ML20112G464
| ML20112G464 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 01/07/1985 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20112G447 | List: |
| References | |
| PROC-850107, NUDOCS 8501160347 | |
| Download: ML20112G464 (102) | |
Text
{{#Wiki_filter:p ENCLOSURE 2 RIVER BEND STATION GULF STATES UTILITIES OFFSITE DOSE CALCULATION MANUAL (ODCM) i-l 4 i i I e i,. to '? t 2 .'; ,f - I-b'- k_'ld' d. o
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y- - - Table of Contents Section Page l.0 Introduction....................................... 1-1 2.0 Liquid Effluent Methodology........................ 2-1 2.1 River Bend Station Site Description................ 2-1 2.2 Compliance with 10CFR20 ( L iq u i ds ) . . . . . . . . . . . . . . . . . . 2-1 2.3 Determination of Setpoints for Radioactive Liquid Effluent Monitors................................ 2-2 2.4 Determining the Dose for Radioactive Liquid Efflu-ents............................................. 2-4 2.5 Projecting Dose for Radioactive Liquid Effluents. . . 2-5 3.0 Gaseous Effluent Methodology....................... 3-1 3.1 . Introduction....................................... 3-1 3.2 Data Requirements for Gaseous Ef fluents . . . . . . . . . . . . 3-1 3.3 Instantaneous Release Rate and Setpoint Determina-tion............................................. 3-1 3.4 Cumulative Dose Determination for Radioactive Gaseous Effluents................................ 3-9 3.5 Dose Projection - Determination of Need to Operate Ventilation Exhaust Treatment System............. 3-16 I 4.0 Radiological Environmental Monitoring Program...... 4-1 4.1 Deviations from the RBS Environmental Report Operating License Stage.......................... 4-1 5.0 40CFR190 Considerations............................ 5-1 5.1 Compliance with 40CFR190........................... 5-1 5.2 Calculations Evaluating Conformance with 40CFR190.. 5-1
-5.3 Calculations for Total Body Dose................... 5-1 5.4 Thyroid Dose....................................... 5-2 6.0 Interla boratory Comparison S tudies . . . . . . . . . . . . . . . . . 6-1 I 6.1 Requirement........................................ 6-1 6.2 Program............................................ 6-1 p
U> ' Appendices A Liquid MPC Values B Liquid Environmental Dose Transfer Factors Ai lI C Ki Li Air Dose Transfer Factors D JEx ected Gaseous Radionuclide Mixture E X/Q and D/Q Values for Restricted Area Boundary F Maximum X/Q and D/Q for Individual Locations G Instantaneous Dose Transfer Factor Tables H . Gaseous MPC Values I Environmental Dose Transfer Factors for Gaseous Effluents Figures 1 Unrestricted Area Map 2 Schematic of Liquid Radwaste System 3 ~ Effluent Release Points 4 Schematic of Gaseous Radwaste System 5 Radiological Environmental Monitor Locations r i t ':
1.0 INTRODUCTION
This manual provides the methodology to calculate radiation doses to individuals in the vicinity of the River Bend Station (R BS ) . It also provides the methodology for calculating efflu-ent monitoring setpoints and allowable release rates to ensure compliance with the Radiological Effluent Technical Specifica-tions (RETS ) of Gulf States Utilities, River Bend Station. This manual also contains a description of the radiological Environ-mental Monitoring Program which includes sample point descrip-tions for both onsite and offsite locations and sampling and analysis frequencies. The ODCM follows the methodology and models suggested by the
" Guidance Manual for Preparation of Radiological Effluent Tech-nical Specifications for Nuclear Power Plants " (NUREG-0133, dated October 1978) and " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Eval-uating Compliance with 10 CFR Part 50, Appendix I" (Regulatory Guide 1.109, Rev. 1, dated October 1977). Simplifying assump-tions have been applied where applicable to provide a more work-able document for implementing the technical specifications requirements. Alternate calculational methods may be used from those presented as long as the overall methodology does not change or as long as the alternative methods provide results that are more limiting. Also, as available, the most up-to-date revision of Regulatory Guide 1.109 dose conversien factors and site-specific environmental transfer factors may be substituted for those currently included and used in this document.
h 1-1
2.0 LIQUID EFFLUENT METHODOLOGY 2.1 River Bend Station Site Descriotion The River Bend Station Final Safety Analysis Report (FS AR ) con-tains the official description of the site characteristics. The description that follows is a brief summary for dose calculation purposes: The River Bend Station (JRBS ) is on a site in West Feliciana Parish, Louisiana, located approximately 24 miles north- north-west of Baton Rouge, Louisiana. This site is just east of the Mississippi River which is used as the source of the RBS major water requirements and which receives the RBS liquid effluents. 2.2 Compliance with 10CFR20 (Lioulds) 2.2.1 Requirements In accordance with Technical Specification 3.11.1.1, the concen-tration of radioactive material released in liquid ef fluents to Unrestricted Areas (Figure 1) shall be limited to the concentra-tions specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or. entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 uCi/ml total activity. The concen-tration of radionuclides in liquid waste is determined by sampl-ing and analysis in accordance with Technical Specification Table 4.11.1.1-1. 2.2.2 Methodology This section describes the calculational nethod to be used to '
. determine F, L the fraction of 10CFR20 limits of release con-centrations of liquid radioactive effluents.
2.2.2.1 General Approach Liquid effluent releases from River Bend Station are discharged through the cooling tower water blowdown which is directed to the Mississippi River. Principal sources of radwaste are from floor drains, phase separators / backwash tank subsystem and re-actor water cleanup as shown in Figure 2. The liquid radwaste system is operated as a batch system. Only one tank of liq uid radwaste is released at a time and is considered a batch. The radioactive content of each batch release will be determined prior to release in accordance with Table 4.11.1.1-1 of the RBS Technical Specifications. Compliance with 10CFR20 limits will be determined with the following equation: 2-1 L
n f1 Ci FL = . 2.2.2.1-1 f2 m (MPC )1 i=1 where: FL = The fraction of 10CFR20 MPC limits resulting from the release source being discharged fl
= The undiluted release rate of the release source at the monitor location, in gpm f2 = The cooling tower blowdown release rate, in gpm Ci = The undiluted concentration of nuclide (1), in uCi/ml from sample assay. When a radionuclide has a concentration lower than the Lower Level of De-tection (LLD), it is not reported as being present in the sample
( MPC )1
= Maximum Permissible Concentration of nuclide (i) from Appendix A, in uCi/ml as long as FL is less than 1.0 the concentration of the tank is within compliance with 10CFR20 limits.
2.2.2.2 Simplified Approach For purposes of simplifying tha calculations, the value of 3 x 10-8 uCi/ml (unidentified 10( PR 20 MPC value ) could be sub-stituted for (MPC)i and the cumulative concentration (C-Total
= sum of all identified radionuclide concentrations ) or the gross beta-gamma concentration should be substituted for C1 As long as the diluted concentration (C-Total -
f 1 /f2) 18 less than 3 x 10-8 uCi/ml, the nuclide by nuclide calcula-tion is not required to demonstrate compliance with 10CFR20 MPC limits. 2.3 Determination of Setpoints for Radioactive Liquid Effluent Monitors ) 2.3.1 Requirements Technical Specification 3.3.7.11 requires the radioactive liquid effluent monitor be operable with their high alarm / trip set-L points set to ensure that limits of Technical Specification 3.11.1.1 are not exceeded. The high alarm / trip setpoints shall be determined and adjusted by the methodology which follows. In
- all cases, the . setpoint values shall be applied above normal background levels.
2-2
W The high alarm setpoint for the liquid ef fluent radiation mon-itor is derived from the concentration limit provided in 10CFR20, Appendix B, Table II, Column 2 applied at the re-stricted area boundary where the discharge flows into the Mississippi River. 2.3.2 Methodology The high alarm setpoint does not consider dilution, dispersion, or decay of radioactive material beyond the site boundary. That is, the alarm setpoint is based on a concentration limit at the end of the discharge. A sample of each batch of liquid radwaste is analyzed for I-131 and other principal gamma emitters as specified in Table 4.1-1 of Technical Specification 3.11.1, for total activity concentra-tion prior to release. The fraction FL of the 10CFR20 MPC
' limits for unrestricted areas is determined in accordance with the preceding section for the activity concentration released.
. The liquid radwaste effluent line radiation monitor alarm set-point is determined with the equation:
A f2+fl S =. x x g + Bkg 2.3.2-1 FL f1
.where:
S = The radiation monitor setpoint (cpm or uCi) A = The counting rate (cpm /ml) or activity concentra-tion (uci/ml) of the sample as determined in the laboratory-
- g. = The ratio of effluent radiation monitor counting rate to laboratory counting. rate or activity
- con-centration in a given batch of liquid (cpm per cpm /
ml or cpm'per uCi/ml) fl = Release rate of undiluted batch release line
. (ml/sec , gpm, or other consistent units of vol/
time) f2 = Minimum dilution flow of cooling tower blowdown in the discharge (ml/sec, gpm, or other consistent units of vol/ time ) Note: A/FL represents the counting rate of a solution hav-ing the . same radionuclide distribution as the sample and having the maximum permissible concentration (MPC ) of that mixture. 2-3 i ' U
n - - - _ _ - _ . . - _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ 2.4 Determinino the Dose for Radioactive Licuid Effluents 2.4.1 Requirements Technical Specification 3.11.1.2 requires the dose or dose com-mitment to a person offsite due to radioactive material released in liquid ef fluents be calculated on a cumulative basis at least every 31 days. Dose or dose commitment shall be limited to l-a) Less than or equal to 1.5 mRems to the total body and to less than or equal to 5 mRems to any organ, during any quarter; and b) Less than or equal to 3 mRems to the total body and less than or equal to 10 mRems to any organ during any calendar year. 2.4.2 Methodology This section provides the methodology to calculate dose to all age groups and organs from all radionuclides identified in the liquid effluents. The method is based on the methodology suggested by Sections 4.3 and 4.3.1 of NUREG-0133, Rev. 1, November 1978. The site-speci-fic dose factors Ai t. Appendix B. for all viable pathways are listed in The following equation provides for a dose calculation to the total body or any organ for a given age group (D T a) based on actual release conditions during a specific time interval for radioactive liquid releases : n n AltAti Q11 D Ta = Di T = 2.4.2-1 (DF)1 i=1 i=1 where: DIT
= Dose commitment in mrem from radionuclide (1) re-ceived by organ (7) of age group (a) resulting from releases during the time interval t At A1 7 = Site related dose commitment factor to the total body or any organ (T) for each identified radio-nuclide (1). .The Air values listed in Appendix B are site-related to RBS and have the units (mrem /hr per uC1/ml) iti = Number of hours that the release occurred Qil = The total quantity of nuclide (1) released dur-ing the time period at1(uci) 2-4 L.
= The total volume of dilution that occurred during (DF)1 the release time period At1 (i.e., the cooling tower blowdown flow multipliec by the time ) (ml).
The doses associated with each release may then be summed to provide the cumulative dose over a desired time period (e.g., sum all doses for releases during a 31 day period, calendar
-quarter, or a year).
The following equation is used to calculate the total doses for the desired time interval: n i D = (DT al i 2.4.2-2 TOTALy , i=1 where: . D- = ' The total dose commitment to the organ (T) due TOTALT to all releases during the desired time interval in mrem. 2.5 Projectina Dose for Radioactive Licuid Effluents 2.5.1 Requirements Technical Specification 3.11.1.3 requires the liquid radwaste-treatment system be used to reduce the radioactive materials in liquid wastes prior to their discharge when projected doses due to . liquid effluents, to unrestricted areas (Figure 1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a
'31 day period.
2.5.2 Methodology The following calculational methodology shall be performed at least once per 31 day period X PD = - D 2.5.2-1 Ia TOTAL 7 Xo where: PDr a
= Projected dose commitment (mrem) to organ ( T) of age group (a).during the 31 day period X = The number of days remaining in the 31 day period i
Xo = The number of days to date in the 31 day period 2-5 C _ _ _ _ _ _ _ _ _ _ - - - . _ _ _ _ _
D = The total dose commitment (mrem) to an organ ( T) of TOTALT age group (a) 'oring the 31 day period. The age group (a) is selected based upon highest dose com-mitment. 2-6
3.0 GASEOUS EFFLUENT METHODOLOGY 3.1 Introduction The River Bend Station discharges gaseous effluents through the Main Plant Exhaust Duct, Fuel Building Exhaust Duct, and Rad-waste Building Exhaust Duct. The location of these release points in relation to the River Bend site is found in Figure 3. The gaseous effluent streams, radioactivity monitoring points, and ef fluent discharge points are shown schematically in Figure
- 4. For purposes of simplicity, Fuel Building exhaust effluents are included in the Main Plant exhaust duct releases. All gas-eous effluent releases are assumed to be ground level releases.
3.2 Data Requirements for Gaseous Effluents For the purpose of estimating offsite radionuclide concentra-tions and radiation doses, measured radionuclide concentrations in gaseous ef fluents and in ventilation air exhausted from the station are relied upon. Table 4.11.2.1-1 in the Technical Specifications identifies the radionuclides in gaseous dis-charges for which sampling and analysis is done. When a nuclide concentration is below the LLD for the analysis, it is not reported as being present in the sample. Real' meteorological data factors are calculated and used in dose calculations for the Semi-annual Effluent Release Report. His-torical information and conservative receptor assumptions are only used for ease of Limiting Ccndition of Operation (LCO) dose limit calculations. Dose calculations performed with actual occurring data will describe the source of the data in the re-port. Modeling will be performed in accord mce with Regulatcry Guide 1.111, Rev. 1. 3.3 Instantaneous Release Rate and Setpoint Determination 3.3.1 Instantaneous Release Rate Determination The instantaneous release rate determination is performed to show compliance with the limits set forth in 10CFR20. 3.3.1.1 Requirements Technical Specification 3.11.2.1 states that the dose rate due to radioactive materials released in gaseous ef fluents from the site to areas at and beyond the site boundary (see Figure 1)
- shall be limited to the following s
- a. For noble gases: Less than or (qual to 500 mrem / year to the total body and less than or equal to 3,000 mrem / year to the skint and 3-1
- b. For I-131, I-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: less than or equal to 1,500 mrem / year to any organ.
3.3.1.2 Methodology 3.3.1.2.1 General Approach - Total Body and Skin Instantaneous
, Release Rate Calculations To determine the dose rate from noble gases in unrestricted areas, the following formulae are used:
n DRTB = 3.15 x 107- Ki (X/Q) Qi s 3.3.1.2.1-1 i=1 i DR = 3.15 x 107- (Li + 1.1 Mi) (X/Q) Qi i=l 3.3.1.2.1-2 where: DRTB
= Dose rate to the total body in mrem / year.
Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide (1) in mrem /sec cer uCi/m3 Appendix C. Li = Skin dose factor due to beta emissions for each identified noble gas radionuclide (i) in mrem /sec , per uC1/m3 Appendix C. Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide (1) in mrad /sec per uC1/m3 Appendix C. (X/Q) = The highest calculated annual average relative con-centration for any area at or beyond the restricted , area boundary in sec/m3 For either elevated (stack) or vent releases. Appendix E. h1 = The release rate of radionuclide (1) in gaseous effluents from all releases in uCi/sec. 1.1 = Conversion factor for Mi from mrad to mrem. 3.15 x 107 = Number of sec/ year. 3-2 m_
I In order to comply with the limits of 10CFR20, DRTB 1 500 mrem / year and DRskin 1 3,000 mrem / year mus t be met at j the most limiting location. The radionuclide mix was based upon source terms tabulated in ! the River Bend Station FSAR, Table 11.3-1 and are summarized in l Appendix D. l The X/Q values utilized in equations 3.3.1.2.1-1 and 3.3.1.2.1-2 are based upon maximum long-term annual average (X/Q) in the un-restricted area. Appendix F lists the maximum X/Q values for the RBS release points at the restricted area boundary. To select the most limiting location, the highest X/O for each release point is used (from Appendix F): (X/Q)s = 2.0 x 10-6 sec/m3 (%/Q)y a 2.11 x 10-5 sec/m3 ! where: (X/0)s = Chi /Q for Main Plant exhaust duct and Fuel Build-ing exhaust duct
-(X/Q)y = Chi /Q for Radwaste Building exhaust duct Appendix F contains the maximum X/Q and D/Q values used in cal-culating individual doses.
