ML20012A379

Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station.

ML20012A379
Person / Time
Site:	Oconee, McGuire, 05000000
Issue date:	01/01/1990
From:	Birch M, Tuckman M DUKE POWER CO.
To:
Shared Package
ML15217A104	List: ML15217A103 ML20012A368 ML20012A369 ML20012A372 ML20012A373 ML20012A375 ML20012A377 ML20012A379 ML20012A380
References
PROC-900101-02, NUDOCS 9003090350
Download: ML20012A379 (49)

Text

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' (..] December 28, 198g )

Subject:

Offsite Dose Calculation Manual )

Revision 27 j l

The General Office Radiation Protection Staff is transmitting to you this i date. Revision 27 of the Offsite Dose Calculation Manual. As this revision j 0 only offects Oconee Nuclear Station, the approval of other station managers  !

is not required. Please update your copy No. 39 ., and discard the affected pages.

REMOVE THESE PAGES INSERT THESE PAGES Figure A1.0-1 Rev. 11 Figure A1.0-1 Rev. 27 Figure A1.0-2 No Rev. a Figure A1.0-2 Rev. 27 (all four pages) (all four pages)

A-3 Rev. 18 A-3 Rev. 27 i A-5 Rev. 23 A-5 Rev. 27 A-6 Rev. 27 A-6 Rev. 27 A-7 Rev. 15 A-7 Rev. 27 A-8 Rev. 23 A-8 Rev. 27 A-10 Rev. 11 A-10 Rev. 27 A-14 Rev. 23 A-14 Rev. 27 1

Pages A-16 Rev. 23 Pages A-16 Rev. 27 ,

thru thru

\ ') Page A-24 Rev. 23 Page A-24 Rev. 27 r A-25 Rev. 23 A-25 Rev. 27 .

I Table AS.0-2 '

Rev. 21 Table AS.0-2 Rev. 27 I L NOTE: As this letter, with it's attachments, contains "LOEP" information, please insert this letter in front of the December 27, 1989. .

l Approval Da t e : Dec. 21, 1989 Approval Da t e : Dec. 19, 1989 !

l Effective Date: 1/1/go Effective Date: 1/1/g0 Q k ' * '2 m i Mary L. Birch M. S. Tuckman. Manager Radiation Protection Manager Oconee Nuclear Station i if'you have any questions concerning Revision 27, please call Jim Stewart

.at (704) 373-5444.

Osng ll $ lb '

1*  ;

James M. Stewart, Jr.

,_ Scientist r i Radiation Protection

)

Enclosure 9003090350 900228 PDR ADOCK 05000269 R PNV

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JUSTIFICATIONS FOR REVISION 27 i

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!- Figure A1.0 Replaced figure with CAD drawing. l Updated to retlect actual station operation and/or to provide additional. {

information.

Figure A1.0-2 Replaced figure with CAD drawing.  ;

(4 pages) Updated to reflect actual station  ;

operation and/or to provide additional information. .

I L Page A Changed wording to reflect actual  !

station operation.

Changed the minimum dilution flow rate available from 17054 gpm to 3.41E+04gpm{. .

In order to take credit for the -

additional dilution flow provided'by the Keowee Hydro Fire Protection-LWR  !

Mixing.Line.

Page A-6 Corrected typo errors in Table Number 6.

/x.

( Page A-6 Provided additional information for

\ -} '

clarity purposes and changed mileage  !

information for consistency purposes', ,

I Page A-7 Corrected typo errors in Table Numbers.

Page A-8 Corrected " dispersion / dispersion" to

" dispersion /depositior," +

Provided additional information for clarity purposes and changed mileage

-)

information for consistency purposes.

l Page A-10 Changed wording to reflect actual l station operation.

Page A-14 Added "is" to sentence and corrected r "SAS" to " gas".

Section A4.3 Updated section using dose calculations Pages A-16 thru A-24 based on 1989 Effluent Release data (firat nine months)- and t h r. 1989 Land Use Census Data.

Page A-25 Changed wording to reflect actual-station operation. Chang 9d the dates the; r'N latest Land Use Census wna preformed.

E c.

~'). . Table AS.0-2 Changed per attached August 29, 1989 letter from C. T. Yongue, h

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August 29, 1989 l t

Dr. W. A. Haller, Manager  !

Nuclear Technical Services i t

ATTENTION: - W '

SUBJECT:

Oconee Nuclear Station Radiological Environmental Monitoring Program -

File 0S-778.00 I am making the requests listed below as a result of the closing of the Clemson Water Plant. As of July 1 of this  !

year, the University's drinking water plant was shut down  !

with no plans to restart the facility. Clemson University now obtains drinking water from the Anderson water system.

- Delete the drinking water location 065, Clemson, from i Table A5.0-2 and Figure.A5.0-1 at the next revision to the ODCM. Redmarked copies of the needed changes are attached. In addition to the deletion, please correct the sector listed for location 073 from.NNW to NW.  :

t i

p L (_/ - Identify-in the next Semi-Annual Effluent Release ,

Report the deletion of.the Clemson drinking. water

.samplespoint from.0conee's Radiological Environmental Monitoring Program.

- Review the ODCM and make any necessary changes to effluent dose calculation parameters due to the plant's ,

closing.

- Review the need to add a drinking water location  :

further downstream of Anderson, if possible. Oconee Technical Specification 4.11, Table 4.11-1, specifies that the monitoring program include.3 drinking water  :

sites. Anderson is currently the only site downstream

of plant discharges. Ser, ca and Greenville both use l Lake Keowee as their reservoir. We have installed a <

sampler to collect from the water used.to supply the steam plant at the University. This water is collected from the same line that fed the water plant. The L difference is that the sample will be raw. water rather than finished water. This sample point will be considered a special supplemental sample since it is ,

neither a drinking water or surface water sample, and it will not be included in the ODCM. The sample ,

results will be trended and used in the evaluation of fO surface water and drinking water results as needed.

+ - . .

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V Page 2 Radiological Environmental Monitoring Program August 29, 1989 Please contact Libby Wehrman at extension 3207 to discuss these requests.

1 At } ^ L'A&,

C. T. Yo e,jpanager i Radiati Pr #ection ,

xct J. W. CraIn C. F. Lan S. A. Coy J. J. Sevic M. D. Lane ,

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OCONEE RADIOlhCICAL MONITORING PROGRAM SAMPLING LOCATIONS (OTNER SAMPLING LOCATIONS)

E.

CODE: -

== U m

U W - Weekly ( $ 7 days) g I' eo SM - Semimonthly ( $ 15 days) *3 y y = >

M - Monthly ( $'31 days) o, j **

e y SA - Semiannually ( $ 184 days) jg g 3 3' e oc o. .e .nc - * -a uv Y 3 $' d i 3

_ _ _ __ _ __ _ __ _ _ _ __S_ AM__P_L_I NG_ _ _LO_C_A_T_ _I O_N__DE_S_C_R__I m $ N

_PT_ _IO_N_ __ _______ _____ _ ___ _

______________________________________$______U____$

C28 Site Boundary (0.5 miles S) M.

060 New Greenville Water Intake Rd. (2.5 miles NNE)

• W M'~ SA N  !

061 Old Hwy. 183 (1.5 miles SSW) W 062 Lake Keowee/ Hydro Intake (0.7 mile ENE) (CONTROL) M 063 Lake Hartwell - Hwy 183 Bridge (0.8 mile ESE) (000.7) M SA SA 064 Seneca (6.7 miles SW) (004.1) (CONTROL) M 065 Clemson (8.1 miles SSE) (006.1) der.E TED M 066 Anderson (19.0 miles SSE) (012) (CONTROL FOR MILK ONLT) M SM 067 Lawrence Ramsey Bridge, Hwy 27 (4.2 miles SSE) (005.2) SA SA 068 High Fa11s County Park (2.0 miIes W) (CONTROL) SA

069 Powell Residence (4.5 miles WNW) (002.1) SM 071 Clemson Dairy (10.3 miles SSE) (006.3) SM 072 Hwy 130 (1.7 miles S) W --

073 Tamassee Dar School (9.0 miles h )- (CONTROL) W M 074 Keowee Key Resort. (1.7 miles NNW) W 075 Willimon Residence (6.0mildsNE) DELETED' SM

,

• Control for Fish only l

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l APPENDIX A i

i OCONEE NUCIZAR STATION i, SITE SPECIFIC INFORMATION  !

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(}m APPENDIX A-TABLE OF CONTENTS .

t PAGE A1.0 OCONEE NUCLEAR STATION RADWASTE SYSTEMS A-1 A2.0 RELEASE RATE CALCULATION A-3 .

i A3.0 RADIATION MONITOR SETPOINTS A-9 l ,

A4.0 DOSE CALCULATIONS A-15 l  ;

A5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING A-25 l

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6 4

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A1.0 OCONEE NOCLEAR STATION RADVASTE SYSTEMS t

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A1.1 LIQUID RADWASTE PROCESSING ,

The liquid radwaste system at Oconee Nuclear Station (ONS) is used to collect  !

and treat fluid chemical and radiochemical by-products of unit operation. The  ;

systems produce effluents which can be reused in the plant or discharged in i small, dilute quantities to the environment. The means of treatment vary with  ;

waste type and desired product in the various systems:  ;

i A) Filtration - waste sources are filtered prior to processing as ,

necessary.  ;

B) Ion Exchange - ion exchange is used to remove radioactive ions from '

solution. Also, ion exchange is normally used in removing cations (cobalt, manganese) and anions (chloride, fluoride) from evaporator feed and/or distillates in order to purify the distillates for reuse as makeup water. Distillate from the Waste Evaporator System or the '

Waste and Recycle Evaporator can be treated by this method.

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C) Gas Stripping - removal of gaseous radioactive fission products is -

accomplished in Evaporators and the venting of atmospheric holdup tanks.

D) Distillation - production of pure water from the waste by boiling it p) away from the contaminated solution which originally contained it is accomplished by both evaporators. Proper control of the process will yield water which can be reused for makeup. Polishing of this product can be achieved by ion exchange as pointed out above.

E) Concentration - in all Evaporators, radioactivity and dissolved chemicals are concentrated as water is boiled away. In the case of the Waste Evaporator, the volume of water containing waste chemicals

.and radionuclides is. reduced so that the waste may be more easily and cheaply solidified and shipped for burial. In the case of the VR dryer, all water is removed and the dry salts are solidified for burial. ,

Figure A1.0-1 is a schematic representation of the liquid radwaste system at ~l Oconee. l l

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A1.2 GASEOUS WASTE PROCESSING h '

Ihe purpose of the gaseous waste disposal system is to: f

(1)" Maintain"a~non oxidizing cover gas of nitrogen in tanks and equipment that contain potentially radioactive gas.

