ML20245F010
| ML20245F010 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 04/24/1989 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20245F003 | List: |
| References | |
| RSP-0008, RSP-8, NUDOCS 8905020235 | |
| Download: ML20245F010 (111) | |
Text
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RIVER BEND STATION GULF STATES UTILITIES OFFSITE DOSE CALCULATION MANUAL (ODCM)
REVISION 2 i
I 8905020235 890424 PDR ADOCK 05000458' P
PNU-
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Table of Contents i
Section Page 1
1.0 Introduction................................. ............ 3 1.1 Purpose .................................................. 3 1.2 References .... .......................................... 3 ,
1.3 Definitions .................................... ......... 4 1.4 Required Equipment ....................................... 5 1.5 Precautions and Limitat ions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.6 Prerequisites ............................................ 5 2.0 Liquid E f fluent Methodology. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 2.1 River Bend Station Site Description....................... 6 2.2 Compliance with 10CFR20 (Liquids)............... ........ 6 2.3 Determination of Setpoints for Radioactive Liquid Effluent Monitors....................................... 7 2.4 Determining the Dose for Radioactive Liquid Effluents..... 10 2.5 Projecting Dose for Radioactive Liquid Effluents.......... 11 3.0 Gaseous Effluent Methodology.............................. 12 3.1 Introduction.............................................. 12 3.2 Data Requirements for Gaseous Effluents................... 12 3.3 Instantaneous Release Rate and Setpoint Determination...... 13 3.4 Cumulative Dose Determination for Radioactive Gaseous Effluents......................... 4 .................... 27 3.5 "-se Projection - Determination of Need to Operate Ventilation Exhaust Treatment System.................... 38 4.0 Radiological Environmental Monitoring Program.... ......... 39 5.0 40CFR190 Considerations................................... 49 5.1 Comp li ance with 46CFR19 0. . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . 49 5.2 Calculations Evaluating Conformanca with 40CFR190. . . . . . . . . 49 5.3 Calculations for Total Body Dose.......................... 50 i 5.4 Thyroid Dose.............................................. 50 5.5 Or gan : Dos e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 I 5.6 Skin Dose................................................. 52 6.0 Interlaboratory Comparison Studies........................ 52 6.1 Requirement........ ..................................... 52 6.2 Program................................................... 52 RSP-0018 REV. 2 PAGE 1 0F 110 h
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Appendices PAGE A Liquid'KPC Values 54 F Liquid Environmental Dese Transfer Factors A 56 C K L Air Dose Transfer Factors 60 D Expected; Gaseous Radionuclides Mixture 67 E X/Q and D/9 Values _for Restricted Area Boundary 69 F Maximum X/Q and D/Q for Individual Locations 78 G Instantaneous Dose Transfer Factor Tables 80 H Gaseous MPC Values 82 I Environmental Dose Transfer ractors for Gaseous Effluents 84 Figures 1 Restricted Area and Near-Field Environmental Monitoring Locations 104 2 Schematic of Gaseous Radwaste System 105 3 Effluent Release Points 106 4 Schematic of Liquid Radwaste System 107 5 Far-Field Radiological Environmental Monitoring Locations '08 6 Schematic of the Solid Waste Treatment System '.0 9 Attachments 1 ODCM/ Procedure Revision Sheet 110 l
RSP-0008 REV. 2 PAGE 2 0F 110
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1.0 INTRODUCTION
1
~ l 1.1 PURPOSE
}
This manual provides a concise description of the environmental dose models and techniques used to calculate offsite doses resulting from measured or projected releases of radioactive materials from Gulf States Utilities' River Bend Nuclear Station. It also provides the methodology for calculating effluent monitoring setpoints and allowable release rates to ensure compliance with the Radiological I 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 onsh 4.nd offsite locations and sampling and analysis frequencies.
The ODCM follows the methodology and rodels suggested by the " Guidance Manual for Preparation of Radiological 4 Effluent Technical Specification:s for Nuclear Power Plants" (NUREG-0133, dated October 1978) and " Calculation of Annual Doses w S n from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I" (Regulatory Guide 1.109, Rev. 1, dated October 1977). 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 environmental transfer factors may be substituted for those currently included and used in this document.
1.2 RERERENCES 1.2.1 NUREG 0133; Guidance Manual for Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants; October, 1978.
1.2.2 REG. GUIDE 1.109, Rev. 1, October, 1977; Calculation-of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Compliance with 10 CFR Part 50, Appendix I.
1.2.3 U.S. Code of Federal Regulations; 10CFR20.
1.2.4 River Bend Environmental Report, OLS.
1.2.5 REG. GUIDE 1.111; Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water - Cooled Reactors. '
l 1.2.6 River "tnd Station FSAR l RSP-0008 REV. 2 PAGE 3 0F 110 I
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1.2.7 River Bend Technical Specifications; Section 3/4.11.
1.2.8 River Bend Environmental Report,-CPS.
-1.2.9- U.S. Code Of Federal Regulations, 10CFR50.
1.2.10 U.S. Code of Federal Regulations, 40CFR190.
1.2.11 NUREG 0543, Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40CFR Part 190) 1.2.12 QAFR # P-86-03-004 1.2.13 QAFR # P-86-03-005 1.2.14 QAFR # P-86-03-002 1.2.15. CONDITION REPORT # 86-0495 1.2.16 River Bend Technical Specification; Section 6.14.
1.2.17 River Bend Technical Specification 3.3.7.10 1.2.18 River Bend Station Radiological Environmental Operating Report for 1985 1.2.19 QAFR #P-86-03-003 1.3 DEFINITIONS 1.3.1 MEMBER (s) 0F THE PUBLIC -
KEMBER(S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded'from this category are persons who enter the site to service equipment'or to make deliveries. This category does . include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.
1.3.2 0FFSITF. DOSE CAICUIATION MANUAL -
The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring alare/ trip setpoints. It shall also contain a table and figure defining current radiological environmental monitoring sample locations.
RSP-0008 REV. 2 PAGE 4 0F 110
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1.3.3 SITE BOUNDARY -
TheSITEB0dNDARYshallbethat line beyond which the land is not owned, leased, or otherwise controlled by the licensee.
l 1.3.4 UNRESTRICTED AREA -
An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
1.3.5 VENTILATION EXHAUST TREATMENT SYSTEM -
A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulate from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas efflu,nts). Engineered Safety Feature (62F) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST. TREATMENT SYSTEM components.
1.4 REQUIRED EQUIPMENT 1.4.1 None 1.5 PRECAUTIONS AND LIMITATIONS 1.F.1 As per Reference 1.2.16, Licensee-initiated changes to the ODCM/ Procedure shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective.
1.5.2 No changes (s) shall be made to the ODCM/ Procedure that will reduce the accuracy or reliability of dose calculations or setpoint determinations.
1.5.3 Any change (s) shall be recorded on the ODCM Revision Sheet and made in accordance with Reference 1.2.16.
1.6 PREREQUISITES 1.6.1 None RSP-0008 REV. 2 PAGE 5 0F 110
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2.0 LIQUID EFFLUENT ME*HODOLOGY 2.1 River ' Bend 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.
The reactor is a General Electric boiling water reactor of the BWR-6 or 1972 product line. Containment is of the Mark 3 design, a free-standing cylindrical steel structure surrounded by a reinforced concrete shield building.
2.2 Compliance with 10CFR20 (Liquidsj 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 Specification Table 4.11.1.1-1.
2.2.2 Methodology This section describes the calculational method to be used to determine F g, the fraction of 10CFR20 limits of release concentrations of liquid radioactive affluents.
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, sample recovery tanks, and reactor water cleanup (as shown in Figure 4). 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.
. RSP-0008 REV. 2 PAGE 6 0F 110
i The radioactive content of each batch release will be determined prior l to release.in accordance with Table 4.11.1.1-1 of the RBS Technical j Specifications. Compliance with 10CFR20 limits will be determined 1 with~the following equation:
f 3
n C f
2.2.2.1-1 Fg = E f1+#2 i=1 (MPC)g j where:
Fg = The fraction of 10CFR20 MPC limits resulting from the release source being discharged f
3
= The undiluted release rate of the release source at the monitor location, in gpm f
2
= The cooling tower blowdown release rate, in gpm Cg = The undiluted concentration of nuclide (1),.in uCi/ml from sample assay.
=
(MPC)g- Maximum Permissible Concentration of nuclide (i) from Appendix A, in uCi/ml 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 ,
-8 For purposes of simplifying the calculations, the value of 3 x 10 uCi/ml (unidentified 10CFR20 MPC value) could be substituted for (MPC)g and the ei=21stive concentration ( C-Total = sum of all identified raManuclide concentrations) or the gross beta-gamma concentration.should be substituted for Cg . As long as the diluted
-8 uCi/ml, concentration (C-Total x gf /(f g + f2)) is less than 3 x 10 l 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.A Requirements Technical Specification 3.3.7.10 requires 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 alare/ trip setpoints shall be determined and I adjaated by the methodology which follows.
RSP-0006 REY. 2 FAGE 7 OT II0
s The high alarm setpoint for the liquid effluent radiation monitor is derived from the concentration limit provided in 10CFR20, Appendix B.
Table II, Column 2 applied at the restricted area boundary where the discharge flows into the Mississippi River.
