ML20083F114
| ML20083F114 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/31/1983 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20083F110 | List: |
| References | |
| PROC-831231, NUDOCS 8312300152 | |
| Download: ML20083F114 (138) | |
Text
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4 LONG ISLAND LIGHTING COMPANY OFFSITE DOSE CALCULATION MANUAL O REVISION 3-DECEMBER 1983
- DR ADO O 2
- A. .PDR a
l SNPS-1 ODCM FLEASE NOTE Revision 1 -- August 1983 of the LILCO, SNPS-1, Offsite Dose Calculation Manual has been totally revised from the Original - March 1983 Submittal -
Therefore, Revision 1 - August 1983 has no change bars.
CHANGE BARS have been used in subsequent revisions I to locate a change (additions, deletions, and/or modifi-cations) in engineering, design, methodology, etc.
CHANGE BARS are not used for Errata (i.e., typos, format changes).
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DO NOT REMOVE - KEEP IN YOUR ODCM O BN1-11600.02-92 i Revision 3 - December 1983
SNPS-1 ODCM o
TABLE OF CONTENTS Radiological Effluent Technical Specification Section Subject 'Section Page 1 INTRODUCTION 1-1 2 . SET POINTS 2.1-1 2.1 LIOUID EFFLUENT MONITOR SET POINTS 3.11.1.1 2.1-1 l 2.1.1 Radiation Effluent Monitor (RE-13) High/ Trip Alarm Set Point for Dishcarge Waste Sample Tanks, Recovery Sample Tanks, or Yard Piping Drain Sump 2.1-4
-2.1.2 Radiation Effluent Monitor (RE-79) High Alarm Set Point for Reactor Building Salt Water Drain' Tank 2.1-6 2.1.3 Residual Heat Removal Heat Exchanger Service Water Outlet Monitors (RE-23A,RE-23B)
High Alarm Set. Points 2.1-7 2.2 CASEOUS EFFLUENT MONITOR SET POINTS 3.11.2.1 2.2-1 2.2.1 Gaseous Effluent Monitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) 2.2-2 2.2.1.1 Gaseous Effluent Monitor High Alarm Set Point 'for Station Ventilation Exhaust Monitor. (RE-42) Based on Noble Cases Total ,
Body Dose Rate 2.2-2 2.2.1.2 Gaseous Effluent Monitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Gases Skin Dose Rate 2.2-3 2.2.2 Main Condenser Offgas System Effluent Monitors (RE-65A,B) High Alarm Set Point 2.2-4
-2.2.3 Main Condenser Air Ejector Monitors (RE-12A,B)
High Alarm Set Point for Non-bypass Mode Operation 2.2-5 2.2.3.1 Initial Set Point for RE-12A,B Non-bypass Mode Operation 2.2-6 l 2.2.3.2 Subsequent Adjustments of Set Points for RE-12A,B in Non-bypass Mode Operation 2.2-7 l 1
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-BN1-11600.02-92 111 Revision 3 - December 1983
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TABLE OF CONTENTS (CONT'D)
Radiological Effluent Technical-Specification Section Subject Section Page 2.2.4_ Main Condenser Air Ejector Nbnitors (RE-12A,B)
High Alarm Set Point for Bypass Mode Operation 2.2-7 2.2.4.1 Initial Set Point for RE-12A,B in Bypass Mode Operation 2.2-7 2.2.4.2 Subsequent Adjustments of Set Points for RE-12A,B in Bypass Mode Operation 2.2-8 3 DOSE CALCULATION METHODS 3.0-1 3.1 LIOUID EFFLUENT, DOSE CALCULATION 3.11.1.2 3.1-1 3.1.1 Method 1: (Computerized Method) 3.1-1 3.1.2 Method 2: (Backup Method) 3.1-5 3.2 OPERATION OF LIQUID WASTE TREATMENT SUBSYSTEMS 3.11.1.3 3.2-1
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(l,_ -3.3 DOSE RATE DCE TO GASEOUS EFFLUENTS 3.3-1 3.3.1 Method 1: (Computerized Method) 3.3-1 3.3.1.1 Release Rate Estimation 3.11.2.1 3.3-1 3.3.1.2 Total Body Dose Rate 3.11.2.1 3.3-2 3.3.1.3 Skin Dose Rate 3.11.2.1 3.3-3 3.3.1.4 Organ Dose Rate (I-131, I-133, Tritium and Particulate Releases) 3.11.2.1 3.3-4 3.3.2 Method 2: (Backup Method) 3.3-5 3.3.2.1 Noble Gas Total Body Dose Rate 3.11.2.1 3.3-5 3.3.2.2 Noble Gas Skin Dose Rate 3.11.2.1 3.3-6 3.3.2.3 Organ Dose Rate (Particulate Releases) 3.11.2.1 3.3-7 3.4 GASE0US EFFLUENTS NOBLE GAS AIR DOSE 3.11.2.2 3.4-1 3.4.1 Mechod 1: (Computerized Method) 3.4-1 3.4.1.1 Release Estimation 3.11.2.2 3.4-1
-3.4.1.2 Noble Cas Gamma Air Dose 3.11.2.2 3.4-2 3.4.1.3 Noble Gas Beta Air Dose 3.11.2.2 3.4-2 3.4.2 Method 2: (Backup Method) 3.4-3 3.4.2.1 Noble Gas Gamma Air bose 3.11.2.2 3.4-3 3.4.2.2 Noble Gas acta Air Dose 3.11.2.2 3.4-4 3.5 GASEOUS EFFLUENTS, DOSE DUE TO RADIO-IODINES AND RADIOACTIVE MATERIALS IN PARTICULATE FORM'AND RADIONUCLIDES WITH HALF-LIVES GREATER THAN 8 DAYS 3.11.2.3 3.5-1 (g-~)s
. 3.5.1 Method 1: -(Computerized Method) 3.5-1 3.5.1.1 Release Estimation 3.11.2.3 3.5-1 3.5.1.2 Total Body Dose 3.11.2.3 3.5-2 BN1-11600.02-92 iv Revision 3 - December 1983
SNPS-l'0DCM
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TABLE OF CONTENTS (COE'D)
Radiological Effluent Technical Specification Section Subject' Section Page 3.5.1.3 Skin Dose 3.11.2.3 3.5-3 3.5.1.4 Organ Doses Due to Inhalation 3.11.2.3 3.5-5
'3.5.1.5 - Organ -Dosos Due to Ingestion of
- Leafy Vegetables 3.11.2.3 3.5-5 3.5.1.6' _Inf ant Thyroid Dose Due to Inhalation and Ingestion of Goat Milk 3.11.2.3 3.5-7 l 3.5.2 Method 2: (Backup Method) 3.5-11 3.5.2.1 Organ Doses 3.11.2.3 3.5-11 3.6 OPERATION OF VEE!LATION EXHAUST
. TREATMENT SYSTEM 3.11.2.5 3.6-1 3.7 TOTAL DOSE FOR THE URANIUM FUEL CYCLE 3.11.4 3.7-1 3.7.1 Sources of Radiation and Radioactivity 3.7-1 3.7.2 Radiological Lapact of Generation of Electricity 3.7-1
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'4 RECEPTOR LOCATIONS, METEOROLOGY, AND HYDROLOGY 4-1 5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS 5-1 6- . INTERLABORATORY COMPARISON PROGRAM 6-1 Appendix A DERIVATION OF Air A-l '
! Appendix B DERIVATION OF P otj B-1 1
O BN1-11600.02-92 v Revision 3 - December 1983
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SNPS-1 ODCM n'V LIST OF TABLES Table Title 2.2-1 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 3.1-1 Decay Constants 3.1-2 Adult Dose Rate Conversion Factors, Ag7 for (Fish and Invertebrate) Ingestion Pathway 3.4-1 Noble Gas Dose Factors 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,p to be Used for the Maximum O Exposed Individual in Lieu of Site-Specific Data I\
3.5-6 Stable Element Transfer Data 3.5-7 Humidity Parameters at Receptors 3.5-8 Distance from Reactor Centerline by Sector Out to 8046 m 3.5-9 P Contaminated Ground, Ingestion of Leafy and Stored Nhe,tablesDoseRateConversionFactorsforchild 3.5-10 P Child Ingestion of Cow's Milk Dose Rate Nkv,ersionFactors 3.5-11 P Child Ingestion of Goat's Milk Dose Rate Nkv,ersionFactors 3.5-12 P , Child Ingestion of Meat Dose Rate Conversion haftors 3.5-13 P , Infant Ingestion of Cow's Milk Dose Conversion hahtors O BN1-11600.02-92 vi Revision 3 - December 1983 l
SNPS-1 ODCM
' N. / LIST OF TABLES (CONT'D)
Table Title 3.5-14 Poij , Infant Ingestion of Goat's Milk Dose Conversion Factors 3.5-15 P ij, Child Inhalation and Ingestion of Leafy and Stored Vegetables Dose Rate Converson Factors 3.5-16 P ij , Child Ingestion of Goat's Milk Dose Rate Conversion Factors.
3.5-17 Pi , Inf ant Ingestion of Goat's Milk Dose Rate Conversion Fa tors 4-1 Critical Receptor Locations for Gaseous Ef fluent Calculations 5-1 Radiological Environmental 'Honitoring Program -
Sampling and Collection Frequency 5-2 Radiological Environmental Monitoring Program -
. Waterborne Monitoring Stations 5-3
- Radiological Environmental Monitoring Program -
Particulates and Radioiodine 5-4 Radiological Environmental Monitoring Program - Direct Radiation Monitoring Stations
> 5-5 Radiological Environmental Monitoring Program -
- Ingestion Monitoring Stations i
4 4
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BN1-11600-92 vii Revision 3 - December 1983
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-LIST OF FIGURES Figure Title 2.1-1 Detector R2-13, Efficiency vs. Gama Energy 2.1-2 . Detector RE-79, Efficiency vs. Gama Energy 2.1-3 Detector RE-23A, Efficiency vs, Gamma Energy 2.1-4 Detector RE-23B, Efficiency vs. Gama Energy
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2.2-1 Detector RE-42, Efficiency vs. Average Beta Energy 2.2 Linearity Response Curve for Detector RE-42 2.2-3 Detectors RE-65A,B, Generic Efficiency vs. Average Beta Energy 2.2-4 Generic Linearity Response Curve for Detectors RE-65A,B 2.2-5 Detectors RE-12A,B, Efficiency vs. Gama Energy 2.2-6 Generic Linearity Response Curve for Detector RE-12A,B
\ 3.1-1 Site Boundary for Liquid Effluents 3.1-2 Liquid Radwaste System Model-3.2-1 Liquid Radwaste Treatment System 3.3-1 Gaseous Effluent Model 3.6-1 Ventilation Exhaust Treatment System
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5-1 OnSite Sampling Locations - Radiological Environmental Monitoring Program 5-2 offSite Sampling Locations - Radiological Environmental Monitoring Program j
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BN1-11600.02-92 viii Revision 1 - August 1983
SNPS-1-ODCM SECTION 1-I -
INTRODUCTION The purpose _of this manual is to show ~ the calculational methodology and parameters used to comply -with the . Radiological Effluent Technical
- Specifications-(RETS).
Section 2 establishes methods to calculate the Liquid Effluent Monitor set P
point -and the -Gaseous Effluent Monitor set points in order to corply with RETS Sections 3.11.1.1: and 3.11.2.1, respectively.
Section. 3 establishes - -dose calculational methods for -liquid and gaseous
~
effluents. LThe 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 Section 3.1.2 calculation Method 2 is a calculated value based on i '
a' submerged, multiport diffuser with a port discharge velocity of 12 fps, a 300 f t radius mixing zone, and 4 recirculation pumps discharging.
The gaseous . effluent dose ' calculation methods are used to show compliance with RETS Sectiona 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 J. onsite meteorological data for the 2-year period of October 1, 1973 through 4
September 30, 1975.
- J ~
Tables 3.5-10, 3.5-12 and 3.5-13 are incorporated only for future use if there l
l' is a change in the land use census which requires considering any combination of cow's milk and meat pathways. I
^
.j Section '4 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. l Sectk on- 5 indicates locations at which environmental sampling may be conducted.
, Section 6 addresses -the Interlaboratory Comparison Program.
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4 BN1-11600.02-92 1-1 Revision 3 - December 1983 t k
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SET FOINTS
-62.1 LIQUID EFFLUENT MONITOR SET . POINTS (Compliance with Section 3.11.1.1 of l the' Radiological Effluent-Technical Specification (RETS))
The radionuclide concentrations released via liquid effluents to unrestricted
.'. aresse shall be . limited to the concentrations specified in 10CFR20, Appendix R, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the total concentration shall
'be limited to 2 x.10~4 pCi/ml.
. The set points of the effluent monitors are 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 y rate of 574,000 gpm)
= A 2. Flow rates of effluents from tanks and/or from the RHR heat exchanger service' water outlet, and/or yard piping drain sump.
3 3 5i i
V 3. -Individual concentrations of gamma emitters (other than dissolved or T entrained noble gases) and Sr-89, Sr-90, Fe-5 5, and H-3; and . the s- total . concentration of dissolved or. entrained noble gases and gross Ji .
concentration of the alpha emitters in the liquids to be discharged.
\ ~4 4 Maximum allowable concentration of 2x 10 tCi/mi for the total concentration of dissolved or entrained noble gases and maximum D permissible' concentrations (MPCs) of other gamma emitters, Sr-89, Sr-90, Fe-53 H-3, and alpha emitrers in the effluents as specified in 10CFR20,' Appendix B, Table II, Column 2 for an unrestricted area.
NOTE: Precautions should be taken to assure that the circulation system flow rate used in determining the set point remains constant during the period of discharge.
If the -circulating water flow rate during discharge becomes less than the flow rate that was used in calculating the discharge set point, the discharge must be terminated and a new set point calculated.
k, i[ Service continuously water to via the the RHR heat environment exchanger when the RHRservice water outlet heat exchanger is in will be released operation.
. k, m . Reactor- building salt water drain tank contents may be released to the
- A .
[ + environment either as a batch process or continously.
The discharge waste
\ sample tanks, recovery sample tanks, and yard piping drain sump contents will
- s always be released to the environment as batch processes.
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[ BNL-11600.02-92 2.1-1 Revision 3 - December 1983 m.
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.q For batch as well as . continuous releases, the sampling. and analysis program shall be in accordance with the minimum requirements of RETS Table 4.11.1.1.1-1.
Specifically, .the analysis program will include the determination of gross alpha concentration of the alpha emitters. In addition, _ it will include isotopic analysis for determination of individual concentrations of - principal gamma emitters, and the specific radionuclides, Sr-89, Sr-90, Fe-55, and H-3. It will also include the determination of total concentration of the dissolved and entrained noble gases (gamma emitters) in
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the liquids. The concentrations of individual gamma emitters are determined by gasma spectral analysis of 1) the batch sample prior to its release for the batch releases and 2) the weekly composite sample for continuous releases.
For gross alpha and . the . specific radionuclides Sr-89, Sr-90, Fe-55, and H-3, if analysis cannot be performed prior to discharge, then the following concentrations are used in the monitor set point calculations:
Cross alpha and H-3 Cross alpha concentration and H-3 concentrations as determined by analysis of the previous monthly composite sample.
Individual concentrations are determined by analysis of the previous quarterly composite sample for batch releases.
Representative Samples t
l - Representative composite samples utilized in determining the concentrations of H-3, Sr-89, Sr-90, Fe-55, and the gross alpha concentration both for batch and continuous releases,and in determining the concentrations of gamma emitters
' (excluding dissolved and entrained noble gases) for continuous releases are obtained in accordance with the method stated for obtaining such samples in the RETS Table 4.11.1.1.1-1.
j . The tank contents are recirculated prior to obtaining samples for analysis.
The minimum recirculation time rt shall be:
2v t
r " T-r where:
v = the volume of liquid in the tank to be sampled
.f r = the recirculation flow rate being used to mix the tank contents.
For the yard drain sump, the above methodology '
be used unless it can be determined that there has been no condensate wr tye tank overflow events since the . last batch release. Although designu.ed a batch release, there
.maybe times when non-contaminated yard drain runoff to the sump will occur during the discharge period. This input will not increase the discharge concentration.
BN1-11600.02-92' 2.1-2 Revision 2 - September 1983
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% / This will ensure that a representative sample will be obtained for batch releases.
Set Point Philosophy The philosophy of the set points will be based on the sum of the ratios of isotopic concentrations to MPCs being less than 1 for discharges into ,
unrestricted areas. Specifically:
" MPC MPC + ***** + MPC + MPC + MPCG a b n a C C C
('
= Concentration of the individual gamma emitting C,,C b ,......C n radionuclides identified (pCi/ml)
( ) C, = The gross alpha concentration (pCi/ml)
Cg = The total concentration of dissolved or entrained noble gases (pCi/ml)
C, = 'Ihe Sr-89 and Sr-90 concentrations (pCi/ml)
Cg = The H-3 concentration (pci/ml)
C, p
= The Fe-55 concentration (pCi/ml)
MPCg= MFC,, MPCb ....., MPC ,nMPC ,a MPC ,g MPC g, MPC t, MPCFe
= the maximum permissible concentration of the respective radioisotope 1 (uC1/ml) from 10CFR20, Appendix B, Table II Column 2. For dissolved or entrained noble gases, the maximum allowable concentration (MPC g ) will be 2.00E-04 (pCi/ml). For gross alpha, the MPC assumed will be 3.00E-08 (pCi/ml).
If the C/MPC calculated is greater than 1, then no release is possible. The normalization factor (as defined in Section 2.1.1) must be greater than 1 to permit releases. To permit releases, this factor can be increased to a value greater than 1 by increasing dilution flow Fe (by running more circulating water pumps in the applicable discharge structure), and/or decreasing the l
'j effluent flow rates f' I' I I HB, etc. (defined in Section 2.1.1), and
( D s UA' U recalculate C/MPC using new Cg in Equation 2.1-1.
BN1-ll600.02-92 2.1-3 Revision 3 - December 1983
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2.1.1 Radiatioa Effluent Monitor (RE-13) High/ Trip Alarm Set Point for Discharge Waste Sample Tanks, Recovery Sample Tanks, or Yard Piping Drain Sump The function of this monitor set point is to ensure that the sum of the ratios of the discharge concentrations to the MPCs of the corresponding radionuclides of the discharges monitored by this monitor and 'other liquid waste discharges, if any, does not exceed 1. If the monitor count rate is higher than the calculated set point, the radiat: ion monitor will terminate the release.
A sample is taken from any of the following tanks or sump which is to be discharged along with any streams which are in the process of being discharged.
- 1. Discharge waste tanks
- 2. Recovery sample tanks
- 3. Yard piping drain sump
- 4. Reactor building salt water drain tank
- 5. Residual heat removal heat exchanger service water Only one of the first three items above is discharged at any one time, which h
a can be combined with releases from item 4 and/or 5.
Obtain _ the circulating water flow rate from the control room (see NOTE in Section 2.1).
Define Normalizing factor
~ ~
F =
[fD + 'HA + 'HB s c HA HB
- 0.8 (CDi'D + HiA'HA + HiB HB + si s i=1( MPC g An isotopic analysis of each sample is performed. This analysis includes isotopic analysis for gamma emitters; gross alpha emitters; total dissolved or entrained noble gases ; and Sr-89, Sr-90, Fe-55, and H-3. This should be done for all monitors.
Then the set point (NOTE: the background (cpm), if it can be determined, is also added to the set point value. If, however, it cannot be dete mined, it is considered as zero) for detector RE-13 is calculated as:
N S g3 iF*[C i=1 Di i (cpm)
%)
BN1-11600.02-92 2.1-4 Revision 1 - August 1983
SNPS-1 ODCM t-where:-
Cpi concentration of radioisotope (i) (pCi/ml) in any of the following tanks or sump that is to be discharged:
.1. discharge waste tanks
- 2. recovery sample tanks
- 3. yard piping drain sump f
D
= Discharge flow rate (gpm) from any of the following tanks or sump that is to be discharged:
- 1. discharge waste tanks
- 2. recovery sample tanks
- 3. yard piping drain sump.
(Maximum design discharge flow rate = 150 gpm)
Cgg - Reactor building salt water drain tank concentration of radioisotope (i) (pCi/ml)
CHIA = RHR heat exchanger service water outlet concentration of radioisotope (i) (pCi/ml) from loop'A.
} CHiB = RHR heat exchanger service water outlet concentration of radioisotope s/ (i) (pCi/ml) from loop B.
f = Reactor building. salt water drain tank discharge flow rate (gpm).
3 (Maximum design discharge flow rate = 100 gpm) l f
HA = RHR heat exchanger service water outlet discharge flow rate (gpm) from loop A (Maximum design discharge flow rate = 9340 gpm) f MB =. RHR heat exchanger service water outlet discharge flow rate (gpm) from loop B (Maximum design discharge flow rate 9340 gpm)
F =
Total circulating water flow rate (gpm) (this includes FHA and fHB)
C E-g
= Camma counting efficiency of RE-13 for radionuclide (i)
(cpm /pCi/ml). Figure 2.1-1 shows the energy response. For non-gamma emitters, E g=0.
0.8 = Safety factor
.MPC is- defined in Section 2.1. The above calculation is made for each batch l to b released.
After each batch release, the high alarm set point should be reset as close to the background as practical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur.
BN1-11600-02-92 2.1-5 Revision 3 - December 1983
SNPS-1 ODCM
,1 2.1.2 Radiation Effluent Monitor - (RE-79) High Alarm Set Point for Reactor Building Salt Water Drain Tank The function'of.this monitor _ set point is to ensure that the sum of the ratios of the discharge concentrations to the MPCs of the corresponding radionuclides of the discharges monitored by this ' monitor and other liquid waste discharges, if any, does not. exceed 1.
~ If the -monitor count- rate is higher than .the calculated set point, the radiation monitor will alarm in the control room.
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 tanks
- 2. Recovery sample tanks
. 3'. -Yard piping drain sump
- 4. Residual heat removal heat exchanger service water In the case of continuous release, samples will be taken as per requirement RETS Table 4.11.1.1.1-1.
Obtain the circulating water flow rate from the control room (see NOTE in Section 2.1).
The set point for continuous or batch release (see NOTE in Section 2.1.1) will l
'he calculated as follows:
N S79 i F*[yC3 gE] (cpm)
-where:
E1= Gamma counting efficiency of RE-79 for radionuclide 1 (cpe/pci/ml). Figure 2.1-2 shows the energy response. For non-gamma emitters, Eg=0 All other parameters .are as defiaed in Section 2.1.1.
When the tank operates in a batch mode, the above calculation is made for each batch to be released.
After each batch- release or continuous - release period, the high alarm set l O. point should . be reset as close t.o the background as practical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur.
1-11600-02-92 2.1-6 Revision 2 - September 1983
SNPS-1 ODCN O
2.1.3. Residual' Heat Removal Heat Exchanger Service Water Outlet Monitors (RE-23A, RE-238) High Alarm Set Points The function of this monitor set point is to ensure that the sum of the ratios -
of the discharge concentrations to the MPCs of the corresponding radionuclides of the discharges isonitored by this monitor and other liquid waste discharges, if any, does not exceed 1. If the monitor count rate is higher than the calculated set point, the radiation monitor will alarm in the control room.
Monitors RE-23A and RE-238 are independent. Each is dedicated to monitor its l respective RHR loop. -
A sample . will be taken from the RHR heat exchanger service water outlet (A and/or B), along with individual samples of any of the following streams which asy be in the process of being discharged:
- 1. ' Discharge waste sample tanks
- 2. Recovery.. sample tanks
- 3. Yard piping drain' sump
- 4. Reactor building salt water drain tank discharge
\
. 0btain the ' circulating water ' flow rate from the control room (see NOTE in Section 2.1).
The set points for RE-23A and RE-23B are calculated as follows:
23A I 11 HiA iA I S23R { F * [1 1!C HiBEig]
where:
Egg = Camma counting efficiency of RE-23A for radionuclide 1 (cpe/pci/ml). Figure 2.1-3 shows the gamma energy response. For non-gamma emitters, EiA=0 Eg = Gamma' counting efficiency of RE-238 for radionuclide 1
-(cpm /pci/al).. Figure 2.1-4 shows the gamma energy respons2. For non-gamma emitters , Egg = 0 All other parameters are as defined in Section 2.1.
