ML20246J184
| ML20246J184 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/25/1989 |
| From: | Burdette R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20246J177 | List: |
| References | |
| PROC-890825, NUDOCS 8909050055 | |
| Download: ML20246J184 (95) | |
Text
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BIG ROCK POINT NUCLEAR POWER PLANT PROCEDURE LPPROVAL ' AND AUTHORIZATION Procedure No. VOLUME 25 Rev No. 4 Procedure Title BIG ROCK POINT RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS '
l A. OFFSITE DOSE CALCULATIONS B. PROCESS CONTROL PROCRAM CURRENT REVISION STATUS Author RLBurdette Date 03/09/89 Quality Review Form No. 262-89 APPLICABILITY ISSUE HISTORY Revision No. NA Date NA Quality Review Form No. NA Approved for use Procedure Sponsor / Designate 'ff Date 8/9
' Authorized Period of Use [! NA through NA
.n When applicable:
PROCEDURE IMPLEMENTATION HISTORY 8909050055 890830 PDR R ADOCK 05000I55 Reviewed for System or Component Operability PDC Performed by Completed / Reviewed by Method of Verification Title Title o Functional Test a Physical Inspection Date Time Date Time o Administrative Review MAINTENANCE ORDER NO. (if applicable)
CD0689-1336A-BA01
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' Approval Requirements g at tt Yes : Safety Evaluation, PRC and QA Review and Approval 1 Revision No : PRC and QA Review (when applicable)
Tempora ry : Expiration Date Change No : Signatures Below, Subsequent PRC and QA Review Required Yes : Safety Evaluation, PRC & QA fieview & Approval Required
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Page Z of [o PROCEDURE CHANGE FORM PROCEDURE NO e/J2C CURRENT REV NO 3 Type of
- Change of Approval Requirements Change Intent?
Yes : Safety Evaluation, PRC and QA Review and Approval l Revision .K No : PRC and QA Review (when applicable) i Temporary : Expiration Date l Change No : Signatures Below, Subsequent PRC and QA Review Required Yes : Safety Evaluation, PRC & QA Review & Approval Required I
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Paga d of 4 PROCEDURE CHANGE FORM ;
1 l'
PROCEDURE NO YO / 27 CURRENT REV NO 3 Type of
- Change of '
Approval Requirements Change Intent?
Yes : Safety Evaluation, PRC and QA Review and Approval
-X Revision / No : PRC and QA Review (when applicable)
Temporary : Expiration Date Change No : Signatures Below, Subsequent PRC and QA Review Required Ye1 : Safety Evaluation, PRC & QA Review & Approval Required The fc11owing portions / steps of the above procedure are revised as follows:
Steps Revision Reason
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Page Y of 6 PROCEDURE CHANGE FORM PROCEDURE NO [2I CURRENT REV NO 3 Type of
- Change of Approval Requirements Change Intent?
Yes : Safety Evaluation, PRC and QA Review and Approval 1 Revision . K No : FRC and QA Review (when applicable)
Temporary : Expiration Date Change No : Signatures Below, Subsequent PRC and QA Review Required Yes : Safety Evaluation, PRC & QA Review & Approval Required Th2 following portions / steps of the above procedure are revised as follows:
Steps Revision Reason eq Z8 (Wome n.c S$o n
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Page [of h PROCEDURE CHANGE FORM PROCEDURE N0 d[ 2 [ CURRENT REV No 3 Type of
- Change of Change Intent? Approval Requirements g Revision . Yes : Safety Evaluation, PRC and QA Review and Approval l No : PRC and QA Review (vben applicable)
Temporary : Expiration Date Change No : Signatures Below, Subsequent PRC and QA Review Required Yes : Safety Evaluation, PRC & QA Review & Approval Required Th2 following portions / steps of the above procedure are revised as follows:
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_ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ - ._-___ i
Page d of b PROCEDURE CHANGE FORM PROCEDURE NO 6[ Mf CURRENT REV NO 3 l
- *I * ' Approval Requirements
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>C No : PRC and QA Review (when applicable)
Temporary : Expiration Date Change No : Signatures Below, Subsequent PRC and QA Review Required Yes : Safety Evaluation, PRC & QA Review & Approval Required Th'2 following portions / steps of the above procedure are revised as follows:
Steps Revision Reason o
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M : y0LhME'25; BIC ROCK POINT RADIOLOGICAL- Revision 4 EFFLUENT-T/S REQUIRED DOCUMENTS 'Page 1.of 2 A. OFFSITE DOSE CALCULATIONS B. ' PROCESS CONTROL PROGRAM-TABLE OF CONTENTS / EFFECTIVE ' PACES 1
Revision Pages i
4 79
!l I. CASEOUS EFFl.UENTS
'I. A ALARM / TRIP $ET POINT METHOD I.B DOSE CALCUI,ATION
. I.C DESIGN BASIS QUANTITY (DBQ) LIMITS
. I .D ' CASEOUS RADWASTE TREATMENT SYSTEM OPERATION-
-I.E OFFSITE MPC RELEASE RATE I.F PARTICULATE AND IODINE SAMPLING
-I.C NOBLE GAS SAMPLING I.H- . TRITIUM SAMPLING
. II. LIQUID EFFLUENTS-II.A. ALLOWABLE CONCENTRATION II.B INSTRUMENT ALARM SET POINTS
- II.C DOSE II.D OPERABILITY OF LIQUID RADWASTE EQUIPMENT II.E OFFSITE MPC RELEASE RATE III URANIUM FUEL CYCLE DOSE III.A SPECIFICATION III.B ASSUMPTIONS III.C DOSE CALCULATION i
CD0689-1336A-BA01
VOLQME 25- BIG ROCK POINT RADIOLOGICAL
- Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 2 of 2 A. OFFSITE DOSE CALCULATIONS
- B. PROCESS CONTROL PROGRAM Revision _Pages h-B. PROCESS CONTROL PROGRAM 0 4
~
1.0 'PROCRAM OVERVIEW 2.0: DEWATERING SOLIDS IN HICH INTECRITY CONTAINERS (HIC) 3.0 DELWARE CUSTOM MATERIAL (DCM)-SILICATE CEMENT 4.0 10 CFR 61 REQUIREMENTS 5.0 ABSORBED MATERIALS (RICHLAND BURIAL SITE ONLY) l' l
l 1
OD0689-1336A-BA01
- _ _ _ _ - - - _ _ . ___________- _________ _ _ _ Q
-;C. -, VOLUME 25 '- ERP RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS
+
l-r t.
. Consumers Power Company.
~ Big Rock Point Plant-Docket 50-155 i
y U
r l
.A. BIG ROCK POINT OFF SITE DOSE CALCULATIONS t
__m.___ _ _ . _ _ _ _ . _ _ . . .
. =.-
.V'OLUME.25 BIC ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 1 of.79 A. OFFSITE DOSE. CALCULATIONS l
PURPOSE The purpose of this manual is to provide the methodologies and parameters used to:
- 1. Calculate offsite doses consistent with.10 CFR 50, Appendix I,
-during routine operations.
- 2. Determine alarm / trip set points of effluent monitoring instrumentation.
REQUIREMENTS This manual is required per Technical Specifications:
6.9.2.2.A.4 - Radiological Impact on Man 13.1.1.1 - Radioactive Effluent Monitoring Instrumentation Operability and Surveillance Requirements 13.1.3.3 - Caseous Effluent Dose Rate i
13.1.4.4 - Effluent Dose Review, approval, issue and control is performed per Volume 1, Administrative Procedure 1.2.
..ianges to this manual shall be submitted to the Commission in accordance with Technical Specification 6.15.
OD0589-1333A-BA01 j
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ . _ _ _ l
- s. <
v0$UME*25 'BIC ROCK POINT RADIOLOGICAL Revision'4 EFFLUENT 7/S REQUIRED DOCUMENTS Page 2 of 79 A. OFFSITE DOSE CALCULATIONS I. CASEOUS: EFFLUENTS "I.A ALARM / TRIP SET POINT METHOD l
Technical Specification 13.1.3.1 requires that MPC is not exceeded
? when averaged over a period not to exceed one hour. Based on the definition of MPC, the dose in unt'estricted areas due to gaseous effluents from the site shall be limited at all times to the following values:
- 1. 500 mrem /y to the total body and 3,000 mrem /y to the skin from noble gases.
- 2. 1,500 mrem /y to any organ from radiciodines and particulate, due to inhalation.
Specification 13.1.1.1 requires gaseous effluent monitors to have alarm / trip set points to ensure that offsite concentrations, when everaged over one hour, will not be greater than HPC. This section of the ODCM describes the methodology that will be used to determine these set points.
The methodology for determining alarm / trip set points is divided into two major parts. The first consists of calculating an allowable concentration for the nuclide mixture to be released.
The second consists of determining monitor response to this mixture in order to establish the physical settings on the monitors.
I.A.1 Allowable Concentration The total MPC-fraction (R) for the stack release point will be calculated by the relationship defined by Note 1 of Appendix B, 10 CFR 20.
Ci R = (E) (F) i = 51.0 (I.1)
Q MPCg i
4 where:
Cii = The measured or calculated concentration, at ambient tem-perature and pressure, of nuclide i (pCi/cc) at the stack.
MPCi = The MPC of nuclide i from 10 CFR 20, Appendix B.
R = The total MPC-fraction for the stack release point. ]
OD0589-1333A-BA01 ]
7
- s. .
VOLUME *25 BIG ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 3 of 79 A. OFFSITE DOSE CALCULATIONS X/Q = Host conservative sector site boundary dispersion (9.12h-08 sec/m').
F = Release flow rate (39,000 cfm = 18.4 m*/sec) for stack monitor considerations; variable for other monitors.
I.A.2 Monitor Response Normal radioactivity releases consist predominantly of 30-minute decayed fission gasses. Therefore, stack monitor response cali-brations are performed to fission gas typical of normal releases (30-minute-decayed off gas). Air ejector off gas monitor measures only slightly decayed gasses, however, so is calibrated to provide accurate response to relatively fresh fission gasses. Response monitors used to define fission product release rates under accident conditions may vary from that of these mixes, however.
Monitor response for the two categories of monitor is determined as follows:
- 1. Normal Releases (30-minute-decayed fission gasses)
Total gas concentration (pCi/cc) at the monitor is calcu-lated. The calibration curve or constant for cpa/(pCi/cc) is applied to determico cpm expected. The setting for monitor alarms is establieued at some factor (b) greater than 1 but less than 1/R (Equation I.1) times the measured concentration (c):
s=bxc (I.2)
- 2. Accident Releases Monitors are preset to alarm at or before precalculated offsite dose rates would be achieved under hypothetical accident conditions. These set points are established in accordance with Emergency Plan requirements for defining Emergency Action Levels and associated actions. Emergency Implementing Procedures contain monitor-specific curves or calibration constants for conversion between eps and pCi/cc (or R/hr and pCi/ce), depending on monitor type, for fission product mixtures as a function of mixture decay time.
When these monitors are utilized for other than accident conditions, either an appropriately decayed " accident" conversion curve may be used, or a decayed fission gas calibration factor may be applied. In these cases, set points are established as in 1 above.
l CD0589-1333A-BA01 t . .
9-VO(UME75 BIG ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 4 of 79
' A .- OFFSITE DOSE CALCULATIONS
- I.B- DOSE CALCULATION.
1.B.1 Doses are calculated for (1) noble gases and (2) iodines and particulate. Doses as defined in this section are based on 10 CFR 50, Appendix I limits of mrem per quarter and millirem per year. All dose pathways of major importance in the Big Rock environs are considered.
I.B.1.1 Equations and assumptions for calculating doses from noble gases are as follows:
1 l I.B.1.1.1 Assumptions 1
- 1. . Doses to bc calculated are the maximum offsite point in air, total body and skin.
- 2. Exposure pathway is submersion within a cloud of noble gases.
- 3. Noble gas radionuclides mix is based on the historically observed source term given in Table 1.1, plus additional nuclides.
- 4. Basic radionuclides data are given in Table 1.2.
S. All releases are treated as elevated at 73 m.
- 6. Meteorological data expressed as joint-frequency distribution of wind speed, wind direction, and atmospheric stability for the period resulting in X/Qs and D/Qs are shown in Table 1.3.
- 7. Raw meteorological data consist of wind speed and direction measurements at 71 m.
- 8. Dose is to be evaluated at the offsite exposure points where maximum concentrations are expected to exist, and nearest residents.
- 9. Potential maximum population (resident) exposure points are identified in Tcble 1.4.
- 10. A semi-infinite cloud model is used.
- 11. For person exposures, credit is taken for shielding by residence (factor of 0.7).
- 12. Radioactive decay is considered for the plume.
CD0589-1333A-BA01
- . . e t 'g VOLhME15 EIC ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 5 of 79 A. OFFSITE DOSE CALCULATIONS n
- 13. A sector-average dispersion equation is ased.
- 14. The wind speed classes that are used are as follows:
Wind Speed Class Number Range (m/s) Midpoin; (m/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 1.5-10.0 8.75 7 >10.0 -
- 15. The stability classes that will be used are the Standard A through C classifications. The stability Classes 1-7 will correspond to A = 1, B = 2...G = 7.
- 16. Terrain effects are not considered, and no open terrain recirculation factors are applied.
I.B.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 radionuclides:
7 7 i" exP (-Ai )
Izk n /n) j=1 K=1 8
X exp ( -h )
2a 8 zk (I.3) where Xi = Air concentration of radionuclides i, pCi/m*.
fjk = Joint relative frequency of occurrence of winds in wind speed class j, stability class k, blowing toward this exposure point, expressed as a fraction.
Qi = Average release rate of radionuclides i, pCi/s.
1 P = Fraction of radionuclides remaining in plume.
Izk = Vertical dispersion coefficient for stability class k (m).
CD0589-1333A-BA01'
4 .
, VOLUM5 25 BIG ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 6 of 79 A. OFFSITE DOSE CALCULATIONS l
(
i
'uj = Midpoint value 'of wind speed class interval j, m/s.
x = Downwind distance, m.
n = Number of sectors, 16.
I- A = Radioactive decay coefficient of radienuclide i, s'I.
2nx/n
- Sector width at point of interest, m.
h = Stack height (73 meters).
8 o
z.k
= Vertical dispersion coefficient of stability class k.
For determining the total body doset Dg=
T Xi DFBi (I.4) l l where DTB = Total body dose mrem /y.
l l
Xi = Air concentration of radionuclides i, pCi/m*.
l DFBi = Total body dose factor due to gamma radiation, mrem /y per pCi/m* (Table 1.5).
j l
l For determining the skin doset Ds = Xi (DFSi + 1.11 DFYi) (I.5)
L where:
D, = Skin dose mrem /y.
l Xi = Air concentration of radionuclides i, pCi/m'.
DFSi = Skin dose factor due to beta radiation, mrem /y per pCi/m*
(Table 1.5).
1.11 = The average ratio of tissue-to-air energy absorption
- coefficients, mrem / mrad.
l l
DFYi = Camma-to-air dose factor for radionuclides i, mrad /y per pCi/m' (Table 1.5).
i OD0589-1333A-BA01
.3 *-
L.;
L.YOf.UME. 25 BIC ROCK POINT. RADIOLOGICAL
- Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS : Page 7' of 79 A. OFFSITE DOSE CALCULATIONS for determining. dose rate to a point in air!
~
Da = Xi (DFYi or DFB[) (I.6) i wheret Da = Air dose mrad /y.
DFB = Air dose factor for beta radiation (Table 1.5).
I . B .1 '. 2 Equations and assumptions for calculating doses from radiciodines and particulate are as follows:
I.B.I.2.1 Assumptions
- 1. Dose is to be calculated for the critical organ, thyroid, and the critical-age groups (adult, teen, child, infant), infant (milk) and child (green, leafy vegetables).
- 2. Exposure pathways from iodines and particulate are m(Ik ingestion, ground contamination, green leafy vegetables frem home gardens and inhalation.
- 3. The radiciodine and particulate mix is based on the his-torically observed source term given in Table 1.1.
NOTE: Source term (s) may be changed if radionuclides mix differs significantly from the historical source terms per
-Technical Specification 13.1.3.3 - Sampling and Analysis.
- 4. Basic radionuclides data are given in Table 1.2.
- 5. All releases are treated as elevated (73 m).
- 6. Annual average X/Qs are given in Table 1.3.
- 7. Raw meteorological data for elevated releases consist of wind speed and direction measurements at 71 m.
I
- 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 considercd.
- 10. Potential maximum exposure points (Table 1.4) considered are the nearest cow, goat and home garden locations in each sector.
i
- 11. Terrain effects are not considered.
CD0589-1333A-BA01 l L__=________-_-__-_---_-- -
VOLdME 25 BIC ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 8 of 79 A. OFFSITE DOSE CALCULATIONS
- 12. Plume depletion and radioactive decay are considered for air-concentration calculations.
- 13. Radioactive decay is considered for ground concentration calculations.
- 14. Milk cows and goats obtain 100% of thei: food from pasture grass May through October of each year.
- 15. Credit is taken for shielding by residence (factor of 0.7).
I.B.I.2.2 Equations ,
To calculate the dose for any one of the potential maximum-exposure points, the equations of Sections I.B.1.2.2.1- I.B.1.2.2.5 are used.
10B.1.2.2.1 Inhalation Equation for calculating air concentration, X, is the same as in the Noble CasSection I.B.1.1.2 (Equation I.3).
For determining the organ dose rate:
D = 1 x 10 6 X. DFI, BR (I.7)
I 1 a i
wheret DI = Organ dose due to inhalation, mrem /y.
Xi = Air concentratica of radionuclides i, pCi/m*.
DFIi = Inhalation dose factor, mrem /pci (Table 1.7).
BR n Breathing rate 1,400 m'/y, infants 3,700 m 8
/y, child; or 8,000 m'/y, adult and teen.
1 x 106 = pCi/pci conversion factor.
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'I.B.I.2.2.2 Cround Contamination i
. For determining the ground concentration of any nuclides y
C k9 1" k i =3.15'x-10fQ (2nx/n) Ag II - exP - (Ai tb)) lexp jo;h' )) (I.8) zk i
k=1 wheret.
Ci = Ground concentration of radionuclides i, pCi/m*.
1,= Stability class.
fk = Joint relative frequency of occurrence of winds in stability class k blowing toward this exposure point, expressed as a fraction.
Qi = Ava. rage release rate of radionuclides i, pCi/s.
DRk = Relative deposition rate, 1/m..
x = Downwind distance, m.
, n = Number of sectors, 16.
2nx/n = Sector width at poir.t of interest, m.
Ai = Radioactive decay coefficient of radionuclides i, y-I.
tb = Time for buildup of radionuclides on the ground, 35 y.
3.15 x 107 = s/y conversion factor.
h = Stack height (73 m).
o'zk = Vertical dispersion coefficient (m') of stability class.
