ML20073L173

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Pc Dose Calculation Bases
ML20073L173
Person / Time
Site: Callaway Ameren icon.png
Issue date: 09/16/1994
From:
UNION ELECTRIC CO.
To:
Shared Package
ML20073L159 List:
References
EPCI-94-03, EPCI-94-03-R00, EPCI-94-3, EPCI-94-3-R, NUDOCS 9410120355
Download: ML20073L173 (21)
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Text

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CALLAWAY PLANT EPCI - 94 - 03 Rev. 0 1 EMERGENCY PREPAREDNESS

. ELECTMC oEPARTxEur CALCULATION COVER SHEET Page 1 of 21 Callaway Plant

SUBJECT:

PC Dose Calculation Bases PURPOSE AND SCOPE:

This bases documents the mathematical model used by PC Dose.

ASSUMPTIONS:

1. Only decay of short lived radiciodines based on default isotopic mixtures is considered in the '

calculations for holdup in Containment or Auxiliary buildings.

2. For Field Monitoring Team lodine Sampling and Analysis, alliodines are assumed to be based on measured or default isotopic mixes. Since lodine 131 has the highest conversion factor for Ci/cc to Rem /hr of all the radiciodines, decay of short lived radiciodines will be performed when using default isotopic mixtur'es.
3. Readings from Wide Range Gas Monitors (WRGM) are assumed to be from noble gases.
4. All releases are assumed to be ground level releases since all possible release points are effectively lower than two and one-half times the height of adjacent solid structures (ref. 4).

S. Building wake affect is not considered. This is a conservative assumption.

6. Effective Dose Equivalent (EDE) from extemal exposure to gamma emitting radiation, as referred to in ref. 2, is assumed to be equal to the Deep Dose Equivalent (DDE).
7. The Deep Dose Equivalent is assumed to be measurable by Field Monitoring Team survey instruments.
8. The contribution to TEDE by ground shine cannot be properly measured until the plume has past.

A calculated value for ground shine can be derived from plume shine measurements and air samples obtained in the field.

9. Plume meander is not considered for wind speeds less than 6 meters per second. This is a conservative assumption.

A , .

CHECKLIST

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Rev. O Page 2 of 21 ASSUMPTIONS (cont' d) :

10. The equations in this calculation assume a straight line Gaussian Model where the material being diffused is a stable gas or aerosol which remains suspended for long periods of time and where the materials exhibit normal distribution in both horizontal and vertical directions.
11. The source term (ref 6) used for a LOCA is primarily due to an unfiltered release from containment directly into the atmosphere. It does however, consider a portion of the release through the ECCS system to be filtered. it is conservative then, to use the default LOCA source term for all LOCA events even though a release may be through the Unit Vent, a filtered release path.

REFERENCES:

r

1. " Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix 1", USNRC Regulatory Guide 1.109, Revision 1, October,1977.
2. " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents",

1 EPA-400-R-92-001, October,1991.

3. " Unit Vent Wide Range Gas Monitor Correction Factors for LOCA and SGTR Accident Based on EP Dose Assessment Source Term *, Union Electric Licensing and Fuels Calculation ZZ-355, Rev,0, August,1994.
4. " Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants", USNRC Regulatory Guide 1.145, Revision 1, November,1982.
5. " Radiological Assessment, A Textbook on Environmental Dose Analysis", USNRC Nureg/CR-3332, September,1983.

6.- "EP Dose Assessment Source Term", Union Electric Calculation ZZ-341, Revision 0, June,1994.

7. "10 CFR" 201003, Organ Weighting Factor
8. " Radiological Health Handbook", USDHEW, January,1970.
9. SFR-GF-052A
10. SFR-GC-039A l l
11. RFR-00416A, 9-07-84
12. Purchase Specification No.10466-J-374A, Rev. 7, Appendix S, Steam Release Calculation and i

Table 3, Ventilation System Flows.

13. *PORV Monitors Conversion Factor and Response Based on a Realistic Steam Generator Tube Rupture Accident *, Union Electric Calculation ZZ-345, Rev. O. June,1994.

