Text

Radioactive Effluent Release Report, Offsite Dose Calculation Manual, Revision 18
	ML040960097
Person / Time
Site:	Palisades
Issue date:	04/12/2003
From:	; Nuclear Management Co
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML040960097 (110)
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ATTACHMENT 7 RADIOACTIVE EFFLUENT RELEASE REPORT OFFSITE DOSE CALCULATION MANUAL 109 Pages Follow

ODCM Revision 18 Issued Date 4/12/03 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: OFFSITE DOSE CALCULATION MANUAL Date JLBeer I

11/21/02 Technical Reviewer Date t4/A I

User Reviewer Date

/ Z A'3 Plant General Manager -Operations Date

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 Table of Contents GASEOUS EFFLUENTS I

A.

ALARMITRIP SETPOINT METHOD....................................... 1I

1.

Allowable Concentration................................... 2

2.

Monitor Response........................................

3 B.

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

4 C.

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

.21

1.

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

21

2.

Continuous Releases................

22

3.

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

22

4.

Releasing Radionuclides Not Listed in Table 1.9.....................................................

22 D.

OPTIONAL QUARTERLY DOSE CALCULATIONS 23

1.

Methodology for Optional Quarterly Dose Calculations..................................................... 23 E.

GASEOUS RADWASTE TREATMENT SYSTEM OPERATION................. 26

1.

System Description......................................... 26

2.

Determination of Satisfactory Operation....... 27 F.

RELEASE RATE FOR OFFSITE EC.

27 G.

PARTICULATE AND IODINE SAMPLING.

28 H.

NOBLE GAS SAMPLING

............................... 29 I.

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

29 J.

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

30 LIQUID EFFLUENTS 69 A.

CONCENTRATION.....................................................

69

1.

Requirements.................................................... 69

2.

Prerelease Analysis......................................... 69

3.

Effluent Concentration (EC) - Sum of the Ratios....................................................

70

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 Table of Contents B.

INSTRUMENT SETPOINTS 71

1.

Setpoint Determination................................... 71

2.

Composite Samplers....................................... 71

3.

Post-Release Analysis.................................... 72 C.

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

72

1.

RETS Requirement........................................ 72

2.

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

73 D.

OPERABILITY OF LIQUID RADWASTE EQUIPMENT..............................

77 E.

RELEASE RATE FOR OFFSITE EC (50 MREMIYR)..................................

78 F.

FIGURES AND TABLES 79 Ill.

URANIUM FUEL CYCLE DOSE

..................... 100 A.

SPECIFICATION

..................... 100 B.

ASSUMPTIONS 100 C.

DOSE CALCULATION

..................... 101 Appendix A, "Relocated Technical Specification" Appendix B, "Request to Retain Soil in Accordance With 10 CFR 20.302"

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 GASEOUS EFFLUENTS A.

ALARM/TRIP SETPOINT METHOD Appendix A, Section Il.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 III.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 lll.B.1. This section of the ODCM describes the methodology that will be used to 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

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18

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:

RS(k)(F)

C' - < 5.0 (1.1)

QiEQ If gaseous tritium and noble gasses are not present then:

R(k) < 10 where:

C

=

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

EC;

=

The EC of nuclide i from 10 CFR 20, Appendix B, Table 2 R(k)

=

The total EC-fraction for release point k X/Q

=

Most conservative sector site boundary dispersion (sec/m 3) - Table 1.3 F

=

Release flow rate (83,000 cfm = 39.2 m3/sec) for stack monitor considerations; variable for other monitors 2

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 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 5.0.

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-1 33, however. Monitor response for the two categories of monitor is determined as follows:

a.

Normal Release (aged fission gasses)

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

The calibration curve or constant for cpm/pCi/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=bxc (1.2)

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 pCi/cc (or R/hr and gCi/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.

3

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 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.

b)

Exposure pathway is submersion within a cloud of noble gases.

c)

Noble gas radionuclide mix is based on 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.

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 g)

Raw meteorological data consists of wind speed and direction measurements at 10m and temperature measurements at 1Dm and 60m.

h)

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.

o)

The wind speed classes that are used are as follows:

Wind Speed Class Number Range (m/s)

Midpoint (m/s) 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 5

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 p)

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

q)

Terrain effects are not considered.

2)

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:

9x (2) 112 f jk Q P ep j=1 k 1z)

XzkU) (2,rx/n) uJ (1.3) where:

Xi Air concentration of radionuclide i, iCi/m3.

fik

=

Joint relative frequency of occurrence of winds in wind speed class j, stability class k, blowing toward this exposure point, expressed as a fraction.

Q

=

Average release rate of radionuclide i, gcils.

p

=

Fraction of radionuclide remaining in plume.

Yzk

=

Vertical dispersion coefficient for stability class k (m).

Uj

=

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

6

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 x

=

Downwind distance, m.

n

=

Number of sectors, 16.

q

=

Radioactive decay coefficient of radionuclide i, s-1.

27rx/n -

Sector width at point of interest, m.

For determining the total body dose rate:

DTB=; XA DFB, where:

DTB

=

Total body dose rate, mrem/y.

X

=

Air concentration of radionuclide 1, jICi/m3.

DFB=

Total body dose factor due to gamma radiation, mrem/y per ICi/m3 (Table 1.5).

For determining the skin dose rate:

Ds=

Xi (DFSi+1.11DFYi) where:

Ds

=

Skin dose rate, mrem/y.

X

=

Air concentration of radionuclide i, IiCi/m3 DFSj =

Skin dose factor due to beta radiation, mrem/y per jICi/m3 (Table 1.5).

(1.4)

(1.5) 7

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 1.11

=

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

DFY1 =

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

For determining dose rate to a point in air:

Da x(DFYi or DFBI)

(1.6) where:

Da

=

Air dose rate, mrad/yr.

DFBI

=

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.

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.

8

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 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 1Oim and temperature measurements at 1Oim and 60m.

h)

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

i)

Real cow, goat and garden locations are considered.

j)

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

k)

Terrain effects and open terrain recirculation factors are not considered.

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.

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).

9

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18

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:

D= 1 X1o62. XDFliBR (1.7) where:

D

=

Organ dose rate due to inhalation, mrem/y.

Xi

=

Air concentration of radionuclide i, pCi/M3.

DFI1

=

Inhalation dose factor, mrem/pCi (Table 1.7).

BR

=

Breathing rate 1400 m3/y infant; 3700 m3/y child; or 8000 m3/y teen and adult.

1X106 =

pCi/tCi conversion factor.

10

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 b)

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

Gi= 3.15 X10 7 E

fkX

[l-exp-(2Ijtb)J 18 k _1 (2;rX/n)A 1 where:

G

=

Ground concentration of radionuclide i, jICi/m2.

k

=

Stability class.

fk

=

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

Q

=

Average release rate of radionuclide i, gCi/s.

DR

=

Relative deposition rate, m1 (Fig 1.2).

x

=

Downwind distance, m.

n Number of sectors, 16.

2irx/n =

Sector width at point of interest, m.

=

Radioactive decay coefficient of radionuclide i, y-1.

tb

=

Time for buildup of radionuclides on the ground, 15 y.

3.15x107

=

siy conversion factor.

11

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 Corrected Figure 1.2 10-3;.

Corrected January 1977 11!1 i

T i I I 1 1 1 X

i I

Al l

w U-LU a.

LU i

0P V0 R

a-us w

IIW-N H ill A it it I i I III I 1 1 If 10-6 1 -7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Figue 7. Relative Deposition for Ground Lee Releass AII Atmospheric Stability Class) 12

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 For determining the total body or organ dose rate from ground contamination:

DG = (8,760)(1 x 10o6)(0.7)

Gi DFG; (1 *9) where:

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

G

=

Ground concentration of radionuclide i, ACiIm2.

DFGI =

Dose factor for standing on contaminated ground, mrem/h per pCi/m2 (Table 1.8).

8,760 =

Occupation time, h/y.

1X106 pCi/tCi 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:

7 fk Q, DR (r[1 -exp(-AEIte)l +

-e xp (1.10) where:

CV1

=

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

k

=

Stability class.

13

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 fk

=

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

Q

=

Average release rate of radionuclide i, ACi/s.

DR

=

Relative deposition rate, m-(Figure 1.2).

x

=

Downwind distance, m.

n Number of sectors, 16.

2nrx/n =

Sector width at point of interest, m.

r

=

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

MEi

=

Effective removal rate constant, XEi = Xi + Xw, where Xi is the radioactive decay coefficient, h-1, and A is a measure of physical loss by weathering (Xw = 0.0021 h-).

te

=

Period over which deposition occurs, 720 h.

YV

=

Agricultural yield, 0.7 kg/M2.

Biv

=

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

=

Radioactive decay coefficient of radionuclide i, h1.

tb

=

Time for buildup of radionuclides on the ground, 1.31x105 h (15Y).

14

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 p

=

Effective surface density of soil, 240 kg/m2.

3,600 =

s/h conversion factor.

th

=

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:

CV14 =1 X103 X14 (0-11/0.16)

(1.11) where:

CV14 =

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

X14

=

Air concentration of C-14, jiCi/m3.

0.11

=

Fraction of total Plant mass that is natural carbon.

0.16 Concentration of natural carbon in the atmosphere, g/m3.

1x10 3 g/kg conversion factor.

For determining the concentration of H-3 in vegetation:

CVT =1 X 103 XT (0.75)(0.5 /H)

(1.12) where:

CVT

=

Concentration of H-3 in vegetation, PCi/M3.

XT

=

Air concentration of H-3, p.Ci/m 3.

15

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 0.75

=

Fraction of total Plant mass that is water.

0.5

=

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

H

=

Absolute humidity of the atmosphere, g/m.

1x103 =

glkg conversion factor.

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

CMj = CVj FM1 Qf exp (-4i tf)

(1.13) where:

CM1

=

Concentration of radionuclide i (including C-14 and H-3) in milk, AiCi/l.

CV

=

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

FMj

=

Transfer factor from feed to milk for radionuclide i, d/l (Table 1.6).

Qf

=

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

xi

=

Radioactive decay coefficient of radionuclide i, d-1.

tf

=

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

16

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 For determining the organ dose rate from ingestion of green leafy vegetables and milk:

D=1xo0 7 CM iDFiUM (1.14) where:

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

CMi

=

Concentration of radionuclide i in vegetables or milk, pCi/kg (or liters).

DF

=

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

UM

=

Ingestion rate for milk, 330 I/y; for vegetables 26 kg/yr (child), no ingestion by infant.

l1X06 =

pCi/,Ci conversion factor.

d)

Meat Ingestion (Beef)

To calculate the concentration of a nuclide in animal flesh:

C,= Fn, CV1 QO exp (Pts)

(1.15) where:

C

=

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

Ffi

=

Fraction of animal's daily intake which appears in each kg of flesh, days/kg (Table 1.6).

CV1

=

Concentration of radionuclide i in the animal's feed (Equation 1.10).

17

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 Qf

=

Amount of feed consumed by the cow per day, 50 kgld.

ts

=

Average time from slaughter to consumption, 20 days.

To determine the organ dose from ingestion of beef:

Df Cri Dr, U.

(1.16) where:

Dfi

=

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

Uf

=

Ingestion rate of meat for age group, kgly (child-41, teen-65, adult-110).

e)

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

D=Di+DG+DM+Dv+DF (1.17) where:

D

=

Total organ dose rate, mrem/y.

Di

=

Dose rate due to inhalation, mrem/y.

DG

=

Dose rate due to ground contamination, mrem/y.

DM

=

Dose rate due to milk ingestion, mrem/y.

Dv

=

Dose rate due to vegetable ingestion, mrem/y.

DF

=

Dose rate due to beef ingestion, mrem/y.

18

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18

3)

The maximum organ dose rate, maximum total body dose rate, and maximum skin dose rate calculated in the previous section (Sec l.B) 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) 15 millirem to any organ of an individual from iodines and particulates with half-life greater than 8 days (Appendix A,Section III.D.1).

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

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

DE3Q = DA' (Cc)

(1.18) 19

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 where:

DAI

=

Appendix I dose limit (mrem or mrad).

Dc

=

Calculated dose (mrem or mrad).

c

=

Quantity of nuclide resulting in dose Dc (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/DC in the above equation (ie, DC/Cc) is a useful value, since it represents the most limiting dose per unit quantity of each nuclide released. Use of the DC/Cc ratio in quarterly evaluation of offsite dose is discussed in Section D.

Values of Dc/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 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.

20

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18

e.

Gaseous Releases From the Steam Generator Blowdown 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 lodines 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.

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:

X-Ai

<1.0 (1. 19)

I (DBQ)'

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.

21

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18

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 B.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).

System Description

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 leakage outside the system. Explosive mixtures of hydrogen and oxygen have been demonstrated compatible with the system by operational experience over the past 13 years.

26

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18

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 10 CFR 20.1302 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 inhaled or ingested continuously for one year will result in a dose of 50 mrem whole body except for submersion dose isotopes (gaseous tritium and noble gasses) which will results in a dose of 100 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 XIQ, is 2.15E-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.

27

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 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 combined for determination of total activity of particulates and halogens released. Beta and alpha counting also is performed on the particulate filters. Beta yields of the gamma isotopes detected on particulate filters are applied to determine "identified" beta, an the "identified" count rate is subtracted from the observed count rate to give "unidentified" beta. The "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.

28

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 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 [tCi/cc. Sampling and analysis will be performed per Appendix A, Table B-1 requirements.

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.

29

L.

PAUSADES GASEOUS EFFLUMS

'n 5

um Cn z

rm cn COMMN Omf U 0

(Dm 0o I0.

-L CD 0

Inm CD rn 0

0rn 0

I-0z z

a I-

-o E-n a

m CD za 0I-z-I "RE 18Msi AlSo pj? m jWLy Amo 06W F r-oExmAwT!R PALISADES EFFLUENT FLOW PATHS GASEOUS

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.1 PALISADES GASEOUS AND LIQUID SOURCE TERMS, CURIESIYEAR (1)

Nuclide H-3 Kr-85 Kr-85m Kr-87 Kr-88 Ar-41 Xe-1 31m Xe-133 Xe-133m Xe-1 35 Xe-135m 1-131 1-132 1-133 1-134 1-135 Na-24 Cr-51 Mn-54 Co-57 Co-58 Fe-59 Co-60 Se-75 Nb-95 Zr-95 Mo-99 Ru-1 03 Sb-127 Cs-134 Cs-1 36 Cs-1 37 Ba-140 La-1 40 Unidentified beta Gaseous(2) 5.5 4.1 0.12 8.4E-02 2.1E-01 3.1 E-02 2.2 1493 0.43 1.11 0.3 0.025 2.91 E-03 6.5E-03 4.8E-04 1.84E-02 1.5E-06 2.5E-04 4.1 E-04 2.1 E-06 8.6E-04 6.6E-06 1.1E-03 3.7E-06 2.4E-05 4.7E-06 1.5E-07

.3E-07 NA 4.5E-05 NA 2.6E-04 2.8E-07 7.5E-07 3.9E-04 Liquid(2) 159 NA NA NA NA NA NA NA NA NA NA 3.21 E-03 NA 4.7E-05 NA NA NA 3.9E-03 7.8E-03 3.2E-05 2.9E-02 4.1 E-04 1.24E-02 NA 4.53E-04 1.79E-04 NA

.1E-05 3.5E-05 0.7 1.8E-06 1.36E-02 NA 1.1E-04 3.3E-03 (1)

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

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

(2) 31

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.2 BASIC RADIONUCLIDE DATA NUCLIDE I

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 Tritium C-14 N-13 0-19 F-18 NA-24 P-32 AR-41 CR-51 MN-54 MN-56 FE-59 C0-58 C0-60 ZN-69m ZN-69 BR-84 BR-85 KR-85m KR-85 KR-87 KR-88 KR-89 RB-88 RB-89 SR-89 SR-90 SR-91 SR-92 SR-93 Y-90 Y-91m Y-91 Y-92 Y-93 ZR-95 NB-95m NB-95 MO-99 TC-99m HALF-LIFE (days) 4.49E 03 2.09E 06 6.94E-03 3.36E-04 7.62E-02 6.33E-01 1.43E 01 7.63E-02 2.78E 01 3.03E 02 1.07E-01 4.50E 01 7.13E 01 1.92E 03 5.75E-01 3.96E-02 2.21 E-02 2.08E-03 1.83E-01 3.93E 03 5.28E-02 1.17E-01 2.21 E-03 1.24E-02 1.07E-02 5.20E 01 1.03E 04 4.03E-01 1.13E-01 5.56E-03 2.67E 00 3.47E-02 5.88E 01 1.47E-01 4.29E-01 6.50E 01 3.75E 00 3.50E 01 2.79E 00 2.50E-01 LAMBDA (1/s) 1.79E-09 3.84E-12 1.16E-03 2.39E-02 1.05E-04 1.27E-05 5.61 E-07 1.05E-04 2.89E-07 2.65E-08 7.50E-05 1.78E-07 1.12E-07 4.18E-09 1.39E-05 2.03E-04 3.63E-04 3.86E-03 4.38E-05 2.04E-09 1.52E-04 6.86E-05 3.63E-03 6.47E-04 7.50E-04 1.54E-07 7.79E-1 0 1.99E-05 7.10E-05 1.44E-03 3.OOE-06 2.31 E-04 1.36E-07 5.46E-05 1.87E-05 1.23E-07 2.14E-06 2.29E-07 2.87E-06 3.21 E-05 BETA1 (MEV/DIS) 5.68E-03 4.95E-02 4.91 E-01 1.02E 00 2.50E-01 5.55E-01 6.95E-01 4.64E-01 3.86E-03 3.80E-03 8.29E-01 1.18E-01 3.41 E-02 9.68E-02 2.21 E-02 3.19E-01 1.28E 00 1.04E 00 2.53E-01 2.51 E-01 1.32E 00 3.61 E-01 1.36E 00 2.06E 00 1.01E 00 5.83E-01 1.96E-01 6.50E-01 1.95E-01 9.20E-01 9.36E-01 2.73E-02 6.06E-01 1.44E 00 1.17E 00 1.16E-01 1.81 E-0 1 4.44E-02 3.96E-01 1.56E-02 GAMMA' (MEV/DIS) 0.0 0.0 1.02E 00 1.05E 00 1.02E 00 4.12E 00 0.0 1.28E 00 3.28E-02 8.36E-01 1.69E 00 1.19E 00 9.78E-01 2.50E 00 4.16E-01 0.0 1.77E 00 6.60E-02 1.59E-01 2.21 E-03 7.93E-01 1.96E 00 1.83E 00 6.26E-01 2.05E-00 8.45E-05 0.0 6.95E-01 1.34E 00 2.24E 00 0.0 5.30E-01 3.61 E-03 2.50E-01 8.94E-02 7.35E-01 6.06E-02 7.64E-01 1.50E-01 1.26E-01 32

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.2 (continued)

BASIC RADIONUCLIDE DATA 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 NUCLIDE TC-99 TC-104 RU-1 06 TE-132 1-129 1-131 1-132 1-133 1-134 1-135 XE-131m XE-1 33m XE-1 33 XE-135m XE-1 35 XE-1 37 XE-138 CS-134 CS-1 35 CS-136 CS-1 37 CS-138 BA-139 BA-140 LA-140 CE-144 PR-143 PR-144 HALF-LIFE (days) 7.74E 07 1.25E-02 3.67E 02 3.24E 00 6.21E 09 8.05E 00 9.58E-02 8.75E-01 3.61 E-02 2.79E-01 1.18E 01 2.26E 00 5.27E 00 1.08E-02 3.83E-01 2.71E 03 9.84E-03 7.48E 02 1.10E 09 1.30E 01 1.1OE 04 2.24E-02 5.76E-02 1.28E 01 1.68E 00 2.84E 02 1.36E 01 1.20E-02 LAMBDA (1/s) 1.04E-13 6.42E-04 2.19E-08 2.48E-06 1.29E-1 5 9.96E-07 8.37E-05 9.17E-06 2.22E-04 2.87E-05 6.80E-07 3.55E-06 1.52E-06 7.43E-04 2.09E-05 2.96E-03 8.15E-04 1.07E-08 7.29E-1 5 6.17E-07 7.29E-1 0 3.58E-04 1.39E-04 6.27E-07 4.77E-06 2.82E-08 5.90E-07 6.68E-04 BETA' (MEV/DIS) 8.46E-02 1.60E 00 1.01 E-02 1.OOE-01 5.43E-02 1.94E-01 4.89E-01 4.08E-01 6.16E-01 3.68E-01 1.43E-01 1.90E-01 1.35E-01 9.58E-02 3.17E-01 1.77E 00 6.65E-01 1.63E-01 5.63E-02 1.37E-01 1.71 E-01 1.20E 00 8.96E-01 3.15E-01 5.33E-01 9.13E-02 3.14E-01 1.21E 00 GAMMA' (MEV/DIS) 0.0 I.95E 00 0.0 2.33E-01 2.46E-02 3.81 E-01 2.24E 00 6.02E-01 2.59E 00 1.55E 00 2.01 E-02 4.15E-02 4.60E-02 4.32E-01 2.47E-01 1.88E-01 1.10E 00 1.55E 00 0.0 2.15E 00 5.97E-01 2.30E 00 3.53E-02 1.71 E-01 2.31 E 00 1.93E-02 0.0 3.18E 00 1

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

33

USURC CCt4PUT92 CODE -

X~oDfOQ, VERSION 2.0RN W2:901 RUN DATE: 970513

- PALISAWES X0QWQ82 "**9 US1143 (1/01/92 -

12/31/96 MET DATA **

GROUND LEVEL RELEASE - TOP OF CONT1ADNME BUiILDIN3 NO~ DECAY, UNDEPLETED ANNUAL AVERAGE CHt/Q (SECo/MTEA CUBED)

SECTOR 0.250 O.5O 0.750 DISTANCS IIJ MILES FROM THE SITE 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S

4.208E-06 1.381E-06 7.556B-07.4.993E-07 2.782E-07 1.842E-07 1.340E-07 1.033B-07 8.298E-08 6.8673-08 5.813E-08 ssw 3.330E-06 1.086E-06 5.856E-07 3.870B-07 2.160E-07 1.437E-07 1.048E-07 8.108E-O-06.528z-08 5.413E-08 4.590E-08 sW 3.890E-06 1.2422-06'6.590E-07 4.333E-07 2.413E-07 1.614E-07 1.184E-07 9.203e-08 7.440E-08 6.1918-08 5.267E-08 WSW 4.060e-06 1.279E-06 6.715E-07 4.4012-07 2.450E-07 1.64SE-07 1.21SE-07 9.484e-08 7.694E-08 6.422E-08 5.477e-08 W

5.554E-06 1.759E-06 9.2248-07 6.035e-07 3.349e-07 2.2492-07 1.657E-07 1.292E-07 1.047E-07 8.735E-08 7.447E-08 WNW 7.378E-06 2.346E-06 1.235E-06 8.084E-07 4.487E-07 3.010E-07 2.216E-07 1.726E-07 1.399E-07 1.166E-07 9.937e-08 NW 9.531E-06 2.974e-06 1.551E-06 1.012E-06 5.610E-07 3.784E-07 2.8002-07 2.191E-07 1.781E-07 1.490e-07 1.273E-07 NNW 1.286E-05 3.9598-06 2.052E-06 1.339E-06 7.443E-07 5.039E-07 3.741E-07 2.9352-07 2.391E-07 2.003E-07 1.715E-07 N

1.0872-05 3.347E-06 1.7392-06 1.13SE-06 6.348E-07 4.300E-07 3.192E-07 2.504E-07 2.040E-07 1.709E-07 1.4622-07 NNe 5.487E-06 1.717E-06 9.119E-07 6.000E-07 3.353E-07 2.256E-07 1.664e-07 1.2998-07 1.054E-07 8.793E-08 7.5012-08 NE 5.45O2-06 1.803E-06 9.856E-07 6.476E-07 3.578E-07 2.3552-07 1.705e-07 1.310E-07 1.049E-07 8.657E-08 7.312E-08 ENE 4.2582-06 1.379E-06 7.464e-07 4.986E-07 2.697E-07 1.773E-07 1.2822-07 9.8502-08 7.885E-08 6.507E-08 5.496E-08 E

4.618E-06 1.5312-06 8.321E-07 5.438e-07 2.990E-07 1.959B-07 1.413B-07 1.0822-07 8.645e-08 7.120e-08 6.002E-08.

ese 4.436e-06 1.479E-06 8.008B-07 5.210E-07 2.8483-07 1.8602-07 1.338B-07 1.023E-07 8.153E-08 6.704E-08 5.6442-08 SE 5.091E-06 1.679E-06 9.044E-07 5.872E-07 3.2073-07 2.096E-07 1.509E-07 1.155E-07 9.217E-08 7.586E-08 6.391E-08 SSZ 6.044E-06 2.0008-06 1.088E-06 7.106E-07.3.901E-07 2.557z-07 1.845E-07 1.415E-07 1.131E-07 9.317E-08 7.858E-08 ANNUAL AVERAGE CFI/VQ (SC/METER CUBED)

DISTANCE IN MILES FRC1 TffE SITE SsT0R 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 Ct wa, I-m

A CD U),

0' 0

C,n

'ii 0

CO) m I-0 zi z

a r-m CA, z

a 0~

I-z

-i S

.SSW SW WSW.

WN NW.

NW N2 DE SSE 5.010E-08 2.837E-08 1.901E-08 1.086E-08 7.322E-09 5.410E-09 4.227B-09 3.433E-09 2.869E-09 2.450E-09 2.127E-09 3.963E-08 2.257e-08 1.519E-08 8.72SE-09 5.913E-09 4.3798-09 3.431E-09 2.793E-09 2.338E-09 2.0008-09 1.740E-09 4.5603-08 2.627E-08 1.782E-08 1.037E-08 7.086E-09 5.284E-09 4.163E-09 3.40SE-09 2.863E-09 2.458E-09 2.1452-09 4.7532-08 2.763E-08 1.886E-08 1.106E-08 7.602E-09 S.693e-09 4.501E-09 3.693E-09 3.113E-09 2.679E-09 2.342E-09 6.459E-08 3.749E-08 2.557E-08 1.498E-08 1.029E-08 7.706E-09 6 091E-09 4.996E-09 4.211E-09 3.623E-09 3.168E-09 8.61SE-08 4.992E-08 3.4002-08 1.9989-08 1.3642-08 1.021E-08 8.0592-09 6.606E-09 5.56SE-09 4.785E-09 4.183E-09 1.106E-07 6.471E-08 4.4362-08 2.618E-08 1.808B-08 1.359E-08 1.077E-08 8.857E-09 7.481E-09 6.4492-09 5.649E-09.

1.492E-07 8.772e-08 6.035E-08 3.579E-08 2.479B-08 1.867E-08 1.483E-08 1.2212-08 1.033E-08 8.91SE-09 7.817E-09 1.273E-07 7.475E-08 5.139E-08 3.045E-08 2.107E-08 1.586E-08 1.259E-08 1.036E-08 8.762E-09 7.559E-09 6.62SE-09, 6.508E-08 3.782E-08 2.591E-08 1.5132-09 1.039E-08 7.781E-09 6.148E-09 5.042E-09 4.248E-09 3.654E-09 3.194E-09 6.2912-08 3.539E-08 2.361E-08 1.342E-08 9.0332-09 6.656E-09 5.193E-09 4.213E-09 3.517E-09 3.OOOE-09 2.604e-09 4.729E-08 2.66SE-08 1.781E-08 1.01SE-08 6.847E-09 5.056E-09 3.951E-09 3.211E-09 2.6842-09 2.293E-09 1.993E-09 5.155E-08 2.883B-08 1.91sE-08 1.083E-08 7.262E-09 5.3373-09 4.155e-09 3.366e-09 2.806E-09 2.392E-09 2.0742-09 4.843E-08 2.6983-08 1.7992-08 1.007E-08 6.742E-09 4.948e-09 3.8482-09 3.1142-09 2.594E-09 2.210E-09 1.91SE-09 5.498E-08 3.0693-08 2.0398-08 1.154E-08 7.7489-09 5.7028-09 4.4452-09 3.604E-09 3.008E-09 2.5666-09 2.227E-09 6.753E-09 3.785E-08 2.5192-08 1.4282-08 9.5952-09 7.064E-09 5.507E-09 4.466E-09 3.727E-09 3.179E-09 2.758E-09 VENT1 AND BUIfLDIN PARAMETERS:

RELEASE H{EIGH'Ir (METERS)

DIA11METE (HETERS)

REIT VE0CITY WMTERS) 58.10 0.00 0.00 REP. WMN HEIGHT BUILDING HEIGHT'

.MIN.CRS.SEL. AREA HEAT DIISSIctI RATE INETERS)

(mEPs)

(SQ.METERS)

MCAWIS=

10.0 59.1 2000.0 0.0 ALL G F

LEVEL RELEASES.