- cocnn-n
., 'e VQL'UME 25 BIC ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 10 of 79 A. OFFSITE DOSE CALCULATIONS For determining the' total' body or organ dose from ground contamination Dc = (8,760)(1 x 106 )(0.7) C1 DFCi (I.9)
I where:
Dc = Dose due to ground contamination, mrem /y.
Ci = Cround concentration of radionuclides i, pCi/m*.
DFCI = Dose- factor for standing on contaminated ground, mrem /h per pCi/m* (Table 1.8).
8,760 = Occupation time, h/y.
1 x 106 = pCi/pci conversion factor.
0.7 = Shielding factor a ounting for a distance of 1.0 meter above ordinary ground, dimension 1rse.
I.B.I.2.2.3 Milk and Vegetation Ingestion For determining the concentration of any nuclide (except C-14 and H-3) in and on vegetation:
7 I
CVi = 3,600 k9 DR i k (r[1 - exp (~A Ei Ee)) + (I.10)
(2nx/n) Y, AEi J
k=1 B
gy [g , ,,,(-A b pag g t )) (,,p (20;h* ) (,,p (-A i t h) sk where:
CVi = Concentration of radionuclides i in and on vegetation, pCi/kg.
k = Stability class.
fk = Frequency of this stability class and wind direction !
combination, expressed as a fraction.
Qi = Average release rate of radionuclides i, pCi/s.
DRk = Relative deposition rate as a function of wind speed, stability class and downwind distance, a-I (Figures 7 ;
through 10 of Regulatory Guide 1.111). I
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( A. OFFSITE DOSE CALCULATIONS x = Downwind distance, m.
l' n = Number of sectors, 16.
2nx/n = Sector width at point of interest, m.
O
r = Fraction.of deposited activity retained on vegetation (1.0 for iodines, 0.2 for particulate).
AE i = Effective removal rate constant, A E1
- Ai + Aw, where Ai is the radioactive decay coefficient, h-I, and Av is a measure of physical loss by weathering (Aw = .0021 h-I).
te = Period over which deposition occurs, 720 h.-
Yy = Agricultural yield,'0.7 kg/m .
Biy = Transfer factor from soil to vegetation of radionuclides i (Table 1.6).
Ai = Radioactive decay coefficient of radionuclides i, h-1 tb = Time for buildup of radionuclides on the ground, 3.07 x 105 h (35y).
P = Effective surface density of soil, 240 kg/m'.
3,600 = s/h conversion factor.
h = Stack height (73 m).
og = Vertical dispersion coefficient (m).
th = Holdup time between harvest and consumption of food, 0 h for pasture grass or 2,160 h for storage feed.
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For determining the concentration of C-14 in vegetation:
8 CV14 = 1 x 10 X14 (0.11/0.16) (I.11) where:
CV14 = Concentration of C-14 in vegetation, pCi/kg.
X1 4 = Air concentration of-C-14, pCi/m*.
0.11 = Fraction of total plant mass that is natural carbon.
0.16 = Concentration of natural carbon in the atmosphere, g/m8 .
1 x 108 = g/kg conversion factor.
For determining the concentration of H-3 in vegetation:
8 CVT = 1 x 10 XT (0.75)(0.5/H) (I.11a) where CVT = Concentration of H-3 in vegetation, pCi/kg.
XT = Air concentration of H-3, pCi/m*.
0.75 = Fraction of total plant mass that is water.
0.5 = Ratio of tritium concentration in plant water to tritium concent. ration in atmospheric water.
H = Absolute humidity of the atmosphere, g/m8 .
I x 10 8= g/kg conversion factor.
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'VDLUME 25 BIC-ROCK POINT. RADIOLOGICAL Revision 4
): ' EFFLUENT T/S REQUIRED DOCUMENTS Page 13 of 79 A. OFFSITE DOSE CALCULATIONS For ' determining the concentration of any nuclide in cow's or goat's allk:
chi = CVi FMI Qt exp (-Ai tr) (I.12) where CMi = Concentration of radionuclides i (including C-14 and H-3) in milk, pCi/1.
CVi = Concentration of radionuclides i in and on vegetation, pCi/kg.
FHi = Transfer factor from feed to milk for radionuclides 1, d/1 (Table 1.6).
Qg =. Amount of feed consumed by the milk ' animal per day, cow -
50 kg/d, goat - 6 kg/d.
Ai = Rad: ., active decay coefficient of radionuclides i, d-I.
tf = Transport time of activity from feed to milk to receptor, two days.
For determining the organ dose from ingestion of green leafy vegetables and milk:
D = 1 x 10 6 CMi DFi UM (I.13) i where D = Organ dose due to ingestion, mrem /y.
CMi = Concentration of radionuclides i in vegetables or milk, pCi/kg (or liters).
DFi = Ingestion dose factor, mrem /pci (Table 2.1).
UM = Ingestion rate for milk, 3301/y - infant and child, 400 1/y - teen, and 310 1/y - adult.
Ingestion rate for vegetables, 26 kg/y - child, 42 kg/y teen, and 64 kg/y - adult.
1 x 10 6 a pCi/pci conversion factor.
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I.B.1.2.2.4 Heat. Ingestion'(Beef)
To calculate the concentration of a nuclide in animal flesh:
Cri = Fri CVi Qt exp (-Ai ts) (I.14)
- where:
Cri = Concentration of nuclide i in the animal flesh, pCi/kg.
Fri = Fraction of animal's daily intake which appears in each kg of flesh, days /kg (Table 1.6).
CVi = Concentration of radionuclides i in the animal's feed (Equation I.10).-
Qf = Amount of-feed consumed by the cow per day, 50 kg/d.
ts = Average time from slaughter' to consumption, 20 days.
To determine the organ dose from ingestion of beeft Dr = CiDiUf f f (I.1$)
~i where:
Dri = Ingestion dose factor for age group, mrem /pci (Table 2.1) for nuclide 1.
Uf = Ingestion rate of meat for age group, kg/y (child - 41, teen - 65, adult -110).
I.B.I.2.2.5 Organ Dose Rates OD0589-1333A-BA01
' VOLUME.25 BIG ROCK POINT RADIOLOGICAL.
I* Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 15 of-79 A. OFFSITE DOSE CALCULATIONS For determining the total body, ' organ and/or thyroid dose rate from iodines and. particulate:
D=DI+DC + Dg + Dy + De (I.16) where D = Total organ dose, mrem /y.
DI = Dose due to inhalation, mrem /y.
DC = Dose due to ground contamination, mrem /y.
DM = Dose due to milk ingestion, mrem /y.
Dy = Dose due to vegetable ingestion, mrem /y..
Dr = Dese due to meat ingestion, mrem /y.
I.B.1.2.3 The maximum organ doce rate, maximum total body dose rate,' maximum skin dose rate plus beta and gamma air doses calculated in the previous section (Section I.B.1.2.2) are used to calculate design basis quantitles~as described in Section I.B.1.3.
~
I.B.1.3 Design Basis Quantities The design basis quantity of a radionuclides emitted to the atmosphere is the amount of that nuclide, when released in one year, which would result in a dose not exceeding any of the following:
- 1. 15 millirems to any organ of an individual from iodines and particulate with half life greater than 8 days.
- 2. 20-millirad air dose for beta radiation from noble gas (see note below).
- 3. 10-millirad air dose for gamma radiation from noble gas (see.
note below).
4
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,,IV0LUME 251 BIG ROCK' POINT RADIOLOGICAL J
- Revision'4 EFFLUENT T/S: REQUIRED DOCUMENTS Page 16:of 79 A;--.0FFSITE DOSE CALCULATIONS Design basis quantity (C1) is the' smallest. value for each nuclide,
-calculated by dividing the dose' limits (a,through c'above) by the appropriate dose calculated'in. Step 1; the result then is multi-
- plied by the; amount of radionuclides (Ci). used to conservatively.
D estimate the doses of Section D, as listed in Table.l.1L(or c assured a hypothetical 'i Ci/ year for nuclides not sctually present)
DBQ =D AI (Ce) (I.17) e wheret DAI1" A PPendix I' dose limit (mrem or mrad).
De = calculated' dose from. Step 1.(mrem or mead).
Ce = Quantity of nuclide resulting in. dose De (Ci) -.
'DBQ = Design Basis Quantity (Ci).
The limiting values for Design Basis Quantities for radionuclides released to the atmosphere are given in Table 1.9.
NOTE: For conservative calculations the DBQs listed in Table 1.9 are based on:
- 1. 15 millirems to any organ of an individual from iodines and particulate with a half life greater than eight days.
- 2. 15-millirad air dose for beta radiation from noble gas.
- 3. 5-millirad air dose for gamma radiation from noble gas.
The inverse of the ratio'Cc/Dc in the above equation (ie, D c/Ce) is a.useful value, since it represents the most limiting dose per unit quantity of each nuclide released.
I.B.1.4 Land Use Census and DBQ Changes Technical Specification 13.2.3 describes the requirements for an a nnual land use census and revision of the ODCM for use in the following calendar year. Areas of the ODCM which will be re-viewed, and changed if appropriate, are Table 1.4 (Land 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 following the year of the survey.
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yathME25 BIG ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 17 of 79 A. OFFSITE DOSE CALCULATIONS 1.C DESIGN BASIS QUANTITY (DBQ) LIMITS I.C.1 Design Basis Quantity Fraction Per Technical Specification 13.1.4.4 the cumulative DBQ fraction for nuclides released is summed at least every 31 days to assure that the sum of the fractions of all nuclides released does not exceed 1.0 year to date and 0.5 in any calendar quarter.
A.
1 (DBQ);
< 1.0 (I.18) i I.C.2 Exceeding DBQ Limits As discussed under I.B.1.3 the DBQ is a very conservative estimate of activity which could give doses at 10 CFR 50, Appendix I limits. Because different organs are summed together and doses to different people are summed, the DBQ typically overestimates dose by about a factor of five. Thus, if calculations of the DBQ fraction exceed 1.0 for year to date or 0.5 for the quarter, technical specifications probably still would not be exceeded.
However, further discretionary releases should be deferred un'til an accurate assessment of dose is made by use of the NRC CASPAR computer code. The computer run will utilize the annual average joint frequency meteorological data based on not less than 3 years of meteorological measurement., and will reflect demographic and land use information from the land use survey generated in the most recent prior year. Where appropriate, seasonal adjustments will be applied to obtain realistic dose estimates since both recreational and agricultural activities can vary greatly in relation'to season of the year.
It should be noted that Big Rock Paint to date (based on review of semiannual effluent data) has never exceeded the annual or quarterly DBQ fraction, despite its conservatism at any time in the past ten years (since stainless steel fuel cladding was replaced by zircaloy and other engineering changes were made). Thus, it is not expected that an alternate to the DBQ method will be required unless the plant is in a significantly off-normal condition.
1 i
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) . .,o EFFLUENT T/S REQUIRED DOCUMENTS Page 18 of 79 A.- 0FFSITE DOSE CALCULATIONS n, -
l- lI.C.3 Releasing Radionuclides Not Listed in Table 1.9 l' Table '1.9 contains. all: nuclides identified to 'date as routine constituents.of' gaseous' releases at' Big Rock Point. Plant, plus-those common to boiling water reactors in general, even if not previously detected at Big Rock Point.. From time to-time, however, other nuclides may be detected.
If the unlisted nuclide constitutes less than 10% of the NPC-fraction'for the release, and all unlisted nuclides total less than 25% of the MPC-fraction, the nuclide may be considered not present.
If the unlisted'nuclide constitutes greater than 10%.of the MPC-fraction, or all unlisted-nuclides togethec-constituts greater than 25%,' then each nuclide should be assigned a DBQ equal to the most conservative value listed for the physical form of the nuclide involved (noble gas, halogen or particulate).
Should a nuclide not listed in Table 1.9 begin to appear in significant quantities on a routine basis, revision to thss ODCM should be made~ in order to include a design basis quantity specific to that nuclide.
I.D CASEOUS RADWASTE TREATMENT SYSTEM OPERATION
.I.D.1 System Description The gaseous radwaste system consists of a delay line for condenser off gas.which provides approximately 30 minutes of decay time prior to release via the 73 m stack. A flow diagram of gaseous waste release paths is shown in Figure 1-1.
Condenser off-gas represents more than 95% of the total gaseous
=
source ters. The other minor sources are gland seal condenser exhaust, containment ventilation, radwaste. system vents and.
miscellaneous turbine building system leakage. All these sources are ducted.to the stack for release. I p I.D.2' Determination of Satisfactory Operations Operability requirements for the gaseous waste treatment are not
.specified. This is because the decay line is an integral part of the release path' piping for condenser off-gas. J l 4 4
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- I.E :OFFSITE MPC RELEASE RATE 10 CFR 20.106' requires that radioactive effluent: releases to un-restricted areas be in concentrations less than the limits speci-fled in Appendix B, Table II when~ averaged over a. period not to exceed lone year. (NOTE . Total area within the site boundaries is unrestricted as' defined'by Figure 2.1.) ' Concentrations at-this level if present'for one year will result.in a' dose of 500 mrem total body or 3,000 mrem to skin or 1,500 mrem to the critical organ depending on ~ the nuclide(s)' released. 10 CFR 50.36a requires that-the release of-' radioactive materials be kept as low as-reasonably achievable. . However, the section further states that the licensee'is permitted the flexibility of operation, to assure a dependable' source of power, to release quantities of material, higher than a small percentage of 10 CFR 20 limits but not exceeding those limits under. unusual operating conditions. Appendix I to
~
~10 CFR.50 provides the numerical guidelines on limiting conditions for operations to meet the as low as reasonably achievable requirement.
.The CASPAR code has been run to determine the dose due to external radiation'and inhalation. The source term used is-listed in Table 1.1.- The meteorology data is given in Table 1.3. Dose using annual average meteorology, to the most limiting offsite dose.(whole body) assumed to be residing at the residence with highest;I/Q, is 0.105 mrem Cor one_ year. The release rate which would result in a dose equivalent to 500 arem/y (using the total body limit) is the Curies / Year given in Table 1.1 (1.29E04) multiplied by 500/.105 or 1.95.Ci/sec.-
The above calculation is informational as a typical exposure using average releases from Big Rock Point. Actuti exposure calculations are described in Section I.A.
I.F PARTICULATE AND IODINE SAMPLINC Particulate and iodine samples are obtained from the continuoos sample stream pulled from the plant stack. Samples typically are obtained to represent the integrated release from the stack.
Camma analytical results for particulate and halogen filters are combined for determination of total activity of particulate 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 "identi-fied" beta, and the " identified" count rate is subtracted from the observed count rate to give " unidentified" beta. The " unidentified" beta is assumed to be Sr-90 until results on actual Sr-90 (chemically separated from a quarterly composite of filters) are obtained.
Similarly, alpha activity not identified as natural radium or thorium or their daughters is assumed as Pu-239 until results of detailed analyses are obtained from quarterly composites.
Le
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ti ,;V6LUME 25 BIC ROCK POINT RADIOLOGICAL Revision 4 I
- EFFLUENT T/S REQUIRED DOCUMENTS Page 21 of 79 A. - OFFSITE DOSE CALCULATIONS I.C NOBLE CAS SAMPLING Condenser air ejector off gas will be sampled at least weekly and used to calculate monthly noble gas releases. 'Nonroutine releases will' be quantified from the stack noble gas monitor (RE 8283) which has'an LLD of IE-06 pCi/cc.
I.H TRITIUM SAMPLING E. Tritium has a: low dose consequence to the public because of low production rates. . The major contributors to tritium effluents are evaporation from the fuel pool and reactor cavity (when flooded).
Because of the low dose impact, gaseous tritium sampling will not be required. Tritium effluents will.be estimated using conservative evaporation rate calculations from the fuel pool and reactor cavity. .
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Table 1.1 i BIG ROCK' POINT CASEOUS AND LIQUID SOURCE TERMS, CURIES / YEAR III
~
Nuclide Caseous (2) Liquid (2) j H-3 1.21E+01- 8.63E+00 i
N-13 1.53E+03 NA Na-24 3.5 2E-04 1.12E-06 l -
Cr-51 2.82E-04 '6.84E-03 l Ma-54 5.50E-05 .2.60E-02 i Ma-56 1.70E-04 NA L
Co-58 1.65E-06 6.17E-04 Fe-59 2.81E-06 9.05E-03 Co-60 1.89E-04 4.21E-02 2n-65' 3.16E-05 9.01E-04 Br-82 8.11E-03 NA Kr-83m 2.61E+02 NA Kr-85 9.55E-01 NA Kr-85m 3.12E+02 NA Kr-87 1.19E+03 NA Kr-88 7.80E+02 NA Kr-89 6.96E+02 NA Sr-89 NA 2.27E-04 Kr-90 7.76E+02 NA Sr-90 NA 2.22E-03 Kr-91 6.68E+00 NA Sr-91 5.61E-03 NA Sr-92 NA 1.54E-06 Nb-95 1.91E-06 NA Mo-99 3.10E-05 NA Ag-110m 1.57E-05 6.88E-05 Sb-124 .NA 4.01E-04 I-131 1.9CE-03 1.57E-04 Xe-133m 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-133m 6.00E+00 NA Cs-134 4.04E-07 1.75E-02 I-134 1.24E-02 NA I-135 3.00E-02 NA Xe-135 1.11E+03 NA Xe-135m 1.15E+03 NA Cs-136 4.74E-05 NA C -137 1.51E-04 2.04E-01 Xe-137 1.11E+03 NA Cs-138 3.17E-01 NA Xe-138 6.03E+03. NA Ba-139 1.32E-03 NA Xe-139 1.04E+03 NA Ba-140 1.86E-03 NA La-140 7.8CE-03 5.04E-05 Xe-140 7.23E+01 NA Hg-203 1.32E-06 NA Np-239 1.44E-04 NA Unidentified beta 2.42E-03 6.76E-02 (1) Data derived from taking the effluents released during Jan-June 1980-through July-December 1983 and dividine by 4.
(2) Nuclide values listed as NA have not been observed at detectable levels __
in these waste streams. . .
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BASIC RADIONUCLIDES DATA NUCLIDE RALT-LIFE LAMBDA BETA I
CAMMA (days) (1/s) (MEV/ DIS) (KEV / DIS) l 1 Tritium 4.49E 03 1.79E-09 5.68E-03 0.0 2 C-14 2.09E 06 3.84E-12 4.95E-02 0.0 3 N-13 6.94E-03 1.16E-03 4.91E-01 1.02E 00 4 ;0-19 3.36E-04 2.39E-02 , 1.02E 00 1.05E 00 5 F-18 7.62E-02 1.05 E-04 2.50E-01 1.02E 00 6 NA-24 6.33E-01 1.27E-05 5.55E-01 4.12E 00 7' P-32 .
