Text

Rev 2 to FNP-0-M-011, Odcm
	ML20126A194
Person / Time
Site:	Farley
Issue date:	12/08/1992
From:	; SOUTHERN NUCLEAR OPERATING CO.
To:	;
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ML20126A173	List: ML20126A169; ML20126A181; ML20126A194;
References
	FNP--M-11, FNP-0-M-011, NUDOCS 9212180034
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1 FNP-0-M-011 Auguct 20, 1992 Ravision 11-ALABAMA POWER COMPANY JOSEPH M.

FARLEY NUCLEAR PLANT FNP-0-M-011 S

A F

E T

Y OFF-SITE DOSE CALCULATION MANUAL i

R E

L A

T E

D Approved:

l dchiiic'al Mange j

Date Issued: /1/8 91 List of Effective Paces Page

Rev, 1,il,iil,1v,v,1-2,2-1 to 2-3,2-5,2-10 to 2-16,3-1 to 3-5, 10 I

3-17,3-18,3-21,3-22,3-24 to 3-30,3-50,5-2 to 5-4,6-1 10 3-19 8

i 1-1,3-6 to 3-16,3-20,3-23, 7

3-31 to 3-49,4-1,5-1,5-5 to 5-7,6-2 to 6-9 7

l 2-4, 2-6 to 2-9 11 Appendix 10 M-11 9212180034 921214 PDR ADOCK 05000348 R

PDR 2

1

FNP-0-H-OlI CONTENTS PAGE TABLE OF CONTENTS.

1 LIST OF TABLES il LIST OF FIGURES lii ODCM-TECHNI"AL SPECIFICATION CROSS REFERENCE TABLE iv REFERENCES v

CHAPTER 1 INTRODUCTION 1-1 CHAPTER 2 LIQUID EFFLUENTS 2-1 2.1 LIQUID RELEASE CONFIGURATIONS 2-1 2.2 SETPOINT CALCULATIONS

. 2-4 2.3 10CFR2O AND TECHNICAL SPECIFICATION COMPLIANCE 2-7 2.4 DOSE CALCULATIONS 2-8 2.5 COMPOSITE ANALYSES

. 2-11 2.6 DOSE PROJECTIONS

. 2-11 l

CHAPTER 3 GASEOUS EFFLUENTS 3-1 3.1 GASEOUS RELEASE CONFIGURATION 3-1 3.2 CALCULATIONS OF X/Q AND D/Q VALUES 3-4 3.3 SETPOINTS FOR GASEOUS MONITORS 3-17 3.4 GASEOUS 10CFR20 COMPLIANCE 7

3-21 3.5 GAS WASTE STORAGE TANK,

3-25 3.6 CUMULATIVE DOSE CALCULATIONS 3-25 3.6.1 Dose Calculations From Noble Gas Releases 3-25 3.6.2 Dose Calculations For Radionuclides In Particulate Form 3-27 3.7 COMPOSITE ANALYSES 3-50 3.8 DOSE PROJECTIONS 3-50 CHAPTER 4 TOTAL DOSE 4-1 CHAPTER 5 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS 5-1 CHAPTER 6 METEOROLOGICAL

SUMMARY

6-1 APPENDIX ODCM EQUATIONS AND SOURCES A-1 i

Rev. 10

FNP-0-M-011 List of Tcbles Page 2-1 Liquid Release Tanks and Monitors 2-1 2-2 Bioaccumulation Factors 2-12 2-3 Ingestion Dose Conversion Factors 2-13 2-4 Liquid Effluent Dose Commitment Factors 2-15 3-1 Gaseous Release Sources, Release 3-2 Points, and Monitors 3-2 Site Boundary and Limiting Food 3-7 Pathway Distances 3-3 Dose Factors for Noble cases and 3-20 Daughters l

3-4 Infant Dose Factors 3-24 3-5 Organ Dose Factors for Each Nuclide 3-31 5-1 Radiological Environmental Monitoring 5-2 Locations 6-1 X/Q Values for Mixed Mode 6-2 i

1 l,

6-2 X/Q Values for Ground Level Releases 6-4

{

l 1

6-3 D/Q Values for Mixed Mode 6-6 6-4 D/Q Values for Ground Level Releases 6-8 i

l I,

r i

l 11 Rev. 10 l

l L

l

FNP-0-M-Oll-Liot of Figures Page 2-1 Liquid Waste Release Tanks 2-2 2-2 Routine Liquid Waste Effluent Pathways 2-3 3-1 Gaseous Release Sources 3-3 3-2 Vertical Standard Deviation of the Plume

'3-8 3-3 Recirculation Factor-3-9 3-4 Ground Level Relative Deposition 3-13 3-5 Elevated Relative Deposition - 30 m 3-14 3-6 Elevated Relative Deposition - 60 m 3-15 3-7 Elevated Relative Deposition - 100 m 3-16 5-1 Airborne Sampling Locations at Farley 5-5 Nuclear Plant, 0-5000 feet

- j 5-2 Airborne Sampling Locations at Farley 5-6 Nuclear Plant, 0-20 miles 5-3 Water Sampling Locations for Farley 5-7 Nuclear Plant

'l

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-l 111 Rev. 10

.n

.l FNP-0-M-011 l

ODCM-TECHNICAL SPEC 2FICATIONS CROSS REFERENCE TABLE Radiological Effluent Technical Specification Dose Calculation ODCM Section

-Methodology Page 3.3.3.10 Determination of 2-4 Alarm Trip Setpoints For Liquid Monitors 3.3.3.11 Determinaticn of 3-17 Alarm Trip Setpoints For Gaseous Monitors 4.11.1.1.1 Liquid Effluents 2-7 4.11.1.1.2 Liquid Effluents 2-7 4.11.1.1.3 Liquid Effluents 2-7 4.11.1.2 Liquid Effluents 2-8 4.11.1.3.1 Liquid Effluents 2-11 4.11.2.1.1 Noble Gases 3-21 4.11.2.1.2 Gaseous Effluents 3-21 4.11.2.2 Noble Gases 3-25 4.11.2.3 Radiciodines.and 3-27 Radioactive Materials in Particulate Form 4.11.2.4.1 Gaseous Effluents 3-50 4.11.4 Dose Assessment for 4-1 Environmental Radiation Standards 4.12.1 Radiological Environ-5-1 mental-Monitoring 6.9.1.9 ODCM All 6.9.1.10 ODCM All 6.14 ODCM Al iv Rev. 10

~

FNP-0-M-011 REFERENCES 1.

Doegli, J.S., R.R. Bellamy, W.L. Britz, and R.L. Waterfield, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, "NUREG-0133" (October 1978).

2.

Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors, U.S.

NRC Regulatory Guide 1.111, (March, 1976).

3.

Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors, U.S.

NRC Regulatory Guide 1.111, Rev. 1 (July, 1977).

4.

Calculation of Annual Doses to Man from Routine Releases of Resctor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix 1, U.S.

NRC Regulatory Guide 1.109, Rev. 1 (October 1977).

5.

Plume Rise, G.

A.

Briggs, U.S.

Atomic Energy Commision Critical Review Series, TID-25075, 1969.

6.

Meteorology and Atomic Energy, David H.

Slade, editor, Technical Information Center, U.S.

Department of energy, 1968.

7.

T.

E.

Young, T.

S.

Bohn, and W.

Serrano, " Technical Evaluation Report for the Evaluation of ODCM Revision 7 Joseph M.

Farley Nuclear Plant, Units 1 and 2",

EGG-PHY.8674 dated August 1989, transmitted by NRC letter dated 11-9-89.

8.

Jackson, W.

M.,

" Survey Report of Chattahoochee River Water Use Downstream of Farley Nuclear Plant Liquid Effluent Discharge", dated July 19, 1990.

9.

" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR 50, Appendix I",

U.

S.

NRC Regulatory Guide 1.109, Draft, Piarch 1976.

10.

Kocher, D.

C., " Radioactive Decay Data Tables", DOE / TIC-11026, dated 1981.

11.

Joseph M. Farley Nuclear Plant Environmental Report Operating License Stage (July 23, 1975).

v Rev. 10

~

FNP-0-M-011 CHAPTER 1 INTRODUCTION 1

This Off-Site Dose Calculation Manual (ODCM) describes the methods used at Farley Nuclear Plant (FNP) for complying with the effluent release portions of the FNP Technical Specifications and the requirements of 10CFR20 and Appendix I of 10CFR50.

The concentration and dose limits that are required to be met and which are-described in this manual ares o For radioactive liquid effluents, the concentrations released to areas beyond the site boundary are limited to the values given in 10CFR20, Appendix B, Table II.

o For radioactive liquid effluents, the maximum dose to ar.y member of the public will be less than the limits given in 10CFR50, Appendix I.

o For gaseous effluents, the dose rate at any' location beyond the site boundary will be limited to the annual dose limits given in'10CFR20.

o For gaseous ef fluents, the maximum dose to any member of the public will p

be less than the limits given in 10CFR50, Appendix I.

i-o The maximum dose to any member of the public will not exceed the limits given in 40CFR190.

The equations employed are taken from NUREG-01335 and Regulatory. Guide-1.111u, Referer.ces to Regulatory Guides are given with the equation numbers in this ODCM.

Dose tactors are calculated or taken directly from Regulatory Guide 1.109'.

I 1 Gen. Rev. 7 l

v

FNP-0-H-011 This ODCM describes tha physical configuration of release-sources and release points for routine and non-routino liquid and gaseous offluents, the monitor-setpoint calculations, dose, and dose rate calculations.

Units 1 and 2 have independent release points for gaseous releases, and a common release point for 11gulds.

For gaseous-releases, dose limits for the site are normally apportioned equally between the two units, independent of the operational status of either unit but may be altered to allow more dose appropriation to either unit as necessary.

l I

l t

l l

l --

1-2 Rev. 10 I'

i 1

g.

FNP-0-H-01a

)

CHAPTER 2 LIQUID.':FFLUENTS 2.1 LIQUID RELEASE CONFIGURATIONS Routine liquid releases for each unit are discharged through a single i

release point.

These are normally batch roles.ses from the controlled discharge of liquid waste tanks.

A simplified diagram of the waste tanka j

and the discharge paths is.shown in Figure 2-1.

Radiation monitor RE-18 is I

on the discharge path.

l Houtine releases are normally batch or contir.uous releases of the waste sources listed in Table 2-1.

l Table 2-1. Liquid Waste Effluent Pathways for Routine Releases Ianh Enigjute Tyr>e Volume Monito c Waste Monitor Tank i batch 5000 gal 1/2 P118 Waste Monitor Tank 2 batch 5000 gal 1/2 RE18 Turbine Building continuous or batch Sump Steam Generator continuous 1/2 RE23A, Blowdown 1/2 RE23B Figure 2-2 shows the relationship of all of the-routine liquid effluent t-pathways and the combined discharge to the river, other potentiti effluent pathways are monitored regularly, and may be treated as non-routine releases, if required.

Non-routine releases-are un-monitored during. release.

Dose calculations will be made based on estimates mf the activity concentration and volume of flow released.

i

1/2 stands for Unit 1 or Unit 2 L

2-1 Rev..10 i

l l

-m g--

m w y-rywp-'vwge--&+-*

wr-1---7%W*

h 4T""

E,iquid Effluents TNP-0-M-0A1 c----,

11:

e g

TANx 6

P6

)

i U

h.lL2g2,3A,,,,,,,,J TO MAIN CONDENSER (

L L4

^

RE T

I FT RADIATION

!10NITOR T

TO ENVIRONMENT (

i --

1/2RE23B O

S/G B i

DISCl!ARGE PUt!PS l

l l

\\

4 u==Y c,,,, a t L yr FLWR !sRAIN DRAIN g g

,7, 7ANK IAhE IANE iANK (L' NIT I ONIT) l l

1 i

P y

WAIT! M APORATcl D[$POSABLE PACKAGE DMINERALIllR SYSTEM

-a,,,

l,V i

mn y

asTE waste DISCRARGE

" FAN $

STRUCTURE T

r A

WASTE REUSE (

"y;"l**

.f TANK 4

1/2 018 Tigure 2-1. Liquid waste Release Tanks 2-2 Rev. 10

t

~

Liquid Effluents Unit 1 Unit 2 Service Water Service Wate.r Train A Train li Train A Train l' I

4 Cooling Tower Blowdown p

4 Radwaste Discharge IRE 018 ad018 i

Steam Generator Blowdown

'RE23B 2RE2JB M-Turbine Building Sump p

V To River l

l i

Figure 2-2. Routine Liquid Waste Effluent Pathways 2-3 gey, 10 i

l e

FNP+0-H-CG Liquid Etfluents 2.2 SETPOINT CALCULATIONS Calculations are made for the radiation monitors to determine the alarm / trip setpointe so that 10CFR20 compliance is met for the etfluent pathway at the site boundary.

These calculations use the roaximum permissible concentrations (HPC) from 10CFR20 Appendix B,

Table II, Column 2, and the more conservative of the soluble (S) or insoluble (1) values except for the noble gases for which a total of 2 x 10'd pCi/mi is used.

The relationship that must be met to ensure 10CFR20 compliance is Cu 5 1 (2.1)

E i

HPCi whace l

Cu = concentration of radionuclide i at the site boundary (discharge structure at the river) in pCi/ml.

HPC, = 10CFR20 Appendix B, Table II, Column 2 values except for noble gases.

E=

Sum over all radionuclides i

The concentration at the site boundary includes the contribution from all sources of both Units 1 and 2.

The value of Cu is a calculated value _ since only the concentrated input streams are measured for radionuclide content. Therefore 2

E Cw,

f.,

Cu = E 2.2) u=1 F,

where Ca, = concentration of radionuclide, i, in the effluent pathway, p, from Unit, u, in pC1/ml.

f,=

flow rate from the effluent pathway, p, from the Unit, u, _in l'

9Pm.

F,,

=

dilution flow (service water and cooling tower blowdown) plus-f.,in gpm.

i-i, 2-4 Rev. 11'

-.,___,__m v'--,-re,e-,,vw,---

'-N

FNP-0-M-011 l

l Liquid Effluents l

Each unit has an established and measured dilution flow so that if C,

g I

5 1 i

MPC, is met for each unit then equation 2.1 will hold for the site, where C, is the concentration of radionuclide, i, in the discharge t

from Unit u.

Thus the unit specific 10CFR20 limit can be formulated as E

C,.

f,,

p.................

I F,

i

...............--- s 1 (2.3)

MPC, To account for multiple effluent pathwayo from a single unit an apportionment factor, A F,, will be defined for each pathway such that a,

f,,

C I

F, i

5 AF,

(2.4)

MPCi with the restriction that E AF,s 1 (2.5) c P

Rearranging equation 2.4 and substituting Dm, for L at the f.,

limit of the inequality then 1

Cu, Dm,

E

= --------

m AF,

i

MPC, (2.6) where Dm, is the minimum dilution f actor required for this effluent pathway to meet 10CFR20 limits at the site boundary (assumes all the pathways at the maximum value).

2~5 Rev. 10

1 TNP-0-H-011 Liquid Effluento i

A safety factor of 2 is now applied to compensate for uncertainties in the measurements and calibrations so that the required dilution i

f actor (Dr,)

is l

Dr, = 2

Dnq, (2.7) i and can be calculated for each effluent pathway using l

2 Ca, Dr,

E

= -------

A P,,

MPC, (2.8)

If the required dilution factor is less than 1, dilution is not required, but a setpoint must still be calculated.

The actual dilution factor, Da,, is calculated based on the unit-specific dilution-flow, r,,

and the unit-specific, effluent-l pathway-specific effluent flow, f,,, as follows:

1 D a, = F, / f,

I f ( D a, / D r.,) < 1, the release may not_be made as planned.

If

~

the release is to be made, one or more of the following steps must be taken, followed by new determinations of Da, and Dr, a 1) g increase the planned dilution flov; 2) decrease the planned effluent flow, or 3) reprocess the liquid radwaste involved. The calculated ratio of Da,, to Dr, is an indicator of the margin of safety associated with the planned release, in addition to the safety factor of two included above in the calculation of Dr.,.

To allow the discharge to occur without reaching the monitor setpoint the actual, or anticipated, dilution f actor (Da,) must be greater than the required dilution factor, Dr,.

This requirement will li.mit the effluent release point flow rate.

The monitor setpoint is defined as (Da, - Dr )

H,=

E C,,

(2.9) s D r, i

where H, = retpoint in pci/ml w

E C, =. Sum over all gamma-emitting radionuclides in the t

i undiluted waste stream (the monitor is sensitive only to gamma-rays).

-in which 2

Cgs, Dr, =

E AP,

i MPCi 2-6 Rev. 11 J-u

FNP-0-H-011 Liquid Effluents and 2

Ca, D r, =

E AF,

i

HPC,

Summed over all non-gamma-emitting radionuclidos.

The concentration of non-gamma-emitting radionuclides used in this calculation shall be the unit-specific historical maximum vslues based on results of the sampling and analysis program described in Technical-Specification Table 4.11-1.

1 i

- Summed over all gamma-emitting radionuclides.

Once the setpoint has been established the release pathway flowrate must be controlled to less than or equal to the anticipated value, f,.

For the setpoint in counts per minute (epm)

S PC, = T.

N(, + B.,

(2.10) where E.

= monitor calibration factor (cpm / C1/ml)

B, = ef fluent monitor background in epm For a potential effluent pathway, e.g. the service water, that has no detectable activity, the setpoint should be set as close to background as practical to alarm if an inadvertent release were to occur but prevent spurious alarms.

The monitor setpoints determined in accordance with the methodology

. described above establish the upper bound for a particular monitor setpoint. Monitor setpoints may be eutablished at lower values if desired.

2.3 10CFR20 AND TECHNICAL SPECIFICATION COMPLIANCE 2.3.1 Prior to Release Prior to release, all tanks to be released as a batch are isolated from the source and recirculated a minimum of two volumes to ensure-adequate mixing.= The batch tank-is then sampled af ter the appropriate mixing.

Recirculation time to ensure adequate mixing is calculated-as-follows:-

minimum recire duration (minutes): = tank content foallons) X2 recire rate (gpm).

Prior to making a discharge the following parameters-are established for the releases a.

Monitor setpoint (if the pathway has a monitor).

'l 2-7 Rev...

l

FNP-O-H-011 Liquid Effluents b.-

Maximum effluent pathway release flow rate.

c.

Anticipated dilution flow rate.

d.

Assurance that the condition of equation (2.3) will be met considering all effluent pathways during the discharge.

2.3.2 During the Release During the release the following information should be recorded:

a.

Actual flow rate of the effluent release pathway.

)

b.

Actual dilution flow rate.

c.

Effluent monitor response (if there is an operable effluent monitor in the release pathway).

2.3.3 After the Release After the release is completed, the actual effluent discharge information recorded during the release is used to verify that the condition of equation (2.3) was met during the discharge where f and F, are the actual flows recorded.

u 2.4 DOSE CALCULATIONS A river use survey was conducted (reference 8) on the Chattahoochee River and Lake Seminole below Plant Farley. The survey encompassed drinking water, irrigation of crop and gardens, fishing, and recreational use of the river and shoreline. Only two pathways to man for the uptake of the liquid effluents were identified.

These are fishing and irrigation and consumption of vegetables.

Therefore, the dose calculations will consider fish and green leafy vegetables irrigated with river water consumed by an adult as the maximally exposed individual.

The dose limits specified in Technical Specification 3.11.1.2 are oa a per reactor basis.

Therefore the doses calculated in this subsection will be on a per reactor basis.

The dose to the maximum exposed individual due'to radionuclides identified in each liquid effluent release from each unit to unrestricted areas will be calculated as follows:

D, = I [

A,, I At, C, F l (2.11) i 1

2-8 Rev. 11

1 i

FNP-0-N-013 Liquid Effleunts where:

D, =

the cumulative dose commitment to the total body or an organ, t, from the liquid effluents for the total time period I At, i

in mrem.

1 A,,

=

site-related adult ingestion dose commitment factor to the total body or organ, t, for each identified radionuclide in Table 2-4, in mrem /hr per uci/ml.

I Ati=

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

C, =

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

in pCi/ml.

i i

Fi=

the near field average dilution factor for Cy during any liquid i

effluent release.

F,is defined as the ratio of the average undiluted liquid waste flow during release to the product of the average unit flow from the site discharge structure to unrestricted receiving waters times 5.

(5 is the site specific applicable factor for the mixing effect of the discharge structure.)

f, w

F, (2.12)

F,

5 with the limitation that 1

F,

5 s 448,800 gpm.

(1C00 cfe - reference 1)

The values of A,, shown in Table 2-4 are calculated from A, = k. [ U, B Fi + U C Fw ) D F,,

(2.13) wheres k, =

unit conversion f actor 1.14 x 10' (year /hr). (ml/1). (pci/uci)

U, =

adult fish consumption, 21 kg/yr. (reference 4)

BF,=

the bicaccumulation factor (Table 2-2) in fish for each measured radionuclide 1, in pCi/kg per pCi/ liter (Table A-1 of l

Reg. Guide 1.109, Ref. 4).

I

- U. =

adult vegetable consumption, 64 kg/yr (reference 4) 2-9 Rev. 11 l-m.

p-_-

q.v'r y

s' W

r-n-

-t+

v wm v

v

=

e---"'

e

"r~-+

mP-0-M-011 Liquid Effluents CF,, - concentration factor for radionuclide i in the vegetable, pC1/kg/pci/l for radionuclides other than tritium r(1-e

,',)

f, D, (1-e",*,)~

i

= M.I

- +

e Y

P A,

. (2.14)(ref. 4) y i

~

for tritium M

(2.15)(ref. 4)

=

Dr,, = the ingestion dose conversion factor (Table 2-3) for each

organ, T, for each nuclide, i, for adults, in mrenVpCi (Table E-11 of Reg. guide 1.109, Ref. 4).

