Text

Rev 11 to Offsite Dose Calculation Manual.
	ML18065B201
Person / Time
Site:	Palisades
Issue date:	12/24/1996
From:	Neal T; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML18065B198	List: ML18065B197; ML18065B199; ML18065B201; ML18065B202;
References
	PROC-961224, NUDOCS 9804070016
	Download: ML18065B201 (99)
	v • d • e

ATTACHMENT 6 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT OFFSITE DOSE CALCULATION MANUAL

164 Pages

Rev1s1on d Page 1 of 1 PS&L Log No q(p - 2 ~23

---------~----P~--~~...,._~...--.

Item lr-?ntification: No 0 ~ (_ M Rev_.......____ Title Qt=t=" ~I I~ e:, Si: SE

~~ REV 1 . Does the item involve a change to procedures as described in the FSAR? Yes No FSAR Sections affected }-..j \JN I:

FSA R Sections reviewed---'-'--~-----------------

_ _ _d..=_~......;;!...:.l_______________

2. Does the item involve a change to the facility as described or implied in the FSAR?

FSAR Sections affected _ _ _ _..;..d'-l_~_l-J_2_____________

FSAR Sections reviewed _____'d-...:;;...,,--'~...:.1--++-----f't.,.._-..,..._ _ ___,_ __

DBD Sections reviewed _...:N_\).;..)..)...::...'ii<-:;;__:...(~L..:.*~~=' $"'"9~l*~'1J~._C...=.;'.U~"~"':.::.";i..'~n-=GJ~~,Z!(.:;,;~_

1..:. ...:.-+* , 2 s-J...)

3. Does the item involve a test or experiment not described in the FSAR?

FSAR Sections affected * ~ l.l ~

...l-...;...------------------ c FSAR Sections reviewed -----~->;..__;-'.;....+'--~-i.....,...,... __________

DBD Sections reviewed ~ 1:..., i::;; - f..lS> i : ~ ~ .. 0

4. Should the Technical Specifications or any of their B~ses be changed in conjunction with this item?

TS Sections affected ----...--...:N_\);.._~_\.::..;;_ _ _ _ _ _ _ _ _ _ _ _ _ _ __

TS Sections reviewed ------~_ _c..._.- - - - - - - - - - - - - - - -

Justify "NO" answers below if logic is not obvious:

If any Safety Review question listed above is answered "YES," perform a written USO Evaluation according to Section 5.3.

If all Safety Review questions listed above are answered "NO," written USO Evaluation is not required.

However, this attachment shall accompany other review materials for the item to document that a Safety Evaluation was not required *

07 ~

Reviewed By 1Q-10.-cib Date

Procedure No ODCM Revision 11 Issued Date 1/2/97 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: OFFSITE DOSE CALCULATION MANUAL

/J.*12-9" Procedure Sponsor Date

- TPNeal t 12/10/96 Technical Reviewer Date User Reviewer Date I

-~~

Plant Manager

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

11. LIQUID EFFLUENTS Table of Contents

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 A. CONCENTRATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64

1. Requjrems;nts . . . . . . . . . . . . . . . . . . . . . . . . . . 64

2. Prerelease Analysis . . . . . . . . . . . . . . . . . . . . . . 64

3. Effluent Concentration fECl - Sum of the Ratios .. 65

8. INSTRUMENT SETPOINTS . . . . . . . . . . . . . . . . . . . . . . . . 66

1. Setpojnt Determination . . . . . . . . . . . . . . . . . . . 66

2. Composite Samplers . . . . . . . . . . . . . . . . . . . . . 66

3. Post-Release Analysis . . . . . . . . . . . . . . . . . . . . 67 C. DOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 67

1. RETS Requirement . . . . . . . . . . . . . . . . . . . . . . . 6 J.

2. Release Analysis . . . . . . . . . . . . . . . . . . . . . . . . 6 7 D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT ...... 72 E. RELEASE RATE FOR OFFSITE EC (50 mRem/yr) ......... 72 F. FIGURES AND TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . 73 111. URANIUM FUEL CYCLE DOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 94 A. SPECIFICATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 94

8. ASSUMPTIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 94 C. DOSE CALCULATION . . . . . . . . . . . . . . . . . . . . . . . . . . . 95 Appendix A, "Relocated Technical Specification" Appendix 8, "Request to Retain Soil in Accordance With 10 CFR 20.302"

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

i---------------

1. GASEOUS EFFLUENTS A. ALARM/TRIP SETPOINT METHOD Appendix A, Section 111.B.1 requires that the dose rate due to radioactive 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 111.A.1 requires gaseous effluent monitors to have alarm/trip setpoints to ensure that offsite concentrations, when averaged 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 r

determine these setpoints .

The methodology for determining alarm/trip setpoints is divided into two major parts. The first consists of calculating an allowable concentration for the nuclide 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. Allowable Concentration The total EC-fraction (Rk) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 10 CFR 20:

R

<k>

(~J(F)L Q i s_

EC I

~ 10.0

( 1 . 1)

1

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

where:

Actual or measured concentration, at ambient temperature and pressure of nuclide i (µCi/cc)

The EC of nuclide i from 10 CFR 20, Appendix B, Table 2 =

50 mrem/yr - total body The total EC-fraction for release point k X/Q = Most conservative sector site boundary dispersion

( 1. 79E-06 sec/m 3 )

F = Release flow rate (83,000 cfm = 39.2 m 3 /sec) for stack monitor considerations; variable for other monitors NOTE: If a batch release is made while a continuous release or another batch release is in progress, the sum of all values of Rk must be less than 10.0. r

- 2. Monitor Response 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 as follows:

a. Normal Release (aged fission gasses)

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

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

s =bx c ( 1 .2)

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

b. Accident Releases Monitors are preset to alarm at or before precalculated offsite dose rates would be achieved under hypothetical accident conditions. These setpoints are established in accordance with Emergency Plan requirements for defining Emergency Action Levels and associated actions.

Emergency Implementing Procedures contain monitor-specific curves or calibration constants for conversion between cpm and µCi/cc (or R/hr and µCi/cc), depending on monitor type, for fission product mixtures as a function of mixture decay time.

When these monitors are utilized for other than accident conditions, either an appropriately decayed "accident" conversion curve may be used, or a decayed fission gas calibration factor may be applied. In these cases, setpoints are established as in 1 .A above.

r*

Setpoints of accident monitors (if set to monitor normal

releases) are reset to the accident alarm settings at the end of normal release. Setpoints of other release monitors are maintained at the level used at the latest release (well below the level which would allow 10 times EC to be exceeded at the site boundary), or are reset to approximately three times background in order to detect leakage or inadvertent releases of low'level gases.

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 10 CFR 50 Appendix I limits of mrem per quarter and millirem per year. All dose pathways of major importance in the Palisades environs are considered.

a. Equations and assumptions for calculating doses from noble gases are as follows:

1) Assumptions

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

3

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11 I

b) Exposure pathway is submersion within a cloud of noble gases.

c) Noble gas radionuclide mix is based oh the historically observed source term given in Table 1. 1, plus additional nuclides.

d) Basic radionuclide data are given in Table 1 .2.

e) All releases are treated as ground-level.

f) Meteorological data expressed as joint-frequency distribution of wind speed, wind direction, and atmospheric stability for the 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 1Om and r

h) temperature measurements at 1Om and 60m .

Dose is to be evaluated at the offsite exposure points where maximum concentrations are expected to exist (overland sector site boundaries), and nearest residents.

i) Potential maximum population (resident) exposure points are identified in Table 1 .4.

j) A semi-infinite cloud model is used.

k) For person exposures, credit is taken for shielding by residence (factor of 0. 7).

I) Radioactive decay is considered for the plume.

m) Building wake effects on effluent dispersion are considered.

n) A sector-average dispersion equation is used.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

o) The wind speed classes that are used are as follows:

Wind Speed Class Number Range (m/sl Midpoint (m/sl 1 0.0-0.4 0.2 2 0.4-1.5 0.95 3 1.5-3.0 2.25 4 3.0-5.0 4.0 5 5.0-7.5 6.25 6 7.5-10.0 8.75 7 > 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 ,

8=2, ... , G=7.

q) Terrain effects are not considered.

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

For determining the air concentration of any radionuclide:

x, = t f (

i=1 k=1 2

n

] 1 12 fjk a 1 p [

I:zkUJ (2mc/n} exp-(

J\i :i )]

(1.3) where:

= Air concentration of radionuclide i, µCi/m 3 *

= Joint relative frequency of occurrence of winds in wind speed class j, stability

class k, blowing toward this exposure 5

point, expressed as a fraction.

PALISADES NUCLEAR PLANT OFF SITE DOSE CALCULATION MANUAL Revision 11

O; p

=

Average release rate of radionuclide i, µCi/s.

Fraction of radion.uclide remaining in plume.

I.zk = Vertical dispersion coefficient for stability class k (m).

uj = Midpoint value of wind speed class interval j, m/s.

x = Downwind distance, m.

n = Number of sectors, 16.

~ = Radioactive decay coefficient of radionuclide i, s- 1

r 2nx/n = Sector width at point of interest, m.

For determining the total body dose rate:

DTB = I: x1 DEBI

( 1 .4) where:

Dre = Total body dose rate, mrem/y.

Air concentration of radionuclide I,

µCi/m 3 .

Total body dose factor due to gamma*

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

For determining the skir:1 dose rate:

D. =~ X 1 (DFS 1 + 1.11 DFY 1)

I

( 1 .5)

6

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

where:

Ds = Skin dose rate, mrem/y.

xi = Air concentration of radionuclide i, µCi/m 3 DFSi = Skin dose factor due to beta radiation, mrem/y per µCi/m 3 (Table 1.5).

1 .11 = The average ratio of tissue to air energy absorption coefficients, mrem/mrad.

Gamma-to-air dose factor for radionuclide i, mrad/y per µCi/m 3 (Table 1.5).

For determining dose rate to a point in air:

oa = Lj x 1 ~roFY 1 or DFB 1) r*

- where:

Air dose rate, mrad/yr.

(1.6)

Air dose factor for beta radiation (Table 1.5).

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

1) Assumptions 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 particulates are milk ingestion, ground contamination, green leafy vegetables from

home gardens, and inhalation .

7

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

c) The radioiodine and particulate mix is based on 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 1 Om a*nd temperature measurements at 1 Om and 60m.

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

i) j)

Real cow, goat and garden locations are considered.

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.

I) Building wake effects on effluent dispersion are considered.

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 NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

p) Milk cows and goats obtain 100% of their food from pasture grass May through October of each year. Use default values of 0.58 for cows and 0.67 for goats for fraction of year on pasture.

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

2) Equations 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, Xi is the same as in the Noble Gas Section (Equation 1.3) .

For determining the organ dose rate:

DI =1 x 10 6 Lj (1. 7) where:

Organ dose rate due to inhalation, mrem/y.

Air concentration of radionuclide i,

µCi/m 3 .

Inhalation dose factor, mrem/pCi (Table 1 . 7).

BR = Breathing rate 1400 m 3 /y infant; 3700 m 3 /y child; or 8000 m 3 /y teen and adult.

1x106 9

= pCi/µCi conversion factor .

PALISADES NUCLEAR PLANT

. OFFSITE DOSE CALCULATION MANUAL Revision 11

~------------------

b) Ground Contamination For determining the ground concentration of any nuclide; 7

Gi = 3.15 x 10 7

L k=1 (1 .8) where:

= Ground concentration of radionuclide i, µCi/m 2

k = Stability class.

= Joint relative frequency of occurrence of winds in stability cl~ss k blowing toward this exposure point, expressed as a r fraction.

= Average release rate of radionuclide i, µCi/s.

DR = Relative deposition rate, m* 1 (Fig 1 .2).

x = Downwind distance, m.

n = Number of sectors, 1 6.

2nx/n = Sector width at point of interest, m.

"i = Radioactive decay coefficient of radionuclide i, y* 1 *

= Time for buildup of radionuclides on the ground, 1 5 y .

3.15x10 7 =

10 s/y conversion factor.

PALISADES NUCLEAR PLANT OFF SITE DOSE CALCULATION MANUAL Revision 11 er------------------------ Figure 1. 2 Corrected January 1977 io-3 I

I ;

I I I I I I !

I I

! Ti .

I ! :: I

~ .. 1 I ii

-=

LI.I

~

10-'

!Ill I

I I

I LI.I I

2

=

LI.I

"""" "'... I I

w

~

"' ~

~

l z= 1o-S --. 1111 II 0

- ..... r c;

2 ""'" "'-...

"'Q I

"'? !

~

w

"' ... .. I I

= ~, I 1~ ....

i I

i ! 11 !

I' iI '

I I Ij ii I 11 I

I I

0.1 1~ 10~ 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Figure 7. R~ Deposition for Ground Level All._ (All Atmospheric Stability Cllael) n - -- ,..

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

For determining the total body or organ dose rate from ground co'ntamination:

DG = (8,760)(1 x 10 6 )(0.7) L Gi DFGi (1.9) where:

= Dose rate due to ground contamination, mrem/y.

= Ground concentration of radionuclide i, µCi/m 2

Dose factor for standing on contaminated ground, mrem/h per pCi/m 2 (Table 1.8).

8,760 = Occupation time, h/y.

1x106 = pCi/µ'Ci conversion factor.

0.7 = Shielding factor accounting for a distance of 1 .0 meter above ordinary ground, dimensionless.

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

CV, = a,SOO t k=1 ft 0 1 DR (2mc/n)

( r[1 -exp (-Ae1t,))

Y, Ae1

+ B [ 1 -exp (-A,t )]) [lexp-(A,t )Jj I* PA, b h (1.10) where:

Concentration of radionuclide i in and on vegetation, µCi/kg.

k = Stability class.

12

PALISADES NUQLEAR PLANT OFFSITE DOSE CALQULATION MANUAL Revision 11

fk = Frequency of this stability class and wind direction combination, expressed as a fraction.

Qi = Average release rate of radionuclide i, µCi/s.

DR = Relative deposition rate, m- 1 (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 r iodines, 0.2 for particulates) .

AEi = Effective removal rate constant, AEi = A; + Aw, where A; is the radioactive decay coefficient, h- 1 ,

and Aw is a measure* of physical loss by weathering (Aw = 0.0021 h-).

te = Period over which deposition occurs, 720 h.

Yv = Agricultural yield, 0. 7 kg/m 2

Biv = Transfer factor from soil to vegetation of radionuclide i (Table 1.6).

A; = Radioactive decay coefficient of radionuclide i, h- 1 *

tb 13

= Time for buildup of radionuclides on the ground, 1.31x10 5 h (15Y).

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

3,600 p =

=

Effective surface density of soil, 240 kg/m 2

s/h conversion factor.

= Holdup time between harvest and 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 14 = 1x103 x14 co.1110.1s)

( 1 . 11) where:

Concentration of C-14 in vegetation, µCi/kg.

r*

3 Air concentration of C-14, µCi/m .'

0.11 = Fraction of total Plant mass that is natural carbon.

0.16 = Concentration of natural carbon in the atmosphere, g/m 3

1x103 = g/kg conversion factor.

For determining the concentration of H-3 in vegetation:

CV T =1 x 10 3 XT (0.75)(0.5/H)

(1.12) where:

CVr = Concentration of H-3 in vegetation,

µCi/m 3

Xr = Air concentration of H-3, µCi/m 3 .

0.75 = Fraction of total Plant mass that is water.

14

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

0.5 = Ratio of tritium concentration in Plant water to tritium concentration in atmospheric water.

H = Absolute humidity of the atmosphere, g/m 3 .

1x10 3 = g/kg conversion factor.

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

( 1 .13) where:

= Concentration of radionuclide i (including C-14 and H-3) in milk, r*

µCi/t

= Concentration of radionuclide i in and on vegetation, µCi/kg.

Transfer factor from feed to milk for radionuclide i, d/Q (Table 1 .6).

Amount of feed consumed by the milk animal per day, kg/d (cow, 50 kg/d or goat 6 kg/d).

"i =

Radioactive decay coefficient of radionuclide i, d- 1

Transport time of activity from feed to milk to receptor, 2 days .

15

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11 For determining the organ dose rate from ingestion of green leafy vegetables and milk:

D = 1 x 10 6 Li c M.I D. F.I uM (1.14) where:

D = Organ dose rate due to ingestion, mrem/y.

CMi = Concentration of radionuclide i in vegetables or milk, µCi/kg (or liters).

DFi = Ingestion dose factor, mrem/pCi (Table 2.1).

UM = Ingestion rate for milk, 330 e/y; for vegetables 26 kg/yr (child), no !'

d) 1x106 =

ingestion by infant.

pCi/µCi conversion factor.

Meat Ingestion (Beef)

To calculate the concentration of a nuclide in animal flesh:

(1.15) where:

= Concentration of nuclide i in the animal flesh, pCi/kg.

= Fraction of animal's daily intake which appears in each kg of flesh, days/kg (Table 1 .6).

Concentration of radionuclide i in

16 the animal's feed (Equation 1.10).

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

=

=

Amount of feed consumed by the cow per day, 50 kg/d.

Average time*from slaughter to consumption, 20 days.

To determine the organ dose from ingestion of beef:

D f :: Li c fl D fl uf (1 .16) where:

= Ingestion dose factor for age group, mrem/pCi (Table 2.1) for nuclide i.

= Ingestion rate of meat for age group, kg/y (child-41, teen-65, r*

- e) Organ Dose Rates adult-11 0) .

For determining the total body and organ dose rate from iodines and particulates:

( 1 . 1 7) where:

D = Total organ dose rate, mrem/y.

Dose rate due to inhalation, mrem/y.

Dose rate due to ground contamination, mrem/y.

Dose rate due to milk ingestion, mrem/y .

17

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

=

=

Dose rate due to vegetable ingestion, mrem/y.

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 I.Bl are used to calculate design basis quantities as described in Section l.B.1.3.

c. Design Basis Quantities The design basis quantity of a radionuclide emitted to the atmosphere is the amount of that nuclide, when released in one year, which would result in a dose not exceeding any of the following:

1) 1 5 millirem to any organ of an individual from iodines r and particulates with half-life greater than 8 days (Appendix A, Section 111.D.1 ).

2) 1 5 millirem to skin of an individual from noble gas (Appendix A, Section 111.C.1.b).

3) 5 millirem to the total body of an individual from noble gas (Appendix A, Section 111.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 DBQ = DAI {Cc) c (1.18) where:

= Appendix I dose limit (mrem or mrad).

18

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

=

=

Calculated dose (mrem or mrad).

Quantity of nuclide resulting in dose De (Ci).

DBQ = Design Basis Quantity (Ci).

The limiting values for Design Basis Quantities for radionuclides released to the atmosphere are given in Table 1.9.

The inverse of the ratio Cc/De in the above equation (ie, De/Cc) is a useful value, since it represents the most limiting dose per unit quantity of each nuclide released. Use of the De/Cc ratio in quarterly evaluation of offsite dose is discussed in Section D. Values of De/Cc are given in Table 1.9.

d. Land Use Census and DBQ Changes Appendix A, Sections J.3.b and J.3.c describe the requirements for an annual land use census and revision of r the ODCM for use in the following calendar year. Areas of the ODCM which will be reviewed, and changed if appropriate, are Table 1.4 (Land Use Census Data by Sector), Table 1.4a (Critical Receptors), and Table 1.9 (Gaseous Design Basis Objective Annual Quantities).

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

e. Gaseous Releases From the Steam Generator Slowdown Vent and Atmosphere Release Valves Releases from the steam generator blowdown vent and atmospheric relief valves are difficult to quantify as there are no sampling capabilities on these steam release systems.

However, neither 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 Iodines and 1 percent of the Particulates will be released to the environment in the steam phase. Volumes will be released to the environment in the steam phase.

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

19

PALISADES NUCLEAR PLANT OEFSITE DOSE CALCULATION MANUAL Revision 11

c. DESIGN OBJECTIVE QUANTITY (DBQ) 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 . 0:

Ai

< 1.0 (DBQ)i

( 1 .1 9)

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

2. Continuous Releases Low level continuous releases from the vent gas collection header and other low level 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. Exceeding DBQ Limits As discussed under 8.1.3, the DBQ is a very conservative estimate of activity which could give doses at Appendix I limits. Because 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 is 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

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

~--------------------

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

4. Releasing Radionuclides Not Listed in Table 1.9 Table 1 .9 contains all nuclides identified to date as routine constituents of gaseous releases at Palisades Plant, plus those common to PWRs in general, even if not previously detected at Palisades. From time to time, however, other nuclides may be detected.

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

If the unlisted nuclide constitutes greater than 10% of the ,.

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

Should a nuclide not listed in Table 1 .9 begin to appear in significant quantities on a routine basis, revision to this ODCM should be made in order to include a design basis quantity specific to that nuclide.

D. OPTIONAL QUARTERLY DOSE CALCULATIONS

1. Methodology for Optional Quarterly Dose Calculations 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 pathway or characteristics of the assumed critical individual (infant, child, teen, and adult), since Table 1 .9 indicates these parameters .

21

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

a. Simplified Conservative Approach 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.

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 method, but requiring computer support) will be utilized.

1. Assumptions a) All assumptions of Section 1. 1 are utilized.

b) Limiting doses for each gaseous nuclide are

- c) summed, regardless of limiting decay mode (gamma or beta).

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

d) Doses are summed for detected nuclides such that all nuclides which contribute greater than 10% individually or 25% in aggregate, to the EC of released radioactivity, are included in the dose calculation.

2. Equations For determining gaseous effluent dose:

i DG =L A 1 G(D/Cc~G < 5 millirad/quarter, *10 mrad/yr 0

(1.20) 22

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

where:

DG = Dose from gaseous effluents (mrad).

AiG = Quantity of gaseous nuclide i released (Ci).

= Dose per Ci factor for gaseous nuclide i (mrad/Ci).

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.

For determining tritium, particulate and iodine dose to organs:

DTPr where:

=L i

ATPn (D/Cc)TPn < 7.5 mrem/q, 15 mrem/y (1 .21)

DTPI = Dose from particulates and iodines (mrem).

ATPli = Quantity of particulate or iodine nuclide i released (Ci).

Dose per Ci factor for particulate or iodine nuclide i (mrad/Ci).

b. Realistic Calculation 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

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

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 frequency meteorological data based on not less than 3 years of meteorological measurement, and will reflect demographic and land use information from the land use survey generated 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 greatly in relation to season of the year.

An alternative to GASPAR for offsite dose calculation is the use of the Palisades Segmented Gaussian Plume Emergency off site dose calculation program. This dose model allows evaluation of dose under the actual meteorological conditions present at the time of release. It is anticipated that the 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 .

E. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION The gaseous radwaste treatment system (GRTS) described below shall be maintained and operated to keep releases ALARA.

1. System Descrjptjon 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.

Gaseous 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 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 le.akage 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 Revision 11

~---------------------

2. Determination of Satisfactory Operation Design basis quantity fraction will be calculated for batch and continuous releases as described in Section l.C. These calculations will be used to ensure that the GRTS is operating as designed.

Because the Plant was designed to collect and hold for decay a vast majority of the high level gases generated within the primary system, and because the 13-year operating history (to date of 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.

F. RELEASE RATE FOR OFFSITE EC (50 mrem/yr) 1 0 CFR 20. 1 302 requires radioactive effluent 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: there are no unrestricted areas anywhere within the site boundary as defined by Figure 1-1.) Concentrations at this level if present for r'

one year will result in a dose of 50 mrem whole body. 10 CFR 50.36a

requires that the release of radioactive materials be kept as low as reasonably achievable. However, the section further states that the licensee is 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 within those limits. Appendix I to 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as reasonably achievable requirement.

The GASPAR code has been run to determine the dose due to external radiation and inhalation. The source term used is listed in Table 1.1.

The meteorology data is given in Table 1.3. Dose using annual average meteorology, to the most limiting organ of the person assume to be residing at the site boundary with highest X/Q, is 2. 1 5E-02 mrem (for one year). The release rate which would result in a dose rate equivalent to 50 mrem/year (using the more conservative total body limit) is the curies/year given in Table 1.1 multiplied by 50/2.15E-02 or

0. 11 Ci/sec .