USNRC COctlT4JER. CODE -

XOQtOQ.

VERSION 2.*0 RNDT:901 RUH DATE: 970513 PALISADES XOQED0Q82 ***** USING 01/01/92 -

12/31/96 HET DATA **^**

GROUND LEVEL RELEASE -

TOP OF CONTADNMENT BUILDING NO DECAY, UNDEPLETED CHI/Q (SEIMECnE CUBED) FOR EACH SEGMENT SEGNENT lBOUNDARIES IN NILES FROM THE SITE 1-2 2-3 3-4 4-5 5-10 10-20 20-30 DIRECTION

.5-1 FROM SITE S

7.808E-07 SSW 6.085E-07 SW 6.883E-07 WSW 7.038E-07 W

9.666E-07 WNW 1.292E-06 NW 1.627E-06 NNw 2.159E-06 N

1.829E-06 NNE 9.521E-07 NE 1.017E-06 ENE 7.724E-07 E

8.592E-07 ESE 8.271E-07 SE 9.353E-07 SSE 1.123E-06 2.8562-07 2.219E-07 2.484E-07 2.527E-07 3.457E-07 4.630E-07 5.800E-07 7.695E-07 6.557E-07 3.454E-07 3.678E-07 2.773E-07 3.076B-07 2.9342-07 3.3052-07 4.016E-07 1.351E-07 1.057E-07 1.193E-07 1.224E-07 1.6698-07 2.232E-07 2.819E-07 3.765E-07 3.212E-07 1.676E-07 1.720E-07 1.294E-07 1.426E-07 1.351E-07 1.524E-07 1.863E-07 8.334E-08 6.555E-08 7.468E-08 7.721E-08 1.051E-07 1.404E-07 1.787E-07 2.399E-07 2.046E-07 1.057E-07 1.054E-07 7.922E-08 8.686E-08 8.193E-08 9.262E-08 1.136E-07 5.828E-08 4.602E-08 5.279E-08 5.489E-08 7.463E-08 9.958E-08 1.276E-07 1.718E-07 1.465E-07 7.516E-08 7.332E-08 5.511E-08 6.020E-08 5.661E-08 6.411E-08 7.881E-08 2.904E-08 2.308E-08 2.681E-08 2.815E-08 3.821E-08 5.089E-08 6.587E-08 8.923E-08 7.604E-08 3.854E-08 3.627E-08 2.731E-08 2.958E-08 2.770E-08 3.149E-08 3.882E-08 1.110E-08 8.912E-09 1.057E-08 1.126E-08 1.525E-08 2.025E-08 2.662E-08 3.636E-08 3.093E-08 1.540E-08 1.374E-08 1.038E-08 1.109E-08 1.033E-08 1.182E-08 1.462E-08 5.448E-09 4.409E-09 5.316E-09 5.725E-09 7.7492-09 1.026E-08 1.366E-08 1.877E-08 1.594E-08 7.825E-09 6.704E-09 5.092E-09 5.378E-09 4.986E-09 5.745E-09 7.116E-09 30-40 3.445E-09 2.802E-09 3.415E-09 3.703E-09 5.010E-09 6.625E-09 8.879E-09 1.224E-08 1.039E-08 5.056E-09 4.227E-09 3.222E-09 3.378E-09 3.126E-09 3.617E-09 4.482E-09 40-50 2.454E-09 2.004E-09 2.462E-09 2.683E-09 3.629E-09 4.793E-09 6.458E-09 8.928E-09 7.569E-09 3.660E-09 3.006E-09 2.298E-09 2.397E-09 2.214E-09 2.571E-09 3.186E-09 w

v I-m CD 0

co 0

0Co m

0a z

I-la m

CD za C.

I-z-4

USNRC COM4PUTER CODE -

XOQDCOQ, VERSION 2.0 RUN DATE: 970513

- - '* PALISADES XDQDCQ82 ***** US3NG 01/01/92 -

12/31/96 MET DATA *****

GROU1ND LEVEL RELEASE - TOP OF CONTADNMENT BUILDING 2.260 DAY DECAY, UNDEPLETED ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)

SECTOR 0.250 0.500 0.750 DISTANCE IN MILES FROM THE SI7 1.000 1.500 ' 2.000 2.500 S

SSW SW WSW NW NNW N

NNE NqE ESE SE2 4.205E-06 1.379E-06 7.540E-07 4.979E-07 2.769E-07 3.327E-06 1.084E-06 5.842E-07 3.858E-07 2.150E-07 3.887E-06 1.240E-06 6.575E-07 4.319E-07 2.402E-07 4.057E-06 1.277E-06 6.699E-07 4.388E-07 2.439E-07 5.550E-06 1.757E-06 9.203E-07 6.016E-07 3.334E-07 7.373E-06 2.343E-06 1.232E-06 8.062E-07 4.468E-07 9.524E-06 2.969E-06 1.547E-06 1.009E-06 5.585E-07 1.285E-05 3.953E-06 2.047E-06 1.335E-06 7.408E-07 1.087E-05 3.341E-06 1.735E-06 1.134E-06 6.316E-07 5.483E-06 1.714E-06 9.099E-07 5.982E-07 3.338E-07 5.447E-06 1.800E-06 9.837E-07 6.458E-07 3.563E-07 4.255E-06 1.377E-06 7.448E-07 4.872E-07 2.685E-07 4.615E-06 1.528E-06 8.303E-07 5.423E-07 2.977E-07 4.433E-06 1.477E-06 7.992E-07 5.196E-07 2.837E-07 5.088E-06 1.676E-06 9.026E-07 5.856E-07 3.194E-07 6.040E-06 1.997E-06 1.086E-06 7.087E-07 3.885E-07 1.831E-07 1.330E-07 1.428E-07 1.04OE-07 1.604E-07 1.175E-07 1.637E-07 1.206E-07 2.235E-07 1.644E-07 2.993E-07 2.200E-07 3.761E-07 2.779E-07 5.008E-07 3.712E-07 4.271E-07 3.165E-07 2.242E-07 1.652E-07 2.343E-07 1.693E-07 1.763E-07 1.273E-07 1.948E-07 1.403E-07 1.850E-07 1.328E-07 2.085E-07 1.499E-07 2.543E-07 1.833E-07 E

3.000 3.500 4.000 4.500 1.024E 07 8.212E-08 6.785E-08 5.735E-08 8.032E-08 6.457E-08 5.346E-08 4.526E-08 9.117E-08 7.359E-08 6.114E-08 5.193E-08 9.394E-08 7.609E-08 6.341E-08 5.400E-08 1.280E-07 1.036E-07 8.628E-08 7.344E-08 1.712E-07 1.385E-07 1.153E-07 9.810E-08 2.171E-07 1.762E-07 1.472E-07 1.256E-07 2.907E-07 2.365E-07 1.979E-07 1.691E-07 2.478E-07 2.016E-07 1.686E-07 1.440E-07 1.287E-07 1.042E-07 8.687E-08 7.398E-08 1.299E-07 1.039E-07 8.564E-08 7.223E-08 9.763E-08 7.804E-08 6.431E-08 5.423E-08 1.073E-07 8.559E-08 7.039E-08 5.925E-08 1.014E-07 8.075E-08 6.631E-08 5.575E-08 1.145E-07 9.128E-08 7.502E-08 6.312E-08 1.403E-07 1.120E-07 9.213E-08 7.760E-08 0) m rm

-1 ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)

DISTANCE IN MILES FROIM 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 S

4.936E-08 2.7742-08 1.845E-08 1.039E-08 6.911E-09 5.029E-09 3.874E-09 3.103E-09 2.557E-09 2.153E-09 1.844E-09 SSW 3.901E-08 2.204E-08 1.472E-08 8.327E-09 5.555E-09 4.051E-09 3.126E-09 2.506E-09 2.067E-09 1.742E-09 1.492E-09 SW 4.489E-08 2.566E-08 1.727E-08 9.893E-09 6.657E-09 4.889E-09 3.793E-09 3.056E-09 2.531E-09 2.140E-09 1.840E-09 WSW 4.678E-08 2.698E-08 1.827E-08 1.055E-08 7.141E-09 5.267E-09 4.101E-09 3.314E-09 2.751E-09 2.332E-09 2.009E-09 W

6.361E-08 3.664E-08 2.480E-08 1.431E-08 9.688E-09 7.147E-09 5.566E-09 4.500E-09 3.738E-09 3.170E-09 2.732E-09 WNW 8.494E-08 4.886E-08 3.304E-08 1.906E-08 1.289E-08 9.508E-09 7.405E-09 5.987E-09 4.975E-09 4.220E-09 3.639E-09 NW 1.090E-07 6.323E-08 4.301B-08 2.500E-08 1.700E-08 1.259E-08 9.836E-09 7.972E-09 6.638E-09 5.641E-09 4.872E-09 NNW 1.469E-07 8.570E-08 5.851B-08 3.417E-08 2.331E-08 1.730E-08 1.354E-08 1.099E-08 9.164E-09 7.7962-09 6.739E-09 N

1.2512-07 7.285E-08 4.966E-08 2.893E-08 1.969E-08 1.458E-08 1.139Z-08 9.223E-09 7.674E-09 6.516E-09 5.622E-09 NNE 6.410E-08 3.697E-08 2.5042-08 1.446E-08 9.786E-09 7.218E-09 5.620E-09 4.541E-09 3.771E-09 3.196E-09 2.754E-09 NE 6.206E-08 3.468E-08 2.298E-08 1.289E-08 8.558E-09 6.223E-09 4.791E-09 3.836E-09 3.160E-09 2.662E-09 2.280E-09 ENE 4.659E-08 2.607E-08 1.7292-08 9.711E-09 6.459E-09 4.7022-09 3.624E-09 2.904E-09 2.395E-09 2.018E-09 1.730E-09 E

5.0822-08 2.822E-08 1.861E-08 1.037E-08 6.861E-09 4.973E-09 3.819E-09 3.051E-09 2.509E-09 2.110E-09 1.805E-09 ESE 4.776E-08 2.643E-08 1.739E-08 9.664E-09 6.380E-09 4.619E-09 3.544E-09 2.8302-09 2.327E-09 1.956E-09 1.673E-09 SE 5.413E-08 3.005E-08 1.983E-08 1.106E-08 7.329E-09 5.3202-09 4.0912-09 3.273E-09 2.695E-09 2.268E-09 1.943E-09 SSE 6.6592-08 3.706E-08 2.449E-08 1.369E-08 9.073E-09 6.588E-09 5.066E-09 4.053E-09 3.337E-09 2.808E-09 2.404E-09

_C 0

cn m

00cn ni I-0z z

a r-m w

z C)

I-m

a z-Z VENT AND BUILDING PARAHETERS

RELEASE HEIGHTr (METERS)

DIAMETER (METERS)

EXIT VELOCrrf (MEMERS) 58.10 0.00 0.00 REP. WIND HEIGHT BUILDING HEIGHT BLDG.MIN.CFS.SEC.AREA HEAT EMISSION RATE (MEES)

(HETERS)

(SQ.HL'rERS)

(CAL/SEC) 10.0 58.1 2000.0 0.0 ALL GRCOND LEVEL RELEASES.

USNRC COMPUTER CODE -

XOQDOQ, VERSION 2.0 RUN DATE: 970513

- - - - PALISADES X0QDOQ82 ***** USING 01/01/92 - 12/31/96 MET DATA *****

GROUND LEVEL RELEASE - TOP OP CCNTAINMENT BUILDING 2.260 DAY DECAY, UNDEPLETED CHI/Q (SEC/MTER CUBED) FOR EACH SBENWT SEOMENT BOUNDARIES IN MILES FROM THE SITE 1-2 2-3 3-4 4-5 5-10 10-20 DIRECTION

.5-1 FR4 SITE S

7.791E-07 SSW 6.072E-07 SW 6.867E-07 WSW 7.022E-07 W

9.645E-07 WNW 1.290E-06 NW 1.624E-06 NNW 2.154E-06 N

1.82SE-06 NNE 9.500E-07 NE 1.015E-06 ENE 7.708E-07 E

8.574B-07 ESE 8.255E-07 SE 9.335E-07 SSE 1.121E-06 2.843E-07 2.209E-07 2.473E-07 2.516E-07 3.441E-07 4.611E-07 5.775E-07 7.661E-07 6.524E-07 3.438E-07 3.664E-07 2.761B-07 3.063E-07 2.922E-07 3.292E-07 4.000E-07 1.341E-07 1.049E-07 1.184E-07 1.214E-07

1.

656E-07 2.216E-07 2.798E-07 3.736E-07 3.185E-07 1.663E-07 1.709E-07 1.2853-07 1.416E-07 1.342E-07 1.514E-07

1.

850E-07 8.248E-08 6.484E-08 7.387E-08 7.636E-08 1.040E-07 1.390E-07 1.768E-07 2.373E-07 2.022E-07 1.046E-07 1.044E-07 7.840B-08 8.600E-08 8.115E-08 9.173E-08

1.

125E-07 5.750E-08 4.537E-08 5.205E-08 5.412E-08 7.360E-08 9.832E-08 1.258E-07 1.694E-07 1.443E-07 7.414E-08 7.244B-08 5.439E-08 5.943E-08 5.592E-08 6.332E-08 7.783E-08 2.842E-08 2.256E-08 2.621E-08 2.751E-08 3.737E-08 4.985E-08 6.441E-08 8.722E-08 7.415E-08 3.770E-08 3.5573-08 2.673E-08 2.897E-08 2.715E-08 3.0863-08 3.804E-08 1.064E-08 8.515E-09 1.010E-o8 1.075E-08 1.459E-08 1.942E-08 2.545E-08 3.475E-08 2.943E-08 1.473E-08 1.321E-08 9.950E-09 1.064Z-08 9.921E-09 1.135E-08 1.404E-08 20-30 5.069E-09 4.082E-09 4.922E-09 5.300E-09 7.192E-09 9.569E-09 1.267E-08 1.740B-08 1.466E-08 7.263E-09 6.272E-09 4.739E-09 5.015E-09 4.659E-09 5.364E-09 6.642E-09 30-40 3.115E-09 2.516E-09 3.066E-09 3.324E-09 4.514E-09 6.007E-09 7.996E-09 1.102E-08 9.251E-09 4.556E-09 3.851E-09 2.916E-09 3.064E-09 2.842E-09 3.286E-09 4.070E-09 40-50 2.158E-09 1.746E-09 2.145E-09 2.337E-09 3.176E-09 4.229E-09 5.651E-09 7.810E-09 6.528E-09 3.203E-09 2.668E-09 2.023E-09

2. 11SE-09 1.961E-09 2.274E-09 2.81SE-09 4

I-m

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I i.

I I

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USNRC Co3PUrER COCF. -

XOQDOQ, VERSION 2.0 RUN DATE: 970513

^**^ PALISADES XDQDOQ82 ***** USING 01/01/92 -

12/31/96 MET DATA *****

GROUND LEVEL RELEASE -

TOP OF COMTArNMENT BtunLDif3 8.000 DAY DECAY, DEPLETED ANNtUAL AVERAGE CHI/Q (SEC/METER CUBED)

SECTOR 0.250 0.500 0.750 DISTANCE IN MILES FR1M THE SITE 1.000 1.500,

2.000 2.500 3.000 3.500 4.000 4.500 S

SSW SW WSW w

NW NNW ENE SE SSE 3.982E-06 1.261E-06 6.730E-07 3.150E-06 9.913E-07 5.215E-07 3.681E-06 1.134E-06 5.869E-07 3.842E-06 1.168E-06 5.980E-07 5.256E-06 1.606E-06 8.215E-07 6.982E-06 2.141E-06 1.100E-06 9.018E-06 2.715E-06 1.381E-06 1.217E-05 3.6133-06 1.827E-06 1.029E-05 3.055E-06 1.549E-06 5.192E-06 1.567E-06 8.121E-07 5.157E-06 1.646E-06 8.778E-07 4.029E-06 1.259E-06 6.648E-07 4.3703-06 1.397E-06 7.410E-07 4.198E-06 1.350E-06 7.132E-07 4.817E-06 1.532E-06 8.055E-07 5.719E-06 1.826E-06 9.6918-07 4.367E-07 2.359E-07 1.523E-07 3.384E-07 1.832E-07 1.187E-07 3.789E-07 2.047E-07 1.334E-07 3.849E-07 2.078E-07 1.362E-07 5.278E-07 2.841E-07 1.859E-07 7.071E-07 3.806E-07 2.488B-07 8.848E-07 4.758E-07 3.128E-07 1.171E-06 6.312E-07 4.165E-07 9.954E-07 5.384E-07 3.554E-07 5.248E-07 2.844E-07 1.865E-07 5.664E-07 3.035E-07 1.9478-07 4.273E-07 2.287E-07 1.466E-07 4.756E-07 2.536B-07 1.620E-07 4.557E-07 2.416E-07 1.538E-07 5.136E-07 2.7208-07 1.733E-07 6.216E-07 3.309E-07 2.114E-07 1.083E-07 8.1868-08 6.456E-08 8.473E-08 6.423E-08 5.078E-08 9.572E-08 7.291E-08 5.787E-08 9.823E-08 7.513E-08 5.985E-08 1.339E-07 1.023E-07 8.146E-08 1.791E-07 1.368E-07 1.088E-07 2.263E-07 1.736E-07 1.386E-07 3.024E-07 2.325E-07 1.860E-07 2.579E-07 1.983E-07 1.586E-07 1.345E-07 1.0298-07 8.196E-08 1.378E-07 1.038E-07 8.162E-08 1.037E-07 7.804E-08 6.135E-08 1.142E-07 8.576E-08 6.727E-08 1.081E-07 8.103E-08 6.344E-08 1.220E-07 9.152E-08 7.172E-08 1.492E-07 1.121E-07 8.799E-08 5.254E-08 4.141E-08 4.736E-08 4.912E-08 6.682E-08 8.923E-08 1.140E-07

1. 532E-07 1.307E-07 6.727E-08 6.625E-08 4.979E-08 5.449E-08 5.130E-08 5.805E-08 7.129E-08 4.378E-08 3.457E-08 3.966E-08 4.125E-08 5.608E-08 7.486E-08 9.588E-08 1.291E-07 1.101E-07 5.649E-08 5.509E-08 4.139E-08 4.522E-08 4.252E-08 4.815E-08 5.920E-08

-4a)

I-m C;1 AN;UAL AVERAGE CHI/Q (SEC/METER CnUED)

DISTANCE IN MILES FRIO 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 C

0i.

co 0

In CO) m a0 C,)

m 0

z z

a I-E-

CO)

D m

z a0 I-m 5I zIl S

SSW SW WSW NW NNWI N

NNE NIE EN 35 3.719E-08 1.987E-08 1.266E-08 2.941E-08 1.580E-08 1.011E-08 3.384E-08 1.840E-08 1.187E-08 3.527E-08 1.935E-08 1.256E-08 4.794E-08 2.626E-08 1.703E-08 6.396E-08 3.498E-08 2.266E-08 8.212E-08 4.532E-08 2.954E-08 1.107E-07 6.143E-08 4.019E-08 9.439E-08 5.231E-08 3.419E-08 4.831E-08 2.649E-08 1.719E-08 4.671E-08 2.481E-08 1.574E-08 3.510E-08 1.867E-08 1.186E-08 3.827E-08 2.020E-08 1.276E-08 3.596E-08 1.891E-08 1.192E-08 6.668E-09 4.208E-09 5.355E-09 3.392E-09 6.362E-09 4.065E-09 6.786E-09 4.361E-09 9.195E-09 5.907E-09 1.222E-08 7.839E-09 1.607E-08 1.037E-08 2.196E-08 1.422E-08 1.866E-08 1.207E-08 9.289E-09 5.967E-09 8.249E-09 5.194E-09 6.231E-09 3.932E-09 6.651E-09 4.172E-09 6.190E-09 3.875E-09 2.931E-09 2.370E-09 2.860E-09 3.081E-09 4.173E-09 5.533E-09 7.352E-09 1.011E-08 8.564E-09 4.214E-09 3.612E-09 2.740E-09 2.894E-09 2.684E-09 3.093E-09 3.831E-09 2.174E-09 1.683E-09 1.345E-09 1.762E-09 1.367E-09 1.094E-09 2.138E-09 1.667E-09 1.340E-09 2.311E-09 1.807E-09 1.457E-09 3.130E-09 2.448E-09 1.973E-09 4.148E-09 3.241E-09 2.612E-09 5.531E-09 4.335E-09 3.502E-09 7.617E-09 5.980E-09 4.836E-09 6.449E-09 5.058E-09 4.087E-09 3.160E-09 2.470E-09 1.991E-09 2.676E-09 2.070E-09 1.653E-09 2.032E-09 1.574E-09 1.259E-09 2.139E-09 1.652E-09 1.317E-09 1.981E-09 1.529E-09 1.219E-09 2.288E-09 1.769E-09 1.413E-09 2.836E-09 2.192E-09 1.750E-09 1.102E-09 8.973E-10 1.103E-09 1.202E-09 1.628E-09 2.154E-09 2.894E-09 4.002E-09 3.379E-09 1.642E-09 1.353E-09 1.031E-09 1.077E-09 9.955E-10 1.156E-09 1.432E-09 9.195E-10 7.499E-10 9.248E-10 1.010E-09 1.368E-09 1.810E-09 2.436E-09 3.371E-09 2.844E-09 1.379E-09 1.129E-09 8.614E-10 8.971E-10 8.292E-10 9.641E-10 1.194E-09 S8 4.075E-08 2.150E-08 1.359E-08 7.089E-09 4.453E-09 SSE 5.014E-08 2.653E-08 1.679E-08 8.772E-09 5.515E-09 VENT AND BUILDING3 PARAMETERS:

IEL.EASE MEIGHT (1ETERS)

DIAMETER (HMrERS)

EXIT VELOCITY (METERS) 58.10 0.00 0.00 REP. WIND HEIGHT BUIrLDr HEIGHT ELDG.MIN.CRS. SEC.AREA IMAT EHISSION RATE METrERS)

(METERS)

(sQ.HETERS)

(CAL/SEC) 10.0 58.1 2000.0 0.0 ALL GROUN LEVEL RELEASES.

USNM' CC4R' CODE -

XOQDOQ, VERSIOtN 2.0 RUN DATE: 970513

- - -* PALISADES X0QDoQ82 ***** USI?3,01/01/92 - 12/31/96 Mr DATA *****

GRWUND LEVEL RELEASE - TOP OF CONTAMUM BUILDIM 8.000 DAY DMAY, DEPLETED OCI/Q (SEC!/HFER CUaED) FOR EAOC SENT SBE2M BOUNDARIES IN HILES FR4 THE SITE 1-2 2-3 3-4 4-5 5-10 10-20 DIRECTION

.5-1 FRO SITE S

6.986E-07 SSW 5.445E-07 SW 6.160E-07 WSW 6.299E-07 W

8.653E-07 WNW 1.157E-06 NW 1.457E-06 NM 1.932E-06 N

1.637E-06 NNE 8.521E-07 NE 9.101E-07 ENE 6.913E-07 B

7.689E-07 ESE 7.403e-07 SE 8.371E-07 SSE.

1.005E-06 2.434E-07 1.891E-07 2.117E-07 2.153E-07 2.946E-07 3.946E-07 4.943E-07 6.557E-07 5.586E-07 2.943E-07 3.136E-07 2.364E-07 2.622E-07 2.502E-07

2. 818B-07 3.424E-07 1.094E-07 8.560E-08 9.664E-08 9.911E-08 1.351E-07 1.808E-07 2.283E-07 3.049E-07 2.601E-07 1.357E-07 1.394E-07 1.049E-07 1.156E-07 1.09SE-07 1.235E-07 1.510E-07 6.492E-08 5.105E-08 5.816E-08 6.013E-08 8.184E-08 1.094E-07 1.392E-07 1.868E-07 1.593E-07 8.234E-08 8.210E-08 6.171E-08 6.768E-08 6.384E-08 7.217E-08 8.852E-08 4.393E-08 3.468E-08 3.979E-08 4.137E-08 5.625E-08 7.508E-08 9.614E-08 1.295E-07 1.104E-07 5.665E-08 5.529E-08 4.155E-08 4.539E-08 4.269E-08 4.834E-08 5.943E-08 2.052E-08 1.630E-08 1.893E-08 1.987E-08 2.697E-08 3.594E-08 4.648E-08 6.295E-08 5.361E-08 2.721E-08 2.565E-08 1.930E-08 2.091E-08 1.959E-08 2.226E-08 2.745E-08 6.907E-09 5.540E-09 6.565E-09 6.991E-09 9.475E-09 1.259E-08

1. 653E-08 2.257E-08 1.918E-08 9.569E-09 8.556E-09 6.461E-09 6.908E-09 6.434E-09 7.362E-09

9. 106E-09 20-30 2.969E-09 2.399E-09 2.892E-09 3.114E-09 4.218E-09 5.594E-09 7.429E-09 1.021E-08 8.652E-09 4.260E-09 3.659E-09 2.775E-09 2.9322-09 2.721E-09 3.134E-09 3.882E-09 30-40 40-50 1.695E-09 1.106E-09 1.376E-09 9.011E-10 1.677E-09 1.107E-09 1.818E-09 1.206E-09 2.462E-09 1.634E-09 3.261E-09 2.162E-09 4.359E-09 2.904E-09 6.012E-09 4.016E-09 5.085E-09 3.391E-09 2.485E-09 1.648E-09 2.084E-09 1.359E-09 1.585E-09 1.036E-09 1.663E-09 1.081E-099 1.540E-09 1.000E-09 1.782E-09 1.161E-09 W

2.208E-09 1.438E-09 m;

Co 0

0 co m

L-0 m

U)z C,

I-m z-I

UNRZ Ct*GPr2R CODE - )XgQDQ, VESI WN 2.0 RUN DATE: 970513

^***

PAJISAZDES YXX)gQ82 ^^^^* USINS 01/01/92 -

12/31/96 MET DATA *****

G2UXND LEMVE RELEASE - TOP OP CCNTA11NT BUIMIMDDN DIRECTION FROM SITB S

SSW SW WISW w

NW NNW N

NNE NB E

ESE 0.25 2.600E-08 1.731E-08 1.866E-08 1.829E-08 2.673B-08 4.142E-08 4.847E-08 5.897E-08 4.172E-08 2.423E-08 4.208E-08 3.387E-08 3.926E-08 4.148E-08 E

RELATIV DEPOSIMON PER UNIT AREA (H**-2) AT FlX3 POtIS BY WIND SETORS DISTAtNCS IN MILES 0.50 0.75 1.00 1.50 2.00 2.50 3.00 3.50 3.794E-09 4.515E-09 2.772E-09 1.382E-09 8.383E-10 5.668E-10 4.107E-10 3.123E-10 5.BS2E-09 3.005B-09 1.845E-09 9.198E-10 5.579E-10 3.772E-10 2.733E-10 2.078E-10 6.309E-09 3.239E-09 1.989E-09 9.916B-10 6.014E-10 4.066E-10 2.946E-10 2.240E-10 6.183E-09 9.040E-09 1.401E-08 1.6392-08 1.994E-08 1.411E-08 8.194E-09 3.175E-09 1.949E-09 9.719E-10 4.641E-09 2.850E-09 1.421E-09 7.191E-09 4.416E-09 2.201E-09 8.416E-09 5.1682-09 2.5762-09 1.024E-08 6.287E-09 3.135E-09 7.244E-09 4.448E-09 2.218B-09 4.207E-09 2.583E-09 1.288E-09 5.894E-10 3.985E-10 8.6182-10 5.826E-10 1.335E-09 9.027B-10 1.563E-09 1.056E-09 1.9012-09 1.285E-09 1.345E-09 9.093E-10 7.811E-10 5.281E-10 1.356H-09 9.171B-10 1.092B-09 7.382E-10 1.266E-09 8.556E-10 1.337E-09 9.041E-10 2.888E-10 2.196E-10 4.222E-10 3.210E-10 6.541E-10 4.974E-10 7.656E-10 5.821E-10 9.3142-10 7.082E-10 6.589E-10 5.010E-10 3.827E-10 2.910E-10 4.00 4.50 2.4602-10 1.992E-10 1.637B-10 1.325E-10 1.765E-10 1.429E-10 1.730E-10 1.401E-10 2.529E-10 2.048E-10 3.919E-10 3.172E-10 4.586E-10 3.713E-10 5.580E-10 4.5172-10 3.947E-10 3.196E-10 2.292E-10 1.856E-10 1.423E-08 7.306E-09 4.486B-09 2.237E-09 1.145E-08 5.881B-09 3.611E-09 1.800E-09 1.328E-08 6.816B-09 4.185E-09 2.087B-09 1.403E-08 7.2022-09 4.423E-09 2.205B-09 6.646B-10 5.053E-10 3.9812-10 3.223E-10 5.3492-10 4.067B-10 3.2042-10 2.594E-10 6.200B-10 4.7152-10 3.7142-10 3.007E-10 6.552E-10 4.982E-10 3.925E-10 3.177E-10 SB 4.919E-08 1.663E-08 8.5402-09 5.244E-09 2.6142-09 1.586E-09 1.072E-09 7.769E-10 5.907E-10 4.654E-10 3.7682-10 SSB 5.133E-08 1.736E-08 8.9132-09 5.473E-09 2.728B-09 1.6552-09 1.119B-09 8.107E-10 6.165B-10 4.857B-10 3.932B-10 0

