Text

Rev 33 to McGuire Nuclear Station Odcm
	ML20094H239
Person / Time
Site:	Oconee, Mcguire, McGuire
Issue date:	01/01/1992
From:	Mcconnell T; DUKE POWER CO.
To:	;
Shared Package
ML15217A135	List: ML15217A134; ML16131A522; ML16131A524; ML20094H239; ML20094H251;
References
	PROC-920101-01, NUDOCS 9203090199
	Download: ML20094H239 (53)
	v • d • e

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December 24, 1991-SUBJ ECT:

McGuire Nuclear Station Offsite Dose Calculation Manual Revision 33 The General Office Radwaste Processing & Management Staff is transmitting to you this date, Revision 33 of the Offsite Dose Calculation Manual.

As this revision only affects McGuire Nuclear Station, the approval of other station managers is not required.

Please update your copy No.

S/-

and discard the affected pages.

Instructions:

Please replace the entire contents of Section "B" with the attached pages.

NOTE:

As this letter, with its attachments, contains "LOEP" information, please insert this letter in front of the December 23, 1991 letter.

Approval'Date:

/ */u /9/

Approval Date:

/A//9/1/

Effective Date:

1/1/92 Effective Date:

1/1/92 CJ i i

r/

>R y cuidun,o 4 irpc,at]

T. 9 ;,McConnell, Manager G.

L.

Courtbb

/

U.

Radiation Protection Manager McGuire Nuclear Station If you have any questions concerning Revision 33, please call

-Jim Stewart at (704 373-5444.

617; M

~

James M. _ Stewart, Jr.

Sc_lentist Radwaste Processing & Management JMS/prm.091

gn8ans88He P

V

1 APPENDIX _B - TABLE OF CONTENTS EAlt

- Bl.0 MCGUIRE NUCLEAR STATION RADWASTE SYSTEMS B-1_

B2.~0 RELEASE RATE CALCULATION-B '

B3.0 RADIATION MONITOR SETPOINTS B-8 B4.0 DOSE CALCUMTIONS B-12 B5.0 RADIOLOGICAL E.WIRONMENTAL MONITORING B-19 j'

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-APPENDIX B MCGUIRE NUCLEAR STATION i

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SITE. SPECIFIC INFORMATION I

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Bl.0 MCGUIRE NUCLEAR STATION RADWASTE SYSTEMS B l.1 LIQUID RADWASTE PROCESSING Th-liquid radwaste system at McGuire Nuclear Station (MNS) is used to collect ana treat fluid chemical and radiochemical by-products of unit operation.

The system produces effluents which can be reused-in the plant or discharged in small, dilute quantities to the environment.

The means of treatment vary with waste type and desired product in the various systems:

A)

Filtration - Waste sources are filtered during processing.

In aome r

cases, such as the Floor Drain Tank (FDT) Subsystem of the Liquid Waste (WL) System, filtration may be the only treatment required.

~B)

Adsorption - Adsorption of halides and organic chemicals by activated charcoal (Carbon Filter) may be used in treating waste in the Laundry and Hot Shower Tank (LHST).. The carbon filter is designed to remove organ-ophospnates and free chlorine.

Activated charcoal need not be used when these chemicals are not present (e.g., phosphate detergents are not used-at the-station).

Ion exenange resin or other media may be used in the carbon filter vessel as desired.

C)

Ion Exchange - Ion exchange is used to remove radioactive cations from solution, as in the case of either LHST _or FDT waste in the WL System after--removal of organics by carbon filtration (adsorption).

Ion exchange is also used in removing both cations (cobalt, manganese) and anions-(chloride, fluoride) from evaporator distillates in order to purify the distillates for reuse as makeup water. Distillate from the Waste Evaporator _in the WL System and the Boron Recycle Evaporator in the Boron Recycle-System (N9) can be_ treated by this method, as well as FDT, LHST waste, and reactor bleed.

D)

Gas Stripping - Removal of gaseous _ radioactive fission products is accomplished in both the WL Evaporator and the NB Evaporator.

4 E)

Distillation - Production of pure watet from the waste by boiling it 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.

F)

Concentration - In both the WL and NB Evaporators, dissolved chemicals are concentrated in the lower shell as water is boiled away.

In the case of the -WL Evaporator,- the volume of water containing waste chemicals and radioactive cations is reduced so that the waste may be more easily and cheaply solidified and shipped for burial.

In the NB Evaporator, the dilute boron is normally concentrated to 4% so that it may.be reused for-makeup to the reactor coolant system.

Figure Bl.0-1 is a schematic representation of the 11guld radwaste system at McGuire.

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m TABLE Bl.0-1 ABBREVIATIONS Systems:

CM - Condensate cooling i

1 KC - Component Cooling

.NB - Boron Recycle NC - Reactor Coolant

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WC - Conventional Waste Water Treatment WG - Waste Gas WL - Liquid Waste WM - Liquid Waste Monitor and Disposal Terms:

BA - Boric Acid Tank RC - Condenser Cooling Water CDT - Chemical Drain Tank ECST - Evaporator Concentrates Storage Tank FDT - Floor Drain Tank FWST - Fueling Water Storage Tank (formerly Refueling Water Storage O

Tank)

LHST.- Laundry.and Hot Shower Tank MST - Mixing and Settling Tank NCDT - Reactor Coolant Drain Tank RBT -Resin Batching Tank RIIT - Recycle Holdup Tank RHT - Recycle Monitor Tank RMWST - Reactor Makeup Water Storage Tank SRST - Spent Resin Storage Tank VUCDT - Ventilation Unit Condensate Drain Tank

-WDT - Waste Drain Tank WEFT - Waste Evaporator Feed Tank WMT - Waste Monitor Tank-1 TABLE.D1.0 1 O

l Revision 14 1/1/87

Bl.2 GASEOUS RADVASTE SYSTEt!S The gaseous waste disposal system for McGuire is designed with the capability of processing the fission-product gases from contaminated reactor coolt._

fluids resulting from operation.

The design base for the system shown schema-tically in Fig. Bl.0-2 is the retention, through the plant lifetime, of all the gaseous fission products to be discharged from the reactor coolant system to the chemical and volume control system and other plant systems to eliminate the need for intentional discharge of radioactive gases from the waste gas holdup tanks.

Actual system operation is aimed at maximizing storage time for decay prior to infrequent releases.

l'navoidable sources of Ic'w-level radio-active gaseous discharge to the environment will be from periodic purging operations of the containment, from the auxiliary building ventilation system, and through the secondary system air ejector.

With respect to the former, the potential contamination is expected to arise from non-recyciable reactor coolant leakage.

With respect to the air ejector, the potential source of contamination will be f rom leakage of the reactor coolant to the secondary system through defects in steam generator tubes.

The gaseous wt ;n disposal system includes two waste gas compressors, two catalytic hydrogen recombiners, six gas decay storage tanks for usc during normal power generation, and two gas decay storage tanks for use during shutdown and startup operations.

Bl.2.1 Gas Collection System The gas collection system combines the waste hydrogen and fission gases from the volume control tanks, the boron recycle and liquid waste gas stripper evaporators, and other sources produced during normal operation or the gas collected during the shutdown degasification (high percentage of nitrogen) and cycles it through the catalyt.ic recombiners to convert the hydrogen to water.

After the water vapor is removed, the resulting gas stream is transferred from the recombiner into the gas decay tanks, where the accun.ulated activity may be contained in six approximately equal parts.

From the decay tanks, the gas flows back to the compressor suction to complete the loop circuit.

Bl.2.2 Containment and Auxiliary Building Ventilation Nonrecyclable reactor coolant leakage occurring either inside the containment or inside the auxiliary building will generate gaseous activity.

Gases resulting from leakage inside the containment will be contained until t he containment is purged.

The containment atmosphere will be circulated through a charcoal adsorber and a particulate filter prior to release to the atmosphere.

Gases resulting f rom leakage inside the auxiliary building are released, with-out further decay, to the atmosphere via the auxiliary building ventilation system. The ventilation exhaust from potentially contaminated areas in the auxiliary building is passed through charcoal adsorbers to reduce releases to i

the atmosphere upon a radiation monitor alarm.

l B-?

Rovision 7

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B1,0.3 Secondary Systems The gases removed from the secondary system by the air ejectors are discharged

to the unit vent.

If the secondary system contains activity,- the. steam generator blowdown may be n2ther discharged directly to the RC system or through domineralizers to reduce activity levels.

L Gland leak-off steam, Nhich represents a minor source of activity, ts routed to the gland condenser.

The non-condensable gases are passed throrgh a vent stack to the-roof the condensables are condensed and drained to the condensate.starage tank.

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Figure 81,0-2 's a scNmatic representation of the gaseous radwaste system at i

-McGuire.

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PAGE 3 OF 3 r#89121D a

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B2.0 EEIZASE RATE' cal,CULATION Generic-release rate calculations are presented in Section: 1.0; these calcu-f lations will be used to calculate release rates for ticGuire Nuclear Station.

1 I

l B 2.1 -

LIQUID RELEASE RATE CALCULATIONS

.There are three potential release points at ticCult e.

Two of t1ese release points, the waste liquid effluent line and the containment ventilation unit condensate effluent line, discharge into the condenser cooling water system;

.i

--the third release point, the Turbine Building sump, can either be discharged into the condenser cooling water system or into the conventional waste water-4

. treatment system.

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B2.1.1 Fasic_}iquid Ef fluenth li For releases made via the waste 11guld effluent line, the following cal-culation shalI be-performed to determine discharge flow, in-gpm:

n f 5 F + (o E-p'l - -

)

i=1 MPC g where:

f = the undiluted effluent flow, in gpm.

F = the dilution flow available depending on the number (1-8) of condenser cooling water (RC) pumps in service, in gam.

4 p

where:

.F = (2.50E+05 gpm/ pump)(Number of RC pumps in service) h a = The recirculation factor at equilibrium (dimensionless), 2.4 R

a = l' +

=1+

= 2.4 l

U ll where:

Q

= average dilution flow (3720 cfs)

R Q-

= average flow past Cowans Ford Dam (2670 cis) g C

= the= concentration of radionuclide, "3",

in undiluted effluent as g

determined by laboratory analyses, in pCi/ml.

MPC -= the concentration of radionuclide, "i"4 "f rom 10CFR20, Appendix B, j-Table 11, Column 2.

If-radionuclide, 1

is a dissolved noble gas, the MPC = 2,00E-04 pCI/ml, i

k B-4 Revision 16

'/1/87

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B2.1.2 Centainment Ventilation Unit Condensate Effluent Line The containment ventilation unit condensate effluent line normally contains measurable activity above background and administrative controls have been

)

implemented.to assure that. release limits are not exceeded; see section on radiation monitoring alarm / trip setpoints.

1B2.1.3 Conventional Waste Water Treatment System Effluent Ling The conventional waste wa'ter treatment system effluent is normally considered nonradioactive; 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 and by periodit.

analyses of the composite sample collected on that line.

Radiation monitor'.ag alarm / trip setpoints assure that release limits are not exceeded; see section on radiation monitoring alarm / trip setpoints.

B2.1.4 Turbing Buildine Sumo Discharce Ling Normally the discharge from the Turbine Building sump is considered non-radioactive; that is, it is unlikely the effluent will contain measurable activity above background, and will flow into the conventional waste water treatment system.

