RBG-25841, Rev 0 to Procedure RSP-0008, River Bend Station,Offsite Dose Calculation Manual

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Rev 0 to Procedure RSP-0008, River Bend Station,Offsite Dose Calculation Manual
ML20210C372
Person / Time
Site: River Bend Entergy icon.png
Issue date: 04/30/1987
From: Booker J
GULF STATES UTILITIES CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RBG-25841, RSP-0008, RSP-8, NUDOCS 8705060172
Download: ML20210C372 (114)


Text

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RIVER SEND ST*ATION

' APPROVAL SHEET STATION OPERATING PROCEDURES NO. RSP-0008 _ TITLE OFFSITE DOSE' CALCUI.ATION MANUAL (ODCM)

PROCEDURE SAFETT RELATED YES 13 NOl((

QA APPLICABIZ YES l[4 NOl[l l REY. I PAGES INDEP. I I l NO. I ISSUED REVIEW I APPROVED BY I

I EFFECT l 1 i SIGNATURE /DATE I SIGNATURE /DATE I

I DATE I I I I I I I I I I O 1 Thru 112 ff 07/11/86 I I I I I I l -

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o RIVER BEND STATION GULF STATES UTILITIES OFFSITE DOSE CALCULATION MANUAL (ODCM)

REVISION 0 l

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Table of Centents ,

Section Py 1.0 Introduction.............................................. 4 1.1 Purpose .................................................. 4 1.2 References ............................................... 4 1.3 Definitions .............................................. 5 1.4 Required Equipment ....................................... 6 1.5 Precautions and Limitations .............................. 6 1.6 Prerequisites ............................................ 6 2.0 Liquid Effluent Methodology............................... 6

, 2.1 River Bend Station Site Description....................... 6 2.2 Compliance with 10CFR20 (Liquids)......................... 7 2.3 Determination of Setpoints for Radioactive Liquid Effluent Monitors....................................... 8 2.4 Determining the Dose for Radioactive Liquid Effluents..... 11 2.5 Projecting Dose for Radioactive Liquid Effluents.......... 13 3.0 Gaseous Effluent Methodology.............................. 14 3.1 Introduction.............................................. 14 3.2 Data Requirements for Gaseous Effluents.................... 14 3.3 Instantaneous Release Rate and Setpoint Determination. . . . . 14 3.4 Cumulative Dose Determination for Radioactive Gaseous Effluents...............................................29 3.5 Dose Projection - Determination of Need to Operate Ventilation Exhaust Treatment System.................... 41 l

l 4.C Radiological Environmental Monitoring Program.... ......... 42 l

I 5.0 40CFR190 Considerations................................... 52 5.1 Compliance with 40CFR190.................................. 52 5.2 Calculations Evaluating Conformance with 40CFR190......... 52 5.3 Calculations for Total Body Dese.......................... 53 5.4 Thyroid Dose........... ............................ 53 5.5 Organ Dose.............. 1 54 5.6 Skin Dose............... ............................ 55 6.0 Interlaboratory Comparison Studies........................ 55 6.1 Requirement............ . .............. ............ 55 6.2 Program............... . ................. ......... 55

. _ _ . _ _ _ . . _ . . . _ ,____m_ _ _ _ . _ _ _ - _ _ - - _ - , , - , - . . . . .-

e e Aependices , PAGE A Liquid MPC Values .- 57 B Liquid Environmental Dose Transfer Factors A g 39 0 KgL gAir Dose Transfer Factors 63 D Expected Gaseous Radionuclide Mixture 70 E X/Q and Dfg Values for Restricted 4rea Boundary 72 F Maximum X/Q and D/Q for Individual Locations 81 G Instantaneous Dose Transfer Factor Tables 83 H Gaseous MPC Values 85 I

Environmental Dose Transfer Factors for Gaseous Effluents 87 Fizures 1 Restricted Area and Near-Field Environmental Monitoring Locations . 107 2 Schematic of Liquid Radwaste Systes 108 3 Effluent Release Points 109 .

4 Schematic of Gaseous Radwaste System 110 5 Far-Field Radiological Environmental Monitoring Locations 111 Attachments .

1 ODCM/ Procedure Revision Log 112 t

I 8

1.0 INTRODUCTION

1.1 PCRPOSE .

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 fcr 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 1.109, Rev. 1, dated October 1977). Alternate calculational methods may be used from those I

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.

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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.

1.2.6 River Bend Station FSAR 1.2.7 River Bend Technical Specifications; Section 3/4.11.

1.2.8 River Bend Environment.il Report, CPS.

~ _ _.

. o a 1.2.9 U.S. Code Of Federal Regulations, ICCFR50.

1.2.10 U.S. Code of Federal Regulations, 40CFR190.

1.2.11 NURIG 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 Band 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 h

1.3.1 MEMBER (s) 0F THE PUBLIC -

MEMBER (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 aho 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 0FFSITE DOSE CALCULATION MANUAL -

l

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l The OFFSITE DOSE CALCULATION MANU.AL shall contain the methodo1ogy 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 a s:s :rtp setpoints,. It shall also contain a table and figure de:...ng current radiological environmental monitoring sample locations.

1.3.3 SITE BOUNDARY -

The SITE BOUNDARY shall be tb.2: .ne beyond which the land is not owned, leased, or otherwise ::r ::i;ed by the licensee.

i

A e 1.3.4 UNRESTRICTED AREA -

An UNRESTRICTED ARIA shall be any area at or beyond t!e 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 TREAT?fE.VT 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 particulates from the gaseous exhaust streas prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (EST) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

1.4 REQUIPED EQUIPMENT 1.4.1 None 1.5 PRECAUTIONS AND LIMITATIONS 1.5.1 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 Log and made in accordance with Reference 1.2.16.

1.6 PREREQUISITES 1.6.1 None '

2.0 LIQUID EFFLUENT METHODOLOGY

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2.1 River Bend Site Description 1

1 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:

. e The River Bend Station (RBS) is on a site in West Feliciana Parish, Louisiana, located approximately 24 miles north-n'o rthwest of Baton Rouge, Louisiana. This site is just east of the Mississippi River which is used as the source et the RBS major water requirements and which receives the RBS liquid effluents.

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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 Cemeliance with 10CFR20 (Liouids) .. .

2.2.1 Requiremerfs 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/mi 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 j J

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 l 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 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 accordande with Table 4.11.1.1-1 of the RBS Technical Specifications. Compliance witn 10CFR20 limits will be determined with the following equation: -

f Cg 2.2.2.1-1 -

Fg =

fg+f2 i=1 (MPC) .

s .

where:

  • Fg = The fraction of 10CFR20 MPC limits resulting from

- the release source being discharged

=

f l ne undiluted release rate of the release source ,

at the monitor location, in spe *

=

f 2 The cooling tower blowdown release rate,*in sps Cg =

Theundilutedconcentrationofnuclide;-(i),fh uC1/a1 from sample assay.

=

(MPC)g Maximus Permissible Concentration of nuclide (i) from Appendix A, in uCi/a1 as long as F,is g less than 1.0, the concentration of the tank is within compliance with 10CTR20 limits.

2.2.2.2 Simplified Approach For purposes of simplifying the calculations, the value of 3 x 10~8 ~

uCi/s1 (unidentified 10CFR20 MPC value) could be substituted for (MPC)g and the cumulative concentration ( C-Total = sua of all identified radionuclide concentrations) or the gross beta-gamma concentration should be substituted for C g

. As long as the diluted

~

8 concentration [(C-Total x gf /fg + f2)] is less than 3 x 10 uCi/m1, the nuclide by nuclide calculation is not required to demonstrate compliance with 10CFR20 MPC limits.

j 2.3 Determination of Setpoints for Radioactive Liquid Effluent Monitors

! 2.3.1 Requirements l

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 Technt:a1 Specification 3.11.1.1 are not

, exceeded. he high alars/tr:p se: points shall be determined and l

adjusted by the methodology w5.t:n follows.

, n e high alarm setpoint for  :.".e .tquid effluent radiatio.n monitor _.is l

' derived from the concentratten .iste provided in 10CFR20, Appendjx B, Table II, Column 2 applied at tr.e restricted area boundary where th, discharge flows into the Misstss: ppt River.

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. o 2.3.1.2 Liquid Effluent Monitors Two General Atomics RD-53 monitors are provided to ensure compliance with Technical Specification limits for liquid releasis. The RD-33 is an offline gamma scintillation (NaI) monitor designed for detecting radioactivity in liquids. The monitors consists of a removable 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 (IRMS-RE108) 1
a. Range: 10 to 10 cpm
2. Liquid Radwasta Effluent Monitor (1RMS-RE107) 1
a. Range: 10 to 10 cpm 2.3.2 Methodology The high alare setpoint does not consider dilution, dispersion, or -

decay of radioactive material beyond the site boundary. That is, the alars setpoint is based on a concentration limit at the end of the blowdown line discharge. -

2.3.2.1 Liquid Radwaste Effluent Monitor (1RMS-RE107) j 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. Die fraction Fg of the 10CFR20 MPC limits for unrestricted areas is determined in accordance with the preceding section for the activity concentration released.

4 The liquid radwaste 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

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I N/A N/A RSP-0008 REV. O PAGE 9 0F 112

a .

An alarm will also be annunciated in the main pontrol room. i The liquid radwaste effluent line radiation monitor alarm setpoint is determined with the equation:

S = A x g 2.3.2-1 I

L .

where:

S = the radiation monitor setpoint (cpm or uCi/ml)

A = the counting rate (cpa/ml) or activity concentration (uCi/ml) of the sample as determined in the laboratory.

3 = the ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given batch of liquid (cpe per cpe/al, cpm per uCi/m1, or uC1/ml per uCi/al) f g

= release rate of undiluted batch release line *

(al/sec, gpe, or other consistent units of vol/ time) f 2

= minimum dilution flow of cooling tower blowdown in the discharge (al/sec, gpe, or other consistent units of vol/ time)

Note: A/Fg 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.

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. i e 2.3.2.2 Cooling Tower Blowdewn Line Monitor l1RMS-RE108) ,

The cooling tcwer 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:

S = the 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.

2.4 Determining the Dose for Radioactive Liquid Effluents

]

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 mress 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 arems 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.

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l N/A N/A RSP-0008_ - _ _ - _ - . _ _ .

REV. O - _ - _ _

PAGE 11 0F 112

a .

The method is based on the methodology suggested,by Sections 4.3 and 4.3.1 of NUREG-0133, Rev. 1, November 1978.

A ir r all viable pa,thways are listed in Appendix The B.- dose factors 1 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 releases: du. ring a specific time interval for radioactive liquid n n

D, , Dg Ai Atg Qgg 2.4.2-1 i=1 i=1 (DF)g D, D, g

=

Dose commitment in mrem from radionuclide (i) received by organ (t) of age group (a) resulting from releases during the time interval At g

A =

g Site related dose commitment factor to the total body or any organ (t) for each identified radionuclide (1). The A g values listed in Appendix B are site-related to RBS and have the units (area /hr per uC1/ml)

At = '

g Number of hours that the release occurred Q gg =

The total quantity of nuclide (i) released during the time period Atg (uCi)

D, =

The near field dilution factor. Site specific value is 11.4 (River Bend E.R. p.5.4-5, section 5.4.2.3.1)

(DF)g =

The total volume of dilution that occurred during the release time period Atg (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 e desired time period (e.g. , sua all doses for releases during a 31. day period, calendar quarter, or a year).

N/A N/A RSP-0008 REV. O PAGE 12 0F 112

The following equation is used to calculate the total deses for the desired time interval:

n D =

(D ,) 2.4.2-2 TOTAL t i=1 where:

D TOTALt

= The total dose commitment to the organ (t) due to all releases during the desired time interval in mrem.

D ,1 = The dose commitment.in mrem to the organ (t) of age group (a) due to liquid release (i) during the desired time interval.

2.5 Pro _tectina Dose for Radioactive Liquid Effluents 2.5.1 Requirements Technical Specification 3.11.1.3 requires the liquid radwaste treatment systes be used to reduce the radioactive materials in liquid ,

wastes prior to their discharge when projected doses due to liquid j effluents, to unrestricted areas ( Figure 1 ) would exceed 0.06 mres to the total body or 0.2 mrom to any organ in a 31 day period.

2.5.2 . Methodology The following calculational methodology shall be performed at least once per 31 day period:

X

= 2.5.2-1 PD , ,

(DTOTALt)

D where:

PD , = Projected dose commitment (mrem) to organ (t) of age group (a) during the 31 day period X. = The number of hours in the 31 day period (744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />) 1 N/A N/A - R$P-0008 REV. O PAGE 13 0F 112

d a X

D The number of hours in the 5 31 day period during which releases occurred D

TOTALt

= The total dose commitment (mrem) to an organ (:) of age group (a) to date during the 31 day period. The age group (a) is selected based upon highest dose -

commitment.

3.0 GASEOUS EFFLUENT METHODOLOGY 3.1 Introduction The River Bend Station discharges gaseous effluents through the Main Plant Exhaust Duct, Fuel Building Exhaust Duct, and 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 releases. All gaseous effluent releases from the Radwaste Building Exhaust Duct are assumed to be ground level releases. The Main Plant ,

i Exhaust Duct routine releases are treated as a wake split (conditionally elevated) release.

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.

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 1

3.3.1 Instantaneous Release Rate Determination The instantaneous release rate determination is performed to show compliance with the limits set forth in 10CFR20. .

N/A N/A RSP-0008 REV. O PAGE 14 0F 112

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 total body and less than or equal to 3,000 mrem / year to the skin; and
b. For I-131, I-133, tritium, an1 for all radionuclides in particulate form with half-lives greater than 8 days: less than or equal to 1,500 mres/ 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

= 3.15 x 10 Kg (X/Q) Q g i=1 3.3.1.2.1-1 l n

7 DR skk. = 3.15 x 10 (Lg + 1.1 M ) (X/Q) Qg i=1 3.3.1.2.1-2 where:

4 DbB

= Dose rate to the total body in mres/ year.

