Text

Rev 10 to Offsite Dose Calculation Manual
	ML20137G363
Person / Time
Site:	Palisades
Issue date:	02/16/1996
From:	Neal T; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML18067A449	List: ML20137G358; ML20137G363; ML20137G387;
References
	PROC-960216, NUDOCS 9704010385
	Download: ML20137G363 (103)
	v • d • e

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I ATTACHMENT 7 l

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Consumers Power Company Palisades Plant t

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t i

i r.

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RADIOACTIVE EFFLUENT RELEASE l

AND WASTE DISPOSAL REPORT l

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OFFSITE DOSE CALCULATION MANUAL t

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OFFSITE DOSE CALCULATION MANUAL APPENDIX A 1

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i 176 Pages l

9704010385 970327""

PDR ADOCK 05000255 R

PDR l

Pr:cedura No ODCM k

4 Ravi:i:n 10 lasued Date 2/19/06 PAllSADES NUCtFAR PLANT I

I OFFSITE DOSE CALCULATION MANUAL l

l TITLE: OFFSITE DOSE CALCULATION MANUAL t J -/4 -f C Procedure Sponsor Date i 2 "fl - 9 &

Technical Reviewer Date

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i User Reviewer Date Rev #

{

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M

[

4cPlant Manag"er Date 4

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PALISADES NUCi FAR PLANT i'

.OFFSITE DOSE CALCULATION MANUAL l

)

Revision 10 Table of Contents 1.

GASEOUS EFFLUENTS.........................

.......1 A.

ALARM / TRIP SETPOINT METHOD 1

1.

Allowable Concer.tir tion............

1 2.

Monitor R== nonne 2

B.

DOSE RATE CALCULATION.......................

3 C.

DESIGN OBJECTIVE QUANTITY (DBQ) LIMITS ON BATCH AND CONTINUOUS RELEASES.................... 20 1.

Batch Releases.................

20 2.

Continuous R:f-----

.............20 3.

Exceeding DBQ Limits............

20 4.

R=8===ino Radionu.,!!das Not Listed in Table 1. 9.....................

21 D.

OPTIONAL QUARTERLY DOSE CALCULATIONS........ 21 1.

Methodoloov for Ontional nn= teriv Dose Calculationg...............21 j

E.

GASEOUS RADWASTE TREATMENT SYSTEM O PERATION.................................

2 4 1.

System Descriotion..............24 2.

Determination of Satisfactory Operation.....................

2 5 F.

RELEASE RATE FOR OFFSITE EC (50 mrem /yr)

........25 i

G.

PARTICULATE AND LODINE SAMPLING

.............26 H.

NOBLE GAS SAMPLING

........................26 1.

TRITIUM SAMPLING...........................

27 J.

F!GURES AND TABLES.........................

28

t PALISADESRU. CLEAR PLANT OFFSITE DOWE CALCULATION MANUAL Revision 10 t

4 Table of Contents il.

LIQUID EFFLUENTS

...................................S4 A.

CONCENTRATION

............................64 1.

Requirements..................64 2.

Prerelease Analysis

..............64 3.

Effluent Conce. nedon (EC) - Sum of the Rados

.......................65 B.

INSTRUMENT SETPOINTS.......................

66 1.

Satpoint Determination............

66 2.

Composite Samplers

.............66 3.

Post-Release Analysis

............67 C.

DOSE.....................................

67 1.

RETS Reauirement...............

67 2.

Release. Analysis................

67 D.

OPERABILITY OF LIQUID RADWASTE EQUIPMENT

.....72 E.

RELEASE RATE FOR OFFSITE EC (50 mrem /yr)........

72 F.

FIGURES AND TABLES.........................

72 lil.

URANIUM FUEL CYCLE DOSE...........................

94 A.

SPECIFICATION..............................

94 B.

ASSUMPTIONS

..............................94 C.

DO S E CALC U LATIO N..........................

9 4 Appendix A, " Relocated Technical Specification" Appendix B, " Request to Retain Soilin Accordance With 10 CFR 20.302"

PALISADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 1.

GASEOUS Er PLUENTS A.

ALARM / TRIP SETPOINT METHOD Appendix A, Section 111.B.1 requires that the dose rate due to radio materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

For noble gases:

Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and For iodine-131, for iodine-133, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days:

Less than or equal to 1500 mrems/yr to any organ.

Appendix A, Section Ill.A.1 requires gaseous effluent monitors to have alarm / trip setpoints to ensure that offsite concentrations, when a over 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , will not be greater than Appendix A, Section 111.B.1. This section of the ODCM describes the methodology that will be used to determine these setpoints.

t The methodology for determining alarm / trip setpoints is divided into two major parts. The first consists of calculating an allowable concentration for the nuci 'e mixture to be released. The second consists of

{

determining monitor response to this mixture in order to establish the physical settings on the monitors.

1.

- AllowmW= Core =.i. i en i

The total EC-fraction (R,) for each release point will be calculated by the relationship defined by Note 4 of Appendix B,10 CFR 20:

X'(F)[,

= s 10.0 C

R

=

g i

(1.1) f 1

o,. c, -

.. o., a m o g

- - ' - ~ ' ~ ^ ~ ~ ~ ~ ~ ' ~ ~

OFFSITE DOSE eALCULATION MANUAL R:visi:n 10 where:

C, Actual or measured concentration, at ambient

=

temperature and pressure of nuclide i ( Ci/cc)

)

EC, The EC of nuclide i from 10 CFR 20, Appendix B,

=

Table 2 = 50 mrem /yr - total body R,

The total EC-fraction for release point k

=

X/O Most conservative sector site boundary dispersion

=

(1.79E-06 sec/m )

8 i

F

=

Release flow rate (83,000 cfm = 39.2 m'/sec) for stack monitor considerations; variable for other monitors NOIE:

If a batch release is made while a continuous release or another batch release is in progress, the sum of all values of Rg must be less than 10.0.

2.

Monitor Resnonsa Normal radioactivity releases consist mainly of well-decayed fission gases. Therefore, monitor response calibrations are performed to

{

fission gas typical of normal releases (mainly Xe-133). Response of monitors used to define fission product release rates under accident conditions may vary from that of Xe-133, however.

Monitor response for the two categories of monitor is determined i

as follows:

l a.

Normal Release (aged fission gasses)

Total gas concentration ( Ci/cc) at the monitor is calculated.

The calibration curve or constant for cpm /pCi/cc) is applied to determine epm expected. The setting for monitor alarms is established at some factor (b) greater than 1 but less than 1/R, (Equation 1.1) times the measured concentration (c):

s=bxc (1.2) 4 1

2

PALISADES NUCLFAR PLANT i

OFFSITE DOSE CALCULATION MANUAL I

Revision 10 i

5 1

b.

Accident Releases

\\

Monitors are preset to alarm at or before precalculated i

i i

offsite dose rates would be achieved under hypothetical accident conditions. These setpoints are established in i

Emergency Action Levels and associated a j

i Emergency implementing Procedures contain monitor-sp i

i i

curves or calibration constants for conversion between cpm l.

and Ci/cc (or R/hr and Ci/cc), depending on monitor type, for fission product mixtures as a function of mixture dec time.

4 When these monitors are utilized for other than a i

i conditions, either an appropriately decayed " accident" i

I i

conversion curve may be used, or a decayed fission gas calibration factor may be applied. In these cases, setpoints -

i i

l are established as in 1.A above.

Setpoints of accident monitors (if set to monitor normal i

releases) are reset to the accident alarm settings at the end 3

of normal release. Setpoints of other release monitors are i

i maintained at'the level used at the latest release (w the level which would allow 10 times EC to be exc 4

I the site boundary), or are reset to approximately three times -

background in order to detect leakage or inadvertent misases of low level gases.

t, B.

DOSE RATE CALCULATION 1.

Dose rates are calculated for (1) noble gases and (2) iodines and particulates. Dose rates as defined in this section are based on j

10 CFR 50 Appendix i limits of mrem per quarter and milliremi year. All dose pathways of major importance in the Palisades I

environs are considered.

Equations and assumptions for calculating doses from noble a.

gases are as follows:

i 1)

Assumotions i

T a)

Doses to be calculated are the maximum offsite point in air, total body and skin.

3 n--u

~*

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL J

Revision 10 4

b)

Exposure pathway is submersion within a cloud j

of noble gases.

c)

Noble gas radionuclide mix is based 'on the 1

historically observed source term given in Table 1.1, plus additional nuclides.

j d)

Basic radionuclide data are given in Table 1.2.

1 l

e)

All releases are treated as ground-level.

1 f)

Meteorological data expressed as l

joint-frequency distribution of wind speed, wind direction, and atmospheric stability for the 3

period resulting in X/Q's and D/Q's shown in Table 1.3.

g)

Raw meteorological data consists of wind speed and direction measurements at 10m and temperature measurements at 10m and 60m.

1 h)

Dose is to be evaluated at the offsite exposure points where maximum concentrations are 4

expected to exist (overland sector site boundaries), and nearest residents.

i i)

Potential maximum population (resident) exposure points are identified in Table 1.4.

j)

A semi-infinite cloud modelis used.

i 4

k)

For person exposures, credit is taken for shielding by residence (factor of 0.7).

l 1)

Radioactive decay is considered for the plume.

m)

Building wake effects on effluent dispersion are considered.

i n)

A sector-average dispersion equation is used.

4 j

i PALISADES NUCLFAR PLANT DFFSITE DOSE CALCULATION MANUAL Revision 10 4

o)

The wind speed classes that are used are as follows:

i Wind Speed Class Number Ranae (m/sl Midooint Im/s) 1 0.0-0.4 0.2 2

0.4-1.5 i

3 0.95 1.5-3.0 i

4 4

2.25 3.0-5.0 5

4.0 5.0-7.5 6

6.25 7.5-10.0 7

8.75

> 10.0 p)

The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A = 1, B = 2,..., G = 7.

q)

Terrain effects are not considered.

2)

Eauntions i

To calculate the dose for any one of the exposure points, the following equations are used.

For determining the air concentration of any i

radionuclide:

i 9

7 rgm Ok Q, p f

X, = { {

Al -[

exp-j=1 k=1

, IT)

[zkU 3 (2rix/n) u;j,

where:

(1.3)

X, Air concentration of radionuclide i, pCi/m.

=

f;g Joint relative frequency of occurrence of

=

winds in wind speed class j, stability class k, blowing toward this exposure point, expressed as a fraction.

5

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 Average release rate of radionuclide 0

=

4 i, Ci/s.

Fraction of radionuclide remaining in p

=

plume.

L Vertical dispersion coefficient for stability

=

class k (m).

Midpoint value of wind speed class "j

=

interval j, m/s.

Downwind distance, m.

x

=

Number of sectors,16.

n

=

A Radioactive decay coefficient of

=

o radionuclide i, s.

Sector width at point of interest, m.

2rix/n

=

For determining the total body dose rate:

D,=

X,

DFB, 7

(1.4) where:

Total body dose rate, mrem /y.

Drs

=

Air concentration of radionuclide I, X,

=

8 Ci/m.

Tratal body dose factor due to gamma

DFB,

=

3 radiation, mrem /y per Ci/m (Table 1.5).

For determining the skin dose rate:

D, =

X, (DFS, + 1.11 DFY,)

(1.5) 6

PAUSADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 i

where:

O, Skin dose rate, mrem /y.

=

4 X

Air concentration of radionuclide i, Ci/m3 i

=

DFS, Skin dose factor due to beta radiation,

=

mrem /y per Ci/m' (Table 1.5).

1.11 The average ratio of tissue to air energy r

absorption coefficients, mrem / mrad.

4

DFY, Gamma-to-air dose factor for

=

radionuclide i, mradly per pCi/m' (Table 1.5),

For determining dose rate to a point in air:

i D, =

X, (DFY, or DFB,)

where:

(1.6)

D.

Air dose rate, mrad /yr

=

DFB, Air dose factor for beta radiation

=

(Table 1.5).

b.

3 Equations and assumptions for calculating doses from radioiodines and particulates are as follows:

1)

Assumotions a)

Dose is to be calculated for the critical organ, thyroid, and the critical age groups (adult, teen, child, infant), infant (milk) and child (green, leafy vegetables).

b)

Exposure pathways from iodines and

)

particolates are milk ingestion, ground contamination, green leafy vegetables from home gardens, and inhalation.

1 7

4

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 i

i c)

The radioiodine and particulate mix is based on i

the historically observed source term given in Table 1.1.

]

d)

Basic radionuclide data are given in Table 1.2.

e)

All releases are treated as ground-level.

f)

Mean annual average X/Q's are given in Table 1.3.

g)

Raw meteorological data for ground-level releases consist of wind speed and direction measurements at 10m and temperature measurements at 10m and 60m.

j h)

Dose is to be evaluated at the potential offsite exposure points where maximum doses to man are expected to exist.

i)

Real cow, goat and garden locations are considered.

j)

Potential maximum exposure points (Table 1.4) considered are the nearest cow, goat, and home garden locations in each sector.

k)

Terrain effects and open terrain recirculation factors are not considered.

j l}

Building wake effects on effluent dispersion are considered.

j m)

Plume depletion and radioactive decay are considered for air-concentration calculations.

n)

Radioactive decay is considered for ground-concentration calculations.

o)

Deposition is calculated based on the curves given in Figure 1.2.

8

PALISADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL

/

,e Revision 10 4

m'M p)

Milk cows and goats obtain 100% of their food 4

from pasture grass May through October of each year. Use default values of 0.58 for cows i

and 0.67 for goats for fraction of year on pasture.

q)

Credit is taken for shielding by residence (factor of 0.7).

2)

Ecuations To calculate the dose for any one of the potential maximum-exposure points, the following equations in Section 1.2.2 are used.

a)

Inhalation Equation for calculating air concentration, X is the same as in the Noble Gas Section i

(Equation 1.3).

For determining the organ dose rate:

D, = 1 x 10' X, DFI, BR where:

(1.7)

D, Organ dose rate due to inhalation,

=

mrem /y.

X Air concentration of radionuclide i, i

=

8 Ci/m.

DFI, Inhalation dose factor, mrem /pCi

=

(Table 1.7).

BR Breathing rate 1400 m /y infant;

=

a 3700 m /y child; or 8000 m /y 3

8 teen and adult.

1x10' pCi/ Ci conversion factor.

=

9

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL l

Revision 10 b)

Ground Contamination For determining the ground concentration of any nuclide; i

7 f, Q, DR G, = 3.15 x 10' [

(2Mn)A, [1 -exp-(A, t,)]

k=1 (1.8) where:

Ground concentration of G,

=

radionuclide i, pCi/m,

j 2

Stability class.

k

=

i Joint relative frequency of f,

=

occurrence of winds in stability class k blowing toward this exposure point, expressed as a fraction.

Average release rate of Q,

=

radionuclide i, Ci/s.

Relative deposition rate, m '

DR

=

(Fig 1.2).

Downwind distance, m.

x

=

Number of sectors,16.

n

=

Sector width at point of 2nx/n

=

interest, m.

Radioactive decay coefficient of A

=

radionuclide i, y-5 Time for buildup of radionuclides t,

.=

on the ground,15 y.

7 s/y conversion factor.

3.15x10

=

10

PALISADES NUCtFAR PLANT _

OFFSITE DOSE CALCULATION MANUAL r

i i

Revision 10 k

l 10-3 Nsun 1.2 conww January 1977 I

f g

'I I

I e

e I e i!

I 1 e

{

l I

l l

I i

l

.k i

l

\\

10-4

\\

-m w

w y

.)

a x

l i

8

\\

i T

=

A

>(

h I

e l 104

\\

s x

E X

X i

2

' \\

5

\\

wa 10 4 9

i l

li i

i 10-7 i

0.1 1A 10.0 100.0 200.0 FLUME TRAVEL DISTANCE (KILOMETERS)

Figure 7. Reistwo Deposition for Ground Level Reisenes (All Atmospheric SteWiity Ctesses) n._

11 i

l PALISADES NUCIFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 i

For determining the total body or organ dose

)

rate from ground contamination:

Do = (8,760)(1 X 10')(0.7)

G,DFG, where:

Dose rate due to ground Da

=

contamination, mrem /y.

Ground concentration of G,

=

2 radionuclide i, Ci/m,

Dose factor for standing on i

DFG,

=

contaminated ground, mrem /h per 2

pCi/m (Table 1.8).

Occupation time, h/y.

8,760

=

pCi/ Ci conversion factor.

1x108

=

Shielding factor accounting for a 0.7

=

distance of 1.0 meter above ordinary ground, dimensionless.

c)

Milk and Veaetation Inaestion For determining the concentration of any nuclide (except C-14 and H-3) in and on vegetation:

f.Q,DR

' r(1 -exp (-\\,t.)]

1 -exp -

xp-M k=1 (2nx/n)

Y, An (1.10)

I where.

Concentration of radionuclide iin CV,

=

and on vegetation, Ci/kg.

Stability class.

k

=

12

- =. ~ _

i PALISADES NUCLFAR PLANT _

OFFSITE DOSE CALCULATION MANUAL 4

Revision 10 -

f Frequency of this stability class i

=

and wind direction combination, expressed as a fraction.

Q Average release rate of i

=

radionuclide i, pCi/s.

DR Relative deposition rate, m '

=

(Figure 1.2).

x

=

Downwind distance, m.

n

=

Number of sectors,16.

2nx/n Sector width at point of

=

interest, m.

r

=

Fraction of deposited activity retained on vegetation (1.0 for iodines,0.2 for particulates).

AEi Effective removal rate constant,

=

AEi = A + A., where A is the radioactive decay coefficient, h,

and A,is a measure of physical loss by weathering (A, = 0.0021 h').

t, Period over which deposition

=

occurs, 720 h.

Y,

\\

Agricultural yield, 0.7 kg/m,

=

2 l

i B,,

Transfer factor from soil to

=

vegetation of radionuclide i (Table 1.6).

A Radioactive decay coefficient of

=

radionuclide i, h.

t, Time for buildup of radionuclides

=

on the ground,1.31x105 h (15Y).

13

PALISADES NUC1FAR PLANT QEfSITE DOSE CALCULATION MANUAL Revision 10 Effective surface density of soil,

)

p

=

2 240 kg/m,

3,600 s/h conversion factor.

=

Holdup time between harvest and tn

=

consumption of food (2,160 hours0.00185 days 0.0444 hours 2.645503e-4 weeks 6.088e-5 months for stored food).

For determining the concentration of C-14 in vegetation:

CV,, = 1 x 10" X,, (0.11/0.16)

(1.11)

- where:

CV,4 Concentration of C-14 in

=

vegetation, Ci/kg.

X,,

Air concentration of C-14, Ci/m,

a

=

0.11 Fraction of total Plant mass that is

=

natural carbon.

0.16 Concentration of natural carbon in

=

the atmosphere, g/m'.

1x108 g/kg conversion factor.

=

For determining the concentration of H-3 in vegetation:

8 CV = 1 x 10 XT (0.75)(0.5/H) 7 (1.12) where:

CVy Concentration of H-3 in vegetation,

=

Ci/m'.

Xr Air concentration of H-3, Ci/m'.

=

0.75 Fraction of total Plant mass that is

=

v ater.

14

PALISADES NUCLFAR PLANT OFFSITE_ DOSE CALCULATION MANUAL 1

Revision 10 0.5 Ratio of tritium concentration in

=

Plant water to tritium concentration in atmospheric water.

H Absolute humidity of the

=

atmosphere, g/m.

1x10' g/kg conversion factor.

=

For determining the concentration of any nuclide in cow's or goat's milk:

CM, = CV, FM, Q, exp ( A, t,)

(1.13) j where:

CM, Concentration of radionuclide i

=

(including C-14 and H-3) in milk, pCill.

CV Concentration of radionuclide i in i

=

and on vegetation, Ci/kg.

FM, Transfer factor from feed to milk

=

for radionuclide i, d/t (Table 1.6).

O, Amount of feed consumed by the

=

milk animal per day, kg/d (cow.

50 kg/d or goat 6 kg/d).

Ai Radioactive decay coefficient of

=

radionuclide i, d4 t,

Transport time of activity from

=

feed to milk to receptor, 2 days.

15

PALISADES NUCI FAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 For determining the organ dose rate from ingestion of green leafy vegetables and milk:

D = 1 x 10' CM DF, UM i

i e

I (1.14)

L where:

t D

Organ dose rate due to ingestion,

=

mrem /y.

i CM, Concentration of radionuclide iin

=

vegetables or milk, Ci/kg (or liters).

i l

DF, Ingestion dose factor, mrem /pCi

=

(Table 2.1).

UM Ingestion rate for milk, 330 t/y; for

=

l vegetables 26 kg/yr (child), no a

ingestion by infant.

l 1x10' pCl/pCi conversion factor.

=

1 1

d)

Meat inoestion (Beefl To calculate the concentration of a nuclide in j

animal flesh:

i 4

C,3 = F,, CV, Q,3 exp (A,'s)

(1.15)

I where:

C,,

Concentration of nuclide iin the

=

animal flesh, pCi/kg.

F,,

Fraction of animal's daily intake

=

which appears in each kg of flesh, days /kg (Table 1.6).

1 CV, Concentration of radionuclide iin

=

i the animal's feed (Equation 1.10).

16

4 PALISADES NUCLFAR PLANT OFFSITE D_OSE CALCULATION MANUAL i

a Revision 10 d

Q, Amount of feed consumed by the

=

cow per day, 50 kg/d.

i i

t, Average time from slaughter to

=

consumption, 20 days.

To determine the organ dose from ingestion of beef:

D'=

C 0, U, n

where:

(1.16)

D,3

\\

Ingestion dose factor for age

=

i group, mrem /pCl (Table 2.1) for nuclide i.

U, Ingestion rate of meat for age

=

group, kg/y (child-41, teen 65, i

adult-110).

j e)

Draan Dose Rates For determining the total body and organ dose i

- rate from iodines and particulates:

D = D, + Do + Du + Dy + D, (1.17) where:

D Total organ dose rate, mrem /y.

=

O, Dose rate due to inhalation,

=

mrem /y.

D Dose rate due to ground a

=

contamination, mrem /y.

Du Dose rate due to milk ingestion,

=

mrem /y.

17

PALISADES NUCI FAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 Dv Dose rate due to vegetable

=

ingestion, mrem /y.

D, Dose rate due to beef ingestion,

=

mrem /y.

\\

3)

The maximum organ dose rate, maximum total body dose rate, and maximum skin dose rate calculated in the previous section (Sec l.8) are used to calculate design basis quantities as described in Section I.B.1.3.

c.

Desian Basis Quantities The design basis quantity of a radionuclide emitt':i to the atmosphere is the amount of that nuclide, whr n released in one year, which would result in a dose not exceeding any of the following:

1) 15 millirem to any organ of an individual from iodines and particulates with half-life greater than 8 days (Appendix A, Section Ill.D.1).

2) 15 millirem to skin of an individual from noble gas (Appendix A, Section Ill.C.1.b).

3) 5 millirem to the total body of an individual from noble gas (Appendix A, Section Ill.C.1.a).

Design basis quantity (Ci) is the smallest value for each nuclide, calculated by dividing the dose limits (a through c above) by the appropriate dose calculated from the amount of radionuclide (Ci) used to conservatively estimate the doses of Section D, as listed in Table 1.1 (or a hypothetical 1 Ci/ year); the result is then multiplied by the amount of radionuclide used.

D^'(C,)

DBQ =

D, (1.18) where:

Dx, Appendix I dose limit (mrem or mrad).

=

18

PAUSADES NUCI NAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 i

D, Calculated dose (mrem or mrad),

=

i 1

C, Quantity of nuclide resulting in dose D (Ci).

=

DBQ Design Basis Quantity (Ci).

=

h The limiting values for Design Basis Quantities for i

radionuclides released to the atmosphere are given in i

Table 1.9.

}

The inverse of the ratio C,/D, in the above equation (ie, D,/C,) is a useful value, since it represe.its the most limiting i.

dose per unit quantity of each nuclide released. Use of the D,/C, ratio in quarterly evaluation of offsite dose is discussed in Section D. Values of D,/C, are given in Table 19 t

[

d.

Land Une census and DBQ Chanc =

I.

Appendix A, Sections J.3.b and J.3.c describe the requirements for an annual land use census and revision of the ODCM for use in the following calendar year. Areas of j

the ODCM which will be reviewed, and changed if appropriate, are Table 1.4 (Land Use Census Data by i

i Sector), Table 1.4a (Critical Receptoral, and Table 1.9 l Gaseous Qesign Basis Objective Annual Quantities).

i

}

Changes will be effective on January 1 of the year following 1

the year of tie survey.

Gaseous Releases From the Steam Generator Blowdown e.

Vent and Atmonohere Release Valyes Releases from the steam generator blowdown vent and atmospheric relief valve,s are difficult to quantify as there are no sampling capabilities on these steam release systems.

However, riaither system is a normal release path. The steam generator blowdown vent is normally routed to the main condenser and recirculated. Radioactive releases will be calculated by analyzing steam generator blowdown liquid and assuming that 100 percent of Noble Gases,10 percent of the lodines and 1 percent of the Particulates will be released to the environment in the steam phase. Volumes will be released tn the environment in the steam phase.

Volumes will be calculated using water balances or alternate means as available.

19

pas mnDEE NUCi FAR PLANT

-~

~

OFFSITE DOSE CALCULATION MANUAL Revision 10 C.

DESIGN OBJECTIVE QUANTITY (D80) LIMITS ON BATCH AND

- CONTINUOUS RELEASES 1.

Batch Releases Prior to each batch release (waste decay tank release or Containment purge), the quantity of each nuclide identified is summed with the quantity of that nuclide released since the first of the current calendar year. The cumulative total for each nuclide then is divided by the design objective quantity for each nuclide (from Table 1.9), and the resultant fractions are summed in order to assure that the sum fraction of all nuclides does not exceed 1 b

AI

< 1.0 i

(DBQ),

(1.19)

The amount in any calendar quarter should not exceed 0.5. This is checked by subtracting the value ootained at the end of the previous quarter from the value obtained from the cumulative total to date, including the batch to be released.

2.

Continuana P '- :

s Low level continuous releases from the vent gas collection header and other low Igvel sources are totaled on a weekly basis and summed with any batch releases for the week in order to establish the cumulative DBQ fraction from batch plus continuous released for the year-to-date. Calculations are performed in the same manner as for batch releases described in C.1.

3.

Exc :.1.a DBQ Limita As discussed under B.1.3, the DBQ is a very conservative estimate of activity which could give doses at Appendix Ilimits. Because j

different organs are summed together and doses to different people are summed, the DBQ typically overestimates dose by about a factor of five. Thus, if calculations of DBQ fraction exceed 1.0 for year-to-date or 0.5 for the quarter, technical specifications probably still would not be exceeded. However, further discretionary releases should be deferred until an accurate assessment of dose i

made by use of GASPAR computer code or by analysis of appropriate release data via the segment gaussian dose model used in emergency planning (inhalation dose, total body external dose, and boundary dose in air). See also Section D.1.2.

20

)

i

_ _ _ _ _ _ _ _. _ _ _.. _ _ _ _ _ _ _ _. _ _ _. _ _ _ _ _ _. _ _ = _ _ _ _ _ _ _ _. _ _ _ _

i PAtl8 ADES NUCIFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 l

l 4

It should be noted that Palisades Plant to date (based on review of

{

semiannual effluent data) has never exceeded the annual or quarterly DBQ fraction,'despite its conservatism. Thus, it is not j

expected that an alternate to the DBQ method will be required unless the Plant is in a significantly off-normal condition.

]

4.

Bala==Ina P=4nurE-AE_Not Listed in T=M=

9

}

Table 1.9 contains all nuclides identified to date as routine i

constituents of gaseous releases at Palisades Plant, plus those l

common to PWRs in general, even if not previously detected at Palisades. From time to time, however, other nuclides may be

{

detected.

L i

If the unlisted nuclide constitutes less than 10% of the EC-fraction for the release, and all unlisted nuclides total less than 25% of the l

EC-fraction, the nuclide may be considered not present, a

p if the unlisted nuclide constitutes greater than 10% of the l

EC-fraction, or all unlisted nuclides together constitute greater than j

25%, then each nuclide should be assigned a DBQ equal to the most conservative value listed for the physical form of the nuclide involved (noble gas, halogen, or particulate).

5 Should a nuclide not listed in Table 1.9 begin to appear in j

significant quantities on ~a routine basis, revision to this ODCM j

should be made in order to include a design basis quantity specific j

to that nuclide.

4 e

l D.

OPTIONAL QUARTERLY DOSE CALCULATIONS 1

4 1.

Methodology for Ootional th= tariv De-e N8=tions i

4 i

This option may be used in place of, or in addition to, the Design Basis Quantity (DBQ) fraction calculation described by Equation 1.19. This optional conservative calculation relates the DBQ fraction to the doses from which it was originally derived.

Use of this method may assist in identification of the critical dose j

pathway or characteristics of the assumed critical individual (infant, j

child, teen, and adult), since Table 1.9 indicates these parameters.

1 i

1 21 2

h T,

PALISADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL t

Revision 10 Simotified Conservative Acoroach a.

This method utilizes a limiting dose concept such that the limiting dose for each nuclide is summed with the limiting dose for each other nuclide, regardless if such sum is physically possible. It also assumes critical pathways, such as milk and vegetables, are in effect even in winter when the pathway is absent.

a As such, the method is highly conservative and significantly' over-estimates dose. If limits appear to be exceeded by this method, Section D.1.2 (a concise me' hod, but requiring computer support) will be utilized.

1.

Assumotions a)

All assumptions of Section 1.1 are utilized.

b)

Limiting doses for each gaseous nuclide are summed, regardless of limiting decay mode (gamma or beta).

c)

Limiting doses for each particulate and iodine nuclide are summed, regardless of dose point location, exposure pathway, or organ affected.

1 d)

Doses are summed for detected nuclides such that all nuclides which contribu+e greater than 10% individually or 25% in agregate, to the EC of released radioactivity, are included in the dose calculation.

2.

Ecuations t

For determining gaseous effluent dose:

a 4

I i

o = [ A,o(0,/C,j, < 5 millirad / quarter,10 mrad /yr D

o 5

(1.20) 22

_~

PALISADES NUCI FAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 i

where:

i DG Dose from gaseous effluents (mrad).

=

A,o Quantity of gaseous nuclide i released

=

(Ci).

(D,/C,),o Dose per Ci factor for gaseoue ataclide i

=

(mrad /Ci).

t The limit for this mixture is conservatively taken as that for gamma exposure (5 mrem / quarter, 10 mrem / year) although as indicated in Table 1.9, a majority of the gaseous effluents are beta-limiting and on an individual basis have the higher limit of 10 millirem / quarter and 20 millirem / year.

l For determining tritium, particulate and iodine dose to I

organs:

i i

TPli (D Ib )ypgg < 7,5 mrem /q,15 mremly DTPI*{

c c 1

i (1.21) 4 where:

TPI Dose from particulates and iodines D

=

(mrem).

Au TP Quantity of particulate or iodine nuclide i

=

released (Ci).

(D,/C,)m Dose per Ci factor for particulate or iodine

=

nuclide i (mrad /Ci) b.

Realistic Calculatien This methodology is to be used if the highly conservative calculations described in C.1 or D.1 yield values that appear to exceed applicable limits.

