Text

Amend 6 to Offsite Dose Calculation Manual
	ML17285A262
Person / Time
Site:	Columbia
Issue date:	11/30/1988
From:	; WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	;
Shared Package
ML17285A259	List: GO2-89-021, Forwards Semiannual Effluent Rept,Jul-Dec 1988, Corrected Table 3-5 to Jul-Dec 1987 Rept & Amend 6 to Offsite Dose Calculation Manual; ML17285A260; ML17285A261; ML17285A262;
References
	PROC-881130-01, NUDOCS 8902230548
	Download: ML17285A262 (98)
	v • d • e

CONTROLLED COP YNovember 1988 WNP-2 OFFSITE DOSE CALCULATION MANUAL (ODCN)

The following instructional information and checklist is furnished to help you insert Amendment No.

6 into the Washington Public Power Supply System Plant No.

2 ODCN.

Discard the old sheets and insert the new sheets as listed below.

Keep these instructions to serve as a record of changes.'f you have questions concerning insertion of this amendment, or if you are missing any pages, please contact Bernice Kasko/Linda Wilson (509) 377-2369.

DISCARD OLD PAGE List of Effective Pages (LEP LEP-5)

INSERT'EW PAGE List of Effective Pages (LEP-1 LEP-5) 1V 2

6 through 8

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CONTROLLED COPY WNP-2 OFFSITE DOSE CALCULATION MANUAL (ODCM)

List of Effective Pages AMENDMENT NO.

6, November 1988

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CONTROLLED COPY AMENDMENT NO.

6 November 1988 Tab 1 e Title

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Input Parameters Needed for Calculating Dose to the Maximum Individual from WNP-2 Gaseous Effluent"......

71 3-10

.3-11 3-12 3-13 3-14 3-15 3-16 Reactor Building Stack X/Q and D/Q Values..........

-73 Turbine Building X/Q and D/Q Values 77 Radwaste Building X/Q and D/Q Values 81 Characteristics of WNP-2 Gaseous Effluent Release Points 85 References for Values Listed in Table 3-9 86 Design Base Percent Noble Gas (30-Minute Decay) 87 Annual Doses at Special Locations Within WNP-2 Site Boundary.

Source:

WNP-2 Gaseous Effluent 88 3-17 Annual Air Dose at Special Locations Within WNP-2 Site Boundary.....................

89 Section 5.0 5-1 5-2 Radiological Environmental Monitoring Program Plan

~

e 98 WNP-2 REHP Locations 102 5-3 Environmental Radiological Monitoring Program Annual Summary 108 Reporting Levels for Nonroutine Operating Reports 109 LIST OF FIGURES

~Fi ure 2-1 2-2 Title Simplified Block Diagram of Liquid Waste System Simplified Block Diagram of Solid Radwaste System Pa<ac 32a 32b 3-1 Site Boundary for Radioactive Gaseous and Liquid Effluents 90 3-2 3-3 5-1 Simplified Block Diagram of Gaseous Waste System Simplified Block Diagram of Off-Gas Treatment System Radiological Environmental Monitoring Sample Locations Inside of 10-Mile Radius 90a 90b 106 5-2 Radi ologi ca 1 Environmental Monitoring Samp1 e Locations Outside of 10-Mile Radius iv 107

CGNTBOLLEQ COPY

CGNTIRGLLEG CQPY 2.0 LI UID EFFLUENT DOSE CALCULATION AHENDHENT NO.

6 November 1988 2.1 Introduction Liquid radwaste released from NNP-2 will meet 10 CFR 20 limits at the point of discharge to the Columbia River.

This design objective will be kept at all times.

Actual discharges of liquid radwaste effluents will only occur on a

Batch Basis, and the average concentration at the point of discharge will be only a small percentage of the allowed limits.

A simplified block diagram of the liquid waste management system and effluent pathways is contained in Figure 2-1.

Solid radioactive wastes are disposed of by way of an approved disposal site.

A simplified block diagram of the solid radwaste system is described in Figure 2-2.

The cumulative quarterly dose contributions due to radioactive liquid efflu-ents released to the unrestricted areas will be determined once every 31 days using the LADTAP II computer code.

The maximum exposed individual is assumed to be an adult whose.exposure pathways include potable water and fish consump-tion.

The choice of an adult as the maximum exposed individual is based on the highest fish and water consumption rates shown by that age group and the fact that most of the dose from the liquid effluent comes from these two pathways.

The dose contributions will be calculated for all radionuclides identified in the released effluent.

The calculations are based on guidelines provided by Nureg-0133 and the LADTAP II computer code.

The methods for calculating the doses are discussed in Section 2.4 of this manual.

2.2 Radwaste Li uid Effluent Radiation Honitorin S stem This monitoring subsystem measures the radioactivity in the liquid effluent prior to its entering the cooling tower blowdown line.

CGMTRGLLEG CQPV 0

p

CGNTIRGLLED COPY AMENONENT NO.

6 November 1988 unrestricted area would be calculated according to Equation (3) and Equa-tion (4).

To show compliance with 10 CFR 20, the two equations must again hold.

2.4 10 CFR 50 A

endix I Release Rate Limits Technical Specification 4.11.1.2 requires that the cumulative dose contribu-tions be determined in accordance with the OOCN at least once per 31 days.

Technical Specification 3.11.1.2 specifies that the dose to a member of the public from radioactive material in liquid effluents released to the unre-stricted area shall be limited to:

and

< 1.5 mrem/Calendar quarter - Total Body

< 5.0 mrem/Calendar l}uarter Any Organ.

The cumulative dose for the calendar year shall be limited to:

and

< 3 mrem Total Body

< 10 mrem Any Organ.

The dose contribution will be calculated for all radionuclides identified in the liquid effluent released to the unrestricted

area, using the following equation:

m D< =g(A,.

get Ci F )

i g,=l (5) where:

The cumulative dose commitment to the total body or organ,~,

from liquid effluents for the total time period g in mrem.

4tR L=l

CGNTRGLLEG COPY

CONTROLILEG COP'%I" AMENDMENT NO.

6 November 1988 The length of the ath time period over which C.

and 45 Fg are averaged for all liquid releases, in hours.

The number of releases for the time period under consideration.

The average concentration of radionuclide, i, in undiluted liquid e'ffluent during time periodAta from any liquid release, in pCi/ml.

The site-related ingestion dose commitment factor to the total body or any organ

~ for each identified principle gamma and beta emitter listed in Table 2-2, in mrem/hr per >Ci/ml.

The near field average dilution factor for C-1X during any liquid waste release.

Defined as the ratio of the maximum undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times 500.

Li uid Radioactive Waste Flow fw Discharge Structure Exit Flow x 500 ft x 500

CGNTROLLEQ CQPY

CGNYIRGLLEG CQPY AMENDMENT NO.

6 November 1988 The term A, the ingestion dose factors for the total body and critical

organs, are tabulated in Table 2-2." It embodies the dose factor, fish bioac-cumulation factor, pathway usage factor, and the dilution factor for the plant diffuser pipe to the Richland potable water intake.

The following equation was used to calculate the ingestion dose factors:

where:

U Ai> = Ko(D

+ UP BPi)DP w

(7)

The composite dose parameter For total body or criti-cal organ of an adult for nuclide i (in mrem/hr per p,Ci/ml).

K A conversion factor:

1.14E+05

= (10 pCi/pCi) x (10 ml/liter) : 8760 hr/yr.

6 3

Uw 730 liter/yr which is the annual water consumption by the maximum adult (Table E-4 of Regulatory Guide 1.109, Revision 1).

Bioaccumulation factor for radionuclide i in fish (pCi/Kg per pci/liter) (Table A-1 of Regulatory Guide 1.109, Revision 1

and NUREG/CR-4013).

Dp

~

Adult ingestion dose conversion factor for nuclide i

- Total body or critical organ (mrem/pCi)

(Table E-11 of Regulatory Guide 1.109, Revision 1

and NUREG/CR-4013).

'w Dilution factor from near Field area to the Richland potable water intake - 100.

Adult fish consumption, 21 kg/yr (Table E-5 of Regulatory Guide 1.109, Revision 1).

CGNTROLLEG CQPV V

IV

CGNTIRGLLED CGPY ANENDNENT NO.

6 November 1988 d

~

The deposition rate of nuclide i, in pCi/m per hour.

The flow rate of the liquid effluent, in ft /sec.

The fraction of the year crops are irrigated, dimensionless.

iA The stable. element transfer coefficient that relates the daily intake rate by an animal to the concen-tration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal pro-duct) per pCi/day.

The mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food), dimensionless.

The effective "surface density" for soil, in kg (dry soil)/m (Table E-15, Regulatory Guide 1.109, 2

Revision 1).

QAw The consumption rate of contaminated water by an animal, in liters/day.

QF The consumption rate of contaminated feed or forage by an animal, in kg/day (wet weight).

Q; The release rate of nuclide i, in Ci/yr.

The fraction of deposited activity retained on, crops, dimensionless (Table E-15, Regulatory Guide l.'109, Revision 1).

15

CGNYRGLLEG CQPY

CONTIROLLED Cop'r ANENONENT NO.

6 November 1988 The shoreline width factor, dimensionless (Table A-2, Regulatory Guide 1.109, Revision 1).

Y The agricultural productivity (yield), in kg (wet weight)

/m (Table E-15, Regulatory Guide 1.109, Revision 1).

XE; The effective removal rate constant for radionuclide

-1 i from crops, in hr, where XE.

= x. + x El 1

W'

. is the radioactive decay constant, and A,

is 1

w the removal rate constant for physical loss by weathering (Regulatory Guide 1.109, Revision 1, Table 8-15).

The radioactive decay constant of nuclide i, in hr 1100 The factor to convert from (Ci/yr)/(ft /sec) to pCi/1 iter.

110,000 The factor to convert From (Ci/yr)/(ft /sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.

These equations yield the dose rates to various organs of individuals from the exposure pathways mentioned above.

2.7.2 Plant Parameters WNP-2 is a river shoreline site with a variable efFluent discharge'low rate 0 to 7500 gpm.

The population center nearest WNP-2 is the city of Richland, where drinking water withdrawal takes place.