Kg = ne total body dose factor due to gamma emissions for each identified noble gas radionuclide (i) in eres/sec per uCi/m Appendix C.

, Lg = Skin dose factor due to beta emissions for each identified noble gas radionuclide (i) in mrem /sec per uCi/m . Appendix.C. ,

l N/A N/A RSP-0008 REV. O PAGE 15 0F 112

M = The air dose factor due to gp=a emissions for each identified noble gas radionuclide (i) in mrad /sec per uCi/m . Appendix C.

(X/Q) = The highest calculated annual average relative concentration for any 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 effluents from all releases in uCi/sec.

1.1 =

Conversion factor for Mgfrom mrad to arem.

3.15 x 10 = Number of sec/ year.

Inordertocomplywiththelimitsof10CTR20,Dgg 5500 arem/ year and DR, g 53,000 mres/ year must be met at the most limiting location, at or beyond the site boundary.

The radionuclid.e 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 3.3.1.2.1-1 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):

-6 3 (X/Q), = 2.91 x 10 sec/m (X/Q)y = 3.84 x 10-5 , j,3 where:

=

(X/Q), Chi /Q for Main Plant exhaust duct and Fuel Building exhaust duct .,

(X/Q)y = Chi /Q for Radwaste Building exhaust duct N/A N/A RSP-0008 REV. O PAGE 16 0F 112

. Appendix F contains the maximum X/Q and D/Q values used in calcu;anng individual doses.

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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 Ga=

4 Release Rate NOTE This approach for K,gg and (1 + 1.1M),gg should only be used if the relative abundances of the noble gas radionuclides in the effluent streso are similar to those listed in Appendix D or of the previous Semiannual Effluent Report, as appropriate. , t (Reference 1.2.19)

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 j 3.3.1.2.1-1 the simplication proceeds as follows
)

Troe an evaluation of projicted releases, an effective total body dose 1

factor (K,gg) can be derived. This dose factor is, in effect, a j

weighted average total body dose factor. See Appendix C for a

] detailed explanation and evaluation of K,gg. The value of K,gg has i'

been derived from the radioactive noble gas effluents listed in RBS-FSAR and included in Appendix D. The values are:

Radwaste Building Exhaust Duct:

-5 g,,,,,,3/uci-sec)

K,gg = 8.05 x 10 i

i

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i e i

l N/A N/A RSP-0008 REV. O PAGE 17 0F 112 i

I d 0 Main Plant Exhaust Duct and Fuel Building Exhapst Duct:

= 3 K,gg 5.56 x 10~3 (mrem-m /uci-sec).

Either of these values, as appropriate, may be used id conjunction with the total noble gas release rate ( I Qg ) 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 .

DkB eff (X/Q) Qg 3.3.1.2.2-1 0.8 i=1 where:

DkB

= Total body dose rate from noble gases in airborne releases in eres/sec.

s

=

(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).

Qg =

The total release rate of all noble gas nuclides from the release source of interest in uCi/sec.

This limited analysis approach methodology is also available for determining skin 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),gg, can be derived. This dose factor is, in effect, a weighted average skin dose factor. See Appendix C for a detailed explanation and evalus::en of (L + 1.1M),ff. The value of (L-

+ 1.1M),gg has been derived fr:- :r.e radioactive noble gas effluents listed in RBS FSAR and incluce : :- Appendix D. The values are:

G

O O Radwaste Building Exhaust Duct:

(L + 1.1M),ff = 1.59 x 10' (mrem -m /uCi-sec) ,

Main Plant Exhaust Duct and Fuel Building Exhaust Du-6:

(L + 1.1M),gg = 1.36 x 10 (mrom -m /uCi-sec)

Either of these values, as appropriate, may be used in conjunction with the total noble gas release rate ( Qg ) to verify that the instantaneous dose rate is within the allowable limits. To compensate for an unexpected variability in the radionuclide distribution, a conservatism factor of 0.8 is introduced into the calculation. The simplified equation is:

n Skin * (b +

DR 3' *1*

3eff ( IO) Oi * ~

2 0.8 i=1 where:

DR Skin

= Skin dose rate from noble gases in airborne releases in eres/sec (X/Q) = For ground level or elevated releases, the highest calculated annual long-term historical relative concentration for any of the 16 sectors, at or beyond the )

unrestricted area boundary, in sec/m3 (Appendix F).

~

Qg = 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 l

Release Rates The following calculational method is provided for determining the dose rate from radiciodine 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.

f In the calculation to show cocpliance with 10CFR20, only the l inhalation pathway is considered, s:nce it is the most limiting

! pathway. '

i '

i l

N/A N/A RSP-0008 REV. O PAGE 19 0F_112 . _ ..

Inhalation Pathway: ,

n .

DR * ~~

I&8DPt # E ~ 'I

{ i D i i=1 where:

t = The organ of interest for the age group of interest.

Qg = Release rate of nuclide (i), (uCi/sec).

DR I&SDPt= Dose rate to the organ t for the age group of interest from iodines and 8 day particulates via the inhalation pathway (in arem/yr).

= The long-term depleted and 8 day decayed CHI /Q value (X/Q)D based on historical meteorological data (Appendix E)

(in sec/m ).

Note: No credit for decay or depletion has been taken.

=

P g The dose factor for applicable environmental pathway (in units of arem/yr per uCi/m ) (Appendix G).

The determination of limiting location for implementation of 10CFR20 for radiciodines and particulates is a function of the same parameters as for noble gases.

Values for Pg were calculated for an infant for various radionuclides for the inhalation pathway using the methodology of NURIG-0133. The Pg values are presented in Appendix G. The values of Pg reflect, for each radionuclide, the maximumgP value for any organ for the inhalation pathway.

S 0

N/A N/A RSP-0008 REV. O PAGE 20 0F 112 '

3.3.2 Setpoint Determination 3.3.2.1- Requirements .

Instrumentation is provided to monitor be:a-gamma radiecion 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 mrom/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.

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 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 affluent gas sample (s). Results of one or more 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-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 L 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 l

a. HIGH ALARM Setpoint Determination This section describes the methodology for determining HIGH ALARM / trip setpoints for the three release points: '
i. Wide Range Gas Monitor (VRG.9) .

1 N/A N/A RSP-0008 REV. O PAGE 21 0F 112

a Steo 1 ,

Determine the QTB (m8ximum 8C ePtable 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 point by:

500

-8

= 3.17 x 10 ~0

= x 0 Q TB .

. __ . 500 (0.8)

(X/Q)}Kg fg (X/Q) . K,gg i 3.3.2.2-1 where: (X/Q) = The highest calculated annual average relative dispetsion factor for any are'a 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 3

                                . per uC1/m ) from Appendix C, Table C-1.

f g

                            =     Fraction of noble gas radionuclide (i) to total noble gas concentration.

X,gg = E 1 g K .f g , effective dose factor (mres/sec per uCi/m3 ) from Appendix C, Table C-3.

                        -8 3.17x10      =     Inverse of number of seconds per year in year /sec.

0.8 = Conservative factor to account for changing isotopic inventory.

                                                                                         \

N/A N/A RSP-0008 REV. O PAGE 22 0F 112

6' NOTE , The K,gf methodology for determining Q should TB be used only if isotopic analyses gre not available (i.e. prior to initial criticality) or if the relative abundances of noble gas nuclides in the effluent stram are similar to those listed in Appendix D or similar to the noble gas isotopic mixture described in the previous Semiannual , Effluent Report. (Reference 1.2.19) Step 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: Q, = 3.17 x 10' . 3,000 = 3.17 x 10 -8 . 3,000 (0.8) (X/Q) (Lg +1 lMg )fg ] (M ) M .M),ff Lg + 1.1Mg = Total skin dose factor due to emission from noble gas radionuclide (i) ares /sec/uCi/m from Appendix C. (L+1.1M),ff = E1 (Lg + 1.1 M g ) . fg , effective total skin ) NOTE The (L + 1.lM),ff methodology for determining Q, should be used only if isotopic analyses are not available (i.e, prior to initial criticality), or if the relative abundances of l noble gas isotopic mixture described in the effluent stream are similar to those listed in Appendix D or similar to the noble gas isotopic mixture described in the previous Semiannual Effluent Report. (Reference 1.2.19) Step 3 Select the lower of the Q values (C TB #O)s brained in Step 1 and Step 2. ' 4 N/A N/A R;.,r -0008 REV. O PAGE 23 0F 112

0 0 Step 4 Multiply the Q value selected in Step 3 by 0.33 By multiplying the 0 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. Step 5 Multiply the actual ODCM HIGH ALARM setpoint obtained in Step 4 by the applicable monitor's loop accuracy plus a conservatism factor (if desired). Step 6 Subtract the product obtained in Step 5 from the actual ODCM HIGH ALARM setpoint. This remainder is the setpoint to be entered into the applicable WRGM RM-80. The General Atomics Digital Radiation 4 Monitoring System RM-80 allows for automatic fixed background subtraction. It is therefore unnecessary to account for background in the calculation of stack monitor setpoints.

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 0 3.3.2.2-3 F t N/A N/A RSP-0008 REV. O PAGE 24 0F 112

where: 2.12 x 10' = Unit conversion factor,to convert uCi/sec/cfm to uCi/cc. Q = lower of the two Q values, Q #O' TB s , F = The maximum acceptable effluent flow rate at the point of release based on design flow rates (Cfm) Step 3 > Multiply the C,value determine in Step 2 by 0.33. By multiplying the C , value by a factor of 0.33, the allowable opetating setpoints will be administrative 1y controlled to allocate one-third (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 setpont for the appropriate P&G monitor gas channel. Step 4 Multiply the actual ODCM activity concentration HIGH ALARM setpoint obtained in Step 3 by the applicable monitor's loop accuracy plus a - conservatism factor (if desired). Step 5 Subtract the product obtained in Step 4 from the actual ODCM activity .

                                                                                                        }

concentration HIGH ALARM setpoint. This remainder is the setpoint to be entered into the applicable monitor's RM-80.

b. Alert Setpoint determination (Reference 1.2.12)
i. Wide Range Gas Monitor (WRGM)

Step 1 Determine Q G-A (maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent [uCi/sec] based upon the quarterly (92 days) gamma air dose limit of 5 mrads at the SITE BOUNDARY for all release points:

         =

QG -A . 6 x 10 (SMO.8) = 1.26 x 10 (5) (X/Q) (M,ff) (@){M g f' s g 3.3.2.2-4 s . N/A N/A R*'/-0008 REV. O PAGE 25 0F 112

-e . Were: (5) = The highest calculated annual average relative dispersion factor for an area at or beyond the SITE BOUNDARY for all sectors (sec/m ). , See Appendix F for (XTQ) for the considered release point. M,gg = Effective gamma air dose factor (mrad-m3 /uCi-sec). See Appendix C, Table C-5 for applicable values. 5 = 5 mrads/ quarter (92 days) gamma air dose limit at the SITE BOUNDARY. Mg = The gamma air dose factor for radioactive noble gas nuclide (i) in mrad-m /uCi-sec (Appendix C) f g

                                                                               =

The fractional abundance of noble gas radionuclide i 1.26 x 10' Inverse of number of seconds per quarter in quarters /second

  • 0.8 A Conservatism factor to account for changing isotopic inventory NOTE The M,gg methodology for determining QG-A should be used only if isotopic analyses are not available (i.e., prior to initial criticality), or if the relative abundances of noble gas nuclides in the effluent stream are similar to those listed in Appendix D or similar to the noble gas isotopic mixture described in the previous Semiannual Effluent Report. (Reference 1.2.19)

Step 2 Determine Q B -A (maximum *CC*Ptable total release rate of all noble gas radionuclides in the gaseous effluents (uCi/sec] based upon the quarterly (92 days) beta air dose limit of 10 mtads at the SITE BOUNDARY for all. release points.

            =

QB -A . 6 x 10 (10) (0.8) = 1.26 x 10 GO) (EQ)(Ngf) (X/Q){N g fg 3.3.2.2-5 N/A N/A RSP-0008 REV. O PAGE 26 0F 112

Where: (3f[Q) = The highest calculated annual average relative dispersion factor for an area at or beyond the 3 SITE BOUNDARY for all sectors (sec/m ). See Appendix F for (X/Q) for the considered release point. 10 = 10 mrad / quarter (92 days) beta air dose limit at the SITE BOUNDARY. N,gf = Effective beta air dose factor (arad - 3 m /uCi-sec). See Appendix C, Table C-5 for applicable values. Ng = The air dose factor due to beta emissions from each noble gas radionuclide 1. fg = The fractional abundance of noble gas radionuclide i. 1.26 x 10' = Inverse of number of seconds per quarter in quarters /second. 0.8 = Conservatism factor to account for changing , isotopic inventory. j NOTE The N,ff methodology for determining QB-A should be used only if isotopic analyses are not available (i.e., prior to initial criticality), or if the relative abundances of noble gas nuclides in the effluent stream are similar to those listed in Appendix D or the previous Semiannual Effluent Report. (Reference 1.2.19) Step 3 Select the lower of the Q values obtained in Steps 1 and 2, i.e. either QG-A # N B -A* Step 4 i Multiply the Q value selected in Step 3 by 0.33. By multiplying the Q value by this f actor, 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 VRGM's RM-80. N/A N/A RSP-0008 REV. O PAGE 27 0F 112

i l 1 I t l Steo 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 an 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 i 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 I of all noble gas radionuclides for all release points in gaseous effluent [uCi/cc]: '

                                                      ~3 C,= 2.12 x 10                 Q                          3.3.2.2-6 F

! Where: 2.12 x 10' = Unit conversion factor to convert uCi/sec/ cfm to uCi/cc. Q = Lower of the two Q values, Q G-A # OB-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 release pot'nts. The resultant product will be the actual ODCM activity concentration ALERT setpoint. This value is , the setpoint to be entered inte :r.e applicable P&G monitor's RM-80.