(2). Hold up radioactive gas for decay.  ;

(3) Release gases (radioactive or non-radioactive) to the atmosphere under controlled conditions. .

During power operation of the facilities, radioactive materials released to the atmosphere in gaseous effluents include low concentrations of fission product noble gases (krypton and xenon), halogens (mostly iodines), tritium  !

contained in water vapor and particulate material including both fission  :

products and activated corrosion products. ,

The primary source of gaseous radioactive wastes is from the degassing of the primary coolant during letdown of the cooling water into the various holding  :

tanks. Additional sources of gaseous waste activity include the auxiliary

' building exhaust, spent fuel area exhaust, the discharge from the steam jet air ejectors, purging of -the reactor containment building and ventilation air exhausted from the turbine building, i

l  % All components that can contain potentially radioactive gases are vented to a l

I< vent header. The vent gases are subsequently drawn from this vent header by

,d one of three waste gas compressors or a waste gas exhauster. The waste gas compressor discharges through a waste gas separator to one of seven waste gas

. tanks. The waste gas tanks and the. waste gas exhauster discharge to the unit

! vont after passing through a filter bank consisting of a profilter, an ,

absolute filter, and a charcoal filter.  ;

Radioactive gasas may be released inside the reactor containment building when :

components of the primary system are opened to the building atmosphere for

, operational reasons or where minor leaks occur in the primary system. Prior l to access, the reactor containment atmosphere will be monitored for activity ,

and, when necessary, purged through profilters, high-efficiency particulate air (HEPA) filters and-charcoal adsorbers and released to atmosphere through a the unit vent. The purge equipment is sized for a flow rate of 50,000 cfm providing 'approximately 1.5 air changes per hour in the reactor building.

Units 1; 2 & 3 have a separate vent stack from each reactor building.

The gaseous waste handling and treatment systems for the Oconee Nuclear Station are shown schematically in Fig. A1.0-2, 1

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1-RIA56 - UNIT VENT

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CAS HEADER 1-A -

1-RIA37 (FROM REACTOR T 200 FT COOLANT SYSTEMS) ,1-RIA38 r i GAS

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SEPARATOR OlARCOAL

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ADSORBERS COMPRESSOR ,

TO LIQUID  !

WASTE SYSTEM A

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FR.TERS t

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1-RIA51 VENTILATION SYSTEM l CHARCOAL UNIT 1 REACTOR BUILDING UNIT 1 REACTOR BUILDING ~ ~

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PURGE SYSTEM FILTERS ADSORBERS

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A2.0 RELEASE RATE CALCULATION j

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Generic release rate calculations are presented in Section 1.0; these calcu-i lations will be used to calculate release rates from Oconee Nuclear Station. ,

i A2.1 LIQUID RELEASE RATE CALCULATIONS i i

There are two potential release points at Oconee, the liquid radwaste effluent ,

line to the Keowee Hydroelectric Unit Tailrace and the #3 Chemical Treatment  !

Pond effluent line to the Keowee River. i A2.1.1 Liquid Radwaste Effluent Line To The Keowee Hydroelectric Unit Tailrace  ;

To simplify calculations for the liquid radwaste effluent line, it is assumed that no activity above background is present in the #3 Chemical Treatment Pond  !

effluent. This assumption shall be confirmed by radiation monitoring and/or -

the sampling of the pond's radioactive inputs, and by periodic analysis of the ,

composite. sample collected at the #3 Chemical Treatment Pond discharge. For the liquid radwaste effluent line the following calculation shall be performed .i to determine a discharge flow, in gpm:

n Cg j I

f5 F+[a i=1 MPC $ I

, 7%

l where:

f = the undiluted effluent flow, in spm.

Cg = the concentration of radionuclide, 'i', in undiluted effluent as determined by laboratory analyses, in 11Ci/ml.  ;

MPC = the. concentration of radionuclide, 'i', from 10CFR20, Appendix B.

f Table II, Column 2. If radionuclide, 'i', is a dissolved noble gas, r the MPCg = 2.0E-4 pCi/ml.

F = the dilution flow available, in gpm typical flow rates are:

3.41E+04 gpm (based on a leakage rate of 38 cfs, plus the Keowee Hydro Fire Protection - LVR mixing line whose flow rate is 38 cfs) 2.9E+6 gpm (based on one hydro unit operating at 50% power, 6600 cis) o- = the recirculation factor.at equilibrium is 1.0. (See Section 1.1) b l

b Rev. 27 .

A-3 1/1/90

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( ) A2.1.2 #3 Chemical Treatment Pond Effluent Line v

The #3 Chemica1' Treatment Pond effluent is the release point for station effluents that are normally considered to be non-radioactive; that is, the

' pond's effluent will not normally contain measurable activity above background. It is assumed that no activity is present in the effluent until indicated by radiation monitoring measurements on the pond's inputs and/or by periodic analyses of the composite sample collected at the pond's discharge point. Inputs to this pond include the plant's yard drain system, the decant water from the Powdex system, the discharge from the Turbine Building Sump system, and Radwaste Facility monitor tanks whose contents have been determined to be below background. Inputs that have radiation monitors associated with them will be set to assure that Technical Specification 3.9.1 ,

will not be exceeded.

The #3 Chemical Treatment Pond may also be the discharge path for large volumes of slightly contaminated water following a primary secondary leak so long as administrative procedures are implemented to assure that release rate calculations similiar to that used in Section A2.1.1 are performed, that all detectable radionuclides will be accounted for, and that no statica limits will be exceeded.

A2.1.3 Low Pressure Service Water Effluent Line The Low Pressure Service water effluent is normally considered nonradioactive;

/~'g that is, it is unlikely the effluent will contain measurable activity above

( ) background. It is assumed that no activity is present in the effluent until ,

indicated by radiation monitoring measurements. Radiation monitoring alarm setpoints, in conjunction with administrative controls, assure that release limits are not exceeded.

I v

Rev. 11 A-4 9/12/86

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[ ) 'A2.2 GASEOUS RELEASE RATE CALCULATIONS FOR SEMI-ELEVATED RELEASE POINTS vs The unit vents are the release points for waste gau decay tanks, containment building purges,.the condenser air ejector, and. auxiliary building ventila-tion. The unit vent is treated as a semi-elevated release point. The applicable dispersion and deposition parameters are provided in Tables A4.0-1a and A4.0-1b respectively.

The condenser air ejector effluent is normally considered nonradioactive; that is, it is unlikely the effluent will contain measureable activity above background. It is assumed that no activity is present in the effluent until indicated by radiation monitoring measurements and by analyses of periodic samples collected from this source. Radiation monitoring alarm / trip setpoints in conjunction with administrative controls assure that release limits are not exceeded; see section on radiation monitoring setpoints.

The following calculations, when solved for flowrate, are the release rates for noble gases and for radioiodines, particulates and other radionuclides with half-lives greater than 8 days; the most conservative of release rates  !

calculated in A2.2.1 and A2.2.2 shall control the release rates for a single release point. ,

A2.2.1 Release rate limit for noble gases:

A 7

IKg [(X/Q)Q g) ( 500 mrem /yr, and i

I(L[+1.1M)[(X/Q)Q)(3000 g 3 mrem /yr i

where the terms are defined below.

A2.2.2 Release rate limit for all radioiodines and radioactive materials in particulate form and radionuclides other than noble gases:

s 1 IPg W Q )g ( 1500 mrem /yr i i

l where Kg = The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in rurem/yr per pC1/m' from Table 1,2-1.

Lg = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m' from Table 1.2-1.

!!g = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pC1/m' from Table 1,2-1 (unit conversion constant of 1.1=mrom/ mrad converts air dose to skin dose).

g, Pg = The dose parameter for radionuclides other than noble gases for the

( inhalation pathway, in mrem /yr per pC1/m' and for the food and ground ,

i plane pathways in m'-(mrem /yr) per pC1/sec from Table 1.2-2. The dose l factors are based on the critical individual organ and most restrictive age group (child or infant).

Rev. 27 A-5 1/1/90

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k.=Thereleaserateofradionuclides,i,ingaseouseffluentfromall g

release points at the site, in WC1/sec, i

X7d=4.1E-7sec/m'. The highest calculated annual average relative  !

concentration for any area at or beyond the unrestricted area boundary. The location is the S sector @ 3.5 miles for semi-elevated  !

releases. j i

W = The highest calculated annual average dispersion / deposition parameter for  :

estinating the dose to an individual at a controlling location in the unrestricted area where the total inhalation, food and ground plane  !'

pathway dose resulting from combined ground level and semi-elevated releases is determined to be a maximum based on operational source tera data, land use surveys, and NUREG 0133 guidance:

W = 3.0E 6 sec/m8 , for the inhalation pathway. The location is the WNW @ 4.0 miles. l W = 9.2E-10 m'8, for the food and ground plane pathways. The location is the WNW @ 4.0 miles. l hg= k Cigf + ks = 4.72E+2 Cg f where >

Q +

.C the concentration of radionuclide, 1, in undiluted gaseous. effluent, in g = pCi/al.

I f = the undiluted affluent flow, in cfm ki = c:nversion factor, 2.83E+04 ml/fta i

km = conversion factor, 6.0E+01 sec/ min t

5 Rev. 27 A 1/1/90

E i t

I f A2.3 ' GASEOUS RELEASE RATE CALCULATIONS FOR GROUND LEVEL RELEASE POINTS f' Hot' Machine Shop-Building ventilation exhaust, Radwaste Facility Exhaust, and  !

Auxiliary Boller releases are treated as ground-level release points. The applicable dispersion and deposition parameters are provided in Tables A4.0-2a and A4.0-2b respectively.

It is assumed that no activity is present in effluent from these sources until indicated by radiation monitoring measurements and by analyses of periodic ,

i samples collected from these sources. Radiation monitoring alarm / trip f, setpoints in conjunction with administrativo controls assure that release .'

limits are not exceeded; see section on radiation monitoring setpoints.

The following calculations, when solved for flowrate, are the release rates  ;

for noble gases and for radioiodines, particulates and other radionuclides r with half-lives greater than 8 days; the most conservative of release rates ,

calculated in A2.3.1 and A2.3.2 shall control the release rates for a single release point.

• A2.3.1 Release rate limit for noble gases:

IK g[(x/Q)d)g < 500 mrem /yr, and i

(] '

1 (Lg + 1.1 Mg) [(X/Q)Q g) ( 3000 mrem /yr here the terms are defined below:

A2.3.2 Release rate limit for all radiolodines and radioactive materials in particulate form and radionuclides other than noble gases:

1P gW b ] g( 1500 mrem /yr i

where:

Kg = The total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m' from Table 1.2-1.