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14.
  • Turbine Driven Auxiliary Feedwater Pump Exhaust Monitor Conversion Factor and Response Based on a Realistic Steam Generator Tube Rupture Accident *, Union Electric Calculation ZZ-347, Rev.O, June,1994.

ATTACHMENTS: WRGM Detector Correction Factors 5 Values O Correctep AT Values for the Callaway Primary Met Tower Default Flownte far Ventilation Systems Default isotopic Mix for LOCA Default isotopic Mix for SGTR Filter Correction Factors Decay Data ANALYSIS:

1. BASIC CALCULATION The PC Dose Modelis a straight-line Gaussian Plume Diffusion Model that calculates the relative concentrations and resulting doses downwind from a radiological release Two doses are calculated by the Model. The two are:
1. Total Effective Dose Equivalent;
2. Committed Dose Equivalent to the thyroid.

The general equation calculates the doses D in Rem from a grourd level release at points of interest using the following relationship (eq. B-4, ref.1).

D = 0, . DcI; . 7 M - (eq.1) where i = Index of radionuclide.

Oj = Release rate of radionuclide i,in Ci/sec.

DCFj = Dose correction factor for radionuclide i(Table 5-1, ref. 2, for TEDE and Table 5-2, ref. 2, for CDE Thyroid), in Rem - cc/ Ci-hr.

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'T = Time of exposure,in hours.

- Atmospheric dispersion factor,in sec/m3 .

0 3

UCF = Unit Correction Factor 1.0E-6"L (ref. 8).

CC A. Atmosoheric Discersion Factor ( )

All possible points of release from the Callaway Plant are effectively lower than two and one-half times the height of adjacent solid structures and, since plume meander is not considered (assumption 9), the following equation is selected for the ground level centerline 5 values (eq.1, ref. 4):

0 O x 0

~

a

_Uyn(na ,a , + - )

(eq. 2) where x = 3.14159.

71 1 o

= Wind speed at 10 meters above plant grade,in m/sec.

cy = Lateral plume spread, in m, a function of atmospheric stability and distance (Fig.1, ref. 4).

oz

= Vertical plume spread, in m, a function of atmospheric stability and distance (Fig. 2, ref. 4).

A = Smallest vertical-plane cross-sectional area of the reactor building,in m 2. (Other structures or a directional consideration may be justified when appropriate.) The value

^ is assumed to be equal to 0 since this value will provide 2

the most conservative 5 O

f =

Atmospheric dispersion factor, in ].

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Page 5 of 21 E values for various stability classes and distances are provided in Attachment 2.

O B. Stability Chlss (A-G)

Seven classes of atmospheric stability have been developed that correlate atmospheric stability with change in temperature at various heights (Table 2.4, ref. 5) and with the standard deviation of wind direction (Table 2.5, ref. 3). Attachment 3 provides the temperature change with height (*C/100 m) and the corrected values applicable to the Callaway Plant fndeorological tower (90 meter primary tower). The following relation applies.

= To * (eq. 3)

Tc an where Tc

= Corrected temperature for various stability classes,in C.

To

= Temperature change for various stability classes per 100 meters, (Table 2.4, ref. 5), in C.

AH = Difference in height between the two temperature detectors located on the primary meteorological tower.

C. Release Rate Determination (Qj)

Two accident types have been analyzed (ref. 6) that have sufficient source terms that could result in protective action recommendations being made for the general public. They are:

1. Loss of Coolant Accident (LOCA);
2. Steam Generator Tube Rupture (SGTR).

For the LOCA, the only monitored release path is through the unit vent which is filtered.

O Unmonitored release paths include the Auxiliary Building or a di>ect release from Containment which are unfiltered. For a SGTR, three monitored release paths exist. One is through the Steam Generator Power Operated Relief Valves (PORVs) and the second is through the O Auxiliary Feed Pump Turbine Discharge. Both of these are unfiltered. The otheris through the Condenser Air Removal System and out the Unit Vent which is a filtered release.

