lc-07 NO DATA l.TOE-0" PR 14 3 s.tJE-oe 1.,ac-oa l.9SE-09 ~O DATA 6.ltE-09 ND DATA 4.24£-05 PIU44 1.l9C-l0 1.9~E-ll 6.49E-l2 1110 DATA 2ellE-ll NO OAT& l.59E-09 NCl47 2.79E-08 2.26£-08 l.TSE-09 NO DAT& leZ4E-OI NO DAT& J.58E-05 W 187' 4.2,e-01 2.s1tr-01 l.l4E-OT IIIU DAT& NO DATA NO DAT& J.57E-05 1.109-64 *

JULE E-14 PAGE I DF J INGfSTIO~ DOSE F*tTORS FOR IN,ANT C*REM ,at ,ti IN,ESTEDI ll!IUCL IDE IONf L IVEII '.&C'IU't THY1'01D lllDNEY LUNG GI-LLJ

H J NO DATA 1.oee-01 1.01E-Dl 1.oae-01 ,.oae-01 J.08E-D1 J.DIE-01 L: 14 2.,1e-os s.o6E-06 s.o6C-D6 s.o,e-o, s.06~-o, s.o,,-o, s.o,~-o, NA Z4 1.01e-05 1.01E-OS 1.01e~s I.OlE-05 l.DlE-05 1.01e-o~ 1.01e-05

~-----------------------------------------------~~--------------------

P 12 l.lOE-03 a.DOE-04 ** 59E-05 NO DATA NO DATA NO DATA z.1oe-os CR 51 NO DAU NO DATA l.4lE-D8 9.20E-09 Z.01£-09 l.79E-08 4.11£-01 IIIN 54 -.o DATA l.99E-O~ ** 51E-06 ND DATA 4e41E-06 NO DATA 1.JlE-06

~-----------------------------------

MN 56 NO DATA l.llE-01 le4lf-07 ~U DATA T.OlE-07 ND DATA T.43f-05 FE 55 l.39E-D5 ** ,1E-06 Z.40E-06 .NO DATA ND DATA 4.19E-06 lel4E-06 FE H* l.OSE-05 5.JIE-0> Zal2E-05 NO DATA NO DATA le59E-05 Z.51E-05

*----------------------------------------------------

to H ND DlTA J.60E-Ov O.~SE-06 NO DATA 1110 DATA ND DATA l.'7E-06 to ,o NO DATA 1.0BE-05 2.55E-D5 NO DATA NO DUA t!n DAU Z.57E-05

~, 6) 6.J4E-04 J.92f-05 2.lOE-05 NO DATA ftD DATA ND DAU l.'95E-06

111,J u 4.TOE-06 5.JZE-01 2.4ZE-07 NO DATA ND DATA ND DATA 4.05E-05

~u 64 ~D DATA 6.09E-07 z.azE-07 NO DATA t.OJE-06 NO DATA I.ZSE-05 ZN 65 &-.94E-05 6.i.lE-05 2.cne-0~ ND DAU le06E-05 Nfl DAU 5.JlE-05

.-------------------------------------------------------------------

ZN 6Ci 9.JJE-011 lee>>IE-07 1.2se-01 1110 DATA 6.98E-OI Nn DAU 1.,n-os 81l 113 ~n DATA ND DATA J.63E-07 ND DUA ND DATA ND DATA LT E-24 BR 8't NO DATA NO DATA J.IIZE-Ol ND DUA ND DUA ND DAU LT E-14

.nth NO DATA NO DATA l e94E-D 8 NO DATA ND DATA ND DATA LT E-24 Rft 16 ND DATA l.70E-D4 ll.40E-D5 ND DAU ND DATA ND DATA 4.JSE-06 MB 18 NO DATA 4.98E-07 2. ne-01 NO DAU ND *DATA Nn DATA 4.Uf-Ol lllB 19 NO DATA Z.16E-01 le'97E-07 NO DATA ND DATA ND DATA . 9.l4E-08 Sit Ill 2.s1e-03 Ao DATA 7.20£-05 ~o DATA ND DAU ND DATA 5.16E-D5 SR 90 ,.,se-oz ND DATA 4.llE-03 ND DATA ND DATA NO DATA Z.JlE-04

~-------------------~--------

Sit 91 ~.DOE-05 NO DATA lellE-06 ND DATA ND DUA ND DATA s.9ze-05 SR 92 1.9ZE-05 NO DATA 7.l)E-Ol ND DATA ND DATA ND DATA 2.on-01, Y 90 l.69E-OI ~o DATA 2.JsE-09 ~D DATA ND DATA ND DATA 1.ZOE-04

Y ,1- ** ,oe-10 ND DATA 2.l6E-ll NO DATA NO DATA NO DATA Z.TOE-06 Y 91 Y t2 l.lJE-06 NO DATA

_______________

T.65E-09_..._ ND Dill JeOlE-01 NO DITA

_______________________

2.15£-10 NO .,_ ~----------~--~--~-~

ND DUA

______ND DUA DATA NO DATA ND DATA I.IOE-05 l.tt6E-D4

(

-

1.1C,-15

TABLE E-14, tDNT*n Pll;E z or 1 INGESTION uo~ FACTORS FD~ tN~AhT

CNAE~ PE~ PCI INGESTED!

fl!UCL ICE IO~E

LIVER T .DODY THYROID KIDNEY LUNG GI-LLI y 9) Z.43E-OI NO DATA 6.6ZE-10 NO DATA NO DATA NO DATA 1.,2F.-04 ZR 9'i Z.06E-07 s.ozE-08 J.~6E-C,I NO DATA S.41£-01 NO DATA z.soF-05 lR 97 le41E-OI 1.54E-09 l.l6E-09 ND DATA 2.56£-09 NO DATA l.*ZE-04