The applicable dilution factor is 50,000, using average river flow.

The time required for released liquids 17

CGNTRGLLEG COPY (5

to

CONTIRGLLED CGPY AMENDMENT NO.

6 November 1988 leased liquids to reach Richland, approximately 12 miles downstream, is esti-mated at 4.0 hours0 days 0 hours 0 weeks 0 months .

Richland is the "realistic case" location, and doses cal-culated for the Richland location are typically applicable to the population as a whole.

Individual and population doses based on Richland parameters are calculated for all exposure pathways.

Only the population downstream of the WNP-2 site is affected by the liquid effluents released.

There is no significant commercial fish harvest in the 50-mile radius region around MNP-2.

Sportfish harvest is estimated at 14,000 kg/year.

for irrigated foods exposure pathways, it can be assumed that production with-in the 50-mile radius region around MNP-2 is sufficient to satisfy consumption requirements.

Other relevant parameters relating to the irrigated foods pathways are d fined as follows:

~ood Tvae d

(liter/m /mo)

(kg/m )

(Days)

Vegetation Leafy Vegetation Feed for Milk Cows Feed for Beef Cattle 150 200 200 160 5.0 1.5 1.3 2.0 70 70 30 130 Source terms are measured based on sampled effluent.

Table 2-3 summarizes the LADTAP II input parameters.

Documentation and/or calculations of these parameters are discussed in detail in R ~ P.I. 2.3, and Rad.

Prog.

ca 1 cul at ion Log 88-3.

18

CONTROLLED CQPV

CGNTFtGLLEG "CQP"f

Table 2-1 FISH BIOACCUHULATION FACTORS (BF.)

AND ADULT INGESTION DOSE CONVERSION FACTORS (DFi)

AMENDMENT NO.

6 November 1988 Nuclide Fish Bioaccumulation Factor (BF,.)

(pCi/kg per pCi/1 iter)

Total Body

.Dose Conversion Factor (DF,.)

Bone Thyroid Liver

. (mRem per pCi Ingested)

GI Tract Na-24 P-32 Cr-51 Mn-54 Nn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-65 Cu-64 Zn-65 Zn-69m As-76 Br-82 Br-83 Br-84 Rb-89 Sr-89 Sr-90 9.0E-01 1.0E+02 1.0E+05 2.0E+02 4.0E+02 4.0E+02 1.0E+02 1.0E+02 5.0E+01 5.0E+01 1.0E>02 5.0E+01 2.0E+03 2.0E+03 1.0E+02 4.2E+02 4.2E+02 4.2E+02 2.0E+03 3.0E+01 3.0E+Ol 6.0E-OB 1.7E-06 (3) 1.7E-06 2.7E-09 8.7E-07 2.0E-OB 4.4E-07 (3)

(3)

(3) 2.8E-06 3.9E-06 4.3E-06 1.7E-06 4 'E-06 3.1E-OB 3.9E-OB 7.0E-06 (3)

(3) 5.3E-07 (3) 4.8E-06 3.7E-OB 1.7E-07 4.8E-06 2.3E-06 4.0E-OB 5.2E-OB 2.8E-OB B.BE-06 (3)

(3)

(3) 3.1E-04 1.8E-04 8.7E-03 7.5E-06

. 1.9E-04 (3) 1.6E-09 (3)

(3)

(3) 1.2E-05 2.2E-05 (3) 4.6E-06 6.7E-07 1.4E-05 1.2E-07 3.7E-06 1.9E-06 1.1E-06 1.0E-05 3.4E-05 7.5E-07 1.5E-05 2.1E-06 4.0E-05

6. 9E-08

1. IE-06 8.3E-OB 7.1E-06 1.5E-05 9.7E-06 4.1E-07 2.5E-05 (3)

(3)

(3) 4.0E-OB (3)

(3) 4.4E-05 2.6E-06 5.8E-OB 4.1E-13 2.3E-21 4.9E-05 2.2E-04 6.0E-OB 6.0E-OB 6.0E-OB 1.7E-06 1.7E-06 1.7E-06 26

CONTROLLED COPY

CGNTBGLLEG COPY Table 2-1 (contd.)

AMENDMfNT NO.

6 November 1988 Nuclide Fish Bioaccumulation Factor (BF.)

(pCi/kg per pCi/1 iter)

Total Body Dose Conversion Factor (DF,.)

Bone Thyroid Liver (mRem per pCi Ingested)

GI Tract Sr-91 Sr-92 Y-90 Y-91m Y-91

'-92 Y-93 Zr-95 Nb-95 lr-97 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 RU-105 Rh-105 Ru-106 Ag-110m Sb-124 Sb-125 Sb-126 Sb-127 Te-127 Te-129m Te-129 3.0E+01 3.0E+01 2.5E+Ol 2.5E+01 2.5E+Ol

2. 56.01 2.5E+01 3.3E+00 3.0f>04 3.3E+00 3.0E+04 1.Of+01 1.5E+Ol 1.5E+01 1.0E+01

1. Of+01 1.0E+Ol 1.0E+Ol 2.3E+00 1.0E+00 1.Of+00 1.0E+00 1.Of+00, 4.0E+02 4.0E+02 4.0E+02 2.3E-07 5.7E-06 9.3E-OB 2.2E-06 2.6E-10 9.7E-09 3.5E-12 9.1E-ll 3.8E-09 1.4E-07 2.5E-11 8.5E-10 7.4E-1'1 2.7E-09 6.6E-09 3.1E-08 1.9E-09 6.2E-09 1.6E-10 1.7E-09 4.8E-12 5'.2E-11 8.2E-07 8.9E-09 3.6E-09 (3) 2.5E-10 2.5E-10 8.0E-OB 1.9E-07 6.1E-09 1.5E-08 5.8E-OB 1.2E-07 3.5E-07 2.8E-06 8.8E-OB 1.6E-07 1.1E-06 2.8E-06 (3)

(3)

(3) 6.8E-09 (3)

(3)

(3) 9.8E-09 2.7E-05 4.3E-05 1.0E-04 2.7E-10 7,8E-05 1.5E-05 8.5E-05 3.1E-05 3.5E-09 2.1E-05 3.4E-10 1.1E-04 1.3E-11 4.9E.-OB 4.3E-06 1.0E-05 7.0E-10 4.1E-07 3.7E-10 (3)

(3) 8.9E-OB 1.1E-21 2.2E-05 9.4E-06 1.4E-05 1.8E-04 6.0E-05 (3) 1.5E-07 5.3E-OB B.OE-05 1.8E-06 7.7E-09 1.2E-05 4.0E-06 4.3E-06 5'.BE-05 3.1E-OB 2.4E-08 1.2E-OB 2.4E-OB 4.3E-07 1.8E-06 1.8E-09 2.0E-OB 2.'OE-05 4.2E-07 1.2E-06 7.0E.09 2.3E-OB 9.4E-05 9.9E-08 2.6E-07 3.1E-09 5.7E-09 5.9E-05 2.4E-08 1.1E-07 8.2E-OB 4.0E-OB 8.7E-06 27

CONTROLLED COPY

AHENOHENT NO.

6 November 1988 CONTIROLLED COP'II'able 2-2 INGESTION OOSE FACTORS (A..)

FOR TOTAL BOOY AND CRITICAL ORGAN (in mrem/hr per Ci/ml)

Liquid Effluent Total Gi Nuclide

~Bod Bone

~Th roid Liver Tract H-3 1.8E-01 1.8E-01 1.8E-01 1,8E-01 Na-24 4.1E+02 4.1E+02 4.1E+02 4.1E+02 4.1E+02 P-32 1.BE+06 4.6E+07 2.9E+06 5.3E>06 Cr-51 Hn-54 Hn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-65 Cu-64 Zn-65 1.3E+00 8.3E+02 1.9E+01 1.1E+02 6.7E+02 9.4E+02 1.0E+03 2,1E+02 5.7E+02 7.5E+00 1.3E+02 4.7E+00 3.4E+04 2.3E+04 Zn-69m 1.BE+02 8.1E+02 7.7E-01 3.2E~02 4.4E+03 1.3E+04 1.6E+02 3.6E+03 4.6E+02 2.6E+02 2.4E+03 8.2E+03 9.0E+01 1.BE+03 2.5E+02 4.BE+03 1.7E+01 4.1E+02 1.0E+Ol 8.6E+02 7.2E+04 4.7E+04 2.0E+03 1.2E+05 As-76 Br-82 Br-83 Br-84 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 1.2E+03 2.3E+03 4.0E+01 5.2E+01 1.3E+02 6.4E+02 2.3E+04 1.3E+04 6.3E+05 1.7E+01 4.1E+02 6.BE+00 1.6E+02 1.1E+04 2.6E+03 5.BE+01 4.1E-04 1.9E+02 1.1E-11 3.6E+03 1.6E+04 2.0E+03 3elE~03 29

CONTROLLED COPY

CONTROLLED COPY Table 2-2 (contd.)

AMENDMENT NO.