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Etucinic 88 (continuation sheet) c-c-rz-g j7 Inimanate EPCI. 94 - 03 Reviewed by: /*V f/ /b Callawa Plant Initial /Date Rev. O Page 6 of 21 Unmonitored releasepaths could involve the Containment Building, the Steam Generator i Safeties, the Auxiliary Building, or the Turbine Building. Release pathways can be categorized into three main groups: l

1. Unit Vent;
2. S/G PORVs, AFTD;
3. Unmonitored Release Pathways. j When gross release rates (SG PORVs and AFTD) and Noble Gas re' ease rates (Unit Vent) can be obtained directly from either the plant computer or the Rt.b11 system, release rates for radionuclide i(Qj) can be obtained as follows:

l For Unit Vent WRGM:

( X ie ICF, e FCF' Q, -

O + MCF e (eq. 4)

D,sa, For PORV and AFTD Monitors:

X, e ICF, e FCF'

= (eq. 5)

Of Q * [ Xg

  • ICF, e FCF, where i = Index of radionuclide Of

= Release rate for radionuclide i, in Ci/sec MCF = Monitor Correction Factor for the Wide Range Gas Monitors, see Attachment 1 from ref. 3. The lowest correction value for the mid and high range monitor was used. This is conservative. The highest value measurable on the low range monitor would not provide sufficient projected dose to l warrant making protective action recommendations. For an accident involving a significant release, the low and mid range monitors would more than likely be isolated. For all l other monitors, this value is = 1. l O = Release rate obtained from release rate monitor, or calculated value (see eq 6).

Xj = Concentration of radionuclide i, in Ci/cc. This value can be  !

from a default isotopic spectrum (Attachments 5 and 6) in Ci, or i from a grab sample isotopic analysis.

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'Xyg j = Concentration of noble gas radionuclide iin Ci/cc. This value can be from a default isotopic spectrum (Attachments 5 and 6)  !

in Ci, or from a grab sample isotopic analysis. l ICFj = lodine Correction Factor for default spectrums. For  ;

radiciodines, this value can be derived from eq. 7. For all other radionuclides, this value is equal to one (1). l FCFj '= Filter Correction Factor. For noble gases, this value is 1. For j radiciodines, see Attachment 7.

Where a release rate is not available but a gross monitor concentration is, the release rate (Q) can be obtained as follows:

1 O FR = X (eq. 6) 1

=r where Q = Release rate O FR = Flowrate into the atmosphere, in cc/sec X = Concentration from effluent monitor, in Ci/cc

1) Elownple_ (FR)

The flowrate can be obtained from the following sources:  ;

a. Default flowrate based on design;
b. Measured flowrate;
c. Calculated flowrate based on system parameters.

I For releases during emergencies, default flowrates or calculated flowrates are used.

Default flowrates based on design and plant computer calculated flowrates based on  ;

system parameters are included in Attachment 4. Default flowrates and calculated l flowrates based on system parameters can be obtained from the Plant Computer l System (ref. 9,10,11,12).  !

l I

D. Lodjne_ Con.ention FactoLLLCfl i j n The lodine Correction Factor b used for calculations where default isotopic spectrums are l used. Since 1-132.1-133.1-13e(and 1-135 all have half lives shorter than 1-131, over a period l 1

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Initial /Date Rev. O Pago 8 of 21 of time (2-3. hours), the ratio of I-131 to these other iodines would increase. Since 1-131 would be at a higher ratio, the dose rate to gross iodine concentration would increase since 1-131 has the highest dose rate conversion factor of all the default iodines. To use the default spectrums without allowing for decay of short lived radiciodines would be nonconservative. Since the default isotopic mix is assumed to be at 100% power, a new mixture will have to be calculated to allow for decay based on the time after shutdown. This new spectrum can be obtained as follows:

ICFj

- A"' -

e*' (eg.7) 4, where

= Index of radiciodines i r ICFj = fodine Correction Factor, unitiess Anj

= New Activity of default spectrum for radiciodine i, in Ci Aoj = Original Activity of default spectrum for radiciodine i, in if = Decay constant for radiciodine i, in min-1 t = Time after shutdown, in minutes

11. FIELD MONITORING DATA DOSE CALCULATION Dose calculations can be performed using data from field monitoring teams. Doses can be calculated from:

. 1. Gamma dose rate survey instruments;

2. Gross lodine grab samples (Thyroid Dose only);
3. A combination of gamma dose rate survey readings and gross iodine grab samples.

