ML20141M553

Rev 8 to Vol 25 to Procedure Big Rock Point Radiological Effluent TS Required Documents,Offsite Dose Calculations & Process Control Program

ML20141M553
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	03/10/1992
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20141M549	List: ML20141M548 ML20141M552 ML20141M553
References
PROC-920310, NUDOCS 9209010150
Download: ML20141M553 (97)

Text

_ _ _ _. _ _..~ ~

BIC ROCK PolNT NUCLEAR POWER PLANT.

PROCEDURE APPROVAL AND AUTHORIZATION l

Procedure No.

VOLUME 25 Rev No.

8 Procedure Title BIC ROCK POINT RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS e

A.

OFFSITE DOSE CALCULATIONS B. PROCESS CONTR01. PROCRAM 4

CURRENT RFVISION STATUS Author R_LHurdette Date 02/06/92 Quality Review Form No. 232-92 APPLICABILITY ISSUE IIISTORY Revision No.

N/A Date N/A Quality Review Form No.

N/A Approved Ior use 9

Procedure Sponsor / Designate

M/

Date 3 0

'I V Authoriced Period of Use

[/N/A tbrough N/A t

r i

t When applicable:

PROCEDURE lMPLEMENTATION HISTORY

' Reviewed for System or -Component Operability Performed by Completed / Reviewed by Hethod of Verification Title Title a Functional Test a Physical Inspection Date Time Date Time u Administrative lleview 3.

MAINTENANCE ORDER NO. (if applicable) 9209010150 920828 PDR ADOCK 05000155 R

PDR OD0689-lD6A-BA01-BA05

~-

V ol.UM E 2 $

BIC ROCK POINT RADIOLOGICAL Revision A EFFLUENT T/S REQUIRED DOCUMENTS Page 1 of 2 A.

OFFSITE DOSE CALCULATIONS B.

PROCESS CONTROL PROGRAM TABLE OF CONTENTS / EFFECTIVE PACES REVISION FACES A.

OFFSITE DOSE CALCULATIONS 8

94 PURPOSE REQUIREMENTS I.

CASE 00S EFFLUENTS I.A ALARM / TRIP SET PolNT MET 110D 1.B DOSE CALCULATION 1.C DESIGN BASIS QUANTITY (DBQ) LIMITS I.D CASEOUS RADWASTE TREATMENT SYSTEM UPERAtION 1.E OFFSITE M; ' RELEASE RATE I.F PARTICULATE AND IODINE SAMPLING I.C NOBLE CAS SAMPtdFC I. 11 TRITILM SAMPLINC II.

LIQUID EFFLUENTS II,e ALLOWABLE CONCENTRATION II.B INSTRUMENT ALARM SET PolNTS II.C DOSE II.D UPERr.BILITY OF LIQUID RADWASTE EQUIPMENT II.E OFFSITE MPC RELEASE RATE 111 URANIUM FUEL CYCLE DOSE III.A SPECIFICATION Ill.B ASSUMPTIONS-III.C DOSE CALCULATION APPENDIX A DISCtfARGE CANAL DREDCING COMMITMENTS AND REPORTING REQUIREMENTS OD0689-1336A-BA01-BA05

- - -. =

l VOLUME 23 BlC ROCK P0lNT RADIOLOGICAL:

Revision 8-i EFFLUENT T/S REQUIRED DOCUMENTS Page 2 of 2 A.

OFFSITZ DOSE CALCULATIONS B.

PROCESS-CONTROL PROGRAM i

Revision Pages B.

PROCESS CONTROL PROCRAM 0

5-1 l.0 PROGRAM OVERVIEW 2.0 DEWATERING SOLIDS IN HICH INTECRITY CONTAINERS (IIIC)-

4 3.0 DELWARE CUSTOM MATERI AL (DCH)-SlLICATE CEMENT -

4 i

4.0 10 CFR 61 REQUIREMENTS 5.0 ABSORBED MATERI ALS (RitriLAND BURI AL SITE ONLY) d 4

i I

k t

OD0689-l l 36 A-B A01-BA05

.. -.. - ~. -..

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 1 of 94 A.-

0FFSITE DOSE CALCULATIONS I

PURPOSE The purposc of'this manual is to provide the methodologies and parameters used tot 1

1.

Calculate offsite doses consistent with 10 CFR 50, Appendix 1, during routine operations.

2.

Determine alarm / trip set points of effluent monitoring instrumentation.

REQUIREMENTS This manual'is required per Technical Specifications:

6.9.2.2.A.4 - Radiological-Impact on Man 13.1.1

- Radioactive Effluent Monitoring Instrumentation Operability and Surveillance Requirements 13.1.2

- Liquid Effluent Concentration 13.1.3

- Caseous Effluent Dose Rate Effluent Dose 13.1.4 Review, approval, issue and control is performed per Volume 1, Administrative Procedure 1.2.

l Changes to this manual shall be submitted to the Commission in i

accordance with Technical Specification Administ rative Cont rols, Section 6.15.

NOTE: Format of ODCH is such to be consistent with other plants ODCM.

I.

CASEOUS EFFLUENTS I

I l

21.A ALARH/ TRIP SET POINT METHOD l

Technical Specification 13.1.3.1 requires that HPC is not exceeded when averaged over a period not to exceed one hour. Based on the definition of HPC, the dose in unrestricted areas due to gaseous effluents from the site shall be limited at all times to the following values:

1.

500 mrem /y to the total body and 3,000 mrem /y to the ' skin f rom noble gases.

2.

1,500 mrem /y to any organ from radiciodines and particulates, due to inhalation.

OD0589-1333A-BA01-BA05

VOLUME 25 BIG ROCK POINT RAD 101.0CICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 2 of 94-l A.

OFFSITE DOSE CALCULATIONS Specification 13.1.1.1 requires gaseous effluent monitors _to have alarm / trip set points to ensure that offsite concentrations, when averaged over one hour, will not be greater than HPC. This section of the ODCH describes the methodology that will be used to 1

det ermine these set points.

The methodology for determining alarm / trip set points 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 phy ical settings on the monitors.

l.A.1 Allowable Concentration The t otal HPC-fraction (R) for the stack release point will be I

calculated by the relationship defined by Note 1 of Appendix B, 10 CFR 20.

Ci R = (Q) (F) )

I = $1.0 (I.1) 5 HPC; i

i where:

Ci i= The measured or calculated concentration, at ambient temperature and pressure, of nuclide i (pCi/cc) at the stack.

MPCi a The HPC of nuclide i f rom 10 CFR 20, Appendix B.

R=

The total MPC-fraction for the stack release point.

1 X/Q = Most conservative sector site boundary dispersion (9.12E-08 sec/m').

F=

Release flow rate (39,000 cfm = 18.4 m'/sec) for stack monitor considerationsi variable for other monitors.

4 OD0589-1333A-BA01-BA05

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VOLUME 25 BIC HOC 3 l'OlNT RADIOLOGICAL Revision 8 ErPLUENT T/S REQUIRED DOCUMENTS Page 3 c. 94 A.

OffSITE DOSE CALCULATIONS 1.A.2 Honitor Response Normal radiuattivity releases consist predominantly of 30-minute decayed fission gasses.

Therefore, stack monitor response cali-brations are performed to fission gas typical of normal releases (30-minuta-decayed off gas). Air ejector off gas monitor measures only slightly decayed gasses, however, so is calibrated to proviue accurate response to relatively f resh fiscion gasses.

Response

monitors used to define. fission product release rates under-accident conditions may vary f rom that of these mixes, however.

Monitor response for the two categories of monitor is determined as follount 1.

Normal Releases (30-minute-decayed fission gasses)

Total gas concent rat ion (pCi/cc) at t5 monitor is calculated.

The calibration curve or constant for cpm /(pCi/cc) is applied to determine cpm expect ed.-

The setting for monitor alarms is est ablished at some f actor (b) greater than 1 but less than 1/R (Equation 1.1) times the measured concentration (c) sa bx c (1.2) t 2.

Accident Releases Monitors are preset to alarm at or before precalculated of f site dose rates would be achieved under hypothetical accident conditions.

These set points 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 constant s for conversion between cpr and pCi/cc (or R/hr and pCl/cc), depending on monitor type, for fission product mixtures as a function of mixture decay time.

When these monitors are utillred for other than accident conditio e, either an appropriately decayed " accident" convershn curve t.wy be. used, or a decayed fiction gas calibration factor may be applied.

In these cases, set points are established as in 1 above.

1.B IE CALCULATION

1. B. I.

Doses are calculated for (1) noble-gases and (2) lodines and particulates. Doses as defined in this section are based on 10 CFR 50, Appendix-1 limits of mrem per quarter and millirem per

. year. All dose.pethways of major importance in the Big Rock environs are considered.

OD0589-1333A-BA01-ban 5

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Vol.UME 25 blC ROCK POINT RAD 101.0CICAL Resselon 8 1

ErrLUENT T/S REQUIRED DOCUMENTS page 4 of 94 l

A.

OrfSITE DOSE CALCULATIONS 4

I 4

1 1.B.I.1 Equations and assumpt ions for calculating doses f rom noble gases i

are as followst i

j I.H.1.1.1 As sumpt ion s 1

3 1.

Duses to be calculat ed are the maximum offsite point in air, i

total body and skin.

I

]

2.

Exposure pathway is submersion within a cloud of noble gases.

i

)

3.

Noble ga. radionuclide mix is based on the historically j

observed source term given in Table 1.1, plus additional l

j nuclides.

l Basic radionuclide data are given in Table 1.2.

I l

S.

All releases are t reated as elevated at 73 m.

il 6.

Heteorological data expressed as joint-f requency distribution of wind speed, wind direction, and atmospheric stability for i

the period resulting in X/Qs and D/Qs are shown i. Table 1.3.

2 i

7.

Raw meteorological data consist of wind speed and direction-j measurement s at 71 m.

l j

8.

Dose is to be evaluated at the of f site exposure point s where 1

maximum concent rations are expected to exist, ~and nearest i

residents.

j 9.

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

10.

A semi-infinite cloud model is used.

i j

11.

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

i 12.

Radioactive decay is considered for the plume, a

j 13.

A sector-average dispersion equation is used.

l 1

e I

i OD0589-1333A-BA01-BA05

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EFFLUENT T/S REQUIRED DOCUMENTS Page 5 of 94 A.

OFFSITE DOSE CALCULATIONS i

14.

The wind speed classes that are used are as follows:

Wind Speed Class Number Hange(m/s]

Hidpoinj (m/s) l 1

0.i O.0 l

2 0.4 0.95 l

3 1.5

..o 2.25 t

4 3.0-5.0 4.0 i

5 5.0-7.5 6.25 7

6 7.5-10.0 8.7$

~

7

>10.0 3

)

15.

The stability classes that will be used are the Standard A through C classifications. The stability Classes 1-7 will j

cor respond t o A = 1, B = 2...C = 7.

16.

Terrain effects are not considered, and no cpen terrain-recirculation f actors are applied.

1.B.1.1.2 Equations l-To calculate the dose for any one of the exposure points, the following equations are usedt

?

Por determining the air concentration of any radionuclidet i

7 7

Xj=)

(f)I fg7;7 exp (-Ai

)

8 yg j=1 K=1 X

esp ( -h')

i

__ 20 (1.3) 8 zk wheret 8

i Xi = Air concentration of radionuclide i, pCi/m.

fjk = Joint relative frequency of' occurrence of winds in wind spec

• class j, stability class k, blowing toward this exposure point, expressed as a fraction.

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

Pa fraction of radionuclide remaining in plume.-

2zk = Vertical dispersicn coefficient for stability class k (m).

l l

OD0589-1333A-BA01-BA05 l-

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lilC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 6 of 94 A.

OFFSITE DOSE CALCULATIONS i

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

i Downwind distance, m.

=

n = Number of sectors, 16.

Radioactive decay coefficient of radionuclide i, s'I.

A =

2na/n = Sector width at point of interes m.

h = Stack height (73 meters).

o ' = Vertical dispersion coefficient of stability class k.

zk P

For determining the total body doses DTB =

Xi DFB[

(1.4) i I

where DFB = Total body dose mrem /y.

Xi = Air concentratior, of radionuclide i, pCi/m.

8 DFBi = Total body dose factor due to gamma radiation, mrem /y per 8

pCi/m (Table !.5 ).

For determining the skin doses Ds

• Xi (DFSi +-1.11 DFYi)

(I.$)

i where e

Skin dose mrem /y.

Ds a

Xi = Air concentration of radionuclide i, pCi/m.

3 t

DFSi = Skin dose factor due to-beta radiation, mrem /y per pCi/m 3 l

(Table i.5).

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

DFYi = Camma-to-air dbae f actor for radionuclide i, mrad /y per pCi /m' (Table 1.5 ).

l OD0589-1333A-BA01-BA05.

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VOLUME 25 BIC ROCK PolNT RADIOLOGICAL Revision 8 j

EFFLUEWT T/S REQUIRED DOCUMENTS Page 7 of 94

{

A.

OFFSITE DOSC CALCULATIONS i

i 1

j For detertnining dose rate to a point in alrt i

l Da = p

{ Xi (DFY{ or DFBi)

(1.6)-

i j

wheret Da = Air dose mradly.

DFB = Air dose f actor f or beta radiation (Table 1.$).

l.B.1.2 Equations and assumptions for cal'culating doses from radiolodines and particulates are as follows:

j-1 1.B.I.2.1 As sumpt i ons I

I

1. - Dose is to be calculated for-tbe critical organ, thyroid, and the critical ai;c groups (adult, teen, child, infant), infant i

(milk) and child (green, leaf y vegetables).

I 2.

Exposure pathways f re.n iodines and particulates are milk ingest ion, ground cont amination, green leaf y vegetables f rom l

hom(. gardens and inhalation.

}

l 3.

The radiolodine-and particulate mix is based on the his-

}

torically observed source term given in Table 1.1.

NOTE Source term (s) may be changed il radionuclide mix i

dif fers significantly f rom the historical source terms per Technical Specification 13.1.3.3 - Sampling and Analysis.

+

4.

Basic radionuclide data are given in Table 1.2.

l All releases are treated as elevated (73 m).

6.

Annual average X/Qs are given in Table 1.3.

7.

Raw meteorological data for elevated releases consist of wind speed and direction measurements at 71 m.

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

i 9.-

Actual cow, goat and garden. locations are considered.

~

i l

10. -potential maximum exposure point's (Table 1.4) considered are l'

the nearest cow, goat and home garden locations in eacn sector.

l l

11.

Terrain effects are-not considered.

i.

l OD0$89-1333A-BA01-BA05 h

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BIC ROCK POINT RAD 101.0CICAL Revision 8 l

EFFl.UENT T/S REQUIRED DOCUMENTS Page 8 of 94 A.

OFFSITE LOSE cal.CUI.ATIONS i

12.

Plume depletion and radioactive decay are considered for i

air-concentration calculations.

13.

Radioactive decay is considered for grcund-concentration l

calculations.

14.

Hilk cows and goats obtain 100% of their food from pasture grass Hay through Oct ober of each year.

Use default values of 0.58 for cows and 0.67 for goats for fraction of year on pasture.

{

l$.

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

l.B.I.2.2 Equations To calculate the dose f or any one of the potential maximum-exposure points, the equations of Sections 1.B.1.2.2.1-1.B.I.2.2.5 are 4

used.

l.B.I.2.2.1 Inhalation Equation for calculating air concentration, X, is the same as in the Nob.a Cas Section 1.B.1.1.2 (Equation 1.3).

For det ermining the organ dose rate D

=1x 106)

'X DF1, BR (1.7)

I i

n i

l wheret Dg = Organ dose due to inhalation, mrem /y.

Xi = Air concentration of radionuclide i, pCi/m.

8 1

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

8 8

BR = Breathing rate 1,400 m /y, inf ant! 3,700 m /y, childt or 8

8,000 m /y, sdult and teen.

Ix 106 = pCi/pci conversion factor.

OD0589-1333*-BA01-BA0$

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VOLUME 25 Blc ROCK POINT RADIOLOGICAL Revisici 8 EFFLUENT T/S REQUIRED 10CJHENTS Page 9 of 94 A.

OffSITE DOSE CALCULATIONS 1.B.I.2.2.2 Cround Contamination for det ermining the ground concentration of any nuclidet 1

N i k

10 )

gg exP - (Al Lb)) lexP ( ;h' ))

(1.8) 7 k

C,

= 3.15 x 51

,(2nx/n) A; tk k=1 wheret Ci = Cround concentration of radionuclide i, pCi/m'.

k = Stability class.

Ika 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, pCi/s.

DRg = Relative deposition rate, 1/m.

x = Downwind distance, m.

n = Number of sectors, 16.

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

Ai = Radioactive decay coefficient of radionuclide i, y-I.

tb " Time for buildup of rtdionuclides on the ground, 35 y.

3.15 x 107 = s/y conversion factor.

h = Stack height (73 m).

o*zk = Vertical dispersion coefficient (m') of stability class.

l OD0589-1333A-BA01-BA05

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t Vol.UME 25 HIC ROCK l'0 INT RADIOLOClCAL Revision 8 El FLUENT T/S RCQUIRED DOCUMEN'IS Page 10 of 94 A.

OFFSITE DOSE CALCULATIONS For determining the total body or organ dose f rom ground contamination

[

6 DC = (8,760)(1 x 10)(0.7)}

Ci DFCI (1.9) j t

i 1

wheret i

i DC = Dose due to ground contamination, nrem/y.

Ci = Cround concentration of radionuclide i< PCi/m,

l a

DFC; = Dose tactor for standing on contaminated ground, mrem /h 8

per pCl/m (Table 1.8).=

8,760 = Occupation time, h/y.

1x 106 = pCi/pci conversion factor, i

-0.7 = Shielding factor accounting for a distance of 1.0 meter

~

above ordinary ground, dimensionless.

1.B.1.2.2.3 Milk and Vegetation Ingestion I

For determining the concentration of any nuclide (except C-14 and l

H-3) in and on vegetationt 7

9 i k (r[1 - exp (~A l

l CVi=3,600)

.k Ei e)] +

(1.10)

(2nx/n)

Y A y Ei l

I k=1 i

Niv Q t

('Al 'b)]

ye,p

_),,p (-Ag th) wheret CVi = Concentration of radionuclide i in and on vegetation, UCi/kg.

k = Stability class.

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

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

DRk = Relative deposition rate as a function of wind speed, stability elass and downwind distance, m'I (Figures 7 through 10 of Regulatory Guide 1.111).

OD0589-1333A-BA01-BA05

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

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VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQJ1 RED DOCUMENTS PaEe 11 of 94 I

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OFFSliE DOSE CALCULATIONS i

• Downwind di st ance, m.

}

}

na Number of sectors, 16.

i i

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

I r = fraction of deposited activity retained on vegetation (1.0 for iodines, 0.2 for particulates).

AEi = Ef fective removal rate constant, A i

• Ai + Aw, where Ai E

is the radioactive decay coefficient, h"I, and Aw is a

)

measure of physical loss by weathering (Aw =.0021 h"I).

te = Period over which deposition occurs, 720 h.

O 2

Y, a Agricultural yield, 0.7 kg/m.

Biv = Transfer f actor f rom soil to vegetation of radionuclide i j

(Table 1.6).

4 Ai = Rsdioactive decay coefficient of radionuclide i, h"I.

j tb = Time for buildup of radionuclides on the ground, 3.07 a 105 h (35y).

2 P = Effective surface density of soil, 240 kg/m.

3,600 = s/h conversion factor.

I h = Stack height (73 m),

oz = Vertical dispersion coefficient (m).

th = Holdup time between harvest and consumption of food, O h i

for pasture grass or 2.160 h for storage feed.

i l

i l

I l

l OD0589-1333A-BA01-BA05 i_...._...-_._..-,_..._....___,___..._,__,--_.

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f 6

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it!C ROCK POINT RADIOLOGICAL Revision 8 EFFl.UENT T/S REQUIRED DOCUMENTS Page 12 of 94 i

A.

OffSITE DOSE CALCULATIONS 1

For determining the concentration of C-14 in vegetation:

I

)

CV14 = 1 x 10' X14 (0.11/0.16)

(1.11) l wheret i

i l

CV14 = Concentration of C-14 in vegetation, pCi/kg.

l 8

)

X14 = Air concent ration of C-14, pCi/m.

)

0.11 = Fraction of t otal plant mass that is natural carbon.

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

1x 10' = g/kg conversion factor.

i e

For determining the concentration of 11-3 in vegetation:

[

CVT=1x 10' XT (0.75)(0.5/11)

(1. ll a )

i wheret CV7 = Concentration of H-3 in vegetation, pCi/kg.

XT = Air concent ration of 11-3, pcl/m'.

1 0.75 = fract ion of total plant mass that is water.

0.5 a Ratio of tritium concentration in plant water to tritium concentration.in atmospheric water.

11 = Absolute humidity of the atmosphere, g/m'.

1x 10' = g/kg conversion factor.

1 I

l ODOS89-1333A-BA01-BA05

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Vol.UME 25 BIC ROCK l'0 INT HAD101.OCICAL Revision 8 EFFl.UENT T/S REQUIRED DOCUMENTS Page 13 of 94 A.

OFFSITE DOSE CALCUl.ATIONS For determining the concentration of any nuclide in cow's or goat's milks i

4 CHj

• CVi FHj Q( exp (-Ai t()

(I.12) wheret chi = concent ration of radionuclide i (including C-14 and 11-3) in milk, pCi/1.

4 CVi = Concentration o' dionuclide i in and on vegetation, pCi/kg.

fHi = Transfer f actor f rom f eed to milk f or radionuclide i, d/1 (Table 1.6).

Qt = Amount of feed consumed by the milk animal per day, cow -

50 kg/d, goat - 6 kg/d.

Ai = Radioactive decay coefficient of radionuclide i, d'I.

t r = Transport time of activitv f rom f eed to milk to receptor, two days.

For determining tho organ dose-f rom ingestion of green leafy vegetables and milkt D=1x 106 i chi DFi UH (1.13)

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

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

DFi = Ingestion dose f actor. -mrem /pci (Table 2.1).

UH = Ingesti<.n rate for milk, 3301/y - infant and child, 400 1/y t een, and 310 1/y - edult.

Ingestion rate for vegetables, 26 kg/y - child, 42 kg/y j

- teen, and 64 kg/y - -adult.

1x 106 = pCi/pci conversion factor.

OD0589-1333A-BA01-BA05

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VOLUME 25 BIC ROCK PO!MT RADIOLOGICAL Revision 8 EFFLUENT T/S 14EQU* RED DOCUMENTS Page 14 of 94 A.

OFFSITE DOSE CALCULATIONS 1...).2.2.4 Heat Ingestion (Beef)

To calculete 'he concentration of a nuclide in animal flesht Cgi = Fii CVi Qt exp (-Ai ts)

(1.14) where!

Cri = Concent rat ion of nuclide i in the animal flesh, pCi/kg.

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

1 CVi = Concent ration of radionuclide i in the animal's feed (Equation 1.10).

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

t s = Average time f rom slaughter to consumption, 20 days.

To determine the organ dose f rom ingestion of beef t 1

)

' Cg i Dri U[

(I.15)

DF" i

I i

l wheret l

Dfi = Ingestion dose factor for age group, erem/7Ci (Table 2.1) for nuclide 1.

Ur = Ingestion rate of meat for age group, kg/y (child - 41, teen - 65, adult -110).

l t

OD0589-1333A-BA01-hA05

~ -. -... -. -

d 0

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OffSITE DOSE CALCULATIONS I

i 1.E.1.2.2.5 Organ Dose Rates 1

i i

For determining the total body, organ and/or thyroid dose rate f rom iodines and part iculates t De Dj +DC*DH + Dy + De (1.16) i l

wheret 4

l D = Total organ dose, mrem /y.

k Di = Dose due to inhalation, mrem /y.

i j

DC = Dose due $a cround contamination, mrem /y.

l DM = Dose due to milk ingestion, mrem /y.

Dy = Dose due to veget,able ingestion, mrem /y.

i

)

Dr

• Dose due to meat ingestion, mrem /y.

I

{

l.B.I.2.3 The maximum organ dose rate, maximum total body dose rate, maximum skin dose rate plus beta and Eamma air doses calculated in the 1

l previous section (Section I.B.I.2.2) are used to calculate design i

j basis quantities as described in Section 1.B.I.3.