       ,                        N/A                N/A                             RS? ;;CS                                REV. O         PAGE 28 0F 112
  --     -,--------,s,--            -,,,w    .,----m--     ,--,m---------m-+--,         as - - < - . e--c- ,  - , , , - -  -www - ,w w e rw . v gw---~ -s- ,-         -,g--- -~,g~ w,-

Step 4 If the actual ODCM ALERT setpoint determined in . Step 3 is less than two (2.0) times the gas detector background, it is permissible to enter an ALERT setpoint equal to two (2.0) times the normal (approximately 100% unit power) gas 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. . 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:
i. 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 uranium 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 mress.

.r N/A N/A - - - - 38 REV. O PAGE 29 0F 112 l

                         -                      , -- --, _ _-r.,%..,.,_--,-,-----,m-.mm----------              ----, . - -     -,y,   -- --

ii. 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 PUBLIC 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 Protection Standards for Nuclear Power Operation. Cummulative doses from liquid effluents and gaseous pathways (radioiodines and particulates 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 Section 3.4.1.2b. 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 location at the site boundary 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 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 gas releases during a specific time interval for I radioactive gaseous release sources at the site boundary: n D " Gamma-Air i * ( IE)

  • Oi * * * *~1 i=1 3

I N/A N/A RS?-0008 REV. O PAGE 30 0F 112

n , D * } * 'l' "' Beta-Air 'i*( i i=1 s where: D Gamma-Air

                                 =   The gamma air dose from radioactive noble gases in mrad.

M 1

                                 =   The gamma air dose factor for radioactive noble gas nuclide (i) in mrad-m /uCi-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 i the year of interest in sec/m3 (Appendix E). , Qg = The number of uCi of nuclide (i) released during the period of interest. D * *** "I* ** '# * ** ' ""**** "

  • 8**** '" '#*
  • Beta-Air

. Ng = The beta air dose factor for radioactive noble gas , 3 nuclide (i) in mrad-m /uCi-sec (Appendix C), Table C-1.

b. Total Body and Skin Dose (Reference 1.2.13)

This section provides the methodology to calculate the total body and 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 document and are obtained from Table B-1 of RG1.109, Revision 1, October, 1977. i

                                                                                \

l N/A N/A RSP-0008 REV. O PAGE 31 0F 112

 ~. . - - -          - . _ - . -         , ----_-.             .   - -    -. - - .           .

The following equations provide for total body,and skin dose calculations based on actual noble gas releases during a specific time interval for radioactive gaseous release sources at the site boundary: , n - D Total Body " F #3*O ' ~1

                                               )     i*                                 i i=1 n                                                                                                         -

D " 3 Z 3.4.1.2.-2 Skin F (Li* I*IH )i x (X/Q) x Q g i=1 Where: Total Body = The total body dose from radioactive noble gases in D area. Kg = The total whole body dose factor due to gamma emmissions from noble gas radionuclide (1) (arem/sec per uCi/m 3) from Appendix C, Table C-1. (X/Q) = The long-term atmospheric dispersion factor for ground level (annual average) for the year of interest for the maximum receptor. Actual meterological data and sector wind frequency distributions will be used to determine annual X/Q for the year of interest in sec/m3 (Appendix E). NOTE For purposes of calculating D Total Body and Skin f#* * **i""""" D " ""*i"* "*"* 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). Qg = The number of uCi of noble gas nuclide (1)., released during'the period of in'terest. Skin = The skin dose from radioactive noble gases in mrem. D Mg = The gamma air dose factor due to gamma emissions from each noble gas radionuclide (i) released. N/A N/A RSP-0008 REV. O PAGE 32 0F 112

L = The skin dose factor due to beta emissions from noble gas

  ;                 radionuclide (i) (mrem /sec per uCi/m ) from Appendix C. Table C-1.                                                                                         **

1.1 = Average ratio of tissue to air energy absorption coefficients. 5 7

                = 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,gg) 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,gg and N,gg). The values of M,gg and N,ff which have been derived from the projected radioactive noble gas effluents are: Radwaste Building Exhaust Duct: , M,gg = 8.07 x 10 -5 mrad-m3 /uCi-sec N,gg = 7.40 x 10 -5 mrad-m3 /uCi-sec .

;         Main Plant Exhaust Duct and Fuel Building Exhaust Duct:

M,gg = 5.96 x 10 -5 mrad-m3 /uCl-sec N,gg = 8.99 x 10' mrad-m /uCi-sec i NOTE The M,gg and N,gg 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 Effluent Report. (Reference 1.2.19) i N/A N/A RSP-0008 REV. O PAGE 33 0F 112

4 The effective gamma air dose factor may be used in conjunct en ith the total noble gas release ( I Qg ) to simplify the dose evaluation and to verify that the cumulative gamma and bete air dose is within the equivalence of the limits of Technical Specification 3.11.2.2. To compensate for any unexpected variability in the radiohuclide

  • distribution, a conservatism factor of 0.8 is introduced into the calculation. The simplified equation is:

(M,gg) . (X/Q) n D " Gamma-Air

  • S * ' * '

i O.8 i=1 (N,gg) . (X/Q) n D

  • Beta-Air
  • Oi ' * * ~

0.8 i=1 3.4.2 Determining the Radiciodine and 8 Day Particulate Dose to Any Organ from Cumulative Releases

  • 3.4.2.1 Requirements Technical Specification 3.11.2.3 states that the dose to a 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 mrem to any organ; and

b. During any calendar year: less than or equal to 15 mrem to any organ.

i e 1 N/A N/A RSP-0008 REV. O PAGE 34 0F 112

3.4.2.2 Methodology . The following calculational method is provided for deter =ining the critical organ dose due to releases of radiciodines and particulates. It is based on Section 5.3.1 of NUREG-0133. Rev. 1. N 9vember 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 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: 3.4.2.2-1 n D I&8DPt = ( .1 x 10-8) R it ( IO)D

  • 01 i=1 ,

Ground Plane Pathway: 3.4.2.2-2 n D 1&8DPt = (3.17 x 10-8) R it

                                                                                .           (D/Q)             . Q i                                                                )

i=1 Contaminated Forage / Cow / Milk Pathway: 3.4.2.2-3 n D I&8DPt = (3.17 x 10-8) Rg . (D/Q) . Qg i=1 l N/A N/A RSP-0008 'REV.O PAGE 35 0F 112 1 .l l

        . _.,,..,__ _ __.            __  - . - . _ , . _ _ _            ...y,_    _ . , - . . , _ . ,             _ , , . _ . - , . _...m_,     _ , _ , _ . _ _ _     . . _ _ . ,
 . e i

Total Dose: , 3.4.2.2-; n D = D

                     }{}        I&8DPt 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. where: t = The organ of interest in a specified age group. z = All the applicable pathways for the age group of interest.

                =

D I&8DPt Dose in eres to the organ (t) of a specified age group from radioiodines and 8 day particulates due to a particular pathway. . D' = Total dose in eres to the organ (t) of a specified age group from gaseous iodine and particulate effluents, summed over all applicable pathways (z). 3.17 x 10 -8 = The inverse of the number of seconds per year [in years /sec]. Rg = The dose factor for nuclide (i) for pathway (z) to organ (t) of the specified age group. The units are either: 3 mree-m for pathways using (X/Q)D yr-uci

                                                         \

h N/A N/A RSP-0008 REV. O PAGE 36 0F 112

or , mrem-m -see for pathways using (D/Q) yr-uCi (See Appendix I.) , (EQ)D

                             =          The depleted (X/Q) value for a specific location where 3

the receptor is located. n e units are [sec/m ]. (See Appendix F.) Note: No credit is taken for ' depletion and decay. (X/Q)D

  • I IE) a (i7) Q) = The deposition value for a specific location where the receptor is located. The units are [m' }. (See Appendix F.)

j NOTE For purpose of calculating D f r the I&8DPt Semiannual Radioactive Effluent Release Report, X/QD and D/Q values based on meteorological ' data for the actual considered time period should be used rather than historical (X/Q)D , and (D/Q) values. If at all possible, real time X/QD and D/Q values should also be used when de.termining 40CFR190 compliance when Technical Specification limits have been exceeded by a factor of two (2.0).

                            =

Qg ne nu ber of microcuries of nuclide (i) released (or projected) during the dose calculation exposure period. 3.4.2.3 Limited Analysis Approach The contaminated forage /cov/ 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 and particulates by only evaluating the infant's thyroid dose due to the release of radiciodines via the contaminated forage / cow / milk pathway, i i N/A N/A RSP-0008 REV. O PAGE 37 0F 112 c I i _ _ . - . _. ..__________,_.__m.-- . - - , , _ . _ , _ _ - . . . _ , - - _ . . _ - _ . . _ , _ _ _ _ - _ _ _ _ _ _ . _ _ _ . . - - - .

    . e The calculational method to be used includes a conservatism factor of 0.8 which assures that the calculated dose is always greater than or                                                                                                                                          l 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 D= [3.17 x 10~0 (D/Q) Rg . Qg ) / 0.8 io ines 1 3.4.2.4 Approach Selection Criteria  ! The limited analysis may be used in all cases to demonstrate compliance with the dose limit of Technical Specification 3.11.2.3 (7.5 ares /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 Radiciodine and 8-Day Particulates Technical Specification 3.11.2.3 required the annual dose be calculated at least once per 31 days for all pathways. The following formulae are used to calculate the annual dose for radioiodines and 8-day particulates: Inhalation Pathways: 3.4.2.5-1 n D I&8DPt = (3.1 x 10-8) Rit*I IO) D'Oi i=1 Ground Plane Pathway: 3.4.2.5-2 n ___ D I&8DPt = (3.17 x 10-8)  ;

37) ,q i=1 N/A N/A  ?! -  :$ REV. O PAGE 38 0F 112 l

( l _ . . _ _ . - _ _ . . _ _ . . . _ . , . . _ . . _ _ . . _ . - _ _ _ , _ - . _ _ . _ _ _ . . _ _ _ _ _ . _ . _ _ _ _ _ . _ ~ _ _ . ___ _ _..,__ _ . _ . , . . - _

                                                                                             . o Contaminated Forage / Cow / Milk Pathway:                    ,            3.a . 2. 5 -3 n

D I&BDPt

             "(     *     *      }          it
                                               .(D/Q) .Q g            .,

i=1 Contaminated Forage / Goat / Milk Pathway: 3.4.3.5-4 ' n D I&8DPt "( " " * ) it

                                                  *( !O} '0 1 i=1 Contaminated Forage / Meats:                                               3.4.2.5-3 n              _

D I&8DPt

             "(    *     *       )

it'( 0) 'O i i=1 Fresh Fruits and Vegetables: 3.4.2.5-6 n D I&8DPt = (3.17 x 10-8) Rg ,.(D/Q) .Q g i=1

                                                                                                 }

Total Dose: 3.4.2.5-7 n Dt = { z=1 D I&BDPt where: t = The organ of interest in a specified age group. 2 = All the applicable pathways for the age group of interest. DR = I&8DPt Dose rate to the organ (t ) for the age group of interest froo todines and 8-day particulates via the pathway of interast in mrem /yr., For radiciodines, the entire source -r- was used to calculate these values. Qg = The number of . nuclide (i) released during the year of interau Rg = The dose facter : - .uclide (i) for organ (t) for the pathway specif u : units vary with pathway]. For tritium, a site specific absolute humidity (H) value of 12.9 as/s was used for calculation. (See Appendix I.) N/A N/A RSP-0008 REV. O PAGE 39 0F 112

(D7Q) = A long-ters relative deposition value for elevated and 9 ground level releases. A factor with units of m ~ which describes the deposition of particulate matter from a plume at a point downrange from the scurce. Actual meteorological data and sector w'ind frequency distribution will be used to determine annual average D/Q for the year of interest. (X7Q)D

                                  =     A 1 ng-ters depleted and 8-day decayed relative concentration value for elevated and ground level release. It describes the physical dispersion characteristics of a semi-infinite cloud traveling downwind. Since iodines and particulates settle _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 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-described methodology (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, meat and vegetation pathway calculations. i e 6 e i N/A N/A RSP-0008 REV. O PAGE 40 0F 112 I l

CE For purposes of calculating DR

                                                                                              , MSDPt fu W Semiannual Radioactive Effluent Release Report, X/QDand D/Q values based on meteorological data for the actual consid-ered time period should be used rather than historical (X/Q)D and M ) values. H at all possible, real time X/Q Dand D/Q values should also be used when determining 40CFR190 compliance when Technical Specifi-cation limits have been exceeded by a factor of two (2.0).
                              -8 3.17 x 10 =                       The inverse of the number of seconds per year (in year /sec).

Meteorological data (X/Q, X/QD , D/Q) will be determined from actual meteorological data and sector wind frequency distributions for the year of interest. Release rates (uC1/ 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 )J 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 (radiciodines, particulates T 1/2 > 8 days and H-3) would exceed 0.3 mem to any organ in a 31 day period. 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 methcc is provided for determining the

  • projected doses:

, PD , X . D 3.*>. '. l N/A N/A RSP-0008 REV. O PAGE 41 0F 112

where: PD = Projected dose due to radiciodines, particulates sich T 1/2

                              > 8 days and H-3 during the curren; 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 that the unit was operational (Conditions 1 and 2).

D, = Cumulative total dose due to radiciodines, particulates with T 1/2 > 8 days and H-3 during the 31 day period to date (ares). A formal dose projection would be based on the latest results of the monthly calculations of the dose due to radiciodines, particulates with T 1/2 > 8 days, and H-3 (Section 3.4.2.5). The doses calculated would be divided by the number of days that the plant was operational (Conditions 1 and 2) 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.