It is assumed that no activity is present in the effluent until indicated by radiation monitoring measurements. If measurable activity is present in the effluent, sump discharge will be terminated and an alarm activated.

At this time the discharge may be routed to the floor drain tank for processing or routed -directly to the condenser cooling water (RC) flow;

- i rather than the conventional waste water treatment system; administrative controls shall be implemented to assure that release limits are not exceeded; see section on radiation monitoring alarm /setpoints.

B2.2 GASEOUS-RELEASE RATE CALCULATIONS The unit. vent is the release point for waste gas decay tanks, containment building purges, the condenser air ejector, and auxiliary building ventilation. The condenser air ejector effluent is normally considered nonradioactive; that is, it is unlikely the effluent will contain measurable

/

activity above background.

It is assumed that no activity is present in the L

condenser air ejector effluent until indicated by radiation monitoring measurements and by analyses of pariodic samples collected on that line.

Radiation monitoring alarm / trip setpoints in conjunction with administ rative controls assure that release limits are not exceeded; see section B3.0 on radiation monitoring setooints.

The following calculations, when solved for flowrate, are the release rates for noble gases and for radiciodines, particulates and other radionuclides with half-lives greater than 8 days; the most conservative of release rates calculated in B2.2.1 and B2.2.2 shall limit the release rate for a single release point.

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I (Kg ((X/Q)Q ]

< 500 mrem /yr, and p

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a where the terms are defined below.

B2.2.2 Radiciodin g Particulates. and Q1hgn gWh)

< 1500 mrem /yr I P t

where:

l K

= The. total body dose factor due to gamma emissions for each identified g-noble gas radionuclide, in mrem /yr per pC1/m' from Table 1.2-1.

L

= The skin dose factor due to beta emissions for each identified noble i

. gas radicauclide, in mrom/yr por pCi/m' from Table 1.2-1.

M

= The air dose f actor due to gamma emissjons for each identified noble y

gas radionuclido, in mrad /yr per pCi/m from Table 1.2-1 (unit conver-T sion constant of 1.1 mrem / mrad converts-air dose to skin dose).

4 P

= The dose parameter for radionuclides other then noble gases for the I

inhalation pathway, jnmrem/yr 01/m' and for the food and ground plane pathways, in m *(mrem /yr)per.per pC1/sec from Table 1.2-2.

The i

dose factors are based on the critical individual organ and'most restrictive age group (child or infant).

0

= The release rate of radionuclideo, i, in gaseous affluent from all i

release points at'the site, in pCi/sec.

8 X/Q- = 7.2"-5 sec/m.

The highest calculated annual average relative concentration (dispersion parameter) for any area at or beyond the miles.

The-location is the NNE sector @ 0.5 unrestricted area boundary.

W

= The annual 'verage dispersion or deposition parameter for estimating

the dose to an individual 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 operationa1 source term data, land use surveys, and NUREG-0133 guidance:

W ='2.9E-6 sec/m', for the' inhalation pathway. The-location is-the SE sector @ 1.0 miles.

L B-6 Revision 31 1/1/91

W = 7.6E-9 meter'r, for the food and gound plane pathways, The location is the SE sector t? 1.0 miles.

Q

= kC f + k = 4. 72E+20. f 1

i i

where:

C i = the concentration of radionuclide, i, in undiluted gaseous effluent, in pCi/ml.

f

= the undiluted effluent flaw, in efm k

= conversion factor, 2,83E4 ml/ft' k

= conversion factor, 6El sec/ min O

O B-7 Revision 31

!/1/91

_ _ _ _. _ _ _ _. _... ~. _

B3.0-RADIATION MONITOR SETPOINTS' Using the generic calculations presented.in Section-2.0, final offluent radi-ation monitoring setpoints are_ calculated for monitoring as required by the

-Technical Specifications.-

All' radiation monitors for McGuire are of f-line except EMF-50 (Vasto Gas System),which is-in-line.

These monitors alarm on Jow flow; the minimum flow alarm level for both the liquid monitors and the gas monitors is based on the-

- manuf acturer's recommendations.. These monitors measure the activity in the 1

liquid-or gas volume exposed to_the-detector and are independent of flow rate if a minimum flow rate is assured.

Radiation monitoring setpoints calculated in the following sections are expressed in activity concentrations; in reality the monitor readout is in counts per minute.

Station radiation monitor.setpoint procedures which cor-relate concentration and counts per minute shall be based on the following

-relationship:

c=

r 2.22 x 10e V where:

c = the gross activity, in pCi/ml r = the count-rate, in cpm 2.22 x 10 = the disintegration per minute per pCi e =-the counting efficiency, cpm /dpm V-= the volume of f.'uld exposed to the detector, in ml.

B3.1-LlQUID RADIATION MONITORS B3.1.1 Waste Liquid Effluent Line As described in Section B2.1.1 on release rate calculations for the waste liquid effluent, the. release is controlled by limiting the -flow l rate of effluent from the station.

Although the release rate is flow rato controlled, the radiation monitor setpoint shall_be set to terminate _the release if the eifluent-activity should exceed that determined by laboratory analysis and that used to calculate the release rate.

When releases are not.being made, a radiation monitor setpoint shall be calculated to assure that release limits are not exceeded.

A typical setpoint_in calculated as follows:

0" og

= 1.04E-4 pC1/mi wherer c = the gross activity in undiluted effluent,_in pC1/ml f ='the flow f rom the tank may vary from 0-120 gpm but, for this calcu-5 lation, is assumed to be 100 gpm.

B-8 Revision 14 1/1/87

l MPC = 110E-07/pCi/ml.;the MPC for an unidentified mixture o = 2.4 (See Section 32.1.1)

F = the dilution-flow is based on having only one condenser cooling water pump in service or-2.5E+5 gpm.

Should the number of pumps in service increase, the setpoint may be recalculated.'

B3.1.2-Containment Ventilat ion Unit Condensate Effluent Line As described in Section B2.1.2 on release rate calculations.for -the containment ventilation unit condensate effluent, it is probable that the

- effluent will contain measurable activity above background.

Since-the tank i

contents can be discharged automatically, a maximum tank concentratien, which 4

. also is the radiation monitor setpoint, is calculated to assure that release limits are not exceeded.

A typical monitor setpoint and maximum tank

=-z concentration is calculated as follows:

c5 MPC x F = 1.04E-4 pCi/ml where:

c'

= the gross activity in undiluted effluent, in pC1/ml f

= the flow from the tank may vary from 0-120 gpm but, for this calculation, is assumed to be 100 gpm MPC = 1.0E-07 pCi/ml, the MPC for an unidentified mixture a

= 2.4 (See Section B2.1.1)

F-

= the dilution flow is-based on having only one condenser cooling pump in service or 2.5E+5 gpm.

Should-the number of pumps in service increase, the setpoint may be recalculated.

The above calculation will determine the maximum setpoint for this release point; ' releases and/or setpoints may be administratively controlled to assure that release limits are_not exceeded since more than one release source may be t

released to the condenser cooling water.

B3.1.3~

Conventional Vaste Water Treatment Svetem Discharce Line I '

As described in Section B2.1.3 on release rate calculations for the conven-tional. waste water treatment system effluent, the effluent is normally con-sidered non-radioactive; that i s,~ it is unlikely the effluent will contain measurable activit/ above-background.. It is assumed that no activity is

' present in the effluent until indicated by radiation monitoring and by routine l i

.4ma ys s of the-composite semple collected-on-that line.

Since the-system

- discharges-automatically,_the maximum system concentration, which also'is the radiation monitor setpoint, is calculated so that release limits are not exceeded. A tfpical. monitor setpoint and maximum effluent concentration is calculated as-follows:

l l

l B-9 Revision 14 1/1/87

. - - ~

~ _. - - _ _

I l

MC F

[

c5

= 5.36E-07 pC1/mi-

\\.

where

-c

= the-gross activity in undiluted eifluent, in pCi/mi f: = the flow rate of undiluted effluent which may vary from 0-6700 gpm,- but is assumed to be 6700 gpm-l MPC = 1',0E-07 pCi/ml, the MPC for an unidentified mixture F-

=_the flow past Cowan's Ford Dam may vary from 80 to 50,000 cfs, but I

is conservatively estimated at 80 cfs (3.59E404 gpm), the minimum flow available o

= 1 [The Conventional Vaste Water System discharge line is located downstream of Cowan's Ford Dam and, therefore, has no reconcentra-tion (recirculation) factor associated with it.]

B3.1.4 Turbine Buildine Sumn Discharce Line to the Condenser Cooline Water ( RC)

As described in Section B2.1.4 on release rato calculations for the Turbine

-Building sump effluent,.it is possible that the offluent will contain measur-able activity above background.

Since the sump contents can be discharged

= automatically to the RC, a maximum sump concentration, which also is the-radiation monitor setpoint, is calculated to assure that release limits are not exceeded.

A typical monitor setpoint and maximum sump concentration is

-calculated as follows:

c5" a}

i

= 5.21E O6 pCi/ml where:

c

= the gross activity in undiluted effluent, in pC1/ml f

= the flow rate of undiluted effluent which may vary from 0-2000 gpm, but is assumed to be 2000 gpm 4

MPC = 1.0E-07 pCi/ml, the MPC for an unidentified mixture o

= 2.4 (See Section B2.1,1)

F-

= the dilution flow is based on having only one condenser cooling pump in service or-2,5E+5 gpm, should the number (1-8) of pumps in service increast, the setpoint may be recalculated.

The above calculation will determine the maximum setpoint for this release point; releases and/or setpoints may be administratively controlled to assure that release limits are not exceeded since more than one release source may be released to the' condenser cooling water.

B-10 Revision 17 1/1/88

4 B3.2 GAS MONITORS The~ following _ equation shall be-used to-calculate final effluent noble gas radiation monitor setpoints based on Xe-133:

K(57Q) hj < 500 (See section 82.2.1) ha 4.72E+2 O f-(See Section B2.2.2) g f

-C

< 5.00E+01/f g_

where:

Og = the gross activity In undiluted effluent, in pC1/ml f

= the flow from the tank or building and varies for various release s;urces. In cfm-1 K.

= from Table 1.2 1 for Xe-133, 2.94E+2 mrem /yr per pCi/m'

-X7Q = 7.2E-5 sec/m', as defined in Section B2.2,2.

B3.2'l.

Unit Vent As stated in Section B2.2, the unit vent is the release point for the waste gas systam, containment purge ventilation system, the containment air release and addition system, the. condenser air ejector, and auxiliary building ventilation.

Since all of thesn-releases are through the unit vent.-the radiation monitor on the unit vent may be used to assure that station release limits are not exceeded.

For release from the containment air release and addition system and the containment purge ventilation system, a typical radiation monitor setpoint may be calculated as follows:

C < 5.00E+01/f = 1.79E-03 pC1/ml where:

f = 28,000 cfm (containment purge)

For release from the containment air release and addition ~ system, the waste gas decay. tanks, the condenser air ejectors, and the-auxiliary building-ventilation system,-a typical radiation monitor setpoint may be calculated as follows:

C < 5.00E+01/f = 3.51E-04 pC1/ml where:

f = 142,500 cfm (auxiliary ventilation systems)

B-11 Revision 16-5/15/87

,~. _ _... -

I I

1 i

(

B3.2.242-Waste Management racility (EMF-52) l Ventilation exhaust f rom the Waste tianagement Facility is not released through

\\

the unit vent and la considered a separate release point. This. exhaust is

}

l normally considered non-radioactive; that is, it is possible but unlikely that 4

i the effluent will contain measurable activity above background.

