Text

Rev 5 to Crisis Mgt Plan Implementing Procedure EDA-2, Offsite Dose Projections for Catawba Nuclear Station
	ML20033G898
Person / Time
Site:	Catawba
Issue date:	03/30/1990
From:	Harris R; DUKE POWER CO.
To:	;
Shared Package
ML20033G899	List: ML20033G898; ML20033G905;
References
	EDA-2, NUDOCS 9004120361
	Download: ML20033G898 (30)
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DUKE POWER COMPANY l

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EMERGENCY DOSE ASSESSMENT MANUAL I

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FDR ADOCK 05000413 F DC F

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TABLE OF CONTENTS l

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EDA-1 Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 2) i EDA-2 Off-Site Dose Projections for Catawba Nuclear Station j

(Rev. 5)

EDA-3 Off-Site Dose Projections for McGuire Nuclear Station

)

(Rev. 4) j EDA-4 Off-Site Dose Projections for Oconee Nuclear Station I

(Rev. 3) i EDA-5 Mesorem, Jr. Atmospheric Dispersion and Dose Assessment Model Users Manual, Version 4A Catawba (Rev. 0)

EDA-6 Hesorem, Jr. Atmospheric Dispernion and Dose Assessment l

Model Users Manual, Version 4A McGuire (Rev. 0)

EDA-7 Mesorem, Jr. Atmospheric Dispersion and Dose Assessment l

l Model Users Manual, Version 4A Oconee (Rev. 0)

EDA-8 Environmental Monitoring for Emergency Conditions for Catawba Nuclear Station (Rev. 5) l EDA-9 Environmental Monitoring for Emergency Conditions for f

McGuire Nuclear Station (Rev. 5)

EDA-10 Environmental Monitoring for Emergency Conditions for l

Oconee Nuclear Station (Rev. 1) i i

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March 30, 1990 l

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O EMERGENCY DOSE ASSESSMENT MANUAL DISTRIBUTION LIST CONTROL NUMBER HOLDER 1

R. E. Harris 2

W. P.

Deal 3

open 4

open 5

Caryl Ingram 6

R.

E.

Sorber 7

Open 8

open 9

F. G.

Hudson

(}

10 J. W.

Foster 11 J. E. Cole 12 D. P. Sinpson 13 Oconee CMC (R.E.11arris) 14 R. N.

Keener 15 Charlotte CMC Managers Area 16 W.

B. McRee 17 NRC Document Control Desk (via Kay Crane) 18-19 HRC Regional Administrator (via Kay Crane) 20 NRC Resident Inspector-Catawba (via Kay Crane) 21 NRC Resident Inspector-McGuire (via Kay Crane)

()

22 NRC Resident Inspector-Oconee (via Kay Crane)

_.---._.___._..._._.--.___._....__._.._____..._.______..._..y_._.

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CRISIS MANAGEMENT PLAN IMPLEMENTING PROCEDURE l

I EDA - 2 i

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Of f-Site Dose Projections for i

Catawba Nuclear Station' l.

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O 7"dBy khek W30/7o Approve Date Rev 5'

O-March 30, 1990

[DA:2 age 1 of 11 Offsite Done Projections for O

Catawba Nuclear Station 1.0 FURPOSE To describe a n.ethod for projecting dose conmitment from a noble gas and/or iodine release, through the containnent, the unit vent and/or the steam relief valves, during an ttergency.

2.0 FlyERENCES 2.1 IIP /0/B/1000/10, Determination of Radiation Monitor Setpoints 2.2 IIP /0/14/1009/06, Alternative Method for Determining Dose Rate Within the Reactor Putiding 2.3 IIP /0/B/1009/14, lloalth Physics Actions Pollowing an Uncontrolled Release of Liquid Radioactive Material 2.4 llP/0/B/1009/17 Unit 1 Post Accident Containment Air Fanpling System 2.5 llP/0/B/1009/21 Abnormal Unit Vent Sampling 2.6 CNS Technical Specification 3.6.1.2 2.7 Of fsite Dose calculation Manual (ODCM) 2,8 Regulatory Guide 1.4, " Assumptions Used for Evaluating the l'otential Radiological consequences of a Loss of Coolant Accident for Pressurized Vater Reactors" 2.9 Regulatory Guide 1.109, " Calculations of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Corpliance with 10CPR Part 50, Appendix 1" 2.10 NuReg 0396, EPA $20/1-78 016 " Planning Basis.for the Development of State and Local Government Radiological Energency Response Plans in Support of Light Water Nuclear Power Plants" 2.11 NuReg 06$4, PEMA REP-1, Rev.1, " Criteria for Preparation and Evaluation of Radiological Energency Response Plans and Preparedness in Support of Nuclear Power Plants" 2.12 Letter f rom P. O. Iludson, September 30, 1985, re: Release Rate Infoimation for McGuire and Catawba Nuclear Station (Pile: CN 134.10) 2.13 Catawba Nuc1 car Station Class A Conputer Model Validation (Pile NUC+0306) 2.14 Letter f rom J. E. Thomas, May 19, 1987, Pile: CN-1346.05 and personal conversation with Frank Poley 2.15 Radiofodine and Part icle Transmission Through Plant Vent Sampling Lines at Catawla Nuclear Station, prepared by SAIC, dated July 1989.

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EDA >t pcse 2 cf 11 3.0 JrJfillLAND PMC]NTIONS 3.1 This procedure is an alternative method of dose assessment to the Catawba Class A Atmospheric Dispersion Model conputer code.

3.2 This procedure applies to releases made from Catawba Nuclear Station only. Many of the values contained in this procedure are sits specific.

