ML20137X732

Revised Offsite Dose Calculation Manual

ML20137X732
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	02/17/1986
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20137X724	List: ML20137X722 ML20137X729 ML20137X732
References
PROC-860217, NUDOCS 8603120003
Download: ML20137X732 (29)

Text

.. _. _.

ATTACHMENT Consumers Power ' Company Big Rock Point Plant Docket 50-155 4

L f

i BIG ROCK. POINT PLANT OFFSITE DOSE CALCULATION MANUAL Effective February 17, 1986 Revision i

(

i I

i 4

)

l 28 Pages i

IC0286-0037-NLO4 B603120003 860228 PDR ADOCM 05000155 R

PDR

1 I.

GASEOUS EFFT.UENTS A.

ALARM / TRIP SETPOINT METHOD l

Technical Specification 13.1.3.1 requires that MPC is not exceeded when averaged over a period not to exceed I hour. Based on the definition of MPC, the dose rate 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 from noble gases.

2.

1,500 ores /y to any organ from radioiodines and particulates, due to inhalation.

Specification 13.1.1.1 requires gaseous effluent monitors to have

. alarm / trip setpoints to ensure that offsite concentrations,.when

~

averaged over 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, will not be greater than MPC. This section of the ODCM describes the methodology that will be used to'deterstne these setpoints.

The methodology for determining alarm / trip setpoints is divided into two major parts. The first consists of calculating an allowable concentration for the nuclide mixture to be released. The second consists of determining monitor response to this mixture in order to establish the physical settings on the monitors.

1.0 Allowable Concentration The total MPC-fraction (R ) f r the single (stack) release point k

will be calculated by the relationship defined by Note 1 of Appendix B, 10 CFR 20:

R(k)

• MFC MIO784-0004A-RS06 t

k k

L

8 4.

Basic radionuclide data are given in Table 1.2.

5.

All releases are treated as elevated (73a).

6.

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

7.

Raw meteorological data for elevated releases consist of wind speed and direction seasurements at 71a.

8.

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

9.

Actual cow, goat and garden locations are considered.

10.

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

11.

Terrain effects are not considered.

12.

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

13.

Radio, active uecay is considered for ground-concentration calculations.

14.

Milk cows and goats obtain 100% of their food from pasture grass May through October of each year.

15.

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

1.2.2 Equations

~

To calculate the dose fe.any one of the potential maximum-exposure points, the equations of Sections 1.2.2.1 - 1.2.2.4 are used.

1.2.2.1 Inbelation F

Equation for calculating air concentration, X, is the same as_in the

.VobleGasSection1.1.2(Equation 1.3).

l l

MIO784-0004A-RS06 t

9 For determining the organ dose rate:

g = 1x10s X DFI BR (I.7)

D g

g i

where:

O

= organ dose rate due to M alation, areely.

g X

= Air concentration of radionuclide i, pCi/m. 3 g

DFI

= Inhalation dose factor, ares /pci (Table 1.7).

g 3

3 BR

= Breathing rate 1400 m /y, infant; 5500 a /y, child; or 3

8400 m /y adult.

1 x 10s

= pCi/pci conversion factor.

1.2.2.2 Ground Contamination For determining the ground concentration of ar.y nuclide:

7 7

Gg = 3.15x10 f 9 DR k i (2nx/n) A

[1-exp -(A t )I g

g b (exp

-h2

)

(I.8) k=1 202 where:

G

= Ground concentration of radionuclide i, pCi/m,

a g

k

= Stability class.

f

= Joint relative requency f occurrence winds in k

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

Q

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

i DR

= Relative deposition rate, a2 (Table 1.3 for DR/2aX).

x

= Downwind distance, s.

n

= Number of sectors, 16.

2nx/n

= Sector width at point of interest, m.

A

= Radioactive decay coefficient of esdionuclide i, y'1 g

t

= Time for buildup of radionuclides on the ground, 35 y.

b 3.15x107

= s/y conversion factor.

h

= Stack height (73m) z o

= Vertical dispersion coefficiert (m)

MIO784-0004A-RS06

to For determining the total body or organ dose rate from ground contamination:

8 o = (8,760)(1x10 )(0.7)

G DFG (I.9) g g

g I

where:

D

= D se rate due t ground contamination, area /y.

G G

= Ground concentration of radionuclide i, uCi/m,

2 g

DFG

= Dose factor for standing on contaminated ground, meem/h g

per pCi/m2 (Table 1.8).

8,760

= Occupation time, h/y.

lx108

= pCi/pCi conversion factor.

0.7

= Shielding factor accounting for a distance of 1.0 meter above ordinary ground, dimensionless.

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

7 S

R CVg = 3,600 k i j

,{3,,,, (-

g t,)] +

(I.10)

(2nx/n)

Y, g

k=1

\\

Bg (1-exp (-

t )I I t

b g

-h2 eq (-

iO P Ag Mzj l

where:

CV

= Concentration of radionuclide i in and on vegetation, g

pCi/kg.

k

= Stability class.

f

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

Q

= Average release rate of radionuclide 1, pCi/s.

MIO784-0004A-RS06

12 For determining the concentration of H-3 in vegetation:

CV = lx103 I. (0.75)(0.5/H)

(1 11 )

7 t

where:

CV

= Concentration of H-3 in vegetation. uCi/kg.

T y

= Air concentration of H-3, pCi/a

• 0.75

= Fraction of total plant mass that is water.

0.5

= Ratio of tritium concentration in plant water to tritium concentration in atmospheric water.

3 H

= Absolute humidity of the atmosphere, g/m.

lx103

= g/kg conversion factor.

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

CM - CV FM Q exp (-A e)

(1.12) g g

g g g f where:

CM

= Concentration of radionuclide 1 (including C-14 and g

H-3) in milk, uCi/1.

CV

= Concentration of radionuclide i in and on vegetat'on, uCi/kg.

FM

= Transfer factor from feed to milk for radionuclide i, d/1 (Tabis 1.6).

j Q

= Amount of feed consumed by the milk animal per day, kg/d.

g A

= Radioactive decay coefficient of radienuclide 1._d'I.

g t

= Transport time of activity free feed to milk to '

g receptor, 2 days.

l For determining the organ dose rate from ingestion of green leafy l

vegetables and milk:

l D = Ix106 CM DF tlM (1.13) g

{

l l

l HIO784-0004A-RS06 t

15 The inverse of the ratio C /D in the above equation (i.e., D /C )

c c c

is a useful value, since it represents the most limiting dose per unit quantity of each nuclide released. Use of the D /C ratio in c e quarterly evaluation of offsite dose is discussed in section D.

Values of D /C are given in Tame 1.9.

c c 1.4 Land Use Census and DBQ Chantes Technical Specification 13.2.3 describes the requirements for an annual land use census and revision of the ODCM for use in the following calendar year. Areas of the ODCM which will be reviewed, and changed if appropriate, are Table 1.4 (Band Use census data by Sector), and Table 1.9 (Gaseous Design Basis Objective Annual Quantities). Changes will be effective on January 1 of the year following the year of the survey.

C.

DESIGN OBJECTIVE QUANTITY (DBQ) LIMITS ON CONTINUOUS RELEASES 1.0 Continuous' Releases Low level continuous releases from the stack are totaled on a weekly

~

basis and summed with aciy batch released for the week in order to establish the cumulative DBQ fraction from continuous releases for the year to date. The quantity of each nuclide identified is summed with the quantity of that nuclide released since the first of the current calendar year. The cumulative total for each nuclide (from Table 1.9) and the resultant fractions are summed in order to assure

~

that the sua fraction of all nuclides does not exceed 1.0:

{

Ai (I.16)

< 1.0 (DBQ)

MIO784-0004A-RS06

16 the amount in any calendar quarter should not exceed 0.5.

This is checked by subtracting the value obtained at the end of the previous quarter from the value obtained from the cumulative total to date, including the batch to be released.