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, s N/A N/A RS' 0008 REV. O PAGE 42 0F 112

IAMtE 4.I RAD 4Ut OCtCAL [IgviROINILCI AL $6000t iORIIOC PP9 craft Exposuro P:ttsway Sample ruint. Description, Samplitig arid type anst f re.gimency

         .gfid/2r _Samyie       DJnaesgg...pessfJifeg11 sera            091 j _ecLJ3nEggeaesary

_ o f Anajne s , .

    . Airborne Parti-         Samples from 5 locations:

culctos arist 4 flad io s odiese s AAl. River pend Trainirg Cont irtuotes a i r samp le r Charcoal cartridge:

  • l Center; 3. T he II. with filter collection steelysis weekly for i

' weekly or as reqisired by raBioiodines. dust loadieng, whichever Particulate sampler: is more frequent, gross heta setivity i fellowing fiIter changes; composite for gamma isotopic

                                    .                                                                     qua r te rly.

ARI. River Send Station sporth Access fload at Ca te #3; O.8 he asssW. Art. secar River Senal Station Onsite Carden #1; O.9 he nNIW. AQS2. St. I rancis Substation J uti US towy. (Sus. ) 61 in St. 8rareciswille; 5. 8 he IIW ( Cuneiers s t y I oca t ion ) . AI C. P.a r s anspe Powe r Cente r is Osca s ; 70 he SW ( Cosot rol ). 1 l i

                                                                                                                                          ~

I _. l i

                                                                                                        .                         O .

j w

                 ,                                 IAHIi 4.I RAD 06OcICAI ElovsRonniCTAL I4000t IGRIIIC Pacc.       .

tPage 2)

. E myosuro Pa atoway     Sample Point. Ihr sc ri p t ion.         SampIIseas and                  type anes f requeency
. ._ aetd_/1h 8 e _        RLs g ance,_anst_Ji regLion_      Co!lection I rege.s_ency                   of Analysis
'C4roct RediaLion        Seessurements f roe
!                        40 locations:

IIeplCAIOR SI AIIOces

,                         IAI. River Send t raining       flee reoluminescence                  Comme esose aguarterly.
!                        Center; 3.7 he W.                   dosimeters iILDs);

deployment / ret rieva l agasa rt e r ly. IA2. CSU istility pole #246 at Jct. or L A 60wy. to and W92

;                         in Ele Park; 8 he e.

181. River Send Station iron yard area; 0.5 he seest, a i i 187. Stub pole at Jct. LA Iky. 96*2 and Aaadubon Lane j , IWIII); 5 be 8000[. 4 ICS. Stesh pole at Jct. US twy. 68 . seed Old Heghway 61; ] 1.1 he MI . 4 IC2. Stash pole ainseg i A Hwy. 1 966. 0.6 he 5 of Jct. L A Wys, i 9. 66 and %*>: F km set. 108 Stieb pole aloseg WTF, j ISpa 5 of Jct. WfI anet US Hwy. 65;.1.6 he ENE. ID?. Stieb pole a toseg l A Ny. 966. 4 he S or Jct. LA thys. 9t>6 and 965; 6.3 he Enf. i . l i 4 i 1 N/A N/A RS f*-tM H e8 NEV. O I* AGE 48e Of 8I? I s

IA864E C.I RADIOtOCICAI IIfv8RONMICIAL MOIIIIOell80C PWmW (Page 3) f orposaare Pattsway , Sample Point, Description, Samp l ing stad

 .ing/g d eple__                 pistysge. anst__ir_ection D                                                  type asses f regimency Col litct ion Ir: _- --ay of Assalvsis _

fil. Stuto pole along WI F, I he S or Jct. WF F and US by. 63; 1.3 he Ef. 112. Gravel Power Center on 8 A %. 64, 2 he II ur Jct. 8A Hwys 64 and 964; IH be E. III. Stub pole along Wil, l.6 he S er Jct. WfF and US - Hwy. 63; 1.3 he ESE. IF2. McIlowen Deiry on 4 A hy. 954. 0.6 he It of Jct. tA hy. 954 and US h y. 61; 6 he ESE. IGl. Stub pole along WF7,

  • 7 km S or Jct. Wfl and US towy . 63; 4.6 he SE.

IG7. telephorne pole at gate to Marattaean lanh farm on US fewy . 63 near Delectre, f.S be St . lis t . Stesta pole at I t t ianoi s Central Caelf HR crossisig of WI F (near Geasets Bayou); 1.F he SSE. lH2. First teleplausse pole on

                      . I A Hwy. 964 II of entrasice to C-2 papermi18; S.S be SSE.

i 80/A N/A RSP-tM WWI REV. O PAGE 45 Of II? 4 e l w I

r RAMit 4.1

                                                                                                                                            . =

RAD 108OCICAI I alvINOestiCIAL MoeliIONIsec PgKe. .All (Page C) f rposure Pattsway Sample Psisst. Description. Samen t ireg ansa type ased f restinesicy

  • fnd/7r Saeyje__ ._pj stangh an(_ pj regg ion ColJegtlose Regamengy t

af_Ana_tyu s l IJ1 Staati pnie near River Rend Statson Cate #23 on Powell Station Road (LA Stwy.

                     % S); 1.5 km S.

IJ2 targe tree along River Road. 100 e se of C-I papereill antake strascture; 5.8 km S. Ikl. CSU utility pole #L101T8

  • on Powel l Sta t ion Noad ( L A fewy.

965). 20 m S er River llend Station River Access Road; D.9 he $$W. Ik?. Staati pole at Jct. LA Hwys. 434 and 415; 8 he $$W. - Il 1 Seconal est i l i ty pole on

     .              Powell Statioss Road (LA Hwy. 965)
                    $ o r l i f e ssoi s Cent ra l Cul f RR crosseeig; 1.0 km SW.

18 7. Seceand est i l i ty pole a t osMI 1A lawy. 4IS E of touissane and Arkaessas RR crossing (stear Patin's Dike); 9.5 km SW. IMI. Iirst ut434ty pole on Powe1I Statson Road (LA Hwy. 965) 80 or I l l ino i s Cent ra l Culf RR crossisig; 0.9 he WSW. , 99 M/A N/A RSP-EMHDR NfV. O l'AGt 86 6 (12 117

                                                                                          ~.

IAHLL a.Is RADIOt0CICAL f NV8 ftOGIME CI AL MOSIB 1001110G PROGRAM (Page 5) j trposure rattsway Sample Poisit. Description, Sampling and type and frequency

     .JDWlZ,r haple_,   _ pisggnep and D6reggion                Co1Ioct6on ireeuen_cy           or Ana1ysis IMP. Utility pole along LA Hwy. 981. about 3 km S of                                                                                    ,

Jct. L A Hwys. 981 ased to (west bank Terry landing); j 4.2 km WSW. INI. Utili ty pole a los.g Powell Station Road (LA fewy. 965), between River Elend Station Cates #13 and 14; O.9 km W. IN2. Utility pole with electrical meter esear west I bank Ferry landing (LA Hwy. j 10); 6.0 km W. TPl. Beea r R i ve r Bend S ta t in** Onsite Carden #1; 0.9 km WIIbe. 4

         ~

lP?. Stub pole about 1.5 he N of l8linois Central Culf RR j trestle oss lesnica Street. western nestskirts of St. 1 Grancisvolle. 1.3 km WIfW. IQl. CSU property sign pole along Powell Station Road (LA Hwy. 96's ), about I km M or 1 River llend Stat son 80erth Access Road; 3.4 km 80W. 1 1Q2. CSU pole with street

  • i lights at Jct. Isortis Commerce and Americas Beauty Streets.

St. T ranc i svi l le; 6.9 km IIW. e e 1 i l j M/A N/A RSP-nou8 HEV. O Pact 841 of II? i a r bM

I Altl l a.1 s . RADiolOCICAI I NV IROIIMI CI AL N000 l lDR i f0C PHO JI (PI9e O) f rposure Patlway Sample Point, De sc r i p t ion, Sampling and type and Fregieency

   ..e tNf /O r_} amp l e,.__         Distangh_and uiteggiojL                 CoIIect ion f reguency

__ _or Analysis __ TRI. River Send Station 80erth Access Road at Cate #3; 0.8 km leteW. IR?. Stub pole along WI2 at g rave l road about 8.8 km E of Jct. Wi2 said US iky 61; 8 km 8088W. Co0IIROL/SPECI AL SI Al lONS . TAC. Telephone pole alcr.g US eky. 63 about POG e N of l Hami i ton Sta t ion Wa to r Towe r, j , secar Wakefield; 18 km M (Control). II C. Parlange Power Center in Osca r; 20 km SW ( Cont rol ). , Isr. tscla s sed Pentecostal i s . . . s. s ees.o.us i te West feliciana

                                 .=....       .e, :iea r Jct. US Iky. 61
                                 ..os e r - J e ssesad St reet; 84 km 30W

.I I *. g o e e m 0 ) . 18 8%* . St. francis Substation oss II. S. ilwy. ( Bass. ) 68 in St. I ranci svi l le; *p.8 km IIW ( Spec ia l ) .

;                                IL S. Utility polo near f alse

{ River Academy sigas at edge or psew Roads; 9.9 km SW ( Specia l). ICS. Utility pole at gate to j East tuulsiassa State Hospital In Jackson: 12.3 km NE (Special), i 1 1 !i 4 k l 4 M/A N/A R S P-t Hio8 RfV. O f* AGE s as of II? j -

)

I l

IAhl[ 4.1 RAD 104OC1 cal iIIViROSIMEOTAL MOIIIIOR180C PROGRAM ( Page 1) E mpo*ure Pa thway Sample Point, Description, Sampling and type and f requesicy god /*r S epj t e.,_. _ JMasicqu ant,U_jrgq1lgIL i Co l lect ion i rega_se_!Lcy or_ Analysis ICS. .CSU Service Center compound in lachary; 11 km SE ( Spec ia l ) . . THS. Roer or CSU Service Orrice Iksilding, leosth Blvd., Ha ton Rouge; 40 km SSE ( Spec ia l ) .

3. Watorborne SURF ACE WAT ER ( 1 )

SWu. Mississippi River about Weekly grabs composited Monthly composite: i 4 km upstream from the plant over moesthly and gamma isotopic analysis; , liquid discharge outrail, qua rterly periods. Quarterly composite: nea r LA Hwy. 10 Terry crossing. tritium analysis. SWD. Mississippi River about

,                                                                                       as km downstream from plant l                                                                                        ligteld discharge outrail, near l                                                                                        C r eswes-/et s le rbach pape rmi l l .

e s . .. e.n e 9e* I i siet. At blowdown Hoterly grabs composited 1 e . . .e a esing River Access Road, over monthly and 4

  • qisarterly periods, t.HOUNOWAI[H Wu. Upland terrsee Aqteifer Qua rterly grab. Camma isotopic and well espg rad iesit room plant, trititse analyses about ain m-MNE.

s qua rte r l y. WD. Upland Ierrace Aqisi rer we l l downg rad ien t l'r om p l ant, about 4:10 m SW. 1 2 l 4 9 N/A N/A HSP-OOOS HIV. O PACf 8s9 01 I17 1 j 4

I Allt t a,i s RADIC10CICAI INVIHoleMf GIAL MOlllIORING PMot I * (Pa!o 8) i impssesro Pathway Sample Point. Description, Sampling and type and freguesicy a ,__Dd/or $ ample _Dtitar!ce a mnd. Ili rec L {on,_ Collection f regaaeggy of Analysis _ _ SilORELINE SID1 MINI SED. Mississippi River about Sealannual greb. Comma isotopic as km downstream from plant analysis semi-liquid discharge entreII, near annually. Crown-Zellerbach papermill. Ing3stion MILM (2) Ml?. Mcitowen Da i ry on LA Hwy. Semimonthly when Camma isotopic and 9 58 8 , 0.6 km N of Jct. IA Hwy. animals on pasture: 1-131 analyses 93as and US Hwy. 61 6 km EST monthly at other times, semimonthly or monthly. (nearerst source or milk for consumption). MQC. L A State Penitentiary at Angola, 35 km NW (Control). FISH AND INVERIIBRATES I t es one sample of each of Seasonally when Camma isotopic ! t ree e ee e uanener s c 6 a l ly and/or available or semiannually, analysis on edible s e o e s a t suriae l ly important portions. sgeetc e sa s f rom espatream area sust e sil luernced by plant di scha rge. l l 10. One sample or each or i tleree commercially and/or secseativesally important ! species Isom downstream I area inf assenced by plaret l discharge. o O k - i + N/A N/A HSP-sHHis HEV. O pat;[ =30 or ila 1

l Altl L Is .1 RADIOLOGICAL EllVIRONMICTAL MosellDRIIeC PROGRAM (P2ge D) fuposuro Pathwry Sample Point. Description, _And/or Sameje__ SamptIng and type aral I reqisesicy __Dillance. and Directigit Co_j_{eglion rtggtse_pcy of Analy us _ , PRODUCE Cl/C2. Two samples or each or Montlity during growing three dirrorent kinds or leary season. Camma isotopic ared vegetables free onsite gardens 5-931 analyses monthly. nea r the s i te bounda ry o r liighest calculated anniaal , average ground-level D/Q if three olik 4ampling areas p'

                                  .not avallatie.                                                     -

CQC. 'One sample of each or the the sieller vegetables f rom LA State Penitentiary at Ango la, 35 tie w ( Cont ro l ) .