Release rates for all release points must be considered at the same time. If releases are occurring at the same time, the l' total instantaneous dose for all releases must be less than the limits of Technical Specification 3.11.2.1. An administrative control limits - the release rates for each of the three release points to 1/3 the total Technical Specification doses. 3.3.1.2.2 Limited Analysis Approach - Instantaneouc Noble Gas Release Rate The above methodology can be simplifled to provide for a rapid
, determination of cumulative noble gas release limits based on the requirements specified in Section 3.3.1.1. Beginning with equation 3.3.1.2.1-1 the simplication proceeds as follows:
From an evaluation of projected releases, an effective total body dose factor (Keff) can be derived. This dose factor is, in effect, a weighted average total body dose factor. See Appendix C for a detailed explanation and evaluation _ of Kegg. The value of Kegg has been derived from .the radioactive noble gas ef fluents listed in RBS-FSAR and included in Appendix D. The values are: 3-3 3 L_
Radwaste Building Exhaust Duct: K = 8.05 x 10-5 [ mrem-m3 / uCi-sec] Main Plant Exhaust Duct and Fuel Building Exhaust Duct: K = 5.56 x 10-5 [ mrem-m3/ uci-sec) Either of these values, as appropriate, may be used in conjunc-tion with the total noble gas release rate (E Qi) to verify that the instantaneous dose rate is within the allowable limits. To compensate for any unexpected variability in the radionuclide distribution, a conservatism factor of 0.8 is introduced into the calculation. The simplified equation is: n . DR TB
=
Keff - (X/Q) E3 Qi 3.3.1.2.2-1 i=1
0.8 where
DRTB
= Total body dose rate from noble gases in airborne releases in mrem /sec.
(X/Q) = For ground level or elevated releases, the highest calculated annual long-term historic relative con-centration for any of the 16 sectors, at or beyond the unrestricted area boundary, in sec/m3 (Ap-pendix F). Qi = The total release rate of all noble gas nuclides from the release source of interest in uCi/sec. 3.3.1.2.3 Determining the Radiciodine and 8-day Particulate Release Rates The following calculational method is provided for determining the dose rate from radioiodine and particulates with half-lives greater than 8 days and to determine if they are within the limits listed in Section 3.3.1.1-b. In ' the calculation to show compliance with 10CFR20, only the inhalation, ground plane, and cow milk pathways are considered. Inhalation Pathways n . DR = Pi - (X/Q)g
- Qi b I& 8 DP r 3.3.1.2.3-1 i=1 P
3-4 L: -
Ground Plane Deposition Pathway: n . DR = Pi - (D/Q) . Qi i=1 Contaminated Forage / Cow / Milk Patheay n . DR = Pi - (D/Q) - Qi i=1 Total Dose Rate From I&8DP DR y = DR 3.3.1.2.3-4 z I&8DP T where: T = The organ of interest for the age group of inter-est. z = All the applicable pathways
'hi = Release rate of nuclide (i), (uCi/sec].
DR = Dose rate to the organ T for the age group of in-I&8DP r terest from iodines and 8 day particulates via the pathway of interest (in mrem /yr]. DR7
= Total dose rate to organ T from all applicable pathways for the age group of interest [in mrem /
yr]. (X/Q)g = The long-term depleted and 8 day decayed . CHI /Q value based on historical meteorological data (Appendix E) (in sec/m3]. Note: No credit for decay or depletion has been taken. (D/Q) = The long-term relative deposition value based on . historical data (in m-2] (Appendix F). Pi = The dose factor for applicable environmental pathway (in units which vary with pathway chosen] (Appendix G). Note: For calculations involving tritium, use (X/Q)g in sec/m3, The determination of limiting location for implementation of 10CFR20 for radiolodines and particulates is a funct. ion of the same parameters as for noble gases. 3-5
The determination of the controlling site boundary location was based upon the highest site boundary D/Q value. The determina-tion of actual receptor limiting location was based upon the milk pathway D/Q value and the Pi value for the respective milk pathway. Values for Pi were calculated for an infant for various radionuclides for the inhalation, ground plane, and cow milk pathways using the methodology of NUREG-0133. The Pi values are presented in Appendix G. The values of Pi reflect, for each radionuclide, the maximum Pi value for any organ for each individual pathway. For the case of an infant being pres-ent at the site at the site boundary or at the real pathway location, the ground plane pathway is not considered as a rea-sonable exposure pathway. However, Pi values for ground plane are presented in Appendix G for completeness. The annual average D/0 values at the special locations which will be utilized are obtained from the tables presented in Ap-pendix F. 3.3.2 Setpoint Determination 3.3.2.1 Requirements Instrumentation is provided to monitor beta-gamma radiation from radioactive materials released from the River Bend Station in gaseous effluents. Each release point process monitor listed in Tech. Spec. Table 4.11.2.1-1 includes an alarm that is set to report when the radioactive noble gas in gaseous effluents in either (Main Plant exhaust duct or Radwaste Building exhaust duct) is expected to cause a noble gas concentration at ground level offsite equal to or greater than specified in 10CFR20 Appendix B, Table 2, Column 1 for the mixture. MPC values for gaseous radionuclides are listed in Appendix H. The distribution of radioactive noble gases in a gaseous efflu-ent stream is determined by gamma spectrum analysis of identifi-able radionuclides in effluent gas sample (s). Results of one or more previous analyses may be averaged to obtain a representa-tive spectrum. In the event the distribution is unobtainable from measured data, the distribution of radioactive noble gases based on past data or calculated by the BWR-GALE- code appearing in Appendix D may be assumed. To allow for multiple sources of releases from the three differ-ent release points, the allowable operating setpoints will be administratively controlled to allocate one-third (1/3) of the total allowable release to each of the release sources. 3.3.2.2 Methodology This section describes the methodology for determining alarm / trip setpoints for the three release points. 3-6 E
e Step 1 Determine. the QTB (maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent [uCi/sec]) based upon the whole body exposure limit of 500 mrem / year for all release points by: 500 500 Q = 3.17 x 10-8 . = 3.17 x 10-8 . TB (X/Q)bK i fi (X/Q) K 0.8 i eff 3.3.2.2-1 where: (X/Q) = The highest calculated annual average relative dis-persion factor for any area at or beyond the unre-stricted area boundary for all sections (sec/m3), Appendix F. Ki = The total whole body dose factor due to gamma emissions from noble gas radionuclide (i) (mrem / sec/uci/m3) from Appendix C, Table C-1. fi
= Fraction of noble gas radionuclide (i) to total noble gas concentration.
K = E - f i , effective dose factor (mrem /sec/uCi/m 3)
; Ki eff. from Appendix C, Table C-3.
3.17x10-8 = Inverne of number of seconds per year in year /sec. 0.8 = Conservative factor to account for changing iso-topic inventory. Step 2 Determine Qs (the maximum acceptable release rate of all gas radionuclides in the gaseous effluent [uci/sec]) based upon the skin exposure limit'of 3,000 mrem / year for all release points by: 3,000 3,000
'Q = 3.17 x 10-8 = 3.17 x 10-8 .
s (X/Q)b[Li+1.lMi)fl i (X/Q)(L+1.lM)eff 0.8 i 3.3.2.2-2 where: Li + 1.lMi = Total skin dose factor due to emission from noble gas radionuclide (1) (mrem /sec/uCi/m ) from Appendix 3 C. (L+1.lM) eff
=
b(Li+1.1Mi) I factor
- f , effective total skin dose i
(mrem /sec/uCi/m3) from Appendix C, Table C-4. 3-7 [:
Step 3 Determine Cm - (the maximum acceptable total radioactivity con-centration of all noble gas radionuclides for each release point
~in the gaseous effluent [uci/cc]).
2.12 E-3 0 C = 3.3.2.2-3 m p Note: Use the lower of the Q values obtained in Steps 1 and
- 2. This will protect both the skin and total body from being exposed to the limit.
yg .where: F =- The nmximum acceptable effluent flow rate at the point of release based on design flow rates (cfm). 2.12 E-3 =
. Unit conversion factor to convert uci/sec/cfm to uCi/cc.
Step 4 Determine CR (the calculated monitor count rate above background-attributed to the noble gas radionuclides [ cpm]) by: CR = (Cm) (Em) 3.3.2.2-4 i where: Em = Efficency' of the applicable. effluent ' monitor (cpm /uCi/cc ) . Step 5
^
IDetermine -the HSP (the monitor' high alarm setpoint- including background [ cpm])=by: LHSP = T mCR +'Bkg 3.3.2.2-5 where: Tm =- Fraction ofithe radioactivity from7 the . site 1that may be ' released via the monitored pathway to. ensure thatitheLsite boundary limit is not exceeded due to simultaneous releases from.several pathways. Tm = .33 for all release points. 3-8 u
Bkg = The background count rate (cpm) due to internal contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with uncontaminated air. 3.4 Cumulative Dose Determination for Radioactive Gaseous Effluents 3.4.1 Noble Gases
' 3.4.1.1 Requirements Technical Specification 3.11.2.2 states that the air dose due to noble gases released in gaseous effluents from each reactor unit to areas at and beyond the site boundary (see Figure 1) shall be limited to-the following:
a.. 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; and
- b. 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.
3.4.1.2 Methodology This section provides the methodology to calculate the doses to all age' groups and organs from all noble gas radionuclides iden-tified in the gaseous effluents. The method is based on 'the methodology. suggested by sections 5.3 and 5.3.l ~ of ' NUREG-0133, Rev. 1, November , 1978. The site re-lated _ dose factors for all viable pathways are listed in Appen-dix 1.- Dose -factors are compiled by age groups, for all. organs and radionuclides common to a BWR environment.
' '^
1The followi~ng equations provide for air dose calculations based on actual noble gas release ' rates during a specific time inter-val for radioactive gaseous _ release sources at the site bound-ary:. n D Gamma-Air
=
Mi x (X/Q) x Qi 3.4.1.2-1 i=1 n D ,
=
.NiLx_(X/Q)-x 01 3.4.1.2-2
< Beta-Air i=1 F
3-9
where: D , = The gamma air dose from radioactive noble gases in Gamma-Air mrad. Mi = The gamma air dose factor for radioactive noble gas nuclide (i) in mrad-m3 /uci-sec (Appeadix C). (X/Q) = The long-term atmospheric dispersion factor for ground level (annual average) for the year of interest. Actual meteorological data and sector wind frequency distributions will be used to de-termine annual X/Q for the year of interest in sec/m3 (Appendix E).
.Qi = The ' number of uCi of nuclide (i) released during the period of interest.
D- = Beta air dose fron radioactive noble gases in mrad. Beta-Air
-Ni. = The beta air dose factor for radioactive noble gas nuclide (i) in mrad-m3/uCi-sec (Appendix C),
Table C-l. 3 '. 4.1. 3 Simplified' Approach
- . A- single effective gamma air dose factor (Megg) and beta air dose factor (Neff) have been derived, which are representa-tive of - the
- radionuclide abundances and correponding dose con-tributions that are projected in the RBS FSAR. (See Appendix C' for a. detailed explanation and evaluation of Meff and Neff.)
The values of Meff and Neff which have been derived from the projected radioactive noble gas effluents are: Radwaste Building Exhaust Duct: Megg = 1.01 x 10-4 mrad-m3/ uci-sec Neff = 8.08 x'10-5 mrad-m3/ uci-sec Main Plant Exhaust Duct.and' Fuel Building' Exhaust Duct:
- n. . .
?Meff = 7.46'x'10-5 mrad-m3/ uci-sec Negg == 1.61 x '10 .4 mrad-m3/ uCi-sec 4
1 3-10
- The effective gamma air dose factor may be used in conjunction with the total noble gas release ({ Qi) to simplify the dose evaluation and to verify that the cumulative gamma and beta air dose is within the equivalence of the limits of Technical Speci-fication-3.11.2.2. To compensate for any unexpected variability
- .in the radionuclide distribution, a conservatism factor of 0.8 L
-is~ introduced into the calculation. The simplified equation is:
~ n (Mefg) - (X/Q) Qi D = . 3.4.1.3-1 Gamma-Air 0.8 i=1 n (Neff) * (X/Q) Qi
'D .
= . 3.4.1.3-2
- Beta-Air 0.8 i=1 3.~4.2 Determining the Radiciodine and 8 Day Particulate Dose to Any Organ from Cumulative Releases 3.~4.2.1 Requirements Technical Specification 3.11.2.3 states that the dose to a Mem-ber of the Public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the site boundary shall be limited to the following:
^ a.. During any calendar quarter: less than or equal to ;7.5 mrem'to any organ; and 4
- b. During any calendar year: 'less than or equal to 15 mrem to any organ..
=3.4.2.2 Methodology ,
- l The 1 following calculational method is provided . for determining
- the critical. organ dose due to releases of radiciodines and particulates. ..It-is based on Section"5.3.1 of NUREG-0133, Rev.
1, November _1978. The ' equation can .be used for -any age group provided that ' the appropriate dose factors are used and ~ the - itotal - dose . reflects only those pathways that are _ applicable to thetage group. - The symbol (X/Q)o . represents .a depleted (X/Q) which is dif ferent - from._ the noble gas (X/Q) 'in that- (X/0)o-takes ~into account the loss .of- lodines , 8 day particulate _s , and.
-tritium from the plume-as the semi-infinite cloud travels over a-given-distance. The~ dispersion factor (D/Q) represents the rate of fallout from the ' cloud ~ that affects a square meter of ground at various : distances from the site. The total dose to-an organ-3-11
s can then be determined by summing the pathways that apply to the receptor in the sector. The equations are:
'nhalation Pathway:
I 3.4.2.2-1 n D
- I&8DP 3 i=1 Ground Plane Pathway: 3.4.2.2-2 n
D- = (3.17 x 10-8) Ri - (D/,) - Qi I&8DP i=1 Contaminated Forage / Cow / Milk Pathway: 3.4.2.2-3 n D = (3.17 x 10-8) Ri - (D/Q) - Qi i=1 Total Dose: 3.4.2.2-4 n D = ' D I&8DP 7 z=1
~
r -
-where:
T = The organ of interest in a specified age group. z = All the applicable pathways for the. age group of interest. D = . Dose ~ in mrem to the organ (T) of a . specified age I&8DP y group from radioiodines and 8 day particulates due to a particular. pathway. D- = Total' dose in mrem to the organ . (7) of a.specified-age. group from gaseous iodine and ' particulate ' ef-fluents, summed over all. applicable pathways (z). 3.17 x 10-8 = The inverse of the number of seconds per year- [ in .- years /sec ] . 3-12
Ri. = The dose factor for nuclide (i) for pathway (z) to organ (T) of the specified age group. The units are either: mrem-m3 for pathways using (X/Q)o yr-uCi or mrem-m2 -sec for pathways using (D/Q). yr-uci (See Appendix I. ) (X/Q)g = The depleted (X/Q) value for a specific location where the receptor is located. The units are [sec/m3]. (See Appendix F. ) Note: No credit is taken for depletion and decay. (X/0)o = (X/Q) (D/Q) = The deposition value for a specific location where the receptor is located. The units are [m-2), (See Appendix F.) 12 1
= The number of microcuries of nuclide (i) released (or projected) during the dose calculation exposure period.
3.4.2.3 Limited Analysis-Approach The' contaminated forage / cow / milk pathway has been identified in y Section 5.4 of the RBS ER-OLS as the most liniiting , with the
- infant thyroid being ;the most critical age group and organ. It is' possible to demonstrate compliance witn. the dose Llimit of Technical Specification 3.11.2.3 for radiciodines and particu-lates by only' evaluating the inf ant's -thyroid dose .due to the release of radiciodines via the contaminated forage / cow / milk pathway..
-The calculational method to be used includes a conservatism f actor - of 0.8- which assures! that the calculated dose is always
. greater than or equal to ~the actual dose despite possible atypi-cal distributions of radionuclides:in the gaseous effluent. The'
. simplified dose equation reduces to:
3.4.2.3-1 D- '= [3.17 x 10-8 (D/Q) Ri . Ot]'/0.8 lodines 1 3-13 ti
Y: 3.4.2.4 Approach Selection Criteria The limited analysis may be used in all cases to demonstrate compliance with the dose limit of Technical Specification 3.11.2.3 (7.5 mrem /qtr) for radiciodines and particulates. However, for the dose assessment included in the Semi-annual Radioactive Effluent Release Report, doses will be evaluated for all designated age groups and organs via all designated pathways from radiciodines and particulates measured in the gaseous ef-fluents according to sampling and analyses required by the Tech-nical Specifications. 3.'4.2.5 Annual Dose Due to Radiciodine and 8-Day Particulates Technical Specification 3.11.2.3 required the annual dose be calculated at least once per 31 days for all pathways. The following. formulae are used to calculate the annual dose for radiciodines and 8-day particulates: Inhalation Pathways: n D = 3.17 x 10-8 . Ri 7 - (X/Q)D + Qi 3.4.2.5-1 8g i=1 Ground Plane Deposition Pathway: n D = 3.17 x 10-8 . R i.- (D/Q)
- Qi T
3.4.2.5-2 8g i=1 Contaminated Forage / Cow / Milk Pathway: n D = 3.17 x 10-8 , R1 7 (D/Q)
- Qi 3.4'.2.5-3 i=1 Contaminated Forage / Goat / Milk Pathway:
n D g
= 3.17 x 10-8 .