The TEDE which is used to determine protective action recommendations is equal to the sum of the CEDE from inhalation, the DDE from emersion in a gamma emitting radioactive plume (plume shine), and the DDE from exposure to deposited radioactive materials on the ground (ground shine). The CEDE can be evaluated from field monitoring air sample results. The DDE from '

plume shine can be measured by field monitoring teams using direct reading survey instruments.

The DDE from ground shine cannot be immediately measured by field monitoring teams for two reasons. The dose rate from ground shine is directly related to a time integrated air concentration.

The dose rate due to ground shine will continually increase during the plume phase (allowing for

( decay and daughter products) and a decrease in plume concentration will not result in an File K191.0018 CA-#2764a 2/25/94 KDP-ZZ-00007

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Initial /Date Rev. O Page 9 of 21 instantaneous decrease in ground shine dose rates (unlike plume shine). Therefore, ground shine dose cannot be calculated from ground shine dose rates during the early phase of a release when there is significant background radiation from plume shine and the amount of deposited radioactive materials is relatively small. It is not until the plume has passed and an actual radiation survey of the ground can be completed that a measurable dose rate can be obtained. This is too late for PARS based on plume phase dose assessment. Additionally, the DDE contribution to the EPA Protective Action Guide TEDE limit from ground shine is based on a 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> exposure period. A

. relationship can be established between the air concentration measured by FMT air sample analysis, or from direct reading FMT survey instruments, and the resulting ground shine DDE based on a 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> exposure period. Dose Correction Factors (Table 5-5 and 5-3, ref. 2) can be used to calculate DDE from ground shine based on this relationship.

The results can be used to obtain:

1. TEDE f
2. Thyroid CDE A. DDRS3.ased Solely on Grqss_Lqdine Samofes Where only a centerline gross iodine air sample is obtained without a respective gamma dose rate measurement, an estimation of the Thyroid CDE can be obtained.
1. To obtain Thyroid CDE:

XI' e ICF, e FCF' CDEThy =

l G"'e DCFI, e - *T (eq. 8)

XI, o ICF, e FCF, where CDEThy = Committed Dose Equivalent (CDE) to the Thyroid, in Rem.

IConc = Gross iodine concentration from grab sample, in Ci/cc.

DCFj = Dose Conversion Factor for lj (Table 5-4, ref. 2), in l Rem - cc/ Ci - hr. i i

T = Time of exposure (release duration), in hours.

XIj = Concentration for radiciodine i, pCi/cc LOCA and J SGTR default spectrums. (Attachments 5 and 6) may be used if a representative mix from a grab sample is s

not available. If defaults are used, units are in Ci.

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'lCFj = lodine Correction Factor for default spectrums (see eq. 7).

FCFj = Filter Correction Factor. For noble gases, this value is 1. For radiciodines, see Attachment 7.

D. Doses Based On Gamma Dose Rate and Gross lodine Where both a gamma dose rate survey and a gross iodine sample are obtained for the plume centerline, the TEDE and Thyroid CDE may be obtained.

1. To obtain Thyroid CDE, use eq. 7.
2. To obtain TEDE, the following equation is used:

TEDE =

DDEPS + CDE Thy

  • WT+ DDEGS (64 9) tO V where TEDE = Total Effective Dose Equivalent from internal and external exposure, in Rem.

DDEps = Deep Dose Equivalent from external gamma exposure due to plume shine. This is the measured dose rate, in R/hr, times the exposure time (release duration), in hours.

CDEThy = Committed Dose Equivalent (CDE) to the thyroid, in Rem (from eq. 8)

WT = Organ Dose Weighting Factor (ref 7). For the thyroid, this value = .03.

DCFogg * <Y i e 2, e FG,

= ' (eq.10)

DDEGS DDEps e DCFogg = X,

  • ICF, o FCF, Ps, where i = Index of radionuclide. l DDEGS = Deep Dose Equivalent from external gamma radiation from deposited material, in Rem. I File Kl91.0018 CA-#2264a 2/25/94 KDP-ZZ-00007

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'DDEps = Deep Dose Equivalent from external gamma exposure due to plume shine, in Rem.

ocr = Deep Dose Equivalent Dose Conversion Factor for radionuclide idue to ground shine (Table 5-5, ref. 2), in Rem - cc/ Ci-hr.

ocr = Deep Dose Equivalent Dose Conversion Factor for radionuclide idue to plume shine (Table 5-3, ref. 2) in Rem - cc/ Ci-hr.