25

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

~-----------------

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 integrated release from a gas batch {waste gas decay tank or Containment purge, for example), or a series of samples are obtained to follow the course of a release. In any event, sample *intervals are weekly, 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 particulates and iodines) utilized rather than the pre-release estimates, for cumulative records.

Gamma analytical results for particulate and halogen filters are combine(ji-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 "unidentified" beta is assumed to be Sr-90 until results on actual Sr-90

{chemically separated from a quarterly composite of filters) are obtained.

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

H. NOBLE GAS SAMPLING 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 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 1 E-06 µCi/cc. Sampling and analysis will be performed per Appendix A, Table B-1 requirements .

26

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11 I. 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 .

27

L "Tl STACK C>

c

xJ m

lI en WASTE GAS I )>

_.J SURGF TANK 2 RE 2120 RE 1113 c

-t 6r----;i:::-. . .--.L0...&..._'" ATMOsPHERE

)>

CXJ HEPA I m

~ ~ 298 LOW LIEVEL GAS COLLECTION--------...J ..,__;:._---JI- en STEAM GENERATOR HEADER HEPA BLOWDOWN TANK VENT REOlll CONDENSER OFF GAS N

I AUX I 1 HEPA/CHARCOAL 00 llLOO RAD- ~.--. __ * ......

WASTE ARE RE 1809" HEPA WEST SArE GUARD RE 11111 HEPA INORMALI CONTAIN RE Ill 1 FUEL MENT SUl't"L Y HANDl_G BLDG AREA HEPA/CHARCOAL )>

r-IRF.FUFUNGI r---------,

r-----------, HEPA 1 FUEL Q Q RAO- : AREA lh-- StJ, .>Ly RE 5112" ADDIT SUPPLY ----f).:

WAST£ ARFA AODIT N RE 5711" "RE 1ll09. 5711 AND 5112 TRIP SUPPLY AND ONE OF r .. I) [XHAUSTFRS FLOW IS NOT TERMINATED PALISADES EFFLUENT FLOW PATHS GASEOUS

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

TABLE 1.1 PALISADES GASEOUS AND LIQUID SOURCE TERMS. CURIES/YEAR (1)

Nuclide Gaseous(2l !:im.!iQ(2)

H-3 5.5 159 Kr-85 4.1 NA Kr-85m 0.12 NA Kr-87 8.4E-02 NA Kr-88 2.1 E-01 NA Ar-41 3.1 E-02 NA Xe-131 m 2.2 NA Xe-133 1493 NA Xe-133m 0.43 NA Xe-135 1 .11 NA Xe-135m 0.3 NA 1-131 0.025 3.21 E-03 1-132 2.91 E-03 NA 1-133 6.5E-03 4.7E-05 1-134 4.8E-04 NA 1-135 1.84E-02 NA r*

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 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 1.5E-07 NA 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 7.5E-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.

(2) Nuclide values listed as NA have not been observed at detectable levels in these waste streams.

29

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

NUCLIDE HALF-LIFE TABLE 1.2 BASIC RADIONUCLIDE DATA

!:.8MBDA BEIA 1 GAMMA 1 ldaysl ilM IMEV/DISl IMEV/DISl 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 C0-58 7.13E01 1.12E-07 3.41 E-02 9.78E-01 14 C0-60 1.92E 03 4.18E-09 9.68E-02 2.50E 00 15 ZN-69m 5. 75E-01 1.39E-05 2.21 E-02 4.16E-01 r 16 ZN-69 3.96E-02 2.03E-04 3.19E-01 0.0 17 BR-84 2.21E-02 3.63E-04 1.28E 00 1.77E 00 18 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 2.21E-03 21 KR-87 5.28E-02 1.52E-04 1.32E 00 7.93E-01 22 KR-88 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 1.24E-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-OO 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-91m 3.47E-02 2.31E-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 40 M0-99 TC-99m 2.79E 00 2.50E-01 2.87E-06 3.21 E-05 3.96E-01 1.56E-02 1.50E-01 1.26E-01 30

PALISADES NUCLEAR eLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

TABLE 1.2 {continued)

BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA 1 GAMMA 1 (days) ilill IMEV/DISl !MEV/DISl 41 TC-99 7.74E07 1.04E-13 8.46E-02 0.0 42 TC-104 1.25E-02 6.42E-04 1.60E 00 1 .95E 00 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 1-129 6.21 E 09 1.29E-15 5.43E-02 2.46E-02 46 1-131 8.05E 00 9.96E-07 1.94E-01 3.81 E-01 47 1-132 9.58E-02 8.37E-05 4.89E-01 2.24E 00 48 1-133 8.75E-01 9.17E-06 4.08E-01 6.02E-01 49 1-134 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 1.18E01 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 2.71E03 2.96E-03 1.77E 00 1.88E-01 57 XE-138 9.84E-03 8.15E-04 6.65E-01 1.10E 00 58 CS-134 7.48E 02 1.07E-08 1.63E-01 1.55E 00 59 CS-135 1.1 OE 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 1.1 OE 04 7.29E-10 1.71E-01 5.97E-01 62 CS-138 2.24E-02 3.58E-04 1.20E 00 2.30E 00 63 BA-139 5.76E-02 1.39E-04 8.96E-01 3.53E-02 64 BA-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 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 Average energy per disintegration values were obtained from ICRP Publication No 38, Radionuclide Transformations: Energy and lntensitv of Emissions 1983 and NUREG/CR-1413 (ORNL/NUREG-70), a Radionuclide Qecay Data Base - Index and Summary Table, DC Kocher, May 1980.

31

USNRC COMPUTER CODE - XOQDOQ. VERSIQN 2.0 RUN DATE: 931116

- '""* PALIS.ADES llOQOOQ82 ..... US.ING 01/01/BB - 12/31/92 MET DATA ... ._

GROUHO LEVEL RELEASE - TOP OF CONTAINMENT BUILDING NO l)[CAY, UNDEPLETED ANNUAL AVERAGE CHl/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE SECTOR 0.250 D.500 0.750 l.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S 3.613£-06 1.ZOSE-06 6.540E-07 4.310E-07 2.395E-07 l.586E-07 1.153[-07 8.895E-08 7.l45E-08 5.913E-08 5.006l-OB SSW 3.005£-06 9.699£-07 5.193E-07 3.431£-07 l.919E-07 l.278E-07 9.340E-08 7.233E-08 5.830£-08 4.839E-08 4.107£-08 SW 3.948E-06 1.259E-06 6.682E-07 4.392E-07 2.445E-07 l.634E-07 l.199E-07 9.308[-08 7.522E-08 6.257£-08 5.321£-08 WSW WNW W

4.031E-06 4.756E-06 6.204E-06 1.259E-06 1.492[-06 1.951£-06 6.556E-07 7.747E-07 l.016E-06 4.287E-07 5.051E-07 6.6Z2E-07 2.384E-07 2.798E-07 3.665E-07 l.606E-07 1.880[-07 2.462£-07 l.187E-07 1.387£-07 l.816E-07 9.277£-08 1.083£-07 l.417E-07 7.537E-oa 8.786£-08 1.150£-07 6.298£-08 7.336£-08 9.601£-08 5.378E-08 6.259f-08 8.192E-08 0

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S 4.315E*08 2.445[-08 l.639E-08 9.379E-09 6.336E-09 4.68ZE-09 3.661£-09 2.976£-09 Z.488E-09 2.126E-09 1.848E-09 SSW 3.548£-08 Z.OZ7E-08 l.367E-08 *1.884E-09 5.355E-09 3.975£-09 3.119£-09 2.543£-09 2.132E-09 1.825£-09 1.569£-09 SW 4.606E-08 2.65ZE-08 l.798E-08 l.045E-08 7.140E-09 5.323£*09 4.19ZE-09 3.429E-09 2.882E-09 2.474(-09 2.159£-09 z~

WSW 4.671E-08 2.726E-08 l.866E-08 l.099E-08 7.574E-09 5.686E*09 4.503E-09 3.701[-09 3.124£-09 2.691E-09 2.356£-09 s:)> )>z W 5.434E-08 3.165E*08 Z.164E-08 l.273E-08 8.770E-09 6.582£-09 5.212E-09 4.283E-09 3.615E-09 3.114E-09 2.726£-09 WNW 7.llOE-08 4.139£-08 2.829[-08 l.663E-08 1.145[*08 6.594£-09 6.804E-09 5.589E-U9 4.717E-09 4.063E-09 3.556E-09 z-4 NW 9.440E-08 5.54DE-08 3.807E-08 Z.254E-06 1.560£-08 l.174E-08 9.321£-09 7.674E-09 6.488E-09 5.598E-09 4.907E-09 c NNW l.236E-07 7.285E-D8 5.021E-08 2.985£-08 2.071E-08 1.562£-08 1.242£-08 l.024E-08 8.668f-09 7.486E-09 6.568E-09 )>

N l.270E-07 7.462£-08 5.132£-08 3.042E-08 2.l06E-08 l.586£-08 l.259E-08 l.037E-08 8.770£-09 7.567£-09 6.634£-09 r-NNE 6.428E-08 3.7J2E*08 2.522E-08 l.470E-08 l.005E-08 7.503E-09 5.914E-09 4.840E-09 4.071E-09 3.496f-09 3.052E-09 NE 5.842E-08 3.272E*08 2.176£-08 l.232E-08 8.275E-09 6.088£-09 4.743£-09 3.844E-09 3.206£-09 2.734£*09 2.371£*09 ENE 4.llOE-08 2.310E*08 1.540£*08 8.758£-09 5.900£-09 4.351E-09 3.398E-09 2.759£-09 2.305£-09 1.968£-09 1.710£-09 E 4.148E-08 2.308E-08 l.528E-08 8.597E-09 5.751£-09 4.218£-09 3.279E-09 2.653E-09 2.209£-09 1.881£-09 1.630[-09 ESE 4.234E-08 2.351E-08 l.554E-08 8.734£-09 5.839£-09 4.281£-09 3.328E;09 2.692£-09 2.242E-09 1.909£-09 1.654£-09 SE 4.763E-08 2.646E-08 l.750E-08 9.846£-09 6.589[-09 4.836£-09 3.762£-09 3.045[-09 2.538£-09 2.162£-09 1.875[-09 SSE 5.546£-08 3.102E-08 2.061E-08 1.166£-08 7.833£-09 5.764£-09 4.493£-09 3.643£-09 3.040E-09 2 592[-09 2.25DE-09 VENT ANO BUILDING PARAMETERS:

RELEASE HE (Giff (HEH RS) 58.10 REP. WIND HEIGHT (METERS I 10 0 OIAHETER (HfTfRS) 0.00 BUILDING HEIGHT (METERS) 58 I EXIT VELOCITY (METERS) 0.00 BLDG.HIN.CRS SEC.AREA (SQ.METERS) 2000 0 HEAT EHlSSIOif RATE (CA.L/SlC) aa ALL GROUND LEVEL RELEASES.

USNRC COMPUTER COOE - XOQOOQ, VERSION 2 .0 RUN DATE: 931116 0

"T1

- - - - PALISADES XOQOOQ82 ***** USING 01/01/88 - 12/31/92 MET OA£A ***** "T1 (J)

GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING -i "'O NO DECAY, UNDEPLETED m r)>

0 (J)

CHl/Q (SEC/METER CUBED) fOR EACH SEGMENT 0 )>

(J)

SEGMENT BOUNDARIES IN MILES FROM THE SITE

xJ m 0m DIRECTION .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 a> n en FROM SITE s 6.773E-D7 2.461E-07 1.163[-07 7 .176E-08 5.019£-08 2.503[-08 9. 585E-09 4. 714E-09 2.986£-09 2 .130£-09

-i

)> :s.

(I)

)>

r- cz w SSW 5.411E-D7 l.970E-07 9.415E-08 5.853E-08 4.117£-08 2.072£-08 8.046[-09 4.00DE-09. 2.551£-09 I. 629£-09 DJ c;* n w 2.707£-06 l.065E-08 5.35SE-09 3.439£-09 2.478[-09 r- c n SW 6.978E-D7 Z.517E-07 l.208E-07 7.550E-08 5. 334E-DB m :J r r WSW 6.889E-07 2. 46lE-07 1.195E-07 7. 56ZE-08 5.389E-08 Z. 776E-08 I. ll 7f-08 5 716E-09 3.710[-09 2.695[-09 ...... ...... m

)> )>

w 8. l42E-07 2.891E-07 l.397E-07 8.817E-08 6.273[-08 3.Z24E-06 1.295£-08 6.61BE-09 4.294E-09 3.119E-09 ......

WNW l.067E-06 3. 787E-07 1.829£-07 l.l54E-07 B.209£-08 4. 217£-08 I. 692£-08 B.640E-09 5.604[-09 4.069[-09 w ::! ::xJ NW l.376E-06 4.898[-07 2.390£-07 1.520[-07 1. 087£-07 5.636[-08 2.291£-0B I. 180£-0B 7.693£-09 5.606[-09 0 "'O NNW 1.785£-06 6.336£-07 3.104£-07 1. 9B2E-07 I. 422E-07 7.407£-08 3.031£-0B I 570E-08 I. 026£-08 7.496[-09 z r N 1.837£-06 6.554£-07 3.206[-07 2.042E-07 l. 462E-07 7.590£-08 3.090E-OB 1. 594E-OB 1.040[-0B 7.578£-09 s: )>

NNE 9.584E-07 3.475£-07 l. 675£-07 l. 050£-07 7.437E-08 3.7B7E-08 I. 497£-0B 7.548£-09 4. 854[ -09 3. 502f:-09 )> z NE 9.675E-07 3. 473E-07 l. 613£-07 9.832£-06 6.819E-OB 3.356E-OB 1.262[-08 6.133E-09 3.BSBE-09 2. 739[-09 z -i ENE 6.805£-07 2. 431£-07 l.130E-07 6.902E-08 4.794E-08 2.368[-08 8.965[-09 4.383£-09 2.769£-09 1.972[-09 c

[ 7.085E-07 Z.519£-07 1.159£-07 7. 025E-08 4.850£-08 2.370[-08 8.617[-09 4.251[-09 2.663[-09 1 885£-09 )>

ESE 7.373E-07 2.597£-07 1.189£-07 7.188E-06 4.955£-08 2.415£-08 8.960£-09 4.315E-09 2.702[-09 I .9Ll(-09 r-SE 6 .350£-07 Z.928£-07 1. 338[-07 6.087£-08 5.574£-0B 2. 718£-08 l.OlOf-08 4.874E-09 3.057f-09 2 .167£-09 SSE 9.387E-07 3.330[-07 1.538£-07 9.353£-08 6.477£-06 3 .182£ -06 1.195[-08 5.807E-09 3.656£-09 2.598[-09

USNRC COMPUTER CODE - XOQDOQ, VERSION 2.0 RUH DATE: 931116

- - - - PALISADES XOQDOQBZ ***** USING 01/01/88 - 12/31/92 MET DATA *****

GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING 2.260 DAY DECAY, UNDEPLETEO ANNUAL AVERAGE CHl/Q (SEC/METER CUBED) DISIANCE IN MILES FROM THE SITE SECTOR 0.250 0.500 0.750 1.000

1.500 2.000 Z.500 3.000 3.500 4.000 4.500 s l.670E-06 l.203E-06 6.522E-07 4.294E-07 2.382E-07 l.574E-07 l.143E-07 8.798E-06 7.055E-08 5 828£-08 4 925E-08 SSW l.OOJE-06 9.680E-07 S.177E-07 3.418E-07 l.907E-07 l.268E-07 9.Z49E-08 7.148E-08 5.750[-08 4.763£ *08 4 035E-08 SW 3.943E-06 1.Z56E-06 6.658E-07 4.371E-07 2.428£-07 l.618E-07 l.184E-07 9.174E-08 7.396E-08 6.137[-08 5.207E-08 WSW 4.027E-06 1.Z56E-06 6.536E-07 4.Z69E-07 Z.36BE-07 1.592£-07 l.174E-D7 9.160E-OB 7.426E-08 6.192£-08 5.277£-0B w 4.7SZE-06 l.489E-06 7.724E-D7 5.031E-07 2.781E-07 l.86SE-07 l.373E-D7 1.070[-07 8.663E-08 7.216E-08 6.147E-06 WNW 6.199E-06 1.94BE-06 l.013E-06 6.S99E-07 3.846E-07 2.445E-07 l.801E-07 1.403£-07 l.136E-07 9.469E-08 8.065[-06 NW 8.158E-06 2.SZlE-06 1.304E-06 8.SOOE-07 4.71ZE-07 3.180[-07 2.354E-D7 l.842E-07 I 497£-07 1.251£-07 l.066E-07 NNW l.07DE-05 3.280E-06 l.690E-06 l.099E-06 6.090E-07 4.lZZE-07 3.060E-07 2.399E-07 l.954E-07 1.636[-07 l.399E-07 N l.09ZE-05 3.359E-06 l.742E-06 1.136E-06 6.307E-07 4.Z6ZE-07 3.158E-07 2.473E-07 2.0llE-07 1.682£-07 1.437£*07 NNE 5.434[-06 l.721E-06 9.l67E-07 6.0ZBE-07 3.358E-07 2.246E-07 l.648E-07 l.280E-07 l.034E-07 8.597E-08 7.307E-08 NE 5.173E-06 l.717E-06 9.353E-07 6.119E-07 3.360E-07 2.200£-07 l.585E-07 l.213E-07 9.677E-06 7.960£-08 6.702£-08 ENE 3.740E-06 l.ZlSE-06 6.557E-07 4.278E-07 2.350E-07 l.540E-07 l.llOE-07 6.496E-06 6.784E-08 5.583(-08 4.703E-OH E 3.796E-06 1.262£-06 6.848E-07 4.456E-07 2.434E-07 1.586£-07 l.138E-07 8.679[-08 6.905E-OB 5.666E-08 4.760E-08 ESE 3.957E-06 1.321£-06 7.ll8E-07 4.613E-07 2.509E-07 1.63JE-07 1.169£-07 8.905E-08 7.0BOE-08 5.806£-08 4.675E-08 ::JJ CD SE 4.523E-06 1.499£-06 8.056£-07 5.207[-07 2.826E-07 l.835E-07 1.3l5E-07 l.OOlE-07 7.956£-08 6.SZSE-08 5 478E-08 ~

.... ~

SSE 5.082£-06 l.679E-06 9.051E-07 5.887E-07 3.217E-07 2.lOOE-07 J.SIDE-071.154E-07 9.198[-0B 7.559£-08 6 359E-08 .,... !!!.

0 ANNUAL AVERAGE CHI/Q (SEC/HETER CUBED) DISTANCE IN MILES FROH THE SITE :::::s SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.DOO 35.000 40.0DO 45.000 50.00D ......

s 4.Z38E-08 2.380E-08 1.58ZE-D8 8.896E-09 5.911E-09 4.299E-09 3.310£-09 2.65DE-09 Z.183£-09 1.838E-09 1.575E-09 SSW 3.479E-08 l.969E-08 l.31SE-08 7.447E-D9 4.969£-09 3.6Z5E-09 2.797E-09 2.243£-09 l.850E-09 l.560E-09 l.337E-09 SW 4.496E-08 Z.558E-08 1.71SE-D8 9.751E-09 6.SZlE-09 4.763E-09 3.679£-09 2.952E-09 2.436£-09 2.0SSE-09 1.762[-09 llSW 4.574E-08 Z.641E-08 l.789E-08 l.033E-D8 6.966f-09 5.147E-D9 4.D04E-D9 3.233[-09 2.682E-D9 Z.Z7ZE-09 l.957£-09 w 5.325E-08 3.07lE-08 2.080E-08 1.201E-08 8.lZSE-09 S.992E-09 4.666E-09 3.771E-09 3.132E-09 2.656[-09 2.289£-09 lllN 6.988E-08 4.033E-08 Z.733E-08 l.581E-08 l.D72E-08 7.915E-09 6.17ZE-09 4.996E-09 4.155E-09 3.528£-09 3.045£-09 IN 9.278E-08 5.399[-08 3.679[-08 2.l43E-08 1.459£-08 1.082£-0B B.459E-09 6.862E-09 5.718E-09 4.663E-09 4.204£-09 NIN 1.216E-07 7.lllE-08 4.863[-08 2.848E-08 1.947E-08 l.448E-08 J.llSE-08 9.233E-09 7.711E-09 6.S72E-09 5.692£-09 H l.248E-07 7.274E-D8 4.963£-08 Z.895E-08 l.973E-08 1.464[-08 l.l45E-D8 9.294E-09 7.748E-09 6.593E-09 5.700[-09 NNE 6.319E-08 3.619E-08 2.439£-08 1.400£-08 9.430E-09 6.934E-09 S.388E-09 4.347E-09 3.606£-09 3.0SSE-09 2.632[-09 NE 5.749E-08 3.195E-08 2.108[-08 J.175E-08 7.778E-09 5.641E-09 4.334E-09 3.465E-09 2.852£-09 2.400E-09 2 055E-09 ENE 4.036E-08 2.249£-08 l.486E-08 8.308E-D9 5.SOSE-09 3.996E-09 3.073E-09 2 458E-09 2.023£-09 1.703[-09 1.459£-09 E 4.076£-08 Z.Z48E-08 1.476[-08 8.168£-09 5.376E-09 3.882£-09 2.972E-09 2.369£-09 I .944£-09 l.631E-09 1.394£-09 ESE 4.173£-08 2.JOOE-08 1.510£-08 8.361E-09 5.510E-09 3.96SE-09 3.055[-09 2.438£-09 2.003£*09 l.683E-09 1.440[-09 SE 4.688£-08 2.584E-08 l.697E-OB 9.401E-09 6.200[-09 4.486E-09 3.442E-09 2.749£-09 2.261£-09 1.901[-09 1.62/l-09 SSE 5.452E-D8 3.023E-08 1.992E-OB l.l09E-08 7.331E-09 5.313[-09 4.079E-09 3.259£-09 2.681(-09 2.255[-09 1.930£*09 VENT ANO BUILDING PARAMETERS:

RELEASE HEIGHT (METERS) 58 .10 REP. WINO HEIGHT (METERS) 10.0 DIAMETER (METERS) 0.00 BUILDING HEIGHT (HETERS) 58. I EXIT VELOCITY (METERS) 0.00 BLOG.MIN.CRS.SEC.AREA (SQ METERS) 2000.0 llEAT EMl~SION RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.

USNRC COMPUTER CODE - XOQDOQ, VERSION 2 .0 RUN DATE: 931116

- - - - PALISADES XOQDOQ82 ***** USING 01/01/88 - 12/31/92 MET DATA *****

GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING 2.260 DAY DECAY, UNDEPLETED CHl/Q (SEC/HETER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN HILES FROM THE SITE DIRECTION . 5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FROM SITE ::0 CD s 6.755E-07 2.448E-07 1.153E-07 7.085E-08 4.938E-08 2.438E-08 9. l07E-09 4.333E-09 2.661E-09 l. 843E-09 -i <

w SSW 5.396E-07 l .959E-07 9.323E-08 5.773[-08 4.045E-08 2.0l4E-08 7.613[-09 3.652E-09 2.251E-09 l.563E-09 l=- ~:

SW 6.954E-07 2.500[-07 7.424E-08 9.960[-09 4.798E-09 2.963[-09 al U1 l.193E-07 5.219E-08 2.614E-08 2.059E-09 r- 0 WSW 6.868E-07 2 .446E-07 1.183[-07 7.451E-08 5.288[-08 2.692[-08 1.053[-08 5.180[-09 3.243E-09 2.277E-09 m :::J w 8.118E-07 2.874£-07 1. 383E-07 8.693E-08 6.160E-08 3 .132[-08 1. 224[-08 6.030E-09 3.783[-09 2.661E-09 ..... .....