I.B.I.3 Design Basis Quantities I

Th design basis quantity of a radionuclide emitted to the atmosphere is the amount-of t. hat nuclide, when released in one year, which i

i veuld result in a dose not exceeding any of the following

)

i 1.

15 millirems to any organ of an individual f rom iodines and particulates with half life greater than 8 days..

2.- 20-millirad air dose for beta radiation from noble gas (see note below).

t 3.

10-militrad air dese for gamma radiation from' noble gas (see note below).

d t-l l-l l

I

. 0D0589-1333A-BA01-BA05 h

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VOLUME ?$

HlC RDCK POINT RADIOLOGICAL Revision 8 1

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OFFSITE DOSE CALCULATIONS i

A ll k

Design basis quantity (Cl) is the smallest value for each nuclide,

).

calculated by dividing the dose limit s (a through c above) by the appropriate dose calculated in Step 18 the result then is multi-1 plied by the amount of radionuclide (Ci) used to conservatively

{

estimate the doses of Section D, as listed in Table 1.1 (or j

assumed a hypothetical i Ci/ year for nuclides not actually present):

1 i

l-DBQ = AI (Cc)

(1.17) i C

I 4

j wheret D g = Appendix I dose limit (mrem or mrad).

A De = Calculated dose f rom Step 1 (mreu or mrad).

I i

Ce = Quant ity of nuclide resulting in dose De (Cl).

f l

LoQ = Design Basis Quantity (Cl).

The limiting values f or Design Basis Quantities for radionuclides

}

released to the atmosphere are given in Table 1.9.

NOTE! For conservative calculations the DBQs listed in Table 1.9 l

are be. sed on I

j 1.

15 millirems to any organ of-an individual f rom lodines and-j particulates with a half life greater than eight days.

j 2.

15-millirad air dose f or beta radiation f rom noble gas.

l 3.

5-millirad-air dose f or gamma radiation f rom noble gas.

l The inverse of the ratio C /De in the above equation (ie, Dc/Ce) c is a useful value, since it represents the most limiting dose per unit quantity of each.nuclide released.

1.D.I.4 Land Use Census and DBQ Changes l

Technical Specification 13.2.3 describes the requirement s for an annual land use census and revision of the CDCM for use in the

. following calendar year.-

Areas of the 0DCH which will-be re--

viewed,. and changed if appropriate, are Table 1.4 (Land Use Census -

Dat a by Sectoi), and Table 1.9 (Caseouc Design Basis Objective Annual Quantities). Changes will be; eflective on Janurry 1 of-the year following the year of the ' survey.

4 e

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V01.UME 25 BIC ROCK polNT RADIGl.OCICAL Revision 8 EFFLUENT T/d kEQUlRED DOCUMENTS Page !? of 94 A.

OFFSITE DOSE CALCULATIONS 1.C DESIGN BASIS QUANTITY (DBQ) LIMITS 1.C.1 Design Basis Quantity Fraction per Technical Specification 13.1.4.4 the cumulative DBQ fraction for nuclides released is summed at least every 31 days to assure i

that the sum of the f ractions of all nuclides released does not exceed 1.0 year to date and 0.5 in any calendar quarter.

A '.

\\

< l.0 (1.18)

/

,(DBQ)[

t I.C.2 Exceeding DBQ Limits As discussed under I.B.I.3 the DBQ is a very conservative estimate of activity which could give doses at 10 CFR 50, Appendix I c

limits.

Because different organs are summed together and doses to different people are summed, the DBQ typically overestimates dose by about a f actor of five.

Thus, if calculations of the DBQ f raction exceed 1.0 for year to date or 0.5 for the quarter, technical specifications probably still would not be exceeded, llowe ve r, further discretionary releases should be deferred until an accurate assessment. of dose is made by use of the NRC CASPAR i

computer code. The computer run will utilize the annual average joint f requency meteorological data based on not less than 3 years of meteorological measurement, and will reflect demographic and i

land use information from the land use survey generated in the l

most recent prior year.

Where appropriate, seasonal adjustments l

will be applied to obtain realistic dose estinates since both I

recreational and ag:icultural activities can vary greatly in relation to season of the year.

It should be noted that Big Rock Point to date (based on review of semiannual effluent data) has never exceeded the annual or quarterly DBQ f raction, despite its conservatism, at any time in the past ten years (since stainless steel fuel cladding was replaccd by zirealoy and other engineering changes were made). Thus, it-is not expected that an alternate to the DBQ method will be required unless the plant is iin a significantly of f-normal Tondition.

l OD0589-1333A-BA01-BAC5

1 VOLUME 25 BIC ROCK PolHT RADIOLOGICAL Revision 8

{

EFFLUENT T/S REQUIRED DOCUMENTS Page 18 of 94 l

A.

OFFSITE DOSE CALCUl.ATIONS 1

I.C.)

Releasing Radionuclides Not I.isted in Table l_.9 j

Table 1.9 contains all nuclides identified to date as. iutine l

constituents of gaseous releases at Big Rock Point Pl ant. - pl us j

those conmon to boiling water reactors in general, even if not l

previously detected at Big Rock Point.

From time to time, however, l

other nuclides may be detected.

1 If the unlisted nuclide constitutes less than 10% of the HPC-fraction for the release, and all unlisted nuclides total less than 25% of the HPC-fraction, the nuclide may be considered not present.

e If the unlisted nuclide-constitutes greater thsn 10% of the HPC-f raction, or all unlisted nuclides together constitute greater than 25%, then each nu:lide rhould be assigned a DBQ equal to the most conservative value listed foi the physical form of-the

)

nuclide involved (noble gas, halogen or particulate).

Should a nuclide not listed in Table 1.9 begin to appear in significant quantities on a routine basis, revision to this ODCH J

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

to that nuclide.

2 l

1.D CASEOUS RADWASTE TREATHENT SYSTEM OPERATION I

1.D.1 Syst em Description l

The gaseous radwaste system consists of a delay line for condenser l

off gas which provides approximately 30 minutes of decay time i

prior to release via the 73 m stack. A flow diagram of gaseous waste release paths is shown in Figure 1-1.

l Condenser off gas represents more than 95% of the total Easeous source term. The other minor sources are gland seal condenser exhaust, containment ventilation, radwaste system vents and miscellaneous turbine building system leakage. Ali these sources are-ducted to the stack for release.

I 1.D.2 Determination of Satisfactory Operations l

Operability requirement s for the gaseous waste treatment are not specified. This is because the decay line is an integral part of the release, path piping for condenser off gas.

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VOLUME 25 BlC ROCK POINT RADIOLOGICAL Revieion 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 20 of 94 A.

OFFSITE DOSE CALCUl.ATIONS s

1.E OffSITE HPC ilELEASE RATE 10 CFR 20.106 requires that radioactive effluent releases to un-r-st ricted areas be in concent rat ions it,s than t he limit s speci-fied in Appendix B, Table 11 when averaged over a period not to exceed one year.

(NOTEt Total area within the site boundaries is restricted as defined by Figure 2.1.)

Concentrations at this level if present for one year will result in a dose of 500 mrem total body or 3,000 mrem to snin or 1,500 mrem to the critical organ depending on the nuclide(s) released.

10 CFR $0.36a requires that the release of radioactive materials be kept as low as reasonably achievable.

flowever, the section further states that the licensee is permitted the flexibility of operation, to assure i

a dependabic source of pcwer, to relasse quantities of material higher than a small percentage of l'. 4FR 20 limits but-not exceeding those limits under unusual operating conditions.. Appendix 1 to l

10 CFR 50 provides the numerical guidelines on limiting cond!tions for operations to meet the as low as reasonably achievable requirement.

The CASPAR code has been run to determine t he dose due to external radiation and inhalation. The source term used is listed in Tab le 1.1.

The meteorology data Is given in Table 1.3.

Dose using annual average meteorology, to the most l i.aiting of f sit e dose (whole body) assumed t o be residing at the residence with highest X/Q, is 0.105 mrem for one year.

The release rate which would result in a dose equivalent to 500 mrem /y (using the total bv.ly limit) is the Curies / Year given in Table 1.1 (1.29E04) multiplied by $00/.105 or 1.95 Ci/sec.

The above calculation is informationst ao a typical exposure using average releases from Big Rock Point. Actual exposure calculations are described in Section 1.A.

l.F pAhTICULATE AND 10 DINE SAMPLING Particulate and iodine samples are obtaiacd f rom the continuous I

sample st ream pulled f rom the plant stack. - Samples typically are obtained to represent the integrated release-frem the stack.

Canna analytical results for particulate and. halogeo. filters are combined for determination of total activity of gt ciculates.and halogens released. Beta and alpha counting also is nerformed on the particulate filters. Beta yields of the gamma isotopes detected on particulate filters are-applied to determine "identi-fied" beta, and the " identified" count rate is subt racted from the observed count rate to give " unidentified" beta. The " unidentified" beta is assumed to be Sr-90 until results on cetual Sr-90 (chtmically separated from a quarterly composite'of filters) are obtained.

Similarly, alpha activity not identified as natural radium or thorium or their daughters is as. -ed as Pu-239 until 5csults of detailed analyses are obtained from quarterly composites.

s 4

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Vol.UME 25 BIC ROCK POINT HAD101.OCICAl.

Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 21 of 94 A.

OFFSITE DOSE CALCULATIONS The "Stackgas" Program,. used to calculate the release rates when analyzing the stack's particulate and iodine samples, takes the total release rate and ratios it to the allowable Sr 90 (most i

restrictive nuclide) release rate.

If the ratio is ? 0.5 it warns that the Technical Specification 13.1.3.1.b limat may have been exceeded.

1.C NOBLE CAS SAMPt.ING Condenser air ejector of f 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 tronitor (RE 8283) which has an Ll.D of IE-06 pCi/cc.

1.H TRITIUH SAMPLING Tritium has a low dose consequence to the public because of low production rates. The major contributors to tritium ef fi" ant s are evaporatirn f rom the fuel pool and reactor cavity (when flooded).

Bccause of the low dose impact, gaseous tritium sampling will not be required. Tritium ef fluents will be' estimated 'using conservative evaporation rate calculations from the fuel pool and reactor cavity.

I o

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i VOLUME 25 H1C ROCK POINT RAD 10LOClCAL IMvision 8

+

EITLUENT T/S REQUIRED DOCUMENTS Page 22 of 94 A.

OffSITE ICSE CALCUl.ATIONS TABLE 1.1 i

810 accr ronrr CAstous Aro E1gule sounCE Trant. Ctmits/ftAs (II ~

Fucitde Caeeous 1.t qu'idIII

~

H3 1.21E+01 8.63E&00 N-13 1.53E+03 NA Na 24 3.52I.04 1.12E 06 Cr-51 2.82E-04 6.84E 03 Ma-54 5.50E-05 2.6eE 02 Ma 56 1.70E-04 XA Co 58 1.65E-06 6.17E 04 re 59 2.81E-06 9.0$E 03 Co 60 1.89E-04 4.21E 02 In 65 3.16E-05 9.01E-04 Br-82 8.11E-03 NA Kr.83e

.2.61E+02 NA Kr*85 9.55E 01 MA Kr 85e 3.12E402 NA Kr 87 1.19E+03 NA Kr 84 7.80E+02 NA-Kr 89 6.96t+02 XA St 89 XA 2.27E 04-Kr-90 7.76t+02 NA St 90 NA 2.22I 03 Kr 91 6.68E+00 RA St-91 5.61E-03 MA St 92 NA 1.54E 06 Nb 95 1.91E-06 NA Mo 99 3.10E-05 NA Ag 110e 1.57E-05 6.88E 05 Sb 124

.RA 4.01E 04 I 131 1.94t-03 1.57E-04 Ze 131m 4.38E 01 NA I 132 8.07E-03 RA I 133-1.99E-02 NA Xe 133 2.01E402 4.86E 05 Xe 133a 6.00E+00 NA Cs 134

4. ' it-07 1.75E-02 1-134 1.24E-02 EA 1 135 3.00E-02 NA Xe 135 1.11E+03 EA Xe 135e 1.15E+03 EA Cs 136 4.74E-05 EA -

Cs 137

-1.51E-04 2.04E 01 Ke 137 1.11E+03 EA Cs-138 3.17E-01 RA Ic-138_

6.03E+03.-

EA Ba 139-1.321-03 RA

_Xe 139 1.04E+03 NA Ba 140 1.86E NA

!.a 140 7.80E-03 5.04E-05 L

Ic-140 7.23E+01 RA r

Eg 203 1.31E-06 RA i

l Fp 239 1.44E-04 NA l

t!aidentified beta 2.42E-03 6.76E 02-(1) Data derived from taktog the effluents released during Jan June l --

1980 -through, Juix December 1983 and dividian by,4.,

(2) Fuclide values listed as NA have not been observed at detectable levels in these vaste streana..

OD0589-1333A-BA01-BA02

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VOLUME H Blc ROCK PolNT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED tt0CUMENTS Page 73 of 94 A.

OFFSITE DOSE cal.CUI.ATIONS TABLE 1.2 BASIC KADIONUCLIUE DATA I

I NUC1.lDE EA1.Td.1T E 1).HBDA BETA CAMKA (davs)

_(l / s )_

JHEY/DI5)_

(HEV/ DIS)_~

l Tritium 4.49E 03 1.79E-09

5. 68 E-03 0.0 2

C-14 2.09E 06 3.84E-12 4.91E-02 0.0 3

N-13 6.94E-03 1.16E-03 4.9tt-01 1.02E 00 4

0-19 3.36E-04 2.39E-02 1.02E 00 1.05E 00 T-18 7.62E-02

1. 05'E-04 2.50E-01 1.02E 00 6

NA-24 6.33E-01 1.27E-05 5.55E-01 4.127 00 7

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

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

CR-51 2.78E 01 2.89E :07 3.86E-03 3.28E-02 10 MI-54 3.03E 02 2.65E-OL 3.80E-03 8.36E-01 11 M1-56 1.07E-01

,7. 50 E-05 8.29E-01 1.69E 00 12 TE-59 4.50E 01 1.78E-07 1.18E-01 1.19E 00 13 CO-58 7.13E 01 1.12E-07 3.41E-02 9.78E-01 14 CO-60 1.92E 03 4.18E-09

9. 68E-02, 2.50E 00 15 ZN-69m 5.75E-01 1.39E-05

2. 21 E-2

4.16E-01 16 EN-69 3.96E-02 2.03E-04 3.19E-01 0.0 17 ER-84 2.21E-02 3.63E-04 1.28E 00 1.77E 00

~

18 BR-85 2.08E-03 3.86E-03 1.04E 00 6.60E-02 19 ER-85m 1.83E-01 4.38E-05 2.53E-01 1.59E-01 20 KR-85 3.93E 03-2.04E-09 2 dlE-01 2.21E-03 21 KR-87 f28E-02 1.52E-04 1.32E 00 7.93E-01 22 ER-88 1.17E-01 6.86E-05 3.61E-01 1.96E 00 13 KR-89 2.21E-03 3.63E-03 1.36E 00 1.83E 06 24 RB-88 1.24E-02 6.47E-04 2.06E 00 6.26E-01 25 R3-89 1.07E-02 7.50E-04 1.01E 00 2.05E 00 26 SR-89 5.20E 01 1.54E-07 5.83E-01 8.45E-05 27 SR-90 1.03E 04 7.79E-10 1.96E-01 0.0 l

28 SR-91 4.03E-01 1.99E-05

6. 50 E-01 6.95E-01 29 SR-92 1.13E-01 7.10E-05 1.95E-01, 1.34E 00 30 SR-93 5.56E-03 1.44E-03

9. 20E-01 2.24E 00 31 T-90 2.67E 00 3.00E-06

9. 36E-01 0.0 32 T-91m

3. 47 E-02 2.31E-04 2.73E-02 5.30E-01 33 T-91 5.88E 01 1.36E-07 6.06E-01 3.61E-03 34 T-92 1.47E-01 5.46E-05 1.44E 00 2.50E-01 35 T-93 4.29E-01 1.87E-05 1.17E 00 8.94E-02 36 ZR-95 6.50E 01 1.23E-07 1.16E-01

7. 35E-01 37 NB-953 3.75E 00 2.14E-06 1.81E-01 6.06E-02 38 NB-95 3.50E 01 2.29E-07 4.44E-02 7.64E-01 39 E0-99 2.79E 00 2.87E-06

3. 96E-01 1.50E-01 40 TC-99m 2.50E-01 3.21E-05 1.56E-02 1.26E-01 41 TC-99

7. 4E 07 1.04E-13 8.46E-02 0.0 i

42 TC-104 1.25E-02 6.42E-04 1.60E 00 1.95E 00 OD0589-1333A-BA01-BA02

VOt.UML 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 24 of 94 A.

OFFSITE DOSE CALCULATIONS TABLE 1.2 BASIC RADIONDCLIDE DATA NUCL1DE MALT-LIFE 1.AM3DA I

I BETA CAMMA (days)_

_1/s)

(MEV/ DIS)

(MEV/ DIS)

(

43 RU-106 3.67E 02 2.19E-08 1.01E 0.0 44 11-132 3.24E 00 2.48E-06 1.00E-01 2.33E-01 45 1-129 6.21E 09 1.29E-15

5. 43 E-02 2.46E-02 46 1-131 8.0$E 00

9. 96 E-07 1.90E 3.81E-01 47 1-132 9.5BE-02 8.37E-05

4. 89 E-Oi 2.24E 00 48 1-133 8.75E-01 9.17E-0G 4.08E-Ol 6.02E 01 49 1-134 3.61E-02 2.22E-04

$.16E-01 2.59E 00 50 1-135 2.79E-01 7.87E-05 3.68E-01 1.55E 00 51 IE-131m 1;18E 01 6.80t-07 1.43E-01 2.0lE-02

$2 1E-133a 2.26E 00 3.55E-06 1.90E-01 4.15E-02 53 IE-133 5.27E 00 1.52E-06 1.35E-01 4.60E-02 54 IE-135m 1.0BE-02 7.43E-04

9. 58 E-02 4.32E-01 55 12-135 3.83E-01 2.09E-05 3.17E-01 2.47E-01 56 IE-137 2.71E-03 2.96E-03 1.77E 00 1.88E-01 57 YE-138 9.84E-03 8.15E-04 6.65E-01 1.10E 00 58 CS-134 7.40E 02 1.07E-08 1.63E 1.55E 00 59 CS-135 1.10E 09

7. 2.9E-15 5,63E-02 0.0 60 CS-136

. l'. 30E, 01 6.17E-07 1.37E-01 2.15E 60 61 CS-137

.l.10E 04 7J9E-10 1.71E 5.97E-01 62 CS-138 2.24E-02 3.58E'04_

l.20E 00 2.36E 00-63 BA-139 5.76E-02 1.39E-04 8.96E-01 3.53E 4 64 EA-140 1.28E 01 6.??E-07 3.15E-01 1.71E-01 65 1A-140 1.68E 00 4.77E-06 5.33E-01 2.31E 00 66 CE-144 2.84E 02 2.82E-04 9.13E-02 1.93E-02 67 FI-143 1.36E 01 5.90E-07 3.14E-01 0.0

'68 Pt-144 1.20E-02 6.68E-04 1.21E 00 3.18F 02 I

herage energy per disintegration values were obtained from ICIP Pubiteetion 1to 38, Radionuclide Transformations : Energf_ and Intensity of Entssions, 1983 and NUREC/C1-1413 (ORNL/NUREC-70), 3 Radionuelf de Decay Data Base -

_1ndet and Summaarv Table. D. C. Eocher, May 1980.

OD0589-1333A-BA01-DA02 8

VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS TABLE 1.3 Page 25 of 94 A.

OFFSITE DOSE CALCULATIONS USMAC COMPUTER'<0DE - X00D00, VERSION 2.6.

RUN DATE e,-z/-90 schs $10 ROCK POINT X00D0082 mum USING 01/01/84 - 12/31/88 MET DATA maan ELEVATED RELEASE - 240* STACK M0 DECAY.

UNDEPLETED

$NNUAL' AVERAGE CHI /Q' (5EC/ METER CURED)

DISTANCE IN MILES FROM THE SITE r

SECTOR 0.250 0.500 0.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 S

1.332E-08 1.977E-08 2.105E-08 2.550E-08 3.242E-d8 3.346E-08 3.194E-03 2.963E-03 2.722E-08 2.496E-08 2.292E-08 6.343E-09 1.413E-08 1.582E-08 1.888E-08 2.356E-08 2.420E-08 2.307E-08 2.138E-08 1.963E-08 1.798E-08 1.650E-05 6.188 E-09 7.535E-09 7.740E-09 1.07 0E-08 1.595E-03 1.751E-08 1.721E-08 1.624E-08 1.507 E-05 1.391E-08 1.284 E 35H 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+000 5H

.H5H 0.000E+00 0.000E*00 0.000E+00 0.000E+00 1.550E-09 4.053t-09 8.163E-09 H

0.000E+00 3.246E-44 9.752E-30 7.284E-22 2.699E-15 1.608E-12 4.900E-11 3.921E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+GD 1.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E i

HnN 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0 HH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0 NNN 6.344E-09 1.277E-08 2.302E-08 3.369E-08 4.499E-08 4.623E-08 4.374E-08 4.025E-08 3.674E-08 3.351E-08 3.064E-03 M

2.449E-08 3.784E-08 4.604E-08 4.896E-08 4.460E-08 3.913E-08 3.415E-08 2.994E-03 2.645E-03 2.355E-05 kNE NE lt00BE-04 4.705E-08 5.316E-08 5.449E-08 4.885E-08 4.231E-08 3.67 0E-08 3.'197 E-03 2.809E-0 5 2.489 0-08 EN E -

1.836E-c? 3.828E-08 E

1.794E CE 4.517E-08 5.248E-08 5.480E-08 5.138E-08 4.422E-08 3.752E-CA 3.200E-03 2.757E-08 2.402E-05 2.115E-08 3.89&E-Os 4.308E-08 4.342E-os 3.971E-08 3.39eE-Os 2.875E:D8 2.e48E-os 2.108E-08 1.834E-08 1.415E-c8 1.594E-08 E5E 1.704E.

3.411E-08 3.470E-08 3.512E-C, 3.425E-08 3.060E-08 2.667E-08 2.321E-08 2.032E-08 1.792E-08 1.238E-08 2.745E-08 2.909E-08 3.262E-08 3.710E-08 3.601E-08 3.302E-08 2.973E-08 2.668E-08 2.400E-05 2.169E-08 1.563E-66 SE SSE 4

DISTANCE IM MILES FROM THE SITE l 4NNUAL AVERAGE CHI /O (SEC/ METER CURED)

SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 1.108E-08 7.197E-09 5.230E-09 4.058E-09 3.287E-09 2.746E-09 2.348E-09 2.043E-09 1.803E-09 2.111E-08 1.474E-08 1.518E-08 1.057E-08 7.924d-09 5.131E-09 3.722E-09 2.883E-09 2.333E-09 1.948E-09 1.663E-09 1.446 E-09 1.276E-09 5

55H' 1.314E-09 1.141 E-09 1.005E-09 1.186 E-08 8.349E-09 6.2 84 E-09 4.080E-09 2.956E-09 2.287E-09 1.848E-09 1.540E-09 0.000E+00 0.0c0E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E 5H 0.000E*00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.'000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 H5H 1.382E-08 5.307E-08 8.609E-05 1.ll4E-07 1.092E-07 9.907E-08 8.794E-08 7.772E-08 6.886E-05 6.131E-08 5.490

.H

' O.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0 HNH 0.000E*00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0 NH 0.000E+00 0.000E+00 0.000E+00 0.000E*00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E MNW i

2.812E-08 1.941E-08 1.450E-08 9.358E-09 6.774E-09 3.246E-09 4.245E-09 3.543E-09 3.027E-09 2.633E-W9 2.323E-09 N.