Xj = Concentration for radionuclide i, in Ci/cc. LOCA and SGTR r default spectrums (Attachments 5 and 6) may be used if grab sampie data are not available. If default spectrums are used, units are in Ci.

O iCFj = lodine Correction Factor for default spectrums. For

() radiciodines, this value can be derived using eq. 7. For all other radionuclides, this value is equal to one (1).

FCFj = Filter Correction Factor. For noble gases, this value is 1. For radiciodines, see Attachment 7.

C. Ogies_ Bases! Solefv on Gamma Dose Rate Measurement Where only a centerline dose rate reading from plume shine is obtained without a respective iodine grab sample, an estimation of the thyroid CDE and TEDE can be obtained.

1. To obtain Thyroid CDE:

[ DC, eX,eICF,eFC ,,

CDEThy = (eq.11)

DDEps

  • p' C,_ . x, . ,C,, . ,c,,

Ps, where i = Index of radionuclide.

CDEThy = Committed Dose Equivalent (CDE) to the thyroid, in Rem.

DDEps = Deep Dose Equivalent from plume shine,in Rem. This is j measured dose rate, in R/hr times the exposure rate, in hours.

'O O  :

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Page 12 of 21 ocr = Thyroid Dose Conversion Factor for radionuclide / due to plume Thy, inhalation (Table 5-4, ref. 2), in Rem - cc/ Ci-br.

ocr = Deep Dose Equivalent Dose Conversion Factor for radionuclide Me esi i due to plume shine (Table 5-3, ref. 2), in Rem - cc/ Ci-hr.

Xi = Concentration for radionuclide i, in Ci/cc. LOCA and SGTR default spectrums (Attachments and 6) may be used if grab sample data are not available, if default spectrums are used, units are in Ci.

ICF- = lodine Correction Factor for default spectrums. For radiciodines, this value can be derived using eq. 7. For all other radionuclides, this value is equal to one (1).

FCFj = Filter Correction Factor. For noble gases, this value is 1. For radiciodines, see Attachment 7.

2. To obtain TEDE:

[DCF TEDE

  • X,
  • ICF,

DDEpSe[DCF

  • X,
  • ICF,
  • FCF i PS, where i = Index of radionuc!ide.

TEDE = Total Effective Dose Equivalent, in Rem.

DDEps = Deep Dose Equivalent from plume shine, in Rem.

ocrrect = Total Effective Dose Equivalent Dose Conversion Factor for i

radienuclide i(Table 5-1, ref. 2), in Rem - cc/ Ci-hr.

ocF gc, - Deep Dose Equivalent Dose Conversion Factor for radionuclide  ;

es, l i due to plume shine (Table 5-3, ref. 2), in Rem - cc/ Ci-hr.

Xj = Concentration for radionuclide i, in Ci/cc. LOCA and SGTR l default spectrums (Attachments 5 and 6) may be used if grab ,

/7 sample data are not available. If default spectrums are used, Q units are in Ci. l l

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'ICFf = lodine Correction Factor for default spectrums. For radiciodines, this value can be derived using eq. 7. For all other radionuclides, this value is equal to one (1).

FCFj = Filter Correction Factor. For noble gases, this value is 1. For radiciodines, see Attachment 7.

D. Ecolecting Doses at Other Locations from FMT Data After plume centerline doses are determined at one location, an estimation of doses at other plume centerline locations can be obtained. The following relation applies:

X / Q" DxL

=

c1x . (eg.13)

X lOtx f

where

,q Dy L

= Unknown dose at plume centerline location X, in Rem.

b Dg t

= Measured or calculated dose at plume centerline location K, in Rem.

X/QLX = Atmos heric Dispersion Factor at plume centerline location X, in sec/m .

X/Ot g = Atmos heric Dispersion Factor at plume centerline location K,in sec/m .

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'Ifllf4f B

{

~ Accident Correction Type Factor LOCA 1.11

SGTR 1.30 4

l f

O t

N 4

, ., ,, , - , - , --,-.r.. - r - - - > vm, -

.--m.