2.0 Exceedina DBQ Limits As discussed under B.1.3, the DBQ is a very conservative estimate of activity which could give doses at Appendix I limits. Because different organs are summed together and doses to different people are summed, the DBQ typically overestimates dose by about a factor of five. Thus, if calculations of DBQ fraction exceed 1.0 for year-to-date or 0.5 for the quarter, technical specifications probably still would not be exceeded. However, further discre-tionary releases should be deferred until an accuenta assessment of dose is made by use of GASPAR computer code or by analysis of appropriate release data via the segmented gaussian dose model used in emergency planning (inhalation dose, total body extecnal dose.

and boundary dose in air). See also Section D.1.2.

~

It-should be noted t' at Big Rock Point to date (based on review of h

semiannual effluent data) has never exceeded the annual or quarterly DBQ fraction, despite its conservatism at any time in the past 10 years (since stainless steel fuel cladding was replaced by zircaloy 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 in a significantly off-normal condition.

4.0 Releasing Radionuclides : lot Listed in Table 1.9 Table 1.9 contains all nuclides identified to date as routine constituents of gaseous releases at Big P.ock Point Plant plus those MIO784-0004A-RS06

17 common to BWRs in general, even if not previously detected at Big Rock Point. From time to time, however, other nuclides may be detected.

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

If the unlisted nuclide constitutes 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 1.9 begin to appear in signifi-cant quantities on a routine basis, revision to this ODCM should be made in order to include a design basis quantity specific to that nuclide.

D.

OPTIONAI QUARTERLY DOSE CALCUI.ATIONS 1.0 Methodology for Optional Quarterly Dose Calculations This option may be used in place of, or in addition to, the desian basis quantity (DBQ) fraction calculation described by Equation I.16 l

This optional conservative calculation relates the DBQ fractio _n to the doses from which it was originally derived. Use of this method may assist in identification of the critical dose pathway or char-acteristics of the assumed critical individual (infant, child, adult), since Table 1.9 indicates these parameters.

MIO784-0004A-RS06

23 average meteorology, to the most limiting offsite dose (whole body) assumed to be residing at the residence with highest X/Q, is (TBD) 1.05E - 01 mrem for one year. The release rate which would result in a dose rate equivalent to 500 mrem / year (using the total body limit) is the Curies / year given in Table 1.1 (1.29E-04) multiplied by 500/.105 or 1.95 ci/sec.

G.

PARTICULATE AND IODINE SAMPLING Particulate and iodine samples are obtained from the continuous sample stream pulled from the plant stack. Samples tyni illy are obtained to represent an. integrated release from the stack.

Gamma analytical results for particulate and halogen filters are combined for determination of total activity of particulates and halogens released. Beta and alpha counting also is performed on the particulate filters. Beta yields of the gamma isotopes detected on particulate filters are applied to determine " identified" beta, and the " identified" count rate is subtracted from the observed count

' rate to give " unidentified" beta. The " unidentified" beta is assumed to be Sr-90 until results on actual St-90 (chemically a

f M

MIO784-0004A-RS06 L

O O

9 ;l USNRC COMPUTER JDE - X00D04. VERSIDH 2.0 RUN DATE: 06-L.-84 Tahic 1.1 2

eeum SIG ROCK TOINT XOQD0082 mum USING 31/01/83 - 12/31/83 NET DATA wrur ELEVATED RELEASE - 240' STACK 13 DECAY.

UNDEFLETED 4NNU4L AVERACE CHI /O (SEC/NEYEP CUBED)

DISTANCE IN MILES FROM THE SITE t*

SEclDR t.250 3.583 8.750 1.000 1.506 2.000 2.500 3.008 3.500 4.000 4.500 5

3.634E-08 2.763E-08 2.550E-08 2.987E-88 3.661E-08 3.690E-88 3.462E-03 3.168E-08 2.378E-08 2.614E-04 2.381E-04 55M 3.74tE-08 2.396E-08 2.17eE-03 2.619E-08 3.341E-08 3.422E-88 3.237E-GE 2.977E-48 2.715E-08 2.473E-98 2.257E-08 j

SW 4.435E-08 2.396E-08 1.964E-08 2.123E-08 2.450E-08 2.419E-88 2.243E-08 2.036E-88 1.839E-08 1.662E-05 1.587E-98 l

W5u 5.679E-88 2.371E-e8 1.483E-08 1.319E-08 1.285E-03 1.189E-88 1.073E-88 9.686E-09 8.615E-09 7.756E-89 7.821E-89 W

3.000E*00 0.000E*0s 0.000E*00 0.000E*00 0.000E*00 0.00GE*00 0.000E*00 9.000E*00 0.000E*00 8.000E*80 0.000E*08' WNu e.000E*0C 9.773E-47 2.936E-30 2.193E-22 8.126E-16 4.E42E-13 1.475E-11 1.180E-10 4.654E-10 1.220E-09 2.458E-09 H.S 0.000E*03 0.000E*00 8.0CCE*C0 0.000E+00 0.C30E*30 0.00CE*00 8.300E*00 0.C00E*00 8.000C+00 0.000E*00 0.000E*e0 i

HH'A 7.039E-08 3.140E-SC 1.843E-08 1.40lE-08 1.045E-03 S.221E-01 6.(37E-C9 5.5702-89 4.743E-09 4.10EE-09 3.604E-89 M

1.043E-07 5.360E-08 3.835E-03 3.804E-03 3.940E-08 3.651[-08 3.235E-08 2.9272-08 2.6130-OS 2.345E-88 2.II7E-08 HHE 5.793E-08 3.864E-08 4.054E-08 4.763E-08 5.300E-08 4.993E-08 4.503E-C8 4.815E-C8 3.533E-08 3.214E-08 2.900E-88 HE 7.830E-05 4.951E-88 4.389E-08 4.552E-03 4.475E-08 3.964E-88 3.432E-08 2.974E-08 2.595E-08 2.281E-C8 2.032E-08 i

EHE 4.755E-08 3.700E-03 4.115E-03 4.752E-08 4.756E-08 4.451E-05 3.865E-08 3.345E-03 2.913E-08 2.559E-09 2.268E-98 I

E I.868[-07 7.756E-08 6.195E-08 5.917E-DE 5.359E-33 4.530E-03 3.794E-31 3.207E-0& 2.745E-05 2.330E-03 2.pE7E-83

)

E5E 1.299E-07 9.115E-08 6.114E-08 5.174E-03 4.339E-OL 3.54CE-03 2.960E-00 2.492E-C3 2.132E-38 1.849E-03 1.623E-03 1

SE 9.134E-C8 5.939E-03 4.4405-05 4.240E-05 4.113E-05 3.674E-c5 3.293E-00 2.7522-05 2.455E-C5 2.171E-08 I.95tE-08 SSE 5.15tE-08 3.328E-03 2.723E-08 2.970E-08 3.353E-08 3.23GE-03 2.955E-03 2.654E-05 2.377E-OL 2.135E-03 1.927E-88

)

tNNUAL AVERACE CHI /O (SEC/ METER CUBED)

DISTANCE IN MILES FRDM THE SITE SEC104 5.880 7.500 18.800 15.000 20.000 25.000 30.500 3'i.000 40.000 45.000 50.000 5

2.178E-03 1.484E-08 1.097E-08 6.979E-09 5.004E-C9 3.344E-89 3.890E-39 2.565E-09 2.181E-09 1.889E-89 1.661E-99 5 5tl 2.06EE-08 1.417E-08 1.8510-03 6.707E-09 4.Cl3E-09 3.706E-C9 2.902E-09 2.477E-09 2.107F-89 1.826E-09 1.606E-09 Su 1.174E-08 9.253E-89 6.788E-C9 4.276E-09 3.047E-09 2.330E-89 1.067E-07 1.545E-09 1.31IE-09 1.133E-09 9.939E-19 W5u 6.395E-09 4.317E-01 3.181E-09 2.023E-09 1.454E-09 1.12CE-3? 9.020E-10 7.503E-10 6.3920-IS 5.546E-10 4.833E-It u