L(
BN1-11600.02-92 2.1-7 Revision 2 - September 1983
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a' 107 i i 10 10 2 jo s 10*
GAMMA ENERGY (KEV)
SOURCE: FIGURE 2.1-1 DETECTOR RE-13
^
BATTELLE COLUMBUS INSTITUTE COLUMBUS, OHIO DATA SHEET IL-CP-600-D5 EFFICIENCY VS. GAMMA ENERGY
EXTRAPOLATION FROM GENERAL ATOMIC CC. SHOREHAM NUCLEAR POWER STATION-UNIT 1
(< 300 KEV) GENERIC CALIBRATION CURVE FOR RD-53 OFFSITE DOSE CALCULATION MANUAL CALCULATED VALUE REVISION 3 - DECEMBER 1983
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107, , i i 10 10 2 jo s 10' GAMMA ENERGY (KEV)
SOURCE: FIGURE 2.b2
- BATTELLE COLUMBUS INSTITUTE COLUMBUS, OHIO DETECTOR RE- 79 DATA SHEET: IL- C P- 600 -D 5 EFFICIENCY VS. GAMMA ENERGY
--==== EXTRAPOLATION FROM GENERAL ATOMIC CO. SHOREHAM NUCLEAR POWER STATION-UNIT 1
( <300 KEV)
GENERIC CALIBRATION CURVE FOR RD -53 OFFSITE DOSE CALCULATION MANUAL
- - - - - - CALCULATED VALUE
( > l.15 MEV) REVISION 3- DECEM B ER 1983
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SNPS-1 ODCM im 2.2 GASEOUS EFFLUENT MONITOR SET POIMS (Compliance with Section 3.11.2.1 of the RETS)
' The high alarm set point for the. Station Ventilation Exhaust Monitor (RE-42) is set . in _ accordance 'with the dose rate limit for noble gases at the site boundary specified in Section 3.11.2.1 of the RETS:
Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mres/yr to the skin. The set point for this monitor will be determined based on the lower of the two set points . calculated for: 1) the total body dose rate and 2) the skin dose rate, calculated respectively in Sections 2.2.1 and 2.2.2. The high alarm set points for the Main Condenser Offgas System Effluent Monitors (RE-65A, B) is based on the MPC limit specified in 10CFR20 Appendix
'B, Table II, Column I which is in conformance with the dose rate limits specified above. The high alarm set point for the Main Condenser Air Ejector Monitor (RE-12A, B)'in normal operation is based on the RETS limited total noble gas (beta and gamma) release rate at the main condenser air ejector, which is 244,000 pCi/sec at 30 minutes delay. The high alarm set point for
. the Main Condenser Air Ejector Effluent Monitors in the bypass mode (RE-12A, B
(% in the bypass mode) are based on 25% of the limit specified above, b For all the above monitors, the initial set points are based on expected release rates (Ci/ year) for radionuclides given in the Safety Evaluation Report (SER) for Shoreham (NUREG-420, April 1981, Table 11-2). An effective initial concentration, C g(pCi/cc) for each radionuclide, i, is obtained from the release rate, Og (Ci/yr) for the radionuclide and the appropriate flow rate V(cc/sec) as follows: 0 (Ci/yr)
- 10 1
(p ) Cg (pCi/cc) =
- 3.15
- 107(m) V(m sec )
When the mechanical vacuum pump is in operation, g (Ci/yr) from mechanical vacuum pump exhaust will be used vacuum pump operates for -100 hours or 3.6 x 10 theasguming mec thatthe releas seconds per year. The effective initial concentration C ( Ci/cc) for radionuclide, i, when the
. mechanical vacuum pump is in operatkon,p is calculated as:
Og , (Ci/yr)
- 10 ( )
Cg '(pCi/cc) =
- 3.6
- 10 (**y"r) Y( c)
Once operation has begun, the concentration,g C , for each radionuclide, will be obtained as the measured value from a grab sample. BN1-11600.02-92 2.2-1 Revision 1 - August 1983
h SNPS-1 ODCM
\
v) The methodology of multipying the observed cpm by the calculated scale factor will be used to obtain the set point in the range where the detector response is linear with changes in nuclide concentration. In the non-linear region, appropriate correction as derived from Figures 2.2-2 or 2.2-4 will be made. 2.2.1 Gaseous Effluent. Monitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) 2.2.1.1 Caseous Effluent Monitor High Alarm Set Point for Station Ventilation Exhaust Monitor (RE-42) Based on Noble Cases Total Body Dose Rate
- 1. During operation a gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, C. g Before startup, Cg will be calculated as noted in Section 2.2.
- 2. At the' time of sampling, the net count rate (excluding background),
CR (cpm), of the Station Ventilation Exhaust Noble Gas Radiation Monitor will be recorded. Before startup, the estimated CR is calculated as: CR = 10 *( g C
*E} (cpm) l c where:
E t
= detector efficiency (cpm /pCi/cc) for RE-42 for radionuclide, i, as provided in Figure 2.2-1. The linearity response for RE-42 is shown in Figure 2.2-2.
- 3. The noble gas total body dose rate is calculated using the following equation:
{DR
=
X/0*V*({DFB*C) g (arem/yr) 4 where: DR g = predicted dose rate based on gas sample for isotope 1 l (mrem /yr), X/Q = annual average X/0 (sec/m3 ) at 366 meters NNE due to releases via the station ventilation exhaust point (6.6E-07 sec/m3 ), DFB t=totalbodydosg)rateconversionfactor (arem/yr/pCi/m , from Table 2.2-1, C = sampled isotope release concentration (pCi/cc), f
'V = station ventilation exhaust rate (cc/sec). ,
G (Maximum exhaust rate = 1.73E+08 cc/sec (3.66E+05 cfm).) l
. \g BN1-11600.02-92 2.2-2 Revision 3 - December 1983
SNPS-1 ODCM O ,
- 4. The ' isotopic release activity concentration is normalized to a total body dose. rate of 500 mrem /yr by multiplying by the following normalizing factor:
- F3 =500/{DRg
- 5. From the above, the set point (see NOTE in Section 2.1.1) based on total body dose rate.can be calculated as follows:
8 S 4210.8
- FB
- CR (cpm)
- where:
B S q= high alarm set point that results in a total body dose rate of less than 500 mrem /yr, 3 F B
=
normalization factor (unitiess), CR =
' station ventilation exhaust notle gas radiation monitor count rate (cpm), and
- 0.8^= safety factor.
l The above procedon and format will be used to calculate the ser point for RE-42 when the mechanical vacuum pump is f n operation or during containment purge. Under these conditions, the short term atmospheric dispersion factor at 366 meters NNE (3.60E-06 sec/m ) shall be used instead of the annual average value. 2.2.1.2 Caseous Effluent Monitor High Alarm Set Point for Station Ventilation l Exhaust Monitor (RE-42) Based on Noble Gases Skin Dose Rate
- 1. During operation a gaseous sample from the monitor will be taken and analyzed for isotopic composition and concentration, C. f Before startup, C gwill be calculated as noted -in Section 2.2.
2
- 2. At the time of sampling, the net count rate (excluding background),
CR (cpm), of the station ventilation exhaust noble gas radiation monitor will be recorded. Before startup, CR is calculated as noted in Section 2.2.1.
- 3. The noble gases beta and gamma skin dose rate is calculated using the following equation:
{DR = x/0
- V * ([ K,g* Cg ) (area /yr) where:
, a . DRg = predicted dose rate based on gas sample for isotope 1 l (mrem /yr) ,- BN1-11600.02-92 2.2-3 Revision 3 - December 1983
l l SNPS-1 ODCM X/0 = annual average X/O (sec/m3 ) at 366 meters NNE due to releases via the station ventilation exhaust point, (6.6E-07 sec/m 3), bim = skin dose rate ' conversion factor (arem/yr/pCi/m3 ), from Table 2.2-1, Cg = sampled isotope release concentration (pCi/cc), V- = station ventilation exhaust rate (cc/sec). (Maximum exhaust rate = 1.73E+08 cc/sec (3.66E+05 cfm).) l
- 4. The isotopic release activity concentration is normalized to a skin dose rate of 3000 arem/yr by multiplying by the following normalizing j factor:
F g=3000/{DR
,5. From the above,- the alarm set point (see NOTE in Section 2.1.1),
based on skin dose rate, can be calculated as follows: I S q < 0.8
- FS
- CR (cpm) p where:
S S = high alarm set point that. results in a skin dose rate 42 of less than 3000 mrem /yr (cpm), j Fg = normalization factor (unitiess), t ! CR = station ventilation exhaust noble gas radiation monitor count rate (cpm), and 0.8 = safety factor. l l %e above procedure and format will be used to calculate the set point for i RE-42 when the mechanical vacuum pump is in operation or during containment purge. Under these conditions, the short term atmospheric dispersion factor 3 at 366 meters NNEL (3.60E-06 sec/m ) shall be used instead of the annual average value. 2.2.2 Main Condenser Offgas System Effluent Monitors (RE-65A,B) High Alarm Set Point The' Itain' Condenser Offgas System Effluent Monitor has two chambers (65A, 65B) in series. Each chamber constitutes a separate independent output channel containing a detector composed of 3 m tubes whose output are summed up. The monitor set point will be based on a release rate which results in 0.1 MPC at the site boundary. - The set point calculated shall be divided by a factor of 3 to account for the case when only one m tube per chamber is functional. BN1-11600.02-92 2.2-4 Revision 3 - December 1983 l
-. _ . . . . _ , . . , _ _ _ ~ - . . _ _ , . , _ _ , - . - _ . - _ - , , , . , - _ . - - - - _ . , . - . _ . - . . . _ , ,
SNPS-1 ODCM TT
-1. During operation, a gaseous . sample from the monitor will be taken and analyzed *or isotopic composition and concentration, C.
g Before startup, (.g will be calculated as noted in Section 2.2.
- 2. At the time of sampling, the . net count rate (excluding background),
CR : (cpa), of the monitor will be recorded. _ Before startup, the estimated count rate CR (cpe) due to concentration, C g , is calculated as: CR = 10
' ~
*( g C*E) (cpm) l where:
Eg = detector efficiency (cpm /pCi/cc) for RE-65A,B for radionuclide,- i, as provided in Figure 2.2-3. The generic linearity response for RE-65A,B is shown in Figure 2.2-4
- 3. The sum of the ratios of the released isotopic concentrations to MPC ,
is normalized to 0.1 at the site boundary by multiplying by the
- following factor:
F= 0.1 C (g! 1 MPC )* v
- x/O
- 3.0 1
where: V condenser offgas flow
= Magn system ventilgtion rate (m /sec) (Maximum flow rate = 1.18E-02 m /sec (25 cfm).) '
x/0 = annual average dispersion factor at 366 meters NNE (6.6E-07 meteorologig)al sec/m dua to releases via the station ventilation exhaust point. 3.0 = Safety factor in case of 2 out of 3 CM tube failures.
- 4. From the above, the high alarm set point for RE-65A,B (see NOTE in l Section 2.1.1) is calculated as follows:
1 S65 1 0.8
- F
- CR (cpm) 2.2.3 Main Condenser Air Ejector Monitors (RE-12A.B) High Alarm Set Point for Non-bypass Mode Operation (normal operation)
The Main Condenser Air Ejector Monitor System has two detectors looking
- at one chamber. The alarm will be set off - by a signal from either
, detector. i BN1-11600.02-92 2.2-5 Revision 3 - December 1983 U-E.--,-,'.u-+ .-,,,ww,%, .-, .,%-, - , . ----.,,-e,-,,...,vym m-w__ - , . . . - . . , --,wemw,,..<
SNPS-1 ODCM 4 (_) 2.2.3.1 Initial Set Point for RE-12A,B Non-bypass Mode Operation
- 1. Use the t=0 CE noble gas spectrum for off-gas system release rate prior to treatment (CE document 22A2703B Rev. 3, Table V), scale it to the Shoreham RETS (3.11.2.7) limit of 244,000 pCi/sec at 30 minutes decay by multiplying by 2.44. Divide it by the air ejector flow rate (1.05E+06 cc/sec) to obtain the limiting concentrations Cg (pCi/cc) of each radioisotope 1.
- 2. Using the isotopic concentrations, Cg (pCi/cc), defined above and the effective gamma energy per disintegration, Etg (MEV/ dis) calculate the specific gamma activity, Afg(MEV/cc-sec), for the 1-th isotope in each of the following gamma ray energy bins: 0-0.4, 0.4-0.8, 0.8-1.3, 1.3-1.7, 1.7-2.2, 2.2-2. 5, and 2.5-3.5 (MEV) . Thus:
^11 = K
- Egg *C g where E t is the total gamma energy (MEV) emitted per disintegration of the 1-th isotope by gamma rays belogging to the i-th energy bin derined above. The factor K = 3.7 x 10 (dis /sec/pCi) is introduced for unit conversion.
O h The total specific gamma activity, Ag (MEV/cc-sec), for each gamma energy bin, i, is calculated by summing the specific gamma activity, Agg, for bin 1, over all isotopes.
" A
^i i 1 gg
- 3. Using the response curve for RE-12A,B given in Figure 2.2-5, calculate the dose rate. The generic linearity response curve for RE-12A,B is shown in Figure 2.2-6.
7 DR = [ CFg* A g (mrem /hr) l i=1 where: CF is the efficiency (gy*j ) at the i-th energy group I
- 4. The high alarm set point (see NOTE in Section 2.1.1, but note the background unit is in mrem /hr) for RE-12A,B in the non-bypass mode l will be:
S12 < 0.8
- DR (mrem /hr) l
, %J l BN1-ll600.02-92 2.2-6 Revision 3 - December 1983
SNPS-1 ODCM i 2.2.3.2 Subsequent Adjustments of Set Points for RE-12A,B in Non-bypass Mode Ope ration
- 1. During operation, a gaseous sample from the monitor will be taken and analyzed for noble gases isotopic composition and concentration, C, g (pCi/cc) at t=30 minutes. Before 'startup, Cg will be calculated as noted in Section 2.2.
- 2. At the time of sampling, the net dose rate reading (excluding background) of the monitor will be recorded, DR (mrem /hr).
- 3. The isotopic release activity concentrations, C, t are summed and multiplied by the air ejector flow rate, V (cc/sec) to obtain the noble gas release rate, pCi/sec.
- 4. The release rate in step 3 is normalized to the RETS Section 3.11.2.7 release limit of 2.44E+05 pCi/see at t=30 minutes as follows:
p, 2.44E+05 (p C1 )
- v
- 5. From above, the high alarm set point (see NOTE in Section . 2.1.1, but note the background is in mrem /hr) based on a release rate of l 2.44E+05 pCi/see at t=30 minutes can be calculated as follows:
S12 < 0.8
- F
- DR (arem/hr) l 2.2.4 Main Condenser Air Ejector Monitor (RE-12A,B) High Alarm Set point for.
Bypass Mode Operation 2.2.4.1 Initial Set Point for RE-12A,B in Bypass Mode Operation
- 1. Same as steps 1, 2, and 3 in Section 2.2.3.1
- 2. The off-site total body dose rate DT corresponding to the above concentration is calculated as:
DT = 10 *X/Q*V*([DFB*C) l 1 and the beta and gamma skin dose rate is calculated as : D,=10+6*X/O*V*([K,1, *C) g l 3 i where: DT " predicted total body dose rate (arem/yr) D, = predicted beta and gamma skin dose rate (mres/yr) BN1-ll600.02-92 2.2-7 Revision 3 - December 1983
x SNPS-1 ODCM X/Q
= annual NNE (6.6E-07 average atmosp)heric sec/m due todispersion releasesfactor via the at366 meters station ventilation exhaust point V = Air ejector exhaust flow rate (cc/sec) (Maximum exhaust flow rate is 1.05E+06 cc/sec)
DFBg = total body dose rate conversion factor (*#** Y#) from Table 2.2-1 3 pCi/m K,g , = skin dose rate conversion factor (*#*" ) from Table l- 2.2-1 pCi/m ! 3. The normalizing factor F is chosen to be the smaller of the two (to ! comply with 25% of the RETS (3.11.2.1) dose rate limit): yT ,125 arem/yr D T 750 meen/yr S" D S F = the smaller of FT or FS (unitiess) 4.- The high alarm set point (see NOTE in Section 2.1.1, but note the background is in area /hr) RE-12A,B in bypass mode is set at: l S12 1 0.8* F
- DR (arem/hr) l 2.2.4.2 Subsequent ' Adjustments of Set Points for RE-12A,B in Bypass Mode Operation
- 1. A gaseous sample from the monitor will be taken and analyzed for isotopic composition'and concentration, Cf (pCi/cc)
- 2. At the time of sampling, the net dose rate reading, DR (arem/hr), of l the monitor will be recorded.
- 3. Follow procedures 2, 3, and 4 of Section 2.2.4.1 to get the high l
alarm set point for RE-12A,B in bypass mode. G
-BN1-11600.02-92 2.2-8 Revision 3 - December 1983
^
O "O O SNPS-1 00CM
., TABLE 2.2-1
- DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES j
nc de S-Air (I) (DFbi ) .FSkinW (DFSt ) Y-Air (I):(DFHg ) . Body (2) (DFBt ) Skin s (2)' Skin e (2) Kr-83m 2.88E-04(3) - 1.93E-05' 7.56E-08 1.5E-05 2.1-05 Kr-85a 1.97E-03 1.46E-03 1.23E-03 1.17E-03 2.4E-03 2.8-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E-05 1.4E-03 1.4-03 Kr-87 1.03E-02 9.73E-03 6.17E-03 -5.92E-03 1.5E-02 1.7-02 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 -1.4E-02. '1.9-02' Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 2.4E-02 2.9-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 2.0E-02 2.5-02 Xe-131a 1.11E-03 4.76E-04 1.56E-04 9.15E-05 6.0E 6.5-04 Xe-133a 1.48E-03 9.94E-04 3.27E-04 2.51E-04 1.2E-03 1.4-03 Xe-133 1.05E-03 3.06E-04 3.53E-04 2.94E-04 5.8E-04 7.0-04 Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 3.3E-03 4.4-03 Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 3.4E-03 4.0-03 Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 1.3E-02 1.4-02 BN1-11600.02-93 1 of 2 Revision 1 - August 1983
O O O SNPS-1 ODCM TABLE 2.2-1 (CONT'D) n id . S-Air (I) (DFbg ) 6-Skin (2)'.(DFSg ).. Y-Air (I) (DFHg )' Y -Body (2) (DFBg ) Ski s (2) Skin e (2) Xe-138 4.75E-03 4.13E-03 9.21E-03 8.83E 1.1E-02 1.4-02 Ar-41 3.28E-03 2.69E-03 9.30E-03 _8.84E-03. 9.9E-03 1.3-02 (1) erad-m pCi-yr (2) ares-a
.pCi-yr (3) 2.88E-04 = 2.88
- 10-4 (4) gsi = (0.7
- 1.11
- DFH )g + DFSg (5) K,1 , = (1.11
- DFH g) + DFS g BN1-11600.02-93 o 2 Revision 1 - August 1983
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SOURCE LILCO LETTER FILE No.221.9 LIL- 21157
--- - IDEAL CURVE
- Call 8MATION CURVE FIGURE 2.2-2 (DATA CONSISTENT WITH LINEARITY RESPONSE CURVE FOR (q)
FIGURE 2.2 -1) DETECTOR RE-42 SHOREHAM NUCLEAR POWER STATION-UNITI OFFSITE DOSE CALCULATION MANUAL REVISION 1-AUGUST 1983
10' . . .
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t ++ t 10 10' d 10" AVERAGE BETA ENERGY (KEV) SOURCE: GE MEMO (Pearson)-PROCESS RADIATION SAMPLING SENSITIVITIES. JUNE 26,1977 (REV.1 )
- GENERIC CALIBRATION CURVE FIGURE 2.2-3 DETECTORS RE-65A,B GENERIC EFFICIENCY VS. AVER AGE BETA ENERGY i
A < SHOREHAM NUCLEAR POWER STATION-UNIT 1
; OFFSITE DOSE CALCULATION MANUAL
, n REVISION 1-AUGUST 1983 I
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===== IDEAL CURVE GENERIC CALIBRATION CURVE FIGURE 2.2 4 GENERIC LINEARITY RESPONSE CURVE O)
L/ FOR DETECTORS RE-65 A, B SHOREHAM NUCLEAR POWER STATION UNIT l OFFSITE DOSE CALCULATION MANUAL REVISION I- AUGUST 1983 l
O O O 2.5 - m 9 2 E 5 gj 2.o- - E g U - z W o ir - IIi 1.5 . . . . . o 1.0 2.0 3.o 4.o GAMMA ENERGY (MEV) FIGURE 2.2-5 DETECTORS RE-12 A,B EFFICIENCY VS. GAMMA ENERGY SOURCES: SHOREHAM NUCLEAR POWER STATION-UNIT 1
- 1. uLco STARTUP PACKAGE No. CS.630.OO4 OFFSITE DOSE C ALCULATION M ANUAL
, 2. SWEC CALCULATION Il600.02-SNPS-1-URB-:15 P j e GAMMA ENERGY BINS (CFj ) I REVISION 1- AUGUST 1983
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- IDEAL CURVE e ACTUAL DATA FIGURE 2.2-6 c,. GENERIC LINEARITY CURVE FOR DETECTORS RE-12 A,B
^
('x d SHOREHAM NUCLEAR POWER STATION-UNIT I OFFSITE DOSE CALCULATION MANUAL REVISION 1 - AUGUST 1983
SNPS-1 ODCM SECTION 3 O '
~
DOSE CALCULATION METHODS s
.; 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.II.1.3-OperationofLiquidRadwasteTreatmentSystem 3.I't.2'.1'- Gaseous Effluent Dose Rate 3.I l.2.2 - Noble Gas Air Dose
, ,)3.11.2.3 - Caseous Effluent Dose From Radioiodines, Radioactive Materials In Particulate Form 3.11.2.5 - Operation of Ventilation Exhaust Treatment System 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 for the Purpose of Evaluating Compliance
'with 10CFR50, Appendix I".
s Two methods are provided for each analysis. The first method is the method used by the computerized radiation monitoring system. Method 2 is a backup hand calculational method to be used only if the computer is not functional.
.. ,r s
,e .
/
)
O BN1-11600.02-92 3.0-1 Revision 1 - August 1983
't .j[ SNPS-1 ODCM yh.
O p 3.1 LIOUID EFFLUENT, DOSE CALCULATION If To comply with Section. 3.11.1.2 of the RETS, the liquid effluents released to Q i, unrestricted areas shall be limited:
- 1. During any calendar quarter to less than or equal to 1.5 arem to the total body and to less than or equal to 5 area to any organ.
- 2. During any calendar year to less than or equal to 3 mrem to the total
.f body and to less than or equal to 10 mrem to any organ.
u - 7, The site boundary for liquid effluents is shown in Figure 3.1-1. The liquid l 3
~
radwaste system model is shown in Figure 3.1-2.
~3.1.1 Method 1: (Computerized Method)
The equations which follow are used by the computer sof tware 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 , 1 _ 1iquid to be discharged, and the number of circulating water pumps running,
-M supplied by the operator, shall be used.
'%. 4 i The .. software computes the. isotopic releases by multiplying the lab measurements by the volume of the liquid to be released:
.s.
Qg
= -3.785 x 10-3 y q where:
Q-1
=
total inventory of isotope i in the liquid to be released (Ci)
'% ; n mg ,
m 7 4 qt = concentration of isotope i in the liquid to be discharged (as
.,% measured in laboratory) (pCi/cc)
A - V = volume of liquid to be discharged (gallons) 3.785 x 10-3 = [(Ci/pci) (cc/ gal)! , 1 The dose equations which follow are from Regulatory Guide 1.109, with minor modifications. They are employed for the computation of dose from any single i vi batch discharge. Weekly and quarterly cumulative doses are also calculated and stored in data files for reporting. g ~~ c;%g;
-(a) Organ Dose due to Ingestion of Saltwater Fish ing nsh s * ~ +- ,
- R ja = 0.389 Uap (1/K) E Oi Bip DFI e i part+I ija l
),,.
- . v 1 ,-
~3' BN1-11600.02-92 3.1-1 Revision 3 - December 1983
? % , 3.