Since the

[

_ exhaust is continuous, a maximum concentration of gases in the exhaust, which is also.the radiation monitor setpoint, is calculated to assure compliance i

with release limits.

A typical radiation monitor setpoint may be calculated g.

as follows:

i C < S.00E+01/f = 5.95E-03 I

where:

l~

f = 8400 cfm i

l B3.2,3 Wast e llandling Area (EMF-53)

[

Vent.ilation exhaust from the Waste llandling Area is not released through the l

unit vent and is considered a separate release point.

This exhaust is l

normally considered non-radioactive; that is, it is possible but unlikely that h

the effluent will contain measurable activity above background. Eince the j

exhaust is continuous,-a maximum concentration of gases in thu exhaust, which is also the radiation monitor setpoint, is calculated to assure compliance r

i with release limits. A typical radiation monitor setpoint may be calculated l

as follows:

C < 5.00E+01/f = 5.00E-04 I

+

where:

i l

f = 100,000 cfm a

B3,2.4 Unit 2 Staging Building (2 EMF-59)

^

Ventilation exhaust from the Unit 2 Staging Eullding is not released through the unit vent and is considered a separate release point.

This exhaust is

.normally considered non-radioactive; that is, it is possible but unlikely that the ef fluent will contain measurable activity above background.

Since the F

exhaust is continuous, a maximum concentration of gases in the exhaust, which is also the radiation monitor setpoint, is calculated to assure compliance with release limits.

A typical radiation monitor setpoint may_be calculated as follows:

l C < 5.00E+01/f = 7.35E-03 l

where:

f = 6800-cfm I

d t

l.

i L

i i

D-11a Revision 33 1/1/92 w-----..---.-

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

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04,0 DOSE CALG LATIONS B4.1 FREQUENCY OF CALCULbTIONS Dose-contributions to-the_ maximum individual shall be calculated at least every 31 days, quarterly,: semiar.aually and annually (or as required _ by technical specifications) using the methodology in the generic information sections or the LADTAP and GASPAR computer program:

Example input templates for McGuire LADTAP and GASPAR computer program calculations are provided in Figures B4.0-1 and B4.0-2.

One of these methods shall also be used for any 4

special reports.

Station long-term historical and dose projection calculations are periodically performed to determine the station's status with respect to meeting annual ALARA goals specified in the McGuire Nuclear Station Selected Licensing Commitment Manual.

Such calculations are used to verify that adequate margin remains during a report period to allow normal station and radwaste system i

operation,_ including anticipated operational occurrences, for the remairder of-the report period without exceeding applicable goals, Stat.on dose projections can be performed using generic methodology, LADTAP and/or GASPAR.

or simplified dose calculation methods presented in Section B4.3.

Dose calculations that are required for individual pre release calculations, and/or abnormal releases shall not be calculated using simplified dose calculation methods.

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 or the IADTAP and/or GASPAR computer codes.

l 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 or the LADTAp and GASPAR l

l computer programs.

t l

B4.2 DOSE MODELS FOR MAXIMUM EXPOSED INDIVIDUAL B4.2.1 Liould Effluents Generic methodology for calculating liquid pathway exposures to the maximum individual is presented in Section 3.1.1 McGuire site specific parameters to be used in the generic methodology are presented as follows:

Tables B4.0-3 through B4.0 6 A,g,

=

(f x c)/(F + f)

(0.027 default for projections)

' F,

=

4 Where:

McG11re average liquid radwaste flow, gpm (100 default for f

=

projections).

Recirculation factor at equilibrium, 2.4.

o

=

McGuire average dilution flow for period of interest, gpm (3,3E+03-F

=

def ault-for projections - based on 1985 - 1990 worst-case projections).

An input template for McGuire--LADTAP computer program calculations is provided in Figure B4.0-1.

The input template includes default dilution parameters.

Radionuclide release input (C1/ period) and optional non-default dilution flow (CFS) parameters are necessary to perform IADTAP calculations to determine offsite dose impact from specific releases during the period that dilution flow is averaged over, B-12 Revision 33 1/1/92

B4,2.2.

Gaseous Effluents B4.2.2.1 Noble' Gases 1

Gamma ~ Air and Beta Air Dose Generic methodology for calculating.nobin gas airborne pathway gamma air (D,)

and beta air (D,) doses is presented in Section 3.1.2.1.

McGuire site specific parameters to be used in the generic methodology are presented as follows:

j (X/Q)-=

7,2E-5 sec/ml The highest calculated annual average relative concentration for any area at or beyond the restricted area boundary.

Th7 location is the NNE sector 0 0.5 miles.

An input template for McGuire GASPAR computer program noble gas airborno pathway gamma air (D and beca air (D ) dose calculations is provided in

- Figure B4. 0-2. - Locati)on 1.

TheinputkemplateincludesthemaximumMcGuire site specific annual average relative concentration parameters.

Radionuclide release input (Ci/ period) and optional non-default relative concentration parameters are necessary to perform GASPAR calculations to determine offsite dose impact from specific releases.

B4,2.2.2 Radiciodines. Particulates, and Other Radionuclides with T 1/2 > 8 Days Generic methodology for calculating airborne pathway maximum organ (Dexposures to the maxim External exposure from deposited ground contamination and inhalation exposure pathways are considered to exist at all locations of fsite.

Food pathways (i.e.,

vegetable' meat and milk)'are analyzed only at locations where site surveys have. verified vegetable gardens, meat producing animals, or cow / goat milk producing animals exist, however, Therefore.the location of the maximum individual may vary depending on the mixture and leve s of radionuclides i

released during a period of time, Additionally, the aritical (or limiting) age group and organ will vary based on the location (i.e., combination of dose pathways contributing dose) and mixture / level of radionuclide releases during the release period.

Performing calculations separately for all potential maximum locations, age groups and organs assures that a maximum location is identified, and that a conservative estimate is obtained for maximum offsite dose impact to any organ or age group.

McGuire site specific meteorological dispersion (X/Q) and deposition-(D/Q) parameters and applicable terrestrial / food pathways for the potential maximum locations to be analyzed using generic methodology are

. presented in Table B4.0-7.

An input template for McGuire GASPAR computer program airborne pathway maximum organ (D dose calculations is provided in Figure B4.0-3, locations 1 - 5.

Radionucli)de release input (C1/ period) and optional non-default meteorological parameters and pathway applicability flags are necessary to perform GASPAR calculations to determine offsite dose impact from specific releases.

B-13 Revision 33 1/1/92

E O

-B4.3' SlHPLIFIED DOSE ESTIMATE B4,3.1-Liould Effluents.

For dose estimates, a simplified calculation based on the assumptions-presented in Section B4.2.1 and operational source term data is presentod '

'below.

Updated operational source term data shall be used to revise these calculations as necessary.

WB (F,)(T,) (CCs-134 + 0. H C-Cs-137)

=

where:-

i*l 7.49E+5 '= 1,14E+d5 (U /D

+U DF ) DFg (1.27) g where:

1.14E405 = 10pC1/pC1 x 10'ml/kg + 8760 hr/yr 4

U,-= 730 t/yr, adult water consumption D = 1. dilution factor from the near field area to the nearest possible

~

W potable water intake (llunterville Water Intake).

U,g = 21 kg/yr, adult fish consumption BF = 2.00E+03. Moaccumulation factor for Cesium GaW 3.1-D g

DF

= 1.21E-04'. adult total-body' ingestion dose factor for Cs-134 agt (Table 3.1-2)'

1.27 = factor derived from the assumption that 79% of adult whole body-dose is q

contributed by Cs-134 and Cs-137 via the fish and drinking water pathway or 100% 6 - 79%_= 1.27-m = number of releases where:

F, = fg F+f j

where:

f = liquid radwaste flow, in gpm h

- 0 = recirculation factor at equilibrium, 2.4 F = dilution flow. in gpm where:

Cs-134' Cs-137, and F, "T, = The' length'of time, in hours, over which C are averaged.

(The time period'during which all' releases (m) are made)

C

= the average concentration of Cs-134 in undiluted effluent, in C8-134 pC1/ml, during the-time period considered, C

= d e average concentration of Cs-137 in undtluted effluent, in Cs-137-pCi/mi, during the time period considered.

0.59 = Thr. ratio of the adult total body ingestion dose factors for Cs-134 and Cs-137 or 7.14E-05'+ 1.21E-04 = 0.59 B-14 Revision 33

~

1/1/92

...... _ ~

~

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

'i 6

B4e3.2-Gaseous Ef flu flig tieteorological data is provided in Tables B4.0-1 and B4.0-2, B4.3.2.1-Noble Gases For dose estimates, simplified dose calculations based on the assumptions in' B4.2.2.1 and operational source term data are presented belowi Updated opara-tional source-term data shall be used to revise these calculations as neces-sary.

These calculations further assume that the annual average dispersion parameter is used and that Xenon-133 contributes 62% of the gamma air dose and 81% of the beta air dose.

D = 8.06E-10 [Q)Xe-133 (1.61)

D = 2.40E-09 [Q]Xe-133 II' 3I 3

where:

R

= 7.2E-05 sec/m',-as defined in Section B2.2.2.

8.06E-10 = (3.17E-8)(353) (X/Q), derived from equation presented in y

Section 3.1.2.1.

&~oi-.38E-f

= (3,17E-08)-(1050) (X/Q), derived from equation presented in L

Section-3.1.2.1,

[Q)Xe-133 = the total Xenon-133 activity released in pCi 1.61 = f actor derived f rom the assumption that 62% of the ganana air dose is contributed by-Xc-133, 1.23 = factor derived from the assumption that 81% of the beta air dose is contributed by Xe-133, B4.3.-2.2

'Radiolodines, particulates, and Other Radionuclides with T 1/2 ) 8 days For dose estimates, simplified dose calculations based on the assumptions in B4.2.2.2 and operational source term data are presented below.

Updated opera-tional source term' data shall be used to revise these calculations as neces-scry.

These calculations further assume that the annual average dispersion /

deposition parameters are used and that 81% of the dose results from 11 ingested by the maximally exposed individual via the vegetable pathway at the controlling-location. The simplified dose estimate co the thyroid of a child

-is:

-D =-1.28E-4 W (Q)}l-3 (l.23) where:

3 W = 4.6E-6 = XTQ for food and ground plane pathsay, in sec/m from Table B4.0-1 for the controlling location (E sector at 1.0 miles).

(Q);g.3 = the total-ll-3 activity released in-pCi.

V 1.28E-4 =-(3.17E-08)(R - [X/Ql) with the nppropriato substitut.fons for-See child-vegetable pathway f actor, R'i [X/Q) for 11-3.

Section 3.1.2.2.

B-15 Revision 33 1/1/92 v

,.w-.

.m-,

r

-, -,,, - - ~ -

rey,-vr

.~..~.._._.._...._____..___...m_...._..g.._

. s.-

h 23 = f actor derived': f rom-the assumption that 81% of the total inhala-

-tion, food andJground plane pathway done to the maximally exposed-individual:.is-contributed _by li-3 via the vegetable garden pathway.