1.351E-08 9.620E-09 5.848E-09 4.080E-09 3.074E-09 2.435E-09 1.997E-09 1.681E-09 1.444E-09 1.259E-09 MME NE 2.115E-08 ENE 2.226E-08 1.404E-08 9.900E-09 5.949E-09 4.122E-09 3.090E-09 2.438E-09 1.994E-09 1.474E-09 1.435E-09 1.250E-c9 1.881E-08 1.16 5E-08 8.129E-09 4.835E-09 3.343E-09 2.503E-09 1.974E-09 1.613E-09 1.3340-09 1.161E-09 1.011E-09 1.436E-08 8.901E-09 6.213E-09 3.696E-09 2.557E-09 1.916E-09 1.512E-09 1.234E-09 1.038 E-0 9 3.901E-10 7.755E-10 E

1.430E-08 9.140E-09 6.502E-09 3.955E-09 2.768E-09 2.091E-09 1.659 E-09 1.364E-09 1.iSOE-09 9.894E-10 3.666E-10 i

E5r 1.554E-09 1.141 E-09 SE

,1.970E-08 1.312E-08 9.555E-09 5.968E-09 4.231E-09 3.224 E-09 2.575E-09 2.127E-09 1.800E-09 55E VENT AND SUILDING PARAMETER 58 '

REL EASE HEIJMT * (METEMS) 73.30 REF. MIMD HEIOMT (METERSI 71.3 LI AMETER.

(METERS) 1.14 SUILDING HEIGHT (METER 5) 31.4 i

EXIT VELOCITY (METER 3) 15.21 BLDO.MIM.CRS.3EC. AREA (SO. METER 3) 2900.0 HEAT EMISSION RATE (CAL /SEC) 0.0 ALL ELEVATED RELEASES.

OD0589-1233A-BA01-BA02 Data in sectors WSW through N are not valid.

Refer to note at the end of Table 1.3.

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS LABLE 1.3 Page 26 of 94 l

A.

OFFSITE DOSE CALCULATIONS iNRC COMPUTER 60DE - XOQD0Q, VERSION 2.0 tiJN DATE: 09-41-90 t

Acc BIO ROCK POINT X0QD0082 mum USING 01/01/34 - 12/31/88 MET DATA numm LEVATED RELEASE - 240' STACK ocOc:mummanummmmmmmmmum RELATIVE DEPOSITION PER UNIT AREA (Mum-23 8Y DONNHIND SECTORS maapammmmmmmmmmmmmmmmune SEGMEXT BOUNDARIES IN MILES IEECTION

.5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 44-50 ROM SITE 3.690E-10 2.093E-10 1.179E-10

7. 536 E-11 5.144E-11 2.359E-11 7.908E-12 3.607E-12 2.356 E-12 1.790E-12 '

SSN 2.631E-10 1.442E-10 3.015E-11 5.112E-11 3.489E-11 1.603E-11 5.397E-12 2.458E-12 1.577E-12 1.167E-12 5N 1.239E-10 8.240E-71 4.908E-11 3.190E-11 2.185E-11 1.002E-11 3.340E-12 1.472E-12 8.948E-13 6.256E-13 H5H 0.000E+00 0.000E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l

W 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.c00E+00 MrK 2.6 48 E-09 2.839E-09 1.954E-09 1.312E-09 9.038E-10 4.114E-10 1.342E-10 5.600E-11 3.140E-11 2.031E-11 l

ce 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+R0 0.000E+00 0.000E+00 1H 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0

0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MNE 5.351E-10 3.732E-10 2.233E-10 1.439E-10 9.81(E-11 4.445E-11 1.441E-11 6.162E-12 3.644E-12 2.503E-12,

NE 1.035E-09 6.687E-10 3.845E-10 2.443E-10 1.660E-10 7.488E-11 2.411E-11 1.021E-11 5.884E-12 3.C7 3E-12 ENE 1.032E-09 6.548E-10 3.806E-10 2.440E-10 1.664E-10 7.563E-11 2.477E-11 1.0(8E-11 6.274E-12 4.206E-12 E

1.125E-09 6.292E-10 3.480E-10 2.206E-10 1.501E-10 6.857E-11 2.274E-11 1.003E-11 6.008E-12 4.072E-17 ESE 9.603E-10 5.118E-10 2.738E-10 1.712E-10 1.161E-10 5.291E-11 1.747E-11 7.718E-12 4.647E-12 3.159E-12 SE 6.679E-10 3.546E-13 1.921E-10 1.212E-10 8.243E-11 3.776E-11 1.262E-11 S.642E-12 3.449E-12 2.385E-12 33E

'4.855E-10 2.763E-10 1.558E-10 9.968E-11 3.804E-11 3.120E-11 1.045E-11 4.713E-12 2.992E-12 2.194E-12 ENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS) 73.10 REP. HIND HEIDHT (METERS) 71.3 EIAMETER (hETERS) 1.14 BUILDING HEIGHT (METERS) 31.4 EXIT VELOCITY (METEFS) 18.21 BLDO. MIN.CRS.SEC. AREA (SQ. METERS) 2000.0 HEAT EMISSION RATE (CAL /SEC) 0.0 LL ELEVATED RELEASES.

i OD0589-1333A-BA01-BA02 Data in sectors WSW through N are not valid. Refer to note at the end of Table 1.3.

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS TABLE 1.3 Page 27 of 94 A.

OFFSITE DOSE CALCULATIONS INRC COMPUTER CODE - XOQDOQ, VER$10H 2.0 RUN DATE: 09-z1-90

~

t ecQ BIO ROCK P01MT XOQD0Q82 man U51HO 01/01/84 - 12/31/88 MET DATA Manu

<EVATED RELEASE - 240' STACK eoceenummmmmmmmmmmma RELATIVE CEP031T10N PER UNIT AREA (Mum-2) AT FIXED FOINTS BY DONMHIND SECTOR 3 mununmanmuunnuunamar IRECTION DISTANCES IN MILES

1. DM SITE 0.25 0.50 0.75 1.00 1.50 2.00 2.50 3.00 3.50 4.00 4.50

-5 5.659E-10 4.587E-10 3.745E-10 3.199E-10 2.092E-10 1.540E-10 1.183E-10 9.343E-11 7.536E-11 6.180E-11 5.137 E-11 33H 4.267E-10 3.363E-10 2.670E-10 2.235E-10 1.435E-10 1.050E-10 8.035E-11 6.341E-11 5.111E-11 4.191E-11 3.484E-11 5H 1.757E-10 1.464E-10 1.297E-10 1.195E-10 8.323E-11 6.322E-11 4.940E-11 3.940E-11 3.194E-11 2.625E-11 2.184E-11 H5H 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

.H 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 HNH 2.008E-10 1.205E-09 2.565E-09 3.432E-09 2.975E-09 2.440E-09 1.979E-09 1.609E-09 1.317E-09 1.086E-C" 9.038E-10 MH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.c00E+00 NNH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 N

0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 MNE 4.894E-10 5.369E-10 5.445E-10 5.271E-10 3.827E-10 2.892E-10 2.245E-10 1.783E-10 1.441E-10 1.181E-10 9.805E-11 ME 1.022E-09 1.110E-09 1.063E-09 9.764E-10 6.832E-10 5.040E-10 3.858E-10 3.038E-10 2.443E-10 1.998E-10 1.657E-10 r/E 1.231E-09 1.153E-09 1.051E-09 9.58 3E-10 6.647E-10 4.955E-10 3.823E-10 3.025E-10 2.441E-10 2.001E-10 1.662E-10 2

1.660E-09 1.4kOE-09 1.148E-09 9.707E-10 6.299E-10 4.580E-10 3.488E-10 2.742E-10 2.205E-10 1.805E-10 1.499E-10 SSE 1.433E-09 1.225E-09 9.858E-10 8.086E-10 5.109E-10 3.641E-10 2.737E-10 2.136E-10 1.710E-10 1.397E-10 1.159E-10 0E 1.073E-09 8.654E-10 6.814E-10 5.590E-10 3.526E-10 2.538E-10 1.923E-10 1.508E-10 1.211E-10 9.907E-11 8.230E-11

,q 7.436E-10 6.025E-10 4.926E-10 4.217E-10 2.763E-10 2.036E-10 1.564E-10 1.236E-10 9.969E-11 8.175E-11 6.796 E-11

.5E alECTION DISTANCES IN MILES COM SITE 5.00 7.50 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 4.321E-11 2.271E-11 1.444E-11 7.625E-12 4.853E-12 3.562E-12 2.813E-12 2.344E-12 2.023E-12 1.781E-12 1.612E-12

$$H 2.932E-11 1.544E-11 9.837E-12 5.210E-12 3.517E-12 2.431E-12 1.906 E-12 1.570E-12 1.337E-12 1.161E-12 1.036E-12 SH 1.835E-11 9.644E-12 6.130E-12 3.222E-12 2.033E-12 1.456E-12 1.112E-12 8.499E-13 7.360E-13 6.228E-13 5.398E-13 i

HSH 0.000E+00 0.00DE+00 0.000E*00 0.300E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 W

0.000E*00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 HMH 7.579E-10 3.958E-10 2.499E-10 1.292E-10 8.022E-11 5.519E-11 4.053E-11 3.116E-11 2.477E-11 2.021E-11 1.683E-11 NH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NMH 0.000E+00 0.000E+00 0.000E*00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 M

0.00LE+00 0.000E+00 0.000E+00 0.000E+00 0.000E*00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+CU 0.000E+0G MNE 8.229E-11 4.273E-11 2.682E-11 1.384E-11 8.643E-12 6.078E-12 4.577E-12 3.620E-12 2.966E-12 2.491E-12 2.144E-12 NE 1.391E-10 7.195E-11 4.498E-11 2.312E-11 1.441E-11 1.009E-11 7.517E-12 5.846E-12 4.692E-12 3.857 E-12 3.233E-12 EME 1.396 E-10 7.273E-11 4.584E-11 2.383E-11 1.494E-11 1.057E-11 7.946E-12 6.238E-12 5.052E-12 4.189E-12 3.545E-12 E

1.261E-10 6.598E-11 4.178E-11 2.192E-11 1.384E-11 9.939E-12 7.556E-12 5.979E-12 4.872E-12 4.057E-12 3.445E-12 ESE 9.750E-11 5.088E-11 1.213E-11 1.682E-11 1.062E-11 7.655E-12 5.835E-12 4.626 E-12 3.775E-12 3.148E-12 2.675!-12 SE 6.925E-11 3.634E-11 2.308E-11 1.217E-11 7.718E-12 5.597E-12 4.296E-12 3.434E-12 2.827E-12 2.377E-12 2.040E-12 SSE,

5.716E-11 3. cD4E-11 1.910E-11 1.008E-11 6.397E-12 4.661E-12 3.634E-12 2.977E-12 2.523E-12 2.184E-12 1.940E-12 i

OD0589-1333A-BA01-BA02 Data in sectors WSW through N are not valid. Refer to note at the end of Table 1.3.

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Revision 6 VOLUME 25 BIC ROCK POINT RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS TABLE 1.3 Fage 19 of 94 A.

OFFSITE DOSE CALCULATIONS

'UdNRC COMPUTER' COM - X0QD00, VERSION 2.0 RtM DATE: 09-z/-90 l

comm BIO ROCK POINT X00D0Q82 mum USING 01/01/84 - 12/31/88 MET DATA maan ELEVATED RELEASE - 240' STACK 8.000 DAY DECAY.

DEPLETED DISTANCE IN MILES FR0rt THE SITE 0.250 0.500 0.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 AMMt'At AVERAGE CHI /Q (SEC/ METER CURED) 1.331E-08 1.953E-08 2.068E-08 2.509E-08 3.192E-08 3.290E-08 3.136E-03 2.905E-08 2.66 SECTOR 0

f.341E-09 1.399 E-08 1.552E-08 1.854E-08 2.313E-08 2.376E-08 2.261E-08 2; 092E-08 1.917E-08 1.754E-08 1.6 07E-5 1.479 E-0 8 1.16 3E-08 1.256E-08 s

6.186E-09 7.458E-09 7.620E-09 1.05a E-08 1.578E-08 1.728E-08 1.696E-08 1.5 55H l

SH H

0.0000+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000C+00 0.000E+c3 0.0 i

WPtM 0.000E+00 3.233C-46 9.693C-3o 7.226E-22 2.442E-15 1. 3 52 E-12 4.4 61 E-11 3.479 E-lo 1.4 H5W 0.000E+00 0.00DE*00 0.000E*00 0.000E+00 0.CCCE+00 0.000E+00 0.000E+00 0.000E*C0 0.000E+00; 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E*00 0.000E+00 0.C00E+00 0.0 0.000E+00 0.000E*00 0.000E+00 0.000E+00 0.000E+00 0.000E'00 0.000E+00 0.C00E+00 0.QQ0E+00 0.000E*00 0.0 MM 0.000E+00 www 6.343E-09 1.268E-08 2.281E-08 3.343f-08 4.453E-05 4.544E-08 4.3985-08 3.956E-08 3.605E-0 M

1.008E-08 2.430E-08 3.735E-08 4.545E-08 4.837E-08.4.355E-08 3.802E-08 3.303E-05 2.884E-NME 1.836E-08 3.793E-08 4.637E-08 5.241E-08 5.344E-05 4.742E-08 4.112E-08 3.542E-08 3.071E-08 2 NE 1.793E-08 4.475E-08 5.177E-08 5.374E-08 5.012E-08 4.289E-05 3.#18E-08 3.070E-03 2.632E-08 2 ENE 1.704E-08 3.860E-08 4.228E-08 4.248E-08 3.863E-08 3.284E-03 2. 44E-08 2.343E-OS 2.007E-Oa E

2.973E=ca 2.541C-os 2.237 C-Ca 1.931E-Ca 1.715E-ca 1.SzoE-Os 1.23sz-Os 2.73ac-Os 2.as4E-Os 3.204E-Os s.642f-ca 3.529E-Da s.229E-ca 2.901E-ca 2.59aE-Os E5E 1.543E-08 3.377E-05 3.404E-ca 3.439C-Da 3.341E-08 SE sst DISTANCE IN MILES FRDN THE SITE SECTOR 5.000 7.500 10.000 15.000 20.000 23.000 30.000 35.000 40.000 45.000 50.000 ANNUAL AVERAGE CHI /O (SEC/ METER CUSE9) 2.059E-08 1.431E-08 3.071E-05 4.909E-09 4.991 E-09 3.852E-09 3.103E-09 2.583E-09 2.1960-09 1.9 1.477E-08 1.023E-08 7.632E-09 4.905E-09 3.534E-09 2;722E-09 2.191E-09 1.E30E-09 1.546E-09 1.338E-09 1.174E-09 5

1.159E-08 8.114E-09 6.083E-09 3.920E-09 2.823E-09 2.172E-09 1.746E-09 1.e 7E-

$5H 0.000t+00 0.000E+00 0.000E+00 0.000r+00 0.0c0E+00 6ceE+50 c.ce5t+06 5H 0.000E+00 0.000E+00 0.000E+00 0.000E+000c 0.000c+oo 9.oo0g+oo e.oco4+ro 0.000**ce e. cost +oo s.ooe p0o

0. con 5.209E-05 4.306E-08 3.573E-08 3.013E-08 2.528E-05 MSN 6.9 31 E-ca.i.227 E-08 7.4 53C-a;8 ~.29 0E-08 0.000E+00 0.000E+00 0.000E*00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000g+os 4.485E-08 M

1.232E-000E+00 MNH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.00ct+00 0.000E+00 0.000E+00 0.000E+00 0.000E 3

NH 0.000E*00 0.000E+00 0.000E+00 C.000E+00 0.00GE+C0 0.000E+00 0.000E+00 0.000E+00 0 MKH 2.747E-08 1.887E-08 1.405E-08 9.021E-09 6.5C4E-D? 3.018E-09 4.047E-09 3,369E-09 2.869E-09 2.490E-09 2.190E-09 M

2.014E-08 1.272E-05 3.%6E-09 5.368E+09 3.618&Of 2.757E-09 2.163E-09 1.739E-09 1.469E-NME 2.111E-05 1.311E-08 9.129E-09 5.375E-09 3.6Mt-09 2.703E-09 2.104E-09 1.700E-09 1.410E-09 NE ENE 1.771E-08 1.078E-08 7.420E-09 4.310E-09 2.91's t-0,9 2.144E-19 1.s42E-09 01st-ce s.saat-10 7.Os,E-10 a.0ter-lo s.es08-0, 2.rgar-c i.es0E-Oe 3 242r-00

.168E-09 9.722E-10 a.267E-10 7.129C-10 E

s.350-Osa.2},SE-09,4.02aE-0,5.27sE-09,2.474E-091.a40E-091.440E-09 I.3402-Da s.s t-0 3.5072-0 1.907 E-08 1.259E-08 9.117E-09 5.633E-09 3.955E-09 2.987E-09 2.367E-09 1.941E-09 1.630E-09 esg w

SSE VEMT AMD BUILDIMO PARAMETER 5s REP. MIND HEIGHT (METERS) 71.3 RELEASE HEIGHT (METERS) 73.10 DIAMETER (NETER5) 1.14 BUILDING HEIOMT (MET ERS) 31.4 EXIT VELOCITY (METERS) 18.21 BLDO. MIN.CRS.5EC. AREA (59. METERS) 2000.0 MEAT EMISSIOM RATE (CAL /SEC) 0.0 ALL ELEVATED RELEASES.

in sectors WSW through N are not valid. Refer to note at the end of Table 1.3.

OD0589-1333A-BA01-BA02 Data N N'

m___

P P P tD o m a n c e P e a c o m unconoooucoqMMMe O

f i l$+04++ 0 0 s I l l t i

e WWWWWWWWWWWWWWWW 9

4 9 4 c o no o O Nte m ek t)

O o H e o p e p o n e M P W &A N D 1

W e M o p o. G. e. o O W N M M O. N.M.

e e e.

e e e e e e j

MMM O o M Oo o NMN eN WM -

e n

4 4 e

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m o WMo o o N oo o NW ON eMt 4

ym O eNAcceOOONeofMNW p

y M M e.f o o N. O. O. o M N N M c M. e e

e e e e e e o e e e

g y i

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VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision S EFFLUENT T/S REQUIRED DOCUMENTS TABLE 1.3 Page 31 of 94 A.

OFFSITE DOSE CALCULATIONS U5NRc CDtWUTE5f GLDE - X00DC% VERSION 2.0 RUN DATES 09-41-90 i

meum 810 ROCK POINT X00D0082 num USING 01/01/84 - 12/31/88 MET DATA numa ELEVATED RELEASE - 240' STACK 2.260 DAY DECAY.

UNDEPLETED AN*tUAL AVC*CE CHI /O (SEC/ METER CUBED)

DISTANCE IN MILES FROM THE SITE SECTOR 0.250 0.500 0.750 1.000 1.910 2.006 2.500 3.000 3.500 4.000 4.500 5

1.330E-08 1.967E-08 2.096E-08 2.541E-08 3.229E-08 3.331E-05 3.177E-08 2.945E-98 2.704E-08 2.477E-08 2.273E-ca SSW 6.337E-09 1.407E-08 1.575E-08 1.881E-08 2.345E-08 2.409E-08 2.294E-08 2.124E-08 1.948E-05 1.783E-08 1.634E-ca SH 6.1872-09 7.490E-09 7.698E-09 1.066E-08 1.589E-08 1.742E-08 1.712E-08 1.413E-08 1.496 E-08 1.379E-08 1.271E-Os H5W 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E400 0.000E+00 0;00CE+00 N

0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0J 0.000E*00 0.000E+00 0.000E*00 0.000E+00 0.000E+00 0.000E+0c HMH 0.000E+00 3.200E-44 9.545E-30 7.079E-22 2.586E-15 3.519E-12 4.562E-11 3.599E-10 1.403E-09 3.615E-09 7.179E-09 NH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.CCOE+00 MHH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+C0 N

0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.C00E+00 0.000E+0C HNE 6.340E-09 1.115E-08 2.299E-08 3.365E-08 4.491E-08 4.612E-08 4.361E-08 4.011E-08 3.659E-05 3.336E-08 3.048E-08 NE 1.007E-08 2.WE-08 3.776E-08 4.595E-08 4.885E-08 4.447E-08 5.899E-08 3.401E-08 2.979E-08 2.6'AE-08 2.340E-08 ENE 1.835E-08 3.843E-08 4.690E-08 5.302E-08 5.431E-08 4.864E-08 4.219E-US 3.650E-08 3.177E-05 2.788E-08 2.469E-03 E

1.792E-08 4.502E v5 5.252E-08 5.464E-08 5.120E-08 4.402E-08 3.732E-08 3.180E-08 2.738E-08 2.383E-08 2.096 E-08 E5E 1.703E-05 3.884E-08 4.295E-08 4.329E-08 3.957 E-08 3.379E-08 2.857 E-08 2.431C-05 2.092E-08 1.820E-08 1.600E-ca SE L.562E-08 3.395E-08 3.454E-08 3.499E-08 3.410E-05 3.043E-08 2.650E-05 2.304E-08 2.014t-08 1.775t-08 1.377E-cs SSE 1.237E-08 2.731E-08 2.896 E-08 3.249E-04 3.695E-04 3.5E5E-08 3.284E-08 2.955E-08 2.650E-04 2.341E-04 2.149E-05 ANMUAL AVERACE CMI/O (SEC/ METER CUBED)

DISTANCE IN MILES FROM THE SITE SECTOR 5,000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 5

2.092E-08 1.455E-08 1.089E-08 7.017E-09 5.059E-09 3.894E-09 3.131E-09 2.596E-09 2.203E-09 1.903E-09 1.e68 E-09 SSH 1.503E-08 1.042E-05 7.772E-09 4.987E-09 3.586E-09 2.75%E-09 2.210E-09 1.829E-09 1.550E-09 1.337E-09 1.170E-09 5H 1.174E-08 8.221E-09 6.159E-09 3.953E-C? 2.840E-09 2.1765-09 1.742E-09 1.458E-09 1.216E-09 1.046 E-09 9.136E-10 0.000E+00 0.000E+00 0.000g*+00 0.000E+00 0.0GOE*00 0.000E000 0.000E+00 e.000E+00 0.000E+00 0.000E*00 0.000E+00 ksH 0.000E*00 0.000E+00 0.000c 00 0.000E+00 0.000E+0c 0.900E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 N

NNH 1.198E-08 4.284E-08 6.470E-08 7.260E-03 6.166E-08 4.852t-GE I.733E-04 2.860E-05 2.197E-08 1.496E-08 1.317E-08 NH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0C 0.690E+00 0.000E*00 0.000E+00 0.000E+00 0.000E+00 MMH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0D 2.esGE+00 0.000E+00 0.000E+00 0.000E+00 N

0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+eG 0.000E+00 0.000E400 0.200E*00 NME 2.796E-08 1.924E-06 1.433E-08 9.202E-09 6.626E-09 5.102E-09 4.106E-09 3.409E-09 2.897E-69 2.307E-09 2.200E-09 HE 2.099E-08 1.337E-08 9.485E-09 5.725E-09 3.965E-09 2.966E-09 2.332E-09 1.899E-09 1.587E-09 1.354E-09 1.173E-09 ENE 2.205E-08 1.384E-08 9.719E-09 5.784E-09 3.969E-09 2.947E-09 2.304E-09 1.866E-09 1.553E-09 1.319E-09 1.139E-09 E

1.861E-05 1.147E-08 7.960E-09 4.483E-09 3.202E-09 2.371E-09 1.849 E-09 1.495E-09 1.242E-09 1.05?E-09 9.081E-10 ESE 1.421E-08 8.755E-09 6.076E-09 3.573E-09 2.444E-09 1.811E-09 1.412E-09 1.142E-09 9.489E-10 8.049E-10 6.940 E-10 SE 1.414E-08 8.979E-09 6.349E-09 3.816E-09 2.C?8E-09 1.969E-09 1.544E-09 1.255E-09 1.046E-09 8.903E-10 7.697E-10 SSE 1.951E-08 1.293E-08 9.377E-09 5.803E-09 4.077E-09 3.078E-09 2.437E-09 1.995E-09 1.675E-09 1.443E-09 1.246E-09 V8MT AND BUILDING PARAMETER 5s RELEASE HEIGHT (METERS) 73.10 REP. HINO HEIGHT (METERS) 71.3 DI AMET ER (METER 5) 1.14 BUILDING MEIOMT (METER 5) 31.4 EXIT VELOCITY (METER 5) 18.21 BLDO. MIN.CRS.3EC. AREA (50. METERS) 2000.0 MEAT EMISSICM RATE (CAL /3EC) 0.0

.% L ELEVATED RELEASES.

OD0589-1333A-BA01-BA02 Data in sectors WSW through N are not valid. Refer to note at the end of Table 1.3.

VOLLHE 25 BIG ROCK POINT RADIOLOGICAL Revision S EFFLUENT T/S REQUIRED DOCUMENTS TABLE 1.3 Page 32 of 9t.