23

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

i y

PALISADES NUCI FAR PLANT i

OFFSITE DOSE CALCULATION MANUAL i

Revision 10 i

j i.

Doses for released particulates, iodines and noble gases will be determined by use of the NRC GASPAR computer code.

[

The computer run will utilize the annual average joint j

frequency meteorological data based on not less than 3 years

[

of metecrological measurement, and will reflect demographic and land use information from the land use survey generated j

in the' most recent prior year. Where appropriate, seasonal

}

adjustments will be applied to obtain realistic dose estimates since both recreational and agricultural activities can vary i

greatly in relation to season of the year.

ir An alternative to GASPAR for offsite dose calculation is the j

[

use of the Palisades Segmented Gaussian Plume Emergency offsite dose calculation program. This dose model allows

{

evaluation of dose under the actual meteorological co' nditions present at the time of release. It is anticipated that the i

system may be used in major short-term releases such as Containment purges are to be made under conditions which depart significantly from mean annual conditions.

1 E.

GASEOUS RADWASTE TREATMENT SYSTEM OPERATION l

The gaseous radwaste treatment system (GRTS) described below shall be maintained and operated to keep releases ALARA.

1.

Swatam Dame intion i

A flow diagram for the GRTS is given in Figure 1-1. The system consists of three waste-gas compressor packages, six gas decay tanks, and the associated piping, valves, and instrumentation.

Gassous wastes are received from the following: degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown, displacing of cover gases caused by liquid i

accumulation in the tanks connected to the vent header, and boron recycle process operation.

Design of the system precludes hydrogen explosion by means of ignition source elimination (diaphragm valves, low flow diaphragm compressors and system electrical grounding), and minimization of leakage outside the system. Explosive mixtures of hydrogen and oxygen have been demonstrated compatible with the system by operational experience over the past 13 years.

24

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL i-Revision 10 i'

1 2.

Determination of Satisfactory Onoration il' Design basis quantity fraction will be calculated for batch and j

continuous releases as described in Section I.C. These calculations will be used to ensure that the GRTS is operating as designed.

i Because the Plant was designed to collect and hold for decay a j

vast majority of the high level gases generated within the primary j.

system, and because the 13-year operating history (to date of 1

writing the initial ODCM) of the Plant has demonstrated the system's consistent performance well below Appendix I limits, no additional operability requirements are specified.

1

[

F.

RELEASE RATE FOR OFFSITE EC (50 mrom/yr) i j

- 10 CFR 20.1302 requires radioactive affluent releases to unrestricted areas be in concentrations less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. (Note:

i there are no unrestricted areas anywhere within the site boundary as defined by Figure 1-1.) Concentration 6 at this levelif present for one year J

}

will result in a dose of 50 mrom whole body.10 CFR 50.36a requires

[

that the relsase of radioactive materials be kept as low as reasonably j

achievabla. However, the section further states that the licensee is j

permitted the flexibility of operation, to assure a dependable source of power even under unusual operating conditions, to release quantities of material higher than a small percentage of 10 CFR 20.1302 limits but still i

within those limits. Appendix 1 to 10 CFR 50 provides the numerical l

guidelines on limiting conditions for operations to meet the as low as i

j.

reasonably achievable requirement.

The GASPAR code has been run to determine the dose due to external j

radiation and inhalation. The source term used is listed in Table 1.1. The j

meteorology data is given in Table 1.3. Dose using annual average meteorology, to the most limiting organ of the person assume to be j

residing at the site boundary with highest X/Q, is 2.15E-02 mrem (for one i

year). The release rate which would result in a dose rate equivalent to j

50 mrem / year (using the more conservative total body limit) is the

{

curies /y' ear given in Table 1.1 multiplied by 50/2.15E-02 or 0.11 Ci/sec.

l 25 i

PALISADES NUCI FAR PLANT OFFSITE COSE CALCULATION MANUAL Revision 10 4

G.

PARTICULATE AND IODINE SAMPLING Particulate an iodine samples are obtained from the continuous sample stream pulled from the Plant stack. Samples typically are obtained to represent an ir'tegrated release from a gas batch (waste gas decay tank or Comainment purge, for example), or a series of samples are obtained to follow the course of a release. In any event, sample intervals are weekly, j

at a minimum.

Because HEPA filters are present between most source inputs to the

. stack and the sample point, releases of particulates normally are significantly less than pre-release calculations indicate. This provides for conservatism in establishing setpoints and in estimation of pre-release design basis quantity fraction. However, for the sake of maintaining accurate release totals, monitor results (for gases) and sample results (for particu;stes and iodines) utilized rather than the pre-release estimates, for cumulative records.

Gamma analytical results for particulate and halogen filters are combined for determination of total activity of particulates and halogens released.

Beta and alpha counting also is performed on the particulate filters. Beta yields of the gamma isotopes detected on particulate filters are applied to determine " identified" beta, an the " identified" count rate is subtracted

}

from the observed count rate to give " unidentified" beta. The i

" unidentified" beta is assumed to be Sr-90 until results on actual Sr-90 (chemically separated from a quarterly composite of filters) are obtained.

i Sampling and analysis will be performed per Appendix A, Table B-1 requirements.

l H.

NOBLE GAS SAMPLING l

Noble gases will be sampled from Waste Gas Decay Tanks prior to release and the Containment prior to purging. Analysis of these samples will be t

used for accountability of noble gases. Off gas will be sampled at least weekly and used to calculate monthly noble gas releases. Nonroutine releases will be quantified from the stack noble gas monitor (RE 2326) which has a LLD of 1E-06 pCi/ce. Sampling and analysis will be performed per Appendix A, Table B-1 requirements.

d 26 d

i PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 1.

TRITIUM SAMPLING Tritium has a low dose consequence to the public because of low production rates. The major contributors to tritium effluents are evaporation from the fuel pool and reactor cavity (when flooded).

Because of the low dose impact, gaseous tritium sampling will not be required. Tritium effluents will be estimated using conservative

~

evaporation rate calculations from the fuel pool and reactor cavity.

l i

i i

4 27

l

.C-

"S" PALISADES GASEOUS EFFLUENTS AC f fVITY CA%

I 8I PM T

808 101 tot FLOW STACK CONTROL O""

r-C 80DfNE/PART WASTE GAS riir v-m fttPRGF TANK I

J E

TH8

)

,, m REIH3 8000tE Z

gas g

O,,

ATesO!PHERE JL!!?"#L mPA as 4'

LOW LEVEL r

m >

GAS (X)LLECTIOft O

fTt C

STE Ae8 GENERATOR HEActR m_.

m g m 8t05UDOuvet TANK VENT HEPA o N (p) C gyg gggy m

_ _ a _

- -E ER n.

c ____..

y 1990 S.

Aux Z

pg peEPNtseAsocOAL St erPLY AD-O C l

AREA RE ISUt*

VWFST 4 m

sArt NA e

Q p

GUARO RE 8818 d 3 HEPA POD 89tBAll o "O FUEL O

gg SIfPPL Y =*== HA800LC g,g,gy

E 981F AREA O

g StDG

H HEPAN.NAR(X)AL 2

(REFLPFLSNG) l C

i l

M r....______.,

7--_____.,

r-MEPA man-yggt StMY AREA -4 su.. tY RA ME 5712' "I"

ADDITM RE $71t'

RE 1 Wit. 5711 A880 SFf 2 TRIP SUPPLY A880 088E OF T.-0 E RNAU5 tests FLOUF f5 MOT TEftnesesATED PALISADES EFFLUENT FLOW PATHS GASEOUS 4

i I

s

)

PALISADES NyCLEAR PLAlyT OFFSITE DOSE CALCULATION MANUAL i

Revision 10 P

TABLE 1.1 PALISADES GASEOUS AND LIQUID SOURCE TERMS, CURIM/ YEAR fil 1

Nuclide Gaseon,2) 1.igidd(2) i H-3 5.5 159 Kr-85 4.1 NA

^

Kr-85m 0.12 NA i

Kr 87 8.4E-02 NA Kr-88 2.1 E-01 NA Ar-41 3.1 E-02 NA Xe-131m 2.2 NA l

Xe-133 -

1493 NA Xe-133m 0.43 NA Xe-135 1.11 NA Xe-135m 0.3 NA

{

i 1-131 0.025 3.21 E-03 l

l-132 2.91 E-03 NA l-133 6.5E-03 4.7E-05 l

l-134 4.8E-04 NA l-135 1.84E-02 NA

}

Na-24 1.5E-06 NA Cr 51 2.5E-04 3.9E-03 Mn-54 4.1 E-04 7.8E-03 Co-57 2.1 E-06 3.2E-05 Co-58 8.6E-04 2.9E-02 3

Fe-59 6.6E-06 4.1 E-04 Co-60 1.1 E-03 1.24E-02 Se-75 3.7E-06 NA Nb-95 2.4E-05 4.53E-04 Zr-95 4.7E-06 1.79E-04 Mo-99 1.5 E-07 NA i

Ru-103

.3E-07

.1 E-05 Sb-127 NA 3.5E-05 Cs-134 4.5E-05 0.7 Cs-136 NA 1.8E-06 Cs-137 2.6E-04 1.36E-02 Ba-140 2.8E-07 NA La-140 7.5 E-07 1.1 E-04 Unidentified beta 3.9E-04 3.3E-03 (1)

Data derived from taking the effluents released during July-December 1978 through January-June 1982 and dividing by 4.

I j

(2)

Nuclide values listed as NA have not been observed at detectable levels in these waste streams, i

1 29

PALISADES NUCL FAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 1.2 BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA' GAMMA' (days) 1141,1 BiEV/ DIS)

(MEV/ DIS) 1 Tritium 4.49E 03 1.79E-09 5.68E-03 0.0 2

C-14 2.09E 06 3.84E-12 4.95E-02 0.0 3

N 13 6.94E-03 1.16E-03 4.91 E-01 1.02E 00 4

0 19 3.36E-04 2.39E-02 1.02E 00 1.05E 00 5

F-18 7.62E-02 1.05E-04 2.50E-01 1.02E 00 6

NA-24 6.33E-01 1.27E-05 5.55E-01 4.12E 00 7

P-32 1.43E 01 5.61 E-07 6.95E-01 0.0 8

AR-41 7.63E-02 1.05E-04 4.64E-01 1.28E 00 9

CR-51 2.78E 01 2.89E-07 3.86E-03 3.28E-02 10 MN-54 3.03E 02 2.65E-08 3.80E-03 8.36E-01 11 MN-56 1.07E-01 7.50E-05 8.29E-01 1.69E 00 12 FE-59 4.50E 01 1.78E-07 1.18E-01 1.19E 00 13 CO-58 7.13E 01 1.12E-07 3.41 E-02 9.78E-01 14 CO-60 1.92E 03 4.18E-09 9.68E-02 2.50E 00 1E ZN-69m 5.75E-01 1.39E-05 2.21 E-02 4.16E-01 18 ZN-69 3.96E-02 2.03E-04 3.19E-01 0.0 17 BR 84 2.21 E-02 3.63E-04 1.28E 00 1.77E 00 10 BR-85 2.08E-03 3.86E-03 1.04E 00 6.60E-02 19 KR-85m 1.83E-01 4.38E-05 2.53E-01 1.59E-01 20 KR-85 3.93E 03 2.04E-09 2.51 E-01 2.21 E-03 21 KR-87 5.28E-02 1.52E-04 1.32E 00 7.93E-01 22 Kil-SS 1.17E-01 6.86E-05 3.61 E-01 1.96E 00 23 KR-89 2.21 E-03 3.63E-03 1.36E 00 1.83E 00 24 RB-88 1.240-02 6.47E-04 2.06E 00 6.26E-01 25 RB-89 1.07E-02 7.50E-04 1.01 E 00 2.05E-00 26 SR-89 5.20E 01 1.54E-07 5.83E-01 8.45E-05 27 SR-90 1.03E 04 7.79E-10 1.96E-01 0.0 28 SR-91 4.03E-01 1.99E-05 6.50E-01 6.95E-01 29 SR-92 1.13E-01 7.10E-05 1.95E-01 1.34E 00 30 SR-93 5.56E-03 1.44E-03 9.20E-01 2.24E 00 31 Y-90 2.67E 00 3.00E-06 9.36E-01 0.0 32 Y-91 m 3.47E-02 2.31 E-04 2.73E-02 5.30E-01 33 Y-91 5.88E 01 1.36E-07 6.06E-01 3.61 E-03 34 Y-92 1.47E-01 5.46E-05 1.44E 00 2.50E-01 35 Y-93 4.29E-01 1.87E-05 1.17E 00 8.94E-02 36 ZR-95 6.50E 01 1.23E-07 1.16E-01 7.35E-01 37 NB-95m 3.75E 00

'2.14E-06 1.81 E-01 6.06E-02 38 NB-95 3.50E 01 2.29E-07 4.44E-02 7.64E-01 39 MO-99 2.79E 00 2.87E-06 3.96E-01 1.50E-01 40 TC-99m 2.50E-01 3.21 E-05 1.56E-02 1.26E-01 30

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 4

I TABLE 1.2 (continued)

BASIC RADIONUCLIDE DATA i

NUCLIDE HALF-LIFE LAMBDA BETA' GAMMA' idayM il/M (MEV/ DIS)

(MEV/ DIS) 41 TC-99 7.74E 07 1.04E-13 8.46E-02 0.0 i

42 TC-104 1.25E-02 6.42E-04 1.60E 00 1.95E 00 i

43 RU-106 3.67E 02 2.19E-08 1.01 E-02 0.0

)

44 TE-132 3.24E 00 2.48E-06 1.00E-01 2.33E-01 45 l-129 6.21E 09 1.29E-15 5.43E-02 2.46E-02 3

46 l-131 05E 00 9.96E-07 1.94E-01 3.81 E-01 47 l-132

.58 E-02 8.37E-05 4.89E-01 2.24E 00 48 l133 8.75E-01 9.17E-06 4.08E-01 6.02E-01 49 l-134 3.61 E-02 2.22E-04 6.16E-01 2.59E 00 50 1-135 2.79E-01 2.87E-05 3.68E-01 1.55E 00 51 XE-131m 1.18E 01 6.80E-07 1.43E-01 2.01 E-02 52 XE-133m 2.26E 00 3.55E-06 1.90E-01 4.15E-02 53 XE-133 5.27E 00 1.52E-06 1.35E-01 4.60E-02 54 XE-135m 1.08E-02 7.43E-04 9.58E-02 4.32E-01 55 XE 135 3.83E-01 2.09E-05 3.17E-01 2.47E-01 56 XE-137 2.71 E 03 2.96E-03 1.77E 00 1.88E-01 57 XE-138 9.84E-03 8.15E-04 6.65E-01 1.10E 00 i

58 CS-134 7.48E 02 1,07E-08 1.63E-01 1.55E 00 59 CS 135 1.10E 09 7.29E-15 5.63E-02 0.0 60 CS-136 1.30E 01 6.17E-07 1.37E-01 2.15E 00 61 CS-137 1.10E 04 7.29E-10 1.71 E-01 5.97E-01 62 CS-138 2.24E-02 3.58E-04 1.20E 00 2.30E 00 63 8A-139 5.76E-02 1.39E-04 8.96E-01 3.53E-02 64 8A-140 1.28E 01 6.27E-07 3.15E-01 1.71 E-01 65 LA-140 1.68E 00 4.77E-06 5.33E-01 2.31 E 00 66 CE-144 2.84E 02 2.82E-08 9.13E-02 1.93E-02 i

67 PR 143 1.36E 01 5.90E-07 3.14E-01 0.0 68 PR-144 1.20E-02 6.68E-04 1.21 E 00 3.18E 00 2

Average energy per disintegration values were obtained from ICRP Publication No 38, Radionuclide Transformations: Enarav and Intensity of Emissions 1983 and NUREG/CR-1413 (ORNL/NUREG-70), a Radionuclide Decav Data Base -Index and Summarv Table. DC Kocher, May 1980.

31

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 i

1 TABLE 1.3

{

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8. 8 8. 8. 8. 8. 8. 8 8 8 8 8 8 8 8 8 o

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"*" PALISAKS N0000082 ***** USING 01/01/88 - 12/31/92 ME T DAI A "*"

GROUNO LEVEL RELEASE - TOP DF CONTAINMEhi BUILDING 8.000 OAT KEAY.

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6.340E-07 2.147E-07 9.389E-08 5.470E-08 3.654E-08 1.673E-08 5.476E-09 2..'08E - 09 1.303E-09 8.442E-10 ESE 6.599E-07 2.214E-07 9.635E-08 5.600E-08 3.736E-08 1.708E-08 5.579E-09 2..%1 E-09 1.329E-09 8.620E-10 SE 7.473E-07 2.496E-07 1.084E-07 6.299E-08 4.201E-08 1.921E-08 6.282E-09 2.652E-09 1.501E-09 9.747[-10 55E 8.400E-07 2.838E-07 1.246E-07 7.484E-08 4.880E-08 2.247E-08 7.423E-09 3.154E-09 1.190E-09 1.164E-09 l

USNRC CDPruTER CODE - X00000. VERSION 2.0 Alse DME: 931116

- - - - PALISA0E5 XD000082 "* USING 01/01/88 - 12/31/92 NET OATA ""

GROUND L.E. VEL RELEASE - TOP OF CONTAlf0ENI BUILDING

.en*********

RELAllVE DEPOSIIION PER UNii MIEA (N'*-2) Al FIXED P0lNis SV 00WWIND SECIOR$

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2.434E-08 8.230E-09 4.22M-09 2.59K-09 1.294E-09 7.845E-10 5.304E-10 3.844E-10 2.9230-10 2 303E-10 1.864E-10 55W l.655E-08 5.596E-09 2.873E-09 1.764E-09 8.795E-10 5.334E-10 3.601E-10 2.614E-10 1.987E-101.566E-10 1.267E-10 0

SW l.921E-08 6.49?E-09 3.336E-09 2.04K-091.021E-09 6.19X-10 4.187E-10 3.034E-10 2.307E-101.81K-101.472E-10 m

W5W l.805E-08 6.IO5E-09 3.135E-09 1.925E-09 9.596E-10 5.820E-10 3.935E-10 2.851E-10 2.168E-10 1.708E-10 1.383E-10 W

2.41K-08 8.181E-09 4.200E-09 2.57K-051.286E-09 7.799E-10 5.273E-lO 3.82tE-10 2.905E-10 2.289E-10 1.853E-10 E

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NW 4.290E-08 1.454E-08 7.483E-09 4.583E-09 2.28 K-09 1.386E-09 9.369E-10 6.789E-10 5.162E-10 4.067E-10 3.292E-ID MNW 5.43 W-08 1.838E-08 9.436E-09 5.794E-00 2.889E-09 1.752E-09 1.185E-09 8.584E-10 6.527E-10 5.142E-10 4.163E-10 U

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g hME 2.933E-08 9.919E-09 5.093E-09 3.127E-091.559E-09 9.45K-10 8.393E-10 4.63X-10 3.523E-10 2.775E-10 2.247E-10 rYI NE 4.872E-08 1.580E-08 8.112E-09 4.981E-05 2.48K-09 1.506E-09 1.0lK-09 7.379E-10 5.611E-10 4.420E-10 3.578E-10 g

ENE 3.458E-08 1.150E-08 0.000E-09 3.004E-09 1.837E-OS 1.Il4E-00 1.532E-10 5.450E-10 4.150E-10 3.270E-10 2.64?E-10 ac w

E 3.70lE-08 1.251E-08 6.425E-09 3.945E-09 1.967E-09 1.19M-09 8.065E-10 5.844E-10 4.444E-10 3.50lE-10 2.834E-10 E

r-00 ESE

- 4.171E-08 1.4 tee-08 7.242E-09 4.447E-03 2.217E-09 1.34K-09 9.09tE-10 6.588E-10 5.009E-10 3.946E-10 3.195E-10 E

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FROM SITE 5.00 7.50 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 g

5 1.E42E-10 7.55K -Il 4.741E-11 2.396E-Il 1.450E-Il 9.725E-12 6.968E-12 5.233E-12 4.068E-12 3.250E-12 2.653E-12 55W I.048E-10 5.138[-11 3.224E-Il 1.629E-11 9.862E-12 6.613E-12 4.730E-12 3.558E-72 2.766E-12 2 ZIDE-12 1.804E-12 E

SW l.217E-10 5.965E-Il 3.743E-11 1.892E-Il 1.145E-11 7.67FE-12 5.501E-12 4.131E-12 3.212E-12 2.566E-12 2.094E-12 W5W 1.144E-10 5.60K-11 3.517E-11 1.770E-11 1.07K-Il 1.214E-12 5.le9E-12 3.882E-12 3.018E-12 2.41tE-12 1.966E-12 I

W l.53 X-10 7.511E-11 4.713E-11 2.382E-11 1.442E-Il 9.567E-12 6.927E-12 5.20lE-12 4.044E-12 3.231E-12 2.637E-12 h

WNW 2.290E-10 1.122E-10 7.043E-11 2.560E-11 2.15M-11 1.44W-11 1.035E-11 7.77M-12 6.043E-12 4.827E-12 3.940E-IZ r-NW 2.72M -10 1.33 K-10 0.374E-Il 4.233E-!! 2.542E-11 1.718E-11 1.231E-II 9.242E-12 7.184E-12 5.740E-12 4.685E-12 isIW 3.44K-10 1.687E-10 1.059E-10 5.352E-Il 3.239E-11 2.172E-11 1.556E-Il 1.169E-11 9.086E-12 7.258E-12 5.924C-12 N

3.183E-10 1.521E-10 9.542E-Il 4.823E-Il 2.919E-Il 1.95?[-11 1.402E-Il 1.05M-Il 3.180E-12 8.540E-12 5.33K-12 NNE 1.858E-10 9.107E-Il 5.714E-11 2.800E-Il 1.74K -11 1.172E-!! 8.399E-12 6.306E-12 4.903E-12 3 917E-12 3.197E-12 NE 2.960E-lO 1.45tE-10 9.102E-11 4.500E-Il 2.784E-Il 1.867E-11 1.33K-11 1.004E-Il 7.810E-12 6.239E-12 5.092E-12 ENE 2.190E-10 1.07X -10 S.733C-11 3.40X-11 2.060E-Il 1.381E-11 9.895C-12 7.43K-12 5.777E-12 4.615E-12 3.76?E-12 E

2.345E-10 1.149E-10 7.209E-Il 3.644E-Il 2.285E-!! 1.479E-11 1.06 K-11 7.956E-12 6.lB6E-12 4.542E-12 4.033E-12 ESE 2.54X-10 1.29K-10 P.12eE-11 4.107E-Il 2.48K-il I.667E-11 1.194E-Il 8.968E-12 6.973E-12 5.570E-12 4.546E-12 SE 3.378E-10 1.65EE-10 1.039E-10 5.251E-11 3.17K-11 2.131E-11 1.527E-Il 1.146E-Il 8.914E-12 7 120E-12 5.812E-12 SSE 3.266E-10 1.601E-10 1.004E-10 5.071E-11 3.073E-!! 2.060E-11 1.476E-11 1.108E-Il 8.619E-12 ti 885E-12 5.619E-12

. m

. m s

m

-_m_.---..,__--_____.-_.~m,

.~-.

s I

L I

-i USNRC COIFUTER CODE - XOOD00. M R$10N 2.0 RUli DATE. 931115

- - " PAtl5 AGES X0000082 **"* USING 01/01/98 - 12/31/92 NET DATA *****

i liRetAID LEVEL RELEAR - TOP OF EONTAINNENT BUILDING O

i 3

,u,rl,,,051,,0,,,,,,,I,,,E u,,..,3 8, 0,,,,,,0 y C 5 SEGWhi BoulIDARIE5 IN MILE 5.

Q DIE CTION

.5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30 40 40 50 m

t FRelt SITE Q

5 4.391E-09 1.356E-09 5.398E-10 2.95K-10 1.875E-10 8.053E-Il 2.497E-Il 9.897[-12 5 285E-12 3.271E-12 0

55W 2.98K-08 9.223E-10 3.670E-10 2.00eE-10 1.27K-10 5.47K-11 1.69K-Il 6.72K-12 3.594E-12 2.224E-12 M

i m

[

Sif 3.466[-0B 1.071E-09 4.261E 10 2.32K -10 1.480E-10 6.357E-11 1.971E-Il 7.813E-12' -4.lF2E-12 2.582E-12 l31 USW 3.257E-09 1.90K-09 4.004E-10 2.188E-!O 1.391E-10 5.974E-Il 1.852E-11 T.342E-12 3.92tE-12 2.427E-lz O

+

,g W

4.364E-09 1.348E-09 5.36K-10 2.932E-!O 1.864E-10 8.005E-II 2.482E-Il 9.838E-12

5. 254E-12 3.252E-12 y

1 Wini 8.522E-09 2.815E-tB 8.0lK-10.4.381E-lO 2.785E-10 1.196E-10 3.709E-Il 1.470E-Il 7.851E-12 4.859E-12 W

E-5 Inf 7.75W-09 2.39EE-OS 9.533E-10 5.210E-10 3.31tE-10 1.422E-10 4.410E-II 1.748E-Il 9.335E -12 5.TF8E-12 Q

C

. IlllW 9.00E-09 3.029E-85 -1.26W-09 6.58FE-10 4.lS7E-18 1.798E-10 5.5FSE-Il 2.210E-Il 1.180[-11

7. 30$E-12

'a R

S.830E-09 2.730E-09 1.00EE-99 5.936E-10 3.FF3E-IS 1.621E-10 5.82M-Il 1.992E-11 1.064E-Il 6.583E-12 o

sulE 5.292E-09 1.83W-99 6.50K-10 3.555E-10 2.259E-IG 9.70K-Il 3.810E-11 1.193E-11 S.370E-12 3.943E-12 la8 d

.l Ilt 8.42EE-09 2.604E-09 1.836E-09

'3.652E-10 3.59K -10 1.54K-10 4.194E-11 1.900E-11 1.0lK-11 6.280E-12 0

EllE 5.235E-09 1.926E-99 7.66M-10 ' 4.188E-10 2.662E-10 1.143E-10 3.54K-11 1.405E-11 1.50W-12 4.64W-12 E

E S.6 FEE-09 2.063E-09 8.20TE-10 4.485[-10 2.astE-10 1.224E-10 3.797E-Il 1.505E-11 8.03M-12 4.974E-12 g

i

[5E 7.52K-09 2.32K-09 9.251E-10

5. 055E-10 3.213E-10 1.380E-10 4.200E-11 1.884E-11 9.058E-12 5.606E-12 g

SE 9.619E-09 2.972E-09 1.183E-05 6.462E-10 4.107E-10 1.164E-10 5.4FIE-11 2.168E-Il -1.15eE ;l 1 161E-12 3

SSE 9.30lE-09 2.8FM -99 1.143E-Os 6.24aE-10 3.971E-10 1.70K -10 5.290E-11 2.097E-11 1.120E Ti i ?J0E 12.

C j

t VENT AND BillLDING PARAKTER5i P"

i RELEAK HE16HI (METER 5) 58.10 REP. Wino itI6ni (METER 5) 18.0 i

SIAllETER (IIETERS) 0.00 BultolleG MEIGHT (ETERS) 58.1 l

ERIT VELOCITY (IEETERS) 0.00 BL96. MIN.CR5.5EC. AREA (SQ.fETERS) 2000.0

~

HEAT EMISSION RATE (CAL /SECl 00 ALL Eft 0UND LEKL RELEASES.

f f

{

f J

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 i

TABLE 1.4 j

i l

1995 PALISADES LAND USE CENSUS j

Distance to the nearest residence, garden, dairy / beef cattle, and goat in each sector.

SECTOR RESIDENCE GARDEN BEEF CATTLE DAIRY COW GOAT N

> 5 mi

> 5 mi NNE 1.1 mi 1.6 mi

> 5 mi

> 5 mi NE 1.2 mi 1.2 mi

> 5 mi

> 5 mi 3.2 mi l ENF 1.3 mi 2.7 mi 4.0 mi

> 5 mi

> 5 mi l

E 1.0 mi 2.2 mi 3.5 mi

> 5 mi

> 5 mi l ESE 1.0 mi 2.3 mi 4.0 mi

> 5 mi 3.0 mi-l SE 1.0 mi 1.8 mi

> 5 mi 4.3 mi

> 5 mi l SSE 0.7 mi 1.6 mi 3.0 mi

> 5 mi 5.0 mi S

0.5 mi 1.5 mi

> 5 mi

> 5 mi SSW 0.7 mi

> 5 mi

> 5 mi i

40

- - - ~

PALISADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 i

J TABLE 1.4a 1994 PALISADES LAND USE CENSUS _

Critical Recentor items 4

7 Distance Sector (Miles)

Location /Descriotion Jiam

'X/O isec/m )

3 I

SSE 0.48 Site Boundary N/A 1.80E-06 S

0.50 Residence, Palisades Park:

Residence 1.20E-06 l

1/2 mile West of i

29th Avenue and Blue Star 4

intersection 1

NE 1.2 L Swetay, Rt 3, Box 133 Garden 4.69E-07 i

Blue Star Hwy, East side 1

SSE 3.0 35760 76Tth Street Beef 1.17E-07 ld West side, between Cattle l

l s{t 34th and 38th Streets a

1 SE 4.3 7240136th Ave Dairy 6.09E-08 l

i Cow NE 3.2 C Bernt Goat 1.13E-07 l

18019 M-140

Based on Palisades 5 year composite meteorological data, 1988-1992.

4 4

41

1 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL i

Revision 10 4

TABLE 1.5 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES

i l

)

DFR DFY2 DFS' DFB2

)

Kr-85m 1.17( + 3)3 1.23( + 3) 1.46( + 3) 1.97( + 3)

Kr-85 1.61 ( + 1) 1.72( + 1) 1.34( + 3) 1.95( + 3)

Kr 87 5.92( + 3) 6.17( + 3) 9.73( + 3) 1.03( + 4)

Kr-88 1.47( + 4) 1.52( + 4) 2.37( + 3) 2.93( + 3)

Kr-89 1.66( + 4) 1.73( + 4) 1.01 ( + 4) 1.06( + 4)

Xe-131 m 9.15( + 1) 1.56( + 2) 4.76( + 2) 1.11( + 3)

Xe-133m 2.51 ( + 2) 3.27( + 2) 9.94( + 2) 1.48( + 3)

Xe-133 2.94( + 2) 3.53( + 2) 3.06( + 2) 1.05( + 3) i l

Xe-135m 3.12( + 3) 3.36( + 3) 7.11 ( + 2) 7.39( + 3)

Xe-135 1.81 ( + 3) 1.92( + 3) 1.86( + 3) 2.46( + 3)

Xe-137 1.42( + 3) 1.51( + 3) 1.22( + 4) 1.27( + 4)

Xe-138 8.83( + 3) 9.21( + 3) 4.13( + 3) 4.75( + 3)

Ar-41 8.84( + 3) 9.30( + 3) 2.69( + 3) 3.28( + 3) 1.

mrem /y per Ci/m3 2.

mrad /y per Ci/m8 3

3.

1.17( + 3) = 1.17x 0

' Dose factors for exposure to a semi-infinite cloud of noble gases. Values were obtained from USNRC Regulatory Guide 1.109, Revision 1 (October 1977).