Lg = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pC1/m' from Table 1,2-1.

Mg = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pC1/m' from Table 1.2-1 (unit conversion constant of 1.1 mrem / mrad converts air dose to skin dose).

Pg = The dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem /yr per UCi/m'. and for the food and ground plane pathways in m8 -(mrem /yr) per DCi/sec from Table 1,2-2. The dose l factors are based on the critical individual organ and most restrictive r 3 age group (child or infant).

G Rev. 27 A-7 1/1/90 ,

t l

.i " ) s Q1 - The releas. rete of radionuclides, i, in gaseous effluent from all '

release points at the site, in WC1/sec. l X/Q = 9.2E-6 sec/m*, The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary.

The location is the S sector @ 1.0 miles for ground-level releases.

W = The highest calculated annual average dispersion / deposition parameter l !

for estimating the dose to an individual at a controlling location in i the unrestricted area where the total inhalation, food and ground plane pathway dose resulting from combined ground level and semi-elevated  !

releases is determined to bw a maximum based on operational and .

design basis source term data, land use surveys, and NUREG 0133  !

guidance:

W = 9.80E 08 sec/m , for the inhalation pathway.

8 The location is the WNW @ 4.0 miles. l W = 2.10E-10 m'8, for the food and ground plane pathways. The location is the WNW @ 4.0 miles, g

Qg = k Cg f + ks = 4.72E+2 Cg f f where

]Y Cg = the concentration of radionuclide, i, in undiluted gaseous effluent, in i pC1/ml.

f = the undiluted effluent flow, in cfm 8

kg = conversion factor, 2.83E+04 ml/ft ,

ks = conversion factor, 6.0E+01 sec/ min Rev. 27 A-8 1/1/90

i. l b I

.1 I

A3.0 EADIATION MONITOR SETPOItfrS l (V) '

'Using the generic calculations presented in Section 2.0, final radiation monitoring setpoints are calculated for monitoring as required by the Technical Specifications. ,

1 All final effluent radiation monitors for Oconee are off-line. These monitors i alarm on low flow; the minimum flow alare level for the liquid monitors is 3 gallons per minute and for all gas monitors, except in the Radwaste Facility, is 7 standard cubic feet per minute. These monitors measure the activity in the liquid or gas volume exposed to the detector and are independent of flow i rate if a minimum flow rate is assured. The Radwaste Facility gas monitors l have a minimum flow alarm level of 2 standard cubic feet per minute and adjusts flow rate as the line flow changes. l Radiation monitoring setpoints calculated in the following sections are expressed in activity concentrations; in reality the monitor readout is in j counts per minute, except for the Radwaste Facility gas monitor where its readout is in (pC1/ml). The relationship between concentration and counts per ,

minute shall be established by station procedure using the following  !

relationship Station radiation monitor setpoint procedures which correlate d concentration and counts per minute shall be based on the formula below and ,

.will be determined using.the monitor's correlation graph. The correlation I graph shows concentration (VCi/ml) vs. monitor reading (cpm) based on  ;

empirical data.

(

i' r c= 2.22 x 10'e V i where:' <

c = the gross activity, in UCi/ml  !

r = the count rate, in cpm l 2.22 x 10' = the disintegration per minute per 901 l e = the counting efficiency, cpm /dpm v = the volume of fluid exposed to the detector, in ml.

A3.1 LIQUID RADIATION HONITORS A3.1.1 Liquid Radwasta Effluent Line To The Keowee Hydroelectric Unit Tailrace As described in Section A2.1.1 of this manual on release rate calculations for the waste liquid effluent, the release is controlled by limiting the flow rate of effluent from the station. Although the release rate is flow rate controlled, the radiation monitor setpoint shall be set to terminate the release if the effluent activity should exceed that used to calculate the

• release rate. Also, a radiation monitor setpoint shall be set to alarm if the

-effluent activity should exceed that determined by. laboratory analyses.

O b .

Rev. 11 A-9 9/12/86

1 l

i i

l i

.( ,,) - A3.1.2 Turbine Building Sump Discharge Line l G )

' As described in Section A2.1.2 of this manual on release rate calculations for  !

. the turbine building sump effluent, the effluent is normally considered nonradioactive; that is, it is unlikely the effluent will contain measurable L activity above background. It is assumed that no activity is present in the

- effluent until indicated by radiation monitoring and by routine analysis of the composite sample collected at the #3 Chemical Treatment Pond. Since the system discharges automatically, the maximum system concentration, which also is the radiation monitor setpoint, is calculated to assure compliance with release limits.

0 A typical setpoint is calculated as follows: i c5 E=4.5E-6pC1/ml l 1

a where: I I

c = the gross activity in undiluted effluent, in pCi/mi, i l

f = the flow rate of undiluted effluent which may vary from 0-375 gps, but j is assumed to be 375 spa. j l

MPC = 1.0E-07 pCi/al, the MPC for an unidentified mixture.

. o =1 (See Section A2.1.1)

F = the flow may vary from 38 to 6,600 cfs, but is conservatively estimated at 38 cfs (1.7E+4 gpe), the minimum flow available.

A3.1.3 Radwaste Facility Effluent Line To CTP #3 l Asidescribed-in Section A2.1.2 of this manual on release rate calculations, the Radwaste Facility Effluent is normally considered non-radioactive; that is, it is unlikely the effluent will contain measurable activity above -

background. It is assumed that no activity is present in the effluent until indicated by radiation monitoring and/or by routine analyses of the composite sample collected at the discharge of the #3 Chemical Treatment Pond. In order to assure that no activity is unknowingly discharged into the pond,.the inputs to the Radwaste Facility Effluent Line are released in discrete batches where ,

each batch is sampled for activity prior to release.

O Rev. 27 A-10 1/1/90

- t  ;

i f

. , , -m (s- A3.1.4 Low Pressure Service Water Discharge Line l s

.As described in Section A2.1.3 of this manual on release rate calculations for i the Low Pressure Service water ef fluent, the ef fluent is normally considered .i nonradioactive;"that is, 'it'is' unlikely the effluent will"contain measurable l activity above background. It is assumed that no activity is present in the i effluent until indicated by radiation monitoring equipment. Since the system  ;

discharges automatically, the maximum system concentration which is also the i radiation monitor setpoint, is calculated to assure compliance with release  ;

limits. .

A typical monitor setpoint is calculated as follows:

{

M x F = 1.16E-5 pCi/ml CS  !

t where C = the gross activity in undiluted effluent, in DCi/ml.

f = the flow rate of undiluted effluent which may vary from 0 to 10,500 gpm but is assumed to be 10,500 gpm. i tGC = 1.0E-07 pC1/m1, the MPC for an unidentified mixture. i

= recirculation factor for Lake Keowee, 1.02. i

_g ' .

F = the flow rate of the condensate cooling water is based on having seven '

CCW pumps in operation, 1.24E+06 gps. Should the number of operating pumps decrease, the setpoint must be recalculated.-

N Rev. 11 A- 1?. 9/12/86

.- - r. - - -- - . - . . _ .

r, ,

jg--

A3.2

-- (w) GASEOUS RADIATION HONITOR SETPOINTS FOR SEMI-ELEVATED RELEASE POINTS l

'Ihe following equ4 tion shall be used to calculate final offluent noble gas  !

radiation monitor setpoints based on Xe-133:

l K(X/Q)Qg < $00 mrom (See Section A2.2.1) l r .

Qg = 4.72E+2 Cg f (See Section A2.2.2) l (K)(X/Q)(472)(Cg )(f) < 500 ,

i Cg -< (294)(4 -7)(472) ' I Cg < 8.79E+3/f j where:

C = the gross activity in undiluted effluent, in WC1/ml -l j

f = the flow from the tank or building and varies for various release i sources, in cfm i

K = from Table 1,2-1 for Xe-133, 2.94E+2 arem/yr per'pCi/m'  !

X/Q '= 4.1E-7 sec/m , as defined in section A2.2.2.

8 C

A3.2.1 Gaseous Radweste Effluent Line - Waste Gas Decay Tanks l  !

i As-described in Section 2.2, the release is controlled by limiting the flow-rate of the effluent from the station. Although the release rate is flow rate  ;

controlled,=the radiation monitor setpoint shall be_ set to terminate the release if the effluent activity _should exceed that determined by laboratory '

' analyses and that used to calculate the release rate. A typical radiation monitor setpoint may be calculated as follows: ,

C < 8.79E+3/f = 2.93E+02 pC1/ml where f = 30 cfm I a

]

4 l

f}

K.A j y

Rev. 21 -'

A-12 8/1/88

., , av , -!

['.'., ' ' '

• J:' lG -

1)#N ,F

' A3. 2. 2 - UnitLVent-

'\_ /L i  !

p~

' As 4 statednin Section A2.2,'the' unit vent is the release point for waste gas .

- decay tanks.: containment -building purges, theLeondenser air ejector,7 and .i'

auxiliary building ventilation. Since all-of these releases are through tho' unit-vent,-the radiation monitor on the, unit vent may be used to assure that'  !

station. release limits are not exceeded. Depending on the stack flow, a-

- typical rediation monitor setpoint may be calculated as follows:J  ;

'C < 8.79E+3/f'= 9.25E-2 pC1/m1'

"- where:

?f = 45,000 cfm (auxiliary building) + 50,000 cfm .(containment purge) = 95,000 ~

C cfm or. l C < 8.79E+3/f = 1.95E-1 pCi/ml where:L f = 45,000!cfm (auxiliary building ventilation) l

'l ) l

s) j

.h

F 'l

.I 1

'(.

a Y

4-

'(',.< 1 o

4 A-13 Rev. 21 8/1/88

j 3; .

]

{

9 j, ,f # /A3.3J GASEOUS RADIATION HONITOR SETPOINTS FOR GROUND-LEVEL RELEASE POINTS  ;

< y

-<h M The*following* equation shall be used to calculate final effluent noble gas c . radiation monitor setpoints based on Xe-133: -

?

-~ . . . .

..K(X/Q)Qg < 500 mres (See Section-A2.2.1)

• l

~ l 91

= 4.72E+2 Cg f.(See Section A2.2.2) 5 -

(K)(X/Q)(472)(Cg )(f) < 500 l

i ! (294)(9 -6)(472) '

Cg <'3.92E+2/f 'l wheret'.