DIRETOIcN FROM SITE S

SSW SW WSW w

NW WNI NS NNW NE NNE NE ENE SE SSE 5.00 7.50 10.00 1.648E-10 8.074E-11 5.066E-11 1.096E-10 5.373E-11 3.3712-11 1.182E-10 5.792E-11 3.634E-11 1.159E-10 5.6772-11 3.562E-11 1.694E-10 8.300E-11 5.2082-11 2.624E-10 1.286E-10 8.069E-11 3.071B-10 1.505E-10 9.443E-ll 3.736E-10 1.831E-10 1.1492-10 2.643E-10 1.295E-10 8.128E-11 1.535E-10 7.523E-11 4.720E-11 2.6662-10 1.306E-10 8.198E-11 2.146E-10 1.052E-10 6.598E-11 2.487E-10 1.219E-10 7.648E-11 2.628E-10 1.288E-10 8.081E-11 3.117E-10 1.527E-10 9.583E-11 3.252E-10 1.594E-10 1.000E-10 DISTANCS IN MILES 15.00 20.00 25.00 30.00 35.00 2.5612-11 1.5502-11 1.039E-11 7.446E-12 5.5912-12 1.704E-11 1.031E-11 6.915E-12 4.955E-12 3.721E-12 1.837E-11 1.112E-11 7.4552-12 5.342E-12 4.011B-12 1.801E-11 1.090E-11 7.3072-12 5.236E-12 3.9312-12 2.632E-11 1.593E-11 1.068E-11 7.654E-12 5.7482-12 4.078E-11 2.468E-11 1.655E-11 1.186E-11 8.905E-12 4.773E-11 2.889E-11 1.937B-11 1.388E-11 1.042B-11 5.807E-11 3.515E-11 2.357E-11 1.689E-11 1.268E-11 4.108E-11 2.487E-11 1.667E-11 1.195E-11 8.970E-12 2.3862-11 1.444E-11 9.682E-12 6.938E-12 5.210E-12 4.143E-11 2.508E-11 1.681E-11 1.205E-11 9.047E-12 3.335E-11 2.019E-11 1.353E-11 9.698E-12 7.282E-12 3.866E-11 2.340E-11 1.569E-11 1.124E-11 8.441E-12 4.085E-11 2.472E-11 1.658E-11 1.188E-11 8.919E-12 4.844E-11 2.932E-11 1.966E-11 1.408E-11 1.058E-11 5.055E-11 3.059E-11 2.051E-11 1.470E-11 1.104E-11 40.00 45.00 50.00 4.347E-12 3.473E-12 2.834E-12 2.893E-12 2.311B-12 1.886E-12 3.119E-12 2.491E-12 2.033E-12 3.057E-12 2.442E-12 1.993E-12 4.469E-12 3.570E-12 2.914E-12 6.924E-12 5.531E-12 4.514E-12 8.103E-12 6.473E-12 5.283E-12 9.859E-12 7.875E-12 6.428E-12 6.975E-12 5.571E-12 4.547E-12 4.051E-12 3.236E-12 2.641E-12 7.034E-12 5.619E-12 4.586E-12 5.662E-12 4.523E-12 3.692E-12 6.563E-12 5.242E-12 4.279E-12 6.935E-12 5.539E-12 4.521E-12 8.223E-12 6.569E-12 5.361E-12 8.581E-12 6.855E-12 5.595E-12 a)

I-m

.C,)

CD 00 0

-In U,

m 0Ca m

0 I-z z

C l-0 m

CO) z C.,

m I-z-I

USNR CtHPTIEl COtE -

XOQIXOQ, VERSION 2 *aRN 0E 901 RUN DATE: 970513

--** PALISADES XOQD0Q82 **-*- USING 01/01/92 -

12/31/96 MrT DATA &****

GROUND LEVEL RELEASE - TOP OF C1NTADNMENT BUILDING

- -*h********************R DIRECTION

.5-1 1-2 FROM SITE S

4.691E-09 1.449Z-09 SSW 3.122E-09 9.645E-10 SW 3.366E-09 1.040E-09 WSW 3.299E-09 1.0198-09 W

4.823E-09 1.490B-09 WNW 7.472E-09 2.308E-09 NW 8.745E-09 2.702E-09 NNW 1.064E-08 3.287E-09 N

7.527E-09 2.325E-09 NNE 4.371E-09 1.351E-09 NZ 7.591E-09 2.345E-09 ENE 6.110Z-09 1.888E-09 E

7.082E-09 2.188Z-09 ESE 7.484E-09 2.312E-09 SE 8.874E-09 2.7421-09 SSE 9.261E-09 2.861Z-09 MATIVE DIPOSITION PER UNIT AREA (M**-2)

BY DOWNMIND SECTRS SEGMENT BOUNDARIES IN MILES 2-3 3-4 4-5 5-10 10-20 20-30 30-40 5.768E-10 3.838Z-10 4.138Z-10 4.055Z-10 5.929E-10 9.186B-10 1.075Z-09 1.308B-09 9.253E-10 5.374B-10 9.333Z-10 7.512Z-10 8.707E-10 9.200E-10 1.091E-09 1.139Z-09 3.152Z-10 2.0031-10 2.0971-10 1.333E-10 2.261E-10 1.437E-10 2.216E-10 1.409E-10 3.240E-10 2.059E-10 5.020E-10 3.190E-10 5.875E-10 3.734E-10 7.147E-10 4.543E-10 5.057E-10 3.214E-10 2.937E-10 1.866E-10 5.100E-10 3.241E-10 4.105E-10 2.609E-10 4.758E-10 3.024E-10 5.028E-10 3.195E-10 5.962E-10 3.789Z-10 6.222E-10 3.954E-10 8.604E-11 5.726E-11 6.173E-11 6.050E-11

8. 845E-11 1.370E-10 1.604E-10 1.951E-10 1.3801-10 8.017Z-11 1.392E-10 1.121E-10 1.299E-10 1.373E-10 1.629E-10 1.699E-10 2.669E-11 1.057E-11 1.7761-11 7.037E-12 1.914E-11 7.587E-12 1.876Z-11 7.4361-12 2.7431-11 1.0871-11 4.249E-11 1.684E-11 4.974E-11 1.971E-11 6.051E-11 2.3981-11 4.281E-11 1.697B-ll 2.4861-11 9.8531-12 4.317E-11 1.711E-11 3.4751-11 1.377E-11 4.0281-11 1.596E-11 4.2561-11 1.687E-11 5.047B-11 2.000Z-11 5.267B-11 2.088E-11 5.647E-12 3.758E-12 4.051E-12 3.971E-12 5.805E-12 8.994E-12 1.053E-ll 1.281E-11 9.060E-12 5.262E-12 9.1389-12 7.355E-12 8.525E-12 9.008E-12 1.068Z-11 1.115E-11 40-50 3.495E-12 2.326E-12 2.508E-12 2.458E-12 3.593E-12 5.567E-12 6.516E-12 7.927E-12 5.609E-12 3.257E-12 5.656E-12 4.552E-12 5.277E-12 5.5761-12 6.612Z-12 6.900-12

-4 a)

I-m VENr AND BUILDING PARAMETERS:

RELEASE H1IGHS (MErERS) 58.10 DIAMETER (METERS) 0.00 EXIT VELOCITY (METERS) 0.00 REP. WIND HEIGHT (METERS) 10.0 BurLDrNG HEIGHT (METERS) 58.1 ML.MIN.CRS.SEc.ARA (SQ.METERS) 2000.0 HEAT EMISSION RATE (CAL/SEC) 0.0

a CD UV 0F 3o 0m

'1

'ii m

a 0CA m

C, I-I-

0z z

F-IC U) a mCO) z a

m z-I ALL GROUND LEVEL RELEASES.

USNRC CXWPUTER CODE - XOQCOQ, VERSION 2.0 RUN DATE: 970513

- - - - PALISADES XOQ!OQ82 ***** USING 01/01/92 - 12/31/96 MET DATA ****

GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING SPECIFIC POINTS OF INTEREST RELEASE TYPE OF DIRECTION DISTANCE X/Q LOCATION FRCM SITE (MILES)

(KETERS)

(SEC/CUB.ETER)

NO DECAY UNDEPLETED A

SITE BOUNDARY NNE 0.50 805.

1.72E-06 A

SITE BOUNDARY NE 0.65 1046.

1.22E-06 A

SITE BOUNDARY ENE 0.87 1400.

5.99E-07 A

SITE BOUNDARY E

0.82 1320.

7.28E-07 A

SITE BOUNDARY ESE 0.76 1223.

7.85E-07 A

SITE BOUNDARY SE 0.63 1014.

1.18E-06 A

SITE BOUNDARY SSE 0.48 772.

2.13E-06 A

SITE BOUNDARY S

0.42 676.

1.78E-06 A

SITE BOUNDARY SSW 0.48 772.

1.16E-06 A

GARDEN NNE 1.60 2575.

3.06E-07 A

GARDEN NE 1.20 1931.

4.96E-07 A

GARDEN ENE 2.70 4345.

1.15E-07 A

GARDEN E

2.20 3541.

1.70E-07 A

GARDEN ESE 2.30 3701.

1.51E-07 A

GARDEN SE 1.80 2897.

2.45E-07 A

GARDEN SSE 1.60 2575.

3.55E-07 A

GARDEN 5

1.50 2414.

2.78E-07 A

BEEF COw NE 2.90 4667.

1.38E-07 A

BEEF COW ENE 4.00 6437.

6.51E-08 A

BEFF COW E

3.50 5633.

8.64E-08 A

BEEF COW ESE 4.00 6437.

6.70E-08 A

BEEF CXXW SSE 3.00 4828.

1.41E-07 A

DAIRY COW SE 4.30 6920.

6.83E-08 A

GOAT NE 3.20 5150.

1.19E-07 A

GOAT ESE 3.00 4828.

1.02E-07 X/Q X/Q D/Q (SE)/CUB.HETER) (SEC/CUB.METERj (PER SQ.METER) 2.260 DAY DECAY 8.000 DAY DECAY UNDEPLZM DEPLETE 1.71E-06 1.57E-06 8.19E-09 1.22E-06 1.10E-06 9.30E-09 5.98E-07 5.29E-07 4.58E-09 7.27E-07 6.45E-07 5.86E-09 7.83E-07 6.98E-07 7.04E-09 1.18E-06 1.06E-06 1.14E-08 2.12E-06 1.95E-06 1.86E-08 1.78E-06 1.64E-06 1.16E-08 1.15E-06 1.06E-06 6.26E-09 3.04E-07 2.58E-07 1.15E-09 4.95E-07 4.28E-07 3.29E-09 1.14E-07 9.20E-08 6.45E-10 1.69E-07 1.40Z-07 1.07E-09 1.50E-07 1.23E-07 1.05E-09 2.44E-07 2.04E-07 1.91E-09 3.53E-07 2.99E-07 2.44E-09 2.77E-07 2.36E-07 1.38E-09 1.36E-07 1.09E-07 7.06E-10 6.43E-08 4.98E-08 3.20E-10 8.56e-08 6.73E-08 4.71E-10 6.63E-08 5.13E-08 3.93E-10 1.40E-07 1.12E-07 8.11E-10 6.75E-08 5.18E-08 4.09E-10 1.18E-07 9.39E-08 5.93E-10 1.01E-07 8.10E-08 6.55E-10 m

m

-1 CD 0

co 0m

'1 CO) m a0Uj) m 0

I-0 a

0z z

a I-Ca m

cnz a

0 m

I-z

-I VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS)

DIAMETER (METERS)

EXIT VELOCITY (METERS) 58.10 0.00 0.00 REP. WIND HEIGHT BUILDIN3 HEIGHT BLDG.HIN.CRS.SEC.AREA HEAT EMISSION RATE (METERS)

(METERS)

(SQ.METERS}

(CAL/SEC) 10.0 58.1 2000.0 0.0 ALL GROUND LEVEL RELEASES.

USNRC CotmPurER CODE - XOQDOQ, VERSION 2.0 RUN DATE: 970513

- PALISADES XOQDOQ82 ***** USING 01/01/92 - 12/31/96 MET DATA *****

GROUND LEVEL RELEASE - TOP OF CONTADnwT BUILDING SPECIFIC POINTS OF INvtlEST RELEASE TYPE OF DIRECTION DISTANCE X/Q ID LOCATION FRON SITE (HILES) (MWERS) (SEC/CUB.NETER)

NO DECAY UNDEPLETED A

SITE BOUNDARY NNE 0.50 805.

1.72E-06 A

SITE BOUNDARY NE 0.65 1046.

1.22E-06 A

SITE BOUNDARY ENE 0.87 1400.

5.99E-07 A

SITE BOUNDARY E

0.82 1320.

7.28E-07 A

SITE BOUNDARY ESE 0.76 1223.

7.8SE-07 A

SITE BOUNDARY SE 0.63 1014.

1.18E-06 A

SITE BOUNDARY SSE 0.48 772.

2.13E-06 A

SITE BOUNDARY S

0.42 676.

1.78E-06 A

SITE BOUNDARY SSW 0.48 772.

1.16E-06 A

RESIDENCE NNE 1.10 1770.

5.23E-07 A

RESIDENCE NE 1.20 1931.

4.96E-07 A

RESIDENCE ENE 1.30 2092.

3.33E-07 A

RESIDENCE E

1.00 1609.

5.44E-07 A

RESIDENC ESE 1.00 1609.

5.21E-07 A

RESIDENCE SE 1.00 1609.

5.87E-07 A

RESIDENCE SSE 0.70 1127.

1.21E-06 A

RESIDENCE S

0.50 805.

1.38E-06 A

RESIDENCE SSW 0.70 1127.

6.50E-07 A

BEEF COW NE 2.90 4667.

1.38E-07 A

BEEF COW ENE 4.00 6437.

6.51E-08 A

BEEF COW E

3.50 5633.

8.64E-08 A

BEEF COW ESE 4.00 6437.

6.70E-08 A

BEEF COW SSE 3.00 4828.

1.41E-07 A

DAIRY COW SE 4.30 6920.

6.83E-08 A

GOAT NE 3.20 5150.

1.19E-07 A

GOAT ESE 3.00 4828.

1.02E-07 X/Q X/Q D/Q (SEC/CUB.HETER) (SEC/CUB.METER)

(PER SQ.METER) 2.260 DAY DECAY 8.000 DAY DECAY UNDEPLErED DfPLETED 1.71E-06 1.57E-06 8.19E-09 1.22E-06 1.10E-06 9.30E-09 5.98E-07 5.29E-07 4.58E-09 7.27E-07 6.45E-07 5.86E-09 7.83E-07 6.98E-07 7.04E-09 1.18E-06 1.06E-06 1.14E-08 2.12E-06 1.95E-06 1.86E-08 1.78E-06 1.64E-06 1.16E-08 1.15E-06 1.06E-06 6.26E-09 5.21E-07 4.55E-07 2.20E-09 4.95E-07 4.28E-07 3.29E-09 3.31E-07 2.85E-07 2.30E-09 5.42E-07 4.76E-07 4.19E-09 5.20E-07 4.562-07 4.42E-09 5.86E-07 5.14E-07 5.25E-09 1.20E-06 1.08E-06 1.00E-08 1.38E-06 1.26E-06 8.79E-09 6.49E-07 5.81E-07 3.37E-09 1.36E-07 1.09E-07 7.06E-10 6.43E-08 4.98E-08 3.20E-10 8.56B-08 6.73E-08 4.71E-10 6.63E-08 5.13E-08 3.93E-10 1.40E-07 1.12E-07 8.11E-10 6.75E-08 5.18E-08 4.09E-10 1.18E-07 9.39E-08 5.93E-10 1.01E-07 8.10E-08 6.55E-10 lm I-m C4 CD rA, 00 0

m a

m I-;

0 Z I z

a ID 0in a

m z

a m

a z-I VENT AND BUILDING PARAMETERS

RELEASE HEIGHT (METFERS)

DIAMETER (METERS)

ExIT VELOCITY (METERS3 58.10 0.00 0.00 REP. WIND HEIGHT BUILDING HEIGHT ELDG.HIN.CRS.SEC.AREA BEAT EHISSION RATE (METERS)

(METERS)

(SQ.METERS)

(CAL/SEC) 10.0 58.1 2000.0 0.0 ALL GROUND LEVEL RELEASES.

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.4 2002 PALISADES LAND USE CENSUS I

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

SECTOR NNE NE ENE E

ESE SE SSE S

SSW RESIDENCE 1.1 mi 1.2 mi 1.3 mi 1.0 mi 1.0 mi 1.0 mi 0.7 mi 0.5 mi 0.7 mi GARDEN 1.7 mi 1.2 mi 1.6 mi 2.1 mi

1.0 Mi

1.0 ml 1.6 mi 4.0 mi

>5.0 mi BEEF CATTLE

>5 mi 2.9 mi 4.0 mi 3.5 mi

4.0 mi 2.2 mi

>5 mi

>5 mi DAIRY COW

>5 mi

>5 mi 4.3 mi

>5 mi

>5 mi GOAT

>5 mi 3.2 mi

>5 mi

2.0 mi

2.0 mi

>5 mi 4.7 mi

>5 mi

Note:

Garden and Farm bisected by ESE/SE sector line.

44

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.4a 2002 PALISADES LAND USE CENSUS I

Critical Receptor Items Distance Sector Miles Location/Description Item SSE 0.48 Site Boundary N/A S

0.50 Residence, Palisades Park; Residence 1/2 mile west of 2 9th Avenue and Blue Star intersection SE 1.0 77550 28th Avenue Garden SE 2.2 76th Street, 0.3 miles N of 34th Beef Cattle East side of road SE 4.3 72401 36th Ave Dairy Cow SE 2.0 SE corner of 3 0 th Goat and 7 6 th

Based on Palisades 5-year composite meteorological data, 1992 - 1996.

XIQ (sec/M 3) 2.13E-06 1.38E-06 5.87E-07 1.86E-07 6.83E-08 2.1 OE-07 45

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.5 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES*

Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-1 31 m Xe-133m Xe-133 Xe-1 35m Xe-135 Xe-1 37 Xe-138 Ar-41 DFR1 1.17(+3)3 1.61(+1) 5.92(+3) 1.47(+4) 1.66(+4) 9.15(+1) 2.51 (+2) 2.94(+2) 3.12(+3) 1.81 (+3) 1.42(+3) 8.83(+3) 8.84(+3)

DFy 2 1.23(+3) 1.72(+1) 6.17(+3) 1.52(+4) 1.73(+4) 1.56(+2) 3.27(+2) 3.53(+2) 3.36(+3) 1.92(+3) 1.51 (+3) 9.21 (+3) 9.30(+3)

DFS1 1.46(+3) 1.34(+3) 9.73(+3) 2.37(+3) 1.01 (+4) 4.76(+2) 9.94(+2) 3.06(+2) 7.11(+2) 1.86(+3) 1.22(+4) 4.13(+3) 2.69(+3)

DFB2 1.97(+3) 1.95(+3) 1.03(+4) 2.93(+3) 1.06(+4) 1.11 (+3) 1.48(+3) 1.05(+3) 7.39(+3) 2.46(+3) 1.27(+4) 4.75(+3) 3.28(+3)

1.

mrem/y per ACi/m 3

2.

mrad/y per ixCi/m 3

3.

1.17(+3) = 1.17x 103

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

46

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.6 STABLE ELEMENT TRANSFER DATA ELEMENT H

C Na P

Cr Mn Fe Co Ni Cu Zn Rb Sr y

Zr Nb Mo Tc Ru Rh Ag Te I

Cs Ba La Ce Pr Nd W

Np Fm - MILK (COW)

(DAYS/L) 1.OE-02 1.2E-02 4.0E-02 2.5E-02 2.2E-03 2.5E-04 1.2E-03 1.OE-03 6.7E-03 1.4E-02 3.9E-02 3.OE-02 8.0E-04 1.OE-05 5.OE-06 2.5E-03 7.5E-03 2.5E-02 1.OE-06 1.OE-02 5.0E-02 1.OE-03 6.0E-03 1.2E-02 4.0E-04 5.OE-06 1.OE-04 5.0E-06 5.0E-06 5.OE-04 5.0E-06 Fm - MILK (GOAT)

(DAYS/L) 1.7E-01 I.OE-01 4.OE-02 2.5E-01 2.2E-03 2.5E-04 1.3E-04 1.OE-03 6.7E-03 1.3E-02 3.9E-02 3.0E-02 1.4E-02 1.OE-05 5.OE-06 2.5E-03 7.5E-03 2.5E-02 1.OE-06 1.OE-02 5.0E-02 1.OE-03 6.OE-02 3.OE-01 4.OE-04 5.0E-06 1.OE-04 5.0E-06 5.OE-06 5.0E-04 5.OE-06 Ff-MEAT (DAYS/KG) 1.2E-02 3.1 E-02 3.OE-02 4.6E-02 2.4E-03 8.0E-04 4.OE-02 1.3E-02 5.3E-02 8.OE-03 3.OE-02 3.1 E-02 6.01E-04 4.6E-03 3.4E-02 2.8E-01 8.OE-03 4.OE-01 4.OE-01 1.5E-03 1.7E-02 7.7E-02 2.9E-03 4.OE-03 3.2E-03 2.OE-04 1.2E-03 4.7E-03 3.3E-03 1.3E-03 2.OE-04 Biv (VEG/SOIL) 4.8E-00 5.5E-00 5.2E-02 1.1E-00 2.5E-04 2.9E-02 6.6E-04 9.4E-03 1.9E-02 1.2E-01 4.OE-01 1.3E-01 1.7E-02 2.6E-03 1.7E-04 9.4E-03 1.2E-01 2.5E-01 5.OE-02 1.3E+01 1.5E-01 1.3E-00 2.OE-02 1.OE-02 5.OE-03 2.5E-03 2.5E-03 2.5E-03 2.4E-03 1.8E-02 2.5E-03 47

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-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 1.25E-04 2.65E-05

0.

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

0.

3.33E-07

0.

6.1OE-07 NA22 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 NA24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P32 1.45E-03 8.03E-05 5.53E-05

0.

1.15E-05 AR39

0.

1.00E-08 0.

AR41

0.

3.14E-08 0.

CA41 7.48E-05

0.

8.16E-06.

0.

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

0.

3.56E-04

0.

2.19E-05 CR51

0.

6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 MN54

0.

1.81E-05 3.56E-06

0.

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

0.

1.10E-09 1.58E-10

0.

7.86E-10 8.95E-06 5.12E-05 FE55 1.41 E-05 8.39E-06 2.38E-06

0.

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

0.

7.25E-04 1.77E-05 C057

0.

4.65E-07 4.58E-07

0.

2.71 E-04 3.47E-06 C058

0.

8.71 E-07 1.30E-06

0.

5.55E-04 7.95E-06 C060

0.

5.73E-06 8.41 E-06

0.

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

0.

5.48E-05 6.34E-07 N163 2.42E-04 1.46E-05 8.29E-06

0.

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

0.

5.80E-06 3.58E-05 CU64

0.

1.34E-09 5.53E-10

0.

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

0.

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-05 ZN69 3.85E-11 6.91E-11 5.13E-12

0.

2.87E-11 1.05E-06 9.44E-06 SE79

0.

2.25E-06 4.20E-07

0.

2.47E-06 2.99E-04 3.46E-06 BR82

0.

9.49E-06

0.

BR83+D

0.

2.72E-07

0.

BR84

0.

2.86E-07

0.

BR85

0.

1.46E-08

0.

KR83M

0.

2.50E-09 0.

KR85M

0.

1.31 E-08 0.

KR85

0.

1.16E-08 0.

KR87

0.

6.59E-08 0.

KR88+D

0.

1.38E-07 0.

KR89

0.

8.67E-08 0.

RB86

0.

1.36E-04 6.30E-05

0.

2.17E-06 RB87

0.

7.11 E-05 2.64E-05

0.

2.99E-07 RB88

0.

3.98E-07 2.05E-07

0.

2.42E-07 RB89+D

0.

2.29E-07 1.47E-07

0.

4.87E-08 SR89+D 2.84E-04

0.

8.15E-06

0.

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

0.

1.85E-03

0.

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

0.

2.47E-09

0.

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

0.

2.79E-10

0.

1.70E-05 1.OOE-04 Includes a 50% increase to account for percutaneous transpiration.

48

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Y90 2.35E-06

0.

6.30E-08

0.

1.92E-04 Y91M+D 2.91E-10

0.

9.90E-12

0.

1.99E-06 Y91 4.20E-04

0.

1.12E-05

0.

1.75E-03 Y92 1.17E-08

0.

3.29E-10

0.

1.75E-05 Y93 1.07E-07

0.

2.91 E-09

0.

5.46E-05 ZR93+D 2.24E-04 9.51E-05 6.18E-05

0.

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

0.

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

0.

1.85E-08 7.88E-05 NB93M 1.38E-04 3.59E-05 1.15E-05

0.

3.68E-05 2.09E-04 NB95 1.12E-05 4.59E-06 2.70E-06

0.

3.37E-06 3.42E-04 NB97 2.44E-10 5.21 E-11 1.88E-11

0.

4.07E-11 2.37E-06 M093

0.

6.46E-06 2.22E-07

0.

1.54E-06 3.40E-04 M099+D

0.

1.18E-07 2.31E-08

0.

1.89E-07 9.63E-05 TC99M 9.98E-13 2.06E-12 2.66E-11

0.

2.22E-11 5.79E-07 TC99 2.09E-07 2.68E-07 8.85E-08

0.

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

0.

6.99E-13 4.17E-07 RU103+D 1.44E-06

0.

4.85E-07

0.

3.03E-06 3.94E-04 RU105+D 8.74E-10

0.

2.93E-10

0.

6.42E-10 1.12E-05 RU106+D 6.20E-05

0.

7.77E-06

0.

7.61 E-05 8.26E-03 RH105 8.26E-09 5.41E-09 3.63E-09

0.

1.50E-08 2.08E-05 PD107

0.

4.92E-07 4.11E-08

0.

2.75E-06 6.34E-05 PD109

0.

3.92E-09 1.05E-09

0.

1.28E-08 1.68E-05 AG110M+D 7.13E-06 5.16E-06 3.57E-06

0.

7.80E-06 2.62E-03 AG111 3.75E-07 1.45E-07 7.75E-08

0.

3.05E-07 2.06E-04 CD113M

0.

6.67E-04 2.64E-05

0.

5.80E-04 1.40E-03 CD115M

0.

1.73E-04 6.19E-06

0.

9.41E-05 1.47E-03 SN123 2.09E-04 4.21E-06 7.28E-06 4.27E-06

0.

2.22E-03 SN125+D 1.01 E-05 2.51 E-07 6.OOE-07 2.47E-07

0.

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

0.

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

0.

1.89E-03 SB125+D 3.69E-05 3.41 E-07 7.78E-06 4.45E-08

0.

1.17E-03 SB126 3.08E-06 6.01 E-08 1.11 E-06 2.35E-08

0.

6.88E-04 SB127 2.82E-07 5.04E-09 8.76E-08 3.60E-09

0.

1.54E-04 TE125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06

0.

3.19E-04 TE127M+D 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 TE127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 TE129M+D 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 TE129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 TE131M+D 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 TE131+D 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 TE132+D 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 TE133M+D 6.13E-11 3.59E-11 2.74E-11 5.52E-11 1.72E-10 3.92E-06 TE134+D 3.18E-11 2.04E-11 1.68E-11 2.91 E-11 9.59E-11 2.93E-06 1129 2.16E-05 1.59E-05 1.16E-05 1.04E-02 1.88E-05 0.

1130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.

1131+D 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.