. y'y.s s -
4 e , ,-.e . , , - - . - - - . - ,- , .--.w,9.,,- ,.m-w,,- .yc ,,n,, .,%.-----,,,,,,,,,.,y,, ,,--,,--.,--y.~,, ,,e ,,,~-e,--,-y-,,,,.,,7 y
SNPS-1 ODCM O where: R "I = dose to organ j of individual in age group a due to 3* ingestion of fish contaminated with particulates and ratio-iodines (area) ' (Ref. Reg. Guide 1.109, with the following special values:
- F (flow rate of 11 3 uid 9 effluent) 18 represented by product K
- F [ft /sec], where K is the number of pumps operat[ng and F is the flow rate per unit pump pump 5
*F pump = 1.435x10 18pm] = 319.7 [ft3/sec]
e (mixing ratio (reciprocal of dilution factor) at the int of exposure) = 0.113 l
- D,gp3 (dose factor) = DFI g) , (see below) et o (transit time required for nuclides to reach the point of exposure) = 24 [hr] (see pg 1.109-12 of the Regulatory Guide) is U
ap = fish consumption rate by individual in age group a [kg/yr] (from Table E-5 of the Guide, for maximum individual) K = number of pumps operating (circulating water system) Q1 .= total activity of isotope i released [Ci], from above s B ip
= Bioaccumulation factor for saltwater fish [(pci/kg)/
(pCi/ liter)] -(from Table A-1 of the Guide) DFI gj, = dose conversion- factor for nuclide i to organ j of indivf. dual in age group a due to ingestion [ mrem /pCi ingested] (from Tables E-11 through E-14 of the Guide) Ag = radionuclide decay constant [hr-I] (from Table 3.1-1) l 0.389 = 1100 Mp/Fpump = 1100 x 0.113 / 319.7 [(pCi/1)/(Ci/yr)] l part+I = 68 particulates and 5 iodines in the summation sign (b) Organ dose due to ingestion of saltwater invertebrate
.R ,"8 = 0.389 d "#(1/K) E Qg B DFI e' i l
(%
- BN1-11600.02-92 3.1-2 Revision 3 - December 1983
.1 >
SNPS-1 ODCM s v i
-where:
I~
' R "E
= dose ~ to crgan 'j of individual in age group' a due to the
. ingestion of . ' saltwater invertebrate contaminated. with radioactive particulates 'and iodines - [arem] - (Ref. : Reg.
Guide 1.109 - Eq. A-3 with the special values identified in
- the fish-ingestion equation above)
B ip = Bioaccumulation factor for saltwater invertebrate [(pCi/kg)/ (pCi/ liter)] (from Table A-1 of the Guide) M"' ap = invertebrate consumption rate by individual in age group a [kg/yr] (from Table E-5 of the Guide, for msximum c individual) (c) Total'boly dose from shoreline deposits j R = 0.561.U," (1/K) . E part+I Q DFG g( A') l l i l where: l
\
R -~
= total body dose to individual in age group a from shoreline deposits [ mrem] (RefL: Reg. Cuide 1.109 Eq. A-7 with the following special values:
e F(flow . rate of d effluent) is represented by the
, product K*F liqug/sec],
[ft where K is the number of l operating puhEand Fpump is the flow rate per unit pump eF pu,p = 1.435 x 105 [ epm] = 319.7 [f t3 /sec] eMp (mixing ratio) = 0.113 l f: *W (shore-width factor that describes the geometry of the
- j. exposure) =
0.5 for ocean site (from Table A-2 of the I guide) et p (transit time from source to shoreline) = 0 (see Reg.
'Cuide-pg 1.109-69, for Eq. A-7) eT i (radionuclide half life, days) =
0.693/(24A1 ) where 0.693 = log,2 and At is the decay constast in [hr-1] e D,gp3 = DFGiy (see below)
.. U" ap = shoreline exposure time for individual in age group a
[hr/yr] (from Table E--S of the Guide, for maximum
-individual)
BN1-11600.02-92 3.1-3 Revision 3 - December 1983
SNPS-1 ODCM-
.K = number of pumps operating (circulating water system)
Q1 = total activity of isotope i released [Ci], from above DFG gy = total body conversion factor fo standing on contaminated ground (shore) [(arem/hr)/(pCi/m{)] (from Table E-6 of the guide) t b " time Period oger which accumulation is evaluated (15 years, or 1.314 x 10 hours) 0.561 = 110,000 M p W (T t1A )/ Fpump ((pCi/1)/(C1/yr)] l
= 110,000 x 0.113 x 0.5 x (0.693/24)/ 319.7 l part+I = 68 particulates and 5 iodines in the summation sign ,
,(d) Skin dose from shoreline deposits R
, = 0.561 (1/k)pdt+I Og DFGg ( ) l where:
-R = skin ~ dose to individual in age group a from shoreline skin, a
! deposits [ mrem]; (Ref.: Reg. Guide 1.109 Eq. A-7 with the special values listed for the total body dose) DFG 12 = skin dose conversion factor for ' standing on contaminated ground (shore) [(arem/hr)/(pCi/m2 )] (from Table E-6 of the Guide)- i Other parameters are as defined earlier for the total body dose from
- shoreline deposits.
-(e) Total doses The individual dose cooponents described in items (a), (b), (c), and (d) above ~ are summed in the following way fc,r the computation of total doses:
1 Rja = Ring Hsh + R "E "# ja ja ing fish ing, inv + shore bb ,a =R wb,a
+
wb,a wb,a shore l R skin,a =R skin,a [y w-l l l BN1-11600.02-92 3.1-4 Revision 3 - Decembet- 1983 s
, , - - , ,-c+.--,-.,_-,v---,- ., , -n---,---nw.--.-- . , - , , , , - , - - , , - - , . - - , , - -
SNPS-1 ODCN
~b v where:
.R,3
= total dose t'o organ .j '(exclusive of the total body) of individual . in age group a due to the ingestion of fish and -
invertebrate -(area) R wb a = total dose to the total body of individual in age group a due to the ingestion of fish and invertebrates, and direct radiation from shoreline deposits t' and.
'Rakin,a = total dose to the skin of an individual in age group a from shoreline. deposits (arem).
.3.1.2 Method . 2: (Backup Method)
The dose : contributions for the total release period shall be calculated for all radionuclides -identified in liquid effluents released to unrestricted l areas using the following expression: N M t ib 1 ^it- ib1 Atg C ig Fg) (3.1-1) D7 = the cumulative dose or dose commitment to the total body or an organ from the liquid effluents for the total release M period g{g Atg (arem), At g = the -length of the ith release period over which C1g and Fg are
' averaged for all liquid released (minutes),
Cgg = the average concentration of radionuclide C 1 in undiluted liquid effluent' during release period At g from any liquid release (pCi/cc), Ag7 = the site-related ingestion dose or dose commitment factor to the -total body or any organ for each identified principal gamma and beta emitter listed in Table 3.1-2 (mrem / min per l pCi/cc), see. Appendix A for derivation F g_ = the near field average dilution factor for C g g, during any liquid effluent release, defined as the undiluted liquid waste flow rate during release divided by the product of the circulating water flow rate times 8.85 *(N/4). (8.85 is the near field mixing factor for the mixing of the diffuser O y discharge into Long Island Sound based on 4 operating recirculating pumps. operating during discharge.) N is the number of recirculating pumps BN1-11600.02-92 3.1-5 Revision 3 - December 1983
SNPS-1 ODCM D The total dose from liquid effluents from all discharges, DTotal, is: DTotal.= DTD+DTR + DtH + D73 + D7p . where:
-D tD
= Dose contribution from discharge waste sample tanks as calculated in Equation 3.1-1 DTR = Dose contribution from recovery sample tanks as calculated in Equation 3.1-1 D
TH
=
Dose . contribution from RHR heat exchanger, service water as calculated in Equation 3.1-1 DTS =
- g. Dose contribution from reactor building salt water drain tank as calculated in Equation 3.1-1 D
ip
=
Dose contributfon from yard piping drain sump as calculated in
-Equation 3.1-1.
.If the calculated total dose exceeds the limit specified in Section 3.1, consult RETS Section 3.11.1.2.
O o BN1-11600.02-92 3.1-6 Revision 1 - August 1983
SNPS-1 ODCM - ( ,/ TABLE 3.1-1 l DECAY CONSTANTS (1/hr) Radio- Radio-nuclide Constant nuclide Constant 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-03 Te-125m 5.000E-04 Mn-54 9.252E-05 Te-127m 2.600E-04 Ma-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 Zm-65 1,184E-04 I-132 3.000E-01 Zn-69 7.296E-01 1-133 3.334E-02 Br-83 2.900E-01 1-134 7.900E-01 7s 1.300E+00 1.100E-01 1 Br-84 I-135
\- / Br 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 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 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-G4 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 ,O t 'u J BN1-11600-02-112 1 of 1 Revision 3 - December 1983
e [] (N 7 U (j SNPS-1 ODCM-TABLE 3.1-2 ADULT DOSE RATE CONVERSION FACTORS (I) ,A 17 FOR (FISH AND INVERTEBRATE) INGESTION PATHWAY (mrem / min per y Ci/cc) Nuclide Bone Liver T. Body Thyroid Kidney- Lung GI-LLI H-3 II) 4.6E-03 4.6E-03 4.6E-03 4.6E-03 4.6E-03 4.6E-03 C-14 2.4E+02 4.7E+01 4.7E+01 4.7E+01 4.7E+01 4.7E+01 4.7E+01 F-18 1.2E-05 - 1.4E-06 - - - 3.7E-07 NA-24 2.5E-03 2.5E-03 2.5E-03 2.5E-03 2.5E-03 2.5E-03 2.5E-03 P-32 2.6E+05 1.6E+04 1.0E+04 - - 3.0E+04 CR-51 - - 9.0E-02 5.3E-02 2.0E-02 1.2E-01 2.2E+01 MN-54 - 1.2E+02 2.2E+01 - 3.4E+01 - 3.5E+02 MN-56 - 4.6E-03 8.1E-04 - 5.9E-03 -
'1.4E-01 FE-55 8.3E+02 5.8E+02 1.4E+02 - -
3.2E+02- 3.3E+02 FE-59 1.3E+03 3.1E+03 1.2E+03 - - 8.6E+02 1.0E+04-CO-58 - 9.8E+00 2.2E+01 - - - 2.0E+02 i CO-60 - 2.8E+01 6.3E+01 - - - 5.4E+02 NI-63 8.1E+02 5.6E+01 2.7E+01 - - - 1.2E+01 NI-65 4.8E-03 6.2E-04 2.9E-04 - - - 1.6E-02 CU-64 - 9.6E-01 4.5E-01 - 2.4E+00 - 8.2E+01 ZN-65 2.7E+03 8.4E+03 3.8E+03 - 5.6E+03 - 5.3E+03 ZN-69M 1.7E+00 3.3E+00 2.2E-01 - 2.1E+00 - 4.9E-01 BR-83 - - 1.1E-06 - - - 1.6E-06 BR-84 - - 2.7F-17 - - - RB-86 - 9.8E+00 4.6E+00 - - - 1.9E+00 SR-89 8.lE+01 - 2.3E+00 - - - 1.3E+01 SR-90 2.0E+03 - 5.0E+02 - - - 5.8E+01 SR-91 2.6E-01 - 1.0E-02 - - - 1.2E+00 SR-92 1.2E-03 - 5.3E-05 - - - 2.4E-02 i Y-90 7.6E-02 - 2.lE-03 - - - 8.2E+02 Y-91M 1.9E-12 - 7.2E-14 - - - 5.4E-12 Y-91 1.4E+00 - 3.9E-02 - - - 8.0E+02 Y-92 7.9E-05 - 2.3E-06 - - - 1.4E+00 Y-93 5.4E-03 - 1.5E-04 - - - 1.8E+02 ZR-95 2.6E-01 8.3E-02 5.6E-02 - 1.3E-01 - 2.6E+02 1 BN1-11600-116 1 of 3 Revision 3 - Ihoenber 1983 i
- g-
~ . . . - . . , _ . . , .- -. . . - - - . . - - . . ~ . , ~ - .
e ' o SNPS-1.ODCM d'- ,
. TABLE 3.1-2 (' CONT'D)
Nuclide Bone ' Liver T. Body Thyroid- Kidney M GI-LLI ZR-97: 5.4E-03' 1.1E-03 4.9E-04 -- 1.6E-03 , ;- 3.4E+02 -! NB-95 '7.2E+00 4.0E+00 2.1E+00 ~- '4.0E+00 -
'2.4E+04 MO-99 ' --
1.6E+00 3.1E-01 - 3.7E+00. - 3.8E+00 TC-99M .1.3E-05 3.8E-05 4.8E-04 -
'5.7E 1.8E-05 ,2.2E RU-103- 1.7E+00 ' -
7.4E-01 - 6.6E+00 - 2.0E+02 RU-105 3.4E-03 - 1.3E-03 '
.~ 4.5E-02 -'
2.1E+00 RU-106 2.6E+01 - 3.2E+00' - 5.1E+01 - 1.7E+03 AG-110M 2.6E+01 2.4E+01 1.4E+01- - 4.7E+01. - 9.7E+03-SB-124 4.5E+00 8.5E-02 -1.8E+00 1.1E-02 - 3.5E+00 -1.2E+02 , TE-125M 3.5E+00 1.3E+00 4.7E-01 1.0E+00 1.4E+01' - 1.4E+01 TE-127M 8.9E+00 '3.1E+00 1.1E+00 2.3E+00 3.7E+01 -
.3.0E+01 TE-127 2.5E-02 8.9E-03 5.4E-03 1.8E-02 1.0E-01 --
.2.0E+00 TE-129M 1.5E+01 5.6E+00 2.4E+00 '5.1E+00- 6.2E+01 -
7.5E+01' TE-129 2.7E-08 1.0E-08 6.5E-09 2.1E-08 11.1E-07. - 2.0E-08 TE-131M 1.3E+00 6.4E-01 5.4E-01 1.0E+00 6.5E+00 . 6.4E+01 TE-131 1.3E-19 5.4E-20 4.1E-20 1.1E-19 5.7E-19 - 1.9E-20 TE-132 2.7E+00 1.7E+00 1.7E+00 2.0E+00 1.7E+01 - 8.2E+01 I-130 1.7E-01 5.0E-01 2.0E 4.2E+01 7.9E-01 - 4.4E-01 I-131 3.3E+00 4.7E+00 2.7E+00 1.5E+03 8.1E+00 .- 1.2E+00! I-132 1.2E-04 3.3E-04 1.1E-04 1.1E-02 5.2E-04 - 6.1E-05. I-133 5.5E-01 9.6E-01 2.9E-01 1.4E+02 1.7E+00 - 8.6E-01 I-134 5.1E-10 1.4E-09 4.9E-10 '2.4E-08 2.2E-09 - 1.2E-12 1-135 3.1E-02 8.1E-02 3.0E-02 5.3E+00 1.3E-01 - 9.0E-02 CS-134 1.1E+02 2.7E+02 2.2E+02 - ' 8.6E+01 2.9E+01 14.7E+00' i CS-136 1.1E+01 4.4E+01 3.2E+01 - 2.4E+01 3.3E+00 5.0E+00 CS-137 1.5E+02 2.0E+02 1.3E+02 - 6.7E+01. 2.2E+01 3.8E+00 CS-138 3.6E-15 7.0E-15 -3.4E-15 - 5.2E-15 5.2E-16 3.0E-20 i BA-139 8.1E-07 5.8E-10 2.4E-08 - 5.4E-10 3.3E 1.4E-06 BA-140 2.6E+01 3.2E-02 1.7E+00 - 1.1E-02 1.8E 5.3E+01 i LA-140 1.7E-02 8.6E-03 2.3E-03 - - - 6.3E+02. LA-142 2.7E-08 1.2E-08 3.1E-09 - - - 8.9E-05 CE-141 5.5E-02 3.7E-02 4.2E-03 - 1.7E-02 -
'1.4E+02 CE-143 6.0E-03 4.4E+00 4.9E-04 -
1.9E-03 -- 1.6E+02 CE-144 2.9E+00 1.2E+00 1.6E-01 - 7.3E-01 - 9.9E+02 l PR-143 9.1E-02 3.6E-02 .4.5E-03 - 2.1E-02 - 4.0E+02 l BN1-11600>-116 2 of 3 Revision 3 - Ihcember 1983 -
O O b SNPS-l'ODCM TABLE.3.1-2 (CONT'D) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI ND-147 6.IE-02 7.1E-02 4.2E-03 - 4.1E-02 - 3.4E+02 U-187 7.5E-02 6.3E-02 2.2E-02 - - - 2.1E+01 NP-239 4.3E-04 4.2E-05 2.3E-05 - 1.3E-04 - 8.7E+00 (1) The dash (-) indicates insufficient data or that the dose factor is < 1.0E-20. l l BN1-11600-116 3 of 3 Revision 3 -Iheeder 1983
,r~~ _[ \ [~
k s L0NG /SLAND S00NO ,
a
qrdz 4 ,- ,,,,......
" )
. #(' ,
--t:::'t.:::Will 4
- j L d
=- i
,r2 h I \
'?"".'$?~~A; ye ((.
j k ' ( l
-A4 ;
f sTnbfCes ; .
' ""' k 0,L Ja"MT,,:e 5 -- ~
_. ha '
'. ' f '1b '/;-peti?)C
- 7!Ihc "-
t- -
\ N"}{(A.d198QFM:,k x
j'g pjy Qg h - g w-
~\ _
~
/j//ll f
/ L q
i ,a 1 3 se x
}.,)E -
/ ,/ P C .;
,,7 g / i va
} \ ,
. .//
ll ( I ( r- . , [}/ #
% ,-<c I e o FIGURE 3.1-1 / [S,,/'[<r -
I
.4".:
y' SITE BOUNDARY FOR LIQUID EFFLUENTS
/ '/ '
e
"[ '
? ia ? ** "" SHOREHAM NUCLEAR POWER STATION-UNIT 1
= a" OFFSITE DOSE CALCULATION MANUAL h n /> $ >
REVISION 1-AUGUST 1983
FLOOR DRAIN __ FLOOR DR AIN COLLECTOR TANK FlLTER CIRCULATING WATER SYSTEM lI WASTE I DI S CH ARGE EVAPORATOR WASTE TANK If i f WASTE RADWASTE RECOVERY i f COLLECTOR L DEMINERAllZER/ + SAMPLE - -> TANK FILTER TANK JL JL JL YARD PIPING DR AIN SUMP REGENERANT EVA POR ATOR RESIDUAL HEAT REMOVAL SYSTEM REACTOR BUILDING SALT WATER 5 DRAIN TANK 1 f TO DIFFUSER FIGURE 3.1-2 LIQUID RADWASTE SYSTEM MODEL 9 SHOREHAM NUCLEAR POWER STATION-UNIT 1 0FFSITE DOSE CALCULATION MANUAL REVISION 1-AUGUST 1983
SNPS-1 ODCM
' fi b
3.2 OPERATION OF LIOUID WASTE TREATMENT SUBSYSTEMS The dose projection analysis will be performed using the methodology described in Section 3.1 with the exception that ,the calculated doses vill be compared with the limits specified in RETS Section 3.11.1.3. The liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system _ shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent to UNRESTRICTED AREAS would exceed 0.06 arem to the total body or 0.2 mrem to any organs in a 31-day period. Liquid radwaste treatment subsystems are shown on Figure 3.2-1. ( )' e 4 BN1-11600.02-92 3.2-1 Revision 1 - August 1983
v FLOOR DRAIN _ FLOOR ORAIN COLLECTOR TANK FILTER I I WASTE I DI S C H ARGE EVAPORATOR WASTE TANK I f I f
\
% WASTE RADWASTE RECOVERY COLLECTOR = DEMINERALIZER/ + SAMPL E TANK FI LT E R TANK Il J l I f To OlFF U SER REGENERANT EVA POR ATOR FIGURE 3.2-1 D LIQUID RADWASTE TREATMENT C) SYSTEM SHOREHAM NUCLEAR POWER STAT lON UNIT 1 OFFSITE DOSE CALCULATION MANUAL REVISION 1- AUGUST 1983l
SNPS-1 ODCM t L < U 3.3 EDOSE RATE DUE TO GASEOUS EFFLUENTS b : 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
- f. duct shall.be limited to the following values:
l- 1. _For. noble gases: Less than or equal to 500 mrea/yr to the total body and less than or ' equal to 3000 arem/yr to the skin, and
- 2. ' For' I-131, I-133, tritium, and for all radionuclides in particulate form with half lives .igreater than 8 days: Less than or equal to
~1500 area /yr to any organ.
The gaseous effluent model is shown in Figure 3.3-1. 3.3.1 Method 1: (Computerized Method)
~
3.3.1.1 Release Rate Estimation
' Dose rate estimation . is ~ carried out every 15 minutes by making use of a atmospheric dispersion- data computed every hour, and of the following equation for the release rate'(Ci/hr):
O where: Og = F* E g l F'=' 4k F,(j) U (j ) At l f t = 10-0 qi (t) /U ng (}
~k = 2.832 x 104 (cc/ft3 )
F,(j) = vent flow during time interval j (cfm) bng (j ) = n ble gas effluent monitor count rate during tine interval j (cpa). At- = time interval (=1 minute) qi = concentration of isotope i in the effluent as measured in the lab at time T (pCi/cc) F' = 15-ininute average of the flow and countrate product (for l dose rate estimation every 15 minutes) assumed to apply for a 60-minute interval [(cc/hr) (cpm)] 4 x 15 = number of At intervals per hour (1/hr) BN1-11600.02-92 3.3-1 Revision 3 - December 1983
SNPS-1 ODCN-3.3.1.2 Total Body' Dose Rate Sb. .=D '+ Di "h -+ D b
'where: i D
= (X/0) ** F 2.22 x 10 nobles i i !
D = (X/Q) F 3.17 x 10 Rad paht+I i ^1j,ad ! DE "" = (D/0) F 7 x 10"p jrt+I fi DFGgy[1-e" b i]/ Ag l
-D = total -body dose due to direct radiation from the radioactive cloud [mres/hr] (Ref.: Reg. Guide 1.109 Eq.
B-8; also similar to Eq. B-6 if one use of the gassa (X/Q) and the DFB instead of DF ykes dose conversion " f f factor) D = total body dose (j = total body) due to inhalation [mrea/hr] (Ref.: Reg. Guide 1.109, Eqs . C-3 and C-4, for an adult) V (and = total body radioactivity depositing on the ground [ mrem /hr] (Ref.: dose due to particulate and iodine Reg. Guide 1.109, Eqs. C-1 and C-2 with the product 8760 [hr/yr] (1/ A g) [yr] replaced by (1/ A ) [hr] and parameter 6f (r,0) represented by the (D/0)). 1 DFB f = gamma dose to body conversion factor [(arem/yr)/(pCi/m3 )] (from Table B-1 of the guide) DFA ij,ad " dose conversion factor for nuclide i to organ j of an adult individual-' [ mrem /pCi inhaled] (from Tables E-7 through E-10 of Reg. Guide 1.109) DFGgy
=totalbodyconversionfagtorforstandingoncontaminated ground [(area /hr)/(pCi/m )] (from Table E-g of Reg. Guide 1.109)
(x/Q)sa
= concentration dispersion factor (sector-average mogel) for the period of release (site boundary only) (sec/m )
(x/0)** Y = gamma (X/0) (finite cloud sector-average modyl) for the period of release (site boundary only) (sec/m ) (D/0) = particulate deposition rate (site boundary only) (1/m2) F' f t =Qg (C1/hr) (as defined in Section 3.3.1.1) l BN1-11600.02-92 3.3-2 Revision 3 - December 1983
SNPS-1 ODCM .p V R ad = adult breathing rate (m3 /yr) (from Table E-5 of the.
, Guide)
A 1
= radionuclide decay constant (hr-1) t = time period over which the is evaluated, b accugulation which is 15 years (1.314 x 10 hours) (Reg. Guide pg 1.109-24) 3.17x10 0 = 10 12/ (8760 x 3600) [(pci/C1) (yr/sec)]
2.2x10 4 = 3.17 x 104 x 0.7, where 0.7 is the shielding factor which accounts for the dose reduction due to the shielding effects of residential structures during occupancy (Ref.: Reg. Guide 1.109 Table E-15) 7x10 11 = 10 12 x 0.7, where 0.7 is the shielding factor and 10 12 1, the number of pCi per Ci (see Eqs. C-1 and C-2 of the guide) part+I = 68 particulates and 5 iodines in the summation sign 3.3.1.3 Skin Dose Rate /^N DE# "" v) + Dskin = D ( skin skin where: D = 1.11 x 0.7 (X/0) F 3.17 x 10 ,,(1,, ft DF g l
+ (x/Q)sa F 3.17 x 10 nkbles f iDFSg l
(" = (D/Q) F 7 x 10"p {rt+1 fi DFGi2 [1 - e b 1]/ Ag l D"s kin
= skin dose due to direct gamma tadiation from the radioactive cloud (first component of the equation with finite cloud modeling) and beta radiation (second component, semi-infinite cloud immersion) [ mrem /hr]
(Ref.: Reg. Guide 1.109 Eq. B-9; also similar to Eq. B-7 if one makes use of the gamma (X/0)) D8round = skin dose' due to particulate and iodine radioactivity depositing on the ground [ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs. C-1 and C-2 with the product 8760 [hr/yr] (1/A1 ) [yr] replaced by (1/ A [hr] and parameter 6 (r,0) represented by the (D/Q))g) 1 U DF{ = gamma dose to air conversion factor [(mrad /yr)/(pCi/m3 )j (from Table B-1 of the Guide) BN1-11600.02-92 3.3-3 Revision 3 - December 1983
SNPS-1 ODCM i
! I
" '%J ' DFS g = beta dose to skin , conversion factor- [(area /yr)/(pCi/m3 )j . (from Table B-1 of the Guide). DFG i2 = skin dose conversion fagtor for standing on contaminated ground [(arem/hr)/(pCi/m )] (from Table E-6 of Reg. Guide . 1.109) 1.11 = average ratio of tissue' to air energy absorption coefficient (from Reg. Guide 1.109, pg 1.109-6) 0.7 - shielding dose-reduction factor (see pg 1.109-68 of the
- Guide)
A-t = radionuclide decay constant [hr-1]
- 3. 3.1.4
~
Organ Dose ' Rate (I-131, I-133, Tritium and Particulate Release) l D =-(X/Q**F 3.17 x 10 R,) g g f DFA l
~w here:
D d*' = dose to organ j of individual in age group a due to inhalation of airborne radioactivity -[ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs. C-3 rci.1 C-4.)
