ML20216A961
| ML20216A961 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/01/1997 |
| From: | Popa T CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20216A940 | List: |
| References | |
| PROC-970101, NUDOCS 9805140316 | |
| Download: ML20216A961 (95) | |
Text
'
BIG ROCK POINT NUCLEAR POWER PLANT PROCEDURE APPROVAL AND AUTHORIZATION f
Procedure No.
VOLUME 25 Rev No.
13 Procedure Title BIG ROCK POINT RADIOLOGICAL EFFLUENT T/S RE0VIRED DOCUMENTS A. OFFSITE 00SE CALCULATIONS B. PROCESS CONTROL PROGRAM CURRENT REVISION STATUS Author TFPopa Date 12/16/96 Quality Review Form No. 1375-96 APPLICABILITY ISSUE HISTORY Revision No.
N/A Date N/A Quality Review Form No.
N/A f[ 7
/
Approved for use Procedure Sponsor / Designate.
p Date /- / - 9 Authorized Period of Use N/A throuah N/A BEFORE USING THIS PROCEDURE FOR WORK ACTIVITIES, VERIFY WITH THE RESPECTIVE PROCEDURE CONTROLLING DEPARTNENT THERE ARE NO OUTSTANDING TENPORARY CHANGES When applicable:
PROCEDURE IMPLEMENTATION HISTORY Reviewed for System or Component Operability Performed by Completed / Reviewed by Method of Verification Title Title O Functional Test O Physical Inspection Date Time Date Time O Administrative Review AMMS WORK ORDER NO. (if applicable) 9805140316 980430 gDR ADOCK 05000155 PDR
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Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS Page I of 2 A.
OFFSITE DOSE CALCULATIONS B.
PROCESS CONTROL PROGRAM TABLE OF CONTENTS / EFFECTIVE PAGES E.EVISION PAGES 13 92 A.
0FFSITE DOSE CALCULATIONS PURPOSE RE0VIREMENTS I.
GASE0US EFFLUENTS 1.A ALARM / TRIP SET POINT METHOD I.B DOSE CALCULATION DESIGN BASIS QUANTITY (DBQ) LIMITS I.C GASE0US RADWASTE TREATMENT SYSTEM OPERATION I.D I.E OFFSITE MPC RELEASE RATE I.F PARTICULATE AND IODINE SAMPLING I.G NOBLE GAS SAMPLING I.H TRITIUM SAMPLING II.
LIOUID EFFLUENTS II.A ALLOWABLE CONCENTRATION II.B INSTRUMENT ALARM SET POINTS II.C DOSE i
OPERABILITY OF LIQUID RADWASTE EQUIPMENT II.D II.E OFFSITE MPC RELEASE RATE
_RANIUM FUEL CYCLE 00SE U
III III.A SPECIFICATION III.B ASSUMPTIONS III.C DOSE CALCULATION APPENDIX A DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING REQUIREMENTS I
I I
I
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OFFSITE DOSE CALCULATIONS B.
PROCESS CONTROL PROGRAM TABLE OF CONTENTS / EFFECTIVE PAGES REVISION PAGES B.
1.0 PROGRAM OVERVIEW
{
2.0 DEWATERING SOLIDS IN HIGH INTEGRITY CONTAINERS (HIC) 3.0 DELWARE CUSTOM MATFRIAL (DCM)-SILICATE CEMENT 4.0 10 CFR 61 RE0VIREMENTS 5.0 ABSORBED MATERIALS (RICHLAND BURIAL SITE ONLY) l l
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VOLUME 25 BIG ROCK POINT RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS Page 1 of 92 l
A.
OFFSITE DOSE CALCULATIONS PURPOSE The purpose of this manual is to provide the methodologies and l
parameters used to:
Calculate offsite doses consistent with 10 CFR 50, Appendix I, 1.
during routine operations.
2.
Determine alarm / trip set points of effluent monitoring instrumentation.
l RE0VIREMENTS This manual is required per Technical Specifications:
6.9.2.2.A.4 - Radiological Impact on Man 13.1.1
- Radioactive Effluent Monitoring Instrumentation Operability and Surveillance Requirements 13.1.2
- Liquid Effluent Co'ncentration 13.i.3
- Gaseous Effluent Dose Rate 13.1.4
- Effluent Dose Review, approval, issue and cotitrol is performed per Volume 1, Administrative Procedure 1.2.
Changes to this manual shall be submitted to the Commission in 1
accordance with Technical Specification Administrative Controls, Section 6.15.
Format of ODCM is such to be consistent with other plants NOTI:
ODCM.
I Whenever MPC and 10 CFR 20 are mentioned in this 00CM, it NOTE:
means HPC values from the old 10 CFR 20 (prior to the NRC final rule published on May 21,1991) unless specifically stated otherwise. The NRC has not changed tb? dose
(
conversion factors of Regulatory Guide 1.109 which is the l
basis for demonstrating compliance with 10 CFP. 50, l
Appendix I doses, the tables of this ODCM, and gaseous effluent dose rate limits of Technical Specification 13.1.3.
The use of the old MPC values of 10 CFR 20 are appropriate for use with these doseUse of conversion factors and design basis quantities.
the new 10 CFR 20 effluent concentrations without changes to Regulatory Guide 1.109 Will give incorrect results.
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GASE0US EFFLUENTS 1.
ALARM / TRIP SET POINT METHOD I.A Technical Specification 13.1.3.1 requires that the dose in unrestricted areas due to gaseous effluents from the site shall be limited when averaged over a period not to exceed one hour to the following values:
500 mrem /y to the total body and 3,000 mrea/y to the skin from 1.
noble gases.
1,500 mrem /y to any organ from radioiodines and particulates, 2.
due to inhalation.
Specification 13.1.1.1 requires gaseous effluent m over one hour, will not exceed the dose rate limits ofThis section o Specification 13.1.3.1. methodology that will be used to determine the The methodology for determining alarm / trip set points is divided The first consists of calculating an allowable concentration for the nuclide mixture to be releas into two major parts.
The seco id consists of determining monitor response to this mixture in order to establish the physical settings on the monitors.
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Allowable Concentration I. A.1 The total MPC-fraction (R) for the stack relea l
Ci (I.1)
= sl.0 R=(f)(F)
[,
MP i
where:
The measured or calculated concentration, at ambient temperature and pressure, of nuclide i (pci/cc) at the Ci g
stack.
The MPC of nuclide i from 10 CFR 20, Appendix 8.
MPC 4
The total MPC-fraction for the stack release point.
R
=
Most conservative sector site boundary dispersion X/Q
=
(9.12E-08 sec/m*).
i Release flow rate (39,000 cfm = 18.4 m*/sec) for stack i monitor considerations; variable for other monitors.
F
=
I.A.2 Monitor Response Normal radioactivity releases consist predominantly of 30-mi Therefore, stack monitor response decayed fission gases. cal.ibrations are performed to fission releases (30-minute-decayed off-gas).
measures only slightly decayed gases, however, so is cali provide accurate response to relatively fres under accident conditions may vary from that o however.
determined as follows:
Normal Releases (30-minute-decayed fission gasses) 1.
Total gas concentration (pci/cc) at the monitor is calcula The calibration curve or constant for cpm /(pci/cc) to determine cpm expected.
established at some factor (b) greater than 1 but less than
)
1/R (Equation I.1) times the measured concentration (c)
(I.2) s-bxc l
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OFFSITE DOSE CALCULATIONS Page 4 of 92 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.
Implementing Procedures contain monitor-specific curves orEmergency calibration constants for conversion between cpm and pCi/cc product mixtures as a) function of mixture decay time.(or r 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.
are established as in 1 above.
In these cases, set points I.B DOSE CALCULATION I.B.1 Doses are calculated for (1) noble gases and (2) iodines and particulates.
Doses as defined in this section are based on 10 CFR 50, Appendix I limits of mrem per quarter and millirem per All dose pathways of major importance in the Big Rock year.
environs are considered.
I.B.1.1 Equations and assumptions for calculating doses from noble gases are as follows:
1.B.1.1.1 Assumptions 1.
Doses to be calculhted 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 radionuclide mix is based on the historically observed source term given in Table 1.1, plus additional nuclides.
4.
Basic radionuclide data are given in Table 1.2.
5.
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.
\\
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OFFSITE DOSE CALCULATIONS Oose is to be evaluated at the offsite exposure points where maximum concentrations are expected to exist, and nearest 8.
residents.
J Potential maximum population (resident) exposure points are 9.
identified in Table 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.
- 13. A sector-average dispersion equation is used.
- 14. The wind speed classes that are used are as follows:
Wind Speed Class Numbgr Ranae (m/sl Midooint (m/sl 0.0-0.4 0.0 1
0.95 0.4-1.5 2
2.25 1.5-3.0 3
4.0 3.0-5.0 4
6.25 5.0-7.5 5
8.75 7.5-10.0 6
7
>10.0 The stability classes that will be used are the Standard A The stability Classes 1-7 will 15.
through G classifications.
correspond to A - 1, B = 2...G = 7.
Terrain effects are not considered, and no open terrain 16.
recirculation factors are applied.
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OFFSITE DOSE CALCULATIONS I.B.'l. l. 2 Equations To calculate the dose for any one of the exposure points, the I
following equations are used:
for determining the air concentration of any radionuclide:
7 7
)
- P I-Al Xi" b
b
(
) ~ Z u (2xx/n) j=1 K-1 X
- P I
)
(I.3)
Zk where:
Air concentration of radionuclide i, pCi/m*.
X
=
j Joint relative frequency of occurrence of winds 'in wind speed class j, stability class k, blowing toward f
dk this exposure point, expressed as a fraction.
Average release rate of radionuclide 1, pCi/s.
Qj
=
Fraction of radionuclide remaining in plume.
P
=
Vertical dispersion coefficient for stability class k I
=
zk (m).
Midpoint value of wind speed class interval j, m/s.
uj Downwind distance, m.
x
=
Number of sectors, 16.
-I.
n
=
Radioactive decay coefficient of radionuclide 1, s A
=
j Sector width at point of interest, m.
2xx/n
=
Stack height (73 meters).
h oy
=
Vertical dispersion coefficient of stability class k.
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For determining the total body dose:
(I.4)
DFB DTB "
bXi 4
i where:
Total body dose mrem /y.
D TB Ci/m*.
Air concentration of radionuclide i, X
=
g Total body dose factor due to gamma radiation, mrem /y DFB 4
per pCi/m* (Table 1.5).
For determining the skin dose:
(I.5)
[
X,(DFSj + 1.11 DFY )
g D
s i
where:
Skindosemrem/y.
D s
Air concentration of radionuclide i, yci/m*.
X j
Skin dose factor due to beta radiation, mrem /y per DFS g
l2Ci/m* (Table 1.5).
The average ratio of tissue-to-air energy absorption 1.11 coefficients, mrem / mrad.
G;mma-to-air dose factor for radionuclide i, mrad /y DFY 4
per gCi/m* (Table 1.5).
For determining dose rate to a point in air:
(I.6) or DFB )
D, -
E Xj (DFY3 g
i where:
Airdosamrad/y.
D, =
Air d.ise factor for beta radiation (Table 1.5).
DFB =
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OFFSITE 00SE CALCULATIONS I
Equations and assumptions for calculating doses from radiciod l
I.B 1.2 and particulates are as follows:
I.B.1.2.1 Assumptions Oose is to be calculated for the critical organ, thyroid, and the critical age groups (adult, teen, child, infant), infant 1.
(milk) and child (green, leafy vegetables).
Exposure pathways from iodines and parti 2.
home gardens and inhalation.
The radiciodine and particulate mix is based on the historically observed source term given in Table 1.1.
3.
Source term (s) may be changed if radionuclide mix differs significantly from the historical source terms N_0JTE:
Q per Technical Specification 13.1.3.3 - Sampling and Analysis.
Basic radionuclide data are given in Table 1.2.
~
4.
All releases are treated as elevated (73 m).
5.
Annual average X/Qs are given in Table 1.3.
6.
Raw meteorological data for elevated releases consist of w 7.
speed and direction measurements at 71 m.
Dose is to be evaluated at the potential offsite exposure points where maximum doses to man are expected to exis 8.
Actual cow, goat and garden locations are considered.
9.
- 10. Potential maximum exposure points (Table 1.4) considere the nearest cow, goat and home garden locations in each sector.
- 11. Terrain effects are not considered.
- 12. Plume depletion and radioactive decay are considered for air-concentration calculations.
- 13. Radioactive decay is considered for ground-concentration calculations.
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OFFSITE DOSE CALCULATIONS l
- 14. Milk cows and goats obtain 100%'of their food from pastureUse default grass May through October of each year.0.58 for cows an pasture.
- 15. Credit is taken for shielding by residence (factor of 0.7).
1.B.1.2.2 Equations To calculate the dose for any one of the potential maximum-exposure points, the equations of Sections I.B.I.2.2.1-I.B.1.2.2.5 are used.
I.8.1.2.2.1 Inhalation Equation for calculating air concentration, X, is the same as in the Noble GasSection I.8.1.1.2 (Equation I.3).
For determining the organ dose rate:
D
= 1 x 10
[
X OFI BR (I.7) 6 j
g g
i where:
Organ dose due to inhalation, mrem /y.
D7-Airconcentrationofradionuclide1,pCi/m*.
Xj=
Inhalation dose factor, mrem /pci (Table 1.7).
DFI 4=
Breathing rate 1,400 m*/y, infant; 3,700 m*/y, child; BR =
F or 8,000 m*/y, adult and teen.
I 6
pCi/yCi conversion factor.
1 x 10 25PARTA 12/16/96 1
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0FFSITE DOSE CALCULATIONS I.B.1.2.2.2 Ground Contamination For determining the ground concentration of any nuclide:
7 t )] [exp (
)]
(I.8) 7
[1 - exp - (Aj G
- 3.15 x 10
{
2x n b
9 k=1 where:
Ground concentration of radionuclide i, pCi/m2 G
=
j Stability class, k
=
J int relative frequency of occurrence of winds in fk stability class k blowing toward this exposure
=
point, expressed as a fraction.
Average release rate of radionuclide i, pCi/s.
Qj
=
Relative deposition rate,1/m.
DR
=
k Downwind distance, m.
x =
Number of sectors, 16.
n Sector width at point of interest, m.
2xx/n
=
Radioactive decay, efficient of A
=
j radionuclide i, y Time for buildup of radionuclides on the t
=
b ground, 35 y.
7 s/y conversion factor, 3.15 x 10 Stack height (73 m).
h Vertical dispersion coefficient (m ) of stability 2
2 0 zk class.
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OFFSITE DOSE CALCULATIONS For determining the total body or organ dose from ground j
contamination:
g - (8,760)(1 x 10 )(0.7) {
G DFG (I.9) 6 4
j D
i where:
Dose due to ground contamination, mrem /y.
Dg-Ground concentration of radionuclide i, pCi/m.
2 Gg=
Dose factor for standing on contaminated ground, DFGg=
mrem /h per pCi/m2 (Table 1.8).
8,760 =
Occupation time, h/y.
6 pCi/pCi conversion factor.