6 November 1988 Total Nuclide

~Bod Bone

~Th roid Liver G1 Tract Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Nb-95 Zr-97 Nb-97 Mo-99 1.6E-02 5.9E-01 2.1E-04 5.5E-03 2.3E-01 8.5E+00 1.5E-03 5.2E-02 4.5E-03 1.6E-01 5.3E-02 2.5E-01 1.4E+02 4.5E+02 1.3E-03 1.4E-02 3.5E-01 3.7E+00 2.0E+01 Tc-99m 3.3E-Ol 9.2E-03 Tc-101 1.3E-01 9.2E-03 Ru-103 2.0E+00 4.7E+00 Ru-105 1.5E-01 3.7E-01 Rh-105 1.4E+00 3.0E+00 Ru-106 8.7E+00 6.9E+Ol 6.1E+03 1.6E-02 4.7E+03 9.1E+02 5.2E+03 7.9E-02 2.5E+02 2.5E+02 1.5E+06 2.7E-03 8.BE+02 9.3E-01 3.5E+03 1.1E+02 2.5E+02 2.6E-02 1.5E+01 1.4E-02 4.0E-14 5.5E+02 2.3E+02 2.2E+00 3.5E+02 4.5E+03 Ag-110m Sb-124 5.6E-01 1.0E-OO 9.5E-01 3.BE+02 3.6E+00 9.0E+00 2.2E-02 1.7E-01 2.6E+02 Sb-125 1.4E+00 5.BE+00 5.8E-03 6.5E-02 6.5E+Ol Sb-126

).4E+00 3.9f+00 2.3E-02 7.4E-02 3.0E+02 Sb-127 3.2E-Ol 8.4E-Ol 1.0E-02 1.8E-02 1.9fw02 Te-127 2.3E+Ol 1.1E+02 7.9E+01 3.BE+01 8.3E+03 Te-129m 1.7E+03 1.2E+04 3.BE+03 4.1E+03 5.6E+04 Te-129 7.4E+00 3.0E+Ol 2.3E+01 1.2E+01 2.3E+Ol Te-131m 6.BE+02 1.6E+03 1.3E+03 8.2E+02 8.1E+04 Te-131 Te-132 I-131

'I-1 32 I-133 I-134 I-135 7.0E+00 7.4E+00 7.0E+02 2.0E+01 2.BE+01 5.1E+Ol 1.3E+04 9.2E+Ol

'.7E+00 8.1E+01 3.7E+00 1.6E+01 4,0E+00 1.6E+Ol 1.BE+02 1.1E+01 9.2E-03 2.BE+03 4.4E+01 4.BE+01 5.9E+00 1.9E+Ol 1.5E+01 7.9E+00 2.7E+00 1.4E+03 2.4E+03 1.7E+03 1.5E+03 7.4E-04 1.3E+02 1.5E+02 7.4E+04 2.2E+02 5.9E+Ol 30

CONTROLLEG COPY

CONTRQLLED COPY Table 2-2 (contd.)

AMENDMENT NO.

6 November 1988 Total Gi Nuclide

~Bod Bone

~Th roid Liver Tract Ba-139 2.9E-02 1.0E-OO Ba-140 1.4E+01 2.1E+02 La-140 2.0E-02 1.5E-01 La-141 La-142 Ce-141 Ce-143 9.7E-04 1.9E-02 9.1E-04 7.9E-03 2.3E-03 3.0E-02 4.5E-04 5.5E-03 Ce-144 8.4E-02 1.6E+00 Pr-143 Nd-147 2.8E-02 5.6E-01 2.7E-02 3.8E-01 Hf-179m 4.2E+01 Hf-181 3.BE+01 Cs-134 5.BE+05 3.0E+05 Cs-136 9.1E+04 3.1E+04 Cs-137 3.4E+05 3.BE+05 Cs-138 2.6E+02 2.6E+02 7.2E+05 1.3E+04 1.3E+05 1.4E+04 5.3E+05 1.0E+04 5.3E+02 2.3E-03 7.2E-04 1.BE+00 2.7E-Ol 4.4E+02 7.9E-02 5.6E+03 6.0E-03 7.3E+02 3.5E-03 2.6E+Ol 2.0E-02 7.7Ew01 3.9E+00 1.5E+02 6.5E-Ol 5.5E+02 2.3E-01 2.4E+03 4.4E-01 2.1E>03 3.6E+02 3.6E+02 W-185 W-187 Np-239 4.0E+01 1.2E+03 8.6E+Ol 2.9E+02 1.6E-03 3.0E-02 4.0E+02 4.6E+04 2.5E+02 8.1E+04 3.0E-03 6.0E+02

- No Ingestion Dose Factor (DF;) is listed in NUREG/CR-4013.

(Total body dose factor value will be used as an approximation.)

31

CGNTRGLLEG CGPY

CGNTBGLLEG COPY AMENDMENT NO.

6 November 1988 TABLE 2-3 INPUT PARAMETERS USED TO CALCULATE MAXIMUM INDIVIDUAL DOSE FROM LI UID EFFLUENTS River Dilution:

River Transit Time:

Usage Factors:

Boatin and A uatic Food River Dilution:

Transit Time:

Usage Factors:

(Aquatic Food)

(Boating) 50,000 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Adult = 730 1/yr Child = 510 1/yr 2,000 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Adult =

21 kg/yr Child = 6.9 kg/yr Adult = 100 hr/yr Child =

85 hr/yr Teenager

= 510 1/yr Infant

= 330 1/yr Teenager

= 16 kg/yr Infant

= 0 Teenager

= 100 hr/yr Infant

= 0 Recreation River Dilution:

Shoreline Width Factor:

Usage Factors:

20,000 0.2 Shoreline Activities:

Swimming:

Adult

= 90 hr/yr Teenager

= 500 hr/yr Child

= 105 hr/yr Infant

= 0 Adult

= 18 hr/yr Teenager

= 100 hr/yr Child

= 21 hr/yr Irri ated Foodstuffs River Dilution:

River Transit Time:

Food Delivery Time:

Usage Factors:

Adult Teenager Child Monthly Irrigation Rate:

Annual Yield:

Annual Growing Period:

Annual 50-Mile Production:

50,000 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 14 days 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 20 days 520 kg/yr 310 1/yr 110 kg/yr 630 kg/yr 400 1/yr 65 kg/yr 520 kg/yr 330 1/yr 41 kg/yr 180 1/m~

200 1/m2 160 1/m2 5.0 kg/m 1.3 1/m2 2.0 kg/m2 70 days 30 days 130 days 3.5E+09 kg 2.BE+08 L 2.3E+07 kg Leafy Ve etabl es 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 64 kg/yr 42 kg/yr 26 kg/yr 200 1/m2 1.5 kg/m2 70 days 1.9E+06 kg 32

CGNTROLLEQ COPY

t CONTIROLLED COPY AMENDMENT NO.

6 November 1988 SUMPS RADWASTE BLDG TURBINE BLDG DRYWELL VASTE SURGE AND COLLECTOR TANKS VASTE SAMPLE TANKS (TVQ)

COOLING TQVER BLOVDOVN LINE MISC WASTE REACTOR BLDG FLOOR DRAIN

~

COLLECTOR TANK FLOOR DRAIN SAMPLE TANK DETERGENT DRAIN TANKS DISTILLATE TANKS (TWO)

FILTERS 8

DENINERAL-,

IZERS

<SOLID WASTE)

CHEMICAL WASTE TANKS SHOP DECON CHEM PUMPS DECON DRAIN REACTOR BLDG TURBINE BLDG PLANT USE CONDENSATE STORAGE TANKS (TVQ)

COLUMBIA RIVER SIMPLIFIED BLOCK DIAGRAM OF LIQUID VASTE SYSTEM FIGURE 2-1 32a

CGNTROLLEQ CQPY d

AMENDMENT NO.

6 November 1988 CGNTFtGLLE0 CGPV DEMINERALIZERS Condensate RHCU EDR/FDR Radwaste Bead Phase Separator Dewatering Liners Disposal Site Dry Active Haste Compactor.

Disposal Site SIMPLIFIED BLOCK DIAGRAM OF SOLID RADHASTE SYSTEM Figure 2-2 32b

CONTROLLED CGPY

'p

AMENDMENT NO.

6 November 1988 All other locations listQQgggQ}$3+1QQpQQLPI~~2 activities and are controlled by the Supply System.

Figure 3-2 provides a simplified block diagram of the gaseous radwaste system for the reactor, turbine and radwaste buildings.

figure 3-3 provides a simplified block diagram for the Off-Gas Treatment System.

Air doses and doses to individuals at these locations were calculated based on the NRC GALE code design base mixture, location specific estimated occupancy, and X/Qs from XOQOOQ.

(Note:

Oesert Sigmas.were used in calculating X/Q and D/Q values, and are listed in Table 3-10 to 3-12).

These doses are listed in Tables 3-16 and 3-17 along with the doses to the maximum exposed individual.

The most likel ex osed member of the ublic is considered to be residing in Taylor Flats (4.2 miles ESE of WNP-2).

This is the closest residential area with the high-est X/Q and 0/Q values.

3.2 Gaseous Effluent Radiation Monitorin S stem 3.2.1 Main Plant Release Point The Main Plant Release is instrument monitored for gaseous radioactivity prior to discharge to the environment via the main plant vent release point.

Particulates and iodine activity are accumulated in filters which will be changed and analyzed as per Technical Specification 4.11.2.1.2 and Table 4.11.2.

The effluent is supplied from:

i the gland seal exhauster, mechanical vacuum pumps, treated off gas, standby gas treatment, and exhaust air from the entire reactor building's ventilation.

Two 100-percent capacity vanaxial fans supply 98,000 CFM ventilation air.

One is normally operating, the other is in standby.

The radiation monitors are located on'he ventilation exhaust plenum.

Effluent monitoring consists of a low range beta scintillator, an intermediate range beta scintillator and two ion chamber LOCA monitors.

The beta scintillators are mounted in thick lead shielded chambers.

The low range beta scintillator has an approximate response of 80 cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc to Xe-133 and a meter range of 10-10 cpm.

The intermediate 34

CONTROLLED COPY If,

AMENDMENT NO.

6 November 1988 range has a response frdgclgT+~L'PgoeQOPF/nival ant, and reads in panel meter units (PMU) with a meter range of 10

-10 PMU.

The readouts and recorder are located in the main control room panel BD-RAD-24.

Power is provided from 125 VDC divisional buses.

This monitor has no control Function but annunciates in the main control room.

The alarm will e

initiate proper action as defined in the WNP-2 Plant Procedures.

3.2.2 Radwaste Buildin Ventilation Exhaust Monitor The radwaste building ventilation exhaust monitoring system monitors the radio-activity in the exhaust air prior to discharge.

Radioactivity can originate from:

radwaste tank vents, laboratory hoods, and various cubicles housing liquid process treatment equipment and systems.

The radwaste building exhaust system has three 50 percent capacity exhaust filter units of 42,000 cfm capacity.

Each exhaust unit has a medium-efficiency prefilter, a high efficiency particulate air filter (HEPA) and two centrifugal fans.

Total exhaust flow will vary as the combined exhaust unit maintains a

radwaste building differential pressure of -0.25 inches H20 to the environment.