WNW l.064E-06 3.768E-D7 l.813E-07 l .140E-07 8.082E-08 4.112E-08 1.611E-08 7.965[-09 5.012E-09 3.535[-09 l.088E-08 w

NW 1.373E-06 4.873E-07 2.370[-07 1.502E-07 1.070E-07 5.496[-08 2. lBlE-08 6.883E-09 4. 872E-09 NNW l.781E-06 6.305[-07 3.079E-07 1.960[-07 1.401E-07 7.234[-08 2.895[-08 1.456[-08 1.472[-08

9. 259E-09 6.584E-09 z r-N NNE l.832E-06 9.560E-07 6.521£-07 3.17BE-07 2.018E-07 1.440E-07 7.404[-08 3.695[-08 2.945[-08 l.428E-08 6.981E-09 9.322E-09 4.362E-09 6.604[-09 s: l=-

3.457E-07 1.660E-07 l.038E-07 7.323E-08 3.062E-09 l=- z NE ENE 9.653E-07 6.788E-07 3.458£-07 2.418£-07 l.600E-07 1.120E-07 9.723£-08 6.816£-08 6.722E-08 4.717E-08 3.280[-08 2.307£-08 1.206[-08 8.519E-09 5.688E-09 4.029E-09 3.480[-09 2.468[-09 2.406E-09 l.707E-09 z -i E 7.067E-07 2.507E-07 1.149E-07 6.940£-08 4.775[-08 2.311[-08 8.392E-09 3.917E-09 2.379E-09 1. 636.E-09 c

8.591E-09 4.020E-09 2.449[-09 l=-

ESE 7.358£-07 2.586E-07 1. 181[-07 7. 116E-08 4.891E-08 2.365E-08 1. 688E-09 r-SE 8.331E-07 2.915£-07 1.328E-07 7.999£-08 5.496[-08 2.657E-08 9. 659E-09 4. 525E-09 2.761[-09 1. 906[-09 SSE 9.365E-07 3.314[-07 1.525E-07 9.243E-08 6.379[-08 3. 105£-08 1.138[-08 5.358E-09 3.273[-09 2.261[-09

USNRC CO"PUTER CODE - XOQDDQ, VERSION 2.0 RUN DATE: 931116

- - - - PALISADES XDQDOOB2 ***** USING 01/01/88 - 12/31/92 HET DATA *****

GROUND LEVEL RELEASE - TOP OF CONTAINHENT BUILDING 8.000 DAY DECAY, DEPLETED ANNLJAL AVERAGE CHl/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE SECTOR D.250 0.500 0.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 s 3;476E-06 l.lOOE-06 5.823E-07 3.769E-07 2.0JlE-07 l.310E-07 9.318[-08 7.043E-08 5.555£-08 4.521£-08 3.767£-08 SSW 2.844E-06 8.852E-07 4.623£-07 3.000E-07 1.627£-07 l.056E-07 7.545[-08 5.726E-08 4.531£-08 J.698E**08 3.089t-08 SW 3.735£-06 l.149E-06 5.949E-07 3.839[-07 2.073E-07 l.349E-07 9.675£-08 7.363£-08 5.84lf~08 4.777E-08 3.998E-08 WSW 3.814E-D6 l.149E-06 5.837E-D7 3.748E-07 2.021E-07 l.327E-07 9.586£-08 7.342£-08 5.856E-08 4.811E-08 4.044E-08 w 4.500£-06 1.361£-06 6.898£-07 4.416£-07 2.372£-07 1.553£-07 1.120£-07 8.57DE-08 6.828E-08 5.605E-08 4.708£-08 llllW 5.870£-06 1.781£-06 9.048£-07 5.791E-07 3.108£-07 2.035£-07 1.468[-07 l.l23E-07 8.943E-08 7.341E-08 6.166£-08 llW 7.7Z6E-06 Z.305£-06 1.164£-06 7.459£-07 4.017£-07 2.647£-07 1.919£-07 1.474[-07 l.178E-07 9.700£-08 8.168E-08 NllW l.014E-05 Z.999E-06 1.509£-06 9.646£-07 5.191£-07 3,430£-07 Z.493£-07 1.919[-07 1.537£-07 l.267E-07 l.069E-07 N 1.034E-05 3.072E-06 l.SSSE-06 9.970E-07 5.376E-07 3.547E-07 Z.574E-07 1.979£-07 l.583E-07 l.304E-07 1.098[-07 NllE 5.146£-06 1.574E-06 8.184E-07 S.290E*07 2.863E-07 l.869E-07 l.343E-07 l.024E-07 8.l38E-08 6.665E-08 5.586£-08 llE 4.899E-08 l.570E-06 8.349E-07 5.368E-07 Z.864E-07 1.830E-07 1.291£-07 9.700E-08 7.61lf-08 6.167[-08 5.120£-08 EllE 3.542£-06 1.lllE-06 5.854E-07 3.754£-07 Z.004£-07 l.281E-07 9.048£-08 6.802E-08 5.341£-08 4.330E-08 3.597E-08 E 3.595E-06 l.154E-06 6.114E-07 3.91DE-D7 2.015E-07 l.320E-07 9.275£-08 6.945£-08 5.435E-08 4.393£-08 3.640E-08 ::D ESE 3.747E-06 l.208E-06 6.353E-07 4.046E-D7 2.137E-07 l.356E-07 9.516£-08 7.118£-08 5.564£-08 4.494£-08 3.721£-08 -i CD SE 4.283£-06 l.371E-06 7.191E-07 4.568E-07 2.408E*07 1.527£-07 1.071£-07 8.007£-08 6.259E-08 5.054£-08 4 184f-08 )>

w SSE 4.813£-06 l.535E-06 8.080£-07 5.165E-07 2.742£-07 1.748[-07 1.231£-07 9.235[-08 7.239£-08 5.859£-08 4 861f-08 CCI ~:

O> r- 0 m ::::J ANNUAL AVERAGE CHI/Q (SEC/HETER CUBED) DISTANCE IN HILES FRotl THE SITE .....

SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50 000 ..... .....

5 3.ZDOE-08 l.710£-08 l.090E-08 5.742£-09 3.625£-09 2.525£-09 1.873[~09 l.450E-09 l.159E-09 9.490t-IO 1.920E-10 w

SSW 2.630£-08 1.417£-08 9.082£-09 4.821£-09 3.059£-09 2.139£-09 1.591[-09 1.235£-09 9.896E-10 8.ll8E-IO 6.786£-10 SW 3.410E-08 1.850£-08 1.191£-08 6.366E-09 4.057£-09 2.847£-09 2.123£-09 l.652E-09 1.325£-09 1.088£-09 9.109£-10 WSW 3.461£-08 1.904£-08 l.238E-08 6.709E-09 4.318£-09 3.053£-09 2.292£-09 l.792E-09 l.445E-09 l.192E-09 l.OOIE-09 w 4.0Z7E-08 2.212£-08 1.437£-08 7.780E-09 5.007E-09 3.541£-09 2.658E-09 2.079E-09 l.677£-09 1.364£-09 1.163£-09 WIN 5.274E-08 2.896£-08 l.882E-08 1.019E-08 6.559E-09 4.640£-09 3.484£-09 2.727E-09 2.200E-09 1.816£-09 1.527£-09 HW 7.002£-08 3.876£-08 2.532£-08 1.381£-08 8.931£-09 6.340E-09 4.775£-09 3.745£-09 3.027£-09 2.SOJE-09 2.108£-09 9.171£-08 5.100£-08 3.342£-08 1.831£-08 1.l88E-08 8.451E-09 6.377£-09 5.0llE-09 4.057£-09 3.359E-09 2.832£-09 )>

""'N 9.420E-08 5.ZZZE-08 3.415E-08 l.864E-08 l.Z07E-08 8.569E-09 6.456£-09 5.066f-09 4.096E-09 3.388£-09 2.854[-09 r-HNE 4.768£-08 2.598E-08 1.678£-08 9.009E-09 5.762E-09 4.056E-09 3.033£-09 2.366E-09 1.903£-09 l.567E-09 1.314[-09 NE 4.335£-08 2.291E-08 1.449£-08 7.557E-09 4.744E-09 3.292£-09 2.434£-09 l.880E-09 l.499E-09 l.225E-09 1.021[-09 ENE 3.048E-08 l.816E-08 l.024E-Q8 5.362£-09 3.375£-09 2.347E-09 1.738£-09 1.344(-09 1.073£-09 8.783E-10 7.327E-10 E 3.076£-08 l.615E-D8 1.016£-08 S.266E-09 3.292£-09 2.277£-09 l.679E-09 l.294E-09 l.030E-09 8.403E-10 6.992£-10 ESE 3.143E-08 l.647E-08 l.036f-08 5.362£-09 3.352E-09 Z.319E-09 1.711£-09 l.319E-09 1.051E-09 8.SBIE-10 7.145E-10 SE 3.534E-08 1.853£-08 1.165£-08 6.040£-09 3.779£-09 2.616E-09 1.931[-09 l.490£-09 l.18BE-09 9.703E-10 8.083E-IO SSE 4.ll4E-08 2.171E-08 1.371£-08 7.146£-09 4.485£-09 3.llZE-09 Z.301£-09 1.777£-09 1.418£-09 l.159E-09 9.660f-10 VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS) 58.10 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (METERS) 0.00 BUILDING HEIGHT (MEHRS) se .1 EXIT VELOCITY (HEfERSJ 0.00 BLO.G. Hltl. CRS. SEC. AREA (SQ.HEHRS) 2000.0 HEAT EHISSlON RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.

USNRC COMPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE: 931116

- - - - PALISADES XOQDOQ8Z ***** USING 01/01/BB - 12/31/92 MET DATA *****

GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING 8.000 DAY DECAY. DEPLETED CHl/Q (SEC/HETER CUBED) FOR EACH SEGMENT SEGMENT BOUNDARIES IN MILES FROM THE SITE DIRECTION .5-l l-2 2-3 3-4 4-5 5-10 10-20 20-30 30-110 40-50 :u FROM SITE (1)

~

s 6.0&0E-07 2.097E-07 9.418E-08 5.586£-08 3.780E-08 l. 766E-08 5.9-HE-09 2.557E-09 1.460E-09 9. 531 [-10 <

u;*

w SSW 4.842£-07 l.678£-07 7 .621[-08 4.555£-08 3.099E-D8 l.46DE-08 4.985E-09 2 .165[-09 1.243E-09 c;*

...... 6.243E-07 B 151[-LO SW 2.144E-07 9.769E-08 5.870E-OB 4.DllE-08 1. 904E-08 6.573E-09 Z.880E-09 I. 662E -09 l.093E-09 :I WSW 6.16SE-07 2.096E-07 9.670E-08 5.883£-08 4.056E-08 1.954£-08 6.907E-09 3.086[-09 l.803[-09 1. 196£-09 ...a.

w 7.287E-07 2.46ZE-D7 l.130E-07 6.860£-08 4 .12ZE-DB Z.Zllf-08 8.DlZE-09 3.578[-09 2.091£-09 1.389£-09 ...a.

WNW 9.547E-07 3.227£-07 1.481E-07 8.985£-08 6.184[-08 2.974[-08 l. 049£-08 4.689E-09 2.743[-09 l. 823£-09 IHI 1. 232E-06 4.173£-07 1.935£-01 l.183£-07 8.190[-08 3.974E-08 I. 420E-08 6.405£-09 3.766E-09 2.512E-09

1. 598E-06 5.398E-07 1.543[-07 1. 881E-08 8.535E-09 z "tJ r-

""" M 1.644£-06 NKE 8.577E-D7 5.584[-07 2.960[-07 2.513£-07 2.595E-D7 1.356[-07 l.S90E-07 8.178[-08 1.071£-07

l. lOlE-07 S.603E-08 5.223E*08 5.351E-08 2.671E-08 1.916E-08 9.293£-09 8.656[-09 4.102E-09 5.038[-09 5.094E-09 2.380[-09 3.371E-09 3.400E-09

l. 573[-09

~ )>

)> z NE 8.6!i7E-07 2.961E-07 1.306[-07 7.658E-08 5 .139£-08 2. 37lE-08 7.847E-09 3.336E-09 l .893E-09 1. 231£-09 z -f ENE 6.089E-07 2.072E-07 9.154£-08 S.373E-OB 3.611[-08 1. 671E-08 5.563£-09 2 .377E-09 1. 353E-09 8.822[-10 c E 6.34DE-07 2.147£-07 9.389E-08 5.470£-08 3.654E-08 1. 673E-OB 5.476E-09 2.308[-09 1.303[-09 8.442£-10 )>

r-ESE 6.599£-07 2.214E-07 9.635[-08 5.600E-OB 3.736[-08 1. 708E-08 5.579£-09 2.351[-09 1 329[-09 8.620[-10 SE 7.473£-07 2.496E-07 1.084£-07 6.299E-08 4.201[-08 1.921£-08 6.262£-09 2.652E-09 1.501[-09 9. 747E-10 SSE 8.400E-07 2.838£-07 l.246E-07 7.284E-08 4.880[-08 2.247[-08 7.423E-09 3. l 54E-09 I . 790£-09 l. 164E -09

USNRC COMPUTER CODE - XOQOOQ, VERSION 2.0 RUN DATE: 931115

- - - - PALISADES XDQOOQ82 ***** USING 01/01/88 - 12/31/92 HET DATA *****

GROUND LEVEL RELEASE - TOP OF CONTAINMENT OUILDING

- - - - RELATIVE DEPOSITION PER UNIT AREA (M**-2) AT FIXED POINTS BY DOWNWIND SECTORS DIRECTION DISTANCES JN MILES FROM SITE 0.25 0.50 0.75 1.00 1.50 2.00 2.50 3.00 3.50 4.00 4 50 S 2.434E-08 8.230£-09 4.225£-09 2.S9SE-09 1.294£-09 7.845£-10 S.304E-10 3.844£-10 2.923E-IO 2 303E-IO l.864f-ID SSW 1.655£-08 5.596£-09 2.873£-09 1.764£-09 8.795E-10 5.334£-10 3.607E-10 2.614£-10 l.987£-10 1 .566E-10 1.267E-IO 0 SW 1.921E-08 6.497£-09 3.336E-09 2.048£-09 1.021£-09 6.193£-10 4.187£-10 3.034£-10 Z.307£-10 1.818£-10 l.472E-IO "11 WSW 1.805£-08 6.105£-09 3.135£-09 1.925£-09 9.596£-10 5.820E-10 3.935£-10 2.851E-10 Z.168£-10 l.708£-10 1.383E-10 "11 W 2.419E-08 8.181£-09 4.200£-09 2.579£-09 1.286£-09 7.799£-10 5.273£-10 3.821£-10 Z.905E~l0 Z.289£-10 l.853E-IO WNW 3.615£-08 1.222£-08 6.277£-09 3.854£-09 1.921£-09 1.165£-09 7.879£-10 5.710£-10 4.341£-10 3.420£-10 2.769£-10 NW 4.Z98f-08 1.454£-08 7.483£-09 4.583£-09 2.285£-09 1.386£-09 9.369E-10 6.789£-10 5.162E-l0 4.067E-10 3.292£-10 HNW 5.435E-08 1.838£-08 9.436E-09 5.794£-09 2.889£-09 1.752£-09 1.185E-09 6.584E-IO 6.527E-10 5.142E-10 4.163E-1D H 4.898E-08 l.656E-08 8.504E-09 5.222E-09 2.603E-09 l.579E-D9 1.067£-09 7.735£-10 5.882E-10 4.634E-10 3.751E-10 NNE 2.933E-08 9.919E-09 5.093E-09 3.127E-09 1.559E-09 9.456E-10 6.393E-10 4.633E-IO 3.523£-10 Z.775E-10 2.247£-10 NE 4.672[-08 l.580E-08 8.llZE-09 4.981[-09 2.483E-09 1.506£-09 1.018£-09 7.379£-10 5.611£-10 4.420£-10 3.578E-IO ENE 3.456£-08 l.169E-08 6.00DE-09 3.684(-09 l.837E-09 1.114£-09 7.532£-10 5.458E-10 4.150£-10 3.270£-10 2.647E-10 ~)>

(,.) E 3.701£-08 l.251£-08 6.425£-09 3.945(-09 l.967E-09 1.193£-09 8.065£-10 5.844E-l0 4.444E-l0 3.SOIE-10 2.834[-IO CX> ESE 4.171[-08 l.410E-08 7.242£-09 4.447£-09 2.217E-09 1.345(-09 9.091E-10 6.588E-10 5.009£-10 3.946£-10 3.195E-10 ~

SE 5.332£-08 1.803£-08 9.258£-09 5.685£-09 2.834E-09 l.719£-09 l.162E-09 8.421E-10 6.404£-10 5.045£-10 4.084£-10 SSE 5.156£-08 1.743£-08 8.951£-09 5.496£-09. 2.740£-09 1.662£-09 l.l24E-09 B.142£-10 6.191£-10 4.878f-10 3.949£-10 ~. ~

~

DIRECTION DISTANCES IN MILES FROM SITE 5.00 7.50 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 S l.542E-10 7.556E-ll 4.741E-ll 2.396E-11 l.45DE-ll 9.725£-12 6.968£-12 5.233E-12 4.068E-12 3.250f-12 2.653E-12 SSW l.048E-10 5.138E-ll 3.224E-ll 1.629£-11 9.862E-12 6.613£-12 4.738f-12 3.558£-lZ Z.766£-12 2 ZIOE-ll 1.804£-12 SW l.217E-1D 5.965E-ll 3.743E-ll l.892E-ll l.145E-ll 7.677£-12 5.501E-12 4.131E-12 3.212E-12 2.566E-ll 2.094£-12 WSW l.144E-10 5.605E-ll 3.517£-11 l.778E-ll 1.076£-11 7.214£-12 5.169£-12 3.882E-1Z 3.018£-12 2.4llf-1Z l.968E-12 W 1.533£-10 7.SllE-11 4.713E-ll Z.38ZE-ll *1.442£-11 9.667£-12 6.927E-l2 5.201E-12 4.044E-12 3 23lf-1Z 2.637E-l2 )>

WNW 2.290E-10 l.12ZE-10 7.043£-11 3.560E-11 2.155£-11 1.445[-ll l.035E-ll 7.773E-12 6.043E-l2 4.827E-12 3.'940E-12 r-NW Z.723E-10 l'.335E-10 8.374E-ll 4.233£-11 Z.56ZE-11 1.718[-11 l.231E-ll 9.242£-12 7.166[-12 5.740£-12 4.685£-12 HNW 3.443£-10 1.687£-10 l.059E-10 5.352E-ll 3.239£-11 2.172£-11 1.556£-11 1.169£-11 9.086£-12 7.258£-12 5.924£-12 N 3.103£-10 l.521E-10 9.542E-11 4.823E-ll Z.919£-11 l.957E-11 l.402f-ll l.05JE-11 8.188E-12 6.540E-12 5.338£-12 HNE l.858E-l0 9.107E-ll 5.714[-ll Z.888£-11 l.748E-ll 1.172£-11 8.399E-12 6.306£-12 4.903[-12 3.917E-12 3.197E-12 NE 2.960E-l0 1.451£-10 9.102E-ll 4.600E-ll 2.784E-ll l.867£-11 1.338£-11 l.OD4E-11 7.810[-12 6.239E-12 S.092E-12 ENE 2.190£-10 1.073£-10 6.733£-11 3.403£-11 Z.060£-11 1.361£-11 9.695£-12 7.430£-12 5.777£-12 4.615E-12 3.767£-12 E 2.345£-10 l.149E-10 7.209£-11 3.644£-11 2.205£-11 1.479£-11 l.060E-ll 7.956£-12 6.lBGE-12 4.942[-12 4.033£-12 ESE 2.643E-10 1.295£-10 8.126E-ll 4.107E-ll 2.486E-ll 1.667£-11 l.194E-ll B.96BE-12 6.973E-12 5.570[-12 4.546[-12 SE 3.378E-IO 1.656£-10 l.039E-10 5.251£-11 3.178£-11 2.131£-11 l.527E-ll l.146E-11 8.914E*l2 7.120E-12 5.812£-12 SSE 3.266[-10 1.601E-l0 1.004[-10 5.077£-11 3.073E-11 2.060£-11 l.476£-11 l.lOBE**ll 8.619[*12 o 885£-12 ~.619£-12

USNRC COMPUTER CODE - XOQOOQ. VERSION 2.0 RUM DATE: 931116

- - - - PALISADES XOODOQ82 ***** USING 01/01/88 - 12/31/92 MET DATA *****

GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING aataw*aaawA************* RELATIVE DEPOSITION PER UNIT AREA (M**-2) BY OOWNWINO SECTORS **************~*-**~~*~*

SEGMENT BOUNDARIES IN HILES DIRECTIOK .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30*40 40-50 FROM SITE s 4.391E-09 l.356E-09 5.398E-10 Z.95DE-10 1.875E-10 8.053E-ll Z.497E-ll 9. 697E-12 5 265£-12 3 .271E-12 SSW 2.985E-09 9.223[-10 J.670E-10 z. 006[-10 1.275[-10 5.475E-11 l.698£-11 6.729E-12 3.594E-12 2.224E-l2 SW 3.466[-09 1.071E-09 4.261[-10 2.328£-10 l.480E-10 6.357E-ll l.971E-ll 7 .IHJE-12* 4.172£-12 2. 582E-12 :a WSW 3.257E-09 1.006[-09 4.004[-10 2.188£-10 l.391E-10 5.974[-ll l.852E-ll 7.342E-12 3.921[-12 2 427E-12 (I) 4.364£-09 l.348[-09 5.366E-10 Z.932E-10 l.B64E-10 8.005[-ll 2.482E-ll 9.83BE-12 5.254£-12 3.252E-12

-i s.

w

<O WNW" NW 6.52ZE-09 7.755E-09 2.0l!iE-09 2.396E-09 8.018E-10 9.533E-10 4.381E-10 5.210[-10 2.785[-10 l.196E-10 . 3.709E-ll 3.311E-10 l. 422£-10 4 .410E-ll l.470E-11 L.748E-11 7 .851£-12 9.335E-12

4. 859E-12

5. 718f- l 2

)>

co r-m 0

J 0 NNW 9.805E-09 3.029E-09 l.ZO!iE-09 6.587E-10 4.187[-10 l. 798£-10 5.576E-ll 2.210E-11 1.180£-11 7.305[-12 ...a.

r

...a. )> )>

8.836£-09 2.730£-09 l.086f-09 5.936E*:JO 3.773E-10 l.621E-10 5.025E-ll l.992E-ll I. 064E- ll 6. 583E -12 ...a.

MME" NE 5.292E-09 8.42BE-09

1. 635E-09 2.604E-09 6.505E-10 l.036E-09 3.555[-10 5.662£-10 2.259E-10 9.705E-ll 3.0lOE-11 3.599E-10 I. 546E- l 0 4.794E-ll

1. 193E-ll

1. 900E-ll 6.370£-12 I. 015£-11 3.943E-l2 li.2110E-12 c...> :j :a 0 -a ENE 6.235(-09 l .926E-:09 7.665E-10 4.188£-10 2.662£-10 l.143E-10 3.546£-11 l. 405E-l 1 7.505£-12 4.645E-l2 z r-E 6.676[-09 2.063E-09 8.207E-10 4.485E-10 2 .851£-10 l.224E-10 3.797E-ll I. 505E-ll

1. 696E-l l 8.036[-12 9.058£-12 4.974E*12 s:: )>

)> z ESE 7.525£-09 2.325E-09 9.251E-10 5.055£-10 3.213£-10 l.360£-10 4.260E-ll 5.606E-12 SE 9.619£-09 2.972£-09 l.183[-09 6.462£-10 4 .107E-l O 1. 764E-10 5.471E-11 2 168E-ll I .158£-11 7.l67E*l2 z -i SSE 9.301[-09 2.873£-09 1.143[-09 6.246E-JO 3.971£-10 l. 706[-10 5. 290[-ll 2.097£-11 1.120[-ll 6 930E-12 c

)>

VENT AND BUILDING PARAMETERS: r-RELEASE HEIGHT (METERS) 58.10 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (METERS) Q_QO BUILDING HEIGHT (METERS) 58. l EXIT VELOCITY (METERS) 0.00 BLOG.MIH.CRS.SEC.AREA (SQ.METERS) 2000.0 HEAT EMISSION RATE (CAL/SEC) 0.0 ALL GROUND LEVEL RELEASES.