2.3.1.2 Liquid Effluent Monitors Two General Atomics RD-53 m6nitors are provided to ensure compliance with Technical Specification limits for liquid releases. The RD-53 is an offline gamma scintillation (NaI) monitor designed for detecting radioactivity in liquids. The monitors consists of a .emovable sample canister surrounded by Pb shielding. A well inside the canister-holds the detector within the sample fluid. The two monitors are as follows:
- 1. Cooling Tower Blowdown Line Monitor (1RMS-RE108) 1
- a. Range: 10 to 10 cpm
- 2. Liquid Radwaste Effluent Monitor (1RMS-RE107) 1
- a. Range: 10 to 10 cpm 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 blowdown line discharge.
2.3.2.1 Liquid Radweste Effluent Monitor (1RMS-RE107)
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 3
unrestricted areas is determined in accordance with the preceding section for the activity concentration released.
The liquid reduasta. effluent monitor will terminate a liquid radwaste discharge if activity levels exceed the Technical Specifications limits. The automatic actions associated with a trip of the monitor are:
- 1. 1LWS-FV197 closes
- 2. ILWS-A0V258 opens RSP-0008 REV. 2 PAGE 8 0F 110
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An alarm will also be annunciated in the main control room.
The liquid [adwaste effluent line radiation monitor alarm setpoint is determined with the equation:
S = A x g 2.3.2-1 L
where:
S = .the radiation monitor setpoint (cpm or uC1/ml)
A = the counting rate (cpm /ml) or activity concentration (uCi/ml) of the sample as determined in the laboratory.
g =' the ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given batch of liquid (cpm per cpm /ml, cpm per uC1/ml, or uCi/ml per uCi/ml)
Note: A/F grepresents the counting rate of a solution having the same -
radionuclides distribution as the sample and having the maximum permissible concentration (MPC) of that mixture.
2.3.2.2 Cooling Tower Blowdown Line Monitor (1RMS-RE108)
The cooling tower monitor alarms at high levels of radioactivity in the normal plant service water / circulating water effluent to the Mississippi River. An alarm will be annunciated in the main control room if predetermined setpoints are exceeded.
The cooling tower monitor alarm setpoint is determined by the equation:
S = 2 x BKG 2.3.2.2-1 where:
i S = tha. radiation monitor setpoint (cpm or uCi/ml)
BKG = monitor background value (cpm or uCi/ml)
The cooling tower blowdown line is not expected to be a contaminated stream and normally would serve as a dilution source for the final radwaste system effluent discharge. Any significant upward fluctuation in the background level is indicative of a release which could approach 10CFR50 Appendix I limits or 10CFR20 limits when combined with the liquid radwaste effluent.
RSP-0008 REV. 2 PAGE 9 0F 110
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2.4 Determining the Dose for Radioactive Liquid Effluents
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2.4.1 Requirements Technical Specification 3.11.1.2 requires the dose or dose commitment I 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 m: ems to the total body and less than or equal to 10 mrems to any organ during any calendar year.
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2.4.2 Methodology i 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 l 4.3.1 of NUREG-0133, Rev. 1 , November 1978. The dose factors A
h ,f r all viable pathways are listed in Appendix B.
Th< following equation provides a dose calculation to the total body ;
. or any organ for a given age group (D ) based on actual -!
release conditions for a specific radioactive liquid batch release:
D =A 2.4.2-1 h h
- At
- Q g Di
- D w
n D = I D h 2.4.2-2 i=1 1
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REV. 2 RSP-0008 PAGE 10 0F 110
_. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -._____-.__.__ _ _ ____ ._ __ _ ____ ____ _ _ _ _ _ _ __ -.___J
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=
Dg Dose commitment in mrem from radionuclides (i) received by organ (t) of age group (a) resulting from a bar-5 release during the time interval at 1
A g
= Site relat dose commitment factor to the total body or any organ (t) for each identified radionuclides (1). The A g values listed in Appendix B are site-related to RBS and have the units (mrem /hr per uCi/ml)
At = The time interval in nours that the batch release occurred Q1 = The total quantity of nuclide (1) released during the batch release interval at (uC1)
= The near field dilution factor. Site specific value D,
is 77.4 l
l DF = The total volume of dilution that occurred during the bs.ch release time interval 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 doses for releases during a 31 day period, calandar quarter, or a year).
The following equation is used to calculate the total dose for the desired time period:
n D = 2.4.2-3 E
D ,)
TOTAL t j=1 where:
! D = The total dose commitment to the organ (t) due to TOTALT all releases during the desired time period in mrem.
D ,)
= The dose commitment in mrem to the organ (t) of age group (a) due to a batch liquid release (j).
RSP-0008 AEV. 2 PAGE 11 0F 110
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2.5 Projecting Dose for Radioactive Liquid Effluents
- 2. 5.1 - Requ'irements !
Technical Specification 3.11.1.3 requires the liquid radwaste treatment system be used to reduce the radioactive materials in liquid wastes prior to their discharge when projected doses due to liquid effluents, to unrestricted areas ( Figure 1 ) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.
2.5.2 Methodology The following calculational methodology shall be performed at least once per 31 day period:
TOTAL t L =
- 31 2.5.2-1 b
L PD
= Projected dose commitment (mrem) to organ (
t) of age group (a) during the 31 day period from liquid effluents.
X D
= Number of days to date in the current quarter 3.0 GASEOUS EFFLUENT METHODOLOGY 3.1 Introduction
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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 5. For purposes of simplicity, Fuel Building avhanat effluents are included in the Main Plant exhaust duct releases. All gaseous effluent releases from the Radwaste Building Exhaust Duct are assumed to be ground level releases. The Main Plant ,
Exhaust Duct routine releases are treated as a waka split I (conditionally eleveted) release.
i 3.2 Data Requirements for Gaseous Effluents For the purpose of estimating offsite radione.clide concentrations and radiation doses, measured radionuclides concentrations in gaseous effluents and in ventilation tir 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.
RSP-0008 REV. 2 PAGE 12 0F 110 j; i-e
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When a nuclide concentration is below the LLD for the analysis, it is not reported _as being present in the sample, In the absence of real-time meteorological data, historical information will be used to calculate off-site dose. Modelling will be performed in accordance with the methodologies described in Reg.
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.
3.5.1.1 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 total body and less than or equal to 3,000 mrem / year to the skin; and
- 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 formulaa are used:
n DR = (3. 5 x 10 ) (Kg ) (X/Q) 3. 3. L 2.1-1 TB I
( f) i=1 RSP-0008 REV. 2 PAGE 13 0F 110
L .
n
(!
7 DR skin = (3. x 0) I (Lg + 1.1 M )g (X/Q) ( g) ' 3.3.1.2.1-2 i=1 where:
=
DR TB D se rate.to the total body in mrem / year.
K =
g The total body dose factor due to gamma emissions
-for each identified noble gas radionuclides (i) in mrem /sec per uCi/m Appendix C.
Lg =
Skin dose factor due to beta emissions for each I identified noble gas radionuclides (i) in mrem /sec per uCi/m . Appendix C.
Mg = The air dose factor due to gamma emissions for each identified noble gas radionuclides (i) in mrad /sec per uCi/m . Appendix C.
(X/Q) = T.a highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all Sectors (sec/m3 ),
Appendix F.
Qg = The release rate of radionuclides (1) in gaseous effluents from all releases in uCi/sec.
1.1 =
Conversion factor for M gfrom mrad to mrom.
3.15 x 10 = Number of sec/ year.
In order to comply with the limits of 10CFR20, D g 1500 mram/ year and DR, kin $ I*" "* *******"*'I
- I I "'*I "' **
or beyond the site boundary.
The radionuclides six 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 3.3.1.2.1-1 and 3.3.1.2.1-2 are l 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 appropriate receptor locacions.
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8 6 To select.the most limiting location, the highest X/Q for each release point is used ,(from Appendix F):
(X/Q), = 3.31 x-10'0 sec/m
~
(X/Q)y = 4.21 x 10 sec/m where:
=
(X/Q), Chi /Q for Main Plant exhaust duct and Fuel Building exhaust duct (X/Q)y = Chi /Q for Radwasre 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 i 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 r'elease 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 NOTE ;
1 This approach for K,ff and (L + 1.1M),fg should only be used if the relative abundar.cc:
of the noble gas radionuclides in the effluent stream are similar to those listed in Appendix D or of the previous Semiannual Effluent Report, as appropriate.
(Refarance 1.1.19) l l
i RSP-0008 REV. 2 PAGE 15 0F 110 i
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- f. The above methodology can be simplified to provide for a rapid j determination of cumulative noble gas release limits based on the '
requirements 4pecified in Section 3.3.1.1. Beginning with equation 3.3.1.2.1-1 the implication proceeds as follows:
.1 1
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 L detailed explanation and evaluation of K gf. The value of K,ff h's a
been derived from the radioactive noble gas effluents' listed in RBS-FSAR and included in Appendix D. The values are:
! Radwaste Building Exhaust Duct:
K,ff =
(8.05 x 10-5) ,,3/ Ci-s W Main Plant Exhaust Duct and Fuel Building Exhaust Duct:
3 K,ff =
5.56 x 10-5 @ rem-m /uci-s u)
Either of these values, as appropriate, may be used in conjunction 1
with the total noble gas release rate (Qg ) to verify that the instantaneous dose rate is within the allowable limits. To compensate for any unexpected variability in the radionuclidc distribution, a conservatism factor of 0.8 is introduced into the calculation. The simplified equation is:
n .