= dose conversion factor for- nuclide i to organ j of DFA g ),
individual in age group a [ mrem /pCi inhaled] (from Tables E-7 through E-10 of the Guide) R, = breathing rate of individual in age group a [m3 /yr] (from
-Table E-5 of Reg. Guide 1.109, for the maximum- -i individuals).
The analysis is limited to the computation of the thyroid dose to a child at l the site boundary in the downwind sector for the period of the release (i.e., j = thyroid, a = child). l 4 1-O 1-I BN1-11600.02-92 3.3-4 Revision 3 - December 1983
SNPS-1 ODCM O V 3.3.2 Method 2: (Backup Method) 3.3.2.1 Noble Cas Total Body Dose Rate I Irr, = 0.7
- x/03 * [ [DFBg *(Cgy *V 3
-C 12
*Y 2
-C g3 *V))
3
+ 0.7
- V2-
- X/02-*{[DFBg *Ci2]
+ 0.7
- V3
- X/0 3 *{[DFBi
*C i3 I ("#*"II#)
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, = 0.7
- Vg
- X/0 *{[DFBg *Cg]
1 (arem/yr) where: DT, = total body dose rate from all radionuclides releases (arem/yr), DFB 1 = the total body dose rate factor due to gamma emisgions for each identified noble gas radionuclide (mres/yr per pCi/m ) m (Table 2.2-1), Cgg = the station ventilation exhaust duct release concentration of radionuclide, i, (pci/cc) (from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor), C i2
= 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 e ntainment drywell purge ventilation exhaust concentration of 13 radionuclide, i, (pCi/cc) (from the isotopic analyses performed on the gaseous sample taken from the containment drywell filter train exhaust monitor),
.Vi = 1.73E+08 cc/sec (3.66E+05 cfm), station ventilation exhaust duct l ventilation exhaust flow rate, V
2 = 5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct ventilation exhaust flow rate, V 3 = 5.70E+05 cc/sec (1200 cfm), containment drywell purge ventilation exhaust flow rate, BN1-11600.02-92 3.3-5 Revision 3 - December 1983
SNPS-1 ODCM i X/01 . - annual average X/0 at 366 meters NNE due to release da the station ventilation exhaust point (6.6E-07 sec/m3 ), X/0 2 l
=.via short the-station tern X/O at 366 meters ventilation exhaust NNE point due to airsec/m (3.6E-06 removal puy) release X/Q3 = short tern X/0 at 366 meters NNE due to containment drygell purge l via the station ventilation exhaust point (3.6E-06 sec/m ).
0.70 = shielding factor that accounts for dose reduction due to shielding from residential' structures.
- 3.3.2.2 Noble Cas Skin Dose Rate DS, = x/Qg *{(K *(C g *V -C 12
*V 2
-C i3 3}
+V 2 *X/0[*((K *C ]+V 3* X/03* [ ( K,i *C i3)(arem/yr)
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,=V{*x/01
- f *si
- 11 (*#*" Y#
where: DS, = skin dose rate from all radionuclides released (mrem /yr), si- = the . skin dose factor due to beta and gamma emissions gor each identified noble gas radionuclide (arem/yr per pCi/m ) from Table 2.2-1, C ig =.the station ventilation exhaust duct release concentration of radionuclide, i, (pCi/cc) (from isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor), Ci2 = 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 13 = 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), Vg = 1.73E+08 cc/sec (3.66E+05 cfm), station ventilation exhaust duct O ventilation exhaust flow rate, l BN1-11600.02-92 3.3-6 Revision 3 - December 1983
SNPS-1 ODCM l-O V 2
= 5.70E+05 cc/sec- (1200 cfm), air removal pump exhaust duct ventilation exhaust flow rate, V
3
- 5.70E+05 cc/sec (1200 cfa), containment drywell purge ventilation
-exhaust flow rate, X/Qg = annual' average X/Q at 366 meters NNE due to 3 release via the station' ventilation exhaust point (6.6E-07 sec/m ),
-X/Q2 = short term X/Q at 366 meters NNE due l via the station ventilation exhaust point to air removal (3.6E-06 puy) release sec/m ,
.X/Q3 = short tern X/Q at 366 metersfNNE due to containment dr l via the station ventilation exhaust point (3.6E-06 sec/mgell ). purge 3.3.2.3 Organ Dose Rate (Particulate Releases) 6 D,j.=I(10*R,*P *X/0 *(Cg 1 Vg -C 12 2 -C g3 3V)
V 0
+ V2 *Ig (10 *Rf *Pg .*X/Q 2 *C 12
+-V
- 3 (100 *Ra
- ij *X! 3 13 ("#** I#}
\ During . periods of no intermittent releases, such as . no main condenser air removal . pump operation and no containment drywell purgo, the above formula reduces 'to the following:
' D, = Vy
- I ' 10
- R,
- P
- x/Q g *C gg (mrem /yd where:
D,3 = total dose rate to organ, j, mrem /yr. P ij = the inhalation dose conversion factor, for radionuclides other than noble gases, i, and organ, j, in mrem per pCi from Table 3.5-3. The dose factor P is based on the critical individual organ for the Child group, bich is most restrictive. R, = inhalation rate (m 3/yr), from Table 3.5-5. Cgg = the station ventilation exhaust duct release concentration of radionuclide, i, (pCi/cc) (from the isotopic analyses performed on the filter paper and charcoal cartridge taken from the station
. ventilation exhaust monitor),
v e BN1-11600.02-92 3.3-7 Revision 3 - December 1983
SNPS-1 ODCM n V removal C 12 = the . air pump ventilation exhaust duct release concentration of radionuclide, i, (pC1/cc) (from the isotopic analyses performed on the iodine and filter cartridge taken from the' air removal pump discharge monitor), C 13 = the containment drywell purge ventilation exhaust concentration of radionuclide, i. (pCi/ce) (from the isotopic analyses performed on the gaseous sample taken from the containment drywell filter train exhaust monitor), V i
= 1.70E+08 cc/sec - (3.60E+05 cfm), station ventilation exhaust duct ventilation exhaust flow rate, V2 = 5.70E+05 cc/sec (1200 cfm) ,- air removal pump exhaust duct ventilation exhaust flow rate, V
3 = 5.70E+05 cc/sec (1200 cfm), containnent drywell purge ventilation exhaust flow rate, X/0 1 = annual average X/Q at 2478 meters ESE due to geleases via the station ventilation exhaust point (1.54E-07 sec/m ), X/Q2 = short term X/Q at 2478 meters ESE due to condenser air removal the station ventilation exhaust point (4.22E-07 pump sec/m g)elease via X/Q 3 = short term X/Q at 2478 meters ESE due to containment drywgli purge via the station ventilation exhaust point (4.22E-07 sec/m ). i l-D l l [ BN1-ll600.02-92 3.3-8 Revision 3 - December 1983
[ D Y SACRIFPCIAL AOSORGER CHARCOAL AOSORSERS 2 $TAGE AIR EJECTOR $ boENEa3 - g g I g F M ) ! w w - l pREHEATERS ) DESUPEmHEATEg COOLER CONDENSERS CONDEN$ER$ pyg,g REcomemERS SEP A 3 OFF. GAS SYSTEk PREFILTE R FAN gg,
' ' ~ ~
W REACTOR 9ulLDING r- , l ORT ELL ANo uPPREssioM y _
. l o = <ricas
'A 5 I
,RI., ART Co,lT.AIN.ENT a i URGE .T TE . AT os. To RufA.EERE l
--+
L-_-____ h 5 h h ' a I l FAN FAN PREFILTER FAN NORMAL VENTILATION TumelNE BUILDING 1 r p - T R. E lL. WECMANsC AL VACUUW POMP E FFL UENT MECMANICAL VACUUW PUMP l l NEPA PREFILTER FAN FILTER FAN
; ; W RA0 WASTE BulLDING W 1
l l l FIGURE 3.3-1 GASEOUS EFFLUENT MODEL SHOREHAM NUCLEAR POWER STATION-UNIT I . OFFSITE DOSE CALCULATION MANUAL l
.e REVISION 1- AUGUST 1983 -
SNPS-1 ODCM
.W 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: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation. J 2. During any calendar year: less than or equal - to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation. 3.4.1. Method 1: (Computerized Method) Cumulative doses are calculated by making use of hourly' dose rate equations ' presented in the following subsections. 3.4.1.1 Release Estimation Dose estimation is carried out every hour by making use of the atmospheric dispersion data computed every hour, and of the following equation for the release rate (Ci/hr): Og = F' f g l
\/ where:
60 F' =k I F (j) 0 (j) At 8 ng l j=1 f f
= 10 q1 (t) / Dng ( }
4 k = 2.832 x 104 (cc/ft3) Fs (j ) = vent flow rate during interval j (cfm) dng(j ) = noble gas effluent monitor count rt.te during interval j (ep ) At = time-interval (= 1 minute) qi = concentration of isotope i in the effluent as measured in i the lab at time t (pCi/cc) F' = 60-minute average of the flow and count-rata product l {(cc/hr) (cpm)] 60 = number of at intervals per hour (1/hr) O V
.BN1-11600.02-92 3.4-1 Revisiot 't - December 1983
SNFS-1 ODCM 'uJ 3.4.1.2 : Noble Gas Gamma Air Dose DY , air = (X/0)*8 7 F 3.17 x 10 .E f gDF{ l nobles
-a where DY , air = gamma dose to air . at the site boundary in the downwind sector during the period of release (mrad /hr) (Ref.: Reg.
Guide 1.109, Eqs. B-4 and B-5, and also Eq. B-1 with the substitution of (X/0)y (X/0)** 7 = finite-cloud sector-average ' gaga' dilution factor at the downwind site-boundary [sec/m ] DF . = gamma dose to air conversion factgr (from Table B-1 of Reg. Guide 1.109) [(mrad /yr)/(pCi/m )] F'f g = Og (Ci/hr) (see Section 3.4.1.1) l 3.4.1.3 Noble Gas Beta Air Dose DS , air " (X/Q) F 3.17 x 10 E fg DF l
%) nobles where DS , air = beta dose to air at the site boundary in the downwind sector during the period of release [ mrad /hr] (Ref.: Reg.
Guide 1.109, Eqs. B-4 and B-5) DF'
= beta dose to air conversion fact (from Table B-1 of Reg. Guide 1.109) [(mrad /yr)/(pCi/m )]
F'f g =. Og (C1/hr) (see Section 3.4.1.1) l (X/Q)88 = sector-average concentration dilution factor at the site boundary during the period of release [eec/m )3 O V BN1-11600.02-92 3.4-2 Revision 3 - December 1983
SNPS-1 ODCM 'O ' X_) (Backup Method) 3.4.2 Method 2: 3.4.2.1 Noble Gas Camma Air Dose The general equation is:
*{[M g *(Cg V1 t g -C g 2V2 t i3 Y3* ))
Dg -C s
= 3.17E-08 *X/Q g
+ 3.17E-08 *V 2 *t 2 *X/Q2 *k (Mi*C 2]
+ 3.17E-08 *V 3 **3
- X/03* [ bM i* Cg3 ) (mrad)
During periods of no ir*.ermittent releases, such as no main condenser air removal pump operation and no containment drywell purge, the above formula reduces to the following: Dg = 3.17E-08 *V 1 *t i *X/Qg*E[M i g
*Cig] _ (mrad) s where:
Dg = the total gamma air dose from the releases (mrad), a 3.17E-08 = the inverse of number of seconds in a year, I i ch
%Y Mg = the air dose factor due to gamma emissions for eagh identified noble gas radionuclide (mrad /yr per pCi/m )
from Table 3.4-1, tg = 7.88E+06 see for quarterly dose calculation,
= 3.15E+07 see for yearly dose calculation t
2 = release period (sec) for ' condenser air removal pump t 3 = release period (sec) for containment drywell purge i exhaust ' C ig = the station ventilation exhaust duct release concentration of radionuclide, i, (pCi/ce) (from the isotopic analyses performed on the gaseous sample taken from the station ventilation exhaust monitor), l C 12 = 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 13 = the containment drywell purge ventilation exhaust concentration of radionuclide, i, (pCi/cc) (from the O isotopic analyses performed on the gaseous sample taken h from monitor),
the containment drywell filter train exhaust BN1-11600.02-92 3.4-3 Revision 3 - December 1983
. -. . . . . - . .. . . - . - -- __ ._- . ~
4 SNPS-1 ODCM < O V 3
= 1.73E+08 cc/sec .(3.66E+05 cfa), .
station ventilation l !, exhaust duct ventilation' exhaust' flow rate, V- 2 - 5.70E405 cc/sec (1200 cfa), air'. removal pump exhaust duct ventilation exhaust flow rate,
-V 3 -= 5.70E+05 cc/sec (1200 cfm), containment. drywell purge _
. ventilation exhaust flow rate, .
X/Qg -= annual average X/Q at- 457 metera ESE ' due to release via
. the station ventilation exhaust point (8.44E-07 sec/m3 ),
= short tera - X/Q at 457 meters ESE due to condenser air X/Q 2 l removal pump release via the station ventilation exhaust point (1.83E-06 sec/m ),
X/Q 3 = short term X/Q at- 457 meters ESE due - to containment- l drywell purge release via the station ventilation exhaust release point (1.83E-06 sec/m ). . 3.4.2.2 Noble Gas Beta Air Dose,- j- The. general equation is: D3 -= 3.17E-08
- X/0g *E (N *(C g g1Vt -CgV2 t3 -
C g3V3t3} , .V a 1- , i
+ 3.17E-08
- X/0 2 *Y 2 **2
- I (N *C g) i
- + 3.17E-08,* X/0 3 *V3 *t g *C (*#8d}
3*i. I (N i3
- During periods of no intermittent releases, such as no main condenser air
. removal . pump- operation and no containment drywell purge, the above formula i reduces to the following:
D B
= .
-08 *X/Qg*V i *t g I [Ng *Cfg) (mrad) s i ,
- where:
f L DB'S = beta air dose from all radionuclides released (mrad), Ng
= identified the air dose factor due to beta emissions for eagh noble gas radionuclide (mrad /yr per pCi/m )
from Table 3.4-1, 3.17E-08 = the inverse of number of seconds in a year, i I f P BN1-11600.02-92 3.4-4 Revision 3 - December 1983 y ,p,ymr-w-.-wv-ve,--peey-tv--.< -T,,,,v-e e--e we r- w , we+ m y wr- ee- e+,,, g re? r- eve --*mm--w t rwvo wee w w e w- ww -w-+me-**'v=*==vv-w"---'"+v '*'"-v'
v l SNPS-1 ODCM i t0 V tg = 7.88E+06 see for quarterly dose calculation,
; =
3.15E+07 see for yearly 6ae calculation, t = release period (sec) for 2 'er air removal pump, t 3
= release period (see' inment drywell purge exhuast, Cgg = the- station xhaust duct release concentration , i, ( pCi/cc) (from the isotopic analyse.. tris -o un the gaseous sample taken from the station ,,atilation exhaust monitor),
C12 = the air removal pump ventilation exhaust duct release concentration of radionuclide, i, (ifi/cc) (from the isotopic analyses performed on the gaseous sample taken from the air removal pump discharge monitor), C13 = the containment drywell purge ventilation exhaust concentration of radionuclide, i, (pCi/cc) (from the isotopic analysis performed on the gaseous sample taken from the containment drywell filter train exhaust monitor), V i
= 1.73E+08 cc/sec- (3.66E+05 cfm), station ventilation l exhaust duct ventilation exhaust flow rate, V
2
=
5.70E+05 cc/sec (1200 cfm), air removal pump exhaust duct
, ventilation exhaust flow rate, V3 =
5.70E+05 cc/sec 1200 cfm), containment drywell purge
', ventilationexhaus(tflowrate, e
X/Q1
=
annual average X/Q at 457 meters ESE due to release via the station ventilation exhaust point (8.44E-07 sec/m ),
=
X/Q 2 short term X/Q at 457 meters ESE due to condenser air l removal pump release via the station ventilation exhaust point (1.83-06 sec/m3), and X/Q 3 = short term X/0 at 457 meters ESE due to containment l drywell purge releas via the station ventilation exhaust [. /: point (1.83E-06 sec/n 3). O V l B,N1-11600.02-92 3.4-5 Revision 3 - December 1983
y[
- x. '/e.
u' .. rg
- !. .,,I^f SNPS-1 ODCM
,f..%ik lQ;x ', ~
ea .
\ -
'_ - TABLE 3.4-1
,[ , NOBLE CAS DOSE FACTORS m * 'g-
' '. Gamma Air Beta Air
'.j Dose Factor Dose Factor 4 p g Ng
'/ Q Isotope (arad/yr per Wi/m 3) (arad/yr per Wi/m 3)
' h .O .u
,! - (4 <y.IV r-Kr .83m' 1.9E+01 2.9E+02 s ;j z i
g6 ~ *i' Kr - 85m 1.2E+03 2.0E+03 k' ' Kr-- 85 1.7E+01 2.0E+03 ..y Kr - 87 6.2E+03 1.0E+04 Y" -:'pyn ; w .Kr. 1.5E+04 2.9E+03 Q ~N 'z T u' ' Kr - 89 1.7E+04 1.1E+04
- o.V -
l 9 Kr-90) 1.6E+04 7.8E+03 l -t ! JN,h,Xe*-131m 1.6E+02 1.1E+03
.e y .
T Xe - 133m 3.3E+02 1.5E+03 Xe - 133 3.5E+02 1.1E+03 Xe - 135m 3.4E+03 7.4E+02 (e Xe - 135 R i-
- r. 1.9E+03 2.5E+03
>1 : -% ?
"i 7 ~' Xe - 137 1.5E+03 1.3E+02
'%./ .Xef- 138 9.2E+03 4.8E+03
, y *x '
- ESA
. Ar - 41 9.3E+03 3.3E+03
- df !. >
i,
.an s
((S: ) .i h g ';w;, 1(Yo'- k. y lll k i I- \. 8 t i BN1-11600.02-112 1 of 1 Revision 1 - August 1983 l s% -
SNPS-1 ODCM l O 3.5 GASEOUS EFFLUENTS, DOSE DUE TO RADIO 10 DINES 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 via the station ventilation exhaust point shall be limited to the following:
- 1. During any calendar quarter: Less than or equal to 7.3 mrem to any organ, and
- 2. During any calendar year: Less than or equal to 15 mrem to any organ.
3.5.1 Method 1: (Computerized Method) Cumulative doses are calculated by making use of hourly dose rate equations presented in the following subsections. 3.5.1.1 Release Estimation Dose estimation is carried out every hour by making use of the atmospheric dispersion data computed every hour, and of the following equation for the release rate (Ci/hr): Q1 = F' f l i where: 60 P' =k I F (j ) d (j ) At ng l j=1 s
-6 f
t
= 10 q (T) 7 g ( T) k = 2.832 x 104 (cc/ft3)
Fs (j) = vent flow rate during interval j (cfm) U (j) = noble gas effluent monitor count rate during interval ng j (cpm) At = time interval (= 1 minute) qi = concentration of isotope i in the effluent as measured in the lab at time T ( $1/cc) F' = 60-minute average of the flow and count-rate product l [(cc/hr) (cpm)] 60 = number of at intervals per hour (1/hr) BN1-11600.02-112 3.5-1 Revision 3 - December 1983
SNPS-1 ODCM
/ 3.5.1.2 Total Body Dose
=D nd + Ih +
Dwb D "b D,gr , und where: 1 eloud , g q)say F' 2.22 x 10 D E f DFB l wb 1 1 nobles ih q)sa F' 3.17 x 10' Rg E f DFA l D "b part+I l-Dgrund = (D/Q) F' 7 x 10 E
~
l wb part+I f IDFG11 [1 - e b1]/Ai D elad
= total body dose due to direct radiation from the wb radioactive cloud [ ares /hr] (Ref.: Reg. Guide 1.109 Eq . B-8; also similar to Eq . B-6 if one makes goe of the gamma (X/Q) and the DFB t instead of DF ' dose conversion factor) ih D "b " # W d* U" # W d"" ***
[arem/hr] (Ref.: Reg. Guide 1.109, Eqs . C-3 and C-4, for an adult) ("" = total body dose due to particulate and iodine radioactivity depositing on the ground [ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs. C-1 and C-2 with the product 8760 [hr/yr] (1/ A [yr] replaced by [1/ A ihr] and parameter 16 (r 0)g) represented by the (D/Q)g) ) DFB t
= gamma dose to body conversion factor 3
[(arem/yr)/(pCi/m )] (from Table B-1 of the Reg. Guide) DFA = d se conversion factor for nuclida i to organ j of an ij,ad adult individual [ mrem /pci inhaled] (from Tables E-7 through E-10 of Reg. Guide 1.109) DFG it
= total body conversion factor for standing on 2
contaminated ground [(mrem /hr)/(pCi/m )] (from Table E-6 of Reg. Guide 1.109) (X/Q)88 = concentration dispersion factor (sector-average f model)3)or (sec/m the period of' release (site boundary only) O v Bijl-11600.02-112 3.5-2 Revision 3 - December 1983
SNPS-1 ODCM (x/Q)saT " gamma (x/Q) (finite cloud sector-average model) 3for f] the period of release (site boundary only) (sec/m ) L) (D/Q) =part{culate deposition rate (site boundary only) (1/m ) F' f t = Qg (Ci/hr) (as defined in Section 3.5.1.1) l R ad
= adult breathing rate (m /yr) (from Table E-5)
Ig = radionuclide decay constant (1/hr) t b "timeperiodoverwhichtheaccymulationisevaluated, which is 15 years (1.314 x 10 hours) (Reg. Guide pg 1.109-24) 3.17x10 0 = 10 12/ (8760 x 3600) [(pCi/Ci) (yr/sec)] 2.22x10 4 - 3.17 x 104 x 0.7, where 0.7 is the shielding f actor which accounts for the dose reduction due to the shielding effects of residential structures during occupancy (Ref.: Reg. Guide 1.109 Table E-15) 7x10 ll = 10 12 x 0.7, where 0.7 is the shielding f actor and 12 is the number of pCi per C1 (see Eqs. C-1 and C-10 2 of the guide) y~ ! ) part+I = 68 particulates and 5 iodines in the summation sign Note that the total ' total body' dose as computed above is used only for hourly assessment of plar. operation within the specification limits. The reports prepared by the dose software include the total body dose due to inhalation as a separate parameter. Also note that the equation conservatively includes the dose due to the airborne noble gases, even though this section addresses only the iodines and particulates. 3.5.1.3 Skin Dose D =D eloud + D 8round skin skin skin where: D eloud = I f DF Ti l skin 1.11 x 0.7 (x/Q)*Y* F' 3.17 x 10 nobles i i 1
+ (X/Q)88 F' 3.17 x 10' E f DFS l nobles l L.)
BN1-11600.02-112 3.5-3 Revision 3 - December 1983
SNPS-1 ODCM {nd - (D/Q) F' 7 x 10 ll I part+1 f DFG 2[1 - e bi]/Ag l D eloud
= skin dose due to direct gamma radiation from the sMn radio.ctive cloud (first compotient of the equation with finite cloud modeling) and beta radiation (second component, semi-infinite cloud immersion)
[ mrem /hr] (Ref.: Reg. Guide 1.109 Eq. B-9; also similar to Eq . B-7 if one makes use of the gamma (y/Q)) DE# "" = skin dose due to particulate and iodine radioactivity skin depositing on the ground [ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs. C-1 and C-2 with the product 8760[hr/yr] (1/At )[yr] replaced by (1/ A )[hr] and parameter 6 t 1 (r,0) represented by the (D/Q)) Y DF = gamma dose to air conversion factor [(arad/yr)/(pCi/m3)] (from Table B-1 of the Guide) DFS t
= beta dose go skin conversion factor
[(arem/yr)/(pCi/m )] (from Table B-1 of the Guide) DFG i2 = skin dose conversion factor for standing on 2 g contaminated ground [(mrem /hr)/(pC1/m )] (from Table E-6 of Reg. Guide 1.109) V)
-(
j 1.11 = average ratio of tissue to air energy absorption f coefficient (from Reg. Guide 1.109, pg 1.109-6) 0.7 = shiciding dose-reduction factor (from Reg. Guide 1.109, pg 1.109-68) and the remaining parameters are as defined above in Section 3.5.1.2. Note that the total skin dose as described here includes the contribution of airborne noble gases, even though this section addresses only the iodines and particulates.