C = the gross activity-in undiluted effluent, in pCi/ml

\

f- = the flow from the tank or' building and varies for various release.

sources, in cfm W :K - = from Table'1.2-1 for Xe-133, 2.94E+2 aree/yr per pCi/m8

• = . - X/Q;'= 9.2E-6 sec/m3 ', as defined in section A2'3.2. .

i

[}

y

'A3.3.1 Interim'Radwaste Building Ventilation Exhaust .

t

- ' (Ventilation exhaust from the Interim Radwaste Building-is considered a: ..

.' separate release point. This exhaustsis.normally considered non-radioactive;. .-

that'is, it in possible but unlikely.that'the effluent will contain measurable

' activity above background.= Since the exhaust is continuous, a maximum con-

• at' centration:ofegases'in the exhaust, which also is'thetradiation monitor set-'

point is calculated to-assure compliance with release limits. LA typical radiation monitor setpoint may be calculated as follows:

o >

t C:< 3.92E+2/f = 2.67E-2-pCi/mi

'o.

-where:

/ .f =gl'.47E+04 cim. -t CA3.3d Hot Machine Shop Building. Ventilation Exhaust

' Ventilation; exhaust from the Hot Machine Shop is considered to be a separate

release point. This filtered cxhaust is sampled and analyzed for particulates and radiciodines to: assure that'the effluent released has not exceeded station I

% ' ~ release limitsP:Since'it'is assumed that no noble gases will be' generated by machine shop work, no provision for monitoring noble gas releases are +

provided.'

w.

y' '

A-13a Rev. 23 1/1/89 s,

rt9 g

+ -_.- _ _ _ _ _ _ _ _ _ _ _ _ __.___. _

v , , s j

l 1

i lyn q

w

[ A3. 3. 2 ' Contaminated Oil Burning In Auxiliary Boiler (Contaminated oi1~is' burned in- the auxiliary boiler which -is not released-j

through,the-unit vent and is considered a separate release point. The q

contaminated' oil _is' filtered,' mixed, and sampled to' determine-the total- l

-activity to be released and the allowable release (burn) rate.  !

I By Technical Specification, releases from the auxiliary boiler from i incineration of contaminated oil must meet the instantaneous release rate for '

l

'lodines and particulates given in Section A2.2.2. Also, the total dose due to these releases must be less than 0.1% of the allowable yearly dose from particulate gaseous effluents.

Doses.from incineration of contaminated oil are calculated for all organs and-all pathways using either: the models provided in Section 3.1.2.2 of this manual or the GASPAR computer program. Cumulative doses are calculated quarterly at a minimum, e

All.the activity in the contaminated oil is assumed to be released during rincineration and the total is-added to-the station's quarterly and annual release records, i

A3.3.3- Radwaste Facility Ventilation and Process Gas Exhaust 1:

P'D ' .

The ventilation and process . gas exhaust frca tho' Radwaste Facility _ is . considered a separate' release point. This exhaust ~is sampled continuously for-iodine-and [ .

particulates and noble gases. -This data'is used in calculations to assure

i. that the effluents released have not exceeded station release limits. A-l typical radiation monitor setpoint may be calculated as follows:

1 l

C < 3.92E+2/f = 3.02E-03 tici/ml where:

L f = 129,700 cfe, The total combined ventilation and process gas

. exhaust' flow. l ,

l-l 1

i

, 6

' sk Rev. 27 A-14 1/1/90

A4.' 0 DOSE CALCULATIONS

[O]

LA4.1 FREQUENCY OF CALCULATIONS

~ Dosewcontributions to"the maximum individual sha117 be calculated at least '

every 31 days, quarterly, semiannually, and annually (or as required by Technical Specifications) using the methodology in the generic information sections. This methodology shall also be used for any special reports. Dose -

z calculatioas that are required for individual pre-release calculations, and/or

- abnormal releases shall not be calculated by using the simplified dose 4 calculations. Station dose projections for these types and others that are known to vary from the station historical averages shall be calculated by using the methodology in the generic information sections. STATION Dose projections may be performed using simplified dose estimates.

Fuel cycle dose calculations shall be performed annually or as required by special reports. Dose contributions shall be calculated using the methodology in the appropriate generic information sections.

A4.2 DOSE H0DELS FOR MAXIMUM EXPOSED INDIVIDUAL A4.2.1 Liquid Effluents For dose contributions from liquid radioactive effluent releases, it is assumed that the maximum exposed individual is an adult who consumes fish (p

. caught in the discharge area and drinks water from the nearest downstream-I water supply.

l A4.2.2 Gaseous Effluents A4.2.2.1 ' Noble Gases For dose contributions from exposure to beta and gamma radiations from noble gases, it is assumed that the maximum exposed individual is an adult at a controlling location in the unrestricted area where the total noble gas dose from combined semi-elevated and ground level releases is determined to be a maximum; this location may not be controlling for semi-elevated or ground-level releases considered separately, however, A4.2.2.2 Radiciodines, Particulates, and Other Radionuclides with L T'1/2 > 8 days l For dose contributions from radiciodines, particulates, and other radio-I nuclides; it is assumed that the maximum exposed individual is a child or infant at a controlling location in the unrestricted area where the total inhalation, food and ground plane pathway dose is determined to be a maximum based on operational source term data, land use surveys, and NUREG-0133 guidance. The controlling location is determined based on total combined l: semi-elevated and ground level radioidine, particulates and other radionuclide l releases with T 1/2 > 8 days; this location may not be controlling for semi-l .

elevated or ground-level releases considered separately, however.

l A. .

Rev. 23 A-15 1/1/89 l- y

y  ;. .

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

• p l f ,

)

l

' ^

// ' E A4.3: SIMPLIFIED-DOSE ESTIMATES i i ~

.A4.3.1 Liquid Effluents-J.NForidose. estimates,;aisimplifiedcalculation:basedonathe: assumptions _ $

presented in Section_A4.2.1 and operational source term data is presented -

, i e below. ._ Updated operational source term data shall be used:to revise these. j

. calculations as necessary.

.m

, D WB.

= .13E+05 I (Fg )(Tg ).(C Cs-134 + 0.59 CCs-137 )'

, g E

U -where:- 1 7'13E+05 =_1.14E+05 (U,,/D,+ U,f BFg) DF ait

. (1.23) _[

m I where:

L ,

-1.14E+05.= 10'pci/pci x 10'al/kg + 8760 hr/yr j U, = 730 kg/yr,' adult-water consumption' a

D, ='27.5, dilution factor from the near field areatto;the_ nearest possible. ,

. potable _ water -intake.

q .U;g = 21 kg/yr, adult. fish consumption BFg f12;00E+03,MoaccumulationJactor_ for Cesium Game 3.1-1)

~

DF .= 1.21E-04,-adult, total body, ingestion-dose factor (Table 3.1-2) ait

'1.23 = factor derived from the assumption that 81% of dose is-from Cs-134 and a Cs-137 or 100%'+ 81% = 1.23 '

where:' '

'F g _= 7 ff ,

lt .

L .f = liquid radwaste flow, in gpm ,

.o =. recirculation factor at equilibrium, 1.0 ,

[g

) ,

F'= dilution flow, in gpm and where:

Tg= the length of time, in hours, over which CCs-134, CCs-137, and Fg are averaged

CCs-134<= theiaverage. concentration of Cs-134--in undiluted effluent, in

~

' ^

pC1/m1, during the time period considered.

'CCs-137 = the average concentration of Cs-137 in undiluted effluent, in L/ .

pC1/m1, during the time period' considered.

L A. 0.59 = the' ratio of the adult total body ingestion dose factors for Cs-134 L and Cs-137 or 7.14E-05 + 1.21E-04 = 0.59 R

Rev. 27 A-16 1/1/90

[

1 r-

,s %

( - A4.3.2 Gaseous. Effluents From Semi-Elevated Release Points Meteorologica1' data for Unit Vent releases is provided in Tables A4.0-1a and A4.0-1b.

A4.3.2.1 Noble Gases For dose estimates, simplified dose calculations based on the assumptions in

' A4.2.2.1 and operational source term data are presented below. Updated operational source term data shall be used to revise those calculations as necessary.: These-calculations further assume that the annual average

-~ dispersion parameter is used and that Xenon-133 contributes 92% of the gamma -

air dose and 84% of the beta air dose for semi-elevated releases.

y Dg = 2.91E-12 [ Q ]Xe-133 (1.09)

D,5 = 8.65E-12 [ Q ]Xe-133 II'19) where:

2.91E-12 = (3.17E-8) (353) (X/Q), derived'from equation presented in Section .

3.1.2.1.

~ 8.65E-12 = (3.17E-8) (1050) (X/Q), derived from equation presented in Section 3.1.2.1.

U -[-Q ] Xe-133= the total Xenon-133 activity released in 1:01 X/Q = 2.60E-7 sec/m', the semi-elevated release dispersion parameter

-(E/Q) corresponding'to the controlling location (S @ 1.0 miles) defined in Section A4.2'.2.1.

1.09 = factor derived from the assumption that 92% of the Gamma Air dose is contributed by Xe-133 ,

1.19 = factor derived from the assumption that 84% of the Beta-Air dose is l contributed by Xe-133 l.

Rev. 27 A-17 1/1/90 L

. . - - . . .. - ~ - .

< r ic >  ;

i- 1 L ,

w P

w- .- .

I ,,[ , , [("Np 'A4.3.2.2 iRadioiodines, Particulates, and Other Radionuclides with'  :

[1,M T 1/2') 8 Days l

For dose estimates,. simplified dose calculations based on'the assumptions in A4.2,~2.2'and-operational' source term data are presented-below.:-Updated-operational: source term data shall be used to revise these calculations as necessary.- These calculations'further assume that the annual average J dispersion / deposition parameter is used and that 99% of the semi-elevated release ~ dose results from Iodine-131 ingested by the maximally exposed

'~

individual via the cow milk pathway at the controlling location. The l simplified dose estimate for exposure to the thyroid of an infant-is:-

D = 1.53E4 W (Q)1,731 (1.01) -

where:

I

' W = 9.2E-10, the semi-elevated, release deposition parameter (D/Q) for food and  ;

ground plane pathway, in m 8 corresponding to the controlling location (WNW @ 4.0 miles) defined in Section A4.2.2.2. (

-(Q)I-131 = the total Iodine-131 activity released in 901. 1 SN 1.53E4 = (3.17E-08)-~(R [D/Q)) with the appropriate substitutions for the-cow milk pathway factor, R [D/Q], for Iodine-131. See Section 3.1.2.2.

-1.01 =-factor derived from the assumption that 99% of the total inhalation,-

-food and-ground plane pathway dose to the maximally exposed individual is contributed by I-131 via the cow-milk pathway.