Particulate and iodine air sample filters are changed weekly for laboratory analysis.

After the particulate and iodine filters, the air sample streams are combined in a manifold prior to being monitored by a beta scintillator.

The beta scintillators, on the 487'evel are mounted in lead shielded chambers.

The low range beta scintillator has an approximate response of 80 cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc to Xe-133 and a meter range of 10-10 cpm.

The intermediate range has a response from 10

-10 pCi/cc 6

-2 3

Xe -133 equivalent, and reads in panel meter units (PMU) with a meter range of 10

-10 PMU.

The readouts and recorder are located in the main control 0

5 room panel BO-RAO-24.

Power is provided from 125 VDC divisional buses.

This monitor has no control functions but annunciates in the main control room.

The alarm will initiate proper action as defined in the WNP-2 plant procedures.

35

CONTRGLLEG CGPY 0

t

AMENDMENT NO.

6 November 1988 3.2.3 Turbine Buildin IIVKb Exhale o

QP This monitoring system detects fission and the activation products from the turbine building air which may be present due to leaks from the turbine and other primary components in the building.

The turbine building main exhaust system consists of four roof-mounted centri-fugal fans which draw air from a central exhaust plenum.

Three fans operate continuously, with one in,.standby to provide a flow of 260,000 cfm.

A representative sample is extracted from the exhaust vent and passed through a particulate and charcoal Filter.

The air sample then passes to a beta scintillator.

The beta scinti llators are mounted in lead shielded chambers.

The low range beta scintillator has an approximate response of 80 cpm/pCi/cc to Kr-85, and 50 cpm/pCi/cc to Xe-133 and a meter range of 10-10 cpm.

The intermediate range has a response from 10 10 qCi/cc Xe -133 equivalent, and reads

-2 3

in panel meter units (PHU) with a meter range of 10 - 10 PHU.

The monitors are on the 525'evel of the radwaste building and the readouts and the recorder are located in the main control room panel BD-RAD-24.

Power is provided from the 125 VDC divisional buses.

This monitor has no control functions but annunciates in the main control room.

The alarm will initiate proper action as defined in the INP-2 plant procedures.

3.3 10 CFR 20 Release Rate Limits Limits for release of airborne effluents to the unrestricted area are stated in Technical Specification 3.11.2.1.

The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

'a)

"The dose rate limit for noble gases shall be <500 mrem/yr to the total body and

<3000 mrem/yr to the skin.

(b)

"The dose rate limit for all radioiodines and For all radio-active materials in particulate form and radionuclides other than noble gases with halF-lives greater than eight days shall be <1500 mrem/yr to any organ."

36

CONTRGLLEQ CQPY

3.3.1 Noble Gases CONTROLLED COPY AMENDMENT NO.

6 November 1988 In order to comply with Technical Specification 3.11.2.1, the Following equa-tions must hold:

Nhole body:

g Ki [(X/Q)

Q.

+ (X/Q)

Q.

)

500 mrem/yr

('I) 1 m

im g

ig Skin p [(Li + 1.1N,.)((X/Q)

Q.

+ (X/Q)

I), )] S 3000mrem/yr (2) 3.3.2 Radioiodines and Particulates Part "b" of Technical Specification 3.11.2.1 requires that the release rate limit for all radioiodines and radioactive materials in particulate Form and radionuclides other than noble gases must meet the following relationship:

Any organ:

QP.

W

(}.

+ M g.

1 <1500 mrem/yr i

H im g

igJ (3)

The terms used in equations 1 through 3 are defined as follows:

K.

=

The total body dose Factor due to gamma emissions for each identified noble gas radionuclide i (mrem/yr per t Ci/m ).

L

=

The skin dose factor due to beta emissions for each iden-tified noble gas radionuclide i (mrem/yr per vCi/m ).

CONTROLLEG COPY

AHENOMENT NO.

6 November 1988 qim CTQNv~egoLrglpD Qogllg gas radionuclides in gaseous ef fluents, i, for short-term releases (equal to or less than 500 hr/yr) from the main plant release point, in pCi.

Releases shall be cumulative over the calendar quarter or year, as appropriate.

lg The average release of noble gas radionuclides in gaseous effluents, i, for short-term releases (equal to or less than 500 hr/yr) from Radwaste and Turbine Building, in pCi.

Releases shall be cumulative over the calendar quarter or year, as appropriate.

oim The average release of noble gas radionuclides in gaseous

releases, i, for long-term releases (greater than 500 hr/yr) from the main plant release

point, in pCi.

Release shall be cumulative over the I

calendar quarter or year, as appropriate.

0;g The average release of noble gas radionuclides in gaseous effluents, i, for long-term releases'greater than 500 hr/yr) from Radwaste and Turbine Building, in pCi.

Releases shall be cumulative over the calendar quarter or year, as appropriate.

-8 3.17 x 10

=

The inverse of the number of seconds in a year.

3.4.2 Radioiodines Tritium and Particulates Technical S ecification

~3. 11. 2. 3 The following equation calculates the dose to an individual from radioiodines, tritium radioactive material in particulate form, and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to the unrestricted areas:

CONTROLLEG COPY

AHENDMENT NO.

6 November 1988 3.4.2.1 Rose Parameter r Ki A iRe i RQQpV The R. values used in equations 12 and 13 of this section are calculated separately for each of the following potential exposure pathways:

~

Inhalation Ground plane contamination Grass-cow/goat-milk pathway Grass-cow-meat pathway Vegetation pathway Monthly dose assessments for WNP-2 gaseous effluent will be done for all age groups.

Calculation of R. (Inhalation Pathway Factor) 1 R. (Inhalation)

=

K (SR)

(DFA.)

(mrem/yr per qCi/m )

I I

3 (14) where:

RI 1

The inhalation pathway factor (mrem/yr per pCi/m ).

3 A constant of unit conversion, 10 pCi/pCi.

(BR)

The breathing rate of the receptor of age group (a) in meter /yr.

( Infant = 1400, child = 3,700, teen

= 8,000, 3

adult

= 8,000.

From P.32 NUREG-0133).

47

CONTROLLED COPY

(OFA.)

AMENDMENT NO.

6 November 1988 The QQÃeTVprl-4IIaQtQPPosY factor for receptor of age group (a) for the ith radionuclide (mrem/pCi).

The total body is considered as an organ in the selection of (OFA.)a.

(OFAi)a values are listed in Tables E-7 through E-10 of Regulatory Guide 1.109 manual, Revision 1

and NUREG/CR-4013.

Values of R. are listed in 1

Table 3-,5.

Calculation of R.

(Ground Plane Pathway Factor)

G R.(Ground Plane)

=

K K

(SF)(DFG-) (1-e

)/A (m

x mrem/yr per vCi/sec)

(15)

G A 8 where:

R.

=

Ground plane pathway factor (m

x mrem/yr per uCi/sec).

G K

=

A conversion constant of (10 pCi/uCi).

A K

=

A conversion constant (8760 hr/yr).

8

'I The decay constant for the ith radionuclide (sec

).

t

=

Exposure time, 6.31 x 10 sec (20 years).

DFG.

The ground plane dose conversion factor for the ith radio-

nuclide, as listed in Table E-6 of Regulatory Guide 1.109, Revision 1

and NUREG/CR-4013 (mrem/hr per pCi/m ).

SF

=

Shielding Factor (dimensionless) 0.7 if building is

present, as suggested in Table E-15 of Regulatory Guide 1.109, Revision 1.

CGNTIRGLLEG COPY

AMENDMENT NO.

6 November 1988 (DFLi)

The+gbggggn'f~iQQP+factor for the ith radio-nuclide for the receptor in age group (a), in mrem/pCi (Tables E-11 to E-14 of Regulatory Guide 1.109, Revision 1

and NUREG/CR-4013).

The decay constant for the ith radionuclide, in sec The decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10 sec (cor-responding to a 14-day half;life).

The transport time from pasture to animal, to milk, to

receptor, in sec.

The transport time from pasture, to harvest, to animal, to milk, to receptor, in sec.

Fraction of the year that the cow/goat is on pasture (dimensionless).

's Fraction of the cow/goat feed that is pasture grass while the cow is on pasture (dimensionless).

NOTE:

For radioiodines, multiply R. value by 0.5 to obtain the amount of elemental iodihe present.

The input parameters used for calculating R. are listed in Table 3-6 and the 1

R,. values are tabulated in Table 3-7.

M For Tritium:

In calculating RT, pertaining to tritium in milk, the airborne concentration C

rather than the deposition will be used:

RT (Grass-Cow/Goat-Milk Factor)

=

C K

K F

Q U

(DFL.)

0.75(0.5/H)

(mrem/y"r per >Ci/m )

(17) 50

CONTROLLEI3 COPY

AHENOHENT NO.

6 November 1988 tf

=

The tranQQgC)"rg~~aQugp'gceptor, in sec.

h The transport time from crop field to receptor, in sec.

NOTE:

For radioiodines, multiply R. value by 0.5 to obtain the amount of elemental iodine present.

The input parameters needed for solving equation 18 are listed in Table 3-7.

For Tritium:

In calculating the RT for tritium in meat, the airborne concentration is used rather than the deposition rate.

The following equation is used to calculate the RT values for tritium:

R (Grass-Cow-Heat Pathway)

=

H T

K K F g U

(OFL.)

0.75(0.5/H)

(mrem/yr per pCi/m )

A C

3 (19)

Where the terms are as defined in equations 16-18, R

values for tritium pertaining to the infant age group is zero since there is no meat consumption by this age group.

Calculation of R, (Vegetation Pathway Factor)

V R. (Vegetation Pathway Factor)

=

V 1

Y 1

w ULf i

L USf ih aL ag (20)

(m x mrem/yr per pCi/sec) 2 52

COÃTRGLCEQ CGPY

AMENDMENT NO.

6 November 1988 where:

CGNTIRGLLED CGPY I

K

=

A constant of unit conversion, 10 pCi/vCi.

U

=

The consumption rate of fresh leafy vegetation by the receptor L

a in age group (a), in kg/yr.