. 1.43E 01 5.61E-07 6.95E-01 0.0 8 AR-41 7.63E-02 1.05E-04 4.64E-01 1.28E 00 9 CR-51 2.78E 01 2.89E-07 3.86E-03 3.28E-02 10 MN-54 3.03E 02 2.65E-08 3.80E-03 8.36E-01 11 MN-56 1.07E-01 7.50E-05 8.29E-01 1.69E 00 12 FE-59 4.50E 01 1.78E-07 1.18E-01 1.19E 00 13 CO-58 7.13E 01 1.12E-07 3.41E-02 9.78E-01 14 CD-60 1.92E 03 4.18E-09 9.68E-02 2.50E 00 15 ZN-69m 5.75E-01 1.39E-05 2.21E-2** 4.16E-01 16 ZN-69 3.96E-02 2.03E-04 3.19E-01 0.0 17 BR-84 2.21E-02 3.63E-04 1.28E 00 1.77E 00 18 BR-85 2.08E-03 3.86E-03 6.60E-02 1.04E 00 ~
19 KR-85m 1.83E-01 4.38E-05 2.53E-01 1.59E-01 20 KR-85 -
3.93E 03- 2.04E-09 2.51E-01 2.21E-03 KR-87 21 .
5.28E-02 1.52E-04 1.32E 00~ 7.93E-01 22 KR-88 1.17E-01 6.86E-05 3.61E-01 1.96E 00 13 . KR-89 2.21E-03 3.63E-03 1.36E 00 1.83E C0 24 RB-88 1.24E-02 6.47E-04 2.06E 00 6.26E-01 25 RB-89 1.07E-02 7.50E-04 1.01E 00 2.0$E 00 26 SR-89 5.20E 01 1.54E-07 5.8?E-01 8.45E-05 27 SR-90 1.03E 04 7.79E-10 1.96E-01 0.0 28 SR-91 4.03E-01 1.99E-05 6.50E-01 6.95E-01 29 SR-92 1.13E-01 7.10E-05 1.95E-01 1.34E 00 30 SR-93 5.56E-03 1.44E-03 9.20E-01 2.24E 00 31 Y-90 2.67E 00 3.00E-06 9.36E-01 0.0 32 Y-91m 3.47E-02 2.31E-04 2.73E-02 5.30E-01 33 Y-91 5.88E 01 1.36E-07 6.06E-01 3.61E-03 34 Y-92 1.47E-01 5.46E-05 1.44E 00 2.50E-01 35 Y-93 4.29E-01 1.87E-05 1.17E 00 8.94E-02 36 ZR-95 6.50E 01 1.23E-07 1.16E-01 7.35E-01 37 NB-95m 3.75E 00 2.14E-06 1.81E-OL 6.06E-02 38 NB-95 3.50E 01 2.29E-07 4.44E-02 7.64E-01 39 MO-99 2.79E 00 2.87E-06 3.96E-01 1.50E-01 40 TC-99m 2.50E-01 3.21E-05 1.56E-02 1.26E-01 41 TC-99 7.74E 07 1.04E-13 8.46E-02 0.0 42 TC-104 1.25E-02 6.42E-04 1.60E 00 1.95E 00 OD0589-1333A-BA01
4: e
- VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 4
. EFFLUENT T/S'REQUIPED DOCUMENTS Page 24 of 79 A. OFFSITE DOSE CALCULATIONS Table 1.2 BASIC RADIONUCLIDES DATA NUCLIDE HALF-LIFE LAMEDA l BETA CAMMA (days) (1/s) (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 I-129 6.21E 09 1.29E-15 5.43E-02 2.46E-02 46 I-131 8.05E 00 9. 96 E-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 XE-131m 1.18E 01 6.80E-07 1.43E-01 2.01E-02 52 XE-133m. 2.26E 00 3.55E-06 1.90E-01 4.15E-02 53 XE-133 5.27E 00 1.52E-06 1.35E-01 4.60E-02 54 XE-135m 1.08E-02 7.43E-04 9.58E-02 4.32E-01 55 XE-135- 3.83E-01 2.09E-05 3.17E-01 2.47E-01 56 XE-137 2.71E-03 2.96E-03 1.77E 00 1. 88E-01 57 XE-138 9.84E-03 8.15E-04 6.65E-01 1.10E 00 58 CS-134 7.48E 02 1.07E-08 1.63E-01 1.55E 00 59 CS-135 1.10E 09 7. 2.9 E- 15 5,63E-02 0.0 60 CS-136 l'.30E 01 ,6.17E-07 1.37E-01 . 2.15E 00 61 CS-137 .l.10E 04 - 7.29E-10 1.71E-01 5.97E-01 62' CS-138 2.24E-02 3.58E-04 1.20E 00 2. 36E 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-08 9.13E-02 1. 93E-02
- 67. PR-143 1.36E 01 5.90E-07 3.14E-01 , 0.0 68 PR-144 1.20E-02 6.68E-04 1.21E 00 3.18E 02 Average energy per disintegration values were obtained from ICRP Publication No 38, Radionuclides Transformations : Energy and Intensity of Emissions, 1983 and NUREG/CR-1413 (ORNL/NUREG-70), A Radionuclides Decay Data Base -
Index and Summary Table, D. C. Kocher, May 1980.
OD0589-1333A-BA01
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' VOLUME.25 BIC ROCK POINT RADIOLOGICAL
- Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 33 of 79 A. OFFSITE DOSE CALCULATIONS BIC ROCK POINT LAND USE CENSUS REPORT Table 1.4 Distance to the nearest residence, garden, milk cow, beef cow and goat in each-sector.
' Sector Residence Carden Dairy Cow- Beef Cattle Coat WSW 2.5 mi' >5 mi >5 mi >5 mi >$ mi SW 1.1 mi >5 mi >5 mi >5 mi >5 mi SSW 1.3 mi 2.1 mi >5 mi >5 mi >5 mi' S 1.9 mi >5 mi >5 mi 2.5 mi >5 mi.
SSE 1.7 mi 1.8 mi 3.5 mi 3.5 mi 3.25 mi SE 1.7 mi >5 mi 4.5 mi 2.0 mi >$ mi ESE 1.5 mi 2.4 mi 2.6 mi 2.6 mi >5 mi E 1.4 mi 2.5 mi 2.5 mi 2.5 mi >$ mi ENE 2.3 mi >5 mi >5 mi >5 mi >5 mi OD0589-1333A-BA01
y0LUME 25 BIG ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS: 'Page 34 of 79 A. OFFSITE DOSE CALCULATIONS
~1989 BIC ROCK POINT CASPAR INPUT PARAMETERS Table 1.4a Critical Receptors X/Q X/Q Decay Distance X/Q Decay D/Q Location Sector (miles) (sec/m8 ) (sec/m*) andDef)
(sec/m (1/m*)
Residence /Carden E' 1.4 5.00E-08 5.00E-08 4.90E-08 6.60E-10 Site Boundary E 0.57 4.20E-08 4.20E-08 4.20E-08 1.30E-09 Beef Cattle. E 2.5 3.60E-08 3.60E-08 3.50E-08 3.40E-10 Dairy Cow- E 2.5 3.60E-08 3.60E-08 3.50E-08 3.40E-10 Coat SSE 3.25 2.40E-08 2.40E-08 2.40E-08 1.00E-10 OD0589-1333A-BA01
_ .: - . _ _ . _ _ _ __. _ i
.j +-
' VOLUME 251 BIG ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 35 of 79 L A. OFFSITE DOSE CALCULATIONS l
DOSE FACTORS FOR SUBMERSION IN N0 ELE CASES
- Table 1.5 8
DFBI __ DFY DPS I
DFB 8 Kr-85m 1.17(+3)8 1.23(+3) 1.46(+3) 1.97(+3)
Kr-85 1.61(+1) 1.72(+1) 1.34(+3) 1.95(+3)
Kr 5.92(+3) 6.17(+3) 9.73(+3) 1.03(+4)
Kr-88 1.47(+4) 1.52(+4) 2.37(+3) 2.93(+3)
Kr-89 1.66(+4)- 1.73(+4) 1.01(+4) 1.06(+4)
Ke-131m 9.15(+1) 1.56(+2) 4.76(+2) 1.11(+3)
Xe-133m 2.51(+2) 3.27(+2) 9.94(+2) 1.48(+3)-
Xe-133 2.94(+2) 3.53(+2) 3.06(+2) 1.05(+3)
Xe-135m 3.12(+3) 3.36(+3) 7.11(+2) 7.39(+3)
Xe-135 1.81(+3) 1.92(+3) 1.86(+3) 2.46(+3)
Xe-137 1.42(+3) 1.51(+3) 1.22(+4) 1.27(+4)
Xe-138 8.83(+3) 9.21(+3) 4.13(+3) 4.75(+3)
Ar-41 8.84(+3) 9.30(+3) 2.69(+3) 3.28(+3)
- 1. mrem /y per pCi/m 8
- 2. mrad /y per pCi/m 8
- 3. 1.17(+3) = 1.17 x 108 CDose factors for exposure to a semi-infinite cloud of noble gases. Values were obtair.ed from US NRC Regulatory Guide 1-109, Revision 1 (October 1977).
i CD0589-1333A-BI.01
'VOEU E.25 BIC ROCK POINT RAD 10 LOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 36 of 79 A. OFFSITE DOSE CALCULATIONS
. STABLE ELEMENT TRANSFER DATA Table 1.6 F2 - Milk (d/L) Fm - Milk (d/L) Biv Element (Cow) (Coat) Ff - Meat (d/kg) Veg/ Soil l H 1.0E-02 1.7E-01 1.2E-02 4.8E-00 C 1.2E-02 1.0E-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-O' 1.1E-00 Cr 2.2E-03 2.2E-03 2.4E-03 2.5E-04 Mn 2.5E-04 2.5E-04 8.0E-04 2.9E-02 Fe 1.2E-03 1.3E-04 4.0E-02 6.6E-04 Co 1.0E-03 1.0E-03 1.3E-02 9.4E-03 Ni 6.7E-03 6.7E-03 5.3E-02 1.9E-02 Cu 1.4E-02 1.3E-02 8.0E-03 1.2E-01 Zn 3.9E-02 3.9E-02 E.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 4.6 E-03 2.6E-03 Zr 3 0E-06
. 5.0E-06 3.4E-02 1.7E-04 Nb 2.5E-03 2.5E-03 2.8E-01 9.4E-03 Mo 7.5E-03 7.5E-03 8.0E-03 1.2E-01 Tc 2.5E-02 2.5E-02 4.0E-01 2.5E-01 Ru le0E-06 1.0E-06 4.00-01 5.0E-02 Rh 1.0E-02 1.0E-02 1.*E-03 1.3E+01 Ag 5.0E-02 5.0E-02 1.7E-02 1.5E-01 Te 1.0E-03 1.0E-03 7.7E-02 1.3E-00 I 6.0E-03 6.0E-02 2.9E-03 2.0E-02 Cs 1.2E-02 3.0E-01 4.0E-03 1.0E-02 Ba 4.0E-04 4.0E-04 3.2E-03 5.0E-03 La 5.0E-06 5.0E-06 2.0E-04 2.5E-03 Ce 1.0E-04 1.0E-04 1.2E-03 2.5E-03 Pr 5.0E-06 5.0E-06 4.7E-03 2.5 E- 03 Nd 5.0E-06 5.0E-06 3.3E-03 2.4E-03 W 5.0E-04 5.0E-04 1.3E-03 1.8E-02 Np 5.0E-06 5.0E-06 2.0E-04 2.5E-03 OD0589-1333A-BA01
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' Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 37 of 79 A. OFFSITE DOSE CALCULATIONS Table 1 7 INKALATION JOSE FACTOR $ FOR INTANT (MREM PER PCI INHALED)
Nect!DE BONE LIVER T.50DY THYRotD KIDNEY LUNC CI-LLI l N 3 NO DATA 4.62E-07 4.62E-07 6.62E-07 6.62E-07 4.62E-07 i
4.62E*07 C 14 1.89E*05- 3.79E-06 3.79E-06 3.79E*06 3. 79E-M 3.79E 06 3.79E-06 f!A 24 7.54E-06 7.54E-06 7. 5&E-M 7.5&E-06 7.5&E-06 7.5&E-06 1
j 7.5&E 06 F 32 1.65E-03 '8.03E-05 5.5?E-05 NO DCA NO DATA NO DATA
' 1.15E-05 CR 51 NO DATA NO DATA 6.39E-08 4.11E 06 9.45E-09 9.17E.M 2.55E-07 HN 56 NO DATA 1.81E-05 3.56E-06 NO DATA 3.56E-06 7.1&E-M 5.0&E 06 NN $6 NO DATA 1.10E-09 1.58E-10 NO DATA 7.86E-10 8.95E-06 5.12E 05 FE 55 1.61E-05 8.39E-06 2.38E 06 NO DATA NO DATA 6.21E-05 7.82E-07 FE 59 9. 69E-M 1.68E-05 6.77E-06 NO DATA NO DAH 7. 25E-M 1.77E-05 CO 58 NO DATA 8.71E-07 1.30E-06 NO DATA 5. 55E-M NO DATA 7.?5I M CO 60 NO DATA 5.73E-06 8.61E-06 NO DATA NO DAH 3.22E-03 2.2BE 03 NI 63 2.42E-% 1 &6E-05 8.29E-06 NO DATA NO DATA 1.49E-% 1.73E M N'I 65 1.711-09 2.03E-10 8.79E-11 NO DATA NO DATA 5.80E-06 3.58E-05 CU 64 NO DATA 1.3&Ey09 5.53E 10 NO DATA 2.84E-09 6.64E-06 ~ 1.,07E 05 ZN 65 1.3EE 05 4.67E-05 2.22E-05 NO DATA 2.32E-05 4. 62E-M 3.67E-05
..............a..................................*..................................::............
IN 69 3.85E 11 6.91E-11 5.13E-12 NO DATA 2.87E-11 1.05E-06 9.6&E-06 BR 83 NO DATA NO DATA 2.72E*07 NO DATA NO DATA NO DATA LT E-26 BR 86 NO DATA NO DATA 2.86E-07 NO DATA NO DATA NO DATA LT E.26 BR 85 NO DATA NO DATA 1.&6E-08 NO DATA NO DATA NO DMA LT E 24 RB 86 NO DAIA 1.36E-M 6.30E-05 NODCA NO DATA NO DATA 2.17E-M RB 88 NO DATA 3.98E-07 2.05E 07 NO DATA NO DATA NO DATA 2.42E-07 RS 89 NO DATA 2.29E-07 1.&7E 07 NO DATA NO DATA NO DATA 4.8*E.08 SR 89 2.8&E-% NC DATA 8.15E-06 NO DGA NO DATA 1.65E 03 6.57E-05 SR 90 2.92E-02 NO DATA !
1.85E-03 NO DATA NO DATA 8.03E-03 9.36E-05 SR 91 6.83E 08 NO DATA 2.67E-09 NO DAIA NODMA 3.76E 05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E 10 NO DATA NODCA 1.70E-05 1.00E-%
Y 90 2.35E-06 NO DATA 6.30E-08 NO DMA NO DATA 1. 92E.% 7.&3E.0
.................................................................................................5 Y 91m 2.91E-10 NO DATA 9.90E.12 NO DATA NO DATA 1.99E-06 1.68E-06 i Y 91 A.20E-% NO DATA 1.12E 05 NO DAIA NO DATA i 1.75E-03 5.02E-05 Y 92 1.17E-08 NO DATA 3.29E 10 NO DATA NO DATA 1.75E-05 9
........................................................................................... 0&E-05 ......
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INHA1ATIow Dost rActoRs PoiTiriftr-- ~
(MREM PER PCI INHALED)
NUCL7DE BONE 1.IVER T. BODY TNYROID KIDNEY LUNC CI LLI Y 93 1.07E-07 NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-%
21 95
- 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E 05 IR 97 1.07E-07 1.83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1.00E-M El 95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 No 99 No DATA -1.18E-07 2.31E-08 No DATJ. 1.89E-07 9.63E-05 3.48E-05 TC 99s .9.98E-13 2.06E-12 2.66E 11 .NO DATA 2.22E-11 5.79E-07 1.45E-06 TC101 4.65E-14 5.88E-14 5.80E 13 NO DATA 6.99E-13 4.17E-07 6.03E-07 RU103 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-26 3.94E-% 1.15E-05 R1*105 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E 10 1.12E-05 3.46E-05 RU106 6.2CE-05 NO DATA 7.77E-06 . NO DATA 7.61E-05 8.26E-03 1.17E-M AC110m 7.13E-06 5.16E-06 3.57E-05 NO DATA 7.80E-06 2.62E-03 2.36E 05 TE125e 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No DATA 3.19E-04 9.22E-06
- TE127m 1.19E-05 4.935-06 1.48E-06 3.48E 06 2.68E-05 9.37E-M 1.95E-05 1I127- 1.59E*09 6.81E-10 3.49E 10 h32E-09 3.47E-09 7.39E 06 1.74E-05' TE129m 1.01E-05 4.35E-06 1.59E 06 3.91E-06 2.27E-05 1.20E 03 ,4.93E-05 TE129 5.63T-11 2.48E-11 1. 34E-11 4.82E-11. 1.25E-10 2.1cE-06 '
~
1.88E-05 TE131m f.62E-08 3.93E-08 2.59E 08 6.38E-08 1.89E-07 1.42E-% 8.51E-05 TE131 1.24E-11 5.87E-12 3.57E 12 1.13E 11 2.85E-11 1.47E-06 5.87E-06 TE132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-M 3.15E-05
! 130 4.54E-06 9.911-06 3.98E-06 1.14E-03 1.09E-05
{
NO DATA 1.42E-06 I 131 2.71I-05 3.17E-05 1.40E-05 1.06'-02 3.70E-05 No DATA 7.56E-07 I 132 1.21I-06 2.53E-06 8.99E-07 1.21T.-04 2.82E-06 NO DATA 1.36E-06 I 133 9.46E-06 1.37E-05 4.00E-06 2.541 03 1.60E-05 NO DATA 1.54E-06 1 134 6.58E-07 1.54E-06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21E 07 I 135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 NO DATA 1.31E-06 2.83E-%
C5134 5.02E-% 5.12E-05 NO DATA 1.36E* % 5.69E-05 9.53E-07 C5136 3.45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 CS137 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E* % 5.09E-05 9.53E-07 CS138 3.61E-07 5.58E-07 2.84E-07 NO DATA 2.93E-07 4.67E-08 6.26E-07 BA139 1.06E-09 7.03E-13 3.07E-11 NO DATA 4.23E-13 4.25E-06 3.64E-05
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__ _ _ , . . . . - . . . _ _ _ . . . _ . _ . ~ . - -
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. IffRA1AT10W DOSE FACIVR$ FOR INTANT ~
!MPIM PER PCI INKA1.ED) kt1CLIDE SONE 1,IVER T.80DY THYROID KIDNEY [fMC Cf.LLI .
l 8A140 4.00E-05 4.00E.00 2.07E-06 NC DATA 9.59E-09 1.1&E 03
! 2.7&E.05 8A141 1.12I+10 7.70E.14 3.55E.12 No DATA 4.6&E.14 2.12E.06 3.39E-06 f.A142 2.8&E-11 2.36E.14 1.&oE 12 No DATA 1.36E 14 1.11E 06 4.95E 07 1.A1&D 3.61E 07 1.43E.07 3.68E-06 No DATA NO DATA 1.20E-04 6.06E 05 1.A162 7.36E.10 2.69E-10 6.46E-11 NO DATA NO DATA 5.87E-06
- 6.25E-05 C5141 1.98E 05 1.19E-05 1.62E-06 NO DAIA 3.75E-06 3.69E.M 1.5&E-05 CEl&3 2.09E-07 1.38E-07 1.58E-08 NO DATA 4.03E-08 8.30E.05 3.55E-05 CEl&& 2.26E-03 8.65E-% 1.26E.04 NO DATA 3.8&E M 7.03E 03 1.06E-%
PA143 1.00E-05 3.74E-06 6.99E-07 HO DATA. 1.41I-06 3.09E.04 2.66E-05 PR144 3.&2E.11 1.32E.11 1.72E-12 NO DATA 4.80E*12 1.15E.06 3.06E-06 ND147 . 5.67E-06. 5.s1E-06 3.57E-07 No DATA 2.25E-06 2.30E-M 2.23E 05 V 187 9.26E-09 6.&&E-09 2.23E-09 No DATA NO DAIA 2.83E-05 2.5&E 05 NP239 2.65E-07 2.37E.08 1.3&E-08 NO DATA 4.73E-08 4.25E 05
, 1.78E-05
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VOLURE 25 BIG ROCK POINT RADIOLOGICAL Revision 4
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ITRALATION DOSE FACTORS FOR CHILD (HRIM PER PCI INRALED)
NDC1IDE BONE LIVER T. BODY INYROID KIDNEY LUNC CI LLI E 3 NO DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E 07 3.04E-07 C 14 9.70E-06 1.82E-06 1.82E-06 ^
1.82E-06 1.82E-06 1.82E-06 1.82E-06 NA 24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E 4.35E-06 F 32 7.04E-04 3.09E-05 2.67E-05 NO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA *NO DATA 4.17E-08 2.31E-08 6.57E-09 4.59E 06 2.93E-07 MN 54 NO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19E-06
................................................................................. 4...............