9.000E*00 0.000E*e0 0.000E*00 0.000E*00 0.000E*00 0.00CE*00'0.000E*p3 8.setE*00 0.000E*00 0.000E*00 0.000E*00 WHu 4.868E-89 1.598L-08 2.592E-08 3.354E-08 3.286E-08 2.983E-08 2.647E-08 2.340E-88 2.873E-08 1.846E-08 1.653E-08 Hu 8.000E*00 0.000E*00 0.00GE*00 0.000E*00 0.000E*00 0.000E*e9 s.800E*00 0.000E*00 0.000E*00 0.000E*00 0.000E*00 MHH 3.201E-0 9 2.02iE-0 9 1.4 39E-01 8.84 0E-10 6.26 7 E-10 4.7 90E-10 3.8' 3E-10 3.1E9E-10 2. 7130-10 2. 35 3E-10 2. 0 7 2E-18 N

1.125E-04 1.29 3E-08 9.529E-0 9 6.0 7 3E-0 9 4. 3 74E-0 9 3.37 7E-0 9 2.72SE-0 7 2.275E-c 9 1.142E-C 9 1.689E-09 1.490E-09 HNE 2.634E-03 1.75tE-93 1.292E-08 8.181E-09 5.561E-09 4.505E-99 3.625E-09 3.0132-C9 2.555E-01 2.225E-09 1.95EE-89 HE 1.822E-03 1.154E-08 8.300E-09 5.058E-07 3.555E-09 2.690E-01 2.139E-O? 1.761E-89 1.437E-09 1.2&lE-09 1.120E-09 EHE 2.073E-08 1.278E-03 9.020E-31 5.424E-09 3.75CE-09 2.317E-81 2.223E-09 1.818E-09 1.527E-09 1.309E-09 1.140E-89 E

I.850E-0C 1.!!5E-08 7.137E-07 4.69CE-01 3.25tE-09 2.435E-09 1.927E-09 1.579E-09 1.328E-09 1.141E-09 9.958E-It ESE 1.441E-C8 8.941E-89 6.277E-09 3.786E-01 2.655E-09 2.012E-09 1.604E-09 1.324E-89 1.121[-09 9.633E-18 8.496E-le SE-1.740E-08 1.120E-08 8.018E-09 4.922E-09 3.465E-09 2.630E-89 2.e96E-09 I.728E-09 I.462E-09 1. 2 6 0 E- 0 9 ~ 1.10 4 E-8 9 SSE 1.749E-08 1.161 E-0 8 8.4 52 E-0 9 5.27 7 E-0 9 3. 7 41 E-0 9 2.851 E-0 9 2.27& E-0 9 1.88 3 E-0 9 1. 5 95E-0 9 1.377E-09 1.207E-59 ENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (IEIER5) 73.10 RrP. ulHD HElcHT (HrTF25) 71.3 DIAMETER t iit 1 E25 )

1.14 BU!LDING HEICHI (HETER 5) 31.4 EXII VELOCITY titEILRS) 13.21 Bl L'G.HIN.CRS.5EC. AR E A (50.HtIERS) 2000.0 HEAI EHISSIO(IRATE ELAt/dEC) 0.0 LE ELEVA'1ED RELEASES.

I t

O O

O 4

O O

I:50CC COMP!TE2 LO;E - X00D09, VERSION 2.0 RUN DATE: 06-C5-81 Talit e 1.3 (contil) 29 SIC ROCK POINT XDQD0082 unu USING C1/01/83 - 12/31/83 NET DATA unum eous ELEVATED RELEASE - 240' STACK 80 DECAY.

UNDEPLETED

,1 CHI /9 (SEC/ METER CU3ED) FOR EACH SEGMENT (

g-3ICECTIDH

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

2.791E-08 3.524E-08 3.405E-08 2.860E-08 2.375F-08 1.466E-08 6.938E-09 3.852E-01 2.569E-09 1.891E-89 55W 2.420E-08 3.217E-08 3.182E-03 2.697E-08 2.251E-08 1.399E-03 6.712E-09 3.713E-09 2.480E-09 1.824E-09 SW 2.131E-03 2.353E-03 2.207E-08 1.828E-03 1.504E-C5 9.155E-09 4.288E-09 2.336E-99 1.548E-01 1.134E-09 W5u 1.603E-08 1.250E-08 1.059E-03 8.570E-09 7.000E-09 4.274E-01 2.027E-09 1.122E-09 7.513E-10 5.551E-10 W

0.c00E*00 0.0COE*00 0.00SE*C0 0.000E*09 0.0?9E*90 0.0S22*C0 0.000E*c0 0.00CE*C0 0.000E*00 0.000E*00 M*:u 9.746E-23 2.155E-13 5.226E-II S.5410-10 2.72tE-09 1.777E-05 3.155E-C3 2.925E-08 2.326E-08

• 1.842E-08 HM 0.000E*00 0.000E*00 0.000E*00 0.000E*00 0.e00E*nS 0.009E*00 0.000[*00 0.000E*00 0.000E*00 0.000E*00 Huu 1.935E-08 1.025E-08 6.652E-09 4.741E-09 3.606L-09 2.027E-09 8.931E-10 4.805E-10 3.195E-10 2.356E-IG H

4.159E-08 3.784E-08 3.243E-08 2.5 DIE-08 2.ll3E-08 1.282E-08 6.086E-09 3.383E-09 2.277E-09 1.690E-09 MHE 4.329E-C8 5.647[-08 4.439E-03 3.546E-08 2.895E-08 1.747E-08 8.203E-09 4.514E-09 3.017E-09 2.227E-09 HE 4.535E-08 4.265E-04 3.371E-08 2.536E-0C 2.030E-08 1.162E-03 5.114E-09 2.700E-09 I.764E-09 1.282E-09 EHE 4.3C6E-08 4.68&E-C8 3.313E-05 2.902E-08 2.265E-08 1.278E-08 5.432E-09 2.830E-09 1.823E-09 I.311E-09 E

6.41AE-03 5.Il8E-03 3.755E-08 2.735E-04 2.006E-08 1.141E-08 4.763E-01, 2.450E-09 1.533E-09 1.143E-09 E5E 6.363E-08 4.1&2[-OS 2.935E-03 2.127E-08 1.622E-05 8.973E-09 3.C37E-09 2.020E-07 1.326E-09 9.696E-10 SE 4.695E-88 3.946E-08 3.168E-08 2.445E-08 I.933E-08 1.Il6E-03 4.962E-09 2.639E-09 1.731E-09 1.262E-09 SSE 2.167E-08 3.219E-08 2.911E-08 2.364E-08 1.923E-08 1.151E-G8 5.300E-09 2.859E-09 1.8E6E-09 1.378E-09 AVEOAGE EFFECTIVE STACK HEIGHT IN METERS FOR EACH SEGMENT DICECTION

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

~COM SIIE 5

8.438E*01 8.430E*01 8.438E*01 8.438E*01 8.433E*01 8.430E*01 8.438E*01 8.438E*0I S.438E*01 8.438E*01 55u 8.424E*01 8.425E*01 8.425E*01 8.425E*01 8.425E*01 8.425E*01 8.425E*01 8.425E*01 8.425E*01 8.425E*01 SW 8.529E*01 0.529E*01 8.529E*01 8.529E*01 8.529E*01

.8.529E*01 8.529E*01 8.529E*01 8.529E*01 8.529E*01 W5W 8.610E*01 8.6ISE*01 8.610E*01 8.610E*01 8.610E*01 8.610E*01 8.610E*01 8.650E*01 8.610E*01 8.6 tee *01 W

0.000E*00 0.0CSE*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 WNu 3.817E*02 3.853E*02 3.853E*02 3.853E*02 3.853E*02 3.853E*02 3.853E*02 3.853E*02 3.853E*02 3.853E*02 Hu S.003E*00 0.000E*00 0.000E*00 0.000E*00 0.000L*00 0.000E*00 0.000E*00 0.000E*00 0.000E*00 0.000E*00 NHu 8.508E*01 8.588E*01 8.503E*01 8.588E*01 8.58BE*01 8.523E*01 8.588E*01 8.580E*01 8.588E*01 8.588E*01 N