DR =
TB (3.15 x 10 ) (K,ff) (X/Q) I Qf 3.3.1.2.2-1 1
0.8 i=1 where:
DRg = Total body dose rate from nobla gases in airborne releases-in arem/ year (X/Q) = The highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all Sectors (sec/m3 ),
Appendix F.
Qf = The total release rate of all noble gas nuclides from the release source of interest in uCi/sec.
3.15 x 10 7 = Number of seconds / year kSP 0008 REV. 2 PACE 16 0F 110
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This limited analysis approach methodology is also available for determining sk_in dose rates from noble gas release rates:
Beginning with equation 3.3.1.2.1-2, the simplification proceeds as follows:
From an evaluation of projected releases, an effective skin dose factor, (L + 1.1M),ff, can be derived. This dose factor is, in effect, a weighted average skin dose factor. See Appendix C for a detailed explanation and evaluation of (L + 1.1M),ff. The value of (L
+ 1.1M),ff has been derived from the radioactive noble gas effluents listed in RBS FSAR and included in Appendix D. The values are:
l Radwaste Building Exhaust Duct:
(L + 1.1M),ff = 1.59 x 10"' (mrem -m /uCi-sec)
Main Plant Exhaust Duct and Fuel Building Exhaust Duct: l 3
(L + 1,1M),ff = 1.36 x 10 (mrem -m /uCi-sec)
Either of these values, as appropriate, may be used in conjunction with the total noble gas release rate ( Q ) to verify that the f
instantaneous dose rate is within the allowable limits. To compensate for an unexpected variability in the radionuclides distribution, a conservatism factor of 0.8 is introduced into the calculation. The simplified equation is:
n .
DR Skin = (3.1 x 10 ) G + 1.1M),ff ) I Qf 3.3.1.2.2-2 0.8 i=1 where:
DR n se ra e aa e gases 2 ai h e releases 6 Skin mram/ year .
(X/Q) = The highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all Sectors (sec/m ). l Appendix F. l Qg = The total releare rate of all noble gas nuclides from the release source of interest in uCi/sec. (
3.15 x 10 = Number of seconds / year I
3.3.1.2.3 Determining the Radiciodine and 8-day Particulate l Release Rates
]
RSP-0008 REV. 2 PAGE 17 0F 110
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The following calculational method is provided for determining the f dose rate from radiciodine (I-131, I-133), tritium and particulate I j with half-lives greater than 8 days and to determine if they are I 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:
n .
DR I&BDPt
( i) ( IO) (01 ) 3.3.1.2.3-1 !
i=1 where:
I&8DPt = Dose rate to the organ t for the age group of interest from radioiodines (I/131, I-133), Tritium and 8 day particulate via the inhalation pathway (in mrem /yr).
Qg = Release rate of nuclide (1), (uCi/sec).
(X/Q) = The highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all Sectors ,
(sec/m ). Appendix F. l P
g
= The dose factor for applicable environmental pathway (in units of mrem /yr per uCi/m ) (Appendix G).
Values for. P g were calculated for a child using the inhalation pathway methodology of'NUREG-0133. The Pg values are presented in Appendix G.
l i
l l
RSP-0008 RE7. 2 PAGE 18 0F 110 j i
.~
-) ,
3.3.2 'Setpoint Determination 3.3.2.1 Requirements Instrumentatica is provided to monitor beta-gamma radiation from radioactive materials released from the River Bend Station in gaseous effluents. Each release point process monitor listed in Tech. Spec.
Table 4.11.2.1.2-1 includes an alarm (HIGH ALARM) that is set to report when the radioactive noble gas in gaseous effluents (Main Plant exhaust duct, Fuel Building exhaust duct and/or Radwaste Building exhaust duct)'is expected to cause a noble gas concentration at ground level offsite resulting in a dose rate equal to or greater than 500 mrem /yr to the total body and/or 3000 mrem /yr to the skin. ,
The ALERT alarm is set to report when the radioactive noble gas in l gaseous effluents (Main Plant exhaust duct, Fuel Building exhaust duct l and/or Radwaste Building exhaust duct) is expected to cause a noble gas concentration at ground level offsite that would result in meeting or exceeding either the 5 mrad per quarter gamma air dose or 10' mrad per quarter beta air dose limit (Technical Specification 3.11.2.2).
It is permissible to set the ALERT alarm at twice (2.0) normal (approximately 100 % unit power) detector background if nuisance alarms would result from setpoints based on gamma and beta air dose.
(Reference 1.2.12)
The distribution of radioactive noble gases in a gaseous effluent stream is determined by gamma spectrum analysis of identifiable radionuclides in effluent gas sample (s). Results of one or more i previous analyses may be averaged to obtain a representative spectrum.
In the event the distribution is unobtainable from measured data, the distribution of radioactive noble gases based on past data or calculated by the BWR-GAIZ 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
- a. HIGH ALARM Setpoint Determination This section describes-the methodology for determining HIGH ALARM / trip setpoints for the three release points:
- 1. Wida Range Gas Monitor (WRGM)
RSP-0008 REV. 2 PAGE 19 0F 110 A
- =. ;
4 g Step 1 Determine hTB utilizing ne f the following methods:
)
3
= (3.17 x 10-8) (500)-(0.8) 3.3.2.2-1 (X/Q) (K,ff) or NOTE
- methodology for determining h should I i TB be used only if isotopic analyses is available and the relative abundances of noble gas nuclides in the effluent stream are not similar to those listed in Appendix D or not similar to the noble !
gas isotopic mixture described in the previous Semiannual Effluent Report. (Reference 1.2.19) .l B
(X/Q) I (Kg ) (f f) i where: .
hTB = maximum acceptable total release rate of all noble gas radionuclides in the gryeens effluent [uci/sec]. ;
(X/Q) = The highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary-for all Sectors 3
(sec/m ). Appendix F.
Kg = The' total whole body dose factor due to gamma emissions from noble gas radionuclides (i) (mrem /see
^
per uCi/m3) from Appendix C, Table C-1.
f = Fraction of noble gas radionuclides (1) to total g
noble gas concentration.
eff i i 'i ' "' "" 'Y* ** '" #
(mrem /sec per uCi/m ) from Appendix C, Table C-3.
-8 3.17x10 = Inverse of number of seennda per year in year /sec.
RSP-0008 REV. 2 PAGE 20 0F 110
! l 0.8 = Conservative factor to account for changing isotopic
, inventory.
500 = Whole body exposure limits of 500 mrem / year.
-8 l- 3.17x10 = Inverse of number of seconds per year in year /sec.
1 Step 2 .
Determine Q, util'izing one of the following methods.
l.
= (3.17 x 10-8) (3,000) (0.8) 3.3.2.2-3 (X/Q) (L+1.1M),f, or NOTE The (L + 1.1M)g methodology for determining Q g
.ahould be used only if isotopic analyses is ;
available and the relative abundances of noble gas nuclides in the effluent stream are not similar to those lirted in Appendix D or not similar to the noble gas isotopic mixture ,
described in the previous Semiannual Effluent- '
Report. (Reference 1.2.19)
= (3.17 x 10-8) (3,000) 3.3.2.2-4
, (X/Q) I [(Lg + 1.1Mg )fg ]
. i Q,
= the maximum acceptable release rate of all gas radionuclides in the gaseous effluent [uci/sec))
Lg + 1.1Mg = Total sW dose factor due to emission from noble gas radionuclides (i) ares /sec/uci/m from Appendiz C.
(X/Q) = The highest calculated annual average relative dispersion factor for any area ar or beyond the unrestricted area boundary for all Sectors 3
(sec/m ). Appendix F.
I l
e RSP-0008 REV. 2 PAGE 21 0F 110
=
= (f ), effective total skin (L+1.1M),ff I (Lg + 1.1 Mg ) f i
3 dose factor (mrem /sec/pci/m ) from Appendix C '
Table C-4 3000 = Skin exposure limit of 3000 mrem / year
-8 3.17x10 = Inverse of humber of seconds per year in year /sec.
Step 3
_ i SelecttheloweroftheQvalues(kB #O) sbtained in Step 1 and j Step 2.
NOTE Actual alarm setpoint in the data-base may be modified to account for loop accuracy.
Step 4 MultiplythehvalueselectedinStep3by0.33. Bymultiplyingtheh f value by a factor of 0.33, the allowable operating setpoints will be administrative 1y controlled to allocate one-third (1/3) of the total allowable release rate to each of the release points. The resultant product will be the actual ODCM release rate HIGH ALARM setpoint for the appropriate WRGM Monitor.
'~
- 11. Particulate and Gas Monitor (P&G) (gas channel only).
Step 1 Perform Steps 1 through 3 of Section 3.3.2.2a.i above Step 2 Determine C, (the maximum acceptable total radioactivity concentration of all noble gases radionuclides for all release points in the gaseous effluent [uci/cc)):.
C , = (2:12 x 10'3)'O 3.3.2.2-5 l
I where: 2.12 x 10" = Unit conversion factor to convert uCi/sec/cfm to uCi/cc.
h = lower of the two h values, h #
s' TB F = The maximum acceptable effluent flow rate at the point of release based on design flow rates (cfm)
. RSP-0008 REV. 2 PAGE 22 0F 110
(
NOTE Actual alarm setpoint in the data-base may be modified to account for see;, accurug .