A.

OFFSITE DOSE CALCULATIONS USNRC COMPUTER t;0DE - X00D00, VERSION 2.0 RUN DATE: 09-d-9 0 I

i acca BIO ROCK POINT XOQD0Q82 umm USIMO 01/01/84 - 12/31/88 MET DATA munu ELEVATED RELEASE - 240' STACK HO DECAY, UNDEPLETED CHI /Q (SEr/ METER CUSED) FOR EACH SEGMENT SEOMENT BOUNDAMIES IN MILES FROM THE SITE DIRECTION

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

2.274E-08 3.134E-08 3.142E-08 A.705E-08 2.285E-08 1.453E-08 7.186E-09 4.062E-09 2.749E-09 2.044E-09 5$H 1.680E-08 2.280E-08 2.270E-08 1.950E-08 1.645E-08 1.042E-08 5.125E-09 2.887E-09 1.950E-09 1.448E-09 SH 9.009E-09 1.548E-08 1.6902-05 1.496E-08 1.230E-08 8.213E-09 4.071E-09 2.290E-09 1.542E-09 1.142E-09 H3H 0.000E+00 0.000E+00 0.000E+0e 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 H

P 000E+00 0.000E+00 0.000E+0e 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 HMH

. 2 'i7 E-22 7.157E-13 1.736E-10 2.173E-G9 9.039E-09 5.902E-08 1.048E-07 9.731E-08 7.726E-08 6.117E-DE NH v.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0 JOE +00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NNH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 N

0.000E+00 0.000E+0C 0.00CZ+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NME 2.549E-08 4.303E-08 4.301E-na 3.651E-08 3.055E-08 1.916E-08 9.352E-09 5.253E-09

3. 547 E-09 2.635E-09 dE 3.852E-08 4.6 37 E-08 3.860E-08 2.981E-08 2.351E-08 1.348E-08 5.901E-09 3.087E-09 2.00ZE-09 1.446 E-09 ENE 4.782E-08 5.168E-08 4.183E-08 3.185E-05 2.486E-08 1.402E-08 6.015E-09 3.104E-09 1.999 E-09 1.437E-09 ~<

E 5.195E-08 4.895E-08 3.709E-08 2.748E-08 2.113E-08 1.167E-08 4.904E-09 2.515E-09 1.618E-09 1.163E-09 E3E 4.?31E-08 3.797E-08 2.842E-08 2.101E-08 1.614E-08 8.920E-09 3.749E-09 1.925E-09 1.239E-09 8.915E-10 SE 3.476E-08 3.282E-08 2.635 E-08 2.023E-08 1.592E-08 9.115E-09 3.994E-09 2.099E-09 1.367E-09 9.908E-10 53E 3.029E-08 3.562E-E8 3.250E-08 2.653E-08 2.164E-08 1 300E-08 5.993E-09 3.233E-09 2.131E-09 1.555E-09 AVERA!E EFFECTIVE STACK HEIGHT IN METERS FOR EACH SEOMENT DIRECTION

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

8.463E+01 8.464E+01 8.464E+01 8.464E+01 8.464E+01

^ 544E+01 8.464E+01 8.464E+01 8.464E+01 8.464E+01 SSH 8.623E+01 8.624E+01 8.624E+01 8.624E+01 8.624E+01

.6%*E+01 8.624E+01 8.624E+01 8.624E+01 8.624E+01 SH 8.711E+01 8.712E+01 8.712E+01 8.712E+01 8.712E+01 L. H ; c +01 8.712E+01 8.712E+01 8.712E+01 8.712E+01 HSH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C 4 % ?.+ 0 0 0.000E+00 0.000E+00 0.000E+00 0.000E+00 L M

0.000E+00 0.000E+00 0.000E+00 0.000E+00 e.900E+00 0.

T E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0c ;

HHH 3.817E+02 3.8 53E+ 02 3.853E+02 3.853E+02 5.953E+02 3.bs3E+02 3.853E+02 3.853E+G2 3.853E+02 3.853E+0Z ~

NH 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E*00 0.000E+00 0.000E+00 0.000E*00 ENH 0.000E+00 0.000E*00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 N

0.000E+00 0.000E*00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

0. 0 0 0 E+ 00 0.000E+00 0.000E+00 0.000E+00 NME 8.273E+01 8.273E*01 8.273E+01 8.273E+01 8.273E+01 8.273E+01 8.273E+01 8.273E+01 8.273E+01 8.273E+01 N E.

8.410E*01 8-

'tE+01 8.411E+01 8.411E+01 8.411E+01 8.411E+01 8.411E+01 8.411E+01 8.411E+01 8.411E+01 ENE 3.588E+01 8.

E+01 8.590E+01 8.590E+01 8.590E+01 8.590E+01 8.590E+01 8.590E+01 8.590E+01 8.590E*01 E

8.708E+01 8.

4E+C; 8.710E+01 8.710E+01 8.710E+01 8.710E+01 8.710C+01 8.710E+01 8.710E+01 8.710L 01 ESE 8.754E+01 8.756E+P 8. 754 E+ 01 8.756E+01 8.756E+01 8.756E+01 8.756E+01 8.75fE*01 8.756I+01 8.756E+01 SE 8.824E+01 S.827E*01 8.827E+01 8.827E+01 8.827E+01 8.827E+01 8.827E+01 8.827E+01 8.827E+01 8.6+?E+0 SSE

8. 556 E+ 01 8.557E+01' 4.557E+01 4.557E+01 8.557E+01 8.557E+01 E.557E+01 8.557E+01 4.557E+01 8.557E+01 OD0589-1333A-BA01-BA02 Data in sectors WSW through N are not valid.

Refer to note at th end of Table 1.3.

d 4

4 VOLUME-25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 33 of 94 A.-

0FFSITE DOSE CALCULATIONS TABLE 1.3 NOTES Big Rock Point gathers meteorological data from sensors mounted on 'the 73 meter stack. A wind speed and wind direction sensor i s mou:.< ed - i nto the prevailing wind direction.

Because of interference to the wind flow by the stack when winds are from the 71* to 159' sector (flowing towards Lake Michigan),

the met eorological data recorded in these sectors are considered invalid.

For dose calculational purposes, this effectively invalidates six-(6) sectors (WSW, W, WNW, NW, NNW. and N).

Therefore zerca.are recorded in Table 1.3 for these sectors, llowever, the program which calculates the annual average Chi /Q i

requires input of the full years met data.- Any data recorded for these six sectors are input in the WNW sector-to satisfy the program.

Values of Chi /Q-4 listed in the-WNW sector are invalid.

During emergencies with wind directions into the above six sectors;- The dose assessor is directed to alternate meteorological information by emergency procedures.

4 l

i OD0589-1333A-BA01-BA05

t VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 34 of 94 l

A.

OFFSITE DOSE CALCULATIONS 1

TABLE 1.4 1991 BIC ROCK POINT LAND USE CENSUS REPORT I

Dist ance to the nearest residence, garden, mili cow, beef cow and goat in each sector.

Sector Residence Carden DahCy Beef Cattle Coat WSW 2.5 mi-

>5 mi-

>$ mi

>5 mi

>5 mi SW l.1'mi

>5 mi

>5 mi

>5 mi

>5 mi SSW l.3 mi 2.1 mi

>5 mi

>5 mi

>5 mi b

S 1,9 mi

>$ mi

>5 mi 2.5 mi

>5 mi l

SSE 1.7 mi 1.8 mi 3.5 mi 3.5 mi

>5 mi g

i j

l SE 1.7 mi 1.7 mi' 4.5 mi 2.0 mi 4.0 mi-

}

ESE 1.5 mi

-1.8 mi 2.6 mi-2.6_mi-

>5 mi E

1.4 mi 2.5 mi

-2.5 mi.

2.5 mi

>5 mi ENE 2.3 mi

>5 mi

>5 :ai

>5 mi

>5 mi i

e i

n I

i i

5 i

i.-

i 4

i d

e

\\

i s

OD0589-1333A-BA01-BA05 i

. __,,_._. ~.-._.-. - ~.._ _. _ _ _. _,. _.,_ _.,-,- _..-..

.. -. - - =,..

~.

YOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFl.UENT T/S REQUIRED DOCUMENTS Page 35 of 94 A.

OFFSITE DocE-CALOULATIONS

+

l TABLE 1.4a j

1992 BIC ROCK POINT CASP/R INPUT PARAMETERS Critical Receptors 1

X/Q X/Q Decay Distance X/Q Decry and Dep D/Q

(

Location Sector (miles)

(sec/m')

(sec/m')

(sec/m')

(1/m')

Residence /Carden E

1.40 5.20E-08 5.20E-08 5.10E-08 6.80E-10 J

Site Boundary E

0.57 4.70E-08 4.60E-08 4.60E-08 1.30E-09 (1) Beef Cattle E

2.50 3.80E-08 3.70E-0E 3.60E-06 3.50E-10

^

l Dairy Cow E

2.50 3.80E-08 3.70E-08 3,60E-08 3.50E-10 l

Coat SE.

4.00 1.80E-08 1.806-08 1.70E-08 9.90E-11 1

(1) NOTE:

Although the beef cattle location is closer in the SE sector (2.00 miles) than in the E sector (2.50 miles), the X/Q for the.

E sector at 2.50 miles is greater at.3.80E-08 than in the SE sector at i

2.00 miles which is 3.10E-08.

Thus the E sector at 2.50 miles has the more limiting criteria and will be used for the critical receptor location.

3 j

^

}

I 4

OD0589-1333A-BA01-BA05 n

--n

,-___.____m.._.

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

1 i-

--VOLUME 25 BIC ROCK POINT RADIOLOCICAL Revision 8 j

EFFLUENT T/S REQUIRED DOCUMENTS Page 36 of 94 A.

OFFSITE DOSE CALCULATIONS I

j DOSE FACTORS FOR SUBHERSION IN NOBLE CASES

• i-Table 1.5 I

I DFB DFY' DFS DFB' i

Kr-85m 1.17(+3)'

l.23(+3) 1.46(+3) 1.97(+3).

Kr-85 1.61(+1)'

l.12(+1) 1.34(+3) 1.95(+3) i Kr-87 5.92(+3) 6.17(+3) 9.73(+3) 1.C 3 ( + 4 )

4 1

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

l l

Kr-89

1. 66 ( + 4 )

1.73(+4) 1.01(+4) 1.06(+4)

I j

Xe-131m 9.15(+1) 1.56(+2) 4.76(+2) 1.11(+3) i Xe-133m 2.51(+2) 3.27(+2) 9.94(+2) 1.4 8( + 3 )

j Xe-133 2.94(+2) 3.53(+2) 3.06(+2) 1.05(+3) j Xe-135m 3.12(+3) 3.36(+3) 7.11(+2) 7.39(+3) l Xe-135 1.81(+3) 1.92(+3)

'l.86(+3) 2.46(+3)

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

1. 2 7 ( + 4 )

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

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

mrem /y per pCi/m' f-2.

mrad /y per pCi/m' l

l 3.

1.17(+3) = 1.17 x 10' i

l

• Dose f actors f or exposure to a semi-infinit e -cloud of noble gases. Values l

were obtained' f rom US NRC Regulatory Guide 1-109, Revision :1 (October 1977).

i l.

i l

i OD0589-1333A-BA01-BA05 i

..w.

. av

.- _. -.. - ~..

u

., ~....,

..w,x u

m.

.. ~. _.....

...,;.._.n

... ~. -.

. ~ _. -.,

W 3

VOLUME 25 BIC ROCK PolNT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 37 of 94 l

A.

OPPSITE DOSE CALCULATIONS STABLE ELEMENT TRANSFER DATA Table 1.6 Fm - Hilk (d/L)

Fm - Hilk (d/L)

Biy i

(Cow)

(Coat) l'f - He a t (d/kg)

Veg/ Soil Element H

1.0E-02.

1.7E-01 1.2E-02 4.8E-00 j

C 1.2E-02 1.0E-01 3.lE-02 5.5E-00.

Na 4.0E-02 4.0E-02 3.0E-02 5.2E-62 i

P 2.5E-02 2.5E 4.6E-02 1.1E-00 i

Cr 2.2E-03 2.2E-03 2.4E-03' 2.5E-04

}

Mn 2.5E-04 2.5E-04 8.0E-04 2.9E-02 i

Fe 1.2E-03 1.3E-04 4.0E-02 6.6E-04 l

Co 1.0E-03 1.0E-03 1.'3E-02 9.4E-03 l

Ni 6.7E-03 6.7E-03 5.3E-02 1.9E-02 Cu 1.4E-02 1.3E-02 3.0E-03 1.2E-01

}

Zn 3.9E-02 3.9E-02 E.0E-02 4.0E-01 Rb 3.0E-02 3.0E-02 3.lE-02

'1.3E-01 i

Sr 8.0E-04 1.4E-02 6.0E-04 1.7E-02 1

Y 1.0E-05

'l.0E-05 4.6E-03 2.6E J l

Zr 5.0E-06 5.0E-06 3.4E-02 1.7E-04 Nb 2.5E-03 2.5E-03 2.EE-01 9.4E-03 j.

Ho 7.5E-03 7.5E-03 8.0E-03 1.2E-01 Tc 2.5E-02 2.5E-02 4.0E-01 2.5E-01 Ru 1.0E-06 1.0E-06 4.0E-01 5.0E-02 Rh 1.0E-02 1.0E-02 1.5E-03 1.3E+01 4

1 Ag 5.0E-02 5.0E-02 1.7E-02 1.5E-01 Te 1.0E-03 1.0E-03 7.7E-02 1.3E-00 I

0.0E-03 6.0E-02 2.9E-03

.2.0E-02 f

Cs 1.2E-02 3.0E-01 4.0E-03 1.0E-02 l

Ba 4.0E-04 4.0E-04 3.2E-03 5.0E-03 l.a 5.0E-06 5.0E-06 2.0E-04 2.5E-03 i

ce 1.0E-04 1.0E-04 1.2E-03 2.5E-03 Pr 5.0E-06 5.0E-06 4.?E-03 2.5E-03 Nd 5.0E-06 5.0E-06 3.3E-03.

2.4E-03 W

5.0E-04 5.0E-04 1.3E-03 1.8E-02 s

Np 5.0E-06 5.0E-06 2.0E-04 2.5E-03 i

t l'

i I.

i e

i OD0589-1333A-BA01-BA05 i

i

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 38 of 94 A.

OFFSITE IOSE CALCULATIONS TABLE 1.7 I m t>T1cw Dost tac!Vt1 Tot INTAN,T DaI't in PCI INKAltDi 3WLIDE ICK!

LIV 11t T.800T TWY1totD K1DNIT 11 %

cf.LLt a

3 No DATA 4.62E47 a.62E 07 4.62t47 4.62t 07 4.62E47 4.62I 07 C '14 1.89t 45

3. 7 9t.M 3.79E 06

3. 79 E-M 3.79t46 3.79t M 3.79t.06 ftA 26

7. ME *M 7.M E-06 7.HE 06 7.%E46 7.%E46 7.Mt46 7.54t 06 F 32 1.45E $3 8.03E 05 5.53E.05 No DAu m DATA NO DATA 1.15t.0$

CR 51 NO DATA No DATA

6. 39 E.08 4.11Z-06 9.65t49 9.17E 46 2.55t 07 MH $4 No DATA 1.811 0?

3.56E-06 No DATA 3.56t 46 7.1'E 44 5.ME 06 NN $6 No DATA 1.10E-09 1.58E-10 No DATA 7.86t-10 8.95t 06 5.12t.05 I"E 55 1.61E 05 8.39E C4 2.38E 06 NO DATA NO DAIA 6.211 05 7.82E 07 TI $9 9.691 06 1.68E-05 6.77t 06 NO DATA NO DATA

7. 25t44 1.77t45 CO $8 NO DAu 8.71E*07 1.30E 06 NO DAu M0 LAIA 5.55E M 7.95t.06 CO 60' NO DAu 5.73E-06 8.41I N N DAu No DATA 3.22I-03 2.28t.0$

ar! 63 2.62E M 1.46t 05 8.29E 06 No DAu No DAIA 1.49t M 1.7Nt-06 N'1 65

, 1.711 49 2.03E 10 8.19E 11 NO DATA NO DAIA 5.80546 3 5&r43 CU 64 NO DATA

1. 34 E,- 09 5.53E 10 No DATA 1.64t-09 6.64t 06

.Igo7t.0$

IJE 65 1.18E45 4.47E 45 2.22I 4 5 MO DAIA 2.321 05 6.62144 3.67145 l

..............o................................'..................................:.~............

l LN 69 3.85E*11 6.91E-11 5.13E 12 NO DATA 2.87E 11 1.05t46 9.L&t-06 l

ER 83 NO DATA NO DATA 2.72E 07 NO DAu NO DAIA 30 DAu Lt 1 24 SA $4 NO DATA No DAH

2. 86 E-07 No DATA NO DAIA MO DAu

?.I t 24 3R 85 No DAu No DATA 1.46t 04 NO DATA NO DATA NO DAIA LT !.24 u 86 No DAu 1.36E M 6.30E-05 NO DAu No DAIA No DAIA 2.171 06 u 88 NO CAIA 3.96E-07 2.05E 07 NO BAN NO DAIA DO DAIA 2.L21 07 8.3 89 No DATA

2. 2,9 E-07 1.67 E-07 No DAu No DAIA NO DATA 4,87t.08 51 89 2.86E-M NO DATA 8.15E-06 NO DATA NO DAIA 1.45t.03 4.57t45

$1 90 2.92I-02 NO DATA 1.85E-03 NO DATA N0 DATA 8.03t43 9.36t.cs SR 91 6.83E 08 NO DAIA 2.67E49 NO DATA M0 DAIA 3.76E45 5.2&t45

$1 92 7.50E49 NC DATA 2.79E-10 NO DAu NO DnIA 1.70E-05 1.00E-04 Y 90 2.35E46 NO DATA 6.30E-04 NO DATA NO DATA 1.92t-06 7.43E.0$

Y 91m 2.91I 10 NO DATA 1.90E 12 NO DAu No DAIA 1.99t 06 1.68I-0 6 Y 91

&.20T M NO VAIA 1.12E 05 NO DAu NO DATA 1.75E-03 5.02E-0$

T 92 1.17 t-04 NO DATA 3.29E 10 NO DAu NO DATA 1.75t45 1,gt.c3

.................... ~............... ~......................................................

OD0589-1333A-BA01-BA02

VOLUME 25 BIC ROCK POINT RADIOLOCICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 39 of 94 A.

OFFSITE DOSE CALCULATIONS TABLE 1.7 LWAt>T1ou tost FACTtts it* IMA7tT (NRIM PIk PCI IWAUIQ g ttog 30 art uvrR T.600T TW10tD titHIT tl/M Cf.tif Y 9) 1.07t47 W3 DATA 2.91I-09 NO DATA NO DATA 5.461-05 1.191 M IR 95

• 8.24E-05 1.99E.05 1.=5E-05 M0 DATA 2.221 05 1.25t-03

1. 55t 45' 11 17 1.07t 07 1.83t-08 8.%t49 NO DATA 1.85t44 7.88145 1.00t.M p 95 1.121 05 4.59t 06

2. 70t-06 No DATA 3.371-04 3.42E-M 9.05t-06

• 1.16t*07 2.31E*06 MO DATA 1.89047 9.6 X-05 3.64t 45 30 99

.NO DATA TC 99u 9.96E 13 2.06t.12 2.66E.11 M0 DATA

'. 22t-u 5.79147 1.65t46 3t101 6.65E 14 5.88 t-14 5.80t.13 P0 DAIA 6.99t.13 4.17t47 6.03t47 RU103 1.L&t 06 NO DATA 6.85t47 30 DATA 3.01E.M

3. 94t.M 1.15145 tr105 8.741 10 No DAIA 2.93t.10 NO DATA 6.62C 10 1.12I.05 3.66t45 En06 6.20E45 It) DATA 7.77E46

.NO DAIA 7.61I-0 5

4. 26t-03 1.17t-M l

Acnos 7.13t C6 5.16t.06

3. 571.M NO DATA 7.80E.M 2.62Z43 2.Xt45 TI125a 3.60t44 1.42E.M 4.70E47 1.16t-M po LAIA 3.111.M

9. 221-M l

l TU 27a 1.19t45 4.93t46 1.44t46 3.68t44 1.64t45

9. 37t-04 1.95t45 l

n127 1.59I 4 9 6.81I.10 3.49,E.10 h 32t49 3.47t 09

7. 39t.M 1.76t45" l

T1129s 1.011 05 4.35E46 1.59t46 3.911 06 2.27t-05 1.20E 03 4.93t-05

......................................,......................s...................................

11129 5.631 11. 2.68t-11

1. XI.11 6.82E 11 1.25t-10 2.14t46 1.84t45

~

T1131m 7'.62I 06 3.9 3t

• 08 2.59t.06 6.38t.06 1.89t 47 1.471.M 8.511 05 II1n 1.24t.11 5.87E.12 3.571 12 1.131 11 2.85t.11 1.47t46 5.471 M TT132 2.66147 1.692-07

1. 26t-07 1.991-07 7.392 07 2.4X.M 3.15t4$

I 130 6.54t.M 9.91I.M 3.98I.M 1.1A143 1.011 05 H0 DAIA 1.47t46 1 131 2.71I 4 5 3.17 E-05 1.40t-05 1.ME-02 3.70E-05 po DAIA 7.56.07 I 132 1.21I 4 4 2.531-M 8.99E-07 1.211 44 2.82E46 P0 DAIA 1.34 I-04 1 133 9.L6t M

1. 37 t-05

4. cot M 2.54t43 1.60t.05 WO DAIA 1.54t-M 1 134

6. Sat 47 1.%E M h.75t47 3.let.05 1.49t-06 M0 DAIA 9.211 47 I 135 2.76t46 5.43t.M 1.9st-M 4.971-04 6.05t44 No DATA 1.311-06 C51%

2.83t M 5.021-M 5.32t 05 M0 DAIA 1.34t b6 5.691 05 9.53t47 CS136 3.45t45 9.61t-05 3.76t-05 MO DAIA 4.03E 05 8.40E.06 1.02146 C5137 3.91144 4.37 t-M

3. 25t-05 WO DAIA 1.23E.M 5.09t.05 9.5 3t-07 C$138 3.611 07 5.58 t.07 2.nt47 30 DAIA 2.9X.07 4.671 08 6.261 07 EA139 1.06I41 7.03t.13 3.07t.11 30 DAIA 4.22 13 4.251 46 3.64145

......m g

4 OD0589-1333A-BA01-BA02

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 40 of 94 A.

OFFSITE DOSE CALCULATIONS TABLE 1._7 i

IMA1AT10st Do$Y FACTis.3 Tot IMTAxt fMP,LM PER PCI IMAlID) kW11DE SME LIVER T. BODY TWtotD KIIWEY IfMC CI LLI 3Auc 4.Cct 05 4.00E 04 2.07E 06 NO DATA 9.51!-Of 1.}LE03 2,74E 0)

BA161 1.12E 10 7.70E u 3.55E*12 NO CATA

4. 64 t * %

2.12E 04 3.31E 04 BA142

2. 84t.11 2.36E 16 1.60E.12 NO PAM

1. 34 E.M 1.11E 06 4.15! 07

.............................................................................................. 3..

t.Au0 3.611 07 1.41E 07 3.68E*06 NO DAIA N DAM

1. 20E.M 6.06 E-05 LAuf 7.36t 10 2.69E 10 4.&&E.11 NO DAIA NO DAu 3.87E-04 4.251 05 Crut 1.tt: 05

' 1.19E 05 1.42E 06 No CAIA 3.731 06 3.69E-04 1.54E C$

1

< tit) 2.091 07 1.34E 07 1.5tE 04 NO DAIA 4.02 04

'8.30E.03 3.55t 0$

CE144 2.;tt 03 8.65E M 1.26E.M NO DATA 3.841 M 7.03E-03 1.ME M PR163 1.0C 3.7kE*06 4.19E-07 NO DAIA 1.41E 04 3.0lE.M 2.64t.0 f,...............E 05.................................................................................$

F RIt.4 3.421 11 1.32E 11 1.72E.12 No DAIA 4.30E.12 1.15E-04 3.04E.M KD147 5.67E 06 5.41E 06 3.57E-07 10 DATA 2.25E-06

2. 30E.M 2.22 05 k 107 9.26t 09 4.L4E 01 2.23E-09 NO DATA 30 DAM 2.43E.0$

..........................................................................................1.34!-0$

N7239 2.65t 07 2.37E.04 1.34E-04 No DAIA 4.73E Oc 4.25E-0$

1.7st-c5 l

OD0589-i333A-BA01-BA02

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 41 of 94 A.

