ML20153G104
| ML20153G104 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/12/1988 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20153G020 | List: |
| References | |
| PROC-880412, NUDOCS 8809080040 | |
| Download: ML20153G104 (74) | |
Text
{{#Wiki_filter:. . V0ttMI 25 REG ROCK POIFT PLANT RADIOLOGICAL EFFLUENT T/S REQUIED DOCUMI.NTS A. CFTSITE DOSI CALCULATIONS
- 8. PROCESS COMROL PROGRAM Approved by n.. ...
Effec.tive D.t. I 8b 8809080040 680831 PDR ADOCK 05000155 R PDC . L
l l VOLUME 25 BRP RADIOLOGICAL EFFLUENT T/S REQUIR$D DOCUMENTS Rev 3 Page 1 of 2 BIC RCCK POINT PLANT MANUAL YOLUME 25 BRP Radiological Etfluent T/S Required Documents A. Of f Site Dose Calculations
- 5. Process Control Progran I
l l TABLE OF CONIENTS/ETTECTIVES PAGES Revision Pg A. OFF SITE DOSE CALCULAIIONS 3 71 1 GASE0US EFFLUENTS 1 of 71 A. ALARM / TRIP SETFOINT METHOD 1 of 71 Allowable concentration 1 of 71 Monitor Response ?, of 71 B. DOSE RATE CALCULAIION 3 of 71 C. DESIGN BASIS QUANTITY (DBQ) LIMITS 15 of 71 Continuous Releases 15 of 71 Exceeding DSQ Lir_its 16 of 71 Releasing Radione:lides Not Listed in Table 1,9 16 of 71 D. GASEOUS RADWASTE TRIAINENT SYSTD( OPERATION 14 of 71 Systes Description 14 of 71 Determination of Satisf actory Operation 18 of 71 E. RELEASE RATE FOR OFFSITE MFC (500 mRee/yr) 20 of 71 i F. PARTICULATE AND IODINE SAPLING 21 of 71 , I 1 C. MOBLE CAS SAMPLING 22 of 71 1 H. TRITIUM SAMPLING 22 of 71 l l l II LIQUID EFFLUENTS 51 of 71 A. CONCENTRATION 51 of 71 RETS Requirament 51 of 71 Prerelease _A'nalysis 51 of 71 Total MPC-Fraction 52 of 71 l - L i I
VOLUME 25 BKP RADIOLOGICAL EPFLUENT T/S RIQUIRED DoctHENTS Rev 3 Page 2 of 2 Revision Pages S. INSTRUMENT SETPOINTs 53 of 71
~Setpoint Determination 53 of 71 Post Release Analysis 53 of 71 C. DOSE $5 of 71 RETS Requirement 55 of 71 Release Analysis 56 of 71
' Annual Analysis 59 of 71 i
- 3. OPERABILIIY OF LIQUIS RADWASTE EQCIPMENT 61 of 71 l
l
!. RELEASE RATE POR OFFSITE M/C (500 mkes/yr) 61 of 71 I
III CRANIUM FUEL CYCLE DOSE, 63 of 71 A SPECIPICATIONS 63 of 71 i 5 ASSUMPTIONS 63 of 71 C DOSE CAL;ULATION 64 of 71
- 3. *1t0 CESS CONTROL PROGRAM 0 4 1.0 PR0 CRAM OVERVIEW L of 4 2.0 DEWATERING SOLIDS IN HICE INTEGRITY CONTAINERS (HIC) 1 of 4 3.0 DELAWARE CUSTCR4 MATERIAL (DCN) - SILICATE CDENT 1 of 4 4.0 10 CPR 61 REQUIREMENTS 2 of 4 1
5.0 A350RSED MATERIALS TRichland lurial Site Only) 3 of 4 l ATTACEMINT 1 - Table ! - Absorbents 4 of 4 i l 1 l l l 1 I L _ .
VC L'J 225 39' RADIOLO2!!AL ETTLt. TNT T'? '7 ;UIFU DOCL'MENTS D* 3 A. CFTSITI Or.?I ALct'LAT'Or.: Fate 1 of 71 .
- f. CA$t0U$ IT7ttt.VTs
'l A. ALARM / TRIP SETPo!NT METM00 Technical Spe:!ft:stion 131 3.*. requires that MFC is n:t exceeded when averaged :ver a Fert:1 n:t 1: exceed 1 hour. !ased sn the definition of MPO. the 1:se rate in unrestricted aress due to gase:us effluer.ts from the site shall be linited at all times to the folleving values:
. I
- 1. 500 eras /y to the total body and 3,000 ares /y to the skia free j noble gases.
2. 1,500 nrea/y to any organ fran radiotodines and particulates, due to inhalation. i 5 i l Specification 13.1.1.1 requires gaseous ef fluent soaitars to have j
! alars/ trip setpoints to ensure that offsite concentrations, when averaged over 1 hour, will not be greater than KPC. This sectioa of , ; the ODCM describes the methodology that will be used to determina j i these setpoints. ,'
The methodology for determining alars/ trip setpoints is divided into two major parts. The first consists of calculating an allowable 1 concentration for the nuclide atiture to be released. The second consists of determining monitar response to this sixture in order to J establish the physical settings on the monitors. 1.0 A,11owable Concentration l The total MPC fraction (R h ) for the single (stack) release point l will be calculated by the relatic: ship defined by Note 1 of Appendix B, 10 CTR 20: R(g) = ( ) (T) M
= 51.0 (1 1) c PC h k
k
VOLT.HI 29 BPP .RC: LCCICAL ITTLt.Trl T/S ?I4UI?ED DOC %.S Fev 3 A. ??T!!3 DCSE CALCU!.ATIO:C . Page 2 of 71 Ci a Concentration, at ambient temperature and pressure cf nuclide 1 (pC1/cc) MPC( = The MFC of nuclide i froe 10 CTR 20, A;pendix 5 Rgg) = The total MPC fraction for release poist k ' X/Q s Most conservative sector site boundary dispersion (9.!!I 04 sec/m3) T = Release flow rate (39,000 cfm = 18.4 e3/sec) for stack eenitor consid(rations; variable for other monitors. ! 2.0 Monitor Response Normal radioactivity releases coesist predoeinstely of 30 minute decayed fission gasses. Therefore, stack sonitor re'sponse calibrations are performed to fission gas typical of normal releases (30-minute decayed of fgas). Air ejector offgas sonitor seasures only slightly decayed gasses, however, so is calibrated to provide g accurate response to relatively fresh firview gueses. Response monitors used to define fission product release estas under accident . l conditions say vary from that of these sixes, bewever. Monitor response for the two categories of monitor is determined as follows: ,
- 1) Normal Releases (30 einute decayed fission gasses) l Total gas concentration (pCL/cc) ct the monitor is calculated.
The :alibration curve or constant for cpe/(sci /cc) is applied t? determine cpe expected. The setting for sonitor alares is i established at some factor (b) greater than 1 but less than 1/Rg (Equetton 1.1) times the allowed conce:tration(c): I
- abI C (I.I) l
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y, VOLLME 23 ERP FK : :.CC AL ETT*.',T.-' T/3 F AJIPED DCCLYriTS Rev A. CTTI:TI NSE CA1.7.~ CIONS Pag 9 3 of 11
- 2) Acendest Releases j
Monators are preset to alars at or before precalculated offstte dose rates would be achieved under hypothetical accident-conditions. These setpoints are established is accordance with l Energency plan requirements for deitaing Emrgeery Actiou kiets and associated actionr. Emergency !spissen? ing Pruce-dures contain monitor specific curves or calibration coinereNr.
- for conversion between cpe and pCi/cc (or R/hr and pC1/cc).
depending on monitor type, for fissf 9n pr:wiur.t mistures se a
- tanction of sixtura decay tiet.
4 When these monitors are utilized for other than accident condi-tions, either an appropriately decayed "accident," conversion I curve may be used, or a decayed fission gas cal'.bration factor j say be applied. In these cases, setpoints are establiabed as j in 1) above. I B. DOSE RATE CALCUI.ATION ; 1.0 The first step involves calculating a dose rate'baset',on the ~4stga objective source ters siz used in Appendia ! licensing calcum%as. t Recent meteorological data obtained froe current meteorologi;al monitoring instrumentation are used in this calculatios. Dosis are determined for (1) noble gases and (2) todines and particulates. Dose rates as defined is this asction are I i l l l a m _A- 'A
.e .
VOLLHE 25 3RP RAD 80Z,0GICAL EFF /,TC T/S REQUU.C DOCLHE'CS A. OFFSITE :CSE CALC'JLATIONS hv 3 Page 4 af 71 in terms of 10 CFR 50 Appendix I limits of ares per quarter and sillires per year. All dose pathways of major importance in the ! Sig Rock environs are considered. ! 1.1 Equations and assumptions for calculating doses from noble gases are . . as follows: 1.1.1 Assumptions 1
- 1. Dos'es to be (ciculated are the maximum offsite point in air, !
total body and skin.
- 2. Exposure pathway is submersion widda a cloud of noble gases. ,
- 3. Noble gas radionuclide six is based on the historically I t
observed source term given in Table 1.1, plus additional l nuclides.
- 4. Basic radionuclide data are given in Table 1.1. . I
- 5. '# '
All releases are treated as elevated at 73a. *
- 6. Meteorological data expressed as joint-frequency distribution : .
of wind speed, wind direction, and atmospheric stability for the period resulting in X/Q's and D/Q's shown in Table 1.3. ,
. 7. Raw meteorological data consist of wind speed and direction seasurements at 71m.
- 8. Dose is to be evaluated at the offsite exposure points where maximum concentrations are expected to exist and nearest 1
residents. i t'
- 9. Potential maximum population (resident) exposure points are identified in Table 1.4.
I l i 1 I I l l
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VOLUME 25 ?RP RADIOLO.'d?.1L EFFLUENT T/S RECUTPE DOCLNENTS Rev 3 A. CFFSITI XiE CALCULATIONS Page 5 of 71
- 10. A semi-ir. finite cloud model is used.
- 11. For persec exposures, credit is taken for shf elding by residence (factor of 0.7).
- 12. Radioactin decay is considered for the plume.
- 13. A sector-average dispersion equation is used.
- 14. The wind speed classes that are used are as follevs:
Wind Speti Class Number Ranae (a/s) Midpoint (a/s) 1 0.0-0.4 0.0 2 0.4-1.5 0.95 3 1.5-3.0 2.25 4 3.0-5.0 4.0 5 5.0-7.5 6.25 6 7.5-10.0 8. 75 ' ' - 7 >10.0 --
- 15. T' a stabi.ity classes **Mt will be used are the standard A through G classifica: .s. The stability classes 1-7 will correspoci to A=1 3=2, . . ,, G=7.
- 16. Terrain effects ate not considered, and no open terrain recirculation factors are applied.
- 1.1.2 Equations To calculate the dose for any one of the exposure points, the following equations are used.
For determining the air concentration of any radionuclide: i 9 7 ' Xi= 1/2 f_lk 0P 1 .A I
"j (2nx/n)-
,,p x)j-zk jul Kal X exp
[g-h8\ ( af , (1,3) 3 a
v:,,n 25 BRP RADZOLOG::AL EFFLUENT ! $ REQU2 BED DoctNENTS Rev 3 A. OFFSI"T .r,3E CALCULAT::n Page 6 of 71 ; where: Xg j r Air concentration of radionuclide i, pC1/m3 . f jk = Joint relative frequency of occurrence of winds in wind speed class j, stability class k, blowing toward this exposure potat, erpressed as a fraction. Q = Average release ra',e of radionuclide 1, pCi/s. p
= Fractica of radionuclios ressining in plume.
1,g = Vertical dispersion coefficient for stability class k (a). u) = Midpoint value of wind speed class interval J, s/s.
- x. = Downwind distance, s.
a = Number of sectors,16. Ag
= Radioactive decay coefficient of redionuclide i, a 1 2nx/n = Sector width at point of interest, m.
For determining the total body dose rate: D TB
- I tDFB g I.4) i -
where: -_
~
U
- T **l body dose rate, aree/y.
TB - X g = Air concentration of radionuclide i, pCi/s3 . DFB g = Total body dose factor due to gamma radiation, ares /y per pCi/m3 (Table 1.5). For detemining the skin dose rate: D, a Xg (DFSg + 1.11 DFYg ) (1.5) i l .
y, _t;yz 25 3E7 ?.ADf0LOGTCAL EFFLUENT T 's REQUIGED M ",72N"'S A. TFSITE DOSE CALCULATI",'3 Rev 3 Page 7 of 71 where: D, = Skin dose rate, aree/y. Ig = Air concentration of radionuclide i, pCi/m3 . DT5 g = Skin dose factor due to beta radiation, eres/y per pCi/m3 (Table 1.5). 1.11 = The average ratio of tissue to air energy absorption coef ficients, mees /arad. DFT g = Garama-to-air dose factor for adionuclide i, mead /y per pCi/m3 (Table 1.5). For determining dose rate to a point in air: D, = 3.17E-02 Xg (DFYg or DFBg ) (!.6) i q where: / D, = Air dose rate eres/yr
~
DTB - Air dose factor for beta radiation (Table 1.5) .
, 3.17E-02 = Conversiot 'f rom r'eleas /yr (Ci) to pCi/m3 divided by seconds /yr.
1.2 Equations and assumptions for calculating doses free radioiodines and particulates are as follows: 1.2.1 Assumptions,
- 1. Dose in to be calculated for the critical organ, thyroid, and the critical age groups, infant (milk) and child (green, leafy vegetables).
- 2. Exposure pathways from iodines and particulates are milk ingestion, ground contamination, green leafy vegetables from home gardens, and inhalation.
- 3. The radioiodine a64 particulate six is based on the histori-cally observed source tern given in Table 1.1.
VOLLHE 25 BRP ?ADIOLOGICA*. UFWENT T/S REQUITiED F. CHEM A. "FFSITE DOSE !.C ULATIONS Rev 3 Fage 8 of 71
- 4. Etsic radionuclide data are given in Table 1.2.
- 5. All releases are treated as elevated (73e).
- 6. Annual average I/Q's are given in Table 1.3.
- 7. Raw meteorological data for elevated releases consist of wind speed and direction measurements 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 {
thi nearest cow, goat and home garden locations in each sector.
- 11. Terrain effects are not considered.
l
- 12. Plume depletion and radioactive decay are considered for I air-concentration calculations.
- 13. Radioactive decay is considered for ground-concentration calculations.
- 14. Milk cows and goats obtain 100% of their food froe pasture l grass May through October of each year.
- 15. Credit,is taken for shielding by residence (factor of 0.7). ~
.- j 1.2. 2 Equations .
\
l To calculate the dose for an'y one of the potential maximus-exposure I i points, the equations of Sections 1.2.2.1 - 1.2.2.4 are used. 1.2.2.1 Inhalation Equation for calculating air concentration, X, is the same as in the Noble Gas Section 1.1.2 (Equation 1.3). l l l l l
\
VOIly 25 BTsP RADIGI4GICAL ETFLUENT T/S 8.E;*.*IGED DOCUMEN'IS A. OTFSITE 'CSE CALCULATIONS "ev 3 Tor determining the organ dose rate: Page 9 of 71 l l 1 4 Dg = 1x10 Xg DFI g 8R (l.7) i where: Dg = organ dose rate due to inhalation, area /y. Xg = Air concentration of radionuclide i, pCi/a3. DTI g = Inhalation dose factor, area /pci (Table 1.7). I BR = Breathing rate 1400 3m /y, infant; 5500 3m /y, child; or 8400 m 3 /y adult. 1 x 10' = pCi/pci conversion f actor. 1.2.2.2 Ground Contas,ination For determining the ground concentration of any nuclide: 7 og= 3.15x107 fk 01 DR (2nx/n) A g [1-exp -(Ag tb)I (ex g[ '(I.8) k=1 Ej 202
-{:
. - \
where: Gg = Ground concentration of radionuclide i, pCi/ma , k = Stability class, i k = Joint relative frequency of occurrence of winds in stability class k blowing toward this exposure point, erpressed as a fraction.
)
Qg = Average release rate of radionuclide i, pCi/s. ' DR = Relative deposition rate, a2 (Table 1.3 for DR/2nX). x = Downwind distance, s. n = Number of ser: tors, 16. 2nx/n = Sector vidth at point of interest, s. Ag = Radioactive decay coefficient of radionuclide i, y*1 g = Time for buildup of rad.%nuclides on the ground, 35 y. 3.15x107 = s/y conversion factor. h = Stack height (73a) ca = Vertical dispersion coefficient (a)
YOL M 25 BRP RAD * ?*.03ICAL EFFLUENT T/S RWJIRED DOCUME'Ci A. OFFS O DOSE CALCULATICNS Rev 3 Page 10 of 71 Tor determining the total body or organ dose este from ground coctamination: DG = (8,760)(1x108 )(0.7) Gg DFG g (I.9) i where: Dg = Dose rate due to ground contamination, ares /y. Gg = Ground concentration of radionuclide i, pCi/m2 , DFG g = Dose factor for standing on contaminated ground, mees /h per pCi/m2 (Table 1.8). 8,760 = Occupation time, h/y. lx10s = 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 iny nuclide (except- C-14 and H-3) in and on vegetation: 7, .- CVg = 3,600 Ik 0 1 DR ( ,gg,,,,( g t,)] + (I.10) (2Ax/n) ( Y, AEi Eg , [1-exp (-Aght )I -ha (. A (tg l A i
/k *) k where: !
l CV g = Concentration of radionuclide i in and on vegetation, pCi/kg. k = Stability class. f k = Frequency of this stability class and wind direction combination, expressed as a fraction. i Qg = Average release rate of radionuclide i, pCi/s. 8
r
.*cLLHE 25 3RP RADIC'lCICAL EFFLL:.a. T/S REQUIRFD DOCUMEN"5 A. OFFSIC DCSE CALCUI.'s-~0NS 14v 3 Page 11 :f 71 DR g = Relative deposition rate as a functioc of wind speeJ.
stability class acd downw'ad distance, e*I (Tigures
- through 10 of Regulatory Guide 1.111).
x = Lownwind distance, s. a = Number of sectors, 16.
..nx/a = Sector width at point of interest, s.
r = Traction of deposited activity retained or vegetatio2 (1.0 for iodines, 0.2 for particulates). A Ei = EUective removal rate constant, g=Ag + Ay, whert Ag is the radioactive decay coefficient, h'1, sud A, is a seasure of physical loss by weathering (A, = .0021 h'1), t, = Period over which deposition occurs, 720 h. Y, = Agricultural yield, 0.7 kg/a t, B gy = Transfer factor f rom soil to vegetation of radionucl de i (Table 1.6). A g
= Radioactive decay coefficient of radicauclide i' h"1 t
b = Time for buildup of radionuclides on the ground, 3.07x10s b T35y). .. i P = Effective sutixe density of soil, 240 kg/m . 0 , 3,600 = s/h conversion factor. -
- h = Stack height (73a) e, = Vertical dispersion coefficient (a) t h
a liold-up time between harvest and consumption of food. 0 h for par ture grass or 2160 h for storage feed. For determining the concentration of C-14 in vegetation: 1 3 CVg4 = 1x10 Xg4 (0.11/0.16) (f.11) where: , 1 CV g4 = Concentration of C-14 in vegetation, pCi/kg. l X g4
= Air concentration of C-14. pCi/m 3. l 0.11 = Tlaction of tota). plant mass that is natural carbon.
0.16 = Concentration of natural carbon in the atmosphere, g/m3 . lx103
- g/kg conversion factor.
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VOLUME 29 :.;P BADf 0LOGZCAL ETTLlTE'C T/S @ EQUI @E' ?CCUME!CS
- 1. OFFS 8TE DCSE CALCULA30 G Rev 3 Page 12 of 71 Ter determining the concentration of E-3 in vegetation:
3 It.lla) CV7 = 1:10 IT (0.75)(0.5/B) where CY = Concentration of E-3 in vegetation, 9Ci/kg. 7 X, = Air conce-**ation cf H-3. pC1/s
- 0.75 = Fraction < f totsi plant mass that is water.
0.5 e Ratio of uitium :oncentration in plant water to tritiva
. concentration in atmospheric water.
H = Absolute humidity of the atmosphere, s/a3 . lx103 = g/kg conversion factor. For determining the concentration of any nuclide in cow's or goat's milk: CMg = CVg FM g og exp (-A g t) g d.12)
~
viere. .
~
Ch g
= Coneentration of radionuclide 1 (including C-14 and H-3) in silk, uCi/1.
CV = Concentration of radionuclide i in and on vegetation, 3 uCi/kg. PH g = Transfer factor from feed to milk for radionuclide t, d/1 (Table 1.6). Qg = Amount of feed consumed by the milk animal per day, kg/d.
= Radioactive decay coef ficient of radionuclide 1. d'I.
~
l g
, t g
= Transport time of activity from feed to milk to receptor, 2 days.
For determining the organ dose rate from ingestion of green leafy I vegetables and milk o - lx105 _ CMg org UM (t.13) L n&
- VOLLHE 25 2?P RAD 20 LOG: i'. EFTLUENT T/S DEQUZ9E~, 20CUMENTS A. CFFSZTE XSE CALCULATIONS l Rev 3 l Page 13 of 71 i l
I where: ' D = organ dose rate due to ingestion, ares /y. CM g = Concentration of radionuclide i in vegetables or silk, j WCi/kg (or liters). DF g = Ingestion dose factor, stem /pci (Table 2.1). UM = Ingestion rate for silk, 3301/y; for vegetables 26 kg/y ) (child), no ingestion by infant. lx108 = pCi/pci conversion factor. 1.2.2.4 Ornan Dose Rates i For deterwining the total thyroid dose rate free iodines and particulates: i D=Dg+Dg+D3+Dy (I.14) where:
~
D = Total orpn dose rate, aren/y. -
- l Dy = Dose rat a due to inhalation, mres/y.
