ML20073P288
| ML20073P288 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 03/31/1983 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20073P276 | List: |
| References | |
| PROC-830331, NUDOCS 8304250106 | |
| Download: ML20073P288 (86) | |
Text
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SNPS-1-ODCM 4
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LONG ISLAND LIGHTING COMPANY l
4 t-OFFSITE DOSE CALCULATION MANUAL l
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March 1983 i-83042501'06 IB30420 W
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SNPS-I ODCM
' TABLE OF CONTENTS Radiological Effluent Technical Specification Section Subiect Section Page 1.,0 INTRODUCTION 1-1 2.0 SET POINTS 2-1 2.1 LIQUID EFFLUENT SET POINT 3.3.7.11 2-1 2.1.1 Liquid Radwaste Effluent Line Flow Indicator Set Point (FE-179) 2-1 2.1.1.1 Discharge Waste Sample Tanks, and Recovery Sample Tanks Discharge Radiation Monitor Set Point (RE-013) 2-2 2.1.2 Reactor Building Salt Water Drain Tank Discharge Monitor Set Point (RE-079) 2-4 2.1.3 Residual Heat Removal Heat Exchanger Service Water Outlet Monitor Set Point (RE-023) 2-5 2.2 GASEOUS EFFLUENT MONITOR SET POINT 3.3.7.12 2-6 2.2.1 Method 1 (Computerized Method) 2-6 2.2.2 Method 2 (Noncomputerized Method) 2-6
[s 2.2.2.1 Gaseous Effluent Monitor Set Point
\\
Based on Noble Gases Total Body Dose Rate 2-7 2.2.2.2 Gaseous Effluent Monitor Set Point Based on Noble Gases Skin Dose Rate 2-8 2.2.2.3 Gaseous Effluent Monitor Set Point Based on Organ Dose Rate 2-9 2.2.3 Main Condenser Offgas System Effuent Monitor Set Point (RE-065) 2-10 2.2.4 Main Condenser Air Ejector t
Monitor Set Point (RE-012) 2-11 2.2.5 Main Condenser Air Ejector Effluent, Bypass Mode, Set Point (RE-012) 2-11 2.2.5.1 Main Condenser Air Ejector Effluent, Bypass Mode Set Point Based on Main Condenser Air Removal Pump Discharge Monitor (RE-051) 2-12 3.0 DOSE CALCULATION METHODS 3-1 I
3.1 -
LIQUID EFFLUENT, DOSE CALCULATION 3.11.1.2 3-1 3.1.1 Method 1 (Computerized Method) 3-1 3.1.2 Method 2 (Noncomputerized Method) 3-3 l
l Original
,,,111 March 1983 l
l
SNPS-1 ODCM Radiological Effluent Technical Specification Section Subiect Section Pace 3.2 OPERATION OF LIQUID WASTE TREATMENT SUBSYSTEMS 3.11.1.3 3-4 3.3 DOSE RATE DUE TO GASEOUS EFFLUENTS 3-4 3.3.1 Method 1 (Computerized Method) 3-4 3.3.1.1 Noble Gas Total Body and Skin Dose Rate 3.11.2.1 3-4 3.3.1.2 Organ Dose Rate (Particulate Releases) 3.11.2.1 3-5 3.3.2 Method 2: (Noncomputerized Method) 3-5 3.3.2.1 Noble Gas Total Body Dose Rate 3.11.2.1 3-5 3.3.2.2 Noble Gas Skin Dose Rate 3.11.2.1 3-7 3.3.2.3 Organ Dose Rate (Particulate Releases) 3.11.2.1 3-9 3.4 GASEOUS EFFLUENTS, NOBLE GAS AIR DOSE 3.11.2.2 3-11 3.4.1 Method 1: (Computerized Method) 3-12 3.4.1.1 Noble Gas Gamma and Beta Air Dose 3.11.2.2 3-12 3.4.2 Method 2: (Noncomputerized Method) 3-12 3.4.2.1 Noble Gas Gamma Air Dose 3.11.2.2 3-12 3.4.2.2 Noble Gas Beta Air Dose 3.11.2.2 3-14 3.5 GASEOUS EFFLUENT, DOSE DUE TO RADIOIODINES AND RADIOACTIVE MATERIALS IN PARTICULATE FORM, AND RADIONUCLIDES 3.11.2.3 3-16 i
3.5.1 Method 1: (Computerized Method) 3-16 l
3.5.1.1 Organ Doses 3.11.2.3 3-16 I
3.5.2 Method 2: (Backup Method) 3-20 l
3.5.2.1 Organ Doses 3.11.2.3 3-20 3.6 OPERATION OF VENTILATION EXHAUST TREATMENT SYSTEM 3.11.2.5 3-23 4.0 RECEPTOR LOCATIONS, METEOROLOGY AND HYDROLOGY 4-1 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS 5-1 O
Original iv March 1983
=_
SNPS-1 ODCM LIST OF TABLES
()
~ Title Table 2.2-1 Dose-Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 3.1 Bioaccumulation Factors to be Used in the Absence of Site-Specific Data 3.1 Ingestion Dose Factors for Adults 3.1-3 Ingestion Dose Factors for Teenager 3.1-4 Ingestion Dose Factors for Child 3.1-5 Decay Constants 3.1-6 External Dose Factors for Standing on Contaminated Ground 3.1-7 Dose Rate Conversion
- Factors, A
for (Fish and Invertebrate) Ingestion Pathway 3.3-2 Child Inha'lation Dose Rate Conversion Factors, Pij 3.4-1 Noble Gas Dose Factors O
3.5-1 Inhalation Dose Factors for Adults 3.5-2 Inhalation Dose Factors for Teenager 3.5-3 Inhalation Dose Factors for Child 3.5-4 Inhalation Dose Factors for Infant 3.5-5 Recommended Values for U to be Used for the Maximum Exposed Individual in Lieu of Site-Specific Data 3.5-6 Stable Element Transfer Data 3.5-7.
Humidity Parameters at Receptors 3.5-8 Child Inhalation Dose Rate Conversion Factors, Pij 3.5-9 Poij Contaminated Ground, Ingestion of Leafy and Stored Vegetables Dose Rate Conversion Factors
-3.5-10 Distance from Reactor Centerline by Sector Out to 8046 m
()
Original v
March 1983
~ ~..
SNPS-1 ODCM LIST OF TABLES (CONT'D) 3.5-11
- Poij, Child Ingestion of Cow's Milk Dose Rate Conversion Factors 3.5-12
- Poij, Child Ingestion of Goat's Milk Dose Rate Conversion Factors 3.5-13
- Poij, Child Ingestion of Meat Dose Rate Conversion Factors 3.5-14
- Poij, Infant Ingestion of Cow's Milk Dose Conversion Factors 3.5-15
- Poij, Infant Ingestion of Goat's Milk Dose Conversion Factors 4-1 Critical Receptor Locations for Gaseous Effluent Calculations O
i l
Original vi March 1983 4
= - =. _ -
SNPS-1 ODCM LIST OF FIGURES Fiqure Title l
3.1-1 Site Boundary for Liquid Effluents 3.2-1 Liquid Radwaste Treatment System 3.6-1 Ventilation Exhaust Treatment System.
5-1 On Site Sampling Locations - Radiological Environmental Monitoring Program 5-2 Off Site Sampling Locations - Radiological Environmental Monitoring Program i
i O
i f
Original vii March 1983
p SNPS-1 ODCM
()
1.0 INTRODUCTION
The-purpose of this manual is to show the calculational methodology and-parameters used to comply with the Radiological' Effluent Technical Specification (RETS).
Section 2.0 establishes methods to calculate the Liquid Effluent
-Monitor set point and the Gaseous Effluent Monitor set point in order to comply with RETS Sections 3.3.7.11 and 3.3.7.12, respectively.
Section 3.0 establishes dose calculational methods for liquid and gaseous' effluents.
The liquid effluents dose calculation methods
-are used-to show compliance with RETS Sections 3.11.1.2 and 3.11.1.3.
The dilution factor of 8.85 used in calculation Method 2
is a calculated value based on a submerged, multiport diffuser with a port discharge velocity of 12 fps and a
300 ft radius mixing zone.
The gaseous' effluent dose calculation methods are used to show compliance with RETS Sections 3.11.2.1, 3.11.2.2, and 3.11.2.3.
The atmospheric dispersion and deposition factors used in calculation methods were calculated based on onsite meteorological data for the 2 year period October 1, 1973 -
September 30, 1975.
()
Section 4.0' identifies the' receptor locations which represent critical pathway locations, water
- dilution, atmospheric dispersion, and deposition factors used in calculation Method 2.
Table 4-1 summarizes the above factors for the gaseous effluent pathways.
Section 5.0 indicates locations at which environmental sampling may be conducted.
Tables 3.5-11 through 3.5-15 are incorporated only for future use if there is a change in the land use census which requires considering any combination of the following pathway (s): cows' milk; goats' milk; and meat.
l t
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Original 1-1 March 1983
SNPS-1 ODCM
.2. 0 SET POINTS
,s I
I 2.1 LIQUID EFFLUENT SET POINT (Compliance with Sections 3.3.7.10 and 3.11.1.1 of the Radiological Effluent Technical Specification (RETS)
The radionuclide concentrations released into Long Island Sound via-the diffuser may not exceed the concentrations specified in
- 10CFR20, Appendix B, Table II, Column 2 and 2.00E-04 gCi/ml for dissolved or entrained noble gases.
The alarm set point of the_ effluent monitors is dependent on:
1.
circulating water flow rate,.a once-through system (the circulating water' system is composed of four pumps and circulates sea water at a rate of 574,000 gpm) 2.
discharge waste sample tank flow rate, 3.
isotopic coniposition of liquid to be discharged, and 4.
the maximum permissible concentration (MPC) of the radionuclides in the effluent.
2.1.1 Liquid Radwaste Effluent Line Flow Indicator Set Point (FE-179)
(^'s A
sample will be taken of the liquid to be discharged and an
(,)
isotopic analysis performed.
Using the results of the isotopic
- analysis, calculate the following:
C Ca Cb Cn 4
etc. = concentration of the individual radio Ca Cb,
nuclides identified (uci/ml), and MPCA, MPC, etc. = maximum permissible concentration of B
the respective radionuclides
( uCi/ml) from
Table II, Column 2.
For dissolved or entrained noble gases, the MPC assumed will be 2.00E-04.
C The quantity MPC is numerically equivalent to the required dilution factor (i.e., circulating water flow rate / tank discharge flow rate).
OO Original 2-1 March 1983
-v
--~,-r-
,.n-.-
SNPS-1 ODCM Obtain the circulating water discharge flow rate from the control room.
Calculate the radwaste discharge isolation release rate as follows:
Cire. Water Flow (qpm) *.8 Isolation Release Rate (gpm)
=
C MPC This isolation release rate is the maximum discharge pump release i
rate which would discharge the tank contents at exactly 80 percent of the MPC permitted in 10CFR20, Appendix B, Table II, Column 2 and 2.00E-04 uCi/ml for dissolved and entrained noble gases.
1 1
2.1.1.1 Discharge Waste Sample Tanks, and Recovery Sample Tanks Discharge Radiation Monitor Setpoint (RE-013)
The function of this monitor set point is to verify that the liquid radwaste being discharged has the same activity as was i
analyzed to be discharged.
If the activity is higher than the activity which was analyzed to be discharged, the radiation l
monitor will terminate the release.
l l
A sample is taken from the discharge waste sample tanks or recovery sample tanks.
1.
Discharge waste sample tanks or recovery sample tanks as applicable 2.
Reactor building salt water drain tank discharge i
3.
Residual heat removal heat exchanger service water discharge.
Service water discharge and an isotopic analysis of each sample is performed.
This analysis includes isotopic analysis for gamma
If the analysis for alpha
- emitters, beta
- emitters, and specifically Sr-89, Sr-90, Fe-55, Ha cannot be performed at the time of discharge, then the concentrations done to comply with Technical Specification Table 4.11.1.1.1-1 will be used.
Obtain the circulating water flow rate from the control room.
The set point is calculated as follows:
l O
Original 2-2 March 1983
SNPS-1 ODCM Discharge waste sample tanks setpoint:
N Setpoint
=
C E
fD+
R+f'+
S+
C H)
(cpm)
~
Di g
H
_ 1"1
~
N gD Di + fR Ri +
S si +
H Ri i=1 (MPC)g Recovery sample tanks setpoint:
J
~~
N
~
Setpoint =
[
C E
fD+
R+
H+
S+
(
cpm)
~
gg g
C H
_ 1" I N
b D Di + fR Ri +
S Si +
H Ri (MPC)g Where CDi Discharge waste sample tank concentration of
=
radioisotope (i)(pC /ml) i CRi Recovery sample tank concentration of radioisotope (i)
=
(uC /ml) i Reactor building salt water drain tank concentration of Cg
=
g radioisotope (i) (pCi/ml) chi RHR heat exchanger service water outlet concentration of
=
radioisotope (i) (uC /ml) i fo Discharge waste sample tank discharge flow rate (gpm)
=
fR Recovery sample tank discharge flow rate (gpm)
=
O Original 2-3 March 1983 s
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,,r-.
,,.. ~ - -,,,.
.-n-n
,,,, ~, -,
w,,,,,,,-,,-,.,,,..n--,,---n-
SNPS-1 ODCM f3 Reactor building salt water drain tank dischajge flow
=
rate (gpm),
f RHR heat exchanger service water outlet discharge flow
=
H rate (gpm),
F Total circulating water flow rate (gpm) (this includes
=
C
)
Ei councing efficiency of RE-013 for radionuclide(i) (cpm /
=
Ci/ml)
(MPC)i=
maximum permissible concentration of nuclide (i)(uC /ml) i from 10CFR20, Appendix B,
Table II, Column 2.
For dissolved or entrained noble gases, the MPC assumed will be 2.00 E-04.