1 x 10
=
Shielding factor accounting for a distance of 1.0 0.7 -
meter above ordinary ground, dimensionless, i
l l
l
\\
l l
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OFFSITE DOSE CALCULATIONS f
I.8,1,2.2.3 Milk and Vegetation Ingestion For determining the concentration of any nuclide (except C-14 and H-3) in and on vegetation:
i 7
(I.10)
+
CV4 - 3,600
{
Y A x n k=1 t
iv II - e o (-A B
bil )exp (2
) **P (~Ai t) i h
zk i
where:
Concentration of radionuclide i in and on vegetation, CV
=
4 pCi/kg.
Stability class.
k Frequency of this stability class and wind direction fk combination, expressed as a fracticn.
Average release rate of radionuclide i, pCi/s.
Q
=
Relative deposition rate as a function of wind speed, stability class and downwind distance, m-1 (Figures 7 DR
=
k through 10 of Regulatory Guide 1.111).
Downwind distance, m.
x
=
Number of sectors, 16.
n Sector width at point of interest, m.
2xx/n Fraction of deposited activity retained on vegetation (1.0 for iodines, 0.2 for particulates).
r
=
where Effective removal rate constant, AEi " Ai+A is the radioactive decay coefficient, h-1,w,n A
Ei a
A 9is a measure of physical loss by weathering (X, =.0021 h-I).
Period over which deposition occurs, 720 h.
t,
=
2 Agricultural yield, 0.7 kg/m,
Y y
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OFFSITE DOSE CALCULATIONS Transfer factor from soil to vegetation of 8
4V radionuclide i (Table 1.6).
Radioactive decay coefficient of radionuclide i, h'I A
j Timeforguildupofradionuclidesontheground, t
b 3.07 x 10 h (35y).
2 Effective surface density of soil, 240 kg/m,
P
=
s/h conversion factor.
3,600
=
Stack height (73 m).
h Vertical dispersion coefficient (m).
a z
H ldup time between harvest and consumption of food, 0 h for pasture grass or 2,160 h for storage feed.
t
=
h For determining the concentration of C-14 in vegetation:
(I.11)
X14.(0.11/0.16)
CV34 - 1 x 108 where:
Concentration of C-14 in vegetation, pCi/kg.
CVg4 =
AirconcentrationofC-14,pCi/m2 Xi4 =
Fraction of total plant mass that is natural carbon.
0.11 =
Concentration of natural carbon in the atmosphere, 0.16 -
8 g/m.
g/kg conversion factor.
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OFFSITE 00SE CALCULATIONS A.
r For determining the concentration of H-3 in vegetation:
(I.lla)
CVT = 1 x 108 XT (0.75)(0.5/H) where:
l Concentration of H-3 in vegetation, pCi/kg.
CVT-8 Air concentration of H-3, gCi/m.
XT=
Fraction of total plant mass that is water.
0.75 -
Ratio of tritium concentration in plant water to 0.5 -
tritium concentration in atmospheric water.
Absolute humidity of the atmosphere, g/m*.
H-g/kg conversion factor.
1 x 108
=
For determining the concentration of any nuclide in cow's or goat's milk:
t)
(I.12)
FM Q exp (-Ag CMg - CVg g
f f
where:
Concentration of radionuclide i (including C-14 and H-3)
CM4-in milk, pCi/1.
Concentration of radionuclide i in and on vegetatiore, CV4-pCi/kg.
Transfer factor from feed to milk for radionuclide i, d/1 FM'. =
(Table 1.6).
Amount of feed consumed by the milk animal per day, cow -
Q-f 50 kg/d, g,at - 6 kg/d.
Radioactive decay coefficient of radionuclide i, d'I A4=
Transport time of activity from feed to milk to receptor, tf-two days.
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VOLUME 25 EFFLUENT T/S REQUIRED DOCUMENTS OFFSITE DOSE CALCULATIONS A.
For determining the organ dose from ingestion of green leafy vegetables and milk:
6 (I.13)
D - 1 x 10
{
CM 0F UM g
4 i
where:
Organ dose due to ingestion, mrem /y.
D-Concentration of radionuclide i in vegetables or milk, CM) =
pCi/kg (or liters).
Ingestion dose factor, meem/pci (Table 2.1).
DF9-Ingestion rate for milk, 3301/y - infant and child, VM -
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.
6 pCi/pCi conversion factor.
1 x 10 I.B.1.2.2.4 Heat Ingestion (Beef)
To calculate the concentration of a nuclide in anim (I*I4) t)
exp (-Ag s
CV Qf Cf3 - Ffg g
where:
Concentration of nuclide i in the animal flesh, pCi/kg.
l Cfg -
Fraction of animal's daily intake which appears in each k Ffg =
of flesh, days /kg (Table 1.6).
Concentration of radionuclide i in the animal's f l
i CVj-(Equation I.10).
l Amount of feed consumed by the cow per day, 50 kg/d.
Q-f Average time from slaughter to consumption, 20 days.
t s
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OFFSITE DOSE CALCULATIONS To determine the organ dose from ingestion of beef:
Dp= {
C 0
U (1.15) 74 79 p
i where:
Ingestion dose factor for age group, mrem /pci (Table 2.1)
D '. -
7 for nuclide i.
Ingestion rate of meat for age group, kg/y (child - 41, Uf=
teen - 65, adult -110).
I.B.1.2.2.5 Organ Dose Rates For determining the total body, organ and/or thyroid dose rate from iodines and particulates:
(I.16) 0
-Dg+Dg+DM+Dy+Dp where:
Total organ dose, mrem /y.
D
=
Dose due to inhalation, mrem /y.
D y
f Dose due to ground contamination, mrem /y.
D g
Dose due to milk ingestion, mrem /y.
D 1
=
g Dose due to vegetable ingestion, mrem /y.
D y
Dose due to meat ingestion, mrem /y.
D p
The maximum organ dose rate, maximum total body dose rate, maximum skin dose rate plus beta and gamma air doses calculated in the I.B.1.2.3 previous section (Section I.B.I.2.2) are used to calculate design basis quantities as described in Section I.B.I.3.
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OFFSITE 00SE CALCULATIONS I.B'.1.3 Design Basis Quantities The design basis quantity of a radionuclide emitted to the atmosphere is the amount of that nuclide, when released in one year, which would result in a dose not exceeding any of the following:
15 millirems to any organ of an individual from iodines and 1.
particulates with half life greater than 8 days.
20-millirad air dose for beta radiation from noble gas (see 2.
note below).
10-millirad air dose for gamma radiation from noble gas (see 3.
note below).
Design basis quantity (Ci) is the smallest value for each nuclide, calculated by dividing the dose limits (a through c above) by the appropriate dose calculated in Step 1; the result then is multiplied by the amount of radionuclide (Ci) used to conserstively estimate the doses of Section D, as listed in Table 1.1 (or assumed a hypothetical i Ci/ year for nuclides not actually present):
(I.17)
DBQ = AI- (C )
c C
where:
Appendix I dose limit (mrem or mrad).
Dgg =
Calculated dose from Step 1 (mrem or mrad).
D
=
c Quantity of nuclide resulting in dose Dc (Ci).
C
=
c DBQ =
Design Basis Quantity (Ci).
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OFFSITE DOSE CALCULATIONS The limiting values for Design Basis Quantities for radionuclides released to the atmosphere are given in Table 1.9.
ROIE:
For conservative calculations the DBQs listed in Table 1.9 0
are based on:
1.
15 millirems to any organ of an individual from iodines and particulates 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.
in the above equation (ie, O /C }
The inverse of the ratio C /Dc c c is a useful value, since ik 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 annual land use census and revision of the ODCM for use in the following calendar year. Areas of the ODCM which will be reviewed and changed, if appropriate, are Table 1.4 (Land Use Census Data by Sector) and Table 1.9 (Gaseous Design Basis Objective Annual Quantities). Changes will be effective on January 1 of the year following the year of the survey.
I.C DESIGN BASIS QUANTITY (DBQ) LIMITS 1.C.1 Desian 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.
(1.18)
[ (DBQ), < 1.0 i
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OFFSITE DOSE CALCULATIONS I.C.2 Exceedina DB0 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, Because different organs are summed together Appendix I limits.and doses to different people are summed, the DBQ ty Thus, if overestimates dose by about a factor of five.
calculations of the DBQ fraction exceed 1.0 for yea l
However, further discretionary releases should not be exceeded.be deferred until an accurate assessment of dose is The computer run will utilize the the NRC GASPAR computer code.
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 Where appropriate, generated in the most recent prior year. seasonal adjustme estimates since both recreational and agricultural activities can vary greatly in relation to season of the year.
It should be noted that Big Rock Point to date (based on review of semiannual effluent data) has never exceeded the annual o 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 i
be required unless the plant is in a significantly off-normal j
condition.
1 i
25PARTA 12/16/96 i
Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL Page 20 of 92 EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS Releasina Radionuclides Not listed in Table 1.9 I.C.3 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 MPC-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 J
MPC-fraction, or all unlisted nuclides together constitute greater than 25%, then each nuclide should be assigned a DBQ equal to the most conservative value listed for the physical form of the nuclide involved (noble gas, halogen or particulate).
Should a nuclide not listed in Table 1.9 begin to appear in I
significant quantities on a routine basis, revision to this 00CM should be made in order to include a design basis quantity specific to that nuclide.
f GASEGUS RADWASTE TREATMENT SYSTEM OPERATION I.D I.D.1 System Descriotion 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 term. 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.D.2 Dgtermination 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.
25PARTA 12/16/96
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Revision 13 BIG ROCK POINT RADIOLOGICAL Page 22 of 92 VOLUME 25 EFFLUENT T/S REQUIRED DOCUMENTS l
A.
OFFSITE DOSE CALCULATIONS l
1.E OFFSITE RELEASE RATE 10 CFR 50.36a requires that the release of radioactive materials However, the section be kept as low as reasonably achievable.further states tha operation, to assure a dependable source of powe l
10 CFR 20 limits but not exceeding those 'imits under unusual l
Appendix I to 10 CFR 50 provides the operating conditions. numerical guidelines on limiting conditions for the as low as reasonably achievable requirement.
The GASPAR code has been run to determine the dose due The source term used is listed in radiation and inhalation.
Dose The meteorology data is given in Table 1.3.
Table 1.1.
using(annual average meteorology, to the most lim dose The release rate which highest X/Q, is 0.105 mrem for one year.would result in a dos body limit of Technical Specification 13.1.3.1) is the Curies / Year 500/.105 or 1.95 given in Table 1.1 (1.29E04) multiplied by Ci/sec.
The above calculation is informational as a typical exposure using
)
Actual exposure i
average releases from Big Rock Point.
l calculations are described in Section I.A.
l i
l l
l l
i l
25PARTA 12/16/96
VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 13 EFFLUENT T/S REQUIRED DOCUMENTS Page 23 of 92 A.
OFFSITE DOSE CALCULATIONS I.F PARTICULATE AND 10 DINE SAMPLING Particulate and iodine samples are obtained from the continuous sample stream pulled from the plant stack.
Samples typically are obtained to represent the integrated ralease from the stack.
Gamma analytical results for particulate and halogen filters are combined for determination of total activity of particulates and halogens released. Beta and alpha counting also is performed on the particulate filters.
Beta yields of the gamma isotopes detected on particulate filters are applied to determine
" identified" beta, and the " identified" count rate'is subtracted from the observed count rate to give " unidentified" beta. The
" unidentified" beta is assumed to be Sr-90 until results on actual Sr-90 (chemically separated from a quarterly composite of filters)
Similarly, alpha activity not identified as natural are obtained.
radium or thorium or their daughters is assumed as Pu-239 until results of detailed analyses are obtained from quarterly composites.
The "Stackgas" Program, used to calculate the release rates when analyzing the stack's particulate and iodine samples, takes the total release rate and ratios it to the allowable Sr 90 (most restrictive nuclide) release rate.
If the ratio is ;t 0.5, it warns that the Technical Specification 13.1.3.1.b limit may have been exceeded.
I.G N0BLE GAS 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)
I which has an LLD of IE-06 pCi/cc.
l i.
I.H TRITIUM SAMPLING Tritium has a low dose consequence to the public because of low The major contributors to tritium effluents are production rates.
evaporation from the fuel pool and reactor cavity (when flooded).
Because of the low dose impact, gaseous tritium sampling will not Tritium effluents will be estimated using be required.
conservative evaporation rate calculations frcm the fuel pool and l
i reactor cavity.
25PARTA 12/16/96
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0FFS11E DOSE CALCULATIONS TABLE 1.1 II)
BIG ROCK POINT GASE0US AND L10010 SOURCE TERMS. CURIES / Y l
Gaseous (2)
Licuid(2) suclide
-I-3 1.21E+01 8.63E+00 N-13 1.53E+03 NA Na-24 3.52E-04 1.12E-06 Cr-51 2.82E-04 6.84E-03 Mn-54 5.50E-05 2.60E-02 Mn-56 1.70E-04 NA Co-58 1.65E-06 6.17E-04 Fe-59 2.81E-06 9.05E-03 Co-60 1.89E-04 4.21E-02 Zn-65 3.16E-05 9.01E-04 Br-82 8.llE-03 NA Kr-83m 2.61E+02 NA Kr-85 9.55E-01 NA Kr-85m 3.12E+02 NA l
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 i
Sr-90 NA 2.22E-03 Kr-91 6.68E+00 NA Sr-91 5.61E-03 NA l-Sr-92 NA 1.54E-06 Nb-95 1.91E-06 NA Mo-99 3.10E-05 NA l
Ag110m 1.57E-05 6.88E-05 Sb-124 NA 4.01E-04 I-131 1.94E-03 1.57E-04 Xe-131m 4.38E-01 NA I-132 8.07E-03 NA I-133 1.99E-02 NA Xe-133 2.01E+02 8.86E-05 i
Xe-133m 6.00E+00 NA l
Cs-134 4.04E-07 1.75E-02 I-134 1.24E-02 NA I-135 3.00E-02 NA Xe-135 1.llE+03 NA i
Xe-135m 1.15E+03 NA Cs-136 4.74E-05 NA Cs-137 1.51E-04 2.04E-01 Xe-137 1.llE+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 7.80E-03 5.04E-05 Xe-140 7.23E+01 NA H -203 1.32E-06 NA N -239 1.44E-04 NA U identified Beta 2.42E-03 6.76E-02 (1) Data derived from taking the effluents released during Jan June 1980 h July-December 1983 and dividing by 4.
throu9 Nuclide values listed as NA have not been observed at detect (2) in these waste streams.
)
25PARTA 12/16/96 i
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A.