R1 7 (D/Q) 01 3.4.2.5-4 i=1 3-14
f lCont'aminated Forage / Meats: n
, D. = 3.17 x 10-8 .
Ri T - (D/Q) - Qi 3.4.2.5-5 I&8DP 7 i=1
' Fresh Fruits and' Vegetables:
n
'D = 3.17 x 10-8 . Ri -
(D/Q) - Qi 3.4.2.5-6 i=1 Total Annual Dose: n D = DR 3.4.2.5-7 T. z=1 I&8DP 7 where: 7- = The-organ of; interest in a~specified age group. z = All the applicable pathways - for the age group of interest.
.DR- = Dose rate - to the , organ (T) for the age . group of I&8DP r
~
. . interest from iodines and 8-day particulates
'via the pathway of-interest in mnem/yr.
- 01. -
=- The number of uCi .of nuclide -(1)'-released during '
the year of~1nterest.
=
J r. Ri Y, .The'do,se factor for nuclide (i) for organ (T) for. the' pathway specified. .[ units! vary with ' pathway].
- (See Appendix _ I. ).
~
(D/Q) , != ~ A long-term relative ' deposition value , for elevated and groundilevel releases. A factor with units . of , m-2 which describes the . deposition of pa r ticu- .- late matter. from a plume ~ at a point downrange from.. p .'the source. f Actual meteorological ~ data 'and sector y" 1 wind frequency distribution will be used to deter-- b
.mine annual average D/Q..for the' year of interest.
' =--A.long-term depleted and" 8-day decayed relative.
~
-(X/Q)'o concentration value . for elevated 'and. ground level release. It describes the physical dispersion characteristics of a semi-infinite cloud travelling '
downwind. Since lodines and particulates settle, out- '(fallout of the- cloud) - on . the ~ ground,- the 3-15 1 _' _ _ _ _ - - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.___ _
(X/Q)o represents what physically remains of the cloud at a given location downwind from the release point. Actual meteorological data and sector wind frequency distributions will be used to determine annual average (T/U) g for the year of interest. Total body and organ doses will be calculated for pathway and age group on an annual basis using the above-described methodology (sec/m3), 3.17 x 10-8 = The inverse of the number of seconds per year (in year /sec). Meteorological data (x/Q, X/QD , D76) will be determined from actual meteorological data and sector wind frequency distribu-tions for the year of interest. Release rates (uCi/ year) will be based on total activity released through elevated and ground level (total of all vent pathways) as reported in the Semi-annu-al Radioactive Effluent Release Report. 3.5 Dose Proiection - Determination of Need to Operate Ventilation Exhaust Treatment System 3.5.1 Requirement Technical Specification 3.11.2.5 requires that the ventilation exhaust treatment system be used to reduce radioactive material in waste prior to discharge when the projected dose due to gase-ous effluents would exceed 0.3 mrem to any organ in a 31 day period. 3.5.2 Methodology The following calculation method is provided for determining the projected doses: PD = X . D 3.5.2-1 7 7 XD where: PD y = Projected dose due to all radioactive gaseous ef-fluents during the current 31 day period (mrem).
-X = Number of days remaining in tha 31 day period.
X = The number of days to date in the 31 day period. D7 = Cumulative total dose due to all radioactive gas-eous effluents during the 31 day period to date (mrem). 3-16 i
r , e A formal dose projection would be based on the latest results of q the- monthly calculations of the ' gamma air dose (Section 3.4.1.2). The doses calculated would be divided by the number of days that the plant was operational during that 31 day period. The value may need - to be adjusted to account for any changes - in operating conditions that could significantly alter the, actual releases, such as failed fuel, or changes in ventil-ation flow rate. N l 9 e 4 Y s
< 1 t
k N 3-17 , i e
r: I-4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAP1 Table 4.1 contains the sample point description, sampling and collection frequency analysis, and ar.alysis frequency for vari-ous exposure pathways in the vicinity of RBS for the radio-logical. monitoring program. Figure 5 indicates the locations of the various onsite and offsite sampling points and TLD loca-
..tions.
i. e t' y l' 4 l A-
<- .i ,,
4-1 i' s f , i a
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONtTORING PROGRAM Exposure Pathway Sample Point, Description, Sampling and Analysis and/or Sample Distance, and Direction Collection Frequency Frequency Analysis
- 1. Airborne Parti- Samples from 9 locations:
culates and Radiciodines A-1 Training Center. 1.8 Continuous air sampler Weekly Radioiodine canister: km from site on llwy #61 in operation with filter analysis weekly for N Sector. collection weekly or I-131 as required by dust Weekly Particulate sampler: loading, whichever Quarterly Cross beta activity is more frequent. following filter , change composite for' gamma isotopic quarterly. B-1 Iron Yard Area. 0.76 km from site in NNE Sector. R-1 At Gate #23. 1.22 km from site in NNW Sector. Met Tower Area. 0.76 km from site in W Sector. K-S River Road. 2.9 km from site in SSW Sector (near intake embayment). St. Francis Substation. 5.8 km from site in WNW sector on Hwy Bus 61.
^ = .
TA BLE - 4. I ' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 2) Exposure Pathway Sample Point, Description,- Sampling and Analysis [ j and/or Sample Distance, and Direction ' Collection Frequency Frequency Analysis I Airborne Parti - CSU Service Center in Zachary. l -culates and 22 km from site in ESE '- Radiciodine Sector.
- (Cont.)
North: Blvd.-in Baton Rouge. 40 km from site in SSE Sector.
.Parlange. Substation. . 20 ,
km from. site in SW Sector. h e m
=
4
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 3) Exposure Pathway Sample Point, Description, Sampling and Analys is and/or Sample Distance, and Direction Collection Frequency Frequency Analysis
- 2. Direct Radiation LOCATION INDICATOR STATIONS A-1 Air sampler location Thermoluminescent Monthly Gamma dose at the EOF. 1.8 km from dosimeters (TLDs) Quarterly Gamam dose site in N Sector.
A-2 On CSU pole 246 at intersection of LA Hwy 10 and Feliciana liwy. 2.8 km from site in N Sector. B-1 Air sampling station, iron yard area. 0.8 km from site in NNE Sector. B-2 On a stub pole at the intersection of LA Hwy 965 and WF !!wy 17. 7 km from site in NNE Sector. C-1 On an existing stub pole across US 61 from intersection of Old Hwy 61 and US 61 about 0.5 km north of WF 7. 1.7 km from site in NE Sector.
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 4) Exposure Pathway Sample Point, Description, Sampling and Analysis and/or Sample Distance, and Direction Collection Frequency Frequency Analysis Direct Radiation C-2 On LA Hwy 966 on a (Cont.) stub pole about 0.6 south of the intersection of AL Hwys 966 and 965. 7.5 km from site in NE Sector. D-1 On a stub pole on WF road 7 about 1.5 km south of the intersection of WF 7 and US Hwy 61. l.6 km from site in ENE Sector. D-2 On a stub pole adjacent to a gate into a field to the right of Hwy 966 and about 4 km south of the intersection of LA Hwys 965 and 966. 7.3 km from site in ENE Sector. E-1 In the Gravel Power Center on LA Hwy 68 about 2 km north of the inter-section of LA Hwys 964 and
- 68. 8.8 km from site in E Sector.
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 5) Exposure Pathway Sample Point, Description, Sampling and Analysis and/or Sample Distance, and Direction Collection Frequency Frequency Analysis Direct Radiation E-2 In the Gravel Power (Cont.) Center on LA Hwy 58 about 2 km north of the inter-section of LA Hwys 964 and
- 68. 8.8 km from site in E Sector.
F-1 On a stub pole approxi-mately 1.7 km from intersec-tion of Hwy 61 and WF 7 about 0.2 km after the church. 1.3 km from site in ESE Sector. F-2 On a stub pole on LA Hwy 954 and about 0.6 km north of the intersection of LA Hwys 954 and US 61. 6 km from site in ESE Sector. C-1 On a stub pole installed about 2 km south of WF 7/US 61 intersection. 1.5 km from site in SE Sector. C-2 On US Hwy 61 on a South Central Bell pole adjacent to the entrance to Marathon Oil Tank Farm about 5.3 km south ! of the intersection of US Hwy l 61 and LA Hwy 964. 8.3 km from l site in SE Sector. l l t i
1 i TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 6) Exposure Pathway Sample Point. Description, Sampling and A nalysis and/or Sample Distance, and Direction Collection Frequency Frequency Analysis Direct Radiation H-1 On a stub pole at (Cont.) the railroad crossing on WF 7. 1.7 km from site in SSE Sector. H-2 On the first South Central Bell telephone pole north of the entrance gate to the Crown Zellerbach , Mill on LA Hwy 964 (west side of 964). 5.5 km from . site in SSE Sector. J-l On a stub pole at River Bend Gate #23. 1.5 km from site in S Sector. J-2 On a large tree, last one from the site side on the C-Z fence. 6 km from site in S Sector. K-1 On CSU utility pole fL10178 about 0.1 km south of intersection of River Bend access road and WF 7. 1.2 km from site in SSW Sector. K-2 On a stub pole at the intersection of LA Hwys 414 and 415. 8.4 km from site in SSW Sector. ,
TABLE 4.1
- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 7)
Exposure Pathway Sample Point, Description, Sampling and Analysis and/or Sample Distance, and Direction Collection Frequency Frequency Analysis Direct Radiation L-1 On the second utility (Cont.) pole south of the Illinois Central Railroad crossing on LA Hwy 965. 0.9 km from site in SW Sector. L-2 At Patins Dike on the second South Central Bell . telephone pole east of the , railroad crossing on LA Hwy 415. 10.1 km from site in SW Sector. M-1 On the first CSU util-ity pole of the Illinois Central Railroad crossing on LA Hwy 965. 0.9 km from site in WSW Sector.
. M-2 On a CSU utility pole about 3 km south of the ferry landing on LA liwy 965.
4.7 km from site in WSW Sector. N-1 On the eighth CSU utility pole north of the Illinois Central Railroad Crossing on LA Hwy 965 be- ! tween Cates 13 and 14. 0.9 km from site in W Sector.
i TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROCPAM (Page 8) Exposure Pathway Sample Point, Descriptien, Sampling and Analysis and/or Sample Distance, and Direction Collection Frequency Frequency Analysis Direct Radiation N-2 On the CSU utility pole with the electrical meter at the Point Coupee Parish Ferry Landing. 6.3 km from site in W Sector. P-1 Behind the onsite garden near the energy center. 0.9 km from site in WNW Sector. . P-2 Approximately 1.5 km north of the railroad trestle on Tunica Street on a stub pole. 7.3 km from site in WNW Sector. Q-1 On a CSU property sign opposite to the 2nd trailer on LA Hwy 965 from the river access road. 1.4 km from site in NW Sector. Q-2 On CSU pole with street lights at the intersection of North Commerce Street and American Beauty Street in St. Francisville. 6.1 km from site in NW Sector.
+-
N TABLE 4.1 RADIOLOGICAL ENVIRONMENTA', MONITORING PROGRAM j (Page 9) l Exposure Pathway Sample Point, Description, Sampling and Analysis and/or Sample Distance, and Direction Collection Frequency Frequency Analysis Direct Radiation R-1 Air sampling station (Cont.) R-1 at Cate #2. 1.2 km from site in NNW Sector. R-2 On a stub pole at the intersection of West Feli-ciana Road 2 and a gravel road about 1.5 km east of the intersection of US Hwy 61 and WF 2. 8.2 km from site in !CrJ Sector. CO!TTROL LOCATIONS: E-C At the intersection of LA Hwy 955 and Midway Rcad about 5 km northeast of the intersection of LA Hwys 955 and 964 (on a stub pole). 15.2 km from site in E Sector. L-C In Parlange Power Center in Oscar, LA at the air sampler station. 20.0 km from site in SW Sector.
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 10) Exposure Pathway Sample Point. Description, Sampling and Analysis and/or Sample Distance, and Direction Collection Frequency Frequency Analysis Direct Radiation A-C On a South Central (Cont.) Bell pole adjacent to a gravel driveway about
$50 feet north of the Hamilton Station Water Tower on US Hwy 61 after Wakefield. 19.7 km from site in N Sector.
SPECIAL INTEREST LOCATIONS: P-S(l) Behind the onsite garden near the energy center. 1.0 km from site in L'NW Sector. K-S (2) Air sampling station K-S on the river access road. 2.8 km from site in SSW Sector. Q-S-1 (3) Behind the Pente-costal Church on US Hwy 61 and Ferdinand Street (oppo-site the WF Hospital). 4.0 km from site in NW Sector. Q-S-2 (4) In the St. Francis Substation. 5.0 km from site in NW Sector. l
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 11) Exposure Pathway Sample Point. Description. Sampling and Analysis i and/or Sample Distance, and Direction Collection Frequency Frequency Analysis l Direct Radiation R-S (5) on a stub pole at (Cont.) the intersection of T.T2 and US Hwy 61 near West Feliciana High School. 9.5 km from site in NNW Sector. L-S (6) On a utility pole near the False River Academy sign at the edge of New Roads. l 10.0 km from site in S'J Sector. C-S (7) On a utility pole on the left side at tte gate to the East Louisiana State Hos-pital, Jackson, LA. 12.0 km from site in NE Sector. C-S-1 (8) Air sampler station behind CSU Service Center in Zachary LA. 17.0 km from site in SE Sector. l Q-S-3 (9) On a utility pole at LSP Angola Dairy. 35 km from site in hv Sector. C-S-2 (10) On the roof of CSU Service Office Building, North Blvd., Baton Rouge, LA. 40 km from site in SSE Sec tor.
TAFI.E 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 12) Exposure Pathway Sample Point. Description, Sampling and Analysis and/or Sample Distance, and Direction Collection Frequency Frequerel Analysis
- 3. Vaterborne SURFACE (1)
I sample from about 4 km Weekly grabs compo- Monthly Crcss beta and gamma upstream of the plant sited over 1 month isotopic analysis liquid dischar se out fall, periods. near IA INy 10 ferry Qt.arterly Composite for tritium crossing. (2) I sarple from about 4 km down=tream of the plant liquid discharge outfall, near Crown-Zellerbach paper mill. DEINKING I sample from nearest down- Weekly grabs compo- Monthly Cross beta anJ gan:p stream water supply sited over I month isotopic analysis (People's Water Service Co. periods River Mile 175.5). Quarterly Composite for tritium CROUND 1 sample from Upland Terrace Quarterly grab Quarterly Cross beta gamma Aquifer well up gradient isotopic analysis from site. and tritium analysis I sample from Upland Terrace Aquifer well down gradient l free site.
TABLE 4.1 RADIOLDCICAL ENVIRONMENTAL MONITORING PROGRAM (Page 13) Exposure Pathway Sample Point, Description, Sampling and Analysis and/or Sample Distance, and Direction Collection Frequency Frequency Analysis
- 3. Wateroorne SEDIMENT Fh0M RISTR (Coo..) SHORELINE 1 sample from aloag east Semi-annual grabs Semi- Camma isotopic shore of river near (spring and autumn Annually analysis Crown Zellerbach paper quarters )
mill.
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 14) Exposure Pathway Sample Point, Description. Sampling and Analys is and/or Sample Distance, and Direction Collection Frequency Frequency Analysis
- 4. Ingestion MILE I sample from McKowen Dairy Semi-conthly when Semi- Gamma isotopic and 6 km ESE (nearest source animals on pasture; Monthly I-131 analyses of milk for consumption). conthly at other (when on (3) times pastures Monthly (other times)
I sample from animals at control location (LA State Penitentiary at Angola), 35 km NJ. PRODUCE 3 samples of leafy vege- Monthly (when Monthly Canma isotopic and tables grown in two on- samples available) (when 1 831 analyses on site gardens near the samples edible portions site of the highest calcu- available) lated annual average ground-level D/Q (2 km EJ and I km WTJ). 3 samples of leafy vege-tables grown in two off-site gardens in areas of the highest dose potential (N. YJ WWJ Sectors) when available only. l l l 1 e
TABLE 4.1 .l BADIOLOGICAL ENVltOIDtENTAL MONITORING FROGRAM r .( Fase 15) Esposure Pathway Sample Point. Description, Sampling and Analysis and/or Sample Distance, and Direction Collection Frequency Frequency Analysis
- 4. lagestion PRODUCE (Coet.)
