RBG-22-117, Rev 3 to Offsite Dose Calculation Manual
| ML20132D967 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 09/16/1985 |
| From: | Booker J GULF STATES UTILITIES CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| PROC-850916, RBG-22-117, NUDOCS 8509300345 | |
| Download: ML20132D967 (100) | |
Text
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OFFSITE DOSE CALCULATION MANUAL (ODCM) ;
REVISION 3 1
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l Table of Contents
.Section- ,- Page 1.0 Introduction................................................... 1-1 2.0 Liquid Effluent Methodology.................................... 2-1 2.1 River Bend Station Site Description............................ 2-1 2.2 Compliance with 10CFR20 (Liquids).............................. 2-1 2.3 Determination of Setpoints for Radioactive Liquid Effluent Monitors............................................ 2-2 2.4 Determining the Dose for Radioactive Liquid Effluents...'....... 2-4 2.5 Projecting Dose for Radioactive Liquid Effluents............... 2-5 3.0 Gaseous Effluent Methodology................................... 3-1 3.1 Introduction................................................... 3 3.2 Data Requirements for Gaseous Effluents........................ 3-1 l 3.3 Instantaneous Release Rate and Setpoint Determination.......... 3-1
! 3.4 Cumulative Dose Determination for Radioactive Gaseous Effluents.................................................. . 3-9 3.5 Dose Projection - Determination of Need to Operate li Ventilation Exhaust Treatment System......................... 3-17 O
4.0 Radiological Environmental Monitoring Program.................. 4 !
i- 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 Tota l Body Dos e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -1 5.4 - Thyroid Dose................................................... 5-2 6.0 Interlaboratory, Comparison Studies............................. 6-1 Requirement....'................................................. 6-1
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6.1
.6.2 Program........................................................ 6-1 i
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Appendices A Liquid MPC Values l B Liquid Environmental Dose Transfer Factors A h C K L Air Dose Transfer Factors
$ 3 D Expected Gaseous Radionuclide Mixture E X/Q nd 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 Restricted Area and Near-Field Environmental Monitoring Locations 2 Schematic _of Liquid Radwaste System 3 Effluent Release Points 4 Schematic of Gaseous Radwaste System 5- Far-Field Radiological Environmental Monitoring Locations !
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1.0 INTRODUCTION
This manual provides the methodology to calculate radiation doses to individuals in the vicinity of the River Bend Station (RBS). It also provides the methodology for calculating effluent monitoring setpoints and allowable release rates to ensure compliance with the Radiological Effluent Technical Specifications (RETS) of Gulf States Utilities, River Bend Station. This manual also contains a description of the ,
radiological Environmental Monitoring Program which includes sample point descriptions 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 Technical 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 Evaluating Compliance with 10 CFR Part 50, Appendix I" (Regulatory Guide l'.109, Rev. 1, dated October 1977). Simplifying assumptions have been applied where applicable to provide a more workable 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 conversion factors and site-specific I~)/ environmental transfer factors may be substituted for those currently included and used in this document.
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/ '\ 2.0 LIQUID EFFLUENT METHODOLOGY LJ 2.1 River Bend Station Site Description The River Bend Station Final Safety Analysis Report (FSAR) contains the official description of the site characteristics. The description that follows is a brief summary for dose calculation purposes:
The River Bend Station (RBS) is on a site in West Feliciana Parish, Louisiana, located approximately 24 miles north- northwest 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 (Liquids) 2.2.1 Requirements In accordance with Technical Specification 3.11.1.1, the concentration of radioactive material released in liquid effluents to Unrestricted Areas (Figure 1) shall be limited to the concentrations 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" uCi/ml total activity. The concentration of radionuclides in liquid waste is determined by sampling and analysis in accordance with Technical
("')T
%- Specification Table 4.11.1.1-1.
2.2.2 Methadology This ,section describes the calculational method to be used to determine Fg , the fraction of 10CFR20 limits of release concentrations 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 reactor water cleanup as shown in Figure 2. The liquid radwaste system is operated as a batch system. Only one tank of liquid 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:
r'N O
2-1
P
[ s
.-] p =
f g
n C 2.2.2.1-1 L f (MPC)y 2 i=1 where:
Fg = The fraction of 10CFR20 MPC limits resulting from the release source being discharged f
y
= The undiluted release rate of the release source at the monitor location, in gpm f = The cooling tower blowdown release rate, in gpm 2
C = The undiluted concentration of nuclide (i), in f
uCi/ml from sample assay.
Note: When isotopic analyses indicate that activity is present at less than or equal to the Lower Limit of Detectability (LLD), utilize the laboratory determined LLD values for I-131 and the principal gamma emitters as defined in Tech Spec Table 4.11.1.1.1-1 for C.
f (MPC)g
= Maximum Permissible Concentration of nuclide (i) from Appendix A, in uCi/ml
,,3
'w/ as long as Fg 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 the calculations, the value of 3 x 10" uC1/ml (unidentified 10CFR20 MPC value) could be substituted for (MPC)g and the cumulative concentration (C-Total = sum of all identified radionuclide concentrations) or the gross beta-gamma concentration should be substituted for Cf . Is long as the diluted -
- -8 f y/f 2) is less than 3 x 10
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concentration (C-Total uC1/ml, the nuclide by nuclide calculation 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 3.3.7.10 regt51res the radioactive liquid effluent monitor be operable with their high alarm / trip setpoints 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.
2-2
('~'T The high alarm setpoint for the liquid effluent radiation monitor is
(_) derived from the concentration limit provided in 10CFR20, Appendix B, Table II, Cnlumn 2 applied at the restricted 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 4.11.1.1-1 of Technical Specification 3.11.1.1, for total activity concentration prior to release. The fraction F 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 setpoint is determined with the equation:
S =
A x
f2+fl x g 2.3.2-1 b I lT where:
k.)
S = The radiation monitor setpoint (cpm or uCi/ml)
A = The counting rate (cpm /ml) or activity concentra-tion (uCi/ml) of the sample as determined in the laboratory I
The ratio of effluent radiation monitor counting l g =
rate or activity concentration to laboratory counting rate or activity concentration in,a given batch of liquid (cpm per cpm /ml or uCi/ml per uCi/ml) f y
= Release rate of undiluted batch release line (ml/sec, gpm, or other consistent units of vol/
time) f = Minimum dilution flow of cooling tower blowdown 4 2
in the discharge (ml/sec, gpm, or other consistent I units of vol/ time)
Note: A/F represents the counting rate of a solution having the same radionuclide distribution as the sample and having the maximum permissible concentration (MPC) of that mixture. ;
(A) 2-3
I-2.4- Determining the Dose for Ra'dioactive Liquid Effluents l
l 2.4.1 Requirements Technical Specification 3.11.1.2 requires the dose or dose commitment to a person offsite due to radioactive material released in liquid effluents be calculated on a cumulative basis at least every 31 days.
Dose or dose commitment shall be limited to:
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-specific dose factors A f for all viable pathways are listed in Appendix B.
-The following equation provides for a dose calculation to the total body or any organ for a given age group (D ,) based on actual release conditions during a specific time interval for radioactive liquid releases:
n n D = D =
^iT6 1 i1 Ta g,1 iT g,y M Dy y 2. h . 2-1 ~
D it = Dose commitment in mrem from radionuclide (i) re-ceived by organ ( t ) of age group (a) resulting
'from releases during the time interval At 1
^it = Site related dose commitment factor to the total body or any organ ( t ) for_each identified radio- '
nuclide (1). The A h values listed in Appendix B are site-related to RBS and have the units L (mrem /hr per uCi/ml)
, - . At 1-
= Number of hours that the release occurred L.
Q 17 = The total quantity of nuclide (1) released during l-the time period Atg (uCi) 2-4
p.
ff~j Dw = The near field dilution factor. -Site specific k/ value is 11.4 (River Bend E.R. p.5.4-5, section 5.4.2.3.1)
= The total volume of dilution that (DF)g occurred during the release time period At (i.e., the cooling tower blowdown flow rate multiplied 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 dose-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 D
=
}{ (D ,)f 2.4.2-2 TOTALt i=1
- where:
D = The total dose commitment to the organ TOTALT (t ) due to all releases during the desired time interval in mrem.
D = The dose commitment in mrem
- 1 to the organ ( t ) of age group (a) due to liquid release (i) during the desired time interval.
2.5 Projecting Dose for Radioactive Liquid 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.
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( ,) 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 ta X
D t where:
PD ta = Projected dose commitment (mrem) to organ ( t ) of age group (a) during the 31 day period X = The number of days in the 31 day period X = The number of days to date in the 31 day period D
D = The total dose commitment (mrem) to an organ TOTALt (t ) of age group (a) to date during the 31 day period. The age group (a) is selected based upon highest dose commitment.
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3.0 GASEOUS EFFLUENT METHODOLOGY t
3.1 Introduction The River Bend Station discharges gaseous effluents through the Main Plant Exhaust Duct, Fuel Building Exhaust Duct, and Radwaste 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 effluent discharge points are shown schematically in Figure 4. For purposes of simplicity, Fuel Building exhaust effluents are included in the Main Plant exhaust duct i
releases. All gaseous effluent releases are assumed to be ground level releases.
3.2 Data Requirements for Gaseous Effluents For the purpose of estimating offsite radionuclide concentrations and radiation doses, measured radionuclide concentrations in gaseous effluents and in ventilation air exhausted from the station are relied upon. Table 4.11.2.1.2-1 in the Technical Specifications identifies the radionuclides in gaseous discharges 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.
P) t Real meteorological data factors are calculated and used in dose calculations for the Semi-annual Effluent Release Report. Historical information and conservative receptor assumptions are only used for ease of Limiting Condition of Operation (LCO) dose limit calculations.
Dose calculations performed with actual occurring data will describe the source of the data in the report. Modeling will be performed in accordance with Regulatory 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 effluents from the site to areas at and beyond the site boundary (see Figure 1) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrem / year to the j total body and less than or equal to 3,000 mrem / year to the skin; and 3-1
= .
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- 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 DR ' * }
TB i i i=1 3.3.1.2.1-1 n
DR = 3.15 x 10 (Lg + 1.1 Mg ) (7Q) Qg i=1 3.3.1.2.1-2 where:
D = Dose rate to the total body in mrem / year.
Kg = The total body dose factor due to gamma emissions for each identified noble gas radionuclide (i) in mrem /sec per uCi/m . Appendix C.
I Lg = Skin dose factor due to beta emissions for each identified noble gas radionuclide (1) in mrem /sec per uCi/m . Appendix C.
Hg = The air dose factor due to gamma emissions for each identified noble gas radionuclide (i) in mrad /sec per uCi/m . Appendix C.
(X[Q) = The highest calculated annual average relative con-centration for an'y area at or beyond the restricted area boundary in sec/m . For either elevated
,(stack) or. vent releases. Appendix F. !
Qg = The release rate of radionuclide (i) in gaseous
.f effluents from all releases in uC1/sec. l 1.1 = Conversion factor for Mg from mrad to mrem.
3.15 x 10 = Number of sec/ year.
3-2 l
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F g
'U In order to comply with the limits of10CFR20,DkB 00 mrem / year and DR $ 3,000 mrem / year must be met at 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 Appendix D.
The X/Q values utilized in equations 3.3.1 4 1-1 and 3.3.1.2.1-2 are based upon maximum long-term annual average (X/Q) in the unrestricted 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/Q for each release point is used (from Appendix F):
~0 (X/Q), = 2.91 x 10 sec/m
-5 3 (X/Q) = 3.84 x 10 sec/m where:
(X/Q), = Chi /Q for Main Plant exhaust duct and Fuel
/7 Building exhaust duct b
(X/Q)y = Chi /Q for Radwaste Building exhaust duct Appendix F contains the maximum X/Q and D/Q values used in calculating individual doses.