  • NOI r s: ,

l. the upstenas simpse will be taken at a distance beyond inritsence or the plant discharge. The downktream sdeplu well be taken in an area beyond but near the mixing zone. 2. O r mi s t pe udor eng animals become available within a $-km raditis or the plant, top to 3 samples from these high dose animals will potesstial areas.be analyzed in lieu of the leary vegetable samples from onsite gardens its l I N/A . N/A ItSP-unOS REV. n l'Act e, I of II? e 4 9 W

     . -e 5.0      40CFR190 CONSIDERATIONS d

5.1 Cempliance 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 Evaluatina Conformance with 40CTR190 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 mram/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 ares /yr. 5.2.3 Environmental sampling data which demonstrate that no pathway exists may be used to delete a pathway to man from a calculation. , 5.2.4 To sum numbers represented as "less than" (<) , use the value of the largest number in the group. e.g., <5 + <1 + <1+ <3 = 5 5.2.5 When doses via direct radiation are added to doses via inhalation pathway, they will be calculated for the same distance in the same sector. i 5.2.6 The calculational locations for a Member of the Public will only be at residences or places of employment. 5.2.7 If at all possible; X/Q, X/Q , and D/Q values based on D meterological data for the actual considered time period l should be used in determining complian'ce with 40CFR190. Note: Additional- assumptions may be used to provide situation specific parameters, provided they are documented along with their concomitant bases.

5.3 Calculations of Total Body Dose Estimates will be made for each of the following. exposure pathways to

  • the same location by age class. Only those age classe,s known to exist at a location are considered. -

5.3.1 Direct Radiation (from storage tanks, N-16 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 arem/yr. 5.3.4 Total Body 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.

                                                                                                         )

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 The dose to the thyroid will be calculated for the limiting sector as the sum of: 5.4.1 Direct Radiation (from storage tanks, N-16 sources, etc.) The component of dose to the thyroid due to direct radiation will be determined by thermoluminescent dosimeters (TLDs). 5.4.2 Inhalation Dose i 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. N/A N/A RSP-0008 REV. O PAGE 53 0F 112

                                                                                                                  \

l

                                                                                                                  )

l 5.4.3 Ingestion Pathway (cow milk, goat eilk, meat, vegetation) The dose to the thyroid via the ingestion pathwap 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. 5.4.4 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. 5.4.5 Ground Plane Deposition 5.4.6 Other Uranium Fuel Cycle Sources The dose from other fuel cycle sources will be treated as < 1 mrem /yr. 5.5 Orman 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 1 determined by thermoluminescent dosimeters (TLDs). I 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 dose via this pathway will be treated as < 1 mres/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 6 N/A N/A RSP-0008 REV. O PAGE 54 0F 112

e , The dose from other fuel cycle sources will be treated as < 1 crem/yr. 5.6 Skin Dose 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 component 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 i consumers at risk. If no milk pathway exists in a sector, the dose via this pathway will be treated as < 1 mram 1 yr. P 5.6.4 Skin Noble Gas Immersion Dose , This dose will be calculated in accordance with Section 3.4.1.2b for the moximally exposed MEMBER OF THE PUBLIC in the limiting sector (s). 5.6.5 Ground Plane Deposition 5.6.6 Other Uranium Fuel Cycle Sources This dose from other fuel cycle sources will be created as < 1 mrem /yr. l 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 N/A N/A RSP-0008 REV. O PAGE 55 0F 112

 . e
                                                                                                     )

6.2.1 Environmental Sample Analyses Coeparisep Program l Environmental samples from the River Bend Station are to be analyzed by the River B'nd e 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 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.

                                        ~.

N/A N/A RSP-0008 REV. O PAGE 56 0F 112

APPENDIX A LIQUID .MPC VALUES 3 6 i N/A N/A RSP-0008 REV. O PAGE 57 0F 112

I

     . e.

i MAXIMUM PERMISSIBLE CONCENTRATIONS IN WATER IN UNRESTRICTED AREAS MPC MPC - MFC 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-3 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-3 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 Br-83           3 E-6               Sn-113                         8 E-5     Ba-141      None Br-84           None**               In-113a                       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     Co-141      9 E-5 Rb-89           None               Te-125m                         1 E-4     Co-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 hours." i s e N/A N/A RSP-0008 REV. O PAGE 58 0F 112

s . APPENDIX B , LIQUID ENVIRO.WESTAL DOSE TRANSFER FACTORS A it k 1 0 N/A N/A RSP-0008 REV. O PAGE 59 0F 112

TABLE B-1 , LIQUID EFFLUENT DOSE PARAMETERS (Page 1)  : A g

                                         , mrem /hr per uCi/mi Radionuclide                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 Sr-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 ht-95                        1.34E02                           1.51E06 Mo-99                        6.84                              2.96E02 Tc-99m                       3.45E-01                          1.60E01 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 Te-132 6.80E03 3.42E05 Ba-139 3.51E-01 6 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 .11E-01 1.39E04 Ce-143 7 73E-02 2.61E04 Ce-144 1.50E01 9.44E04 N/A _ N/A __ _RSP-0008_ __.. . pgV. O _ PAGE.60 0F_112

a

                                                                                  ,                                  t e TABLE 3-1           ,

LIQUID EFFLUEST DOSE PARAMETERS (Page 2)  : Radionuclide Total Body Critical Organ Pr-143 2.87E-01 Nd-147 2.54E04 2.74-01 2.20E04 W-187 8.66E01 Np-239 8.12E04 1.70E-02 6.22E03 Br-83 4.80E01 Br-84 6.91E01 6.22E01 6.22E01 I-131 1.57E02 I-132 8.98E04 8.75 8.75E02 I-133 3.49E01 I-134 1.68E04 4.74 2.30E02 I-135 1.97E01 Rb-89 3.52E03 1.51E02 2.15E02 Cs-134 6.49E05 Cs-136 7.94E05 9.93E04 1.38E05 ' Cs-137 3.83E05 Cs-138

                 '                                                                  5.85E05 2.90E02                            5.85E02

, H-3 2.80E-01 2.88E-01 N/A 4 N/A RSP-0008 REV. O PAGE 61 0F 112

TABLE B-2 , CALCULATIONAL ASSUMPTIONS FOR A g

                                                ~

A it

                              =    1.1     x 10      (Uw/Dw + U     F 1 + UgBIg)DFg F
                             =

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)

                           =

BF g bioaccumulation factor for nuclide i in fish (pCi/kg per pCi/1) - 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" - U = 5 kg/yr 7 adult invertebrate consumption (R,eg. Guide 1.109 Table E-5) BI g = bioaccumulation factor for nuclide i in invertebrates (pCi/kg per pCi/1) Reg. Guide 1.109 Table A-1 DF g = dose conversion factor for nuclide i for adults in pre-selected organ t (arem/pCi). Reg. Guide 1.109, Table E-11. I

                                                                                \

N/A N/A , 2SP-0008 REV. O PAGE 62 0F 112

G APPENDIX C K. L AIR DSSE TRANSFER FACTORS 1 i , 9 0 s 4 0 N/A N/A RSP-0008 REV. O PAGE 63 0F 112

TA3LE C-1 DOSE TRANSFER FACTORS FOR EXPOSURE TO A SEMI-INFINITE " CLOUD OF RADI0 ACTIVE NOBLE GASES DOSE TRANSFER FACTORS Gamma Beta Beta and Gamma Ki Li_ (L+1.1M)i eres 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-3 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-3 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 Mi Ni mrad mrad Nuclide uCi sec/m3 uCi sec/m3 Kr-83m 6.1E-7 9.1E-6 Kr-85a 3.9E-5 6.2E-5 Kr-85 5.4E-7 6.2E-3 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-131a 4.9E-6 3.5E-5 Xe-133s 1.0E-5 4.7E-5 Xe-133 1.1E-3 1 3.3E-3 Xe-135a 1.1E-4 2.3E-5 Xe-135 6.1E-5 7.8E-5

         .               Xe-137               4.8E-3                           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.

N/A N/A RSP-0008 REV. O PAGE 64 0F 112

e . . 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 radionuclide specific. These effective factors, which are based on the typical radionuclide distribution in the rele'ases, 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,gg, (L + 1.1M),gg, M,gg, or N,gg 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 l 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 =

                                                                             )                   Kg        . f g

i where: I K,gg = The effective total body dose factor due to gamma emissions from all noble gases released. Kg = The total body dose factor due to gamma emissions from each noble gas radionuclide "1" released. f g

                                    =                      The fractional abundance of noble gas radionuclide "i" l                                                           of the total noble gas radionuclide.

4 ) N/A N/A RSP-0008 REV. O PAGE 65 0F 112

  - - - - - -,w.      - . - . .     - - - , . , . - , . -              -------,,---,-w.----_,,-,--~,,r-n-w       -
                                                                                                                            - - - - . , , - , - - , , , - - - - - - -       - - , , - - , -,-n-   g-,-----r,
   . 4 TABLE C-2        ,

TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS (Continued) , EQUATION C-2 (L + 1.1 M) ,gg ={(L +g 1.1 Mg ) .f i where:

                               =

(L + 1.1. M),gg The effective skin dose factor due to beta and gamma emissions from all noble geses released.

                               =

(Lg + 1.1 Mg ) The skin dose factor due to beta and gamma emissions from each noble gas radionuclide "i" released. EQUATION C-3 M,gg ={M g . f g i where: .

                   =

M,gg The effective 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 radionuclide "i" released. EQUATION C-4 N,gg ={Ni g

                                                 . f g

where

                   =

N,gg The effective air dose factor due to beta emissions from all noble gases released. Ng = The air dose factor due to beta emissions from each noble gas radionuclide "i".

                                                               \

l 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 l 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. L N/A N//h fW2-gw6c nrm _A N

4 O TABLE C-3 , EFFECTIVE DOSE FACTORS FOR NOBLE GASES TOTAL BODY EFFECTIVE DOSE - K,gf Main Plant Radwaste Building Exhaust Duct

  • Exhaust Duct 3 3 Year K,gg (aree-m /uCi-sec) K,fg (mrem-m /uci-sec),

Projected ** 5.56E (-5)*** 8.05 (-5) Main Plant exhaust duct contains contributions from Fuel Building. Projected values from RBS FSAR. When RBS becomes operational, actual release rates reported in semi-annual < affluent report should be used to generate effective dose factors.

 ***     5.56 (-5) = 5.56 x 10 -5 1
                                          ~.

4 N/A N/A RSP-0008 REV. O PAGE 67 0F 112

   . e 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 3 Year (L+1.1M),ff (aree-m /uci-sec) 3 (L+1.1M),f f (mrem-m /uci-sec) Projected ** 1.36E (-4) 1.59E (-4) Main Plant exhaust duct contains contributions from Fuel Building.

       **     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.

t N/A RMA FKi-/W#60 OFBL_/a rVVa~LJV116R_JUL9

TABLE C-5 EFFECTIVE DOSE FACTORS FOR NOBLE GASES AIR DOSES M,gf and'N,ff 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 Y*** 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.
 **    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.

1 l l l L W W 5%%i=l#X00 M M

APPESTIX D , EXPECTED GASEOUS RADIOhTCLIDE . MIX'It'RE G S e g G e s e e O N/A N/A RSP-0008 REV. O PAGE 70 0F 112 - _

S e EXPECTED RELEASE OF RADI0 ACTIVE NOBLE GASES IN GASE0C5 EFFLUENTS FROM RIVER BEND STATION FSAR* - Containment Building ** Radwaste Building Nuclide - Ci/yr Fraction Ci/yr Fraction Kr-83m 4.7(-2) 1.07(-5) 1 --- Kr-85s 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-133a 6.6(-2) 1.504(-5) 1 --- Xe-133 2,340 0.533 220 .19 Xe-135 693 0.158 280 .24 Xe-135m 140 0.032 530 46 Xe-137 380 0.087 83 .07 Xe-138 208 0.047 2 1.75 x 10 ~3 4,389. 1.0000 1,144 .99

                                                                                                                  ]
  • RBS FSAR Table 11.3-1
   **  Containment Building contains releases from Fuel Building e

g G e 9 i l O e h N/A N/A RSP-0008

                                       . _ - - . , - . ~ _ .

REV. O._ ,PAGE 71 0F._112 _

APPENDIX E X/Q AS D/Q VALUES FOR RESTRICTED 4REA BOIJNDARY

               *w           a e

e S g O e D

  • s 4

e N/A N/A RSP-0008 REV. O PAGE 72 0F 112

1 i . Long Term Diffusion Estimates , E.1 Ob j ect ive- , Annual average CHI /Q and D/Q estimates for continuous and intermittent releases gare calculated for each of the sixteen 22.5'deg sectors at receptor locations used to determine the maximum individual and popu-lation doss ieceptors'. 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 , Nomenclature

                                          ~

1 2.032 = (2/w / ) (2w/16) 1

                                                     .                       (dimensionless) w            =      3.14159...