~B 95 4.ZOE-08 l.lJE-08 1.ooe-01 NO DATA le74t-OI NO DATA l.46E-05 MO 91 NO DATA 1.4Cc-05 6.63£-06 NO DATA 5.0IE-05 NO DATA 1.12e-os TC 99..- l.92E-09 J.96E-09

5.lOE-01 NO DATA 4.26t-OI Z.07£-09 l. lSE-06

.--------------------------------------------

rc101 2.27E-09 z.e,E-09" Z.13E-0B NO DATA J.40E-O~ l.S6E-09 4.16£-01 AU103 l.41E-06 NO DATA 4.95E-07 ~D DATA J.Olc-06 NO DATA l.lOE-05 llUl05 le36E-07 NO DATA 4.S8E-OI ~O DATA l.OOE-~6 Nn DATA 5.41E-05

~Ul06 2.4lE-05 NO DATA 1.0lE-06 NO DATA Z.95E-05 NO DATA l .13F-04

~GllO~ 9;96E-07 7.27£-07 4.llE-07 ~O DATA l.04E-06 NO DATA J. 71E-05 T£12~~ Z.l3E-05 7.79C-06 J.l>E-O* 7.14£-06 NO DATA NO DATA 1.11e-os

~--------------------------------------------------

TE127~ §.85E-05 le94F-05 7.0BE-06 l.69E-0S l.44E-04 NO DATA z.ue-os TE127 1.ooe-06 J.35E-07 2.15E-OT 8.l4E-~7 Z.44t-06 NO DATA 2.10£-05 TE129H l.OOE-04 J.43F.-05 l.54E-05 J.14E-05 z.soE-04 NO DATA 5.cne-os

~------------------------------------------------

TEl29 z.a~E-07 9.79E-08 6.63E-08 l.JIE-07 T.07E-D7 NO DITA 2.27E-05 TE lJl" l.~ZE-05 6.lZE-06 5.05E-06 l.24E-05 4.ZlE-05 NO DATA 1.01£-04 TElll l.76E-Ol 6.501:-08 4e94E-OI J.~TE-07 4.50E-07 NO DATA T. llE-06

TEl32 z.oae-oa; 1.oJe-0~ t.6LE-06 l.52F-0S 6.44E-05 NO DATA J.llE-05 I 130 6.00f-06 l.JZE-~5 5.JOE-06 l.48E-OJ i.45E-0S NO DATA z.ne-06 I 131 J.59E-D5 4.ZlE-05 l.~6E-05 l.J9E-02 4.94E-05 NO DATA l.lilE-06 1 nz l.66E-D6 J.JTE-06 leZOE-06 l.58E-04 S.76E-~6 NO DATA 2.UE-06 I U3 1.z~e-05 a.lZc-05 5.JJE-06 1.JlE-01 Z.l4E-~S NO DAT& J.OIE-06 I U4 l.69E-07 l.TIE-D6 6.33E-07 4.lSE-05 l.99E-06 ND DATA l.84E-06 I 135 J.64E-06 T.241:-06 2.64E-06 6.lt9E-04 .9.0TE-06 NO DATA Z.62E-D6 tS134 J.7TE-04 T.OJE-04 T.IOE-05 NO DATA l.llE-04 T.42E-D5 l.91E-D6 CSll6 4.59E-05 l.J5E-04 s.04E-05 NO UATA s.,,e-os 1.aoe-05 z.05E-06

CSU7 s.zzE-04 6.llE-04 4.13E-05 NO DATA l.64E-04 6e64E-05 l.91E-06 CS1J8 4.llE-07 7.82£-07 J.79E-01 NO DATA 1.,oe-01 6.o,e-01 1.zsE-0*

IAU9 lellE-07 5.14E-l0 2.55E-OI ~D DATA J.51E-10 S.54E-l0 5.51E-05

-

1.10M6

- JAdlt E-14, CONT'D PA:.E J OF J l..ciESTIO~ DOSE FACTORS FD- INFANT C~RE~ PER ,ct INGfSTEDI lltUCL I DE LIVER felODY fHYlOID KIDNEY LUllfC GI-LLI

IU4g le?lE-04 *1.llE-07 l.llE-06 -D DATA 4.06E-OI l.05E-Ol 4.ZOE-05 1Al4l 4.ZSE-07 z.tlc-10 i.J~E...08 NO DATA 1.,se-10 1.,,e-10 1.1,e-o, B&l4Z *** 4E*D7 1.s1e-10 ,.o,e-o, NO DAT& lellE*ii ~.Z6E*il 7.59E-07

LAl40 Z.llE*DI l.32E-09 z.l4E-09 NO DITA ND DATA ND DATA 9.77E**5 LU42 lelOE-09 4e04E*IO ** 61f*ll NO DATA NC DATA ND DATA 6.l6f-15 CEl4l 7.17E*OI 4.IOE*OI S.6SE-09 NO DATA l.41f-08 ND DATA Z.41E**.5

*

tElO le4IE-D8 9.IZE-06 lel1.E-09 llfD DATA z.~6f*D9 NO DATA 5.ne-os tEl44 z.tac-06 1.ZZE-06' l.67E-07 NO DATA 4.93E-07 NO DATA 1. TlF.-0'*

PRiO O.l!E*OB J.C4E*OI 4.0lE-Ot .ND DATA l.llE-08 NO DATA 4.Z9E-',~

PRl44 Z.74[-10 1.o,e-10 1.,ae-11 NO DATA J.14~*ii ~n DATA 4.9JE-06 NDl47 s.SJE-08 s.~,e-oa J.48E-09 ND DATA Z.l9E-OR NO DATA J.60E-DS W 117 9.03[*07 6o2Bt*07 Z.lTE-01 NO DATA ND DATA NO DATA 1.69E-05

NPZJ9 1.11E-08 9.93E-l0 S.6lE-lO ~o UATA a.,eE-09 ND DATA I

z.&TE-05

(>

1.109-67

......