- (Cant.)
l '3 samples of leafy vege-l tables grown at a control l location (IA State Feniten-tiary at Angola), 35 km NW. FISH AND SHELLFISH I sample from downstream Seasonally (e.g. Seasonally Camma isotopic of plant liquid discharge summer for shrimp) or semi- analysis on edible outfall, near Crown Zeller- when available or annually portions bach Paper Mill of each of semi-annually the following: river shrimp,
. . blue catfish, freshwater drum.
NOTES: (1) The upstream sample will be taken at a distance beyond influence of the plant discharge. The downstream sample will be taken in an area beyond but near the mixing zone. (2) The upstream surface unter sampling location (near IA Hwy 10 ferry crossing) will be used as a control for drinking water sampling. (3) - If milk producing animals become available within a 5 km radius of the plant, up to 3 samples from these animals will be analysed . in lieu of the leafy vegetable samples from onsite gardens in high dose potential areas. _ . . . _ . _ _ . .. - _ _ _ = ..- - - - . , - - -.- . .- , .,
5.0 40CFR190 CONSIDERATIONS 5.1 Compliance with 40CFR190 Compliance with 40CFR190 as prescribed by Technical Specifica-tion 3.11.4 is to be demonstrated only when one or more of Tech-nical Specification (s) 3.ll.1.2.a, 3.11.1.2.b, 3.ll.2.2.a, 3.11.2.2.b, 3.ll.2.3a, and 3.ll.2.3.b, including direct radia-tion are exceeded by a factor of 2. Once this occurs , CSU has 30 days to submit a report in accordance with Specification 6.9.2. 5.2 Calculations Evaluating Conformance with 40CFR190 To perform the calculations to evaluate conformance with 40CFR190, an effort is made to develop doses that are realistic by removing assumptions that lead to overestimates of dose to a Member of the Public (i.e., calculations for compliance with 10CFR50 Appendix I). To accomplish this, the following calcula-tional rules are used: 5.2.1 Doces to Members of the Public via the liquid release pathway are considered to be <1 nsem/yr (Ref NUREG-0543). 5.2.2 Dosos to a Member of the Public due to a milk pathway will be evaluated only as can be shown to exist. Otherwise, doses via this pathway will be estimated as
<1 nRem/yr.
5.2.3 Environmental sampling data which demonstrate that no pathway exists may be used to delete a pathway to man from a calculation. 5.2.4 To sum numbers represented as "less than" (<), use the value of the largest number in the group. e.g., <5+<1+<1+<3=5 5.2.5 When doses via direct radiation are added to doses via inhalation pathway, they will be calculated for the same distance in the same sector. 5.2.6 The calculational locations for a Member of the Public will only be at residences or places of employment. Note: Additional assumptions may be used to provide situation specific parameters, provided they are documented along with their concomitant bases. 5.3 Calculations of Total Body Done Estimates will be made for each of the following exposure path-ways to the same location by age class. Only those age classes known to exist at a location are considered. 5-1
5.3.1 Direct Radiation The component of dose to a Member of the Public due to direct radiation will be determined by thermolt..ninescent dosimeters (TLDs ) . 5.3.2 Inhalation Dose The inhalation dose will be determined at the calculational locations for each age group according to the methods outlined in Sections 2.0 and 3.0 of this manual. 0.3.3 Ingestion Pathway The dose via the ingestion pathway will be calculated at the consumer locations for the consumers at risk. If no milk path-way exists in a sector, the dose via this pathway will be treated as <1 mrem /yr. 5.3.4 Other Uranium Fuel Cycle Sources The dose from other fuel sources will be treated as <1 mrem /yr. 5.4 Thyroid Dose The dose to the thyroid will be calculated for each sector as the sum of inhalation dose and milk ingestion dose (if exist-ing). The calculational methods will be those identified in Section 3.0 of this manual. 5-2
6.0 INTERLABORATORY COMPARISON STUDIES 6.1 Requirement Technical Specification 3.12.3 states " Analyses shall be per-
, formed on radioactive materials supplied as part of an Inter-laboratory. Comparison Program that has been approved by the Commission."
6.2 Program 6.2.1 Environmental Sample Analyses Comparison Program Environmental samples from the River Bend Station are to be analyzed by the River Bend Station Environmental Services Group or by a qualified contracting laboratory. These laboratories will participate at least annually in a nationally recognized interlaboratory comparison study. The results of the labora-tories' performance in the study will be provided to RBS En-vironmental Services Group. The results will be provided to the NRC upon request. 6.2.2 Effluent Release Analyses Program RBS Chemistry Group will perform- sample analyses for gamma-emitting radionuclides in effluent releases. The radiochemistry laboratory will participate annually in a corporate interlabora-tory comparison study or an equivalent study. The results of these studies will be provided to the NRC upon request. 6.2.3 Abnormal Results If the GSU laboratory or vendor laboratory results lie at great-er than three (3) standard deviations from the " recognized value," an evaluation' will be performed to identify any recom-mended remedial - actions to.. reduce anomalous errors.. Complete documentation on the evaluation will be available to RBS En-vironmental Services Group and will be provided to the NRC . upon request. 6-1 i
O 9 APPENDIX A LIQUID MPC VALUES f-O
l MAXIMUM PERMISSIBLE CONCENTRATIONS IN WATER IN UNRESTRICTED AREAS MPC MPC MPC
. Nuclide* (uCi/ml) Nuclide* (uCi/ml) Nuclide* (uCi/ml)
H-3 3 E-3 Y-90 2 E-5 Te-129 8 E-4 Na-24 3 E-5 Y-91 3 E-3 Te-131m 4 E-5 P-32 2 E-5 Y-91 3 E-5 Te-131 None Cr-51 2 E-3 Y-92 6 E-5 Te-132 2 E-5 Mn-54 1 E-4 Y-93 3 E-5 I-130 3 E-6 Mn-56 1 E-4 Zr-95 6 E-5 I-131 3 E-7 Fe-55 8 E-4 Zr-97 2 E-5 I-132 8 E-6 Fe-59 5 E-5 Nb-95 1 E-4 I-133 1 E-6 Co-57 4 E-4 Nb-97 9 E-4 I-134 2 E-5 Co-58 9 E-5 Mo-99 4 E-5 I-135 4 E-6 Co-60 3 E-5 Tc-99m 3 E-3 Cs-134 9 E-6 Ni-65 1 E-4 Tc-101 None Cs-136 6 E-5 i Cu-64 2 E Ru-103 8 E-5 Cs-137 2 E-5 Zn-65 1 E-4 Ru-105 1 E-4 Cs-138 None Zn-69 2 E-3 Ru-106 1 E-5 Ba-139 None Br-82 4 E-5 Ag-110m 3 E-5 Ba-140 2 E-5 Br-83~ 3 E-6 Sn-113 8 E-5 Ba-141 None Br-84 None** In-ll3m 1 E-3 Ba-142 None Br-85 None Sb-122 3 E-5 La-140 2 E-5 Rb-86 2 E-5 Sb-124 2 E-5 La-142 None
'Rb-88 Sb-125 Ce-141 ~
None 1 E-4 9 E Rb-89 None Te-125m 1 E-4 Ce-143 4 E-5 Sr-89 3 E-6 Te-127m 5 E-5 Ce-144 1 E-5 Sr-90 3 E-7 Te-127 2 E-4 Pr-144 None Sr-91 5 E-5 Te-129m 2 E W-187 6 E-5 Sr-92 6 E-5 Np-239 1 E-4
~
~
- If_a'nuclide is not listed, referL to 10CFR20, Appendix B and
-use the most conservative insoluble / soluble ~ MPC where they-are given in Table II, Column 2.
** Nonei(as _ per 10CFR20, Appendix B) "No MPC ' limit for any sin-
- gle radionuclide ' not listed above with decay. mode other L than alpha emission or' . spontaneous _ fission and with radioactive half-lives'less than 2 hours."
) 41'
E 5 APPENDIX B LIQUID ENVIRONc4 ENTAL DOSE TRANSFER FACTORS AT 1 O
TABLE B-1 LIQUID EFFLUENT DOSE PARAMETERS
. (Page 1)
Ait, nRem/hr per uCi/ml Radionuclide Total Body Critical Organ Na-24 1.99E-04 1.99E-04 P-32 2.18E+00 5.63E+01 Cr-51 1.86E-06 4.68E-04 Mn-54 1.16E-03 1.86E-02 Mn-56 3.84E-08 6.90E-06 Fe-55 1.83E-04 1.13E-03 Fe-59 1.58E-03 1.38E-02 Co-58 4.28E-04 3.87E-03 Co-60 1.22E-03 1.04E-02 Ni-63 1.80E-03 5.37E-02 Ni-65 1.31E-08 7.27E-07 Cu-64 2.05E-06 3.71E-04 Zn-65 4.33E-02 9.57E-05 Zn-69M 6.87E-05 4.58E-02 Sr-89 1.72E-03 5.99E-02 Sr-90 3.69E-01 1.50E+00 Sr-91 4.84E-06 5.70E-04 Sr-92 1.88E-08 8.60E-06 Y-91 6.79E-07 1.40E-02 Y-92 1.83E-ll 1.10E-05 Y-93 1.55E-09 1.78E-03 Zr-95 7.56E-07 3.54E-03 Zr-97 3.62E-09 2.45E-03 Nb-95 1.68E-04 l.89E+00
.Mo-99 7.61E-05 _ 9.27E-04 Tc-99M 3.39E-08 1.57E-06 Tc-101 .0 .0 Ru-103 1.06E-05 2.88E-03 Ru-105 5.40E-09 8.37E-06 Ru-106' 4.76E-05 2.43E-02 Ag-110M 9.93E-06 6. 83 E-03 Te-129M 2.37E-03 7.54E-02 Te-131M- 5.25E-04 6.25E-02.
Te-132 1.63E-03 8.21E-02 Ba-139 1.94E-13 1.18E-ll Ba-140 1.44E-04 4.54E-03 Ba-141 .0 .0 Ba-142 .0 .0
TABLE B-1 LIQUID EFFLUENT DOSE PARAMETERS (Page 2) A i ., , mrem /hr per uCi/ml Radionuclide Total Body Critical Organ La-142 2.27E-14 6 . 64 E-10 Ce-141 7.58E-08 2.56E-03 Ce-143 6.31E-09 2.13E-03 Ce-144 2.86E-06 1.80E-02
-Pr-143 7.77E-08 6.86E-03 Nd-147 7.29E-08 5.85E-03 W-187 5.62E-05 5.26E-02 Np-239 5.62E-09 2.09E-03 Br-83 4.93E-08 7.llE-08 Br-84 .0 .0 I-131 4.57E-04 2.61E-01 I-132 6.39E-09 6.39E-07 I-133 3.58E-05 1. 73E-02 I-134 2.63E-14 1.27E-12 I-135 2.17E-06 3.88E-04 Rb-89 .0 .0 Cs-134 7.53E-01 9.22E-01 Cs-136 1.09E-01 1.52E-01 Cs-137 4.45E 6.79E-01 Cs-138 .0 .0 H-3 1.15E-01 1.15E-05 f
APPENDIX C Ki Li AIR DOSE TRANSFER FACTORS
TABLE C-1 DOSE TRANSFER FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF RADIOACTIVE NOBLE GASES DOSE TRANSFER FACTORS Gamma Beta Beta and Gamma Ki Li (L+1.lM)1 mrem _ mrem _ mrem Nuclide uCi sec/m3 uCi sec/m3 uCi sec/m3 Kr-8'3 m 2.4E-9 --- 6.7E-7 Kr- 85 m 3.7E-5 4.6E-5 8.9E-5 Kr-85 5.lE-7 4.2E-5 4.3E-5 Kr-87 1.9E-4 3.lE-4 5.3E-4 Kr-88 4.7E-4 7.5E-5 6.0E-4 Kr-89 5.3E-4 3.2E-4 9.3E-4 Kr-90 4.9E-4 2.3E-4 8.0E-4 Xe-131m 2.9E-6 1.5E-5 2.0E-5 Xe-133m 8.0E-6 3.lE-5 4.2E-5 Xe-133 9.3E-6. 9.7E-6 2.2E-5 Xe-135m 9.9E-5 2.3E-5 1.4E-4 Xe-135 5.7E-5 5.3E-5 1.3E-4 Xe-137 4.5E-5 3.9E-4 4.4E-4
.Xe-138 2.8E-4 1.3E-4 '4.5E-4 Ar-41 2.8E-4 8.5E-5 4.0E-4 AIR DOSE TRANSFER FACTORS Gamma Beta Mi Ni mrad mrad Nuclide uCi sec/m3 uCi sec/mJ Kr-83m- 6.lE-7 9.lE-6
' Kr- 85m .3.9E-5 .6.2E-5 Kr-85 5.4E-7 6.2E-5 Kr-87 2.0E-4 3.3E-4 Kr-88 4.8E-4 9.3E-5 i Kr-89 5.5E-4 .3.4E-4 Kr-90 5.2E-4 2.5E-4 Xe-131m 4.9E-6 3.5E-5 Xe-133m 1.0E-5 4.7E-5 Xe-133 1.lE-5 3.3E-5 Xe-135m 1.lE-4 -
2.3E-5 Xe-135 6.lE-5 7.8E-5. Xe-137 '4.8E-5 4.0E-4 Xe-138 2.9E-4 1.5E-4 Ar-41 2.9E-4 1.0E-4 Ref. '. Regulatory, Guide 1.109,; Revision 1, Table B-1.
- m. .
a
TABLE C-2 TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the us'e of effective dose transfer factors instead of using dose factors which are radio-nuclide specific. These effective factors, which are based on the typical radionuclide distribution in the releases, can be applied.to the total radioactivity released to approximate the dose in the environment, i.e., instead of having to sum the isotopic distribution multiplied by the isotope specific dose factor only a single multiplication (Keff, Meff, of Neff) times the total . quantity of radioactive material released, would be needed. This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calcula-tional technique. Determination of Effective Dose Factors The - ef fective dose transfer factors should be based on past operating data. The radioactive ef fluent - distribution for the past years can be used to derive single ef fective factors by the following equations: Keff = ^
' EQUATION C-1 Ki -
fi i where K -
= The effective total body dose factor due to eff gamma emissions from all noble gases released.
.Ki 5 The total body dose factor due to gamma emis-sions-from each noble gas radionuclide'"i" re-leased.
fi- = -The fractional abundance-of noble gas radio-nuclide "i" of the total noble gas radio-nuclide. EQUATION C-2 (L + 1.1 M) eff
=
(Li + 1.1 Mi) - fi i where
-(L + 1.1. M) = The effective skin doce factor due to beta eff - ~and gamma _ emissions from all noble gases released.
(Li + 1.1 Mi) S The skin dose factor due to beta and gamma emissions from each noble gas radionuclide "i" released, i
w TABLE C-2 TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS (Continued) EQUATION C-3 Meff = Mi fi i where M -= The effective air dose factor due to gamma eff emissions from all noble gases released. Mi 5 The air dose factor due to gamma emissions from each noble gas radionuclide "i" released. EQUATION C-4 Neff = Ni .fi i where N eff
-= The ef fective air dose factor due to beta emissions from all noble gases released.
4 Ni -3 The air dose factor due to beta emissions from each noble gas radionuclide "i".
~ To' provide an'_ additional degree of conservatism, a factor of 0.8 is introduced into the _ dose ' calculation process when the effec-
- tive dose transfer factor is .used. This added conservatism provides additional assurance that the evaluation of dose by the use of a: single ef fective factor 'will not significantly under-estimate any actual dose in.the environment.
Each year the dose factors should be determined and the iaverage annual values be' used.
l l e TABLE C-3 EFFECTIVE DOSE FACTORS FOR NOBLE GASES TOTAL' BODY EFFECTIVE DOSE - Keff Main Plant Radwaste Building Exhaust Duct
- Exhaust Duct
_ Year K. (mrem-m3 / uCi-sec) K (mrem-m3 / uci-sec) eff eff Projected ** 5.56 (-5)*** 8.05(-5) Main Plant exhaust - duct contains contributions from Fuel Building.
** Projected values from RBS FSAR. When RBS becomes operation-al, actual release rates reported in semi-annual effluent report should be used to generate effective'. dose factors.