/'s O
BN1-11600.02-112 3.5-4 Revision 3 - December 1983
SNPS-1 ODCM
.O '3.5.1.4 Organ Doses Due to Inhalation U~
Di "h == (X/Q)sa ye 3.17 x 104 R I f DFA ja a part+I i ija where: Di "h = dose to organ j of individual in age group a due to d' inhalation of airborne radioactivity [ mrem /hr] (Ref.: Reg. Guide 1.109 Eqs. C-3 and C-4) DFA = dose conversion factor for nuclide i to organ j of ija individual in age group a [mrea/pCi inhaled] (from Tables E-7 through E-10 of the Guide) Ra = breathing rate of individual in age group a [m3/yr] (from Table E-5 of Reg. Guide 1.109, for the maximum individuals) (X/Q)sa = concentration dispersion factor (Sector-Average model) for the period of release (nearest garden and nearest residence) [sec/m3] 3.5.1.5 Organ Doses Due to Ingestion of Leafy Vegetables
= (Djang)part + (Dja ng) iodines + (Dja i i i i D "E ng)C14
'[\d] ja ing
+ (Dja )H3 whece:
ing UL f DFI (Dja ) = (D/Q) F' 1.1 x 108 E a l part Part i ija 0.2 , Biv -24A 240 A 1 2(At + 0.0021) ing
=(D/Q) F' 5.5 x 10 7 iodines g 3L f DFI ija l (Dja) iodines a i B iv 1.0 -24A 240 A g 2(At + 0.0021)
(D"8) = (X/Q)sa F' 2.2 x 107Uba fC14 DFI C14,ja l ja C14 . (D ) = (x/Q)**F' (
- H )U f H3 H3 ja BN1-11600.02-111 3.5-5 Revision 3 - December 1983
._. . - . . . _ .. . _ _ . _ _ . . . _ . . ._ _ _ - _ _ .. _ _ , _ _ _ _ _ ~
SNPS-1 ODCM l 5 (D ) . = do6e to organ j of individual in age group a due to part ingestion of leafy vegetables contaminated with particulate radioactivity [mrea/hr] (Ref.: Reg. Guide 1.109, Eqs . C-5, C-6 and C-13 for leafy vegetables l only, with the following: e r(fraction of deposited activity retained on crops)
= 0.2 (see pg 1.109-68 of the Guide) e t, (time period that crops cre exposed to contamination during growing season) = = [ hrs]
et b (time Period over which the accumulation is
. evaluated) = = [ hrs]
et h (time delay between harvest of vegetation or crops and ingestion) = 24 [ hrs] _ eY y(agricultural productivity) = 2 [kg/m 2) 2 e P (soil effective surface density) = 240 [kg/m j eA Ei A + 0.0021 [hr-I] (Ref.: Reg. Guide 1.109, pgs 1. 1d9-4 and 1.109-69)
*61 (r 0) = (D/Q) [m" ]
ef g (fraction of leafy vegetables growing in garden of interest) = 1.0 (D",E) = dose to organ j of individual in age group a due to iodines ingestion of leafy vegetchles contaminated with-radioiodines [ area /hr] (Ref.: Reg. Guide 1.109 Eqs. C-5, C-7 and C-13 for leafy vegetables only; similar to the organ dose due to particulate radioactivity given above but with r = 1.0 and different multiplying constant) (D"E) = Jose to organ j of individual in age group a due to d* C14 ingestion of leafy vegetables exposed to airborne Carbon-14 [mrea/hr) (Ref.: Reg. Guide 1.109, Eqs. C-8 and C-13 for leafy vegetables only, with p (the ratio of ' the total annual release time to the total annual time during which photosynthesis occure) = 1) (D E) = dose to organ j of individual in age group a due to H3 ingestion of leafy vegetables exposed to airborne t tritium [mrea/hr] (Ref.: Reg. Guide 1.109, Eqs. C-9 and C-13 for leafy vegetables only) BN1-11600.02-112 3.5-6 Revision 3 - December 1983
SNPS-l ' 0DCM .w g ( ) U = ingestion rate of leafy vegetables by individual in (J age group a (from Table E-5 of the Guide, maximum individual) [kg/yr] B gy = concentration factor for uptake of radionuclide i frota soil by edible parts of crops [(pCi/kg)(wet woLght)/ (pCi/kg) (dry soil)] (Ref.: Reg. Guide 1.109, Table E-1 and included on Table 3.5-6) l DFI kja = d se conversion factor for nuclide i to organ j of individual in age group a due to ingestion of contaminated food [ mrem /pCi ingested] (from Tables E-11 through E-14 of the Guide) DFIC14,ja = DFI gja for Carbon-14 DFI H3,ja = DFIgj,for tritium F C14 "f i for Carbon-14 (see Section 3.5.1.1 above) f H3 "f i f r tritium H the atmosphere at the location
= of absolute humidity]
interest [g/m of (x/Q)sa = concentration dispersion factor (Sector - Average s'y model) for the period of release (nearest garden and nearest residence) [sec/m3 ] (D/Q) = particulate deposition rate (nearest garden and nearest residence) [1/m2 ) 3.5.1.6 Infant Thyroid Dose Due to Inhalation and Ingestion of Goat Milk Infant is used here as a def ault age group but in locations where there is no infant, such as 6B1 (see Table 5-5), child parameters will be substituted as appropriate. inh milk Dthy,inf =D + thy,inf thy,inf where: milk inilk D thy,inf =(Dthy,inf) + (D hy,inf) iodines
+
+(D*hy,inf)C14 t (Dthy ,inf ) 113 4
D" hf = (x/Q) F' 3.17 x 10 R hf Z f DFA l i f part+I ( BN1-11600.02-112 3.5-7 Revision 3 - December 1983
SNPS-1 ODCM (D inf " part part ' I" B
, 0.2 gv _4gA
*
- l mi b.7(Ag + 0.0021) + 240 A I (D 'inf
"( *
- nf i 1, thy,inf iodines iodines
, 1.0 + iv -48A
*
- i mi t.7 ( Ag + 0.0021) 240 A )
' DFI (D inf "( ) nf C14 C14, thy,inf I C14
*b# m,C14 exP(-48 k14) !
inf H3
" ( X/[ F ' h *g ) nf IH3 H3, thy ,inf x 6 Fm ,H3 exp(-48 3) !
D" = infant thyroid dose due to inhalation of airborne m- I' " radioactivity _[ mrem /hr] (Ref.: Reg. Guide 1.109, Eqs. C-3 and C-4) (Dthy,inf) = infant thryoid dose due to ingestion of milk part contaminated with radioactive particulates [ mrem /hr] (Reg . Guide Eqs . C-5, C-6, C-10, C-11 and C-13) f or milk, with the following: or (fraction of depcsited activity retained on crops) = 0.2 (see pg-1.109-68 of the Guide) e t, (time period that crops are exposed to l contamination during growing season) = = [ hrs] et b (time period over which accumulation is evaluated) = = [ hrs] eth (time delay for ingestion of forage by animale)
= 0 [ hrs] (see pg 1.109-69 of Reg Guide) eY y man(agricultural pathway) = 0.7 productig]ity,
[kg/m grass-animal-(Reg Guide 1.109, milk-Rev. 0) e P (soil effective surface density) = 240 [kg/m )2 0\ v 3.5-8 Revision 3 - December 1983 BN1-11600.02-112
i SNPS-1 ODCM S
'* =. + 0.0021 [hr-11 (see Pgs 1.109-4 and 1.kO9-69 e at (r.0) = (D/Q) [a-2j e tg (average transport time of activity f rom the
' feed into the milk and to the receptor) = 48 [ hrs ]
ef (fraction of the year that animals graze on p$sture)=1(conservativeassumption) e f, (fraction of daily feed that is pasture grass _ when the . animal grazes on pasture) = 1 (conservative assumption) (D = infant thyroid dose due to ingestion of milk
'hf ) iodines contaminated with radio-iodines [arem/hr] (Ref.:
Reg. Guide Eqs . C-5, C-7, C-10, C-11, and C-13 for milh; similar to the infant thyroid dose due to. the ingestion of particulates given above, with the exception of a different multiplying factor-and r = 1.0)
= infant thyroid dose due to ingestion of milk (D*I'")C14 contaminated with C14 [ area /hr] (Ref .: Reg. Guide b
D) 1.109, Eqs. C-8, C-10, C-11 and C-13 for milk, with p (the ratio of the total annual release time to
-the total annual time during which photosynthesis occurs) = 1, and tg, f ,p and f, _as given above for the particulates)
= infant thyroid dose due to ingestion of milk (D" I' " )H3 contaminated with tritium [ mrem /hr) (Ref.: Reg.
Guide 1.109, Eqs . C-9, C-10, C-11, and C-13 for milk, with t particulates)g. p f, and f, as given above for the Rg ,g = infant breathing rate [m3 /yr] (from Table E-5 of the Guide, for maximum individual)
- D Mi , thy,inf = dose conversion f actor for nuclide i to the infant thyroid due to inhalation [mren/pCi inhaled] (from Table E-10 of the Guide)
DFIi thy,inf = dose conversion f actor for nuclide i to the infant thyroid due to ingestion [ mrem /pCi ingested] (from ' Table E-14 of the Guide) DFI C14, thy,inf = DFIt , thy,inf for Carbon-14 DFI H3, thy,inf = DFI i thy,inf for tritium BN1-11600.02-112 3.5-9 Revision 3 - December 1983
SNPS-1 ODCM p F C14 "f i for Carbon-14 (see Section 3.5.1.1 above) FH3 "f i f # '#iti"" (g = milk ingestion rate by infant [ liters /yr] (Ref.: Reg. Guide-1.109, Table E-5, max ind.) F ,t = average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk [ days / liter] from Table E-2 of the Guide, with F, = F,t , f or goat ) B gy = concentration f actor for uptake of radionuclide i from soil by edible parts of crops [(pCi/kg) (wet weight) / (pCi/kg) (dry soil)] (from Table E-1 of the Guide and included on Table 3.5-6) l H
=absolutehumidit3]oftheatmosphereatthelocation of interest [g/m 6 = amount of feed consumed by a goat per day [kg/ day 1 l (from Table E-3 of the Guide, Qp factor)
O)
'(/
48 = average transport time of activity from the feed into the milk and the receptor [ hrs] (see page 1.109-27 of the Guide) ( X/Q)8" = concentration dispersion f actor (Sector - Average model) for the period of release (nearest goat location) [sec/m3 ] (D/Q) =part{culatedepositionrate(nearestgoatlocation) [1/m ] l O BN1-11600.02-112 3.5-10 Revision 3 - December 1983
SNPS-1 ODCM 3.5'.2 ' Method 2: (Backup Method) 3.5.2.1 Organ Doses: D) = 3.17E-08* { ((10*R, *Pg ) N /Qg + P,g) *D/Qg)* (Cg* V *tg-C *V *t 2
-C i3 3 **3
+ 3.17E-08* V 2*"2*E[(10'*R,*P)*X/Q2 g + P,g) *D/Q 2)*C12
+ 3.17E-08 *V 3 .*t3*{((10 *R, .*Pg ) *X /03+Pog) *D/Q3 )*Ci3) ("#**)
(3.5.2-1) , During periods of no internittent releases, such as no main condenser air removal pimp operation and no containment . drywell purge, the above formula reduces to the following: D = 3.17E-08 *V 1
*t l I l( o' **a *P1) *X/Qg + P,g) *D/Q g)*Cgg) (arem) ,
(3.5.2-2) where:
+
Dj '= total dose to organ j (arem), Pji
= the inhalation dose conversion factor for radionuclides, i, (other than noble gases, tritium, carbon-14), and organ j, (arem per pCi inhaled) from Table 3.5-3. . For tritium and carbon-14, Pg4.
includes the contribution- from ingestion of leafy and stored vegetables 'and .from inhalation pathways and is listed in Table 3.5-15. P ij values listed in Tables 3.5-16 and 3.5-17 are the dose rate conversion factors for tritium and carbon-14 from ingestion of
. goat's milk.
Note: For short ~ term releases such as from condenser air removal pump or containment drywell purge Pii for C-14 must be adjusted (see note in Tables 3.5-15, 3.5-16 and 3.5-17). ~ i~ R, = inhalation rate (m3/yr) f ro.a Table 3.5-5, P = the dose conversion factor for radionuclides, other than noble ' oij gases, 1, and -organ j, for the leafy vegetables, stored ; vegetables, and contaminated ground pathways in m2 (arem/yr per ' O. pCi/sec) respectively, from Table 3.5-9. BN1-11600.02-112 3.5-11 Revision 3 - December 1983
'SNPS-1 ODCM
, ' The dose factorsi P j, .Poij are based on the critical individual organ for the child group, since .this group is most restrictive.
= 7.88E+06 see for quarterly dose calculation-t1
= 3.15E+07 see for yearly dose calculation, t2 = release period '(sec) for condenser air removal pump, t'
3 -= release period (sec) for containnent drywell purge exhaust,
.Cil' = the station ventilation exhaast duct release concentration of
.radionuclide, i,. (pCi/cc) (from the isotopic analyses performed on the iodine and filter. cartridge talen from the station ventilation exhaust monitor),
C 12 = the . air removal. pump. ventilation exhaust duct release (pC1/cc) .( from the isotopic l concentration of radionuclide. 1, l' analyses performed on the iodine and filter cartridge taken from the air removal pump discharge monitor),
,C13_ = 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),
Vi = .1.73E+08 cc/sec (3.66E+05 cfa), station ventilation exhaust duct l ventilation exhaust flow rate, V = 5.70E+05 cc/sec (1200 cfa), air removal pump exhaust duct 2 ventilation exhaust flow rate, V 3_ = 5.70E+05 cc/sec (1200 cfa), containment drywell purge ventilation exhaust flow rate, X/Q1 = annual- average X/Q at 2478 meters ESE due to releases via the station ventilation exhaust point (1.54E-07 sec/m3), X/Q2 = short term X/Q at 2478 meters ESE due to condenser air removal pump release via the station ventilation exhaust point ;4.22E-07 sec/m3), X/Q3 w1
= short ternstation via the X/Q at ventilation 2478 metersexhaust ESE due point to containment dry /m3)1 purge (4.22E-07 sec ,
. D/Q1 - = annual average D/Q deposition factor at 2478 meters ESE due t releases via the station ventilation exhaust point (3.08E-09 m-2)o ,
D/_Q2 = short term D/Q deposition factor at 2478 meters ESE due to l condenser air removal pump releases via the station vertilation exhaust point (8.47E-09 m-Z), I ( BN1-11600.02-112 3.5-12 Revision 3 - December 1983
SNPS-1~ODCM
'i
[V . p/q3 = short term D/Q ' deposition factor at 2478 meters ESE due to containment drywell purge exhaust via the station ventilation exhaust point (8.47-09 m-2), i 3.17E-08 = inverse of 3.15E+07 sec/yr, and JNOTE: i r ! If the land 'use census (see Table 3.5-8) changes , ' the critical location', i.e. , [. the location where an individual would be exposed to the highest dose, must be reevaluated using Equation 3.5.2-1 for. each of the following -locations:
- 1. nearest residence,
! 2. nearest vegetable garden, and 3. nearest milk cow or goat. Poij used in Equation 3.5.2-1 will include the values in Tables 3.5-10 through 3.5-14, if those pathways exist.
' At . each location, the following pathways must be considered and dose (dose
.. rates) reevaluated if any actual pathway exists:
- 1. . inhalation,
- 2. . leafy vegetables (fresh),
O
.3. stored vegetables, _
4.- goat's or L cow's milk (if both exist choose the one resulting in a
-higher dose), and
- 5. deposition ' on ground.
'Since a. - ,erson will always be present, pathways 1 and 5 must always be evaluated.
~0nce the location of the critical individual is determined and found to be other ~than the one at 2478 meters ESE, the values of X/Q and D/Q at the l
updated critical location must be used.
'BN1-11600.02-112. 3.5-13 Revision 3 - December 1983
v- v \_) SNPS-1 ODCM TABLE 3.5-1 INHA1ATION DOSE FACTORS FOR ADULTS (arem per pCi inhaled) Radio-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 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data- No Data 1.08E-05 Cr-51 No Data No Data 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E 1.75E-04 9.67E-06 Mn-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 Fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 Co-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 Ni-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 7.00E-07 1.54E-06 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 1.29E-05 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 Br-83 No Data No Data 3.01E-08 No Data No Data No Data 2.90E-08 Br-84 No Data No Data 3.91E-08 No Data No Data No Data 2.05E-13 Br-85 No Data No Data 1.60E-09 No Data No Data No Data <1.00E-24 Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06 4 Rb-88 No Data 4.84E-08 2.41E-08 No Data No Data No Data 4.18E-19 Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.16E-21 Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75E-04 4.37E-05 Sr-90 1.24E-02 No Data 7.62E-04 No Data No Data 1.20E-03 9.02E-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-05 Y-92 1.29E-09 No Data 3.77E-11 No Data No Data 1.96E-06 9.19E-06 Y-93 1.18E-05 No Data 3.26E-10 No Data No Data 6.06E-06 5.27E-05 BN1-11600.02-99 1 of 3 Revision 1 - August 1983
-m
( ! t i
'm ' 'O L SNPS-1 ODCM TABLE 3.5-1 (CONT'D)
Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 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 Data 9.67E-07 6.31E-05 1.30E-05 Mo-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 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 7.32E-15 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21 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 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 1.58E-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 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 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-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-06 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 1-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 No Data. 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.3BE-05 No Data 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2./8E-05 9.40E-06 1.05E-06 Cs-138 4.14E-05 7.76E-08 4.05E-08 No Data 6.00E-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 1.432-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-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 N) Data No Data 7.91E-07 2.64E-07 BN1-11600.02-99 2 of 3 Revision 1 - August 1983
O O O SNPS-1 ODCM i . TABLE 3.5-1 (CONT'D) Radio-nuclide Bone Liver T. Body Thyroid Kidney 13 gy( GI-LLI l' Ce-141 2.49E-06 1.69E-06 1.91E-07 No Data' 7.83E-07 4.52E-05 1.50E-05 j Ce-143 2.33E-08 1.72E-08 -1.91E-09 No Data 7.60E-09 9.97E-06 2.83E-05 i Ce-144 4.29E-04 1.79E-04 2.30E-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 4.56E-08 No Data 4.45E-07 2.76E-05 '2.16E-05 W-187' 1.06E-09 8.85E-10. 3.10E-10 No Data No Date !3.63E-06 1.94E-05 l Np-239 2.87E-08 2.82E-09. 1.55E-09 No Data- 8.75E-09 4.70E-06 1.49E-05 l l l i i i 4
- I 1 '
a I i 1 l i j BN1-11600.02-99 3 of 3 Revision 1 - August -1983 i i i
% ,/ \. J L/
SNPS-1 ODCM TABLE 3.5-2 INHAIATION DOSE FACTORS FOR TEENAGER (arem per pCi inhaled) Radio-nuclide Bone Liver T. Body Thyroid i dney Lung GI-LLI 11 - 3 No Data '1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 l P-32 2.36E-04 1.37E-05 8.95E-06 No Data No Data No Data 1.16E-05 l Cr-51 No Data No Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Ma-54 No Data 6.39E-06 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06 Mn-56 No Data 2.12E-10 3.15E-11 No Data 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91E-04 2.23E 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 Ni-65 2.73E-10 3.66E-11 1.59E-11 No Data No Data 1.17E-06 4.59E-06 Cu-64 No Data 2.54E-10 1.96E-10 No Data 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 No Data 7.53E-12 1.98E-07 3.56E-08 Br-83 No Data No Data 4.30E-08 No Data No Data No Data <1.00E-24 Br-84 No Data No Data 5.41E-08 No Data No Data No Data <1.00E-24 Br-85 No Data No Data 2.29E-09 No Data No Data No Data <1.00E-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 1.00E-08 No Data No Data 3.66E-05 6.99E-05 Y-91m 4.63E-11 No Data 1.77E-12 No Data No Data 4.00E-07 3.77E-09 Y-91 8.26E-05 No Data 2.21E-06 No Data No Data 3.67E-04 5.11E-05 . Y-92 1.84E-09 No Data 5.36E-11 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 BN1-11600.02-100 1 of 3 Revision 1 - August 1983
gwy f# m. p"' ( ) ) I i r ( J Q' x_- SNPS-1 ODCM TABLE 3.5-2 (CONT'D) Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 2'r -95 1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 No Data 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-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 j 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-16 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 E.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 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.0/6-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 l
Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 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-il 7.72E-12 2.92E-07 1.89E-09 l l 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 . 1-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 No Data 8.11E-07 l 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 4.362-07 7.76E-05 1.86E-06 No Data 8.69E-07 Cs-134 6.28E-05 1.*1E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 No Data 1.38E-05 2.22E-06 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 BN1-11600.02-100 2 of 3 Revision 1 - August 1983
LJ , I SNPS-1 ODCM TABLE 3.5-2 (CONT'D) Radio-nuclide Bone Liver T. Body- Thyroid Kidney Imog( GI-LLI 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-08 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-04 1.67E-03 1.08E-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 2.219-09 No Data 1.25E-08 8.11E-06 1.65E-05 l l l l
~
l l BN1-11600.02-100 3 of 3 Revision 1 - August 1983
SNPS-1 ODCM '
~
TABLE . 3. 5-3 INHALATION DOSE FACTORS.FOR-CHILD. 1(area per pCL inhaled) Radio-nuclide Bone Liver T. Body Thyroid Kidney -CI-LLI 1a93[ H-3 No Data 3.04E-07 3.04E-07 3.04E-07 -3.04E-07 3.04E 3.04E-07
-C-14 9.70E-06 1.82E-06 -1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 .4.35E-06 4.35E 4.35E-06 4.35E-06 4.35E-06 '4.35E 4.355-06 P-32 7.04E-04 3.09E-05 2.67E No Data No Data- No Data 1.14E-05 Cr-51 No Data No Data 4.17E-08 2.31E 6.57E-09 4.59E-06 2.93E Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71E-06 4.26E-04 6.19E-06 Mn-56' No Data 4.48E-10 8.43E-11 No Data 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 No Data No Data 3.00E 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51R-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:
Co-60 No Data 3.55E-96 6.12E-06 No Data No Data 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data ~7.43E-05 -1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 No Data No Data 2.21E-06 '2.27E-05 Cu-64 No Data 5.39E-10 2.90E-10 No Data. 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41E-06' Zn-67 1.81E-11 2.61E-11 2.41E-12 No Data 1.58E 3.84E 2.75E Br-83 No Data No Data 1.28E-07 No Data No Data No Data <1.00E-24 Br-84 No Data No Data 1.48E-07 No Data No Data No Data <1.00E-24 Br-85 No Data No Data 6.84E-09 No Data No Data No Data <1.00E-24 I Rb-86 No Data 5.36E-05 3.09E-05 No Data No Data No Data '2.16E-06 ) Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 ! Rb-89 No Data 9.33E-08 7.83E-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-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 i 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 Y-91 2.47E-04 No Data 6.59E-06 No Data No' Data 7.10E-04 4.97E-05 Y-92 5.50E-09 No Data 1.57E 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 , BN1-11600.02-101 1 of 3 Revision 1 - August 1983
( , 7
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nj
) \w SNPS-1 ODCM TABLE 3.5-3 (CONT'D)
Radio-nuclide Bone Liver T. Rody Thyroid Kidney Lung GI-LLI 2'-95 r 5.13E-05 1.13E-05 1.00E-05 No Data 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 No Data 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 No Data 2.33E-06 1.66E-04 1.00E-05 Mo-99 No Data 4.66E-08 1.15E-08 No Data 1.06E-07 3.66E-05 3.42E-05 l Tc-993 4.81E-13 9.41E-13 1.56E-11 No Data 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 No Data 3.92E-13 1.58E-07 4.41E-09 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 Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.16E-04 Ag-110m 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-06 1.48E-03 2.71E-05 Te-125m 1.82E-06 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 4.00E-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-05 l Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 l Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 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 l Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 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-06 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 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 No Data 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 Na 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 1.7eE-05 4.62E-05 3.14E-05 No Data 2.58E-05 3.93E-06 1.13E-06 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-11 No Data 2.33E-13 1.56E-06 1.56E-05 Ba-140 2 00E-05 1.75E-08 1.17E-06 No Data 5.71E-09 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-08 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 6.08E-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 Ho Data 2.35E-06 2.05F-05 BN1-11600.02-101 2 of 3 Revision 1 - August 1983
O O SNPS-1 ODCM O TABLE 3.5-3 (CONT'D) Radio-nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data 2.31E-06 1.47E-04 1.33E-05 l Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 50 Data 3.17E-04 3.23E-03 1.05E-04 j Pr-143 4.99E-06 1.50E-06 2.47C-07 No Data 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.10E-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 1.30E-06 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-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 1 BN1-11600.02-101 3 of 3 Revision 1 - August 1983
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-SNPS-1 ODCM-TABLE 3.5-4 INHAIATION DOSE FACTORS FOR INFANT (arem per pCi inhaled)
}~ i Radio-- nuclide Bone Liver T. Body Thyroid Kidney ifinj( GI-LLI H-3 No Data 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 -3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-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-05 3.56E-06 No Data 3.56E-06 7.14E-04 5.04E-06 Mn-56 No Data 1.10E-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 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 l Co-58 No Data 8.71E-07 1.30E-06 No Data No Data 5.55E-04 7.95E-06 l 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 Ni-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 Za-65 1.38E-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 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 i Br-83 No Data No Data 2.72E-07 No Data No Data No. Data <1.00E-24 l Br-84 No Data No Data 2.86E-07 No Data No Data No Data <1.00E-24 Br-85 No Data No Data 1.46E-08 No Data No Data No Data <1.00E-24 Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06 Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07 Rb-89 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.87E-08 I 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 l Sr-92 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.00E-04 Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05 Y-91m 2.91E-10 No Data 9.90E-12 No Data. No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 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 Y-93 1.07E-07 No Data 2.91E-09 No Data No Data 5.46E-05 1.19E-04 Revision 1 - August 1983 BN1-11600.02-102 1 of 3 (
f (/ () .f( ) SNPS-1 ODCM TABLE 3.5-4 (CONT'D) i Radio-nuclide Bone Liver T. Body Thyroid Kidney Ignj[ CI-LLI Zr-95 8.24E-03 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E 9.05E-06 i Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05 Tc-993 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 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 Ru-106 6.20E-05 No Data 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No Data 3.19E-04 9.22E-06 Tc-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Ta-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Ta-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Ta-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Ta-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 l I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 No Data 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 No Data 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 No Data 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 No Data 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 No Data 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-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 Co-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 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 No Data 4.23E-13 4.25E-06 3.64E-05 l Ba-140 4.00E-05 4.00E-08 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05 Be-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 Revision 1 - August 1983 2 of 3 BN1-11600.02-102
N PS O. , ). O SNPS-1 ODCM TABLE 3.5-4 (CONT'D) Radio-nuclide Bone Liver T. Body Thyroid Kidney Igniy( GI-LLI Ce-141 1.98E 1.19E-05 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 8.65E-04 1.26E-04 No Data 3,84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 No Data 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 No Dsta 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 9.26E-09 6.44C-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-03 1.34E-08 No Data 4.73E-08 4.25E-05 1.78E-05 s l I 1 Revision 1 - August 1983 3 of 3 BN1-11600.02-102
SNPS-1 ODCM TABLE 3.5-5 RECOMMENDED VALUES FOR U,p TO BE USED FOR THE MAXIMUM EXPOSED INDIVIDUAL IN LIEU OF SITE-SPECIFIC DATA Pathway Infant Child Teen Adult Fruits, vege-yr) I 3 N/A(7) 520 630 520 l Leafy vege-tables (kg/yr) (I) N/A 26 42 64 l Milk (t/yr)(I) 330 330 400 310 Meat & p try (kg/yr) N/A 41 65 110 l Fish (fresh or salt) (kg/yr)(3) N/A 6.9 16 21 l Othersegod 1.7 3.8 (kg/yr) N/A 5 l Drinkin ater (1/yr) 330 510 510 730 Shoreline re-creatio (hr/yr) 4) N/A 14 67 12 l Inhglation (in /yr) 1400(5) 3700(6) 8000(6) 8000(5) (1) Consumption rate obtained f rom Reference 19 for average individual and age-prorated and maximized using techniques contained in Reference 10 of Regulatory Guide 1.109, Rev 1, Oct. 1977. (2) Consists of the following (on a mass easis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain. O BN1-11600.02-112 1 of 2 Revision 3 - December 1983 (
/
SNPS-1 ODCM O TABLE 3.5-5 (CONT'D) (3) Consumption rate for adult obtained by averaging data from References 10 and 21-24 of Regulatory Guide 1.109, Rev. 1, Oct. 1977 and age prorated using techniques contained in Reference 10. (4) Data obtained 'directly from Reference 10 of Regulatory Guide 1.109, Rev.1, Oct 1977. (5) Data obt'ained directly from Reference 20 of Regulatory Guide 1.109, Rev. 1, Oct. 1977. (6) Inhalation rate derived from data provided in Reference 20 of Regulatory Guide 1.109, Rev. 1, Oct'. 1977. (7)N/A indicates not applicabie.