3.3 It is assumed that the shole body dose from an iodine release is very small compared to the thyroid dose; therefore, iodine whole body dose is not considered here.

3.4 This procedure considers all releases to be ground level releases and that meteorological data are 15 minute averages.

3.5 Once a zone has been added to the Ifst of affected zones, it shall not be removed except under the direction of the Dose Assessment Coor d inator.

3.6 Once the Crisis Manntement Center (CMC) has been activated, the doses calculated by the Technical Support Center (TSC) dose assessment group, should be compared with those calculated by the CMC before an evacuation recommendation is made.

4.0 H OCEDUKE 4.1 Meteorology Asser.sment 4.1.1 Acquire the following information and record on the Dose Assessment Worksheet (Enclosure 5.1):

4.l.1.1 bower tower wind speed (WS) in miles per hour.

4.1.1.1.1 Use upper tower wind speed if lower tower wind speed is not available.

4.1.1.2 Upper tower wind direction in degrees from North (North = 0).

4.1.1.2.1 Use lower tower wind direction if upper tower wind direction is not available.

4.1.1.2.2 If the wind speed or wind direction.

cannot be obtained from plant systems, obtain them from the National Weather Service (phone 704 359 8466).

If the NWS information is unavailable, then obtain data from McGuire Nuclear O

Station Control Room (73 or 78, b

then 875, then ext. 4262, or 4263, or 4264).

.=

EDA 32 Fago 3 cf 11 4.1.1.3 Topperature gradient (67) in degrees centigrade.

4.1.1.4 Using Enclosure 5.2, record the stability class based on AT.

4.1.1.4.1 If the temperature gradient is unknown, the following applies:

If between 1000 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months , use stability class D; If between 1600 - 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months , use stability class G.

4.1.1.5 If necessary, use forecasted seteorolegical data for calculating doses due to changing seteorological conditions.

4.1.2 Determine the atmospheric dispersion parameter, X/Q (sec/m'), for

.5, 2, 5 and 10 miles (record on Enclosure 5.1, page 2):

4.1.2.1 Use AT, determine the two hour relative.

concentration value (C ) from Enclosure 5.2.

H 4.1.2.2 Convert the C values to X/Q:

H X/Q = CH Ws 4.2 Source Tern Assessment - Steam Relief Yalve (Enclosure 5.4) 4.2.1 Determine the Sub Noble Can Release Rates,'$QNG (Cl/sec),

by the following methodt 4.2.1.1 For Unit 1 EMF 26, EMF 27, EMF 23 and EMF 29 or for Unit 2 EMF 10 EMF 11 EMF 12 EMF 13:

SQgg = R/hr x _ 1 _ x LBM x CF Cl YOFEN lbe R/hr wheret R/hr =

EMF 26. EMP27. EMF 28. EMF 29, EMF 10 EMF 11. EMF 12. EMF 13 reading VOTEN=

time the valve is open in seconds lbm released for the time the valve LBH =

was open correction factor per Enclosure 5.5 CF

=

0 0

EDA *2 Page 4 cf 11 4.2.2 Dete mine the Noble Cas Release Rate, Ogg(C1/sec):

Ogg = 80 (I.nr26) 4 so (EMr27) + so (Enr28) +

gg gg So (F.Mr29) 4.2.3 Determine the lodine release rate. Q (Cf/sec):

g Qg*Ogg x Irat where:

Irat = ratio of 1131 eqv./Xe133 eqv. from Enclosure $ 6.

4.2.4 Record O and Q on inclosure 5.1, page 2.

gg 3

4.3 Source Term Assessment Containment (Enclosure 5.7) 4.3.1 Determine the Noble ces Release Rate Ogg(Cf /sec) based on one of the following methods; 4.3.1.1 Based on an EMr reading, wherel ONG = IMF x cr x 1.R wherol EMP = 39(L), if ENT39(L) <1E7 cpm and flovpath not isolated, EMP = 39(H), if Dir39(L) is of fscale and EMr39(H) > 100 cpm and flowpath not isolated.

EMr = 53A or $38, if EMP39(H) is offscale.

(fse survey seter reading (Reference 2.P.) if 53A and $3B are not available.

CT = correction factor per Enclosure 5.8.

LR = Leak Rate x BYPAS8, Leak Rate, (al/hr), by one of the following methods based on containment pressure:

LR = RLR (from Enclosure 5.9) based on an opening in containment:

LR = 010 (from Eactosure $.10) based on design Icak rate:

LR = 2.449E6 (Referenen 2.13)

BYPASS = Bypass leakage, default is 7%

or 0.07 (Reference 2.6) e

4 (DA*2 Pego 5 of 11 4.3.1.1 Ensed on PACS sanple, 6hereg Ogg = PACS x CT x LR wheret FAC8 = pCf /n1 (Reference 2.4)

CF

= 2.76E 10 _Ci hr sec pC1 1.R

= Leak rate, as determined in Step 4.3.1.1 above 4.3.2 Dettaine the lodine Release Rate, Qg (Cl/sec) based on one of the following methods 4.3.2.1 Based on ONGI Qg=QNG " II'*

where QNG = Noble Gas Releasa Rate as ddermined in Step 4.3.1 above trat = ratio of 1131 eqv./Xe 133 eqv. from.6.

4.3.2.2 Based on DiF 40 (if flowpath is not Isolated):

Qg = _ ACPM x 9.82E-20 C1 hr min x 1.R Amin sec al cpn wheret ACPN = readirts from EMF 40 Delta Counts Amin = the time interval for EMr40 observation (normally 15 minutes) 9.82E 20 = 4,0E 5 pCi/cpn x.25 min /f t' (inverse of EMF'ilow rate) n.