42

PALISADES NUCLFAR PLANT QEESITE DOSE CALCULATION MANUAL Revision 10 TABLE 1.Q STABLE ELFMENT TRANSFER DATA F - MILK (COW)

F - MILK (GOAT)

F, - MEAT B,

ELEMENT (DAYS /L)

(DAYS /L) fDAYS/KG)

(VEG/ SOIL)

H 1.0E-02 C

1.7E-01 1.2E-02 4.8E-00 1.2E-02 1.0E-01 Na 4.OE-02 3.1 E-02 5.5E-00 P

4.0E-02 3.0E-02 5.2E-02 2.5E-02 2.5E-01 Cr 2.2E-03 2.2E-03 4.6E-02 1.1 E-00 Mn 2.5E-04 2.4E-03 2.5E-04 2.5E-04 Fe 1.2E-03 8.0E-04 2.9E-02 1.3E-04 Co 1.OE 03 1.0E-03 1.3E-02 9.4E-03 4.0E-02 6.6E-04 Ni 6.7E-03 6.7E-03 5.3E-02 1.9E-02 Cu 1.4E-02 1.3E-02 8.0E-03 1.2E-01 Zn 3.9E-02 3.9E-02 3.0E-02 4.0E-01 Rb 3.0E-02 3.OE-02 Sr 8.0E-04 3.1 E-02 1.3E-01 Y

1.4E-02 6.0E-04 1.7E-02 1.0E-05 1.0E-05 4.6E-03 2.6E-03 Zr 5.0E-06 5.0E-06 3.4E-02 1.7E-04 Nb 2.5E-03 2.5E-03 2.8E-01 9.4E-03 Mo 7.5E-03 7.5E-03 8.0E-03 1.2E-01 Tc 2.5E-02 2.5E-02 4.0E-01 2.5E-01 Ru 1.OE-06 1.0E-06 Rh 1.OE-02 4.0E-01 5.0E-02 1.0E-02 1.5E-03 1.3E + 01 Ag 5.OE-02 5.0E-02 Te 1.0E-03 1.7E-02 1.5 E-01 1

1.OE-03 7.7E-02 1.3E-00 6.0E-03 6.0E-02 2.9E-03 2.0E-02 Cs 1.2E-02 3.0E-01 4.0E-03 1.0E-02 Ba 4.0E-04 4.0E-04 3.2E-03 5.0E-03 La 5.0E-06 5.0E-06 Ce 1.0E-04 2.0E-04 2.5E-03 1.0E-04 1.2E-03 2.5E-03 Pr 5.0E-06 5.0E-06 4.7E-03 2.5E-03 Nd 5.0E-06 5.0E-06 3.3E-03 2.4E-03 W

5.0E-04 5.0E-04 1.3E-03 1.8E-02 Np 5.0E-06 5.0E-06 2.0E-04 2.5E-03 43

PALISADES NUCtFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 1.7 INFANT INHALATION DOSE COMMITMENT FACTORS (MREM /50Y PER PCIINHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYR 010 KIDNEY LUNG GI-LLI HS' O.

4.62E-07 4.62E-07 4.62E-07 4.62 E-07 4.62E-07 4.62E-07 BE10 9.49E-04 1.25 E-04 2.65 E-05 O.

O.

1.49E-03 1.73E 05 C14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E 06 N13 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 F18 3.92E-06 0.

3.33E-07 0.

O.

6.10E-07 NA22 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 NA24 7.54E-06 7.54 E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P32 1.45E-03 8.03E-05 5.53E-05 O.

O.

1.15 E-05 AR39 0.

O.

1.00E-08 0.

AR41 0.

O.

3.14E-08 0.

CA41 7.48E-05 O.

8.16E-06.

O.

6.94E-02 2.96E-07 SC46 3.75 E-04 5.41 E-04 1.69E-04 0.

3.56E-04 0.

2.19E-05 CR51 0.

O.

6.39E-08 4.11 E-08 9.45E-09 9.17E-06 2.55 E-07 i

MN54 0.

1.81 E-05 3.56E-06 0.

3.56E-06 7.14E-04 5.04E-06 MN56 0.

1.10E-09 1.58E-10 0.

7.86E 10 8.95 E-06 5.12E-05 FESS 1.41 E-05 8.39E-06 2.38E-06 0.

O.

6.21 E-05 7.82E-07 FE59 9.69E-06 1.68E 05 6.77E-06 0.

O.

7.25E-04 1.77E-05 C057 0.

4.65 E-07 4.58E-07 0.

O.

2.71 E-04 3.47E-06 C058 0.

8.71 E-07 1.30E-06 0.

O.

5.55E-04 7.95E-06 i

CO60 0.

5.73E-06 8.41 E-06 0.

O.

3.22E-03 2.28E-05 N159 1.81 E-05 5.44E-06 3.10E-06 0.

O.

5.48E-05 6.34E-07 i

NI63 2.42E-04 1.46E-05 8.29E-06 0.

O.

1.49E-04 1.73E-06 N165 1.71 E-09 2.03E-10 8.79E-11 0.

O.

5.80E-06 3.58E-05 CU64 0.

1.34E-09 5.53E-10 0.

2.84E-09 6.64E-06 1.07E-05 ZN65 1.38E-05 4.47E-05 2.22E-05 O.

2.32E-05 4.62 E-04 3.67E-05 ZN69M + D 8.98E-09 1.84E-08 1.67E-09 0.

7.45 E-09 1.91 E-05 2.92E-05 ZN69 3.85E 11 6.91 E-11 5.13E-12 0.

2.87E-11 1.05E-06 9.44E-06 i

SE79 0.

2.25E-06 4.20E-07 0.

2.47E-06 2.99E-04 3.46E-06 i

BR82 0.

O.

9.49E-06 0.

O.

BR83 + D 0.

O.

2.72E-07 0.

O.

BR84 0.

O.

2.86E-07 0.

O.

BR85 O.

O.

1.46E-08 0.

O.

KR83M 0.

O.

2.50E-09 0.

KR85PA 0.

O.

1.31 E-08 0.

KR85 O.

O.

1.16E-08 0.

KR87 0.

O.

6.59E-08 0.

KR88 + D 0.

O.

1.38E-07 0.

KR89 0.

O.

8.67E-08 0.

RB86 0.

1.36E-04 6.30E-05 O.

O.

2.17E-06 RB87 0.

7.11 E-05 2.64E-05 O.

O.

2.39E-07 RB88 0.

3.98E-07 2.05E-07 0.

O.

2.42E-07 RB89 + D 0.

2.29E-07 1.47E-07 0.

O.

4.87E 08 SR89 + D 2.84E-04 0.

8.15 E-06 0.

O.

1.45E-03 4.57E-05 SR90+D 2.92E-02 0.

1.85 E-03 0.

O.

8.03E-03 9.36E 05 SR91 + D 6.83E-08 0.

2.47E-09 0.

O.

3.76E-05 5.24E-05 SR92 + D 7.50E-09 0.

2.79E-10 0.

O.

1.70E-05 1.00E-04 Includes a 50% increase to account for percutaneous transpiration.

44

.~.

PALISADES NUCL FAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 i

TABLE 1.7 (continued)

INFANT INHALATION DOSE COMMITMENT FACTORS ISOTOPE BONE LIVER TOTAL BODY THYROID ED IN FIRST YR)

Y90 2.35E-06 0.

6.30E-08 0.

O.

1.92E-04 7.43E-05 KIDNEY LUNG

31-LLI Y91M + D 2.91 E-10 0.

1 Y91 4.20E-04 0.

1.12E-05 O.

O.

1.75 E-03 5.02E 05 9.90E-12 0.

O.

1.99E 06 1.68E 06 Y92 1.17E-08 0.

3.29E 10 0.

O.

1.75E-05 9.04E-05 Y93 1.07E-07 0.

2.91 E-09 0.

O.

5.46E-05 1.19E-04 ZR93 + D 2.24E-04 9.51 E-05 6.18E-05 O.

3.19E-04 1.37E-03 1.48E-05 ZR95 + D 8.24E-05 1.99E-05 1.45E-05 O.

2.22E-05 1.25E-03 1.55E-05 ZR97 + D 1.07E-07 1.83E-08 8.36E-09 0.

N893M 1.38E-04 3,59E-05 1.15 E-05 O.

3.68E-05 2.09E 04 2.47E-06 1.85E-08 7.88E-05 1.00E-04 i

NB95 1.12E-05 4.59E-06 2.70E-06 0.

N897 2.44E 10 5.21 E-11 1.88E-11 0.

4.07E 11 2.37E-06 1.92E-05 3.37E-06 3.42E-04 9.05E-06 MO93 0.

6.46E-06 2.22E-07 0,

1.54E-06 3.40E-04 3.76E-06 MO99 + D 0.

1.18E-07 2.31 E-08 0.

1.89E-07 9.63E-05 3.48E-05 TC99M 9.9BE-13 2.06E-12 2.66E-11 0.

2.22E-11 5.79E-07 1.45E-06 4

TC99 2.09E-07 2.68E-07 8.85E-08 0.

2.49E-06 6.77E-04 7.82E-06 TC101 4.65E-14 5.88E-14 5.80E-13 0,

6.99E-? 3 4.17E-07 6.03E-07 RU103 + D 1.44E-06 0.

4.85E-07 0.

3.03E-06 3.94E-04 1.15E-05 RU105 + D 8.74E-10 0.

2.93E 10 0.

6.42E 10 1.12E-05 3.46E-05 RU106 + D 6.20E-05 O.

7.77E-06 0.

7.61 E-05 8.26E-03 1.17E-04 RH105 8.26E-09 5.41 E-09 3.63E-09 0.

1.50E-08 2.08E-05 1.37E-05 PD107 0.

4.92E-07 4.11 E-08 0.

2.75E-06 6.34E-05 7.33E-07 PD109 0.

3.92E-09 1.05E-09 0.

1.28E-08 1.68E-05 2.85E-05 AG110M + 0 7.13E-06 5.16E-06 3.57E-06 0.

7.80E-06 2.62E-03 2.36E-05 AG111 3.75E-07 1.45 E-07 7.75E-08 0.

3.05E-07 2.06E-04 3.02E-05 CD113M 0.

6.67E-04 2.64E-05 O.

5.80E-04 1.40E-03 1.65E-05 i

CD115M 0.

1.73E-04 6.19E-06 0.

9.41 E-05 1.47E-03 5.02E-05 i

SN123 2.09E-04 4.21 E-06 7.28E-06 4.27E-06 0.

2.22E-03 4.08E-05 i

SN125 + D 1.01 E-05 2.51 E-07 6.00E-07 2.47E-07 0.

6.43E-04 7.26E-05 SN126 + D 8.30E-04 1.44E-05 3.52E-05 3.84E-06 0.

4.93E-03 1.65E-05 SB124 2.71 E-05 3.97E-07 8.56E-06 7.18E-08 0.

1.8SE-03 4.22E-05 i

SB125 + D 3.69E-05 3.41 E-07 7.78E-06 4.45E-08 0.

1.17E-03 1.05E-05 SB126 I

3.08E-06 6.01 E-08 1.11 E-06 2.35E-08 0.

6.88E-04 5.33E-05 SB127 2.82E-07 5.04E-09 8.76E-08 3.60E-09 0.

1.54E-04 3.78E-05 i

TE125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.

3.19E-04 9.22E-06 TE127M + D 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81 E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE129M + D 1.01 E-05 4.35E-06 1.59E-06 3.91 E-06 2.27E-05 1.20E-03 4.93E-05 TE129 5.63E-11 2.48E-11 1.34E-11 4.82E 11 1.25E-10 2.14E-06 1.88E-05 TE131M + D 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51 E-05 I

TE131 + 0 1.24E 11 5.87E 12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E 06 TE132 + D 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 TE133M + D 6.13E-11 3.59E-11 2.74E-11 5.52E 11 1.72E-10 3.92E-06 1.59E-05 TE134 + D 3.18E-11 2.04E-11 1.68E-11 2.91 E-11 9.59E 11 2.93E-06 2.53E-06 1129 2.16E-05 1.59E-05 1.16E-05 1.04E-02 1.88E-05 O.

2.12E-07 1130 4.54E 06 9.91 E-06 3.98E-06 1.14E-03 1.09E-05 O.

1.42E-06 1131 + D 2.71 E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 O.

7.56E-07 4

45

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 1.7 (continued)

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM /50Y PER PCIINHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.21 E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.

1.36E-06 1133 + D 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 O.

1.54E-06 I

1134 6.58E-07 1.34E-06 4.75 E-07 3.18E-05 1.49E-06 0.

9.21 E-07 1135 + D 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05 E-06 0.

1.31 E-06 XE131M 0.

O.

6.77E-09 0.

XE133M 0.

O.

8.89E ' f O.

XE133 0.

O.

7.4.

39 0.

XE135M 0.

O.

8.05 E-09 0.

XE135 O.

O.

1.80E-08 0.

XE137 O.

O.

8.30E-08 0.

XE138 + D 0.

O.

9.78E-08 0.

CS134M + D 1.32E-07 2.10E-07 1.11 E-07 0.

8.50E-08 2.00E-08 1.16E-07 CS134 2.83E-04 5.02E-04 5.32E-05 O.

1.36E-04 5.69E-05 9.53E-07 CS135 1.00E-04 8.66E-05 4.73E-06 0.

2.58E-05 1.01 E-05 2.18E-07 CS136 3.45E-05 9.61 E-05 3.78E-05 O.

4.03E-05 8.40E-06 1.02E-06 CS137 + D 3.92E-04 4.37E-04 3.25 E-05 O.

1.23E-04 5.09E-05 9.53E-07 CS138 3.61 E-07 5.58E-07 2.84E-07 0.

2.93E-07 4.67E-08 6.26E-07 CS139 + D 2.32E-07 3.03E-07 1.22E-07 0.

1.65E-07 2.53E-08 1.33E-08 8A139 1.06E-09 7.03E-13 3.07E-11 0.

4.23E-13 4.25E-06 3.64E-05 8A140 + D 4.00E-05 4.00E-08 2.07E-06 0.

9.59E-09 1.14E-03 2.74E-05 8A141 + D 1.12E-10 7.70E-14 3.55E-12 0.

4.64E-14 2.12E-06 3.39E-06 8A142 + D 2.84E-11 2.36E-14 1.40E-12 0.

1.36E-14 1.11 E-06 4.95 E-07 LA140 3.61 E-07 1.43E-07 3.68E-08 0.

O.

1.20E-04 6.06E-05 LA141 4.85 E-09 1.40E-09 2.45E-10 0.

O.

1.22E-05 5.96E-05 LA142 7.36E-10 2.69E-10 6.46E-11 0.

O.

5.87E-06 4.25E-05 CE141 1.98E-05 1.19E-05 1.42E-06 0.

3.75 E-06 3.69E-04 1 54E-05 CE143 + D 2.09E-07 1.38E-07 1.58E-08 0.

4.03E-08 8.30E-05 3.55E-05 CE144 + D 2.28E-03 8.65 E-04 1.26E-04 0.

3.84E-04 7.03E-03 1.06E 04 PR143 1.00E-05 3.74E-06 4.99E-07 0.

1.41 E-06 3.09E-04 2.66E-05 PR144 3.42E-11 1.32E-11 1.72E-12 0.

4.80E-12 1.15 E-06 3.06E-06 i

ND147 + 0 5.67E-06 5.81 E-06 3.57E-07 0.

2.25 E-06 2.30E-04 2.23E-05 PM147 3.91 E-04 3.07E-05 1.56E-05 O.

4.93E-05 4.55 E-04 5.75E-06 PM148M + D 5.00E-05 1.24E-05 9.94E-06 0.

1.45E-05 1.22E-03 3.37E-05 PM148 3.34E-06 4.82E-07 2.44E-07 0.

5.76E-07 3.20E-04 6.04E-05 PM149 3.10E-07 4.08E-08 1.78E-08 0.

4.96E-08 6.50E-05 3.01 E-05 PM151 7.52E-08 1 10E-08 5.55E-09 0.

1.30E-08 3.25 E-05 2.58E-05 SM151 3.38E-04

6. +5E-05 1.63E-05 O.

5.24E-05 2.98E-04 3.46E-06 SM153 1.53E-07 1.18E-07 9.06E-09 0.

2.47E-08 3.70E-05 1.93E-05 EU152 7.83E-04 1.77E-04 1.72E-04 0.

5.94E-04 1.48E-03 9.88E-06 EU154 2.96E-03 3.46E-04 2.45E-04 0.

1.14E-03 3.05E-03 2.84E-05 EU155 5.97E-04 5.72E-05 3.46E-05 O.

1.58E-04 5.20E-04 5.19E-05 EU156 1.56E-05 9.59E-06 1.54E-06 0.

4.48E-06 6.12E-04 4.14E-05 T8160 1.12E 04 0.

1.40E-05 O.

3.20E-05 1.11 E-03 2.14E-05 HO166M 1.45E-03 3.07E-04 2.51 E-04 0.

4.22E-04 2.05 E-03 1.65 E-05 W181 4.86E-08 1.46E-08 1.67E-09 0.

O.

1.33E-05 2.63E-07 W185 1.57E-06 4.83E-07 5.58E-08 0.

O.

4.48E-04 1.12 E-05 W187 9.26E-09 6.44E-09 2.23E-09 0.

O.

2.83 E-05 2.54E-05 46

-1 i

\\

pal MADER NUCtFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 1.7 (continuad)

INFANT INHALATION DOSE COMMITMENT FACTOR ISOTOPE SONE LIVER TOTAL BODY THYROID D IN FIRST YR)

P8210 + D 8.62E-02 2.02E-02 3.43E-03 0.

6.85E-02 1.76E-01 3.79E-05 KIDNEY LUNG GI-LLI B1210 + D 0.

1.33E-05 1.18E-06 0.

1.03E-04 F.96E-03 3.27E-05 PO210 2.98E-03 5.63E-03 7.12E-04 0.

1.30E-02 2.40E-01 4.36E-05 RN222 + D 0.

O.

9.88E-06 0.

RA223 + D 1.56E-03 2.26E-06 3.12E-04 0.

RA224 + D 1.77E 04 4.00E-07 3.54E-05 O.

7.30E-06 7.91 E-02 3.42E-04 4.16E-05 2.25E-01 3.04E-04 RA225 + 0 2.57E-03 2.88E-06 5.13E-04 0.

5.31 E-05 2.57E-01 2.87E-04 RA226 + D 2.48E-01 1.46E-05 2.05E-01 0.

2.94E-04 7.83E-01 3.05E-04 RA228 + D 1.60E-01 7.61 E-06 1.80E-01 0.

1.53E-04 1.09E-00 5.19E-05 AC225 3.69E-03 4.72E-03 2.48E-04 0.

3.49E-04 1.96E-01 2.71 E-04 AC227+0 5.29E + 00 8.76E-01 3.28E-01 0.

1.86E-01 1.62E + 00 5.27E-05 TH227 + D 1.82E-03 3.03E-05 5.24E-05 O.

1.13E-04 3.27E-01 3.53E-04 TH228 + D 8.46E-01 1.10E-02 2.86E-02 0.

5.61 E-02 4.65E + 00 3.62E 04 TH229 1.34E + 01 1.82E-01 6.62E-01 0.

8.99E-01 1.22E + 01 3.29E-04 TH230 3.46E + 00 1.79E-01 9.65E-02 0,

8.82E-01 2.18E + 00 3.87E-05 TH232 + D 3.86E + 00 1.53E-01 2.29E-01 0.

7.54E-01 2.09E + 00 3.29E-05 TH234 1.33E-05 7.17E-07 3.84E-07 0.

2.70E-06 1.62E 7.40E-05 PA231 + D 9.10E + 00 3.00E-01 3.62E-01 0.

1.62E +00 3.85E-01 4.61 E-05 PA233 6.84E-06 1.32E-06 1.19E-06 0.

3.68E-06 2.19E-04 9.04E 06 U232 + D 2.57E-01 0.

2.13E 02 0.

2.40E-02 1.49E + 00 4.36E-05 U233 + D 5.44E-02 0.

3.83E-03 0.

1.09E-02 3.56E-01 4.03E-05 U234 5.22E-02 0.

3.75E-03 0.

1.07E-02 3.49E-01 3.95E-05 U235 + D 5.01 E-02 0,

3.52E-03 0.

1.01 E-02 3.28E-01 5.02E-05 U336 5.01 E-02 0.

3.60E-03 0,

1.03E-02 3.35E-01 3.71 E-05 U237 3.25E-07 0.

8.65E-08 0.

8.08E-07 9.13E-05 1.31 E-05 U238 + D 4.79E-02 0.

3.29E-03 0.

9.40E-03 3.06E-01 3.54E-05 NP237 + D 3.03E + 00 2.32E-01 1.26E-01 0.

7.69E-01 3.49E-01 5.10E-05 NP238 2.67E 6.73E-08 4.16E-08 0.

1.47E-07 9.19E-05 2.58E-05 '

NP239 2.65E-07 2.37E-08 1.34E-08 0.

4.73E-08 4.25E-05 1.78E-05 PU238 5.02E + 00 6.33E-01 1.27E-01 0.

4.64E-01 9.03E-01 4.69E-05 PU239 5.50E + 00 6.72E-01 1.34E-01 0.

4.95E-01 8.47E-01 4.28E-05 PU240_

6.49E + 00 6.71 E-01 1.34E-01 0.

4.94E-01 8.47E-01 4.36E-05 PU241 + D 1.55E-01 6.69E-03 3.11 E-03 0.

1.15E-02 7.62E-04 8.97E-07 PU242 5.09E + 00 6.47E-01 1.29E-01 0.

4.77E-01 8.15E-01 4.20E-05 PU244 5.95E + 00 7.40E-01 1.48E-01 0.

5.46E-01 9.33E-01 6.26E-05 AM241 1.84E+00 8.44E-01 1.31 E-01 0.

7.94E-01 4.06E-01 4.78E-05 AM242M 1.90E+00 8.24E 01 1.35E-01 0.

8.03E-01 1.64E-01 6.01 E-05 AM243 1.82E + 00 8.10E-01 1.27E-01 0.

7.72E-01 3.85E-01 5.60E-05 CM242 8.58E-02 7.44E-02 5.70E-03 0.

1.69E 02 2.97E-01 5.10E-05 CM243 1.73E + 00 7.94E-01 1.06E-01 0.

3.91 E-01 4.24E-01 5.02E-05 CM244 1.43E + 00 7.04E-01 8.89E-02 0.

3.21E-01 4.08E-01 4.86E-05 CM245 2.26E + 00 8.80E-01 1.36E-01 0.

5.23E-01 3.92E-01 4.53E-05 CM246 2.24E + 00 8.79E-01 1.36E-01 0.

5.23E-01 3.99E-01 4.45E-05 CM247 + D 2.18E + 00 8.64E-01 1.33E-01 0,

5.15E-01 3.92E-01 5.85E-05 CM248 1.82E + 01 7.12E + 00 1.10E + 00 0.

4.24E + 00 3.23E + 00 9.43E-04 CF252 4.26E + 00 0.

1.01E-01 0.

O.

1.37E + 00 1.85E-04 47

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MAhlUAL Revision 10 i

i TABLE 1.7 (contd)

CHILD INHALATION DOSE COMMITMENT FACTORS (MREM /50Y PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3' O.

3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 BE10 8.43E-04 9.83E-05 2.12E-05 O.

O.

7.41 E-04 1.72E-05 i

i C14 9.70E-06 1.82E-06 1.82E-06

' 1.82 E-06 1.82E-06 1.82E-06 1.82E-06 l

N13 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 F18 1.88E-06 0.

1.85 E-07 0.

O.

3.37E-07 NA22 4.41 E-05 4.41 E-05 4.41 E-05 4.41 E-05 4.41 E-05 4.41 E-05 4.41 E-05 NA24 4.35 E-06 4.35E-06 4.35E-06 4.35 E-06 4.35E-06 4.35 E-06 4.35E-06 P32 7.04E-04 3.09E-05 2.67E-05 O.

O.

1.14E-05 AR39 0.

O.

4.89E-09 0.

AR41 0.

O.

1.68E-08 0.

i CA41 7.06E-05 O.

7.70E-06 0.

O.

7.21 E-02 2.94E 07 SC46 1.97E-04 2.70E-04 1.04E-04 0.

2.39E-04 0.

2.45 E-05 CR51 0.

O.

4.17E-08 2.31 E-08 6.57E-09 4.59E-06 2.93E-07 MN54 0.

1.16E-05 2.57E-06 0.

2.71 E-06 4.26E-04 6.19E-06 MN56 0.

4.48E-10 8.43E-11 0.

4.52E-10 3.55E-06 3.33E-05 FESS 1.28E-05 6.80E-06 2.10E-06 0.

O.

3.00E-05 7.75E-07 l

FE59 5.59E-06 9.04E-06 4.51 E-06 0.

O.

3.43E-04 1.91 E-05 C057 0.

2.44E-07 2.88E-07 0.

O.

1.37E-04 3.58E-06 C058 0.

4.79E-07 8.55 E-07 0.

O.

2.99E-04 9.29E-06 CO60 0.

3.55 E-06 6.12E-06 0.

O.

1.91 E-03 2.60E-05 i

N159 1.66E-05 4.87E-06 2.83E-06 0.

O.

2.73E-05 6.29E-07 NI63 2.22E-04 1.25 E-05 7.56E-06 0.

O.

7.43E-05 1.71 E-06 4

j N165 8.08E-10 7.99E-11 4.44E-11 0.

O.

2.21 E-06 2.27E-05 CU64 0.

5.39E-10 2.90E-10 0.

1.63E-09 2.59E-06 9.92E-06 ZN65 1.15 E-05 3.06E-05 1.90E-05 O.

1.93E-05 2.69E-04 4.41 E-06 ZN69M + D 4.26E-09 7.28E-09 8.59E-10 0.

4.22E-09 7.36E-06 2.71 E-05 ZN69 1.81 E-11 2.61 E-11 2.41E 12 0.

1.58E-11 3.84E-07 2.75E-06 SE79 0.

1.23E-06 2.60E-07 0.

1.71 E-06 1.49E-04 3.43E-06 BR82 0.

O.

5.66E-06 0.

O.

BR83 + D 0.

O.

1.28E-07 0.

O.

BR84 0.

O.

1.48E-07 0.

O.

BR85 0.

O.

6.84E-09 0.

O.

e KR83M 0.

O.

1.22E-09 0.

j KR85M 0.

O.

6.58E-09 0.

KR85 O.

O.

5.66E-09 0.

KR87 0.

O.

3.38E-08 0.

KR88 + D 0.

O.

6.99E-08 0.

KR89 0.

O.

4.55 E-08 0.

RB86 0.

5.36E-05 3.09E-05 O.

O.

2.16E-06 RB87 0.

3.16E-05 1.37E-05 O.

O.

2.96E-07 RB88 0.

1.52E-07 9.90E-08 0.

O.

4.66E-09 RB89 + D 0.

9.33E-08 7.83E-08 0.

O.

5.11 E-10 l

SR89 + D 1.62E-04 0.

4.66E-06 0.

O.

5.83E-04 4.52E-05 SR90 + D 2.73E-02 0.

1.74E-03 0.

O.

3.99E-03 9.28E-05 SR91 + D 3.28E-08 0.

1.24E-09 0.

O.

1.44E-05 4.70E-05 j

SR92 + D 3.54E-09 0.

1.42E-10 0.

O.

6.49E-06 6.55 E-05

includes a 50% increase to account for percutaneous transpiration.

48

(

PAllAADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL i

Revision 10 i

j TABLE 1.7 fcontd)

CHILD INHALATION DOSE COMMITMENT FACTORS ISOTOPE BONE LIVER TOTAL 8ODY THYROID IN FIRST YR)

Y90 1.11 E-06 0.

2.99E-08 0.

O.

7.07E-05 7.24E-05 KIDNEY LUNG GI-LLI Y91M + D 1.37E-10 0.

4.98E-12 0.

O.

7.60E-07 4.64E-07 Y91 2.47E 04 0.

6.59E-06 0.

O.

7.10E-04 4.97E-05

)

Y92 5.50E-09 0.

1.57E 10 0.

O.

6.46E 06 6.46E-05 Y93 5.04E-08 0.

1.38E-09 0.

O.

2.01E 05 1.05E-04 ZR93 + D 2.07E-04 ' 7.80E-05 5.55E-05 O.

3.00E-04 7.10E-04 1.47E-05 ZR95 + D 5.13E-05 1.13E-05 1.00E-05 0,

1.61 E-05 6.03E-04 1.65E-05 ZR97 + D 5.07E-08 7.34E-09 4.32E-09 0.

1.05E-08 3.06E-05 9.49E-05 NB93M 1.27E-04 3.17E-05 1N E-05 O.

3.44E-05 1.04E-04 2.45E-06 NB95 6.35E-06 2.48E-06

1.,7E-06 0.

N897 1.16E-10 2.08E-11 9.74E-12 0.

2.33E-06 1.66E-04 1.00E-05 MO93 0.

3.76E-06 1.35E-07 0.

2.31E 11 9.23E-07 7.52E-06 i

MO99 + D 0.

4.66E 1.15E-08 0.

1.06E-07 3.66E-05 3.42E-05 1.06E-06 1.70E-04 3.78E-06 TC99M 4.81E 13 9.41E 13 1.56E-11 0.

1.37E-11 2.57E-07 1.30E-06 TC99 1.34E-07 ' 1.49E 07 5.35E-08 0.

TC101 2.19E-14 2.30E 14 2.91E 13 0.

3.92E 13 1.58E-07 4.41 E-09 1.75E-06 3.37E-04 7.75E-06 RU103 + D 7.55E-07 0.

2.90E-07 0.

1.90E-06 1.79E-04 1.21E-05 RU105 + D 4.13E-10 0.

1.50E-10 0.

3.63E-10 4.30E-06 2.69E-05 RU106 + D 3.68E-05 O.

4.57E-06 0.

4.97E-05 3.87E-03 1.16E-04 RH105 3.91 E-09 2.10E-09 1.79E-09 0.

8.39E-09 7.82E-06 1.33E-05 i

PD107 0.

2.65E-07 2.51 E-08 0.

1.97E-06 3.16E-05 7.26E-07 PD109 0.

1.48E-09 4.95E-10 0.

7.06E-09 6.16E-06 2.59E-05 AG110M + D 4.56E46 3.08E-06 2.47E-06 0.

5.74E-06 1.48E-03 2.71 E-05 AG111 1.81 E-07 5.68E-08 3.75E-08 0.

1.71 E-07 7.73E-05 2.98E-05 CD113M 0.

4.93E-04 2.12E-05 O.

5.13E-04 6.94E-04 1.63E-05 CD115M 0.

7.88E-05 3.39E-05 O.

5.93E-05 0.86E-04 4.97E-05 j

SN123 1.29E-04 2.14E-06 4.19E-06 2.27E'06 0.

9.59E-04 4.05E-05 SN125 + D 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0.

2.43E-04 7.17E-05 i

SN126 + D 6.23E-04 1.04E 05 2.36E-05 2.84E-06 0.

3.02E-03 1.63E-05 S8124 1.55E-05 2.00E-07 5.41 E-06 3.41 E-08 0.

8.76E-04 4.43E-05 S8125 + D 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.