8.459E*01 8.459E*01 8.459E*01 3.45%E*01 8.459E*01 8.459E401 8.459E*01 8.459E*01 8.459E*01 8.459E*01 MHE 8.328E*01 8.328E*01 8.328E*01 8.328E*0I 3.323E*01 8.328E*01 8.328E*01 8.328E*01 8.328E*01 8.328E*01 NE 8.548E*01 8.549E*0I 8.549E*01 8.549E*01 8.549E*01 8.549E*01 8.549E*01 8.549E*01

8. 5 '. 9 E

• 01 8.549E*01 ENE 8.457E*01 8.457E*01 8.457E*0l' 8.457E*01 8.457E*01 8.457E*01 8.457E801 8.457E*01 8.457E*01 8.457E*01 E

9.025E*01 9.027E*01 9.027E*01 9.027E*01 9.027E*01 9.027E601 1.027E601 9.027E*0I 9.027E*03 9.027E*01 ESE 9.342E*01 9.346E*01 9.346E*01 9.3'6E*e1 9.346E*01 1.346E*01 9.346E*01 9.346E*01 9.346E*01 9.346E*01 SE 8.853E*01 8.855E*01 8.855E*01 8.855E*01 8.C55E*01 8.855E*01 8.855E*01

8. 8 5 5 L * 'J I 8.855E*01 8.855E*01 SSE 8.589E*01 8.590E*01 8.510E*01 C.590E*01 3.590E*01 8.550E*01 8.590E*01 8.595E*01 8.590E*01 8.590E*01 3

0 0

0

1 1

O O

USNRC COMPUTER CODE - XO9 DOS, VERSION 2.8 RUN DATE: 06-06-84 Table 1.3 (Contd) e I

30 occa SIG ROCK POINT XOtD0482 uum U51HG 01/01/83 - 12/31/83 MET DATA nWuu

• MLEV41ED RELEASE - 240' STAEK 2.268 DAY DECAY, UNDEPLETED

, ANNUAL AVERAGE CHI /t (SEC/ METER CUBED 7 3

DISTANCE IN MILES FROM THE SITE 4*

SECTOR 8.250 e.500 0.750 1.000 1.500 2.000 2.588 3.499 3.500 4.000 4.500 5

3.631E-98 2.755E-08 2.543E-08 2.980E-08 3.651E-08 3.678E-88 3.448E-88 3.153E-88 l

SSW 3.738E-88 2.339E-04 2.163E-08 2.612E-88 3.331E-08 3.410E-05 Su 1.961E-03 2.118E-08 2.444E-08 2.411E-88 2.235E-88 2.827E-883.223E-04 2.963E-98 2.700 4.432E-88 2.393E-88 W5u I

5.675E-08 2.369E-08 1.481E-08 1.317E-08 1.282E-08 1.185E-08 1.068E-88 9.558E-8 9 8.562E-8 9 7.7 0 1.829E-08 1.652E-88 1.498E-08 W

8.000E*00 0.000E*80 8.080E*00 0.000E*00 0.000E*00 0.000E*00 0.000E*00 0.088E*88 0 l

WMil 8.000E*88 9.634E-47 2.874E-30 2.131E-22 7.786E-16 4.573E-13 1.373E-11 1.084E-10 NW 8.008E*89 9.900E*99 9.890E*00 0.000E*00 0.000E*00 NHW 7.036E-08 3.138E-88 1.841E-08 1.399E-08 0.000E*88 0.00eE*st 9.858E*te 0.000E*00 0.980E*00 8.000E*88 H

1.042E-07 5.351E-08 3.E23E-08 3.796E-08 3.930E-081. 0 4 3 E-08 8.2 0 lE-0 9 6.6 6 7E-9 9 5.55&E-9 9 4. 7 29 NHE 5.789E-88 3.8 56 E-88 4.84 7E-08 4. 76 0 E-0 8 -5.28 9E-03 4. 93 5 E-0 8 4.48 S E-083.653E-08 3.274E-88 2.9 2.332E-88 2.105E-88 NE 7.824E-88 4.940E-88 4.380E-08 4.543E-08 4.463E-08 4.000E-88 3.568E-08 3.199E-08 2.885E-08 EHE 4.750E-08 3.951E-08 3.691E-88 4.197E-08 4.744E-08 4.945E-08 4.439E-88 3.851E-083.411E-0 8 2.161 E-08 2.58 3 E-08 2.274 E-88 E

I.867E-t?

1.298E-07 9.886E-08 6.091E-08 5.155E-08 4.318E-087.734E-88 6.176E-08 5.901E-08 5.349E-08 ESE 3.186 3.547E-08 2.939E-08 2.472(-88 2.111E-08-88 2.724E-08 2.359E-SE 9.124E-88 5.972E-08 4.427E-08 4.228E-08 4.099E-08 E

1.828E-88 1.693E-08 SSE 5.146E-88 3.319E-08 2.716E-88 2.963E-08 3.658E-08 3.191E-88 2.781E-08 2.438E-88 2.154E-08 3.348E-08 3.227E-08 2.943E-88 2.640E-08 2.363E-08 2.121E-08 1.119E-88 1.912E-08 aCMUAL AVERACE CHI /t (SEC/MElER CUBED)

DISTANCE Ill Mile 5 FROM THE SITE SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.008 35.000 40.000 45.889 50.000 5

2.162E-88 1.468E-88 2.853E-88 1.481E-88 1.035E-08 6.564E-09 4.682E-0 9 3.5 76 E-0 9 2.858 55u 1.550E-09 su

1. 3 6 4 E-88 9.15 7E-8 9 6.6 95E-0 9 4.18 9E-0 9 2. 966 E-0 9 2.25 3E-9 9 1. 7 9 3 E-8 9 1.4 7 4 E-0 9 1.498E-59 WSM 6.343E-99 4.263E-89 3.129E-09 1.973E-09 1.407E-09 1.075E-89 8.589E-lO 7.88 E-18 5.9 1.242E-89 1.067E-89 9.299E-19 u

0.000E*88 0.000E*00 0.000E*00 0.000E*00 0.000E*00 6nrJ 3.606E-89 1.293E-88 1.948E-08 2.186E-08 1.856E-08 0.000E* B0 8.000E* 0 0 8.00 0E* 0 0 9.900E

• 00 0.0 0 0E

• 0 0 0.00 0E

• 0.000E*00 0.000Esto 0.000E*00 9.800E*00 8.000E*88 0.000E*001.46 Hu 9.000E*88 8.000E*00 8.000E*00 Mi u 3.189E-01 2.806E-89 1.423E-09 8.684E-10 6.!!9E-10 4.643E-10 3.706E-10 3.056E-10 2.583E-10 2.226E-100.0 N

1.912E-08 1.281E-88 9.408E-09 5.959E-89 4.267E-09 3.274E-09 2.629E-99 2.179E-89 1.849E-09 1.599E-09 1.947E-18 NNE 2.619E-08 1.745E-88 1.277E-88 8.042E-09 1.152E-88 8.180E-09 4.9580-09 3.4510-09 2.592E-89 2.846E-895.729E-09 4.371E-09 3.554E-8 HE 1.801E-85 1.852E-89 ENE 2.814E-08 1.265E-88 8.897E-09 1.6FIE-09 1.401E-09 1.198E-09 1.840E-09 5.312E-09 3.654E-09 2.719E-89 2.130E-09 1.730E-01 1.442E-09 1.227E-09 1.06 E

1.830E-08 1.Il8E-08 7.730E-09 4.537E-09 3.101E-09 2.297E-09 ESE 1.421E-08 8. 7 52E-0 9 6. 0 97E-0 9 1.792E-09 1.451E-09 1.20%E-09 1.823E-89 8.825E-10 3.620E-09 2.498E-G9 1.E63E-09 1.462E-09 SE 1.723E-88 1.lO4E-08 7.860E-09 4.776L-49 3.329E-09 2.500E-09 1.I'8E-09 9.901E-10 8.430E-te 7.287E-It SSE 1.735E-08 1.172E-09 1.610E-09 1.3%9E-09 1.152E-89 9.991E-10 1.147E-08 8.316E-09 5.151E-09 3.622E-09 2.739E-09 2.172E-09 1.781E-89 1.497E-09 1.282E-89 1.!!6E-99 VECT AND BUILDING PARAMETERS:

REL EASE HEICHI (110 t E R51 73.13 REP. WIND IIEIGIIT (METER 51 73.3 DI*NEtER (tEIER51 1.14 BullDING llEIGill (MEIER5) 31.4 EXII V[LOCITY (METER 51 18.21 3LDG.filli.CES.5EC. AREA (50. METER $1 2000.8 HEAT EMI5510ll'R ATE (CAL /SECl 0.0 SLL ELEVATED RELEASES.