Step 3 Multiply the C, value determihed in Step 2 by 0.33. By multiplying the C, value by a factor of 0.33, the allowable' operating setpoints will be administrative 1y controlled to allocate one-thire (1/3) of the total allowable release to each of the release points. The resultant product will be the actual ODCM activity concentration HIGH ALARM setpoint for the appropriate P&G monitor gas channel.
- b. ALERT Setpoint Determination (Reference 1.2.12)
- 1. Wide Range Gas Monitor..(WRGM)
Step 1 ,
Determineh-A G utilizing one of the following methods:
G-A
= ( . 6 x IO N ( W O.8) 3.3.2.24 (X/Q) (M,ff)
OR NOTE The'M g methodologyfordeterminingh-A should G
be used only'if isctcpic analysas 1:, .:.._Mable and the relative abundances of noble gas nuclides in the effluent stream are not similar to those listed in Appendix D or not similar to the noble j gas isotopic mixture described in the previous i Semiannual F.ffluant Report. (Reference 1.2.19) -
I
-A
= (1.26 x 10~I) (5) 3.3.2.2-7 (X/Q) 1 Myfg i
Where:
- m8ximum 8CC*Ptable total release rate of all noble h-A G
gas radionuclides in the gaseous effluent [uci/sec]
l RSP-0008 REV. 2 FAGE 23 0F 110
(X/Q)
= The highest calculated annual average relative dispersion factor for any area at or beyond the unrestricted area boundary for all Sectors (sec/m ). Appendix F.
M,ff = Effective gamma air dose factor (mrad-m /uCi-sec).
See Appendix C, Table C-5 for applicable values.
5 = 5 mrads/ quarter (92 days) gamma air dose limit at the unrestricted area boundary.
Hg = The gamma air dose factor for radioactive noble 3
gas nuclide (i) in mrad-m /uCi-sec (Appendix C) f f
= The fractional abundance of noble gas radionuclides i
~
1.26 x 10 = Inverse of number of seconds per quarter in quarters /second 0.6 = Conservatism factor to account for changing isotopic inventory Step 2 Determine BQ -A utilizing ne f the following methods: 1 B-A
= ( . x O N (10) (0.8) 3.3.2.2-8 (X/Q) (N,ff) or NOTE
~
The Ng methodology for determining Q3 ,3 should be used only if isotopic analyses is available the relative abundances of noble gas nuclides in the affluent stream are not similar to those listed in Appendix D or the previous Semiannual Effluent Report. (Reference 1.2.19)
NB -A
=
H . 6 x IO N (10) 3.3.2.2-9 (X/Q) I (N g) (f f)
RSP-0008 REV. 2 PAGE 24 0F 110
Where:
h-A B
= maximum acceptable total release rate of all noble gas radionuclides in the gasecus effluents [uci/sec) i (X/Q) = The highest calculated annual average relative dispersion factor for an area at or beyond the unrestricted area boundary for all sectors (sec/m ) (Appendix F).
10 = 10 mrad / quarter (92 days) beta air dose limit .
at the unrestricted area BOUNDARY. I N,ff =
Effective beta air dose factor (mrad -
3 m /uCi-sec). See Appendix C, Table C-5 for applicable values.
c Ng = The air dose factor due to beta emissions from each noble gas radionuclides i.
f = The fractional abundance of noble gas radionuclides i.
1.26 x 10 = Inverse of number of seconds per quarter in quarters /second.
0.8 n Conservatism factor to account for changing isotopic inventory.
Step 3 Select the lower of the Q values obtained in Steps 1 and 2, eitherh,gg or h y,g. ,
Step 4 MultiplythehvalueselectedinStep3by0.33. Bymultiplyingtheh l value by this factor, the allowable operating setpoints will be administratively controlled to allocate one-third (1/3) of the total allowable release rate to each of the release points. The resultant product will be the actual ODCM ALERT setpoint to be entered into the applicable WRGM's RM-80.
RSN REY. 2 PAGE 25 OF 110 3
e Step 5 If the actual ODCM ALERT setpoint determined in Step 4 is less than two (2.0) times the detector background, it is permissible to enter t.n ALERT setpoint equal to two (2.0) times the normal (approximately 100*.
unit power) detector background to reduce the possibility of nuisance alarms. The twice background setpoint should provide sufficient indication that an offsite dose limit could possibly be exceeded.
ii. Particulate and Gas Monitor (P&G) (gas channel only)
Step 1 Perform Steps 1 through 3 of Section 3.3.2.2.b.i above.
Step 2 Determine C, (the maximum acceptable total radioactivity concentration of all noble gas radionuclides for all release points in gaseous effluent [uCi/cc)):
C,= (2.12 x 10~3) Q 3.3.2.2-10 F
~3 Where: 2.12 x 10 = Unit conversion factor to convert uCi/sec/
cfm to uCi/cc.
h = Lower of the two h values, hG-A #
B-A F = The maximum acceptable effluent flow rate at the point of release based on design flow rates (cfm).
Step 3 Multiply the C ,value determined in Step 2 by 0.33. By multiplying the C, value by this factor, the allowable operating setpoints will be administrative 1y controlled to allocate (1/3) of the total allowable release to each of the relt.-ase points. The resultant product will be the actual'0DCff activity concentration ALERT setpoint. This value is the setpoint to be entered into the applicable P&G monitor's RM-80.
Step 4 If the actual OLCM ALERT setpoint determined in Step 3 is less than two (2.0) times the gas detector background, it is permissible to anter an ALERT setpoint equal to two (2.0) times the normal (approximately 100% unit power) gas detector background to reduce the l possibility of nuisance alarms. The twice background setpoint should l
provide sufficient indication that e.n offsite dose limit could possibly be exceeded.
9 RSP M REY. 2 l _ _ _ - - _ - _ - - - - - - - -
PAGE 26 0F 110
4 , 4 3.4 Cumulative Dose Determination for Radioactive Gaseous Effluents 3.4.1 Noble Gases 3.4.1.1 Requirements
- a. Air Dose 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:
- 1. 'During any calendar quarter: less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation; and
- 11. 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.
- b. Total Body and Skin Dose (Reference 1.2.13)
- 1. Technical Specification 3.11.4 states that the annual
. (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from arenium fuel cycle sources, shall be limited to less than or equal to 25 mrems to the total body or any organ.
except the thyroid, which shall be limited to less than or equal to 75 mrems.
- 11. Technical Specification 6.9.1.8 (Semi-Annual Effluent Release Report)~ requires that an assessment of radiation doses to the likely most-exposed MEMBER OF THE ?UBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) be performed for the previous calendar year to show conformance with 40 CFR190, Environmental Radiation l
Protection Standards for Nuclear Power Operation.
l l Cummulative doses from liquid effluents and gaseous pathways (radiciodines (I-131, I-133), Tritium and particulate with T 1/2'> 8' days) are determined in accordance with Sections 2.4.2 and 3.4-2.5. Cummulative total body and skin doses from noble gas releases are determined in accordance with j Section 3.4.1.2b.
I 3.4.1.2 Methodology
- a. Air Dose This section provides the methodology to calculate the gamma and beta air doses to a maximum receptor ? cation at the site boundary from all noble gas radionuclides identified in the gaseous effluents.
RSP-0008 REV. 2 PAGE 27 0F 110 ,
)
i l
)
)
. j The method is based on the methodology suggested by sections 5.3 and 5.3.1 of NUREG-0133, Rev. 1, November, 1978. The dose factors for beta and gamma air dose are listed in Appendix C and are obtained from Table B-1 of RG 1.109, Revision 1, October 1977. !
The following equations provide for air dose calculations based on ~ ^
actual noble gss releases during a specific time interval for radioactive gaseous release sources at the site boundary:
n
" 3.4.1.2a-1 D (X/Q) (Qg )
Gamma-Air ("1) i=1 n
D Beta-Air
= I (Ng ) (X/Q) (Qg ) 3.4.1.2a-2 i=1 where:
D Gamma-Air
= The gamma air dose from radioactive noble gases in mrad.
Mg = The gamma air dose factor for radioactive noble gas 3
nuclide (i) in mrad-m /uCi-sec (Appendix C).
(X[Q) = The highest calculated annual average relative dispersion factor for an area at or beyond the unrestricted area boundary for all sectors (sec/m3 ) (Appendix F). ,
Qg = The number of uCi of nuclide (i) released during the period of interest.
D = Bau a d se fr a radioactive nome gases in mrad.
Beta-Air Ng = no W & dose factor for m active noble gas nuclider (1) in arrad-s3/nci-ree (Appendix C), Table C-1.
- b. Total Body and Sk'in Dose (Reference 1.2.13) L This section provides the methodology to calculate the total body and i skin doses to the likely most-exposed MEMBER OF THE PUBLIC from all noble gas radionuclides identified in the gaseous effluents.
The method is based on the methodology suggested in Section C.2 and Appendix B of RG 1.109, Revision 1, October, 1977. The dose transfer ,,
factors required for the calculations are listed in Appendix C of this e document and are obtained from Table B-1 of RG 1.109, Revision 1, October, 1977, l !