Release rates for all release points must be considered at the same time. If releases are occurring at the same time, the 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 - Instantaneous Noble Gas
! Release Rate The above methodology can be simplified 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 (K,ff) 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 K,ff. The value of K,ff has
'd been derived from the radioactive noble gas effluents listed in RBS-FSAR and included in Appendix D. The values are:
3-3
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Radwaste Building Exhaust Duct:
-5 ,,3/uCi-sec]
K,gg = 8.05 x 10 Main Plant Exhtest Duct and Fuel Building Exhaust Duct:
-5 3 K,gg = $.56 x 10 Rm-m /uCi-sec]
Either of these values, as appropriate, may be used in conjunction with the total noble gas release rate (I Q ) 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 K .
0.8 (X/Q)
{
i=1 1 where:
DR = Total body dose rate from noble gases in airborne TB releases in mrem /sec.
Q
-\/
(X/Q) = For ground level or elevated releases, the highest calculated annual long-term historic relative concentration for any of the 16 sectors, at or beyond the unrestricted area boundary, in sec/m (Appendix F).
Qf = 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 radiolodine 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 pathway is considered, since it is the most limiting pathway.
-Inhalation Pathway:
D .
DR 3.3.1.2.3-1 I&8DPt
{ Pg (M)D i i=1 .
L 3-4
b l
l l
l'h U where:
= The organ of interest for the age group of interest.
f t I
= Release rate of nuclide (1), [uCi/sec].
Q1 DR = Dose rate to the organ t for the age group of I&8DP interest from iodines and 8 day particulates l
via the inhalation pathway (in mrem /yr].
= The long-term depleted and 8 day decayed CHI /Q (X/Q)D value based on historical meteorological data (Appendix E) [in sec/m ). Note: No credit for decay or depletion has been taken.
P = The dose factor for applicable environmental 1
pathway [in units of mrem /yr per uCi/m j (Appendix G).
I Note: For calculations involving tritium, use (X/Q)D I" sec/m .
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The determination of limiting location for implementation of 10CFR20 for radiciodines and particulates is a function of the same parameters as for noble gases.
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M Values for P gwere calculated for an infant for various radionuclides for the inhalation pathway using the methodology of NUREG-0133. The Pg values are presented in Appendix G. The values of Pg reflect, for each radionuclide, the maximum P value for any organ for the inhalation pathway.
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 Ber.d Station in gaseous effluents. Each release point process monitor listed in Tech. Spec. i Table 4.11.2.1.2-1 includes an alarm that is set to report when the radioactive noble gas in gaseous effluents (Main Plant exhaust duct, Fuel Building 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, t Column i for the mixture. MPC values for gaseous radionuclides are listed in Appendix H.
The distribution of radioactive noble gases in a gaseous effluent stream is determined by gamma spectrum analysis of identifiable j Results of one or more
~
radionuclides in effluent gas sample (s).
previous analyses may be averaged to obtain a representative spectrum. l In the event the distribution is unobtainable from measured data, the .
distribution of radioactive noble' gases based on past data or l calculated by the BWR-GALE code appearing in Appendix D may be -
assumed.
To allow for multiple sources of releases from the three different release points, the allowable operating setpoints will be administrative 1y 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.
-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:
-8 500 -8 500(0.8)
Q = 3.17 x 10 .
= 3.17 x 10 .
B f g (X/Q) . K,gg (X/Q){K g i
3.3.2.2-1 3-6
l' where:
(X/Q) = The highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all sections (sec/m ).
Appendix F.
Kg = The total whole body dose factor due to gamma emissions from noble gas radionuclide (i) (mrem /sec ;
I per uCi/m ) from Appendix C, Table'C-1.
f = Fraction of noble gas radionuclide (1) to total noble gas concentration.
K,ff =
Kg . f ,f effective dose factor (mrem /sec per uCi/m )
from Appendix C, Table C-3.
-8 Inverse of number of seconds per year in year /sec.
3.17x10 =
0.8 = Conservative factor to account for changing isotopic inventory.
Stop 2 Determine - Q, (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:
-8 3,000 -8 3,000 (0.8)
Qs = 3.17 x 10 .
= 3.17 x 10 . ,
(X/Q)(L+1.1M),ff (X/Q){[L+1.1M)f)g f g where: 1 3.3.2.2-2.
Lg + 1.1Mg = Total skin dose factor due to emission from noble gas radionuclide (i) (mrem /sec/uCi/m ) from Appendix C.
(L+1.1M),gg = (1 1 + 1.1 Mg )
- f , effective total sMn dose 1 f factor (mrem /sec/uCi/m ) from Appendix C, Table C-4. ,
I V("'N 3-7
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(_ ,/ Step 3 Determine C , (the maximum acceptable total radioactivity concentration of all noble gas radionuclides for each release point in the gaseous effluent [uCi/cc).
2.12 E-3 Q C = F 3.3.2.2-3 m
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.
where:
F = The maximum 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.
Stpp 4 Determine CR (the calculated monitor count rate above background
- attributed to the noble gas radionuclides [ cpm]) by:
k_)s CR = (Cm) (Em ) 3.3.2.2-4 where:
E = Efficiency of the applicable effluent monitor (cpm /uCi/cc).
Step 5 Determine the HSP (the monitor high alarm setpoint including background [ cmp]) by:
HSP = T CR + Bkg 3.3.2.2-5 m
.where:
=' Fraction of the radioactivity from the site that T,
may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from several pathways.
= .33 for all release points.
T,
(')
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l
(' ') Bkg = The background count rate (cpm) due to internal
\s/ contamination and the radiation levels in the area in which the monitor is installed when the detector sample chamber is filled with uncontaminatad 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
[ ~'1 This section provides the methodology to calculate the doses to all age groups and organs from all noble gas radionuclides identified in the gaseous effluents.
The method is based on the methodology suggested by sections 5.3 and 5.3.1 of NUREG-0133, Rev. 1, November, 1978. The site related dose factors for all viable pathways are listed in Appendix I. Dose factors are compiled by age groups, for all organs and radionucli 's common to a BWR environment.
The following equations provide for air dose calculations based on actual noble gas release rates during a specific time interval for radioactive gaseous release sources 'at the site boundary:
n D
Gamma-Air
= M.
1 x (X/Q) x Q i 3.4.1.2-1 e
i=1 n
Beta-Air
=
) Ng x (X/Q) x Q f 3.4.1.2-2 L=1 3-9 A
U
I 7
(/ where:
D = e gamma air dose from radioactive noble gases in mrad.
Gamma-Air M = The gamma air dose factor for radioactive noble gas f
nuclide (i) in mrad-m /uCl-sec (Appendix 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 determine annual X/Q for the year of interest in sec/m (Appendix E).
Q = The number of uCi of nuclide (i) released during the period of interest.
D = Beta air dose from radioactive noble gases in mrad.
Beta-Air Ng = The beta air dose factor for radioactive noble gas nuclide (i) in mrad-m /uCi-sec (Appendix C), Table C-1.
,a
! i V' 3.4.1.3 Simplified Approach A single effective gamma air dose factor (M,ff) and beta air dose factor (N,ff) have been derived, which are representative of the radionuclide abundances and corresponding dose contributions that are projected in the RBS FSAR. (See Appendix C for a detailed explanation and evaluation of M,ff and N,ff.) The values of M,gf and N,ff which have been derived from the projected radioactive noble gas effluents are:
Radwaste Building Exhaust Duct:
-5 3 M,ff = 8.07 x 10 mrad-m /uCi-sec
-5 3 N,ff = 7.40 x 10 mrad-m /uCi-sec l
Main Plant Exhaust Duct and Fuel Building Exhaust Duct: i 1
M,gg
= 5.96 x 10~ mrad-m /uCi-sec N,gg = 8.99 x 10~ mrad-m /uCi-sec l
.[h 1
s, 3-10
'I The- effective gamma air dose factor may be used in conjunction with
/ the total noble gas release (I Q) to simplify the dose 1
evaluation and to verify that the cumulative gamma and beta air dose is within the equivalence of the limits of Technical Specification 3.11.2.2. 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:
(Megg) .
M) Qi D = .
3.4.1.3-1 Gamma-Air 0.8 i=1 n
(Negg) -
(X/Q) . Qi D = . 3.4.1.3-2 Beta-Air 0.8 i=1 3.4.2 . Determining the Radioiodine 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 Member 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:
c~. During any calendar quarter: less than or equal to 7.1 mrem to 3 any organ; and I b. During any calendar year: less than or equal to 15 mrem to any
. organ.
_3.4.2.2 . Methodology The followir.g calculational method is provided for determining the
, critical organ dose due to releases of radioiodines 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 total dose reflects only those pathways that are applicable to the age group. The symbol (X/Q)D represents a depleted (X/Q) which is different from the noble gas (X/Q) in'that (X/Q)D takes into account the loss of iodines, 8 day particulates, 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 cf ,
ground at various distances from the site. The total dose to an organ I~ can then be determined by summing the pathways that apply to the receptor'in the sector. The equations are:
3-11 L
L -_ . _ _ _ - . _ - . - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Inhalation Pathway: 3.4.2.2-1 n .
=(. '
D I&8DP x 10 ) { R it
(
)D I
i=1 Ground Plane Pathway: 3.4.2.2-2 n
D
- Oi R gt (D/Q)
I&8DP = (3.1 x 10 ) {
i=1 Contaminated Forage / Cow /flilk Pathway: 3.4.2.2-3 n
D I68DP = (3.1 x 10 )
{ R it' ( ) I i=1 q Total Dose: 3.4.2.2-4
-V n a;.
= D I&8DPt 7
where:
T = The organ of interest in a specified age l group. j z =- All the applicable pathways for the age group of - l interest.
D = Dose in mrem to the; organ (t) of a specified I&8DPt age group from radioiodines and 8 day particulates due to a particular pathway.
D. = Total dose in mrem to the organ (t) of a
.specified age group from gaseous iodine and particulate effluents, summed over all applicable pathways (z). '
-8 =
3.17 x 10 The inverse of the number of seconds per year [in years /sec].
3-12 -l
{} R g
= The dose factor for nuclide (i) for pathway (z) to organ (t) of the specified age group. The units are either:
3 -
mrem-m for pathways using (X/Q)D yr-uCi or -
mrem-m -sec for pathways using (D/Q) yr-uCi (See Appendix I.)
(X/Q)D The depleted (X/Q) value for a specific location where the receptor is located. The units are
, [sec/m ]. (See Appendix F.) Note: No crep t is taken for depletion and decay. !}
(X/Q)D (D/Q) = The deposition value for a specific location where the receptor is located. The units are
[m' ]. (See Appendix F.)
,q i
Qi =
The number of microcuries of nuclide (i) released 3
V (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 Section 5.4 of the RBS ER-OLS as the most limiting, with the infant thyroid being the most critical age group and organ. It is possible to demonstrate compliance with the dose limit of Technical Specification 3.11.2.3 for radiciodines and particulates by only '
evaluating the infant's thyroid dose due to the release of s
radioiodines via the contaminated forage / cow / milk pathway, The calculational method to be used includes a conservatism factor of 0.8 which assures that the calculated dose is always greater than or equal to the actual dose despite possible atypical distributions of
- radionuclides in the gaseous effluent. The simplified dose equation reduces to
3.4.2.3-1 l D = [3.17 x 10' (D[Q) { Rg Q1 ] /0.8 iodines n
b 3-13
c
[] 3.4.2.4 Approach Selection Criteria w
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 radioiodines 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 effluents according to sampling and analyses required by the Technical Specifications.
3.4.2.5 Annual Dose Due to Radioiodine 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: 3.4.2.5-1 n
D I&8DP
= .1 x 10 [ R it
(
D -
i=1 f~,
(j Ground Plane Pathway: 3.4.2.5-2 n
D I68DP
= 3.17 x 10 [ R it
( )
i=1 Contaminated Forage / Cow /flilk Pathway: 3.4.2.5-3 n
D I&8DP
= . x 0
{ R it
( )
i=1 Contaminated Forage / Goat /flilk Pathway: 3.4.2.5-4 n
-8 g .(g). Qi D
I&8DP
= 3.17 x 10 i=1 l
1 I
g l \
3-14 L_______.___________
Contaminated Forage / Meats: 3.4.2.5-5 n
D "
- I68DP it
( ) '
i i=1 Fresh Fruits and Vegetables: 3.4.2.5-6 I&8DP = -8 * '
01 3.17 x 10 Rg (D[Q) i=1 Total Dose: 3.4.2.5-7 n
I&8DPt z=1 0
3-15
/
where:
t = 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 8DP t interest from iodines and 8-day particulates via the pathway of interest in mrem /yr. For radioiodines, the entire source term was used to calculate these values.