.A4.3.3 ' Gaseous: Effluents From Ground-Level Release. Points.

Meteorological data for Hot Machine Shop Building Ventilation exhaust, Radwaste Facility exhaust, and Interim Radwaste Building releases is provided in Tables A4.0-2a and A4.0-2b.

.A4.3.3.1 Noble Gases

- For= dose estimates, simplified dose calculations based on the assumptions in

-A4.2.2.1 and operational and design basis source term data are presented below. These calculations further assume that the annual average dispersion parameter is used and that Xenon-133 contributes 95% of the gamma air dose and 93% of the beta air dose for ground-level releases.

1 Dy = 1.03E-10 [ Q ]Xe-133 (1.05)

Dg = 3.06E-10 [ Q ]Xe-133 (1.08)

Rev. 27 -

A-18 1/1/90

p ,

r k

wheret

((d'%,L]  ;

1.03E-10=(3.17E-8)-(353)'(X/3),derivedfromequationpresentedinSection

!? ,

3.1.2.1.

3.06E-10 = (3.17E-8) (1050)-(X/Q), derived from equation presented in Section 3.1.2.1. j

[ I) ) Xe-133 = the total Xenon-133 activity released in 9C1

= 9.2E-6 sec/m 8 , the ground level release dispersion parameter (X/Q) y/0 corresponding to the controlling location (S @ 1.0 miles) defined in Section A4.2.2.1.

-1.05 = factor derived from the assumption that 95% of the Gamma Air dose is contributed by Xe-133 1.08 = factor derived from the assumption that 93% of the Beta-Air dose is contributed by Xe-133 A4.3.3.2 Radioiodines, Particulates, and Other Radionuclides with T 1/2 ) 8 Days For dose estimates, simplified dose calculations' based on the asaumptions.in .

l A4.2.2.2 and operational and design basis source term data are presented below. These calculations further assume that the annual average dispersion / deposition parameters are used and that 98% of the ground-level l Ak"h} .

i _ .4 L release dose is from I-131 ingested by the maximally exposed individual via L the cow milk pathway at the controlling location. The simplified dose -

estimate for exposure to.the infant thyroid is:

D = 1.53E4 W (Q)g,g3g (l'.02) l where:

W = 2.10E-10 (D/Q) for food and ground plane pathway, in m'8 corresponding to' the controlling location (WNW @ 4.0 milea) defined in Section A4.2.2.2. l N- ,

L (Q)I-131 = the total I-131 activity released from Oconee ground-level l release points in WC1.

l-1.53E4 = (3.17E-08) (R [D/Q]) with the appropriate substitutions for ,

the infant-cow milk pathway, (R [D/Q]), for l I-131. See Section 3.1.2.2.

l' 1.02 = factor derived'from the assumption that 98% of the total inhalation, I food and ground plane pathway dose to the maximally exposed individual

. / is contributed by I-131 via the cow milk pathway.

l Rev. 27 l

A-19 1/1/90 L

l

n._ ,

b% <

l l p

F

/h

. L,/ 2

'A4.4 FUEL CYCLE CALCULATIONS i

, V <Assdiscussed=in Section13.3.S, more than_one nuclear power-station site may. r o contribute to'the doses to be considered in accordance with 40CFR190- The. .

-fuelkcycle=dosa assessments'for-Oconee' Nuclear Station only include liquid and' j gaseous dose: contributions from Oconee Nuclear Station since no other uranium  :'

. fuel cycle facility contributes significantly to Oconee's maximum exposed.

individual. For'this dose assessment, the total body and maximum organ dose <

contributions-to the maximum exposed-individual from Oconee's liquid and

' gaseous releases are: estimated using the following calculations:

• _DWB(T) DT =DWB(l o ).+ DWB(8e ) + DWB(83 )

DM0(T) DT =DH0(I o) + DMOI8)&DM0(8 e g)  ?

where:

DWB(T) = Total estimated fuel cycle whole body dose commitment resulting from the combined liquid and gaseous effluents from Oconee during the calendar year of-interest, in arem.

-DM0(T) = Total: estimated fuel cycle maximum organ dose commitment resulting

from the combined liquid and gaseous effluents from Oconee during the-l, calendar year of interest, in arom.

l 1 n .A4.4.1 -LIOUID' EFFLUENTS JLiquid pathway dose estimates are based on values and assumptions presented in i

Section A.4.3.1. Station operational source terms shall'be used to update ,j L 'these simplified calculations las necessary.

• Based on operational history, the Oconee .'uel cycle maximum exposed individual whole_ body done resulting from Oconee's '.1 quid effluent releases'(DWB(1,)) is estimated using the simplified dose calculation given below:

l DWB(I o ) = ( 7.13E5 ) (Fg)(T_g)(CCs-134 + 0.59 CCs-137 )

i M where: i l' 7.13E5 = 1.14E+05 ( U,,/ D , + U,g x BFg )'( DFait ) ( 1.23 )- l

[:

L where: '

l 1.14E+05 = ( 1.0E-06 pCi/uC1 x_.1.0E+03 ml/kg ) / ( 8760 hr/yr ) 1 U,,= 730 t/yr, Adult water consumption L

D" ==27.5, Dilution factor from the near field area to the nearest l y possible potable water intake p-

'U ag = 21 kg/yr, Adult fish consumption A

1 h

BFf = 2.00E+03, Bioaccumulation factor for Cesium (Table 3.1-1) l o Rev. 27 l!

A-20 1/1/90

F_

s m 4 -

L*

y, ,,

(@ , 4 e

b;w '  ;

[% ['}

~

pp g

.-g;21E-04, Adult; total bodylingestionLdose factor for.Cs-134 yq) (Table 3;1-2):

1.23 = Factor derived from the assumption th'at 81% of the dose is-l - derived from Cs-134'and'Cs-1377or'100% / 81% = 1.23 c- .where:

h' '. F g '= (f) (c)T/ (F4 f) -

4 - whers::

'f = Oconee's liquid radwaste' flow, in spm F = Oconee's dilution flow, in spa o =.1.0, the- recirculation factor at equilibrium

, where:

1 TI= 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />, the time period of time over which CCs-134 , C-Cs-137  ;

and'Fg-are averaged.

C Cs-134

= The average-concentration of-Cs-134 in Oconee's undiluted l' ,

offluent..-in: uC1/m1, during the calsadar ; year;of interest.

=C Cs-137

= e average e ncentration of Cs-137- h Oconee's undiluted -

E 'Q) * -affluent, in-uCi/m1, during the calendar year of interest =

L%

0.59-= The ratio of the adult' total, body' ingestion dose factors'for.

Cs-134 and Cs-137 or 7;14E-05 /"1.21E-04 = 0.59 Based on operational history, the-Oconee fuel' cycle maximum exposed. individual maximum organ dose _(Adult GI-Track) resulting from Oconee's liquid effluent releases..-(DM0(l o )) is estimated using-the simplifiedidose calculation given below: . 1 Dgg(1,);= '(-1.67E6 ) (Fg)(Tg )-( CNb-95 ]

$ where:

1 j l1.67E6 =~1.14E+05 ( U,, / D, + U,g x BFg ) ( DF,gg ) ( 1.11 )

l

~

where:

? 1~.14E+05 = ( 1.0E+06 pC1/uci x 1.0E+03 ml/kg )-/ ( 8760 hr/yr) y,  ! U,, = 730: t/yr, Adult water consumption L

1 D,= 27.5, Dilution factor from the near field area to the nearest possible potable water intake p U,g = 21 kg/yr, Adult fish consumption

? .BFg = 3.0E4, Bioaccumulation factor for Niobium (Table 3.1-1) l Rev. 27

!: A-21 1/1/90 p

.. a

/

8 ,

+

.- (

': Q : .

l c c: ,

)

..T' J a  ;

, ,g . 1 3 b DF =-2.10E-5,' Adult.GI-track ingestion dose ~ factor M ait. ~

'for Nb-95 (Table 3.1-2). s

+ >:1'.11-= Factor derived from the, assumption.that.90% of.the dose is derived-

~

.from Nb-95 or 100% / 90%:= 1.11 where:-

'F g =(f)'(c)\/'(F.+f)  ;

where::

q f = Oconee's liquid radwaste flow, in gpm. .;

F = Oconee's-dilution _ flow, in gpm g ]

'o = 1.0, the recirculation factor at equilibrium n

')

where:

~ Tg=;8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />,.the. time period of. time-over,which C Nb-95 and Jg are are averaged.

-C e average c ncentrat n f -9 in Oconee's unu luted Nb-95 = effluent, in.uci/m1, during the calendar year-of interest.-

KM L. A ,/ ,A4.4.2. GASEOUS EFFLUENTS FROM SEMI-ELEVATED RELEASE POINTS 6' 1 Airborne effluent pathway-dose-estimates are based on the: values and H assumptions presented in Section A4.3.2. -Station operational source term data 1 shall be used to update these calculations as necessary. q Based on operational history, the Oconee fuel cycle maximum exposed individual

- L whole- body' dose::resulting from 0coriee's semi-elevated gaseous. effluent releases (DWB(8,)) is; estimated using the simplified dose calculation given below:

' WB(8e ) = ( 9.32E-06 ) ( w ) ( QXe-133 ) (8 F ) ( I* )

tt- 'where:-

18

.l

? w = 2.6E-7 = (X/Q) defined in Section A4.3.2.1.

1 3 s s-QXe-133 = The total Xe-133 activity released from Oconee during the l calendar year of interest,.in uCi.

1 9.32E-06'= '( 3.17E-08 ) ( Kg ), with appropriate substitutions for l' whole body exposure in a semi-infinite cloud of Xe-133. See l} Section 1.2.1.

L

- )

l' Rev. 27

(< -

A-22 1/1/90 l J l s a _ - - _ _ _ 1

s w t

(:I H , ,

g: -.

t.

([ Sp = 0.7.= External radiation shielding factor for individuals.

.1.09 = The factor derived from the conservative assumption (based on historical data) .that.92% of the.whole body dose. to the maximally L exposed individual is contributed by Xe-133. ,

Based on operational history, the Oconee fuel cycle maximum exposed individual ,

maximum organ dose-(Adult GI-Track) resulting from Oconee's semi-elevated

-gaseous effluent releases (DMn(8 8 )) is conservatively estimated using the

-simplified' dose calculation gIven below:

n DQOI8 e ) = ( 3.27E+2 ) ( W )Cs( h -137 ) ( 1.89 ) .

where:

3.27E2 = ( 3.17E-8 ) ( R [D/Q) ) with appropriate substitutions for the ground plane pathway factor, R [D[Q),forCesium-137. See Section-3.1.2.2.

tal Cs-137 activity released in W .