6.27E-04 1.09E-05 i

S8126 1.72E-06 2.62E-08 6.16E-07 1.00E-08 0.

2.86E-04 5.67E-05 I

i S8127 1.36E-07 2.09E-09 4.70E-08 1.51 E-09 0.

6.17E-05 3.82E-05 i

TE125M

- 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.

1.29E-04 9.13E-06 i

TE127M + D 6.72E-06 2.31 E-06 8.16E-07 1.64E-06 1.72E 05 4.00E-04 1.93E-05 i

TE127 7.49E-10 2.57E 10 1.65E-10 5.30E 10 1.91 E-09

'2.71 E-06 1.52E-05 TE129M + D 5.19E 06 1.85E-06 8.22E-07 1.71 E-06 1.36E-05 4.76E-04 4.91 E-05 TE129 2.64E-11 9.4 5E-12 6.44E 12 1.93E 11 6.94E-11 7.93E-07 6.89E-06 TE131M + D 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E 05 TE131 + D 5.87E-12 2.28E-12 1.78E-12 4.59E 12 1.59E-11 5.55E-07 3.60E-07 1

TE132 + 0 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E 05 TE133M + D 2.93E-11 1.51 E-11 1.50E-11 2.32E 11 1.01 E-10 1.60E-06 4.77E-C6 j

TE134 + D 1.53E 11 8.81E 12 9.40E-12 1.24E-11 5.71 E-11 1.23E-06 4.87E 07 i

1129 1.05E-05 6.40E-06 5.71E-06 4.28E-03 1.08E-05 O.

1130 2.21 E-06 4.43E-06 2.28E-06 4.99E-04 6.61 E-06 0.

1.38E-06 2.15E 07 1131 + D 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 O.

7.68E-07 49 1

~

PALISADES NUCLEAR PLANT OFFSITE DOFd CALCULATION MANUAL Revision 10 TABLE 1.7 (contdl CHILD INHALATION DOSE COMMITMENT FACTORS (MREM /50Y PER PCIINHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.

8.65 E-07 1133 + D 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.

1.48E-06 1134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0.

2.58E-07 1135 + D 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0.

1.20E-06 XE131M 0.

O.

3.30E-09 0.

XE133M 0.

O.

4.36E-09 0.

XE133 0.

O.

3.66E-09 0.

XE135M O.

O.

4.48E-09 0.

XE135 O.

O.

9.09E-09 0.

XE137 0.

O.

4.07E-08 0.

XE138 + D 0.

O.

5.17E-08 0.

CS134M + D 6.33E-08 8.92E-08 6.12E-08 0.

4.94E-08 8.35E-09 7.92E-08 CS134 1.76E-04 2.74E-04 6.07E-05 O.

8.93E-05 3.27E-05 1.04E-06 CS135 6.23E-05 4.13E-05 4.45E-06 0.

1.53E-05 5.22E-06 2.17E-07 CS136 1.76E-05 4.62E-05 3.14E-05 O.

2.58E-05 3.93E-06 1.13E-06 CS137 + D 2.45E-04 2.23 E-04 3.47E-05 O.

7.63E-05 2.81 E-05 9.78E-07 CS138 1.71 E-07 2.27E-07 1.50E-07 0.

1.68E-07 1.84E-08 7.29E-08 CS139 + D 1.09E-07 1.15E-07 5.80E-08 0.

9.08E-08 9.36E-09 7.23E 12 BA139 4.98E-10 2.66E 13 1.45E-11 0.

2.33E-13 1.56E-06 1.56E-05 BA140 + D 2.00E-05 1.75E-08 1.17E-06 0.

5.71 E-09 4.71 E-04 2.75E-05 BA141 + D 5.29E-11 2.95E-14 1.72E-12 0.

2.56E-14 7.89E-07 7.44E-08 BA142 + D 1.35E-11 9.73E-15 7.54E-13 0.

7.87E-15 4.44E-07 7.41 E-10 LA140 1.74E-07 6.08E-08 2.04E-08 0.

O.

4.94E-05 6.10E-05 LA141 2.28E-09 5.31 E-10 1.15 E-10 0.

O.

4.48E-06 4.37E-05 LA142 3.50E-10 1.11 E-10 3.49E-11 0.

O.

2.35E-06 2.05 E-05 CE141 1.06E-05 5.28E-06 7.83E-07 0.

2.31 E-06 1.47E-04 1.53E-05 CE143 + D 9.89E-08 5.37E-08 7.77E-09 0.

2.26E-08 3.12E-05 3.44E-05 CE144 + D 1.83E-03 5.72E-04 9.77E-05 O.

3.17E-04 3.23E-03 1.05E-04 PR143 4.99E-06 1.50E-06 2.47E-07 0,

8.11 E-07 1.17E-04 2.63 E-05 i

PR144 1.61 E-11 4.99E-12 8.10E-13 0.

2.64E-12 4.23E-07 5.32 E-08 ND147 + D 2.92E-06 2.36E-06 1.84E-07 0.

1.30E-06 8.87E-05 2.22E-05 PM147 3.52E-04 2.52E-05 1.36E-05 O.

4.45E-05 2.20E-04 5.70E-06 i

PM148M + D 3.31 E-05 6.55E-06 6.55 E-06 0.

9.74E-06 5.72E-04 3.58E-05 j

PM148 1.61 E-06 1.94E-07 1.25 E-07 0.

3.30E-07 1.24E-04 6.01 E-05 PM149 1.47E-07 1.56E-08 8.45E-09 0.

2.75E-08 2.40E-05 2.92E-05 PM151 3.57E-08 4.33E-09 2.82E-09 0.

7.35E-09 1.24E-05 2.50E-05 SM151 3.14E-04 4.75 E-05 1.49E-05 O.

4.89E-05 1.48E-04 3.43E-06 i

SM153 7.24E-08 4.51 E-08 4.35E-09 0.

1.37E-08 1.37E-05 1.8'7E-05 EU152 7.42E-04 1.37E-04 1.61 E-04 0.

5.73E-04 9.00E-04 1.14E-05 EU154 2.74E-03 2.49E-04 2.27E-04 0.

1.09E-03 1.66E-03 2.98E-05 EU155 5.60E-04 4.05E-05 3.18E-05 O.

1.51 E-04 2.79E-04 5.39E-05 EU156 7.89E-06 4.23E-06 8.75E-07 0.

2.72E-06 2.54E-04 4.24E-05 TB160 7.79E-05 O.

9.67E-06 0.

2.32E-05 5.34E-04 2.28E-05 HO166M 1.34E-03 2.81 E-04 2.37E-04 0.

4.01 E-04 1.13E-03 1.63E-05 W181 2.66E-08 6.52E-09 8.99E-10 O.

O.

5.71 E-06 2.61 E-07 W185 8.31 E-07 2.08E-07 2.91 E-08 0.

O.

1.86E-04 1.11 E-05 W187 4.41 E-09 2.61 E-09 1.17 E-09 0.

O.

1.11 E-05 2.46E-05 50

PAUSADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 l

TABLE 1.7 (contd)

CHILD INHALATION DOSE COMMITMENT FACTORS ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1

PB210 + D 8.03E-02 1.85 E-02 3.18E-03 0.

6.31 E-02 8.74E-02 3.75 E-05 B1210 + D 0.

5.11 E-06 5.65E-07 0.

5.76E-05 3.70E-03 3.21 E-05 PO210 1.70E-03 2.76E-03 4.09E-04 0.

8 85E-03 1.05E-01 4.32E-05 RN222 + D 0.

O.

4.82E-06 0.

RA223 + D 7.69E-04 8.89E-07 1.54E-04 0.

2.36E-05 8.48E-02 3.00E-04

)

RA224 + D 8.44E-05 1.53E-07 1.69E-05 O.

4.06E-06 2.92E-02 3.34E-04 RA225 + D 1.28E-03 1.14E-06 2.56E-04 0.

3.02E-05 9.74E-02 2.84E-04 RA226 + D 2.34E-01 7.66E-06 1.92E-01 0.

2.03E-04 3.90E-01 3.02E-04 RA228 + D 1.49E-01 3.94E-06 1.68E-01 0.

1.04E-04 5.37E-01 5.14E-05 AC225 1.81 E-03 1.87E-03 1.21 E-04 0.

1.99E-04 7.37E 02 2.67E-04 AC227 + D 4.96E + 00 8.05E-01 3.07E-01 0.

1.77E-01 8.04E-01 5.22E-05 TH227 + D 9.24E-04 1.26E-05 2.67E-05 O.

6.67E-05 1.26E-01 3.49E-04 TH228 + D 8.06E-01 1.04E-02 2.72E-02 0.

5.41 E-02 3.34E + 00 3.59E-04 i

TH229 1.28E + 01 1.76E-01 6.31 E-01 0.

8.68E-01 1.04E + 01 3.27E-04 TH230 3.30E + 00 1.73E-01 9.20E-02 0.

8.52E-01 1.85E + 00 3.84E-05 TH232 + D 3.68E + 00 1.47E-01 1.28E-01 0.

7.28E-01 1.77E + 00 3.27E-05 TH234 6.94E-06 3,07E-07 2.00E-07 0.

1.62E-06 6.31 E-04 7.32E-05 PA231 + D 8.62E + 00 2.86E-01 3.43E-01 0.

1.56E + 00 1.92E-01 4.57E-05 PA233 4.14E-06 6.48E-07 7.25E-07 0.

2.38E-06 9.77E-05 8.95E-06 U232 + D 2.19E-01 0.

1.56E-02 0.

1.67E-02 7.42E-01 4.33E-05 U233+D 4.64E-02 0.

2.82E-03 0.

7.62E-03 1.77E-01 4.00E-05 U234 4.46E-02 0.

2.76E-03 0.

7.47E-03 1.74E-01 3.92E-05 U235 + 0 4.27E-02 0.

2.59E-03 0.

7.01 E-03 1.63E 01 4.98E-05 U236 4.27E-02 0.

2.65E-03 0.

7.16E-03 1.67E-01 3.67E-05 U237 1.57E-07 0.

4.17E-08 0.

4.53E-07 3.40E-05 1.29E-05 U238 + D 4.09E-02 0.

2.42E-03 0.

6.55E-03 1.53E 01 3.51 E-05 NP237 + D 2.88E + 00 2.21 E-01 1.19E-01 0.

7.41 E-01 1.74E-01 5.06E-05 NP238 1.26E-06 2.56E-08 1.97E-08 0,

8.16E-08 3.39E-05 2.50E-05 NP239 1.26E-07 9.04E-09 6.35E-09 0.

2.63E-08 1.57E-05 1.73E-05 PU238 4.77E + 00 6.05E-01 1.21 E-01 0.

4.47E-01 6.08E-01 4.65E-05 PU239 5.24E + 00 6.44E-01 1.28E-01 0.

4.78E-01 5.72E-01 4.24E-05 PU240 5.23E + 00 6.43E-01 1.27E-01 0.

4.77E-01 5.71 E-01 4.33E-05 PU241 + D 1.46E-01 6.33E-03 2.93E-03 0.

1.10E-02 5.06E-04 8.90E-07 PU242 4.85E + 00 6.20E-01 1.23E-01 0.

4.60E-01 5.50E-01 4.16E-05 PU244 5.67E + 00 7.10E-01 1.41E-01 0.

5.27E-01 6.30E-01 6.20E-05 AM241 1.74E + 00 7.85 E-01 1.24E-01 0.

7.63E-01 2.02E-01 4.73E-05 AM242M 1.79E + 00 7.65 E-01 1.27E-01 0.

7.71 E-01 8.14E-02 5.96E-05 AM243 1.72E + 00 7.53E-01 1.20E-01 0.

7.42E-01 1.92E-01 5.5 5 E-05 CM242 6.33E-02 4.84 E-02 4.20E-03 0.

1.34E-02 1.31 E-01 5.06E-05 CM243 1.61 E + 00 7.33E-01 9.95 E-02 0.

3.74E-01 2.10E-01 4.98E-05 CM244 1.33E + 00 6.48E-01 8.31 E-02 0.

3.06E-01 2.02E-01 4.82E-05 CM245 2.14E + 00 8.16E-01 1.28E-01 0.

5.03E-01 1.95E-01 4.49E-05 CM246 2.13E + 00 8.15E-01 1.28E-01 0.

5.03E-01 1.99E-01 4.41 E-05 CM247 + D 2.07E + 00 8.02E-01 1.26E-01 0.

4.95 E-01 1.95E-01 5.80E-05 CM248 1.72E + 01 6.61 E + 00 1.04E + 00 0.

4.08E + 00 1.61 E + 00 9.35E-04 CF252 3.92E + 00 0.

9.33E-02 0.

O.

6.62E-01 1.84E-04 51

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL 4

1 l

Revision 10 -

TABLE 1.7 (contd)

TEEN INHALATION DOSE COMMITMENT FACTORS (MREM /50Y PER PCI INHALED IN FIRST YR) j ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI i

H3*

0.

1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 BE10 2.78E-04 4.33E-05 7.09E-06 0.

O.

3.84E-04 1.77E-05 l

C14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 N13 8.65E-09 8.65E-09 8.65E-09 8.65 E-09 8.65 E-09 8.65 E-09 8.65 E-09 l

F18 6.52E-07 0.

7.10E-08 0.

O.

3.89E-08 NA22 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05 NA24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P32 2.36E-04 1.37E-05 8.95E-06 0.

O.

1.16E-05 AR39 0.

O.

4.00E-09 0.

+

AR41 0.

O.

1.44E-08 0.

i l

i CA41 4.05E-05 O.

4.38E-06 0.

O.

1.01 E-01 3.03E-07 l

SC46 7.24E-05 1.41 E-04 4.18E-05 O.

1.35E-04 0.

2.98E-05 CR51 0.

O.

1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75 E-07 MN54 0.

6.39E-06 1.05E-06 0.

1.59E-06 2.48E-04 8.35E-06 i

MN56 0.

2.12 E-10 3.15E-11 0.

2.24F-10 1.90E-06 7.18E-06 i

FESS 4.18E-06 2.98E-06 6.93E-07 0.

O.

1.55E-05 7.99E-07 FE59 1.99E-06 4.62E-06 1.79E-06 0.

O.

1.91 E-04 2.23E-05 j

C057 0.

1.18E-07 1.15 E-07 0.

O.

7.33E-05 3.93E-06 C058 0.

2.59E-07 3.47E-07 0.

O.

1.68E-04 1.19E-05 l

CO60 0.

1.89E-06 2.48E-06 0.

O.

1.09E-03 3.24E-05 NI59 5.44E-06 2.02E-06 9.24E-07 0.

O.

1.41 E-05 6.48E-07 l

N163 7.25E-05 5.43E-06 2.47E-06 0.

O.

3.84E-05 1.77E-06 l

N165 2.73E-10 3.66E-11 1.59E-11 0.

O.

1.17E-06 4.59E-06 l

CU64 0.

2.54E-10 1.06E-10 0.

8.01 E-10 1.39E-06 7.68E-06 ZN65 4.82E-06 1.67E-05 7.80E-06 0.

1.08E-05 1.55E-04 5.83E-06 ZN69M + D 1.44E-09 3.39E-09 3

.10 0.

2.06E-09 3.92E-06 2.14E-05 i

l ZN69 6.04E-12 1.15E 11 8 ; M-13 0.

7.53E-12 1.98E-07 3.56E-08 i

SE79 0.

5.43E-07 8.71 E-08 0.

8.13E-07 7.71 E-05 3.53E-06 i

BR82 0.

O.

2.28E-06 0.

O.

i BR83 + D 0.

O.

4.30E-08 0.

O.

O, i

BR84 0.

O.

5.41 E-08 0.

O.

l BR85 O.

O.

2.29E-09 0.

O.

KR83M 0.

O.

9.97E-10 0.

KR85M 0.

O.

5.46E-09 0.

KR85 O.

O.

4.63E-09 0.

KR87 0.

O.

2.82E-08 0.

KR88 + D 0.

O.

5.81 E-08 0.

l KR89 0.

O.

3.85 E-08 0.

RB86 0.

2.38E-05 1.05E-05 O.

O.

2.21 E-06 RB87 0.

1.40E-05 4.58E-06 0.

O.

3.05 E-07 R888 0.

6.82E-08 3.40E-08 0.

O.

3.65E-15 RB89 + D 0.

4.40E-08 2.91 E-08 0.

O.

4.22 E-17 SR89 + D 5.43E-05 O.

1.56E-06 0.

O.

3.02E-04 4.64E-05 i

SR90 + D 1.35E-02 0.

8.35E-04 0.

O.

2.06E-03 9.56E-05 4

SR91 + D 1.10E-08 0.

4.39E-10 0.

O.

7.59E-06 3.24E-05 SR92 + D 1.19E-09 0.

5.08E 11 0.

O.

3.43E-06 1.49E-05 e

' Includes a 50% increase to account for percutaneous transpiration.

i 52 a

PALISADES NUC1FAR PLANT

\\

OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 1.7 fcontdl TEEN INHALATION DOSE COMMITMENT FACTORS (M ISOTOPE BONE LIVER TOTAL BODY THYR 010 CI INHALED IN FIRST YRI Y90 3.73E-07 0.

KIDNEY LUNG GI-LLI Y91M + D 4.63E-11 0.

1.00E-08 0.

O.

3.6BE-05 6.99E-05 Y91 1.77E-12 0.

O.

8.26E-05 O.

4.00E-07 3.77E-09 2.21 E-06 0.

O.

Y92 1.84E-09 0.

3.67E-04 5.11 E-05 5.36E-11 0.

O.

Y93 1.69E-08 0.

3.35E-06 2.06E-05 4.65E-10 0.

O.

ZR93 + D 6.83E-05 3.38E-05 1.84E-05 O.

1.16E-04 3.67E-04 1.60E-05 i

1.04E-05 7.24E 05 2R95 + D 1.82E-05 5.73E-06 3.94E-06 0.

ZR97+D 1.72E-08 3.40E-09 1.57E-09 0.

8.42E-06 3.36E-04 1.86E-05 NB93M 4.14E-05 1.36E-05 3.41 E-06 0.

5.15E-09 1.62E-05 7.88E-05 N895 2.32E-06 1.29E-06 7.08E-07 0.

1.59E-05 5.36E-05 2.52E-06 N897 3.92E-11 9.72E-12 3.55E-12 0.

1.25E-06 9.39E-05 1.21 E-05 i

MO93 0,

1.66E-06 4.52E-08 0.

1.14E-11 4.91 E-07 2.71 E-07 MO99 + D 0.

5.06E-07 8.81 E-05 3.99E-06 2.11 E-08 4.03E-09 0.

TC99M 1.73E-13 4.83E-13 6.24E 12 0.

5.14E 08 1.92E-05 3.36E-05 TC99 4.48E-08 6.58E-08 1.79E-08 0.

8.35E-07 1.74E-04 7.99E-06 7.20E-12 1.44E-07 7.66E-07 TC101 7.40E 15 1.05E-14 1.03E-13 0.

RU103 + D 2.63E-07 0.

1.90E-13 8.34E-08 1.09E 16 1.12E-07 0.

9.29E-07 9.79E-05 1.36E-05 RU105 + D 1.40E 10 0.

5.42E-11 0.

1.76E-10 2.27E-06 1.13E-05 RU106 + D 1.23E-05 O.

1.55E-06 0.

2.38E-05 2.01E-03 1.20E-04 RH105 1.32E-09 9.48E-10 6.24E-10 0.

PD107 0.

4.04E-09 4.09E-06 1.23E-05 1.17E-07 8.39E-09 0.

9.39E-07 1.63E-05 7.49E-07 PD109 0.

6.56E 10 1.66E-10 0.

3.36E-09 3.19E-06 1.96E-05 AG110M + D 1.73E-06 1.64E-06 9.99E-07 0.

3.13E-06 8.44E-04 3.41 E-05 AG111 6.07E-08 2.52E-08 1.26E-08 0.

8.17E-08 4.00E-05 3.00E-05 CD113M 0.

2.17E-04 7.10E-06 0.

2.43E-04 3.59E-04 1.68E-05 CD115M 0.

3.48E-05 1.14E-06 0.

2.82E-05 3.03E-04 5.10E-05 SN123 4.31 E-05 9.44E 07 1.40E-06 7.55E-07 0.

SN125+D 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0.

1.26E-04 7.29E-05 4.96E-04 4.16E 05 SN126 + D 2.18E-04 5.39E-06 8.24E-06 1.42E-06 0.

S8124 5.38E-06 9.92E-OB 2.10E-06 1.22E-08 0.

1.72E-03 1.68E-05

$8125 + D 9.23E-06 1.01 E-07 2.15E-06 8.80E-09 0.

3.42E-04 1.24E-05 4.81 E-04 4.98E-05

$8126 6.19E-07 1.27E-08 2.23E-07 3.50E-09 0.

SB127 4.64E-08 9.92E-10 1.75 E-08 5.21 E-10 0.

1.55E-04 6.01E 05 TE125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0.

3.31 E-05 3.94E-05 TE127M + D 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E 04 1.99E-05 6.70E-05 9.38E-06 TE127 2.51 E-10 1.14E 10 5.52E-11 1.77E 10 9.10E 10 1.40E-06 1.01 E-05 TE129M + D 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE129 8.87E-12 4.22E-12 2.20E-12 6.48E 12 3.32E-11 4.12E-07 2.02E-07 TE131M + D 1.23E-08 7.51 E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-06 TE131 + D 1.97E-12 1.04E-12 6.30E-13 1.55 E-12 7.72E-12 2.92E-07 1 M00 TE132 + 0 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 6 % Ob TE133M + D 1.01E 11 7.33E 12 5.71E 12 8.18E 12 5.07E 11 8.71 E-07 i 3E.O '

TE134 + D 5.31 E-12 4.35E 12 3.64E 12 4.46E 12 2.91E 11 6.75E-07 12 he 1129 3.53E-06 2.94E-06 4.90E-06 3.66E-03 5.26E-06 0.

1130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.

1.1003 1131 + D 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05 E-05 O.

2..'EC /

8.116-07 53

=-

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL i

Revision 10 i

1 J

TABLE 1.7 (contd)

TEEN INHALATION DOSE COMMITMENT FACTORS (MREM /50Y PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KlDNEY LUNG GI-LLI 1132 1.99E-07 5.47E-07 1.97E-07 1.89 E-05 8.65E-07 0.

1.59E-07 1133 + D 1.52E-06 2.56E-06 7.78 E-07 3.65E-04 4.49E-06 0.

1.29E-06 1134 1.11 E-07 2.90E-07 1.05 E-07 4.94E-06 4.58E-07 0.

2.55E-09 1135 + D 4.62E-07 1.18 E-06 4.36E-07 7.76E-05 1.86E-06 0,

8.69E-07 l

XE131M 0.

O.

2.70E-09 0.

XE133M 0.

O.

3.59E-09 0.

XE133 0.

O.

2.99E-09 0.

XE135M 0.

O.

3.88E-09 0.

XE135 O.

O.

7.55E-09 0.

XE137 0.

O.

3.33E-08 0.

j XE138 + D 0.

O.

4.38E-08 0.

CS134M + D 2.20E-08 4.35 E-08 2.35E-08 0.

2.54E-08 4.56E-09 2.02E-08 CS134 6.28 E-05 1.41 E-04 6.86E-05 O.

4.69E-05 1.03E-05 1.22E-06 CS135 2.08E-05 1.82E-05 4.47E-06 0.

7.30E-06 2.70E-06 2.23E-07 CS136 6.44E-06 2.42E-05 1.71 E-05 O.

1.38E-05 2.22E-06 1.36E-06 CS137 + D 8.38E-05 1.06E-04 3.89E-05 O.

3.80E-05 1.51 E-05 1.06E-06 CS138 5.82E-08 1.07E-07 5.58E-08 0.

8.28E-08 9.84E-09 3.38E-11 l

CS139 + D 3.65 E-08 5.12E-08 1.97E-08 0.

4.34E-08 4.86E-09 1.66E-23 BA139 1.67E-10 1.18E-13 4.87E-12 0.

1.11 E-13 8.08E-07 8.06E-07 i

BA140 + D 6.84E-06 8.38E-09 4.40E-07 0.

2.85E-09 2.54E-04 2.86E-05 BA141 + D 1.78E 11 1.32E-14 5.93E-13 0.

1.23E-14 4.11 E-07 9.33E-14 BA142 + D 4.62E-12 4.63E-15 2.84E-13 0.

3.92E-15 2.39E-07 5.99E-20 LA140 5.99E-08 2.95 E-08 7.82E-09 0.

O.

2.68E-05 6.09E-05 LA141 7.63E-10 2.35E-10 3.87E 11 0.

O.

2.31 E-06 1.54E-05 LA142 1.20E-10 5.31 E-11 1.32E-11 0.

O.

1.27E-06 1.50E-06 4

CE141 3.55 E-06 2.37 E-06 2.71 E-07 0.

1.11 E-06 7.67E-05 1.58E-05 I

CE143 + D 3.32E-08 2.42E-08 2.70E-09 0.

1.08E-08 1.63E-05 3.19E-05 CEi44 + D 6.11 E-04 2.53E-04 3.28E-05 O.

1.51 E-04 1.67E-03 1.08E-04 PR143 1.67E-06 6.64E-07 8.28E-08 0.

3.86E-07 6.04E-05 2.67E-05 PP.144 5.37E-12 2.20E-12 2.72E 13 0.

1.26E-12 2.19E-07 2.94E-14 N0147 + D 9.83E 07 1.07 E-06 6.41 E-08 0.

6.28E-07 4.65E-05 2.28E-05 PM147 1.15 E-04 1.10E-05 4.50E-06 0.

2.10E-05 1.14E-04 5.87E-06 PM148M + D 1.32E-05 3.35E-06 2.62E-06 0.

5.07E-06 3.20E-04 4.10E-05

}

PM148 5.44E-07 8.88E-08 4.48E-08 0.

1.60E-07 6.52E-05 6.14E-05 PM149 4.91 E-08 6.89E-09 2.84E-09 0.

1.31 E-08 1.24E-05 2.79E-05 PM151 1.20E-08 1.99E-09 1.01 E-09 0.

3.57E-09 6.56E-06 2.27E-05 SM151 1.07E-04 2.10E-05 4.86E-06 0.

2.27E-05 7.68E-05 3.53E-06 SM153 2.43E-08 2.01 E-08 1.47E-09 0.

6.56E-09 7.11 E-06 1.77E-05 EU152 2.96E-04 7.19E-05 6.30E-05 O.

3.34E-04 5.01 E-04 1.35 E-05 EU154 9.43 E-04 1.23E-04 8.60E-05 O.

5.44E-04 9.12E-04 3.34E-05 EU155

?.00E-04 1.96E-05 1.21 E-05 O.

7.65 E-05 1.51 E-03 5.97E-05 EU156 2.70E-06 2.03 E-06 3.30E-07 0.

1.36E-06 1.37E-04 4.56E-05 TB160 3.04E-05 O.

3.79E-06 0.

1.20E-05 2.97E-04 2.60E-05 HO166M 4.40E-04 1.36E-04 9.87E-05 O.

2.00E-04 6.24E-04 1.68E-05 W181 8.90E-09 2.88E-09 3.01 E-10 0.

O.

2.95 E-06 2.69E 07 W185 2.78E-07 9.17E-08 9.73E-09 0.

O.

9.60E-05 1.14E-05 4

W187 1.50E-09 1.22 E-09 4.29E-10 0.

O.

5.92E-06 2.21 E-05 54

PALISADES NUCI FAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 1.7 fcontdl TEEN INHALATION DOSE COMMITMENT FACTORS (

4 ISOTOPE BONE LIVER TOTAL BODY THYROID FIRST YR)

PB210 + D 3.09E-02 8.28E-03 1.07E 03 0.

2.95E 02 4.52E-02 3.87E-05 KIDNEY LUNG GI LLI B1210 + D O.

4 2.26E-06 1.89E-07 0.

2.74E-05 1.91 E-03 3.19E-05 PO210 5.63E-04 1.22E-03 1.37E-04 0.

4.21 E-03 5.41 E-02 4.45E-05 RN222 + D 0.

O.

3.94E-06 0.

RA223 + D 2.57E-04 3.93E-07 5.14E-05 O.

1.12E-05 4.39E-02 3.04E-04 RA224 + D 2.83E-05 6.77E-08 5.65E-06 0.

1.93E-06 1.51 E-02 3.29E-04 RA225 + D 4.28E-04 5.04E-07 8.56E-05 O.

1.44E-05 5.04E-02 2.89E-04 RA226 + D 1.33E-01 3.38E-06 9.87E-02 0.

9.67E-05 2.02E-01 3.11 E-04 RA228 + D 5.34E-02 1.74E-06 5.88E-02 0.

AC225 6.04E-04 8.25E-04 4.06E-05 O.

9.47E-05 3.81 E-02 2.70E-04 4.97E-05 2.78E-01 5.30E-05 AC227 + D 2.49E + 00 3.69E-01 1.48E-01 0.

1.07E-01 4.16E-01 5.38E-05 TH227 + D 3.09E-04 5.56E-06 8.93E-06 0.

TH228 + D 2.60E-01 4.37E-03 8.78E-03 0.

3.18E-05 6.50E-02 3.57E-04 TH229 9.06E + 00 1.36E-01 4.45E-01 0.

6.67E-01 5.05 E + 00 3.36E-04 2.45E-02 1.69E + 00 3.70E-04 TH230 2.34E + 00 1.34E-01 6.49E-02 0.

6.55E-01 8.98E-01 3.95 E-05 TH232 + D 2.61 E + 00 1.14E-01 9.21 E-02 0.

5.60E-01 8.60E-01 3.36E-05 a

TH234 2.32E-06 1.35E-07 6.71 E-08 0.

7.73E 07 3.26E-04 7.49E-05 j

PA231+D 5.32E + 00 2.00E-01 2.07E-01 0,

1,12E + 00 9.91 E-02 4.71 E-05 PA233 1.68E-06 3.24E-07 2.89E-07 0.

1.22E-06 5.39E-05 1.00E-05 U232 + D 7.31 E-02 0.

5.23E-03 0.

7.94E-03 3.84E-01 4.46E-05 U233 + D 1.55E-02 0.

9.42E-04 0.

3.63E-03 9.18E-02 4.12E-05 U234 1.48E-02 0.

9.23E-04 0.

3.55E-03 8.99E-02 4.04E-05 U235 + D 1.42E-02 0.

8.67E-04 0.

3.34E-03 8.44E-02 5.13E-05 U236 1.42E-02 0.

8.86E-04 0.

3.41 E-03 8.62E-02 3.79E-05 U237 5.25E-08 0.

1.40E-08 0.

2.16E-07 1.76E-05 1.29E-05 U238 + D f.36E-02 0.

8.10E-04 0.

3.12E-03 7.89E-02 3.62E-05 NP237 + 0 1.77E + 00 1.54E-01 7.21E 02 0.

5.35E-01 8.99E 02 5.22E-05 NP238 4.23E-07 1.13E-08 6.59E-09 0.

3.88E-08 1.75 E-05 2.38E-05 NP239 4.23E-08 3.99E-09 2.21 E-09 0.

1.25E-08 8.11 E-06 1.65E-05 PU238 2.86E + 00 4.06E-01 7.22 E-02 0.