1

?

1

'k I

m B-16 Revision 31 1/1/91

i

'B4.4f FUEL CYCLE CALCULATIONS 1

. As discussed in Section 3. 3.5, more than-one nuclear power station site' may

_ contribute to the doses to-be considered in accordance with 40CTR190. Jnie fuel cycle dose assessments for McGuire Nuclear Station must-include gaseous dose: contributions ~from Catawba-Nuclear Station, which.is located-approximately thirty miles SSW of McGuire.

For this dose assessment, the total body and maximum-organ dose contributions to the-maximum exposed Individual from McGuire-liquid releases and the combined Catawba and McGui~re gaseous releases are estimated using the following calculations:

Dg3(T) = Dyg(1,) + Dg3(g,) + DWB(8 )

c.

Dng(T) = Dgg(1,) + Dgg(g,) + Dgg(g )

e where:

-DWB(T) = Total estimated fuel cycle whole body dose commitment resulting from the combined liquid and gaseous ef fluents of Catawba and McGuire.during the calendar-year of interest, in mrem.

DM0(T) = Total estimated fuel cycle maxmium organ dose commitment resulting f om the combined liquid and gaseous effluents of Catawba and McGuire during the calendar year of interest. In I

mrem.

A fuel cycle dose calculation worksheet is provided in Figure B4'.0 4.

B4.4.1 LIOUID EFFLUENTS Liquid-pathway dose' estimates are calculated using generic methodology or the

-LADTAP computer-program.

The values for DVB(lo) and-DM0(lo) 11guld pathway does contributions are calculated based on the methodology, values and assumptions presented in Section B4.2.1.

B4.4.2-CASEOUS EFFLUENTS-

' Total Body:

The methodology for calculating noble gas airborne pathway whole body exposures-to the maximum individual, DVB. is derived from Section 3.1.2.1

- generic methodology for gamma air and beta air dose calculations as follows:

1

= 3.17E-8 [ K ](XM)Qgj mrem /yr

.Dy g

ial are described ig Section 1.2.1. -The McGuire Generic methodology _ parameters K g site specific parameter X/Q value is L 2E-5 sec/m as described in Section B4.2.2.1 for McGuire gamma air and beta air dose calculations - Dose contributions by Catawba via the airborno pathway'to the-McGuire fuel cycle whole body dose are trivial and need not be calculated unicas a significant (beyond Tech Spec)-release takes place at Catawba during the period of Jnterest.

l B-17 Revision 33 1/1/92-

.m

4-j 1

!!aximum Organ Airborne pathway maximum organ dose estimates are calculated using generic j -:

methodology.or the GASPAR. computer-program.

The maximum organ dose is established by calculating doses to all organs for each potential maximum L

offsite location identified in Table B4.0-7.

A conservative estimate ( i.e.,

1 overestimate) of the fuel cycle maximum organ dose is obtained by 1) determininig the locations with the highest exposure releases for each organ -

l--

2)-adding the highest exposure-value-for the airborne release to the same i

. organ dose resulting from liquid releases, and 3) comparing valuts obtained when the liquid a.

irborne pathway components are added for all organs and age groups to determine the maximum (or limiting) organ and age group.

Dose 4

i contributions by Catawba via the airborne pathway to the McGuire fueld cycle l

maximum organ dose are trivial and need not be calculated unless a significant (beyond Tech Spec) release takes place at Catawba during t.he period ct interest.

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TABLE B4.0-3 (1 of 2)

LIQUID EFFLUENT DOSE - ADULT PARAMETERS MCGUIRE NUCLEAR STATION A MREM /HR PER UCl/ML m

N_UCLIDE BONE LIVE R_,.

T. BODY THYROID KIDNEY LUNG GI-LU_

H 3

0.00E + 00 8.96 E + 00 8.96F 4 00 8.96E + 00 8.96E + 00 8.96 E + 00 0.96E + 00 NA E4 5.48 E + 02 5.48 E + 02 5.48 E + 02 5.48 E + 02 5.48 E + 02 5.48 E + 02 5.48 E + 02 CR 51 0.00E + 00 0.00E + 00 1.49E + 00 8.94 E - 01 3.29E-01 1.98E + 00 3.76 E + 02 MN 54 0.00E + 00 4.76E + 03 9.085 + 02 0.00 $ + 00 1.42E + 03 0.00E + 00 1.46E + 04

~

MN 56 0.00E + 00 1.20E + 02 2.12 E + 01 0.00 E + 00 1.52E + 02 0.00E + 00 3.82 E + 03 FE 55 _

8.87 E + 02 6.13 E + 02 1.43E + 02 0.00E + 00 0.00E + 00 3.42E + u2 3.52E + 02 FE 59 1.40E + 03 3.29E + 03 1.26E + 03 0.00E + 00 0.00E + 00 9.19E + 02 1.10E + 04 CO 58 0.00E + 00 1.51 E + 02 3.39 E + 02 0.00E + 00 0.00E + 00 0.00E + 00 3.00E + 03 C1 60 0 00E + 00 4.34 E + 02 9.58 E + 02 0.00E + 00 0.00E + 00 0.00E + 00 8.16E + 03 FI 63 4.19 E + 04 2.91 E + 03 1.41 E + 03 0.00E + 00 0.00E + 00 0.00E + 00 6.07 E + 02 NI 65 1.70E + 02 2.21 E + 01 1.01 E + 01 0.00E + 00 0.00E + 00 0.00E + 00 5.61 E + 02 C,U 64 0.00E + 00 1.6'E + 01 7.93 E + 00 0.00E + 00 4.26E + 01 0.00E + 00 1.44 E + 03 O

ZN 65 2.36E + 04 7.50E + 04 3.39 E + 04 0.00E + 00 5.02E + 04 0.00E + 00 4.73E + 04 BR 83 0.00E + 00 0.00E + 00 4.30 E + 01 0.00E + 00 0.00E + 00 0.00E + 00 6.30E + 01 BR 85 0.00E + 00 0.00E + 00 2.33E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00

~RB 86 0.00$ + 00 ' 1.03E + 05 4.79F + 04 0.00E + 00 0.00E + 00 0.00E + 00 2.03 E + 04

~

RB 88 0.00E + 00 2.95 E + O2 1.56 E + O2 0.00E + 00 0.00E + 00 0.00E + 00 4.07E - 09 RB 89 0.00E + 00 1.95 E + 02 1.37E + 02 0.00E + 00 0.00E + 00 0.00E + 00 1.13 E-11

'R 89 4.78 E + 04 0.00E + 00 1.37E + 03 0.00E + 00 0.00E + 00 0.00E + 00 7.66 E + 03 S

SR 90 5.95 E + 05 0.00E + 00 1.60E + 05 0.00E + 00 0.00E + 00 0.00E + 00 3.40E + 04 SR 91 8.79E + 02 0.00E + 00 3.55E + 01 0.00E + 00 0.00E + 00 0.00E + 00 4.19E + 03 SR 92 3.33E + O2 0.00E + 00 1.44 E + 01 0.00E + 00 0.00E + 00 0.00E + 00 6.60E + 03 Y

90 1.38E + 00 0.00E + 00 3.69E - 02 0.00E + 00 0.00 E '+ 00 0.00 E + 00 1.46E + 04 Y

91 M 1.30E- 02 0.00E + 00 5.04 E-04 0.00E + 00 0.00E + 00 0.00E + 00 3.82 E- 02 Y

91 2.02E + 01 0.00E + 00 5.39E -01 0.00E + 00 0.00E + 00 0.00E + 00 1.11 E + 04 Y

92 1.21 E -01 0.00E + 00 3.53 E -03 0.00E + 00 0.00E + 00 0.00E + 00 2.12E 4 03 Y

93 3.83 E- 01 0.00E + 00 1.06E- 02 0.00E + 00 0.00E + 00 0.00E + 00 1.22E + 04 ZR 95 2.77 E + 00 0.88 E -01 6.01 E -01 0.00E + 00 1.39E + 00 0.00E + 00 2.82 E + 03 ZR 97 1.53E-01 3.09E-02 1.41 E-02 0.00E + 00 4.67E - 02 0.00E + 00 9.57E + 03 NB 95 4.47 E + 02 2.49 E + 02 1.34 E + 02 _ __0.00E + 00 2.46E + 02 0.00E + 00 1.51 E + 06_

MO 99 0.00E + 00 4.62E + 02 8.79E + 01 0.00E + 00 1.05 E + 03 0.00E + 00 1.07 E + 03 TC 99 M 2.94 E - 02 8.32E - 02 1.06E + 00 0.00E + 00 1.26E + 00 4.07 E- 02 4.92 E + 01 TC 101 3.03E - 02 4.36E- 02 4.20 E- 01 0.00E + 00 7.85 E -01 2.23 E - 02 1.31 E - 13 O

Rev.33 1 92

l n

v TABLE B4.0-3 (2 of 2) 1.10U1D EFFLUENT DOSE - ADULT PARAMETERS MCGUIRE NUCLEAR STATION A MREM /HR PER UCl/ML m

NUCLlDE ISONE UVER T. DODY THYROID KIDNEY LUNG Gl-LU RU 103 1.98E + 01 0.00E + 00 8.54 E + 00 0.00E + 00 7.57 E + 01 0.00E + 00 2.31 E + 03 AU 105 1.65E + 00 0.00E + 00 0.52E- 01 0.00E + 00 2.13 E + 01 0.00E + 00 1.01 E + 03 RU 106 2.95 E + 02 0.00E + 00 3.73E + 01 0.00E + 00 5.69E + 02 0.00E + 00 1.91 E + 04 AG 110 M 1.42E + 01 1.31 E + 01 7.8'0E + 00 0.00E + 00 2.58 E + 01 0.00E + 00 5.36E + 03 TE 125 2.79E + 03 1.01 E + 03 3.74 E + 02 8.39E + 02 1.13E + 04 0.00E + 00 1.11 E + 04 TE 127 M 7.05 E + 03 2.52E + 03 8.59 E + 02 1.80E + 03 2.86E + 04 0.00E + 00 2.36 E + 04 fE 127 1.14 E + 02 4.11 E + 01 2.48 E + 01 8.48 E + 01 4.66E + 02 0.00E + 00 9.03 E + 03 TE 129 M 1.20E + 04 4.47 E + 03 1.89E + 03 4.11 E + 03 5.00E + 04 0.00E + 00 6.03E + 04 TE 129 3.27E + 01 1.23E + 01 7.96E + 00 2.51 E + 01 1.37E + 02 0.00E + 00 _ 2.47 E + 01 TE - 131 M 1.80E + 03 8.81 E + 02 7.34E + 02 1.39E + 03 8.92E + 03 0.00E + 00 8.74 E + 04 TE 131 2.05 E + 0' 8.57E + 00 6.47E + 00 1.69E + 01 8.98E + 01 0.00E + 00 2.90E + 00 TE 132 2.62E + 03 1.70E + 03 1.59E + 03 1.87 E + 03 1.63E + 04 0.00E + 00 8.02E + 04 1

120 9.01 E + 01 2.36E + 02 1.05E + 02 2.25E + 04 4.15E + 02 0.00E t 00 2.29 E + 0:

1 131 4.96E + 02 7.09E + 02 4.00 E + 02 2.32E + 05 1.22E + 03 0.00E + 00 1.87E + 0c 1

132 2.42E + 01 6.47E + 01 2.26E + 01 2.26E + 03 1.03E + 02 0.00E + 00 1.22E + 01 1

133 1.69 E + 02 2.94 E + 02 8.97E + 01 4.32E + 04 5.13E 4 02___0.00E + 00 2.64 E + 02 1

135 5.28 E + 01 1.38E + 02 5.10E + 01 9.11 E + 03 2.22E + 02 0.00E + 00 1.56E + 02 CS 134 3.03 E + 05 7.21 E + 05 5.89E + 05 0.00E + 00 2.33E + 05 7.75E + 04 1.26E + 04 CS 136 3.17E + 04 1.25E + 05 9.01 E + G4 0.00E + 00 6.97 E + 04 4.55 E + 03 1.42 E + 04 CS 137 3.88 E + 05 5.31 E + 05 3.48E + 05 0.00E + 00 1.80E + 05 5.99E + 04 1.03E + 04 CS 138 2.69 E + 02 5.31 E + 02 2.63 E + 02 0.00E + 00 3.90E + 02 3.85 E + 01 2.27E - 03 LA 142 1.83E - 02 0.33E -03 2.07E- 03 0.00E + 00 0.00E + 00 0.00E + 00 6.08E + 01 CE 141 0.01 E - 01 5.42E-01 0.15E-02 0.00E + 00 2.52E - 01 0.00E + 00 2.07 E + 03 CE 143 1.41 E -01 1.04 E + 02 1.16E- 02 0.0_0E + 00 4.60E - 02 0.00E + 00 3.00E + 03 CE 144 4.18 E + 01 1.75E + 01 2.24 E + 00 0.00E + 00 1.04 E + 01 0.00E + 00 1.41 E + 04 PR 143 1.32E + 00 5.28E -01 6.52 E-02 0.00E + 00 3.05 E -01 0.00E + 00 5.77 E + 03 PR 144 4.31 E - 03 1.79E -03 2.19E-04 0.00E + 00 1.01 E-03 0.00E + 00 6.19E-10 ND 147 9.00E -01 1.04 E + 00 6.22 E -- 02 0.00E + 00 638h-01 0.00E + 00 4.99E + 03 W

187 3.04 E + 02 2.55E + 02 8.90E + 01 0.00E + 00 0.00E + 00 0.00E + 00 0.34 E + 04 NP 239 1.28 E- 01 1.25E- 02 6.91 E -03 0.00E + 00 3.91 E -02 0.00E + 00 2.57E + 03_

Rev.33 1 92

TABLE B4.0-4 (1 of 2; LIQUID EFFLUENT DOSE - TEEN PARAMETERS MCGUIRE NUCLEAR STATION A MREM /HR PER UCl/ML m

NUCLQE BONE LIVER T. B_ODY THYROID KIDNEY LUNG GI-LLl__

H 3

0.00E + 00 6.34 E + 00 6.34 E + 00 6.34 E + 00 6.34 E + 00 6.34 E + 00 6.34 E + 00 NA 24 5.53 E + 02 5.53 E + 02 5.53E + 02 5.53E + 02 5.53 E + 02 5.53E + 02 5.53 E + 02 CR 51 0.00E + 00 0.00E + 00 1.52E + 00 8.46E - 01 3.34 E -01 2.17 E + 00 2.56 E + 02 MN 54 0.00E + 00 4.65E + 03 9.22E + 02 0.00E + 00 1.39E + 03 0.00E + 00 9.53E + 03 MN 56 0.00E + 00 1.24 E + 02 2.21 E + 01 0.00E + 00 1.58E + 02 0.00E + 00 8.19E + 03 FE 3B 9.09E + 02 6.45E + 02 1.50E + 02 0.00E + 00 0.00E + 00 4.09 E + 02 2.79 E + 02 FE 59 1.41 E + 03 3.30E + 03 1.27 E + 03 0.00E + 00 0.00E + 00 1.04 E + 03 7.79E 4 03 CO 58 0.00E + 00 1.45E + 02 3.35 E + 02 0.00E + 00 0.00E + 00 0.00E + 00 2.00E + 03 CO 60 0.00E + 00 A'20E + 02 9.45E + 02 0.00E + 00 0.00E + 00 0.00E + 00 5.47E + 03 Ni 63 4.26E + 04 3.01 $ + 03 1.44 E + 03 0.00E + 00 0.00E + 00 0.00E + 00 4.79 E + 02 NI 65 1.80E + 02 2.30E + 01 1.05E + 01 0.00E + 00 0.00E + 00 0.00E + 00 1.25E + 03 CU 64 0.00E + 00 1.72E + 01 8.08 E + 00 0.00E + 00 4.35 E + 01 0.00E + 00 1.33E + 03 tO ZN 65 2.13E + 04 7.41 E + 04 3.46E + 04 0.00E + 00 4.74 E + 04 0.00E + 00 3.14 E + 04 DR 83 0.00E + 00 0.00E + 00 4.73E + 01 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 8R 85 0.00E + 00 0.00E + 00 2.51 E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00__

f1B 86 0.00E + 00 1.10E + 05 5.19 E + 04 0.00e + 00 0.00E + 00 0.00E + 00 1.63s + 04 RB 88 0.00E + 00 3.16E + 02 1.68 E + 02 0.00E + 00 0.00E + 00 0.00E + 00 2.71 E- 05 RB 89 0.00E + 00 2.04 E + 02 1.44 E + 02 0.00E + 00 0.00E + 00 0.00E + 00 3.12 E - 07 SR 89 4.97 E + 04 0.00E + 00 1.42 E + 03 0.00E + 00 0.00E + 00 0.00E + 00 5.91 E + 03 SR 90 5.06E + 05 0.00E + 00 1.35 E + 05 0.00E + 00 0.00E + 00 0.00E + 00 2.63E + 04 SR 91 9.11 E + O2 0.00E + 00 3.62 E + 01 0.00E + 00 0.00E + 00 0.00E + 00 4.13E + 03,

~

SR 92 3.44 E + 02 0.00E + 00 147E + 01 0.00E + 00 0.00E + 00 0.00E + 00 8.77 E + 03 Y

90 1.42E + 00 0.00E + 00 3.83 E-02 0.00 E + 00 0.00E + 00 0.00E + 00 1.17E + 04 Y

91 1.34 E - 02 0.00E + 00 5.11 E-04 0.00E + 00 0.00E + 00 0.00E + 00 6.32 E -01 Y

91 M 2.09 E + 01 0.00E + 00 5.59 E-01 0.00E + 00 0.00E + 00 0.00E + 00 8.55 E + 03 Y

92 1.26 E-01 0.00E + 00 3.63E-03 0.00E + 00 0.00E + 00 0.00E + 00 3.44 E + 03 Y

93 3.97E -01 0.00E + 00 1.09E-02 0.00E + 00 0.00E + 00 0.00E + 00 1.21 E + 04 ZR

-95 2.64 E + 00 8.34E- 01 5.74 E - 01 0.00E + 00 1.23E + 00 0.00E + 00 1.92E + 03 ZR 97 1.52E -01 3.01 E - 02 1.39E-02 0.00E + 00 4.56E-02 0.00E + 00 8.15E + 02 NB 95 4.50E + 02 2.50E + 02 1.37E + 02 0.00E + 00 2.42E + 02 0.00E + 00 1.07E + 06 MO_ 99 0.00E + 00 4.61 E + 02 8.78 E + 01 0.00E + 00 1.05 E + 03 0.00E + 00_ _ _8.25E + 02 TC 99 M 2.84 E - 02 7.92E -02 1.03E + 00 0.00E + 00 1.18E + 00 4.39 E - 02 5.20E + 01 TC 101 3.08 E - 02 4.38 E - 02 4.30E - 01 0.00E + 00 7.92E - 01 2.67 E - 02 7.48 E -09 O

Rev.33 1-1-92

TABLE D4.0-4 (2 of 2)

LIQUID EFFLUENT DOSE - TEEN PARAMETERS MCGUIRE NUCLEAR STATION A MREM /HR PER UCl/ML m

NUCLIDE DONE LIVER T. BODY THYROID KIDNEY LUNG Gl-LLI RU 103 1.95 E + 01 0.00E + 00 0.33 E + 00 0.00E + 00 6.87E + 01 0.00E + 00 1.63E + 03 RU 105 1.67E + 00 0.00E + 00 6.46E -01 0.00E + 00 2.10E + 01 0.00E + 00 1.34 E + 03

_RU 106 2.99 E + 02 0.00E + 00 3.77E + 01 0.00E + 00 5.77E + 02 0.00E + 00 1.44 E + 04 AG 110 M 1.20 E + 01 1.21 E + 01 7.36 E + 00 0.00E + 00 2.31 E + 01 0.00E + 00 3.40E + 03 TE 125 M 3.02E + 03 1.09E + 03 4.03 E + 02 8.43E + 02 0.00E + 00 0.00E + 00 B.90E + 03 TE 127 M 7.62E + 03 2.70E + 03 9.06E + O2 1.81 E + 03 3.09E + 04 0.00E + 00 1.90E + 04 IE 127 1.24 E + 02 4.41 E + 01 2.68E + 01 8.59 E + 01 5.04 E + 02 0.00E + 00 9.61 E + 03 TE 129 M 1.28E + N 4.77 E + 03 2.03E + 03 4.14E + 03 5.37E + 04 0.00E + 00 4.82E + 04 TE _129 3.53E + 01 1.32E + 01 8.59 E + 00 2.52E + 01 1.4BE + 02. 0.00E + 00 1.93E + 02 TE 131 M 1.92E + 03 9.22E + 02 7.69E + 02 1.39 E + 03 9.61 E + 03 0.00E + 00 7.40E + 04 TE 131 2.20E + 01 9.06E + 00 6.87E + 00 1.69E + 01 9.61 E + 01 0.00E + 00 1.80E + 00 TE 132 2.75E + 03 1.74E + 03 _1.64 E + 03 1.84 E + 03 1.67E + 04 0.00E + 00 5.51 E.+ 04_

g l

130 8.81 E + 01 2.55E + 02 1.02E + 02 2.08E 4 04 3.92E + 02 0.00E + 00 1.96E + 02 1

131 5.00E + 02 7.00E + 02 3.76E + 02 2.04 E + 05 1.21 E + 03 0.00E + 00 1.39E + 02 1

132 2.39E + 01 6.24 E_+ 01 2.24 E + 01 2.10E + 03 9.83E + 01 0.00E + 00 2.72 E + 01 1

133 1.72 E + 02 2.02E + 02 8.89E + 01 4.07 E + 04 5.11 E + 02 0.00E + 00 2.21 E + 02 1

135 5.22E + 01 1.34 E + 02 4.98E + 01 8.64 E + 03 2.12E + 02 0.00E + 00 1.49 E + 02 CS 134 3.10E 4 05 7.30E + 05 3.39 E + 05 0.00E + 00 2.32 E + 05 8.86E + 04 9.08 E + 03 6S 136 3.18 E + 04 1.25E + 05 8.41 E + 04 0,00E + 00 6.82E + 04 1.07E + 04 1.0Td + 04 CS 137 4.15E + 05 5.52E + 05 1.92E F05 0.00E + 00 1.88 E + 05 7.30E + 04 7.86E + 03 CS 138 2.88 E + 02 5.52 E + 02 2.76E + 02 0.00E + 00 4.0BE + 02 4.74 E + 01 2.51 E- 01 BA 139 9.10E + 00 6.40E-03 2.6S E- 01 0.00E + 00 6.03E- 03 4.41 E - 03 8.11 E + 01 BA 140 1.86E + 03 2.28 E + 00 1.20E + 02 0.00E + 00 7.72 E -01 1.53 E + 00 2.87E + 03 BA 141 4.39 E + 00 3.28E - 03 1.47E-01 0.00E + 00 3.04 E - 03 2.24 E -03 9.36E - 06 BA 142 1.96 E + 00 1.9GE-03 1.20E -01 0.00E + 00 1.66E- 03 1.30E - 03 6.01 E-12 LA 140 3.61 E- 01 1.77E - 01 4.72E -02 0.00E + 00 0.00E + 00 0.00E + 00 1.02E + 04 LA 142 1.86E- 02 8.25E- 03 2.05E - 03 0.00E + 00 0.00E + 00 0.00E + 00 2.51 E + 02__