3.53 5 ft'/m1 x IC1/1E6 pCi x 1 hr/3600 sec.

4.0E-5 = correlation factor for EMT40 from Reference 2.1.

I LR = Leak rate, as determined in Step 4.3.1.1 above O

(DA-2 Tage 6 cf 11 4.3.2.3 Based on FACS samplel Qg = FACS x CF x LR wherel FACS = (pCi/el) (Reference 2.4) f 1

CF = 2.78E 10 Ciht, j

sec pCi LR = Leak rate as determined in Step I

4.3.1.1 above

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4.3.3 Record O and Q on Enclosure 5.1, page 2.

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l 4.4 Source Tern Assessment

Unit Vent (Enclosure 3.11)

I 4.4.1 Determine the Noble Gas Release Rate, Ogg(Cf/sec) based on l

one of the following methods:

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4.4.1.1 Pased on as EMP reading, where!

Ogg = EMF x CF x CFM

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I where:

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i EMF = 36(L) if EMF 36(L) < IE7 cps, EMF = 36(H) if EMF 36(L) is offscale and I

EMF 36(H) > 100 cpm and compressor not

tripped, EMF = $4 f f EMF 36(H) is offscale or j

compressor tripped.

CF = correction factor per Enclosure 5.12 l

CFM = unit vent flow rate (ft'/ min) 4.4.1.2 Based on unit vent. samp1n, wheren ONG = Unit Vent Sample x CF x CFM where Unit Vent Sample = (pC1/ml) per Reference 2.$

CF = 4.72E 4.31_ min _al, see it' pei CFM = unit vent flow rate (ft'/ min)

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' EDA-2 Page 7 of 11'

.O 4.4.2 Determine tM lodine Release Rate, Qy (CJ/sec), based on one of the following methods:

4.4.2.1 Based on Ogg; Q3=ONG I'**

where:-

Ogg = Noble Gas' Release Rate as det$rmined in Step 4.4.1 above i

.irat a. ratio of 1131 eqv./Xe133 eqv. from.6.

4.4.2.2 Based on EMF 37 (if compressor not tripped);

ACIE x 1.33E-13 0.1 min mill x CrH = Qg Amin

<ee ft* cpm a

where ACPM = reading from EMP37 Delta Counts Amin = the' time int 3rval from EHF37 i

observation (normally 15 minutes) l 1.33E-13 = 4.0E-5 pC1/ cpm x 0'.1667. min /fts (inverse of EMF flow' rate) x IC1/IE6 pCi x 1 inin/60 sec. x 1.2 where:

4.0E-5 = correlation factor for EMF 37 from Reference 2.1.

1.2

= inverse of' iodine transmission factor (see Reference 2 15)'

CFM'

= unit vent: flow rate (ft*/ min) i 4.4.2.3 Bamed on unit vent sample Qg = Unit vent sample x 4.72E-4 : Ci min e1 x CFM j

sec ft' pCi

-l where:

i Unit vent sample = (pC1/ml) (Reference 2.5)

{

l CFM = unit vent flow rate (ft*/ min) i 4.4.3 Record Q and Q on' Enclosure 5.1, page 2.

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EDA-2 page 8 ef 11-i

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4.5 Dose Assessment (Enclosure 5.1 or Class A conputer printout) v 4.5.1 On Item 1, record if this information is for a drill or teal emergency.

l 4.5.2 On item 4 record which unit is affected.

4.5.3 On item 9:

4.5.3.1 If normal plant conditions exist, circle A.

N/A Items 10 through 13.

Go to step 4.5.8.

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4.5.3.2 If an emergency event is occurring and releases are less than operational limits and:

l 4.5.3.2.1 Containment pressure is less than 1 psig, circio B or, 4.5.3.2.2 containment pressure is greater than or equal to 1 psig with increased reactor building activity or steam generator tubo Icak exists or increased unit vont activity

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exists or field teams report activity, circle E, but do not p

provido dose calculations to (j

state / counties.

4.5.3.3 If an emergency event is occurring and releases are greater than operational limits, circle C if releases are occurring or D if they have already occurred.

4.5.4 On Item 10, record what type of release has occurred.

4.5.5 On Item 11, record the noble gas and lodino release rates (curies por second) from all releases.

4.5.5.1 If available, record the highest fodine/ xenon ratio.

4.5.6 On Item 12, record the reactor status.

4.5.6.1 If the reactor has not tripped, use the data sheet date/ time as the time of reactor trip.

On the computer printout, cross out the shutdown time /dato and record the % power from the data shcat.

4.5.7 On Item 13, record the dose rates and the integrated doses.

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4.5.7.1 If new doses were calculated, check the NEW s

l block.

EDA-2 Pago 9 cf 11

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4.5.7.2 The duration is the total time of previous releases plus the time estimated for the i

x-projected relecae.

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4.5.7.3 The integrated done (mrem) is the total dose from all releases plus the dose from the j

projected release.

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t 4.5.7.4 If information 1s available contradicting the calculated doses, change the data to reflect i

the new values, j

4.5.7.5 On Enclosure 5.1:

l 4.5.7.5.1 Determine the Projected Whole Body Dose Rate, DRwb (rem /hr), due to the noble gases for.5, 2, 5 and 10 i

miles:

?