The above calculation is made for,each batch released.
2.1.2 Reactor Building Salt Water Drain Tank Discharge Monitor Set Point (RE-079)
The function of this monitor set point is to verify that the release from the reactor building salt water drain tank does not exceed the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 and 2.00E-04 uci/ml for dissolved or entrained noble gas.
A sample will be taken from the reactor building salt water drain tank discharge along with individual samples of any of the following streams which may be in the process of being discharged:
1.
Discharge waste sample tank discharge 2.
Recovery sample tanks discharge 3.
Residual heat removal heat exchanger service water discharge An isotopic analysis of each sample is performed.
This analysis includes isotopic analysis for gamma
- emitters, alpha
If the analysis for alpha
- emitters, beta
- emitters, and specifically Sr-89, Sr-90, FE-55, Ha cannot be performed at the time of discharge, then the concentrations done to comply with Technical Specification Table 4.11.1.1.1-1 will be used.
Obtain the circulating water flow rate from the control room.
O Original 2-4 March 1983
SNPS-1 ODCM The set point will be calculated as follows:
O Set point =
[
CRi i
D+
R H+ S+ (C H
~
_i=1 N
(cpm) f
]"
D Di + fR Ri +
S Si +
H Ri i=1 (MPC)g Where:
counting /ml) efficiency 'of RE-079 for radionuclide(i)
E=
i (cpm /uct All other parameters are as defined in Section 2.1.
When the tank operates on a batch mode, the above calculation is made for each batch to be released.
1 2.1.3 Residual Heat Removal Heat Exchanger Service Water Outlet Monitor Set Point (RE-023)
The function of this monitor is to detect RHR leakage into the service water.
The service water is expected to contain activity only if there is RHR system leakage.
Therefore, initially the set point will be based on three times the background.
After operation of RHR
- system, and if activity is measured in the service water
- system, then the monitor set point will be calculated as follows.
_A sample will be taken from the RHR heat exchanger service water outlet along with individual samples of any of the following streams which may be in the process of being discharged:
E 1.
Discharge waste sample tank discharge t
2.
Recovery sample tanks discharge 3.
Reactor building salt water drain tank discharge An isotopic analysis of each sample is perform'ed.
This analysis includes isotopic analysis for gamma
- emitters, alpha
If the analysis for alpha
- emitters, beta
Original i.
2-5 March 1983
,..,.,,..-.,_,_-...m
,_._,-m._,__..-__-.,______,._,._.____..__-_.-_._,__._m
SNPS-1 ODCM time of discharge, then the concentrations done to comply with Technical Specification Table 4.11.1.1.1-1 will be used.
Obtain the circulating water flow rate from the control room.
The set point is calculated as follows:
Set point =
N Hi Hi f
)
_ _D+
R+
H+
S+
C ~
H (cpm)
D Di +
R Ri +
Si +
H Ri s
i=1_
(MPC)f Where:
E=
counting efficiency of RE-023 for radionuclide (i) i All other parameters are as defined in Section 2.1.
2.2 GASEOUS EFFLUENT MONITOR SET POINT (Compliance with Section 3.3.7.12 of the RETS)
The alarm set point for the station ventilation exhau.et monitor is set to the noble gas, total body, dose rate limit specified in Section 3.11.2.1 of the RETS.
Either of two methods may be used to calculate the dose rates based on the measured release rate of each isotope.
The first method is the method used by the computerized radiation monitoring
- system, the second method is an alternate noncomputerized method.
2.2.1 Method 1:
(Computerized Method)
Computerized method is under development.
2.2.2 Method 2: (Noncomputerized Method)
To calculate the set point in epm, the following methodology is established:
1.
A gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, C 1 Original 2-6 March 1983
SNPS-1 ODCM i
2.
At the time of sampling, the count rate, cpm, of the station ventilation exhaust noble gas radiation-monitor O
will be recorded, C.R.
2.2.2.1 Gaseous Effluent Monitor Set Point Based on Noble Gases Total Body Dose Rate 1.
The noble gas total body dose rate is calculated using the following equation:
Total Body Dose Rate:
s t ]R1 = 0.7E-05
- DFB i
- X/Q
- Ci*V (mrem /hr)
D where:
i
= predicted dose rate based on gas sample (mrem /hr),
DR X/Q
= 7.94E-07 sec/m*, historic annual average X/Q at 366 meters NNE due to releases via the station ventilation exhaust point, DFB
= total body dose rate conversion factor 1
(mrem /yr/pCi/m*), from Tablo 2.2-1, C
= sampled isotope release concentration (pCi/cc),
1 V
= 1.70E+08 cc/sec (3.60E+05 cfm), station ventilation 4
exhaust rate, and
.07
= dose reduction factor due to shielding provided by residential structures.
2.
The isotopic release activity concentration is normalized to a total body dose rate of 500 mrem /yr by multiplying by the following normalizing factor:
F
= 500/
DR 3.
From the above, the set point based on total body dose rate can be calculated as.follows:
Set point = F
- C.R.
(cpm) where:
Set point = alarm set point that results in a total body dose rate of 500 mrem /yr, F = normalization factor-(unitless), and C.R. = station ventilation exhaust noble gas radiation monitor count rate (cpm).
Original 2-7 March 1983'
SNPS-1 ODCM The above procedure and format can be used for variable set point calculation.
As an
- example, the expression could be used to calculate a new set point during containment purge by substituting the appropriate purge X/Q (from Table 4-1), purge V (5.70E+05 cc/sec (1200 cfm)), and purge Ci (pCi/cc).
2.2.2.2 Gaseous Effluent Monitor Set Point Based on Noble Gases Skin Dose Rate 1.
The noble gases skin dose rate is calculated using the following equation:
iDRi=
Ksi*
X/Q
- Ci*V (mrem /yr) where:
DR
= predicted dose rate based on gas sample, (mrem /yr),
X/Q = 7.94E-07 sec/m*, historic annual average X/Q at 366 meters NNE due to releases via the station ventilation exahust point, Ksi=
skin dose rate conversion factor (mrem /yr/pCi/m*), from Table 2.2-1, C1=
sampled isotope release concentration (pCi/cc),
V 1.70E+08 cc/sec (3.60E+05), station ventila-
=
tion exhaust rate.
2.
The isotopic release ac tivi ti-concentration is normalized to a
skin dose rate of 3000 mrem /yr by multiplying by the following normalizing factor:
F3 = 3000/
DR I
3.
From the above, the alarm set point, based on skin dose rate, can be calculated as follows:
Set point = F
- C.R.
(cpm) where:
Set point = alarm set point that results in a skin dose rate of 3000 mrem /yr (cpm),
F = normalization factor (unitiess), and C.R. = station ventilation exhaust noble. qas g
radiation monitor count rate (cpm).
W Original 2-8 March 1983
SNPS-1 ODCM
~~()
(,)
The above procedure and format can be used for variable set point calculation.
As an
- example, the expression could be used to calculate a new set point during containment purge by substituting the appropriate purge X/Q, (from Table 4-1),
purge V (5.70E+05 cc/sec (1200 cfm)), and purge C 1 (pCi/cc).
2.2.2.3 Gaseous Effluent Monitor Set Point Based on Organ Dose Rate 1.
Skip Step 2 of Section 2.2.2.
2.
The organ (inhalation thyroid) dose rate is calculated using the following equation:
iDRi = 1.14E-04
- DFAi
- X/Q
- Cf*V*R (mrem /hr) a where:
DR.
= calculated inhalation dose rate 1
to adult thyroid based on gas sample (mrem /hr),
a X/Q
= 7.94E-07 sec/m', historical annual
(\\_
average X/Q at 336 meters NNE due to release via the station ventilation exhaust point, i
= dose factors adult thyroid only DFA (I-131 through I-135), from Table 3.5-1, (mrem /pci),
Ci
= sampled isotope release concentration (pci/cc),
V
= 1.70E+08 cc/sec station venti-lation exhaust rate, and R
= constant, adult breathing rate 8,000 m*/yr.
a 3.
The isotopic release activity concentration is normalized to an organ dose rate of
.17 mrem /hr by multiplying by the following normalizing factor:
F=.17/
- DR o
V original 2 March 1983
SNPS-1 ODCM 4.
From the above, the alarm set point, incremental change during one hour, based on an organ dose
- rate, can be calculated as follows:
One Hour Incremental Set Point = F
- C
- T
- S
- E (cpm)
Where:
One Hour Incremental Set Point = alarm set point that results in an organ dose rate of.17 mrem /hr (or.17 mrem in one hour) (cpm),
F=
normalization factor (unitless),
C=
I-131 concentration in sampled release, (pCi/cc)
T=
Iodine detector efficiency for I-131, (cpm /pCi),
S=
radiation monitor sample flow rate (cc/hr), and E=
charcoal cartridge Iodine filter efficiency.
2. 2.- 3 Main Condenser Offgas System Effluent Monitor Set Point (RE-065) 1.
A gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, Ci.
sampling, the count rate,"hr, of the 2.
At the time of monitor will be recorded, CR.
3.
The isotopic release activity concentration, Ci, is normalized to 1 MPC at the site boundary by multiplying by the following factor:
l 1
i l
F = [i=n C.
I
[
- V * */g 1
l (i=1 (MPC)f)
Where; V = Main condenser offgas system ventilation flow rate (m /sec) 8 7/0 = Site boundary annual average meteorological dispersion f actor ( sec )
3 m
5.
From the above, the alarm set point, based on 1 MPC at the site boundary, is calculated as follows:
Set Point = F * (CR)
(mr/hr)
O Original 2-10 March 1983
SNPS-1 ODCM 2.2.4' Main Condenser Air Eiector Monitor Set Point (RE-012)
. s 1.
A gaseous sample from the monitor will be taken and.
analyzed for noble isotopic composition and concentration, yC /ce. gases i
2.
At the time of sampling, the count rate, rpm, of the monitor will be recorded, CR.
3.-
The ' isotopic. release. activity concentrations, C, are 1
summed-and multiplied by the air ejector flow
- rate, V
CC to obtain the noble gas release rate, g C /sec.
1 sec 4.
The release rate in step 3
is normalized to the
-Technical Specification Section 3.11.2.7 release limit of 244,0000u tc /sec by dividing by 2440000u C /sec.
i 5.
From above, the alagm set point, based on a release rate of 2440000u C /sec can be calculated as follows:
]
1
[Ci
- V
- CR Set Point =
2440000 2.2.5 Main Condenser' Air Eiector Effuluent, Bypass Mode, Set Point (RE-012) 1.
A gaseous sample from the monitor will be taken and i-analyzed for isotopic composition and concentration, C.
1 I
mrem 2.
At the time of sampling, the count rate, hr, of the monitor will be recorded, CR.
i 3.
The isotopic release activity concentration, C1, is normalized to 1 MPC at the site boundary by multiplying by the following factor:
1 L
F = [i=n I
C i
{
, y. $j (i=1 (MPC)g) i Where; V = Main Condenser Air Ejector, bypass mode, Ventilation flow rate (m*/sec)
Y/Q = Site Boundary annual average meterological dispersion factor (8ec) i 3
m ilO l
l Original 2-11 March 1983
,-...--,--.v--
e
-........,,. ~,.... - -
,v..
.,, -. - -.,,. - - - - - -.., - =,,... -..,... -..
._.--.r,r.m-#. -...,
SNPS-1 ODCM 4.
From the above, the alarm set point, based on 1 MPC at the Site Boundary, is calculated as follows:
Set Point = F * (CP)
(mr/hr) 2.2.5.1 Main Condenser Air Eiector Effluent, Bypass Mode Set Point Based on Main Condenser Air Removal Pump Discharge Monitor (RE-051) 1.
A gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, C1 2.
At the time of sampling, the count rate,"h#
f the monitor will be recorded, CR.
3.
The isotopic release activity concentration, c, is i
normalized to 1 MPC at the site boundary by multiplying by the following factor:.
1 F=
fi=n I
C b
i V
+ V'*
/g
,t 2,
(i=1 (MPC)g)
Where; V
= Air removal pump discharge flow rate 3
(m*/sec)
O v
= Air ejector discharge flow rate (m*/sec) 2 Y/O
= Site boundary annual average meteoro-logical dispersion f actor ( sec )
3 m
4.
From the above, the high alarm set point, based on 1 MPC at the site boundary, is calculated as follows:
Set Point =F*
(CR)
(mrem /hr)
O Original 2-12 March 1983
~
~~s
)
i
)
J t
n SNPS-1 DOCM i
TA8LE 2.2-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NO8LE GASES l
Radio-Ks1 "'
nuclide M-A ir "' (DFbi )
0-Sk in "' (DFSi )
Y-A i r "' (DFHi )
7-Body *" (DF8i )
Skin Dose "'
4 Kr-83m
- 2. 88E -04 '"
1.93E-05 7.56E-06 1.5E-05 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 2.4E-03 l
Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E-OS 1.4E-03 i
3 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 1.5E-02 1
l Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 1.4E-02 Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 2.4E-02 s
Kr-90 7.83E-03 7.29E-03 7.63E-02 1.56E-02 2.OE-02
- f4 Xe-131m 1.11E-03 4.76E-04 1.56E-04 9.15E-05 6.OE-04 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04 1.2E-03 l'
i d
l Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 5.8E-04 j
1 j
Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 3.3E-03 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 3.4E-03 I
~
Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 1.3E-02 l
j Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 1.1E-02
-r-Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 9.9E-03 I
i t
"' mrad-m' j
pC1-yr I
"'mree-m' j
pC1-yr
"' 2. 88E -04 = 2.88 x 10-*
,(
)
"'Ks1 = (0.7)(1.11)(DFHj).+ OFSg 1
i i
i
. Original 1 of 1 March 1983
SNPS-1 ODCM 4
3.0 DOSE CALCULATION METHODS l
)
This section presents the calculational specifics required to demonstrate compliance with the following Radiological Effluent Technical Specifications (RETS) sections:
3.11.1.2 - Liquid Effluent Dose Calculation 3.11.1.3 - Operation of Liquid Radwaste Treatment System 3.11.2.1 - Gaseous Effluent Dose Rate 4
3.11.2.2 - Noble Gas Air Dose 3.11.2.3 - Gaseous Effluent Dose From Radioiodines, Radio-active Materials In Particulate Form y.