OFFSITE DOSE CALCULATIONS TABLE 1.7 ImuT1on tost rAcTras tot Cuto

( mtat PER K 1 I W A113) svc11DE SmE Livt1 T.BOCT T M OID UtwtY 11NO C1. tit __

g 3

m DMA 3.04t47 3.M E.07 3.04E.07 3.ME-07 3.04E41 3.Mt47 C 14 9.70E 06 1.821-W 1.8 2E.M 1.82E M 1.82E M 1.82I M

1. 8 2E-M kA 24 4.35t M 4.35E M 4.35E M 4.35E 04 4.35E46 6.356M 4.35E46 F 32 7.Mt.M 3.MI45 2.67E-05 No DAH NO DAu NO DATA 1.14t 43 Ot $1 No DA u po DAIA 4.17E 08

• 311 48 6.57E.09 4.59E.M 2.91E47 yat 54 NO DAu 1.16E45. 2.57E-06 NO DATA 2.71146 4.261.M 6.19E.04

..................................................................................J...............

tct 56 NO DAIA 4.48t*10 8.43E.11 NO DATA 4.52E 10 3.55E M

3. 3)E-05 FI $5

1. 2tI-05 a.soE-M 2.10E.M 80 DATA NO DAu 3,00t.05 7.75E-C7 IT. 59 5.59t-04 9.MI-06 4.f.1I M NO DATA P0 DATA 3.43E M 1.91I-05 I

CO $8 MO DATA 4.791-07 8.55E47 NO DATA P) DATA 2.99E-M 9.29E.M CO 60 No DATA

3. 55t.M 6.12E.M NO DATA NoDMA 1,911 03 2.60E 45 l

F1 63 2.22I-M 1.25E-05

7. 5 6E.M No DATA M DAIA 7.431 05

1. 711.M K1 65 8.082-10 7.991 11 4."4E.11 No DATA NO DATA 2.2.1E.06 2.27E 45

.CU 64~

no DATA 5.393 10' 2.90E.10 NO DAIA 1.6,1E 49 2.59E-M

.9.92I-06 IX 65 1.15t-05 3.Mt45 1.90E 05 NO DAT&

1.93 45

2. 691.M 4.41I.C6 i

..........................................~..................................................

IJ 69 1.81I.11 2.61I.11 2.41I.12

0'r*CA 1.58E.11 3.t4E47

2. 75t.M 8x 83' 50 DAIA NO DATA

• 1.28E 07 NO DATJ NO B4D DO Mu LT E.26 3R 84 P3 DATA 50 MIA 1.44 E47 NO DATA NO DAH FC CATA LT E.24 81 85 M CAIA 30 CAR 6.8AE49 R0 DATA NO DAIA NO DAu LT E.24 R3 86 N0 DATA 5.361-05 3.09E-05 NO DAR WO DAIA NO DATA 2.16t.0(

u 68 m DAIA 1.511 07 9.90E.04 NO DAM NO DAIA No MIA 4.66t49 6.. ~..............................................

H $9 po DAu 9.331*08 7.85E44 NO DAIA NO DATA NO DATA

5. 11I-1 0

$R 89 1.6tI-M 30 DAIA 4.66E M 10 DAIA NO DAIA 5.83Z M 4.52I.05

$1t to 2.73E-02 30'DAIA 1.74E43 NO DAIA NO DATA 3.99143 9.28E-0$

51 91 3.tst-08 30 DAIA 1.24E-09 NO DATA 50 DA R 1.441.C5 4.70E-0$

SR 92 3.5AI49 F0 DAIA 1.42E 10 IC DATA NO dan 6.49t.M 6.55E-05 T 90 1.111-M 30 DAIA 2.99E44 NO DATA NO DAH 7.07E45

7. 24E.C3 T 91m 1.37E.10 NO DATA 4.idt-12 R DATA NO DAIA 7.60E 07

4. 64E-07 T 91 2.47E-M 30 DATA 6.59E-M M DATA WO DATA 7.102.M 4.97145 Y 92 5.5cE49 30 MIA 1.57d10 30 DATA 30 MT4 4.46146 ; 6.46E4$

OD0589-1333A-BA01-BA01

VOLUME ?$

BIC ROCK POINT RADIOLOGICAL Revision 8

~

EFFLUENT T/S REQUIPED DOCUMENTS Page 42 of 94 i

A.

OFFSITE DOSE CALCULATIONS 4

TABLE 1.7 1

i 1XRALATION DOSE FACKAS FOR CRID 09IM Pt.R PCI INRALID),

f NUct *DE BONE LIYE1 T. FJDT THYROID K1 TWIT LineC Cl lif_

b 7 13 5.06t48 m DATA 1.38t 09 80 DAIA No DAu 2.01I 4 5 1.05t-M 11 95 5.13E 45 1.1X.05 1.00t45 NO DAIA 1.612-05 6.02-M 1.65t45 In 97 5.07t-08 7.34t49 4.32I 09 MO DATA

! ?$t-C4 3.06t-05 9.49t 05 l

F3 95 6.35t46 2.L8t44 1.771-06 PO DATA 2.33t4(

1. 66t-M 1.00E-05 H) 99 tC DATA

.4.66t 08 1.13t 06 MO DATA 1.06t47 3.66t-05 3.41I 4 5 TC 99s

'4.81t*13 1.411 13 1.56t 11 No DATA 1.371 11

2. Sit 07

1. E-M TC101 2.19t 14 2.30t 14 2.91E 13 ' No DATA 3.921 13 1.38t-07 4.41t.09 W103' 7.55t-07 30 DATA 2.90E 07

, M0 DATA 1.901 M

1. 79t-M 1.21I -05 i

W105 4.132 10 30 CATA 1.50E 10-N0_ DATA 3.6 X 10 4.M 06 2.69045 w1M 3.66t45 to DAIA 4.57t46 NO DATA

~4.97E-05 3.87t 03 1.16E M Acuos 4.56t-M 3.06E 06 2.471 06 M0 DATA 5.74t M 1.441-0) 2.71I 4 5 Tn25e 1.82E46 6.29E-07 2.47t47 5.20E-07 No DATA 1.29t M 9.13t.M Tn27m 6.72E 04 2.31I 4 6

-8.16t 07 1.64t-04 1.72145.

4.00E M 1.1X45 fn27 7.49t.10 2.571-1D 1.65t*10 5.30t 10 1.912 09 2.ilt M 1.52245 i

T n29e 5.19t66 T.85E M 8.22t 47 1.711-06

• 1. 36t95

• 4.76t-M.

4.91I 05

.........,............... ~.. J.........................*.....................*....J...............

In29 2.64t 11 1.451 12 6.64t 12 1.93t-11 6.94t-n -

7.9X 07 6.)9E-M TQ na.

3.631 08 L60E 08 1.37t 08 2.64t-08 1.08E 07 5.541 05 -

8.31t.05 ft131

-5.871 12 2.28t42 1.78t 12 4.59t-32 1.511 n 5.55t 07 3.60t47 TEU 2 1.30t47 7.36t-08 7.12148 8.58t-od 4.191 07 1.021 M 3.721-05 1 D0 2.211 M 6.4R-M 2.28E 06

4. 9t E-M 4.61I 06 NO DATA 1.38I -06 1 131 1.WE45 1.)ct45 7.37E M 4.39t-03 2.1X 05 '

No DAIA 7.68147 I 132

- !.72I.0 7 1.10E46 5.01t47 5.23E-05 1.61E-04 30 DATA 4.65E-07 1 133 4.L81 On 5.411-06 2.08E-M

1. M E-03 9.1X 06 10 DATA 1.481-M I un 3.17t47 5.84t47 -

2.691 07 1.37245 8.921-07 M0 DATA 2.58t47 2 135 1.331 06

• 36t46

1.

• 2t44 2.14E-M -

3. 621-M F0 DAIA 1.20E-06 CSD4 1.76t M

4. 7 4-M '

6.07E45.

NO DATA

.8.93T 4$

3.27t 05 1.04t-06 CSU6 1.76t 0; 4.62t-05.

3.14t 05 NO DATA 2.58t 05 3.93E46 1.ut46

......................... ~......................................................................

C5137 2.45t 04 2.13144 3.47t45 NO DATA-7.4X45 2.811-C5 9.78t47 l

'C3134 1.71t47 7.27E47 1.50t 47' po DATA 1.68t47 1,84Z-04 7.29t,08 BAut 4.94t.18 2.642 13 1.45E 11 90 DAIA 2.1X 13 1.54Z-04 1.56t 05 1

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

OD0589-1333A-BA01-BA02-l

- ~ - - - _ -

VOLUME 25 BIC. ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 43 of 94 l

A.

OFFSITE DOSE CALCULATIONS-4 l

TABLE 1.7 l

t 1

1 11(KALAT10n tost FACTt*$ PCd Gita fMRIMPERPCIIt(F>1ED) pectfDE BOWE LIV n T.800T TWYRotD Kit #ET II'NC C! tt!

t 1A140 2.rCE 05 1.75E 08 1.17E-M NO DATA 5.71I-09 4.711 04 2.75E 05-LA141 5.291 11 2.95E 14 1.72I-12 NO DATA:

2.56E*14 7.89t-07 7.44E-08.

SA142

1. 35t-11 9.73E 15 7.54E 13 No DAIA 7.87t 15 4.44E-07' 7.41I.13 i-LA140

1. 74't-07 i %E*08 2.04E-04 NO DATA NO DATA 4.94E-05 6.10t-05 1A142 3.50t 10

,'1.11E 10 3.49E-11 NO DAIA

' N0 DATA 2.35E M 2.05E 05 CI141 1.06t 05 5.28E 06-7.8 3E-07 NO DATA 2.31I M 1.47E*04 1.53E-05 4

'CE143 9.891 08 5.37E-08 7.77E-09 No DAIA.

.2.262 08 3.12I 05 3.44E-06 CI144 1.8 2 03 5.72E-M 9.77E-05 No DATA

. 3.17E-M 3.2X 03 1.0$E-04 FA143 4.99t M -

1.5CE-M 2.47E*07 EO DAIA 8.11I-07_'

1.17E-04 2.63E 05 PR1*4 1.611 11

4. HE 12 8.10E 13 NO DAIA 2.64t*12-4.23E-07 5.32E-08 l

ND147 2.9:t M 2.36E M 1.84E 07 No DATA 1.30E M

- 8.871 05 2.22Z-05 W 187 6.41I 09 2.61E-09 1.17E-09 NO DAZA NO IMIA.

' 1.11I 05 2.46E-05 l

FP239 1.26E 07 9.%r-09 6.35I 09 30EWA 2.6X M 1.57E-05

-1.7?t.05 I

i i

4 OD0589-1333A-BA01-BA02 g-

+, - - - -

y._

~, _

..,n

--..,,y..

,,n-.

,,-p 6--,

er w <

---w=

e

VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 6 EFFLUENT T/S REQUIRED DOCUMENTS Page 44 of 94 A.

OFFSITE DOSE CALCULATIONS TABLE 1.7 INNALATION Dost F AC T0a $ FCR T E E N A GE 4

( =A ( M P til PCI INFatt03 NUCLICE 80NE LivCA T. 00 CY TNyR010 KloNEY LUNC Cl-ttl 1

N 3

NO DATA 1.59I-0F l.591-07 t.39C-07 1.59f-07 1.59E-07 1.59t-07 C 14 3.2bt-06 6.C9C-07

6. 09C-0 7 6.091-07 6.09E-07 6.09t-0F 6.091-07 14 24

1. 72 C-06 1.72C-06

1. 72 E-0 6 t.72f-06 1.12t-06 1 72C-06 1.T2C-04 p 12 2.36[-04 1.lf -0>

8. 0 5 E -0 6 60 DATA NO DATA NO DATA 1.16F-05 CA at 30 D AT A 40 DATA 1.69F-08 9 3Tt-09 3.94l-09 2.62t-06 3.75t-07 FN 54 NC CATA 6.39F-06 1.0>C-06 NO DATA 1.59t-06 2.481-04 8.35t-06 NN $6 NO DATA 2.124 14 3.15C-11 NO DATA 2 24E- 0 1.90E-C6 7 18t-06 FC 55 4.t8E-06 2.98t-06

6. 9 3 C-0 7 NO DATA NO DATA t.55E-05 7.99t-07 FE %)

1 1%!-06 4.62C-06

'. 7 9 C -0 6 NO DATA NO DATA t.9tt-04 2.23C-05 C0 58 NO DATA 2.39f-07 3.4 7C-0 7 NO DATA NO DATA 1.68t-04 1.19f-05 CD 60 NO CATA t.89E-C6

2. 4 8 E -0 6 NO DAT4 ho DATA l.09E-03 3.24t-05 NI 6)

T.25t-05 5.43t-06

2. 4 7 t -0 6 NO DATA NO DATA 3.84[-05 1 77t-06

~

gl 6b 2.73t-10 3.o6f-lt 1.59C-1i NO CATA NO DATA 1.17t-06 4.59E-06 CU 64 NO D AT A 2.54C-10

1. 06 C-10 NO DATA

8. 01 t -10 1.39t-J6 7.68t-06 IN 65 4.62C-06 1.07E-05

7. 80 E-0 6 NO DATA 1.08t-05 1.5$t-04 3.83t-06 t ti 69 6.04[-12 1.15F-11 4.07C-13 NO DATA 7.531-12 1.98t-07 1 56f-08 na 8)

NO DATA NO DATA

4. 30C-0 8 *NO DATA NO DATA NO DATA LT C-26 Sk 84 NO CATA NO DATA 5.4 t t-0 8 NO DATA NO DATA NO DATA LT t-24 44 85 NO CATA 40 CATA

2. 2 9 C-0 9 NO DATA NO DATA NO OATA LT t-24 98 86 NO DATA 2.38t-05

1. 0 5 C-0 5 NO DATA NO DATA NO CATA 2.28t-06 a5 88 NO DATA 4.82C-08

3. 40 E -0 4 NO DATA NO DATA NO DATA 3.65[-15 48 89 NO DATA 4.402-08 2.910-0 8 NO DATA NO DATA NO DATA 4 22C-If SR 89 5.43t-05 NO CATA t. 56 C-0 6 NO DATA NO DATA 3.02C-0 4 4.64t-05 54 93 1.35t-02 wo CATA

8. 3 5 t-0 4 NO DATA NO DATA 2.06 t-0 3 9.56t-05 5A 11 1.tCt-08 WG CATA

4. 3 9C-10 NO DATA NO DATA 7.5 9 E-0 6 3.24E-0$

54 12 1.19C-09 NO DATA 5.08C-t 1 NO DATA NO DATA 3.4 3C-0 6 1.49t-05 Y 90 3.T3C-07 NO DATA 1.00C-OS NO DATA NO DATA 3.66E-05 6.99f-05 Y 9tr 4.611-11 NO DATA

1. 7 7 C-12 NO DATA NO CATA 4.00E-07 3.771-01 Y 91 8.261 05 ho CATA

2. 2 t E-0 6 40 DATA NO DATA 3.67C-04 5.ttt-05 Y 92 1.84t 09 ko CATA, 5.36C-1L no DAT%

NO DATA 3.35t-06 2.06t-05 l

l OD0589-1333A-BA01-BA02

VOLUME 2$

BIC ROCK POINT RADIOLOCICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 45 of 94 A.

OFFSITE DOSE CALCULATIONS TABLE 1.7 INH At41109 00W F Ac tot 5 FC4 TEFNAGEL I

(

• R E 88 P L8t PCI ItH AL E0 5 f

WELICE Scht Livf4 f.AOCY THyn010 K10NEY LU Cl-s t i

......................................-.....................'to l

l j

l 7 93 1.69E-08 NO CnfA 4.65E-10.N0 Ca7A NO LATA 1.04E-05 7.24E-05 la 95

!. 8 2 E-05 5.73E-04 % 94 E-0 6 NO CATA 8.42E-06 3.36E-04 1.8&E.05 2a 17 1.72C-08 3.40E-C9

1. 5 7 E-0 9 No DATA 5.lSE-09 1.62E-05 7.88E.05 NB 95 2.32E-06 1.29E-06

7. 08 E -0 7 No 0ATA 1.25E-06 9.39E-05 1 2tE.05 PO 99

40 D AT A 2.llE-08 4.03E-09 NO CATA S.14E-08 1.97C-05 1.16C-05 1C 99P 1 73E-13

4. a 3C-Il 6.24E-12 NO CATA 7.20E-12 1.*4E-07 7.66E-07 TE8Cl 1.40E-15 1.05E-14 1.0 3E al 3 NO 0474 1.90E.13 8.34E-08 1.09E-14 ai>.03 2.63E-07 40 CATA 1.12 E-0 7 No CATA 9.29E-07 9.71E-05

1. 3 6E-05 10105 1.60E-10 NO 04fA 5.42C Il NO DATA 1.76E-10 2.27E-06 1.13 C-05 tul06 1.23E-05 NO DATL

1. 5 5 E-0 6 k0 CATA 2.38E-05 2.0lE-03 1.20E-04 4C110P 1.71E-06 1.66E-06 N 99 E-0 7 NO DATA 3.13E-06 8.44E-04 3.41E.05 (El25 6.10E-07 2.80E-07 8.34E-0C 1 75E-07 NO DATA 6.70E-05 9.38C-06 v......

TEl27M 2.25E-06 1.C2C-04

2. 7 3 E -0 7 5.48E-07 8 17E-06 2.0it-04 1.99E-05 TEl27 2.5tE-10 1.14F-10 5.5tC-11 1 7 7E-10 9.10E-10 1.40E-06 1.0lt.05 I

IE129M l.74E-06 8.23C-07

2. 81 E-0 7 5.12 E-0 7 6.49E-06 2.41d-04 5.0 6E.45 I

x.

.......... ~...

l TE129 0.87E-12 4.22E-12 2.20E-12 e.48E-12 3.32E-Il 4.12C-07 2.02E-07 i

IE131P 1.23C-08

7. Sit-09

5. 03 E -0 9 9.06E-09 5.49E-08 2.97E-05 7.76E-05 l

fE133 1.97E-12 1.04C-12 6.30E-13 1.551-12 7.72E-12 2.92C-07 1 89E-09 l

.........~........~..........

I TEI)2 4.50E-Of 1.61E-08 2.74E-08 3.07E-04

2. 4 4 E-0 7 5.6tt-05 5.79E-05 1 130 7.80E-07 2.24E-04 8.9 6 E.0 7 1.86E-04 3.4%-06 ho DATA 1.14E-04 1 131 4.43E-06 6.14E-06

.% 3 0E-0 6 1.83C-03 1,05E-05 NO CA7a 8.llF.07 i 132 1.9M -07 5.47E-07 1.97E-07 1.89E-05 9.65E-07 h0 DATA 1.59E 07 1 13s 1.52E-06 2.36E-06 7.78E-07 3 65E-04 4.49C-06 NO DATA 1.29E-04 1 134 4.llE-07 2.90E-07

1. 05 E -0 7 4.94E-06 4.58E-07 ho 0474 2.5 5 E.0i i 135 4.62C-37 1 18E 4. 7 6E-0 7

7. 76 E -0 5 1.86E-06 50 CATA 8'. 6 9 E -0 7 C5134 6.2 8 E-05 1.4tE-04

6. 8 6 E-0 5 No CATA 4.69E-05 1.83E-05 1 22E-04 r

2.42E-05

1. 7 t t-0 5 1.38E 05 2.222 06 1 3 %.04

.. -.............. 'to CA TA C5116 6.44E-06 C5137 8.38E-05 1.06E-04

3. 8 9 E-0 5 NO DA74 3.80E-05 1.51E-05 1.0 6E-06 05138 5.82E-08 1.01E-07

5. 5 8 E-0 8 NC OATA 8.28E-08 9.84E.01 3.38E.it BA139 1 67E-10 1.18E-13 4.87E.12 40 DATA 1.111-13 8.08E-07 8.362-07 l

l t

l l

l i

OD0589-1333A-BA01-BA02 l

.~

VOLUME 25 BIG ROCK FOINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQi; IRED DOCUMENTS Page 46 of 94 A.

OFFSITE DOSE CALCULATIONS TABLE 1.7 5

INH ALAI lOg Oggg p gCf04 5 FCA TEEka0ER IMEM PE4 PCI INH AL E01 NUCliuE CONE LivEt T.30CY lfHyaolo KIONEY

......................~....... -................ ~.....tuNC Cl-Ltl Bat 40 6.84E-06 8.38E*09 4.40E-07 NO 04f4 2.4SE-09 2 54E-04. 2.86E.05-d4141 1.78E-tt 1.s2E-14 S.9 s E-13 NO DATA l.2 3E-14 ~ R.11E-07 9.33E.14 batel 4.62E-12 4.63E-!S 2 84E-13 NoCAf4 3.92

.................................-..................E-15 2 39E-07. 5.9%E....~.............

(A140 S.59E-04 2 95C-08 7.82E-09-N0 CAf4 NO DA T A 2.68E-05 6.09E-05 LAl=2 1.20E-10 5 3tE-tt 1.32E.tt -ho DATA NO DATA 1.27E-06 ' t.50r-?6 CEt41 3.55E.06 2 37C-06

2. 71 E-0 7 NO DATA

1. tit.0 1.5t -05

............................. -.....................6 '7.67E-05:

CE14) 3 32E-04 2.42E-C8 2.70E.09 No CATA 1.086-08 1.63E-05 3.19(-05 CEt44 6.llE-04 2 53E-04 3 28E-0 5 NO OATA 1.SIE-04 1.67E-03 t.08E-06 ett43 1 47E-06 6 64Ea07.

8. 2 8 E-0 4 No DATA 3.86

...............................-...-..................E-07-6.04E-05

. 4FE-05

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

ral44 5.37E-12 2.20E-12 2.72E-13 10 DATA 1.26E-12 2.19E-0? 2.94E-16 N0147 9.83E.07 1.07E-C6 6.4tE-04 No O AT A.

6.2%E 4,65E-05 2.2 8 f.05 w 187-1.50E-09 1 225-09 4.29F-10 NO D A T A - NO

.............................-................04fA 5.92E-06 2.2tE....................

• sPt39 4.21E-08.3 99E-09 2.21E-09 40 CATA 1.25E.03 a.ltt-06 ~1.65C-05 I

I i

OD0589-1333A-BA01-BA02

..s.

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOClHENTS Page 47 of 94 A.

OFFSITE DOSE CALCOLATIONS EXTERNAL DOSE FACTORS FOR STANDIWC ON CONTAMINATED CROUND Table 1.8 (mrem /hr per pCi/m )

8 El ement

, Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08

2. 90F - :.8 P-32 0.0 0.0 Cr-51 2.20E-10 2.66..-10 Hn-54 5.80E-09 6.80E-09 Hn-56 1.10E-08

1. 30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-04 Cc-60 1.70E 08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 2n-69 0.0 0.0 Br-83 6.40L 11 9.30E-Il t

Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 RS-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 c -91 7.10E-09 8.30E-09 r

Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-ll 2.70E-ll i

Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Ho-99 1.90E-09 2.20E-09 Tc-99m 9.s0E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.o0E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110n 1.80E-08 2.10E-08 Te-125m 3.50E-11 4.80E-Il=

Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-Il OD0589-1333A-BA01-BA05 I

4 i

' VOLUME 25 BIC ROCK POINT RADIOLOCICAL-Revision 8 l

EFFLUENT T/S REQUIRED DOCUMENTS '

Page 48 of 94 i

A.

OFFSITE DOSE CALCULATIONS i

_FJTERNAL DOSE FACTORS FOR STANDING -ON CONTAMINATED CROUND Table 1.8.

i f

(m, rem /hr per pCi/m#)

i I

Element Total Body Sk.i n -

i Te-129m 7.70E-10 9.00E-10.

f Te-129 7.10E-10 8.40E-10 Te-131m _

8.40E-09 9.90E-09 Ta-131 2.20E-09 2.60E-06 I

Te-132 1.70E-09 2.00E-09

{

1-130 1.40E-08 1.70E-08 l

I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 j

I-134 1.60E-08

.l.90E-08 4

I-135 1.20E-08 1.40E-08 ce-134 1.20E-08 1.40E-08 Cs-lao 1.50E-08 1.70E-08.