IN FIRST YR)

GI-LLI 7.43E-05 1.68E-06 5.02E-05 9.04E-05 1.19E-04 1.48E-05 1.55E-05 1.OOE-04 2.47E-06 9.05E-06 1.92E-05 3.76E-06 3.48E-05 1.45E-06 7.82E-06 6.03E-07 1.15E-05 3.46E-05 1.17E-04 1.37E-05 7.33E-07 2.85E-05 2.36E-05 3.02E-05 1.65E-05 5.02E-05 4.08E-05 7.26E-05 1.65E-05 4.22E-05 1.05E-05 5.33E-05 3.78E-05 9.22E-06 1.95E-05 1.74E-05 4.93E-05 1.88E-05 8.51 E-05 5.87E-06 3.15E-05 1.59E-05 2.53E-06 2.12E-07 1.42E-06 7.56E-07 49

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY 1132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 1133+D 9.46E-06 1.37E-05 4.OOE-06 2.54E-03 1.60E-05 1134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 1135+D 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 XE131M

0.

XE133M

0.

XE133

0.

XE135M

0.

XE135

0.

XE137

0.

XE138+D

0.

CS134M+D 1.32E-07 2.10E-07 1.1IE-07

0.

8.50E-08 CS134 2.83E-04 5.02E-04 5.32E-05

0.

1.36E-04 CS135 1.00E-04 8.66E-05 4.73E-06

0.

2.58E-05 CS136 3.45E-05 9.61E-05 3.78E-05

0.

4.03E-05 CS137+D 3.92E-04 4.37E-04 3.25E-05

0.

1.23E-04 CS138 3.61E-07 5.58E-07 2.84E-07

0.

2.93E-07 CS139+D 2.32E-07 3.03E-07 1.22E-07

0.

1.65E-07 BA139 1.06E-09 7.03E-13 3.07E-11

0.

4.23E-13 BA140+D 4.00E-05 4.00E-08 2.07E-06

0.

9.59E-09 BA141+D 1.12E-10 7.70E-14 3.55E-12

0.

4.64E-14 BA142+D 2.84E-11 2.36E-14 1.40E-12

0.

1.36E-14 LA140 3.61E-07 1.43E-07 3.68E-08

0.

LA141 4.85E-09 1.40E-09 2.45E-10

0.

LA142 7.36E-10 2.69E-10 6.46E-11

0.

CE141 1.98E-05 1.19E-05 1.42E-06

0.

3.75E-06 CE143+D 2.09E-07 1.38E-07 1.58E-08

0.

4.03E-08 CE144+D 2.28E-03 8.65E-04 1.26E-04

0.

3.84E-04 PR143 1.OOE-05 3.74E-06 4.99E-07

0.

1.41E-06 PR144 3.42E-11 1.32E-11 1.72E-12

0.

4.80E-12 ND147+D 5.67E-06 5.81 E-06 3.57E-07

0.

2.25E-06 PM147 3.91E-04 3.07E-05 1.56E-05

0.

4.93E-05 PM148M+D 5.00E-05 1.24E-05 9.94E-06

0.

1.45E-05 PM148 3.34E-06 4.82E-07 2.44E-07

0.

5.76E-07 PM149 3.1OE-07 4.08E-08 1.78E-08

0.

4.96E-08 PM151 7.52E-08 1.10E-08 5.55E-09

0.

1.30E-08 SM151 3.38E-04 6.45E-05 1.63E-05

0.

5.24E-05 SM153 1.53E-07 1.18E-07 9.06E-09

0.

2.47E-08 EU152 7.83E-04 1.77E-04 1.72E-04

0.

5.94E-04 EU154 2.96E-03 3.46E-04 2.45E-04

0.

1.14E-03 EU155 5.97E-04 5.72E-05 3.46E-05

0.

1.58E-04 EU156 1.56E-05 9.59E-06 1.54E-06

0.

4.48E-06 TB160 1.12E-04

0.

1.40E-05

0.

3.20E-05 H0166M 1.45E-03 3.07E-04 2.51E-04

0.

4.22E-04 W181 4.86E-08 1.46E-08 1.67E-09

0.

W185 1.57E-06 4.83E-07 5.58E-08

0.

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

0.

INHALED IN FIRST YR)

LUNG GI-LLI

0.

1.36E-06

0.

1.54E-06

0.

9.21 E-07

0.

1.31E-06 6.77E-09 0.

8.89E-09 0.

7.41 E-09 0.

8.05E-09 0.

1.80E-08 0.

8.30E-08 0.

9.78E-08 0.

2.00E-08 1.16E-07 5.69E-05 9.53E-07 1.01E-05 2.18E-07 8.40E-06 1.02E-06 5.09E-05 9.53E-07 4.67E-08 6.26E-07 2.53E-08 1.33E-08 4.25E-06 3.64E-05 1.14E-03 2.74E-05 2.12E-06 3.39E-06 1.11E-06 4.95E-07 1.20E-04 6.06E-05 1.22E-05 5.96E-05 5.87E-06 4.25E-05 3.69E-04 1.54E-05 8.30E-05 3.55E-05 7.03E-03 1.06E-04 3.09E-04 2.66E-05 1.15E-06 3.06E-06 2.30E-04 2.23E-05 4.55E-04 5.75E-06 1.22E-03 3.37E-05 3.20E-04 6.04E-05 6.50E-05 3.01 E-05 3.25E-05 2.58E-05 2.98E-04 3.46E-06 3.70E-05 1.93E-05 1.48E-03 9.88E-06 3.05E-03 2.84E-05 5.20E-04 5.19E-05 6.12E-04 4.14E-05 1.11E-03 2.14E-05 2.05E-03 1.65E-05 1.33E-05 2.63E-07 4.48E-04 1.12E-05 2.83E-05 2.54E-05 50

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY PB210+D 8.62E-02 2.02E-02 3.43E-03

0.

6.85E-02 B1210+D

0.

1.33E-05 1.18E-06

0.

1.03E-04 P0210 2.98E-03 5.63E-03 7.12E-04

0.

1.30E-02 RN222+D

0.

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

0.

4.16E-05 RA224+D 1.77E-04 4.00E-07 3.54E-05

0.

7.30E-06 RA225+D 2.57E-03 2.88E-06 5.13E-04

0.

5.31 E-05 RA226+D 2.48E-01 1.46E-05 2.05E-01

0.

2.94E-04 RA228+D 1.60E-01 7.61E-06 1.80E-01

0.

1.53E-04 AC225 3.69E-03 4.72E-03 2.48E-04

0.

3.49E-04 AC227+D 5.29E+00 8.76E-01 3.28E-01

0.

1.86E-01 TH227+D 1.82E-03 3.03E-05 5.24E-05

0.

1.13E-04 TH228+D 8.46E-01 1.10E-02 2.86E-02

0.

5.61E-02 TH229 1.34E+01 1.82E-01 6.62E-01

0.

8.99E-01 TH230 3.46E+00 1.79E-01 9.65E-02

0.

8.82E-01 TH232+D 3.86E+00 1.53E-01 2.29E-01

0.

7.54E-01 TH234 1.33E-05 7.17E-07 3.84E-07

0.

2.70E-06 PA231+D 9.10E+00 3.OOE-01 3.62E-01

0.

1.62E+00 PA233 6.84E-06 1.32E-06 1.19E-06

0.

3.68E-06 U232+D 2.57E-01

0.

2.13E-02

0.

2.40E-02 U233+D 5.44E-02

0.

3.83E-03

0.

1.09E-02 U234 5.22E-02

0.

3.75E-03

0.

1.07E-02 U235+D 5.01E-02

0.

3.52E-03

0.

1.01E-02 U236 5.01E-02

0.

3.60E-03

0.

1.03E-02 U237 3.25E-07

0.

8.65E-08

0.

8.08E-07 U238+D 4.79E-02

0.

3.29E-03

0.

9.40E-03 NP237+D 3.03E+00 2.32E-01 1.26E-01

0.

7.69E-01 NP238 2.67E-06 6.73E-08 4.16E-08

0.

1.47E-07 NP239 2.65E-07 2.37E-08 1.34E-08

0.

4.73E-08 PU238 5.02E+00 6.33E-01 1.27E-01

0.

4.64E-01 PU239 5.50E+00 6.72E-01 1.34E-01

0.

4.95E-01 PU240 6.49E+00 6.71 E-01 1.34E-01

0.

4.94E-01 PU241+D 1.55E-01 6.69E-03 3.11E-03

0.

1.15E-02 PU242 5.09E+00 6.47E-01 1.29E-01

0.

4.77E-01 PU244 5.95E+00 7.40E-01 1.48E-01

0.

5.46E-01 AM241 1.84E+00 8.44E-01 1.31E-01

0.

7.94E-01 AM242M 1.90E+00 8.24E-01 1.35E-01

0.

8.03E-01 AM243 1.82E+00 8.10E-01 1.27E-01

0.

7.72E-01 CM242 8.58E-02 7.44E-02 5.70E-03

0.

1.69E-02 CM243 1.73E+00 7.94E-01 1.06E-01

0.

3.91E-01 CM244 1.43E+00 7.04E-01 8.89E-02

0.

3.21E-01 CM245 2.26E+00 8.80E-01 1.36E-01

0.

5.23E-01 CM246 2.24E+00 8.79E-01 1.36E-01

0.

5.23E-01 CM247+D 2.18E+00 8.64E-01 1.33E-01

0.

5.15E-01 CM248 1.82E+01 7.12E+00 1.10E+00

0.

4.24E+00 CF252 4.26E+00

0.

1.01E-01

0.

INHALED IN FIRST YR)

LUNG 1.76E-01 9.96E-03 2.40E-01 9.88E-06 2.25E-01 7.91 E-02 2.57E-01 7.83E-01 1.09E-00 1.96E-01 1.62E+00 3.27E-01 4.65E+00 1.22E+01 2.18E+00 2.09E+00 1.62E-03 3.85E-01 2.19E-04 1.49E+00 3.56E-01 3.49E-01 3.28E-01 3.35E-01 9.13E-05 3.06E-01 3.49E-01 9.19E-05 4.25E-05 9.03E-01 8.47E-01 8.47E-01 7.62E-04 8.15E-01 9.33E-01 4.06E-01 1.64E-01 3.85E-01 2.97E-01 4.24E-01 4.08E-01 3.92E-01 3.99E-01 3.92E-01 3.23E+00 1.37E+00 GI-LLI 3.79E-05 3.27E-05 4.36E-05 0.

3.04E-04 3.42E-04 2.87E-04 3.05E-04 5.19E-05 2.71 E-04 5.27E-05 3.53E-04 3.62E-04 3.29E-04 3.87E-05 3.29E-05 7.40E-05 4.61 E-05 9.04E-06 4.36E-05 4.03E-05 3.95E-05 5.02E-05 3.71 E-05 1.31 E-05 3.54E-05 5.10E-05 2.58E-05 1.78E-05 4.69E-05 4.28E-05 4.36E-05 8.97E-07 4.20E-05 6.26E-05 4.78E-05 6.01 E-05 5.60E-05 5.10E-05 5.02E-05 4.86E-05 4.53E-05 4.45E-05 5.85E-05 9.43E-04 1.85E-04 51

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

CHILD INHALATION DOSE ISOTOPE BONE H3*

0.

BE10 8.43E-04 C14 9.70E-06 N13 2.33E-08 F18 1.88E-06 NA22 4.41 E-05 NA24 4.35E-06 P32 7.04E-04 AR39 0.

AR41 0.

CA41 7.06E-05 SC46 1.97E-04 CR51 0.

MN54 0.

MN56 0.

FE55 1.28E-05 FE59 5.59E-06 C057 0.

C058 0.

C060 0.

N159 1.66E-05 N163 2.22E-04 Nl65 8.08E-10 CU64 0.

ZN65 1.15E-05 ZN69M+D 4.26E-09 ZN69 1.81 E-11 SE79 0.

BR82 0.

BR83+D 0.

BR84 0.

BR85 0.

KR83M 0.

KR85M 0.

KR85 0.

KR87 0.

KR88+D 0.

KR89 0.

RB86 0.

RB87 0.

RB88 0.

RB89+D 0.

SR89+D 1.62E-04 SR90+D 2.73E-02 SR91+D 3.28E-08 SR92+D 3.54E-09 COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN LIVER TOTAL BODY THYROID KIDNEY LUNG 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 9.83E-05 2.12E-05

0.

7.41E-04 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08

0.

1.85E-07

0.

4.41 E-05 4.41 E-05 4.41 E-05 4.41 E-05 4.41 E-05 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 3.09E-05 2.67E-05

0.

4.89E-09

0.

1.68E-08

0.

7.70E-06

0.

7.21 E-02 2.70E-04 1.04E-04

0.

2.39E-04 0.

0.

4.17E-08 2.31 E-08 6.57E-09 4.59E-06 1.16E-05 2.57E-06

0.

2.71 E-06 4.26E-04 4.48E-10 8.43E-11

0.

4.52E-10 3.55E-06 6.80E-06 2.10E-06

0.

3.00E-05 9.04E-06 4.51E-06

0.

3.43E-04 2.44E-07 2.88E-07

0.

1.37E-04 4.79E-07 8.55E-07

0.

2.99E-04 3.55E-06 6.12E-06

0.

1.91E-03 4.67E-06 2.83E-06

0.

2.73E-05 1.25E-05 7.56E-06

0.

7.43E-05 7.99E-11 4.44E-11

0.

2.21 E-06 5.39E-10 2.90E-10

0.

1.63E-09 2.59E-06 3.06E-05 1.90E-05

0.

1.93E-05 2.69E-04 7.28E-09 8.59E-10

0.

4.22E-09 7.36E-06 2.61E-11 2.41E-12

0.

1.58E-11 3.84E-07 1.23E-06 2.60E-07

0.

1.71 E-06 1.49E-04

0.

5.66E-06

0.

1.28E-07

0.

1.48E-07

0.

6.84E-09

0.

1.22E-09

0.

6.58E-09

0.

5.66E-09

0.

3.38E-08

0.

6.99E-08

0.

4.55E-08 5.36E-05 3.09E-05

0.

3.16E-05 1.37E-05

0.

1.52E-07 9.90E-08

0.

9.33E-08 7.83E-08

0.

4.66E-06

0.

5.83E-04

0.

1.74E-03

0.

3.99E-03

0.

1.24E-09

0.

1.44E-05

0.

1.42E-10

0.

6.49E-06 FIRST YR)

GI-LLI 3.04E-07 1.72E-05 1.82E-06 2.33E-08 3.37E-07 4.41 E-05 4.35E-06 1.14E-05 0.

0.

2.94E-07 2.45E-05 2.93E-07 6.19E-06 3.33E-05 7.75E-07 1.91 E-05 3.58E-06 9.29E-06 2.60E-05 6.29E-07 1.71 E-06 2.27E-05 9.92E-06 4.41 E-06 2.71 E-05 2.75E-06 3.43E-06 0.

0.

2.16E-06 2.96E-07 4.66E-09 5.11E-10 4.52E-05 9.28E-05 4.70E-05 6.55E-05

Includes a 50% increase to account for percutaneous transpiration.

52

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI ISOTOPE Y90 Y91M+D Y91 Y92 Y93 ZR93+D ZR95+D ZR97+D NB93M NB95 NB97 M093 M099+D TC99M TC99 TC101 RU103+D RU105+D RU106+D RH105 PD107 PD109 AG110M+D AG111 CD113M CD115M SN123 SN125+D SN126+D SB124 SB125+D SB126 SB127 TE125M TE127M+D TE127 TE129M+D TE129 TE131M+D TE131+D TE132+D TE133M+D TE134+D 1129 1130 1131+D BONE 1.11 E-06 1.37E-10 2.47E-04 5.50E-09 5.04E-08 2.07E-04 5.13E-05 5.07E-08 1.27E-04 6.35E-06 1.16E-10 0.

0.

4.81 E-1 3 1.34E-07 2.19E-14 7.55E-07 4.13E-10 3.68E-05 3.91 E-09 0.

0.

4.56E-06 1.81 E-07 0.

0.

1.29E-04 4.95E-06 6.23E-04 1.55E-05 2.66E-05 1.72E-06 1.36E-07 1.82E-06 6.72E-06 7.49E-10 5.19E-06 2.64E-11 3.63E-08 5.87E-12 1.30E-07 2.93E-1 I 1.53E-11 1.05E-05 2.21 E-06 1.30E-05 LIVER 0.

0.

7.80E-05 1.13E-05 7.34E-09 3.17E-05 2.48E-06 2.08E-1 1 3.76E-06 4.66E-08 9.41E-13 1.49E-07 2.30E-14 0.

0.

2.10E-09 2.65E-07 1.48E-09 3.08E-06 5.68E-08 4.93E-04 7.88E-05 2.14E-06 9.94E-08 1.04E-05 2.00E-07 2.05E-07 2.62E-08 2.09E-09 6.29E-07 2.31 E-06 2.57E-1 0 1.85E-06 9.45E-12 1.60E-08 2.28E-12 7.36E-08 1.51 E-11 8.81 E-12 6.40E-06 4.43E-06 1.30E-05 TOTAL BODY THYROID 2.99E-08 0.

4.98E-12 0.

6.59E-06 0.

1.57E-10 0.

1.38E-09 0.

5.55E-05 0.

1.OOE-05 0.

4.32E-09 0.

1.04E-05 0.

1.77E-06 0.

9.74E-12 0.

1.35E-07 0.

1.15E-08 0.

1.56E-11 0.

5.35E-08 0.

2.91E-13 0.

2.90E-07 0.

1.50E-10 0.

4.57E-06 0.

1.79E-09 0.

2.51 E-08 0.

4.95E-10 0.

2.47E-06 0.

3.75E-08 0.

2.12E-05 0.

3.39E-06 0.

4.19E-06 2.27E-06 2.95E-07 1.03E-07 2.36E-05 2.84E-06 5.41 E-06 3.41 E-08 5.59E-06 2.46E-08 6.16E-07 1.00E-08 4.70E-08 1.51 E-09 2.47E-07 5.20E-07 8.16E-07 1.64E-06 1.65E-10 5.30E-10 8.22E-07 1.71 E-06 6.44E-12 1.93E-11 1.37E-08 2.64E-08 1.78E-12 4.59E-12 7.12E-08 8.58E-08 1.50E-11 2.32E-11 9.40E-12 1.24E-11 5.71 E-06 4.28E-03 2.28E-06 4.99E-04 7.37E-06 4.39E-03 KIDNEY 0.

0.

3.OOE-04 1.61 E-05 1.05E-08 3.44E-05 2.33E-06 2.31 E-11 1.06E-06 1.06E-07 1.37E-11 1.75E-06 3.92E-13 1.90E-06 3.63E-10 4.97E-05 8.39E-09 1.97E-06 7.06E-09 5.74E-06 1.71 E-07 5.13E-04 5.93E-05 0.

0.

1.72E-05 1.91 E-09 1.36E-05 6.94E-11 1.08E-07 1.59E-1 1 4.79E-07 1.01E-10 5.71E-11 1.08E-05 6.61 E-06 2.13E-05 INHALED IN FIRST YR)

LUNG GI-LLI 7.07E-05 7.24E-05 7.60E-07 4.64E-07 7.10E-04 4.97E-05 6.46E-06 6.46E-05 2.01 E-05 1.05E-04 7.10E-04 1.47E-05 6.03E-04 1.65E-05 3.06E-05 9.49E-05 1.04E-04 2.45E-06 1.66E-04 1.00E-05 9.23E-07 7.52E-06 1.70E-04 3.78E-06 3.66E-05 3.42E-05 2.57E-07 1.30E-06 3.37E-04 7.75E-06 1.58E-07 4.41 E-09 1.79E-04 1.21 E-05 4.30E-06 2.69E-05 3.87E-03 1.16E-04 7.82E-06 1.33E-05 3.16E-05 7.26E-07 6.16E-06 2.59E-05 1.48E-03 2.71 E-05 7.73E-05 2.98E-05 6.94E-04 1.63E-05 5.86E-04 4.97E-05 9.59E-04 4.05E-05 2.43E-04 7.17E-05 3.02E-03 1.63E-05 8.76E-04 4.43E-05 6.27E-04 1.09E-05 2.86E-04 5.67E-05 6.17E-05 3.82E-05 1.29E-04 9.13E-06 4.OOE-04 1.93E-05 2.71 E-06 1.52E-05 4.76E-04 4.91 E-05 7.93E-07 6.89E-06 5.56E-05 8.32E-05 5.ssE-07 3.60E-07 1.02E-04 3.72E-05 1.60E-06 4.77E-06 1.23E-06 4.87E-07

0.

2.15E-07

0.

1.38E-06

0.

7.68E-07 53

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

CHILD INHALATION DOSE COMMITMENT FACTORS (MREM150Y PER PCI ISOTOPE 1132 1133+D 1134 1135+D XE131M XE133M XE133 XE135M XE135 XE1 37 XE138+D CS134M+D CS134 CS135 CS136 CS1 37+D CS138 CS139+D BA139 BA140+D BA141 +D BA142+D LA140 LA141 LA142 CE141 CE143+D CE144+D PR143 PR144 ND147+D PM147 PM148M+D PM148 PM149 PM151 SM151 SM153 EU152 EU154 EU155 EU156 TBI60 H0166M Wi 81 W185 W187 BONE 5.72E-07 4.48E-06 3.17E-07 1.33E-06 0.

0.

6.33E-08 1.76E-04 6.23E-05 1.76E-05 2.45E-04 1.71 E-07 1.09E-07 4.98E-10 2.OOE-05 5.29E-1 1 1.35E-11 1.74E-07 2.28E-09 3.50E-1 0 1.06E-05 9.89E-08 1.83E-03 4.99E-06 1.61E-11 2.92E-06 3.52E-04 3.31 E-05 1.61 E-06 1.47E-07 3.57E-08 3.14E-04 7.24E-08 7.42E-04 2.74E-03 5.60E-04 7.89E-06 7.79E-05 1.34E-03 2.66E-08 8.31 E-07 4.41 E-09 LIVER 1.1OE-06 5.49E-06 5.84E-07 2.36E-06 0.

0.

8.92E-08 2.74E-04 4.13E-05 4.62E-05 2.23E-04 2.27E-07 1.1 5E-07 2.66E-13 1.75E-08 2.95E-14 9.73E-15 6.08E-08 5.31 E-10 1.11E-10 5.28E-06 5.37E-08 5.72E-04 1.50E-06 4.99E-12 2.36E-06 2.52E-05 6.55E-06 1.94E-07 1.56E-08 4.33E-09 4.75E-05 4.51 E-08 1.37E-04 2.49E-04 4.05E-05 4.23E-06 0.

2.81 E-04 6.52E-09 2.08E-07 2.61 E-09 TOTAL BODY 5.07E-07 2.08E-06 2.69E-07 1.12E-06 0.

0.

6.12E-08 6.07E-05 4.45E-06 3.14E-05 3.47E-05 1.50E-07 5.80E-08 1.45E-11 1.1 7E-06 1.72E-12 7.54E-1 3 2.04E-08 1.15E-10 3.49E-1 I 7.83E-07 7.77E-09 9.77E-05 2.47E-07 8.1OE-13 1.84E-07 1.36E-05 6.55E-06 1.25E-07 8.45E-09 2.82E-09 1.49E-05 4.35E-09 1.61 E-04 2.27E-04 3.18E-05 8.75E-07 9.67E-06 2.37E-04 8.99E-1 0 2.91 E-08 1.17E-09 THYROID 5.23E-05 1.04E-03 1.37E-05 2.14E-04 0.

0.

KIDNEY 1.69E-06 9.13E-06 8.92E-07 3.62E-06 0.

0.

4.94E-08 8.93E-05 1.53E-05 2.58E-05 7.63E-05 1.68E-07 9.08E-08 2.33E-13 5.71 E-09 2.56E-14 7.87E-15 0.

0.

2.31 E-06 2.26E-08 3.17E-04 8.11E-07 2.64E-12 1.30E-06 4.45E-05 9.74E-06 3.30E-07 2.75E-08 7.35E-09 4.89E-05 1.37E-08 5.73E-04 1.09E-03 1.51 E-04 2.72E-06 2.32E-05 4.01 E-04 0.

0.

INHALED IN FIRST YR)

LUNG GI-LLI

0.

8.65E-07

0.

1.48E-06

0.

2.58E-07

0.

1.20E-06 3.30E-09 0.

4.36E-09 0.

3.66E-09 0.

4.48E-09 0.

9.09E-09 0.

4.07E-08 0.

5.17E-08 0.

8.35E-09 7.92E-08 3.27E-05 1.04E-06 5.22E-06 2.17E-07 3.93E-06 1.13E-06 2.81 E-05 9.78E-07 1.84E-08 7.29E-08 9.36E-09 7.23E-12 1.56E-06 1.56E-05 4.71 E-04 2.75E-05 7.89E-07 7.44E-08 4.44E-07 7.41 E-10 4.94E-05 6.10E-05 4.48E-06 4.37E-05 2.35E-06 2.05E-05 1.47E-04 1.53E-05 3.12E-05 3.44E-05 3.23E-03 1.05E-04 1.17E-04 2.63E-05 4.23E-07 5.32E-08 8.87E-05 2.22E-05 2.20E-04 5.70E-06 5.72E-04 3.58E-05 1.24E-04 6.01E-05 2.40E-05 2.92E-05 1.24E-05 2.50E-05 1.48E-04 3.43E-06 1.37E-05 1.87E-05 9.OOE-04 1.14E-05 1.66E-03 2.98E-05 2.79E-04 5.39E-05 2.54E-04 4.24E-05 5.34E-04 2.28E-05 1.13E-03 1.63E-05 5.71 E-06 2.61 E-07 1.86E-04 1.11E-05 1.1 IE-05 2.46E-05 54

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+D 8.03E-02 1.85E-02 3.18E-03

0.

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

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.

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.

5.41 E-02 3.34E+00 3.59E-04 TH229 1.28E+01 1.76E-01 6.31 E-01

0.

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

0.

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

0.

7.28E-01 1.77E+00 3.27E-05 TH234 6.94E-06 3.07E-07 2.OOE-07

0.

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

0.

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

0.

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

0.

1.56E-02

0.

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

0.

2.82E-03

0.

7.62E-03 1.77E-01 4.OOE-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 3.51E-05 NP237+D 2.88E+00 2.21E-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 2.50E-05 NP239 1.26E-07 9.04E-09 6.35E-09

0.

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

0.

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

0.

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

0.

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

0.

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

0.

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

0.

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

0.

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

0.

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

0.

7.42E-01 1.92E-01 5.55E-05 CM242 6.33E-02 4.84E-02 4.20E-03

0.

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

0.

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

0.

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

0.

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

0.

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

0.

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

0.

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

0.

9.33E-02

0.

6.62E-01 1.84E-04 55

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

TEEN INHALATION DOSE COMMITMENT FACTORS (MREMI50Y ISOTOPE BONE LIVER TOTAL BODY THYROID H3*

0.

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

C14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 N13 8.65E-09 8.65E-09 8.65E-09 8.65E-09 F18 6.52E-07

0.

7.1OE-08 0.

NA22 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 P32 2.36E-04 1.37E-05 8.95E-06 0.

AR39

0.

AR41

0.

CA41 4.05E-05

0.

4.38E-06 0.

SC46 7.24E-05 1.41 E-04 4.18E-05 0.

CR51

0.

1.69E-08 9.37E-09 MN54

0.

6.39E-06 1.05E-06 0.

MN56

0.

2.12E-10 3.15E-11 0.

FE55 4.18E-06 2.98E-06 6.93E-07 0.

FE59 1.99E-06 4.62E-06 1.79E-06 0.

C057

0.

1.18E-07 1.15E-07 0.

C058

0.

2.59E-07 3.47E-07 0.

C060

0.

1.89E-06 2.48E-06 0.

N159 5.44E-06 2.02E-06 9.24E-07 0.

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

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

CU64

0.

2.54E-10 1.06E-10 0.

ZN65 4.82E-06 1.67E-05 7.80E-06 0.

ZN69M+D 1.44E-09 3.39E-09 3.11E-10 0.

ZN69 6.04E-12 1.15E-11 8.07E-13 0.

SE79

0.

5.43E-07 8.71 E-08 0.

BR82

0.

2.28E-06 0.

BR83+D

0.

4.30E-08 0.

BR84

0.

5.41 E-08 0.

BR85

0.

2.29E-09 0.

KR83M

0.

KR85M

0.

KR85

0.

KR87

0.

KR88+D

0.

KR89

0.

RB86

0.

2.38E-05 1.05E-05 0.

RB87

0.

1.40E-05 4.58E-06 0.

RB88

0.