I i TABLE E-15 RECOIWIIDED YALUES FOR OTHER PARAMETERS I.

hr1111ter Equatton(s)

S.Jllb01 Def1ntt1on Where Used Values RefertneelsJ*

f9 Fnettcm of produce ingested grown tn garden of tnterest 14 I C-13 0.76 -*

,,

Fncttcm of 1NfJ yegetables grown tn garden of tnterest 14 I C-13 1.0

, tfftctfYe surface denstty of sot1 (1ss11111es 1 15 1*.rer, Hpressed tn dry weight)

C111 plow 4, A-8, A-13, I C-5 240 kgt,l* 10

.

. Fractton of cte,osfted 1ct1Ytt1 retatned on crops, leafy

,egetables, or pasture grass 4, A-8, I A-13 C-5 O.H 1.0 ffor todtnes) 27 2, 4, 13, 0.2 for other 28-31 particulates)

--s

. s, Atten.atton factor accounttng for shteldtng provtded by restdenttal structures B, 9, 10, 11, 12, B-6, B-7, B-8, B-9, I C-2 0.7 (for **f-tndhtdual) 0.5 (for gen@rl1 26 f&

i population)

'1t

I ,.,tod of I0119-tera butldup for actt,tty fn sedi111ent or 3, 4, A-4, A-5, A-&, 1.31

105 hr sotl (110111tna11y 15 yr) *A-7, A-8, A-13, I C-5

!

te Perfod of crop, lnfy .eget1ble, or pasture grass . 4, A-8, A-13, I C-5 720 hrs (30 days, 10 I 32 exposure durtng growtng season ' for grass-cow-111tlk-1111n pathway) 1440 hrs (60 days, for crop/v~tatton-111n pathway t, . *' TrtMport tt* frm 1nt*l feed-111tlk-11111n C-10 2 days (for***-

fndtv1dua1) 4 days (for yeneral population Par1111eter values given wfthout references are based on staff judgments.

1

.1

-~

J

i ,a,-ter SJ1111,o1 .

. TABLE E-15 (Conttnued)

Equatfon(s)

Def1nttfon Where Used Y11ues RefertttCe(sl*

t,. Tf* delay tletwen hlf'ftst of ftgetatfon or crops and fngest1on t) For tngestton of forage by anfll111s 4, A-8, A-13, I C-5 Zero (for pasture grass) --

2160 hr (90 days for stor@d feed)

H) ror tngestton of crops by aan 4, A-8, A-13, I C-5 24 hr (1 day, for leefy vegetables I

... 11111111 1ndiwtdual) 1440 hr (&o days, for produce I 1111x i - --

1ndhidual) 336 hr (14 days. fOf' general populatton) t, ltnwfronlltfttll tr1Mft tf*, releese to receptor 1 I A-2 U hf' (for *xtlla

--. (add t1ae fro11 reluse to exposure point to iatntllllalS shot,n for d1str1bution) tndt,tduat) 24 hr (for general population)

- - '° 2 I A-3 24 hf' ( for ...1 -

tndfwtdual) 1&8 hr (7 days for populatton sport

~,,

'

ftsh doses) 240 hr (10 days for populatton coa-111erctal fhh doses

}

.;

'

t, Aft.-. tf* ,,.. s1aughtll"of . .t ant..1 to consu..ptfon 3 I A-7 C-12 Z1ro 20 days

,

"

I ~

. ,, .

. ; *~..

Agrtn1tun1 )"uctt,tty by unft aru (111easum tn .et wetght .

~. A-8, A-13, I C-5 0.1 lg/a'l (fOP IJNSI*

cow... t1l-1111n patt.ay) 33 l ....

,~ 2.0 t.g,,I (fOf' produce 34 or leafy ,egetabtes tngested by 11111n)

\, Rate constant for f"MOYa1 of 1ctfwfty on plant or leaf 0.0021 hr* 1 surfaces by weathering (corresponds to a 14-day half-ltfe)

P1r1111eter ,,tues gt,en without references are based on staff judginents.

a.., . ~ ... --- ..... _.,._. --*~ --~.....:.-1e, 'a% - t - - - - ~ : t t t # c*

~

e* c nicn ,-)tire.ea in St I Wi: *+_.a.;_.w,-:.,-....,__ -4.---~ . .

REFERENCES FOR APPENDIX E

1. Y. C. Ilg et 11., *Prectfctfon of the Naxt. . Dosage to Nan frOII the F111out of Nuclear It Devices, Handbook for Est1*tfng the Naxf- Intern1l Dose fraa Rldfonucltdes Released to the Biosphere,* USAEC Report UCRL-50163, P1rt IV, 1968.

2. I. H. Weiss et 11., *netafled NeasuN111ent of 1-131 1ft Afr, Vegetation 1nd Nfllt 1round Three Oper1tfng Reactor Sftes,* Envfrorwnent1l Survefll1nce Around Nuclear Install1tfons. lnter-n1tfonal Atanfc Energy Agency. JAEAjSM-180/'4, Vienna, Austrt1, Vol. I: pp. 169-190, 1974.

. 3. F. O. Hofflllln, *[nvfronmrntal Y1rt1bles Involved with the Estfmatton of the ~nt of I-131 1n Milk and the Subsequent Dose to the Thyroid,* Institute fur Relktorsicherheit, Cologne, West 6ennany, IRS-W-6, June 1973.

4. F. 0. Hoffllen, *Parameters To Be Considered When Calculating the Age-Dependent I-131 Dose to the Thyroid,* lnstitute.f°ur Reaktorsicherheit, Cologne, West 6e!"'llllny, IRS-w-s. April 1973. .

5. F. 0. Hoffman. *A Reassessment of the P!rameters Used To Predict the Environmental Transport of I-131 froin Air to Milk,* Institute fur Reaktorstcherhett, Cologne, West 6ennany. IRS-W-13, April 1975.