NN 56 NO DAIA 4.48E-10 8.43E-11 NO DATA 4.52E-10 3.55E-06 3.33E-05 FE 55 1.28E-05 6.80E 06 2.10E-06 No DATA NO DATA 3.00E-05 7.75E-07 TE $9 5.59E-06 9.04E-06 4.51I-06 NO DATA NO DATA 3.43E-04 1.91E-05 CO $8 NO DATA 4.79E 07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 03 60 NO DATA 3.55E-06 6.12E-06 No DATA NO DATA 1.61E-03 2.60E-05' NI 63 2.22E-04 1.25E-05 7.56E-06 No DATA NO DATA 7.43E-05 1.71E-06' NI 65 8.08E.10 7.99E.11 4.44E-11' NO DATA NO DATA 2.21E-06 2.27E-05
.CU W NO DATA 5.39E 10' 2.90E-10 NO DATA 1.63E-09 2.59E-06 9.92E-06 ZN 65 1.15E-05 3.06E-05 ,
1.90E-05 NO DATA. 1.93E-05 2.69E-04 4.41E-06 ZN 69 1.81E-11 2.61E-11 2.41E*12 NO DATA 1.58E-11 3.84E-07 2.75E-06 BR 8 3 ' ~ NO DATA NO DATA - 1.28E-07 NO DATA NO DATA NO DATA LT E-14 SR 84 NO DATA NO DATA 1.48E-07 NO DATA NO DATA NO DATA LT E ..................................................................................................!
BR 85 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LT E.24 -
RB 86 NO DATA 5.36E-05 3.09E-05 NO DATA NO DATA NO DATA 2.16E-06' RB 88 NO DATA 1.52E*07 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 RB 89 No DATA 9.33E-08 7.85E-08 NO DATA NO DATA NO DATA 5.11Z-10 SR 89 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.52E-05 SR 90 2.73E-02 N0' DATA 1.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 SR 91 3.28E-00 NO DATA 1.24E-09 NO DATA NO DATA 1.44E-05 4.70E-05l SR 92 3.54E-09 NO DATA 1.42E-10 NO DATA NO DATA 6.49E-06 6.55E-05 t Y 90 1.11E-06 NO DATA 2.99E-08 NO DATA NO DATA 7.07E-05 7.24E-05
.................................................................................................g g
Y 91m 1.37E-10 NO DATA 4.98E-12 NO DATA NO DATA 7.60E-07 4.64E-07+
Y 91 2.47E-04 NO DATA 6.59E-06 NO DATA NO DATA 7.10E-04 4.97E-05; Y 92 5.50E.09 NO DATA 1.57E-10 NO DATA NO DATA 6.46E-06 6.46E-05' 1
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A. OFFSITE DOSE CALCULATIONS Table 1.7 I
I,NMALATION DOSE TACTORS FOR CHIIS (MREM PER PCI INRALED)
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNC CI.LLI
.Y 93 5.%E 06 NO DATA 1.38E-09 NO DATA NO DATA 2.01E-05 1.05E-04 IR 95 5.13E-05 1.13E-05 1.00E-05 No DATA 1.61E-05 6.03E-% 1.65E-05 IR 97 5.07E-08 7.3&E-09 4.32E-09 HO DATA , 1.05E-08 3.06E-05 9.49E-05 NB 95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-M 1.00E-05 MO 99 NO DATA .4.66E-08 1.15E-08 NO DATA 1.06E-07 3.66E-05 3.42E-03 TC 99a 4.81E-13 9.41E-13 1.56E-11 NO DATA 1.37E-11 2.57E-07 1.30E-06 TC101 2.19E-14 2.30E-14 2.91E-13 NO DATA 3.92E-13 1.taE-07 4.41E-09 RU103 7.55E-07 No DATA 2.90E-07 NO DAIA 1.90E-06 1.79P 04 1.21E-05 RU105 4.13E-10 NO DATA 1.50E 10 NO DATA 3.63E-10 4.30E-06 2.69E 05 RU106 3.68E-05 NO DATA 4.57E-06 No DATA 4.97E-05 3.87E 03 1.16E-04 AC110m 6.5C-06 3.08E-06 2.47E-06 No DATA 5.7&E-06 1.48E-03 2.71I 05 II125m 1.82E-06 6.29E-07 2.47E-07 5.20E 07 NO DATA 1.29E-04 9.13E 06 TE127m 6.72E 06 2.31I-06 8.16E-07 1.6&E-06 1.72E-05 4.00E-04 1.93E ~05 TI127 7.49E-10
~
2.57E-10 1.63E-10 5.30E 10 1.91E-09 2.}1E-06 1.52E-05 TE129e 5.19E T.85E-06 8.22E-07 1.71E-06 *1.36E.05 4. 76E-M 4.91E 05
.........,.....................~...................................................;...............
TE129 2.6&E-11 9.45E-12 6.&&E-12 1.93E 11 6.9&E-11 7.93E-07 6.39E 06 2f131m . 3.63E-08 1.60E-08 1.37E-06 2.6&E 08 1.08E-07 5.56E-05 8.32E 05 TI131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 TE132 1.30E-07 7.36E-08 7.12E-08 8.58E 08 4.79E-07 1.02E-M 3.72E-05 1 130 2.217 06 4.43E-06 2.2BE-06 4.99E-% 6.61E-06 NO DATA 1.38E 06 1 131 1.30E-03 1.30E-05 7. 37E-M 4.39E-03 2.13E-05 NO DATA 7.68E-07 I 132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07 I 133 4.48E-06 5.49E-06 2.08E-06 1.0&E-03 9.13E*06 NO DATA 1.68E-06 I 134 3.17E-07 5.6&E-07 2.69E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 I 135 1.33E-06 2.36E-06 1.12E-06 2.1&E-M 3.62E-06 NO DATA 1.2CE-06 CS134 1.76E-04 2.7&E-M 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.0&E-06 CS136 1.76E-05 4.62E-05 3.1&E-05 NO DATA 2.58E-05 3.93E-06 1.13E 06 CS137 2.45E-04 2.23E-M 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 C5138 1.71E-07 2.27E-07 1.50E-07 NO DAIA 1.68E-07 1.8&E-08 7.29E.-08 BA139 4.98E-10 2.66E-13 1.45E-11 NO DATA 2.33E-13 1.56E-M 1.56E-05 CD0589-1333A-BA01
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- Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Pa;.a 42 of 79 A. OFFSITE DOSE CALCULATIONS Table 1.7
~' ~~~ _
' INHALATION DOSE FAC2DR$ CHILD '
(MREM PEll PCI INHALED)
NLTLIDE BONE LIVER T. BODY 2WYROID KIDNEY LUNC CI-LLI SA140 2.00E 05 1.75E-08 1.17E 06 NO DATA 5.71E-09 4.71E-04 l
SA141 5.29E*11 2.95E-14 1.75E-05 !
1.72E 12 NO DATA 2.56K-14 7.89E-07 BA162 1.35E 11 7 LLE-08 9.73E-15 7.54E*13 NO DATA 7.87E-1 4.44E-07 7.41E-10
...................................................................... 5...........................
LA140 1.74'E-07 E. 08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 1A142 3.50E-10 , 1.11E-10 6.10E-05 3.49E 11 NO DATA NO DATA 2.35E-06 CE161 1.06E-05 '5.28E-06 2.05E 05 7.83E-07 NO DATA 2.31E 1.53E-05
.............................................................................1.47E-04 CElk) ....................
9.89E-08 5.37E-08 7.77E-09 NO DATA 2.26E 06 3.12E-05 3.4&E-05 CE2&& - 1.83E-03 5.72E-M 9.77E-05 NO DATA 3.17E-% 3.23E-03 1.0$E-%
PR143 4. 99E-M 1.50E-06 2.67E-07 NO DATA 8.11E-07 2.63E-05
.............................................................................1.17E-04 PR144 1.61E-11 4.99E-12 8.10E-13 NO DATA 2.64E-12 4.23E-07 5.32E-08 ND147 2.92E-06 2.36E-06 1.84E-07 NO DATA 1.30E 06 8.87E-05 2.21E-05 s 187 a.41E-09 2.61E-09 1.17E-09 NO DAIA NO DATA 2.46E-05
............................................................................ 1.11E-05 .....................
NP239 1.26E-07 9.04E-09 ,_ 6.35E-09 NO DATA 2.63E-08 1.57E-05 1.73E-05 1
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VOLUME 25 BIC ROCK POINT RADIOLOGICAL
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Par,e 43 of 79 A. OFFSITE DOSE CALCULATIONS Table 1.7
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1NHALAft0N DOSE F ACTORS FCP fEENAGER tuREM PER PCI INHALE 08 NUCLICE- L!vCR T.00CY Ct-LLI BONE THYRDID KIDNEY LUNG H 3 NO DATA 1.59E-07 1. 5 9E -0 7 1.59E-07 1.59f-07 1.59E-07 1.59E-07 C 14 3.2SE-06 6.C9E-07 6. 09E-0 7 6.09E-07 6.09E-07 6.09E-07 6.09E-07 14 24 1.72E-06 3 72E-06 1. 72 E-0 6 1.72E-06 1.72E-06 1.72E-06 1.72E-06 7 32 2.36E-04 1.lFC 8.95E-0 6 NO DATA NC DATA NO DATA 1.16F-05 CR 31 NO DATA NO DATA 1.69F-08 9.37E-09 3.942-o9 2.62E-06 3.75E-07 rN 54 NO CATA 6.39F-06 1. 03E-0 6 40 DATA 1.59E-06 2.48E-04 8.35E-06 WN 56 NO DATA 2.12d-10 3.15E-11 NO DATA 2.246-10 1.90E-C6 7 18E-06 FE 55 4 18E-06 2.98E-06 6.93E-0 7 NO DATA NO DATA 1.55E-05 7.99E-07 FE 57 1.79E-06 4.622-06 1. 7 9 E-0 6 NO DATA NO DATA 1.91E.04 2.23E-05 C0 SE 40 DATA 2.39E-07 3.4 7E-0 7 NO JATA NO DATA 1.68E-04 1.19E-05 CD 40 NO CATA 1 81E-06 2. 48 E-0 6 NO DATA NG CATA 1.09E-03 3.24E-05 NI 6s 7.25E-05 5.*3E-06 2 47E-06 *;o Daft No CATA 3.84E-05 1.77E-06 41 6b 2.73E-10 3.o6E-11 1. 59 E-1 1 NO DATA NO DATA 1.17E-06 4.59E-06 CU 64 NO DATA 2.546-10 1.06E-10 NO DATA 8.01E-10 1.39E-06 7.68E-06 IN 65 4.82E-06 1.07E-05 7. 80 E-0 6 NO DATA 1.08E-Ob 1.55E-04 5.83E-06 IN 69 6.04E-12 1.15F-11 8.07E-13 NO DATA 7.53E-l? 1.98E-07 1.560-08 np 83 NO DATA NO DATA 4.30E-08 '40 DATA NO LATA NO DATA LT E-24 DR 84 NO DATA' NO DATA 5. 41 E-0 8 NO DATA NC DATA NO DATA LT E-24 4R 85 NO DATA NO DATA 2.29E-09 NO DATA NO DATA NO DATA LT E-24 18 86 NO DATA 2 38E-05 1.05E-05 NO DATA NO DATA NO DATA 2.21E-06 R$ 88 NO DATA 6.82E-08 3. 40 E -0 8 No DATA NO DATA No DATA 3.65E-15 RB 89 NO DATA 4.402 08 2. 91 E-0 8 NO DATA NO DATA NO DATA 4 22E-17 SR 89 5.43E-05 NO DATA 1.56E-06 NO CATA NC CATA 3.c2E.04 4.64E-05 54 90 1.35E-02 NO DATA 8. 3 5 E -0 4 NO DATA NO DATA 2.06E-03 9.56E-05 5A 91 1.10E-08 N0 CATA 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05 54 92 1 19E-09 NO CATA 5. 08 E-11 NO DATA NO DATA 3.43E-06 1.49E-05 Y 90 3.T3E=07 NO DATA 1. 00E -0 5 NO DATA NO DATA 3.66E-05 6.99E-05 l Y 91k 4.63E-11 40 DATA 1.77E-12 NO DATA NO DATA 4.00E-07 3.77E-09 I Y 91 8.26E-05 NO DATA 2.21E-06 NO DATA NO DATA 3.67E-04 5.11E-05 Y 92 1.84E-09 NO DATA 5.36E-11 NO DATA NO DATA 3.35E-D6 2.06E-05 l
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(=REW PL4 PCI INHALE 01 .
"40CL 10 E UCNE Liv?R T.AOCY THYR OI O KIONEY LUNG Cl-tLi y 93 1.69E-08 NO OtTA 4. 6 5 E-10 NO DATA' NO DATA 1.04E-05 7.24E-05 ZR 95 1.82E-05 5.73E-06 3. 94 E-0 6 N0 DATA 8.42E-06 3.36E-04 1.86E-05 2R 77 1.72E-08 3.40E-09 1. 5 7 E-0 4 NO DATA 5.15C-09 1.62E-05 7.88E-05 N8 95 2.32E-06 1 29E-06 7.08E-07 NO D' T A A 1.25E-06 9.39E-05 1.21E-05 MO 99 'd0 DATA 2.llE-08 4. 0 3 E -0 9 40 CATA 5.14E-08 1.92E-05 1.36E-05 1C 99P 1.73E-13 4. 8 3C-I l 6 24E-12 NO DATA 7.20E-12 1.44E-07 7.660-07 TC101 7.40E-15 1.0$E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 RU103 2.63E-07 NO CATA 1.12E-07 N0 DATA 9.29E-07 9.79E-05 1.36E-05 tut 05 1.40E-10 NO DATA 5.42E-11 NO DATA 1.76E-10 2.27E-06 1.13E-05 9U106 1.23E-05 NO DATA 1. 5 5 E-0 6 NO DATA 2.38E-05 2.01E-03 1.20E-04 4G110P 1.73E-06 1.64E-06 9.99E-07 NO DATA 3.13E-06 8.44E-04 3.41E-05 TE125M 6.10E-07 2.80E-07 8.34E-08 f . 7 5E-0 7 NO DATA 6.70E-05 9.38E-06 TEl27M 2.25E-06 1.02C-06 2.73E-07 5. 4 8 E-0 7 8.17E-06 2.07E-04 1.99E-05 IE127 2.51E-10 1.14F-10 5.52C-11 1. 7 7E- L C 9.10E-10 1.40E-06 1.0tE-05 TE129M 1.74E-06 8.23E-07 2. 81 E-0 7 5. 72 E-0 7 6.49E-06 2.47E-04 5.06E-05
.................................~......s...............................