6.82E-08 3.40E-08 0.

RB89+D

0.

4.40E-08 2.91 E-08 0.

SR89+D 5.43E-05

0.

1.56E-06 0.

SR90+D 1.35E-02

0.

8.35E-04 0.

SR91+D 1.10E-08

0.

4.39E-10 0.

SR92+D 1.19E-09

0.

5.08E-11 0.

PER PCI INHALED IN FIRST YR)

KIDNEY 1.59E-07 0.

6.09E-07 8.65E-09 0.

1.76E-05 1.72E-06 0.

0.

1.35E-04 3.84E-09 1.59E-06 2.24F-10 0.

0.

8.01 E-10 1.08E-05 2.06E-09 7.53E-12 8.1 3E-07 0.

0.

LUNG 1.59E-07 3.84E-04 6.09E-07 8.65E-09 0.

1.76E-05 1.72E-06 0.

4.OOE-09 1.44E-08 1.01 E-01 0.

2.62E-06 2.48E-04 1.90E-06 1.55E-05 1.91 E-04 7.33E-05 1.68E-04 1.09E-03 1.41 E-05 3.84E-05 1.17E-06 1.39E-06 1.55E-04 3.92E-06 1.98E-07 7.71 E-05 0.

0.

9.97E-1 0 5.46E-09 4.63E-09 2.82E-08 5.81 E-08 3.85E-08 0.

0.

3.02E-04 2.06E-03 7.59E-06 3.43E-06 GI-LLI 1.59E-07 1.77E-05 6.09E-07 8.65E-09 3.89E-08 1.76E-05 1.72E-06 1.16E-05 0.

0.

3.03E-07 2.98E-05 3.75E-07 8.35E-06 7.18E-06 7.99E-07 2.23E-05 3.93E-06 1.19E-05 3.24E-05 6.48E-07 1.77E-06 4.59E-06 7.68E-06 5.83E-06 2.14E-05 3.56E-08 3.53E-06 0.

0.

2.21 E-06 3.05E-07 3.65E-15 4.22E-17 4.64E-05 9.56E-05 3.24E-05 1.49E-05

Includes a 50% increase to account for percutaneous transpiration.

56

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

TEEN INHALATION DOSE COMMITMENT FACTORS (MREMI50Y PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 3.73E-07

0.

1.00E-08

0.

3.66E-05 6.99E-05 Y91M+D 4.63E-11

0.

1.77E-12

0.

4.OOE-07 3.77E-09 Y91 8.26E-05

0.

2.21 E-06

0.

3.67E-04 5.11E-05 Y92 1.84E-09

0.

5.36E-11

0.

3.35E-06 2.06E-05 Y93 1.69E-08

0.

4.65E-10

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 3.41E-06

0.

1.59E-05 5.36E-05 2.52E-06 NB95 2.32E-06 1.29E-06 7.08E-07

0.

1.25E-06 9.39E-05 1.21E-05 NB97 3.92E-11 9.72E-12 3.55E-12

0.

1.14E-11 4.91E-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.

2.11E-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

0.

2.38E-05 2.01E-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

0.

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

0.

6.56E-10 1.66E-10

0.

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

0.

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

0.

8.17E-08 4.OOE-05 3.OOE-05 CD113M

0.

2.17E-04 7.10E-06

0.

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

0.

3.48E-05 1.14E-06

0.

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

0.

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+D 2.18E-04 5.39E-06 8.24E-06 1.42E-06

0.

1.72E-03 1.68E-05 SB124 5.38E-06 9.92E-08 2.1OE-06 1.22E-08

0.

4.81E-04 4.98E-05 SB125+D 9.23E-06 1.01E-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 6.01E-05 SB127 4.64E-08 9.92E-10 1.75E-08 5.21E-10

0.

3.31E-05 3.94E-05 TE125M 6.1OE-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 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 TE129M+D 1.74E-06 8.23E-07 2.81E-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 5.61E-05 5.79E-05 TE133M+D 1.01E-11 7.33E-12 5.71E-12 8.18E-12 5.07E-11 8.71E-07 1.23E-07 TE134+D 5.31E-12 4.35E-12 3.64E-12 4.46E-12 2.91E-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 1131+D 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05

0.

8.11E-07 57

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

TEEN INHALATION DOSE COMMITMENT FACTORS (MREMI50Y PER PCI INHALED IN FIRST YR)

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

0.

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

0.

1.29E-06 1134 1.11E-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 XE131M

0.

2.70E-09 0.

XE133M

0.

3.59E-09 0.

XE133

0.

2.99E-09 0.

XE135M

0.

3.88E-09 0.

XE135

0.

7.55E-09 0.

XE137

0.

3.33E-08 0.

XE138+D

0.

4.38E-08 0.

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

0.

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

0.

4.69E-05 1.83E-05 1.22E-06 CS135 2.08E-05 1.82E-05 4.47E-06

0.

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

0.

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

0.

3.80E-05 1.51E-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

0.

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

0.

1.11E-13 8.08E-07 8.06E-07 BA140+D 6.84E-06 8.38E-09 4.40E-07

0.

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

0.

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

0.

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

0.

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

0.

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

0.

1.27E-06 1.50E-06 CE141 3.55E-06 2.37E-06 2.71E-07

0.

1.1IE-06 7.67E-05 1.58E-05 CE143+D 3.32E-08 2.42E-08 2.70E-09

0.

1.08E-08 1.63E-05 3.19E-05 CE144+D 6.11E-04 2.53E-04 3.28E-05

0.

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

0.

3.86E-07 6.04E-05 2.67E-05 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 6.41E-08

0.

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

0.

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

0.

5.07E-06 3.20E-04 4.10E-05 PM148 5.44E-07 8.88E-08 4.48E-08

0.

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

0.

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

0.

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

0.

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

0.

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

0.

3.34E-04 5.01E-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.OOE-04 1.96E-05 1.21E-05

0.

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

0.

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

0.

3.79E-06

0.

1.20E-05 2.97E-04 2.60E-05 H0166M 4.40E-04 1.36E-04 9.87E-05

0.

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

0.

2.95E-06 2.69E-07 WI85 2.78E-07 9.17E-08 9.73E-09

0.

9.60E-05 1.14E-05 W187 1.50E-09 1.22E-09 4.29E-10

0.

5.92E-06 2.21E-05 58

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG PB210+D 3.09E-02 8.28E-03 1.07E-03

0.

2.95E-02 4.52E-02 B1210+D

0.

2.26E-06 1.89E-07

0.

2.74E-05 1.91E-03 P0210 5.68E-04 1.22E-03 1.37E-04

0.

4.21E-03 5.41E-02 RN222+D

0.

3.94E-06 RA223+D 2.57E-04 3.93E-07 5.14E-05

0.

1.12E-05 4.39E-02 RA224+D 2.83E-05 6.77E-08 5.65E-06

0.

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

0.

1.44E-05 5.04E-02 RA226+D 1.33E-01 3.38E-06 9.87E-02

0.

9.67E-05 2.02E-01 RA228+D 5.34E-02 1.74E-06 5.88E-02

0.

4.97E-05 2.78E-01 AC225 6.04E-04 8.25E-04 4.06E-05

0.

9.47E-05 3.81 E-02 AC227+D 2.49E+00 3.69E-01 1.48E-01

0.

1.07E-01 4.16E-01 TH227+D 3.09E-04 5.56E-06 8.93E-06

0.

3.1 BE-05 6.50E-02 TH228+D 2.60E-01 4.37E-03 8.78E-03

0.

2.45E-02 1.69E+00 TH229 9.06E+00 1.36E-01 4.45E-01

0.

6.67E-01 5.05E+00 TH230 2.34E+00 1.34E-01 6.49E-02

0.

6.55E-01 8.98E-01 TH232+D 2.61E+00 1.14E-01 9.21E-02

0.

5.60E-01 8.60E-01 TH234 2.32E-06 1.35E-07 6.71 E-08

0.

7.73E-07 3.26E-04 PA231+D 5.32E+00 2.OOE-01 2.07E-01

0.

1.12E+00 9.91E-02 PA233 1.68E-06 3.24E-07 2.89E-07

0.

1.22E-06 5.39E-05 U232+D 7.31 E-02

0.

5.23E-03

0.

7.94E-03 3.84E-01 U233+D 1.55E-02

0.

9.42E-04

0.

3.63E-03 9.18E-02 U234 1.48E-02

0.

9.23E-04

0.

3.55E-03 8.99E-02 U235+D 1.42E-02

0.

8.67E-04

0.

3.34E-03 8.44E-02 U236 1.42E-02

0.

8.86E-04

0.

3.41 E-03 8.62E-02 U237 5.25E-08

0.

1.40E-08

0.

2.16E-07 1.76E-05 U238+D 1.36E-02

0.

8.10E-04

0.

3.12E-03 7.89E-02 NP237+D 1.77E+00 1.54E-01 7.21 E-02

0.

5.35E-01 8.99E-02 NP238 4.23E-07 1.13E-08 6.59E-09

0.

3.88E-08 1.75E-05 NP239 4.23E-08 3.99E-09 2.21 E-09

0.

1.25E-08 8.11 E-06 PU238 2.86E+00 4.06E-01 7.22E-02

0.

3.10E-01 3.12E-01 PU239 3.31 E+00 4.50E-01 8.05E-02

0.

3.44E-01 2.93E-01 PU240 3.31 E+00 4.49E-01 8.04E-02

0.

3.43E-01 2.93E-01 PU241+D 6.97E-02 3.57E-03 1.40E-03

0.

6.47E-03 2.60E-04 PU242 3.07E+00 4.33E-01 7.75E-02

0.

3.31 E-01 2.82E-01 PU244 3.59E+00 4.96E-01 8.88E-02

0.

3.79E-01 3.23E-01 AM241 1.06E+00 4.07E-01 7.10E-02

0.

5.32E-01 1.05E-01 AM242M 1.07E+00 3.93E-01 7.15E-02

0.

5.30E-01 4.21E-02 AM243 1.06E+00 3.92E-01 6.95E-02

0.

5.21E-01 9.91E-02 CM242 2.12E-02 2.14E-02 1.41 E-03

0.

6.40E-03 6.76E-02 CM243 8.45E-01 3.50E-01 5.OOE-02

0.

2.34E-01 1.09E-01 CM244 6.46E-01 3.03E-01 3.88E-02

0.

1.81 E-01 1.05E-01 CM245 1.32E+00 4.11 E-01 7.53E-02

0.

3.52E-01 1.01 E-01 CM246 1.31 E+00 4.11 E-01 7.52E-02

0.

3.51 E-01 1.03E-01 CM247+D 1.28E+00 4.04E-01 7.41E-02

0.

3.46E-01 1.01E-01 CM248 1.06E+01 3.33E+00 6.11 E-01

0.

2.85E+00 8.32E-01 CF252 1.29E+00

0.

3.07E-02

0.

3.43E-01 FIRST YR)

GI-LLI 3.87E-05 3.19E-05 4.45E-05 0.

3.04E-04 3.29E-04 2.89E-04 3.11E-04 5.30E-05 2.70E-04 5.38E-05 3.57E-04 3.70E-04 3.36E-04 3.95E-05 3.36E-05 7.49E-05 4.71 E-05 1.OOE-05 4.46E-05 4.12E-05 4.04E-05 5.13E-05 3.79E-05 1.29E-05 3.62E-05 5.22E-05 2.38E-05 1.65E-05 4.79E-05 4.37E-05 4.46E-05 9.17E-07 4.29E-05 6.39E-05 4.88E-05 6.14E-05 5.72E-05 5.21 E-05 5.13E-05 4.96E-05 4.63E-05 4.54E-05 5.97E-05 9.63E-04 1.89E-04 59

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG H3*

0.

1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 BE10 1.98E-04 3.06E-05 4.96E-06

0.

2.22E-04 C14 2.27E-06 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 FIB 4.71E-07

0.

5.19E-08

0.

NA22 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 P32 1.65E-04 9.64E-06 6.26E-06

0.

AR39

0.

2.08E-09 AR41

0.

8.06E-09 CA41 3.83E-05

0.

4.13E-06

0.

3.83E-06 SC46 5.51 E-05 1.07E-04 3.11 E-05

0.

9.99E-05 0.

CR51

0.

1.25E-08 7.44E-09 2.85E-09 1.80E-06 MN54

0.

4.95E-06 7.87E-07

0.

1.23E-06 1.75E-04 MN56

0.

1.55E-10 2.29E-11

0.

1.63E-10 1.1BE-06 FE55 3.07E-06 2.12E-06 4.93E-07

0.

9.01 E-06 FE59 1.47E-06 3.47E-06 1.32E-06

0.

1.27E-04 C057

0.

8.65E-08 8.39E-08

0.

4.62E-05 C058

0.

1.98E-07 2.59E-07

0.

1.16E-04 C060

0.

1.44E-06 1.85E-06

0.

7.46E-04 N159 4.06E-06 1.46E-06 6.77E-07

0.

8.20E-06 N163 5.40E-05 3.93E-06 1.81E-06

0.

2.23E-05 Nl65 1.92E-10 2.62E-11 1.14E-11

0.

7.OOE-07 CU64

0.

1.83E-10 7.69E-11

0.

5.78E-10 8.48E-07 ZN65 4.05E-06 1.29E-05 5.82E-06

0.

8.62E-06 1.08E-04 ZN69M+D 1.02E-09 2.45E-09 2.24E-10

0.

1.48E-09 2.38E-06 ZN69 4.23E-12 8.14E-12 5.65E-13

0.

5.27E-12 1.15E-07 SE79

0.

3.83E-07 6.09E-08

0.

5.69E-07 4.47E-05 BR82

0.

1.69E-06

0.

BR83+D

0.

3.01 E-08

0.

BR84

0.

3.91 E-08

0.

BR85

0.

1.60E-09

0.

KR83M

0.

5.19E-10 KR85M

0.

2.91 E-09 KR85

0.

2.41 E-09 KR87

0.

1.53E-08 KR88+D

0.

3.13E-08 KR89

0.

2.13E-08 RB86

0.

1.69E-05 7.37E-06

0.

RB87

0.

9.86E-06 3.21E-06

0.

RB88

0.

4.84E-08 2.41 E-08

0.

RB89+D

0.

3.20E-08 2.12E-08

0.

SR89+D 3.80E-05

0.

1.09E-06

0.

1.75E-04 SR90+D 1.24E-02

0.

7.62E-04

0.

1.20E-03 SR91+D 7.74E-09

0.

3.13E-10

0.

4.56E-06 SR92+D 8.43E-10

0.

3.64E-11

0.

2.06E-06 FIRST YR)

GI-LLI 1.58E-07 1.67E-05 4.26E-07 6.27E-09 9.24E-09 1.30E-05 1.28E-06 1.08E-05 0.

0.

2.86E-07 3.23E-05 4.15E-07 9.67E-06 2.53E-06 7.54E-07 2.35E-05 3.93E-06 1.33E-05 3.56E-05 6.11 E-07 1.67E-06 1.54E-06 6.12E-06 6.68E-06 1.71 E-05 2.04E-09 3.33E-06 1.30E-06 2.90E-08 2.05E-13 0.

0.

2.08E-06 2.88E-07 4.18E-19 1.1 6E-21 4.37E-05 9.02E-05 2.39E-05 5.38E-06

Includes a 50% increase to account for percutaneous transpiration.

60

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

ADULT INHALATION DOSE COMMITMENT FACTORS ISOTOPE Y90 Y91M+D Y91 Y92 Y93 ZR93+D ZR95+D ZR97+D NB93M NB95 NB97 M093 MO99+D TC99M TC99 TC101 RU1 03+D RU 105+D RU106+D RH105 PD107 PD109 AG110M+D AG111 CD113M CD115M SN123 SN125+D SN126+D SB124 SB125+D SB126 SB127 TE125M TE127M+D TE127 TE129M+D TE129 TE131M+D TE131+D TE132+D TE133M+D TE134+D 1129 1130 1131+D BONE 2.61 E-07 3.26E-11 5.78E-05 1.29E-09 1.18E-08 5.22E-05 1.34E-05 1.21 E-08 3.10E-05 1.76E-06 2.78E-1 I 0.

0.

1.29E-13 3.13E-08 5.22E-1 5 1.91 E-07 9.88E-1 1 8.64E-06 9.24E-10 0.

0.

1.35E-06 4.25E-08 0.

0.

3.02E-05 1.1 6E-06 1.58E-04 3.90E-06 6.67E-06 4.50E-07 3.30E-08 4.27E-07 1.58E-06 1.75E-1 0 1.22E-06 6.22E-12 8.74E-09 1.39E-12 3.25E-08 7.24E-12 3.84E-12 2.48E-06 5.72E-07 3.15E-06 LIVER 0.

0.

2.92E-06 4.30E-06 2.45E-09 1.01 E-05 9.77E-07 7.03E-12 1.17E-06 1.51 E-08 3.64E-1 3 4.64E-08 7.52E-1 5 0.

0.

6.73E-1 0 8.27E-08 4.63E-10 1.25E-06 1.78E-08 1.54E-04 2.46E-05 6.67E-07 3.12E-08 4.18E-06 7.36E-08 7.44E-08 9.13E-09 7.22 E-1 0 1.98E-07 7.21 E-07 8.03E-1 1 5.84E-07 2.99E-12 5.45E-09 7.44E-1 3 2.69E-08 5.40E-12 3.22E-1 2 2.11E-06 1.68E-06 4.47E-06 TOTAL BODY 7.01 E-09 1.27E-12 1.55E-06 3.77E-1 I 3.26E-10 1.37E-06 2.91 E-06 1.13E-09 2.49E-06 5.26E-07 2.56E-12 3.17E-08 2.87E-09 4.63E-12 1.25E-08 7.38E-14 8.23E-08 3.89E-1 1 1.09E-06 4.43E-10 5.87E-09 1.16E-10 7.43E-07 8.87E-09 4.97E-06 7.95E-07 9.82E-07 7.03E-08 6.OOE-06 1.55E-06 1.58E-06 1.62E-07 1.27E-08 5.84E-08 1.96E-07 3.87E-1 1 1.98E-07 1.55E-12 3.63E-09 4.49E-1 3 2.02E-08 4.17E-12 1.57E-12 6.91 E-06 6.60E-07 2.56E-06 (MREM/50Y PER PCI INHALED IN FIRST YR)

THYROID KIDNEY LUNG GI-LLI

0.

2.12E-05 6.32E-05

0.

2.40E-07 1.66E-10

0.

2.13E-04 4.81E-05

0.

1.96E-06 9.19E-06

0.

6.06E-06 5.27E-05

0.

1.11E-05 2.13E-05 1.51E-06

0.

6.77E-06 2.21 E-04 1.88E-05

0.

3.71 E-09 9.84E-06 6.54E-05

0.

1.16E-05 3.11E-05 2.38E-06

0.

9.67E-07 6.31 E-05 1.30E-05

0.

8.18E-12 3.OOE-07 3.02E-08

0.

3.55E-07 5.11 E-05 3.79E-06

0.

3.64E-08 1.14E-05 3.10E-05

0.

5.52E-12 9.55E-08 5.20E-07

0.

5.85E-07 1.01 E-04 7.54E-06

0.

1.35E-13 4.99E-08 1.36E-21

0.

7.29E-07 6.31 E-05 1.38E-05

0.

1.27E-10 1.37E-06 6.02E-06

0.

1.67E-05 1.17E-03 1.14E-04

0.

2.86E-09 2.41 E-06 1.09E-05

0.

6.57E-07 9.47E-06 7.06E-07

0.

2.35E-09 1.85E-06 1.52E-05

0.

2.46E-06 5.79E-04 3.78E-05

0.

5.74E-08 2.33E-05 2.79E-05

0.

1.71 E-04 2.08E-04 1.59E-05

0.

1.98E-05 1.76E-04 4.80E-05 5.67E-07

0.

2.88E-04 3.92E-05 2.59E-08

0.

7.37E-05 6.81 E-05 1.23E-06

0.

1.17E-03 1.59E-05 9.44E-09

0.

3.10E-04 5.08E-05 6.75E-09

0.

2.18E-04 1.26E-05 2.75E-09

0.

9.57E-05 6.01 E-05 3.97E-10

0.

2.05E-05 3.77E-05 1.31 E-07 1.55E-06 3.92E-05 8.83E-06 4.11 E-07 5.72E-06 1.20E-04 1.87E-05 1.32E-10 6.37E-10 8.14E-07 7.17E-06 4.30E-07 4.57E-06 1.45E-04 4.79E-05 4.87E-12 2.34E-11 2.42E-07 1.96E-08 6.88E-09 3.86E-08 1.82E-05 6.95E-05 1.17E-12 5.46E-12 1.74E-07 2.30E-09 2.37E-08 1.82E-07 3.60E-05 6.37E-05 6.27E-12 3.74E-11 5.51E-07 5.49E-08 3.44E-12 2.18E-11 4.343-07 2.97E-11 5.54E-03 4.53E-06

0.

2.22E-07 1.42E-04 2.61 E-06

0.

9.61 E-07 1.49E-03 7.66E-06

0.

7.85E-07 61

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG 1132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.

1133+D 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0.

1134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.

1135+D 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0.

XE131M

0.

1.40E-09 XE133M

0.

1.89E-09 XE133

0.

1.57E-09 XE135M

0.

2.22E-09 XE135

0.

4.05E-09 XE137

0.

1.74E-08 XE138+D

0.

2.44E-08 CS134M+D 1.59E-08 3.20E-08 1.72E-08

0.

1.83E-08 2.93E-09 CS134 4.66E-05 1.06E-04 9.1OE-05

0.

3.59E-05 1.22E-05 CS135 1.46E-05 1.29E-05 5.99E-06

0.

5.11E-06 1.57E-06 CS136 4.88E-06 1.83E-05 1.38E-05

0.

1.07E-05 1.50E-06 CS137+D 5.98E-05 7.76E-05 5.35E-05

0.

2.78E-05 9.40E-06 CS138 4.14E-08 7.76E-08 4.05E-08

0.

6.OOE-08 6.07E-09 CS139+D 2.56E-08 3.63E-08 1.39E-08

0.

3.05E-08 2.84E-09 BA139 1.17E-10 8.32E-14 3.42E-12

0.

7.78E-14 4.70E-07 BA140+D 4.88E-06 6.13E-09 3.21 E-07

0.

2.09E-09 1.59E-04 BA141+D 1.25E-11 9.41E-15 4.20E-13

0.

8.75E-15 2.42E-07 BA142+D 3.29E-12 3.38E-15 2.07E-13

0.

2.86E-15 1.49E-07 LA140 4.30E-08 2.17E-08 5.73E-09

0.

1.70E-05 LA141 5.34E-10 1.66E-10 2.71E-11

0.

1.35E-06 LA142 8.54E-11 3.88E-11 9.65E-12

0.

7.91E-07 CE141 2.49E-06 1.69E-06 1.91 E-07

0.

7.83E-07 4.52E-05 CE143+D 2.33E-08 1.72E-08 1.91E-09

0.

7.60E-09 9.97E-06 CE144+D 4.29E-04 1.79E-04 2.30E-05

0.

1.06E-04 9.72E-04 PR143 1.17E-06 4.69E-07 5.80E-08

0.

2.70E-07 3.51E-05 PR144 3.76E-12 1.56E-12 1.91E-13

0.

8.81E-13 1.27E-07 ND147+D 6.59E-07 7.62E-07 4.56E-08

0.

4.45E-07 2.76E-05 PM147 8.37E-05 7.87E-06 3.19E-06

0.

1.49E-05 6.60E-05 PM148M+D 9.82E-06 2.54E-06 1.94E-06

0.

3.85E-06 2.14E-04 PM148 3.84E-07 6.37E-08 3.20E-08

0.

1.20E-07 3.91E-05 PM149 3.44E-08 4.87E-09 1.99E-09

0.

9.19E-09 7.21E-06 PM151 8.50E-09 1.42E-09 7.21E-10

0.

2.55E-09 3.94E-06 SM151 8.59E-05 1.48E-05 3.55E-06

0.

1.66E-05 4.45E-05 SM153 1.70E-08 1.42E-08 1.04E-09

0.

4.59E-09 4.14E-06 EU152 2.38E-04 5.41E-05 4.76E-05

0.

3.35E-04 3.43E-04 EU154 7.40E-04 9.10E-05 6.48E-05

0.

4.36E-04 5.84E-04 EU155 1.01E-04 1.43E-05 9.21E-06

0.

6.59E-05 9.46E-05 EU156 1.93E-06 1.48E-06 2.40E-07

0.

9.95E-07 8.56E-05 TB160 2.21E-05

0.

2.75E-06

0.

9.10E-06 1.92E-04 H0166M 3.37E-04 1.05E-04 8.OOE-05

0.

1.57E-04 3.94E-04 W181 6.23E-09 2.03E-09 2.17E-10

0.

1.71E-06 W185 1.95E-07 6.47E-08 6.81 E-09

0.

5.57E-05 W187 1.06E-09 8.85E-10 3.10E-10

0.

3.63E-06 FIRST YR)

GI-LLI 5.08E-08 1.11E-06 1.26E-10 6.56E-07 0.

0.

7.92E-09 1.30E-06 2.11E-07 1.46E-06 1.05E-06 2.33E-1 3 5.49E-31 1.12E-07 2.73E-05 1.45E-17 1.96E-26 5.73E-05 7.31 E-06 2.64E-07 1.50E-05 2.83E-05 1.02E-04 2.50E-05 2.69E-18 2.16E-05 5.54E-06 4.18E-05 5.80E-05 2.50E-05 2.OOE-05 3.25E-06 1.58E-05 1.59E-05 3.40E-05 5.95E-06 4.50E-05 2.68E-05 1.59E-05 2.53E-07 1.07E-05 1.94E-05 62

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.7 (continued)

ADULT INHALATION DOSE COMMITMENT FACTORS ISOTOPE BONE LIVER TOTAL BODY PB210+D 2.64E-02 6.73E-03 8.37E-04 B1210+D

0.

1.59E-06 1.32E-07 P0210 3.97E-04 8.60E-04 9.58E-05 RN222+D

0.

RA223+D 1.80E-04 2.77E-07 3.60E-05 RA224+D 1.98E-05 4.78E-08 3.96E-06 RA225+D 3.OOE-04 3.56E-07 5.99E-05 RA226+D 1.25E-01 2.39E-06 9.14E-02 RA228+D 4.41 E-02 1.23E-06 4.78E-02 AC225 4.23E-04 5.82E-04 2.84E-05 AC227+D 2.30E+00 3.05E-01 1.36E-01 TH227+D 2.17E-04 3.92E-06 6.25E-06 TH226+D 2.OOE-01 3.39E-03 6.77E-03 TH229 8.88E+00 1.33E-01 4.36E-01 TH230 2.29E+00 1.31E-01 6.36E-02 TH232+D 2.56E+00 1.12E-01 9.04E-02 TH234 1.63E-06 9.56E-08 4.70E-08 PA231 +D 5.08E+00 1.91 E-01 1.98E-01 PA233 1.21 E-06 2.42E-07 2.09E-07 U232+D 5.14E-02

0.

3.66E-03 U233+D 1.09E-02

0.

6.60E-04 U234 1.04E-02

0.

6.46E-04 U235+D 1.OOE-02

0.

6.07E-04 U236 1.OOE-02

0.

6.20E-04 U237 3.67E-08

0.

9.77E-09 U238+D 9.58E-03

0.

5.67E-04 NP237+D 1.69E+00 1.47E-01 6.87E-02 NP238 2.96E-07 8.OOE-09 4.61 E-09 NP239 2.87E-08 2.82E-09 1.55E-09 PU238 2.74E+00 3.87E-01 6.90E-02 PU239 3.19E+00 4.31E-01 7.75E-02 PU240 3.18E+00 4.30E-01 7.73E-02 PU241+D 6.41 E-02 3.28E-03 1.29E-03 PU242 2.95E+00 4.15E-01 7.46E-02 PU244 3.45E+00 4.76E-01 8.54E-02 AM241 1.01E+00 3.59E-01 6.71 E-02 AM242M 1.02E+00 3.46E-01 6.73E-02 AM243 1.01 E+00 3.47E-01 6.57E-02 CM242 1.48E-02 1.51 E-02 9.84E-04 CM243 7.86E-01 2.97E-01 4.61 E-02 CM244 5.90E-01 2.54E-01 3.51 E-02 CM245 1.26E+00 3.59E-01 7.14E-02 CM246 1.25E+00 3.59E-01 7.13E-02 CM247+D 1.22E+00 3.53E-01 7.03E-02 CM248 1.01 E+01 2.91 E+00 5.79E-01 CF252 9.78E-01

0.