*** 5.56(-5) = 5.56 x 10-5 I .4 "
7*
7 TABLE C-4 EFFECTIVE DOSE FACTORS FOR NOBLE GASES SKIN EFFECTIVE DOSE (L + 1.1 M)eff Main Plant Radwaste Building Exhaust Duct
- Exhaust Duct Year (mrem - m3/uCi-sec) (mrem-m3 / uci-sec)
' Projected ** 1.99 (-4)*** 1.59(-4)
-*- -Main Plant exhaust duct contains contributions from. Fuel Building.
**~ Projected values from ~ RBS FSAR.. When RBS becomes operation--
p al, actual.. release rates reported .in semi-annual effluent. report should be used to generate effective dose factors.
**
- L 1. 99 ( -4 ) =_ l.99 x 10-4 9
'\ 9
- k. 9 n' -
b
'?.
x Em
'P ' ' *") --
og " [' .a 7%'.'
TABLE C-5 EFFECTIVE DOSE FACTORS FOR NOBLE GASES AIR DOSES Meff and Neff Main Plant Radwaste Building Exhaust Duct
- Exhaust Duct (mrad - m3/uci-sec ) (maad - m3/ uci-sec )
Gamma Air Beta Air Gamma Air Beta Air M N M N Year Off , eff eff eff
- Projected ** 7.46(-5)*** 1.61(-4) 1.01(-4) 8.08(-5) 1
- 1
- Main Plant exhaust duct contains contributions from Fuel Building.
** Projer:ted values from RBS FSAR.. When 'RES becomes operation-
-al, actual release rates reported- in semi-annual effluent-
' " report should be used to generate ef fective dose factors .
~ ^
- *** 7746 y 5)[=,7.46_x 10-5
.....-y... .
_ . _._s .- 1 3
'a Ql1' " *_ "] ,
k APPENDIX D EXPECTED GASEO'TS RADIONUCLIDE MIXTURE
>+
. . .w,j
-e + - -.
.-- = a.-. - e. .
m .
- g. . w y
.- g.g s
6,
.e 4 y No"" -.e.e v 4909t+., 9 G-4
_[,
EXPECTED RELEASE OF RADIOACTIVE NOBLE GASES IN GASEOUS EFFLUENTS FROM RIVER BEND STATION FSAR* Containment Building ** Radwaste Building Nuclide Ci/yr Fraction Ci/yr Fraction Kr-83m 4.7(-2) 1.07(-5) <1 -- Kr- 85m 218 0.050 <1 -- Kr-85 210 0.048 <1 -- Kr-87 14.2 0.003 <1 -- Kr-88 47.2 0.011 <1 -- Kr-89 118 0.027 29 .03 Xe-131m 21 0.005 <1 -- Xe-133m 6.6(-2) 1.504(-5) <1 -- Xe-133. 2,340 0.533 220 .19 Xe-135 693 0.158 280 .24 Xe-135m 140 0.032 530 .46 Xe-137 380 0.087 83 .07 Xe-138 208 0.047 2 1.75 x 10-3 4,389. 1.0000 1,144 .99
- RBS FSAR Table 11.3-1
'** Containment Building.contains releases from Fuel Building
APPENDIX E X/Q AND D/Q VALUES FOR RESTRICTED AREA BOUNDARY
. .Long Term Diffusion Estimates E.1 Obiective
- Annual average CHI /Q and D/Q estimates for continuous and inter-mittent releases were calculated for each of the sixteen 22.5-deg sectors at receptor locations used to determine the maximum individual and population dose receptors. The methodology de-l scribed in Regulatory Guide 1.111, Rev. 1 provided guidance for the aforementioned analysis. The resultant CHI /Q and D/Q values for.-the maximum individual dose receptors are displayed in Appendix'F.
- - ' E.2 Calculation Techniques :
! Nomenclature h 2.032 = (2/v 11 /2) (2 v/16)-1 (dimensionless) T = 3.14159... (dimensionless) exp = 2.71828... (dimensionless) ET = Entrainment coefficient (dimensionless ) 2 Dk = Terrain recirculation (dimensionless) factor x = Downwind receptor distance (m)
'e z = Vertical dispersion '
(plume spread) coefficient (m) , u = 30-ft average wind speed 30 corresponding.to a given hour of onsite meteoro-logical data . (m sec-1) u = 150-ft average wind speed 150 corresponding.to a'given hour of onsite meteoro-logical data (m-sec-1) (CHI /Q) =. Average concentration normalized by" source strength (sec m-3) (CHI /Q) =. Depleted CHI /Q (sec m-3 ) D FM = Momentum flux (m4 sec-3) eJ.
- E-1
9 hb = Maximum adjacent building height (m) hr = Release height (m) h e. = Effective release height (m) h = Nonbuoyant plume rise (m) pr ht = Topographic height of receptor above plant grade (m) d = Stack or vent diameter (m) ue = Efflux velocity (m sec-1) N = Total number of valid hours of onsite wind data in all sectors for appli-cable averaging period (dimensionless ) 8/Q = Relative deposition rare normalized by source. strength (m-1) D/Q = Relative deposition per unit' area normalized-by source strength (m-2) G = Ground release (subscript) (dimensionless) i = Index.for atmospheric stability group (Classes A through G) (dimensionless) j- = Index for' number of-hours (dimensionless) k ~ = Index for a particular receptor distance (dimensionless) L- = Index for'a particular (dimensionless) 22.5-deg sector. n = Number of hours . onsite - wind data in a-particular 22.5-deg sector (dimensionless) - S = Stability parameter (sec-2) E .
E.3 CHI /Q .Modeling. Technl_que Annual average values of relative concentration were calculate d for continuous gaseous releases of activity from the containmer.t building. vent and the radwaste building vent according to the straight-line airflow (Gaussian ) model desenbed. in Regulatory Guide 1.111, Rev. 1. An adjustment was made to the model to characterize the regional. airflow pattern. The equation of this model is as follows:
....ne._ - . .
[r_} g . 2.on
=
N 3.(.1,;a+-)s
, D-go;%fs t ,x/
n ..,,, E.3-1 Since the River Bend Station site is located in relatively open terrain, the terrain recirculation factor ( n )k (presented in Figure 2 of Regulatory Guide 1.111) was applied.
* ?: ....-A ,a.
The entrainment coefficient (ET) is a function of the ratio of efflux velocity (ue) to elevated wind speed (ul50) for the conditionally elevated release points. For vent releases occuring below the level of a nearby struct-ure, 100 percent downwash (total entrainment) is conservatively assumed (ET = 1). For vent releases occuring be tween 1 and 2 times the height of a nearby-structure, a conditionally elevated release is assu'med', rand " the entrainment coefficient is defined as follows: _ .,. ET = 0.0'when,ue /ul50 > 5.1,{ { tot, ally elevated) ET = 0.30-0.06 -(u e/E150)
~
when 1.5 < ue /G150 1 5.0 (partially entrained)
~
ET = 2 . 5 8. -l'5 8 (ue /ul50) when 1.0 < ue /6150 1 1.5 (partially entrained) ET = 1.0 when eu /6150 1 1.0 (totally entrained) E.3-2 Within 5 km in each downwind sector, Equation E. 3-1 was evalu-ated by sector at the property and restricted area boundaries and nearest resident, vegetable garden, milk cow, and meat E-3
k animal There _were no goats whose milk is consumed in the area of interest. This evaluation was performed for each continu-ously emitting release point and the intermittent release from the mechanical vacuum pump with onsite data collected during the period of March 17, 1977 through March 16, 1979. The ' effective release height was computed from the following equation: he = hr-(h ltk+hrp where the downwash correction factor (as defined by Equation (5) in Regulatory Guide 1.111, Rev. 1) is included in the equation for h pr (see Equation E.3-5). Values of topographic heights were ccnservatively assessed as the maximum height within a particular annulus-sector (annsect). An annsect is an area bounded by a 22.5-deg sector and any two radial distances from the release point. For A-D stability conditions, plume rise for nonbuoyant sources was calculated by the following algorithm: when "e! 150 h 1.5 E.3-4 h = 1,44 I
/ ue ) */a / x ) */ 3 d'.
i (d j I U ( 150) when u,/ E15 0 < l . 5 ,
'
- E.3-5 h =1.44!$* \ X
^
d-3 1.5-
\ "150/
d; Pr ( u150 / (d . and fu, ) E.3-6 h pr43l- 1 d; ("150/ E-4
r The result from - Equation E.3-I orI5'.3-5 ,(wh[ichever condition exists) is then compared to Equation E.3-6 and the smaller value of hpr is used. For. E-G stability conditions, Equations E.3-4, E.3-5, and E. 3-6 are compared with: w = w.. - <h .s-n> ,P r ". 4 (*/S and, h pr =1.5(Im/ bl50 S where 2' :- ~~ > -e -' m>> " m- >u-.- Fm* 4 and the smallest value was chosen. In the ground level portion of Equation E.3-1, ' the vertical dispersion ter,m: ..... ,-l, ,i- a , ,J., s - l 2 a*i,k +0.Sh{/tr\b f was co strained to be less than or equal to 1.7325 .
.=.
, u
,i zi.,k
- . s -- >
E.4 (CHI /Q) and D/Q Modeling Techniques Annual average depeleted relative concentration values were conservatively assumed to be equal to annual average relative Therefore, no credit concentration values (CHI /Q - (CHI /Q)o) . was taken for attendant plume depletion of radiciodines and particulates. Annual average relative deposition values were calculated using Regulatory Guide 1.111, Rev. 1 with the following equations (ki)=(Eff > "1 he,4
- k .., ,1- "" h,, l l
E-5 l_'_
For the c,onditionally elevated release points, Figures 6 through 9 of Regulatory Guide 1.111, Rev. 1 were used to calculate the ( 8 /Q)g and ( 6 /Q){ values, while for the ground level re-lease points, Figure 6 was utilized to calculate the ( 8 /Q)g value. E.5 Methodology Employed for Intermittent Release The methodology employed in the calculation of intermittent release CHI /Qs and D/Qs was as follows:
.l. Two-hour sector-averaged CHI /Q values were calculated with-out terrain recirculation factors.
- 2. The 15 percent, 1 hour value was plotted at 2 hours on leg-log coordinates, while the annual average value was plotted at 8,760 hr. A straight line connecting the two points was drawn..
- 3. Log-log interpolation
- based on total ground intermittent release hours versus annual hours yielded a CHI /Q multi-plier.
- 4. The multiplier was applied to annual average CHI /O and D/Q values to obtain intermittent CHI /O and D/Q values.
For River Bend Station, a 320 hr/yr intermittent release through the containment building vent from the mechanical vacuum pump was evalu .2d. e E-6 k _ _ _ - - - - _ _ _ _ _ _ _ _ _ ____ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _._ _ _ _ _ __ _ _ ___
~
f f i. l ... . _ _ . . . . . . . .. . TABLE E-1 l ANNUAL AVERAGE CHI /Q VALUES x 10-7 (sec/m3 ) i- FOR RESTRICTED AREA BOUNDARY l
~
l' Main' Plant Exhaust Radwaste Building Sector Duct (Continuous) Exhaust Duct (Continuous) l ruaar,e .s.a a..; '- - -
'-----u-S 12.4 105 SSW . ... .. .. 13.1. 121 SW 11.2 152
. WSW 14.7 247 578
- l. W -
19.7 WNW 29.1 384 l NW __ 14.4. 262 NNW 12.1 138
-N 15.0 180 NNE .. 20.0 _. 211 NE 12.9 150 ENE -- 9.86 146 E 7.37 168 ESE 8.33 - =154
- SE 6.99 93.1 IL SSE 6.53 45.6 -
O t' S s
f:
~
l-TABLE E-2 l l ANNUAL AVERAGE D/Q VALUES x 10-9 (m-2) FOR RESTRICTED AREA BOUNDARY t Main Plant Exhaust Radwaste Building ! Sector Duct (Continuous)._ Exhaust Duct (Continuous)
.S 9.37 21.4 SSW 8.47 25.1 .
SW 8.62 25.3 . WSW 8.75 29.0 W 13.1 61.1
- WNW 18.1 46.0 NW 9.18 40.8 NNW 9.92 24.7 N .. 11.0 28.6
! NNE 10.6 27.1 NE 7.77 22.3 ENE 9.27 22.7 E 7.53 23.0 ESE 7.06 24.6 SE 6.30 17.2 SSE 5.01 11.8 t I 6 I l Y
_ , _ . _ . . . _ _ _ _ _ _ _ _ - _ - _ _ - . _ - . _ _ _ -____.__ --.- - ~ _ e w . m
- APPENDIX F MAXIMUM X/O AND D/Q VALUES FOR INDIVIDUAL LOCATIONS
.' ~ . _ _ _ .
; TABLE F-1 ATMOSPHERIC DISPERSION A ID DEPOSITION. RATES FOR THE MAXIMUM INDIVIDUAL DOSE CALCULATIONS
- t il 1 }
h( i Ih i !
. i .<
f Location Radwaste Bldg. Main Plant Analysis N d (adters) Exhaust Duct Exhaust Duct
-Gamma air d se (1) !k4mNNE 9 CHI /Q1(5) - 211.0 CHI /Q2 - 20.0 and Beta Air Dose Maximum Receptor (2) 1,260 m NW CHI /Q1 - 216.0 CHI /Q2 - 11.4 Resident Same D/Q1(6) - 32.9 D/Q2 - 6.92 Carden Same Meat animal Same Immersion Same Resident (3) 2,000 m NW CHI /Q1 - 75.5 CHI /Q2 - 4.57 Carden Same D/Q1 - 10.1 D/Q2 - 2.32 Milk animal 1,300 m NNW CHI /Q1 - 124.0 CHI /Q2 - 10.3 D/Q1 - 22.0 D/Q2 - 8.16 Hypothetical milk 1,173 m NNW CHI /Q1 - 138.0 CHI /Q2 - 12.1 animal (4) D/Q1 - 24.7 D/Q1 - 9.92
- Ref. Table 5.4-1 RBS ER-OLS i
Notes: _ (1) Maximum offsite location (property boundary) with highest CHI /Q (unoccupied). ! (2) Maximum occupied offsite location with highest CHI /Q and D/Q. (3) Maximum occupied location associated with maximum milk cow grazing pasture. (4) Hypothetical maximum grazing location for milk cow (see (3) above). (5) All CHI /Q = 10-7 sec/m3 (6) All D/Q = 10-9 m-2 l - l \ l l l
F APPENDIX G INSTANTANEOUS DOSE TRANSFER FACTOR TABLES r-m
- M
'O^>b q ms*dl>f EOW e -see = ~.- m sn e - .us,- -, w , -. s Sw . . w m ,e -
e
.M Y' WY 'y ' hsf Pff a4 Y sf a
. .. --+.,
t'KsM i'd'wAmh Mr M & F e W " i
TABLE C-1 ENVIRONMENTAL PATHWAY.- DOSE CONVERSION FACTORS P(i) FOR CASEQUS DISCllARGE PATHWAY' = 1NilALATION AGE GROUP = INEANT Organ' Dose Factors (mrem /yr per uCi/m3) 'Nuclide T. Body- CI-Tract Bone Liver Kidney Thyroid Lung Skin Hn-54 5.01E+00 7. 09 E+00 .0 2.55E+01 5. ole +00 .0 1.00E+03 .0 Co-60 'l.18E+0! 3.21E+01. .0 8.06E+00 .0 .0 4.53E+03 .0 Zn-65 3.12E+01 5.16E+01 1.94E+01 8.29E+0! 3.26E+01 .0 6.50E+02 .0 Sr-89 1.15E+01 6.43E+0! 4.00E+02 .0 .0 .0 2.04E+03 .0 - Sr-90 2.60E+03 .1'. 3 2 E +0 2 4.llE+04 .0 .0 .0 1.13E+04 .0 Cs-134 7.49E+01 1.34E+00 3.98E+02 7.06E+02 1.91E+02 .0 8. ole +01 .0 Cs-137 4.57E+01 1.34E+00. 5.52E+02 6.15E+02 1.73E+02 .0 7.16E+01 .0 Ba-140 2.91E+00 3.86E+01 5.63E+01 5.63E-02 1.35E-02 .0 1.60E+03 .0 Ce-141 2.00E+00 2.17E+01 2.79E+01 1.67E+01 5.28E+00 .0 5.19E+02 .0 1-131 1.97E+00 1.06E+00- 3.81E+0! 4.46E+01 5.21E+01 1.49E+04 .0 .0 1-133 5.63E+00 2.17E+00 1.33E+01 1.93E+01 2.25E+01 3.57E+03 .0 .0 11 - 3 6.50E+01 6.50E-01 .0 6.50E-01 6.50E-01 6.50E-01 6.50E-01 6.50E-01 Based on I uci/sec release rate of each nuclide (i) and a value of 1.0 for X/Q and relative deposition. Note: The units for C-14 and H-3 are (mrem / year per uCi/m3).