Dg = Dese ' rate due to ground contamination, ares /y. D 3 = Dose rate due to milk ingestion, ares /y. Dy = Dose cate due to vegetable ingestion, area /y. i 1.2.3 The maximum organ dose rate, maximum total body dose rate; maximum skin dose rate plus beta and samma air doses calculated is the l previous section dec 1r2.2) are used to calculate design basis ' quanr'.*ies as described in Section 1.3. , 1 1.3 Desita Basis Quantities l The desian basis quantity of a radionuclide esitted to the atmos-phere is the amount of that nuclide, when released in one year, l I which would result in a dose not exceeding any of the following: j 1 l
' --- - - - - - - - ~ - " - - - ' '
V!".".yE 25 BRP RADIOLOGICA!, EFFLtJEyr T $ REQUITED DOCLHE:frS A. CFFSITE DCSE CALCULAT!!"J Rev 3 Page 14 of ";
- a. 15 millires to any organ of an individual fron todines and particulates.
- b. 20 eillires to skin of an individual from noble gas.
- c. 10 mil.lires to the total body of an individual from coble gas.
Design basis quantity (Ci) is the smallest value for each nuclide, calculated by dividing the dose Itaits (a through c above) by the appropriate dose calculated in step 1; the result then is meiltiplied by the amount of radionuclide (Ci) used to conservatively estimate the doses of Section D, as listed in Table 1.1 (or assumed g l hypothetical 1 Ci/ year for nuclides not actually present): DBQ = DAI (cc ) (I.15) D, where: . D AI
- Appendix I dose Itait (area or mead).
D, = Calculated dose free step 1 (rrem or acad). C, = Quantity of nuclide resulting in dose D, (CL). DBQ = Design Basis Quantity (Ci). The limiting values for Design Basis Quantities for -adionuclides enleased to the atmosphere are given in Table 1.9.
, _ . _ , _ _ _ _ _ , - _ _ _ . _ _ _ _ _ - - - _ _ . , _g__ . - _ ,# w.--_- -._~c __ _- . -
VOLUME 25 BRp ?.CIOLOGICAL EFFLUENT T/S PEQUIRED DOC'Y..NTS A. 27 SITE DOSE CALCULATIONS Rev 3 Page 15 of 71 The imerse of the ratio C,/D, in the above equation (i.e. . D,/C,) is a aseful value, since it representa the most limiting dose per unit luantity of each nuclide released. 1.4 Land Use Census and DBQ Changes Tecrehal Specification 13 2 3 describes the requirements for an a:.=al land use census and revision of -le CDCM for use in the foll:.".ng calendar year. Aress of the ODCY. which will be reviewed, and : ranged if appropriate, are Table 1.k (*And Use Census Data by Sector), and Table 1.9 (Caseous Design Basis Objective Annual Quantities). Changes will be effective on January 1 of the year folloving the year of the survey C. DESIGN BASIS QUANTITY (DBQ) LIMITS
-1.0 Conti:uous Releases ,
Lov level continuous releases from the stack are totaled on a weekly basis and sunned with any ba.tch 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 suaned in order to assuu that the sua fraction of all nuclides does not exceed 1.0: Ai {, (m), < 1 0 (I'I0) i i
. VOLUME 23 BRP RADIOLOGICAL T?LUENT T/S REQUIRED DCNNTS A. CFFSZ DCSE .'.C.CULATIONS i Rev 1 ' Page 16 of 71 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. Per Technical Specification 13.1.4.4 this calculation mst be performed at least once per 31 days. 2.0 Ezeeeding DBQ Limits As discussed under B.I.3, the DBQ is a very conservative estisite of activity which could give doses at Appendiz 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. Ho: sever, further discre-tionary releases should be deferred until an accurate. assagement of dose is sade by use of the NRC GASPAR computer coce. Tne computer run will utilize the annual average joint frequency meteorological data
, based on not iess thari 3' years of meteorological' measure:mant, and will reflect demoeraphic and land use information from the land Use survey
^
generated in the mos: recent prior year. Where appropriate, seasonal adjustments will be applied to obtain realistic dese estimates since both recreational and agricultural activities can vary greatly in relation to season of the year. It should be noted that Big R'o ck Point to date (based on ieview of ~ 1 semiannual effluent data) has never exceeded the annual or quarterly DBQ fraction, despite its conservatism at any time in the past to yests (since stainless r ccel fuel claddios was replaced by aircatoy ; and other engineering crianges were made). Thus, it is not expected that an alternate to the DBQ aethod will be required unless the Plant is in a significantly off-normal condition. 3,n Releasing Radionuclides Not Listed in Table 1.9 i ( Table 1>9 contains all nuclides identified to date as rout 4ne constituents of gasens releases at Big Rock Point Plant, ;hs 1 e l
VOLUME 25 BBP RADICLOGNAL :.e.-I.UE!C T/S REr; RED DOCLME!CS A. OFFSITE DCSE C/J.CULATIONS Rev 3 l Pa,e 17 of 71 those common to boi'.ing vater res: tors in general, even if not previously detected at Big Rock 7: int. From time to time, however, other nuclides may be detected. If the unlisted nuclide constitutes less thaa 10% of the MPC-fraction for the release, and all unlisted nuclides total less l than 25% of the MPC-fraction, the nuclide say be considered not present. 4 If the unlisted nuclide constitut es 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 inc hde a design basis quantity specific to that nuclide. -
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4 m 4 4 i 4 l l l l l l 1
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I
, YpLUME 25 BRP ftAO 0*CGICAL EFFLUENT T/S PEQUIRED DOCUMLT!S I
A. OFPS:~I DOSE CALCULATIONS ' Rev 3 ' Page 18 of 71 ! l D. GASEOUS RADWASTE TREATMENT SYSTDI OPERATION
- 1. System Description The gaseous radwaste systes consists of a delay line for condenser offgas which provides approximately 30 minutes of decay time prior to release via the 73e stack. A flow diagram of gaseous waste release paths is shown in Tigure 1-1.
Condenser offgas represents more than 95% of the total gaseous source ters. The other minor sources are gland seal condenser exhaust, containment venti 11ation, radwaste systen vents and misce,11aneous turbine building system leakage. 'All these ,
, sources are ducted to the stack for telease.
- 2. Determination of Satisfactory Operations Operability requirements for the gaseous waste tesatsent are not specified. This is because the delay lino is an integral part of the release path piping for condenser offgas. ;
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VOIANE littl* ItA!:10llEICAL EFFIlJENT T/S H1X111THED IX .EN'IS A. OFFSITE DOSE CAlfilLATIONS g9 BIG ROCK POINTGASEOUS EFFLUENT FLOW PATHS nA~ i-i f
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VOLWE 25 ??? RADIOLOGTCAL EFFLUEr T/9 @EQUIRC 'OCUMENTS l ' l t. OFFSITE DOSE CALCULACONS Rev 3 l Page 20 of 71 l E. REII.ASE RATI TOR OTTSITA MPC (500 mRes/yr) 10 CTR 20.106 requires radioactive effluent releases to unrestricted areas be in concentrations less than the limits specified in Appen-diz 8, Table II when averaged over a period not tc exceed see year. (Note: There are no unrestricted acess anywhere within the site boundary as defined by Tigure 2.1.) Concentrations at this level if present for one year will result in a dose of 500 ares due to external exposure or inhalation depending on the nuclide(s) rele a s ed, 10 CFR 50.36a requires that the release of redioactive materials be kept as low as reasonably achievable, However, the section further states that the licensee is permitted the flex ' ibilt.ty of operation, to assure a dependable source of power, to release quantities of material higher than a ; sail peteentage of 10 CFR 20 timits but not exceeding those limits under unusus1 operating conditions. Appendix I to 10 CFR 50 provides the numer-ica'. guidelines on limiting conditions for operations to acet the as low as reasonably achievable requirement. . The CASPAR code has been run to determine 'the dose due to exte(nal ~ I
~
l radiattort and it.halation. The source term used is listed'in Table l 1.1. Tht meteorology data is given in Table 1.3. Dose using annual l l 1 I l 5 l
' 1
VOLUME 25 DEP DADIOLOGI*.U. EFTLUENT T/S REQUIRED DOCUMENTS A, OTTSITE DOEI CALCULATIONS Rev 3 Page 21 of 71 ! l average meteor:*:gy,
. to the most limiting off site dese (whole ,
body) assumed :: be residing at the residence with highest X/Q. is 0.105 mFe= for one year. The release rate which would i result in a dose rate equivalent to 500 mrem / year (using the I total body liai-) is the Curies / year given in Table 1.1 (1.29E04) multiplied by 5:0/.105 or 1 95 ci/see. I The above cair:1ation is informational as a typical exposure j using average releases from Big Rock Point. Actual exposures are calculated per section I. A. T. PARTICULATE AND IODINE SAMPLING Particulate and iodine samples are obtained stos the continuous ; sample stream pelled from the plant stack. Samples typically are' l obtained to repsesent an integrated release from the stack.
?
Gamma acalytical results for particulate and halogen filters are combined for determination of total actisity 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" beto, and - ' the "identified
- count ra,te is subtracted from the observed 'cosat -
, rate to give "snidentified" beta. The "unidentified" beta. is assumed to be St-90 until results on actual Sr-90 (cheetcally j 4 l
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V: *.'.ME 2 5 BRP RADICLCGTCl?., EFFLUENT T '! ?EQUIRED DOCLHENTS A. OFFSITE DCSE oaf.,CULATICNS Rev 3 Page 22 of 71 : separated from a quarterly cosesite of filters) are obtained. Similarly, alpha activity not identified as natural radium or thorium or their daughters is assumed as Pu-239 until resvits of detailed analyses are obtained from quarterly composites. , G. NOBt.E GAS SAMPLING Condenser air ejector offgas will be sampled at least weekly and used to calculate monthly noble gas releases. Noaroutine releases will be quantified from the stack noble gas monitor (RE 8283) which has a LED of IE-06 pCi/cc. H. TRITIUM SAMPLING Tritius has a low dose consequence to the public because of low production rates. The major contributors to tritium effluents are evaporation from the fuel pool and reactor cavity (when flooded). Because of the low dose impact, gaseous tritium saepling will not be
~
required. Tritium effluents will be estimated using <onservative
, evaporation rate calculations from the fuel pool and reacior cavity.
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- VOLLHE 25 CM Pr:0 LOGICAL EFFLUENT T/S PrEQUIRED DOCLN Rev 3 A. GF!*-*E DOSE TABLE 1.1 Pego 13 of 71 i BIG RokklhNOUS AND LIQUID SOURCE TERhS. CQt!E8/ YEAR III Nuclide Gaseous (2) Ltquid(2)
I-3 1.21E+01 8.63E+00 N-13 1.53E+03 NA Na-24 3.52E-04 1.12E-06 ) Cr-51 2.82E-04 6.84E-03 ' Ma-54 5.50E-05 2.60E-02 Ma 56 1.70E-04 NA Co-54 1.65E-06; 6.17E-04 Fe-59 2,811-06 9.05E-03 Co 60 1.89E-04 4.21E-02 l Za-65 3.16E-05 9.01E-04 Br 82 8.11E-03 NA Kr 83a 2.61E+02 NA Kr-85 9.55E-01 MA Kr 85e 3.12E+02 NA Kr-87 1.19E+03 NA Kr-88 7.80E+02 NA Kr-89 6.96E+02 NA St-89 NA 2.271 04 Kr 90 7.76E+02 NA Sr-90 NA 2.22E-03 Kr 91 6.68E+00 NA St 91 5.61E-03 NA Sr-91 NA 1.54E-06 Nb-95 1.91E-06 NA Mo 99 3.10E-05 NA As-110e 1.57E-05 6.88E-05 St-124 .NA 4.01E-04 I-131 1.941-03, 1.57E-04 . , Xe-131m 4.38E-01' NA I-132 8.07E-03 NA - I-133 - 1.99E-02 NA Xe-133 2.01E+02 8.86E-05 Xe=133e 6.00E+00 NA Cs-134 4.04E-07 1.75E-02 1-134 1.24E-02 NA 11,5 3.00E-02 NA Xe-135 1.11E+03 NA X4-135e 1.15E+03 NA Cs-136 4.74E-05 NA Cs-13? 1.51E-04 2.04E-01 Xa-137 1.11E+03 NA Cs 138 3.17E-01 NA Xe-138 6.03E+03 NA lla-139 1.32E*03 NA Xe l.39 1.04E+03 NA Ba-140 1.86E-03 NA La 140 7.80E-03 5.04E-05 Xe 140 7.23E+01 NA
'3 g-203 1.321-06 NA Np-239 1.44E-04 NA Ur. identified beta 2.42E-03 6.76E-02 (1) Data derived from taking the effluents released during Jan-June 1980 through July-December 1983 and dividing by 4.
(2) Nuclide values listed as NA have not been observed at detectable levels in these waste streams.
VOLUMI 29 ERP PJC:0 LOGICAL EFT.*.I;T T/S REQUIriED DOCL%T:s Ro 3 Page 24 of 71 A. OFTS:'~E DOSE CALC.~.CIO?fS ;
, l l
l l TABLE 1.2 BASIC RADIONUCLIDE DATA KUCLIDE RALF-LIFE LAMBDA SETA CAMP 4 h (1/s) (NEY/ DIS) (MET / DIS) 1 Tritium 4.49E 03 1.79E-09 5.64E-03 0.0 2 C-14 2.09E 06 3.84E-12 4.95E-02 0.0 3 N-13 6.94E-03 1.16E-03 4.91E-01 1.02E 00 4 0-19 3.36E-04 2.39E-02 1.02E 00 1.0$E 00 5 F-18 7.62E-02 1.05E-04 2.50E-01 6 1.02E C0 NA-24 6.33E-01 1.27E-05 5.55E-01 4.12E 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 1.2WE 00 9 CR-51 2.78E 01 2.89E-07 3.86E-03 3.28E-02 10 MM-54 3.03E 02 2.65E-08 3. 60E-03 8. 36 E-01 11 HH-56 1.07E-01 7.50E-05 1 12 8.29E-01 1.69E 00 FE-59 4.50E 01 1.78E-07 1.18E-01 13 1.19E 00 i CO-58 7.13E 01 1.12E-07 3.41E-02 9.78E-01 14 00-60 1.92E 03 4.13E-09 9. 68 E-02 2.50E 00 15 ZN-69m 5.75E-01 1.39E-05 2.21E-2** 4.16E-01 e 16 ZN-69 3.96E-02 2.03E-04 3.19E-01 0.0 17 3R-84 2.21E-02 3.63E-04 1.28E 00 18 1.77E 00 3R-85 2. 08 E-03 3.86E-03 1.04E 00 6. 60 E-02 19 KR-85a 1.83E-01 4.38E-05 2.$3E-01 29 - 1.59E-01 KR-85 3.93E 03 2.04E-09 2.5 t E-01 2.21E-03 21 KR-87 5'.28E-02 1.52E-04 1.32E 00 22 7.93E-01 KR-88 1.17E-01 6.86E-05 3.61E-01 13 . 1.96E 00 KR-89 2.21E-03 3.63E-03 1.36E 00 24 1.83E C0 R8-88 1.2AE-02 6.47E-04 2.04E 00 25 6.26E-01 R3-89 1.07E-02 7.50E-04 1. ole 00 26 2.05E 00 1 SR-89 5.20E 01 1.54E-07 5.83E-01 8.45E-05 l 27 SR-90 1.03E 04 7.79E-10 1.96E-01 0.0 ! 28 SR-91 4.03E-01 1.99E-05 6. 50 E-01 6.95E-01 29 51-92 1.13E-01 7.10E-05 1.95E-01 1.34E 00 30 $1-93 5.56E-03 1.44E-03 9.20E-01 , 2.24E 00 31 T-90 2.67E 00 3. 00 E-06 9.36E-01 0.0 32 Y-9ta 3.47E-02 2.3tE-04 2.73E-02 5.50E-01 33 T-91 5.88E 01 1.36E-07 6.0;E-01 34 T-92 3.6tt-03 1.47E-01 5.46E-05 1.44E 00 2.50E-01 35 Y-9'; 4.29E-01 1.87E-05 1.17E 00 8.94E-02 36 2R-95 6.50E 01 1.23E-07 1.16E-01 7.35E-01 37 N3-95a 3.75E 00 2.14E-06 1.81E-01 38 6.06E-02 N3-95 3.50E 01 2.29E-07 4.45E-02 7. 64 E-01 39 MO-99 2.79E 00 2.87E-06 3.96E-01 1.50E-01 40 TC-99: 2.50E-01 3.21E-05 1.56E-02 1.26E-01 41 TC-99 7.74E 07 1.04E-13 8.46E-02 0.0 42 TC-104 1.25E-02 6.42E-04 1.60E 00 1.95E 00 1 l l l
. . 1 Rev 3 l VOLtME 28 BRP RADIOLOGICAL E?T*.'3T T/S RE;'.':7D DOCLHDiTS Pap 21 of 71 A. OFFSITE DCSE CALC';1ATIONS ;
TABLE 1.2(CON'T[ l B ASIC RADIOfUCLIDE DATA l l NUCLtDE RALF-LIFE 'AMBDA l BETA t CN (days) (T/O. (MEV/ DIS) (MEV/ DIS) 43 RU-106 3.67E 02 2.19E-08 1.01E-02 0.0 : 44 TE-132 3.24E 00 2.48E-06 1.00E-01 2.33E-01 ! 45 T-129 6.2tE 09 1.29E-15 5.43K-02 2.46E-02 46 I-131 8.05E 00 9.96E-07 1.90E-01 3.81E-01 47 I-132
- 9.58E-02 8.37E-05 4.89E-01 2.24E 00 48 I-133 8.75E-01 9.17E-06 4.08E-01 6.02E-01 49 I-134 3.61E-02 2.22E-04 6.16E-01 2.59E 00 50 I-135 2.79E-01 2.87E-05 3.68E-01 1.55E 00 51 EZ-131m 1.18E 01 6.80E-07 1.43E-01 2.01E-02 52 XE-133e 2.26E 00 3.55E-06 1.90E-01 4.15E-02 33 XE-133 5.27E 00 1.52E-06 1.35E-01 4.60E-02
$4 IE-135e 1.08E-02 7.43E-04 9.58E-02 4.32E-01 55 XE-135 3.83E-01 2.09E-05 3.17E-01 2.47E-01
. 36 XE-137 2.7tE-03 2.96E-03 1.77E 00 1.88E-01 Si XE-138 9.84E-03 8.15E-04 6.65E-01 1.10E 00 58 CS-134 7.48E 02 1.07E-08 1.63E-01 1.55E 00 59 CS-135 1.10E 09 7.29E-15 5.63E-02 0.0 ,
60 CS-136 1.30E 01 6.17E-07 1.37E-01 - 2.15E 00
' 61 CS-137 1.10E 04 7.29E-10 1.71E-01 5.97E-01 62' CS-138 2.24E-02 3.58E-04 1.20E 00 2.30E 00 63 BA-139 5.76E-02 1.39E-04 -
8.96E-01 3.53E-02 - 64 BA-140 1.28E 01 6.27E-07 3.15E-01 1.71E-01 65 LA-140 1.68E 00 4.77E-06 5.33E-01 2.31E 00 66 CE-144 2.84E 02 2.82E-00 9.13E-02 1.93E-02 ) 67 PR-143 1.36E 01 5.90E-07 3.14E-01 0.0 68 PR-144 1.20E-02 6.68E-04 1.21E 00 3.18E 02 l I Average energy per disintegration values vern obtained f rom ICRP Publication No 32, Radionuclide Transformations : Energy and Intensity of Emissions. . 1983 and NUREG/CR-1413 (ORNL/NUREC-70) A Radionuclide Decay _ Data Base - ' Indez and Summary Table. D. C. Kocher. Hay 1980. 1 l
'NTS Voll 25 BRP RADIOLOGICAL EFFLUENT T/S REQUIRED D0' A. OFFSITE DOSE CALCULATIONS Rev 3 USNRC COMPUTEK CODE - X00D00, VERSION 2.0 Rt* DATES 11-us-87 Page,26 of 71 .