L 3.11.2.5 - Operation of V.entilatio: Exhaust Treatment System L
Calculation methods are based on the equation and calculational methods described in Regulatory Guide 1.109
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents i
for the Purpose of Evaluating Compliance with
- 10CPR50, Appendix I".
Either of two methods may be used to calculate the dose rates based on the measured release rate of each _ isotope.
The first method is the method used by the computerized radiation monitoring
- system, the second method is an alternate noncomputerized method.
3.1 LIQUID EFFLUENT, DOSE CALCULATION To comply with Section 3.11.1.2 of the RETS, the' liquid effluents released into Long Island Sound (see Fig. 3.1-1) shall be
-limited:
- 1. During any calendar quarter to less than or equal to
'l.15 mrem to the total body and to less than or equal to 5 mrem to any organ.
- 2. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
t 3.1.1 Method 1: (Computerized Method)
Equations A
through C
are to be used to calculate the offsite
-doses due to release of liquid. radwaste.
For this dose calculation the actual concentration to be discharged by isotope, the total volume of liquid to be discharged, and the number of circulating water pumps running, supplied by the operator, shall be used.
Original 3-1 March 1983
SNPS-1 ODCM A.
Ingestion of Fish 75
- U,/O b Og*Bf*Daij Raj = (0.3 %
- exP (-Lg + 24.0) i=1 where:
Raj
= dose to organ (j) of individuals in age group (a) due to the release (mrem),
x
= Integer variable, 1 to 4, number of circulating water pumps running, Ua
= constants, child 6.9, teen 16.0, adult 21.0 kg/yr, Q;
= variable, quantity of each isotope (i) released (curies),
B;
= constants, from Table 3.1-1 for fish, D, g,
= constants, from Tables 3.1-2 through 3.1-4, and L;
= constants, from Table 3.1-5.
B.
Ingestion of Seafood Equation and parameters are identical to Equation A except for the following:
Ua
= constants, child 1.7, teen 3.8, adult 5.0 kg/yr, and
= constants, from Table 3.1-1 for seafood.
B i C.
Shoreline Deposits 80 3 = (0. 506
- U,/K)
R D
- Q
- exp (-L
- 1.0)/L1 i=1
- (1. 0 - exp (-L1
- 1.314E+05))
where:
R.
= dose to organ (j) of individuals in age group (a) 83 due to the release (mrem),
g '.
= variable, quantity of each isotope (i) released (curies),
Original 3-2 March 1983
SNPS-1 ODCM U,
= constants, child 14.0, teen 67.0, adult 12.0 hr/yr, and O
s,/
Dall. = constants, from Table'3.1-6.
All other terms are as defined in Equation A
-3.1.2 Method 2: (Noncomputerized Method)
The dose. contributions for the total release period shall be.
calculated for all radionuclides identified in liquid effluents released into Long Island Sound using the following expression:
N M
)
At
[]
C F
(3.1-11 D
A
=
f y
yy 1
i=1 1=1 where:
Dr
= the: cumulative dose or dose commitment to the total body or an organ from the liquid effluents for the
~
M
. total release period (mrem),
{
1=1 O
a t.
= the. length of the Ith release period over which ci r
p \\_,,/
and Fg are averaged for all liquid released (minutes),
i ci
= the average concentration of radionuclide Cil in i
undiluted liquid effluent during release ' period Al l from any liquid release (gCi/cc),
A;*
= the site-related ingestion dose or dose commitment factor to the total body or any organ for each l
identified principal gamma and beta emitter listed in l
Table 3.1-7~(mrem / min per uCi/cc), and
= the near field average dilution factor for C ti p,
during any liquid effluent release,- defined as the average undiluted -liquid waste flow rate during release divided by the product of the average circulating water = flow rate times.8.85.
(8.85 is the near field mixing factor for the mixing of the diffuser discharge into Long Island Sound.)
1 L
If the calculated doses exceed the limit specified above consult i
RETS'Section 3.11.1.2.
s
!O c
Original 3-3 March 1983
SNPS-1 ODCM 3.2 OPERATION OF LIQUID WASTE TREATMENT SUBSYSTEMS The dose projection analysis will be performed using the methodology described in Section 3.1 with the ex'ception that the calculated doses will be compared with the limits specified in RETS Section 3.11.1.3.
Liquid radwaste subsystems are shown on Fig. 3.2-1.
3.3 DOSE RATE DUE TO GASEOUS EFFLUENTS To comply with Section 3.11.2.1 of RETS, the dose rate at any time in the unrestricted area for noble gas dose and for organ dose due to radioactive materials in gaseous effluents released via the station ventilation exhaust duct shall be limited to the following values:
1.
The dose rate limit for noble gas shall be less than 2 mrem /hr to the total body and less than 12 mrem /hr to the skin, and 2.
the dose rate limit for all radioiodines and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half lives greater than 8 days shall be less than 6 mrem /hr to any organ.
Either of the following two methods may be used to determine the dose rates:
3.3.1 Method 1: (Computerized Method) 3.3.1.1 Noble Gas Total Body and Skin Dose Rate 15 (X/Q)
- 2.22E+04 *]Q DT
=
- DFB s
g i=1 15 (X/0) * [ (2. 4 6E+0 4 * ]{)
O
- DFH )
DS
=
s g
i=1 15
+ (3.17E+04 * }{} Q
- DFSg)]
g where:
i=1 DT and DS
= dose to adult total body and skin in sector (s) s s
at site boundary, due to noble gases during the last 15 minutes (mrem),
9 Original 3-4 March 1983
-SNPS-1 ODCM Qi
= variable, quantity of each isotope, i, (noble gases only), released in the last 15 minutes
)3 (curies),
(X/Q)
= variable, atmospheric dispersion factor for the period of release (site boundary only),
.(sec/m*), and-DFH, and DFS
= constants, from Table 2.2-1.
- DFBg, 3
3.3.1.2 Organ Dose Rate (Particulate Release)
The-organ dose rate will be calculated as described in Section 3.5.1.1.
4 3.3.2 Method 2: (Noncomputerized Method) 3.3.2.1 Noble Gas Total Body Dose Rate
'1.14E-04* X/O *
[DFB.* (C.
- V
- C.
- V
-C.
- V )]*0.70 DT 1
1 11 1
12 2
13 3
=
S i
(}
+ 1.14E-04
- V
- X/Q * ), [DFBy* C1]
- 0.70 2
2 1
1.14E-04* V
- X/0 * )() [DFB
- C 3
3 g
i 3
+
i During periods of no intermittent releases such as no main l
condenser air removal pump operation and no containment drywell l
-purge the above formula reduces to the following:
1.14E-04* V
- X/0
- ][] [DFB
- C1]
- 0.70 3
3 y
DT
=
s i
= 8.00E-05* V
- X/0
- }] [DFB
- Cgl ]
1 i
O Original 3-5 March 1983 l
SNPS-1 ODCM where:
DT total body dose rate from all radionuclides
=
g releases (mrem /hr),
DFB the total body dose rate factor due to gamma
=
i emissions for each identified noble gas radionuclide (mrem /yr per pCi/m*) (Table 2.2-1),
the station ventilation exhaust duct release ein
=
concentration of radionuclide, i, (pCi/cc)
(from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor),
the air removal pump ventilation exhaust duct C i,
=
release concentration of radionuclide, i, (pCi/cc)
(f om the isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor),
the containment drywell purge ventilation exhaust c,3
=
concentration of radionuclide, i, (pCi/cc)
(from the isotopic analyses performed on the gaseous sample taken from the containment drywell filter train exhaust monitor),
1.70E+08 cc/sec (3.60E+05 cfm),
station V2
=
ventilation exhaust duct ventilation exhaust flow
- rate, 5.70E+05 cc/sec (1200 cfm),
air removal pump V
=
exhaust duct ventilation exhaust flow rate, 5.70E+05 cc/sec (1200 cfm), containment drywell V
=
purge ventilation exhaust flow rate, X/Q2 7.94E-07 sec/m*,
historic annual average X/Q at
=
1 366 meters NNE due to release via the station ventilation exhaust point, l
X/Q:
1.89E-06 sec/m*,
historic annual average, short
=
term X/Q at 1931 meters ESE.due to air removal pump release via the station ventilation exhaust
- point, l
X/Q.
1.89E-06 sec/m*,
historic annual average short
=
term X/Q at 1931 meters ESE due to containment drywell purge via the station ventilation exhaust
- point, inverse of 8,760 hr/yr, and 1.14E-04
=
Original 3-6 March 1983 l
SNPS-1 ODCM shielding factor that accounts for dose reduction
.0.70
=
due to shielding from residential structures.-
Substituting' historic values for X/Q's and V's.
L The noble gas total body dose rate (mrem /hr)-is calculated by the following equation:
= 3. 7E-05 * [ [DFB.
- DT (298 C.
- C.
-C
)]
s 1
1 1 12 i3
.1
+ 8.4E-05*
[DFB
- Cf] + 8. 4E-05 *
[DFBf*C
]
f 1
1-Note that during periods of no intermittent releases such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the following:
DT, = 1.1E-02
- { [DFBi ' *C
]
mrem /hr i
3.3.2.2 Noble Gas Skin Dose Rate 1.14E-04* X/O * [ [K DS
- (C.
- V.
- C.
- V
- C.
- V )]
=
i si 11 1
12 2
1 3 3
s' O
1.14E-04
- V
- X/O * [ [K
+
- C1]
2 2
si 2
i
+ 1.14E-0 4
- V
- X/O * [ [K C
]
si g3 i
During periods of no intermittent releases such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the following:
.DS
= 1.14E-04* V
- X/O * [ [K s
.* Ci]
1 1
l si 1
where:
os,
= skin dose from all radionuclides released (mrem /hr),
= the skin dose factor due to beta and gamma emissions K *.
for each identified noble gas radionuclide (mrem /yr per pCi/m*) from Table 2.2-1,
(
Original 3-7 March 1983
SNPS-1 ODCM Cgi
= the station ventilation exhaust duct release concentration of radionuclide, i,
(pCi/cc)
(from isotopic analyses performed on the gaseous sam taken from the station ventilation exhaust monitor)ple C ia
= the air removal pump ventilation exhaust duct release concentration of radionuclide, i, (pCi/cc)
(from the isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor),
C
= the containment drywell purge ventilation exhaust i
concentration of radionuclide, i, (pCi/cc)
(from the isotopic analyses performed on the gaseous sample taken from the containment drywell filter train exhaust monitor),
Vi
= 1.7E+08 cc/sec (3.60E+05 cfm),
station ventilation exhaust duct ventilation exhaust flow rate, V
= 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct ventilation exhaust flow rate, Vi
= 5.70E+05 cc/sec (1200 cfm), containment drywel1 purge ventilation exhaust flow rate, X/Q
= 7.94E-07 sec/m*,
historic annual average X/Q at 366 meters NNE due to release via the station ventilation exhaust point, X/Q
= 1.89E-06 sec/m*,
historic annual average short term X/Q at 1931 meters ESE due to air removal pump release via the station ventilation exhaust point, X/Q
= 1.89E-06 sec/m*,
historic annual average short term X/Q at 1931 meters ESE due to containment drywell purge via the station ventilation exhaust point, and 1.14E-04 = inverse of 8,760 hr/yr.
O Original 3-8 March 1983
SNPS-1 ODCM 3.3.2.3 Organ Dose Rate (particulate releases)
O
-DS
= 1.14E-04* [
[P.. *X/Q * ( C V-C V )]
i i i 12 2
s 1_
13,
i
-C V )] + 1.14E-04* V * ['[P..*X/Q
- Ci2]
1 3 s 2
i 13 2
+ 1/4E-04* V * [
[P..*X/Q
- C
]
i 13 3
13 3
During periods of no intermittent releases such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the following:
D
= 1.14E-04* V * [
P..*X/Q
- Ci s
i i
13 i
t where:
Ds
= total dose rate to organ j (mrem /hr),
Pj
= the inhalation dose rate conversion factor for radio-i nuclides other than noble
- gases, i,
and organ j,
(mrem /yr per uCi/m*) from-Table 3.3-1, C2
= the station ventilation exhaust duct release i
concentration of radionuclide, i, ( Ci/cc)
(from the isotopic analyses performed on the filter paper and charcoal cartridge taken from the station ventilation exhaust monitor),
Cp
= the air removal pump ventilation exhaust duct release concentration of radionuclide, i, (p Ci/cc )
(from the isotopic analyses performed on the iodine and filter cartridge taken from the air removal pump discharge monitor),
C:
= the containment drywell purge ventilation exhaust concentration of radionuclide, i, ( Ci/cc)
(from the isotopic analyses performed on the gaseous sample taken from the containment drywell filter train exhaust monitor),
O V
Original 3-9 March 1983
_,. _ _. _. _ _..... _ ~.. _ _.. _ _ _.. _ _ _ _ _. -. _ _ _ _ _ _ _. _ _ _ _ _ _. _ _ _ _ _
SNPS-1 ODCM V
= 1.70E+08 cc/sec (3.60E+05 cfm), station ventilation exhaust duct ventilation exhaust flow rate, g
V:
= 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct ventilation exhaust flow rate, V
= 5.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation exhaust flow rate, X/Qi = 1.10E-07 sec/m*,
historic annual average X/Q at 1931 meters ESE due to releases via the station ventilation exhaust point, X/Q
= 3.60E-07 sec/m*,
historic annual average short term X/Q at 1931 meters ESE due to condenser air removal pump release via the station ventilation exhaust
- point, X/Q
= 3.60E-07 sec/m*,
his' toric annual average short term X/Q at 1931 meters ESE due to containment drywell purge via the station ventilation exhaust point, D/Q
= 4.80E-09 m-8, historic annual average D/Q deposition factor at 1931 meters ESE due to releases via the station ventilation exhaust point, D/Q: = 1.40E-08 m-8, historic annual average short term D/Q deposition factor at 1931 meters ESE due to condenser 8
air removal pump releases via the station ventilation W
exhaust point, D/Q
= 1.40E-08 m-8, historic annual average short term D/Q deposition factor at 1931 meters ESE due to containment drywell purge via the station ventilation exhaust point, and 1.14E-04 = Inverse of 8,760 hr/yr.