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

~----------------- TABLE 1 .4 1995 PALISADES LAND USE CENSUS 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 > 5 mi > 5 mi > 5 mi NNE 1I1 mi 1.6 mi > 5 mi > 5 mi > 5 mi NE 1.2 mi 1.2 mi 2.9 mi > 5 mi 3.2 mi ENE 1 .3 mi 2.7 mi 4.0 mi > 5 mi > 5 mi

., E 1.0 mi 1.5 mi 3.5 mi > 5 mi > 5 mi r

ESE 1.0 mi 2.3 mi *4.0 mi > 5 mi 3.0 mi

... I SE 1.0 mi 1 .8 mi *4.0 mi 4.3 mi > 5 mi SSE 0.7 mi 1 .6 mi 4.8 mi > 5 mi 5.0 mi s 0.5 mi 1.5 mi > 5 mi > 5 mi 4.7 mi SSW 0.7 mi > 5 mi > 5 mi > 5 mi > 5 mi I *Note: Farm bisected by ESE/SE boundary line .

40

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

TABLE 1 .4a 1994 PALISADES LAND USE CENSUS Critical Receptor Items Distance Sector (Miles} Location/Description Item

X/Q (sec/m 3 l SSE 0.48 Site Boundary N/A 1. 79E-6 s 0.50 Residence, Palisades Park; Residence 1.20E-06 1 /2 mile West of 29th Avenue and Blue Star intersection NE 1.2 L Swetay, Rt 3, Box 133 Garden 4.69E-07 Blue Star Hwy, East side !'

NE SE

.... 'i L..

4.

18847 M-140, 0.25 miles N of 20th, West side of road 72401 36th Ave Beef Cattle Dairy Cow 1.30E-07 5.94E-08 If' I~

I ...!.

NE 3.2 C Bernt Goat 1.32E-07 18019 M-140

Based on Palisades 5-year composite meteorological data, 1 988-1 992 .

- 41

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL

,.,.._..____________ Revision 11 TABLE 1.5 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES*

DFR 1 DFY 2 DFS 1 DFB 2 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) r'

X~-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)

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 µCi/m 3

2. mrad/y per µCi/m 3

3. 1.17(+3) = 1.17x 0 3

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

42

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

TABLE 1.6 STABLE ELEMENT TRANSFER DATA Fm - MILK (COW) Fm - MILK (GOAT) F1 - MEAT Biv ELEMENT IDAYS/Ll lDAYS/Ll IDAYS/KGl (VEG/SOILl H 1 .OE-02 1. 7E-01 1 .2E-02 4.SE-00 c 1 .2E-02 1.0E-01 3.1E-02 5.5E-OO Na 4.0E-02 A.OE-02 3.0E-02 5.2E-02 p 2.5E-02 2.5E-01 4.6E-02 1. 1E-00 Cr 2.2E-03 2.2E-03 2.4E-03 2.5E-04 Mn 2.5E-04 2.5E-04 8.0E-04 2.9E-02 Fe 1 .2E-03 1.3E-04 4.0E-02 6.6E-04 Co 1 .OE-03 1.0E-03 1.3E-02 9.4E-03 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 3.0E-02 3. 1 E-02 1.3E-01 !'

Sr 8.0E-04 1.4E-02 6.0E-04 1. 7E-02 y 1 .OE-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 4.0E-01 5.0E-02 Rh 1.0E-02 1.0E-02 1.5E-03 1.3E+01 Ag 5.0E-02 5.0E-02 1. 7E-02 1.5E-01 Te 1 .OE-03 1.0E-03 7. 7E-02 1 .3E-OO I 6.0E-03 6.0E-02 2.9E-03 2.0E-02 Cs 1.2E-02 3.0E-01 4.0E-03 1 .OE-02 Ba 4.0E-04 4.0E-04 3.2E-03 5.0E-03 La 5.0E-06 5.0E-06 2.0E-04 2.5E-03 Ce 1.0E-04 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 NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

-**~

TABLE 1.7 INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOT AL BODY THYROID KIDNEY LUNG Gl-LLI H3* 0. 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 BE10 9.49E-04 1.2SE-04 2.6SE-OS 0. 0. 1.49E-03 1.73E-OS C14 1 .89E-OS 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. 0. 0. 6.10E-07 NA22 7.37E-OS 7.37E-OS 7.37E-OS 7.37E-OS 7.37E-OS 7.37E-OS 7.37E-OS NA24 7 .S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 7.54E-06 P32 1.4SE-03 8.03E-OS S.S3E-OS 0. 0. 0. 1.1SE-05 AR39 0. 0. 0. 0. 0. 1.00E-08 0.

AR41 0. 0. 0. 0. o. 3.14E-08 0.

CA41 7A8E-OS 0. 8.16E-06. 0. 0. 6.94E-02 2.96E-07 SC46 3.7SE-04 S.41 E-04 1.69E-04 0. 3.S6E-04 0. 2.19E-OS CRS1 0. 0. 6.39E-08 4.11 E-08 9.4SE-09 9.17E-06 2.SSE-07 MNS4 0. 1.81 E-OS 3.S6E-06 0. 3.S6E-06 7.14E-04 S.04E-06 MNS6 0. 1.1 OE-09 1.SBE-10 0. 7.86E-10 8.9SE-06 S.12E-OS FESS 1.41 E-OS 8.39E-06 2.38E-06 0. o. 6.21E-OS 7.82E-07 FES9 9.69E-06 1.68E-OS 6.77E-06 0. 0. 7.2SE-04 1.77E-OS COS7 0. 4.6SE-07 4.SSE-07 0. o. 2. 71 E-04 3.47E-06 COSS 0. 8.71E-07 1.30E-06 0. 0. S.SSE-04 7.95E-06 C060 0. 5.73E-06 8.41 E-06 0. o. 3.22E-03 2.28E-OS

.Nl59 1.81E-05 5.44E-06 3.1 OE-06 0. 0. 5.48E-05 6.34E-07 N163 2.42E-04 1.46E-05 8.29E-06 o. o. 1.49E-04 1.73E-06 N165 1. 71 E-09 2.03E-10 8. 79E-11 o. 0. 5.SOE-06 3.58E-05 CU64 0. 1.34E-09 5.53E-10 0. 2.84E-09 6.64E-06 1.07E-OS ZN65 1.38E-05 4.47E-05 2.22E-05 o. 2.32E-05 4.62E-04 3.67E-05 ZN69M+D 8.98E-09 1.84E-08 1.67E-09 0. 7.45E-09 1.91 E-05 2.92E-OS ZN69 3.85E-11 6.91 E-11 5.13E-12 0. 2.87*E-11 1.05E-06 9.44E-06 SE79 o. 2.25E-06 4.20E-07 0. 2.47E-06 2.99E-04 3.46E-06 BR82 0. 0. 9.49E-06 0. 0. o. 0.

BR83+D 0. 0. 2.72E-07 o. o. 0. 0.

BR84 0. 0. 2.86E-07 o. o. 0. 0.

BR85 0. 0. 1.46E-08 0. 0. 0. 0.

KR83M 0. 0. o. o. o. 2.50E-09 o.

KR85M 0. 0. 0. o. 0. 1.31E-08 0.

KR85 0. 0. o. o. o. 1.16E-08 0.

KR87 0. 0. 0. 0. 0. 6.S9E-08 0.

KR88+D 0. 0. o. o. o. 1.38E-07 o.

KR89 0. 0. 0. 0. 0. 8.67E-08 0.

RB86 0. 1.36E-04 6.30E-05 0. o. 0. 2.17E-06 RB87 0. 7 .11 E-05 2.64E-05 o. 0. 0. 2.99E-07 ABBS 0. 3.98E-07 2.0SE-07 0. 0. 0. 2.42E-07 RB89+D 0. 2.29E-07 1.47E-07 0. 0. 0. 4.87E-08 SR89+D 2.84E-04 o. 8.1 SE-06 0. 0. 1.45E-03 4.57E-OS SR90+D 2.92E-02 0. 1.85E-03 0. 0. 8.03E-03 9.36E-05 SR91 +D 6.83E-08 0. 2.47E-09 0. 0. 3.76E-05 5.24E-05 SR92+D 7.SOE-09 0. 2.79E-10 0. 0. 1.70E-05 1.00E-04

Includes a 50% increase to account for percutaneous transpiration.

44

PALISADES NUCLEAR PLANT OFF SITE DOSE CA LC ULA TION MANUAL Revision 11

-~-------------------- TABLE 1. 7 (continued)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 2.35E-06 0. 6.30E-08 0. 0. 1 .92E-04 7 .43E-05 Y91 M +D 2.91E-10 0. 9.90E-12 0. 0. 1 .99E-06 1.68E-06 Y91 4.20E-04 0. 1.12E-05 0. 0. 1. 75E-03 5.02E-05 Y92 1.17E-08 0. 3.29E-10 0. 0. 1.75E-05 9.04E-05 Y93 1.07E-07 0. 2.91 E-09 0. 0. 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 0. 2.22E-05 1.25E-03 1.55E-05 ZR97 + D 1.07E-07 1.83E-08 8.36E-09 0. 1.85E-08 7 .88E-05 1.00E-04 N893M 1.38E-04 3.59E-05 1.15E-05 0. 3.68E-05 2.09E-04 2.47E-06 N895 1.12E-05 4.59E-06 2.70E-06 0. 3.37E-06 3.42E-04 9.05E-06 N897 2.44E-10 5.21 E-11 1.88E-11 0. 4.07E-11 2.37E-06 1.92E-05 M093 0. 6.46E-06 2.22E-07 0. 1 .54E-06 3.40E-04 3.76E-06 M099+D 0. 1.1 SE-07 2.31 E-08 0. .1.89E-07 9.63E-05 3.48E-05 TC99M 9.98E-13 2.06E-12 2.66E-11 0. 2.22E-11 5.79E-07 1.45E-06 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-13 4. l7E-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 0. 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-G'5 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+D 7.13E-06 5.16E-06 3.57E-06 0. 7 .80E-06 2.62E-03 2.36E-05 AG111 3.75E-07 1.45E-07 7. 75E-08 0. 3.05E-07 2:06E-04 3.02E-05 CD113M 0. 6.67E-04 2.64E-05 0. 5.80E-04 1.40E-03 1.65E-05 CD115M 0. 1.73E-04 6.19E-06 0. 9.41E-05 1.47E-03 5.02E-05 5N123 2.09E-04 4.21 E-06 7.28E-06 4.27E-06. 0. 2.22E-03 4.0SE-05 5N125 +D 1 .01 E-05 2.51 E-07 6.00E-07 2.47E-07 0. 6.43E-04 7.26E-05 5N126+D 8.30E-04 1.44E-05 3.52E-05 3.84E-06 0. 4.93E-03 1.65E-05 58124 2.71E-05 3.97E-07 8.56E-06 7 .18E-08 0. 1.89E-03 4.22E-05 58125+0 3.69E-05 3.41 E-07 7. 78E-06 4.45E-08 0. 1 .17E-03 1.0SE-05 58126 3.0SE-06 6.01 E-08 1.11 E-06 2.35E-08 0. 6.88E-04 5.33E-05 58127 2.82E-07 5.04E-09 8.76E-08 3.60E-09 0. 1.54E-04 3.78E~os 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 6.81E-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 TE131 M + D 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1 .89E-07 1.42E-04 8.51 E-05 TE131 + D 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 0. 2.12E-07 1130 4.54E-06 9.91 E-06 3.98E-06 1.14E-03 1.09E-05 0. 1.42E-06 1131 +D 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3. 70E-05 0. 7.56E-07

- 45

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL

., Revision 11 TABLE 1 .7 (continued)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.21 E-06 2.53E-06 8.99E-07 1.21 E-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 0. 1.54E-06 1134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0. 9.21E-07 1135 + D 2. 76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0. 1.31 E-06 XE131 M 0. 0. 0. 0. 0. 6.77E-09 0.

XE133M 0. 0. 0. 0. 0. 8.89E-09 0.

XE133 0. 0. 0. 0. 0. 7.41 E-09 0.

XE135M 0. 0. 0. 0. 0. 8.05E-09 0.

XE135 o. 0. 0. o. 0. 1.80E-08 0.

XE137 0. 0. 0. 0. 0. 8.30E-08 0.

XE138+D o. 0. 0. o. 0. 9.78E-08 0.

CS134M + D 1.32E-07 2.1 OE-07 1.11 E-07 o. 8.50E-08 2.00E-08 1.16E-07 CS134 2.83E-04 5.02E-04 5.32E-05 0. 1.36E-04 5.69E-05 9.53E-07 CS135 1.00E-04 8.66E-05 4.73E-06 o. 2.58E-05 1.01 E-05 2.18E-07 CS136 3.45E-05 9.61 E-05 3.78E-05 0. 4.03E-05 8.40E-06 1.02E-06 CS137+D 3.92E-04 4.37E-04 3.25E-05 0. 1.23E-04 5.09E-05 9.53E-07 CS138 3.61 E-07 5.58E-07 2.84E-07 o. 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 BA139 1.06E-09 7 .03E-13 3.07E-11 0. 4.23E-13 4.25E-06 3.64E-05 BA140+D 4.00E-05 4.00E-08 2.07E-06 o. 9.59E-09 1.14E-03 2.74E-05

BA141 +D 1.12E-10 7. 70E-14 3.55E-12 o. 4.64E-14 2.12E-06 3.39E-06 BA142+D 2.84E-11 2.36E-14 1.40E-12 o. 1.36E-14 1.11 E-06 4.95E-07 LA140 3.61 E-07 1.43E-07 3.68E-08 o. 0. 1.20E-04 6.06E-05 LA141 4.85E-09 1.40E-09 2.45E-10 0. 0. 1.22E-05 5.96E-05 LA142 7.36E-10 2.69E-10 6.46E-11 0. 0. 5.87E-06 4.25E-05 CE141 1.98E-05 1.19E-05 1.42E-06 0. 3.75E-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 8.65E-04 1.26E-04 o. 3.84E-04 7.03E-03 1.06E-04 PR143 1.00E-05 3.74E-06 4.99E-07 o. 1.41 E-06 3.09E-04 2.66E-05 PR144 3.42E-11 1.32E-11 1.72E-12 o. 4.80E-12 1.15E-06 3.06E-06 ND147+D 5.67E-06 5.81 E-06 3.57E-07 o. 2.25E-06 2.30E-04 2.23E-05 PM147 3.91 E-04 3.07E-05 1.56E-05 o. 4.93E-05 4.55E-04 5.75E-06 PM148M+D 5.00E-05 1.24E-05 9.94E-06 o. 1.45E-05 1.22E-03 3.37E-05 PM148 3.34E-06 4.82E-07 2.44E-07 o. 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 o. 1.30E-08 3.25E-05 2.58E-05 SM151 3.38E-04 6.45E-05 1.63E-05 0. 5.24E-05 2.98E-04 3.46E-06 SM153 1.53E-07 1.18E-07 9.06E-09 o. 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 0. 1.58E-04 5.20E-04 5.19E-05 EU156 1.56E-05 9.59E-06 1.54E-06 o. 4.48E-06 6.12E-04 4.14E-05 TB160 1.12E-04 0. 1.40E-05 o. 3.20E-05 1.11 E-03 2.14E-05 H0166M 1.45E-03 3.07E-04 2.51 E-04 0. 4.22E-04 2.05E-03 1.65E-05 W181 4.86E-08 1.46E-08 1.67E-09 o. 0. 1.33E-05 2.63E-07 W185 1.57E-06 4.83E-07 5.58E-08 o. 0. 4.48E-04 1.12E-05

W187 9.26E-09 6.44E-09 2.23E-09 46

o. 0. 2.83E-05 2.54E-05

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

LIVER TABLE 1. 7 (continued)

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

ISOTOPE BONE TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210+ D 8.62E-02 2.02E-02 3.43E-03 0. 6.85E-02 1. 76E-01 3.79E-05 81210+0 0. 1.33E-05 1.18E-06 0. 1.03E-04 9.96E-03 3.27E-05 P0210 2.98E-03 5.63E-03 7.12E-04 0. 1.30E-02 2.40E-01 4.36E-05 RN222+0 0. 0. 0. 0. 0. 9.88E-06 0.

RA223+0 1.56E-03 2.26E-06 3.12E-04 0. 4.16E-05 2.25E-01 3.04E-04 RA224+0 1.77E-04 4.00E-07 3.54E-05 0. 7.30E-06 7.91E-02 3.42E-04 RA225 +D 2.57E-03 2.88E-06 5.13E-04 0. 5.31E-05 2.57E-01 2.87E-04 RA226+0 2.48E-01 1.46E-05 2.05E-01 0. 2.94E-04 7.83E-01 3.05E-04 RA228+0 1.60E-01 7.61 E-06 1.SOE-01 0. 1.53E-04 1.09E-OO 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+D 5.29E+OO 8.76E-01 3.28E-01 0. 1.86E-01 1.62E+OO 5.27E-05 TH227+0 1.82E-03 3.03E-05 5.24E-05 0. 1.13E-04 3.27E-01 3.53E-04 TH228 + D 8.46E-01 1.1 OE-02 2.86E-02 0. 5.61 E-02 4.65E+OO 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+OO 1. 79E-01 9.65E-02 0. 8.82E-01 2.18E+OO 3.87E-05 TH232 + D 3.86E+OO 1.53E-01 2.29E-01 0. 7.54E-01 2.09E+OO 3.29E-05 TH234 1.33E-05 7.17E-07 3.84E-07 0. 2.70E-06 1.62E-03 7.40E-05 PA231 +D 9.10E+OO 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+OO 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 o. 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 U236 5.01 E-02 o. 3.60E-03 o. 1.03E-02 3.35E-01 3.71E-05 U237 3.25E-07 0. 8.65E-08 0. 8.0SE-07 9.13E-05 1.31E-05 U238+D 4.79E-02 0. 3.29E-03 0. 9.40E-03 3.06E-01 3.54E-05 NP237+D 3.03E+OO 2.32E-01 1 .~6E-01 0. 7.69E-01 3.49E-01 5.10E-05 NP238 2.67E-06 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+OO 6.33E-01 1.27E-01 0. 4.64E-01 9.03E-01 4.69E-05 PU239 5.50E+OO 6.72E-01 1.34E-01 0. 4.95E-01 8.47E-01 4.28E-05 PU240 6.49E+OO 6.71E-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+OO 6.47E-01 1.29E-01 0. 4. 77E-01 8.15E-01 4.20E-05 PU244 5.95E+OO. 7.40E-01 1.48E-01 0. 5.46E-01 9.33E-01 6.26E-05 AM241 1.84E+OO 8.44E-01 1.31E-01 0. 7.94E-01 4.06E-01 4.78E-05 AM242M 1.90E+OO 8.24E-01 1.35E-01 0. 8.03E-01 1.64E-01 6.01 E-05 AM243 1.82E+OO 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 5.1 OE-05 CM243 1.73E+OO 7.94E-01 1.06E-01 0. 3.91 E-01 4.24E-01 5.02E-05 CM244 1.43E+OO 7.04E-01 8.89E-02 0. 3.21E-01 4.0SE-01 4.86E-05 CM245 2.26E+OO 8.BOE-01 1.36E-01 0. 5.23E-01 3.92E-01 4.53E-05 CM246 2.24E+OO a.79E-01 1.36E-01 o. 5.23E-01 3.99E-01 4.45E-05 CM247+D 2.18E+OO 8.64E-01 1.33E-01 0. 5.15E-01 3.92E-01 5.85E-05 CM248 1.82E+01 7.12E+OO 1.10E+OO 0. 4.24E+OO 3.23E+OO 9.43E-04 CF252 4.26E+OO 0. 1.01 E-01 0. 0. 1.37E+OO 1.85E-04

47

eALISADES NUQLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11 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. 0. 7.41 E-04 1.72E-05 C14 9. 70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 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. 1.85E-07 0. 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 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.~SE-06 P32 7.04E-04 3.09E-05 2.67E-05 o. 0. 0. 1.14E-05 AR39 0. 0. 0. 0. o. 4.89E-09 0.

AR41 0. 0. 0. o. 0. 1.68E-08 0.

CA41 7.06E-05 0. 7.70E-06 o. o. 7.21E-02 2.94E-07 SC46 1.97E-04 2.70E-04 1.04E-04 o. 2.39E-04 0. 2.45E-05 CR51 0. 0. 4.17E-08 2.31E-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 o. 4.52E-10 3.55E-06 3.33E-05 FESS 1.28E-05 6.SOE-06 2.1 OE-06 0. o. 3.00E-05 7.75E-07 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 o. 0. 1.37E-04 3.58E-06 C058 o. 4.79E-07 8.55E-07 o. o. 2.99E-04 9.29E-06 C060 0. 3.55E-06 6.12E-06 o. 0. 1.91 E-03 2.60E-05

N159 1.66E-05 4.67E-06 2.83E-06 o. 0. 2.73E-05 6.29E-07 N163 2.22E-04 1.25E-05 7.56E-06 o. 0. 7.43E-05 1. 71 E-06 N165 8.0SE-10 7.99E-11 4.44E-11 o. o. 2.21 E-06 2.27E-05 CU64 o. 5.39E-10 2.90E-10 0. 1.63E-09 2.59E-06 9.92E-06 ZN65 1.15E-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 o. 4.22E-09 7.36E-06 2.71 E-05 ZN69 1.81E-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. 0. 5.66E-06 o. o. 0. o.

BR83+D 0. 0. 1.28E-07 o. 0. 0. 0.

BR84 o. 0. 1.48E-07 o. o. o. 0.

BR85 o. 0. 6.84E-09 o. 0. o. 0.

KR83M o. 0. o. o. o. 1.22E-09 0.

KR85M o. 0. o. o. o. 6.SSE-09 o.

KR85 0. 0. 0. o. o. 5.66E-09 0.

KR87 0. o. o. 0. o. 3.38E-08 0.

KR88+D o. 0. 0. 0. o. 6.99E-08 0.

KR89 o. 0. o. o. o. 4.55E-08 0.

RB86 o. 5.36E-05 3.09E-05 o. 0. o. 2.16E-06 RB87 o. 3.16E-05 1.37E-05 o. o. 0. 2.96E-07 RB88 0. 1.52E-07 9.90E-08 o. 0. 0. 4.66E-09 RB89+D o. 9.33E-08 7.83E-08 o. 0. 0. 5.11E-10 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 SR92+D 3.54E-09 0. 1.42E-10 o. o. 6.49E-06 6.55E-05

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

48

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

BONE LIVER TABLE 1. 7 (contd)

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

ISOTOPE TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 1. 11 E-06 0. 2.99E-08 0. 0. 7.07E-05 7 .24E-05 Y91 M+D 1.37E-10 0. 4.98E-12 0. 0. 7.60E-07 4.64E-07 Y91 2.47E-04 0. 6.59E-06 0. 0. 7.1 OE-04 4.97E-05 Y92 5.50E-09 0. 1.57E-10 0. 0. 6.46E-06 6.46E-05 Y93 5.04E-08 0. 1.38E-09 0. 0. 2.01 E-05 1.05E-04 ZR93 +D 2.07E-04 7.BOE-05 5.55E-05

0. 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 N893M 1.27E-04 3.17E-05 1.04E-05 0. 3.44E-05 1.04E-04 2.45E-06 N895 6.35E-06 2.48E-06 1. 77E-06 0. 2.33E-06 1.66E-04 1.00E-05 N897 1.16E-10 2.0BE-11 9.74E-12 0. 2.31 E-11 9.23E-07 7.52E-06 M093 0. 3.76E-06 1.35E-07 0. 1.06E-06 1. 70E-04 3.78E-06 M099+D 0. 4.66E-08 1.15E-08 0. 1.06E-07 3.66E-05 3.42E-05 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. 1. 75E-06 3.37E-04 7.75E-06 TC101 2.19E-14 2.30E-14 2.91 E-13 0. 3.92E-13 1.58E-07 4.41 E-09 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 0. 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

PD107 0. 2.65E-07 2.51E-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 4.56E-06 3.0BE-06 2.47E-06 0. 5.74E-06 1.48E-03 2.71E-05 AG111 1.81E-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 o. 7.88E-05 3.39E-06 0. 5.93E-05 5.86E-04 4.97E-05 5N123 1.29E-04 2.14E-06 4.19E-06 2.27E-06 o. 9.59E-04 4.05E-05 5N125 + D 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0. 2.43E-04 7.17E-05 5N126 +D 6.23E-04 1.04E-05 2.36E-05 2.84E-06 0. 3.02E-03 1.63E-05 58124 1.55E-05 2.00E-07 5.41 E-06 3.41 E-08 0. 8.76E-04 4.43E-05 58125+0 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0. 6.27E-04 1.09E-05 58126 1. 72E-06 2.62E-08 6.16E-07 1.00E-08 0. 2.86E-04 5.67E-05 58127 1.36E-07 2.09E-09 4.70E-08 1.51 E-09 0. 6.17E-05 3.82E-05 TE125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0. 1.29E-04 9.13E-06 TE127M +D 6.72E-06 2.31 E-06 8.16E-07 1.64E-06 1. 72E-05 4.00E-04 1.93E-05 TE127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91 E-09 2.71E-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 9.45E-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 1.0BE-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 TE132+D 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 1.01E-10 1.60E-06 4.77E-06 TE134+D 1.53E-11 8.81 E-12 9.40E-12 1.24E-11 5. 71 E-11 1.23E-06 4.87E-07 1129 1.05E-05 6.40E-06 5.71 E-06 4.28E-03 1.0BE-05 0. 2.15E-07 1130 2.21 E-06 4.43E-06 2.28E-06 4.99E-04 6.61 E-06 0. 1.38E-06 1131+0 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0. 7.68E-07

49

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

-~--------------------- TABLE 1. 7 (contd)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 5.72E-07 1.1 OE-06 5.07E-07 5.23E-05 1.69E-06 0. 8.65E-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

!135 + D 1.33E-06 2.36E-06 1 .12E-06 2.14E-04 3.62E-06 0. 1.20E-06 XE131 M 0. 0. 0. 0. 0. 3.30E-09 0.