M=

additionp1 river dilution at the point of irrigation usage (4 x 10' using actual river flow data for 1989 as a typical year) averageirr[gationrateduringthegrowingseason,1/m#/hr 1-(1.26 x 10' estimate based on pump capacity and garden size from reference 8 for 10% of the time).

fraction of deposited activity retained on leafy vegetables, r=

1.0 for iodines and 0.2 for others (reference 4).

Y, - agricultural proeductivity, 2.0 kg/m* (reference 4).

the fraction of the year that the vegetables are irrigated f

=

t (0.1, estimate based on reference 8).

crop to soil concentration factor, pCi/kg leaf per pCi/kg D

=

g soil, Reg. Guide 1.109, Table E-1 (reference 4).

P=

effective surface density for soil, 240 kg/m# (reference 4).

A, = decay constant for radionuclide 1 (reference 10).

(=

rate constant for removal of activity from a plant leaf (helf-life = 14 days), 0.0021 hr'* (reference 4).

AE,

( + X, (effective removal rate for radionuclide i from

=

crops, reference 4).

t, = period of leafy vegetable exposure during growing season, 60 days (1440 hours0.0167 days 0.4 hours 0.00238 weeks 5.4792e-4 months ) (reference 4).

period of long tprm activity buildup in soil (norainally 15 t

3 years) 1.31 x 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months (reference 4).

2-10 Rev. 10 1

IUP-0-14-011 Liquid Effluents t, = time delay between harvest of vegetable and censumption by man, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (reference 4).

2.5 COMPOSITE N RLYSES ror radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar month or quarter cumulative summation may be approximated by assuming an average monthly or quarterly concentration based on the previous monthly or quarterly composite analyses.

The nuclides determined f rom composite analyses are 11-3, re-55, Sr-89, Sr-90, and gross alpha.

2.6 DOSE PROJECTIONS Dose projections shall be made at least once in every 31 days, for all liquid effluent doses, based on the expected operating conditions.

These dose projections will be compared to the projected dose limits of 0.06 mrem for the total body and 0.2 mrem for any organ.

These limits are for the month.

2-11 Fev. 10

FNP-0-M-011 Liquid Effluents Bioaccumulation Factors for Fresh Water fich Bioaccumulation Factor for Element Fresh Water Fish H

9.00E-01 C

4.60E+03 NA 1.00E+02 P

3.00E+03 (Reference 7)

CR 2.00E+02 MN 4.00E+02 FE 1.00E+02 Co 5.00E+01 NI 1.00E+02 CU 5.00E+01

~

ZN 2.00E+03 BR 4.20E+02 RB 2.00E+03 SR 3.00E+01 Y

2.50E+01 ZR 3.30E+00 NB 3.00E+04 MO 1.00E+01 TC 1.50E+01 RU 1.00E+01 R11 1.00E+01 TE 4.00E+02 I

1.50E+01 CS 2.00E+03 BA 4.00E+00 LA 2.50E+01 CE 1.00E+00 PR 2.50E+01 ND 2.50E+01 W

1.20E+03 NP 1.00E+01 SB 3.00E+02 (Reference 11)

AG 2.30E+00 (Reference 9)

Units are pCi/Kg per pCi/ liter Table 2-2.

Bioaccumulation Factors (Ref. 4, except as indicated) 2-12 Rev. 10

FNP-0-M-011 Liquid Effluents INGESTION LOSE COINERSION ThC10RS Nuclide Bone Liver T. Body Thy,roid Kidney Lung GI-LLI H-3 0.00E+00 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 CR-51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN-54 0.00E+00 4.57E-06 8.72c-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 MN-56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 TE-55 2.75E-06 1.90E-06 4.43C-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 PE-59 4.34E-06 1.02E-05 3.91E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 Co-58 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 CO-60 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 NI-63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 NI-65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 CU-64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 ZN-65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 ZN-69 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 BR-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-00 BR-84 0.00E400 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 BR-85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 2.11E-05 9.83C-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 RB-88 0.00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 RB-89 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 SR-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 SR-90 7.58E-03 0.00Ev00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 SR-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 SR-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y-90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91M 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 SB-124 2.81E-06 5.30E-08 1.11E-06 6.79E-09 0.00E+00 2.18E-06 7.95E-05 SB-125 2.23E-06 2.40E-08 4.48E-07 1.98E-09 0.00E+00 2.33E-04 1.97E-05 Units are mrenVpci Table 2-3.

Ingestion Dose Conversion ractors (Ref. 4, except SB (Ref. 9))

2-13 Rev. 10

FNP-0-M-011 Liquid Effluents Nuclide Bone.

Liver T. Body Thyroid Kidney Lung GI-LLI Y-93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 ZR-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 ZR-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 NB-95

6. 22 E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 2.10E-05 MO-99 0.00E+00 4.31E-06 8.20E-07 0.00F400 9.76E-06 0.00E+00 9.99E-06 TC-99M 2.47E-10 6.98E-10 0.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07 TC-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 RU-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 RU-105 1.54E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+00. 9.42E-06 RU-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E AG-110M 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05 TE-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.0?t-05 TE-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 TE-127 1.10E-07 3.95E-00 2.38E-08 8.15E-08 4.48E-07 0.00E+00 8.68E-06 TE-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.00E+00 5.79E-05 TE-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0.00E+00 2.37E ]

TE-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 TE-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.00E+00 2.79E-09 TE-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E+00 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E 4.99E-06 4.58E-07 0.00E+00 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.00E+00 1.31E-06 CS-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E-05 -2.59E-06 CS-136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-06 CS-137 7.97E 1.09E-04 7.14E-05 0.00E+00.3.70E-05 1.23E-05~ 2.11E-06 CS-138 5.52E-08 1.t9E-07 5.40E-08 0.00E+00 8.01E-08 7.91E-09 4.65E-13 i

BA-139 9.70E-08 6.!iE-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 BA-140 2.03E-05 2.0;E-08 1.33E-06 0.00E+00 8.67E 1.46E-08 4.18E-05 BA-141 4.71E-08 3.L E-11 1.59E-09 -0.00E+00 3.31E-11 2.02E-11 2.22E-17 BA-142 2.13E-08 2.llE-11 1.34E-09 0.00E+00 1.85E-11 1.24E-11 -3,00E LA-140 2.50E-09 1.2 E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E-05 LA-142 1.28E-10 5.6J E-11 1.45E 0.00E+00 0.00E+00 0.00E+00 4.25E-07 CE-1A1 9.36E-09 6.21E-09 7.18E-10 0.00E+00.2.94E-09 0.00E+00 2.42E-05 CE-143 1.65E 1.2.3E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 CE-144 4.88E-07 2.f!E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E PR-143-9.20E-09 3.33E-09 4.56E 0.00E+00 2.13E-09 0.00E+00- 4.03E -- PR-144-3.01E-11 1.25E 1.53E-12 -0.00E+00 -7.05E 0.00E+00 4.33E-18=

ND-147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 W-187 1.03E-07 8.61E-08 3,01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05

- NP-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05 Units are mren/pCi Table 2-3.

Ingestion Dose Conversion Factors (continued) 2-14 Rev. 10 e.,e-

~.-.

-v-,

s

- -.. - --w,n,-

---.<,.*-e mm -

w

,,1,.e~

-m n-,

e

FNP-0-M-011 Liquid Effluents LIQUID EFFLUUU DOSE COMMIT 7'J2TT FACTORS Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 2.57E-01 2.57E-01 2.57E-01 2.57E-01 2.57E-01 2.57E-01 Na-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 CR-51 0.00E+00 0.00E+00 1.28E+00 7.63E-01 2.81E-01 1.69E+00 3.21E+02 MN-54 0.00E+00 4.38E+03 8.36E+02 0.00E+00 1.30E+03 0.00E+00 1.34E+04 MN-56 0.00E+00 1.10E402 1.95E+01 0.00E+00 1.40E+02 0.00E+00 3.51E+03 FE-55 6.63E+02 4.58E+02 1.07E+02 0.00E+00 0.00E+00 2.56E+02 2.63E+02 FE-59 1.04E+03 2.46E+03 9.41E+02 0.00E+00 0.00E+00 6.86E+02 8.18E+03 Co-58 0.00E+00 9.03E+01 2.02E+02 0.00E+00 0.00E+00 0.00E+00 1.83E+03 Co-60 0.00E+00 2.60E&O2 5.73E+02 0.00E+00 0.00E+00 0.00E+00 4.88E+03 NI-63 3.14E+04 2.17E+03 1.05E+03 0.00E+00 0.00E+00 0.00E+00 4.53E+02 NI-65 1.26E+02 1.64E+01 7.49E+00 0.00E+00 0.00E+00 0.00E+00 4.17E+02 CU-64 0.00E+00 9.97E+00 4.68E+00 0.00E+00 2.51E+01 0.00E+00 8.50E+02 ZN-65 2.32E+04 7.38E+04 3.33E+04 0.00E+00 4.93E+04 0.00E400 4.65E+04 BR-83 0.00E+00 0.00E+00 4.04E+01 0.00E+00 0.00E+00 0.00E+00 5.82E+01 RB-86 0.00E+00 1.01E+05 4.71E+04 0.00E+00 0.00E+00 0.00E+00 1.99E+04 SR-89 2.25E+04 0.00E+00 6.47E+02 0.00E+00 0.00E+00 0.00E+00 3.62E+03 SR-90 5.58E+05 0.00E+00 1.37E+05 0.00E+00 0.00E+00 0.00E+00 1.61E+04 SR-91 4.07E+02 0.00E+00 1.64E+01 0.00E+00 0.00E+00 0.00E+00 1.94E+03 SR-92 1.54E+02 0.00E+00 6.68E+00 0.00E+00 0.00E+00 0.00E+00 3.06E+03 Y-90 5.78E-01 0.00E+00 1.55E-02 0.00E+00 0.00E+00 0.00E+00 6.13E+03 Y-91 8.64E+00 0.00E+00 2.31E-01 0.00E+00 0.00E+00 0.00E+00 4.75E+03 Y-92 5.06E-02 0.00E+00 1.48E-03 0.00E+00 0.00E+00 0.00E+00 8.86E+02 Y-93 1.60E-01 0.00E+00 4.43E-03 0.00E+00 0.00E+00 0.00E+00 5.09E+03 ZR-95 2.84E-01 9.09E-02 6.16E-02 0.00E+00 1.43E-01 0.00E+00 2.88E+02 ZR-97 1.33E-02 2.69E-03 1.23E-03 0.00E+00 4.06E-03 0.00E+00 8.33E+02 NB-95 4.47E+02 2.49E+02 1.34E+02 0.00E+00 2.46E+02 0.00E+00 1.51E+06 MO-99 0.00E+00 1.04E+02 1.98E+01 0.00E+00 2.36E+02 0.00E+00 2.41E+02 TC-99M 8.87E-03 2.51E-02 3.19E-01 0.00E+00 3.81E-01 1.23E-02 1.48E+01 RU-103 4.66E+00 0.00E+00 2.01E+00 0.00E+00 1.78E+01 0.00E+00 5.45E+02 RU-105 3.69E-01 0.00E+00 1.46E-01 0.00E+00 4.76E+00 0.00E+00 2.26E+02 RU-106 7.05E+01 0.00E+00 8.92E+00 0.00E+00 1.36E+02 0.00E+00 4.56E+33 AG-110M 1.15E+00 1.06E+00 6.31E-01 0.00E+00 2.09E+00 0.00E+00 4.34E+61 TE-125M 2.57E+03 9.31E+02 3.44E+02 7.73E+02 1.05E+04 0.00E+00 1.03E+04 TE-127M 6.49E+03 2.32E+03 7.91E+02 1.66E+03 2.64E+04 0.00E+00 2.18E+04 Units are mrem /hr per vCi/ml Table 2-4.

Liquid Dose Commitment Factors Ai 2-15 Rev. 10

FNP-0-M-011 l

Liquid Effluet.ts Nuclide Bone.

Liver T. Body Thyroid Kidney Lung GI-LLI TE-127 1.05E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 0.00E+00 8.31E+03 TE-129M 1.10E+04 4.11E+03 1.75E+03 3.79E+03 4.60E+04. 0.00E+00 5.55E+04 TE-131M 1.66E+03 8.10E+02 6.75E+02 1.28E+03 8.21E+03 0.00E+00 8.04E+04 TE-132 2.41E+03 1.56E+03 1.47E+03 1.72E+03 1.50E+04 0.00E+00 7.39E+04 I-130

2. 72E+ 01 8.03E+01 3.17E+01 6.80E+03 1.25E+02 0.00E+00 6.91E+01 I-131 1.62E+02 2.31E+02 1.33E+02 7.58E+04 3.97E+02 0.00E+00 6.10E+01 I-132 7.29E+00 1.95E+01 6.82E+00 6.82E+02 3.11E+ 01 0.00E+00.3.66E+00 I-133 5.13E+01 8.93E+01 2.72E+01 1.31E+04 1.56E+02 0.00E+00 8.02E+01 1-135 1.59E+01 4.17E+01 1.54E+01 2.75E+03 6.68E+01 0.00E+00 4.71E4 01 CS-134 2.98E+05 7.09E+05 5.80E+05 0.00E+00 2.29E+05 7.62E+04 1.24E+04 CS-136 3.12E+04 1.23b+05-8.86E+04 0.00E+00 6.85E+04 9.39E+03 1.40E+04 CS-137 3.82E+05 5.22E+05 3.42E+05 0.00E+00 1.77E+05 5.89E+04 1.01E+04 BA-140 2.11E+02 2.65E-01 1.38E+01 0.00E+00 9.00E-02 1.51E-01 4.34E+02 LA-140 1.50E-01 7.56E-02 2.00E-02 0.00E+00 0.00E+00 0.00E+00 5.55E+03 i

CE-141 3.37E-02 2.28E-02 2.58E-03 0.00E+00 1.06E-02 0.00E+00 8.71E+01-CE-143 4.11E-03 3.04E+00 3.36E-04 0.00E+00 1.34E-03 0.00E+00 1.14E+02 CE-144 1.98E+00 8.28E-01 1.06E-01 0.00E+00 4.91E-01 0.00E+00 6.70E+02 PR-143 5.58E-01.2.24E-01 2.77E-02 0.00E+00 1.29E-01 0.00E+00 2.45E+03 ND-147 3.81E-01 4.40E-01 2.64E-02 0.00E+00 2.57E-01 0.00E+00 2.11E+03 W-187 2.96E+02 2.47E+02 8.65E+01 0.00E+00 0.00E+00 0.00E+00 8.10E+04

[

NP-239 2.87E-02 2.82E-03 1.56E-03 0.00E+00 8.81E-03 0.00E+00 5.79E+02 Sb-124 1.75E+03 3.31E+01 6.92E+02 4.24E+00 0.00E+00 1.36E+03 4.96E+04 Sb-125 1.39E+03 1.50E+01 2.80E+02 1.24E+00 0.00E+00 1.45E+05 1.23E+04 Units are mrem /hr per vCi/ml

?

Table 2-4.

Liquid Dose Commitment Factors Ai (continued)-

2-16

- Rev. 10

. 1. -

,..A...

-m.

. ~., - -

m.-.-

nJP-0-M-011 d6 -

i Cl! APTER 3 CASEOUS EFFLUENTS 3.1 GASEOUS RELEASE CONFIGURATION Gaseous releases consist of releases through three different release points:

o Plant vent stack o Turbine building vent (condenser steam jet air ejector) o ILRT (integrated leak rate test) vent The containment ventilation, the auxiliary building ventilation, and the waste gas decay tanks all exhaust through the plant vent stack.

When a waste gas decay tank is released, this is treated as a contribution to the continuous release already occurring through the plant vent stack.

All other ~ releases through - the plant vent stack are continuous.

The turbine building vent is a continuous release also.

The ILRT is a batch-release, performed infrequently.

The plant vent stack is a mixed mode release, according. to - the definition in Reg. Guide' 1.111.

The release vent is at a-comparable height to adjacent. structures (the-stack and containment building are both approximately 40 meters high).

I All other releases are ground level releases.

A schematic diagram of the routine. release points - and release - sources and monitors is shown in Figure 3-1.

Typical flow rates (where applicable) for each release. source-and' release point are given in Table 3-1.

L

[

3-1 Rev. 10-i l

. ~.

~

rie-0-M-Oll Gaseous Effluents Table 3-1.

Gaseous Releases, Flow Rates, and Monitors Release point Release _ type Vent flow rate Monitor Plant vent stack continuous 80,000-150,000 cfm 1/2RE-14 1/2RE-22 Turbine building vent continuous 1,060 cfm 1/2RE-15 ILRT batch Release sources Waste gas decay tank batch 1/2RE-14 Containment purge continuous 1/2RE-24 Release processing of the waste gas decay tank (WGUT) and containment purge releases are made through the plant vent stack.

The WGDT Curie content is tracked separately for Tech. Spec.

compliance.

Activities and dose f rom the plant vent stack are ttacked to account for all activity release from containment and the auxiliary building.

Containment purge activities and calculated doses are not added into the total activity and dose teleased since they are included in the measurements of plant vent stack activity.

WGDT activity and dose are separately calculated and tracked as 5

batch releases.

To eliminate double counting, for each plant stack release, if there was a WGDT batch release, the individual WGDT nuclide activity and dose are subtracted from the plant vent stack release for the time of the WGDT release.

If any nuclide activity is negative, it is set to zero.

3-2 Rev. 10

_ _ _ - _ _ _ _ _ ~ _

Gasoous Effluonts FNP-0-M-011 Waste Gas Decay Tanks sr y

.,h ta c6 II

}F 9P if l

f P

r ef db JL dk 4L di sg ak g,i 7

8 1

2 3

4 5

6 1

1F 17 1F 1?

17 1,

2; 2a 2

41 42 2

26 za J

-~

y 8?

zu da 4%

f, Waste Gas j

RE-13 MONITOR Compressor

)

[

l M

X-PLANT VENT STACK l

U E-l '.

lL AT ---* gghT

"' RE-22 MONITORS

~ ~ ~ ~ ' " '

VENT l

CONTAINMENT AUX.

PURGE BLDG' CONTAIN-MENT T

EXHAUST Q

PLENUM RE-24'"

MONITOR AUXILIARY BUILDING RE-15 MONITOR TURBINE TURBINE

> BUILDING BUILDING VENT Figure 3-1.

Routine Gaseous Release Sources and Release Points 3-3 Rev. 10 t

l FNP-0-M-011 Gaseous Effluents 3.2 CALCUIATICtJS OF X/Q AND D/Q VALUES The calculations of X/Q and D/Q values are based on the constant wind speed model described in Reg. Guide 1.111, Rev. 0 (March, 1976), and Rev. 1 (July, 1977), sections C.l.c, C.2.a, C.2.b, and C.2.c.

As noted in section 3.1, the plant vent stack is a mixed inode release, and the turbine building vent and ILRT are ground level releases.

A mixed mode release is handled by using portiores of ground and elevated telease values in combination with a

factor, E,

representing the degree of entrainment of the release in the building wake.

If it should happen that the ground and elevated values are in differerit sectors, the doses and activities will be attributed to the proper sector for each of the ground and clevated releases.

Mixed Mode X/Q and D/Q The mixed mode X/O value is obtained from the equation X/O = ((1-E)(X/Q),3,y + E(X/Q),g ]

(3.1) where E = fraction of effluent entrained in the building wake (X/Q),3,y = X/O value for elevated release (X/0),g = X/O for ground level release similarly for D/Q values, the mixed mode D/Q value is obtained from the equation D/0 = [ ( 1-E) ( D/Q),1, y + E(D/Q),,,)

( 3.0 where E = fraction of ef fluent entrained in the building wake (D/Q),1,y - D/0 value for elevated release (D/Q),g = D/Q for ground level release 3-4 Rev. 10

mP-0-M-011 Gaseous Effluents E is determined from the following equations, depending upon the rangeofthevalueof(W/u):

(3.3)

E-1 if (W/u)f1 or h, 5 h, E - 2.58-1.58 (W/u) if 1 < (Wfu) f 1.5 E-0.3-0.06(W/u) if 1.5<(W/u)f5.0 E-0 if (W/u)>5.0 where W, - effluent velocity from the stack b - average wind speed Ground Level X/Q Ground level releases (turbine building vent and ILRT) use the following calculations for X/0, which are taken from Reg. Guide 1.111.

(X/0),,, - 2.032 k,/ (b r I,)

(3.4) 3 where the subscripts jev are for hour j, sector e, and vent v.

I, - ( o', + 0.5h',/n)*'#

(3.5) where Ig is subject to the condition I, f

( 3)*

o,-

(3.6)

The values of o,

are shown in Figure 3-2 for all stability classes.

The parameters used are 3-5 Rev. 10 z____

a

,e,-w e-,

FNP-0-M-011 Gaseous Effluents 2.032 = (2/n)*'8 divided by width of 22.5 degree sector in radians a, = the vertical standard deviation of the plume for the applicable atmospheric stability class (Pasquill category) determined at least hourly, or the distance r, during the time period ot (rigure 3-2) 3 r, = the distance from the midpoint between the vent stacks to the receptor for each sector 0, in meters, provided in

-Table 3-2.

k, = the recirculation factor accounting for spatial and temporal variations in air flow.

For noncontinuous releases, its value is unity.

For continuous releases,-

see rigure 3-3 for correction factor, 0 = the average _ wind speed determined at least hourly, during 3

l time period at in sector e, at a height of 10 meters for ground-level r$ leases, in W sec.

b - the height of the tallest adjacent structure, which is the y

containment building (-40 m).

i i

1 p

3-6 Cen. Rev. 7-l L

g

ne-0-M-011 Gassous Effluents

. -PARLEY NUCLEAR PIN 7T VALUES OF SECTOR DISTMJCES SITE DOUNDARY

!EAREST RECEPTOR SECTOR DISTMJCE DISTMJCE (meters)

(miles)

(meters)

(miles) i N

1290 0.8 4103 2.6 NNE 1450 0.9 4023 2.5 tm 1450 0.9 3862 2.4 ENE 1450 0.9 3862 2.4 E

1290 0.8 4505 2.8 ESE 1290 0.8 4505 2.8 SE 1450 0.9 5471 3.4 SSE 1610 1.0 8045 5.0 S

1610 1.0 6919 4.3 SSW 1610 1.0 4666 2.9 j

1 SW 1450 0.9 1931 1.2 i

WSW 1450 0.9 3862 2.4 W

1290 0.8 2092 1.3 WrM 1290 0.8 3379 2.1 tM 1450 0.9 2414 1.5 NtM 1450

-0.9 3218 2.0' This table may be updated based on annual land census results as required in STS Section 3.12.2.