OFFSITE DOSE CALCULATIONS TABLE 1.2 l
l BASIC RADIONUCLIOE DATA 1
I NUCLIDE HALF-LIFE LAMBDA BETA GAMMA (days) 11/11 (MEV/ DIS)
(MEV/ DIS) 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 l
3 N-13 6.94E-03 1.16E-03 4.91E-01 1.02E 00 l
4 0-19 3.36E-04 2.39E-02 1.02E 00 1.05E 00 5
F-18 7.62E-02 1.05E-04 2.50E-01 1.02E 00 6
NA-24 6.33E-01 1.273-05 5.55E-01 4.12C 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 i
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 C0-58 7.13E 01 1.12E-07 3.41E-02 9.78E-01 14 C0-60 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 1.04E 00 6.60E-02 19 KR-85m 1.83E-01 4.38E-05 2.53E-01 1.S9E-01 20 KR-85 3.93E 03 2.04E-09 2.51E-01 2.21E-03 l
21 KR-87 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 23 KR-89 2.21E-03 3.63E-03 1.36E 00 1.83E 00 24 R8-88 1.24E-02 6.47E-04 2.06E 00 6.26E-01 25 RB-89 1.07E-02 7.50E-04 1.01E 00 2.05E 00 26 SR-89 5.20E 01 1.54E-07 5.83E-01 8.45E-05 27 SR-90 1.03E 04 7.79E-10 1.96E-01 0.0 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-01 6.06E-02 38 NB-95 3.50E 01 2.29E-07 4.44E-02 7.64E-01 39 M0-99 2.79E 00 2.87E-06 3.96E-01 1.50E-01 l
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 1
25PARTA 12/16/96 1
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VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 13
)
EFFLUENT T/S REQUIRED DOCUMENTS Page 26 of 92 A.
OFFSITE DOSE CALCULATIONS I
TABLE 1.2 (continued)
BASIC RADIONUCLIDE DATA 1
1 NUCLIOE HALF-LIFE LAMBDA BETA GAMMA (days)__
[l/_$_).
(MEV/ DIS)
(MEV/ DIS) s 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 1-129 6.21E 09 1.29E-15 5.43E-02 2.46E-02 46 I-131 8.05E 00 9.96E-07 1.90E-01 3.81E-01 47 I-132 9.58E-02 8.37E-05 4.89E-01 2.24E 00 48 1-133 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 1-135 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 7.29E-15 5.63E-02 0.0 60 CS-136 1.30E 01 6.17E-07 1.37E-01 2.15E 00 61 CS-137 1.10E 04 7.29E-10 1.71E-01 5.97E-01 62 CS-138 2.24E-02 3.58E-04 1.20E 00 2.30E 00 63 BA-139 5.76E-02 1.39E-04 8.96E-01 3.53E-02 64 BA-140 1.28E 01 6.27E-07 3.15E-01 1.71E-01 65 LA-140 1.68E 00 4.77E-06 5.33E-01 2.31E 00 66 CE-144 2.84E 02 2.82E-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 l
Average energy per disintegration values were obtained from ICRP Publication 1
No 38, Radionuclide Transformations: Enerav and Intensity of Emissions, 1983 and NUREG/CR-1413 (0RNL/NUREG-70), A Radionuclide Decay Data Base -
Index and Summary Table, D. C. Kocher, May 1980.
25PARTA 12/16/96
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1 1
Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS Page 35 of 92 A,
OFFSITE DOSE CALCULATIONS TABLE 1.3 USNRC COMPUTER CODE - X00000. VERSION 2.0 RUN DATE: 940629
- BIG ROCK POINT X0000082 **" USING 01/01/89 - 12/31/93 MET DATA "**
j i
ELEVATED RELEASE - 240' STACK SPECIFIC POINTS OF INTEREST l
RELEASE TYPE OF DIRECTION DISTANCE X/Q X/Q X/0 0/0 2
l 10 LOCATION FROM $1TE (MILES)
(METERS) (SEC/ CUB. METER) (SEC/ CUB. METER) (SEC/ CUB. METE s
NO DECAY 2.260 DAY DECAY 8.000 DAY DECAY
)
(
UNDEPLETED UNDEPLETED DEPLETED A
SITE BOUNDARY E
0.57 917.
4.91E-08 4.90E-08 4.85E-08 1.25E-09 l
A SITE BOUNDARY ESE 0.52 837.
4.11E-08 4.10E-08 4.07E-08 1.16E-09 i
A SITE BOUNUARY SE 0.55 885.
3.09E-08 3.08E-08 3.05E-08 8.19E-10 j
A SITE BOUNDARY SSE 0.58 933.
2.25E-08 2.24E-08 2.22E-08 5,12E-10 l
A SITE BOUNDARY S
0.68 1094.
2.07E-08 2.06E-08 2.03E-08 3.68E-10 9
j A
SITE BOUNDARY SSV 0.71 1143.
1.95E-08 1.94E-08 1.91E-08 3.65E-10 A
$1TE BOUNDARY SV 0.50 805.
3.58E-09 3.57E-09 3.55E-09 1.16E-10 A
RESIDENCE / GARDEN ENE 2.30 3701.
4.55E-08 4.54E-08 4.44E-08 3.66E-10 l
A RESIDENCE / GARDEN E
1.40 2253.
5.20E-08 5.18E-08 5.07E-08 6.23E-10 A
RESIDENCE / GARDEN ESE 1.50 2414.
3.82E-08 3.81E-08 3.72E-08 4.47E-10
(
- 2736, 3.29E-08 3.28E-08 3.21E-08 3.07E-1G l
A RES:0ENCE/ GARDEN SSE 1.70 2736.
3.61E-08 3.59E-08 3.54E-08 2.22E-10 l
A RESIDENCE / GARDEN S
1.90 3058.
3.37E-08 3.35E-08 3.31E-08 1.42E-10 A
RESIDENCE / GARDEN SSV 1.30 2092.
2.62E-08 2.61E-08 2.56E-08 2.15E-10 l
A RESIDENCE / GARDEN SV 1.10 1770.
1.15E-08 1.15E-08 1.14E-08 8.66E-11 A
DAIRY COV E
2.50 4023.
3.75E-08 3.73E-08 3.61E-08 3.16E-10 A
DAIRY COV ESE 2.60 4184.
2.70E 08 2.68E-08 2.59E-08 2.25E-10 l
A DAIRY COV SE 4.50 7242.
1.67E-08 1.65E-08 1.59E-08 8.27E-11 A
DAIRY COV SSE 3.50 5633.
2.66E-08 2.65E-08 2.60E-08 9.29E-11 i
A BEEF COV E
2.50 4023.
3.75E-08 3.73E-08 3.61E-08 3.16E-10 i
A BEEF COV ESE 2.60
- 4184, 2.70E-08 2.68E-08 2.59E-08 2.25E-10 A
BEEF COV SE 2.00
- 3219, 3.09E-08 3.08E-08 3.01E-08 2.58E-10 A
BEEF COV SSE 3,50
- 5633, 2.66E-08 2.65E-08 2.60E-08 9.29E-11 A
BEEF COV 2.50 4023.
3.26E-08 3.24E-08 3.20E-08 1.02E-10 g
A GOAT SE 4.00
- 6437, 1.87E-08 1.85E-08 1.79E-08 9.96E-11 A
MAXIMUM CHI /O 2.00 3219.
3.37E-08 3.35E-08 3.31E-08 1.34E-10 A
MAXIMUM CHI /Q SSW 2.00 3219.
2.73E-08 2.71E-08 2.67E-08 1.31E-10 A
MAXIKUM CHl/Q SW 2.50 4023 1.85E-08 1.84E-08 1.82E-08 3.84E-11 i
A MAXIMUM CHl/Q VSV 50.00 80467.
0.00E+00 0.00E+00 0.00E+00 0.00E+00 A
MAXIMUM CHl/Q V
50.00 80467.
0.00E+00 0.00E+00 0.00E+00 0.00E+00 f
A MAXIMUM CHl/Q VNV 15.00 24140.
1.12E-07 7.29E-08 8.26E-08 1.30E-10 A
MAXIMUM CHI /O NV 50.00 80467.
0.00E+00 0.00E+00 0.00E+00 0.00E+00 A
MAXIMUM CHl/Q NNV 50.00 80467.
0,00E+00 0.00E+00 0.00E+00 0.00E+00 l
A MAXIMUM CHI /O N
50.00 80467.
0.00E+00 0.00E+00 0.00E+00 0.00E+00 f
A MAXIMUM CHl/Q NNE 2.00 3219.
4.47E-08 4.46E-08 4.43E-08 1.90E-10 A
MAXIMUM CHI /Q NE 1.50
- 2414, 4.63E-08 4.62E-08 4.54E-08 5.46E-10 A
MAXIMUM CHl/Q ENE 1.50 2414.
5.32E-08 5.30E-08 5.22E-08 5.79E-10 A
MAXIMUM CHI /Q E
1.00
'1609.
5.40E-08 5.39E-08 5.30E-08 8.96E-10 l
A MAXIMUM CHI /Q ESE 0.75
- 1207, 4.29E-08 4.28E-08 4.21E-08 9.15E-10 A
MAXIMUM CHl/Q SE 1.50 2414.
3.40E-08 3.38E-08 3.32E-08 3.60E-10 A
MAXIMUM CHI /O SSE 1.50 2414.
3.59E-08 3.58E-08 3.52E-08 2.57E-10 VENT AND BUILDING PARAMETERS:
RELEASE HEIGHT (METERS) 73.10 REP. WIND HEIGHT (METERS) 71.3 25PARTA 12/16/96
I Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS Page 36 of 92 A.
OFFSITE DOSE CALCULATIONS TABLE 1.3 NOTES Big Rock Point gathers meteorological data from sensors mounted on the 73 meter stack. A wind speed and wind direction sensor is mounted into the Because of interference to the wind flow by the prevailing wind direction.
stack when winds are from the 71* to 159' sector (flowing towards Lake Michigan), the meteorological data recorded in these sectors are considered invalid.
For dose calculational purposes, this effectively invalidates six (6) sectors (WSW, W, WNW, NW, NNW, and N). Therefore zeros are recorded in Table 1.3 for these sectors.
However, the program which calculates the annual average Chi /Q requires input of the full years met data.
Any data recorded for these six sectors are input in the WNW sector to satisfy the program.
Values of Chi /Q listed in the WNW sector are invalid.
During emergencies with wind directions into the above six sectors, the dose assessor is directed to alternate meteorological information by Emergency I
Procedures.
l I
l i
i 25PARTA 12/16/96
Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL Page 37 of 92 EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS TABLE 1.4 l
1996 BIG ROCK POINT LAND USE CENSUS REPORT Distance to the nearest residence, garden, milk cow, beef cow and goat in each sector.
Sector Residence Garden Dairy Cow Beef Cattle Goat _
WSW 2.5 mi
> 5 mi
> 5 mi
> 5 mi
> 5 mi SW l.1 mi 2.7 mi
> 5 mi
> 5 mi
> 5 mi SSW 1.3 mi
> 5 mi
> 5 mi
> 5 mi
> 5 mi S
1.9 mi 2.1 mi
> 5 mi
> 5 mi
> 5 mi SSE 1.7 mi 1.7 mi
> 5 mi 1.7 mi
> 5 mi SE 1.8 mi 1.8 mi 4.5 mi 1.8 mi
> 5 mi ESE 1.5 mi 1.8 mi
- 2.8 mi 3.2 mi
> 5 mi 1.4 mi 2.4 mi 3.5 mi 2.7 mi
> 5 mi E
ENE 2.3 mi
> 5 mi
> 5 mi
> 5 mi
> 5 mi
- HOIE: Farm bisected by E/ESE boundary line.
l l
25PARTA 12/16/96 i
Revision 13 BIG ROCK POINT RADIOLOGICAL Page 38 of 92 VOLUME 25EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS TABLE 1.4a 1997 BIG ROCK POINT GASPAR INPUT PARAMETERS l
Critical Receptors
)
X/Q X/Q Decay Distance X/Q Decay and Dep D/Q is_ec]_nt*1 (sec/m*1 (sec/m*)
(1/m )
2 e
Location Sector (miles L Residence / Garden E
1.40 5.20E-08 5.18E-08 5.07E-08 6.23E-10 l
Site Boundary E
0.57 4.91E-08 4.90E-08 4.85E-08 1.25E-09 Beef Cattle SSE 1.70 3.57E-08 3.56E-08 3.50E-08 2.30E-10 E
2.80 3.43E-08 3.41E-08 3.29E-08 2.75E-10 Dairy Cow e
'l!
25PARTA 12/16/96 1
l VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 13 EFFLUENT T/S REQUIRED DOCUMENTS Page 39 of 92 A.
OFFSITE DOSE CALCULATIONS DOSE FACTORS FOR SUBMERSION IN N0BLE GASES
- Table 1.5 I
I DFB DFY2 DFS 0FB2 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-87 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)
Xe-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/m8 2.
mrad /y per pC1/m8 3.
1.17(+3) = 1.17 x 108
- Dose factors for exposure to a semi-infinite cloud of noble gases.
Values were obtained from US NRC Regulatory Guide 1-109, Revision 1 (October 1977).
1 25PARTA 12/16/96
VOLUME 25 BIG ROCK P0lNT RADIOLOGICAL Revision 13 i
EFFLUENT T/S REQUIRE 0 DOCUMENTS Page 40 of 92 A.
OFFSITE DOSE CALCULATIONS STABLE ELEMENT TRANSFER DATA Table 1.6 B
Fm - Milk (d/L)
Fm -(Milk (d/L)
Goat) f - Heat (d/ko)
VeaNoil p
Element (Cow)
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-02 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 4.0F-02 6.6E-04 Co 1.0E-03 1.0E-03 1.3t A2 9.4E-03 Ni 6.7E-03 6.7E-03 5.3F 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 4.6E-03 2.6E-03 Zr 5.0E-06 5.0E-06 3.4E-02 1.7E-04 1
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 1.0E-06 1.0E-06 4.0E-01 5.0E-02 Rh 1.0E-02 1.0E-02 1.5E-03 1.3E+01 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 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 2.5E-03 Nd 5.0E-06 5.0E-06 3.3E-03 2.4E-03 W
5.0E-04 5.0E-04 1.3E-03 1.8E-02 Np 5.0E-06 5.0E-06 2.0E-04 2.5E-03 25PARTA 12/16/96
VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 13 EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS Page 41 of 92 TABLE 1.7 INHALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED)
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUi GI-LLI H
3 NO DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E MA 24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 l
P 32 1.45E-03 8.03E-05 5.53E-05 NO DATA NO DATA NO DATA 1.15E-05 CR 51 NO DATA NO DATA 6.39E-08 4.llE-06 9.45E-09 9.17E-06 2.55E-07 MN 54 NO DATA 1.81E-05 3.56E-06 N0 DATA 3.56E-06 7.14E-04 5.04E-06 MN 56 NO DATA 1.10E-09 1.58E-10 N0 DATA 7.86E-10 8.95E-06 5.12E-05 FE 55 1.41E-05 8.39E-05 2.'M -06 NO DATA fr DATA 6.21E-05 7.82E-07 FE 59 9.69E-06 1.68E-05 6.N E-05 NO DATA NO DATA 7.25E-04 1.77E-05 C0 58 NO DATA 8.71E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 C0 60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 NI 63 2.42E-04 1.46E-05 8.29E-06 N0-DATA NO DATA 1.49E-04
- 1. 73 E-06 NI 65 1.71E-09 2.03E-10 8.79E-Il NO DATA NO DATA 5.80E-06 3.58E-05 CU 64 NO DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 ZN 65 1.38E-05 4.47E-05 2.22E-05 N0 DATA 2.32E-05 4.62E-04 3.67E-05 ZN 69 3.85E-11 6.91E-Il 5.13E-12 NO DATA 2.87E-Il 1.05E-06 9.44E-06 BR 83 N0 DATA N0 DATA 2.72E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA N0 DATA 2.86E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 1.46E-08 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 RB 88 NO DATA 3.98E-07 2.50E-07 NO DATA NO DATA NO DATA 2.42E-07 RB 89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 SR 89 2.84E-04 N0 DATA 8.15E-06 NO DATA NO DATA 1.45E-03 4.57E-05 SR 90 2.92E-02 NO DATA 1.85E-03 NO DATA NO DATA 8.03E-03 S.36E-05 SR 91 6.83E-08 NO DATA 2.47E-09 NO DATA NO DATA 3.76E-05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E-10 N0 DATA NO DATA 1.70E-05 1.00E-04 Y 90 2.35E-06 NO DATA 6.30E-08 NO DATA NO DATA 1.92E-04 7.43E-05 Y 91m 2.91E-10 NO DATA 9.90E-12 NO DATA NO DATA 1.99E-06 1.68E-06 Y 91 4.20E-04 N0 DATA 1.12E-05 NO DATA NO DATA 1./5E-03 5.02E-05 Y 92 1.17E-08 NO DATA 3.29E-10 NO DATA NO DATA 1.75E-05 9.04E-05 Y 93 1.07E-07 NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-04 ZR 95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05 ZR 97 1.07E-07 1.83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1.00E-04 NB 95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 M0 99 NO DATA 1.18E-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3.48E-05 f
TC 99m 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06 t
25PARTA 12/16/96
VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 13 EFFLUENT T/S REQUIRED DOCUMENTS Page 42 of 92 A.