Qg = The number of uCi of nuclide (i) released during '
the year of interest.
R =
it The dose factor for nuclide (i) for organ (t) for the pathway specified [ units vary with pathway]. For tritium, a site-specific absolute humidity (H) value of 12.9 gm/m was used for calculation. (See Appendix I.)
r (D[Q) = A long-term relative deposition value for elevated and ground level releases. A factor
-2 with units of m which describes the deposition of particulate matter from a plume at a point downrange from the source. Actual meteorological
' data and sector wind frequency distribution will be used to determine annual average D/Q for the year of interest.
l (X/Q)D
= A long-term depleted and 8-day decayed relative concentration value for elevated and ground level l release. It describes the physical dispersion characteristics of a semi-infinite cloud
' travelling downwind. Since iodines and particulates set':le out (fallout of the cloud) on the ground, the (X/Q)D 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 (X/Q)D ' #
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 3
methodology (sec/m ).
3-16
/'~N 8 I
Q 3.17 x 10 = The inverse of the number of seconds per year (in year /sec).
Meteorological data (X/Q, X/Q , D/Q) will be determined from actual D
meteorological data and sector wind frequency distributions 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-annual Radioactive Effluent Release Report. ,
3.5 Dose Projection - Determination of Need to Operate Ventilation Exhaust Treatment System 3.".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 gaseous 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 g projected doses:
O PD = X . D 3.5.2-1 D
where:
PD = Projected dose due to all radioactive gaseous effluents during'the current 31 day period (mrem).
X = Number of days in the 31 day period.
X D
= The number of days to date in the 31 day period.
D = Cumulative total dose due to all radioactive i
gaseous effluents during the 31 day period to date
! (mrem).
l O
3-17 u-_____---
\
A-formal-doseprojectionEouldbebasedonthelatestresultso the.-
monthly calculations of the'glamma air dose (Section 3.4.1.2). Tha 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 ventilation flow rate.
I s
's 1
2
%
- 3 E
1 1
t
- O-3-18
I
! 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table 4.1 contains the sample point description, sampling and collection frequency, analysis, and analysis frequency for various exposure pathways in the vicinity of RBS for the radiological monitoring program. Figures 1 and 5 indicate the locations of the various onsite and offsite sampling points and TLD locations.
This section describes only those elements of the radiological environmental monitoring program required by the RBS Technical Specifications. Additional exposure pathways, sample points, analyses, and/or frequencies are performed as described in ER-OLS Section 6.2.
Samples of groundwater are taken from onsite wells located to intercept any potencial contamination of the Upland Terrace Aquifer so that any such contamination would be detected before migrating beyond RBS site boundaries.
,em N.
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4-1
, p yy sj -
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Point, Description, Sampling and Type and Frequency and/or Sample Di stance. and Di rect ion Collect ion Frecuency of Analysis
- 1. Ai rbo rne Pa rt i- Samples f rom 5 locations:
culates and Radioiodines AA1. River Bend Training Continuous a i r sampler Cha rcoa l ca rt r idge :
Cente r; 1.7 km N. with filter collection ana lysis weekly for weekly or as requi red by 1-131.
dust loading, whichever Pa rticulate sampler:
is more f requent. gross beta act ivi ty following filter changes; composite for gamma isotopic qua rte r ly.
ARI. River Bend Station North Access Road at Cate #3; O.8 km NNW.
API. Near River Bend Station Onsite Carden #1; 0.9 km WNW.
AQS2. St. Francis Substation on US Ftwy. (Bus.) 61 in St.
Francisville; 5.8 km NW (Community Location).
ALC. Pa rlange Power Center in Oscar: 20 km SW ( Con t ro l ) .
O :O O J 1 '
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
. ( Page 2)
Exposure Pathway Sample Point, Description, . Sampling and Type and Frequency and/or Sample Distance. and Di rection Collection frecuency of Analysis
- 2. Direct Radiation Measurements from
- 40 locations:
INDICATOR STATIONS TA1. River Bend Training The rmo l umi nescence Gamma dose qua rterly, i Cente r; 1.7 km N. dcsimeters (TLDs);
dep l oyment/ ret r i eva l 1 qua rte r ly.
I J TA2. GSU utility pole #246 at i 1 ' Jct. of LA Hwy.-10 and WF2 '
4 in Elm Pa rk; 8 km N.
I TB1. River Bend Station iron ya rd a rea; 0.5 km NNE.
1 -TB2. Stub pole at Jct. LA 1 Hwy 965 and Audubon Lane
- (WF17); 5 km NNE.
~
? TC1. Stub pole at Jct. US 1
J Hwy. 61 and Old Highway 61; 1,7 km NE.
4 TC2 Stub pole along LA Hwy, 966, 0.6 km S of Jct. LA Hwys.
9.66 and 965; 7 km NE.
j TD1. Stub pole along WF7, !
150m S of Jct. ,WF7 and US !
3 Hwy. 61; 1.6 km ENE.
TD2, Stub pole along LA Hwy, 966, 4 km S of Jct. LA Hwys, 966 and 965; 6.3 km ENE.
i TE1. Stub pole along WF7, '
1 km S of Jct. WF7 and US
- Hwy. 61; 1.3 km NE.
l TE2. Grave l Power Center on i LA Hwy. 68, 2 km N of Jct.
LA Hwys. 68 and 964; 10 km E.
. TF1 Stub pole along WF7,
? 1.6 km S of Jct. WF7 and US '
Hwy. 61; 1.3 km ESE.
i I - - - - , . . . . - . _ . . . - - . . . . . . . . . ,
p__ .,
fg ,/^\
Q' s
\_j}
( \
V)
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM
( Pa ge 3 )
Exposure Pathway Sample Point, De sc r i p t i on, Sampling and Type and Frequency and/or Samole _ Distance. and Di rection Collect ion Frecuency of Analysis TF2. McKowen Dairy on LA Hwy. 954, 0.6 km N or Jct.
LA Hwy. 954 and US Hwy. 61; 6 km ESE.
TG1. Stub pole along WF7, 2 km S of Jct. WF7 and US Hwy. 61; 1.6 km SE.
TG2. Telephone pole at gate to Ma rathon Tank Fa rm on US Hwy. 61, nea r Delombre, l
1 7.5 km SE.
TH1. Stub pole at lilinois -
Cent ra l Gulr RR crossing of WF7 (near Grants Bayou); 1.7 km SSE.
TH2. First telephone pole on LA Hwy. 964 N or entrance to C-Z papermi l l; 5.5 km SSE.
TJ1. Stub pole near River l Bend Station Cate #23 on
- Powell Station Road ( LA Hwy.
l 965): 1.5 km S.
l TJ2. La rge tree a long River Road, 100 m N of C-Z papermill intake structure: 5.8 km S.
TK1. GSU utility pole #L10178 on Powell Sta t ion Road ( LA Hwy, 965), 20 m s or River Bend Station River Access Road; 0.9 km SSW.
TK2. Stub pole at Jct. LA Hwys. 414 and 415; 8 km.SSW.
TL1 Second utility pole on Powell Station Road (LA Hwy. 965) i S or Illinois Central Gulf RR l c ross ing; 1.0 km SW.
l l
p ,- ,/--
j %
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (P39e 4)
Exposure Pathway Sample Point, Description, Sampling and Type and Frequency and/or Sample Distance, and Direction Collection Freauency of Analysis T L2. Second utility pole along LA Hwy. 415 E of Louisiana and Arkansas RR crossing (nea r Patin's Dike); 9.5 km SW.
TM1. first utility pole on Powell Station Road ( LA Hwy.
965) N of I l l i no i s Cent ra l Gulf RR crossing; 0.9 km WSW.
TM2. Utility pole along LA Hwy, 981, about 3 km S of Jct. LA Hwys. 981 and 10 (west bank ferry landing);
4.2 km WSW.
a i
TN1. Utility pole along Powell Station Road ( LA Hwy. 965), between River Bend Station Cates #13 and 14; O.9 km W.
TN2. Utility pole with electrical mater nea r west bank ferry landing (LA Hwy.
10); 6.0 km W.
TPl. Near River Bend Station Onsite Ca rden #1; 0.9 km WNW.
TP2. Stub pole about 1.5 km N of Illinois Central Gulf RR trestle on Tunica Street, western outskirts of St.
Franci svi l le. 7. 3 km WNW.
TQ1. CSU property sign pole along Powell Station Road (LA Hwy. 965), about 1 km N of River Bend Station North Access Road; 1.4 km NW.
4 TQ2. CSU pole with street lights at Jct. North Commerce and American Beauty Streets, St. Franci svi l le; 6.9 km NW.
i 4
9
O d L/
l l TABLE 4.1 RADIOLOCICAL ENVIRONMENTAL MONITORING PROGRAM
( Page 5) .
l Exposure Pathway Sample Point, Desc ri p t ion. Sampling and Type and Frequency and/or Sample Distance. and Direction Collection Freouency of Analysis l TRI. River Bend Station North Access Road at Cate #3; O.8 km NNW.
TR2. Stub pole along WF2 at g ravel road about 1.8 km E or Jct. WF2 and US Hwy 61; 8 km NNW.
CONTROL /SPECIAL STATIONS TAC. Telephone pole along US Hwy. 61 about 200 m N of Hamilton Station Water Tower, near Wakerield; 18 km N (Control).
i
' TLC. Parlange Power Center in Osca r; 20 km SW (Con t ro l ) .
TQSt. Behind Pentecostal Church (opposite West Feliciana Hospital) near Jct. US Hwy. 61 and Ferdinand Street; 4 km NW (Special).
TQS2. St. Francis Substation i
on U.S. Hwy. (Bus.) 61 in St.
Francisville; 5.8 km NW (Special).
TLS. Utility pole near False River Academy sign at edge of New Roads; 9.9 km SW (Special).
TCS. Utility pole at gate to i East Louisiana State Hospital i in Jackson; 12.3 km NE (Special).
t TCSI. CSU Service Center compound in Zachary; 17 km SE (Specia l).
TGS2. Roor of GSi' Se rvice Orrice Building, North Blvd.,
Baton Rouge; 40 km SE (Special).
l
Q} f~~)\
Q. w/
TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
( Page 6) l
, Exposure Pathway Sample Point, Description, Sampling and Type and f requency and/or Samo 5e Distance. and Direction Collection Freauency of Analysis l
Wa te rbo rne
- 3. SURFACE WATER (1)
SWU. Mississippi River about Weekly grabs composited Monthly composite:
4 km upstream f rom the plant over monthly and gamma isotopic analysis; liquid discha rge outfa l l, near qua rterly periods. Quarterly composite:
LA Hwy. 10 fe r ry c ro s s i ng, tri tium analysis.
SWD. Mississippi River about 4 km downstream from plant I l iquid di scha rge outfa l l, near C rown-Ze l le rba ch pa pe rmi l l .
Discharge Line. At blowdown Hourly grabs composited line along River Access Road, over monthly and l quarterly periods.
I l CROUNDWATER WU. Upland Terrace Aquifer Qua rterly g rab. Gamma isotopic and well upg rad ien t f rom plant, tritium analyses about 470 m NNE. qua rte rly.
WD. Upland Terrace Aqui fer well downg radient f rom plant, about 470 m SW.
SHORELINE SEDIMENT SED. Mississippi River about Semiannua l grab. Gamma isotopic 4 km downstream from plant ana lys i s qua rte rly.
liquid d ischa rge outfa l l, near Crown-Ze l le rba ch pa pe rm i l l .
1 1
i i
,m
(}
(U) V .V TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
( Page 7)
Exposure Pathway Sample Point, Description, Sampling and Type and Frequency and/or Sample Distance. and Di rection Col lect ion Freauency of Analvsis
- 4. Ingestion MILK (2)
MF2. McKowen Dai ry on LA Hwy. Semimonthly when Gamma isotopic and 954, 0.6 km N of Jct. LA Hwy. animals on pasture; l-131 analyses 954 and US Hwy. 61, 6 km ESE monthly at other times. semimonthly or monthly.