DRwb 33.6 Irm m' x'TO x X/Q j

NG hr Ci where:

33.6 is the adult whole body fg dose conversion factor from s,)

Reference 2.9 in rem s' hr Ci 4.5.7.5.2 Determine the Projected Whole Body Dose, Dwb(rem), due to noble gases for.5, 2, 5 and 10 miles:

Dwb = DRwb x 2 hr where:

dose is integrated over 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months time period 4.5.7.5.3 Determine the Projected Thyroid Dose Rate, DRet (rem /hr), due to iodine for

.5, 2, 5 and 10 miles:

DRct = X/Q x TQ x 2.26F.6 rem m8 g

hr Ci i

where:

2.26E6 is the child thyroid dose conversion factor from

/~

Reference 2.13 in Irm_ml

(

hr Ci e

4

- =

EDA-2 P go 10 cf 11 i

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4.5.7.5.4 Determine the Projected Thyroid

(_ '

Dose, Det(rem), duo to lodino for t

.5, 2, 5 and 10 miles:

I Dct = PRet x 2 hr where:

doso is integrated over 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months timo period 4.5.8 On Item 14, record the meteorological data.

4.5.9 On Item 16, this section is for the TSC Dose Assessment i

Coordinator or the CMC off-Site Dose Assessment Director.

t 4.6 Protectivo Action Recommendations (Enclosure 5.1 or Class A computer printout):

4.6.1 Circle on Enclosure 5.1 the Protective Action Zones (PAZ),

hased upon 1) the wind speed and wind direction, using.3; and 2) the projected dose from Enclosure 5.1 compared to the following.

4.6.2 If the projected dose in a PAZ is < 1 rem whole body or 7

<5 rem thyroid, then recommend no protective action (action A).

4.6.3 If the projected dose in a PAZ is 1 - 5 rem whole body or 5 - 25 rem thyroid, then recommend to considor evacuating pregnant women and children and shelter all other PAZs (actions OTilER and B).

4.6.4 If the projected dose in a PAZ is > 5 rem whole body or

> 25 rem thyroid, then recommend evacuate everyone and l

shelter all other PAZs (actions C and B).

4.6.5 Recheck meteorology conditions approximately every 15 minutes to ensure that other sectors have not been affected.

4.7 Emergency Classification (Enclosure 5.1) 4.7.1 Check the box indicating the emergency classification based upon the following.

4.7.2 If the dose rate at the site boundary is 2 S.0E-4 rem /hr whole body then recommend an Alert.

4.7.3 If the dose rate at the site boundary is 2 05 rem /hr wholo body or 2 25 rem /hr thyroid, then recommend a Site f 3, Area Emergency if readings last 30 minutes.

V 4.7.4 If the doso. rate at the site boundary is 2 5 rem /hr whole body or 2 2.5 rem /hr thyroid, then recommend a Site Area Emergency if readings Inst 2 minutes.

EDA-2 P2ge 11 ef.11 L

4.7.5 If the dose rate at the-site boundary is 1.1 res/hr whole body or.t 5 rem /hr. thyroid, then recommend a General Emergency.

5.0 ENCLOSUES 5.1

-Sample of Meteorology Source Term and Dose. Assessment Worksheet 5.2 Two hour Relative Concentration Factors (C )

H 5.3 Protective Action Zones Determination 5.4 Sample of Source Term Assessment - Steam Relief Valves 5.5.

EMF 26 EMP27, EHF28, EMP29 or EMF 10, EMF 11, EMF 12 EMF 13 Noble Gas Correction Factor 5.6 1131 eqv./Xe 133 eqv. Ratio 5.7 Sample of Source Term Assessment - Containment 5.8 Containment Noble Gas' Correction Factor.

5.9 Containment Leakage Rate' versus Pressure 5.10 Containment Leakage Rate versus Pressure and Size Opening 5.11 Sample of Source Term Assessment - Unit Vent 5.12 Unit Vent Noble Gas Correction Factor 5.13 Integrated Dose 1

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DUKE POWER COMPANY Pago 1 of 2 CAT /WBA NUCLEAR STAT 30N EDA-2 ENCLOSURE 5.1 METEOROLOGY, SOURCE TERM AND DOSE ' ASSESSMENT

<w EMERGENCY NOTIFICATION

(

)

1.

Tills IS A(N) DRILL EMERGENCY 4.

SITE: Catawba Unit 9.

EMERGENCY INVOLVES:

I A.

NO RELEASE (If A go to 14.)

B.

POTENTIAL RELEASE C.

A RELEASE IS OCCURRING:

Started Expected Duration D.

A RELEASE HAS OCCURRED:

Started Stopped E.

THE RELEASE IS WITHIN NORMAL OPERATIONAL LIMITS 10.

TYPE OF REl. EASE:

GROUND LEVEL A.

RADI0 ACTIVE GASES C.

RADIOACTIVE PARTICULATES B.

RADIOACTIVE LIQUIDS D.

OTHER 11.

RELEASE: CURIES PER SEC.

A.

NOBLE GASES C.

10 DINES B.

10 DINE / NOBLE GAS RATIO (If availabic)

OTHER 12.

REACTOR STATUS:

A.

SHUTDOWN: TIME /DATE

__/__/__

B.

% POWER (EASTERN)

HM/DD/YY

(]

13.

ESTIMATE OF PROJECTED OFFSITE DOSE:

\\ _,-

NEW UNCilANGED DURATION:

HRS.

Whole Body Child Thyroid DOSE RATE DOSE RATE Whole Body Child Thyroid Distance mrem /hr mrem /hr mrem mrem Site Boundary 2 miles 5 miles 10 miles 14.

METER 0 LOGICAL DATA:

_,_NOT AVAILABLE A.

WIND DIRECTION (from) degrees C.

STABILITY CLASS B.

WIND SPEED (mph)

D.

PRECIPITATION (type)-

15.

RECOMMENDED PROTECTIVE ACTIONS:

A.

NO RECOMMENDED PROTECTIVE ACTIONS B.