TE129 8.87E-12 4.22E-12 2.20E-12 6.4RE-12 3.32E-11 4.12E-07 2.02E-07 IE131r 1.23E-08 7.51C-09 5.03E-09 9. 06E-0 9 5.49E-08 2.97E-05 7.76E-05 TE131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE132 4 50E-08 1.03E-08 2. 74 E-0 8 3.07E-06 2.44E-07 5.61E-05 5.79E-05 1 130 7.80E-07 2.24E-06 8.96E-0 7 1.86E-04 3.44E-06 NO DATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1. 8 3 E -0 3 1.05E-05 NO DATA 8 11F.07 1 132 1.99E-07 5.47E-07 1. 97 E4 7 1 89E-05 6.65E-07 NO DATA 1.59E-07 I 133 1.52E-06 2.36E-06 7. 78 E-0 7 3. 65 E- 04 4.49E-06 NO DATA 1.29E-06 8 134 1.11E-07 2.90E-07 1. 05 E-0 7 4 94E-06 4.5EE-07 ho DATA 2.55E-09 8 135' 4.62E-01 1.18 E- 06 4.36E-07 7. T6E-05 1.86E-06 40 DATA 8'.69E-07 C5134 6.28E-05 1.41E-04 6.86E-05 No DATA 4.69E-05 1.83E-05 1.22E-06 C5116 6.44E-06 2.42E-05 1. 7 t E-0 5 NO DATA 1.38E-05 2.22E-06 1 36E-06 C5137 8.3BE-05 1.06E-04 3. 89 E-0 5 NO DATA 3.80E-05 1.51E-05 1.06E-06 C5138 5.82E-08 1.07E-07 5 58E-0 8 NO Ca7A 8.28E-08 9 84E-09 3.38E-11 SA139 1.67E-10 1.18E-13 4.87E-12 NO DATA 1.11E-13 0 08E-07 8.06E-07 l
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' Table 1.7 INHALATION DUSE Facf0R1 FCR TEENAGER (MREM PER PCI INHALE 03 NUCL19E BONE LIVER T.3C0Y THYROID KIONEY LUNG' G1-LLI B4140 6.f14 E-06 8.38F-09 4.40E-37 NO DATA 2.85E-09 2.54E-04 2.86E-05 eA141 1.T8E-11 1.s2E-14 5.93E-13 NO DATA 1.23E-14 4.11E-07 9.33E-14 q
bA142 .4.62E-12 4.636-15 2.84E-13 NO DATA 3.921-15 2.39E-07 5.99E-20 LA141 5.99E-08 2.95E-08 7. 82 C-0 9 NO CATA NO DATA 2.6BE-05 6.09E-05 LA142 '1.20E-10 5.31E-11 1.32E-11 NO DATA NO DATA 1.27E-06 1.50E-06 CE141 3.55E 2.37C-06 2. 71 E-0 7 NO DATA 1.11E-06 7.67E-05 1.58E-05 CE143 3.32E-00 2.42E 2. 70E-0 9 NO DATA 1.08i-08 1.63E-05 3.19E-05 CE144 6.!!E 2.53E-04 3.2 8 E-0 5 No DATA 1.51E-04 1.67E-03 1.08E-04 P4143 1.67E-06 6.64E-07 8.28E-08 NO DATA- 3.86E-07 6.04E-05 2.67E-05 va144 5.37E-12 2.20E-12 2.72E-13 No DATA 1.26E-12 2.19E-07 2.94E-14 40147 9.83E-07 -1.07E-06 6.41E-08 NO DAT1 6.26E-07 4.65E-05 2.28E-05 W 187 1.50E-09 1.22E-09 4.29E-10 NO DATA No CATA 5.92E-06 2.21E-05 1F239 4.23E-08 3.99E-09 2. 21 E-0 9 NO DATA 1.25E-08 8.11E-06 1.65E-05 CD0589-1333A-BA01
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. EXTERNAL' DOSE FACTORS FOR STANDING ON CONTAMINATED CROUND Table 1.8 (mrem /hr'per pCi/m*)
Element Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50 E- 08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Hn 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 '
Cu-64 '1.50E-09 1.70E-09
.Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-C' 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.303-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99m 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-10f- 1.50E-09 1.80E-09 Ag-110m 1.80E-08 2.10E-08 Te-125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.00E-12 Te-127 1.00E-11 1.10E-11 CD0589-1333A-BA01
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EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED CROUND
.Tabl e '.1.8 (mrem /hr per pCi/m*)
Element Total Body Skin Te-129s 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06
.Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-68 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08' -
Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09
-.Ba-140 2.10E-09 2.40E-09 '
Be-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 :
La-140 1.50E-08 1.70E-08 -l '
La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 i Pr-143 0.0 0.0 .
Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 I
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-A. -0FFSITE DOSE CALCULATIONS 1989 BIC ROCK POINT CASEOUS DESICH Table 1.9 Objective Annual Quantities r
Design Objective Dose Factor Annual Quantity Nuclide Organ mrem /Ci (Ci)
Ar-41 Total Body 9.81E-06 5.10E+05 Kr-83m Skin 2.38E-08 6.30E+08 Kr Skin 2.15E-06 . ,98E+06 Kr-85m Total Body 1.30E-06 3.85E+06 Kr-87 Skin 2.30E-05 -6.52E+05 Kr-88 Total Body 1.63E-05 3.07E+05 Kr-89 Total Body 1.84E-05 2.72E+05 H-3 Total Body-C 6.15E-06 8.13E+05 C-14 Bone-C 5.37E-03 2.79E+03 Cr-51 CI Tract-A,T 3.43E-04 4.37E+04 Hn-54 CI Tract-T 3.55E-02 4.23E+02 '
Fe-55 Bone-C 3.01E-02 4.98:+02 Co-58 Total Body-C 7.37E-03 6.78E+02 Fe-59 Total Body-C 1.17E-02 4.27E+02 Co-60 Total Body-C 4.39E-02 1.14E+02 Zn-65 Total Eody-C 6.67E-02 7.50E+01 Sr-89 Bone-C 1.33E+00 1.13E401 Sr-90 Bone-C 5.45E+01 2.75E-01 Zr-95 CI Tract-A 4.12E-02 3.64E+02 Sb-124 CI Tract-T 1.13E-01 1.33E+02 I-131 Thyroid-I 3.02E+00 4.97E+00 Xe-131m Skin 9.47E-07 1.58E+07 Xe-133 Total Body 3.26E-07 1.53E+07 Xe-133m skin 1.98E-06 7.58E+06 Xe-135 Total Body 2.01E-06 2.49E+06 Xe-135m Total Body 3.46E-06 1.45E+06 !
Xe-137 Skin 2.12E-05 7.08E+05 Xe-138 Total Body 9.80E-06 5.10E+05
'I-133 Thyroid-I 2.80E-02 5.36E+02 Cs-134 Liver-C 1.01E+00 1.49E+01 Cs-136 Total Body-I 1.23E-02 4.07E+02 I
Cs-137 Bone-C 9.87E-01 1.52E+01 Ba-140 Bone-C 6.69E-03 2.24E+03 Ce-141 CI Tract-T 1.85E-02 8.11E+02 Ce-144 CI Tract-T 4.91E-01 3.05E+01 Mn-56 CI Tract-C 3.58E-08 4.19E+08 Co-57 CI Tract-T 1.24E-02 1.21E+03 Ni-65 CI Tract-C 1.60E-08 9.38E+08 Rb-88 Total Body-C 3.21E-33 1.56E+33 Nb-95 CI Tract-A 3.66E-02 4.10E+02 Mo-99 Kidney-I 1.81E-03 8.29E+03 1
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L LVOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 4 J a .,f* '
EFFLUENT T/S REQUIRED DOCUMENTS Page 49 of 79 A. OFFSITE DOSE CALCULATIONS 1989 BIC ROCK POINT CASEOUS DESICN Table 1.9 Objective Annual Quantities Design Objective Dose Factor Annual Quantity Nuclide Organ mrem /Ci (Ci )
Tc-99m' CI Tract-I 9.61E-08 1.56E+08 Ru-103- CI Tract-A 5.84E-02 2.57E+02 Sb-125' CI Tract-T 6.37E-02 2.35E+02 Te-127 CI Tract-A 6.35E-06 2.36E+06 I-132 Thyroid-C 5.18E-08 2.90E+08 I-134 Thyroid-C 3.99E-14 3.76E+14 I-135 Thyroid-C 6.73E-05 2.23E+05 La-140 CI Tract-A 9.93E-04 1.51E+04 N-13* Total Body 1.53E-51 3.27E+51 Na-24* Total Body 1.10E-04 4.55E+04 Br-82* Total Body 1.38E-03 3.62E+03 -
Sr-91* CI Tract 1.28E-05 1.17E+06 Sr-92* CI Tract 1.18E-07 1.27E+08 T-101*- Total Body 1.26E-40 3.97E+40 Ag-110m* CI Tract 1.91E-01 7.85E+01 Cs-138 Total Body 4.32E-22 1.16E+22 Ba-139 CI Tract 2.38E-11 6.30E+11 Np-239* CI Tract 2.52E-04 5.95E+04
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V01,USE 25 - 'BIC ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 50 of 79 A. OFFSITE DOSE CALCULATIONS LII. LIQUID EFFLUENTS II.A ALLOWABLE CONCENTRATION y II.A.1 RETS Requirement Technical Specification 13.1.2.1 of the Radiological Effluent Technicel Specifications (RETS) requires that the concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to the maximum permissible concentration (MPC) specified in 10 CFR 20, Appendix B, Table II, Column 2 for nuclides other than dissolved or entrained noble gases. For dissolved or en shallbelimitedto2x10-grainednoblegases,theconcentration pCi/ml total activity. To ensure compliance, the following approach will be used for each release.
II.A.2 Prerelease Analysis Most tanks will be' recirculated through two volume changes prior to sampling for release to the environment to ensure that a representative sample is obtained. The appropriate recirculation time for-those tanks too large to provide two volume changes will be the time that the suspended particulate concentration reaches steady state. Either a one-time test, or prior sampling data, may be used to determine appropriate recirculation time.
Prior to release, a grab sample will be analyzed for each release, and the concentration of each radionuclides determined.
n Cj = Cij (II.1) i=1 where:
Gj = Total concentration in the liquid effluent at the release point, pCi/ml, at release point j.
Cij = Concentration of a single radionuclides i, pCi/ml, at release point j.
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II.A.3 . Total HPC-Fraction i
The total MPC-fraction (Rj) for each release point will be calculated i by the relationship defined by Note 1 of Appendix B,10 CFR 20: 1 C..
R(j) = (II.2) j I
1 {
where:
Cij = Undiluted effluent concentration of radionuclides i, as
. determined in Section II.A.2, pCi/ml, at release point j.
MPCi = The MPC of radionuclides i, as specified in Section II.A.1, pCi/ml.
Rj = The total _MPC-fraction for the release point.
The sum of the ratios at the discharge to the lake must be 51 due a to the releases from any or all concurrent releases. The following relationship will assure this criterion is mett fg(Rg -1) + f 2(R2 - 1) + f 3(R3 - 1) $ F (II.3) where f g,f tefs = The effluent flow rate (gallons / minute) for the respective releases, determined by plant personnel.
Rg,R2 ,R3 = The total MPC-fractions for the respective releases as determined by Equation II.2.
~
F = Minimum required dilution flow rate. Normally, a conservatively high dilution flow rate is used, that is, flow rate used = (b)(F) where b is a conservative factor greater than 1.0.
II.B INSTRUMENT ALARM SET POINTS II.B.1 Set Point Determination The set point for each liquid effluent monitor will be established using plant instructions. Concentration, flow rate, dilution, principal gamma emitter, geometry and detector efficiency are combined to give an equivalent set point in counts per minute (cpm). The physical and technical description, location and identification number for each liquid effluent radiation detector is contained in Figure 2-2.
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., EFFLUENT T/S REQUIRED DOCUMENTS Page 53 of.-79 A. OFFSITE DOSE CALCULATIONS' The respective alarm / trip set points at each release point will be-set such that the sum of the ratios at each point, as calculated by Equation II.2, will not exceed 1. The value of R is directly related to the total concentration calculated by Zquation 11.1.
An ' increase in the concentration would indicate an increace in the value of R.- A large increase would cause the limits specified in i
Section II.A.1 to be exceeded. The minimum alarm / trip set point '
l value is equal to the release concentration, but for ease of operation it may be desired that the set point (S) be. set above the effluent concentration (C) by the same factor (b) utilized in setting dilution flow. . That ist S=bxC (II.4)
Liquid effluent flow paths and release points are indicated in Figure 2.1.
II.B.2 Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in Section II.A.1 were not 6 exceeded.
A composite list of concentrations (Cij), by isotope, will be used with the actual liquid radwaste (fj) and dilution (F) flow rates (or volumes) during the release. The data vill.be substituted into Equation II.3 to demonstrate compliance with the limits in Section II.A.1. This data and set points will.be recorded in auditable records by plant personnel.
II.C DOSE II.C.1 RETS Requirement Technical Specification 13.1.4.1 of the Radiological Effluent Technical Specifications (RETS) requires that the quantity of j radionuclides released be limited 'such that the dose or dose j commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas from each reactor (see ,
Figure 2.1) will not exceed! I
- 1. During any calendar quarter, 1.5 mrem to the total body and 5 mrem to any organ, and
- 2. During any calendar year, 3 mrem to the total body and 10 mrem to any organ. l l
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-A. OFFSITEl DOSE CALCULATIONS; cII.C.2' Rele"ase Analysis:(Desian Basis Quantity' Fraction)
Per Technical' Specification 13.1.4.4 the cumulative DB'Q fraction for nuclides released is' summed at least every 31 days to: assure that.theEsum of'the fractions of all nuclides released does not?
( . exceed.1.0. year to date and 0.5 in any calendar quarter.
- ^
7 Calculations-shal1~be performed according to the formulat
?
A *.
(DBQ)g
= Fraction of DBQ (II.5) i where Ai = Cumulative quarterly or annual activity of nuclide i identified in liquid release (C1).
(DBQ)[ = Design objective annual quantity of radionuclides i from Table 2.2 (C1).
Radionuclides may be omitted from the summation if they fall under the criteria of allowed omission specified by Note 5 to Appendix B, 10 CFR 20.
- II.C.3 Exceeding DBQ Limits
.The design basis quantities are derived in such a conservative manner that doses may be greatly overestimated by this technique.
As a' consequence of this conservatism, and in light of histor-
- ically consistent' operations'with releases well below annual ;
design basis quantities, the Big Rock Point Plant technical specifications do not require monthly dose projections. However, Technical Specification 13.1.4.4 requires a cumulative dose contribution to be determined for current quarter and year every 31 days. If at'any time this calculation, by Equation II.5, results in values greater than 0.5 for a given quarter or 1.0 for year to date, the NRC LADTAP code will be run to ensure that Technical Specification 13.1.4.1 has been met. j II.C.4 Dose Calculation Values for the design basis quantities (Ci), and the dose per curie'(Dc/Cc)i for each nuclide i shown in Table 2.2, were calculated as follows. 1
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. 's VOLdME25 BIC ROCK' POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 55 of 79 A. OFFSITE DOSE. CALCULATIONS II.C.4.1 Water Ingestion The dose to an individual from ingestion of radioactivity from any source is described by the following equation:
i Dj = { (DCF)ij x Ii = mrem. (II.6) i=1 where:
Dj = Dose for the jth organ from radionuclides released, mrem, j = The organ of interest.
(DCF)ij= the Ingest il {ondosecommitmentfactorforthejthorg,,g,,,
radionuclides mrem /pci (see Table 2.1).
Ii = Activity ingested'of the ith radionuclides, pCi.
11 is described by:
(A (V)(365)(106 )
$: 11 = ;)(800)(d) = pCi (II.7) where:
365 = Days per year.
Ai = Annual activity released of i th radionuclides, pCi.
V = Average rate of water consumption; adult - 2,000 ml/d, teen and child - 1,400 ml/d, infant - 900 ml/d (Reg Guide 1.109).
d = Dilution water flow for year (ml).
800 = Dispersion factor from discharge to nearest drinking water supply.
106 = Converts pCi to pCi.
The dose equation then becomes:
i m
Dj = (4.56E5)(V) (DCF)ij x Ai = mrem (II.8) l 11 CD0589-1333A-BA01
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} g:3 A. OFFSITE DOSE CALCULATIONS II.C.4.2 Fish Ingestion The dose to an individual from the consumption of fish'is de-
~
scribegbyEquation1I.10. In this case the activity ingested of the l' ra'dionuclide (II) is described by:
Ai B IF Ii = (109 ) = pCi (II.9) 15d where:
Ai = Annual activity released of i th radionuclides, pCI.
Bi = Fish concentra ion factor of ith radionuclides, (see Table 2.0 E F = Amount. of fish eaten per yeart adult - 21 kg, teen - 16 kg, child - 6.9 kg'and infant - none.
15 = Dispersion-factor from discharge to fish exposure' point.
d = Dilution water flow for year (ml).
109 = Converts pCi to pCi and gm to kgm.
Substitution of Equation II.9 into Equation II.6 gives:
1 Dj = (6.7E07)(F) (Ai)(Bi)(DCFij) = mrem (II.10) i=1 II.C.4.3 Releasing Radionuclides Not Listed in Table 2.2~
Table 2.2 contains all nuclides identified to date as routine constituents of liquid releases at Big Rock Point Plant, plus those common to boiling water reactors in gene al, even if not previously detected at Big Rock Point. From time to time, however, other nuclides may be detected.
If the unlisted nuclide constitutes less than 10% of the MPC-fraction for the release, and all unlisted nuclides total less than 25% of the MPC-fraction, the nuclide may'be considered not present.
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EFFLUENT T/S REQUIRED DOCUMENTS Page 57'of 79 A. OFFSITE DOSE CALCULATIONS q If.the unlisted nuclide constitutes greater than 10% of the HPC-fraction, or all unlisted nuclides together constitute greater than 25%, then each nuclide should be assigned a DBQ equal to the most conservative value listed for the physical form of the nuclide involved (noble gas, halogen or particulate).
Should a nuclide not listed in Table 2.2 begin to appear in significant quantities on a routine basis, revision to this ODCM should be made in order to include a design basis quantity specific to that'nuclide.
11I.C.5 Annual Analysis A complete analysis utilizing the NRC computer code LADTAP with the total source release will be done annually in conjunction with the annual environmental report. This analysis will provide estimates of dose to the total body and various organs in addition to the dose limiting organs considered in the method of Section 2 The following approach is utilized in LADTAP. The dose to the jt6 organ from a radionuclides, Dj, is described by:
m Dj = Dij = rem (II.11) i=1 m
Dj = (DCF)ij x Ii = rem (II.12) i=1' CD0589-1333A-BA01
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25 BIC ROCK POINT RADIOLOGICAL Revision 4 4
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where Dij = Dose to the jth organ from the i th radionuclides, rem.
j = The organ of interest (bone, GI tract, thyroid,' liver,-
i kidney, lung or total body).
j (DCF)ij= Ingest {ondosecommitmentfactorforthejth organ from the it radionuclides, rem /pci (see Table 2.1).
It = Activity ingested of the ith radionuclides, pCi.
Ii for water ingestion is described by:
A; VI Il = pCi (11.13) vd and for fish ingestion It is described by:
A; B; FT '
It = ,, # W.N where:
A1 = Activity released of jth radionuclides during the year, pCi.
V = average rate of water consumption (Table 2.2).
.I = Number of days during the year (365 d).
l v = Dispersion factor from point of discharge to point of exposure (Table 2.2).
d = Dilution water volume (ml).
Si = Fish concentration factor of the ith radionuclides, m$
(Table 2.0).
F = Amount of fish eaten per day (Table 2.2).
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. VOLUME 25 BIC ROCK POINT RADIOLOGICAL
' Revision 4 EFFLUENT T/S. REQUIRED DOCUMENTS Page 59 of 79 A. OFFSITE DOSE CALCULATIONS II.D OPERABILITY OF LIQUID _RADWASTE EQUIPMENT The Big Rock Point liquid radwaste system is designed to reduce the radioactive materials in liquid wastes prior to their dis-charge (by recycle or shipment for disposal) so that radioactivity in liquid effluent releases to unrestricted areas (see Figure 2.1) will not exceed Technical Specification 13.1.4.1. Maintaining the cumulative DBQ fraction of releasea assures compliance with this requirement. In addition, more thun 13 years of operating experience (to the date this ODCM was first adopted) has shown the,t design basis quantities never have been exceeded.