O O

O

I O

O 6~

31 USNtc CDNPUTER LtCE - XOtDOS, VE 5 ION 2.0 CUN DATE: 06-6.-84 Table 1.3 (Contil) ccus egg ROCR FOINT XOtD0082 unu USING 01/01/43 - 12/31/83 MET DATA wous ELEVATED RELEASE - 240' STACK 2.260 DAY DECAY.

UNDEPLETED 0%I/O (SEC/ METER CUSED) FOR EACM SEGME'MT g.

DIRECTION

.5-1 1-2 7-3 3-4 4-5*

5-10 10-20 20-30 30-40 40-50 FCOM SITE 5

2.784E-08 3.514E-04 3.391E-08 2.855E-08 2.359E-08 1.450E-98 6.841E-09 3.719E-09

2. 446 E- 0 9 1.777E-09 55W 2.413E-08 3.206E-08 3.169E-08 2.683E-08 2.236E-08 1.343E-08 6.570E-09 3.584E-09 2.362E-09 1.717E-t9 SW 2.127E-08 2.357E-08 2.199E-08 1.315E-08 1.414E-08 it.060E-09 4.202E-t1 2.259E-09 1.477E-09 1.068E-09 W5W 3.605E-08 1.246E-C8 1.054E-08 8.520E-09 6.955E-89 4.221E-09 1.57&E-09 1.077E-09 7.0?9E-10 5.163F-19 W

0.000E*00 0.000E*00 0.000E*00 0.003E*(3 0.000E*00 0.000E*00 0.000E*00 0.000E*00 0.000E*00 0.000E*00 WisW 9.472E-23 2.035[-13 4.804E-11 3.063E-10 2.378E-09 1.37&E-08 1.936E-08 3.431E-SE 5.602E-09 5.130E-09 NW 0.000E*00 0.003E*00 0.000E*00 0.000E*00 0.000E400 0.000E400 0.000E*00 0.000Es00 0.000E800 0.000E400 MPIW I.933E-08 1.023E-05 6.633E-09 4.722E-09 3.5EEE-09 2.010E-09 8.776E-10 4.663E-10 3.061E-10 2.229E-10 N

4.151E-05 3.77&E-08 3.23tE-08 2.5t3E-08 2.101E-06 1.270E-08 5.973E-09 3.280E-09 2.182E-09

.1.E00E-01 MHE 4.322E-C8 5.035E-33 4.426E-c3 3.551E-05 2.379E-08 1.731E-98 8.e55E-09 4.35SE-09 2.101E-09 2.Il8E-09 HE 4.577E-08 4.253r-38 3.378E-C8 2.573E-03 2.017E-05 1.149E-03 5.004E-09 2.603C-09 1.675E-09 1.199E-09 EllE 4.293E-08 4.675E-08 3.800E-08 2.838E-08 2.2520-03 1.255E-08 5.372F-09 ' 2.733E-09 3.734E-09 1.229E-C1 E

6.400E-08 5.095E-08 3.734E-08 2.717E-08 2.066E-08 1.1235-98 4.60LE-49 2.309E-09 1.455E-09 1.025E-09 ESE 6.340E-08 4.16tE-08 2.914E-08 2.106E-08 1.602E-08 8.785E-09 3.672E-09 1.872E-09 1.191E-09 8.444E-10 SE 4.652E-08 3.?*it =4 3.152E-0C 2.428E-08 1.?t4E-08 1.103E-SC 4.510E-39 2.51*E-09 1.614E-09 1.154E-09 SSE 2.96CE-05 3.2J9E-03 2.398E-08 2.350E-08 1.108E-08 1.1375-00 5.175E-C9 2.P.0E-09 I.784E-09 1.284E-09 e

D e

S k

1 O

O O

e

O O

1 o

l USNRC COMPUTER CODE - X00C01. VERSICM 2.J RUM DATER 35-C'-84 Table 1. 3 ( Con t et )

32 P

ecum SIG ROCK Po!NT XD100482 uuu USING 01/01/83 - 12/31/83 NET DATA rup4 ELEVsTED RELEASE - 240' STACR 8.880 DAY DECAY.

DEPLETED AFMUAL AVERAGE CHI /O (SEC/NETER CUBED)

DISTAMCE IN MILES FRON THE SITE SECTOR S.25e s.588 0.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 5

3.633E-08 2.737E-08 2.507E-08 2.941E-08 3.605E-08 3.629E-88 3.399E-98 3.185E-98 2.816E-88 2.554E-08 2.32 55u 3.740E-08 2.373E-08 2.133E-88 2.579E-08 1.927E-08 2.083E-08 2.406E-03 2.373E-08 2.198E-383.292E-08 3.368E-88 3.182E-98 2.922E i

i 5W 4.434E-08 2.374E-08 1.192E-08 1.715E-08 1.620E-08 1.467E-98 WSW 5.678E-88 2.349E-08 1.453E-08 1.288E-08 1.252E-08 1.157E-08 1. 042E-08 9.31 t E-0 9 8. 332E-0 9 7.488E-0 9 j

W 0.000E*00 0.000E*00 0.000E*00 0.000E*00 0.00tE*00 0.000E*00 0.000E*00 0.000E*08 0.000E*00 0.000E*00 8.0 i

WHM 0.000E*08 9.733E-47 2.91tE-30 2.175E-22 7.953E-16 4.672E-13 1.4030-11 1.108E-10 9.32tE-10 1.!!50-89 2.219E-i l

EM 0.000E*00 0.000E*00 0.000E*00 0.000E*00 0.000E*00 0.000C+00 0.000E*00 8.OOCE*80 0.000E*00 0.000E*00 0 HHW 7.038E-03 3.IIIE-08 1.8340-08 1.353E-08 1.0092-08 7.894E-89 6.387E-09 5.302E-09 4.492E-09 3.870E-09 3.381E 4

N 1.843E-87 5.31tE-08 3.765E-08 3.738E-08 3.862F-08 3.578E-88 3.202E-C8 2.8%4E-88 2.532E-88 2.267E-88 7.