(dimensionless) exp = ' 2.71828... (dimensionless) E = Entrainment coefficient (di'mensionless) . T D = Terrain recirculation factor T x = Downwind receptor distance (m) o = Vertical dispersion z (plume spread) coefficient (m) u = 30-ft average wind speed 30 corresponding to a given hour of onsite meteoro-logical data (m sec'1)

                           ~      '

l - u = 150-ft average wind speed 150 ! corresponding to a given ., ( hour of onsite meteoro-

                                                                                     ~

! logical data (m sec ) l

                  =      Average concentration (CHI /Q) normalized by source strength                                             (see a-3)
 ,         N/A        N/A                   RSP-0008                        REV. G     PAGE 73 0F 112
                                                 +          .
                                                                ------c-m--              9 -- --. --- ----v   p-   --,,--m-g        -,a+

(CHI /QD ) = Depleted CHI /Q (see m'3) F = Momentda flux (m' sec'3) 3 . h = Maximum adjacent - b

                                   . . . building height                                     (m) h,                 =        Release height                                      (m)
                                  =

h, Effective release height (m) h,p

                                  =        Nonbuoyant plume rise                               (m) hg                 =       Topographic height of receptor above plant grade                         (m) d                  =        Stack or vent diameter                             (m)
                                 =

u, Efflux velocity (a sec-1) N = Total number of valid hours of onsite wind data in all sectors for appli-cable averaging period (dimensionless) 8/Q = Relative deposition rate , normalizwd by source strength (m'1) . 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) I k = Index for a particular receptor distance (dimensionless) 1 = Index for a particular 22.5-deg sector (dimensionless) n = Number of hours onsite . wind data in a particular l 22.5-deg sector (dimensionless)

                                                                                                   ~
    ,         S                  =        Stability psrameter                                 (sec )

N/A N/A RSP-0008 REV. O PAGE 74 0F 112

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 s,traight-line airflow (Gaussian) model described in Regulatory Guide 1.111, Rev. 1. An adjustment was made to the model to characterize the regional airflow partirn. The equation of this model is as follows:

                                                                            =

i Sp (1*t -h ('a .h / t at e t .unf,8.(g, -,,(.,je.+)s. E.3 1 Since the River Bend Station site is located in relatively open terrain, the terrain recirculation factor (Q)k (Presented in Figure 2 of Regulatory Guide 1.111) was applied. The entrainment coefficientT(E ) is a functi n f the ratio of efflux velocity (u,) to elevated wind speed (u150) f r the conditionally 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 y nearby structure, a conditionally elevated release is assumed, and the ) entrainment coefficient is defined as follows:

                  =                         > 5.0 E

T 0.0 when u,/E 150 (totally elevated) E = T 0.30-0.06 (u,/E150) when 1.5 < u,/E 150 $ 5.0 (partially entrained) E T . 2.58-1:58 (u,/E150) when 1.0' < u,/E 150 f 1.5 (Partially entrained)

 .           E T
                  =

1.0 when u,/u150 $ 1.0 (totally entiained) E.3-2 N/A N/A RSP-0008 REV. O PAGE 75 0F 112

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 froe 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 = a hr - (h )k t + hpr 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 heightg 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 algoriths: when: m u,/u150 I* u, 2/3 x 1/3 h pr

                         =     1.44                                                                d            E.3-4 d
                                   .                          150 0

6 i N/A N/A RSP-0008 REV. O PAGE 76 0F 112

s . when: , u,/ 150 *

  • u, 2/3 x 1/3 .u,} E.3.4 h = 1.44 d-3 1.5 pr d u 150 150 ud - -

h,p 5 3 d E.3-6 "150 The result from Equation E.3-4 or E.3-5 (whichever condition exists) l is then compared to Equation E.3-6 and the smaller value ofph ,is used. For E-G stability conditions, Equations E.3-4, E.3-5, and E.3-6 are compared with: - h,=4(F,/s p and, I/3S - 1/6 h,=1.5(F,/150 p where:

         ,..    ("Y 

4 ' and the smallest yalue Nas chosen. 9 i N/A N/A _ _ RSP-0008 _ _ _ _ REV. 0_ .

                                                                                       .PAGE_77_OF_833____

I I In the ground level portion of Equation E.3-1, the vertical dispersion ters:

                                                     'z           +   0.5g /w      I                                             '
                                              ..         1,k ,
          ,        was constrained to be less than or equal to 1.732a,

, ik E.4 (CHI /Q) and D/Q Modelina Techniques Annual average depleted relative concentration values were conservatively assumed to be equal to annual average relative eref re, no credit was concentration values (CHI /Q = (CHI /Q)D). taken for attendant plume depletion of radiciodines and particulates. Annual average relative deposition values were calculated using Regulatory Guide 1.111, Rev. I with the following equation: kt k ok " i", n 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 value. E.5 Methodolony 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, 1 hour value was plotted at 2 hours on log-log coordinates, while the annual, average value was plotted at 8,760 4

hr. A straight line connecting the two points was drawn.

3. Log-log interpolation based on total ground. intermittent release hours versus annual hours y:e ded a CHI /Q multiplier.
4. The multiplier was appliec :: innual average CHI /Q and D/Q values to obtain intermittent CH: . end D/Q values.

For River Bend Station, a 320 hr yr :ntermittent release through the containment building vent frem t e mechanical vacuum pump was

           ,      evaluated.

N/A N/A RSP-0008 REV. O PAGE 78 0F 112

s . TABLE E-1 ,

                                                    ~

3 AEUAL A ERAGE CHI /Q VALUES x 10 (sec/m ) FOR RESTRICTED 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 WhV 29.1 384 hV 14.4 262 Nhv 12.1 138 N 15.0 180 h%I 20.0 211 NE 12.9 150 Eht 9.86 146 E 7.37 168 ESE 8.33 154 SE 6.99 93.1 SSE 6.53 45.6 - 1 l p G e N/A N/A RSP-0008 REV. O PAGE 79 0F 112

+ TABLE E-2 ANNUAL AVERAGE D/Q VALUES x 10,(m-2) FOR RESTRICTED AREA BOUNDARY 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 - e e g S e e 4 E N/A N/A RSP-0008 REV. O PAGE 80 0F 112

i l e o APPENDIX F , MAXIMUM X/Q AND D/Q VALUES FOR INDIVIDUAL LOCATIONS I 9 e i g S e d

                                           't e

O N/A N/A RSP-0008 REV. O PAGE 81 0F 112

IA Br F-1 . . AIMOSPHEQlc OISP[2S10N AND O( POSill006 RAIES FOR THE MAXIMUM IIIDlulDUAL DOSE CALCULA110NSS location Radweste Ridg. Main Plant Analysis imeleI13 inhaust Duct Exhaust Duct Camme ai r dose ( I) 953 m WNW (containment) Call /Ql(5) - 384.0 CH1/02 - 29.1

  • Cnd Beta Air Dose Maximum Receptor (2) 1,260 m NW Call /Q1 - 205.0 CHl/Q2 - 13.0 Resident same D/Ql(6) -

31.0 D/02 - 7.01 Ca rgen Same Mes t an i me l Same g immersion Same

  • R3sisent ( 3) >

2,Odb e NW CH1/Q1 - 75.5 CHI /Q2 - 4.57 Ca r$cn Same D/Q1 - 10.1 D/Q2 - 2.32 Milk animal 5.200 m ESE CHl/QI - 4.35 CH1/Q2 -0.44

  • D/Q1 -

0.38 D/02 - 0.15 Hypothetical milk 1,173 m NNW Cill/Q t - 138.0 CHl/Q2 -12.8 cnimal (4) D/QI - 24.7 D/Q2 - 9.92 Onn a to garden (1) 960 m WNW Call /Q1 - 388.0 CHl/Q2 - 32.8 D/Q1 - 46.3 D/Q2 - 11.8

  • Dar. Table 5.4-l RBS (R-Di S and Reference 1.2.18 '

Notsu ( 1) Maximum orrsi te location (property boiendary) witte liighest CHl/Q (unoccupied). (2) M2ximum occupied orrsite location with liighest Clll/Q aged D/Q. (3) Maximum occupied location associated with maximum milk cow grating pasture. - (Q) Hypothetical maximum grazing locatiosi for milk cow (see (3) above). This location should be used for cow milk, goat milk ~patleways dose calculations. (5) All Cill/Q = 10-7 sec/m3 (6) All D/Q = 10-9 m-2 ( F) Maximum receptor vegetation pathways dose calculations should be made for this location. . b/A N/A RSP-0008 R[V. O PACE 82 Or 112 O e 4

APPENDIX G , INSTANTANEOUS DOSE TRANSFER FACTOR. TABLES e - e

                   *a         .

O e

                                                                                                                                            .1
                          ,     e.

e 9 4' N/A N/A RSP-0008 REV. O PAGE 83 0F 112

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APPENDIX H , GASEQUS MPC VALLTS - E o 1

                                                                                   )

l i l p 4 e e N/A N/A RSP-0008 REV. O PAGE 85 0F 112

TABLE H-1 MAX MUM 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-83e 3 E-6 Zr-95 1 E-9 Kr-85e 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-113a 2 E-7 Xe-131a 4 E-7 Sn-123 1 E-10 Xe-133e 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-129s 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 Co-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, Coluta I. "

None (as per 10CFRf0, Appendix B) "no MPC limit for any single radionuclide not listed above with decay mode other than alpha emission or spo.ntaneous fission and with radioactive half-lives less than 2 hours." 0 i N/A N/A __ _ _ _ RSP-0008_ _ _ _ , REV._0__,,PA.GE 86__OF_112, _ _ _

4 O APPESTIX I ENVIRONMESTAL DOSE TRANSFER FACTORS FOR GASEOUS EFFLLThTS u . t 1

                                                                                                                                                             . i l

i e ) i I I i N/A N/A RSP-0008 RIV. O PAGE 87 0F 112

                   .                                                         I Aal f I-l

[NVillONMf CI AL PAllWAY - DOSE CONVf CSION TA e0R3 C(i) TOR CASE 005 CISCHARGE PATHWAY a lleHAL A1104 ACE GROUP = Aout i - shaclide 1. sody organ Dose Factors (aree/yr per uCi/m*) Gl-Iroct sone Liver Kidney Thyroid Lung Skin MM-54 6296 77360 0

  • 39600 CD-60 14800 9840 0 .14t+07 284800 0 11520 0 0
                                                                                                                                         .0

, IN-65 46560 53440 32400 103200 68960

                                                                                                                         .5968[+07       .0 54-8)             8 F20           349600                                                               0               864000 SR-90            .61[+0F          7220F4 304000
                                                        .992653E+08 0

0 0 0 0 .44[+0F l' 0,1 9 CS-133 728000 10400 0 .96063E+07 .0 4 ' 3F2800 848000 287200 0 3 CS-337 428000 8400 478400 620400 97600 .0 SA-140 2568 I 222400 0 75200

                                    '218400              39040 -         49.04              16.F2          0
                                                                                                                                         .0 C[141             1528         '120000                19920           13520             6264
                                                                                                                         .12F2[+0F       .0 1-131             40960           12560                                                                0               361600         0
  • 50400 66F20 122560 2.38r+07 0

! l-133 9040 37760 4 17240 29600 51280 .0 . t-3 1.26E+03 4.3[+06 0

  • 1.26E+03 ) , .0 1.26E+03 1.26E+03 1.26E*03 1.26E+03
                                                                                                                                         .0 1                                                                                                                                    1.26E.+03 1

t Batos ose I ut. e / se. 'essense e s t e of 'esch nuc l ide ( i ) and a va lue of 1.0 for M/Q and rela t ive depos i t ion.

; 39111 the units for C-114              and H-3 are (mRee/ year per uCi/m3).

k I I i t/A N/A RSP-0008 REV. O PACE 88 0F 112 4 i j . I J e

IABLF 1-2 ElfvlROISIE*,*;IAL eATISMY - DOSE COIIVEZSIOst FACIORS C( l) FOII CASE 005 CISCHAACE PAIHW . s eestALAl leet , ACE CAY 00e u((u ! Organ Oose Factors (mres/yr per uCl/e') 1 aluclide 1. Body Cl-T ract Gene Liver Kidney Thyroid lawig Skin i t post-54 8400 66800 0 - $1120 12720 0 .1984E+07 .0 ] C0-60 19840 259200 0 15820 0 0 .8121+0F .0 4 IW"5 _ 62400 46640 38560 133600 86400 0 .324E+0F .0**

!     SA-C9                   12480                     311200                   434400                       0                   0                   0              .2416E+0F 5A-90                  .664E*07                    764800                '108E+09                        0                   0                   0 p.0
                                                                               ,                                                                                     .3648F+08       .O j     CS-133                   548800                    9160                  . 502400                      .1I28E+0F '           3F5200              0                I46400        .0
  • 4 CS-137 331200 8480
  • 670400 848000 304000 0 120800 .0 8A-140 3520 228800 9 54720 . 68.64 22.8 0 .2032[+07 .0 C-141 2168 126400 28400 18960 8880 0 6I3600 .0 4

t-138 ' 5.28E*04 1.30E+04 7.09E+04 9.82E+04 1.68[*05 2.93E+07 0 .0 i B-133 l.24E*04 2.06E+04 2.43[+04 4.10E*04 7.18E+04 5.84E*06 0 t.0

  • M-3 1.2i[+03 1.27[+03 ,. ,
                                                                               .0                           1.27E+03              1.27E+03           1.27E+03        1.27[+03    l.27E+03
)
. Based on I eet / sm.                              . e ese s e t er or each nuclide (I) and a value of 1.0 for X/Q and relative depositiosi.-

i 4011: l ei . ... . t . s... . -i% .. s is- 3 a re (onee/ yea r per uCl/m3). ' i .t t i I i I i 1 4 i j t/A N/A RSP-0008 REY. O PACE 89 Of 112 l 1 I i i:- ' i i 4 I l kamend

_ - - -. ~ . . ~ . .- - . , _ - - -. -. IAhlt 1-3

  • ElevillosetECIAL PAIHWAY - DOSE ColevtMS1001 IACI0fts C(i) los MSEcuS DISCHAACC j PAIHWAY = IIeHALAl lOld ACE Gft00P = CHILO l

aluctide 1. Sody Cl-T rac t Organ Bone Dese factors (ares /yr per uCi/e sy t.ive r Kidney 1hyroid Lun9 Skin .

 ! sees-54                 9509            22903               0                 42920 Co-60             22644           96200               0 10027             0             .I5162E+0F         . 0 *.