6. F. W. Lengeinann, *Radfofodine fn the Mfllt of Cows 1nd Goats After Oral Aanfnfstr1tfon of Radio1odate 1nd Radfofodfde,* Health Phys .* Vol. 17, pp. 565-9, 1969.

7. R. J. Garner and R. S. Russel, Radfoactfvity 1nd H11111n Diet, R. Scott Russel (ed.). Pergamon Press. Oxford, England, 1966.

8. P. M. Bryant, *o.~ for Assessments Concerning Controlled and Accidental Rele1ses of 1-131 and Cs-137 to the Stratosphere,* Health Phys .* Vol. 17, p. 51, 1969.

9. J. D. Zfmbrfclt and P. 6. Voilleque (eds.), *t967 CERT Progress Report,* USAEC Report ID0-12067, p. 36, 1968.

10. J. F. Fletcher and W. L. Dotson (compilers). *HERMES - A Digital Computer Code for Estfmatfng Regional Radiological Effects from the Nuclear Power Industry,* USAEC Report HEDL-lME-71-168, Hanford Engineering Development Laboratory, 1971.

11. J. K. Soldat, *eonverston of Survey Meter Readings to Concentratfon (~Ci/M2),* Item 04.3.4 1n *Emergency Radfologfcal Plans and Procedures,* l. R. Heid (ed.), USAEC Report HW-70935, Hanford L1bor1tories, 1962.

12. *Pennissible Dose fl'OIII External Sources of Ionizing Radfatfon,* Handbook 59, U.S. Dept. of Colllnerce. 1954.

13. R. S. Booth et 11 ** *A Systems Analysts Methodology for .Predfctfng Dose to Min from*

Radioactivity ~ntamtnated Terrestrial Environment,* Proceedings of the Third National Symposium on Radtoecology, USAEC Report CONF-710501, Oak Ridge, Tenn., pp. 877-893, 1971.

14. D.S. Altinan and P. L. Altinan (Ids.), *Netaboli111,* Federation of ~rican Societies for Experf111ental ltology, Bethesda, Md., 1968.

15. R. J. Garner, *Transfer of Radioacthe Materf1ls frca the Terrestrial Environnent to An1111ls and Man,* CRC Press, Cleveland, Ohio, 1172.

16. J. l. Soldat et 11., *Models 1nd COfflPuter Codes for Evaluating Radiation Doses,* USAEC Report BNWL-1754, P1ciffc Northwest L1bor1tories. February 1974.

17. A. L. Rogers, *Gott keeping 1n the ... itld Shttse* lntemattonal Dairy liolt Conference, London, July 1964.

11. R. &. Bond and C. P. Straub (Ids.), Handbook of Environmental Control, Vol. 111.:.,,.ter Supply-and Tre1t111ent 1

CRC Press, Cleveland, Ohio, 1975.

1.109-70

'. ...-- ...... ! . . .. . . _* . . , . . _ - - - - -

, ***-------- ..... ____ .......'!'**- -* -

19. *food Cons1111Ptfon, Prices, and Expenditures,* AER-138, U.S. Departaent of Agriculture, Washington, D.C ** Decaber 1974.

20. *Report of the Task lroup on Reference Nin.* ICRP Publfcatfon 23, PergUIOn Press, Oxford, England, 1975.

21. L. IC. Bustad and J. L. Terry, *Basic AnatCllfc1l, Dietuy, and P~siological Dita for Radiological Celculatfons,* 111-41638, &ener1l Electric Co ** Richland, Wash., February 1956.

22. N. N. N111er and D. A. Nash, *Regfonal and Other Related Aspects of Shellfish Cons1111ption -

Solie Pre11a1nary Findings of the 1969 Consmer Panel Survey,* MS Circular 361, USDC/NOAA, Seattle, Wash ** Jilr,e 1971.

23. *The Potential Radfologfcal l11c>lfcatfons of Nuclear Facfl1ttes tn the Upper Nississippi River Basin tn the Year 2000,* USAEC Report WASH-1209, Washington, D.C ** January Hl73.

24. *Draft Environmental Statement - Waste Nanagenent Operations, Hanford Reservation, Richland, Washington,* USAEC Report WASH-1528, Washington, D.C., September 1974.

25. 6. R. Hoenes and J. IC. Soldat, *Age-Specific Radi1t1on Dose c-nftaent factors for I One Year Chronic Intake,* USNRC Report NJR£6-0172, to be issued in 1977. A draft is available in the Public Doc1111ent Room.

26. z. 6. Burson and A. E. Profio, *structural Shielding from Cloud and fallout 6anlna Ray Sources for Assessing the Consequences of Reactor Accidents,* E&IG-1183-1670, Las Vegas, Nev., 1975.

27. D. A. Baker et al ** *FOOD - An Interactive Code to Celculate Internal Riadiation Doses from Contaminated Food Products,* INWL-SA-5523, February 1976.

28.

D. F. Bunch (ed.), *eontrolled Environmental Radioiodine Test, Progress Report Number Two,"

USAEC Report 100-12063, January 1968.

29. J. D. Zillbrfck and P. 6. Voflleque, *tontrolled Envfrormiental Rldio1odine Tests it the National Reactor Testi"il Station, Progress Report NLlllber four,* USAEC Report ID0-12065, December 1968.

30. C. A. Pelletier and P. 6. Voilleque, -Yhe Behavior of Cs-137 and Other Fallout Radionuclides on a Michigan Dairy Fann,* Health Pt\ys., Vol. 21, p. 777, 1971.

31. P. G. Voflleque 1nd C. A. Pelletier, *cmnparison of External lrr1di1tion and Consumption of Cow's Milk as Critical Pathways for Cs-137, tto-54 and Pr-144 Released to the*Atmosphere,*

Health Phys., Vol. 27, p. 189, 1974.

32. J. J. Koranda, *Agricultural factors Affecting the Daily Intake of fresh fallout by Dairy Cows,* USAEC Report UCRL-12479, 1965.