< Ta51e 1.3 mamm SIS ROCK POINT XOGD0482 muu USING 01/01/A4 - 12/31/86 MET BATA Mumm ELEVATED RELEASE - 240' STACK No DECAY, UMDEPLETED
' ANNUAL AVERAGE CHI /O (SEC/ METER CUBED) DISTANCE IN MILES FRhM THE SITE 4.SSs 9.500 0.750 1.000 1.500 2.008 2.506 3.000 3.500 4.884 ! SECTOR e.258 i
5 1.235E-08 1.620E-98 1.944E-04 2.451E-08 3.089E-08 3.161E-08 3.081E-04 2.773E-08 2.541E-04 2.325E-84 2d32f.-88 55M 7.372E-09 1.282E-SS 1.521E-SE 1.865E-08 2.329E-08 2.388E-es 2.270E-05 2.099E-63 1.924E-88 1.760E-88 1.61IE-88 SW 1.818E-88 8.879E-89 9.25EE-09 1.251E-08 1.748E-08 1.857E-08 1.792E-08 1.669E-08 1.534E-84 1.489E-SS 1.293E-84 MSN 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 e.800E+00 9.884E+ee S.SetE*4G H 0.000E+00 0.000E+00 S.880E+00 0.000E+GO 0.000E+00 0.000E+00 8.000E+00 0.000E+00 0.000E*03 0.089E+ee s.eetE*se WNN 0.000E+00 3.482E-46 1.044E-29 7.814E-22 2.896E-15 1.725E-12 5.25tE-11 4.204E-10 1.663E-09 4.347E-89 8.757E-49 MW e.809E+00 0.030E+08 0.08eE+0e 0.000E+00 0.0C0E+00 0.000E+00 e.000E+00 0.000E+08 0.088E*C8 8.000E+sa S.899E+0e MMW 8.800E+00 0.000E+0S 0.00SE+00 0.000E+00 0. 0 0 G f'+ 0 0 0.0J0E*Se 0.890E+0S 3.000E*00 0.000E+es 8.030E+0S 9.486
- M
! Q 0.00eE+00 0.000E+90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C.S00E*38 0.000E+0e 0.Se8E+0e S.Setteet 0.See *DS l NME 1.039E-08 1.w76E-Da 2.718E-OS 3.734E-08 4.199E-05 4.70CE-05 4.377t-C2 3.*A5E-04 3.607E-es 3.249E-sA 2.972 -48 i NE 1.053E-04 2.252E-04 3.784 E-05 4.745E-08 5.155E-08 4.714E-08 4.139E-04 3.612E-08 3.165E-C8 2.794E-04 2.446E-88 l ENE 1.921E-88 3.200E-08 4.317E-08 5.141E-08 5.451E-05 4.950E-08 4.327E-04 3.743E-04 3.287E-08 2.893E-88 2.568E-88
- E 1.849E-08 4.800E-08 4.469E-04 5.174E-08 4.911E-08 4.252E-08 3.620E-04 3.094E-04 2.670E-08 2.329E-04 2.052E-43 i ESE 1.886E-08 3.530E-05 3.992E-08 4.103E-08 3.809E-08 3.279E-04 2.785E-08 2.378E-04 2.050E-08 1.787E-88 1.573E-04 SE 1.778E-88 2.447E-08 3.018E-C3 3.104E-83 3.011E-08 2.683E-04 2.335E-08 2.830E-88 1.774E-88 1.566E-es 1.392E-88 l SSE 1.896E-88 2.125E-05 2.454E-88 2.84eE-05 3.225E-08 3.119E-88 2.852E-08 2.563E-84 2.297E-88 2.044E-88 1.864E-88 ANNUAL CVERAGE CMI/4 (SEC/ METER CUSED) DISTANCE IN MILES FReM THE SITE 50.009 10.000 15.000 20.000 25.000 30.000 33.000 40.088 45.898
- SECTeR 5.008 7.5e8 i
- 5 1.961E-88 1.36*E-08 1.022E-05 6.414E-09 4.792E-39 3.709E-09 2.998E-89 2.50eE-09 2.133E-89 1.854E-89 1.634E-89 SSN 1.483E-88 1.030E-08 7.703E-09 4.976E-09 3.605E-09 2.790E-89 2.256E-09 1.882E-99 1.686E-09 1.396E-89 1.2SIE-09 ' SH 1.190E-08 8.266E-09 6.179E-09 3.978E-09 2.870E-09 2.215E-89 1.785E-09 1.445E-09 1.265E-89 1.e972-e9 9.654E-18 WSN 8.estE+88 0.880E+80 8.50SE+88 c.000E+00 0.000E+0D 0.000E+88 0.000E*St 8.08tE+98 0.00SE+0S 8.848E*00 e. Sect +Se M S.SSSE+0e 8.000E+S8 8.000E+00 0.000E+00 0.000E+00 0.000E+08 S.000E+49 8.000E+00 W.000E+00 8.Sett+00 e. sect +es
- MNH 1.482E-es 5.693E-08 9.235E-08 1.195E-07 1.171E-07 1.063E-07 9.435E-SS 8.337E-04 7.346E-88 6.577E-es 5.as9E-e4 NW 0.000E+80 0.000E+00 0.000E+00 0.009E+00 0.000E*00 0.000E+08 S.000E*06 0.800E*00 0.00eE+86 0.040E+89 8.se#E+5e
- NNH e.000E+00 8.000E+00 0.000E+00 0.000F.+00 0.000E+00 0.000E+0e 0.000E+48 0.860E+00 0.00CE+0e 0.000E*08 8.80s
- O e.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+08 8.000E+08 0.000E+04 0.000E400 0.888E+00 0.00 j NME 2.716E-84 1.846E-48 1.889E-88 1.346E-056.115E-09 a.709E-094.252E-09 6.255E-093.194E-99 4.815E-09 3.578E-89 2,526E-89 3.225E-09 2.969E-89 2.744E-09 1.739E-39 2.382E-89 1.491E-39 2.097E-49 1.5eeE-99 NE 2.229E-88 1.421E-OS
- . ENE 2.294E-e4 1.453E-es 1.026E-88 6.167E-09 4.271E-09 3.200E-09 2.523E-a9 2.062E-99 1.730E-09 1.432E-89 1.290E-e9 4 E 1.326E-05 1.133E-Sa 7.91eE-09 4.704E-09 3.249E-09 2.431E-09 1.914E-99 1.564E-89 1.3'1E-49 1.123E-89 9.775E-10 ESE 1.399E-04 S.668E-09 6.045E-89 3.588E-89 2.478E-09 1.353E-89 1.459E-89 1.192E-09 9.993%-18 S.541E-le 7.452E*Re i SE 1.249E-08 7.973E-09 5.669E-09 3.446E-09 2.411E-09 1.820E-09 1.444E-89 1.186E-09 1.0C0E-89 8.59&E-18 7.511E-te J SSE 1.692E-88 1.125E-88 8.186E-09 5.109E-09 3.621E-09 2.759E-tf 2.283E-09 1.819E-09 1.548E-09 1.328L-09 1.163E-e jVENT AND SUILDING PARAMETERS REP. WIND HEIGHT (METERS) 71.3 RELEASE MEIGHT (METERS) 73.10 (METERS) 31.4 CIAMETER (METERS) 1.14 . . SUILDINI) NEIGNT EXIT VELOCITY (MET ERS) 18.21 SLDO. MIN.CRS.5EC. AREA (54. METERS) 2848.8 6.8 NEAT EMISSION RATE (CAL /SEC) l lALL ELEVATED RELEASES.
l l - - _ _ _ - _ - _ _ _ . - _ _ _ - _ _ - _ _ - _ . - - - - _ _ _ _ - _ _ - _ _ _ _ _ - _ _ . _ -
l ,RP RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS VOLUME 25 *
. A. OFFSITE DOSE CALCULATIONS - Rav 3 Page 27 of 71 ,.
NBC COMPUTE ~CSDE - XO9000, VERSION 2.0 RUN DATES 11-v4-87 I Tisbie 1.1 (cmi' t ) 1 !em BI3 ROCK PeINT XeepetS2 mum USING 81/01/84 - 12/31/86 MET DATA umMN , )EV3TEDRELEASE-248' STACK ga RECAY, UNGEFLETES ! 1 7 81/4 (SEC/ METER CUSED) FOR EACH SEONENT SEONENT BOUNDARIES IN MILES FROM THE SITE 40-Se 1-2 2-3 3-4 4-5 5-18 10-20 20-38 30-4e
- IMECTIoM .5-1
- tSM SITE 1.545E-88 6.606E-89 *3.713E-99 2.583E-99 1.SSSE-09 1 5 2.898E-e8 2.979E-es 2.955E-88 2.525E-88 2.126E-88 1.SS4E-89 1.397E-09 1.621E-88 2.252E-88 2.233E-e4 1.911E-88 1.60SE-es 1.015E-es 4.973E-89 2.794f-89
) SSN 2.217E-09 1.098E-09 SM 1.e42E-88 1.484E-es 1.76eE-es 1.526E-98 1.289E-08 S.145E-99 3.975E-09 1.487E-09 l 8.000E+0e e.800E+ee 0.000E+00 0.000E+0e e.000E+00 0.eetE+0e 8.steE+0e e.seeE*ee MSN e.eeGE+00 0.SetE+et 0.000E+es 8.000E+0e e.eeeE+ee 3.000E+08 3.SesE+83 8.800E+80 e.setE+08 0.SetE+0e 0.000E+C0 e.sesE*00 M 1.862E-10 2.331E-09 9.696E-09 6.331E-84 1.124E-07 1.e44E-87 S.2SSE-SS 4.562E-08 MMM 3.473E-22 7.678E-13 8.08eE+0e 0.000E+et e.steE+SS NM e.808E+0S 8.8882+8C e.Se8E+es e.80eE+3e 0.000E+00 8.seeE+00 e.setE+es S.SetE+0e 0.000E+00 0.000E+00 0.eetE+80 0.000E+se e.eetE*08 0.000E+88 i NMM e.088E+es 0.000E+00 0.000E+ee 0. ecee +es 0.Se8E+08 e.SetE+0e e.teeE+0e 8.000E+00 0.000E+08 0.000E+0e e.SetE+0e e.teeE+0e 8.teSE+et O 3.586E-08 2.965E-08 1.426E-se 8.718E-39 4.824E-09 3.229E-89 2.384E-09 NME 2.934E-04 4.4SSE-88 4.386E-88 6.178E-89 3.209E-09 2.874E-09 1.494E-09 3.SaeE-04 4.472E-84 4.881E-04 3.151E-84 2.482E-08 1.418E-88 ' CE 2.544E-88 1.451E-88 6.234E-99 3.215E-89 2. 067 E-89 1.48SE-09 ENE 4.435E-04 3.159E-e4 4.26SE-04 3.273E-88 2.442E-09 1.56SE-09 1.12SE-09 4.477E-88 3.578E-88 2.462E-es 2.050E-es 1.135E-08 4.770E-09 E 4.812E-04 2.444E-e4 1.572E-04 S.6SSE-09 3.641E-09 1.862E-89 1.195E-99 S.574E-te
- j. RSE 3.939E-04 3.639E-54 2.754E-SS 7.952E-e9 3.4 Set-09 1.s27E-89 1.189E-09 S.4118-10 3.e22E-SS 2.304E-84 1.74SE-es 1.390E-08 1.330E-99 SE 2.SS4E-04 2.285E-SS. 1.869E-es 1.115E-04 5.132E-89 2.746E-09 1.822E-09
[. SSE 2.552E-SS 3.392E-SS 2.SSSE-88
#Fe w EFFECT1WE STACK MEIGNT IN METERS FOR EACH SEGMENT 5-18 10-2e 2e-3e 3e-4e 4e-se beeCTIoM .5-1 1-2 2-3 3-4 4-5 NME SITE S.400E+01 8.4eeE+01 S.409E+el 8.48eE+01 S.44SE+01 S.488E>11 5 8.400E+01 S.400E+01 8.488E+01 3.400E+01 S.539E+41 S.539E+01 S.539E+el S.539E*81 8.539E+01 S.539E+et 8.5395+41 S.539E+01 S.539E+01 S.479E+et SSN S.539E*01 8.679E+01 8.679E+01 8.679E+01 S.679E+el S.679E+01 SM S.678E+el 8.679E+01 S.679E+01 8.679E+01 e.SeeE+ee P.000E+Se 0.000E+ee e.eGGE+0S e.SeeE+0e e.SeeE+88 0.00SE+ee 8.000E+ee 0.000E+00 0.00eE+et e.000E+es MSN e.eesE+es 0.000E+0e e.eeeE+0e 0.eetE+0e 0.000E+0e e.setE+es M 8.eteE+es e.seeE+se e.seec+4e 3.853E+02 3.853E+02 3.453E+S2 3.453E+02 3.855E+82 MMM 3.817E+02 3.433E+82 3.453E+eZ 3.453E+02 3.853E+42 8.00SE+es 0.00eE+80 0.e00E*e8 8.setE+eS 8.eesE+0e 0.000E+es 0.000E+0e S.SetE+00 MM 8.setE+88 e.setE+0e 8.000E+88 0.800E+0e 0.000E+0e 0.0SSE+00 0.eGGE+ee e.seeE+0e NNM e.SSSE+88 0.000E+es 8.000E+0e e.setE+0e e.eetE&de e.066E+0e 9.000E+0e S.SSSE+et 8.setE+0e 0.000E+00 8.000E+88 0.SetE+00 e.Sett+et S.28SE+S1 Q e.000E+ee S.2SSE+41 S.2SSE+41 8.285E+91 S.285E+01 S.28SE*01 NME S.2SSE*01 S.285E+01 S.285E*01 S.285E+01 S.376E+01 S.376E+01 S.376E+01 S.374E+el 8.376E+01 S.374E+01 S.376E+01 S.376E+01 S.376E+01 S.49eE+S1 NE 3.374E+et S.498E+01 S.498E*e1 S.498E+41 S.498E+et S.498E+01 EME 4.497E*01 S.498E*01 S.494E+01 S.494E+81 S.600E+01 S.49eE+01 S.48eE+01 S.dett+et f
S.60eE+el S.6stE+el S.60eE+el S.600E+01 S.665E*e1 S.64SE+01 E S.599E+el S.4etE+el S.665E+el S.445E+01 S.66SE*01 4.64SE+el S.645E+61 ESE S.444E+el S.665E+01 S.665E+01 S.73SE+01 S.735E+01 S.73SE+01 4.73SE+01 S.735E+01 S.735E+C1 S.735E*01 S.735E+el S.735E+01 S.735E+01 S.434E*01 S.436E+01 SE S.436E+81 S.436E+01 S.436E*01 S.436E+01 SSE S.435E+el S.436E*01 8.436 E+ 01 S.436E+s1
VOLUME 25 BRP RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENT * ,. A. OFFSITE DOSE CALCULATIC"S USNRC COMPUTER C3DE - X0QDOS, VERSION 2.0 RUN DATES 11-u4-87 "" 3 Page 28 of 71 maak SIO ROCK POINT X04DUQ42 MMM USING 01/01/84 - 12/31/86 MET DATA muum Table 1.3 (Con't) ELEVATED RELEASE - 240' STACK 2.248 DAY DECAY, UNDEPLETED ANNUAL AVERAGE CHI /O (SEC/ METER CURED) DISTANCE IN MILES FROM THE SITE SECTOR 8.258 0.500 8.750 1.000 1.500 2.000 2.580 3.000 3.500 4.888 4.588 5 1.234E-08 1.615E-08 1.941E-88 2.445E-08 3.030E-08 3.150E-04 2.989E 98 2.76eE-04 2.527E-se 2.311E-es 2.117E-SS CSM 7.345E-89 1.274E-e8 1.516E-84 1.asoE-Da 2.321E-04 2.37st-es 2.259E-es 2.884E-04 1.911E-es 1.7472-es 1.400(-88 SW 1.017E-88 5.546E-89 9.226E-09 1.247E-04 1.742E-08 1.450E-04 1.783E-88 1.66SE-88 1.525E-88 1.398E-88 1.282E-04 MSN 0.000E+00 0.000E+00 0.000E+SS 0.000E+A0 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E*00 0.000E+0S 9.800E+es N 0.000E+00 0.000E+00 0.000E+00 0.000fv00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0e 8.000E+es e.800E+0e NNN 0.000E+00 3.435E-46 1.024E-29 7.594E-22 2.774E-13 1.630E-12 4.894E-11 3.861E-10 1.505E-89 3.878E-09 7.701E-89 NM 8.000E+00 0.000E+80 8.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 S.800E+08 8.setE+es 8.SetE+Se MNM S.000E*00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+08 0.000E+00 8.800E+0e 8.000E+SS C 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+08 0.000E+08 S.SetE+0t S.Se8E+es NME 1.035E-04 1.673E-05 2.714E-04 3.729E-08 4.691E-08 4.690E-05 4.345E-04 3.971E-05 3.593E-SS 3.254E-se 2.95SE-es ME ENE 1.053E-05 2.247E-08 3.780E-05 4.757E-08 5.144E-05 4.701E-JS 4.125E-08 3.598E-04 3.15eE-08 2.779E-05 2.471E-SS E 1.920E-Os 3.192E-05 4.308E-08 5.130E-08 5.437E-08 4.935E-04 4.311E-04 3.745E-04 3.269E-04 2.876E-04 2.551E-SS E3E 1.859E-04 3.991E-08 4.858E-08 5.164E-08 4.897E-03 4.237E-04 3.604E-04 3.078E-04 2.455E-08 2.313E-es 2.937E-84 1.485E-04 3.522E-OS 1.983E-05 4.093E-08 3.797E-05 3.266E-08 2.772E-04 2.364E-05 2.037E-es 1.773E-es 1.56et-es SE 1.76sE-SS 2.859E-08 3.009E-05 3.095E-08 3.001E-08 2.671E-08 2.323E-85 2.elsE-Os 1.763E-84 1.553E-SS 1.34eE-es SSE 1.e95E-es 2.119E-es 2.447E-88 2.435E-04 3.216E-08 3.104E-84 2.840E-84 2.551E-es 2.285E-84 2.052E-SS 1.451E-es ANNUAL AVERAGE CHI /O (SEC/ METER CUBED) DISTANCE IN MILES FROM THE SITE SECTOR 5.800 7.500 10.000 15.000 20.000 25.000 38.800 35.000 48.000 45.000 54.848 5 1.947E-08 1.349E-08 1.008E-08 4.477E-09 4.662E-09 3.584E-09 2.879E-09 2.385E-89 2.823E-89 1.744E-e9 1.53eE-99 55H 1.470E-04 1.817E-84 7.579E-09 4.350E-09 3.495E-09 2.685E-09 2.155E-09 1.785E-09 1.515E-89 1.386E-09 1.145E-99 SW 1.179E-SS 8.151E-09 4.065E-09 3.871E-09 2.767E-09 2.116E-09 1.691E-89 1.395E-89 1.178E-et 1.015E-99 8.841E-10 MSN S.980E+00 0.000E+00 0.MOE+00 0.000E+00 0.000E+00 0.000E+00 0.00SE+00 0.CSOE+00 0.000E+0S 8.speE+ee 3.sest+se M 0.SOSE 84 4.080E+00 8.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+89 8.000E+00 9.800E+98 8.000E+0e 0.888E+S8 MMN 1.285E-98 . 595E-04 4.940E-80 7.75f E-05 6.614E-08 5.204E-04 4.085E-88 3.068E-88 2.357E-98 1.819E-es 1.412E-es NW e.800E+0. 0.000E+00 0.000E+00 0.000E+00 0.000E*00 0.000E+00 e. Oste *SS e.08SE+00 0.000E+et 0.000E+es e.SeeE+se NNM 0.000E+38 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.030E+SS 8.000E+00 0.000E+00 0.000E+80 8.eteE+0e S.eest+es O G.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E*00 9.800E+4e 0.000E+00 0.000E*00 e.sett+0e e.steE+es NNE 2.781E-08 1.831E-08 1.351E-04 S.567E-09 6.121E-09 4.486E-09 3.754E-99 3.106E-09 2.431E-09 2.27eE-09 1.98aE-09 NE 2.215E-SS 1.487E-05 9.961E-09 5.993E-09 4.341E-09 3.891E-09 2.427E-09 1.974E-09 1.643E-09 1.404E-49 1.216E-09 ENE 2.281E-04 1.437E-04 1.0m1E-05 6.030E-09 4.144E-09 3.081E-89 2.411E-09 1.955E-09 1.629E-89 1.385E-09 1.197E-49 E 1.811E-es 1.118E-08 7.776E-09 4.583E-Ot 5.137E-09 2.326E-99 1.816E-SC 1.478E-09 1.222E-09 1.03SE-99 8.952E-Je ESE 1.346E-04 8.545E-09 5.931E-09 3.486E-09 2.344E-09 1.765E-89 1.377E-09 1.114E-89 9.259E-10 7.855E-18 6.775E-le SE 1.237E-08 7.859E-09 9.560E-09 3.347E-09 2.319E-09 1.734E-99 1.343E-09 1.199E-09 9.264E-10 7.393E-18 6.835E-18 SSE 1.680E-88 1.112E-04 S.668E-09 5.000E-09 3.519E-09 2.662E-09 2.111E-09 1.731E-09 1.456E-89 1.247E-09 1.946E-99 CENT AND SUILDING PARAMETER 5s RELEA5e HEIGHT (METERS) 73.10 REP. WIND HEIGHT (METER $) 71.3 BIAMETER (METERS) 1.14 BUILDING HEIGHT (METER $) 31.4 EXIT VELOCITY (METERS) 15.21 BLDO. MIN.CRS.5EC. AREA (St. METERS) 2988.8 HEAT EMISSION RATE (CAL /SEC) 8.8 4LL ELEVATED RELEASES.
t VOLUME 25 CKP KAD10 LOGICAL EFFLUENT T/S REQU1KED DOCUMlWr5 ~ A. OFFSITE DOSE CALCULATIONS . Rev 3 *
$NRC COMPUTEK~ CODE - X00D00, VERSION 2.0 RUN DATES 11-u4-87 Page 29 of 71 mum 513 ROCK POINT XO4D0482 mien USING 01/01/84 - 12/31/86 MET DATA MMMM LEVATED RELEASE - 240' STACK 7 *AR DAY DECAY, UNDEPLETED NI/4 (SEC/ METER CUSEDI FOR EACM SE0 MENT SEOMENT BOUNDARIES IN MILES FROM THE SITE 5-10 10-20 28-38 30-43 40-58 1-2 2-3 3-4 4-5
'IRECTION .5-1 ROM SITE 1.330E-04 6.470E-89 3.590E-09 2.3SSE-09 1.748E-89 2.893E-es 2.970E-OS 2.94eE-OS 2.512E-08 2.112E-08 2.489E-09 1.787E-99 1.307E-59 5 1.899E-08 1.596E-08 1.003E-05 4.857E-09 55W 1.416E-88 2.244E-OS 2.222E-05 a.032E-89 3.848 E-09 2.119E-89 1.397E-89 1.014E-89 1.680E-04 1.751E-es .1.515E-08 1.27aE-04 0.88SE+08 a.seeE+88 SW 1.05s E-es 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.800E+0e MSN 0.000E+80 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+0e 0.088E+49 8.000E+ee 8.000E*00 0.000E+00 0.000E+00 0.000E+00 5.100E-es 3.945E 1.82SE-es W 0.00 0 E+ 0 0 1.712E-10 2.0892-09 8.475E-09 4.902E-08 7.078E-Os 0.SesE*Se
- MNW 3.375E-22 7.252E-13 0.000E+00 0.000E+es 0.000E+00 S.setE+0e 0.884E+00 8.000E+0S 0.000E+00 0.000E+00 0.000E+00 S.eGeE+et 8.seeC+es 8.csst+es NW 0.000E+0? 0.000E+00 0.000E+00 0.000E+0e 0.000E+es e.seeC+ee NNW 8.CeeE+38 0.000E+00 0.000E+00 0.088E+00 0.000E+es 8.seeE+08 e.seeE+ee 8.000E,00 0.000E+00 8.030E+00 0.000E*00 s.578E-09 4.494E-09 3.118E-89 2,272E-89 D
4.476E-08 4.294E-08 3.572E-05 2.950E-08 1.311E-et 1.9792-09 1_.487f-89 NME 2.934E-88 3.137E-08 2.468E-08 1.404E-08 6.052E-09 3.105E-09 NE 3.874E-C8 4.861E-05 4.048E-88 1.435E-08 6.097E-09 3.094E-09 1.941E-89 1.347E-89 5.146E-08 4.251E-05 3.256E-05 2.547E-08 2.335E-09 1.474E-89 1.840E-99 ENE 4.425E-ts 2.644E-08 2.035E-08 1.121E-Da 4.650E-09 E 4.801E-88 4.663E-04 3.563E-04 1.559E-08 8.564E-09 3.340E-09 1.775E-09 1.118E-99 7.271E-le 3.938E-es 3.627E-04 2.74 e E-08 2.030E 'OE 3.382E-09 1.742E-09 1.112E-89 7.946E-le ESE 2.294E-08 1.756E-08 1. 378 E-08 7.839E-09 1.735E-09 1.249E-99 SE 3.81(E-es 2.875E-04 1.847E-08 1.le3E-04 5.824E-99 2.67 8E-89 SSE 2.546E-88 3.043E-08 2.796E-05 2.272E-08 i e t
- VOLUME 25 BRP RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS ,.