ATTAgjNT 2 DISPERSION FACTOR > (SEC-M/SEC-M^3) [ '

EPCI-94-03 Rev. O Page 15 of 21 1

DISTANCE Stability 1 2 3 4 5 6 7 8 9 10 Class EAB Mile Miles Miles Miles Miles Miles Miles Miles Miles Miles A 2.OE-6 1.1 E-6 5.4 E-7 4.0E-7 3.2E-7 2.5E-7 2.1E-7 1.9 E-7 1.8 E-7 1.7E-7 1.6E-7 8 1.2 E-5 7.2 E-6 9.OE-7 5.0E-7 4.0E-7 3.2 E-7 _2.7 E-7 2.3 E-7 2.1 E-7 2.1 E-7 1.9 E-7 C 3.2E-5 2.1 E-5 5.9E-6 2.8E-6 1.8E-6 1.3 E-6 9.9 E-7 8.1 E-7 6.3 E-7 5.4 E-7 4.5 E-7 D 1.1 E-4 8.1E-5 2.3 E-5 1.2E-5 8.1 E-6 5.9E-6 4.4 E-6 3.7 E-6 3.3E-6 2.7 E-6 2.2E-6 E 2.1 E-4 1.4 E-4 4.OE-5 2.4 E-5 1.5 E-5 1.3 E-5 9.9E-6 8.6E-6 7. 2 E-6 6.8 E-6 5.4E-6 F 5.OE-4 3.4 E-4 1.1 E-4 5.9 E-5 4.OE-5 3.2 E-5 2.4 E-5 2.2 E-5 1.9 E-5 1.6E-5 1.4E-5 'i G 1.1 E-3 8.6 E-4 2.7 E-4 1.4 E-4 1.OE-4 8.1 E-5 6.3 E-5 5.4E-5 4.5 E-5 4.2E-5 3.7E >

Note: To obtain X/O, divide the above d' ispersion factors (Xu/Q) by the wind speed in M/S.

Y.1 d)

N

~

N

EPCI-94-03 Rev 0 Page 16 of 21 Oc (62/7//c/ty ATTACHMENT 3 CORRECTED DELTA T VALUES FOR THE CALLAWAY PLANT PRIMARY MET TOWER i

Stability NUREG/CR 3332 90m-10m 60m-10m Class ( C/100m) ( C/80m) ( C/50m)

A A T 5 -1.9 AT s -1.52 AT s -0.95 B - 1.9 < A T $ -1.7 - 1.52 < AT 5 -1.36 - 0.95 < AT $ -0.85 C - 1.7 < AT s -1.5 - 1.36 < AT 5 -1.20 - 0.85 < AT 5 -0.75 D - 1.5 < AT rs -0.5 - 1.20 < AT s -0.40 - 0.75 < AT 5 -0.25 E - 0.5 < AT 5 +1.5 - 0.40 < AT 5 +1.20 - 0.25 < AT s +0.75 O F +1.5 < AT 5 +4.0 +1.20 < AT s +3.20 +0.75 < AT s +2.00 L}

G +4.0 < A T +3.20 < AT +2.00 < AT 1

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C l File K191.0018 i

ATTACHMENT 4 DEFAULT FLOWRATES for VENTILATION SYSTEMS p.

EPCI 94-03 Rev,0

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Page 17 of 21

@ 9luin System Fan Flowrate Name Numbers (cfm)

Unit Vent Area 5 CGF03A & CGF038 16,500 Condenser Air Removal CGE01 A &CGE018 1,000 Access Control Exhaust CGK02A & CGK028 6,000 Fuel Bldg. Emerg. Exhaust CGG02A & CGG028 9,000 Aux / Fuel Bldg.

Normal Exhaust - Fast CGLO3A & CGLO38- Fast 32,000 Aux / Fuel Bldg.

Normal Exhaust Slow CGLO3A & CGLO38 Slow 12,000 Cont. SD Purge Exhaust CGT01 20,000 Cont, mini Purge Exhaust CGT02 4,000 lRW Vent l RW Bldg. Eff Flow lCGH018 & CGH01 A l 12,000 l 1

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ATTk 2NT 5 Default Isotopi for LOCA (/.