S Table 3-2. SITE BOUNDARY AND LIMITING FOOD PATHWAY DISTANCES 1

3-7 Gen. Rev. 7 4

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Figure 1. Vertical Standard Deviation of Materialin a Plume (Letten denote Pasquill Stability Class)

I figure 3-2. Vertical Standard Deviation for the Plume (Ref. 3) 3-8 Gen. Rev. 7

Gaseous Effluents TNP-0-M-011 10

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Figure 3-3. Recirculation Factor k0(

39 Gen. Rev. 7

ne-0-M-011 Gaseous Effluents Elevated X/Q The elevated X/Q value is given by:

(

.(X/Q),1,, = (2.032 k,/(0,3,, r, e,)),-[(h,/a,l'/2]

(3.7) where h = effective plume height i

= h, + h,, = h, - c (3.8) c = correction for low relative exit velocity of the plume when W, / L,1,, is less than 1.5.

)

1

-3(1.5-W/u,3,,)d (3.9) d = inside diameter of stack W, - exit velocity of the plume 0,1,, = average elevated wind speed h,, = plume rise h, = height of release point l

h, - terrain height above stack base h,,=1.44d(W/u,1,y)'(r,/d)*

(3.10)-

4 subject to h,( 3(W/u,3,,)d (3.11) p l

l l

3-10 Gen. Rev. 7 l

l l

r.4

FNP-0-M-Oll Gaseous Effleunts h

<1.5(Ffu,1,,)* S-'

if S > 0 (3.12) g where F, = (p,/p) W', (d/2)#

(3.13)

S = (9.0/T) (oT/az + 9.8 x 10)

(3.14) where p, is the ambient air density p is the effluent air density S is the stability parameter with T in degrees K z in meters Since the temperature of the air released is primarily that of the auxiliary building, the value of ( p,/p) will be set to unity.

Ground and Elevated D/Q For ground level releases, the hourly (D/Q)3,y is given by (D/Q)3,, = k, f, 6,,,3 / (0.3927 r,)

(3.15) where j,, = subscripts for hour j, sector 9, and vent v.

f, = 1 if the wind direction is into sector e and is equal to zero otherwise.

0.3927 r, = width (arc length) of 22.5 degree sector at distance r, in meters.

6,y,) = ground level relative deposition rate (linear) at distance r, in sector e for stability class of interest and for ground level 3-11 Gen. Rev. 7

i FNP-0-M-011 Gaseous Effluents

. release in meter-'.

(rigure 3-4) ror elevated releases, (D/Q)3,y is given by

( D/0 ) 3,, - k,, f, 6, y,, / (0.3927 r,)

(3.16) where i

6,y,, - elevated relative deposition rate (linear) at distance r, in sector o for stabilit releaseheighth,inmeter"yclassofinterestand (rigures 3-5, 3-6, and 3-7.)

and all other terms were defined earlier.

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~ Gen. Rev_. 7

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Figure 3-7.

Elevated Relative Deposition - 100 m (Ref. 3) 3-16 Gen. Rev. 7 1

e

RIP-0-M-Oll Gaseous Effluents 3.3 SETPOINTS FOR GASEOUS MONI'IORS 3.3.1 Alarm setpoints for the gaseous monitors R-14, R-15, and R-22 will be calculated based on the more restrictive of the dose rate limits for noble gases for whole body and skin.

These limits are expressed as 500 mrem /yr F,

,E K Q,<

(3.17) i 1

(X/Q), x F where i

subscript numbering noble gases in

=

consideration, and the sum is over all noble gases the total body dose factor due to gamma K

=

1 emissions for identified noble gas isotope 1 (mrem /yr per uti/m ) from Table 3-3.

0, = release rate of isotope i from release point 1

v (uci/sec) 500 = the site dose rate limit in mrem / year v = subscript indicating release point in consideration (turbine building vent or plant vent stack)

F, = release fraction allotted to release point in consideration. The sum of the fractions for the turbine building vent, plant vent stack, and ILRT vent will not exceed 1 for each unit.

(K/Q)y Nighest value of annual average atmospheric

=

dispersion factor at site boundary for all sectors (sec/m').

1.08x10" sec/m' for the plant vent stack (K/Q),

=

(K/Q), = 4.87x10" sec/m' for the turbine building vent F=

unit apportionment factor for compliance with 10CFR20 limits for a multi-unit site.

F=

the number of reactor units that can be operating 3-17 Rev. 10 M-011 Gaseous Effluents simultaneously.

3000 mrem /yr F, I (L + 1.lM,) Q, <

(3.18) 3 i

(X/Q), x F

-j where skin dose factor due to beta emissions for L

1 identjfied noble gas isotope 1 (mrenVyr per uC1/m ) from Table 3-3.

air dose factor due to gamma emissions for M

1 ident uC1/m}fiednoblegasisotope1(mrad /yrper

) from Table 3-3.

The factor of 1.1 mrea/ mrad converts air dose to skin dose (see Ref. 1, page 22).

The actual monitor setpoints will be adjusted for a

-lower (thus more conservative) count rate based on the worst isotope release-dose rate-Q need not be changed, except based on, as follows and reapportioning of allotted release fraction from operating experience as mentioned above. From Tsble 3-3, Kr-891 would be tne most restrictive isotope -in either-the H

total body or skin dose restrictions. Assuming that the total release consists of Kr-89, the whole - body dose equation is more restrictive than the skin dose

equation, and the release rate limit would be calculated as:

500 mrem /yr F, Q, =

(3.19)

(X/Q)y xFxK g This yields:

Q, = 1.39x10' vCi/sec (F,) for the stack, and' Q,

3.09x10' pCi/sec -(F ) - for-the turbine building g

vent.

Based on maximum flow rate and conservative detector-efficiency, the monitor setpoints S, _ (cpm) - may be calculated as follows:

S, = E,,(Q,/F,) + b (3.20) 3 Rev. 10-I' s

n

=

r-s n-e

.s

FNP-0-M-011-Gaseous Effluents.

where b = monitor background count rate (cpm)

E, = gross monitor calibration factor (cpm per uCi/ml)

F, - maximum effluent flow rate (ml/sec)

Setpoint calculations will be made for radiation monitors R-14, R-15, and R-22 on this basis.. '1he limiting release rate Q (uci/ssc) is based on the value satisfying the reIationship 3.17 for total body dose. The setpoint S (cpm) corresponding to this t

release rate may be described as-S = E, (O /F,) + b (3.21) t t

where F, = maximum release flow rate (ml/sec) 3.3.2 R-24, while not a gaseous effluent monitor, monitors an effluent release source to the plant vent stack.

The maximum setpoint for R-24 will be calculated based upon the monitor response curve and the alarm setpoint specified in the Technical Specifications.

S

= (E ) (43) t 3

where S

- maximum monitor alarm setpoint in cpm t

E

-=_ gross monitor calibration factor (cpm per 3

Ci/cc) g,.= maximum setpoint allowed by Technical Specifications in pCi/cc To provide early detection and termination of an abnormally high containment purge release ~, the R-24.

setpoint may be reduced per Section 3.3.1 above.

3.3.3 R-13 monitors the supply to-the waste gas decay tanks from the waste gas compressor. The alarm setpoint-for R-13 is based on expected buildup in the --waste.

. gas system and the Technical. Specification limit for waste gas-storage.

S '= (E ) ( B,,, )

t 3

where:

B,,, = maximum expected buildup of radioactivity-in pC1/cc 3-19 Rev. 8

FNP-0-M-011 Gaseous Effluents Noble Gas Nuclides and Dose Factors Nuclide Ki Li Mi Ni KR-83M 7.56E-02 0.00E+00 1.93E+01 2.88E+02 KR-85M 1.17E+03 1.46E+03 1.23E+03 1.97E+03 KR-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 KR-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 KR-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 KR-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 KR-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 XE-131M 9.15E+01 4.76E+02 1.56E+02 1.11E+03 XE-133M 2.51E+02 9.94E+02 3.27E+02 1.48E+03 XE-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 XE-135M 3.12E+03 7.11E+02 3.36E+03 7.39E+02-XE-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 XE-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 XE-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 AR-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 These dose factors are obtained from Regulatory Guide 1.109 (Octoper,1977),withuCi instead of pC1.

for Ki and Li, and mrad /yr per uci/m, Units are miem/yr per uci/m for Mi and Ni.

Table 3-3.

Dose Factors for Noble Gases and Daughters (Ref. 4) 3-20 Gen. Rev. 7

FNP-0-M-011 Gaseous Effluents 3.4 GASEOUS 10CFR20 COMPLIANCE The dose rate from each unit in unrestricted creas due to radioactive materials released in gaseous effluents from the site shall be limited to the following expressions:

(a) Release rate limit for noble gases:

IK I [ (UQ)y Q,1 < 250 mrem /yr (3.22) 1 i

,E (L + 1.1M ),I [ ( F Q), Q,y] < 1500 mrem /yr (3.23) 1 1

where the terms are defined below.

(b)

Release rate limit for all radioiodines and for all radioactive materials in particulate form and radionuclides (other than noble gases), with half lives greater than 8 days (radiciodines, tritium, and all radionuclides in particulate form with half-lives greater than 8 days):

E I, I, (P, W,y Q,] < 750 mrem /yr (3.24) 1 i

1 where:

I = sum over all radionuclides i

E = sum over all vents v

E - sum over all pathways P

K = the total body dose factor due to gamma emissions for each 1

3 identified radionuclide, in mrervyr per vCi/m (Table 3-3),

3-21 Rev. 10

FNP-0-M-011:

Gaseous Effluents

-L, =. the skin-dose factor due - to beta emissions [or each identified _ radionuclide, in mrenVyr - per uC1/m (Table

,3-3).

M, the air _ dose factor due to gamma emissions (or each identified radionuclide, in mrad /yr per uC1/m (Table 3-3).

P " = the infant age group dose factor for the critical organ i

-for nuclides other than noble gases fgr the inhalation pathway _(in units of mrem /yr per uti/m ) and for ground plane and food pathways (in units of m# (mrem /yr per uCi/sec)). (Table 3-4)

()QQ).

for tritium and the inhalation pathway and =

W

.(D?Q) for other nuclides and pathways.

(300),

the highest value of the annual averag? atmospheric dispersion factor at the site boundary, al The value of 1.08 x 10-{orsec/m}-

sectors, in sec/m.

will be used for the. plant vent and 4.87 x 10-5 sec/m' for the turbine building steam jet air ejector or the ILRT vent.

( 3QQ),,

the highest value of the annual average - atmospheric

=

dispersion factor at the distance of the nearest receptor, or at 5 miles if there is no h

8.03 x 10 9s, for'all sectors,-in sec/' pat way at less than 5 mil The value of sec/m will be used for the plant vent and 8.74 X 10-' sec/m' for the turbine building steam jet air ejector or the ILRT vent.

(D7Q),, _ = the-highest value of the annual - average deposition factor at the distance of the nearest receptor, or at 5 miles if there is_po pathway at less than 5 miles, for all-sectors, in m o, = the average - release rate of nuclide i= in gaseous i

effluent-from each vent _ release point v at the site, in uC1/sec. Noble gases may.be averaged.over a period of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and any other nuclides may be averaged over a period of 1 week.

3-22 Rev. 10

FNP-0-M- 011 Gaseous Effluents 500 - site dose rate limit for whole body in mrenvyear 3000 - site dose rate limit for skin in mrenvyear 1500 - site dose rate limit for any organ in mrenVyear 3-23 Gen. Rev. 7

FNP-0-M-011 Gaseous Effluents Pi VALUES FOR AN INFANT Isotope Inhalation Ground Plane Cow Milk Goat Milk 11 - 3 6.47E+02 0.00E+00 2.38E+03 4.86E+03 P-32 2.03E+06 0.00E+00 1.60E+11 1.92E+11 CR-51 1.28E+04 6.65E+06 4.70E+06 5.64E+05 MN-54 1.00E+06 1.10E+09 3.90E+07 4.68E+06 FE-55 8.69E+04 0.00E+00 1.35E+08 1.76E+06 FE-59 1.02E+06 3.89E+08 3.92E+08 5.10E+06 CO-58 7.77E+05 5.26E+08 6.04E+07 7.26E+06 00-60 4.51E+06 4.40E+09 2.10E+08 2.52E+07 NI-63 3.39E+05 0.00E+00 3.49E+10 4.19E+09 ZN-65 6.47E+05 6.88E+08 1.90E+10 2.28E+09 RB-86 1.90E+05 1.28E+07 2.23E+10 2.67E+09 SR-89 2.03E+06 3.07E+04 1.26E+10 2.64E+10

^

SR-90 4.09E+07 0.00E+00 1.22E+11 2.55E+11 Y-91 2.45E+06 1.51E+06 5.25E+06 6.30E+05 ZR-95 1.75E+06 3.43E+08 8.26E+05 9.91E+04 Na-95 4.79E+05 1.95E+08 2.06E+08 2.48E+07 RU-103 5.52E+05 1.54E+08 1.05E+05 1.27E+04 RU-106 1.16E+07 2.99E+08 1.45E+06 1.73E+05 AG-110M 3.67E+06 3.13E+09 1.46E+10 1.75E+09 TE-125M 4.47E+05 2.19E+06 1.51E+08 1.81E+07 TE-127M 1.31E+06 1.18E+05 1.04E+09 1.24E+08 TE-129M 1.68E+06 2.82E+07 1.39E+09 1.67E+08 I-131 1.48E+07 2.46E+07 1.05E+12 1.26E+12 I-133 3.56E+06 3.50E+06 9.61E+09 1.15E+10 I-135 6.96E+05 3.61E+06 2.00E+07 2.41E+07 CS-134 7.03E+05 2.81E+09 6.80E+10 2.04E+11 CS-136 1.35E+05 2.16E+08 5.81E+09 1.74E+10 CS-137 6.12E+05 1.15E+09 6.02E+10 1.81E+11 BA-140 1.60E+06 2.93E+07 2.41E+08 2.89E+07 CE-141 5.17E+05 1.95E+07 1.37E+07 1.64E+06 CE-144 9.84E+06 5.85E+07 1.33E+08 1.60E+07 PR-143 4.33E+05 0.00E+00 7.84E+05 9.41E+04 ND-147 3.22E'05 1.20E+07 5.74E+05 6.8BE+04 Values are calculated from equatien in ref. 1, with parameters from ref. 4.

Units are mrem /yr per uC1/m' for !!-3 and the inhalation pathway and mrem /yr per uCi/sec per m' for the food and ground plane pathways.

Table 3-4. Infant Dose Factors 3-24 Rev. 10

Fre-0-M-011 l

Gaseous Effluents 3.5 WASTE CAS STORAGE TA!E The radio $ctivity contained in the waste gas decay tanks will be monitored regularly to ensure that it is below the Tech. Spec.

limit of 70,500 Curies per tank.

The storage limit for each tank may be verified by sampling and analysis or by use of R-13.

Sample analysis results for nuclides other than Xe-133 will be converted to an equivalent Xe-133 level by normalizing with the ratio of the MPC value for that nuclide to the MPC value for Xe-133, 3.6 CUMULATIVE DOSE CALCULATIONS Two methods of calculating cumulative doses can be employed.

These are designated " Method A" and " Method B" below.

Method A uses real-time input of hourly averages of meteorological data, and Method B uses highest average value of X/O and D/Q for all releases.

Method B is the

" annual average" method described in NUREG-0133.

Method A or B may be selected at the discretion of the licensee.

3.6.1 Dose Calculations From Noble Gas Releases I.

Method A: Real Time Meteorological Input The air dose in unrestricted areas due to noble gases released in gaseous effluents from each reactor at the site shall be determined by using the following expressions:

During any time period, for gamma radiation:

D,

- 1.14 x 10" E h I, ot, v (X/Q)3,y I

Q (3.25) g i

i 1g During any time period, for beta radiation:

D

- 1.14 x 10" E N I ot E (X/Q),gy Q, (3.26) y i

1 3

3 13 v

where:

1.14 x 10" - 1 / 8760 hours0.101 days 2.433 hours 0.0145 weeks 0.00333 months / year 3-25 Rev. 10

R&-0-N-Oll Gaseous Effluents the to*.al beta air dose in sector e f rom gaseous D

=-

g effluents for the total time period at, in mrad 3

the total gamma air dose in sector 0 from gaseous D

=

g effluents for the total time period at, in mrad, 3

the length of the j" time period over which (X/Q)g,

at

=

3 and Q are averaged for all gaseous releases, in hours.13 For batch releases, no time period at shall be more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; for continuous releases, ho time period at, shall be more than a week.

the air dose factor due to beta emissions {or each N*

identified radionuclide, in mrad /yr per Ci/m (Table 3-3).

the air dose factor due to gamma emissions for each M

1 3

identified radionuclide, in mrad /yr per uCi/m, (Table 3-3).

(X/0)g, = the average atmospheric dispersion factor for the time period at in sactor 9, from gach vent release point at the sile boundary, in sec/m. When at is greater 3

than 1

hour, the average shall be based on observations of wind speed and atmospheric stability taken at least every hour during at.

3 Q, = release rate for nuclide i at hour j for vent v, in 13 uCi/sec.

II.

Method B: Annual Average Meteorological Input The dose contribution due to noble gases in gaseous effluents shall be calculated using the following expressions:

For any time period, for gamma radiation:

D, = 3.17 x 10-

I M I (K/Q), 0, y (3.27) 1 i

y and for beta radiation:

3-26 Rev. 10

~

F!1P-0-M-011 Gaseous Effluents D,

- 3,17 x 10-' [ rg I (X7Q), o (3.28) g v

where:

D, - the total gamma air dose from gaseous effluents, in mrad.

D, - the total beta air dose from gaseous effluents, ir. mrad.

3.17 x 10-' - inverse of number of seconds in a year.

()G'Q), - the highest value of the annual average atmospheric dispersign factor at the site boundary, for all sectors, in sec/m. The value of 1.00 x 10" sec will be used for the plant vent and 4.87 x 10" sec/m[m'for the turbine building steam jet air ejector.

O

- the release of noble gas radionuclides, i, in gaseous n

effluents in uCi for each vent. Releases shall be cumulative over the calendar month or quarter as appropriate.

3.6.2 Dose calculations for radiciodines and radioactive material in particulate form, and radionuclides (other than noble gases) with half lives greater than 8 days (radioic* lines, tritium, and radionuclides in particulate form with half-lives greater than 8 days).

Method A: Real Time Meteorological Input The dose to an individual from radiciodines,

tritium, and radionuclides in particulate form, with half lives greater than 8 days, in gaseous effluents released from each reactor at the site to unrestricted areas (see Figure 5-1) shall be the following expression:

For any time period D

- 1.14 x 10" E E f R

E 6t, v [W,, Q1 g ] (3.29)

E g,

i p

g j

3-27 Rev. 10

, M-Oll Gaseous Effluents where:

1.14 x 10-' = 1/8760 hours / year-D,,, = the cumulative dose from gaseous effluents to the total body or an organ e of an individual in age group a in sector O for the total time period Iot,. in mrem.

3 R

= "he dose factor R for each pathway p for each organ T ip,,

i tor each age group a for nuclide i in spetor 9, in mrenvyr-per uCi/m for tritium and in m -mrenVyr per uCi/sec for other isotopes. The R values for each pathwayareasdefinedinNUREG-Olb3usingthedefault values of Regulatory Guide 1.109, and are given in Table 3-5.

The dose factors are non-zero only-for nuclides with half-lives greater than 8 days.

For sectors with real pathways within 5 miles from the-

-l point midway between the Unit 1 plant vent stack and the Unit 2 plant vent stack, the values of R are used based j

1 on these real pathways.

For sectors with no real l

pathways within 5 miles from the point at midway between the Unit 1 plant vent stack and the Unit 2 plant vent stack, I R is calculated assuming that all pathways exist d the 5-mile distance. Refer to table 3-5, calculated in accordance with NUREG-0133.

f,, = 1 for included pathways, O for excluded.

W,3y - dispersion parameter for calculation of food pathway dose, which is W,3,=((X/Q)Il,_rallpathways.for inhalation pathway and for tritium H-3) o 1

W, p = ( D/Q) 3,, for other isotopes-

- (D/Q),,, - relative deposition _jareal) for the. period ot,, in sector e, in meters 1

l l

i f

3-28 Rev. 10

n@-0-M-Oll Gaseous Cffluents-Maximum exposed individual

-The maximum exposed individual is determined by selecting the age

~

group with the largest single organ dose (reference 7).

If the ground and elevated portions of the mixed mode release are located in separate sectors, the dose obtained - is apportioned between the two.cectors ' using the entrainment factor E.

The ground portion is the fraction E, and the elevated portion is (1-E).

Methed B: Annual Average Methodology Input For any time period, organ doses from radiciodines, tritium, and all radionuclides in particulate form with half-lives greater than 8 days are:

D,, = 3.17 x 10 I I R IW Q,

(3.30) ip,,

y i

ip v

where:

3.17 x 10 = inverse of number of seconds in a year D,

the cumulative dose for age group a and organ To from y

iodines and particulates with half lives greater than 8 days in gaseous effluents, in mrem.

.R,,,

the dose ' factor for each raqionuclide i, pathway p,

=

i organ T, and age. oroup a, in m -(mrem /yr) per uCi/sec or l

mretr/yr per C1/m.

the annual average dispersion parameter for estimating W

=

the dose to' an individual at the~ critical location:

(XX)) s for the inhalation pathway, in sec/m', and for i

tritium in all pathways.