A. OFFSITE DOSE CALCULATIONS USNRC COMPUTER CODE - XOOD04. VERSION 2.0 RUN DATES 11-u4-87 Rev 3 Page 30 of 71 usan SIS RSCE FOINT XO4D0042 muu USING 01/81/44 - 12/31/84 MET DATA NMmW Table 1.3 (Con't) tELEWOTED RELEASE - 24C' STACK j 5.098 BAY DECAY, DEFLETED 1 jANNUAL CVERAGE CMI/G (SEC/ METER CURES) DISTANCE IN MILES FROM THE SITE 4.000 4.54G 8.584 0.750 1.000 1.50S 2.000 2.50s 3.000 3.500 SECTet e.25e l 5 1.235E-SS 1.605E-88 1.915E-sa 2.415E-08 3.044E-08 3.110E-08 2.948E-05 2.720E-es 2.449E-SS 2.274E-68 2.842E-SS SSN 7.37eE-49 1.278E-SS 1.494E-05 1.333E-88 2.290E-08 2.345E-08 E.226E-05 2.055E-48 1.841E-88 1.718E-SS 1.572E-SS i SN 1.818E-04 4.794E-89 9.121E-09 1.236E-08 1.727E-08 1.830E-08 1.762E-08 1.637E-08 1.503E-08 1.376E-88 1.261E-SS j NSW S.000E+98 0.980E+0S 0.809E+00 0.000E+00 0.000E*00 0.000E+00 0.000E+88 8.000E+0e 0.000E+0e 8.SSSE+ec S.sesE*Se W 0.880E+00 e.800E*08 S.000E*00 0.000E+0D 0.000E+00 0.000f*00 0.000E+00 3.000E+00 9.SeeE+00 8.090E+88 0.000E*80 { NNM 0.SSSE+00 3.46SE-44 1.040E-29 7.75.i-22 2.834E-15 1.665E-12 5.000E-11 3.947E-10 1.540E-09 3.974E-09 7.986E-09 MM 0.80SE+08 0.800E+0S 8.80SE+00 S.000E+00 0.000E+00 0.000E+00 0.000E+00 8.000E+00 0.000E+S8 0.setE+0e S. ecee +Se NNM s.sesE+se s.s00E+s0 s.steE+0e 0.000E+00 0.000E+00 0.000E+00 8.000E+98 0.000E*00 8.00SE+et 8.909E*00 0.sett+ee i N S.000E*00 0.000E+00 4.080E+00 0.000E+00 0.000E+00 0.000E+00 0.908E+00 0.0095,00 0.800E+se S.SetE+fe S.SeeE+86 i NNE 1.039E-88 1.663E-84 2.690E-04 3.700E-08 4.643E-08 4.631E-08 4.381E-08 3.907E-08 3.529E-SS 3.192E-SS 2.898E-64 l NE 1.053E-08 2.23*E-04 3.746E-04 4.711E-04 5.067E-08 4.607E-08 4.024E-08 3.494E-08 3.048E-08 2.6SSE-es 2.376E-84
- ENE 1.921E-08 3.173E-04 4.261E-04 5.376E-08 5.355E-08 4.837E-08 4.206E-08 3.639E-08 3.164E-04 2.774E-08 2.452E-84 E 1.360E-08 3.965E-08 4.787E-04 5.040E-04 4.796E-08 4.130E-04 3.497E-98 2.974E-08 2.555E-04 2.218E-es 1.946E-68 I ESE 1.384E-es 3.49sE-05 3.928E-08 4.018E-08 3.709E-08 3.175E-08 2.683E-88 2.278E-08 1.954E-08 1.495E-08 1.486E-84
- SE 1.769E-88 2.848E-88 2.961E-08 3.e40E-08 2.939E-08 2.60SE-08 2.261E-88 1.954E-84 1.786E-08 1.499E-es 1.329E-es ! $5E 1.096E-84 2.185E-84 2.412E-64 2.793E-88 3.169E-05 3.06eE-0C 2.792E-04 2.584E-84 2.239E-es 2.SSSE-84 1.818E-es I DISTANCE IN MILES FROM TME SITE 30.088 lANNUAL AVERAGE CMI/4 (SEC/ METER CUSED) 18.900 15.000 20.000 25.000 38.000 35.099 40.888 45.968 SECTea 5.004 7.589 l 5 1.915E-88 1.325E-88 9.349E-09 4.340E-09 4.583E-09 3.530E-99 2.842E-09 2.36SE-09 2.se$E-39 1.735E-09 1.299E-e9 1.522E-89 1.139E-09 l SSN 1.444E-SS 9.972E-09 7.430E-89 4.748E-09 3.433E-09 2.643E-89 2.127E-09 1.764E-89 1.SeeE-89 1.175E-09 1.015E-09 8.849E-te l SN 1.154E-08 7.997E-09 5.944E-89 3.800E-09 2.723E-89 2.08dE-89 1.675E-09 1.384E-99 l h5N 0.999E+0S 3.000E+00 8.00SE+s0 0.000E+00 0.000E+00 0.000E*04 0.090E*00 0.000E+0S 8.SSSE+00 e.000E+e9 0.SeeL ! N S.800E+Se N.SSSE*00 0.80SE+08 0.040E+08 0.000E+00 0.SeGE+99 S.SetE*Se 8.000E+00 0.000E+98 S.seeE*ee s.See J NNW 1.322E-08 4.811E-88 7.435E-08 8.825E-08 7.995E-08 6.747E-SS 5.SSSE-84 4.621E-88.3.33SE-es 3.232E-es 2.712E-88 ! NN S.800E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.088E+88 S.SSSE*SS 0.000E+et e.000E*S0 8.eest+se 0. ece t l NNW 8.00SE+Se 8.000E+00 8.000E+00 0.000E+00 0.000E+00 0.000E+et 8.000E+0e 0.setE+88 0.990E+00 0.000E+es e.88
- O S.SSSE+08 8.800E+00 0.800E+00 0.000E+00 0.000E+00 0.000E+et 8.998E+00 0.000E+08 8.SetE*00 0.eesE+es e.seeE+
i NNE 2.444E-SS 1.747E-04 1.317E-04 S.343E-09 5.943E-09 4.574E-89 3.667E-99 3.039E-99 2.579E-09 2.231E-89 1.957E-99 j NE 2.124E-08 1.336E-SS 9.391E-09 5.599E-09 3.845E-09 2.559E-09 2.239E-99 1.318E-09 1.516E-89 1.293E-89 1.118E-49 j ENE 2.187E-SS 1.362E-88 9.584E-09 5.613E-09 3.32aE-89 2.331E-89 2.207E-09 1.785E-09 1.453E-89 1.24eE-e9 1.SS6E-99 . E 1.725E-88 1.053E-SS 7.254E-09 4.22SE-89 2.362E-09 2.185E-09 1.633E-09 1.316E-89 1.Ss9E-e9 9.215E-te 7.96SE-te ESE 1.314E-84 S.013E-09 5.566E-09 3.191E-89 2.157E-89 1.583E-89 1.226E-39 9.857E-18 S.142E-10 6.SS2E-IS 5.897E-10 f SE 1.14aE-08 7.488E-89 5.269E-09 3.144E-09 2.167E-09 1.613E-09 1.244E-09 1.025E-99 8.54sE-18 7.276E-It 4.2 Set-18 I 55E 1.641E-84 1.883E-08 7.836E-09 4.345E-89 3.406E-09 2.576E-89 2.844E-89 1.677E-89 1.418E-89 1.21eE-09 1.8S 1
- WENT AND BUILDING FARAMETER5s REP. WIND HEIGHT (METEts) 71.3 RELEASE MEIGNT (METERS) 73.10 (METER 5) 31.4 l
- BIAMETER (METER 5) 1.14 BUILDING HEIGHT EXIT VELOCITY (METERS) 18.21 BLDO. MIN.CAS.5EC. AREA (54.NETERS) 2008.8 8.4
! HEAT EMISSION RATE (CAL /5EC) IALL ELEVATED RELEA5ES. 1 i
VOLLME 25 BRP RADIOLOGICA. EFFLUENT T/S REQUIRED DOCUMEhTF . A. OFFM TE DOSE CALCULATIONS
' ~
kSNaC COMPUTEk CODE - XOGDOS, VERSION 2.8 RUN DATES 11-v4-87 Rev 3 Page 31 of 71 sumu DD ::",CK POINT XO4DO482 NER USING S1/41/84 - 12/31/86 MET DATA numa Table 1.3 (Con't) ELEVATED RE*_ EASE - 240' 5 TACK 8.CCe DAY DECAY, DEPLETED 381/4 (SEC/rETER CURED) FOR EACH SE0 MENT SEGMENT BOUNSARIE5 2N r1ILES FROM TME SITE 38-44 40-54 1-2 2-3 3-4 4-5 5-18 10-20 28-58 AIRECTIC1 .5-1 rem SITE C.077E-08 1.304E-05 4.354E-89 3.5"4E-89 2.343E-84 1.734E-89 5 2.06SE-86 2.954E-05 2.9SSE ^,4 2.473E-08 4.766E-EJ 2.647E-09 1.768E-89 1.299E-89 2.213E-08 2.149E-08 1.569E-04 i . 56 8 f. -0 5 9.335E-09 CSM 1.595E-88 1.493E-08 1.257E-08 7.844E-89 5.799E-09 2.892E-89 1.300E-09 1.eldt-89 SW 1.049E-e4 1,664E-GE 1.730E-08 0.000E+00 0.SetE+se e.800E+48 e.864E+S8 0.000E+00 0.000E+00 0.500E*50 0.000E+00 0.000E*00 0.006E+se c. esse +se M5M 0.000E+00 0.000E+00 0.0e1E+se e.osoE+0e 3.seeE+es e.seeE+es W e.000E+00 0.000E+00 e.OOSE+00 3.709E-09 5.202E-08 E.147E-04 6.416E-SS 4.59dE-88 3.219E-te NNW 3.445E-22 7.408E-13 1.750E-IP 2.140E-09 S.setE+Se 0.888E*e8 8.80GE+06 0.000E+00 0.000E+0S e,000E*00 0.000E+00 0.000E+es 4. 000 E+ 00 S.SesE*Se led 8.380 E+00 0.000E+00 0.ce8E+00 0.08eE+0e e.8 eE+0e S.SesE+0e NNW S.000E+00 0.000E+00 0.000E+04' O.000E+0C 8.et0E+0S 4.80SE+S8 a.868E+88 0.000E*00 0.000 E+00 0.000E+00 0.000E+08 0.se0E+04 C e.000E+00 e.000E+00 2.491E-08 1.76sE-es 3.357E-09 4.530E-89 3.f43E-89 2.235C-89 NME 2.913E-85 4.42eE-04 4.251E-0 3.509E-et 5.462E-09 2.474E-09 1.525E-09 1.294E-09 4.784E-C3 3.947E-64 3.035E-Sc 2.373E-O'e 1.335E-08 1.242E-89 NE 3.839E-08 3.151E-03 2 ' ME-ca 1.363E-08 5.485E-89 2.a(7E-89 1.791E-89 ENE 4.351E-08 5.443E-05 4.147E-08 2-04 1.e57E-SE 4.292E-09 2.1182-of 1.320E-89 9.224E-le f 4.735E-85 4.543E-05 3.457E-04 2.546E-Os 3 '.e 3.246E-89 1.593E-29 9.69eE-13 4. stet-Ke 2.452E-es 1.94aE-es 1.. 3E-88 a.e42E-49 1.621E-89 1.829E-89 7.234E-12 i E3E 3.6702-88 3.541E-es 1.499E-83 1.527E-05 7.473E-89 3.182E-a9 1.211E-89 SE 2.949E-ed 2.514E-OS 2.232E-es 1.886E-08 1.574E-68 4.87 e E"w9 2.544E-69 1.6SSE-89
~
SSE 2.515E-64 3.837E-es 2.768E-sa 2.227E-es l - i . . J l 1 2
l .- l VOLUME 25 ARP RADIOIACICAL EFF1.UENT T/S REQUIRED DOCUMENT. I A. OFFSITI? IMISl? CAI.CIII.ATIONS l
.- [
):5NIC COMPUTEK CODE - XO4904, VERSION 2.0 RUN BATE: 11-m4-87 Rev 3
*
- Page 32 of 71
'ema B1:1 RSCE PGINT XOGDOGS2'umm USINe 01/01/84 - 12/31/86 MET DATA mann Table 1.3 (Con't)
'LEVATED RELEASE - 248' STACK maammmmmmmmmmmmmmmme t cacccccommmmmmmmmmma RELATIVE BEP051TieN PER UNIT ASEA (Mem-2) AT FIXES POINTS SY Celee41NS SECieR$ i i s1CECT1 elf DISTANCES IN MILES jRen SkTE 0.25 0.50 0.75 1.88 1.50 2.08 2.50 3.00 3.58 4.88 4.50 5 5.389E-le 4.400E-18 3.447 E-18 3.152E-le 2.SSM-le 1.543E-19 1.1SSE-18 9.495E-11 7.593E-11 6.229E-11 S.178E-11 S5H 4.452E-le 3.514E-10 2.777E-18 2.312E-le 1.477E-18 1.877E-19 8.225E-11 6.481E-11 5.220E-11 4.274E-11 3.556E-71 ,
SM 2.493E-19 7.e42E-10 1.754E-10 1.582E-10 1.eS2E-10 8.154E-11 6.346E-11 5.e51E-11 4.991E-11 3.361E-11 2.79M-11 MSN 0.000E+06 0.000E+00 S.SeeE+00 W.setE*e8 0.000E+00 8.000E+CS 8.000E+00 0.00SE+00 0. ESSE +et 0.SSSE+00 0.000E+0e i N 0.e00E+00 0.SetE+S8 0.Se8E+00 C.000E+00 0.000E+G0 0.000E*00 0.098E+00 0.000E+08 0.000E*00 12E-898.eGGE+00 0.000E+0e 1.16M-89 9.49SE-10 MNW 2.154E-10 1.292E-095.000E+00 2.752E-090.eesE+00 3.681E-09 3.191E-09 2.617E-09 2.123E-09 1.726E-99 i S. 1.4.e5E+ee 8.setE+08 e.eeGE+e : NW S.SetE+00 0.000E+et 0.000E+00 0.000E+00 8.4SSE*00 8.000E+et l INIH 0.0COE+S8 0.000E+00 8.SeeE+88 9.000E+08 0.000E+00 0.000E*00 0.000E+98 G.048E+48 0.00SE*00 e.eteE+89 0.000E+0W l- ! N e.SeeE*00 0.000E*00 0.000E+00 0.4898.+00 8.fCC+0S 0.Se3E+SS 8.088E+0S 0.SetE+0e 0.000E+es S.eGGE+Se 0.GGSE*88 l 1 IN0E 4.547E-le 7.827E-18 6.85M-10 6. 691E-t e 4.62*E-le 3.461E-10 2.672E-18 2.115E-10 1.786E-10 1.397E-le 1.140E-le l j IIE 9.494E-12 1.114E-09 I 195E-09 1.134E-99 7.345E-10 5.445E-10 4.178E-18 3.294E-18 2.651E-18 2.16SE-te 1.798E-19 t ; t FNE 1.153E-99 1.1135-09 1.e32E-09 9.516E-10 6.64SE-le 4.976E-le 3.842E-18 3.042E-10 2.455E-le 2.812E-18 1.671E-Es l E 1.5SsE-89 1.34eE-09 1.195E-09 9.371E-10 4.100E-18 4.437E-le 3.379E-18 2.656E-18 2.236E-10 1.74SE-18 1.452E-IC ESE 1.394E-99 1.204E-89 9."r79E-10 8.043E-10 5.994E-le 3.63eE-10 2.72SE-18 2.12SE-te 1.791E-10 1.391E-te 1.154E-te 1 3E 1.011E-99 S.r5SE-10 6.261E-le 5.087E-10 3.176E-10 2.279E-18 I.724E-10 1.351E-10 1.045E-te S.874E-11 7.375E-11 i } SSE 4.SSIE-18 5.535E-18 4.498E-10 3.83M-18 2.584E-18 1.843E-10 1.415E-18 1.118E-le 9.020E-11 7.396E-11 6.149E-11 f i91 RECT 10W S15TA80CES IN MILES PRen 317E 5.ea 7.5e Is.80 15.se 2s.ee 25.00 so.es 35.ee 4e.ee 45. 3.. - 5 4.355E-11 2.SSE-11 1.455E-11 7.671E-12 4.874E-12 3.562E-12 2.799E-12 2.319E-12 1.990E-12 1.7421-12 1.569E-12 5 94 2.992E-11 1.575E-11 1.se3E-11 5.318E-12 3.381E-12 2.48eE-12 1.946E-12 1.604E-12 1.364E-12 1.1SSE-12 1.06eE-12 l SN 2.358E-11 1.236E-11 7.86eE-12 4.139E-12 2.616E-12 1.876E-12 1.434E-12 1.144E-12 9.456E-13 7.981E-13 4 193C-13 ' NSW e.)SSE+et 9.SSSO 90 S.9stE+0e 0.000E+98 0.000E+0S 9.80eE*e0 8.000E+ee e.teeE+99 0.00SE+ee e.808E+Se S.SeeE*06 e."SeeE+ee e.getE+GO 0.te8E+ee S.SeeE*0s 3.000E+0e e.00CE+08 e.SetE*Se e.SeeE+ee S.setE+ee e.seeE+ee S.SeeE+04 l W i 888M 4.13eE-t e 4.246E-te 2.6SSE-le 1.386E-10 S.6 05E-11 5.920E-11 4.34SE-11 3.342E-11 2.457E-11 2.14SE-11 1.485E-11 . e.eeeE+Se S.SesE+et e.SeeE+0e e.eeeE+ee e.900E+00 0.000E+80 0.000E+89 e.SetE+ee e.seeE+es e.seeE+se e.seeE+ee 1 8md , ! Imed 0.te4E+es e.setE+et 8.setE+ee e.899E+es 0.000E+es 0.000E+e9 0.000E+ee S.SeeE+88 S.SSSE+0e e.SeeE+ee 0.eettete ! I Cl 8.000E+0e 9.eseE+00 e.N aE+ee S.SeeE+80 0.000E+0S 8.setE+09 0.08eE+0e S.seeE+es e.000E+0e e.Sett+ee e.eeeE+es INef 9.735E-11 3.049E-11 3.;;.4E-11 1.63 M-11 1.820E-11 7.172E-12 5.386E-12 4.239E-12 3.451E-12 2.880E-12 2.459E-12 IIE 1.5s+E-10 1.798E-11 4.67eE-11 2.494E-11 1.554E-11 1.SSSE-11 S.062E-12 4.259E-12 5.817E-12 4.121E-12 3.453E-12 ' E80E 1.483E-19 7.345E-11 4.599E-11 2.386E-11 1.494E-11 1.e55E-11 7.919E-12 6.211E-12 5.029E-12 4.169E-12 3.529E-12 E 1.221E-le 6.386E-11 4.941E-11 2.118E-11 1.3'i4E-11 9.591E-12 7.289E-12 5.749E-12 4.702E-12 3.913E-12 3.329E-12 I ESE 9.784E-11 5.e59E-11 3.191E-11 1.644E-11 1.SS2E-11 7.578E-12 5.775E-12 4.5SSE-12 3.740E-12 3.121E-12 2.656E-12 ! i SE 6.2872-11 3.262E-11 2.874E-11 1.997E-11 6.963E-12 5.063E-12 3.891E-!2 3.112E-12 2.562E 12 2.153E-12 1.846E-12 ' SSE 5.172E-11 2.719E 8,1 1.73 E-11 9.131E-12 5.798E-12 4.22M-11 3.293E-12 2.69M-12 2.281E-12 1.972E-12 1.749E-12 i , i
VOLUME 25 BRP RADIOLOGICAL EFFIEENT T/S REQUIRED DOCUMENTS
%. OFFSITE DOSE CALCULATIONS SMRC COMPUT CODE - XO4909, VE~.5 ION 2.8 RUN DATE: 11-e4-87
.~
Rev 3 meu 313 p.3CK POINT X04D0042 mum USING 81/01/a4 - 12/31/84 MET DATA mumm Page 33 of 71 LEVOTED RELEASE - 240' STACK Table 1.3 (Con't)
-n...nmmmmmmmmmmmmm RELATIVE DEPOSITION PER UNIT AREA (Mum-2) SY DONNNIND SECTOR 5 mammmmmmmmmmmmmmmmmmmmma SEOMENT BOUNDARIES IN MILES 40-Se 1CECTI(;.1 .5-1 1-2 2-3 3-4 4-5 5-10 18-20 20-30 38-40 ROM SITE 2.377E-11 .C 't.-12 3.407 E-12 2.331E-12 1.751E-12 5 3.593E-10 2.081E-10 1.184E-10 7.591E-11 5.184E-11 1.193E-12 1.485E-10 8.205E-11 5.221E-11 3.541E-11 1.634E-11 5,1E-12 2.507E-12 1.611E-12 SSN 2.734E-18 1.284E-11 4.a88E-12 1.396E-12 1.152E-17 s.015E-13 SW 1.742E-10 1.075E-10 6.310E-11 4.087E-11 2.798E-11 0.000E+00 0.000E+00 0 000E+C0 0.000E+00 0.003E+00 0.000E+00 0.000E+0E 0.980E+04 H5N 8.000E+00 0.000E+00 e,000E+80 0.000E+s8 0.SteE+0e A.SeeE+0e N 0.000E+00 0.000E+00 0.000E+GO 0.000E+00 0.000E+00 0.CetE+00 2.896E-89 1.404E-09 9.695E-10 4.413E-le 1.44eE-10 6.447E-11 3.340E-11 2.178E-11
' NNN 2.841E-09 3.045E-89 0.000E+00 0.SSOE+00 0.000E+Se S.setE*Se S.SSSE+0e NH 9.SeeE+0e 8.000E+00 0.000E+0e 3.seSE+se e.800E+0e 9.SGSE+44 e.000E+0S 9.000E*00 S 000E+00 0.000E+0e S.setE*00 0.000E+0e 0.80eE+98 Need e.Se0E+es 0.000E+0e e.setE+0e S.setE+0e 8.000E+Se 8.000E*GS 3.000E+90 0 0.000E*e0 e.SetE+se 8.000E+0e 0.000E*80 4 e.se0E+et 4.525E-te 2.659E-te 1.705E-le 1.161E-10 5.253E-11 1.781E-11 7.265E-12 4.267E-12 2.893E-12 ' .aNE 6.741E-te 1.801E-10 8.117E-11 2.686E-11 1.099E-11 4.381E-12 4.139E-12 I NE 1.076E-09 7.I67E-le 4.162E-le 2.451E-le 2.454E-10 2.673E-10 7.597E-11 2.441E-11 1.067E-11 4.249E-12 4.186E-12 ENE 1.014E-09 e.546E-le 3.525E=le 6.634E-11 2.198E-11 9,676E-12 5.797E-12 3.952E-12 E 1.083E-09 6.seSE-10 3.372E-le 2.137E-10 1.454E-le 7.e42E-12 4.481E-12 3.132E-12 1.795E-le 1.156E-10 5.261E-11 1.735E-11 ESE 9.519E-le 5.099E-10 2.725E-le 7.ss7E-11 3.389E-11 1.134E-11 5.181E-12 3.125E-12 2.168E-12 SE 6.137E-10 3.20ZE-10 1.'723E-10 1.004E-10 2.788E-12 1.941E-12 2.596E-10 1.411E-10 9.019E-11 6.157E-11 2.824E-11 9.464E-12 4.272E-12
.55E 4.434E-10 ENT AND SUlfDINO PARAMETER 58 REF. HIND HEIOe<T (METERS) 71.3 RELEASE HE10HT (ME1ERS) 73.18 31.4 (METERS) 1.14 BUILDING HEIGHT (METER $)
- DIAMETER (59. METER 5) 2000.e EXIT VEs.0 CITY (METERS) 18.21 BLDG. MIN.CRS.5EC. arf 3 HEAT FMISSION RATE (CAL /5EC) s.e
; .LL ELEVATED REs. EASES.