33. N. E. Heath et 11., Forages, the Iowa State Unfvers1ty Press, *s. Iowa, 1973.

34. *statistical Abstract of the United States.* U.S. Bureau of the Census, 93rd Edition, 1972.

1.109-71

.-,... ....... .... *-... *~~~.~"'* = ";',:4 -. ,. C>~ :t.wa +c,. >. CfW£' z. 14:,.,-w.on a;tct ~ . . . -...--..-.6 ~~*-,._ ...... - - ~ - * : .- ~

APPENDIX F IIETHOOS FOR EVALUATING THE I FUNCTION The NRC staff calculates ground-level gaiana radi1tfon doses from elevated noble gas releases usfng Equation (6) 1n Regulatory Position c.2.1 of this guide. Equation (6) 1s blsed on the

.( IIOdel presented tn Slide (Ref. 1), whfch can be characterized Is I vert1c1lly f1nfte sector-1ver1ged Gaussian plUllle IIOdel. Use of the aodel involves volume tntegr1tfon over I distributed source, resultfnsi fn certain tnt~rals thlt deftne the J function, denoted by Tr 1n Reference 1.

1. Derfv1tion of the I Function The dertv1tion of the I function presented below ts tlten directly fro111 Reference 1, which should be consulted for further details.

The sector-average 1frborne radionuclide concentration resulting fran I continuous release ts gfven by the Gaussian plUlle IIOdel 1s (see Equation 7.60 of Ref. 1):

i(R,z) * ~ Lxp [

Ir. ozuRe L (z -l1 2o 2

] + exp [ (z +l) 2oz 2

]} (F-1) 1

(

ts the effective release height, 1n aetersi

. I fs the.effective release rate, considering decay fn transit, fn Cf/seci 1s the dlMIWfnd di stance, tn meters.

I u ts the average wind speed, fn m/seci i(R,z) ts the sector-average concentration at location (R,z). 1n Ci/m 3 i z fs the vertical distance 1bove the ground plane, fn meters; e fs the sector width, tn radfanSi and ts the vertical pl1111t spread, fn meters.

Equation (F-1) aay be restated, for shnplicfty, as:

,

C i(R,z) * (F-2) r 1 I'& al.Re

' where J

J

&(z)

exp[-' (z -2 h)2 20 z

+ exp [- Cz +2h >2 2oz J (F-3) wre the tenns ire IS defined above.

1.109-72

..... * ~ * ...... - .. .........,_..-- ------------- --**--* - -

-***

f.

The 911111111 dose rate to air at* distance of r meters fn1111 point source of q curies ts expressed l)y (see £qU1t1on 7.33 of Ref. 1):

q(3.7xlo10)£(1.6x10-6)8(11,111,r)exp(-11r)

~

1 D' * (F-4) 4wr2(1Z93)(1DO) where 1(11,111 ,r) ts the buildup factor, diaenstonless; D' ts the dose rate to air, tn rad/sec; E 1s the 9111111 ray energy per distntegration, 1n MeV; q 1s the point source strength, tn curies; r is the distance, in aeters; is the attenuation coefficient for air, tn .-1,

.,a fs the energy absorption coefficient for air, in .-1 ,

100 ts the nll!lber of ergs per 9r1111-r1di 1293 fs the density of air at standard temperature and pressure, tn g/ml, 1.6 X 10- 6 ts the number of ergs per NeV; and 3.7

1010 ts the n1.111ber of disintegrations, per Ct-sec.

Equation (F-4) 111&y be simplified es follows:

k11 1 q£B(11,11 1 ,r)exp(-11r)

D' .. (F-5) 411r where k * (3.7 .k 1010lfl,6 X 10-6)

0 46 (F-6)

(1293) 00)

The next step ts to incorporate Equation (F-2) tnto Equetio~ (F-5) to arrive 1t en expression for the differen!iel dose rate dD' from the differential voliane dV containing the radionuclide concentration x(R,z). Consider I volume element of the pl1111e located z meters above the ground and at a horizontal distance L 111eters from receptor location (R, 0) (see Figure 7.20 of Ref. 1). All such volume elements located et the horizontal distance Lare included in the ring-shaped differential volume 211Ldldz. If R ts sufficiently_lerge that the concentration averaged over 111 such volume elements can be 1pproxi11111ted by x(R,z), the contribution of the ring-shaped differential volume dV to the air dose rate at location (R,O) ts given as (F-7)

I_

1.109-73

..--* ... ...,_. .. :-* ..._*.*~~---.... *.:-w*--.=+-*-*-,.***.,,..,_w..,_._..,.,..,,..,~~--....-.-,----=..-...**~-:. .. - ..... -*,**** *.. -,,-. . . . *.- *--*--

....

- -* .,;._..__.;.......,~...... _. .._........_,...;41~ .....................

,.,,

......._._.~,......,..,,,,___....

tct......

------*...

---- . ..* - - - . . . . . . ~ ~ ~ - ~ - - - . . ; . _..,.

wre q his been Nl)1actd by 'i(R,z)dY. Subst1tutfng *(L2 + 1 2) l/Z for r and 2wldldz for dY 1n Equation (F-7), and integrating, the following expression ts obtained:

D'

laaaEr/'

-J I 11.u- (L + 12 )l/Z

-.-

2 2

11(L + z )

2 1/2 LdLdz

-

2 Ir. iiltozI J

o o L

(F-8)

The 1 function, denoted by T1 tn Reference 11 t~ defined as I *

1

r,r JJ* I "*~a.(L2 + z2)1/2 G(~)exp [-11(L2 + 12)112]

Ldldz (F-9) 2 "z L. + I .

llfhich, when substituted into Equation (F-8), ytelds.

la, EQD D'

a I (F-10) r; iika The constant K, equal to 0.46, when divided by lw9 yields the factor 0.260, which is the same as the factor of 260 in Equation (6) of Regulatory Position C.2.a, after 11111ltiplytn9 by the nuinber of IIIT'ld per rad.