Cs-137 4.20E-09 4.90E-09 a

l Cs-138 2.10E-08 2.40E-03 Ba-139 2.40E-09 2.70E-09 Ba-140-2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E +

1 Ce-141 5.50E-10 6.20E-10 i

- Cc-143 2.20E 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10

-2.30E-10 Nd-147

- 1.00E-09 1.20E-69 W-187 3.10E-09

=3.60E-09 l

Np-239 9.50E-10 1.10E-09 i

I l

l OD0589-1333A-BA01-BA05

1 I

VOLUME 25 BIC ROCK POINT RADIOLOGICAL-Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 49 of 94 A.

OFFSITE DOSE CALCULATIONS TABLE 1.9 1992 BIC ROCK POINT CASE 00S DESIGN j

i OBJECTIVE ANNUAL QUANTITIE9 Design Objective Dose Factor Annual Quantity Nuclide Organ mrem /Ci (Ci)

Ar-41 Total Body 1.02E-05 4.90E+05 Kr-83m Skin 2.47E-08 6.07E+08 Kr-85 Skin 2.23E-06

6. 7 3E+ 06 Kr-85m Total Body 1.35E-06 3.70E+06 Kr-87 Skin 2.39E-05 6.28E+05 Kr-88 Total Body 1.70E-05 2.94 E+ 05 i

Kr-89 Total Body 1.92E-05 2.60E+05 11 - 3 Total Body-C 6.39E-Ob 7.82E+05 C-14 Bone-C 5.59E-03 2.68E+03 Cr-51 CI Tract-A,T 1.79E-04 8.38E+04 Mn-54 CI Tract-T 1.85E-02 8.11E+02 Fe-55 Bone-C 1.57E-02 9.55E+02 Co-58 CI Tract-T 1.15E-02 1.30E+03 Fe-59 CI Tract-T

.1.84E-02 8.15E+02 co-60 CI Tract-T 6.57E-02 2.28E402 l

Zn-65 Total Body-1 6.23E-02 8.03E+01 Sr-89 Bone-C 6.93E-01 2.16E+01 l

Sr-90 Bone-C 2.85E+01 5.26E-01 Zr-95 CI Tract-T 2.43E-02 6.17E+02 l

Sb-124 CI Tract-T 5.91E-02 2.54E+02 I-131 Thyroid-I 3.11E+00 4.82E+00 Xe-131m Skin 9.84E-07 1.52E+07 Xe-133 Total Body 3.39E-07 1.47E+07 Xe-133m Skin 2.06E-06 7.28E+06 Xe-135 Total Body 2.09E-06 2.39E+06 Xe-135m Total Body 3.60E-06 1.39E+06 Xe-!??

Skin 2.20E-05 6.82E+05 Xe-138 Total Body 1.02E-05 4.90E+05 I-133 Thyroid-I 2.71E-02 5.54E+02 Cs-134 Liver-C 5.28E-01 2.84E+01 l

Cs-136 Liver-I

-1.22E-02 1.23E+03-l Cs-137 Bone-C 5.16E-01 2.91E+01 l

Ba-140 Bone-C 3.50E-03 4.29E+03 I

Cc-141 CI Tract-T 9.66E-03 1.55E+03 Ce-144 CI Tract-T 2.57E-01 5.84E+01 Mt-56 CI Tract-I 6.69E-05 2.24E+05 Co-57 CI Tract-T 6.50E-03 2.31E+03 Ni-65 CI Tract-I 4.63-05 3.24E+05 Rb-88 Total Body-C 1.05E-08 4.76E+08 l

Nb-95 CI Tract-A 4.31E-02 3.48E+02 Ho-99 Kidney-1 1.84E-03 8.15E+03 Tc-99m CI Tract-T 7.41E-06 4.02E+06 Ru-103 CI Tract-A 6.86E-02 2.19E+02 OD0589-13 33 A-BA31-BA05 l

l VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS

-Page 50 of 94 A.

OFFSITE DOSE CALCULATIONS l

l TABLE 1.9 f

1992 Bic ROCK POINT CASEOUS DESIGN 3

i OBJECTIVE ANNUAL QUANTITIES (Continued) i j

Design Objective l

Dose Factor Annual Quantity Nuclide Organ __

mrem /Ci (Ci) l Sb-125 C1 Tract-T 3.33E-02

'4.50E+02 Te-127 Cl Tract-T 1.05E-04 1.43E+05-T-132 Thyroid-C 1.72E-04 8.72E+04 l-134 Thyroid-C 1.98E-05 7.58E+05 l

I-135 Thyroid-C 9.81E-04 l.53E+04 La-140 CI Tract.

6,94E-04

_ 2.16E+04 l

N-13 Total Body-!

2.lbE-53 2.31E+55 i

Na-24 Total Body-I 8.56E-05 5.84E+04 Br-82 Total Body-I

1. l( E-C 3 4.39E+03 Sr-91 CI Tract-A 1.84E-05 8.15E+05 Sr-92 CI Tract-C 1.20E-07 1.25E+08 l

Tc-101 Total Body-C 3.36E-12

'1.49E+12 Ag-110m CI Tract-T 1.69E-01 8.88E+01 l

Cs-138 Kidney-A 3.75E-20 4.00E+20 i

Ba-139 CI Ttact-C 1.93E-Il 7.77E+11 l

Np-239 CI Tract-A 3.85E-04 3.90E+04 i

i i.

t i

i I

I l

i l

l l

i l

i I

i f

OD0589-1333A-BA01-BA05

i j'

d i

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 51 of 94 A.

OFFSITE DOSE CALCULATIONS i

j_

II.

LIQUID EFFLUENTS II.A AL!OWABLE CONCENTRATION II.A.1 RETS Requirement i

Technical Specification 13.1.2.1 of the Radiological Effluent Technical Specifications (RETS) requires that the concentration of l

radioactive material releesed at any time from the site to 2

unrestricted treas shall be limited to the maximum permissible concentration (HPC) specified in 10 CPR 20, Appendix B, Table II, Column 2 for nuclides other than dissolved or entrained noble

.ases.

For dissolved or engrained noble gases, the concentration 10~

pCi/ml total activity. To ensure i

shall be limited to 2 x i

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

E i

II.A.2 Prerelease Analysis Host 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, i

Prior to release, a grab sample will be analyzed for each release, and the concentration of each radionuclide determined. -

4 i

i Cj = \\)

, Ci j (11.1) l i=1 where:

Cj = Total concentration in the liquid-effluent at the release j

point, pCi/ml, at release point j.

Cij = Concentration of a single radionuclide i, pCi/ml, at release point J.

J A

)

OD0589-1333A-BA01-BA05 4

4 i

VOLUME 25 dlC ROCK IOINT RADIOLOGICAL-Revision-8 EFFLUEN1 T/S REQUIRED DOCUMENTS Page $2 of 94 A.

OFFSifE DOSF CALCOLATIONS II.A.3 Total HPC-Fraction The total HPC-f raction (RJ) for _ each release point will be calculated by the relationship defined by Note 1 of Appendix B, 10 CFR 20.

1d-R(j)=)

, HPC; (11.2) i where Cij = Undiluted 'ff1-nt concentration of radionuclide i, as determined i.. Section.II. A.2, pCi/ml, at release point j.

MPCi = The MPC of radionuclide i, as specified in Section II. A.' 1, pCi/ml.

Rj = The total MPC-fraction for the_ release point.

TP, sum of the ratios at the discharge to the lake must be 51 due to the releases from any or all concurrent releases. The following relationship will assure this criterion _is mets fj(R - 1) + f (R2~ 1) + fa(R 2

3 - 1) 5 F (11.3) where:

f,f.f3 = The effluent flow rate (gallons / minute) for the respective i 2 releares, determined by plant personnel.

R,R,R3 = The total MPC-fractions for the respective releases as i 2 determined by Equation 11.2.

i F = Hinimum required dilution flow rate. Normally, a conservatively high dilution-flow rate is used, that is, flow rate used = (b)(F) where b is a conservstire factor greater than l'.0.

II.B INSTRUMENT ALARH SET. POINTS II.B.1 Set Point Determination The set point for each liquid ef fluent monitor will be established using plant instructions. Concentration, flow rate, dilution, principal gamma emitter, geometry and detector _ efficiency are combined to give an equivalent _ set point in count s - pe r. minute (cpm). The physical and technical description,-location and identification number for _each liquid ef fluent radiation detector is contained in Figure 2-2.-

2 OD0589-1333A-B A01-BA05

f G 4 2

9 n

R E

4 2

7 GL o'

E l

T RA i

r

^

8 A

AM s

n w

H HA i3 U

C CC v5 t

I H

e t

t R e F

O g

t a

4, P

S W

O L

r F

E f

SA p

l e

EL iN E

e g

R 2

T5 L

D 1

O F

2 R

I T

U N

E O

TRM Q

C SOR L R ATA W

A E

WI L E7 C

I 5

C vl K AOi 8

F MI DN L

A R2 L

E E

CN RMH H EA M

@HIHL C

RT R

G A T

A N

s i

T E

I O

CR IVE RT P

S A

E T

SW NS K

EN LMO E

C AUI TE 8

CCT 3

AG l OA S

O t

S A CDL Ex T

NA" O

U TN i

E 0^

R LDC SA D

AT N$

T OEL W R 1

O I RA AU Avl G

DI C NE C

E I

RQE E

B LC A

ES C E 3

TRO R

1 N

D T

I S O/E PTT 2

I 0

KTS A

CNF B

OEF RUO 1

L 8

8 0

GF S

5 A

4 1

1 B

I F.

E E

T S

T BEA T M K

SA gN A

AT A

3 gT WR 3

1 3

5 YE D

2 T VI pL 1

R E O

C A

H A

9 E

ID M

E 4

1 8

U R

t 1

5 Y

T L

0 O

D V

O

i VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page $4 of 94 A.

OFFSITE DOSE CALCULATIONS The respective alarm / trip set points at each release point will be set such that the sum of the ratios at each point, as-calculated by Equation'!I.2, will not exceed 1.

The value of R is-directly related to the total concentration calculated by Equation 11.1.

An increase in the concentration would indicate an increase in the value of R.

A large increase would cause the limits specified in Section II.A.1 to be exceeded. The minimum alarm / trip set point value is equal to the release concentration, but for ease of operation it may be desired that the set point (S) be set-above-the effluent concentration (C) by the same factor (b) utilized in setting dilution flow. That is:

S=bxC (II.4)

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

11.B.2 Post-Release Analysis 1

A post release analysis will be done using actual release data to ensure that the limits specified in Section II.A.1 wera not exceeded.

l A composite list of concentrations (Cij), by isotope, will be used with the actual liquid radwaste (f j) and dilution (F) flow rates (or volumes) during the release.

The data will be substituted into Equation 11.3 to demonstrate compliance -with the limits in Section II.A.I.

This data and set points will be recorded in auditable records by plant personnel.

II.C DOSE II. Col RETS Requirement Technical Specification 13.1.4.1 of the Radiological Effluent Technical Specifications (RETS) requires that-the quantity of

.3 radionuclides released be limited such that the dose or dose commitment to-an individual:from-radioactive materials in liquid effluents released to unrestricted areas from each reactor-(see-Figure 2.1) will not exceed:

1.

During any calendar quarter, 1.5 mrem to the total body and 5 mrem to any organ,-and 2.

During any calendar year,-3 mrem to the total body and 10 mrem l

to any organ.

OD0589-1333A-BA01-BA05

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

-. ~. -.-.

t VOLUME-25 BIC ROCK POINT RADI01.OGICAL Revision 8 i

EFFLUENT T/S REQUIRED DOCUMENT' Page 55 of 94 A.

OFFSITE DOSE CALCULATIONS i

l II.C.2 Release Analysis-(Desir,n Basis Quantity Fractica)

Per Technical Specification 13.1.4.4 the cumulative DBQ fraction for nuclides released is summed at least every 31 days to assure that the sum of the fractions of all nuclides released does not exceed 1.0 year to date and 0.5 in any calendar quartet.

Calculations shall be performed according to the formula:

A.

= Fraction of DBQ (II.5)

T 1

/_

(DBQ);

i where:

Ai = Cumulative quarterly or annual activity of nuclide i identified in liquid release (Ci),

(DBQ){ = Design objective annual quantity of radionuclide i from Table 2.2 (Ci).

Radionuclides may be omitted f rom the summation if they f all under the criteria of allowed omission specified by Note 5 to Appendix B, 10 CFR 20.

II.C.3 Exceeding DBQ Limits 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 histor--

ically consistent operations with releases well.below annual design basis quantities, the Big Rock Poier Plant technical specificatiens do not require monthly dosi projections.- However, Technical Specification 13.1.4.4 requires'a cumulative dose contribution to be determined for current quarter and year ever/

31 days.

If at any time this calculation, by Equation II 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 Technical. Specification 13.1.4.1 has.been met.

II.C.4 Dose Calculation Values for the design basis quantities (Ci), and the dose per curie (Dc/Cc)i for each nuclide i shown in Table-2.2, were calculated as follows.

i l

OD0589-1333A-BA01-BA05 l

1 I

..-. - =

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

. -.. ~.

.~

b i

VOLUME 25 BIC-ROCK POINT RADIOLOCICAL Revision 8 i

EFFLUENT T/S REQUIRED DOCUMENTS Page 56 of 94 A.

OFFSITE DOSE CALCULATIONS

'l 3-H i

4

{

II.C.4.1 Water Ingestion The dose to an individust f rom ingestion of radioactivi* y f rom any source is described by the following equation:

l i

j Dj=)

(DCF)ij x l i = mrem (II.6)

,l i

i=1

.I i

I where:

Dj = Dose for the jth organ from radionuclides released, mrem.

j = The organ of interest.

i l

(DCF)ij = Ingest {on dose connitment factor for the jth organ from l

the i radionuclide mrem /pCi _ (see Table 2.1).

th I i = Activity ingested of the i radionuclide, pCi.

t li is described by:

6 (A;)(V)(365)(10 )

i Ii =

= pCi (II.7) i-(800)(d) where:

j i

j 365 = Days per year.

f Ai = Annual activity released of i radionuclide, pCi.

th V = Average rate of water _consumptioni adult - 2,000 ml/d, teen l'

and child - 1,400 ml/d, infant - 900 ml/d (Reg Cuide 1.109).

e i

j --

d = Dilution water flow for year (ml).-

800 = Dispersion factor from discharge to. nearest drinking water

. suppl y.

?

106 = Converts pCi to pCi.-

l The dose equation then_becomes:

I

-1 Dj = (4.56 5)(v).

(DCF)jj x Ai

= mrem (11.8) i=1 OD0589-1333A-BA01-BA05 I'

i

~_

4 VOLUME 25 BIC ROCK POINT RADIOLOClCAL Revision 8 EFFLUENT T/S REQUIPED DOCUMENTS Page 57 of 94 A.

OFFSITE DOS 5' CALCULATIONS II.C.4.2 Fish Ingestion The dose to an individual from the consumption of fish is de-the i g by Equation 11.10.

In this case the activity ingested of scribe l

radionuclide (ii) is described by:

A. B; F 9

li =

(10 ) = pCi (11.9) 15d where:

th A; = Annual. activity released of i radionuclide, pCi.

th Bi = Fish concentration factor of i radionuclide, k

(see Table 2.0).

F = Amount of fish eaten per year; adult - 21.kg, teen - 16 kg,-

child - 6.9 kg and infant none.

15 = Dispersion factor from discharge to fish exposure point.

d = Dilution water flow for year (ml).

109 = Converts pCi to pCi and gm to kgm.

Substitution of Equation II.9 into Equation II.6 gives:

i i

Dj=(6.7E07)(F)f (Ai)(Bi)(DCF j) = mrem-(11.16, i

i =1 l

II.C.4.3 Releasing Radionuclides Not Listed in Table 2.2 l

Table 2.2 contains all nuclides identified to date as routine conatituents of liquid releases at Big Rock Point Plant, plus those common to boiling water reactors in general, even if not previously detected at Big Rock Point. From time to time, however, i

I -

other nuclides may be detected.

If the unlisted nuclide constitutes less than 10% of the HPC-fraction for the release, and all unlisted nuclides total less than 25% of the HPC-f raction, the nuclide may be considered not present.

l OD0589-1333A-BA01-BA05

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision B EFFLUENT T/S REQUIRED DOCUMENTS Page 58 of 94 A.

OFFSITE DOSE CALCULATIONS If the unli-a ed nuclide const itutes greater than 10% of the MPC-fraction, or all unlisted nuclides together constitute greater than 25%, then each nuclide should be assigned a DBQ equal to the most conservative value listed for the physical form of the nuclide involved (noble gas, halogen or particulate).

Should a nuclide not listed in Table 2.2 begin to appear in significant quantities on a routine basis, revision to this ODCM should be made in order to include a design basis quantity specific to that nuclide.

II.C.5 Annual Analysis A complete analysis utilir.ing 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 in LADTAP. The dose to the jth organ from m radionuclider, Dj, is described by:

n

-f g

Dj = /

,D l, = rem (II.11) i i=1 m

x i

Dj = j/

(DCF)ij x It = rem (11.12) i=1 l

t OD0589-1333A-BA01-BA05

_r.-.__________._.._.__-._______.____.-_.________._________.____

Vol.UME 25 B10 ROCK PolNT RAD 101.0CICAL Revision 8 frPLUENT 7/S REQUIRED DOCUMENTS Page 59 of 94 A.

OffSITE DOSE CALCULATIONS F

4 wheret Dij = Dose to the jlh organ f rom t he i radioauclide, rem.

th j

j --

rgan of interest (bone, Cl t ract, thyroid, liver, j

t.jr.cy, lung or tot al, body).

(DCF)ij = Ingestion dose connitment f actor for the jth organ from i

the ith radionuclide, rem /pci (see Table 2.1).

th j

li = tctivity ingested of the i radionuclide, pct.

j i

j li f or water ing;estion is described byt I

1 A VI li = v; pCi (11.13) i d

j I

and for fish ingestion 1[ is described by_

i A; B; F1

?

li =

pCi

-(11.14) vd wheret Aj = Activity released of jth radioniaclide N r n.e he year, pCl.

)

V = Average rate of water consumption (Table 2.2),

t = Numb (r of days during-the year (365 d).

I v = Dispersion factor from point of diecharge to point of exposure j

(Table 2.2).

l l

d = Dilution water volume (ml)'.

radionuclide,hh th Bi = Fish concentration f actor of the i (Table 2.0).

f F - Amount of fish caten per day (Table 2.2).

4 1-e i

l OD05 89-1333 A-B A01-B A05 I

9.. h. m.,

,yw prr-.~,w-.,r,-

a,-++-=eg.

y-..,,a g,,.

wp

<7,e

-m------r-,mm-',,,,q,,,.c.,.

ce w

,.,,n+w,e,,

,,.,-y..w-e-,

,,,,y.,-r,,,%,,v-rw=.er-**-e rm*'*--*N're e'er'-*''t-*7

1 I

VOLUME 75 BIC Ruta P0lNT RADIOLOGICAL Revision 8 EFFLUENT T/S khQUIRED DOCUMENTS Page 60 of 94 A.

OFFSITE DOSE CALCULATIONS 1

a ll.D OPERABILITY OF LlQUID RADWASTE EQt!!pMENT The Big Rock Point liquid radwaste system is designed to reduce j

the radioactive materials in liquid wastes prior to their dis-charge (by secycle or shipment for disposal) so that radioactivity in liquid effluent releases to unrest:!.cted areas (see Figure 2.1) will not exceed Technical Specification 13.1.4.1.

Maintaining the cumulative DBQ f raction of relca_ as assures compliance with this I

requirement.

In addition, more than 13 years of operating experience 1

(to the date this ODCH was first adopted) has shown that design basis quantitics never have been execeded, li.E OFFSITE HPC RELEASE _RA1E y

I 10 CFR 20.106 requires that radioactive effluent releases to une restricted areas be less than the limits specified in A-ndix B, Table II when. averaged over a period not to exceed one year.

Concentrations at this level, if ingested for one year, will result in a dose af 500 millirems to the total body or its equiva-lent to internal organs.

In addition, 10 CFR 50.36a requires that the release of radioactive materials be kept as low as is reasonably l

achievabla. However, the section further states that the licensee is permitted the flexibility of operation, to assure a dependable source of power, to release quantities of material _ Sigher than a small percentage of 10 CFR 20 limits but not exceedis.g those limits under unusual operating conditions.

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

The LADTAP code has been run te determine the dose due to drinking water at plant discharge conceue ation (800 x nearest drinking water intake concentration).

The source term used is given in Ta bl e 1.1.

The most limiting dose of the person hypothetically

.rinking this water is 4.E9E-01 mrem, whole body.' The release rate which would result in a dose rate equivalet.t to 500 mrem /y (the total body limit) is the Curies / Year given in Table 1.1 i

(8.94) times 500/.489 or 9141 Ci/Yr = 2.9E-04 Ci/sec..

l The above calculation'is informational as a typical exposure using l

the drinking water pathway and an avenage release from Big Rock l

Point. Per Section ll.C.5 annual analyses are run using LADTAP to

}-

calculate estimates of dose to the total body and limiting organs.

l L

OD0589-1333A-BA01-BA05 1

i

.i VOLUME 25 lilC ROCK PolNT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 61 of 94 1

A.

OffSITE DOSE CALCULATIONS l

i 4

BIOACCUMUI.ATION PACTORS 4

{

~

Tabl e 2.0 i

l

[ECi/gm per pCl/ml) i El emen t Freshwater Fish 1

1 11 9.0E-01 C

4.6E+03 Na 1.0E+02 l

P 3.0E+03 J

Cr 2.0E+02 j

Mn 4.0E+02 i

Fe 1.0E+02 j

Co 5.0E+01 j

Ni 1.0E+02 4

Cu 5.0E+01

^

Zn 2.0E403 Br 4.2E+02 Rb 2.0E+03 1

Sr 3.0E+01 Y

2.5E+01 l

Zr 3.3F+00

{

Nb 3.0E+04 Ho 1.0E+01 l

Tc 1.5E+01 i

Ru 1.0E+01 l

Rh 1.0E401 i

Te 4.0E402 1.5E+01 Cs

'2.0E+03 l-Ba 4.0E+00 La 2.5E+01 l

Ce 1.0E+00 Pr 2.5E+01 Nd 2.5E+01 W

1.2E103 j

Np 1.0E+01 i

j I

1 f

ODJ5E9-1333A-BA01-BA05 i

... ~. -, -

1 1

l VOLUME 25 hic HOCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 62 of 94 A.

OFFSITE DOSE CALCUl.ATIONS j

i 1

4 TABLE 2.1

(

2 AWt.T 1MCt3fjos Dost FACTMS 4

J.oni/K1 IKt5TED) i 4

FWt!Dt 50AI ttytt T. foDT Tv00TO rit*tY LtNO Ct.tl!

8 to DA!A

1. 0$ t.07 h05t47 1.0M 47 1.0$t47 1.0$t 07 1.0$t47 1

C 16 2.stt4

$.68t47 5 d f1367 M6t-07

$.66t47 S.64t.07 5.68147 DA 26

1. 7CE4

1. 70t.M

1. 7Ct46 1.70t44 1.70[ 46 1.700 06 1.70t.06 i

3

................................................. ~ ~............. ~........................ 6 j

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7.46t-06 NODATA MO MTA NO CATA t.17t4$

j CR $1 N0 CAU DO DATA 2.66t*09 1.llt.09

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HN $6 H3 CATA

(.$7t06 8.72E.07 M DATA

1. 36t46 NO DATA 1.L0t4$

s y'

HN $6 NO DAIA

.1.1$t*07 2.04t44 M0CATA 1.L6t47 NO DATA 3.67146

)

l tt $$

2.7$t 4 1.900 06 4.43t47 NODATA W3 tdTA 1.06t.M 1.091 M i

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4. 34t46 1.0!E 0$

3.91t M NO DATA N0 CATA 2.8$!46 3.60C4$

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C0 Se l*0 DATA 7.&$t*07 1.67t*M 90 DATA N0 !*IA MO DATA 1 $1t.0$

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- 6. 02t 45 El 63 1.30!$

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1. 68 ! 4 6 1

El il 3.18t41 6.86 t44 3.13t48 NotiATA N0 DATA Iv0 DATA

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CU 64 NO DAH 8.33E.08 3.91E*08 30 DATA 2.10[ 4 7 NO DATA 7.10t46 l

tm 65 6.64146 1.54 t 4$

6. 96t-06 to DATA 1.03t4$

No DATA

.9.70t 06

~

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~

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1. 97t48

1. 37E49 M DATA 1.28148 NO DATA 2.Ht49 i

IR 43 NO DATA M0 DATA 4.0ft 08 30 DATA N0 DATA' MO DATA.