1 i { l l l4 1 4 l I i
V01.UME 25 BRP RADIOLNICAL EFFLUENT T/S REQUIRED DOCUME}rr$ A. OFFSITE MSE CALCULATIONS Rev 3 Pase 34 of 71 i SIC 003 Polik I.AND USE CEWSUS REPott l l TABLE 1.4 Oletance to the nearest residence, garden, milk cow, beef Jew and goet in each sector. SECTOR RESIDENCE CARDEW pyRY COW BEEF CA m t COAT WSW 2.5 mi >5 mi >$ mi > 5 al >5 mi l SW 1.1 mi >5 mi >S mi 25 al 25 mi SSW 1.3 mi 2.1 mi 25 mi > 5 mi >5 mi j 5 1.9 mi >5 mi 55 il 2.5 mi >5 m! SSE 1.7 al 1.8 al 3.5 al 3. 5 ml. 3.75 mi SE 1.7 mi >! ml 4.5 mi 2.0 mi >5 mi ESE 1.5 mi 1.4 mi 2.6 mi 2.6 mi 55 mi E .\.4 mi 2.5 mi 2.5 ml 2.5 ni >5 mi ENE 2.3 mi >5 mi >5 mi > 5 mi >5 mi l l l i 1 IC1287-0256A-HP01
O VOLLME 25 BRP RADI0thCICAL EFFLUENT T/S REQUIRED DOCUME!Gf . A. OFFSITE DOSE CALCULATIONS Rev 3 Page 35 of 71 , Table 1.4a Critical Receptore O 1988 BIC ROCE POINT CASPAR INPUT PARANETERS Distance X/Q I/Q Decay I/Q Decay & Der D/Q Location Sector (ciles) (sec/m') (sec /s:') (sec/m") (1/s*) Residence /Carden E 1.4 S.00F-08 5.00E-08 4.90E-08 6.4CE-18 j site soundary C u.57 4.20E-08 4.20E-04 4.20E-04 1.30E-09 seef C.attle t 2.3 3.6eE-08 3.60E-ce 3. Set-ce 3.40s-le Dairy Cow E 2.5 3.64E-08 3.60E-08 3. Set-08 3.4es-le Coat $3E 3.25 2.40E-04 2.40E-04 2.4eE-88 1.eet-le
/
-I P
1
'(
IC1287-0267A-NP01 3 2 O e .
VOLU:E 25 BSP PX*,"0GICAL EFFLUENT T/S ?.I;UIfiED DOCLE.5 A.. OFF!N DOSE CALCULATIONS Rev 3 Page 36 of 71 TABLE 1.5 ' DOSE TACTORS FOR SUBMERSION IN N08LE CASES oft 1 DFYa DFSI DFla Kr-85e 1.17(+3)3 1.23(+3) 1.44(+3) 1.97(+3) Kr 85 1.61(+1) 1.72(+1) 1.34(+3) 1.95(+3) Kr 87 5.92(+3) 6.17(+3) 9.73(+3) 1.03(+4) Kr 88 1.47(+4) 1.5 2 (+4) 2.37(+3) 2.93(+3) Kr-89 '- 1.66(+4) 1.73(+4) 1.01(+4) 1.06(+4) Xe-131e 9.15(+1) 1.56(+2) 4.74(+2) 1.11(+)? Xe 133e 2.51(+2) 3.27(+2) 9.94(+2) 1.48(+3% Xe-133 2.94(+2) 3.53(+2) 3.06(+2) 1.05(+3) Xe-135m 3.12(+3) 3.36(+3) 7.11(+2) 7.39(+3) ' Xe-135 1.81(+3) 1.92(+3) 1.86(+3) 2.46(+3) . Xe-137 1.42(+3) 1.51(+3) 1.22(+4) 1.27(+4) . Xe-138 8 . 8'3 ( +3 ) 9.21(+3) 4.13(+3)
, 4.75(+3)
Ar-41 8.84(+3) 9.30(+3) 2.69(+3) 3.28(+3)
- 1. eres/y per pC1/e'
- 2. erad/y per pCi/e3
, 3. 1.17(+3)
- 1.17:103 i i
- Dose factors for exposure to a semi-infinite cloud of noble gases.
Values were obtained froe US NRC Regulatory Guide 1-109. Revision 1 (October 1977). 1 i l 1
V0txME 25 BLP MDICLCG CAL EFFLUEr ' S GEQUIRED DOCUMEN"'S Rev 3 A. CFFSITE ".CSE CALCULAT !IS Pa$e 37 of 71 TAlt.E 1.6 STABLE ELEMENT TRANSFER DATA EI.EMENT F,- MILE F, - MI!JC Fg- MEAT I gy (COW) (00AT) Ven/ Soil N 1.0E-02 1.7K 01 1.2E-02 4.8E-00 C 1.2E-02 1.0L 01 3.1E-02 5.5E-00 Na 4.0E-02 4.0E-02 3.0E-02 5.2E-02 P 2.5E-02 2.5E-01 4.6E-02 1.1E 00 Cr 2.2E-03 2.21 03 2.4E-03 2.5E-04 Mn 2.5E-04 2.5E-04 8.0E-04 2.9E-02 Fe 1.2E-03 1.3E-04 4.ut 07 6.6E 04 Co 1.0E-03 1.0E-03 1.3F-02 9.4E-03 Ni 6.7E-03 6.7E-03 5.3E-02 1.9E-02 Cu 1.4E-02 1.3E 02 8.0E 03 1.2E 01 Za 3.9E-02 3.9E-02 3.0E-02 4.0E-01 Rb 3.0E-02 3.0E-02 3.1E-02 1.3E-01 Sr 8.0E-04 1.4E 02 6.0E-04 1.7E-02 Y 1.0E-05 1.0E-05 4.6E-03 2.6E-03 ; Zr 5.0E-06 5.0E-06 3.4E-02 1.7E-04 Nb 2.5E-03 2.5E 03 2.8E-01 9.4E 03 Mo 7.5E-03 7.5E-03 8.0E-03 1.1E-01 Tc 2 5E-07. 2.5E-02 4.0E-01 2.5E-01 - t
. Ru 1.0E-06 1.0E-06 4.0E 5.0E-02
..Rh 1.0E-02 -
1.0E-02 1.5E 03 , 1.3E+01 Ag 5.0E-02 5.0E-02 1.7E-02 1.3E-01 Te 1.0E-03 1.0E-03 7.7E-02 1.3E-00 I 6.0E-03 6.0E-02 2.9E-03 2.0E-02 Cs 1.2I-02 3.0E-01 4.0E-03 1.0E-02 Ba 4.0E-04 4.0E-04 3.2E-03 5.0E-03 La 5.0f-06 5.0E-06 2.0E-04 2.5E 03 i ce 1.0L-04 1.0E-04 1.1E-03 2.5E-03 9 Pc 5.0E-06 5.0E-06 4.7E-03 2.51-03 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 1 Np 5.0E-06 5.0E 06 2.0E 04 2.5E-03 i i I l i ; l I
Rev 3 vou.HE 25 3?? ?ADIOLccICAL EFF*.JJir T/S REQUIPED ?.'T.MI'CS Page 38 of 71 A. OFFSITE DOSE CALCU;.C:a*;S TABLE 1.* IWALATION D0f t FACTCel F08 fMFANT (>gtKM PER PCI DEALE2n Pane 1 of 3 "M IONI - LW T.900Y TWTtotD I!DWTY trNC _ _Ct.LLt M 3 NO DATA 4.62t*07 6.62t*0* 4.621-07 4.62t*07 6.62t*07 6.621*07 C 14 1.49t*05 3.79:*M 3.79t M 3.79t*M 1. 79t
- M 3. 79t
- M 3.79E*06 ftA 26 7.Mt 44 7.54! 4 4 7. 54 t
- 04 7.kt 04 7.kt*04 7. 54 t.04 7.54t*04
..........a............
P 32 1.65t43
'8.03t*05 5.53t*05 N0 33 NO DAIA NO DATA 1.15t*05 C% $1 No TATA No DAu 6.39t 08 6.112 06 9.6,t*09 9.17 t *M 2.55t47 P98 54 ho DATA 1.8u 05 3.56t 04 NO DCA 3. 54t44 ! .ME*M
............................................................................7.14t*%
NN $6 No DATA 1.10t*09 1.54t*10 NO DCA 7.848 10 8.95t44 5.12145 F1 55 1.631 05 8.39t M 2.34t M NoDCA No DAIA 6.211 05 7.82t*07 F1 59 9.49t*04 1.68t*C5 6.77t*C4 NO DCA No DATA 7 1.77t*05
.............................................................................. 25t-Ca C0 St NO DATA 8.712 07 1. 30t *06 No 04:A CO 60 NO DATA 5.55t*% 7.951 04 NO DATA 5. 73t
- M 8.411*04 NO DCA NO DATA 3.221 03 2.24t*05 N1 62 1. 6 2 t *M 1.66t-05 8.29t*06 No 2:A NO CAIA 1. 7 3t *M
...........................................................................1.69t*%
N'1 65 1.711 09 2.03t*10 8.79t*11 NO CA:A No DATA CU M 5.00t*04 3.34t.05 No DATA 1.36t'09 5.53t*10 % MIA 2.84t*09 6.66E 46 1.07t*05 T.11 65 1.38t*05 4.67t*05 2.22t*05 10 *A:A 2'. 3 2t *0 5 4 ' 3.67C 05
............................................................................621*M EM 49
.....c.............
3.85t 11 6.911 11 5.13t*12 NoDCA 2.871 11 39 83 NO DATA 1 05t44 9.64t*04 No DATA 2.721*07 No M2a NO D11A NO DAIA LT E*26 AR 84 NO DAD NO DAIA 2.041 07 NODCA NO DATA
- N DATA LT t.26
..............................................................................O DR al NO DATA
, NO DAIA 1. 64 t*04 4 DCA 30 DATA LI E.26 NO DATA R3 04 NO CIA 1. 34t *h 4.30t*0$ NODCA NO DATA NO DATA 2.17E*04 R3 84 too DAIA 3.9ft*C7 2.05t*07 NO DCA MO DATA N DATA 2.621 07 RA 19
......................................................................O....................
NO DATA 2.29t*07 1.67t 47 MODCA NG CAIA 3R 89 2.845* % NO DATA C A*t*04 NO DAIA 8.15 t *M .9) DCA NO M TA SR to 1.65t*03 6.5"DOS 1.921 02 M Rt.IA 1.85t*03 NO *.4:A NO DATA 8.03t*03 9.36 M 5
..................s......................................................t. .......................
SR 91 3.83t M No LAIA 2.67t*09 NO OCA NO DATA 3R 92 7.50t*09
).76t*05 5.26t*05
%C DATA 2.79E*10 NO .'LIA P9 DATA 1.70t*05 1 90 1. 00 t * %
2.35t*06 NC CATA 6. 30t *04 NO .*4:4 No DATA 7.61i
.............................................................................1.92C+%..................'05 Y 91p 2.9*!*10 NO OATA 9.kt*12 NO .*4:A NO Dalt 1.992'04 1.681-06 Y 11 6. 20t * % NO DATA 1.12145 NO M:A ki DATA 1.75t.03 s.02t*05 Y 92 1.17t*04 NO DATA 3.29t*16 NO'CA NO DATA 1.71t*05 9.kt*0f
.......................................................e.................... .....................
- m - , - - - - - , .- , - - - . . _ , , ~ - - - -
Rev 3 vottHE 25 3?? ?.AD!CLCGICA*. E7FI.UE'iT T/S FE4UI'4ED DCTYEM pag, 39 og n A. OTFSITE OCSE JA*.CtLATIONS TAst! 1.7 (CcwT'D)
!*0LAft0N 00ft FACTORS FOR INFurf
, (MRIM PER PCI !WMA1.tD) Pane 1 of 3 WCt ?DE 80 0 t!VER T.600T If%TT THYROID t.!JMC CtLQ T 93 1.071 07 NO DATA 2.9U 49 MO DATA 90 SATA 5.648 0$ 1.19t *04 ZR 95
- 8.26t*05 1.99t 05 1.65t*05 MO DAZA 2.221*05 1.25t*03 1.55E 05 IR 97 1.07t*07 1.8 3t 43 8.34t49 MO DAIA 1.85t-08 7.84t*05 1.00t*%
NB 93 1.12r 05 6.59t 04 7.70t 04 M0 DATA 3.37t 48 3.62E M 9.05t 04
'10 99 NO DATA 1.18t*07 2.311*00 M0 DAIt. 1.498 07 9.63t*05 3.44t
- 05 TC 99e 9.94t*13 2.04t*12 2.66 tan M0 DAZA 2. 22t* u 5.79t*07 1.65t44 70111 4.65t*16 5.88t*14 5.808 13 M0 DATA 6.?9t*13 6.171 07 6.03t*07 A'103 1. 448 'M NO DATA 4.855 07 NO DATA J.0 M 06 3. 94t * % 1.15t*05 Rt'199 8.76t*10 30 CAIA 2.93t+10 1:0 DAIA 6-621 10 1.112 03 3.64t*05 RL'104 6.2CE*05 90 DATA 7.77t 44 NO AATA 7.611-05 8. 26 t-0 3 1.17 t*%
Acuou 7.13t*04 1.16t*se 3.57t*04 No CAT.1 7.80t*06 2.62t*03 2. ME*05 TI125e 3.60t*04 1.42t*04 4.7CE*07 1.16E 44 M0 DATA 3.19t M 9.221 04 Tt127a 1.19E 05 6.93t*C6 1.=8E 06 3.68E 04 2.68t*05 9. 37 t *% 1.95E 05 T1127 1.59t 09 6.81Z 10 3.69t 10 h 321 O'9 3. 6 7 E
- 09 7.39t M 1. 76t
- 0 5' -
Tt129e 1.01t*05 6.151 06 1.59t*04 3.91E*04 2.27t*05 1.20t*03 , 4.93145 - TI129 5.6 ". 11 2.68t 11 1.Mt*11 6. 8 2 t
- 11. 1. 25 E 40 2.16t*04 1.88t*05 TT131m 7'.62t 04 3.93t os 2. 5 9t *')4 6.38t 04 1.89t 07 1.621* % ' 8.511 05 75131 1.26t*11 5.87t*12 3.571 12 1.136 11 2.45t*u 1.67t 04 5.471 06
'*1132 2.66t*07 1.69t*07 1. 26t47 1.99t-07 7.39t 07 2.43t M 3.ut*C5
! 130 6. % E
- 06 9.911 06 3. 94t *06 1.148 03 *i 098 05 MO PAIA 1.42t*04
! 1J1 2.711 05 3.17t 05 1.60E*0$ 1.04E-02 ?.70t45 MO DATA 7.54t47 i
......................................................................... ....................... l 1 132 1.2U 44 2.5 M44 8.99t*07 1. 23 *M 2.8tt*C4 NO DATA 1.36t 04 1 133 9.641 M 1.371 0$ 6.00t*06 2.%t 03 1.60t*05 10 DATA 1.ME*04 2 1M 6.54t-07 ? 34t*M 6.75E47 3.18t*05 1. 69t-M NO BATA 9.211 07 I 13! 2.765 44 5.6M 04 1.98t M 6.97t M 6.05t*04 D CATA 1. P t *04 l CS136 2.838 * % 5.021* % 5.32t 0$ No DAIA 1. ME * % 3. 69F 4) 9.53t*07 I C$1H ;.6 5t*f 5 9. 61t *05 3.781-05 M0 DAIA 6.03t 05 8.40L.04 1.02t*C6 !
s
.................................................................................~................ l CS137 1. 9 2 t *% 6. 37 t*% 3.25t*C5 NC DAIA 1.23t % 5.09t 05 9.531 07 l l
C5138 3. 6 U 41 5.54F'07 2.64t*07 30 CAIA 2.938 07 6.67t*04 6.26t*07 l 84139 1. 04 t*0's Y. 0 3 t *12 3.07t 11 ho CAIA 6.231 13 6.25 t44 3.64t*05 I 1 l l J f _ _ _ _ _ _ . -__ ,- -_ , - ~ _ ,, . . - . ~ ,
Rev 3 VC *.'.E 2 5 SPP P.ADIC'.CG! CAL ITTLL'ENT T/S ir.'IBED DCCLENTS p,g,43 og 7g A. CFFS!TI DCSE CA*,CU MT!CNS TAsL! 1.7 (CCtti'D)
!!NLATICE DCST FACT %f FCR INTAlf!
@ PD PC: IM4ALd)
Pene 3 of 3 WCtfDt 90 4 Lt\TR T tGrf TWY10!D t!Dwff tiX C * *.1' BA160 6.00t*0$ 6.00t*00 2.071-06 180 DATA t.$9t*09 1.14t*03 2.*41*05 M161 1.12t=10' 7.70C+16 3.55t*12 180 DAla 4.ut 14 2.12t *M 3.29t M SA162 2.86t=11 2.36t*16 1.60f*12 180 ')ATA 1. 34t.16 1.11t*0$ 6.95t*07 LA160 3.41t*0' 1.63t*07 3.64t*00 NO DATA 180 DATA 1. 20E *M 6.D6t*05 LA162 7.36t*10 2.69t*10 6.66t+11 feo DAIA NO D1!A 3. 87t *M 6.13t*05 CI161 1.94t*05 ' 1.19t*0$ 1.621*06 N.) DATA 3.75t-04 3.698-M 1.kt*0$ C1163 2.09t*07 1. 34 t *07 1.545 04 No DATA 6.038 09 8.30t*01 3.$3t 9) Ct164 2.248 03 8.65t M 1. 261*M 180 DATA 3. Mt
- M 7.0)t*03 1.061* M PR163 1.00t*01 3. 7Q *M 6.99t*07 NO DATA 1.611 M 3.09t M 2.64t*05
...........................................................c......................................
PR164 3.62t*11 1.31t*11 1. 71t*12 NO DATA 6. 0M.12 1.15t M 3.NE*M PrD167 5.67t.06 S.811 06 5.57t*07 NO CAIA 2. 25t *M 2. 30!* M 2.23t*0$ V 147 9.26t*09 6.u t*09 2.;31-09 'O DATA le0 CAIA 2.818 05 2. Sat 05 a .................................................................................................. KF239 2.65t*07 2. 37E *06 1 %t*07 NO DATA 6.73t*04 6.25t*05 1.78t*05 l . .