Substituting constant historic values for X/Qs, D/Q's, and V.
l The organ dose rate (mrem /hr) from the particulate releases is l
calculated by the following equation:
l O
Original 3-10 March 1983
SNPS-1 ODCM
= 1.14E-04 * [ _[ (1.10E-07 P
)-
Ds fl]'s i
- (1. 70E+0 8 C.
- 5.70E+05 C.
- 5.70E+05 C1 )]
11 12 3
+ 6.50E+01*
)[(3.60E-07P
- C g
i2 l'
- ]
[(3.60E-07 P..
- C
+ 6.50E+01 13 i 3]
,1 Note that during periods of no intermittent releases such as no main condenser air removal pump operation and no Containment Drywell purge the above formula reduces to the following:
= 1. 90E+0 4 * )[) 1.10E-0 7 P..
i D
- C
-s 13 1 1
,1 3.4 GASEOUS EFFLUENTS, NOBLE GAS AIR DOSE To comply with Section 3.11.2.2 of the RETS, the air dose in unrestricted area location due to releases via the station ventilation exhaust point shall be limited to the following:
1.
During any calendar quarter to less than or equal to 5 mead for gamma radiation and less than or equal to 10 mrad for beta radiation.
2.
During any calendar year to less than or equal to 10 mrad for gamma radiation and less than or equal to i
20 mrad for beta radiation.
l
.Either of the following two methods may be used to determine the dose:
l t
l
- 1. (O
)
Original l
3-11 March 1983 l__
- - - - - - - - - - - - - - - - - - - - - - - ~ ~ - - - - " - ~ ~ - ~ ~ ~ ' " ' - ~
' - ~ ~ ~ ~ ' - ' ~ ~ ~ ~ ~ "
SNPS-1 ODCM 3.4.1 Method 1: (Computerized Method) 3.4.1.1 Noble Gas Gamma and Beta Air Dose 15 E+04 + (X/Q)
- Q
- DFH D
=
G g
g s
i=1 15 D
7E+04 * (X/Q)
- Q
- DFB B
i f
where:
s i=1 D
and D B
= dose in sector (s) at site boundary due to gamma G s S
air and beta air radiation (mrad),
Qi
= variable, quantity of each isotope, i, released in the last hour (curies),
(X/Q)
= variable, atmospheric dispersion factor for the period of release (site boundary only) (sec/m*),
and DFH i and DFBi
= constants, from Table 2.2-1.
3.4.2 Method 2: (Noncomputerized Method) 3.4.2.1 Noble Gas Gamma Air Dose The general equation is:
(
}*(i i2 2 2 D
i3 3 3.
G i
1 l 1 1 s
1
+ 3.17E-08*V *t *X/O *[
M
- C g
i2_.
1
+ 3.17E-08*V *t *X/0 Mi'*
i 3
3_
During periods of no intermittent
- releases, such as no main condenser air removal pumps operation and no containment drywell purge the above formula reduces to the following:
D
= 3.17E-08* V *X/O *t *[
M.
+C.
G i
1 1
_1 1 1_
g 1
Original 3-12 March 1983
SNPS-1 ODCM where:
-(3
(
/-
n
= the total gamma air dose.from the releases (mrad),
Gs 3.17E-08
= the inverse of number of seconds in a year, M
= the air dose factor;due to gamma emissions for each i
idH tified noble gas radionuclide (mrad /yr per gCi/m*) from Table 3.4-1, t
= release period (seconds),
Ca
= the-station ventilation exhaust duct release i
concentration of radionuclide, i, (gCi/cc)
(from the isotopic analyses performed on the gaseous sam taken from the station ventilation exhaust monitor)ple C
= the air removal pump ventilation exhaust duct release i
concentration of radionuclide, i, (gCi/cc)
(from the isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor),
Cp
= the containment drywell purge ventilation exhaust concentration of radionuclide, i, (pCi/cc)
(from the isotopic analyses performed on the gaseous sample taken from the containment drywell filter train
\\
exhaust monitor),
v2
= 1.70E+08 cc/sec (3.60E+05 cfm), station ventilation exhaust duct ventilation exhaust flow rate, V:
= 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct ventilation exhaust flow rate, V
=.S.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation exhaust flow rate, X/Q2 = 8.44E-07 sec/m*,
historic annual average X/Q at 457
. meters ESE due to release via the station ventilation exhaust point, X/Q: = 1.83E-06 sec/m*,
historic annual average, short term X/Q at 457 meters ESE due to condenser air ESE due to condenser air removal pump release via the station ventilation exhaust point, and X/Q
= 1.83-06 sec/m*,
historic annual average, short. term X/Q at 457 meters ESE due to containment drywell purge release via the station ventilation exhaust release point.
O Original 3-13 March 1983
-,----.--,n..
,,,,,.n..,..,.,,. -, -,.
,_,_-,-,--,n.
SNPS-1 ODCM Substituting historic values for X/Q's and V.
O The noble gas gamma air dose is calculated by the following equation:
1.60E-08*)[]
(M ) * (298 C.
t
-C.
t
-C.
t )
D
=
i 11 1 12 2 13 3-Gs
.1
+3.30E-08*)
- )]
M *C D
+ 3.30E-08 M *C
- t i
i2 2
i f3 3
i 1
Note that during periods of no intermittent releases such as no main condenser air removal pump, operation and no containment drywell purge the above formula reduces to the following:
- ))
D
= 4.50E-06 t M *C g
i f
f g
1 3.4.2.2 Noble Gas Beta Air Dose The general equation is:
D
(
Bs 1
i (i
t i 1
-C Yt
- C Vt )
i2 2 2 1 3 3 3 _.
+ 3.17E-08
- X/Q *V *t
- )()
N.
+ C.
2 2
2 1
1 i
2,
+ 3.17E-08
- X/Q *V *t
- )[
N.
- C.
3 3
3 1
13.
1 J
During periods of no intermittent
- releases, such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the following:
3.17E-08
- X/Q *V *t * )[
D
=
N.
- C.
B*
1 I
I 1
l l Original i
3-14 March 1983
SNPS-l'ODCM r/
.where:
D
= beta air dose from all radionuclides released BS (mrem /yr),
Ng
= the air dose-factor due to beta emissions for each
- identified noble ~
radionuclide (mrad /yr per gas pCi/m*) from Table 3.4-1, 3.17E-08 = the inverse of number-of seconds in a year, t.
= release period (seconds),
Ca := the station ventilation exhaust duct release i
concentration of radionuclide, i, (gCi/cc)
(from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor),
Cg.
= the air removal pump ventilation exhaust duct release concentration of radionuclide, i, (gCi/cc)
(from the isotopic analyses performed on the gaseous sample j
taken from the air removal pump discharge monitor),
.C s
= the containment drywell purge ventilation exhaust i
concentration of radionuclide, i, (gCi/cc)
(from the
,m isotopic' analysis performed on the gaseous sample taken from the containment drywell filter train exhaust monitor),
v2
= 1.70E+08 cc/sec (3.60E+05 cfm), station ventilation exhaust duct ventilation exhaust flow rate, V
= 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct ventilation exhaust flow rate, V*
= 5.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation exhaust flow rate, X/Q
= 8.44E-07 sec/m*,
historic annual average X/Q at 457 meters ESE due to release via the station ventilation exhaust point, X/Q: = 1.83E-06 sec/m*,
historic annual average short term X/Q at 457 meters ESE due to condenser air removal pump release via the station ventilation exhaust point, and Original 3-15 March 1983 i
..... - -......... - -.... - -.. -........ _.,. - _... ~,--..._ _,. _,.
.,_.m..-,_-.,.,,-,,....m,,,
SNPS-1 ODCM X/Q. = 1.83E-06 sec/m*,
historic annual average short term X/Q at 457 meters ESE due to containment.drywell purge release via the station ventilation exhaust point.
The noble gas beta air dose is calculated by the following equation:
Substituting historic values for X/Q's and V's the general equation reduces to:
1.60E-08*)
(N ) * (298 C.
t
- C.
t
-Ci t )
D
=
f 11 1 12 2 3
3.
Bs 1
3.30E-08*t*)[
+ 3. 3 0E-0 8
- t * )]
N *C N *C
+
3 g
g3 2
i 1
i i
Note that during periods of no intermittent releases such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the following:
- [
N.*C, D
= 3.30E-08
- t Bs 1
1 11
~
~
i 3.5 GASEOUS EFFLUENT, DOSE DUE TO RADIOIODINES AND RADIOACTIVE MATERIALS IN PARTICULATE FORM AND RADIONUCLIDES (other than Noble Gases) with Half-Lives Greater than 8 days To comply with Section 3.11.2.3 of the Radiological Effluent Technical Specifications, the organ dose to maximum individual in unrestricted area due to radioiodines and particulates releases l
via the station ventilation exhaust point shall be limited to the following:
1.
During any calendar quarter to less than or equal to 7.5 mrem to any organ, and 2.
During any calendar year to less than or equal to 15 mrem to any organ.
Either of the following two methods may be used to determine the dose:
3.5.1 Method 1: (Computerized Method) 3.5.1.1 Organ Doses A.
Inhalation Dose 80
- )
Q.
- DFA 3asL (X/0)L *R D.
= 3.17E+04
- 1 i
a Original "I
3-16 March 1983
SNPS-1 ODCM where:
~-
~b)
/
D;,,i
= dose to an organ (j) of a person in age group (a) in. sector (s) at location (L) during the last hour (mrem),
R
= constants, child 3,700, teen 8,000, adult 8,000, a
infant 1,400 m*/yr, Q i
= variable, quantity of isotope (i) released in the last hour-(curies),
(X/Q)g -= variables, atmospheric dispersion factors at location (L) for the period of release (sec/m*), and
'DFA
= constants, from Tables 3.5-1 through 3.5-4.
g B.
Dose Due to Standing on C'ontaminated Ground 80 jsL (D/Q)L * )
DFG13
- Og /Li D
= 7.00E+11
- i=1
- (1. 0 - exp) (-L1
- 1.31E+05))
N-I where:
Djst
= dose to organ (j) of individuals in all age groups in~ sector (s) at location (L) due to the release (mrem),
(D/Q)t
= variables, relative deposition factors at location (L) for the period of release (m-*),
DFGj
= constants, from Table 3.1-6, i
Qg
= variable, quantity of each isotope (i) released in the last hour (curies), and Lg
= constants, from Table 3.1-5.
O Original 3-17 March 1983 m.
_.,. ~,, _..
__y
,.,,.__,,,.,,y,..,,,.,..w.,,.m_,wy_,c.-..-,,,,
,,,.,,_,_-,y.,,,.y,,y..,_._,_,.%
,n.,,.._y_,.my.
,e.,,,,_r m.,,
.m,
SNPS-1 ODCM C.
Dose Due to Eating Vegetation For All Isotopes Except H-3 and C-14 7S r,
1.00 *C
- U
- (D/Q)
- L DFI..
- Q.
D
=
jas a
13 1
i=)
+ (Bg,/2.40.0*L )]
- exP (-Li
- 24.0)
- [(R/2.0*Eg) p For C-14 D.
= 2.2E+07
- U
- (X/Q) *Q
- DFI..
Jas a
ig 13 For H-3 D
1.2E+07
- DFI jas f
- U, * (X/Q)
- Q /H where:
= dose to organ (j) of an individual in a D.,,
in sector (s) due to the release (mrem)ge group (a) 3 C
= constants, 5.50E+07 for iodines, 1.10E+08 for other
- isotopes, U,
= constants, child 26.0, teen 42.0, adult 64.0 kg/yr (from Table 3.5-5),
(D/Q)
= variable, relative deposition factor at the nearest garden for the period of release (m-2),
DFI j
= constants, from Tables 3.1-2 through 3.1-4, i
Qi
= variable, quantity of each isotope (i) released in the last hour (curies),
R
= constants, 1.0 for iodines, 0.2 for other isotopes, E i
=L
+ 0.0021, Bii
= constants, from Table 3.5-6, Li
= constants, from Table 3.1-5, (X/Q)
= variable, atmospheric dispersion factor at the nearest garden for the period of release (sec/m*),
Original 3-18 March 1983
SNPS-1 ODCM Qs.
= variable, quantity of C-14 released in the last hour p
(curies),
Q,.
= variable, quantity of H-3 released in the last hour (curies), and H-
= constants, from Table 3.5-7.
D.
Dose Due to Drinking Milk For All Isotopes Except C-14 and H-3 78 D
Of
- U, * (D/Q)
- C*
Fmi *
(!*
jas i}
i=1 (B / 240.0*Lf)P
- DFIija i
+
- Q
- exp (-Lg
- 48.0) g For C-14 jas = 2.20E+07
- DFIg3, a
14 g
- U
- Q
- (X/Q)
- Of
- F D
- exp (-Lg
- 48.00)
O For H-3 Djas = 1.20E+07
- U,
- O t * (X/Q)
- Of
- F 3,
- exp (-Lg
- 48.0)/H where:
D
= dose to organ (j) of an individual'in age group (a) g, in sector (s) at the nearest cow (mrem),
U.