TABLE C-2 ENVIRONMENTAL PATl!WAY - DOSE CONVERSION - FACTORS P(i) FDR CASEOU'S DI' CHAR'GE $ PATHWAY =
.GROUNDI PLANE DEPOSITION.
AGE GROUP = ALL. Organ Dose Factors (m2 -mrem /yr per uCi/sec) Nuclide T. Body- CI-Tract Bone Liver Kidney Thyroid LEng Skin Mn-54 1.39E+06 1.39E+06 1.39E+06 1.39E+06 1.39Et06 1.39E+06 1. 3'OE+06 1.63E+06 Co-60 2.16E+07 2.16E+07 2.16E+07 2:16E+07 2.16E+07 2.16E+07 2. l'6'E+ d7 2.55E+07 Zn-65 7.49E+05 7.49E+05 7.49E+65 7449E+05 7.49E+05 7.49E+05 7.4NE+05 8.62E+05 Sr-89 2.17E+01 '2.17E+01 2.17E+01 2 41'7E +01 2.17E+0! 2.17E+01 2. lie +di 2.52E+01 Cs-134 6.87E+06 6.87E+06 6.81s+66 6.8'7E+06 6.87E+06 6.87E+06 6.87E+0'6 8.01E+06 Cs-137 1.04E+07- 1. 04E+ 07 1.04E+67 1. 04 E + 0'7 i.04E+07 1.04E+07 1.ddE+0'7 1.21E+07 Ba-140 2.06E+04 2.06E+04 2.06E+d4 2'.d6E404 d.06EiO4 2.06E+04 2.ddE+0'4 2.36E+04
-Ce-141 1.37E+04' l.37E+04 14 37'E'+ 04 1.37E+04 I.37E+04 1.37E+04 1. 3 fE + 0'4 1.55E+04 I-131 8.65E+03 8.65'E+03 8'.65E+03 8.65E+03 8.65E+03 8.65E+03 8.6hE+0'3 1.05E+04 1-133 1.23E+03' l.23E+03 l'. 2dE'+ 63 1.23E+03 l'.23E+03 1.23E+03 1. 2'3 E + 03 1.50E+03 L
t .. .ld i 3
.j- 1 , 'l ta 'If I ' Based on 1 uCi/sec release rate of each nuclide (i) and a value of 1.0 for X/Q and relative deposition, m Note: 'The uni'ts for' C-14 and 11-3 are (mrem / year' per uCi/m3),
Z - '! -
- b y t- v ' h+ /
m b z O
+':
, s
/A~ _
- o
, TA BLE G-3
- 1. -
1 ENVIRONMENTAL:-PATHWAY '- DOSE CONVERSION FACTORS ~ P(i) FOR CASEOUS DISCHARGE s. PATHWAY- = ' COW' MILK-AGE GROUP 3 = -INFANT.- Organ Dose Factors (m2 -mrem /yr per uCi/sec) Nuclide T.! ody. B Gi-Tract = Bone Liver Kidney Thyroid Lung Skin > I iMn-54 - 6.62E+03 il.07E+04 .0 2.92E+04 6.47E+03 .0 .0 .0 , :Co-60 1.55E+05 1.56E+05~ .0 6. 56E+ 04 .0 .0 .0 .0 Zn 7.47E+06 .l.37E+07~ 4.72E+06 1.62E+07 7.86E+06 .0 .0 .0
- Sr-89 2.88E+05 ,2.07E+05 1.00E+07 .0 .0 .0 .0 .0 <
p Sr-90 2.42E+07 1.19E+06 9.52E+07 .0 .0 .0 .0 .0 , Cs-134~ 5.08E+06- 1.37E+05L 2.70E+07 5.03E+07 1.29E+07 .0 5.31E+06 .0 Cs-137 3.24E+06 1.43E+05 a3.91E+07 4.58E+07 1.23E+07 .0 4.97E+06 .0 Ba-140 1.11E+04 5.31E+04 2.16E+05 2.16E-02 3.13E-01 .0 1.33E+02 .0 i- Ce-141 1.54E+01 -6.77E+04 2.15E+02 1.31E+02 4. 04E+01 .0 .0 .0 1-131: 6.50E+05 5.27E+04; .l.25E+06 1.48E+06 1.73E+06 4.86E+08 .0 .0 I-133: 7.25E+03'- '4.19E+03 1.70E+04 2.47E+04 2.91E+04 4.50E+06 .0 .0 H-3 1.50E+00 1. 50E+ 00 .0 1.50E+00 1.50E+00 1.50E+00 1.50E+00 1.50E+00 i t-C 6.99E+02- 6.99E+02 3.27E+03 6.99E+02 6.99E+02 6.99E+02 6.99E+02 6.99E+02 Based on 1.0 uCi/sec~ release rate of each'nuclide (i) and a value of 1.0 for X/Q 'and relative deposition. Note: The units for C-14' E and H-3 are (mrem / year per uCi/m3), 4 1 3' I i-
7 .. 2, . - , . . 7 . . . . APPENDIX H GASEOUS MPC VALUES a 6
- o A e M 9 e W .- F 7 -
. 7 ; - - t-
;* , a 7 % .= . R ,3 1 _ -; w - - .
s .- . . v -
- w N-y.g . ,% -% j .= * * % , L'* .
~
s 1
- s ~ , - m , ' , . ~ -
y' .- V 2 b i h I N-s-.
TABLE H-1 MAXIMUM PERMISSIBLE CONCENTRATIONS IN AIR IN UNRESTRICTED AREAS MPC MPC Nuclide* (uCi/cc) Nuclide* (uCi/cc) Ar-41' 4 E-8 Y-91 1 E-9 Kr-83m- None** Zr-95 1 E-9 b- Kr-85 m 1 E-7 Nb-95 3 E-9 Kr-85 3 E-7 Ru-103 3 E-9 Kr-87 2 E-8 Ru-106 2 E-10 Kr-88 2 E-8 Ag-110m 3 E-10 Kr-89 None Sn-ll3 2 E-9 Kr-90 None In-ll3m 2 E-7 Xe-131m 4 E-7 Sn-123 None Xe-133m 3 E-7 Sn-126 None Xe-133 3 E-7 Sb-124 7 E-10
-Xe-135m None Sb-125 9 E-10 Xe-135 1 E-7 Te-125m 4 E-9 Xe-137 None Te-127m 1 E-9 Xe-138 None Te-129m 1 E-9 H-3 2 E-7 _I-130 None P-32 2 E-9 I-131 1 E-10 Cr-51 8 E-8 I-132 3'E-9 Mn-54 1 E-9 I-133 4 E-10 Fe-59 2 E-9 I-134 6 E-9
-Co-57 6 E-9 I-135 1 E-9 Co-58 -.2 E-9 Cs-134 4 E-10 Co-60 3 E-10 Cs-136 6 E-9 Zn-65 2 E-9 Cs-137 5 E-10 Rb-86 2 E-9 Ba-140 1 E-9 Sr-89 3 E-10 La-140 4 E-9 Sr 3 E-11 Ce-141 5 E-9 Rb-88 None Ce-144 2 E-10
- If a'nuclide is not listed, refer to 10CFR20 Appendix B'and use the most conservative insoluble / soluble . MPC ' where they are given:in Table II, Column I.
** None (as per 10CFR20, Appendix B) "No MPC limit.for any sin-gle radionuclide'not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive half-lives less than 2 hours."
e l 1 i
.-c. .
APPENDIX I _ ._ ENVIRONMENTAL DOSE TRANSFER FACTORS _ . FOR GASEOUS EFFLUENTS
. . - ... . . . .. a.. - . ..
T - W W e e." % .D M N 4
,. . . . .* *,, o,
.e .y,s . %1 .. a -,
.1.% .v p m no g. G = g
#*k . *T g 4
- an* ,A 4 .
M ee g M .! 8$ a4k
- M M d
, 1 .- . .. a, r. .
.c . , . .
u % . ' ^5
e. TABLE I-l'
' ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS ' DISCHARGE -PATHWAY = INHALATION ACE CROUP = ADULT Organ Dose Factors'(mrem /yr per uCi/m 3)
Nuclide- T. Body CI-Tract Bone Liver Kidney Thyroid Lung Skin Mn 6.33E+00 7.78E+01 .0 3.98E+01 9.89E+00 .0 1.41E+03 .0 Co-60 1.49E+01 2.86E+02 .0 1.16E+01 .0 .0 6.00E+03 .0 Zn-65' .4.68E+01 5.37E+01 3.26E+01 1.04E+02 6.93E+01 .0 8.68E+02 .0 Sr 8.77E+00 3.51E+02 3.06E+02 .0 .0 .0 1.41E+03 .0 Sr-90 6.13E+03 7.25E+02 9.97E+04 .0 .0 .0 9.65E+03 .0 Cs-134 7.32E+02 'l.05E+01 3.75E+02 8.52E+02 2.89E+02 .0 9.81E+01 .0 Cs-137 4.30E+02 8.44E+00 4.81E+02 6.24E+02 2.24E+02 .0 7.56E+01 .0 Ba-140 2.58E+00 -2.20E+02 3.92E+01 4.93E-02 1.68E-02 .0 1.28E+03 .0 Ce-141- 1.54E+00 1.21E+02 '2.00E+01 1.36E+01 6.30E+00 .0 3.63E+02 .0 1-131 2.06E+01 6.31E+00 2.53E+01 3.59E+01 6.16E+01 1.20E+04 .0 .0 1-133 4.54E+00 8.93E+00 8.68E+00 1.49E+01. 2.60E+01 2.16E+03 .0 .0 H-3 1.27E+00 1.27E+00 .0 1.27E+00 1.27E+00 1.27E+00 1.27E+00 1.27E+00 Based on 1 uCi/sec release rate of each nuclide (i) and.a value of 1.0 for X/Q and relative deposition.
QD ~ ~ '~ s D TABLE I-2 ENVIRONMENTAL PATHWAY - DOSE CDNVERSION FACTORS R(i) FOR . GASEOUS DISCHARbE PATHWAY = -INHALATION ACE GROUP. = . TEEN
-drgan Dose Factors (mrem /yf per uCi/m3 )
Nuclide T. Body GI-Tract Bone -Liver Kidne'y Thyroid Lung Skin Ma-54 8.44E+00 6.ilE+01 ;0 5.14E+dl 1.28E+dl' .0 1.99k+03 .d Co-60 1.99E+01 2.61E+02 .d 1.52E+01 .'O .0 8.77E+03 ;0 Zn-65 6.27E+01 4.69E+01 $.88E+01 I . 34 E+02 8.68E+01 .0 1.25E+03 .0 Sr-89 1.25E+01 3.73E+0d 4.37E+d2 .0 .0 .0 2.43E+03. .0 Sr-90 6.71E+03 -7.69E+02 i . 09 E+05 .0 .D .0 1.66E+04 .0 Cs-134 5.52E+02 9.81E+00 5;b5E+02 i.13E+d3 3.77E402 .0 1.47E+02 .0 Cs-137 3.13E+02 8.52E+0d 6.74E+02 8.52E+02 3.06E+02 .0 1.21E+02 .0 Ba-140 3.54E+00 2.50E+02 5;50E+bl 6.74E-d2 2.29E-02 .0 2. 04E+03 .0 Ce-141 2.18E+00 1.27E+02 2.85h+UI i.91E+01 8.93E400 .0 6.17E+02 .0 1-131 2.65E+01 6.52E+0d 3.56E+01 4.94E+di 8.44E401 1.47E+04 .0 .0 1-133 6.26E+00 1.d4E+01 1.22E+01 2.06E+di 3.61E+01 2.94E+03 .0 .0 H-3 1.28E+00 1.28h+0d .0 l1.28E+00 1.28E400 1.28E+00 1.28E+0d 1.28E+00 Based on 1 uCi/sec release rate 6f eaEh nuclide (i) and'a value of 1.0 for X/Q and relatise depdsition.
.TA BLE 1-3 .
ENVIRONMENTAL PATHNAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE . PATHWAY = INHALATION ACE GROUP = . CHILD Organ Dose Factors (mrem /yr per uCi/m3) Nuclide .T. Body 'GI-Tract Bone'- Liver Kidney Thyroid Lung Skin-Mn-54 9.56E+00 .2.30E+01 .0 -4.31E+01 1.01E+01 .0 1.58E+03 .0 co-60 2.28E+01 9.67E+01- .0, .l.32E+01 .0 .0 7.10E+03 .0 Zn 7.07E+01 1. 64 E+01 4 ~. 28E+ 01 'l.14E+02 7.18E+01 .0 1.00E+03 .0 Sr-89 1.73E+01 1.68E+02 6.03E+02 .0 .0 .0 2.17E+03 . 'O
.Sr-90 '6.47E+03. 3.45E+02 1.02E+05 .0 .0 .0 1.48E+04 .0 Cs-134 2.26E+02 3.87E+00- 6.55E+02 1.02E+03 3.32E+02 .0 1.22E+02 .0 Cs-137 .1. 29 E+02 - 3. 64E+00 9.11E+02 8. 29 E+02 2.84E+02 .0 1.05E+02 .0 Ba-140 4.35E+00' 1.02E+02 .7.44E+01 6.51E-02 2.12E-02 .0 1.75E+03 .0 Ce-141- 2.91E+00' '5.69E+01 3.94E+01. 1.96E+01 8.59E+00 .0 5.47E+02 .0 I-131 2.74E+01 2.86E+00 ' 4. 84E+01 - 4.84E+01 7.92E+01 1.63E+04 .0 .0 I-133 . 7.74 E+00 ' 5.50E+00 1.67E+01 2. 04E+01 3.40E+01 3.87E+03 .0 .0 H-3 1.13E+00 1.13E+00 .0 1.13E+00 1.13E+00 1.13E+00 1.13E+00 1.13E+00 Based on 1 uCi/sec: release rate of each nuclide (i) and a value of 1.0 for X/Q and relative deposition.
~
s , 1
..TA BLE .I . ENVIRONMENTAL PATHWAY. - DOSE.; C0gERSION FACTORS R{i) FOR GASEOUS DISCHARGE
=
PATHWAY. INHALATION'. ,
.. AGE GROUP; = INFANT Organ Dose "'
Factors (mrem /yr.per uCi/m3 )
. Nuclide -T. Body GI-Tract. Bone - ' i. ive r Kidney Thyroid Lung Skin Mn-54: :5.01E+00 7.09 E+00 .0 ,2.55E+Q1.5.01E+Q0 .0 1.00E+03 .0 Co-60-- 1.18E+01 ~3.21E+01 .0 8.06E+00 .0 .0 4.53E+03 .0 Zn-65 J3.12E+01 5.16E+01 1.94E+01 '6.29E&01 3.26E+gl .0 6.50E+02 .0
. Sr-89 :1.15E+01 6.43E+01 4.00E+02- .0. .0 .0 2.04E+03 .0 Sr-90 2.60E+03 .1.32E+02 -4.llE+04 .0 .0 .0 1.13E+04 .0 Cs-134 7.49E+01 '1.34E+00 -3.98E+02 J.06E+02 1.91E+g2 .0 8.01E+01 .0 Cs-137 .4.57E+01 ' l . 34 E+00 5.52E+02 6.15E+02 1.73E+g2 .0 7.16E+01 .0 Ba-140 2.91E+00- 3.86E+01 5.63E+Q1 5.63E-02 1.35E-p2 .0 1.60E+03 .0 Ce-141 2.00E+00 2.17E+01 _2.79E+01 1.67E+91 5.28E+00
.0 5.19E+02 .0
- I-131 .l.97E+01 1.06E+00 -3.81E+01 4.46E+91 5.21Etpl 1.49E+04 .0 .0 I-133 5.63E+00 2.1,7E+00 1.33E+Q1 1.93E+Q1 2.25E+01 3.57E+03 .0 .0 H-3 6.50E-01' '. 6. 50E-01 .0 6.50E-01 6.50E-g1 6.50E-01 6.50E-01 6.50E-01 Based on 'l uCi/sec release rate of each nuclide (i) andavalueof1.0.forX/Qandr$lativ'e-depoytion.