OFFSITE DOSE CALCULATIONS TABLE 1.7 INHALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED)
NUCLIDE BONE LIVER T.B0DY THYR 0ID KIDNEY LUNG GI-LLI 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-06 3.94E-04 1.15E-05 RU105 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E-10 1.12E-05
~.46E-GE RU106 6.20E-05 N0' DATA 7.77E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04 AG110m 7.13E-06 5.16E-06 3.57E-06 NO DATA 7.80E-06 2.62E-03 2.36E-05 TE125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06 TE127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81E-10 3.49E-10 1.32E-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 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE131m 7.62E-08 3.93E-08 2.59E-06 6.38E-08 1.89E-07 1.42E-04 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-04 3.15E-05 I 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 I 131 2.71E-05 3.17E-05 1.40E-05 1.06E-02
-3.70E-05 NO. DATA 7.56E-07 I 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1.36E-06 I 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 1.54E-06 I 134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21E-07 I 135 2.76E-06 5.43:.-06 1.98E-06 4.97E-04 6.05E-06 NO DATA 1.31E-06 CS134 2.83E-04 5.023-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 CS136 3.45E-05 9.611'-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-04 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 BA140 4.00E-05 4.00E-08 2.07E-05 NO DATA 9.59E-09 1.14E-03 2.74E-05 BA141 1.12E-10 7.70E-14 3.55E-12 NO DATA 4.64E-14 2.12E-06' 3.39E-06 BA142 2.84E-11 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.11E-06 4.95E-07 LA140 3.61E-07 1.43E-07 3.68E-08 NO DATA NO DATA 1.20E-04 6 06E-05 LA142 7.36E-10 2.69E-10 6.46E-11 NO DATA NO DATA 5.87E-06 4.25E-05 CE141 1.98E-05 1.19E-05 1.42E-06 NO DATA 3.75E-06 3.69E-04 1.54E-05 CE143 2.09E-07 1.38E-07 1.E8E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 CE144 2,28E-03 8.65E-04 1.26E-04 NO DATA 3.84F-04 7.03E-03 1.06E-04 PR143 1.00E-05 3.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.66E-05 PR144 3.42E-11 1.32E-11 1.72E-12 NO DATA 4.80E-12 1.15E-06 3.06E-06 ND147 5.67E-06 5.81E-06 3.57E-07 NO DATA 2.25E-06 2.30E-04 2.23E-05 W 187 9.26E-09 6.44E-09 2.23E-09 NO DATA NO DATA 2.83E-05 2.54E-05 NP239 2.65E-07 2.37E-08 1.34E-08
- !0 DATA 4.73E-08 4.25E-05 1.78E-05 25PARTA 12/16/96
Revision 13 j
BIG ROCK POINT RADIOLOGICAL Page 43 of 92 VOLUME 25EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS TABLE 1.7 INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALLD1 NUCLIDE B0NE LIVER T. BODY THYROID KIDNEY LUNG GI-Lll H
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-06 4.35E-06 P 32 7.04E-04 3.09E-05 2.67E-05 NO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA N0 DATA 4.17E-08 2.31E-008 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 MN 56 NO DATA 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 FE 59 5.59E-06 9.04E-06 4.C1E-06 NO DATA NO DATA 3.43E-04 1.91E-05 C0 58 NO DATA 4.79E-07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 C0 60 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-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 64 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-C5 BR 83 NO DATA NO DATA 1.28E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.48E-07 NO DATA NO DATA NO DATA LT E-24 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 5.11E-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 NO DATA 1.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 SR 91 3.28E-08 NO DATA 1.24E-09 NO DATA NO DATA 1.44E-05 4.70E-05 SR 92 3.54E-09 NO DATA 1.42E-10 NO DATA NO DATA 6.49E-06 6.55E-05 Y 90 1.llE-06 NO DATA 2.99E-08 NO DATA NO DATA 7.07E-05 7.24E-05 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 Y 93 5.04E-08 NO DATA 1.38E-09 NO DATA NO DATA 2.01E-05 1.05E-04 ZR 95 5.13E-05 1.13E 05 1.00E-05 NO DATA 1.61E-05 6.03E-04 1.65E-05 ZR 97 5.07E-08 7.34E-09 4.32E-09 NO 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-04 1.00E-05 MO 99 NO DATA 4.66E-08 1.15E-08 NO DATA 1.06E-07 3.66E-05 3.42E-05 TC 99m 4.81E-13 9.41E-13 1.56E-11 NO DATA 1.37E-11 2.57E-07 1.30E-06
/
25PARTA 12/16/96
Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL Page 44 of 92 EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS TABLE 1.7 INHALAT:0N DOSE FACTORS FOR CHILD (MREM PER PCI INHALE 01-NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI TC101 2.19E-14 2.30E-14 2.91E-13 NO DATA 3.92E-13 1.58E-07 4.41E-09 RU103 7.55E-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-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 AG110m 4.56E-06 3.08E-06 2.47E-06 NO DATA 5.74E-06 1.48E-03 2.71E-05 TE125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 1.93EU TE127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 TE127 7.49E-10 2.57E-10 1.67E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 TE129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 TE129 2.64E-ll 9.45E-12 6.44E-12 1.93E-11 6.94E-Il 7.93E-07 6.89E-06 l
TE131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE131 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-04 3.72E-05 1 130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 NO DATA 1.38E-06 I 131 1.30E-05 1.30E-05 7.37E-06 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 1.04E-03 9.13E-06 NO DATA 1.48E-06 I 134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 N0 DATA 2.58E-07 f
I 135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 N0 DATA 1.20E-06 CS134 1.~6E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 CS136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 CS137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 CS138 1.71E-0?
2.27E-07 1.50E-07 NO DATA 1.68E-07 1.84E-08 7.29E-08 BA139 4.98E-10 2.66E-13 1.45E-11 NO DATA 2.33E-13 1.56E-06 1.56E-05 BA140 2.00E-05 1.75E-08 1.17E-06 NO DATA 5.71E-09 4.71E-04 2.75E-05 BA141 5.29E-11 2.95E-14 1.72E-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 BA142 1.35E-11 9.73E-15 7.54E-13 NO DATA 7.87E-15 4.44E-07 7.41E-10 LA140 1.74E-07 6.08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05 LA142 3.50E-10 1.11E-10 3.49E-Il N0 DATA NO DATA 2.35E-06 2.05E-05 CE141 1.06E-05 5.28E-06 7.83E-07 NO DATA 2.31E-06 1.47E-04 1.53E-05 i
CE143 9.89E-08 5.37E-08 7.77E-09 NO DATA 2.26E-08 3.12E-05 3.44E-05 l
CE144 1.83E-03 5.72E-04 9.77E-05 NO DATA 3.17E-04 3.23E-03 1.05E-04 PR143 4.99E-06 1.50E-06 2.47E-07 NO DATA 8.11E-07 1.17E-04 2.63E-05 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 2.22E-05 W 187 4.41E-09 2.61E-09 1.17E-09 NO DATA NO DATA 1.11E-05 2.46E-05 HP239 1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.57E-05 1.73E-05 25PARTA 12/16/96
Revision 13 BIG ROCK POINT RADIOLOGICAL Page 45 of 92 VOLUME 25EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS TABLE 1.Z INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALE 01 NUCLIDE B0NE LIVER T.80DY THYROID KIDNEY LUNG GI-LLI H
3 NO DATA 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C 14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 NA 24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E 06 1.72E-06 1.72E-06 P 32 2.36E-04 1.37E-05 8.95E-06 NO DATA NO DATA NO DATA 1.16E-05 CR 51 N0 DATA NO DATA 1.69E-08 9.37E-09 3.84E-0) 2.62E-06 3.75E-07 MN 54 NO DATA 6.39E-06 1.05E-06 NO DATA 1.59E-06 2.48E-04 8.35E-06 MN 56 NO DATA 2.12E-10 3.15E-11 NO DATA 2.24E-10 1.90E-06 7.18E-06 FE 55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-07 FE 59 1.09E-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 C0 58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 C0 60 NO DATA 1.89E-06 2.48E-06 NO DATA NO DATA 1.09E-03 3.24E-05 NI 63 7.25E-05 5.43E-06 2.47E-06 NO DATA NO DATA 3.84E-05 1.77E-06 NI 65 2.73E-10 3.66E-11 1.59E-11 NO DATA N0 DATA 1.17E-06 4.59E-06 CU 64 N0 DATA 2.54E-10 1.06E-10 NO DATA 8.01-10 1.39E-06 7.68E-06 ZN 65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06 ZN 69 6.04E-12 1.15E-11 8.07E-13 NO DATA 7.53E-12 1.98E-07 3.56E-08 BR 83 NO DATA NO DATA 4.30E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 N0 DATA NO DATA 5.41E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 2.29E-09 N0 DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.38E-05 1.05E-05 NO DATA NO DATA NO DATA 2.21E-06 RB 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 RB 89 NO DATA 4.40E-08 2.91E-08 NO DATA NO DATA NO DATA 4.22E-17 SR 89 5.43E-05 NO DATA 1.56E-06 NO DATA NO DATA 3.02E-04 4.64E-05 SR 90 1.35E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9.56E-05 SR 91 1.10E-08 NO DATA 4.39E-10 NO DATA NO DATA 7.552-06 3.24E-05 SR 92 1.19E-09 NO DATA 5.08E-Il NO DATA NO DATA 3.43E-06 1.49E-05 Y 90 3.73E-07 NO DATA 1.00E 08 NO DATA NO DATA 3.66E-05 6.99E-05 Y 91m 4.63E-11 NO DATA 1.77E-12 NO DATA NO DATA 4.00E-07 3.77E-09 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 N0 DATA NO DATA 3.35E-06 2.06E-05 Y 93 1.69E-08 NO DATA 4.65E-10 NO DATA NO DATA 1.04E-05 7.24E-05 ZR 95 1.82E-05 5.73E-06 3.94E-06 NO DATA 8.42E-06 3.36E-04 1 86E-05 ZR 97 1.72E-08 3.40E-09 1.57E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05 NB 95 2.32E-06 1.29E-06 7.08E-07 NO DATA 1.25E-06 9.39F-05 1.21E-05 M0 99 NO DATA 2.11E-08 4.03E-09 N0 DATA 5.14E-08 1.92E-05 3.36E-05 TC 99m 1.73E-13 4.83E-13 6.24E-12 NO DATA 7.20E-12 1.44E-07 7.66E-07 25PARTA 12/16/96
Revision 13 BIG ROCK POINT RADIOLOGICAL Page 46 of 92 VOLUME 25EFFLUENT T/S REQUIRED DOCUMENTS A.
0FFSITE DOSE CALCULATIONS TABLE 1.7 INHALATION DOSE FACTORS FOR TEENAGER (MREM PER PCI INHALEDl_
NUCLIDE BONE LIVER T.80DY THYROID KIDNEY LUNG GI-lli-TC101 7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 RU103 2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-05 1.36E-05 RU105 1.40E-10 NO DATA 5.42E-11 NO DATA 1.76E-10 2.27E-06 1.13E-05 RU106 1.23E-05 NO DATA 1.55E-06 NO DATA 2.38E-05 2.01E-03 1.20E-04 AG110m 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 1.75E-07 NO DATA 6.70E-05 9.38E-06 TE127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 TE129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TE131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 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 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 1 130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 NO DATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11E-07 I 132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA 1.59E-07 I 133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1.29E-06 I 134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09 1 135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 NO DATA 8.69E-07 CS134 6.28E-05 1.41E-04 6.85E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 CS136 6.44E-06 2.42E-05 1.71E-05, NO DATA 1.38E-05 2.22E-06 1.36E-06 CS137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51E-05 1.06E-06 CS138 5.82E-08 1.07E-07 5.58E-08 NO DATA 8.28E-08 9.84E-09 3.38E-11 8A139 1.67E-10 1.18E-13 4.87E-12 NO DATA 1.11E-13 8.08E-07 8.06E-07 2.86EM 8A140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 BA141 1.78E-11 1.32E-14 5.93E-13 NO DATA 1.23E-14 4.11E-07 9.33E-14 BA142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99E-20 LA140 5.99E-08 2.95E-08 7.82E-09 NO DATA NO DATA 2.68E-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-06 2.37E-06 2.71E-07 NO DATA 1.11E-06 7.67E-05 1.58E-05 CE143 3.32E-08 2.42E-08 2.70E-09 NO DATA 1.08E-08 1.63E-05 3.19E-05 CE144 6.11E-04 2.53E-04 3.28E-05 NO DATA 1.51E-04 1.67E-03 1.08E-04 PR143 1.67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 PR144 5.37E-12' 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14 ND147-9.83E-07 1.07E-06 6.41E-08 NO DATA 6.28E-07 4.65E-05 2.28E-05 W 187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21E-05 NP239 4.23E-08 3.99E-09 2.21E-09 NO DATA 1.25E-08 8.11E-06 1.65E-05 f
I 25PARTA 12/16/96
Revision 13 81G ROCK POINT RADIOLOGICAL Page 47 of 92 VOLUME 25EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE 00SE CALCULATIONS Table 1.8 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMIN l
(mrem /hr oer oCi/m21 Element Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-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 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 l
Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 8r-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-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-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-106 1.50E-09 1.80E-09 1.80E-08 2.10E-08 Ag-110m Te-125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129m 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 25PARTA 12/16/96
Revision 13 BIG ROCK POINT RADIOLOGICAL Page 48 of 92 l
VOLUME 25 EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS Table 1.8 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMj (mrem /hr oer oCi/m )
2 Flement Total Body Skin Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 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 l
I-135 1.20E-08 1.40E-08 J
Cs-134 1.20E-08 1.40E-08
)
Cs-136.