U

=

The consumption rate of stored vegetation by the receptor in S

a age group (a), in kg/yr.

fL

=

The fraction of the annual intake of fresh leafy vegetation grown local ly.

f

=

The fraction of the annual intake of stored vegetation grown g

locally.

tL

=

The average time between harvest of leafy vegetation and its consumption, in seconds.

th

=

The average time between harvest of stored vegetation and its consumption, in seconds.

Yv The vegetation area density, in kg/m NOTE:

For radioiodines, multiply R. value by 0.5 to obtain the amount of elemental iodine present.

All other items are as defined in equations 16-18.

For Tritium:

In calculating the RT for tritium, the concentration of tritium in vegetation is based on airborne concentration rather than the deposition rate.

The fol-lowing equation is used to calculate R

for tritium:

53

CONTROLLED COPY

AMENDMENT NO.

6 November 1988 mrem/yr to the whole boQQi%YBOLkgQ>CIQRVn.

The initial setpoints determination is calculated using a conservative radionuclide mix obtained from the WNP-2 GALE code.

Once the plant is operating and sufficient measur-able process fission gases are in the effluent, then the actual radionuclide mix will be used to calculate the alarm-setpoint.

3.6.2 Set oint Determination for all Gaseous Release Paths The setpoints for gaseous effluent are based on instantaneous noble gas dose rates.

Sampling and analysis of radioiodines and radionuclides in particulate form will be performed in accordance with technical specifications to ensure compliance with 10 CFR 20 and 10 CFR 50 Appendix I limits.

The three release points will be partitioned such that their sum does not exceed 100 percent of the limit.

Originally, the setpoints will be set at 40 percent for the reactor building, 40 percent for the turbine building and 20 percent for the radwaste building.

These percentages could vary at the plant discretion, should the operational conditions warrant such change.

However, the combined releases due to variations in the setpoints will not result in doses which exceed the limit stated in technical specifica-tion.

Both skin dose and whole body setpoints will be calculated and the lower limit will be used.

3.6.2.1 Set pints Calculations Based on Whole Bod Dose Limits The fraction

( < i) of the total gaseous radioactivity in ea'ch gaseous effluent release path (j) for each noble gas radionuclide i will be determined by using the following equation:

H ~

~

(dimensionless) iJ NT-(22) where:

H..

=

The measured individual concentration of radionuclide i in the 1j gaseous ef fluent release path j ( pCi/cc).

55

CGNTRGLLEG CGPY

AMENDMENT NO.

6 November 1988 MT

=

The measurQQg8f g~gtpQoQpp noble gases identified in the gaseous effluent release path j (qCi/cc).

Based on Technical Specification 3.11.2.1, the maximum acceptable release rate of all noble gases in the gaseous effluent 'release path j is calculated by using the following equation:

F 500 gT~ =

m x/q. g (K,.)( ~,

)

i =

1 (p Ci/sec)

(23) where:

9T>

=

The maximum acceptable release rate (qCi/sec) of all noble gases in the gaseous effluent release path j (qCi/cc).

Fj

=

Fraction of total dose allocated to release path j.

500

=

Nhole body dose rate limit of 500 mrem/yr as specified in Tech-nical Specification 3.11.2.1a.

X/g.

Maximum normalized diffusion coefficient of effluent release path j at the site boundary (sec/m ).

Turbine 3

Building and Radwaste Building values are based on average annual ground level values.

Main plant vent release values are for mixed mode and may be either short term or average annual value dependent upon type of release.

K.

=

The total whole body dose factor due to gamma emission from noble gas nuclide i (mrem/yr per wCi/m ) (as listed=- in Table 8-1 of Regulatory Guide 1.109, Revision 1).

56

CONTROLLED COPY

AMENDMENT NO.

6 November 1988 As definedQQf(0pg0L2+ED QGpy m

=

Total number of radionuclides in the gaseous effluent.

j

=

Different release pathways.

The total maximum acceptable concentration (CT ) of noble gas radionuclides TJ in the gaseous effluent release path j (uCi/cc) will be calculated by using the following equation:

OT

~

CT.

= ~R (pCi/cc)

(24) where:

CT.

=

The total allowed concentration of all noble gas radionuclides TJ in the gaseous effluent release path j (pCi/cc).

0T

=

The maximum acceptable release rate (pCi/sec) of all noble gases J

in the gaseous effluent release path j.

R

=

The ef fluent release rate (cc/sec) at the point of release.

J To determine the maximum acceptable concentration (C..) of noble gas radio-ij nuclide i in the gaseous effluent for each individual noble gas in the gaseous effluent (uCi/cc), the following equation will be used:

C

~ - =;. CT.

(q Ci/cc)

(25) 57

CONTROLLED COPY

AMENDMENT NO.

6 November 1988 CGNTHGLLE0 CGPY Table 3-2 DISTANCES (MILES) TO CONTROLLING LOCATIONS AS MEASURED FROM CENTER OF NNP-2 CONTAINMENT BUILDING*

Location Distance Sector (miles)

Comments Si.te Boundary Taylor Flats Ringold 1.2 4.2 4.0 SE Air dose measurement.

ESE The nearest significant residence in the southern direction with vegetable

gardens, milk, and meat production.

ENE The nearest significant residence in the northern direction with vegetable

gardens, milk, and meat production.

"Selection of location sector is based on the highest annual average X/Q values.

'1

COÃTRGLEEG CGPY 0

Table 3-3 LNP-2 ANNUAL AVERAGE DISPERSION (X/Q)

"e Location Site Boundary SE 1.2 Containment Bldg.

Turbine Bldg.

Radwaste Bldg.

Sector Distance Point of Release (miles)

X/Q No Decay No De letion (sec/m

)

1.8E-06 1.1E-05 1.1E-05 X/Q 2.3 Days Decay No De letion (sec/m

)

1.8E-06 1.1E-05 1.1E-05 X/Q 8.0 Days Decay

~0e leted (sec/m

)

1.6E-06 1.0E-05 1.0E-05 (m

)

1.0E-08 A

8. 3E-08

-OK 8.3E-OB Taylor Flats ESE Ringold 4.2 4.0 Containment Bldg.

Turbine Bldg.

Radwaste Bldg.

Containment Bldg.

Turbine Bldg.

Radwaste Bldg.

4.1E-07 8.9E-07 8.9E-07 2.5E-07 3.9E-07 3.9E-07 4.1E-07 8.7E-07 8.7E-07 2.5E-07 3.8E-07 3.8E-07 3.8E-07 6.8E-07 6.8E-07 1.9E-07 3.0E-07 8.2E-10 IO I

7. 2E-10 U

7.2E-10 O.

3.3E-10 3.3E-10 3.0E-07 3.3E-10 BPA"Ashe Substation 0.5 Containment Bldg.

Turbine Bldg.

Radwaste Bldg.

6.4E-06 3.0E-05 3.0E-05 6.4E-06 2.9E-05 2.9E-05 5.8E-06 3.7E-OB 2.7E-05 7.8E-OB 2.7E-05 7.8E-OB 0( Pl ED O CI lD Pl s

CO O Q)

~

CGRTRGLL,Et3 CQPY

AMENDMENT NO.

6 November 1988 Table DOSE RATE PARAMETERS IMPLEMENTATION OF 10 CFR 20 AIRBORNE RELEASES Nuclide H-3 Na-24 Cr-51 Hn-54 Hn-56 Fe-55 Fe-59 Co-58 Co-60 Cu-64 Zn-65 Zn-69m As-76 Br-82 Sr-89 Sr-90 Zr-95 Nb-95 Zr-97 Nb-97 Ho-99 Tc-99m Ru-106 Ag-110m Sb-124 Sb-125 Sb-126 Sb-127 1.8E-09 1.3E-05 2.9E-07 2.6E-OB 7.5E-05 8.5E-09 1.8E-07 1.1E-07 4.2E-09 1.5E-05 3.3E-OB 1.4E-05 7.3E-06 5.5E-06 1.5E-07 7.9E-10 1.2E-07 2.3E-07 1.1E-05 1.6E-04 2.9E-06 3.2E-05 2.2E-OB 3.2E-OB

'1.3E-07 7.9E-09 6.5E-07 2.1E-06 Child Dose DFA.

m~rem/ Ci 1.7E-07 4.4E-06 4.6E-06 4.3E-04 3.3E-05 3.0E-05 3.4E-04 3.0E-04 1.9E-03 9 'E-06 2.7E-04 2.7E-05 1.9E-05 5.7E-06 5.8E-04 1.0E-02 6.0E-04 1.7E-04 9.5E-05 7.5E-06 3.7E-05 1.3E-06 3.9E-03 1.5E-03 8.8E-04 6.3E-04 2.9E-04 6.2E-05 63 Factor*

DFGi mrem/hr

~Ci /m 0.0 2.9E-OB 2.6E-10 6.8E-09 1.3E-OB 0.0 9.4E-09 8.2E-09 2.0E-OB 1.7E-09 4.6E-09 3.4E-09 1.7E-07 2.2E-OB 6.5E-13 2.6E-12*"

5.8E-09 6.0E-09 6.4E-09 5.4E-09 2.2E-09 1.1E-09 1.8E-09 2.1E-08 1.5E-OB 3.5E-09 1.0E-OB 6.6E-09 PI 1

Inhalation

~mrem/ r

~Ci /m3 6.3E+02 1.6E+04 1.7E+04 1.6E+06 1.2E+05 1.1E+05 1.3E+06 1.1E+06 7.0E+06 3.7E+04 1.0E+06 1.0E+05 7.0E+04 2.1E+04 2.2E+06 3.7E+07 2.2E+06 6.3E+05 3.5E+05 2.BE+04 1.4E+05 4.BE+03 1.4E+07 5:6E+06 3.3E+06 2.3E+06 1.1E+06 2.3E+05

CGNTRGLLEG CQPY

AMENDMENT NO.