RSF-0005 REV. 2 Pr E 28 0F 110 I 1
y The following equations provide for total body and skin dose i calculations, based on actual noble gas releases during a specific time I
-interval for radioactive gaseous release sources at the site boundary:
n D
Total Body F ( i)( )(01) 3.4.1.2b.-1 i=1 D
Skin F (bi + 1'1"i)( )(01) 3.4.1.2L -2 i=1 Where:
D Total Body = The total body dose from radioactive noble gases in mrem.
Kg = The total whole body dose factor due to gamma emmissions from noble gas radionuclides (i) (mrem /sec per uCi/m ) from Appendix C, Table C-1. ,
(XTQ) = Ths highest calculated annual average relative dispersion factor for an area at or beyond the unrestricted area boundary for all sectors (sec/m ) (Appendix F).
NOTE For purposes of calculating D Total Body and D f r the Semiannual Radioactive Effluent Skin Release Report, X/Q values based on meteorological data for the actual considered time period should be used rather than historical (X/Q) values. If at all possible, these real time X/Q values should also be used when determining 40CFR190 compliance when Technical Specification limits have been exceeded by a factor of two (2.0).
Q g = The number of uCi of noble gas nuclide (i) released during the period of interest.
D = e sb dose from radioactive nome gases in mrem.
Skin Mg = The gamma air dose factor due to gamma emissions from each noble gas radionuclides (i) released.
RSP-0008 REV. 2 PAGE 29 0F 110 I l
L = The skin dose factor due to beta emissions from noble gas f
radio $uclide (1) (mrem /sec per uCi/m3 ) from Appendix C, Table C-1.
1.1 = Average ratio of tissue to air energy absorption coefficients.
l S
p = 0.7, attenuation factor accounting for shielding provided by residential structures for maximally exposed individual.
3.4.1.3 Simplified Approach A single effective gamma air dose factor (M,ff) and beta air dose factor (N,fg) have been derived, which are representative of the radionuclides abundances and corresponding dose contributions that are projected in the RBS FSAR. (See Appendix C for a detailed explanation aid evaluation of M,ff and N,ff). The values of M,ff and N,gf which have been derived from the projected radioactive noble gas effluents are:
Radwaste B'2ilding Exhaust Duct:
~
=
M,ff 8.07 x 10 mrad-m /uCi-sec
~
N,ff = 7,40 x 10 mrad-m /uCi-sec Main Plant Exhaust Duct and Fuel Building Exhaust Duct:
~
M,ff = 5.96 x 10 mrad-m /uCi-sec
~
3 N,ff = 8.99 x 10 mrad-m /uCi-sec NOTE The M,ff and N,ff factors should only be used if the actual effluent is similar to that described in Appendix D or similar to the noble gas isotopic mixture described in the previous Semiannual Effluant. Report. (Reference 1.2.19) 1 RSP-0008 REV. 2 PAGE 30 0F 110
The effective gamma air dose factor may be used in conjunction with 3 the total noble gas release ( I Qg ) to simplify the. dose evaluation and to verify that the cumulative gamma and beta air dose is within the equivalence of the limits of Technical Specification 3.11.2.2. To compensate for liny unexpected variability in the radionuclides g distribution, a conservatism factor of 0.8 is introduced into the .)
calculation. The simplified equation is:
J l
1 (M,ff) (X/Q) n D g ,,,,,gg, = I Qi 3 4 1 3-1 0.8 i=1 (N,ff) (X/Q) n D " * * * ~
Beta-Air i 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:
- a. During any calendar quarter: less than or equal to 7.5 mram to any organ; and,
- b. During any calendar year: less than or equal to 15 mrom to any organ.
M -QQ0A REY. 2 PAGE 31 0F 110
3.4.2.2 Methodology i The follow'ing calculational method is provided for determining the I critical organ dose due to releases of. radiciodines (I131, I133),
trituim and particulate. 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 t'., c age group.
The symbol (X/Q)D represents a depleted (X/Q) which is different from I
the noble gas (X/Q)'in that (X/Q)D. takes into account the loss of radiciodines (I-131, I-133), 8 day particulate, and tritium from the l plume as the semi-infinite cloud travels over a given distance. .The dispersion factor (D/Q) represents the rate of fallout from the cloud that affects a square meter of ground at various distances from the site. The total dose to an organ can then be determined.by summing the pathways that apply to the receptor in the sector. The equations are:
Inhalation Pathway:
n D =(. x 0 -8) I (Oi ) 3. .2.2-1 I&BDPt (Rit) ( !O)D i=1 Ground Plane Pathway:
n D (. x 0 -8) I ( !O) (01 ) ~
I&8DPt (Rit) '
i=1 Contaminated Forage / Cow / Milk Pathway:
n D
I&8DPt "(* * ) ( it) ( !O} (01) * * *
~
i=1 Total Dose:
n D = I D I&8DPt 3.4.2.2-4 z=1 IMPORTANT When calculating organ doses due to the release of C-14 and/or tritium (H-3), X/Q values (not D/Q values) must be used for cow milk, goat milk, meat and vegetation pathway calculations.
1 REP-0008 REV. 2 PAGE 32 0F 110
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1
+ .
where:
D I&BDPt
= Dose in mrem to the organ (t) of a specified age group from radiciodines (I-131, I-133), Tritiu= and 8 day particulate due to a particular pathway.
z = All the applicable pathways for the age group of interest.
D = Total dose in mrem to the organ (t) of a specified age group from gaseous radiciodine (I-131, I-133), tritium and particulate effluents, summed over all applicable pathways (z).
~
3.17 x 10 = The inverse of the number of seconds per year [in i years /sec]. i R = The dose factor for nuclide (i) for pathway (z) to f
organ (t) of the specified age group. The units are either:
~
3 mrem-m for pathways using (X/Q)D yr-uCi or 2
mrem-m -see for pathways using (D/Q) yr-uCi (See Appendix I.)
= The depleted (X/Q) value for a specific location where (X/Q)D the receptor is located. The units are (sec/m ].
(See Appendix F.) Note: No credit is taken for depletion and decay. (X/Q)D " ( IO)
(D/Q) = The. d? -4 tdem valus for a specific location where the receptor is located. The units are [m-2), (3,,
Appendix F.)
l l
RSP-0008 REV. 2 PAGE 33 0F 110 L ____- _ _ _
NOTE
~
For purpose of calculating D #*
- I&8DPt Semiannual Radioactive Effluent Release Report, X/QD and D/Q values based on meteorological data fer the actual considered time period should be used rather than historical (X/Q)D and .F'Q) values. If at all possible, real time A/QD and D/Q values should also be used when determining 40CFR190 compliance when Technical Specification limits have been exceeded by a factor of two (2.0).
=
Qg The number of microcuries of nuclide (i) released (or projected) during the dose calculation exposure period.
3.4.2.3 Limited Analysis Approach The contaminated forage / cow / milk pathway has been identified in 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 radioiodines (I-131, I-133), Tritium and particulate by only evaluating the infant's thyroid dose due to the release of radiciodines via the contaminated forage / cow / milk pathway.
The calculational method to be used includes a conservatism 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:
1 D= (3.17 x 10-8) (D/Q) I (Rg ) (Qf ) 3.4.2.3-1 0.8 radiciodinas 3.4.1.4 A=meh Sedaction Critaria.
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 (I-131, I-133), tritium and particulate.
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 (I-131, I-133), tritium and particulate measured in the gaseous effluents according to sampling and analyses required by the Technical Specifications.
t RSP-0008 REV. 2 PAGE 34 0F 110 l
t
l 3.4.2.5 Annual Dose Due to Radioiodines (I-131, I-133), tritium, and 8-Day Particulate I
Technical Specification 3.11.2.3 required the annual dose be l calculated at least once per 31 days for all pathways. The following formulae are used to calculate the annual dose for radiciodines, (I-131, I-133), tritium and 8- day particulate:
Inhalation Pathways:
- D I&8DPt
= ( .1 x 10 ) (Rit) (
)D (01) 3.4.2.5 1 i=1 Ground Plane Pathway:
D I&8DPt
= (3.1 x 10 ) (Rit) ( IO) (01 ) 3.4.2.5-2 i=1 Contaminated Forage / Cow / Milk Pathway:
n D
I&8DPt
= ( .17 x 10 ) I (Rit) ( ) (01 ) 3.4.2.5-3 i=1 9
Contaminated Forage / Goat / Milk Pathway:
n D = (3 ( ) (Qg ) 3.4.2.5-4 I&BDPt x 10 ) I (Rgt) i=1 Contaminated-Forage /Ffests:
D IE8DPt
= (3.17 x 10 ) (Rgt) ( ) (Qg ) 3.4.2.5-5 4
i=1 RSP-0008 REY. 2 PAGE 35 0F 110
4 .
Fresh Fruits and Vegetables:
n D
I&BDPt = (3.1 x 10 )
I (Rgt) (D/Q) (Qg ) 3.4.2.5-6 )
i=1 Total Dosa: .
n D = I DI&8DPt 3.4.2.5-7 ;
z=1 where:
I&8DPt = Dose rate to the organ (t )
for the age group of interest from j radiciodines (I-131, I-133), tritium and 8-day particulate f via the pathway of interest in mrem /yr.
For radiciodines (I-131, I-133), the entire source term was used to calculate these values.
z = All the applicable pathways for the age group of interest.
Q = The number of uCi of nuclide (i) released during the year of interest.