The buildup factor given 1n Reference 1 1s of the fonn B(u,ua*")

1 + kur (F-11) where u - u (F-12)

It.___!.

u, Substituting the above expression for the buildup factor into Equation (F-9). the I function is then given as :

I

11 + 1tI 2 (F-13) where the 11 and I 2 integrals can be written for this fora of the buildup factor as 1, *

~

1 I- (F-14)

...

~

and 12

2 1

-::rrr::-

"z f0 G(z)exp(-11z)dz (F-15) l!fhere E1 (11z) is the exponential integral defined by

-

.,-:.*

J11Z exp(-ur) d(11r) 11r

...

(F-16)

1.109-74

-=-*---- ----:-** -**----

2. Evaluation of the I Functfon In Reference 1 the 11 and 12 integrals MW! Ileen evaluated and the results presented graphically. Extraction of the data fraa these sfx-cycle 1og-1og aulticurve plots ts a fonnfdable task. A aore satisfactory approach ts to prepare a tabulation of the tntegrals as evaluated using n1.111erical *thods. These data can then N 1nterpolated tn 1aplaentfng Equation (6) of Regulatory Pos1tton C.2.a.

The NRC staff has developed a CCllll)Uter routtne that evaluates the I function as formulated 1n £qu1tfon (F-9). The I function 1s expressed tn Equation (F-9) ts independent of the buildup factor form. A ltsting of this routine ts provtded tn Ftgure F-t. Coaiunication with the routine 1s through the CCMtON statement, which also C011111Unicates with the function subprogram IULDUP, which defines the dose buildup factor l(11,11a,r) dist~ by the uur.

Also, Yankee Atomic Electric Canpan,y his supplfed I routtne written by Dr. John N. Hamewi of that compan,y (Ref. 2). This routine evaluates the 11 and 12 tntegrals as fol"'IIUlated in Equations (F-14) and (F-15). respectively. A ltsttng of the routine fs provtded in Figure F-2 (reproduced.with the pennfssion of Yankee Atomic £1ectrfc Callp1n,y). With the excepttons of changes 1n the title, the 1dd1t1on cf the tOlf<<lN statement, the CCIIIIPUtfng of I fl"CIII 11 and 12, and camnent cards as to its authorship, the routine is reproduced as written by Qr. Halllawi. The staff has compared the two routines and found their results to be tn excellent agreement. The routine supplied by the Yankee Atomic £1,ctrfc Callp1ny was found to be constderably faster than the staff's routine. . .*

1.109-75

__........ * * - * . , _ . , * -

T .-. .. , , _ _ . ~c....,.* "I' Cf . zp ,.,...,..-:... ~-.,....,.......~-~-.,-.*-~*..,..~**:*-=*******.---. ...,;. ...... . -- ...........

IUIIOUTINE DINT .

COMNONIDATIIT/INU,IIC,Hl,IIINZ,tlll,Dl,N

.C C**."Dblt INTtGIIL IUIIOUTJNt ***'* !CK!RNIN 11*21*71 C .*UIIOUTIN! IVALUAT!I TH! DOit INTEGRAL 1 1T' ** Dr,rNtD IY IIN , ** ,

C IN NET I A!*l**** THE TWO DIN!NltDNAL INTtGIATIDN 11 !VALUATED C UIING CAUIIIIN*L!l!NDI! 8UADl1Tu*r o, ORDER 11.

C C CONNDN IN,D C SNU*NAII ITT!NUITIOM cor,,1c1tNT (l/M!T!RI>

C ZK*IUILDu, 'ACTOR (NU*NUA)INUA 1, UIED C Hl*l!LEAIE ,ulNT M!ITH C *tL!AIE ,DINT HEIIHT (N!TEII)

C IIGMZ*ITANDARD DEVIATION a, ,LUNE (NETEII)

C IIAA*GANNA IAT !N!IGT (N!V)

C Dl*DDIE INTEGRAL C Na(NEAGY 81DU' IND!X t, NE!D!D C NOTE*ZIC,EIAR,& N ARE Ul!D IY IULou, C** DIM[NltDN X(Zl),wc11; DATA NN/lll,IIZ.IZIIZ7125/

DATA XI u.uueo110,, O,HTOOUHi, o.1u2HJS6o, O.H117'J7'0J, JO* H7JU417J, o,uensun, o.1oau,u1,, o.1u,02*001, Jo.n1uo,10, o.177U47i60, 0.*21H7J9U, 0.'7717237'*,

to. 7llOJ4UO,, o. 1uu,ous, o.1010.U040, 0.14J5UhU, I0.176571010,, o.*osenun, o.,3uu**o1, o.,u,01031,

o.*nonuus, DATA NI

. 10.0*07J76961, Z0.0620J9423t, o.,uu.sen, o.,nuo11u, 0.0,,,,,1,,a, o.o,o7ooa391, o.onuuus, o.on11111,zz, o.os,u4uu, -0.osn1nu1, 0 ,'987710012,

.

- ~ ..

~~ ;**:

a{. .* ... '*':~ ...

Jo.oss1,,soJ,, o.os,e,011,ij, 0.0503590355, O, Oll7b 16UB4,

,:./ - . .,.-.-r;. ;:-; :' .'ft Jrt. O~lf/llt.16U ;,* 0~'11_!1, 511501,2', o.OJUci13510, 0 0 OJCl777,Zll5,

,.* M.o*:rtt,,tzh, o.o2hh5D'7, o.OU5707Utl, o.ou*ul,o4,

- o.01ss1*11s,, o.01(a112J,s, o.001uns1,, O.OOJ15J3460/

IU"*O.

1*0.S/CIIGNZ*ltGNZ)

ZLB*Hl*11 0 d?GMZ ZUB*Hl+a.*IIGNZ 1,CZLB.LT.0 )ZLl*O.