II.E OFFSITE MPC RCLEASE RATE 10 CFR 20.106 requires that radioactive effluent releases to un-restricted areas be less than the limits specified in Appendix B, Table II when averaged over a period not to exceed one year.
Concentrations at this level, if ingested for one year, will result in a dose of 500 millirems to the total body or its equiva-lent to internal organs. In addition, 10 CFR 50.36a requires that the release of radioactive materials be kept as low as is reasonably achievable. However, the section further states that the licensee is permitted the flexibility of operation, to assure a dependable source of power, to release quantities of material higher than a small percentage of 10 CFR 20 limits but not exceeding those limits under unusual operating conditions. Appendix I to 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as is reasonably achievable requirement.
The LADTAP code has been run to determine the dose due to drinking water at plant discharge concentration (800 x nearest drinking water intake concentration). The source term used is given in Table 1.1. The most limiting dose of the person hypothetically drinking this water is 4.89E-01 mrem, whole body. The release rate which would result in a dose rate equivalent to 500 mres/y (the total body limit) is the Curies / Year given in Table 1.1 (8.94) times 500/.489 or 9141 Ci/Yr = 2.9E-04 Ci/sec.
The above calculation is informational as a typical exposure using the drinking water pathway and an average release from Big Rock Point. Per Section II.C.5 annual analyses are run using LADTAP to calculate estimates of dose to the total body and limiting organs.
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' Revision 4 a .' EFFLUENT T/S REQUIRED DOCUMENTS Page 60 of 79 A. OFFSITE DOSE CALCULATIONS BI0 ACCUMULATION F CTORS Table 2.0 (pCi/gm per pCi/ml)
Element Freshwater Fish H 9.0E-01 C 4.6E+03 Na 1.0E+02 P 3.0E403 Cr 2.0E+02 Mn 4.0E+02 Fe 1.0E+02 Co 5.0E+01 Ni 1.0E+02 Cu 5.0E+01 Zn 2.0E+03 Br 4.2E+02 Rb -2.0E+03
- Sr 3.0E+01 Y 2.5E+01 Zr 3.3E+00 Nb 3.0E+04 Mo 1.0E+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 2.5E+01 Ce 1.0E+00 Pr 2.5E401 Nd 2.5E+01 W 1.2E+03 Np 1.0E+01 l
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VOLLINE ,25 BIC ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 61 of 79 A. OFFSITE DOSE CALCULATIONS 1 Table 2.1 ADULT INCESTION DOSE TACIORS (MREM /PCI IkcESTED)
N1'CLIDE SONE LIVER T.80DY IHYROID KIDNEY LUM CI-LLI R 3 NO DATA 1.05E-07 1.0$E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E 07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E.06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA ~4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 NN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FI $5 2.73E-06 1.90E-06 4.43E-07 No DATA NO DATA 1.06E-06 1.09E 06
'FE 59 4.34E;06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO $8 NO DAIA 7.45E-07 1.67E-06 NU DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14E-06 4.72E*06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-02 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 , 3.91E-08 , NO DATA ,2.10E-07 NO DATA 7.10E-06 IN 65 4.84E-06
- 1.54E.05 6.96E-06 NO DATA 1.03E-05 ,NO DATA 9.70E-06 *
~~ZN 69 1.03E-08 '1.97E-08. 1.37E-09' HO DATA 1.28E-08 NO DATA - 2.96E-09 8R 83 NO DATA NO DATA 4.02E-0C NO DATA . NO DATA NO DATA 5.79E-08 8R 84 NO DATA NO DATA 5.21E*08 NO DATA NO DATA NO DATA 4.09E ....................................... ..........................................................
BR 85 NO DATA NO DAIA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 !
RE 86 No DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 i R3 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA S.36E*19 RS 89 NO DATA 4.01E-08 2.82E-08 PO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E.04 SR 91 5.67E-06 NO DATA 2.29E.07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91m 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA N0 FATA 2.67E-10 Y 91 1.41E-07 NO DATA 3.77E-09 NO DATA NO DATA No DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E*11 NO DATA NO DAIA NO DATA 1.48E-05 CD0589-1333A-BA01
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(MREM /PCI INCESTED)
NUCLIDE SONE L1Y!R T. BODY THYROID KIDNET LUNO Cf.LLI
~Y .93 2.68E-09 NO DATA 7.LDE-11 NO CAIA No DATA NO DATA 8.50E-05 ZR 95 3. %E*06 9. 75E49 6.60E-09 No DATA 1.53E-08
.ER 97 1.68E-09 3.39E-10 NO DATA 3.09E45 1.55E*10 NO DATA 5.12E-10 DATA 1.05E-%
..............................................................................NO .....................
. MS 95 6.22E-09 ,3.46E-09 1.86E-09 NO DATA 3.42E49 NO DATA 2.10E-05,'
MD 99 NO DATA '4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA TC 99m 2.47E-10 6.98E-10 9.99E-06 8.89E49 NO DATA 1.06E-08 10 6.13E 07
.............................................................................3.42E TC101 2.5&E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 RU103 1.85E-07 1.87E 10 1.10E-21 NO DATA 7.97E-08 NO DATA 7.ME-07 NO DATA 2.16E45 kU105 1.5&E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 N DATA 9.42E46
..............................................................................O RU106 2.75E46 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-M AC110m 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 No DATA 6. %E-05
- TE125e 2.68E-06 9.71E-07 3.59E-07 8.06E 07 1.09E-05 DATA 1.07E45
.............................................................................No TE127m 6.77E-06 2.42E 06 S.25E-07 1.73E~06 TE127, 1.10E-07 2.75E-05 _ NO-DATA 2.27E45 3.95E 08 2.38E-08 8.15E-08 ~4.48E-07 TE129m 1.15E-05 No DATA 8.68E46 4.29E-06 1.82E 06 3.95E-06 4.80E45
............................................................ ,..................O N DATA . 5.79E-05 TE129 3.14E-04 1.18E 7.65E-09 2.41E48 1.32E47 NO MTA 2.37148 TE131m 1 'iX-M 8.66E-07 7.05E-07 1. ME-06 8.57E-06 No DATA 8.60E 05 TE131 1.97E-08 8.23E-09 6.22E49
- 1.62E-04 8.6X-08 N DATA 2.79E49
..............................................................................O TE132 2.52E-06 1.63E-06 1.5X-06 1.80E-06 1.57E45 1 130 7.56E-07 2.23E-06 No DATA 7.71E45 8.80E47 1.89E*% 3.68E-06 1 131 6.16E46 NO DATA 1.921-06 5.95E-06 3.41E-06 1.95E-03 1.02E4 NO DATA 1.57E46
.......................................................................5 I 132 ..........................
2.03E47 5.4X47 1.90E-07 1.90E-05 8.65E-07 No DATA 1.02E-07 I 133 1.42E-M 2.47E-06 7.5X47 3.63E-% 4.31E-06 No DATA 2.22E-06 1 1M 1.06E-07 2.88E-07 1.03E47 6.99E-06 4.58E47 DATA 2.511 10
.............................................................................NO I 135 .....................
4.43E-07 1.16E-06 4.28E-07 7. 65E-05 1.86E-06 NO DATA 1.31E-06 C$1% 6.22E-05 1.48E-M 1. 21E*% NO DATA 4.79E-05 1.59E-05 2.59E-06 CS136 6.51E46 2.57E-05 1.85E-05 NO DATA 1.4 X-05 2.92E46
...........................................................................1.96E46 CS137 7.97E-05 1.09E-M 7.1&E-05 No DATA 3.70E 05 1.23E 45 2.11E46 CS138 5.52E-08 1.0ft-07 5.40E-08 NO DATA 8.01E-08 SA139 7.91E-09 6.65E-13 9.70E-04 6.91E-11 2.8&E-09 NO DATA 6.46 3.92E-11 1.72E-07
..........................................................E-11
=ew* ay %e..,=w..
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...~ - _.. -
ADULT INGESTION DOSE TAC 70R5 (MRouPCI INctsnD)
NL'CLIDE BONE LIVER T. BODY THYROID KIDNEY LUNC CI-LLI RA140 ' 2.03E-05 2.55E-08 1.33E-04 No DAu 8.67E-09 1.46E-08. 4.18E-05 BA141 4.71E-08 3.56E*u 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.21E*17 BA142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA140 2.50E-09 1.26E-09 3.33E-10. NO DAu NO DATA NO DATA 9.25E-C5 LAli.2 1.28E-10 5.82E n 1.45E-U NO DAM NO DATA NO DATA 4.25E-07 CE141 9.36E-09
- 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.27E-10 NO DATA 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR143 9.20E-09 3.65E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR144 3.01E-11 1.25E-11 1.53E 12 NO DAIA 7.05E-12 NO DATA 4.33E-18 ND147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61E-08 3.01I-05 NO DATA NO DATA NO DATA 2.82E-05 NP239 '1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.400-05 C.D0589-1333A-BA01 t, . - - . __ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
[ l VOLUME 25 BIC ROCK POINT RADIOLOGICAL l .,
- Revision'4 EFFLUENT T/S' REQUIRED DOCUMENTS Page 64 of 79 A. OFFSITE DOSE CALCULATIONS Table 2.1 INGE 5 f l01 305E FACTOR $ FC# TEENA*Et (MREP PER PCI INCESTE01 NUCLICE 80NE L i vE t T.80rY THYR 010 K!DNEr LUNG Ct-LLt el 3 NO DATA 1.06E-07 1.00E-0 7 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C 14 4.06E-06 8.12E-07 8.12E-0T 8.12F-07 8.12E-07 a.12E-07 .8.12F-07 NA 24 2.30E-06 2.20E-96 2. 30 E-0 6 2.30E-06 2.30L-06 2.30E-06 2 30E-06 P 32 2.76C-04 1.71E-05 1.07E-0 5 NO DATA 40 DATA NO DATA 2.32E-05 CR St NU OATA NO DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6 05E-0T FN $4 NO CATA $.90E-06 1. ! TE-0 6 NO 0ATA 1.76E-06 NO DATA 1 21E-05 kN $6 40 DATA 1.38E-07 2. 4 L E-0 8 NO DATA 2.00E-07 NO DATA 1 04E-05 FE 53 s 3.T8E-06 2.68F-06 6.25E-01 40 DATA NC DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.JfE-05 5.2 9E-0 6 NO DATA NO DATA 4.32E-06 3.24E-05 Co 58 NO DATA 9.72E-0F 2. 2 4 E-0 6 No JATA' No UATA NO DATA 1.34E-05 CD 60 NO DATA 2.61E-06 6. 3 3 E-0 6 NO DATA NO DATA NO CATA 3.66E-05 4! 63 1.77E-04 1.25E-05 0. 00E-0 6 NO DATA NO DATA NO DATA 1.99E-06
- vt 65 7.49E-07 9. 5 7E-04 4.36E-08 NO DATA NO DATA NO DATA 5 19E-06 CU 64 NO DATA 1.15E-07 5.4tE-08 No DATA 2.91.-07 NO DATA 8.92E-06
- TN 6b 5.76E-06 2.C0E-E5 9. 3 5E-0 6 NO DATA 1.2BE-05 NO DATA 4.47E-06 2N 69 1.47E-08 2.60E-08 1.96E-09 NO DATA 1.83E-08 40 DATA 5.16E-08 Rt 83 NO DATA NO D AT A S. 74 E-0 8 NO DATA 40 DATA BR 84 NO CATA NO DATA LT E-24 NO CATA 7.22E -0 8 NO CATA NC DATA NO CATA LT E-24 e 4 '8 % NO DATA NO DATA 3.0 $ E-0 9 NO DATA NO DATA NO DATA LT E-24 28 46 N0 DATA 2.18E-05 1.40E-0 5 NO DATA NO DATA NO CATA 4.4LE-06 48 88 NO DATA B.52E-08 4.56E-08 R0 DATA NO DATA NO DATA 7.30E-15 (E 89 NO DATA 5.50E-08 J.89E-08 NO DATA NO DATA NO DATA 8.43E-17
$A 81. 4.40E-04 NO D AT A 1.26E-03 NO DATA NO DATA NO DATA S.24E-05 SR 90 8.30E-03 NO DATA 2.0SE-03 NO DATA NO DATA NO DATA 2.33E-04 SR 11 8.07E-06 NO DATA 3.21E-0 7 NO DATA NO CATA NO DAT A 3.66E-05 54 92 3.05E-06 40 DATA 1. 30E-0 7 NO DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E-08 NO DATA 3. 0 7E-10 NO DATA NO DATA N0 DATA 1.13E-04 Y 91P 1.29E-10 NO DATA 4.93E-12 NO DATA NO DATA NO DATA 6.09E-09 Y 91 2 01E-07 NO DATA 5. 3 9E-0 9 N0 DATA NO DATA NO DATA 8.24E-05 Y 92 1.21E-09 NO CATA 3.50E-11 NO CATA NO DATA NO CATA 3.32E-05 i
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INGESTION 00$E FACTCRS FOR TEENAGER twREM #FA PCI INCESTEDI NUCLIOE BONE Ltvit T . 800Y THYR 0!D KtDNEY LUNG Cl-LLI y 93 3.83E-C9 NO DATA 1.05E-10 NO DATA NO CATA No DATA 1.17E-04 Zu 95 4.12E-08 1.30E-08 R.9*E-09 NO DATA 1.91E-08 ho DATA 3.00E-05 tt 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.11E-10 NO DATA 1.27E-04 -
de 95 B.22E-09 4.561-09 2. 51E -0 9 NO DATA 4.42E-09 NO DATA 1.95E-05 MD 99 NO DATA 6.03E-06 1.156-06 NO DATA 1.38E-05 N0 DATA 1.08E-05 TC 99P J.32E-10 9.26E-10 1.20E-08 NO D A T A 1.38E-08 5.14E-10 6.08E-07 TC101 3.60E-10 5.122-10 5. 0 3 E-09 NO DATA 9 26E-09 3.12E-10 8.75E-17 9U103 2.55E-07 NO DATA 1. 09 E -0 7 NO DATA 8.99E-07 40 DATA 2.13E-05 etU 105 2.18E-04 NO DATA 8.460-09 NO DATA 2.75E-07 N0 DATA 1.76E-05 Rut 06 3.92E-06 NO DATA 4.944-07 NO DATA 7.56E-06 k0 CATA 1.88E-04 AG110p 2.CSE-07 1.94E-07 1.18E-07 NO DATA 3.70E-07 NO DATA 5.45E-05 TE12b 3.33E-06 1.386-06 5.12E-07 1 07E-06 NO DATA TF127M 9.67E-06 3.4JE-06
.................- .............. ...... . ...... .... . 40 OATA 1.13E-05 1.15 E-0 6 2.30E-06 1.92E-05 NO DATA 2.41E-05 IEt27 1.58E-07 5.60E-08 ~3.40E-08 1.09E-07 6.40E-07 ha OLT4 1.22E-05 TE129M l.63E-05 6.C5E-06. 2. 5 8 E-0 6 5.26E-06 6.42E-05 No DATA 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.8"8E-07 No DATA 2.45E-07 TE131" 2.44E-06 1.17E-06 9.76E-07 1.F6E-06 1.22E-05 WO DATA 9 39E-05 TE131 2.79E-08 1 15E-08 8.72E-09 2.15E-08 1.22E-07 NO DATA 29E-09 TE132 3.49E-06 2.2tE-06 2.06E-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 I 130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 No DATA 2.29E-06 1 131 5.85E-06 8.19E-06 4. 40E-0 6 2.39E-03 1.41E-05 NO DATA 1.62E-06 1 132 2.79E-07 7.3CE-07 2. 62 E-0 7 2.46E-05 1.15E-06 NO DATA 3.18E-07 1 133 2.01E-06 3.4tE-06 1.04E-06 4.76E-04 5.98E-06 ho DATA 2.58E-06 1 134 1.46E-07 3.87E-07 1. 3 9E -0 7 6.45E-06 6.10E-07 NO DATA 5 10E-09 I 135 6.10E-07 1.57E-06 5. 82 E-0 7 1.01E-04 2.48E-06 NO DATA 1.74E-06 C5134 8.37E-05 1.9fE-04 9.14 E-0 5 NO DATA 6.26E-05 2.39E-05 2.45E-06 C5136 8 59E-06 3.JBE-05 2 27E-05 NO DATA t.84E-05 2.90E-D6 2.72E-C6
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ~ . . . . . . . . . . . . . . . . . . . . . - - . . . . . . . . . . . . . . . . -
C5137 1.12E-04 1.49E-04 5 19E-0 5 NO DATA 5.07E-05 1.97E-05 2.12E-06 C5134 7.76E-08 1.49E-07 7.45E-08 NO DATA 1.10E-07 1.28E-08 6.76E-11 81139 1.39E-07 9.78E-11 4. 05E-0 9 NO DATA 9.22E-11 6.74E-11 1.24E-06 J
l 4
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- 25. BIG ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 66 of 79 A. OFFSITE DOSE CALCULATIONS Table 2.1 I tGE5Tl0N 005E F ACTOR 5 FCR TEFNAGER t uaEM PER *CI INCESTEDI NutttLE BONE- LivCR T.90CY THYROIO K10NEY LUNC GI-Lt!