6 November 1988 CONTIROLLED COPY Table 3-4 DOSE RATE PARAMETERS IMPLEMENTATION OF 10 CFR 20 AIRBORNE RELEASES Nuclide Te-127 Te-131m I-131 I-132 I-133 I-135 Cs-134 Cs-137 Cs-138 Ba-140 La-140 Ce-141 Ce-144 Nd-147 Hf-1 79m Hf-181 W-185 sec

'2.1E-05 6.4E-06 1.0E-06 8.4E-05 9.2E-06 2.9E-05 1.1E-08 7.3E-10 3.6E-04 6.3E-07 4.8E-06 2.4E-07 2.8E-OB 7.2E-07 3.7E-02 1.8E-07 1.1E-07 DFA.

m~rem/ Ci 1.5E-05 8.3E-05 4.4E-03 5.2E-05 1.0E-03 2.1E-04 2.7E-04 2.5E-04 2.3E-07 4.7E-04 6.1E-05 1.5E-04 3.2E-03 8.9E-05 2.0E-05 6.0E-05 1.9E-04 DFG.

mrem/hr

~Ci /m 1.1E-ll 9.9E-09 3.4E-09 2.0E-OB 4.5E-09 1.4E-OB 1.4E-OB 4.9E-09 2.4E-OB 2.4E-09 1.7E-08 6.2E-10 3.7E-10 1.2E-09 NO DATA 1.2E-08 0.0 Child Dose Factor" PI 1

Inhalation

~mrem/ r

~Ci /m3 5.6E+04 3.1E+05 1.6E+07

'1.9E+05 3.7E+06 7.BE+05 1.0E+06 9.3E+05 8.5E+02 1.7E+06 2.3E+05 5.6E+05 1.2E+07 3.3E+05 7.4E+04 2.2E+05 7.0E+05

Maximum Organ

- No data is listed for Sr-90 in Table E-6 of Regulatory Guide 1.109, Revi-sion l.

Y-90 valves were used for dose conversion factor Sr-90.

63a

CQNTlRGLLEG,CGPY 0'

CONTIROLLED

'COP'It'ABLE 3-5 a AflEHDNENT NO.

6 November 1988 RADIO-NUCLIDE DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS AIRBORNE RfLEASES AGE GROUP:

ADULT ORGAN OF REFEREN(f:

MAXIMUMORGAN (I), INDIVIDUALPATHWAY DOSE PARAMETfRS FOR RADIONUCLIDES OTHER THAN NOBLE GASES INHALATION GROUND PLANE COW-MILK GOAT-MILK ANIMAL-MfAT VEGETABLE S (MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (MZ.MREM/YR (M2.MREM/YR PER UCI/M3)

PER UCI/SEC)

H 3

NA 24 CR 51 MN 54 MN 56 FE 55 FE 59 CO 58 CO 60 CU 64 ZN 65 ZN 69M AS 76 BR 82 SR 89 SR 90 ZR 95 NB 95 ZR 97 NB 97 MO 99 TC 99M RU106 AG11OM SB124 58125 SB126 SB127 TE127 TE131M I 131 I 132 I 133 I 135 CS134 CS136 CS137 CS138 BA140 LA140 CE141 CE144 ND147 HF179M HF181 W 185 7.2Et02 1.0Et04 1.4E+04 1.4Et06 2.0Et04 7.2Et04 1.0E+06 9.3Et05 6.0Et06 4.9Et04 8.6Et05 1.4EtOS 1.5E+05 1.4E+04 1.4Et06 2.9Et07 1.BE+06 5.1Et05 5.2E+05 2.4Et03 2.5EtOS 4.2Et03 9.4Et06 4.6Et06 2.5Et06 1.7Et06 7.7Et05 3,0Et05 5.7E+04 5.6Et05 1.2E+07 1.1Et05 2.2E+06 4.5Et05 8.5Et05.

1.5Et05 6.2ft05 6.2E+02 1.3E+06 4.6E+05 3.6E+05 7.8Et06 2.2E+05 1.6Et05 4.BE+05 4.5Et05 O.OE-01 1.2Et07 4.7E+06 1.4E+09 9.0E+05 O.OE-01 2.7E+08 3.8Et08 2.3E+10 6.1Et05 7.5E+08 1.3Et06 3.8Et06 2.1E+07 2.2E+04 6.7Et06 2.5E+08 1.4E+08 3.0E+06 1.BE+05 4.OE+06 1.BEt05 4.2E+08 3.5E+09 6.0E+08 2.4Et09 8.4E+07 1.7Et07 3.0E+03 B.OE+06 8.6E+06 6.2Et05

1. 2f+06 1.3f+06 6.9Et09 1.5E+08 1.3E+10 3.6E+05 2.1E+07 1.9Et07 1.4E+07 7.0E+07 B.SE+06 O.OE-01 2.1Et08 1.8Et04 5.8Et02 1.2E+06 3.3Et06 1.4Et07 6.2E-02 1.4Et07 1.1Et08 4.7Et07 1.7Et08 1.0Et06 2.7E+09 1.3Et07 2.1Et07 1.9Et07 6.9Et08 3.4E+10 4.6Et05 1.3Et08 1 ~ 4E+04 1.6E-09 2.9E+07 2.8Et03 7.3Et05 1.2E+10 3.5Et08 1.3Et08 2.2Et08 5.2Et07 2.6E+04 8.9Et06 3.4E+10 3.9E+00 2.5Et08 5.5Et05 7.4E+09 5.0Et08 6.0Et09 1.0E-23 2.7Et07 8.4Et04 5.8Et06 6.4Et07 2.5E+05 O.OE-01 S.SEt05 2.4ft07 1.2E+03 2.2E+05 5.9E+05 2.1E+06 1.1E-02 2.2Et06 2.DE+07 7.6Et06 2.5Et07 1.7Et05 4.0E+08 2.4E+06 3.BE+06 3.4Et06 2.0E+09 8.3E+10 7.6E+04 2.2E+07 2.4E+03 2.9E-10 5.2E+06 5.0Et02 1.1E+05 1.BE+09 5.8Et07 1.8Et07 4.DE+07 9.3Et06 4.7E+03 1.6E+06 6.1E+10 6.9E+00 4.5E+08 9.BE+05 2.7Et10 2.2Et09 2.1E+10 4.6E-23 4.BE+06 1.5E+04 1.0Et06 9.6E+06 4.6E+04 O.OE-01 9.3E+04 3.9f+06 2.4E+02 7.2E-04 8.2f+05 1.5E+07 O.OE-01 1.6f+08 9.BE+08 1.8Et08 B.OE+08 1.1E-05 7.0Et08 1.2E-03 2.9Etol 7.0ft02 1.4E+08 8.9ft09 9.2Et08 3.6E+09 6.4E-01 O.OE-01 1.2E+05 3.6E-18 1.0E+11'.4Et09 2.7E+08 1.2E+08 7.6E+07 1.9E+06 8.4E-09 1.1Et04 1.2E+09 O.OE-01 2.4Etol

l. 7E-15 8.6E+08 2.3E+07 7.1E+08

'.OE-OO 2.BE+07 7.0Et02 1.7E+07 2.6E+08 1.9E+07 O.OE-01 1.2E+10 1.9Et07 1.6Et03 1.1Et05 2.3Et07 9.4Et08 2.0E+02 1.9E+08 1.5E+09 B.OEt08 2.9E+09 3.3Et05 1.3Et09 1.4Et06 B.OE t06 7.7E+05 1.5E+10

7. 4f+ll 1.6Et09 8.4E+08 B.BE+06 8.1E-04 9.3Et06 2.2Et03 1.2f+10 4.4Et09 4.OEt09 1.4E+09 1.6Et09 1.2E+08 2.0E+05 2.0Et07 4.4E+10 l.lft03 1.1Et08 1.4Et06 1.Of+10 4.6Et08 8.6E+09 3.0E-11 7.3E+08 3.3ft07 9.3Et08 1.1E+10 5.1E+08 O.OE-01 1.BE+09 8.4ft08 64

CGNTIRGLLEG CGPY P

..a oi I

t-f 1

CONTQQPPPP COPY N

NO.

6 November 1988 DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS AIRBORNE RELEASES AGE GROUP:

TEEN ORGAN OF REFERENT:

MAXIMUM ORGAN R(I), INDIVIDUALPATHWAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES RADIO-INHALATION GROUND PLANE COW-MILK GOAT-MILK ANIMAL-MEAT.

VEGETABLES NUCLIDE (MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR PER UCI/M3)

PER UCI/SEC)

H 3

NA 24 CR 51 MN 54 MN 56 FE 55 FE 59 CO 58 CO 60 CU 64 ZN 65 ZN 69M AS 76 BR 82 SR 89 SR 90 ZR 95 NB 95 ZR 97 NB 97 MO 99 TC 99M RU106 AG110M SB124 SB125 SB126 SB127 TE127 TE1 31M I 131, I 132 I 133 I 135 CS134 CS136 CS137 CS138 BA140 LA140 CE141 CE144 ND147 HF1 79M HF181 W 185 7.3Et02 1.4Et04 2.1Et04 2.0Et06 5.7Et04 1.2E+05 1.SEt06 1.3E+06 8.7Et06 6.1Et04 1.2Et06 1.7E+05 1.5Et05 1.8ft04 2.4Et06 3.3Et07 2.7Et06 7.5Et05 6.3Et05 3.9Et03 2.7Et05 6.1Et03 1.6Et07 6.8Et06 3.8Et06 2.7Et06 1.2Et06 3.2Et05 8.1Et04 6.2E+05 1.5Et07 1.5Et05 2.9Et06 6.2E+05 1.1Et06 1.9E+05 S.SEt05 8.6E+02 2.0Et06 4.9E+05 6.1Et05 1.3Et07 3.7Et05 7.1Et04 4.8EtOS 7.7Et05 O.OE-01 1.2Et07 4.7Et06 1.4E+09 9.0E+05 O.OE-01 2.7Et08 3.BE+08 2.3E+10 6.1E t05 7.5Et08 1 ~ 3E+06 3.8Et06 2.1E+07 2.2Et04 6.7E+06 2.5Et08 1.4E+08 3.0Et06 1.BE+05 4.0E+06 1.8E+05 4.2Et08 3.5f+09 6.0Et08 2.4E+09 8.4E+07 1.7E+07 3.0Et03 8 'Et06 8.6E+06 6.2ft05 1.2E+06 1.3Et06 6.9Et09 1.5E+08 1.3Etl0 3.6Et05 2.1Et07 1.9Et07 1.4Et07 7.0Et07 8.5ft06 O.OE-01 2.1Et08 1.8Et04 7.5Et02 2.1E+06 3.9Et06 1.6Et07 2.3E-01 2 'E+07 1.3Et08 5.3Et07 2.1Et08 1.6ft06 4.5Et09 2.1E+07 2.7E+07 2.8ft07 1.3Et09 5.1E+10 5.8Et05 1.6Et08 2.1Et04 1.9E-08 5.1Et07 5.3Et03 9.9ft05 1.4E+10 4.5Et08 1.6f+08 2.8Et08 6.9Et07 4.8Et04 1.3Et07 5.4E+10 6.4ft00 4.2Et08 9.3E+05 1.3E+10 8.4E+08 1.1E+10 1.8E-23 3.6E+07 1.1E+05 7.9E+06 8.8f+07 3.5E+05 O.OE-01 7.1E+05 3.3E+07 1.5E+03 3.9E+05 6.Sf+05 2.3E+06 4.1E-02 3.8E+06 2.5E+07 8.7E+06 3.Of+07 2.7E+05 6.7Et08 3.8E+06 4.9E+06 5.1E+06 3.7E+09 1.3Etll 9.5ft04 2.7Et07 3.8Et03 3.3E-09 9.2Et06 9.5Et02 1.5Et05 2.1Et09 7.3Et07 2.3Et07 5.1Et07 1.2Et07 8.6Et03 2.3E+06 9.7Et10