1.50E-08 1.70E-08 I
Cs-137 4.20E-09 4.90E-09 i
Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 f
Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 l
La-142 1.50E-08 1.80E-08 l
Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Dr-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 9.50E-10 1.10E-09 Np-239 25PARTA 12/16/96
Revision 13 BIG ROCK P0 INT RADIOLOGICAL Page 49 of 92 VOLUME 25EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE 00SE CALCULATIONS TABLE 1.9
_1997 BIG ROCK POINT GASE0US DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Annual Quantity Dose Factor (Cil mrem /Ci -
Oroan 5.50E+05 Nuclide _
Total Body 9.10E-06 6.79E+08 Ar-41 2.21E-08 Kr-83m Skin 6.73E+06 2.23E-06 Kr-85 Skin 3.88E+06 Total Body 1.29E-06 7.25E+05 Kr-85m 2.07E-05 Kr-87 Skin 3.16E+05 l
Total Body 1.58E-05 i
2.20E+06 Kr-88 Kr-89 Total Body 2.27E-06 6.07E+05 Total' Body-C 8.24E-06 2.68E+03 H-3 5.59E-03 C-14 Bone-C 5.73E+04 Cr-51 GI Tract-T 2.62E-04 3.37E+02 Mn-54 GI Tract-T 4.45E-02 1.03E+03 Fe-55 Bone-C 1.45E-02 8.24E+02 GI Tract-T 1.82E-02 6.67E+02 Co-58 GI Tract-T 2.25E-02 3.09E+01 Fe-59 Co-60 GI Tract-T 4.86E-01 Zn-65 Liver-I 1.13E-01 1.33E+02 2.35E+01 Sr-89 Bone-C 6.37E-01 5.68E-01 Sr-90 Bone-C 2.64E+01 G1 Tract-1 2.75E-02 5.45E+02 2.25E+02 Zr-95 Sb-124 GI Tract-T 6.66E-02 6.10E+00 1-131 Thyroid-I 2.46E+00 9.84E-07 1.52E+07 Xe-131m Skin 1.47E+07 Xe-133 Total Body 3.39E-07 2.05E-06 7.32E+06 Xe-133m Skin 2.45E+06 Xe-135 Total Body 2.04E-06 Xe-135m Total Body 2.22E-06 2.25E+06 3.80E-06 3.95E+06 Xe-137 Skin 8.31E+05 Xe-138 Total Body 6.02E-06 2.60E-02 5.77E+02 I-133 Thyroid-I Cs-134 Liver-C 6.22E-01 2.41E+01 Cs-136 Total Body-I 1.11E-02 4.50E+02 6.78E-01 2.21E+01 Cs-137 Bone-C 4.01E+03 3.74E-03 Ba-140 Bone-C 1.61E+03 Ce-141 GI Tract-T 9.33E-03 Ce-144 GI Tract-T 2.39E-01 6.28E+01 Mn-56 GI Tract-C 2.00E-04 7.50E+04 Co-57 GI Tract-T 6.01E-03 2.50E+03 Ni-63 Bone-C 8.63E-01 1.74E+01 GI Tract-C 1.29E-04 1.16E+05 Total Body-C 6.14E-07 8.14E+06 Ni-65 Hb-95 GI Tract-A 3.20E-02 4.69E+02 Rb-88 Mo-99 Kidney-I 1.50E-03 1.00E+04 Tc-99 GI Tract-A 8.75E-02 1.71E+02 25PARTA 12/16/96
I i
Revision 13 BIG ROCK POINT RADIOLOGICAL Page 50 of 92 VOLUME 25EFFLUENT T/S REQUIRED DOCUMENTS OFFSITE DOSE CALCULATIONS A.
TABLE 1.9 t
1997 BIG ROCK POINT GASE0US DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Annual Quantity Dose Factor (Ci)
Oraan
__ mrem /Ci Nuclide_
1.14E+06 GI Tract-T 1.31E-05 3.07E+02 Tc-99m GI Tract-A 4.89E-02 4.87E+02 Ru-103 GI Tract-T 3.08E-02 1.15E+05 Sb-125 GI Tract-T 1.30E-04 5.79E-01 Te-127 2.59E+01 i
Thyroid-A 5.02E+04 1-129 2.99E-04 Thyroid-C 2.17E+05 I-132 6.91E-05 Thyroid-C 1.16E+04 1-134 1.29E-03 Thyroid-C 1.01E+04 I-135 GI Tract-T 1.49E-03 7.34E+07 La-140 Total Body-C 6.81E-08 1.91E+04 4
Total Body-C 2.62E-04 4.76E+03 N-13 Total Body-I 1.05E-03 Na-24 2.33E+02 Br-82 6.44E-02 Bone-I 4.00E+04 Sr-91 GI Tract-C 3.75E-04 1
3.05E+06 4'.92E-06 Sr-92 GI Tract-I 7.69E+01 Tc-101 GI Tract-T 1.95E-01..
1.04E+03 Ag-110m Total Body-C 4.82E-03 1.83E+05 Cs-138 8.20E-05 3.93E+04 GI Tract-C Ba-139 GI Tract-T 3.82E-04 9.09E404 l
Np-239 GI Tract-C 1.65E-04 3.95E-01
{
Ru-105 3.80E+01 Bone-T 3.42E-01 Pu-238 4.39E+01 Bone-T 1.62E+01 Pu-239 9.26E-01 Bone-T 1.00E+00 Pu-241 1.50E+01 1.72E+01 Bone-T Am-241 8.70E-01 1.63E+00 3
Cm-242 Lung-T 9.18E+00 i
Cm-244 Bone-T 25PARTA 12/16/96
Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL Page 51 of 92 EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS II.
-L10010 EFFLUENTS ALLOWABLE CONCENTRATION (Sections ll.A and II.B use the II.A 10 CFR 20 values)
II.A.1 RETS Reouirement Technic;l Specification 13.1.2.1 of the Radiologica radioactive material released at any time from the site to unrestricted areas shall be limited to the effluent concentrat specified in 10 CFR 20, Appendix 8, Table 2, Column 2 for nuclides For dissolved or other than dissolved or entrained noble gases.
entrained noble gases, the concentration shall be limited to 1.4 x 10-4 #Ci/ml total activity. To ensure compliance, the following approach will be used for each release.
II.A.2 Prerelease Analysis 1
Most tanks will be recirculated through two volume changes prior to sampling for release to the environment to ensure that aThe a representative sample is obtained. time for those tanks too i
be the time that the suspended particulate concentration reaches l
Either a one-time test, or prior sampling data, may steady state.
be used to determine appropriate recirculation time.
Prior to release, a grab sample will be analyzed for each release, and the concentration of each radionuclide determined, n
(11.1) 3-
{
C C
g3 i=1 where:
Total concentration in the liquid effluent at the release C3-point, pCi/ml, at release point J.
Concentration of a single radionuclide i, pCi/ml, at Gjj =
release point J.
l f
f 25PARTA 12/16/96 l
Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL Page 52 of 92 EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS II.A.3 Total Release-Fraction The total release-fraction (R ) for each release point will be l
calculated by the relationshi defined as:
C (II.2)
R())= {
gphij i
where:
Undiluted effluent concentration of radionuclide Id i, as determined in Section II.A.2, pCi/ml, at C
=
release point j.
The effluent concentration of radionuclide i, as
- MPC, specified in Section II. A.1, yCi/ml.
(Big Rock Point
=
still uses MPC terminology in Liquid Analyses I
Programs.)
The total release-fraction for the release point.
R)
The sum of the ratios at the discharge to the lake must be si due The to the releases from any.or all concurrent releases.
following relationship will assure this criterion is met:
- 1) s F (II.3)
- II + I (R3 f(R - 1) + f (R2 3
3 3 2
where:
The effluent flow rate (gallons / minute) for the f,f 'I respective releases, determined by plant
=
y 2 3 I
personnel.
The total release-fractions for the respective R,R,R releases as determined by Equation II.2.
3 2 3 Normally, a Minimum required dilution flow rate.
conservatively high dilution flow rate is used, F
=
that is, flow rate used = (b)(F) where b is a i
conservative factor greater than 1.0.
25PARTA 12/16/96
Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL Page 53 of 92 EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS II.B INSTRUMENT ALARM SET POINTS l
Set Point Determination II.B.1 The set point for each liquid effluent monitor will be established using plant instructions.
Concentration, flow rate, dilution, l
principal gamma emitter, geometry and detector efficiency are combined to give an equivalent set point in counts per minute The physical and technical description, location and (cpm).
identification number for each liquid effluent radiation detector is contained in Figure 2-2.
l 25PARTA 12/16/96 i
l I
CE 3-e%
J llll g=
e 8, 2
}I.!
= ms
$,5 l
2
=
a QU g
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)
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e 5
=>
o
}
b g
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' =V
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u a
si as 8
m 52 2
\\
uBS
=
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+
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$85 l
-+
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-i og g
wm M"8
\\
-m gl uG
@I 8 5 ti" c!
g I
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$$.4
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-+
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=
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5 n
l
VOLUME 25 BIG ROCK POINT RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS Revision 13
\\
i A.
OFFSITE DOSE CALCULATIONS Page ': of 92 The respective alarm set such that the sum / trip set points at each release point will be of the ratios at each point, as calculated by Equation II.2, will not exceed 1.
An increase in the concentration would indi value of R.
n 11.1.
Section II.A.1 to be exceeded.A large increase would cause crease in the value is equal to the release concentration, but for easThe operation it may be desired that the set point (S) be set e of the effluent concentration (C) by the same factor (b) above setting dilution flow.
That is:
utilized ir.
S-bxC I
(II.4)
Liquid effluent flow paths and release points are indic t d Figure 2.1.
ae n
11.B.2 Post-Release Analysis
\\
A post-release analysis will be done using actual releas
\\
ensure that the limits specified in Section II A 1 were n t e data to exceeded.
o A composite list of concentrations (Cjj), by isotope with the actual liquid radwaste (fj) and dilution (F) flow
, will be used (or volumes) during the release.
rates into Equation II.3 to demonstrate compliance with the li itTh Section II.A.1.
auditable records by plant personnel.This data and set points will b m s in II.C 00SE
\\
II.C.1 RETS Reauirement Technical SpecificationsTechnical Specification 13.1.4.1 of th radionuclides released be(RETS) requires that the quantity of uent limited such that the dose or dose commitment to an individual from radioactive mate effluents released to unrestricted areas from each reacto Figure 2.1) will not exceed:
see i
1.
During any calendar 5 mrem to any organ, quarter,1.5 mrem to the total body and and 2.
During any calendar year, 3 mrem to the total body and 10 to any organ, mrem i
25PARTA 12/16/96 1
1 VOLUME 25 BIG ROCK POINT RADIOLOGICAL EFFLUENT T/S REQUIRED DOCUMENTS Revision 13 A.
OFFSITE DOSE CALCULATIONS Page 56 of 92 l
II.C.2 Release Analysis (Desian Basis Ouantity Fraction)
Per Technical Specification 13.1.4.4 the cumulative DBQ fraction that th sum of the fractions of all nuclides release exceed 1.0 year to date and 0.5 in any calendar quarter.
Calculations shall be performed according to the formula:
A
[
(DBQ)$ = Fraction of DBQ (II.5) i i
l where:
A Cumulative quarterly or annual activity of nuclide i j
identified in liquid release (C ).
4 (DBQ)j Design objective annual quantity of radionuclide i
=
from Table 2.2 (Ci).
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 Exceedina DB0 Limits The design basis quantities are derived in such a conservative t
As a consequence of this conservatism, and in light ofm historically consistent operations with releases well below a:nual design basis quantities, the Big Rock Point Plant Technical Specifications do not require monthly dose projections.
Technical Specification 13.1.4.4 requires a cumulative doseHowever, 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.
II.C.4 Dose Calculation Values for the design basis quantities (Ci), and the dose per curie calcula(D/C)i 1
for each nuclide i shown in Table 2.2, were c c ted as follows.
25PARTA 12/16/96
Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL Page 57 of 92 EFFLUENT T/S REQUIRED DOCUMENTS A.
0FFSITE 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 (II.6) 3={
(DCF)jj xI j = mrem D
i=1 where:
Dose for the jth organ from radionuclides released, 03=
mrem.
J=
The organ of interest.
Ingestion dose commitment factor for the j* organ (DCF)43 =
from the i* radionuclide mrem /pci (see Table 2.1).
Activity ingested of the i* radionuclide, pCi.
I j=
I is described by:
j 6
(A )(V)(365)(10 )
(II.7) j
= pCi I j (800)(d)
=
where:
365 -
Days per year.
Annual activity released of i* radionuclide, pCi.
Aj-Average rate of water consumption; adult - 2,000 ml/d, V=
teen and child - 1,400 ml/d, infant - 900 ml/d (Reg Guide 1.109).
d - Dilution water flow for year (ml).
Dispersion factor from discharge to nearest drinking water 800 -
supply.
6 Coaverts pCi to pCi.
10 The dose equation then becomes:
i (11.8)
D) = (4.56 5)(V)-
{
(DCF)43 xAj = mrem i=1 25PARTA 12/16/96
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OFFSITE DOSE CALCULATIONS II.C.4.2 Fish Ingestion The dose to an individual from the consumption of fish is decribegbyEquation11.10.
In this case the activity ingested of the i radionuclide (I ) is described by:
j A, B9 9
F (10 ) = pCi (II.9) 11' 15d where:
Annual activity released of i* radionuclide, pCi.
Ag=
Fish concentration factor of i* radionuclide, uCUom Bj=
pCi/ml (see Table 2.0).
F=
Amount of fish eaten per year; adult - 21 kg, e.een -
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).
9 10 Converts pCi to pCi and gm to kgm.
Substitution of Equation II.9 into Equation II.6 gives:
i (6.7E 7)(F) j=
{
(A )(B )(DCFjj) = mrem (11.10)
D j
j 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 general, even if not previously detected at Big Rock Point.
From time to time, however, other nuclides may be detected.
If the unlisted nuclide constitutes less than 10% of the MPC-fraction for the release, and all unlisted nuclides total less than 25% of the MPC-fraction, the nuclide may be considered not presnnt.
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OFFSITE DOSE CALCULATIONS If the unlisted nuclide constitutes greater than 10% of the MPC-fraction, or all unlisted nuclides together constitute greater than 25%, then each nuclide should be assigned a DBQ equal to the most conservative value listed for the physical form of the nuclide involved (noble gas, halogen or particulate).
Should a nuclide not listed in Table 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.
l II.C.5 Annual Analysis.
A complete analysis utilizing the NRC computer code LADTAP with the total source re; ease will be done annually in conjur.ction 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 g.
The dose to the j The following approach is utilized in LADTAP.
organ from m radionuclides, 0, is described by:
3 m
(11.11) j=
[
Dgj = rem D
i=1 m
(11.12) j-
{
(DCF)g) x 1 3 = rem D
i=1 where:
Dose to the j* organ from the i* radionuclide, rem.
D)=
9 The organ of interest (bone, GI tract, thyroid, liver, kidney, lung or total body).
J=
Ingestion dose commitment factor for the j* organ from the i* radionuclide, rem /pCi (see Table 2.1).
(DCF)43 =
Activity ingested of the i* radionuclide, pCi.
l 1 9=
i 1
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A.
OFFSITE DOSE CALCULATIONS I, for water ingestion is. described'by:
A V7 (II13)
- C I,-
vd is described by:
and for fish ingestion l j A B Fr (11.14) j pCi 1 5=
vd where:
Activity released of j* radionuclide during the year, A
9 pCi.