~
ngj -- . . TABLE I-5 ENVIRONMENTAL; PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE
~ PATHWAY = GROUND PLANE DEPOSITION
-ACE CROUP = ALL Organ' Dose Factors (m2 -mrem /yr per uCi/sec)
Huclide T. Body CI-Tract Bone Liver Kidney . Thyroid Lung Skin Mu-54 1.39 E+06 1.39 E+06 1.39E+06 1,39 E+06 1.39E+06 1.39 E+06 1. 39 E+06 1.63E+06 Co-60 2.16E+07 2.16E+07 2.16E+07 2.16E+07 2.16E+07 2.16E+07 2.16E+07 2.55E+07 Zn-65 7.49E+05 7.49E+05 7.49E+05 7.49E+05 7.49E+05 7.49E+05 7.49E+05 8.62E+05 Sr-89 2.17E+01 2.17E+01 2.17E+01 2.17E+01 2.17E+01 2.17E+01 2.17E+01 2.52E+01 Cs-l'4 3 6.87E+06 6.87E+06 6.87E+06 '6.87E+06 6.87E+06 6.87E+06 6.87E+06 0.01E+06
- Cs-137 - 1. 04E+ 07 1. 04E+07 .l.04E+07 1.04E+07 1.04E+07 1.04E+07 1.04E+07 1.21E+07 Ba-140 2.06E+04 2.06E+04 2.06E+04' 2.06E-04 2.06E-04 2.06E+04 2.06E+04 2.36E+04 Ce-141 1.37E+04 1.37E+04 1.37E+04 1.37E+04 1.37E+04 1.37E+C4 1.37E+04 1.55E+04 1-131 8.65E+03 8.65E+03 8.65E+03 8.65E+03 8.65E+03 8.65E403 8.65E+03 1.05E+04 I-133- 1.23E+03 1.23E+03 1.23E+03 1.23E+03 1.23E+03 1.23E+03 1.23E+03 1.50E+03 Based on 1 uCi/sec release rate of each nuclide (i) and a value of_1.0 for-X/Q and relative deposition.
7.
+
?
YABLE' i-6 ,
' ENVIRONMENTAL PATHWAY - DOSE ' COINERSION FACTORS R(i) FOR CASEOUS DISCHARGE
' PATHWAY = COW MILK - 41' AGE CROUP = ADULT Organ Dose ~ Factors (m2 -mRed/yr per uCi/sec) Nuclide T. Body CI-Tract Bone Liver Kidney Thyroid Lung Skin Mn-54 1.20E+03 l'93E+04
. 1. 0 ' '- d.30E+0'3 1. 88 E+'03 .0 ' .0 .0 Co-60 2.69E+04 2.29E+05 '0. 1.22E+04 .0 .0 .0 .0 Zn-65 1.68E+06 2. 34 E+06 1.17E+06 3.71E+06 2.48E+06 .0 .0 .0 Sr-89 3.32E+04 1.86E+05 1.16E+06 .0 ' .0 -" .0 .0 '. 0 Sr-90 8.99E+06 1. 06E+06 3.66E+07 '. 0 .0 .0 .0 .0
~
-Cs-134 8.13E+06 1.74E+05 4.18E+06 9'.94E+06 3.22E406 .0 1.07E+06 .0 Cs-137 5.02E+06 1.48E+05 5.61E+06- 7.67E+06 2.60E+06 .0 8.65E+05 .0 Ba-140 1.58E+03 4.96E+04 2.41E+ 04 3'.03E+01 1.03E401 .0 1.73E+01 .0 Ce-141 ' l . 84 E+00 6.21E+04 2.40E+01- 'f.62E+01 7.54 E+D0 .0 .0
'. 0 I-131 1.12E+05 5.15E+04' l'.37E+05 l'.95E+05 3.35E+D5 6.40E+07 .0 .0 1-133 9.62E+02 2.84E+03 1.81E+03 3.15E+03 5.50E+03 4.64E+05 .0 .0 H-3 .4.80E-01 4.80E-01 ,
; .0 , , t i,4.80E-01 4.80E-01 4.80E-01 4.80E-01 4.80E-01 7.37E+01 " 3.69E+02 *7.37E+01- 7.37E+01
~
C-14 7.37E+01 7.37E+01 7.37E+01 7.37E+01 Based on I uCi/sec release rate of-each nuclide (i) and a value of 1.0 for X/Q and-relative deposition. Note: The units for 'C-14 and H-3 are (mrem / year per uCi/m3).
s
' TABLE 1-7 ENVIRONMENTAL ; PATHWAY - DOSE. CONVERSION FACTORS R(i)' FOR CASEOUS DISCHARCE PATHWAY =' COW MILK ACE GROUP = TEEN Organ Dose Factors (m2 -mrem /yr per uCi/sec)
Nuclide- T. Body- CI-Tract Bone Liver Kidney Thyroid Lung Skin Mn-54 2.08E+03 2.15E+04 .0 1.05E+04 3.13E+03 .0 .0 .0 Co-60 4. 66E+ 04 2.69E+05 .0 2.078+04 .0 .0 .0 .0 Zn-65 2.90E+06 2.64 E+06 1.79E+06 6.22E+06 3.98E+06 .0 .0 .0 Sr-89 6. llE+ 04 2.54E+05 2.13E+06 .0 .0 .0 .0 .0 , Sr-90 1.28E+07 1.45E+06 5.17E+07 .0 .0 .0 .0 .0 Cs-134 7.92E+06 2.12E+05 7.26E+06 1.71E+07 5.43E+06 .0 2.07E+06 .0 .cs-137 4.71E+06 1.92E+05 1.02E+07 1.35E+07 4.60E+06 .0 1.79E+06 .0 Ba-140 2.80E+03 '6.71E+04 4.35E+04 5.33E+01 1.81E+01 .0 3.58E+01 .0 Ce-141 3.38E+00 8.41E+04 4.40E+01 2.94E+01 1.38E+01 .0 .0 .0 I-131 1.86E+05 6.86E+04- 2.48E+05 3.47E+05 5.97E+05 1.01E+08 .0 .0 I-133 1.71E+03 4.25E+03 3.31E+03 5.62E+03 9.86E+03 7. 84 E+ 05 .0 .0 H-3 6.25E-01 -6.25E-01 .0 6.25E-01 6.25E-01 6.25E-01 6.25E-01 6.25E-01 C-14. 1.36E+02 1.36E+02 6.80E+02 1.36E+02 1.36E+02 1.36E+02 1.36E+02 1.36E+02 Based on 1 uCi/sec. release ' rate of each nuclide (i) and a value;of 1.0 for X/Q-and relative deposition.
~
Note: The units for C-141 and H-3 are (mrem / year per uCi/m3 ).
, ,a
.. i ). _
~
< :c:
a: _. m TABLE I-8 ' ENVIRONMENTAL PATHWAY , . DOSE COMVERSION FACTORS R(i)L FOR CASEOUS DISCHARGE
-PATHWAY = COW MILK:
AGE GROUP = CHILD Organ Dose Factors (m2-mRemlyr per 'uCi/sec) Nuclide. T. Body CI-Tract Bone Liver' ' Kidney- Thyroid . Lung Skin Mn-54 ' 4.18E+03 .l.32E+04 .0' '1. 57 E+04 4.40E+03 .0 .0 .0 Co-60 9.48E+ 04 1.78E+05- .0 ~3.21E+04 .0 .0 .0 .0
, Zn-65 -5.83E+06 1.65E+06 3.52E+06' 9,.37E+06 -- 5.90E+06 .0 .0 .0 Sr-89 1.51E+05 2.05E+05- 5.28E+06 '0
. .0 .0 .0 .0
~Sr-90 2.22E+07 [1.18E+06 .8.74E+07, .0 .0 .0 .0 .0
'Cs-134 5. 79E+ 06 -1.48E+05 - 1. 67E,+ 07 :2.75E+07 8.51E+06 .0 3.05E+06 .0 Cs-137 3.46E+06 1.47E+05, -2.45E+07 : 2.34E+07 7. 64 E+06 .0 2.75E+06 .0.
Ba-140 6.13E+03 5.32E+04 1.05E+05- ,9.20E+01 3.00E+01 .0 5.49E+01 .0. Ce-141 8.03E+00' 6.74E+04 1.0$E+02 .5.41E+01 2.37E+01 .0 .0 .0 I-131 3.43E+05 - 5. 38E+04 6.01E+05 16.04E+05 : 9.92E+05 2.00E+08 .0 .0 1-133 3.77E+03 4.01E+03 8.05E+03' 9.95E+03 1.66E+04 1.85E+06 .0 .0
;H-3 9.88E-01 ' 9. 88E-01. .0- 9.88E-01 9. 88E-01 9.88E-01 9.88E-01 9.88E-01 C-14 3.34E+02 3.34E+02 l1.67E+03 " 3. 34E+02 3.34E+Q2 - 3. 34 E+02 3.34E+02 3.34E+02 I
Based cns 1,uci/sec release rate of 'each nuclide (i) and a value of'l.0 for X/Q and-relative deposition.
' Note: The units for C-14 and H-3, 'are 3 (mrem / year ' per . uCi/m 3 ),
i I i t.
c TABLE I-9 ENVIRONMENTAL PATHWAY. - DOSE CONVERSION FACTORS R(i) FOR GASEDUS DISCHARGE PATHWAY' = COW MILK ACE CROUP = INFANT Organ Dose Factors (m2 -mrem /yr per uCi/sec) Nuclide T. Body CI-Tract Bone -Liver Kidney Thyroid Lung Skin Mn-54 6.62E+03 1.07E+04 .0 2.92E+04 6.47E+03 .0 .0 .0
-Co-60 1.55E+05 1.56E+05 .0 6.56E+04 .0 .0 .0 .0 Zn-65 7.47E+06 1.37E+07 4.72E+06 1.62E+07 7.86E+06 .0 .0 .0 Sr-89 -2.88E+05 2.07E+05 1.00E+07 .0 .0 .0 .0 .' O Sr-90 2.42E+07- 1.19E+06 9.52E+07 .0 .0 .0 .0 .0 Cs-134 5.08E+06 1.37E+05 2.70E+07 5.03E+07 1.29E+07 .0 5.31E+06 .0 Cs-137 3.24E+06 1.43E+05 3.91E+07 4.58E+07 1.23E+07 .0 4.97E+06 .0 Ba-140 1.llE+04 5.31E+04 2.16E+05 2.16E+02 5.13E+01 .0 1.33E+02 .0 Ce-141 1. 54 E+01 6.77E+04 2.15E+02 1.31E+02 4. 04 E+01 .0 .0 .0 1-131 6.50E+05 5.27E+04 1.25E+06 1.48E+06 1.73E+06 4.86E+08 .0 .0 1-133 -7.25E+03 4.19E+03 1.70E+04 2.47E+04 2.91E+04 4.50E+06 .0 .0 H-3 1.50E+00 1.50E+00 .0 1.50E+00 1.50E+00 1.50E+00 1.50E+00 1.50E-00 C-14 6.99E+02 6.99E+02 3.27E+03 6.99E+02 6.99E+02 6.99E+02 6.99E+02 6.99E+02
*ased on l'uCi/sec release rate of each nuclide (i) and a value of 1.0 for I/Q and relative deposition.
Note: The units for C-14 and H-3 are (mrem / year per uCi/m3). t
re s a e i; TABLE I-10 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR CASEOUS DISCHARGE PATHWAY = -GOAT MILK ACE GROUP = - ADULT Organ Dose Factors (m2 -mrem /yr per uCi/sec) Nuclide T. Body CI-Tract Bone Liver Kidney Thyroid- Lung Skin Mn-54 1.44E+02 2.32E+03 .0' 7.56E+02 2.25E+02 .0 . . 'O 0
- Co 3.23E+03 2.75E+04 .0 1.47E+03 .0 .0 .0 .0 Zn-65 2.01E+05 2.81E+05 .l.40E+05 4.46E+05 2.98E+05 .0 .0 .0 Sr-89 6.98E+04 -3.90E+05 2.43E+06 .0 .0 .0 .0 ,0 Sr-90 1.89E+07 2.22E+06 7.69E+07 .0 .0 .0 .0 0 Cs-134 2.44E+07 15.22E+05' 1.25E+07 2.98E+07 9.65E+D6 .0 3.20E+06 .0
- Cs-137 1.51E+07- 4.45E+05 1.68E+07 2.30E+07 7.81E+06 .0 2.60E+06 .0 ,
Ba-140. 1.89E+02 5.96E+03 2.89E+03 3.63E-00 1.24E-00 .0 2.08E+00 .0 ce-141 2.21E-02 7.45E+03 2.88E+00 1.95E+00 9.05E-01 .0 .0 .0 1-131 1.34E+05 6.18E+04 1.64E+05 2. 34E + 05 4.02E+05 7.68E+07 .0 .0 1-133- 1.15E+03- .3.40E+03 2.18E+03 3.79E+03 6.61E+03 5.56E+05 .0 .0 H-3 9.79E-01 9.79E-01 .0' 9 79E-01 9.79E-01 9.79E-01 9.79E-01 9.79E-01 C-14 -7.37E+01 7.37E+01 3.69E+02 7.37E+01 7.37E+01 7.37E+01 7.37E+01 7.37E+01 Based on 1 uCi/sec release rate of each nuclide (i) and a value of 1.0 for. X/q and relative deposition. Note: The units for C-14 and H-3 are (mrem /ypar per uCi/m 3).
,i TABLE I-ll
!i ;f i i ENVIRONMENTAL PATHERY h DOSE .. CONVERSION FACTORS R(i) FOR CASEOUS DISCHARCE I! >
if3y 5 I , PATHWAY = COATMIL}j EI 3 ACE CROUP -= TEEN 4 ; i ff'l(ij f g i
- Organ Dose Factors . (m2 -mrem /yr per uCi/sec)
Nuclide T. Body CI-Tract: 1 ?lBone Liver Kidney Thyroid Lung Skin Mn-54 2.50E+02 2.58E+03 .0 1.26E+03 3.76E+02 .0 .0 .0 Co-60 5.59E+03 3. 23E+ 04 .0 2.48E+03 .0 .0 .0 .0 Zn-65 3.48E+05 3.16E+05 2.15E+05 7.47E+05 4.78E+05 .0 .0 .0 S r-89 1.28E+05 5. 34E+ 05 4.48E+06 .0 .0 .0 .0 .0
+
S r-90 2. 68 E+ 07 3.05E+06 1.09E+08 .0 .0 .0 .0 .0 Cs-134 2. 38E+ 07 6.37E+05. 2.18E+07 ' 5.12E+07 1.63E+07 .0 6.22E+06 .0 Cs-137 1.41E+07 5.77E+05 3.05E+07 4. 06E +07 1.38E+07 .0 5.36E+06 .0 Ba-140 3. 36E+ 02 8.05E+03 -5.2?E+03 6.40E+00 2.17E+00 .0 4.30E+00 .0 ce-141 4.05E-01 1.01E+04 5.28E+00 3.53E+00 1.66E+00 .0 .0 .0 1-131 2.24E+05 8.23E+04 2.97E+05- 4.16E+05 7.16E+05 1.21E+08 .0 .0 1-133 2. 06E+03 5.10E+03 3.97E+03 6.74E+03 1.18E+04 9.41E+05 .0 .0 H-3 1.28E+00 1.28E+00 .0 1.28E+00 1.28E+00 1.28E+00 1.28E+00 1.28E+00 C-14 -1.36E+02 1. 36E+02 6.80E+02 1. 36E+02 1.36E+02 1.36E+02 1. 36 E + 02 1.36E+02 l l Eased on I uCi/sec release rate'of each nuclide (i) s-d a value of 1.0 for I/Q and -relative deposition. l l Note: The units for C-14 and H-3 are _ (mrem / year per uCi/m3 ). i i
TABLE I-12 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR CASEOUS DISCHARCE j - - PATHWAY = COAT MILK' ACE GROUP = CHILD Organ Dose Factors (m2 -mrem /yr per uCi/sec) Nuclide T. Body CI-Tract Bone Liver Kidney Thyroid Lung Skin Mn-54 5.02E+02 1.58E+03 .0 1.89E+03 5. 29 E+02 .0 .0 .0 Co-60 1.14E+04 2.14E+04 .0 3.86E+03 .0 .0 .0 .0 Zn-65 6.99E+05 1.97E+05 4.22E+05 1.12E+06 7.09 E+05 .0 .0 .0 Sr-89 3.17E+05 4.29E+05 1.11E+07 .0 .0 .0 .0 .0 Sr-90 4.66E+07 2.47E+06 1.84E+08 .0 .0 .0 .0 .0 Cs-134 1.74E+07 4.44E+05 5.02E+07 8. 24E + 07 2.55E+07 .0 9.16E+06 .0 Cs-137 1.04E*07 4.40E+05 7.35E+07 7.03E+07 2.29E+07 .0 8.24E+06 .0 Ba-140 7.36E+02 6.38E+03 1.26E+04 1.10E+01 3.59E+00 .0 6.58E+00 .0 Ce-141 9.63E-01 8. 09 E +03 1.30E+01 6.49E+00 2.84E+00 .0 .0 .0 1-131 4.12E+05 6.46E+04 7.21E+05 7.25E+05 1.19E+06 2.40E+08 .0 .0 1-133 4.52E+03 4.81E+03 9.66E+03 1.19E+04 1.99E+04 2.22E+06 .0 .0 H-3 2.02E+00 2.02E+00 .0 2.02E+00 2.02E+00 2.02E+00 2.02E+00 2.02E+00 C-14 3. 34 E +02 3. 34 E +02 1.67E+03 3. 34 E + 02 3. 34 E +02 3. 34 E+ 02 3. 34 E + 02 3. 34 E +02 Based on 1 uCi/see release rate of each nuclide (i) and a value of 1.0 for I/Q and relative deposition. Note: The units for C-14 and H-3 are (mrem / year per uCi/m 3). (
TABLE I-13 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR CASEOUS DISCILARGE PATINAY = COAT MILK ACE CROUP = INEANT Organ Dose Factors (m2 -mrem /yr per uCi/sec) Nuclide T. Body CI-Tract Bone Liver Kidney Thyroid Lung Skin Mn-54 7.95E+02 1. 29 E+03 .0 3.51E+03 7.77E+02 .0 .0 .0 Co-60 1.86E+04 1.87E+04 .0 7.87E+03 .0 .0 .0 .0 2n-65 8.96E+05 1.64E+06 5.67E+05 1.94E+06 9.43E+05 .0 .0 .0 Sr-89 6.05E+05 4. 345+05 2.11E+07 .0 .0 .0 .0 .0 Sr-90 5. 09 E +07 2.50E+06 2.00E+08 .0 0 .0 .0 .0 Cs-134 1.52E+07 4.10E+05 8.09E+07 1.51E+08 3.88E+07 .0 1.59E+07 .0 Cs-137 9.73E+06 4.29 E+05 1.17E+08 1.37E+08 3.68E+07 .0 1.49E+07 .0 Ba-140 1. 34E+ 03 6.37E+03 2. 59 E+ 04 2.59E+01 6.16E+00 .0 1.59E+01 .0 Ce-141 1.85E+00 8.13E+03 2.58E+01 1.57E+01 4.85E+00 .0 .0 .0 1-131 7.80E+05 6.33E+04 1.50E+06 1.77E+06 2.07E+06 5.83E+08 .0 .0 1-133 8.70E+03 5.03E+03 2.04E+04 2.97E+04 3.49E+04 5.40E+06 .0 .0 H-3 3. 06E+ 00 3.06E+00 .0 3.06E+00 3.06E+00 3.06E+00 3.06E+00 3.06E+00 C-14 6.99E+02 6.99E+02 3.27E+03 6.99E+02 6.99E+02 6.99E+02 6.99E+02 6.99E+02 Based on 1 uCi/see release rate of each nuclide (i) and a value of 1.0 for X/Q and relative deposition. Note: The units for C-14 and H-3 are (mrem / year per uCi/m 3).