20-65 13135 0 0 70300 16311 42550 133220 71410

                                                                                                                                       .7067t+07      60                          t Sa-83             17242           161240              599400           0 0               995300         40                        '

Sa-90 .644E+07 0 0 .215FIE+07 343467 30104tt+09 0 0 0 '. CS-334 224590 384a 651200 O .I47616E*06 .0 CS-33F 828390 ,'3618.6 5 .lol3st+0F 330410 0 120990 906500 825500 282310 0 8A-103 4329 108T50 14000 64.75 0 10J910 .0 CE-141 2897.3 56610 39220 21.27 0 .I142iE+07 .0 8-131 19536 8547

I-133 5.45E+04 5. 64E +b3 9.62E+04 9.62[+04 1.5aE+05 0

3.25E+07 543900 *

                                                                                                                                                       ..e
  • 1.54E+04 1.10E+04 T. 3.32E+04 4.06E+04 0 .0 M-3 1.12E+03 1.12E+03 0
  • 6.76t+04 7.70E+06 0 .Q 1.12E+03 1.12E+03 1.12L+03 1.12E+03 1.12E*03 1'
! Sated on I uC4/sec sesease rate or each nuclide (I) and a value or 1.0 for X/Q and relative deposition.

5 Igq[{: ilee un i t s f o r C- 14 a nd H- 3 a re ( mRee/ yea r pe r uC l /m3 ) . 4 T i t l i I j .- i I l 4 1 1- ? C/A N/A RSP-0008 R[V. O PACE 90 Or 112 i . 4 0 4 1 i e

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t I AHl f I-1 , , [NVIRONM[CIAL PAlllWAY - OCSE CONV[T.SION FACIORS C(i) IOP CAS[0US CISCHANCE PAIHWAY a COW MILE ACE CROUP = IEEN Organ Dose Factors (m2-eres/yr per uci/sec) Nuclide 1. Body Cl-Iract Bone Liver Midney Thyroid Lung Skin MN-53 .22f*07 227521E*08 .0 .l1094[+08 .33094E+07 .0 .0 0 .. CD-60 .498[*08 .283896E*09 .0 .237964E*08 0 .0 0 0 . IZ-65 .304[+10 .275979E*lO 187618[+10 .651661[+10 .417063E+10 0 0 0 0 j1

                                                                                                                         .0     '

SH-G9 .646[+08 .268654[+09 22558FE+10 .0 0 .0 . 134[+31 .352302[+10 .542537[+11 .0 .0 .0 .0 0 SR-90 CS-134 .836[*10 .224092E+09 % .7655FIE+IO .180188[*11 .572578E+10 0 .218604E+10 .0 CS-33F .496[+10 .20260$[*09 10703FE+11 . 3 84? 391[+ 11 484532E+10 .0 38821[+10 ,.0 uA-140 .297[+07 .710852E*08 460918E*08 56418.7 19150.8 .0 3799F.1 .0 C[-l%1 594.76 .348107f404 7755.2 5111.91 2437.35 0 .0 .0

  • 1-131 3.96[*08 1.46E+08 *
                                        . .5.26E+08       7.38[*08             1.27[+09     2.16[*11        0            .0            '

J-133 3.66[*06 9.08[+06 - f.04E+06 1.20[*01 2.10E*07 1.68[+09 .0 0 H-3 6.16[*02 6.16[*02 .0 6.16[+02 6.16E*02 6.16[+02 6.16[+02 6.16E+02 C-14 1.35[+05 1.35[*05 6.67E+05 1.35E*05 1.35E*05 1.35E*05 1.35[+05 1.35E+05 6azed on a uCl/sec rolesse rate of each nucIlde ll) and a value or 1.0 for X/q and relative deposition. Mot 2 Ihe units for C-14 and H-3 are (ares / year per uCi/m3). i.e. X/Q values are to be used when calculating doses f rom 11-3 and C-14. N/A RSP-0008 REV. O PACE 94 or it? t/A

l Apl i 1-O' EleVIROIIMICI AL PAlllWAY - DOSE C0tIVf RSIO88 TAC 10RS R FOR CASIOUS CISCHANCE PAIHWAY = COW MILIL ACE CROUP = CHIT 0 Or9an Inose Factors (m2-eree/yr per uCl/sec)

  • Nuclide T. Body Cl-Tract Bone Liver Ridney Thyroid Lung Skin MM-54 441E+07 .338954E*08 0 .365568E+08 .464211[+07 .0 .o .0 C3-60 .999E+os 381633E*u9 0 .338163E*08 .0 .0 .o .o ,;

23-05 .681E+10 .ll2533E+10 .368753E*10 .982445L+10 .619075E+10 .0 .o .it g SR-G3 .359E*09 .215515E+09 .556718E*lo SH-90

                                                                       .0                  0              0            .0           ou r .

CS-134

                  .233E*ll
                  .6 TIE +IO
                                .123798[+10       .919026E+ll          .0                 .0         .  .o             .o           . 33            I
                                .356844E+0_3      . I l65 t lE + l l   .289659E+11        .897642E+10   .0             .322095E+10  .o CS-13F             .364t+10        454424E+w         251636t+11         .246606t+11        .503636E+10   .0             .289952E+10  .O BA-840             .649f*0F      .563359E+08         3112E+09            91436.9            31714        .0              58075.5     .0 CE-831               1410        .lI8459E+08         19039.8             9495.92            4162.86      .0             .0           .o 1-131            7.3E*08     1.14E+0d            1.28E*09            1.28E+09           2.lE+09        4.24E*ll        .0 l-133            8.04t+D6    8.56E*06        ;   1.72E+0F
                                                                                                                                    .0 l          l 2.12E*07           3.54E+07       3.94E*09         0             0 c-3               9.73E+02    9.73E*02       - -     0                9.73E*02           9.73E*02       9.73E+02      9.13f*p2      9.73E*02 C-14              3.32E+05    3.32E*05            1.66C+06            3.32[+05           3.32E*05       3.32E*05       3.32L*n5     3.32[+05 Based on I uCi/sec release rate or each nuclide (1) and a value or 1.0 for M/Q and relative deposition.

Itate1 The units for C-14 and H-3 are (eres/ year per uCi/m3), i . e. M/Q va l ue s a re to be used when ca l cu l a t i ng doses from H-3 and C-14. t/A N/A RSP-0008 RIV. O PACE 95 of 112 W

e e t

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            *= W       Q      t               e a e r= c= M *=     to

IABLI l-13 EltVIR00We[CIAL PAIHWAY - OOSE COIIVECSlose FACIORS Cli) FOR CASEOUS CISCHARCE PATHWAY = COAI MILK ACE GROUP = A00LI leucl ide 1. Body Cl-Iract Organ Dose Factors (m2-aree/yr per uCl/sec) Sone Liver Midney Thyroid Lung Skin CO-60 .341E+07 .290428E+0a 0 .154606E+07 .0

               .152E*06                                                                          .0           .0            .0 Mee-54                         .244037E+07         .0               796606             237064      0 FC-05            21t[+09        294066E+09         .14673f+09                                                  .0              0                ',*

EA-89

                                                                 .466868[+09       .312256E+09   .0           .0              0
               .738E*08       .432432E+09         .257131E+10    .0 58t-90          .598E+I1       .233129E+10         .806903[+11    .0
                                                                                   .0
                                                                                   .0
                                                                                                 .0
                                                                                                .0
                                                                                                              .0           .0            {t ,

T4-134 .257E*11 .550107E+09 .0 .0 ..

                                                 .332318E+11     .334347E+11       .301734E+11  .0            .337711E+10  .0 W 137           .159E+Il       .469874E+09         .377483E+11    .242731E+ll       .82395E*10 bA-840           20I000        .631714E+07E       .306789E+07
                                                                                                .0            .273908E+10  .0
E-Ib1 3453.76 1310.28 .0 2206.47 .0 38.936 331233E+07 507.578 343.266 159.432 .0 l-131 2.86E+08 1.31E+04 3.48E+08 4.98E*08 8.52E+04
                                                                                                             .0            .0 1-133         2.46E+06                                                                          1.63E+11        0           .0 7.26E*06*'
  • 4.64E*06 S.06E+06 1.41E+07 1.19E*09 a-3 9.65E+02 9.65E+02 * ..e 9.65E+02 9.65E*02 9.650+02
                                                                                                             .0 9.65E+02
                                                                                                                           .0' 9.65E+02 l- 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*t uC4/sec release rate of each nuclide (1) and a value of 1.0 for M/Q and relative deposition.

pto; The units for C-14 and H-3 are (area / year per uCi/m3), i.e. M/Q values are to be used when calculating do se s f rom H-3 a nd C- 14. i N/A N/A RSP-0008 REV. O PACE 97 Of 112 a

IAaEE l-Il ENVIRONME NI A PAlHWAY - DOSE CONVERSION EAC10RS Rii) EOR CASE 005 DISCHARGE PAlllWAY = COA l M i t K CE GROUP x EEEN hcIlde 1. Body Organ Dose Eactors (m2-eres/yr per uCl/sec) Cl-I rac t Bone Liver Kidney thyroid Eung Skin l l EM-54 264000 .273026E+0F .0 .333128E+0F 39F128 .0 LO-60 .0 .0

              .59E+0F          .34883FE*08       .0            .261912E+0F        .0            .0           .0            .0         .*

f -05 .365[+09 .333356E+09 .225338E*09 .782422E*09 .50075E*09 .0 .0 .0 W-C3 .336E*09 .56558FE+09 .47492tE+10 LR-90 .282E+33

                                                               .0                  0            .0           .0            .0 t(   e.
                              . 32051FE*10         314816E+12  .0                 .0            .0           .0            .0 l5- 13 3       .25E*ll                            .228939E+ll   .53884E+18         .171225E+11 i

l2H 13 7 .449E+ll .670531E+09'

                               .608632E+09e      .328541E+J1
                                                                                                .0           .653F2E+10    .0
                                                               .42F F65E +11      .345555E+11   .0           .565568E*10   .0 A-140         356000            .852066E+07       .552488E*01    6769.84            2295.52       0            4552.33
.E-131       F1.37                                                                                                         .0
                             .lFFF25E+07          930.609     628.339              292.4F7      .0           .0            .0
 -131        4.76t+08        1. FSE *08.'      6.32E+08       8.84E+08           1.52E+09
 -133                                                                                         2.58[+12       .0            .O.-              .'

4.40+06 1.09E*07 / 8.48E+05 1.44[+0F 2.52E*07 2.00E+09 .0 .0 l-3 1.26t+03 3.26E+03 .0 1.26E*03 l.26E*03 1.26E+03 1.26E*03 1. 26 E +0 3-

- 13 1.35E+05 1.35E+05 6.76E+05 1.35E+05 1.35E*05 f.35E+05 1.35E+E. 1.35E+05 3 sed oss t ute/me. .....s. ..se or each nuclide (i) and a value of 1.0 for X/Q and relative deposition.
 ;LO; the unets f.sr 0 - 84 ared 18-3 are (ares / year per uCi/m3). i.e. X/Q values are to be used when calculating doses f rom 18-3 and C-14.

C/A N/A RSP-0008 REV. O PAGE 98 Of 112 e

I Ast f 1-12 EIWlH00ge[OIAL PA1HWAY - DOSE COINE021000 FACI 0ftS C(l) TOR CASEOUS RISCHARGE I PAiedWAY = COAT selLK J ACE CAOUP = CHILO l organ Dose f actors (e2-eree/yr per asCl/sec)

  • saucaldo T. Body Cl-Tract sosse Liver Kidney Thyroid Laang Skin 9

fee-54 530000 .166996E*0F .0 198982f*07 557895 0 .0 0 4 00-60 12[+0S .225385E*04 0 .406923E+0F 0 .0 .0 .0 ./ l20-65 .733E+09 .206944E+09 442383E*09 .117861E+10 .742687E+09 0 .0

' 58t-89               .335E+09           .4540F2E+09                .317294E+11          .0                         0                    .0             .H                 0 f .*
                                                                                                                                                                           .0 r
. 54-90                .489E*11           .259887E+10                  19298F7+12          0                         0                    .0              .0               .0                e' i C5-134                .laiE+11           .467667E+09                .52866FE+ll          .86F556E+11             .268452E+11             .0           . %4 Fo4E +10        0 lCS-337               .109E*18              46242est+0W              .773493t*11          .738463E+11                2es0649E+11          .0           .865866E+10         .0 l84-140                       FF9000      .6F6204E+0F                  1334F4E+0S           18693                    3806.F               .0             69 FO. 9          .0
CE-l'H 1F0 .142823E+0F 2295.58 1144.9 501.905 .0 .0 .o i8-131
  • 8.76E+0S 1. 3 FE +0e 1.53E+09 1.54E*09 2.52E+03 5.10E+11 0 .0 t j6-133 9.66E+06 1.03E+0F 2.12E+07 2.56E+0F 4.26E+07 4.F4E+09 .0 .0 1.99E+03 1.99E+03 I .0 1.99E+03 1.99E+03 1.99E*03 1.99f+03 1.99E+03
)jC-3 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 os. I a.C e / se. war... este ut eacts nasclide (i) and a value of 1.0 for X/Q and relative deposition.
get n t he un e t s 8 ser C- l4 anst H-3 a re ( aree/ yea r pe r esCi/m3 ), i . e . X/Q va l tees a re to be tesed when ca l cae l a t i ng j doses f rom 88-3 ased C-14.

l . a l N/A N/A MSP-DOO8 REV. O PACE 99 Of 112 I + i 1 4

/ .

l

  • 1

e 1 ABI E l-13 EleVIR0eIMI CI AL PAlldWAY - 00SE C0elvtCSION EACIORs Cli j IOS CAST 005 CISCHAftCE PAlHbe4Y .= COAL Milk W G80MF = 1Off ANI Organ Dese Iactors (m2-eree/yr per asci/sec) baclide I. Body Cl-tract Bone tiver Ilissney Thyroid

  • l eing Skin h-54 .838E+o6 3 3*>82 FE+07 .0 .369161E+0i .819419E*06 0 .o .0
0-60 196t+08 .1915 3 7 E +08 0 .830838(+0F 0 .0 .O .O ,.'