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EPCI 03 Rev. O Page 18 of 21 E PA-400 E PA-4 00 Table 5-1 Table 5-4 ACTIVITY TEDE DOSE RATE Thyroid DOSE RATE RELEASED FACTOR FACTOR ISOTOPE (Cil rem-cm3/uCi-Hr rem-cm3/uci-Hr Kr-83m 2.79E + 03 0.OOE + 00 Kr-8 5 2.62E + 04 1.30E + 00 Kr-85m 1.44E + 04 9.30E + 01, -

Kr-87 8.01 E + 03 5.10E+O2 Kr-88 2.52E + 04 1.30E + 03 Kr-89 5.72E + O2 1.20E + 03 1-131 2.37E + 03 5.30E + 04 1.30E + 06 Xe-131 m 1.67E + 04 4.SOE + 00 1-132 1.16E + O2 4.90E + 03 7.70E + 03 1-133 8.24 E + O2 1.50E + 04 2.20E + 05 Xe-133 1.65E + 06 2.OOE + 01 Xe- 133m 2.54E + 04 1.70E + 01 1-134 9.75E + 01 3.10E + 03 1.30E + 03 1-135 3.32E + O2 8.10E + 03 3.80E + 04 Xe-135 4.40E + 04 1.40E + O2 Xe- 135m 1.22E + 03 2.50E + O2 Xe-138 4.82E + 03 7.20E + O2 TOTALM G. 1.82E + 06

  • KR-83m is not included in the calculation for Unit Vent releases since the WRGM have a discriminator threshold level set at 60 kev.

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( b ATTAL. iENT 6 Defatilt

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Isotepins Jx for SGTR (/)

w EPCI 03 Rev. O Pa0e 19 of 21 EPA-400 EPA-400 Tab!e 5-1 Table 5-4 ACTIVITY TEDE DOSE RATE Thyroid DOSE RATE RELEASED FACTOR FACTOR ISOTOPE (CD rem cm3/uCi-Hr rem-cm3/uCi Hr Kr-83m 4.82 E + 00 O.OOE + 00 Kr-85 1.77E + 00 1.30E + 00 Kr-8 5m 2.38E + 01 9.30E + 01 Kr-87 1.39E + 01 5.10E + O2 Kr-88 4.45 E + 01 1.30E + 03 Ka-89 1.20E + 00 1.20E + 03 1-131 3.13E-01 5.30E + 04 1.30E + 06 Xe-131 m 4.19E + 00 4.90E + 00 1-132 1.07E-01 4.90E + 03 7.70E + 03 1-133 4.37 E-01 1.50E + 04 2.20E + 05 Xe-133 1.14E + 03 2.OOE + 01 Xe-133m 2.29E + 01 1.70E + 01 1-134 4.4 2 E-02 3.10E + 03 1.30E + 03 1-135 2.13 E-01 8.10E + 03 3.80E + 04 Xe-135 6.81 E + 01 1.40E + O2 Xe-135m 3.11 E + 00 2.502 + O2 Xe-137 2.15E + 00 1.10E + O2 Xe-138 1.05E + 01 7.20E + 02 TOTAL 1.34E + 03

  • KR-83m is not included in the calculation for Unit Vent releases since the WRGM have a discriminator threshold level set at 60 kev.

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I ATTACHMENT 7 ElLTER CORRECTION FACTORS EPCI-94-03 Rev 0 7g Page 20 of 21 (w- )

@ % l1y NG IODINE FCF FCF LOCA 1 1 SGTR Unit Vent 1 .01 (Filtered)

SGTR PORV/ Safeties 1 1 (Unfiltered) r I

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N,.J File Kl91.0018

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ATTACHMENT 8 DECAY DATA l EPCI-94-03 Rev 0 Page 21 of 21 f& v/u(W NUCLIDE HALF LIFE A (min-1) 1-131 8.04 d 5.99 E-5 l-132 2.29 h 5.04 E-3 1-133 20.80 h 5.55 E-4 1-134 52.6 m 1.32 E-2 1-135 6.6 'h 1.75 E-3 r

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~j File Kl91.0018 l

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