(Q)Cs-137 = . de

W = 4.-5E-9, the semi-elevated release deposition. parameter (D/Q) for= food and ground plane pathway, in m 8 corresponding to the controlling location S @ 1.0 miles.

v

). 1.89 = factor derived from the assumption that 53% of the total inhalation food,s and ground plane pathway dose to.the maximally r

exposed 4 individual is contributed by Cs-137 via the ground plane prthway.

A4.4.3 -GASEOUS-EFFLUENTS FROM GROUND-LEVEL RELEASE POINTS

-Airborne effluent pathway dose estimates are based on the values and rassumptions presented in Section A4.3.2. Station operational source term data shall be used to update these calculations as.necessary.

Based'on design basis source term-data and operational history, the Oconee fuel cycle maximum exposed individual whole body dose resulting from Oconee's

. ground-level gaseous effluent releases (DWB(g 8 )) is estimated using the simplified dose calculation given below:

DWB(8 g )= 9.32E-06 ) ( w ) ( hXe-133 ) ( F) ( 1.05 ) .

where:

w = 9.2E-6 = (X/Q) as defined in Section A4.3.3.1. l~

Q Xe-133

= The total Xe-133 activity released from Oconee during the

._ calendar year of interest, in uC1.

.O

'(/ 9.32E-06 = ( 3.17E-08 ) ( Kg ), with appropriate substitutions for l whole body exposure in a semi-infinite cloud of Xe-133. See l

Section 1.2.1.

Rev. 27 l A-23 1/1/90 l

i l

e

]

$ .. - . l

_ (~

( ) S' = 0.7 =' External radiation shielding factor for' individuals.  !

LJ I l'.05 = The factor-derived-from the conservative assumption (based on historical data)-that_95% of the whole body dose to the maximally exposed individual is contributed by Xe-133.

Based on design basis source term data and operational _ history, the Oconee fuel cycle maximum exposed individual maximum organ dose (Adult GI-Track) I- 1 resulting from Oconee's ground-level gaseous effluent releases (DM0(8 g )) I*

conservatively estimated using the simplified dose calculation given below:

DM0(g) = ( 3.27E+2 ) F W ) ( Csh -137 ) ( 1.89 ) ,

, .where:  ;

3.27E2 = ( 3.17E-8 ):( R [6[d])withappropriatesubstitutionsforthe ground plane pathway factor, RU [D/Q], for Cesium-137. See Section 3.1.2.2.

(Q)Cs-137 = the total'Cs-137 activity released in 901.

W = 2;1E-8, the ground-level release deposition parameter (D/Q) for food ,

and ground plane pathway, in m 8 corresponding to the controlling location S @ 1.0 miles.

n

'I I 1 89 = factor derived from the assumption-that_53% of the total V inhalation, food, and ground plane pathway dose to the maximally-exposed individual is contributed by Cs-137 via the 8round plane pathway, r

s U>6 Rev 27 l A-24 1/1/90

~'

[

y- -

,1 TAB M A4.0-1a .

OCONEE NUCIEAR STATION (1 of 1)

DISPERSION' PARAMETER (X/0) FOR SEMI-EIEVATED IANG 'IERM RELEASES > 500 HR/YR OR > 125 HR/UIR-(sec/m')

Distance to the control location, in miles Sector 0-0.5* 0.5-1.0* 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 6.5E-8 4.8E-8 4.7E-8 -4.7E-8 4.7E-8 6.3E-8 5.9E-8 5.6E-8 NNE 1.1E-7 9.3E-8 8.7E-8 8.9E-8 9.2E-8 9.2E-8 7.2E-8 5.9E-8 NE 7.5E-8 7.2E-8 6.8E-8 5.8E-8 6.1E-8 6.4E-81 6.0E-8 5.7E-8 ENE 6.0E-8 6.4E-8 5.9E-8 6.1E-8 5.7E-8 5.7E-8 5.6E-8 5.6E-8 E 4.1E-8 3.7E-8 5.7E 4.8E-8 5.2E-8 4.9E-8 4.7E-8 4.5E-8 ESE 3.0E-8 4.0E-8 6.7E-8 5.8E-8 4.3E-8 5.3E-8 4.9E-8 4.7E-8

! SE 2.8E-8 2.8E-8 '6.0E-8 5.1E-8 4.1E-8 3.7E-8 3.8E-8 3.8E-8

! SSE 2.3E-7 2.0E-7 3.2E-7 2.5E-7' 3.7E-7 2.9E-7 2i7E-7 2.5E-7 l S 2.6E-7 3.0E-7 2.1E-7 2'.1E-7 3.6E-7 4.1E-7 3.7E-7 3.6E-7 SSW 3.2E-7 3.1E-7 2.9E-7 2.7E-7 2.0E-7 1.7E-7. 1.7E-7 1.7E-7 j

SW 7.3E-8 7.1E-8 7.1E-8 5.9E-8 3.9E-8 4.4E-8 4.5E-8 4.5E-8 l

WSW 5.3E-8 5.2E-8 5.3E 4.2E-8 4.8E-8 4.3E-8 4.2E-8. 4.2E-8 W 2.7E-8 3.2E 3.7E-8 '3.7E-8 3.9E-8 3.9E-8 3.7E-S 3.6E-8 ,

WNW 2.3E-8 2.5E-8 3.5E-8 3.5E-8 3.3E-8 3.2E-8 3.0E-8 2.9E-8 NW 3.2E-8 3.7E-8 3.1E-8 3.3E-8 3.0E-8 3.1E-8 2.9E-8 2.8E-8 NNW 6.8E-8 '7.7E-8 8.3E-8 7.7E-8' 7.8E-8' 6.5E-8 6.3E-8 6.2E-8

• Inside Exclusion Arec Boundary (EAB)

Rev. 23 1/1/89

_ _ _ _ . - .- . - - , . - , - , . - , . ~ . . . - . . - .- .a ..: . . .

_. m .__ - . ,

w

~

}{

TABE A4.0-1b OCONEE NUCEAR STATION (1 of 1).

DEPOSITION PARAMETER (D/0) FOR SEMI-ELEVATED LONG TERM REEASES > 5001Dt/YR OR > 125 HR/QTR (m~2)

Distance to the control location. in miles

. Sector 0-0.5* 'O.5-1.0* 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 2.4E-9 1.4E-9 8.7E-10 6.0E-10 4.7E-10 3.6E-10 2.8E-10. 2.3E-10 NNE 4.1E-9 2.2E-9 1.4E-9 9.6E-10 7.4E-10' 5.7E-10 4.4E-10 3.6E-10 NE 2.7E-9 1.5E-9 9.7E-10 6.6E-10 5.0E-10 3.9E-10 3.1E-10 2.5E ENE 1.5E-9 8.4E-10 5.4E-10 3.7E-10 2.8E-10 2.2E-10 1.7E-10 1.4E-10' E 1.6E-9 8.7E-10 5.6E-10 3.9E 3.0E-10 2.3E-10 1.8E-10 1.5E-10 ESE 1.3E-9 7.0E-10 4.5E-10 3.0E-10 2.3E-10 1.8E-10 1.4E-10 1.1E-10 SE 8.0E-10 4.4E-10 2.9E-10 2.0E-10 1.5E-10 1.2E-10 8.9E-11 7.3E-11 SSE 2.7E-9 1.6E-9 1.1E-9 '7.5E-10 6.0E-10 4.6E-10 3.6E-10 3.0E-10 S 4.5E-9 2.6E-9 1.7E-9 1.2E-9 9.0E-10 7.0E-10 5.5E-10 4.5E-10 SSW 4.3E-9 2.5E-9 1.6E-9 1.1E-9 8.5E-10 6.5E-10 5'0E-10

. 4.2E-10 SW 1.4E-9 8.4E 5.5E-10 .3.9E-10 3.0E-10 2.3E-10 1.8E-10 1.5E-10 WSW 1.6E-9 9.1E-10 6.0E-10 4.1E-10 3.2E-10 2.5E-10 1.9E-10 1.6E-10 W 1.4E-9 7.9E-10 5.1E-10 3.6E-10 2.7E-10 2.1E-10 1.6E-10 1.3E-10 WNW 7.7E-10 4.4E-10 2.9E-10 2.0E-10 1.5E-10 1.2E-10 9.2E-10 7.4E-11 NW 1.1E-9 5.9E-10 3.8E-10 2.6E-10 2.0E-10 1.6E-10 1.2E-10 9.9E-11 NNW 1.9E-9 1.0E 6.6E-10 4.5E-10 3.5E 2.7E-10 2.1E-10 1.7E-10

• Inside Exclusion Area Boundary (EAB)

Rev. 23 1/1/89

em,, g, 7 .

Y

• f,_,?-

~

._y

_ s

. TABLE A4.0-2a l l OCONEE NUCEAR STATION 1 L (1 of 1)

I DISPERSON PARAMETER (X/0) FOR GROUND EVEL. LONG TERM RELEASES > 500 HR/YR OR > 125 HR/GTR.

l (sec/m')

Distance to the control location. In miles Sector 0-0.5* 0.5-1.0* 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0- 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 2.7E-6 1.1E-6 6.1E-7 3.9E-7 2.8E-7 2.1E-7 1.6E-7 1.3E-7 NNE 2.4E-6 .9.8E-7 5.4E-7 3.4E-7 2.4E-7 1.8E-7 1.4E-7 1.2E-7 NE 2.9E-6 1.2E-6 6.5E-7 4.2E-7 2.9E-7 2.2E-7 1.7E-7 .1.4E-7 ENE 2.6E-6 1.0E-6 5.7E-7 3.6E-7 2.6E-7 1.9E-7 1.5E-7 1.2E-7 E 3.0E-6 1.2E-6 6.6E-7 4.3E-7 3.0E-7 2.3E 1.8E-7 1.4E-7 ESE 3.1E-6 1.2E-6 6.9E-7 4.5E-7 3.2E-7 2.4E-7 1.9E-7 1.6E-7 SE 3.7E-6 1.5E-6 8.4E-7 5.4E-7 3.9E-7 2.9E-7 2.3E-7 1.9E-7 SSE 5.3E-6 2.2E-6 1.2E-6 7.9E-7 5.7E-7 4.3E-7 3.4E-7 2.8E S 9.2E-6 3.7E-6 -2.1E-6 1.4E-6 9.8E-7 7.4E-7 5.9E-7 4.8E-7 SSW 4.4E-6 1.8E-6 1.0E-6 '6.5E-7 4.6E-7 3.5E-7 2.8E-7 2.3E-7 SW 4.5E-6 1.8E 1.0E-6 6.5E-7 4.6E-7 3.5E-7 2.7E-7 2.2E-7 WSW 2.6E-6 1.1E-6 5.9E 3.8E-7 2.7E-7 2.0E-7 1.6E-7 1.3E-7 W 2.2E-6 9.1E-7 5.0E-7 3.2E-7 2.3E-7 1.7E-7 1.3E-7 .1.1E-7 WNW 1.6E-6. 6.6E-7 3.6E 2.3E-7 1.7E-7 1.2E-7 9.8E 8.0E-8 NW 1.9E 7.7E-7 4.2E-7 2.7E-7 1.9E -1.4E-7 1.1E-7 9.1E-8 NNW 2.4E-6 9.9E-7 5.4E-7 3.5E-7 2.5E-7 1.9E-7 1.5E-7 1.2E-7

• Inside Exclusion Area Boundary (EAB) 4 Rev.'23 1/1/89

_ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - -_ _ -. - - - - , . . . _ - . . . . - . . . - - - - a

c-- _

--m m : - -,

'n

%.f 9,( ; }

W TABE A4.0-2b OCONEE NUCIEAR' STATION (1 of 1)'

DEPOSITION PARAMETER (D/0) FOR GROUND IZVEL. IDNG "IERM RELEASES > 500 HR/YR OR > 125 BR/QTR (m~8).