)

MHE 5.792E-08 3.831E-08 4.st2E-88 4.71tE-88 5.217E-08 4.899E-08 4.397E-C8 3.907E-OS 3.4770-08 3.IllE-08. 800 j

p HE 7.829E-08 4.986E-05 4.319E-08 4.475E-08 4.374E-08 3.854E-88 3.32SE-98 2.864E-08 2.489E-08 2.184E-08 ENE 4.753E-08 3.569E-s8 4.e63E-08 4.693E-05 4.865E-08 4.343E-08 3.749E-98 3.228E-48 2.79EE-08 2 447E-08 2 l

E 1.06EE-07 7.683E-08 6.081E-88 5.798E-08 5.225E-08 4.378E-68 3.6%1E-08 3.056E-08 2.600E-08 2.241E ESE 1.299E-87 T.027E-08 5.985E-OC 5.844E-08 4.198E-03 3.430E-08 2.827E-08 2.366E-08 2.812E-08 i

I l

5E 9.'31E-88 5.932E-08 4.356E-08 4.153E-05 4.01tE-08 3.567E-98 3.191E-98 2.694E-88 2.354E-68 2.074E-081.736E-0 l

S5E 5.s50E-08 3.297E-08 2.677E-05 2.924E-08 3.299E-08 1.843E-08 3.172E-OS 2.887E-08 2.584E-08 2.308E 08 2.068E-08 1.862E-88 ANMUAL AVERAGE CHI /t (SEC/NEVER CUBED)

DISTANCE IN MILES FRON THE SITE g

SECIOR 5.00s 7.sse 1e.e00 15.000 2s.000 25.000 30.ses 35.000 40.000 45.Os0 5s.000 5

2.123E-88 1.438E-08 1.059E-08 6.686E-09 4.762E-09 3.63fE-89 2.908E-09 2.402E-89 2.030E-09 l'. 7 5 0 E-0 9 1.529E-55W 2.820E-08 1.376E-08 3.817E-08 6.445E-09 4.600E-09 3.518E-89 2.816E-99 2.328E-99 1.969E-89 1.698E-89 1.484E-09 SM 1.336E-08 8.939E-09 6.524E-09 4.074E-09 2.E30E-09 2.137E-09 1.74eE-09 1.432E-89 1.206E-09 1.037E-09 9.033E-10 W5u 6.153E-09 4.120E-09 3.016E-09 1.894E-09 1.346E-09 1. 82 5E-8 9 8.17 9E-10 6.74 0E-19 5.6 8 4 E-18 4. 88 4 E-18 4.256E-10 W

0.000E*80 0.000E*08 8.000E*00 0.000E*09 0.000E*00 0.0GOE800 0.800E*88 0.000E*08 8.800E*00 e.808E*00 9.800E*09 WHu 3.718E-89 1.358E-e8 2.087E-08 2.477E-05 2.244E-08 1.894E-88 1.568E-98 1.297E-08 1.877E-08 9.070E-09 7.612E-09 NW S.800E*03 3.880E*00 8.000E*00 8.000E*00 0.000E*00 0.000E*00 8.OOSE*00 9.000E*00 0.000E*00 0.000E*00 0.000E*

4 Nr:M 2.997E-09 1.858E-09 1.30lE-09 7.766E-10 5.360E-10 3.996E-1s 3.132E-19 2.542E-18 2.ll5F-10 1.715E-10 1.544E-10 l

N I.8532-08 1.235E-08 9.04tE-09 5.700E-09 4.06CE-09 3.Il4E-01 2.496E-99 2.867E-09 1.752E-09 1. 514 E-0 9 1.326E-9 HHE 2.53aE-08 I.682E-08 1.227E-03 7.694E-09 5.469E-09 4.176E-09 3.140E-89 2.762E-09 2.3390-09 2.020E-09 HE 3.729E-04 1.768E-09 1.089E-08 7.653E-09 4.6G9E-09 3.182E-09 2.375E-09 1.865E-89 1.515E-89 1.268E-05 1.081E-09 9.355E-10 EHE I.123E-88 1.19 3E-08 8.320 E-0 9 4. 906 E-09 3.344E-0 9 2.4 72E-89 1.927 E-O f 1.558E-0 9 1.294L-0 9 1.0 9 9E-8 9 9.4 E

I.723E-88 1.834E-08 7.063E-09 4.062E-09 2.731E-89 f

1. 34 0E-88 8.138 E-0 9 5.610E-0 9 3.2 72E-0 9 2.22 3C-0 9 1.6 3 ? E-0 9 1.26 9E-0 91.196E-89 1.539E-09 1.233E-8 ESE i.

SE

1. 021 E-0 9 8. 4 26 E-10 7.100E-It 6.066E-te I.6 51 E-08 1. 0 4 9E-88 7.423E-0 9 4.4 6 9 E-0 9 3.0 92E-0 9 2.30 9E-89 1.814 E-0 9 1.4 7 5E-8 9 1.2 31 E-0 9 g

SSE 1.e48E-09 9.054E-10 I.686E-88 1.109E-98 E.816E-09 4.944E-09 3.46EE-09 2.619E-09 2.975E-09 1.70lE-09 1.429E-09 1.225E-09 1.065 l VEDT AND BUILDING PAR AMETERS:

RELEASE HEIGHT inEIER5) 73.10 REP. WIND llEIGHT (NETE25) 71.3 DianETER (NFTERS) 1.14 BUIL DittG llEIGui INEIER5) 31.4 j

Ex!T VELOCITY tite I E R $ )

18.21 SLDG. Nill.CRS.5EC. AREA ($Q.itETER5) 2000.0 llEAT EI115510N RATE (CAL /SEC) 0.0

{ ALL ELEVATED RELEASES.

l>

l 1

O O

O

O O

C J5MRC COMPUTER LJDE - X00D04. VERSION 2.0 RUN DATE: 86-bw-84 Table 1.1 (Conts!)

33

• C n BIS ROCK PolNT XO900082 unu USING 01/01/83 - 12/31/83 NET DATA unum E1EVATED RELEASE - 240' STACK 8.000 DAY DECAY.

DEPLETED CCI/O (SEC/ METER CUSEDI FOR EACM SEGMENT i'

SEGNEHT SOUNDARIES IN MILES FROM INE SITE BICECTION

.5-1 1-2 2-3 3-4 4-5 5-18 19-20 28-38 30-44 40-50 rEOM SITE 5

2.751E-88 3.468E-98 3.343E-08 2.799E-0*

2.318E-08 1.422E-98 6.698E-89 3.645E-09 2.495E-09 1.751E-09 1

55u 2.3840-08 3.167E-08 3.128E-08 2.644E-Os 2.201E-08 1.359E-93 6.452E-99 3.526E-89 2.33tE-09 1.699E-09 5W 2.096E-05 2.320E-88 2.162E-08 1.735E-08 1.464E-08 W5W l.571E-08 1.218E-88 1.828E-SS 8.210E-09 6.753E-09 ' 8.347E-09 4.tB3E-09 2.193E-89 1.434E-09 1.037E-09 4.981E-09 1.930E-99 1.023E-99 6.749E-lO 4.888E-It W

t.ase[*00 0.83eE*se 0.300E*00 0.setE*00 0.000E*00 8.SBSE*tt 8.900E*00 e.steE*00 0.000E*00 0.000E*00 WNW 9.668E-23 2.879E-13 4.111E-11 6.006E-10 2.444E-81 1.460E-OS 2.287E-08 1.857F-08 1.29tE-88 9.834E-99 HW 0.000E*e8 0.000E*00 9.900E*00-0.SesE*00 e.800E*OS 8.000E*00 0.000Eise 8.000E800 0.000E*00 0.000E*00 NitM 1.89EE-84 9.899E-09 6.355E-09 4.487E-89 3.384E-89 1.864E-09 7.863E-18 4.SI4E-18 2.548E-le 1.797E-10 N

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U5htC COMPUTE 3 CODE - XO9 pet. VERSION 2.0 RUN DATE: 06-06-84 Tahle 1.3 (Contel) 35

!.see SIS EDCE POINT XS9DO982 men USING C1/01/83

- 12/31/43 NET DATA numa ELEWATED RELEASE - 240' 5 TACE cameensomnumwamuunnumwww RELATIVE DEPOSITION PER UNIT AREA (nau-21 SY DOWNWIND SECTORS mammmmmmmmmmmmmmusemaeus SEGMENT SOUNDARIES IN MILES DIRECTION

.5-1 1-2 2-3 3-s 4-5 5-10 10-20 20-30 30-40

'40-50 I*

FADM SITE 5

5.663E-10 2.920E-10 1.573E-10 9.916E-II 6.750E-Il 3.102E-11 1.045E-11

4. 7 98 E-12 3.307E-32 2.330E-32.