(nearerst source of milk for consumption).
MQC, LA State Penitentia ry at Angola, 35 km NW (Control).
FISH AND' INVERTEBRATES FU. One sample of each of Seasonally when Gamma isotopic three commercially and/or ava ilable or semiannual ly. analysis on edible recreationally important portions.
species from upstream a rea not influenced by plant discharge.
FD. One sample of each of three commercially and/or recreationally important species f rom downstream a rea influenced by plant d i scha rge.
PRODUCE G1/C2. Two samples of each of Monthly during g rowing Camma isotopic and th ree d i f feren t kinds of leafy season. 1-131 analyses monthly, vegetables from onsite ga rdens nea r the site bounda ry of highest calculated annual average ground-level D/Q L
i f three mi lk samp t s ng a reas not available.
GQC, One sample of each of the the simila r vegetables f rom LA State Penitentia ry at Angola, 35 km NW (Control).
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 a rea beyond but nea r the mixing zana.
- 2. If milk-producing animals become available within a 5-km radius of the plant, up to 3 samples f rom these anima ls will be analyzed in lieu of the leafy vegetable samples from onsite gardens in high dose-potential a rea s .
() 5.0 40CFR190 CONSIDERATIONS 5.1 Compliance with 40CFR190 Compliance with 40CFR190 as prescribed by Technical Specification 3.11.4 is to be demonstrated only when one or more of Technical Specification (s) 3.11.1.2.a. 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b, 3.11.2.3a, and 3.11.2.3.b, including direct radiation are exceeded by a factor of 2. Once this occurs, GSU has 30 days to submit a report in accordance with Specification 3.11.4.
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 calculational rules are used:
5.2.1 Doses to Members of the Public via the liquid release pathway are considered to be <1 mrem /yr (Ref NUREG-0543).
5.2.2 Doses 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 mrem /yr.
O)
\s. 5.2.3 Environmental sampling data which demonstrate that no pathway exists may be used to delete a pathway to man from a calculalon.
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, thuy will be calculated for the same distance in the same sector.
i 5.2.6 The calculational locations for a Member of the Public will l 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.
5-1 O
d
(~ 5.3 Calculations of Total Body Dose
(-]-
Estimates will be made for each of the following exposure pathways to the same location by age class. Only those age classes known to exist '
at a location are considered.
5.3.1 Direct Radiation The component of dose to a Member of the Public due to direct radiation will be determined by thermoluminescent 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.
5.3.3 Ingestior. Pathway The dose via the ingestion pathway will be calculated at the consumer locations for the consumers at risk. If no milk pathway exists in a sector, the dose via this pathway will be treated as <1 mrem /yr.
5.3.4 Other Uranium Fuel Cycle Sources
,- s 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 existing). The calculational methods will be those identified in Section 3.0 of this manual.
1 4
5-2
'l
l
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v 6.0 INTERLABORATORY COMPARISON STUDIES 6.1 Requirement Technical Specification 3.12.3 states " Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory 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 7tation are to be analyzed by the River Bend Station Environmental Services Group or by a qualified contracting laboratory. These laboratories will participate in the U.S. Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck) Program or an equivalent program. This participation will include all of the determinations (sample-radionuclide combinations) that are offered by EPA and that are also included in the licensee's environmental monitoring program. Results of the Interlaboratory Program will be included in the Annual Radiological Environmental Operating Report.
6.2.2 Effluent Release Analyses Program RBS Chemistry Group will perform sample analyses for gamma-emitting radionuclides in effluent releases. The radiochemistry laboratory
{s)
(_ will participate annually in a corporate interlaboratory 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 greater than three (3) standard deviations .from the " recognized value," an evaluation will be performed to identify any recommended remedial actions to reduce anomalous errors. Complete documentation on the evaluation will be available to RBS Environmental Services Group and will be provided to the NRC upon request.
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APPENDIX A l LIQUID MPC VALUES F
l i
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).
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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 Cu-64 2 E-4 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
,q
, Br-83 3 E-6 Sn-113 8 E-5 Ba-141 None
() Br-84 None** In-113m 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 None Sb-125 1 E-4 Ce-141 9 E-5 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-5 W-187 6 E-5 Sr-92 6 E-5 Np-239 1 E-4
-
- 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 2.
- None (as per 10CFR20, Appendix B) "No MPC limit for any single radionuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive' half-lives less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />."
[)
m
,_u,,_.. _ - ~ . . - _ _ - -
1 4 !
i p
f t
APPENDIX B LIQUID ENVIRONMENTAL DOSE TRANSFER FACTORS i'
A 11 0 ,
i h
t i i i
)
l 1
I l
5 L
i O
I r
i .
i TABLE B-1 LIQUID EFFLUENT DOSE PARAMETERS (Page 1)
A lt, mrem /hr per uCi/mi Radionuclido Total Body Critical Organ Na-24 6.13E02 6.13E02 P-32 1.87E06 4.84E07 Cr-51 4.31 1.08E03 Hn-54 4.56E04 7.32E05 Mn-56 1.07E03 1.92E05 Fe-55 9.14E02 5.67E03 Fe-59 8.07E03 7.02E04 Co-58 4.02E02 3.64E03 Co-60 1.14E03 9.68E03 Ni-63 1.29E03 3.85E04 Ni-65 9.28 5.16E02 Cu-64 1.36E01 2.47E03 Zn-65 7.30E04 1.61E05 Zn-69 1.40E01 2.07E02
' O Sr-89 Sr-90 1.20E03 2.50E05 4.19E04 1.03E06 l Sr-91 3.01E01 3.68E03 Sr-92 1.30E01 5.80E03 l Y-91 2.37 4.89E04 l
! Y-92 1.56E-02 9.32E03 j Y-93 4.66E-02 5.35E04 l Zr-95 7.74E-02 3.62E02 l Zr-97 1.82E-03 1.23E03 l
Nb-95 1.34E02 1.51E06 Mo-99 6.84 2.96E02 Tc-99m 3.45E-01 1.60E01 1 Tc-101 1.39E-01 2.55E-01 Ru-103 1.55E01 4.21E03 Ru-105 1.19 1.84E03 Ru-106 6.78E01 3.47E04
[ Ag-110M 1.21E01 8.35E03 ,
'~
Te-129M 6.08E03 2.57E05 Te-131M 3.13E03 3.73E05 l Te-132 6.80E03 3.42E05 Ba-139 3.51E-01 2.13E01 Ba-140 1.64E02 5.17E03 i Ba-141 1.96E-01 5.82
. Ba-142 1.66E-01 2.63 ,
La-142 9.13E 03 2.68E02 Ce-141 4.11E-01
() 1.39E04 i
Co-143 7.73E-02 2.61E04 Co-144 1.50E01 9.44E04 ,
l 1
A (l. TABLE B-1
\-./
LIQUID EFFLUENT DOSE PARAMETERS (Page 2)
Radionuclide Total Body Critical Organ Pr-143 2.87E-01 2.54E04 Nd-147 2.74-01 2.20E04 W-187 8.66E01 8.12E04 Np-239 1.70E-02 6.22E03 Br-83 4.80E01 6.91E01 Br-84 6.22E01 6.22E01 I-131 1.57E02 8.98E04 I-132 8.75 8.75E02 1-133 3.49E01 1.68E04 I-134 4.74 2.30E02 I-135 1.97E01 3.52E03 Rb-89 1.51E02 2.15E02 Cs-134 6.49E05 7.94E05 Cs-136 9.93E04 1.38E05 .
Cs-137 3.83E05 5.8SE05 Cs-138 2.90E02 5.85E02 H-3 2.80E-01 2.88E-01 t
1 i
,u i
[J
~
TABLE B-2 CALCULATIONAL ASSUMPTIONS FOR A h
^1t = 1.14 x 105 (Uw/Dw + U pBF g + UyBIg)DFg Uw = 730 kg/yr adult water consumption (Reg. Guide 1.109 Table E-5)
Dw = 24,800 dilution factor for potable water intake (RBS Environmental Report page 5.4-5)
Up = 21 kg/yr adult fish consumption (Reg. Guide 1.109 Table E-5)
BFg = bioaccumulation factor for nuclide i in fish (pC1/kg per pCi/t RBS Environmental Report Table 5.4-3 (Table B-3)
Reg'. Guide 1.109 Table A-1 RBS ER-CPS Appendix N, " Stable Element Study" Uy = 5 kg/yr adult invertebrate consumption (Reg. Guide 1.109 Table E-5)
BI g = bioaccumulation factor for nuclide i in invertebrated (pC1/kg per pCi/1)
! P Reg. Guide 1.109 Table A-1 C).
DF f
= dose conversion factor for nuclide i for adults in pre-selected organ t (mrem /pC1).
Reg. Guide 1.109, Table E-11.
l l
l 0- .
,m.a_
= . ,n.-sq e.maam mam .+w a deAa u a. .e m- _ - -A.-.%m..a-h_, ._ a f. Q,A .,.,, +- _ - _A. -_4 hd-~-a4 -a.a._
O l
l
)
l APPENDIX C KgL AIRg DOSE TRANSFER FACTORS i r
l l
@ \
I i
l l
1 l
1 I
I l
l l
e i
I
p (j TABLE C-1 DOSE TRANSFER FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF RADI0 ACTIVE NOBLE GASES D0SE TRANSFER FACTORS Gamma Beta Beta and Gamma Ki Li (L+1.1M)i mrem mrem mrem Nuclide uCi sec/m3 uCi sec/m3 uCi sec/m3 Kr-83m 2.4E-9 ---
6.7E-7 Kr-85m 3.7E-5 4.6E-5 8.9E-5 Kr-85 5.1E-7 4.2E-5 4.3E-5 Kr-87 1.9E-4 3.1E-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 3.1E-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 5.9E-5 1.3E-4 Xc-137 4.5E-5 3.9E-4 4.4E-4
(] Xe-138 2.8E-4 1.3E-4 4.5E-4 V' Ar-41 2.8E-4 8.5E-5 4.0E-4 AIR DOSE TRANSFER FACTORS Gamma Beta Hi Ni mrad mrad Nuclide uCi sec/m3 uCi sec/m3 Kr-83m 6.1E-7 9.1E-6 Kr-85m 3.9E-5 6.2E-5 l Kr-85 5.4E-7 6.2E-5 Kr-87 2.0E-4 3.3E-4 Kr-88 4.8E-4 9.3E-5 Kr-89 5.5E-4 3.4E-4 Kr-90 5.2E-4 2.5E-4 Xe-131m 4.9E-6 3.5E-5 t Xe-133m 1.0E-5 4.7E-5 Xe-133 1.1E-5 3.3E-5 Xe-135m 1.1E-4 2.3E-5 Xe-135 6.1E-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
()
ta Ref. Regulatory Guide 1.109, Revision 1, Table B-1.
1 u
p TABLE C-2
- \J-TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS 4
The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors-instead of using dose factors which are radionuclide 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 (K,ff, M df, r N,ff) 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 calculational technique.
Determination of Effective Dose Factors The effective dose transfer factors should be based on past operating.
data. The radioactive effluent distribution for the past years can be used to derive single effective factors by the following equations:
EQUATION C-1 K,gg = [ K g *f g i
where K,ff = The effective total body dose factor due to gamma emissions from all noble gases released.
K.g
= The total body dose factor due to gamma emissions from each noble gas radionuclide "1" released.
f f
= The fractional abundance of noble. gas radionuclide "i" of the total noble gas radionuclide.
EQUATION C-2 (L + 1.1 M) ,gg = E1 (Lg + 1.1 Hg ) *f t where (L + 1.1. M),ff =
The effective skin dose factor due to beta and gamma emissions from all noble gases released.
(Lg + 1.1 Mg ) = The skin dose factor due to beta and gamma emissions from each noble gas radionuclide "1" released.
O 4 8 4 l
- w. _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ - _ . _ _ _ - _ _ - - - . _ _ _ _ _ _ - _ . _ _ . . - - _ _ - _ _ _ - _ _ _ - _ - - _ _ - _ - _ _ _ _ _ _ _ __a.