& g
- t i
r i l l l 1 l l
Rev 3 vot.t.HI 25 BRP RA"CGICAL EFT'.t*Er T/S ?E'UIRED DCCLYL*"? p ,g , 4 g og 71 A. CFis !E DCSE CALCULCCNS TABLE 1.? (CON'T), imuf. ten
.- - xst rAeroRs ren :N:ta (MtIM PER Pct INHALID)
Pnv 1 of 3 Net!CE t0NE t.!VER T.tceY TWYRotD KfDNtY %'NC Ct.tLi i R 3 50 DATA 3.ME*07 3.ht 07 3. k E*07 3.NE*07 3. M E*C7 3. k E*07 , C 14 9.70t.04 1.421 04 1. 8 2t
- M 1.821 04 1. 8 2t + M 1.82t 04 1.42t*04 NA 26 4.35E M 4.35t*04 6.35t*04 6.35t*04 6.35t*06 6.31t*04 6.35t*04
......a...............................s...........................................................
P 32 f.%t*% 3.093 0$ 2.61t*C5 No DATA TO VAIA PC D.'.TA 1.16t*05 CR 51 2 DATA 'NO DAIA 6.17t*00 2.312*01 6.$7E*09 6.19t*04 2.91t*07 MN 54 NO DATA 1.16t*0$ 2.57 E44 NO DATA 2.713 04 6. 26 t *M 4.19C*04 MN $6 NO DAIA 6.L3t*10 8.43t*11 NO DATA 6.52t*10 3. Sit *04 3.331-01 Ft 35 1.281 05 6. 40t
- 04 2.10E*C4 NO DATA NO DATA 3.00E*05 7. 75t
- 07 ft 59 3.19t*C4 9. M E-04 6.51t-06 No MTA NO DATA 3.631 M 1.91t*05 M 38 NO DATA 6.792 07 8.3(E*07 NO DATA No DATA 2.99E*M 9.29E*04 CO 60 NOOATA 3.55t*06 6 12E*C4 NO DATA No DATA 1.911 03 2.60t*05 N1 63 2. 22 t *% 1.25t*0$ ).56t*C4 '50 DATA NO DATA 7.63t*05 1.71E *M MI A5 4.04t 10 7. 99 t *11 6.66t*11 NO DATA NO DATA 2.24*04 2.27E*05
.CU W No DA h S.39t*10
- 9CE*10
. NO DATA 1.63t*09 1.59E*04 9.9kI 04 ZN 45 1.13t*0$ 3.66E*05 1. 90t *0 5 NO CATA. 1.931 05 2. 6 9t *% 6.=12 04 ZN 69 1.811 11 2.612 11 ?.61t*12 NO DAIA 1.588 11 3. 86 t*97 2.75E+04 BR A3' ~ NO DAIA NC DAIA ~ 1. 28 t
- 07 NO DATA NO DATA 90 DAM L2 t*26 8R 84 2 DATA . NQ DATA 1.48 t *07 NO DATA NO DATA NO DATA LT t*26 IR 85 IE) AAIA No DATA 6.84E49 MQ DAIA NO DAIA MO DATA LT E*24 RB 84 50 DATA 5.34t*05 3.09t*0$ NO DATA NO DATA PO DATA 2.16t=04 RI $4 NO DAIA 1.521 07 9. 90t *00 NO DATA NO DATA NO PATA 6.64t*Q9 R3 89 50 DATA 9e331*C3 7.85t*04 NO DATA NO DATA *) DATA 5.11E*10
$?. 49 1.422 * % NO DAIA 4.66t*04 NO DAIA NO DATA S. 4 3t * % 6.521*05 SR 90 2.?38*02 H0'DAIA 1. 74t *0 3 NO DATA NO DATA 3.99E*03 9.2SE*05 l SR 91 3.288 06 NO DAIA 1.268-09 NO DATA NO D6TA 1.44t*0% 6 !CE*05 SR 92 3.542 09 No DAla 1.62E 10 NO DATA 6.69t*M NO DATA 6.55t*05 Y 90 3.11E*04 NO DA!A 2.99t*04 NO DATA NO DAIA 7.07t*05 7.1*E*05 Y 91a 1.37t*10 NO DAIA 6.94t*12 NO DATA NO DATA 7.60t*C7 6. HE*0)
Y v1 2. 6 7t * % NO DAIA 6. 59t
- M NO DATA NO DATA 7.10E *% 4.971 05 Y 92 5.50E*C9 No DAIA 1.57t*10 NO DATA 6.66t*04 NO DATA 6.66t*0$
s w . - - - -. .
VOLLME 25 N PM:0 LOGICAL u t..T;; ;/3 pr;UIDED DCCLHI*r-3 Rev A. CFI;;E DCSE CAL.*UTICNS Page o TAlt! 1.7_fCONT'D)
!?tALJTION DOSE FACTORS FOR CMith f>gtJX PER PCT INMALID) ge 2 o f 3 WCitDE 8092 LDt3 T. MDT TW710!D R2DNTY
- C% C2 tLt Y 93 $.kt*00 20 DA*A 1.34t*09 100 DA!A te0 DATA 2.0M45 1. 0 $ t *%
3 95 S.135 01 1.1X4G 1.00t 05 700 DATA' 1.63 05 6.0M % 1.65t 45 ZR 97 S.07E44 7. At-39 6.32t*09 NO DAIA 1.05t44 3.068 01 9.69t*0S NS 9$ 4.35t44 2.64t <4 1.77t*06 700 DATA 2.33t M 1. F. 3 *% 1.00C 0$ MD 99 ?e0 DATA 6. 662 <4 1.131 08 1.ME*07 3.Mt 45 100 DATA 3.611 05
!C 19e 4.81t*13 9.6U 13 1.56t*11 NO DATA 1.37t*11 2.57t47 1. 30C *M . TC101 2.19t 14 2.301 16 2.911 13 1e0 DATA 3.921*13 1.54t47 6.41149 RV103 7.55t*07 283 eda 2.90t*07 700 DAIA 1.90t*0m 1.79t*% 1.21145 RU105 6.13t*10 1E0 DA*A 1.50t 10 100 DAIA 3.63t 10 6. 30t*M 2.692 05 ILU1M 3.64t*03 No 2a:A 6.57t46 NO DATA 6.97t45 3.371 03 1.16 t *%
ACn0= 4. 56t
- M 3.04!<6 2. 47 t
- M No DATA 5.74t M 1.itt*03 2.711 03 ft125e 1.42t44 6.291-37 2.47t*07 5.20t*07 NO DATA 1.29t % 9.13t C4 71127s 6.72t*04 2. 3U-04 8.16E47 1. 461*H 1. 7 2E45 6. 00t * % 1.93t 05 Tri2? 7.695 10 2.5*t 10 1.65t*10 $. 30t *10 1.93 09 1.73*M 1.3*E*05 Tt12 W 5.19t 04 T. t!!<4 8.22t*07 1. 73
- M 1.36t*05 6.76t*% 6.93 41 TE129 2.64t*11 9.65!*12 6.66t*12 1.93t*11 6.%C 11 7.93t*07 4.49t M TI'131a. 3.631 04 1.60t<4 1.379 08 2.66t*04 1.06t*07 S.561 05 8.31t*05 T1131 S.87t.12 2.281 12 1.74t*11 4.$9t 12 1.39t.11 1.5M 47 3.60t 0?
T1132 1.30t*07 7.341-04 7.12t 08 8.541 08 6.79t*07 1. 02 *% 3.721 0$
! 130 2. nt *M 6.6X 04 2.248+M 4. 99t * % 6.611 M 1E0 DATA 1.38E46
! 131 1.30E 05 1. Jct 05 7. 3 7t *M 6.39t*03 2.13t*CS MD DAIA 7.66t*07 I 132 S.71t*07 1.lfA 06 S.07t*07 S.23t*CS 1. 6 9t *M MO DAIA 8.65t*07 1 133 6.64t*06 S.69t-06 2.088 06 1.ht43 9.13t
- M mo DATA 1.64t *M
! 134 3.17147 $.46t 07 2.69t*07 1.37t45 8.92t*07 NO DATA 2.54t*07 I 135
- 1. 3 M *M 2.34t-36 1.12t 44 2.16t *% 3. 6 2 t *M M OAIA 1.2Ct C6 CS1h 1.76t*% 2.76! 4 6 6.07t45 No DAIA 4.93t*05 3.271*05 1.%E C6 CS136 1.76t*0$ 4.63*:S 3.16E 45 NO DAIA 2.54t*0$ 3. 93t *M 1.131 C6 CS137 2.65t % 2.231 4 3.67E*05 NO DATA 7.63t*0$ 2.I'.2'05 9.78t*07 CS134 1.7H *07 2.271-07 1.50t*07 180 DAIA 1.64t*07 1.64t 04 7.29t C8 BA139 6.985 10 2.661 13 1. 4 5 t
- u No DATA 2.33E 13 1.54 E-M 1.56t*0
............................. ................................................................. 5 .
- .m_
RV 3 VOLL " '* **P FA0!OLCG CAL ETT'.L'ENT T/s RECD CCCLH INTS Page 43 of 71 A. CFFS:7E OCSE CALC'.'LATIONS TAALE 1.7 (CONT'D) INNA1. Aft 0W Dost FACTOR $ FOR CMit.D (MRDI Ptn Nt INNALED) Pem 3 of ) WC1!Dt 90NE t.!Vt1t T.8007 tYrtotD K10wtf LL'MC CT*ut 1A160 2.00t*05 1.75t*04 1.17t 04 M0 DATA $.73 09 4. 71E *% 2.75t-Cl SA161 S.29t*11 2.95t*14 1.72t*12 30 DAIA 2.56t 16 7.49t 07 7. 66t
- 30 1A162 1.35t*11 9.73t*15 7. 54t 13 MO DAIA 7.871*15 6.66t*07 7.63 10 1A160 1.74t*07 6.04t*08 2.04t*04 NO DATA M0 DATA 4.94t*05 6.101*CS
*A162
. 3.508 10 1.11E*10 3.69t 11 NO DATA Mo DATA 2. 35t *M 2.058 05 C2161 1. M t*05 ' $ 28t 04 7.338 07 MO DATA 2. *11*M 1. 6 7t *% 1. S M *05 Ct143 9.49t 04 5.37t*04 7.77t 09 MO DATA 2. 26t*M 3.11E*05 3.6&t*05 Ct166 1.83t 03 5. 7 2 t * % 9.77t 05 M0 DATA 3.17E # 3.23t*03 1. 05t*% i fit 143 6.99t 04 1.50t*04 2.67t*07 N0 DATA 8.1H+07 1.17t*% 2.43t*05 i PR164 1.612*11 6.99t*12 0.10t*13 MO DATA 2.64t*12 4.23t*07 5.32t M ND167 2.92t*04 2.36E 06 1. 84 t = 07 NO DATA 1. 30t
- M 8.87t*05 2.22t*05 b' 2 8 7 4.63 09 2.61t*09 1.171*09 M0 DATA M0 DATA 1.11E*05 2. 66t-0$
FP239 1.26t*07 9.% E*09 6.35t*09 NO DAIA 2.63t*04 1. S 71 0 $ , 1.73t C$ I y . I l i 1 l 4 1 4
,w a
VolLHE 25 3RP PADICLN :AL EFFLUTNT T/S REQU!?ID DCCWINTS 3 A. CFFSITE ?SF CALCULATIONS Page 44 of 71 tA3Lt 1.1 (CON *t) INMA!.ATTOM Dost FACTORS PCR ADl'LT1 (MRIM PER M2 iq,}, Pese 1 of 3
'KCttDE SMt L2VTR T.ScDY TNYR0!D K@ Ltl1ec C2 L17 C 3 NO DAD 1.58t*07 1.54t*07 1.58t*07 1.548 47 1.58t 07 1.541*07 C 14 2.271-M 6.26t*07 6.26t 07 4,26t*07 6.268 07 6.262 07 6.26t*07 1A 26 1.28t*06 1.28t*04 1.24t M 1.18t.M 1.28t*06 1.24t*04 1. 281*M
...............c,.................................................................................
F 32 1.65!*06 ,9.66t*04 6.26t*06 M0 DATA No MIA M0 DATA 1.04t*05 t CR 51 No CA:A 'No DATA 1.25t*04 7.bst*09 2.85t-09 1.80t M 6.15t*47
?st 54 NO DAIA 4.95t*06 7.8?t*07 No DATA 1. 23t M 1. 75 t *% 9. 67 t*M 1 ..................................................................................................
MM 56 M0 DA!A 1.55E 10 2.29t.11 M0 DA1 A 1.61 10 1.18t*04 2.3 38-M Ft $$ 3.07t*06 2.121 04 i. 93t.0) No DAIA 80 MIA 9.012-04 7.56t*07 F1 59 1.67 t *04 3.47E*06 1.32t*04 NO DATA No k!A 1. 27t *% 2.35t 05
...................................................,.................s.............................
CO 58 NO DAIA 1.94t*07 2.59t*07 No CAIA No MIA 1.16t *% 1.13t*05 CO 60 NO DAIA 1. 66 t
- M 1.85t*04 NO DAIA NO MIA 7. 6 6t* % 3.561*05 F2 63 5.60t*C5 3.93t 06 1.8 U 04 ho DAIA M0 M3 2.231-05 1. 4 7 t-M 51 65 1. 9 2t *12 2.62t=11 1.16t*11 M0 CATA No MTA 7.00t*07 1.56t*04
'C',' 64 Ho CAIA 1.83t*10 7.691 11 No DATA 5.7t! 10 8.68t*07 6.12t M
?.N 65 6.0$t C4 1.29E 05 5.42t*C6 No DATA 8.6:.!*04 1. 04t-M 6.64t*0G
~
Z.N 49 6. 23t *12 8.16t*12 5.65:*13 No DAIA 5.23 12 1.15 t > 07* 2.06t*09 . BR 83 NO DATA NO DATA 3.011.*04 NO DATA MO MIA MO DATA 2.93t*04 13 84 NO DAIA MO Dt.TA 3.93*04 MO DATA M0 MIA NO DATA 2.05t 13 SR 85 NO DATA M0 DATA 1.60t*09 M0 DAIA . MO MIA M0 DATA LT t 24 R3 d6 M0 DAu 1.69t*05 7.37t M NO DAu NO *mA M0 DAIA 2.08t*04 M 64 M0 DAIA 6. 86t *M 2.41t*04 MO DAIA M0 MIA M0 DATA 6.18t*19 4
.................................................. u ............... .............................
RA 89 80 DAI6 3.208 06 2.122*06 M3 MIA MO MIA MO DATA 1.16t*21 ; 5'R 89 ) SCE* 5 M0 DAIA 1. C?t*M NO DAIA NO MIA 1. 75t *% 4.371 05 l t'l 90
- 1. M-02 MO DATA 7. 61t *% NO DATA W3 !AIA 1.20t 03 9.02t *05 s
SR 91 7.76t*09 *to DATA 3.13t*10 N3 DATA MO 2AIA 4.56t*06 2.14t*05 ' 51 92 4.61t.U M DATA 3.66t=11 NO DATA NC 2A2A 2.04t *M 5. 341*M l T 90 2.611 07 MO DATA 7.011 09 NO DAIA No MIA 2.121-05 6.32t*05 l
.............. ...... ............................................................................ j Y 91, 3.26t 11 No DATA 1.27t*12 NO DAIA '60 MIA 2.60t*07 1. lit *10 ! Y 91 5. 78t *05 No DATA 1.55t*04 NO CAIA MO MIA 2.13t * % 6. 8 U +0S T 92 1.295 09 'to DATA 3.778 11 NO CAIA MO MM 1.961 04 9.191.M 1
I l l 1 1
o .