i SSW 4.526E-10 2.318E-10 1.243E-10 7.845E-II 5.344E-11 2.460E-11 8.332E-12 3.898E-12 2.635E-IZ 2.059E-32 SW 4.920E-10 2.237E-10 1.124E-10 6.949E-Il 4.735E-11 2.193E-11 7.538E-12 3.535E-12 2.291E-12 1.665E-12 W5W 3.813E-It 2.332E-10 1.070E-10 6.427E-11 4.339E-11, 2.020E-11 7.050E-12 3.395E-12 2.236E-12 1.590E-32 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 WWW 7.972E-10 4.546E-10 5.882E-10 3.951[-10 2.721E-10 1.239E-10 4.041E-11 3.686E-II 9.453k-12 6.313E-12 MM 0.000E*00 0.000E*00 0.000E*80 0.000E*00 0.000E*00

' O.000E*00 0.000E*00 0.000E*00 0.000E*00 0.000E*00 NNW 8.259E-10 3.210E-10 1.441E-10 8.605E-11 5.804E-11 2.711E-11 9.529E-12 4.588E 2.929E-12 2.el8E-12 N

1.214E-09 5.741E-10 2.929E-10 1.520E-10 3.235E-10

5. 6 96 E-11 1.934E-11 8.852E-12 5.473E-12 3.762E-12 NME 1.133E-09 6.725E-10 3.792E-10 2.409E-10 1.639E-10 7.455E-11 2.446E-Il 1.065E-II 6.327E-12 4.284E-12 NE I.351E-09 7.284E-10 3.493E-10 2.429E-10 1.645E-10 7.471E-11 2.449E-Il I.072E-11 6.376E-32 4.272E-12 ENE 1.166E-09 7.197E-10 4.085E-10 2.592E-10 1.761E-10 7.971E-11 2.587E-11 1.IllE-Il 6.525E-12 4.382E-12 E

1.511E-09 7.739E-10 4.137E-10 2.592E-10 1.761E-10 8.064E-11 2.693E-11 1.202E-11 7.250E-32

~4.894E-12 ESE 1.31st-09 S.440E-10 3.234E-10 1.99"E-10 1.355E-10 6.247E-11 2.125E-I.I 9.752E-12 6.025E-12 4.119E-12 g

SE I.194E-09 5.449E-10 2.823E-10 1.755E-10 1.191E-10 5.46tE-11 1.433E-11 8.290E-12 5.197E-12 3.528F-32 55E 6.530E-10 3.479E-10 1.892E-10 1.196E-10 8.145E-11 3.736E-11 1.252E-11 5.6310-12 3.492E-12 2.462E-12 WENT ANS SUILDIMS PARAMETER 58 RELEASE MERCHT (METER 5)

T3.10 REP. WIND I'EIGHT (METERS) 71.3 DIAMETER (METERS) 1.14 SUILD:tIG HEIGHT (METERSI 31.4 EXIT VELOCITY (METERSI 18.21 01DG.ntit.CCS.5EC. AREA (50.nEIERSI 2000.0 liEAT EMISSION RATE (CAL /5EC) 0.0 ALL ELEVATED RELEASE 5.

e 9

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0 0

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35 i

b

~

BIG ROCK POINT PLANT TABLE 1.4 Distance to the nearest residence, garden, milk cow, beef cow and goat in each sector.

i SECTOR RESIDENCE GARDEN DAIRY COW BEEF CATTLE GOAT i

i WSW 2.5 mi

>5 mi

>5 mi

>5 mi

>5 mL i

SW 1.1 mi 2.5 mi

>5 mi

>5 mi

>5 mi 1

SSW 1.3 mi 2.1 mi

>5 mi

>5 mi

>5 mi 4

S 1.9 mi 2.2 mi 2.3 mi 2.3 mi

>5 mi SSE 1.7 mi 1.8 mi 3.5 mi 3.5 mi

>5 mi i

SE 1.7 mi 1.9 mi 2.3 mi 1.9 mi

>5 mi t

4 ESE 1.5 mi 1.9 mi 2.2 mi 3.2 mi

>5 mi 1

I i

E 1.4 mL 3.0 mi 2.5 mi 2.5 mi

>5 mi i

ENE 2.3 mi

>5 mi

>5 mi

>5 mi

>5 mi 4

I i

j I

i i

i 1

l i

IC0685-0178A-HP01

)

l

36a Table 1.4a 4'

Critical Receptors BIG ROCK POINT PLANT 1986 GASPAR INPUT Distance X/Q X/Q Decay X/Q Decay & Dep D/Q 3

3 3

2 Pathway Sector (miles)

(sec/m )

sec/m )

(sec/m )

(1/m )

Residence /Carden E

1.4 5.92E-08 5.90E-08 N5.80E-08 1.25E-09 Site-Boundary ESE 0.5 9.12E-08 9.09E-08 9.03E-08 1.97E-09 Beef Cow SE 1.9 4.llE-08 4.10E-08 4.01E-08 5.37E-10 Dairy Cow,

ESE 2.2 3.57E-08 3.55E-08 3.43E-08 4.35E-10 Ir"'86-0012A-HP01

1 1

e 50 I

Table 1.9 BIG ROCK POINT PI. ANT 1986 GASEOUS DESIGN OBJECTIVE ANNUAI QUANTITIES I

D /C l

Dose FEctor Design Objective Nuclide Oraan mrem /Ci Annual Quantity (CL)

H-3 Tota 1 Body-c 1.12E-05 4.46E+05 N-13 Total Body.

1.53E-51 3.27E+51 C-14 Bone-c 9.80E-03 1.53E+03 Na-24 Total Body 1.10E-04 4.55E+04 Ar-41 Total Body 1.62E-05 3.09E+05 Cr-51 GI Tract-a,t 5.20E-04 2.88E+04 I'

Mn-54 GI Tract-t 5.38E-02 2.79E+02 Fe-55 Bone-c 4.57E-02 3.28E+02 Na-56 GI Tract-c 5.07E-08 2.96E+08 Co-57 GI Tract-t 1.88E-00 7.98E+02 Co-58 Total Body-c 1.12E-02 4.46E+02 Fe-59 GI Tract-t 5.33E-02 2.81E+02 Co-60 Total Body-c 6.66E-02 7.51E+01 Ni-65 GI Tract-c 2.26E-08 6.64E+08 Zn-65 Total Body-c 1.01E-01 4.95E+01 Be-82 Total Body 1.38E-03 3.62E+03 Kr-83m Skin 3.94E-08 3.81E+08 Kr-85 Skin 3.91E-06 3.84E+06 Kr-85m Total Body 2.26E-06 2.21E+06 Kr-87 Skin 3.65E-05 4.11E+05 Kr-88 Total Body 2.79E-05 1.79E+05 Rb-88 Total Body-c 2.66E-33 1.88E+33 Kr-89 Total Body 1.18E-06 4.24E+06 Sr-89 Bone-c 2.01E+00 7.46E+00 Se-90 Bone-c 8.27E+01 1.81E-01 Sr-91 OI Tract 1.28E-05 1.17E+06 Sr-92 GI Tract 1.18E-07 1.27E+08 Nb-95 GI Tract-a 5.78E-02 2.60E+02 Zr-95

-GI Tract-t 7.04E-02 2.13E+02 Mo-99 Kidney-i 2.31E-03 6.49E+03 Tc-99m GI Tract-i 1.17E-07 1.28E+08 Tc-101 Total Body 1.26E-40 3.97E+40 Ru-103 GI Tract-a 9.22E-02 1.63E+02 Ag-110m GI Tract 1.91E-01 7.85E+01 Sb-124 GI Tract-t 1.71E-01 8.77E+01 Sb-125 GI Tract-t 9.67E-02 1.55E+02 Te-127 GI-Tract-a 9.45E-06 1.59E+06 I-131 Thyroid-i 3.86E+00 3.89E+00 Xe-131m Skin 1.73E-06 8.67E+06 I-132 Thyroid-c 7.26E-08 2.07E+08 I-133 Thyroid-l 3.53E-02 4.25E+02 Xe-133 Total Body 5.94E-07 8.42E+06 Xe-133m Skin 3.60E-06 4.17E+06 Cs-134 Liver-e 1.53E+00 9.80E+00 IC0186-0012A-HP01

51 Table 1.9 (cont'd)

BIG ROCK POINT PLANT 1986 GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Dose Factor Design Objective Nuclide Organ mrem /Ci Annual Quantity (CL) 1-134 Thyroid-c 4.93E-14 3.04E+14 I-135 Thyroid-c 9.93E-05 1.51E+05 Xe-135 Total Body 3.59E-06 1.39E+06 Xe-135m Total Body' 3.17E-06 1.58E+06 Cs-136 Total Body-i 1.55E-02 3.23E+02 Cs-137 Bone-c 1.50E+00 1.00E+01 Xe-137 Skin 2.48E-06 6.05E+06 Cs-138 Total Body 4.32E-22 1.16E+22 Xe-138 Total Body 8.39E-06 5.96E+05 Ba-139 GI Tract 2.38E-11 6.30E+11 Ba-140 Bone-c 1.01E-02 1.49E+03 La-140 GI Tract-a 1.50E-03 1.00E+04 Ce-141 GI Tract-t 2.80E-02 5.36E+02 I

Ce-144 GI Tract-t 7.45E-01 2.01E+01 Np-239 GI Tract 2.52E-04 5.95E+04 IC0186-0012A-HP01

o

$2 II.