= constants, child 330, teen 400, adult 310, infant 330 litres /yr, F;
= constants, from Table 3.5-6, m
Of
= constants, 50 kg/ day for cattle, (X/Q)
= variable, atmospheric dispersion factor at the nearest cow for the period of release (sec/m'), and O
Original 3-19 March 1983
SNPS-1 ODCM (D/Q)
= variable, relative dispersion factor at the nearest cow for the period of release (m-2).
All other terms are as defined in Equation B.
3.5.2 Method 2: (Backup Method) 3.5.2.1 Organ Doses:
3.17E-08*)()
(P..*X/Q +P
..
- D/Q ) * (C.
- V *t D.
=
J 1J 1
01]
1 11 1
1 i
~
- C.
- V *t
- C.
- C *t
)
12 2
2 1 3 3
3
- ),
(P.g3
- X/O
+ 3.17E-08
- t gi3*D/O )
- C
+P i2_
1
- ]s (P..
- X/Q
+P
..*D/O )
- C.
+ 3.17E-08
- t 3
IJ 3
01]
3 13 1
(3.5.1-1)
During periods of no intermittent
- releases, such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the following:
- )(]
(P..*X/Q
+P
.. *D/Q )
- C.
3.17E-08
- t D.
=
3 1
1]
01]
1 11 1
where:
D
= total dose to organ j (mrem /yr),
j the inhalation dose conversion factor for P;j
=
radionuclides, i, (other than noble gases), and organ j, (mrem /yr per uCi/m) from Table 3.5-8, the dose conversion factor for radionuclides, other P
- =
o,3 than noble gases, i,
and organ j,
for the leafy vegetables, stored vegetables, and contaminated ground pathways in m*
(mrem /yr per uCi/sec) respectively, from Table 3.5-9 the dose factors Pj, Poij are i
based on the critical individual organ for the child group, since this group is most restrictive),
9 Original 3-20 March 1983
SNPS-1 ODCM release period (seconds),
t'
=
()
the station ventilation exhaust duct release C;
=
concentration of radionuclide, i, ( u Ci/cc) (from the
- isotopic analyses performed on the iodine and filter cartridge taken'from the station ventilation exhaust monitor),
the air removal pump ventilation exhaust duct release C
=
i concentration of radionuclide, i, (
Ci/cc) (from the isotopic. analyses performed on the iodine and filter cartridge taken-from the air removal pump discharge monitor),
the containment drywell purge ventilation exhaust C_i
=
concentration.of radionuclide, i, (p Ci/cc) (from the isotopic analyses performed on the gaseous sample a
taken from the-containment drywell filter train exhaust monitor),
1.70E+08 cc/sec (3.60E+05 cfm), station ventilation v2
=
exhaust duct ventilation exhaust flow rate, 5.70E+05 cc/sec (1200 cfm), air. removal pump exhaust V:
=
duct ventilation exhaust flow rate, 5.70E+05 cc/sec (1200 cfm), containment drywell purge V
=
ventilation exhaust flow rate, X/Q 1.10E-07 sec/m*,
historic annual average X/Q at 1931
=
meters ESE due to releases via the station ventilation exhaust point, X/Q:
3.60E-07 sec/m*,
historic annual average short term
=
X/Q at 1931 meters ESE due to condenser air removal pump release via the station ventilation exhaust
- point,.
X/Q
= 3.60E-07 sec/m*,
historic annual average short term X/Q at 1931 meters ESE due to containment drywell purge'via the station ventilation exhaust point, D/Q2 4.80E-09 m-8,.
historic annual average D/Q deposition
=
factor at 1931 meters ESE due to releases via the station ventilation exhaust point, D/Q 1.40E-08 m-8, historic annual average short term D/Q
=
deposition factor at 1931 meters ESE due to condenser air removal pump releases via the station ventilation exhaust point, 4
L Original 3-21 March 1983
-+-e or.--+wrvs.->--s---
w.v--ee-sr,-ww.e-..
e we..-=.,,,,..-rewe=w-y-=
e--w,_w.-+e. wm,e,.
s,
,-,.-m
-e-wmov=,,---c.,.yw,,v.-.--,.,,-w,--wwtg
.ere,ww-,,
- y er
SNPS-1 ODCM D/Q
= 1.40E-08 m-8, historic annual average short term D/Q deposition factor at 1931 meters ESE due to containment drywell purge exhaust via the station ventilation exhaust point.
The organ dose from the particulate releases is calculated by the following equation:
Substituting constant historic values for X/Q's, D/Q's, and V's, the general equation reduces to:
D. = 3.17E-08 *b (1.10E-07 P..
+ 4.80E-09 P 13)
J 1]
i L
- (1.70E+08 C T - 5.70E+05 C T - 5.70E+05 C T 3) 11 3
g g
13
+ 3.17E-08 *
(3.60E-07 P..
+ 1.40E=08 P01])
- C.
- T i
1J 12 2
))
(3.60E-07 P.. + 1.40E-08 PU13)
+ 3.17E-08
- i-13
- C.
- T 13 3
(3.5.1-2) h Note that during periods of no intermittent releases such as no main condenser air removal pump operation and no containment drywell purge the above formula reduces to the following:
D
= 3.17E-08* t (18.7 Pg3 +.82 Pgg )
- C 3
f NOTE:
If the land use census (Table 3.5-10) changes, the critical
- location, i.e., the location where an indiv.idual would be exposed to the highest dose, must be reevaluated using Equation 3.5.1-1 for each of the following locations:
1.
nearest residence, 2.
nearest vegetable garden, and 3.
nearest milk cow or goat.
At each location, the following pathways must be considered and dose (dose rates) reevaluated if any actual pathway exists:
1.
inhalation, Original 3-22 March 1983
SNPS-1 ODCM
{)-
2.
leafy vegetables (fresh),
3.
stored vegetables, s_
4.
goat's or cow's milk (if both exist choose the one resulting in a higher dose), and 5.
deposition on ground.
Since a
person will always be present, pathways 1 and 5 must always be evaluated.
Once the location of the critical individual is determined and found to be other than the one at 1931 meters ESE, the values of X/Q and D/Q in Equation 3.5.1-2 become invalid.
Values for X/Q and D/Q at the updated critical location must be used.
3.6 OPERATION OF VENTILATION EKHAUST TREATMENT SYSTEM The Ventilation-Exhaust Treatment System (Fig. 3.6-1) shall be used to reduce radioactive materials in gaseous waste prior to their discharge as specified in RETS Section 3.11.2.5.
The dose analysis will be performed as described in Sections 3.5.1 or 3.5.2.
If the calculated doses exceed the limits specified above consult RETS Section 3.11.2.5.
O O
Original 3-23 March 1983
SNPS-1 ODCM
)
TABLE 3.1-1 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA (pci/kg per pCi/ liter)(2)
Saltwater Element Fish Invertebrate H
9.0E-01 9.3E-01 C
1.8E+03 1.4E+03 Na 6.7E-02 1.9E-01 P
2.9E+04 3.0E+04 Cr 4.0E+02 2.0E+03 Mn 5.5E+02 4.0E+02 Fe 3.0E+03 2.0E+04 Co 1.0E+02 1.0E+03 Ni 1.0E+02 2.5E+02 Cu 6.7E+02 1.7E+03 Zn 2.0E+03 5.0E+04 Br 1.5E-02 3.1E+00 Rb 8.3E+00 1.7E+01 Sr 2.0E+00 2.0E+01 Y
2.5E+01 1.0E+03 Zr 2.0E+02 8.0E+01
\\,
Nb 3.0E+04 1.0E+02 Mo 1.0E+01 1.0E+01 Tc 1.0E+01 5.0E+01 Ru 3.0E+00 1.0E+03 Rh 1.0E+01 2.0E+03 Te(*)
1.0E+01 1.0E+02 I
1.0E+01 5.0E+01 Cs 4.0E+01 2.5E+01 Ba 1.0E+01 1.0E+02 La 2.5E+01 1.0E+03 Ce 1.0E+01 6.0E+02 Pr 2,5E+0]
1.0E+03 Nd 2.5E+0 1.0E+03 W
3.0E+0.
3.0E+01 Np 1.0E+01 1.0E+01 (2) Values in ?able 3.1-1 are taken from Reference 6 of Regulatory Guide 1.109, Rev. 1, Oct. 1977 unless otherwise indicated.
(*) Data taken from Reference 8 of Regulatory Guide 1.109, Rev. 1, Oct. 1977.
O Original 1 of 1 March 1983
-~
fy f,
Iq.
)
y)
( j*~
(/ i a
N SNPS-1-DDCM TA8tE 3.1-2 INGESTIDN DDSE FACTDRS FDR ADULTS (mrom per pC1 ingested)
Radio-nuc11de Bone Liver T. Sody Thyroid Kidnev
' Lung GI-LLI 4
a 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 5.681-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1."oE-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 1.4GE-07 No Data
'3.67E-06 i
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
.>k) Data No Data 2.85E-06 3.40E-05' Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-60 No Data
-2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 4
1 N1-63 1.3OE-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88E-06 N1-65 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-OS 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 Date No Data 5.21E-08 No Data No Data No Data 4.09E-13 l
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-OG No DNta No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 i
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 Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 3
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 1
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 7
Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04 i
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 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05
}
Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 i
Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 No Data 2.91E-07 No Data' 6.04E-05
)
Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 i
l
]
Drtgtnal J
1 of 2 March 1983 1
I L
SNPS-1 DDCM TABLE 3.1-2 (CDNT'D)
Radio-nuclide Bone Liver T.
Body Thyroid Kidney Lung GI-LLI Te-129m 1.15E-05 4.29E-08 1.82E-OG 3.95E-06 4.80E-05 No Data 5.79E-05 Te-129 3.14 E 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-OG 8.57E-OG No Data 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 Te-132 2.52E-OG 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 I-130 7.56E-07 2.23E 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 I-131 4.16E-OG 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-OS 8.65E-07 No Data 1.02E-07 I-133 1.42E-OG 2.47E-OG 7.53E-07 3.63E-04 4.31E-OG No Data 2.22E-06 I-134 1.OGE-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-OG No Data 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06 Cs-136 G.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-OG Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 No Data G.4GE-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.OOE-26 La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 No Data No Data No Data 4.25E-07 Ce-141 9.3GE-09 G.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E.07 No Data 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 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 Np-239 1.19E-09 1.17E-10 6.45E-11 No Data 3.65E-10 No Data 2.40E-OS Drtgtnal 2 of 2 March 1983 O
O O
[
(
[\\
J
,Y SNPS-1 DOCM TABLE 3.1-3 INGESTION DDSE FACTORS FOR TEENAGER (mrem per pC1 ingested)
Radio-nucIlde Bone Liver T.
Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.OGE-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-OG 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 2.3OE-06 2.30E-06 2.30E-OG 2.30E-06 2.3OE-06 i
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.OOE-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.OOE-07 No Data 1.04E-05 Fe-55 3.78E-06 2.08E-06 6.25E-07 No Data No Data 1.70E-06 1.16E-06 Fe-59 5.87E-OG 1.37E-OS 5.29E-06 No Data No Data 4.32E-06 3.24E-05 Co-58 No Data 9.72E-07 2.24E-06 No Data No Data No Data 1.34E-05 Co-60 No Data 2.81E-06 6.33E-06 No Data No Data No Data 3.66E-05 N1-63 1.77E-04 1.25E-05 E.OOE-06 No Data No Data No Data 1.99E-06 N1-65 7.49E-07 9.57E-08 4.36E-08 No Data No Data No Data 5.19E-06 Cu-64 No Data 1.15E-07 5.41E-08 No Data 2.71E-07 No Data 8.92E-06 Zn-65 5.76E-06 2.OOE-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 No 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 8.92E-08 4.54E-08 No Data No Data No Data 7.30E-15 Rb-89 No Data 5.50E-09 3.89E-08 No Data No Data No Data.
8.43E-17 Sr-89 4.40E-04 No Data 1.26E-05 No Data No Data No Data 5.24E-05 Sr-90 8.30E-03 No Data 2.09E-03 No Data No Data No Data 2.33E-04 Sr-91 8.07E-OG 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 i
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 No 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 i
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 1.01E-08 No Data 3.OOE-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 No Data 7.11E-10 No Data 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 No Data 4.42E-09 No Data 1.95E-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 Tc-101 3.60E-10 5.12E-10 5.03E-09 No Data 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 No Data 1.09E-07 No Data 8.99E-07 No Data 2.13E-05 Ru-105 2.18E-08 No Data 8.46E-09 No Data 2.75E-07 No Data 1.76E-05 3
Ru-106 3.92E-06 No Data 4.94E-07 No Data 7.56E-OG No Data 1.88E-04 Ag-110m 2.05E-07 1.94E-07 1.18E-07 No Data 3.70E-07 No Data 5.45E-05 Te-125m 3.83E-OG 1.38E-OG 5.12E-07 1.07E-06 No Data No Data 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 No Data 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 No Data 1.22E-05 i
Driginal 1 of 2 March 1983 i
SNPS-1 ODCM TABLE 3.1-3 (CONT'D)
Radio-nuclide Bone Liver T.