' m/ TABLE C-2 TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS (Continued)
=)M EQUATION C-3 M f t
ff i i
where M,ff = The effective air dose factor due to gamma emissions from all noble gases released.
M f
5 The air dose factor due to gamma emissions from each nobic gas radionuclide "i" released.
N,gg=}))N 1 EQUATION C-4 f i
where C';
x >
N,ff _= The effective air dose factor due to beta emissions from all noble gases released.
N 1
= The air dose factor due to beta emissions from each noble gas radionuclide "i".
To provide an additional degree of conservat. ism, a factor of 0.8 is introduced into the dose calculation process i; hen the effective dose transfer factor is used. This added conservatism provides additional assurance that the evaluation of dose by the use of a single effective factor will not significantly under-estimate any actual dose in the environment.
Each year the dose factors should be determined and the average annual values be used.
u
)
u.
/7 TABLE C-3 O
EFFECTIVE DOSE FACTORS FOR N0BLE GASES TOTAL BODY EFFECTIVE DOSE - K,ff Main Plant Radwaste Building Exhaust Duct
- Exhaust Duct 3
Year K,ff (mrem-m /uCi-sec) K,ff (mrem-m /uCi-sec)
Projected ** 5.56 (-5)*** 8.05 (-5)
- Main Plant exhaust duct contains contributions from Fuel Building.
(O
(_) ** Projected values from RBS FSAR. When RBS becomes operational, actual release rates reported in semi-annual effluent report should be used to generate effective dose factors.
- -5 5.56 (-5) =_ 5.56 x 10
, l l
l i -O :
1
- __--__ _ -- ____. _--__ --- ---_--- _ _ ___.-- --- -- .--_- -_ - --.-----.----___--..------.---_-------------u----- -l
(v ; TABLE C-4 EFFECTIVE DOSE FACTORS FOR NOBLE GASES :
SKIN EFFECTIVE DOSE (L + 1.1 M),ff Main Plant Radwaste Building Exhaust Duct
- Exhaust Duct
! Year (L+1.1M),ff (mrem-m /uCi-sec) (L+1.1M),gg (mrem-m /uCi-sec)
Projected ** 1.36 (-4)*** 1.59 (-4)
- Main Plant exhaust duct contains contributions from Fuel Building.
- 1.36 (-4) = 1.36 x 10
O L)
r.
l-
/7 TABLE C-5
(_)
EFFECTIVE DOSE FACTORS FOR NOBLE GASES AIR DOSES M,gg and N,fg Main Plant Radwaste Building Exhaust Duct
- Exhaust Duct 3
(mrad-m /uCi-sec) (mrad-m /uCi-sec)
Gamma Air Beta Air Gamma Air Beta Air Year M,gg N,gg H off N off Projected ** 5.96(-5)*** 8.99(-5) 8.07 (-5) 7.40(-5)
[')
- Main Plant exhaust duct contains contributions from Fuel Building.
- -5 5.96 (-5) = 5.96 x 10 Y
l 1
~-
_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _1L_____
..m._ _ __. . _ _ _ _ . . . _ ___
I i
l; i t
t iG l
l APPENDIX D EXPECTED GASEOUS RADIONUCLIDE MIXTURE 1
l
?
I h
i
't I
- i t
s c p I
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I l
3 I
O
,ar.
g] EXPECTED RELEASE OF RADIDACTIVE NOBLE GASES V IN GASEOLS EFFLUENTS FRO?! RIVER BEND STATION FSAR*
i Containment Bui1 ding ** Radwaste Building Nuclido C1/yr Fraction C1/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 Xo-131m 21 0.005 <1 ---
Xo-133m 6.6(-2) 1.504(-5) <1 ---
Xo-133 2,340 0.533 220 .19 Xo-135 693 0.158 280 .24 Xo-135m 140 0.032 530 .46 Xo-137 380 0.087 83 .07
~
Xo-138 208 0_.047 2 1.75 x 10 4,3S9.- 1.0000 1,144 .99 P
- HBS FSAR Tablo 11.3-1
- Containment Building contains rolcasos from Fuel Building i
l i
e
I e ?
APPENDIX E X[QANDD/QVALUESFORRESTRICTEDAREABOUNDARY i
t 1
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O I
L i
,p i Long. Term Diffusion Estimates E.1 Objective Annual average CHI /Q and D/Q estimates for continuous and intermittent releases were calculated for each of the sixteen 22.5-deg sectors at l receptor locations used to determine the maximum individual and
. population dose receptors. The methodology described 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 I
Nomenclature
~
2.032 = (2/w)1/2) (23/16) 1 (dimensionless) w = 3.14159... (dimensionless) exp = 2.71828... (dimensionless)
E T.
= Entrainment. coefficient (dimensionless)
D = Terrain recirculation n k d -
factor (dimensionless) x = Downwind. receptor distance ,
(m) o = Vertical dispersion z
(plume spread) coefficient. (m) u 30
= 30-ft average wind speed 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 (see m"3)
.A. (CHI /QD ) = DePleted CHI /Q 3 (see m-3) 4 -
= Homentum-flux (m sec 3)
F, E-1 T T' Y V"' 1"Yr i F -'T" - -WF'T'"*
(~) h b
= Maximum adjacent
' \- building hefght (m) h r
= Release height (m) h, = Effective release height (m) h, = Nonbuoyant plume rise (m) h = P Er3Phic height of t
receptor above plant grade (m) d = Stack or vent diameter (m) u, = Efflux velocity (m sec" )
N = Total number of valid hours of onsite wind data in all sectors for appli-cable averaging period (dimensionless) 6/Q = Relative deposition rate normalized by source
/^i strength (m'I)
(,,/
D/Q = Relative deposition per unit area normalized by source strength (m' )
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)
- f. = Index for a particular 22.5-deg sector (dimensionless) n = Number of hours onsite wind data in a particular 22.5-deg sector (dimensionless)
S
= Stability parameter (sec' )
E-2
.h-.- -,
j.
l . E.3 CHI /Q Modeling Technique Annual average values of relative concentration were calculated for continuous gaseous releases of activity from the containment building vent and the radwaste building vent according to the straight-line airflow (Gaussian) model described 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:
a
{ )-
m
- ' '" . .on ggh ::
,i 2-1 ho(',,,,+05h/')s.(-s)~s('.,/
n
" iso ',g ,
t.3-1 '!
Since the River Bend Station site is located in relatively open
. terrain, the terrain recirculation factor (D)k (Presented in Figure 2 of Regulatory Guide 1.111) was applied.
The entrainment coefficient (E T ) is a function of the ratio of efflux velocity .(ug ) to elevated wind speed (u150) fr the conMtionaHy elevated release points.
For vent releases occuring below the level of a nearby structure, 100 percent downwash (total entrainment) is conservatively assumed (E T "
' (~' 1). For vent releases occuring'between 1 and 2 times the height of a
-\ nearby structure, a conditionally elevated release is assumed, and the entrainment coefficient is defined as follows:
ET = 0.0 when u,/u150 > 5.0 (totally elevated)
E T 0.30-0.06 (u,/u150)'
when 1.5 < u,/u150 5 5.0 (partially entrained)
E T = 2.58-158 (u,/E150) when 1.0 < u,/u150 5 1.5 (partially entrained)
ET = 1.0 when u,/u150 5 1.0 (totally entrained)
E.3-2 Within 5 km in each downwind sector, Equation E.3-1 was evaulated by sector at the property and . restricted area boundaries and nearest L resident, vegetable garden, milk cow, and meat animal. There were no E-3
-- _ _ , , , - - - ~ _ . - - - - - , _ _ _ - .., - _.- _
O V
goats whose milk is consumed in the area of interest. This evaluation was performed for each continuously 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:
h =
e hr -(ht)k + h pr 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 conservatively 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
, u,/u150 1.5 ud "e x E.3-4 h = 1.44 d Pr "150 d when u u < 1.5, j 150 "e u fx d-3 e
d E.3-4 1.5-h = 1.44 Pr "150 d ,/ "150 and -
["e\ E.3-6 Pr "150f o%J E-4 i
L_
The -result from Equation E.3-4 or E.3-5 (whichever condition exists) is.then compared to Equation E.3-6 and the smaller value of h is !-
pr used.
For E-G. stability conditons, Equations E.3-4, E.3-5, and E.3-6 are compared with: 1 1
h
=4 'm"I Pr and, h
p
= 1.5 m/ 150 I S' I where 2 2 u'
Leld F =
l m 4
and the smallest value was chosen.
[_,\
=
In the ground' level portion of Equation E.3-1, the vertical dispersion term:
[0 2 ' '2 1 7
2 I
3 + 0.5hb /*
i,k I
was constrained to be less than or equal to 1.732c .
- 1,k E.4 (CHI /Q) and D/Q Modeling Techniques Annual average depleted relative concentration values were conservatively assumed to be equal to annual average relative concentration values (CHI /Q . -
(CHI /Q)D)*
- ' #** " ##* "#8 taken for attendant plume depletion of radioiodines and particulates.
' t') .
.Q E-5 o.
/~3 Annual average ' relative deposition values were calculated using V Regulatory Guide 1.'111, Rev. I with the following equation:
r 3
~ -
' ~
E 1 ff n g, 6--
Nl .[' */
iQ/ kt
[2n{
kt16 j 4{
j=1
[(Qjg k
E T+db 1Ih ng n=1 E
T "it iQt ik s
- . , _ J - s For the conditionally elevated release points, Figures 6 through 9 of Regulatory Guide 1.111, Rev. I were used to calculate the (6/Q)g and (6/Q)g values, while for the ground level release points, Figure 6 was utilized to calculate the (6/Q)G V"I"**
E.5 Methodology Employed for Intermittent Release The methodology employed in the calculation of intermittent release CHI /Qs and D/Qs was as follows:
- 1. Two-hour sector-averaged CHI /Q values were calculated without terrain recirculation factors.
- 2. The 15 percent, I hour value was plotted at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on log-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 multiplier.
- 4. The multiplier was applied to annual average CHI /Q and D/Q values to obtain intermittent CHI /Q and D/Q values.
For River Bend Station, a 320 hr/yr intermittent release thr'ough the containment building vent from- the mechanical vacuum pump was evaluated. .
.x E-6
() TABLE E-1 ANNUAL AVERAGE CHI /Q VALUES x 10' (sec/m )
FOR RESTRICTID AREA BOUNDARY Main Plant Exhaust Radwaste Building Sector Duct (Continuous) Exhaust Duct (Continuous)
S 12.4 105 SSW 13.1 121 SW 11.2 152 WSW 14.7 247 W 19.7 578 WNW 29.1 384 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 SSE 6.53 45.6
/"%,
%_/
O
f'T TABLE E-2
-I ANNUAL AVERAGE D/Q VALUES x 10 9 (m_2)
FOR RESTRICTED AREA B0UNDARY 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 O
o ,
- 1. i 1
i !
!- l
! I t i p
j i t i
i t i
1 c j -
1 i i
l APPENDIX F MAXIMUM X/Q AND D/Q VALUES FOR INDIVIDUAL LOCATIONS i
i i
Le l.
i k
i i
I 1
i 1
I i t a
h i
L ._
,/~'s -
-3 m
% ,j' Q,-
l TABLE F-1 ATMOSPHERIC DISPERSION AND DEPOSITION RATES FOR THE MAXIMUM INDIVIDUAL DOSE CALCULATIONS
- Location Radwaste Bldg. Main Plant Analysis (meters) Exhaust Duct Exhaust Duct G:mma air dose (1) 914 m NNE CHI /Q1(5) - 384.0 CHI /Q2 - 29.1 and Beta Air Dose M;ximum 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 Garden Same .
Heat animal Same _
Immersion Same Resident (3) 2,000 m NW CHI /Q1 -
4.57 CHI /Q2 - 75.5 Garden Same D/Q1 - 2.32 - D/Q2 - 10.1 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 - 138.0 CHI /Q1 CHI /Q2 -12.1 animal (4) D/Q1 - 24.7 D/Q1 - 9.92
- Ref. Table 5.4-1 RBS ER-OLS Notes:
(1) Maximum offsite location (property boundary) with highest CHI /Q (unoccupied). The WNW sector is the controlling sector.