Rg = The dose factor for nuclide (1) for organ (t) for the pathway specified (units vary with pathway). For tritium, a site-specific absolute humidity (H) value 3
of 12.9 gm/m was used for calculation.
(See Appendix I.)
(D/Q) = A long-term relative deposition value for elevated and l
-2 ground level releases. A factor with units of e 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 dstermine annual average D/Q for the year of interest.
l l
RSP-0008 REV. 2 pag, y op gg 3
1 1
(X/Q)D A long-term depleted and 8-day decayed relative q concentration value for elevated and ground level j release. It describes the physical dispersion j characteristics of a semi-infinite cloud traveling i downwind. Since radioiodines (I-131, I-133), and particulate settle out (fallout of the cloud) on the ground, the (X/Q)D represents what physically remains of the c,'oud 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 f r the year of interest. Total body and organ doses will be calculated for pathway and age group on an annual basis using the above-describoo methodology 3
(sec/m ).
IMPORTANT When calculating organ doses due to the release of C-14 and/or tritium (H-3), (X/Q) values (not D/Q values) must be used for cow milk, goat milk, l meat and vegetation pathway calculations.
NOTE For purposes of calculating DR I&8DPt f r the Semiannual Radioactive Effluent Release Report, X/0 3and D/Q values based on meteorological data for the actual consid-ered time period should be used rather than If at historical (X/Q)D and (D/Q) values.
all possible, real time X/Q and D/Q D
values sherld also be used when determining 40CFR190 compliance when Technical Specifi-cation limits have been exceeded by a factor of two (2.0).
-8 3.1'1 x 10 = The inverse of the number of seconds per year (in year /sec).
Meteorological data (X/Q, X/Q , D/Q) will be detershed from actual D
meteorological data and sector wind frequency distributions for the j year of interest. Release rate' (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.
RSP-0008 REV. 2 PAGE 37 0F 110
3.5 Dose Projectian - Determination of Need to Operate Ventilation Exhaust Treatment System
- 3.5.1 Requirement Technical Specification 3.11.2.5 requires that the ventilation exhaust treatment system be used to reduce radioactive material in waste prior to discharge when the projected dose due to gaseous effluents (radioiodines (I-131, I-133), particulate T 1/2 > 8 days and H-3) would exceed 0.3 mrem to any organ in a 31 day period. f l NOTE The ventilation exhaust treatment system does not reduce the noble gas concentration in plant effluents (See Definition 1.3.5).
3.5.2 Methodology The following calculation method is provided for determining the projected doses:
- l. t PD =
- 31 3.5.2-1 b i where:
G PD
- # d*"** "* ** ' ' '"** ( ' '
~
)'
particulate with T1/2 > 8 days and H-3 during the current 31 day period (mrem). I X
D
= The number of days to date in the current quarter D = Cumulative total dose due to radiciodines (I-131, I-133), particulate with T 1/2 > 8 days and H-3 during the current quarter (mrem).
A dose pro}ection wou.1d ha based on the latest results of tha j monthly calculations of the dose due to radiolodines (I-131, I-133), j particulate with 7 1/2 > 8 days, and H-3 (Section 3.4.2.5). The '
value may~need to be adjusted to account for any changes in operating conditions that could significantly alter the actual releases, such as i failed fuel, or changes in ventilation flow rate. -l 1
l l
9 RSP-0008 RE7. 2 PAGE 38 0F 110 m . _ _ _ _ _ _ _ _ . ._ _ . _ _ . _ . m__m. _ - . _ _ :
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 potential contamination of the Upland Terrace Aquifer so that any such contamination would be detected before migrating beyond RBS site boundaries.
1 n
l RSP-0008 REV. 2 PAGE 39 0F 110 1
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l 5.0 40CFR190 CONSIDERATIONS '
~
5.1 Comp 1'iance with 40C/R190
. 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.
5.7 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 removinr, 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.
5.2.3 Environmental sampling data which demonstrate that no pathway exists may be used to delete a pathway to man from a calculation.
5.2.4 To sum numbers represented es "less than" (<) , use the value of the largest number in the group, e.g., <5 + <1+ <1 + <3 = 5 5.2.5 When doses via direct radiation are added to doses via inhalation pathway, they will be calculated for the same distance in the same sector.
5.2.6 The calculational locations for a Member of the Public will only be at residencee or places of employment.
5.2.7 If'at all possible; I/Q, I/Q , and D/Q values based on D
meterological data 'for the actual considered time .,eriod should be used in determining compliance with 40CFR190.
Note: Additional assumptions may be used to provide situation specific parameters, provided they are documented along with their concomitant bases.
i RSP-0008 REV. 2 PAGE 49 0F 110 1
1 l
l 5.3 Calculations of Total Body Dose
~
Estimates wil1 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 (from storage tanks, N-26 sources, etc.)
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 Ingestion Pathway (cow milk, goat milk, meat, vegetation)
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 Total Body Noble Gas Immersion Dose l
This dose will be calculated in accordance with Section 3.4.1.2b. for the maximally exposed MEMBER OF THE PUBLIC in the limiting sector.
5.3.5 Ground Plane Deposition 5.3.6 Other Uranium Fuel Cycle Sources The dose from other fuel sources will be treated as < 1 mrem /yr.
5.4 Thyroid Dose l
The dose to the thyroid will be calculated for the limiting sector as the sum of:
l 5.4.1 Direct Radiation (from storage tanks, N-16 sources, etc.)
The component of done to the thyroid due to direct radiation will be determined:by thermaluminescent dosimeters (TLDs).
5.4.2 Inhalation Dose The inhalation dose to the thyroid 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.
1 RSP-0008 REV. 2 PAGE 50 0F 110 l
5.4.3 Ingestion Pathway (cow milk, goat milk, meat, vegetation)
The dose to the thyroid 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.
l 5.4.4 Noble Gas Immersion Dose It is assumed that an external total body dose from noble gases irradiates internal body organs at the same numerical rate (Reference 1.2.11). This dose for the thyroid will therefore be equal to the-dose calculated in Step 5.3.4 above.
l 5.4.5 Ground Plane Deposition l
5.4.6 Other Uranium Fuel Cycle Sources The dose from other fuel cycle sources will be treated as < 1 mrem /yr.
5.5 Organ Dose (other than thyroid and skin)
The dose to any organ will be calculated for the limiting sector as the sum of:
5.5.1 Direct Radiation (from storage tanks, N-16 sources, etc.)
The component of dose to an organ due to direct radiation will be determined by thermoluminescent dosimeters (TLDs).
5.5.2 Inhalation Dose The inhalation dose to an organ 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.
5.5.3 Ingestion Pathway (cow milk, goat milk, meat, vegetation)
The dose to an organ 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 done via this pathway will be treated as < 1 mreu/yr.
5.5.4 Noble Gas Immersion Dose It is assumed that an external total body dose from noble gases irradiates internal body organs at the same numerical rate (Reference 1.2.11). This dose for an organ will therefore be equal to the dose calculated in Step 5.3.4 above.
5.5.5 Ground Plane Deposition 5.5.6 Other Uranium Fuel Cycle Sources RSP-0006 REV. 2 PAGE 51 0F 110
l l * .
The dose from sther fuel cycle sources will be treated as < 1 mrem /yr.
5.6 Skin Dose 1 The dose to the skin will be calculated for the limiting sector as the sum of:
5.6.1 Direct Radiation (from storage tanks, N-16 sources, etc.)
The compenent of dose to the skin due to direct radiation will be determined by thermoluminescent dosimeters (TLDs).
5.6.2 Inhalation Dose The inhalation dose to the skin (only tritium is considered) 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.
5.6.3 Ingestion Pathway (cow milk, goat milk, meat, vegetation)
The dose to the skin via the ingestion pathway (only tritium and C-14 considered) 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.
5.6.4 Skin Noble Gas Immersion Dose This dose will be calculated in accordance with Section 3.4.1.2b for the maximally exposed MEMBER OF THE PUBLIC in the limiting sector (s).
5.6.5 Ground Plane Deposition L 5.6.6 Orher Uranium Fuel Cycle Sources This dose from other fuel cycle sources will be treated as < 1 mrem /yr.
6.0 I!CIRIABORATORY 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 Progras RSP-0008 REV. 2 PAGE 52 0F 110
j 6.2.1 Environmental Sample Analyses Comparison Program l
~
Environmental samples from the River Bend Station are to be analyzed by the River Bend Station Environmental Services Group or by a qualified contracting laboratory. These laboratories will participate 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-radionhclide 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 analises for gamma-emitting radionuclides in effluent releases. The radiochemistry laboratory will participate annually in a corporate interlaboratory comparison study or an equivalent study. The re.sults 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 reducr> anomalous errors. Complete documentation on the evaluation will be available to RBS Environmental Services Group and will be provided to the NRC upon request.