~
l O O BN1-11600.02-112 2 of 2 Revision 3 - December 1983
.SNPS-1 ODCM ;h TABl.E-3.5-6 v:
LSTABLE ELEENT TRANSFER DATA (1) B _. F (Cow) F Element Veg/ Soil Milk (d/1) Meat (d/kg) n
. H(2) :4.8E+00 1.0E-02 1.2E-02
-C(2) 5.5E+00 1.2E-02 3.1E-02
' Na . '5.2E-02 4.0E-02(3) 3.0E-02
.P 1.1E+00 2.5E-02 .4.6E-02 Cr. -2.5E-04 2.2E-03 ~2.4E-03
.Its 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 l'
Ni 1.9E-02 6.7E-03 5.3E-02 Cu - 1.2E-01 1.4E-02 8.0E-03
'2h. 4.0E-01 3.9E-02 3.0E-02 Rb -1.3E-01 3.1E-02
.Sr . 1.7E-02 3.0E-02(3) 8.0E-04 6.0E-04 Y. 2.6E-03 1.0E-05 4.6E-03 Zr , 1.7E-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01
. No 1.2E-01 .7.5E-03 8.0E-03 Tc. 2.5E-01 2.SE-02 4.0E-01
- p
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 2.9E-03 Cs 1.0E-02 6.0E-03((4) 1.2E-02 3) 4.0E-03
.Ba 5.0E-03 4.0E-04(3) 3.2E-03 La 2.5E-03 2.0E-04
=Ce 2.5E-03 5.0E-06(3) 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(5)
(I) Data presented in this table is from Reference 1 of Regulatory Guide 1.109, Rev. 1, Oct. 1977. (2)
.(3) Meat and milk coefficients are based on specific activity considerations.
From Reference 15 ~of Regulatory Guide 1.109, Rev. 1, Oct. 1977.
-(4)See text (Regulatory Guide 1.109, Rev. 1, Oct. 1977).
(5)From Reference ~13 of Regulatory Guide 1.109, Rev. 1, Oct. 1977. O BN1-11600.02-112 1 of 1 Revision 1 - August 1983
SNPS-1 ODCM TABLE 3.5-7 HUMIDITY PARAMETERS AT RECEPTORS Monthly Average Absolute Humidity (ge./m3 ) 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 l 9 BN1-11600.02-112 1 of 1 Revision 1 - August 1983
I SNPS-1 DDCM As _/ TABLE 3.5-8 DISTANCE FROM REACTOR CENTERLINE BY SECTOR OUT TO 8046 m (Meters) - Nearest Nearest Nearest Sector Residence Vegetable Garden Site Boundary N - - 436 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 (v '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 WNW 610 - 354 NW - - 419 NNW - - 436 N0fE: There are no milk cows or meat animals within the 8,046 m radius of the site. The nearest milk cow is located 8,690 m east of the site. The nearest milk goats are located 2,478 m east-southeast, 3,846 m southwest and 7,725 m south-southwest of the site. O V BN1-11600.02-112 1 of 1 Revision 3 - December 1983
. . ~ , .
~ '
' +, =
$ ( h SNPS-1?ODCM-TABLE 3.5-9
.P,g3 STORED VEGETABLES DOSE RATE CONVERSION FACTORS FOR CHILD
- CONTAMINATED GROUND, . INGESTION m OF LEAFY Ap(area /yr/ p Ci/sec),
'Nuclide- Bone . ,Tfver T. Body Thyroid Kidney M CI-LLI
.N-13 4.0E+04 4.0E+04 .4.0E+04 4.0E+04 4.0E+04 4.0E+04 4.0EM4 F-18 4.0E+05 4.0E+05 4.0E+05 '4.0E+05- 4.0E+05 4.0E+05 4.0E+05' NA-24 1.2E+07 1.2E+07 1.2E+07 1 +07 1.2E+07 1.2E+07 1.2E+07-P-32 3.6E+09 1.7E+08 1.4E+08 - -
. 9.9E+07.
CR-51 /' 4.9E+06 4.9E+06 5.0E+06 5.0E+06 4.9E+06 5.0E+06 '1.lE+07: MN-54 1.3E+09 1.9E+09 1.5E+09 1.3E+09 1.5E+09 1.3E+09 1.8E+09 MN-56 9.0E+05 9.0E+05 9.0E+05 9.0E+05. 9.0E+05 9.0E+05 9.0E+05 FE-55 7.3E+08 3.8E+08' 1.2E+08 - - 2.1E+08 7.lE+07
'FE-59 6.SE+08 8.8E+08 5.8E+08 2.8E+08 J2.8E+08 4.5E+08 9.1E+08-CO-58 3.8E+08 4.4E+08 5.6E+08 3.8E+08' 3.8E+08 3.8E+08 7.3E+08 CO-60 2.3E+10 2.3E+10 2.4E+10 2.3E+10 2.3E+10 2.3E+10 2.5E+10 I
NI-63 4.6E+10 2.4E+09 1.6E+09 - - - 1.6E+08 NI-65 3.0E+05 3.0E+05 3.0E+05 3.0E+05 3.0E+05 3.0E+05 3.0E+05 CU-64 6.1E+05 6.2E+05 6.2E+05 6.1E+05 6.4E+05 6.lE+05 1.1E406 ZN-65 1.8E+09 3.4E+09 2.5E+09 8.6E+08 2.5E+09 8.6E+08 1.3E+09 ZN-69M 1.3E+06 1.3E+06~ .1.3E+06 1.3E+06 1.3E+06 1.3E+06 1.5E+06 l ! BR-83 4.9E+03 4.9E+03 4.9E+03 4.9E+03 4.9E+03 4.9E+03 '4.9E+03 BR-84 2.0E+05 2.0E+05 2.0E+05 2.0E+05 2.0E+05 2.0E+05 ,2.0E+05 RB-86 9.0E+06 4.5E+08 2.8E+08 9.0E+06 9.0E+06 9.0E+06 3.7E+07-RB-88 3.3E+04 3.3E+04 3.3E+04 3.3E+04 3.3E+04 3.3E+04 3.3E+04 RB-89 1.2E+05 1.2E+05 1.2E+05 1.2E+05 1.2E+05 1.2E+05 1.2E+05 SR-89 3.3E+10 2.2E+04 9.5E+08 2.2E+04 2.2E+04 2.2E+04 1.3E+09 SR-90 1.4E+12 6.7E+06 3.4E+11 6.7E+06 6.7E+06 6.7E+06 1.8E+10-SR-91 3.8E+06 3.3E+06 3.3E+06 3.3E+06 3.3E+06 3.3E+06 4.4E+06 SR-92 9.5E+05 9.5E+05 9.5E+05 9.5E+05 9.5E+05 9.5E+05 9.6E+05 Y-90 2.7E+04 4.5E+03 5.1E+03 4.5E+03 4. 5E+03 4.5E+03 6.3E+07 Y-91M 1.OE+05 1.0E+05 1.0E+05 1.0E+05 ~1.0E+05 1.0E+05 1.0E+05 Y-91 1.8E+07 1.IE+06 1.6E+06 1.1E+06 1.IE+06 1.1E+06 2.3E+09 Y-92 1.8E+05 1.8E+05 1.8E+05 1.8E+05 1.8E+05 1.8E+05 1.9E+06 Y-93 1.8E+05 1.8E+05 1.8E+05 1.8E+05 ' 1.8E+05 -1.8E+05 4.5E+06 ZR-95 5.0E+08 5.0E+08 5.0E+08 5.0E+08 5.0E+08 5.0E+08 1.3E+09 ZR-97 5.3E+06 5.3E+06 5,3E+06 5.3E+06 5.3E+06 5.3E+06 1.7EM7 BN1-ll600-117 1 of 3 Revision 3 - December 1983
f ,r
& / .)
-SNPS-1 ODCM TABLE 3.5-9 (CONT'D)
Nuclide Bone Liver T. Body Thyroid- Kidney Lung CI-LLI NB-95 1.4E+08 1.4E+08 1.4E+08 1.4E+08 1.4E+08 1.4E+08 4.2E+08 MO-99 6.lE+06 1.4E+07 7.9E+06 6.lE+06 2.2E+07 6.lE+06 1.2E+07 TC-99M 1.8E+05 1.8E+05 1.8E+05 1.8E+05 1.8E+05 1.8E+05 1.9E+05 TC-101 2.0E+04 2.0E+04 -2.0E+04 2.0E+04 2.0E+04 2.0E+04 2.0E+04 RU-103 1.2E+08 1.lE+08 1.2E+08 1.lE+08 1.5E+08 1.lE+08 4.9E+08 RU-105 7.3E+05 7.3E+05 7.3E+05 7.3E+05 7.3E+05 7.3E+05 7.9E+05 RU-106 1.lE+09 .4.2E+08 5.lE+08 4.2E+08 1.4E+09 4.2E+08 1.lE+10 AC-Il0M 3.5E+09 3.5Et09' 3.5E+09 5.5E+09 3.5E+09 3.5E+09 6.2EM9 SB-124 6.8E+08 6.0E+08 6.3E+08 6.0E+08 6.0E408 6.6E+08 3.08+09 TE-125M 4.2E+08 1.lE+08 5.7E+07 1.2E+08 1.6E+06 1.6E+06 4.IE+08-TE-127M 1.9E+09 4.9E+08 2.2E+08 4.4E+08 5.2E+09- 9.2E+05 1.4E+09~ TE-127 1.3E+04 5.7E+03 5.2E+03 9.9E+03 3.2E+04 3.0E+03 3.9E+05 TE-129M 9.7E08 2.9E+08 1.8E+08 3.3E+08 2.7E+09 3.8E+07 1.2E+09 TE-129 2.6E+04 2.6E+04 2.6E+04 2.6E+04 2.6E+04 2.6E+04 2.6E+04 ! TE-131M 1.4E+07 1.3E+07 1.3E+07 1.3E+07 1.7E+07 1.2E+07 3.4E+07 l TE-131 6.6E+04 6.6E+04 6.6E+04 6.6E+04 6.6E+04 6.6E+04- 6.6E+04
- TE-132 5.4E+07 5.0E+07 5.IE+07 5.2E+07 7.6E+07 4.7E+07 7.9E+07 l I-130 3.1E+06 3.4E+06 3.lE+06 6.9E+07 3.7E+06 2.8E+06 3.1E+06 I-131 7.7E+07 7.8E+07 4.8E+07 2.3E+10 1.2E+08 8.6E+06~ 1.5E+07 I-132 6.2E+05 6.2E+05 6.2E+05 6.2E+05 6.2E+05 6.2E+05 6.2E+05 I-133 2.9E+06 3.3E+06 2.0E+06 3.9E+08 4.7E+06 1.2E+06. 2.0E+06 I-134 2.2E+05 '2.2E+05 2.2E+05 2.2E+05 2.2E+05 2.2E+05 2.2E+05 I-135 1.3E+06 1.4E+06 1.'3E+06 6.0E+06 1.4E+06 1.3E+06 1.3E+06 CS-134 2.2E+10 3.lE+10 1.2E+10 6.9E+09 1.4E+10 9.6E+09 7.0E+09 CS-136 2.3E+08 3.6E+08 2.9E+08 1.5E+08 2.6E+08 1.7E+08 1.6E+08 CS-137 3.7E+10 3.6E+10 1.6E+10 1.3E+10 2.lE+10 1.6E+10 1.3E+10 CS-138 3.6E+05 3.6E+05 3.6E+05 3.6E+05 3.6E+05 3.6E+05 3.6E+05 BA-139 1.lE+05 1.1E+05 1.1E+05 1.lE+05 1.lE+05 1.lE+05 1.1E+05 BA-140 4.3E+08 1.7E+08 1.9E+08 1.7E+08 1.7E+08 1.7E+08 3.0E+08 BA-141 5.0E+04 5.0E+04 5.0E+04 5.0E+04 5.0E+04 5.0E+04 5.0E+04 BA-142 1.3E+05 1.3E+05 1.3E+05 1.3E+05 1.3E+05 1.3E+05 1.3E+05 LA-140 1.9E+07 1.9E+07 1.9E+07 1.9E+07 1.9E+07 1.9E+07 4.9E+07 LA-142 7.3E+05 7.3E+05 7.3E+05 7.3E+05 7.3E+05 7.3E+05 7.3E+05 CE-141 1.5E+07 1.4E+07 1.4E+07 1.4E+07 1.4E+07 1.4E+07 4.0E+08 CE-143 2.3E+06 3.2E+06 2.3E+06 2.3E+06 2.3E+06 2.3E+06 1.5E+07 CE-144 2.3E+08 1.5E+08 1.2E+08 1.lE+08 1.3E+08 .l.1E+08 9.6E+09 BN1-ll600-117 2 of 3 Revi81 " 3 .Ib '"ber 1983
\
'f% (
V d SNPS-1 ODCM-
-v TABLE 3.5-9-(CONT'D)
Nuclide Bone Liver T. Body, Thydoid Kidney Lung CI-LLI PR-143- 1.4E+05 4.2E+04 6.8E+03 - 2.3E+04 -- 1.5E+08 PR-144 1.8E+03 1.8E+03 1.8E+03 1.8E+03 '1.8E+03- 1.8E+03 1.8E+03 ND-147 8.5E+06 8.5E+06 8.4E+06 8.4E+06 8.4E+06 8.4E+06 9.5E+07 W-187 2.5E+06 2.4E+06 2.4E+06 2.4E+05 2.4E+06 2.4E+06 7.6E+C6 NP-239 1.7E+06 1.7E+06 1.7E+06 1.7E+06 1.7E+06 1.7E+06 1.5E+07 (1) The dash (-) indicates insufficient data or that the dose factor is < l.0E-20. l BN1-ll600-117 3 of 3 kvision 3 - Deceber 1983 l
a 7w g -m s N ' N.) SNPS-1 ODCM-TABLE 3.5-10 P og). S MIT.K DOSE RATE CONVERSION FACTORS CHILDINGESTIONOFCf(a' m rem /yr/pCi/sec) I Nuclide Bone Liver T. Body 1hyroid Kidney Inng GI-LLI F-18 3.5E-03 - 3.9E-04 - - - 1.0E NA-24 4.3E+06 4.3E+06 4.3E+06 4.3E+06 4.3E+06- 4.3E+06 4.3E+06 P-32 3 1.7E+09 1.4E+09 - - 1.0E+09
-(g+10 CR-51 -
4.6EM4 2.5F+04 7.0E+03 4.6E+04 2.4E+06 MN-54 - 1.1E+07 2.9E+06 - 3.0E+06 - 9.0E+06 MN-56 - 6.;E-03 1.4E-03 - 7.5E-03 - 9.0E-01 FE-55 5.8E+07 3.1E+07 9.5E+06 - - 1.7E+07 5.7E+06 FE-59 5.4E+07 8.8E+07 4.4E+07 - - 2.5E+07 9.lE+07 CO-58 - 5.6E+06 1.7E+07 - - - 3.3E+07 CO-60 - 2.3E+07 6.9E+07 - - - 1.3E+08 NI-63 1.8E+10 9.8E+08 6.2E+08 - - - 6.6E+07 , NI-65 9.5E-01 8.9E-02 5.2E-02 - - - 1.1E+01 CU-64 - 3.7E+04 2.3E+04 - 9.lE+04 - 1.8E+06 ZN-65 2.4E+09 6.5E+09 4.1E+09 - 4.lE+09 - 1.1E+09 ZN-69M 2.5E+04 3.6E+04 3.3E+03 - 2.2E+04 - 2.2E+06 BR-83 - - 2.3E-01 - - - - RB-86 - 4.0E+09 2.4E+09 - - - 2.5E+08 l SR-89 3.0E+09 - 8.6E+07 - - - 1.2E+08 SR-90 6.6E+10 - 1.7E+10 - - - 8.9E+08 SR-91 6.2E+04 - 2.4E+03 - - - 1.4E+05 SR-92 1.1E+00 - 4.2E-02 - - - 2.0E+01 ' Y-90 1.5E+02 - 4.lE+00 - - - 4.4E405 Y-91M 1.5E-19 - - - - 2.9E-16 Y-91 1.8E+04 - 4.8E+02 - - - 2.4E+06 Y-92 1.2E-04 - 3.5E-06 - - - 1.4E+02 Y-93 5.1E-01 - 1.4E-02 - - - 7.6E+03 ZR-95 1.8E+03 3.9E+02 3.5E+02 - 5.6E+02 - 4.1E+05 ZR-97 9.0E-01 1.3E-01 7.7E-02 - 1.9E-01 - 2.0E+04 i 8 l BN1-11600-Il8 1 of 3 Revision 3 - Deceber 1983
SNPS-1 ODCM TABLF 3.5-10 (CONT'D) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI NB-95 1.4E+05 5.5E+04 3.9E+04 - 5.2E+04 - 1.0E+08 MO-99 - 3.9E+07 9.7E+06 - 8.4E+07 - 3.2E+07 TC-99M 6.5E+00 1.3E401 2.lE+02 - 1.8E+02 6.4E+00 7.2E+03 RU-103 1.9E+03 - 7.4E+02 - 4.8E+03 - 5.0E+04 RU-105 1.9E 6.8E-04 - 1.6E-02 - 1.2E+00 , RU-106 4.9E+04 - 6.lE+03 - 6.6E+04 - 7.6E+05 l AG-110M 1.lE+08 7.6E+07 6.1E+07 - 1.4E+08 - 9.0E+09 SB-124 1.3E+07 2.4E+05 5.CZ+06 3.0E+04 - 9.8E+06 3.6E+08 TE-125M 3.8E+07 1.0E+07 5.1E+06 1.lE+07 - - 3.7E+07 TE-127M 1.3E+08 3.4E+07 1.5E+07 3.0E+C7 3.6E+08 - 1.0E+08 TE-127 1.5E+03 4.0E+02 3.2E+02 1.0E+03 4.3E+03 - 5.8E+04 TE-129M 1.3E+08 3.6E+07 2.0E+07 4.2E+07 3.8E+08 - 1.6E+08 TE-129 7.8E-10 2.2E-10 1.8E-10 5.5E-10 2.3E-09 - 4.8E-08 TE-131M 7.9E+05 2.7E+05 2.9E+05 5.6E+05 2.6E+06 - 1.lE+07 TE-132 5.0E+06 2.2E+06 2.7E+06 3.2E+06 2.lE+07 - 2.2E+07 l I-130 4.2E+05 8.6E+05 4.4E+05 9.4E+07 1.3E+06 - 4.0E+05 I-131 3.1E+08 3.IE+08 1.8E+08 1.0E+11 5.1E+08 - 2.7E+07 I-132 1.6E-01 2.8E-01 1.3E-01 1.3E+01 4.4E-01 - 3.4E-01 l I-133 4.lE+06 5.lE+06 1.9E+06 9.5E+08 8.5E+06 - 2.lE+06 I-134 2.0E-12 3.7E-12 1.7E-12 8.5E-Il 5.7E-12 - 2.5E-12 I-135 1.3E+04 2.3E+04 1.1E+04 2.IE+06 3.6E+04 -
- 1. 8E+04 CS-134 1.2E+10 1.9E+10 4.1E+09 -
6.0E+09 2.2E+09 1.0E+08 CS-136 4.6E+08 1.3E+09 8.2E+08 - 6.7E+08 1.0E+08 4.4E+07 CS-137 1.8E+10 1.7E+10 2.6E+09 - 5.7E+09 2.0E+09 1.lE+08 BA-139 1.1E-07 5.7E-11 3.lE-09 - 5.0E-Il 3.4E-11 6.2E-06 BA-140 5.4E+07 4.7E+04 3.lE+06 - 1.5E+04 2.8E+04 2.7E+07 LA-140 9.4E+00 3.3E+00 1.0E+00 - - - 9.1E+04 LA-142 2.0E-11 6.3E-12 2.0E-12 - - - 1.2E-06 CE-141 9.7E+03 4.hE+03 7.2E+02 - 2.lE+03 - 6.0E+06 CE-143 9.0E+01 4.9E+04 7.lE+00 - 2.lE+01 - 7.2E+05 CE-144 8.2E+05 2.6E+05 4.4E+04 - 1.4E+05 - 6.7E+07 PR-143 3.3+02 9.8E+01 1.6E+01 - 5.3E+01 - 3.5E+05 EN1-ll600-Il8 2 of 3 Revision 3 -Iheember 1983
O O SNPS-1 ODCM O TABLE 3.5-10 (CONT'D) Nuclide -Bone. Liver T. Body ' Thyroid Kidney Lung .GI-LLI , ND-147 2.lE+02 1.7E+02 1.3E+01 - 9.lE+01 - 2.6E+05 W-187 1.4E+04' 8.3E+03 3.7E+03 - - - 1.2E+06 NP-239 8.3E+00 6.0E-01 4.2E-01 - 1.7E+00 - 4.4E+04 (1) The dash (-) indicates insufficient data or that the dose factor is < 1.0E-20. I l l BN1-11600-Il8 3 of 3 Revision 3 - December 1983
f} O,rx v L/ SNPS-1 ODCM TABLE 3.5-11 P og3 CHILDINGESTIONOFCgAT'SMILKDOSERATECONVERSIONFACTORS m (arem/yr/p Ci/sec) Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI F-18 3.0E-04 - 3.3E-05 - - - 8.8E-06. NA-24 5.2E+05 5.2E+05 5.2E+05 5.2E+05 5.2E+05 5.2E+05 5.2E+05 P-32 4g+10 2.lE+09 1.7E+09 - - - 1.2E+09 CR-51 E - 5.5E+03 3.lE+03 8.3E+02 5.6E403 2.9E+05 MN-34 - 1.3E+06 3.4E+05 - 3.6E+05 - 1.lE+06 MN-56 - 7.5E-04 1.7E-04 - 9.0E-04 - 1.lE-01 FE-55 7.5E+05 4.0E+05 1.2E+05 - - 2.3E+05 7.4E+04 FE-59 7.0E+05 1.IE+06 5.7E+05 - - 3.3E+05 1.2E+06 CO-58 - 6.8E+05 2.lE+06 - - - 3.9E+06 CO-60 - 2.8E+06 8.2E+06 - - - 1.5E+07 NI-63 2.2E+09 1.2E+08 7.4E+07 - - - 7.9E+06 NI-65 1.lE-01 1.lE-02 6.2E-03 - - - 1.3E+00 CU-64 - 4.2E+03 2.5E+03 - 1.0E404 - 2.0E+05 ZN-65 2.9E+08 7.8E+08 4.9E+08 - 4.9E+08 - 1.4E+08 l ZN-69M 3.0E+03 4.3E+03 3.9E+02 - 2.6E+03 - 2.7E+05 l BR-83 - - 2.8E-02 - - - - I RB-86 - 4.7E+08 2.9E+08 - - - 3.1E+07 SR-89 6.3E+09 - 1.8E+08 - - - 2.4E+08 SR-90 1.4E+11 - 3.5E+10 - - - 1.9E+09 SR-91 1.3E+05 - 4.9E+03 - - - 2.9E+05 SR-92 2.2E+00 - 8.9E-02 - - - 4.2E+01 Y-90 1.9E+01 - 5.0E-01 - - - 5.3E+04 Y-91M 1.8E-20 - - - - 3.4E-17 Y-91 2.lE403 - 5.7E+01 - - - 2.9E+05 Y-92 1.5E-05 - 4.2E-07 - - - 1.7E+01 Y-93 6.lE-02 - 1.7E-03 - - - 9.lE+02 ZR-95 2.lE+02 4.7E+01 4.2E+01 - 6.7E+01 - 4.9E+04 ZR-97 1.lE-01 1.6E-02 9.2E-03 - 2.2E-02 - 2.4E+03 BN1-11600-119 1 of 3 Itevision 3 - Iheenber 1963
,. m p \.