'1.2Et01 7.5ft08 1.7Et06 4.6E+10 3.8E+09 3.8Etlo 8.1E-23 6.4ft06 2.1E+04 1.4Et06 1.3ft07 6.2Et04 0.0f-01 1.2Et05 5.4E+06 1.5Et02 5.8E-04 4.4Et05 7.BE+06 O.OE-OO 1.3E+08 5.5Et08 9.4E+07 4.3Et08 8.0E-06 5.4Et08 9.1E-04 1.7Et01 4.9ft02 1.2Et08 6.2Et09 5.3Et08 2.0Et09 4.6E-01 O.OE-01 9.4Et04 3.2E-18 6.2Et10 7.6E+08 1.6Et08 6.8E+07 4.5Et07 1.2Et06 7.0E-09 7.4E+03 9.0Et08 0.0f-00 1.8Et01 1,3E-15 6.8Et08 1.8Et07 5.7Et08 O.OE-OO 1.8Et07 4.4Et02 1.0Et07 1.6Et08 1.2Et07 O.OE-01 7.0Et09 1.2E+07 1.9Et03 1.0Et05 2.5E+07 9.6E+08 3.7Et02 3.0E+08 1.7Et09 8.3ft08 3.1Et09 2.7E+05 2.0E+09 1.1E+06 5.3E+06 6.1E+05 2.4Et10 1.0E+12 1.BE+09 9.1E+08 7.0E+06 4 'E-03 1.1E+07 2.1E+03 1.5E+10 4.6E+09

'4.6E+09 1 ~ 6E+09 1.BE+09 1.2E+08 1.8E+05 1.Sf+07 6.1E+10 9.3E+02 9.6Et07 1.2E+06 1.6EtiO 7.0Et08

1. 4E+10 2.7E-11 S.SE+08 2.4E+07 1.1Et09 1.3Et10 6.1E+08 0.0f-01 2.1Et09 1.0Et09 65

CGNTRGLLEG CGPY

CONTROLLED COPY TABLE 3-5 c At4ENDMENT t<0.

6 November 1988 DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS AIRBORNE RELEASES AGE GROUP:

CHILD ORGAN OF

REFERENCE:

MAXIMUMORGAN R(I), INDIVIDUALPATHVAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLf GASES RADIO-INHALATION GROUND PLANE COW-MILK GOAT-MILK ANIMAL-MEAT VEGETABLES NUCLIDf (MREM/YR (M2.MREM/YR (M2;MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.NREM/YR PER UCI/M3)

PER UCI/SEC)

H 3

NA 24 CR 51 MN 54 MN 56 FE 55 FE 59 CO 58 CO 60 CU 64

- ZN 65 ZN 69M AS 76 BR 82 SR 89 SR 90 ZR 95 NB 95 ZR 97 NB 97 MO 99 TC 99M RU106 AG110M SB124 SB125 SB126 SB127 TE127 Tf131M I 131 I 132 I 133 I 135 CS134 CS136 CS137 CS138 BA140 LA140 CE141 CE144 ND147 HF179M HF181 W 185 6.4E+02 1.6Et04 1.7E+04 1.6E+06 1.2E+OS 1.1E+05 1.3E+06 1.1Et06 7.1E+06 3.7E+04 1.0E+06 1.0E+05 7.0E+04 2 'E+04 2.2E+06 3.BE+07 2.2E+06 6.1E+05 3.5Et05 2.8Et04 1.3E+05 4.8Et03 1.4Et07 5.5Et06 3.2Et06 2.3E+06 1.1E+06 2.3Et05 5.Sf+04 3.1ft05 1.6E+07 1.9Et05 3.BE+06 7.9Et05 1.0E+06 1.7E+05 9.1E+05 8.4E+02 1.7Et06

'.3Et05 5.4f+05 1.2Et07 3.3E+OS 7.4Et04 2.2Et05 6.9E+05 O.OE-01 1.2Et07 4.7E+06 1.4E+09 9.0E+05 O.OE-01 2.7E+08 3.BE+08 2.3E+10 6.1Et05 7.5E+08 1.3E+06 3.BE+06 2.1E+07 2.2E+04 6.7Et06 2.5E+08 1.4E+08 3.0E+06 1.Sf+05 4.0E+06 1.BE+05 4.2Et08

'3.5E+09 6.0Et08 2.4E+09 8.4E+07 1.7E+07 3.0Et03 S.OEt06 8.BE+06 6.2ft05 1.2E+06 1.3Et06 6.9E+09 1.5Et08 1.3E+10 3.6E+05 2.1E+07 1.9E+07 1.4Et07 7.0Et07 S.SEt06 O.OE-01 2.1E+08 1.8Et04 1.2Et03 4.5E+06 2.5Et06 1.1Et07 B.BE-.01 6.1E+07 9.5E+07 3.4E+07 1.4E+08 1.7Et06 6.BE+09 2.2Et07 2.2E+07 5.BE+07 3.1E+09 1.0E+11 4.2E+05 1.1Et08 2.1E+04 4.2E-07 8.7E+07 7.4Et03 7.9E+05, 9.4E+09 3.3E+08 1.2E+08 2.2E+08 5.5Et07 5.9E+04 1.1E+07 1.1Etli 1.5Et01 9.9Et08 2.1Et06 2.0E+10 1.3Et09 1.9Et10 3.2E-23 5.6Et07 9.5Et04 6.3Et06 7.0E+07 2.8Et05 O.OE-01 5.9Et05 2.7E+07 2.4Et03 B.QEt05 4.4Et05 1.7Et06 1.6E-01 9.6Et06 1.7Et07 5.6E+06 2.0E+07 2.9E+05 1.0E+09 4.0Et06 4.0Et06 1.0E+07 9.2E+09 2.BE+11 7.0E+04 1.BE+07 3.BE+03 7.6E-OS 1.6E+07 1.3E+03 1.2E+05 1.4E+09 5.4E+07 1.7E+07 4.0E+07 1.0Et07 1.1E+04 2.1E+06 1.9E+11 2.7E+Oi 1.8Et09 3.8Et06 7.5E+10 6.0Et09 6.BE+10 1.4E-22 1.Of+07 1.7Et04 1.1E+06 1.1Et07 S.OEt04 O.OE-01 9.9E+04 4.3E+06 1.8Et02 9.2E-04 2.2E+05 4.3E+06 O.OE-OO 2.5E+08 3.0Et08 4.7E+07 2.2E+08 6.5E-06 6.2E+08 7.2E-04 1.1E+01 7.6Et02 2.3E+08 9.8Et09 3.0ftOB 1.0E+09 3.5E-Oi O.OE-01 1.2E+05 3.4E-18 3.BE+10 3.8Et08 S.BE+07 3.8Et07 2.7Et07 7.2E+05 6.7E-09 5.0E+03 1.4E+09 O.OE-OO 3.3E+01 2.3E-15 8.3f+08 2.1Et07 7.9E+08 O.OE-OO 2.1E+07 2.BE+02 6.4E+06 1.0Et08 7.4Et06.

0.0E-01 4.4E+09 7.3ft06 2.9E+03 1.6Et05 1.6Et07 6.9Et08 1.1Et03 7.6Et08 1.2Et09 5.3Et08 2.1Et09 2.2Et05 3.0Et09 9.0Et05 3.3Et06 9.5Et05 6.0Et10 2.1Et12 1.3Et09 6.2Et08 5.2Et06 8.2E-02 1.6Et07 2.2E+03 1.2E+10 3.0Et09 3.3Et09 1.2Et09 1.4E+09 9.2Et07 1.7E+05 9.9Et06 1.2Etll 1.6Et03 1.7E+08 2.1E t06 2.6E+10 1.'1Et09 2.5E+10 3.6f -11 1.4Et09 1.6E+07 9.0EtQB 1.1Etl0 4.8Et08 O.OE-01 1.BE+09 8.3Et08 66

CONTRGLLEG COPY fg

CONTIROLLED COPY AMFNDMENT NO.