3.10E-01 3.12E-01 4.79E-05 i

PU239 3.31 E + 00 4.50E-01 8.05E-02 0.

3.44E-01 2.93E-01 4.37E-05 i

PU240 3.31 E + 00 4.49E-01 8.04E-02 0.

3.43E-01 2.93E-01 4.46E-05 PU241 + D 6.97E-02 3.57E-03 1.40E-03 0.

6.47E-03 2.60E-04 9.17E-07 PU242 3.07E + 00 4.33E-01 7.75E-02 0.

3.31 E-01 2.82E-01 4.29E-05 t

PU244 3.59E + 00 4.96E-01 8.88E-02 0.

3.79E-01 3.23E 01 6.39E-05 AM241 1.06E + 00 4.07E-01 7.10E-02 0.

5.32E-01 1.05E-01 4.G3E-05 AM242M 1.07E + 00 3.93E-01 7.15E-02 0,

5.30E-01 4.21E-02 6.14E-05 AM243 1.06E + 00 3.92E-01 6.95E-02 0.

5.21 E-01 9.91 E-02 5.72E-05 j

CM242 2.12E-02 2.14E-02 1.41 E-03 0.

6.40E-03 6.76E-02 5.21 E-05 CM243 8.45E-01 3.50E-01 5.00E-02 0.

2.34E-01 1.09E-01 5.13E-05 CM244 6.46E-01 3.03E-01 3.88E-02 0.

1.81 E-01 1.05E-01 4.96E-05 CM245 1.32E + 00 4.11 E-01 7.53E-02 0.

3.52E-01 1.01 E-01 4.63E-05 CM246 1.31 E + 00 4.11E 01 7.52E-02 0.

3.51 E-01 1.03E-01 4.54E-05 CM247 + D 1.28E + 00 4.04E-01 7.41E-02 0.

3.46E-01 1.01 E-01 5.97E-05 CM248 1.06E + 01 3.33E + 00 6.11E-01 0.

2.85 E + 00 8.32E-01 9.63E-04 CF252 1.29E + 00 0.

3.07E-02 0.

O.

3.43E-01 1.89E 04 55

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 1.7 (contdl ADULT INHALATION DOSE CCMMITMENT FACTORS (MREM /50Y PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3' O.

1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 BE10 1.98E-04 3.06E-05 4.96E-06 0.

O.

2.22E-04 1.67E-05 C14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 N13 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 F18 4.71 E-07 0.

5.19E-08 0.

O.

9.24E-09 NA22 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 NA24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P32 1.65 E-04 9.64E-06 6.26E-06 0.

O.

1.08E-05 AR39 0.

O.

2.08E-09 0.

AR41 0.

O.

8.06E-09 0.

CA41 3.83E-05 O.

4.13E-06 0.

O.

3.83E-06 2.86E-07 SC46 5.51 E-05 1.07 E-04 3.11 E-05 O.

9.99E-05 O.

3.23E-05 CR51 0.

O.

1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN54 0.

4.95E-06 7.87E-07 0.

1.23E-06 1.75E-04 9.67E-06 MN56 0.

1.55E 10 2.29E-11 0.

1.63E-10 1.18E-06 2.53E-06 FESS 3.07E-06 2.12E-06 4.93E-07 0.

O.

9.01 E-06 7.54E-07 FE59 1.47E-06 3.47E-06 1.32E-06 0.

O.

1.27E-04 2.35 E-06 C057 0.

8.65E-08 8.39E-08 0.

O.

4.62E-05 3.93E-06 C058 0.

1.98E-07 2.59E-07 0.

O.

1.16E-04 1.33E-05 CO60 0.

1.44E-06 1.85 E-06 0.

O.

7.46E-04 3.56E-05 NI59 4.06E-06 1.46E-06 6.77E-07 0.

O.

8.20E-06 6.11 E-07 Nf63 5.40E05 3.93E-06 1.81 E-06 0.

O.

2.23E-05 1.67E-06 Nf65 1.92E 10 2.62E-11 1.14E-11 0.

O.

7.00E-07 1.54E-06 CU64 0.

1.83E-10 7.69E-11 0.

5.78E 10 8.48E-07 6.12E-06 ZN65 4.05E-06 1.29E-05 5.82E-06 0.

8.62E-06 1.08E-04 6.68E-06 ZN69M + D f.02E-09 2.45 E-09 2.24E-10 0.

1.48E-09 2.38E-06 1.71 E-05 ZN69 4.23E-12 8.14E 12 5.65E-13 0.

5.27E-12 1.15E-07 2.04E-09 SE79 0.

3.83E-07 6.09E-08 0.

5.69E-07 4.47E-05 3.33E-06 8R82 0.

O.

1.69E-06 0.

O.

1.30E-06 8R83 + D 0.

O.

3.01 E-08 0.

O.

2.90E-08 BR84 0.

O.

3.91 E-08 0.

O.

2.05E-13 BR85 O.

O.

1.60E-09 0.

O.

KR83M 0.

O.

5.19E-10 0.

KR85M 0.

O.

2.91 E-09 0.

KR85 O.

O.

2.41 E-09 0.

KR87 0.

O.

1.53E-08 0.

I KR88 + D 0.

O.

3.13E-08 0.

KR89 0.

O.

2.13E-08 0.

RB86 0.

1.69E-05 7.37E-06 0.

O.

2.08E-06 RB87 0.

9.86E-06 3.21 E-06 0.

O.

2.88507 RB88 0.

4.84E-08 2.41 E-08 0.

O.

4.18E-19 RB89 4 D 0,

3.20E-08 2.12E-08 0.

O.

1.16E 21 SR89 + D 3.80E-05 O.

1.09E-06 0.

O.

1.75E-04 4.37E-05 SR90 + D 1.24E-02 0.

7.62E-04 0.

O.

1.20E-03 9.02E-05 j

SR91 + D 7.74E 09 0.

3.13E 10 0.

O.

4.56E-06 2.39E-05 i

SR92 + D 8.43E 10 0.

3.64E-11 0.

O.

2.06E-06 5.38E-06 i

Includes a 50% increase to account for percutaneous transpiration.

56 i

PALISADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 1.7 (contd)

ADULT INHALATION DOSE COMMITMENT FACTORS (M ISOTOPE 80NE LIVER TOTAL BODY THYROID ALED IN FIRST YR)

Y90 2.61 E-07 0.

KIDNEY LUNG GILLI 7.01 E-09 0.

O.

2.12E-05 6.32E-05 Y91M + D 3.26E 11 0.

1.27E-12 0.

O.

2.40E-07 1.66E 10 Y91 5.78E-05 O.

1.55E-06 0.

O.

2.13E-04 4.81 E-05 Y92 1.29E-09 0.

3.77E-11 0.

O.

Y93 1.18E-08 0,

3.26E-10 0.

O.

1.96E-06 9.19E-06 ZR93 + D 5.22E-05 2.92E-06 1.37E-06 0.

1.11 E-05 2.13E-05 1.51 E-06 6.06E-06 5.27E-05 ZR95 + D 1.34E-05 4.30E-06 2.91 E-06 0.

6.77E-06 2.21 E-04 1.8BE-05 ZR97+D 1.21 E-08 2.45E-09 1.13E-09 0.

3.71 E-09 9.84E-06 6.54E-05 NB93M 3.10E-05 1.01 E-05 2.49E-06 0.

1.16E-05 3.11 E-05 2.38E-06 N895 1.76E-06 9.77E-07 5.26E-07 0.

9.67E-07 6.31 E-05 1.30E-05 N897 2.78E-11 7.03E-12 2.56E-12 0.

8.18E-12 3.00E-07 3.02E-08 MO93 0.

1.17E-06 3.17E-08 0.

3.55 E-07 5.11 E-05 3.79E-06 MO99 + D O.

1.51 E-08 2.87E-09 0.

3.64E-08 1.14E-05 3.10E-05 TC99M 1.29E-13 3.64E-13 4.63E-12 0.

5.52E-12 9.55E-08 5.20E-07 TC99 3.13E-08 4.64E-08 1.25E-08 0.

5.85E-07 1.01 E-04 7.54E-06 TC101 5.22E-15 7.52E-15 7.38E-14 0.

1.35E-13 4.99E-08 1.36E-21 RU103 + D 1.91 E-07 0.

8.23E-08 0.

7.29E-07 6.31 E-05 1.38E-05 RU105 + D 9.88E 11 0.

3.89E-11 0.

1.27E-10 1.37E-06 6.02E-06 RU106 + D 8.64E-06 0.

1.09E-06 0.

i.67E-05 1.17E-03 1.14E-04 RH105 9.24E-10 6.73E-10 4.43E-10 0.

2.86E-09 2.41E-06 1.09E-05 PD107 0.

8.27E-08 5.87E-09 0.

6.57E-07 9.47E-06 7.06E-07 PD109 0.

4.63E-t 3 1.16E-10 0.

2.35E-09 1.85E-06 1.52E-05 AG110M + D 1.35E-06 1.25 E-06 7.43E-07 0.

2.46E-06 5.79E-04 3.78E-05 AG111 4.25E-08 1.78E-08 8.87E-09 0.

5.74E-08 2.33E-05 2.79E-05 CD113M 0,

1.54E-04 4.97E-06 0.

1.71 E-04 2.08E-04 1.59E-05 CD115M 0.

2.46E-05 7.95E-07 0.

1.98E-05 1.76E-04 4.80E-05 SN123 3.02E-05 6.67E-07 9.82E-07 5.67E-07 0.

2.88E-04 3.92E-05 SN125 + D 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0.

7.37E-05 6.81 E-05 SN126 + D 1.58E-04 4.18E-06 6.00E-06 1.23E-06 0.

1.17E-03 1.59E-05 S8124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.

3.10E-04 5.08E-05 SB125 + D 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.

2.18E-04 1.26E-05 SB126 4.50E-07 9.13E-09 1.62E-07 2.75E-09 0.

9.57E-05 6.01 E-05 S8127 3.30E-08 7.22E-10 1.27E-08 3.97E-10 0.

2.05E-05 3.77E-05 TE125M 4.27E-07 1.98E-07 5.84E-08 1.31 E-07 1.55E-06 3.92E-05 8.83E-06 TE127M + D 1.58E-06 7.21 E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04 1.87E-05 TE127 1.75E-10 8.03E-11 3.87E-11 1.32E 10 6.37E-10 8.14E-07 7.17E-06 TE129M + D 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 TE131M + D 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE131 + D 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 TE132 + D 3.25 E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 TE133M + D 7.24E-12 5.40E-12 4.17E-12 6.27E 12 3.74E-11 5.51 E-07 5.49E-08 TE134 + D 3.84E-12 3.22E-12 1.57E 12 3.44E 12 2.18E-11 4.343-07 2.97E-11 1129 2.48E-06 2.11 E-06 6.91 E-06 5.54E-03 4.53E-06 0.

2.22E-07 1130 5.72E 07 1.68E-06 6.60E-07 1.42E-04 2.61 E-06 0.

9.61 E-07 1131 + D 3.15 E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.

7.85E-07 57

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 1.7 fcontd)

ADULT INHALATION DOSE COMMITMENT FACTORS (MREM /50Y PER PCIINHALED IN FIRST YR) l ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48 E-07 0.

5.08E-08 1133 + D 1.08E-06 1.85 E-06 5.65E-07 2.69E-04 3.23 E-06 0.

1.11 E-06 1134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.

1.26E-10 1135 + D 3.35 E-07 8.73E-07 3.21 E-07 5.60E-05 1.30E-06 0.

6.56E-07 XE131M 0.

O.

1.40E-09 0.

XE133M 0.

O.

1.89E-09 0.

XE133 0.

O.

1.57E-09 0.

XE135M 0.

O.

2.22E-09 0.

XE135 O.

O.

4.05 E-09 0.

XE137 0.

O.

1.74E-08 0.

XE138 + 0 0.

O.

2.44E-08 0.

CS134M + D 1.59E-08 3.20E-08 1.72E-08 0.

1.83E-08 2.93E-09 7.92E-09 CS134 4.66E-05 1.06E-04 9.10E-05 O.

3.59E-05 1.22 E-05 1.30E-06 CS135 1.46E-05 1.29E-05 5.99E-06 0.

5.11 E-06 1.57E-06 2.11 E-07 CS136 4.88E-06 1.83E-05 1.38E-05 O.

1.07E-05 1.50E-06 1.46E-06 CS137 + D 5.98E-05 7.76E-05 5.35 E-05 O.

2.78E-05 9.40E-06 1.05E-06 CS138 4.14E-08 7.76E-08 4.05 E-08 0.

6.00E-08 6.07E-09 2.33E-13 1

CS139 + D 2.56E-08 3.63E-08 1.39E-08 0.

3.05 E-08 2.84E-09 5.49E-31 BA139 1.17E-10 8.32E-14 3.42E-12 0.

7.78 E-14 4.70E-07 1.12E-07 BA140 + D 4.88E-06 6.13E-09 3.21 E-07 0.

2.09E-09 1.59E-04 2.73E-05 BA141 + D 1.25E-11 9.41 E-15 4.20E-13 0.

8.75E-15 2.42E-07 1.45 E-17 BA142 + D 3.29E-12 3.38E-15 2.07E-13 0.

2.86E-15 1.49E-07 1.96E-26 LA140 4.30E-08 2.17E-08 5.73E-09 0.

O.

1.70E-05 5.73E-05 LA141 5.34E-10 1.66E-10 2.71 E-11 0.

O.

1.35 E-06 7.31 E-06 LA142 8.54E-11 3.88E-11 9.65E-12 0.

O.

7.91 E-07 2.64E-07 CE141 2.49E-06 1.69E-06 1.91 E-07 0.

7.83E-07 4.52E-05 1.50E-05 CE143 + D 2.33E-08 1.72E-08 1.91 E-09 0.

7.60E-09 9.97E-06 2.83E-05 CE144 + D 4.29E-04 1.79E-04 2.30E-05 O.

1.06E-04 9.72E-04 1.02E-04 PR143 1.17E-06 4.69E-07 5.80E-08 0.

2.70E-07 3.51 E-05 2.50E-05 PR144 3.76E-12 1.56E-12 1.91 E-13 0.

8.81E-13 1.27E-07 2.69E-18 ND147 + D 6.59E-07 7.62E-07 4.56E-08 0.

4.45 E-07 2.76E-05 2.16 E-05 PM147 8.37E-05 7.87E-06 3.19E-06 0.

1.49E-05 6.60E-05 5.54E-06 PM148M + D 9.82E-06 2.54E-06 1.94E-06 0.

3.85 E-06 2.14E-04 4.18E-05 PM148 3.84E-07 6.37E-08 3.20E-08 0.

1.20E-07 3.91 E-05 5.80E-05 PM149 3.44E-08 4.87E-09 1.99E-09 0.

9.19E-09 7.21 E-06 2.50E-05 PM151 8.50E-09 1.42E-09 7.21 E-10 0.

2.55E-09 3.94E-06 2.00E-05 SM151 8.59E-05 1.48E-05 3.55E-06 0.

1.66E-05 4.45 E-05 3.25 E-06 SM153 1.70E-08 1.42E-08 1.04E-09 0.

4.59E-09 4.14 E-06 1.58E-05 EU152 2.38E-04 5.41 E-05 4.76E-05 O.

3.35 E-04 3.43E-04 1.59E-05 EU154-7.40E-04 9.10E-05 6.48E-05 O.

4.36E-04 5.84E-04 3.40E-05 EU155 1.01 E-04 1.43E-05 9.21 E-06 0.

6.59E-05 9.46E-05 5.95E-06 EU156 1.93E-06 1.48E-06 2.40E-07 0.

9.95 E-07 8.56E-05 4.50E-05 TB160 2.21 E-05 O.

2.75E-06 0.

9.10E-06 1.92E-04 2.68E-05 HOl66M 3.37E-04 1.05E-04 8.00E-05 O.

1.57E-04 3.94E-04 1.59E-05 W181 6.23E-09 2.03 E-09 2.17E-10 0.

O.

1.71 E-06 2.53E-07 W185 1.95 E-07 6.47E-08 6.81 E-09 0.

O.

5.57E-05 1.07E-05 W187 1.06E-09 8.85E-10 3.10E-10 0.

O.

3.63 E-06 1.94E-05 58

PALISADES NUC1FAR PLANT OFFSITE DOSE CALCULATION MANUAL k

Revision 10 TABLE 1.7 (contd) 1 ADULT INHALATION DOSE COMMITMENT FACTORS (MREM /5 ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY-LUNG GI-LLI j

P8210 + D 2.64E 02 6.73E-03 8.37E-04 0.

2.12E-02 2.62E-02 3.65E-05 B1210 + D 0.

1.59E-06 1.32E 07 0.

1.92E-05 1.11 E-03 2.95E-05 PO210 3.97E-04 8.60E-04 9.58E-05 O.

2.95 E-03 3.14E-02 4.19E-05 RN222 + D 0.

O.

2.05E-06 0.

RA223 + D 1.80E-04 2.77E-07 3.60E-05 O.

7.85E-06 2.55E 02 2.84E-04 RA224 + D 1.98E-05 4.78E-08 3.96E-06 0.

1.35E 06 8.77E-03 3.01 E-04 4

RA225 + D 3.00E-04 3.56E-07 5.99E 05 O.

1.01 E-05 2.92E-02 2.71 E-04 i

RA226 + D 1.25E-01 2.39E-06 9.14E-02 0.

6.77E-05 1.17E-01 2.94E-04 RA228 + 0 4.41 E-02 1.23E-06 4.78E-02 0.

3.48E-05 1.61 E-01 5.00E-05 AC225 4.23E-04 5.82E-04 2.84E-05 O.

6.63E-05 2.21 E-02 2.52E-04 1

AC227 + D 2.30E + 00 3.05E 01 1.36E-01 0.

9.82E-02 2.41 E-01 5.08E-05 TH227 + D 2.17E-04 3.92E-06 6.25E-06 0.

2.22E-05 3.77E-02 3.34E-04 TH226 + D 2.00E 01 3.39E 03 6.77E-03 0.

1.89E-02 1.01 E + 00 3.49E-04 TH229 8.88E + 00 1.33E-01 4.36E-01 0.

6.52E-01 3.49E + 00 3.17E-04 TH230 2.29E + 00 1.31 E-01 6.36E-02 0.

6.40E-01 6.21 E-01 3.73E-05 TH232 + D 2.56E + 00 1.12E-01 9.04E-02 0.

5.47E-01 5.96E 01 3.17E-05 TH234 1.63E-06 9.56E-08 4.70E-08 0.

5.41 E-07 1.89E-04 7.03E-05 4

PA231 + D 5.08E + 00 1.91 E-01 1.98E-01 0.

1.07E + 00 5.75E-02 4.44E-05 PA233 1.21 E-06 2.42E-07 2.09E-07 0.

9.15E-07 3.52E-05 1.02E-05 U232 + D 5.14E-02 0.

3.66E-03 0.

5.56E-03 2.22E-01 4.21 E-05 U233 + D 1.09E-02 0,

6.60E-04 0.

2.54E-03 5.32E-02 3.89E-05 U234 1.04E-02 0.

6.46E-04 0.

2.49E-03 5.22E-02 3.81 E-05 U235 + 0 1.00E-02 0,

6.07E-04 0.

2.34E-03 4.90E-02 4.84E-05 U236 1.00E-02 0.

6.20E-04 0.

2.39E-03 5.00E 02 3.57E-05 U237 3.67E-08 0.

9.77E-09 0.

1.51 E-07 1.02E-05 1.20E-05 U238 + D 9.58E-03 0.

5.67E 04 0.

2.18E-03 4.58E-02 3.41 E-05 i

NP237 + D 1.69E + 00 1.47E-01 6.87E-02 0.

5.10E-01 5.22E-02 4.92E-05 NP238 2.96E-07 8.00E-09 4.61 E-09 0.

2.72E-08 1.02E-05 2.13E-05 NP239 2.87E-08 2.82E-09 1.55E-09 0.

8.75E-09 4.70E-06 1.49E-05 PU238 2.74E + 00 3.87E-01 6.90E-02 0.

2.96E-01 1.82E-01 4.52E-05 PU239 3.19E + 00 4.31E-01 7.75E-02 0.

3.30E-01 1.72E-01 4.13E-05 PU240 3.18E + 00 4.30E-01 7.73E-02 0.

3.29E-01 1.72E-01 4.21 E-05 PU241 + D 6.41 E-02 3.28E-03 1.29E-03 0.

5.93E-03 1.52E-04 8.65E-07 PU242 2.95E+00 4.15E-01 7.46E-02 0.

3.17E-01 1.65E-01 4.05E-05 PU244 3.45E + 00 4.76E-01 8.54E-02 0.

3.64E-01 1.89E-01 6.03E-05 AM241 1.01 E & OO 3.59E-01 6.71 E-02 0,

5.04E-01 6.06E-02 4.60E-05 i

AM242M 1.02E + 00 3.46E-01 6.73E-02 0.

5.01 E-01 2.44E-02 5.79E-05 AM243 1.01 E + 00 3.47E-01 6.57E-02 0.

4.95E-01 5.75E-02 5.40E-05 CM242 1.48E-02 1.51 E-02 9.84E-04 0.

4.48E-03 3.92E-02 4.91 E-05

{

CM243 7.86E-01 2.97E-01 4.61 C-02 0.

2.15E-01 6.31 E-02 4.84E-05 CM244 5.90E-01 2.54E-01 3.51 E-02 0.

1.64E-01 6.06E-02 4.68E-05 CM245 1.26E + 00 3.59E-01 7.14E-02 0.

3.33E-01 5.85E-02 4.36E-05 CM246 1.25E + 00 3.59E-01 7.13E-02 0.

3.33E-01 5.96E-02 4.29E-05 CM247 + D 1.22E + 00 3.53E-01 7.03E-02 0.

3.28E-01 5.85E-02 5.63E-05 CM248 1.01 E + 01 2.91 E + 00 5.79E-01 0.

2.70E + 00 4.82E-01 9.09E-04 j

CF252 9.78E-01 0,

2.33E-02 0.

O.

1.99E-01 1.78E-04 s

4 59

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 1.8 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (MREM /HR PER PCl/M23 i

ELEMENT TOTAL BODY SKIN H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 j

Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0

)

Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-0D Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn 69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 j

Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91 m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo 99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 60

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL, i

Revision 10 TABLE 1.8 (continued)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (DFG,)

(MREM /HR PER PCl/M3)

ELEMENT TOTAL BODY SKIN I

Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 l

Ag-110m 1.80E-08 2.10E-08 i

Te-125m 3.50E-11 4.80E-11 i

Te-127m 1.10E-12 1.30E-12 Te-127 -

1.00E-11 1.10E-11 Te-129m 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 i

Te-131 m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 i

Te-132 1.70E-09 2.00E-09 1-130 1.40E-08 1.70E-08 l-131 2.80E-09 3.40E-09 l-132 1.70E-08 2.00E-08 l

l-133 3.70E-09 4.50E-09 i

i 1-134 1.60E-08 1.90E-08 l-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 4

l Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 2

Cs-138 2.10E-08 2.40E-08 i

Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 i

Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E 08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 61

_._._____.._______.__.-.-._.m._.

PALISADES NUCLFAR PLANT j

OFFSITE DOSE CALCULATION MANUAL i

Revision 10 i

TABLE 1.9 i

l 1996 ALISADES GASEOUS DE31GN j

OBJECTIVE ANNUAL QUANTl"lES

$i Design Objective Dose Factor Annual Quantity l

Nuclide Oraan Mrem /Ci (Cil t

1 l

Ag-110m Gl Tract-T 1.06E + 00 1.41 E + 01 Ar-41 Total Body 3.51 E-04 1.42E + 04 Ba-139 GI Tract-C 3.00E-03 5.00E + 03 Ba-140 Lung-T 1.06E-01 1.42E + 02 Br-82 Total Body-l 1.47E-03 3.40E + 03 i

C-14 Bone-C 1.29E-01 1.16E + 02 l'

Ce-141 GI Tract-T 1.17E-01 1.28E + 02 p

Ce-144 Gl Tract-T 3.10E + 00 4.84E + 00 Co-57 31 Tract-T -

7.85E-02 1.91 E + 02 i

Co-58 Total Body-C 4.66E-02 1.07E + 02 Co-60 Total Body-C 2.77E-01 1.80E + 01 Cr-51 GI Troct-A,T 2.17E-03 6.91 E + 03 Cs-134 Liver-C 6.39E + 00 2.35E + 00 i

Cs-136 Total Body-l 8.21 E-02 6.09E + 01 Cs-137 Bone-C 6.24E + 00 2.40E + 00

?

' Cs-138 Total Body-C 2.89E-05 1.73E + 05 Fe-55 Bone-C 1.90E-01 7.89E + 01 Fe-59 GI Tract-T 2.22E-01 6.76E + 01 H-3 Total Body-C 1.48E-04 3.38E + 04 l-129 Thyroid-A 3.40E + 02 4.41 E-02 1-131 Thyroid-l 8.21 E + 00 1.83E + 00 y

1-132 Thyroid-C 1.05E-02 1.43E + 03 1-133 Thyroid-C 2.09E-01 7.18E + 01

?

l-134 Thyroid-C 2.76E-03 5.43E + 03 N

l-135 Thyroid-C 4.30E 02 3.49E + 02 Kr-83m Skin 8.51 E-07 1.76E + 07 Kr-85 Skin 7.68E-05 1.95E + 05 Kr-85m Total Body 4.65E-05 1.08E + 05 Kr-87 Skin 8.24E-04 1.82E + 04 Kr-88 Total Body 5.84E-04 8.56E + 03 Kr-89 Total Body 6.59E-04 7.59E + 03 La-140 GI Tract-T 2.53E-02 5.93E + 02 Mn-54 GI Tract-T 2.24E-01 6.70E + 01 Mn-56 GI Tract-C 6.41 E-03

-2.34E + 03 Mo-99 GI Tract-T 1.40E-02 1.07E + 03 N Total Body-C 4.48E-06 1.12E + 06 Na-24 Total Body-C 8.37E-04 5.97E + C3 Nb-95 GI Tract-T 9.98E-02 1.50E 4 Q2 Ni-63 Bone-C 1.14E + 01 1.32L 00 Ni 65 GI Tract-C 4.37E-03 3.43E + 03 Np-239 GI Tract-T 6186E-03 2.19E + 03 Rb-88 Total Body-C 1.90E-05 2.63E + 05 Ru-103 GI Tract-T 1.27E-01 1.18E + 02 Ru-105 GI Tract-C 5.17E-03 2.90E + 03 j

62 4

a

PALISADES NUCI FAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 1-9 (contd) 1996 PALISADES GASEOUS DESIGN l

i QBJECTIVE ANNUAL QUANTITIES i

Design Objective Dose Factor Annual Quantity Nuclide Oraan Mrem /Ci (Ci)

Sb-124 GI Tract-T 7.15E-01 2.10E + 01 4

Sb-125 Gl Tract-T 4.03E-01 3.72E + 01 Sr-89 Bone-C 8.38E + 00 1.79E + 00 Sr-90 Bone-C 3.45E + 02 4.35E-02 i

Sr-91 Bone-l 2.13E + 00 7.04E + 00 Sr-92 GI Tract-C 1.26E-02 1.19E + 03 i

Tc-99 Gl Tract-T 5.44E-01 2.76E + 01 Tc-99m GI Tract-T 3.19E-04 4.70E + 04 Tc-101 Gl Tract-l 4.39E-05 3.42E + 05 Te-127 Gl Tract-T 4.20E-03 3.57E + 03 i

Xe-131 m Skin 3.39E-05 4.42E + 05 Xe-133 Total Body 1.17E 05 4.27E + 05 i

Xe-133m Skin 7.08E-05 2.12E + 05 1

Xe-135 Total Body 7.19E-05 G.95E + 04 y

Xe-135m Total Body 1.24E-04 4.03E + 04 Xe-137 Skin 7.59E-04 1.98E + 04

(

Xe-138 Total Body 3.51 E-04 1.42E + 04 i

Zn-85 Total Body-C 4.42E-01 1.18E + 01 i

Zr-95 GI Tract-T 2.93E-01 5.12E + 01 Pu-238 Bone-T 1.19E + 03 1.26E-02 i

Pu-239 Bone-T 1.38E + 03 1.09E-02 Pu-241 Bone-T 2.90E + 01 5.17E-01 j

Am-241 Bone-T 4.41 E + 02 3.40E-02 Cm-242 Lung-T 2.81 E + 01 5.34E-01 Cm244 Bons-T 2.69E + 02 5.58E-02

?

63

PAllSADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 11.

LIQUID EFFLUENTS A.

CONCENTRATION 1.

Reauirements Appendix A, Section Ill.G requires that the concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to ten times the Effluent Concentration (EC) specified in 10 CFR 20, Appendix B, Table 2, Column 2 for nuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 pCi/ml total activity. To ensure compliance, the following approach will be used for each release.

2.

Prerelease Analysis Most tanks will be recirculated through two volume changes prior to sampling for release to the environment to ensure that a representative sample is obtained. The appropriate recirculation time for those tanks too large to provide two volume changes will be the time that the suspended particulate concentration reaches steady state. Either a one-time test, or prior sampling data, may be i

used to determine appropriate recirculation time.

Prior to release, a grab sample will be analyzed for each release, and the concentration of each radionuclide determined.

n c=Ec, i=1 (2.1) where:

C Total concentration in the liquid effluent at the release

=

point, pCi/ml.

C, Concentration of a single radionuclide i, pCi/ml.

=

64

l PALISADES NUCIFAR PLANT i

OFFSITE DOSE CALCULATION MANUAL Revision 10 3.

Effluent ConcentrationJEC) - Sum of the Ratios l

The EC-Fraction (R,) for each release point will be calculated by the relationship defined by Note 4 of Appendix B,10 CFR 20:

C' RI= i s 10.0 l

EC, (2.2)

~

where:

Ci Effluent concentration of radionuclide i, pCi/ml.

=

EC, The EC of radionuclide i,10 CFR 20, Appendix B,

=

Table 2, Column 2 - Ci/ml.

R3 The Total EC-Fraction for the release point.

=

The sum of the ratios at the discharge to the lake must be s 10 due to the releases from any or all concurrent releases. The j

following relationship will assure this criterion is met:

l f (R,-1) + f,(R,-1) + f (R -1) s F 3

3 3 i

where:

f,f,fs The effluent flow rate (gallons / minute) for the

=

i2 respective releases, determined by Plant personnel.

R,R,R The Total EC-Fractions for the respective releases as

=

i 2 3 determined by Equation 2.2.

F Minimum required dilution flow rate. Normally,

=

a conservatively high dilution flow rate is used, that is, flow rate used = (b,)(F) where b,is a conservative factor greater than 1.0.

65

P.ALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 4

B.

INSTRUMENT SETPOINTS 1.

Setoolnt Determination Appendix A, Section Ill.F requires alarm setpoints for each liquid effluent monitor will be established using Plant instructions to ensure the requirements of Appendix A, Section Ill.G are not exceeded. Concentration, flow rate, dilution, principal gamma emitter, geometry, and detector efficiency are combined to give an equivalent setpoint in counts per minute (cpm). The identification number for each liquid effluent radiation detector is contained in Figure 2-2.