SHELTER A0 B1 El Al C1 D1 F1 B2 A2 C2 D2 E2 F2 F3 A3 C.

EVACUATE A0 B1 El 1A C1 D1 F1 B2 A2 C2 D2 E2 F2 F3 A3 D.

OTHER 16.

APPROVED BY:

(NAHE)

(TITLE)

TIME /DATE:

/

(EASTERN) mm dd yy

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EQIES: 1) For all evacuations, recommend that the remainder of the 10 mile k'

emergency planning zone stay Indoors.

2) Compare these recommendations with other groups' recommendations that the Emergency Coordinator / Recovery Manager reviews.

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i DUKE POVER COMPANY Page 2 cf 2 CATAVBA NUCLEAR STATION EDA-2 ENCLOSUPE 5.1 HETEOR01.0GY, SOURCE 'JERM AND DOSE ASSESSMENT l

(

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Projection based on data on,_ /

/.

Time since trip hrs.

Hiles

.5 1

2 4

5 7

8 PAZ A0 B1 El AlC1D1F1 B2 A2 C2 D2 E2 F2 F3 A3 Total Source Term Assessment o Current a llypothetical Steam Relief Containment Unit Vent Encl. 5.4 Encl. 5.7 Encl. 5.11

__ C1/sec +

C1/sec +

C1/Sec =

C1/Sec (TQNG)

_ Ci/sec +

C1/sec +

C1/See =

01/Sec (TQ )

Source Term Based on g

1.

I.0CA 5.

Tube Rupture i

2.

LOCA (charcoal) 6.

New Tuol Accident (< 100 days old) 3.

Helted Core 7.

Old ruel Accident (> 100 days old) 4.

Molted Core (charcoal) 8.

Vasto Gas Decay Tank Dose Assessment b=X/Q WS

<- -< Adult whole body < ---<

Child thyroid 2 hr (g')

Dose = 2 x DRwb = 33.6 x TQ 2 hr x

X x

TQ x_2.26E6

= DRct x 2 = Dose (Chsec)(se/Qc/m')(di/sec)

(rem /hr) (rem)

(rem)

(rem /hr)

Distance miles

=2 x

= 33.6 x TQ

.5 N x 2.26E6 =

x 2=

gg

=2 x

33.6 x TQ x. 6E6

x 2=

NG

=2 x

= 33.6 x TQ

.x 2.26E6 =

x 2=

NG

=2 x

33.6 x TQ 10 W x 2.26E6

x 2=

NG

=2 x

= 33.6 x TQ 1

N x 2.26F,6 =

x 2=

NG

=2 x

= 33.6 x TQ 4

TQ x 2.26E6 =

x 2=

NG

=2 x

= 33. 6 x 'IT)gg 7

N x 2.26E6 =

x 2=

=2 x

= 33.6 x TQ 8

N x 2.26E6 =

x 2=

gg l

Review with Emergency coordinator the recommended Emergency Classification, o Recommend Alert Recommend Site Area Emergency if readings last 30 minutes o

t Recommend Site Area Emergency if readings last 2 minutes o

Recommend General Emergency a

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[ Stability l Distance _ teiles t I

l Credient tc) l Class l

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l 2 l 3

l 4 l 5 l

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A l 1.+E-S l 1.2E-6 l 5.9E-7] +.1E-7 [ 3.2E-7 l 2.5E-7 l 2.0E-7 l 1.9E-7 ! 1.8E-7 l 1.6E-7 l 1.5E-7 I I

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l 3.8E-4 l 1.4E-4 l 4.W-5] 2.7E-5 l 1.7E-5 l 1.ZE-S l 9.2E-4 l 7.3E-6 l 6.9E-6 I 5.0E-6 l 4.3E-6 l 1

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I I s)

.o.+3aT<.1.2 l r

I 1.1E-3 I s.1E-4 1 2.oE-41 1.2E-+ 1 a.2E-s I 6.u-s I s.1E-s I 4.u-s 1 3.aE-s 1 3.3E-s i 3.oE-s I I

I 1

I I

I l 6)

+1.2547 l

C l 1.8E-3 1 1.1E-3 1 4.3E-4l 2.7E-4 l 2.0E-4 l 1.7E-4 l 1.3E-4 l 1.2E-4 l 8.6E-5 l 7.eE-5 I 7.3E-S l e

e e

te-TE :

If aT is unevailable use:

1000-1600 hours use stability class 0 1600-1000 hours Use Stability Cless C

~

' - - ~ - - -

~

' - - ~ ^ " ~ - ' ~ ' ~

~~~ ~ ~ ' ~ ~ ' ' ' ~

~' ~~~~~

t DUKE POVik COMPANY CATAWBA NUCLEAR STATION 3

EDA-2

.[-s]

ENCLOSURE 5.3 s/'

PROTECTIVE ACTION ZONES DETEKH1 NATION

{

i i

Determine the af fected r.ones (based on wind' df rection) from the table below and record on Enclosure 5.1.

j l

i HQIE:

If wind speed is less than or equal to 5 mph, the affected ' sones for -

l 0-5 miles shall be A0, A1, B1, C1, D1, E1, F1.

i Wind Direction PAZ's i

(degrees from North)-

0 5 miles 5-10 miles

[

l 1

'I 0.0 - 22 A0, C1, D1 C2, D2 l.

22.1 - 73 A0, C1, D1, El C2, D2, E2, F2

[

73.1 '108 A0, C1, D1, E1, F1 D2,E2,F2,F3f f

108.1 - 120 A0,D1,E1,F1 D2, E2, F2, F3 J

120.1 - 159 A0, E1, F1 D2, E2,'F2, F3, A2 j

159.1 - 207 A0,E1,F1,A1 E2, F2, F3. A2, B2 207.1 - 247 A0, F1, A1, B1 F2, F3, A2, B2

(

247.1 - 265 A0, A1, B1 F3, A2, B2, A3, C2 265.1 - 298 A0,A1,B1,C1 A2, B2, A3, C2 f

298.1 - 338 A0, B1, C1 B2, A3, C2, D2 338.1 - 359.9 AD,B1,C1,D1 B2, C2, D2 j

e 6

i i

n

[

DUKE POWER COMPANY' l

CATAWBA NUCbEAR STATION

~

EDA-2

, Pg ENCbOSURE 5.4.

l V

SOURCE TEkN ASSESSMENT - STEAM REblEF VAbVES i

i Report #

_ Reactor Trip

/

Projection based on data on

/

{

(Date/ Time)

Calculations based on Helted Core BOCA HQEILGA8 I

based on EMF 26 or EHF10 SG

,l yg, R/hr.x l

1 l'

l sec x

.lbm x G.i =

..01_

~j J_

J, (Encl. 5.5):

'{

Ibn R/hr sec I

based on EHF27 or EMF 11 t

R/hr x 1

l

.,i

_ s eC lx lbm x

_ $1 =

S1

,j_

J lbm R/hr.

sec

}

(Encl. 5.5) j v

based on EHF28 or EHF12 t

r R/hr x 1

s

.t sec x

lbe x G.i =

Gi_

i J,

Ibn R/hr see (Encl. 5.5)

,q based on EMF 29 or'EHF13 i

R/hr x 1

I sec l

x lba x G1 =

Q1.

1 JL lba R/hr sec (Encl. 5.5)

C1/sec f

Total from all Steam Relief Valves, Q a

gg IODINE

[

From all Steam Relief valves i

QI l

Q x

1131 eqv./Xe 133 eqv. ratio NG Ci/sec.

l

=

(Encl. 5.6) i i

{

o Emergency a Drill Prepared by:

g f

t-

.j 1

DUKE POWER COMPANY.

l

.CATAVBA NVCLEAR' STATION EDA ENCLOSURE 5. 5 -

[s I;MF26,~ EMF 27, EMF 28, EMF 29 or EHF10, EMF 11~, EMF 12, EMF 13 NOBLE GAS CORRECTION FACTOR Time Since Trip (hrs)

Correction factor, j

based on Malted Core.or LOCA 1

3.622

' 1 20 22 3.971 f

14 4.041 18 4.029 1

i 124 3.332 148.

2.647

]

>100 2.438 j

'1250 2.438

.i 1500 2.438

{

2.438 2720 i

units in ci f

Ibn R/hr l ()

Enclosure 5.5 is 'the correlation factor per Reference 2.13 x i

2.83E4 p_L, x.41 its x

,a ft' lba IE6 m1 i

i l

.41 = specific gravity of steam per Reference 2.13.

j i

t s

I l

i-i a

4

,l

. i o

h i

P 4

+

4 85

y.w, c wg g1

.2,,

n-.-w,3,~--wee

.-.-,r.cr,,*e-g.,._-,-

,,,+-----,-,-ww a nc as, - - -,

c-6 w t.

-*-mw---

==T-,--

7

+-*-rt-

DUKE POWER COMPANY.

CATAWBA NUCLEAR STATION EDA-2

/'i ENCLOSURE 5.6 V

1131 eqv./Xe133 eqv. KATIO Ratio based on Ratio based on LOCA Melted Core Tin.c Since Trip (hrs)

(Column 1)

(Column 2) to 2.74E-3 2.24E 3 22 3.42E-3 9.66E 3 24 3.82E-3 1.59E 2 28 4.34E-3 2.85E 2 124 4.79E 3 7.52E 2 248 4.84E-3 1.11E-1 1100 5.06E 3 1.33E-1 1250-6.55E-3 1.80E-1 1500 1.02E-2 2.90E 1 2720 1.44E-2' 4.33E-1

Enclosure 5.6 is from Reference 2.13.

!LQIE -

For imit vent releases in which Irat is utilized to determine I-131 p

equiv. concentration, apply' the appropriate - correction from 'the table below:

LOgA, use column 1 (based on LOCA).

1.

Q 2.

LOCA through charcoal filters, divide column 1 value by 100.

3.

Coro damagg, use column 2 (based on Core Melt).

4.

Coro damaro throuch charcoal filters, divide columri 2 value by-200.

5.

Tube rypture, use 1.44E-5 6.

F_qw fuel accident, use 2.217E-4 7.

Old fuel accident, use 7.217E-4 8.

9,ps decay tank, assume no radiolodine released, only nobic gases are considered to be released from gas tank, use 0.

F_QIS:

Tor steam releases in which Irat is utilized to determine I-131 equiv. concentration, apply the appropriate correction from the tablo below:

1.

LQC4 divide column 1 value by 100.