(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 mayimum grazing location for milk cow (see (3) above).
(5) All CHI /Q = 1,g _gec/m 3 (6) All D/Q = 10 m
l
\
4 APPENDIX G INSTANTANEOUS DOSE TRANSFER FACTOR TABLES O
4 0
e O
1
TABLE G-1
. ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS P(i) FOR GASEOUS DISCHARGE l PATHWAY = INHALATION AGE GROUP = INFANT Organ Dose Factors (mrem /yr per uCi/m3 )
Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin MN-54 4984 7056 0 25340 4984 0' 999600 .0-Co-60 11774 31920 0 8022 0 4
0 .4508E+07 .0 ZN-65 31080 51380 19320 '62580 32480 0 646800 .0 1 SR-89 11410 63980 397600 0 0 SR-90 0 .203E+07 .0
.259E07 131040 .4088E+08 0 0 0 CS-134 74480
.11242E+08 .0 1334.2 396200 702800 190400 0 79660 .0 CS-137 45500 1334.2 548800 611800 172200 BA-140 0 71260 .0 2898 38360 56000 56 13.426.
4 CE-141 0 .1596E+07 .0 1988 21560 27720 16660 5250 I-131 0 516600 .0 3.92E+04 2.12E+03 7.59E+04' 8.88E+04 1.04E+05 2.97E+07 0 .0
! I-133 1.12E+04 4.31E+03 2.65E+04 3.84E+04 l
4.48E+04 7.11E+06 - 0 .0 [
q H-3 6.47E+02 6.47E+02 .0 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 I
Based on 1 uCi/sec release rate of each nuclide (i) and a value of 1.0 for X/Q and relative deposition.
i ~
4
a---. -m- -_ _
Of I
APPENDIX H GASEOUS MPC VALUES O
t 6 1 1 g t r 9
Il TABLE H-1 AJ 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 3 E-6 Zr-95 1 E-9 Kr-85m 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 3 E-8 Sn-113 2 E-9 Kr-90 3 E-8 In-113m 2 E-7 Xe-131m 4 E-7 Sn-123 1 E-10 Xe-133m 3 E-7 Sn-126 1 E-10 Xe-133 3 E-7 Sb-124 7 E-10 Xe-135m 3 E-8 Sb-125 9 E-10 Xe-135 1 E-7 Te-125m 4 E-9 Xe-137 3 E-8 Te-127m 1 E-9 Xe-138 3 E-8 Te-129m 1 E-9 H-3 2 E-7 I-130 1 E-10 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-90 3 E-11 Ce-141 5 E-9 Rb-88. 3 E-8 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 single radionuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive half-lives less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />."
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b APPENDIX I ENVIRONMENTAL DOSE TRANSFER FACTORS FOR GASEOUS EFFLUENTS O
I l
i l
l i
i I
i
)
O
ks TABLE I-1 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE PATHWAY = INHALATION AGE GROUP = ADULT Organ Dose Factors (mrem /yr per uCi/m3 )
Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin MN-54 6296 77360 0 39600 9840 0 .14E+07 .0 C0-60 14800 284800 0 11520 0 0 .5968E+07 .0 ZN-65 46560 53440 32400 103200 68960 0 864000 .0 SR-89 8720 349600 304000 0 0 0 .14E+07 .0 SR-90 .61E+07 722074 .992651E+08 0 0 0 .96063E+07 .0 CS-134 728000 10400 372800 848000 287200 0 97600 .0 CS-137 428000 8400 478400 620800 222400 0 75200 .0 BA-140 2568 218400 39040 49.04 16.72 0 .1272E+07 .0 CE141 1528 120000 19920 13520 6264 0 361600 .0 I-131 40960 12560 50400 66720 122560 I-133 2.38E+07 0 .0 9040 17760 17280 29600 51280 4.3E+06 H-3 0 .0 1.26E+03 1.26E+03 .0 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 l
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 / year per uCi/m3 ).
h TABLE I-2 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE PATHWAY = INHALATION AGE GROUP = TEEN l
l Organ Dose Factors (mrem /yr per uCi/m3 )
Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin
, MN-54 8400 66800 0 51120 ' 12720 0 .1984E+07 .0
! CO-60 19840 259200 0 15120 .0 0 .872E+07 .0 '
ZN-65 62400. 46640 38560 133600 86400 0 .124E+07 .0 SR-89 12480 371200 434400 0 -0 0 .2416E+07 .0 SR-90 .668E+07 764800 .108E+09 0 -
0 0 .1648E+08 .0 CS-134 548800 9760 502400 .1128E+07 375200 0 146400 .0 CS-137 .311200 8480 670400 848000 304000 0 120800 .0 ~
l BA-140 3520 228800 54720 68.64 22.8 0 .2032E+07 .0 ,
l C-141 2168 126400 28400 18960 8880 0 613600 .0 '
! I-131 5.28E+04 1.30E+04 7.09E+04 9.82E+04 -
1.68Et05 2.93E+07 0 .0 l I-133 1.24E+04 2.06E+04 2.43E+04 4.10E+04 7.18E+04 5.84E+06 0 .0 l H-3 1.27E+03 1.27E+03 ,
.0 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1
l Based on 1 uCi/sec release rate of each nuclide (i) and a value'of 1.0 for X/Q and relative deposition.
l Note: The units for C-14 and H-3 are (mrem / year per uCi/m3 ).
1 l
___....-._~..~.3 .,_.m.,, m.,m_. , ,- ,%,,..y - --,.e 3s... +.-
TABLE I-3 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS-DISCHARGE PATHWAY = INHALATION AGE GROUP = CHILD Organ Dose' Factors (mrem /yr per uCi/m3 )
Nuclide T. Body CI-Tract Bone Liver Kidney Thyroid Lung Skin HN-54 9509 22903 0 42920 10027 0 .15762E+07 .0 CO-60 22644 96200 0 13135 0 0 .7067E+07 .0
~.
ZN-65 70300 16317 42550 113220 71410 0 . 995300 .0 SR-89 17242 167240 599400 0 0 0 - .21571E+07 .0 SR-90 .644E+07 343467 .101041E+09 0 0 0 .147676E+08 .0 CS-134 224590 3848 651200 .10138E+07 330410 0 120990 .0 CS-137 128390 3618.6 906500 825100. 282310 0 103970 .0 BA-140 4329 101750 74000 64.75 21.27 0 .17427E+07 .c CE-141 2897.1 56610 39220 19536 8547 0 543900 .0 I-131 5.45E+04 5.68E+03 9.62E+04 9.62E+04 1.58E+05 3.25E+07 0 .0 I-133 1.54E+04 1.10E+04 3.32E+04 4.06E+04 6.76E+04 7.70E+06 0 .0 H-3 1.12E+03 1.12E+03 .0 1.12E+03 1.12E+03 1.12E+03 1.12E+03 -1.12E+03 i
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; year per uCi/m3 ).
L 1
9
m h ,
l l TABLE I-4 ENVIRONMENTAL PATWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE l
PATHWAY = INHALATION AGE GROUP = INFANT Organ Dose Factors (mrem /yr uCi/m3 )
i Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin-
- MN-54 4984 7056 0 25340 4984 0 999600 .0 l CO-60 11774 31920 0 8022 0 0 .0
.4508E+07 ZN-65 31080 51380 19320 62580 -32480 0 646800 .0 SR-89 11410 63980 397600 0 0 0 .203E+07 .0 l SR-90 .259E07 131040 .4088E+08 0 0 0 .11242E+08 .0 l CS-134 74480 1334.2 396200 702800 190400 0 79660 .0 l CS-137 45500 1334.2 548800 611800 172200 0 71260 .0 l BA-140 2898 38360 56000 56 13.426 0 .1596Et07 .0 CE-141 1988 21560 27720 16660 5250 0 516600 .0 I-131 3.92E+04 2.12E+03 7.59E+04 8.88E+04 1.04E+05 2.97E+07 0 .0 I-133 l 1 1.12E+04 4.31E+03 2.65E+04 3.84E+04 4.48E+04 7.11E+06 0 .0 H-3 i 6.47E+02 6.47E+02 .0 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 l
Bassd 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 / year per uCi/m3 ).
I i
i i
i
LJ LJ v TABLE I-5 ENVIRONMENTAL PATINAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE PATINAY = GROUND PLANE DEPOSITION AGE GROUP = ALL Organ Dose Factors (m2 -mrem /yr per uCi/sec)
Nuclide T. Body GI-Tra ct Bone Liver Kidney Thyroid Lung Skin MN-54 1.39E+09 1.39E+09 1.39E+09 1.39E+09 1.39E+09 1.39E+09 1.39E+09 1.63E+09 CO-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.55E+10 ZN-65 7.45E+08 7.45E+08 7.45E+08 7.45E+08 7.45E+08 7.45E+08 7.45E+08 8.62E+08 SR-89 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.52E+04 CS-134 6.85Et09 6.85E+09 6.85E+09 6.85E+09 6.85E+09 6.85E+09 6.85E+09 8.00E+09 CS-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.21E+07 BA-140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.36E+07 CE-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.55E+07 I-131 3.46E+07 3.46E+07 3.46E+07 3.46E'07 3.46E+07 3.46E+07 3.46E+07 4.18E+07 I-133 4.90E+06 4.90E+06 4.90E+06 4.90E+06 4.90E+06 4.90E+06 4.90E+06 5.96E+06 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 / year per uCi/m3 ).
[ -
~
TABLE I-6 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i).FOR GASEOUS DISCHARGE PATHWAY = COW MILK AGE GROUP = ADULT Organ Dose Factors (ma -mrem /yr per uCi/sec)
Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin CO-60 .284E+08 .241881E+09 .0 .128763E+08 .0 .0 .0 .0 MN-54 .127E+07 .203899E+08 .0 .665585E+07 .198073E+07 .0 .0 .0 I
ZN-65 ~
'176E+10
. .245287E+10 .122391E+10 .389425E+10 .26046E+10 .0 .0 .0 l SR-89 .351E+08 .196147E+09 .122294E+10 .0 .0 .0 .0 .0 l SR-90. .946E+10 .111384E+10 .38552E+11 .0 .0 .0 .0 .0 l CS-134 .857E+10 .18344E+09 .44054E+10 .104823E+11 .339259E+10 .0 .112614E+10 .0 CS-137 .529E+10 .156329E+09 .590494E+10 .807577E+10 .274132E+10 .0 .911303E+09 .0 BA-140 .167E+07 .524857E+08 .254895E+08 32018.8 10886.4 .0 18332.3 .0 CE-141 324.468 .109361E+08 4229.83 2860.56 1328.6 .0 .0 .0 I-131 2.38E+08 1.10E+08 2.90E+08 4.16E+08 7.12E+08 1.36E+11 .0 .0
! I-133 2.06E+06 6.04E+06 3.86E+06 '
6.72E+06 1.17E+07 9.88E+08 .0 .0 l
H-3 4.73E+02 4.73E+02 .0 4.73E+02 4. 73E+02- 4.73E+02 4.73E+02 4.73E+02 C-14 7.33E+04 7.33E+04 3.67E+05 7.33E+04 7.33E+04 7.33E+04 7.33E+04 7.33E+04 Based on 1 uCi/sec release rate of each nuclide (i) and a value of 1.0 for X/Q,and relative deposition.
Nate: The units for C-14 and H-3 are (mrem / year per uCi/m3 ).
I
U
) f.