$.79140 j

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lR el to tufa No DATA 2.1At 09 80 DATA N0 Dita NO DATA LT t.26 RA 46 NO DATA 2.11t+0$

9. 8 3t.M 30 DATA MO MTA NO DATA 6.16E.06 4

31 68 N) Data 6.0$t.00 3.211 44 30 tATA 30 IdTA No tATA 3.36:.19 1

f-RA 49 HO ktA -

6.011 04 2.821 M 30 DATA DO MTA

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$.67146 NO DATA 2.29047 80 DATA 30 MTA NO DATA 2.70t4$

9

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, 30 M H MQ DATA 1.02146 j

T tin 9.09t.11 MO dan 3.$2t.11 30 !ATA NO kTA No taTA-2.67t*18 T 91 1.611 07 -

No DATA 3.77t 09 80 DATA NO MTA NO DAh 7.76t4$ -

T ' 92 8.45t.18 50 taTA 2.47t.11 30 DATA BC MTA MO DATA 1.Let4$

.......................................................... ~.

f OD0589-1333A BA01-DA02 t

4

--1 m-

-m..-.v.

,,,m_r-m---,.--r+,

4,-r.

....n,-.--r,_

.,.,,.,.w..ww._,.,,i-.,wr, 9y-w,,.-e.--

~ vw, _

py,,--m--,s

-y r

my--.-+-,,3--m-r+_,

VOLUME 25 BIC ROCK l'0 INT RADIOLOGICAL Revision 8 EITLUENT T/S REQUIRED DOCUMENTS Page 63 of 94 A.

OITSITE DOSE CALCULATIONS TABLE 2.1

- ~ ~..

AM_f imCr$T10s tost FACTOM ffMPIM/PCI !MCESTED)

FUC170t 132 t1Vit T.700Y T m otD r!t*IT Lt*NC C1 111-T 93 2.60t.09 80 DATA 7.tCE.11 MO DATA IC DATA NO DAu 8.301 03 2R 95 3.%t48 9.75t*09 6.600 09 90 DATA 1 $3108 H3 tA u 3.09t45, n 97 1.68 t49 3.39t.10 1.S$t.10

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OFFSITE DOSE CALCULATIONS i

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OFFSITE DOSE CALCULATIONS 1.

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OD0589-1333A-BA01-BA02

VOLUME 25 BIC ROCK P0lNT RADIOLOGICAL Revision 0

{

EFFLUENT T/S REQUIRED DOCUMENTS Page (,9 of 94 A.

OFFSITE DOSE CALCULATIONS TABLE 2.1 19Ct 5 f l04 00 M f AC f 045 F Ct CHIL O i

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1. 5 6 E-0 7 1.79E-05 1 19C-06 NO DAT\\

5.16t-07 8 135 1.75t-06 3.15t-06

1. 4 9 C-0 6 2.79C-04 4.83[-06 NO DATA 2.40E-06 C1134 2.341-04 3.84C-04 8.10 E-0 5 No DATA 1 19t-04 4.271-05 2.0ft-06 C5136 2.35t-05 6.46C-05 4 18t-0 5 NO CATA 3,44C-05 5.13C-06 2.2 f E-06 C5137 3.2f[-04 3.13C-04

4. 62 t-0 5 W CATA 1 02k-C4 3.67t-05 1.96t-06 C5131 2.28C-07 3.17E-07

2. 01 E-0 7 40 DATA 2.23E-07 2.40t*08 1.46C-07 84139 4.14t-07 2.2tt- 0

1. 2 0 E-0 8 NO DATA 1 93E-10 1 30t-10

2. 3 9 E-05 J

l OD0589-1333A-BA01-BA02 I

i

1 I

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VOLUME /5 BIC ROCK P01HT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 70 of 94 A.

OFFSITE DOSE CALCULATIONS 4

4 4

t TABLE 2.1 4

i l

It4415 f l01 0051 F AC TU4 5 F Ct CHILU l>AEP Pit PCI IN"t$ttet NUCLivt 8ONI Lista f.d orf THYRolo KIONEY LUNO Cl-LLI RAI40 8.31E-05 f.28C.08 4.4LC-06 NO D A T A 2.374 08 4.3AC 08 4 21C-05 "Al48 2.00C-07 1.122 10

6. b l E *0 9 NO DATA 9.691-11 6.S8f-10 1.14 C-O f 4

SA142 8.74C*08 6 29C-Il

4. 8 8 E -0 9 NO C ATA S. cit.lt 3.70C-ll 1 14(-01

.i L4140 1.01C-08 1.53C-09 1 11C-0 9 40 DATA NC 04fA NO DATA 9.84E.05 LA142 S.24E-10 1.67!.10 S. 21t-i l NO CATA 40 04f4 NO DATA 3.)lt.05 Ctl41 3.9fC-08 1.98C.09 2.9

• C-0 9 NO CATA 8.68(-09 NO DATA 2.4ft-05 Ct!43 6.99C-09 3.79E-04

5. 4 9 C-10 NO CATA I.$9E-09 NO DATA

%.95C-05 CEint 2.08E-06 6.52C-07

1. l l t.0 7 NO CATA 1.616 07 NO CATA l.70[.04 P4141 5.93C-08 1.lat.08

1. 9 % C -0 9 NO DATA 6.19E-09 h0 DATA 4 24t.05 Pal 44 1 29C-10 1.11(.!!

6.49E-12 NO DATA 2.Ilt-il k0 DATA 8.59t.08 N0147 2.79t-0A 2.26C-08

1. 7 5 E-0 9 No DATA l.24E-08 No DATA 3 54[-OS v 187 4.29(-07 2 54C.07

1. l * [-0 7 NU DAIA NO DATA NO DATA 3.Sf

.t.03 24r219 5.2bf-09 3.775 10 2.4bt-10 NO DATA 1.09d-09 ho CATA 2.79t-05 I

OD0589-1333A-BA01-BA02

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Off 5ITE DOSE CALCULAT10tJS r

TABLE 2.1 r

i l

INGt 5i101005E F ACICA5 FCA INFist patM Pta PCI IN0t5f f 01 W C;,lCt 80NE t!vit f.dOUY.

fHYt0!0 KIONtr LVatC C

.......................................................................l-Lil H

)

NO DAfa

).085 07

). 08 C.0 7 3.08t*07 1.08t-0F 3.C8C-0 7 3.08t.07 c to

2. 3 7 t-05 5.06C-06

1. 06 C-0 6 1.0AC+06 5.061 06 a.06F-06 1.06t-06 NA 24 1.0tt 1.01C.05 1.0lt-0 5 1.081-05 1.01t.05 4.01t.05

..................................................................1.018-05 p 32 lef0t-03 1 00C.04

6. 5 9 E-0 5 40 UAfA NO DAf6 NO DAT&

2.10E-05 to 11 ho CATA NO DATA 1.41[.0 8 9.2 0t - 09 2.Olt-09 1.79t.08 4.ttt.cf

.*N 54 NO CATA l.99t.05

4. 51 C-0 6 NO DATA 4.44t-06 40 CATA f.3t

.......................s............t 06

+

NN 56 NO CatA 8 18C.07

1. 4 t t-0 7 NU Dat8 7 011-07 NO Dat&

7.43f.05 FF. 55 l.391-05 8.18C-06

2. 4 C E.0 6 NO CATA NO O&f A 4.19E-06 1.14t-06 FE 59 3.C8t-05 5.J82 05

2. ! 2 C.0 5 NO CAfa NO CATA

't.59

2. Sit 05

............t-05 CO 58 NO 04f4 3.60C.06

8. 93 C -0 6 NO DATA NO DATA 40 DATA 8.9ft*06 Cc 60 No 0ATA 1.08E.05

2. 55t.0 5 - NO D A T A NO 04fA No DATA

2. S it -05 NI 63 6.14 t-04 1.92E.05

2. 20t-0 5 NO DATA NO DATA 40 C A T A

..........................~.................1 95t-06 1'

41 65 A.70[.06 5 32C.07 2.426-07 NO DATA NO O&fA

-40 DATA 4 05t.05 40 66 NO DATA 6 09t.0F 2.82t-07 10 CATA 1.03C-06 40 CAfa 1 25t-85 2N 65 l.14t-05 6 11(.05

2. 9 t t-0 3 NO DATA 3 06t-05 NO

..................................................,..... CATA

.5 33C-05 IN 69 9.DC-08 1 08C.0f 1.25[-08 NO DATA 6.18 t.04 No Cat &

t.5 f f,-0$

nA $3 in DATA NO 04fA

3. 6J C.0 7 NO 0&fA

.N0 CATA h0 DATA Lt t.24 ba 84 NO DATA NO DATA

3. 82 C -0 7 NO DATA k0 DATA h0 i

............... -...............-..........................CATA LT E.24 W A 8)

'NO DATA NO DATA 1 i. 44 ND DATA. NO DATA NO DATA LT t.24 RB 86 ' id DATA 1 70C.04

8. H05 -h0 Data NO DATA NO CafA 4 55t.04 48 $s NO CATA 4.98C-07

2. 73 C-4 7 NO DAIA NO CafA N

4 85t<JT

.............-.........................................O DATA tt 89. 40 DA T A 2.86[-07 1.97t.37 NO DATA No DATA 40 CATA 9 74t.08 54 89 2.51t.03 NO CATA f. 2 0 C-0 5 NO DATA

10 Caf a ha DATA 5.16t-05 SR 90 1.85t-02 N0'04fA

4. f t t-0 3 NO DATA

• t1 OATA 4

........0 D&fe 2.)lt-04 SR 94 5.001.C5 NO DafA

1. tit-06 No NATA NO DATA NO DATA 5.92[-05 52 92 1.92t-05 NO DATA.

7.1)[.0 7 - NO Ja f A NO DATA NO DATA-2 0?t-04 Y 90 8.69t-08 40 DafA

2. 3 s t.0 9 NO DATA NO DATA NO 04?A 1 20t.04 Y 9 t m. 8.10E-10 NO D AT A 2.7&t-Lt ho Data NO Cafa ho Cafa

2. f o t-06 Y-91 1.13t-04 40 D AT A

3. 0 l t.0 8 ho DATA 40 DAfa NO DATA 8 10t.05 Y 92 7.65C-09 NO DAT&

2.15 C.10.hD DATA NO DAf A 40 DAT&

t.46t.04 OD0589-1J33A-BA01-BA02

- ~ ~... -

=

.w.a.-.--.....

--..-.a....

- - ~. -. -.

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OFFSITE DOSF. CALCULATIONS TAh!.E 2.1 l

f IMilf f tA 90W F AC TOR $ F0a t he AAT thtta etL PCI I,4Ctattos

%VCL10t 60Nt,

tivtA f.000f THYR 010 st icht f L

01.LLI

...........................................................UNG y 93 2.43E-08 40 CATA 6.62C-10 NO CATA NO 0&fA ko DAf6 1.12 t 46 2n 15 2.06t.07 5.02C 08 3.16C-08 NO 04fA

5. 4 t t a.0 8 h0 D&fA 2.$0F45 la 97 1.48t-08 2.$4te09 1.16C-09 NO DATA 2.)6t-09 NO

......................w..................................CafA 1.62t-04 16 95 4 20t-08 1.71E*08 1.00C-08 40 Daft 1.24L42 ho CATA 1.46t-05 eso 99 h0 04f4 1.4Cl-05 6.6 3 C -0 6 NO DATA 5.081-05 40 DAfA 1.12( 4 5 TC 91p I J2 t- 09 3.961-09 5.10 E *0 6 NG 0&fA 4 26t-08

......................._.2.0ft.09 1.llt 06 IClot 2.211-09 2.86t-09 2.8 3t-0 4 NO 04fA 3.40t48 1.56f-09

4. 8 6t47 Rul03 1.48t-06 NO 04f4 4.95C-07 NO 04f4 1.08!.06 40 DATA l.00t-05 4Ul05 l.36t-07 NO CAf4

4. 5 8 C -0 8 60 04f4 1.00t-06 h S.4tt-09

.. 0 CATA 4U106 2.41!-0$ NO DATA

3. 0 l t -0 6 NC' OAIA

't.8$(41 h0 DAf6 1.83t-04 4Gilom 9496t-C7 7 2ft-Of 4.8 t f-0 7 NO DATA 1 04t-06 No DATA

3. 7 7f-05 ftl2bn 2.33t-05 7.791-06 3 l>t-0 6 7.44t-06 NO bata N

................................................... O CAfA l.11t-05 ft!277 $.85t.05 1.14t-05 f.0tt-06 1.69t-05 1.44! 4 4 h0 DATA 2.16t-09 ftl27 1.00t-06 1 35!-07 2.15 C -0 7 8.14E-07 2.44i 06 40 DATA 2.10t-05 i[129M l.00t-0*

3.43!-05 1 5 4 C-0 5 3 84E-05 2

.............................. ~...........<.. lot *04 h0 OAfA S.97t-0) fil29 2.84[ 4 ? 9.11t-08 6 63C-08 t.381-07 7.0ft-07 N0 DATA 2 2ft-05 TEl31P l.52t-05 6.12t*06 S.05 C.0 6 1.24t.09 4.21t-05 No DATA 1.03E-04 TEl31 1 76t-07

6. 5 0t-08

4. 94 C-0 8 1.>ft-Of 4.$

........................................... -.0t*07 40 DATA 7.llt 04 TE132 2.061 85 1 03145

1. 6 t t -0 6 1.12F45 6.44t-05 No CATA 3.8tt.03 1 130 6.00t.06 1 32t45

1. 30C -0 6 1.48t*03 1.45t 45 N0 DATA 2.85t-04 l 131 3 59t 4. 2 3t-05 1.46t-OS l.31E-02 4

............-............................... 94t-91 %0 DATA 1.11t-06 I 132 1,66( 4 6

3. lf f-C6 1.20C-06 1.58t-04 1.161-06 h0 DATA 2.73C-06 1 133 1.251-05 1.82t-05 1.3tt-06

3. Alt-0) 2 14t-05 h0 CATA 3.08E-06 1 134 8.691-07 1 78t46 6 3 3 C-0 7 4.151-05

......................e.........1.99C-06 h0 CATA 1.84t-06 I 135 3.64t-06 7 24t-06 2 44 C-e 6 6.49t-04 9.0ft.06 ho CATA 6.62t-06 C1134-3.77t-04 7.03t-04 7.10 E-C S NO DATA l.8tt-04 f.42t-05 1.4tt-06 C1136 4.59t=0$

l.llt-04 S.04 C-0 5 NO DATA S. 3 e t 'M 1 10!-05 2.0 5t44 C$117 S.22t 44 6 1t[ 04 4.13 C-0 5 NO DATA 1.64t-04 6.64t-05 1.9 t t 44 C1138 4.8tt-07 7.82t-of 3 79t-0 7 NO DATL 3.90C-07 6.09t-08 1.2 5t-06 8A139 8.81C-07 5 84t-10 2 5$t-08 No DATA

3. SIC-10 3.14t.10 $.58t4$

i

.h I

OD0589-1333A-BA01-BA02 I

i 1

VOLUME 25 BIC ROCK PolNT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS fage 73 of 94 l

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OFFSITE DOSE CALCULA7 IONS i

t TABLE 2.1 i

)

f f

I l

)

i INCC111010052 F4Cidt$ FC9 thrANT i

tra(M Ftt #Cl thCESit04

{

1UCt t0!

00NC LivtA f.ACC' KIONtY tuNC j

.......................................Tkf40io..............................C l L t Sat 49 t.Ftt.04 t.ftt-07

8. Alt-0 6 NO Cafa 4.C6t.06 1.0SE*07 4 20t-05 paint 4 25t 07 2.912 10 1 34t-08 NO 0&ta 1.f5t-10 1.ffE*l0 S.19t-06 pat 42 t.84t 07 t.5)t-10 9.06t-

.NO 04fA S.Itt 9.26

........_..................... 09 l

............................t-1i f.59t-07 LA140

2. tit-08 8.11E-09 2 14t-09 NO 08tA No DATA NO DATA 9.fft-05 Lat42 1 10t-09 4.06t-10--9.6ftall NO DS L'. NC DATA No DAf4 6.86t.0$.

CC141 f.87t-08 4.80!-08 S.64t-01 NO DATA 1.48t-09 ko DATA 2.481 05 C;143 1.48t-08 9.82C-04 1 12 C-09 N0 DafA

?.96i-09 N0 DATA S.7)t=0S Ctt44 2.58E-06 1.22C-06 1.6ft-07 40 Otta 4.9)t.07 No DATA t.ftt.04 PAlt) 8 13t-08

).C4t-08 4 NO DifA l '.13 t.nl N

............................ 0 t t -0 9...........................

.O DATA 4 29C-05 PR144 2.76t.10 1.06t-10 1.1tt.11 No cafa 3.44t.it N0 DATA 4.9)t.06 1

N0147 S.5)t*08 S.68t-08

3. 4 8 t -0 9 No CATA 2 11t-08 40 DATA-1.60[-05 i

w 187 9.0)( a 0 7 6.2si.07 2 1ft-No 04fa NO 04f4 40 1.69t-09

...............................0f...........-.......

.....0*f4 j

iP23%

l.llt-Of 9.9)t-10 S. 6 t t-10 NO DATA 1.94t-C9 NO DAf4 2.lft-05 3

\\

l

?

OD0589-1333A-BA01-BA02

VOLUME 25 BIC ROCK POINT RADICLOGICAL Revision 8 EFFL')ENT T/S REQUIRED DOCUMENTS Page 74 of 94 A.

OFFSITE DOSE CALCULATIONS Table 2.2 i

BIC ROCV POINT DES!CN OBJECTIVE ANNUAL QUANTITIES FOR LIQUID EFFLUENTS AS DETERMINED BY LADTAP t

Design ob)cetive annual quantities for liquid effluents were calculated utilizing the computer code LADTAP, a program for calculating radiation exposure to mer f rom routine releases of nucicar reactor liquid ef fluents (reference NUREC/CR-1276).

Input parameters used are as follows:

Process Times Pathwal Age Group Usage Dilution (Hr)

Fish Adult 21.0 kg/yr 15.0 24.0 Teen 16.0 15.0 24.0 Child 6.9 15.0 24.0 Infant 0.0-15.0 24.0 Drinking Adult 730.0 L/yr 800.0 16.6 Teen 510.0 800.0 16.6 Child

$10.0 800.0 16.6 Infant 330.0 800.0 16.6 I

Shoreline Adult 12.0 hr/yr 2.0 0.0-1 Teen 67.0

?.0 0.0

[

Child 14.0 2.0 0.0 l

Infant 0.0 2.6 0.0 l

l Swimming Adult 12.0 hr/yr

?.0 0.0 l-Teen 67.0 2.0

-0.0 l

Child 14.0 2.0 0.0 Infant.

0.0 2.0' O.0 Boating Adu!t 100.0 hr/yr 15.0-0.0 Teen 100.0 15.0 0.0 l

Child 50.0 15.0 0.0 i

Infant 0.0 15.0 0.0 N c-age figures are obtained from' Regulatory Guide 1.109 and are default

.i '

s.

Dilutions.and the process time for drinking water were taken f rom the WG utudy dated June 4, 1976. The' minimum process times that can'be utilized.

for fish and drinking are 24.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> and 12.0-hours -respectively.

The federal limit to unrestricted areas for any int *ividual through the liquid i

pathway isl3 mrem, total body, and 10 mrem to any organ;(Referen:e Part. 50, Appendix I).

The attac' hed table lists the design quantities as calculated from LADTAP.

OD0589-1333A-BA01 OA05 l

~,- - --- - -. = - -

I J

i l

VOLUME 25 BIC ROCK p0 INT RADIO!,0CICAl.

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OFFSITE LOSE CALCULATIONS i

j Table 2.2 j

Bic ROCK POINT DESIGN OBJECTIVC ANNUAL QUANTITIES F02 I

LI-QUID EFFLUENTS AS DETERMINED BY LADTAP 3

i^

The following input parameters are used when running LADTAP for BRPI

(

1.

50-mile population - 1.54E05 l

I 2.

Shore width f actor - 0.3 3.

Total discharge (ft'/sec) - 109 4.

Transit time for all pathways - 4.6 l

l 5.

Sport fish harvest (kg/yr) - 3.29E05 1

6.

Commercial fish harvest-(kg/yr) - 1.70E05 i

i 7.

Invertebrate and algae consumption - 0 i

8.

Drinking water population - 7.07E03 i

l 9.

Shoreline population usage (man-hours) - 3.8E07 i

10.

Swimming population usage (rnan-hours) - 1.2E07 11.

Boating population usage (man-hours) - 3.7E07 i

i OD0589-1133A-BA01-BA05 O'

. _,... _.., - -... _, _ - -.. =, - - _ _. _, - - -. _,.. -

..a~.-

VOLUME 25 BIC ROCI' POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUlHED DOCUMENTS Page 76 of 94 A.

OFFSITE DOSE CALCULATIONS Table 2.2 BIC ROCK POINT DESIGN OBJECTIVE ANNUAL QUANTITIES FOR LIQUID EFFLUENTS AS DETERMINED BY LADTAP Design Objective Dose Conversion Annual Quantity Nuclide Factors (mrem /Ci)

Individual /0igan (Curies) 6 11 - 3 2.34E-06 Adult /TB 1.282 x 10 Na-24 3.95E-03 Teen /TB

'759.49 Sc-46 1.24E-02 Teen /TB 241.94 Cr-51 1.90E-03 Adult /Cl (LLI) 5,263.16 Mn-54 8.39E-02 Adult /CI (LLI) 119.19 Fe-55 5.50E-03 Child / Bone 1,818.18 l

Hn-56 1.22E-05 Teen /TB 2,459.02 Co-57 2.80E-03 Teen /TB 1,071.43 l

Co-58 6.95E-03 Teen /TB 431.66-Fe-59 4.93E-02 Adult /Ji (LLI) 202.84 i

Co-60 2.90E-01 Teen /TB 10.34 i

Cu-64 1.48E-03 Teen /CI (LLI) 6,756.76-i Ni-65 3.82E-04 Teen /TB 7,853.4 i

Zn-65 2.16E-01 Child /TB 13.89 Br-84 1.33E-03 Teen /TB 2,255.64 1

j Rb-86 3.75E-01 Child /TB 8.0 Rb-88 4.54E-04 Teen /TB 6,607.93 Sr-89 1.93E-01 Child / Bone 51.81 Sr-90 3.34E+00 Adult / Bone 2.99 l

Sr-91 2.90E-03 Teen /CI-(LLI) 3,448.28 I

i l

r l

l s

Op0589-1333A-BA01-BA05'

VOLUME 25 B10 ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 77 of 94 A.