2.33E-02 (MREM/50Y THYROID 0.

0.

PER PCI INHALED IN FIRST YR)

KIDNEY 2.12E-02 1.92E-05 2.95E-03 0.

7.85E-06 1.35E-06 1.01 E-05 6.77E-05 3.48E-05 6.63E-05 9.82E-02 2.22E-05 1.89E-02 6.52E-01 6.40E-01 5.47E-01 5.41 E-07 1.07E+00 9.15E-07 5.56E-03 2.54E-03 2.49E-03 2.34E-03 2.39E-03 1.51 E-07 2.18E-03 5.1 OE-01 2.72E-08 8.75E-09 2.96E-01 3.30E-01 3.29E-01 5.93E-03 3.17E-01 3.64E-01 5.04E-01 5.01 E-01 4.95E-01 4.48E-03 2.15E-01 1.64E-01 3.33E-01 3.33E-01 3.28E-01 2.70E+00 0.

LUNG 2.62E-02 1.11E-03 3.14E-02 2.05E-06 2.55E-02 8.77E-03 2.92E-02 1.17E-01 1.61 E-01 2.21 E-02 2.41 E-01 3.77E-02 1.01 E+00 3.49E+00 6.21 E-01 5.96E-01 1.89E-04 5.75E-02 3.52E-05 2.22E-01 5.32E-02 5.22E-02 4.90E-02 5.OOE-02 1.02E-05 4.58E-02 5.22E-02 1.02E-05 4.70E-06 1.82E-01 1.72E-01 1.72E-01 1.52E-04 1.65E-01 1.89E-01 6.06E-02 2.44E-02 5.75E-02 3.92E-02 6.31 E-02 6.06E-02 5.85E-02 5.96E-02 5.85E-02 4.82E-01 1.99E-01 GI-LLI 3.65E-05 2.95E-05 4.19E-05 0.

2.84E-04 3.01 E-04 2.71 E-04 2.94E-04 5.OOE-05 2.52E-04 5.08E-05 3.34E-04 3.49E-04 3.17E-04 3.73E-05 3.17E-05 7.03E-05 4.44E-05 1.02E-05 4.21 E-05 3.89E-05 3.81 E-05 4.84E-05 3.57E-05 1.20E-05 3.41 E-05 4.92E-05 2.13E-05 1.49E-05 4.52E-05 4.13E-05 4.21 E-05 8.65E-07 4.05E-05 6.03E-05 4.60E-05 5.79E-05 5.40E-05 4.91 E-05 4.84E-05 4.68E-05 4.36E-05 4.29E-05 5.63E-05 9.09E-04 1.78E-04 63

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.8 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (DFGI)

(MREMIHR PER PCIIM 2)

ELEMENT TOTAL BODY SKIN H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m TC-101 0.0 0.0 2.50E-08 0.0 2.20E-1 0 5.80E-09 1.1OE-08 0.0 8.OOE-09 7.OOE-09 1.70E-08 0.0 3.70E-09 1.50E-09 4.OOE-09 0.0 6.40E-11 1.20E-08 0.0 6.30E-1 0 3.50E-09 1.50E-08 5.60E-1 3 7.1 OE-09 9.OOE-09 2.20E-12 3.80E-09 2.40E-1 I 1.60E-09 5.70E-1 0 5.OOE-09 5.50E-09 5.10E-09 1.90E-09 9.60E-10 2.70E-09 0.0 0.0 2.90E-08 0.0 2.60E-1 0 6.80E-09 1.30E-08 0.0 9.40E-09 8.20E-09 2.OOE-08 0.0 4.30E-09 1.70E-09 4.60E-09 0.0 9.30E-1 1 1.40E-08 0.0 7.20E-1 0 4.OOE-09 1.80E-08 6.50E-1 3 8.30E-09 1.OOE-08 2.60E-12 4.40E-09 2.70E-11 1.90E-09 7.80E-1 0 5.80E-09 6.40E-09 6.OOE-09 2.20E-09 1.1OE-09 3.OOE-09 I

64

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.8 (continued)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (DFGi)

(MREM/HR PER PCIIM2)

ELEMENT TOTAL BODY SKIN Ru-1 03 Ru-1 05 Ru-106 Ag-1 1 Om Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 1-130 1-131 1-132 1-133 1-134 1-135 Cs-1 34 Cs-1 36 Cs-137 Cs-138 Ba-1 39 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-1 44 Nd-147 W-187 Np-239 3.60E-09 4.50E-09 1.50E-09 1.80E-08 3.50E-11 1.10E-12 1.OOE-11 7.70E-1 0 7.10E-10 8.40E-09 2.20E-09 1.70E-09 1.40E-08 2.80E-09 1.70E-08 3.70E-09 1.60E-08 1.20E-08 1.20E-08 1.50E-08 4.20E-09 2.1 OE-08 2.40E-09 2.1 OE-09 4.30E-09 7.90E-09 1.50E-08 1.50E-08 5.50E-1 0 2.20E-09 3.20E-1 0 0.0 2.00E-10 1.OOE-09 3.1 OE-09 9.50E-1 0 4.20E-09 5.1 OE-09 1.80E-09 2.1 OE-08 4.80E-11 1.30E-12 1.1OE-11 9.OOE-10 8.40E-1 0 9.90E-09 2.60E-06 2.OOE-09 1.70E-08 3.40E-09 2.OOE-08 4.50E-09 1.90E-08 1.40E-08 1.40E-08 1.70E-08 4.90E-09 2.40E-08 2.70E-09 2.40E-09 4.90E-09 9.OOE-09 1.70E-08 1.80E-08 6.20E-1 0 2.50E-09 3.70E-1 0 0.0 2.30E-1 0 1.20E-09 3.60E-09 1.10E-09 65

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.9 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES I

Nuclide Ag-11 Om Ar-41 Ba-1 39 Ba-140 Br-82 C-14 Ce-141 Ce-144 Co-57 Co-58 Co-60 Cr-51 Cs-134 Cs-136 Cs-1 37 Cs-138 Fe-55 Fe-59 H-3 1-129 1-131 1-132 1-133 1-134 1-135 Organ GI-Tract-T Total Body GI Tract-C Lung-T total Body-C Bone-C GI Tract-T GI Tract-T GI Tract-T GI Tract-T GI Tract-T GI Tract-A Liver-C Liver-I Bone-C Total body-C Bone-C GI Tract-T Total Body-C Thyroid-A Thyroid-I Thyroid-C Thyroid-C Thyroid-C Thyroid-C Dose Factor Mrem/Ci 2.13E+00 3.64E - 04 2.97E - 03 1.26E - 01 4.97E - 03 1.48E - 01 1.34E- 01 3.37E+00 8.53E - 02 2.59E - 01 6.86E+00 3.75E - 03 8.77E+00 5.32E-01 9.58E+00 1.OOE - 01 2.06E - 01 3.20E - 01 2.19E -04 3.66E+02 1.97E+01 1.12E - 02 2.46E - 01 2.45E - 03 4.93E - 02 Design Objective Annual Quantity Ci 7.04E+00 1.37E+04 5.05E+03 1.19E+02 1.01E+03 1.01 E+02 1.12E+02 4.45E+00 1.76E+02 5.79E+01 2.19E+00 1.33E+03 1.71 E+00 2.82E+01 1.57E+00 5.OOE+01 7.28E+01 4.69E+01 2.28E+04 4.1 OE - 02 7.61E - 01 1.34E+03 6.11E+01 6.12E+03 3.04E+02 66

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.9 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES I

Nuclide Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Kr-89 La-140 Mn-54 Mn-56 Mo-99 N-13 Na-24 Nb-95 Ni-63 Ni-65 Np-239 Rb-88 Ru-1 03 Ru-1 05 Sb-124 Sb-125 Sr-89 Sr-90 Sr-91 Sr-92 Oraan Skin Skin Total Body Skin Total Body Total Body GI Tract-T GI Tract-T GI Tract-C GI Tract-T Total Body-C Total Body-C GI Tract-A Bone-C GI Tract-C GI Tract-T Total Body-C GI Tract-A GI Tract-C GI Tract-T GI Tract-T Bone-C Bone-C Bone-I GI Tract-C Dose Factor Mrem/Ci 8.82E - 07 9.14E - 05 5.22E - 05 8.03E - 04 6.35E - 04 5.08E - 04 3.04E - 02 6.29E - 01 6.91 E - 03 1.66E - 02 3.44E- 06 4.02E- 03 1.92E - 01 1.21 E+01 4.70E - 03 8.13E - 03 2.38E - 05 2.93E - 01 5.82E - 03 9.47E- 01 4.35E - 01 8.98E+00 3.73E+02 2.46E+00 1.37E - 02 Design Objective Annual Quantity Ci 1.70E+07 1.64E+05 9.58E+04 1.87E+04 7.87E+03 9.84E+03 4.93E+02 2.38E+01 2.17E+03 9.04E+02 1.45E+06 1.24E+03 7.81 E+01 1.24E+00 3.19E+03 1.84E+03 2.1 OE+05 5.12E+01 2.58E+03 1.58E+01 3.45E+01 1.67E+00 4.02E- 02 6.1 OE+00 1.09E+03 67

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 1.9 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES I

Nuclide Tc-99 Tc-99m Tc-101 Te-127 Xe-1 31m Xe-133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 Zn-65 Zr-95 Pu-238 Pu-239 Pu-241 Am-241 Cm-242 Cm-244 Oraan GI Tract-T GI Tract-T GI Tract-T GI Tract-T Skin Total Body Skin Total Body Total Body Skin Total body Liver-C Gl Tract-T Bone-T Bone-T Bone-T Bone-T Lung-T Bone-T Dose Factor Mrem/Ci 5.85E - 01 3.64E - 04 8.33E - 05 4.87E - 03 4.03E - 05 1.39E - 05 8.39E - 05 8.32E- 05 9.55E - 05 5.85E - 04 2.70E - 04 9.38E - 01 3.90E - 01 1.42E+03 1.64E+03 3.45E+01 5.25E+02 3.35E+01 3.20E+02 Design Objective Annual Quantity Ci 2.62E+01 4.12E+04 1.80E+05 3.08E+03 3.72E+05 3.60E+05 1.79E+05 6.01 E+04 5.24E+04 2.56E+04 1.85E+04 1.60E+01 3.85E+01 1.06E - 02 9.15E - 03 4.35E - 01 2.86E - 02 4.48E - 01 4.69E - 02 68

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 LIQUID EFFLUENTS A.

CONCENTRATION

1.

Requirements Appendix A,Section III.G requires that the concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to ten times the Effluent Concentration (EC) specified in 10 CFR 20, Appendix B, Table 2, Column 2 for nuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 piCi/ml total activity.

To ensure compliance, the following approach will be used for each release.

2.

Prerelease Analysis Most tanks will be recirculated through two volume changes prior to sampling for release to the environment to ensure that a representative sample is obtained. The appropriate recirculation time for those tanks too large to provide two volume changes will be the time that the suspended particulate concentration reaches steady state. Either a one-time test, or prior sampling data, may be 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=

C Ci (2.1) i=1 where:

C

=

Total concentration in the liquid effluent at the release point, jiCi/ml.

C,

=

Concentration of a single radionuclide i, piCi/ml.

69

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18

3.

Effluent Concentration (EC) - Sum of the Ratios The EC-Fraction (Rj) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 10 CFR 20:

Rj= EC <10.0 (2.2) where:

C;

=

Effluent concentration of radionuclide i, pCi/ml.

ECQ

=

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

Rj

=

The Total EC-Fraction for the release point.

The sum of the ratios at the discharge to the lake must be < 10 due to the releases from any or all concurrent releases. The following relationship will assure this criterion is met:

f1(Ri-1)+f 2(R2-1) + f3(R3-1)< F (2.3) where:

flh=

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

R1,R2,R3

=

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 b1 is a conservative factor greater than 1.0.

70

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 B.

INSTRUMENT SETPOINTS

1.

Setpoint Determination Appendix A, Section lIl.F requires alarm setpoints for each liquid effluent monitor will be established using Plant instructions to ensure the requirements of Appendix A,Section III.G are not exceeded.

Concentration, flow rate, dilution, principal gamma emitter, geometry, and detector efficiency are combined to give an equivalent setpoint in counts per minute (cpm). The identification number for each liquid effluent radiation detector is contained in Figure 2-2.

The respective alarm/trip setpoints at each release point will be set such that the sum of the ratios at each point, as calculated by Equation 2.2, will not be exceeded. The value of R is directly related to the total concentration calculated by Equation 2.1. An increase in the concentration would indicate an increase in the value of R. A large increase would cause the limits specified in Section 2.1.1 to be exceeded. The minimum alarm/trip setpoint value is equal to the release concentration, but for ease of operation it may be desired that the setpoint (S) be set above the effluent concentration (C) by the same factor (b) utilized in setting dilution flow. That is:

S=bxC (2.4)

Liquid effluent flow paths and release points are indicated in 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.

71

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18

3.

Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in Section 1 were not exceeded.

A composite list on concentrations (CQ), by isotope, will be used with the actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.3 to demonstrate compliance with the limits in Section 1. This data and setpoints will be recorded in auditable records by Plant personnel.

C.

DOSE

1.

RETS Requirement Appendix A,Section III.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.

72

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18

2.

Release Analysis Calculations shall be performed for each batch release, and weekly for continuous releases according to the formula:

Ai/Ci<0.5 (2.5) where:

Ai

=

Cumulative quarterly activity of nuclide i identified in liquid release (C;).

C;

=

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 consequence 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 III.H.1 has been met.

Values for the design basis quantities (CQ), and the dose per Curie (Dc/Cc)i for each nuclide i shown in Table 2.2, were calculated as follows in Sections 2.1 and 2.2.

a.

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

Dj Z (DCF},jxli (2.6) i=1 where:

Dj

=

Dose for the jth organ from radionuclides releases, mrem.

j

=

The organ of interest.

73

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 (DCF)i

=

Ingestion dose commitment factor for the jth organ from the jth radionuclide mrem/pCi, see Table 2.1.

I

=

Activity ingested of the ith radionuclide, pCi.

Ii is described by:

i = (AIV)(3 65) (1EO6) wh(1 e

)(d) where:

365

=

Days per year.

A

=

Annual activity released of jth radionuclide, pCi.

V Average rate of water consumption (2000 ml/d - adult, 1400 ml/d - teen and child, 900 ml/d - infant, ICRP 23, p 358).

d

=

Dilution water flow for year, ml.

1000 =

Dispersion factor from discharge to nearest drinking water supply.

1 E06 =

Conversion pCi to pCi.

The dose equation then becomes:

Dj= (3.65E05)(V) X (DCF),jxAimrem d i=1 (2.7)

(2.8) 74

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18

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 jth radionuclide (Ii) is described by:

I= A1BiF(1E09) =pCi (2.9) where:

A;

=

Annual released of ith radionuclide, piCi.

B1

=

Fish concentration factor of ith radionuclide Cl/gm PCi/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.

1 E09 =

Conversion of jiCi and Kgm to gross.

Substitution of Equation 2.9 into Equation 2.6 gives:

i i

m 75

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 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 LADTAP. The dose to the jth organ from m radionuclides, Dj, is described by:

m Dj= X Dq mrem (2.11) i=1 m

= E (DCF) 1 x IJ mrem i=1 where:

Dj

=

Dose to the jth organ from the ith radionuclide, mrrem.

j

=

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

(DCF)ij

=

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

i

=

Activity ingested of the ith radionuclide, pCi.

I1 for water ingestion is described by:

1=AiVr pCi (2.13) vd and for fish ingestion Ii is described by:

11= Ai B Fr Pci v d 76

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 where:

Ai

=

Activity release of jth radionuclide during the year, pCi.

V

=

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

F

=

Number of days during the year (365 d).

v

=

Dispersion factor from point of discharge to point of exposure.

d

=

Dilution water volume (ml).

Bi

=

Fish concentration factor of the ith radionuclide, pCi/gm Table 2.0, PC/mi F

=

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

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, III.H.1. Maintaining the cumulative fraction if allowable release for each batch release and 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.

77

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 E.

RELEASE RATE FOR OFFSITE EC (50 MREMNYR) 10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. Concentrations at this 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 3.88E-03 mrem. This is only 0.13% of the more conservative 50 mrem/yr total body value.

78

I-lz

-iI.

-J z

0 4C.

-j z4 20

-j U)w a,

II.

U.

0 co V-0 0)

TI IL2 a) hir 3)

CO) n LU I-0 z

U) w en LI

PALISADES RADWASTE EFFLUENTS - LIQUID CLFAN WAS It SYSILM STEAPAGEN BLOWDOWN PRIMARY QTANK M

S70ORAGE 01 R U07 z

TREK RE z

~TREAIID)

Z WASTE 7 90 J

Z TANKS471 TRIP&FLOWCONTROL o-c

<DNYWSL RELAK830

-JM C

.INI SERVICE mr\\

M MISCELLANEOUS WASTE SYSTEM LAKE C

_u LAUNDRY UTILITY B l3_

0n SYSSEM WATER

<0c TANK ju TURBINE BLDG lILILE1Lf ILWASTFE jDRAINS

u.

~~TANKTUBN Li.

SM RE 01

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.0 BIOACCUMULATION FACTORS pCilgm per uCilml FRESHWATER FISH ELEMENT H

C NA P

CR MN FE CO NI CU ZN BR RB SR y

ZR NB MO TC RU RH TE I

CS BA LA CE PR ND W

NP 9.OE-01 4.6E 03 1.0E 02 1.OE 05 2.0E 02 4.OE 02 1.OE 02 5.0E 01 1.OE 02 5.OE 01 2.OE 03 4.2E 02 2.OE 03 3.0E 01 2.5E 01 3.3E 00 3.0E 04 1.OE 01 1.5E 01 1.OE 01 1.OE 01 4.0E 02 1.5E 01 2.OE 03 4.OE 00 2.5E 01 1.OE 00 2.5E 01 2.5E 01 1.2E 03 1.OE 01 81

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3

0.

3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.083-07 BE10 1.71E-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

0.

4.43E.07

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 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01E-05 1.01 E-05 P32 1.70E-03 1.OOE-04 6.59E-05

0.

2.30E-05 AR39

0.

AR41

0.

CA41 3.74E-04

0.

4.08E-05

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.

1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MN54

0.

1.99E-05 4.51E-06

0.

4.41E-06

0.

7.31E-06 MN56

0.

8.18E-07 1.41E-07

0.

7.03E-07

0.

7.43E-05 FE55 1.39E-05 8.98E-06 2.40E-06

0.

4.39E-06 1.14E-06 FE59 3.08E-05 5.38E-05 2.12E-05

0.

1.59E-05 2.57E-05 C057

0.

1.15E-06 1.87E-06

0.

3.92E-06 C058

0.

3.60E-06 8.98E-06

0.

8.97E-06 C060

0.

1.08E-05 2.55E-05

0.

2.57E-05 N159 4.78E-05 1.45E-05 8.17E-06

0.

7.16E-07 N163 6.34E-04 3.92E-05 2.20E-05

0.

1.95E-06 N165 4.70E-06 5.32E-07 2.42E-07

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 2.91E-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

0.

2.10E-05 3.90E-06

0.

2.43E-05

0.

5.58E-07 BR82

0.

1.27E-05

0.

BR83+D

0.

3.63E-07

0.

BR84

0.

3.82E-07

0.

BR85

0.

1.94E-08

0.

KR83M

0.

KR85M

0.

KR85

0.

KR87

0.

KR88+D

0.

KR89

0.

RB86

0.

1.70E-04 8.40E-05

0.

4.35E-06 RB87

0.

8.88E-05 3.52E-05

0.

5.98E-07 RB88

0.

4.98E-07 2.73E-07

0.

4.85E-07 RB89+D

0.

2.86E-07 1.97E-07

0.

9.74E-08 SR89+D 2.51E-03

0.

7.20E-05

0.

5.16E-05 SR90+D 1.85E-02

0.

4.71 E-03

0.

2.31 E-04 SR91+D 5.OOE-05

0.

1.81E-06

0.

5.92E-05 SR92+D 1.92E-05

0.

7.13E-07

0.

2.07E-04 82

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG

.GI-LLI Y90 8.69E-08

0.

2.33E-09

0.

1.20E-04 Y91M+D 8.10E-10

0.

2.76E-11

0.

2.70E-06 Y91 1.13E-06

0.

3.01E-08

0.

8.1OE-05 Y92 7.65E-09

0.

2.15E-10

0.

1.46E-04 Y93 2.43E-08

0.

6.62E-10

0.

1.92E-04 ZR93+D 1.93E-07 9.18E-08 5.54E-08

0.

2.71E-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 NB93M 1.23E-07 3.33E-08 1.04E-08

0.

3.25E-08

0.

3.98E-06 NB95 4.20E-08 1.73E-08 1.OOE-08

0.

1.24E-08

0.

1.46E-05 NB97 4.59E-10 9.79E-11 3.53E-11

0.

7.65E-11

0.

3.09E-05 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 5.10E-08

0.

4.26E-08 2.07E-09 1.15E-06 TC99 1.08E-06 1.46E-06 4.55E-07

0.

1.23E-05 1.42E-07 6.31 E-06 TC101 2.27E-09 2.86E-09 2.83E-08

0.

3.40E-08 1.56E-09 4.86E-07 RU103+D 1.48E-06

0.

4.95E-07

0.

3.08E-06

0.

1.80E-05 RU105+D 1.36E-07

0.

4.58E-08

0.

1.OOE-06

0.

5.41E-05 RU106+D 2.41E-05

0.

3.01E-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 AGIIOM+D 9.96E-07 7.27E-07 4.81E-07

0.

1.04E-06

0.

3.77E-05 AG111 5.20E-07 2.02E-07 1.07E-07

0.

4.22E-07

0.

4.82E-05 CD113M

0.

1.77E-05 6.52E-07

0.

1.34E-05

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

0.

6.58E-05 SN125+D 7.4iE-05 1.38E-06 3.29E-06 1.36E-06

0.

1.IIE-04 SN126+D 5.53E-04 7.26E-06 1.80E-05 1.91 E-06

0.

2.52E-05 SB124 2.14E-05 3.15E-07 6.63E-06 5.68E-08

0.

1.34E-05 6.60E-05 SB125+D 1.23E-05 1.19E-07 2.53E-06 1.54E-08

0.

7.72E-06 1.64E-05 SB126 8.06E-06 1.58E-07 2.91E-06 6.19E-08

0.

5.07E-06 8.35E-05 SB127 2.23E-06 3.98E-08 6.90E-07 2.84E-08

0.

1.15E-06 5.91E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06

0.

1.11E-05 TE127M+D 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04

0.

2.36E-05 TE127 1.OOE-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06

0.

2.10E-05 TE129M+D 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04

0.

5.97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07

0.

2.27E-05 TE131M+D 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05

0.

1.03E-04 TE131+D 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07

0.

7.11E-06 TE132+D 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05

0.

3.81E-05 TE133M+D' 3.91E-07 1.79E-07 1.71E-07 3.45E-07 1.22E-06

0.

1.93E-05 TE134+D 2.67E-07 1.34E-07 1.38E-07 2.39E-07 9.03E-07

0.

3.06E-06 1129 2.86E-05 2.12E-05 1.55E-05 1.36E-02 2.51E-05

0.

4.24E-07 1130 6.OOE-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

0.

1.51E-06 83

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06

0.

2.73E.06 1133+D 1.25E-05 1.82E-05 5.33E-06 3.31 E-03 2.14E-05

0.

3.08E-06 1134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06

0.

1.84E-06 1135+D 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06

0.

2.62E-06 XE131M

0.

XE133M

0.

XE133

0.

XE135M

0.

XE135

0.

XE137

0.

XE138+D

0.

CS134M+D 1.76E-07 2.93E-07 1.48E-07

0.

1.13E-07 2.60E-08 2.32E-07 CS134 3.77E-04 7.03E-04 7.10E-05

0.

1.81E-04 7.42E-05 1.91E-06 CS135 1.33E-04 1.21E-04 6.30E-06

0.

3.44E-05 1.31E-05 4.37E-07 CS136 4.59E-05 1.35E-04 5.04E-05

0.

5.38E-05 1.10E-05 2.05E-06 CS137+D 5.22E-04 6.11E-04 4.33E-05

0.

1.64E-04 6.64E-05 1.91E-06 CS138 4.81 E-07 7.82E-07 3.79E-07

0.

3.90E-07 6.09E-08 1.25E-06 CS139+D 3.10E-07 4.24E-07 1.62E-07

0.

2.19E-07 3.30E-08 2.66E-08 BA139 8.81E-07 5.84E-10 2.55E-08

0.

3.51E-10 3.54E-10 5.58E-05 BA140+D 1.71 E-04 1.71 E-07 8.81E-06

0.

4.06E-08 1.05E-07 4.20E-05 BA141+D 4.25E-07 2.91E-10 1.34E-08

0.

1.75E-10 1.77E-10 5.19E-06 BA142+D 1.84E-07 1.53E-10 9.06E-09

0.

8.81E-11 9.26E-11 7.59E-07 LA140 2.11E-08 8.32E-09 2.14E-09

0.

9.77E-05 LA141 2.89E-09 8.38E-10 1.46E-10

0.

9.61E-05 LA142 1.10E-09 4.04E-10 9.67E-11

0.

6.86E-05 CE141 7.87E-08 4.80E-08 5.65E-09

0.

1.48E-08

0.

2.48E-05 CE143+D 1.48E-08 9.82E-06 1.12E-09

0.

2.86E-09

0.

5.73E-05 CE144+D 2.98E-06 1.22E-06 1.67E-07

0.

4.93E-07

0.

1.71E-04 PR143 8.18E-08 3.04E-08 4.03E-09

0.

1.13E-08

0.

4.29E-05 PR144 2.74E-10 1.06E-10 1.38E-11

0.

3.84E-11

0.

4.93E-06 ND147+D 5.53E-08 5.68E-08 3.48E-09

0.

2.19E-08

0.

3.60E-05 PM147 3.88E-07 3.27E-08 1.59E-08

0.

4.88E-08

0.

9.27E-06 PM148M+D 1.65E-07 4.18E-08 3.28E-08

0.

4.80E-08

0.

5.443-05 PM148 6.32E-08 9.13E-09 4.60E-09

0.

1.09E-08

0.

9.74E-05 PM149 1.38E-08 1.81E-09 7.90E-10

0.

2.20E-09

0.

4.86E-05 PM151 6.18E-09 9.01E-10 4.56E-10

0.

1.07E-09

0.

4.17E-05 SM151 2.90E-07 6.67E-08 1.44E-08

0.

4.53E-08

0.

5.58E-06 SM153 7.72E-09 5.97E-09 4.58E-10

0.

1.25E-09

0.

3.12E-05 EU152 6.74E-07 1.79E-07 1.51E-07

0.

5.02E-07

0.

1.59E-05 EU154 2.64E-06 3.67E-07 2.20E-07

0.

9.95E-07

0.

4.58E-05 EU155 5.42E-07 6.25E-08 3.23E-08

0.

1.40E-07

0.

8.37E-05 EU156 1.14E-07 7.06E-08 1.12E-08

0.

3.26E-08

0.

6.67E-05 TB160 2.59E-07

0.

3.24E-08

0.

7.37E-08

0.

3.45E-05 H0166M 1.25E-06 2.69E-07 2.13E-07

0.

3.57E-07

0.

W181 8.85E-08 2.72E-08 3.04E-09

0.

3.82E-07 W185 3.62E-06 1.13E-06 1.29E-07

0.

1.62E-05 W187 9.03E-07 6.28E-07 2.17E-07

0.

3.69E-05 84

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+D 5.28E-02 1.42E-02 2.38E-03

0.

4.33E-02

0.

5.62E-05 Bl210+D 4.16E-06 2.68E-05 3.58E-07

0.

2.08E-04

0.

5.27E-05 P0210 3.10E-03 5.93E-03 7.41E-04

0.

1.26E-02

0.

6.61E-05 RN222+D

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 2.91E-03

0.

6.OOE-04

0.

3.86E-04 RA225+D 5.78E-02 6.42E-05 1.15E-02

0.

1.19E-03

0.

3.24E-04 RA226+D 6.20E-01 4.76E-05 5.14E-01

0.

8.71 E-04

0.

3.44E-04 RA228+D 4.32E-01 2.58E-05 4.86E-01

0.

4.73E-04

0.

5.86E-05 AC225 3.92E-05 5.03E-05 2.63E-06

0.

3.69E-06

0.

4.36E-04 AC227+D 4.49E-03 7.67E-04 2.79E-04

0.

1.56E-04

0.

8.50E-05 TH227+D 1.20E-04 2.01E-06 3.45E-06

0.