NJ TABLE I ;
ENVIRONMENTAL PATHWAY - DOSE CONVERSION' FACTORS R(i) FOR' GASEOUS DISCHARGE PATHWAY = COW MILK AGE GROUP = TEEN Organ Dose Factors-(ma -mrem /yr per uCi/sec)
Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid -Lung Skin MN-54 .22E+07 .227521E+08' .0 .11094E+08 .33094E+07 .0 .0 . .0 CO-60 .491E+08 .283896E+09 .217964E+08- .0 .0 .0
.0 .0 ZN-65 .304E+10 ' .275979E+J0 .187678E+10 .651661E+10 .417063E+10 .0 .0 *
.0 SR-89 .646E+08- .268654E+09 .225587E+10 .0 .0 .0 .0 .0 SR-90 .134E+11- .152302E+10 .542537E+11 .0 .0 .0 .0 .0 CS-134 .836E+10 .224092E+09 .765571E+10 .180188E+11 .572578E+10 .0 .218604E+10 .0 CS-137 .496E+10 .202605E+09 .107037E+11 .142397E+11 .484532E+10 .0- .18827E+10 .0 BA-140 .297E+07 .710852Et08 .460918E+08 56478.7 19150.8- .0 37997.1 .0 CE-141 594.76 .148107E+08 7755.2 5177.91 2437.35 .0 .0 .0 I-131 3.96E+08 '1.46E+08 5.26E+08 7.38E+08 1.27E+09 2.16E+11 .0 .0 I-133 3.66E+06 9.08E+06 7.08E+06 1.20E+07 2.10E+07 1.68E+09 .0 .0 H-3 6.16E+02 6.16E+02 .0 6.16E+02 6.16E+02 6.16E+02 6.16E+02 6.16E+02 C-14 1.35E+05 1.35E+05 6.67E+05 1.35E+05 1.35E+05 1.35E+02 1.35E+05 1.35E+05 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 / year per uCi/m3 ).
7.- s b \_) V TABLE I-8 l ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS P(i) FOR GASEOUS DISCHARGE 1
1 i
PATHWAY = COW MILK AGE GROUP = CHILD Organ Dose Factors (m2 -mrem /yr per uCi/sec)
Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin MN-54 .441E+07 .138954E+08 .165568E+08 .464211E+07 .0 .0
.0 .0 l CO-60 .999E+08 .187633E+09 .0 .338763E+08 .0 .0 . 0' .0 ZN-65 .611E+10 .172533E+10 .368753E+10 .982445E+10 .619075E+10 .0 .0 .0 SR-89 .159E+09 .215515E+09 .556711E+10 .0 .0
.0 .0 .0 SR-90 .233E+11 .123798E+10 .919026E+11 .0 .0 .0
.0 .0 CS-134 .611E+10 .156144E+09 .176511E+11 .289659E+11 .897642E+10 .0 .0
.322095E+10 CS-137 .364E+10 .154424E+09 .257636E+11 .246606E+11 .803636E+10 .0 .289152E+10 .0 BA-140 .649E+07 .563359E+08 .1112E+09 97416.9 31714 .0 58075.5 .0 CE-141 1410 .118459E+08 19039.8 9495.92 4162.86 .0 .0 .0 I-131 7.3E+08 1.14E+08 1.28E+09 1.28E+09 2.1E+09 4.24E+11 .0 .0 I-133 8.04E+06 8.56E+06 1.72E+07 2.12E+07 3.54E+07 3.94E+09 .0 .0 H-3 9.73E+02 9.73E+02 .0 9.73E+02 9.73E+02 9.73E+02 9.73E+02 9.73E+02 C-14 3.34E+02 3.32E+05 1.66E+06 3.32E+05 3.32E+05 3.32E+05 3.32E+05 3.32E+05 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 / year per uCi/m3 ).
p , ,,
V U U TABLE I-9 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE PATHWAY = COW MILK AGE GROUP = INFANT l
l Organ Dose Factors (m2 -mrem /yr per uCi/sec)
Nuclide T. Body GI-Tract Bone Liver
- Kidney Thyroid Lung Skin MN-54 .698E+07- .113135E+08 .0 .307987E+08 .682523E+07 .0 .0 .0 i C0-60 .163E+09 .164278E+09 .0 .690353E+08 l .0 .0 .0 .0 ZN-65 .783E+10- .143415E+11 .495093E+10 .169785E+11 .823361E+10 .0 .0 .0 SR-89 .304E+09 .217867E+09 .105978E+11 .0
.0 .0 .0 .0 SR-90 .254E+11 .124573E+10 .997665E+11 .0
.0 .0 .0 .0 CS-134 .536E+10 .144192E+09 .284608E+11 .530715E+11 .136642E+11 .0 .560158E+10 .0 CS-137 .341E+10 .150418E+09 .41109E+11 .48113E+11 .129155E+t1 .0 BA-140
.522919E+10 .0
.118E+08 .562543E+08 .229035E+09 229035 54379.1 .0 140636 .0 CE-141 2720 .119391E+08 37887.4 23108 7124.96 .0 .0 .0 I-131 1.38E+09 1.12E+08 2.66E+09 3.38E+09 3.66E+09 1.03E+12 .0 .0 1-133 1.55E+07 8.96E+06 3.64E+07 5.30E+07 6.22E+07 9.62E+09 .0 H-3
.0 1.48E+03 1.48E+03 .0 1.48E+03 1.48E+03 1.48E+03 1.48E+03 1.48E+03 C-14 6.95E+05 6.95E+05 3.26E+06 6.95E+05 6.95E+05 6.95E+05 6.95E+05 6.95E+05 Bseed on 1 uCi/sec release rate of each nuclide (i) and a value of 1.0 for X/Q and relative deposition.
1 Note: The units for C-14 and H-3 are (mrem / year per uCi/m3 ).
l
e L )x p) w
- 7 L)
TABLE I-10 l ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE PATHWAY = GOAT MILK AGE GROUP = ADULT Organ Dose Factors (m2 -mrem /yr per uCi/sec)
Nuclide T. Body GI-Tra ct Bone Liver Kidney Thyroid Lung Skin CO-60 .341E+07 .290428E+08 .0 .154606E+07 .0 .0 .0 .0 MN-54 .152E+06 .244037E+07 .0 796606 237064 .0 .0 .0 ZN-65 .211E+09 .294066E+09 .14673E+09 .466868E+09 .312256E+09 .0 .0 .0 SR-89 .738E+08 .412412E+09 .257131E+10 .0 .0 .0 .0 .0 SR-90 .198E+11 .233129E+10 .806903E+11 .0 .0 .0 .0 .0 CS-134 .257E+11 .550107E+09 .132111E+11 .314347E+11 .101738E+11 .0 .337711E+10 .0 CS-137 .159E+11 .469874E+09 .177483E+11 .242731E+11 .82395E+10 .0 .273908E+10 .0 BA-140 201000 .631714E+07 .306789E+07 3853.76 1310.28 .0 2206.47 .0 CE-141 38.936 .131233E+07 507.578 343.266 159.432 .0 .0 .0 I-131 2.86E+08 1.31E+08 3.48E+08 4.98E+08 8.52E+08 1.63E+11 .0 .0 I-133 2.46E+06 7.26E+06 4.64E+06 8.06E+06 1.41E+07 1.19E+09 .0 .0 H-3 3.65E+02 9.65E+03 .0 9.65E+02 9.65E+02 9.65E+02 9.65E+02 9.65E+02 C-14 7.33E+04 7.33E+04 - 3.67E+05 7.33E+04 7.33E+04 7.33E+04 7.33E+04 7.33E+04 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 / year per uCi/m3 ).
O O O TABLE I-11 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE i
! PATHWAY = GOAT MILK AGE GROUP = TEEN Organ Dose Factors (m2 mrem /yr per uCi/sec)
Nrclide T. Body CI-Tract Bone l
Liver Kidney Thyroid Lung Skin MN-54 264000 .273026E+07 .0 .133128E+07 397128 .0 .0 .0 CO-60 .59E+07 .341137E+08 .0 .261912E+07 .0 .0
.0 .0 ZN-65 . 365E+09 .331356E+09 .225338E+09 .782422E+09 .50075E+09 .0 .0 .0 l SR-89 .136E+09 .565587E+09 .474921E+10 .0 .0 .0 .0 .0 SR-90 .282E+11 .320517E+10 .114176E+12 .0 .0 .0 .0 .0 CS-134 .25E+11 .670131E+09 .228939E+11 .53884E+11 .171225E+11 .0 .65372E+10 .0 CS-137 .149E+11 .608632E+09 .321541E+11 .427765E+11 .145555E+11 .0 .565568E+10 .0 BA-140 356000 .852066E+07 .552481E+07 6769.84 2295.52 .0 4552.13 .0 CE-141 71.37 .177725E+07 930.609 621.339 292.477 .0 .0 .0 I-131 4.76E+08 1.75E+08 6.32E+08 8.84E+08 1.52E+09 2.58E+12 .0 .0 I-133 4.40+06 1.09E+07 8.48E+05 1.44E+07 2.52E+07 2.00E+09 .0 .0 H-3
~
1.26E+03 1.26E+03 .0 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 C-14 1.35E+05 1.35E+05 6.76E+05 1.35E+05 1.35E+05 1.35E+05 1.35E+05 1.35E+05 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 ).
.n U O- O,-~
l TABLE I-12 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE
~
PATHWAY = GOAT MILK -
, AGE GROUP = CHILD ~
l l Organ Dose Factors (m2 -mrem /yr per uCi/sec)
L Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin HN-54 530000 .166996E+07 .198982E+07 557895 .0
.0 .0 .0 CO-60 .12E+08 .225385E+08 .0 .406923E+07 .0 .0 l
.0 .0 ZN-65 .733E+09 .206984E+09 .4423.83E+09 .117861E+10 .742687E+09 .0 .0 .0 SR-89 .335E+09 .454072E+09 .117294E+11 .0 .0 .0 .0 .0 i SR-90 .489E+11 .259817E+10 .1929377+12 .0 .0 .0 .0 .0 CS-134 .183E+11 .467667E+09 .528667E+11 .867556E+11 .268852E+11 .0 .964704E+1 .0 CS-137 .109E+11 .462424E+00 .771493E+11 .738463E+11 .240649E+11 .0 .865866E+10 .0 i BA-140 779000 .676204E+07 .133474E+08 11693 3806.7 .0 6970.9 .0 j CE-141 170 .142823E+07 2295.58 1144.9 .501.905 .0 .0 .0 I-131 8.76E+08 1.37E+08 1.53E+09 1.54E+09 2.52E+03 5.10E+11 .0 .0 I-133 9.66E+06 1.03E+07 2.12E+07 2.56E+07 4.26E+07 4.74E+09 .0 .0 i H-3 1.99E+03 1.99E+03 .0 .' 1.99E+03 1.99E+03 1.00E+03 1.99E+03 1.99E+03 C-14 3.32E+05 " 3.32E+05 1.66E+06 3.32E+05 3.32E+05 3.32E+05 3.32E+05 3.32E+05 Based on 1 uCi/sec talease rate of each nuclide (i) and a value of 1.0 for X/Q and relative deposition.-
Note: The units for C-14 and 11-3 are (mrem / year per uCi/m3 ).
! I i
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TABLE I-13 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE f
PATHWAY = GOAT MILK AGE GROUP = INFANT Organ Dose Factors (ma -mrem /yr per uCi/sec)
Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin HN-54 .838E+06 .135827E+07 CO-60
.0 .369761E+07 .819419E+06 .0' .0 .0
.196E+08 .197537E+08 .0 .830118E+07 .0 .0 ZN-65 .0 .0
.939E+09 .171989E+10 .593732E+09 .203611E+10 .987402E+09 .0 .0 SR-89 .0
.64E+09 .458667E+09 .223111E+11 .0 .0 .0 .0 SR-90 .535E+11
.0
.262389E+10 .210138E+12 .0 .0 .0 .0 .0 CS-134 .161E+11 .433113E+09 .854887E+11 .159413E+12 CS-137
.410437E+11 .0 .168256E+11 .0
.102E+11 .449931E+09 .122965E+12 .143931E+12 .386328E+11 .0 BA-140 .156416E+11 .0
.141E+07 .672191E+07 .273678E+08 27367.8 6497.84 .0 CE-141 326 16804.8 .0
.143094E+07 4540.92 2769.56 853.947 .0 .0 .0 I-131 1.66E+09 1.35E+08 3.2E+09 3.78E+09 4.4E+09 1.24E+12 .0 .0 I I-133 1.86E+07 1.07E+07 4.36E+07 6.36E+07 7.46E+07 1.16E+10 H-3 ' .0 .0 3.01E+03 3.01E+03 .0 3.01E+03 3.01E+03 3.01E+03 3.01E+03 C-14 3.01E+03 6.9eE+05 6.95E+05 3.26E+06 6.95E+05 6.95E+05 6.95E+05 6.95E+05 6.95E+05 B: sed 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 / year per uCi/m3 ).