ESP-0008 REV. 2 PAGE 53 0'i 110 ,
k
G
'G ,
t ' s APPENDIX A
. _ LIQUID MPC VALUES RSP4008 REV. 2 PAGE 54 0F 110 l
>- .; +
t 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 l 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 l Sr-89 3 E-6 Te-127m 5 E-5 Ce-144 1 E-5 i 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 radionuclides 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 />."
l RSP-0008 REV. 2 PAGE 55 0F 110 I
l * ' '
APPENDIX B i
l LIQUID ENVIRONMENTAL DOSE TRANSFER FACTORS A
Lt I
l l
l l
l RSP-0008 REV. 2 PAGE 56 OF 110
TABLE B-1
~
LIQUID EFFLUENT DOSE PARAMETERS (Page 1)
A g
, mrem /hr per uCi/ml Radionuclides Total Body Critical Organ Na-24 6.13E02 6.13E02 P-32 1.87E06 4.84E07 Cr-51 4.31 1.08E03 Mn-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
$r-89 1.20E03 4.19E04 Sr-90 2.50E05 1.03E06 Sr-91 3.01E01 3.68E03 Sr-92 1.30E01 5.80E03 Y-91 2.37 4.89E04 Y-92 1.56E-02 9.32E03 Y-93 4.66E-02 5.35E04 Zr-95 7.74E-02 3.62E02 Zr-97 1.82E-03 1.23E03 Nb-95 1.34E02 1.51E06 Mo-99 6.84 2.96E02 Tc-99m 3.45E-01 1.60E01 l Tc-101 1.39E-01 2.55E-01 l
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-129Mm 6.08E03 2.57E05 Te-131N- 3.13E03 3.73E05 i Te-132- 6.80E03 3.42E05 l Ba-139- 3.51E-01 2.13E01 Ba-140 1.64E02 5.17E03 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 Ce-143 7.73E-02 2.61E04 i
Ce-144 1.50E01 9.44E04 ,1
.1 RSF-0008 REV. 2 PAGE 57 0F 110
_ _ - - - _ _ - _ - --- - _ _ 1
TABLE B-1 LIQUID ETFLUEhT DOSE PARAMETERS (Page 2)
Radionuclides 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 1-131 1.57E02 8.96E04 I-132 8.75 8.75E02 I-133 3.49E01 1.68E04 I-134 4.74 2.30E02 I-135 1.97E01 3.52E03 Rb-09 1.51E02 2.15E02 Cs-134 6.49E05 7.94E05 Cs-136 9.93E04 1.38E05 Cs-137 3.83E05 5.85E05 Cs-138 2.90E02 5.85E02 H-3 2.80E-01 2.88E-01 l
l l
RSP-0008 REV. 2 PAGE 58 QF 110
1 . .
~ TABLE B-2 CALCULATIONAL ASSUlfPTIONS FOR A it
=
A g 1.14 x 10-5 (Uw/Dw + U FBF g + U7BIf)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 l Environmental Report page 5.4-5) j U
F
= 21 kg/yr adnit fish consumption (Reg. Guide 1.109 Table E-5)
BF g =- bioaccumulation factor for nuclide i in fish (pci/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"'
Ug ~. = 5 kg/,r adult invertebrate consumption (Reg. Guide 1.109 Table E-5)
- BIy- = ' bioaccumulation factor for nuclide i in invertebrates (pCi/kg per pCi/t)
Reg. Guide 1.109 Table A-1 DF g = dose conversion factor for nuclide i for adults in pre-selected-organ t (mrem /pC1).
Reg. Guide 1.109, Table E-11.
RSP-0008 REV. 2 PAGE 59 QF 110 f'
0 0
e ,
. APPENDIX C KgL AIR g DOSE M SFER FACTORS RSP-0005 REV. 2 PAGE 60 0F 110 l
TABLE C-1 DOSEhRANSFERFACTORSFOREXPOSURETOASEMI-INFINITE CLOUD OF RADI0 ACTIVE NOBLE GASES D0SE TRANSFER FACTORS Gamma Beta Beta and Gamma Kg Lg (L+1.1M)g 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 Xe-137 4.5E-5 3.9E-4 4.4E-4 Xe-138 2.8E-4 1.3E-4 4.5E-4 Ar-41 2.8E-4 8.5E-5 4.0E-4 AIR DOSE TRANSFER FACTORS Gamma Beta i "i 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 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 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 Ref. Regulatory Guide 1.109, Revision 1, Table B-1.
l RSP-0008 REV. 2 PAGE 61 0F 110
l l
TABLE C-2 TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclides specific.
These effective factors, which are based on the typical radionuclides 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, f, (L + 1.1M),f7, M,ff, or 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.
Use of effective dose factors should only be used if isotopic analyses are not available (i.e., prior to initial criticality), if the relative abundances of the noble gas isotopic mixture are similar to those listed in Appendix D or if the relative abundances of the noble gas isotopic mixture are similar to those listed in the previous Seminannual Radioactive Effluent Release Report. (Reference 1.2.19)
Determination of Effective Dose Factors The effective dose transfer factors should be based on past operating data. The radioactive offluent distribution for the past years can be used to derive single effective factors by the following equations:
EQUATION C-1 K,ff = K g
. f f
i where:
K,ff = The effective total body dose factor due to gamma emissions from all noble gases released.
1 K
f
= The total body dose factor due to gamma emissions from l each noble gas radionuclides "i" released.
f g
= The fractional abundance of noble gas radionuclides "i" of the total noble gas radionuclides.
RSP-0008 REV. 2 PAGE 62 0F 110
TABLE C-2 TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS (Continued)
EQUATION C-2 (L + 1.1 M) ,ff =
{(Lg+1.1M). g fg i
where:
(',+ 1.1. M),ff = The effective skin dose factor due to beta and gamma emissions from all ncble gases released.
(Lg + 1.1 Mg ) = The skin dose factor due to beta and gamma emissions from each noble gas radionuclides "i" released.
EQUATION C-3 M,ff =}"M g ,
. E g
i where:
M,ff = The effectiva air dose factor due to gamma emissions from all noble gases released.
Mg = The air dose factor due to gamma emissions from each noble gas radionuclides "i" released.
EQUATION C-4 N,ff = )[ N g . f g
i where N,ff = The effectiva air dose factor due to beta emissions from all noble gases relaased.
Ng = The air dose factor due to beta emissions from each noble gas radionuclides "i".
To provide an additional degree of conservatism, a factor of 0.8 is introduced into the dose calculation process when 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.
RSP-0008 REV. 2 PAGE 63 0F 110
C- ,
TABLE C-3 l
' EFFECTIVE DOSE FACTORS FOR NOBLE GASES TOTAL BODY EFFECTIVE DOSE - K eff i
Main Plant Radwaste Building l Exhaust Duct
- Exhaust Duct {
3 3 I Year K,ff (mrem-m /uCi-sec) K,ff (mrem-m /uci-sec) q l
l Projected ** 5.56E (-5)*** 8.05E (-5) l
- Main Plant exhaust duct contains contributions from Fuel j Building. j i
1
- -5 5.56E (-5) = 5.56 x 10 l
o a
l N
ll O
RSP-0008 REV. 2 PAGE 64 0F 110
TABLE C-4
~
l l
EFFECTIVE DOSE FACTORS FOR NOBLE GASES SKIN EFFECTIVE DOSE (L + 1.1 M),ff I-fain Plant Radwaste Building Exhaust Duct
- Exhaust Duct Year (L+1.1M),gf (mrem-m /uCi-sec) (L+1.1M),ff (mrem-m /uCi-sec)
Projected ** 1.36E (-4) 1.59E (-4)
Main Plant exhaust duct contains contributions from Fuel Building.
i h
Il a
I e
1 RSP-0008 REY. 2 PAGE 65 0F 110 l
TABLE C-5
~~
EFFECTIVE DOSE FACTORS FOR NOBLE GASES AIR DOSES M,ff and N,gf Main Plant Radwaste Building Exhaust Duct
- Exhaust Duct 3 3 (mrad-m /uCi-sec) (mrad-m /uci-sec)
Gamma Air Beta Air Gamma Air Beta Air "eff "eff eff "eff Projected ** 5.96E(-5) 8.99E(-5) 8.07E (-5) 7.40E (-5)
- Main Plant exhaust duct contains contributions from Fuel Building.
1 1
1 L
l l
'l RSP-0008 REY. 2 PAGE 66 0F 110 )
r___-__
l APPENDIX D EXPECTED GASEOUS RADIONUCLIDES MIXTURE l
I l
1 l
l l
l l
a 1
1
)
l l
RSP-0008 REV. 2 PAGE 67 0F 110
~ EXPECTED REIZASE OF RADIOACTIVE' NOBLE GASES
.IN GASEOUS EFFLUENTS FROM RIt"R BEND STATION'FSAR*
Containment Building ** Radwaste Building Nuclide .Ci/yr Fraction Ci/yr Fraction Kr-83m 4.7E (-2) 1.07E (-5) <1 ---
Kr-85m 218 0.050 <1 ---
Kr-85 210 0.048 <1 ---
Kr-87 14.2 0.003 <1 ---
Kr-88 47.2 0.011 <1 ---
Kr-89 118 0.027' 29 .03 Xe-131m 21- 0.005 <1 ---
Xe-133m 6.6E (-2) 1.504E (-5) < 1. ---
Xe-133 2,340 0.533 220 .19 Xe-135 693 0.158 280 .24 Xe-135m 140 0.032 530 .46 Xe-137 380 0.087 83 .07 Xe-138 208 0.047 2- 1.75E (-3) 4,389. 1.0000 1,144 .99
- Containment Building contains releases from Fuel Building i
l 1
F g.