Average rate of water consumption (Table 2.2).
V
=
Number of days during the year (365 d).
7 -
Dispersion factor from point of discharge to point of v
exposure (Table 2.2).
Dilution water volume (ml).
d uCihm Fish concentration factor of the i* radionuclide, gCi/ml B
=
9 (Table 2.0).
Amount of fish eaten per day (Table 2.2).
F
=
OPERABILITY OF LIQUID RADWASTE EQUIPMENT II.D The Big Rock Point liquid radwaste system is designed to reduce the radioactive materials in liquid wastes prior to their discharge (by recycle or shipment for disposal) so that radioactivity in liquid effluent releases to unrestricted areas (see Figure 2.1) will not exceed Technical Specification 13.1.4 Maintaining the cumulative D8Q fraction of releases assures In addition, more than 13 years compliance with this requirement.
j of operating experience (to the date this ODCM was first adopte has shown that design basis quantities never have been exceeded.l l
1 i
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OFFSITE DOSE CALCULATIONS II.E OFFSITE RELEASE RATE 10 CFR 50.36a requires that the release of radioactive materials Appendix I to be kept as low as is reasonably achievable.
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 The source term used is given in water intake concentration).The most limiting dose of the person hypo Table 1.1.
The release drinking this water is 4.89E-01 mrem, whole body.
rate which would result in a dose rate eg'livalent to 500 mrem /y (the total body limit of Technical Specification 13.1.3.1) is the Curies / Year given in Table 1.1 (8.94) times 500/.489 or 9141 l
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 Per Section II.C.5 annual analyses are run using LADTAP to Point.
calculate estimates of dose to the total body and limiting organs.
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OFFSITE DOSE CALCULATIONS Ej0 ACCUMULATION FACTORS Table 2.0
_uCi/cm oer uCi/ mil
(
Freshwater Fish Element 9.0E-01 H
4.6E+03 C
1.0E+02 Na 3.0E+03 P
2.0E+02 Cr 4.0E+02 Mn 1.0E+02 Fe 5.0E+01 Co 1.0E+02 Ni 5.0E+01 Cu 2.0E+03 Zn 4.2E+02 Br 2.0E+03 Rb 3.0E+01 Sr 2.5E+01 Y
3.3E+00 Zr 3.0E+04 Nb 1.0E+01 Mo 1.5E+01 Tc 1.0E+01 Ru 1.0E+01 Rh 4.0E+02 Te 1.5E+01 1
2.0E+03 Cs 4.0E+00 l
l Ba 2.5E+01 La 1.0E+00 i
Ce 2.5E+01 Pr 2.5E+01 Nd
!.2E+03 W
1.0E+01 Np i
l l
1 l
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OFFSITE DOSE CALCULATIONS T_ABLE 2.1 ADULT INGESTION DOSE FACTORS (MREM PER PCI INGESTE01 NUCLIDE BONE LIVER T.B0DY THYROID KIDNEY LUNG GI-LLI H
3 NO DATA 1.05E-07 1.05E-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 MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-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 N0 DATA 2.85E-06 3.40E-05 C0 58 NO DATA 7.45E-07 1.67E-06 N0 DATA NO DATA NO DATA 1.51E-05 C0 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-07 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 ZN 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 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA N0 DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 N0 UATA 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 NO DATA 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 DATA NO DATA 1.48E-05 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.474.'-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99m 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 25PARTA 12/16/96
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0FFSITE DOSE CALCULATIONS TABLE 2.l_
ADULT INGESTION DOSE FACTORS (MREM PER PCI INGESTED)
NUCLIDE 80NE LIVER T.80DY THYROID KIDNEY LUNG GI-LLI TC101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 l
RU103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 l
RU106 2.75E-06 N0 DATA 3.48E-07 N0 DATA 5.31E-06 NO DATA 1.78E-04 j
AG110m 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 N0 DATA 6.04E-05 TE125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 N0 DATA 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 1
TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 I
I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-0?
1.02E-05 NO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 1 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS136 6.51E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-ll 3.92E-11 1.72E-07 BA140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-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 DATA NO DATA NO DATA 9.25E-05 LA142 1.28E-10 5.82E-11 1.45E-11 NO DATA 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 5.37E-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 3.69E-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 DATA 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 3.01E-08 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 2.40E-05 25PARTA 12/16/96
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OFFSITE DOSE CALCULATIONS TABLE 2.1 INGESTION DOSE FACTORS FOR TEENAGER (MREM PER PCI INGESTE01 NUCLIDE B0NE LIVER T.80DY THYROID KIDNEY LUNG GI-LLI H
3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C 14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 NA 24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P 32 2.76E-04 1.71E-05 1.07E-05 NO DATA NO DATA NO DATA 2.32E-05 CR 51 NO DATA NO DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN 54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 MN 56 NO DATA 1.58E-07 2.81E-08 NO DATA 2.00E-07 NO DATA 1.04E-05 FE 55 3.78E-06 2.68E-06 6.25E-07 NO DATA NO DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 C0 58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 C0 60 N0 DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 NI 63 1.77E-04 1.25E-05 6.00E-06 NO DATA NO DATA NO DATA 1.99E-06 NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA N0 DATA N0 DATA 5.19E-06 CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 ZN 65 5.76E-06 2.00E 05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ZN 69 1.47E-08 2.80E-08 1.96E-09 NO DATA 1.83E-08 NO DATA 5.16E-08 BR 83 N0 DATA NO DATA 5.74E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 3.05E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.98E-05 1.40E-05 NO DATA NO DATA NO DATA 4.41E-06 RB 88 NO DATA 8.52E-08 4.54E-08 NO DATA NO DATA NO DATA 7.30E-15 RB 89 NO DATA 5.50E-08 3.89E-08 NO DATA NO DATA NO DATA 8.43E-17 SR 89 4.40E-04 NO DATA 1.26E-05 N0 DATA NO DATA NO DATA 5.24E-05 SR 90 8.30E-03 NO DATA 2.05E-03 NO DATA NO DATA NO DATA 2.33E-04 SR 91 8.07E-06 NO DATA 3.21E-07 NO DATA NO DATA NO DATA 3.66E-05 SR 92 3.05E-06 NO DATA 1.30E-07 NO DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E-08 NO DATA 3.69E-10 NO DATA NO DATA NO DATA 1.13E-04 Y 91m 1.29E-10 NO DATA 4.93E-12 NO DATA NO DATA NO DATA 6.09E-09 Y 91 2.01E-07 NO DATA 5.39E-09 N0 DATA NO DATA NO DATA 8.24E-05 Y 92 1.21E-09 NO DATA 3.50E-11 NO DATA NO DATA NO DATA 3.32E-05 Y 93 3.83E-09 NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 ZR 95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ZR 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.11E-10 NO DATA 1.27E-04 I
N8 95 8.22E 09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95 -05 MO 99 NO DATA 6.03E-06 1.15E-06 NO DATA 1.38E-05 NO DATA 1.08E-05 TC 99m 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.38E-08 5.14E-10 6.08E-07 25PARTA 12/16/96
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OFFSITE DOSE CALCULATIONS TABLE 2.1 3
MGESTION DOSE FACTORS FOR CHILD i
(MREM PER PCI INGESTED) f NUCLIDE B0NE LIVER T.80DY THJROID KIDNEY LUNG GI-lli H
3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C
14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P 32 8.25E-04 3.86E-05 3.18E-05 NO DATA NO DATA N0 DATA 2.28E-05 CR 51 NO DATA NO DATA 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN 54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 NO DATA 4.84E-05 FE 55 1.15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 NO DATA N0 DATA 7.74E-06 2.78E-05 C0 58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 C0 60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 NI 63 5.38E-04 2.88E-05 1.83E-05
~N0 DATA NO DATA NO DATA 1.94E-06 l
l NI 65 2.22E-06 2.09E-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 CU 64 N0 DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 NO DATA 1.15E-05 ZN 65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 l
ZN 69 4.38E-08 6.33E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 N0 DATA NO DATA
'1.71E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA N0 DATA 1.98E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 9.12E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 6.70E.05 4.12E-05 NO DATA NO DATA NO DATA 4.31E-06 RB 88 NO DATA 1.90E-07 1.32E-07 NO DATA NO DATA NO DATA 9.32E-09 RB 89 NO DATA 1.17E-07 1.04E-07 NO DATA NO DATA NO DATA 1.02E-09 SR 89 1.32E-03 NO DATA 3.77E-05 NO DATA NO DATA N0 DATA 5.11E-05 SR 90 1.70E-02 N0 DATA 4.31E-03 NO DATA NO DATA NO DATA 2.29E-04 SR 91 2.40E-05 NO DATA 9.06E-07 NO DATA NO DATA NO DATA 5.30E-05 i
SR 92 9.03E 06 NO DATA 3.62E-07 NO DATA NO DATA NO DATA 1.71E-04 Y 90 4.11E-08 NO DATA 1.10E-09 NO DATA NO DATA NO DATA 1.17E-04 Y 91m 3.82E-10 NO DATA 1.39E-11 N0 DATA N0 DATA NO DATA 7.48E-07 f
Y 91 6.02E-07 NO DATA 1.61E-08 NO DATA NO DATA NO DATA 8.02E-05
~,
Y 92 3.60E-09 NO DATA 1.03E-10 NO DATA NO DATA NO DATA 1.04E-04 Y 93 1.14E-08 N0 DATA 3.13E-10 NO DATA NO DATA NO DATA 1.70E-04 ZR 95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ZR 97 6.99E-09 1.01E-09 5.96E-10 NO DATA 1.45E-09 NO DATA 1.53E-04 NB 95 2.2SE-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 M0 99 NO DATA 1.33E-05 3.29E-06 N0 DATA 2.84E-05 NO DATA 1.10E-05 TC 99m 9.23E-10 1.81E-09 3.00E-08 N0 DATA 2.63E-08 9.19E-10 1.03E-06 25PARTA 12/16/96
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EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS TABLE 2.1 INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTE01 NUCLIDE BONE LIVER T.80DY THYROID KIDNEY LUNG GI-LLI TC101 1.07E-09 1.12E-09 1.42E-08 NO DATA 1.01E-08 5.92E-10 3.56E-09 RU103 7.31E-07 NO DATA 2.81E-07 NO DATA 1.84E-06 NO DATA 1.89E-05 RU105 6.45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.21E-05 RU106 1.17E-05 NO DATA 1.46E-06 NO DATA 1.58E-05 NO DATA 1.82E-04 AG110m 5.39E-07 3.64E-07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TE125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.10E-05 TE127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 NO DATA 2.34E-05 TE127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 NO DATA 1.84E-05 TE129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 NO DATA 8.34E-06 l
TE131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 NO DATA 1.01E-04
)
TE131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 TE132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 NO DATA 4.50E-05 I 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06 I 131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 I 132 8.00E-07 1.47E-06 6.76E-07 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 I 134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 NO DATA 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 CS134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 CS136 2.35E-05 6.46E-05 4.18E-05 NO DATA 3.44E-05 5.13E-06 2.27E-06 CS137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.01E-07 NO DATA 2.23E-07 2.40E-08 1.46E-07 BA139 4.14E-07 2.21E-10 1.20E-08 NO DATA 1.93E-10 1.30E-10 2.39E-05 BA140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 8A141 2.00E-07 1.12E-10 6.51E-09 NO DATA 9.69E-11 6.58E-10 1.14E-07 BA142 8.74E-08 6.29E-11 4.88E-09 NO DATA 5.09E-11 3.70E-11 1.14E-09 LA140 1.01E-08 3.53E-09 1.10E-09 NO DATA NO DATA NO DATA 9.84E-05 LA142 5.24E-10 1.67E-10 5.23E-11 NO DATA NO DATA NO OATA 3.31E-05 CE141 3.97E-08 1.98E-08 2.94E-09 NO DATA 8.68E-09 NO DATA 2.47E-05 CE143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1.59E-09 NO DATA 5.55E-05 CE144 2.08E-06 6.52E-07 1.11E-07 NO DATA 3.61E-07 NO DATA 1.70E-04 PR143 3.93E-08 1.18E-08 1.95E-09 NO DATA 6.39E-09 NO DATA 4.24E-05 PR144 1.29E-10 3.99E-11 6.49E-12 NO DATA 2.11E-11 NO DATA 8.59E-08 ND147 2.79E-08 2.26E-08 1.75E-09 NO DATA 1.24E-08 NO DATA 3.58E-05 W 187 4.29E-07 2.54E-07 1.14E-07 NO DATA NO DATA NO DATA 3.57E-05 NP239 5.25E-09 3.77E-10 2.65E-10 NO DATA 1.09E-09 NO DATA 2.79E-05 25PARTA 12/16/96
VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 13 EFFLUENT T/S REQUIRED DOCUMENTS Page 69 of 92 A.
OFFSITE DOSE CALCULATIONS TABLE 2.1 INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)
NUCLIDE B0NE LIVER T.B0DY THYROID KIDNEY LUNG GI-lLI H
3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C 14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA 24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P 32 1.70E-03 1.00E-04 6.59E-05 NO DATA NO DATA NO DATA 2.30E-05 CR 51 NO DATA NO DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.llE-07 MN 54 N0 DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 MN 56 NO DATA 8.18E-07 1.41E-07 NO DATA 7.03E-07 NO DATA 7.43E-05 FE 55 1.39E-05 8.98E-06 2.40E-06 NO DATA NO DATA 4.39E-06 1.14E-06 FE 59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 C0 58 NO DATA 3.60E-06 8.93E-06 NO DATA NO DATA NO DATA 8.97E-06 C0 60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA N0 DATA 2.57E-05 NI 63 6.34E-04 3.92E-05 2.20E-05 NO DATA NO DATA NO DATA 1.95E-06 NI 65 4.70E-06 5.32E-07 2.42E-07 NO DATA NO DATA N0 DATA 4.05E-05 CU 64 NO DATA 6.09E-07 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-05 ZN 65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ZN 69 9.33E-08 1.68E-07 1.25E-08 N0 DATA 6.98E-08 NO DATA 1.37E-05 BR 83 NO DATA NO DATA 3.63E-07 NO DATA NO DATA N0 DATA LT E-24 BR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 1.94E-08 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.70E-04 8.40E-05 NO DATA NO DATA N0 DATA 4.35E-06 RB 88 NO DATA 4.98E-07 2.73E-07 NO DATA NO DATA N0 DATA 4.85E-07 RB 89 NO DATA 2.86E-07 1.97E-07 NO DATA NO DATA NO DATA 9.74E-08 SR 89 2.51E-03 NO DATA 7.20E-05 NO DATA NO DATA NO DATA 5.16E-05 SR 90 1.85E-02 NO DATA 4.71E-03 NO DATA NO DATA NO DATA 2.31E-04 SR 91 5.00E-05 NO DATA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 SR 92 1.92E-05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 NO DATA 2.33E-09 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 Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA N0 DATA NO DATA 1.92F-04 ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 N0 DATA 2.50F-05 ZR 97 1.48E-08 2.54E-09 1.16E-09 NO DATA 2.56E-09 NO DATA 1.62E-04 NB 95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 M0 99 NO DATA 3.40E-05 6.63E-06 NO DATA 5.08E-05 NO DATA 1.12E-05 TC 99m 1.92E-09 3.96E-09 5.10E-08 NO DATA 4.26E-08 2.07E-09 1.15E-06 25PARTA 12/16/96
VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 13 EFFLUENT T/S REQUIRED DOCUMENTS Page 70 of 92 A.