The respective alarm / trip setpoints at each release point will be set such that the sum of the ratios at each point, as calculated by Equation 2.2, will not be exceeded. The value of R is directly related to the total concentration calculated by Equation 2.1. An increase in the concentration would indicate an increase in the value of R. A large increase would cause the limits specified in Section 2.1.1 to be exceeded. The minimum alarm / trip setpoint value is equal to the release concentration, but for ease of operation it may be desired that the setpoint (S) be set above the effluent concentration (C) by the same factor (b) utilized in setting dilution flow. That is:

S=bxC (2.4)

Liquid effluent flow paths and release points are indicated in i

Figure 2.1.

2.

Comoosite Samolars Effluent pathways, Turbine Sump and Service Water, are equipped with continuous compositors to meet the requirements of Appendix A, Table D-1. These compositors are adjustable and normally set in a time mode and collect three to six samples hour!y, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day with a total collection of approximately one gallon per day. A representative sample is collected daily from the compositor and saved for the weekly, monthly analysis requirements of Appendix A, Table D-1. In the event that a compositor is not operational, effluent releases via this pathway may continue provided that grab samples are collected and analyzed for gross beta or gamma radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per Appendix A, Table C-1, Action 3.

66

~

PALISADES NUCI FAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 3.

Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in Section 1 were not exceeded.

A composite list on concentrations (C,), by isotope, will be used with the actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.3 to demonstrate compliance with the limits in Section 1. This data and setpoints will be recorded in auditable i

records by Plant personnel.

{

C.

DOSE 1.

RETS Requirement i

Appendix A, Section Ill.H.1 requires that the quantity of radionuclides released by limited such that the dose or dose commitment to an individual from radioactive materials in liquid 1

effluents release to unrestricted areas from the reactor (see Figure 2-1) will not exceed:

a.

During any calendar guarter,1.5 mrem to the total body and 5 mrem to any organ, and b.

During any calendar year,3 mrem to the total body and 10 mrem to any organ.

Tn ensure compliance, quantities'of activity of each radionuclide released will be summed for each release and accumulated for each quarter as follows in Section 2.

2.

Release Analysis Calculations shall be performed for each batch release, and weekly for continuous releases according to the formula:

A/C s 0.5 i

(2.5) c 67

PALISADES NUptFAR PLANT i

i OFFSITE DOSE CALCULATION MANUAL Revision 10 where:

A Cumulative quarterly activity of nuclide iidentified in

=

i liquid release (C,).

C Design objective annual quantity of radionuclide i from i

=

Table 2.2.

The design basis quantities are derived in such a conservative manner that doses may be greatly overestimated by this technique.

As a consequence of this conservatism, and in light of historically consistent operations with releases well below annual design basis j

quantities, the Appendix A, effluent requirements do not require monthly dose projections. Instead, if at any time, calculations by Equation (2.5) results in values greater than 0.5 for a given quarter or 1.0 for year-to-date, the NRC LADTAP code will be run to ensure that Appendix A, Section Ill.H.1 has been met.

Values for the design basis quantities (C), and the dose per Curie i

3 (Dc/Cc)i for each nuclide i shown in Table 2.2, were calculated as follows in Sections 2.1 and 2.2.

a.

Water inoestion The dose to an individual from ingestion of radioactivity from any source as described by the following equation:

i D [ (DCF), x 1, 3

i=l (2.6) where:

D, 1

Dose for the jth organ from radionuclides

=

releases, mrem.

j The organ of interest.

=

(DCF)q Ingestion dose commitment factor for the jth

=

organ from the l'" radionuclide mrem /pCi, see

(

i Table 2.1.

1 Activity ingested of the i'" radionuclida, pCi.

=

4 1

68 i

l i

PAllSADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 l,is described by:

I, = (A,)(V)(365) (1E06)

(1000)(d)

(2.7) where:

365 Days per year.

=

A, Annual activity released of i'h radionuclide, pCi.

=

V Average rate of water consumption

=

(2000 ml/d - adult,1400 ml/d - teen and child, 900 ml/d - infant, ICRP 23, p 358).

d Dilution water flow for year, ml.

=

1000 =

Dispersion factor from discharge to nearest drinking water supply.

1E06 =

Conversion Ci to pCi.

1 The dose equation then becomes:

D = (3.65E05)N) {i 3

(DCF), x A, mrem d

i,3 (2.8) b.

Fish Inoestion The dose to an individual from the consumption of fish is described by Equation 2.10. In this case the activity ingested of the i'h radionuclide (1,) is described by:

A,B,F(1 E09)

I, =

= pCi 15d (2.9) where:

Annual released of i'" radionuclide, Ci.

A,

=

69

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 pCilgm B,

Fish concentration factor of i* radionuclide

=

(see Table 2.0).

pCl/ml F

Amount of fish eaten per year (21 kg adult,

=

16 kg teen, 6.9 kg child, none infant).

15 Dispersion factor from discharge to fish

=

exposure point, d

Dilution water flow for year, ml.

=

1E09 =

Conversion of Ci and Kgm to gross.

Substitution of Equation 2.9 into Equation 2.6 gives:

0, = (6.7E07)F [1 A, x B, x DCF, mrem d

i=$

(2.10) c.

Annual Analvsis A complete analysis utilizing the NRC computer code LADTAP with the total source release will be done annually in conjunction with the annual environmental report. This analysis will provide estimates of dose to the total body and various organs in addition to the dose limiting organs considered in the method of Section 2. The following approach is utilized on LADTAP. The dose to the j* organ from m radionuclides, Dj, is described by:

m D, = [ D mrem y

I*I (2.11) l m

= { (DCF), x 1 mrem 3

i=1

\\

70

PAUSADES NUCI FAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 where:

Dose to the j'" organ from the i'" radionuclide, D,

=

mrem.

Tho organ of interest (bone, GI tract, thyroid, j

=

liver, kidney, lung, or total body).

Adult ingestion dose commitment factor for the (DCF)g

=

j'" organ from the i'" radionuclide, mrem /pCi (see Table 2.1).

Activity ingested of the i'" radionuclide, pCi.

I,

=

I, for water ingestion is described by:

A, Vr I, =

pCl vd (2.13) and for fish ingestion I,is described by:

A, B, Fr 1, =

pCi i

vd where:

Activity release of j'" radionuclide during the A,

=

year, Ci.

Average rate of water consumption V

=

(2000 ml/d).

Number of days during the year (365 d).

F

=

Dispersion factor from point of discharge to v

=

point of exposure.

Dilution water volume (ml).

d

=

Fish concentration factor of the it" radionuclide, 8,

=

pCilgm Table 2.0, pCi/mi Amount of fish eaten per day (57.5 gm/d).

F

=

71

PALISADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 D.

OPERABILITY OF LIQUID RADWASTE EQUlPMENT The Palisades liquid radwaste system is designed to reduce the shipment for disposal) so that radioactivity A, Ill.H.1. Maintaining the cumulative fraction each batch release and weekly for continuous releases assures compliance with this requirement. In addition,13 years of opera experience (to the date this ODCM was first adopted) has shown thj design basis quantities never have been exceeded.

i

}

E.

RELEASE RATE FOR OFFSITE EC (50 mrem /yr) 10 CFR 20.1402 requires radiosctive effluent releases to unrestri areas be less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. Concentrations at this j l

Effluent Concentration (EC) level, if ingested for one year, will re dose of 50 millirem to the total body. In addition,10 CFR 50 36a requires that the release of radioactive materials be kept as low as is reasonably achievable. Appendix l to 10 CFR 50 provides the numerica guidelines on limiting conditions for operations to meet the as low as k

reasonably achievable requirement.

I Y

The LADTAP code has been run to determine the dose due to N

water at Plant discharge concentration (1,000 x nearest drinking water l

intake concentration.) The nominal average source term used is g drinking this water is 3.88E-03 mrem. This is n

l l

conservative 50 mrem /yr total body value.

l 4

72

/

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 F.

FIGURES AND TABLES Fiaure 2-1 l

I t

s' l

I e

r y, s I-l

-s'-

s'

\\

~9 l'

\\

$ l!

/

e' g*i

/ i /

s *

/

e'

\\

s

\\

I

/

ks, '

SE

/

--,','~a,*a

.>.s..

~,

s

= ~,.,

c s-

[

/

f

,,,,,'g~~,-

s 4

.==5, t

\\ '. = %

" " ~ ~

,*.g

/

s

~

u s

/

/ $.

/

j.'\\

,g

' s~

E

s s'

/

.' \\ jx 1

% ~,,

g e'

/ i I 1 ml \\

\\

/

's

s I

/

?

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/

e/

/

f SS g

N u k N

/

3r

/

l 3

\\

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s

.5

/

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t i'