;7 TABLE I-14
, 4V. 1 -
Gi ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR CASEOUS DISCHARCE PATHWAY = MEAT ACE CROUP = ADULT
- .i Organ Dose Factors (m2 -mrem /yr per uCi/sec)
Nuclide T. Body CI-Tract Bone Liver Kidney Thyroid Lung Skin
-1 i t Mn-54 1.31E+03 2.llE+04- .0 6.88E+03 2.05E+03 .0 .0 .0 Co-60 1.23E+05 1.05E+06 .0 5.60E+04 .0 ,
.0 .0 .0 Zn-65 4.35E+05 6.07E+05 3.03E+05 9.63E+05 6.44E+05 .0 .0 .0 S r-89 6.91E+03 3.86E+04 2.dlE+05 .0 . 0, .0 .0 .0 .
S r-90 2.39E+06 2.81E+05 9.73E+06 ,.0 .0 ,
.0 .0, .0 Cs-134 9.46E+05 2.02E+04 4.86E+05 1.16E+06 3.74E+05 .0 1.24E+05 .0 Cs-137 5.93E+05 1.75E+04 6,.62E+05 9.06E+05 3.07E+05 .0 1.02E+05 . 0, Ea-140 1.69E+03 5.31E+04 2.5,8E+04 3.24E+0,1 1.10E+01 .0 1.85E+01 .0 Ce-141 8.90E-01 3.00E+04 1.16E+01 7. 84 E + 00 3. 64 E +00 .0 .0 .0 I-131 4.06E+03 1.87E+03 4.95E+03 7.08E+03 1. 21E+ 04 2.32E+06 .0 .0 I-133 9.03E-05 2.66E-04 1.70E-04 2.96E-04 5.17E-04 4.35E-02 .0 .0
. i H-3 2. 04 E-01 2.04E-01 .0 2. 04E-0,1 2.04Eq01 2.04E-01 2.04E-01 2.04E-01 C-14 6.76E+01 6.76E+01 3.38E+02 6.76E+01 6.76E+01 6.76E+01 6.76E+01 6.76E+01 tw Based on 1 uCi/see release rate;of each nuclide (i) and a value of 1.0 for I/Q and relative deposition.
Note: The units for C-14 and H-3 are (mrem / year per uCi/m ), 3 a
IABLE I-15
- ENVIROISIENTAL' PATHWAY - DOSE CONVERSION FACTORS R(i) FOR CASEOUS DISCHARGE
, PATHWAY = MEAT l ACE CROUP = ' TEEN l Organ Dose Factors -(m2 -mrem /yr per uCi/sec) l Nuclide T. Body CI-Tract Bone' Liver Kidney Thyroid Lung Skin - l Ma-54 1.04E+03 1.08E+04 .0 5.25E+03 1.56E+03 .0 .0 .0 co-60 9.78E+04 5.66E+05 .0 4. 34E+ 0* .0 .0 .0 .0 Zn-65 3.45E+05 3.13E+05 .2.13E+05 7.39 E+05 4.73E+05 .0 .0 .0 Sr-89 5.82E+03 2.42E+04 2.03E+05 .0 .0 .0 .0 .0 Sr-90 1.56E+06 1.77E+05 6.30E+06 .0 .0 .0 .0 .0 Cs-134 .4.22E+05 1.13E+04 ' 3.87E+05 9.10E+05 2.89E+05 .0 1.10E+05 .0 Cs-137 2.55E+05- 1.04E+04 5.50E+05 7.32E+05 2.49E+05 .0 9.67E+04 .0
'Ra-140 .l.37E+03 3.29E+04 : .2.13E+04 2.61E+01 8.85E+00 .0 1.76E+01 .0 Ce-141 7.47E-01 1.86E+04 9.74E+00 6.50E+00 3.06E+00 .0 .0 .0 I-131 3.09E+03 1.14E+03 4.llE+03 5.76E+03 9.91E+03 1.68E+06 .0 .0 1-133 7.37E-05 1.83E-04 1.42E-04 2.42E-04 4.24E-04 3.37E-02 .0 .0 H-3 1.22E-01 1.22E-01 .0 1.22E-01 1.22E-01 1.22E-01 1.22E-01 1.22E-01 C-14 5.71E+01 5.71E+01 2.85E+02 5.71E+01 5.71E+01 5.71E+01 5.71E+01 5.71E+01 Eased on 1 oci/sec release rate of each nuclide (i) and a value of 1.0 for I/Q and relative deposition.
Note: The units for C-14 and H-3 are (mrem / year per uCi/m3 ). i
~ . - - , -, .
TABLE I-16 ENVIRONMENTAL PATHM4Y - DOSE CONVERSION FACTORS R(i) FOR CASEOUS DISCHARGE PATHWAY == MEAT
. ACE CROUP = CHILD
( Organ Dose Factors (m2 -mrem /yr per uCi/sec) l Nuclide T. Body CI-Tract Bone Liver Kidney Thyroid Lung Skin Mn-54 -1.60E+03 5.04E+03 .0 6.00E+03 1.68E+03 .0 .0 .0 Co-60 -1.52E+05 2.86E+05 .0 5.16E+04 .0 .0 .0 .0 Za-65 '5.29E+05 1.49E+05 '3.19E+05 8.51E+05 5.36E+05 .0 .0 .0 [ Sr-89 1.10E+04 1.49E+04 3.84E+05 .0 .0 .0 .0 .0 Sr-90 2.06E+06 1.10E+05 8.14E+06 .0 .0 .0 .0 .0 Cs-134 2.36E+05 6.03E+03 6.82E+05 l'.12E+06 3.47E+05 .0 1.24E+05 .0 Cs-137 1.43E+05 6.07E+03 1.01E+06 9.70E+05 3.16E+05 .0 1.14E+05 .0 Ba-140 2.30E+03 1.99E+04 3.93E+04 3.45E+01 1.12E+01 .0 2.05E+01 .0 Ce-141 1.36E+00 1.14E+04 1.83E+01 9.15E+00 4.01E+00 .0 .0 .0 I-131 4. 36E+03 6.83E+02 7. 63E+03 7.67E+03 1.26E+04 2.54E+06 .0 .0 1-133 1.24E-04 1.32E-04 2.65E-04 3.27E-04 5.45E-04 6.08E-02 .0 .0 H-3 1.47E-01 1.47E-01 .0 1.47E-01 1.47E-01 1.47E-01 1.47E-01 1.47E-01 C-!4 1.07E+02 1.07E+02 5.36E+02. 1.07E+02 1.07E+02 1.07E+02 1.07E+02 1.07E+02 Based on 1 uCi/sec release rate of each nuclide (i) and a value of 1.0 for I/Q and relative deposition. Note: The units for C-14 and H-3 are (mrem / year per uCi/m3).
m TAELE I-17 ENVIRoletENTAL PATini&T - DOSE CONVERSIOtt FACTORS R(i) FOR CASEOUS DISCHARGE FATIniAT .= VEGETATICII ACE GROUP = ADULT Organ Dose Factors (m2 -mrem /yr per uCi/sec) Nuclide T. Body CI-Tract Bone Liver Eidney Thyroid Lung Skin Ma-54 5.90E+04 9.47E+05 .0 3.09E+05 9.20E+04 .0 .0 .0 Co-60 3.69E+05 3.14E+06 .0 1.67E+05 .0 .0 .0 .0 Zn-65 5.79E+05 8.08E+05 4.03E+05 1.28E+06 8.57E+05 .0 .0 .0 i Sr-89 2.82E+05 1.57E+06 9.81E+06 .0 .0 .0 .0 .0 Sr-90 .1.66E+08 -1.95E+07 6.75E+08 .0 .0 .0 .0 .0 Cs-134 8.89E+06 1.90E+05 4.57E+06 1.09E+07 3.52E+06 .0 1.17E+06 .0 Cs-137 5.98E+06 1.77E+05 6.68E+06 9.13E+06 3.10E+06 .0 1.03E+06 .0 Ba-140 8.45E+03 2.66E+05 1.29E+05 1.62E+02 5.51E+01 .0 9.28E+01 .0 Ce-141 1.50E+01 5.0$E+05 1.95E+02 1.32E+02 6.13E+01 .0 .0 .0 1-131 3.33E+04 1.53E+04 4.06E+04 5.80E+04 9.95E+04 1.90E+07 .0 .0 1-133 5.53E+02 1.63E+03 1.04E+03 1.82E*03 3.17E+03 2.67E*05 .0 .0 l M-3 1.42E+00 1.42E+00 .0 1.42E+00 1.42E+00 1.42E+00 1.42E+00 1.42E+00 C-14 1.82E+02 1.82E+02 9.10E+02 1.82E+02 1.82E+02 1.82E+02 1.82E+02 1.82E+02 Eased on I uCi/sec release rate of each nuclide (i) and a value of 1.0 for I/Q and relative deposition. Note: The units for C-14 and E-3 are (mrem / year per uci/m3).
Il I4 il I)ll l ll ) 0 2 0 0 n + + i E E k 3 5 S 0 0 0 0 0 0 0 0 0 0 0 6 9 - 1 2 _ E
~CR 6 6 2 0 2 _
A 0 0 0 0 0 g + + + + + H C n E E E E E S u 8 7 4 3 5 I L 0 0 0 0 0 9 8 1 0 0 0 6 9 _ D .
) 1 1 1 1 2 S c _
U e O s 7 5 0 2 E /d 0 0 0 0 . S i i + + + + - A Co E E E E C ury 8 0 3 5 0 0 0 0 0 0 0 0 0 5 3 6 9 R rh O eT p 1 2 1 2 F
) r i y 5 6 6 6 1 1 4 3 0 2
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+
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- F 5 5 6 7 7 2 2 4 3 0 2 u
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L 1 t v 9 9 7 4 2 0 7 0 4 3 5 i n - B S ci 4 4 8 0 0 6 4 7 8 4 6 6 9 ( io A R aL r T E F 4 2 1 1 ~1 1 1 5 1 '1 ~2 et a V di e i t e i 's y 0 s l o / C o 5 7 8 6 7 5 2 4 2 3 cp m D 0 0 0 0 0 0 0 0 0 0 ue e E .e + + s + + + + + + + nd R S nn E E E E E E E E E E ( m O ao 8 9 8 5 6 9 0 6 0 8 h e cv D gB 0 0 3 4 3 9 0 3 8 8 7 0 4 r ai e
- O 5 1 8 6 1 1 '2 3 9 1 et r a a T fl E oe 3 r -
I H t 5 6 5 6 7 5 5 5 5 4 3 0 2 'e R T c 0 0 0 0 0 0 0 0 0 0 0 0 0 td A a + + + + + + + + + + + + + an d P r E E E 1E E E E E E 1 E E E E ra n a 1 4 8 5 3 4 5 7 4 3 5 L T- 2 2 9 7 3 0 0 1 3 0 2 5 9 eQ A I s/ 4 T N C '9 3 7 '1 2 2 2 2 5 1 1 1 2 aI 1 . N O e E I l r C-G D T eo I A 4 5 5 5 8 6 6 3 1 4 2 0 2 rf r O T y 0 0 0 0 0 0 0 0 C 0 0 0 0 o L i EN d + + + + + + + + + + + + + c0 e
. f
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TABLE I-19 I ENVIROIBEETAL PATillhY - BOSE CCEVERS1018. FACTotS R(i) FOR CASEOUS DISCHARCE l PATIERY = VEGETATIOE l ACE C300F = CHILD Organ Dose Factors (m2 -mEem/yr per uCi/sec) j Euclide T. Body CI-Tract Bone Liver Eidney anyroid Lung Skin En-54 1.75E+05 5.51E+05 .0 6.57E+05 1.84E+05 .0 .0 .0 l Co-60 1.12E+06 2.10E+06 .0- 3.79E+05 .0 .0 .0 .0 , .In-65 1.73E+06 4.83E+05 1.03E+06 2.75E+06 1.73E+06 .0 .0 .O i Sr-89 1.01E+06 1.37E+06 3.54E+07 .0 .0 .0 .0 .0 l Sr-90 3.52E+08 1.87E+07 1.39E+09 .0 .0 .0 .0 .0 Cs-134 5.43E+06 1.39E+05 1.57E+07 2.58E+07 7.94E+06 .0 2.86E+06 .0 Cs-137 3.55E+06 1.51E+05 2.51E+07 2.40E+07 7.83E+06 .0 2.82E+06 .0 Ba-140 1.62E+04 1.41E+05 2.78E+05 2.43E+02 7.93E+0! .0 1.45E+02 .0 Ce-141 ~ 4.81E+0! 4.04E+05 6.50E+02 3.24E+02 1.42E+02 .0 .0 .0 ! I-131 4.10E+04 6.43E+03 7.18E+04 7.22E+04 1.19E+05 2.39E+07 .0 .0 l I-133 8.27E+02 8.81E+02 1.77E+03 2.19E+03 3.64E+03 4.06E+05 .0 .0 E-3 2.52E+00- 2.52E+00 .0 2.52E+00 2.52E+00 2.52E+00 2.52E+00 2.52E+00 C-14 7.IIE+02 7.1IE+02 3.56E+03 7.IIE+02 7.1IE+02 7.1IE+02 7.1IE+02 7.1IE+02 Based on 1 uCi/sec release rate of each nuclide (i) and a value of 1.0 for I/Q and relative deposition. Note: The units for C-14 and E-3 are (mrem / year per uCi/m3).
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