XE133M 0. 0. 0. 0. 0. 4.36E-09 0.

XE133 0. 0. 0. 0. 0. 3.66E-09 0.

XE135M 0. 0. 0. 0. 0. 4.48E-09 0.

XE135 0. 0. 0. 0. 0. 9.09E-09 0.

XE137 0. 0. 0. 0. 0. 4.07E-08 0.

XE138+D 0. 0. 0. 0. 0. 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 0. 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 0. 2.58E-05 3.93E-06 1.13E-06 CS137 + D 2.45E-04 2.23E-04 3.47E-05 0. 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+0 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 7.41E-10

LA140 1.74E-07 6.08E-08 2.04E-08 0. 0. 4.94E-05 6.1 OE-05 LA141 2.28E-09 5.31E-10 1.15E-10 0. 0. 4.48E-06 4.37E-05 LA142 3.50E-10 1.11E-10 3.49E-11 0. 0. 2.35E-06 2.0SE-05 CE141 1.06E-05 5.28E-06 7.83E-07 0. 2.31E-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 0. 3.17E-04 3.23E-03 1.0SE-04 PR143 4.99E-06 1.50E-06 2.47E-07 0. 8.11 E-07 1.17E-04 2.63E-05 PR144 1 .61 E-11 4.99E-12 8.10E-13 0. 2.64E-12 4.23E-07 5.32E-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 0. 4.45E-05 2.20E-04 5.70E-06 PM148M+D 3.31E-05 6.55E-06 6.55E-06 0. 9. 74E-06 5. 72E-04 3.58E-05 PM148 1:61 E-06 1.94E-07 1.25E-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.SOE-05 SM151 3.14E-04 4.75E-05 1.49E-05 0. 4.89E-05 1.48E-04 3.43E-06 SM153 7.24E-08 4.51 E-08 4.35E-09 0. 1.37E-08 1.37E-05 1.87E-05 EU152 7.42E-04 1.37E-04 1.61E-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 0. 1.51E-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 0. 9.67E-06 0. 2.32E-05 5.34E-04 2.28E-05 H0166M 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 0. 0. 5.71E-06 2.61 E-07 W185 8.31 E-07 2.08E-07 2.91 E-08 0. 0. 1.86E-04 1 .11 E-05 W187 4.41 E-09 2.61 E-09 1. 17E-09 0. 0. 1 . 11 E-05 2.46E-05 50

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

ISOTOPE TABLE 1. 7 (contd)

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

BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210+D 8.03E-02 1 .85E-02 3.1 BE-03 0. 6.31E*02 8.74E-02 3.75E-05 81210+0 0. 5.11E-06 5.65E-07 0. 5.76E-05 3.70E-03 3.21E-05 P0210 1. 70E-03 2. 76E-03 4.09E-04 0. 8.85E-03 1.05E-01 4.32E-05 RN222+D 0. 0. 0. 0. 0. 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 0. 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 1.81E-03 1.87E-03 1.21E-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 0. 6.67E-05 1 .26E-01 3.49E-04 TH228 + D 8.06E-01 1 .04E-02 2. 72E-02 0. 5.41E-02 3.34E+OO 3.59E-04 TH229 1.28E+01 1.76E-01 6.31E-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+OO 1.47E-01 1.28E-01 0. 7.28E-01 1.77E+OO 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+OO 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-0,6

11 , U232+D 2.19E-01 0. 1 .56E-02 0. 1.67E-02 7.42E-01 4.33E-0'5 1.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+D 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. 7.41E-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.SOE-05 NP239 1 .26E-07 9.04E-09 6.35E-09 0. 2.63E-08 1.57E-05 1. 73E-05 PU238 4.77E+OO 6.05E-01 1.21E-01 0. 4.47E-01 6.0SE-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 2.93.E-03 0. 1. 1OE-02 5.06E-04 8.90E-07 PU242 4.85E +00 6.20E-01 1.23E-01 0. 4.60E-01 5.SOE-01 4.16E-05 PU244 5.67E+OO 7.10E-01 1.41E-01 0. 5.27E-01 6.30E-01 6.20E-05 AM241 1.74E+OO 7.85E-01 1.24E-01 0. 7 .63E-01 2.02E-01 4. 73E-05 AM242M 1.79E+OO 7.65E-01 1.27E-01 0. 7.71E-01 8.14E-02 5.96E-05 AM243 1.72E+OO 7.53E-01 1.20E-01 0. 7.42E-01 1.92E-01 5.55E-05 CM242 6.33E-02 4.84E-02 4.20E-03 0. 1.34E-02 1.31E-01 5.06E-05 CM243 1.61E+OO 7.33E-01 9.95E-02 0. 3. 74E-01 2.1 OE-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+OO 8.15E-01 1.28E-01 0. 5.03E-01 1.99E-01 4.41E-05 CM247+D 2.07E +00 8.02E-01 1.26E-01 0. 4.95E-01 1.95E-01 5.BOE-05 CM248 1.72E+01 6.61E+OO 1.04E+OO 0. 4.0SE+OO 1.61E+OO 9.35E-04 CF252 3.92E +00 0. 9.33E-02 0. 0. 6.62E-01 1.84E-04

51

PALISADES NUQl..EAR PLANT OFESITE DOSE CALQULATION MANUAL Revision 11 TABLE 1 .7 (contd)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 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 7.0SE-06 0. 0. 3.84E-04 1.77E-05 C14 3.25E-06 6.09E-07 6.0SE-07 6.0SE-07 6.0SE-07 6.0SE-07 6.09E-07 N13 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 F18 6.52E-07 o. 7. 1OE-08 0. 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. 0. 1 .16E-05 AR39 o: o. 0. o. 0. 4.00E-09 0.

AR41 0. 0. 0. 0. 0. 1 .44E-08 0.

CA41 4.0SE-05 0. 4.38E-06 0. 0. 1.01 E-01 3.03E-07 SC46 7.24E-05 1.41 E-04 4. 1SE-05 0. 1 .35E-04 o. 2.98E-05 CR51 0. 0. 1 .69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN54 0. 6.39E-06 1 .OSE-06 0. 1 .59E-06 2.48E-04 8.35E-06 MN56 0. 2.12E-10 3.15E-11 o. 2.24F-10 1 .90E-06 7.18E-06 FE55 4. 1 SE-06 2.98E-06 6.93E-07 0. o. 1.SSE-05 7.99E-07 FE59 1 .99E-06 4.62E-06 1 .79E-06 o. o. . 1.91 E-04 2.23E-05 C057 0. 1. 1 SE-07 1.15E-07 0. o. 7.33E-05 3.93E-06 COSS 0. 2.59E-07 3.47E-07 0. 0. 1 .68E-04 1.19E-05 C060 0. 1 .89E-06 2.48E-06 0. 0. 1 .09E-03 3.24&'05 N159 5.44E-06 2.02E-06 9.24E-07 0. 0. 1.41E-05 6.48E-07 Nl63 . 7.25E-05 5.43E-06 2.47E-06 0. 0. 3.84E-05 1. 77E-06 N165 2. 73E-10 3.66E-11 1.59E-11 0. o. 1. 17E-06 4.59E-06 CU64 o. 2.54E-10 1.06E-10 0. 8.01E-10 1 .39E-06 7.68E-06 ZN65 4.82E-06 1 .67E-05 7.SOE-06 0. 1 .OSE-05 1 .55E-04 5.83E-06 ZN69M+D 1 .44E-09 3.39E-09 3.11E-10 o. 2.06E-09 3.92E-06 2. 14E-05 ZN69 6.04E-12 1.15E-11 8.07E-13 0. 7.53E-12 1 .98E-07 3.56E-08 SE79 o. 5.43E-07 8.71 E-08 0. 8. 13E-07 7.71E-05 3.53E-06 BR82 o. 0. 2.28E-06 0. 0. o. 0.

BR83+D 0. 0. 4.30E-08 0. o. 0. 0.

BR84 o. o. 5.41 E-08 0. o. 0. 0.

BR85 0. o. 2.29E-09 0. o. 0. 0.

KR83M o. 0. 0. 0. 0. 9.97E-1 O 0.

KRSSM . o. o. 0. 0. o. 5.46E-09 0.

KR85 o. 0. o. 0. o. 4.63E-09 0.

KR87 o. 0. 0. 0. o. 2.82E-08 0.

KR88+D o. 0. 0. 0. o. 5.81 E-08 0.

KR89 o. 0. 0. 0. 0. 3.85E-08 0.

RB86 o. 2.38E-05 1 .OSE-05 0. o. 0. 2.21 E-06 RB87 o. 1.40E-05 4.58E-06 0. 0. o. 3.0SE-07 RB88 0. 6.82E-08 3.40E-08 0. o. 0. 3.65E-15 RB89+D o. 4.40E-08 2.91 E-08 0. o. o. 4.22E-17 SR89+D 5.43E-05 o. 1.56E-06 o. 0. 3.02E-04 4.64E-05 SR90+D

1.35E-02 0. 8.35E-04 0. o. 2.06E-03 9.56E-05 SR91 +D 1. 10E-08 0. 4.39E-10 0. o. 7.59E-06 3.24E-05 SR92+D 1 .19E-09 0. 5.0SE-11 0. o. 3.43E-06 1.49E-05

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

52

PALISADES NUCLEAB PLANT

(.

OFFSITE DOSE CALCULATION MANUAL Revision 11 TABLE 1 . 7 (contd)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 3. 73E-07 0. 1.00E-08 0. 0. 3.66E-05 6.99E-05 Y91 M +D 4.63E-11 0. 1.77E-12 0. 0. 4.00E-07 3.77E-09 Y91 8.26E-05 0. 2.21 E-06 0. 0. 3.67E-04 5.11E-05 Y92 1.84E-09 0. 5.36E-11 0. 0. 3.35E-06 2.06E-05 Y93 1.69E-08 0. 4.65E-10 0. 0 .. 1.04E-05 7.24E-05 ZR93+D 6.83E-05 3.38E-05 1.84E-05 0. 1.16E-04 3.67E-04 1.60E-05 ZR95 + D 1.82E-05 5. 73E-06 3.94E-06 0. 8.42E-06 3.36E-04 1 .86E-05 ZR97 +D 1.72E-08 3.40E-09 1.57E-09 0. 5.15E-09 1.62E-05 7.88E-05 NB93M 4.14E-05 1.36E-05 3.41 E-06 0. 1.59E-05 5.36E-05 2.52E-06 N895 2.32E-06 1.29E-06 7.08E-07 0. 1.25E-06 9.39E-05 1.21 E-05 NB97 3.92E-11 9.72E-12 3.55E-12 0. 1 . 14E-11 4.91 E-07 2.71E-07 M093 0. 1.66E-06 4.52E-08 0. 5.06E-07 8.81 E-05 3.99E-06 M099+D 0. 2.11 E-08 4.03E-09 0. 5.14E-08 1.92E-05 3.36E-05 TC99M 1.73E-13 4.83E-13 6.24E-12 0. 7.20E-12 1.44E-07 7.66E-07 TC99 4.48E-08 6.58E-08 1.79E-08 0. 8.35E-07 1.74E-04 7.99E-06 TC101 7.40E-15 1.05E-14 1.03E-13 0. 1.90E-13 8.34E-08 1.09E-16 RU103 +D 2.63E-07 0. 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 0. 1.55E-06 o. 2.38E-05 2.01 E-03 1.20E-04

RH105 1.32E-09 9.48E-10 6.24E-10 0. 4.04E-09 4.09E-06 1.23E-05 PD107 0. 1.17E-07 8.39E-09 o. 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 o. 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 5.1 OE-05 SN123 4.31 E-05 9.44E-07 1.40E-06 7.55E-07 0. 4.96E-04 4.16E-05 SN125 +D 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0. 1.26E-04 7.29E-05 SN126+0 2.18E-04 5.39E-06 8.24E-06 1.42E-06 0. 1. 72E-03 1.68E-05 58124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 0. 4.81 E-04 4.98E-05 SB125 + D 9.23E-06 1.01 E-07 2.15E-06 8.80E-09 0. 3.42E-04 1.24E-05 SB126 6.19E-07 1.27E-08 2.23E-07 3.50E-09 0. 1.55E-04 6.01 E-05 SB127 4.64E*-00 9.92E-10 1.75E-08 5.21E-10 0. 3.31 E-05 3.94E-05 TE125M 6.1 OE-07 2.80E-07 8.34E-08 1. 75E-07 0. 6.70E-05 9.38E-06 TE127M+D 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127 2.51 E-10 1.14E-10 5.52E-11 1.77E-1 O 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-05 TE131 + D 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE132+D 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05 TE133M+D 1 .01 E-11 7.33E-12 5. 71 E-12 8.18E-12 5.07E-11 8. 71 E-07 1.23E-07 TE134+D 5.31 E-12 4.35E-12 3.64E-12 4.46E-12 2.91 E-11 6.75E-07 1.37E-09 1129 3.53E-06 2.94E-06 4.90E-06 3.66E-03 5.26E-06 0. 2.29E-07 1130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0. 1.14E-06 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0. 8.11 E-07 1131 + D 53

PALISADES NUQLEAR PLANT OFFSITE POSE CALCULATION MANUAL

(. Revision 11 TABLE 1. 7 (contd)

TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INHALED IN FIRST YR!

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0. 1.59E-07 1133+0 1 .52E-06 2.56E-06 7. 78E-07 3.65E-04 4.49E-06 0. 1.29E-06 1134 1 . 11 E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0. 2.55E-09 1135 + D 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1 .86E-06 0. 8.69E-07 XE131 M 0. 0. o. 0. 0. 2.70E-09 0.

XE133M 0. 0. 0. o. 0. 3.59E-09 0.

XE133 0. o. 0. 0. 0. 2.99E-09 0.

XE135M 0. 0. 0. 0. 0. 3.88E-09 0.

XE135 0. 0. 0. 0. 0. 7.55E-09 0.

XE137 0. 0. o. 0. 0. 3.33E-08 0.

XE138+D 0. 0. 0. o. o. 4.38E-08 0.

CS134M +D 2.20E-08 4.35E-OB 2.35E-08 0. 2.54E-08 4.56E-09 2.02E-08 CS134 6.28E-05 1 .41 E-04 6.86E-05 o. 4.69E-05 1.83E-05 1.22E-06 CS135 2.08E-05 1.82E-05 4.47E-06 o. 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 CS139 + D 3.65E-08 5.12E-08 1.97E-08 o. 4.34E-08 4.86E-09 1 .66E-23 BA139 1.67E-10 1.18E-13 4.87E-12 o. 1 .11 E-13 8.0SE-07 8.06E-07 BA140+D 6.84E-06 8.38E-09 4.40E-07 o. 2.85E-09 2.54E-04 2.86E-~5

BA141 +D 1.78E-11 1.32E-14 5.93E-13 o. 1.23E-14 4.11 E-07 9.33E-14 BA142+D 4.62E-12 4.63E-15 2.84E-13 o. 3.92E-15 2.39E-07 5.99E-20 LA140 5.99E-08 2.95E-08 7.82E-09 o. o. 2.68E-05 6.09E-05 LA141 7.63E-10 2.35E-10 3.87E-11 o. 0. 2.31 E-06 1.54E-05 LA142 1.20E-10 5.31 E-11 1 .32E-11 o. 0. 1 .27E-06 1 .50E-06 CE141 3.55E-06 2.37E-06 2. 71 E-07 0. 1. 11 E-06 7.67E-05 1 .58E-05 CE143+D 3.32E-08 2.42E-08 2.70E-09 o. 1.0SE-08 1 ;63E-05 3.19E-05 CE144+0 6.11 E-04 2.53E-04 3.28E-05 0. 1 .51 E-04 1 .67E-03 1.0SE-04 PR143 1 .67E-06 6.64E-07 8.28E-08 o. 3.86E-07 6.04E~05 2.67E-05 PR144 5.37E-12 2.20E-12 2. 72E-13 0. 1.26E-12 2. 19E-07 2.94E-14 ND147+D 9.83E-07 1 .07E-06 6.41 E-08 o. 6.28E-07 4.65E-05 2.28E-05 PM147 1. 15E-04 1. 1OE-05 4.50E-06 o*. 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 4.1 OE-05 PM148 5.44E-07 8.88E-08 4.48E-08 o. 1 .60E-07 6.52E-05 6. 14E-05 PM149 4.91E-08 6.89E-09 2.84E-09 o. 1 .31 E-08 1.24E-05 2.79E-05 PM151 1 .20E-08 1 .99E-09 1.01 E-09 o. 3.57E-09 6.56E-06 2.27E-05 SM151 1.07E-04 2.10E-05 4.86E-06 o. 2.27E-05 7.68E-05 3.53E-06 SM153 2.43E-08 2.01 E-08 1.47E-09 o. 6.56E-09 7.11 E-06 1.77E-05 EU152 2.96E-04 7. 19E-05 6.30E-05 0. 3.34E-04 5.01 E-04 1 .35E-05 EU154 9.43E-04 1.23E-04 8.60E-05 0. 5.44E-04 9. 12E-04 3.34E-05 EU155 2.00E-04 1 .96E-05 1 .21 E-05 o. 7.65E-05 1 .51 E-03 5.97E-05 EU156 2.70E-06 2.03E-06 3.30E-07 o. 1.36E-06 1 .37E-04 4.56E-05 TB160 3.04E-05 o. 3.79E-06 o. 1 .20E-05 2.97E-04 2.60E-05 H0166M 4.40E-04 1 .36E-04 9.87E-05 o. 2.00E-04 6.24E-04 1.68E-05 W181 8.90E-09 2.SSE-09 3.01E-10 o. 0. 2.95E-06 2.69E-07 W185 2.78E-07 9. 17E-08 9.73E-09 0. o. 9.60E-05 1.14E-05

W187 1 .50E-09 1 .22E-09 4.29E-10 0. 0. 5.92E-06 2.21E-05 54

PALISADE~ NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11 TABLE 1 . 7 (contd)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210+D 3.09E-02 8.28E-03 1.07E-03 0. 2.95E-02 4.52E-02 3.87E-05 81210+0 0. 2.26E-06 1.89E-07 0. 2.74E-05 1.91 E-03 3.19E-05 P0210 5.68E-04 1.22E-03 1.37E-04 0. 4.21 E-03 5.41 E-02 4.45E-05 RN222+D o. o.. o. 0. 0. 3.94E-06 0.

RA223+D 2.57E-04 3.93E-07 5.14E-05 0. . 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 0. 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 3.11E-04 RA228+D 5.34E-02 1. 74E-06 5.88E-02 0. 4.97E-05 2.78E-01 5.30E-05 AC225 6.04E-04 8.25E-04 4.06E-05 0. 9.47E-05 3.81 E-02 2.70E-04 AC227 + D 2.49E+OO 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. 3.18E-05 6.50E-02 3.57E-04 TH228+D 2.60E-01 4.37E-03 8.78E-03 0. 2.45E-02 1,69E+OO 3.70E-04 TH229 9.06E+OO 1.36E-01 4.45E-01 0. 6.67E-01 5.05E+OO 3.36E-04 TH230 2.34E+OO 1.34E-01 6.49E-02 0. 6.55E-01 8.98E-01 3.95E-05 TH232+D 2.61 E +00 1.14E-01 9.21 E-02 0. 5.60E-01 8.60E-01 3.36E-05 TH234 2.32E-06 1.35E-07 6. 71 E-08 0. 7.73E-07 3.26E-04 7.49E-05 PA231 +D 5.32E+OO 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 o. 5.23E-03 0. 7.94E-03 3.84E-01 4.46E-05 U233+D 1.55E-02 o. 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 o. 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 1.36E-02 o. 8.10E-04 o. 3.12E-03 7.89E-02 3.62E-05 NP237+D 1.77E+OO 1.54E-01 7.21 E-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. 75E-o5 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+OO 4.06E-01 7.22E-02 0. 3.10E-01 3.12E-01 4.79E-05 PU239

3.31 E +00 4.50E-01 8.05E-02 0. 3.44E-01 2.93E-01 4.37E-05 PU240 3.31E+OO 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+OO 4.33E-01 7.75E-02 0. 3.31 E-01 2.82E-01 4.29E-05 PU244 3.59E+OO 4.96E-01 8.88E-02 0. 3. 79E-01 3.23E-01 6.39E-05 AM241 1.06E+OO 4.07E-01 7.1 OE-02 0. . 5.32E-01 1.05E-01 4.88E-05 AM242M 1.07E+OO 3.93E-01 7.15E-02 0. 5.30E-01 4.21 E-02 6.14E-05 AM243 1.06E+OO 3.92E-01 6.95E-02 0. 5.21 E-01 9.91 E-02 5.72E-05 CM242 2.12E-02 2.14E-02 1.41 E-03 o. 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+OO 4.11 E-01 7.53E-02 0. 3.52E-01 1.01 E-01 4.63E-05 CM246 1.31 E+OO 4.11 E-01 7.52E-02 0. 3.51 E-01 1.03E-01 4.54E-05 CM247+D 1.28E+OO 4.04E-01 7.41 E-02 0. 3.46E-01 1.01 E-01 5.97E-05 CM248. 1.06E+01 3.33E+OO 6.11 E-01 0. 2.85E+OO 8.32E-01 9.63E-04 CF252 1.29E+OO 0. 3.07E-02 0. 0. 3.43E-01 1.89E-04 55

PALJSAD~S NUQL~AR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

ADULT INHALATION DOSE ISOTOPE H3*_ 0.

BONE LIVER 1.58E-07 TABLE 1. 7 (contd)

COMMITMENT FACTORS TOTAL BODY 1.58E-07 (MREM/SOY PER PCI INHALED IN FIRST YR)

THYROID 1.58E-07 KIDNEY-1.58E-07 LUNG 1.58E-07 Gl-LLI 1.58E-07 BE10 1.98E-04 3.06E-05 4.96E-06 0. 0. 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 4.71E-07 0. 5.19E-08 0. 0. 0. 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 1.65E-04 9.64E-06 6.26E-06 0. 0. 0. 1.08E-05 AR39 o. 0. 0. 0. 0. 2.08E-09 0.

AR41 0. 0. 0. 0. 0. 8.06E-09 0.