6
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TABLE I-14 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE
. PATHWAY = MEAT AGE GROUP = ADULT Organ Dose Factors (ma -mrem /yr per uCi/sec)
Nuclide -
T. Body .-GI-Tract Bone Liver Kidney Thyroid Lung Skin CO-60 .13E+09 .11072E+10 .0 .589407E+08 .0 .0 .0 .0 MN-54 .138E+07 .22156E+08 .0 .723234E+07 .215229E+07 .0 .0 .0 ZN-65 .456E+09 .635517E+09 .317103E+09 .100897E+10 .674828E+09 .0 .0 .0 SR-89 .732+07 .409059E+08 .255041E+09 .0 .0 .0 .0 .0 SR-90 .251E+10 .295532E+09 .102289E+11 .0 .0 .0 .0 .0 CS-134 .998E+09 ~ .213621E+08 .513022E+09 .122069E+10 .395076E+09 .0 .131142E+09 .0 CS-137 .625E+09 .184699E+08 .697654E+09 .954132E+09 .32388E+09 .0 .107668E+09 .0 BA-140 .179E+07 .562571E+08 .273211E+08 34319.6 11668.6 .0 19649.6 .0 CE-141 941.49 .317327E+08 12273.5 8300.32 3855.13 .0 .0 .0 .
I-131 8.68E+06 4.0E+06 1.06E+07 1.51E+07 2.6E+07 4.96E+09 .0 .0 I-133 2.00E-01 5.80E-01 3.8E-01 6.40E-01 1.12
- 9.5Et01 .0 .0 -
H-3 2.01E+02 ~2.02E+02 .0 2.01E*02 2.01E+02 ' 2.01E+04 2.01E+04 2.01E+04 C-14 6.72E+04 6.72E+04 3.36E+05 6.72E+04 6.72E+04 6.72E+04 6.72E+04 6.72E+04 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 / year per uCi/m3 ).
, -oa=-
U~ U,, LJ ,
TABLE I-15 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE PATHWAY = MEAT AGE GROUP = TEEN Organ Dose Factors (ma -mrem /yr per uCi/sec)
Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin MN-54 .11E+07 .113761E+08 .0 .554701E+07 .16547E+07 .0 .0 .0 CO-60 .103E+09 .595545E+09 .0 .457235E+08 .0- .0 .0 .0 ZN-65 .361E+09 .327725E+09 .222868E+09 .773848E+09 .495263E+09 .0 .0 .0 SR-89 .616E+07 .256178E+08 .215111E+09 '. 0 .0 .0 .0 .0 SR-90 .164E+10 .1864E+09 .664E+10. .0 .0 .0 .0 .0 CS-134 .445E+09 .119283E+08 .407511E+09 .959136E+09 .304781E+09 .0 .116362E+09 .0 CS-137 .268E+09 .109472E+08 .578343E+09 .769403E+09 .261803E+09 .0 .101726E+09 .0 BA-140 .146E+07 .349443E+08 .226579E+08 27763.9 9414.21 .0 18668.9 .0 CE-141 790.3 .1968E+08 10304.9 6880.26 3238.68 .0 .0 .0 1-131 6.62E+06 2.44E+06 '8.80E+06 1.23E+07 2.12E+07 3.6E+09 .0 .0 I-133 1.60E-01 4.00E-01 3.2E-01 5.2E-01 9.20E-01 7.37E+01 .0 .0 H-3 1.20E+02 1.20E+02 .0 1.20E+02 1.20E+02 1.20E+02 1.20E+62 1.20E+02 C-14 5.67E+04 5.67+04 2.84E+05 5.67E+04 5.67E+04 5.67E+05 5.67E+Q4 5.67E+04 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 / year per uCi/m3 ).
l
TABLE.I-16 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i)'FOR GASEOUS DISCHARGE i
-PATHWAY = NEAT
- AGE GROUP = CHILD i
i Organ Dose Factors (m2 -mrem /yr per uCi/sec)
Nuclide T. Body -GI-Tract Bone Liver Kidney Thyroid Lung Skin j MN-54 .169E+07 .532498E+07 .0 .634491E+07 .177895E+07 .0 .0 .0 j CO-60 .16E+09 .300513E+09 .0 .542564E+08 .0 .0 .0 .0- ,
ZN-65 .554E+09 .156438E+09 .334352E+09 .890793E+09 .561322E+09 .0 .0 . .0 '
SR-89 .116E+08 .157231E+08 .406154E+09 .0- - .0 .0 .0 .0
- SR-90 .217E+10 .115297E+09 .855917E+10 .0 .0 .0 .0 .0 CS-134 .249E+09 .636333E+07 .719333E+09 .118044E+10 .365815E+09 .0 .131263E+09 .0 CS-137 .151E+09 .640606E+07 .106877E+10 .102301E+10 .333377E+09 .0 .11995E+09 .0 j BA-140 .243E+07 .210934E+08 .416357E+08 36475.1 11874.4 .0 21744.7 .0 CE-141 1440 .12098E+08 19444.9 9697.96 4251.43 .0 .0 .0 I-131 9.34E+06 1.46E+06 1.63E+07 1.64E+07 2.70E+07 5.42E+09 .0 .0 I-133 2.80E-01 2.80E-01 5.80E-01 7.2E-01 1.18 1.33E+02 .0 .0 ,
H-3 1.45E+02 1.45E+02 .0 1.45E+02 1.45E+02 1.45E+02 1.45E+02 1.45E+02 i
C-14 1.07E+05 1.07E+05 5.33E+05 1.07E+05 1.07E+05 1.07E+05 1.07E+05 1.07E+05
) Based on 1 uCi/sec release rate of each nuclide (i) and a value of 1.0 for X/Q and relative deposition.
l Note: The units for C-14 and H-3 are (mrem / year -per. uci/m3 ).
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TABLE I-17 ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE PATHWAY = VEGETATION AGE GROUP = ADULT Organ Dose Factors (m2 -mrem /yr per uCi/sec)
Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin CO-60 .36E+09 .30661E+10 .0 .16322E+09 .0 .0 .0 .0 MN-54 .576E+08 .924771E+09 .0 .301872E+09 .898349E+08 .0 .0 .0 ZN-65 .548E+09 .763736E+09 .38108E+09 .121253E+10 .810977E+09 .0 .0 .0 SR-89 .277E+09 .154794E+10 .965113E+10 .0 .0 .0 .0 .0 SR-90 .159E+12 .18721E+11 .647968E+12 .0 .0 .0 .0 .0 CS-134 .869E+10 .186009E+09 .446709E+10 .106291E+11 .344009E+10 .0 .114191E+10 .0 CS-137 .579E+10 .171105E+09 .646307E+10 .883908E+10 .300042E+10 .0 .997437E+09 .0 BA-140 .883E+07 .2618E+09 .127142E+09 159711 54301.6 .0 91442.1 .0 CE-141 14700 .49546E+09 191632 129598 60192.2 .0 .0 .0 I-131 6.6E+07 3.04E+07 8.04E+07 1.15E+08 1.97E+08 3.78E+10 .0 .0 I I-133 1.1E+06 3.24E+06 2.08E+06 3.62E+06 6.30E+06 5.30E+08 .0 .0 l H-3 1.40E+03 1.40EiO3 .0 1.40E+03 1.40E+03 1.40E+03 1.40E+03 1.40E+03 C-14 1.81E+05 1.81E+05 9.05E+05 1.81E+05 1.81E+05 1.81E+05 1.81E+05 1.81E+05 Based on 1 uCi/sec release rate of each nuclide (i) and a value of 1.0 for X/Q and r elative deposition.
Note: The units for C-14 and H-3 are (mrem / year per uCi/m3 ).
TAB -18 ENVIRONMENTAL PATINAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE PATHWAY = VEGETATION AGE GROUP = TEEN Organ Dose Factors (m2 -mrem /yr per uCi/sec)
Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin MN-54 .871E+08 .900778E+09 .0 .439222E+09 .131022E+09 .0 .0 .0 CO-60 .548+09 .316853E+10 .0 .243267E+09 .0 .0 .0 .0 ZN-65 .838E+09 .760757E+09 .517351E+09 .179636E+10 .114967E+10 .0 .0 .0 SR-89 .419E+09 .174251E+10 .146317E+11 .0 .0 .0 .0 .0 SR-90 .201E+12 .228454E+11 .813805E+12 .0 .0 .0 .0 .0 CS-134 .723E+10 .193802E+09 .662091E+10 .155833E+11 .495184E+10 .0 .189056E+10 .0 CS-137 .48E+10 .196069E+09 .103584E+11 .137803E+11 .468902E+10 .0 .182197E+10 .0 BA-140 .88E+07 .210623E+09 .136568E+09 167344 56743.2 .0 112525 .0 CE-141 21100 .525431E+09 275127 183694 86468.6 .0 .0 .0 I-131 5.76E+07 2.12E+07 7.66E+07 1.07E+08 1.85E+08 3.12E+10 .0 .0 I-133 9.98E+05 2.48E+06 1.93E+06 3.28E+06 5.74E+06 4.56E+08 .0 .0 H-3 1.60E+03 1.60E+03 .0 1.60E+03 1.60E+03 1.60E+03 1.60E+03 1.60E+03 C-14 2.93E+05 2.93E+05 1.47E+06 2.93E+05 2.93E+05 2.93E+05 2.93E+05 2.93E+05 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 / year per uCi/m3 ).
I
l O
o o TABLE I O ~
ENVIRONMENTAL PATHWAY - DOSE CONVERSION FACTORS R(i) FOR GASEOUS DISCHARGE PATHWAY = VEGETATION AGE GROUP = CHILD '
Organ Dose Factors (ma -mrem /yr per uCi/sec) "
Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin
, MN-54 .171E+09 .5388E+09 .0 .642E+09 .18E+09 .0 .0 .0 l CO-60 .109E+10 .204724E+10 .0 .369622E+09 .0 .0 .0 .0 ZN-65 .165E+10 .465925E+09 .995815E+09 .265308E+10 .167181E+10 .0 .0 .0 SR-89 .993E+09 .134595E+10 .347682E+11 .0 .0 .0 .0 ,0 SR-90 .342E+12 .181712E+11 .134896E+13 .0 .0 .0 . .0 .0 CS-134 .532E+10 .135956E+09 .153689E+11 .252207E+11 .78158E+10 .0 .280449E+10 .0-CS-137 .346E+10 .146788E+09 .244896E+11 .234411E+11 .763896E+10 .0 .274853E+10 .0 BA-140 .16E+08 .138887E+09 .274144E+09 240165 78185.6 .0 143175 .0 CE-141 47300 .397384E+09 638711 318551 139648 .0 .0 .0 I-131 8.14E+07 1.28E+07 1.42E+08 1.43E+08 2.36E+08 4.74E+10 .0 .0 l I-133 1.64E+06 1.75E+06 3.50E+06 4.34E+06 7.22E+06 8.06E+08 .0 .0 l H-3 2.49E+03 2.49E+03 .0 2.49E+03 2.49E+03 2.49E+03 2.49E+03 2.49E+03 i
C-14 7.07E+05 7.07E+05 3.54E+06 7.07E+05 7.07E+05 7.07E+05 7.07E+05 7.07E+05 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 / year per uCi/m3 ).
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l GULF STATES UTILITIES COMPANY P o S T O F F I C E B o x 2 9 51 . BEAUMONT. TEXAS 77704 AREACODE 409 838-6831 September 16, 1985 RBG- 22,117 File No. G9.5 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Denton:
River Bend Station-Unit 1 Docket No. 50-458 In accordance with the commitment in our August 5, 1985 letter, Gulf States Utilities Company encloses Revision 3 to the Offsite Dose Calculation Manual. The contents of this document have been previously discussed with your Staff and their comments appropriately included.
, Any comments or questions should be directed to Mr. James Cook of my staff at (409) 839-3013.
Sincerely,
$A.
J. E. Booker Manager-Engineering, Nuclear Fuels & Licensing -
River Bend Nuclear Group JEB/WJR/ C/kt Enclosure
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