Body Thyroid Kidney Lung GI-LLI Te-129m 1.63E-05 6.05E-OG 2.58E-OG 5.2GE-OG G.82E-OS No Data G.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 No Data 2.45E-07 Te-131m 2.44E-06 1.17E-OG 9.76E-07 1.75E-OG 1.22E-05 No Data 9.39E-05 Te-131 2.79E-08 1.15E-08 5.72E-09 2.15E-08 1.22E-07 No Data 2.29E-09 Te-132 3.49E-06 2.21E-OG 2.08E-06 2.33E-OG 2.12E-05 No Data 7.OOE-05 1-130 1.03E-OG 2.98E-06 1.19E-OG 2.43E-04 4.59E-06 No Data 2.29E-OG I-131 5.85E-06 8.19E-OG 4.40E-06 2.39E-03 1.41E-05 No Data 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-OG No Data 3.18E-07 I-133 2.01E-06 3.4tE-06 1.04E-06 4.76E-04 5.98E-06 No Data 2.58E-OG I-134 1.4GE-07 3.87E-07 1.33E-07 6.45E-06 6.10E-07 No Data 5.10E-09 I-135 6.10E-07 1.57E-OG 5.82E-07 1.01E-04 2.48E-OG No Data 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 No Data 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-09 2.27E-05 No Data 1.84E-05 2.90E-OG 2.72E-OG Cs-137 1.12E-04 1.49E-04 5.19E-05 No Data 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 No Data 1.10E-07 1.28E-08 6.76E-11 Ba-139 1.39E-07 9.78E-11 4.05E-09 No Data 9.22E-11 6.74E-11 1.24E-OG Ba-140 2.84E-05 3.48E-08 1.88E-OG No Data 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.OtE-11 2.24E-09 No Data 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.54E-09 No Data 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 No Data No Data No Oata 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 No Data No Data No Data 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 No Data 4.18E-98 No Data 2.54E-05 Ce-143 2.35E-09 1.71E-OG 1.91E-10 No Data 7.67E-10 No Data 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 No Data 1.72E-07 No Data 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 No Data 3.04E'09 No Date 4.31E-05 Pr-144 4'.30E-11 1.76E-11 2.13E-12 No Data 1.01E-11 No Data 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.ttE-tO No Data 5.99E-09 No Data 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 No Data No Data No Data 3.22E-05 Np-239 1.76E-09 1.665-10 9.22E-11 No Data 5.21E-10 No Data 2.67E-05 Original 2 of 2 March 1983 O
O O
s
[
[
N N
SNPS-1 ODCM i
1 TABLE 3.1-4 4
INGESTION'DDSE FACTDRS FDR CHILD j
(arem per pC1 Ingested)
Radio-nuclide Bone Liver T. Body Thyroid 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 i
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 No Data 2.28E-05 Cr-51 No Data No Data 8.90E-09 4.84E-09
.1.35E-09 9.02E-09 4.72E-07 4
Mn-54 No Data 1.07E-05 2.85E-06 No Data 3.OOE-06 No Data 8,98E-06 i
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 1.35E-OS No Data No Data 7.74E-06 2.78E-05 i
Co-58 No Data 1.80E-06 5.51E-06 No Data No Data No Dats 1.05E-05 l
Co-60 No Data 5.29E-06 1.56E-05 No Data No Data No Data 2.93E-05 N1-63 5.38E-04 2.88E-05 1.83E-OS No Data No Data No Data 1.94E-06 i
N1-65 2.22E-06 2.09E-07 1.22E-07 No Data No Data No Data 2.56E-05 Cu-64 No 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 i
Zn-69 4.38E-08 6.33E-08 5.85E-09 No Data 3.84E-08 No Data 3.99E-06 Br-83 No Data No Data 1.71E-07 No Data No Data No Data LT E-24 Br-84 No Data No Data 1.93E-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-OS No Data No Data No Data 5.11E-05 Sr-90 1.70E-02 No 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 5.3OE-05 d
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 1.37E-11 No Data No Data No Data 7.48E-07 Y-91 6.02E-07 No Data 1.61E-08 No Data No Data No Data 8.02E-05 i
Y-92 3.60E-09 No Data 1.03E-10 No Data No Data No Data 1.04E-04 4
Y-93 1.14E-08 No Data 3.13E-10 No Data No Data No Data 1.70E-04 1
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 2.25E-08 8.76E-09 6.26E-09 No Data 8.23E-09 No Data 1.62E-05 Mo-99 No Data 1.33E-05 3.29E-06 No Data 2.84E-05 No Data 1.10E-05 i
Tc-99m 9.23E-10 1.81E-09 3.OOE-08 No Data 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 No Data 1.91E-08 5.92E-10 3.56E-09 I
Ru-103 7.31E-07 No Data 2.81E-07 No Data 1.84E-06 No Data 1.89E-05 Ru-105 6.45E-08 No Data 2.34E-08 No Data 5.67E-07 No Data 4.21E-05 i
Ru-106 1.17E-05 No Data 1.46E-06 No Data 1.58E-05 No Data 1.82E-04 Ag-110m 5 39E-07 3.64E-07 2.91E-07 No Data S.78E-07 No Data 4.33E-05 l
Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 No Data No Data-1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 No Data 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 No Data 1.84E-05 i
' Original 1 of 2 March 1983 i
SNPS-1 DDCM TABLE 3.1-4 (CONT'D)
Radio-nuclide Bone Liver T.
Body Thyroid Kidney Luno GI-LLI Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 No Data 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 No Data 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 No Data 1.OtE-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 No Data 4.36E-07 Te-132 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.OOE-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 Cs-134 2.34E-04 3.84E-04 8.10E-05 No Data 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-OS 6.46E-05 4.18E-05 No Data 3.44E-OS 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 No Data 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 No Data 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.2OE-08 No Data 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 No Data 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.OOE-07 1.12E-10 6.51E-09 No Data 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 No Data 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.10E-09 No Data No Data No Data 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 No Data No Data No Data 3.31E-05 Ce-141 3.97E-08 f.98E-08 2.04E-09 No Data 8.68E-08 No Data 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 No Data 1.59E-09 No Data 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 No Data 3.61ErO7 No Data 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 No Data 6.39E-09 No Data 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 No Data 2.11E-11 No Data 8.59E-08 Nd-147 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 Np-239 5.25E-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Data 2.79E-05 Dr-f g i nal 2 of 2 March 1983 O
O O
1 a,
s--
-m
^
- f N
I.
e o
j SNPS-1 ODCM-TABLE 3.1-5 DECAY CONSTANTS (1/Hr) 1.
Radio-~
Radio-nuclide Constant nuclide Constant H-3
.6.408E-06 Ru-103 7.300E-04 C-14 1.379E-08 Ru-105 1.600E-01 Na-24 4.600E-02 Ru-106 7.800E-05
.P-32 2.000E-03 Ag-110m 1.100E-04 Cr-51 1.044E Te-125m 5.000E-04 Mn-54 9.252E-05 Te-127m 2.600E-04 Mn-56 2.700E-01 Te-127 7.400E-02 Fe-55 2.930E-05 Te-129m 8.600E-04 Fe-59 6.480E-04 Te-129 5.900E-01 Co-58 4.068E-04 Te-131m 2.300E-02 Co-60 1.501E-05 Te-131 1.700E+00 Ni-63 8.600E-07 Te-132 8.900E-03 Ni-65 2.700E-01 I-130 5.600E-02 Cu-64 5.400E-02 I-131 3.593E-03 Zn-65 1.184E-04 I-132 3.000E-01 Zn-69 7.296E-01 I-133 3.334E-02 Br-83 2.900E-01 I-134 7.900E-01 Br-84 1.300E+00 I-135 1.100E-01 i
Br-85 1.449E+01 Cs-134 3.852E-05 Rb-86 1.500E-03 Cs-136 2.203E-03 Rb-88 2.400E+00 Cs-137 2.635E-06 l
Rb-89 2.700E+00 Cs-138 1.300E+00 Sr-89 5.724E-04 Ba-139 5.000E-01 Sr-90 2.776E-06 Ba-140 2.257E-03 Sr-91 7.300E-02 Ba-141 2.300E+00 Sr-92 2.600E-01 Ba-142 3.900E+00
- Y-90 1.100E-02 La-140 1.700E-02 l
Y-91m 8.300E-01 La-142 4.500E-01 Y-91 4.900E-04 Ce-141 8.892E-04 Y-92 2.00E-01 Ce-143 2.100E-02 Y-93 6.800E-02 Ce-144 1.019E-04 i
Zr-95 4.392E-04 Pr-143 2.100E-03 Zr-97 4.100E-02 Pr-144 2.400E+00 Nb-95 8.200E-04 Nd-147 2.600E-03 Mo-99 1.000E-02 W-187 2.900E-02 Tc-99m 1.200E-01 Np-239 1.200E-02 Tc-101 2.900E+00 i
- o Original 1 of 1 March 1983
SNPS-1 ODCM
-TABLE 3.1-6
,()
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /hr per pCi/m*)
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 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58
.7,00E-09 8.20E-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-ll 9.30E-ll Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 f
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 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-ll 2.70E-ll 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 Ag-110m 1.80E-08 2.10E-08 Te-125m 3.50E-ll 4.80E-ll Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-ll 1.10E-ll Te-129m 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 O
\\m /
Original 1 of 2 March 1983 l
SNPS-1 ODCM i
TABLE 3.1-6 (CONT'D)
Element Total Body Skin Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-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 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 t
I l
l l
O Original 2 of 2 March 1983 l
[N
. - (g k
.s SNPS-1 DOCM
{
TABLE 3.1-7 OOSE RATE CONVERSION FACTORS *'. A FOR (FISH ANO INVERTEBRATE) INGESTION PATHWAY (mrem / min per pC1/cc) t Isotope Bone Liver T.
Body Thyroid kidney Lung GI-LLI H-3 5.9E-03 5.9E-03 5.9E-03 5.9E-03 5.9E-03 5.9E-03 4
C-14 I
Na-24 3.3E-03 3.3E-03 3.3E-03 3.3E-03 3.3E-03 3.3E-03 3.3E-03 P-32 2.6E+05 1.6E+04 1.OE+04 3.OE+04 Cr-51 8.9E-02 5.3E-02 2.OE-02 1.2E-01.
2.2E+01 Mn-54 1.2E+02 2.2E+01 3.4E+01 3.6E+02 Mn-56 4.6E-03 8.3E-04 5.6E-03 1.4E-01 l
Fe-55 1.9E+03 8.6E+03 2.2E+03 9.9E+03 3.3E+03 Fe-59 1.3E+03 3.1E+03 1.2E+03 8.6E+02 1.OE+04 Co-58 9.8E+00 2.2E+01 2.OE+02 Co-60 2.8E+01 6.2E+01 5.3E+02 NS-63 8.3E+02 5.8E+01 2.7E+01 1.2E+01 N1-65 4.8E-03 6.3E-04 2.8E-04 1.6E-02 Cu-64 9.6E-01 4.5E-01 2.4E+00 8.2E+01
]
Zn-65 2.6E+03 8.3E+03 3.8E+03 5.6E+03 5.2E+03 i
Zn-69m 2.8E+01 6.7E+01 6.2E-OO 4.1E+01 4.1E+03 Br-83 1.2E-06 1.7E-06 Br-84 2.8E-17 2.1E-22 I
Br-85 Rb-86 Rb-88 Rb-89 5.3E-31 3.8E-31 Sr-89 8.2E+01 2.3E+00 1.3E+01 i
Sr-90 2.OE+03 4.9E+02 2.7E+01 Sr-91 2.6E-01 1.2E-02 1.3E+00 Sr-92 1.2E-03 5.3E-05 2.4E-02 Y-90 Y-91m d
Y-91 1.5E+00 3.8E-02 7.9E+02 Y-92 7.9E-05 2.3E-06 1.4E+00 Y-93 5.4E-03 1.5E-04 1.7E+02 Zr-95 2.6E-01 8.3E-02 5.6E-02 1.3E-01 2.6E+02 Zr-97 5.4E-03 1.1E-03 4.9E-04 1.GE-03 3.3E+02 Nb-95 7.2E+00 4.OE+00 1.6E+00 3.9E+00 2.4E+04
+
Mo-99 1.6E+00 3.2E+01 3.7E+00 3.7E+00 Tc-99m 1.4E-05 3.8E-05 4.8E-04 5.7E-04 1.9E-05 2.2E-02 I
Tc-101 6.3E-35 9.OE-35 9.OE-34 1.6E-33 4.6E-35 Ru-103 1.7E+00 7.3E-01 6.6E+00 2.OE+02 l
Ru-105 3.5E-03 1.4E-03 4.4E-02 2.1E+00 1
Ru-106 2.6E+01 3.3E+00 5.OE+01 1.7E+03 Ag-110m 2.5E+01 2.4E+01 1.4E+01 4.5E+01 9.8E+03 j
Te-129m 1.5E+01 5.5E+00 2.4E+00 5.2E+00 6.2E+01 7.5E+01 1
Te-131m 1.3E+00 6.4E-01 5.3E-01 1.OE+00 6.4E+00 6.3E+01 Te-132 2.7E+01 1.8E+00 1.6E+00 1.9E+00 1.7E+01 8.3E+01 Original 1 of 2 March 1983 i
SNPS-1 DDCM TABLE 3.1-7 (CONT'D) t Isotope Bone Liver T.