CA41 3.83E-05 o. 4.13E-06 0. 0. 3.83E-06 2.86E-07 SC46 5.51 E-05 1.07E-04 3.11E-05 0. 9.99E-05 0. 3.23E-05 CR51 0. 0. 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 FE55 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. 0. 1.27E-04 2.35E-05 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. 0. 1.16E-04 1.33E-05 C060 0. 1.44E-06 1.85E-06 0. 0. 7.46E-04 3.56E-~5 N159 4.06E-06 1.46E-06 6.77E-07 o. o. 8.20E-06 6.11E-07

.N163 5.40E-05 3.93E-06 1.81 E-06 0. o. 2.23E-05 1.67E-06 Nl65 1.92E-10 2.62E-11 1 .14E-11 0. 0. 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 o. 8.62E-06 1.08E-04 6.68E-06 ZN69M+D 1.02E-09 2.45E-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 BR82 o. 0. 1.69E-06 0. 0. 0. 1.30E-06 BR83+D 0. 0. 3.01 E-08 0. 0. 0. 2.90E-08 BR84 0. 0. 3.91 E-08 0. 0. 0. 2.0SE-13 BR85 0. 0. 1.60E-09 0. o. 0. 0.

KR83M 0. 0. 0. 0. 0. 5.19E-10 0.

KR85M 0. 0. 0. 0. 0. 2.91 E-09 0.

KR85 0. 0. 0. 0. 0. 2.41 E-09 0.

KR87 0. 0. 0. 0. 0. 1.53E-08 0.

KR88+D o. 0. 0. o. 0. 3.13E-08 0.

KR89 0. o. o. 0. 0. 2.13E-08 o.

RB86 0. 1.69E-05 7.37E-06 0. 0. o. 2.0SE-06 RB87 0. 9.86E-06 3.21 E-06 o. 0. 0. 2.88E-07 RB88 0. 4.84E-08 2.41 E-08 0. 0. 0. 4.1 SE-19 RB89+D 0. 3.20E-08 2.12E-08 0. 0. 0. 1.16E-21 SR89+D 3.SOE-05 o. 1.09E-06 o. 0. 1. 75E-04 4.37E-05 SR90+D 1.24E-02 0. 7.62E-04 0. 0. 1.20E-03 9.02E-05 SR91 +D 7. 74E-09 0. 3.13E-10 0. 0. 4.56E-06 2.39E-05 SR92+D 8.43E-10 0. 3.64E-11 0. o. 2.0SE-06 5.38E-06

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

56

PALISADES NUCL.EAB PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11 TABLE 1 . 7 (contd)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0. 5.0SE-08.

1133 + D 1.0SE-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 o. 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 3.35E-07 . 8.73E-07 3.21 E-07 5.60E-05 1.39E-06 0. _6._5_6E-O?

XE131 M 0. o. 0. 0. o. 1.40E-09 0.

XE133M 0. 0. 0. 0. o. 1.89E-09 0.

XE133 0. 0. 0. 0. 0. 1.57E-09 0.

XE135M 0. 0. 0. 0. 0. 2.22E-09 0.

XE135 0. 0. 0. 0. o. 4.05E-09 0.

XE137 0. 0. 0. 0. o. 1.74E-08 0.

XE138+D 0. 0. 0. 0. 0. 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 9.1 OE-05 0. 3.59E-05 1.22E-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.BBE-06 1.83E-05 1.38E-05 0. 1.07E-05 1.50E-06 1.46E~o6 CS137+D 5.98E-05 7.76E-05 5.35E-05 0. 2.78E-05 9.40E-06 1.05E-06 CS138 4.14E-08 7.76E-08 4.05E-08 0. 6.00E-08 6.07E-09 2.33E-13 CS139+D 2.56E-08 3.63E-08 1.39E-08 0. 3.05E-08 2.84E-09 5.49E-31 BA139 1.17E-10 8.32E-14 3.42E-12 0. 7.78E-14 4.70E-07 1.12E-07 r'

BA140+D 4.88E-06 6.13E-09 3.21E-07 0. 2.09E-09 1.59E-04 2.73E:o5 BA141 +D 1.25E-11 9.41 E-15 4.20E-13 0. 8.75E-15 2.42E-07 1.45E-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. 1.35E-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 1.91E-13 0. 8.81E-13 1.27E-07 2.69E-18 ND147+D 6.59E-07 7.62E-07 4.56E-08 0. 4.45E-07 2.76E-05 2.16E-05 PM147 8.37E-05 7.87E-06 3.19E-06 0. 1.49.E-05 6.60E-05 5.54E-06 PM148M+D 9.82E-06 2.54E-06 1.94E-06 0. 3.85E-06 2.14E-04 4.1 BE-05 PM148 3.84E-07 6.37E-08 3.20E-08 0. 1.20E-07 3.91 E-05 5.BOE-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 4.45E-05 3.25E-06 SM153 1.70E-08 1.42E-08 1.04E-09 0. 4.59E-09 4.14E-06 1.58E-05 EU152 2.38E-04 5.41 E-05 4.76E-05 0. 3.35E-04 3.43E-04 1.59E-05 EU154 7.40E-04 9.10E-05 6.48E-05 0. 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. 9.95E-07 8.56E-05 4.50E-05 TB160 2.21 E-05 0. 2.75E-06 0. 9.10E-06 1.92E-04 2.68E-05 H0166M 3.37E-04 1.05E-04 8.00E-05 o. 1.57E-04 3.94E-04 1.59E-05 W181 6.23E-09 2.03E-09 2.17E-10 0. o. 1.71 E-06 2.53E-07 W185 1.95E-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. 3.63E-06 1.94E-05 58

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

- ----------------------- TABLE 1. 7 (contd)

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

ISOTOPE BONE LIVER TOT AL BODY THYROID KIDNEY LUNG Gl-LLI PB210+D 2.64E-02 6. 73E-03 8.37E-04 0. 2.12E-02 2.62E-02 3.65E-05 81210+0 0. 1 .59E-06 1.32E-07 0. 1.92E-05 1.11 E-03 2.95E-05 P0210 3.97E-04 8.60E-04 9.58E-05 0. 2.95E-03 3.14E-02 4.19E-05 RN222 +D 0. 0. 0. 0. 0. 2.05E-06 0.

RA223 + D 1 .SOE-04 2. 77E-07 3.60E-05 0. 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 RA225 + D 3.00E-04 3.56E-07 5.99E-05 0. 1 .01 E-05 . 2.92E-02 2. 71 E-04 RA226+D 1 .25E-01 2.39E-06 9.14E-02 0. 6. 77E-05 1.17E-01 2.94E-04 RA228+D 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 0. 6.63E-05 2.21 E-02 2.52E-04 AC227+D 2.30E + 00 3.0SE-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 1.01E+00 3.49E-04 TH229 8.88E+OO 1.33E-01 4.36E-01 0. 6.52E-01 3.49E + 00 3.17E-04 TH230 2.29E+OO 1.31E-01 6.36E-02 0. 6.40E-01 6.21 E-01 3.73E-05 TH232+D 2.56E+OO . 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. 5.41E-07 1.89E-04 7.03E-05 PA231 +D 5.08E+OO 1.91E-01 1.98E-01 0. 1.07E+OO 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 eios U233+D 1 .09E-02 0. 6.60E-04 0. 2.54E-03 5.32E-02 3.89E-05 U234 1 .04E-02 O. 6.46E-04 O. 2.49E-03 5.22E-02 3.81 E-05 U235 +D 1 .OOE-02 0. 6.07E-04 0. 2.34E-03 4.90E-02 4.84E-05 U236 1 .OOE-02 0. 6.20E-04 0. 2.39E-03 5.00E-02 3.57E-05 U237 3.67E-08

0. 9. 77E-09 0. 1.51E-07 1.02E-05 1.20E-05 U238+D 9.58E-03 0. 5.67E-04 0. 2.1 SE-03 4.58E-02 3.41 E-05 NP237+D 1.69E+OO 1.47E-01 6.87E-02 0. 5.1 OE-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+OO 3.87E-01 6.90E-02 0. 2.96E-01 1.82E-01 4.52E-05 PU239

3.19E+OO 4.31E-01 7.75E-02 0. 3.30E-01 1. 72E-01 4.13E-05 PU240 3.18E+OO 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+OO 4.15E-01 7.46E-02 0. 3.17E-01 1.65E-01 4.05E-05 PU244 3.45E+OO 4.76E-01 8.54E-02 0. 3.64E-01 1 .89E-01 6.03E-05 AM241 1.01E+OO .3.59E-01 6.71E-02 0. 5.04E-01 6.06E-02 4.60E-05 AM242M 1.02E+00 3.46E-01 6. 73E-02 0. 5.01 E-01 2.44E-02 5. 79E-05 AM243 1.01E+OO 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 E-02 0. 2.1 SE-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+OO 3.53E-01 7.03E-02 0. 3.28E-01 5.85E-02 5.63E-05 CM248 1.01E+01 2.91E+OO 5.79E-01 0. 2. 70E + 00 4.82E-01 9.09E-04 CF252 9. 78E-01 0. 2.33E-02 0. 0. 1.99E-01 1.78E-04 59

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

TABLE 1.8 EXTERNAL DOSE FACTORS FOR STANDING ON CQNTAMINATION GRQUND {DFG 1l

<MREM/HR PER PCl/M 2 l 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 Mn-54 5.80E-09 6.SOE-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-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 r*

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 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.SOE-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-91m 3.SOE-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.SOE-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.1 OE-09 6.00E-09 Mo-99 1.90E-09 2.20E-09

Tc-99m 9.60E-10 1 .1 OE-09 Tc-101 2.70E-09 3.00E-09 60

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11 TABLE 1 .8 (continued)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND {DFG,l

{MREM/HR PER PCl/M 2 )

ELEMENT TOTAL BODY SKIN Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.1 OE-09 Ru-106 1.50E-09 1.80E-09 Ag-11 Om 1 .BOE-08 2.1 OE-08 Te-125m 3.50E-11 4.80E-11 Te-127m 1.1 OE-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129m 7.70E-10 9.00E-10 Te-129 7 .1OE-10 8.40E-10 Te-131 m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132

1.70E-09 2.00E-09 1.40E-08 1-130 1.70E-08 !'

1-131 2.BOE-09 3.40E-09 1-132 1.70E-08 2.00E-08 1-133 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.1 OE-08 2.40E-08 Ba-139 2.40E-09 2. 70E-09 Ba-140 2.1 OE-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.SOE-08 1.70E-08 La-142 1.SOE-08 1.80E-08 Ce-141 5.SOE-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 3.1 OE-09 3.60E-09 Np-239 9.50E-10 1.1 OE-09 61

PALISAQES NUCLEAR PLA~T OFFSITE DOSE CALCULATION MANUAL Revision 11 .

TABLE 1.9 1997 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ Mrem/Ci {Cil Ag-11 Om GI Tract-T 1 .98E+OO 7.58E +00 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 I Br-82 Total Body-C 4.43E-03 1.13E+03 C-14 Bone-C 1 .29E-01 1. 16E + 02 I Ce-141 GI Tract-T 1.25E-01 1.20E+02 I Ce-144 GI Tract-T 3.15E+OO 4.76E+OO I Co-57 GI Tract-T 7.96E-02 1.88E+02 I Co-58 GI Tract-T 2.41 E-01 6.22E+01 I Co-60 GI Tract-T 6.41E+OO 2.34E+OO I Cr-51 GI Tract-A 3.50E-03 4.29E+03 r I Cs-134 Liver-C 8.21 E +00 1.83E+OO Cs-136 Liver-I 2.24E-01 6.70E+01 I'! Cs-137 Bone-C 8.95E+OO 1.68E+OO a--.'I I Cs-138 Total Body-C 9.37E-02 5.34E +01 Fe-55 Bone-C 1 .92E-01 7.81E+01 I I Fe-59 GI Tract-T 2.99E-01 5.02E+01

-1 H-3 Total Body-C 1 .91 E-04 2.62E+04 I 1-129 Thyroid-A 3.42E+02 4.39E-02 I 1-131 Thyroid-I 8.26E+OO 1.82E+OO l-l32 Thyroid-C 1.05E-02 1 .43E+03 1-133 Thyroid-C 2.09E-01 7.18E+01 1-134 Thyroid-C 2.76E-03 5.43E+03 1-135 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-A 2.73E-02 5.49E +02 Mn-54 GI Tract-T 5.87E-01 2.56E +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-13 Total Body-C 4.48E-06 1. 12E +06 62

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11 TABLE 1-9 (continued) 19~7 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ Mrem/Ci ICil Na-24 Total Body-C 3.64E-03 1.37E+03 Nb-95 GI Tract-T 1 .39E-01 1.08E+02 Ni-63 Bone-C 1.14E + 01 1.32E+OO Ni-65 GI Tract-C 4.37E-03 3.43E +03 Np-239 GI Tract-T 7 .08E-03 2.12E +03 Rb-88 Total Body-C 2.14E-05 2.34E +05 Ru-103 GI Tract-A 1.69E-01 8.88E +01 Ru-105 GI Tract-C 5.17E-03 2.90E+03 Sb-124 GI Tract-T 8.85E-01 1.69E+01 I Sb-1 25 GI Tract-T 4.06E-01 3.69E+01 I Sr-89 Bone-C 8.40E+OO 1.79E +00 I Sr-90 Bone-C 3.49E+02 4.30E-02 I I' Sr-91 Bone-I 2.13E+OO 7.04E +00 °"

Sr-92 Tc-99 GI Tract-C GI Tract-T 1.26E-02 5.46E-01 3.19E-04 1.19E +03 2.75E+01 4.70E+04 I --

l I

Tc-99m GI Tract-T Tc-101 Lung-T 7.63E-05 1.97E+05 Te-127 GI Tract-T 4.20E-03 3.57E +03 Xe-131 m Skin 3.39E-05 4.42E+05 Xe-133 Total Body 1.17E-05 4.27E+05 Xe-133m Skin 7.08E-05 2.12E +05 Xe-135 Total Body 7.19E-05 6.95E+04 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 Zn-65 Liver-C 8.76E-01 1.71E+01 Zr-95 GI Tract-T 3.64E-01 4.12E+01 Pu-238 Bone-T 1.19E + 03 1.26E-02 Pu-239 Bone-T 1.38E+03 1.09E-02 Pu-241 Bone-T 2.90E+01 5.17E-01 Am-241 Bone-T 4.41 E +02 3.40E-02 Cm-242 Lung-T 2.81E+01 5.34E-01 Cm-244 Bone-T 2.69E+02 5.58E-02 63

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULA Tl ON MANUAL Revision 11

11.

A.

LIQUID EFFLUENTS CONCENTRATION

1. Requirements 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 8, 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 µCi/ml total activity. To ensure compliance, the following approach will be used for each release.

2. Pre release 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 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 = .E c, i=1 (2.1) where:

c = Total concentration in the liquid effluent at the release point, µCi/ml.

= Concentration of a single radionuclide i, µCi/ml.

64

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

~---------------------

3. Effluent Concentration f EC> - Sum of the Ratios The EC-Fraction (Ri) for each release point will be calculated by the relationship defined by Note 4 of Appendix B; 10 CFR 20:

R j

= Li (2.2) where:

= Effluent concentration of radionuclide i, µCi/ml.

= The EC of radionuclide i, 10 CFR 20, Appendix B, Table 2, Column 2 - µCi/ml.

= 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 following relationship will assure this criterion is met:

~(R,-1) + ~(R 2 -1) + ~(R 3 -1) s F (2.3) where:

= The effluent flow rate (gallons/minute) for the respective releases, determined by Plant personnel.

= The Total EC-Fractions for the respective releases as 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 = (bi)(F) where bi is a conservative factor greater than 1.0 .

65

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

- B. INSTRUMENT SETPOINTS

1. Setpoint Determination Appendix A, Section 111.F requires alarm setpoints for each liquid effluent monitor will be established using Plant instructions to ensure the requirements of Appendix A, Section 111.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 r 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 =bx c (2.4)

Liquid effluent flow paths and release points are indicated in Figure 2.1.

2. Composite Samplers 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 hourly, 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 NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL

~

3. Post-Release Analysis Revision 11 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 (Ci), by isotope, will be used with the actual liquid radwaste (f) arid 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 records by Plant personnel.

C. DOSE

1. RETS Requirement Appendix A, Section 111.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 !'

effluents release to unrestricted areas from the reactor (see Figure 2-1) will not exceed:

a. During any calendar quarter, 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.

To 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:

(2.5)

67

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

~---------------------

where:

= Cumulative quarterly activity of nuclide i identified in liquid release (Ci).

= Design objective annual quantity of radionuclide i from 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 co.nsequence of this conservatism, and in light of historically consistent operations with releases well below annual design basis 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 111.H.1 has been met.

Values for the design basis quantities (Ci), and the dose per Curie r

(De/Celi for each nuclide i shown in Table 2.2, were calculated as follows in Sections 2.1 and 2.2.

a. Water Ingestion The dose to an individual from ingestion of radioactivity from any source as described by the following equation:

i DJ L (DCF)IJ x 1, i=I (2.6) where:

Di = Dose for the jth organ from radionuclides releases, mrem.

= The organ of interest.

(DCF)ii = Ingestion dose commitment factor for the jth organ from the ith radionuclide mrem/pCi, see Table 2.1 .

Ii = Activity ingested of the ith radionuclide, pCi.

68

PALISADES NUCLEAR PLANT OFFSITE POSE CALCULATION MANUAL Revision 11 Ii is described by:

I. = (A1)(V)(365) (1 EOS)

I (1 OOO)(d)

(2.7) where:

365 = Days per year.

Annual activity released of ith radionuclide, µCi.

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 µCi to pCi.

The dose equation then becomes:

i (3.65E05)(V) ~

DJ = Li (DCF)IJ x Ai mrem d i=1 (2.8)

b. Fish Ingestion The dose to an individual from the consumption of fish is described by Equation 2. 10. In this case, the activity ingested of the ith radionuclide (Ii) is described by:

A 1B1F(1 E09)

I = = pCi I 15d (2.9) where:

= Annual released of ith radionuclide, µCi.

69

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

= Fish concentration factor of ;th radionuclide

µCi/gm

µCi/ml (see Table 2.0).

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 µCi and Kgm to gross.

Substitution of Equation 2.9 into Equation 2.6 gives:

i (6.7E07)F ~

Di = .t..J A 1 x 8 1 x DCF 1 mrem d

i=1 (2.10)

c. Annual Analysis 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 LADT AP. The dose to the jth organ from m radionuclides, Dj, is described by:

m D1 = L D 1i mrem i=1 (2. 11) m

= .E (DCF)IJ x IJ mrem i=1

70

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

~---------------------

where:

= Dose to the r organ from the ith radionuclide, mrem.

= The organ of interest (bone, GI tract, thyroid, liver, kidney, lung, or total body).

= Adult ingestion dose commitment factor for the r organ from the ith radionuclide, mrem/pCi (see Table 2.1).

= Activity ingested of the ith radionuclide, µCi.

Ii for water ingestion is described by:

AV I = _i_r µCi I Vd (2.13) and for fish ingestion Ii is described by:

A1 81 Fr .

II = µC1 vd where:

= Activity release of r radionuclide during the year, µCi.

v = Average rate of water consumption (2000 ml/d).

r = Number of days during the year (365 d).

v = Dispersion factor from point of discharge to point of exposure.

d = Dilution water volume (ml).

= Fish concentration factor of the ith radionuclide,

µCi/gm Table 2.0,

µCi/ml

F = Amount of fish eaten per day (57.5 gm/d).

71

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11

D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT The Palisades liquid radwaste system is designed to reduce the radioactive materials in liquid wastes prior to their discharge (by recycle or shipment for disposal) so that radioactivity in liquid effluent releases to unrestricted areas (see Figure 2-1) will not exceed the limits of Appendix A, 111.H.1. Maintaining the cumulative fraction if allowable release for each batch release cind weekly for continuous releases assures compliance with this requirement. In addition, 13 years of operating experience (to the date this ODCM was first adopted) has shown that design basis quantities never have been exceeded.

E. RELEASE RATE FOR OFFSITE EC (50 mRem/yr) 10 CFR 20. 1 302 requires radioactive effluent releases to unrestricted areas be less than the limits specified in Appendix 8, Table 2 when averaged over a period not to exceed one year. Concentrations at this Effluent Concentration (EC) level, if ingested for one year, will result in a ["

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 I to 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as is reasonably achievable requirement.

The LADTAP code has been run to determine the dose due to drinking water at Plant discharge concentration ( 1,000 x nearest drinking water intake concentration). The nominal average source term used is given in Table 1 . 1 . Dose to the most limiting organ of the person hypothetically drinking this water is 3.SSE-03 mrem. This is only 0.13% of the more conservative 50 mrem/yr total body value .