0 YUB*U.IGNU C*O.!*ClUtl*ZLII>

l*OeS*CZUB+ZLI)

E*O.!*TUB DU 70 U*l ,NN

,.,.

l*ll*UII rx*o.

1,c*ooc1r,z;.Ea.o,,** 1.

ZZ*FeXCr>*C+G

~RGU*B*CZZ*Hl)*CZZ*HI) r,c,RGU.GT.20.,10 TD 55 EX-EXP C*ARGU)

IS ARGUaB*CZZ+Hl)*CZZ+HI) r,c,AGU.GT.zo.,,o TD SI rx*Ex+rx,c*aRGU>

11

.......

1,crx.ra.o.;,o TD 70

,.1. ,,

DD *o KKal ,NN IFCNODCICIC,1).!G.O)'**l*

PfgU1"e P-1. Staff-ltrttten Computer Ltstt,ig 1.109-76

-

i l

,_. ,. . . . . **!'Ci.- . ..:~ ........... r.~*------.. ._.:.,_ -

n*, .x rec> *E+r 11 oun+zz.zz AR8U*GMU*l9RT(D1J 1,c,i;u.cT.10.,10 To *o IXl*tX*!XP(*ARGU)*IULDUP(ARGU)*TT/D1 IUM*IUN+N(JjeN(K)e!Xt 60 CDNTJNUE

,0 CDNTJNUE DJ*IUM*C*EICA*IJIMlJ IIETURN IND

\

Figure F-1 (continued) 1.109-77

--.:

_ ""f-.-...,-.*-=-.-*"'S~*...,....rY.-~.......---~-i.;r-..--.--,*

-~. . . . ..,............~ *'. ,.*..,.._..___. ,... *-...--.*--*-:-*p** - .... - *- ..

. . . . . .- ..:. . *----* - * :.a--*--11!'**** - ~....-...._ ,._.____---* ~-,,.,.*_,._.._........---*.......-..*,na..*.-.-..,.., .:...*+..*-~--...==-e*--......**-*-*....,.... ........__ ....__,..*. -* ... _

IUIIIOUTINE DINT IEAL NU CONNON/OATAIT/NU,ZK,H,IICZ,Dl,L c**

C DOIE INTEGRAL IOUTINE WRITTEN IY C DI. JOHN N. MANANI C YANKE! ATOMIC ELECTRIC COM,ANY C *NUCLEAR IERVIC!I DIVIIION C ZO TURN,IK! ROAD C *EITIORDUGH, MAIIACHUIETTI 01111 C YAEC *r,oRT NO. 1101 C

C COMMON IN,O C NU*NAIS ATTENUATION COEF,ICl!NT (l/N[TtRI>

C ZK*IUILDU' ,ACTOR CNU*MUA)/NUA C IIGZ*ITANDAAD DEVIATION o, PLUME (NETERI)

C DI*DOIE INTEGRAL *I TOTAL C L* DETERMINES NUMBER a, INT!IVALI Ul!D IN INTEGRATION C** DIMENSION CDATA(S),ECl'),ICl*>,,c1,)

DATA .. ,,1,CDATAIS.OD+J,l.OD+4,2.0D+4,l.oo*1,1.0D+I/

DATA AO,Al,AZ,AJ,A4,A5/ *0.57721166, 0.,,,,,1,J,

o.z1,,1oss, c o.os51***a,*o.oo,1*00*, 0.001011511 DATA I0,11,12,IJ/ o.a.777J7J4J, *** J11,01*2s, 11.01,01,,130, C l,57JJ297GOl/

DA1A CO,Cl,CZ,CJ/ 1.,511,,,221, z1.o***sJ0127, ,, ** ,2,s,1116, C t,17JJZ2JG54/

DATA D,D1,DZ,DJ,DG,D~,D6,D7,Dl,Dt/

c *. JS1J. 75, ,11,., 5111111., .,211., 104'*., .1110., 101,,., .,ze., 1a11., ,,,.,

C**** CON~UT! LINITI OF INTEGRATION ZMIN AND ZNAX, AND INTERVAL WIDTH ~: ..

1,CL 0 LT 0 Z,OA,L,GT.*> L *

C

CDATACL*l>

N

L*Cfll*l) + 1 IIGZZ

IIGZ*IIGZ ALFA* H

MU*SIGZZ IETA

IIGZ* IQRTCZ.O*ALDGCC))

IF(ALFA.GT,o.o, GO TD 150 ZNIN

O.O ZNAX

AL'A

IQRT(AL,A*ALFA

IETA*l!TA)

GD To ZOO 110 ZMIN *ALFA* IETA 1,CZMIN.LT,O,O) ZNIN

0,0 ZNAX *ALFA* IETA 200 DZ* (ZMAX*ZMIN)/CN*l) c**** coM,uT! rx,oN£NTIAL INTEGRAL T!RNI !Cl) (l'!CIAL ,*ocED.

[(ll

2.ll907*ALDGCNU*DZ)

,a. !Cl>>

DO lSO l

l, N Z

ZMIN * (l*t)*DZ X

NUd IFCX.Lr.o.o; X2

x.x

,o TD 250 XJ

x.xz X4

X.XJ XS

I.XI IFCX ,LI!: .1.0) !(I)* *ALOGcx; + A0+Al*X+A2*X2+AJ*XJ*A*****AS*XI 1,cx.GT.1.0, rci> * (IO*Bl*X+l2*Xl+IJ*XJ+X4)/

e CC0+Cl*X*Cl*XZ+CJ*XJ+X4J/CX* rx,cx,;

HO CONTINU!