Dody Thyroid Kidney Luno GI-LLI I-131 3.3E+00 4.7E+00 2.7E+00 1.5E+03 8.OE+00 1.2E+00 I-132 1.2E-04 3.3E-04 1.1E-04 4.3E-02 5.1E-04 6.1E-05 I-133 5.5E-01 9.6E-01 2.9E-01 1.8E+02 1.7E+00 8.5E-01 I-134 5.OE-10 1.4E-09 4.9E-10 1.8E-07 2.2E-09 1.2E-12 I-135 3.1E-02 8.2E-02 2.9E-02 1.1E+01 1.3E-01 8.9E-02 Cs-134 1.1E+02 2.7E+02 2.1E+02 8.6E+01 2.8E+01 4.6E+00 Cs-136 1.1E+01 4.4E+01 3.2E+01 2.4E+01 3.3E+00 5.OE+00 Cs-137 1.5E+02 1.9E+02 1.3E+02 G.7E+01 2.2E+01 3.8E+00 Cs-138 3.5E-15 7.OE-15 3.5E-15 5.2E-15 5.2E-16 3.OE-20 Ba-139 8.1E-07 5.7E-10 2.4E-08 5.4E-10 3.3E-10 1.5E-06 Ba-140 2.5E+01 3.2E-02 1.7E+00 1.1E-02 1.8E-02 5.3E+01 Ba-141 1.OE-28 4.6E-27 9.7E-29 5.8E-29 6.4E-35 Ba-142 8.OE-43 8.2E-46 5.1E-44 7.OE-46 4.6E-46 La-142 2.6E-08 1.2E-08 3.OE-09 8.9E-05 Ce-141 5.5E-02 3.7E-02 4.2E-03 1.7E-02 1.4E+02 Ce-143 5.9E-03 4.4E+00 4.9E-04 2.OE-03 1.6E+02 Ce-144 2.9E+00 1.2E+00 1.6E-01 7.2E-01 9.7E+02 Pr-143 8.8E-02 3.6E-02 4.5E-03 2.1E-02 3.9E+02 Nd-147 6.1E-02 7.OE-02 4.2E-03 4.1E-02 3.4E+02 W-187 7.5E-02 6.3E-02 2.1E-02 2.OE+01 Np-239 4.4E-04 6.3E-02 2.1E-02 2.OE+01
See Section 4.0 Original 2 of 2 March 1983 O
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SNPS-1 ODCM
()
TABLE 3.4-1 NOBLE GAS DOSE FACTORS Gamma Air Beta Air Dose Factor Dose Factor Mi Ni Isotope (mrad /yr per uCi/m*)
(mrad /yr per uCi/m )
8 Kr - 83m 1.9E+01 2.9E+02 Kr - 85m 1.2E+03 2.0E+03 Kr - 85 1.7E+01 2.0E+03 Kr - 87 6.2E+03 1.0E+04 Kr - 88 1.5E+04 2.9E+03 4
Kr - 89 1.7E+04 1.1E+04 Kr - 90 1.6E+04 7.8E+03 Xe - 131m 1.6E+02 1.lE+03 Xe - 133m 3.3E+02 1.5E+03 l
Xe - 133 3.5E+02 1.1E+03 Xe - 135m 3.4E+03 7.4E+02 Xe - 135 1.9E+03 2.5E+03 Xe - 137 1.5E+03 1.3E+02 Xe - 138 9.2E+03 4.8E+03 Ar - 41 9.3E+03 3.3E+03 O
Original 1 of 1 March 1983
-,-- ~--
-+. -
~
1.,
%,,/
n SNPS-1 ODCM a
s TABLE 3.5-1 f
INHALATION DOSE FACTORS FOR ADULTS l
(mrem per pC1 inhaled)
Radio-l nuclide Bone Liver T.
Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 i
Na-24 1.28E-06 1.28E-OC 1.28E-06 1.28E-06 1.28E-06 1.20E-06 1.28E-06 l
P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data No Data 1.08E-05 I
Cr-51 No Data No Data 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 j
Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 f
pn-56 No Data 1.55E-10 2.29E-11 No Data 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.98E-07 No Data No Data 9.01E-06 7.54E-07 l
Fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 i
Co-58 No Data 1,98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 j
Co-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 N1-63 5.40E-05 3.03E-06 1.81E-06 No Data No Data 2.23E-05 1.67E-06 NI-65 1.92E-10 2.62E-11 1.14E-11 No Data No Data 7.OOE-07 1.54E-06 i
Cu-64 No Data 1.83E-10 7.69E-11 No Data 5.78E-10 8.48E-07 6.12E-06
)
Zn-65 4.05E-06 1.2PF-OS 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06 l
2n-69 4.23E-12 8.14t-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 4
Br-83 No Data No Data 3.01E-08 No Data No Data No Data 2.90E-08 l
Br-84 No Data No Data 3.91E-08 No Data No Data No Data 2.OSE-13 1
Br-85 No Data No Data 1.60E-09
.No Data No Data No Data LT E-24 j
Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06 I
Rb-88 No Data 4.84E-08 2.41E-08 No Data No Data No Data 4.18E-19 l
Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.16E-21 l'
Sr-90 1.24E-02 No Data 7.62E-04 No Data No Data 1.20E '9.02E-05 Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75E-04 4.37E-05 Sr-91 7.74E-09 No Data 3.13E-10 No Data No Data 4.56E-06 2.39E-05 Sr-92 8.43E-10 No Data 3.64E-11 No Data No Data 2.06E-06 5.38E-06 Y-90 2.61E-07 No Data 7.01E-09 No Data No Data 2.12E-05 6.32E-05 Y-91m 3.26E-11 No Data 1.27E-12 No Data No Data 2.40E-07 1.66E-10 Y-91 5.78E-05 No Data 1.55E-06 No Data No Data 2.13E-04 4.81E-C5 4
Y-92 1.29E-09 No Data 3.77E-11 No Data No Data 1.96E-06 9.19E-06 l
Y-93 1.18E-05 No Data
'3.26E-10 No Data No Data 6.06E-06 5.27E-05 i
j Zr-95 1.34E-05 4.30E-06 2.91E-06 No Data 6.77E-06 2.21E-04 1.88E-05
}
Zr-97 1.21E-08 2.45E-09 1.13E-09 No Data 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 No cata 9.67E-07 6.31E-05 1.3OE-05 Mo-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 i
Tc-99m 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21 I
Ru-103 1.91E-07 No Data 8.23E-08 No Data 7.29E-07 6.31E-05 1.38E-05
{
Ru-105 9.88E-11 No Data 3.89E-11 No Data 1.27E-10 1.37E-06 6.02E-06 e
Ru-106 8.64E-06
.No Data 1.09E-06 No Data 1.67E-05 1.17E-03 1.14E-04 Ag-110m 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1 20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07
.7.17E-06 Original 1
1 of 2 March 1983 l
SNPS-1 ODCJ TABLE 3.5-1 (CONT'D)
Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.*5E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m B.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 ~
6.60E-07 1.42E-04 2.61E-06 No Data 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 I-133 1.08E-06 1.85E-OG 5.65E-07 2.69E-04 3.23E-06 No Data 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.5GE-07 Cs-134 4.66E-05 1.OGE-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.3OE-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.4GE-C4 Cs-137 5.98E-05 7.76E-05 5.35E-OS No Data 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-05 7.76E-08 4.05E-08 No Data 6.OOE-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 La-140 4.3OE-08 2.17E-08 5.73E-09 No Data No Data 1 70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 No Data No Data 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 No Data 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 No Data 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.3OE-05 No Data 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 No Data 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.5GE-08 No Data 4.45E-07 2.76E-C5 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 No Data No Data 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 No Data 8.75E-09 4.70E-06 1.49E-05 Driginal 2 of 2 March 1983 O
O O
'Wl 8
SNPS-1 ODCM TA8LE 3.5-2 INHALATIDN DOSE FACTORS FOR TEENAGER (mrem per pC1 inhaled)
Radio-nuclide Bone Liver T. Body Thyroid Kidney (ung GI-LLI H-3 No Data 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1
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 No Data No Data 1.69E-08 9.37E-09 3.84E-09 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-OG
'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 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91E-04 2.23E-05 j
Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.68E-04 1.19E-05 Co-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 N1-65 2.73E-10 3.66E-11 1.59E-11 No Data No Data 1.17E-06 4.59E-06 4'
Cu-64 No Data 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.68E-06 2n-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 2n-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 No Data No Data 5.41E-08 No Data No Data No Data LT E-24 Br-85 No Data No Data 2.29E-09 No 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 7.59E-06 3.24E-05 Sr-92 1.19E-09 No Data 5.08E-11 No Data No Data 3.43E-06 1.49E-05 Y-90 3.73E-07 No Data 1.OOE-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.OOE-07 3.77E-09 i
Y-91 8.26E-05 No Data 2.21E-06 No Data No Data 3.67E-04 5.11E-05
)
Y-92 1.84E-09 No Data 5.36E-11 No Data No Data 3.35E-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 2r-97 1.72E-08 3.40E-09 1.57E-09 No Data 5.15E-09 1.62E-05 7.88E-05 i
Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21E-05 Mo-99 No Data 2.11E-08 4.08E-09 No Data 5.14E-08 1.92E-05 3.36E-05 l
Tc-99m 1.73E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-15 Ru-103 2.63E-07 No Data 1.12E-07 No Data 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 No Data 5.42E-11 No Data 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 No Data 1.55E-06 No Data 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41E-05 Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.39E-06 1
Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 l
Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-OG 1.01E-05 Original
}
1 of 2 March 1983 I
SNPS-1 ODCM TABLE 3.5-2 (CONT'D)
Radio-nucitde Bone Liver T. Body Thyroid Kidney Lung GI-LLI Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-OS Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-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-OG 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 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-OS 1.71E-05 No Data 1.38E-05 2.22E-OG 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 No Data 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 No Data 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 No Data No Data 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 No Data 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-OS 2.70E-09 No Data 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 No Data 1.51E-D4 1.67E-03 1.OBE-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 No Data 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 No Data 1.26E-12 2.19E-07 2.94E-14 Nd-147 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 Np-239 4.23E-08 3.99E-09 2.21E-09 No Data 1.25E-08 8.11E-06 1.65E-05 Original 2 of 2 March 1983 e
O O
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rx
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)
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t
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%/
s SNPS-1 DDCM TABLE 3.5-3 INHALATIDN DDSE FACTDRS FDR CHILD (mrem per pC1 inhaled)
Radio-nucIlde Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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-OG 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 i
P-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 Cr-51 No Data No Data 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71E-06 4.26E-04 6.19E-06 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.OOE-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 No Data No Data 3,43E-04 1.91E-05 Co-58 No Data 4.79E-07 8.55E-07 No Data No Data 2.99E-04 9.29E-06 A
Co-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91E-03 2.60E-05 i
N1-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data 7.43E-05 1.71E-06 N1-65 8.08E-10 7.99E-11 4.44E-11 No Data No Data 2.21E-OG 2.27E-05 l
Cu-64 No Data 5.39E-10 2.90E-10 No Data 1.63E-09 2.59E-06 9.92E-06 j
2n-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41E-06 1
2n-67 1.81E-11 2.61E-11 2.41E-12 No Data 1.58E-11 3.84E-07 2.75E-06 i
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 tio Data No Data LT E-24 4
Rb-86 No Data 5.36E-05 3.09E-OS 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 7.83E-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-OS Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-OS Sr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05 Y-90 1.11E-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 f-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 2r-95 5.13E-05 1.13E-05 1.OOE-05 No Data 1.61E-05 6.03E-04 1.65E-05 2r-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-OG 1.77E-06 No Data 2.33E-06 1.66E-04 1.OOE-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 I
Tc-101 2.19E-14 2.30E-14 2.91E-13 No Data 3.92F-13 1.58E-07 4.41E-09 4
Ru-103 7.55E-07 No Data 2.90E-07 No Data 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 No Data 1.50E-10 No Data 3.63E-10 4.30E-06 2.69E-05 i
Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.16E-04 j
Ag-110m 4.56E-06 3.08E-OG 2.47E-06 No Data 5.74E-06 1.48E-03 2.71E-05 Te-125m 1.82E-OG 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-OS Te-129m 5.19E-OG 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-OS Original i
1 of 2 March 1983
SNPS-1 DDCM TA!LE 3.5-3 (CDNT'D)
Radio-nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-tt 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-tt 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-OG 2.28E-06 4.99E-04 6.61E-06 No Data 1.38E-06 I-131 1.30E-05 1.30E-05 7.37F-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.GSE-07 I-133 4.48E-06 5.49E-06 2.OSE-OG 1.04E-03 9.13E-06 No Data 1.48E-OG I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2.58E-07 I-135 1.33E-06 2.36E-OG 1.12E-06 2.14E-04 3.62E-06 No Data 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 No Data 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 No Data 2.58E-05 3.93E-06 1.13E-OG Cs-137 2.45E-04 2.23E-04 3.47E-05 No Data 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66F-13 1.45E-tt No Data 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.OOE-05 1.75E-08 1.17E-06 No Data 5.71E-OC 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E-C8 Ba-142 1.35E-11 9.73E-15 7.54E-13 No Data 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.OBE-08 2.04E-08 No Data No Data 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 No Data No Data 2.35E-06 2.05E-05 Ce-149 1.06E-05 5.28E-06 7.83E-07 No Data 2.3tE-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.2GE-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 No Data 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.11EdO7 1.* 17 E -04 2.63E-05 Pr-144 1.61E-it 4.99E-12
- 8. TOE-13 No Data 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.3OE-OG 8.87E-05 2.22F-05 W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Data 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-O?