6 November 1988 TABLE 3-5 d

DOSE PARAMETERS FOR 10 CFR 50 EVALUATIONS AIRBORNE RELEASES AGf GROUP:

INFANT ORGAN OF REFEREN(f:

MAXIMUM ORGAN R(I), INDIVIDUALPATHWAY DOSE PARAMETERS FOR RADIONUCLIDES OTHER THAN NOBLE GASES RADIO-INHALATION GROUND PLANE COW-MILK GOAT-MILK ANIMAL-MEAT VEGETABLES NUCLIDE (MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR (M2.MREM/YR PER UCI/M3),

PER UCI/SEC)

H 3

NA 24 CR 51 MN 54 MN 56 FE 55 FE 59 CO 58 CO 60 CU 64 ZN 65 ZN 69M AS 76 BR 82 SR 89 SR 90 ZR 95 NB 95 ZR 97 NB 97 tS 99 TC 99M RU106 AGiiOM SB124 SB125 SB126 SB127 TE127 TE131M I 131 I 132 I 133 I 135 CS134 CS136 CS137 CS138 BA140 LA140 CE141 CE144 ND147 HF1 79M HF181 W 185 3.7E402 1.1E004 1.3E>04 i.'Of~06 7.2E+04 8.7E+04 1.0E+06 7.8E+05 4.5E+06 1.5E+04 6.5E+05 4.1E+04 2.7EI04 1.3E+04 2.0E+06 1.6E+07 1.8E+06 4.8E+05 1.4E+05 2.7E+04 1.3ft05 2.0E+Q3 1.2E~07 3.7E+06 2.6E+06 1.6E>06 9.6E+05 2.2E+05 2.4fi04 2.0E+05 1.5E+07 1.7E+05 3.6E406 7.0E+05 7.Of<05 1.3E405 6.lfi05 8.8E+02 1.6ft06 1.7E+05 5.2E005 9.8f+06 3.2E+05 2.8E+04 8.4E>04 6.3E+05 O.OE-01 1.2E+07 4.7E+06 1.4E+09 9.0E+05 O.OE-01 2.7E+08 3 'E+08

2.3E+10 6.1E+05 7.5E>08 1.3E+06 3.8E+06 2.1E+07 2.2E+04 6.7E+06 2.5E+08 1.4E+08 3.0ft06 1.8E+05 4.0E+06 1.8E+05 4.2E+08 3.5E+09 6.0E+08 2.4E+09 8.4E+Q7 1.7E+07 3.0E+03 8.0E+06 8.6E+06 6.2E+05 1.2E+06 1.3E+06 6.9E+09 1.5E+08 1.3E+10 3.6E+05 2.if~07

'1

~ 9E+07 1.4E+07 7.0E+07 8.5E+06 O.OE-01 2.1E+08 1.8E+04 1.8E+03 7.8f+06 2.2E+06 2.1E+07 1.3E+00 7.4E+07 1.8E+08 2.9E+07 1.2E+08 1.9E+06 1.2E+10 2.4E+07 2.2E+07 9.8E+07 6.0E+09 1.2E+11 4.0E+05 9.6E+07 2.2E+04 1.1E-06 1.6E>08 8.2E+03 8.0E+05 8.2E+09 3.1E+08 1.1E+08 2.1E+08 5.5E+Q7 6.8E+04 1.2E+07 2.6E+11 3.4E+Oi 2.4E>09 4.9E+06

3. 7E+10 2.BE+09 3.6E+10 1.2E-22 1.2E+08 9.4f+04 6.4E+06 7.if+07 2.BE+05 O.OE-01 5.9E+05 2.7E+07 3.7E+03 1.4E+06 3.BE~05 3.1E+06 2.4E-01 1.2E+07 3.4E+07 4.BE+06 1.7E+07 3.2E+05 1.7E+09 4.3E+06 4.0E+06 1.8E+07

1. 8E+10 2.9E+11 6.5E+04 1.7E+07 4.0E+03 1.9E-07 2.8E+07 1.5E+03 1.2ft05 1.2f+09 5.1E+07 1.6E+07 3.7E+07 9.9E+06 1.2E+04 2.1E+06 4.7E+11 6.1E+01 4.3E+09 8.9E+06 1.4E+11 1.2E+10

1. 3E f11 5.6E-22 2.ifi07 1.7E<04 1.if~06 1.if~07 5.Of~04 O.OE-01 9.9E~04 4.4E~06 O.OE-01 O.OE-Oi O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-Oi O.OE-Oi O.OE-01 O.OE-01 O.OE-01 O.OE-Oi O.OE-01 O.OE-01 O.OE-Ol Q.OE-Oi O.OE-01, O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-Oi O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.QE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-Oi 0.0E-01 O.OE-01 O.QE-01 O.OE-01 O.OE-01 O.OE-01 0.0E-01 O.OE-01 O.OE-01 O.OE-01 O.OE-Ol O.OE-01 O.OE-01 O.OE-01 O.OE-01 0.0f-01 O.OE-01 0.0f-01 O.OE-01 O.OE-Oi O.OE-01 Q.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-Oi O.QE-01 O.OE-01 O.QE-Oi O.OE-01 O.QE-01 0.0E-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-Oi Q.OE-01 O.OE-01 0.0f-01 Q.OE-01 O.QE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 O.OE-01 67

CONTROLLED COPY

CGNTRGLLEG CQPY Table 3-9 AMENDMENT NO.

6 November 1988 INPUT, PARAMETERS NEEDED FOR CALCULATING DOSE SUMMARIES TO THE MAXIMUM INDIVIDUALAND THE POPULATION NITHIN 50 MILES FROM NNP-2 GASEOUS EFFLUENT In ut Parameter Distance to Maine (miles)

Fraction of year leafy vegetables are grown 3000 0.42 Value Reference*

Ref 1

Ref 2

Fraction of year cows are on pasture 0.5 Ref 2

Fraction of crop from garden 0.76 Ref 3

Fraction of daily intake of cows

'erived from pasture while on pasture 1.0 Annual average'relative humidity (5) '3.8 Ref 2

Ref 4

Annual average temperature (Fo) 53.0 Ref 5

Fraction of year goats are on pasture 0.75 Ref 2

Fraction of daily intake of goats derived from pasture while on pasture Fraction of year beef cattle are on pasture Fraction of daily intake of beef cattle derived from pasture while on pasture Population within 50 miles of plant by direction and radii interval in mi 1 es.

Annual 50-mile milk production

( 1 iters/yr)

Annual 50-mile meat production (kg/yr)

Annual 50-mile vegetable production (kg/yr)

Source terms 1.0 0.5 1.0 252,356 2.8E+08 2.3E+07 3.5E+09 Ref 2

Ref 2

Ref 6

Refs 7

& 9 Refs 7

& 9.

Ref 8 71

CGNTRGILLEG CGPY

C0NTR@J.gg COPY REFERENCES FOR VALUES LISTED IN TABLE 3-9 AMENDMENT NO.

6 November 1988 Reference 1

U.S.

Hap Reference 2

Site Specific Reference 3

Regulatory Guide 1.109, Revision 1, Table E-15 Reference 4

Section 2.3, WNP-2 FSAR, Table 2.3-1 Reference 5

Section 2.3, WNP-2

FSAR, page 2.3-3 Reference 6

WNP-1

& WNP-2 Emergency Preparedness Plan Table 12.1, Permanent Population Distribution, Rev 5, Feb.

88 Reference 7

1986 50-Hile Land Use Census, WPPSS REHP Reference 8

WNP-2 Effluent Analysis for Applicable Time Period Reference 9

Radiological Programs Calculation Log No. 88-3 Reference 10 WNP-2 XOQDOQ Computer Run 86

CGNTIRGLILEG.CGPV 11 x

k

AMENDMENT NO.

6 November 1988 TABLE 3-16 ANNUAL D I

I IN WNP-2 SITE BOUNDARY Source:

WNP-2 Gaseous Effluent Location Distance Miles Occupancy hrs/ r Whole Body Dose mrem/ r Thyroid Dose mrem/ r BPA Ashe Substation DOE Train Wye Burial Site WNP-1 WNP-4 WNP-2 Visitor Center Taylor Flats"~

Site Boundary*""

0.5 N

0.5 SE*

0.5 WNW 1.2 ESE 1.0 ENE 0.08 ESE 4.2 ESE 1.2 SE 2080

. 78 2080 2080 1.1E+00 6.7E-02 4.1E-03 f

3.8E-02 7.0E-02 8.6E-02 8760 3.1E-02 8760 1.1E+00 1.7E+00 1.0E-01 6 'E-03 1.3E-01 1.1E-01 1.3E-01 5.2E~OO 1,.7E+00

The sector with the highest X/9 values (within 0-0.5 mile radius) was used.

- Not within site boundary.

Closest residental area representative of maximum individual dose from plume,

ground, ingestion, and inhalation exposure pathways.

Included for comparison.

- - Assumed continuously occupied.

Actual occupancy is very low.

Doses from Inhalation and Ground Exposure pathways.

No food crops.

88

AMENDMENT NO.

6 November 1988 CONTROLLED COPY

~Rx Bld.

Refueling Pump Rooms Main Steam Tunnels Plenum Monitors Exhaust Plenum RM To Elevated Release Plenum Monitors Turbine Bldg.

Cond.

Pump Rm.

Turb. Opr.

Deck Condenser Area Exhaust Pl enum RM To Atmosphere Radwaste Bld Hot Mach.

Shop Chem.

Labs Demin.

Room Radwaste Proc.

Area Control Room Filter Units RM To Atmosphere SIMPLIFIED BLOCK DIAGRAM OF GASEOUS WASTE SYSTEM Figure 3-2 9oa

AMENDMENT NO.

6 November 1988 Main Condenser Air Ejector.

Condensers Off-Gas Preheaters Hater Separator Off-Gas Condenser Off-Gas Recombiners Gycol Cooler Condenser Off-Gas Moisture Separators Off-Gas Pre-Filters Charcoal Coolers Dr yers Absorbers Post Treatment

Monitor, After Filters Elevated Release SIMPLIFIED BLOCK DIAGRAM OF OFF-GAS TREATMENT SYSTEM Figure 3-3 90b

CGNTlRQLLEG CQPY 1,

CONTIROLILED COP"r AMENDMENT NO.

6 November 1988 0

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( ~ 0AWOAO aa attaowo ao Oa Caarfl tio Iofatoaar laic l EMERGENCY PLAN ZONE MAP SUP%.Y SYSTKM 10 MIISRAOIUS 4jSUPPLY SYSTEM 880334 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS INSIDE OF 10 NILE RADIUS figure 5-1 106

CGNTlRGLLEG CQPV 0':

ML17285A262

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REFERENCE:

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