'.'OLUME 2$ 3RP PA.DIOLCG:0AL EFFLlTEr ! S PE;UIRED OCCUMENS Rev 3 I A. CFFSI"'E DCEE CALCU!AT 25 Page 45 of 71 IGLE 1.7 (CDNT'D)
INHA1ATTON 00$t FACTOR.9 FCE AZCLTS I'0K4 PER PCI INMALED) Pane 2 of 3 NUCt!DE SONE 11YTR T. SCOT TWYtotD E7DNET Lt*mC C!*LLt Y 93 . 1.18t44 NO DAIA 3.26t*10 No DATA NO DATA 6.Cet*M S.27t=0$ Ek 95 1.ht*0$ 6. 30t M 2. 918.M NO DATA 6.771 04 2. 211*M 1.88t*05 ZR 97 1.2M44 2.65t49 1.13t*09 NO DAIA 3.71249 9.86t M 6.34t*05 NB 95 1.76t C4 9.77t*07 S.24t 07 NO DATA 9.471-07 6.33*0$ 1.30t'*05 i M319 NO DAIA '1.31t*06 2.87t49 NO DAIA 3. 64t *06 1.16t41 3.10C+0S TC 19e 1.29t=13 3.6i.t*13 6.63t*12 NO DATA 5.511.!.2 9.55t44 S.20t*C7 TC101 S.22t*15 7.$1t*15 7.38t*16 NO DATA 1.35t*13 6.99t44 1.34Ee n RU103 1.9M *0F NO DAIA 8.238 04 NO DATA 7.29t*07 6.311 05 1.54t 05 RC10$ 9.89t*11 NO DATA 3.89t 11 NO TAIA 1.27ta10 1.371*06 6.0it*04 RU104 8.66t*M NO CA!A 1.09t*04 NO DATA 1.67t*05 1.17t*03 1.16t M ', A0110m 1.35t M 1.2$t C4 7.631 07 NO DATA 2. 64t
- M l . 7 9t *M 3.78t*05 TI125e 6.27t*07 1.98t*07 1.84t 04 1.311 07 1.35C M 3.92:*05 8.83t*04
, T1127e 1.58t C4 7.21t*07 1.96t*07 6. utf07 S.72t*04 1. 20t M 1.871 05 1127 1.75t*10 8.012 11 3.87t 11 ~1.32t 10 6.37t*10 8.16t*01 7.2 71 M -
. TI129e 1.22t M S.46t*07 1.9tt*07 6.30t*07 6. 3 71;* M 1. 6 5 t *% . 4.79E*CS Tritt .4.221 12 2.99t*12 1.55t*12 6.87t*12 2.%E 13 2.12147 1.96t*04 t Tt131m 8.76t M S.63t*09 3.45t*09 4.848 09 3.84t*00 1.81E*06 6.95t*C5 ft131 1.395 12 7.66t*13 4.69t*13 1.171 12 S.4t-12 1.768-07 2.30t*09 T1132 3..i'44 2.69t*04 2.025 06 2.37144 1.81147 2.6M49 6.37t 0$
! 130 $.721 02 1.64t*06 6.608 07 1. 6 22 *M 2.612 M NO MIA 9.6M*07 l t 131 3.13 t *M 6.P144 2.368 M 1.69( 4 3 7.64246 NO DA1A 7.45t*07 I 132 1.651 07 6.071-07 1. 6 5 t*07 1.6 31 0$ 6.64147 NO DAIA S .04 t*00
- 1 133 1.048 06 1.858-06 S.6M*of 2. 6 9t *M 3. 2 X *M NO DA1A 1.111.M I 136 8.0$t*04 2.16147 7.69E44 3.7 )t4f 3.66t*07 r? DATA 1.24t*10 t 135 3.35t*C7 C ,7 3t *07 3.212 07 5.60t%3 1.39t-04 NO DAIA 4.$6t*07
. CSIM 6.2At*0$ 1.Mt *M 9.10t *05 No DATA 3.39t*05 1.22t*0$ 1.30t*f6 I C5136 6.68t*C6 1.838 4 l 1.300 05 NO DATA 1.0 3 tMS 1.50t44 1. 66 t *M
............................................. ..............................................u..... i CS137 5.98t*05 7. 76t-05 1. 35t4) NO DATA 2.18E-05 9. M M 1.0 $ t *M , CS134 4.ut49 7.76t*00 6.055 04 NO DATA 6.00C 04 4.07t+0i 2.33t 13 l } SA139 1.17t*10 8.)JE*16 3.62t*12 NO DATA 7.78t.16 6.70t*07 1 122 07 l I
i
I Rev 3
'loLtStE 25
. 3.9 ?ADICLCCICAL ETF:.*.Tl! T/S PEqu! RED N!*.}ENTS Page 46 of 11 A. .'TTSI E DCSE CALCL".AT* *."S TAsu 1.7 (C3r;'0)
!*MA1A!!Ne 009t FACM PCR ADCLTS omt> Pts pet :euuz)
Pese 3 of 3 M.'C'. *38 40 4 L2VtX T. Sce? *n1010 KIDwtT ttlNC C7.t17 1A164 6.88t M 6.135 09 3.2M*07 No M:A 2.09t+09 1.595 E 2.73t 01 BA161 1.25t 11 9. 6 M
- 13 4.20t*13 MO MIA I.75t 13 2.428 07 1.65t*17 1A16' 3.29Ce12 3.38t.13 2.075 13 MO MIA 2.868+1$ 1.69t*07 1. 96t + 26 LA160 6. %t*04 2.17t 00 5.738 09 MC MIA No DATA 1.708 0S S.73t*05 1A162 8.54t*11 -
3.88t*11 9.65t*12 MC M:A M0 DATA 7.918 07 2. 66 t *07 4 Ct161 2.49t M 1.69t=04 1.91t*07 No DA!A 7.8M*07 4.52E.05 1.508 0$ Ct163 2.23t.08 1.72t*00 . J.09 NO MTA 7.60t 09 9.97t+06 2.IM 03 C1164 6.295 % 1.79t.04 2.30t*0$ MC MIA 1.NE % 9. 7 2t +% 1.021 M 1 PR163 1.17s*04 6.69t*07 $.80L*04 NC M1A 2.70t+07 3.33 05 2.50t 05 1 Pit 166 3.76t*12 1.$6t.12 1.9 4 =13 NO MIA 8.83+U 1.271 07 2.69ta18 NV167 6.39t*07 7.62t*07 6.56t*06 NO OAIA 4.65t-07 2.76t+0S 2.16t 05 V 187 1.06t.09 8.8st.10 3.1CE*10 NO MIA M0 DATA 3. 6 M a # 1.96t*05 NP239 2.87t*08 2.8 3 09 1.551 09 No MTA 8.75t*09 6.70t 0$ 1.49E 05
,=
1 i a 1
c Rev 3 VOLLME 25 3EP PADIOLC3* A!., EFFLUENT T/S BEAUI'ID DOCUTICS Page 47 af 7'. A. CFFSITE DNE CALCU!ATICNS TABLE 1.8 EXTELNAL DOSE FACTORS FOR STANDIN0 ON CONTAMINATED GROUND (ares /hr per pet /s )a TLEMENT TOTAL 800Y SKIN H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E 04 2.90E 04 P 32 0.0 0.0 Cr-51 2.20E 10 2.60E 10 Ma-54 5.30E 09 6.80E 09 Ma- 56
- 1.10E-08 1.3CE 04 Fe 55 0.0 0.0 Te-59 8.00E-09 9.40E 09 Co-58 7.00E-09 8.20E 09 Co-60 1.70E-04 2.00E-04 Ni-63 0.0 '
0.0 Ni-65 3.70E-09 4.30E 09 Cu-64 1.50E-09 1.70E 09 Zn-65 4.00E 09 4.60E 09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E 11 Br-84 1.20E-08 1.40E-04
~
Br-85 0.0 0.0 ' l . Rb-86 6.30E-10 7.20E-10 . Rb-88 3.50E-09 4.00E 09 I o Rb-89, 1.50E-08 1.73E-04 Sr-89 5.60E-13 6.50E-13 . Sr-91 7.10E-09 8.30E-09 . St-92 9.00E-09 1.00E-08 , Y-90 2.20E-12 2.60E-12 j Y-91e 3.80E-09 4.40E 09
- Y-91 2.40E-11 2.70E 11 J
Y 92 1.60E-09 1.90E-09 Y-93 5.70E 10 7.80E 10 f Zr 95 5.00E-09 5.80E 09 Zr-97 5.50E-09 6.40E 09 Nb-95 5.10E-09 6.00E-09 No-99 1.90E-09 2.20E 09 Tc-99e 9.60E 10 1.10E 09 Tc-101 2.70E-09 3. 00E-09 Ru-103 3.60E-09 4.20E 09 Ru-105 4.50E-09 5.10E 09 Ru-106 1.50E 09 1.80E 09 Ag-110e 1.80E-08 2.10E 08 Te-115e 3.50E-11 4.80E-11 Te-127e 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E 11
l VoLL"2 25 3RP RADICLCGICAL DTLUENT T/S RM* ' PED DOCUMEWS p,g,,4g,f7f A. CFFSI!E DCSE CAI.CULATICNS TARIA 1.4 (CON $ ELINENT TOTAL BODY SEIN Te-129s 7.70E-10 9.00E-10 ' Te-129 7.10E 10 8.401-10 Te-131e 4.40E-09 9.90E-09 Te-131 2.20E 09 2,COE 06 Te-132 1.70E-09 2.00E 09 I-130 1.408-04 1.70E-04
?.- 131 2.80E 09 3.40E 09 I 132 1.70E-04 2.005-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-04 1.90E-08 I-135 1.20E 08 1.408 04 Cs-134 1.202-08 1.40E-04 :
Cs-136 1.50E-08 1.70t-03 Cs-137 4.20E-09 4.908-M Cs-138 2.10E-04 2.400-08 24-139 2.40E-09 2.70E 09 84-140 2.10E-09 2.40E-09 B4-141 4.30E-09 4.90E-09 Da-142 7.90E-09 9.00E 09 : La-140 1.50E-08 1.70E-08 - La 142 1.50E-08 1.80*;-00 Ce-141 5.50E-10 6.20E - Ce-143 2.20E-09 2.50E 09 Ce-144 - 3.20E-10 3'.70E-10 Pr-143 0.0 0.0 Pe-144 2.00E-10 2.30E-10 N1-147 1.00E-09 1.20E-49 V'187 3.101-09 3.60E-09
.Vp-239 9.50E-10 1.10E-09
)
l l l 1 l
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. , ~ , , - - - - -
Rev 3 . Page 49 of 71 i Table 1.9 1944 81C bOCat POINT CA380US Det!CW 04JECTIVE AlefuhL QUANT!T!IS ; i Design Objective Dosa Facter Annual Quantity 1 mucilde ornan er en/ci__ ,_ (Cl) : Ar-41 Totsi tody 9.418-46 5.144+45 i Er>83a Stia 2.38548 4.348*48 , Kr-SS Skin 2.158-46 6. 94t+ M Kr-45m Totat Rody 1.30t46 3.45t+46 C r-47 Skin 2.304-05 6.52t+45 Er-84 Total Body 1.638-45 3.47t*45 4 Er-49 Total toJy 1.448-45 2.728*45 l 8.13t+45 -
! M-3 Total tody-C 6.15t44 Gene-C 5.315-43 2.798+43 C.-14 CI Tract-A.T 3.438-04 4. 37 t* 04 ,
. Cr-51 4. 23t+ 42 J Ma-54 C1 Tract-T 3.558-42 l Fe-55 Rone C 3.018-42 4.94ts et I Co-58 Total Rodr-C 7.37t-43 6.78t+42 Totat lody-C 1.171-42 4,27t*02 Fe-59
' Total Body-C 4.39t-42 1.14E+02 >
Co-60 ' Total body-C 6.67E42 7.50E+01 2n-65 Sr-89 Bone-C 1.33t+00 1.13t+01 S r-90 Bone-C 5.45t+01 2.75t-01 . 2r-95 C1 Tract-A 4.171-42 3.64t+02 [ Sb-124 Cl Tract-T 1.138-41 1.33t+02 I-131 Thyroid-! 3.02F40 4.97t+00 , Ie-131a Skio 9.47;:-47 1.54t+47
- Xe-133 Total Body 3.268-47 1.53t+47 l 7.54t+44 Xe-133m Skh 1.98844 Xe-135 Total Body 2.018-44 -
2.49t+46 j ze-135e 7otat ledy 3.46444 1. 45t+ M j
! Ie-137 Skin 2.128-45 7.94t+45 i Xea134 Total Body 9.40844 5.14t+4S I-133 Thyroid-! 2.808-42 5.34t+42
] 1.01: 4 4 1.49t+01
- Co-134 Liver-C Total lody-! 1.238-42 4.67t+02
< Co-136 1.52t+41 Cs-137 Gene-C 9.878-41 tone-C 6.69t43 2.24t+43 Ba-140 I Ce-141 C1 Tract-T 1.858-42 4.11t>02 Co-144 C1 Tract-T 4.918-41 3.05t+01 j CI Tract-c 3.548-04 4.19t+04 Mn 56 . Co-57 CI Tract-T 1.2 4 t-02 1.21t*03 C1 Tract-C 1.608-44 9. 388+ 04 i Wi-65
- Rb-88 Total nody-C 3.218-33 1.56t+33 C1 Tract-A 3.66t-02 4.10t+01 l Wb-95 Mo-99 Kidney-1 1.81843 8.29t+03 l 1.56t+04 Tc-99e C1 Tract-! . 9.61t-48 tu-103 CI Tract-A 5.44t-42 2.57t+02 i
1
, .. . .. . w ,s -.
- . . ,. m .
Rev 3 Page 50 of 71 I table 1.9 (Cont'd) t 1M4 510 tom Po!Irf CA880W DESIC11 C&JECTIVE AleNAL quAlfTITIES Deelgo 00jective l Dose Facter Annual %stity Wwellde ~Orman eres/Cl CCl) sh-125 CI tract-T 4.378-02 2.35t+02 1 Te-127 C1 Tract-A 4.358-04 2. 36 t + 04 1-132 Thyreid-C 5.18t-04 2.905+04 1-1 34 Thyrold-C 3.998-14 3.76E+14 1-13% Thyrold-C 6.73t-05 2.23t+05 La-140 C1 Tract-A 9.93t-04 1.51t+04 I
*W-13 Total tods 1.53t-51 3.27tv51
- *Wa-24 Total Body 1.108-04 4.55t+04 '
*Br-82 Total Body 1. 34 t-93 3.62E*03
*Sr-91 C1 Tract 1.28tr05 1.17t+06 i *S r-92 CI Tract 1.18E-07 1.27t+04 ,
, *T-101 Total Body 1.268-40 3.97t+44 I *Ag-110m C1 Tract 1.91t-01 7.45t+41
*Co-138 Total Body 4.321-22 1.16t+22 i *Ba-139 C1 Tract 2.345-11 6. 30 t+ 11
*N p-2 3 9 CI Tract 2.52t-04 5.95t+04 i
i
- WRC CAlt Code j
i 1 4 1 1 1
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, - . - - . , - . - - , - . , - . . - - - - - - . . . . . . . _.-.---,...S n- , , , _,,,.a- - - , ~ . - - - -
V '.'ST 25 3RP RA0!OLCGICA*. EFTL'sTU T. ! FI;UIPED DCC'atERS Pa 51 o A. CFTSITE DCSE CA1.CU!AT:CNS , , t ! QUID ETT1UT.NTS A. CONCINT1 TAT!0N
- 1. RETS Requirement Techni:s1 Specifiesti:n 131.2.1 of the Radie.ogical Effe;ent Technt:s1 Spe:ifiesti::: (PITS) requires the the concentrsti:n of radioactive materis! released at sny time from the site ::
unrestricted areas sis 11 be limited to tne .V.aximum Permissit*.e Concentration (MFC) s;ecified in 10 CTR 20, Ap;endix 3, Tatie II, Colura 2 for nuclidea other than dissolved or entrained netle gases. For dissolve! or entrsined r.oble gases, the concenirs-lon shall be limited to ;x10 ~4 pCi/mi total activity. To enstee :om-pliance, she following scproach vill be used for each relesse.
- 2. Prerelease Anaissis Most canks will be recirculated through two volume changes pr.or to saeplies fo,e release to the anvironment to ensure that.a represen-tative sample is obtained. The appropriate recirculation time for those tJOAS too large to provide two vcluse cleanges will be the tim t
. that the wapended particulate concentration reaches steady state. Either a one time test, or prior sampling data, may be used te deter-nine appropriate recirculation time. Prior to release, a grab sample will be analyzed for each release, , and the concentration of enth radionuclide determined, a C= Cg (2.1) ist x__________ _ _ _ _ _ __
4 . , , yc*,;;:!E 25 SPP ?.C:.,CGICAL ETTL'JENT T/s FEq*JIT<ID DCCL'E3 A, :T7!;-'E OCSE CALCU'JTIONS Rev 3 P.sge 52 of 71 where: C = Total concentration is the liquid effluent at the release point, pCi/nl. Cg
- Concentration of a single radionuclide i, pCi/ml. ,
- 3. Total MPC-Traction '
The Total MPC Iraction (R)) for each release point will be calculated by the relationship defined by Note 1 +f Appendix B,10 CTR 20: (j )* C i MC g (2.2) , i ( where: Cg
- Undiluted effluent concentration of radionuclide i, as determined in Section A.2, pC/al. !
MPC g a The MPC of radionuclide 1, as specified in Section A.1, pCi/e1. - R) = The Total MPC-fraction for the relea1e point. - The 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 met f g(Rg -1) + f2II2*I)
- I (R3 3 -1) $ T (2.3) j where:
f.f'3 g 2 = The ef fluent flow rate (gallons / minute) for the respec-tive releases, determined by plant personnel. R ,R 'A , g 2 3 a The Total MPC-Tractions for the respective releases as ! determined by Equation 2.2. T = Minimum required dilatien flow rate. Normally, a cot. serv 4tively high dilutica flow rate is used, that is, flow rate used = (bg )(T) where b is a conserva-g tive factor greater than 1.0.
jottyr 25 3RP ?%ICLCGICAL EFmi? T/3 PEqv:9ED XCLETS A. cry 3:TE XSE CA*.~.~ AT!0 iS Rev 3 Page 53 of 71
- 8. INSTRUtGNT SETPOINTS
- 1. Setpoint Detarutostien .
The setpoint for each liquid effluent monitor will be established using plant instructions. Concentration, flow rate, dilution, principal samma esitter, geometry and detector ef ficicacy are coe-bined to site an equivalent setpoint in counts per sinute (eps). The physical and technical description, location and identification number for each liquid effluent radiation detector is contained in Figure 2-2. The respective alars/ trip setpoints at each release point will be set such that the sus of the ratios at each point, as calculated by Equation 2.2. will not be exceeded. The value of R is directly i related to the total concentration calculated by Equation 2.,1. An, increase in the concentration would indicate an increase in the value . ] of R. A large increase would cause the. limits specified ia Section A.1 ~to b,e excteded. The minimum alara/ trip setpoint value is equal to the release concentration, but for ease of operation it ,say be l
. desired that the setpoint (S) be set above the ef fluent concentration (C) by the same factor (b) utilized in setting dilution flow. That .
L is: ' l 5=b C (2.4) l Liquid effluent flow paths and release points are indicated in Figure 2.1.
- 2. Post-Release Analysis A post-release analysis will be done ustag actual release data to unsure that the limits specified in Section A.1 vare not exceeded.'
i \ l l l l _ . - - - _ - .. ~ .._._ - ,
.-- . . - _._ __ -- _ _ -... - ._ - . - .~ - . . _ . - _ _ _ _ _ _ . _ _ . . -_ .. _ . ..
VOLUME . SHP RADIOIBGICAL EFFIDENT T/S REQUIRED EDCUM . I Rev 3 A. OFFSITE DOSE CAlfULATIONS l Page 54 of 71 .- I i D6eTY WA5TE CtE Aas WASTE FIG 4 HIE 2 2 SECEsW eTAmES 2(CEsW RTAGES CM(IB6 CAL
\ % WASTE SteveCE l Ties il34 Tl38 TIS RECE8VER c is4A TAast WATEA l
1 r !r 1r l AADWASTE
' 4 i
a608ssTOA 80s ALAAes WASTE geStB TAMES f , sessee AtAmes I; i cometesATE # 8( STORAGE esse T s6e 1 Asset H H 1964 I T-*8 " o at rr 8275 2452 o W f - FLOW CoseTROL
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- BIG ROCK POINT - LIQUID RELEASE FLOWS _
vcLt.yE 2 $ 3FP MDIOLN*:AL EFTLLTNT .'s FE;U:?I: OCCWE'CS A. CFFS!!E : !I CALCULATICNS Rev 3 Page 55 of 71 A composite list of concentrations (Cg ), by isotope, will be used with the actual liquid radwaste (f) and dilution (T) flew rates (or voluees) durias the release. The data vill be substituted into Equation 2.3 to demonstrate compliance with the limits in Section A.1. This data and setpoints will be recorded in auditable records by plant personnel. C. DOSE
- 1. RETS Requirement t
Technical Specification 131.h.1 the Radi: logical Effluent Techt.ical Specification (RETS) requires itst the quantity of radienuelides released te limited e ach that the dose or dose ce=-itment to an individual from raiiometive materials in liquid eff?aents released to unres ricted areas from each reactor (see Fig"re 2.1.) will not exceedt
- a. During any calendar quarter,1.5 mres to the tot'ai body and 5 ares to any organ, and b'. During aay calendar year, 3 ares to the total body and 10 area to any orgaa.
To ensure compliance, quantities of activity of each radteauclide released will be summed for each release and accumulated at least every 31 days as follows: l l I l i i ) l
, - - - - -- ---n-.--. , --,-n, -- _ ,_,- . - - - n- - - > - - - , - - . , - - - - .
Rav 3 VCLty2 23 SEF PAD!".*.~.GICAL EFFLLE. T/S FI;UIRED DCct,"E:r;": Pago 56 of 71 A. CFTS:n OCSE CALCU'Z:.*:.3
- 2. Release Analysis Calculations shall be performed for each batch release, and weekly for continuous releases according to the formula:
A (2.5) g ,,, p- i ) = Fraction of DBQ A g a Cumulative quarterly activity of nuclide i identified in 4 liquid release (Ci). (DBO)g a Design objective aunual quantity of radionuclide i from 6 Table 2.2 (Cg ). Traction of D50 =ust be ( 0.5 for quarter and g 1 for year. Radionuclides may be omitted from the sumusation if they fall under the criteria of allowed osission specified by Note 5 to Appendix 3, 10 CIlt 20.
- The design basis quantities are derived in such a conservative manner '
that doses say be greatly overistimated by this technique. As a i
- l. consequence of this conservatise, and in light of historically consistent operations with releases well below annual design basis
;antities, the 3ig Rock Potat Plant technical specift:ations do r.:t require mor.stly dose projections. However, Technical Specificatien 13.1.4.4 requires a cumulative dose contribution to be determined l
for current quarter and year every 31 days. If, at any time this calculation, by Iquation (2.5), results in values greater than 0.5 for a given quarter or 1.0 for year-to-date, the NRC 123 TAP code vill be run to ensure that Technical Specification 13.1.4.1 has been met. 1 values for the design basis quantities (Ci), and the dose per Curte (Dg /C,)g for each nuclide i shown in Table 2.2, were calculated as , follows: 1
a . l I Rev 3 l VOLUME 25 I?? ?X?ICLOGICAL EFFLL'E!i; 7/S PEQUIRED MtME'I"3 Page 57 of 71 A. :TFS!'"! DCSE CALCULA7:",!;S l l l 2.1 Water Innestica l The dose to an individual free Lagestion of radioactivity froe any source is described by the following equation: i (DCT)g) : Ig ree (2.6) D) = 1., where:
= Dose for the j th organ free radionuclides released, res. ;
D) ' j = The organ of interest.
= Adult ingestion dose coenitment factor for the j' (DCT)4) th organ from the i radionuclide res/pci, see Table 2.1.
I
!g Activity ingested of tae I radionuclide, pCi. ,
Ig is described by: r I g = I^t)(V)(365) pCi , (2.7)
'(800)(d) .
where: 365 = Days per year, i A g s Anegal activity released of 1" radionuclide, WCi. V a Average rate of wat,tr consumptior. (730 al/d ICRP 23,
- p. 358). ;
d = Dilution water flow for year (al). 800 m Dispersion factor free discharge to nearest drinking l vater supply, i
)
I l e 4
Rev 3 - VOLUME 25 ~d? FAO 0LCC* A' ITTLLTNT 7/S FE;UIRED '!!NO page 58 of 71 A. OFTSITE DCSI .'ALCULATICNS The dose equation thea becomes: i i D } (DCT)g) : AgRee (2.8) I = }}d ist 2.2 Tish _ t aae s tion The dose to an individual from the consumption of fish is described by
; Equat!,a 2.10. In this case the activity ingested of the t' radio- T nuclide (I )g is described by: I
!g
- A i I
t,I pCi ' 154 (2.9) , where: A g
- Annual rolessed of L I radionuclide,'pCi.
3 = Tish 6 socentration 'f actor of i th radionuclide pCi as A see Table 2.0. pdt/al, ! T = Amount of fish eates per year (21 kg). 15 = Dispersion factor froe discharge to fish exposure point. d a Dilution water flow for year (et). 4 Substitution of Equ.tica 2.9 into Iguation 2.s gives: l i Dj Ag aB g a DCTg )Ree (2.10)
= 1400 4
l
/ .
(s) ' 4 l 1 I 1
! 1 l
v:*.3 25 3RP PA0to!.CGlen EFT *.' INT T/s ?E;U!?EO OCC'.WNM A. CFFSITE OCSE !A* C"AT MS Rev 3 Page 59 of 71
- 3. Annual Analysis A complete analysis utilizing the NRC computer code IADTAP with r.'34 i tttal source release will b* done annually in conjuncties win the annual environmental report. This analysis will provti!e estimates of dosu to the total body and various organs to addition to the dose
, limiting organs considered in the method of Section 2. Tae for 'owing I
approaca is utilized in t.ADTAP. The dose to the j organ free a radionuclides. Dj , is described by a I D j* D gj res (2.11) ist a (DCF)g) x !( res (2.12) ist wherei i D g a Dese to the j'D crgan from the (* radionuclide, res, i j = The organ of interest (bone, GI tract, thyrcad. liver. : Gdney, luas or total body). - (DCT)g' = Adult ingestion dose comettaeat factor for :.ha J th organ free the i th radtonu' elide., res/pt,'t, see table 2.1. i
= Activity ingested of tae i th radionuclic's , pct.
!g
\ -
( for water ingessior, is descri' sed by: I g:A t uti (1,13) ud 1 r and (nr fish irrgestics !g is described by: I Tt I g*A t t WCi ( 2. l f.) i Vd , b r
. i V01E4E 25 3RP R.QIOLOGICAL Ef7LUE9 T/S REQUIRED DOCCES xe., 3 CTTSITE DOSE CALC'tLATIONS Page 60 of 71 A.
2.3 Releasine Radionuclides Not Listed in Table 2.2 Table 2.2 contains all nuclides indentified to date es routine constituents of licuid relv.sses at Big Rock Point Plant, plus those comon to boiling water reactors in general, even if not previously c'etected at Big Rock Point. Trom time to time, however, other nuclides may be detected. If the unlis:ed nuclids constitutes less than 10% of the NPC-fraction for the release, and all dnlisted nuclides total itse than 25% of-the MFC-f raction, i:ht nuclide may be considered not preser?. If the unlisted nuclide constitutes greater than 10% of the MPC ,
' taction, or all unlisted nuclides togeth 2r constitute greater than 25%, then each nuclide. should be assigned a DBQ equal to tha nost concsrvative value }isted for the physical form of the nuclide involved (noble gas, halogen or particulate).
should a nuclide not listed in Table 2.2 begin to aspear in sig-nificant quantities on a routine basis, rev$sion to this ODCM should be made in order to include a design basis quantity specific to that nuclide. t e
- , w , e, --,aw , + en w - - - -wr es-n vv-=--~-~q- w ~w w . s
Rev 3 VOLUME 25 2P- RADIOLOGIOC IF7LUI.E T/S PERUI3ED 2CUMEMS Page 61 of 71 A. CFFCITZ DOSE lECULATIONS where: Ag
- Actittity released of j" radionuclide kuring the year, pCi.