OFFSITE DOSE CALCULATIONS TABLE 2.1 INGESTION DOSE FACTORS FOR INFANT (MREM PER PCI INGESTED)
NUCLIDE B0NE LIVER T.800Y THYROID KIDNEY LUNG GI-Lll TC101 2.27E-09 2.86E-09 2.83E-08 N0 DATA 3.40E-08 1.56E-09 4.86E-07 RU103 1.48E-06 NO DATA 4.95E-07 N0 DATA 3.08E-06 NO DATA 1.8CE-05 RU105 1.36E-07 NO DATA 4.58E-08 NO DATA 1.00E-06 NO DATA 5.41E-05 RU106 2.41E-05 NO DATA 3.01E-06 NO DATA 2.85E.05 NO DATA 1.83E-04 AG110m 9.96E-07 7.27E-07 4.81E-07 N0 DATA 1.04E-06 NO DATA 3.77E-05 TE125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 NO DATA NO DATA 1.11E-05 TE127m 5.58E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE129m 1.00E-04 3.43E-05 1.54E-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 1.52E-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 DATA 7.11E-06 TE132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 NO DATA 3.81E-05 I 130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 NO DATA 2.83E-06 I 131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 I 132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 NO DATA 2.73E-06 I 133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 NO DATA 3.08E-06 I 134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 NO DATA 1.84E-06 I 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 NO DATA 2.62E-06 CS134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91r.-06 CS136 4.59E-05 1.35E-04 5.04E-05 NO DATA 5.38E-05 1.10E-05 2.05L-06 CS137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 CS138 4.81E-07 7.82E-07 3.79E-07 NO DATA 3.90E-07 6.09E-08 1.25E-06 BA139 8.81E-07 5.84E-10 2.55E-08 NO DATA 3.51E-10 3.54E-10 5.58E-05 BA140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 BA141 4.25E-07 2.91E-10 1.34E-08 NO DATA 1.75E-10 1.77E-10 5.19E-06 BA142 1.84E-07 1.53E-10 9.06E-09 NO DATA 8.81E-11 9.26E-11 7.59E-07 l
LA140 2.11E-08 8.32E-09 2.14E-09 NO DATA N0 DATA NO DATA 9.77E-05 LA142 1.10E-09 4.04E-10 9.67E-11 NO DATA NO DATA NO DATA 6.86E-05 CE141 7.87E-08 4.80E-08 5.65E-09 NO DATA 1.48E-08 NO DATA 2.48E-05 CE143 1.48E-08 9.82E-06 1.12E-09 NO DATA 2.86E-09 NO DATA 5.73E-05 CE144 2.98E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.71E-04 l
PR143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E-05 PR144 2.74E-10 1.06E-10 1.38E-11 NO DATA 3.84E-11 NO DATA 4.93E-06 ND147 5.53E-08 5.68E-08 3.48E-09 NO DATA 2.19E-08 NO DATA 3.60E-05 l
W 187 9.03E-07 6.28E-07 2.17E-07 NO DATA NO DATA NO DATA 3.69E-05 l
NP239 1.11E-08 9.93E-10 5.61E-10 NO DATA 1.98E-09 NO DATA 2.87E-05 25PARTA 12/16/96
i VOLUME 25 81G ROCK POINT RADIOLOGICAL Revision 13 EFFLUENT T/S REQUIRED DOCUMENTS Page 71 of 92 A.
OFFSITE DOSF. CALCULATIONS Table 2.2 BIG ROCK POINT DESIGN OBJECTIVE ANNUAL OVANTITIES FOR L10VID EFFLUENTS AS DETERMINED BY LA0 TAP Design objective annual quantities for liquid effluents were calculated utilizing the computer code LADTAP, a program for calculating radiation exposure to man from routine releases of nuclear reactor liquid effluents (reference NUREG/CR-1276).
Input parameters used are as follows:
Process Times Pathway _.
Aae Group Usaae 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
~)0.0 L/yr 800.0 16.6 Teen 510.0 800.0 16.6 Child 510.0 800.0 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 37.0 2.0 0.0 Child 14.0 2.0 0.0 Infant 0.0 2.0 0.0 Boating 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 tfme for drinking water were taken from the NUS study dated June 4, 1976. The minimum process times that can be utilized for fish 7,.. inking 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.
The fed-at i.mit to unrestricted areas for any individual through the liquid pa ' wa:
3 mrem, total body, and 10 mrem to any organ (Reference Part 50, Apper.c I).
The attached table lists ti _ dasign quantities as calculated from LADTAP.
25PARTA 12/16/96
VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 13 EFFLUENT T/S REQUIRED DOCUMENTS Page 72 of 92 A.
OFFSITE DOSE CALCULATIONS Table 2.2 BIG ROCK POINT DESIGN OBJECTIVE ANNUAL OVANTITIES FOR LIOUID EFFLUENTS AS DETERMINED BV LADTAP The following input parameters are used wher, running LADTAP for BRP:
1.
50-mile population - 1.54E05 2.
Shore width factor - 0.3 3.
Total discharge (ft*/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 water population - 7.07E03 9.
Shoreline population usaga (man-hours) - 3.8E07 1
10.
Swimming population usage (man-hours) - 1.2E07 11.
Boating population usage (man-hours) - 3.7F07 25PARTA 12/16/96
l VOLUHF. 25 BIG ROCK POINT RADIOLOGICAL Revision 13 EFFLUENT T/S REQUIRED DOCUMENTS Page 73 of 92 i
A.
OFFSITE DOSE CALCULATIONS Table 2.2 BIG ROCK POINT DESIGN OBJECTIVE ANNUAL OVANTITIES FOR LLQUJD EFFLUENTS AS DETERMINED BY LADTAP Design Objective Dose Conversion Annual Quantity Nuclide Factors (mrem /Ci)
Individual /0raan (Curies) 6 H-3 2.34E-06 Adult /TB 1.282 x 10 Na-24 3.95E-03 Teen /TB 759.49 Sc-46 1.24E-02 Teen /TB 241.94 Cr-51 1.90E-03 Adult /GI (LLI) 5,263.16 Mn-54 8.39E-02 Adult /GI (LLI) 119.19 Fe-55 5.50E-03 Child / Bone 1,818.18 Mn-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 /GI (LLI) 202.84 Co-60 2.90E-01 Teen /TB 10.34 Cu-64 1.48E-03 Teen /GI (LLI) 6,756.76 Ni-65 3.82E-04 Teen /TB 7,853.4 Zn-65 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 6,607.93 Sr-89 1.93E-01 Child / Bone 51.81 Sr-90 3.34E+00 Adult / Bone 2.99 Sr-91 2.90E-03 Teen /GI (LLI) 3,448.20 j
25PARTA 12/16/96
1 1
VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 13 EFFLUENT T/S REQUIRED DOCUMENTS Page 74 of 92 A.
OFFSITE DOSE CALCULATIONS Table 2.2 BIG ROCK POINT DESIGN OBJECTIVE ANNUAL QUANTITIES FOR LIOUID EFFLUENTS AS DETERMINED BY LA0 TAP Design Objective Dose Conversion Annual Quantity Nuclide Factors (mrem /Ci)
Individual /0raan (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 /GI (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 /GI (LLI) 3,649.64 Mo-99 1.31E-03 Teen / Kidney 7,633.59 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 /GI (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 /GI (LLI) 1,106.19 Te-127m 1.71E-01 Teen / Kidney 58.48 Te-129m 3.27E-01 Adult /GI (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 /GI (LLI) 35.97 5
I-132 1.95E-05 Teen /TB 1.538 x 10 Te-132 3.59E-01 Adult /GI (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 Tecn/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 Yeen/TB 98,360.7 Ba-140 2.75E-03 Adult /GI (LLI) 3,636.36 La-140 2.27E-02 Adult /GI (LLI) 440.53 Ce-141 2.30E-04 Teen /TB 13,043.5 Ce-144 4.08E-03 Adult /GI (LLI) 2,450.98 Eu-152 1.99E-01 Teen /TB 15.08 W-187 2.43E-01 Adult /GI (LLI) 41.15 Np-239 2.78E-03 Adult /GI (LLI) 3,597.12 25PARTA 12/16/96
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VOLUME 25 BIG ROCK POINT RADIOLOGICAL Revision 13 EFFLUENT T/S REQUIRED DOCUMENTS Page 76 of 92 A.
OFFSITE DOSE CALCULATIONS III.
URANIUM FUEL CYCLE DOSE III.A SPECIFICATION In accordance with Technical Specific 4 tion 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 calculated.
This calculation is performed to ensura that the annual (calendar year) dose or dose commitment to any member of the public is s25 mrem to the total body or any organ, except the thyroid, which shall be s75 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 ce a fisnemn.
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 shorelin9 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 af 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. hours for the first quarter.
III.B.3 The dose contribution due to uranium fuel cycle sources other than the plant is ignored in the calculation.
This is based on the lack of any operations that fall in the "tycles" definition within a 5 mile radius of Big Rock Point.
I l
l 25PARTA 12/16/96 1
Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL Page 77 of 92 EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS III.C DOSE CALCULATION Maximum doses to the total body and internal organs of an individual shall be determined by use of LADTAP and GASPAR computer codes, and doses to like organs and total body summed.
Added to this sum will be a mean dose rate, calculated or measured for the shoreline due to plant presence during the quarter in question, times the assumed fishing time:
(III.1)
D
=Dg+DL + (R )(T)
T 40, where:
40 CFR 190 dose to organ (i) (mrem).
D 40 g Cumulative dose to en individual organ from gaseous D
G releases (mrem)..
Cumulative dose to an individual organ from liquid D
g releases (mrem).
Mean dose rate (direct radiation ccmponent) calculated R
to be applicable to Lake Michigan shoreline adjacent
=
T to plant site (mrem /hr).
Assumed shoreline fishing time for the quarter in T
question (hours) (see Section III.B.2).
NjQTE:
For this calculation, total body is considered as an organ.
25PARTA 12/16/96
Revision 13 VOLUME 25 BIG ROCK POINT RADIOLOGICAL Page 78 of 92 EFFLUENT T/S REQUIRED DOCUMENTS A.
OFFSITE DOSE CALCULATIONS SD APPENDIX A DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING REQUIREMENTS l
l 25PARTA 12/16/96
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OFFSITE DOSE CALCULATIONS l
APPENDIX A DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING REQUIREMENTS COMMITMENTS AND REPORTING RE0UIREMENTS 1.
Commitments related to Discharge Canal Dredging are given in the CPCo December 29, 1989 Application for Disposal of Dredged Discharge Canal Sediment and in the NRC Safety Evaluation dated August 31, 1990.
I.A COMMITMENTS Prior to dredging the canal, radionuclide concentrations and I.A.1 environmental exposure pathway doses must be evaluated in a manner equivalent to that described in the CPCo December 29, 1989 application.
with This evaluation must include a comparison of resultant doses the following NRC staff guidelines for onsite disposal:
The radioactive material should be disposed in a manner such 1.
that it is unlikely that material would be recycled.
Doses to the total body and any body organ of the maximally 2.
exposed individual (a member of the general public or a non-occupationally exposed worker) from the probable pathways of exposure to the disposed material should be less than 1 mrem /yr.
Doses to the total body and any body organ of an inadvertent 3.
intruder from the probable pathways of exposure should be less than 5 mrem /yr.
Doses to the total body and any body organ of an individual 4.
from assumed recycling of the disposed material at the time the disposal site is released from regulatory control from all likely pathways of exposure should be less than 1 mrem.
The dredging spoils will be thoroughly surveyed using a I.A.2 gama-sensitive instrument prior to release for public use.
Release for public access will be contingent upon confirmation that post-disposal area dose rate has not increased above pre-disposal area background, as defined by criterion that pre-The value o and post-disposal levels vary by not more than 25%.
25% allows for temporal variations observed in monthly environmental TLD background data.
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OFFSITE DOSE CALCULATIONS APPENDIX A DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING REQUIREMENTS Quality Control surveillance will be performed to ensure the I.A.3 dredge material is deposited in the location specified in the Dredging Permit and is graded accordingly.
Confirmatory measurements of the dredged materials will be I.A.4 recorded after the dredgings are land-spread.
)
I.B REPORTING REQUIREMENTS If the NRC staff guidelines in I.A.1 cannot be met, a new I.B.I must be submitted for the disposal.
application per 10 CFR 20.2002 Should the measurement of I. A.2 and I. A.4 indicate that the levels I.B.2 of radioactivity measured in the pre-operational (pre-dredging) sediment samples were significant underestimates (greater than 25%) of the actual radioactivity of the dredging spoils, CPCo The NRC will then reassess possible will notify the NRC.
radiation doses and require appropriate remedial actions as appropriate.
II.
PRE-ORE 0GING RE0VIREMENTS Mechanical dredging of Big Rock Point's Discharge Canal introduces a potential of re-releasing radionuclides absorbed on sediment to the environment in a manner not already accounted for in release i
records.
Disposal of dredging spoils by relocation from the plant discharge canal to an unrestricted area onshore as specified by Corps of II.A 88-56-143 and 87-56-185 has been Engineers Permits Numbers reviewed in the approved NRC Safety Evaluation dated August 31, If a new permit is to be used for dredging, review the 1990.
permit requirements to ensure no unreviewed exposure pathway has been created.
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0FFSITE DOSE CALCULATIONS APPENDIX A DISCHARGE CANAL DRE0GING COMMITMENTS AND REPORTING REQUIREMENTS Prior to dredging the canal, a minimum of 10 sediment samples j
The distribution of the sample points should II.B should be collected.
Sediment sample be representative of the area to be dredged.
i collection should be coordinated with plant operations to ensure there are no radioactive liquid batch releases during or within the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> previous to sediment sampling.
The concentration and total activity of the material to be dredged will be determine for each isotope identified in the sediment 11.B.1 Results of semi-annual sediment samples taken from the samples.
canal discharge since the time of the previous canal dredging may be used to aid in evaluation of the sediment activity below the immediate surface.
These expected activity concentrations will be compared to the activities given in Table A-1 and will be used as the basis for II.B.2 comparison to the total exposures given in Table A-2.
If any isotopes not listed above are present in the sediment i
samples, the dose contribution from these isotopes must be II.C determined for all exposure pathways in a manner equivalent to the calculations used in the December 29, 1989 application which are 1
outlined in Section V.
The calculated doses will be compared to the NRC staff guidelines If any of these guidelines cannot be met, 11.0 given in Section I.A.I.the disposal of the particular dredging wi outside the scope of the 10 CFR 20.302 review already approved by the NRC in the Safety Evaluation dated August 31, 1990.
In this event, a new application for disposal will be submitted to the NRC for this particular dredging or an alternative disposal method will be pursued.
A pre-dredging survey of the disposal area should be provided no more than 10 days prior to dredging to provide a baseline for II.E comparison to post-dredging survey.
Dredging operations should be coordinated with piant operations to ensure no liquid batch releases within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to dredging II.F and no liquid batch releases during the time period of the dredging.