7.41E-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 1.94E-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.

5.31E-05 TH234 6.92E-07 3.77E-08 2.OOE-08

0.

1.39E-07

0.

1.19E-04 PA231+D 7.57E-03 2.50E-04 3.02E-04

0.

1.34E-03

0.

7.44E-05 PA233 3.11E-08 6.09E-09 5.43E-09

0.

1.67E-08

0.

1.46E-05 U232+D 2.42E-02

0.

2.16E-03

0.

2.37E-03

0.

7.04E-05 U233+D 5.08E-03

0.

3.87E-04

0.

1.08E-03

0.

6.51E-05 U234 4.88E-03

0.

3.80E-04

0.

1.06E-03

0.

6.37E-05 U235+D 4.67E-03

0.

3.56E-04

0.

9.93E-04

0.

8.10E-05 U236 4.67E-03

0.

3.64E-04

0.

1.01E-03

0.

5.98E-05 U237 4.95E-07

0.

1.32E-07

0.

1.23E-06

0.

2.11E-05 U238+D 4.47E-03

0.

3.33E-04

0.

9.28E-04

0.

5.71 E-05 NP237+D 2.53E-03 1.93E-04 1.05E-04

0.

6.34E-04

0.

8.23E-05 NP238 1.24E-07 3.12E-09 1.92E-09

0.

6.81E-09

0.

4.17E-05 NP239 1.11E-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.

1.21E-04

0.

7.57E-05 PU239 1.45E-03 1.77E-04 3.54E-05

0.

1.28E-04

0.

6.91E-05 PU240 1.45E-03 1.77E-04 3.54E-05

0.

1.28E-04

0.

7.04E-05 PU241+D 4.38E-05 1.90E-06 8.82E-07

0.

3.17E-06

0.

1.45E-06 PU242 1.35E-03 1.70E-04 3.41E-05

0.

1.23E-04

0.

6.77E-05 PU244 1.57E-03 1.95E-04 3.91E-05

0.

1.41E-04

0.

1.01E-04 AM241 1.53E-03 7.18E-04 1.09E-04

0.

6.55E-04

0.

7.70E-05 AM242M 1.58E-03 7.02E-04 1.13E-04

0.

6.64E-04

0.

9.69E-05 AM243 1.51E-03 6.88E-04 1.06E-04

0.

6.36E-04

0.

9.03E-05 CM242 1.37E-04 1.24E-04 9.10E-06

0.

2.62E-05

0.

8.23E-05 CM243 1.45E-03 6.88E-04 8.98E-05

0.

3.27E-04

0.

8.10E-05 CM244 1.22E-03 6.16E-04 7.59E-05

0.

2.71E-04

0.

7.84E-05 CM245 1.88E-03 7.49E-04 1.13E-04

0.

4.32E-04

0.

7.30E-05 CM246 1.87E-03 7.49E-04 1.13E-04

0.

4.31E-04

0.

7.17E-05 CM247+D 1.82E-03 7.36E-04 1.11E-04

0.

4.24E-04

0.

9.43E-05 CM248 1.51 E-02 6.07E-03 9.16E-04

0.

3.50E-03

0.

1.52E-03 CF252 1.24E-03

0.

2.95E-05 0

0.

2.99E-04 85

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3

0.

2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 BE10 1.35E-05 1.57E-06 3.39E-07

0.

1.11E-06

0.

2.75E-05 C14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 N13 3.1OE-08 3.10E-08 3.1OE-08 3.1OE-08 3.10E-08 3.1OE-08 3.1OE-08 F18 2.49E-06

0.

2.47E-07

0.

6.74E-07 NA22 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 NA24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P32 8.25E-04 3.86E-05 3.18E-05

0.

2.28E-05 AR39

0.

AR41

0.

CA41 3.47E-04

0.

3.79E-05

0.

1.90E-07 SC46 1.97E-08 2.70E-08 1.04E-08

0.

2.30E-08

0.

3.95E-05 CR51

0.

8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN54

0.

1.07E-05 2.85E-06

0.

3.OOE-06

0.

8.98E-06 MN56

0.

3.34E-07 7.54E-08

0.

4.04E-07

0.

4.84E-05 FE55 1.15E-05 6.10E-06 1.89E-06

0.

3.45E-06 1.13E-06 FE59 1.65E-05 2.67E-05 1.33E-05

0.

7.74E-06 2.78E-05 C057

0.

4.93E-07 9.98E-07

0.

4.04E-06 C058

0.

1.80E-06 5.51 E-06

0.

1.05E-05 C060

0.

5.29E-06 1.56E-05

0.

2.93E-05 N159 4.02E-05 1.07E-05 6.82E-06

0.

7.10E-07 N163 5.38E-04 2.88E-05 1.83E-05

0.

1.94E-06 N165 2.22E-06 2.09E-07 1.22E-07

0.

2.56E-05 CU64

0.

2.45E-07 1.48E-07

0.

5.92E-07

0.

1.15E-05 ZN65 1.37E-05 3.65E-05 2.27E-05

0.

2.30E-05

0.

6.41 E-06 ZN69M+D 7.10E-07 1.21E-06 1.43E-07

0.

7.03E-07

0.

3.94E-05 ZN69 4.38E-08 6.33E-08 5.85E-09

0.

3.84E-08

0.

3.99E-06 SE79

0.

8.43E-06 1.87E-06

0.

1.37E-05

0.

5.53E-07 BR82

0.

7.55E-06

0.

BR83+D

0.

1.71 E-07

0.

BR84

0.

1.98E-07

0.

BR85 0

0.

9.12E-09

0.

KR83M

0.

KR85M

0.

KR85

0.

KR87

0.

KR88+D

0.

KR89

0.

RB86

0.

6.70E-05 4.12E-05

0.

4.31E-06 RB87

0.

3.95E-05 1.83E-05

0.

5.92E-07 RB88

0.

1.90E-07 1.32E-07

0.

9.32E-09 RB89+D

0.

1.17E-07 1.04E-07

0.

1.02E-09 SR89+D 1.32E-03

0.

3.77E-05

0.

5.11E-05 SR90+D 1.70E-02

0.

4.31 E-03

0.

2.29E-04 SR91+D 2.40E-05

0.

9.06E-07

0.

5.30E-05 SR92+D 9.03E-06

0.

3.62E-07

0.

1.71 E-04 86

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY Y90 4.11E-08

0.

1.10E-09

0.

Y91M+D 3.82E-10

0.

1.39E-11

0.

Y91 6.02E-07

0.

1.61E-08

0.

Y92 3.60E-09

0.

1.03E-10

0.

Y93 1.14E-08

0.

3.13E-10

0.

ZR93+D 1.67E-07 6.25E-08 4.45E-08

0.

2.42E-07 ZR95+D 1.16E-07 2.55E-08 2.27E-08

0.

3.65E-08 ZR97+D 6.99E-09 1.01E-09 5.96E-10

0.

1.45E-09 NB93M 1.05E-07 2.62E-08 8.61 E-09

0.

2.83E-08 NB95 2.25E-08 8.76E-09 6.26E-09

0.

8.23E-09 NB97 2.17E-10 3.92E-11 1.83E-11

0.

4.35E-11 M093

0.

2.41 E-05 8.65E-07

0.

6.35E-06 M099+D

0.

1.33E-05 3.29E-06

0.

2.84E-05 TC99M 9.23E-10 1.81E-09 3.00E-08

0.

2.63E-08 TC99 5.35E-07 5.96E-07 2.14E-07

0.

7.02E-06 TC101 1.07E-09 1.12E-09 1.42E-08

0.

1.91E-08 RU103+D 7.31E-07

0.

2.81E-07

0.

1.84E-06 RU105+D 6.45E-08

0.

2.34E-08

0.

5.67E-07 RU106+D 1.17E-05

0.

1.46E-06

0.

1.58E-05 RH105 5.14E-07 2.76E-07 2.36E-07

0.

1.10E-06 PD107

0.

4.72E-07 4.01E-08

0.

3.95E-06 PD109

0.

5.67E-07 1.70E-07

0.

3.04E-06 AG11OM+D 5.39E-07 3.64E-07 2.91 E-07

0.

6.78E-07 AGI11 2.48E-07 7.76E-08 5.12E-08

0.

2.34E-07 CD113M

0.

1.02E-05 4.34E-07

0.

1.05E-05 CD115M

0.

5.89E-06 2.51 E-07

0.

4.38E-06 SN123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 0.

SN125+D 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0.

SN126+D 3.33E-04 4.15E-06 9.46E-06 1.14E-06 0.

SB124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0.

SB125+D 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.

SB126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 0.

SB127 1.06E-06 1.64E-08 3.68E-07 1.18E-08 0.

TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.

TE127M+D 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 TE127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 TE129M+D 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 TE131M+D 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 TE131+D 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 TE132+D 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 TE133M+D 1.87E-07 7.56E-08 9.37E-08 1.45E-07 7.18E-07 TE134+D 1.29E-07 5.80E-08 7.74E-08 1.02E-07 5.37E-07 1129 1.39E-05 8.53E-06 7.62E-06 5.58E-03 1.44E-05 1130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 1131+D 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 INGESTED IN FIRST YR)

LUNG GI-LLI

0.

1.17E-04

0.

7.48E-07

0.

8.02E-05

0.

1.04E-04

0.

1.70E-04

0.

2.37E-05

0.

2.66E-05

0.

1.53E-04

0.

3.95E-06

0.

1.62E-05

0.

1.21 E-05

0.

1.22E-06

0.

1.10E-05 9.19E-10 1.03E-06 5.27E-08 6.25E-06 5.92E-10 3.56E-09

0.

1.89E-05

0.

4.21 E-05

0.

1.82E-04

0.

1.71 E-05

0.

9.37E-07

0.

3.35E-05

0.

4.33E-05

0.

4.75E-05

0.

2.63E-05

0.

8.01 E-05

0.

6.52E-05

0.

1.10E-04

0.

2.50E-05 6.16E-06 6.94E-05 3.99E-06 1.71 E-05 2.10E-06 8.87E-05 4.60E-07 5.97E-05

0.

1.10E-05

0.

2.34E-05

0.

1.84E-05

0.

5.94E-05

0.

8.34E-06

0.

1.01 E-04

0.

4.36E-07

0.

4.50E-05

0.

5.77E-06

0.

5.89E-07

0.

4.29E-07

0.

2.76E-06

0.

1.54E-06 87

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY 1132 8.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 1133+D 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 1134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 1135+D 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 XE131M

0.

XE133M

0.

XE133

0.

XE135M

0.

XE135

0.

XE137

0.

XE138+D

0.

CS134M+D 8.44E-08 1.25E-07 8.16E-08

0.

6.59E-08 CS134 2.34E-04 3.84E-04 8.10E-05

0.

1.19E-04 CS135 8.30E-05 5.78E-05 5.93E-06

0.

2.04E-05 CS136 2.35E-05 6.46E-05 4.18E-05

0.

3.44E-05 CS137+D 3.27E-04 3.13E-04 4.62E-05

0.

1.02E-04 CS138 2.28E-07 3.17E-07 2.01E-07

0.

2.23E-07 CS139+D 1.45E-07 1.61 E-07 7.74E-08

0.

1.21 E-07 BA139 4.14E-07 2.21E-10 1.20E-08

0.

1.93E-10 BA140+D 8.31 E-05 7.28E-08 4.85E-06

0.

2.37E-08 BA141+D 2.00E-07 1.12E-10 6.51E-09

0.

9.69E-11 BA142+D 8.74E-08 6.29E-11 4.88E-09

0.

5.09E-11 LA140 1.01E-08 3.53E-09 1.19E-09

0.

LA141 1.35E-09 3.17E-10 6.88E-11

0.

LA142 5.24E-10 1.67E-10 5.23E-11

0.

CE141 3.97E-08 1.98E-08 2.94E-09

0.

8.68E-09 CE143+D 6.99E-09 3.79E-06 5.49E-10

0.

1.59E-09 CE144+D 2.08E-06 6.52E-07 1.1IE-07

0.

3.61E-07 PR143 3.93E-08 1.18E-08 1.95E-09

0.

6.39E-09 PR144 1.29E-10 3.99E-11 6.49E-12

0.

2.11E-11 ND147+D 2.79E-08 2.26E-08 1.75E-09

0.

1.24E-08 PM147 3.18E-07 2.27E-08 1.22E-08

0.

4.01E-08 PM148M+D 1.03E-07 2.05E-08 2.05E-08

0.

3.04E-08 PM148 3.02E-08 3.63E-09 2.35E-09

0.

6.17E-09 PM149 6.49E-09 6.90E-10 3.74E-10

0.

1.22E-09 PM151 2.92E-09 3.55E-10 2.31 E-10

0.

6.02E-10 SM151 2.56E-07 3.81E-08 1.20E-08

0.

3.94E-08 SM153 3.65E-09 2.27E-09 2.19E-10

0.

6.91E-10 EU152 6.15E-07 1.12E-07 1.33E-07

0.

4.73E-07 EU154 2.30E-06 2.07E-07 1.89E-07

0.

9.09E-07 EU155 4.82E-07 3.47E-08 2.72E-08

0.

1.30E-07 EU156 5.62E-08 3.01E-08 6.23E-09

0.

1.94E-08 TB160 1.66E-07

0.

2.06E-08

0.

4.94E-08 H0166M 1.08E-06 2.26E-07 1.91E-07

0.

3.22E-07 W181 4.23E-06 1.04E-08 1.43E-09

0.

W185 1.73E-06 4.32E-07 6.05E-08

0.

W187 4.29E-07 2.54E-07 1.14E-07

0.

INGESTED IN FIRST YR)

LUNG GI-LLI

0.

1.73E-06

0.

2.95E-06

0.

5.16E-07

0.

2.40E-06

0.

1.09E-08 1.58E-07 4.27E-05 2.07E-06 6.81 E-06 4.33E-07 5.13E-06 2.27E-06 3.67E-05 1.96E-06 2.40E-08 1.46E-07 1.22E-08 1.45E-11 1.30E-10 2.39E-05 4.34E-08 4.21 E-05 6.58E-10 1.14E-07 3.70E-11 1.14E-09

0.

9.84E-05

0.

7.05E-05

0.

3.31 E-05

0.

2.47E-05

0.

5.55E-05

0.

1.70E-04

0.

4.24E-05

0.

8.59E-08

0.

3.58E-05

0.

9.19E-06

0.

5.78E-05

0.

9.70E-05

0.

4.71 E-05

0.

4.03E-05

0.

5.53E-06

0.

3.02E-05

0.

1.84E-05

0.

4.81 E-05

0.

8.69E-05

0.

6.83E-05

0.

3.68E-05

0.

3.79E-07

0.

1.61 E-05

0.

3.57E-05 88

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY PB210+D 4.75E-02 1.22E-02 2.09E-03

0.

3.67E-02 B1210+D 1.97E-06 1.02E-05 1.69E-07

0.

1.15E-04 P0210 1.52E-03 2.43E-03 3.67E-04

0.

7.56E-03 RN222+D

0.

RA223+D 2.12E-02 2.45E-05 4.24E-03

0.

6.50E-04 RA224+D 6.89E-03 1.25E-05 1.38E-03

0.

3.31E-04 RA225+D 2.80E-02 2.50E-05 5.59E-03

0.

6.62E-04 RA226+D 5.75E-01 1.84E-05 4.72E-01

0.

4.88E-04 RA228+D 3.85E-01 9.99E-06 4.32E-01

0.

2.65E-04 AC225 1.88E-05 1.94E-05 1.26E-06

0.

2.07E-06 AC227+D 4.12E-03 6.63E-04 2.55E-04

0.

1.46E-04 TH227+D 5.85E-05 7.96E-07 1.69E-06

0.

4.22E-06 TH228+D 2.07E-03 2.65E-05 7.OOE-05

0.

1.38E-04 TH229 1.38E-02 1.81E-04 6.80E-04

0.

8.84E-04 TH230 3.55E-03 1.78E-04 9.91E-05

0.

8.67E-04 TH232+D 3.96E-03 1.52E-04 3.01E-04

0.

7.41E-04 TH234 3.42E-07 1.51E-08 9.88E-09

0.

8.01E-08 PA231+D 7.07E-03 2.34E-04 2.81E-04

0.

1.28E-03 PA233 1.81E-08 2.82E-09 3.16E-09

0.

1.04E-08 U232+D 1.76E-02

0.

1.26E-03

0.

1.34E-03 U233+D 3.72E-03

0.

2.25E-04

0.

6.1OE-04 U234 3.57E-03

0.

2.21 E-04

0.

5.98E-04 U235+D 3.42E-03

0.

2.07E-04

0.

5.61E-04 U236 3.42E-03

0.

2.12E-04

0.

5.73E-04 U237 2.36E-07

0.

6.27E-08

0.

6.81 E-07 U238+D 3.27E-03

0.

1.94E-04

0.

5.24E-04 NP237+D 2.36E-03 1.81E-04 9.79E-05

0.

6.05E-04 NP238 5.83E-08 1.18E-09 9.08E-10

0.

3.76E-09 NP239 5.25E-09 3.77E-10 2.65E-10

0.

1.09E-09 PU238 1.25E-03 1.56E-04 3.16E-05

0.

1.15E-04 PU239 1.36E-03 1.65E-04 3.31E-05

0.

1.22E-04 PU240 1.36E-03 1.65E-04 3.31E-05

0.

1.22E-04 PU241+D 4.00E-05 1.72E-06 8.04E-07

0.

2.96E-06 PU242 1.26E-03 1.59E-04 3.19E-05

0.

1.17E-04 PU244 1.47E-03 1.82E-04 3.65E-05

0.

1.35E-04 AM241 1.43E-03 6.40E-04 1.02E-04

0.

6.23E-04 AM242M 1.47E-03 6.25E-04 1.04E-04

0.

6.30E-04 AM243 1.41E-03 6.14E-04 9.83E-05

0.

6.06E-04 CM242 8.80E-05 6.73E-05 5.84E-06

0.

1.87E-05 CM243 1.33E-03 6.03E-04 8.24E-05

0.

3.08E-04 CM244 1.11E-03 5.36E-04 6.93E-05

0.

2.54E-04 CM245 1.76E-03 6.64E-04 1.05E-04

0.

4.11E-04 CM246 1.74E-03 6.64E-04 1.05E-04

0.

4.10E-04 CM247+D 1.70E-03 6.53E-04 1.03E-04

0.

4.04E-04 CM248 1.41E-02 5.38E-03 8.52E-04

0.

3.33E-03 CF252 1.07E-03

0.

2.54E-05

0.

INGESTED LUNG 0.

0.

IN FIRST YR)

GI-LLI 5.57E-05 5.17E-05 6.55E-05 0.

3.38E-04 3.78E-04 3.21 E-04 3.41 E-04 5.81E-05 4.31 E-04 8.43E-05 5.63E-04 5.79E-04 5.27E-04 6.19E-05 5.27E-05 1.18E-04 7.37E-05 1.44E-05 6.98E-05 6.45E-05 6.32E-05 8.03E-05 5.92E-05 2.08E-05 5.66E-05 8.16E-05 4.04E-05 2.79E-05 7.50E-05 6.85E-05 6.98E-05 1.44E-06 6.71 E-05 1.OOE-04 7.64E-05 9.61 E-05 8.95E-05 8.16E-05 8.03E-05 7.77E-05 7.24E-05 7.11E-05 9.35E-05 1.51 E-03 2.96E-04 89

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREMI50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3

0.

1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 BE10 4.48E-06 6.94E-07 1.13E-07

0.

5.30E-07

0.

2.84E-05 C14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 N13 1.15E-08 1.15E-08 1.15E-08 1.15E-08 1.15E-08 1.15E-08 1.15E-08 F18 8.64E-07

0.

9.47E-08

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.

2.32E-05 AR39

0.

AR41

0.

CA41 1.97E-04

0.

2.13E-05

0.

1.95E-07 SC46 7.24E-09 1.41E-08 4.18E-09

0.

1.35E-08

0.

4.80E-05 CR51

0.

3.60E-09 2.OOE-09 7.89E-10 5.14E-09 6.05E-07 MN54

0.

5.90E-06 1.17E-06

0.

1.76E-06

0.

1.21E-05 MN56

0.

1.58E-07 2.81 E-08

0.

2.OOE-07

0.

1.04E-05 FE55 3.78E-06 2.68E-06 6.25E-07

0.

1.70E-06 1.16E-06 FE59 5.87E-06 1.37E-05 5.29E-06

0.

4.32E-06 3.24E-05 C057

0.

2.38E-07 3.99E-07

0.

4.44E-06 C058

0.

9.72E-07 2.24E-06

0.

1.34E-05 C060 0

2.81 E-06 6.33E-06

0.

3.66E-05 N159 1.32E-05 4.66E-06 2.24E-06

0.

7.31 E-07 N163 1.77E-04 1.25E-05 6.00E-06

0.

1.99E-06 N165 7.49E-07 9.57E-08 4.36E-08

0.

5.193-06 CU64

0.

1.15E-07 5.41E-08

0.

2.91E-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.

3.11E-05 ZN69 1.47E-08 2.80E-08 1.96E-09

0.

1.83E-08

0.

5.16E-08 SE79

0.

3.73E-06 6.27E-07

0.

6.50E-06

0.

5.70E-07 BR82

0.

3.04E-06

0.

BR83+D

0.

5.74E-08

0.

BR84

0.

7.22E-08

0.

BR85

0.

3.05E-09

0.

KR83M

0.

KR85M

0.

KR85

0.

KR87

0.

KR88+D

0.

KR89

0.

RB86

0.

2.98E-05 1.40E-05

0.

4.41E-06 RB87

0.

1.75E-05 6.11 E-06

0.

6.11 E-07 RB88

0.

8.52E-08 4.54E-08

0.

7.30E-15 RB89+D

0.

5.50E-08 3.89E-08

0.

8.43E-17 SR89+D 4.40E-04

0.

1.26E-05

0.

5.24E-05 SR90+D 8.30E-03

0.

2.05E-03

0.

2.33E-04 SR91+D 8.07E-06

0.

3.21E-07

0.

3.66E-05 SR92+D 3.05E-06

0.

1.30E-07

0.

7.77E-05 90

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 1.37E-08

0.

3.69E-10

0.

1.13E-04 Y91M+D 1.29E-10

0.

4.93E-12

0.

6.09E-09 Y91 2.01 E-07

0.

5.39E-09

0.

8.24E-05 Y92 1.21 E-09

0.

3.50E-11

0.

3.32E-05 Y93 3.83E-09

0.

1.05E-10

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 NB93M 3.44E-08 1.13E-08 2.83E-09

0.

1.32E-08

0.

4.07E-06 NB95 8.22E-09 4.56E-09 2.51 E-09

0.

4.42E-09

0.

1.95E-05 NB97 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

0.

6.03E-06 1.15E-06

0.

1.38E-05

0.

1.08E-05 TC99M 3.32E-10 9.26E-10 1.20E-08

0.

1.38E-08 5.14E-10 6.08E-07 TC99 1.79E-07 2.63E-07 7.17E-08

0.

3.34E-06 2.72E-08 6.44E-06 TC101 3.60E-10 5.12E-10 5.03E-09

0.

9.26E-09 3.12E-10 8.75E-17 RU103+D 2.55E-07

0.

1.09E-07

0.

8.99E-07

0.

2.13E-05 RU105+D 2.18E-08

0.

8.46E-09

0.

2.75E-07

0.

1.76E-05 RU106+D 3.92E-06

0.

4.94E-07

0.

7.56E-06

0.

1.88E-04 RH105 1.73E-07 1.25E-07 8.20E-08

0.

5.31E-07

0.

1.59E-05 PD107

0.

2.08E-07 1.34E-08

0.

1.88E-06

0.

9.66E-07 PD109

0.

2.51 E-07 5.70E-08

0.

1.45E-06

0.

2.53E-05 AG110M+D 2.05E-07 1.94E-07 1.18E-07

0.

3.70E-07

0.

5.45E-05 AG111 8.29E-08 3.44E-08 1.73E-08

0.

1.12E-07

0.

4.80E-05 CD113M

0.

4.51 E-06 1.45E-07

0.

4.99E-06

0.

2.71 E-05 CD1 5M

0.

2.60E-06 8.39E-08

0.

2.08E-06

0.

8.23E-05 SN123 4.44E-05 7.29E-07 1.08E-06 5.84E-07

0.

6.71E-05 SN125+D 1.19E-05 2.37E-07 5.37E-07 1.86E-07

0.

1.12E-04 SN126+D 1.16E-04 2.16E-06 3.30E-06 5.69E-07

0.

2.58E-05 SB124 3.87E-06 7.13E-08 1.51E-06 8.78E-09

0.

3.38E-06 7.80E-05 SB125+D 2.48E-06 2.71E-08 5.80E-07 2.37E-09

0.

2.18E-06 1.93E-05 SB126 1.59E-06 3.25E-08 5.71E-07 8.99E-09

0.

1.14E-06 9.41E-05 SB127 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.

1.13E-05 TE127M+D 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05

0.

2.41E-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 2.21E-06 2.08E-06 2.33E-06 2.12E-05

0.

7.OOE-05 TE133M+D 6.44E-08 3.66E-08 3.56E-08 5.11E-08 3.62E-07

0.

1.48E-07 TE134+D 4.47E-08 2.87E-08 3.OOE-08 3.67E-08 2.74E-07

0.

1.66E-09 1129 4.66E-06 3.92E-06 6.54E-06 4.77E-03 7.01 E-06

0.

4.57E-07 1130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06

0.

2.29E-06 1131+D 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05

0.

1.62E-06 91

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1133+D 1134 11 35+D XE131M XE133M XE133 XE135M XE135 XE137 XE138+D CS134M+D CS134 CS135 CS136 CS1 37+0 CS138 CS139+D BA139 BA140+D BA141 +D BA142+D LA140 LA141 LA142 CE141 CE143+D CEI44+0 PR143 PR144 ND147+D PM147 PM148M+D PM148 PM149 PM151 SM151 SM1 53 EU152 EU154 EU155 EU156 TB160 H0166M W181 Wi 85 WI 87 2.79E-07 2.01 E-06 1.46E-07 6.1 OE-07 0.

0.

2.94E-08 8.37E-05 2.78E-05 8.59E-06 1.12E-04 7.76E-08 4.87E-08 1.39E-07 2.84E-05 6.71 E-08 2.99E-08 3.48E-09 4.55E-1 0 1.79E-1 0 1.33E-08 2.35E-09 6.96E-07 1.31 E-08 4.30E-1 1 9.38E-09 1.05E-07 4.14E-08 1.02E-08 2.1 7E-09 9.87E-1 0 8.73E-08 1.22E-09 2.45E-07 7.91 E-07 1.74E-07 1.92E-08 6.47E-08 3.57E-07 1.42E-08 5.79E-07 1.46E-07 7.30E-07 3.41 E-06 3.87E-07 1.57E-06 0.

0.

6.09E-08 1.97E-04 2.55E-05 3.38E-05 1.49E-04 1.49E-07 7.17E-08 9.78E-1 I 3.48E-08 5.01 E-1 1 2.99E-1 1 1.71 E-09 1.40E-10 7.95E-1 1 8.88E-09 1.71 E-06 2.88E-07 5.23E-09 1.76E-1 I 1.02E-08 9.96E-09 1.05E-08 1.66E-09 3.05E-1 0 1.63E-10 1.68E-08 1.01 E-09 5.90E-08 1.02E-07 1.68E-08 1.44E-08 0.

1.1OE-07 4.58E-09 1.91 E-07 1.19E-07 2.62E-07 1.04E-06 1.39E-07 5.82E-07 0.

0.

3.13E-08 9.14E-05 5.96E-06 2.27E-05 5.1 9E-05 7.45E-08 2.63E-08 4.05E-09 1.83E-06 2.24E-09 1.84E-09 4.55E-1 0 2.31 E-11 1.98E-1 1 1.02E-09 1.91 E-1 0 3.74E-08 6.52E-10 2.18E-12 6.11E-10 4.06E-09 8.21 E-09 8.36E-1 0 1.25E-10 8.25E-1 1 3.94E-09 7.43E-1 1 5.20E-08 7.19E-08 1.04E-08 2.35E-09 8.07E-09 7.96E-08 4.79E-1 0 2.02E-08 4.17E-08 2.46E-05 4.76E-04 6.45E-06 1.01 E-04 0.

0.

1.15E-06 5.98E-06 6.1 OE-07 2.48E-06 0.

0.

3.39E-08 6.26E-05 9.73E-06 1.84E-05 5.07E-05 1.1OE-07 5.79E-08 9.22E-1 1 1.18E-08 4.65E-1 1 2.53E-1 1 0.