(t9Q) for-the food and ground ~

l

-plane pathways in meters, L-l:

L 3-29 Rev. 10' L

1:

l 1

r--

Gaseous Effluents l

0,,

- the release of radiciodines, tritium, and all radioactive materials in particulate form with half lives greater than 8 days, i, in gaseous effluents for each vent,v.

Releases are cumulative over the time period selected for the report.

The maximum exposed individual is determined by selecting the age group with the largest single organ dose (Reference 7).

k 3-30 Rev. 10

.=

FWP-0-M-011 Gaseous Effluents

)

Patrrsay:- GROUND

_j Nuclide T. Body Skin H-3 0.00E+00 0.00E+00 C-14 0.00E+00 0.00E+00 P-32 0.00E+00 0.00E+00 CR-51 4.66E+06 5.51E+06 MN-54 1.39E+09 1.63E+09 FE-55 0.00E+00 0.00E+00 FE-59 2.73E+08 3.21E+08 CO-58 3.79E+08 4.44E+08 Co-60 2.15E+10 2.53E+10 NI-63 0.00E+00 0.00E+00

q ZN-65 7.47E+08 8.59E+08

-RB-86 8.99E+06 1.03E+07 SR-89 2.16E+04 2.51E+04 SR-90 0.00E+00 0.00E+00 Y-91 1.07E+06 1.21E+06 ZR-95 2.45E+08 2.84E+08 I

NS-95 1.37E+08 1.61E+08 RU-103 1.08E+08 1.26E+08 RU-106 4.22E+08 5.07E+08 AG-110M 3.44E+09 4.01E+09 TE-125M 1.55E+06 2.13E+06 TE-127M 9.17E+04 1.08E+05 l

TE-129M-1.98E+07 2,31E+07 L

I-131 1.72E+07 2.09E+07 I-133 2.45E+06 2.98E+06 I-135 2.53E+06 2.95E+06 CS-134.

6.86E+09 8.00E+09 CS-136 1.51E+08 1.71E+08 i

CS-137 1.03E+10 1.20E+10 BA-140 2.05E+07 2.35E+07 CE-141 1.37E+07 1.54E+07 CE-144 6.96E+07. 8.04E+07 PR-143 0.00E+00 0.00E+00 ND-147 8.39E+06 1.01E+07 Units are m* (mrem /yr) per uCi/sec, except for tritium, in mrem /yr per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-31 Gen. Rev. 7 l

FNP-0-M-011 Gaseous Effluents Pathway:--INHALATION Age Group: ADULT Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 C-14 1.82E+04

3. 41E+ 03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 P-32 1.32E+06 7.71E+04 5.01E404 0.00E+00 0.00E+00 0.00E+00 8.64E+04 CR-51 0.00E+00 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 0.00E+00 3.96E+04 6.30E+03 0.00E+00 9.84E+03 1.40E+06 7.74E+04 FE-55 2.46E+04 1.70E+04 3.94E+03 0.0CE+00 0.00E+00 7.21E+04 6.03E+03 FE-59 1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 CO-58 0.00E+00 1.58E+03 2.07E+03 0.00F no O_00E+00 9.28E+05 1.06E+05 Co-60 0.00E+00 1.15E+04 1.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 NI-63 4.32E+05 3.14E+04 1.45E+04 0.00E+00 0.00E+00 1.78E+05 1.34E+04 ZN-65 3.24E+04 1.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.34E+04 RB-86 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.00E400 0.00E+00 1.66E+04 SR-89 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E4 00 1.40E+06 3.50E+05 SR-90 9.92E+07 0.00E+00 6.10E+06 0.00E+00 0.00E+00 9.60E+06 7.22E+05 Y-91 4.62E+05 0.00E+00 1.24E+04 0.00E+00 0.00E+00 1.70E+06 3.85E+05 ZR-95 1.07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 NB-95 1.41E+04 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.05E+05 1.04E+05 RU-103 1.53E+03 0.00E+00 6.5SE+02 0.00E+00 5.83E+03 5.05E+05 1.10E+05 RU-106 6.91E+04 0.00E+00 8.72E+03 0.00E+00 1.34E+05 9.36E+06 9.12E+05 AG-110M 1.08E+04 1.00E+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 TE-125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 I.14E+05 7.06E+04 TE-127M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 TE-129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 I-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+03 I-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.00E+00 8.88E+03 I-135 2.68E+03 6.98E+03 2.57E+03 4.48E+05 1.11E+04 0.00E+00 5.25E+03 CS-134 3.73E+05 8.46E+05 7.28E+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04-CS-136 3.90E+04 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 CS-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 BA-140 3.90E+04 4.90E+01 2.57E+03 0.00E+00 1.67E+01 1.27E+06 2.18E+05 CE-141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.26E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05 PR-143 9.36E+03 3.75E+03 4.64E+02 0.00E+00 2.16E+03 2.81E+05 2.00E+05 ND-147 5.27E+03 6.10E+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05 Units are m* (mrem /yr) per uCi/sec, except for tritium, in mrem /yr per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-32 Gen. Rev. 7 l

M-011 Gaseous Effluents Pathway: _ INHALATION Age Group: TEEN Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.97E+03 P-32 1.89E+06 1.10E+05 7.16E+04 0.00E+00 0.00E+00 0.00E+00 9.28E+04 CR-51 0.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 MN-54 0.00E+00 5.11E+04 8.40E+03 0.00E+00' 1.27E+04 1.98E+06 6.68E+04 FE-55 3.34E+04 2.38E+04 5.54E+03 0.00E+00 0.00E+00 1.24E+05 6.39E+03 FE-59 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00

1. 53E+06 1.78E+05 Co-58 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 1.34E+06 9.52E+04 00-60 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.72E+06 2.59E+05 NI-63 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00- 8.64E+04 1.24E+06 4.66E+04 RB-86 0.00E+00 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.00E+00 1.77E+04 SR-89 4.34E+05 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 SR-90 1.08E+08 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 Y-91 6.61E+05 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.94E+06 4.09E+05 ZR-95 1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05 NB-95 1.86E+04 1.03E+04 5.66E+03 0.00E+00 1.00E+04 7.51E+05 9.68E+04 RU-103 2.10E+03 0.00E+00 8.96E+02 0.00E+00 7.43E+03 7.83E+05 1.09E+05 RU-106 9.84E+04 0.00E+00 1.24E+04 0.00E+00 1.90E+05.1.61E+07-9.60E+05 AG-110M 1.38E+04 1.31E+04 7.99E+03 0.00E+00 2.50E+04 6.75E+06 2.73E+05 TE-125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.00E+00 5.36E+05 7.50E+04 TE-127M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 TE-129M 1.39E+04 6.58E+03 2,25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 I-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 I-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04-I-135 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 0.00E+00 6.95E+03 CS-134 5.02E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76E+03 CS-136 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04 CS-137 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 BA-140 5.47E+04 6.70E+01 3.52E+03 0.00E+00 2.28E+01 2.03E+06 2.29E+05-CE-141 2.84E+04 1.90E+04 2.17E+03 0.00E+00 8.88E+03 6.14E+05-1.26E+05 CE-144 4.89E+06 2.02E+06 2.62E+05 0.00E+00 1.21E+06 1.34E+07 8.64E+05 PR-143 1.34E+04 5.31E+03 6.62E+02- 0.00E+00 3.09E+03 4.83E+05 2.14E+05 ND-147 7.86E+03 8.56E+03 5.13E+02 0.00E+00 5.02E+03 3.72E+05 1.82E+05 m* (mrem /yr) per uCi/sec, except for tritium, in mrenvyr per Units are uC1/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-33 Gen. Rev. 7

FNP-0-M-011 Gaseous Effluents Pathways ~INHAIATION Age Group: CHILD-Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 P-32 2.60E+06 1.14 E+ 05 9.83E+04 0.00E+00 0.00E+00 0.00E+00 4.22E+04 CR-51 0.00E+00 0.00E+00 1,54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 MN-54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 FE-55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 FE-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.07E+04 00-58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 Co-60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04 NI-63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 ZN-65 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 RB-86 0.00E+00 1.98E+05 1.14E+05 0.00E400 0.00E+00 0.00E+00 7.99E+03 l

SR-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 SR-90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 Y-91 9.14E&05 0.00E+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84E+05 ZR-95 1.90E+05 4.18E+04 3.70E+04 0.00E+00 5.96E+04 2.23E+06. 6.11E+04 NB-95 2.35E+04 9.18E+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70E+04 RU-103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 RU-106 1.36E+05 0.00E+00 1.69E+04 0.00E+00- 1.84E+05 1.43E+07 4.29E+05

-AG-110M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 -5.48E+06 1.00E+05 TE-125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 TE-127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 l

TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00E+00 2.84E+03 I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 I-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05' 1.34E+04 0.00E+00 4.44E+03

-CS-134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 -3.85E+03 CS-136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 CS-137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.59E403 BA-140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05.

CE-141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61E+05 0.00E+00- 1.17E+06 1.20E+07 3.89E+05

[

PR-143-1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 ND-147 1.08E+04-8.73E+03 6.81E+02 0.00E+00 4.81E+03 3.28E+05 8.21E+04-Units are m* (mrem /yr) per uCi/sec, except for tritium, in mrem /yr

-per uci/sec.

l Table 3-5. Dose Factors for Particulates and Iodines 3-34 Gen. Rev. 7 l

l-i i

FNP-0-M-011 Gaseous Effluents Pathway:

INHALATION Age group:

INFMTr Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 C-14 2.65E+04 5.31E+03 5.31E+03 E.31E+03 5.31E+03 5.31E+03 5.31E+03 P-32 2.03E+06 1.12E+05 7.74E+04 0.00E+00 0.00E+00 0.00E+00 1.61E+04 CR-51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN-54 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.98E+03 1.00E+06 7.06E+03 FE-55 1.97E+04 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04 1.09E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 CO-58 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 Co-60 0.00E+00 8.02E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06 3.19E+04 NI-63 3.39E+05 2.04E+04 1.16E+04 0.00E+00 0.00E+00 2.09E+05 2.42E+03

~

ZN-65 1.93E+04 6.26E+04 3.11E+04 0.00E+00 3.25E+04 6.47E+05 5.14E+04 RB-86 0.00E+00 1.90E+05 8.82E+04 0.00E+00 0.00E+00 0.00E+00 3.04E+03 SR-89 3.98E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 SR-90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 Y-91 5.88E+05 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+06 7.03E+04 ZR-95 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 NB-95 1.57E+04 6.43E+03 3.78E+03 0.00E+00 4.72E+03 4.79E+05 1.27E+04 RU-103 2.02E+03 0.00E+00 6.79E+02. 0.00E+00 4.24E+03 5.52E+05 1.61E+04 RU-106 8.68E+04 0.00E+00

1. 09E+ 04 0.00E+00 1.07E+05 1.16E+07 1.64E+05 AG-110M 9.98E+03 7.22E+03 5.00E+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 TE-125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.00E+00 4.47E+05 1.29E+04 TE-127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 TE-129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 I-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00E+00 1.06E+03 I-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 2.16E+03 I-135 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47E+03 0.00E+00 1.83E+03 CS-134 3.96E+05 7.03E+0S 7.45E+04 0.00E+00 -1.90E+05 7.97E+04 1.33E+03 CS-136 4.83E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18E+04 1.43E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 i

BA-140 5.60E+04 5.60E+01 2.90E+03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 -1.99E+03 0.00E+00.5.25E+03 5.17E+05 2.16E+04 CE-144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.38E+05 9.84E+06 1.48E+05 PR-143 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05.3.72E+04 ND-147

.7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03 3.22E+05 3.12E+04 Units are mrem /yr per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines (Continued) 3-35 Gen. Rev. 7

~~

~

l

- - -011 1

Gaseous Effluents Pathways CCW MILK Age Group: ADULT Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02-C-14 2.63E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 P-32 1.71E+10 1.06E+09 6.61E+08 0.00E+00 0.00E+00 0.00E+00 1.92E+09 CR-51 0.00E+00 0.00E+00 2.86E+04 1.71E+04 6.30E+03 3.79E+04 7.19E+06 MN-54 0.00E+00 8.41E+06 1.61E+06 0.00E+00 2.50E+06 0.00E+00 2.58E+07 FE-55 2.51E+07 1.74E+07 4.05E+06 0.00E+00 0.00E+00 9.68E+06 9.95E+06 o

FE-59 2.97E+07 6.98E+07 2.68E+07

0. 00E+ 00 0.00E+00 1.95E+07 2.33E+08 C0-58 0.00E+00 4.71E+06 1.06E+07 0.00E+00 0.00E+00 0.00E+00 9.55E+07 Co-60 0.00E+00 1.64E+07 3.62E+07 0.00E+00 0.00E+00 0.00E+00 3.08E+08 l

NI-63 6.73E+09 4.66E+08 2.26E+08 0.00E+00 0.00E+00 0.00E+00 9.73E+07

~

ZN-65 1.37E+09 4.37E+09 1.97E+09 0.00E+00 2.92E+09 0.00E+00 2.75E+09 RB-86 0.00E+00 2.60E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 5.12E+08 SR-89 1.45E+09 0.00E+00 4.16E+07 0.00E+00 0.00E+00 0.0DE+00 2.33E+08 SR-90 4.68E+10 0.00E+00 1.15E+10 0.00E+00 0.00E+00 0.00E+00 1.35E+09 Y-91 8.59E+03 0.00E+00 2.30E+02 0.00E+00 0.00E+00 0.00E+00 4.73E+06 ZR-95 9.43E+02 3.03E+02 2.05E+02 0.00E+00 4.75E+02 0.00E+00 9.59E+05 NB-95 8.26E+04 4.59E+04 2.47E+04 0.00E+00 4.54E+04 0.00E+00 2.79E+08 RU-103 1.02E+03- 0.00E+00 4.39E+02 0.00E+00 3.89E+03 0.00E+00 1.19E+05 RU-106 2.04E+04 0.00E+00 2.58E+03 0.00E+00 3.94E+04 0.00E+00 1.32E+06 AG-110M 5.82E+07 5.39E+07 3.20E+07 0.00E+00 1.06E+08 0.00E+00 2.20E+10 TE-125M 1.63E+07 5.90E+06 2.18E+06 4.90E+06 6.63E+07 0.00E+00 6.50E+07 TE-127M 4.58E+07 1.64E+07 5.58E+06 1.17E+07 1.86E+08 0.00E4 00 1_ IsE F08 TE-129M 6.02E+07 2.25E+07 9.53E+06 2.07E+07 2.51E+08 0.00E+00 3.03E+08 I-131 2.96E+08 4.24E+08 2.43E+08 1.39E+11 7.26E+08 0.00E+00 1.12E+08 I-133 3.87E+06 6.73E+06 2.05E+06 9.90E+08 1.18E+07 0.0CE+00 6.05E+06 I-135 1.29E+04 3.37E+04 1.24E+04 2.22E+06 5.40E+04 0.00E+00 3.80E+04 CS-134 5.65E+09 1.35E+10 1.10E+10 0.00E+00 -4.35E+09 1.45E+09 2.55E+08 CS-136 2.63E+08 1.04E+09 7.48E+08 0.00E+00 5.78E+08 7.93E+07 1.18E+08 CS-137 7.38E+09 1.01E+10 6.61E+09 0.00E+00 3.43E+09 1.14E+09 1.95E+08 1

BA-140 2.69E+07 3.38E+04 1.76E+06 0.00E+00 1.15E+04 1.93E+04 5.54E+07 CE-141 4.84E+03 3.28E+03 3.72E+02 0.00E+00 1.52E+03 9.00E+00 1.25E+07 CE-144

-3.58E+05 1.50E+05 1.92E+04 0.00E+00 8.87E+04 0.00E+00 1.21E+08 PR-143 1.58E+02 6.33E+01 7.83E+00. 0.00E+00 3.66E+01 0.00E+00 6.92E+05 ND-147 9.42E+01 1.09E+02 6.51E+00 0.00E+00 6.36E+01 0.00E+00 5.22E+0E Units are m* (mrenvyr) per uCi/sec, except for tritium, in mrem /yr per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-36 Gen. Rev. 7

{

~

~ ~OAA Gaseous EEEluents Pathway: COW MILK Age Group: TEEN Nuclide Bone Liver-T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 9.94E+02 9.94E+02 9.94E+02 9.94E+02 9.94E+02 9.94E+02 C-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 P-32 3.16E+10 1.96E+09 1.22E+09 0.00E+00 0.00E+00 0.00E+00 2.65E+09 CR-51 0.00E+00 0.00E+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 MN-54 0.00E+00 1.40E+07 2.78E+06 0.00E+00 4.18E+06 0.00E+00 2.87E+07 FE-55 4.45E+07 3.16E+07 7.36E+06 0.00E+00 0.00E+00 2.00E+07 1.37E+07 FE-59 5.18E+07 1.21E+08 4.67E+07 0.00E+00 0.00E+00 3.81E+07 2.86E+08 00-58 0.00E+00 7.94E+06 1.83E+07 0.00E+00 0.00E+00 0.00E+00 1.09E+08 Co-60 0.00E+00 2.78E+07 6.26E+07 0.00E+00 0.00E+00 0.00E+00 3.62E+08 NI-63 1.18E+10 8.35E+08 4.01E+08 0.00E+00 0.00E+00 0.00E+00 1.33E+08 ZN-65 2.11E+09 7.32E+09 3.41E+09 0.00E+00 4.68E+09 0.00E+00 3.10E+09 RB-86 0.00E+00 4.73E+09.2.22E+09 0.00E+00 0.00E+00 0.00E+00 7.00E+08 SR-89 2.67E+09 0.00E+00 7.66E+07 0.00E+00 0.00E+00 0.00E+00 3.19E+08 SR-90 6.61E+10 0.00E+00 1.63E+10 0.00E+00 0.00E+00 0.00E+00 1.86E+09 1

Y-91 1.58E+04 0.00E+00 4.24E+02 0.00E+00 0.00E+00 0.00E+00 6.48E+06 ZR-95

1. 65E+03 5.21E+02 3.58E+02 0.00E+00 7.65E+02

0. 00 E+00 1.20E+06 I

NB-95 1.41E+05 7.81E+04 4.30E+04 0.00E+00 7.57E+04 0.00E+00 3.34E+08 RU-103 1.81E+03 0.00E+00 7.74E+02 0.00E+00 6.38E+03 0.00E+00 1.51E+05 RU-106 3.75E+04 0.00E+00 4.73E+03 0.00E+00 7.24E+04 0.00E+00 1.80E+06' AG-110M 9.63E+07 9.11E+07 5.54E+07 0.00E+00 1.74E+08 0.00E+00 2.56E+10 TE-125M-3.00E+07 1.08E+07 4.02E+06 8.39E+06 0.00E+00 0.00E+00 8.86E+07 TE-127M 8.44E+07 2.99E+07 1.00E+07 2.01E+07 3.42E+08 0.00E+00 2.10E+08 TE-129M 1.20E+08 4.09E+07 1.74E+07 3.55E+07 4.61E+08 -0.00E+00 4.13E+08 I-131 5.37E+08 7.52E+08 4.04E+08 2.20E+11 1.30E+09 0.00E+00 1.49E+08 I-133 7.07E+06 1.20E+07 3.66E+06 1.67E+09 2.10E+07- 0.00E+00 9.08E+06 I-135 2.28E+04 5.88E+04 2.18E+04 3.78E+06 9.28E+04 0.00E+00 6.51E+04 CS-134 9.82E+09 2.31E+10 1.07E+10. 0.00E+00 7.34E+09 2.80E+09 2.87E+08 CS-136 4.48E+08 1.76E+09 1.18E+09 0.00E+00 9.60E+08 1.51E+08 1.42E+08 CS-137 1.34E+10 1.78E+10 6.20E+09 0.00E+00 6.06E+09 2.35E+09 2.53E+08 BA-140 4.85E+07 5.95E+04 3.13E+06 0.00E+00 2.02E+04 4.00E+04 7.48E+07 CE-141 8.88E+03 5.93E+03 6.81E+02 0.00E+00 2.79E+03 0.00E+00 1.70E+07 CE-144 6.58E+05 2.72E+05 3.54E+04 0.00E+00 1.63E+05.0.00E+00 1.66E+08 PR-143 2.90E+02 1.16E+02 1.44E+01 0.00E+00 6.73E+01 0.00E+00 9.55E+05 ND-147 1.81E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.00E+00 7.11E+05 Units are m'(mrenVyr) per uCi/sec, except for tritium, in mrenVyr per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-37 Gen. Rev. 7

nip-0-M-011 Gaseous Effluents Pathway:_ COW MILK

-Age Group: CHILD Nuclide Bone.