6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 Drtgtnal 2 of 2 March 1983 O
O O
O p
s SNPS-1 DOCM i
TABLE 3.5-4 1
i INHALATIDN DOSE FACTORS FOR INFANT (mrem per pC1. inhaled) i 5
Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LL1-a l
H-3 No Data 4.62E-07
.4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 I
C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 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 4.11E-08 9.45E-09 9.17E-06 2.55E-07
]
Mn-54 No Data 1.81E-OS 3.56E-06 No Data 3.56E-06 7.14E-04 5.04E-06 i
Mn-56 No Data 1.10E-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-OS i
Fe-55 1.41E-OS 8.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 Co-58 No Data 8.71E-07 1.3OE-06 40 Data No Data 5.55E-04 7.95E-06 Co-60 No Data 5.73E-06 8.41E-06 No Data No Data 3.22E-03 2.28E-05 N1-63 2.42E-04 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06 i
N1-65 1.71E-09 2.03E-10 8.79E-11 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 No Data 2.32E-05 4.62E 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 No Data 2.87E-11 1.05E-06 9.44E-06 Br-83 No Data No Data 2.72E-07 No Data No Data No Data LT E-24 Br-84 No Data No Data 2.86E-07 No Data No Data No Data LT E-24 Br-85 No Data No Data 1.46E-08 No Deta 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 j
Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07 1
Rb-89 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.67E-08 Sr-89 2.84E-04 No 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 9.36E-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 No Data No Data 1.70E-05 1.OOE-04 Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-01 7.43E-05 j
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 No Data 1.12E-05 No Data No Data 1 75E-03 5.02E-05 Y-92 1.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 l
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-OS 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.OOE-04 i
Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06 Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05 l
Tc-99m 9.98E-13 2.06E-12 2.66E-11 No Data 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5,80E-13 No Data 6.99E-13 4.17E-07 6.03E-07 j
Ru-103 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 No Data 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 i
Ru-106 6.20E-05 No Data 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04 i
Ag-110m 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 l
Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No Data 3.19E-04 9.22E-OG l
Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 4
Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 i
Driginal 1 of 2 March 1983 j
SNPS-1 00CJ TA!LE 3.5-4.(CONT'D)
Radio-nuclide Bone Liver T. Body Thyroid Kidney Luna GI-LLI Te-129m 1.01E-OS 4.35E-06 1.59E-06 3.91E-OG 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 1-130 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-OG I-133 9.46E-06 1.37E-05 4.OOE-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 5.43E-06 1.98E-06 4 97E-04 6.05E-OG No Data 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-OS No Data 1.3GE-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 No Data 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.2GE-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 No Data 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.OOE-OS 4 OOE-08 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 No Data 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 No Data 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 No Data No Data 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-OS 1.42E-06 No Data 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 No Data 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.2GE-04 No Data 3.84ErO4 7.03E-03 1.06E-01 Pr-143 1.OOE-05 3.74E-06 4.99E-07 No Data 1.41E-OG 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 No Data 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 No Data 2.25E-06 2.30E-04 2.23E-05 W-187 9.2GE-09 6.44E-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 No Data 4.73E-08 4.25E-OS 1.78E-05 Original 2 of 2 March 1983 0
O O
SNPS-1 ODCM TABLE 3.5-5 O'V RECOMMENDED VALUES FOR Uap TO BE USED FOR THE MAXIMUM EXPOSED INDIVIDUAL IN LIEU OF SITE-SPECIFIC DATA Pathway Infant Child Teen Adult Fruits, vege-tables & grain (kg/yr)(2)
(*)
520 630 520 Leafy vege-tables (kg/yr)(2) 26 42 64 Milk (//yr)(2) 330 330 400 310 Meat & poultry (kg/yr)(2) 41 65 110 Fish (fresh or salt)
(kg/yr)(*)
6.9 16 21 Other seafood (kg/yr)(*)
1.7 3.8 5
[)
Dr'nking water
(//yr)(
\\'
- )
330 510 510 730 Shoreline re-creation (hr/yr)(*)
14 67 12 Inhalation (m*/yr) 1400(*)
3700(*)
8000(*)
8000(*)
i l
(2) Consumption rate obtained from Reference 19 for average individual and age prorated and maximized using tech-niques contained in Reference 10 of Regulatory Guide 1.109, Rev 1, Oct. 1977.
- ) Consists of the following (on a mass basis): 22% fruit,
(
54% vegetables (including leafy vegetables), and 24% grain.
I
(*) Consumption rate for adult obtained by averaging data from l
References 10 and 21-24 of Regulatory Guide 1.109, Rev. 1, i
Oct. 1977 and age prorated using techniques contained in Reference 10.
l Original l
1 of 2 March 1983 l
L
'SNPS-1 ODCM TABLE 3.5-5 (CONT'D)
( *2 Data obtained directly from Reference 10 of Regulatory Guide 1.109, Rev. 1, Oct 1977.
(*) Data obtained directly from Reference 20 of Regulatory Guide 1.109, Rev. 1, Oct. 1977.
(*) Inhalation rate derived from data provided in Reference 20 of Regulatory Guide 1.109, Rev. 1, Oct. 1977.
O l
O Original 2 of 2 March 1983
SNPS-1 ODCM O
Q)
TABLE 3.5-6 STABLE ELEMENT TRANSFER DATA (2)
B F
(Cow)
F Element Veq/ Soil Milk (d/1)
Meat (d/kg)
H(*)
4.8E+00 1.0E-02 1.2E-02 C(*)
5.5E+00 1.2E-02 3.1E-02 Na 5.2E-02 4.0E-02(*)
3.0E-02 P
1.lE+00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.0E-02 Co 9.4E-03 1.0E-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1.2E-01 1.4E-02 8.0E-03 Zn 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02 3.1E-02 Sr 1.7E-02 8.0E-04(*)
6.0E-04 Y
2.6E-03 1.0E-05 4.6E-03 2r 1.7E-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo 1.2E-01 7.5E-03 8.0E-03
('
Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E-01 1.0E-02 1.5E-03 Ag 1.5E-01 5.0E-02 1.7E-02 Te 1.3E-00 1.0E-03 7.7E-02 I
2.0E-02 6.0E-03(*)
2.9E-03 Cs 1.0E-02 1.2E-02(*)
4.0E-03 Ba 5.0E-03 4.0E-04(8) 3.2E-03 La 2.5E-03 5.0E-06 2.0E-04 Ce 2.5E-03 1.0E-04(*)
1.2E-03 Pr 2.5E-03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E-06 3.3E-03 W
1.8E-02 5.0E-04 1.3E-03 Np 2.5E-03 5.0E-06 2.0E-04(*)
(2) Data presented in this table is from Reference 1 of Regulatory Guide 1.109, Rev. 1, Oct. 1977
'22 Meat and milk coefficients are based on specific activity considerations.
- 'From Reference 15 of Regulatory Guide 1.109, Rev. 1, Oct. 1977.
See text (Regulat:ry Gu.de 1.109, Rev. ;, Oct. 19'7).
')Frc Reference 13 of Regulatory Guide 1.109, Rev.
1, Oct. 1977
/
Original 1 of 1 March 1983
.~.
~
4 l
SNPS-1 ODCM TABLE 3.5-7 HUMIDITY PARAMETERS AT RECEPTORS Monthly Average Absolute Humidity (om/m*)
January 3.06 February 3.09 March 3.83 April 5.71 May 8.19 June 12.62 July 15.53 August 14.62 September 11.68 October 8.11 November 5.37 December 3.73 O
Original 1 of 1 March 1983
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SNPS-1 ODCM TABLE 5.5-10 DISTANCE FROM REACTOR CENTERLINE BY SECTOR OUT TO 8,046 m (Meters)
Nearest Nearest Nearest Sector Residence Vecetable Garden Site Boundary 436
.N NNE 381 365 NE 518 332 ENE 884 1,932 311 E
1,128 3,867 346 ESE 914 1,932 457 SE 1,097 2,091 1,105 SSE 914 1,771 876 i
S 610 1,771 610
()
SSW 518 7,080 457 SW 549 4,073 533 WSW 1,585 2,252 457 W
1,570 2,252 360 l
WNW 610 354 NW 419 NNW 436 NOTE:
There are no milk cows, milk goats, or meat animals within the 8,046 m radius of the site.
The nearest milk cow and milk goat are located 8,690 m east of the site.
OV Original i
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w so w w w w w w w w w w w w w w w w w wa m m N
O
- e N
e e ao e -
oE v O w e 6
b N
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4 M M M
M-N 80 6
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b N
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O e O e v O O O O O O O O O O
O O b
L e
+ + + + +
e t
+ + + + + + + + +
2 e
w w w w w w w w w w w w w w N.
n.
w J
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w N.
6 N.
co. e.
b.
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m e m o m b
en e O ao O e e O
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+
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+ + + + + + + + + + + +
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N.
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3 SNPS-1 OOCM 1
1 TABLE 3.5-15 Polj INFANT INGESTION OF GOAT'S MILK OOSE CONVERSION FACTORS m'(mrem /yr/,pC1/sec) l Isotope Bone Liver T. Body Thyroid Kidney Lung
.GI-LLI Cr-51 1.6E+03 9.1E+02 3.4E+02 2.OE+03 3.8E+05 Mn-54 5.OE+05 9.5E+04 1.5E+05 1.5E+06 i
l Fe-59 1.7E+05 4.1E+05 1.6E+05 1.1E+05 1.4E+06 Co-58 1.3E+06 3.2E+06 3.4E+06 1
l Co-60 5.1E+06 1.2E+07 1.3E+07 I
Zn-65 9.7E+07 3.OE+08 1.4E+08 2.OE+08 1.9E+08 1
Sr-89 1.3E+10 3.6E+08 2.4E+08 Sr-90 1.8E+11 4.7E+10 1.7E+09 Zr-95 3.5E+02 9.OE+01 6.4E+01 2.7E+01 4.1E+04 4
Sb-124 1.4E+06 2.6E+05 5.6E+05 3.4E+03 1.1E+06 4.OE+07 I-131 6.7E+08 8.OE+10 4.8E+08 2.6E+11 2.OE+08 3.1E+07 j
I-133 9.7E+06 1.4E+07 4.3E+O6 3.4E+09 3.4E+06 2.6E+06 j
Cs-134 6.2E+10 1.1E+11 9.6E+09 6.7E+09 1.3E+10 2.7E+05 Cs-136 3.7E+08 1.4E+O9 1.OE+09 7.7E+08 1.1E+08 1.6E+08 1
Cs-137 9.8E+10 1.1E+11 6.2E+09 5.6E+09 1.3E+10 2.9E+08 i
Ba-140 1.2E+07 1.3E+04 6.5E+05 6.3E+02 7.7E+03 3.2E+05 i
Ce-141 1.3E+04 8.OE+03 9.4E+02 4.9E+02
'3.8E+06
[
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LIQUID EFFLUENTS x
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/
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w.
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FLOOR DRAIN FLOOR DRAIN COLLECTOR TANK FILTER I f WASTE I
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=
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TO DIFFUSER REGENERANT EVA POR ATOR FIGURE 3.2-1 LIQUID RADWASTE TREATMENT SYSTEM ORIGINAL-MARCH 1983
I O
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VENTILATION EXHAUST l
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6 CHEM. LABORATORY FILTER i
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BUILDING VENTILATION H EPA 40,000 CFM F ILTE R R AD WA STE
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CHARCOAL VENT 2270 CFM R ADWA STE AND TANK HEPA 4'
l VENT FILTE R S 1
l OFFGAS i
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VENTIL ATION EXHAUST TRE ATMENT SYSTEM 3
ORIGINAL-MARCH 1983 1
i
SNPS-1 ODCM 4.0 RECEPTOR LOCATIONS, METEOROLOGY AND HYDROLOGY The purpose of this section is to identify those receptor locations which represent critical pathway locations and to specify the dilution, dispersion, and deposition factors at these locations to be used in Calculation Method 2
when computerized radiation monitoring system is inoperable.
For liquid effluent pathways a dilution factor of 8.85 is used based on a calculation.
For gaseous effluent
- pathways, Table 4-1 lists the critical locations for receptors and their respective dispersion and deposition factors.
The atmospheric dispersion and deposition factors were calculated based on onsite meteorological data for the 2 year period October 1, 1973 - September 30, 1975.
Regulatory Guide 1.109 methodology and parameters, except as noted above, were used in the noncomputerized method dose rate conversion factors.
O i
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original i
4-1 March 1983
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SNPS-1 DOCM i
7 TABLE 4-1 CRITICAL RECEPTOR LOCATIDNS FOR GASEOUS EFFLUENT CALCULATIONS-Technical Spectftcation 3.11.2.1 3.11.2.2 3.11.2.3 3.11.2.5 Section Sections in this Manual 3.3 3.4 3.5 3.6 I
Limiting Criteria Instantaneous Dose Quarterly and Annual Quarterly and Dose to any organ Rate to Whole Body Air Doses due to Annual Dose due due to radionucitdes and Skin due to Gamma and Beta to radionuc11 des other than Noble Gas a
{
Noble Gas and Dose radiation other than Noble for 31 day period to any organ due Gas.
To radionucifdes j
other than Noble i
Gas Distance and Direction
- 1) Noble Gas:
457 meters. ESE 1931 meters. ESE 1931 meters. ESE i
of Receptor from the 366 meters. NNE 4
Plant
- 2) Organ:
1931 meters. ESE Description of Location Location of highest Location of highest Location of highest Location of highest j
Dose Rate Dose Dose Dose Long Term Atmospheric
- 1) 7.94E-07 sec/m' 8.44E-07 sec/m'
- 1. TOE-07 sec/m' 1.10E-07 sec/m' Dispersion Factor for
- 2) 1.10E-07 sec/m' Station Ventilation Exhaust X/Qi
{
Short Term Atmospheric
- 1) 1.89E-06 sec/m' 1.83E-06 sec/m' 3.60E-07 sec/m' 3.60E-07 sec/m' Dispersion Factor for
- 2) 3.60E-07 sec/m' Air Removal Pump X/Qs Short Term Atmospheric
- 1) 1.89E-06 sec/m' 1.83E-06 sec/m' 3.60E-07 sec/m' 3.60E-07 sec/m' Disperston Factor for
- 2) 3.60E-07 sec/m' Containment Drywell Purge X/Qs Long Term Relative
- 1) NA NA 4.80E-09 m-'
4.80E-09m-'
Deposition Factor for
- 2) 4.80E-09 m-'
Station Venttiation i
Exhaust D/Q I
Short Term Relative
- 1) NA NA 1.40E-08 m-'
1.40E-08 m-'
j Deposition Factor for
- 2) 1.40E-08 m-'
Air Removal Pump D/Q i
Short Term Relative
- 1) NA NA 1.40E-08 m-'
1.40E-08 m-'
Deposition Factor for
- 2) 1.40E-08 m-'
j Containment Drywell Purge D/Qs Original 1 of 1 March 1983
]
l
r SNPS-1 ODCM 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS The purpose of this section is to identify those sampling locations from which the radiological environmental monitoring samples shall be collected pursuant to Technical Specification 3/4.12.
Sampling locations for on site and off site locations are shown on Figures 5-1 and 5-2 respectively.
The number and frequency for sampling at these locations is given in Technical Specification Table 3.12-1.
O O
Original 5-1 March 1983
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5 10 MONITORING PROGR AM i
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SC A LI-MlLES ORIGINAL-MARCH 19ts3 O
O O
.