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y-

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es 1;a j

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m El s

J

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s

's.,,,,'
1
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o I
i a
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y Eg g
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-e
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c 3191 73 1
PALISADES RADWASTE EFFLUENTS - LIOuto
[
W4%il sv5f(M i
J~
P gyggg ggg l
J PRIMARY
(
SYS TEM TM D
STORAGE I?99 +
2 N
A im int a ra H q was,, n l
g ranusen i so
-E 9?OF tsaa.
2 rsee
(
i N/
i l
J Z g
trac a rtow rontact O
E h
l t
4 o
' ne soee
$ 5 M.sc... ~. ous w.5,,,,s,..
]
~
neenn o 3 e
stavect _M _
i nim s y wasst e
==
o o
h e
3 e Aimimy
(
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svsn u utstiiv I LAas u) o e
W E
g ware n 4
O w s,onac, at isni 5
(/)
v4==
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4 C
ris n nen
.MeMiNG ;1g-3 wasst runeeses stoo
,g,
. ix L
m DRAWS 3
mAsem ::
)
us 19 LL SuMr i
ne sses f
DeLUTIOst Flour /
s t
SERvlCE WATER -
"E *IEI i
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 2.0 BIOACCUMULATION FACTORS uCi/am oer uCi/ml d
i 1
FRESHWATER ELEMENT FISH l
H 9.0E-01 i
C 4.6E 03 l
NA 1.0E 02 j
P 1.0E 05 1
CR 2.0E 02 MN 4.0E 02 4
FE 1.0E O2 i
CO 5.0E 01 NI 1.0E 02 CU 5.0E 01 l
ZN 2.OE 03 BR 4.2E 02 RB 2.0E 03 SR 3.0E 01 Y
2.5E 01 ZR 3.3E 00 3
NB 3.0E 04 MO 1.0E 01 TC 1.5E 01 RU 1.0E 01 RH 1.0E 01 TE 4.0E 02 1
1.5E 01 CS 2.0E 03 BA 4.0E 00 LA 2.5E 01 CE 1.0E 00 PR 2.5E 01 ND 2.5E 01 W
1.2E 03 NP 1.0E 01 75
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 2.1_
INFANT INGESTION DOSE COMMITMENT FACTORS (MREM /50Y P ISOTOPE BONE LIVER TOTAL BODY THYROID TED IN FIRST YR)
H3 0.
3.08E 07 3.08E-07 3.08E-07 3.08E-07 3.08E 07 3.083-07 KIDNEY LUNG GI-LLI 8E10 1.71E 05 2.49E-06 5.16E-07 0.
C14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 1.64E-06 0.
N13 5.85E-08 5.85E-08 5.85E-08 5.835E-08 5.85E-08 5.85E-08 5.85E-08 2.78E 05 F18 5.19E-06 0.
4.43E.07 0.
O.
O.
NA22 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 1.22E-06 NA24 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01E-05 P32 1.70E-03 1.00E-04 6.59E-05 O.
O.
O.
2.30E-05 AR39 0.
O.
O.
O.
O.
O.
O.
AR41 0.
O.
O.
O.
O.
O.
O.
CA41 3.74E-04 0.
4.08E-05 O.
O.
O.
SC46 3.75E-08 5.41 E-08 1.69E-08 0.
3.56E-08 0.
3.53E-05 1.91 E-07 CR51 0.
O.
1.41 E-08 9.20E-09 2.01 E-09 1.79E-08 4.11 E-07 MN54 0.
1.99E-05 4.51 E-06 0.
4.41 E-06 0.
7.31 E-06 3
MN56 0.
8.18E-07 1.41 E-07 0.
7.03E-07 0.
7.43E-05 FESS 1.39E-05 8.98E-06 2.40E-06 0.
O.
4.39E-06 1.14E-06 FE59 3.08E-05 5.38E-05 2.12E-05 O.
O.
1.59E 05 2.57E-05 C057 0.
1.15E-06 1.87E-06 0.
O.
O.
3.92E-06 C058 0.
3.60E-06 8.98E-06 0.
O.
O.
8.97E-06 CO6O 0.
1.08E-05 2.55E-05 O.
O.
O.
2.57E-05 N159 4.78E-05 1.45 E-05 8.17E-06 0.
O.
O.
7.16E-07 N163 6.34E-04 3.92E-05 2.20E-05 O.
O.
O.
1.95E-06 4
N!65 4.70E-06 5.32E-07 2.42E-07 0.
O.
O.
CU64 d.
6.09E-07 2.82E-07 0.
1.03E-06 0.
1.25E-05 2
4.05E-05 ZN65 1.84E-05 6.31 E-05 2.91 E-05 O.
3.06E-05 O.
5.33E-05 ZN69M + D 1.50E-06 3.06E-06 2.79E-07 0.
1.24E-06 0.
4.24E-05 ZN69 9.33E-08 1.68E-07 1.25E-08 0.
6.98E-08 0.
1.37E-05 SE79 0.
2.10E-05 3.90E-06 0.
2.43E 05 O.
5.58E-07 1
8882 0.
O.
1.27E 05 O.
O.
O.
O.
BR83 + D 0.
O.
3.63E-07 0.
O.
O.
O.
BR84 0.
O.
3.82E-07 0.
O, O.
O.
8R85 O.
O.
1.94E 08 0.
O.
O.
O.
KR83M 0.
O.
O.
O.
O.
O.
O.
KR85M 0.
O.
O.
O.
O.
O.
O.
KR85 O.
O.
O.
O.
O.
O.
O.
KR87 0.
O.
O.
O.
O.
O.
O.
KR88 + D 0.
O.
O.
O.
O.
O.
O.
KR89 0.
O.
O.
O.
O.
O.
O.
RB86 0.
1.70E-04 8.40E-05 O.
O.
O.
4.35 E-06 RB87 O.
8.88E-05 3.52E-05 O.
O.
O.
5.98E-07 RB88 0.
4.98E-07 2.73E-07 0.
O.
O.
4.85E-07 RB89 + D 0.
2.86E-07 1.97E-07 0.
O.
O.
9.74E-08 SR89 + D 2.51 E-03 0.
7.20E 05 O.
O.
O.
5.16E-05 SR90+D 1.85E-02 0.
4.71 E-03 0.
O.
O.
2.31 E-04 SR91 + 0 S.00E-05 O.
1.81 E-06 0.
O.
O.
5.92E-05 SR92 + D 1.92E-05 O.
7.13E-07 0.
O.
O.
2.07E-04 a
76
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM /50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 8.69E-08 0.
2.33E-09 0.
O.
O.
1.20E-04 i
Y91 M + D S.10E-10 0.
2.76E-11 0.
O.
O.
2.70E-06 l
Y91 1.13E-06 0.
3.01 E-08 0.
O.
O.
8.10E-05 Y92 7.65 E-09 0.
2.15E-10 0.
O.
O.
1.46E-04 Y93 2.43E-08 0.
6.62E-10 0.
O.
O.
1.92E-04 ZR93 + D 1.93E-07 9.18E-08 5.54E-08 0.
2.71 E-07 0.
2.39E-05 ZR95 + D 2.06E-07 5.02E-08 3.56E-08 0.
5.41 E-08 0.
2.50E-05 1
ZR97 + D 1.48E-08 2.54E-09 1.16E-09 0,
2.56E-09 0.
1.62E-04 i
NB93M 1.23E-07 3.33E-08 1.04E 08 0.
3.25 E-08 0.
3.98E-06 NB95 4.20E-08 1.73E-08 1.00E-08 0.
1.24E-08 0.
1.46E-05 NB97 4.59E-10 9.79E-11 3.53E-11 0.
7.65E-11 0.
3.09E-05 MO93 0.
5.65E-05 1.82E-06 0,
1.13E-05 O.
1.21 E-06 MO99 + D 0.
3.40E-05 6.63E-06 0.
5.08E-05 O.
1.12E-05 i
TC99M 1.92E-09 3.96E-09 5.10E-08 0.
4.26E-08 2.07E-09 1.15E-06
]
TC99 1.08E-06 1.46E-06 4.55E-07 0.
1.23E-05 1.42E-07 6.31 E-06 TC101 2.27E-09 2.86E-09 2.83E-08 0.
3.40E-08 1.56E-09 4.86E-07 RU103+D 1.48E-06 0.
4.95E-07 0.
3.08E-06 0,
1.80E-05 RU105 + D 1.36E 07 0.
4.58E-08 0.
1.00E-06 0.
5.41 E-05 RU106 + D 2.41 E-05 O.
3.01 E-06 0,
2.85 E-05 O.
1.83E-04 RH105 1.09E-06 7.13E-07 4.79E-07 0.
1.98E-06 0.
1.77E-05 PD107 0.
1.19E-06 8.45E-08 0.
6.79E-06 0.
9.46E-07 PD109 0.
1.50E-06 3.62E-07 0.
5.51 E-06 0.
3.68E-05 AG110M + D 9.96E-07 7.27E-07 4.81E 07 0.
1.04E-06 0.
3.77E-05 AG111 5.20E-07 2.02E-07 1.07E-07 0.
4.22E-07 0.
4.82E-05 CD113M 0.
1.77E-05 6.52E-07 0,
1.34E-05 O.
2.66E-05 i
CD115M 0.
1.42E-05 4.93E-07 0.
7.41 E-06 0.
8.09E-05 SN123 2.49E-04 3.89E-06 6.50E-06 3.91 E-06 0.
O.
6.5 BE-05 SN125 + D 7.41 E-05 1.38E-06 3.29E-06 1.36E-06 0.
O.
1.11 E-04 SN126 + D 5.53E-04 7.26E-06 1.80E-05 1.91 E-06 0.
O.
2.52E-05 SB124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0.
1.34E-05 6.60E-05 SB125 + D 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.
7.72E-06 1.64E-05 SB126 8.06E-06 1.58E-07 2.91 E-06 6.19E-08 0.
5.07E-06 8.35E-05 SB127 2.23E-06 3.98E-08 6.90E-07 2.84E-08 0.
1.15E-06 5.91 E-05 TE125M 2.33E-05 7.79E-06 3.15 E-06 7.84E-06 0.
O.
1.11 E-05 i
TE127M + D 5.85E-05 1.94E-05 7.08E 06 1.69E-05 1.44E-04 0.
2.36E-05 1
TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.
2.10E-05 i
TE129M + D 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.
5.97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.
2.27E-05 TE131M + D 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 O.
1.03E-04 TE? 31 + D 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.
7.11 E-06 TE132 + D 2.08E-05 1.03E-05 9.61 E-06 1.52E-05 6.44E-05 O.
3.81 E-05 TE133M + D 3.91 E-07 1.79E-07 1.71 E-07 3.45E-07 1.22E-06 0.
1.93E-05 TE134 + D 2.67E-07 1.34E-07 1.38E-07 2.39E-07 9.03E-07 0.
3.06E-06 1129 2.86E-05 2.12E-05 1.55E-05 1.36E-02 2.51 E-05 O.
4.24E-07 1130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45 E-05 O.
2.83E-06 1131 + D 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 O.
1.51 E-06 77
PAUSADES NUCLFAR PLANT _
OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS ISOTOPE 80NE LIVER TOTAL BODY THYRolD TED IN FIRST YR) 1132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.
2.73E.06 KIDNEY LUNG Gl-LLI 1133 + D 1.25 E-05 1.82E-05 5.33E-06 3.31 E-03 2.14E-05 O.
1134 8.69E-07 1.78E-06 6.33E-07 4,15 E-05 1.99E-06 0.
3.08E-06 1135 + D 3.64E-06 7.24E-06 2.64E-06 6.49E 04 8.07E-06 0.
2.62E-06 1.84E-06 XE131M 0.
O.
O.
O.
O.
O.
O.
XE133M 0.
O.
O.
O.
O.
O.
O.
XE133 0.
O.
O.
O.
O.
O.
O.
XE135M 0.
O.
O.
O.
O.
O.
O.
XE135 O.
O.
O.
O.
O.
O.
O.
XE137
' O.
O.
O.
O.
O.
O.
O, i
XE138 + D 0.
O.
O.
O.
O.
O.
O.
CS134M + 0 1.76E-07 2.93E-07 1.48E-07 0.
1.13E-07 2.60E-08 2.32E-07 CS134 3.77E-04 7.03E-04 7.10E-05 O.
1.81 E-04 7.42E-05 1.91 E-06 CS135 1.33E-04 1.21 E-04 6.30E-06 0.
3.44E-05 1.31 E-05 4.37E-07 CS136 4.59E-05 1.35E-04 5.04E-05 O.
5.38E-05 1.10E-05 2.05E-06 CS137 + D 5.22E-04 6.11 E-04 4.33E-05 O.
1.64E-04 6.64E-05 1.91 E-06 CS138 4.81 E-07 7.82E-07 3.79E-07 0.
3.90E 07 6.09E-08 1.25E-06 CS139+D 3.10E-07 4.24E-07 1.62E-07 0.
2.19E-07 3.30E-08 2.66E-08 BA139 8.81 E-07 5.84E-10 2.55E-08 0,
3.51 E-10 3.54E-10 5.58E-05 BA140 + 0 1.71 E-04 1.71 E-07 8.81 E-06 0.
4.06E-08 1.05E-07 4.20E-05 BA141 + D 4.25E-07 2.91E 10 1.34E-08 0.
1.75E-10 1.77E-10 5.19E-06 BA142 + 0 1.84E-07 1.53E 10 9.06E-09 0.
8.81 E-11 9.26E-11 7.59E-07 LA140 2.11 E-08 8.32E-09 2.14E-09 0.
O.
O.
9.77E-05 LA141 2.89E-09 8.38E-10 1.46E-10 0.
O.
O.
LA142 1.10E-09 4.04E-10 9.67E-11 0.
O.
O.
6.86E-05 9.61 E-05 CE141 7.87E-08 4.80E-08 5.65E-09 0.
1.48E-08 0.
2.48E-05 CE143 + D 1.48E-08 9.82E-06 1.12E-09 0.
2.86E-09 0,
5.73E-05 CE144 + D 2.98E-06 1.22E-06 1.67E-07 0.
4.93E-07 0.
1.71 E-04 PR143 8.18E-08 3.04E-08 4.03E-09 0.
1.13E-08 0.
4.29E-05 PR144 2.74E-10 1.06E-10 1.3BE-11 0.
3.84E 11 0.
4.93E-06 ND147+D 5.53E-08 5.68E-08 3.48E-09 0.
2.19E-08 0.
3.60E-05 i
PM147 3.88E-07 3.27E-08 1.59E-08 0.
4.88E-08 0.
9.27E-06 PM148M + D 1.65 E-07 4.18E-08 3.28E-08 0.
4.80E-08 0.
5.443-05 PM148 6.32E-08 9.13E-09 4.60E 09 0.
1.09E-08 0.
0.74E-05 PM149 1.38E-08 1.81 E-09 7.90E-10 0.
2.20E-09 0.
PM151 6.18E-09 9.01 E-10 4.56E 10 0.
1.07E49 0.
4.86E-05 SM151 2.90E 07 6.67E-08 1.44E-08 0.
4.53E-08 0,
5.58E-06 4.17E-05 SM153 7.72E 09 5.97E-09 4.58E-10 0.
1.25E-09 0.
3.12 E-05 EU152 6.74E-07 1.79E-07 1.51 E-07 0.
5.02E-07 0.
1.59E 05 EU154 2.64E-06 3.67E-07 2.20E-07 0.
9.95E-07 0.
4.58E-05 EU155 5.42E-07 6.25E-08 3.23E-08 0.
1.40E-07 0.
8.37E-05 EU156 1.14E-07 7.06E-08 1.12E-08 0.
3.26E-08 0.
6.67E-05 T8160 2.59E-07 0.
3.24E-08 0.
7.37E-08 0.
3.45 E-05 HOl66M 1.25 E-06 2.69E-07 2.13E-07 0,
3.57E-07 0.
O.
W181 8.85E-08 2.72E-08 3.04E-09 0.
O.
O.
3.82E 07 W185 3.62E-06 1.13E-06 1.29E-07 0.
O.
O.
1.62 E-05 W187 9.03E-07 6.28E-07 2.17E-07 0.
O.
O.
3.69E-05 78
PALISADES NUClFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM /50Y PER PCIINGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROlD KIDNEY LUNG GI-LLI P8210 + D 5.28E-02 1.42 E-02 2.38E-03 0.
4.33E-02 0.
5.62E-05 81210 + D 4.16E-06 2.68E-05 3.58E-07 0.
2.08E-04 0.
5.27E-05 PO210 3.10E-03 5.93E-03 7.41 E-04 0.
1.26E-02 0.
6.61 E-05 RN222 + D 0.
O.
O.
O.
O.
O.
O.
2 l
RA223 + D 4.41 E-02 6.42E-05 8.82E-03 0.
1.17E-03 0.
3.43E-04 RA224 + D 1.46E-02 3.29E-05 2.91 E-03 0.
6.00E-04 0.
3.86E-04 RA225 + D 5.78E-02 6.42E-05 1.15E-02 0.
1.19E-03 0.
3.24E-04 RA226 + D 6.20E-01 4.76E-05 5.14E-01 0.
8.71 E-04 0.
3.44E-04 RA228 + D 4.32E-01 2.58E-05 4.86E-01 0.
4.73E-04 0.
5.86E-05 AC225 3.92E-05 5.03E-05 2.63E-06 0.
3.69E-06 0.
4.36E-04 AC227 + D 4.49E-03 7.67E-04 2.79E-04 0.
1.56E-04 0.
8.50E-05 TH227 + D 1.20E-04 2.01 E-06 3.45E-06 0.
7.41 E-06 0.
5.70E-04 TH228 + D 2.47E-03 3.38E-05 8.36E-05 O.
1.58E-04 0.
5.84E-04 TH229 1.48E-02 1.94E-04 7.29E-04 0.
9.29E-04 0.
5.31 E-04 TH230 3.80E-03 1.90E-04 1.06E-04 0.
9.12E-04 0.
6.24E-05 TH232 + D 4.24E-03 1.63E-04 1.65 E-04 0.
7.79E-04 0.
5.31 E-05 TH234 6.92 E-07 3.77E-08 2.00E-08 0.
1.39E-07 0.
1.19E-04 PA231 + D 7.57E-03 2.50E-04 3.02E-04 0.
1.34E-03 0.
7.44E-05 PA233 3.11 E-08 6.09E-09 5.43E-09 0.
1.67E-08 0.
1.46E-05 U232 + D 2.42E-02 0.
2.16E-03 0.
2.37E-03 0.
7.04E-05 U233 + D 5.08E-03 0.
3.87E-04 0.
1.08E-03 0.
6.51 E-05 U234 4.88E-03 0.
3.80E-04 0.
1.06E-03 0.
6.37E-05 U235 + D 4.67E-03 0.
3.56E-04 0.
9.93E-04 0.
8.10E-05 U236 4.67E-03 0.
3.64E-04 0.
1.01 E-03 0.
5.98E-05 U237 4.95E-07 0.
1.32E-07 0.
1.23E-06 0.
2.11 E-05 U238 + D 4.47E-03 0,
3.33E-04 0.
9.28E-04 0.
5.71 E-05 NP237 + D 2.53E-03 1.93E-04 1.05E-04 0.
6.34E-04 0.
8.23E-05 NP238 1.24E-07 3.12E-09 1.92E-09 0.
6.81 E-09 0.
4.17E-05 NP239 1.11 E-08 9.93E-10 5.61E 10 0.
1.98E-09 0.
2.87E-05 PU238 1.34E-03 1.69E-04 3.40E-05 O.
1.21 E-04 0.
7.57E-05 PU239 1.45E-03 1.77E-04 3.54E-05 O.
1.28E-04 0.
6.91 E-05 PU240 1.45E-03 1.77E-04 3.54E-05 O.
1.28E-04 0.
7.04E-05 PU241 + D 4.38E-05 1.90E-06 8.82E-07 0.
3.17E-06 0.
1.45E-06 PU242 1.35E-03 1.70E-04 3.41 E-05 0.
1.23E-04 0.
6.77E-05 PU244 1.57E-03 1.95 E-04 3.91 E-05 O.
1.41 E-04 0.
1.01 E-04 AM241 1.53E-03 7.18E-04 1.09E-04 0.
6.55 E-04 0.
7.70E-05 AM242M 1.58E-03 7.02E-04 1.13E-04 0.
6.64E-04 0.
9.69E-05 AM243 1.51 E-03 6.88E-04 1.06E-04 0.
6.36E-04 0.
9.03E-05 CM242 1.37E-04 1.24E-04 9.10E-06 0.
2.62E-05 O.
8.23E-05 CM243 1.45 E-03 6.88E-04 8.98E-05 O.
3.27E-04 0.
8.10E-05 CM244 1.22E-03 6.16E-04 7.59E-05 O.
2.71 E-04 0.
7.84E-05 CM245 1.88E-03 7.49E-04 1.13E-04 0.
4.32E-04 0.
7.30E-05 CM246 1.87E-03 7.49E-04 1.13E-04 0.
4.31 E-04 0.
7.17E-05 CM247 + D 1.82E-03 7.36E-04 1.11 E-04 0.
4.24E-04 0.
9.43E-05 CM248 1.51 E-02 6.07E-03 9.16E-04 0.
3.50E-03 0.
1.52E-03 CF252 1.24E-03 0.
2.95E-05 0
0.
O.
2.99E-04 79
~.
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
\\
4 Revision 10 i
TABLE 21 CHILD INGESTION DOSE COMMITMENT FACTORS (M ISOTOPE BONE LIVER TOTAL BODY THYRotD KIDNEY LUNG GI-LLI YR) i H3 0.
2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 8E10 1.35E-05 1.57E-06 3.39E-07 0.
1.11 E-06 0.
2.75 E-05 C14 1.21 E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 N13 3.10E 08 3.10E-08 3.10E 08 3.10E-08 3.10E-08 3.10E-08 3.10E-08 F18 2.49E-06 0.
2.47E-07 0.
O.
O.
6.74E-07 NA22 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 NA24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P32 8.25E-04 3.86E-05 3.18E-05 O.
O.
O.
2.28E-05 AR39 0.
O.
O.
O.
O.
O.
O.
i j
AR41 0.
O.
O.
O.
O.
O.
O.
CA41 3.47EO4 0.
3.79E-05 O.
O.
O.
1.90E-07 SC46 1.97E-Ob 2.70E-08 1.04 E-08 0.
2.30E-08 0.
3.95E-05 1
CR51 0.
O.
8.90E-09 4.94E-09 1.35 E-09 9.02E-09 4.72E-07 MN54 0.
1.07E-05 2.85E-06 0.
3.00E-06 0.
8.98E-06 t
MN56 0.
3.34E-07 7.54E-08 0.
4.04E-07 0.
4.84E-05 FESS 1.15E-05 6.10E-06 1.89E-06 0.
O.
3.45 E-06 1.13E-06 FE59 1.65E-05 2.67E-05 1.33E-05 O.
O.
7.74E-06 2.78E-05 C057 0.
4.93E-07 9.98E-07 0.
O.
O.
4.04E-06 I
C058 0.
1.80E-06 5.51 E-06 0.
O.
O.
1.05E-05 i
CO60 0.
5.29E-06 1.56E-05 O.
O.
O.
2.93E-05 i
N159 4.02E-05 1.07E-05 6.82E-06 0.
O.
O.
7.10E-07 3
N163 5.38E-04 2.88E-05 1.83E-05 O.
O.
O.
1.94E-06 N165 2.22E-06 2.09E-07 1.22E-07 0.
O.
O.
2.56E-05 CU64 0.
2.45E-07 1.48E-07 0.
5.92E-07 0.
1.15E-05 ZN65 1.37E-05 3.65 E-05 2.27E-05 O.
2.30E-05 O.
6.41 E-06 i
ZN69M + D 7.10E-07 1.21 E-06 1.43E-07 0.
7.03E-07 0.
3.94E-05 i
ZN69 4.38E-08 6.33E-08 5.85 E-09 0,
3.84E-08 0.
3.99E-06 SE79 0,
8.43E-06 1.87E-06 0.
1.37E-05 O.
5.53E-07 i
BR82 0.
O.
7.55E-06 0.
O.
O.
O.
i BR83+0 0.
O.
1.71 E-07 0.
O, O.
O.
8R84 0.
O.
1.98E-07 0.
O.
O.
O.
BR85 0
0.
9.12E-09 0.
O.
O.
O.
KR83M 0.
O.
O.
O.
O.
O.
O.
KR85M 0.
O.
O.
O.
O.
O.
O.
t KR85 O.
O.
O.
O.
O.
O.
O.
1 KR87 0.
O.
O.
O.
O.
O.
O.
KR88+D 0.
O.
O.
O.
O.
O.
O.
KR89 0.
O.
O.
O.
O.
O.
O.
4 RB86 0.
6.70E-05 4.12E-05 O.
O.
O.
4.31E-06 RB87 O.
3.95 E-05 1.83E-05 O.
O.
O.
5.92E-07 R888 0.
1.90E-07 1.32E-07 0.
O.
O.
9.32E-09 RB89 + D O.
1.17E-07 1.04E-07 0.
O.
O.
1.02E-09 SR89 + D 1.32E-03 0.
3.77E-05 O.
O.
O.
5.11 E-05 i
SR90 + D 1.70E-02 0.
4.31 E-03 0.
O.
O.
2.29E-04 SR91 + D 2.40E-05 O.
9.06E-07 0.
O.
O.
5.30E 05 SR92+D 9.03E-06 0.
3.62E-07 0.
O.
O.
1.71 E-04 i
80
PALISADES NUClFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 11 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM /50Y PER PCI INGESTED IN FIRST YR) 4 ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 4.11 E-08
'O.
1.10E-09 0.
O.
O.
1.17E-04 Y91 M + D 3.82E-10 0.
1.39E-11 0.
O.
O.
7.48E-07 Y91 6.02E-07 0.
1.61 E-08 0.
O.
O.
8.02E-05 Y92 3.60E-09 0.
1.03E-10 0.
O.
O.
1.04 E-04 Y93 1.14E-08 0.
3.13E 10 0.
O.
O.
1.70E-04 i
ZR93 + D 1.67E-07 6.25E-08 4.45 E-08 0.
2.42E-07 0,
2.37E-05 ZR95 + D 1.16E-07 2.55 E-08 2.27E-08 0.
3.65 E-08 0.
2.66E-05 ZR97 + D 6.99E-09 1.01 E-09 5.96E-10 0.
1.45E-09 0.
1.53E-04 NB93M 1.05E-07 2.62E-08 8.61 E-09 0.
2.83E-08 0.
3.95 E-06 NB95 2.25E-08 8.76E-09 6.26E-09 0.
8.23E-09 0.
1.62E 05 NB97 2.17E 10 3.92E-11 1.83E-11 0.
4.35E-11 0,
1.21 E-05 MO93 0.
2.41 E-05 8.65 E-07 0.
6.35 E-06 0.
1.22 E-06 MLF.9+D 0.
1.33E-05 3.29E-06 0.
2.84E-05 O.
1.10E 05 TC99M 9.23E-10 1.81 E-09 3.00E-08 0.
2.63E-08 9.19E 10 1.03E-06 TC99 5.35 E-07 5.96E-07 2.14E-07 0.
7.02E-06 5.27E-08 6.25 E-06 TC101 1.07E-09 1.12E-09 1.42 E-08 0.
1.91 E-08 5.92E 10 3.56E-09 i
RU103 + D 7.31 E-07 0.
2.81 E-07 0,
1.84E-06 0.
1.89E-05 RU105 + D 6.45 E-08 0.
2.34E-08 0.
5.67E-07 0.
4.21 E-05 RU106 + D 1.17E-05 O.
1.46E-06 0.
1.58E-05 0.
1.82E-04 RH105 5.14E-07 2.76E-07 2.36E-07 0.
1.10E-06 0.
1.71 E-05 PD107 0.
4.72E-07 4.01 E-08 0.
3.95E-06 0.
9.37E-07 i
PD109 0.
5.67E-07 1.70E-07 0.
3.04E-06 0.
3.35E-05 AG110M + D 5.39E-07 3.64E-07 2.91 E-07 0,
6.78E-07 0.
4.33E-05 AG111 2.48E-07 7.76E-08 5.12E-08 0.
2.34E-07 0.
4.75E-05 CD113M O.
1.02E-05 4.34E-07 0.
1.05E-05 O.
2.63E-05 CD115M 0.
5.89E-06 2.51 E-07 0.
4.38E-06 0.
8.01 E-05 SN123 1.33E-04
~ 1.65 E-06 3.24E-06 1.75E-06 0.
O.
6.52E-05 SN125 + D 3.55E-05 5.35 E-07 1.59E-06 5.55E-07 0.
O.
1.10E-04 SN126 + D 3.33E-04 4.15E-06 9.46E-06 1.14E-06 0.
O.
2.50E-05 SB124 1.11 E-05 1.44E-07 3.89E-06 2.45 E-08 0.
6.16E-06 6.94E-05 SB125 + D 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.
3.99E-06 1.71 E-05 S8126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 0.
2.10E-06 8.87E-05 S8127 1.06E-06 1.64E-08 3.68E-07 1.18E-08 0.
4.60E-07 5.97E-05 TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.
O.
1.10E-05 TE127M + D 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 O.
2.34E-05 TE127 4.71 E-07 1.27E-07 1.01 E-07 3.26E-07 1.34E-06 0.
1.84E-05 TE129M + D 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.
5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.
8.34E-06 TE131 M + D 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41 E-05 O.
1.01 E-04 TE131 + D 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51 E-07 0.
4.36E-07 TE132 + D 1.01 E-05 4.47E-06 5.40E-06 6.51 E-06 4.15E-05 O.
4.50E-05 TE133M v D 1.87E-07 7.56E-08 9.37E-08 1.45 E-07 7.18E-07 0.
5.77E-06 TE134 + D 1.29E-07 5.80E-08 7.74E-08 1.02E-07 5.37E-07 0.
5.89E-07 1129 1.39E-05 8.53E-06 7.62E-06
5.58E-03 1.44E-05 O.
4.29E-07 1130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.
2.76E-06 1131 + D 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 O.
1.54E-06 81
PALISADES NUCLFAR PLANT i
OFFSITE DOSE CALCULATION MANUAL i
Revision 10 TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM /50Y PER ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI I
1132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.
1.73E 06 1133 + D 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 O.
2.95E-06 1134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.
5.16E-07 1135 + D 1.75E-06 3.15 E-06 1.49E-06 2.79E-04 4.83E-06 0.
2.40E-06 XE131M 0.
O.
O.
O.
O.
O.
O.
XE133M 0.
O.
O.
O.
O.
O.
O.
3 XE133 0.
O.
O.
O.
O.
O.
O.
i XE135M 0.
O.
O.
O.
O.
O.
O.
XE135 O.
O.
O.
O.
O.
O.
O.
XE137 0.
O.
O.
O.
O.
O.
O.
XE138 + D 0.
O.
O.
O.
O.
O.
O.
CS134M + D 8.44E-08 1.25 E-07 8.16E-08 0.
6.59E-08 1.09E-08 1.58E-07 CS134 2.34E-04 3.84E-04 8.10E-05 O.
1.19E-04 4.27E-05 2.07E-06 CS135 8.30E-05 5.78E-05 5.93E-06 0.
2.04E-05 6.81 E-06 4.33E-07 CS136 2.35E-05 6.46E-05 4.18E-05 O.
3.44E-05 5.13E 06 2.27E-06 CS137 + D 3.27E-04 3.13E-04 4.62E-05 O.
1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.01 E-07 0.
2.23E-07 2.40E-08 1.46E-07 CS139 + D 1.45E-07 1.61 E-07 7.74E-08 0.
1.21 E-07 1.22E-08 1.45 E-11 BA139 4.14E-07 2.21 E-10 1.20E-08 0.
1.93E-10 1.'30E 10 2 39E 05 BA140+D 8.31 E-05 7.2BE-08 4.85 E-06 0.
2.37E-08 4.34E-08 4.21 E-05 BA141 + D 2.00E-07 1.12E-10 6.51 E-09 0.
9.69E-11 6.58E-10 1.14E-07 8A142 + D 8.74E-08 6.29E-11 4.88E-09 0.
5.09E-11 3.70E-11 1.14E 09 LA140 1.01 E-08 3.53E-09 1.19E-09 0.
O.
O.
9.84E-05 LA141 1.35E-09 3.17E-10 6.88E-11 0.
O.
O.
7.05E-05 LA142 5.24E-10 1.67E-10 5.23E-11 0.
O.
O.
3.31 E-05 CE141 3.97E-08 1.98E-08 2.94E-09 0.
8.68E-09 0.
2.47E-05 CE143 + 0 6.99E-09 3.79E-06 5.49E-10 0.
1.59E-09 0.
5.55E-05 CE144 + D 2.08E-06 6.52E-07 1.11 E-07 0.
3.61E 07 0.
1.70E-04 PR143 3.93E-08 1.18E-08 1.95 E-09 0.
6.39E-09 0.
4.24E-05
{
PR144 1.29E-10 3.99E 11 6.49E-12 0.
2.11 E-11 0.
8.59E 08 ND147 + D 2.79E-08 2.26E 08 1.75E-09 0.
1.24E-08 0.
3.58E-05 PM147 3.18E-07 2.27E-08 1.22E-08 0.
4.01 E-08 0.
9.19E-06 PM148M + D 1.03E-07 2.05 E-08 2.05E-08 0.
3.04E-08 0.
5.78E-05 PM148 3.02E-08 3.63E-09 2.35E-09 0.
6.17E-09 0.
9.70E-05 PM149 6.49E-09 6.90E-10 3.74E-10 0.
1.22E-09 0.
4.71 E-05 PM151 2.92E-09 3.55E-10 2.31 E-10 0.
6.02E-10 0.
4.03E-05 SM151 2.56E-07 3.81 E-08 1.20E-08 0.
3.94E-08 0.
5.53E-06
)
SM153 3.65 E-09 2.27E-09 2.19E-10 0,
6.91 E-10 0.
3.02E 05 EU152 6.15E-07 1.12E-07 1.33E-07 0.
4.73E-07 0.
1.84E-05 EU154 2.30E-06 2.07E-07 1.89E-07 0.
9.09E-07 0.
4.81 E-05 EU155 4.82E-07 3.47E-08 2.72E-08 0.
1.30E-07 0.
8.69E-05 EU156 5.62E-08 3.01 E-08 6.23E-09 0.
1.94E-08 0.
6.83E-05 T8160 1.66E-07 0.
2.06E-08 0.
4.94E-08 0.
3.68E-05 HO166M 1.08E-06 2.26E-07 1.91E-07 '
O.
3.22E-07 0.
O.
W181 4.23E-06 1.04E-08 1.43E-09 0.
O.
O.
3.79E-07 W185 1.73E-06 4.32E-07 6.05E 08 0.
O.
O.
1.61 E-05 WS87 4.29E-07 2.54E-07 1.14E-07 0.
O.
O.
3.57E-05 82
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM /50Y PER PCIINGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI P8210 + D 4.75E-02 1.22E-02 2.09E-03 0.
3.67E-02 0.
5.57E-05 B1210 + D 1.97E-06 1.02 E-05 1.69E-07 0.
1.15E-04 0.
5.17E-05 PO210 1.52E-03 2.43E-03 3.67E-04 0.
7.56E-03 0.
6.55E-05 RN222 + D O.
O.
O.
O.
O.
O.
O.
RA223 + D 2.12E-02 2.45 E-05 4.24E 03 0.
6.50E-04 0,
3.38E-04 RA224 + D 6.89E-03 1.25E-05 1.38E-03 0.
3.31 E-04 0.
3.78E-04 RA225 + D 2.80E-02 2.50E-05 5.59E-03 0.
6.62E-04 0.
3.21 E-04 RA226 + D 5.75 E-01 1.84E-05 4.72E-01 0.
4.88E-04 0.
3.41E-04 RA228 + D 3.85 E-01 9.99E-06 4.32E-01 0.
2.65 E-04 0.
5.81 E-05 AC225 1.88E-05 1.94E-05 1.26E-06 0.
2.07E-06 0.
4.31 E-04 AC227+D 4.12E-03 6.63E-04 2.55E-04 0.
1.46E-04 0.
8.43E-05 TH227 + D 5.85E-05 7.96E-07 1.69E-06 0.
4.22E-06 0.
5.63E-04 TH228 + D 2.07E-03 2.65 E-05 7.00E-05 O.
1.38E-04 0.
5,79E-04 TH229 1.38E-02 1.81 E-04 6.80E-04 0.
8.84E-04 0.
5.27E-04 TH230 3.55 E-03 1.78E-04 9.91 E-05 O.
8.67E-04 0.
6.19E-05 TH232 + D 3.9SE-03 1.52E-04 3.01 E-04 0.
7.41 E-04 0.
5.27E-05 TH234 3.42E-07 1.51 E-08 9.88E-09 0.
8.01 E-08 0.
1.18E-04 PA231 + D 7.07E-03 2.34E-04 2.81E-04 0.
1.28E-03 0.
7.37E-05 PA233 1.81 E-08 2.82E-09 3.16E-09 0.
1.04E-08 0.
1.44E-05 U232 + D 1.76E-02 0.
1.26E-03 0.
1.34E-03 0.
6.98E-05 U233 + 0 3.72E-03 0.
2.25 E-04 0.
6.10E-04 0.
6.45E-05 U234 3.57E-03 0.
2.21 E-04 0.
5.98E-04 0.
6.32E-05 U235 + D 3.42E-03 0.
2.07E-04 0.
5.61 E-04 0.
8.03E-05 U236 3.42E-03 0.
2.12E-04 0,
5.73E-04 0.
5.92E-05 U237 2.36E-07 0.
6.27E-08 0.
6.81 E-07 0.
2.08E-05 U238 + 0 3.27E-03 0.
1.94E-04 0,
5.24E-04 0.
5.66E-05 NP237 + D 2.36E-03 1.81 E-04 9.79E-05 O.
6.05E-04 0.
8.16E-05 NP238 5.83E-08 1.18E-09 9.08E.10 0.
3.76E-09 0.
4.04E 05 NP239 5.25E-09 3.77E-10 2.65E-10 0.
1.09E-09 0,
2.79E-05 PU238 1.25E-03 1.56E-04 3.16E-05 O.
1.15E-04 0.
7.50E-05 PU239 1.36E-03 1.65E-04 3.31 E-05 0,
1.22E-04 0.
6.85E-05
)
PU240 1.36E-03 1.65E-04 3.31 E-05 O.
1.22E-04 0.
6.98E-05 PU241 + D 4.00E-05 1.72E-C6 8.04E-07 0.
2.96E-06 0.
1.44E-06 PU242 1.26E-03 1.59E-04 3.19E-05 O.
1.17E-04 0.
6.71 E-05 PU244 1.47E-03 1.82E-04 3.65E-05 0.
1.35 E-04 0.
1.00E-04 AM241 1.43E-03 6.40E-04 1.02E-04 0.
6.23E-04 0.
7.64E-05 AM242M 1.47E-03 6.25 E-04 1.045-04 0.
6.30E-04 0.
9.61 E-05 AM243 1.41 E-03 6.14E-04 9.836-05 O.
6.06E-04 0.
8.95E-05 CM242 8.80E 05 6.73E-05 5.84E-06 0.
1.87E-05 O.
8.16E-05 CM243 1.33E-03 0.03E 04 8.24E-05 O.
3.08E-04 0.
8.03E-05 CM244 1.11 E-03 5.36E-04 6.93E-05 O.
2.54E-04 0.
7.77E-05 CM245 1.76E-03 6.64E-04 1.05E-04 0.
4.11 E-04 0.
7.24E 05 CM246 1.74E-03 6.64E-04 1.05 E-04 0.
4.10E-04 0.
7.11 E-05 CM247 + 0 1.70E-03 6.53E-04 1.03E-04 0.
4.04E-04 0.
9.35E 05 CM248 1.41 E-02 5.38E-03 8.52E-04 0.
3.33E-03 0.
1.51 E-03 CF252 1.07E-03 0.
2.54E-05 O.
O.
O.
2.96E-04 83
PALISADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS IM ISOTOPE SONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI
)
H3 0.
1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 BE10 4.48E-06 6.94E-07 1.13E-07 0.
5.30E-07 0.
2.84E-05 C14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E 07 8.12E-07 8.12E-07 N13 1.15E-08 1.15E-08 1.15E-08 1.15 E-08 1.15E-08 1.15E-08 1.15E-08 F18 8.64E-07 0.
9.47E-08 0.
O.
O.
7.78E-08 NA22 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E 05 2.34E-05 NA24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P32 2.76E-04 1.71 E-05 1.07E-05 O.
O.
O.
2.32E-05 AR39 0.
O.
O.
O.
O.
O.
O.
4 AR41 0.
O.
O.
O.
O.
O.
O.
CA41 1.97E-04 0.
2.13E-05 O.
O.
O.
1.95E-07 SC46 7.24E-09 1.41 E-08 4.18E-09 0.
1.35E-08 0.
4.80E-05 CR51 0.
O.
3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN54 0.
5.90E-06 1.17E-06 0.
1.76E-06 0.
1.21 E-05 MN56 0.
1.58E-07 2.81 E-08 0.
2.00E-07 0.
1.04E-05 FE55 3.78E-06 2.68E-06 6.25E-07 0.
O.
1.70E-06 1.16E-06 FE59 5.87E-06 1.37E-05 5.29E-06 0.
O.
4.32E-06 3.24E-05 C057 0.
2.38E-07 3.99E-07 0.
O.
O.
4.44E-06 i,
C058 0.
9.72E-07 2.24E-06 0.
O.
O.
1.34E-05 CO60 0
2.81 E-06 6.33E-06 0.
O.
O.
3.66E-05 NI59 I
1.32E-05 4.66E-06 2.24E-06 0.
O.
O.
7.31 E-07 NI63 1.77E-04 1.25 E-05 6.00E-06 0.
O.
O.
1.99E-06 Nf65 7.49E 07 9.57E 08 4.36E-08 0.
O.
O.
5.193-06 CU64 O.
1.15E-07 5.41 E-08 0.
2.91 E-07 0.
8.92E-06 ZN65 5.76E-06 2.00E-05 9.33E-06 0.
1.28E-05 O.
8.47E-06 ZN69M + D 2.40E-07 5.66E-07 5.19E-08 0.
3.44E-07 0.
3.11 E-05 ZN69 1.47E-08 2.80E-08 1.96E-09 0,
1.83E-08 0.
5.16E-08 SE79 0.
3.73E-06 6.27E-07 0.
6.50E-06 0.
5.70E-07 BRB2 0.
O.
3.04E-06 0.
O.
O.
O.
BR83+D 0.
O.
5.74E-08 0.
O.
O.
O.
BR84 0.
O.
7.22E 08 0.
O.
O.
O.
8R85 O.
O.
3.05E-09 0.
O.
O.
O.
KR83M 0.
O.
O.
O.
O.
O.
O.
KR85M 0.
O.
O.
O.
O.
O.
O.
KRBS 0.
O.
O.
O.
O.
O.
O.
KR87 0.
O.
O.
O.
O.
O.
O.
KR88 + D O.
O.
O.
O.
O.
O.
O.
KR89 0.
O.
O.