6$ 141 7.98E- 01 5.32E - 01 6.12 E-02 0.00E + 00 2.51 8 - 01 0.00E + 00 1.52E + 03 CE 143 1.41 E- 01 1.03E + 02 1.15E -02 0.00E + 00 4.60E -02 0.00E + 00 3.08E + 03 CE 144 4.17E + 01 1.73 E + 01 2.24 E + 00 0.00E + 00 1.03 E + 01 0.00E + 00 1.05E + 04 PR 143 1.36 E + 00 5.43 E - 01 6.76E - 02 0.00E + 00 3.15 E - 01 0.00E + 00 4.47E + 03 PR 144 4.46E - 03 1.83 E - 03 2.26E - 04 0.00E + 00 1.05 E - 03 0.00E + 00 4.92 E- 06 ND 147 9.73 E-01 1.06E + 00 6.34 E -02 0.00E + 00 6.21 E-01 0.00E + 00 3.82E + 03 W

187 3.28E + O2 2.67 E + 02 9.37 E + 01 0.00E + 00 0.00E + 00 0.00E + 00 7.24 E + 04 NP 239 1.34 E - 01 1.27 E- 02 7.04 E -03 0.00E + 00 3.98E - 02 0.00E + 00 2.04 E + 03_

O Rev.33 1 92 i

~

[

h TABLE B4.0-5 (1 of 2)

LIQUID EFFLUENT DOSE.- CHILD PAfWAETERS MCGUIRE NUCLEAR STATION A MREM /HR PER UCl/ML m

NUCLlDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H

3 0.00 E + 00 1.19E + 01 1.19E + 01 1.19 E + 01 1.19E + ' t 1.19 E + 01 1.19E + 01 NA 24 7.93 E + 02 7.93 E + 02 7.93 E + 02 7.93E + 02 7.93E + 02 7.93 E + 02 7.93 E + 02 CR 51 0.00E + 00 0.00E + 00 1.92 E + 00 1.06E 4 00 2.91 E - 01 1.94E + 00 1.02E + 02 MN 54 0.00E + 00 3.99 E + 03 1.06E + 03 0.00E + 00 1.12 E + 03 0.00E + 00 3.35E + 03 MN 56 0.00E + 00 1.25 E + 02 2.81 E + 01 0.00E + 00 1.51 E + 02 0.0CE + 00 1.80E + 04 FE 55 1.57E + 03 8.34 E + 02 2.59 E + 02 0.00 E + 00 0.00E + 00 4.72E + 02 1.55E + 02 FE 59 2.26E + 03 3.65 E + 03 1.82 E + 03 0.00E + 00 0.00E + 03 1.06 E + 03 3.60E + 03 CO 58 0.00E + 00 1.75 E + 02 5.37E + 02 0.00E + 00 0.00E + 00 0.00E + 00 1.02E + 03 dO 60 0.00E + 00 5.16E + 02 1.52 E + 03 0.00E + 00 0.00E + 00 0.00E + 03 2.86E + 03 NI 63 7.36E + 04 3.94 E + 03 2.50E + 03 0.00E + 00 0.00E + 00 0.00E + 00 2.65E + 02 NI 65 3.04 E + O2 2.86 E + 01 1.67E + 01 0.00E + 00 0.00E + 00 0.00E 4 00 3.50E + 03 cx CU 64 0.00E + 00 2.39E + 01 1.44 E + 01 0.00E + 00 5.77 E + 01 0.00E + 00 1.12E + 03

)

ZN 65 2.23 E + 04 5.95E + 04 3.70E + 04 0.00E + 00 3.75 E + 04 0.00E + 00 1.05E + 04 BR 83 0.00E + 00 0.00 E + 00 6.64 E + 01 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 BR 85 0.00E + 00 0.00 E + 00 3.54 E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 RB 86 0.00 E + 00 1.09 E + 05 6.72 E + 04 0.00 E + 00 0.0CE + 00 0.00E + 00 7.03 E + 03 RB 80 0.00 E + 00 3.10E + 02 2.15E + 02 0.0054 00 0.00E + 00 0.00 E + 00 1.52E + 01 RB 89 0.00E + 00 1,91 E + O2 1.70E + O2 0.00E + 00 0.00E + 00 0.00E + 00 1.6 GE + 00 SR 89 1.00E + 05 0.00E + 00 3.00E + 03 0.00E + 00 0.00E + 00 0.00 E + 00 4.18E + 03 SR 90 9.24 E + 05 0.00E + 00 2.48E + 05 0.00E + 00 0.00 E + 00 0.00E + 00 1.87E + 04 SR 91 1.96E + 03 0.00E + 00 7.41 E + 01 0.00E + 00 0.00ETCOTON + 00 4.33$ + 03 SR 92 7.38E + 02 0.00E + 00 2.96E + 01 0.00E + 00 0.00E + 00 0.00E + 00 1.40E + 04 Y

90 3.20 E + 00 0.00E + 00 8.56 E - 02 0.00E + 00 0.00E + 00 0.00E + 00 9.10 E + 03 Y

91 M 2.97 E - 02 0.00E + 00 1.00 E - 03 0.00E + 00 0.00E + 00 0.00E + 00 5.82E + 01 Y

91 4.68E + 01 0.00E + 00 1.25 E + 00 0.00E + 00 0.00E + 00 0.00E + 00 6.24E + 0L Y

92 2.80E -01 0.00E + 00 0.01 E-03 0.00E + 00 0.00E + 00 0.00E + 00 0.09E + 03%

Y 93 8.87E - 01 0.00E + 00 2.44 E - 02 0.00E + 00 0.00E + 00 0.00E 4 00 1.32 E + 04 ZR 95 7.05E + 00 1.55E + 00 1.38E + 00 0.00E + 00 2.22E + 00 0.00E + 00 1.62E + 03 ZR 97 4.25 E -01 6.13E - 02 3.62 E - 02 0.00E + 00 8.01 E - 02 0.00 E + 00 9.29 E + 03 fib 95 5.32E + 02 2.07E + 02 1.48 E + 02 0.00E + 00~ 1.95E + 02}.T00E + 00 3.835 0.00E + 00 7.26E + O2 MO 99 0.00E + 00 8.78E + O2 2.17E + O2 0.00E + 00 1.8Q + (j TC _, 99 M 6.46 E - 02 1.27 E - 01 2.10E + 00 0.00E + 00

1. 84F. + 7) 6 43E-02 7 20E + 01 V

Rev.33 1 92

O TABLE B4,0-5 (1 of 2)

LIQUID EFFLUENT DOSE - CHILD PARAMETERS MCGUlRE NUCLEAR STATION A MREM /HR PER UCl/ML m

N_UCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG Gl-LU L

TC 101 7.40 E -02 7.83 E -02 9.93E -01 s.00E + 00 1.34 E + 00 4.14 E- 02 2.493-0T RU 103 4.83E + 01 0.00E + 00 1.85E + 01 0.00E + 00 1.21 E + 02 0.00E + 00 1.25E + 03 RU 105 4.26E + 00 0.00E + 00 1.54 E + 00 0.00E + 00 3.74 E + 01 0.00E + 00 ? 78E +03 RU 106 7.72E + 02 0.00E + 00 9.64 E + 01 0.00E + 00 1.04 E + 03 0.00E + 00 1.20E + 04 AG 110 M 3.23E + 01 2.18 E + 01 1.74E + 01 0.00E + 00 4.06G + 01 0.00E + 00 2.60E + 03 TE 125 M 4 25E +03 1.15E + 03 5.67E + 02 1.19E + 03 0.00E + 00 0.00E + 00 4.10E + 03 TE 127 M 1.00 E + 04 2.00E + 03 1.28E + 03 2.58 E + 03 3.07E + 04 0.00E + 00 8.72E + 03 TE 127 1.76E + 02 4.73E + 01 3.77E + 01 1.22E + 02 5.00E + 02 0.00E + 00 6.86E + 03 TE 129 M 1.82E + 04 5.07E + 03 2.82E 4 03 5.85E + 03 5.33E + 04 0.00E + 00 2.21 E + 04 TE 129 5.00E + 01 1.39 E + 01 1.19E + 01 3.56E + 01 1.46sT02 0.00$ + 00 3.11 E + 03 TE - 131 M 2.68 E + 03 9.28 E + 02 9.88E + 02 1.91 E + 03 8.98E + 03 0.00E + 00 3.77E + 04 TE 131 3.09E + 01 9.43E + 00 9.21 E + 00 2.37 E + 01 9.36E + 01 0.00E + 00 1.63E + 02 O

TE 132 3.77E + 03 1.67 E + 03 2.01 E + 03 2.43 E + 03 1.55 E + 04 0.00E + 00 1.68E + 04 l

100 2.04E + 02-4.13E + 02 2.13E + 02 4.55E + 04 6.17 E + 02 0.00E + 00 1.93E + 02 1

131 1.20E + 03 1.21 E + 03 6.87E + 02 4.00E + 05 1.99E + 03 0.00E + 00 1.00E + 02 i

132 5.60E + 01 1.03E + 02 4.73 E + 01 4.77 E + 03 1.57 E + 02 0.00E + 00 1.21 E + 02 1

133 4.14 E + 02 5.12 E + 02 1.94 E + 02 9.51 E + 04 8.53E + 02 0.00E + 00 2.06 E + 02 l_

135 1.22E + 02 2.20E + 02 1,04 E + 02 1.95E + 04 3.38 E + 02 _ 0.00E + 00 1.68E + 02 CS 134 3.02E + 05 6.26 E + 05 1.32E + 05 0.00E + 00 1.94 E + 05 6.97E + 04 3.38E + 03 CS 136 3.83 E + 04 1.05E + 05 6.82E + 04 0.00E + 00 5.61 E + 04 8.37E + 03 3.70E + 03 CS 137 5.33E + 05 5.11 E + 05 7.54 E + 04 0.00E + 00 1.66 E + 05 5.99E + 04 3.20E + 03 CS 138 3.72E + 02 5.17 E + 02 3.20E + 02 0.00E + 00 3.64 E + 02 3.92E + 01 2.38E + 6f