Distance to the control location. in siles Sector 0-0.5* 0.5-1.0* 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 1.2E-8 4.3E-9 2.1E-9 1.3E-9 8.2E-10 5.8E-10 4.3E-10 3.3E-10 NNE 1.5E-8 5.2E-9 2.6E-9 1.5E-9 1.0E-9 7.0E-10 5.2E-10 4.0E-10 NE 1.7E-8 5.9E-9 2.9E-9 1.7E-9 1.1E-9 8.0E-10 5.9E-10 4.6E-10 ENE 1.1E-8 3.9E-9 1.9E-9 1.1E-9 7.5E-10 .5.3E-10 3.9E-10 3.0E-10 E '1.2E-8 4.2E-9 2.1E-9 1.2E-9 8.0E-10 5.6E-10 4.2E-10 3.2E-10 ESE 1.1E-8 3.8E-9 'I.9E-9 1.1E-9 7.3E-10 5.1E-10 3.8E-10 2.9E-10 SE 9.5E-9 3.4E-9 1.7E-9 1.0E-9 6.5E-10 4.6E-10 3.4E-10 2.6E-10 l SSE 1.2E-8 4.2E-9 2.1E-9 1.2E-9 7.9E-10 -5.6E-10 4.1E-10 3.2E-10 S 2.1E-8 7.5E-9 -3.7E-9 2.2E-9 1.4E-9 1.0E-9 7.4E-10 5.7E-10 i SSW 1.2E-8 4.1E-9 2.1E-9 1.2E-9 7.9E-10 5.6E-10 4.1E-10 3.2E-10 SW 1.6E 5.9E-9 2.9E-9 1.7E-9 1.1E-9 8.0E-10 5.9E-10 4.5E-10 WSW 1.3E-8 4.5E 2.2E-9 1.3E-9 8.6E-10 6.1E-10 4.5E-10 3.5E-10 W 9.8E-9 3.5E-9 1.8E-9 1.0E-9 6.7E-10 4.7E-10 J3.5E-10 2.7E-10 WNW 5.9E-9 2.1E-9 '1.1E-9 6.2E-10 4.1E-10 2.9E-10 2.1E-10 1.6E-10 NW 7.3E-9 2.6E-9 1.3E-9 7.7E-10 5.0E-10 3.5E-10 2.6E-10 2.0E-10 NNW 9.7E-9 3.5E-9' 1.7E-9 1.0E-9 6.6E-10 4.7E-10 3.5E-10 2.7E-10

• Inside Exclusion Area Boundary (EAB)

Rev. 23 1/1/89 l

l

b 4 4

Y

p.).

t TABLE A4.0-3 *-

Q (1 of 3)

OCONEE NUCLEAR STATION ADULT A ah DOSE PARAMETERS (ares /hr per pCi/ml)'

- NUCLIDE BONE = LIVER T. BODY THYROID KIDNEY LUNG GI-LII H 3 0.0 5.44E-01 5.44E-01 5.44E-01 5.44E-01 5.44E-01 5.44E-01 1 NA 24 4.12E+02 4.12E+02 4.12E+02 4.12E+02 4.12E+02 4.12E+02 4.12E+02 j

. CR 51 0.0 0.0 1.28E+00 7.66E-01 2.82E-01 1.70E+00 3.22E+02  !

MN 54 0.0 4.39E+03 '8.38E+02 0.0- 1.31E+03 0.0 1.34E+04  !

MN 56 0.0 1.10E+02 1.96E+01 0.0 1.40E+02 0.0 3.53E+03 1' FE 55 6.67E+02 4.61E+02 1.07E+02 0.0 0.0 2.57E+02 2.64E+02 FE 59 1.05E+03 2.47E+03 9.48E+02 0.0 0.0 6.91E+02 8.24E+03 ,

CO 58 0.0 9.14E+01- 2.05E+02 0.0 0.0 0.0 1.85E+03 .l CO 60 0.0 2.63E+02 5.79E+02 0.0 0.0 0.0 -4.93E+03-  !

NI 63 3.15E+04 2.18E+03 1.06E+03 0.0 0.0 C.0 4.56E+02 NI 65 1.28E+02 1.66E+01 7.59E+00 0.0 0.0 0.0- 4.22E+02  !

, ' CU 64' O.0 '1.02E+01 4,80E+00 0.0 2.58E+01 0.0- 8.71E+02 l ZN 65- 2.32E+04 7.38E+04 3.33E+04 0.0 4.93E+04 .0.0 4.65E+04 l

- ~

ZN 69- 4.93E+01 9.44E+01 6.56E+00 0.0 6.13E+01 0.0 1.42E+01 j BR 83 0.0 -0.0 4.05E+01 0.0 0.0 0.0 5.84E+01. l BR 84 0.0- 0.0 5.25E+01 0.0 0.0 0.0 4.12E-04 j BR 85 0.0 0.0 2.16E+00 '0.0 0.0 0.0 0.0

- RB 86 0.0 1.01E+05 4.71E+04 0.0 0.0 0.0 1.99E+04 ..

I RB 88 0.0 2.90E+02 1.54E+02 0.0 0.0 0.0 4.01E-09 RB:89 0.0 1.92E+02 1.35E+02 0.0 0.0 0.0 1.12E-11  :

SR 89 2.31E+04 0.0 6.62E+02 0.0 0.0 0.0 3.70E+03 I SR 90 2.87E+05 0.0 7.71E+04 0.0 '0.0 0.0 1.64E+04 .

SR 91 4.24E+02 0.0 1.71E+01 0.0 0.0 0.0 -2.02E+03

' SR 92 1.61E+02 0.0 6.96E+00 0.0 0.0 0.0 3.19E+03 -1 Y 90 6.05E-01 0. 0 - 1.62E-02 0.0 0.0 0.0 6.41E+03 j Y i91M 5.72E-03 0.0 2.21E-04 0.0 0.0 0.0 1.68E-02 -i Y - 91 8.87E+00 0.0 2.37E 0.0 0.0 0.0 4.88E+03 ~)

Y ' 92 5.31E-02 0.0 1.55E-03 0.0 0.0 0.0 9.31E+02 i

• Methodology for. table provided by: M. E. Wrangler, RAB:NRR:NRC on 3/17/83-(

\

TABLE A4.0-3 Rev. 10 (1 of 3) 1/1/86

kI 1

J/~'d TABLE A4.0-3 (2 of 3)

OCONEE NUCLEAR STATION ADULT A,g DOSE PARAMETERS

-(mree/hr per UC1/ml) l- ,

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LII .

5 Y 93 1.69E-01 0.0 4.65E-03 0.0 0. 0 - 0.0 5.34E+03-ZR 95 3.32E-01 1.07E-01 7.21E-02 0.0 1.67E-01 0.0 3.38E+02 ZR 97 1.84E-02 3.70E-03 1.69E-03 0.0 5.59E-03 0.0 1.15E+03

• NB 95. 4.47E+02 2.49E+02 1.34E+02 0.0 2.46E+02 0.0 1.51E+06 MO 99 0.0 1.16E+02 2.21E+01 0.0 2.63E+02 0.0 2.69E+02 TC 99M 9.62E-03 2.72E-02 3.46E-01 0.0 4.13E-01 1.33E-02 1.61E+01 TC 101 9.89E-03 1.43E-02 1.40E-01 0.0 2.57E-01 7.28E-03 4.28E-14 RU 103 4.99E+00 0.0 2.15E+00 0.0 1.90E+01 0.0 5.82E+02 RU 105.~4.15E-01 0.0 1.64E-01 0.0 5.37E+00 0.0 2.54E+02-1

.RU 106 7.42E+01 0.0 9.38E+00 0.0 1.43E+02 0.0 4.80E+03 AG 110M'1.37E+00 .1.26E+00 7.50E-01 0.0 2.48E+00 0.0 5.15E+02 .