2.

Coro damann, divide column 2 value by 100.

t-

'~

DUKE POWER COMPANY -

CATAWBA NUCl, EAR STATION.

EDA.2

- (3 ENCLOSURE $.7

\\

SOURCE TERH ASSESSMENT.- CONTAINMENT Report #

Reactor Trip

/

Projection based on data on

__/

(Date/ Time)

Calculations based on Melted Core LOCA Containment pressure psig LR =

ml/hr x BYPASS (def ault =.07)

LR based on Realistic Leak Rate (check.one) 1" 2"

4" 6"

8" 12" 18" 34" diameter opening (circle one) Personnel llatch opening Equipment flatch opening Design Leak Rate (2.449E6)

!i0ELLGAS based on-(check one) o EMF 39(L) if < 1E7 cpm o EMF 39(H) if > 100 cpm o EHF53 if 39(H) is off scale EMF CF LR

QNG cpm or x

x ml/hr =-

_G1 g

R/hr (Encl. 5.8) sec (Note on Encl. 5.9) based on PACS sample pC1/ml x 2.78E-10 Ci hr x

ml/hr.-=

_Q1 l

(

r.ec pCi sec l

IODINE l

based on

_J O

N NG I-

_G1 x 1131 eqv./Xe133 eqv..

_Q1

=

sec ratio (Encl. 5.6) sec based on EMF 40 LR l

ACPM x 9.82E-20 Ci hr min x ml/hr

_Q1 j

=

Amin sec mi cpm sec

(

based on PACS sample pGi x 2.78E-10 C1 br.

x

.ml/hr =

_G1 (V'~g m1 sec pCi see o Emergency a Drill Prepared by:

L

EDA-2 DUKE POWER COMPANY ENCLOSURE 5.8 CATAWBA CONTAIN".ENT NOBLE GAS CORRECTION FACTOR

~

Time Since EMF 39(L)

EMF 39(H)

E"F 53

~

Trip (bours) based on based on based on LOCA Melted Core LOCA

~ Melted Core LOCA Melted Core 20 6.389E-18 6.672E-17 5.56E-14 1.429E-13 3.781E-10 1.190E-9 22 6.389E-18 4.448E-17 5.56E-14 1.003E-13 3.114E-10 5.894E-10 24 6.389E-18 3.058E-17 5.56E-14 1.232E-13 2.780E-10 4.726E-10 28 6.389E-18 2.113E-17 5.56E-14 1.195E-13 2.446E-10 3.392E-10 224 6.389E-18 1.112E-17 5.56E-14 7.339E-14 2.335E-10 1.890E-10 248 6.389E-18 1.056E-17 5.56E-14 6.060E-14 2.335E-10 1.668E-10 2100 6.389E-18 1.390E-17 5.56E-14 5.699E-14 2.335E-10 1.612E-10_.

2250 6.389E-18 1.446E-17 5.56E-14 5.588E-14 2.335E-10 1.557E-10 1500 6.389E-18 9.730E-18 5.56E-14

-5.560E-14 2.335E-10 1.251E-10 2720 6.389E-18 6.394E-18 5.56E-14 5.560E-14 2.335E-10 1.056E-10 Units in Ci hr units in

- Ci hr units in Ci hr see al cpm see al cpe sec al R/br.8 is the correlation factor per Reference 2.13 x br x

Ci 3600 see IE6 pCi NOTE:

Reference 2.14.

If Time Since Trip is > 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and EMF 53A or EMF 53B is less than or equal to 150 R/hr, add 150 R/hr to reading.

~_

~...

I s

i _,

o DUKE 1'0WER COMPANY -

CATAWBA '40 CLEAR STATION Eb.'-2

'[

ENCL,0SO E 5.9 CONTAINHENT LEAKAGE RA-YERSUS l'RESSURE I

i l

Lua ~

mithE l

f to

2.081E5 22

'4.536E5 14 8.316ES to 1.397E6 210 1.591E6-I til 1.663E6 212 1.713E6

'I 213 1,764E6 l

- 114 1.800E6

[

115 1.836E6.9 is the realistic leakage rate'- (m'/sec) per Reference 2.12 x 5

IE6 ml/m* x 3600 s6c/hr.

.l

~

2.081ES ml/hr is derived as follows:

,f

)

l'E6R}x36003.cs f

2.081E5'al = 0.017 %/ day x 3.4E-3 as -daI x

hr

%-sec a

hr where:

0.017 is determined from containment leakage rate vs pressu're curve from Reference 2.13 for an assumed 1 psig.

3.4E-3 is from Reference'2.12.

,t I

I i

t i

i t

1 f

t 9

'ts

> f I

DUKE POVER COMPANY.

CATAWilA NUCEEAR STATION EDA-2 rs ENCLOSURE 5.10

(,f CONTAINMENT 1.EAKAGE NATE VERSUS PRESdvRE AND S12E OPENING for 1" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 2.209E8, >5.0 3.906E8

>12.5 5.862E8

>2.50 2.889E8

>7.5 4.588E8-

>15.0 6.287E8

>3.75 3.483E8

>10.0-5.268E8 Por 2" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 8.496E8

>5.0 1.512E9

>12.5 2.243E9

>2.50 1.121E9

>7.5 1.784E9

>15.0 2.464E9

>3.75 1.342E9

> 10. 0 '

2.027E9 Tor 4" diameter opening PS10 ml/hr PS10 ml/hr PS10 ml/hr

>1.25.

3.144E9

>5.0 5.692E9

>12.5 8.496E9-

>2.50 4.248E9

' >7.5 6.797E9

>15.0 9.176E9

>3.75 5.098E9

>10.0 7.73109 Tor 6" diameter opening PSIG ml/hr

' PSIG-ml/hr-PSIG ml/hr

>1.25 7.137E9

>5.0 1.291E10

>12.5' 1.937E10

>2.50 9.516E9

>7.5 1.529E10

>15.0 2.124E10

>3.75 1.138E10

>10.0 1.716E10 For B" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr?

>1.25 1.257E10

>5.0 2.243E10 >12.5 3.381E10