Liver

.T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 C-14 1.19E+09 '2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 -2.39E+08 P-32 7.78E+10 3.64E+09 3.00E+09 0.00E+00 0.00E+00 0.00E+00 2.15E+09 CR-51 0.00E+00 0.00E+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 MN-54 0.00E+00 2.10E+07 5.59E+06 0.00E+00 5.88E+06 0.00E+00 1.76E+07 FE-55 1.12E+08 5.93E+07 1.84E+07 0.00E+00 0.00E+00 3.35E+07 1.10E+07 FE-59 1.20E+08-1.95E+08 9.69E+07 0.00E+00 0.00E+00 5.64E+07 2.03E+08 CO-58 0.00E+00 1.21E+07 3.71E+07 0.00E+00 0.00E+00 0.00E+00 7.07E+07 CO-60 0.00E+00 4.32E+07 1.27E+08 0.00E+00 0.00E+00 0.00E+00 2.39E+08 NI-63 2.96E+10 1.59E+09 1.01E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+08 ZN-65 4.13E+09 1.10E+10 6.85E+09 0.00E+00 6.94E+09 0.00E+00 1.93E+09 RB-86 0.00E+00 8.77E+09 5.39E+09 0.00E+00 0.00E+00 0.00E+00 5.64E+08 SR-89 6.62E+09 0.00E+00 1.89E+08 0.00E+00 0.00E+00 0.00E+00 2.56E+08 SR-90 1.12E+11 0.00E+00 2.83E+10 0.00E+00 0.00E+00 0.00E+00 1.51E+09 Y-91 3.90E+04 0.00Er00 1.04E+03 0.00E+00 0.00E+00 0.00E+00 5.20E+06 ZR-95 3.83E+03 8.42E+02 7.50E+02 0.00E+00 1.21E+03 0.00E+00 8.79E+05 NB-95 3.18E+05 1.24E+05 8.84E+04 0.00E+00 1.16E+05 0.00E+00 '2.29E+08 RU-103 4.28E+03 0.00E+00 1.65E+03 0.00E+00 1.08E+04 0.00E+00 1.11E+05 RU-106 9.24E+04 0.00E+00 1.15E+04 0.00E+00 1.25E+05 '0.00E+00 1.44E+06 AG-110M 2.09E+08 1.41E+08 1.13E+08 0.00E+00 2.63E+08 0.00E+00 1.68E+10 TE-125M 7.38E+07 2.00E+07 9.84E+06 2.07E+07 0.00E+00 0.00E+00 -7.12E+07 TE-127M 2.08E+08 5.60E+07 2.47E+07-4.97E+07 5.93E+08 0.00E+00 1.68E+08 TE-129M 2.71E+08 7.58E+07 4.21E+07 8.75E+07 7.97E+08 0.00E+00 3.31E+08 I-131 1.30E+09 1.31E+09 7.45E+08 4.33E+11 2.15E+09 0.00E+00 1.17E+08 I-133 1.72E+07 2.12E+07 8.04E+06 3.95E+09 3.54E+07 0.00E+00 8.56E+06 I-135 5.41E+04 9.73E+04 4.60E+04 8.62E+06 1.49E+05 0.00E+00 7.41E+04 CS-134 2.26E+10 3.72E+10 7.84E+09 0.00E+00 1.15E+10 4.13E+09 2.00E+08 CS-136 1.01E+09 2.78E+09 1.80E+09 0.00E+00 1.48E+09 2.21E+08 9.77E+07 CS-137 3.22E+10 3.09E+10 -4.55E+09 0.00E+00 1.01E+10 3.62E+09 1.93E+08 BA-140 1.17E+08 1.03E+05-6.84E+06 0.00E+00 3.34E+04 6.12E+04 5.93E+07 CE-141 2.19E+04 1.09E+04 1.62E+03 0.00E+00 4.78E+03 0.00E+00 1.36E+07 CE-144 1.62E+06 5.09E+05 8.66E+04 0.00E+00 2.82E+05 0.00E+00 1.33E+08 PR-143 7.18E+02 2.16E+02 3.56E+01 0.00E+00 1.17E+02 0.00E+00 7.75E+05 ND-147 4.45E+02 3.60E+02 2.79E+01 -0.00E+00 1.98E+02 0.00E+00 5.71E+05 Units are m'(mremryr) per uCi/sec, except for tritium, in mrem /yr per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-38 Gen. Rev. 7 1

FNP-0-M-011 Gaseous Effluents Pathway: COW MILK Age Group:

INFAM' Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 C-14 2.34E+09 5.00E+08 S.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 P-32 1.60E+11 9.43E+09 6.22E+09 0.00E+00 0.00E+00 0.00E+00 2.17E+09 CR-51 0.00E+00 0.00E+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 MN-54 0.00E+00 3.90E+07 8.84E+06 0.00E+00 8.64E+06 0.00E+00 1.43E+07 FE-55 1.35E+08 8.73E+07 2.33E+07 0.00E+00 0.00E+00 4.27E+07 1.11E+07 FE-59 2.24E+08 3.92E+08 1.54E+08 0.00E+00 0.00E+00 1.16E+08 1.87E+08 Co-58 0.00E+00 2.42E+07 6.05E+07 0.00E+00 0.00E+00 0.00E+00 6.04E+07 Co-60 0.00E+00 8.82E+07 2.08E+08 0.00E+00 0.00E+00 0.00E+00 2.10E+08 NI-63 3.49E+10 2.16E+09 1.21E+09 0.00E+00 0.00E+00 0.00E+00 1.07E+08 ZN-65 5.55E+09 1.90E+10 8.78E+09 0.00E+00 9.23E+09 0.00E+00 1.61E+10 RB-86 0.00E+00 2.23E+10 1.10E+10 0.00E+00 0.00E+00 0.00E+00 5.70E+08 SR-89 1.26E+10 0.00E+00 3.61E+08 0.00E+00 0.00E+00 0.00E+00 2.59E+08 SR-90 1.22E+11 0.00E+00 3.10E+10 0.00E+00 0.00E+00 0.00E+00 1.52E+09 Y-91 7.33E+04 0.00E+00 1.95E+03 0.00E+00 0.00E+00 0.00E+00 5.25E+06 ZR-95 6.80E+03 1.66E+03 1.18E+03 0.00E+00 1.79E+03 0.00E+00 8.26E+05 NB-95 5.93E+05 2.44E+05 1.41E+05 0.00E+00 1.75E+05 0.00E+00 2.06E+08 RU-103 8.67E+03 0.00E+00 2.90E+03 0.00E+00 1.80E+04 0.00E+00 1.05E+05 RU-106 1.90E+05 0.00E+00 2.38E+04 0.00E+00 2.25E+05 0.00E+00 1.45E+06 AG-110M 3.86E+08 2.82E+08 1.86E+08 0.00E+00 4.03E+08 0.00E+00 1.46E+10 TE-125M 1.51E+08 5.04E+07 2.04E+07 5.07E+07 0.00E+00 0.00E+00 7.18E+07 TE-127M 4.21E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 0.00E+00 1.70E+08 TE-129M 5.57E+08 1.91E+08 8.58E+07 2.14E+08 1.39E+09 0.00E+00 3.33E+08 I-131 2.72E+09 3.21E+09 1.41E+09 1.05E+12 3.74E+09 0.00E+00 1.14E+08 I-133 3.63E+07 5.28E+07 1.55E+07 9.61E+09 6.21E+07 0.00E+00 8.94E+06 I-135 1.12E+05 2.24E+05 8.15E+04 2.00E+07 2.49E+05 0.00E+00 8.09E+04 CS-134 3.65E+10 6.80E+10 6.87E+09 0.00E+00 1.75E+10 7.18E+09 1.85E+08 CS-136 1.98E+09 5.81E+09 2.17E+09 0.00E+00 2.32E+09 4.74E+08 8.83E+07 CS-137 5.15E+10 6.02E+10 4.27E+09 0.00E+00 1.62E+10 6.55E+09 1.88E+08 BA-140 2.41E+08 2.41E+05 1.24E+07 0.00E+00 5.72E+04 1.48E+05 5.92E+07 CE-141 4.34E+04 2.64E+04 3.11E+03 0.00E+00 8.16E+03 0.00E+00 1.37E+07 CE-144 2.33E+06 9.52E+05 1.30E+05 0.00E+00 3.85E+05 0.00E+00 1.33E+08 PR-143 1.49E+03 5.55E+02 7.36E+01 0.00E+00 2.06E+02 0.00E+00 7.84E+05 ND-147 8.81E+02 9.05E+02 5.55E+01 0.00E+00 3.49E+02 0.00E+00 5.74E+05 Units are m*(mrem /yr) per u(i/sec, except for tritium, in mrem /yr per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-39 Goa. Rev. 7

~

FNP-0-M-011 Gaseous Effluents Pathway GOAT MILK Age Group: ADULT Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 11 - 3 0.00E+00 1.56E+03 1.56E+03 1.56E+03 1,56E+03 1.56E+03 1.56E+03 C-14 2.63E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 P-32 2.05E+10 1.28E+09 7.93E+08 0.00E+00 0.00E+00 0.00E+00 2.31E+09 CR-51 0.00E+00 0.00E+00 3.43E+03 2.05E+03 7.55E+02 4.55E+03 8.62E+05 MN-54 0.00E+00 1.01E+06 1.93E+05 0.00E+00 3.00E+05 0.00E+00 3.09E+06 FE-55 3.26E+05 2.26E+05 5.26E+04 0.00E+00 0.00E+00 1.26E+05 1.29E+05 FE-59 3.86E+05 9.08E+05 3.48E+05 0.00E+00 0.00E+00 2.54E+05 3.03E+06 CO-58 0.00E+00 5.66E+05 1.27E+06 0.00E+00 0.00E+00 0.00E+00 1.15E+07 Co-60 0.00E+00 1.97E+06 4.34E+06 0.00E+00 0.00E+00 0.00E+00 3.70E+07~

NI-63 8.07E+08 5.60E+07 2.71E+07 0.00E+00 0.00E400 0.00E+00 1.17E+07 ZN-65 1.65E+08 5.24E+09 2.37E+08 0.00E+00 3.50E+08 0.00E+00 3.30E+08 RB-86 0.00E+00 3.11E+08 1.45E+08 0.00E+00 0.00E+00 0.00E+00 6.14E+07 SR-89 3.05E+09 0.00E+00 8.75E+07 0.00E+00 0.00E+00 0.00E+00 4.89E+08 SR-90 9.83E+10 0.00E+00 2.41E+10 0.00E+00 0.00E+00 0.00E+00 2.84E+09 Y-91 1.03E+03 0.00E+00 2.76E+01 0.00E+00 0.00E+00 0.00E+00 5.67E+05 ZR-95 1.13E+02 3.63E+01. 2.46E+01 0.00E+00 5.70E+01 0.00E+00 1.15E+05 NB-95 9.91E+03 5.51E+03 2.96E+03 0.00E+00 5.45E+03 0.00E+00 3.34E+07 RU-103 1.22E+02 0.00E+00 5.26E+01 0.00E+00 4.66E+02 0.00E+00 1.43E+04-RU-106 2.45E+03 0.00E+00 3.10E+02 0.00E+00 4.73E+03 0.00E+00 1.58E+05 AG-110M 6.99E+06 6.46E+06 3.84E+06 0.00E+00 1.27E+07 0.00E+00 2.64E+09 TE-125M 1.95E+06 7.08E+05 2.62E+05 5.88E+05 7.95E+06 0.00E+00 7.81E+06 TE-127M 5.49E+06 1.96E+06 6.69E+05 1.40E+06 2.23E+07 0.00E+00 1.84E+07 TE-129M 7.22E+06 2.70E+06 1.14E+06 2.48E+06 3.02E+07 0.00E+00 3.64E+07 I-131 3.55E+08 5.08E+08 2.91E+08 1.67E+11 8.71E+08 0.00E+00 1.34E+08 I-133 4.65E+06 8.08E+06 2.46E+06 1.19E+09 1.41E+07 0.00E+00 7.26E+06 I-135-1.54E+04 4.04E+04 1.49E+04 2.66E+06 6.48E+04 0.00E+00- 4.56E+04 CS-134 1.70E+10 4.04E+10 3.30E+10 0.00E+00 1.31E+10 4.34E+09 7.06E+08 CS-136 7.90E+08 3.12E+09 2.24E+09 0.00E+00 1.74E+09 2.38E+08 3.54E+08 CS-137 2.21E+10 3.03E+10 1.98E+10 0.00E+00 1.03E+10 3.42E+09 5.86E+08 BA-140 3.23E+06 4.05E+03 2.11E+bi 0.00E+00 1.38E+03 2.32E+03 6.64E+06 CE-141

-5.81E+02 3.93E+02 4.46E+01 0.00E+00 1.83E+02 0.00E+00 1.50E+06 l

CE-144 4.29E+04 1.79E+04 2.30E+03 0.00E+00 1.06E+04 0.00E+00 1.45E+07 l

FR-143 1.90E+01 7.60E+00 9.39E-01 0.00E+00 4.39E+00 -0.00E+00 8.30E+04 ND-147 1.13E+01 1.31E+01-7.81E-01 0.00E+00- 7.64E+00- 0.00E+00 6.27E+04 2

Units are m (mrem /yr) per u.1/sec, except for tritium, in mrem /yr per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-40 Gen. Rev. 7 l

ORP-0-M-011 Gaseous Effluents l

Pathways - GOAT MILK Age Groupt TEEN Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 2.03E403 2.03E+03 2.03E+03 2.03E403 2.03E+03 2.03E+03 i

C-14 4.86E+08 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 9.72E+07 l

P-32 3.79E+10 2.35E+09 1.47E+09 0.00E+00 0.00E+00 0.00E+00 3.18E+09 CR-51 0.00E+00 0.00E+00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06 MN-54 0.00E+00 1.68E+06 3.34E+0s 0.00E+00 5.02E+05 0.00E+00 3.45E+06 FE-55 5.79E+05 4.11E+05 9.57E+04 0.00E+00 0.00E+00 2.60E+05 1.78E+05 l

IE-59 6.74E+05 1.57E+06 6 07E+05 0.00E+00 -0.00E+00 4.96E+05 3.72E+06 CO-58 0.00E+00 9.52E+05 2.19E+06 0.00E+00 0.00E+00 0.00E+00 1.31E+07 00-60 0.00E+00 -3.34E+06 7.52E+06 0.00E+00 0.00E+00 0.00E+00 4.35E+07 NI-63 1.42E+09 1.00E+08 4.81E+07 0.00E+00 0.00E+00 0.00E+00 1.59E+07 ZN-65 2.53E+08 8.78E+08 4.10E+08 0.00E+00 5.62E+08 0.00E+00 3.72E+08 RB-86 0.00E+00 5.67E+08 2.67E+08 0.00E+00 0.00E+00 0.00E+00 8.40E+07 SR-89 5.62E+09 0.00E+00 1.61E+08 0.00E+00 0.00E+00 0.00E+00 6.69E+08 SR-90 1.39E+11 0.00E+00 3.43E+10 0.00E+00 0.00E+00 0.00E+00 3.90E+09 r

Y-91 1.90E+03 0.00E+00 5.08E+01 0.00E+00 0.00E+00 0.00E+00 7.77E+05 ZR-95 1.98E+02 6.25E+01 4.30E+01 0.00E+00 9.18E+01 0.00E+00 1.44E+05.

ND-95 1.69E+04 9.37E+03 5.16E+03 0.00E+00 9.08E+03 0.00E+00 4.01E+07 RU-103 2.17E+02 0.00E+00 9.29E+01 0.00E+00 7.66E+02 0.00E+00 1.82E+04 RU-106 4.50E+03 0.00E+00 5.67E+02 0.00E+00 8.68E+03 0.00E+00 2.16E+05 AG-110M 1.16E+07 1.09E+07 6.65E+06 0.00E+00 2.08E+07 0.00E+00 3.07E+0C TE-125M 3.60E+06 1.30E+06 4.82E+05 1.01E+06 0.00E+00 0.00E+00 1.06E+07 TE-127M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.10E+07 0.00E+00 2.52E+07

~

TE-129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.00E+00 4.96E+07 I-131 6.45E+08 9.03E+08 4.85E+08 2.63E+11 1.55E+09 0.00E+00 1.79E+08 I-133 8,49E+06 1.44E+07 4.39E+06 2.01E+09 2.52E+07 0.00E+00 1.09E+07 I-135 2.74E+04 7.05E+04 2.61E+04 4.54E+06 1.11E+05 0.00E+00 7.82E+04 CS-134 2.94E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 8.41E+09 8.62E+08 CS-136 1.34E+09 5.29E+09 3.55E+09 0.00E+00 2.88E+09 4.54E+08 4.26E+08 CS-137 4.02E+10 5.34E+10 1.86E+10 0.00E+00 1.82E+10 7.06E+09 7.60E+08 BA-140 5.82E+06 7.14E+03 3.75E+05- 0.00E+00 2.42E+03 4.80E+03 8.98E+06 CE-141 1.07E+03 7.12E+02 8.18E+01 -0.00E+00 3.35E+02. 0.00E+00 2.04E+06 CE-144 7.90E+04 3.27E+04 4.24E+03 0.00E+00 1.95E+04 0.00E+00 1.99E+07 PR-14?

3.48E+01 1.39E+01 1.73E+00 0.00E+00 8.08E+00 0.00E+00 1.15E+05 i

ND-147 2.17E+01 2.36E+01 1.42E+00 0.00E+00 1.39E+01 0.00E+00 8.53E+04 i

Units are m# (mrenvyr) per uCi/sec, except for tritium, in mrem /yr per uCi/sec.

I Tabl-3-5. Dose Factors for Particulates and Iodines l:

l 3-41 Gen. Rev. 7 l

l l-h.

IUP-0-N-011 Gasec..s Effluents Pathways GOAT MILK Age Groupt CHILD Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 3,20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 3.20E+03 C-14 1.19E+09 2.39E*08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 P-32 9.34E+10 4.37E+09 3.60E+09 0.00E+00 0.00E+00 0.00E+00 2.58E+09 CR-51 0.00E+00 0.00E+00 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.48E+05-MN-54 0.00E+00 2.52E+06 6.70E+05 0.00E+00 7.06E+05 0.00E+00 2.11E+06 TE-55 1.45E+06 7.7:E+05 2.39E+05 0.00E+00 0.00E+00 4.36E+05 1.43E+05 FE-59 1.56E+06 2.53E+06 1.26E+06 0.00E+00 0.00E+00 7.33E+05 2.63E+06 Co-58 0.00E+00 1.45E+06 4.45E406 0.00E+00 0.00E+00 0.00E+00 8.49E+06 00-60 0.00E+00 5.18E+ 06 1.53E+07 0.00E+00 0.00E+00 0.00E+00 2.87E+07-NI-63 3.56E+09 1.90E+08 1.21E+08 0.00E+00 0.00E+00 0.00E+00 1.28E+07 ZN-65 4.96E+08 1.32E+09 8.22E+08 0.00E+00 8.33E+08 0.00E+00 2.32E+08 L

RB-86 0.00E+00 1.05E+09 6.47E+08 0.00E+00 0.00E+00 0.00E+00- 6.77E+07 I

SR-89 1.39E+10 0.00E+00 3.97E+08 0.00E+00 0.00E+00 0.00E+00 5.38E+08-SR-90 2.35E+11 0.00E+00 5.95E+10 0.00E+00 0.00E+00 0.00E+00 3.16E+09 Y-91 4.68E403 0.00E400 1.25E+02 0.00E+00 0.00E+00 0.00E+00 -6.24E+05 ZR-95 4.60E+02 1.01E+02 9.00E+01 0.00E+00 1.45E+02 0.00E+00 1.05E+05 ND-95 3.81E+04 1.49E+04 1.06E+04 0.00E+00 1.40E+04 0.00E+00 2.75E+07 RU-103 5.14E+02 0.00E+00 1.98E+02 0.00E+00 1.29E+03

0. 00E+ 00 1.33E+04 RU-106 1.11E+04 0.00E+00 1.38E+03 0.00E+00 1.50E+04 0.00E+00 1.72E+05 AG-110M 2.51E+07 1.69E+07 1.35E+07 0.00E+00 3.15E+07 0.00E+00 2.01E+09 TE-125M 8.85E+06 2.40E+06 1.18E+06 2.48E+06 0.00E+00 0.00E+00 8.54E+06

{

TE-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 0.00E+00 2.02E+07 TE-129M 3.26E+07

9. 09E+ 06 5.06E+06 1.05E+07 9.56E+07 0.00E+00 3.97E+07 I-131 1.56E+09 1.57E+09 8,94E+08 5.20E+11 2.58E+09 0.00E+00 1.40E+08 I-133 2.06E+07 2.55E+07 9.65E+06 4.74E+09 4.25E+07- 0.00E+00 1.03E+07 :

I-135 6.49E+04 1.17E+05 5.52E+04 1.03E+07 1.79E+05 0.00E+00 8.90E+04 CS-134 6.79E+10 1.11E+11 2.35E+10

0. 00E400 3.45E+10 1.24E+10 6.01E+08 CS-136 3.04E+09 8.34E+09 5.40E+09 0.00E+00 4.44E+09 6.63E+08 2.93E+08 CS-137 9.67E+10 9.26E+10 1.37E+10 0.00E+00 3.02E+10 1.09E+10 5.80E+08 BA-140 1.41E+07 1.23E+04 8.20E+05 0.00E+00 4.01E+03 7.34E+03 7.12E+06-CE-141 2.63E+03 1.31E+03 1.94E+02 0.00E+00 5.74E+02 0.00E+00 1.63E+06 CE-144 1.95E+05 6.11E+04 1.04E+04 0.00E+00 3.38E+04 0.00E+00 1.59E+07 PR-143 8.62E+01 2.59E+01 4.28E+00 0.00E+00 1.40E+01 0.00E+00 9.30E+04 ND-147 5.34E+01 4.32E+01 3.35E+00 0.00E+00 2.37E+01 0.00E+00 6.85E+04 Units are m'(mrenvyr) per uCi/sec, except for tritium, in mrem /yr per uti/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-42 Gen. Rev. 7

FNP-0-M-011 Gaseous Effluents Pathway: GOAT MILK Age group INTNTT Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E400 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 C-14 2.34E409 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.00E408 5.00E+08 P-32 1.92E+11 1.13E+10 7.46E+09 0.00E+00 0.00E+00 0.00E+00 2.60E+09 CR-51 0.00E400 0.00E+00 1.94E+04 1.26E+04 2.76E+03 2.46t+04 5.64E+05 MN-54 0.00E+00 4.68E+06 1.06E+06 0.00E+00 1.04E+06 0.00E+00 1.72E+06 TE-55 1.76E+06 1.13E+06 3.03E+05 0.00E+00 0.00E+00 5.55E+05 1.44E+05 FE-59 2.92E+06 5.10E+06 2.01E+06 0.00E+00 0.00E+00 1.51E+06 2.43E+06 Co-58 0.00E+00 2.91E+06 7.26E+06 0.00E+00 0.00E+00 0.00E+00 7.25E+06 Co-60 0.00E+00 1.06E+07 2.50E+07 0.00E400 0.00E+00 0.00E+00 2.52E+07 NI-63 4.19E+09 2.59E+08 1.45E+08 0.00E+00 0.00E+00 0.00E+00 1.29E+07 ZN-65 6.66E+08 2.28E+09 1.05E409 0.00E+00 1.11E+09 0.00E+00 1.93E+09 RB-86 0.00E+00 2.67E+09 1.32E+09 0.00E+00 0.00E+00 0.00E+00 6.83E+07 SR-89 2.64E+10 0.00E+00 7.58E+08 0.00E+00 0.00E+00 0.00E+00 5.43E+08 SR-90 2.55E+11 0.00E400 6.50E+10 0.00E+00 0.00E400 0.00E+00 3.19E+09