OFFSITE DOSE CALCULATIONS Table 2.2 BIC_ ROCK POINT DESICN_0BJECTIVE ANNUAL QUANTITIES FOR LIQUID EFFLUENTS AS DETERHINED BY LADTAP Design Objective Dose Conversion Annual Quantity Nuclide factors (mrem /Cl)

Individual / Organ (Curies)

Sr-92 9.94E-04 Teen /TB 3,018.11 Y-92 1.76E-04 Teen /TB 17,045.5 Nb-95 8.88E+00 Adult /Cl (LLI) l'13 Zr-95 3.82E-03 Teen /TB 785.34 Nb-97 4.56E-04 Teen /TB 6,578.95 Zr-97 2.74E-03 Teen /Cl (LLI) 3,'49.64 Ho-99 1.31E-03 Teen / Kidney 7,633.59 Tc-99m 9.33E-05 Tecn/TB-

_32,154.3 Ru-103 1.69E-03 Teen /TB-1,775.15 Ag-110m 4.76E-02 Teen /TB 63.03 Cd-113m 7.38E-02 Adult /C1 (LLI) 135.50-Sb-124 9.34E-03 Teen /TB 321.20 Sb-125 3.13E-02 Teen /TB 95.85 Te-127 9.04E-03 Teen /CI-(LLI) 1,106.19 Te-12?m 1.71E-01 Teen / Kidney 58.48' Tc-129m 3.27E-01 Adult /CI (LL1) 30.58 I-130 1.40E-02 Child / Thyroid 714.29 I-131 4.07E-01 Child / Thyroid 24.57 Te-131m 2.78E-01 Adult /CI (LLI) 35.97 I-132 1.95E-05 Teen /TB 1.538 x 105 Te-132 3.59E-01 Adult /CI (LLI) 27.86 I-133 4.85E-02 Child / Thyroid 206.19 Cs-134 3.49E+00 Adult /TB 0.8596 I-134 1.59E-03 Teen /TB 1,886.79 1-135 1.91E-03 Child / Thyroid 5,235.6 Cs-136 5.0$E-01 Adult /TB 5.94 Cs-137 2.08E+00 Adult /TB 1.44 Cs-138 1.52E Teen /TB 1,973.68 Ba-139 3.0$E-05 Teen /TB 98,360.7 Ba-140 2.75E Adult /CI (LLI) 3,636.36 La-140 2.27E-02 Adult /G1 (LLI) 440.53 Ce-141 2.30E-04 Teen /TB 13,043.5 Ce-144 4.08E-03 Adult /CI (LLI) 2,450.98 Eu-152 1.99E-01 Teen /TB 15.08 W-187 2.43E-01 Adult /Cl (LLI) 41.15 Np-239 2.78E-03 Adult /GI (LLI) 3,597.12 OD0589-1333A-BA01-BA05

._=...

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/5 REQUI"ED DOCUMENTS Page 78 of 94 A.

OFFSITE DOSE CALCULATIONS by(bus t

IAK #

Ai_1_t u i e, a u

" LICOID E' ABOVE

~

m 2W~

t i

. },

RELEASE k

W b# ANNE SEA LEVEL I

,p 6

i 8

• p

hv s

\\

% D

)

iz la C

BW $

'f

/

s

~ ?.

+y

/#

./

yp s_,

g

/,/

L=*

-.e.....

/

/

a

/g y

~ von nc,~ r g.,,gs,

}

y-q<ve mn

/

R ure

4. _t 4

3

/

%. j pLOCATION p am y

OD0589-1333A-BA01-BA02 5

}

I VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 l

EFFLUENT T/S REQUIRED DOCUMENTS Page 79_of 94

)

A.

1FFSITE DOSE CALCULATIONS 1

III.

URANIUH FUEL CYCLE DOSE i

^

ll!.A SPECIFICATION in accordance with Technical Specifica* ion 13.1.6.1, if either

)

liquid or gaseous quarterly releases exceed the quantity which would cause offsite doses more than twice the limit of Technical Specification 13.1.4, then the cumulative dose contributions: f rom combined release plus direct radiation sources (from the reactor I

unit and radwaste storage tanks) shall be calculated. This calculation is performed to ensure that the annual (calendar year) dose or dose commitment to any member of the public is $25 mrem to t'.e total body or any organ, except the thyroid, which shall be 575 mrem. The dose is to be determined. for the member of the public projec 41 to be_the most highly exposed to these combined sources.

If the results of this calculation show t he ' dose to exceed either the 25 or 75 mrem limit, a special report shall be prepared and submitted to the Commission within 30 days, as described in Technical Specification 13.1.6.1.

i III.B ASSUMPTIONS Ill.B.1 The full time resident determined to be the 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.4.1 and II.C.4.2.

III.B.2 Amount of shoreline fishing (at accessible shoreline adjacent to site secerity fence) is conservatively assumed as 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> per quarter (average of approximately 1/2 hour per day each day of the quarter) for the sece,d.tnd third quarters of the year, 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> for the fourth quarter and 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> for the first quarter.

Ill.h.3 The dose contribution due to uranium fuel' cycle sources other than the plant, is ignored in the calculation. This is based on the i

lack of any operations that fall in the " cycles" definition within a 5 mile radius of Big Rock Point.

5 OD0589-1333A-BA01-BA05

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OFFSITE DOSE CALCULATIONS r

Ill.C DOSE CALCULATION Maximum doses to the total body and internal organs of an indi-vidual-shall be determinei by use of LADTAP-and CASPAR computer codes, and doses to like organs and total body summed. Added to j

this sum will be a mean dose rate, calculated or measured for the shoreline due to plant presence during the quarter in question, times the assumed fishing time!

Do.=DC+DL + (R )(T)

(111.1) 4 T

1

+

where!

D o, = 40 CFR 190 dose to organ (i) (mrem).

4 1

i i

Dc = Cumulative dose to an individual organ from gaseous releases (mrem).

4 DL = Cumulative dose to an individual organ f rom liquid releases (mrem).

RT = Hean dose rate (direct radiation component) calculated to l

be applicable to 1.ake Michigan shoreline adjacent to plant site (mrem /hr).

T = Assumed shoreline fishing time for the quarter in question (hours) (see Section-Ill.B.2).

NOTE:

For this calculation, total body is considered as an. organ.

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APPENDIX A 1

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DISCllARCE CANAL DREDCING COMMITHENTS 4

AND REPORT!NC REQUIREMENTS t

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OFFSITE DOSC cal,CULATIONS APPENDIX A DISCHARGE CANAL, DREDCING COMMITMENTS

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AND REPORTING REQUIREMENTS i

j 1.

COMMITHENTS AND REPORTINC REQUIREMENTS l

j Conenitments related to Discharge Canal Dredging are given in the CPCo December 29, 1989 Application for Disposal of Dredged Distnarge I

Canal Sediment and in the NRC Safety Evaluation dated August 31, 1990.

3 1.A COMMITHENTS i

1 1.A.1 Prior to dredging the canal, radionuclide concent rations and environmental exposure pathway doses must be evaluated in a manner j

equivalent to that described in the CPCo December 29, 1989 application.

I This evalu4 tion must include a comparison of resultant doses with-f the following NRC staf f guidelines for onsite disposalt t

l.

The radioactive material should be disposed in a manner such j

that i t. is unlikely that material would be recycled.

2.

Doses to the total body and any body organ of the maximally-exposed individust (a mernber of the general public or a non-occupationally exposed worker) f rom the probable pathways 1

of exposure to the disposed material should be less than I mrem /yr.

4 3.

Doses to the total body and any body organ of an inadvertent i

intruder f rom the probable pathways of exposure should be less j

than 5 mrem /yr.

i 4.

Doses to the total body and any body organ of an individual f rom assucied recycling of the disposed material at the time the disposal site is released f rom regulatory control f rom all likely pathways of exposure should be less than 1 mrem.

l.A.2 The dredging spoils will be thoroughly surveyed using a gamma-sensitive inetrument prior to release for publit use.

Release for public access will be contingent upon confirmation that post-disposal area dose rate has not increased above

~

pre-disposal area background, as defir.ed by criterion _ that pre-and post-disposal levels vary by not more than 251. The value of 25% allows for temporal variations observeo in monthly environmental 4

4 TLD b6ckground dt.ta.

l.A.3 Quality Control surveillance will be performed to ensure-the 1

dredge mater!al is deposited in the location specified in the Dredging permit and is graded accordingly.

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OFFSITE DOSE CALCULATIONS APPENDIX A DISCHARCE CANAL DREDCING COMMITMENTS AND REPORTING REQUIREMENTS 1.A.4 Confirmatory measurement s of the dredged materials will be recorded af ter the dredgings are land-spread.

1.B REP 0;TINC REQUlkEMENTS 1.B.1 If the NRC staf f guidelines in I. A.1 can not be met, a new application per 10 CFR 20.302 must be submitted for the disposal.

1.B.2 Should the measurement of I.A.2 and I.A.4 indicate that the levels of radioactivity measured in the pre-operational (pre-dredging) sediment samples were significant underestimates (greater than 25%)

of the actual radioactivity of the dredging spoils, CPCo will notify the NRC. The NRC will then reassess possible radiation doses and require appropriate remedial actions as appropriate.

II.

PRE-DREDCINC REQUIREMENTS Mechanical dredging of Big Rock Point's Discharge Canal introduces a potential of re-releasing radionuclides absorbed on sediment to the environment in a manner not already accounted for in release records.

II.A Disposal oi dredging spoils by relocation f rom the plant discharge canal to an unrestricted area onshore as specified by Corps of Engineers Permits Numbers 88-56-143 and 87-56-185 has been reviewed in the approved NRC Safety Evaluation dated August 31, 1990.

If a new permit is to be used for dredging, review the permit requirements to ensure no unreviewed exposure pathway has been created.

II.B Prior to dredging the canal, a minimum of 10 sediment samples shoulo be collected. The distribution of the sample points should be representative of the area to be dredged. Sediment sample collection should be coordinated with plant operations to ensure there are no radioactive liquid batch releases during or within the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> previous to sediment sampling.

II.B.1 The concentration and total activity of the material to be dredged will be determine for each isotope identified in the sediment samples. Results of semi-annual sediment samples taken from the canal discharge since the time of the previous canal dredging may be used to aid in evaluation of the sediment activity below the immediate surface.

11.B.2 These evpecteo activity concentrations will be compared to the activit'es given in Table A-1 Snd will be used as the basis for comparison to the total capor-as given in Tab;e A-2.

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DISCHARCE CANAL DhdDCINC COMMITHENTS AND rep 0RTING REQUIREMENTS 1

II.C If any isotopes not listed above are present in the.rdiment samples, the dose cont ribution f rom these isotopes must be j

determined for all exposure pathways in a manner equivalent to the calculations used in the December 29, 1989 application which are outlined in Section V.

4 II.D The calculated doses will be_ compared to the NRC staff guidelines given in Section I. A.I.

If any of these guidelines can not be-l met, the disposal of the particular dredging will be deemed to be j

outside the scope of the 10 CFR 20.302 review already approved by j

the NRC in the safety Evaluation dated August 31, 1990.

In this event, a new application for disposal will be submitted to the NRC I

for this particular dredging or an alternative disposal method will be pursued.

11..

A pre-dredging survey of the disposal area should be provided no j

more than 10 days prior to dredging to provide a baseline for comparison to post-dredging survey.

I II.F Dredging operations should be coordinated with plant operations to ensure no liquid batch releases within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to dredging and no liquid batch releases during the time period of the dredging.

1 Ill.

p0ST-DREDCINC REQUIREMENTS I

Ill.A A post-dredging survey of the area should be provided no more than l

10 days af ter the spoils are lar.d-spread.

Should these measurements i

indicate the activity in the disposal area has increased greater than 25% of the pre-dredging activity, the NRC will be notified.

III.B Sediment samples will be analyzed and recorded as confirmatory measurements of the dredged materials af ter the dredgings are land-spread.

Should.these measurements indicate that the levels l

of radioactivity measured in the pre-operational (prr Jredging) sediment samples were significant underestimates (greater than 25%) of the actual radioactivity of the dredging spoils, the NRC

+

will be notified. The NRC will reassess possible radiation doses and require remedial actions as appropriate.

IV.

DOCUMENTATION REOUIREMENTS Records of survey and sampling r esult s shall be maintained until the NRC' authorizes disposition.

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APPENDlX A DIScilARCE CANAL DREDGINC COHHITHENTS AND REPORTINC REQUIREMENTS V.

EVALUATION OF Tile RADIOLOGICAL IMPACTS OF SEDlHENT DISPOSAL Potential exposure pathways due to dredging and disposing of sediment from the BRP Discharge Canal include:

1.

external exposure to the sediment during dredging, 2.

groundshine in the disposal area, 3.

Inhalat ion of re-suspended isotopes f rom dried sediment blown i

by the wind, 4.

exposure f rom assumed infilt ration and contamination of groundwater, and 5.

internal exposure f rom ingestion of food grows: on the disposal.

site.

The maximum exposure to workers will be to those workers involved j

in grading the sediment in the disposal area during the dredging operations. The dose to these workers is determined as groundshine in the disposal area (exposure pathway 2).

Exposure f rom assumed infiltration and contamination of groundwater is of minimal concern in this case on the basis of location.

ad,)acent to Lake Michigan. There are no wells in either potential disposal area or between the disposal trea and Lake Michigan

.(direction of groundwater flow).

Exposure to the general public from activity released to Lake Michigan-via this pathway is accounted for in Big-Rock Point Semiannual Radioactive Effluent Release Reports based on data at the time of the original l'. auld radioactive releases from which the dredged activity is derived.

The activity absorbed on the sedin.ent removed from the canal and re-released to Lake Michigan via this pathway will not i.ncrease those original. exposure estimates.

Even though these doses have been' accounted for previously, estimates due'to potential radionuclide release from the spoils is included in radiological impact calculations.

Internal exposure f ror ingestion of f ood grown on the disposal 1

site l's not of concern due--to lack of nutrient content within this washed-stone / gravel / sand misture..The disposal sites also are unprotected f rom harsh of f shore winds. Cultivatable vegetation is not supported in either area.

Conservative calculations of external exposure during dredging, liquid pathways, groundshine in the disposal area, and inhalation of dried windblown sediment are detailed below.

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APPENDIX A DISCHARCE CANAL DREDCINC COMMITHENTS l

AND REPORTINC REQUIREMENTS l

V.A External Exposure to the Sediment during Dredging and Croundshine 3

in the Disposal Area 1

Assume the worker is exposed a total of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6 The disposal area may be part of a nature trail open to the public.

Assume time spent on the nature trial is half the average time spent for shoreline recreation (per Regulatory Cuide 1.109) i Child 7 hr/yr Teen 34 hr/yr (this is taken as-maximum public exposure time)

Adult 6 hr/yr it is reasonable to assume plant personnel using the t rail for walks during work breaks also will itequent the area of ten.

t = 2 walks / day x.25 hr/valk x $ days / week x $0 week /yr t = 125 hr/yr Howevert due to weather conditions, the trails will be accessible only 3 months per year.

t = 31 hr/yr (since this is not as long as the teen usage time calculated above, the 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> for teen exposure la used for dose to public.)

Using methods and parameters described in Regulatory Guide 1.109, the dose DC (r, 0) to the worker is given-ast J

DC (r, 0) = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SF l[__,'C?(r, 0) DFCij i'

i 8

i i

8 Where Ci is in [pci/m ]

DFC = open field groundplanc dose conversion factor

[ mrem-m'/pci hr).

Valves of DFC are given in ODCM Table 1.8.

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APPENDIX A DISCHARCE CANAT. DREDCING COMMITHE!; f S i

,AND REPORTINC REQUIREMENTS i

l SF = Shielding Factors The thickness of sedicent graded out in the disposal-erea will range from 2 to 4 incaes. Assuming the minimal shielding (ie, 2 inch thichness' there will be approximately 1 inch of sediment as sh.elding.

l From American Institute of Steel C

.n. ruction (AISC)' Hat. mal of Steel Construction 7th Eoition p dry sediment = 90 to 105 lb/ft' for excavated P rd and

' ravel j

dry and loose taking p ot; sediment as 98 lb/ft'

>p

1.57 g/cc (p/o)Co60 = 0.0578 cm*/g dry

=

i sediment dry sediment = 1.57 g/cc x 0.575 s'

p dry sediment = 9.07E-02 cm'I SF = e-P* = e-9.07E-02/cm (2.54 cm) 9F = 0.79 Ci = P-

. t 'ivity [pCi/m*]

= act. i ty [pci/g) x p dry sedimenc [g/cc) r 106 cc/m3 x

thicknes.t of layer (2" or 5.08E-02 m)

Ci [pCi/m*] = 7.90E+04 x activity [pCi/g) l l

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APPENDIX A-DISCHARCE CANAL DIEDCING COMMITHENTS AND REPORTINC REQUIREMENTS Assuming dredging is performed annually and each year the new 1

sediment is deposited and spread to 2" over the previous sediment, the groundshine exposure tach year will increase as C

C

~AII Yrl -p(2") + DC total D year two = D year one Be e

year two J

J J

C

-A(2 YF)e~P(0")

total DC year threc = D year one Be J

J 4

i 9

~ACI YT)e~PI2") + DC

+D year two Be year three g

J J

i e

i etc C

C 5

But D year n = D year one J

J l

i Therefore 1

I 10 j

total D year ten = D year one I e~A(""1) e-p(2")(n-1) B[2(n-1)p]

C C

n=1 The accumulative dose each yaar will increase.as i

X C

C i

D year x = I D year n J

3 n=1 i:

B = Buildup = 2 + a (pX) + b (pX)* + c (pX)*

Where for Mn54

-a = 1.04 b = 0.21 c=0 l-Co60 a_= 0.78 b = 0.08 e=0 i

Cal 34 a = 1.07' b = 0.28 c=0 Cs137 a = 1.07 b = 0.14 Le = 0 i

Doses to the most exposed member of the public-(teen exposed 34 hrs /yr) are 34/24 = 1.42 times-the worker. doses.

Buildup f actors for gamma emitters not-listed above can be-i obtan.ed using tl.e Table A-3.

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DISCliARCE CANAL DREDCING COMMITHENTS' AND REPORTING REQUIREMENTS V.B

_ inhalation of Re-Suspended Isotopes f rom Dried Sediment Blown by

{

Wind 4

Using methodology of Regulatory cuide 1.109, the annual organ dose j

from inhalation of radionuclides in air ist DA (r,0) = Ra I xi (r,0) DFAija

{

Ja g

i Where DFAlja = inhalation dose factor (mrem /pC1]

1 i

Values of DFA given in ODCH Table 1.7.

3 l

Ra = annual intake for individual [m /yr) l 3

Ra infant = 1400 m /yr Ra child = 3700 m /yr 3

8000 m /yr Ra teen, Ra adult

=

i Xi=antiualavegageconcentrationofradionuclidein air (pci/m }

i i

Prom Maik's Standard Handbcok for Mechanical Engineers i

(pg. 18.12).

The amount of suspended matter in normal-city 3

air = 1.37 mg/m and the amount of suspended matter in 3

manufacturing plant = 4.58 mg/m o

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OFFSITE DOSE CALCULATIONS APPENDIX'A DISCHARCE CANAL DREDGING COMNITMENTS AND REPORTINC REQUIREMENTS Using the value for suspended matter in normal city air would be j

conservative considering that fresh clean air blows off Lake Michigan acrors the disposal site.to re-suspend isotopes f rom the oried sedimant.

Assuming a gentle breeze throughout the year since individuals would not remain in the area if higher winds blowing the sand were present.

For added conservatism the value for suspended matter in a manufacturing plant is osed.

l The maximum time an individual would be in the area is 260 i

hours /yr ao determined for fisherman by the discharge canal (RAE 81-53). Therefore the annual intake for each individual is reduced by the factor f.

)

(,260hr/yr j

8760hr/yr

}

f = 0.03

Then, 3

3

.001 g/mg x activityi [pci/gm) x.03 Xi (pCi/m ] = 4.58 mg/m x

i V.C Exposure from Infiltration and Contamination of Groundwater

~

i There are no wells in or near the disposal sites Ground water flow is toward Lake Michigan at a rate of 0.05 f t/ day (per FHSR)

The distance f rom the nearest edge of the west side disposal l

site (Permit Number 87-56-185) to Lake Michigan is -14 ft.

The distance f rom the nearest edge of the east. side disposal a.e (Permit Number 88-56-143) to take Michigan is 25 ft.

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OFFSITE DOSE CALCULATIONS APPENDIX A DISCilARCE CANAL DREDCING COHNITHENTS AND REPORTING REQUIREMENTS The ratention time for radionuclides deposited at the we.t side disposal site ist 14 ft i 0.05 ft/ day = 280 days minimum ano for the cast side disposal site is 25 ft i 0.05 ft/ day = 500 days minimum in the interest of conservatism, we assume all the radionuclides f rom a single dredging will be released f rom the disposal area into Lake Michigan, 280 days af ter dredging.

Dose calculational methods from the Big Rock Point Radiological Effluents Technical Specifications Offsite Dose Calculations Manual (ODCH) for liquid ef fluents are used to determine the annual dose to individuals exposed via this pathway, t

The total exposure f rom this pathway is calculated in the 1989 10 CFR 20.302 Submittal, using the ratio of annual DBQ fraction representing activity of dredging to annual DBQ fraction representing total annual liquid release activity. This fraction is used to determine total exposure based on the annual liquid effluent exposure determined using the LADTAP code.

2 DBQ dredging Dose from drtdging annual liquid Pose from LADTAP)

DBA annual release This method is conservative. A more accurate method to estimate dose from infiltration and contaminatior of ground water is provided in ODCM Section 11 C for all liquid exposure pathways.

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TABLE A-1:

3ADIOLOCICAL PROPERTIES OF SEDIMENT (pCi gm)

/

j VARIATION TOTAL t NUCLIDE AIN) TO (HAX)

AVERACE VARIANCE (s)

ACTIVITY (mCj) i Sr 90 0-0.108 0.015 0.032 0.011

.Mn 65 0-1.996 0.202 0.312 0.147 Co 60 0-4.904 0.431 0.785 0.314 Cs 134 0-0.070 0.001 0.002 0.001 l

Cs 137 0.170-1.583 0.605 0.309 0.441 fe 5.90-17.50 9.696 3.225 7.07 4

• Average Cross Beta at control sampling. location (Ludington) =

8.19 with variance of 3.07 [pci/gm wet).

Therefore, no unidentified beta emitters present.

Exposure due to beta j

activity is taken into account in dose calculations for specific Isotopes.

t Total Activity = Average Concentration (pC /gm wet) x max mass A

b excavated (gm) x (ImC /10 pCi).

i 2

l Assuming 500 cubic yards excavated with density l

of 119 lb/ft3 (density of excavated sand, gravel i

vet = 118 to 120 lb/f t3 per AISC Manual of Steel i

Construction 7th Edition) 3 3

Max mass excavated = 500 cu yard (27 ft /cu yard) 119 lb/f t x

(453.592 g/lb) = 7.29E+08 gm.

These analyses include samples taken annually from 1985 through 1989 as part of Big Rock Point's Radiological 2nvironmental Monitoring j.

Program as well as ten-(10) samples taken in June 1989 to ensure samples are representative of activity distributed throughout the j

canal. The results of these analyses-provide a conservative estimate 2

of the activity which may be contained in the sediment at the time of dredging. The total activity o.f the sediment is based on the average 3

activity concentration encountered in surf ace samples (see Appendix 1).

J n

i 3

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APPENDIX A DISCHARCE CANAL DREDCING COMMITHENTS AND REPORTINC REQUIREMENTS TABLE A-2:- RADIOLOGICAL. IMPACT OF SEDlHENT DISPOSAL -

SUMMARY

OF VALUES CALCULATED IN APPENDIX 2 Integrated Exposure Du:.

Exposure due to to Annual Dredging _

Exposure Pathway Single Dredging (mrem /yr's through 1998 (mrem)

External Exposure to Sediment During Dredging (worker) 2.13E-02 5.83E-Ol' External Exposure Due to Croundshine in the Disposal Area (public) 3.02E-02 8.27E-01 Internal Exposure g

Due to Inhalation of Resuspended Isotopes 8.67E-04 8.67E Exposure from Assumed Infiltrat.on and Cxtamination of-Croundcater 3.33E-03 3.33E-02 Total Exposure 5.57E-02 mrem

• 1.44 mrem /10 yrs first year

• NOTE: The total exposure is extremely conservative'since no individual will-receive-the total exposure from each pathway.--

NRC did not include external. exposure to sediment during dredging (worker) in the totals approved-in the safety evaluation dated August' 31, 1990. --Total doses to the general

. public of 3.57E-02 mrem / year and 8.57E-01 mrem / ten years were

-accepted.

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l APPENDlX A j

DISCHARCE CANAL. DREDCING COMMIThENTS E

AND REPORTING REQUIREHENTS TABl.E A-3:

B'JII. DUP FACTOR PARAMETERS l

Average Camma PARAMETER l

Energy (MeV)

A B

C 0.5 1.10 0.385 0

l.0 1.02 0.122 0

2.0 0.76 0.046 0

4.0 0.55 0.008 0

6.0 0.42 0.007 0

8.0 0.33 0.006 0

10.0 0.28 0.006 0

i These valves are based on results from MLTobias, DRVondy, and HPLietzke; Nightmare Program; Oak Ridge National Laboratory, February 26, 1972. Parameter valves have been interpolated

^

for concrete (z of material = 11),

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i I

f i

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