V 8 average rate of water consumption (730 al/d), t = Number of days during the year (365 d). V = Uispersion factor from point of discha Se to point of exposure. d = Dilution water volume (al). 8, = Tish concentration factor of the i th radionuclide,gpC,e/ * ' F- = Amovst of fish eaten per day (57.5 ge/d). D. OPERABILITY 0F LIQUIP RADWASTE EQUIP
- TNT The Big Rock Point liquid radvatte system is designed to reduce the radioretive raterials in liquid wastes prior ts their discharge (by recycle or shipment for disposal) so that radioactivity in liquid effluent releases to unrestricted areas (see Figare 2.1) will not*
exceed Techri:al Specification 131. .1. Maintaining the cumulative fri.ction of 1; lovable release for esch batch reletae and veekly for continuous releases assures couplian:e < tith this require =ent. In addition,1: yesrs of operating experiance (to the lato this Oy.'M vas "irst at:ptet) has shown that design basis quantities never have been exceedet. E. RELEASE RATE FOR OFFSITE MPC (500 mReis/ye) If CTR 20.106 requires radioactive ef ttuent releases to unrestricted arass be 16 ss than the limits specified in Appendix B, tabis II when averaged over a period not to exceed one year. Concentrations at this level, if ingested far one year, will result in a dose of 509 millites to the total bcdy or its equivalent to interna!, organs. In addition,10 CFR 50.36a reqvires that the release of radioactive materials be kept as inv as is reasonably achievable. However, the section further states that the licensee is permitted the flexibility 7m,
VOLOC 25 SRP RADIOLOGICAL EFFLLTr'; T/s .:nUIRED DOOLHCITS Rev 3 A. OFFSITE DOSE CALCDL4TIONS Page 62 of 71 of operation, to asaure a dependable source af power, to release quantities of material hisber than a small percentage of 10 CTR 20 limits but not exceeding those lisits under unusual operating condi-tions. Appendia I to 10 C7150 provides the numerical guidelines on limiting conditions for operations to meet the as low as is reason-ably achievable requirement. The IADTAP eJe 1:an been run to determine the dose due to dri9,ing vster at piant discharge c:ncentration (860 x nearest drinking etter intake concentration ~. The source tern used is given in !sble 1.1. The :::t limiting dose of the person hypothetically drinki ? this water is k.89E:.01 trer, whole body. The release rate which would resul- in a dose rate equivalent to 500 mre=/ year (the to il body limit ? is the Curies.' year given in Table 1.1 (8.9L) times 500/.L89 or 91h1 Ci/Yr = i.)E-OL Ci/sec. The above calculation is informational as a typical exposure using the drinking vater pa:hvay and an average release from Big Rock Point. Per seccies C.3 annual analyses are ruA using LADTAP to calculate estimatas of done to the total body and limiting chgans. i l l l l 1 1 l l U
VOLUME 2$ BRP R.CI0 LOGICAL EFFLUEST T/S REQUIRED DOCUMD3 A. OFTSITE DOSE CALCULATIONS Rsv 3 Page 63 of 71 III. UIUWital FUEL CYCLE DOSE A. SPECIFICATION It' ace:rlance with Technical Specification 13.2.o.1, if either liquil : gaseouc quarterly releases exceed the quantity which vould cause :ffsite doses more than -vice the limit :f Technical Specifica-ion 13.1.' . -hen the cumulative dose contributions from combined release plus direct radiation sources 'from the reset:r unit and radvaste storage anks) shall be calculsted. The dose is to be determined for the : ember of the public projected to be :te most highly exposed to these combined sources. B. ASSUMPTIONS I
- 1. The full time resident determined to be the maximally exposed individual (excluding infsat) is assumed also to be a fishersin.
This individual is assumed to drink vater and it. gest local fish l at the rates specified in Sections II C.2.1 and II C.2.2. l l l t
,. - - - n e - -- +m- , v v,
VOLC'E 25 SP? ?X)IOLcGICA:. 277.tT,n T/s 3Equ:aED r,ccLEr? A. ".7FSITE DCSE .CLUT!CNS key 3 1 Page 64 of 71
- 2. Amount of shorsline fishing (at accessible shoreline adjacent to site security fence) is conservatively assumed as 48 hours per quarter (average of app.oxtsately hour per day each day of the '
quarter) for the second and third quarters of the year, 36 hours for the fourth quarter and 18 hours for the first quarter. C. DOSE CALCULATION Maximum doses to the total body and inte>nal organs of an individual shall be, determined by use of LADTAP and GASPAR computer codes, and doses to like organs and total body summed. Added to this sum will be a mean dose rate, calculated or seasured for the shcreline due to plant presence daring the quarter in question, times the assumed fishing time: Do=Dg+Dg 4 + (R7)(T) (2.15) where:
~
~
D4 o = 40 CTR 190 Dose (area) . Og = Limiting dose to an_ individual from gaseous source term (ares) , Dg = LLaiting dose to an individual from liquid - source tern (area) RT = Mean dose rate calculated to'be applicable to Lake Michigan shoreline adjacent to plant site (ares /hr) T = Assumed shoreline fishing time for the quarter in question (hours?. et l l l l i
t a Rcv 3
??LLME 25 3RP RADIOLCG: CAL EFFLUE:i ! $ REQUIRED DOCLHE CS Pago e5 of 71 A. CFF SI' E DCSE CALCULAT:.':.1 TABLE 2.0 BIOACCLMUIATION FACTORS (pci/km per pCi/ liter) 1 FRESEWATER ELEMENT FISH H 9.0E-01 C. 4.6E+03 XA' 1.0C+02 P
1.0E+05 CR 2.0E+02
. NN 4. 0E+02 TE 1.0E+02 C0 5.0E+01 NI 1.0E+02 CU 5.0E+01 ZN 2.0E+03 BR 4.1E+02 ,
RB 2.0E+03 SR 3.0E+01 ; Y ' 2.5E+0i ' ZR - 3.3E+00 5'B 3.0E+04 MO 1.0E+01 TC 1.5E+01 RU
- 1.0E+01 RH 1.0E+01 TE 4.0E+02 :
I 1.5E+01 CS 2.0E+03 BA 4.0E+00 LA' 2.5t+01 CE 1.0E+00 PR 2.5E+01 XD 2.5E+01 W 1.25+03 N7 1.0E+0i i l l l 1 l l k l
. i.
'lOLLHE 2? 3RP RAD:0LCOICAL EFF*/JENT T/S REQU:7.I2 XCODTS A. OFF SITE DME CAI.""LATICNS Rev 3 Page 66 of 71 TABLE
-~
7.1
.A't.T INCESTION DOS' FACf0RS 08tDE/PCI IX2STED)
Pete 1 of 3 NYCL:7 SONT LIVER Y.Boof TNT 90TD _K t' WTY t t.'No ft LLt il 3 NO DATA 1.05t*07 1.05t*07 1.05t *07 1.05t*G; 1.05t47 1. 05f,*C 7 C w 2. 84 t *M $.68t 07 f 68t47 5.65 *C7 S.681 07 S.eet of 5.64t*07 NA 26 1. 70E *M 1.70t*06 1.70E*06 1.7C1 46 1. 70t46 1.70t*06 1.70t-06 P 32 1. 93t *% 1.20t*05 7.66t*06 NO D4IA NO DATA NO DATA 2.17E*05 CR $1 NO OTA NO DATA 2.66t*0% 1. $ 9t *01 5.86t *10 3.53t-09 6.69t 07 MM 54 NO DATA '6.57t*06 8.72t*07 NO L474 1. 9 04 NO DAIA 1.40t*05 MN 56 No DATA 1.15E*07 2.M E*0s No W2A 1.64t*07 No DATA 3.67s.4e TE $$ 2.75t M 1.90t*06 6.63t*07 No DAZA NO DATA 1.06t*06 1.09E*06 FI 59 4.34E 06 1.02t*0$ 3.91t*C4 No Dan No DAIA :.85t'06 3.60E*4$
..>.................................................................. n......................~.....
C0 54 NO DAIA 7.65t*07 1.67h*06 NO MIA NO DAIA NO DATA 1.312*05 CO 60 No DATA 2.16 t
- M 4.721*o6 NO ' IA 30 DATA No DATA 6.02t*05 MI 63 1.3CE % 9.01t*06 4.34t*06 No DATA NO DATA NO MtA 1.88t*C6 N! d$ 5. 28 t*01 6.86E*04 3.131 04 No MIA No DATA No DATA 1. 74t
- M CU 64 NO DAT4 8.33t*08 3.91E*00 .C MIA 2.10E*07 ho DATA 7.10t 06 .
ZN 65 6.461 06 ' 1.54t*05 6-96t*06 NO OAIA ~1.03t-05 ,No CATA .9.7CE*06 ~
'ZN 49 1.03t*08 1.975 08 1.31t*09 No MIA 1.2SE*08 No DATA 1.96t*09 BR 81 NO DATA No DATA 4.02Z*08 No DAIA NO DAM '40 DAIA $.79E*04 -
BL d4 NO DATA NO DATA , $.21E*04 NO '.AIA NO DATA NO DAIA 4.09t*13 80 85 NO DATA NO DAZA 2.1&E*09 No DAIA NO DAIA NO DAIA Li't*26 ita 86 NO DATA 2.111*0$ 1.83t*G4 NO DAIA NO DAIA NO DA'A 4.16E46 R3 84 NO LTA 6.0$t*00 3.212 06 NO ImIA NO DAIA #0 DATA 8.361 19
............................v........................................ ............................
R3 89 NO CA*A 6.011 06 2.821 00 NO DAIA !a3 DATA NO DAIA 2.33t*21 14 49 3.08t*% NO DA M 8.844 M NO L.aIA NO DATA NO DATA 6.94t*05
- $A 90 7.588 03 NO DAIA 1.ME43 NO DAIA NO DAIA NO %TA 2.19t*%
$R 91 5.671 46 NO DATA 2.29E*07 NO MIA NO DATA No JATA 2.70t*05
$R 92 2.13t*06 NO DATA 9. 30t
- 00 No MIA NO DATA 90 DATA k.26t*05 Y 90 t.621*09 NO DATA 2.34t*10 NO MTA NO DATA NO DATA 1.021* %
Y 91a 1.09 M 1 NO DATA 3.$21 12 No DAIA NO DATA NO DAIA 2.67t*10 Y 91 1.61E 07 NO DATA 3.77149 No DAIA M DATA No DATA 7.761 05 l Y *2 8.e.5 M 0 NC BATA 2.67t*11 NO DAIA NO DATA MO DATA 1.44t*0$ I l l I l 1 l t
- r --
, , , + , - - - , . ~ - - - - -
, i i
*r.*;3E 2 5 3?? ?.CIOLOGICAL EFFLU2n **/S BEQUIS' DCC.ES p,, y 3 A. :" $ ICE D?SE CALCULATIC'I? Page 67 o' 71 i
l ustZ 2.1 (Coe u ADCt.T !M 2STtoet D0$1 FACTot$ ORDf/K7 INGESTED) Fame 2 of 3 i
)
NUctt0E towt _ LIVER T.300T TWYR0!; KTDWIT LL'NC Ct.LLI Y 93 2.WI 09 MO DATA 7.6M* 11 MO DATA 10 DAIA NO DA'A 4. 50E-05 3 95 3. 0+ 04 9.75E 09 6.*CE*09 No DAIA ' 1.33t=08 NO DATA 3.09E *05 Z1 97 1.WE 09 3.39E 10 1.55E 10 NO DAIA $.175 10 No DATA 1.05t % 38 95 6.22t*09 3.66t*09 1.86t-09 M DATA 3.62Z 09 NO DAIA 2.10t*05 MD 99 NC 2ATA '6. 3'l M 4.202 07 NO DAIt. 9.76t*06 NO DATA 9.99E *% TC 99e 2.671 10 6.9tE*10 4.89E 09 1.06t*04 NO DATA 3.62E+10 6.13t 07
..........................................e.................... ..................................
.TC103 2.%E*10 3.64E 10 3.59E 09 NO DAIA 6.59t*09 1.87t*10 1.10t
- 21 AU103 1.13E 07 No DATA 7.971-08 NO DATA 7.04t*07 NO DATA 2.16t*05 RC105 1.% E*04 NO DAD 6.08t*09 NO DATA 1.99E*07 MO DAT4 9.62Z-04
............................................................... ......................... 2......
RU104 2.75t 06 NO DAh 3.632-07 NO DAIA 5.312 04 NO DATA 1. 78 t *% AC110e 1.6C:*07 1.64E 07 8.79E*08 NO DATA 2.93*07 NO DAu 6.ME 05 ft125e 2.WE*06 9.7 H 07 3.59t 07 0.06t*07 1.09t*05 No DATA 1..nt*0$ II127e 6.7*I 04 2.62E-06 8.252 07 1.73t*06 2.75t 05 NO DATA 1.27E*0$ It127 1.*CE 07 3.95t*04 2.30 06 8.1.5E 0J ~*.64E 07 NO DATA 8.68C*C6 TE129e 1.'5! 03
. 6.29t 06 1.42t-04 3.95E ot 4.80E-0$ NO DATA $.79t*0$
....................... .................................. .........................~..............
It129 3.16t 04 1.18t 08 7.65E-09 2.61t'04 1.32Z-07 NO DITA 2.37E*04
- Tt131A - L.73t*06 8.66E 07 7.05t*07 1. 36t
- N 8.572 ^6 NO C.iTA 8.6CE*05 TE1]1 . 1.971 04 8.23t 09 6.221-09 1.62f*04 S.63E-04 40 DAZA 2.79C 09 l T1132 2.53 04 1.63t-04 1. 338-M L.80t 04 1.57E*05 No DAIA 7.7u 0$ !
! 130 7.541 07 2.23E 06 8.80t*07 1. 89E*% 3.64t 04 No DATA 3.92Z-04 l I 131 4.16E 04 d.93E 04 3.611-04 1.951 03 1.02Z 0$ NO DATA 1.571*04 )
I 132 2.0M 07 5.63t 07 1. 90E-07 1.901 05 8.65t*07 No DAIA 1.071-07 1 133 1.63 06 2.67E*04 7.53E;07 3.632 % 6.312 04 90 DATA 2.*3 *04 I 13A 1.64 t*07 2.84t*07 1.03s*07 4.198 04 6.34t 07 ) NO DAIA 2.SlI*10 t I 135 6.62 07 1.16t 06 4. 28 E-07 7.65t 05 1.86t*06 No DAu 1.32-04 CS136 6.23 05 7.64t % 1.21E % No DAfA 6.79t 05 1.59t*05 2.5ff*04 1 C$134 6.53 04 2.57E*05 1.85t*05 No DATA 1.63t*05 1.96t 04 2.9*I 06 l CS137 7.171 0$ 1.09t % 7.16t 05 NO DATA 3.701 05 1.23E 05 2.1H +04 C$134 S.321 04 1.09E*07 5.60t*08 No DATA 1.012 04 7.93 09 6.6SE 13 BA139 9.70t 04 6.911 11 2. 86 t*09 NO DATA 6.66t+11 3.92t*11 1.73 07 l 1 l
. 1
Rsv 3 VOLLHE 25 3RP EECLN: 1* EFFLWr; T/S REQUIPD :. ..O"N Pago 68 of 71 A. CTF SI'"I : .'SE CALC'JLATIONS IABLE 2.1 (CorrI'D)
,ADetI INGESTION Doff TACIORS i'Ot2/PCI I4CTT!7Di Ps2e 3 of 3 ErL31 t0NE t'VER ". acDY INTR 0fD IIIDNtf LUNC CT LLt RA164 2.03E-05 2.35E-04 1.33E-04 NO DAIA 4. 6 7E-(4 1.64E 04 6,18E 05 hA161 6.711 08 3.564 11 1. 5'.E 09 !O DAIl. 3.311-11 2.02E 11 2.221 17 BA162 2.131 04 2.19E 11 1.36F*09 NO DAI.4 1.85E.11 1.26E 11 3.00E 26 1.4160 2.50E 09 1.26E 09 3.33E-10 NO DATA MO Dd.IA MO DATA 3.2SE C5 1.41Q 1.20E.10 5.'J2E Li 1.658'. 11 No DA*!A NO DATA NO DATA 4.25E 07 CI161 9.36E 09 '6.33E ~9 7.18E-10 NO DAM 2.941-09 MO DATA 2.62E 05 ,
....................................................................... -..........o............
CE163 1.65E 09 1.22E Ci 1.35E-10 NO Dt.IA 5.771 10 NO DATA 6.56E 05 C1166 6.69E 07 2.06E 07 2.62E 06 No 36TA 1.111 07 NO DAIA 1.65E 06 PR143 9.20E 09 3.69E 09 6.56E-10 NC D GA 2.131 09 NO DATA 4.03E 02 l I PR164 3.011 11 1.25E 11 1.53E 12 NO DAIA 7.05E 12 NO B*IA 4.33t*18 ND14) 6.19E 09 7.27E 09 6.35E 10 NO DAIA le.13E 09 NO DATA 3.69E OS I V 187 1.03E 07 f.6LE 08 3.011 04 NO DAIA NO DAIA NO DATA 2.82E*05
.TP239 1.19E*09 1.17E 10 6.65E-11 NO DATA 3.65E-10 NO DATA 2.60E 05 !
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3RP RADIOLCGICAL EFTLUENT T ! PEQUIRED DCCUMENTS Rev 3 VC".'XE 25 A. OFT SITE 0'.EE CALCULATION! Page 70 ef 71 TAB LE 2. 2 BIG ROCK POINT Laguid Ef fluent Desian Objective Annual Quantity Design Objective Dose Conversion Annual Quantity Nuclide Factors (ares /Ci) Individual /Orman (Curies) W-3 2.34E-06 Adult /TB 1.282 x 108 Na-24 3.95E 03 Teec/TB Sc-46 759.49 1.24E-02 Teen /TB 241.94 Cr-51 1.90E-03 Ma-54 Adult /GI (LLI) 5,263.16 8.39E 02 Adult /GI (LLI) 119.19 Fe-55 5.50E-03 Chiid/ Bone 1,818.18 Mn-56 1.22E-03 Tean/TB 2,459.02 Co-57 - 2.80E-03 Tees /Tl 1,071.43 Co-54 6.95E-03 Teen /TB Fe-59 431.66 4.93E-02 Adult /CI (LLI) 202.84 Co-60 2.90E-01 Teen /TB 10.34 Cu-64 1.48E-03 Teen /GI (LLI) 6,756.76 Ni-65 - 7.82E-04 Teen /TB - 7,853.4-2n 2.16E-01 Child /TB
~
Br-84 . 13.89 1.33E-03 Teen /TB 2,255.64 Rb-86 3'55E-01 Child /TB 3.0 Rb-88 4.54E.04 Teen /TB 6,607.93 Sr-89 1.93E-01 Child / Bone Sr-90 51.81 1.69E+00 Adult / Bone Sr-91 5.92 2.90E-03 Tseu/GI (LLI) 3,448.28 St-92 9.94Z-04 Teen /TE 3,018.11 Y-92 1.76E 04 Teen /73 17,045.5 Nb-95 8.88E+00 Zr 95 Adult /GI (LLI) 1.13 3.82E-03 Teen /T3 785.34 Xb-97 4.56E-04 Teen /T3 6,578.95 Zr-97 2.74E-03 Mo-99 Teen /GI (LLI) 3,649.64 1.31E-03 Teen /Xidney 7,633.b9 I Te-99 9.33E-05 Teen /TB 32,154.3 Ru-103 1.691 03 Teen /TB 1,775.15 Ag-110m 4.76E 02 Teen /TB 63.03 Cd-113e 7.38E-02 Adult /GI (LLI) 3b-124 135.50 9.3&E-03 Teen /TB 321.20 Sb-125 3.13E-02 Teen /TB 95.85 Te-127 9.04E-03 Teen /GI (LLI) 1,106.19 Te-1276 1.71E-01 Teen / Kidney
$8.48 O
y . . . - - - ,_.- . r-, -1_-.- -_,. -- , , , , - - , - ~ , -, -. - - - - - , - . - e - . . . - - ,w-~. . -- , - -y
% i Rev 3 VOLUME 25 17.: RADIOLCGICAL EFFLUIT T/S PERUIFE! NCOUIS Page 71 of 71 1 CFF SITE DCSE CALCULATIONS TABLE 2.2 (Contd)
Desian Objective Annual Quantity Design Objective bose Conversion Annual Quantity Nuclide Factors (ares /Ci) Individual /Orgas (Curies) Te-129s 3.27E-01 I-130 Adult /GI (LLI) 30.54 1.40E-02 Child / Thyroid 714.29 I-131 4.07E-01 Child / thyroid Te-131a 24.57 2.78E-01 Adult /GI (LLI) 35.97 I-132 1.95E-05 Teen /TB 1.534 a los
' Te-132 3.59E-01 Adult /GI (LLI)
I-133 27.86 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 I-135 1.91E-03 Child / Thyroid 5,235.6 j Ca-136 5.05E-01 Adult /TB 5.94 Cs-137 2. 08F.+00
- Cs-138 Acalt/TB . 1.44 1.52E-03 . Teen /TB Ba-139 3.05E-05 1.973.68 Ba-140 Teen /TB 98,360.7
- 2.75Ew03 -
Adult /GI (LLI) 3,636.36
~
La-140 2.27E-02 Ce-141 Adult /GI (LLI) 440.53 2.30E-04 Teen /TB . 13,043.5 Ce-144 4.08E-03 Eu-152 Adult /GI (LLI) 2,450.98 1.99E-01 Teen /T3 15.08 V-167 2.43E-01 Adult /GI (LLI) 41.15 NP -239 2.78E-03 Adult /CI (LLI) 3,597.12 t 9}}