SNPS-1 ODCM TABLE 3.5-11 (CONT'D) Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI NB-95 1.7E+04 6.6E+03 4.7E+03 - 6.2E+03 - 1.2E+07 MO-99 - 4.7E+06 1.2E+06- - 1.0E+07 - 3.9E+06 TC-99M 8.1E-01 1.6E+00 2.6E+01 - 2.3E+01 8.0E-01 9.0E+02 RU-103 2.3E+02 - 8.9E+01 - 5.8E+02 - 6.0E+03 RU-105 2.2E-04 - 8.lE-05 - 2.0E-03 - 1.5E-01 RU-106 -5.8E+03 - 7.3E+02 - 7.9E+03 - 9.lE+04 AG-110M 1.3E+07 9.lE+06 7.3E+06 - 1.7E+07 - 1.1E+09-SB-124 1.5E+06 2.9E+04 6.0E+05 3.7E+03 - 1.2E+06 4.3E+07 TE-125M 4.6E+06 1.2E+06 6. lE405 1.3E+06 - - 4.4E+06 TE-127M 1.5E+07 4.lE+06 1.8E+06 3.6E+06 4.3E+07 - 1.2E+07 TE-127 1.8E+02 4.8E+01 3.8E+01 1.2E+02 5.lE+02 - 7.0E+03' TE-129M 1.6E+07 4.4E+06 2.4E+06 5.0E+06 4.6E+07 - 1.9E+07 TE-129 9.3E-11 2.6E-11 2.2E-Il 6.6E-Il 2.7E-10 - 5.8E-09 TE-131M 9.4E+04 3.3E+04 3.5E+04 6.7E+04 3.2E+05 - 1.3Et06 TE-132 6.0E+05 2.7E+05 3.2E+05 3.9E+05 2.5E+06 - 2.7E+06 I-130 5.lE+05 1.0EiO6 5.3E+05 1.lE+08 1.5E+06 - 4.8E+05 I-131 3.7E+08 3.7E+08 2.lE+08 1.2E+11 6.lE+08 - 3.3E+07 I-132 1.9E-01 3.4E-01 1.6E-01 1.6E+01 5.2E-01 - 4.0E-01 1-133 5.0E+06 6.lE+06 2.3E+06 1.lE+09 1.0E+07 - 2.5E+06 I-134 2.4E-12 4.4E-12 2.0E-12 1.0E-10 6.8E-12 - 3.0E-12 I-135 1.6E+04 2.8E+04 1.3E+04 2.5E+06 4. 3E404 - 2.lE+04~ l CS-134 3.6E+10 5.8E+10 1.2E+10 - 1.8E+10 6.5E+09 3.lE+08 ! CS-136 1.4E+09 3.8E+C9 2.5E+09 - 2.0F+09 3.0E+08 1.3E+08 l CS-137 5.5E+10 5.2E+10 7.7E+09 - 1.7E+10 6.lE+09 3.3E+08 l BA-139 1.3E-08 6.8E-12 3.7E-10 - 6.0E-12 4.0E-12 7.4E-07 BA-140 6.4E+06 5.6E+03 3.8E+05 - 1.8E+03 3.4E+03 3.3E+06 LA-140 1.1E+00 3.9E-01 1.2E-01 - - - 1.IE+04 LA-142 2.4E-12 7.5E-13 2.4E-13 - - - 1.5E-07 CE-141 7.0E+03 3.5E+03 5.2E+02 - 1.5E+03 - 4.4E+06 CE-143 6.5E+01 3.5E+04 5.lE+00 - 1.5E+01 - 5.2E405 CE-144 5.9E+05 1.8E+05 3.1E+04 - 1.0E+05 - 4.8E+07 PR-143 3.9E+01 1.2E+01 1.9E+00 - 6.4E+00 - 4.2E+04 I BN1-Il600-119 2 of 3 Revision 3 - December 1983 '
- - - - - - l
. c
- - - - - _ . _ - _ _ _ _ ____o
. _. _ _ _ _ . ~ . . . _. _ _ . . __ _ ,. . . . ._ . _ . .- . . .
1 l
, 5
, SNPS-1 ODCM ' f j TABLE 3.5--11 (CONT'D) l .i , Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI l ND-147 2.5E+01 2.0E+01 1.5E+00 - 1.1E+01 -
.3.2E+04-l W-187 1.7E+03 1.0E+03 4.5E+02- - - -
1.4E+05 ! NP-239 1.0E+00 7.2E-02 5.1E-02 -- 2.1E-01 - 5.3E+03 } (1) The dash (-) indicates insufficient data or 'that the dose factor is < 1.0E-20. I 1 A I 1 i l l i I
- l t
I { BN1-11600-119 3 of 3 hvision 3 -Ihcamber 1983 i i i . I -- ,- _
TABLE 3.5-12 P ogj CHILD INGESTION OF MEAT DOSE RATE CONVERSION FACTORS m 2 (mrem /yr/p Ci/sec) Nuclide Bone Liver T. Body Thyroid Kidney Ltmg GI-LLI 1 NA-24 9.5E-04 9.5E-04 9.5E-04 9.5E-04 9.5E-04 9.5E-04 9.5E-04 P-32 3 1.7E+08 1.4E+08 - - - 9.8E+07 g+09 CR-51 - 4.0E+03 2.2E+03 6.lE+02 4.lE+03 2.lE+05 l MN-54 - 4.lE+06 1.lE+06 - 1.lE+06 - 3.4E+06 l l FE-55 2.4E+08 1.3E+08 3.9E+07 - -' 7.lE+07 2.3E+37 FE-59 1.7E+06 2.8E+08 1.4E+08 - - 8.0E+07 2.9E+08 Co-58 - 7.6E+06 2.3E+07 - - - 4.5E+07 l CO-60 - 3.7E+07 1.lE+08 - - - 2.lE+08 NI-63 1.8E+09 9.6E+07 6.IE+07 6.5E+06 CU-64 - 2.0E-07 1.2E-07 - 4.7E-07 - 9.2E-06 "N-65 2.2E+08 5. 9 E+08 3.7E+08 - 3.7E+08 - 1.0E+08 ZN-69M 1.0E-06 1.5E-06 1.4E-07 - 9.0E-07 - 9.3E-05 RB-86 - 2.6E+08 1.6E+08 - - - 1.7E+07 SR-89 2.2E+08 - 6.2E+06 - - - 8.5E+06 SR-90 6.2E+09 - 1.6E+09 - - - 8.3E+07 SR-91 1.lE-10 - 4.2E-12 - - - 2.5E-10 Y-90 8.3E+01 - 2.2E+00 - - - 2.4E+05 Y-91 8.2E+05 - 2.2E+04 - - - 1.lE+08 Y-93 5.lE-12 - 1.4E-13 - - - 7.6E-08 ZR-95 1.2E+06 2.7E+05 2.4E+05 - 3.9E+05 - 2.8E+08 ZR-97 1.3E-05 1.9E-06 1.lE-06 - 2.7E-06 - 2.8E-01 l l l BN1-Il600-120 1 of 3 lbvision 3 - lhember 1983
- y. y _
( b SNPS-1 ODCM TABLE 3.5-12 (CONT'D) i Nuclide Bone Liver T. Body Thyroid Kidney Lung- CI-LLI-NB-95 1.4E+06 5.4E+05 3.8E+05 - 5.0E+05- - 9.9E+08 MO-99 - 5.6E+04 1.4E+04 - 1.2E+05 - 4.6E+04 TC-99M - - 1.lE-19 - - - 3.8E-18 RU-103 7.0E+07 - 2.7E+07 - 1.8E+08 - 1.8E+09 RU-106 2.3E+09 - 2.9E+08 - 3.2E+09 - 3.6E+10 1G-110M 4.5E+06 3.0E+06 2.4E+06 - 5.7E+06 - 3.6E+08 SB-124 3.4E+06 6.4E+04 1.3E+06 8.2E+03 - 2.6E+06 9.6E+07 TE-125M 3.0E+08 8.0E+07 3.9E+07 8.3E+07- - - 2.9E+08 TE-127M 1.1E+09 2.9E+08 1.3E+08 2.6E+08 3.lE+09 - 8.7E+08 TE-127 2.0E-10 5.5E-11 4.4E-11 1.4E-10 5.8E-10 - 8.0E-09 TE-129M 8.6E+08 2.4E+08 1.3E+08 2.8E+08 2.5E+09 - 1.0E+09 TE-131M 3.5E+02 1.2E+02 1.3E+02 2.5E+02 .12E+03 - 4.9E+03 i TE-132 1.0E+06 4.6E+05- 5.5E+05 6.6E+05 4.2E+06 - 4.6E+06 I-130 8.7E-07 1.7E-05 9.0E-07 1.9E-04 2.6E-06 - 8.2E-07 I-131 3.9E+06 3.9E+06 2.2E+06 1.3E+09 6.4E+06 - 3.5E+05 I-133 1.4E-01 1.7E-01 6.6E-02 3.2E+01 2.9E-01 - 7.0E-02 I-135 1.6E-17 2.8E-17 1.3E-17 2.5E-15 4.3E-17 - 2.1E-17 CS-134 4.8E+08 7.9E+08 1.7E+08 - 2.5E+08 8.8E+07 4.3E+06 CS-136 7.3E+06 2.0E+07 1.3E+07 - 1.1E+07 1.6E+06 7.0E+05- 1 CS-137 7.5E+08 7.2E+08 1.lE+08 - 2.4E+08 8.5E+07- 4.5E+06 BA-139 - - - - - - - BA-140 2.06:07 1.8E+04 1.2E+06 - 5.7E+03 1.0E+04 1.0E+07 l LA-140 2.8E-02 9.6E-03 3.'0E-03 - - - 2.7E+02 CE-141 9.9E+03 4.9E+03 7.3E+02 - 2.2E+03 - 6.1E+06 l CE-143 1.5E-02 8.4E+00 1.2E-03 - 3.5E-03 - 1.2E+02 CE-144 1.2E+06 3.7E+05 6.2E+04 - 2.0E+05 - 9.5E+07 PR-143 1.5E+04 4.6E+03 7.6E+02 - 2.5E+03 - 1.6E+07 BN1-Il600-120 2 of 3 Revision 3 - December 1983
.=____________ -
--- - --- - - -- - y s
N SNPS-1 ODCM I TABLE 3.5-12 (CONT'D) Nuclide Bone Liver T. Body- Thyroid Kidney ,Lgu GI-LLI
-5.4E+03 4.4E+03 ND-147 3.4E+02 -
2.4E+03 - 6.9E+06 1.6E-02 9.7E-03 4.4E-03 1.4E+00. W-187. - - - NP-239 2.lE-01 .1.5E-02 1.lE-02 - 4.4E-02 -
'l.lE+03 (1) The dash (-) indicates insufficient data or that. the dose factor is < l.0E-20. .
4
)
l l i l l l BN1-ll600-120 3 of 3 Revision 3 - Mr 1983
1,,,) (/- ~) - (, xV)
\s L./ :
SNPS-1 ODCM - TABLE 3.5-13 P og) INFANTINGESTIONOFg0W'SMILKDOSERATECONVERSIONFACTORS m (arem/yr/p Ci/sec) i Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI F-18 3.5E-03 - 3.9E-04 - - - 1.0E-04 NA-24 7.5E+06 7.5E+06 7.5E+06 7.5E+06 7.5E+06 7.5E+06 7.5E+06 P-32 4.5E+09 2.9E+09 - - - 1.0E+09 CR-51
'7g+10 I -
7.3E+04 4.7E+04 1.0EM4 9.2E+04 2.1E+06 MN-54 - 2.0E+07 4.5E+06 - 4.4E+06 - 7.3E+06 MN-56 - 1.5E-02 2.6E-03 - 1.3E-02 - 1.4E+00 , FE-55 7.0E+07 4.5E+07 1.2E+07 - - 2.2E+07 5.8E+06 I FE-59 1.0E+08 1.8E+08 7.0E+07 - - 5.2E+07 8.4E+07 i CO-58 - 1.1E+07 2.8E+07 - - - 2.8E+07 ) CO-60 - 4.8E+07 1.1Et08 - - - 1.1E+08 NI-63 2.1E+10 1.3E+09 7.5E+08 - - - 6.6E+07 NI-65 2.0EMO 2.3E-01 1.0E-01 - - - 1.7E+01 CU-64 - 9.3E+04 4.3E+04 - 1.6E+05 - 1.9E+06 ZN-65 3.3E+09 1.lE+10 5.2E+09 - 5.5E+09 - 9.5E+09 ZN-69M 5.2E+04 9.4E+04 7.0E+03 - 3.9E+04 - 7.7E+06 BR-83 - - 4.9E-01 - - - - RB-86 - 1.0E+10 5.0E+09 - - - 2.6E+08 SR-89 5.7E+09 - 1.6E+08 - - - 1.2E+0S SR-90 7.2E+10 - 1.8E+10 - - - 9.0E+08 SR-91 1.3E+05 - 4.7EM3 - - - 1.5E+05 SR-92 2.2E+00 - 8.3E-02 - - - 2.4E+01. Y-90 3.3E+02 - 8.8E+00 - - -
'4.5E+05 Y-91M 3.lE-19 -
1.lE-20 - - -
'1.0E-15 Y-91 3.3E+04 -
8.9E+02 - - - 2.4E+06 4.9E+00 Y-92 2.oE-04 - 7.3E-06 - - - Y--9 3 1.lE+00 - 2.9E-02 - - - 8.6E43 ZR-95 3. lEM3 7.7E+02 5.4E+02 - 8.3E+02 - 3.8E+05 l l i l BN!-ll600-121 1 of 3 Revision 3 - Decader 1983
/ j /n 't Q C /-
SNPS-1 ODCM
\._./ '
TABLE.3.5-13 (CONT'D) Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI ZR-97 1.9E+00 3.3E-01 1.SE-01 - 3.3E-01 - 2.1E+04 NB-95 2.6E+05 1.1E+05 6.3E+04 - 7.8E+04 - 9.2E+07-MO-99 - 1.0E+08 2.0E+07 - 1.5E+08' - 3.3E+07 TC-99M 1.3E+01 2.8E+01 3.6E+02 - 3.0E+02 1.5E+01 8.lE+03 RU-103 3.9E+03 - 1.3E+03 - 8.lE+03 - 4.7E+04 RU-105 3.9E-03 - 1.3E-03 - 2.9E-02 - 1.6E+00 RU-106 1.0E+05 - 1.3E+04 - 1.2E+05 - 7.6E+05 AG-110M 2.1E+08 1.5E+08 1.0E+08 - 2.2E+08 - 7.8E+09-SB-124 1.3E+07 2.4E+05 5.0E+06 3.0E+04 - 9.8E+06 3.6E+08 TE-125M 7.8E+07 2.6E+07 1.lE+07 2.6E+07 - -
- 3. 7 E+07 TE-127M 2.5E+08 8.4E+07 3.lE+07 7.3E+07 6.3E+08 -
1.0E+08 TE-127 3.2E+03 1.1E+03 6.8E+02 2.6E+03 7.7E+03 - 6.7E+04 1 TE-129M 2.7E+08 9.2E+07 4.lE+07 1.0E+08 6.7E+08 - 1.6E+08 I TE-129 1.6E-09 5.7E-10 3.8E-10 1.4E-09 4.1E-09 - 1.3E-07 ! TE-131M 1.7E+06 6.7E+05 5.5E+05 1.4E+06 4.6E+06 - 1.1E+07 l TE-132 1.0E+07 5.lE+06 4.8E+06 7.5E+06 3.2E+07 - 1.9E+07 1 I-130 8.7E+05 1.9E+06- 7.7E+05 2.2E+08 2.1E+06 - 4.1E+05 , I-131 6.4E+08 7.5E+08 3.3E+08 2.5E+11 8.8E+08 - 2.7E+07 l I-132 3.2E-01 6.5E-01 2.3E-01 3.IE+01 7.3E-01 - 5.3E-01 I-133 8.7E+06 1.3E+07 3.7E+06 2.3E+09 1.5E+07 - 2.2E+06 I-134 4.lE-12 8.5E-12 3.0E-12 2.0E-10 9.5E-12 - 8.8E-12 l I-135 2.7E+04 5.4E+04 2.0E+04 4.8E+06 6.0E+04 - 1.9E+04 CS-134 1.9E+10 3.6E+10 3.6E+09 - 9.2F+09 3.8F+09 9.7E+07 CS-136 9.0E+08 2.6E+09 9.9E+08 - 1.IE+09 2.2E+08 4.0E+07 CS-137 2.9E+10 3.4E+10 2.4E+09 - 9.lE+09 3.7E+09 1.lE+08 BA-139 2.3E-07 1.5E-10 6.6E-09 - 9.1E-11 9.lE-11 1.4E-05 BA-1,40 1.1E+08 1.lE+05 5.7E+06 - 2.6E+04 6.8E+04 2.7E+07 LA-140 2.0E+01 7.7E+00 2.0E+00 - - - 9.1E+04 LA-142 4.1E-11 1.5E-Il 3.6E-12 - - - 2.6E-06 CE-141 1.9E+04 1.2E+04 1.4E+03 - 3.6Et03 - 6.1E+06 CE-143 1.9E+02 1.3E+05 1.4E+01 - 3.7E+01 - 7.4E+05 CE-144 1.2E+06 4.8E405 6.6E+04 - 1.9E+05 - 6.7E+07 PR-143 6.8E+02 2.5E+02 3.4E+01 - 9.4E+01 - 3.6E+05 BN!-Il600-121 2 of 3 Hevision 3 - Decenber 1983
I SNPS-1 ODCM TABLE 3.5-13 (CONT'D) Nuclide Bone Liver T. Body Thyrofd Kidney Lung CI-LLI ND-147 4.IE+02 4.2E+02 2.6E+01 - 1.6E+02 - 2.6E+05 W-187 2.9E+04 2.lE+04 7.lE+03 - - - 1.2E+06 NP-239 1.8E+01 1.6E+00 8.9E-01 - 3.lE+00 - 4.6E+04 1 l (1) The dash (-) indicates insufficient data or that the dose factor is < l.0E-20. l I l l I l I BN!-11600-121 3 of 3 Revision 3 -Ibember 1983
p.s 7 ~~s d U SNPS-1 ODCM d TABLE 3.5-14 P ogy , INFANT INGESTION OF C0AT'S MILK DOSE RATE CONVERSION FACTORS m 2 (mrem /yr/ p Ci/sec) Nuclide Bone Liver T. Body Thyroid Kidney Lung 'GI-LLI b F-18 3.0E-04 - 3.3E-05 - - .- 8.8E-06 I NA-24 9.1E+05 9.1E+05 9.IE+05 9.1E+05 9.1E+05 9.1E+05 9.1E+05 P-32 9 5.4E+09 3.5E+09 - - - 1.2E+09 CR-51 -{+10 - 8.7E+03 5.7E+03 1.2E+03 1.lE+04 2.5E+05 MN-54 - 2.4E+06 5.4E+05 - 5.3E+05 - 8.8E+05' MN-56 - 1.8E-03 3.lE-04 - 1.6E-03 - 1.7E-01 FE-55 9.1E+05 5.9E+05 1.6E+05 - - 2.9E+05 7.5E+04 FE-59 1.3E+06 2.3E+06 9.1E+05 - - 6.8E+05 1.lE+06 l CO-58 - 1.4E+06 3.4E+06' - - - - 3.4E+06'- l C0-60 - 5.7E+06 1.3E+07 - - - 1.4E+07 l NI-63 2.6E+09 1.6E4 08 8.9E+07 - - - 7.9E+06 l NI-65 2.4E-01 2.7E-02 1.2E-02 - - - 2.1E+00 CU-64 - 1.0E+04 4.8E+03 - 1.8E+04 - 2.IE+05 ZN-65 3.9E+08 1.4E+09 6.2E+08 - 6.6E+08 - 1.lE+09 ZN-69M 6.3E+03 1.1E+04 e.6E+02 - 4.7E+03 - 9.2E+05 BR-83 - - 5.8E-02 - - - RB-86 - 1.2E+09 6.0E+08 - - - 3.1E+07 SR-89 1.2E+10 - 3.4E+08 - - - 2.5E+08 SR-90 1.5E+11 - 3.9E+10 - - - 1.9E+09 SR-91 2.7E+05 - 9.9E+03 - - - 3.2E+05 SR-92 4.7E+00 - 1.7E-01 - - - 5.lE+01 Y-90 3.9E+01 - 1.lE+00 - - - 5.4E+04 Y-91M 3.7E-20 - - - - - 1.2E-16 Y-91 4.0E+03 - 1.lE+02 - - - 2.9E405 Y-92 3.lE-05 - 8.7E-07 - - - 5.9E-01 Y-93 1.3E-01 - 3.5E-03 - - - 1.0E+03 ZR-95 3.8E402 9.2E+01 6.5E+01 - 9.9E+01 - 4.6E+04 ZR-97 2.3E-01 3.9E-02 1.8E-02 - 4.0E-02 - 2.5E+03 BN-ll600-122 1 of 3 Revision 3 - Decenber 1983
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-SNPS-1 00CM TABLE 3.5-14'(CONT'D)
Nuclide Bone Liver T. Body -Thyroid Kidney Inng CI-LLI-PR-143 8.lE+01 3.0E+01 4.0E+00 - 1.lE+01 - 4.3E+04 ND-147 4.9E+01 5.0E+01 3.lE+00 - 1.9E+01 - 3.2E+04 W-187. 3.5E+03 2.5E+03 8.5E+02 - - 1.4E+05 -NP-239 2.lE+00 1.9E-01 1.lE-01 - 3.8E-01 - 5.5E+03-(1) The dash (-) indicates insufficient data or that the dose factor is < 1.0E-20.