72

LL

PALISADES RADWASTE EFFLUENTS - LIQUID I

. . ~

1J; I 1111\N IL WI\~ rl -----,---------,

'.;Y:;Jf M STEAM GEN BlOWOOWN PRIMARY

..J SYSTEM

<t STORAGE T /\NI<

rnr 11 ri. n WI\'.; If T 90 r l\Nl ~~~Y~ff M w11 rrn sronAGF _,~~

~~a: TANI< .....~~

~~T 91 J II II nllJ TURBINE BLDG Wll<;H DRAINS -**---,~~

~~11\NI< TURBINE SUMP AE 5Jll DILUTION FLOW SERVICE WATER _ _ _ _ __.__ _ _ _ _ _ _ _ _L_A_IC_E_IN_L_E_r_ _-¥r~~

~~r -~- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -~~

~~PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11~~

~~--~\----------------------------------------------------------------~~

TABLE 2.0 BIOACCUMULATION FACTORS pCi/gm per pCi/ml FRESHWATER ELEMENT FISH H 9.0E-01 c 4.6E 03 NA 1.0E 02 p 1.0E 05 CR 2.0E 02 MN 4.0E 02 FE 1.0E 02 co 5.0E 01 NI 1.0E 02 cu 5.0E 01 r'

ZN 2.0E 03 BR 4.2E 02 RB 2.0E 03 SR 3.0E 01 y 2.5E 01 ZR 3.3E 00 NB 3.0E 04 MO 1 .OE 01 TC 1.5E 01 RU 1.0E 01 RH 1 .OE 01 TE 4.0E 02 I 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 .OE 01
-* 75
PALISADES NUQLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
., Revision 11 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 3.08E-07. 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.083-07 BE10 1. 71 E-05 2.49E-06 5.16E-07 0. 1.64E-06 0. 2. 78E-05 C14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 N13 5.85E-08 5.85E-08 5.85E-08 5.835E-08 5.85E-08 5.85E-08 5.85E-08 F18 5.19E-06 o. 4.43E.07 0. 0. 0. 1.22E-06 NA22 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 NA24 1 .01 E-05 1.01E-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 0. 0. 0. 2.30E-05 AR39 0. 0. 0. 0. 0. 0. 0.
AR41 0. o. 0. 0. 0. 0. 0.
C.A.41 3.74E-04 o. 4.08E-05 0. 0. 0. 1.91E-07 SC46 3. 75E-08 5.41 E-08 1.69E-08 0. 3.56E-08 0. 3.53E-05 CR51 0. 0. 1.41E-08 9.20E-09 2.01 E-09 1.79E-08 4.11 E-07 MN54 o. 1.99E-05 4.51 E-06 0. 4.41 E-06 0. 7.31 E-06 MN56 o. 8.18E-07 1.41 E-07 0. 7.03E-07 0. 7.43E-05 FE55 1.39E-05 8.98E-06 2.40E-06 0. 0. 4.39E-06 1.14E-06 FE59 3.0SE-05 5.38E-05 2.12E-05 0. 0. 1.59E-05 2.57E-Oq.
C057 o. 1.15E-06 1.87E-06 0. 0. 0. 3.92E-06 o.
C058 3.60E-06 8.98E-06 0. 0. 0. 8.97E-06 C060 0. 1.0SE-05 2.55E-05 0. 0. 0. 2.57E-05 Nl59 4. 78E-05 1.45E-05 8.17E-06 0. 0. 0. 7.16E-07 Nl63 6.34E-04 3.92E-05 2.20E-05 0. 0. o.* 1.95E-06 Nl65 4.70E-06 5.32E-07 2.42E-07 0. 0. 0. 4.05E-05 CU64 0. 6.09E-07 2.82E-07 0. 1.03E-06 0. 1.25E-05 ZN65 1.84E-05 6.31E-05 2.91 E-05 0. 3.06E-05 0. 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 o. 2.10E-05 3.90E-06 0. 2.43E-05 0. 5.58E-07 BR82 o. o. 1.27E-05 0. 0. 0. 0.
BR83.f-D 0. o. 3.63E-07 0. 0. 0. 0.
BR84 o. o. 3.82E-07 0. 0. 0. 0.
BR85 0. o. 1.94E-08 0. 0. 0. 0.
KR83M o. o. 0. 0. 0. 0. 0.
KR85M o. 0. 0. 0. 0. 0. 0.
KR85 o. o. 0. o. 0. 0. 0.
KR87 o. 0. 0. 0. 0. 0. 0.
KR88+D o. o. 0. 0. 0. 0. 0.
KR89 o. o. 0. 0. 0. 0. 0.
RB86 0. 1.70E-04 8.40E-05 0. 0. 0. 4.35E-06 R887 0. 8.BSE-05 3.52E-05 0. 0. 0. 5.98E-07 ABBS o. 4.98E-07 2.73E-07 0. 0. 0. 4.85E-07 R889+D o. 2.86E-07 1.97E-07 0. 0. 0. 9.74E-08 SR89+D 2.51 E-03 o. 7.20E-05 0. 0. 0. 5.16E-05 SR90+D 1.85E-02 o. 4.71 E-03 0. 0. 0. 2.31 E-04
~~SR91 +D 5.00E-05 o. 1.81 E-06 0. 0. 0. 5.92E-05 SR92+D 1.92E-05 0. 7.13E-07 0. 0. 0. 2.07E-04 76~~
~~PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11~~
~~TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INGESTED IN FIRST YR)~~
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 8.69E-08 0. 2.33E-09 0. 0. 0. 1.20E-04 Y91 M +D 8.10E-10 0. 2.76E-11 0. 0. 0. 2. 70E-06 Y91 1.13E-06 0. 3.01 E-08 0. 0. 0. 8.1 OE-05 Y92 7.65E-09 0. 2.15E-10 0. 0. - - 0. 1.46E-04 Y93 2.43E-08 0. 6.62E-10 0. 0. 0. 1.92E-04 ZR93+D 1.93E-07 9.18E-08 5.54E-08 o. 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 ZR97 +D 1.48E-08 2.54E-09 1.16E-09 0. 2.56E-09 0. 1.62E-04 N893M 1.23E-07 3.33E-08 1.04E-08 o. 3.25E-08 o. 3.98E-06 N895 4.20E-08 1.73E-08 1.00E-08 0. 1.24E-08 0. 1.46E-05 N897 4.59E-10 9.79E-11 3.53E-11 0. 7.65E-11 0. 3.09E-05 M093 0. 5.65E-05 1.82E-06 0. 1.13E-05 0. 1.21E-06 M099+D 0. 3.40E-05 6.63E-06 0. 5.08E-05 0. 1.12E-05 TC99M 1.92E-09 3.96E-09 5.1 OE-08 o. 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 o. 3.40E-08 1.56E-09 4.86E-07 RU103+D 1.48E-06 0. 4.95E-07 o. 3.08E-06 0. 1.SOE-05 RU105 + D 1.36E-07 0. 4.58E-08 0. 1.00E-06 0. 5.41 E-95 RU106+D 2.41 E-05 o. 3.01 E-06 0. 2.85E-05 0. 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 4.81 E-07 0. 1.04E-06 0. 3. 77E-05 AG111 5.20E-07 2.02E-07 1.07E-07 0. 4.22E-07 o. 4.82E-05 CD113M o. 1. 77E-05 6.52E-07 0. 1.34E-05 0. 2.66E-05 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 o. 0. 6.58E-05 5N125 + D 7.41 E-05 1.38E-06 3.29E-06 1.36E-06 o. 0. 1.11 E-04 5N126+0 5.53E-04 7.26E-06 1.SOE-05 1.91 E-06 0. o. 2.52E-05 58124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0. 1.34E-05 6.60E-05 *-
58125 +D 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0. 7.72E-06 1.64E-05 58126 8.06E-06 1.58E-07 2.91 E-06 6.19E-08 0. 5.07E-06 8.35E-05 58127 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 3.15E-06 7.84E-06 o. o. 1.11 E-05 TE127M+D 5.85E-05 1.94E-05 7.0SE-06 1.69E-05 1.44E-04 o. 2.36E-05 TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0. 2.1 OE-05 TE129M+D 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 o. 5.97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 o. 2.27E-05 TE131M+D 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 0. 1.03E-04 TE131 + D 1. 76E-07 6.50E-08 4.94E-08 1.57E-07 4.SOE-07 0. 7 .11 E-06 TE132+D 2.0SE-05 1.03E-05 9.61 E-06 1.52E-05 6.44E-05 0. 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 o. 3.06E-06 1129 2.86E-05 2.12E-05 1.55E-05 1.36E-02 2.51E-05 0. 4.24E-07 1130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0. 2.83E-06 1131 + D 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 o. 1.51E-06 77
PALISADES *NUQLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11
~~BONE TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INGESTED IN FIRST YR)~~
ISOTOPE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210+ D 5.28E-02 1.42E-02 2.38E-03 0. 4.33E-02 0. 5.62E-05 81210+0 4.16E-06 2.68E-05 3.58E-07 0. 2.0SE-04 0. 5.27E-05 P0210 3.1 OE-03 5.93E-03 7.41 E-04 0. 1.26E-02 0. 6.61 E-05 RN222+D 0. 0. 0. 0.- 0. 0. 0.
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 o. 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 o. 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 o. 7.41 E-06 0. 5.70E-04 TH228+D 2.47E-03 3.38E-05 8.36E-05 0. 1.58E-04 0. 5.84E-04 TH229 1.48E-02 l.94E-04 7.29E~04 0. 9.29E-04 0. 5.31E-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 1.65E-04 0. 7.79E-04 0. 5.31 E-05 TH234 6.92E-07 3.77E-08 2.00E-08 o. 1.39E-07 0. 1.19E-04 PA231 +D 7.57E-03 2.50E-04 3.02E-04 0. 1.34E-03 o. 7.44E-05 1.46E~65 PA233 3.11E-08 6.09E-09 5.43E-09 0. 1.67E-08 0.
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 o. 6.51 E-05 U234 4.88E-03 0. 3.80E-04 o. 1.06E-03 o. 6.37E-05 U235 +D 4.67E-03 0. 3.56E-04 o. 9.93E-04 0. 8.1 OE-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 o. 5.71E-05 NP237 +D 2.53E-03 1.93E-04 1.05E-04 0. 6.34E-04 o. 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 0. 1.21 E-04 0. 7.57E-05 PU239 1.45E-03 1.77E-04 3.54E-05 0. 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 o. 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 1.95E-04 3.91 E-05 0. 1.41E-04 0. 1.01 E-04 AM241 1.53E-03 7.18E-04 1.09E-04 0. 6.55E-04 o. 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 9.1 OE-06 0. 2.62E-05 0. 8.23E-05 CM243 1.45E-03 6.88E-04 8.98E-05 0. 3.27E-04 0. 8.1 OE-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 o. 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 o.
CM247 +D 1.82E-03 7.36E-04 1.11 E-04 4.24E-04 0. 9.43E-05 CM248 1.51E-02 6.07E-03 9. 16E-04 0. 3.50E-03 o. 1.52E-03 CF252 1 .24E-03 0. 2.95E-05 0 0. 0. 2.99E-04 79
PALISADES NUCLEAR PLANT OFF SITE DOSE CALCULATION MANUAL Revision 11
~~ISOTOPE BONE LIVER TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCl. INGESTED IN FIRST YR)~~
TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 4.11 E-08 0. 1.1 OE-09 0. 0. 0. 1 .17E-04 Y91M+D 3.82E-10 0. 1.39E-11 0. 0. 0. 7.48E-07 Y91 6.02E-07 0. 1.61 E-08 0. 0. 0. 8.02E-05 Y92 3.60E-09 0. 1.03E-10 0. 0. 0. 1 .04E-04 Y93 1.14E-08 0. 3.13E-10 0. 0. 0. 1. 70E-04 ZR93+D 1.67E-07 6.25E-08 4.45E-08 0. 2.42E-07 0. 2.37E-05 ZR95 +D 1.16E-07 2.55E-08 2.27E-08 0. 3.65E-08 0. 2.66E-05 ZR97 + D 6.99E-09 1 .01 E-09 5.96E-10 0. 1.45E-09 o. 1.53E-04 NB93M 1 .05E-07 2.62E-08 8.61 E-09 0. 2.83E-08 0. 3.95E-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 M093 o. 2.41 E-05 8.65E-07 0. 6.35E-06 0. 1.22E-06 M099+D 0. 1.33E-05 3.29E-06 0. 2.84E-05 0. 1.1 OE-05 TC99M 9.23E-10 1.81E-09 3.00E-08 0. 2.63E-08 9.19E-10 1.03E-06 TC99 5.35E-07 5.96E-07 2.14E-07 0. 7.02E-06 5.27E-08 6.25E-06 TC101 1.07E-09 1.12E-09 1.42E-08 0. 1.91E-08 5.92E-10 3.56E-09 RU103+D 7.31E-07 0. 2.81 E-07 0. 1.84E-06 0. 1.89E-05 RU105 +D 6.45E-08 0. 2.34E-08 0. 5.67E-07 0. 4.21 E-05 1.17E-05 o. 1.46E-06 0. 1.58E-05 0. 1.82E1b4 RU106 + D RH105 5.14E-07 2.76E-07 2.36E-07 0. 1.1 OE-06 0. 1. 71 E-05 PD107 0. 4.72E-07 4.01 E-08 0. 3.95E-06 0. 9.37E-07 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 o. 4.33E-05 AG111 2.48E-07 7.76E-08 5.12E-08 0. 2.34E-07 0. 4.75E-05 CD113M 0. 1.02E-05 4.34E-07 o. 1.05E-05 o. 2.63E-05 CD115M 0. 5.89E-06 2.51 E-07 o. 4.38E-06 0. 8.01 E-05 SN123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 0. 0. 6.52E-05 SN125+D 3.55E-05 5.35E-07 1.59E-06 5.55E-07 o. 0. 1.1 OE-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 2.45E-08 0. 6.16E-06 6.94E-05 SB125 + D 7.16E-06 5.52E-08 1.50E-06 6.63E-O~ 0. 3.99E-06 1. 71 E-05 SB126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 0. 2.1 OE-06 8.87E-05 SB127 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. 0. 1.1 OE-05 TE127M+D 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 0. 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 o. 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0. 8.34E-06 TE131M+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 6.51E-06 4.15E-05 o. 4.SOE-05 TE133M+D 1.87E-07 7.56E-08 9.37E-08 1.45E-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 0. 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 0. 1.54E-06 81
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL
,. Revision 11 TABLE 2. 1 CHILO INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)
ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI PB210 + D 4. 75E-02 1.22E-02 2.0(~E-03 0. 3.67E-02 0. 5.57E-05 81210+0 1.97E-06 1.02E-05 1.69E-07 0. 1 .15E-04 0. 5.17E-05 P0210 1.52E-03 2.43E-03 3.67E-04 0. 7.56E-03 0. 6.55E-05 RN222+D 0. 0. 0. 0. 0. 0. 0.
RA223+D 2.12E-02 2.45E-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. 3.21E-04 RA226+D 5. 75E-01 1.84E-05 4.72E-01 0. 4.88E-04 0. 3.41 E-04 RA228+D 3.85E-01 9.99E-06 4.32E-01 0. 2.65E-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 +O 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 2.65E-05 7.00E-05 0. 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 3.55E-03 1.78E-04 9.91 E-05 0. 8.67E-04 0. 6.19E-05 TH232+D 3.96E-03 1.52E-04 3.01 E-04 0. 7.41E-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 2.81 E-04 0. 1.28E-03 0. 7.37E-05 o.
PA233 1.81 E-08 2.82E-09 3.16E-09 0. 1.04E-08 1.44E-05 U232+D 1.76E-02 0. 1.26E-03 0. 1.34E-03 0. 6.98E-05 U233+D 3.72E-03 0. 2.25E-04 o. 6.10E-04 0. 6.45E-05 U234 3.57E-03 o. 2.21 E-04 0. 5.98E-04 0. 6.32E-05 U235 + D 3.42E-03 0. 2.07E-04 o. 5.61 E-04 0. 8.03E-05 U236 3.42E-03 0. 2.12E-04 o. 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+D 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 0. 6.0SE-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 o. 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 o. 6.85E-05 PU240 1.36E-03 1.65E-04 3.31 E-05 0. 1.22E-04 0. 6.98E-05 PU241 +D 4.00E-05 1.72E-06 8.04E-07 o. 2.96E-06 0. 1.44E-06 PU242 1.26E-03 1.59E-04 3.19E-05 o. 1.17E-04 0. 6.71E-05 PU244 1.47E-03 1.82E-04 3.65E-05 0. 1.35E-04 o. 1.00E-04 AM241 1.43E-03 6.40E-04 1.02E-04 o. 6.23E-04 o. 7.64E-05 AM242M 1.47E-03 6.25E-04 1.04E-04 0. 6.30E-04 o. 9.61 E-05 AM243 1.41E-03 6.14E-04 9.83E-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 6.03E-04 8.24E-05 o. 3.0SE-04 0. 8.03E-05 CM244 1.11 E-03 5.36E-04 6.93E-05 0. 2.54E-04 0. 7.77E-05 CM245 1.76E-03 6.64E-04 1.0SE-04 0. 4.11 E-04 o. 7.24E-05
\. CM246 CM247 +D CM248 CF252 1.74E-03 1.70E-03 1.41E-02 1.07E-03 6.64E-04 6.53E-04 5.38E-03 0.
1.0SE-04 1.03E-04 8.52E-04 2.54E-05 83 o.
0.
0.
0.
4.10E-04 4.04E-04 3.33E-03 0.
0.
o.
0.
0.
7 .11 E-05 9.35E-05 1.51 E-03 2.96E-04
PALISADES NUCLEAR e!:.ANT OFFSITE DOSE CALCULATION MANUAL Revision 11
~~ISOTOPE BONE LIVER TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)~~
TOTAL BODY THYROID KIDNEY LUNG Gl-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 o. 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 1.1 SE-08 1.1 SE-08 1.15E-08 1.15E-08 1. 1SE-08 1.15E-08 F18 8.64E-07 0. 9.47E-08 0. 0. 0. 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 0. 0. 0. 2.32E-05 AR39 0. 0. 0. 0. 0. 0. 0.
AR41 0. 0. o. 0. 0. 0. 0.
CA41 1.97E-04 0. 2.13E-05 0. 0. 0. 1.95E-07 SC46 7.24E-09 1.41 E-08 4.18E-09 0. 1.35E-08 0. 4.80E-05 CR51 0. 0. 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.0SE-07 MN54 0. 5.90E-06 1.17E-06 0. 1. 76E-06 0. 1.2lE-05 MN56 0. 1.58E-07 2.81 E-08 0. 2.00E-07 o. 1.04E-05 FE55 3. 78E-06 2.68E-06 6.25E~07 0. 0. 1. 70E-06 1 .16E-06 FE59 5.87E-06 1.37E-05 5.29E-06 0. 0. 4.32E-06 3.24E-05 c C057 0. 2.38E-07 3.99E-07 0. 0. 0. 4.44E-06 C058 0. 9.72E-07 2.24E-06 0. 0. 0. 1.34E-05
.C060 0 2.81 E-06 6.33E-06 0. 0. 0. 3.66E-05 Nl59 1.32E-05 4.66E-06 2.24E-06 0. 0. o. 7.31E-07 Nl63 1. 77E-04 1.25E-05 6.00E-06 0. 0. 0. 1.99E-06 Nl65 7.49E-07 9.57E-08 4.36E-08 0. 0. 0. 5.193-06 CU64 0. 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 0. 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 o. 5.16E-08 SE79 0. 3.73E-06 6.27E-07 0. 6.50E-06 0. 5.70E-07 BR82 0. 0. 3.04E-06 0. 0. 0. 0.
BR83+D 0. 0. 5.74E-08 0. 0. 0. 0.
BR84 0. 0. 7.22E-08 0. 0. 0. 0.
BR85 0. 0. 3.05E-09 0. 0. 0. 0.
KR83M 0. 0. 0. 0. 0. 0. 0.
KR85M 0. 0. 0. o. 0. 0. 0.
KR85 o. 0. o. 0. o. 0. 0.
KR87 0. 0. 0. 0. 0. 0. 0.
KR88+D 0. o. 0. 0. 0. 0. o.
KR89 0. 0. 0. 0. 0. o. 0.
RB86 0. 2.98E-05 1.40E-05 0. 0. 0. 4.41 E-06 RB87 0. 1.75E-05 6.11E-06 0. 0. o. 6.11E-07 RB88 0. 8.52E-08 4.54E-08 0. 0. 0. 7.30E-15 RB89+D 0. 5.SOE-08
3.89E-08 0. 0. 0. 8.43E-17 SR89+D 4.40E-04 0. 1.26E-05 0. 0. o. 5.24E-05 SR90+D 8.30E-03 0. 2.05E-03 0. 0. 0. 2.33E-04
(.R91 +D 8.07E-06 0. 3.21 E-07 0. 0. 0. 3.66E-05 R92+D 3.05E-06 0. 1.30E-07 0. 0. 0. 7.77E-05 84
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11
ISOTOPE BONE LIVER TABLE 2. 1 TEEN INGESTION DOSE COMMITMENT FACTORS !MREM/SOY PER PCI INGESTED IN FIRST YRl TOTAL BODY THYROID KIDNEY LUNG GI-LU Y90 1.37E-08 0. 3.69E-10 0. 0. 0. 1 .13E-04 Y91M + D 1.29E-10 0. 4.93E-12 o. 0. 0. 6.09E-09 Y91 2.01 E-07 0. 5.39E-09 0. 0. 0. 8.24E-05 Y92 1.21 E-09 0. 3.50E-11 0. 0. 0. 3.32E-05 Y93 3.83E-09 0. 1.05E-10 0. 0. 0. 1. 17E-04 ZR93+D 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. 7.11E-10 0. 1.27E-04 N893M 3.44E-08 1.13E-08 2.83E-09 0. 1.32E-08 0. 4.07E-06 N895 8.22E-09 4.56E-09 2.51E-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 M093 0. 1.06E-05 2.90E-07 0. 3.04E-06 0. 1.29E-06 M099+D o: 6.03E-06 1.15E-06 0. 1.38E-05 0. 1.0SE-05 TC99M 3.32E-10 9.26E-10 1.20E-08 0. 1.38E-08 5.14E-10 6.0SE-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 2.55E-07 o. 1.09E-07 0. 8.99E-07 0. 2.13E-05 RU105+D 2.1 SE-08 0. 8.46E-09 0. 2.75E-07 0. 1.76E-05 r'
RU106+D 3.92E-06 0. 4.94E-07 o. 7.56E-06 0. 1.88E-04 RH105 1. 73E-07 1.25E-07 8.20E-08 0. 5.31 E-07 0. 1 .59E-05 PD107 0. 2.08E-07 1.34E-08 0. 1.88E-06 o. 9.66E-07 PD109 0. 2.51E-07 5.70E-08 0. 1.45E-06 o. 2.53E-05 AG110M +D 2.05E-07 1.94E-07 1.1 SE-07 o. 3.70E-07 0. 5.45E-05 AG111 8.29E-08 3.44E-08 1.73E-08 0. 1.12E-07 o. 4.SOE-05 CD113M 0. 4.51 E-06 1.45E-07 0. 4.99E-06 o. 2.71 E-05 CD115M 0. 2.60E-06 8.39E-08 0. 2.08E-06 o. 8.23E-05 5N123 4.44E-05 7.29E-07 1.08E-06 5.84E-07 0. 0. 6.71E-05 5N125 + D 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0. 0. 1.12E-04 5N126+D 1.16E-04 2.16E-06 3.30E-06 5.69E-07 0. 0. 2.58E-05 58124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 0. 3.38E-06 7.SOE-05 58125 + D 2.48E-06 2.71 E-08 5.80E-07 2.37E-09 0. 2.1 SE-06 1.93E-05 58126 1.59E-06 3.25E-08 5.71E-07 8.99E-09 0. 1.14E-06 9.41 E-05 58127 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. 0. 1.13E-05 TE127M+D 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0. 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 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0. 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0. 2.45E-07 TE131M + D 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0. 9.39E-05 TE131 +D 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0. 2.29E-09 TE132+D 3.49E-06 2.21 E-06 2.0SE-06 2.33E-06 2.12E-05 0. 7.00E-05 TE133M +D 6.44E-08 3.66E-08 3.56E-08 5.11 E-08 3.62E-07 o. 1.48E-07 TE134+0 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 o. 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 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 0. 1.62E-06 85
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11
ISOTOPE BONE LIVER TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YRl TOT AL BODY THYROID KIDNEY LUNG GI-LU 1132 2. 79E-07 7.30E-07 2.62E-07 2.46E-05 1. 15E-06 0. 3.18E-07 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 6.45E-06 6.1 OE-07 0. 5.1 OE-09 1135 +D 6.1 OE-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 0. 1. 74E-06 XE131 M 0. 0. o. 0. 0. 0. o.