~-

BA 139 2.S4 E + 01 1.35E -02 7.35E-01 0.00E + 00 1.18 E - 02 7.97 E-03 1.46E + 03

_BA 140 5.00E + 03 4.46 E + 00 2,97 E + 02 0.00E + 00 1.45E + 00 2.66 E + 00 2.58E + 03 BA 141 1.23 E + 01 6.86E- 03 3.99E-01 0.00E + 00 5.94 E -03 4.03 E -02 6.99 E + 00 BA 142 5.36E + 00 3.85E-03 2.99E-01 0.00E + 00 3.12E- 03 2.27E-03 6.99E-02 LA 140 7.86E - 01 2.75E-01 9.26E-02 0.00E + 00 0.00E + 00 0.00E + 00 7.66E + 03 LA 142 4.08E - 02 1.30E-02 4.07 E- 03 0.00E + 00 0.00E + 00 0.00E + 00 2.58E + 03 CE 141 2.34 E + 00 1.17E + 00 1.73E-01 0.00E + 00 5.11 E -01 0.00E + 00 1.46E + 03 CE 143 4.12E - 01 2.23 E + 02 3.24 E - 02 0.00E + 00 9.37 E -02 0.00E + 00 3.27E + 03 CE 144 1.23E + 02 3.84 E + 01 6.54 E + 00 0.00E + 00 2.13 E + 01 ' O.00E + 00 1.00E + 04 PR 143 3.06E + 00 9.18E - 01 ' 52E-01 0.00E + 00 4.97 E-01 0.00E + 00 3.30E + 03 PR 144 1.00E - 02 3.10E -03 5.05E- 04 0.00E + 00 1.64 E- 03 0.00E + 00 6.68E + 00 ND 147 2.17E + 00 1.76E + 00 1.36E - 01 0.00E + 00 9.65E- 01 0.00E + 00 2.79E + 03 W

187 4.30E + 02 2.55E + 02 1.14 E + 02 0.00E + 00 0.00E + 00 0.00E + 00 3.58E + 04 NP 239 3.47E -01 2.49E- 02 1.75E - 02 0.00E + 00 7.19E - 02 0.00E + 00 1.84 E + 03 f

's Rev.33 1 92

O TABLE B4.0-6 (I of 2)

LIQUID EFFLUENT DOSE - INFANT PARAMETERS i

MCOUIRE NUCLEAR STATION Am MREM /HR PER UCl/ML NUCUDE BONE UVER T. BODY.

THYROID KlDNEY LUNG 01-LU H

3 0.00E + 00 1.16E + 01 1.16 E + 01 1.16E + 01 1.16E + 01 - 1.16E + 01 1.16E + 01 i

NA 24 3.80E + 02 3.80E + 02 3.80E + 02 3.80E + 02 3.80E + 02 3.80E + 02 3.80E + 02 CR 51 0.00E + 00 0.00E + 00 5.30E-01 3.46E- 01 7.56E-02 6.73E-01 1.55E + 01 MN 54 0.00E + 00 7.49E + 02 1.70E + 02 0.00E + 00 1.66 E + 02 - 0.00E + 00 2.75E + 02 MN 56 0.00E + 00 3.08 E + 01 5.30E + 00 0.00E + 00 2.64 E + 01 0.00E + 00 2.80E + 03 FE

$5 5.23 E + 02 3 38E +02 9.03 E + 01 0.00E + 00 0.00E + 00 _1.65E + 02 ' 4.29E + 01 i

FE 59 1,16E + 03 2.02E + 03 7.98E + 02 0.00E + 00 0.00E + 00 5.98E + 02._ 9.67E + 02 CO 58 0.00E+00 1.35E+02 3.38E + 02 000E + 00 0.00E + 00 0.00E + 00 3.37E + 02 CO _60 0.00E + 00 4.06E + 02 9.59E + 02 0.0L E + 00 0.00E + 00 0.00E + 00 9.67E + 02 N1 63-

_ 2.39E + 04 1.47 E + 03 0.28 E + 02 0.00E + 00 0.00E + 00 0.00E + 00 7.34E + 01 NI 65-1.77E + 02 2.00E + 01 9,10E + 00 0,00E + 00 0.00E + 00 0.00E + 00 1.52E + 03 CU 64 0.00E + 00 2.29E + 01 - 1.06E + 01 0.00E + 00 3.87E + 01 _0.00E + 00 4.70E + 02_

j ZN. 65 6.92E + 02 2.37 E + 03 1.09E + 03 0.00E + 00 1.15E + 03 0.00E + 00 2.01 E + 03 BR 83-0.00E + 00 0.00E + 00 1.37E + 01 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 '

1 BR 85 0.00E + 00 0.00E + 00 7.30E-01 0.00E + 00 0.00E + 00 0.00E + 00 - 0.00E + 00 RB 86 0.00E + 00 6.40E + 03 3.16E + 01 0.00E + 00__0.00E + 00 0.00E + 00 1.64E + 02 RB 0.00E + 00 1'.87E + 01 1.03E + 01 0.00E + 00 0.00E + 00 0.00E+ 00 1.82E+01 RB 89 0.00E + 00 1.08E + 01 - 7.41 E + 00 0.00E + 00 _0.00E + 00 - 0.00E + 00 3.66E + 0_0 SR 89 9.44 E + 04 0.00E + 00 2.71 E + 03 0.00E + 00 0.00E + 00 0.00E + 00 1.94 E + 03 SR 90 4.70E + 05 0.00E + 00 1.27E + 05 0.00E + 00 0.00E + 00 0.00E +00 8.69E+03 SR 91 1.88 E + 03 0.00E + 00 6.8_1 E + 01 0.00E + 00 0.00E + 00 0.00E + 00 2.23 E + 03 SR 92 7.22E + 02 0.00E + 00 2.68 E + 01 0.00E + 00 0.00E + 00 - 0.00E + 00_ 7.79E + 03 Y

90 3.27E + 00 0.00E + 00 8.77E -02 0.00E + 00 0.00E + 00 0.00E + 00 4.51 E + 03 Y

91 M 3.05E-02 0.00E + 00 1.04E-03 0.00E + 00 0.00E + 00 0.00E + 00 - 1.02E + 02 Y

91 4.25E + 01 0.00E + 00 1.13E + 00 0.00E + 00 0.00E + 00 0.00E + 00 3.05E + 03 Y

92 2.88E -01 0.00E + 00 8.09E-03 0.00E +00 0.00E + 00 ~_0.00E + 00 5.49E + 03 -

Y 93 9.14 E- 01 0.00E + 00 2.49E-02 0.00E + 00 0.00E + 00 - 0.00E + 00 7.22E + 03 ZR 95 7.75E + 00 1.89E +00 - 1.34E + 00 0.00E + 00 2.04 E + 00 0.00E + 00 9.41 E + 02 ZR -- 97 5.57E-01 9.56E 4.36E-02 0.00E + 00._ 9.63E-02. 0.00E + 00 - 6.09E + 03 NB 95-1.58E + 00 6.51 E- 01 3.76E-01 0.00E + 00 4.66E -01 0.00E + 00 5.49E + 02 MO - 99 0.00E + 00 1.28 E + 03 2.49E + 02 0.00E + 00 1.91 E + 03 ~ 0.00E + 00 - 4.21 E + 02 TC 99 M 7.22E- 02 1.49E 1.92E + 00 0.00E + 00 1.60E+00 7.79E-02 4.33 E + 01 TC 101 8.54E-02 1.08E-01 1.06E +00 0.00E +00 1.28E + 00 5.87 E - 02,1.83 E + 01_

O Rev.33 1 92

O TABLE B4.0-6 (2 of 2)

LIQUID EFFLUENT DOSE - INFANT PARAMETERS MCGUIRE NUCLEAR STATION A MREM /HR PER UCl/ML m

NUCLIDE BONE UVER T. BODY THYROlO KIDNEY LUNG GI-LU RU 103 5.57E + 01 0.00E + 00 1.86E + 0i 0.00 E + 00 1.16 E + 02 0.00E + 00 6.77E + 02 RU 105 5.12E + 00 0.00E + 00 1.72 E + 00 0.00E + 00 3.76E + 01 0.00E + 00 2.04 E + 03 AU 106 9.07 E + 02 0.00E + 00 1.13E + 02 0.00E + 00 1.07E + 03 0.00E + 00 6.88E + 03 AG 110 M 3.75E + 01 2.73E + 01 1.01 E + 01 0.00E + 03 3.91 E + 01 0.00E + 00 1,42E + 03 TE 125 M 8.77 E + 02 2.93E + 02

1. i D E + 02 2.95E + 02 0.00E + 00 0.00E + 00 4.18E + 02 TE 127 M 2.20_Et03 7.30E + 02 2.66 E + 02 6.36E + 02 5.42E + 03 0.00E + 00 8.88 E + 02_

TE 127 3.76 E + 01 1.26 E + 01 8.09E + 00 3.06E + 01 9.18 E + 01 0.00E + 00 7.90E + 02 TE 129 M 3.76E + 03 1.29E + 03 5.79E + 02 1.44 E + 03 9.41 E + 03 0.00E + 00 2.25E + 03 TE 129 1.07 E + 01 3.6BE + 00 2.49E + 00 8.95E + 00 2.66 E + 01 0.00E + 00 8.54E + 02 TE 131 M 5.72 E + 02 2.30E + 02 1.90E + 02 4.66E + 02 1.5iiN + 03 0.WG + 00 3.87E + 03 TE 131 6.62E + 00 2.45 E + 00 1.86E + 00 5.91 E + 00 1.69E + 01 0.00E + 00 2.67 E + 02 TE 132 7.82 E + 02 3.87E + 02 3.62E + 02 5.72E + 02 _2.42E + 03 0.00E + 00 1.43E + 03 iO' i

130 2.26E + 02 4.97E + 02 1.99E + 02 5.57E + 04 5.45E + 02 0.00 E + 00 1.00E + 02 l

131 1.35E + 03 1.59 E + 03 7.00E + 02 5.23 E + 05 1.86E + 03 0.00E + 00 5.6BE + 01 1

132 6.24 E + 01 1.27E + 02 4.51 E + 01 5.94 E + 03 1.41 E + 02 0.00E + 00 1.03E + 02

~.01 E + 02 1.25E + 05 8.05E + 02 0.00E + 00 1.16 E + 02 1

133 4.70E + 02 6.85 E + 02 2

1 135 1.37E + 02 2.72E + 02 9.93E + 01 2.44 E + 04 3.04 E + 02 0.00E + 00 9.86E + 01 CS 134 1.42 E + 04 2.64 E + 04 2.67 E + 03 0.00E + 00 0.81 E + 03 2.79 E + 03 7.10 E + 01 CS 136 1.73 E + 03 5.0BE + 03 1.90E + 03 0.00E + 00 2.02E + 03 4.14 E + 02 7.71 E + 01 CS 137 1.sSE + 04 2.30E + 04 1.63E + 03 0.00E + 00 0.17E + 03 2.50E + 03 7.19E + 01 CS 138 1.81 E + 01 2.94 E + 01 1.43E + 01 0.00E + 00 1.47E + 01 2.29 E + 00 4.70E + 01 BA 139 3.31 E + 01 2.20E- 02 9.59E- 01 0.00E+00 1.32E-02 1.33E -02 2.10E + 03 BA 140 6.43E + 03 6.43E + 00 3.31 E + 02 0.00E + 00 1.53E + 00 3.95E + 00 1.58E + 03 BA 141 1.60E + 01 1.09E- 02 5.04 E- 01 0.00E + 00 6.58 E-03 6.66E-03 1.95E + 02_