1 i
RSP-0008 REV. 2 PAGE 68 0F 110
k l l l
l APPENDIX E X/Q AND D/Q VALUES FOR RESTRICTED AREA BOUNDARY i
t I'l i
RSP-0008 REV. 2 PAGE 69 0F 110
r-------------~---~~-------
- - - - - ~ - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - , - - - - - ~ ~ -
-- - --- o l
.: . I Long Term Diffusion Estimates l
E.1 Obj ectiire~
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 receptor locations used to determine the maximum individual and popu-lation dose receptors. ,
l The methodology described in Regulatory Guido 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. 1 E.2 Calculation Techniques Nomenclature
~
2.032 =
(2/v)1/2 (27/16) 1 (dimensionless) w = 3.14159...
(dimensionless) exp . = 2.71828... (dimensionless)
=
E T
Entrainment coefficient (dimensionless) ,
Q = Terrain recirculation factor T
(dimensionless) t x = Downwind receptor distance (m) og = Vertical dispersion (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
= 150-ft average wind speed corresponding to a given hour of onsite meteoro-logical data (m sec~1)
(CHI /Q) = Average concentration normalized by source strength (see m-3)
\
RSP-0008 REV. 2 PAGE 70 0F 110 '
l I
_ _ - - - - - _ - - - - - - - - - - - - - - _ -- - - _ - - -- - 1
(CHI /QD ) = Depleted CHI /Q (see m'3)
Fg- = Momentum flux (m sec )
h = Maximum adjacent b
building height (m) h r
= Release height (m) h = Effective release height (m) h p
= Nonbuoyant plume rise (m) h t
= Topographic height of '
receptor above plant grade (m) d = Stack or vent diameter (m) u, = Efflux velocity (m sec'1)
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 streng'th (m'1)
D/Q = Relative deposition per unit area normalized by source strength (m-2)
G = Ground release (subscript) (dimensionless) i = Index for atmospheric stability group (Classes A through G) (dimensionless) j = Index for. number of hours (dimensionless) k ==- Inder for a particular receptor' distance (dimensionless) i t = Index*for a particular 22.5-des sector (dimensionless) n = Number of hours onsite wind data in a.particular 22.5-deg sector (dimensionless)
~
S = Stability parameter (sec )
. 1 RSP-0008 REV. 2 PAGE 71 0F 110 1
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:
9.1
. 2.211 )
,b.-% 's E.3-1
... [ g.
,,(. ., j'e. .,;. p s,...,,,
Since the River Bend Station site is located in relatively open terrain, the terrain recirculation factor (0)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 (u,) to elevated wind speed (u150) I # * *" *' "" Y elevated release points.
For vent releases occuring below the level of a nearby structure, 100 '
percent downwash (total entrainment) is conservatively assumed (ET
- 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:
E =
0.0 when u,/E 150 5.0 (totally elevated)
T
=
E T 0.30-0.06 (u,/E150) when 1.5 < u,/u15 0 $ S.0 (partially entrained)
=-
E T 2.58-1.58 (u,/u150) when 1.0 < u,/u150 $ 1.5 (partially entrained)
E T
=
1.0 when u,/u150 5 1.0 (totally entrained)
L i .
RSP-0008 REV. 2 PAGE 72 0F 110 l l
4
Within 5 km in each downwind sector, Equation E.3-1 was evaluated by sector at the, property and restricted area boundaries and nearest resident, vegetable garden, milk cow, and meat animal. There were no 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 kas computed from the following equation:
h, =
h, - (h t)k + hp , E.3-2 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.3-4).
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:
> 1.5 "e 150 u, 2/3 x 1/3 h = 1.44 d E.3-3 pr 150 4
. RSP-0008 REV. 2 PAGE 73 0F 110 0
\
V when:
< 1.5, u,/u150 u 2/3 x 1/3 u -
h = 1.44 (d-3) 1.5- d E.3-4 {
pr d u 150 150
- ~
ed h
pr 5 3 d E.3-5
(_ ;
\ "150 l The result from Equation E.3-3 or E.3-4 (whichever condition exists) is then compared to Equation E.3-5 and the smaller value of h is pr used., !
For E-G stability conditions, Equations E.3-3, E.3-4, and E.3-5 are compared with:
f \$
h pr
=4! Fm /s and, h = 1.5' Fm/ 150 l 1/3S - 1/6 l
pr where: N Y d*
y ,
4 and the smallest value was chosen.
l RSP-0008 REY. 2 PAGF. 74 0F 110 E1-______-----_
8-. .
In the ground level portion of Equation E.3-1, the vertical dispersion term: ,
- 2 z + 0.Sh b I
i,k was constrained to be less than or equal to 1.732o ik 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 ere a, n credit was concentration values (CHI /Q = (CHI /Q)D).
taken for attendant plume depletion of radiciodines and particulate.
Annual average relative deposition values were calculated using Regulatory Guide 1.111, Rev. 1 with the following equation:
~
ng P '- --
3
, 3 b '
k k C.,
T* 1 if '
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
""1"**
(6/Q)G 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 through the containment building vent from the mechanical vacuum pump was evaluated.
RSP-0008 REV. 2 PAGE 75 0F 110
4 TABLE E-1
~
ANNUAL AVERAGE CHI /Q VALUES x 10 (sec/m )
FOR RESTRICTED AREA BOUNDARY Main Plant Exhaust Radwaste Building Sector Duct (Continuous) Exhaust Duet (Continuous)
S 11.4 105 SSW 19.7 186 SW 16.4 215 VSW 19.5 '
326 W 23.6 654 WhV 33.1 421 hv 15.7 262 NhV 14.8 138 N 18.8 180 NNE 24.9 211 NE 16.6 150 ENE 12.2 146 E 9.07 168 ESE 10.4 154 SE 8.19 93.1 SSE 7.69 45.6 l
RSP-0008 REV. 2 PAGE 76 0F 110 i
l L_-- -- . - - - - - - - - - - - - _ _ - - - - - _ _ - - - - - - - - - _ - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - "
TABLE E-2
~ ANNUAL AVERAGE D/Q VALUES x 10 (m' )
FOR RESTRICTED AREA BOUNDARY Main Plant Exhaust Radwaste Building Sector Duct (Continuous) Exhaust Duct (Continuous)
S 7.61 21.4 SSW 11.3 39.6 SW 10.4 36.1 WSW 9.79 38.5 W 13.8 68.8 WhV 18.0 50.3 hv 8.68 40.8 Nhv 10.5 24.7 N 11.8 28.6 NNE 11.2 27.1 NE 8.26 22.3 ENE 9.73 22.7 E 7.75 23.0 ESE 7.76 24.6 SE 6.60 17.2 SSE 5.34 11.8 RSP-0008 REV. 2 PAGE 77 0F 110
APPENDIX F 1
MAXIdW X/Q AND D/Q VALUES FOR INDIVIDUAL LOCATIONS RSP-0008 REV. 2 PAGE 78 0F 110
S 0 N 1 9 3 11 1 O t . 5 02 .. 1 I
c 3 3 5 72 38 T tu 3 1 8 31 F A nD 7 O L a - - - - - .
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APPENDIX G
_ INSTANTANEOUS DOSE TRANSFER FACTOR TABLES 4
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RSP-0008 REV. 2 PAGE 80 0F 110 I
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l APPENDIX H l i
~
GASEOUS MPC VALUES n
RSP-0008 REV. 2 PAGE 82 0F 110
TABLE H-1 MAXIMUM PERMISSIBLE CONCENTRATIONS IN AIR IN UNRESTRICTED AREAS MPC MPC Nuclide* (uCi/cc) Nuclide* (uC1/cc)
Ar-41 4 E-8 Y-91 1 E-9 Kr-83m 3 E-6' Zr-95 1 E-9 Kr-85m i 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 3E^ 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 radionuclides 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 />."
l RSP-0008 REV. 2 PAGE. 83 0F 110
L.
I' APPENDIX I ENVIRONMENTAL DOSE TRANSFER FACTORS FOR GASE0'US EFFLUENTS RSP-0008 REV. 2 PAGE 84 0F 110
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" l l 1 I9 l l l ATTACHMENT - 1 l ODCM/ PROCEDURE REVISION SHEET NO, l 1 I I
- I I !
l l DESCRIBE THE INFORMATION TO BE CHANGED INCLUDE THE RATIONALE FOR AND A COMPLETE l l
l DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: l I I I I ;
I I l l l l 1 I i i l l I I I i i I I I I I I I I I I I I I 1 I I f I l l
l I l l l I I I I I I
, I I l COMMENTS: I I I I l l 1 I I I I I I I WILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DOSE CALCULATIONS OR l l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.14)7 YES N0 l I I I WILL THIS CHANGE REQUIRED REVISION TO LOWER TIER IMPLEMENTING PROCEDLTES OR l l COMPUTER PROGRAMS. YES N0 I l l l THESE CHANGES HAVE BEEN REVIEWED AND FOUND ACCEPTABLE, PURSUANT TO TECHNICAL l l SPECIFICATION 6.5.2. I I I I REVIEWED, RADIOLOGICAL ENGINEERING SUPERVISOR: / I l DATE l l l l REVIEWED, DIRECTOR - RADIOLOGICAL PROGRAMS: / I l DATE l l l l l l 1 11 1 I I l ATTACHMENT I PAGE 1 ll l l l l 1 l OF 1 l1 RSP-0008 l REV - 2 l PAGE 110 0F 110 l l 1 1 II I I I
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