XE133M 0. o. 0. 0. o. 0. 0.
XE133 0. o. o. 0. 0. 0. 0.
XE1~5M 0. 0. 0. 0. 0. 0. 0.
XE135 0. 0. 0. 0. 0. 0. 0.
XE137 0. 0. 0. 0. 0. 0. 0.
XE138+D 0. 0. o. 0. 0. 0. o.
CS134M+D 2.94E-08 6.09E-08 3.13E-08 0. 3.39E-08 5.95E-09 4.05E-08 CS134 8.37E-05 1.97E-04 9.14E-05 0. 6.26E-05 2.39E-05 2.45E-06 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 0. 1.84E-05 2.90E-06 2.72E-06 CS137+D 1.12E-04 1.49E-04 5.19E-05 0. 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 r BA139 1.39E-07 9.78E-11 4.05E-09 0. 9.22E-11 6.74E-11 1.24E-06 BA140+D 2.84E-05 3.48E-08 1.83E-06 0. 1.18E-08 2.34E-08 4.38E-05 BA141 +D 6. 71 E-08 5.01E-11 2.24E-09 0. 4.65E-11 3.43E-11 1.43E-13 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. 0. 0. 9.82E-05 LA141 4.55E-10 1.40E-10 2.31 E-11 0. o. 0. 2.48E-05 LA142 1.79E-10 7.95E-11 1.98E-11 0. 0. 0. 2.42E-06 CE141 1.33E-08 8.88E-09 1.02E-09 0. 4.1 SE-09 0. 2.54E-05 CE143+D 2.35E-09 1.71E-06 1.91E-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 PR144 4.30E-11 1. 76E-11 2.18E-12 0. 1.01E-11 0. 4.74E-14 ND147+D 9.38E-09 1.02E-08 6.11E-10 0. 5.99E-09 0. 3.68E-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 o. 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 3.0SE-10 1.25E-10 0. 5.81 E-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-08 3.94E-09 0. 1.84E-08 0. 5.70E-06 SM153 1.22E-09 1.01 E-09 7.43E-11 o. 3.30E-10 0. 2.85E-05 EU152 2.45E-07 5.SOE-08 5.20E-08 0. 2.74E-07 0. 2.17E-05 EU154 7.91 E-07 1.02E-07 7.19E-08 o. 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 o. 8.07E-09 0. 2.56E-08 0. 4.19E-05 H0166M 3.57E-07 1.10E-07 7.96E-08 0. 1.61E-07 0. 0.
W181 1.42E-08 4.58E-09 4.79E-10 0. o. 0. 3.90E-07 (e'Z185 5.79E-07 1.91E-07 2.02E-08 0. o. 0. 1.65E-05 187 1.46E-07 1.19E-07 4.17E-08 o. 0. 0. 3.22E-05 86
PALISADES ~!JQLEAR PLANT OFFSITE DOSE QALQULATION MANUAL Revision 11
~~ISOTOPE BONE LIVER TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)~~
TOTAL BODY THYROID KIDNEY LUNG Gl*LLI PB210+D 1.81 E-02 5.44E-03 7.01 E-04 0. 1.72E-02 0. 5. 74E-05 81210+ D 6.59E-07 4.51 E-06 5.66E-08 0. 5.48E-05 0. 5.15E-05 P0210 6.09E-04 1.07E-03 1.23E-04 0. 3.60E-03 0. 6. 75E-05 RN222 + D 0. 0. 0. 0. 0. 0. 0.
RA223+D 7 .11 E-03 1.08E-05 1.42E-03 0. 3.1 OE-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 1.1 OE-05 1.87E-03 0. 3.15E-04 0. 3.27E-04 RA226+D 3.22E-01 8.13E-06 2.39E-01 o. 2.32E-04 0. 3.51 E-04 RA228 +D 1.37E-01 4.41 E-06 1.51E-01 0. 1.26E-04 0. 5.98E-05 AC225 6.29E-06 8.59E-06 4.22E-07 0. 9.85E-07 0. 4.36E-04 AC227+D 2.05E-03 3.03E-04 1.22E-04 0. 8.81E-05 0. 8.68E-05 TH227 + D 1.96E-05 3.52E-07 5.65E-07 o. 2.01 E-06 0. 5.75E-04 TH228+ D 6.80E-04 1.14E-05 2.30E-05 o. 6.41 E-05 0. 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 0. 5.99E-04 0. 6.38E-05 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 o. 3.81 E-08 0. 1.21 E-04 PA231 +D 4.31 E-03 1.62E-04 1.68E-04 o. 9.1 OE-04 0. 7 .60E-9,5 PA233 7.33E-09 1.41E-09 1.26E-09 0. 5.32E-09 0. 1.61E-05 U232+D 5.89E-03 0. 4.21 E-04 o. 6.38E-04 0. 7.19E-05 U233+D 1.24E-03 0. 7.543-05 o. 2.90E-04 o. 6.65E-05 U234 1.19E-03 o. 7.39E-05 o. 2.85E-04 0. 6.51E-05 U235 + D 1.14E-03 o. 6.94E-05 o. 2.67E-04 0. 8.28E-05 U236 1.14E-03 0. 7.09E-05 0. 2.73E-04 0. 6.11E-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 1.25E-04 5.85E-05 o. 4.33E-04 o. 8.41 E-05 NP238 1.95E-08 5.22E-10 3.04E-10 0. 1.79E-09 0. 3.83E-05 NP239 1.76E-09 1.66E-10 9.22E-11 o. 5.21 E-10 0. 2.67E-05 PU238 7.21E-04 1.02E-04 1.82E-05 0. 7.SOE-05 0. 7. 73E-05 PU239 8.27E-04 1.12E-04 2.01 E-05 o. 8.57E-05 0. 7.06E-05 PU240 8.26E-04 1.12E-04 2.01 E-05 0. 8.56E-05 0. 7.19E-05 PU241 +D 1.84E-05 9.42E-07 3.69E-07 o. 1. 71 E-06 0. 1.48E-06 PU242 7.66E-04 1.0SE-04 1.94E-05 0. 8.25E-05 0. 6.92E-05 PU244 8.95E-04 1.23E-04 2.22E-05 0. 9.45E-05 0. 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.SOE-05 o. 4.30E-04 o. 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 0. 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 0. 2.84E-04 0. 7.33E-05 o.
CM247+D 1.03E-03 3.27E-04 6.00E-05 0. 2.SOE-04 9.63E-05 CM248 8.60E-03 2.69E-03 4.95E-04 0. 2.31 E-03 0. 1.55E-03 CR252 3.51 E-04 0. 8.37E-06 0. 0. 0. 3.05E-04 87
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11
~~ISOTOPE BONE LIVER TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR}~~
TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 1.0SE-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 BE10 3.1 BE-06 4.91 E-07 7.94E-08 0. 3. 71 E-07 0. 2.68E-05 C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 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. 0. 0. 1.85E-08 NA22 1. 74E-05 1.74E-05 1.74E-05 1.74E-05 1. 74E-05 1. 74E-05 1. 74E-05 NA24 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. 0. 0. 2.17E-05 AR39 0. 0. 0. 0. 0. 0. 0.
AR41 0. 0. 0. 0. 0. 0. 0.
CA41 1.83E-05 0. 2.00E-05 0. 0. 0. 1.84E-07 SC46 5.51E-09 1.07E-08 3.11 E-09 0. 9.99E-09 0. 5.21 E-05 CR51 0. 0. 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. 1.40E-05 MN56 0. 1.15E-07 2.04E-08 0. 1.46E-07 0. 3.67E-06 FE55 2. 75E-06 1.90E-06 4.43E-07 o. 0. 1.06E-06 1.09E-06 FE59 4.34E-06 1.02E-05 3.91 E-06 0. 0. 2.85E-06 3.40E-05 r C057 0. 1. 75E-07 2.91 E-07 0. o. 0. 4.44E-06 C058 0. 7.45E-07 1.67E-06 o. 0. 0. 1.51E-05
.C060 0. 2.14E-06 4.72E-06 o. 0. 0. 4.02E-05 Nl59 9.76E-06 3.35E-06 1.63E-06 o. 0. 0. 6.90E-07 Nl63 1.30E-04 9.01E-06 4.36E-06 0. 0. 0. 1.88E-06 Nl65 5.28E-07 6.86E-08 3.13E-08 0. 0. 0. 1. 74E-06 CU64 0. 8.33E-08 3.91 E-08 o. 2.1 OE-07 0. 7.1 OE-06 ZN65 4.84E-06 1.54E-05 6.96E-06 o. 1.03E-05 0. 9.70E-06 ZN69M+D 1. 70E-07 4.0SE-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 o. 4.55E-06 0. 5.38E-07 BR82 0. 0. 2.26E-06 o. o. 0. 2.59E-06 BR83+0 o. o. 4.02E-08 o. 0. 0. 5.79E-08 BR84 0. 0. 5.21 E-08 0. o. 0. 4.09E-13 8R85 0. o. 2.14E-09 0. 0. 0. 0.
KR83M o. o. 0. o. o. 0. 0.
KR85M 0. o. 0. o. 0. 0. 0.
KR85 0. o. 0. 0. 0. 0. 0.
KR87 0. 0. 0. o. 0. 0. 0.
KR88+D 0. 0. 0. 0. 0. o. 0.
-KR89 o. 0. 0. o. 0. 0. 0.
R886 0. 2.11E-05 9.83E-06 0. 0. 0. 4.16E-06 R887 0. 1.23E-05 4.28E-06 0. o. 0. 5.76E-07 RB88 0. 6.05E-08 3.21 E-08 0. 0. 0. 8.36E-19 RB89+0 o. 4.01 E-08 2.82E-08 o. 0. 0. 2.33E-21 SR89+0 3.0SE-04 0. 8.84E-06 0. 0. 0. 4.94E-05 SR90+0 7.58E-03 o. 1.86E-03 o. 0. 0. 2.19E-04
.91+0 5.67E-06 o. 2.29E-07 o. 0. o. 2.70E-05 92+0 2.1 SE-06 0. 9.30E-08 0. 0. o. 4.26E-05 88
PALl§!ADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11
~~LIVER TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)~~
ISOTOPE BONE TOTAL BODY THYROID KIDNEY LUNG Gl-LLI Y90 9.62E-09 0. 2.58E-10 0. o: 0. 1.02E-04 Y91 M +D 9.09E-11 0. 3.52E-12 0. 0. 0. 2.67E-10 Y91 1.41 E-07 0. 3.77E-09 0. 0. 0. 7.76E-05 Y92 8.45E-10 0. 2.47E-11 0. 0. 0. 1 .48E-05 Y93 2.68E-09 0. 7.40E-11 0. 0. 0. 8.SOE-05 ZR93+D 4.1 BE-08 2.34E-09 1.09E-09 0. 8.87E-09 0. 2.43E-06 ZR95 +D 3.04E-08 9. 75E-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 .OSE-04 NB93M 2.55E-08 8.32E-09 2;05E-09 o.
9.57E-09 0. 3.B4E-06 N895 6.22E-09 3.46E-09 1.86E-09 o. 3.42E-09 0. 2.1 OE-05 N897 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 o. 1.06E-08 3.42E-10 4.13E-07 TC99 1.25E-07 1.86E-07 5.02E-08 0. 2.34E-06 1.58E-08 6.0SE-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 o. 7.06E-07 0. 2.16E-05 RU105 +D 1.54E-08 o. 6.08E-09 o. 1.99E-07 0. 9.42E-06 RU106+D 2.75E-06 o. 3.48E-07 0. 5.31 E-06 0. 1. 78E-0:4
~~RH105 PD107 PD109 AG110M+D AG111 CD113M 1.21E-07 0.~~
o.
1.60E-07 5.81 E-08 0.
8.85E-08 1.47E-07 1.77E-07 1.48E-07 2.43E-08 3.18E-06 5.83E-08 9.40E-09 3.99E-08 8.79E-08 1.21 E-08 1.02E-07 0.
0.
0.
o.
0.
0.
3.76E-07 1.32E-06 1.01 E-06 2.91 E-07 7.84E-08 3.50E-06 0.
0.
o.
0.
0.
0.
1.41 E-05 9.11E-07 1.96E-05 6.04E-05 4.46E-05 2.56E-05 CD115M 0. 1.84E-06 5.87E-08 o. 1.46E-06 0. 7. 74E-05 5N123 3.11E-05 5.15E-07 7.59E-07 4.38E-07 0. 0. 6.33E-05 5N125 + D 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0. 0.
1.04E-04 5N126 + D 8.45E-05 1.67E-06 2.40E-06 4.92E-07 0. 0. 2.43E-05 58124 2.80E-06 5.29E-08 1.11 E-06 6.79E-09 0. 2.18E-06 7.95E-05 58125 + D 1. 79E-06 2.00E-08 4.26E-07 1.82E-09 0. 1.38E-06 1.97E-05 58126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0. 7.05E-07 9.40E-05 58127 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. 1.07E-05 TE125M+D 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2. 75E-05 o. 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 o. 8.68E-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 1.1 SE-08 7.65E-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 o. 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 0. 7.71 E-05 TE133M+D 4.62E-08 2.70E-08 2.SOE-08 3.91 E-08 2.67E-07 o. 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.SOE-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 0. 1.57E-06 89
~~PALISADES N!JQLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11~~
~~ISOTOPE LIVER TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI BONE TOTAL BODY THYROID KIDNEY INGESTED IN FIRST YR)~~
LUNG Gl-LLI 1132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0. 1.02E-07 1133 + D 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 0. 2.22E-06 1134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0. 2.51E-10 1135 + D 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86J:'.-06 o. 1.31 E-06 XE131M 0. 0. 0. 0. 0. 0. 0.
XE133M 0. 0. 0. 0. 0. 0. 0.
XE133 0. 0. 0. o. 0. 0. 0.
XE135M 0. 0. 0. 0. 0. 0. 0.
XE135 0. 0. 0. 0. 0. 0. 0.
XE137 0. 0. 0. 0. 0. 0. 0.
XE138+D 0. 0. 0. 0. 0. 0. 0.
CS134M + D 2.13E-08 4.48E-08 2.29E-08 0. 2.43E-08 3.83E-09 1.58E-08 CS134 6.22E-05 1.48E-04 1.21 E-04 0. 4.79E-05 1.59E-05 2.59E-06 CS135 1.95E-05 1.SOE-05 7.99E-06 0. 6.81 E-06 2.04E-06 4.21 E-07 CS136 6.51 E-06 2.57E-05 1.85E-05 0. 1.43E-05 1.96E-06 2.92E-06 CS137 +D 7.97E-05 1.09E-04 7.14E-05 0. 3.70E-05 1.23E-05 2.11E-06 CS138 6.52E-08 1.09E-07 5.40E-08 0. 8.01 E-08 7.91E-09 4.65E-13 CS139 +D 3.41 E-08 5.08E-08 1.85E-08 o. 4.07E-08 3.70E-09 1.1 OE-30 BA139 9.70E-08 6.91E-11 2.84E-09 0. 6.46E-11 3.92E-11 1. 72E-117
BA140+D BA141 +D BA142+D LA140 LA141 LA142 2.03E-05 4.71 E-08 2.13E-08 2.50E-09 3.19E-10 1.28E-10 2.55E-08 3.56E-11 2.19E-11 1.26E-09 9.90E-11 5.82E-11 1.33E-06 1.59E-09 1.34E-09 3.33E-10 1.62E-11 1.45E-11 0.
0.
0.
0.
0.
0.
8.67E-09 3.31 E-11 1.85E-11 0.
0.
0.
1.46E-08 2.02E-11 1.24E-11 0.
0.
0.
4.1 SE-05 2.22E-17 3.00E-26 9.25E-05 1.1 SE-05 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 0. 2.94E-09 0. 2.42E-05 CE143+D 1.65E-09 1.22E-06 1.35E-10 o. 5.37E-10 0. 4.56E-05 CE144+D 4.88E-07 2.04E-07 2.62E-08 0. 1.21 E-07 0. 1.65E-04 PR143 9.20E-09 3.69E-09 4.56E-10 o. 2.13E-09 0. 4.03E-05 PR144 3.01 E-11 1.25E-11 1.53E-12 0. 7.05E-12 0. 4.33E-18 ND147+D 6.29E-09 7.27E-09 4.35E-10 0. 4.25E-09 0. 3.49E-05 PM147 7.54E-08 7.09E-09 2.87E-09 0. 1.34E-08 0. 8.93E-06 PM148M+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 2.1 SE-10 8.78E-11 o. 4.06E-10 0. 4.03E-05 PM151 6.97E-10 1.17E-10 5.91 E-11 0. 2.09E-10 0. 3.22E-05 SM151 6.90E-08 1.19E-08 2.85E-09 o. 1.33E-08 o. 5.25E-06 SM153 8.57E-10 7.1 SE-10 5.22E-11 o. 2.31E-10 o. 2.55E-05 EU152 1.95E-07 4.44E-08 3.90E-08 0. 2.75E-07 0. 2.56E-05 EU154 6.1 SE-07 7.56E-08 5.38E-08 0. 3.62E-07 0. 5.48E-05 EU155 8.60E-08 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 o. 7.08E-09 0. 7.26E-05 TB160 4.70E-08 0. 5.86E-09 0. 1.94E-08 0. 4.33E-05 1.26E-07 0.
H0166M 2.70E-07 8.43E-08 6.40E-08 0. 0.
W181 9.91 E-09 3.23E-09 3.46E-10 o. 0. 0. 3.68E-07 W185 4.05E-07 1.35E-07 1.42E-08 o. 0. 0. 1.56E-05 W187 1.03E-07 8.61 E-08 3.01 E-08 o. 0. 0. 2.82E-05 90
PALISADES NUgLt;AR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11
~~ISOTOPE BONE LIVER TABLE 2. 1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI TOTAL BODY THYROID KIDNEY INGESTED IN FIRST YR)~~
LUNG Gl-LLI PB210+D 1 .53E-02 4.37E-03 5.44E-04 0. 1.23Ec02 0. 5.42E-05 81210+0 4.61 E-07 3.1 BE-06 3.96E-08 0. 3.83E-05 0. 4. 75E-05 P0210 3.56E-04 7.56E-04 8.59E-05 0. 2.52E-03 0. 6.36E-05 RN222+D 0. 0. 0. 0. 0. 0. 0.
RA223 +D 4.97E-03 7.65E-06 9.94E-04 0. 2.17E-04 0. 3.21 E-04 RA224+D 1.61E-03 3.90E-06 3.23E-04 0. 1.1 OE-04 0. 3.40E-04 RA225 +D 6.56E-03 7.78E-06 1.31E-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 0. 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 0. 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 0. 4.67E-05 0. 5.63E-04 TH229 7.98E-03 1.19E-04 3.91 E-04 o. 5.75E-04 0. 5.12E-04 TH230 2.06E-03 1.17E-04 5.70E-05 0. 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 o. 2.67E-08 0. 1.13E-04 PA231 +D 4.1 OE-03 1.54E-04 1.59E-04 0. 8.64E-04 0. 7.17E-05 5.26E-09 1.06E-09 9.12E-10 0. 3.99E-09 0. 1.64E-05 PA233 U232+D 4.13E-03 0. 2.95E-04 o. 4.47E-04 o. 6.78E-05 U233+D 8. 71 E-04 o. 5.28E-05 o. 2.03E-04 o. 6.27E-05 U234 8.36E-04 0. 5.17E-05 0. 1.99E-04 o. 6.14E-05 U235 + D 8.01 E-04 0. 4.86E-05 0. 1.87E-04 o. 7.81E-05 U236 8.01 E-04 o. 4.96E-05 o. 1.91 E-04 0. 5. 76E-05
_U237 5.52E-8 o. 1.47E-08 o. 2.27E-07 0. 1.94E-05 U238 + D 7.67E-04 o. 4.54E-05 o. 1.75E-04 0. 5.50E-05 NP237 +D 1.37E-03 1.19E-04 5.54E-05 o. 4.12E-04 0. 7.94E-05 NP238 1.37E-08 3.69E-10 2.13E-10 o. 1.25E-09 0. 3.43E-05 NP239 1.19E-09 1.17E-10 6.45E-11 0. 3.65E-10 o. 2.40E-05 PU238 6.80E-04 9.58E-05 1.71E-05 o. 7.32E-05 o. 7.30E-05 PU239 7.87E-04 1.06E-04 1.91 E-05 o. 8. 11 E-05 0. 6.66E-05 PU240 7.85E-04 1.06E-04 1.91 E-05 0. 8.10E-05 0. 6.78E-05 PU241 +D 1.65E-05 8.44E-07 3.32E-07 o. 1.53E-06 o. 1.40E-06 PU242 7.29E-04 1.02E-04 1.84E-05 o. 7 .81 E-05 0. 6.53E-05 PU244 8.52E-04 1. 17E-04 2.11E-05 o. 8.95E-05 0. 9.73E-05 AM241 8.19E-04 2.88E-04 5.41 E-05 o. 4.07E-04 0. 7.42E-05 AM242M 8.24E-04 2.78E-04 5.43E-05 o. 4.05E-04 0. 9.34E-05 AM243 8.18E-04 2.78E-04 5.30E-05 0. 3.99E-04 o. 8.70E-05 CM242 2.06E-05 2.1 OE-05 1.37E-06 o. 6.22E-06 0. 7.92E-05 CM243 6.39E-04 2.41 E-04 3. 75E-05 0. 1. 75E-04 o. 7.81 E-05 CM244 4.83E-04 2.07E-04 2.87E-05 o. 1.34E-04 0. 7.55E-05 CM245 1.02E-03 2.87E-04 5.76E-05 0. 2.69E-04 o. 7.04E-05 CM246 1.01 E-03 2.87E-04 5. 75E-05 0. 2.68E-04 0. 6.91 E-05 o.
CM247+D 9.84E-04 2.83E-04 5.67E-05 0. 2.64E-04 9.09E-05 CM248 8.18E-03 2.33E-03 4.67E-04 o. 2.1 SE-03 o. 1.47E-03 CF252 2.64E-04 0. 6.29E-06 0. 0. 0. 2.88E-04 91
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11
TABLE 2.2 PALISADES Liquid Effluent Design Objective Annual Quantity Design Objective Dose Conversion Annual Quantity Nuclide Half-Life Factors !mrem/Cil Individual/Organ !Curies!
H-3 12.3 yr 1.75E-06 Adult/TB 1.71 E +06 Na-24 15 h 5.44E-03 Teen/TB 551.5 Sc-46 83.9 d 2.02E-02 Teen/TB 148.5 Cr-51 27.8 d 1.56E-03 Adult/GI (LLll 6,410.0 Mn-54 303 d 3.50E-02 Teen/TB 85.7 Fe-55 2.6 yr 4.48E-03 Child/Bone 2,232.0 Mn-56 2.576 h 1.86E-03 Teen/TB 1,612.0 Co-57 270 d 4.39E-03 Teen/TB 683.4 Co-58 71.3 d 1.03E-02 Teen/TB 291.3 r
~~Fe-59 Co-60 Cu-64 Ni-65 Zn-65 45.6 d 5.26 yr 12.8 h 2.56 h 245 d 4.08E-02~~
~~4. 71 E-01 1.32E-03 5.82E-04 1 .83E-01 Adult/GI (LLI)~~
Teen/TB Teen/GI (LLll Teen/TB Teen/TB 245.1 6.37 7,575.0 5, 154.0 16.4 Br-84 31.8 mo 2.02E-03 Teen/TB 1,485.2 Rb-86 1.02 mo 3.06E-01 Child/TB 9.80 Rb-88 17.8 mo 6.92E-04 Teen/TB 4,335.3 Sr-89 52.7 d 1.56E-01 Child/Bone 64.1 Sr-90 27. 7 yr 2. 71 E-00 Adult/Bone 3.69 Sr-91 9.67 h 1.16E-03 Teen/TB 2,586.0 Sr-92 2.71 h 1.51 E-03 Teen/TB 1,986.8 Y-92 3.53 h 2.69E-04 Teen/TB 11,150.0 Nb-95 35 d 7.24E+OO Adult/GI (LLI) 1.38 Zr-95 65.5 d 6.17E-03 Teen/TB 486.2 Nb-97 72 mo 6.95E-04 Teen/TB 4,316.6 Zr-97 17 h 9.28E-04 Teen/TB 3,232.8 Mo-99 66.7 h 1.11 E-03 Teen/Kidney 9,009.0 Tc-99m 6.05 h 1.42E-04 Teen/TB 21,126.8 Ru-103 39.5 d 2.74E-03 Teen/TB 1,094.9 Ag-11 Om 255 d 7.75E-02 Teen/TB 38.7 92
PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11
~~TABLE 2.2 (continued)~~
PALISADES Liquid Effluent Design Objective Annual Quantity Design Objective Dose Conversion Annual Quantity Nuclide Half-Life Factors lmrem/Cil Individual/Organ !Curies)
Cd-113m 13.6 yr 6.02E-02 Adult/GI (LLI) 166.1 Sb-124 60 d 1.51E-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 Te-127m 109 d 1 .39E-01 Teen/Kidney 71.9 Te-129m 34.1 d 2.66E-01 Adult/GI (LLI) 37.6 1-130 12.3 h 1.17E-02 Child/Thyroid 854.7 1-131 8.05 d 3.27E-01 Child/Thyroid 30.6 Te-131 m 30 h 2.27E-01 Adult/GI (LLI) 44.0 r 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 1-133 20.3 h 3.94E-02 Child/Thyroid 253.8 Cs-134 2 yr 2.86E+OO Adult/TB 1.04 1-134 52 mo 2.43E-03 Teen/TB 1,234.0 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+OO 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 1.85E-02 Adult/GI (LLI) 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 Np-239 2.346 d 2.26E-03 Adult/GI (LLI) 4,424.0
93
~~PALISADES NUCLEAR PLANT OFF SITE DOSE CA LC ULA TION MANUAL Revision 11~~
~~111.~~
A.
URANIUM FUEL CYCLE DOSE SPECIFICATION In accordance with Appendix A, Section 111.1.1, if either liquid or gaseous quarterly releases exceed the quantity which would cause offsite doses more than twice the limit of Appendix A, Sections 111.C.1, 111.D.1, or 111.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 11.C.2. 1 and 11.C.2.2. r~~
2. Amount of shore line fishing (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 .
94
~~PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 11~~
~~~---------------------~~
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.
(2., 5) where:
040 = 40 CFR 190 dose (mrem).
DG = Limiting dose to an individual from gaseous source term (mrem).
DL = Limiting dose to an individual from liquid source term {mrem).
~~RT T~~
=
=
Mean dose rate calculated to be applicable to Lake Michigan shoreline adjacent to Plant site (mrem/hr).
Assumed shoreline fishing time for the quarter in questions (hours) .
95

ML18065B201

Text

(~J(F)L Q i s_

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