)
i l i BN-11600-122 3 of 3 kvision 3 -Iheenher 1983
( O O
-SNPS-1 ODCM TABLE"3.5-15 P
gj CHILD INHALATION AND INCESTION OF LEAFY AND STORED VEGETABLES DOSE RATE CONVERSION FACTORS (arem per pCi)
. I Nuclide Bone Liver T. Body Thyroid Kidney ' Lung CI-LLI H-3 -
1.4-6 1.4-6 1.4-6 1.4-6 11.4-6 1.4-6' C-14* 9.6-4 1.9-4 1.9-4 1.9-4 1.9-4 1.9-4 1.9-4 Note:
- For short term releases such as from air removal pump or from containment drywell purge vent C-14 values should be multiplied by 2.
t BN1-11600-123 1 of 1 kvision 3 - Decenter 1983
SNPS-1 ODCM TABLE 3.5-16 P gj CHILD INCESTION OF GOAT'S MILK DOSE RATE CONVERSION FACTORS (mrem per pCi) ; j Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI H-3 - 8.6-7 8.6-7 8.6-7 8.6-7 8.6-7 8.6-7 C-14* 4.7-4 8.9-5 8.9-5 8.9-5 8.9-5 8.9-5 8.9-5
*See ?bte in Table 3.5-15 i
EN1-Il60()-125 1 of 1 Pevision 3 - lhcomber 1983
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- 3.6 OPERATION OF VENTILATION EXHAUST TREAT)ENT SYSTEM The Ventilation Exhaust Treatment System (see Figure 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 l l BN1-11600.02-112 3.6-1 Revision 1 - August 1983
O O O STATION VENTILATION EXHAUST CHEM. LABORATORY EXH.AUST HEPA 4300 CFM J i CHEM. LABORATORY FILTER l
^
DRYWELL PURGE AND 1200 CFM PRIMARY ' CONTAINMENT HEPA FILTERS BUILDING VENTIL ATION H EPA 40,000 CFM F ILTE R R ADWA STE d ' BUILDING j TANK VENT AND 2270 CFM RADWASTE _ TANK HEPA l VENT , FILT E R S OFFGAS TREATMENT j SYSTEM OFFGAS TRE ATMENT EXHAUST HEPA - (CHARCOAL) - p p FIGURE 3.6-1 l VENTILATION EXHAUST TREATMENT SYSTEM SHOREH AM NUCLE AR POWER STATION - UNIT-1 0FFSITE DOSE CALCULATION MANUAL l REVISION 1- AUGUST 1983
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- SNPS-1 ODCM O 3.7 . TOTAL DOSE FOR THE URANIUM FUEL CYCLE
' To comply with Section 3.11.4 of the RETS which implements 40CFR190, radiation doses shall be limited as follows:
The dose or dose commitment to a member of the public, due_to releases of radioactivity and radiation, from uranium fuel cycle sources shall be-limited to 25 area, or leas, to the total body and/or any organ (except the thyroid, which shall ie limited to 75 mrem, or less), over any 12 ! consecutive months.' , 3.7.1 Sources of Radiation and Radioactivity The uranium fuel cycle is defined in 40CFR190 to include: p a. operations of milling of uranium ore,
- b. chemical conversion of uranium,
- c. . isotopic enrichment of uranium,
- d. fabrication of. uranium fuel,
. e. generation of electricity by a nuclear power plant .using uranium
. fuel, and.
. f. reprocessing of spent uranium fuel.
- The maximum individual doses due to each of the processing f acilities for items a, b, c, d,eand-f above'are required to - be less than - 10CFR20 limits.
.Therefore, the dose contribution to any person living in the Shoreham service
- - area due to the above f acilities, which are all more than 125 kilometers distance away, is expected to be negligible compare to 40CFR190 limits.
The only radiological source of concern- will be due to item e above. The nearest nuclear power plant 'using uranium fuel is more than 75 kilometers away. 3.7.2 Radiological Impact of Generation of Electricity _ The generation of electricity using a nuclear power plant results in radioactivity released in gaseous and liquid effluents. The dose rate assessment of these is done in Section 3.3. The radiological impact of direct radiation -(including skyshine) from the plant can be determined by
- measurement. The direct radiation measuring devices (TLD systems) are provided. by the Radiological Environmental Monitoring Program (REMP)' and listed in Tables 5-1 and 5-4.
' Dose regiatered by the TLDs will be added to the doses calculated in Sections 3.1.1 (Dose From Liquid Effluent) and 3.5.1 (dose to maximum individual due to inhalation and ingestion from gaseous effluents) to determine the total body
- . dose due to all sources'of radiation in the uranium fuel cycle.
- BN1-11600.02-112 3.7-1 Revision 2 - September 1983 4 'v*-' y*' ,9- yo7--.rge-p.i-.-e.p-- 4yi ye9.i--y w 4.-pg, ,y.*4 -*yD'N*W-PW tWM-'WPT=W -'*W#w tWWp'sy M&4'PW*
SNPS-1 ODCM SECTION 4' RECEPTOR LOCATIONS, _ }ETEOROLOGY, 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 calculated ' dilution f actor of 8.85 is used in the. backup method.- 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 of October 1, 1973 through September
-30, 1975 and 1 the Final Environmental Statement, NUREG-0285, dated October 1977, docket No.-50-322.
Regulatory Guide -1.109, Rev. 1 (October 1_977) methodology and parameters, l except - as noted above, .were used in the backup method dose rate conversion factors. O i 11600-112. 4-1 Revision 3 - December 1983
m- m rv
- SNFS-1 ODCM TABLE 4-1 r
~ CRITICAL RECEPTOR. LOCATIONS FOR GASEOUS EFFLUENT CALCULATIONS Technical Specification 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 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 radionuclides and Skin due to Gamma and Beta to radionuclides other than Noble C.w Noble Gas and Dose radiation other than Noble for 31 day period to any organ due Gas to radionuclides other than Noble l Cas Distance and Direction 1) Noble Gas: 457 meters, ESE 2478 meters, ESE 2478 meters, ESE l 1 of Receptor from the 366 metert, NNE Plant 2) Organ: 2478 meters, ESE l Description of Incation Location of highest Location of highest Location of Location of highest Dose Rate Dose highest Dose Dose Long Term Atmospheric 1) 6.6E-07 sec/m 3 8.44E-07 sec/m 3 1.54E-07 sec/m 3 1.54E-07 sec/m3 Dispersion Factor for 2) 1.54E-07 sec/m 3 Station Ventilation Exhaust X/0 1 Short Term Atmospheric 1) 3.6E-06 sec/m 3 1.83E-06 sec/m 3 4.22E-07 sec/m 3 4.22E-07 sec/m 3 Dispersion Factor for 2) 4.22E-07 sec/m 3 Air Removal Pump x/0 2 ' 3 3 3 3 Short Term Atnospheric 1) 3.6E-06 sec/m 1.83E-06 sec/m 4.22E-07 sec/m 4.22E-07 sec/m
- 2) 4.22E-07 sec/m 3 Dispersion Factor for
- Containment Drywell Purge X/0 3 i~
Revision 3 - December 1983 1 of 2 BN1-11600.02-109
i .. O r O ) . SNPS-1 ODCM TABLE 4-1 (CONT'D). l Long Term Relative. 1) NA 3.08E-09 m-2 NA 3.08E-09m-2 l Deposition Factor for. 2) 3.08E-09 m-2 j Station Ventilation Exhaust D/0 1 } Short Term Relative 1) NA NA. 8.47E-09 m-2 8.47E-09 m-2 i Deposition Factor for 2) 8.47E-09 m-2 Air Removal Pump D/0 2 Short Term Relative 1) NA NA 8.47E-09 m-2 8.47E-09 m-2 Deposition Factor for 2) 8.47E-09 m-2 f Containment Drywell Purge D/0 3 i i i 1 1 - l l I i i
' Revision 3 - December 1983 2 of 2 BN1-11600.02-109 ,
._ _. ._ . ~ . _ . -
t 4 SNPS-1 ODCM SECTION 5 i RADIOLOGICAL ENVIRON) ENTAL PONITORING 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 2, respectively. The number and frequency for sampling at these locations is given in Table 5-1 which is taken from -Technical Specification Table 3.12.1-1. Radiological Environmental Monitoring Program monitoring stations are given in Tables 5-2, 5-3, 5-4, and 5-5. .i
't.1 t
e i i BN1-11600.02 5-1 Revision 1 - August 1983
.m.. . . _ . _ . . . . _ . _ . . _ ~ _._ . . _ - _ . _ . . _ . . , _ _ . _ _ _ _ . - . _ - _ _ . . _ _ . . . _ . . _ , . . _._ ,__- ~
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. , \j b. ^ SNPS-1 ODCM TABLE'5-1 l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM * (SAMPLING AND, COLLECTION FREQUENCY) *
~
i EXPOSURE PATHWAY - SAMPLING AND TYPE AND FREQUENCY j- -AND/OR SAMPLE .SAMPLES'AND NUMBER OFSAMPLE REPRESENTATIVE LOCATION . a-COLLECTION FREQUENCY OF ANALYSISt , ) 1. DIRECT RADIATIOND ~ 36 routine monitoring stations, Ouarterly. Gamma dose' quarterly.~ j- DRI-DR36, either with ; two or - more dosimeters or with one. instrument:for measuring and recording dose rate. continuously, . j placed as follows: i , j a. An inner ring of stations, one in. each meteorological sector in the t ! general ' area of the SITE BOUNDARY, , { DR1-DRl6; i
. p. An outer ring of stations, .one in ;
each meteorological. sector in the 6- to 8-km range from the site, , DR17-DR25; - i c. The balance of the stations, j DR26-DR36, to . be placed in special interest areas such as population centers, nearby-l residences, schools, and in 1 i or 2 areas to serve as control stations. 4 d
*The number, media, frequency, and location of samples may vary from site to site. This table presents an
} acceptable minimum program for a site at which each ' entry is applicable. Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's dose and. should be included in the sampling program. The code letters in parentheses, e.g., DR1, A1, provide one way i of defining generic sample locations -in this' specification that can be used to identify the specific l 1ccations.in the map (s) and tables in.the ODCM. i
- BN1-llq00.02-Il3 1 of 5 Revision 17- August 1983
._ _ _ ._ _. -_ - ~ . - , --
_ . . _. - . . . ~, . __ __ ._ _ SNPS-1'ODCM TABLE 5-1 (CONT'D) EXPOSURE. PATHWAY ' NUMBER OF REPRESENTATIVE SAMPLING AND ~ TYPE AND FREQUENCY ~ AND/OR SAMPLE SAMPLES AND SAMPLE LOCATION a. COLLECTION FREOUENCY. OF ANALYSIS t
- 2. ' AIRBORNE-t i Radioiodine and' Samples from 5 locations,-Al-A5: Continuous. sampler Radioiodine Cannister:
Particulates operatin with sample I-131 analysis weekly. l 3 samples , Al-A3* from close collection weekly, or
- to the 3 SITE BOUNDARY locations, more frequently if i -in different sectors, of the' required by dust Particulate Sampler
j highest. calculated annual average loading. Gross beta radioactivity
- groundlevel D/O. . analysis folle gng.
! filter change;:
- I sample, A4, from the vicinity' Gamma isotopic analysis
- of a come.nnity having the highest of. composite (by.
calculated annual-average groundlevel location). j D/O. i ! I sample, A5, from.a control location,
.as for example 15-30 km distant and in j the . least' prevalent wind direction.
r
-3. WATERBORNE 1
- a. Surface I sample control, WAl Grab-sample semi- Gamma isotopic analysis'
! (Long Island I sample discharge, WA2 or WA3 annually, and tritium analysis f Sound) semi-annually. ; b. Ground Samples from 1 or 2 sources, Wbl, Quarterly. Casuna isotopic
- and Wb2, only if likely to be affected. tritium analysis
! quarterly.
I j c. Sediment form I sample from downstream area with ' Semi-annually. Gamma isotopic' analysis
- i shoreline existing or potential recreational semi-annually.
! value, Wdl. 1 i *The first and second highest D/0 sectors have radioiodine and particulate samples. -The third highest D/O j sector at the SITE BOUNDARY is approximately 150 ft from the first highest sector, i i i t
! BN1-11600.02-Il3 2' of 5 Revision 1 - August 1983 i
I. . < . , -, ,
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L) d_ SNPS-1 ODCM (J\_ TABLE 5-1 (CONT'D) EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND: TYPE AND FREQUENCY
, AND/OR SAMPLE - SAMPLES-AND SAMPLE LOCATIONa COLLECTION FREQUENCY OF ANALYSIS
- 4. INGESTION i a. Milk Samples from milking animals in Semi-monthly when Gamma isotopic
- and I-131
!. location, Ial, within 5 km distance animals are on . analysis semi-monthly when l having the highest dose potential. pasture, monthly at animals are on pasture; If there are none, then -1 sample other times. . monthly at other times. from milking animals in each of
- 3 areas, Ial, between 5 to . 8 km
] 4 distant where doses are calcu-j- lated go be greater than 1 mrem per yr , or if there are none
- available within 8 km, then a
. location 8 to.17 km distant will
- be used.
1 sample from milking animals at a
- control location, Ia2, 15-30 km 4
distant and not in the least prevalent wind directions. i b. Fish and I sample of each commercially and Sample semi- Gamma isotopic analysis e-Invertebrates recreationally important species in annually, on edible portions. , l vicinity of plant discharge area, Ibl - Ib2. I I sample of same species in areas not {; influenced by plant discharge, Ib3. j c. Food Products Samples of - 3 dif ferent kinds of broad At time of Gaimea Isotopic
- and leak vegetation grown nearest each of harvest.8 I-131 analysis.
two different offsite locations of I highest predicted annual average l ground-level D/Q, if milk sampling l is not performed, Icl - Ic3. i i I sample of each of the similar broad At time of Gamma isotopic * { ' 1eak vegetation grown 15-30 kra distant harvest 8 and I-131 analysis. in the least prevalent wind. direction 3 if milk sampling is not. perform, Ic3. 4 BN1-il600 .02-Il3 3 of 5 Revision 3 - December 1983
- \ .
Q SNPS-1 ODCM TABLE 5-1 (CONT'D)L TABLE NOTATION a Specific parameters of distance and direction : sector from the centerline of 'one reactor, and additional description
.where pertinent, are provided for each and every sample location in Table 3.12.1-1 in a table and figure in the ODCM. - Refer to NUREG-0133, " Preparation or Radiological Effluent Technical Specifications ' 'for Nuclear. . Power. -
Plants," October 1978, and to Radiological Assessment . Branch . Technical Position, Revision .1, November '1979. Deviations are . permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate ' reasons. If specimens _ are unobtainable due . to sampling. equipment malfunction, every effort shall be made to complete. corrective action prior to the end of the next sampling period. .All deviations from the' sampling schedule shall.be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.
~
It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at. the most desired location or time. In' these instances ' suitable alternative media .and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days -in the radiological environmental monitoring program. In lieu of _ a - Licensee Event Report and pursuant to Specification 6.9.1.9, identify the : cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining ' replacement samples in the next Semi-annual Radioactive Effluent Release Report - and also included . in the report a revised figure (s) and table for the ODCM reflecting the new location (s).- 6 b One or more instruments, such as . a pressurized ion chamber, for measuring and recording dose rate continuously may. be used in place of, or in addition to, integrating . dosimeters. For the purposes of. this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; .two or more phosphors in packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters f or measuring ' direct radiation.- The frequency of analysis or readout for . TLD systems will depend upon the characteristics of the specific system used : and should be selected to obtain optimum dose information.with minimal fading. C The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted. BN1-11600-Il3 4 of .5 Revision 1 - August 1983
m r% SNPS-1 ODCM TABLE .5-1 (CONT'D) TABLE NOTATION d Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more af ter sampling to allow for radon end thoron daughter decay. If gross beta activity in air particulate samples is ' greater than .10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on individual samples.
- Camma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that say.be attributable to the effluents from the facility.
f The dose shall be calculated-for the maximum organ and age group, using the methodology and parameters in the 0DCM. 8 If ' harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harve?.t occurs continuously, sampling shall be- monthly. Attention shall be paid to including samples of tuberous and root food products. t et BN1-ll600-113 5 of 5 Revision 1 - August 1983
SNPS-1 ODCM TABLE 5-2 RADIOLOGICAL ENVIRON) ENTAL PONITORING PROGRAM (REMP) WATERBORNE PONITORING STATIONS Location Codes
'NUREG-0473 Shoreham REMP Location Description WA1 3Cl Surface, outfall area, 2.9 mi. NE WA2 14Cl Surface, outfall area, 2.1 mi. WNW
-WA3 13G2 Surface, background area, 13.3 mi. W Wbl 2S1 Potable Water, well on site, 0.1 mi. NNE Wb2 13S2 Potable Water, well on site, 0.2 ni W Wb3 10B1 Potable Water, background well, 1.5 mi. SSW Wdi 2A4 Sediment, beach, 0.4 mi NNE
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l l i I l BN1-11600.02-112 1 of 1 Revision 3 - December 1983
SNPS-1 ODCM
.p- ..
- b TABLE 5-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
(PARTICULATES AND RADI0 IODINE) Location Codes NUREG-0473 Shoreham'REMP Location Description
. A1 6S2 Site Boundary, 0.1 mi. ESE A2- 2A2 . West end cf Creek Road, 0.2 mi. NNE A3 3Si Site Boundary, 0.1 mi, NE
'A4 7B1 Overhill Road, 1.5 mi. SE A5 11G1 MacArthur Substation, 16.6 mi. SW i
O k i i O BN1-11600.02-112 1 of 1 Revision 3 - December 1983
; SNPS-1 ODCM l
'~' '
C'D RADIOLOGICAL ENVIRONPENTAL PONITORING PROGRAM (REMP) l DIRECT RADIATION MONITORING STATIONS Location Codes NUREG-0473 Shoreham REMP Location Description DR1 ISL Beach east of intake, 0.3 mi. N DR2 2A2 West end of Creek Road, 0.2 mi. NNE. DR3 3St. Site Boundary, 0.1 mi. NE DR4 4Si Site Boundary, 0.1 mi. ENE DRS SS2 Site Boundary, 0.1 mi. E DR6 6S2 Site Boundary, 0.1 mi. ESE DR7 7A2 North Country Road, 0.7 mi. SE
, DR8 8A3 North Country Road, 0.6 mi. SSE DR9 9SL Service Road SNPS, 0.3 mi. S DR10 10A1 North Country Road, 0.3 mi. SSW i- DR11 11A1 Site Boundary, 0.2 mi. SW l DR12 12A1 Meteorological Tower, 0.9 mi, WSW DR13' 13S3 Site Boundary, 0.3 mi. W DR14 14S2 St. Joseph's Villa, 0.4 mi. WNW DR15 15Si Beach west of intake, 0.3 mi. NW
-DR16 16S2 Site Boundary 0.2 mi. NNW DR17 SD3 Wildwood State Park, 3.4 mi. E DR18 6El LILCO R0W, 4.8 mi. ESE
[.v'- DR19 7El Calverton, 5.0 mi. SE DR20 8E1 Calverton, 4.4 mi. SSE DR21 9El Brookhaven National Laboratory,
~5.0 mi. S DR22 10E1 Ridge Substation, 4.0 mi. SSW DR23 11El LILCO ROW. 4.7 mi. SW DR24 .12D1 North Shore Beach Substation, 3.7 mi. WSW DR25 13E1 Sound Way Drive, 4.5 mi. W i'
-DR26 SD1 Wildwood State Park, 3.4 mi. E DR27 SF3 Dairy Farm, 7.8 mi. E j DR28 7B1 Overhill Road, 1.5 mi. SE DR29 12G2 Flowerfield Substation,
! 15.4 mi. WSW DR30 i2G1 Central Islip Substation, l 19.9 mi. WSW DR31 11G1 MacArthur Substation, 16.6 mi. SW DR32 8G1 Wading River Road, 10.1 mi. SSE , 'DR33 6G1 Dairy Farm, 7.2 mi. ESE l DR34 6Al Sound Road, 0.7 mi. ESE l DR35 2A3 Nearest Residence, 0.3 mi. NNE l DR36 9S2 East Gate SNPS, 0.3 mi. S : 1 O BN1-11600.02-112 1 of 1 kevision 1 - August 1983 i l a - -_ . - - _ . - - - _ - - _ - - - - - - . -. .--
SNPS-1 ODCM TABLE 5-5 RADIOLOGICAL ENVIRON) ENTAL 10NITORING PROGRAM (RENP) INGESTION PONITORING STATIONS Location Codes NUREG-0473 Shoreham RENE Location Description Ia1 6B1 Goat Farm, 1.54 mi. ESE l Ia2 10F1 Goat Farm, 9.2 mi. SSW Ib1 3C1 Fish and Invertebrates, outfall area, 2.9 mi. NE Ib2 14C1 Fish and Invertebrates, outfall area 2.1 mi. WNW Ib3 13G2 Fish and Invertebrates, background, 13.3 mi. W Ici 8B1 Local Farm, 1.2 mi. SSE Ic2 SC2 Local Farm, 2.8 mi. E Ic3 12H1 Background Farm, 26 mi. WSW O i l l r
't BN1-11600.02-112 1 of 1 Revision 3 - December 1983
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FIGURE 5-1 , ONSITE SAMPLING LOCATIONS
"" RADIOLOGICAL ENVIRONMENTAL i MONITORING PROGRAM SCALE - NILEs SHOREHAM NUCLEAR POWER STATION -UNIT 1 OFFSITE DOSE CALCULATION MANUAL
' REVISION 3-DECEMBER 1983
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- / OFFSITE SAMPLING LOCATIONS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM o 5 to SHOREHAM NUCLEAR POWER STATION-UNIT 1 OFFSITE DOSE CALCULATION MANUAL SC ALE - MILES REvtSION 3-DECEMBER 1983
SNPS-1 ODCM SECTION 6 INTERLABORATORY COMPARISON PROGRAM The laboratory performed the radiological environmental analyses shall participate in an interlaboratory comparison program which has been approved by the NRC. Currently this program is the Environmental Protection Agency
.(EPA) environmental radioactivity laboratory intercomparison studies (cross-check) program. Our participation code is "CJ".
1 ) 1 0 1 l-l BN1-11600.02-112 6-1 Revision 3 - Decercher 1983 l
SNPS-1 OLCM APPENDIX A DERIVATION OF AIT V. A -7 ares / min per pCi/cc) is the dose conversion factor for the combined fish pkus(seafood pathways due to a liquid radwaste system discharge. The doses to organ,'j, due to ingestion of fish and seafood (contribution from shoreline deposit is considered insignificant) containing isotope, i, were calculated by a computer code based on Regulatory Guide 1.109, Rev. I methodology and default parameters. The computer isotopic dose rates' output were normalized to unit intake concentration with the following equation: A = Fij + sij rij C /F where: D pg) = Calculated fish ingestion dose rate (mrem / min) to organ, j, from isotope, i, (Ref. Reg. Guide 1.109, Eq. (A-3)) D,g) = Calculated seafood ingestion dose rate (mrem / min) to organ, j, from isoi. ope, i, (Ref. Reg. Guide 1.109, Eq. (A-3)) Cg = Discharge concentration of isotope, i, (pCi/cc) F = Near field dilution f actor, 8.85 (unitiess) e BN1-11600.02-112 A-1 Revision 3 - December 1983
T E SNPS-1 ODCM APPENDIX B v/ DERIVATION OF Potj , 2 P oij f Ci/ ) is the dose conversion f actor due to combined effect of g ingestion of leafy vegetables, ingestion 'of . stored--vegetables, (fruits,
-vegetables, and grains), and contaminated ground pathways.
~
The dose delivered to organ, j, due to the combined effect of the 3 pathways were calculated for each radioisotope, i, using a computer code based on Regulatory Guide 1.109, Rev. I methodology and def ault parameters. l The computer isotopic does rates output were normalized to unit isotopic ! release rate and deposition factor with the equation: i p ,Meij+ Lij + sij oij ~
-3.17*10 *C 1
- D/Q where:
D = Calculated contatninated ground dose to organ, j, from cij isotope, i. D gg) = Calculated leafy vegetable ingestion dose to organ, j, from isotope, i,
= Calculated stored vegetables dose to organ, j , from isotope, D,g) i, C1 = Gaseous effluent release rate of isotope, i, (C1/yr)
D/Q = Deposition factor (m-2) as used in calculation of D cij' Dtt), D,g) . 3.17*10-2 = The number of years peg second (3.17 x 10-8) times the number of (,1 per C1 (10 ). t i i O BN1-11600.02.112 B-1 Revision 3 - December 1983 l i
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