O.
O.
O.
O.
I RBBS 0.
2.98E-05 1.40E-05 O.
O.
O.
4.41 E-06 RB87 0.
1.75E-05 6.11 E-06 0.
O.
O.
6.11 E-07 3
RB88 0.
8.52E-08 4.54E-08 0.
O.
O.
7.30E-15 1
RB89 + D 0,
5.50E-08 3.89E-08 0.
O.
O.
8.43E-17 SR89 + D 4.40E-04 0.
1.26E-05 O.
O.
O.
M.24E-05 SR90 + D 8.30E-03 0.
2.05E-03 0.
O.
O.
2.33E-04
~
SR91 +D 8.07E-06 0.
3.21 E-07 0.
O.
O.
3.66E-05 SR92 + D 3.05E-06 0.
1.30E-07 0.
O.
O.
7.77E-05 84
~.
l PALISADES NUCtFAR PLANT OFFSITE DOSE CALCULATION MANUE Revision 10 TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM /50Y PER PCIINGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROlD KIDNEY LUNG GI-LLI Y90 1.37E-08 0.
3.69E.10 0.
O.
O.
1.13E-04 Y91 M + D 1.29E-10 0.
4.93E-12 0.
O.
O.
6.09E-09 Y91 2.01 E-07 0.
5.39E-09 0.
O.
O.
8.24E-05 Y92 1.21 E-09 0.
3.50E-11 0.
O.
O.
3.32E 05 Y93 3.83E-09 0.
1.05E 10 0.
O.
O.
1.17E-04 ZR93 + 0 5.53E-08 2.73E-08 1.49E-08 0.
9.65E-08 0.
2.58E-05 ZR95 + D 4.12E-08 1.30E-08 8.94E-09 0.
1.91 E-08 0.
3.00E-05 ZR97 + D 2.37E-09 4.69E 10 2.16E-10 0.
7.11 E-10 0.
1.27E-04 N893M 3.44 E-08 1.13E-08 2.83E-09 0.
1.32E-08 0.
4.07E-06 NB95 8.22E 09 4.56E-09 2.51 E-09 0.
4.42E-09 0.
1.95E-05 N897 7.37E 11 1.83E-11 6.68E 12 0.
2.14E-11 0.
4.37E-07 MO93 0,
1.06E-05 2.90E 07 0.
3.04E-06 0.
1.29E-06 MO99 + D 0.
6.03E-06 1.15 E-06 0.
1.38E-05 O.
1.08E-05 TC99M 3.32E-10 9.26E-10 1.20E-08 0.
1.38E-08 5.14E 10 6.08E-07 TC99 1.79E-07 2.63E-07 7.17E-08 0.
3.34E-06 2.72E-08 6.44E-06 TC101 3.60E 10 5.12E-10 5.03E-09 0.
9.26E-09 3.12E-10 8.75E-17 RU103 + D 2.55 E-07 0.
1.09E-07 0.
8.99E-07 0.
2.13E-05 RU105 + D 2.18E-08 0.
8.46E-09 0.
2.75E-07 0.
1.76E-05 RU106 + D 3.92E-06 0.
4.94E-07 0.
7.56E-06 0.
1.88E-04 RH105 1.73E-07 1.25 E-07 8.20E-08 0.
5.31 E-07 0.
1.59E-05 i
PD107 0,
2.08E-07 1.34E-08 0,
1.88E-06 0.
9.66E-07 PD109 0.
2.51 E-07 5.70E-08 0.
1.45E-06 0.
2.53E-05 AG110M + D 2.05E-07 1.94E-07 1.18E-07 0.
3.70E-07 0.
5.45E-05 l-AG111 8.29E-08 3.44E 08 1.73E-08 0.
1.12E-07 0.
4.80E-05 CD113M 0.
4.51 E-06 1.45 E-07 0.
4.99E-06 0.
2.71 E-05 4
CD115M O.
2.60E-06 8.39E-08 0.
2.08E-06 0.
8.23E-05 i
SN123 4.44E-05 7.29E-07 1.08E-06 5.84E-07 0.
O.
6.71 E-05 SN125 + D 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0.
O.
1.12E-04 SN126+D 1.16E-04 2.16E-06 3.30E-06 5.69E-07 0.
O.
2.58E-05 SB124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 0.
3.38E-06 7.80E-05 S8125 + D 2.48E-06 2.71 E-08 5.80E-07 2.37E-09 0.
2.18E-06 1.93E-05 SB126 1.59E-06 3.25 E-08 5.71 E-07 8.99E-09 0.
1.14E-06 9.41 E-05 S8127 3.63E-07 7.76E-09 1.37E-07 4.08E-09 0.
2.47E-07 6.16E-05 TE125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.
O.
1.13E-05 TE127M + D 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 O.
2.41 E-05 TE127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.
1.22E-05 TE129M + D 1.63 E-05 6.05 E-06 2.58E-06 5.26E-06 6.82E-05 O.
6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0,
2.45E-07 TE131 M + D 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 O.
9.39E-05 TE131 + D 2.79E-08 1.15 E-08 8.72E-09 2.15E-08 1.22E-07 0.
2.29E-09 TE132 + D 3.49E-06 2.21 E-06 2.08E-06 2.33E-06 2.12E-05 O.
7.00E-05 TE133M + D 6.44E-08 3.66E-08 3.56E-08 5.11 E-08 3.62E-07 0.
1.48E-07 TE134 + D 4.47E-08 2.87E-08 3.00E-08 3.67E-08 2.74E-07 0.
1.66E-09 1129 4.66E-06 3.92E-06 6.54E-06 4.77E-03 7.01 E-06 0.
4.57E-07 1130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.
2.29E-06 1131 + D 5.85 E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 O.
1.62E-06 85
i PALISADES NUCtEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10
)
\\
TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORSlM ISOTOPE BONE LIVER TOTAL BODY THYROID ST YR) 1132 2.79E-07 7.30E 07 2.62E-07 2.46E-05 1.15E-06 0.
3.18E-07 KIDNEY LUNG GILLI 1133 + D 2.01 E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 0.
2.58E-06 1134 1.46E-07 3.87E-07 1.39E-07 6.45 E-06 6.10E-07 0.
5.10E-09 1135 + D 6.10E-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 0.
1.74E-06 XE131M 0.
O.
O.
O.
O.
O.
O.
XE133M 0.
O.
O.
O.
O.
O.
O.
XE133 0.
O.
O.
O.
O.
O.
O.
XE135M 0.
O.
O.
O.
O.
O.
O.
XE135 O.
O.
O.
O.
O.
O.
O.
XE137 0.
O.
O.
O.
O.
O.
O.
XE138 + D 0.
O.
O.
O.
O.
O.
O.
CS134M + D 2.94E-08 6.09E-08 3.13E-08 0.
CS134 8.37E-05 1.97E-04 9.14E-05 O.
6.26E-05 2.39E-05 2.45E-06 3.39E-08 5.95E-09 4.05E-08 CS135 2.78E-05 2.55E-05 5.96E-06 0.
9.73E-06 3.52E-06 4.46E-07 CS136 8.59E-06 3.38E-05 2.27E-05 O.
1.84E-05 2.90E-06 2.72E-06 CS137 + 0 1.12E-04 1.49E-04 5.19E-05 O.
5.07E-05 1.97E-05 2.12E-06 CS138 7.76E-08 1.49E 07 7.45E-08 0.
1.10E-07 1.28E-08 6.76E 11 CS139 + D 4.87E-08 7.17E-08 2.63E 08 0.
5.79E-08 6.34E-09 3.33E-23 BA139 1.39E-07 9.78E-11 4.05 E-09 0.
9.22E-11 6.74E 11 1.24E-06 BA140 + D 2.84 E-05 3.48E-08 1.83E-06 0.
1.18E 08 2.34E-08 4.38E-05 BA141 + D 6.71 E-08 5.01 E-11 2.24E-09 0.
4.65E-11 3.43E 11 1.43E 13 i
BA142 + D 2.99E-08 2.99E-11 1.84E-09 0.
2.53E 11 1.99E-11 9.18E 20 LA140 3.48E-09 1.71 E-09 4.55E-10 0.
O.
O.
9.82E-05 LA141 4.55E 10 1.40E 10 2.31E 11 0.
O.
O.
2.48E-05 LA142 f.79E-10 7.95E-11 1.98E-11 0.
O.
O.
2.42E-06 CE141 1.33E-08 8.88E-09 1.02E-09 0.
4.18E-09 0.
2.54E-05 CE143 + D 2.35E-09 1.71 E-06 1.91 E-10 0.
7.67E-10 0,
5.14E-05 CE144 + D 6.96E-07 2.88E 07 3.74E-08 0.
1.72E-07 0.
1.75E-04 PR143 1.31 E-08 5.23E-09 6.52E-10 0.
3.04E-09 0.
4.31 E-05 l
PR144 4.30E-11 1.76E 11 2.18E 12 0,
1.01 E-11 0.
4.74E-14 ND147 + D 9.38E-09 1.02E-08 6.11 E-10 0.
5.99E-09 0.
3.68 E-05 PM147 1.05E-07 9.96E-09 4.06E-09 0.
1.90E-08 0.
9.47E-06 PM148M + D 4.14E-08 1.05E-08 8.21 E-09 0.
1.59E-08 0.
6.61 E-05 PM148 1.02E-08 1.66E-09 8.36E-10 0.
3.00E-09 0.
9.90E-05 PM149 2.17E-09 3.05E-10 1.25E-10 0,
5.81E 10 0.
4.49E-05 PM151 9.87E-10 1.63E-10 8.25E-11 0.
2.93E-10 0,
3.66E-05 SM151 8.73E 08 1.68E-OB 3.94E 09 O.
1.84E-08 0.
5.70E-06 SM153 1.22E-09 1.01 E-09 7.43E-11 0,
3.30E-10 0.
2.85E-05 EU152 2.45E 07 5.90E-08 5.20E-08 0.
2.74E-07 0.
2.17E-05 EU154 7.91 E-07 1.02E-07 7.19E 08 0.
4.56E-07 0.
5.39E-05 EU155 1.74E-07 1.68E-08 1.04E-08 0,
6.57E-08 0.
9.63E-05 EU156 1.92E-08 1.44E-08 2.35E-09 0.
9.69E-09 0.
7.36E-05 TB160 6.47E-08 0,
8.07E-09 0.
2.56E-08 0.
4.19E-05 HO166M 3.57E-07 1.10E-07 7.96E-08 0.
1.61 E-07 0.
O.
W181 1.42E-08 4.58E-09 4.79E-10 0.
O.
O.
3.90E-07 W185 5.79E-07 1.91 E-07 2.02E-08 0.
O.
O.
1.65E-05 W187 1.46E-07 1.19E-07 4.17E-08 O.
O.
O.
3.22E-05 86
PALISADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 2.1 4
TEEN INGESTION DOSE COMMITMENT FACTORS (MREM /50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROlO KIDNEY LUNG GI-LLI P8210 + D 1.81 E-02 5.44E-03 7.01 E-04 0.
1.72E-02 0.
5.74E-05 Bl210 + D 6.59E-07 4.51 E-06 5.66E-08 0.
5.48E-05 O.
5.15E-05 l
PO210 6.09E-04 1.07E-03 1.23E-04 0.
3.60E-03 0.
6.75E-05 RN222 + D 0.
O.
O.
O.
O.
O.
O.
RA223 + D 7.11 E-03 1.08E-05 1.42E-03 0.
3.10E-04 0.
3.43E-04 RA224 + D 2.31 E-03 5.52E-06 4.61 E-04 0.
1.58E-04 0.
3.71 E-04 RA225 + D 9.37E-03 1.10E-05 1.87E-03 0.
3.15E-04 0.
3.27E-04 RA226 + D 3.22E-01 8.13E-06 2.39E-01 0.
2.32E-04 0.
3.51 E-04 RA228 + D 1.37E-01 4.41 E-06 1.51 E-01 0.
1.26E-04 0.
5.98E-05 AC225
6.29E-06 8.59E-06 4.22E-07 0.
9.85 E-07 0.
4.36E-04 i
AC227 + D 2.05 E-03 3.03E-04 1.22E-04 0.
8.81 E-05 O.
8.68E-05 TH227 + D 1.96E-05 3.52E-07 5.65 E-07 0.
2.01 E-06 0.
5.75E-04 1
TH228 + D 6.80E-04 1.14E-05 2.30E-05 O.
6.41 E-05 O.
5.97E-04 TH229 8.39E-03 1.26E-04 4.11 E-04 0.
6.10E-04 0.
5.43E-04 TH230 2.16E-03 1.23E-04 6.00E-05 O.
5.99E-04 0.
6.38E-05 i
TH232 + D 2.42E-03 1.05E-04 1.63E-04 0.
5.11 E-04 0.
5.43E-05 TH234 1.14E-07 6.68E-09 3.31 E-09 0.
3.81 E-08 0.
1.21 E-04 PA231 + D 4.31 E-03 1.62E-04 1.68E-04 0.
9.10E-04 0.
7.60E-05 PA233 7.33E-09 1.41 E-09 1.26E-09 0.
5.32E-09 0.
1.61 E-05 U232 + D 5.89E-03 0.
4.21 E-04 0.
6.38E-04 0.
7.19E-05 U233 + D L24E-03 0.
7.543-05 O.
2.90E-04 0.
6.65E-05
{
U234 1.19E-03 0.
7.39E-05 O.
2.85E-04 0.
6.51 E-05 U235+D 1.14E-03 0.
6.94E-05 O.
2.67E-04 0,
8.28E-05 U236 1.14E-03 0.
7.09E-05 O.
2.73E-04 0.
6.11 E-05 U237 7.89E-08 0.
2.10E-08 0.
3.24E-07 0.
2.09E-05 U238 + D 1.09E-03 0.
6.49E-05 O.
2.50E-04 0.
5.83E-05 NP237 + D 1.44E-03 1.25 E-04 5.85E-05 O.
4.33E-04 O.
8.41 E-05 d
NP238 1.95E-08 5.22E-10 3.04E-10 0.
1.79E-09 0.
3.83E-05 s"
NP239 1.76E-09 1.66E-10 9.22E 11 0.
5.21E 10 0.
2.67E-05 PU238 7.21 E-04 1.02E-04 1.82E-05 O.
7.80E-05 O.
7.73E-05 PU239 8.27E-04 1.12E-04 2.01 E-05 O.
8.57E-05 O.
7.06E-05 PU240 8.26E-04 1.12E-04 2.01 E-05 O.
8.56E-05 O.
7.19E-05 PU241 + D 1.84E-05 9.42E-07 3.69E-07 0.
1.71 E-06 0.
1.48E-06 PU242 7.66E-04 1.08E-04 1.94E-05 O.
8.25E-05 O.
6.92E-05 PU244 8.95E-04 1.23E-04 2.22E-05 O.
9.45 E-05 O.
1.03E-04 AM241 8.62E-04 3.29E-04 5.75E-05 O.
4.31 E-04 0.
7.87E-05 AM242M 8.70E-04 3.19E-04 5.80E-05 O.
4.30E-04 0.
9.90E-05 AM243 8.60E-04 3.17E-04 5.62E-05 O.
4.22E-04 0.
9.23E-05 CM242 2.94E-05 2.97E-05 1.95E-06 0.
8.89E-06 0.
8.40E-05 CM243 6.91 E-04 2.86E-04 4.09E-05 O.
1.91 E-04 0.
8.28E-05 CM244 5.32E-04 2.49E-04 3.19E-05 O.
1.49E-04 0.
8.00E-05 CM245 1.07E-03 3.33E-04 6.10E-05 O.
2.85E-04 0.
7.46E-05 CM246 1.06E-03 3.32E-04 6.09E-05 O.
2.84E-04 0.
7.33E-05 CM247 + D 1.03E-03 3.27E-04 6.00E-05 O.
2.80E-04 0.
9.63E-05 CM248
' 8.60E-03 2.69E-03 4.95E-04 0.
2.31 E-03 0.
1.55 E-03 CR252 3.51 E-04 0.
8.37E-06 0.
O.
O.
3.05 E-04 87
PALISADES NUCLFAR PLANI OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MR ISOTOPE BONE LIVER H3 0.
TOTAL BODY THYROID CI INGESTED IN FIRST YR)
KIDNEY LUNG GI-LLI BE10 1.05E 07 1.05 E-07 1.05E-07 1.05E 07 1.05 E-07 1.05E-07 3.18E-06 4.91 E-07 7.94E-08 0.
C14 2.84E-06 5.68E-07 5.68E-O'I 5.6BE-07 5.68 E-07 5.68E-07 5.68E-07 3.71 E-07 0.
2.68E-05 N13 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 F18 6.24E 07 0.
6.92E-08 0.
O.
O.
NA22 1.74 E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E 05 1.74E-05 NA24 1.85E-08 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P32 1.93E-04 1.20E-05 7.46E-06 0.
O.
O.
2.17E-05 AR39 0.
O.
O.
O.
O.
O.
O.
AR41
0.
O.
O.
O.
O.
O.
O.
CA41 1.83E-05 O.
2.00E-05 O.
O.
O.
SC46 5.51 E-09 1.07E-08 3.11 E-09 0.
9.99E-09 0.
CR51 0.
O.
1.84E-07 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN54 0.
4.57E-06 8.72E-07 0.
1.36E 06 0,
5.21 E-05 MN56 0.
1.15 E-07 2.04E-08 0.
1.46E-07 0.
FESS 2.75 E-06 1.90E-06 4.43E-07 0.
O.
1.40E-05 3.67E-06 FES9 4.34E-06 1.02 E-05 3.91E-06 0.
O.
1.06E-06 1.09E-06 C057 0.
1.75E-07 2.91E-07 0.
O.
O.
2.85E-06 3.40E-05 C058 0.
7.45E-07 1.67E-06 0.
O.
O.
4.44E-06 CO60 0,
2.14E-06 4.72E-06 0.
O.
O.
4.02E-05 1.51 E-05 N159 9.76E-06 3.35E-06 1.63E-06 0.
O.
O.
6.90E-07 NI63 1.30E-04 9.01E 06 4.36E-06 0.
O.
O.
1.88E-06 N165 5.28E-07 6.86E-08 3.13E-OB 0.
O.
O.
1.74E-06 CU64 0.
8.33E-OS 3.91 E-08 0.
2.10E-07 0.
7.10E-06 ZN65 4.84E-06 1.54E-05 6.96E-06 0.
1.03E-05 O.
9.70E-06 ZN69M + D 1.70E-07 4.08E-07 3.73E-08 0.
2.47E-07 0.
2.49E-05 ZN69 1.03E-08 1.97E-08 1.37E-09 0.
1.28E-08 0.
2.96E-09 SE79 0.
2.63E-06 4.39E-07 0.
4.55E-06 0.
5.38E-07 BRB2 0.
O.
2.26E-06 0.
O.
O.
2.59E-06 BR83 + D 0.
O.
4.02E 08 0.
O.
O.
5.79E-08 BR84 0.
O.
5.21 E-08 0.
O.
O.
BR85 O.
O.
2.14E 09 0.
O.
O.
O.
4.09E-13 KR83M 0.
O.
O.
O.
O.
O.
O.
KR85M 0.
O.
O.
O.
O.
O.
O.
KR85 O.
O.
O.
O.
O.
O.
O.
KR87 0.
O.
O.
O.
O.
O.
O.
KR88 + D 0.
O.
O.
O.
O.
O.
O.
KR89 0.
O.
O.
O.
O.
O.
O.
RB86 0.
2.11 E-05 9.83E-06 0.
O.
O.
RB87 0.
1.23E-05 4.28E-06 0.
O.
O.
5.76E-07 4.16E-06 RB88 0.
6.05E-08 3.21E 08 0.
O.
O.
8.36E-19 RB89 + D 0.
4.01 E-08 2.82E-08 0.
O.
O.
2.33E-21 SR89 + D 3.08E-04 0.
8.84E-06 0.
O.
O.
4.94E-05 SR90 + D 7.5BE-03 0,
1.86E-03 0.
O.
O.
2.19E-04 SR91 + D 5.67E-06 0.
2.29E-07 0.
O.
O.
2.70E-05 SR92 + D 2.15E-06 0.
4 9.30E-08 0.
O.
O.
4.26E-05 88
PALISADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL e
Revision 10
/
TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM /50Y PER PCIINGESTED IN FIRST YR)
ISOTOPE 80NE LIVER TOTAL 80DY THYR 010 KIDNEY LUNG GI-LLI Y90 9.62E-09 0.
2.58E-10 0.
O.
O.
1.02E-04 Y91 M + D 9.09E 11 0.
3.52E-12 0.
O.
O.
2.67E-10 Y91 1.41 E-07 0.
3.77E-09 0.
O.
O.
7.76E-05 Y92 8.45E-10 0.
2.47E 11 0.
O.
O.
1.48E-05 Y93 2.68E 09 0.
7.40E-11 0.
O.
O.
8.50E-05 i
ZR93 + D 4.18E-08 2.34E-09 1.09E-09 0.
8.87E-09 0.
2.43E-06 ZR95 + D 3.04E-08 9.75 E-09 6.60E-09 0.
1.53E-08 0.
3.09E-05 ZR97 + D 1.68E-09 3.39E-10 1.55E-10 0.
5.12E-10 0.
1.05 E-04 N893M 2.55E-08 8.32 E-09 2.05 E-09 0.
9.57E-09 0.
3.84E-06 N895 6.22E-09 3.46E-09 1.86E-09 0.
3.42E-09 0.
2.10E-05 NB97 5.22E-11 1.32E-11 4.82E-12 0.
1.54E-11 0.
4.87E-08 M093 0.
7.51 E-06 2.03E-07 0.
2.13E-06 0.
1.22E-06 M099 + D 0.
4.31 E-06 8.20E-07 0.
9.76E-06 0.
9.99E-06 TC99M 2.47E-10 6.98E-10 8.89E-09 0,
1.06E-08 3.42E 10 4.13E-07
.TC99 1.25 E-07 1.86E-07 5.02E-08 0.
2.34E-06 1.58E-08 6.08E-06 TC101 2.54E-10 3.66E-10 3.59E-09 0.
6.59E-09 1.87E 10 1.10E-21 RU103 + D 1.85E-07 0.
7.97E-08 0.
7.06E-07 0.
2.16E-05 RU105 + D 1.54E-08 0.
6.08E-09 0.
1.99E-07 0.
9.42E-06 Rll106+D 2.75E-06 0.
3.48E-07 0.
5.31 E-06 0.
1.78E-04
'H105 1.21 E-07 8.85E-08 5.83E-08 0.
3.76E-07 0.
1.41 E-05 FD107 0,
1.47E-07 9.40E-09 0.
1.32E-06 0.
9.11 E-07 PD109 0.
1.77E-07 3.99E-08 0.
1.01 E-06 0.
1.96E-05 AG110M + D 1.60E-07 1.48E-07 8.79E-08 0.
2.91 E-07 0.
6.04E-05 AG111 5.81 E-08 2.43E-08 1.21 E-08 0.
7.84E-08 0.
4.46E-05 CD113M 0.
3.18E-06 1.02E-07 0.
3.50E-06 0.
2.56E-05 CD115M O.
1.84E-06 5.87E-08 0.
1.46E-06 0.
7.74E-05 SN123 3.11 E-05 5.15E-07 7.59E-07 4.38E-07 0.
O.
6.33E-05 SN125 + D 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0.
O.
1.04E-04 SN126 + D 8.45 E-05 1.67 E-06 2.40E-06 4.92E-07 0.
O.
2.43E-05 SB124 2.80E-06 5.29E-08 1.11 E-06 6.79E-09 0.
2.18E-06 7.95E-05 SB125 + D 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.
1.38E-06 1.97E-05 S8126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0.
7.05E-07 9.40E-05 S8127 2.58E-07 5.65E-09 9.90E-08 3.10E-09 0.
1.53E-07 5.90E-05 TE125M 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 O.
1.07F-05 YE125M + D 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 O.
2.27EOS TE127 1.10E-07 3.95 E-08 2.38E-08 8.15E-08 4.48E-07 0.
6.68E-06 TE129M + D 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 O.
5.79E-05 TE129 3.14E-08 1.18 E-08 7.65 E-09 2.41 E-08 1.32E-07 0.
2.37E-08 TE131M + D 1.73E-06 8.46E-07 7.05E-07 1.34E 06 8.57E-06 0.
8.40E-05 TE131 + D 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.
2.79E-09 TE132 + D 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 O.
7.71 E-05 TE133M + D 4.62E-08 2.70E-08 2.60E-08 3.91 E-08 2.67E-07 0.
6.64E-08 TE134 + D 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07 0.
3.59E-11 1129 3.27E-06 2.81 E-06 9.21 E-06 7.23E-03 6.04E-06 0.
4.44E-07 1130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.
1.92E-06 1131 + D 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 O.
1.57E-06 89
PALISADES NUCLFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 IABLE 2.1_
ADULT INGESTION DOSE COMMITMENT FACTORS (M ISOTOPE BONE LIVER TOTAL BODY THYROID NGESTED IN FIRST YR) 1132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E 07 0.
KlDNEY LUNG GI-LLI 1133 + D 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 0.
2.22E-06 1134 1.02E-07 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.
2.51 E-10 1135 + D 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0.
1.31E-06 XE131M 0.
O.
O.
O.
O.
O.
O.
XE133M 0.
O.
O.
O.
O.
O.
O.
XE133 0.
O.
O.
O.
O.
O.
O.
XE135M O.
O.
O.
O.
O.
O.
O.
XE135 O.
O.
O.
O.
O.
O.
O.
XE137 0.
O.
O.
O.
O.
O.
O.
XE138 + D 0.
O.
O.
O.
O.
O.
O.
CS134M + D 2.13E-08 4.48E-08 2.29E-08 0.
CS134 6.22E-05 1.48E-04 1.21 E-04 0.
2.43E-08 3.83E-09 1.58E-08 CS135 1.95E-05 1.80E-05 7.99E-06 0.
4.79E-05 1.59E-05 2.59E-06 CS136 6.51 E-06 2.57E-05 1.85E-05 O.
6.81 E-06 2.04E-06 4.21 E-07 CS137 + D 7.97E-05 1.09E-04 7.14E-05 O.
3.70E-05 1.23E-05 2.11 E-06 1.43E-05 1.96E-06 2.92E-06 CS138 6.52E-08 1.09E-07 5.40E-08 0.
CS139 + D 3.41 E-08 5.08E-08 1.85E 08 0.
8.01 E-08 7.91 E-09 4.65E 13 BA139 9.70E-08 6.91 E-11 2.84E-09 0,
6.46E 11 3.92E-11 1.72E-07 4.07E-08 3.70E-09 1.10E-30 BA140 + D 2.03E-05 2.55E-08 1.33E-06 0.
8.67E-09 1.46E-08 4.18E-05 8A141 + D 4.71 E-08 3.56E 11 1.59E-09 0.
3.31E 11 2.02E-11 2.22E-17 BA142 + D 2.13E 08 2.19E-11 1.34E-09 0,
LA140 2.50E-09 1.26E 09 3.33E 10 0.
O.
O.
9.25E-05 1.85E-11 1.24E-11 3.00E 26 LA141 3.19E-10 9.90E-11 1.62E-11 0.
O.
O.
LA142 1.28E 10 5.82E-11 1.45E-11 0.
O.
O.
1.18E-05 CE141 9.36E-09 6.33E-09 7.18E 10 0.
2.94E-09 0.
2.42E-05 4.25E-07 CE143 + D 1.65E-09 1.225-06 1.35E-10 0.
5.37E 10 0.
4.56E-05 CE144 + D 4.88E-07 2.04E-07 2.62E-08 0.
1.21 E-07 0.
1.65 E-04 PR143 9.20E-09 3.69E-09 4.56E-10 0.
2.13E-09 0.
PR144 3.01E 11 1.25E-11 1.53E-12 0.
7.05 E-12 0.
4.33E 18 4.03E-05 ND147 + D 6.29E-09 7.27E-09 4.35E-10 0.
4.25E-09 0.
3.49E-05 PM147 7.54E-OB 7.09E-09 2.87E-09 0,
1.34E-08 0.
8.93E-06 PM 148M + D 3.07E-08 7.95E-09 6.08E-09 0.
1.20E-08 0,
6.74E-05 PM148 7.17E-09 1.19E-09 5.99E-10 0.
2.25E 09 0.
9.35E-05 PM149 1.52E-09 2.15E-10 8.78E-11 0.
4.06E-10 0.
4.03E-05 PM151 6.97E-10 1.17E-10 5.91 E-11 0.
2.09E-10 0.
SM151 6.90E-08 1.19E-08 2.85E-09 0.
1.33E-08 0.
5.25E-06 3.22E-05 SM153 8.57E-10 7.15E 10 5.22E-11 0.
2.31 E-10 0.
2.55E-05 EU152 1.95E-07 4.44E-08 3.90E-08 0.
2.75E-07 0.
2.56E-05 EU154 6.15E-07 7.56E-08 5.38E-08 0.
3.62E-07 0.
5.48E-05 EU155 8.60E-OB 1.22E-08 7.87E-09 0.
5.63E 08 0.
9.60E-06 EU156 1.37E-08 1.06E-08 1.71 E-09 0.
7.08E-09 0.
7.26E-05 TB160 4.70E-08 0,
5.86E-09 0.
1.94E-08 0,
4.33E-05 HOl66M 2.70E-07 8.43E-08 6.40E-OB 0,
1.26E-07 0.
O.
W181 9.91 E-09 3.23E-09 3.46E-10 0.
O.
O.
3.68E-07 W185 4.05E-07 1.35E.07 1.42E-08 0.
O.
O.
1.56E-05 W187 1.03E-07 8.61 E-08 3.01 E-08 0.
O.
O.
2.82E-05 90
pat utADES NUClFAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM /50Y PER PCIINGESTED IN FIRST YR) i ISOTOPE BONE LIVER TOTAL BODY THYROID KlDNEY LUF3 GI-LLI i
PB210 + D 1.53E-02 4.37E-03 5.44E-04 0.
1.23E-02 0.
5.42E-05 B1210 + D 4.61 E-07 3.18E-06 3.96E-08 0.
3.83E-05 O.
4.75 E-05 PO210 3.56E-04 7.56E-04 8.59E-05 O.
2.52E-03 0.
6.36E-05 RN222 + D 0.
O.
O.
O.
O.
O.
O.
RA223 + 0 4.97E-03 7.65E-06 9.94E-04 0.
2.17E-04 0.
3.21 E-04 RA224 + D 1.61 E-03 3.90E-06 3.13E-04 0.
1.10E-04 0.
3.40E-04 l
RA225 + D 6.56E-03 7.78E-06 1.31 E-03 0.
2.21 E-04 0.
3.06E-04 RA226 + D 3.02E-01 5.74E-06 2.20E-01 0.
1.63E-04 0.
3.32E-04 RA228 + D 1.12E-01 3.12E-06 1.21 E-01 0.
8.83E-05 O.
5.64E-05
?
AC225 4.40E-06 6.06E-06 2.96E-07 0.
6.90E-07 0.
4.07E-04 AC227 + D 1.87E-03 2.48E-04 1.11 E-04 0.
8.00E-05 O.
8.19E-05 TH227 + D 1.37E-05 2.48E-07 3.95E-07 0.
1.41 E-06 0.
5.40E-04 TH228 + D 4.96E-04 8.40E-06 1.68E-05 O.
4.67E-05 O.
5.63E-04 TH229 7.98E-03 1.19E-04 3.91 E-04 0.
5.75E-04 0.
5.12E-04 TH230 2.06E-03 1.17E-04 5.70E-05 O.
5.65E-04 0.
6.02E-05 TH232 + D 2.30E-03 1.00E-04 1.50E-04 0.
4.82E-04 0.
5.12E-05 TH234 8.01 E-08 4.71 E-09 2.31 E-09 0.
2,67E-08 0.
1.13E-04 PA231 + D 4.10E-03 1.54E-04 1.59E-04 0.
8.64E-04 0.
7.17E-05 PA233 5.26E-09 1.06E-09 9.12E-10 0.
3.99E-09 0.
1.64E-05 i
U232 + D 4.13E-03 0.
2.95 E-04 0.
4.47E-04 0.
6.78E-05 U233 + D 8.71 E-04 0.
5.28E-05 O.
2.03E-04 0.
6.27E-05 U234 8.36E-04 0.
5.17E-05 O.
1.99E-04 0.
6.14E 05 U235 + D 8.01 E-04 0.
4.868E 05 O.
1.87E-04 0.
7.81 E-05 U236 8.01 E-04 0.
4.96E-05 O.
1.91 E-04 0.
5.76E-05 i
U237 5.52E-8 0.
1.47E 08 0.
2.27E-07 0.
1.94E-05 U238 + D 7.67E-04 0.
4.54E-05 O.
1.75 E-04 0.
5.50E-05 NP237 + D 1.37E-03 1.19E-04 5.54E-05 O.
4.12E-04 0.
7.94E 05 MP238 1.37E-08 3.69E 10 2.13E 10 0.
1.2E E-09 0.
3.43E-05 NP239 1.19E-09 1.17E-10 6.45E-11 0.
3.65E-10 0.
2.40E 05 PU238 6.80E-04 9.58E-05 1./1 t:-05 O.
7.32E-05 O.
7.30E-05 PU233 7.87E-04 1.06E-04 141 E-05 O.
8.11 E-05 0.
6.66E-05 PU240 7.85 E-04 1.06E-04 1.91 E-05 O.
8.10E-05 O.
6.78E-05 1
PU241 + D 1.65 E-05 8.44E-07 3.32E-07 0.
1.53E-06 0.
1.40E-06 PU242 7.29E-04 1.02E-04 1.84E-05 O.
7.81 E-05 O.
6.53E-05 PU244 8.52E-04 1.17E-04 2.11 E-05 O.
8.95E-05 O.
9.73 E-05 AM241 8.19E-04 2.88E-04 5.41 E-05 O.
4.07E-04 0.
7.42E-05 i
AM242M 8.24E-04 2.78E-04 5.43E-05 O.
4.05 E-04 0.
9.34E-05 AM243 8.18E-04 2.78E-04 5.30E-05 O.
3.99E-04 0.
8.70E-05 i
CM242 2.06E-05 2.10E-05 1.37E-06 0.
6.22E-06 0.
7.92E-05 CM243 6.39E 04 2.41 E-04 3.75E-05 O.
1.75E-04 0.
7.81 E-05 CM244 4.83E-04 2.07E-04 2.87E-05 O.
1.34E-04 0.
7.55E-05 j
CM245 1.02E-03 2.87E-04 5.76E-05 O.
2.69E-04
'./.
7.04E-05 CM246 1.01 E-03 2.87E-04 5.75E-05 O.
2.68E-04 0.
6.91 E-05 CM247 + D 9.84E-04 2.83E-04 5.67E-05 '
O.
2.64E-04 0.
9.09E-05 CM248 8.18E-03 2.33E-03 4.67E-04 0.
2.18E-03 0,
1.47E-03 i
l CF252 2.64 E-04 0.
6.29E-06 0.
O.
O.
2.8BE-04 91
PALISADES NUCt FAR PLANT OFFSITE DOSE CALCULATION MANUAL t
Revision 10 TABLE 2.2
\\
PALISADES Liquid Effluent Desian Oblective Annual Quantity _
i Dose Conversion Design Objective thg[ gig Half-Ufe Individual /Oraan Annual Quantity Factors (mrem /Cil (Curies)
H-3 12.3 yr 1.75E-06 Na-24 15 h Adult /TB Sc-46 83.9 d Teen /TB 1.71 E + 06 5.44E-03 2.02E-02 551.5 Cr-51 27.8 d Teen /TB 1.56E-03 148.5 Mn-54 303 d Adult /GI (LLI) 6,410.0 3.50E-02 Teen /TB 85.7 F455 2.6 yr 4.48E-03 Child / Bone Mn-56 2.576 h 1.86E-03 2,232.0 Co-57 270 d Teen /TB 4.39E-03 1,612.0 Co-58 71.3 d Teen /TB i
1.03E-02 683.4
^
Fs-59 45.6 d Teen /TB 291.3 4.0BE-02 Adult /GI (LLI) 245.1 Co-60 5.26 yr 4.71 E-01 Cu-64 12.8 h Teen /TB 6.37 1.32E-03 Teen /GI (LLI)
Ni 65 2.56 h 5.82E-04 7,575.0 Zn-65 245 d Teen /TB 5,154.0 1.83E-01 Teen /TB Br-84 31.8 mo 2.02E-03 Teen /TB 16.4 1,485.2 j
Rb-86 1.02 mo 3.06E-01 Child /TB Rb-88 17.8 mo 6.92E-04 Teen /TB 9.80 Sr-89 52.7 d 1.56E-01 Child / Bone 4,335.3 i
Sr-90 27.7 yr 2.71 E-00 64.1 St-91 9.67 h Adult / Bone 3.69 1.16E-03 Teen /TB 2,586.0 St-92 2.71 h 1.51 E-03 Teen /TB
+
Y-92 3.53 h 2.69E-04 1,986.8 Nb-95 35 d Teen /TB 7.24E + 00 11,150.0 Zr 95 65.5 d Adult /GI (LLI) 1.38 6.17E-03 Teen /TB Nb-97 72 mo 6.95E-04 Teen /TB 486.2 4,316.6 Zr 97 17 h 9.28E-04 Mo-99 66.7 h Teen /TB 1.11 E-03 3,232.8 Tc-99m 6.05 h Teen / Kidney 9,009.0 1.42E-04 Ru 103 39.5 d Teen /TB 2.74E-03 21,126.8 Ag-110m 255 d Teen /TB 1,094.9 7.75 E-02 Teen /TB 38.7 92
PALISADES NUCI FAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 TABLE 2.2 (continued)
PALISADES Liquid Effluent Desian Obiective Annual Nantity Design Objective Dose Conversion Annual Quantity.
Nuclide Half-Life Factors (mram/Ci)
Individual /Oraan (Curien) a 1
Cd-113m 13.6 yr 6.02E-02 Adult /GI (LLil 166.1 l
Sb-124 60 d 1.51 E-02 Teen /TB 198.7 Sb-125 2.7 yr 5.11 E-02 Teen /TB 58.7 Te-127 9.4 h 7.38E-03 Teen /GI (LLI) 1,355.0 l
Te127m 109 d 1.39E-01 Teen / Kidney 71.9 i
Te129m 34.1 d 2.66E-01 Adult /GI (LLI) 37.6 l-130 12.3 h 1.17E-02 Child / Thyroid 854.7 i
1-131 8.05 d 3.27E-01 Child / Thyroid 30.6 i
Te-131m 30 h 2.27E-01 Adult /GI (LLI) 44.0 1-132 2.26 h 3.18E-05 Teen /TB 94,339.0 Te-132 77.7 h 2.93E-01 Adult /GI (LLI) 34.1 l
l133 20.3 h 3.94E-02 Child / Thyroid 253.8 I
Cs-134 2 yr 2.86E + 00 Adult /TB 1.04 i
1134 52 mo 2.43E-03 Teen /TB 1,234.0 i
1-135 6.68 h 1.64E-03 Child / Thyroid 6,097.0 Cs 136 13.7 d 4.13E-01 Adult /TB 7.26 Cs 137 30 yr 1.71 E + 00 Adult /TB 1.75 Cs-138 32.2 mo 2.31 E-03 Teen /TB 1,298.0 Ba-139 82.9 mo 4.66E-05 Teen /TB 64,377.0 Ba-140 12.8 d 7.96E-04 Teen /TB 3,768.0 La-140 40.22 h 1.85 E-02 Adult /Gl (LLl) 540.5 Ce 141 32.5 d 3.70E-04 Teen /TB 8,108.0 Ce-144 284 d 1.56E-03 Teen /TB 1,923.0 Eu-152 12.7 yr 3.24E-01 Teen /TB 9.25 W 187 23.9 h 1.98E-01 Adult /GI (LLI) 50.5 5
Np 239 2.346 d 2.26E-03 Adult /Gl (LLl) 4,424.0 93
PALISADES NUCI FAR PLANT i
OFFSITE DOSE CALCULATION MANUAL Revision 10 111.
URANIUM FUEL CYCLE DOSE A.
SPECIFICATION i
in accordance with Appendix A, Section Ill.l.1, if either liquid or gaseous quarterly releases exceed the quantity which would cause offsite doses more than twice the limit of Appendix A, Sections Ill.C.1, Ill.D.1, or lit.H.1, then the cumulative dose contributions from combined release plus direct radiation sources (from the reactor unit and radwaste storage tanks) shall be calculated. The dose is to be determined for the member '
of the public protected to be the most highly exposed to these combined sources.
B.
ASSUMPTIONS 1.
The full time resident determined to be maximally exposed individual (excluding infant) is assumed also to be a fisherman.
This individual is assumed to drink water and ingest local fish at the rates specified in Sections ll.C.2.1 and ll.C.2.2.
2.
Amount of shore line fishinD (at accessible shoreline adjacent to site security fence) is conservatively assumed as 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per quarter (average of approximately 1/2 hour per day each day of the quarter) for the second and third quarters of the year,36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months for the fourth quarter and 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months for the first quarter.
C.
DOSE CALCULATION Maximum doses to the total body and internal organs of an individual shall be determined by use of LADTAP and GASPAR computer codes, and doses to like organs and total body summed. Added to this sum will be a mean dose rate, calculated or measured for the shoreline due to Plant present curing the quarter in question, times the assumed fishing time.
D o = Do + Do + (Rr)(T) 4 (2.15) 94
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 10 where:
i De 40 CFR 190 dose (mrem).
=
Da Limiting dose to an individual from gaseous source term
=
(mrem).
1 4
D Limiting dose to an individual from liquid source term (mrem).
=
t i
Rr Mean dose rate calculated to be applicable to Lake Michigan
=
shoreline adjacent to Plant site (mrem /hr).
i T
Assumed shoreline fishing time for the quarter in questions
=
(hours).
i i
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e a
b 4
4 4
o 95 i
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