C**** COMPUTE INTEGRAND TlRNI ICI) &ND P(I)

DO Joo I

1, N Z

ZMIN + (l*ll*DZ Ffgure F-2. Hullwf-Wrftten Collputer Ltstfng 1.109-78

- Ex,,-,z*M>*<Z+N;1r1.l*IIIZl>i

11, r*<Z*Mi*rz*M)/(I.O*ll&Z2))

IU>

leECU JOO ,cl)* C* !XP(*NU*Z>

< C**** P[R,aRM NUNtllCAL INT[GRATION UIINI **,DINT NlNTDN*COTll PORNULA IUNI

o.O IUNP

1.0

""

N *

....... " I . l DD sso i

s,KN,MN IUN&

IUNI + Dl*l(K)*Dl*ICK4l)+DJ*l(K+lj+Dl*l(K+J)*~5*1(K+I)

C +D**tC**S)+D7*1CK+*;+Dl*ltK+7>*D**ICK+I>

IUNP

IUNP + Dl*P(Kl+Die,CK+l)+DJe,tK+z;+D1e,tK+J)+D5*PCK+I)

C +D**PCK+l)+D7ePCK+*;+D1*P(K+7)+D**PCK+I)

HO CDNTJNU!

'Dl*DZ*CIUMl+'IUNP*ZKJ/CO*l.121*17*111Z)

IIETURN

-!ND Figure F-2 (continued) 1.109-79

. . . .---------=,-.,._,. , ,. ___.. . . . . . .-*- -* ----

-*-* .--**- ,_ . ._. . . -~. . . .----~-----*-.J,~---.**---*,

. **- - - -* --* .. *-*** . *-

..

1£FOENCES FOR APPEJl>ll F 1*. 'Weteoroloa, and Atcatc Energy 1118.* D. N. S1-* (acl.J. USAEC leport TID-241090. 1968 .

. 2_': J/1*. ...;.,,,-. ilot!Dd for '-U!'I t11e - -

lntegr1ls T 111d T "'* t11e 1 YAEC-1105.

2 r,,,...

. Cloud. Sector-Anr1ge Node1.

rant" Atcatc £1actrfc Collpan, leport 1976.

,1,,

',\

I

\

I 1.109-ID

'-*- I

@@ Line 71: / Line 71: @@
 These dose limitations assure that:
 : 1)    the   concentration of radioactive      liquid   effluents   to  the unrestricted area will be limited to the concentration levels of 10CFR20, Appendix B, Table II;
-: 2)    the exposure to the maximum exposed member of the public in the unrestricted area from radioactive liquid effluents will not result in doses greater than the liquid dose limits of lOCFRSO, Appendix I;
+: 2)    the exposure to the maximum exposed member of the public in the unrestricted area from radioactive liquid effluents will not result in doses greater than the liquid dose limits of 10CFRSO, Appendix I;
 : 3)    the dose rate at and beyond the site boundary from radioactive gaseous effluents wi 11 be limited to the annual dose limits of 10CFR20;
-: 4)    the exposure to the maximum exposed member of the public in the unrestricted area from radioactive gaseous effluents will not result in doses greater than the gaseous dose limits of lOCFRSO, Appendix I; and
+: 4)    the exposure to the maximum exposed member of the public in the unrestricted area from radioactive gaseous effluents will not result in doses greater than the gaseous dose limits of 10CFRSO, Appendix I; and
 *
 : 5)    the exposure to the maximum exposed member of the public will not exceed 40CFR190 dose limits.
@@ Line 194: / Line 194: @@
 i MPCi where:
 uCi/mli   = the concentration of nuclide i in the liquid effluent discharge;
-                        =  the maximum permissible concentration in unrestricted areas of nuclide, i, expressed as uCi/ml from lOCFR Part 20, Appendix B, Table II, for *radionuclides other than noble gases and 2E-04 uCi/ml for dissolved or entrained noble gases.
+                        =  the maximum permissible concentration in unrestricted areas of nuclide, i, expressed as uCi/ml from 10CFR Part 20, Appendix B, Table II, for *radionuclides other than noble gases and 2E-04 uCi/ml for dissolved or entrained noble gases.
 : 3. EXAMPLE 3.1   Compilation of data from liquid effluent release records for a day indicated the following radionuclides and concentrations were released from the liquid radwaste effluent line.
 * Radionuclide    Concentration (uCi/ml)      MPC     uCi/ml/MPC Co-60                4.00E-06           3E-05      1.33E-01 Cs-137               3.00E-06           2E-05      1.SOE-01 Cs-134               1.00E-06           9E-06      1.llE-01 Co-58                4.50E-06           9E-05      5.00E-02 I-131                5.00E-08           3E-07      1.67E-01 I uCi/ml i *MPC 1
@@ Line 748: / Line 748: @@
        . 4Release Report submitted within 60 days after January 1 of each year include, in part, an assessment of the radiation doses to individuals due to the radioactive liquid and gaseous effluents from the station during the previous calendar year, and an assessment of the radiation doses to the maximum exposed member of the public from reactor releases and radiation.
 : 2. DOSE ASSESSMENT
-: 1. The radiation doses to individuals due to the radioactive liquid and gaseous effluents from the station during the previous calendar year shall be calculated using the methodology _presented in this Manual or in Regulatory Guide 1.109 (Revision 1), October 1977, "Calcula-tion of Annual Doses to Man from Routine Releases of Reactor Efflu-ents for the Purpose of Evaluating Compliance with lOCFR Part 50, Appendix I"    (see Appendix B). Population doses are not to be included in the dose assessment.
+: 1. The radiation doses to individuals due to the radioactive liquid and gaseous effluents from the station during the previous calendar year shall be calculated using the methodology _presented in this Manual or in Regulatory Guide 1.109 (Revision 1), October 1977, "Calcula-tion of Annual Doses to Man from Routine Releases of Reactor Efflu-ents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I"    (see Appendix B). Population doses are not to be included in the dose assessment.
 : 2. The dose to the maximum exposed member of the public due to the radioactive liquid and gaseous effluents from the station shall be incorporated with the dose assessment performed above. If the dose to the maximum exposed member of the public exceeds twice the limits
 * of Specifications 3.11.A.2, 3.11.B.2 or 3.11.B.3, the dose assessment shall include the contribution from direct radiation.

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