)

Y-91 0.79E+03 0.00E+00 2.34E+02 0.00E+00 0.00E+00 0.00E+00 6.30E+05 2R-95 8.17E+02 1.99E+02 1.41E+02 0.00E+00 2.14E+02 0.00E+00 9.91E+04 NB-95 7.12E+04 2.93E+04 1.70E+04 0.00E+00 2.10E+04 0.00E+00 2.48E+07 RU-103 1.04E+03 0.00E400 3.48E+02 0.00E+00 2.17E+03 0.00E+00 1.27E+04 RU-106 2.28E+04 0.00E+00 2.85E+03 0.00E+00 2.70E+04 0.00E+00 1.73E+05 AG-110M 4.63E+07 3.38E+07 2.24E+07 0.00E+00 4.83E+07 0.00E+00 1.75E+09 TE-125M 1.81E+07 6.05E+06 2.45E+06 6.09E+06 0.00E+00 0.00E400 8.62E+06 TE-127M 5.05E+07 1.68E+07 6.12E+06 1.46E+07 1.24E+08 0.00E+00 2.04E+07 TE-129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.00E+00 3.99E+07 I-131 3.26E+09 3.85E+09 1.69E+09 1.26E+12 4.49E+09 0.00E+00 1.37E+08 I-133 4.35E+07 6.34E+07 1.86E+07 1.15E+10 7.45E+07 0.00E+00 1.07E+07 I-135 1.35E+05 2.68E+05 9.79E+04 2.41E+07 2.99E+05 0.00E+00 9.71E+04 CS-134 1.09E+11 2.04E+11 2.06E+10 0.00E+00 5.25E+10 2,15E+10 5.54E+08 CS-136 5.93E+09 1.74E+10 6.51E+09 0.00E+00 6.95E+09 1.42E+09 2.65E+08 CS-137 1.54E+11 1.81E+11 1.28E+10 0.00E+00 4.85E+10 1.96E+10 5.65E+08 EA-140 2.89E+07 1.89E+04 1.49E+06 0.00E+00 6.87E+03 1.78E+04 7.iOE+06 CE-141 5.20E+03 3.17E+03 3.74E+02 0.00E+00 9.79E+02 0.00E+00 1.64E+06 CE-144 2.79E+05 1.14E+05 1.56E+04 0.00E+00 4.62E+04 0.00E+00 1.60E+07 PR-143 1.78E+02 6.67E+01 8.84E+00 0.00E+00 2.48E+01 0.00E+00 9.41E+04 ND-147 1.06E+02 1.09E+02 6.66E+00 0.00E+00 4.19E+01 0.00E+00 6.88E+04 Units are m'(mrem /yr) per uCi/sec, except for tritium, in mrem /yr per uci/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-43 Gen. Rev. 7

-M-011 Gaseous Effluents Pathways-MEAT Age Group ADULT Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 3.25E+02 3.25E+02 3.25E+02

3. 25E+ 02 3.25E+02 3.25E+02 C-14 2.41E+08 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 P-32 4.66E+09 2.90E+08 1.00E+08 0.00E+00 0.00E+00 0.00E+00 5.24E+08 CR-51 0.00E+00 0 00E+00 7.05E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06 MN-54 0.00E+00 9.18E+06 1.75E+06 0.00E+00 2.73E+06 0.00E+00 2.81E+07 rE-55 2.93E,08 2.03E508 4.72E+07 0.00E+00 0.00E+00 1.13E+08 1.16E+08 FE-59 2.66E+08 6.24E+08 2.39E+08 3.00E+00 0.00E+00 1.74E+08 2.08E+09 C0-58 0.v03^00 1.82E+07 4.09E+07 0.00E+00 0.00E+00 0.00E+00 3.69E+08-Co-60 0.001+00 7.52E+07 1.66E+08 0.00E+00 0.00E+00 0.00E+00 1.41E+09 HI-63 1.89E+10 1.31Es09 6.33E+08 0.00E+00 0.00E+00 0.00E+00 2.73E+08 4

ZN-65 3.56E+08 1.13E+09 5.12E+08 0.00E+00 '7.57E+08 0.00E+00 7.13E+ 08 RB-86 0.00E+00 4.87E+08 2.27E+08 0.00E+00 0.00E+00 0.00E+00 9.61E+07-l SR-89 3.02E+08 0.00E+00 8.66E+06 0.00E+00 0.00E+00 0.00E+00 4.84E+07 SR-90 1.24E+10 0.00E+00 3.05E+09 -0.00E+00 0.00E+00 0.00E+00 3.59E+08 Y-91 1.13E+06 0.00E+00 3.03E+04 0.00E+00 0.00E+00 0.00E+00 6.23E+08 ZR-95 1.87E+06 6.01E+05 4.07E+05 0.00E>00 9.43E+05 0.00E+00 1.90E+09 NB-95 2.30E406 1.28E+06 6.87E+05 0.00E+00 1.26E+06 0.00E+00 7.76E+09 RU-103 1.05E+08 0.00E+00 4.53E+07 0.00E+00 4.02E+08 0.00E+00 1.23E+10 RU-106 2.80E+09 0.00E+00 3.54E+08 0.00E+00 5.40E+09 0.00E+00 1.81E+11 AG-110M 6.68E+06 6.18E'06 3.67E+06 0.00E+00 1.22E+07 0.00E+00 2.52E+09 TE-125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46E+09 0.00E+00 1.43E+09 TE-127M 1.12E+09 3.99E+08 1.36E+08.2.85E+08 4.53E+09 0.00E+00 3.74E+09 TE-129M 1.13E+09 4.23E+08 1.80E+08 3.90E+08 4.73E+09 0.00E+00 5.71E+09 I-131-1.07E+07 1.54E+07-8.81E+06 5.04E+09 2.63E+07 0.00E+00 4.05E+06 I-133 3.67E-01 6.38E-01 1.94E-01 9.37E+01 1.11E+00- 0.00E+00 5.73E-01 t

I-135 4.47E-17 1.17E-16 4.32E-17 7.73E-15.1.88E-16 0.00E+00 1.32E-16 CS-134 6.58E+08 1.56E+09 1.28E+09 0.00E+00 5.06E+08 1.68E+08 -2.74E407 CS-136 1.21E+07 4.76E+07 3.43E+07 0.00E+00 -2.65E+07 3.63E+06 5.41E+06 CS-137 8.72E+08 1.19E+09 7.81E+08 0.00E+00 4.05E+08 1.35E+08 2.31E+07l BA-140 2.87E+07 3.61E+04 1.88E+06 0.00E+00 1.23E+04 2.07E+04 5.92E+07 CE-141 1.40E+04 9.50E+03 1.G8E+03 0.00E+00 4.41E+03- 0.00E+00 3.63E+07 CE-144 1.46E+06 6.09E+05 7.83E+04 0.00E+00 3.61E+05 0.00E+00- 4.93E+08 PR-143 2.10E+04 8.41E+03 1.04E+03 0.00E+00 4.86E+03 0.00E+00 9.19E+07 ND-147 7.07E+03 8.17E+u3 4.89E+02 0.00E+00 4.78E+03 0.00E+00 -3.92E+07 Units are m* (mrenVyr) per uCi/sec, except for tritium, in mrem /yr per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-44 Gen. Rev. 7 w

w f'#-

w md-N v

4E aw't -w hw

'we--F

+T"-v-*'-

w-r'-P-ri-"-Me-ei'-'m

'r

}

FNP-0-M-011 Gaseous Effluents Pathway: MEAT Age Group: TEEN Nuclide Bone Liver T. Body Thyroid Kidney L_unJ GI-LLI H-3 0.00E+00 1.94E+02 1.94E+02 1.94E402 1.94E+02 1.94E+02 1.94E+02 C-14 2.04E+08 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 4.08E+07 P-32 3.94E+09 2.44E+08 1.53E+08 0.00E+00 0.00E+00 0.00E+00 3.31E+08 CR-51 C.00E+00 0.00E+00 5.64E+03 3.13E+03 1.24E+03 8.05E+03 9.47E+05 MN-54 0.00E+00 7.00E+06 1.39E+06 0.00E+00 2.09E+06 -0.00E+00 1.44E+07 FE-55 2.38E+08 1.69E+08 3.94E+07 0.00E+00 0.00E+00 1.07E+08 7.31E+07 FE-59 2.12E+08 4.95E+08 1.91E+08 0.00E+00 0.00E400 1.56E+08 1.17E+09 CO-58 0.00E+00 1.41E+07 3.24E+07- 0.00E+00- 0.00E+00 0.00E+00 1.94E+08 Co-60 0.00E+00 5.83E+07 1.31E+08 0.00E+00 0.00E+00 0.00E+00 7.60E+08 NI-63 1.52E+10 1.07E+09 5.15E+08 0.00E+00 0.00E+00 0.00E+00 1.71E+08 ZN-65 2.50E+08 8.69E+08 4.05E+08 0.00E+00 5.56E+08 0.00E+00 3.68E+08 RB-86 0.00E+00 4.07E+08 1.91E+08 0.00E+00 0.00E+00 0.00E+00 6.02E+07 SR-89 2.55E+08 0.00E+00 7.29E+06 0.00E+00 0.00E+00 0.00E+00 3.03E+07 SR-90 8.05E+09 0.00E+00 1.99E+09 0.00E+00 0.00E+00 0.00E+00 2.26E+08 Y-91 9.54E+05 0.00E+00 2.56E404 0.00E+00 0.00E+10 0.00E+00 3.91E+08 ZR-95 1.50E+06 4.73E+05 3.25E+05 v.00E+00 6.95E+0i 0.00E+00 1.09E+09 NB-95 1.79E+06 9.95E+05 5.48E+05 0.00E+00 9.65E+05 0.00E+00 4.26E+09 i

RU-103 8.57E+07 0.00E+00 3.66E+07 0.00E+00 3.02E+08

. 0'JE+00 7.16E+09 RU-106 2.36E+09 0.00E+00 2.97E+08 0.00E+00 4.55E+09 0.'0E+00 1.13E+11 AG-110M 5.06E+06 4.79E+06 2.91E+06 0.00E+00 9.13E+06 o a1E+00 1.34E+09 TE-125M 3.03E+08 1.09E+08 4.05E+07 8.47E+07' O.00E+00 0 20E+00 8.94E+08 l

TE-127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.82E+09 0.00E+00 2.35E+09 TE-129M 9.50E+08 3.53E+08 1.50E+08 3.07E+08 3.97E+09 0.00E+00.3.57E+09 I-131 8.93E+06 1.25E+07 6.71E+06 3.65E+09 2.1FE+07 0.00E+00 2.47E+06 I-133 3.07E-01 5.20E-01 1.59E-01 7,26E+01 9.12E-01 0.00E+00 3.93E-01 1-135 3.645-17 9.37E-17 3.47E-17 6.03E-15 1.48E-16 0.00E+00 1.04E CS-134 5.23E+08 1.23E+09 5.71E+08 0.00E+00 3.91E+08 1.49E+08 1.53E+07 CS-136 9.40E+06 3.70E+07 2.48E+07 0.00E+00 2.01E+07 3.17E+06 2.98E+06 CS-137 7,24E+08 9.63E+08 3.36E+08 0.00E+00 3.28E+08 1.27E+08 1.37E+07-BA-140 t.38E+07 2.91E+04 1.53E+06 0.00E+00' 9.87E+03 1.96E+04 3.66E+07 CE-141 1.18E+04 7.88E+03 9.05E+02 0.00E+00~ 3.71E+03 0.00E+00 2;25E+07 CE-144 1.23E+06 5.08E+05 6.60E+04 0.00E+00 3.04E+05 0.00E+00 3.09E+08 PR-143 1.76E+04 7.04E+03 8.78E+02- 0.00E+00 4.09E+03 0.00E+00 5.81E+07 ta>-147 6.23E+03-6.78E+03 4.06E+02 0.00E+00 3.98E+03 0.00E+00 2.44E+07 Units 'are m* (mrenvyr) per uCi/sec, except for tritium, in mrem /yr

+

per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines-3-45 Gen. Rev. 7 e

......i..-, - ~,..

~m4~-,-

,e

Gaseous Effluents Pathway - MEAT Age Group: CHILD Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 C-14 3.83E+08 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 P-32 7.43E+09 3.48E+08 2.86E+08 0.00E+00 0.00E+00 0.00E+00 2.05E+08 CR-51 0.00E+00 0.00E+00 8.79E+03 4.88E+03 1.33E+03 8.91E+03 4.66E+05 MN-54 0.00E+00 8.01E+06 2.13E+06 0.00E+00 2.25E+06 0.00E+00 6.72E+06 FE-55 4.57E+08 2.42E+08 7.51E+07 0.00E+00 0.00E+00 1.37E+08 4.49E+07 FE-59 3.76E+08 6.09E+08 3.03E+08 0.00E+00 0.00E+00 1.77E+08 6.34E+08 Co-58 0.00E+00 1.64E+07 5.03E+07 0.00E+00 0.00E+00 0.00E+00 9.58E+07 Co-60 0.00E+00 6.93E+07 2.04E+08 0.00E+00 0.00E+00 0.00E+00 3.84E+08 NI-63 2.91E+10 1.56E+09 9.91E+08 0.00E+00 0.00E+00 0.00E+00 1.05E+08 ZN-65 3.75E+08 1.00E+09 6.22E+08 0.00E+00 6.30E+08 0.00E+00 1.76E+08 RB-86 0.00E+00 5.77E+08 3.55E+08 0.00E+00 0.00E+00 0.00E+00 3.71E+07-SR-89 4.82E+08 0.00E+00 1.38E+07 0.00E+00 0.00E+00 0.00E+00 1.87E+07 SR-90 1.04E+10 0.00E+00 2.64E+09 0.00E+00 -0.00E+00 0.00E+00 1.40E+08 Y-91 1.80E+06 0.00E+00 4.82E+04 0.00E+00 0.00E+00 0.00E+00 2.40E+08 ZR-95 2.66E+06 5.86E+05 5.21E+05 0.00E+00 8.38E+05 0.00E+00 6.11E+08 NB-95 3.10E+06 -1.21E+06 8.62E+05 0.00E+00 1.13E406 0.00E+00 2.23E+09 RU-103 1.55E+08 0.00E+00 5.96E+07 0.00E+00 3.90E+08 0.00E+00. 4.01E+09 RU-106 4.44E+09 0.00E+00 5.54E+08 0.00E+00 5.99E+09 0.00E+00 6.90E+10 AG-110M 8.39E+06 5.67E+06 4.53E+06 0.00E+00 1.06E+07 0.00E+00 6.74E+08 TE-125M 5.69E+08 1.54E+08 7.59E+07 1.60E+08 0.00E+00 0.00E+00 5.49E+08 TE-127M 1.77E+09 4.78E+08 2.11E+08 4.24E+08 5.06E+09 0.00E+00 1.44E+09 TE-129M 1.79E+09 5.00E+08 2.78E+08 5.77E+08 5.26E+09 0.00E+00 2.18E+09 I-131 1.66E+07 1.67E+07 9.46E+06 5.51E+09 2.73E+07 0.00E+00 1.48E+06 I-133 5.70E-01 7.04E-01 2.66E-01 1.31E+02 1.17E+00 0.00E+00 2.84E-01 I-135 6.59E-17 1.19E-16 5.61E-17 1.05E-14 1.82E-16 0.00E+00 9.04E-17 CS-134 9.22E+08 1.51E+09 3.19E+08 0.00E+00 4.69E+08. 68E+08 8.16E+06 CS-136 1.62E+07 4.46E+07 2.89E+07 0.00E+00 2.37E+07 3.54E+06 1.57E+06-CS-137 1.33E+09 1.28E+09 1.88E+08 0.00E+00 4.16E+08 1.50E+08 7.99E+06 BA-140 4.39E+07 3.84E+04 2.56E+06 0.~00E+00 1.25E+04 2.29E+04 2.22E+07 CE-141 2.22E>04 1.11E+04 1.64E+03 0.00E+00 4.86E+03 0.00E+00 1.38E+07 CE-144 2.32E+06 7.26E+05 1.24E+05 0.00E+00 4.02E+05 0.00E+00 1.89E+08 PR-143 3,34E+04 1.00E+04 1.66E+03 0.00E+00 5.43E+03 0.00E+00 3.60E+07 ND-147 1.17E+04 9.47E+03 7.33E+02 0.00E+00 5.20E+03 0.00E+00 1.50E+07 Units are m'(mrem /yr) per uCi/sec, except for tritium, in' mrem /yr per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-46 Gen. Rev. 7 f

-~

i FNP-0-M-011 Gaseous Effluents Pathways -VEGETABLE Age Group: ADULT tuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI j

H-3 0.00E+00 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 2.26E+03 C-14 2.28E+08 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 4.55E+07 P-32 1.41E+09 8.74E+07 5.44E+07 0.00E+00 0.00E+00 0.00E+00 1.58E+08 CR-51 0.00E+00 0.00E+00 4.64E+04 2.78E+04 1.02E+04 6.16E+04 1.17E+07 MN-54 0.00E+00 3.13E+08 5.97E+07 0.00E+00 9.31E+07 0.00E+00 9.59E+08 FE-55 2.10E+08 1.45E+08 3.38E+07 0.00E+00 0.00E+00 8.08E+07 8.31E+07 FE-59 1.26E+08 2.96E+08 1.14E+08 0.00E+00 0.00E+00 8.28E+07 9.88E+08 Co-58 0.00E+00 3.07E+07 6.89E+07 0.00E+00 0.00E+00 0.00E+00 6.23E+08 CO-60 0.00E+00 1.67E+08 3.69E+08 0.00E+00 0.00E+00 0.00E+00 '3.14E+09 NI-63 1.04E+10 7.21E+08 3.49E+08 0.00E+00 0.00E+00 0.00E+00 :1.50E+08 ZN-65 3.17E+08 1.01E+09 4.56E+08 0.00E+00 6.75E+08 0.00E+00 6.36E+08 i

RB-86 0.00E+00 2.19E+08 1.02E+08 0.00E+00 0.00E+00 0.00E+00 14.33E+07 SR-89 9.97E+09 0.00E+00 2.86E+08 0.00E+00 0.00E+00 0.00E+00 1.60E+09 SR-90 6.05E+11 0.00E+00 1.48E+11 0.00E+00 0.00E+00.0.00E+00 1.75E+10 i

Y-91 5.11E+06 0.00E+00 1.37E+05 0.00E+00 0.00E+00 0.00E+00 2.81E+09 2R-95 1.17E+06 3.77E+05 2.55E+05 0.00E+00 5.91E+05 0.00E+00 1.19E+09 NB-95 1.42E+05' 7.92E+04 4.26E+04 0.00E+00 7.83E+04 0.00E+00 4.81E+08 RU-103 4.77E+06 0.00E+00 2.06E+06 0.00E+00 1.82E+07 0.00E+00. 5.57E+08 RU-106 1.93E+08 0.00E+00 2.44E+07 0.00E+00 3.72E+08 0.00E+00 1.25E+10 AG-110M 1.05E+07 9.75E+06 5.79E+06 0.00E+00 1.92E+07 0.00E+00 3.98E+09 TE-125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 0.00E+00 3.86E+08 TE-127M 3.49E+08 1.25E+08 4.26E+07 8.92E+07 1.42E+09 0.00E+00 1.17E+09 TE-129M 2.51E+08 9.38E+07 3.98E+07 8.64E+07 1.05E+09 0.00E+00 1.27E+09 I-131 8.08E+07 1.16E+08 6.62E+07 3.79E+10 1.98E+00 0.00E+00 3.05E+07-I-133 2.09E+06 3.63E+06 1.11E+06 5.33E+08 6.33E+06 0.00E+00 3.26E+06 I-135 3.90E+04 1.02E+05 3.77E+04 6.74E+06 -1.64E+05 0.00E+00 1.15E+05 CS-134 4.67E+09 1.11E+10 9.08E+09 0.00E+00 3.59E+09 1.19E+09 1.94E+08 CS-136 4.27E+07 1.69E+08 1.21E+08 0.00E+00 9.38E+07 1.29E+07.1.91E+07 CS-137

6. 36E+ 09 8.70E+09 5.70E+09 0.00E+00 2.95E+09 9.81E+08 1.68E+08 BA-140 1.29E+08-1.61E+05 8.42E+06 0.00E+00- 5.49E+04 9.24E+04 2~65E+08 CE-141 ~ 1.97E+05 1.33E+05 1.51E+04 0.00E+00 6.19E+04 0.00E+00 5.10E+08 CE-144 3.29E+07 1.38E+07 1.77E+06. 0.00E+00 8.16E+06 0.00E+00.1.11E+10 PR-143 6.26E+04 2.51E+04 3.10E+03 0,00E+00 1.45E+04 0.00E+00 2.74E+08 ND-147 3.33E+04 3.85E+04 2.31E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08 Units are m* (mrem /yr) per uCi/sec, except for tritium, in mrem)yr

~

per uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-47 Gen. Rev. 7 i..

i-

- - ~ ~ - - -

Gaseous Effluents Pathway: VEGETABLE Age Group: TEDJ Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 C-14 3.69E+08 7.38t+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 7.38E+07 P-32 1.61E+09 9.99E+07 6.25E+07 0.00E+00 0.00E+00 0.00E+00 1.35E+08 CR-51 0.03E+00 0.00E+00 6.17E+04 3.43E+04 1.35E+04 8.81E+04 1.04E+07 MN-54 0.00F+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9.32E+08 FE-55 3.26E+08 2.31E+08 5.39E+07 0.00E+00 0.00E+00 1.47E+08 1.00E+08 FE-59 1.79E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9.90E+08 CO-58 0.00E+00 4.36E+07 1.00E+08 0.00E+00 0.00E+00 0.00E+00 6.01E+08 Co-60 0.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 NI-63 1.61E+10 1.13E+09 5-45E408 0.00E+00 0.00E+00 0.00E+00 1.81E+08 ZN-65 4.24E+08 1.47E+09 6.87E+08 0.00E+00 9.42E+08 0.00E+00 6.23E+08 RB-86 0.00E+00 2.74E+08 1.29E+08 0.00E+00 0.00E+00 0.00E+00 4.05E+07 SR-89 1.51E+10 0.00E+00 4.34E+08 0.00E+00 0.00E+00 0.00E+00 1.80E+09 SR-90 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 Y-91 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.21E+09 2R-95 1.72E+06 5.43E+05 3.74E+05 0.00E+00 7.98E+05 0.00E+00 1.25E+09 NB-95 1.92E+05 1.07E+05 5.87E+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 RU-103 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.41E+07 0.00E+00 5.70E+08 RU-106 3.10E+08 0.00E+00 3.90E+07 0.00E+00 5.97E+08 0.00E+00 1.48E+10 AG-110M 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 TE-125M 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.00E+00 4.38E+08 TE-127M 5.52E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 0.00E+00 1.37E+09 TE-129M 3.62E+08 1.34E+08

5. 73 E+ 07 1.17E+08 1.51E+09 0.00E+00 1.36E+09 I-131 7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 I-133 1.94E+06 3.29E+06 1.00E+06 4.59E+08 5.77E+06 0.00E+00 2.49E+06 I-135 3.52E+04 9.07E+04 3.36E+04 5.84E+06 1.43E+05 0.00E+00 1.01E+05 CS-134 7.10E+09 1.67E+10 7.75E+09 0.00E+00 31E+09 2.03E+09 2.08E+08 CS-136 4.38E+07 1.72E+08 1.16E+08 0.00E+00 9.17E+07 1.48E+07 1.39E+07 CS-137 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.E9E+09 1.78E+09 1.92E+08 aA-140 1.38E+08 1.69E+05 8.90E+06 0.00E+00 5.74E+04 1.14E+05 2.13E+08 CE-141 2.83E+05 1.89E+05 2,17E+04 0.00E+00 8.90E+04 0.00E+00 5.41E+08 CE-144 5.27E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.00E+00 1.33E+10 PR-143 7.01E+04 2.80E+04 3.49E+03 0.00E+00 1.63E+04 0.00E+00 2.30E+08 ND-147 3.62E+04 3.94E+04 2.36E+03 0.00E+00 2.31E+04 0.00E+00 1.42E+08 Units are m*(mrem /yr) per uCi/sec, except for tritium, in mrem /yr per uCi/ sac.