E 125M 2.57E+03 9.33E+02 3.45E+02 7.74E+02 1.05E+04 0.0 1.03E+04

- (~') TE 127M 6.50E+03 2.32E+03 7.93E+02 1.66E+03 2.64E+04 0.0 2.18E+04

( ,/ TE 127 1.06E+02 3.79E+01 2.29E+01 7.83E+01 4.30E+02 0.0 8.34E+03~

'TE 129M 1.10E+04 4.12E+03 1.75E+03 3.79E+03 4.61E+04 0.0 5.56E+04 TE 129 3.02E+01 1.13E+01 .7.35E+00 2.32E+01 1.27E+02 0.0 2.28E+01'  ;

-TE 131M 1.66E+03 8.13E+02 6.77E+02 1.29E+03 8.23E+03 0.0 8.07E+04 ,

TE 131 1.89E+01. 7.91E+00 5.98E+00 1.56E+01 8.29E+01 0.0 2.68E+00 TE1132 '2.42E+03 1.57E+03 1.47E+03 1.73E+03 1.51E+04 - 0. 0 7.41E+04 3 I :130--2.94E+01 8.68E+01 3.43E+01 7.36E+03 1.35E+02 0.0 7.48E+01

I '131 1.62E+02 2.32E+02 1.33E+02 7.59E+04 3.97E+02 00

. 6.11E+01 l I 132 7.90E+00 2.11E+01 7.40E+00 7.40E+02 3.37E+01 0.0 3.97E+00 I 133. 5.53E+01 9. 62E+01- 2.93E+01 1.41E+04 1.68E+02 0.0 8.64E+01 :l I. 134 4.13E+00 1.12E+01 4.01E+00 1.94E+02 1.78E+01 0.0- 9.77E-03 l I 135 1.72E+01 4.52E+01 1.67E+01 2.98E+03 7.24E+01. 0.0 5.10E+01 l CS 134 2.98E+05 7.09E+05 5.80E+05 0.0 2.29E+05 7.62E+04 1.24E+04

-CS 136 3.12E+04 1.23E+05 8.86E+04 0.0 6.85E+04 9.39E+03 1.40E+04 CS 137- 3.82E+05 5.22E+05 3.42E+05 0.0 1.77E+05 5.89E+04 1.01E+04 CS 138' 2.64E+02 5.22E+02 2.59E+02 0.0 3.84E+02 3.79E+01 2.23E-03 BA 139 1.22E+00 8.71E-04 3.58E-02 0.0 8.14E-04 4.94E-04 2.17E+00-

-s

\,)

TABLE A4.0-3 Rev. 10 (2 of 3) 1/1/86

p i' l l

TABLE A4.0-3 v[ \ (3 of 3) i OCONEE NUCLEAR STATION ADULT A,g DOSE PARAMETERS ,,

(mzem/hr per pC1/ml) .

l NUCLIDE ' BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LII BA 140 2.56E+02 3.21E-01 1.68E+01 0.0 1.09E-01 1.84E-01 5.27E+02 BA 141' 5.94E-01 4.49E-04 2.00E-02 0.0 4.17E-04 2.55E-04 2.80E-10 BA 142 2.68E-01 2.76E-04 1.69E-02 0.0 2.33E-04 1.56E-04 3.78E-19 LA 140 1.57E-01 7.92E-02 2.09E-02 0.0 0.0 0.0 5.82E+03 LA 142 8.05E-03 3.66E-03 9.12E-04 0.0 0.0 0.0 2.67E+01 i CE 141 5.07E-02 3.43E-02 3.89E-03 0.0 1.59E-02 0.0 1.31E+02 CE 143 8.94E-03 6.61E+00 7.32E-04 0.0 2.91E-03 0.0 2.47E+02 '

CE'144 2.65E+00 1.11E+00 1.42E-01 0.0 6.56E-01 0.0 8.94E+02 PR 143 5.78E-01 2,32E-01 2.87E-02 0.0 1.34E-01 0.0 2.53E+03 PR 144 1.89E-03 7.86E-04 9.62E-05 0.0 4.43E-04 0.0 2.72E-10 ND 147 3.95E-01 4.57E-01 2.74E-02 0.0 2.673-01 0.0 2.19E+03 W 187 2.96E+02 2.48E+02 8.66E+01 0.0 0.0 0.0 8.11E+04-

[~'h NP 239- 3.21E-02 3.16E-03 1.74E-03 0.0 9.84E-03 0.0 6.47E+02 4g ~.,

I l

l l

l l

l' #%

%- l i

TABLE A4.0-3 Rev. 10 l (3 of 3) 1/1/86 I s

^

4 ,

)

I i

gs _

.(

f~f. ~

'A5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING The radiological environmental monitoring progr.im shall be conducted in <

s accordance with Technical Specification 4.11.

The monitoring program locations and analyses are given in Tables AS.0-1 through A5.0-3-and Figure AS 0-1.

Site specific characteristics make ground water sampling and food product i sampling unnecessary. : Ground water recharge is from~ precipitation and the -

ground water gradient is toward the effluent discharge area; therefore, contamination of ground water from liquid effluents is highly; improbable. .g However,=some ground water sampling is performed to verify this. Food products will not be sampled since lake water irrigation of crops is not _ .; '

. practiced in the vicinity.

The laboratory performing the radiological environmental analyses shall i participate in an.interlaboratory comparison program which has been approved.

by the NRC. This' program is the Environmental Protection Agency's (EPA's)

Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck)  !

Program, our participation code is CP, The dates of the' land-use census that was used to identify the controlling receptor locations was 08/02/89 - 08/10/89.

l O .

(

], Rev. 27 A-25 1/1/90 L

~

(

l -

(,/ . "

TAB E A5.0-1 (l'of 1)

OCONEE RADIGIDGICAL MONI1DRING PROGRAM SAMPLING IDCATIONS (TLD LOCATIONS)

SAMPLING LOCATION DESCRIPTION

• SAMPLING IDCATION DESCRIPTION *

(0.2 MILES N). 040 4-5 MIE RADIUS (4.5 MILES E) 020 SITE BOUNDARY '

041 4-5 MIM RADIUS (4.0 MILES ESE) 02I SITE BOUNDARY (0.2 MILES NNE)

(0.5 MILES NE) 042 4-5 MILE RADIUS (5.0 MILES SE) 022 SITE BOUNDARY SITE BOUNDARY (0.9 MIES ENE) 043 4-5 MIM RADIUS (4.0 MIES SSE) 023 (4.0 MILES S)

(0.8 MILES E) _044 4-5 MILE RADIUS 024 SITE BOUNDARY (0.6 MIES ESE) 045 4-5 MIE RADIUS (5.0 MILES SSW) 025 SITE BOUNDARY (0.3 MILES SE) 046 4-5 MILE RADIUS (4.5 MIES SW) 026 SITE BOUNDARY (0.3 MILES SSE) :047 4-5 MIM RADIUS (4.0 MIES WSW)

! 027 SITE BOUNDARY (0.5 MILES S) 048 4-5 MILE RADIUS (4.0 MIES W) 028 SITE BOUNDARY (4.0 MIES WNW)

(0.6 MILES SSW) 049 4-5 MILE RADIUS- ,

029 SITE BOUNDARY '

(0.4 MILES SW) 050 4-5 MILE RADIUS (4.0 MILES NW)

! 030 SITE BOUNDARY (0.2 MILES WSW) 051 4-5 MIE RADIUS (4.5 MILES NNW)

! 031 SITE BOUNDARY (0.2 MILES W) 052 SPECIAL INTEREST . (12.0 MILES ENE) f 032 SITE BOUNDARY SITE BOUNDARY (0.2 MILES WNW) 053 SPECIAL INTEREST (11.0 MIES E) l 033 (9.5 MIES ESE)

(0.2 MILES NW) 054' SPECIAL INIEREST-034 SITE BOUNDARY (0.1 MIES NNW) 055 SPECIAL INTEREST (9.5 MILES SSE) 035 SITE BOUNDARY

-(4.0 MILES N) 056 SPECIAL INTEREST (8.4 MILES SSW) 036 4-5 MILE RADIUS 4-5 MILE RADIUS (4.5 MILES NNE) 057 SPECIAL INTEREST (9.0 MIES SW) f 037 (10.0 MI E S WSW)

(4.0 MIES'NE)- 058 SPECIAL INTEREST 038 4-5 MILE RADIUS (9.0 MILES IW) 4-5 MILE RADIUS (4.0 MILES ENE) 059 SPECIAL INITmT 039

• All sampling locations are collected quarterly l

l i

Rev. 23 1/1/89-

~ -= _ -. .. ._ _ _ . - .2 - _ _ _ . _ . . _ . _ .

. , _^

, .: ~

f 'N ~- ~

. .TABIE . -2' bl 6 (1 0F 1)

OCONEE RADIDIDGICAL MONITORING PROGRAM SAMPLING LOCATIONS (UIMER SAMPLING IDCATIONS) .,

'N -

' CODE: ,,

3- u 3- t W - Weekly ( $ 7 days)

• g 3 j g

,g -j m- '>.

SM - Semimonthly.( $ 15 days) lg M - Monthly.( $ 31 days) o t'  :* , g g SA - Semiannually ( $'184 days) g

• 3 g .g

• O E -.c l-

'E .w '

a ti e t .8 0 2 m

• A m m

_______________________________________x:

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _S_ A_M_P_ L_ IN_G_ _L_O_C_ A_T_ _I O_N_ _D_E_S_C_R_ _I P_T_ I_O_N_ _ _ _ _ _ _ ___. _ _ _ _ _ _ _ _ _ _4

• 028 Site Boundary (0.5 miles-S) M 060 New Greenville Water Intake Rd. (2.5 miles ISIE)

• W M SA M 061 Old Hwv. 183 (1.5 miles SSW) W 062 Lake Keowee/ Hydro' Intake (0.7 mile ENE) (CONIROL) M Lake Hartwell - Hwv'183 Bridae (0.8 alle ESE) (000.7) M SA SA 063 064 Seneca (6.7 miles SW) (004.1) (CONTROL) M 065 Clemson (8.1 miles SSE)'(006.1) DELETED M .

066 Anderson (19.0 miles SSE) (012) (C0KITOL FOR MIIK ONLY) M SM 067 Lawrence Ramsey Bridae, Hwy 27 (4.2 miles SSE) (005.2) SA - SA 068 High Falls County Park (2.0 miles W) (CONTROL)' SA 069 Poweil Residence (4.5 miles WNW) (002.1) SM 071 Clemson Dairy (10.3 m'iles SSE) (006.3) SM 072 Hwy 130 (1.7 miles S) W 073 Tamassee Der School (9.0 miles NW) (CONTROL) W M l 074 Keowee Key Resort (1.7 miles NNW) W 075 Willison Residence (6.0 miles NE) DEIE1TD - SM

~

• Control for Fish only.

Rev. 27 1/1/90

_ _ _ _ _ __._____m_

. _ + -t* - = _ _ _ m-_ 1 M __ - ' ' ' ' * ' -

_. _ 4'r- 'r*eN^r M M

-*'~,

. _ , .. /-

,sw

- '. #" 'N .

N..J Y .

TABE AS.0-3 (1 of 1)

OCONEE RADIOLOGICAL MONI~IDRING PROGRAM ANALYSES ANALYSES SAMPLE MEDIUM ANALYSIS SCHEDUE GAMMA ISUIUPIC "IltITIUM Iinf EVEL I-131 GROSS BETA "I~tD '

1. Air Rsdiolodine and Particulates . Weekly .X

2. Direct Radiation. Quarterly X 4

3. Surface Water Monthly X Quarterly Composite. X

4. Drinking Water Monthly X X Quarterly Composite X

5. Shoreline Sediment Semiannually X

6. Milk Semimonthly. X X

7. Fish Semiannually X

8. Broadleaf Vegetation Monthly X b

Rev. 3

-I 1/1/84 t

. - .#,.<.m . -.,y,.

- ~,._-,,-..-.m__ , , , , .,..% .-,.m.. , . . . . ...,s . , . .. . , ,w ,