LIQUID EFFLUENTS A.

CONCENTRATION 1.

RETS Requirement Technical Specification 13.1.2.1 of the Radiological Effluent Technical Specifications (RETS) requires that the concentration of radioactive material released at any time from the site to unrestricted areas shall ce limited to the Maximum Permissible Concentration (MPC) specified in 10 CFR 20, Appendix B, Table II, Column 2 for nuclides other than dissolved or entrained noble gases. For dissolved or entrained noble

~4 gases, the concentration shall be limited to 2x10 uCi/mi total activity. To ensure compliance, the following approach will be used for each release.

2.

Prerelease Analysis Most tanks will be recirculated through two volume changes prior to sampling for release to the environment to ensure that a represan -

tative 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 deter-mine appropriate recirculation time.

Petor to telease, a grab sample wiLL be. analyzed for each release, and the concentration of each radionuclide determined.

n C = )b, C (2.1) g i=1 MIO784-0004A-RS06

o 53 where:

C

= Total concentration in the liquid effluent at the release point, pCi/el.

C

= Concentration of a single radionuclide i, pCi/e1.

g 3.

Total MPC-Fraction The Total MPC-Fraction (R)) for each release point will be calculated by the relationship defined by Note 1 of Appendix 8,10 CTR 20:

R())=

1 C

MPC (2.2) g l

1 where:

C

= Undiluted effluent concentration of radionuclide i, as g

determined in Section 2.1.2, pC/ml.

MPC

= The MPC of radionuclide i, as specified in Section 2.1.1, g

i pCi/ml.

~

R) = The Total MPC-Fraction for the release point.

'~

The sum of the ratios at the discharge to the 1ake must be 51 due to the releases from any or all concurrent releases.

The following relationship will assure this criterion is met:

I f (R -1) + f (R 'l)

• t ( 3-0 F

(2.3) g g 2 2 3

where:

~

f.f 'I g 2 3 The effluent flow rate (gallons / minute) for the respec-

=

tive releases, determined by plant personnel.

R,R,R,

= The Total MPC-Fractiana for the respective releases as g 2 3 detemined by Equation 2.2.

F

= Minimum required dilution flow rate. Normally, a conservatively high dilution flow rate is used, that is, flow rate used n (b )(F) where b is a conserva-g g

tive f actor greater than 1.0.

MIO784-0004A-RS06

o 56 A composite list of concentrations (C;), by isotope, will be used with the actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.3 to demonstrate compliance with the limits in Section 1.

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

C.

DOSE 1.

RETS Requirement Technical Specification 13.1.4.1 the Radiological Effluent Technical l

Specification (RETS) requires dhat the quantity of 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:

During any ca_lendar quarter,1.5 mrem to the total body and 5 4.

mres to any organ, and b.

During any calendar year, 3 mren to the total body and 10 mrem tc any organ.

To ensure compliance, quantities of activity of each radionuclide released will be :uased for each release and accumulated for each quarter as follows:

e MIO784-0004A-RS06

o 57 2.

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

A /C 5 0.5 (2.5) g t where:

A

= Cumulative quarterly activity of nuclide i identified in g

liquid release (Ci).

C

= Design objective annual quantity of radionuclide i from g

Table 2.2.

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

The design basis quantities are derived in such a conservative manner that doses may be greatly overestimated by this technique. As.a consequence of this conservatism, and in light of historically consistent operatians with releases well below annual design basis quantities, the Big Rock Point Plant Technical Specifications do not l

require monthly dose projections.

Instead, if at, any time, calcula-tions by Equation (2.5) results in values greater than 0.5 for a given quarter or 1.0 for year-to-date, the flRC LADTAP code will be run to ensure that Technical specification 13.1.4.1 has been met.

l Values for the design basis quantities, (Ci), and the dose pec. Curie (D /C,)g for each nuclide i shown in Table 2.2, were calculated as c

follows:

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o 58 0

2.1 Water Innestion The dose to an individual froe ingestion of radioactivity from any source is described by the following equation:

i

'(2.6)

D) =

(DCT)g) x I ree g

ist where:

D)

= Dose for the j'u organ from radionuclides released, rem.

J

= The organ of interest.

th (DCT)q

= Adult ingestion dose commitment factor for the j th organ from the i radionuclide res/pCL, see Table 2.1.

th I

= Activicy ingested of the i radionuclide, pCL.

t I is described by:

g (A )(V)(365)

Iga L

pCi

('. 7) z (800)(d) where:

365

= Days per year.

th A

• Annual activity released of i radionuclide, pCL, g

V s Average rate of water consumption (730 al/d ICRP 43,

p. 358).

d

= Dilution water flow for year (ml).

800

= Dispersion factor from discharge to nearest drinking water supply.

l MIO784-0004A-RS06

e 59 o

The dose equation then becomes:

i

(

3=E ij * ^i (2.8)

D d

tal 2.2 Fish Inaestion The dose to an individual from the consumption of fish is described by E

Equation 2.10.

In this case the activity ingested of the i radio-i nuclide (I ) is described by:

g I

g = ^i I

i pCi 15d (2.9) where:

A

= Annual released of.1 radionuclide, pCi.

g ch B

= Fish concentration factor of i radionuclide pCi/as i

g see Table 2.0.

pC1/al.

F

= Amount of fish eaten per year (21 kg).

15

= Dispersion factor from discharge to fish exposure potat.

d

= Dilution water flow for year (al).

Substitution of Equation 2. 9 into Equation 2.6 gives:

l 1

D) = 1400 A xB x DCF Rem (2.10) g g

g ist i

i MIO784-0004A-RS06

e 63 O

of operation, to assure a dependable source of power, to release quantities of material higher than a small percentage of 10 CFR 20 limits but not exceeding those limits under unusual operating condi-tions. Appendix I to 10 CTR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as is reason-ably achievable requirement.

The LADTAP code has been run to determine the dose due to drinking water at plant discharge concentration (800 x nearest drinking water intake concentration). The source term used is given in Table 1.1.

The most limiting dose of the person hypothetically drinking this water is 4.89E-01 mrem whole body. The release rate which would result in a dose rate equivalent to 500 mrem / year (the total body limit) is the Curies / year given in Table 1.1,8.94 times 500/.489 or 9141 CL/yr = 2.9E-04 Ci/sec.

III.

URANILH FTEL CYCLE DOSE A.

SPECIFICATION In accordance with Technical Specification 13.2.6.1 if either liquid l

or gaseous quarterly releases exceed the quantity which would cause offsite doses more than twice the limit of Technical Specification 13.1.4 then cumulative dose contributions from combined release plus direct radiation sources (from the reactor unit and radwaste storage tanks) shall be calculated. The dose is to be determined for the member of the public projected to be,the nest highly expose,d to these combined sources.

B.

ASSUMPTIONS 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 !! C.2.1 and II C.2.2.

MIO784-0004A-RS06

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