Table 3-5. Dose Factors for Particulates and Iodines 3-48 Gen. Rev. 7

.. ~. ---. - - -. - - - - - - - - - - ~. - -. ~.

i FNP-0-M-011 Gaseous Effluent s 4

Pathways _ VEGETABLE Age Group CHILD Nuclide Bone Liver T. Body Thyro _i,d Kidney Lung GI-LLI H-3 0.00E+00 4.01E+03 4.01E+03 4.01E+0? 4.01E+03 4.01E+03 4.01E+03 C-14 8.89E+08 1.78E+08 1.78E+08 1.78E+58 1.78E+08 1.78E+08 1.79E+08 P-32 3.38E409 1.58E+08 1.30E+08 0.00F+00 0.00E+00 0.00E+00 9.33E+07 CR-51 0.00E+00 0.00E+00 1.17E+05 6.50E+04 1.78E+04 1.19E+05 6.21E+06 MN-54 0.00E+00 6.65E+08 1.77E+08 0.00E+00- 1.86E+08 0.00E+00 5.58E+08 FE-55 8.01E+08 4.25E+08 1.32E+08 0.00:300 0.00E+00 2.40E+08 7.87E+07 FE-59 3.93E+08 6.43C+08 3.20E+08 0.00E+00 0.00E+00 1.87E+08 6.70E+08 C0-58 0.00E+00 6.44E+07 1.97E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+08 Co-60 0.00E+00 3.78E+08 1.12E+09 0.00E+00 0.00E+00 0.00E+00 2.10E+09 NI-63 3.95E+10 2.11E+09 1.34E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+08 ZN-65 8.13E+08 2.17E+09 1.35E+09 0.00E+00 1.36E+09 0.00E+00 3.80E+08 RB-86 0.00E+00 4.52E+08 2.78E+08 0.00E+00 0.00E+00 0.00E+00 2.91E+07 SR-89 3.60E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 0.00E+00 1.39E+09 l

SR-90 1.24E+12 0.00E+00 3.15E+11 0.00E+00 0.00E+00 0.00E+00 1.67E+10 Y-91 1.86E+07 0.00E+00 4.99E+05 0.00E+00 0.00E+00 0.00E+00 2.48E+09 ZR-95 3.86E+06 8.48E+05 7.55E+05 0.00E+00 1.21E+06 0.00E+00 8.85E+08 NB-95 4.11E+05 1.60E+05 1.14E+05 0.00E+00 1.50E+05 0.00E+00 2.96E408 RU-103 1.53E+07 0.00E+00 5.90E+06 0.00E+00 3.86E+07 0.00E+00 3.97E+08 RU-106 7.45E+08 0.00E+00 9.30E+07 0.00E+00 1.01E+09 0.00E+00 1.16E+10 1

AG-110M 3.21E+07 2.17E+07 1.73E+07 0.00E+00 4.04E+07- 0.00E+00 2.58E+09 TE-125M 3.51E+08 9.50E+07 4.67E+07 9.84E+07 0.00E+00 0.00E+00 3.38E+08 TE-127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 -3.77E+09 0.00E+00 1.07E+09 TE-129M 8.41E+08 2.35E+08 1.31E+08 2.71E+08 2.47E+09 0.00E+00 1.03E+09 I-131 1.43E+08 1.44E+08 8.17E+07 4.76E+10 2.36E+08 0.00E+00 1.28E+07 I-133 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06- 0.00E+00 1.76E+06 I-135 6.26E+04 1.13E+05 5.33E+04 9.98E+06 1.73E+05 0.00E+00 8.59E+04 CS-134 1.60E+10 2.63E+10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08 CS-136 8.24E+07 2.27E+08 1.47E+08 0.00E+00 1.21E+08 1.80E+07 7.96E+06 4

CS-137 2.39E+10 2.29E+10 3.38E+09 0.00E+00 7.46E+09 2.68E+09 1.43E+08 BA-140 2.77E+08 2.42E+05 1.62E+07 0.00E+00 7.89E+04 1.45E+05 1.40E+08 CE-141 6.56E+05 3.27E+05 4.86E+04 0.00E+00 1.43E+05 0.00E+00 4.08E+08 CE-144 1.27E+08 3.98E+07 6.78E+06 0.00E+00 2.21E+07- 0.00E+00 1.04E+10 PR-143 1.46E+05 4.37E+04 7.23E+03 0.00E+00 - 2.37E+04 0.00E+00 1.57E+08 ND-147 7.15E+04 5.79E+04 4.48E+03 0.00E+00 3.18E+04 0.00E+00 9.17E+07 Units are m* (mrem /yr) per uCi/sec, except for tritium, in mrem /yr-L per_uCi/sec.

Table 3-5. Dose Factors for Particulates and Iodines 3-49 Gen. Rev. 7 e

'1

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=*----------------------------------------------------e..------------------.--------u-

TNP-0-M-011 Gaseous Effluents 1

3.7 COMPOSITE.R4ALYSES ror radionuclides not determined in each batch or weekly composite the dose contribution to the current calendar month or quarter cumulative summation may be approximated by assuming an average monthly or quarterly concentration based on the previous monthly or quarterly composite analyses.

The nuclides determined from 1

composite analyses are H-3, Sr-89, Sr-90, and gross alpha.

3.8 DOSE PROJECTIONS Dose projections shall be made at least once in every 31 days, based on expected operating conditions.

The projected doses from noble gases and from particulates shall be compared to projected dose limits of 0.2 mrad to air for gamma radiation, 0.4 mrad to air for beta radiation, and 0.3 mrem to any organ.

These are monthly dose-limits, o

3-50 Rev. 10 m

. =.

FUP-0-M-Oll l

l Cl! APTER 4 TOTAL DOSE (Dose Assessment for Environmental Radiation Standards)

The Radiological Effluent Technical Specification 3.11.4 specifies in the Action that when the calculated doses associated with the effluent releases exceed twice the limits of ar'y one of the Speci fications 3.11.1.2, 3.11. 2. 2 or 3.11. 2. 3, it is required to prepare and submit a Special Report to the Conv.iission and limit subsequent releases such that the dose or dose commitment to the critical individual from all uranium fuel cycle scutres is limited f

to <25 mrem to the total body or any organ (oxcept the thyroid, which is limited to <75 mrem) over 12 consecutive a.cr.ths.

The dose ar.sessment which will be described in a Special Report, shall include dose contributions f rom threct radiation f rom the plant and its components.

A variety of techniques is available for assessing th.i s contribution.

Is simple calculation may be sufficient to demonstrate that the contribution is unimportant, or conditions may dictate more complex analyses.

Tbc most appropriate assessment tech.ique.:111 he determined in Qe course of preparing the Sptciel Report and il be documented in the t

Special Report.

There are no other uranium fuel cycle sources within a 50 mile radius.

4-1 Gen. Rav. 7

WP-0-M-011 Cl&PTER 5 PADIOLOGICAL DNIRO!MD1TAL !GI'IORI!JG thCATIO!?S Table 5-1 and Figures 5-1, 5-2, and 5-3 provide the Radiological Environmental Monitoring point locations.

5-1 Gen. Rev. 7

rnP-0-M-011 RADICIDGICAL DNIRONMDITAL MCtJTIORI!G IOCATIONS l

EXPOSURE PA71MAY SAMPLI!G LOCATIONS

SAMPLE NJD/OR SAMPLE IDD(I'IFICATION i

1.

AIRDOPJE a.

Particulates Indicator Stations:

4 g River Intake Structure (ESE-0.8 miles)-PI - 0501

' South Perimeter (SSE-1.0 miles)-

PI - 0701 Plant Entrance (WSW-0.9 miles)

PI - 1101 11 orth Perimeter (N-0.8 miles)

PJ - 1601 control Stations:

j Dlakely, GA (NE-15 miles)

PD - 0215 Dothan, AL (W-18 miles)

PD - 1238

' Neals Landing, FL (SSE-18 miles)

PB - 0718 Community Stations:

Great Southern Paper Co. -(SSE-3 miles) PC - 0703 Ashford, AL (WSW-8 miles)

PC - 1108 Columbia, AL (N-5 miles)

PC - 1605 l

b.

Radiciodine Indicator Stations:

' River Intake Structure (ESE-0.8 miles) II - 0501 South Permiter (SSE-1.00 miles)

II - 701 Plant Entrance (WSW-0.9 miles)

II - 1101 North Perimeter (N-0.8 miles)

II - 1601 Control Stations:

Blakely,- GA (TIE-15 miles)

IB - 0215 Dothan, AL'(W-18 miles)

ID - 1218

Neals Landing, FL (SSE-10 miles)

ID - 0718-Community Stations:

' Great Southern Paper Co. (SSE-3 miles) IC - 0703 2.

Direct Radiat$on-Indicator Stations:

Plant Perimeter (NNE-0.9~ miles)

RI - 0101-(NE-1.0 miles)

RI - 0201

- (ENE-0.9 miles)'

RI - 0301-(E-0.8 miles)

(ESE-0.8 miles)-

RI - 0401 RI - 0501 (SE-1.1 miles)

RI - 0501 (SSE-1.0 miles)

RI - 0701 (S-1.0 miles)

RIL- 0801

- (SSW-1.0 miles)

RI - 0901-(SW-0.9 miles)

-RI - 1001

- (WsW-0.9 miles)-

-RI - 1101

Distance as neasured from the centerpoint.between Unit i uand Unit 2 plant-

vent stacks.

Not required by Tech. Spres.. Used as a spare station.~-

Notirequired by Tech.' Specs. Use for comparison purposes with State of GA EPD.

~

Table 5-1. Radiological Environmental Monitoring Locations 5-2 Rev. 10 m

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FNP-0-M-011 RADIOIDGICAL DNIRONME!EAL MotRIORING IDCATIQJS EXPOSURE PATif4AY SNFLItJG !DCATIGJS SAMPLE NJD/OR SAMPLE IDDRIFICATIQ1 (W-0.8 miles)

RI - 1201 (icM-0.8 miles)

RI - 1301 (NW-1.1 miles)

RI - 1401 (NNW-0.9 miles)

RI - 1501 (N-0.8 miles)

RI - 1601 Control Stations:

Blakely, GA, (NE-15 miles)

RB - 0215

!!cals Landing, FL (SSE-18 miles)

RB - 0718 Dothan, AL (W-15 miles)

RB - 1215 Dothan, AL (W-18 miles)

RB - 1218 Webb, AL 00/4-11 miles)

RB - 1311 Haleburg, AL (N-12 miles)

RB - 1612 Community Stations:

(NNE-4 miles)

RC - 0104 (NE-4 miles)

RC - 0204 (ENE-4 miles)

RC - 0304 (E-5 miles)

RC - 0405 (ESE-5 miles)

RC - 0505 (SE-5 miles)

RC - 0605 (SSE-3 ulles)

RC - 0703 (S-5 miles)

RC - 0805 (SSW-4 miles)

RC - 0904 (SW-1.2 miles)

RC - 1001 (SW-5 miles)

RC - 1005 (WSW-4 miles)

RC - 1104 (WSW-8 miles)

RC - 1108 (W-4 miles)

RC - 1204 (WNW-4 miles)

RC - 1304 (NW-4 miles)

RC - 1404 (NNW-4 miles)

RC - 1504 (N-5 miles)

RC - 1605 3.

WATERBORNE Indicator Station:

a.

Surface Great Southern Paper WRI Intake Structure (River Mile-40)

Control Station:

Andrews Lock & Dam Upper Pier (River Mile-47)

WRB b.

Ground Indicator Station:

Great Southern Paper WGI - 07 Co. Well (SSE-4 miles)

Control Station:

Whatley Well (SW-1.2 miles)

WGB - 10 Table 5-1. Radiological Environmental Monitoring Locations (con't) 5-3 Rev. 10

FNP-0-M-011 RADIOLOGICAL EINIRONMDJTAL MOffrIORING LOCATIOtJS EXPOSURL PATIMAY SAMPLItG LOCATIOlJS SNtPLE NJD/OR SAMPLE IDENTIFICATION c.

Sediment Indicator Station:

Smith's Bend (River Mile-41)

RSI Control Station:

Andrews Lock & Dam Reservoir (River Mile-47)

RSB 4.

INGESTICri a.

Milk Indicator Station:

None (There are no milk animals within 5 miles per the current land use survey)

Control Station:

Ray Lewis Dairy Ashford, AL (WSW-14 miles)

MB-1114 b.

Fish Indicator Station:

Smith Bend (River Mile-41)

Game Fish FGI Bottom Feeding Fish FBI Control Station:

Andrews Lock & Dam Reservoir (River Mile-47)

Game Fish FGB Bottom Feeding Fish

- FBB c.

Forage Indicator Stations South Southeast Perimeter (SSE-1.0 miles)- FI - 0701 North Perimeter (N-0.8 miles)

FI - 1601

' South Perimeter (S-1.0 miles)-

FI - 0801 3 Northeast Perimeter (NE-1.0 miles)

FI - 0201 Control-Station:

Dothan, Alabama (W-18 miles)

FB - 1218 3 Alternate forage. plots l

Table 5-1. Radiological Environmental Monitoring' Locations (con't) l-5-4 Rev. 10 a

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IWP-0-M-011 PADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS l

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Water sa::pling Locations for Fa-ley Nuclear Plant 3-7 Rev. 7 n.,

4

rNP-0-M-011 ClaPTER 6 METEOROLOGICAL SLM ERY Tables 6-1 through 6-4 provide a summary of meteorological data for the years 1971 through 1975.

The annual average X/Q and D/Q j

values for the ground level and mixed mode releases are taken from

- 1 this data.

The selection of annual average value for site boundary is made by using the highest value for any sector (see Table _3-2 for site boundary and nearest receptor distances).

The determination of annual average values for nearest receptor is made by comparing.

the X/Q and D/Q values at ' each near receptor, and selecting - the j

highest of these values. Near resident locations are based on the annual land use census.

The nearest receptor is at 1.2 miles in the SW sector, and is the same for the mixed mode and ground level releases.

For the data presented in Tables 6-1 through 6-4, the annual average X/Q and D/Q values are:

. Plant Stack (mixed mode)

Site boundary:

(X?Q), = 1.08 E-6 at SSE, 0.5 - 0.99 mile Nearest receptor (X)Q),, = 8.03 E-7

'D20),y,= 1.05 E-8 Turbine Building and ILRT (ground level)

Site boundary:

(R?Q), - 4.87 E-5 at S, 0.5 - 0.99 mile Nearest receptor:

(R}Q),, = 8.74'E-6 (D?Q),, --2.64 E-8 1 Rev. 10.~

s

--M--

r Ww w

-t-v-m-Ev-m

-m -A--

_?r ww.-e, g+we vg

- - 'er

v-

$r f-P w

a.a-wv w-we r ve e-a n--r w-v-m 6rp-

.-p--w.

.gi7 p.e..y y

~.

w g,,

FNP-0-M-011 Meteorological Summary FARLEY !JUCLEAR PLNTT DISPERSION PAPRIETER X/Q TOR MIXED MODE Distance to the control location, in miles sector 0.25-0.5 0.5-0.99 1.0-1.49 1.5-1.99 2.0-2.49 N

2.16E-06 9.21E-07 5.92E-07 3.83E-07 2.42E-07 tcIE 2.35E-06 1.02E-06 6.18E-07 3.82E-07 2.34E-07 NE 2.23E-06 9.61E-07 6.06E-07 3.86E-07 2.40E-07 FRE 1.12E-06 5.03E-07 3.76E-07 2.65E-07 1.76E-07 E

1.20E-06 5.21E-07 3.57E-07 2.45E-07 1.60E-07 ESE 1.55E-06 6.43E-07 3.83E-07 2.44E-07 1.55E-07 SE 2.47E-06 9.69E-07 5.52E-07 3.47E-07 2.19E-07 SSE 2.77E-06 1.08E-06 6.57E-07 4.34E-07 2.81E-07 S

2.50E-06 9.37E-07 5.90E-07 4.09E-07 2.74E-07 SSW 2.02E-06 8.29E-07 6.30E-07 4.16E-07 2.66E-07 SW 2.05E-06 8.34E-07 8.03E-07 5.07E-07 3.16E-07 WSW 1.89E-06 7.41E-07 7.33E-07 4.66E-07 2.88E-07 W

1.67E-06 6.74E-07 5.81E-07 4.12E-07 2.53E-07 WrM 1.43E-06 5.97E-07 4.11E-07 3.13E-07 2.17E-07 tM 1.32E-06 5.65E-07 3.88E-07 2.68E-07 1.77E-07 tam 1.66E-06 7.21E-07 4.85E-07 3.23E-07 2.07E-07 Note: Values are based on the joint frequency data between 1971 and 1975.

P Table 6-1. X/O Values for the Plant Stack 6-2 Gen. Rev. 7

l F!iP-0-M-011 Meteorological Summary FARLEY !JUCLEAP pud 7T DISPERSIOt1 PAP /44ETER X/O FOR MIXED MODE (Continued)

Distance to the control location, in miles Sector 2.5-2.99 3.0-3.49 3.5-3.99 4.0-4.49 4.5-4.99 ti 1.65E-07 1.24E-07 1.01E-07 9.11E-08 8.27E-08 tRJE 1.55E-07 1.15E-07 9.23E-08 8.28E-08 7.48E-08 ffE 1.61E-07 1.19E-07 9.62E-08 8.63E-08 7.79E-08 Erie 1.22E-07 9.28E-08 7.61E-08 6.88E-08 6.24E-08 E

1.12E-07 8.54E-08 7.09E-08 6.43C-08 5.86E-08 ESE 1.07E-07 8.13E-08 6.75E-08 6.12E-08 5.58E-08 SE 1.51E-07 1.14E-07 9.50E-08 8.61E-08 7.88E-08 SSE 1.96E-07 1.50E-07 1.26E-07 1.15E-07 1.05E-07 S

1.96E-07 1.52E-07 1.29E-07 1.18E-07 1.09E-07 SSW 1.84E-07 1.39E-07 1.22E-07 1.18E-07 1.08E-07 SW 2.13E-07 1.60E-07 1.30E-07 1.27E-07 1.15E-07 WSW 1.92E-07 1.57E-07 1.26E-07 1.13E-07 1.02E-07 W

1.68E-07 1.69E-07 1.34E-07 1.19E-07 1.00E-07 WITA 1.74E-07 1.72E-07 1.35E-07 1.21E-07 1.09E-07 174 1.37E-07 1.24E-07 1.18E-07 1.06E-07 9.60E-08 tcM 1.42C-07 1.07E-07 1.04E-07 9.36E-08 8.50E-08 IJote: Values are based on the joint frequency data between 1971 and 1975.

Table 6-1. X/Q Values for the Plant Stack (Continued) 6-3 Gen. Rev. 7 l

FNP-0-H-011 Meteorological Summary FARLEY !A) CLEAR PIRTT f

DISPERSION PARAMETER XA) I'OR GROG O LEVEL RELEASES Distance to the control location, in miles sector 0.25-0.5 0.5-0.99 1.0-1.49 1.5-1.99 2.0-2.49 N

7.25E-05 2.38E-05 8.63E-06 4.02E-06 2.05E-06 fam 6.16E-05 2.02E-05 7.32E-06 3.39E-06 1.73E-06 NE 5.86E-05 1.94E-05 7.04E-06 3.24E-06 1.65E-06 ENE 5.27E-05 1.74E-05 6.32E-06 2.92E-06 1.49E-06 E

6.28E-05 2.02E-05 7.27E-06 3.40E-06 1.75E-06 ESE 6.18E-05 1.97E-05 7.09E-06 3.33E-06 1.72E-06

-l SE 9.48E-05' 3.01E-05 1.07E-05 5.06E-06 2.63E-06 SS?.