>2.50 1.64BE10

>7.5 2.634E10 >15.0 3.568E10

>3.75 1.971E10

>10.0 3.042E10 for 12" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr

>1.25 2.719E10

>5.0 5.012E10 >12.5 7.476E10

>2.50 3.738E10

>7.5 5.947E10 >15.0 8.156E10

>3.75 4.452E10

>10.0 6.712E10 For 18" diameter opening PS10 ml/hr PS10 ml/hr PSIG ml/hr

>1.25 5.522E10

>5.0 1.003 Ell >12.5 1.529E11

>2.50 7.476E10

>7.5 1.189E11

>15.0 1.665E11

>3.75 8.836E10

>10.0 1.351E11 i

1

EDA-2

' 4 ENCLOSURE: 5.10 -

t

. Pags 2 of 2 j

i

! /N)

Tor 34" diameter opening

's_,

PS10-ml/hr PSIG ml/hr PSIG ml/hr t

>1.25' 1.869 Ell

>5.0 3.398E11

>l2.5' 5.132 Ell

.i

>2.50' 2.'583E11

>7.5 4'. 0 78E11 - >15.0 5.607E11 j

>3.75 3.093E11. >10.0 4.588E11 l

For Personnel llatch opening-PSIG' ml/hr PSIG ml/hr' PSIG ml/hr

.{

i

>1.25 2.379E12

>5.0 4.690E12. >12.5 6.967E12 4

>2.50 3.398E12

>7.5 5.573E12

>15.0 7.646E12

>3.75 4'.111E12 L>10.0

,6.372E12 For Equipment llatch opening I

PSIG

.ml/hr PSIG

-ml/hr PSIG ml/hr' i

>1.25 1.121E13

>5.0 2.022E13

>12.5

.3.059E13

>2.50

'1.478E13

>7.5 2.379E13 ->15.0 3.398E13

>3.75 1.767E13: >10.0 2.719E13 l

.l

Enclosure 5~.10 is the containment leakage for an opening.sf r.e in standard I

cubic foot por min (scfm) x 2.83E4 ml/ft* x 60 min /hr..

(])-

4 i

f k

't I

r

?

t I

3 I

/"'N i

. (_ /

{

t t

~

\\l f

DUKE F0WER COMPANY,-

CATAWBA NUCI. EAR STATION EDA-2 (q

f ENCLOSUEE 5.11-i-

_f SOURCE TERM ASSESSMENT UNIT VENT Report #-

Rractor Trip

/_

Projection-based on data on

/

(Date/TJme)

(Date/ Time)

Calculations based on

_Helted Core LOCA CTH =

ft*/ min HQEIL.CAS based on (check one) o EHF36(b) if < 1E7 cpm o EMF 36(li) if > 100 cpm o EMF 54 f f '36(H)-

is offscale EHF CF CFM

'QNG cpm or R/hr x x

11

=

E 8

(Encl'. 5.12) min sec based on Unit Vent Sarnple pCf/ml x 4.72E-4 Qf_ min m1____ x 11,8

=

' E sec its pCi min sec 10 DINE

(

based on NG I

Q.1 x 1131 eqv./Xe133 eqv.

E

=

sec ratio (Encl. S.6)

.sec based on CFM EHF37 AGEH x 1.33E-13 Ci min min x

fis

',,g,g Amin sec ft'. cpm min sec' based on Unit Vent Sample

_pCi/ml x 4.72E-4 Ci min al_ x fl,s y.

see its pCi min sec o Emergency a Drill Prepared by 1

e

EDA-2 DUKE COMPANY (V-)

r'^

ENC 5.12 5

)

CATA*='3A UNIT VENT NO GAS CORRECTION FACTOR Tine Since EMF 36(L)

EMF 36(H)

EMF 54 Trip (hours) based on based on based on Melted Core Melted Core Melted Core 20 1.133E-10 2.426E-7 1.887E-3 22 7.552E-11 1.704E-7 1.179E-3 24 5.192E-11 2.091E-7 9.905E-4 28 3.587E-11 2.030E-7 6.367E-4 224 1.888E-11 1.246E-7 2.931E-4 248 1.794E-11 1.029E-7 2.405E-4 2100 2.360E-11 9.676E-8 2.358E-4 2250 2.454E-11 9.487E-8 2.358E-4 2500 1.652E-11 9.440E-8 2.35BE-4 2720 1.086E-11 9.440E-8 2.358E-4 If accident is:

1.

Melted core use table.

2.

Melted core through charcoal use table.

3.

New Fuel Accident (less than 100 days old) use 2.358E-11 for EMF 36(L), use 9.67E-8 for E."J36(H),

use 2.358E-4 for EMF 54 4

All other accidents use 1.086E-11 for EMF 36(L), use 9.44E-8 for EMF 36(H), use 2.358E-4 for E"J54.

Units in Ci min units in Ci min units in Ci min see ft* cpm see ft" cpm sec ft' R/hr.12 is the correlation factor per Reference 2.13 x 2.83E4 mL x_ min x

Ci ft' 60 see IE6 pCi

p sp.

4,

~

,i DUKE lWER COMPANY CATAWBA NUCl. EAR STATION j

EDA.2:

~*

l -

.CNCI050RE 5.13

~ '.

INT 00 RATED DOSE

' Duration (hrn)

A0 q..

B1 El'

.A1

- i C1 j

e q.

'l

o.J

' F1 -

4.i q

B2

,j A2 L

Lj i-t-l S.

l{

C2

.i.

~ D2 ~

4 g

,e a

s E2 i

F2

.[

t F3-h A3

,s.

Instructionst Li; i ',

1)

Add the doses from ' previous. releases to.the projected '

fi relonse.

/

'l 2)

' Add the. times of releases to.the time 1of the projected' d

release, l

'k

}

I

n

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3

..q

,d j

4

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'l '

,')

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i,

,j

,f'

.',1'.

.

ML20033G898

Text

33.6 x TQ x. 6E6

33.6 x TQ 10 W x 2.26E6

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