BA140 2.84E-05 3.4RE-05 1. 8 3E-0 6 -No OATA 1.18E-08 2.34E-J8 4.38E-05 MA141 6.7tE-C8 5.01E-11 2.24E-09 NO DATA 4.65E-11 3.43E-11 1.43E-13 BA142 2.99E-08 2.19E-11 1.84E-09 '40 DATA 2.53t-11 1.99E-11 9.18E-20 La140 3.48E-09 1. TIE-09 4.55E-10 NO CATA NC DATA NO DATA 9.82E-05 LA142 1.79E-10 7.95E-11 1.9BE-11 NO DATA NO DATA NO DATA 2.42E-06 CE141 1.33E-08 8.88E-09 1.02E-09 NO DATA 4.18E-09 NO 04TA 2.54E-05 CE143 2.35E-09 1.71E-06 1.91E-10 NO DATA F.67E-10 h0 DATA 5.14E-05 CE144 6.96f-CT 2.88E-07 3.74E-08 NO CATA 1.72E-07 NO DATA 1.75E-04 PR143 1.31E-08 5.23E-C9 6.52E-10 NO DATA 3.n4E-09 NO CATA 4 31E-05 PR144 4.30E-11 1.762-11 2.18E-12 NO DATA 1.01E-11 NO DATA 4.74E-14 N014T 9.18E-09 1.02E-08 6.11E-10 NO DATA 5.99E-09 NO DATA 3.68E-05
. 137 1.46E-07 1.19E-07 4.t TE-08 NO DATA NO DATA NO DATA 3.?2E-05 NP239 1.76E-09 1.66E.10 9.22E-11 NO DATA 5.2tt-10 40 CATA 2.67E-05 P
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VOLUME 25 BIC ROCK POINT RADIOLOGICAL
- Revision 4 ETFLUENT T/S REQUIRED DOCUMENTS Page 67 of 79 A. OFFSITE DOSE CALCULATIONS Table 2.1
. INGE5fl0N 005E F ACTORS FOR CHILO IMREM PE4 pCI INGESTEDI suCLILE 80NE L t vet -T.60LT TH140!D KIDNEY LUNG Gt-LLI H 1 NO DATA 2.03E-07 2. 01E-0 7 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 14 1.21E-05 2.*2E.06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 5.30E-06 5.80E-06 5.80E-06 5.83E-06 5.90E-06 5.90E-06 5.80E-06
- 32 8.25E-04 3.86E-05 3. LEE-05 40 DATA NO DATA NO DATA 2.28E-05 CR'51 NO DATA NO CATA 8. 90E -0 9 4.94E-c9 1.35E-09 9.02E-C9 4.72E-07 FN 54 NO DATA 1.37E-05 2. 6 5 E-0 6 NO DATA 3.0CE-06 NO DATA 8.98E-06 MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.C4E-07 NO DATA 4.84E-05 FE 55 1.15E-05 6 10E-06 1.89E-06 NO DATA NC DATA 3.45f-C6 1.13E-06 FE 59 1.62E-05 2.67E-05 1. 3 3 E-0 5 NO DATA NC OATA 7.74E-06 2.78E-05 CO $s 40 DATA. 1.80E-06 5.51E-06 NO DATA NC DATA 40 DATA 1.05E-05 CO 60 NO DATA 5.29E-06 1. 56 E-0 5 NO DATA NO DATA NO DATA 2 93E-05 4! 63 5.38E-C4- 2.E8F-05 1.83E-05 NO DATA NO DATA NO DATA 1.94[-06 NI 65 2.22E-06 2.09F-07 1. 22 E-0 7 No DATA No DATA NO DATA 2.56E-C5 CU 64 NO DATA 2.45E-07 1.4sE-07 NO DATA 5.92E-07 NO DATA 1.15E-05 ,
IN 65 1.37E-05 3.oSE-0) 2.2 TE-0 5 NO DATA 2.30E-05 No DATA 6.41E-06
.................................._.............-......................., 4 IN 69 4.38E-08 6.s3E-08 5. 85E-0 9 NO DATA 3.S4E-08 NO DATA 3.99E-06 '
SR 8A NO DATA NO DATA 1. 71 E-0 7 NO DATA NO DATA NO DATA LT E-24 '
BR 84 NO DATA NO DATA 1.986-07 NO DATA NO DATA NO DATA LT ,E-24 P.R 85 NO DATA NO DATA 9 12 E-09 NO DATA NO DA*A NO DATA LT E-24 RB 86 NO DATA 6.70E-05 4.12 E-0 5 - NO D AT A 40 DATA NO DATA 4.31F-06 R8 88 NO DATA 1.90E-07 1.12 E -0 7 NO DATA NO DATA No DATA 9.32E-09 18 49 NO DATA 1.17E-07 1.04E-0 7 NO DATA NO DATA NO DATA 1.02E-09 SR 89 1.32E-03 NO CATA 1. 7 7 E-0 5 ;10 DATA NO DATA NO DATA 5.11E-05 SR 90 1.70E-02 NO OATA 4. 31 E-0 3 40 DATA NO DATA NO DATA 2.29E-04 SR 91 2 40E-05 NO DATA 9. C6E-0 7 NO DATA NO DATA NO CATA 5.30E-05 SR 92 9.03E-C6 NO DATA 3.62E-07 NO DATA NO DATA NO DATA 1.71E-04 Y 90 4.11E-08 NO DATr 1~.7 DE-0 9 -N0*0ATA NO DATA 1 17E-04
.................................- ...'No-CATA .... ...................~............
Y 91E 3.82E-10 NO DATA 1.31E-11 NO DATA NO DATA NO DATA 7.48E-07 Y 91 6.02E-07 NO DATA 1. 61 F-0 8 NO DATA NO DATA NO CATA B.02E-05 Y 92 3.60E-09 NO DATA 1. 0 3 E-10 NO DATA NO DATA NO DATA 1.04E-04 1 ' CD0589-1333A-BA01 1
' VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 4 i' , ., EFFLUENT T/S REOUIRED DOCUMENTS Page 68 of 79 A. OFFSITE DOSE CALCULATIONS Table 2.1
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INGESTION UO5E F ACTOP.5 FCR CHILO t> REM PE4 vCI INCESTEDI NUCLIGE SONE LIVE 9 T.300Y THYR 010 KIDNEY LUNG Ct-LLI V 93 1.14E-08 NO DATA 3.13E-10 NO DATA *O DATA NO DATA 1.70E-04 2R 95 1.16E-07 2.35E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 in 97 6.49E-09 1.C1E-09 S.96E-10 NO DATA 1.45E-09 NO DATA 1.53E-04' NA 95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 MD 99 NO DATA 1.33E-05 3.29E-06 NO DATA 2.84E-05. NO DATA 1.10E-05 IC 99p 9.23E-10 1.81E-09 3. 00 E -0 8 NO DATA 2.63E-08 9.19E-10 1.03E-06 l
TC101 1.07E-09 1 12E-09 1 42E-08 NO DATA 1.9tE-08 5.92E-10 3.56E-09 nU103 7.31E-07 No DATA 2. 81 E-0 7 NO CATA 1.84E-06 NO DATA 1.89E-05 nU105 6.45E-08 NO DATA 2.34E-08 No DATA 5.67E-07 No DATA 4.21E-05 4U106 1 17E-05 NO DATA 1 46 E-0 6 NO DATA 1.58E-05 NO DATA 1.82E-04 AG110M 5.39E-07' 3.64E-07 2. 91 E-0 7 NO DATA 6.78E-07 NO CATA 4.33E-05 TE125M 1.14E-05 3.09E-06 1. 5 2 E-0 6 3.20E-06 NO DATA NO DATA 1.10E-05 TE12TM 2.89E-05 7.79E-06 3. 4 s E-0 6 6.91E-06 e.24E-05 NO CATA 2.34E-05 TE127 4.71E-07 1.27F-07 1.01E-0 7 - 3.26E-07 1.34E-06 No DATA 1.84E-05 TE129" 4.87E-05 1.36E-05 7. 50 E-0 6 1.57E-05 1.43E-04 NO DATA 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 1.56E-38 3.92E-07 NO DATA 8.34E-06 TE!)1M 7.20E-06 2.49E-06 2 65E-06 5.12E-36 2. 41E -05 NO CATA 1.01E-04 TE131 8.30E-08 2.53E-08 2. 47 E-0 8 6. 35E-04 2.51E-07 NO DATA 4.36E-07 TE132 1.01E-05 4.47E-On 5. 40 E-0 6 6 51E-06 4.15E-05 NO DATA 4.50E-05 1 130 2.92E-06 5.90E-06 3.04E-On 6 50E-04 8.82E-06 NO DATA 2.76E-06 I 131 1.72E-05 1.73E-05 9. 8 J E-0 6 5.72E-03 2.84E-05 NO DATA 1.54E-06 1 132 8.00E-07 1.47E-06 6. 76E-0 7 6.82E-05 2.25E-06 NO DATA 1.73E-06 I 133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 NO DATA 2.95E-06 l 134 4.19E-07 7.78E-07 3. 5 8 E-0 7 1.79E-05 1 19E-06 No Daft 5.16E-07 I 135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 NO DATA 2.40E-06 C5134 2.34E-04 3.84E-04 8.10E-0 5 NO DATA 1.19E-04 4.97E-05 2.07E-06 C5136 2.35E-05 6.46E-05 4.18E.05 NO DATA 3.44E-05 5.13E-06 2.27E-06 C5137 3.27E-C4 3.13E-04 4. 62 E-0 5 NO DATA 1.02E-04 3.67E-05 1.96E-06 C5138 2.28E-07 3.17E-07 2.01E-07 NO DATA 2.23E-07 2.40E-08 1.46E-07 3Al39 4.14E-07 2.21E-10 1. 2 0E-0 8 NO DATA 1.93E-10 1.30E-10 2.39E-05 ,
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- l. INGEST 101 DOSE F ACToa5 FCR CHILO IFREP pet PCI INGESTEDI
. NUClicE' 8ONE liver T . d OCY . THYRDID KIONEY LUNG Cl-Lt1 RA140 8.J1E-05 7.28E-08 4.85E-06 10 DATA 2.3 7t-08 4.34E-08 4.21C-05 OA141 2.00E-07 1.122-10 6. 51 E-0 9 NO DATA- 9.69E-11 6.58E-10 1.14E-07 8.T4E-08 6.29E-11 4.88E-09 10 DATA 5.09E-11 3.70E-11 1.14E-09 SA142 LA140 1.01E-08 3.53E-09 1.19E-09 '40 DATA WC DATA NO DATA 9.84E.05 LA142 5.24E-10 1 67E-10 S.23E-11 NO DATA NO DAT4 NO CATA 3.31E-05 CE141 3.97E-08 .1.98E-08 2.9=E-09 NO DATA R.68E-09 NO DATA 2.4FE-05 CEles 6.99E-09 3.79E-06 5.49E-10 NO DATA- 1.59E-09 NO DATA 5.55t-05 CE144 2.08E-06 6.52E-07 1.!!E-07 NO CATA 3.61k-07 NO DATA 1.70E-04 PR141 5.93E-08 1.185-08 1. 95 E-0 9 NO DATA 6.19E-09 NO DATA 4.24E-05 PR144 1 29E-10 1.11E-11 6.49E-12 NO DATA 2.11E-11 NO DATA 8.59E-08 N0147 2.79E-0A 2.26E-08 1.75E-09 No DATA 1.24E-08 NO DATA 3.58E-05 W 187 4.29E-07 2.54f-07 1.16E-07 NU OATA NO DATA NO DATA 3.57E-05 4P239 5.25E-09 3.77E-10 2.6bt-10 NO DATA 1.09t=09 NO DATA 2.79E-05 CD0589-1333A-BA01
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BIG ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 70 of 79 A. OFFSITE DOSE CALCULATIONS Table 2.1 INGESTIO4 00$E F ACTOR 5 FOR INFANT twaEM PER PC1 INGESTE01 l WCL ICE BONE LIVER T.dOGY THv401D KIONEY LUNG GI-LL1 1
............................................................................ j H 3 NO DATA 3.085-07 3.0 8 E-0 7 3. ORE-07 3.08E-07 3.C8E-07 3.08E-07 C 14 2.37E-05 5.06E-06 5. 0 bE-0 6 5.06E-06 5.06E-06 5.06F-06 5.06E-06 NA 24 1.01E-05 1 01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-6h 1.Olt-05 9 32 1.70E-03 1.00E-04 6.59E-05 NO DATA NO DATA No DATA 2.lcE-05
", A 51 NO DATA NO DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4 1tE-07
- N 54 NO DATA 1.99E-Ob 4. 51 E -0 6 No DATA 4.4tE-06 NO CATA 7.31E-06 MN 56 40 DATA 8.18E-07 1.4 t E-0 7 Mu CATA 7.01E-07 NO DATA 7.43E-05 FE 55 1.39E-05 8.18E-06 2. 4 0 E-0 6 NO DATA NO DATA 4.19E-06 1.14E-06 FE 59 3.08E-05 5.482-05 2.12 E-0 5 NO CATA NO DATA 1.59E-05 2.57E-05 CO 58 NO DATA 3.60E-06 8. 93 E-0 6 NO DATA NO DATA NO DATA 8.9ft-06 Cc 60 NO DATA 1.08E-05 2. 55 E-0 5 NO DATA NO QATA N0 f. AT A 2.57E-05 NI 63 6.34E-04 3.92E-05 2. 2 0 E-0 5 NO DATA NO DATA NO GATA 1.95E-06 wt 65 4.70E-06 5.32E-07 2. 42 E-0 7 NO DATA NO DATA NO DATA 4.05E-05 Cu 64 NO DATA 6.09E-0T 2. 82 E-0 7 NO DATA 1.03E-06 NO DAT4 1.25E-05 IN 65 1.54E-05 6.31E-05 2. 91 E -0 5 NO DATA 3.06E-05 NO DATA 5.33E-05 ZN 69 9.33E-08 1.o8E-0T 1.2 5E-0 8 NO DATA 6.98E-08 NO DATA 1.37F-05 na 83 NO DATA NO DATA 3. 63 E-0 7 NO DATA NO DATA NO DATA LT E-24 bR 84 NO DATA NO DATA 3. 82 E-0 7 NO DATA N0 DATA NO DATA LT E-24 dR 85 NO DATA NO DATA 1. 94 E-0 8 NO DATA NO DATA NO DATA LT E-24 MB 86 NO DATA 1.70E-04 8.4 0E-0 5 NO DATA NO DATA NO DATA 4.35E-06 48 88 NO DATA 4.98E-07 2.730-07 NO DATA NO DATA NO DATA 4.85E-07 92 89 NO DATA 2.86E-07 1.97E-37 NO OATA NO DATA No DATA 9.74E-08 SR 89 2.51E-03 NO DATA 7. 2 0E-0 5 NO DATA NO DATA NO DATA 5.16E-05 5A 90 1.85E-02 NO DATA 4. 7 t E -0 3 No DATA NO DATA NO DATA 2.3tE-04 5 A 91 h.00E-05 NO DATA 1. 81 E-0 6 NO DATA NO DATA No DATA 5.92E-05 52 92 1.92E-05 NO DATA 7.13 E-0 7 NO DATA NO DATA NO DATA 2.0TE-04 Y 90 8.69E-08 40 DATA 2. 3 s f-0 9 No DATA NO DATA No DATA 1.20E-04 y 91M 8 10E-10 NO DATA 2.76E-11 NO DATA NO DATA NO DATA 2.70E-06 y 91 1.13E-06 NO DATA 3.01E-08 NO DATA NO DATA NO DATA 8.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04 OD0589-1333A-BA01
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BIC ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 71 of 79 A. OFFSITE DOSE CALCULATIONS
. Table 2.1 INGESTION 00$E F ACTOR 5 F0a INc4NT (MREM PE4 PCI twCESTEDI NUCLICE BONE LIVER T.DODY THYto! O (10NEY LUNG GI-LLI Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA 1.92E-04 2R 95 2.06E-07 5.02E-08 3. 56 E-0 6 NO DATA 5.41E-08 NO DATA 2.50F-05 la 97 1.48E-08 2.54E-09 1.lbE-09 NO DATA 2.56E-09 NO DATA 1.62E-04 N8 95 4 20E-08 1.73E-08 1.03E-Of NO DATA 1.24L-08 NO DATA 1.46E-05 MO 99 NO DATA 3.4CE-05 6. 6 3 E-0 6 NO DATA 5.08E-05 NO DATA 1.12E-05 TC 99F 1.92E-09 3.965-09 5.10E-0 8 ND DATA 4.26L-08 2.07E-09 1.15E-06 IC101 2.27E-09 2.86E-09 2.83E-08 NO DATA 5.40E-08 1 56E-09 4.86E-07 RU103 1.48E-06 NO bafA 4.95E-07 40 DATA 3 08E-06 NO DATA 1.80E-05 autos 1.36E-07 N0 DATA 4 58E-08 40 CaTA 1.00E-06 Nn DATA 5,44E-05 RL* t oe 2.41E-05 NO DATA 3.01E-36 NO CATA 2.45E-05 NO DAT A 1.83F-04 4G110M 9.96E-07 7.27E-07 4.8tE-07 No DATA 1.04E-06 NO DATA 3.77E-05 TE125M 2.33E-05 7.79E-06 3.1)E-06 7.84E-C6 NO DATA NO DATA 1.11E-05 TEt27P 5.85E-05 1.14E-05 7.00E-06 1 69E-05 1.44E-04 ho DATA 2.36E-05 TE!27 1.00E-06 3.J5E-07 2.15E-07 8.14 E-0 7 2.44s-06 40 DATA 2.10E-05 7E12sA 1.00E-04 3.43E-05 1.5*E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 NO DATA 2.27E-05 TE131M !.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04 TE131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 No 0ATA 7.11E-06 TE132 2.08E-05 1. 0 3E -05 9.61E-06 1.52f-05 6.44E-05 No DATA 3.81E-05 1 130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 NO DATA 2.8 3E-06 1 131 3.59E-05 4.2 3E-05 1. R6E-0 5 1.39E-02 4. 94 E -05 No DATA 1.51E-06 g 132 1.66E-06 3.37E-06 1. 2 0 E-0 6 1.58E-04 3.76E-06 NO DATA 2.73E-06 1 133 1.2SE-05 1.82E-05 5.35E-06 3.31E-03 2 14E-35 NO DATA 3.08E-06 1 134 8.69E-07 1.78E-06 6 33E-0 7 4.15Z-05 1.99E-06 NO DATA 1.84E-06 I 135 3.64E-06 7.24E-06 2.64 E-0 6 6.49E-04 9.07E-06 NO DATA 2.62E-06 C1134 3.77E-04 7.03E-04 7 10E-0 5 NO CATA 1.81E-04 7.42E-05 1.41E-06 C5136 4.59E-05 1.35E-04 5. 04 E-0 5 NO DATA 5.38E-05 1.10E-05 2.05E-06 C5137 5.22E-04 6.11E-04 4. 3 3 E -0 5 10 DATA 1.64E-04 6.64E-05 1.9tt-06 C5138 4.81E-07 7.82E-07 3 70E-0 7 NO DATA 3.90E-07 6.09E-08 1.2SE-06 8A139 8.81E-07 5.84E-10 2. 5 5 E-0 8 40 DATA 3.51E-10 3.54E-10 5.58E-05 I
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INCEST 10N DOLE FACTOR $ FCt INFANT 1* REM PER PCI INCESTE03 l vuCL1;E BONE liver T.AC0Y THY 4010 K!0NEY LUNG CI-LL1 Saleu 1.71E-04 1.71E-0T 8.41E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05
'ealet 4.25E-07 2.112-10 1. 3* E-0 8 No DATA 1.75E-1C 1.7FE-10 S.19E-06 rA142 1.84E-07 1.53E-10 9.06E-09 NO DATA 8 51E-11 9.26E-11 7.59E-07 lf LA140 2.11E-08 8.32E-09 2.14 E-0 9 NO DATA NO DATA NO DATA 9.77E-05 I LA142 1.10E-09 *.06E-10 9.6/E-11 NO DATA NC OATA NO DATA 6.86E-05.
l CE141 7.87E-08 4.80E-08 5. 6S E -0 9 NO DATA 1.486-C% NC OATA 2.48E-05 CE143 1.48E-08 9.82E-06 1.12 E-0 9 NO DATA 2.966-C9 NO DATA 5. 7 ?.E-05 CE144 2.98E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.T!E-04 PR143 8.13E-08 3.C4E-04 4. 01 E-0 9 NO DATA 1.13E-08 NO DATA 4.29E-05 L PR144 2.74E-10 1.06E-10 1 38E-11 NO DATA 3.A4L-11 NO DATA 4.9 3E-06 N0147 5 53E-08 5.68E-08 3. 4 8 E -0 9 NO DATA 2.19E-08 'NO DATA 3.60E-05 w 187 9.03E-07 6.28i-07 2.17E-0T NO CATA NO DATA NO DATA 3.69E-05 NP234 1.11E-08 9.93E-10 5. 61 E-10 NO DATA. 1.98E-09 NO DATA 2.8 7E-05
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VOLUkE75' BIC ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 73 of 79 A. OFFSITE DOSE CALCULATIONS Table 2.2 BIC ROCK POINT DESIGN OBJECTIVE ANNUAL QUANTITIES FOR -
LIQUID EFFLUENTS AS DETERMINED BY LADTAP 0: sign objective annual quantities for liquid effluents were calculated utilizing the computer code LADTAP, a program for calculating radiation cxposure to man from routine releases of nuclear reactor liquid effluents (reference NUREC/CR-1276).