BA 142 6.92E + 00 5.76 E- 03 3.41 E -01 0.00E + 00 3.31 E- 03

3. t BE - 03 2.86E + 01 lA 140 7.94 E - 01 3.13E-01 8.05E-02 0.00E + 00 0.00E + 00 0.00E + 00 3.68E + 03 LA 142 4.14 E -02 1.52E- 02 3.64 E - 03 0.00E + 00 0.00E + 00 0.00E + 00 2.58E + 03 CE 141 2.96E + 00 1.81 E + 00 2,13E - 01 0.00E + 00 5.57E-01 0.00E + 00 9.33E + 02 CE 143 5.57 E- 01 3.69E + 02 4.21 E - 02 0.00E + 00 1.08E-01 0.00E + 00 2.16E + 03 CE 144 1.12E + 02 4.59E + 01 6.20E + 00 0.00E + 00 1.85E + 01 0.00E &oO 6.43E + 03 PR 143 3.06E + 00 1.14 E + 00 1.52E -01 0.00E + 00 4.25E - 01 0.00E + 00 1.61 E + 03 PR 144 1.03 E- 02 3.99E - 03 5.19E- 04 0.00E + 00 1.44 E-03 0.00E + 00 1.85E + 02 ND 147 2.08 E + 00 2.14E + 00 1.31 E - 01 0.00E + 00 8.24E 01 0.00E + 00 1.35E + 03 W

187 3.40E + 01 2.36E + 01 8.16E + 00 0.00E + 00 0.00E + 00 0.00E + 00 1.39E + 03 J NP 239 4.18 E - 01 3.74 E-02 2.11 E-02 0.00E + 00 7.45E -02 0.00E + 00 1.08E + 03 O

Rev.33 1 92

Table b4.0-7 Meteorological Parameter and Applicable Pathways for Potential Worst case Offsito locations i

Ground Level Rolcasa Vorst-Laso locations *

(%76)

(II/I))

Applicable Food Pathways **

l (1) Inhalation, Ground Sita Boundary, NNE 7.2E-5 1.3E 7 (2) Garden, 0.75 mi, E 1.8E-5 3.0E 8 Veg, Heat, Milk (3) Meat Animal, 3.5 mi, SSW 3.0E-7 8.3E-10 Veg, Meat (4) Milk Animal, 2.8 mi, ESE 4.8E-7 7.8E-10 Veg, Milk (5) Combination, 2.8 mi, ESE 4.BE 7 7.8E-10 Veg, Meat.

Cow Milk Based on August 1991 Land Use Census Data (Sec Table B4.0-8)

The food pathways to be included for exposure contribution to the maximum individual at this location.

Inhalation and ground exposure pathways also considered at all locations, i

Table B4.0-7 (1 of 1)

O Revision 33 1/1/92

TABLE B4.0-8 PATINAY Ai PLICABILITT FVR ALL LOCATIONS BASED ON SITE SUiWEY MCGUIRE NUCLEAR STATION (1 of I)

Distance to the contrul location in miles SEL*TUR 0-0.5*

O.5-1.0 I.0-I.5 I.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5

3. 5 -4. 0. 0-4. 5 4. 5-5. O**

N X

X X

V V

VCMG NNE X

X X

V V

VCMG NE X

X X

X V

V V

VCMG ENE X

X X

X V

V V

VC VCM VCMG E

X V

V V

V VCG VCG VCG VCMG VCMG ESE X

V V

VC VC VC VC VCMG SE X

X X

X V

VM VM VCMG SSE X

X X

V V

VCM VCM VCM VCM VCMG

)

S x

X v

v v

VCMG SSV X

X X

X V

VM VM VCMG SW X

X X

X V

VCMG WSV X

X V

V V

VCMG X

X V

V V

V VM VM VM VCMG fW j WNV X

X X

V V

VCMG hV X

X X

V V

VCMG NNW X

X X

X V

V V

VCMG PATINAYS: I - None V

'vT. GETABLE M - MEAT G - GOAT MILX C - COW MII.K No pathways exist within the Site Boundary (Exclusion Area Boundary) it is conservative to assume that a Since there is no site survey data outside of 5 miles from the plant, Vegetable, Heat, Cow, and Goat pathway exists at every 5 mile location.

Eevision 33 1/I/92

- - - ~ -

fl0URE 64.0*1 MCoultt LADIAP I W 1 itMPLAft IOR l10U10 t.ADi(WUCtIDE titLAst 07f 811t Dost CAltVLA110kl een+e nunnenenennononee top op pagg nununenennenennnn ecolle

+++.1****2..++3++..+4.+.5**+*6"~n"*T" 000001 LADIAP IWPUT f or MCoultt ODCM Mt1NCD + Of f AULT DILUll0N 000002 0

3.3t+03 1.0 1

000003 1.0 000004 tl0Ul0 tittA51 SOURCE IIRNl

CVAlt$ Plt ttttAEL l'ttl00 000005 a3 0.00t+00 000006 u24 0.00t+00 000U07 talt 0.00t+00 000008 Mh54 0.00t+00 000009 MNS&

0.00t+00 000010 f155 0.00t+00 0D0011 7159 0.00t+00' 000012 C058 0.00t+00 000013 C060 0.00t+00 000014 kI63 0.00t+00 000015 Nf65 0.00t+00 000016 CU64 0.00t+00 000017 2k65 0.00t+00 000018 Ch69 0.00t+00 000019 RR83 0.00E+00 000020 8t15 0.00t+00 000021 ttS6 0.00t+00 000022 Rsta 0.00t+00 000023 tl89 0.00t+00 000024 st09 0.00t+00 000025 st90 0.00t*00 000026 sa91 0.00t+00 000027 st97 0.00t+00 j

000028 Y 90 0.00t+00 000029 i 91 N 0.00t+00 000030 f 91 0.00t+00 000031 Y 92 0.00t+00 000032 Y 93 0.00t+00 000033 It95 0.00t+00 000034 2t97 0.00E+00 000035 ht95 0.00t+00 000034 M099 0.00E+00 000037 1C99 M 0.00t+00 000038 1C101 0.N)(+00 000039 RU103 0.00t+00 000040 ay105 0.00t+00 000041 RU106 0.00t+00 000042 AG110M 0.00E+00 000043 ftitSM 0.00t+00 000044 ft12?M 0.00t+00 000045 18127 0.00E+00 000046 ft129M 0.00E+00 000047 ft129 0.00E+00 000048 ft131N 0.00E+00 000049 It131 0.00t+00 000050 it132 0.00t+00 000051 1 130-0.00E+00 000052 1 131 0.00t+00 000053 1 132 0.00t+00 000054 1 133 0.00E+00 000055 l 135 0.00t+00 000056 Cs134 0.00t+00 000057. Ct136 0.00t+00 000058 C$137 0.00t+00 000059 Cs138 0.00E+00 000060 SA139 0.00E*00 f

000061 BA140 0.00t+00

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l Rev. 33 1-1-92 L

l rigure %.0 4 - ruel Cycle Dose Calculation Worksheet for i

Potential Worst-Case Of fsite Locations I

g, i

j Ground Level Release Wernt-Case locations

i (TTq~)

(@)

Applicable rood Pathways **

(1) Inhalation, Ground Site Boundary NNE 7.2E 5 1.30-7 (2) Garden, 0.75 mi, E 1.8E-5 3.0E 8 Veg, Heat, tillk (3) Heat Animal, 3.5 mi, SSW 3.0E-7 8.3E-10 Yeg, Heat (4) Milk Animal, 2.8 mi, ESE 4.8E-7 7.8E-10 Veg, tillk (5) Combination, 2.8 mi, ESE 4.8E-7 7.8E-10 Veg, liest, Cow Milk Based en August 1991 !.and Use Census Data (See Table B4.0 8)

The food pathways to be included for exposure contribution to the maximum individual at this location.

Inhalation and ground-exposure pathways also considered at all locations.

j Figure B4.0 4 (1 of '0)

Revision 33 1/1/92

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.y Organ Doses j

i Adult Age Group

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I Revisior. 33 1/1/92 l

D5.O fiA1)10 LOGICAL ENVIR0!C11XIR2l111.CElliG The radiological environmental manitoring program sihall be conducted in accor-f dance with Selected Licensee Commitment Manual Section 16.11-13.

The monitoring program locations and analyses are given in Tables US.0-1 through B5.0-3 and figure B5.0-1 Sito specific characteristics rnake groundwater sampling unnecessary.

Groundwater recharge is from Lake Norman and local precipitation.

The groundwatnr gradient flews directly to the Catawba River; l

therefore, contamination of groundwater from liquid effluents is highly

{

irtp roba ble.

Additionally, two site boundary TLD locations in the N and N!N sectors do not exist since the required locations are over water.

However, special interest TLD's have been placed in these sectors on the discharge canal at 0.3 and 0.2 miles, respectively.

The laboratory performing the radiological environmental annlyses shall parti-cipate 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 participt. tion code is CP.

The dates of the land-use census that was used to identify the controlling receptor locations was 06/13/91 - 06/24/91.

The 1991 land use census also identified the following location where l

navironmental monitoring samples were required but were not available for i

collection.

DISTANCE DIRECTION SAMPII. TYPE REASON FOR NOT OBTAINING 2.6 miles East Goat Milk Not used for human consumption C,

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TABLE B5.0-2 (1 of 1)

MCGUIRE RADIOLOGICAL MONITORING FROGRAM SAMPLING LOCATIONS g

(OTHER SAMPLING IDCATj0NS) c a

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V i

125 Site Boundt rv i0.4 mi SV)

W M

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FV i

_129 Discharre ( inal Entrance to Lake Nor:sn f 0.6 =1 ENE )

SA SA I

_130 Hwv. 73 Pm tre Dcenstream (0.6 mi SV)

SA

_lll Cevans Fort Dam ( 0. 7 mi V)

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_133 Cornelius t6.2 mi NE)

W 134 East Eincelo Junior Efeh School iB.7 mi VNWl X

W M

135 Plant Marsi all Intake Cans 1 (12.0 ei N)

X EW

_136 Mooresv1111 Municinsi Vater Surriv f12.5 mi NNE)

X EV j'

_137 Pinnacle b :ess Area (12.0 mi N')

X SA SA i

_1 18 Henry Cg 1 Psirv f2.75 ei ESE) 53 i

_139 Villiam Coc k Dairr (2.6 mi E)

SM 140 Kidd Dairv-Cows ( 2.B mi SSE)

SM 141 Lynch Dsin -Ccvs (14.5 mi VNW)

X SM 142 Davidsen Mioicioni Vater Surnly ( 7. 5 mi NE )

PW 4-5 Mile R Jins ( 5.0 mi NNE )

M j

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154 5 Mile Esdj es - Gardens ( 2.5 =i ENE )

Mt a)

Snecial Interest (deleted 01/91/92)

Mial I

_185 5 Mile Radjus - Gardens (4.9 ci N)

_153 5 Mile Radias - Gardens (2.8 mi N)

Special Interest Misi I

(a) during i*arvest season i

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REVISION 33

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