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OFFSITE DOSE CALCULATIONS APPENDIX A DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING REOUIREMENTS POST-DREDGING REQUIREMENTS III.
A post-dredging survey of the area should be provided no more than Should these III.A 10 days after the spoils are land-spread.
measurements indicate the activity in the disposal area has increased greater than 25% of the pre-dredging act:vity, the NRC will be notified.
Sediment samples will be analyzed and recorded as confirmatory measurements of the dredged materials after the dredgings ar III.B land-spread.
(pre-dredging) of radioactivity measured in the pre-operational sediment samples were significant underestimates (greater than 25%) of the actual radioactivity of the dredging spoils, the NRC The NRC will reassess possible radiation doses will be notified.
and require remed' 1 actions as appropriate.
DOCUMENTATION REQUIREMENTS IV.
Records of survey and sampling results shall be maintained until the NRC authorizes disposition.
EVALUATION OF THE RADIOLOGICAL IMPACTS OF SEDIMENT D V.
Potential dose pathways due to dredging and disposing of sediment from the BRP Discharge Canal include:
external dose from the sediment during dredging, 1.
2.
groundshine in the disposal area, inhalation of re-suspended isotopes from dried sediment blown 3.
by the wind, dose from assumed infiltration and contamination of 4.
groundwater, and internal dose from ingestion of food grown on the disposal 5.
site.
The maximum dose to workers will be to those workers involved i grading the sediment in the disposal area during the dredging The dose to these workers is determined as operations.
groundshine in the disposal area (exposure pathway 2).
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OFFSITE 00SE CALCULATIONS APPENDIX A l
DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING REQUIREMENTS Dose from assumed infiltration and contamination of groundwater is of minimal concern in this case on the basis of locatio area or between the disposal area and Lake Michigan (direction of to Lake Michigan.
Exposure to the general public from activity groundwater flow).
released to Lake Michigan via this pathway is accounted for in Big Rock Point Semiannual Radioactive Effluent Re' lease Reports ba on data at the time of the original liquid radioactive releasesThe activi from which the dredged activity is derived.
on the sediment removed from the canal and re-release Michigan via this pathway will not increase those origin exposure estimates.
for previously, estimates due to potential radiof Internal exposure from ingestion of food grown on the disposal s;te is not of concern due to lack of nutrient content within this The disposal sites also are washed stone / gravel / sand mixture.
Cultivatable vegetation is unprotected from harsh offshore winds.
not supported in either area.
Conservative calculations of external expos of dried windblown sediment are detailed below.
External Dose from the Sediment during Dredging and Ground V.A the Disposal Area Assume the worker is exposed a total of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The disposal area may be part of a nature trail open to the public.
Assume time spent on the nature trial is half the average time spent for shoreline recreation (per Regulatory Guide 1.10 Child 7 hr/yr 34 hr/yr (this is taken as maximum public exposure time)
Teen Adult 6 hr/yr 25PARTA 12/16/96
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DISCHARGE CANAL DREDGlhG_ COMMITMENTS AND REPORTING REQUIREMENTS It is reasonable to assume plant personnel using the trail for walks during work breaks also will frequent the area often.
t - 2 walks / day x.25 hr/ walk x 5 days / week x 50 week /yr t - 125 hr/yr However; due to weather conditions, the trails will be accessible only 3 months per year.
t = 31 hr/yr (since this is not as long as the teen usage time calculated above, the 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> for teen exposure is used for dose to public.)
UsingmethgdsandparametersdescribedinRegulatoryGuide1.109 the dose D; (r, 0) to the worker is given as:
03(r,0)-24hoursSF
[
CO (r, 0) DFG g3 i
~
Where C, is in [pCi/m2]
DFG - open field groundplane dose conversion factor
[ mrem-m8/pci hr].
Valves of DFG are given in 00CM Table 1.8.
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OFFSITE DOSE CALCULATIONS APPENDIX A DISCHARGE CANAL OREDGING COMMITMENTS AND REPORTING REOUIREMENTS SF = Shielding Factors The thickness of sediment graded out in the disposal area will Assuming the minimal shielding (ie, range from 2 to 4 inches.2 inch thickness), there will be approx sediment as shielding.
From American Institute of Steel Construction (AISC) Manu Steel Construction 7th Edition l
l a dry sediment = 90 to 105 lb/ft* for excavated sand and gravel dry and loose taking p dry sediment as.98 lb/ft' = > p = 1.57 g/cc l
f (p/p)hr
= 0.0578 cm /g 2
sediment y dry sediment = 1.57 g/cc x 0.578 cm /g 2
-I y dry sediment = 9.07E-02 cm
-M* = e-9.07E-02/cm (2.54 cm)
SF = e SF = 0.79 j = ground activity [pC /m8]
C g
0
= activity [pCj/g] x p dry sediment [g/cc) x 10 cc/m8 x thickness of layer (2" or 5.08E-02 m) 9 [pC /m ] = 7.98E+04 x activity [pC /g]
2 C
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0FFSITE DOSE CALJJLATIONS APPENDIX A DISCHARGE CANAL DREDGING COMMITNENTS AND REPORTING RE0VIREMENTS Assuming dredging is performed annually and each year the new sediment is deposited and spread to 2" over the previous sediment, the groundshine exposure each year will increase as total Dj year two = 03 year one Be-M1 yr)e-g(2") + Dj year two total Dj year three - Dj year one Be-M2 yr),- (4")
+DjyeartwoBe-M1 yr)e-g(2") + Dj year three etc But Dj year n = Dj year one Therefore 10 -M "~I) e-g(2")(n-1) B[2(n-1)p]
total Dj year ten = Dj year one I e n=1 The accumulative dose each year will increase as X
Djyearx=I Djyearn n=1 B = Buildup = 1 + a (pX) + b (gX)2 + c (gX)*
Where for Mn54 a = 1.04 b = 0.21 c=0 Co60 a = 0.78 b = 0.08 c=0 Cs134 a = 1.07 b = 0.28 c=0 Cs137 a = 1.07 b = 0.14 c=0 Doses to the most exposed member of the public (teen exposed 34 hrs /yr) are 34/24 = 1.42 times the worker doses.
Buildup fo: tors for gamma emitters not listed above can be obtained using the Table A-3.
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OFFSITE 00SE CAL ULATIONS APPENDIX A DISCHARGE CANAL DREDGING CCMMITMENTS AND REPORTING RE0VIREMENTS V.B Inhalation of Re-Suspended Isotopes from Dried Sediment Blown by Wind Using methodology of Regulatory Guide 1.109, the annual organ dose from inhalation of radionuclides in air is:
D,(r,0) = R, E xg (r,0) DFAija ija ' inhalation dose factor [ mrem /pC ]
Where DFA g
Values of DFA given in ODCM Table 1.7.
Ra - annual intake for individual (m*/yr]
Ra infant - 1400 m*/yr l
Ra child - 3700 in8/yr Ra teen, Ra adult - 8000 m'/yr y - annual average concentration of radionuclide in X
air [pC /m8]
g
\\
From Mark's Standard Handbook for Mechanical Engineers (pg.18-12). The amount of suspended matter in normal city air = 1.37 mg/m2 and the amount of suspended matter in 8
manufacturing plant - 4.58 mg/m i
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OFFSITE DOSE CALCULATIONS APPENDIX A DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING RE0VIREMENTS I
Using the value for suspended matter in normal city air would be conservative considering that fresh clean air blows off Lake Michigan across the disposal site to re-suspend isotopes from the dried sediment. Assuming a gentle breeze throughout the year since individuals would not remain in the area if higher winds blowing the sand were present.
For added conservatism the value for suspended matter in a manufacturing plant is used.
The maximum time an individual would be in the area is 260 I
hours /yr as determined for fisherman by the discharge canal (RAE 81-53).
Therefore the annual intake for each individual is reduced by the factor f.
260hr/vr I " 8760hr/yr f = 0.03
- Then, g [pC /gm] x.03
~
Xg [pC /m ) = 4.58 mg/m x.001 g/mg x activity 2
8 g
g S
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OFFSI1E DOSE CALCULATIONS APPENDIX A DISCHARGE CANAL OREDGING COMMITMENTS AND REPORTING RE0VIREMENTS V.C Dose from Infiltration and Contamination of Groundwater There are no wells in or near the disposal sites.
Ground water flow is toward Lake Michigan at a rate of 0.05 ft/ day (per FHSR).
The distance from the nearest edge of the west side disposal site (Permit Number 87-56-185) to Lake Michigan is ~14 ft.
The distance from the nearest edge of the east side disposal site (Permit Number 88-56 143) to Lake Michigan is 25 ft.
The retention time for radionuclides deposited at the west side disposal site is:
14 ft + 0.05 ft/ day - 280 days minimum and for the east side disposal site is 25 ft + 0.05 ft/ day - 500 days minimum In the interest of conservatism, we assume all the radionuclides from a single dredging will be released from the disposal area into Lake Michigan, 280 days after dredging.
Dosa calculational methods from the Big Rock Point Radiological Effluents Technical Specifications Offsite Dose Calculations Manual (0DCM) for liquid effluents are used to determine the annual dose to individuals exposed via this pathway.
The total dose from this pathway is calculated in the 1989 10 CFR 20.302 Submittal, using the ratio of annual DBQ fraction representing activity of dredging to annual DBQ fraction representing total annual liquid release activity. This fraction is used to determine total exposure based on the annual liquid effluent exposure determined using the LADTAP code.
2 D
annual liquid dose from LADTAP Dose from dredging A
release This method is conservative. A more accurate method to estimate dose from infiltration and contamination of ground water is provided in ODCM Section II C for all liquid exposure pathways.
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OFFSITE DOSE CALCULATIONS APPENDIX A DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING REQUIREMENTS TABLE A-1:
RADIOLOGICAL PROPERTIES OF SEDIMENT (pC /gm) g NUCLIDE VARIATION AVERAGE VARIANCE (S)
TOTAL t (MIN) T0 (MAX)
ACTIVITY (mC )
i Sr 90 0-0.108 0.015 0.032 0.001 M1 65 0-1.996 0.202 0.312 0.147 Co 60 0-4.904 0.431 0.785 0.314 Cs 134 0-0.070 0.001 0.002 0.001 Cs 137 0.170-1.583 0.605 0.309 0.441 Gross Beta
- 5.90-17.50 9.696 3.225 7.07 Average Gross Beta at control sampling location (Ludington) = 8.19 with variance of 3.07 [pCj/gm wet). Therefore, no unidentified beta emitters present. Dose due to beta activity is taken into account in dose calculations for specific isotopes, t Total Activity -
Average Concentration (pCj/gm wet) x max mass excavated (gm) x '(ImCj/109 pCj).
Assuming 500 cubic yards excavated with density of 119 lb/ft* (density of excavated sand, gravel wet -
118 to 120 lb/ft* per AISC Manual of Steel Construction 7th Edition)
Max mass excavated - 500 cu yard (27 ft8/cu yard) 119 lb/ft* x (453.592 g/lb) - 7.29E+08 gm.
These analyses include samples taken annually from 1985 through 1989 as part of Big Rock Point's Radiological Environmental Monitoring Program as well as ten (10) samples taken in June 1989 to ensure samples are representative of activity distributed throughout the canal. The results of these analyses provide a conservative estimate of the activity which may be contained in the sediment at the time of dredging.
The total activity of the sediment is based on the average activity concentration encountered in surface samples (see Appendix 1).
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OFFSITE DOSE CALCULATIONS APPENDIX A DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING RE0VIREMENTS TABLE A-2:
RADIOLOGICAL IMPACT OF SEDIMENT DISPOSAL -
SUMMARY
OF VALUES CALCULATED IN AFPENDIX 2 Integrated Dose Due Dose due to to Annual Dredging Exposure Pathway Sinale Dredoino (mrem /vr) throuah 1998 (mrem)
External Dose to Sediment During Dredging (worker) 2.13E-02 5.83E-01 External Dose Due to Groundshine in the Disposal i
Area (public) 3.02E-02 8.27E-01 j
l Internal Dose i
Due to Inhalation of Resuspended Isotopes 8.67E-04 8.67E-03 Dose from Assumed Infiltration and Contaminatfoa of Groundwater 3.33E-03 3.33E-02 Total Dose 5.57E-02 mrem
- 1.44 mrem /10 yrs i
first year i
- HQIf,: The total dose is extremely conservative since no individual will i
receive the total dose from each pathway.
NRC did not include external dose to sediment during dredging (worker) in the totals approved in the Safety Evaluation dated August 31, 1990.
Total doses to the general public of 3.57E-02 mrem / year and 8.57E-01 mrem / ten years were accepted.
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OFFSITE DOSE CALCULATIONS APPENDIX A DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING RE0VIREMENTS B
TABLE A-3:
BUILDUP FACTOR PARAMETERS Average Gamma PARAMETER Energy (MeV)
A B
C 0.5 1.10 0.385 0
1.0 1.02 0.122 0
2.0 0.76 0.046 0
4.0 0.55 0.008 0
6.0 0.52 0.007 0
8.0 0.33 0.006 0
10.0 0.28 0.006 0
These valves are based on results from MLTobias, DRVondy, and MPLietzke; Nightmare Program; Oak Ridge National Laboratory, February 26, 1972.
Parameter valves have been interpolated for concrete (z of material - 11).
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A.
OFFSITE DOSE CALCULATIONS APPENDIX A
)
l l
DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING RE0VIREMENTS l
TABLE A-2:
RADIOLOGICAL IMPACT OF SEDIMENT DISPOSAL -
SUMMARY
OF VALUES CALCULATED IN APPENDIX 2 l
Integrated Dose Due Dose due to to Annual Dredging i
l Exoosure Pathway Sinale Dredaina (mrem /vr) throuah 1998 (mreml External Dose to Sediment During Dredging (worker) 2.13E-02 5.83E-01 External Dose Due to Groundshine in the Disposal Area (public) 3.02E-02 8.27E-01 l
Internal Dose Due to Inhalation of Resuspended Isotopes 8.67E-04 8.67E-03 Dose from Assumed Infiltration and Contamination of Groundwater 3.33E-03 3.33E-02
~
Total Dose 5.57E-02 mrem
- 1.44 mrem /10 yrs first year 4
- N_0TE: The total dose is extremely conservative since no individual will receive the total dose from each pathway.
NRC did not include external dose to sediment during dredging (worker) in the totals approved in the Safety Evaluation dated August 31, 1990.
Total doses to the general public of 3.57E-02 mrem / year and 8.57E-01 mrem / ten years were accepted.
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OFFSITE DOSE CALCULATIONS APPENDIX A DISCHARGE CANAL DREDGING COMMITMENTS AND REPORTING REQUIREMENTS TABLE A-3:
BUILDUP FACTOR PARAMETERS Average Gamma PARAMETER Energy (MeV)
A B
C 0.5 1.10 0.385 0
1.0 1.02 0.122 0
2.0 0.76 0.046 0
4.0 0.55 0.008 0
6.0 0.52 0.007 0
8.0 0.33 0.006 0
10.0 0.28 0.006 0
l These valves are based on results from MLTobias, DRVondy, and MPLietzke; Nightmare Program; Oak Ridge National Laboratory, February 26, 1972.
Parameter valvas have been interpolated for concrete (z of material - 11).
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