Input parameters used are as follows:
Process Times Pathway Age Group Usage Dilution (Hr)
Fish Adult 21.0 kg/yr 15.0 24.0 Teen 16.0 15.0 24.0 Child 6.9 15.0 24.0 Infant 0.0 15.0 24.0 Drinking Adult 730.0 L/yr 800.0 16.6 Teen 510.0 800.0 16.6 Child $10.0 800.0 16.6 Infant 330.0 800.0 16.6 Shoreline Adult 12.0 hr/yr 2.0 0.0 Teen 67.0 2.0 0.0 child 14.0 2.0 0.0 Infant 0.0 2.0 0.0 Swimming Adult 12.0 hr/yr 2.0 0.0 Teen 67.0 2.0 0.0 Child 14.0 2.0 0.0 Infant 0.0 2.0 0.0 B: sting Adult 100.0 hr/yr 15.0 0.0 Teen 100.0 15.0 0.0 child 50.0 15.0 0.0 Infant 0.0 15.0 0.0 The usage figures are obtained from Regulatory Guide 1.109 and are default values. Dilutions and the process time for drinking water were taken from the NUS study dated June 4, 1976. The minimum process times that can be utilized ]
fer fish and drinking are 24.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> and 12.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> respectively. l The federal limit to unrestricted areas for any individual through the liquid p;thway is 3 mrem, total body, and 10 mrem to any organ (Reference Part 50, l Appendix I).
l l The attached table lists the design quantities as calculated from LADTAP.
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VOLUME 25,- BIG ROCK; POINT RADIOLOGICAL ~
Ravision 4-
.,7, EFFLUENT T/S REQUIRED DOCUMENTS Page 74 of 79 A. . OFFSITE DOSE CALCULATIONS' Table 2.2 BIG ROCK POINT DESIGN OBJZCTIVE ANNUAL QUANTITIES FOR-
. LIQUID EFFLUENTS AS DETERMINED BY LADTAP' The following input parameters are used when running LADTAP for BRP
- 1. ' 50-mile population - 1.54E05
- 2. Shore. width factor - 0.3
- 3. Tota 1' discharge (is*/sec) - 109
- 4. ' Transit time for all pathways -'4.6 5.. Sport fish harvest (kg/yr) - 3.29E05
- 6. Commercial fish harvest (kg/yr) - 1.70E05-
- 7. Invertebrate and-algae consumption - 0 8.- Drinking vater population - 7.07E03
- 9. Shoreline' population usage (man-hours) - 3.8E07 10.. Swimming population usage (man-hours) - 1.2E07
- 11. Boating. population usage (man-hours) - 3.7E07 l'
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VOLbHE 25 - BIC ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS - Page 75 of 79 A. OFFSITE DOSE CALCULATIONS Table 2.2 BIC ROCK POINT DESIGN < OBJECTIVE ANNUAL QUANTITIES FOR LIQUID EFFLUENTS AS DETERMINED BY LADTAP .
Design Objective Dose Conversion Annual Quantity Nuclide Factors'(mrem /Ci) Individual / Organ (Curies)
H-3 2.34E Adult /TB 1.282 x 106 Na-24 3.95E-03 Teen /TB 759.49 Sc-46 1.24E-02 Teen /TB 241.94 Cr-51 1.90E-03 Adult /CI (LLI) 5,263.16 Hn-54 8.39E-02 Adult /CI (LLI) 119.19 Fe-55 5.50E-03 Child / Bone 1,818.18 Hn-56 1.22E-03 Teen /TB 2,459.02 Co-57 2.80E-03 Teen /TB 1,071.43 Co-58 6.95E-03 Teen /TB 431.66 Fe-59 4.93E-02 Adult /CI (LLI) 202.84 Co-60 2.90E-01 Teen /TB 10.34 Cu-64 1.48E-03 Teen /CI (LLI) 6,756.76 Ni-65 3.82E-04 Teen /TB 7,853.4 Zn 2.16E-01 Child /TB 13.89 Br-84 1.33E-03 Teen /TB 2,255.64 Rb-86 3.75E-01 Child /TB 8.0 Rb-88 4.54E-04 Teen /TB 6,6C7.93 Sr-89 1.93E-01 Child / Bone 51.81 Sr-90 3.34E+00 Adult / Bone 2.99 Sr-91 2.90E-03 Teen /CI (LLI) 3,448.28 Design Objective Dose Conversion Annual Quantity
, Nuclide Factors (mrem /Ci) Individual / Organ (Curies)
Sr-92 9.94E-04 Teen /TB 3,018.11 Y-92 1.76E-04 Teen /TB 17,045.5 Nb-95 8.88E+00 Adult /CI (LLI) 1.13 Zr-95 3.82E-03 Teen /TB 785.34 Nb-97 4.56E-04 Teen /TB 6,578.95 Zr-97 2.74E-03 Teen /CI (.LLI) 3,649.64 l Mo-99 1.31E-03 Teen / Kidney 7,633.59 l ~Tc-99m 9.33E-05 Teen /TB 32,154.3 Ru-103 1.69E-03 Teen /TB 1,775.15 Ag-110m 4.76E-02 Teen /TB 63.03 Cd-113m 7.38E-02 Adult /CI (LLI) 135.50 Sb-124 9.34E-03 Teen /TB 321.20 Sb-125 3.13E-02 Teen /TB 95.85 Te-127 9.04E-03 Teen /CI (LLI) 1,106.19 Te-127m 1.71E-01 Teen / Kidney 58.48 OD0589-1333A-BA01
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'p : VOLU'ME,' 25 BIC ROCK POINT RADIOLOGICAL 4
- o. Revision 4 EFFLUENT T/S ~ REQUIRED. DOCUMENTS : Page 76 of 79 A.- OFFSITE DOSE CALCULATIONS Table 2.2 BIC ROCK POINT DESICN OBJECTIVE ANNUAL QUANTITIES FOR LIQUID EFFLUENTS AS DETERMINED BY LADTAP .
.Te-129m 3.27E Adult /CI (LLI) 30.58 I-130 1.40E-02 Child / Thyroid 714.29
'I-131 4.07E-01 Child / Thyroid. 24.57 Te-131m 2.78E-01 Adult /CI (LLI) 35.97 I-132 1.95E-05 Teen /TB 1.538 2 105-Te-132 3.59E-01 Adult /CI (LLI) 27.86 I-133 4.85E-02 Child / Thyroid 206.19 Cs-134 3.49E+00 Adult /TB 0.8596 I-134 1.59E-03 Teen /TB 1,886.79
.I-135 '1.91E-03 Child / Thyroid 5,235.6 Cs-136 5.05E-01 Adult /TB 5.94 Cs-137 2.08E+00 Adult /TB 1.44 Cs-138 1.52E-03' Teen /TB 1,973.68 Ba-139 3.05E-05 LTeen/TB 98,360.7
.Ba-140- 2.75E-03 Adult /CI (LLI) 3,636.36 La-140 2.27E-02 Adult /CI (LLI) 440.53
,s Ce-141 2.30E-04 Teen /TB 13,043.5 C2-144 4.08E-03 Adult /CI (LLI) 2,450.98' Eu-152 1.99E-01 Teen /TB 15.08 W-187 2.43E-01 Adult /CI (LLI)- 41.15 Np-239 2.78E-03 Adult /CI (LLI) 3,597.12 CD0589-1333A-BA01
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- 1 l VOtUMD 25 BIC ROCK POINT RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 78 of 79 j A. OFFSITE DOSE CALCULATIONS III. URANIUM FUEL CYCLE DOSE III.A SPECIFICATION In <accordance with Technical Specification 13.1.6.1, if either liquid or gaseous quarterly releases exceed the quantity which would cause offsite doses more than twice the limit of Technical Specification 13.1.4, then the cumulative dose contributions from combined release plus direct radiation sources (from the reactor unit and radwaste storage tanks) shall be caleclated. This calculation is performed to ensure that the annual (calendar year) dose or dose commitment to any member of the public is 525 mrem to the total body or any organ, except the thyroid, which shall be 575 mrem. The dose is to be determined for the member of the public projected to be the most highly exposed to these combined sources. If the results of this calculation show the dose to exceed either the 25 or 75 mrem limit, a special report shall be prepared and submitted to the Commission within 30 days, as described in Technical Specification 13.1.6.1.
III.B ASSUMPTIONS III.B.1 The full time resident determined to be the maximally exposed individual (excluding infant) is assumed also to be a fisherman.
This individual is assumed to drink water and ingest local fish at the rates specified in Sections II.C.4.1 and II.C.4.2.
III.B.2 Amount of shoreline fishing (at accessible shoreline adjacent to site security fence) is conservatively assumed as 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> per quarter (average of approximately 1/2 hour per day each day of the quarter) for the second and third quarters of the year, 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> for the fourth quarter and 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> for the first quarter.
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-g yO1 ME 25 BIC ROCK. POINT-RADIOLOGICAL Revision 4 EFFLUENT T/S REQUIRED DOCUMENTS Page 79 of-79 A. OFFSITE DOSE CALCULATIONS III.C . DOSE CALCULATION Maximum doses to the total' body and : internal organs of.an.indi-vidual shall be determined _by use of : LADTAP and CASPAR computer.
codes, and doses'to like organs and total body summed. Added'to-this sum will be.a mean dose rate, calculated or' measured for the shoreline due to plant presence during the quarter in question,'
times the assumed fishing time:
-D4 o ,= Da + DL + (RT )(T) t (III.1) where:
D4 o,E' = 40 CFR 190' dose to organ (i) (arem).
DC = Cumulative' dose to an individual organ from gaseous releases
'(mrem).
DL = Cumulative dose to an individual organ from liquid releases (mrem).
, RT = Mean dose rate (direct radiation component) calculated 'to be applicable to Lake Michigan shoreline adjacent to plant site (mrem /hr).
T. = Assumed shoreline fishing time for the ' quarter in question (hours) (see'Section III.B.2).
NOTE: For this calculation, total body is considered as an organ.
CD0589-1333A-BA01
((P50lESSUbUEE05P50 GRAM Page 1 of L }
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PROCES3 CONTROL PROGRAM (PCP)
~
< . 1.0 ' PROGRAM OVERVIEW 1.1 Liquid vastes are treated by filtering and demineralization for clean vastes and either recycled or released to Lake Michigan. Bead resin and filter media vill be shipped devatered as described in Section 2.0.
Liquid vastes, if ~ required, vill be processed using the methodology described in Section 3.0, if solidified, or Section 5.0, if absorbed for-shipment to Richland only.
2.0. DEWATERING SOLIDS IN HIGH DrfEr:RITY CONTAINERS (HIC) 2.1_ Solids such as bead resin and' filter media vill be devatered and shipped in HICs per approved vendor procedures and.the HIC certificate of com-pliance.
2.2 High integrity contain*_1 are approved by the individual burial ground agreement states as meeting 10 CFR 61 waste form stability requirements.
.2.3 Free water determination shall be verified by the successful completion and documentation of the vendors approved devatering procedure.
3.0 DELVARE CUSTOM MATERIAL (DCM) - SILICATE CINENT Liquid vastes can be solidified by the DCM method. The silicate solidi-fies and the cement gives structural strength.
31 For solidification, acquire a representative sample of vaste. Before following the guidelines outlined below, determine the type of vaste to be solidified, example, lab waste, laundry vaste, decon solutions, boric
~
acid, oil, etc., Sample for,JH2 borie acid. visible organics and radio -
activity. __
_ Use' analysis to determine the proper laboratory procedure to test. . -
All batches shall be lab tested prior to solidification in a larger con-ta. er unless sample analysis (pH
- 20%) matches the analysis of a vaste type which has previously passed lab test criteria.
For all oil vaste, do not exceed 50% by volume. Oil must be emulsified with a detergent or boric acid in some type of neutral aqueous vaste or tap water.
NOTE: 011 cannot be shipped to Ba:nvell, South Carolina.
For spent resins, liquid abosrbent, or other earthen-like material, di-lute with an equal volume of concentrate or tap water to solidify.
All results must be recorded initially, at approximately Rh hours and approximately h8 hours after testing. Grade observations to evaluate sample mixes. The h8-hour test can be omitted if the 2h-hour test is good.
The quantity of chemicals added to solidify radvaste shall be within 20%
of the quantity as determined by the laboratory test of Step G.
i i . f. VeLUME 25 3RP RADIOLOG CAL EFFLUENT T/S REQUIRED DOCUMENTS ' Rev O' B. PROCESS CON ~ROL PROGRAM Page 2 of4 e ,
.t.1 32 SOLTDIFICATIOR AND FREE VATER DETERMIMATIOR o
Solidification shall be considered successful. if, kB hours after com-pletion of Appendix A solidification, there is not standing water on the vaste surface and the. surface is not penetrated more than 2" with a 1" diameter rod. .If deeper penetration is possible, then the' drum' can still be considered solid if the penetration hole remains open after the rod is withdrawn.
H Silicate cement shall cure for a minimum of 28 days prior to shipment !
for disposal. . For silicate cement drums, the follovf.ng shall be done:
j Each drum shall be inspected for absence of detectable freestanding liquid after curing at least'28 days. With the drum lid installed, 7
invert each drum and allow drum to remain upside down for at least.
E
~ 2h hours.
n After 2h hours, inspect each drum by placing upright, and removing. the lid. The Radvaste Supervisor or designate and a QC Inspector shall inspect each drum for presence.of liquid. Druas which failed the L8 hour solidification evaluation should be capable of passing at this point. If no detectable freestanding liquid is present, the drum can be prepared for shipment. Radvaste Supervisor and QC Inspector docu-ment if no detectable freestanding liquid is present.
In the event liquid is observed. those drums with liquid shall be drain-ed of all liquid. When no further liquid can be drained from the drum
~ ~
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in a 2h-hour period, the drum shall be core-bored or overpacked with _ -
~_ two thgs of approved' ab' sorbent and inspected by QC and RadOaste Guper-
- visor to verify that the. drum is dry. After this verification (and ,
documentation) the drum may be prepared for shipment. - ..
Inspect the drum lid and gasket for defects prior to lid installation.
Install lid. Use a different lid if defects are found which prevent a tight seal between drum and lid.
h.0 10 CFR 61 REQUIRDENTS k .1' 10 CFR 61 classification requirements vill be met using Wastetrak computer softvare program using the scaling factor methodology of AIF/
NESP-027. Methodologies for Classification of Low-Level Radioactive Wastes From Nuclear Power Plants, 1983 The scaling factors vill be updated by an ongoing analysis program of actual vaste streams. The program vill initiate with semiannual samples of available vaste streams and may be modified to longer intervals if the data base warrants. Waste streams should include, if available; bead resin, reactor coolant, clean vaste, filter crud, and compacted trash.
h.2 ~ Documentation of the vaste stream analysis, vaste form stability and computer software sealing factor security shall be maintained by the Palisades RMC section.
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' VOLUME 25 BRP- RADIOLOGI' CAL' EFFLUENT T/S REQUIRED DOCLHENTS Rev 0
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. B. PROCESS CONTROL PROGRAM L . . ,
50 ABSORBED MATERIALS (Richland Burial Site Only) 5 1 . PACKAGING , ABSORBED, LIQUI,DSg IWCLt! DING 0,ILS Container must meet DOT Specification TA requirements as listed in h9 CTR.
Container must be lined with h mil plastic liner and sealed at the top when container is packed.
Container must be filled with enough absarbent material to absorb at least tvice the volume of radioactive liquid contents (ratio based on absorbency and not on volume or veight). Liquid should be placed at approximately every 12 inches of absorbent to ensure even dispersion.
52 PACKAGING OE SC_INTIT.LATION VIALS Container must meet DOT Specification 7A requirements as listed in h9 CFR.
Container must be lined' vith h , mil plastic liner and sealed at the top when container is packed. It is recommended that a layer of absorbent be placed in the bottom of the drum prior to the installation of the plastic liner. ,
Place approximately 3 inches of abosrbent at the bottom of the con-tainer, inside the plastic liner. Vials and absorbent must be placed in the container in alternate layers not exceeding 5 inches in' depth.
The vials are NOT to be opened. -
Container must be filled with enough absorbent material to absorb at least twice the volume of radioactive liquid contents (ratio based on absorbency not on volume or weight).
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TABLE I - ABSORBERTS I
A. . Diatomaceous Earth (Medium Grind)
B. Speedi' Dry 1
- .C. Celatom (M-P 78)
'_ D . . Floor Dry - Super Fine
, .E. Ei Dri F. T1orco and Florcox G. ~ Instant-Dri 4
H. Safe-T-Sorb I. Oil-Dri (Safe n Dri)
J. Zonolite'- Grade No. . 2, 3 or k (Vemiculite) h ' Absorbency efficiencies and volumes of absorbent required could vary. In al1~
'=
cases, it . is the responsibility- of the vasta generator and/or packager to .de-termine the efficiency and proper proportions required for the liquids being absorbed.
' A vritten request must be submitted and Departmental approval received prior' to
.use of- any absorbent not listed in Table 1. This request must contain the fol-v loving information:
- 1. A statement of the absorbency of the material as determined by the.manu-
- facturer and' copy of_ the manufacturer's_ descriptive information. ,
- 2. . . Absorbency for the actual liquid to be disposed must be determined by a e bench test (e.g. , Westinghouse, Gardner Coleman). .
3 Additional factors such as vibration tests, gas generation, long ' term chem-ical and radiological stability..
Approval of the absorbent or the procedure approval by the Department does not alter any liability or surety arrangements.
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