0.

4.18E-09 7.67E-1 0 1.72E-07 3.04E-09 1.01 E-11 5.99E-09 1.90E-08 1.59E-08 3.OOE-09 5.81 E-10 2.93E-1 0 1.84E-08 3.30E-10 2.74E-07 4.56E-07 6.57E-08 9.69E-09 2.56E-08 1.61 E-07 0.

0.

5.95E-09 2.39E-05 3.52E-06 2.90E-06 1.97E-05 1.28E-08 6.34E-09 6.74E-11 2.34E-08 3.43E-1 1 1.99E-11 0.

0.

3.18E-07 2.58E-06 5.1 OE-09 1.74E-06 0.

0.

4.05E-08 2.45E-06 4.46E-07 2.72E-06 2.12E-06 6.76E-1 I 3.33E-23 1.24E-06 4.38E-05 1.43E-13 9.18E-20 9.82E-05 2.48E-05 2.42E-06 2.54E-05 5.14E-05 1.75E-04 4.31 E-05 4.74E-14 3.68E-05 9.47E-06 6.61 E-05 9.90E-05 4.49E-05 3.66E-05 5.70E-06 2.85E-05 2.17E-05 5.39E-05 9.63E-05 7.36E-05 4.19E-05 0.

3.90E-07 1.65E-05 3.22E-05 92

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+D 1.81 E-02 5.44E-03 7.01 E-04

0.

1.72E-02

0.

5.74E-05 B1210+D 6.59E-07 4.51E-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.

RA223+1D 7.11E-03 1.08E-05 1.42E-03

0.

3.10E-04

0.

3.43E-04 RA224+D 2.31 E-03 5.52E-06 4.61 E-04

0.

1.58E-04

0.

3.71 E-04 RA225+1D 9.37E-03 1.10E-05 1.87E-03

0.

3.15E-04

0.

3.27E-04 RA226+D 3.22E-01 8.13E-06 2.39E-01

0.

2.32E-04

0.

3.51E-04 RA228+D 1.37E-01 4.41 E-06 1.51 E-01

0.

1.26E-04

0.

5.98E-05 AC225 6.29E-06 8.59E-06 4.22E-07

0.

9.85E-07

0.

4.36E-04 AC227+D 2.05E-03 3.03E-04 1.22E-04

0.

8.81 E-05

0.

8.68E-05 TH227+D 1.96E-05 3.52E-07 5.65E-07

0.

2.01 E-06

0.

5.75E-04 TH228+D 6.80E-04 1.14E-05 2.30E-05

0.

6.41 E-05

0.

5.97E-04 TH229 8.39E-03 1.26E-04 4.11E-04

0.

6.1OE-04

0.

5.43E-04 TH230 2.16E-03 1.23E-04 6.OOE-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 3.31E-09

0.

3.81E-08

0.

1.21E-04 PA231+D 4.31E-03 1.62E-04 1.68E-04

0.

9.1OE-04

0.

7.60E-05 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

0.

6.38E-04

0.

7.19E-05 U233+D 1.24E-03

0.

7.543-05

0.

2.90E-04

0.

6.65E-05 U234 1.19E-03

0.

7.39E-05

0.

2.85E-04

0.

6.51E-05 U235+D 1.14E-03

0.

6.94E-05

0.

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.

2.1OE-08

0.

3.24E-07

0.

2.09E-05 U238+D 1.09E-03

0.

6.49E-05

0.

2.50E-04

0.

5.83E-05 NP237+D 1.44E-03 1.25E-04 5.85E-05

0.

4.33E-04

0.

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

0.

5.21 E-10

0.

2.67E-05 PU238 7.21 E-04 1.02E-04 1.82E-05

0.

7.80E-05

0.

7.73E-05 PU239 8.27E-04 1.12E-04 2.01E-05

0.

8.57E-05

0.

7.06E-05 PU240 8.26E-04 1.12E-04 2.01E-05

0.

8.56E-05

0.

7.19E-05 PU2411+D 1.84E-05 9.42E-07 3.69E-07

0.

1.71 E-06

0.

1.48E-06 PU242 7.66E-04 1.08E-04 1.94E-05

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

0.

4.31 E-04

0.

7.87E-05 AM242M 8.70E-04 3.19E-04 5.80E-05

0.

4.30E-04

0.

9.90E-05 AM243 8.60E-04 3.17E-04 5.62E-05

0.

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

0.

1.49E-04

0.

8.OOE-05 CM245 1.07E-03 3.33E-04 6.10E-05

0.

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 CM247+D 1.03E-03 3.27E-04 6.OOE-05

0.

2.80E-04

0.

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.

3.05E-04 93

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3

0.

1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 BE10 3.18E-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.

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.

2.17E-05 AR39

0.

AR41

0.

CA41 1.83E-05

0.

2.OOE-05

0.

1.84E-07 SC46 5.51 E-09 1.07E-08 3.11 E-09

0.

9.99E-09

0.

5.21 E-05 CR51

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

0.

1.06E-06 1.09E-06 FE59 4.34E-06 1.02E-05 3.91 E-06

0.

2.85E-06 3.40E-05 C057

0.

1.75E-07 2.91 E-07

0.

4.44E-06 C058

0.

7.45E-07 1.67E-06

0.

1.51 E-05 C060

0.

2.14E-06 4.72E-06

0.

4.02E-05 N159 9.76E-06 3.35E-06 1.63E-06

0.

6.90E-07 N163 1.30E-04 9.01 E-06 4.36E-06

0.

1.88E-06 N165 5.28E-07 6.86E-08 3.13E-08

0.

1.74E-06 CU64

0.

8.33E-08 3.91 E-08

0.

2.10E-07

0.

7.10E-06 ZN65 4.84E-06 1.54E-05 6.96E-06

0.

1.03E-05

0.

9.70E-06 ZN69M+D 1.70E-07 4.08E-07 3.73E-08

0.

2.47E-07

0.

2.49E-05 ZN69 1.03E-08 1.97E-08 1.37E-09

0.

1.28E-08

0.

2.96E-09 SE79

0.

2.63E-06 4.39E-07

0.

4.55E-06

0.

5.38E-07 BR82

0.

2.26E-06

0.

2.59E-06 BR83+D

0.

4.02E-08

0.

5.79E-08 BR84

0.

5.21E-08

0.

4.09E-13 BR85

0.

2.14E-09

0.

KR83M

0.

KR85M

0.

KR85

0.

KR87

0.

KR88+D

0.

KR89

0.

RB86

0.

2.11E-05 9.83E-06

0.

4.16E-06 RB87

0.

1.23E-05 4.28E-06

0.

5.76E-07 RB88

0.

6.05E-08 3.21E-08

0.

8.36E-19 RB89+D

0.

4.01 E-08 2.82E-08

0.

2.33E-21 SR89+D 3.08E-04

0.

8.84E-06

0.

4.94E-05 SR90+D 7.58E-03

0.

1.86E-03

0.

2.19E-04 SR91+D 5.67E-06

0.

2.29E-07

0.

2.70E-05 SR92+D 2.15E-06

0.

9.30E-08

0.

4.26E-05 94

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 9.62E-09

0.

2.58E-10

0.

1.02E-04 Y91M+D 9.09E-11

0.

3.52E-12

0.

2.67E-10 Y91 1.41 E-07

0.

3.77E-09

0.

7.76E-05 Y92 8.45E-10

0.

2.47E-11

0.

1.48E-05 Y93 2.68E-09

0.

7.40E-11

0.

8.50E-05 ZR93+D 4.18E-08 2.34E-09 1.09E-09

0.

8.87E-09

0.

2.43E-06 ZR95+D 3.04E-08 9.75E-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.

1.05E-04 NB93M 2.55E-08 8.32E-09 2.05E-09

0.

9.57E-09

0.

3.84E-06 NB95 6.22E-09 3.46E-09 1.86E-09

0.

3.42E-09

0.

2.10E-05 NB97 5.22E-11 1.32E-11 4.82E-12

0.

1.54E-11

0.

4.87E-08 M093

0.

7.51E-06 2.03E-07

0.

2.13E-06

0.

1.22E-06 M099+D

0.

4.31E-06 8.20E-07

0.

9.76E-06

0.

9.99E-06 TC99M 2.47E-10 6.98E-10 8.89E-09

0.

1.06E-08 3.42E-10 4.13E-07 TC99 1.25E-07 1.86E-07 5.02E-08

0.

2.34E-06 1.58E-08 6.08E-06 TC101 2.54E-10 3.66E-10 3.59E-09

0.

6.59E-09 1.87E-10 1.10E-21 RU103+D 1.85E-07

0.

7.97E-08

0.

7.06E-07

0.

2.16E-05 RU105+D 1.54E-08

0.

6.08E-09

0.

1.99E-07

0.

9.42E-06 RU106+D 2.75E-06

0.

3.48E-07

0.

5.31E-06

0.

1.78E-04 RH105 1.21E-07 8.85E-08 5.83E-08

0.

3.76E-07

0.

1.41E-05 PD107

0.

1.47E-07 9.40E-09

0.

1.32E-06

0.

9.11E-07 PD109

0.

1.77E-07 3.99E-08

0.

1.01 E-06

0.

1.96E-05 AG110M+D 1.60E-07 1.48E-07 8.79E-08

0.

2.91E-07

0.

6.04E-05 AG111 5.81 E-08 2.43E-08 1.21 E-08

0.

7.84E-08

0.

4.46E-05 CD113M

0.

3.18E-06 1.02E-07

0.

3.50E-06

0.

2.56E-05 CD115M

0.

1.84E-06 5.87E-08

0.

1.46E-06

0.

7.74E-05 SN123 3.11E-05 5.15E-07 7.59E-07 4.38E-07

0.

6.33E-05 SN125+D 8.33E-06 1.68E-07 3.78E-07 1.39E-07

0.

1.04E-04 SN126+D 8.45E-05 1.67E-06 2.40E-06 4.92E-07

0.

2.43E-05 SB124 2.80E-06 5.29E-08 1.11E-06 6.79E-09

0.

2.18E-06 7.95E-05 SB125+D 1.79E-06 2.OOE-08 4.26E-07 1.82E-09

0.

1.38E-06 1.97E-05 SB126 1.15E-06 2.34E-08 4.15E-07 7.04E-09

0.

7.05E-07 9.40E-05 SB127 2.58E-07 5.65E-09 9.90E-08 3.10E-09

0.

1.53E-07 5.90E-05 TE125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05

0.

1.07E-05 TE125M+D 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05

0.

2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07

0.

8.68E-06 TE129M+D 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05

0.

5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07

0.

2.37E-08 TE131M+D 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06

0.

8.40E-05 TE131+D 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08

0.

2.79E-09 TE132+D 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05

0.

7.71E-05 TE133M+D 4.62E-08 2.70E-08 2.60E-08 3.91E-08 2.67E-07

0.

6.64E-08 TE134+D 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07

0.

3.59E-11 1129 3.27E-06 2.81 E-06 9.21 E-06 7.23E-03 6.04E-06

0.

4.44E-07 1130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06

0.

1.92E-06 1131+D 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05

0.

1.57E-06 95

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-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 4.31E-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 1.86E-06

0.

1.31E-06 XE131M

0.

XEI33M

0.

XE133

0.

XE135M

0.

XE135

0.

XE137

0.

XE138+D

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 1.80E-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.

8.01E-08 7.91E-09 4.65E-13 CS139+D 3.41E-08 5.08E-08 1.85E-08

0.

4.07E-08 3.70E-09 1.10E-30 BA139 9.70E-08 6.91 E-11 2.84E-09

0.

6.46E-11 3.92E-11 1.72E-07 BA140+D 2.03E-05 2.55E-08 1.33E-06

0.

8.67E-09 1.46E-08 4.18E-05 BA141+D 4.71E-08 3.56E-11 1.59E-09

0.

3.31E-11 2.02E-11 2.22E-17 BA142+D 2.13E-08 2.19E-11 1.34E-09

0.

1.85E-11 1.24E-11 3.00E-26 LA140 2.50E-09 1.26E-09 3.33E-10

0.

9.25E-05 LA141 3.19E-10 9.90E-11 1.62E-11

0.

1.18E-05 LA142 1.28E-10 5.82E-11 1.45E-11

0.

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

0.

5.37E-10

0.

4.56E-05 CE144+D 4.88E-07 2.04E-07 2.62E-08

0.

1.21 E-07

0.

1.65E-04 PR143 9.20E-09 3.69E-09 4.56E-10

0.

2.13E-09

0.

4.03E-05 PR144 3.01E-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 2.15E-10 8.78E-11

0.

4.06E-10

0.

4.03E-05 PM151 6.97E-10 1.17E-10 5.91E-11

0.

2.09E-10

0.

3.22E-05 SM151 6.90E-08 1.19E-08 2.85E-09

0.

1.33E-08

0.

5.25E-06 SM153 8.57E-10 7.15E-10 5.22E-11

0.

2.31E-10

0.

2.55E-05 EU152 1.95E-07 4.44E-08 3.90E-08

0.

2.75E-07

0.

2.56E-05 EU154 6.15E-07 7.56E-08 5.38E-08

0.

3.62E-07

0.

5.48E-05 EU155 8.60E-08 1.22E-08 7.87E-09

0.

5.63E-08

0.

9.60E-06 EU156 1.37E-08 1.06E-08 1.71E-09

0.

7.08E-09

0.

7.26E-05 TB160 4.70E-08

0.

5.86E-09

0.

1.94E-08

0.

4.33E-05 H0166M 2.70E-07 8.43E-08 6.40E-08

0.

1.26E-07

0.

W181 9.91E-09 3.23E-09 3.46E-10

0.

3.68E-07 W185 4.05E-07 1.35E-07 1.42E-08

0.

1.56E-05 W187 1.03E-07 8.61E-08 3.01E-08

0.

2.82E-05 96

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.1 ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+D 1.53E-02 4.37E-03 5.44E-04

0.

1.23E-02

0.

5.42E-05 Bl210+D 4.61E-07 3.18E-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.

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.

1.10E-04

0.

3.40E-04 RA225+D 6.56E-03 7.78E-06 1.31 E-03

0.

2.21 E-04

0.

3.06E-04 RA226+D 3.02E-01 5.74E-06 2.20E-01

0.

1.63E-04

0.

3.32E-04 RA228+D 1.12E-01 3.12E-06 1.21E-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 1.11E-04

0.

8.OOE-05

0.

8.19E-05 TH227+D 1.37E-05 2.48E-07 3.95E-07

0.

1.41E-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 3.91E-04

0.

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.OOE-04 1.50E-04

0.

4.82E-04

0.

5.12E-05 TH234 8.01E-08 4.71E-09 2.31E-09

0.

2.67E-08

0.

1.13E-04 PA231+D 4.10E-03 1.54E-04 1.59E-04

0.

8.64E-04

0.

7.17E-05 PA233 5.26E-09 1.06E-09 9.12E-10

0.

3.99E-09

0.

1.64E-05 U232+D 4.13E-03

0.

2.95E-04

0.

4.47E-04

0.

6.78E-05 U233+D 8.71 E-04

0.

5.28E-05

0.

2.03E-04

0.

6.27E-05 U234 8.36E-04

0.

5.17E-05

0.

1.99E-04

0.

6.14E-05 U235+D 8.01 E-04

0.

4.86E-05

0.

1.87E-04

0.

7.81 E-05 U236 8.01 E-04

0.

4.96E-05

0.

1.91 E-04

0.

5.76E-05 U237 5.52E-8

0.

1.47E-08

0.

2.27E-07

0.

1.94E-05 U238+D 7.67E-04

0.

4.54E-05

0.

1.75E-04

0.

5.50E-05 NP237+D 1.37E-03 1.19E-04 5.54E-05

0.

4.12E-04

0.

7.94E-05 NP238 1.37E-08 3.69E-10 2.13E-10

0.

1.25E-09

0.

3.43E-05 NP239 1.19E-09 1.17E-10 6.45E-11

0.

3.65E-10

0.

2.40E-05 PU238 6.80E-04 9.58E-05 1.71 E-05

0.

7.32E-05

0.

7.30E-05 PU239 7.87E-04 1.06E-04 1.91E-05

0.

8.11E-05

0.

6.66E-05 PU240 7.85E-04 1.06E-04 1.91E-05

0.

8.1OE-05

0.

6.78E-05 PU241+D 1.65E-05 8.44E-07 3.32E-07

0.

1.53E-06

0.

1.40E-06 PU242 7.29E-04 1.02E-04 1.84E-05

0.

7.81 E-05

0.

6.53E-05 PU244 8.52E-04 1.17E-04 2.11 E-05

0.

8.95E-05

0.

9.73E-05 AM241 8.19E-04 2.88E-04 5.41E-05

0.

4.07E-04

0.

7.42E-05 AM242M 8.24E-04 2.78E-04 5.43E-05

0.

4.05E-04

0.

9.34E-05 AM243 8.18E-04 2.78E-04 5.30E-05

0.

3.99E-04

0.

8.70E-05 CM242 2.06E-05 2.1 OE-05 1.37E-06

0.

6.22E-06

0.

7.92E-05 CM243 6.39E-04 2.41 E-04 3.75E-05

0.

1.75E-04

0.

7.81 E-05 CM244 4.83E-04 2.07E-04 2.87E-05

0.

1.34E-04

0.

7.55E-05 CM245 1.02E-03 2.87E-04 5.76E-05

0.

2.69E-04

0.

7.04E-05 CM246 1.01 E-03 2.87E-04 5.75E-05

0.

2.68E-04

0.

6.91 E-05 CM247+D 9.84E-04 2.83E-04 5.67E-05

0.

2.64E-04

0.

9.09E-05 CM248 8.18E-03 2.33E-03 4.67E-04

0.

2.18E-03

0.

1.47E-03 CF252 2.64E-04

0.

6.29E-06

0.

2.88E-04 97

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.2 PALISADES Liquid Effluent Desiqn Obiective Annual Quantity Nuclide H-3 Na-24 Sc-46 Cr-51 Mn-54 Half-Life 12.3 yr 15 h 83.9 d 27.8 d 303 d Dose Conversion Factors (mrem/Ci) 1.75E-06 5.44E-03 2.02E-02 1.56E-03 3.50E-02 Individual/Orqan AdulVtTB TeenlTB Teen/TB Adult/GI (LLI)

Teen/TB Design Objective Annual Quantity (Curies) 1.71 E+06 551.5 148.5 6,410.0 85.7 Fe-55 Mn-56 Co-57 Co-58 Fe-59 Co-60 Cu-64 Ni-65 Zn-65 Br-84.

Rb-86 Rb-88 Sr-89 Sr-90 Sr-91 Sr-92 Y-92 Nb-95 Zr-95 Nb-97 Zr-97 Mo-99 Tc-99m Ru-1 03 Ag-1 Om 2.6 yr 2.576 h 270 d 71.3 d 45.6 d 5.26 yr 12.8 h 2.56 h 245d 31.8 mo 1.02 mo 17.8 mo 52.7 d 27.7 yr 9.67 h 2.71 h 3.53 h 35 d 65.5 d 72 mo 17 h 66.7 h 6.05 h 39.5 d 255 d 4.48E-03 1.86E-03 4.39E-03 1.03E-02 4.08E-02 4.71 E-0I 1.32E-03 5.82E-04 1.83E-01 2.02E-03 3.06E-01 6.92E-04 1.56E-01 2.71 E-00 1.16E-03 1.51 E-03 2.69E-04 7.24E+00 6.17E-03 6.95E-04 9.28E-04 1.11E-03 1.42E-04 2.74E-03 7.75E-02 Child/Bone TeenlTB Teen/TB Teen/TB AdultUGI (LLI)

TeenlTB Teen/GI (LLI)

TeenlTB Teen/TB Teen/TB ChildlTB Teen/TB Child/Bone Adult/Bone Teen/TB Teen/TB Teen/TB Adult/GI (LLI)

Teen/TB Teen/TB Teen/TB Teen/Kidney Teen/TB Teen/TB Teen/TB 2,232.0 1,612.0 683.4 291.3 245.1 6.37 7,575.0 5,154.0 16.4 1,485.2 9.80 4,335.3 64.1 3.69 2,586.0 1,986.8 11,150.0 1.38 486.2 4,316.6 3,232.8 9,009.0 21,126.8 1,094.9 38.7 98

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 TABLE 2.2 (continued)

PALISADES Liquid Effluent Design Obiective Annual Quantity Design Objective Dose Conversion Annual Quantity Nuclide Half-Life Factors (mrem/Ci)

Individual/Organ (Curies)

Cd-113m 13.6 yr 6.02E-02 Adult/GI (LLI) 166.1 Sb-124 60 d 1.51 E-02 Teen/TB 198.7 Sb-125 2.7 yr 5.11E-02 TeenlTB 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-41 Child/Thyroid 30.6 Te-131m 30 h 2.27E-01 Adult/GI (LLI) 44.0 1-132 2.26 h 3.18E-05 TeenlTB 94,339.0 Te-132 77.7 h 2.93E-01 AdultVGI (LLI) 34.1 1-133 20.3 h 3.94E-02 Child/Thyroid 253.8 Cs-1 34 2 yr 2.86E+00 AdulVtTB 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-1 36 13.7 d 4.13E-01 Adult/TB 7.26 Cs-137 30 yr 1.71 E+00 Adult/TB 1.75 Cs-138 32.2. mo 2.31E-03 Teen/TB 1,298.0 Ba-1 39 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-1 52 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 99

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 Il1.

URANIUM FUEL CYCLE DOSE A.

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 III.C.1, III.D.1, or llI.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 II.C.2.1 and Il.C.2.2.

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.

100

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 18 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.

D40 = DG + DL + (RT)(T)

(2.15) where:

D40

=

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

=

Mean dose rate calculated to be applicable to Lake Michigan shoreline adjacent to Plant site (mrem/hr).

T

=

Assumed shoreline fishing time for the quarter in questions (hours).

101

Proc No 3.07 Palisades Nuclear Plant Attachment I 50.59 SCREEN Revision 13 Page 1 Of 5 LogNo.SDR-62-I13 Activity/Document No.

6 t L

A Revision No.l Title Offsite Dose Calculation Manual PART I -

Describe the Proposed Activity and Search the UFSAR (Admin Proc 3.07, Attachment 6. Section 1.3.1)

1.

Summarize the proposed activity.

(You may reference or attach appropriate descriptive materials).

Tables 1.4 and 1.4a are being revised as a result of the 2002 Land Use Environmental Survey.

These Tables are updated annually to reflect the current locations of all critical receptors within 5 miles of the Plant.

2.

Does the activity involve a change to the Technical Specifications?

O'Yes

3.

Describe the design function(s), performance requirements, and methods.of evaluation of the affected SSCs and indicate where the function(s) are described in the UFSAR.

Search the Updated Final Safety Analysis Report (UFSAR) and other relevant documents to identify the relevant sections.

(It is acceptable to attach and highlight appricable portions of the UFSAR.)

The operational environmental survey is an extension of the preoperational survey. The results of the operational environmental survey are submitted in annual reports to the NRC. UFSAR section 2.6 X

A land use census shall be vi-nducted and shall identify within a distance of 8km the-location in each of the 9 overland meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m2 producing broad leaf vegetation. ODCM Appendix A section iII J 3 (b&c).

Chnge;l the~c 'Ieticial Spicirkations require a Teclutijal Spet-imfraons Chang Request per

.1

Palisades Nuclear Plant 50.59 SCREEN PART II -

Determine If the Activity Involves a Design Funi (Admin Proc 3.07, Attachment 6, Section 1.3.2)

1.

Compare the proposed activity to the relevant portions ofl following questions:

Proc No 3.07 Attachment I Revision 13 Page 2 of 5 Wtlon the UFSAR and answer the YES NO QUESTION 0

Does the proposed activity involve Safety Analyses or an SSC(s) credited In the Safety Analyses?

o

/~

Does the proposed activity Involve SSCs that support SSC(s) credited in the Safety Analyses?

o Gao Does the proposed activity involve SSCs whose failure could Initiate a transient (e.g., scram, loss of feedwater, etc) or accident OR whose failure could impact SSC(s) credited in the Safety Analyses?

E l Does the proposed activity involve UFSAR-described SSCs or procedural controls that perform functions that are required by, or otherwise necessary to comply with, regulations, license conditions, orders or technical specifications?

o w-' Dces the proposed activity involve a method of evaluation described in the.

UFSAR?

o 3 Is the proposed activity a test orexperiment?

o 2

,- Does the proposed activity exceed or potentially affect a design basis limit for a fission product barrer (DBLFPB)?

If the answer to all of these questions is NO, skip PART IlIl and proceed directly to PART IV.

2.

If any of the above questions are marked YES, identify the specific design function, method of evaluation or DBLFPB involved.

Te results of the land use census shall be included in the Annual Radiological Environmental Report and shall be included in a revision of the ODCM for use in the following calendar year.

Proc No 3.07 Palisades Nuclear Plant Attachment I 50.59 SCREEN Revision 13 Page 3 of 5 PART IlIl -

Determine Whether the Activity Involves Adverse Effects (Admin Proc 3.07, Attachment 6, Section 1.3.3)

Answer the following questions to determine if the activity involves any adverse effects.

Any YES answer means that a 10 CFR 50.59 evaluation Is required except where noted in Question 3.

1.

Changes to the Facility or Procedures (if the activity does not Involve a change to the facility or procedures, these questions are 0 Not Applicable.)

YES NO QUESTION 0

E}/ Does the activity adversely affect the design function(s) that were identified in Part In-o u;--Does the activity adversely affect the method of performing or controlling the design function(s) that were Identified in Part II?

If either answer is YES, a 10 CFR 50.59 Evaluation is required. If both answers are NO, describe the basis for the conclusion (attach additional discussion, as necessary):

The proposed activity Is based on the Land Use Census environmental survey conducted

-this year. 'The results of this survey are to be included in the ODCM in Tab'es 1.4 and 1.4a.

This activity does not involve the design function of any SSC.

2.

Changes to a Method of Evaluation (If the activity does not involve a method of evaluation, these questions are 13Nlot Applicable.)

YES NO QUESTION o

o Does the activity use a revised or different method of evaluation for performing safety analyses than that described in the UFSAR?

o O

Does the activity use a revised or different method of evaluation for evaluating SSCs credited in safety analyses than that described in the UFSAR?

If either answer is YES, a 10 CFR 50 59 Evaluation is required. If both answers are NO, describe the basis for the conclusion (attach additional discussion, as necessary).

NOTE:

The UFSAR section (or reference) that describes the method should be identified in Part I, Item #3.

a;.1 or sit Be Proc No 3.07 Attachment I Re6VIslon 13 Page 4 of 5 Palisades Nuclear Plant 50.59 SCREEN

3.

Tests or Experiments (If tbactivity is not a test or experiment, then the questions in 3.a and 3.b are E&ot Applicable.)

a.

Answer these two questions first:

YES NO QUESTION O

0 Is the proposed test or experiment bounded by other tests'or experiments that are described in the UFSAR-o c

Are the SSCs affected by the proposed test or experiment isolated from the facility?

If the answer to both questions Is NO, continue to 3.b. If the answer to either question is YES, then briefly describe the basis.

I1

.4 11i

b.

Answer these additional questions only for tests or experiments which do not meet the criteria given above. If the answer to either question in 3.a is YES, then these three questions are 0 Not Applicable:

YES NO QUESTION O

0 Does the activity utilize or control an SSC in a manner that is outside the reference bounds of the design bases as described in*-

the UFSAR?

o 0

Does the activity utilize or control an SSC in a manner that Is inconsistent with the analyses or descriptions In the UFSAR?

[

0 Does the activity place the facility in a condition not previously evaluated orthat could affect the capability of an SSC to perform its intended functions?

If any answer in 3.b is YES, a'.10 CFR 50.59 Evaluation is required. If the answers are all NO, describe the basis for the conclusion (attach additional discussion, as necessary):

Palisades Nuc 50.59 SCl Part IV -

Conclusion (Admin Proc 3.07. Attachment 6, Section 1.3.4 Proc No 3.07

lear Plant Attachnnt 1 MEEN Re'vsIon 13 Pige of 5 4)

Check all that apply:

1.

A 10 CFR 50.59 Evaluation is a required or Eg-,1T required

2.

A UFSAR change is O 3 required or ET required.

Additional Comments Prepared By:

J,-

Date.

I I r /6 I Reviewed By:

C, aafi Date / A -i-C..

t an IRTSAR Chluuge Request has not alnuady been initiated, tden cnstur that an IJFSAR Clunge U

A.....:.:....

It:

_l..............

0 on

-1

........

ML040960097

Text

System Description

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