'se-O .939E*o9 371989E+10 .59313?[*u9 .203651t+I0 .987402E+09 .0 .o 0 . Jt-89 .64t+09 .45866FE*09 .2231.l lt + 81 .0 .0 .0 .0 .0 LY. Wt-90 .53SE+Il .262389E+10 .2tol38t+I2 .o .0 . 0 .o .o ..

5-134 .16tE+33 .433113E*09 .854881E+ll .lS9413f+12 .410437t+13 0 .3682S6t+11 .0
S-137 .302E*ll 449931E+09 9 .32296SE*12 .14393t[+12 .386328E*ll .0 . 3 568e 16t + l l .0 A-140 .141E*07 .67289tE+07 .273618E*08 21367.8 6491.84 .n 16804.8 . Il T-131 326 .143094E+0F 4540.92 2169.56 853.947 0 .0 .0
-131          1.66t+09        1.3SE*08.*            3.2[+09            3.78t*09                 4.4E+09             1.24[+12        .0                  ou .*            ..
-133          1.86t*01        1.071*0F         .-' 4.36E+0F            6.36E*nt                 F.46E*pF            1.161*10        .0                    0 l- 3           3.01t+03        3.plE*03               .0                3.01E*n3                 3.01E+03            3.ull*o3        3.0l[*03           3.01E*03
- l *l 6.951+0S - 6.958+0S 3.26E+06 , 6.95E*05 6.95t*05 6.951+0S 6.958*uS 6.95E+uS' m sed os. I sec s / sec s er e era se s e te o f eacle nuc l ide ( i ) and a va l tse o f 1.0 for X/Q and re l a t i ve depos i t i on.

M el I he use i t s f ea r C- 14 a nd H-3 a re ( a ree/ yea r pe r uC i /m3 ), i . e. X/Q va t tee s a re to be tesed when ca l cte l a t i ng doses from H-3 ared C-14. II/A N/A HSP-0008 REV. O PACE 100 of I12

e e t 6 s s

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w C. O. C. O. C. O. O. O. O. @. m. N. @. e m~-e L O . W d 5 - 1 e a m em u e E e > O CO O d C + ++ 0 m NA + w ww-e  % W

                     =g          W       m                     -NX      X         e             .

a Q. ~ @ "S 0m N.W* ~C 0 0 3 3

         =           .D          X N              NeMe+e++              b        =
         =              =        c e              M=-mwwww               0        e                    **       .

E bX @ m O@XNNQQ~ w > e m a .O.s.C.C.m.N. e m =.N.N.@* O E Nm-e O.  % C . O b - X .

         -           h                                                  w                          >

u  % . w c 4 5 mem em O

e. E
     - w             e           COO              CO e             w           +++              ++                     e       =
     -    2           5          www              wwm@

O eb -ce @m NM = *

     - =             NO          Oms              mom*N.~0 = O C         e a

m

      =

M g e> w.=

                                 ~Ne s%m
                                                  ~3@C+C++

me~eweww E 2 w a i oc~ cc~emwo~ e  %

     =    >           a b          o. .~.C.O.@.~.N @ N.N.N.4              g
                                                                                 =

O

  • O -e-e C 3 a e o b e

w e a e m m mm mee = w a O O CO C00 O 8 d e ++ +++ e b e e e---mm e b e og Q. w w C w w w m.%O 4-+-2~20- O V

                                                                        ~e O

h d

         >                               e-wemeO*C                  +   =        %                 E 2

c3 e Non-e@mwe N-@C~NCOW w X g y a 9 2 m C 6

         -            6          C.O.N.N.e.a.c.N.- e.N.O.W.                        E
          <          O                                       em N        a        w A                                                              u
e. *e. e e a # k
          <                      emme See                                          e
          -                       COCO COO                               b m

E d ++++me++q O

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e -c

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s

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e me~e@e@@@www+ O~ w 2e-su

          >               o                                               e                         <

E w

                                  -.o.m.N.
                                      @ N ee .oe - CNa m ,8.N.e.m.
  • e . ,e2I
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z e ee

                                                                         -        um o

me~Cmm~ - 6e h O O Q = C, O O e-Ne

                                  ~C++++                                           Q=
c. o w
                                   *wwwwwww + + m.O             QQC
                                                              +e++                     s
               -m         E        w--@sce@Cww                      w     .e       40
   .           <w                  -Q4-@a@,mNOO~

ab

                                                                                  =w ww            .
                                   - .- .m. 4. . ,. N. . ~ 4 4. N. @.

x- N 4--e

y. g=
               =n A

ee 40 e me

               >8
               <g         a e

s-C-O 'h = e m o m m a g e= m 9 .a  %

               $v
               -w g

c

                                   # 3 4. e m. e e e .. m m.- m ,

e e e e z 49 = I C

  • M E *
  • 4 w e e ' .e 2 2

IABLE l-11 E NVlf:081MENI AE PAIHWAY - 00SE CONVERS1001 f ACTORS R( 8 ) IOR CASEOUS DISCHARCE 'A lifWAY m MEAI CE CROUP = ClllE D Organ Dose Eactors (m2-ares /yr per uCi/sec) kcl ide 1. Body Cl -I rac t Bone Eiver Kidney Thyroid tung Skin bM-54 .169E*0T .532498E*0F .0 .614498t+07 .lF7895E+01 0 0 .0-60 36f*09 .300513E+09 .0 .542564E+08

                                                                                                                                                                             .0       .'
                                                                                                                                  .0           .0             .0             .0 2-15                     .554E+09              .356438E+09                                    .33435?E+09       .890l93E+09       .561322E+09  .0              0             .0 9

4-1 ,R-CO .356t*08 .406154E*u9 ,R-90 .251E+10

                                               .35123tE*08
                                               .31529fE+09                                    .8559tFE*10
                                                                                                                .0
                                                                                                                .0
                                                                                                                                  .0
                                                                                                                                  .0
                                                                                                                                               .0
                                                                                                                                               .0
                                                                                                                                                              .0               0              .'
                                                                                                                                                              .0              .0 2-133                    .249E*09              .636333[+07                                    .719333I*09       .ll8044E+IO       .365815E+09 3-137                   .353E+09               .640606E*07,+                                  .406811E+l0
                                                                                                                                               .0             .331263E+09     .0 A-140
                                                                                                                .lu2301E+10       .3333FFE+09  .0             .II995E+09      .0
                        .243[+0F               .2tu934E*08                                    .41635fE+08        36475.1            188T4.4    .0              21744.7       .0 E-143                            1440          .12098E+98                                       19444.9          9691.96            4251.43 0131                 9.34E+06                 1.46E+06                                   . 1.63E+0F         1.64E*01           2.70E+0F
                                                                                                                                               .0 5.42E+09
                                                                                                                                                              .0              .0           .'
                                                                                                                                                              .0              .0 0333                 2.80E-01                2.80E-01                            * .5.80E-On                7.?E-03             1.18          1.33[*02        .0             .0
-3                   1.45f+02                 1.45E+02                                        .0            1.45E+02            1.45E+02      1.45E+02       l.45f+02     1.45E+02
-14                  1.07E*05                 1.07E*05                                       5.33E*05       1.0TE+05            1.07E*05      I.07t+05       1.011+05     1.0TE+05 ased on 1 uCi/sec relwase rate of each nucIlde (1) and a value of 3.0 for X/Q and relative deposition.
"j g; lhe units for C-14 and H-3 are (ares / year per uCi/m3).                                                           i.e. X/Q values are to be used when calculating doses f rom Il-3 and C-14.

k C/A N/A RSP-0008 REY. O PACE 103 of 132

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o O *M== C 2 w e U  % w e = e e m w ONoce = 4 0 m====c w 3 8 e w C+++++

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e Q e b e gg

                    =-

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( CO =e%44%=wW w 0 E

           }         e              e4323N@Re e                            3    G
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  • C. O. O. O. E 4 O e N *.> R =

b ** U e

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g e esma%4~~ewwww b Ce

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E w mm== a =C

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eb N e= @ messe@me = .

   .= -

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u L Ind e a e e W m = o @ ** N .= O .*== 4 c .= - 0S O e ++++++ 6 . so gg w = e a w w a.4 e ea e e

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o=O7e@hO = he @ ( m m e O o e a= * + + = NU E 23  %@mNm@eww W g S g e =4=@Omm M  % g e

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s. l P= e= C w u m J . ..

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                                     % e a= t% # e C @ X + + + +                             8       98        *
       -                =

e o @ O 2 e m 4 C o isJ 4.3 had eed *= C9 0 == @ N N @ @ a= N N e O M ed

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N N '* N e =* E

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             =

c @SN2

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             ==

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C. C. C. C. O. N. N. = C. O. D. R. D. a

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e U C O @ g C

                                                                                                                                       =

0 u 1 D eh = ome D W

           =

0 e e 43 6 C. C O O a > d Q h ++++ = 3 M L W X, ned a.d ned ned W

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A i w a s e N P= 6 e w h a e s O = e E O

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e O *= ==== 0 t b ++ ++ e. ned E

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O e6 CNe r= == e = e @ m e =

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                            .4                                   e m a = m a m F=                     4      %

E t-

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O O g y 9 a = a N P= C 3 u . e 4.d 4 6 e nn. ll

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8 e ++++++ == w 6 e j g w w d i.e w i.e e e

                      .= .

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3

       =

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       =

6 O C. O. m. m. =. a r= m N O. N. N. e s.6Ee. C. ei%. A *= m M A w u

      =
  • e O 4 CeCamm e 6
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                                                                    +++

b 0 m 4

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m unNm=ceeeOOec e r m e e- m ~ e m +,+ + + a a \ E e e s c a == c @ e % edned w ind e. v=

      =                                                                                             E Ce
                          =

Q MO4memammeemm SU . 2 A. N. a. ..... s= == = == = m. . N. P= s. O. m e 4.s 4 s- ,= N p= a 23

                                                                                                            ==                       %

z = ae X C = 0

               =

SCODNOO e m

               *=

h 6 6e 4 C = = C == = = e h@me O=

              == O                   +++++++0300                                                   o        b e                wledw w nessednd* C + + 0 +0                                  e               S Q=                     == m e m N N @ w m w ame n+.d a.d                             a         #O
              == 3          .        % O @ m 2 M M @ P= a s m am                                  %         d 6-
              >Q          >          ==...= = m. m.e...            m e=.g . e= ..@se              =         =b e = N P=

g. aa 3m e L 3 g.

                                                                                                            .O
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                         =
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              =

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              <                      w ead=e4     = =mmg m a         a A

21EW u e< gw=e==.3 m. y =. O e g a

l  ! l l RESTRIOTED AREA AND NEAR-FIELD ENVIRONMEN A* , l FIGURE -1 . l MONITORING LOCATIONS l l 1- -- i l . l l

        'l'                                                  -

o . R A - - a l I l (NW) - s (NNW) , \ (N) (NNE) I C l l 4, -

                                                                    '                                           '                                                                                                             (NE)        l E

l s \ ' l l P 's

  • s i ' ",

li I

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s i '5 N l 1 's 1 Y, ,' '!' ' I l N N Dr 1 g 1

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o - * .4 l s l l l l ATTACHMENT - 1 I ODCM/ PROCEDURE RETISION LOG l l l 1 1 - 1 I DESCRIBE TE ISTORMATION TO BE CHANGED (INCLUDE PAGE NUMBERS, EQUATION NUMBERS, 1 l ETC.) ,

                                                                                                 ,                          I I

I I i I i l l l l l 1 I I I I I I I DESCRIBE (IN DETAIL) THE CHANGE (S) TO BE MADE. INCLUDE THE RATIONALE FOR AND l l A COMPLETE DESCRIPTION OF THE CHANGE (S) MADE TO THE ODCM: i I i l I i l I I I I I I I I i 1 l l 1 - 1 I

                                                                                                                     -1 I

I i 1. I REFERENCES (ATTACH COPIES OF COMPLETED PROCEDURE CHANGE FORMS, TCN'S AND S0.59 I I REVIEWS): I I l l l l 1 l 1 I I I I I ' I WILL THIS CHANGE REDUCE THE ACCURACY OR RELIABILITY OF DOSE CALCULATIONS ")R I l SETPOINT DETERMINATIONS (TECHNICAL SPECIFICATION 6.11.)? YES NO l l I 1 THESE CHANGES HAVE BEEN REVIEVED AST FOUND ACCEPTABLE, PURSUAhT TO TECHNICAL l l SPECIFICATION 6.S.2. . -- l I REVIEWED, RADIOLOGICAL ENpINEERING SUPERVISOR: l 1 . I I REVIEWED, SUPERVISOR - RADIOLOGICAL PROGRAMS: l 1 - . I I - I 1 I I l ll l 1 1 I ATTACHMEhT I PAGE 1 II I l l

 ,        i                    1     1   0F 1               1I      RSP-0008     I  REV - 0          I PAGE 112 0F 112 I I                          I                      ll                   I                   I                 I

GULF STATES RIVER BENO STATION UTILITIES COMPANY POST OFFICE BOX 220 ST FRANCISVILLE LOUISIANA 70775 ARE A CODE 504 635 6094 346 8651 April 30, 1987 RBG- 25841 File No. G9.5 U.S. Nuclear Regulatory Ccmnission Document Control Desk Washington, D.C. 20555 Gentlenen: River Bend Station - Unit 1 Docket No. 50-458 Per verbal request by your Messrs. Stern and Meinke on March 24, 1987, enclosed is a copy of the Offsite Dose Calculation Manual currently being used at River Bend Station. If you have any questions, contact our Mr. James Cook at 504-381-4151. Sincerely,

                                                                            . I-J. E. Booker Manager-River Bend Oversight River Bend Nuclear Group
          % r_.

JEB/ ERG /JNC/ks Enclosure cc: U.S. Nuclear Regulatory Ccmnission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Resident Inspector P.O. Box 1051 St. Francisville, IA 70775

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