1. 44 E-04 4.55E-05 1.61E-05 7.65E-06 3.99E-06 i

S 1.55E-04 4.87E-05 1.72E-05 8.20E-06 4.28E-06 SSW 9.78E-05 3.12E-05 1.11E-05 5.23E-06 2.71E-06 SW 7.400-05 2.40E-05 8.74E-06 4.05E-06

~2.07E-06 Wsw 6.01E-05 1.97E-05 7.18E 3.31E-06 1.68E-06 W

5.76E-05 1.88E-05 6.79E-06

-3.14E-06 1.60E-06

& chi

-5.55E-05 1.82E-05 6.55E-06 3.03E-06 1.55E-06 NW 5.67E-05 1.86E-05 6.76E-06 3.14E-06 1.60E-06 NNW 6.60E-05 2.16E-05 7.85E-06 3.65E-06 1.87E-06 Note: Values are based on the joint frequency data between 1971 and 1975.

l

- Table 6-2 XA) values for Ground Level Releases 6-4 Gen. Rev. 7 s

W rww et =,w s

- -.s*w+v

=e n-v=-+-

m=w w r a-.

.wa u--

.-- ------------w

rNP-0-M-011 Meteorological Summary rARLEY 10 CLEAR PLAffr DISPERSION PAPAMETER X/Q FOR GROUtm LEVEL RELEASES (Continued)

Distance to the control location, in miles Sector 2.5-2.99 3.0-3.49 3.5-3.99 4.0-4.49 4.5-4.99 N

1.19E-06 8.24E-07 6.09E-07 5.35E-07 4.71E-07 4-tan:

1.00E-06 6.94E-07 5.13E 4.50E-07 3.96E-07 NE 9.47E 6.54E-07 4.82E-07 4.23E-07

-3.71E-07 n a:

8.56E-07 5.92E-07 4.37E 3.82E-07 3.37E-07 E

1.02E-06 7.08E-07 5.24E-07 4.61E-07 4.06E-07 ESE 1.02E-06 6.99E-07 5.18E-07 4.56E-07 4.02E-07 SE 1.54E-06 1.07E-06 7.99E-07 7.04E-07 6.20E-07 SSE 2.34E-06 1.64E-06 1.22E-06 1.08E-06 9.49E-07 s

2.51E-06 1.76E-06 1.31E-06 1.16E-06 1.02E-06 Ssw 1.58E-06 1.10E-06 8.17E-07 7.19E-07 6.33E-07 SW 1.20E-06 8.30E-07 6.12E-07 5.38E-07 4.73E-07 WSW 9.65E-07 6.67E-07 4.91E-07 4.31E-07 3.79E-07 W

9.20E-07 6.37E-07 4.71E-07 4.13E-07 3.63E-07 va&f 8.92E-07 6.18E 4.56E-07 4.01E-07 3.52E-07 NW 9.25E-07 6.41E-07 4.73E-07 4.16E 3.65E-07 ta&4.

1.10E-06 7.50E-07 5.54E-07 4.87E-07

-4.28E-07 Notes'. Values are based on the joint frequency data between 1971 and 1975.

-l Table'6-2. K/Q Values for Ground Level Releases (Continued)-

6-5 Gen. Rev. 7 i

..[ ~

..[

5 - -- -- -

-.. ~ - - - - - - - - - - - - -. - - - - - - - - ~ -

-m_,

i i

mP-0-M-011

-Meteorological Summary FARLEY NUCLEAR PLA!TT-DEPOSITICtf PARAMETER DA) POR MIXED MODE Distance to the control location, in miles Sector 0.25-0.5 0.5-0.99 1.0-1.49 1.5-1.99 2.0-2.49 N

3.82E-08 1.78E-08 7.53E-09 3.39E-09 1.62E-09

!Ptt 4.57E-08 2.08E-08 8.69E-09 3.88E-09 1.85E-09 NE 4.78E-08 2.20E-08 9.08E-09 4.03E-09 1.92E-09 INE 2.67E-08 1.32E-08 5.63E-09 2.54E-09 1.22E-09 E

2.87E-08 1.40E-08 5.77E-09 2.55E-09 1.22E-09 ESE 3.29E-08 1.53E-08 6.17E-09 2.70E-09 1.28E-09 SE 5.30E-08 2.37E-08 9.31E-09 4.01E-09 1.90E-09 SSE 5.07E-08 2.35E-08 9.53E-09 4.19E-09 1.99E-09 S

4.86E-08 2.29E-08 9.16E-09 4.00E 1.90E-09 SSN 4.29E-08 2.10E-08 9.09E-09 3.97E 09 1.88E-09 SW 4.70E-08 2.28E-08 1.05E-08 4.39E-09 2,04E-09 WSW 4.46E-08 2.17E-08 9.88E-09 4.12E-09 1.925-09 l

W 3.96E-08 1.94E-08 8.39E-09 3.63E-09 1.70E-09 MM 3.22E-08 1.56E-08 6.35E 2.85E-09 1.37E-09 tM 2.83E-08 1.35E-08 5.55E-09 2.46E-09 1.18E-09 tRM 3.24E-08 1.55E-08 6.59E-09 2.97E-09 1.42E-09 Note: Values are based on the joint frequency data between 1971 and 1975.

+

h 1

l r

Table 6-3. DA) Values for the Plant Stack 6-6 Cen. Rev. 7 f

~

L l

.2.-

. -2..

- - ~. -. -

~.. -.....

i RfP-0-M-011

- Meteorological Summary FARLEY IEJCLEAR PIRJT DEPOSITIOt1 PARAMETER D/Q FOR MIXED LODE (Continued)

Distance to the control location, in miles Sector 2.5-2,99 3.0-3.49 3.5-3.99 4.0-4.49 4.5-4.99 11 8.71E-10 5.64E-10 3.10E-10 3.37E-10 2.91E-10

!UE 9.91E-10 6.43E-10 4.44E-10 3.82E-10 3.30E-10 tJE 1.03E-09 6.65E-10 4.62E-10 3.98E-10 3.43E-10 E2fE 6.57E-10 4.22E-10 2.96E-10 2.55E-10 2.20E-10 E

6.57E-10 4.20E-10 2.9CE-10 2.55E-10 2.20E-10 ESE 6.88E-10 4.40E-10 3.09E-10 2.66E-10 2.29E-10 SE 1.01E-09 6.48E-10 4.55E-10 3.90E 3.36E -

SSE 1.07E-09 6.85E-10 4.79E-10 4.12E-10 3.55E-10 S

1.02E-09 6.49E-10 4.59E-10 3.94E-10 3.40E-10 SSW 1.00E-09 6.41E-10 4.50E-10 3.86E-10 3.32E-10 SW 1.08E-09 6.90E-10 4.81E-10 4.12E-10 3.53E-10 W5M 1.02E-09 6.51E-10 4.53E-10 3.87E-10 3.32E-10 W

9.00E-10 5.92E-10 4.13E-10 3.54E-10 3.04E-10 WIM 7.33E-10 4.95E-10 3.52E-10 3.05E-10 2.65E-10 tM 6.37E-10 4.11E-10 2.91E-10 2.50E-10 2.14E-10 tcM 7.66E-10 4.95E-10 3.45E-10 2.97E-10 2.56E-10 Notes Values are based on the joint frequency data between 1971 and 1975, e

l Table 6-3. DA) Values for the Plant Stack (Continued) 6-7 Gen.-Rev. 7

_~_'_ - _ _ _'-

z w

r 'a v2.

+

,rr--w--r

--*wt e-e-n,--r-v+vrr-,-w--

we

--+a w

e-

.ev 1x

, - + ~*

e-=

~-s-

-*-e-

--m---

--* - - *e--r

--*-t--!

FNP-0-M-011 Meteorological Summary FARLEY NUCLEAR PLA!TT DEPOSITION PARAMETER DM) FOR GROUND LEVEL PILEASES Distance to the control location, in miles Sector 0.25-0.5 0.5-0.99 1.0-1.49 1.5-1.99 2.0-2.49 N

2.50E-07 7.84E-08 2.53E-08 9.61E-09 4.28E-09.

tam 2.48E-07 7.77E-08 2.51E-08.

9.53E-09 4.24E-09 NE 2.49E-07 7.80E-08 2.52E-08 9.57E-09 4.26E-09 ENE 1.69E-07 5.29E-08 1.71E-08 6.48E-09 2.88E-09 E

1.69E-07 5.28E-08 1.71E-08 6.48E-09 2.88E-09 ESE 1.80E-07 5.54E-08 1.79E-08 6.80E-09 3.02E-09 SE 2.75E-07 8.63E-08 2.79E-08 1.06E-08 4.71E-09 SSE 3.66E-07 1.15E-07 3.71E-08 1.41E-08 6.25E-09 S

3.70E-07 1.16E-07 3.75E-08 1.42E-08 6.33E-09 SSW 2.75E-07 8.62E-08 2.79E-08 1.06E-08 4.70E-09 SN 2.60E-07 8.15E-08 2.64E-08 1.00E-08 4.45E-09 WSW 2.31E-07 7.24E-08 2.34E 8.88E-09 3.95E-09 W

2.11E-07 6.61E-08 2.14E-08 8.11E-09 3.61E-09 vn&f 1.83E-07 5.73E-08 1.85E-08 7.02E-09 3.12E-09 NW 1.74E-07 5.45E-08 1.76E-08 6.68E-09 2.97E-09 ta&f 2.13E-07 6.67E-08 2.16E-08 8.19E-09 3.64E-09 Note: Values are based on the joint frequency data between 1971 and 1975.

l-l I

l-Table 6-4..D/O Values-for Ground Level Releases L

6-8 Gen. Rev. 7 I

_.-..,._-.a___.

.,...,._m.,-

.,,_,.,.m.

__._,__ _ _~U,_,

FNP-0-M-011 Meteorological Summary l

FARLEY MJCLEAR PLANT DEPOSITION PARAMETER D/Q FOR GROUND LEVEL RELEASES (Continued)

Distance to the control location, in ndles Sector 2.5-2.99 3.0-3.49 3.5-3.99 4.0-4.49 4.5-4.99 N

2.22E-09 1.45E-09 9.79E-10 8.27E-10 6.99E-10 NNE 2.20E-09 1.43E-09 9.71E-10 8.20E-10 6.93E-10 NE 2.21E-09 1.44E-09 9.75E-10 8.23E-10 6.96E-10 ENE 1.50E-09 9.76E-10 6.60E-10 5.58E-10 4.72E-10 E

1.50E-09 9.75E-10 5.60E-10 5.57E-10 4.71E-10 ESE 1.57E-09 1.022-09 6.72E-10 5.85E-10 4.94E-10 SE-

.2.44E-09 1.59E-09 1.06E-09 9.11E-10 7.70E-10' SSE 3.25E-09 2.12r-09 1.43E-09 1.21E-09 1.02E-09 S

3.29E-09 2.14E-09 1.45E-09 1.22E-09 1.04E-09 SSW 2.44E-09 1.59E-09 1.08E-09 9.10E-10

~7.69E-10 SW 2.31E-09 1.51E-09 1.02E-09 8.60E-10 7.27E-10 WSN 2.05E-09 1.34E-09 9.04E-10 7.64E-10 6.46E-10 W

1.87E-09 1.22E-09 8.25E-10 6.97E-10

'5.90E-10 1

WNW 1.62E-09 1.06E-09 7.15E-10 6.04E-10 5.11E-10 NW 1.54E-09 1.01E-09 6.80E-10 5.75E-10 4.86E-10 NNW 1.89E-09 1.23E-09 8.34E-10 7.04E-10 5.95E-10 1

Notes values are based on the joint frequency data between 1971 and L

1975.

l Table 6-4. D/Q Values for Ground Level-Releases (Continued)-

6-9 Gen.'Rev. 7

-.- - -.-. L..-.-.-.

i l

mP-0-M-011 l

l i

APPDJDIX ODCM EQUATICXJS AND SOURCES The equation number used in the text is-indicated, along with the equation and an explanation of the origin of the equation. Terms L

and factors are not defined here since they are described in detail in the text.

Equation Origin 2.1 C' ' '

I

$1

\\

i

MPC, This is the - equation that must be satisfied to meet j

l 10CFR20, Appendix B, Table II, Column 2 requirements at l

the discharge point of the site.

2.2 2

I C* * " ' "

f" ' "

C

=I p

u-1 u

This equation is - the derived concentration-- of radionuclide,-i, at the site boundary considering all liquid pathways discharging radioactive water.

2.3 I C,,,,,

f,,,

I P

i F"

f1 1

MPC i

3 l

This is the requirement ' for multiple release pathways I

to meet 10CFR20 concentration limits, i

- A 'Rev. 10 l

L L

1 C

FNP-0-M-011 ODCM Equations and Sourcos Fnuation Origin

'u.p

f

.p 1

u e

7 i

Iu u,p

MPC, This defines the pathway apportionment f actor with the restriction of equation 2.5.

I F

,p Il u

P k

The sum of t'.a apportionment factor shall not exceed one.

Requirement to meet 10CFR20 concentration limits.

2.6 1

C.uv L

7 AF,,,

i

MPC, This is the definition of the mini tm dilution factor required for the pathway to meet "R20 concentration lim-2."

Dr,,,

2

Dm,,,,

This is the definition of the requited dilution factor.

The factor of 2 is the saloty factor.

2.8 2

C, 1

=

- L Dr "'"

AF,,7 i

MPC.

This in the formula used to calculate the minimum required dilution factor.

2.9 Da,,,

- Dry M,,,

=

c C

~

g,,,,

Dr i

g This is the definition of the monitor setpoint in the units of vCi/ml.

2.10 SPC,,, = E,

M,,,, + B

,p y

This is the derived moni;.or setpoint in the units of cpm.

A-2 Rev. 10

ne-0-N-011

-ODCM Equations and Sources

. Equation._-

Origin 2.11 D, - I ( A,,, 1I at C F }-

3 41 3

i This is the definition of the dose to an organ, T,

for each liquid release. Taken f:;om ?UREG-0133, page-15.

2.12 f,,

y F

=

3 F,

5 This is the definition of the near field average dilution factor for each release pathway. Adapted from YJREG-0133, page 16.

2.13 A,,

K,

[U, BF,-+ U Cri y ) DF,,

=

y This is the organ, T, dose commitment factor taken f rom tmREG-0133, page 16 with invertebrate and -drinking water deleted and irrigation-vegetable consumption from Reg. Guide 1.109 adapted from equation A-13.

1

~ (1-e~*

)

f

B' " ( 1-e- * ' d )

e"

2.14-r i

CF

= MaI

+

gy i,

Y (

P A, y

This is the equation that defines the concentration of.

radionuclide, i, in vegetable, v, from the irrigation of crops with. contaminated river water.

Adapted from Reg. Guide 1.109 equation A-8 and A-9.

2.15 CF M

=

y Equation for truium ad/;tei f rom Reg. Guide 1.109 c

equations A-10 and A-9.

3.1 X M = [(1-E)(X/Q),1,y + E(X/Q) g }

This is the algebraic equivalent of Reg. Guide.1.111 (Ref. 3); statement following equation (8):

"... elevated release 100(1-E percent of the time ~and as a ground release E, percenh)of-the. time."-

3.2 This equation is the same as 3;1, but with D/O instead of X/Q.

A-3 Rev. 70 9

A.w

+a m

FNP-0-M-Oll ODCM Equations and Sources Equation Origin 3.3 E=1 if (W/u) f1 o r h, $ h y E-2.58-1.58(Wfu) if 1 < (Wfu)51.5 E-0.3-0.06(Wfu) if 1.5 < (W /u) $ 5.0 E-0 if sWfu)>5.0 The equations for E are taken from Reg. Guide 1.111 equations (6), (7), and (8).

3.4 (X/Q),,, - 2.032 k, / (0, r, I,)

This is Reg. Guide 1.111 equation (3), with h, = 0 for a ground release. Also, in this equation x has become r, the index i is dropped from n, and N and n, are i

taken care of in the sum over j,,, and v.

k is added according to the discussion following eequation (3) in Reg. Guide 1.111 (March, 1976) (Ref. 2) page 1.111-9:

"(1) Sites in open terrain.. multiply by open terrain correction factor (Fig. 2)"

3.5 I, = ( c', + 0. 5h',, / rt ) * ' '

This is Reg. Guide 1.111 equation (9).

3.6 I, 5 ( 3 )i / 2 This is Reg. Guice 1.111 equation (9), second part.

-[ ( h,/, ) 2/2]

3.7 (x/0),1,, - (2.032 k /(b 1,, r, e,)) e o

This is Reg. Guide 1.111 equation (3), with thanges es noted above for equation 3.4, and e instead of I according to the comment in Reg. Guide 1.111 uith th$

definitio.i of E,.

3.8 h, y - h, + h

- h, - c g

This is Reg. Guide 1.111 equation (4).

A-4 Rev. 10

3

' IWP-0-M-011 ODCM Equations-and Sources Equation;.

Origin 3.9 e - 3(1.5

_W 41,3,,)d This is Reg. Guide 1.111 equation (5).

3.10 h,-1.44d.(W/u,3,,)' (r,/d)*

y nis is from Briggs, Plume Rise, (Ref. 5) equation 4.33, page 59.

3.11 h, < 3 (W Mi,3,,)d p

This is from Briggs, Plume Rise, equation 5.2, page 59.

3.12 h, < 1.5 (F,Mi,3,y)* Sif S >

0-'

p This is f rom - Briggs, Plume Rise, equation 4.28, page 59,

!!awever, note in the discussion following '. that -

equation - that since there is no data to support ; the theory, the ">" sign'in the equation shown in Briggs is changed to a *<" sign, using the expression as a upper limit to be conservative.

3.13 r, - (p,/p)

W', (d/2)'

'l This is from Briggs, Plume Rise, equation 4.19b,- page 27.

3.14 S - ( 9.8/r) ( oT/az + 9.8 x 10- 2 )

stability parameter from Briggs, Plume Rise, S

equation 4.16,' pag <a 27.

S - (g/T) (30/0z) 09/8z - BT/82 + 9.8 deg C/Km-

.%is-latter expression is from Meteorology and Atomic Energy (Ref. 6), page' 192, 'in the text following-equation (5.9).

The units in equation 3.14 are az in'm and temperature in deg K.

(9 - 9.8 nVsee squared)

~A-5 Rev.'.10 k

4

l FNP-0-ti-011 ODCM Equations and Sources l

I Equation.

Origin 3.15 (D/Q)3,y -k,f,6,,g (0.3927 to)

This is for ground releases, and is from Reg. Guide 1.111, page 12, in the section on Dry Deposition.

The relative deposition rate (6 is multiplied by the fraction of the release in t$af ) sector (f ) and divided o

by the cross wind distance.

Since the sector is 22.5 degrees wide (0.3927 radians),

the cross wind distance is 0.3927 r, at distance r,,,

k, is as given in equations 3.4 and 3.7.

3.16 (D/0)3,y - k, f, 6,,,,/ (0.3927 r,)

This is for elevated releases, and the development is the same ac for equation 3.14.

500 mrem /yr F, 3.17 I,

K Q,, <

3 (X/Q), xF This is derived from NUREG-0133 equation on page 22 for noble gases, whole body dose.

3000 mrenvyr Fy 3.18 E,

( L, + 1.lti ) 0 t

1y (X/Q), x F This is derived from NUREG-0133 equation on page 22 for noble gases, skin dose.

500 mrem /yr F y

3.19 Q, =

(X/Q), x F x K3 This is derived from equation 3.18, 3.20 S, = E,(Q,/F,) + b This is from a units conversion of Q, in equation 3.19 to cpm, plus background.

A-6 Rev. 10

d FNP-0-M-011 ODCM Equations and Sources Equation

-Origin 3.21 S - E,(O /F,) + b t

t This is equation 3.20 for a specific case.

3.22 I, K I, [(X20), Q1y] < 250 mrenvyr l.

1 This is NUREG-0133 organ dose equation ~ f rom page 22, with V 0, ' and with unit dose rate limit equal to

=

halfodsitelimit.

3.23 I,(Li + 1.1M )

,I ((R70), Q,,1 < 1500 mrenVyr i

i This _ is tMREG-1033 organ - dose equation f rom page 22, with V 0, and with unit dose rate limit equal to e

halfo$sitelimit.

l 3.24 I, I, I, [ P, W Q,) < 750 mrenvyr i

,y i

This is tUREG-0133 organ dose equation from page 22, with W = 0, and with unit dose rate limit equal to half of site 11mit.

Also, it=is summed over all pathways, as indicated in the definition of P.

3 3.25 D,, = 1.14 x 10-* I M at, v (X/0)3,, Q, 3,

I I

i1 3

3.26 D

= 1.14 x 10-

I N, I) 6t I (X/Q)),, D,.

y i

3 13 v

r Equations '3.25 and -3.26 are NUREG-013 page 28, becomes 1.14 x 10-}y values.

3.17 x 10~},1/sec/ year converted to hour 1/hr/ year.

0 and b, = 0.

B

=

3 l.

A-7 Rev. 10

ne-0-M-011

=0DCM Equations and Sources Equation..

Origin 3.27 D, = 3.17 x 10~ ' [ M I (Kt), Q,

1 1

v D, = 3,17 x 10,E N, I (R7Q), O,

3.28 g

y Equations 3.27 and 3.28 are from NUREG-0133, page 28, with B = 0 and b, = 0.

i 3.29 D,,, = 1.14 x 10 I, E

f,R E).6t-E [W,3,D,3,]

p p

ipy, y v I.

This is from NUREG-0133, page 29, with time in hours, and W, - O and w, = 0.

D,, = 3.17 x'10 E I R,p,,

3.30 IW Q, y ip v

This is from txREG-0133, page 29 again, with W, - 0 and

, = 0.

w h

i:

A-8 Rev. 10

. i, 5

- - -

ML20126A194

Text

SUMMARY

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